BVY 16-020, Transmittal of 2015 Radioactive Effluent Release Report: Difference between revisions

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{{#Wiki_filter:BVY 16-020 May 12, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001  
{{#Wiki_filter:Entergy Nuclear Vermont Yankee, LLC
'/
                                                  '/            Vermont Yankee
~Entergy 320 Governor Hunt Rd.
Vernon, VT 05354 (802) 257-7711 Coley C. Chappell Manager, Design and Programs BVY 16-020 May 12, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001


==SUBJECT:==
==SUBJECT:==
2015 Radioactive Effluent Release Report Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28  
2015 Radioactive Effluent Release Report Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28


==Dear Sir or Madam,==
==Dear Sir or Madam,==
Entergy Nuclear Vermont Yankee, LLC Vermont Yankee 320 Governor Hunt Rd. Vernon, VT 05354 (802) 257-7711 Coley C. Chappell Manager, Design and Programs In accordance with Vermont Yankee (VY) Technical Specifications (TS) 6.6.D, enclosed is a copy 'of the annual 2015 Radioactive Effluent Release Report. In addition, VY TS 6.7.B requires reporting of changes to the Off-Site Dose Calculation Manual (ODCM). There were no changes made to the ODCM during 2015 as noted in Appendix H of the subject report. There are no new regulatory commitments being made in this submittal.
 
In accordance with Vermont Yankee (VY) Technical Specifications (TS) 6.6.D, enclosed is a copy 'of the annual 2015 Radioactive Effluent Release Report.
In addition, VY TS 6.7.B requires reporting of changes to the Off-Site Dose Calculation Manual (ODCM). There were no changes made to the ODCM during 2015 as noted in Appendix H of the subject report.
There are no new regulatory commitments being made in this submittal.
Should you have any questions or require additional information concerning this submittal, please contact me at (802) 451-3374.
Should you have any questions or require additional information concerning this submittal, please contact me at (802) 451-3374.
Sincerely,
Sincerely, t~Mw~
[CCC/TBS]  
[CCC/TBS]


==Enclosure:==
==Enclosure:==
Radioactive Effluent Release Report for 2015 cc listing (next page) cc:      Mr. Daniel Dorman, Region 1 Administrator
BVY 16-020 I Page 2 of 2 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Mr. Jack D. Parrott, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop T-8F5 11555 Rockville Pike
      .Rockville, MD 20852-2378 Mr. Christopher Recchia, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, VT 05620 Vermont Department of Health Division of Radiological Health Attn: Bill Irwin P.O. Box 70 Burlington, VT 05402-0070 Massachusetts Department of Public Health Jack Priest, Director Radiation Control Program 529 Main Street, Suite 1M2A Charlestown, MA 02129 Augustinus Ong, Administrator Department of Health and Human Services Radiological Health Section 29 Hazen Drive Concord, NH 03301-6504 \.*
John Giarrusso Nuclear Preparedness and Planning Manager 400 Worcester Road Framingham, MA 01702 Tony Honnellio Radiation Program Manager, Health and Safety Coordinator EPA, New England, Region 1 5 Post Office Square, Suite 100 (OSRR02-2).
Boston, Massachusetts 02109
RADIOACTIVE EFFLUENT RELEASE REPORT FOR2015 INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN Entergy Nuclear Vermont Yankee, LLC Docket No. 50-271 License No. DPR-28 Prepared  by:_,.,,,,..,Y'--"""--L,,.-~~~"""'-""'~=_,,___ _ _ _ ____;/ 6 Is'/ I to
                                              , Clvisol)* Scientist, AREVA, Inc. Date
                              --b~~~-'--~~~1~1$/td&                          Date Revie-ived by:_~----.......,....,~--+-+--------*ut:f0 Approved for  Distribution:_-1!--L-=:::i~~r==::::::::__ _ _ _ _ _ ___!/ ~kb(?
Date
                                                                                      \..


Radioactive Effluent Release Report for 2015 cc listing (next page) cc: Mr. Daniel Dorman, Region 1 Administrator BVY 16-020 I Page 2 of 2 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Mr. Jack D. Parrott, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop T-8F5 11555 Rockville Pike . Rockville, MD 20852-2378 Mr. Christopher Recchia, Commissioner VT Department of Public Service 112 State Street -Drawer 20 Montpelier, VT 05620 Vermont Department of Health Division of Radiological Health Attn: Bill Irwin P.O. Box 70 Burlington, VT 05402-0070 Massachusetts Department of Public Health Jack Priest, Director Radiation Control Program 529 Main Street, Suite 1 M2A Charlestown, MA 02129 Augustinus Ong, Administrator Department of Health and Human Services Radiological Health Section 29 Hazen Drive Concord, NH 03301-6504
TABLE OF CONTENTS
\.* John Giarrusso Nuclear Preparedness and Planning Manager 400 Worcester Road Framingham, MA 01702 Tony Honnellio Radiation Program Manager, Health and Safety Coordinator EPA, New England, Region 1 5 Post Office Square, Suite 100 (OSRR02-2).
Boston, Massachusetts 02109 RADIOACTIVE EFFLUENT RELEASE REPORT FOR2015 INCLUDING ANNUAL RADIOLOGICAL IMP ACT ON MAN Entergy Nuclear Vermont Yankee, LLC Docket No. 50-271 License No. DPR-28 Prepared
_____ ___;/ 6 Is'/ I to , Clvisol)*
Scientist, AREVA, Inc. Date Date Revie-ived 0 Approved for
_______ __!/
Date \..
TABLE OF CONTENTS  


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==
.............................................................................................................................................. 1 2.0 METEOROLOGICAL DATA ............................................................................................................................ 2 3.0 DOSE ASSESSMENT .................................................................................. :.................................................... 3 3.1 DOSES FROM LIQUID EFFLUENTS ............................... : ................................................................................... 3 3.2 DOSES FROM NOBLE GASES ........................................................................................................................... 4 3 .3 DOSES FROM IODINE-131, IODINE-133, TRITIUM, CARBON-14, AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS .................................................................................. 4 3.4 WHOLE BODY DOSES IN UNRESTRICTED AREAS FROM DIRECT RADIATION ................................................. 5 3 .5 DOSES FROM ON-SITE DISPOSAL OF SEPTIC WASTE, COOLING TOWER SILT AND SOIL ............................... 6 3.6 ON-SITE RECREATIONAL ACTIVITIES ............................................................................................................. 6 REFERENCES .......................................................................................................................................................... 7 APPENDIX A -SUPPLEMENTAL INFORMATION ......................................................................................... A-1*
APPENDIX B -LIQUID HOLDUP TANKS ........................................................................................................ B-1 APPENDIX C -RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ............................................................................................................... C-1 APPENDIX D -RADIOACTIVE GASEOUS EFFLUENT MONITORING '
INSTRUMENTATION ................................................................................................................ D-1 APPENDIX E-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..................................... E-1 APPENDIX F - LAND USE CENSUS .................................................................................................................. F-1 APPENDIX G -PROCESS CONTROL PROGRAM ............................................................................................ G-1 APPENDIX H -OFF-SITE DOSE CALCULATION MANUAL ......................................................................... H-1 APPENDIX I - RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS ............................................................................................................ I-1 APPENDIX J - ON-SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE ............................................................ J-1 11


..............................................................................................................................................
LIST OF TABLES IA       Gaseous Effluents - Summation of All Releases                           8 IB       Gaseous Effluents - Elevated Releases                                 10 IC       Gaseous Effluents - Ground Level Releases                             I2 lD       Gaseous Effluents - Non-routine Releases                               14 2A       Liquid Effluents - Summation of All Releases                           15 2B       Liquid Effluents - Routine Releases                                   17 3       Solid Waste and Irradiated Fuel Shipments                             19 4A       Maximum Quarterly and Annual Off-Site Doses from Direct Radiation and 21 Liquid and Gaseous Effluents for 2015 (10CFR50, Appendix I) 4B       Maximum Annual Off-Site Doses from Direct Radiation and               22 and Liquid and Gaseous Effluents for 2015 (40CFR190) 4C       Receptor Locations                                                     23 4D       Usage Factors for Environmental Pathways                               24 4E       Environmental Parameters for Gaseous 'Effluents                       25 4F       Environmental Parameters for Liquid Releases (Tritium) Via Groundwater 27 5A to 5H Annual (2015) Summary of Lower Level Joint Frequency Distribution     28-35 6A to 6H Annual (2015) Summary of Upper Level Joint Frequency Distribution     36-43 111
1 2.0 METEOROLOGICAL DA TA ............................................................................................................................
 
2 3.0 DOSE ASSESSMENT
Radiological Effluent Release Report for 2015
..................................................................................
[Including Annual Radiological Impact on Man]
: ....................................................
Entergy Nuclear Vermont Yankee, LLC
3 3.1 DOSES FROM LIQUID EFFLUENTS
...............................
: ...................................................................................
3 3.2 DOSES FROM NOBLE GASES ...........................................................................................................................
4 3 .3 DOSES FROM IODINE-131, IODINE-133, TRITIUM, CARBON-14, AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS ..................................................................................
4 3.4 WHOLE BODY DOSES IN UNRESTRICTED AREAS FROM DIRECT RADIATION
.................................................
5 3 .5 DOSES FROM ON-SITE DISPOSAL OF SEPTIC WASTE, COOLING TOWER SILT AND SOIL ...............................
6 3.6 ON-SITE RECREATIONAL ACTIVITIES
.............................................................................................................
6 REFERENCES
..........................................................................................................................................................
7 APPENDIX A -SUPPLEMENTAL INFORMATION
.........................................................................................
A-1* APPENDIX B -LIQUID HOLDUP TANKS ........................................................................................................
B-1 APPENDIX C -RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
...............................................................................................................
C-1 APPENDIX D -RADIOACTIVE GASEOUS EFFLUENT MONITORING
' INSTRUMENTATION
................................................................................................................
D-1 APPENDIX E-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .....................................
E-1 APPENDIX F -LAND USE CENSUS ..................................................................................................................
F-1 APPENDIX G -PROCESS CONTROL PROGRAM ............................................................................................
G-1 APPENDIX H -OFF-SITE DOSE CALCULATION MANUAL .........................................................................
H-1 APPENDIX I -RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS ............................................................................................................
I-1 APPENDIX J -ON-SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE ............................................................
J-1 11 LIST OF TABLES IA Gaseous Effluents  
-Summation of All Releases 8 IB Gaseous Effluents  
-Elevated Releases 10 IC Gaseous Effluents  
-Ground Level Releases I2 lD Gaseous Effluents  
-Non-routine Releases 14 2A Liquid Effluents  
-Summation of All Releases 15 2B Liquid Effluents  
-Routine Releases 17 3 Solid Waste and Irradiated Fuel Shipments 19 4A Maximum Quarterly and Annual Off-Site Doses from Direct Radiation and 21 Liquid and Gaseous Effluents for 2015 (10CFR50, Appendix I) 4B Maximum Annual Off-Site Doses from Direct Radiation and 22 and Liquid and Gaseous Effluents for 2015 (40CFR190) 4C Receptor Locations 23 4D Usage Factors for Environmental Pathways 24 4E Environmental Parameters for Gaseous 'Effluents 25 4F Environmental Parameters for Liquid Releases (Tritium)
Via Groundwater 27 5A to 5H Annual (2015) Summary of Lower Level Joint Frequency Distribution 28-35 6A to 6H Annual (2015) Summary of Upper Level Joint Frequency Distribution 36-43 111 Radiological Effluent Release Report for 2015 [Including Annual Radiological Impact on Man] Entergy Nuclear Vermont Yankee, LLC  


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==


Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste shipments for the year, 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 the year 2015 in response to the ALARA objectives of 10 CFR Part 50, Appendix I. Also included in Table 4A is the estimate of direct dose from fixed station sources along the limiting west site boundary line. Tables SA through 6H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 2015. Radioactive effluents reported in Tables 1and2 were used to determine the dose to the maximum exposed individual for 2015. 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.l (Reference 1). These dose estimates were made using a "Method II" analysis as described in the ODCM, and as reported in Tables 4A and 4B ofthis report. A "Method II" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference
Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste shipments for the year, 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 the year 2015 in response to the ALARA objectives of 10 CFR Part 50, Appendix I. Also included in Table 4A is the estimate of direct dose from fixed station sources along the limiting west site boundary line. Tables SA through 6H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 2015. Radioactive effluents reported in Tables 1and2 were used to determine the dose to the maximum exposed individual for 2015.
: 2) and actual measured meteorological data recorded concurrently with the quarterly reporting period. As required by ODCM Section 10.1, this report shall also include an assessment of the radiation*
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.l (Reference 1). These dose estimates were made using a "Method II" analysis as described in the ODCM, and as reported in Tables 4A and 4B ofthis report. A "Method II" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 2) and actual measured meteorological data recorded concurrently with the quarterly reporting period.
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.
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 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," is also required to be included in this report ifthe 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.
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 Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," is also required to be included in this report ifthe 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 Part 190. All calculated dose estimates for members of the public at the site boundary or beyond for the 2015 annual reporting period are below the dose criteria of 10 CFR Part 50, Appendix I, and 40 CFR Part 190. Appendices B through H indicate the status of reportable items per the requirements of ODCM Section 10.1. 1 2.0 METEOROLOGICAL DATA Meteorological data were collected in 2015 from the site's 300-foot meteorological tower located approximately 2,200 feet northwest of the reactor building, and about 1,400 feet from the plant stack. The 300-foot tower is approximately the same height as the primary plant stack (308 feet) and is designed to meet the requirements of Safety Guide 23 (Reference
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 Part 190.
: 3) for meteorological monitoring.
All calculated dose estimates for members of the public at the site boundary or beyond for the 2015 annual reporting period are below the dose criteria of 10 CFR Part 50, Appendix I, and 40 CFR Part 190.
In mid-2009, the tower was moved to a location approximately 200 feet northwest of the original location.
Appendices B through H indicate the status of reportable items per the requirements of ODCM Section 10.1.
r.JQ and D/Q values for elevated releases were derived for all receptor points from the site meteorological record for each quarter using a straight-line airflow model. All dispersion factors have been calculated employing appropriate source configuration considerations, as described in Regulatory Guide 1.111 (Reference 4). A source depletion model as described in "Meteorology and Atomic Energy -1968" (Reference
1
: 5) was used to generate deposition factors, assuming a constant deposition velocity of 0. 01 m/sec for all stack (elevated) releases.
 
Changes in terrain elevations in the site environment were also factored into the meteorological models as appropriate.
2.0 METEOROLOGICAL DATA Meteorological data were collected in 2015 from the site's 300-foot meteorological tower located approximately 2,200 feet northwest of the reactor building, and about 1,400 feet from the plant stack. The 300-foot tower is approximately the same height as the primary plant stack (308 feet) and is designed to meet the requirements of Safety Guide 23 (Reference 3) for meteorological monitoring. In mid-2009, the tower was moved to a location approximately 200 feet northwest of the original location.
In the event of a ground-level release, r.JQ and D/Q values would be derived for the site boundary receptor points from the site meteorological record for each quarter using a straight-line airflow model. During this reporting period, there were no ground-level releases and therefore no associated dose impact. Table 4C lists the distanc.es from the plant stack to the nearest site boundary, resident, and milk animal in each of the 16 principle compass directions as determined during the 2015 land use census. These locations were used in the calculation of atmospheric dispersion factors. The meteorological model was also executed for each calendar quarter to determine the location of the predicted maximum ground level air concentration from elevated releases from the plant's primary vent stack. These locations were included in the assessment of effluent doses along with identified points of interest from the annual land use census. " 2 3.0 DOSE ASSESSMENT 3.1 Doses From Liguid 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 Part 50, Appendix I. By implementing the requirements of 10 CFR Part 50, Appendix I, ODCM 3/4.2.2 assures that the release ofradioactive material in liquid effluents will be kept "as low as is* reasonably achievable." . *', *
r.JQ and D/Q values for elevated releases were derived for all receptor points from the site meteorological record for each quarter using a straight-line airflow model. All dispersion factors have been calculated employing appropriate source configuration considerations, as described in Regulatory Guide 1.111 (Reference 4). A source depletion model as described in "Meteorology and Atomic Energy - 1968" (Reference 5) was used to generate deposition factors, assuming a constant deposition velocity of 0. 01 m/sec for all stack (elevated) releases. Changes in terrain elevations in the site environment were also factored into the meteorological models as appropriate.
* There were no recorded routine liquid radioactive waste discharges during the report period. However, an abnormal release to the Connecticut River is postulated due to a past leak in an underground pipe tunnel that runs between the Advanced Offgas (AOG) system building and other plant buildings which allowed accumulated piping system leakage to enter the subsurface groundwater adjacent to the plant structures.
In the event of a ground-level release, r.JQ and D/Q values would be derived for the site boundary receptor points from the site meteorological record for each quarter using a straight-line airflow model.
The existence of the leak was first recognized in January 2010, when a river shoreline Protected Area Boundary monitoring well sample was reported to have detectable tritium. The addition of other monitoring wells and subsequent analysis defined the extent of the affected groundwater plume moving toward the.river and helped locate the source of the leak, which was stopped in February 2010. \ Estimates of tritium-contaminated ground water released from the site are based on Protected Area Boundary monitoring well data collected throughout 2015, and hydrological modeling of ground water movement in the affected zone impacted by the pipe tunnel leak. 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 2015 was generated and reported in Table 2A. Forthe projected ground water flow into the Connecticut River in 2015, the dose impact to the maximum exposed individual (MEI) assumed the following exposure pathways:
During this reporting period, there were no ground-level releases and therefore no associated dose impact.
(1) ingestion offish (taken from Vernon Pond), (2) ingestion of vegetables and, fresh leafy produce irrigated by water taken from the river below Vernon Dam, (3) ingestion of milk and meat from animals that were fed irrigated crops and drinking water taken from the river below Vernon Dam, and (4) water for a hypothetical individual drawing drinking water fed by the river below Vernon Dam. For Vernon Pond (river area adjacent to the plant property), the near shore mixing zone associated with the fish ingestion pathway is conservatively taken as 1 % of the minimum recorded monthly river flow (3,107 cfs in September 2015) for dilution.
Table 4C lists the distanc.es from the plant stack to the nearest site boundary, resident, and milk animal in each of the 16 principle compass directions as determined during the 2015 land use census. These locations were used in the calculation of atmospheric dispersion factors. The meteorological model was also executed for each calendar quarter to determine the location of the predicted maximum ground level air concentration from elevated releases from the plant's primary vent stack. These locations were included in the assessment of effluent doses along with identified points of interest from the annual land use census.   "
All irrigation exposure pathways for the consumption of food products grown with irrigated water occur below Vernon Dam and assume the lowest 2015 quarterly average growing season river flow value (5394 cfs in the third quarter) for environmental mixing. For the drinking water pathway, river flow mixing is assumed to occur below Vernon Dam and uses the lowest annual quarterly average river flow (5394 cfs in the third quarter) as a conservative estimate ofriver dilution for all four quarters of the year. The dose models are !aken from Regulatory Guide 1.109 (Reference
2
: 2) and use environmental parameters for exposure pathways listed in Tables 4D and 4F. . The maximum estimated quarterly and annual whole body and organ doses to the limiting age group from liquid releases are reported in Table 4A. These estimated doses are well below the 10 CFR Part 50, Appendix I dose criteria of ODCM 3/4.2.2. Table 4B provides an estimate of the total annual'dose impact (including contribution from liquids) associated with the highest exposed member of the public for demonstration of compliance to the dose standard contained in 40 CFR 190 for the uranium fuel cycle. \. 3 3.2 Doses From Noble Gases ODCM 3/4.3.2 limits the gamma air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I. By implementing these, ODCM 3/4.3.2 assures that the releases ofradioactive noble gases in gaseous effluents will be kept "as low as is reasonably achievable." Dose estimates due to the release of noble gases to the atmosphere are typically calculated at the site boundary, at the nearest resident in each of the sixteen principal compass directions, at the point of highest off-site ground level air concentration of radioactive materials, and at each of the milk animal locations located within five miles of the plant. For 2015, there were no noble gases detected in effluents released from the plant stack. 3.3 Doses From Iodine-131, Iodine-133, Tritium, Carbon-14, and Radionuclides in Particulate Form with Half-Lives Greater Than 8 Days ODCM 3/4.3.3 limits the organ dose to a member of the public from Iodine-131, Iodine-133, Tritium, Carbon-14, and radionuclides in particulate form with half-lives greater than 8 days (hereafter called "iodines and particulates")
 
