ML21158A166
| ML21158A166 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 05/05/2021 |
| From: | Daniels C NorthStar Nuclear Decommissioning Company |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BVY.21-014 | |
| Download: ML21158A166 (55) | |
Text
~ -
Northstar
~VY.21-014 May 5, 2021 A TIN: Document Control Desk, U.S. _Nuclear Regulatory Commis_sion Washington, DC 20555-0001 Northstar Nuclear Decommissioning Co., LLC Vermont Yankee Nudear Power Station 320 Governor Hunt Rd.
Vernon, VT 05354 802-451-5354 Corey R. Daniela ISFSI Senior Manager 10 CFR 50.36a
SUBJECT:
2020 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 Ya.nkee (VY) Off-site Dose Calculation Manual, please find enclosed a* copy *of the Annual Radiol~gical Effluent Release Report for 2020.
It is noted that there were no changes made to the ODCM during 2020.
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 Mas~achusetts Metropolitan District Cornmission (MDC). However, since the MDC is currently part of the Massachusetts Department of-Conservation and Recreation (DCR), this report is being provided to the DCR 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.
CRD/tbs
BVY 21-014 / Page 2 of 2
Enclosure:
Annual Radiological Effluent Release Report for 2020.
cc:
Regional Administrator, Region 1
- U.S. Nuclear Regulatory Con:imission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Ms. June Tierney, Commissioner Vennont Department of Public Service 112 State Street -* Drawer 20 Montpelier, Vennont 05602-2601 Massachusetts Dep~rtrnent-of Public Health.
Director, Radiation Control Program 529 Main Street, Suite 1 M2A Charlestown: MA 02129 Jim Montgomery, Commissioner Massachu*setts Department of Conservation and Recreation 251 Causeway Street Boston*, MA 02114
Enclosure Vermont Yankee Nuclear Power Station Annual Radiological Effluent Release Report for 2020 (52 pages excluding this cover sheet)
, Docket No. 50-271
BVY'21-014 / Endosure / Page 1 of 52 Vermont Yankee Nuclear Power Station*
Annual Radiological *Effluent Release Report
. January - December io20. *_
Northstar - V ennont Yankee.
Vermont Yankee Nuclear Power Station 320 Governor H~t Road Vernon, V~ont 05354 Docket No. 50-271 License No. i>PR-28 *
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VERMONT YANKEE ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR2020 Prepared by:~-=--=--fi_f._~
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Pete Hollenbeck, Radiation Safety & Control Services Date Reviewed by:_,._&,_---"'
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Norman Hassell,Chemistry~
Date
BVY 21-014 /Enclosure/ Page 3 of 52 Table of Contents
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 Doses from On-Site Disposal of Septic Waste, Cooling Tower Silt and Soil............................. 8 3.6 On-Site Recreational Activities.................................................................................................... 9 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 21-014 /Enclosure/ Page 4 of 52 List of Tables Table IA - Gaseous Eflluents -Summation of All Releases..................................................................... 10 Table lB - Gaseous Effluents -Elevated Releases.................................................................................... 11 Table 1 C - Gaseous Effluents Ground Level Releases............................................................................ 13 Table ID - 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 Distnbution Tables for Ground Level Releases............................................ 28 Tables 6A-6G - Frequency Distribution Tables for Elevated Releases.................................................... 35
BVY 21-014 /Enclosure/ Page 5 of 52
1.0 INTRODUCTION
Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste shipments for 2020, 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 effiuents released during 2020, to the maximumly exposed individual member of the public, in response to the ALARA objectives of 10 CPR Part 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 peri~ 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 2020.
Dose commitments resulting from the release of radioactive materials in liquids and gases during the reporting period were estimated in accordance with the plant's 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 3.6, 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 CPR Part 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 CPR Part 190.
All calculat~ dose estimates for members of the public at the site boundary or beyond for the 2020 annual reporting period are below the dose criteria of 10 CPR Part 50, Appendix I, and 40 CPR Part 190.
Appendices B through J indicate the status of reportable items per the requirements of ODCM Section 10.1.
BVY 21-014 / Endosure / Page 6 of 52 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 (BP A) Protective Actions Guide.
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 (&ctors.
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 or not 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 40 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 SA through 5G. The five-year aggregate joint frequency distribution tables for elevated releases are presented in Tables 6A through 6G.
fNY 21-014 /Enclosure/ Page 7 of 52 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 eflluents to a member of the public to those specified in 10 CFR Part 50, Appendix I. By implementing the requirements of 10 CFR Part 50, Appendix I, ODCM 3/4.2.2 assures that the release of radioactive material in liquid eflluents will be kept "as low as is reasonably achievable."
There were no continuous or batch routine liquid radioactive waste discharges during 2020.
Dose estimates of tritium-contaminated groundwater released from the site are based on Protected Area Boundary monitoring well data collected throughout 2020 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 Darcy's Law. Using a conservative estimate of groundwater flow through the affected1area toward the river on a quarterly basis, an estimate of the total potential tritium released from the site during each quarter of 2020 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 present~ 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 1 OCFR Part 20.1001 - 20.2402, Table 2, Column 2. The tritium concentrations at the point of discharge from the plant ranged from 0.07% to 0.13 % of the Table 2, Column 2 values.
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 plant stack in 2020.
3.3 Dose from Radionuclides in Particulate Form and Tridum 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 Part 50, Appendix I (7.5 mrem per quarter and 15 mrem per year). By implementing the requirements of 10 CFR Part 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 2020. There was no radioactively contaminated used oil burned in 2020.
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I BVY 21-014' / Enclosure / Page 8 of 52
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Continuous sampling of the plant stack for trithn;n, per ODCM Table 4.3.1, w~ performed by*
us~g silica gel cartridges in 2020. The cartridges were analyzed monthly. Based upon the stack flow rate_, and sample flow rates, th{l average release rate in µCi/sec and-total release in Ci for each quarter was calculated. The quantity of tritium released from the site by the plant stack in each quarter was then converted to dose by using the calculated dose conversion factors presented in ODCM Table 1.1; 12.
