Text

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

NorthStar Nuclear Decommissioning Co., LLC Vermont Yankee Nuclear Power Station

~ 320 Governor Hunt Rd.

Vernon, VT 05354 802-451-5354 NorthStar

Corey R. Daniels ISFSI Senior Manager

10 CFR 50.36a

BVY 24-018

May 5, 2023

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

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: R egional 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 2 of 53

VERMONT YANKEE ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR2023

Reviewed By: _ A._..i...:.__- ii_i :a_~- ----/ _----'--I __ /} Si+--fr._/4_c>l~--'------

Andy Miller, ~ t Dat<!

Approved By:---"'----L-IC.-~-~--------/,<, 0, Scott Dorval, RP Manager, ISFSI Date / 7-o ? c/"

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 - LIQU ID HOLDUP TANKS.......................................................................................... 44 APPENDIX C - RADIOACTIVE L IQU ID 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 CALCULATIONMANUAL.......................................................... 50 APPENDIX I - RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS................................................................................................................................................. 51 APPENDIX J - ON-S IT E DISPOSAL OF SEPTIC/SILT/SOIL WASTE.............................................. 52 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

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.

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 releaseassessment 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.

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 th e 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 Ra dionuclides 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.

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 foremployees, their families, and guests. As such, therewas no associated dose impactto members of the public due to any recreational activities on -site.

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.

Units 1st 2nd 3rd 4th Est. Total Quarter Quarter Quarter Quarter 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 ISFS I 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 totalparticulate and Tritiumactivity in each quarter.

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.)

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.)

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 Ci 1.44E-3 1.16E-2 6.41E-4 5.05E-3 for Period

(1) No releases of this type.

(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.

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.

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

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

Average diluted concentration during µCi/ml ND ND ND ND period Percent of applicable limit (2) % NA NA NA NA B. Tritium Total Release Ci 3.31E-03 3.21E-03 2.99 E-03 2.69 E-03 1.8E+01 Average diluted concentration during µCi/ml 1.79 E-06 1.82E-06 1.52E-06 1.20E-06 period Percent of applicable limit (2) % 4.55E-05 4.41E-05 4.10E-05 3.69 E-05 C. Dissolved and Entrained Gases Total Release Ci ND ND ND ND Average diluted concentration during µCi/ml ND ND ND ND period 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 Liters (3) (3) (3) (3) NA to dilution)

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

During Period

ND = Not Detected NA = Not Applicable (1) All spent fuel is in casks on the ISFS I 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.

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. SeeTable2A.

(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.

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)

Dry Compressible Waste, equipment, Irradiated components, control rods, Spent resins, filter sludges etc. 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-N/A 1/Type B Solidification Agent or Absorbent Used N/A None N/A

GDC = General Design Container 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)

Dry Compressible Waste, equipment, Irradiated components, control rods, Spent resins, filter sludges etc. 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 (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 (ME I) 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.

(40 CFR 190)

Pathway Total Body Maximum Organ Thyroid (mrem) (mrem) (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 1.878 hours 0.0112 weeks 0.00257 months ).

(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.

Site Boundary (1) Nearest Resident (2)

Sector (meters) (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 20162023Land 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.

Age Fish Potable Veg. Leafy Milk Meat Inhalation Group (kg/yr) Water (kg/yr) Veg. (l/yr) (kg/yr) (m3/yr)

(l/yr) (kg/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 In fant 0 330 0 0 330 0 1,400

Datafrom Regulatory Guide 1.109, Table E-5 (Reference 2).

Vegetables Cow Milk Goat Milk Meat

Variable Stored Leafy Pasture Stored Pasture Stored Pasture Stored YV Agricultural Productivity 2 2 0.70 2 0.70 2 0.70 2 (kg/m2)

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) 131,400 131,400 131,400 131,400 131,400 131,400 131,400 8760 131,400 8760 8760 8760 8760 8760 8760 8760 TE Crop Exposure Time to Plume 1,440 1,440 720 1,440 720 1,440 720 1,440 (hrs)

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(c) Pasture Feed When on -- -- 1 -- 1 -- 1 --

Pasture

Note: Footnotes on following page.

(Continued)

Vegetables Cow Milk Goat Milk Meat

Variable Stored Leafy Pasture Stored Pasture Stored Pasture Stored

FG Fraction of Stored VegetablesGrown in Garden 0.76 -- -- -- -- -- -- --

FL Fraction of Leafy VegetablesGrown 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 0.211 hours 0.00126 weeks 2.8918e-4 months (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).

Variable Name Potable Water Aquatic Food Stored Veg. Leafy Veg. Meat Cow Milk (Units)

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

Values are from Regulatory Guide 1.109, Table E -15 (Reference 2)

- Values are from Regulatory Guide 1.109, Table E-3 (Reference 2)

Tables 5A-5G - Frequency Distribution Tables for Ground Level Releases

Table 5A

Five Year Aggregate 35-foot PASQUILL A