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 iodines and particulates in gaseous effluents will be kept "as low as is reasonably achievable." During 2015, a single frac tank was used on the Vermont Yankee site to temporarily store (outdoors) tritium-contaminated water extracted from onsite groundwater wells. The quantity of tritium released to the atmosphere through the evaporation of water from this frac tank was estimated, and the dose consequence to the maximally exposed individual was calculated.
3.0 DOSE ASSESSMENT 3.1 Doses From Liguid 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 Part 50, Appendix I. By implementing the requirements of 10 CFR Part 50, Appendix I, ODCM 3/4.2.2 assures that the release ofradioactive material in liquid effluents will be kept "as low as is*
Exposure pathways that could exist as a result of the planned (routine) release of iodines and particulates to the atmosphere include external irradiation from activity deposited onto the ground surface, inhalation, and ingestion of vegetables, meat and milk. Dose estimates were made at the site boundary and nearest resident in each of the sixteen principal compass directions, as well as all milk animal locations within five miles of the plant. The nearest resident and milk animals in each sector were identified by the most recent annual land use census as required by ODCM 3/4.5.2 (see Table 4C). Conservatively, a vegetable garden was assumed to exist at each milk animal and nearest resident location.
reasonably achievable."                                                                                     . *', *
Furthermore, the meat pathway was assumed to exist at each milk cow location since this data category is not part of the annual land use census. Doses were also calculated at the point of maximum ground level air concentration of radioactive materials in gaseous effluents and included the assumption that the inhalation, vegetable garden, and ground plane exposure pathways exist for an individual with a 100 percent occupancy factor. It is assumed that milk and meat animals are free to graze on open pasture during the second and third quarters with no supplemental feeding. This assumption is conservative since most of the milk animals inventoried in the site vicinity are fed stored feed throughout the entire year with only limited grazing allowed during the growing season. It has also been assumed that only 50 percent of the iodine deposited from gaseous effluent is in elemental form (I 2) and is available for uptake (seep. 6, Reference 2). 4 During the non-growing season (first and fourth quarters), the milk animals are assumed to receive only stored feed. During the growing season (second and third quarters), all animal feed is assumed to be derived from fresh pasture. Usage factors for gaseous effluents are listed by age group and pathway in Table 4D. Table 4E provides other dose model parameter assumptions used in the dose assessments.
* There were no recorded routine liquid radioactive waste discharges during the report period.
In June 2009, the NRC issued Revision 2 of Regulatory Guide 1.21 (Reference
However, an abnormal release to the Connecticut River is postulated due to a past leak in an underground pipe tunnel that runs between the Advanced Offgas (AOG) system building and other plant buildings which allowed accumulated piping system leakage to enter the subsurface groundwater adjacent to the plant structures. The existence of the leak was first recognized in January 2010, when a river shoreline Protected Area Boundary monitoring well sample was reported to have detectable tritium. The addition of other monitoring wells and subsequent analysis defined the extent of the affected groundwater plume moving toward the.river and helped locate the source of the leak, which was stopped in February 2010.
: 6) which introduced the term "principal radionuclide" in a risk-informed or dose context. A radionuclide can be considered a principal radionuclide if it contributes either (1) greater than 1 percent of the 10 CFR Part 50, Appendix I design objective dose for all radionuclides in the type of effluent being c01;1sidered, or (2) greater than 1 percent of the activity of all radionuclides in the type of effluent being considered.
                                                                        \
In addition to natural production in the environment, Carbon-14 is also produced in nuclear reactors as a function of power output, but at amounts muc11 less than those generated naturally or from past weapons testing. Since the time of 1 the e&rlier publication of Regulatory Guide 1.21 (Revision
Estimates of tritium-contaminated ground water released from the site are based on Protected Area Boundary monitoring well data collected throughout 2015, and hydrological modeling of ground water movement in the affected zone impacted by the pipe tunnel leak. 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 2015 was generated and reported in Table 2A.
: 1) in 1974, commercial nuclear power plants have decreased total radioactive effluents (other than Carbon-14) through improved fuel performance and waste management practices to the point today that Carbon-14 could be considered a principal radionuclide under today's definition.
Forthe projected ground water flow into the Connecticut River in 2015, the dose impact to the maximum exposed individual (MEI) assumed the following exposure pathways: (1) ingestion offish (taken from Vernon Pond), (2) ingestion of vegetables and, fresh leafy produce irrigated by water taken from the river below Vernon Dam, (3) ingestion of milk and meat from animals that were fed irrigated crops and drinking water taken from the river below Vernon Dam, and (4) pota~le water for a hypothetical individual drawing drinking water fed by the river below Vernon Dam. For Vernon Pond (river area adjacent to the plant property), the near shore mixing zone associated with the fish ingestion pathway is conservatively taken as 1% of the minimum recorded monthly river flow (3,107 cfs in September 2015) for dilution. All irrigation exposure pathways for the consumption of food products grown with irrigated water occur below Vernon Dam and assume the lowest 2015 quarterly average growing season river flow value (5394 cfs in the third quarter) for environmental mixing. For the drinking water pathway, river flow mixing is assumed to occur below Vernon Dam and uses the lowest annual quarterly average river flow (5394 cfs in the third quarter) as a conservative estimate ofriver dilution for all four quarters of the year. The dose models are
With the plant permanently shut down since December of2014, there was no plant related Carbon-14 production or associated dose impact for 2015. 3.4 Whole Body Doses in Unrestricted Areas From Direct Radiation As opposed to previous years where 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 2015 due to the plant being permanently shut down. The other fixed sources of direct and scatter radiation to the site boundary are the Independent Spent Fuel Storage Installation (ISFSI), the low level radioactive materials stored in the North Warehouse, the Low Level Waste Storage Pad Facility (no radioactive_
!aken from Regulatory Guide 1.109 (Reference 2) and use environmental parameters for exposure pathways listed in Tables 4D and 4F. .
waste material stored on the pad in 2015), and old turbine rotors and casings in the Turbine Storage Facility.
The maximum estimated quarterly and annual whole body and organ doses to the limiting age group from liquid releases are reported in Table 4A. These estimated doses are well below the 10 CFR Part 50, Appendix I dose criteria of ODCM 3/4.2.2. Table 4B provides an estimate of the total annual'dose impact (including contribution from liquids) associated with the highest exposed member of the public for demonstration of compliance to the dose standard contained in 40 CFR P~rt 190 for the uranium fuel cycle.
The annual dose is based on dose rate measurements in these storage facilities and is projected to impact the same most restrictive site boundary dose location. ,J The estimated direct radiation dose from all major sources combined for the most limiting site boundary location is listed in Table 4A. These site boundary doses assume a 100 percent occupancy factor, and take no credit for the shielding effect of any residential structure.
                                                                                                \.
Table 4B lists the combination of direct radiation doses 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 Part 190. For 2015, this annual dose was below the 25 mrem total body and organ limit, as well as the 75 mrem thyroid limit, of 40 CFR Part 190. 5 -::::.-..._.  
3
-:*' -. -..
 
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/soil 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 mrern/year to the whole body and any organ. After the period associated with Vermont Yankee operational control, the dose to the inadvertent intruder is to be limited to 5 mrern/year.
3.2 Doses From Noble Gases ODCM 3/4.3.2 limits the gamma air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I. By implementing these, ODCM 3/4.3.2 assures that the releases ofradioactive noble gases in gaseous effluents will be kept "as low as is reasonably achievable."
The projected dose from on-site disposals of septic waste, cooling tower silt, and sand/soil mixes is given in Appendix J of this report. .. The dose limits applicable to the on-site spreading of materials were met for the single spreading of septic waste in 2015, based on the combined dose from this spreading and all past spreadings.
Dose estimates due to the release of noble gases to the atmosphere are typically calculated at the site boundary, at the nearest resident in each of the sixteen principal compass directions, at the point of highest off-site ground level air concentration of radioactive materials, and at each of the milk animal locations located within five miles of the plant. For 2015, there were no noble gases detected in effluents released from the plant stack.
3 .6 On-Site Recreational Activities During 2015, no access to the on-site boat launching ramp located north of the intake structure was permitted for employees, their families, and guests. As such, there was no associated dose impact to members of the public. 6 REFERENCES
3.3 Doses From Iodine-131, Iodine-133, Tritium, Carbon-14, and Radionuclides in Particulate Form with Half-Lives Greater Than 8 Days ODCM 3/4.3.3 limits the organ dose to a member of the public from Iodine-131, Iodine-133, Tritium, Carbon-14, and radionuclides in particulate form with half-lives greater than 8 days (hereafter called "iodines and particulates") 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).
: 1. Off-site Dose Calculation Manual (ODCM), Revision 35, Entergy Nuclear Vermont Yankee, LLC, dated October 9, 2014. 2. Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 1.0 CFR Part 50, Appendix I," U.S. Nuclear Rygulatory Commission, Office of Standards Development, Revision 1, October 1977. 3. Safety Guide 1.23, "Onsite Meteorological Programs," U.S. Atomic Energy Commission, February 17, 1972. 4. Regulatory Guide "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. 7 A. l. 2. 3. B. l. 2. 3. c. l. 2. 3. 4. D. l. 2. 3. E. l. 2. TABLElA Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents  
By implementing the requirements of 10 CFR Part 50, Appendix I, ODCM 3/4.3.3 assures that the releases of iodines and particulates in gaseous effluents will be kept "as low as is reasonably achievable."
-Summation of All Releases Unit Quarter Quarter 1 2 Fission and Activation Gases Total release Ci ND ND Average release rate for period µCi/sec ND ND Percent ofODCM limit (1) % ND ND Iodines Total Iodine Ci ND ND Average release rate for period µCi/sec ND ND Percent of ODCM limit (3) % (3) (3) Particulates Particulates with T-112>8 days Ci ND ND Average release rate for period µCi/sec ND ND Percent of ODCM limit (3) % (3} (3) Gross alpha radioactivity Ci ND ND Tritium (4) Total release Ci 7.34E-02 7.09E-02 Average release rate for period µCi/sec 9.63E-03 9.22E-03 Percent ofODCM limit (3) % (3) (3) Carbon-14 Total release Ci ND ND Percent of ODCM limit (2) % 4.99E-04 4.53E-04 ND =Not Detected, or in the case of C-14, no power operations in 2015 leads to a zero estimate of C-14 production/release.
During 2015, a single frac tank was used on the Vermont Yankee site to temporarily store (outdoors) tritium-contaminated water extracted from onsite groundwater wells. The quantity of tritium released to the atmosphere through the evaporation of water from this frac tank was estimated, and the dose consequence to the maximally exposed individual was calculated.
Est. Total Error,% +/-2.30E+Ol NIA NIA +/-l.80E+Ol NIA NIA +/-l.80E+Ol NIA NIA NIA +/-l.80E+Ol NIA NIA NIA NIA (1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results. (2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form. Percentage of ODCM limit calculated using Method I dose results. ' (3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E. (4) Tritium released through evaporation from the onsite frac tank is included in these totals. 8 A. 1. 2. 3. B. 1. 2. 3. C. 1. 2. 3. 4. D. 1. 2. 3. E. 1. 2. TABLE IA (Continued)
Exposure pathways that could exist as a result of the planned (routine) release of iodines and particulates to the atmosphere include external irradiation from activity deposited onto the ground surface, inhalation, and ingestion of vegetables, meat and milk. Dose estimates were made at the site boundary and nearest resident in each of the sixteen principal compass directions, as well as all milk animal locations within five miles of the plant. The nearest resident and milk animals in each sector were identified by the most recent annual land use census as required by ODCM 3/4.5.2 (see Table 4C). Conservatively, a vegetable garden was assumed to exist at each milk animal and nearest resident location. Furthermore, the meat pathway was assumed to exist at each milk cow location since this data category is not part of the annual land use census. Doses were also calculated at the point of maximum ground level air concentration of radioactive materials in gaseous effluents and included the assumption that the inhalation, vegetable garden, and ground plane exposure pathways exist for an individual with a 100 percent occupancy factor.
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents  
It is assumed that milk and meat animals are free to graze on open pasture during the second and third quarters with no supplemental feeding. This assumption is conservative since most of the milk animals inventoried in the site vicinity are fed stored feed throughout the entire year with only limited grazing allowed during the growing season. It has also been assumed that only 50 percent of the iodine deposited from gaseous effluent is in elemental form (I2) and is available for uptake (seep. 6, Reference 2).
-Summation of All Releases Unit Quarter Quarter 3 4 Fission and Activation Gases Total release Ci ND ND Average release rate for period µCi/sec ND ND Percent ofODCM limit (1) % ND ND Iodines Total Iodine Ci ND ND Average release rate for period µCi/sec ND ND Percent of ODCM limit (3) % (3) (3) Particulates Particulates with T-1/2>8 days Ci ND ND Average release rate for period µCi/sec ND ND Percent of ODCM limit (3) % (3) (3) Gross alpha radioactivity Ci ND ND Tritium (4) Total release Ci l.14E-01 7.87E-02 Average release rate for period µCi/sec 1.46E-02 2.78E-02 Percent ofODCM limit (3) % (3) (3) Carbon-14 Total release Ci ND ND Percent ofODCM limit (2) % 7.29E-04 5.03E-04 Est. Total Error,% +/-2.30E+Ol NIA NIA +/-1.80E+Ol NIA NIA +/-1.80E+Ol NIA NIA NIA +/-1.80E+Ol NIA NIA NIA NIA ND= Not Detected, or in the case ofC-14, no power operations in 2015 leads to a zero estimate ofC-14 production/release.
4
(1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results. (2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form. Percentage of ODCM limit calculated using Method I dose results. ' (3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E. (4) Tritium released through evaporation from the onsite frac tank is included in these totals. 9
 
: 1. 2. 3. TABLEIB Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents  
During the non-growing season (first and fourth quarters), the milk animals are assumed to receive only stored feed. During the growing season (second and third quarters), all animal feed is assumed to be derived from fresh pasture. Usage factors for gaseous effluents are listed by age group and pathway in Table 4D.
-Elevated Releases Continuous Mode Quarter Nuclides Released Units 1 2 Fission Gases Argon-41 Ci ND ND Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-133m Ci ND ND Xenon-135 Ci ND ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Unidentified Ci ND ND Total for Period Ci ND ND Iodines lodine-131 Ci ND ND lodine-133 Ci ND ND lodine-135 Ci ND ND Total for Period Ci ND ND Particulates Strontium-89 Ci ND ND Strontium-90 Ci ND ND Cesium-134 Ci NP ND Cesium-137 Ci ND ND Barium-Lanthanum-140 Ci ND ND Manganese-54 Ci ND ND Chromium-51 Ci ND ND Cobalt-57 Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci ND ND Cerium-141 Ci ND ND Zinc-65 Ci ND ND Total for Period Ci ND ND ND Not Detected at the plant stack (1) There were no batch mode gaseous releases for this reporting period. 10 Batch Mode (1) Quarter 1 2 (1) (1) (1) (1) I (1) (1)
Table 4E provides other dose model parameter assumptions used in the dose assessments.
: 1. 2. 3. TABLElB (Continued)
In June 2009, the NRC issued Revision 2 of Regulatory Guide 1.21 (Reference 6) which introduced the term "principal radionuclide" in a risk-informed or dose context. A radionuclide can be considered a principal radionuclide if it contributes either (1) greater than 1 percent of the 10 CFR Part 50, Appendix I design objective dose for all radionuclides in the type of effluent being c01;1sidered, or (2) greater than 1 percent of the activity of all radionuclides in the type of effluent being considered. In addition to natural production in the environment, Carbon-14 is also produced in nuclear reactors as a function of power output, but at amounts muc11 less than those generated naturally or from past weapons testing. Since the --
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents  
time of the e&rlier publication of Regulatory Guide 1.21 (Revision 1) in 1974, commercial nuclear power 1
-Elevated Releases Continuous Mode . Quarter Nuclides Released Units 3 4. Fission Gases ( Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-133m Ci ND ND Xenon-135 Ci ND .ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Unidentified Ci ND ND Total for Period Ci ND ND Iodines Iodine-131 Ci ND ND Iodine-133 Ci ND ND Iodine-135 Ci ND ND Total for Period Ci ND ND Particulates Strontium-89 Ci ND ND Strontium-90 Ci ND ND Cesium-134 Ci ND ND Cesium-137 Ci ND ND Barium-Lanthanum-140 Ci ND ND Manganese-54 Ci ND ND Chromium Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci ND ND Cerium-141 Ci ND ND Cerium-144 Ci ND ND Zinc-65 Ci ND ND Total for Period Ci ND ND ND Not Detected at the Plant Stack (1) There were no batch mode gaseous releases for this reporting period. 11 Batch Mode (1) Quarter 3 4 (1) ' (1) (1) (1) (1) (1)
plants have decreased total radioactive effluents (other than Carbon-14) through improved fuel performance and waste management practices to the point today that Carbon-14 could be considered a principal radionuclide under today's definition. With the plant permanently shut down since December of2014, there was no plant related Carbon-14 production or associated dose impact for 2015.
TABLElC Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents-(Routine)
3.4 Whole Body Doses in Unrestricted Areas From Direct Radiation As opposed to previous years where 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 2015 due to the plant being permanently shut down.
Ground Level Releases <2) Continuous Mode Quarter Batch Mode Quarter Nuclides Released Units 1 (1) 2 (1) 1 (1) 2 (1) 1. Fission Gases Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci .Krypton-88 Ci Xenon-133 Ci Xenon-1.35 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci 2. Iodines lodine-131 Ci Iodine-133 Ci Iodine-I 35 Ci Total for Period Ci 3. Particulates Strontium-89 Ci Strontium-90 Ci _ Cesium-134 Ci Cesium-137 Ci Barium-Lanthanum-140 Ci Mimganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci Iron-55 Ci Total for Period Ci (1) There were no routine ground level gaseous releases for this reporting period. (2) No radioactively contaminated\used oil was burned during 2015. 12
The other fixed sources of direct and scatter radiation to the site boundary are the Independent Spent Fuel Storage Installation (ISFSI), the low level radioactive materials stored in the North Warehouse, the Low Level Waste Storage Pad Facility (no radioactive_ waste material stored on the pad in 2015), and old turbine rotors and casings in the Turbine Storage Facility. The annual dose is based on dose rate measurements in these storage facilities and is projected to impact the same most restrictive site boundary dose location.         ,J The estimated direct radiation dose from all major sources combined for the most limiting site boundary location is listed in Table 4A. These site boundary doses assume a 100 percent occupancy factor, and take no credit for the shielding effect of any residential structure.
: 1. 2. 3. TABLElC (Continued)
Table 4B lists the combination of direct radiation doses 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 Part 190. For 2015, this annual dose was below the 25 mrem total body and organ limit, as well as the 75 mrem thyroid limit, of 40 CFR Part 190.
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents  
5
-(Routine)
                                                                                            -
Ground Level Releases(2) Continuous Mode Quarter Nuclides Released Units 3 (I) 4 (I) Fission Gases Ktypton-85 Ci Krvoton-85m Ci Krvoton-87 Ci Krvoton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci Iodines lodine-131 Ci lodine-133 Ci lodine-135 Ci Total for Period Ci Particulates Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Barium-Lanthanum-140 Ci Manganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci Iron-55 CI Total for Period Ci (1) There were no ground level gaseous releases for this reporting period. (2) No radioactively contaminated used oil was burned during 2015. 13 Batch Mode Quarter 3 (I) 4 (1) '
                                                                          -::::.-..._. -:*' . - .. ~.
: 1. 2. 3. \ ' Nuclides Released Fission Gases Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-135  
 
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/soil 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 mrern/year to the whole body and any organ. After the period associated with Vermont Yankee operational control, the dose to the inadvertent intruder is to be limited to 5 mrern/year. The projected dose from on-site disposals of septic waste, cooling tower silt, and sand/soil mixes is given in Appendix J of this report.         ..
The dose limits applicable to the on-site spreading of materials were met for the single spreading of septic waste in 2015, based on the combined dose from this spreading and all past spreadings.
3 .6 On-Site Recreational Activities During 2015, no access to the on-site boat launching ramp located north of the intake structure was permitted for employees, their families, and guests. As such, there was no associated dose impact to members of the public.
6
 
REFERENCES
: 1. Off-site Dose Calculation Manual (ODCM), Revision 35, Entergy Nuclear Vermont Yankee, LLC, dated October 9, 2014.
: 2. Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 1.0 CFR Part 50, Appendix I," U.S.
Nuclear Rygulatory Commission, Office of Standards Development, Revision 1, October 1977.
: 3. Safety Guide 1.23, "Onsite Meteorological Programs," U.S. Atomic Energy Commission, February 17, 1972.
: 4. Regulatory Guide 1.~-11, "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.
7
 
TABLElA Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - Summation of All Releases Quarter           Quarter     Est. Total Unit 1                 2       Error,%
A.      Fission and Activation Gases
: l. Total release                                     Ci                 ND               ND       +/-2.30E+Ol
: 2. Average release rate for period                 &#xb5;Ci/sec             ND               ND           NIA
: 3. Percent ofODCM limit (1)                           %                 ND               ND           NIA B.        Iodines
: l. Total Iodine                                     Ci                 ND               ND       +/-l.80E+Ol
: 2. Average release rate for period                 &#xb5;Ci/sec             ND               ND           NIA
: 3. Percent of ODCM limit (3)                         %                 (3)               (3)         NIA
: c.      Particulates
: l. Particulates with T-112>8 days                   Ci                 ND               ND       +/-l.80E+Ol
: 2. Average release rate for period               &#xb5;Ci/sec               ND               ND           NIA
: 3. Percent of ODCM limit (3)                         %                 (3}               (3)         NIA
: 4. Gross alpha radioactivity                         Ci                 ND               ND           NIA D.      Tritium (4)
: l. Total release                                     Ci             7.34E-02         7.09E-02   +/-l.80E+Ol
: 2. Average release rate for period               &#xb5;Ci/sec           9.63E-03         9.22E-03       NIA
: 3. Percent ofODCM limit (3)                           %                 (3)               (3)         NIA E.      Carbon-14
: l. Total release                                     Ci                 ND               ND           NIA
: 2. Percent of ODCM limit (2)                         %               4.99E-04         4.53E-04       NIA ND =Not Detected, or in the case of C-14, no power operations in 2015 leads to a zero estimate of C-14 production/release.
(1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results.
(2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form.
Percentage of ODCM limit calculated using Method I dose results. '
(3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E.
(4) Tritium released through evaporation from the onsite frac tank is included in these totals.
8
 
