Text

Radioactive Effluent Release Report
	ML24127A098
Person / Time
Site:	Dresden
Issue date:	04/30/2024
From:	Joseph C; Constellation Energy Generation
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	24-0017
	Download: ML24127A098 (1)
	v • d • e

Constellation.

Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450 April 30, 2024 SVPLTR: #24-0017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 1, 2 and 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos.50-010, 50-237, and 50-249 10 CFR 50.36a (a)(2)

Subject:

Dresden Nuclear Power Station 2023 Radioactive Effluent Release Report The Radioactive Effluent Release Report for January through December 2023 for Dresden Nuclear Power Station (DNPS) is submitted in accordance with Sections 6.9.A.4 and 5.6.3, "Radioactive Effluent Release Report," of the DNPS Unit 1 and Units 2 and 3 Technical Specifications, respectively and 1 O CFR 50.36a, Technical specifications on effluents from nuclear power reactors."

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

Carolyne Joseph Site Vice President Dresden Nuclear P

Attachment:

DNPS 2023 Annual Radioactive Effluent Release Report IE;/f tJf-1 s Sa I

)Ille fl) Iv/ _s-5

Constellation.

Dresden Nuclear Power Station (DNPS)

Annual Radioactive Effluent Release Report 2023 Document Numbers: 50-010/50-237 /50-249 Units 1, 2 and 3

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 1 of 62 Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station TABLE OF CONTENTS 1.0 LIST OF ACRONYMS AND DEFINITIONS................................................................................ 3 2.0 EXECUTIVE

SUMMARY

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

3.0 INTRODUCTION

........................................................................................................................,. 9 3.1 About Nuclear Power...................................................................................................... 9 3.2 About Radiation Dose................................................................................................... 11 3.3 About Dose Calculation........................................................... ;.................................... 13 4.0 DOSE ASSESSMENT FOR PLANT OPERATIONS................................................................. 15 4.1 Regulatory Limits.......................................................................................................... 15 4.2 Regulatory Limits for Gaseous Effluent Doses:............................................................. 15 4.3 Gaseous Effluent Monitoring...................................................................................... ~6 4.4 Regulatory Limits for Liquid Effluent Doses................................................................... 17 4.5 Liquid Effluent Monitoring............................................................................................. 17 4.6 40 CFR 190 Regulatory Dose Limits for a Member of the Public.................................. 18

4. 7 On site Doses (Within SiteBoundary)............................................................................. 18 5.0 SUPPLEMENTAL INFORMATION........................................................................................... 19 5.1 Gaseous Batch Releases.............................................................................................. 19 5.2 Liquid Batch Releases.................................................................................................. 19 5.3 Abnormal Releases........................................................................................................ 20 5.4 Land Use Census Changes.......................................................................................... 20 5.5 Meteorological Data...................................................................................................... 20 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days................................ 20 5.7 Offsite Dose Calculation Manual (ODCM) Changes...................................................... 20 5.8 Process Control Program (PCP) Changes.................................................................... 20 5.9 Radioactive Waste Treatment System Changes........................................................... 40 5.10 Other Supplemental Information................................................................................... 20 6.0 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM............... 27 6.1 Voluntary Notification..................................................................................................... 27 7.0 BIBLIOGRAPHY................................................................................. :.................................... 28 TABLES Table 1, Dresden Nuclear Power Station Unit 1 Dose Summary............................................................ 6 Table 2, Dresden Nuclear Power Station Unit 2 Dose Summary............................................................ 7 Table 3, Dresden Nuclear Power Station Unit 3 Dose Summary............................................................. 8

. Table 4, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for DRE..................................... 8 Table 5, Gaseous Effluents Summation of All Releases Unit 1............................................................ 29 Table 6, Gaseous Effluents Summation of All Releases Unit 2............................................................ 30 Table 7, Gaseous Effluents Summation of All Releases Unit 3............................................................ 31 Table 8, Gaseous Effluents - Ground Level Release Batch Mode Unit 1............................................. 32 Table 9, Gaseous Effluents - Ground Level Release Continuous Mode Unit 1.................................... 33 Table 10, Gaseous Effluents - Ground Level Release Batch Mode Unit 2........................................... 34

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 2 of 62.

Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 11, Gaseous Effluents - Ground Level Release Continuous Mode Unit 2.................................. 35 Table 12, Gaseous Effluents - Ground Level Release Batch Mode Unit 3........................................... 36 Table 13, Gaseous Effluents - Ground Level Release Continuous Mode Unit 3.................................. 37 Table 14, Gaseous Effluents - Mixed Level Release Batch Mode Unit t............................................. 38 Table 15, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 1.................................... 39 Table 16, Gaseous Effluents - Mixed Level Release Batch Mode Unit 2............................................. 40 Table 17, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 2.................................... 41 Table 18, Gaseous Effluents - Mixed Level Release Batch Mode Unit.3............................................. 42 Table 19, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 3.................................... 43 Table 20, Gaseous Effluents - Elevated Level Release Batch Mode Unit 1......................................... 44 Table 21, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 1................................ 4'5 Table 22, Gaseous Effluents - Elevated Level Release Batch Mode Unit 2......................................... 46 Table 23, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 2................................ 47 Table 24, Gaseous Effluents - Elevated Level Release Batch Mode Unit 3......................................... 48 Table 25, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 3................................ 49 Table 26, Liquid Effluents - Summation of All Releases Unit 1............................................................ 50 Table 27, Liquid Effluents - Summation of All Releases Unit 2............................................................ 51 Table 28, Liquid Effluents - Summation of All Releases Unit 3............................................................ 52 Table 29., Liquid Effluents Batch Mode Unit 1...................................................................................... 53 Table 30, Liquid Effluents Continuous Mode Unit 1.............................................................................. 54 Table 31, Liquid Effluents Batch Mode Unit 2...................................................................................... 5~

Table 32, Liquid Effluents Continuous Mode Unit 2.............................................................................. 56 Table 33, Liquid Effluents Batch Mode Unit 3...................................................................................... 57 Table 34, Liquid Effluents Continuous Mode Unit 3.............................................................................. 58 Table 35, Types of Solid Waste Summary Site..................................................................................... 59 Table 36, Major Nuclides Site.............................................................................................................. 59 Table 37, Solid Waste Disposition Site................................................................................................ 60 FIGURES Figure 1, Pressurized Water Reactor (PWR) (1)..................................................................................... 9 Figure 2, Boiling Water Reactor (BWR) [2]............................................................................................. 9 Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3]................................ :................... 11 Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6]............. 1 ~

ATTACHMENTS, ARERR Release Summary Tables (RG-1.21 Tables)................................................... 29, Solid Waste Information................................................................................................. 59., Meteorological Data...................................................................................................... 61, 2023 Annual RGPP Monitoring Report.......................................................................... 62

Annual Radioactive Effluent Release Report

/ YEAR: 2023

/

Page 3 of 62 Licensee: Constellation Energy Company, LLC \\

Plant: Dresden Nuclear Power Station 1.0 LIST OF ACRONYMS AND DEFINITIONS

1.

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

2.

BWR: Boiling Water Reactor

3.

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

4.

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

5.

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

6.

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

7.

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

8.

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

9.

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

10.

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

11.

ISFSI: Independent Spent Fuel Storage Installation

12.

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

13.

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

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

14.

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

15.

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

16.

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

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 4 of 62 Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station

17.

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

18.

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

19.

NIA: 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

32.

TS: Technical Specification

33.

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

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 5 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station 2.0 EXECUTIVE

SUMMARY

Dresden Nuclear Power Station (DNPS) Radiological Effluent Control (REC) Program was established to limit the quantities of radioactive material that may be released based on calculated radiation doses or dose rates. Dose to Members ofthe Public due to radioactive materials released from the plant is limited by Technical Specifications, 1 O CFR 20, and by 40 CFR 190. Operational doses to the public during 2023 were calculated to be within the limits required by regulation and compared to other sources of radiation dose and pose no health hazard. These doses are summarized and compared to the,regulatory limits in Section 2.1 Comparison to Regulatory Limits below.

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

In 2023, the gaseous effluent dose assessments for locations from the Land Use Census showed that the critical receptor for Dresden Nuclear Power Station is the infant. The maximum Annual Organ Dose calculated for this receptor from the site was 3.73E-02 mrem to the thyroid.

The maximum dose calculated to any organ due to radioactive liquid effluents was 2.34E-09 mrem for child total body.

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

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

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 6 of 62 Licensee: Constellation Energy Company, LLC \\

Plant: Dresden Nuclear Power Station 2.1 Comparison to Regulatory Limits During 2023 all solid, liquid, and gaseous radioactive effluents from Dresden Nuclear Power Station were well below regulatory limits, as summarized in Table 1, Dresden Nuclear Power Station Unit 1 Dose Summary, Table 2, Dresden Nuclear Power Station Unit 2 Dose Summary, Table 3, Dresden Nuclear Power Station Unit 3 Dose Summary, and Table 4, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for DRE.

Table 1, Dresden Nuclear Power Station Unit 1 Dose Summary1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Limit 1.5 mrem 1.5mrem 1.5-mrem 1.5 mrem 3mrem Dose Limit, Total Body Dose NIA NIA NIA NIA NIA Total Body

% of Limit NIA NIA NIA NIA NIA Liquid Effluent Limit 5 mrem 5mrem 5 mrem 5mrem 10mrem Dose Limit, Max Organ Dose NIA NIA NIA NIA NIA Any Organ

% of Limit NIA NIA NIA NIA NIA Gaseous Effluent Limit 5 mrad

. 5 mrad 5mrad 5 mrad 10 mrad Dose Limit, Gamma Air Dose NIA NIA NIA NIA NIA Gamma Air (Noble Gas)

% of Limit NIA N/A NIA NIA NIA Gaseous Effluent Limit 10 mrad 10 mrad 10 mrad 10 mrad 20mrad

Dose Limit, Beta Air Dose NIA NIA NIA NIA NIA Beta Air (Noble Gas)

% of Limit NIA NIA NIA NIA NIA Gaseous Effluent Limit

_7.5 mrem

7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ Dose Limit Max Organ Dose 6.77E-04 6.77E-04 6.77E-04 6.77E-04 2.71E-03 (Iodine, Tritium, Particulates with

> 8-day half-life)

% of Limit 9.02E-03 9.02E-03 9.02E-03 9.02E-03 1.S0E-02 1 Table 1 demonstrates compliance with 10 CFR Part 50, App. I Limits.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 7 of 62

Licensee: Constellation Ener~v Company, LLC I Plant: Dresden Nuclear Power Station Table 2, Dresden Nuclear Power Station Unit 2 Dose Summary2 Quarter 1 Quarter 2 Quarter 3 Quarter4 Annual

,*f* v'~

t.s*mr~m 1.5 mrern 3 mrem :.'

Liquid Effluent Limit

. 1.5 mrem 1.5 mrem *.

Dose Limit, Total Body Dose N/A N/A 1.17E-09 N/A 1.17E-09 Total Body

% of Limit N/A N/A 7.82E-08 N/A 7.82E-08, J

5h1re1J1

-5 rnfem V

5' mrerri Liquid Effluent L[mit 5mrem to mrern:

Dose Limit, Max Organ Dose N/A N/A 1.17E-09 N/A 1.17E-09 Any Organ

% of Limit N/A N/A 7.82E-08 NIA

7.82E-08

'

5 mr?d Gaseous Effluent Lim.it*

5.Jliraci 5mrad 5 mrad.... 1Q mrad Dose Limit, Gamma Air Dose 3.04E-04 2.83E-04 2.90E-04 2.16E-04 1.09E-03 Gamma Air (Noble Gas)

% of Limit 6.09E-03 5,65E-03 5.79E-03 4.31E-03 1.09E-02.

Gaseous Effluent limit 10 mra.d

10 mrad 10,mrad 10mrad -

2Qmrad

'i Dose Limit, Beta Air Dose 1.15E-05 1.05E-05 1.12E-05 9.87E-06 4.31E-05 Beta Air (Noble Gas)

% of Limit 1.15E-04 1.05E-04 1.12E-04 9.87E-05 2.16E-04' Gaseous Effluent 4il}1it,_... ;&,

.. ::.z., 7.. ~.mrem *J5,ll)rem:

7.s,mr~m 7.'5. nirem,:,. 15mrem.i

.,,_,,-~

~*~

,, ~" "

Organ Dose Limit Max Organ Dose 6.65E-03 6.19E-03 5.82E-03 1.97E-03 2.06E-02 (Iodine, Tritium, Particulates with

> 8-day half-life)

% of Limit 8.87E-02 8.25E-02 7.74E-02 2.63E-02 1.37E-01 2 Table 2 demonstrates compliance with 10 CFR Part 50, App. I Limits.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 8 of 62 Licensee: Constellation Enerf:lv Company, LLC I Plant: Dresden Nuclear Power Station Table 3, Dresden Nuclear Power Station Unit 3 Dose Summary3 Quarter 1 Quarter 2 Quarter3 Quarter4 Annual*

'1. $* rrYi-em :." 1-.5 mrem 1.5mrem

'j.S:,mi-ern

,F Liquid Effluent Limit

,3 rnr~m,,

.. ~,

Dose Limit, Total Body Dose NIA NIA 1.17E-09 NIA 1.17E-09 Total Body

% of Limit NIA NIA 2.35E-08 NIA 2.35E-08

i..frnit

,..,.,w "wa" jorni~r{j.

Liquid Effluent Smrem

)5 1:nreru Smrem '

.:,5 mr~rn J

Dose Limit, Max Organ Dose NIA NIA 1.17E-09 NIA 1.17E-09 Any Organ

% of Limit NIA NIA 2.35E-08 NIA 2.35E-08

. Limit

.10 mrad/.

Gaseous Effluent

5.mrac}

...., 5 mtad..

s mrad S)nrad ".,,

Dose Limit, Gamma Air Dose 6.60E-05 7.13E-05 1.12E-04 1.56E-04 4.0SE-04 Gamma Air (Noble Gas)

% of Limit 1.32E-03 1.43E-03 2.25E-03 3.11E-03 4.0SE-03

"- 10 rrfrad * *10mrad Gaseous Effluent "Limit'

. '"10 nirad 10o'mrad 20:mr:ad*

Dose Limit, Beta Air Dose 3.34E-06 3.71E-06 4.29E-06 7.27E-06 1.86E-05 Beta Air (Noble Gas)

% of Limit 3.34E-05 3.71E-05 4.29E-05 7.27E-05 9.31E-05.

Gaseous Effluent /Jfnit

,l.5 riJrei!Tl. 7.5 mre,n

1.s* m're111 7.5 mrei;r 1 s *m.r~r,~

\\cs' Organ Dose Limit Max Organ Dose 3.74E-03 3.35E-03 5.22E-03 3.59E-03 1.59E-02 (Iodine, Tritium, Particulates with

> 8-day half-life)

% of Limit 4.99E-02 4.46E-02 6.96E-02 4.79E-02 1.06E-01 Table 4, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for DRE4 Whole Body Thyroid Max Other Organ Gaseous5 3.40E-03 3.66E-02 4.26E-03 Carbon-14 1.03E-02 1.03E-02 5.13E-02 Liquid 2.35E-09 2.35E-09 2.35E-09 Direct Shine 4.37E+00 4.37E+00 4.37E+00 Direct Dose 3.57E+00 3.57E+00 3.57E+00 Other Fuel Cycle sources6 1.79E-01 1.79E-01 1.79E-01 Total w/Other Nearby 8.13E+00 8.17E+00 8.17E+00 Facility6 Limit 25 mrem 75 mrem 25 mrem 3 Table 3 demonstrates compliance with 10 CFR Part 50, App. I Limits.