. The resulting quarterly doses from H-3 were combined with the particulate releases and are presented in Table 4A.
,f
' -Continuous, sampling ~f the plant stack for particulates, per ODCM Table 4.3. ~; was performed
-in 2020. These samples are analyzed weekly for principle gamma emitters. Cobalt-60 was identified on the plant stack particulate filters in the second, third and fourth quarters in 2020. Cesium-137 was also identified on the plant stack particulate filters in the first and fourth quarters iii 2020. Cobalt-60 was als~
identified during-a ground level release in the third quarter of 2020. The quantity of Cobalt 60 and Cs-1 r
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137 did not exceed any dose limits. The doses from Co-:.60 and Gs-137 were combined with H-3 and are presented in Table 4A.
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Whole Body.-Doses in Unrestricted Areas from Direct Radiation
. 1 As opposed to prior years before the permanent shu~ down wJien the 'majority of the dose in the 1 unrestricted area consistep of direc~ and skyslµne radiation from N-16 decay in the Turbine Building steam cycle during power, qperations, there*was no such source during 2020 due to the elimination _of its production and its short half-life.'
I The -other fixed sources-of direct and scatter radiation to the site boundary are the Independent
. Spent Fuel Storage Installation (ISFSI) and old turbine ro~rs and casings in the Turbine Storage Facility. The annual direct radiation dose at the site boundary is driven by the cask loading at the ISFSI.
All spent fuel has been transferred to thltwo ISFSI pads by Augus_t 2018. The method. to assess the direct radiation dose in unrestricted areas has-been agreed upon with the State of Vermont Site,
bo~dary TLDs are changed out monthly. The net'dose at the location ofTLD DR-53A has been chosen to assess direct radiation dose to unrestricted areas.
_ 1 Table 4B lists the combination of the direct radiation dose at ~e limiting site boundary location and !h,e maximum offsite dose from gaseous and liquid effluents for the PllfPOse of demonstrating compliance with the dose standar9-S contained in 40 CFR Part 190. For 2020, this arinual dose was below the 25 mreni total body and ~rgan limit, as 'well as the 75 mrem thyroid limit, of 40 CFR Part 190.
I 3.5 Doses from On-Site Disposal of Septic Waste, Cooling Tower Silt and Soil
~
ODCM Appendices B, F, and I require that all septic waste, cooling tower silt, and/sand/soiJ applied within the approved designated disposal areas* be controlled to ensure the dose to a.maximally exposed individual during the period of Vermont Yankee site control is limited to less than 1 mrem/year to the whole body and any organ. After the period associated wj.th Vermont Yankee operational control, the dose to.the inadvertent intruder is to be limited to 5 mrem/year. The projected dose from on-site disposals of septic waste, cooling tower silt, and sand/soil mixes is gi:ven in Appendix J of this report.,
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BVY 21-014 / ~closure / Page 9 of 52
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During 2020 there was no' ;eptic sludge spread on the southern' on-site disposal field.
3.6 On-Site Recreational Activities During 202Q, no access to the on-site boat launching ramp located north of the intake structure was penni~ed for employees, their families, and guests. As such, there was no associated dose impact to members 9f the public due to any recreational activities on-site.
, REFERENCES
')
I
- 1.
Off-Site Dose Calc~ation Manual (ODCM), Revision 40, Entergy Nuclear V erniont Yankee, LLC, dated October 23, 2018.
)
- 2.
- Regulatory Guide 1_.109, "Calculation of Annual Doses to Man from Routine Release of Reactor
- 3.
- 4.
- 5.
)
- 6.
Eflluents' for the Purpose' of Evaluating Compliance with 10 CPR Part 50, Appendix. I," U. S. -
- Nuclear Regulatory Co~ssion, Office of Stanciards Development, ~vision 1, October 1977.
- ~safety Guide 1.23, "Onsite !v,Ieteorological :erograms," U.S. Atomic Energy Commission, February 17, 1972.
- Regulatory Guide 1
.111, .Methods for-Estimating Atmosph~c Transport and Dispersion of Gaseous Efllµents in Routine Releases from Light-Water-Cooled Reactors," U.S. Nuclear
. Regulatory Cpmmission, Office of Standards Development, March* 1976..
Meteorology and Atomic Energy, 1968, Section 5-3.2.2, "Cloud Depletion," page 204, U.S.
Atomic-Energy Commission, July 1968.
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:
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BVY 21-014 /Enclosure/ Page 10 of 52 A.
- 1.
2.-
I 3..
B.
- 1.
- 2.
- 3.
C.
- 1.
'2.
l
- 4.
D.
- 1.
2:
- 3.
E.
ll.
- 2.
(1)
(2)
I Table lA - Gaseous Effluents -Summation* of All Releases Units ht 2nd 3rd 4th Est. Total Quuter Quarter Quarter Quarter Error,%
Fi'ssion and Activation Gases Total release Ci ND ND ND ND Average release rate for period, µCi/sec.
ND ND ND ND Percent of ODCM limit (1)
NA NA
, NA NA Iodines
~
I
,Total Iodine Ci I
ND ND ND ND A v~ge re~ease rate for period
µCi/sec ND ND ND ND Percent ofODCM limit (1)
NA NA NA NA I
Particulates Particulates with T-1/2>8 days Ci 3.13E-07 9.26E-07 9.33E-06 l.52E-06 l.80E+ol Average release rate for period
µCi/sec 3.98E-08 l.18E-07 l.17E-0b 1.92E-07 Percent of ODCM limit (2)
(2)
( (2)
(2)
(2)
Gross alpha radioactivity Ci ND ND ND ND Tritium Total release Ci 7.lOE-03 1.32E-02 3.94E-02 2.44E-02 l.80E+ol Average re~ease rate for.period
µCi/sec 9.03E-04 l.68E-03' 4.96E-03 3.07E-03
/
Percent of ODCM limit (2) l.24E-05 2.33E-05 6.35E-05, 4.29E-05 Carbon-14 Tot&l release' Ci ND ND ND ND I
Percent ofODCM limit (1)
NA NA NA NA ND = Not Detected' NA= Not Applicable I
(
There is no ODCM Control for Iodines, C-14 and Fission and Activation Gases) All sp~t fuel is in casks on the ISFSI pads.
