W3F1-2025-0014, Waterford Steam Electric Station, Unit 3, Annual Radioactive Effluent Release Report (ARERR) 2024
| ML25120A394 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/30/2025 |
| From: | Twarog J Entergy Operations |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| W3F1-2025-0014 | |
| Download: ML25120A394 (1) | |
Text
John Twarog Manager Regulatory Assurance 504-739-6747 Entergy Operations, Inc., 17265 River Road, Killona, LA 70057 W3F1-2025-0014 10 CFR 50.36a April 30, 2025 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Annual Radioactive Effluent Release Report (ARERR) 2024 Waterford Steam Electric Station, Unit 3 Docket No. 50-382 Renewed Facility Operating License No. NPF-38 Attached is the Annual Radioactive Effluent Release Report for the period of January 1 through December 31, 2024. This report is submitted pursuant to the requirements of Waterford 3 Technical Specification Sections 6.9.1.8 and 6.14.2.c.
There are no commitments contained in this submittal.
If you have any questions, please contact John Twarog, Manager, Regulatory Assurance, at 504-739-6747.
Respectfully, John Twarog JT/llb cc:
NRC Region IV Regional Administrator Entergy Legal, General Sr Counsel Digitally signed by John R. Twarog DN: cn=John R. Twarog, o=Entergy, ou=Waterford 3 Regulatory Assurance, email=jtwarog@entergy.com Date: 2025.04.30 12:06:47 -05'00' John R.
Twarog
Enclosure to W3F1-2025-0014 Annual Radioactive Effluent Release Report CY 2024 (50 pages follow)
2024 Annual Radioactive Effluent Release Report Waterford 3 Document Number: 50-382 Author: ________________________________________
Date: _4/23/2025_
Michelle Moore Effluent Specialist Reviewer: ________________________________________
Date: _4/23/2025__
Terry Parrill Chemistry Supervisor Approved: ________________________________________
Date: ______________
Melody Gibson Chemistry/Radiation Protection Manager 4/24/25 4/25/25 Digitally signed by Michelle Moore DN: cn=Michelle Moore, o=Entergy, email=mbeaver@entergy.com Date: 2025.04.23 12:49:03 -05'00' Michelle Moore Digitally signed by Terry E. Parrill DN: cn=Terry E. Parrill, o=Entergy/Waterford 3 S.E.S., ou=WF3 Chemistry, email=tparril@entergy.com Date: 2025.04.24 08:50:20 -05'00' Terry E. Parrill Digitally signed by Melody Gibson DN: cn=Melody Gibson,
o=Entergy, ou=Fleet Radiation Protection, email=mgibson@entergy.com Date: 2025.04.25 18:05:58 -05'00' Melody Gibson
Waterford 3 2024 Document Number: 50-382 Annual Radioactive Effluent Release Report
Annual Radioactive Effluent Release Report YEAR: 2024 Page 1 of 49 Company: Entergy Plant: Waterford 3 TABLE OF CONTENTS LIST OF ACRONYMS AND DEFINITIONS................................................................................ 3 EXECUTIVE
SUMMARY
............................................................................................................ 5 2.1 Comparison to Regulatory Limits.................................................................................... 6 INTRODUCTION........................................................................................................................ 8 3.1 About Nuclear Power...................................................................................................... 8 3.2 About Radiation Dose................................................................................................... 10 3.3 About Dose Calculation................................................................................................ 12 DOSE ASSESSMENT FOR PLANT OPERATIONS................................................................. 14 4.1 Regulatory Limits.......................................................................................................... 14 4.2 Regulatory Limits for Gaseous Effluent Doses:............................................................. 14 4.3 Regulatory Limits for Liquid Effluent Doses................................................................... 15 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public.................................. 16 4.5 Onsite Doses (Within Site Boundary)............................................................................ 16 SUPPLEMENTAL INFORMATION........................................................................................... 17 5.1 Gaseous Batch Releases............................................................................................. 17 5.2 Liquid Batch Releases.................................................................................................. 17 5.3 Abnormal Releases...................................................................................................... 17 5.4 Land Use Census Changes.......................................................................................... 18 5.5 Meteorological Data...................................................................................................... 18 5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days................................ 18 5.7 Offsite Dose Calculation Manual (ODCM) Changes...................................................... 19 5.8 Process Control Program (PCP) Changes.................................................................... 20 5.9 Radioactive Waste Treatment System Changes........................................................... 20 5.10 Other Supplemental Information................................................................................... 20 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM............... 25 6.1 Voluntary Notification.................................................................................................... 29 BIBLIOGRAPHY...................................................................................................................... 30 TABLES Table 1, Waterford 3 Dose Summary..................................................................................................... 6 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for WF3.................................... 7 Table 3, Onsite Doses (Within Site Boundary)..................................................................................... 16 Table 4, Groundwater Protection Program Monitoring Well Sample Schedule..................................... 25 Table 5, Groundwater Protection Program Monitoring Well Results..................................................... 26 Table 6, Groundwater Protection Program Monitoring Well Results..................................................... 28 Table 7, Groundwater Protection Program Monitoring Well Results..................................................... 29 Table 8, Gaseous Effluents Summation of All Releases WF3.............................................................. 31 Table 9, Gaseous Effluents Ground Level Release Batch Mode WF3............................................ 32 Table 10, Gaseous Effluents Ground Level Release Continuous Mode WF3.................................. 33 Table 11, Liquid Effluents Summation of All Releases WF3............................................................. 34
Annual Radioactive Effluent Release Report YEAR: 2024 Page 2 of 49 Company: Entergy Plant: Waterford 3 Table 12, Batch Mode Liquid Effluents WF3........................................................................................ 35 Table 13, Continuous Mode Liquid Effluents WF3............................................................................... 36 Table 14, Types of Solid Waste Summary WF3................................................................................... 37 Table 15, Major Nuclides WF3............................................................................................................. 38 Table 16, Solid Waste Disposition WF3............................................................................................... 39 Table 17, Irradiated Fuel Shipments Disposition WF3......................................................................... 39 Table 18, Classification of Atmospheric Stability.................................................................................. 49 FIGURES Figure 1, Pressurized Water Reactor (PWR) [1]..................................................................................... 8 Figure 2, Boiling Water Reactor (BWR) [2]............................................................................................. 9 Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3].................................................. 10 Figure 4, Potential exposure pathways to Members of the Public due to Plant Operations [6]............. 12 ATTACHMENTS, ARERR Release Summary Tables (RG-1.21 Tables)................................................... 31, Solid Waste Information................................................................................................ 37, Meteorological Data...................................................................................................... 40
Annual Radioactive Effluent Release Report YEAR: 2024 Page 3 of 49 Company: Entergy Plant: Waterford 3 LIST OF ACRONYMS AND DEFINITIONS 1.
having a mass and charge equal in magnitude of a helium nucleus.
2.
BWR: Boiling Water Reactor 3.
Composite Sample: A series of single collected portions (aliquots) analyzed as one sample. The aliquots making up the sample are collected at time intervals that are very short compared to the composite period.
4.
Control: A sampling station in a location not likely to be affected by plant effluents due to its distance and/or direction from the Plant.
5.
Counting Error: An estimate of the two-sigma uncertainty associated with the sample results based on total counts accumulated.
6.
Curie (Ci): A measure of radioactivity; equal to 3.7 x 1010 disintegrations per second, or 2.22 x 1012 disintegrations per minute.
7.
Direct Radiation Monitoring: The measurement of radiation dose at various distances from the plant is assessed using thermoluminescent dosimeters (TLDs), optically stimulated luminescent dosimeters (OSLDs), and/or pressurized ionization chambers.
8.
Grab Sample: A single discrete sample drawn at one point in time.
9.
Indicator: A sampling location that is potentially affected by plant effluents due to its proximity and/or direction from the plant.
10.
Ingestion Pathway: The ingestion pathway includes milk, fish, drinking water and garden produce. Also sampled (under special circumstances) are other media such as vegetation or animal products when additional information about particular radionuclides is needed.
11.
ISFSI: Independent Spent Fuel Storage Installation 12.
LLD: Lower Limit of Detection. An a priori measure of the detection capability of a radiochemistry measurement based on instrument setup, calibration, background, decay time, and sample volume. An LLD is expressed as an activity concentration. The MDA is used for reporting results. LLD are specified by a regulator, such as the NRC and are typically listed in the ODCM.
13.
MDA: Minimum Detectable Activity. For radiochemistry instruments, the MDA is the a posteriori minimum concentration that a counting system detects. The smallest concentration or activity of radioactive material in a sample that will yield a net count above instrument background and that is detected with 95%
probability, with only 5% probability of falsely concluding that a blank observation represents a true signal.
Annual Radioactive Effluent Release Report YEAR: 2024 Page 4 of 49 Company: Entergy Plant: Waterford 3 14.
MDC: Minimum Detectable Concentration. Essentially synonymous with MDA for the purposes of radiological monitoring.
15.