4 Table 4 is a summation of Units to show compliance with 40 CFR Part 190 Limits.

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

6 Other fuel cycle sources within 5 miles of the site are considered irt this analysis. GE Hitachi Morris Operations 2023 dose contribution 1.79E-01 mrem.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 9 of 62 Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station

3.0 INTRODUCTION

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

ContoiniMnt S11'\\1ct1N Figure 1, Pressurized Water Reactor (PWR) [1]

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

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 1 O of 62 Licensee: Constellation Energy Company, LLC /

Plant: Dresden Nuclear Power Station 3.1 (Continued)

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

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

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 11 of 62 Licensee: Constellation Enerav Companv, LLC I Plant: Dresden Nuclear Power Station 3.2 About Radiation Dose Ionizing radiation, including alpha, beta, and gamma radiation from radioactive decay, has enough energy to break chemical bonds in tissues and result in damage to tissue or genetic material. The amount of ionization that will be generated by a given exposure to ionizing radiation is quantified as dose. Radiation dose is generally reported in units of millirem (mrem) in the US.

Computed tomograptiy (medical)

(24%)

Terrestrial (background)

(3%)

Nuclear medicine (medical)

(12%)

Space (background)

(5%)

lnterventional fluoroscopy (medical)

(7%)

Radon & thoron (background)

(37%)

Industrial

(<0.1o/,)

Occupational

(<0.1%)

Consumer Conventional radiography/fluoroscopy (medical)

(5%)

(2%)

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

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 12 of 62 Licensee: Constellation Enerciv Companv, LLC I Plant: Dresden NucJear Power Station 3.2 (Continued)

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

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

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

Annual Radioactive Effluent Release Report

[ YEAR: 2023 I Page 13 of 62 Licensee: Constellation Enerav Comoany, LLC I Plant: Dresden Nuclear Power Station 3.3 About Dose Calculation Concentrations of radioactive material in the environment resulting from plant operations are very small and it is not possible to determine doses directly using measured activities of environmental samples. To overcome this, dose calculations based on measured activities of effluent streams are used to model the dose impact for Members of the Public due to plant operation and effluents. There are several mechanisms that can result in dose to Members of the Public, including: Ingestion of radionuclides in food or water; Inhalation of radionuclides in air; Immersion in a plume of noble gases; and Direct Radiation from the ground, the plant or from an elevated plume.

.~position Ingest' 0

~

Marine produJs

* * * : Behavior of radionuclide&

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.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 14 of 62 :.

Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station 3.3 (Continued)

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

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

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

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 15 of 62.

Licensee: Constellation Energy Company, LLC \\

Plant: Dresden Nuclear Power Station 4.0 4.1 4.2 DOSE ASSESSMENT FOR PLANT OPERATIONS Regulatory Limits Regulatory limits are detailed in station licensing documents such as the plant Technical Specifications and the Offsite Dose Calculation Manual (ODCM). These documents contain the limits to which DNPS must adhere. DNPS drives to maintain the philosophy to keep dose "as low as is reasonably achievable" (ALARA) and actions are taken to reduce the amount of radiation released to the environment.

Liquid and gaseous release data show that the dose from DNPS is well below the ODCM limits. The instantaneous concentration of liquid radioactive material released shall be limited to ten times the concentration specified in 1 O CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the total concentration released shall be limited to 2.0 x 10-4 microcuries/mL.

The annual whole body, skin and organ dose was computed using the 2023 source term using the dose calculation methodology provided in the ODCM. The calculated doses due to gaseous effluents are used to demonstrate compliance with offsite dose limits are presented in Table 1, Dresden Nuclear Power Station Unit 1 Dose Summary, Table 1, Dresden Nuclear Power Station Unit 1 Dose Summary, Table 2, Dresden Nuclear Power Station Unit 2 Dose Summary, Table 3, Dresden Nuclear Power Station Unit 3 Dose Summary, and Table 4, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for DRE.

Regulatory Limits for Gaseous Effluent Doses:

1.

Fission and activation gases:

a.

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

1)

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

2)

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

b.

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

1)

Quarterly a)

Less than or equal to 5 mrads gamma b)

Less than or equal to 10 mrads beta

2)

Yearly a)

Less than or equal to 10 mrads gamma

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 16 of 62.

Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station 4.2 (Continued) 4.3 a)

Less than or equal to 20 mrads beta

. 2.

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

a.

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

1)

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

b.

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

1)

Quarterly a)

Less than or equal to 7.5 mrem to any organ

2)

Yearly a)

Less than or equal to 15 mrem to any organ Gaseous Effluent Monitoring The 2/3 Chimney (elevated), 2/3 Reactor Building Vent (mixed mode), effluents are continuously sampled for iodine and particulates and the Unit 1 Chemical Cleaning Building (mixed mode) when in operation. These samples are obtained weekly and analyzed by gamma spectroscopy. The particulate filters are composited and sent to a vendor for gross alpha, Sr-89, Sr-90, Ni-63 and Fe-55 analysis quarterly. Noble gas grab samples of the 2/3 Chimney and 2/3 Reactor Building Vent are obtained weekly and analyzed by gamma spectroscopy. Contributing streams of the 2/3 Chimney and 2/3 Reactor Building Vent are also sampled and analyzed by gamma spectroscopy. Tritium samples of the 2/3 Chimney and 2/3 Reactor Building Vent are obtained monthly and analyzed by liquid scintillation.

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

The Unit 1 Main Turbine Floor is used as an area to work on contaminated equipment. The Unit 1 Fuel Building is used as a storage area and potentially as a work area. The ventilation systems to these areas are no longer operational and the areas are at ambient pressure with the outside environment. The potential exists for airborne activity to be released to the environment through various points. Based on

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 17 of 62 Licensee: Constellation Energy Company, LLC I

Plant: Dresden Nuclear Power Station 4.4 4.5 the work normally performed in these areas, an estimated 6.00E-06 Ci of Cs-137 was released via this path per month for a total of 7.20E-05 Ci during 2023.

The Unit 2/3 Heating Steam System has been contaminated in the past and occasionally contains low-level contamination. During normal operation, the*

condensate is converted to steam, a portion of which gets vented to the atmosphere.

If tritium was identified above minimum detectable activity in 2023, permits are generated for the appropriate activity released. This will continue to be monitored when the system is running.

The Chemistry Laboratory exhausts directly into the environment via its ventilation system and is not monitored. The activity concentration from the Offgas Recombiner samples taken weekly from each unit and the sample size (15 cc) was used to calculate a monthly activity released from each unit from the Chemistry Hot Lab fumehood. This activity was captured in the monthly 1 0CFR50 Appendix I calculation and is included in the noble gas totals in Table 11, Gaseous Effluents - Ground Level Release Continuous Mode Unit 2 and Table 13, Gaseous Effluents - Ground Level Release Continuous Mode Unit 3.

Regulatory Limits for Liquid Effluent Doses

1.

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

a.

Quarterly

1)

Less than or equal to 1.5 mrem total body

2)

Less than or equal to 5 mrem critical organ

b.

Yearly

1)

Less than or equal to 3 mrem total body

2)

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

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

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 18 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Containment Cooling Service Water (CCSW) is sampled from the Low-Pressure Coolant Injection (LPCI) heat exchangers monthly and analyzed for gamma-emitting nuclides by gamma spectroscopy. These samples are composited quarterly and analyzed for tritium, gross alpha, Sr-89, Sr-90, Fe-55, and Ni-63. Results are conservatively applied for each month of the quarter. Batch release volume is based on LPCI heat exchanger volume.

On-site storm sewers are sampled and analyzed for tritium content. The CBG well tritium concentration measured during each month of 2023 was used to calculate the released activity for each month via the storm sewers. The volume was based on the monthly rain fall over a 100,000 sqft area of the Site.

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

Beginning in September 2019, groundwater from the West Tritium Remediation Well was monitored via the 2/3 Discharge Tunnel. Although this is a planned continuous release, it is being mentioned here due to its relatively short duration over this life of the plant.

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

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

1.

Total Dose (40 CFR 190)

a.

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

1)

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

2)

Less than or equal to 75 mrem, Thyroid.

Onsite Doses (Within Site Boundary)

Dresden Nuclear Power Station does not have members of the public on site but does have non-occupational exposed individuals working on-site. Doses to these individuals are monitored and calculated utilizing dosimetry in the general vicinity of their working areas and is sufficient in demonstrating that these individuals do not receive dose exposure in excess of 100 mrem per year TEDE as per 1 O CFR 20.1301 requirements.

Annual Radioactive Effluent Release Report I YEAR: 2023 I

Page 19 of 62 Licensee: Constellation Enerav Companv, LLC I Plant: Dresden Nuclear Power Station 5.0 5.1 5.1.1 5.2 5.2.1 SUPPLEMENTAL INFORMATION Gaseous Batch Releases DRENPS Site

1. Number of Batch Releases

2. Total duration of batch releases

3. Maximum batch release duration

4. Average batch release duration

5. Minimum batch release duration Number of batch releases Units minutes minutes minutes minutes Total time period for a batch release Quarter 1

0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Maximum time period for a batch release Average time period for a batch release Minimum time period for a batch release Liquid Batch Releases DRENPS Site Units Quarter 1

1. Number of Batch Releases 0

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

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

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

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

6. Avg stream flow during periods of Ft3lsec release of liquid effluent into a NIA flowing stream Number of batch releases Total time period for a batch release Maximum time period for a batch release Average time period for a batch release Minimum time period for a batch release Average total* flow during period of release Quarter Quarter Quarter 2

3 4

0 0

0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+oo* O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0

O.OOE+dO minutes O.OOE+OO minutes O.OOE+OO minutes O.OOE+OO minutes Quarter Quarter Quarter 2

3 4

0 0

0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NIA NIA NIA 0

O.OOE+OO minutes O.OOE+OO minutes O.OOE+OO minutes O.OOE+OO minutes O.OOE+OO gpm Annual 0

O.OOE+OO O.OOE+:00 O.OOE+OO O.OOE+OO Annual 0

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NIA

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 20 of 62 Licensee: Constellation Enerav Companv, LLC I Plant: Dresden Nuclear Power Station 5.3 Abnormal Releases 5.3.1 Gaseous Abnormal Releases Number of releases 0

Total activity released O.OOE+OO Ci 5.3.2 Liquid Abnormal Releases 5.4 5.5 5.6 Number of releases 0

Total activity released O.OOE+OO Ci Land Use Census Changes No changes or modifications affecting significant aspects of the environmental monitoring program in 2023.

Meteorological Data Meteorological data collected for 2023 met the 90% data accumulation requirement.

Average data recovery was 99.8% Joint Frequency Distribution tables are available on site per request for 2023.

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

5. 7 Offsite Dose Calculation Manual (ODCM) Changes 5.8 5.9 No changes to the ODCM were made in 2023.

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

Radioactive Waste Treatment System Changes No changes to the Radioactive Waste Treatment System were made in 2023.

5.1 O Other Supplemental Information 5.10.1 Outside Tanks No tank exceeded ODCM or Tech Specs limits in 2023.

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

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 21 of 62 Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station

1.

Skyshine

2.

West Independent Spent Fuel Storage Installation (ISFSI) Pad

3.

East ISFSI Pad

4.

Condensate Storage Tanks (CST)

5.

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

Skyshine The radioactivity source that results in the most significant offsite radiation dose at the Dresden Station is skyshine resulting from 16N decay inside turbines and steam piping.

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

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

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

1.

The dose rate decreases as distance from the station increases.

2.

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

3.

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

To calculate offsite dose due to skyshine in a given time period, Dresden Station must track the following parameters:

1.

The total gross energy fa produced with hydrogen being added.

2.

The total gross energy Eo produced without hydrogen being added.

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

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

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 22 of 6;2 Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station Parameters for Calculations of N-16 Skyshine Radiation from Dresden Units 2 and 3 Shielding Location Occupancy Occupancy Factor Number K Activity Hours {OH)

Factor {OF)

{SF)

Distance {R) 1 Living at Home 8344 0.95 0.7 800 2

FishinQ 416 0.05 1

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

a.

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

1.

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

2.

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

b.

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

c.

Estimated from a drawing of the site.

d.

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

3.

A survey of the nearest residents revealed that as they do enjoy fishing, they spend far less time than the above estimate. In addition, because they live on the Kankakee River, they enjoy fishing at their homes rather than the designated 610 meters from the plant. :

As such, these assumptions have been adjusted in order to calculate a more accurate dose to the nearest resident at 868 meters from the plant with 8000 occupancy hours per*

year. This yielded a dose from Unit 2 due to skyshine of 2. t14 mrem and 2.256 mrem from Unit 3 for a total of 4.369 mrem for the site.

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

The equation for a point source is used (DR1*D?= DR2*Dl) to calculate the annual dose to the nearest member of the public. The OSLO with the highest annual reading was used

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 23 of 62 Licensee: Constellation Energy Companv, LLC I Plant: Dresden Nuclear Power Station because they have a lesser contribution by percent of background radiation lending to more accuracy in the dose attributable only to the ISFSI pad.

West ISFSI Pad Dose Calculations Q1 Q2 DR1 DR2 (mrem) (mrem) (mrem/vr)

D1 (ft)

D2 (ft)

(mrem/yr) 23 24 25 26 27 28 326.3 865.3 460.1 141.6 319.6 210.6 West ISFSI Pad 598 1065.8 491 162.9 399.7 235.6 924.3 136.18 2640 2.46 1931.1 91.38 2640 2.31 951.1 98.41 2640 1.32 304.5 89.99 2640 0.35 719.3 61.4 2640 0.39 446.2 117.3 2640 0.88

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 24 of 62 Licensee: Constellation EnerQV Company, LLC I Plant: Dresden Nuclear Power Station East ISFSI Pad Dose Calculations Q1 Q2 DR1 (mrem) (mrem)

(mrem/yr) 17 18 19 20 21 22 East ISFSI Pad 66.5 61.6 69.8 173 273.7 86.9 74.2 140.7 59.4 121.0 76.7 146.5 118.1 291.1 280.3 554.0 96.1 183.0 02 DR2 (ft)

(mrem/yr) 88.84 2660 0.16 99.39 2660 0.17 102.3 2660 0.22 117.0 2660 0.56 118.4 2660 1.10 97.39 2660 0.25 The highest annual dose received from the ISFSI pads were location 21 and 23. These results and distances from the center of the pad was used to calculate a dose of 2.46E+00 mrem/yr for the West pad and 1.1 0E+00 mrem/yr for the East pad. This resulted in a combined annual dose of 3.56E+00 mrem due to direct radiation from storage of spent fuel on the IFSFI pads.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 25 of 62 Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station Condensate Storage Tank (CST)

The Condensate Storage Tanks (A and 8) are a source of make-up water and has become contaminated through the operation of the plant. Although the level of contamination of the water inside the tank isn't at a level to produce a measurable dose rate, tanks are specifically listed in 40CFR 190 and a calculation of the annual dose to the nearest resident must be performed.