ODCM Control 3.3.3. for dose from Tritium and radionuclides in particulate form. The values in row D.3 are based upon the ~tal particulate and Tritium activity in each quarter.
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BVY 21-014 / EndOSJJre / Page 11 of 52 I
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Table 11B - Gaseous Eflhients -ElevatecLReleases Continuous Mode Quarter Nuclides Released
,.Units
-1 2
3
- 1. Fission Gases I
Krypton-85 Ci ND ND ND Unidentified Ci ND ND ND Total (or Period Ci I
ND ND
,ND
~ Iodines Ci ND ND ND r
- 3. Particulates I
I Strontium-90 Ci ND ND ND Cesium-134 Ci' ND ND ND Cesium-137
,Ci 3.13E-07 ND ND' 1 Manganese-54 Ci(
NB ND
-ND Cobalt-57 Ci ND ND ND CoQalt-60 Ci ND 9.26E~07
- 1.25E-06
' Zinc-65 Ci ND ND ND I
Total for Period
- Ci 3.13E-07 9.26E-07 1.25E-06 ND Not Detected at the plant stack
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4 ND ND ND
, ND*
ND ND 2.44E-07 ND
-ND 1.28E-06
~
1.52E-06
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BVY 21-0141 Enclosure/ Page 12 of 52 Table lB - Gaseous Eflluents -Elevated Releases L
(Continued)
Batch Mode Quarter N uclides Released Units l
1 2
3 4
- 1. Fission Gases I
I
(
Ci r
Unidentified Ci
. Total for Period Ci (1)
(1)
(1)
(1)
- 2. Iodines Ci I
I
- 3. Particulates
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Strontium-90 Ci I
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 rele&Ses for this reporting period.
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BVY 21-014 / Enclosure I Page 13 of 52 Table 1 C - Gaseous Effluents Ground Level Releases
/
Continuous Mode r
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Quarter Nuclides Released Units 1
2 3
4
- 1. Fis~ion Gases Krypton-85 Ci
(
Unidentified Ci T6tal for Period ct*
(1)
(1)
(1)
(1)
- 2. Iodines Ci I
- 3. Particulates r
Strontium-90 Ci Cesium-134 Ci I
I Cesium-137 Ci Manganese-54 Ci I
Cobalt-57 Ci Cobalt-60 Ci 8.08E-06 Zinc-65 Ci Total for Period Ci (1)
_(l) 8.0SE-06 (1)
( 1) There were no routine ground level gaseous releases for this reporting period.
ffi/Y 21-014 /Enclosure/ Page 14 of 52
. Table 1 C - Gaseous Effluents Ground Level Releases (Continued)
Batch Mode l..
1 Quarter Nuclides Released Units 1
2
- 1. Fission Gases, Krypton-85 Ci Unidentified Ci 3
Total for Period Ci (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) There were no ground level gaseous releases for this reporting period.
(
4
- (1)
(1)
BVY 21-014 / Enclosure ttage 15 of 52 Table ID - Gaseous Effluents -Non-routine Releases C
r Quarter Nuclldes 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 r
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- 3. Particulates Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Manganese-54 Ci Cobalt-57,
Ci Coba).t-60 Ci Zinc-65 Ci Total for Period Ci (1)
(1)
(1)
(1)
(1) There were no non-routine gaseous releases for this reporting ~od._
BVY 21-014 / Endosure / Page ~6 of 52 -
' Table 2A - Liquid Eflluents - Summation of All Releases 1 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 2020 and hydrological modeling of groundwater movement.
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1st 2nd 3rd 4th li:st. Total Nuclides Released Units Quarter Quart~r Quarter Quarter
- Jj:rror, %
A. Fission and Activation Products Total Release (not including tritium, irases, alpha)
Ci ND ND ND1 ND I
Average diluted concentration during period
µCi/ml ND ND ND ND Percent of applicable limit (2) r NA NA NA
.NA B. Tritium Total Release
. Ci 4.79E-03 2.77E-03 2.96£-03 2.76E-03 l.8E+ol Average diluted concentration during t
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period I'. µCi/ml l.31E-06 7.56E-07 8.00E-07 7.46E-07 Percent of applicable limit (2) 6.58E-05 3.S0E-05 4.07E-05 3.79E-05
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C. Dissolved and Entrained Gases Total Release I
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 Radioa.,;..iyiu Total release Ci ND NJ)
ND ND I
E. Volume of Waste Released (prior Liters (3)
(3)
(3)
(3) -
NA to dilution)
F. Volume ofDilutiop Water Used Liters 3.66E+o6 3.66E+o6 3.70E+o6 3.70E+o6 (4)
Dorlru! Period 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 Conttol 3.2.2 limiting dose (1.5 mrem/quarter to the total body) from liquid eflluents and is related to the abnormal leakage oftritiated plant water into the underground environment. *
(3) Leakage of contaminated plant water to subsurface areas was stopped in F ~bruary ~W 10. The release of contaminated groundwater to the Connecticut River is based on site boundary monitoring well data collected during 2020 and reported in Section B.
1 (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 mnnber of days per quarterf during 2020. An estimated total error is not applicable.
Bvy 21-014 /Enclosure/ Page 17 of 52 Table 2B - Liquid Effluents - Routine Releases 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
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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 I
Unidentified Ci Total 'for period (above)
Ci (1)
(1)
(1)
(1)
~
(1) There were no continuous routine releases.in this reporting period, only continuous non-routine
, liquid releases. See Table 2A.