Mean: The sum of all of the values in a distribution divided by the number of values in the distribution, synonymous with average.
16.
Microcurie (µCi): 3.7 x 104 disintegrations per second, or 2.22 x106 disintegrations per minute.
17.
millirem (mrem): 1/1000 rem; a unit of radiation dose equivalent in tissue.
18.
Milliroentgen (mR): 1/1000 Roentgen; a unit of exposure to X-or gamma radiation.
19.
N/A: Not Applicable 20.
NEI: Nuclear Energy Institute 21.
NRC: Nuclear Regulatory Commission 22.
ODCM: Offsite Dose Calculation Manual 23.
OSLD: Optically Stimulated Luminescence Dosimeter 24.
Protected Area: A 10 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 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
Annual Radioactive Effluent Release Report YEAR: 2024 Page 5 of 49 Company: Entergy Plant: Waterford 3 33.
Unrestricted Area: An area, access to which is neither limited nor controlled by the licensee.
EXECUTIVE
SUMMARY
Waterford 3 (WF3), license number 50-382, Radiological Effluent Control (REC)
Program was established to limit the quantities of radioactive material that may be released based on calculated radiation doses or dose rates. Dose to Members of the Public due to radioactive materials released from the plant is limited by Technical Specifications,10 CFR 20, and by 40 CFR 190. Operational doses to the public during 2024 were calculated to be within the limits required by regulation and compared to other sources of radiation dose and pose no health hazard. These doses are summarized and compared to the regulatory limits in Section 2.1 Comparison to Regulatory Limits below.
The Annual Radioactive Effluent Release Report (ARERR) is published per REC requirements and provides data related to plant operation, including: quantities of radioactive materials released in liquid and gaseous effluents; radiation doses to members of the public; solid radioactive waste shipped offsite for processing or direct disposal; and other information as required by site licensing documents.
In 2024, the gaseous effluent dose assessments for locations from the Land Use Census showed that the critical receptor for Waterford 3 is child, due to vegetation, at PIT Receptor Location 1.45 km NW. The maximum Annual Organ Dose calculated for this receptor was 2.54E-04 mrem to the liver.
The maximum dose calculated to any organ due to radioactive liquid effluents was 2.54E-04 mrem, for adult Gastrointestinal-Lower Left Intestine organ due to drinking water pathway.
Solid radioactive waste shipped offsite for processing or direct disposal included 58.6 Curies and 1.12E+2 m3, shipped in 5 shipments.
In addition to monitoring radioactive effluents, WF3 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 YEAR: 2024 Page 6 of 49 Company: Entergy Plant: Waterford 3 2.1 Comparison to Regulatory Limits During 2024 all solid, liquid, and gaseous radioactive effluents from Waterford 3 were well below regulatory limits, as summarized in Table 1 and Table 2.
Table 1, Waterford 3 Dose Summary1 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Dose Limit, Total Body Limit 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3 mrem Total Body Dose 4.57E-05 3.86E-05 2.00E-05 2.37E-05 1.28E-04
% of Limit 3.05E-03 2.57E-03 1.33E-03 1.58E-03 4.27E-03 Liquid Effluent Dose Limit, Any Organ Limit 5 mrem 5 mrem 5 mrem 5 mrem 10 mrem Max Organ Dose 6.26E-05 9.71E-05 2.93E-05 6.47E-05 2.54E-04
% of Limit 1.25E-03 1.94E-03 5.86E-04 1.29E-03 2.54E-03 Gaseous Effluent Dose Limit, Gamma Air (Noble Gas)
Limit 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Gamma Air Dose 9.39E-07 9.67E-07 0.00E+00 6.71E-04 6.73E-04
% of Limit 1.88E-05 1.93E-05 0.00E+00 1.34E-02 6.73E-03 Gaseous Effluent Dose Limit, Beta Air (Noble Gas)
Limit 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Beta Air Dose 2.79E-06 2.88E-06 0.00E+00 2.44E-04 2.50E-04
% of Limit 2.79E-05 2.88E-05 0.00E+00 2.44E-03 1.25E-03 Gaseous Effluent Organ Dose Limit (Iodine, Tritium, Particulates with
> 8-day half-life)
Limit 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Max Organ Dose 8.61E-03 2.85E-02 8.56E-03 2.65E-03 4.83E-02
% of Limit 1.15E-01 3.80E-01 1.14E-01 3.53E-02 3.22E-01 1 Table 1 demonstrates compliance with 10 CFR Part 50, App. I Limits.
Annual Radioactive Effluent Release Report YEAR: 2024 Page 7 of 49 Company: Entergy Plant: Waterford 3 Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for WF32 Whole Body Thyroid Max Other Organ Gaseous3 (mrem) 6.39E-4 4.83E-2 4.83E-2 Carbon-14 (mrem) 4.13E-01 4.13E-01 2.07E+00 Liquid (mrem) 1.28E-4 1.18E-4 2.54E-4 Groundwater and Storm Drain Total (mrem) 0.00E+0 0.00E+0 0.00E+0 Direct Shine from areas such as dry cask storage, radwaste storage, Equipment Mausoleums (mrem) 4.83E-1 4.83E-1 4.83E-1 Total Site Dose (mrem) 8.97E-01 9.44E-01 2.60E+00 Total w/Other Nearby Facility4 0.00E+0 0.00E+0 0.00E+0 Limit 25 mrem 75 mrem 25 mrem
% of Limit 3.59E+00 1.26E+00 1.04E+01 2 Table 2 is a summation of Units to show compliance with 40 CFR Part 190 Limits.
3 Gaseous dose values in Table 2 include organ dose from Noble Gas, Iodine, Tritium, and particulates.
4 Other fuel cycle sources within 5 miles of the site are considered in this analysis.
Annual Radioactive Effluent Release Report YEAR: 2024 Page 8 of 49 Company: Entergy Plant: Waterford 3 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.
Figure 1, Pressurized Water Reactor (PWR) [1]
Annual Radioactive Effluent Release Report YEAR: 2024 Page 9 of 49 Company: Entergy Plant: Waterford 3 3.1 (Continued)
Figure 2, Boiling Water Reactor (BWR) [2]
Electricity is generated by a nuclear power plant similarly to the way that electricity is generated at other conventional types of power plants, such as those powered by coal or natural gas. Water is boiled to generate steam; the steam turns a turbine that is attached to a generator and the steam is condensed back into water to be returned to the boiler. What makes nuclear power different from these other types of power plants is that the heat is generated by fission and decay reactions occurring within and around the core containing fissionable uranium (U-235).
Nuclear fission occurs when certain nuclides (primarily U-233, U-235, or Pu-239) absorb a neutron and break into several smaller nuclides (called fission products) as well as producing some additional neutrons.
Fission results in production of radioactive materials including gases and solids that must be contained to prevent release or treated prior to release. These effluents are generally treated by filtration and/or hold-up prior to release. Releases are generally monitored by sampling and by continuously indicating radiation monitors. The effluent release data is used to calculate doses in order to ensure that dose to the public due to plant operation remains within required limits.
Annual Radioactive Effluent Release Report YEAR: 2024 Page 10 of 49 Company: Entergy Plant: Waterford 3 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.
Figure 3, Sources of Radiation Exposure (NCRP Report No. 160) [3]
Annual Radioactive Effluent Release Report YEAR: 2024 Page 11 of 49 Company: Entergy Plant: Waterford 3 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: 2024 Page 12 of 49 Company: Entergy Plant: Waterford 3 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.
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 YEAR: 2024 Page 13 of 49 Company: Entergy Plant: Waterford 3 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.
Biennially, 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 YEAR: 2024 Page 14 of 49 Company: Entergy Plant: Waterford 3 DOSE ASSESSMENT FOR PLANT OPERATIONS 4.1 Regulatory Limits Regulatory limits are detailed in station licensing documents: Technical Requirements Manual (TRM) and the Offsite Dose Calculation Manual (ODCM). These documents contain the limits to which WF3 must adhere. WF3 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 WF3 is well below the ODCM/TRM limits. The instantaneous concentration of liquid radioactive material released shall be limited to ten times the concentration specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the total concentration released shall be limited to 2.0 x 10-4 microcuries/ml.
The annual whole body, skin and organ dose was computed using the 2024 source term using the dose calculation methodology provided in the ODCM. The calculated doses due to gaseous effluents are used to demonstrate compliance with offsite dose limits are presented in Table 1, Waterford 3 Dose Summary and Table 2, Total Annual Offsite-Dose Comparison to 40 CFR 190 Limits for WF3.
4.2 Regulatory Limits for Gaseous Effluent Doses:
1.
Fission and activation gases:
a.
Noble gases dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
1)
Less than or equal to 500 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 b)
Less than or equal to 20 mrads beta 4.2 (Continued)
Annual Radioactive Effluent Release Report YEAR: 2024 Page 15 of 49 Company: Entergy Plant: Waterford 3 2.
Iodine, tritium, and all radionuclides in particulate form with half-lives greater than 8 days.
a.
