BVY 24-018, 2023 Radiological Effluent Release Report

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2023 Radiological Effluent Release Report
ML24128A095
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 05/05/2024
From: Daniels C
Northstar Decommissioning Holdings
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
BVY 24-018
Download: ML24128A095 (1)
v • d • e


Text

~

NorthStar BVY 24-018 May 5, 2023 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 NorthStar Nuclear Decommissioning Co., LLC Vermont Yankee Nuclear Power Station 320 Governor Hunt Rd.

Vernon, VT 05354 802-451-5354 Corey R. Daniels ISFSI Senior Manager 10 CFR 50.36a

SUBJECT:

2023 Radiological Effluent Release Report Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28

Dear Sir or Madam:

In accordance with 10 CFR 50.36a and the Vermont Yankee (VY) Off-site Dose Calculation Manual, please find in Enclosure 1 a copy of the Annual Radiological Effluent Release Report for 2023.

It is noted that there were no changes made to the ODCM during 2023.

The VY Renewed Facility Operating License Condition 3.E.10 requires that similar information to that contained within the subject report be provided to the Massachusetts Metropolitan District Commission (MDC). However, since the MDC is currently part of the Massachusetts Department of Conservation and Recreation (OCR), this report is being provided to the OCR to satisfy License Condition 3.E.10.

This letter contains no new regulatory commitments.

Should you have any questions concerning this letter, or require additional information, please contact Mr. Thomas B. Silko at (802) 451-5354, Ext 2506.

Sincerely, CRD/tbs

Enclosure:

Annual Radiological Effluent Release Report for 2023.

BVY 24-018 / Page 2 of 2 cc:

Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road, Suite 102 King of Prussia, PA 19406-1415 Commissioner Vermont Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05602-2601 Massachusetts Department of Public Health Director, Radiation Control Program 529 Main Street, Suite 1 M2A Charlestown, MA 02129 Commissioner Massachusetts Department of Conservation and Recreation 251 Causeway Street Boston, MA 02114

Vermont Yankee Nuclear Power Station Annual Radiological Effluent Release Report January - December 2023 NorthStar - Vermont Yankee Vermont Yankee Nuclear Power Station 320 Governor Hunt Road Vernon, Vermont 05354 Docket No. 50-271 License No. DPR-28 BVY 24-018 / Enclosure / Page 1 of 53

BVY 24-018 /Enclosure/ Page 2 of 53 VERMONT YANKEE ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR2023 Reviewed By: _ A._..i...:.__

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Scott Dorval, RP Manager, ISFSI Date

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1.0 INTRODUCTION

........................................................................................................................... 5 2.0 METEOROLOGICAL DATA......................................................................................................... 6 3.0 DOSE ASSESSMENT..................................................................................................................... 7 3.1 Doses from Liquid Effluents........................................................................................................ 7 3.2 Doses from Noble Gases.............................................................................................................. 7 3.3 Dose from Radionuclides in Particulate Form and Tritium......................................................... 7 3.4 Whole Body Doses in Unrestricted Areas from Direct Radiation............................................... 8 3.5 On-Site Recreational Activities.................................................................................................... 8 REFERENCES.......................................................................................................................................... 9 APPENDIX A - SUPPLEMENTAL INFORMATION........................................................................... 42 APPENDIX B - LIQUID HOLDUP TANKS.......................................................................................... 44 APPENDIX C - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....... 45 APPENDIX D - RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.. 46 APPENDIX E - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM...................... 47 APPENDIX F - LAND USE CENSUS.................................................................................................... 48 APPENDIX G - PROCESS CONTROL PROGRAM............................................................................. 49 APPENDIX H - OFF-SITE DOSE CALCULATION MANUAL.......................................................... 50 APPENDIX I - RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS................................................................................................................................................. 51 APPENDIX J - ON-SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE.............................................. 52 BVY 24-018 / Enclosure / Page 3 of 53

Table 1A - Gaseous Effluents -Summation of All Releases..................................................................... 10 Table 1B - Gaseous Effluents -Elevated Releases.................................................................................... 11 Table 1C - Gaseous Effluents Ground Level Releases............................................................................ 13 Table 1D - Gaseous Effluents -Non-routine Releases............................................................................. 15 Table 2A - Liquid Effluents - Summation of All Releases....................................................................... 16 Table 2B - Liquid Effluents - Routine Releases....................................................................................... 17 Table 3 - Solid Waste and Irradiated Fuel Shipments.............................................................................. 19 Table 4A - Off-Site Doses from Liquid and Gaseous Releases............................................................... 21 Table 4B - Annual Off-Site Doses from Liquid, Gaseous and Direct Radiation..................................... 22 Table 4C - Receptor Locations................................................................................................................. 23 Table 4D - Usage Factors for Environmental Pathways........................................................................... 24 Table 4E - Environmental Parameters for Gaseous Effluents.................................................................. 25 Table 4F - Environmental Parameters for Liquid Releases (Tritium) Via Groundwater.......................... 27 Tables 5A-5G - Frequency Distribution Tables for Ground Level Releases............................................ 28 Tables 6A-6G - Frequency Distribution Tables for Elevated Releases.................................................... 35 BVY 24-018 / Enclosure / Page 4 of 53

1.0 INTRODUCTION

Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste shipments for 2023, with data summarized on a quarterly basis for both liquids and gases. Table 4A summarizes the estimated radiological dose commitments from all radioactive liquid and gaseous effluents released during 2023, to the maximally exposed individual member of the public, in response to the ALARA objectives of 10 CFR 50, Appendix I. Table 4B presents the estimate of direct dose from fixed station sources along the limiting west site boundary line. Tables 5A through 6G present the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 5-year period, 2012 through 2016. Radioactive effluents reported in Tables 1 and 2 were used to determine the dose to the maximum exposed individual member of the public for 2023.

Dose commitments resulting from the release of radioactive materials in liquids and gases during the reporting period were estimated in accordance with the plants Off-Site Dose Calculation Manual (ODCM), Section 10.1 (Reference 1). These dose estimates were made using a "Method I" analysis as described in the ODCM, and as reported in Tables 4A and 4B of this report. A conservative "Method I" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 2) and uses nuclide specific dose factors. Dose factors are the dose per Ci released for the age group and organ receiving the highest dose. This method is conservative since the age and organ receiving the highest dose differs from one nuclide to another.

As required by ODCM Section 10.1, this report shall also include an assessment of the radiation doses from radioactive effluents to member(s) of the public due to allowed recreational activities inside the site boundary during the year. As discussed in Section 3.5, there were no such recreational activities permitted and, therefore, there is no associated dose assessment.

An assessment of radiation doses (including direct radiation) to the likely most exposed real member(s) of the public for the calendar year for the purposes of demonstrating conformance with 40 CFR 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," is also required to be included in this report if the conditions indicated in ODCM 3/4.4, "Total Dose," have been exceeded during the year. Since the conditions indicated in the action statement under ODCM 3/4.4 were not entered into during the year, no additional radiation dose assessment is required. However, Table 4B does provide the combination of off-site doses and dose commitments from plant effluents and direct radiation sources for the limiting member of the public as a demonstration of compliance with the dose standards of 40 CFR 190.