TABLE IA (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - Summation of All Releases Quarter           Quarter     Est. Total Unit 3                 4       Error,%
A.      Fission and Activation Gases
: 1. Total release                                     Ci                 ND                 ND       +/-2.30E+Ol
: 2. Average release rate for period               &#xb5;Ci/sec               ND                 ND         NIA
: 3. Percent ofODCM limit (1)                         %                 ND                 ND         NIA B.        Iodines
: 1. Total Iodine                                     Ci                 ND                 ND       +/-1.80E+Ol
: 2. Average release rate for period                 &#xb5;Ci/sec             ND                 ND         NIA
: 3. Percent of ODCM limit (3)                         %                   (3)               (3)         NIA C.      Particulates
: 1. Particulates with T-1/2>8 days                   Ci                 ND                 ND       +/-1.80E+Ol
: 2. Average release rate for period               &#xb5;Ci/sec               ND                 ND         NIA
: 3. Percent of ODCM limit (3)                         %                 (3)               (3)         NIA
: 4. Gross alpha radioactivity                         Ci                 ND                 ND         NIA D.      Tritium (4)
: 1. Total release                                     Ci               l.14E-01         7.87E-02   +/-1.80E+Ol
: 2. Average release rate for period               &#xb5;Ci/sec             1.46E-02         2.78E-02       NIA
: 3. Percent ofODCM limit (3)                         %                   (3)               (3)         NIA E.      Carbon-14
: 1. Total release                                     Ci                 ND                 ND           NIA
: 2. Percent ofODCM limit (2)                         %               7.29E-04           5.03E-04       NIA ND= Not Detected, or in the case ofC-14, no power operations in 2015 leads to a zero estimate ofC-14 production/release.
(1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results.
(2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form.
Percentage of ODCM limit calculated using Method I dose results.               '
(3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E.
(4) Tritium released through evaporation from the onsite frac tank is included in these totals.
9
 
TABLEIB Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Elevated Releases Continuous Mode       Batch Mode (1)
Quarter            Quarter Nuclides Released               Units             1                2  1           2
: 1. Fission Gases Argon-41                     Ci             ND               ND Krypton-85                     Ci             ND               ND Krypton-85m                   Ci             ND               ND Krypton-87                     Ci             ND               ND Krypton-88                     Ci             ND               ND Xenon-133                     Ci             ND               ND Xenon-133m                   Ci             ND               ND Xenon-135                     Ci             ND               ND Xenon-135m                     Ci             ND               ND Xenon-138                     Ci             ND               ND Unidentified                   Ci             ND               ND Total for Period                 Ci             ND               ND (1)          (1)
: 2.      Iodines lodine-131                   Ci             ND               ND lodine-133                   Ci             ND               ND lodine-135                   Ci             ND               ND Total for Period                 Ci             ND               ND (1)          (1)
: 3.      Particulates Strontium-89                 Ci             ND               ND I
Strontium-90                 Ci             ND               ND Cesium-134                     Ci             NP               ND Cesium-137                     Ci             ND               ND Barium-Lanthanum-140           Ci             ND               ND Manganese-54                   Ci             ND               ND Chromium-51                   Ci             ND               ND Cobalt-57                     Ci             ND               ND Cobalt-58                   Ci             ND               ND Cobalt-60                     Ci             ND               ND Cerium-141                     Ci             ND               ND Zinc-65                       Ci             ND               ND Total for Period                 Ci             ND               ND (1)          (1)
ND    Not Detected at the plant stack (1) There were no batch mode gaseous releases for this reporting period.
10
 
TABLElB (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Elevated Releases Continuous Mode .     Batch Mode (1)
Quarter              Quarter Nuclides Released                 Units           3                 4. 3            4
: 1. Fission Gases                                       (
Krypton-85                       Ci             ND               ND Krypton-85m                     Ci             ND               ND Krypton-87                       Ci             ND               ND Krypton-88                       Ci             ND               ND Xenon-133                       Ci             ND               ND Xenon-133m                       Ci             ND               ND Xenon-135                       Ci             ND               .ND Xenon-135m                     Ci             ND               ND Xenon-138                       Ci             ND               ND Unidentified                     Ci             ND               ND Total for Period                   Ci             ND               ND (1)        '  (1)
: 2.      Iodines Iodine-131                       Ci             ND               ND Iodine-133                       Ci             ND               ND Iodine-135                       Ci             ND               ND Total for Period                   Ci             ND               ND (1)          (1)
: 3.      Particulates Strontium-89                     Ci             ND               ND Strontium-90                     Ci             ND               ND Cesium-134                       Ci             ND               ND Cesium-137                       Ci             ND               ND Barium-Lanthanum-140             Ci             ND               ND Manganese-54                   Ci             ND               ND Chromium                     Ci             ND               ND Cobalt-58                       Ci             ND               ND Cobalt-60                       Ci             ND               ND Cerium-141                       Ci             ND               ND Cerium-144                     Ci             ND               ND Zinc-65                         Ci             ND               ND Total for Period                   Ci             ND               ND (1)          (1)
ND     Not Detected at the Plant Stack (1)   There were no batch mode gaseous releases for this reporting period.
11
 
TABLElC Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents-(Routine) Ground Level Releases <2)
Continuous Mode           Batch Mode Quarter                Quarter Nuclides Released               Units             1 (1)           2 (1) 1 (1)         2 (1)
: 1.     Fission Gases Krypton-85                     Ci Krypton-85m                     Ci Krypton-87                     Ci
            .Krypton-88                     Ci Xenon-133                       Ci Xenon-1.35                     Ci Xenon-135m                     Ci Xenon-138                       Ci Unidentified                   Ci Total for Period                 Ci
: 2.       Iodines lodine-131                     Ci Iodine-133                     Ci Iodine-I 35                   Ci Total for Period                 Ci
: 3.       Particulates Strontium-89                   Ci Strontium-90                   Ci
_ Cesium-134                     Ci Cesium- 137                   Ci Barium-Lanthanum-140           Ci Mimganese-54                   Ci Chromium-51                   Ci Cobalt-58                     Ci Cobalt-60                     Ci Cerium-141                     Ci Zinc-65                       Ci Iron-55                       Ci Total for Period                 Ci (1) There were no routine ground level gaseous releases for this reporting period.
(2) No radioactively contaminated\used oil was burned during 2015.
12
 
TABLElC (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - (Routine) Ground Level Releases(2)
Continuous Mode        Batch Mode Quarter              Quarter Nuclides Released                 Units               3 (I)         4 (I) 3 (I)          4 (1)
: 1. Fission Gases Ktypton-85                       Ci Krvoton-85m                       Ci Krvoton-87                       Ci Krvoton-88                       Ci Xenon-133                         Ci Xenon-135                         Ci Xenon-135m                       Ci Xenon-138                         Ci Unidentified                     Ci Total for Period                   Ci                                                       '
: 2.      Iodines lodine-131                       Ci lodine-133                       Ci lodine-135                       Ci Total for Period                   Ci
: 3.      Particulates Strontium-89                     Ci Strontium-90                     Ci Cesium- 134                       Ci Cesium-137                       Ci Barium-Lanthanum- 140             Ci Manganese-54                     Ci Chromium-51                       Ci Cobalt-58                         Ci Cobalt-60                         Ci Cerium-141                       Ci Zinc-65                           Ci Iron-55                           CI Total for Period                   Ci (1) There were no ground level gaseous releases for this reporting period.
(2) No radioactively contaminated used oil was burned during 2015.
13
 
TABLElD Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Non-routine Releases Quarter                    Quarter Nuclides Released                Units              1(1)              2(1)      3(1)        4(1)
: 1.       Fission Gases Krypton-85                     Ci Krypton-85m                     Ci Krypton-87           "        Ci Krypton-88                     Ci Xenon-133                     Ci Xenon-135                     Ci Xenon-135m                    Ci Xenon-138                      Ci Unidentified                  Ci Total for Period                  Ci
: 2.        Iodines lodine-131                    Ci
              . lodine-133                    Ci Iodine-I 35                  Ci Total for Period                  Ci
: 3. '      Particulates Strontium-89                  Ci                                  )
Strontium-90                  Ci Cesium-134                    Ci Cesium- 137                    Ci
\              Barium-Lanthanum-140          Ci Manganese-54                  Ci Chromium-51                  Ci Cobalt-58                    Ci Cobalt-60                    Ci Cerium-141                    Ci Zinc-65                      Ci lron-55                      Cl Total for Period                  Ci (1) There were no non-routine ground level gaseous releases for this reporting period.
14
 
TABLE2A Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Summation of All Releases Est. Total Units      Quarter 1        Quarter 2        Error,%
A. Fission and Activation Products
: 1. Total Release (not includina tritium, aases, alpha)        Ci          ND                ND            N/A    I
: 2. Average Diluted Concentration Durina Period              uCi/ml        ND                ND
: 3. Percent of Aoolicable Limit (1)                            %          ND                ND
: 8. Tritium
: 1. Total Release                                              Ci      8.85E-03        9.05E-03      +/-2.00E+01  I
: 2.
* Averaae Diluted Concentration Durina Period              uCi/ml      1.67E-06        1.66E-06
: 3. Percent of Applicable Limit (1)                            %        5.90E-05        6.03E-05 C. Dissolved and Entrained Gases
: 1. Total Release                                              Ci          ND                ND            N/A    I
: 2. Averaae Diluted Concentration Durina Period              &#xb5;Ci/ml        ND                ND
: 3. Percent of Aoolicable Limit                                %          ND                ND D. Gross Al ha Radioactivit
: 1. Total Release                                              Ci          ND                ND            N/A E. Volume of Waste Release        rior to dilution              Liters                                          N/A I F. Volume of Dilution Water Used During Period                  Liters      3.89E+06        3.89E+06            (3)
ND    Not detected in liquid effluents.
(1)  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 abnorr:nal leakage of tritiated plant water into the underground environment.
The percent of the concentration limits specified in Appendix B to 1OCFR20.1001 - 20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.
(2)  Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015.
(3)  Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.
15
 
TABLE2A (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Summation of All Releases Est. Total Units    Quarter 3        Quarter 4        Error,%
A. Fission and Activation Products
: 1. Total Release (not including tritium, gases, alpha)        Ci        ND                ND            N/A    I
: 2. Average Diluted Concentration Durina Period            &#xb5;Ci/ml        ND                ND
: 3. Percent of Aoolicable Limit (1)                            %          ND                ND B. Tritium
: 1. Total Release                                              Ci      8.02E-03        7.50E-03      +/-2.00E+01  I
: 2. Average Diluted Concentration During Period            &#xb5;Ci/ml    1.46E-06        1.36E-06
: 3. Percent of Aonlicable Limit (1)                            %      5.35E-05        5.00E-05 C. Dissolved and Entrained Gases
: 1. Total Release                                              Ci        ND                ND            N/A    I
: 2. Average Diluted Concentration Durina Period            uCi/ml        ND                ND
: 3. Percent of Aoolicable Limit                                %          ND                ND D. Gross Al ha Radioactivi
: 1. Total Release                                              Ci        ND                ND            N/A E. Volume of Waste Release        rior to dilution              Liters                                        N/A l F. Volume of Dilution Water Used During Period                  Liters    3.89E+06        3.89E+06            (3)
ND    Not detected in liquid effluents.
(1)  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.
The percent of the concentration limits specified in Appendix B to 1OCFR20.1001 - 20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.
(2)  Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015.
(3)  Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.
16
 
TABLE2B Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Routine Releases Continuous Mode          Batch Mode I Nuclides Released                                Units    Quarter 1 I Quarter 2 Quarter 1 I Quarter 2 Strontium-89                                  Ci        -          -        -            -
Strontium-90                                  Ci        -          -        -            -
Cesium-134                                    Ci        -          -        -            -
Cesium-137                                    Ci        -          -        -            -
lodine-131                                    Ci        -          -        -            -
Cobalt-58                                      Ci        -          -        -            -
Cobalt-60                                      Ci        -          -        -            -
lron-59                                        Ci        -          -        -            -
Zinc-6.5                                      Ci        -          -        -            -
Manganese-54                                  Ci        -          -        -            -
Zirconium-Niobium-95                            Ci        -          -        -            -
Molvbdenum-99                                  Ci        -          -        -            -
Technetium-99                                  Ci        -          -        -            -
Barium-Lanthanum-140                          Ci        -          -        -            -
Cerium-141 Other (specify)                                Ci Ci Ci Unidentified                              I    Ci  I Total for Period (above)                      Ci Xe-133                                        Ci Xe-135                                        Ci ND    Not detected in liquid effluents.
Dash indicates no release of this type.
17
 
TABLE2B (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Routine Releases Continuous Mode          Batch Mode I Nuclides Released                                Units    Quarter 3  I Quarter 4 Quarter 3 I Quarter 4 Strontium-89                                  Ci        -          -        -            -
Strontium-90                                  Ci        -          -        -            -
Cesium-134                                    Ci        -          -        -            -
Cesium-137                                    Ci        -          -        -            -
lodine-131                                    Ci        -          -        -            -
Cobalt-58                                      Ci        -          -        -            -
Cobalt-60                                      Ci        -          -        -            -
lron-59                                        Ci        -          -        -            -
Zinc-65                                        Ci        -          -        -            -
Manganese-54                                  Ci        -          -        -            -
2irconium-Niobium-95                            Ci        -          -        -            -
    *Molybdenum-99                                  Ci        -          -        -            -
Technetium-99                                  Ci        -          -        -            -
Barium-Lanthanum-140                          Ci        -          -        -            -
Cerium-141 Other (specify)                                Ci Ci Ci Unidentified                              I    Ci  I Total for Period (above)                      Ci Xe-133                                        Ci Xe-135                                        Ci ND    Not detected in liquid effluents.
Dash indicates no release of this type.
18
 
TABLE3 Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Solid Waste and Irradiated Fuel Shipments Tabl..l fntersv Nucl*u vennontVanb:e Eftluentw WomD/spo,otAm111ot ~
                                                      ' f/ntonds-a-/!irZOJS Sol/d Wart~.o*dlrrodlottdFudSlr/pmonrs A. t,o114W>illi Slllol><d.OlMlto foto-orOl....,.llo** lm.u....tlucl}
a          ~
m!                No..
Cl              Ncl!lt ml                H. ..
                                                            .Q                NC!!!O        N/A ml              No ..          NA Ct              Horic-        NIA
                                                              **3          o.&.iE*OI        tlS!I cf            5.7Sr*02        ti$>>
mJ                Nnne          fl*
Q.              Nan*          NA mJ            *UOfUJS          US!I Cl          1.00[*cS        >JS!I
                                                                                                                              *! .
J:Ji' *!r'''* (;'~i;,~~M:;~~--:'.ii~ij,t>'*;,                      ~*,;i..~iw~~~ ...
_ *- _.                                                                      .....
Nut!'llt.&      PH<<:ttittt*          Nlldld*          ltrci:ntfll                        NutUitl'  P.af'C'ttl.tCU j"
                                                                                                                            -
tultM-t4            O.U'4            c~~ud'MI              U!J<.                        (Dh!i*liQ
                  ~'.\S              LM'll            C,o:b,.11>60          5131-K
                                      .......                                                              Cc1wmU1*
                                                                                                              .......
                                                                                                                              !!<
Colml*M Cftium-U7    ..    .,.,,,.      &deg;""'""'""I tl!Ullrit-ll1 u~
OJm Hldri..i                              ...... "
ltoA<H            .71.1$Ul*
u ...
                  -
OJ!"
              .....,__124          'U"'
11.J&K.
                                                  .....................
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                                                                              $.-
                                                                              ..,.,.
                                                                              ,,,  .
                                                                                  ,.
* _...__114 A:nrlmc--Ja                ...~-*
                                                        .......              9..1'1!1.
ESllCD lN 1                                                      ffll<l<                  W1 1-~~*''--~--i~~~~.j-~...!!.~~i--.....i.T~N~                              ..i.,_...f.~~~~~k-~~!!f~~~-
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        <iOC*G~IJ!l~,tnQ:mtlh" 19