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

CST Dose Calculations Q1 Q2 (mrem) (mrem) 7 149.1 156.6 2/3 Condensate Storage Tanks DR1 (mrem/yr) 1 305.7 1

17 2540 DR2 (mrem/yr) 1 0.014 1

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

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

DR,*D12=DR2*Di it yields an annual dose of 1.40E-02 mrem. These calculations are very conservative because the measured dose is almost entirely from background and not from the plant or storage tanks.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 26 of 62

Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station GE Hitachi Nuclear Energy Facility This facility is located southwest of the Dresden Nuclear Power Station on Collins Rd and is the location of a de facto high-level radioactive waste storage site that holds 772 tons of spent nuclear fuel. The used fuel from various nuclear generating sites across the country are stored in a spent fuel pool at this location.

Since the source of radiation from the site is from the Uranium fuel cycle, the site is also required to ensure that the requirements of 40CFR190 and 1 0CFR72 are met.

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

40CFR190 states that the annual whole-body dose to a member ofthe public shall not exceed 25 mrem/yr from all sources of the uranium fuel cycle. This distinction dictates that the sum of the dose from the operation of the Dresden Nuclear Power Station and the GE Hitachi Nuclear Energy site cannot cause a member of the public to exceed a whole-body dose of 25 mrem/year. As a result, communication from the two sites is necessary to exchange the calculated dose contributions to ensure this requirement is met. The dose contribution from the GE Hitachi site for the 2023 year was: t.79E-01 mrem/yr.

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

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

Carbon-14 activity released is determined using Electric. Power Research Institute Report 1021106 Boiling Water Reactor proxy value of 5.1 Ci per GWth year, gaseous release fraction of 0.99%, a carbon dioxide fraction of 0.95, a reactor power rating of 2957 MWt for Units 2 and 3. The resultant dose due to C-14 was calculated using the EPRI approved C-14 worksheet. The equivalent full power days (EFPD) of operation of Unit 2 was: 336.5 EFPD and Unit 3 was: 359.1 EFPD which resulted in 13. 76 Ci of C-14 from Unit 2 and 14.69 Ci from Unit 3 being produced in 2023. The calculated dose from C-14 produced from Unit 2 was: 4.96E-03 mrem/yr (Total Body-Child) and 5.29E-03 mrem/yr (Total Body-Child) for Unit 3 for a Station total of 1.03E-02 mrem/yr.

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

5.10.4 Errata/Corrections to Previous ARERRs None

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 27 of 62 Licensee: Constellation Eneray Companv, LLC I Plant: Dresden Nuclear Power Station NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM 5.11 Dresden Nuclear Power Station 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.

Refer to Attachment 4, 2023 Annual RGPP Monitoring Report for information regarding Dresden's Radiological Groundwater Monitoring Program for 2023.

Voluntary Notification During 2023, Dresden Nuclear Power Station did not make a voluntary NEI 07-07 notification to State/Local officials, NRC, and to other stakeholders required by site procedures.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 28 of 62 Licensee: Constellation Enerav Comoanv, LLC \\

Plant: Dresden Nuclear Power Station 6.0

.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 1 O November 2020].

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

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

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

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

Nuclear Regulatory Commission, 1987.

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

Final Guidance Document, Rev. 1,"

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

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

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

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

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

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

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

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

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

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

Nuclear Regulatory Commission, July, 2007.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 29 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station, ARERR Release Summary Tables (RG-1.21 Tables) 1.0 GASEOUS EFFLUENTS Table 5, Gaseous Effluents Summation of All Releases Unit 17 A. Fission & Activation Quarter Quarter Quarter Quarter Est. Total Gases Unit 1

2 3

4 Annual Error%

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

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

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

2.

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

1. Total Release Ci 1.S0E-05 1.S0E-05 1.S0E-05 1.S0E-05 7.20E-05 2.94E+01

2. Average release rate for µCi/sec 2.31E-06 2.29E-06 2.26E-06 2.26E-06 2.28E-06 the period D. Tritium

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

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

1.

Total Release Ci N/A N/A NIA NIA N/A 2.94E+01

2.

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

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

2. Average release rate for µCi/sec N/A N/A NIA N/A N/A the period 7 % of limit is provided in Table 1, Dresden Nuclear Power Station Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 30 of 62 Licensee: Constellation Enerav Company, LLC /

Plant: Dresden Nuclear Power Station Table 6, Gaseous Effluents Summation of All Releases Unit 28 A. Fission & Activation Quarter Quarter Quarter Quarter Est. Total Gases Unit 1

2 3

4 Annual Error%

1. Total Release Ci 6.13E+00 5.76E+00 5.78E+00 5.11 E+00 2.28E+01 1.31 E+01

2. Average release rate for µCi/sec 7.89E-01 7.32E-01 7.28E-01 6.43E-01 7.23E-01 the period

8. lodine-131

1. Total Release Ci 1.09E-04 1.01 E-04 9.83E-05 3.29E-05 3.41 E-04 2.60E+01

2. Average release rate for µCi/sec 1.40E-05 1.29E-05 1.24E-05 4.14E-06 1.0SE-05 the period C. Particulates

1. Total Release Ci 3.0SE-04 5.83E-04 1.96E-04 1.27E-04 1.21 E-03 2.94E+01

2. Average release rate for µCi/sec 3.92E-05 7.42E-05 2.46E-05 1.60E-05 3.84E-05 the period D. Tritium

1. Total Release Ci 1.10E+01 8.18E+00 2.95E+00 4.69E+00 2.68E+01 7.56E+00

2.

Average release rate for µCi/sec 1.41E+00 1.04E+00 3.72E-01 5.90E-01 8.S0E-01 the period E. Gross Alpha

1.

Total Release Ci

<LLD

<LLD 2.94E+01

2.

Average release rate for µCi/sec

<LLD

<LLD the period F. Carbon-14

1. Total Release Ci 3.67E+00 3.57E+00 3.70E+00 2.82E+00 1.38E+01

2. Average release rate for µCi/sec 4.72E-01 4.54E-01 4.65E-01 3.55E-01 4.38E-01 the period 8 % of limit is provided in Table 1, Dresden Nuclear Power Station Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 31 of 62 Licensee: Constellation Enerav Companv, LLC I Plant: Dresden Nuclear Power Station Table 7, Gaseous Effluents Summation of All Releases Unit 39 A. Fission & Activation Quarter Quarter Quarter Quarter Est. Total Gases Unit 1

2 3

4 Annual Error%

1. Total Release Ci 1.77E+00 2.06E+00 2.25E+00 3.91E+00 9.98E+00 1.31 E+01

2. Average release rate for ~tCi/sec 2.27E-01 2.62E-01 2.83E-01 4.92E-01 3.17E-01 the period B. lodine-131

1. Total Release Ci 6.10E-05 5.47E-05 8.83E-05 6.08E-05 2.65E-04 2.60E+01

2. Average release rate for µCi/sec 7.85E-06 6.95E-06 1.11 E-05 7.64E-06 8.39E-06 the period C. Particulates

1. Total Release Ci 1.72E-04 2.95E-04 1.84E-04 2.20E-04 8.70E-04 2.94E+01

2. Average release rate for ~tCi/sec 2.21E-05 3.75E-05 2.31E-05 2.76E-05 2.76E-05 the period D. Tritium

1. Total Release Ci 6.35E+00 3.67E+00 2.75E+00 8.55E+00 2.13E+01 7.56E+00

2. Average release rate for µCi/sec 8.16E-01 4.66E-01 3.46E-01 1.08E+00 6.76E-01 the period E. Gross Alpha

1.

Total Release Ci

<LLD

<LLD 2.94E+01

2.

Average release rate for µCi/sec

<LLD

<LLD the period F. Carbon-14

1. Total Release Ci 3.63E+00 3.55E+00 3.76E+00 3.76E+00 1.47E+01

2. Average release rate for µCi/sec 4.67E-01 4.52E-01 4.73E-01 4.73E-01 4.66E-01 the period 9 % of limit is provided in Table 1, Dresden Nuclear Power Station Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 32 of 62 Licensee: Constellation Enerav Company, LLC \\

Plant: Dresden Nuclear Power Station Table 8, Gaseous Effluents - Ground Level Release Batch Mode Unit 1 Radionuclide

Units Quarter 1 Quarter 2 Quarter 3 Quart--

tal for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

.Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium**

~ ; "

H-3 Ci

~LLD

<LLD

<LLD Gross ~lpha

~

Alpha Ci

<LLD

<LLD Carbon.-14

),',

C-14 Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 33 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 9, Gaseous Effluents - Ground Level Release Continuous Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci 1.B0E-05 1.B0E-05 1.80E-05 1.80E-05 7.20E-05 Total for Period Ci 1.B0E-05 1.S0E-05 1.S0E-05 1.B0E-05 7.20E-05 Tritium I

H-3 I Ci I

<LLD

<LLD GrQSS Alpha I

Alpha I Ci I

<LLD

<LLD Carbon-14 C-14 Ci

<LLD

<LLD II

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 34 of 62 Licensee: Constellation Energy Company, LLC \\

Plant: Dresden Nuclear Power Station Table 10, Gaseous Effluents - Ground Level Release Batch Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3 Ci I

<LLD I

<LLD Gross~lpha Alpha Ci

<LLD

<LLD I

Carbon~14 C-14 Ci

<LLD

Annual Radioactive Effluent Release Report

/ YEAR: 2023

/

Page 35 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 11, Gaseous Effluents - Ground Level Release Continuous Mode Unit 2 Radionuclide Released 1 lni+c, nuarter 1 Quarter 2 Quarter3 Quarter4 Total for year Fission Gases Ar-41 Ci 3.60E-08 3.62E-08 4.32E-08 3.84E-08 1.54E-07 Kr-85 Ci

<LLD

<LLD Kr-85m Ci 3.09E-08 3.18E-08 3.99E-08 1.72E-08 1.20E-07 Kr-87 Ci 1.77E-07 1.83E-07 2.19E-07 9.43E-08 6.73E-07 Kr-88 Ci 1.15E-07 1.17E-07 1.42E-07 5.92E-08 4.34E-07 Xe-133 Ci 5.77E-09 5.53E-09

<LLD

<LLD 1.13E-08 Xe-135 Ci 1.76E-07 1.92E-07 3.78E-09 1.95E-09 3.74E-07 Xe-135m Ci 3.77E-07 3.88E-07

<LLD

<LLD 7.65E-07 Xe-138 Ci 1.50E-06 1.51 E-06

<LLD

<LLD 3.01E-06 Total for Period Ci 2.42E-06 2.46E-06 4.49E-07 2.11E-07 5.54E-06 Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD I Tritium H-3 Ci

<LLD

<LLD GrqssAlpha Alpha Ci

<LLD

<LLD I

~

rbon-14 C-14 Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 36 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 12, Gaseous Effluents - Ground Level Release Batch Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines*

1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3 Ci

<LLD

<LLD I

I Gross Alpha

I I

Alpha I Ci I

<LLD

<LLD I

Carbon-14 I

C-14 I Ci !

<LLD I

<LLD II

<LLD I

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 37 of 62 Licensee: Constellation Energy Companv, LLC I Plant: Dresden Nuclear Power Station Table 13, Gaseous Effluents - Ground Level Release Continuous Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Fission Gases Ar-41 Ci 1.73E-08 1.95E-08 3.40E-08 3.92E-08 1.10E-07 Kr-85 Ci

<LLD

<LLD Kr-85m Ci 1.42E-08 1.50E-08 1.86E-08 2.23E-08 7.01E-08 Kr-87 Ci 7.99E-08 8.48E-08 9.96E-08 1.24E-07 3.89E-07 Kr-88 Ci 4.74E-08 5.44E-08 6.40E-08 7.45E-08 2.40E-07 Xe-133 Ci 1.17E-09 5.27E-10 6.65E-10

<LLD 2.36E-09 Xe-135 Ci 9.32E-08 1.05E-07 1.13E-07 1.33E-07 4.44E-07 Xe-135m Ci 2.01E-07 2.12E-07 2.38E-07 3.17E-07 9.68E-07 Xe-138 Ci 7.00E-07 7.52E-07 8.84E-07 1.21 E-06 3.55E-06 Total for Period Ci 1.15E-06 1.24E-06 1.45E-06 1.92E-06 5.77E-06 lodil)eS 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD iurp H-3 Ci

<LLD

<LLD I

Gross Alpha Alpha Ci I

<LLD I

<LLD II

<LLD I

Carbon-14 C-14 Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 38 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 14, Gaseous Effluents - Mixed Level Release Batch Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD,

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulat~s Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3 Ci II

<LLD

<LLD Gross Alpha*

\\

Alpha Ci

<LLD

<LLD Carbon~14 0

C-14 Ci

<LLD

Annual Radioactive Effluent Release Report

I YEAR: 2023 I Page 39 of 62 Licensee: Constellation Enerav Company, LLC \\

Plant: Dresden Nuclear Power Station Table 15, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 1 Radionuclide Units I Quarter 1 I Quarter 2 I Quarter 3 I Quarter4 I Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3 Ci

<LLD

<LLD I

Gross Alpha Alpha Ci

<LLD

<LLD I

Carbon-14 C-14 Ci

<LLD

<LLD I

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 40 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 16, Gaseous Effluents - Mixed Level Release Batch Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released i= ii;sion ~ases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium

.-.: *~

H-3 Ci

<LLD

<LLD Gross Alpha' Alpha Ci

<LLD

_Ca,rbon~1*4

""'M C-14 Ci

<LLD

Annual Radioactive Effluent Release Report

/ YEAR: 2023 I Page 41 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 17, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter I r Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci 2.45E-06 1.14E-06

<LLD

<LLD 3.59E-06 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci 2.45E-06 1.14E-06

<LLD

<LLD 3.59E-06 Particulates Cr-51 Ci

<LLD

<LLD 1.46E-06 1.46E-06 Mn-54 Ci

<LLD

<LLD 2.78E-06 2.78E-06 Fe-55 Ci

<LLD 7.81E-06

<LLD

<LLD 7.81E-06 Co-58 Ci

<LLD

<LLD 2.96E-06 2.96E-06 Co-60 Ci 1.54E-06 9.79E-06

<LLD 1.15E-07 2.28E-05 Zn-65 Ci

<LLD

<LLD 7.83E-06 7.83E-06 Total for Period Ci 1.54E-06 1.76E-05

<LLD 2.65E-05 4.56E-05 Tritium

.c' H-3 Ci 2.82E+00 2.70E+00 1.72E+00 2.99E+00 1.02E+01 Gross Alpha Alpha Ci II

~LLD

<LLD

<LLD II C_arpoo-14

., )

fr

./.,.

it C-14 Ci

<LLD

<LLD I

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 42 of 62 Licensee: Constellation Eneray Company, LLC I Plant: Dresden Nuclear Power Station Table 18, Gaseous Effluents - Mixed Level Release Batch Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Fission Gases "

Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines*

1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Pa.rticulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD lritium.**

H-3 Ci

<LLD

<LLD ssAlpha Alpha Ci

<LLD

<LLD 11

<LLD I

Carbon~14 C-14 Ci

<LLD

<LLD I

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 43 of 62 Licensee: Constellation Enen:iy Company, LLC I Plant: Dresden Nuclear Power Station Table 19, Gaseous Effluents - Mixed Level Release Continuous Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci 1.39E-06 6.60E-07

<LLD

<LLD 2.0SE-06 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci 1.39E-06 6.S0E-07

<LLD

<LLD 2.0SE-06 Particulates Cr-51 Ci

<LLD

<LLD 1.61E-11 1.61E-11 Mn-54 Ci

<LLD

<LLD 5.86E-06 5.86E-06 Fe-55 Ci

<LLD 4.49E-06

<LLD

<LLD 4.49E-06 Co-58 Ci 1.19E-07 2.21E-07

<LLD 6.24E-06 6.58E-06 Co-60 Ci

<LLD 3.75E-06

<LLD 2.33E-05 2.71E-05 Zn-65 Ci

<LLD

<LLD 1.65E-05 1.65E-05 Total for Period Ci 1.19E-07 8.46E-06

<LLD 5.19E-05 6.0SE-05 Tritium C

H-3 Ci 1.63E+00 1.58E+00 1.60E+00 5.73E+00 1.05E+01 Gross Alph 0

a o'

Alpha Ci II

-::LLD

<LLD

<LLD II Carbon-14 C-14 Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 44 of 62 Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station Table 20, Gaseous Effluents - Elevated Level Release Batch Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines j,.