The dose rate for iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to areas at and beyond the site boundary shall be limited to the following:
1)
Less than or equal to 1500 mrem/yr to any organ b.
The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 DAYS in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
1)
Quarterly a)
Less than or equal to 7.5 mrem to any organ 2)
Yearly a)
Less than or equal to 15 mrem to any organ 4.3 Regulatory Limits for Liquid Effluent Doses 1.
The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:
a.
Quarterly 1)
Less than or equal to 1.5 mrem total body 2)
Less than or equal to 5 mrem critical organ b.
Yearly 1)
Less than or equal to 3 mrem total body 2)
Less than or equal to 10 mrem critical organ
Annual Radioactive Effluent Release Report YEAR: 2024 Page 16 of 49 Company: Entergy Plant: Waterford 3 4.4 40 CFR 190 Regulatory Dose Limits for a Member of the Public 1.
Total Dose (40 CFR 190) a.
The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC in the unrestricted area due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to the following:
1)
Less than or equal to 25 mrem, Total Body or any Organ except Thyroid.
2)
Less than or equal to 75 mrem, Thyroid.
4.5 Onsite Doses (Within Site Boundary)
WF3 classifies individuals within the site boundary as either occupationally exposed individuals or members of the public. This section evaluates dose to non-occupationally exposed workers and members of the public that may be onsite for various reasons. The report must include any other information as may be required by the Commission to estimate maximum potential annual radiation doses to the public resulting from airborne effluents, carbon-14, and direct shine as required by 10 CFR 50.36a(a)(2). While within controlled or restricted areas, the limits from Sections 4.1 through 4.4 do not apply; however, 10 CFR 20.1301 dose limit of 100 mrem per year TEDE and dose rate limit of 2 mrem per hour from external sources continue to apply.
Occupancy times within the controlled areas are generally sufficiently low to compensate for increase in the atmospheric dispersion factor above the site boundary. Groups of concern include an employee at the Waterford 1 and 2 fossil fuel plants, located in the NW sector at a distance of approximately 670 meters (0.42 miles) from the reactor building. Use of a conservative assumption of 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />s/week spent inside the site boundary by these groups conservatively represents the most-exposed individual.
Table 3, Onsite Doses (Within Site Boundary)
Location Sector Approx.
Distance (Meters)
X/Q s/m^3 D/Q 1/m^2 Total Body Dose (mrem)
External Dose Total Noble Gas
- Iodine, Particulate, C-14 & H-3 TLD or OSLD Waterford 1 and 2 fossil fuel plants NW 670 9.80E-06 6.40E-08 1.60E-04 2.06E+01 0.00E+00 2.06E+01
Annual Radioactive Effluent Release Report YEAR: 2024 Page 17 of 49 Company: Entergy Plant: Waterford 3 SUPPLEMENTAL INFORMATION 5.1 Gaseous Batch Releases 5.1.1 WF3 Number of batch releases 4
Total time period for a batch release 368 minutes Maximum time period for a batch release 368 minutes Average time period for a batch release 368 minutes Minimum time period for a batch release 368 minutes 5.2 Liquid Batch Releases 5.2.1 WF3 Number of batch releases 94 Total time period for a batch release 27618 minutes Maximum time period for a batch release 348 minutes Average time period for a batch release 293.8 minutes Minimum time period for a batch release 1 minute Average total flow during period of release 2.04E+8 gpm 5.3 Abnormal Releases 5.3.1 Gaseous Abnormal Releases There were no abnormal releases during the reporting period.
Number of releases 0
Total activity released None 5.3.2 Liquid Abnormal Releases There were no abnormal releases during the reporting period.
Number of releases 0
Total activity released None
Annual Radioactive Effluent Release Report YEAR: 2024 Page 18 of 49 Company: Entergy Plant: Waterford 3 5.4 Land Use Census Changes A land use census performed in 2024 did not identify the need for any changes to locations being used for effluent dose calculations or radiological environmental sampling.
5.5 Meteorological Data The USNRC Regulatory Guide 1.23 Revision 1 specifies that for each parameter collected, a 90 percent data recovery rate should be achieved for an annual collection cycle. Also, a joint recovery rate for parameters used in classifying atmospheric transport and diffusion values should be 90 percent. The Primary and Backup Towers provided 94.7% data recovery in 2024. This meets the greater than 90% requirement.
An Annual Meteorological Monitoring Program Report is maintained on site and is available for review upon request. Attachment 3, Meteorological Data, provides information on the 2024 Joint Frequency Distributions and Classification of Atmospheric Stability.
5.6 Effluent Radiation Monitors Out of Service Greater Than 30 Days Technical Requirements Manual (TRM) Specifications 3.3.3.10 and 3.3.3.11 require reporting in the Annual Radioactive Effluent Release Report of why designated inoperable effluent monitoring instrumentation was not restored to operability within the time specified in the Action Statement. Waterford 3 had multiple effluent radiation monitors inoperable greater than the 30 days specified in the action statement of the TRM 3.3.3.10 and 3.3.3.11; however, not all monitors that were inoperable greater than 30 days had TRM entries greater than 30 days.
All Waterford 3 effluent radiation monitors that were inoperable for 30 days are more are listed below.
Effluent Radiation Monitor Name Number of Days Out of Service Date Range Out of Service Reason Out of Service >30 Days Additional Notes (ODCM or TS)
PRM-IRE-0100.1 Plant Stack (PS)
Particulate Iodine and Gas (PIG) A 328 9/22/2023 8/15/2024 Plank Stack A was taken apart to use parts for the restoration of Containment PIG radiation monitor EOS 23-0425:
Unplanned TRM entry documentation: CR-WF3-2023-15874, CR-WF3-2023-17087, EOS 23-0476, EOS 23-0510, EOS 0533, EOS-24-0009 Planned TRM entry documentation: EOS 23-0494, EOS 24- 0168 Multiple planned TRM entries were made for weekly filter replacement on PS B. PS B and/or PS WRGM remained in service during other times of PS A periods of inoperability; therefore, no TRM entry was made greater than 30 days.
Annual Radioactive Effluent Release Report YEAR: 2024 Page 19 of 49 Company: Entergy Plant: Waterford 3 Effluent Radiation Monitor Name Number of Days Out of Service Date Range Out of Service Reason Out of Service >30 Days Additional Notes (ODCM or TS)
PRM-IRE-0100.2 Plant Stack PIG B 54 1/5/2024 2/28/2024 The particulate monitor lost flow and Iodine monitor was spiking.
EOS 24-0009:
Multiple planned TRM entries were made for weekly filter replacement on PS B. PS WRGM remained in service during other times of PS B periods of inoperability; therefore, no TRM entry was made greater than 30 days.
PRM-IRE-6778 Turbine Building Industrial Waste Sump (TBIWS)
PIG 30 1/23/2024 2/22/2024 Inoperable due to detector alignment EOS 24-0038:
Entered the TRM for the full time of TBIWS PIG inoperability. Needed to restore in 30 days. This monitor was restored on day 30.
PRM-IRE-0100.2 Plant Stack PIG B 49 4/17/2024 6/5/2024 Board failure EOS 24-0168:
Secured CVA train A to comply with TRM 3.3.3.11. Containment purge is not allowed with both Plant Stacks inoperable. Alternate sampling on Plant Stack WRGM.
PRM-IRE-6778 Turbine Building Industrial Waste Sump (TBIWS)
PIG 30 9/13/2024 10/13/2024 Routed hoses from Industrial Waste Sump #1 to the Oil Separator
- Sump, bypassing the TBIWS Radiation Monitor EOS 24-0369:
Entered the TRM for the full time of TBIWS PIG inoperability. Needed to restore in 30 days. This monitor was restored on day 30.
PRM-IRE-0648 Gaseous Waste Monitor PIG 587 as of 4/8/2025 8/30/2023 Current PMI calibration EOS 23-0369:
TRM is only applicable during releases. Permit numbers documenting releases that occurred during the period of inoperability: W3GB2023-160, W3GB2023-163, W3GB2024-037, W3GB2024-042 PRM-IRE-6776 Dry Cooling Tower Sump (DCTS) 2 PIG 254 as of 4/8/2025 7/28/2024 Current Broken Filter Housing EOS 24-0307:
Entered the TRM for the full time of DCTS PIG inoperability.
5.7 Offsite Dose Calculation Manual (ODCM) Changes There were no changes to the Offsite Dose Calculation Manual, UNT-005-014, in 2024.
Annual Radioactive Effluent Release Report YEAR: 2024 Page 20 of 49 Company: Entergy Plant: Waterford 3 5.8 Process Control Program (PCP) Changes There were no changes to the Process Control Program, EN-RW-105, in 2024.
5.9 Radioactive Waste Treatment System Changes During the reporting period, no major changes were made to any Radioactive Waste Systems. All major changes to Radioactive Waste Systems are included in Waterford 5.10 Other Supplemental Information 5.10.1 Unprotected Outside Storage Tank Radioactivity Limit Technical Specification 3/4.11.1.4 specifies that the quantity of radioactivity contained in each unprotected outdoor storage tank be maintained less than or equal to 7.85E-04 Curies (excluding tritium and dissolved and entrained noble gases). At no time during the reporting period was this value exceeded.
