Text

Independent Spent Fuel Storage Installaton - Annual Radioactive Effluent Release Report, Annual Radiological Environmental Operating Report, and Changes to the Off-Site Dose Calculation Manual for 2024
	ML25111A155
Person / Time
Site:	Maine Yankee
Issue date:	04/01/2025
From:	Laing D; Maine Yankee Atomic Power Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	OMY-25-010
	Download: ML25111A155 (1)
	v • d • e

MAINE YANKEE 321 Old Ferry Road, Wiscasset, Maine 04578 April I 2025 OMY-25-010 10 CFR 50.4 and 10 CFR 50.36a(a)(2)

A T1N: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 - 0001 Maine Yankee Atomic Power Company Maine Yankee Independent Spent Fuel Storage In~tallation NRC License o. DPR-36 (NRC Docket Nos. 50-309 and 72-30)

Subject:

Annual Radioactive Effluent Release Report, Annual Radiological Environmental Operating Report, and Changes to the Off-Site Dose Calculation Manual for 2024 10 CFR 50.36a(a)(2) Section 2)b) of Appendix C of the Maine Yankee Atomic Power Company (Maine Yankee) Quality Assurance Program (QAP) for the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) and Section 2 of Appendix A of the Off-Site Dose Calculation Manual (ODCM) for the Maine Yankee ISFSI require Maine Yankee to submit an Annual Radioactive Effluent Release Report. Enclosure 1 provides the report for the period of January 1 through December 31, 2024.

Section 2)a) of Appendix C of the Maine Yankee QAP for the Maine Yankee ISFSI and ection 1 of Appendix A of the ODCM for the Maine Yankee ISFSI require the submittal of an Annual Radiological Environmental Operating Report. Enclosure 2 provides the report for the period of January 1 through December 31, 2024.

Section 1 )c )( 4) of Appendix C of the Maine Yankee QAP for the Maine Yankee IS FSI requires that any changes to the ODCM to be submitted as part of or concurrent with the Annual Radiological Environmental Operating Report. No revisions to the Maine Yankee I FSI ODCM were issued in 2024.

If you have any questions regarding this submittal, please do not hesitate to contact me at (207) 882-1303.

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Maine Yankee Atomic Power Company OMY-25-010/ pril 01, 2025/Page 2

Enclosures:

1. Maine Yankee Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report, January - December 2024.

2. Maine Yankee Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report, January - December 2024.

cc:

A. Kock, NRC Region I Administrator A. Dimitriadis, Chief, Decommissioning Branch, NRC, Region I Y. Diaz-Sanabria, Chief, Division of Fuel Management, Storage and Transportation Licensing Branch N. Saunders, State of Maine Radiation Control Manager

ENCLOSURE 1 MAINEY ANKEE INDEPENDE T SPE T FUEL STORAGE INSTALLATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER2024 OMY-25-010

ENCLOSURE2 MAINE YANKEE OMY-25-010 INDEPENDENT SPENT FUEL STORAGE INSTALLATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY - DECEMBER 2024

MAINE YANKEE INDEPENDENT SPENT FUEL STORAGE INSTALLATION License Nos. DPR-36 and SFGL-14 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERA TING REPORT January - December 2024 March 2025

EXECUTIVE

SUMMARY

The Maine Yankee Independent Spent Fuel Storage Installation (ISFSI) has been in operation since 2001. All fuel has been transferred into dry storage casks and placed at the ISFSI. The Radiological Environmental Monitoring Program (REMP) for the Maine Yankee ISFSI located in Wiscasset, ME was continued for the period January through December 2024 in compliance with the Maine Yankee Offsite Dose Calculation Manual (ODCM).

By design, there are no liquid or gaseous effluents associated with the operation of the ISFSI. Changes in radiological conditions at the ISFSI are only created through radiological decay of the spent nuclear fuel and greater than class C (GTCC) waste.

Therefore, the ODCM only requires monitoring of direct exposure from the facility.