Xenon-135m Xenon-138 Unidentified Total for Period Iodines lodine-131 . lodine-133 Iodine-I 35 Total for Period Particulates Strontium-89 Strontium-90 Cesium-134 Cesium-137 TABLElD Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Non-routine Releases Quarter Units 1(1) 2(1) Ci Ci " Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci ) Ci Ci Ci Barium-Lanthanum-140 Ci Manganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci lron-55 Cl Total for Period Ci (1) There were no non-routine ground level gaseous releases for this reporting period. 14 Quarter 3(1) 4(1)
TABLE2A Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents
-Summation of All Releases Units Quarter 1 Quarter 2 A. Fission and Activation Products 1. Total Release (not includina tritium, aases, alpha) Ci ND ND 2. Average Diluted Concentration Durina Period uCi/ml ND ND 3. Percent of Aoolicable Limit (1) % ND ND 8. Tritium Est. Total Error,% N/A I 1. Total Release Ci 8.85E-03 9.05E-03 +/-2.00E+01 I 2.
* Averaae Diluted Concentration Durina Period uCi/ml 1.67E-06 1.66E-06
: 3. Percent of Applicable Limit (1) % 5.90E-05 6.03E-05 C. Dissolved and Entrained Gases 1. Total Release Ci ND ND N/A 2. Averaae Diluted Concentration Durina Period &#xb5;Ci/ml ND ND 3. Percent of Aoolicable Limit % ND ND D. Gross Al ha Radioactivit
: 1. Total Release Ci ND ND N/A E. Volume of Waste Release rior to dilution Liters N/A I F. Volume of Dilution Water Used During Period Liters 3.89E+06 3.89E+06 (3) ND Not detected in liquid effluents.
(1) 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 abnorr:nal leakage of tritiated plant water into the underground environment.
The percent of the concentration limits specified in Appendix B to 1OCFR20.1001
-20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.
(2) Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015. (3) Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.
15 I TABLE2A (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents
-Summation of All Releases Units Quarter 3 Quarter 4 A. Fission and Activation Products 1. Total Release (not including tritium, gases, alpha) Ci ND ND 2. Average Diluted Concentration Durina Period &#xb5;Ci/ml ND ND 3. Percent of Aoolicable Limit (1) % ND ND B. Tritium Est. Total Error,% N/A I 1. Total Release Ci 8.02E-03 7.50E-03 +/-2.00E+01 I 2. Average Diluted Concentration During Period &#xb5;Ci/ml 1.46E-06 1.36E-06 3. Percent of Aonlicable Limit (1) % 5.35E-05 5.00E-05 C. Dissolved and Entrained Gases 1. Total Release Ci ND ND N/A 2. Average Diluted Concentration Durina Period uCi/ml ND ND 3. Percent of Aoolicable Limit % ND ND D. Gross Al ha Radioactivi
: 1. Total Release Ci ND ND N/A E. Volume of Waste Release rior to dilution Liters N/A l F. Volume of Dilution Water Used During Period Liters 3.89E+06 3.89E+06 (3) ND Not detected in liquid effluents.
(1) 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.
The percent of the concentration limits specified in Appendix B to 1OCFR20.1001
-20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.
(2) Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015. (3) Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.
16 I TABLE2B Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents
-Routine Releases Continuous Mode Batch Mode I Nuclides Released Units Quarter 1 I Quarter 2 Quarter 1 I Quarter 2 Strontium-89 Ci ----Strontium-90 Ci ----Cesium-134 Ci ----Cesium-137 Ci ----lodine-131 Ci ----Cobalt-58 Ci ----Cobalt-60 Ci ----lron-59 Ci ----Zinc-6.5 Ci ----Manganese-54 Ci ----Zirconium-Niobium-95 Ci ----Molvbdenum-99 Ci ----Technetium-99 Ci ----Barium-Lanthanum-140 Ci ----Cerium-141 Other (specify)
I Ci I Ci Ci Unidentified Ci Total for Period (above) Ci Xe-133 Ci Xe-135 Ci ND Not detected in liquid effluents.
Dash indicates no release of this type. 17 TABLE2B (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents
-Routine Releases Continuous Mode Batch Mode I Nuclides Released Units Quarter 3 I Quarter 4 Quarter 3 I Quarter 4 Strontium-89 Ci ----Strontium-90 Ci ----Cesium-134 Ci ----Cesium-137 Ci ----lodine-131 Ci ----Cobalt-58 Ci ----Cobalt-60 Ci ----lron-59 Ci ----Zinc-65 Ci ----Manganese-54 Ci ----2irconium-Niobium-95 Ci ----* Molybdenum-99 Ci ----Technetium-99 Ci ----Barium-Lanthanum-140 Ci ----Cerium-141 Other (specify)
I Ci I Ci Ci Unidentified Ci Total for Period (above) Ci Xe-133 Ci Xe-135 Ci ND Not detected in liquid effluents.
Dash indicates no release of this type. 18 TABLE3 Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Solid Waste and Irradiated Fuel Shipments Tabl .. l fntersv Nucl*u vennontVanb:e Eftluentw WomD/spo,otAm111ot ' f/ntonds-a-/!irZOJS Sol/d A. t,o114W>illi Slllol><d.OlMlto foto-orOl....,.llo**
lm.u....tlucl}
a m! No .. Cl Ncl!lt ml H. .. .Q NC!!!O N/A ml No .. NA Ct Horic-NIA **3 o.&.iE*OI tlS!I cf 5.7Sr*02 ti$>> mJ Nnne fl* Q. Nan* NA mJ *UOfUJS US!I Cl 1.00[*cS >JS!I J:Ji' *!r'''*
Nut!'llt.&
PH<<:ttittt*
Nlldld* ltrci:ntfll tultM-t4 O.U'4 U!J<. .....
LM'll C,o:b,.11>60 5131-K Colml*M ....... &deg;""'""'""I Cftium-U7
.,.,,,. tl!Ullrit-ll1 OJm _ .. *-ltoA<H .71.1$Ul*
Hldri..i OJ!" ...... u ... ..... ,__124 'U"' ..................... " $.--11.J&K. _ .. ..,.,. H2tld*'1 ,,, .
* _...__114 A:nrlmc--Ja
... , .. ....... 9..1'1!1.
ESllCD lN
... NutUitl' (Dh!i*liQ Cc1wmU1* ....... 1 ffll<l< W1
..
* 19 * ! . P.af'C'ttl.tCU j" !!< -
TABLE 3 (continued)
TABLE 3 (continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Solid Waste and Irradiated Fuel Shipments EnleJIY NudearVennont Yanlcee E/ffllflll and W-Olsposc/
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Solid Waste and Irradiated Fuel Shipments Ta~lt'-3 EnleJIY NudearVennont Yanlcee E/ffllflll and W-Olsposc/ An1"Ull Rqiott Jlrlnl oad l'o<mh 4uoJfen:fur 2015 So/Id Wmt., and lrrodi'med Fur:UhlJ11Mflfl II. 5olldW..1~Sl!l,ppodOlf*Slt*lor&deg;",'i'I"' Dhpoool lnotflmll>IO<I l'ucQ J, T~otwa:ne
An1"Ull Rqiott Jlrlnl oad l'o<mh 4uoJfen: fur 2015 So/Id Wmt., and lrrodi'med Fur:UhlJ11Mflfl II.
: 1. < ,;\S!ii\ltdl1oolti1.:?ii&#xa3;w:c,,, <'''<:,"!121"''*"                   ~:r10~.t\iiB&Xi  /i1k1T0inilt..&ilP
Dhpoool lnotflmll>IO<I l'ucQ J, 1 .. < ,;\S!ii\ltdl1oolti1.:?ii&#xa3;w:c,,, <'''<:,"!121"''*"  
        ~fo:ol !!""rf<l""'!'- ....                                 ml             1.45!.0I           t%SS a             3001101           !JS!i.
/i1k1T0inilt..&ilP  
PIYC~..au~.<<lUllElfllftll            fir.               ml                 Ncnc           NIA Cl                 Hn**           N/A c.ln*~~l\.l;f!IUd11c11:b.tU                              mJ                                  II/A 0                 """"
!!""rf<l""'!'-
N&deg;"'           N/A
.... ml 1.45!.0I t%SS a 3001101 !JS!i.
          &deg;'""'""                                                                     ....
fir. ml Ncnc NIA Cl Hn** N/A mJ """" II/A 0 N&deg;"' N/A 4 &deg;'""'"" mJ* Plone NIA Q ,. ... N/A :.a ml NOl>O Ii/A C1 Nooe N/A b ml l.BOfiOJ tis5 0 9.JU*Ol m" c mJ No.,. NIA Cl N-411e 11/11 fif*Olb* ta.g ml 2.JSE!OI us" 0 5.(19&#xa3;.QS i2SK :!. &11...,* cl Molor Nutlldc tomi>MlllO ISV TYl>O of W11u.1. Nudlde P:1rc"ntUl..
                                                                                      ,Plone mJ*                                NIA 4
N'iKUdo 1'1m:ootf11 NU<liile C>rbon 14 :um Ccb1tl*SI UJlil """' Cobol<H D.9. Cul:ri)fl60 nn" Collall"O Ji.ll" Chlomlum-S1 1.)211 Citl.it1:t1*U7 J.Ollt. C0Jr;m.U1 ll20ll "&deg;"'.SS IUSK .,,,.n ,974t'o l.11'1 troon-!9 IU>>I Nldd-63 ll.12" ....... H .. 54 J.IOK Zllic.*6S 1a.uw.
Q                                  N/A
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0.2"" Antt-...JJ.S  
:!. &11...,* cl Molor Nutlldc tomi>MlllO       ISV TYl>O of W11u.1.
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Nudlde                 P:1rc"ntUl..           N'iKUdo           1'1m:ootf11       NU<liile       Por<mrlll  .,,,_  Po1m11U1 C>rbon 14                   :um                                       UJlil                                     toti-.i    10.s'!K Cobol<H                     D.9.
...... (11 *ncfudrs (ITl!y1bDH" nud?dd thi1 .11egruitt th.an u.1\1of1M totaJ Kf1WV U:-0,.
Ccb1tl*SI Cul:ri)fl60             nn"             """'                      O:Wm-Sl?  %Q.ft$10 Collall"O                   Ji.ll"       Chlomlum-S1                 1.)211                                   Mi~...-    5111' Citl.it1:t1*U7               J.Ollt.       C0Jr;m.U1                 ll20ll                                     Z>titH  .., .l"'
Ctte\ 0pt"O-l1ont.
                "&deg;"'.SS                   IUSK               .,,,.n               ,974t'o MIM~54                        l.11'1             troon-!9               IU>>I Nldd-63                   ll.12"         . . . . . . .H . .54         J.IOK Zllic.*6S                 1a.uw.           Mo&lu~!JJ                  um H!~J                    1,28%
WCS-.WHteCentr<<r..r.tr.tw.ius G'OC. Ctwt-tlit1tt x Truck Por<mrlll
Anbm01Pt*l2*                 0.2""
.,,,_ Po1m11U1 toti-.i 10.s'!K O:Wm-Sl? %Q.ft$10 5111' Z>titH .. , .l"' 20 
Antt-...JJ.S                 a*1s~
* (a) (b) (c) (d) (e) (f) (g) TABLE4A Entergy Nuclear Vermont Yankee Maximum* Quarterly and Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 Source Total Body Dose Footnotes Organ Dose Footnotes Beta Air (mrad) Footnotes Gamma Air (mrad) Footnotes (10CFR50, Appendix I) Dose (mrem)(a) 3rd Quarter 9.80E-07 l.OOE-06 8.88E-07 (c) (c) (c) 9.80E-07 l.OOE-06 8.88E-07 (c) (c) (c) l.64E-05 4.24E-05 (g) (t) (d) (d) (d) 0.72 Year(b) 8.31E-07 3.70E-06 (c) (c) 8.31E-07 3.70E-06 (c) (c) (t) (d) "Maximum" means the largest fraction of the corresponding 10CFR50, Appendix I dose design objective.
                                                              *trrte..&#xa3;5             ......
The lettered footnotes indicate the age group, organ, and location of the dose receptor, where appropriate.
(11 *ncfudrs (ITl!y1bDH" nud?dd thi1 .11egruitt th.an u.1\1of1M totaJ Kf1WV x                  Truck Glt*Qi~t<Rwd U:-0,. 9't-~t Ctte\ 0pt"O-l1ont.
The yearly dose is the sum of the doses for each quarter, or a full annual assessment.
WCS-.WHteCentr<<r..r.tr.tw.ius SS*ft1b:fn$.ilttl1~
The critical age group/organ for the Maximum Exposed Individual (MEI) is the Adult/Total Body and all organs (except Bone) from the release ofH-3 to groundwater.
G'OC. ~ G1tt1t"f~ ~ Ctwt-tlit1tt 20
There were no noble gas releases in this quarter. Maximum direct dose point located on the old west site boundary, approximately 208 meters from the Turbine Building (per ODCM, Rev. 35, Sect. 6.11.1). The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location WNW, 2400 meters from the stack. The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location NW, 2900 meters from the stack. 21 TABLE4B Entergy Nuclear Vermont Yankee Maximum* Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 (40CFR190)
 
Pathway Total Body Maximum Organ (mrem) (mrem) Thyroid (mrem) Direct External (a) (b) 2.88 2.88 2.88 Liquids (c) 3.70E-06 3.70E-06 3.70E-06 Gases (c)' l.07E-04 l.07E-04 l.07E-04 Annual Total ( d) 2.88 2.88 2.88 * (a) (b) (c) (d) 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. No residential shielding credit or occupancy time fraction (i.e., occupancy is assumed to be I00%) 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 I. I 09 (Reference
TABLE4A Entergy Nuclear Vermont Yankee Maximum* Quarterly and Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 (10CFR50, Appendix I)
: 2) and an annual occupancy time of 6760 hours). The direct dose reported here was calculated using the current ODCM methodology 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. Maximum dose to any organ over all age groups for each release. Annual dose 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. 22 Sector N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TABLE4C Receptor Locations Entergy Nuclear Vermont Yankee Site Boundary (I) Nearest Resident<2 l (meters) (meters) 400 1400 350 1384. 350 1255 400 966 500 933 700 1915 \ 750 1963 850 2044 385 644 300 451 250 418 250 451 300 628 400 1062 550 2253 550 1738 (1) Site boundary locations taken from Table 6.10.2 of the ODCM. Nearest Mille Animal <2 l (meters) --5520 (cows) --------3600 (cows) --------9730 (cows) 820 (cows) ------(2) The location(s) given are based on information from the Vermont Yankee 2015 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.
Dose (mrem)(a) 3rd Source                                                                                Year(b)
Quarter Total Body Dose            9.80E-07      l.OOE-06      8.88E-07        8.31E-07    3.70E-06 Footnotes        (c)           (c)           (c)             (c)           (c)
Organ Dose                  9.80E-07     l.OOE-06     8.88E-07         8.31E-07    3.70E-06 Footnotes        (c)           (c)           (c)             (c)           (c) l.64E-05     4.24E-05 (g)           (t)             (t)
Beta Air (mrad)
Footnotes        (d)           (d)           (d)             (d)
Gamma Air (mrad)
Footnotes 0.72
*      "Maximum" means the largest fraction of the corresponding 10CFR50, Appendix I dose design objective.
(a)    The lettered footnotes indicate the age group, organ, and location of the dose receptor, where appropriate.
(b)    The yearly dose is the sum of the doses for each quarter, or a full annual assessment.
(c)    The critical age group/organ for the Maximum Exposed Individual (MEI) is the Adult/Total Body and all organs (except Bone) from the release ofH-3 to groundwater.
(d)    There were no noble gas releases in this quarter.
(e)    Maximum direct dose point located on the old west site boundary, approximately 208 meters from the Turbine Building (per ODCM, Rev. 35, Sect. 6.11.1).
(f)    The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location WNW, 2400 meters from the stack.
(g)    The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location NW, 2900 meters from the stack.
21
 
TABLE4B Entergy Nuclear Vermont Yankee Maximum* Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 (40CFR190)
Total Body         Maximum Organ                 Thyroid Pathway (mrem)                 (mrem)                     (mrem)
Direct External (a) (b)               2.88                   2.88                     2.88 Liquids (c)                       3.70E-06               3.70E-06                 3.70E-06 Gases (c)'                         l.07E-04               l.07E-04                 l.07E-04 Annual Total (d)                     2.88                   2.88                     2.88
* 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 I00%)
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 I. I 09 (Reference 2) and an annual occupancy time of 6760 hours).
(b)  The direct dose reported here was calculated using the current ODCM methodology 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.
(c)  Maximum dose to any organ over all age groups for each release.
(d)  Annual dose 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.
22
 
TABLE4C Receptor Locations Entergy Nuclear Vermont Yankee Nearest Mille Sector          Site Boundary (I)   Nearest Resident<2l      Animal <2l (meters)            (meters)             (meters)
N                  400                 1400                   --
NNE                  350                 1384.           5520 (cows)
NE                  350                 1255                   --
ENE                  400                 966                   --
E                  500                 933                   --
ESE                  700                 1915
                                                                  \
                                                                                  --
SE                  750                1963            3600 (cows)
SSE                  850                 2044                 --
s                  385                 644                 --
SSW                  300                 451                   --
SW                  250                 418                 --
WSW                    250                 451             9730 (cows) w                  300                 628             820 (cows)
WNW                    400                 1062                 --
NW                    550                 2253                 --
NNW                    550                 1738                   --
(1) Site boundary locations taken from Table 6.10.2 of the ODCM.
(2) The location(s) given are based on information from the Vermont Yankee 2015 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.
* 23
* 23
* Age *Fish Group (kg/yr) Adult 21 Teen 16 Child 6.9 Infant 0 TABLE4D Usage Factors for Environmental Pathways Entergy Nuclear Vermont Yankee* Potable Veg. Leafy Veg. Milk Water (I/yr) (kg/yr) (kg/yr) (I/yr) 730 520 64 310 510 630 42 400 510 520 26 330 330 0 0 330 Regulatory Guide 1.109, Table E-5 (Reference 2). 24 Meat Inhalation (kg/yr) (m 3/yr) 110 8,000 65 8,000 41 3,700 0 1,400 I Variable I YV Agricultural Productivity (kg/m 2) p Soil Surface Density (kiz/m 2) T Transport Time to User (hrs) TB Soil Exposure Time(a)(hrs)
 
TE Crop Exposure Time to Plume (hrs) TH Holdup After Harvest (hrs) QF Animals Daily Feed (kg/dav) FP Fraction of Year on Pasture FS Fraction Pasture Feed When on Pasture(c)
TABLE4D Usage Factors for Environmental Pathways Entergy Nuclear Vermont Yankee*
Note: Footnotes on following page. TABLE4E Environmental Parameters for Gaseous Effluents
Age        *Fish      Potable       Veg.     Leafy Veg. Milk   Meat  Inhalation Group      (kg/yr)      Water       (kg/yr)      (kg/yr)    (I/yr) (kg/yr)   (m3/yr)
* Entergy Nuclear Vermont Yankee Vegetables I Cow Milk Goat Milk . Stored I Leafy I Pasture Stored Pasture Stored 2 2 0.70 2 0.70 2 240 240 240 240 240 240 ----48 48 48 48 131,400 131,400 131,400 131,400 131,400 131,400 1,440 1,440 720 1,440 720 1,440 1,440 24 0 2,160 0 2,160 ---M 50 so 6 6 "' ----(b) --(b) ------1 --1 --25 I Meat I I Pasture I Stored I 0.70 2 240 240 480 480 131,400 131,400 720 1,440 0 2,160 50 50 (b) --1 --
(I/yr)
FG FL FI H * (a) (b) (c) (d) I Variable Fraction of Stored Vegetables Grown in Garden Fraction of Leafy Vegetables Grown in Garden Fraction Elemental Iodine = 0.5 Absolute Humidity=
Adult        21        730         520           64       310     110      8,000 Teen        16        510         630           42       400     65      8,000 Child        6.9        510         520           26       330     41      3,700 Infant        0        330           0             0       330     0      1,400
5.6Cd) TABLE 4E (Continued)
* Regulatory Guide 1.109, Table E-5 (Reference 2).
Environmental Parameters for Gaseous Effluents Entergy Nuclear Vermont Yankee Vegetables I Cow Milk Stored Leafy Pasture Stored 0.76 --------1.0 --------------------From VY ODCM, Table 6.9.l (Reference 1). Goat Milk Meat Stor--' n-ctnre Stored II ----------------------------I ----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 hours (one year) for all pathways.
24
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. 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. For all Method II analyses, an absolute humidity value equal to 5.6 (gm/m 3) shall be used to reflect conditions in the Northeast (
 
TABLE4E Environmental Parameters for Gaseous Effluents
* Entergy Nuclear Vermont Yankee I        Vegetables     I         Cow Milk               Goat Milk       I        Meat          I Variable I . Stored I Leafy I         Pasture      Stored    Pasture       Stored I Pasture Stored I
Agricultural Productivity YV      (kg/m2) 2              2         0.70            2       0.70           2       0.70           2 p                                        240          240        240           240       240           240       240         240 Soil Surface Density (kiz/m2)
                                                                                                                                          ~
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     131,400 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/dav)          --           -M 50           so         6             6 "'     50          50 FP    Fraction of Year on Pasture          --           --         (b)           --       (b)           --       (b)          --
FS    Fraction Pasture Feed When on Pasture(c)
                                              --           --           1           --         1             --         1           --
Note: Footnotes on following page.
25
 