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8\\/Y 21-014 / Enclosure / Page 18 of 52 Table 2B - Liquid Eflluents - Routine Releases
)
(Continued)
Batch Mode Quarter N uclides 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
'1 Ci Zinc-65 Ci Manganese-54
' Ci Chromium-51 Ci Zirconium-Niobium-95 Ci r,
Molybdenum-99
. Ci Technetium-99m
. Ci Barium-Lathanium-140 Ci Cerium-141 Ci Others-I Ci Ci Unidentified Ci Total for period (above)
Ci (1)
(1)
(1)
(1)
Kr-85 Ci I
Xe-133 Ci
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(1) There were no batch routine releases in this reporting period, only continuous non-rou,tine liquid releases. See Table 2A.
BVY 21-014 I Enclosure I Page 19 of 52 Table 3 - Solid Waste and Irradiated Fuel Shipments A.
Solid Waste Shipped Off-Site for Burial or Disposal (not irradiated Fuel)
I.
Type of Waste Shipped from VY for Burial Unit Quarters I & 2 Est. Total E1rnr %
a.Spent resins, filter sludges etc.
ml l.04E+02
+/-25%
Ci 9.63E+o0
+/-25%
b.Drv Compressible Waste, eauipment, etc.
ml l.87E+o3
+/-25%
Ci 2.18E+ol
+/-25%
- c. irradiated components control rods, etc.
ml 3.00E+o0
+/-25%
Ci 9.24E+ol
+/-25%
ct.Other ml l.54E+o3
+/-25%
Ci l.45E-0 I
+/-25%
Shipped from Processor(s) for Burial Unit Quarters I & 2 Est. Total En-or%
a.Spent resins filter sludges etc.
ml 0
NIA Ci 0
NIA b.Drv Compressible Waste, eauipment, etc.
ml 0
NIA Ci 0
- c. Irradiated components, control rods, etc.
ml 0
NIA Ci 0
NIA ct.Other ml 0
NIA Ci 0
- 2.
Estimate of Major Nuclide Composition (By Type of Waste)
Spent resins, filter sludges Dry Compressible Waste, equipment, Irradiated components, control rods, Other Waste etc.
etc.
Nuclide Percent(I)
Nuclide Percent(!)
Nuclide Percent(!)
Nuclide Percent(!)
C-14 23.36 H-3 0.3 C-14 0.01 H-3 2.88 Fe-55 47.02 Mn-54 0.16 Fe-55 23.33 Fe-55 33.27 Co-60 25.15 Fe-55 25.75 Co-60 75.52 Co-60 55.72 Ni-63 2.9 Co-60 68.72 Ni-63 1.12 Ni-63 2.15 Zn-65 0.88 Ni-63 2.23 Cs-137 O.Q2 Zn-65 0.28 Cs-137 0.39 Cs-137 2.23 Pu-241 0.01 Cs-137 5.35 (I)
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 75 75 0
Rail 0
75 7
7 0
Truck 0
7 B.
lrrad1ated Fuel Shipments (D1spos1tion): None C.
Additional Data ( I" & 2nd Quarters)
Supplemental lnfonnation VY to Processor VY to Burial Processors to Buri a I Class of Solid Waste Shipped NIA A/BIC NIA Type of Containers Used NIA G DCllP-1 /IP-NIA 2ffvoe B Solidification Aeent or Absorbent Used NIA None NIA GDC = General Design Container
BVY 21 -0141 Enclosure I Page 20 of 52 Table 3 - Solid Waste and Irradiated Fuel Shipments (Continued)
A.
Solid Waste Shipped Off-Site for Burial or Disposal (not Irradiated Fuel)
I.
Type of Waste Shipped from VY for Butial Unit Quarters 3 & 4 Est. Total Error %
a.Spent resins, filter sludges, etc.
ml 9.34E+00
+/-25%
Ci
- 5. I0E+0 I
+/-25%
b.Drv Compressible Waste equipment, etc.
ml 3.12E+03
+/-25%
Ci 6.86E-0l
+/-25%
- c. Irradiated comoonents, control rods, etc.
ml 2.56E+o0
+/-25%
Ci 2.75E+02
+/-25%
d.Other ml l.08E+03
+/-25%
Ci 6.95E+0 l
+/-25%
Shipped from Processor(s) for Burial Unit Quarters 3 & 4 Est. Total Error%
a.Spent resins, filter sludl!;es, etc.
ml 0
NIA Ci 0
NIA b.Drv Compressible Waste, eQuipment, etc.
ml 0
NIA Ci 0
- c. Irradiated comoonents, control rods, etc.
ml 0
NIA Ci 0
NIA d.Other ml 0
NIA Ci 0
NIA A.
Estimate of Major Nuclide Composition (By Type of Waste)
Spent resins, filter sludges Dry Compressible Waste, equipment, Irradiated components, control rods, Other Waste etc.
etc.
Nuclide Percent(!)
Nuclide Percent( !)
Nuclide Percent(!)
Nuclide Percent( !)
- 0. 10 H-3 0.26 Fe-55 41.71 H-3 0.01 Fe-55 39.85 Fe-55 26.93 Co-60 43.78 Fe-55 48.60 Co-60 49.25 Co-60 65.39 Ni-59
Includes only those nuchdes that are greater than 0.1 % of the total activity B.
Disposition of Solid Waste Shipments (3 rd & 4th Quarters)
No. of Shipments From VY From Processor Mode To Processor To Burial 68 68 NIA Rail NIA 68 7
A.
Irradiated Fuel Shipments (D1spos1tton): None B.