There were no changes to the ODCM in 2024. TLDs were used to measure direct gamma exposure at nine locations in the vicinity of the ISFSI and one control location 5.2 kilometers away. The results of these measurements showed no significant change in exposures and potential doses to members of the public during the monitoring period.

The results of the monitoring performed in 2024 also show that operating the Maine Yankee ISFSI results in only a small fraction of the 40 CFR Part 190 and 10 CFR Part 72.104 direct radiation dose limit of 25 mrem/year to members of the public.

MY 2024 AREOR Page 2 of 15

Section Title

1.0 INTRODUCTION

............................................................................................ 4 2.0 GENERAL ISFSI AND SITE INFORMATION................................................ 5 3.0 PROGRAM DESIGN...................................................................................... 5 3.1 MONITORING ZONES........................................................................................... 5 3.2 PATHWAYS MONITORED...................................................................................... 5

3.3 DESCRIPTION

OF MONITORING PROGRAM............................................................ 6 4.0 RADIOLOGICAL DATA

SUMMARY

TABLES............................................ 11 5.0 ANALYSIS OF ENVIRONMENTAL RESULTS............................................ 14 5.1 SAMPLING PROGRAM DEVIATIONS..................................................................... 14 5.2 DIRECT RADIATION PATHWAY............................................................................ 14

6.0 REFERENCES

............................................................................................. 16 Table Title 3.1 Radiological Environmental Monitoring Program..................................... 7 3.2 Radiological Environmental Monitoring Locations................................... 8 4.1 TLD Measurements by Half-Year............................................................... 12 4.2 Direct Dose from ISFSI Operations........................................................... 13 Figure 3.1 Radiological Environmental Monitoring Locations (within 0.28 km)....... 9 3.2 Direct Radiation Monitoring Locations (outside 1 km)............................ 10 MY 2024 AREOR Page 3 of 15

1.0 INTRODUCTION

This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Maine Yankee in the vicinity of the ISFSI in Wiscasset, Maine during the calendar year. There were no changes identified in the use of unrestricted areas that would require modifications to the monitoring program for evaluating doses to individuals from principal pathways of exposure.

It is submitted annually in compliance with the ODCM. The remainder of this report is organized as follows:

Section 2:

Provides a brief description of the Maine Yankee site and its environs.

Section 3:

Provides a description of the overall REMP design. Included is a summary of the requirements for REMP sampling, tables listing routine TLD monitoring locations with compass sectors and distances from the ISFSI, and maps showing the location of each of the TLD monitoring locations.

Section 4:

Provides a complete set of TLD data in the exposure units of milliroentgen (mR). These TLD data are then converted to a calculated dose equivalent in units of mrem per year.

Section 5:

Provides the results of the monitoring program. The performance of the program in meeting ODCM requirements is discussed, and the data acquired during the year is analyzed.

Section 6:

References MY 2024 AREOR Page 4 of 15

2.0 GENERAL ISFSI AND SITE INFORMATION The Maine Yankee ISFSI is located in the town of Wiscasset, Lincoln County, Maine, approximately six miles northeast of Bath, Maine. The site vicinity is rural and lightly populated.

The ISFSI site is located near Bailey Point, a peninsula bounded to the east by the Back River and to the west by a shallow inlet known as Bailey Cove, both of which are part of the Montsweag Bay-Sheepscot River Estuary. Bailey point is an elongated bedrock ridge with flat or gently rolling topography rising to an average elevation of about 25 feet above sea level.

The REMP for the ISFSI began pre-operational measurements in the 4th quarter of 1999, approximately 2 years prior to the initial transfer of spent fuel to the ISFSI.

The ISFSI REMP has been in continuous operation since this transfer began.

3.0 PROGRAM DESIGN The REMP for the Maine Yankee ISFSI was designed to provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits. The direct dose limit for members of the public from operation of the ISFSI is 25 mrem per year (References 2 and 3).

The detailed sampling requirements of the REMP are given in the ODCM. The sampling requirements specified in the ODCM are summarized in Table 3.1 of this report. Details of the monitored locations are shown in Table 3.2, as well as Figures 3.1 and 3.2 of this report.