All calculated dose estimates for members of the public at the site boundary or beyond for the 2023 annual reporting period are below the dose criteria of 10 CFR 50, Appendix I, and 40 CFR 190.

Appendices B through J indicate the status of reportable items per the requirements of ODCM Section 10.1.

BVY 24-018 / Enclosure / Page 5 of 53

2.0 METEOROLOGICAL DATA The scope of possible accidents is significantly reduced with all spent fuel in dry cask storage. The potential for any off-site consequences from radiological accidents are also substantially reduced. No reasonably conceivable beyond design basis event can result in a radiological release that exceeds Environmental Protection Agency (EPA) Protective Actions Guidelines. During the final decommissioning and dismantling phases, administrative controls over radiological source accumulation will preempt any significant radiological release to the environment. As a result, there is no need for continued on-site meteorological data accumulation or real time dose assessment.

Conservative atmospheric dispersion factors have been developed from the 2012 through 2016 joint frequency data to provide both short term dose assessment and for assessment in the annual average dose from facility routine releases. There are no planned or existing Emergency Action Levels in the defueled state that could result in the need for real time accident release assessment with other than previously determined conservative atmospheric dispersion factors.

Actual measured meteorological data for the five-year period, 2012 through 2016, were analyzed to determine all the values and locations of the maximum off-site long-term average atmospheric dispersion and deposition factors. The highest offsite dispersion and deposition factors at any location beyond the site boundary, regardless of whether it was an actual location of a residence or food production, was used to calculate Method I dose factors for each nuclide. Each dose and dose rate calculation presented in the current Revision 41 of the ODCM incorporate the maximum applicable off-site long-term average atmospheric dispersion and deposition factors, and maximum organ dose to any age group from each nuclide.

Updated five-year average dispersion factors and deposition factors developed from 2012 through 2016 on-site meteorological hourly data and the nuclide specific dose factors can be used to assess either routine releases or estimate conservative off-site consequences from any on-site radiological event. As such, there is no need to continue to collect on-site meteorological data for either accessing routine releases or potential emergency events. Collection of data from on-site meteorological tower was terminated in November 2018.

The five-year aggregate joint frequency distribution tables for ground level releases are presented in Tables 5A through 5G. The five-year aggregate joint frequency distribution tables for elevated releases are presented in Tables 6A through 6G.

BVY 24-018 / Enclosure / Page 6 of 53

3.0 DOSE ASSESSMENT 3.1 Doses from Liquid Effluents ODCM 3/4.2.2 limits total body doses (1.5 mrem per quarter, and 3 mrem per year) and organ doses (5 mrem per quarter, and 10 mrem per year) from liquid effluents to a member of the public to those specified in 10 CFR 50, Appendix I. By implementing the requirements of 10 CFR 50, Appendix I, ODCM 3/4.2.2 assures that the release of radioactive material in liquid effluents will be kept "as low as reasonably achievable."

There were no continuous or batch routine liquid radioactive waste discharges during 2023. Dose estimates of tritium-contaminated groundwater released from the site are based on Protected Area Boundary monitoring well data collected throughout 2023 and hydrological modeling of groundwater movement. The groundwater discharge rates from the developed portion of the site to the river are estimated using a streamtube approach based on Darcys Law. Using a conservative estimate of groundwater flow through the affected area toward the river on a quarterly basis, an estimate of the total potential tritium released from the site during each quarter of 2023 was generated and reported in Table 2A. The quantity of tritium released from the site by groundwater in each quarter was then converted to dose by using the calculated dose conversion factors presented in ODCM Table 1.1.11.

The resulting quarterly doses are presented in Table 4A.

ODCM Control 3.2.1 states, in part, that groundwater flowing to the Connecticut River from the site in radioactive concentrations above background (Unrestricted Areas for liquids is at the point of discharge from the plant discharge in Connecticut River) shall be limited to 10 times the concentrations specified in Appendix B to 10 CFR 20.1001 - 20.2402, Table 2, Column 2. The tritium quarterly average concentrations discharged from the plant ranged from 0.012% to 0.018% of this limit.

3.2 Doses from Noble Gases The dose limits specified in ODCM 3/4.3.2 have been deleted from Revision 40 of the ODCM. Noble gases were not produced or detected in releases from the Reactor Building Exhaust in 2023.

3.3 Dose from Radionuclides in Particulate Form and Tritium ODCM 3/4.3.3 limits the organ dose to a member of the public from tritium and radionuclides in particulate form in gaseous effluents released from the site to areas at and beyond the site boundary to those specified in 10 CFR 50, Appendix I (7.5 mrem per quarter and 15 mrem per year). By implementing the requirements of 10 CFR 50, Appendix I, ODCM 3/4.3.3 assures that the releases of any tritium and particulates in gaseous effluents will be kept "as low as is reasonably achievable."

There were no non-routine gaseous releases or batch releases in 2023.

BVY 24-018 / Enclosure / Page 7 of 53

Continuous sampling of the plant reactor building exhaust for tritium, per ODCM Table 4.3.1, was performed by using silica gel cartridges in 2023. The cartridges were analyzed monthly. Based upon the reactor building exhaust flow rate and sample flow rates, the average release rate in µCi/sec and total release in Ci for each quarter was calculated. Tritium released to the Turbine Building 228 level during the Torus cutting project was analyzed in the same manner. Reactor to Turbine Building effluent point was sealed in March of 2023. Sampling discontinued. Three additional effluent points were created in the reactor building during 2023. Two on the 252 level and one on the 345 level. Tritium effluent from these points is calculated based on the RB H3 level, the rate of flow and duration of release. The quantity of tritium released from the site by the reactor building exhaust in each quarter was then converted to dose by using the calculated dose conversion factors presented in ODCM Table 1.1.12.

Continuous sampling of the reactor building exhaust for particulates, per ODCM Table 4.3.1, was performed in 2023. These samples are analyzed weekly for principle gamma emitters. Cobalt-60 was identified on the reactor building ventilation exhaust particulate filters in each quarter in 2023.

Cesium-137 was also identified on the reactor building ventilation exhaust particulate filters in the first, second and third quarters in 2023. Three additional effluent points were created in the reactor building during 2023. Two on the 252 level and one on the 345 level. Particulate effluent from these points is calculated based on the effluent stream sampling, the rate of flow and duration of release. The quantity of Cobalt 60 and Cs-137 did not exceed any dose limits. The doses from Co-60 and Cs-137 were combined with H-3 and are presented in Table 4A.

3.4 Whole Body Doses in Unrestricted Areas from Direct Radiation As opposed to prior years before the permanent shut down when the majority of the dose in the unrestricted area consisted of direct and skyshine radiation from N-16 decay in the Turbine Building steam cycle during power operations, there was no such source during 2023 due to the elimination of its production and its short half-life.

The other fixed sources of direct and scatter radiation to the site boundary are the Independent Spent Fuel Storage Installation (ISFSI) and old turbine rotors and casings in the Turbine Storage Facility.