Additional Data (I st & 2nd Quarters)
Supplemental lnfonnation VY to Processor VY to Burial Processors to Burial Class of Solid Waste Shipped NIA N B/C NIA Type of Containers Used NIA GDCIIP-1 /IP-NIA 2/Type B Solidification Agent or Absorbent Used NIA None NIA GDC = General Design Container
(
BVY 21-014 / Endosure / Page 21 of 52 Table 4A - Off-Site Doses from Liquid and Gaseous Releases (10CFR50, -Appendix D Dose (mrem)
So~
1st Quarter 2nd Quarter 3rd Quarter. 4th Quarter Liquid Effluents Total Body Dose 9.87E-07 5.70E-07 6.lOE-07 5.69E-07 Percent of,Limit (1.5 mrem) 6.58E-05
-3.80E-05 4.. 07E-05 3.79E-05 Footnotes
(~)
(a)
(a)
(a)
Organ Dose 9.87E-07 5,70E-07 6.l_0E-07 5.69E-07 Percent of Limit (5 mrem) l.97E-05 l.14E-05
- l.22E-05 l.14E-05 Footnotes (a) -
(a)
(a)
(a)
Airborne Effluents Iodine-s, H-3, C-14 and
'9.29E-07 l.75E-06 7.27E-06 3.24E-06 Particulates Percent of Litpit (7.5 mrem) l.24E-05 2.33E-05 9.69E-05 4.29E-05
- - Footnotes (b)
(b)
(b)
(b)
Noble Gases Beta Air (mrad)
Footnotes (c)
(c)
(c)
(c)
.Gamma Air*(mrad)
Footnotes (c)
(c)
(c)
(c)
Year 2.74E-06 I
2.74E-06 l.32E-05 I
(a)
The critical age group/organ for the Maximum Exposed-Individual (MED is the Adult/fotal Body and, all organs ( except Bone) from the releas~ of H-3 to groundwater.
(b)
These dos.es are based upon the maximum offsite X/Qs and D/Qs. The doses *are tp.e maximum organ dose when the Vegetable, Meat, Cow Mi_lk, and Inhalation pathways are summed.
(c)
- Toere were no noble gas releases in this quarter.
BVY 21-014 /Enclosure/ Page 22...9f 52 Table 4B -Annual Off-Site Doses from Liquid, Gaseous and Direct Radiation (40CFR190)
Pathway Total Body Maximum Organ Thyroid (mrem)
(mrem)
(miem)
Direct External (a) (b) 8.308 8.308 8.308 -
Liquids (c) 2.74E-06 0
2.74E-06 2.74E~06 Gases (c)
\\
l.32E-05 l.32E-05 l.32E-05
~
Annual Total ( d) 8.308 8.308 8.308 The location of the projected maximum individual,doses from combined direct radiation plus liquid and gaseous effluents correspond to residences at the southwest h<?undary 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 ofland 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 dose1 limits contained in 40 CFR Part 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 21-014 /Enclosure/ Page 23 of 52 Table 4C - Receptor Locations Sector Site Boundary (I) Nearest Resident '(2)
(meters)
(meters)
N 400 1400
/
NNE 350 1384 NE 350 1255 ENE 400 966 E
500 933 ESE 700 1915 SE 750 1963 SSE 850
- 2044 s
385 644 SSW 300 451 SW 250 418 WSW 250 451-w 300 628 WNW 4QO 1062 NW 550 2253 NNW 550 1738 (1)
Site boundary locations are taken from the Stack Releases colwnn in Table 6.10.2 of the ODCM.
(2)
The location(s) given are based on information from the Vermont Yankee 2016 Land Use Census and Table 7.1 of the ODCM and are relative to the plant stack. Gardens are assumed to be present at all resident locations.
L
,BIJY 21:-014 /Enclosure/ Page 24 of 52 Table 4D - Usage Factors for Environmental Pathways
/
\\
Age Fish Potable Veg.
Leafy Milk Meat -Inhalation.
Group (kg/yr)
Water (kg/yr)
Veg.
(I/yr)
(kg/yr)
(m3/yr)
(Vyr)
(kg/yr) r Adult 21 730 520 64 310 110 I
8,000 lfeen 16 510 630' 42 400 65
,, 8,000 Child
(
6.9 1
510 520 26 330 41 3,700 Infant 0
330
~ 0 0
330 0
1,400 Data :from}legulatory Guide 1.109, Table E-5 (Reference 2).
\\
(
\\
I' C
/
/
BVY 21-014 / Endosure / Page 25 of 52 Table 4E - Environmental Parameters for Gaseous Effluents Vegetables Cow Milk Goat Milk Meat Variable Stored Leafy Pasture Stored Pasture Stored Pasture Stored Agricultural Productivity YV (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 TimeCa)(hrs) 131,400 131,400 _
131,400 131,400 131,400 131,400 131,400 131,400 TE Crop Exposure Time to Phnne I
(hrs) 1,140 1,440 720 1,440 720 1,440 720 1,440 TH Holdup After Harvest (hrs) 1,440 -
24
- o 2,160 0
2,160
(
0 2,160 QF An_1mRls Daily Feed (kg/day) 50 50 6
6 50 50 FP Fraction of Year on Pasture (b) '
(b)
(b)
Fraction Pasture Feed When on FS PastureCc)
' 1 1-
-- 1 Note: Footnotes on following page.
FNY 21-014 /Enclosure/ Page 26 of 52 Table 4E - Environmental Parameters for Gaseous_Eflluents (Continued)
Vegetables Cow Milk Goat Milk M~t Variable Stored Leafy Pasture Stored Pasture Stored Pasture Stored FG Fraction of Stored Vegetables p.76 Grown in Garden FL Fraction of Leafy Vegetables
\\
1.0 GrowninG-arclen
-1
-- )
FI Fraction Elemental Iodine= 0.5 H
Absolute Humidity= 5.(i<d)
Frorp VY ODCM, Table 6.9.1 (Reference 1).
(a)
For Method II dose/dose rate analyses of identified radioactivity releases ofless than one year, the soil exposure time for that rel~ may (b)
(c) 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.
/
J For Method II dose/dose rate analyses performed for releases occurring during the first or fourth calendar quartet], the fraction of time animals are assunied 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 repo~ as part of the land use census.