3.1 Monitoring Zones The REMP is designed to allow a comparison of levels of radioactivity in samples from the area possibly influenced by the ISFSI to levels found in areas not influenced by the ISFSI. The first area is called "indicator stations." The second area is called "control stations." The distinction between the two is based on relative direction from the facility and distance. Analysis of survey data from the two zones aids in determining if there is a significant difference between the two areas. It can also help in differentiating between radioactivity or radiation due to releases and those due to other fluctuations in the environment, such as seasonal variations in the natural background.

3.2 Pathways Monitored Based on the design of the ISFSI, only the direct radiation exposure pathway is monitored by the REMP. This pathway is monitored by the collection of thermoluminescent dosimeters (TLDs) which are described in more detail below.

MY 2024 ARE OR Page 5 of 15

3.4 Description of Monitoring Program 3.4.1 Direct Radiation Direct gamma radiation exposure was continuously monitored during 2024 with the use of thermoluminescent dosimeters (TLDs). At each monitoring location, these TLDs are sealed in plastic bags and attached to an object such as a tree, fence or utility pole. The TLDs are posted and retrieved on a semi-annual basis.

All TLDs are provided and processed by a National Voluntary Laboratory Accreditation Program (NVLAP) certified vendor. The TLDs are placed at various locations around the ISFSI. Table 3.2 lists the Station ID Codes, distances and direction of the TLDs from the ISFSI.

3.4.2 Special Monitoring Special samples can be taken that are not required in the ODCM. No special samples were collected in 2024.

MY 2024 AREOR Page 6 of 15

Table 3.1 Radiological Environmental Monitoring Program Exposure Collection Analysis Pathway Number of Routine and/or Collection Analysis Analysis Sample Sample Sampling Frequency Type Frequency Media Locations Mode Direct Total Locations:10 Continuous Semi-Gamma Semi-Radiation (9 around annual dose annual (TLD) perimeter of the site and 1 offsite control location)

MY 2024 AREOR Page 7 of 15

Table 3.2 Radiological Environmental Monitoring Locations Station Distance Direction Station Description Zone. From ISFSI Code From ISFSI (km)

TL-I-02 Spent Fuel Storaqe (I)**

1

< 0.28 N

TL-I-04 Spent Fuel Storage (I)**

1

< 0.28 NE TL-I-06 Spent Fuel Storage (I)**

1

< 0.28 E

TL-I-08 Spent Fuel Storage (I)**

1

< 0.28 SE TL-I-10 Spent Fuel Storage (I)**

1

< 0.28 s

TL-I-12 Spent Fuel Storaqe (I)**

1

< 0.28 SW TL-I-14 Spent Fuel Storaqe (I)**

1

< 0.28 w

TL-I-15 Spent Fuel Storaqe (I)**

1

< 0.28 WNW TL-I-16 Spent Fuel Storage (I)**

1

< 0.28 NW TL-O-36 Wiscasset Fire Station (0) 2 5.2 NW

2 = Control TLD; 1 = Indicator TLD

- I = Inner Ring TLD; 0 = Outer Ring TLD MY 2024 AREOR Page 8 of 15

Figure 3.1 Radiological Environmental Monitoring Locations (within 0.28 km)

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MY 2024 AREOR CRAPHIC SCAL.[:

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,(I J I MY 2024 AREOR Figure 3.2 Direct Radiation Monitoring Locations (outside 1 km) f,

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Page 10 of 15

4.0 RADIOLOGICAL DA TA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples which were collected during the monitoring period.

Data from direct radiation measurements made by TLDs are presented in Table 4.1.

Table 4.2 presents the estimated direct dose from ISFSI operations as determined by TLD data shown in Table 4.1.

MY 2024 AREOR Page 11 of 15

Table 4.1 TLD Measurements by Half-Year (mR)

Station ID Direction 1st Half-Year 2nd Half-Year TL-I-02 N

35 41 TL-I-04 NE 42 45 TL-I-06 E

51 40 TL-I-08 SE 41 Note 1 TL-I-10 s

48 48 TL-I-12 SW 49 48 TL-I-14 w

47 46 TL-I-15 WNW 49 52 TL-I-16 NW 52 47 TL-O-36 Control 42 47 TL-O-36a Control Backup 45 45 Note 1 - TLD missing at time of retrieval.