5.10.2 Gaseous Storage Tank Total Radioactivity Limit Technical Specification 3/4.11.2.6 specifies that the quantity of radioactivity contained in each gas storage tank be maintained less than or equal to 8.5E+04 Curies noble gas (considered as Xe-133 equivalent). At no time during the reporting period was this value exceeded.
5.10.3 Non-Routine Planned Discharges There were no non-routine planned discharges for the reporting period.
5.10.4 Unavailability of REMP Milk Samples Due to the unavailability of three milk sampling locations within five kilometers of the plant, Broad Leaf sampling is performed in accordance with Technical Requirements Manual (TRM) Table 3.12-1. The collection of milk occurred until 6/15/2021 when revision 308 of the ODCM became effective at WF3 after the owner of the cows at location MKE-3 got rid of all milking cows and after the 2020 land use census was performed. Before 6/15/2021, milk was collected, when available, from the control location and one identified sampling location as indicated in UNT-005-014, Offsite Dose Calculation Manual, Attachment 13.
Annual Radioactive Effluent Release Report YEAR: 2024 Page 21 of 49 Company: Entergy Plant: Waterford 3 5.10.5 Activity Released Via Secondary Pathways The following secondary release paths were continuously monitored for radioactivity:
The Hot Machine Shop Exhaust (AH-35)
Decontamination Shop Exhaust (AH-34)
The RAB H&V Equipment Room Ventilation System Exhaust (E-41A and E-41B)
The Switchgear/Cable Vault Area Ventilation System (AH-25)
Continuous sampling for these areas is maintained to demonstrate the operability of installed treatment systems and to verify integrity of barriers separating primary and secondary ventilation systems. Sampling for these areas was limited to continuous particulate and iodine sampling and monthly noble gas grab sampling. The activity released via these secondary pathways resulted from routine operations and remained below significant levels.
5.10.6 Missed or Late for Radioactive Effluent Program Samples or Analysis There were no missed Radioactive Effluent Program samples or analysis during the calendar year 2024.
5.10.7 Reactor Coolant System Average Energy (E-Bar)
Reactor Coolant System E-Bar calculations were performed on 2/28/2024 and 8/21/2024 with values of 0.5631 and 0.1045 MeV/disintegration, respectively.
Reactor Coolant System E-Bar is supplied for information only and is not used for effluent dose calculations.
Annual Radioactive Effluent Release Report YEAR: 2024 Page 22 of 49 Company: Entergy Plant: Waterford 3 5.10.8 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.
recommended re-
-14 as appropriate. Carbon-14 production and release estimates were calculated using active core coolant mass, average neutron flux by energy and reactor coolant nitrogen concentrations to determine Carbon-14 generation based upon an effective full power year. The estimated generation for Waterford 3 during 2024 was 9.53E+00 Curies.
Public dose estimates were performed using methodology from the ODCM which is based on Regulatory Guide 1.109 methodology.
5.10.9 Errata/Corrections to Previous ARERRs Through investigation from a Pre-NRC Assessment (tracked through LO-WLO-2021-00018), Waterford 3 found that Tellurium 123m (Te-123m) was being mislabeled as Nickel-56 (Ni-56). The correction to Table 5 of the 2021 ARERR was shown in the 2023 ARERR. Through rechecking the calculations during the 2024 ARERR submittal, it was found that Table 4 was also affected by the change in nuclide. The 2021 ARERR, Table 4, Liquid Effluents-Summation of All Releases Waterford 3 had an error in the A.1 quarter 2 Fission & Activation Products. The previous number was 7.11E-4 Ci. The correct number is 7.12E-4 Ci. A snip of page 15 of the 2021 ARERR in its entirety is shown below.
Through investigation from a Pre-NRC Assessment (tracked through LO-WLO-2021-00018), Waterford 3 found that Tellurium 123m (Te-123m) was being mislabeled as Nickel-56 (Ni-56). The correction 2023 ARERR Table 5 was made during preparation of the report. Through rechecking the calculations during the 2024 ARERR submittal, it was found that Table 4 was also affected by the change in nuclide. In the 2023 ARERR, Table 4, Liquid Effluents-Summation of All Releases Waterford 3 had an error in the A.1 quarter 4 Fission & Activation Products. The previous number was 6.27E-3 Ci. The correct number is 6.28E-3 Ci. A snip of page 21 of the 2023 ARERR in its entirety is shown below.
Annual Radioactive Effluent Release Report YEAR: 2024 Page 23 of 49 Company: Entergy Plant: Waterford 3
Annual Radioactive Effluent Release Report YEAR: 2024 Page 24 of 49 Company: Entergy Plant: Waterford 3
Annual Radioactive Effluent Release Report YEAR: 2024 Page 25 of 49 Company: Entergy Plant: Waterford 3 NEI 07-07 ONSITE RADIOLOGICAL GROUNDWATER MONITORING PROGRAM Waterford 3 has developed a Groundwater Protection Initiative (GPI) program in accordance with NEI 07-07, Industry Ground Water Protection Initiative Final Guidance Document [9]. The purpose of the GPI is to ensure timely detection and an effective response to situations involving inadvertent radiological releases to groundwater in order to prevent migration of licensed radioactive material off-site and to quantify impacts on decommissioning. During 2024, WF3 collected and analyzed groundwater samples in accordance with the requirements of EN-CY-111, Radiological Groundwater Protection Program.
This section is included in this report to communicate results of NEI 07-07 Radiological Groundwater Monitoring Program. Monitoring wells installed as part of GPI program are sampled and analyzed as summarized in Table 4, Groundwater Protection Program Monitoring Well Sample Schedule. In addition to reporting results from NEI 07-07 monitoring wells, voluntary communications to offsite governmental agencies for onsite leaks or spills per NEI 07-07 Objective 2.2, are also reported as part of this report. It is important to note, samples and results taken in support of NEI 07-07 groundwater monitoring program are not part of the Radiological Environmental Monitoring Program (REMP) but should be reported as part of ARERR.
Table 4, Groundwater Protection Program Monitoring Well Sample Schedule Well Name Tritium Gamma HTD Alpha Emitters Monitoring Well #3 Quarterly Quarterly If tritium or plant-related gamma activity is present If tritium or plant-related gamma activity is present Monitoring Well #4 Quarterly Quarterly If tritium or plant-related gamma activity is present If tritium or plant-related gamma activity is present Monitoring Well #5 Quarterly Quarterly If tritium or plant-related gamma activity is present If tritium or plant-related gamma activity is present Monitoring Well #6 Quarterly Quarterly If tritium or plant-related gamma activity is present If tritium or plant-related gamma activity is present Monitoring Well #7 Quarterly Quarterly If tritium or plant-related gamma activity is present If tritium or plant-related gamma activity is present Monitoring Well #8 Quarterly Quarterly If tritium or plant-related gamma activity is present If tritium or plant-related gamma activity is present Monitoring Well #9 Quarterly Quarterly If tritium or plant-related gamma activity is present If tritium or plant-related gamma activity is present Monitoring Well #10 Quarterly Quarterly If tritium or plant-related gamma activity is present If tritium or plant-related gamma activity is present Monitoring Well #11 Quarterly Quarterly If tritium or plant-related gamma activity is present If tritium or plant-related gamma activity is present Monitoring Well #12 Quarterly Quarterly If tritium or plant-related gamma activity is present If tritium or plant-related gamma activity is present
Annual Radioactive Effluent Release Report YEAR: 2024 Page 26 of 49 Company: Entergy Plant: Waterford 3 The 2024 Radiological Groundwater Monitoring Program results are summarized in Table 5, Groundwater Protection Program Monitoring Well Results. All results were less than minimum detectable activity for gamma emitters and tritium during 2024.