For Method II analyses, the fraction of pasture feed while on pasture may be set to less than 1.0 for specific farm locations i.+/-: this information is so identified and reported as part of the land use census.
(d)
For all Method II ap_alyses, 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, PergammonPress).
BVY 21-014 / Enclosure I Page 27 'of 52 Table 4F - Environmental Parameters for Liquid Releases (Tritium) Via Groundwater J
/
I Variable Name Potable Water Aquatic Food Stored Veg.
-, Leafy Veg.
Meat CowMilk (Units)
J Mixing Ratio 1
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**
I 50.0 60.0 (animal) (Uday)
/
Feed Uptake** (animal) 50.0 50.0 (kg/day)
- Values are from Regulatory Guide 1.109, Table E-15 (Reference 2)
- Values are from Regulatory'Guide 1.109, Table E-3 (Reference 2)
)
/
\\
BVY 21-014 /Enclosure/ Page 28 of 52 Tables SA-SG - Frequency Distribution Tables for Ground Level Releases Table SA Five Year Aggregate 35-foot PASQUILLA Class 1 Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Calms Wind mph 0.95 3
7 12 18 24
>24 TOTAL N
JS 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
O_
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 21-014 /Enclosure/ Page 29 of 52 Five Y ~
Aggregate PASQUlbLB,
Class 1 Class 2,r-Class 3 Calms Wind mph 0.95 3
7 N
2 10,,-
65 NNE 0
12 15
,NE 0
7 23 ENE 0
7 22 E
1 9
, 56 ESE 1,
5 65 SE 0
i 2
39,
SSE 0
4 31 -
s 0
3 15
,/
I SSW 0
0 6
SW 0
0 1
WSW 0
0 2
w 0
0 5,
WNW 0
3 6
NW 0
2 17 NNW I
1 5
64 TOTALS 5
69 432 Table 5B 35-foot Class 4 Class 5 12 18
(
36 5
9
'O 0 ' --
0 0
0 7
,0 28 1
. 22 0
\\
65 8
29 11,,
4 0
3 0
3 0
15 14
\\12-
'10 18 14 172 45 323 108
/
Clas's 6 24 1
0-
- 0 0
0 0
0 1
1 0
0 0
3 0
7 6
19
(
r /
Class 7
>~4 0
) 0 0
-0 0
0 0
0 0
0 0
0 0
0 0,
0
~
Io-TOTAL 119 36 30 29 73 100 63 109 59 10
,4 5
l 37 31 58 193 956
\\
BVY 21-014 /Enclosure/ Page 30 of 52 Table SC Five Year Aggregate 35-foot PASQUILLC 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 01 198
~
- NNE 1
31 31 13 0
0 0
76 NE 0
19 23 2
0 0
o*
44 ENE 0
22 56 2
0 0
0 80 E
0 28 111 2
0 0
.o 141 ESE 6
25 128 25 1
0 0
185 L
. SE 0
14 94, 21 0
0 0
129 SSE 0
6 74 99 1-1 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 I
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 I
92 NW 1
11 63 53
'.,44 4
0 176 NNW 0
9 123 109 49 l
6 1
297 TOTALS 11 204 883 558 175 13 2
1846
BVY 21-014 /Enclosure/ Page 31 of 52 Table 5D Five Year Aggregate 35-foot PASQUILLD Class 1 Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Calms 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 f 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 I
w 6
183 412 788 277 13 0
1679 WNW 3
235 370 908 471 42 1
-2030
)ffl 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 21-014 /Enclosure/ Page 32 of 52 Table 5E Five_ Year Aggregate 35-foot PASQUILLE Class 1 Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Calms I
I Wind mph
_0.95 3
7 12 18 24
>24 TOTAL r
N' 51 197 161 43-15 0
0 467 NNE 19 111 23 4_
0 0
0 157 NE 14' 89 I
9 1
1 0
0 114 ENE 14 71 7
I 0 0
0 0
92 E
I 13 91 36 1
0 0
0 141 r
~
\\
ESE 25 156 74 7
0 0
0 262 SE 71 216 277 15 0
0 0
579 960 1
SSE 77 346 428 100 8
1 0
s 46 529 278 125 32 3
o*
I 1013 SSW 34 676 101 17 2
0 o*
830 SW 38 912 98 12 1
0 0
1061 WSW 19 827 214 13 0
1 0
1074 w
19 797 342 1150 22 2
0 1332 WNW 21 ',
640 396 144 36 0
0 r,
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 21-014 /Enclosure/ Page 33 of 52
_)
Five Year Aggregate_
rASQUILLF Class 1 Class 2
- Calms, Wind mph 0.95 3
N 8
73-,
NNE 7
31 NE 5 -
25 ENE 5
~,'
27 E
6 27 ESE 14 26 SE
, 17 75 SSE 19
- 136 s
30 344 SSW 50 501 SW 36 106l WSW I, 29 990
,'w 11
' 677 WNW:
12 349 NW 13 198 NNW 23 94 TOTALS 285 4639 - :'
C
\\
(
Class 3 7
12 3'
0 1.
7 13.-
3~
59 56l
- 68.
47 78 69 84 70 611 Table 5F 35-foot Class 4 12 0
p 0
0 0
- 0.