1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

>,*\\

't:

tes Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritiur:n H-3 Ci

<LLD

<LLD qro~~Alpha

/"

Alpha Ci

<LLD

<LLD Carbpn-14 C-14 Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 45 of 62 Licensee: Constellation Energy Company, LLC \\

Plant: Dresden Nuclear Power Station Table 21, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particulates

',,~

Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium i

~*,

H-3 Ci

<LLD

<LLD Gross Alp~a.-....

~-,

..,,_,i.,'

Alpha Ci

<LLD

<LLD Carbon-14

,,". t I

C-14 I Ci II

<LLD I

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 46 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 22, Gaseous Effluents - Elevated Level Release Batch Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission* Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines

" v' 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Particu]ates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium/

H-3 Ci

<LLD

<LLD Gross Alpha I

Alpha I Ci II

<LLD I

<LLD Carb,o~~14

~"*

~>

I C-14 I Ci II

<LLD I

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 47 of 62 Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station Table 23, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Fission Gases Ar-41 Ci 1.10E+00 1.22E+00 7.47E-01 6.17E-01 3.68E+00 Kr-85 Ci

<LLD

<LLD 4.10E-03 4.10E-03 Kr-85m Ci 2.05E-01 2.33E-01 1.47E-01 1.38E-01 7.22E-01 Kr-87 Ci 1.26E-01 1.07E-01 1.33E-01 4.54E-01 8.20E-01 Kr-88 Ci 1.17E-01 1.19E-01 1.09E-01 4.56E-02 3.92E-01 Xe-133 Ci 5.41E-01 5.89E-01 3.53E-01 6.65E-01 2.15E+00 Xe-135 Ci 1.08E-01 1.10E-01 1.41E-01 2.13E-01 5.71 E-01 Xe-135m Ci 7.27E-01 6.34E-01 7.82E-01 8.39E-01 2.98E+00 Xe-138 Ci 3.21E+00 2.75E+00 3.37E+00 2.14E+00 1.15E+01 Total for Period Ci 6.13E+00 5.76E+00 5.78E+00 5.11E+00 2.28E+01 Iodines 1-131 Ci 1.06E-04 1.00E-04 9.83E-05 3.29E-05 3.37E-04 1-133 Ci 9.08E-04 9.70E-04 8.35E-04 2.29E-04 2.94E-03 1-135 Ci 3.79E-04 2.32E-04 4.16E-04 8.64E-05 1.11 E-03 Total for Period Ci 1.39E-03 1.30E-03 1.35E-03 3.49E-04 4.39E-03 Particulates Cr-51 Ci

<LLD 4.05E-05

<LLD

<LLD 4.05E-05 Mn-54 Ci 4.26E-05 7.15E-05 2.38E-05 1.40E-05 1.52E-04 Fe-55 Ci

<LLD 8.75E-05

<LLD

<LLD 8.75E-05 Co-58 Ci 5.56E-05 5.82E-05 5.70E-06 3.49E-06 1.23E-04 Co-60 Ci 1.46E-04 2.02E-04 1.10E-04 6.79E-05 5.26E-04 Zn-65 Ci 4.35E-05 6.87E-05 3.56E-05 5.66E-06 1.53E-04 Sr-89 Ci

<LLD 9.44E-06 1.47E-05 4.57E-06 2.87E-05 Sn-117m Ci 1.17E-05 7.51E-06 6.30E-06 5.13E-06 3.06E-05 Ba-140 Ci 3.43E-06 2.03E-05

<LLD

<LLD 2.37E-05 Total for Period Ci 3.03E-04 5.66E-04 1.96E-04 1.01E-04 1.17E-03 Tritium H-3 Ci 8.16E+00 5.48E+00 1.23E+00 1.70E E+01 Gross.f\\lpha.

Alpha Ci

<LLD

<LLD I

Carbori'-14 C-14 Ci I 3.67E+00 I

3.57E+00 I

3.70E+00 I

2.82E+00 I

1.38E+01

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 48 of 62 Licensee: Constellation Enen:iv Companv, LLC I Plant: Dresden Nuclear Power Station Table 24, Gaseous Effluents - Elevated Level Release Batch Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Fission Gases Ar-41 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Iodines 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

~articulates Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium H-3 Ci

<LLD

<LLD Gross Alf)ha Alpha Ci I

<LLD I

<LLD II

<LLD I

Carbon-14 I

C-14 I Ci I

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 49 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 25, Gaseous Effluents - Elevated Level Release Continuous Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Fission Gases Ar-41 Ci 6.66E-03 7.31E-03 4.39E-01 4.39E-01 8.92E-01 Kr-85 Ci 3.28E-01 5.47E-01 1.0SE-01 4.26E-03 9.87E-01 Kr-85m Ci 4.S0E-03 5.05E-03 2.48E-02 5.33E-02 8.79E-02 Kr-87 Ci 8.26E-02 7.53E-02 4.84E-02 3.74E-01 5.S0E-01 Kr-88 Ci 1.64E-02 1.90E-02 2.56E-02 5.38E-03 6.64E-02 Xe-133 Ci 1.12E-02 1.00E-02 7.63E-02 4.92E-01 5.90E-01 Xe-135 Ci 2.04E-01 1.79E-01 6.49E-02 2.12E-01 6.60E-01 Xe-135m Ci 2.24E-01 2.47E-01 2.82E-01 8.60E-01 1.61E+00 Xe-138 Ci 8.88E-01 9.73E-01 1.18E+00 1.47E+00 4.51E+00 Total for Period Ci 1.77E+00 2.06E+00 2.25E+00 3.91E+00 9.98E+00 Iodines 1-131 Ci 5.96E-05 5.40E-05 8.83E-05 6.0SE-05 2.63E-04 1-133 Ci 5.13E-04 5.36E-04 7.67E-04 3.14E-04 2.13E-03 1-135 Ci 2.00E-04 1.35E-04 3.66E-04 7.75E-05 7.79E-04 Total for Period Ci 7.73E-04 7.25E-04 1.22E-03 4.53E-04 3.17E-03 Particulates Cr-51 Ci

<LLD 2.35E-05

<LLD

<LLD 2.35E-05 Mn-54 Ci 2.37E-05 4.24E-05 2.20E-05 2.76E-05 1.16E-04 Fe-55 Ci

<LLD 4.98E-05

<LLD

<LLD 4.98E-05 Co-58 Ci 3.15E-05 3.09E-05 5.57E-06 6.12E-06 7.40E-05 Co-60 Ci 8.30E-05 9.03E-05 1.03E-04 1.10E-04 3.86E-04 Zn-65 Ci 2.48E-05 3.28E-05 3.39E-05 1.19E-05 1.03E-04 Sr-89 Ci

<LLD 5.38E-06 1.35E-05 7.48E-06 2.64E-05 Sn-117m Ci 7.01E-06 2.37E-06 6.11 E-06 4.61E-06 2.01E-05 Ba-140 Ci 1.81 E-06 8.88E-06

<LLD

<LLD 1.0?E-05 Total for Period Ci 1.72E-04 2.86E-04 1.84E-04 1.68E-04 8.10E-04 Tritium I

H-3 I Ci I 4.71E+00 2.09E+00 1.16E+00 2.82E+00 1.08E+01 Gross Alpha Alpha Ci

<LLD

<LLD Carbon-14 C-14 Ci 3.63E+00 3.55E+00 3.76E+00 3.76E+::

1.-.,._ 'UI II

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 50 of 62.**

Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station 2.0 LIQUID EFFLUENTS Table 26, Liquid Effluents - Summation of All Releases Unit 110 Quarter Quarter Quarter Quarter Annual Est. Total A. Fission & Activation Products Unit 1

2 3

4 Error%

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

2.

Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A B. Tritium

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

2. Average diluted concentration

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

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

2. Average diluted concentration

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

1.

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

2. Average diluted concentration

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

F. Volume of Dilution Water Used Liters N/A N/A NIA N/A NIA During Period 10 % of limit is provided in Table 1, Dresden Nuclear Power Station Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 51 of 62 Licensee: Constellation Enerav Company, LLC I Plant: Dresden Nuclear Power Station Table 27, Liquid Effluents - Summation of All Releases Unit 211 A. Fission & Activation Products Unit Quarter Quarter Quarter Quarter Annual Est. Total 1

2 3

4 Error%

1. Total Release Ci N/A N/A

<LLD N/A

<LLD 1.95E+01

2.

Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A B. Tritium

1. Total Release Ci N/A NIA 3.21E-04 N/A 3.21E-04 2.37E+00

2. Average diluted concentration

µCi/ml N/A N/A 8.14E-13 N/A 8.14E-13 C. Dissolved & Entrained Gases

1. Total Release Ci N/A N/A

<LLD N/A

<LLD 2.03E+,01

2. Average diluted concentration

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

1.

Total Release Ci N/A N/A

<LLD N/A

<LLD 2.00E+01

2.

Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A E. Volume of Waste Released (prior Liters NIA N/A 1.72E+05 N/A 1.72E+05 to dilution)

F. Volume of Dilution Water Used Liters N/A N/A 3.95E+11 N/A 3.95E+11 During Period 11 % of limit is provided in Table 1, Dresden Nuclear Power Station Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 52 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 28, Liquid Effluents - Summation of All Releases Unit 312 A. Fission & Activation Products Unit Quarter Quarter Quarter Quarter Annual Est. Total 1

2 3

4 Error%

1. Total Release Ci N/A N/A

<LLD

~/A

<LLD 1.95E-i:-01

2.

Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A B. Tritium

1. Total Release Ci N/A NIA 3.21E-04 NIA 3.21E-04 2.37E+0O

2. Average diluted concentration

µCi/ml N/A NIA 8.14E-13 N/A

.8.14E-13 C. Dissolved & Entrained Gases

1. Total Release Ci N/A N/A

<LLD NIA

<LLD 2.03E+01

2. Average diluted concentration

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

1.

Total Release Ci N/A NIA

<LLD N/A

<LLD 2.00E+01

2. Average diluted concentration

µCi/ml N/A N/A N/A N/A N/A E. Volume of Waste Released (prior Liters N/A NIA 1.72E+05 N/A 1.72E+05 to dilution)

F. Volume of Dilution Water Used Liters N/A N/A 3.95E+11 N/A 3.95E+11 During Period 12 % of limit is provided in Table 1, Dresden Nuclear Power Station Unit 1 Dose Summary

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 53 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 29, Liquid Effluents Batch Mode Unit 1 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released Fi$sion-and Activation Products

-l Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Ag-110m Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Tritium

"-~* '

1

),

r

/

H-3 Ci I

<LLD I

<LLD II

<LLD I

Grqss'Alpha" y'

Alpha Ci

<LLD

<LLD E:ntrained Gas.es

1-* *_--

h t_*

e tC Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 54 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Radionuclide Released Units Table 30, Liquid Effluents Continuous Mode Unit 1 Quarter 1 Quarter 2 Quarter 3 Fission and.Ac!iyation Pr6auc~s Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Ag-110m Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD H-3

<LLD

~ross Alph~:

Ci I I

<LLD Alpha Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Total for Perioa Ci

<LLD

<LLD Quarter4 Total for year

<LLD

<LLD I

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 55 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 31, Liquid Effluents Batch Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fission and,Activa_tion Products

{',' -

.t*

fy, Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Ag-110m Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Total for Period Ci

<LLD

~

'<<{'

'i, Ci II

~LLD

<LLD

<LLD c*

Alpha Ci

<LLD

Entrained Gases,

l'*

Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 56 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 32, Liquid Effluents Continuous Mode Unit 2 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter4 Total for year Released and ActivationPrd.ducts.

\\*

Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Ag-110m Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD Triti~m I

H-3 I Ci I

<LLD

<LLD 3.21E-04

<LLu 3.21E-04 Gross Alpha...

><Lld Alpha Ci

<LLD

<LLD Erltrained"Gases {;_

,;'.~

Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 57 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station Table 33, Liquid Effluents Batch Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released Fissi.on arid:Activatiori Ptoducts Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Ag-11 Om Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD tritium

\\

H-3 Ci

<LLD

<LLn

Gross,AfpMr Alpha Ci

<LLD

<LLD Ehtrain~d Gase:s Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 58 of 62 Licensee: Constellation Energy Companv, LLC I Plant: Dresden Nuclear Power Station Table 34, Liquid Effluents Continuous Mode Unit 3 Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Released I Fission ~nd Aqtiv~tion P~odyds L

I Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Fe-55 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Ag-110m Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-133 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD T:ritium r

H-3 Ci

<LLD

<LLD 3.21E-04

<LLD I

3.21E-04 I

G:rq_ss Al~h~

=

Alpha Ci

<LLD

<LLD Entrained Gases Xe-133 Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Total for Period Ci

<LLD

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 59 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station, Solid Waste Information 1.0 SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL}

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

(Ci)

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

1.58E+02 1.31 E+02

b. Dry compressible waste, contaminated equip, etc.

8.51 E+02 1.66E+01

c. Irradiated components, control rods, etc.

0.00E+00 0.00E+00

d. Other (describe) 1.30E+01 1.29E-02 Est. Total Error

(%)

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

ARE REPORTED. [NOTE 1]

Table 36, Major Nuclides Site Major Nuclide Composition Curies

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

Co-60 43.85 5.77E+01 Cs-137 30.61 4.02E+01 Fe-55 19.02 2.50E+01 Ni-63 3.03 3.98E+00 Mn-54 1.14 1.50E+00 Zn-65 1.12 1.47E+00

b. Dry compressible waste, contaminated equip, etc.

Fe-55 52.61 8.76E+00 Co-60 43.96 7.32E+00 Mn-54 1.11 1.84E-01

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 60 of 62 Licensee: Constellation Energv Company, LLC \\

Plant: Dresden Nuclear Power Station Table 36, Major Nuclides Site

c. Irradiated components, control rods, etc.