MY 2024 AREOR Page 12 of 15

Station ID TL-I-02 TL-I-04 TL-I-06 TL-I-08 TL-I-10 TL-I-12 TL-I-14 TL-I-15 TL-I-16 Note:

Table 4.2 Direct Dose from ISFSI Operations (mrem) 1st Half-Year 2nd Half-Year NetTLD Calculated NetTLD Calculated Result Dose Result Dose 0.0 0.00 0.0 0.00 0.0 0.00 0.0 0.00 7.5 0.28 0.0 0.00 0.0 0.00

( 1)

( 1) 4.5 0.17 2.0 0.07 5.5 0.20 2.0 0.07 3.5 0.13 0.0 0.00 5.5 0.20 6.0 0.22 8.5 0.32 1.0 0.04 Max Dose=>

Annual Dose 0.00 0.00 0.28 0.00 (2) 0.24 0.27 0.13 0.42 0.36 0.42 Doses based on a 162.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months occupancy in both of the first and second half-years.

(1) TLD missing at time of retrieval.

(2) TLD result from the first half of the year was doubled to account for the missing TLD.

MY 2024 AREOR Page 13 of 15

Radiological Environmental Monitoring Program Trending An evaluation of current 2024 TLD data was compared to the recent historical data by location for each of the REMP TLDs for trending purposes. This trending assessment evaluates the final doses from each of the indicator locations as compared to recent annual historical doses. The trending assessment is performed for the "real members of the public" based on the guidance provided in the ODCM. The analysis of the trends identifies very low annual doses slightly above or below 1 mrem with minor fluctuations in the data as compared to recent historical data. The trending comparison for each of the indicator locations confirmed that the doses are generally consistent with the most recent historical doses.

In this report, the uncorrected TLD results have been summarized and presented in Table 4.1. The annual doses, calculated for "real members of the public" based upon guidance in the ODCM, are presented in Table 4.2.

5.0 ANALYSIS OF ENVIRONMENTAL RESULTS 5.1 Sampling Program Deviations A sampling program deviation is defined as samples that are unobtainable due to hazardous conditions or to malfunction of sampling equipment. Such deviations do not compromise the program's effectiveness and in fact are considered insignificant with respect to what is normally anticipated for this Radiological Environmental Monitoring Program.

There was one deviation of the sampling program documented in 2024. This deviation was written because of a missing REMP TLD for Indication Location TL-I-08. This was documented in Condition Report number MY-CR-2025-009.

The result from the first half of 2024 for this location was used for the second half of 2024 result. This condition has no impact on the REMP.

5.2 Direct Radiation Pathway 5.2.1 Annual Dose Trends Direct radiation is continuously measured at 9 indicator locations surrounding the Maine Yankee ISFSI, along with 1 control location (Wiscasset Fire Station) using thermoluminescent dosimeters (TLDs). These dosimeters are collected every six months for readout at the NVLAP certified dosimetry services vendor.

The review of the data for trending purposes shows no significant difference in annual doses over time at the indicator locations and their relation to the 25 mrem/yr limit.

5.2.2 Direct Doses from ISFSI Operations A dose estimate is the potential dose to any real member of the public that could use portions of the site or be present adjacent to the site for recreational activities MY 2024 AREOR Page 14 of 15

throughout the year. Direct exposure above background can be estimated by subtracting the average TLD value of the control station from the indicator location measurements. As in previous years, the 2024 dose estimate assumes a total of 325 hours0.00376 days 0.0903 hours 5.373677e-4 weeks 1.236625e-4 months occupancy for the dose calculation; of which 162.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months are used in both the first and second half-years. The most likely location for exposure to a member of the public from the ISFSI is along the Back River, Bailey Cove or Montsweag Bay for boating and fishing and the mud flats in the Cove or Bay exposed at low tides which is worked by clam diggers and worm diggers; however, the time estimates are conservatively applied to all monitoring locations.