All spent fuel has been transferred to the ISFSI since August 2018. The method to assess the direct radiation dose in unrestricted areas has been agreed upon with the State of Vermont. Site boundary TLDs are changed out monthly. The net dose at the location of TLD DR-53A has been chosen to assess direct radiation dose to unrestricted areas.

Table 4B lists the combination of the direct radiation dose at the limiting site boundary location and the maximum offsite dose from gaseous and liquid effluents for the purpose of demonstrating compliance with the dose standards contained in 40 CFR 190. For 2023, this annual dose was below the 25 mrem total body and organ limit, as well as the 75 mrem thyroid limit, of 40 CFR 190.

3.5 On-Site Recreational Activities During 2023, no access to the on-site boat launching ramp located north of the intake structure was permitted for employees, their families, and guests. As such, there was no associated dose impact to members of the public due to any recreational activities on-site.

BVY 24-018 / Enclosure / Page 8 of 53

REFERENCES

1.

Off-Site Dose Calculation Manual (ODCM), Revision 42, effective February 17, 2022.

2.

Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," U. S.

Nuclear Regulatory Commission, Office of Standards Development, Revision l, October 1977.

3.

Safety Guide 1.23, "Onsite Meteorological Programs, U.S. Atomic Energy Commission, February 17, 1972.

4.

Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. Nuclear Regulatory Commission, Office of Standards Development, March 1976.

5.

Meteorology and Atomic Energy, 1968, Section 5-3.2.2, "Cloud Depletion," page 204, U. S.

Atomic Energy Commission, July 1968.

6.

Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Revision 2, June 2009.

BVY 24-018 / Enclosure / Page 9 of 53

Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %

A.

Fission and Activation Gases

1.

Total release Ci ND ND ND ND

2.

Average release rate for period

µCi/sec ND ND ND ND

3.

Percent of ODCM limit (1)

NA NA NA NA B.

Iodines

1.

Total Iodine Ci ND ND ND ND

2.

Average release rate for period

µCi/sec ND ND ND ND

3.

Percent of ODCM limit (1)

NA NA NA NA C.

Particulates

1.

Particulates with T-1/2>8 days Ci 1.56E-3 1.16E-2 6.41E-4 5.05E-3 1.80E+01

2.

Average release rate for period

µCi/sec 1.85E-4 1.47E-3 8.07E-5 6.35E-4

3.

Percent of ODCM limit (2) 2.68E-1 2.07E0 1.16E-1 8.38E-1

4.

Gross alpha radioactivity Ci ND ND ND ND D.

Tritium

1.

Total release Ci 3.54E-2 5.28E-2 3.12E-2 1.79E-1 1.80E+01

2.

Average release rate for period

µCi/sec 4.55E-3 6.71E-3 3.92E-3 2.26E-2

3.

Percent of ODCM limit (2) 3.26E-3 4.85E-3 2.87E-3 1.65E-2 E.

Carbon-14

1.

Total release Ci ND ND ND ND

2.

Percent of ODCM limit (1)

NA NA NA NA ND = Not Detected NA = Not Applicable (1)

There is no ODCM Control for Iodines, C-14 and Fission and Activation Gases. All spent fuel is in casks on the ISFSI pads.

(2)

ODCM Control 3.3.3 for dose from Tritium and radionuclides in particulate form. The values in row D.3 are based upon the total particulate and Tritium activity in each quarter.

BVY 24-018 / Enclosure / Page 10 of 53

Continuous Mode Quarter Nuclides Released Units 1

2 3

4

1. Fission Gases Krypton-85 Ci ND ND ND ND Unidentified Ci ND ND ND ND Total for Period Ci ND ND ND ND
2. Iodines Ci ND ND ND ND
3. Particulates Strontium-90 Ci ND ND ND ND Cesium-134 Ci ND ND ND ND Cesium-137 Ci ND ND ND ND Manganese-54 Ci ND ND ND ND Cobalt-57 Ci ND ND ND ND Cobalt-60 Ci ND ND ND ND Zinc-65 Ci ND ND ND ND Total for Period Ci ND ND ND ND ND Not Detected at the plant stack (The Plant Stack was no longer in service as of the last week in the first quarter of 2021.)

BVY 24-018 / Enclosure / Page 11 of 53

Table 1B - Gaseous Effluents -Elevated Releases (Continued)

Batch Mode Quarter Nuclides Released Units 1

2 3

4

1. Fission Gases Krypton-85 Ci Unidentified Ci Total for Period Ci (1)

(1)

(1)

(1)

2. Iodines Ci
3. Particulates Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Manganese-54 Ci Cobalt-57 Ci Cobalt-60 Ci Zinc-65 Ci Total for Period Ci (1)

(1)

(1)

(1)

(1)

There were no batch mode gaseous releases for this reporting period. (The Plant Stack was no longer in service as of the last week in the first quarter of 2021.)

BVY 24-018 / Enclosure / Page 12 of 53

Continuous Mode Quarter Nuclides Released Units 1

2 3

4

1. Fission Gases Krypton-85 Ci Unidentified Ci Total for Period Ci (1)

(1)

(1)

(1)

2. Iodines Ci (1)
3. Particulates Strontium-90 Ci (1)

Cesium-134 Ci (1)

Cesium-137 Ci 4.13E-4 2.12E-3 1.42E-4 3.11E-5 Manganese-54 Ci (1)

Cobalt-57 Ci (1)

Cobalt-60 Ci 1.02E-3 9.45E-3 4.99E-4 5.02E-3 Zinc-65 Ci (1)

Total for Period Ci 1.44E-3 1.16E-2 6.41E-4 5.05E-3 (1) No releases of this type.

BVY 24-018 / Enclosure / Page 13 of 53

(Continued)

Batch Mode Quarter Nuclides Released Units 1

2 3

4

1. Fission Gases Krypton-85 Ci Unidentified Ci Total for Period Ci (1)

(1)

(1)

(1)

2. Iodines Ci
3. Particulates Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Manganese-54 Ci Cobalt-57 Ci Cobalt-60 Ci Zinc-65 Ci Total for Period Ci (1)

(1)

(1)

(1)

(1)

There were no batch ground level gaseous releases for this reporting period.

BVY 24-018 / Enclosure / Page 14 of 53

Quarter Nuclides Released Units 1

2 3

4

1. Fission Gases Krypton-85 Ci Unidentified Ci Total for Period Ci (1)

(1)

(1)

(1)

2. Iodines Ci
3. Particulates Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Manganese-54 Ci Cobalt-57 Ci Cobalt-60 Ci Zinc-65 Ci Total for Period Ci (1)

(1)

(1)

(1)

(1)

There were no non-routine gaseous releases for this reporting period.

BVY 24-018 / Enclosure / Page 15 of 53

There were continuous non-routine (groundwater flow to the Connecticut River) liquid releases during this reporting period. The data in this table is based upon monitoring well data collected throughout 2023 and hydrological modeling of groundwater movement.