None

d. Other (describe)

Fe-55 47.28 6.11E-03 Co-60 39.19 5.06E-03 Mn-54 5.1 6.59E-04 Cr-51 2.39 3.09E-04 Zn-65 2.26 2.91E-04 Co-58 1.07 1.39E-04 Fe-59 1.06 1.38E-04 3.0 SOLID WASTE DISPOSITION Table 37, Solid Waste Disposition Site Number of Mode of Transportation Destination Shipments 21 Hittman Transport Energy Solutions Services (Bear Creek) 1560 Bear Creek Road 27 Hittman Transport Energy Solutions Clive CWF Clive Containerized Waste Facility 4.0 IRRADIATED FUEL DISPOSITION None

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 61 of 62 Licensee: Constellation Enernv Company, LLC I Plant: Dresden Nuclear Power Station, Meteorological Data 1.0 METEOROLOGICAL DATA

SUMMARY

1.1 Joint Frequency Distributions Joint Frequency Distribution tables are available on site per request for 2023.

1.2 Stability class Stability class information can be found in the Joint Frequency Distribution tables for 2023.

Annual Radioactive Effluent Release Report I YEAR: 2023 I Page 62 of 62 Licensee: Constellation Energy Company, LLC I Plant: Dresden Nuclear Power Station, 2023 Annual RGPP Monitoring Report

875 North Easton Road Suite 10 Doylestown, PA 18902 AMO ENVIRONMENTAL DECISIONS

~ ~ iii Environmental Risk & Remediation Consultants 215-230-8282 (Phone) 215-230-8283 (Fax)

"'"'"'*amoed.com February 15, 2024 Constellation Energy Company, LLC Dresden Generating Station 6500 North Dresden Road Morris, IL 60450-9709

Subject:

2023 Annual RGPP Monitoring Report Summary of Resu Its and Cone! us ions Dresden Generating Station Morris, Illinois Geologists Hydrogeologists GIS Analysts Environmental Scientists This letter report presents the summary of Radiologic Groundwater Protection Plan (RGPP) results for the 2023 groundwater and surface water monitoring rounds conducted at the Constellation Dresden Generating Station. RGPP data for previous monitoring rounds is summarized in AMO's semi-annual/quarterly reports.

Background

In 2006, Conestoga-Rovers & Associates (CRA) was retained by Exelon Nuclear to perform a hydrogeologic investigation at the Dresden Generating Station to evaluate whether groundwater at or near the Station has been impacted by releases of radionuclides. Prior to performing the investigation, CRA evaluated available information concerning historic releases, as well as components, structures, and areas of the facility that have the potential to release radioactive liquid to the environment.

The results of the 2006 investigation identified that almost half of the 39 wells within the protected are showed measurable concentrations of tritium. It was concluded that the tritium in groundwater within the protected area came from historic spills from above ground tanks and leaks of underground lines within the protected area. Groundwater samples collected outside the protected area showed no detectable tritium for 24 of the 26 wells. The two exceptions for the wells outside the protected area include wells DSP 149(R) and DSP-159-1 (M).

The results of the fleet wide study for the Dresden Generating Station (the Station) are presented in the report, entitled Hydrogeologic Investigation Report, Fleetwide Assessment, Dresden Generating Station, Braceville, Illinois (Conestoga-Rovers & Associates, September 2006). The referenced report also provides detailed descriptions of the Station's location, surrounding features and land use, subsurface geology and hydrogeology, and a summary of groundwater use in the area of the Station.

GHD completed three five-year update hydrogeologic investigation reports for the Station (NE! 07-07, Hydrogeologic Investigation Report, dated May 2011, December 201 5, and December 2020). The reports summarized station activities since the 2006 hydrogeologic investigation, including changes at the Station as well as RGPP sampling activities and groundwater flow. Relevant conclusions from the 2020 report are:

Tritium is not migrating off the Station at concentrations greater than the State of Illinois criteria of 200 pCi/L.

Tritium concentrations in groundwater were detected at concentrations greater than the USEPA drinking water standard. The maximum tritium concentration at the end of 20 19 was 33,850 pCi/L Dresden 2023 Summary Report

T c"(I

2023 RGPP Monitoring Report Dresden Generating Station (MD-11). Tritium concentrations greater than the USEPA drinking water standard were limited to the "8" CST, south of the Unit 3 Turbine Building.

No gamma-radionuclides associated with licensed plant operations were detected at concentrations greater than their respective LLDs.

Select transuranics U-233/234 and U-238 were occasionally detected in several wells since 2016. The concentrations are considered background.

In 201 9, Ni-63 was consistently detected in monitoring wells MW-DN-1011 and MW-DN-11 91. Per revision 9 of the RGPP, and to investigate Ni-63 in groundwater, the Station includes Ni-63 and Fe-55 analysis for all Source wells and all Long-Term Shutdown wells currently sampled as part of the RGPP.

In 20 I 9, multiple Sr-90 concentrations were detected above its LLD. Sr-90 was detected in samples collected from MW-ON-I 05S three of the four sampling rounds in 20 19. Sr-90 was also detected in DSP-1 08 during the second quarter 2019 RGPP sampling round.

AFE-1 remains an ongoing tritium source to groundwater. No new AFEs were identified based on results between 2006 and 20 15.

Extraction well R W-DN-1 00S continued to withdraw tritiated water from the " B" CST area. Up until August/September 20 19, groundwater withdrawal from R W-DN-1 00S was on an intermittent basis.

Continuous groundwater extraction of RW-DN-I00S began in September 2019. As of the date of the report, over one million gallons of groundwater was extracted from RW-DN-1 00S. The extracted groundwater is discharged to the Kankakee River through a permitted outfall (Outfall 002).

The next hydrogeologic investigation update is due by the end of 2025.

"B" Condensate Storage Tank Elevated tritium concentrations in surface water (Sewage Treatment Plant (STP) samples and RGPP surface water samples), shallow aquifer samples, and intermediate aquifer samples were detected during the 2nd quarter 2014 RGPP sampling round. The source of the tritiated groundwater was determined to be the "8" Condensate Storage Tank (CST) south of the Turbine Buildings. The groundwater sample collected from shallow aquifer well MD-11, which is in the immediate vicinity of the CST, had a tritium concentration of approximately 1.5 million pCi/L. Subsequent samples collected from MD-I I have had a maximum tritium concentration of approximately 2.3 mi Ilion pCi/L (June 27, 20 14 ). The CST was taken out of service and water from the CST removed. The CST was inspected and subsequently repaired in August 2015.

A tritium monitoring plan was developed and implemented in June 20 14, with weekly sampling of surface water, storm sewer water, sewer treatment plant water, shallow aquifer groundwater, and intermediate aquifer groundwater to evaluate and delineate the tritium plume. A modified tritium monitoring plan was implemented in November 2014. Based on tritium data collected, the plume was relatively small and only encompassed the area between the CST and Turbine Building.

Two groundwater extraction wells (R W-DN-1 00S and RW-DN-10 IS) were installed in January 2015 to assist in the mitigation of tritiated groundwater in the area of the CST. Aquifer testing was completed on the two extraction wells near the end of2015. Results of the aquifer test concluded that only R W-DN-1 00S produced sufficient water to operate as a viable groundwater extraction well. RW-DN-1 00S began intermittent operation during the I st quarter 2016 and continued operating intermittently through August 2019. In August 2019, the extraction well began pumping groundwater on a continuous basis. The extracted water is discharged to the Dresden 202} SUrMW') Report* T~"

Page 2 of JO AMO Environmental Decisions

2023 RGPP Monitoring Report Dresden Generating Station Kankakee River through NPDES permitted Outfall 002. Overall, tritium concentrations in the area of the CST continue to decrease since the CST was repaired.

As of the end of 2023, the maximum tritium concentration in the area of the CST was approximately 4,330 pCi/L (MD-I I).

MW-DN-1191 Nickel 63 Hard-to-detect radionuclide Nickel-63 was detected at a concentration over 50 pCi/L in a sample collected during the 2nd quarter 2017. An investigation into the source of the Nickel-63 was completed and additional samples were collected from MW-DN-1191 and surrounding wells. Results and recommendations of the evaluation are included in AM O's Evaluation of Nickel -63 detections in MW-DN-1191 Update (March 28, 2018). Hard-to-detects (Fe-55 and Ni-63) are currently analyzed annually to monitor concentrations in the area of MW-DN-1191.

As of the end of 2023, Ni-63 was not detected in the sample collected from MW-DN-1191.

Current RGPP Summary Dresden Generating Station had a total of 59 wells (20 Background wells, 18 Source wells, six Mid-Field wells, ten Long-Term Shutdown wells, and five perimeter wells), that are sampled as part of the Station ROPP (EN-DR-408-4160 Revision I 0). Figure I a shows the shallow aquifer ROPP sample locations and Figure I b shows the intermediate aquifer ROPP sample locations.

ROPP sampling at the Station is performed by ATI, under contract to Exelon. Laboratory testing is performed by Teledyne Brown Engineering. The laboratory data, field data, and depth to water readings are uploaded to the RACER website, which is a data repository for the ROPP sampling rounds. The uploaded data is used by AMO for quarterly ROPP reporting.

Gross-Alpha Alert Level At Dresden Generating Station, gross-alpha (dissolved and suspended fractions) was analyzed annually from 201 1 through 2019. In 2020, gross-alpha data was evaluated to establish an Alert Level for the dissolved and suspended gross-alpha fractions. The gross alpha data was evaluated by looking at the average concentration for each gross-alpha fraction for each well. Statistical outlier results were considered during the gross-alpha evaluation. An outlier is a value that is significantly higher or lower than most of the results, that can skew the results and not reflect the true dataset. Therefore, outlier results are not factored into the average gross-alpha concentrations. Outliers were established using methods an online website such as Statisticshowto.com.

Additional websites identified similar statistical models for removing outlier data.

Procedure EN-DR-408-4160 (Revision 9) established an Alert Level of three times the ongoing average gross-alpha concentration for each ROPP monitoring well that had gross-alpha analyzed more than one time and that will continue to be monitored for during future ROPP sampling rounds. Note that in 2024, the Alert Level will change from three times the ongoing average to three times the ongoing standard deviation. According to the EN-DR-408-4160 (Revision I 0), samples from the eighteen Source designated sample points and ten Long-Term Shutdown designated wells will be analyzed once every two years for gross alpha dissolved and suspended fractions in the future. The Alert Level will be able to account for fluctuations in naturally occurring alpha activity in the area of wells, while identifying a result that may be indicative of a potential release.

Beginning in 202 1, select transuranics were analyzed if a gross alpha concentration exceeded the Alert Level in a particular well, to ensure that the Alert Level is conservative enough to detect whether licensed material could be present in groundwater. If the results of the select transuranics analysis showed no unusual activity, Page 3 of 10 AMO Environmental Decisions

2023 RGPP Monitoring Report Dresden Generating Station the gross-alpha result that triggered the select transuranics analysis, was incorporated into the ongoing average concentration for that well.

Table I provides a gross-alpha (dissolved and suspended) results summary as well as the average concentration and Alert Level for each well. Gross-alpha analysis was most recently performed on samples collected from Long-Term Shutdown Source designated wells during the 2nd quarter 2023 ROPP sampling round. Note that a sample could not be collected from Long-Term Shutdown well MW-DN-1171 because the well was inaccessible in 2023. Gross-alpha detections did not exceed the Alert Level in samples collected in 2023. Per the ROPP, all Long-Term Shutdown and Source designated wells will have gross-alpha analysis performed again in 2025.

Gamma-Radionuclides Gamma-radionuclide analysis has been performed on ROPP samples (quarterly to annually) at Dresden Generating Station since 2006. This extensive sampling and analysis produced over 16,800 data records for the Station. Gamma-radionuclides have not been detected at concentrations greater than their respective LLDs, in ROPP samples submitted to the vendor laboratory since 2006. Therefore, in the 2020 ROPP, gamma-radionuclide analysis frequency was reduced from annual to every two years.

Samples collected from all wells were most recently analyzed for gamma-radionuclides during the 2nd quarter 2023 ROPP sampling round. Note that a sample could not be collected from Long-Term Shutdown well MW-MW-DN-106S, MW-DN-1081, and DN-11 71 because the wells were inaccessible in 2023.

Gamma radionuclides were not detected at concentrations greater than their respective LLDs in the samples collected in 2023. All wells will have gamma-radionuclide analysis performed again in 2025.

Select Transuranics Select transuranics analysis is procedurally required annually for ROPP sample locations that were identified as Elevated designated wel Is in the historic EN-DR-408-4 160 revisions and continued additional evaluation is warranted. Additionally, as part of the current EN-DR-408-4160 (Revision l 0), select transuranics analysis is also warranted if a gross alpha concentration exceeds the Alert Level in a particular well.

Select transuranics analysis was performed on former Elevated designated wells MD-I 1, MW-DN-l 24S, and MW-DN-1241, during the 2nd quarter 2023 ROPP sampling round. Select Transuranics were not detected at concentrations greater than their respective LLDs in the samples collected during the 2nd quarter 2023 ROPP sampling round. Table 2 provides a summary of select transuranics results (U-233/234 and U-238) since 2006.

Hard-to-Detects {Fe-55 and Ni-63)

Hard-to-detect analysis (Fe-55 and Ni-63) is procedurally required annually for ROPP sample locations that were identified as Elevated designated wells in the historic EN-DR-408-4160 revisions and continued additional evaluation is warranted, as well as Long-Term Shutdown designated wells. Additionally, as part of the current EN-DR-408-4 160 (Revision 9), hard-to-detect analysis is warranted on samples collected from Source designated wells once every 5 years, starting in 2021.

In 2023, samples collected from the nine Long-Term Shutdown designated wells, one former Elevated designated well, and two Source designated well were analyzed for hard-to-detects (Fe-55 and Ni-63). Fe-55 and Ni-63 were not detected in the samples collected during the 2nd quarter 2023 ROPP sampling round.

Orudrn 2023 SunVIW} Rq,or1

Tc'i"I Page 4 of /0 AMO Environmental Decisions

Sr-89 and Sr-90 2023 RGPP Monitoring Report Dresden Generating Station Sr-89 and Sr-90 have been an annual procedurally required analysis on Detection, Long-Term Shutdown, and Elevated designated wells since sample point designations became part of the RGPP in 20 I 0. EN-DR-408-4160 (Revision 9) states that Sr-89 and 90 analyses should be performed annually for Source and Long-Term Shutdown designated sample locations. If a positive result is reported, samples collected from the wells with Sr-89 and Sr-90 detections will be analyzed quarterly to evaluate the activity in the area of the well. In 2022, samples were collected from the eighteen Source designated wells, nine Long-Term Shutdown designated wells, and one Mid-Field designated well (former Elevated designation) were analyzed for Sr-89 and Sr-90.

Sr-90 was detected in the sample collected from MW-DN-105S (3. 1 pCi/L) and DSP-108 (2.67 pCi/L). Sr-89 and Sr-90 were not detected in any of the other samples collected in 2023.

Precipitation Recapture Dresden Generating Station is a Boiling Water Reactor (BWR) generating station. The RGPP requires BWR generating stations to sample precipitation on a semi-annual basis. The RGPP states that a minimum of eight samples should be collected from within the protected area in a manner that surrounds the Turbine Building and Reactor Building as well as ancillary structures that could vent tritiated vapor to the atmosphere.