Table 4.2 presents the results of the dose calculations. The highest calculated dose is at Station ID number TL-I-15. The maximum calculated annual dose at those locations is 0.42 mrem. This value is only 1.7 percent of the 25 mrem per year limit. It is noted that most of the mud flat region in Bailey Cove that is used by the public is situated further away from this Station. As a result, actual exposures from direct radiation would be much less than the maximum calculated value.

6.0 REFERENCES

1. Maine Yankee Offsite Dose Calculation Manual, Revision 36.

2. 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation".

3.

10 CFR Part 72.104, "Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS".

MY 2024 AREOR Page 15 of 15

MAINE YANKEE INDEPENDENT SPENT FUEL STORAGE INSTALLATION License Nos. DPR-36 and SFGL-14 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)

January - December 2024 March 2025

EXECUTIVE

SUMMARY

Tables 1 and 2 summarize the quantity of radioactive gaseous and liquid effluents, respectively, for each quarter of 2024. There were no gaseous or liquid releases in 2024. Table 3 summarizes waste shipped offsite for disposal for each half year of 2024.

There was no waste shipped for disposal in 2024.

Appendices A and B indicate the status of reportable items per the requirements of the Offsite Dose Calculation Manual (ODCM). There were no reportable items in 2024.

Appendix C presents any changes in the ODCM. The ODCM was not revised in 2024.

MY 2024 ARERR Page 2 of 15

Table 1 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2024 Gaseous Effluents-Summation of All Releases 1st 2nd 3rd 4th Nuclides Released Units Quarter Quarter Quarter Quarter Error A. FiSS!OnJ:rod ActiyatiOI) Gases Total Release Ci NIA*

NIA*

Average release rate

µCils NIA*

NIA*

Percent of regulatory limit NIA*

NIA*

B. Iodines Total Iodines released Ci NIA*

NIA*

Average release rate

µCils NIA*

NIA*

Percent of regulatory limit NIA*

NIA*

C. Particulates Particulates Released Ci NIA*

NIA*

Average release rate

µCils NIA*

NIA*

Percent of regulatory limit NIA*

NIA*

Gross alpha radioactivity Ci NIA*

NIA*

D.Tritium Total release Ci NIA*

NIA*

Average release rate

µCils NIA*

NIA*

Percent of regulatory limit NIA*

NIA*

N/A*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)

MY 2024 ARERR Page 3 of 15

Table 1A MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2024 Gaseous Effluents - Ground Level Releases - Batch Mode Nuclides Released Unit 1st 2nd 3rd 4th Total Quarter Quarter Quart.er Quarter

1. Fission Gases Krypton-85 Ci NIA*

NIA*

Krypton-85m Ci NIA*

NIA*

Krypton-87 Ci NIA*

NIA*

Krypton-88 Ci NIA*

NIA*

N/A*

Xenon-133 Ci NIA*

NIA*

Xenon-135 Ci NIA*

NIA*

Xenon-135m Ci NIA*

NIA*

Xenon-138 Ci NIA*

NIA*

Unidentified Ci NIA*

NIA*

Total for period Ci NIA*

NIA*

2. Iodines lodine-131 Ci NIA*

NIA*

lodine-133 Ci NIA*

NIA*

lodine-135 Ci NIA*

NIA*

Total for period Ci NIA*

NIA*

3. Parti,;u!afes Strontium-89 Ci NIA*

NIA*

Strontium-90 Ci NIA*

NIA*

Cesium-134 Ci NIA*

NIA*

Cesium-137 Ci NIA*

NIA*

Cobalt-60 Ci NIA*

NIA*

Barium-Lanthanum-140 Ci NIA*

NIA*

Others-Plutonium-238 Ci NIA*

NIA*

Curium-243,244 Ci NIA*

NIA*

Uranium-234 Ci NIA*

NIA*

Uranium-238 Ci NIA*

NIA*

Thorium-232 Ci NIA*

NIA*

Radium-226 Ci NIA*

NIA*

N/A*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)