0
'1 I 1
\\
\\
0 0
1 -
1 2
2 6
14
\\
Class 5 18 0
0 0
0 0
.o 0
1 0
- o 0
0 0
0 0
0 1
I Class 6 Class 7 24
>24 TOTAL 0
0 98 0
0 41 0
0 30 0
0
'33 0
0 38 0
0 47 0
0 105 o-0 196 0
0 434 0
0 607 0
0 1165 0
0 1067_
0 0
767 0
0 432 1
0 298 0
0 '
193 1
0 5551
BVY 21-014 / Endosure / Page 34 of 52
(
\\
\\
\\
Table 5G Five Year Aggregate 35-foof' PASQUILLG Class 1 Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Calms 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 K
6 22 0
0 0
0 0
28 I
ESE 10 22 5
0 0
0 0
37 SE 10 27 2
0
- o 0
0 39 SSE 10 52 6
0 0
0 0
68 s
22 96 12 0
0 0
o~
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 21-014 / Endosure / Page 35 of 52 Tables 6A-6G - Frequency Distnbution Tables for Elevated Releases I
Table 6A Five Year Aggregate 1 297-foot
.PASQUILLA Class 1 Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 Calms
/
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
d 0
0 1
ESE b
3 2
3 1
0 0
9 SE o*
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 r 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
-o 2
NW 0
1 0
3 0
0 0
4 I
NNW 1
2 3
3 3
0 0
12 TOTALS 13 23
, 23 20 8
O*
()
87 V
BVY 21-014 /Enclosure/ Page 36 of 52 Five,Year Aggregate PASQUILLB
~
',\\_
Class 1 Class 2 Calms Wind'mph 0.95 3,
N 0
I NNE 0
0 NE 0
1 ENE 0
0 E
0 1
ESE 1
4 SE 0
3 SSE 0
1 s
0 0
SSW 0
0 SW 0
0 WSW 0
0 w
0 0
WNW 0
0 NW 0
- < 1 NNW 0
3 TOTALS, -
1 15, Class 3 7
8 2
1 2
1 13 6
1 0
0
'O 0
0
~
1 9
47
~,
\\
Table 6B 297-foot Class 4-Class 5 Class 6 ' Class 7 12 18 24
>24 TOTAL 14 2
0 0
25 5
2 0
0 9
6 0
0 0
8 3
0 0
0 5
3 1
0 0
6
\\_
26 4
0 0
48 5
~
0 0
17 3
2 0
0 7
0 5
0 0
(
5 0
(
O' 0
0 0
0 0
0 0
0 1
1 0
0 2
3 1
)
1 0-5 r
~
0 2
2 3
10 2
2 0
0 6
24 18 9
4
-67 95
. 43 12 7
220
\\',
BVY 21-014 / Encl~re / Page 37 of 52
_/
Table 6C Five Year Aggregate 297-foot PASQUILLC Class 1 Class 2 Class 3 I
Class 5 Class 6 Class 7 Calms I
Class'4 V{indmph 0.95 3
7 12 18 24
>24 TOTAL r N
0 6
25 36 26 1
d -
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
_)
1 16 E
0 4
9 1
0 0
30 I
ESE 0
~
7 51 47 3
0 0
108 l
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 l
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 I
0 0
p 5
3 9
1 18 WNW
- 0 0
2 7
7 8
0 24 c NW~
1 1
10 11 15 8
2 48 NNW 0
- 3 31 71 62 47 1l 225 TOTALS 2
42 195 301 160,
82
< 16 798 l-l
BVY 21-01~ /Enclosure/ Page 38 of 52 Table 6D Five Year Aggregate 297-foot PASQUILLD Class 1 Class 2 Class 3 Class4 Class 5 Class 6 Class 7 Calms Wind mph 0.95
- 3 7
12 18 24
>24 TOTAL N
18 1
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 3~6 E
8 438 251 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 J WSW 11 50 73
\\
216 92 7
2 451
\\.
w 16 53 101 623 695 175 12 1675 WNW 3
84 138 689 901 285 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 r
\\
BVY 21-014 / Endosure / Page 39 of 52
-~
Table 6E
'\\
, Five Year Aggregate 297-foot PASQUILLE
/
Class 1 Class 2 Class,3 Class 4 Class 5 Class 6 Class 7 Calms
,Wind mph 0.95 3
7 12 18 24
>24 TOTAL N
27
~24 467 222 46 7*
- o 1293
-NNE 8
354 66 27 5
0 0
460 "NE 9
294 41 21 0
0 1
I 347 ENE 5
282' 33 1
- o 2
0 323 E
9 397 70 8
0 0
0 484 ESE 15 457 226 27 3
0 0
728 I
SE 25 474 747 171 6
,1 O'
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 I
w 4
5T 132 299 186 9
1 688
.WNW 4
97 146 284 108 12 1
652 NW 1
206 361 258 83 13 1
I 923 NNW 21
/
441 1536 944 305 58 10 3315 TOTALS 151 4232" 5140 3207 992 139 19 13880
BVY 21-014 / Enclosun:1 / Page 40 of 52 Table 6F Five "X" ear Aggregate 297-foot PASQUILLF -
Class 1 Class 2 Class 3 Class 4 Class 5 Class 6 *-Class 7
\\
Calms Wind mph 0.95 3
7 12 18 24
>24 TOTAL N
9 217 176 19 6
- o 0
427
- NNE 2
161 24 3
0 0
0 190 NE 2
130 6
0 0
b 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
1491
- 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
11?/
154 40 4
0 0
I ---- 315 NNW 3
167 429
.184 9
-o 0
792-TOTALS 55 1888 2155
- 675 44 1
0 4818
BVY 21-014 / Endosure / Page 41 of 52 Table 60 Five Year Aggregate 297-foot PASQUILLG I
\\
Class 1 Class 2 Class 3 Class 4 Class 5 Class 6 Class 7 I Calms
- Wind mph 0.95 3
7
\\
12 18 24
>24 TOTAL N
0 18 19 3
1 0
0 41 I NNE I
0 6
2 0
0 I
0 0
8 NE 0
10 3
0 0
0 0
13 tNE 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 O'
1' 8 19 12 2
0 0
41 SW 0
11 22 17 0
0 0
50 WSW 0
15
' *,29 15 0
(1 0
59 w
0 8
32 26 2
0
-o 68 I
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 I
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BVY 21-014 /Enclosure/ Page 42 of 52 APPENDIX A-SUPPLEMENTAL INFORMATION
- 1.
MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Provided below are the methods used to measure or approximate the total radio,activity in effluents and the methods used to deteID?:ine radionuclide composition.