In 2043, three sample rounds were completed in March, September, and December to evaluate if tritium was present in the atmosphere at the Station. Eight onsite samples were collected during each sampling round. A summary of 2023 precipitation recapture results is presented in Table 3 and sample locations are depicted on Figure 3. A summary of historic precipitation recapture results is provided in Appendix A.

Tritium was detected in one or more samples during the three sampling rounds completed in 2023. The highest tritium concentrations were reported during the December 2023 precipitation recapture sampling round with detected tritium concentrations ranging between 524 pCi/L (FW-2) and 914 pCi/L (FW-3).

Summary of 2023 RGPP Sampling Rounds March 2023 RGPP Sampling Round Activities (P' Quarter 2023)

Data Summary A total of 29 groundwater samples were collected during the I" quarter 2023 sampling round. A sample was not collected from MW-DN-1171 due to the well being inaccessible during the I s i quarter 2023. Per the RGPP, the Background, Perimeter, and Mid-Field designated wells were not sampled during the 1 si quarter 2023 RGPP sampling round. All samples were analyzed for tritium.

Tritium was detected in five shallow aquifer samples with a maximum tritium concentration of 12,700 pCi/L (MD-I I). Tritium was detected in eight intermediate aquifer samples with a maximum tritium concentration of 3,100 pCi/L (MW-DN-1241).

The tritium concentration in MW-DN-111S averaged 412 pCi/L since the inception of the RGPP in 2006 through the 4° 1 quarter 2019. The tritium concentration in MW-DN-111 S increased from approximately 1,000 pCi/L to almost 3,500 pCi/L between the 4 11, quarter 2019 and I st quarter 2020. The tritium concentration in the area of this well has been fluctuating between 1,470 pCi/L and 5,530 pCi/L since the I st quarter 2020. The I" quarter 2023 RGPP tritium result for this well was 7,380 pCi/L. The Station reviewed documents and performed an assessment of potential tritium sources in the area ofMW-DN-111 Sand did not find any potential Dre,d,en 2023 Summarv Report* Tex\\

Page 5 of JO AMO Environmental Decisions

2023 RGPP Monitoring Report Dresden Generating Station sources. The increased tritium activity in this well could be due to historic plumes migrating around the building structures.

The tritium concentration in MW-DN-14 1 S increased from 2,910 pCi/L to 4,430 pCi/L between the 3rd and 4'h quarter 2022 RGPP sampling rounds and shows an increasing tritium concentration trend since the beginning of 2022. The 1st quarter 2023 tritium result is similar to those reported in late 2022, at 3,760 pCi/L. It was recommended that the Station evaluate SSCs in the area ofMW-DN-14 1 S for potential sources of the increased tritium activity and sample MW-DN-141 S on a monthly basis to further evaluate the tritium concentration in the area of the wel I.

Tritium concentrations in samples collected from wells (other than MD-I I) used to monitor the CST leak have decreased to less than 2,000 pCi/L, indicating the extent of the CST leak is confined to a small geographic area south of the Turbine Building.

Water Elevations All groundwater sample locations, with the exception of MW-DN-1 171, had depth to water measurements collected during the I st quarter 2023 sampling round. The J s' quarter 2023 groundwater elevation data was compared to the I st quarter 2022 sampling round to evaluate if changes in groundwater elevations occurred that may have an effect on groundwater flow direction. The variations in groundwater elevations have no significant effect on groundwater flow direction. Based on comparison of groundwater elevations, the wells sampled effectively monitored groundwater conditions at the Station.

June 2023 RGPP Sampling Round Activities (2'"1 Quarter 2023)

Data Summary A total of 57 groundwater samples were collected during the 2nd quarter 2023 sampling round. Samples were not collected from MW-DN-106S, MW-DN-1081, and MW-DN-1171 due to inaccessibility or well damage during the 2nd quarter 2023. All samples were analyzed for tritium and gamma-radionuclides. The samples collected from Long-Term Shutdown designated wells were also analyzed for gross-alpha, hard-to-detects (Fe-55 and Ni-63) and Sr-89 and Sr-90. Source designated wells were also analyzed for gross-alpha and Sr-89 and Sr-90. Samples collected from mid-field designated well MW-DN-1241; and source designated wells MD-I I and MW-DN-I 24S were also analyzed for select transuranics and hard-to-detects (Fe-55 and Ni-63).

Tritium was detected in seven shallow aquifer samples with a maximum tritium concentration of 8,140 pCi/L (MD-I I). Tritium was detected in eleven intermediate aquifer samples with a maximum tritium concentration of2,170 pCi/L (MW-DN-1141).

The tritium concentration in MW-DN-11 lS averaged 412 pCi/L since the inception of the RGPP in 2006 through the 4th quarter 2019. The tritium concentration in MW-DN-11 1 S increased from approximately 1,000 pCi/L to almost 3,500 pCi/L between the 4th quarter 20 19 and I st quarter 2020. The tritium concentration in the area of this wel I has been fluctuating between 1,470 pCi/L and 5,530 pCi/L since the Is' quarter 2020. The 2nd quarter 2023 RGPP tritium result for this well was 5,380 pCi/L. The increased tritium activity in this well could be due to historic plumes migrating around the building structures.

Tritium concentrations in samples collected from wells (other than MD-I I) used to monitor the CST leak have generally decreased to less than 1,000 pCi/L, indicating the extent of the CST leak is confined to a small geographic area south of the Turbine Building.

Dresden 2021 Swnmar) Report* Te'<!

Page 6 of 10 AMO Environmental Decisions

2023 RGPP Monitoring Report Dresden Generating Station The tritium concentration in MW-ON-141 S increased from 2,910 pCi/L to 4,430 pCi/L between the J rd and 4th quarter 2022 RGPP sampling rounds and shows an increasing tritium concentration trend since the beginning of 2022. The 2 nd quarter 2023 tritium result is similar to those reported in late 2022, at 4,770 pCi/L. Two subsequent samples were collected after the completion of the 2nd quarter 2023 RGPP sampling round. As of the end of August 2023, the tritium concentration in the sample collected from MW-ON-141 S was 5,850 pCi/L.

It was recommended that the Station evaluate SSCs in the area ofMW-ON-141S for potential sources of the increased tritium activity and sample MW-ON-14 1 S on a monthly basis to further evaluate the tritium concentration in the area of the well.

Select transuranics analysis was performed on MD-I I, MW-DN-1 24S, and MW-DN-1241, during the 2nd quarter 2023 RGPP sampling round. Select Transuranics were not detected at concentrations greater than their respective LLDs in the samples collected during the 2nd quarter 2023 RGPP sampling round.

Ni-63 has historically been detected in samples collected from MW-DN-1 191 and MW-DN-10 I I. N i-63 was not detected in any of the samples collected during the 2nd quarter 2023 RGPP sampling round.

Sr-90 continued to be detected in the samples collected from MW-DN-105S at 3.1 pCi/L and OSP-108 at 2.67 pCi/L. Low level Sr-90 has been detected sporadically in these wells with a maximum Sr-90 concentration of 4.93 (MON-I 05S, March 20 13). Sr-90 was not detected in the other samples collected during the 2nd quarter 2023 RGPP sampling round.

Gamma-radionuclides were not detected in the samples collected from the samples collected in 2023.

Additionally, gross-alpha detections did not exceed their respective Alert Levels in the samples collected during the 2nd quarter 2023 RGPP sampling round.

Water Elevations All groundwater sample locations had depth to water measurements collected during the 2nd quarter 2023 sampling round. The 2nd quarter 2023 sampling round groundwater elevation data was compared to the 2nd quarter 2022 sampling round to evaluate if changes in groundwater elevations occurred that may have an effect on groundwater flow direction. The variations in groundwater elevations have no significant effect on groundwater flow direction. Based on comparison of groundwater elevations, the wells sampled effectively monitored groundwater conditions at the facility.

September 2023 RGPP Sampling Round Activities (3"1 Quarter 2023)

Data Summary A total of29 groundwater samples were collected during the 3rd quarter 2023 sampling round. A sample was not collected from MW-ON-11 71 due to inaccessibility. All samples were analyzed for tritium. Tritium was detected in eight shallow aquifer samples with a maximum concentration of 7,240 pCi/L (MW-ON-1 11 S).

Tritium was detected in eight intermediate aquifer samples with a maximum concentration of 1,320 pCi/L (DSP-107).

The tritium concentration in MW-ON-11 1S averaged 4 12 pCi/L since the inception of the RGPP in 2006 through the 4th quarter 2019. The tritium concentration in MW-ON-111 S increased from approximately 1,000 pCi/L to almost 3,500 pCi/L between the 4*h quarter 2019 and I" quarter 2020. The tritium concentration in the area of this well has been fluctuating between 1,470 pCi/L and 5,530 pCi/L since the I st quarter 2020. The 3rd quarter 2023 RGPP tritium result for this well was 7,240 pCi/L. The increased tritium activity in this well is likely due to historic plumes migrating around the building structures.

Dre,<lcn 202; SurNJ'W) Report

Text Page 7 of 10 AMO Environmental Decisions

2023 RGPP Monitoring Report Dresden Generating Station The tritium concentration in MW-DN-141 S increased from 2,910 pCi/L to 4,430 pCi/L between the 3rd and 4th quarter 2022 RGPP sampling rounds and shows an increasing tritium concentration trend since the beginning of 2022. The tritium concentration in MW-DN-141S decreased from 4,770 pCi/L to 910 pCi/L between the 2nd and 3rd quarter 2023 RGPP sampling round. Station IR 04699599 was issued to document the groundwater condition in the area of MW-DN-1 4 1 S. It was recommended that the Station continue to evaluate SSCs in the area of MW-DN-141 S for potential sources of the increased tritium activity and sample MW-DN-14 IS on a monthly basis to ensure the tritium concentration continues to decrease.

Tritium concentrations in samples collected from wells (other than MD-I I) used to monitor the CST leak have generally decreased to less than 1,000 pCi/L, indicating the extent of the CST leak is confined to a small geographic area south of the Turbine Building.

Water Elevations All groundwater sample locations had depth to water measurements collected during the 3rd quarter 2023 sampling round. The 3rd quarter 2023 sampling round groundwater elevation data was compared to the 3rd quarter 2022 sampling round to evaluate if changes in groundwater elevations occurred that may have an effect on groundwater flow direction. The variations in groundwater elevations have no significant effect on groundwater flow direction. Based on comparison of groundwater elevations, the wells sampled effectively monitored groundwater conditions at the facil ity.

December 2023 RGPP Sampling Round Activities (4th Quarter 2023)

Data Summary A total of 34 groundwater samples were collected during the 4th quarter 2023 sampling round. A sample was not collected from MW-DN-11 71 due to the well being inaccessible at the time of the 4th quarter 2023 RGPP sampling. All samples were analyzed for tritium.

Tritium was detected in six shallow aquifer samples with a maximum concentration of 6,280 pCi/L (MW-DN-111 S). Tritium was detected in ten intermediate aquifer samples with a maximum concentration of 1,770 pCi/L (MW-DN-1141).

The tritium concentration in the area ofMW-DN-11 IS had been fluctuating between 1,470 pCi/L and 5,530 pCi/L since the I st quarter 2020. The 4th quarter 2023 tritium result for this well was 6,280 pCi/L. The increased tritium activity in this well is likely due to historic plumes migrating around the building structures.

However, it was recommended that Station personnel re-evaluate other potential sources between the CST and MW-DN-11 IS and sample MW-DN-111 S monthly to further evaluate the tritium concentration in the area of the well.

The tritium concentration in MW-DN-141 S increased from 2,91 O pCi/L to 4,430 pCi/L between the 3rd and 4th quarter 2022 RGPP sampling rounds and shows an increasing tritium concentration trend since the beginning of 2022. The tritium concentration in MW-DN-14 1 S decreased from 4,770 pCi/L to 910 pCi/L between the 2nd and 3rd quarter 2023 RG PP sampling round. The tritium concentration increased to 3, 140 pCi/L during the 4th quarter 2023 RGPP sampling round. Station IR 04699599 was issued to document the groundwater condition in the area of M W-DN-141 S. It was recommended that the Station continue to evaluate SSCs in the area of MW-DN-141 S for potential sources of the increased tritium activity and sample MW-DN-1 41 S on a monthly basis to further evaluate the tritium concentration in the area of the well.

Dri:s,,:kn 2023 Summa,y Report* Tc'<t Page 8 of IO AMO Environmental Decisions

2023 RGPP Monitoring Report Dresden Generating Station Tritium concentrations in samples collected from wells ( other than MD-I I) used to monitor the CST leak have generally decreased to less than 1,000 pCi/L, indicating the extent of the CST leak is confined to a small geographic area south of the Turbine Building.

Water Elevations All sampled groundwater locations had depth to water measurements collected during the 4th quarter 2023 sampling round. Groundwater elevations and groundwater flow direction for the shallow aquifer are provided on Figure 2a and groundwater elevations and groundwater flow direction for the intermediate aquifer are provided on Figure 2b. Based on the groundwater flow depicted on figures 2a and 2b, the wells sampled effectively monitored groundwater conditions at the facility.

2024 RGPP Sample Locations Samples could not be collected from MW-DN-106S, MW-DN-1081, and MW-DN-11 71 in 2023 due to inaccessibility and/or well damage. Not being able to sample these wells and assess data associated with the area of these wells is considered a data gap. Therefore, these wells should be repaired and made accessible to sampling crews to complete the RGPP.

Summary of2023 RGPP Conformance The Station did not conform with its RGPP in 2023 with respect to RGPP sampling protocol because water levels and samples were not collected from one Background designated well, one Perimeter designated well, and one Long Term Shutdown well. These wells have not been accessible for over two years.

Conclusions Based on the review of the data collected during the 2023 RGPP sampling rounds AMO concludes:

The Station continued to implement the tritium monitoring plan for the "B" CST. The tritium concentrations in the area of the CST showed a decreasing trend at the Station through 2023. While the tritium concentration in MD-I I decreased from its maximum reported tritium concentration of approximately 2.29 million pCi/L, an elevated concentration persists in the area of the CST. However, tritium concentrations in samples collected from wells (other than MD-1 1) used to monitor the CST leak have generally decreased to less than I,000 pCi/L, indicating the extent of the CST leak is confined to a small geographic area south of the Turbine Building.

The tritium concentration in MW-ON-I I IS averaged 4 12 pCi/L since the inception of the ROPP in 2006 through the 4th quarter 2019. The tritium concentration in MW-DN-1 1 l S increased from approximately 1,000 pCi/L to almost 3,500 pCi/L between the 4th quarter 2019 and pt quarter 2020.

The tritium concentration in the area of this well has been fluctuating between 1,470 pCi/L and 5,530 pCi/L since the I st quarter 2020. Tritium concentrations in samples collected from MW-ON-I I IS ranged between 4, I 20 pCi/L (May 2023) and 7,380 pCi/L (March 2023). The increased tritium activity in this well is likely due to historic plumes migrating around the building structures. However, it was recommended the Station re-evaluate other potential sources of tritium between the CST and MW-DN-1 I IS.