MY 2024 ARERR Page 4 of 15

Table 18 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2024 Gaseous Effluents - Ground Level Releases - Continuous Mode Nuclides Released Unit 1st 2nd 3rd 4th Total Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-85 Ci N/A*

N/A*

Krypton-85m Ci N/A*

N/A*

Krypton-87 Ci N/A*

NIA*

N/A*

Krypton-88 Ci N/A*

NIA*

N/A*

Xenon-133 Ci N/A*

N/A*

Xenon-135 Ci N/A*

N/A*

Xenon-135m Ci N/A*

N/A*

Xenon-138 Ci N/A*

N/A*

Unidentified Ci N/A*

N/A*

Total for period Ci N/A*

N/A*

2. Iodines lodine-131 Ci N/A*

N/A*

lodine-133 Ci N/A*

N/A*

lodine-135 Ci N/A*

N/A*

Total for period Ci N/A*

N/A*

3. Particulates Strontium-89 Ci N/A*

N/A*

Strontium-90 Ci N/A*

N/A*

Cesium-134 Ci N/A*

N/A*

NIA*

N/A*

Cesium-137 Ci N/A*

N/A*

Cobalt-60 Ci N/A*

N/A*

Barium-Lanthanum-140 Ci N/A*

N/A*

Others-Plutonium-238 Ci N/A*

N/A*

Curium-243,244 Ci N/A*

N/A*

Uranium-234 Ci N/A*

N/A*

NIA*

Uranium-238 Ci N/A*

N/A*

Thorium-232 Ci N/A*

N/A*

Radium-226 Ci N/A*

NIA*

N/A*

N/A*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)

MY 2024 ARERR Page 5 of 15

Table 1C MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2024 Gaseous Effluents - Elevated Releases - Batch Mode Nuclides Released Unit 1st 2nd 3rd 4th Total Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-85 Ci NIA*

NIA*

Krypton-85m Ci NIA*

NIA*

Krypton-87 Ci NIA*

NIA*

Krypton-88 Ci NIA*

NIA*

Xenon-133 Ci NIA*

NIA*

Xenon-135 Ci NIA*

NIA*

Xenon-135m Ci NIA*

NIA*

Xenon-138 Ci NIA*

NIA*

Unidentified Ci NIA*

NIA*

Total for period Ci NIA*

NIA*

2. Iodines lodine-131 Ci NIA*

NIA*

lodine-133 Ci NIA*

NIA*

lodine-135 Ci NIA*

NIA*

Total for period Ci NIA*

NIA*

3. Particulates Strontium-89 Ci NIA*

NIA*

Strontium-90 Ci NIA*

NIA*

Cesium-134 Ci NIA*

NIA*

N/A*

NIA*

Cesium-137 Ci NIA*

NIA*

Cobalt-60 Ci NIA*

NIA*

Barium-Lanthanum-140 Ci NIA*

NIA*

Others-Plutonium-238 Ci NIA*

NIA*

Curium-243,244 Ci NIA*

NIA*

Uranium-234 Ci NIA*

NIA*

Uranium-238 Ci NIA*

NIA*

Thorium-232 Ci NIA*

NIA*

Radium-226 Ci NIA*

NIA*

NIA*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)

MY 2024 ARERR Page 6 of 15

Table 10 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2024 Gaseous Effluents - Elevated Releases - Continuous Mode Nuclides Released Unit 1st 2nd 3rd 4th Total Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-85 Ci NIA*