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Tritium,.,
ODCM Table 4.3.1 requires that a continuous sample of stack effluents be collected for H-3 and analyzed monthly. The error involved in this sample is approximately +/-18 percent.
Particulates ODCM Table 4;3.1 requires that a continuous sample of stack eflluents be collected and analyzed weekly for principal gamma emitters. The error involved in this sample is approximately +/-18 percent
- 2.
BATCH RELEASES
_There were no routine liquid or gaseous batch releases during the reporting period.
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- 3.
ABNORMAL RELEASES
- a.
- b.
Liquid VY has 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 2020. A second well, GZ-24 was compromised by excavation activity in 2014 and is no longer able to be sampled. A new well was drilled at GZ-02 in 2020 and the original well has been abandoned. GZ-16 has been found and samples have recommenced at this location as of November 2020. Sample locations GZ-10 and GZ-20 were not sampled in 2020 due to demolition activities -
associated with the Auxiliary Off-Gas Building. 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 2020 and all of these sample results are well below the EPA limit of20,000 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.
Gaseous j
There were no non-routine gaseous releases (measured) during' the reporting period.
BVY 21-014 /Enclosure/ Page 43 of 52 t,
Table A-1: VY Groundwater Tritium Summary - 2020
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~
Concentration Range1 Number of Groundwater analyses Mean well Sampled performed Concentration 1 Min Max GZ-01 1
< 665
< 665 1
< 665 GZ-02 1
< 658 658 658 GZ-031
- 2 656 637 675 GZ-04 2
654 639 669 GZ-0~
,1 669 669 669 GZ-06 1
665
< 665 665 GZ-07 1
633
< 633 I
633 GZ-09 1
< 1710 1710
< 1710 Gz.:.10 0
GZ-11 2
- < 651
< 634 667 GZ-12 2*
'<, 650 634 -
666 GZ-12D
- 4
< 647 612 692 GZ-13 1
< 679 679
<' 679 GZ-13D 2
< 649 632 665 GZ-14 4
< 653 627 699 GZ-14D 4
(1140 944 1640 GZ-15 4
< 651 613 701 GZ-16 1
< 678 I
678 678
(
GZ-17 1
< 659 659 659 GZ-18
'1
< 665
< 665
< 665 GZ-18D 1
< 668
< 668 668 GZ-19 1
< -658
< 658
< 658 GZ-19D 1
< 656
< 656
< 656 GZ-20 0 -
GZ-21 1
< 634
< 634
< 634 GZ-22D 12 1660 709 2270 GZ-23 12
< 634 r-
< 611
< 691 GZ-25 2
< 668 668
< 668 GZ-26 2
< 657
< 657
< 657 GZ-27 I
2
< 667
< 667
< 667 Notes:
- 1. All concentrations are in units ofpCi/L
- 3. "< denotes minimum detectable value for the analytical period
- 4. Bold values denote positive results (greater than minimum detectable valpes)
BVY 21-014 / Endosure / Page 44 of 52
.APPENDIX B. -LIQUID HOLDUP TANKS Requirement With the quantity of radioactive material in any outside tank exceeding the limit of SectionA of the Decommissioning Safety Analysis Report, descdbe the events leading to this condition in the next Radioactive Effluent Release Report. -
J Response 1 The limits for any outside tank were not exceeded during this reporting period.
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FNY 21-014 /Enclosure/ Page 45 of 52
'l APPENDIX C - RADIOACTIVE UQUID EFFLUENT MONITORING INSTRUMENTATION The requirements for rad~oactive liquid effluent monitoring instrumentation channels in o:qc:M' Table 3.1.1 were removed in ODCM Revision 40.
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BVY 21-014 /Enclosure/ Page 46 of 52 I
APPENDIX D - RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 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 eflluent 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 Eflluent Release Report of the reaso~s) for the delay in correcting the inoperability is required per ODCM Section 10.1.
Response
There were no issues related to the radioactive gaseous eflluent monitoring instrumentation for this reporting period.
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BVY 21-014 /Enclosure/ Page 47 of 52 APPENDIXE-RADIOLOGICAL ENVIRONMENfAL MONITORING PROORAM
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This Appendix is no longer required by the O:pCM Revision 40. This Appendix is retained as a placeholder to allow this report to be consistent with previous reports.
BVY 21-014 /Enclosure/ Page 48 of 52 APPENDIX F -LAND USE CENSUS 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.
I
Response
The Land Use Census was completed during the third quarter of 2020. No locations were identified which yielded a 20 percent greater dose or dose co~tment 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 2020 Land Use Census.
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BVY 21-014 /Enclosure/ Page 49 of 52 APPENDIX G-PROCESS CONTROL PROGRAM R~uirement 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 ReleasC? Report for the period in which the change(s) was made.
~
Response
I There were minor editorial changes made to the Process Control Program during this reporting period.
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BVY 21-014 /Enclosure/ Page 50 of 52 APPENDIX H-OFF-SITE DOSE CALCULATION MANUAL R~uirement I
ODCM Se<,iion 10.1 requires that licensee-initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the annual Radioactive Eflluent Release Report for the period in which the change(s).
I R~nse There were no changes to the Offsite Dose Calculation Manual (ODCM) during 2020.
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BVY'21-014 /Enclosure/ Page 51 of 52 APPENDIX I-RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS
/
Requirement ODCM Section 10.5 requires that licensee-initiated major changes to the radioactive waste ~ystems (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 21-014 /Enclosure/ Page 52 of 52 APPENDIX J -ON-SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE R~uirement
)
Off-Site Dose Calculation Manual, Appendices B, F and I require 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 i
Release Report if disposals occur during the reporting year.
Vermont Yankee will report in the Annual Radioactive Eflluent Release Report a list of the radionuclides present and the total radioactivity associated with the disposal activities on the Vermont Yankee site.
Resoonse There was no on-site disposal spreading during 2020.
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