The tritium concentration in MW-DN-141S increased from 2,910 pCi/L to 4,430 pCi/L between the 3rd and 4th quarter 2023 RGPP sampling rounds and shows an increasing tritium concentration trend 0r(sdm 2021 Summar') Reporl

Texl Page 9 of IO AMO Environmental Decisions

2023 RGPP Monitoring Report Dresden Generating Station since the beginning of 2022. Tritium concentration in samples collected from MW-DN-141 S ranged between 818 pCi/L (September 2023) and 6,070 pCi/L (July 2023). The Station issued IR 04699599 to document the groundwater condition in the area of MW-DN-14 IS. It was recommended that the Station continue to evaluate SSCs in the area of MW-DN-141 S for potential sources of the increased tritium activity and sample MW-DN-14 1 S on a monthly basis to further evaluate the tritium concentration in the area of the wel I.

Gamma-radionuclides, gross-alpha, hard-to-detects (Fe-55 and Ni-63), and select transuranics were not detected at concentrations greater than their respective LLDs in the samples collected during the 2nd quarter 2023 RGPP sampling round.

Sr-90 continued to be detected in the samples collected from MW-DN-105S at 3. 1 pCi/L and DSP-108 at 2.67 pCi/L. However, Sr-90 concentrations remained in the historic range for these wells.

Based on recapture tritium results, groundwater could potentially be affected by precipitation recapture.

Based on the evaluation of groundwater flow direction, the wells sampled effectively monitored groundwater conditions at the facility.

Please call me at 215-230-8282 if you have questions.

Respectfully, AMO Environmental Decisions Ralph T. Golia, P.G.

Principal Hydrogeologist Druck-n 202J Sunun:uy Report* Text Page 10 of 10 attachments File AMO Environmental Decisions

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Gron Alpha - Dluolved Resutts 2012 2013 2014 2015 2010 Ma, May Jun Ma, Juo Jul May Jun Jun Nov May Juo Aug Oct Feb 0611 1.15 306 19 25 07-44 2.M. 1 61 I 117 0...,

I -

1.03 I -

2.96 1.74 2.n 1 OS 137 7 87 12.4 5,.

295 I -

1 99 I

171 V IS 2.81 2&3

= t -_

= 1 6~1

=~

- J -

9 1 6 84 12.6

- i -

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1.22 167 2

39 125 2 32 62 1 54 596

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1 -6 I -

129 3.03 4 08 263 1~9+

158 1--= 1-=

19 9 28 3

- I -

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--+..:... - - -

= t -

I 986

- t -

- ---+----

113 0 828-173 1 87 2

22 1- -

1 04

= +

=

0 499 0936 --t 3 81_

4 29

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3 74 2,.

4 01 1 97 652 1 ~ l-1~3 IT-8~i"'t

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0 531 3 87 r -

176 2 S6 I -

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=,

= -t4 ~6

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331 164 -

301 3 77 25~ =-+ -

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4 83 1 38 363 I -

" 5 12 7 I -

131 086 416 I

21 I -

238 I -

527 1 09 2 03 -

165 2.62 365 3 77 4 38 I -

2" 4 2 1 64 17 321 I -

- ~- = -t-!*!~

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Pag* 1 of 2 2017 2010 2019 May Nov Fob Jun Sep Nov May Dec 1 79 l T 1.31 139 1 53 1 -

1 07 11 2 73 I -

l 1 17 1 21 3 84 i -

4 71 32 17

! 186 195 1~,t

=

t s~,

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96

,-=--,...i. 122 1 21 0 978 0996 1 59 4 8 1

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= -t

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5 4 02

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593 515

= I-3~

391 295 l--316 J. 21 165

- -~~

3 79 1 68 3 82 ~ -

157 I t 208 1

1 24 0884 113 HM -

+

025!1

- l 1 "

28.11 *025 3 85 224 329 1~1; -

+3~3 298 719 3 74

4 15 e 35 I -

I 3 72 7 296 JO '

532 7

16 6 85 1.56 -

I 3 46 5 89 I o 476 0 393 1 06 1 288 221 206 1 5 2.71 365

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431 3 66 306 2 48 76-T - -

7 327 2 43

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- _L......=....... -

-~-

2021 May 15 1 35 HO 391

,.20 T able 1 Summary of Gross-Alpha Results 2023 Jun 216 2 14 3 74 4 27 11,4 358 I-562 6 41 11 4 0 978 1 24 3 14 36 1 55 1--

1 78 7 S5 9 21 6 2 57 0 895 006 5 07 6 57 9 23 0 816 113 112 2 32 342 2 84 19~

2 79 1 41 3.97 253 03 144 2 92 399 1 09 4 26 28 25 2.18 806 1.1 259 0 757 1 89 4 57-6 33 148 5 48 AMO Environmental Decisions

Dresden Generating Station Constellation Energy Company WeU AverA98 SITE WeUIO 1-0uthfI OSP-105 OM!

OSP-106 009 OSP-107 060 OSP-108 068

- OSP-122 2 08 I

DSP-123 0 66 OSP-12 080 OSP-125 168 MD-11 066 MW-ON-101-1 018 MW-ON-101-S 1.88 MW-ON-102-I 1.02 MW..OtM 02-S

~

2 82 MW-ON-104-S 3.5 I

MW-ON-105-S 6 84 I

MW-ON-106-S

OIV.101 MW-ON-107-S 3'0 MW-ON*108-I 2 12 MW-ON.10g..I 1 07 MW-ON-109-S 162 i

MW-ON-111-S 057 MW.ON-113--I 2 70 -

MW-ON-113-S 410 Dresden f MW-ON-114-S 077 MW-0N-11S-$

0 85 MW-0_!'*1~I 0 70 MW,ON-116-5 071 MW-ON-117-I 0 82 MW-ON-118-S 0 72 MW-ON-119--1 001 MW-ON-119-S 2.35 MW-ON-122-I

OtV/01 MW-ON-12-I 1 21 MW-ON-12-S 1 83 MW-ON-125-S 1 "

MW-ON-126-S l a, I

l MW-ON-127-S -

0 92 I

MW-ON-134-S 072 I

MW-ON-135-S 0 75 r MW-DN-136-S 1 64 I

t MW-ON-137-S 1 41 I

MW-ON-140.S 1 20 MW-ON-141-S 0 8 MW-ON-142-S 116 I

MW-ON-143-S 1 26 r MW-ON-1-44-S 189 I

RW-ON-100--S 13 84 RW-ON-101-S 1 05 Explanation ALERT LEVEL ALERT (STOEY.

LEVEL (Hist Outliers)

Avgl 1 6900 259 14498 207 l 4761 1 79 1 799 204 71817 625 14235 199 12818 2 0 3 5783 503 1.19i5 l.98 1 7349 23-4 51353 563 3 3470 305 76761 845 11 7380 10 35 206710 20 52

Ol'V.()l

,OIV/0I 13 0167 1020 11 278 637 2 7943 322 4 8092 4 87 07791 170 11 8613 809 19 823-1410 1 4579 231 1 7410 2 55 15728 2 11 14963 231 1627 2 6 1 2529 2 15 1 8339 2 74 a 0503 1 06 t OIVIO*

I IOIV/Ot 3 408 363 5 9504 5 50 2 7851 3.43 3 5834

- -5 2 17664 +-

2 77 1 3220 215 1 4555 2 25 5 5701 4 02 38084 424 21319 359 1 S-4*36 252 26527 349 26054 378 4 7607 586 44 2173 t-41 52 17026 314 2011 2012 Feb Ma, Jun Doc M"

Mav 0 82 I = -

0.009 035 0,..

0 ;45+ =- - t ::- -

0 3"8

~=~:-r =

0 3"7 1 20 066 0.639 -

0 78 112 2

3 s8 062

~

117 25 6 96 O G_j_ -,_-

=- - ~781 0502

- 1 =

0396

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2 83 H1stonc data oother removed from the caleutatlon of the average concenttatton that wes used to calculate the Alen level Gross Alpha

Suspended RHutta I

2013 2014 2015 2018 Jun Ma, Jun Jul Mav Jun Jun Nov Mav Jun Aua, Oct Feb 0 793 -

083 0023 -

0599 I

0 793 = + =

063 0 023

~

0.599 i -

0361 OJSJ 0 918 4.74

~

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0 605 = -r =

f-=

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0 023 0608

- f -

169 0 892 288

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0.711 0 3-47

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~

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0.63 0 359 -

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= +::

0808 1 24 115 8 33 0604 1 24 I O 51 0.357 0 503 1 2 0508 205 o1:,9 +-=

1 3 - = +--=

121 0361

- ~o;j-'* -

= +

()45 2 47 32..-

=-+ -

- t -

- --=- t -=- -

-=- t--=-

~ 50J _-

j__t 24 t o 503 -

0374

- t -

0502 124 0506 0 746 0 491 1.79

0 511 0938 103 1-2.83 0 515 0 912 0557 1 1 2 0 509 238 0 491 0665 I -

121 I 128 173 0358 049 1 21 1 28 2 1

~

362....._-

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798 -= + = ~~~ +-~: -

0 739 --+ =-

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1 5 119

=

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0 1

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5

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0513 1----=--l--' 08 0538 -= t =

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- j -

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0 973 0.513 1 24 = t°-~

0 894 i -

262

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3.35 Alen Level E.xcHdanc. 'Nher* select transUfana we,e analyzed and foond 10 be less than theiJ respecwe LLDs. The result 1s now UHd., generating lhe Alen Level 3.51 Alen Level E.>cceedance However, the resull Is ND and less than LLD Res~s rt pCI/L Page 2 of 2 2017 2018 2010 Mav Nov Feb Jun...

Nov Mav Dec 0617 l 113 0 617

- t-113

- ~

0618 1.13

~

0896 -

0 619 1 14 0897 -

~ -

0617

- I 116 0719 --

221,

165

~ 3.72_ -

--0 822 06241 -

0 84 0 898 0.628 11W.-.--= = ++;; -

= G,: --

2 33 C

t 173 0752 38 137 516

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i---

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- j 1-6 1 84 1 40 18

-+-1 6 1 8

t- -

789 7 27 862 194

i =- = t-

0623 -

-..! 0 627 -

= +~;:,

1 02 0 871 0807 0 491 0 831 115 0 809 -

0 8<12 0892 2.71 ~ 0.85 0501 -

0981 1 54 1.03 3 73 28 5 52 I -

I 2 78 I -

15 1 5 2 87 346 0.. 2 2.87 J -

---j--'151 144 2.77 I -

1 5 - --

257 -

~:~+ = -~~=: -

- td~

083 0932 0884 176 1 36 I 1 3 2~1+ =

142

-+

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11 -

1 03 0 884 147 1.,

1 81 143 0.. 2 1 85 14 102

= T -- --- *

- i -

2021 May -

0 367 0367 t.83

~ 2 4-0369 0912 1 84 0366 0 717 214 -

359 3 58 072 l~

3 56 0517 0931 106 -

3 35 089 4 07 4.33 44

~

433 -

0 869 0 909 666 0 80 Table 1 Summary of Gross-Alpha Results 2023 Jun 0 3'6 03'6 0 32 3 6 1.14 0872 1.75

~

o*

03-47 1.77 614 10 1 1 52 304 0617 f--

0 600 08-0608 0605 122 0616 0613 0.81$1 2 31 -

301 -

123 0608 21 12 AMO Environmental Decisi ons

Dresden Ge nerat ing Station Constellation Energy Company Station Well ID 2011 Dresden i~::::~

OSP-123 OSP-124 OSP-125 M0.11 MW-ON-101~

MW-ON-102.J MW-ON-102-S MW-ON-104..S Fob 0 09023 01733 0 1647 003502 08508 Mar Jun

---+

-t-

~ 0 1329

--+-005616 05784

-+ _0111~

MW-ON-106.S t

t 091 MW-ON-107--5 t

~-ON-tOfH ~

3799

't-MW-ON-111 S +

--i MW-ON-113.a 1-

_J O 09059 MW-ON-113-5 i

0544 MW-ON-116-S 2012 2013 2014 Dec Mar Jun Mar Jun Jun t

1--- +/-:- 1 -- -

0 371 09135 I

-j t-

- t--

r=-

T 2015 2011 Jun Nov May Oct Feb

-l- -+

t

--* ~

0 101*fo 033't

-+

~

1496-,.-

U..23312:W RHuN:,

2017 Nov J..

-+-

.1:tj----

03694 Feb

-r 2011 Jun r

--~

Oct r- +=-

0 1154t oosan o *ssrr 2019 I

2020 Nov Ma,

~

01121 02605*-

0527

--+--

L

__ J r-:+-J

+ t +- l Table 2 Summary of U-233/234 and U238 Results 2021 2022 2023 Nov Ma*

Jun Jun r

-r 0 1474t O 1156 r

+...

0 07296

~~:::~~ j oosm MW-ON-124-S 7" RW-ON-100S 1=::;~;s 032¢-

T

+ + 04082

~1 06408\\- 009179 1 01~

T

-t 01131

~ -~

0 1428+

0 0229

--t- 01oss+-

t o02586:

j.._

j o064ln 0 1186f 01395 0 1191 0 1802 0_1454 0 05042 00489~

0 092303

-+

0 1451 0 0765\\

l--

SW-ON-102 SW-ON-103 SW-ON-104 SW-ON-105 SW-ON--106 0441 06737 07946 0553 0489

+ T t T---t, I

-+

~

-r r

+-

.j.._

I I

I I u

'-----------1--_,. __.._ __._ _ _..__'--'--=---..... -~

1 Dresden Notes Well to 2011 Fob Mar Jun OSP-107 O 07626 OSP-122 0 1605,+-----+--

I IOSP-123

_ ~

o 073 OSP-124

~

06065 lOSP-125 IMD-11 MW-ON-101~

-.I----

MW--ON-102-1 MW.()N..102-S MW-ON-104-S 043S3 M'N-ON-106-S

~

MW-ON-107-S MW-ON-108-1

--'---02105

~111$

MW-ON--11~

MW--ON-113-S MW-ON-116...S MW-ON-119"'

IMW-ON-122-l IMW-ON-124-l

)=~~4:

!RW-ON:;o,s _

SW.ON-101 SW-ON-102

~

~ -

1--

.l- 01465 SW-ON-103 SW-ON-104 SW-ON-105 SW-ON-106

+- --

1--

~

_..... ~1.!111 0079-12 0.1066 0 1116

..(._

0845 006406 02991 0 3512~

-t- -

-=f= oss,e 05302

-t 0 4086 04812 03978 05952 U-238 RHuha 2013 2014 201$

2011 2017 Oec Mar Jun Mar Jun Jun Jun Nov May Oct Feb Mav Nov Jan I +-

t I

~

t t--

f o 1osat-O ~~

a 0579~

o 12s24-r f

o 188 I

I I

I 04333 06638 0 4422 01124 0 O76r s~

0 08078r o09_B O 1891! 005121 02437

_;=__

o0406*f o3619 0153~

_0_20

_ 20-+l--..--0-1399 -

r i

r l-I

- i-- -r--r- --t-

+

I I

t_ t i __ t 1

If a sample was re-anafyl:ed on a part:lcutar date, onty the highest concentrabOn IS noted Results in pCill Page 1 of 1 2011 Fob Jun Ocl t

0123~

00830'1--

t 0 1215P--

I

~-d-= -t 1

.... -...L--'----

f-......