NIA*

Krypton-85m Ci NIA*

NIA*

Krypton-87 Ci NIA*

NIA*

Krypton-88 Ci NIA*

NIA*

Xenon-133 Ci NIA*

NIA*

Xenon-135 Ci NIA*

NIA*

Xenon-135m Ci NIA*

NIA*

Xenon-138 Ci NIA*

NIA*

Unidentified Ci NIA*

NIA*

Total for period Ci NIA*

NIA*

2. Iodines lodine-131 Ci NIA*

NIA*

lodine-133 Ci NIA*

NIA*

lodine-135 Ci NIA*

NIA*

Total for period Ci NIA*

NIA*

3. Particulates Strontium-89 Ci NIA*

NIA*

Strontium-90 Ci NIA*

NIA*

Cesium-134 Ci N/A*

N/A*

Cesium-137 Ci NIA*

NIA*

Cobalt-60 Ci NIA*

NIA*

Barium-Lanthanum-140 Ci NIA*

NIA*

Others-Plutonium-238 Ci NIA*

NIA*

Curium-243,244 Ci NIA*

NIA*

N/A*

NIA*

Uranium-234 Ci NIA*

NIA*

Uranium-238 Ci NIA*

NIA*

Thorium-232 Ci NIA*

NIA*

Radium-226 Ci NIA*

NIA*

NIA*= Not Applicable There are no gaseous effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)

MY 2024 ARERR Page 7 of 15

Table 2 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2024 Liquid Effluents - Summation of All Releases Nuclides Released Units 1st 2nd 3rd Quarter Quarter Quarter A. Fission and Activation Products Total Release (not including Ci NIA*

NIA*

tritium, gases, alpha)

Average diluted concentration

µCi/ml N/A*

N/A*

during period Percent of applicable limit N/A*

N/A*

B.Tritium Total Release Ci N/A*

N/A*

Average diluted concentration

µCi/ml N/A*

N/A*

durinq period Percent of applicable limit N/A*

NIA*

N/A*

C. Dissolved and.Entrained Gases Total Release Ci N/A*

NIA*

Average diluted concentration

µCi/ml N/A*

NIA*

N/A*

durinq period Percent of applicable limit N/A*

N/A*

D. Gross Alpha Radioactivity Total release Ci NIA*

N/A*

Average diluted concentration

µCi/ml N/A*

N/A*

durinq period E. Volume of Waste Released Liters N/A*

N/A*

NIA*

(prior to dilution)

F. Volume of Dilution Water Liters N/A*

N/A*

Used During Period N/A*= Not Applicable 4th Quarter NIA*

NIA*

N/A*

NIA*

N/A*

NIA*

N/A*

NIA*

There are no liquid effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)

Error NIA*

N/A*

NIA*

N/A*

MY 2024 ARERR Page 8 of 15

Nuclides Released Stronti u m-89 Strontium-90 Cesium-134 Cesium-137 lodine-131 Cobalt-58 Cobalt-60 lron-59 Zinc-65 Manganese-54 Chromium-51 Zirconium-Niobium-95 Molybdenum-99 Technetium-99m Barium-Lathanium-140 Cerium-141 Others-lron-55 Antimony-125 Unidentified Total for period (above)

Dissolved and Entrained Gasses Tritium Gross Alpha Table 2A MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2024 Liquid Effluents - Batch Mode Unit 1st 2nd 3rd Quarter Quarter Quarter Ci N/A*

N/A*

Ci N/A*

N/A*

NIA*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

NIA*

Ci N/A*

N/A*

NIA*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci NIA*

N/A*

Ci N/A*

NIA*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

Ci N/A*

N/A*

N/A*= Not Applicable 4th Totals Quarter N/A*

N/A*

NIA*

N/A*

NIA*

N/A*

There are no liquid effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)

MY 2024 ARERR Page 9 of 15

Nuclides Released Stronti u m-89 Strontium-90 Cesium-134 Cesium-137 lodine-131 Cobalt-58 Cobalt-60 lron-59 Zinc-65 Manganese-54 Chromium-51 Zirconium-Niobium-95 Molybdenum-99 Technetium-99m Barium-Lathanium-140 Cerium-141 Others-lron-55 Antimony-125 Unidentified Total for period (above)

Dissolved and Entrained Gasses Tritium Gross Alpha Table 28 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report 2024 Liquid Effluents - Continuous Mode Unit 1st 2nd 3rd Quarter Quarter Quarter Ci N/A*