Table 5, Groundwater Protection Program Monitoring Well Results5 (all results reported in pCi/L)
Monitoring Well #3 Sample Date and Time Number of Positive Detections Tritium Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2/21/2024 10:35 0
< 532
< 8.86
< 6.86
< 15.20
< 7.86
< 16.20
< 7.80
< 12.30
< 11.90
< 7.26
< 7.57
< 34.20
< 11.90 2/21/2024 10:55 DUP 0
< 529
< 5.54
< 8.65
< 13.70
< 8.83
< 19.90
< 7.02
< 14.60
< 11.20
< 6.01
< 8.23
< 37.80
< 12.90 4/9/2024 11:55 0
< 541
< 6.43
< 6.75
< 13.30
< 7.80
< 14.50
< 8.57
< 13.70
< 8.64
< 7.14
< 8.91
< 26.40
< 9.21 8/1/2024 12:35 0
< 548
< 6.00
< 8.32
< 13.50
< 7.57
< 14.60
< 6.93
< 13.40
< 7.66
< 5.27
< 7.18
< 22.90
< 10.80 10/23/2024 14:40 0
< 573
< 5.51
< 7.65
< 14.50
< 9.51
< 16.70
< 6.32
< 14.10
< 10.10
< 7.45
< 7.76
< 25.80
< 10.70 Monitoring Well #4 Sample Date and Time Number of Positive Detections Tritium Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2/21/2024 11:45 0
< 542
< 7.36
< 6.65
< 14.60
< 9.92
< 14.60
< 6.78
< 13.90
< 12.90
< 8.86
< 6.02
< 30.40
< 10.40 4/9/2024 13:15 0
< 567
< 6.48
< 6.44
< 16.80
< 8.43
< 8.78
< 7.88
< 11.10
< 7.08
< 5.89
< 7.29
< 29.70
< 7.71 4/9/2024 13:55 DUP 0
< 550
< 6.88
< 6.17
< 13.80
< 7.69
< 12.30
< 6.69
< 9.10
< 8.70
< 7.16
< 7.43
< 27.40
< 9.45 8/1/2024 11:00 0
< 546
< 6.88
< 7.87
< 12.80
< 7.26
< 15.30
< 7.20
< 8.67
< 9.72
< 8.16
< 7.29
< 31.10
< 10.60 10/23/2024 13:25 0
< 571
< 6.90
< 7.27
< 17.50
< 8.97
< 22.40
< 8.47
< 12.10
< 11.80
< 7.76
< 7.56
< 31.90
< 9.60 Monitoring Well #5 Sample Date and Time Number of Positive Detections Tritium Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2/20/2024 15:40 0
< 533
< 7.12
< 7.52
< 15.50
< 8.63
< 15.50
< 8.42
< 10.70
< 14.00
< 7.93
< 8.31
< 35.70
< 10.40 4/9/2024 16:25 0
< 543
< 6.12
< 5.20
< 12.40
< 5.40
< 11.40
< 6.11
< 10.70
< 8.26
< 7.72
< 7.52
< 22.50
< 8.02 8/1/2024 10:15 0
< 557
< 8.50
< 7.80
< 17.70
< 11.2
< 16.80
< 7.46
< 12.60
< 10.90
< 9.47
< 9.58
< 32.80
< 5.21 10/23/2024 12:20 0
< 568
< 7.84
< 6.68
< 14.60
< 6.94
< 16.80
< 8.80
< 14.20
< 11.30
< 7.88
< 7.26
< 28.10
< 12.40 5 Maximum concentrations for each well are BOLDED throughout the table.
Annual Radioactive Effluent Release Report YEAR: 2024 Page 27 of 49 Company: Entergy Plant: Waterford 3 Table 5, Groundwater Protection Program Monitoring Well Results5 (all results reported in pCi/L)
Monitoring Well #6 Sample Date and Time Number of Positive Detections Tritium Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2/20/2024 16:25 0
< 535
< 6.07
< 6.64
< 13.90
< 5.43
< 15.70
< 6.50
< 12.00
< 10.80
< 7.40
< 6.43
< 32.90
< 10.60 4/9/2024 15:20 0
< 543
< 6.68
< 8.24
< 13.90
< 6.30
< 16.80
< 7.18
< 12.70
< 9.26
< 6.82
< 6.35
< 28.20
< 10.30 8/1/2024 8:00 0
< 554
< 5.32
< 6.02
< 14.80
< 7.93
< 9.30
< 7.15
< 8.15
< 7.18
< 5.84
< 6.49
< 22.00
< 10.80 8/1/2024 8:40 DUP 0
< 557
< 6.32
< 6.56
< 12.40
< 6.09
< 13.40
< 6.13
< 9.65
< 9.05
< 7.57
< 6.50
< 24.90
< 10.40 10/23/2024 11:10 0
< 579
< 8.10
< 8.56
< 19.60
< 7.97
< 13.50
< 8.51
< 13.90
< 11.70
< 8.35
< 7.67
< 33.20
< 10.90 Monitoring Well #7 Sample Date and Time Number of Positive Detections Tritium Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2/21/2024 7:30 0
< 540
< 7.00
< 6.63
< 13.80
< 8.21
< 12.80
< 7.84
< 12.10
< 8.72
< 8.28
< 7.18
< 32.60
< 9.17 4/10/2024 15:05 0
< 544
< 5.66
< 5.41
< 13.30
< 6.59
< 12.10
< 6.89
< 10.50
< 7.48
< 6.31
< 6.39
< 23.90
< 7.77 7/31/2024 14:25 0
< 548
< 5.67
< 6.64
< 14.60
< 9.28
< 15.30
< 5.88
< 10.90
< 8.44
< 5.78
< 7.27
< 29.40
< 9.17 10/22/2024 16:50 0
< 567
< 7.76
< 7.84
< 13.10
< 10.4
< 14.30
< 6.96
< 10.50
< 12.10
< 8.76
< 7.75
< 32.20
< 13.70 Monitoring Well #8 Sample Date and Time Number of Positive Detections Tritium Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2/21/2024 8:45 0
< 537
< 7.94
< 6.19
< 14.00
< 9.51
< 16.40
< 7.38
< 14.30
< 12.60
< 7.57
< 7.96
< 28.20
< 11.40 4/10/2024 16:10 0
< 534
< 6.54
< 6.55
< 14.20
< 10.2
< 14.30
< 6.73
< 12.70
< 9.61
< 8.69
< 7.76
< 28.50
< 9.36 7/31/2024 15:50 0
< 549
< 6.95
< 5.36
< 11.20
< 4.83
< 12.80
< 5.30
< 9.61
< 8.36
< 7.29
< 6.42
< 22.90
< 9.28 10/22/2024 15:40 0
< 578
< 4.97
< 5.15
< 11.60
< 6.54
< 10.20
< 5.33
< 9.72
< 8.94
< 5.88
< 6.08
< 22.50
< 7.27 10/22/2024 16:00 DUP 0
< 568
< 7.20
< 6.15
< 14.10
< 6.96
< 15.80
< 7.23
< 12.30
< 11.20
< 6.95
< 6.95
< 34.20
< 9.32
Annual Radioactive Effluent Release Report YEAR: 2024 Page 28 of 49 Company: Entergy Plant: Waterford 3 Table 6, Groundwater Protection Program Monitoring Well Results5 (all results reported in pCi/L)
Monitoring Well #9 Sample Date and Time Number of Positive Detections Tritium Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2/21/2024 9:35 0
< 544
< 6.14
< 6.49
< 13.30
< 8.01
< 17.40
< 6.79
< 13.20
< 10.10
< 6.78
< 7.14
< 30.50
< 9.62 4/10/2024 17:05 0
< 555
< 6.62
< 6.59
< 14.20
< 4.86
< 13.90
< 5.95
< 14.10
< 8.71
< 7.78
< 8.17
< 28.00
< 6.56 7/31/2024 16:55 0
< 555
< 6.88
< 5.59
< 15.70
< 6.33
< 12.20
< 6.29
< 11.70
< 8.47
< 7.39
< 7.95
< 25.90
< 8.25 10/22/2024 14:50 0
< 560
< 6.30
< 6.32
< 13.00
< 6.66
< 13.50
< 6.36
< 11.30
< 9.54
< 7.83
< 6.60
< 31.10
< 10.50 Monitoring Well #10 Sample Date and Time Number of Positive Detections Tritium Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2/20/2024 12:50 0
< 537
< 7.06
< 6.25
< 15.70
< 11.2
< 18.30
< 8.25
< 11.40
< 13.00
< 7.84
< 9.25
< 36.40
< 10.80 4/10/2024 14:05 0
< 542
< 8.39
< 7.35
< 12.70
< 8.03
< 8.46
< 7.82
< 12.40
< 9.43
< 8.65
< 6.81
< 24.60
< 8.56 8/1/2024 13:35 0
< 556
< 7.18
< 7.70
< 17.40
< 10.1
< 15.70
< 8.68
< 14.30
< 10.40
< 8.47
< 8.30
< 34.90
< 10.00 10/22/2024 12:50 0
< 574
< 5.81
< 5.15
< 12.60
< 7.21
< 13.60
< 6.61
< 11.60
< 9.99
< 6.50
< 6.99
< 29.30
< 12.40 Monitoring Well #11 Sample Date and Time Number of Positive Detections Tritium Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2/20/2024 13:45 0
< 531
< 7.27
< 7.10
< 17.20
< 8.28
< 15.80
< 8.52
< 12.80
< 12.60
< 6.93
< 7.02
< 37.40
< 8.25 4/10/2024 10:05 0
< 551
< 9.69
< 6.76
< 12.90
< 11.2
< 17.40
< 8.04
< 11.80
< 8.63
< 7.25
< 8.80
< 29.40
< 9.22 7/31/2024 17:45 0
< 551
< 5.69
< 6.15
< 13.00
< 7.52
< 13.40
< 6.20
< 10.90
< 9.46
< 6.13
< 6.54
< 28.80
< 7.97 10/22/2024 12:10 0
< 569
< 8.44
< 6.67
< 11.70
< 9.00
< 13.30
< 6.33
< 13.80
< 10.20
< 9.16
< 6.92
< 29.70
< 9.75
Annual Radioactive Effluent Release Report YEAR: 2024 Page 29 of 49 Company: Entergy Plant: Waterford 3 Table 7, Groundwater Protection Program Monitoring Well Results5 (all results reported in pCi/L)
Monitoring Well #12 Sample Date and Time Number of Positive Detections Tritium Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2/20/2024 11:20 0
< 534
< 6.59
< 7.29
< 13.20
< 8.04
< 11.90
< 7.07
< 11.60
< 11.30
< 8.29
< 7.65
< 32.50
< 13.50 4/9/2024 9:45 0
< 551
< 5.84
< 6.62
< 13.30
< 6.71
< 14.40
< 6.74
< 13.60
< 7.63
< 5.54
< 6.49
< 24.10
< 8.17 7/31/2024 12:40 0
< 556
< 7.10
< 6.66
< 15.30
< 3.98
< 15.30
< 8.31
< 13.60
< 9.94
< 7.87
< 7.74
< 32.20
< 8.20 10/22/2024 10:05 0
< 579
< 7.49
< 6.86
< 14.10
< 7.43
< 14.70
< 8.66
< 12.60
< 11.90
< 7.17
< 6.85
< 30.80
< 9.48 6.1 Voluntary Notification During 2024, Waterford 3 did not make a voluntary NEI 07-07 notification to State/Local officials, NRC, and to other stakeholders required by site procedures.