Nuclides Released Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %

A. Fission and Activation Products Total Release (not including tritium, gases, alpha)

Ci ND ND ND ND Average diluted concentration during period

µCi/ml ND ND ND ND Percent of applicable limit (2)

NA NA NA NA B. Tritium Total Release Ci 3.31E-03 3.21E-03 2.99E-03 2.69E-03 1.8E+01 Average diluted concentration during period

µCi/ml 1.79 E-06 1.82E-06 1.52E-06 1.20E-06 Percent of applicable limit (2) 4.55E-05 4.41E-05 4.10E-05 3.69E-05 C. Dissolved and Entrained Gases Total Release Ci ND ND ND ND Average diluted concentration during period

µCi/ml ND ND ND ND Percent of applicable limit (1)

NA NA NA NA D. Gross Alpha Radioactivity Total release Ci ND ND ND ND E. Volume of Waste Released (prior to dilution)

Liters (3)

(3)

(3)

(3)

NA F. Volume of Dilution Water Used During Period Liters 3.62E+06 3.62E+06 3.70E+06 3.70E+06 (4)

ND = Not Detected NA = Not Applicable (1) All spent fuel is in casks on the ISFSI pads. Release of Dissolved and Entrained Gases is not possible.

(2) The percent of limit is based on the ODCM Control 3.2.2 limiting dose (1.5 mrem/quarter to the total body) from liquid effluents and is related to the abnormal leakage of tritiated plant water into the underground environment.

(3) Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated groundwater to the Connecticut River is based on site boundary monitoring well data collected during 2023 and reported in Section B.

(4) Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.38 gpm (times the number of days per quarter) during 2023. An estimated total error is not applicable.

BVY 24-018 / Enclosure / Page 16 of 53

Continuous Mode Quarter Nuclides Released Units 1

2 3

4 Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Iodine-131 Ci Cobalt-58 Ci Cobalt-60 Ci Iron-59 Ci Zinc-65 Ci Manganese-54 Ci Chromium-51 Ci Zirconium-Niobium-95 Ci Molybdenum-99 Ci Technetium-99m Ci Barium-Lathanium-140 Ci Cerium-141 Ci Others-Ci Ci Unidentified Ci Total for period (above)

Ci (1)

(1)

(1)

(1)

Kr-85 Ci Xe-133 Ci (1)

There were no continuous routine releases in this reporting period, only continuous non-routine liquid releases. See Table 2A.

BVY 24-018 / Enclosure / Page 17 of 53

(Continued)

Batch Mode Quarter Nuclides Released Units 1

2 3

4 Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Iodine-131 Ci Cobalt-58 Ci Cobalt-60 Ci Iron-59 Ci Zinc-65 Ci Manganese-54 Ci Chromium-51 Ci Zirconium-Niobium-95 Ci Molybdenum-99 Ci Technetium-99m Ci Barium-Lathanium-140 Ci Cerium-141 Ci Others-Ci Ci Unidentified Ci Total for period (above)

Ci (1)

(1)

(1)

(1)

Kr-85 Ci Xe-133 Ci (1)

There were no batch routine releases in this reporting period, only continuous non-routine liquid releases. See Table 2A.

BVY 24-018 / Enclosure / Page 18 of 53

Shipped from VY for Burial Unit Quarters 1 & 2 Est. Total Error %

a.Spent resins, filter sludges, etc.

m3 4.88E+00

+/-25%

Ci 2.33E+01

+/-25%

b.Dry Compressible Waste, equipment, etc.

m3 6.12E+03

+/-25%

Ci 1.19E+01

+/-25%

c. Irradiated components, control rods, etc.

m3 0

+/-25%

Ci 0

+/-25%

d.Other m3 2.04E+03

+/-25%

Ci 4.37E-01

+/-25%

Shipped from Processor(s) for Burial Unit Quarters 1 & 2 Est. Total Error %

a.Spent resins, filter sludges, etc.

m3 0

N/A Ci 0

N/A b.Dry Compressible Waste, equipment, etc.

m3 0

N/A Ci 0

N/A

c. Irradiated components, control rods, etc.

m3 0

N/A Ci 0

N/A d.Other m3 0

N/A Ci 0

N/A

2.

Estimate of Major Nuclide Composition (By Type of Waste)

Spent resins, filter sludges Dry Compressible Waste, equipment, etc.

Irradiated components, control rods, etc.

Other Waste Nuclide Percent(1)

Nuclide Percent(1)

Nuclide Percent(1)

Nuclide Percent(1)

Fe-55 5.39 Fe-55 24.16 H-3 43.66 Co-60 84.29 Co-60 62.93 Co-60 36.32 Ni-63 9.06 Ni-63 3.77 Cs-137 5.94 Cs-137 8.58 Fe-55 11.26 Ni-63 2.76 (1)

Includes only those nuclides that are greater than 0.1% of the total activity

3.

Disposition of Solid Waste Shipments (1st & 2nd Quarters)

No. of Shipments From VY From Processor Mode To Processor To Burial 95 95 0

Rail 0

95 6

6 0

Truck 0

6 B.

Irradiated Fuel Shipments (Disposition): None C.

Additional Data (1st & 2nd Quarters)

Supplemental Information VY to Processor VY to Burial Processors to Burial Class of Solid Waste Shipped N/A A/B/C N/A Type of Containers Used N/A GDC/IP-1/Type B N/A Solidification Agent or Absorbent Used N/A None N/A GDC = General Design Container BVY 24-018 / Enclosure / Page 19 of 53

Shipped from VY for Burial Unit Quarters 3 & 4 Est. Total Error %

a.Spent resins, filter sludges, etc.

m3 0

+/-25%

Ci 0

+/-25%

b.Dry Compressible Waste, equipment, etc.

m3 7.04E+03

+/-25%

Ci 6.52E+00

+/-25%

c. Irradiated components, control rods, etc.

m3 0

+/-25%

Ci 0

+/-25%

d.Other m3 2.56E+03

+/-25%

Ci 1.88E-01

+/-25%

Shipped from Processor(s) for Burial Unit Quarters 3 & 4 Est. Total Error %

a.Spent resins, filter sludges, etc.

m3 0

N/A Ci 0

N/A b.Dry Compressible Waste, equipment, etc.

m3 0

N/A Ci 0

N/A

c. Irradiated components, control rods, etc.

m3 0

N/A Ci 0

N/A d.Other m3 0

N/A Ci 0

N/A A.

Estimate of Major Nuclide Composition (By Type of Waste)

Spent resins, filter sludges Dry Compressible Waste, equipment, etc.

Irradiated components, control rods, etc.

Other Waste Nuclide Percent(1)

Nuclide Percent(1)

Nuclide Percent(1)

Nuclide Percent(1)

Fe-55 24.15 H-3 71.46 Co-60 62.93 Co-60 22.64 Ni-63 3.77 Cs-137 4.66 Cs-137 8.58 Ni-63 1.23 (2)

Includes only those nuclides that are greater than 0.1% of the total activity B.

Disposition of Solid Waste Shipments (3rd & 4th Quarters)

No. of Shipments From VY From Processor Mode To Processor To Burial 129 129 N/A Rail N/A 129 1

1 N/A Truck N/A 1

A.

Irradiated Fuel Shipments (Disposition): None B.