TABLE 4E (Continued)
Environmental Parameters for Gaseous Effluents Entergy Nuclear Vermont Yankee I        Vegetables         I       Cow Milk                     Goat Milk                      Meat Variable                      Stored       Leafy         Pasture         Stored                      Stor--'      n-ctnre      Stored  II FG      Fraction of Stored Vegetables          0.76           --           --             --           --             --           --           --
Grown in Garden FL      Fraction of Leafy Vegetables            --           1.0            --             --           --             --             --           --
Grown in Garden FI    Fraction Elemental Iodine = 0.5          --             --           --             --           --             --           --           --
H      Absolute Humidity= 5.6Cd)                --             --           --             --           --             --         I --           --
* From VY ODCM, Table 6.9.l (Reference 1).
(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 hours (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:==
==Reference:==
Health Physics Journal, Volume 39 (August), 1980; Pages 318-320, Pergammon Press).                                                  ,
26
TABLE4F Environmental Parameters for Liquid Releases (Tritium) Via Groundwater Entergy Nuclear Vermont Yankee Variable Potable Water    Aquatic Food      Stored Veg.      Leafy Veg.        Meat  Cow Milk Name      (Units)
                                                        ~
Mixing Ratio      3.23E-06        5.62E-04        3.23E-06        3.23E-06      3.23E-06 3.23E-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)
    ,-
27
TABLE5A VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS A                CLASS FREQUENCY (PERCENT) =    1.15 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE      E  ESE      SE    SSE      s  SSW    SW  WSW      w  WNW    NW  NNW VRBL    TOTAL MPH CALM      4    0    0    0      0    0      0        0    0    0      0    0      0    0    0    0      0      4 (1)  4.00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .00  .00  .00  .00    4.00 (2)  .05    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .00  .00  .00  .00      .05 C-3      2    0    1    1      6    3      2        0    0    0      0    0      0    0    0    4      0      19 (1)  2.00    .00 1. 00 1.00  6.00  3.00  2.00      .00    .00  .00  .00  .00    .00  .00  .00  4.00  .00    19.00 (2)  .02    .00  .01  .01    .07  .03  .02      .00    .00  .00  .00  .00    . 00  .00  .00  .05  .00      .22 .
4-7      1    1    0    5    18  14      3        3    1    0      2    0      1    0    2    3      0      54 (1)  1. 00 1. 00  .00  5.00 18.00 14.00  3.00    3.*00  1. 00  .00  2.00  .00  1. 00  .00  2.00  3.00  .00    54.00 (2)  .01    .01  .00  .06    .21  .16  .03      .03    .01  .00  .02  .00    .01  .00  . 02  .03  .00      . 62 8-12      0    1    0    0      0    8      5        3    1    0      0    1      0    0    0    3      0      22 (1)  .00  1. 00  .00  .00    .00 8.00  5.00    3.00  1. 00  .00  .00  1. 00  .00  .00  .00  3.00  .00    22.00 (2)  .00    .01  .00  .00    .00  .09  .06      .03    .01  .00  .00  .01    .00  .00  .00  .03  .00      .25 13-18      0    0    0    0      0    0      0        0    0    0      0    0      0    1    0    0      0      1 (1)  .00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  1. 00  .00  .00  .00    1. 00 (2)  .00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .01  .00  .00  .00      .01 19-24      0    0    0    0      0    0      0        0    0    0      0    0      0    0    0    0      0      0 (1)  .00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .00  .00  .00  .00      .00 (2)  .00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .00  .00  .00  . .00    .00 GT 24      0    0    0    0      0    0      0        0    0    0      0    0      0    0    0    0      0      0 (1)  .00    .00  .00  .00    .00  .00  .00      .,00  .00  .00  .00  .00  .. 00  .00  .00  .00  .oo      .00 (2)  .00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .00  .00  .00  .00      .00 ALL SPEEDS        7    2    1    6    24  25      10        6    2    0      2    1      1    1    2  10      0    100 (1)  7.00  2.00  1. 00 6.00 24.00 25.00 10.00    6.00  2.00  .00  2.00  1.00  1. 00  1. 00 2.00 10.00  .00  100.00 (2)  .08    .02  .01  .07    .28  .29  .. 11    .07    .02  .00    .02  .01    .01  .01  .02  .11  .00    1.15 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 28
TABLE SB VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS B              CLASS FREQUENCY (PERCENT) =  2.05 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE    E  ESE    SE    SSE      s  SSW    SW  WSW      w  WNW    NW  NNW  VRBL  TOTAL MPH CALM      0    0    0    0    0      0    0      0      0    0    0    0      0    0    0    0    0      0 (1)  .00    .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .00  .00  .00    .00 (2)  .00    .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .00  .00  .00    .00 C-3      4    5    5    2    1      3    0      2      1    0    0    0      0    2    0    2    0    27 (1)  2.25  2.81  2.81  1.12  .56  1. 69  .00  1.12    .56  .00  .00  .00  .00  1.12  .00  1.12  .00  15.17 (2)  .05    .06  .06  .02  .01  .03  .00    .02    .01  .00  .00  .00  .00  .02  .00  .02  .00    .31 4-7    10    2    3    6    19    18  11      15      5    1    0    0      0    1    1    4    0    96 (1)  5. 62 1.12  1. 69 3.37 10.67 10.11  6.18  8.43  2.81  .56  .00  .00  .00  .56  .56  2.25  .00  53.93 (2)  .11    .02  .03  .07  .22  .21  .13    .17    .06  .01  .00  .00  .00  .01  .01  .05  .00  1.10 8-12      2    1    0    0    0      2    4      17      8    0    0    0      2    2    2    5    0    45 (1)  1.12    .56  .00  .00  .00  1.12  2.25  9.55  4.49  .00  .00  .00  1.12  1.12 1.12  2.81  .00  25.28 (2)  .02    .01  .00  .00  .00  .02  .05    .20    .09  .00  .00  .00  .02  .02  . 02  .06  .00    .52 13-18      0    0    0    0    0      0    0      2      2    0    0    0      0    0    0    5    0      9 (1)  .00    .00  .00  .00  .00  .00  .00  1.12  1.12  .00  .00  .00  .00  .00  .00  2.81  .00  5.06 (2)  .00    .00  .00  .00  .00  .00  .00    . 02    .02  .00  .00  .00  .00  .00  .00  .06  .00    .10 19-24      0    0    0    0    0      0    0      0      0    0    0    0      0    0    1    0    0      1 (1)  .00  .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .56  .00  .00    .56 (2)  .00  .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .01  .00  .00    .01 GT 24      0    0    0    0    0      0    0      0      0    0    0    0      0    0    0    0    0      0 (1)  .00  .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .00  .00  .00    .00 (2)  .00  .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .00  .00  .00    .00 ALL SPEEDS      16    8    8    8    20    23  15      36    16    1    0    0      2    5    4  16    0    178 (1)  8.99  4.49  4.49  4.49 11.24 12.92  8.43 20.22    8.99  .56  .00  .00  1.12  2.81 2.25  8.99  .00 100.00 (2)  .18  .09  .09  .09  .23  .26  .17    .41    .18  .01  .00  .00  . 02  .06  .05  .18'  .00  2.05 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 29
TABLE5C VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS C              CLASS FREQUENCY (PERCENT) =    3.60 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE      E  ESE    SE    SSE      s  SSW    SW  WSW      w  WNW    NW  NNW  VRBL  TOTAL MPH CALM      0    1    0    0    0    5    0      0    0    0    0      0    0    0    0    0    0      6 (1)  .00    .32  .00  .00    .00 1. 60  .00    .00  .00  .00  .00    .00  .00  .00  .00  .00  .00  1. 92 (2)  .00    .01  .00  .00    .00  .06  .00    .00  .00  .00  .00    .00  .00  .00  .00  .00  .00    .07 C-3      6    5    5    5    4    13    7      4    2    0    0      0    0    1    2    0    0      54 (1)  1. 92 1. 60 1. 60 1. 60 1.28  4.15  2.24  1. 28  . 64  .00  .00    .00  .00  .32  . 64  .00  .oo  17.25 (2)  .07    .06  .06  .06    .05  .15  .08    .05  .02  .00  .00    .00  .00  .01  .02  .00  .00    . 62 4-7    13    9    4    10    13    18  25      29    7    2    1      0    0    1    9    18    0    159 (1)  4.15  2.88  1. 28 3.19  4.15  5.75  7.99  9.27  2.24  .64  .32 I  .00  .00  .32  2.88  5.75  .00  50.80 (2)  .15    .10  .05  .11    .15  .21  .29    .33  .08  .02  .01    .00  .00  .01  .10  .21  .00  1. 83 8-12      11    3    2    0    0    2    1      17    19    2    0      0    3    3    6    12    0      81 (1)  3.51    .96  . 64  .00    .00  . 64  .32  5.43  6.07  . 64  .00  -* 00  .96  .96  1. 92 3.83  .00  25.88 (2)  .13    .03  .02  .00    .00  .02  .01    .20  .22  .02  .00    .00  ."03  .03  .07  .14  .00    .93 13-18      1    0    0    0    0    0    0      1    1    0    0      0    1    0    3    6    0      13 (1)  .32    .00  .00  .00    .00  .00  .00    .32  .32  .00  .00    .00  .32  .00  .96  1. 92  .00  4.15 (2)  .01    .00  .00  .00    .00  .00  .00    .01  .01  .00  .00    .00  .01  .00  .03  .07  .00    .15 19-24      0    0    0    0    0    0    0      0    0    0    0      0    0    0    0    0    0      0 (1)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00  .00    .00  .00  .00  .00  .00  .00    .00 (2)  .00    .00  .oo  .00    .00  .00  .00    .00  .00  .00  .00    .00  .00  .*oo  .00  .00  .00    .00 GT 24      0    0    0    0    0    0    0      0    0    0    0      0    0    0    0    0    0      0 (1)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00  .00    .00  .00  .00  .00  .00  .00    .00 (2)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00  .00    .00  .00  .00  .00  .00  .00    .'oo ALL SPEEDS        31    18    11    15    17    38  33      51    29    4    1      0    4    5    20    36    0    313 (1)  9.90  5.75  3.51  4.79  5.43 12.14 10.54 16.29  9.27  1. 28  .32    .00  1. 28 1. 60 6.39 11.50  .00 100.00 (2)  .36    .21  .13  .17    .20  .44  .38    .59  .33  .05  .01    .00  .05  .06  .23  .41  .00  3.60
'(l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO . 95 MPH) 30
TABLE5D VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS D                CLASS FREQUENCY (PERCENT) =    46.37 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE      E  ESE    SE    SSE      s  SSW    SW  WSW      w  WNW    NW  NNW  VRBL  TOTAL MPH CALM      26    19    21    31    49    91    99      74    24    4      4    5    4      1    7    27    0    486 (1)  . 64  .47  .52  .77  1. 21  2.25  2.45    1. 83  .59  .10    .1.0  .12  .10    .02  .17  . 67  .00  12.04 (2)  .30    .22  .24  .36    .56  1. 05 1.14    .85    .28  .05  .05    .06  .05    .01  .08  .31  .00  5.58 C-3    74    41    42    31    55    73    73      94    73    41    22    26    34    47    63  107    0    896 (1)  1. 83 1. 02 1. 04  .77  1. 36  1. 81 1. 81  2.33  1. 81 1. 02  .55    . 64  .84  1.16  1. 56 2.65  .00  22.20 (2)  .85    .47  .48  .36    . 63  .84  .84    1. 08  .84  .47  .25    .30  .39    .54  . 72 1.23  .00  10.30 4-7  120    35    9    9    19    55  119    162    84    26    22    28    62    61  148  244    0  1203 (1)  2.97    .87  .22  .22    .47  1. 36 2.95    4.01  2.08  . 64  .55    . 69 1. 54  1. 51 3.67  6.05  .00  29.81 (2)  1. 38  .40  .10  .10    .22  . 63 1. 37  1. 86  .97  .30  .25    .32  . 71  .70  1. 70 2.80  .00  13.82 8-12    110    19    1    0      1    10    8      89    82    18    17    18  147    150  142  218    0  1030 (1)  2.73    .47  .02  .00    .02  .25  .20    2.21  2.03  .45  .42    .45  3. 64  3. 72 3.52  5.40  .00  25.52 (2)  1.26    .22  .01  .00    .01  .11  .09    1. 02  .94  .21  .20    .21  1. 69  1. 72 1. 63 2.50  .00  11. 84 13-18      21    0    0    0      0    1    0      8    16    2      0    4    67    80    77    96    0    372 (1)  .52    .00  .00  .00    .00  . 02  .00    .20    .40  .05  .00    .10  1. 66  1. 98 1. 91 2.38  .00  9.22 (2)  .24    .00  .00  .00    .00  .01  .00    .09    .18  .02  .00    .05  .77    . 92  .88  1.10  .00  4.27 19-24      0    0    0    0      0    0    0      0    0    0      0    0    4    10    16    17    0      47 (1)  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00  .00    .00  .10    .25  .40  .42  .00  1.16 (2)  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00  .00    .00  .05    .11  .18  .20  .00    .54 GT 24      0    0    0    0      0    0    0      0    0    0      0    0    0      0    2    0    0      2 (1)  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00  .00    .00  .00    .00  .05  .00  .00    .05 (2)  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00  .00    .00  .00    .00  .02  .00  .00    .02 ALL SPEEDS    351  114    73    71  124    230  299    427  279    91    65    81  318    349  455  709    0  4036 (1)  8.70  2.82  1. 81 1. 76 3.07  5.70  7.41 10.58    6.91  2.25  1. 61  2.01  7.88  8.65 11.27 17.57  .00 100.00 (2)  4.03  1. 31  .84  .82  1. 42  2. 64 3.44 4.91    3.21  1. 05  .75    .93  3. 65  4.01 5.23 8.15    .00  46.37 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 31
TABLE SE VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA            STABILITY CLASS E              CLASS FREQUENCY (PERCENT) =    28.16 WIND DIRECTION FROM
(
SPEED      N  NNE    NE  ENE      E  ESE    SE    SSE      s  SSW    SW  WSW      w    WNW    NW  NNW  VRBL    TOTAL MPH CALM      30  - 18    12    12    10  21    64      74    41    32    30    13    11      16  17    25      0    426 (1) 1. 22  .73  .49    .49    .41  .86 2.61    3.02  1. 67  1. 31 1.22  .53  .45    . 65  .69  1. 02    .00  17.38 (2)  .34    .21  .14    .14    .11  .24  .74    .85    .47  .37  .34  .15  .13    .18  .20  .29      .00  4.89 C-3    30    25    12    14    21  31    44      77    79  110  170  145  135      92  104    60      0  1149 (1) 1.22  1. 02  .49    .57    .86  1.26 1. 80  3.14  3.22  4.49  6.94  5.92  5.51    3.75  4.24  2.45      .00  46.88 (2)  .34    .29  .14    .16    .24  .36  .51    .88    .91 1. 26 1. 95 1. 67 1. 55  1. 06 1.19  .69      .00  13.20 4-7    40      8      1    0      3    8    34      53    28    5    14    43    80      59  84  133        0    593 (1) 1. 63  .33  .04    .00    .12  .33 1. 39  2.16  1.14    .20  .57  1. 75 3.26    2.41  3.43  5.43      .00  24.19
        ,(2)  . 46  .09  .01    .00    .03  .09  .39    . 61    .32  .06  .16  .49  .92    .68  .97  1. 53    .00  6.81 8-12      14      1      0    0      0    0    1      16    21    2    1    3    4*6    36  20    52      0    213 (1)  .57    .04  .00    .00  ,oo    .00  .04    . 65    .86  .08  .04  .12  1. 88  1. 47  .82  2.12      .00  8.69 (2)  .16    .01  .00    .00  .* 00  .00  .01    .18    .24  .02  .01  .03  .53    .41  .23  .60      .00  2.45 13-18      4      0    '-o    0      0    0    0      1      1    0    1    0      9    24    4    21      0    65 (1)  .16    .oo  .oo    .00    .00  .00  .00    . 04    .04  .00  .04  .oo  .37    .98  .16  .86      .00  2.65 (2)  .05    .00  .00    .00    .00  .00  .00    .01    .01  .00  .01  .00  .10    .28  .05  .24      .00    .75 19-24      0      0      0    0      0    0    0      0      0    0    0    0      2      0    0      3      0      5 (1)  .00    .00  .00    .00    .00  .00  .00    .00    .00  .00  .00  .00  .08    .00  .00  .12      .00    .20 (2)  .00    .00  .00    .00    .00  .00  .00    .00    .00  .00  .00  .00  .02    .00  .00  .03      .00    .06 GT 24      0      0      0    0      0    0    0      0      0    0    0    0      0      0    0      0      0      0 (1)  .00    .00  .00    .00    .00  .00  .00    .00    .00  .00  .00  .00  .00    .00  .00  .00      .00    .00 (2)  .00    .00  .00    .00  .00    .00  .00    .00    .00  .00  .00  .00  .00    .00  .00  :"'oo    .00    .00 ALL SPEEDS    118      52    25    26    34  60  143    221    170  149  216  204  283    227  229  294        0  2451 (1) 4.81  2.12  1. 02  1. 06 1. 39  2.45 5.83    9.02  6.94  6.08  8.81  8.32 11.55    9. 26 9.34 12.00      .00 100.00 (2) 1. 36  . 60  .29    .30    .39  .69 1. 64  2.54  1. 95  1. 71 2.48  2.34 3.25    2.61  2.63 3.38      .00  28.16
                                                                  '
(l}=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2}=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 32
TABLE 5F VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS F              CLASS FREQUENCY (PERCENT)        14.03 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE      E  ESE    SE    SSE      s  SSW      SW  . WSW    w_  WNW    NW  NNW  VRBL  TOTAL MPH CALM      5    7    5    5      6    12    16      17    28    49    31    26    10      11    13    22    0    263 (1)  .41    .57  .41  .41    .49  .98  1. 31  1. 39 2.29  4.01  2.54    2.13  .82    .90  1. 06 1. 80  .00  21. 54 (2)  .06    .08  .06  .06    .07  .14  .18    .20  .32  .56    .36    .30  .11    .13  .15  .25  .00  3.02 C-3    16    5    5    2      6    8    15      27    53    84  195    173  116      76    40    20    0    841 (1)  1. 31  .41  .41  .16    .49  .66  1. 23  2.21  4.34  6.88 15.97 14.17    9.50    6.22  3.28  1. 64  .00  68.88 (2)  .18    .06  .06  .02    .07  .09  .17    .31  . 61  . 97 2.24 1. 99    1.33    .87  .46  .23  .00  9.66 4-7      4    0    0    0      0    1    3      5    3    12    11    12    14      17    15    17    0    114 (1)  .33    .00  .00  .00    .00  .08  .25    .41  .25  .98    .90    .98 1.15    1. 39 1. 23 1. 39  .00  9.34 (2)  .05    .00  .00  .00    .00  .01  .03    .06  .03  .14    .13    .14  .16    .20  .17  .20  .00  1. 31 8-12      0    0    0    0      0    0    0      0    0    0      0      0    0      0    1    2    0      3 (1)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .08  .16  .00    .25 (2)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .01  .02  .00    .03 13-18      0    0    0    0      0    0    0      0    0    0      0      0    0      0    0    0    0      0 (1)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 (2)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 19-24      0    0    0    0      0    0    0      0    0    0      0      0    0      0    0    0    0      0 (1)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 (2)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 GT 24      0    0    0    0      0    0    0      0    0    0      0      0    0      0    0    0    0      0 (1)    .00  .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 (2)    .00  .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 ALL SPEEDS      25    12    10    7    12    21    34      49    84  145    237    211  140    104    69    61    0  1221 (1)  2.05    .98  .82  .57    .98 1. 72 2.78    4.01  6.88 11. 88 19. 41 17.28 11. 47  8.52  5.65  5.00  .00 100.00 (2)  .29    .14  .11  .08    .14  .24  .39    .56  .97 1. 67 2. 72 2.42 1. 61      1.19  .79  .70  .00  14.03 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 33
TABLE5G VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS G              CLASS FREQUENCY (PERCENT)    4. 64 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE      E  ESE    SE    SSE    s  SSW    SW  WSW      w  WNW    NW  NNW  VRBL  TOTAL MPH CALM      6    10    4    1      5    9    10    10    22    19    7    7    4    7    6      5    0    132 (1)  1. 49 2.48  .99  .25  1.24  2.23  2.48    2.48  5.45  4.70  1. 73 1. 73  .99 1. 73 1. 49 1.24    .00  32.67 (2)  .07  .11  .05  .01    .06  .10  .11    .11  .25  .22  .08  .08    .05  .08  .07  .06    .00  1. 52 C-3      5    2    4    2      7    7    5    13    12    29    32    44    30    24    13      8    0    237 (1)  1. 24  .so    .99  .50  1. 73 1. 73 1. 24  3.22  2.97  7.18  7.92 10.89  7.43  5.94  3.22  1. 98  .00  58.66 (2)  .06  .02    .05  .02    .08  .08  .06    .15  .14  .33  .37  .51    .34  .28  .15  .09    .00  2. 72 4-7      1    0    0    0      0    1    0      1    1      5    4    1    8    3    5    5    0      35 (1)  .25  .00  .00  .00  .00  .25  .oo    .25  .25  1.24  .99  .25  1. 98  .74  1.24  1.24    .00  8.66 (2)  .01  .00  .00  .00  .00  .01  .00    .01  .01  .06  .05  .01    .09  .03  .06  .06    .00    .40 8-12      0    0    0    0      0    0    0      0    0      0    0    0    0    0    0      0    0      0 (1)  .00  .00  .00  .00    .00  .00  .oo    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 (2)  .00  .00  .00  .00    .00  .00  .oo    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 13-18      0    0    0    0      0    0    0      0    0      0    0    0    0    0    0      0    0      0 (1)  .oo  .00  .00  .00    .00  .00  .oo    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 (2)  .00  .00  .00  .00    .00  .00  .oo    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 19-24      0    0    0    0      0    0    0      0      0    0    0    0    0    0    0      0    0      0 (1)  .00  .00  .00  .00  .00  .00  .00    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    . 00 (2)  .00  .00  .00  .00  .00  .00  .00    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 GT 24      0    0    0    0      0    0    0      0    0      0    0    0    0    0    0    .0    0      0 (1)  .00  .00  .00  .00    .00  .00  .oo    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 (2)  .00  .00  .00  .00    .00  .00  .00    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 ALL SPEEDS      12    12    8    3    12    17    15    24    35    53    43    52    42    34    24    18    0    404 (1)  2.97  2.97  1. 98  .74  2.97  4.21  3. 71  5.94  8.66 13.12 10.64 12.87 10.40  8.42  5.94  4.46    .00 100.00 (2)  .14  .14  .09  .03    .14  .20  .17    .28  .40  . 61  .49  .60    .48  .39  .28  .21    .00  4.64
(!)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 34
TABLE SH VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS ALL            CLASS FREQUENCY (PERCENT) = 100.00 WIND DIRECTION FROM SPEED      N  NNE      NE  ENE      E  ESE    SE    SSE      s  SSW    SW  WSW      w  WNW    NW    NNW  VRBL  TOTAL MPH CALM      71    55    42    49    70  138    189    175  115  104    72    51    29    35    43        79    0  1317 (1)    .82  . 63  .48  .56    .80 1.59  2.17    2.01  1.32  1.19  .83  .59    .33  .40  .49      .91  .00  15.13 (2)    .82  . 63  .48  .56    .80 1. 59 2.17    2.01  1. 32 1.19  .83  .59    .33  .40  .49  __,.-* 91  .00  15.13 C-3  137      83    74    57  100  138    146    217  220  264  419  388    315  242  222      201      0  3223 (1)  1. 57  .95  .85  . 65 1.15  1. 59 1. 68  2.49  2.53  3.03  4.81  4. 4 6 3. 62 2.78  2.55  2.31      .00  37.03 (2)  1. 57  .95  .85  . 65 1.15  1. 59 1. 68  2.49  2.53  3.03  4.81  4.46  3.62  2.78  2.55  2.31      .00  37.03 4-7  189      55    17    30    72  115    195    268  129    51    54    84  165  142  264      424      0  2254 (1)  2.17    .63  .20  .34    .83 1.32  2.24    3.08  1. 48  .59  . 62  . 97  1. 90 1. 63 3.03  4.87      .00  25.90 (2)  2.17    . 63  .20  .34    .83 1. 32 2.24    3.08  1. 48  .59  . 62  . 97  1. 90 1. 63 3.03  4.87      .00  25.90
                            -
8-12    137      25    3    0    1    22    19    142  131    22    18    22  198  191  171      292      0  1394 (1)  1. 57  .29  .03  .00    .01  .25    .22  1. 63 1. 51  .25  .21  .25  2.28  2.19  1. 96  3.36      .00  16.02 (2)  1. 57  .29  .03  .00    .01  .25    .22  1. 63 1. 51  .25  .21  .25  2.28  2.19  1. 96 3.36      .00  16.02 13-18      26      0    0    0    0    1    0      12    20    2      1      4    77  105    84    128      0    460 (1)  .30    .00  .00  .00    .00  .01    .00    .14    .23  .02  .01  .05    .88  1.21  .97  1. 47      .00  5.29 (2)    .30  .00  .00  .00    .00  .01    .00    .14    .23  .02  .01  .05    .88  1.21  .97  1. 47      .00  5.29 19-24      0      0    0    0    0    0    0      0    0    0      0      0    6    10    17        20    0      53 (1)  .00    .00  .00  .00    .00  .00    .00    .00  .oo  .00  .oo  .00    .07  .11  .20      .23  .00    . 61 (2)  .00    .00  .00  .00    .00  .00    .00    .00  .oo  .00  .00  .00    .07  .11  .20      .23  .00    . 61 GT 24      0      0    0    0    0    0    0      0    0    0      0      0    0    0    2        0    0      2 (1)    .00  .00  .00  .00    .00  .00    .00    .00    .oo  .00  .00  .00    .00  .00  .02      .00  .00    .02 (2)    .00  .00  .00  .00    .00  .00    .00    .00    .oo  .00  .00  .00    .00  .00  .02      .00  .00    .02 ALL SPEEDS    560  218    136  136  243  414    549    814  615  443  564  549    790  725  803 1144          0  8703 (1)  6.43  2.50  1. 56 1. 56 2.79  4. 76 6.31    9.35  7.07  5.09  6.48,6.31    9.08  8.33  9.23 13.14      .00 100.00 (2)  6.43  2.50  1. 56 1.56  2.79  4.76  6.31    9.35  7.07  5.09  6.48 '6. 31  9.08  8.33  9.23 13.14      .00 100.00 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 35