Annual Radioactive Effluent Release Report YEAR: 2024 Page 30 of 49 Company: Entergy Plant: Waterford 3 BIBLIOGRAPHY
[1] Nuclear Regulatory Commission, 30 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-pwr.html. [Accessed October 2020].
[2] Nuclear Regulatory Commission, 25 June 2015. [Online]. Available: http://www.nrc.gov/reading-rm/basic-ref/students/animated-bwr.html. [Accessed October 2020].
[3] "NCRP Report No. 160 - Ionizing Radiation Exposure of the Population of the United States,"
National Council on Radiation Protection and Measurements, Bethesda, MD, 2009.
[4] Health Physics Society, [Online]. Available: http://hps.org/hpspublications/radiationfactsheets.html.
[Accessed 2020].
[5] "NRC Resource Page," [Online]. Available: http://www.nrc.gov/about-nrc/radiation.html. [Accessed 10 November 2020].
[6] "Japan Atomic Energy Agency," 06 November 2020. [Online]. Available:
https://www.jaea.go.jp/english/04/ntokai/houkan/houkan_02.html.
[7] "Regulatory Guide 1.109 - Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Demonstrating Compliance with 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 YEAR: 2024 Page 31 of 49 Company: Entergy Plant: Waterford 3 Attachment 1, ARERR Release Summary Tables (RG-1.21 Tables)
GASEOUS EFFLUENTS Table 8, Gaseous Effluents Summation of All Releases WF36 A.
Fission & Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error %
1.
Total Release Ci 5.25E-03 5.40E-03 0.00E+00 1.58E-01 2.50E+01 2.
Average release rate for the period Ci/sec 6.67E-04 6.87E-04 0.00E+00 1.98E-02 B.
Iodine 1.
Total Iodine 131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.50E+01 2.
Average release rate for the period Ci/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C.
Particulates 1.
Particulates with half-lives > 8 days Ci 0.00E+00 5.91E-08 0.00E+00 0.00E+00 2.50E+01 2.
Average release rate for the period Ci/sec 0.00E+00 7.52E-09 0.00E+00 0.00E+00 D.
- 1.
Total Release Ci 1.47E+01 4.87E+01 1.46E+01 4.52E+00 2.50E+01 2.
Average release rate for the period Ci/sec 1.87E+00 6.19E+00 1.84E+00 5.69E-01 E.
Gross Alpha
- 1.
Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.50E+01 2.
Average release rate for the period Ci/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F.
- 1.
Total Release Ci 1.70E+00 4.80E-01 3.71E+00 3.63E+00 2.
Average release rate for the period Ci/sec 2.17E-01 6.11E-02 4.67E-01 4.56E-01 6 % of limit is provided in Table 1, Waterford 3 Dose Summary
Annual Radioactive Effluent Release Report YEAR: 2024 Page 32 of 49 Company: Entergy Plant: Waterford 3 Table 9, Gaseous Effluents Ground Level Release Batch Mode WF3 Radionuclide Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Fission Gases Ar-41 Ci 0.00E+00 0.00E+00 0.00E+00 1.42E-01 1.42E-01 Xe-133 Ci 5.25E-03 5.40E-03 0.00E+00 1.59E-02 2.66E-02 Total for Period Ci 5.25E-03 5.40E-03 0.00E+00 1.58E-01 1.69E-01 Iodines Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Ci 4.02E-01 0.00E+00 0.00E+00 2.40E-01 6.42E-01 Gross Alpha Alpha Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Annual Radioactive Effluent Release Report YEAR: 2024 Page 33 of 49 Company: Entergy Plant: Waterford 3 Table 10, Gaseous Effluents Ground Level Release Continuous Mode WF3 Radionuclide Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Fission Gases Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates Cs-137 Ci 0.00E+00 5.91E-08 0.00E+00 0.00E+00 5.91E-08 Total for Period Ci 0.00E+00 5.91E-08 0.00E+00 0.00E+00 5.91E-08 Tritium H-3 Ci 1.43E+01 4.87E+01 1.46E+01 4.28E+00 8.19E+01 Gross Alpha Alpha Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Carbon-14 C-14 Ci 1.70E+00 4.80E-01 3.71E+00 3.63E+00 9.53E+00
Annual Radioactive Effluent Release Report YEAR: 2024 Page 34 of 49 Company: Entergy Plant: Waterford 3 LIQUID EFFLUENTS Table 11, Liquid Effluents Summation of All Releases WF3 7 A.
Fission & Activation Products Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Est. Total Error %
1.
Total Release Ci 6.48E-03 2.60E-03 4.51E-04 1.53E-03 2.50E+01 2.
Average diluted concentration Ci/mL 1.49E-10 5.80E-11 6.99E-12 6.46E-11 B.
Tritium 1.
Total Release Ci 5.21E+01 3.58E+01 2.66E+01 2.67E+01 2.50E+01 2.
Average diluted concentration Ci/mL 1.20E-06 7.97E-07 4.13E-07 1.13E-06 C.
Dissolved & Entrained Gases 1.
Total Release Ci 3.30E-04 3.03E-04 4.78E-04 1.64E-05 2.50E+01 2.
Average diluted concentration Ci/mL 7.59E-12 6.74E-12 7.41E-12 6.90E-13 D.
Gross Alpha Activity 1.
Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.50E+01 E.
Volume of Waste Released (prior to dilution)
Liters 1.48E+07 1.75E+07 1.74E+07 6.36E+06 F.
Volume of Dilution Water Used During Period Liters 4.35E+10 4.48E+10 6.45E+10 2.37E+10 7 % of limit is provided in Table 1, Waterford 3 Dose Summary
Annual Radioactive Effluent Release Report YEAR: 2024 Page 35 of 49 Company: Entergy Plant: Waterford 3 Table 12, Batch Mode Liquid Effluents WF3 Radionuclide Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Fission and Activation Products Ag-110m Ci 4.34E-06 0.00E+00 0.00E+00 2.19E-05 2.62E-05 Co-58 Ci 3.67E-04 2.35E-04 5.17E-05 1.08E-04 7.62E-04 Co-60 Ci 2.61E-04 6.87E-04 2.49E-04 1.10E-03 2.30E-03 Cr-51 Ci 3.71E-05 1.11E-03 2.45E-05 0.00E+00 1.17E-03 Mn-54 Ci 5.96E-06 5.51E-05 3.32E-06 6.65E-05 1.31E-04 Na-24 Ci 5.68E-06 0.00E+00 0.00E+00 0.00E+00 5.68E-06 Nb-95 Ci 2.93E-05 2.99E-04 4.38E-05 7.24E-05 4.45E-04 Sb-124 Ci 6.56E-04 6.97E-07 0.00E+00 0.00E+00 6.57E-04 Sb-125 Ci 5.10E-03 2.50E-05 4.26E-05 1.27E-04 5.29E-03 Sb-127 Ci 0.00E+00 8.20E-07 0.00E+00 0.00E+00 8.20E-07 Sn-113 Ci 1.22E-06 0.00E+00 0.00E+00 0.00E+00 1.22E-06 Te-123m Ci 6.96E-06 2.82E-05 1.27E-05 2.25E-06 4.74E-05 Zn-65 Ci 0.00E+00 0.00E+00 0.00E+00 3.92E-06 3.92E-06 Zr-95 Ci 8.02E-06 1.58E-04 2.32E-05 3.00E-05 2.19E-04 Total for Period Ci 6.48E-03 2.60E-03 4.51E-04 1.53E-03 1.11E-02 Tritium H-3 Ci 5.20E+01 3.57E+01 2.66E+01 2.67E+01 1.41E+02 Gross Alpha Alpha Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Entrained Gases Xe-133 Ci 3.06E-04 3.03E-04 4.26E-04 1.64E-05 1.05E-03 Xe-135 Ci 2.38E-05 0.00E+00 5.23E-05 0.00E+00 7.61E-05 Total for Period Ci 3.30E-04 3.03E-04 4.78E-04 1.64E-05 1.13E-03
Annual Radioactive Effluent Release Report YEAR: 2024 Page 36 of 49 Company: Entergy Plant: Waterford 3 Table 13, Continuous Mode Liquid Effluents WF3 Radionuclide Released Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total for year Fission and Activation Products Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium H-3 Ci 1.39E-02 5.25E-03 3.37E-02 2.19E-02 7.48E-02 Gross Alpha Alpha Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Entrained Gases Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Annual Radioactive Effluent Release Report YEAR: 2024 Page 37 of 49 Company: Entergy Plant: Waterford 3, Solid Waste Information SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)
Table 14, Types of Solid Waste Summary WF3 Types of Waste Total Volume (m3)
Total Activity (Ci)
Est. Total Error
(%)
- a. Spent resins, filter sludges, evaporator bottoms, etc.