Additional Data (1st & 2nd Quarters)

Supplemental Information VY to Processor VY to Burial Processors to Burial Class of Solid Waste Shipped N/A A/B/C N/A Type of Containers Used N/A GDC/IP-1 N/A Solidification Agent or Absorbent Used N/A None N/A GDC = General Design Container BVY 24-018 / Enclosure / Page 20 of 53

(10CFR50, Appendix I)

Dose (mrem)

Source 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Liquid Effluents Total Body Dose 6.82E-07 6.61E-07 6.15E-07 5.53E-07 2.51E-06 Percent of Limit (1.5 mrem) 4.55E-05 4.41E-05 4.10E-05 3.69E-05 1.67E-04 Footnotes (a)

(a)

(a)

(a)

Organ Dose 6.82E-07 6.61E-07 6.15E-07 5.53E-07 2.51E-06 Percent of Limit (5 mrem) 1.36E-05 1.32E-05 1.23E-05 1.11E-05 5.02E-05 Footnotes (a)

(a)

(a)

(a)

Airborne Effluents Iodines, H-3, C-14 and Particulates 2.04E-02 1.56E-01 8.94E-03 6.42E-02 2.49E-01 Percent of Limit (7.5 mrem) 2.71E-01 2.07E+00 1.19E-01 8.56E-01 3.32E+00 Footnotes (b)

(b)

(b)

(b)

Noble Gases Beta Air (mrad)

Footnotes (c)

(c)

(c)

(c)

Gamma Air (mrad)

Footnotes (c)

(c)

(c)

(c)

(a)

The critical age group/organ for the Maximum Exposed Individual (MEI) is the Adult/Total Body and all organs (except Bone) from the release of H-3 to groundwater.

(b)

These doses are based upon the maximum offsite X/Qs and D/Qs. The doses are the maximum organ dose when the Vegetable, Meat, Cow Milk, and Inhalation pathways are summed.

(c)

There were no noble gas releases in this quarter.

BVY 24-018 / Enclosure / Page 21 of 53

(40 CFR 190)

Pathway Total Body (mrem)

Maximum Organ (mrem)

Thyroid (mrem)

Direct External (a) (b) 6.028 6.028 6.028 Liquids (c) 3.16E-06 3.16E-06 3.16E-06 Gases (c) 1.81E00 1.81E00 1.81E00 Annual Total (d) 7.840 7.840 7.840 The location of the projected maximum individual doses from combined direct radiation plus liquid and gaseous effluents correspond to residences at the southwest boundary relative to the Turbine Hall.

(a)

No residential shielding credit or occupancy time fraction (i.e., occupancy is assumed to be 100%) is used. Expected direct external radiation doses would be reduced by approximately 54% with a realistic residential shielding credit and occupancy time (i.e., by using a 0.7 shielding factor from Regulatory Guide 1.109 (Reference 2) and an annual occupancy time of 6760 hours0.0782 days <br />1.878 hours <br />0.0112 weeks <br />0.00257 months <br />).

(b) The direct dose reported here was calculated by summing the net monthly doses at TLD location DR-53A and represents the dose to the former nearest residence, which was located in the South sector at 385 meters from the stack prior to the vacancy of this residence in 2008 and the purchase of land by Vermont Yankee. Doses are driven by the casks on the ISFSI.

(c) Maximum dose to any organ over all age groups for each release.

(d) Annual dose limits contained in 40 CFR 190 are 25 mrem to the total body and any organ, and 75 mrem to the thyroid for any real member of the public.

BVY 24-018 / Enclosure / Page 22 of 53

Sector Site Boundary (1)

(meters)

Nearest Resident (2)

(meters)

N 529 1400 NNE 468 1384 NE 448 1255 ENE 477 966 E

499 933 ESE 482 1915 SE 512 1963 SSE 555 2044 S

419 644 SSW 575 576 (804)

SW 505 505 (418)

WSW 418 451 W

402 628 WNW 528 1062 NW 917 2253 NNW 831 1738 (1)

Site boundary locations are taken from the Reactor Building column in Table 6.10.2 of the ODCM.

(2)

The location(s) given are based on information from the Vermont Yankee 20162023 Land Use Census and Table 7.1 of the ODCM and are relative to the Reactor Building. Gardens are assumed to be present at all resident locations.

BVY 24-018 / Enclosure / Page 23 of 53

Age Group Fish (kg/yr)

Potable Water (l/yr)

Veg.

(kg/yr)

Leafy Veg.

(kg/yr)

Milk (l/yr)

Meat (kg/yr)

Inhalation (m3/yr)

Adult 21 730 520 64 310 110 8,000 Teen 16 510 630 42 400 65 8,000 Child 6.9 510 520 26 330 41 3,700 Infant 0

330 0

0 330 0

1,400 Data from Regulatory Guide 1.109, Table E-5 (Reference 2).

BVY 24-018 / Enclosure / Page 24 of 53

Vegetables Cow Milk Goat Milk Meat Variable Stored Leafy Pasture Stored Pasture Stored Pasture Stored YV Agricultural Productivity (kg/m2) 2 2

0.70 2

0.70 2

0.70 2

P Soil Surface Density (kg/m2) 240 240 240 240 240 240 240 240 T

Transport Time to User (hrs) 48 48 48 48 480 480 TB Soil Exposure Time(a)(hrs) 131,400 8760 131,400 8760 131,400 8760 131,400 8760 131,400 8760 131,400 8760 131,400 8760 131,400 8760 TE Crop Exposure Time to Plume (hrs) 1,440 1,440 720 1,440 720 1,440 720 1,440 TH Holdup After Harvest (hrs) 1,440 24 0

2,160 0

2,160 0

2,160 QF Animals Daily Feed (kg/day) 50 50 6

6 50 50 FP Fraction of Year on Pasture (b)

(b)

(b)

FS Fraction Pasture Feed When on Pasture(c) 1 1

1 Note: Footnotes on following page.

BVY 24-018 / Enclosure / Page 25 of 53

(Continued)

Vegetables Cow Milk Goat Milk Meat Variable Stored Leafy Pasture Stored Pasture Stored Pasture Stored FG Fraction of Stored Vegetables Grown in Garden 0.76 FL Fraction of Leafy Vegetables Grown in Garden 1.0 FI Fraction Elemental Iodine = 0.5 H

Absolute Humidity = 5.6(d)

(a)

For Method II dose/dose rate analyses of identified radioactivity releases of less than one year, the soil exposure time for that release may be set at 8,760 hours0.0088 days <br />0.211 hours <br />0.00126 weeks <br />2.8918e-4 months <br /> (one year) for all pathways.

(b)

For Method II dose/dose rate analyses performed for releases occurring during the first or fourth calendar quarters, the fraction of time animals are assumed to be on pasture is zero (non-growing season). For the second and third calendar quarters, the fraction of time on pasture (FP) will be set at 1.0. FP may also be adjusted for specific farm locations if this information is so identified and reported as part of the land use census.

(c)

For Method II analyses, the fraction of pasture feed while on pasture may be set to less than 1.0 for specific farm locations if this information is so identified and reported as part of the land use census.

(d)

For all Method II analyses, an absolute humidity value equal to 5.6 (gm/m3) shall be used to reflect conditions in the Northeast

(

Reference:

Health Physics Journal, Volume 39 (August), 1980; Pages 318-320, Pergammon Press).