Health Physics Journal, Volume 39 (August), 1980; Pages 318-320, Pergammon Press). , 26 Variable Name (Units) Mixing Ratio Transit Time (hrs)* Water Uptake** (animal) (L/day) Feed Uptake**
TABLE6A VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA          STABILITY CLASS A              CLASS FREQUENCY (PERCENT) =    .32 WIND DIRECTION
: a. Average gamma energy: Not Applicable
: a. Average gamma energy: Not Applicable
: b. Average beta energy: Not Applicable
: b. Average beta energy: Not Applicable
: 4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
: 4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
: a. Fission and Activation Gases Continuous stack monitors monitor the gross Noble Gas radioactivity released from the plant stack. Because release rates are normally below the detection limit of these monitors, periodic grab samples are taken and analyzed for the gaseous isotopes present. These are used to calculate the individual isotopic releases indicated in Table lB and the totals of Table lA. The error involved in these steps may be approximately  
: a. Fission and Activation Gases Continuous stack monitors monitor the gross Noble Gas radioactivity released from the plant stack. Because release rates are normally below the detection limit of these monitors, periodic grab samples are taken and analyzed for the gaseous isotopes present. These are used to calculate the individual isotopic releases indicated in Table lB and the totals of Table lA. The error involved in these steps may be approximately +/-23 percent.
+/-23 percent. b. Iodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge.
: b. Iodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. The filters and cartridges are normally removed weekly and are analyzed for Iodine-131, 132, 133, 134, and 135. The error involved in these steps may be approximately +/-18 percent.
The filters and cartridges are normally removed weekly and are analyzed for Iodine-131, 132, 133, 134, and 135. The error involved in these steps may be approximately  
A-2
+/-18 percent. A-2
: c. Particulates The particulate filters described in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximately +/-18 percent.
: c. Particulates The particulate filters described in b. above are also counted for particulate radioactivity.
: d. Tritium ODCM Table 4.3 .1 requires as a minimum that grab samples from the plant stack be taken monthly and analyzed for tritium. The stack tritium collection has been upgraded with silica gel columns and continuous sampling of stack effluents. The error involved in this sample is approximately +/-18 percent.
The error involved in this sample is also approximately  
: e.   \\Taste ()il Prior to issuing the permit to burn a drum of radioactively contaminated waste oil, one liter of the oil is analyzed by gamma spectroscopy to determine concentrations of radionuclides that meet or exceed the LLD for all of the liquid phase radionuclides listed in ODCM Table 4.2.1.
+/-18 percent. d. Tritium ODCM Table 4.3 .1 requires as a minimum that grab samples from the plant stack be taken monthly and analyzed for tritium. The stack tritium collection has been upgraded with silica gel columns and continuous sampling of stack effluents.
Monthly, samples from drums that were issued burn permits are sent to the contracted laboratory for compositing and analysis. The lab analyzes for tritium, alpha, Fe-55, Sr-89, and Sr-90 on the composite sample.
The error involved in this sample is approximately  
The error involved in this sample is approximately +/-15 percent.
+/-18 percent. e. \\Taste ()il Prior to issuing the permit to burn a drum of radioactively contaminated waste oil, one liter of the oil is analyzed by gamma spectroscopy to determine concentrations of radionuclides that meet or exceed the LLD for all of the liquid phase radionuclides listed in ODCM Table 4.2.1. Monthly, samples from drums that were issued burn permits are sent to the contracted laboratory for compositing and analysis.
: f. Liquid Effluents If radioactive liquid effluents are to be released from the facility, they are continuously monitored. Measurements are also required on a representative sample of each batch ofradioactive liquid effluents released. For each batch, station records are retained of the total activity (mCi) released, concentration
The lab analyzes for tritium, alpha, Fe-55, Sr-89, and Sr-90 on the composite sample. The error involved in this sample is approximately  
(&#xb5;Ci/ml) of gross radioactivity, volume (liters), and approximate total.quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River.
+/-15 percent. f. Liquid Effluents If radioactive liquid effluents are to be released from the facility, they are continuously monitored.
Each batch of radioactive liquid effluents to be released is analyzed for gross gamma and gammaisotopic radioactivity. A monthly proportional composite sample, comprising an aliquot of each batch released during a month, is analyzed for tritium and gross alpha radioactivity. A quarterly proportional
Measurements are also required on a representative sample of each batch ofradioactive liquid effluents released.
* composite sample, comprising an aliquot of each batch released during a quarter, is analyzed for Sr-89, Sr-90, and Fe-55.
For each batch, station records are retained of the total activity (mCi) released, concentration
A-3
(&#xb5;Ci/ml) of gross radioactivity, volume (liters), and approximate total.quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River. Each batch of radioactive liquid effluents to be released is analyzed for gross gamma and gammaisotopic radioactivity.
: 5. BATCH RELEASES
A monthly proportional composite sample, comprising an aliquot of each batch released during a month, is analyzed for tritium and gross alpha radioactivity.
: a. Liquid There were no*routine liquid batch releases during the reporting period.
A quarterly proportional
: b. Gaseous There were no routine gaseous batch releases during the reporting period.
* composite sample, comprising an aliquot of each batch released during a quarter, is analyzed for Sr-89, Sr-90, and Fe-55. A-3
: 6. ABNORMAL RELEASES
: 5. BATCH RELEASES a. Liquid There were no*routine liquid batch releases during the reporting period. b. Gaseous There were no routine gaseous batch releases during the reporting period. 6. ABNORMAL RELEASES a. Liguid b. 1) In 2015 there was a continuous release due to the residual radioactivity in groundwater from a previously undetected leak from a subsurface structure.
: a. Liguid
The leak condition was identified through monitoring well data in January 2010. The leak was stopped in February 2010 .. 2) For 2015, the total Tritium radioactivity conservatively estimated to be released to the Connecticut River is 0.0334 Curies. No other plant-related radionuclides were detected in ground water. Gaseous There were no non-routine gaseous releases (measured) during the reporting period. A-4 _,
: 1) In 2015 there was a continuous release due to the residual radioactivity in groundwater from a previously undetected leak from a subsurface structure.
Requirement Response:
The leak condition was identified through monitoring well data in January 2010. The leak was stopped in February 2010 ..
APPENDIXB LIQUID HOLDUP TANKS Technical Specification
: 2) For 2015, the total Tritium radioactivity conservatively estimated to be released to the Connecticut River is 0.0334 Curies. No other plant-related radionuclides were detected in ground water.
: 3. l .A.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.1.A.l, a description of the events leading to this condition is required in the next annual Radioactive Effluent Release Report per ODCM Section 10.1. The limits of Technical Specification 3.1.A.1 were not exceeded during this reporting period. (Note that during 2015 the section numbering of the Technical Specifications changed due to the implementation of an approved License Amendment following permanent shutdown and defueling of the plant, but there were no changes made to the limits in Technical Specification 3.1.A.1 from those previously contained in Technical Specification 3.8.D.l) B-1 APPENDIXC RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Requirement:
: b. Gaseous There were no non-routine gaseous releases (measured) during the reporting period.
Response:
_,
Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.1. If an inoperable radioactive liquid effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3 .1.1, an explanation in the rtext annual Radioactive Effluent Release Report of the reason(s) for delay in correcting the inoperability are required per ODCM Section 10.1. Since the requirements of ODCM Table 3.1.1 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period, no response is required.
A-4
j C-1 APPENDIXD RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Requirement:
 
Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.2. If inoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.1.2, an explanation in the next annual Radioactive Effluent Release Report of the reason(s) for the delay in correcting the inoperability is required per ODCM Section lO.l. Response:
APPENDIXB LIQUID HOLDUP TANKS Requirement Technical Specification 3. l .A.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.1.A.l, a description of the events leading to this condition is required in the next annual Radioactive Effluent Release Report per ODCM Section 10.1.
Since the requirements of ODCM Table 3.1.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no response is required.
Response:  The limits of Technical Specification 3.1.A.1 were not exceeded during this reporting period. (Note that during 2015 the section numbering of the Technical Specifications changed due to the implementation of an NRC-approved License Amendment following permanent shutdown and defueling of the plant, but there were no changes made to the limits in Technical Specification 3.1.A.1 from those previously contained in Technical Specification 3.8.D.l)
D-1 APPENDIXE . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirement:
B-1
The radiological environmental monitoring program is conducted in accordance with ODCM Control 3/4.5.1. With milk samples no longer available from one or more of the sample locations required by ODCM Table 3.5.1, ODCM 10.1 requires the following to be included in the next annual Radioactive Effluent Release Report: (1) identify the cause(s) of the sample(s) no longer being available, (2) identify the new location(s) for obtaining available replacement samples and (3) include revised ODCM figure(s) and table(s) reflecting the new location(s).
 
Response:
APPENDIXC RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.1. If an inoperable radioactive liquid effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3 .1.1, an explanation in the rtext annual Radioactive Effluent Release Report of the reason(s) for delay in correcting the inoperability are required per ODCM Section 10.1.
Milk and silage collection at the Vern-Mont Farm (TM-20) was discontinued in August 2015 due to the permanently shut down and defueled status of the plant. It is noted that this was not a required sampling station in the ODCM. F-1 APPENDIXF LAND USE CENSUS Requirement:
Response:    Since the requirements of ODCM Table 3.1.1 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period, no response is required.                 j C-1
A land use census is conducted in accordance with ODCM Control 3/4.5.2. With a land use census identifying a location(s) that yields at least a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3.3, the new location(s) must be identified in the next Annual Radioactive Effluent Release Report Response:
 
The Land-Use Census was completed during the third quarter of2015. No locations were identified which yielded a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3 .3. See Table 4C for a listing of nearest residents and milk animals in the site area as determined in the 2015 Land Use Census. F-2 APPENDIXG PROCESS CONTROL PROGRAM Requirement:
APPENDIXD RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.2. If inoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.1.2, an explanation in the next annual Radioactive Effluent Release Report of the reason(s) for the delay in correcting the inoperability is required per ODCM Section lO.l.
ODCM Section 10.1 requires that licensee initiated changes to the Process Control Program (PCP) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made. Response:
Response:   Since the requirements of ODCM Table 3.1.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no response is required.
There were no changes made to the Process Control Program during this reporting period. G-1
D-1
\ APPENDIXH OFF-SITE DOSE CALCULATION MANUAL Requirement:
 
Technical Specification 6.7.B.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made effective.
APPENDIXE
Response:
            . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirement:   The radiological environmental monitoring program is conducted in accordance with ODCM Control 3/4.5.1. With milk samples no longer available from one or more of the sample locations required by ODCM Table 3.5.1, ODCM 10.1 requires the following to be included in the next annual Radioactive Effluent Release Report: (1) identify the cause(s) of the sample(s) no longer being available, (2) identify the new location(s) for obtaining available replacement samples and (3) include revised ODCM figure(s) and table(s) reflecting the new location(s).
No revisions were made to the ODCM during the reporting period. H-1 APPENDIX I RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Requirement:
Response:       Milk and silage collection at the Vern-Mont Farm (TM-20) was discontinued in August 2015 due to the permanently shut down and defueled status of the plant. It is noted that this was not a required sampling station in the ODCM.
ODCM Section 10.4 requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.
F-1
Response:
 
There were no licensee-initiated major changes to i:he radioactive waste systems during this reporting period. I-1 APPENDIXJ DISPOSAL OF SEPTIC/SILT/SOIL WASTE Requirement:
APPENDIXF LAND USE CENSUS Requirement: A land use census is conducted in accordance with ODCM Control 3/4.5.2.
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.
With a land use census identifying a location(s) that yields at least a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3.3, the new location(s) must be identified in the next Annual Radioactive Effluent Release Report Response:   The Land-Use Census was completed during the third quarter of2015. No locations were identified which yielded a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3 .3. See Table 4C for a listing of nearest residents and milk animals in the site area as determined in the 2015 Land Use Census.
year and from previous years be reported to the Nuclear Regulatory Commission in the Annual Radioactive Effluent Release Report if disposals occur during the reporting year. Entergy Nuclear Vermont Yankee will report in the Annual Radioactive Effluent Release Report a list of the radiomI;clides present and the total radioactivity associated with the disposal activities oh the Vermont Yankee site. Response:
F-2
There was one on-site disposal spreading of 11,000 gallons of septic waste during October of 2015, and no spreading activities for cooling tower silt or sand/soil type materials.
 
The total radioactivity spread on the 1.9 acres (southern) on-site disposal field from this and previous years was as follows: Activity Spread in 2015 Activity from All Past and Current Disposals Decayed to 10/20/2015 Radionuclide (Ci) (Ci) Mn-54 8.00E-11 1.17E-08 Co-60 2.43E-09 9.67E-06 Zn-65 2.68E-10 3.67E-09 Cs-134 O.OOE+OO 6.68E-10 . Cs-137 l.lOE-10 7.50E-05 The maximum organ dose from all past and current spreading operations totaled l.09E-01 mrem/year.
APPENDIXG PROCESS CONTROL PROGRAM Requirement: ODCM Section 10.1 requires that licensee initiated changes to the Process Control Program (PCP) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made.
This calculated value is within the 1 mrem/year limit applied during the period of operational control of the site. The projected hypothetical "intruder" dose for the period following the loss of operational control of the site area, due to all spreading operations to-date, is 2.08E-01 mrem/year versus a 5 mrem/year dose limit. The "intruder dose" period begins on the date that the plant operating license expires, March 21, 2032. J-1
Response:   There were no changes made to the Process Control Program during this reporting period.
G-1
 
APPENDIXH OFF-SITE DOSE CALCULATION MANUAL Requirement: Technical Specification 6.7.B.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made effective.
Response:   No revisions were made to the ODCM during the reporting period.
\
H-1
 
APPENDIX I RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Requirement: ODCM Section 10.4 requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.
Response:   There were no licensee-initiated major changes to i:he radioactive waste systems during this reporting period.
I-1
 
APPENDIXJ ON~SITE    DISPOSAL OF SEPTIC/SILT/SOIL WASTE Requirement:   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 Release Report if disposals occur during the reporting year. Entergy Nuclear Vermont Yankee will report in the Annual Radioactive Effluent Release Report a list of the radiomI;clides present and the total radioactivity associated with the disposal activities oh the Vermont Yankee site.
Response:     There was one on-site disposal spreading of 11,000 gallons of septic waste during October of 2015, and no spreading activities for cooling tower silt or sand/soil type materials. The total radioactivity spread on the 1.9 acres (southern) on-site disposal field from this and previous years was as follows:
Activity from All Past and Current Activity Spread in 2015      Disposals Decayed to 10/20/2015 Radionuclide                 (Ci)                             (Ci)
Mn-54                 8.00E-11                         1.17E-08 Co-60                 2.43E-09                         9.67E-06 Zn-65                 2.68E-10                         3.67E-09 Cs-134               O.OOE+OO                           6.68E-10
              . Cs-137                 l.lOE-10                         7.50E-05 The maximum organ dose from all past and current spreading operations totaled l.09E-01 mrem/year. This calculated value is within the 1 mrem/year limit applied during the period of operational control of the site. The projected hypothetical "intruder" dose for the period following the loss of operational control of the site area, due to all spreading operations to-date, is 2.08E-01 mrem/year versus a 5 mrem/year dose limit. The "intruder dose" period begins on the date that the plant operating license expires, March 21, 2032.
J-1


BVY 16-020 May 12, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001  
Entergy Nuclear Vermont Yankee, LLC
'/
                                                  '/            Vermont Yankee
~Entergy 320 Governor Hunt Rd.
Vernon, VT 05354 (802) 257-7711 Coley C. Chappell Manager, Design and Programs BVY 16-020 May 12, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001


==SUBJECT:==
==SUBJECT:==
2015 Radioactive Effluent Release Report Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28  
2015 Radioactive Effluent Release Report Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28


==Dear Sir or Madam,==
==Dear Sir or Madam,==
Entergy Nuclear Vermont Yankee, LLC Vermont Yankee 320 Governor Hunt Rd. Vernon, VT 05354 (802) 257-7711 Coley C. Chappell Manager, Design and Programs In accordance with Vermont Yankee (VY) Technical Specifications (TS) 6.6.D, enclosed is a copy 'of the annual 2015 Radioactive Effluent Release Report. In addition, VY TS 6.7.B requires reporting of changes to the Off-Site Dose Calculation Manual (ODCM). There were no changes made to the ODCM during 2015 as noted in Appendix H of the subject report. There are no new regulatory commitments being made in this submittal.
 
In accordance with Vermont Yankee (VY) Technical Specifications (TS) 6.6.D, enclosed is a copy 'of the annual 2015 Radioactive Effluent Release Report.
In addition, VY TS 6.7.B requires reporting of changes to the Off-Site Dose Calculation Manual (ODCM). There were no changes made to the ODCM during 2015 as noted in Appendix H of the subject report.
There are no new regulatory commitments being made in this submittal.
Should you have any questions or require additional information concerning this submittal, please contact me at (802) 451-3374.
Should you have any questions or require additional information concerning this submittal, please contact me at (802) 451-3374.
Sincerely,
Sincerely, t~Mw~
[CCC/TBS]  
[CCC/TBS]


==Enclosure:==
==Enclosure:==
Radioactive Effluent Release Report for 2015 cc listing (next page) cc:      Mr. Daniel Dorman, Region 1 Administrator
BVY 16-020 I Page 2 of 2 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Mr. Jack D. Parrott, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop T-8F5 11555 Rockville Pike
      .Rockville, MD 20852-2378 Mr. Christopher Recchia, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, VT 05620 Vermont Department of Health Division of Radiological Health Attn: Bill Irwin P.O. Box 70 Burlington, VT 05402-0070 Massachusetts Department of Public Health Jack Priest, Director Radiation Control Program 529 Main Street, Suite 1M2A Charlestown, MA 02129 Augustinus Ong, Administrator Department of Health and Human Services Radiological Health Section 29 Hazen Drive Concord, NH 03301-6504 \.*
John Giarrusso Nuclear Preparedness and Planning Manager 400 Worcester Road Framingham, MA 01702 Tony Honnellio Radiation Program Manager, Health and Safety Coordinator EPA, New England, Region 1 5 Post Office Square, Suite 100 (OSRR02-2).
Boston, Massachusetts 02109
RADIOACTIVE EFFLUENT RELEASE REPORT FOR2015 INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN Entergy Nuclear Vermont Yankee, LLC Docket No. 50-271 License No. DPR-28 Prepared  by:_,.,,,,..,Y'--"""--L,,.-~~~"""'-""'~=_,,___ _ _ _ ____;/ 6 Is'/ I to
                                              , Clvisol)* Scientist, AREVA, Inc. Date
                              --b~~~-'--~~~1~1$/td&                          Date Revie-ived by:_~----.......,....,~--+-+--------*ut:f0 Approved for  Distribution:_-1!--L-=:::i~~r==::::::::__ _ _ _ _ _ ___!/ ~kb(?
Date
                                                                                      \..