2.00E+01 5.85E+01 25 Waste Class A 1.71E+01 1.57E+00 Waste Class B 2.83E+00 5.70E+01 Waste Class C 0.00E+00 0.00E+00 Unclassified 0.00E+00 0.00E+00
- b. Dry compressible waste, contaminated equip, etc.
8.50E+01 5.24E-02 25 Waste Class A 8.50E+01 5.24E-02 Waste Class B 0.00E+00 0.00E+00 Waste Class C 0.00E+00 0.00E+00 Unclassified 0.00E+00 0.00E+00
- c. Irradiated components, control rods, etc.
0.00E+00 0.00E+00 25 Waste Class A 0.00E+00 0.00E+00 Waste Class B 0.00E+00 0.00E+00 Waste Class C 0.00E+00 0.00E+00 Unclassified 0.00E+00 0.00E+00
- d. Other (describe) 6.80E+00 7.47E-03 25 Waste Class A 6.80E+00 7.47E-03 Waste Class B 0.00E+00 0.00E+00 Waste Class C 0.00E+00 0.00E+00 Unclassified 0.00E+00 0.00E+00
Annual Radioactive Effluent Release Report YEAR: 2024 Page 38 of 49 Company: Entergy Plant: Waterford 3 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY WASTE TYPE) ONLY >1%
ARE REPORTED. [NOTE 1]
Table 15, Major Nuclides WF3 Major Nuclide Composition Curies
- a. Spent resins, filter sludges, evaporator bottoms, etc.
Cr-51 1.08%
1.77E-02 Mn-54 1.35%
2.20E-02 Fe-55 47.01%
7.68E-01 Co-58 7.08%
1.16E-01 Co-60 22.1%
3.61E-01 Ni-63 12.08%
1.97E-01 Cs-137 6.98%
1.14E-01
- b. Dry compressible waste, contaminated equip, etc.
Mn-54 8.63%
4.92E+00 Fe-55 1.52%
8.69E-01 Co-58 12.45%
7.09E+00 Co-60 32.22%
1.83E+01 Ni-63 32.78%
1.87E+01 Zn-65 1.37%
7.81E-01 Sb-125 2.14%
1.22E+00 Cs-137 7.9%
4.50E+00
- c. Irradiated components, control rods, etc.
N/A N/A N/A
- d. Other (describe)
N/A N/A N/A
Annual Radioactive Effluent Release Report YEAR: 2024 Page 39 of 49 Company: Entergy Plant: Waterford 3 SOLID WASTE DISPOSITION Table 16, Solid Waste Disposition WF3 Number of Shipments Mode of Transportation Destination 4
Hittman Transport Energy Solutions Bear Creek Processing 1560 Bear Creek Road 1
Landstar Express America Energy Solutions-Memphis 1790 Dock Street IRRADIATED FUEL DISPOSITION Table 17, Irradiated Fuel Shipments Disposition WF3 Number of Shipments Mode of Transportation Destination None N/A N/A
Annual Radioactive Effluent Release Report YEAR: 2024 Page 40 of 49 Company: Entergy Plant: Waterford 3, Meteorological Data METEOROLOGICAL DATA
SUMMARY
1.1 Joint Frequency Distributions 1.
Period of Record: 2024 2.
Stability Class: All a.
Periods of calm (hours): 29 b.
Hours of missing data: 463 c.
Meteorological data are reported in number of hours for all stability classes.
3.
Elevation: 10m
Annual Radioactive Effluent Release Report YEAR: 2024 Page 41 of 49 Company: Entergy Plant: Waterford 3 Hours of Each Wind Speed and Direction -Stability A Wind Speed (m/s)
Wind Direction 0.21-0.75 0.76-1.00 1.01-1.50 1.51-2.0 2.01-3.00 3.01-5.00 5.01-7.00 7.01-10.0 10.01
-13.0 13.01
-18.0
>18.00 Total N
0 0
0 0
4 9
11 4
0 0
0 28 NNE 0
0 0
0 10 36 9
0 0
0 0
55 NE 0
0 0
0 13 69 18 0
0 0
0 100 ENE 0
0 0
0 3
14 1
0 0
0 0
18 E
0 0
0 1
3 7
0 0
0 0
0 11 ESE 0
0 0
1 1
12 3
0 0
0 0
17 SE 0
0 0
0 4
11 12 0
0 0
0 27 SSE 0
0 0
0 8
35 24 2
0 0
0 69 S
0 0
0 0
5 36 17 0
0 0
0 58 SSW 0
0 0
3 5
10 6
0 0
0 0
24 SW 0
0 0
1 12 6
4 0
0 0
0 23 WSW 0
0 0
0 5
5 0
0 0
0 0
10 W
0 0
0 0
3 6
2 0
0 0
0 11 WNW 0
0 0
0 2
9 1
0 0
0 0
12 NW 0
0 0
0 7
11 0
0 0
0 0
18 NNW 0
0 0
2 5
11 8
0 0
0 0
26 Total 0
0 0
8 90 287 116 6
0 0
0 507
Annual Radioactive Effluent Release Report YEAR: 2024 Page 42 of 49 Company: Entergy Plant: Waterford 3 Hours of Each Wind Speed and Direction -Stability B Wind Speed (m/s)
Wind Direction 0.21-0.75 0.76-1.00 1.01-1.50 1.51-2.0 2.01-3.00 3.01-5.00 5.01-7.00 7.01-10.0 10.01
-13.0 13.01
-18.0
>18.00 Total N
0 0
0 2
6 18 9
1 0
0 0
36 NNE 0
0 1
1 14 14 3
0 0
0 0
33 NE 0
0 0
0 26 45 4
1 0
0 0
76 ENE 0
0 0
0 3
11 0
1 0
0 0
15 E
0 0
0 1
2 4
0 0
0 0
0 7
ESE 0
0 1
1 2
4 5
0 0
0 0
13 SE 0
0 0
0 5
9 3
3 0
0 0
20 SSE 0
0 0
0 6
31 23 0
0 0
0 60 S
0 0
0 4
5 34 18 0
0 0
0 61 SSW 0
0 1
5 6
13 11 3
0 0
0 39 SW 0
0 1
4 8
4 2
0 0
0 0
19 WSW 0
0 1
2 6
7 0
0 0
0 0
16 W
0 0
1 1
6 9
0 1
0 0
0 18 WNW 0
0 1
1 1
8 4
1 0
0 0
16 NW 0
0 0
2 6
5 0
1 0
0 0
14 NNW 0
0 0
3 11 1
2 0
0 0
0 17 Total 0
0 7
27 113 217 84 12 0
0 0
460
Annual Radioactive Effluent Release Report YEAR: 2024 Page 43 of 49 Company: Entergy Plant: Waterford 3 Hours of Each Wind Speed and Direction -Stability C Wind Speed (m/s)
Wind Direction 0.21-0.75 0.76-1.00 1.01-1.50 1.51-2.0 2.01-3.00 3.01-5.00 5.01-7.00 7.01-10.0 10.01
-13.0 13.01
-18.0
>18.00 Total N
0 0
2 4
11 20 11 3
0 0
0 51 NNE 0
1 1
3 24 11 2
1 0
0 0
43 NE 0
1 2
2 40 47 4
0 0
0 0
96 ENE 0
0 1
0 8
13 3
0 0
0 0
25 E
0 0
0 0
3 1
2 0
0 0
0 6
ESE 0
0 0
6 4
5 1
0 0
0 0
16 SE 0
0 0
1 1
11 12 1
0 0
0 26 SSE 0
0 2
6 5
32 18 2
0 0
0 65 S
0 0
6 4
8 29 11 2
0 0
0 60 SSW 0
0 3
2 4
8 7
2 0
0 0
26 SW 0
0 1
1 12 7
1 1
0 0
0 23 WSW 0
0 3
8 16 12 0
0 0
0 0
39 W
0 0
1 2
16 5
0 1
0 0
0 25 WNW 0
0 0
2 1
7 3
1 0
0 0
14 NW 0
0 2
3 8
10 2
0 0
0 0
25 NNW 0
0 0
12 15 12 4
0 0
0 0