2019 2020 2021 No*

Mav Aua 0.-c Mar Jul t_ t

~

1 t

01066 01775 02164 o 06118j t o 112*._

t o mf-t-1 o 03103 0 1499 _ 0 1993t O 12 0 1755"

+

i

+

-4 +

-m,_

__ L_ -~

~ -

-L- * --- ~-

t 006602 2022 Jun 0043:t 007612 I

-,~

009746 004265 00217 008136 008333 0 1556 01403 01348 01141 0 07296 0 1295 L

t 0122 006283 I

I

-+---

l - - --1-- _:..i::...:..:..=

-L-1 -

.l_

I 1

I I

j.._

I-I AMO Environme ntal Decision 2023 Jun 005733 01451 0 180\\

Dresden Generating Station Constellation Energy Company Sample Location FW-4 FW-12 FW-1 FW-2 FW-3 FW-10 FW-5 FW-11 FW-5 FW-4 FW-11 FW-10 FW-12 FW-2 FW-3 FW-1 FW-5 FW-4 FW-1 FW-2 FW-3 FW-10 FW-11 FW-12 Explanation:

Sample Date 3/15/2023 3/15/2023 3/15/2023 3/15/2023 3/15/2023 3/15/2023 3/15/2023 3/16/2023 9/18/2023 9/20/2023 9/21/2023 9/21/2023 9/21/2023 9/22/2023 9/22/2023 9/22/2023 12/5/2023 12/6/2023 12/6/2023.

12/7/2023 12/7/2023 1217/2023 12/7/2023 12/7/2023 Table,3 Summary of 2023 Precipitation Results Directional Sector Result Qual SW 212

+

SSE 281

+

NW 332

+

NNE 218

+

NNW 422

+

E 196 u

NE 198 u

ESE 193 u

NE 197 u

SW 264

+

ESE 195 u

E 198 u

SSE 197 u

NNE 189 u

NNW 188 u

NW 369

+

NE 190 u

SW 191 u

NW 619

+

NNE 524

+

NNW 914

+

E 184.

u ESE 189 u

SSE 191 u

U - Tritium not detected at a concentration greater than the laboratory detection limit.

+ - Tritium detected at a Concentration greater than the laboratory detection limit.

- All results presented in pCi/L.

2023 Summary of Pr~cipitation Tritium Results/ 2023 Summary Page 1 of 1 AMO Environmental Decisions

0 I

MW-DN!,34-S MW-DN-143-S e vrMW-DN-135:S I

MW-DN-136-S MW-DN-144-S MW-DN.'137-S I MW-DN-142-S 500 1,000 0

D Feet Explanation:

Shallow Aquifer RGPP Monitoring Location

Background

Long-Term Shutdown e

Mid-Field Perimeter Source

c MW-DN-112 MW-DN-103-S I

400 MW-DN-10 800 Feet j (

Figure 1a RGPP Sample Locations Shall_ow Aquifer Constellation Energy Corporation Dresden Generating Station

I 0

500 1,000 Feet Explanation:

Intermediate Aquifer RGPP Monitoring Location

Background

Mid-Field Perimeter Source MW-ON-103-I I

400 OSP-149R 800

\\

Feet Figure 1b RGPP Sample Locations Intermediate Aquifer Constellation Energy Corporat!on Dresden Generating Station

Gil 0

c:,

=

a 0

Explanation:

¢

.... 0 c=

0 MW*OIMOJ*S

510.59 I, s "'

4th Qtr: 2023 RGPP Shallow Aquifer Monitoring Location December 2023 Shallow Aquifer Groundwater Monitoring Location Groundwater Elevation Contour

- -

Inferred Groundwater Elevation Contour

-. Estimated Groundwater Row Direction 508.45 - Groundwater elevation with respect to mean sea level pP 0

N *+*

s 1,000 Feet Figure 2a 4th Quarter 2023 (December) RGPP Groundwater Elevations and Water Elevation Contours Surface Water and Shallow Aquifer Constellation Energy Corporation Dresden Generating Station

[ii)

D

¢

= 0

=

0 -

~

0 t::I Gt I

I G1 I

G1 G11 Explanation:

4th Qtr. 2023 RGPP Intermediate Aquifer Monitoring Location December 2023 Intermediate Aquifer Groundwater Elevation Contour Groundwater Elevation Contour

- -

Inferred Groundwater Elevation Contour

_,. Estimated Groundwater Flow Direction 508.45 - Groundwater elevation with respect to mean sea level

/

.po

.,,d.,,.,,* p

~

\\

0 N *4

s 1,000 Feet Figure 2b 4th Quarter 2023 (December) RGPP Groundwater Elevations and Water Elevation Contours Intermediate Aquifer Constellation Energy Corporation Dresden Generating Station

Ci.ii u

=

¢

=

0 c=

=

u - a 0

C:)

G1 G1 Gt Gt Explanation:

2023 Precipitation Recapture Sample Location Result > 200 pCi/L Result <200 pCi/L

- Precipitation sampling completed in March, September, and December in 2023.

pP

)~

0 N *4

s 1,000 Feet Figure 3 2023 Precipitation Recapture Sample Locations Constellation Energy Corporation Dresden Generating Station

Dresden Generating Station Constellation Energy Company Sample ID RB-1 RB-10 RB-11 RB-12 RB-2 RB-3 RB-4 RB-5 RB-6 RB-7 RB-8 RB-9 RB-1 RB-10 RB-11 RB-12 RB-2 RB-3 RB-4 RB-5 RB-6 RB-7 RB-8 RB-9 RB-1 RB-10 RB-11 RB-12 RB-2 RB-3 RB-4 RB-5 RB-6 RB-7 RB-8 RB-9 RB-1 RB-10 RB-11 RB-12 FW-1 FW-10 FW-11 FW-12 FW-1 FW-10 FW-11 FW-12 FW-1 FW-10 FW-11 FW-12 FW-1 FW-10 FW-11 FW-12 FW-1 FW-10 FW-11 FW-12 FW-1 Date 7/28/2011 7/28/2011 7/28/2011 7/28/2011 7/28/2011 7/28/2011 7/28/2011 7/28/2011 7/28/2011 7/28/2011 7/28/2011 7/28/2011 10/21/2011 10/21/2011 10/21/2011 10/21/2011

10/21/2011 10/21/2011 10/21/2011 10/21/2011 10/21/2011 10/21/2011 10/21/2011 10/21/2011 1/11/2012 1/11/2012 1/11/2012 1/11/2012 1/11/2012 1/11/2012 1/11/2012 1/11/2012 1/11/2012 1/11/2012 1/11/2012 1/11/2012 5/23/2012 5/23/2012 5/30/2012 5/30/2012 6/6/2013 6/7/2013 6/13/2013 6/14/2013 5/29/2014 5/30/2014 5/30/2014 5/30/2014 6/1/2015 6/2/2015 6/3/2015 6/8/2015 06/07/2016 06/01/2016 06/01/2016 06/01/2016 05/15/2017 05/23/2017 05/17/2017 05/24/2017 06/12/2018 2023 Summary of Precipitation Tritium Results/ 2011-2023 Tritium Data Appendix A Summary of 2011 - 2023 Precipitation Sample Tritium Results Directional Sector Result Qual Units NW 400

+

pCi/L E

630

+

pCi/L ESE 300

+

pCi/L SSE 100 u

pCi/L NNE 630.

+

pCi/L NNW 200 u

pCi/L SW 100 u

pCi/L NE 100 u

pCi/L ENE 200 u

pCi/L SE 200 u

pCi/L s

100 u

pCi/L SSW 100 u

pCi/L NW 300

+

pCi/L E

0 u

pCi/L ESE 200

+

pCi/L SSE 100 u

pCi/L NNE 300

+

pCi/L NNW 300

+

pCi/L SW 400

+

pCi/L NE 300

+

pCi/L ENE 200 u

pCi/L SE 200 u

pCi/L s

100 u

pCi/L SSW 0

u pCi/L NW 400

+

pCi/L E

300

+

pCi/L ESE 100 u

pCi/L SSE 300

+

pCi/L NNE 600

+

pCi/L NNW 600

+

pCi/L SW 500

+

pCi/L NE 400

+

pCi/L ENE 300

+

pCi/L SE 400

+

pCi/L s

300

+

pCi/L SSW 100

u pCi/L NW 191 u

pCi/L E

199 u

pCi/L ESE 168 u

pCi/L SSE 167 u

pCi/L NW 161 u

pCi/L E

160 u

pCi/L ESE 169 u

pCi/1:.

SSE 168 u

pCi/L NW 194 u

pCi/L E

191 u

pCi/L ESE 194 u

pCi/L SSE 196 u

pCi/L NW 190 u

pCi/L E

188 u

pCi/L ESE 182 u

pCi/L SSE 175 u

pCi/L NW 181 u

pCi/L E

183 u

pCi/L ESE 181 u

pCi/L SSE 182 u

pCi/L NW 177 u

pCi/L E

177 U, pCi/L ESE 175 u

pCi/L SSE 178 u

pCi/L NW 193 u

pCi/L Page 1 of 3 AMO Environmental Decisions

Dresden Generating Station Constellation Energy Company Sample ID FW-10 FW-11 FW-12 FW-1 FW-10 FW-11 FW-12 FW-1 FW-10 FW-11 FW-12 FW-11 FW-10 FW-1 FW-4 FW-12 FW-2 FW-3 FW-5 FW-11 FW-5 FW-10 FW-2 FW-3 FW-1 FW-4 FW-12 FW-4 FW-5 FW-12 FW-11 FW-10 FW-2 FW-3 FW-1 FW-1 FW-10 FW-11 FW-12 FW-2 FW-3 FW-4 FW-5 FW-1 FW-10 FW-11 FW-12 FW-2 FW-3 FW-4 FW-5 FW-1 FW-10 FW-11 FW-12 FW-2 FW-3 FW-4 FW-5 FW-1 FW-10 Date 06/12/2018 06/12/2018 06/02/2018 5/28/2019 5/28/2019 5/28/2019 5/28/2019 11/12/2020 11/12/2020 11/12/2020 11/12/2020 3/8/2021 3/8/2021 3/9/2021 3/11/2021 3/11/2021 3/11/2021 3/11/2021 3/11/2021 8/10/2021 8/10/2021 8/11/2021 8/11/2021 8/11/2021 8/12/2021 8/12/2021 8/12/2021 11/8/2021 11/8/2021 11/9/2021 11/9/2021 11/9/2021 11/9/2021 11/9/2021 11/10/2021 3/15/2022 3/15/2022 3/15/2022 3/15/2022 3/15/2022 3/15/2022 3/15/2022 3/16/2022 6/7/2022 6/7/2022 6/7/2022 6/7/2022 6/7/2022 6/7/2022 6/7/2022 6/6/2022 7/27/2022 7/27/2022 7/26/2022 7/28/2022 7/27/2022 7/27/2022 7/27/2022 7/25/2022 11/16/2022 11/16/2022 2023 Summary of Precipitation Tritium Results/ 2011-2023 Tritium Data Appendix A Summary of 2011 - 2023 Precipitation Sample Tritium Results Directional Sector Result Qual Units E

193 u

pCi/L ESE 196 u

pCi/L SSE 196 u

pCi/L NW 188 u

pCi/L E

181 u

pCi/L ESE 186 u

pCi/L SSE 187 u

pCi/L NW 207

+

pCi/L E

170 u

pCi/L ESE 175 u

pCi/L SSE 276 u

pCi/L ESE 182 u

pCi/L E

187 u

pCi/L NW 404

+

pCi/L SW 180 u

pCi/L SSE 186 u

pCi/L NNE 184 u

pCi/L NNW 182 u

pCi/L NE 182 u

pCi/L ESE 169 u

pCi/L NE 169 u

pCi/L E

161 u

pCi/L NNE 176 u

pCi/L NNW 421

+

pCi/L NW 177 u

pCi/L SW 176 u

pCi/L SSE 173 u

pCi/L SW 193 u

pCi/L NE 177 u

pCi/L SSE 187 u

pCi/L ESE 181 u

pCi/L E

186 u

pCi/L NNE 192

+

pCi/L NNW 239

+

pCi/L NW 21.5

+

pCi/L NW 229

+

pCi/L E

195 u

pCi/L ESE 193 u

pCi/L SSE 175 u

pCi/L NNE 360

+

pCi/L NNW 589

+

pCi/L SW 171 u

pCi/L NE 172 u

pCi/L NW 735

+

pCi/L E

204

+

pCi/L ESE 173 u

pCi/L SSE 182

+

pCi/L NNE 377

+

pCi/L NNW 394

+

pCi/L SW 470

+

pCi/L NE 229

+

pCi/L NW 418

+

pCi/L E

196 u

pCi/L ESE 194 u

pCi/L SSE 195 u

pCi/L NNE 234

+

pCi/L NNW 266

+

pCi/L SW 195 u

pCi/L NE 196 u

pCi/L NW 1,860

+

pCi/L E

176 u

pCi/L Page 2 of 3 AMO Environmental Decisions

Dresden Generating Station Constellation Energy Cor:npany Sample ID FW-11 FW-12 FW-2 FW-3 FW-4 FW-5 FW-4 FW-12 FW-1 FW-2 FW-3 FW0 1D FW-5 FW-11 FW-5

FW-4 FW-11 FW-10 FW-12 FW-2 FW-3 FW-1 FW-5 FW-4 FW-1 FW-2 FW-3 FW-10 FW-11 FW-12 Date 11/16/2022 11/16/2022 11/16/2022 11/16/2022 11/16/2022 11/16/2022 3/15/2023 3/15/2023 3/15/2023

3/15/2023 3/15/2023 3/15/2023 3/15/2023 3/16/2023 9/18/2023 9/20/2023 9/21/2023 9/21/2023 9/21/2023 9/22/2023 9/22/2023 9/22/2023 12/5/2023 12/6/2023 12/6/2023 12/7/2023 12/7/2023 12/7/2023 12/7/2023 12/7/2023 2023 Summary of Precipitation Tritium Results/ 2011

2023'Tritium Data Appendix A Summary of 2011 - 2023 Precipitation Sample Tritium Results Directional Sector Result Qual Units ESE 242

+

pCi/L SSE 230

+

pCi/L NNE 902

+

pCi/L NNW 1,330

+

pCi/L SW 353

+

pCi/L NE 191 u

pCi/L SW 212

+

pCi/L SSE 281

+

pCi/L NW 332

+

pCi/L NNE 218

+

pCi/L NNW 422

+

pCi/L E

196 u

pCi/L NE 198 u

pCi/L ESE 193 u

pCi/L NE 197 u

pCi/L SW 264

+

pCi/L ESE 195 u

pCi/L E

198 u

pCi/L SSE 197 u

pCi/L NNE 189 u

pCi/L NNW 188 u

pCi/L NW 369

+

pCi/L NE 190 u

pCi/L SW 191 u

pCi/L NW 619

+

pCi/L NNE 524

+

pCi/L NNW 914

+

pCi/L E

184 u

pCi/L ESE 189 u

pCi/L SSE 191 u

pCi/L Page 3 of3 AMO Environmental Decisions

ML24127A098

Contents

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3.0 INTRODUCTION

SUMMARY

3.0 INTRODUCTION

SUMMARY

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Background

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ML24127A098

Text

Subject:

Attachment:

SUMMARY

3.0 INTRODUCTION

SUMMARY

3.0 INTRODUCTION

SUMMARY

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Background

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t

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Background

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