BVY 24-018 / Enclosure / Page 26 of 53

Variable Name (Units)

Potable Water Aquatic Food Stored Veg.

Leafy Veg.

Meat Cow Milk Mixing Ratio 5.94E-06 1.27E-03 5.94E-06 5.94E-06 5.94E-06 5.94E-06 Transit Time (hrs)*

12 24 0

0 0

0 Water Uptake**

(animal) (L/day) 50.0 60.0 Feed Uptake** (animal)

(kg/day) 50.0 50.0

BVY 24-018 / Enclosure / Page 27 of 53

Tables 5A-5G - Frequency Distribution Tables for Ground Level Releases Table 5A Five Year Aggregate 35-foot PASQUILL A Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

15 11 30 32 7

2 0

97 NNE 1

2 9

3 0

0 0

15 NE 0

5 10 0

0 0

0 15 ENE 0

5 11 1

0 0

0 17 E

0 12 41 11 0

0 0

64 ESE 1

7 36 32 1

0 0

77 SE 0

3 12 16 0

0 0

31 SSE 1

0 7

23 4

0 0

35 S

0 1

2 9

2 0

0 14 SSW 0

0 0

4 0

0 0

4 SW 0

1 2

4 0

0 0

7 WSW 0

4 2

3 0

0 0

9 W

0 1

3 2

5 0

0 11 WNW 0

0 0

1 6

1 1

9 NW 0

0 11 11 3

1 0

26 NNW 1

10 35 60 19 5

0 130 TOTALS 19 62 211 212 47 9

1 561 BVY 24-018 / Enclosure / Page 28 of 53

Five Year Aggregate 35-foot PASQUILL B Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

2 10 65 36 5

1 0

119 NNE 0

12 15 9

0 0

0 36 NE 0

7 23 0

0 0

0 30 ENE 0

7 22 0

0 0

0 29 E

1 9

56 7

0 0

0 73 ESE 1

5 65 28 1

0 0

100 SE 0

2 39 22 0

0 0

63 SSE 0

4 31 65 8

1 0

109 S

0 3

15 29 11 1

0 59 SSW 0

0 6

4 0

0 0

10 SW 0

0 1

3 0

0 0

4 WSW 0

0 2

3 0

0 0

5 W

0 0

5 15 14 3

0 37 WNW 0

3 6

12 10 0

0 31 NW 0

2 17 18 14 7

0 58 NNW 1

5 64 72 45 6

0 193 TOTALS 5

69 432 323 108 19 0

956 BVY 24-018 / Enclosure / Page 29 of 53

Five Year Aggregate 35-foot PASQUILL C Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

2 19 103 68 6

0 0

198 NNE 1

31 31 13 0

0 0

76 NE 0

19 23 2

0 0

0 44 ENE 0

22 56 2

0 0

0 80 E

0 28 111 2

0 0

0 141 ESE 6

25 128 25 1

0 0

185 SE 0

14 94 21 0

0 0

129 SSE 0

6 74 99 11 0

0 190 S

0 2

30 63 8

0 0

103 SSW 0

5 12 9

1 0

0 27 SW 0

5 8

7 0

0 0

20 WSW 0

3 8

10 0

0 0

21 W

1 1

5 37 22 1

0 67 WNW 0

4 14 38 33 2

1 92 NW 1

11 63 53 44 4

0 176 NNW 0

9 123 109 49 6

1 297 TOTALS 11 204 883 558 175 13 2

1846 BVY 24-018 / Enclosure / Page 30 of 53

Five Year Aggregate 35-foot PASQUILL D Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

33 418 666 514 107 3

0 1741 NNE 21 244 203 58 2

0 0

528 NE 21 232 99 14 1

0 0

367 ENE 31 243 111 2

0 0

0 387 E

51 288 240 24 0

0 0

603 ESE 96 303 474 89 2

0 0

964 SE 102 349 901 101 7

0 0

1460 SSE 79 358 1167 583 48 3

0 2238 S

31 282 493 435 96 3

0 1340 SSW 5

206 177 92 6

0 0

486 SW 27 167 144 94 2

0 0

434 WSW 7

133 205 125 6

0 0

476 W

6 183 412 788 277 13 0

1679 WNW 3

235 370 908 471 42 1

2030 NW 10 400 895 713 359 39 2

2418 NNW 33 521 1440 1181 385 52 1

3613 TOTALS 556 4562 7997 5721 1769 155 4

20764 BVY 24-018 / Enclosure / Page 31 of 53

Five Year Aggregate 35-foot PASQUILL E Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

51 197 161 43 15 0

0 467 NNE 19 111 23 4

0 0

0 157 NE 14 89 9

1 1

0 0

114 ENE 14 71 7

0 0

0 0

92 E

13 91 36 1

0 0

0 141 ESE 25 156 74 7

0 0

0 262 SE 71 216 277 15 0

0 0

579 SSE 77 346 428 100 8

1 0

960 S

46 529 278 125 32 3

0 1013 SSW 34 676 101 17 2

0 0

830 SW 38 912 98 12 1

0 0

1061 WSW 19 827 214 13 0

1 0

1074 W

19 797 342 150 22 2

0 1332 WNW 21 640 396 144 36 0

0 1237 NW 21 601 577 148 29 1

0 1377 NNW 27 407 711 239 49 3

1 1437 TOTALS 509 6666 3732 1019 195 11 1

12133 BVY 24-018 / Enclosure / Page 32 of 53

Five Year Aggregate 35-foot PASQUILL F Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

8 78 12 0

0 0

0 98 NNE 7

31 3

0 0

0 0

41 NE 5

25 0

0 0

0 0

30 ENE 5

27 1

0 0

0 0

33 E

6 27 5

0 0

0 0

38 ESE 14 26 7

0 0

0 0

47 SE 17 75 13 0

0 0

0 105 SSE 19 136 39 1

1 0

0 196 S

30 344 59 1

0 0

0 434 SSW 50 501 56 0

0 0

0 607 SW 36 1061 68 0

0 0

0 1165 WSW 29 990 47 1

0 0

0 1067 W

11 677 78 1

0 0

0 767 WNW 12 349 69 2

0 0

0 432 NW 13 198 84 2

0 1

0 298 NNW 23 94 70 6

0 0

0 193 TOTALS 285 4639 611 14 1

1 0

5551 BVY 24-018 / Enclosure / Page 33 of 53

Five Year Aggregate 35-foot PASQUILL G Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

7 36 4

0 0

1 0

48 NNE 11 18 1

0 0

0 0

30 NE 4

16 0

0 0

0 0

20 ENE 1

10 0

0 0

0 0

11 E

6 22 0

0 0

0 0

28 ESE 10 22 5

0 0

0 0

37 SE 10 27 2

0 0

0 0

39 SSE 10 52 6

0 0

0 0

68 S

22 96 12 0

0 0

0 130 SSW 21 133 15 0

0 0

0 169 SW 7

198 28 0

0 0

0 233 WSW 8

205 8

0 0

0 0

221 W

4 140 17 1

0 0

0 162 WNW 7

90 15 0

0 0

0 112 NW 6

57 26 2

0 0

0 91 NNW 5

38 25 3

0 0

0 71 TOTALS 139 1160 164 6

0 1

0 1470 BVY 24-018 / Enclosure / Page 34 of 53

Tables 6A-6G - Frequency Distribution Tables for Elevated Releases Table 6A Five Year Aggregate 297-foot PASQUILL A Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