Radioactive Effluent Release Report for 2015 cc listing (next page) cc: Mr. Daniel Dorman, Region 1 Administrator BVY 16-020 I Page 2 of 2 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Mr. Jack D. Parrott, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop T-8F5 11555 Rockville Pike . Rockville, MD 20852-2378 Mr. Christopher Recchia, Commissioner VT Department of Public Service 112 State Street -Drawer 20 Montpelier, VT 05620 Vermont Department of Health Division of Radiological Health Attn: Bill Irwin P.O. Box 70 Burlington, VT 05402-0070 Massachusetts Department of Public Health Jack Priest, Director Radiation Control Program 529 Main Street, Suite 1 M2A Charlestown, MA 02129 Augustinus Ong, Administrator Department of Health and Human Services Radiological Health Section 29 Hazen Drive Concord, NH 03301-6504
TABLE OF CONTENTS
\.* John Giarrusso Nuclear Preparedness and Planning Manager 400 Worcester Road Framingham, MA 01702 Tony Honnellio Radiation Program Manager, Health and Safety Coordinator EPA, New England, Region 1 5 Post Office Square, Suite 100 (OSRR02-2).
Boston, Massachusetts 02109 RADIOACTIVE EFFLUENT RELEASE REPORT FOR2015 INCLUDING ANNUAL RADIOLOGICAL IMP ACT ON MAN Entergy Nuclear Vermont Yankee, LLC Docket No. 50-271 License No. DPR-28 Prepared
_____ ___;/ 6 Is'/ I to , Clvisol)*
Scientist, AREVA, Inc. Date Date Revie-ived 0 Approved for
_______ __!/
Date \..
TABLE OF CONTENTS  


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==
.............................................................................................................................................. 1 2.0 METEOROLOGICAL DATA ............................................................................................................................ 2 3.0 DOSE ASSESSMENT .................................................................................. :.................................................... 3 3.1 DOSES FROM LIQUID EFFLUENTS ............................... : ................................................................................... 3 3.2 DOSES FROM NOBLE GASES ........................................................................................................................... 4 3 .3 DOSES FROM IODINE-131, IODINE-133, TRITIUM, CARBON-14, AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS .................................................................................. 4 3.4 WHOLE BODY DOSES IN UNRESTRICTED AREAS FROM DIRECT RADIATION ................................................. 5 3 .5 DOSES FROM ON-SITE DISPOSAL OF SEPTIC WASTE, COOLING TOWER SILT AND SOIL ............................... 6 3.6 ON-SITE RECREATIONAL ACTIVITIES ............................................................................................................. 6 REFERENCES .......................................................................................................................................................... 7 APPENDIX A -SUPPLEMENTAL INFORMATION ......................................................................................... A-1*
APPENDIX B -LIQUID HOLDUP TANKS ........................................................................................................ B-1 APPENDIX C -RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ............................................................................................................... C-1 APPENDIX D -RADIOACTIVE GASEOUS EFFLUENT MONITORING '
INSTRUMENTATION ................................................................................................................ D-1 APPENDIX E-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..................................... E-1 APPENDIX F - LAND USE CENSUS .................................................................................................................. F-1 APPENDIX G -PROCESS CONTROL PROGRAM ............................................................................................ G-1 APPENDIX H -OFF-SITE DOSE CALCULATION MANUAL ......................................................................... H-1 APPENDIX I - RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS ............................................................................................................ I-1 APPENDIX J - ON-SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE ............................................................ J-1 11


..............................................................................................................................................
LIST OF TABLES IA       Gaseous Effluents - Summation of All Releases                           8 IB       Gaseous Effluents - Elevated Releases                                 10 IC       Gaseous Effluents - Ground Level Releases                             I2 lD       Gaseous Effluents - Non-routine Releases                               14 2A       Liquid Effluents - Summation of All Releases                           15 2B       Liquid Effluents - Routine Releases                                   17 3       Solid Waste and Irradiated Fuel Shipments                             19 4A       Maximum Quarterly and Annual Off-Site Doses from Direct Radiation and 21 Liquid and Gaseous Effluents for 2015 (10CFR50, Appendix I) 4B       Maximum Annual Off-Site Doses from Direct Radiation and               22 and Liquid and Gaseous Effluents for 2015 (40CFR190) 4C       Receptor Locations                                                     23 4D       Usage Factors for Environmental Pathways                               24 4E       Environmental Parameters for Gaseous 'Effluents                       25 4F       Environmental Parameters for Liquid Releases (Tritium) Via Groundwater 27 5A to 5H Annual (2015) Summary of Lower Level Joint Frequency Distribution     28-35 6A to 6H Annual (2015) Summary of Upper Level Joint Frequency Distribution     36-43 111
1 2.0 METEOROLOGICAL DA TA ............................................................................................................................
 
2 3.0 DOSE ASSESSMENT
Radiological Effluent Release Report for 2015
..................................................................................
[Including Annual Radiological Impact on Man]
: ....................................................
Entergy Nuclear Vermont Yankee, LLC
3 3.1 DOSES FROM LIQUID EFFLUENTS
...............................
: ...................................................................................
3 3.2 DOSES FROM NOBLE GASES ...........................................................................................................................
4 3 .3 DOSES FROM IODINE-131, IODINE-133, TRITIUM, CARBON-14, AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS ..................................................................................
4 3.4 WHOLE BODY DOSES IN UNRESTRICTED AREAS FROM DIRECT RADIATION
.................................................
5 3 .5 DOSES FROM ON-SITE DISPOSAL OF SEPTIC WASTE, COOLING TOWER SILT AND SOIL ...............................
6 3.6 ON-SITE RECREATIONAL ACTIVITIES
.............................................................................................................
6 REFERENCES
..........................................................................................................................................................
7 APPENDIX A -SUPPLEMENTAL INFORMATION
.........................................................................................
A-1* APPENDIX B -LIQUID HOLDUP TANKS ........................................................................................................
B-1 APPENDIX C -RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
...............................................................................................................
C-1 APPENDIX D -RADIOACTIVE GASEOUS EFFLUENT MONITORING
' INSTRUMENTATION
................................................................................................................
D-1 APPENDIX E-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .....................................
E-1 APPENDIX F -LAND USE CENSUS ..................................................................................................................
F-1 APPENDIX G -PROCESS CONTROL PROGRAM ............................................................................................
G-1 APPENDIX H -OFF-SITE DOSE CALCULATION MANUAL .........................................................................
H-1 APPENDIX I -RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS ............................................................................................................
I-1 APPENDIX J -ON-SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE ............................................................
J-1 11 LIST OF TABLES IA Gaseous Effluents  
-Summation of All Releases 8 IB Gaseous Effluents  
-Elevated Releases 10 IC Gaseous Effluents  
-Ground Level Releases I2 lD Gaseous Effluents  
-Non-routine Releases 14 2A Liquid Effluents  
-Summation of All Releases 15 2B Liquid Effluents  
-Routine Releases 17 3 Solid Waste and Irradiated Fuel Shipments 19 4A Maximum Quarterly and Annual Off-Site Doses from Direct Radiation and 21 Liquid and Gaseous Effluents for 2015 (10CFR50, Appendix I) 4B Maximum Annual Off-Site Doses from Direct Radiation and 22 and Liquid and Gaseous Effluents for 2015 (40CFR190) 4C Receptor Locations 23 4D Usage Factors for Environmental Pathways 24 4E Environmental Parameters for Gaseous 'Effluents 25 4F Environmental Parameters for Liquid Releases (Tritium)
Via Groundwater 27 5A to 5H Annual (2015) Summary of Lower Level Joint Frequency Distribution 28-35 6A to 6H Annual (2015) Summary of Upper Level Joint Frequency Distribution 36-43 111 Radiological Effluent Release Report for 2015 [Including Annual Radiological Impact on Man] Entergy Nuclear Vermont Yankee, LLC  


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==


Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste shipments for the year, 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 the year 2015 in response to the ALARA objectives of 10 CFR Part 50, Appendix I. Also included in Table 4A is the estimate of direct dose from fixed station sources along the limiting west site boundary line. Tables SA through 6H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 2015. Radioactive effluents reported in Tables 1and2 were used to determine the dose to the maximum exposed individual for 2015. 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.l (Reference 1). These dose estimates were made using a "Method II" analysis as described in the ODCM, and as reported in Tables 4A and 4B ofthis report. A "Method II" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference
Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste shipments for the year, 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 the year 2015 in response to the ALARA objectives of 10 CFR Part 50, Appendix I. Also included in Table 4A is the estimate of direct dose from fixed station sources along the limiting west site boundary line. Tables SA through 6H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 2015. Radioactive effluents reported in Tables 1and2 were used to determine the dose to the maximum exposed individual for 2015.
: 2) and actual measured meteorological data recorded concurrently with the quarterly reporting period. As required by ODCM Section 10.1, this report shall also include an assessment of the radiation*
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.l (Reference 1). These dose estimates were made using a "Method II" analysis as described in the ODCM, and as reported in Tables 4A and 4B ofthis report. A "Method II" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 2) and actual measured meteorological data recorded concurrently with the quarterly reporting period.
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.
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 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," is also required to be included in this report ifthe 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.
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 Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," is also required to be included in this report ifthe 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 Part 190. All calculated dose estimates for members of the public at the site boundary or beyond for the 2015 annual reporting period are below the dose criteria of 10 CFR Part 50, Appendix I, and 40 CFR Part 190. Appendices B through H indicate the status of reportable items per the requirements of ODCM Section 10.1. 1 2.0 METEOROLOGICAL DATA Meteorological data were collected in 2015 from the site's 300-foot meteorological tower located approximately 2,200 feet northwest of the reactor building, and about 1,400 feet from the plant stack. The 300-foot tower is approximately the same height as the primary plant stack (308 feet) and is designed to meet the requirements of Safety Guide 23 (Reference
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 Part 190.
: 3) for meteorological monitoring.
All calculated dose estimates for members of the public at the site boundary or beyond for the 2015 annual reporting period are below the dose criteria of 10 CFR Part 50, Appendix I, and 40 CFR Part 190.
In mid-2009, the tower was moved to a location approximately 200 feet northwest of the original location.
Appendices B through H indicate the status of reportable items per the requirements of ODCM Section 10.1.
r.JQ and D/Q values for elevated releases were derived for all receptor points from the site meteorological record for each quarter using a straight-line airflow model. All dispersion factors have been calculated employing appropriate source configuration considerations, as described in Regulatory Guide 1.111 (Reference 4). A source depletion model as described in "Meteorology and Atomic Energy -1968" (Reference
1
: 5) was used to generate deposition factors, assuming a constant deposition velocity of 0. 01 m/sec for all stack (elevated) releases.
 
Changes in terrain elevations in the site environment were also factored into the meteorological models as appropriate.
2.0 METEOROLOGICAL DATA Meteorological data were collected in 2015 from the site's 300-foot meteorological tower located approximately 2,200 feet northwest of the reactor building, and about 1,400 feet from the plant stack. The 300-foot tower is approximately the same height as the primary plant stack (308 feet) and is designed to meet the requirements of Safety Guide 23 (Reference 3) for meteorological monitoring. In mid-2009, the tower was moved to a location approximately 200 feet northwest of the original location.
In the event of a ground-level release, r.JQ and D/Q values would be derived for the site boundary receptor points from the site meteorological record for each quarter using a straight-line airflow model. During this reporting period, there were no ground-level releases and therefore no associated dose impact. Table 4C lists the distanc.es from the plant stack to the nearest site boundary, resident, and milk animal in each of the 16 principle compass directions as determined during the 2015 land use census. These locations were used in the calculation of atmospheric dispersion factors. The meteorological model was also executed for each calendar quarter to determine the location of the predicted maximum ground level air concentration from elevated releases from the plant's primary vent stack. These locations were included in the assessment of effluent doses along with identified points of interest from the annual land use census. " 2 3.0 DOSE ASSESSMENT 3.1 Doses From Liguid 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 Part 50, Appendix I. By implementing the requirements of 10 CFR Part 50, Appendix I, ODCM 3/4.2.2 assures that the release ofradioactive material in liquid effluents will be kept "as low as is* reasonably achievable." . *', *
r.JQ and D/Q values for elevated releases were derived for all receptor points from the site meteorological record for each quarter using a straight-line airflow model. All dispersion factors have been calculated employing appropriate source configuration considerations, as described in Regulatory Guide 1.111 (Reference 4). A source depletion model as described in "Meteorology and Atomic Energy - 1968" (Reference 5) was used to generate deposition factors, assuming a constant deposition velocity of 0. 01 m/sec for all stack (elevated) releases. Changes in terrain elevations in the site environment were also factored into the meteorological models as appropriate.
* There were no recorded routine liquid radioactive waste discharges during the report period. However, an abnormal release to the Connecticut River is postulated due to a past leak in an underground pipe tunnel that runs between the Advanced Offgas (AOG) system building and other plant buildings which allowed accumulated piping system leakage to enter the subsurface groundwater adjacent to the plant structures.
In the event of a ground-level release, r.JQ and D/Q values would be derived for the site boundary receptor points from the site meteorological record for each quarter using a straight-line airflow model.
The existence of the leak was first recognized in January 2010, when a river shoreline Protected Area Boundary monitoring well sample was reported to have detectable tritium. The addition of other monitoring wells and subsequent analysis defined the extent of the affected groundwater plume moving toward the.river and helped locate the source of the leak, which was stopped in February 2010. \ Estimates of tritium-contaminated ground water released from the site are based on Protected Area Boundary monitoring well data collected throughout 2015, and hydrological modeling of ground water movement in the affected zone impacted by the pipe tunnel leak. 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 2015 was generated and reported in Table 2A. Forthe projected ground water flow into the Connecticut River in 2015, the dose impact to the maximum exposed individual (MEI) assumed the following exposure pathways:
During this reporting period, there were no ground-level releases and therefore no associated dose impact.
(1) ingestion offish (taken from Vernon Pond), (2) ingestion of vegetables and, fresh leafy produce irrigated by water taken from the river below Vernon Dam, (3) ingestion of milk and meat from animals that were fed irrigated crops and drinking water taken from the river below Vernon Dam, and (4) water for a hypothetical individual drawing drinking water fed by the river below Vernon Dam. For Vernon Pond (river area adjacent to the plant property), the near shore mixing zone associated with the fish ingestion pathway is conservatively taken as 1 % of the minimum recorded monthly river flow (3,107 cfs in September 2015) for dilution.
Table 4C lists the distanc.es from the plant stack to the nearest site boundary, resident, and milk animal in each of the 16 principle compass directions as determined during the 2015 land use census. These locations were used in the calculation of atmospheric dispersion factors. The meteorological model was also executed for each calendar quarter to determine the location of the predicted maximum ground level air concentration from elevated releases from the plant's primary vent stack. These locations were included in the assessment of effluent doses along with identified points of interest from the annual land use census.   "
All irrigation exposure pathways for the consumption of food products grown with irrigated water occur below Vernon Dam and assume the lowest 2015 quarterly average growing season river flow value (5394 cfs in the third quarter) for environmental mixing. For the drinking water pathway, river flow mixing is assumed to occur below Vernon Dam and uses the lowest annual quarterly average river flow (5394 cfs in the third quarter) as a conservative estimate ofriver dilution for all four quarters of the year. The dose models are !aken from Regulatory Guide 1.109 (Reference
2
: 2) and use environmental parameters for exposure pathways listed in Tables 4D and 4F. . The maximum estimated quarterly and annual whole body and organ doses to the limiting age group from liquid releases are reported in Table 4A. These estimated doses are well below the 10 CFR Part 50, Appendix I dose criteria of ODCM 3/4.2.2. Table 4B provides an estimate of the total annual'dose impact (including contribution from liquids) associated with the highest exposed member of the public for demonstration of compliance to the dose standard contained in 40 CFR 190 for the uranium fuel cycle. \. 3 3.2 Doses From Noble Gases ODCM 3/4.3.2 limits the gamma air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I. By implementing these, ODCM 3/4.3.2 assures that the releases ofradioactive noble gases in gaseous effluents will be kept "as low as is reasonably achievable." Dose estimates due to the release of noble gases to the atmosphere are typically calculated at the site boundary, at the nearest resident in each of the sixteen principal compass directions, at the point of highest off-site ground level air concentration of radioactive materials, and at each of the milk animal locations located within five miles of the plant. For 2015, there were no noble gases detected in effluents released from the plant stack. 3.3 Doses From Iodine-131, Iodine-133, Tritium, Carbon-14, and Radionuclides in Particulate Form with Half-Lives Greater Than 8 Days ODCM 3/4.3.3 limits the organ dose to a member of the public from Iodine-131, Iodine-133, Tritium, Carbon-14, and radionuclides in particulate form with half-lives greater than 8 days (hereafter called "iodines and particulates")
 
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 iodines and particulates in gaseous effluents will be kept "as low as is reasonably achievable." During 2015, a single frac tank was used on the Vermont Yankee site to temporarily store (outdoors) tritium-contaminated water extracted from onsite groundwater wells. The quantity of tritium released to the atmosphere through the evaporation of water from this frac tank was estimated, and the dose consequence to the maximally exposed individual was calculated.
3.0 DOSE ASSESSMENT 3.1 Doses From Liguid 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 Part 50, Appendix I. By implementing the requirements of 10 CFR Part 50, Appendix I, ODCM 3/4.2.2 assures that the release ofradioactive material in liquid effluents will be kept "as low as is*
Exposure pathways that could exist as a result of the planned (routine) release of iodines and particulates to the atmosphere include external irradiation from activity deposited onto the ground surface, inhalation, and ingestion of vegetables, meat and milk. Dose estimates were made at the site boundary and nearest resident in each of the sixteen principal compass directions, as well as all milk animal locations within five miles of the plant. The nearest resident and milk animals in each sector were identified by the most recent annual land use census as required by ODCM 3/4.5.2 (see Table 4C). Conservatively, a vegetable garden was assumed to exist at each milk animal and nearest resident location.
reasonably achievable."                                                                                     . *', *
Furthermore, the meat pathway was assumed to exist at each milk cow location since this data category is not part of the annual land use census. Doses were also calculated at the point of maximum ground level air concentration of radioactive materials in gaseous effluents and included the assumption that the inhalation, vegetable garden, and ground plane exposure pathways exist for an individual with a 100 percent occupancy factor. It is assumed that milk and meat animals are free to graze on open pasture during the second and third quarters with no supplemental feeding. This assumption is conservative since most of the milk animals inventoried in the site vicinity are fed stored feed throughout the entire year with only limited grazing allowed during the growing season. It has also been assumed that only 50 percent of the iodine deposited from gaseous effluent is in elemental form (I 2) and is available for uptake (seep. 6, Reference 2). 4 During the non-growing season (first and fourth quarters), the milk animals are assumed to receive only stored feed. During the growing season (second and third quarters), all animal feed is assumed to be derived from fresh pasture. Usage factors for gaseous effluents are listed by age group and pathway in Table 4D. Table 4E provides other dose model parameter assumptions used in the dose assessments.
* There were no recorded routine liquid radioactive waste discharges during the report period.
In June 2009, the NRC issued Revision 2 of Regulatory Guide 1.21 (Reference
However, an abnormal release to the Connecticut River is postulated due to a past leak in an underground pipe tunnel that runs between the Advanced Offgas (AOG) system building and other plant buildings which allowed accumulated piping system leakage to enter the subsurface groundwater adjacent to the plant structures. The existence of the leak was first recognized in January 2010, when a river shoreline Protected Area Boundary monitoring well sample was reported to have detectable tritium. The addition of other monitoring wells and subsequent analysis defined the extent of the affected groundwater plume moving toward the.river and helped locate the source of the leak, which was stopped in February 2010.
: 6) which introduced the term "principal radionuclide" in a risk-informed or dose context. A radionuclide can be considered a principal radionuclide if it contributes either (1) greater than 1 percent of the 10 CFR Part 50, Appendix I design objective dose for all radionuclides in the type of effluent being c01;1sidered, or (2) greater than 1 percent of the activity of all radionuclides in the type of effluent being considered.
                                                                        \
In addition to natural production in the environment, Carbon-14 is also produced in nuclear reactors as a function of power output, but at amounts muc11 less than those generated naturally or from past weapons testing. Since the time of 1 the e&rlier publication of Regulatory Guide 1.21 (Revision
Estimates of tritium-contaminated ground water released from the site are based on Protected Area Boundary monitoring well data collected throughout 2015, and hydrological modeling of ground water movement in the affected zone impacted by the pipe tunnel leak. 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 2015 was generated and reported in Table 2A.
: 1) in 1974, commercial nuclear power plants have decreased total radioactive effluents (other than Carbon-14) through improved fuel performance and waste management practices to the point today that Carbon-14 could be considered a principal radionuclide under today's definition.
Forthe projected ground water flow into the Connecticut River in 2015, the dose impact to the maximum exposed individual (MEI) assumed the following exposure pathways: (1) ingestion offish (taken from Vernon Pond), (2) ingestion of vegetables and, fresh leafy produce irrigated by water taken from the river below Vernon Dam, (3) ingestion of milk and meat from animals that were fed irrigated crops and drinking water taken from the river below Vernon Dam, and (4) pota~le water for a hypothetical individual drawing drinking water fed by the river below Vernon Dam. For Vernon Pond (river area adjacent to the plant property), the near shore mixing zone associated with the fish ingestion pathway is conservatively taken as 1% of the minimum recorded monthly river flow (3,107 cfs in September 2015) for dilution. All irrigation exposure pathways for the consumption of food products grown with irrigated water occur below Vernon Dam and assume the lowest 2015 quarterly average growing season river flow value (5394 cfs in the third quarter) for environmental mixing. For the drinking water pathway, river flow mixing is assumed to occur below Vernon Dam and uses the lowest annual quarterly average river flow (5394 cfs in the third quarter) as a conservative estimate ofriver dilution for all four quarters of the year. The dose models are
With the plant permanently shut down since December of2014, there was no plant related Carbon-14 production or associated dose impact for 2015. 3.4 Whole Body Doses in Unrestricted Areas From Direct Radiation As opposed to previous years where 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 2015 due to the plant being permanently shut down. The other fixed sources of direct and scatter radiation to the site boundary are the Independent Spent Fuel Storage Installation (ISFSI), the low level radioactive materials stored in the North Warehouse, the Low Level Waste Storage Pad Facility (no radioactive_
!aken from Regulatory Guide 1.109 (Reference 2) and use environmental parameters for exposure pathways listed in Tables 4D and 4F. .
waste material stored on the pad in 2015), and old turbine rotors and casings in the Turbine Storage Facility.
The maximum estimated quarterly and annual whole body and organ doses to the limiting age group from liquid releases are reported in Table 4A. These estimated doses are well below the 10 CFR Part 50, Appendix I dose criteria of ODCM 3/4.2.2. Table 4B provides an estimate of the total annual'dose impact (including contribution from liquids) associated with the highest exposed member of the public for demonstration of compliance to the dose standard contained in 40 CFR P~rt 190 for the uranium fuel cycle.
The annual dose is based on dose rate measurements in these storage facilities and is projected to impact the same most restrictive site boundary dose location. ,J The estimated direct radiation dose from all major sources combined for the most limiting site boundary location is listed in Table 4A. These site boundary doses assume a 100 percent occupancy factor, and take no credit for the shielding effect of any residential structure.
                                                                                                \.
Table 4B lists the combination of direct radiation doses 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 Part 190. For 2015, this annual dose was below the 25 mrem total body and organ limit, as well as the 75 mrem thyroid limit, of 40 CFR Part 190. 5 -::::.-..._.  
3
-:*' -. -..
 