NIA*

N/A*

Ci NIA*

NIA*

Ci NIA*

NIA*

Ci NIA*

NIA*

N/A*

Ci NIA*

NIA*

Ci NIA*

NIA*

Ci N/A*

N/A*

NIA*

Ci NIA*

NIA*

Ci NIA*

NIA*

Ci NIA*

NIA*

Ci NIA*

NIA*

Ci N/A*

NIA*

Ci NIA*

NIA*

Ci N/A*

N/A*

NIA*

Ci N/A*

NIA*

Ci N/A*

NIA*

Ci NIA*

NIA*

Ci NIA*

NIA*

Ci N/A*

NIA*

Ci N/A*

N/A*

Ci N/A*

N/A*

NIA*

Ci N/A*

NIA*

Ci NIA*

NIA*

NIA*= Not Applicable 4th Totals Quarter NIA*

NIA*

N/A*

NIA*

N/A*

NIA*

N/A*

NIA*

N/A*

NIA*

N/A*

NIA*

N/A*

NIA*

N/A*

NIA*

N/A*

NIA*

N/A*

NIA*

N/A*

NIA*

There are no liquid effluents associated with the Maine Yankee Independent Spent Fuel Storage Installation (ISFSI)

MY 2024 ARERR Page 10 of 15

Table 3 MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report First Half 2024 Low Level Waste Shipments Resins, Filters and Evaporator Bottoms Volume Waste Class Solidifying Agent ft3 m3 A

0 0

B 0

0 C

0 0

All 0

0 Major radionuclides for above data: N/A Dry Active Waste Volume Waste Class Solidifying Agent ft3 m3 A

0 0

B 0

0 C

0 0

All 0

0 Major radionuclides for above data: N/A Irradiated ~omponents Volume Waste Class Solidifying Agent ft3 m3 A

0 0

B 0

0 C

0 0

All 0

0 Major radionuclides for above data: N/A Other Waste Volume Waste Class Solidifying Agent ft3 m3 A

0 0

B 0

0 C

0 0

All 0

0 Major radionuclides for above data: N/A MY 2024 ARERR Curies Shipped Curies 0

0 0

0 Curies Shipped Curies 0

0 0

0 Curies Shipped Curies 0

0 0

0 Curies Shipped Curies 0

0 0

0 Page 11 of 15

Table 3A MAINE YANKEE ISFSI Effluent and Waste Disposal Annual Report Second Half 2024 Low Level Waste Shipments Resin~, Filters and Evaporator Bottoms Volume Waste Class Solidifying Agent ft3 m3 A

0 0

B 0

0 C

0 0

All 0

0 Major radionuclides for above data:

Dry Active Waste Volume Waste Class Solidifying Agent ft3 m3 A

0 0

B 0

0 C

0 0

All 0

0 Major radionuclides for above data:

Irradiated Componen1s Volume Waste Class Solidifying Agent ft3 m3 A

0 0

B 0

0 C

0 0

All 0

0 Major radionuclides for above data:

Other Waste Volume Waste Class Solidifying Agent ft3 m3 A

0 0

B 0

0 C

0 0

All 0

0 Major radionuclides for above data:

MY 2024 ARERR Curies Shipped Curies 0

0 0

0 Curies Shipped Curies 0

0 0

0 Curies Shipped Curies 0

0 0

0 Curies Shipped Curies 0

0 0

0 Page 12 of 15

Appendix A Radiation Dose Assessment There were no gaseous or liquid effluent releases in 2024. Therefore, an assessment of radiation doses to the most likely exposed member(s) of the public to show compliance with 40CFR190 or 10CFR72.104 from effluents was not required.

MY 2024 ARERR Page 13 of 15

Appendix B Unplanned Releases There were no unplanned releases of radioactive materials from the site in 2024.

MY 2024 ARERR Page 14 of 15

Appendix C Offsite Dose Calculation Manual Changes There were no changes to the Offsite Dose Calculation Manual in 2024.

MY 2024 ARERR Page 15 of 15

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Subject:

Enclosures:

SUMMARY

1.0 INTRODUCTION

3.3 DESCRIPTION

SUMMARY

6.0 REFERENCES

1.0 INTRODUCTION

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SUMMARY

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