11 1

1 6

0 0

0 19 NNE 1

5 1

1 0

0 0

8 NE 0

1 1

1 0

0 0

3 ENE 0

1 2

0 0

0 0

3 E

0 1

0 0

0 0

0 1

ESE 0

3 2

3 1

0 0

9 SE 0

2 5

1 0

0 0

8 SSE 0

4 4

1 2

0 0

11 S

0 1

2 0

0 0

0 3

SSW 0

0 0

0 0

0 0

0 SW 0

0 0

0 0

0 0

0 WSW 0

0 0

1 0

0 0

1 W

0 1

0 0

2 0

0 3

WNW 0

0 2

0 0

0 0

2 NW 0

1 0

3 0

0 0

4 NNW 1

2 3

3 3

0 0

12 TOTALS 13 23 23 20 8

0 0

87 BVY 24-018 / Enclosure / Page 35 of 53

Five Year Aggregate 297-foot PASQUILL B Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

0 1

8 14 2

0 0

25 NNE 0

0 2

5 2

0 0

9 NE 0

1 1

6 0

0 0

8 ENE 0

0 2

3 0

0 0

5 E

0 1

1 3

1 0

0 6

ESE 1

4 13 26 4

0 0

48 SE 0

3 6

5 3

0 0

17 SSE 0

1 1

3 2

0 0

7 S

0 0

0 0

5 0

0 5

SSW 0

0 0

0 0

0 0

0 SW 0

0 0

0 0

0 0

0 WSW 0

0 0

1 1

0 0

2 W

0 0

0 3

1 1

0 5

WNW 0

0 3

0 2

2 3

10 NW 0

1 1

2 2

0 0

6 NNW 0

3 9

24 18 9

4 67 TOTALS 1

15 47 95 43 12 7

220 BVY 24-018 / Enclosure / Page 36 of 53

Five Year Aggregate 297-foot PASQUILL C Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

0 6

25 36 26 1

0 94 NNE 0

2 11 16 4

0 0

33 NE 0

2 7

7 2

0 0

18 ENE 0

3 14 8

0 0

0 25 E

0 4

16 9

1 0

0 30 ESE 0

7 51 47 3

0 0

108 SE 0

9 21 31 7

1 0

69 SSE 0

4 2

38 13 0

0 57 S

1 1

3 9

14 7

2 37 SSW 0

0 0

0 0

1 0

1 SW 0

0 1

4 0

0 0

5 WSW 0

0 1

2 3

0 0

6 W

0 0

0 5

3 9

1 18 WNW 0

0 2

7 7

8 0

24 NW 1

1 10 11 15 8

2 48 NNW 0

3 31 71 62 47 11 225 TOTALS 2

42 195 301 160 82 16 798 BVY 24-018 / Enclosure / Page 37 of 53

Five Year Aggregate 297-foot PASQUILL D Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

18 269 442 565 426 131 10 1861 NNE 3

182 145 127 55 4

1 517 NE 2

191 125 62 21 1

2 404 ENE 2

186 131 32 5

0 0

356 E

8 238 251 66 18 3

0 584 ESE 7

271 505 192 47 3

0 1025 SE 17 355 878 458 57 10 1

1776 SSE 10 243 811 1092 206 24 3

2389 S

13 102 395 1047 628 136 18 2339 SSW 5

72 124 220 71 8

1 501 SW 7

43 93 171 57 1

0 372 WSW 11 50 73 216 92 7

2 451 W

16 53 101 623 695 175 12 1675 WNW 3

82 138 689 901 285 28 2126 NW 2

173 344 430 564 229 52 1794 NNW 54 358 1172 1527 1240 512 153 5016 TOTALS 178 2868 5728 7517 5083 1529 283 23186 BVY 24-018 / Enclosure / Page 38 of 53

Five Year Aggregate 297-foot PASQUILL E Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

27 524 467 222 46 7

0 1293 NNE 8

354 66 27 5

0 0

460 NE 9

294 41 2

0 0

1 347 ENE 5

282 33 1

0 2

0 323 E

9 397 70 8

0 0

0 484 ESE 15 457 226 27 3

0 0

728 SE 25 474 747 171 6

1 0

1424 SSE 10 277 718 372 30 4

2 1413 S

6 160 281 306 144 23 3

923 SSW 2

90 118 114 40 8

0 372 SW 3

61 87 63 16 0

0 230 WSW 2

61 111 109 20 2

0 305 W

4 57 132 299 186 9

1 688 WNW 4

97 146 284 108 12 1

652 NW 1

206 361 258 83 13 1

923 NNW 21 441 1536 944 305 58 10 3315 TOTALS 151 4232 5140 3207 992 139 19 13880 BVY 24-018 / Enclosure / Page 39 of 53

Five Year Aggregate 297-foot PASQUILL F Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

9 217 176 19 6

0 0

427 NNE 2

161 24 3

0 0

0 190 NE 2

130 6

0 0

0 0

138 ENE 3

115 16 2

0 0

0 136 E

7 165 42 0

0 0

0 214 ESE 5

140 125 14 0

0 0

284 SE 8

188 343 81 0

0 0

620 SSE 5

149 296 79 0

1 0

530 S

2 76 172 51 8

0 0

309 SSW 3

63 60 29 4

0 0

159 SW 1

52 73 19 2

0 0

147 WSW 0

40 67 20 1

0 0

128 W

1 44 81 70 7

0 0

203 WNW 2

66 91 64 3

0 0

226 NW 2

115 154 40 4

0 0

315 NNW 3

167 429 184 9

0 0

792 TOTALS 55 1888 2155 675 44 1

0 4818 BVY 24-018 / Enclosure / Page 40 of 53

Five Year Aggregate 297-foot PASQUILL G Class 1 Calms Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Wind mph 0.95 3

7 12 18 24

>24 TOTAL N

0 18 19 3

1 0

0 41 NNE 0

6 2

0 0

0 0

8 NE 0

10 3

0 0

0 0

13 ENE 0

9 2

0 0

0 0

11 E

1 9

3 0

0 0

0 13 ESE 0

12 7

2 0

0 0

21 SE 0

19 48 19 0

0 0

86 SSE 0

19 50 18 0

0 0

87 S

1 14 39 14 4

1 0

73 SSW 0

8 19 12 2

0 0

41 SW 0

11 22 17 0

0 0

50 WSW 0

15 29 15 0

0 0

59 W

0 8

32 26 2

0 0

68 WNW 0

11 24 25 3

0 0

63 NW 1

20 23 20 0

0 0

64 NNW 0

21 37 19 0

0 0

77 TOTALS 3

210 359 190 12 1

0 775 BVY 24-018 / Enclosure / Page 41 of 53

1.

MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.