43 Total 0
2 24 56 176 230 81 14 0
0 0
583
Annual Radioactive Effluent Release Report YEAR: 2024 Page 44 of 49 Company: Entergy Plant: Waterford 3 Hours of Each Wind Speed and Direction -Stability D Wind Speed (m/s)
Wind Direction 0.21-0.75 0.76-1.00 1.01-1.50 1.51-2.0 2.01-3.00 3.01-5.00 5.01-7.00 7.01-10.0 10.01
-13.0 13.01
-18.0
>18.00 Total N
1 3
13 20 49 72 56 9
0 0
0 223 NNE 1
2 9
23 54 83 35 6
0 0
0 213 NE 1
2 13 29 80 142 12 1
0 0
0 280 ENE 0
4 7
6 35 110 30 8
1 2
0 203 E
0 0
2 1
13 46 15 0
0 1
0 78 ESE 0
0 1
1 12 31 18 3
1 0
0 67 SE 1
1 3
2 18 81 67 18 0
0 0
191 SSE 0
1 0
3 27 131 50 15 0
0 0
227 S
1 1
5 9
34 93 29 12 0
0 0
184 SSW 3
0 5
11 24 53 28 6
0 0
0 130 SW 0
5 11 9
27 26 11 0
0 0
0 89 WSW 0
3 8
17 18 20 5
0 0
0 0
71 W
1 2
9 5
18 17 5
4 0
0 0
61 WNW 0
0 7
6 11 22 15 2
0 0
0 63 NW 2
3 5
19 28 40 23 0
0 0
0 120 NNW 0
3 17 16 39 36 20 0
0 0
0 131 Total 11 30 115 177 487 1003 419 84 2
3 0
2331
Annual Radioactive Effluent Release Report YEAR: 2024 Page 45 of 49 Company: Entergy Plant: Waterford 3 Hours of Each Wind Speed and Direction -Stability E Wind Speed (m/s)
Wind Direction 0.21-0.75 0.76-1.00 1.01-1.50 1.51-2.0 2.01-3.00 3.01-5.00 5.01-7.00 7.01-10.0 10.01
-13.0 13.01
-18.0
>18.00 Total N
3 6
24 31 60 60 12 0
0 0
0 196 NNE 2
6 24 26 76 69 15 1
0 0
0 219 NE 5
6 15 29 118 76 9
0 0
0 0
258 ENE 4
3 12 17 69 121 15 0
0 0
0 241 E
7 3
6 13 48 123 15 1
0 0
0 216 ESE 2
1 10 14 51 101 16 1
0 0
0 196 SE 1
2 12 18 54 90 26 1
0 0
0 204 SSE 5
3 12 35 115 56 6
0 0
0 0
232 S
1 7
37 46 110 41 2
0 0
0 0
244 SSW 8
11 29 32 41 31 3
0 0
0 0
155 SW 1
7 32 36 23 12 0
0 0
0 0
111 WSW 5
9 35 19 30 8
0 0
0 0
0 106 W
9 7
23 19 19 6
0 0
0 0
0 83 WNW 6
10 14 12 15 10 1
0 0
0 0
68 NW 6
12 13 15 35 11 3
0 0
0 0
95 NNW 4
5 15 13 53 22 1
0 0
0 0
113 Total 69 98 313 375 917 837 124 4
0 0
0 2737
Annual Radioactive Effluent Release Report YEAR: 2024 Page 46 of 49 Company: Entergy Plant: Waterford 3 Hours of Each Wind Speed and Direction -Stability F Wind Speed (m/s)
Wind Direction 0.21-0.75 0.76-1.00 1.01-1.50 1.51-2.0 2.01-3.00 3.01-5.00 5.01-7.00 7.01-10.0 10.01
-13.0 13.01
-18.0
>18.00 Total N
16 3
16 13 7
1 0
0 0
0 0
56 NNE 6
2 9
11 28 1
0 0
0 0
0 57 NE 5
4 8
19 25 2
1 0
0 0
0 64 ENE 4
8 9
5 13 3
0 0
0 0
0 42 E
1 5
6 6
8 1
0 0
0 0
0 27 ESE 7
7 12 8
8 0
0 0
0 0
0 42 SE 5
3 4
5 11 1
0 0
0 0
0 29 SSE 6
8 19 23 40 2
0 0
0 0
0 98 S
14 17 63 47 24 1
0 0
0 0
0 166 SSW 10 22 44 21 6
1 0
0 0
0 0
104 SW 17 21 49 20 2
0 0
0 0
0 0
109 WSW 16 17 32 8
4 0
0 0
0 0
0 77 W
13 19 34 10 6
0 0
0 0
0 0
82 WNW 7
12 22 10 2
0 0
0 0
0 0
53 NW 13 19 12 9
5 0
0 0
0 0
0 58 NNW 7
5 16 12 8
2 0
0 0
0 0
50 Total 147 172 355 227 197 15 1
0 0
0 0
1114
Annual Radioactive Effluent Release Report YEAR: 2024 Page 47 of 49 Company: Entergy Plant: Waterford 3 Hours of Each Wind Speed and Direction -Stability G Wind Speed (m/s)
Wind Direction 0.21-0.75 0.76-1.00 1.01-1.50 1.51-2.0 2.01-3.00 3.01-5.00 5.01-7.00 7.01-10.0 10.01
-13.0 13.01
-18.0
>18.00 Total N
12 9
5 3
0 0
0 0
0 0
0 29 NNE 2
2 4
0 0
0 0
0 0
0 0
8 NE 4
1 2
1 1
0 0
0 0
0 0
9 ENE 3
2 1
1 0
0 0
0 0
0 0
7 E
2 0
1 1
0 0
0 0
0 0
0 4
ESE 4
4 13 0
0 0
0 0
0 0
0 21 SE 4
5 2
1 0
0 0
0 0
0 0
12 SSE 3
7 13 7
13 1
0 0
0 0
0 44 S
2 4
37 28 3
1 0
0 0
0 0
75 SSW 15 17 24 14 1
0 0
0 0
0 0
71 SW 18 22 22 5
0 0
0 0
0 0
0 67 WSW 23 18 10 2
0 0
0 0
0 0
0 53 W
29 21 14 7
0 0
0 0
0 0
0 71 WNW 17 9
9 2
0 0
0 0
0 0
0 37 NW 23 4
4 1
0 0
0 0
0 0
0 32 NNW 7
5 6
2 0
0 0
0 0
0 0
20 Total 168 130 167 75 18 2
0 0
0 0
0 560
Annual Radioactive Effluent Release Report YEAR: 2024 Page 48 of 49 Company: Entergy Plant: Waterford 3 Hours of Each Wind Speed and Direction -Stability ALL Wind Speed (m/s)
Wind Direction 0.21-0.75 0.76-1.00 1.01-1.50 1.51-2.0 2.01-3.00 3.01-5.00 5.01-7.00 7.01-10.0 10.01
-13.0 13.01
-18.0
>18.00 Total N
32 21 60 73 137 180 99 17 0
0 0
619 NNE 11 13 48 64 206 214 64 8
0 0
0 628 NE 15 14 40 80 303 381 48 2
0 0
0 883 ENE 11 17 30 29 131 272 49 9
1 2
0 551 E
10 8
15 23 77 182 32 1
0 1
0 349 ESE 13 12 37 31 78 153 43 4
1 0
0 372 SE 11 11 21 27 93 203 120 23 0
0 0
509 SSE 14 19 46 74 214 288 121 19 0
0 0
795 S
18 29 148 138 189 235 77 14 0
0 0
848 SSW 36 50 106 88 87 116 55 11 0
0 0
549 SW 36 55 116 76 84 55 18 1
0 0
0 441 WSW 44 47 89 56 79 52 5
0 0
0 0
372 W
52 49 82 44 68 43 7
6 0
0 0
351 WNW 30 31 53 33 32 56 24 4
0 0
0 263 NW 44 38 36 49 89 77 28 1
0 0
0 362 NNW 18 18 54 60 131 84 35 0
0 0
0 400 Total 395 432 981 945 1998 2591 825 120 2
3 0
8292
Annual Radioactive Effluent Release Report YEAR: 2024 Page 49 of 49 Company: Entergy Plant: Waterford 3 1.2 Stability class Table 18, Classification of Atmospheric Stability Stability Condition Pasquill Categories Percentage Extremely Unstable A
5.77%
Moderately Unstable B
5.24%
Slightly Unstable C
6.64%
Neutral D
26.54%
Slightly Stable E
31.16%
Moderately Stable F
12.68%
Extremely Stable G
6.38%