Tritium ODCM Table 4.3.l requires that a continuous sample of Reactor Building ventilation effluents be collected for H-3 and analyzed monthly. The error involved in this sample is approximately +/-18 percent. This sampling was initiated at the reactor building exhaust in the second quarter of 2021 when the stack was abandoned prior to demolition. Three additional effluent points were created in the reactor building during 2023. Two on the 252 level and one on the 345 level. Tritium effluent from these points is calculated based on the RB H3 level, the rate of flow and duration of release.

Particulates ODCM Table 4.3.l requires that a continuous sample of Reactor Building ventilation effluents be collected and analyzed weekly for principal gamma emitters. The error involved in this sample is approximately +/-18 percent. This sampling was initiated at the reactor building exhaust in the second quarter of 2021 when the stack was abandoned prior to demolition. Three additional effluent points were created in the reactor building during 2023. Two on the 252 level and one on the 345 level.

Particulate effluent from these points is calculated based on the effluent stream sampling, the rate of flow and duration of release.

2.

BATCH RELEASES There were no routine liquid or gaseous batch releases during the reporting period.

3.

ABNORMAL RELEASES

a.

Liquid VY had installed 32 groundwater wells to monitor the 2010 leak event or to monitor additional at-risk structures, systems or components (SSCs) that could cause a release of licensed material to the groundwater. One well (GZ-08) has been dry since installation and no samples were collected from it in 2023. A second well, GZ-24 was compromised by excavation activity in 2014 and is no longer able to be sampled. GZ-05 was inadvertently destroyed during plant demolition activities in 2023. Samples are no longer attainable. Due to the current condition of the facility a groundwater expert panel was convened to evaluate the status of the groundwater sampling wells. Based upon the plant configuration (removal of piping/components) and status of the plume it was prudent to reduce the number of active wells in the program. A summary of the sample results for the remaining wells are presented in Table A-1. There are only two (2) wells that had detectable activity (>MDC) in 2023 and all these sample results are well below the EPA limit of 20,000 pCi/L for drinking water. None of the wells in this program supply drinking water, and no drinking water wells on site or adjacent to VY have shown tritium at detectable levels in regular surveillance samples.

b.

Gaseous BVY 24-018 / Enclosure / Page 42 of 53

There were no non-routine gaseous releases (measured) during the reporting period.

BVY 24-018 / Enclosure / Page 43 of 53

Groundwater well Sampled Number of analyses performed Mean Concentration1 Concentration Range1 Min Max GZ-01 1

< 594

< 594

< 594 GZ-03 1

< 606

< 606

< 606 GZ-04 1

< 608

< 608

< 608 GZ-13 1

< 603

< 603

< 603 GZ-13D 2

< 602

< 597

< 606 GZ-14 2

< 599

< 596

< 602 GZ-14D 4

1840 1220 2300 GZ-18 1

< 610

< 610

< 610 GZ-18D 1

< 599

< 599

< 599 GZ-19 1

< 595

< 595

< 595 GZ-19D 1

< 600

< 600

< 600 GZ-22D 12 1320 975 1820 GZ-23 2

< 606

< 599

< 612 GZ-25 1

< 604

< 604

< 604 GZ-26 1

< 598

< 598

< 598 GZ-27 1

< 592

< 592

< 592 Notes:

1. All concentrations are in units of pCi/L
2. Required LLD for tritium = 2,000 pCi/L
3. < denotes minimum detectable value for the analytical period
4. Bold values denote positive results (greater than minimum detectable values)

BVY 24-018 / Enclosure / Page 44 of 53

Requirement With the quantity of radioactive material in any outside tank exceeding the limit of Section 4 of the Defueled Safety Analysis Report, describe the events leading to this condition in the next Radioactive Effluent Release Report.

Response

The limits for any outside tank were not exceeded during this reporting period.

BVY 24-018 / Enclosure / Page 45 of 53

The requirements for radioactive liquid effluent monitoring instrumentation channels in ODCM Table 3.1.1 were removed in ODCM Revision 40.

BVY 24-018 / Enclosure / Page 46 of 53

Requirement Radioactive gaseous effluent monitoring instrumentation channels are required to be functional in accordance with ODCM Table 3.1.2. If a non-functional, gaseous effluent monitoring instrumentation is not returned to functional status within 30 days pursuant to Note 5 of Table 3.1.2, an explanation in the next annual Radioactive Effluent Release Report of the reason(s) for the delay in correcting the inoperability is required per ODCM Section 10.1. The plant stack was removed from service in March 2021. The release path was relocated to reactor building exhaust path in the overhead of the 280 foot level.

Response

ODCM Required RBHVAC #2 AP Sample Pump Found in OFF Position. CR 2023 - 124.

RB HVAC tritium sampling system was found out of position.

Sampling apparatus out of service. CR-2023 - 165 BVY 24-018 / Enclosure / Page 47 of 53

This Appendix is no longer required by the ODCM as of Revision 40. This Appendix is retained as a placeholder to allow this report to be consistent with previous reports.

BVY 24-018 / Enclosure / Page 48 of 53

Requirement A land use census is conducted in accordance with ODCM Control 3/4.5.2. With a land use census identifying a location(s) that yields at least a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3.3, the new location(s) must be identified in the next Annual Radioactive Effluent Release Report.

Response

The Land Use Census was completed during the third quarter of 2023. No locations were identified which yielded a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3.3. See Table 4C for a listing of nearest residents in the site area as determined in the 2023 Land Use Census.

BVY 24-018 / Enclosure / Page 49 of 53

Requirement ODCM Section 10.1 requires that licensee-initiated changes to the Process Control Program (PCP) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made.

Response

There were no changes made to the Process Control Program during this reporting period.

BVY 24-018 / Enclosure / Page 50 of 53

Requirement ODCM Section 10.1 requires that licensee-initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s).

Response

No revisions made to the Offsite Dose Calculation Manual (ODCM) during 2023. Current revision is 42.

BVY 24-018 / Enclosure / Page 51 of 53

Requirement ODCM Section 10.5 requires that licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Independent Safety Review Committee.

Response

There were no licensee-initiated major changes to the radioactive waste systems during this reporting period.

BVY 24-018 / Enclosure / Page 52 of 53

Requirement The Off-Site Dose Calculation Manual included Appendices B, F and I which required that the dose impact due to on-site disposal of septic waste, cooling tower silt, and sand/soil type materials during the reporting year and from previous years be reported to the Nuclear Regulatory Commission in the Annual Radioactive Effluent Release Report if disposals occur during the reporting year.

In 2021 (BVY 21-025) Vermont Yankee notified the NRC that there will no longer be any alternate disposal material on site.

The subject letter notified the NRC that the referenced approvals for alternate disposal of material on site will no longer be utilized/authorized and the subject documents will cease to be incorporated into the ODCM. As such, this appendix will no longer be included in future submittals.

Response

There was no on-site disposal spreading during 2023.

BVY 24-018 / Enclosure / Page 53 of 53

BVY 24-018 Docket No. 50-271 Enclosure Vermont Yankee Nuclear Power Station Annual Radiological Effluent Release Report for 2023 (53 pages excluding this cover sheet)

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