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/soil 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 mrern/year to the whole body and any organ. After the period associated with Vermont Yankee operational control, the dose to the inadvertent intruder is to be limited to 5 mrern/year.
3.2 Doses From Noble Gases ODCM 3/4.3.2 limits the gamma air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I. By implementing these, ODCM 3/4.3.2 assures that the releases ofradioactive noble gases in gaseous effluents will be kept "as low as is reasonably achievable."
The projected dose from on-site disposals of septic waste, cooling tower silt, and sand/soil mixes is given in Appendix J of this report. .. The dose limits applicable to the on-site spreading of materials were met for the single spreading of septic waste in 2015, based on the combined dose from this spreading and all past spreadings.
Dose estimates due to the release of noble gases to the atmosphere are typically calculated at the site boundary, at the nearest resident in each of the sixteen principal compass directions, at the point of highest off-site ground level air concentration of radioactive materials, and at each of the milk animal locations located within five miles of the plant. For 2015, there were no noble gases detected in effluents released from the plant stack.
3 .6 On-Site Recreational Activities During 2015, no access to the on-site boat launching ramp located north of the intake structure was permitted for employees, their families, and guests. As such, there was no associated dose impact to members of the public. 6 REFERENCES
3.3 Doses From Iodine-131, Iodine-133, Tritium, Carbon-14, and Radionuclides in Particulate Form with Half-Lives Greater Than 8 Days ODCM 3/4.3.3 limits the organ dose to a member of the public from Iodine-131, Iodine-133, Tritium, Carbon-14, and radionuclides in particulate form with half-lives greater than 8 days (hereafter called "iodines and particulates") 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).
: 1. Off-site Dose Calculation Manual (ODCM), Revision 35, Entergy Nuclear Vermont Yankee, LLC, dated October 9, 2014. 2. Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 1.0 CFR Part 50, Appendix I," U.S. Nuclear Rygulatory Commission, Office of Standards Development, Revision 1, October 1977. 3. Safety Guide 1.23, "Onsite Meteorological Programs," U.S. Atomic Energy Commission, February 17, 1972. 4. Regulatory Guide "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. 7 A. l. 2. 3. B. l. 2. 3. c. l. 2. 3. 4. D. l. 2. 3. E. l. 2. TABLElA Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents  
By implementing the requirements of 10 CFR Part 50, Appendix I, ODCM 3/4.3.3 assures that the releases of iodines and particulates in gaseous effluents will be kept "as low as is reasonably achievable."
-Summation of All Releases Unit Quarter Quarter 1 2 Fission and Activation Gases Total release Ci ND ND Average release rate for period &#xb5;Ci/sec ND ND Percent ofODCM limit (1) % ND ND Iodines Total Iodine Ci ND ND Average release rate for period &#xb5;Ci/sec ND ND Percent of ODCM limit (3) % (3) (3) Particulates Particulates with T-112>8 days Ci ND ND Average release rate for period &#xb5;Ci/sec ND ND Percent of ODCM limit (3) % (3} (3) Gross alpha radioactivity Ci ND ND Tritium (4) Total release Ci 7.34E-02 7.09E-02 Average release rate for period &#xb5;Ci/sec 9.63E-03 9.22E-03 Percent ofODCM limit (3) % (3) (3) Carbon-14 Total release Ci ND ND Percent of ODCM limit (2) % 4.99E-04 4.53E-04 ND =Not Detected, or in the case of C-14, no power operations in 2015 leads to a zero estimate of C-14 production/release.
During 2015, a single frac tank was used on the Vermont Yankee site to temporarily store (outdoors) tritium-contaminated water extracted from onsite groundwater wells. The quantity of tritium released to the atmosphere through the evaporation of water from this frac tank was estimated, and the dose consequence to the maximally exposed individual was calculated.
Est. Total Error,% +/-2.30E+Ol NIA NIA +/-l.80E+Ol NIA NIA +/-l.80E+Ol NIA NIA NIA +/-l.80E+Ol NIA NIA NIA NIA (1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results. (2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form. Percentage of ODCM limit calculated using Method I dose results. ' (3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E. (4) Tritium released through evaporation from the onsite frac tank is included in these totals. 8 A. 1. 2. 3. B. 1. 2. 3. C. 1. 2. 3. 4. D. 1. 2. 3. E. 1. 2. TABLE IA (Continued)
Exposure pathways that could exist as a result of the planned (routine) release of iodines and particulates to the atmosphere include external irradiation from activity deposited onto the ground surface, inhalation, and ingestion of vegetables, meat and milk. Dose estimates were made at the site boundary and nearest resident in each of the sixteen principal compass directions, as well as all milk animal locations within five miles of the plant. The nearest resident and milk animals in each sector were identified by the most recent annual land use census as required by ODCM 3/4.5.2 (see Table 4C). Conservatively, a vegetable garden was assumed to exist at each milk animal and nearest resident location. Furthermore, the meat pathway was assumed to exist at each milk cow location since this data category is not part of the annual land use census. Doses were also calculated at the point of maximum ground level air concentration of radioactive materials in gaseous effluents and included the assumption that the inhalation, vegetable garden, and ground plane exposure pathways exist for an individual with a 100 percent occupancy factor.
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents  
It is assumed that milk and meat animals are free to graze on open pasture during the second and third quarters with no supplemental feeding. This assumption is conservative since most of the milk animals inventoried in the site vicinity are fed stored feed throughout the entire year with only limited grazing allowed during the growing season. It has also been assumed that only 50 percent of the iodine deposited from gaseous effluent is in elemental form (I2) and is available for uptake (seep. 6, Reference 2).
-Summation of All Releases Unit Quarter Quarter 3 4 Fission and Activation Gases Total release Ci ND ND Average release rate for period &#xb5;Ci/sec ND ND Percent ofODCM limit (1) % ND ND Iodines Total Iodine Ci ND ND Average release rate for period &#xb5;Ci/sec ND ND Percent of ODCM limit (3) % (3) (3) Particulates Particulates with T-1/2>8 days Ci ND ND Average release rate for period &#xb5;Ci/sec ND ND Percent of ODCM limit (3) % (3) (3) Gross alpha radioactivity Ci ND ND Tritium (4) Total release Ci l.14E-01 7.87E-02 Average release rate for period &#xb5;Ci/sec 1.46E-02 2.78E-02 Percent ofODCM limit (3) % (3) (3) Carbon-14 Total release Ci ND ND Percent ofODCM limit (2) % 7.29E-04 5.03E-04 Est. Total Error,% +/-2.30E+Ol NIA NIA +/-1.80E+Ol NIA NIA +/-1.80E+Ol NIA NIA NIA +/-1.80E+Ol NIA NIA NIA NIA ND= Not Detected, or in the case ofC-14, no power operations in 2015 leads to a zero estimate ofC-14 production/release.
4
(1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results. (2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form. Percentage of ODCM limit calculated using Method I dose results. ' (3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E. (4) Tritium released through evaporation from the onsite frac tank is included in these totals. 9
 
: 1. 2. 3. TABLEIB Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents  
During the non-growing season (first and fourth quarters), the milk animals are assumed to receive only stored feed. During the growing season (second and third quarters), all animal feed is assumed to be derived from fresh pasture. Usage factors for gaseous effluents are listed by age group and pathway in Table 4D.
-Elevated Releases Continuous Mode Quarter Nuclides Released Units 1 2 Fission Gases Argon-41 Ci ND ND Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-133m Ci ND ND Xenon-135 Ci ND ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Unidentified Ci ND ND Total for Period Ci ND ND Iodines lodine-131 Ci ND ND lodine-133 Ci ND ND lodine-135 Ci ND ND Total for Period Ci ND ND Particulates Strontium-89 Ci ND ND Strontium-90 Ci ND ND Cesium-134 Ci NP ND Cesium-137 Ci ND ND Barium-Lanthanum-140 Ci ND ND Manganese-54 Ci ND ND Chromium-51 Ci ND ND Cobalt-57 Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci ND ND Cerium-141 Ci ND ND Zinc-65 Ci ND ND Total for Period Ci ND ND ND Not Detected at the plant stack (1) There were no batch mode gaseous releases for this reporting period. 10 Batch Mode (1) Quarter 1 2 (1) (1) (1) (1) I (1) (1)
Table 4E provides other dose model parameter assumptions used in the dose assessments.
: 1. 2. 3. TABLElB (Continued)
In June 2009, the NRC issued Revision 2 of Regulatory Guide 1.21 (Reference 6) which introduced the term "principal radionuclide" in a risk-informed or dose context. A radionuclide can be considered a principal radionuclide if it contributes either (1) greater than 1 percent of the 10 CFR Part 50, Appendix I design objective dose for all radionuclides in the type of effluent being c01;1sidered, or (2) greater than 1 percent of the activity of all radionuclides in the type of effluent being considered. In addition to natural production in the environment, Carbon-14 is also produced in nuclear reactors as a function of power output, but at amounts muc11 less than those generated naturally or from past weapons testing. Since the --
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents  
time of the e&rlier publication of Regulatory Guide 1.21 (Revision 1) in 1974, commercial nuclear power 1
-Elevated Releases Continuous Mode . Quarter Nuclides Released Units 3 4. Fission Gases ( Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-133m Ci ND ND Xenon-135 Ci ND .ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Unidentified Ci ND ND Total for Period Ci ND ND Iodines Iodine-131 Ci ND ND Iodine-133 Ci ND ND Iodine-135 Ci ND ND Total for Period Ci ND ND Particulates Strontium-89 Ci ND ND Strontium-90 Ci ND ND Cesium-134 Ci ND ND Cesium-137 Ci ND ND Barium-Lanthanum-140 Ci ND ND Manganese-54 Ci ND ND Chromium Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci ND ND Cerium-141 Ci ND ND Cerium-144 Ci ND ND Zinc-65 Ci ND ND Total for Period Ci ND ND ND Not Detected at the Plant Stack (1) There were no batch mode gaseous releases for this reporting period. 11 Batch Mode (1) Quarter 3 4 (1) ' (1) (1) (1) (1) (1)
plants have decreased total radioactive effluents (other than Carbon-14) through improved fuel performance and waste management practices to the point today that Carbon-14 could be considered a principal radionuclide under today's definition. With the plant permanently shut down since December of2014, there was no plant related Carbon-14 production or associated dose impact for 2015.
TABLElC Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents-(Routine)
3.4 Whole Body Doses in Unrestricted Areas From Direct Radiation As opposed to previous years where 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 2015 due to the plant being permanently shut down.
Ground Level Releases <2) Continuous Mode Quarter Batch Mode Quarter Nuclides Released Units 1 (1) 2 (1) 1 (1) 2 (1) 1. Fission Gases Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci .Krypton-88 Ci Xenon-133 Ci Xenon-1.35 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci 2. Iodines lodine-131 Ci Iodine-133 Ci Iodine-I 35 Ci Total for Period Ci 3. Particulates Strontium-89 Ci Strontium-90 Ci _ Cesium-134 Ci Cesium-137 Ci Barium-Lanthanum-140 Ci Mimganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci Iron-55 Ci Total for Period Ci (1) There were no routine ground level gaseous releases for this reporting period. (2) No radioactively contaminated\used oil was burned during 2015. 12
The other fixed sources of direct and scatter radiation to the site boundary are the Independent Spent Fuel Storage Installation (ISFSI), the low level radioactive materials stored in the North Warehouse, the Low Level Waste Storage Pad Facility (no radioactive_ waste material stored on the pad in 2015), and old turbine rotors and casings in the Turbine Storage Facility. The annual dose is based on dose rate measurements in these storage facilities and is projected to impact the same most restrictive site boundary dose location.         ,J The estimated direct radiation dose from all major sources combined for the most limiting site boundary location is listed in Table 4A. These site boundary doses assume a 100 percent occupancy factor, and take no credit for the shielding effect of any residential structure.
: 1. 2. 3. TABLElC (Continued)
Table 4B lists the combination of direct radiation doses 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 Part 190. For 2015, this annual dose was below the 25 mrem total body and organ limit, as well as the 75 mrem thyroid limit, of 40 CFR Part 190.
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents  
5
-(Routine)
                                                                                            -
Ground Level Releases(2) Continuous Mode Quarter Nuclides Released Units 3 (I) 4 (I) Fission Gases Ktypton-85 Ci Krvoton-85m Ci Krvoton-87 Ci Krvoton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci Iodines lodine-131 Ci lodine-133 Ci lodine-135 Ci Total for Period Ci Particulates Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Barium-Lanthanum-140 Ci Manganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci Iron-55 CI Total for Period Ci (1) There were no ground level gaseous releases for this reporting period. (2) No radioactively contaminated used oil was burned during 2015. 13 Batch Mode Quarter 3 (I) 4 (1) '
                                                                          -::::.-..._. -:*' . - .. ~.
: 1. 2. 3. \ ' Nuclides Released Fission Gases Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-135  
 
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/soil 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 mrern/year to the whole body and any organ. After the period associated with Vermont Yankee operational control, the dose to the inadvertent intruder is to be limited to 5 mrern/year. The projected dose from on-site disposals of septic waste, cooling tower silt, and sand/soil mixes is given in Appendix J of this report.         ..
The dose limits applicable to the on-site spreading of materials were met for the single spreading of septic waste in 2015, based on the combined dose from this spreading and all past spreadings.
3 .6 On-Site Recreational Activities During 2015, no access to the on-site boat launching ramp located north of the intake structure was permitted for employees, their families, and guests. As such, there was no associated dose impact to members of the public.
6
 
REFERENCES
: 1. Off-site Dose Calculation Manual (ODCM), Revision 35, Entergy Nuclear Vermont Yankee, LLC, dated October 9, 2014.
: 2. Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 1.0 CFR Part 50, Appendix I," U.S.
Nuclear Rygulatory Commission, Office of Standards Development, Revision 1, October 1977.
: 3. Safety Guide 1.23, "Onsite Meteorological Programs," U.S. Atomic Energy Commission, February 17, 1972.
: 4. Regulatory Guide 1.~-11, "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.
7
 
TABLElA Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - Summation of All Releases Quarter           Quarter     Est. Total Unit 1                 2       Error,%
A.      Fission and Activation Gases
: l. Total release                                     Ci                 ND               ND       +/-2.30E+Ol
: 2. Average release rate for period                 &#xb5;Ci/sec             ND               ND           NIA
: 3. Percent ofODCM limit (1)                           %                 ND               ND           NIA B.        Iodines
: l. Total Iodine                                     Ci                 ND               ND       +/-l.80E+Ol
: 2. Average release rate for period                 &#xb5;Ci/sec             ND               ND           NIA
: 3. Percent of ODCM limit (3)                         %                 (3)               (3)         NIA
: c.      Particulates
: l. Particulates with T-112>8 days                   Ci                 ND               ND       +/-l.80E+Ol
: 2. Average release rate for period               &#xb5;Ci/sec               ND               ND           NIA
: 3. Percent of ODCM limit (3)                         %                 (3}               (3)         NIA
: 4. Gross alpha radioactivity                         Ci                 ND               ND           NIA D.      Tritium (4)
: l. Total release                                     Ci             7.34E-02         7.09E-02   +/-l.80E+Ol
: 2. Average release rate for period               &#xb5;Ci/sec           9.63E-03         9.22E-03       NIA
: 3. Percent ofODCM limit (3)                           %                 (3)               (3)         NIA E.      Carbon-14
: l. Total release                                     Ci                 ND               ND           NIA
: 2. Percent of ODCM limit (2)                         %               4.99E-04         4.53E-04       NIA ND =Not Detected, or in the case of C-14, no power operations in 2015 leads to a zero estimate of C-14 production/release.
(1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results.
(2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form.
Percentage of ODCM limit calculated using Method I dose results. '
(3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E.
(4) Tritium released through evaporation from the onsite frac tank is included in these totals.
8
 
TABLE IA (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - Summation of All Releases Quarter           Quarter     Est. Total Unit 3                 4       Error,%
A.      Fission and Activation Gases
: 1. Total release                                     Ci                 ND                 ND       +/-2.30E+Ol
: 2. Average release rate for period               &#xb5;Ci/sec               ND                 ND         NIA
: 3. Percent ofODCM limit (1)                         %                 ND                 ND         NIA B.        Iodines
: 1. Total Iodine                                     Ci                 ND                 ND       +/-1.80E+Ol
: 2. Average release rate for period                 &#xb5;Ci/sec             ND                 ND         NIA
: 3. Percent of ODCM limit (3)                         %                   (3)               (3)         NIA C.      Particulates
: 1. Particulates with T-1/2>8 days                   Ci                 ND                 ND       +/-1.80E+Ol
: 2. Average release rate for period               &#xb5;Ci/sec               ND                 ND         NIA
: 3. Percent of ODCM limit (3)                         %                 (3)               (3)         NIA
: 4. Gross alpha radioactivity                         Ci                 ND                 ND         NIA D.      Tritium (4)
: 1. Total release                                     Ci               l.14E-01         7.87E-02   +/-1.80E+Ol
: 2. Average release rate for period               &#xb5;Ci/sec             1.46E-02         2.78E-02       NIA
: 3. Percent ofODCM limit (3)                         %                   (3)               (3)         NIA E.      Carbon-14
: 1. Total release                                     Ci                 ND                 ND           NIA
: 2. Percent ofODCM limit (2)                         %               7.29E-04           5.03E-04       NIA ND= Not Detected, or in the case ofC-14, no power operations in 2015 leads to a zero estimate ofC-14 production/release.
(1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results.
(2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form.
Percentage of ODCM limit calculated using Method I dose results.               '
(3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E.
(4) Tritium released through evaporation from the onsite frac tank is included in these totals.
9
 
TABLEIB Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Elevated Releases Continuous Mode       Batch Mode (1)
Quarter            Quarter Nuclides Released               Units             1                2  1           2
: 1. Fission Gases Argon-41                     Ci             ND               ND Krypton-85                     Ci             ND               ND Krypton-85m                   Ci             ND               ND Krypton-87                     Ci             ND               ND Krypton-88                     Ci             ND               ND Xenon-133                     Ci             ND               ND Xenon-133m                   Ci             ND               ND Xenon-135                     Ci             ND               ND Xenon-135m                     Ci             ND               ND Xenon-138                     Ci             ND               ND Unidentified                   Ci             ND               ND Total for Period                 Ci             ND               ND (1)          (1)
: 2.      Iodines lodine-131                   Ci             ND               ND lodine-133                   Ci             ND               ND lodine-135                   Ci             ND               ND Total for Period                 Ci             ND               ND (1)          (1)
: 3.      Particulates Strontium-89                 Ci             ND               ND I
Strontium-90                 Ci             ND               ND Cesium-134                     Ci             NP               ND Cesium-137                     Ci             ND               ND Barium-Lanthanum-140           Ci             ND               ND Manganese-54                   Ci             ND               ND Chromium-51                   Ci             ND               ND Cobalt-57                     Ci             ND               ND Cobalt-58                   Ci             ND               ND Cobalt-60                     Ci             ND               ND Cerium-141                     Ci             ND               ND Zinc-65                       Ci             ND               ND Total for Period                 Ci             ND               ND (1)          (1)
ND    Not Detected at the plant stack (1) There were no batch mode gaseous releases for this reporting period.
10
 
TABLElB (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Elevated Releases Continuous Mode .     Batch Mode (1)
Quarter              Quarter Nuclides Released                 Units           3                 4. 3            4
: 1. Fission Gases                                       (
Krypton-85                       Ci             ND               ND Krypton-85m                     Ci             ND               ND Krypton-87                       Ci             ND               ND Krypton-88                       Ci             ND               ND Xenon-133                       Ci             ND               ND Xenon-133m                       Ci             ND               ND Xenon-135                       Ci             ND               .ND Xenon-135m                     Ci             ND               ND Xenon-138                       Ci             ND               ND Unidentified                     Ci             ND               ND Total for Period                   Ci             ND               ND (1)        '  (1)
: 2.      Iodines Iodine-131                       Ci             ND               ND Iodine-133                       Ci             ND               ND Iodine-135                       Ci             ND               ND Total for Period                   Ci             ND               ND (1)          (1)
: 3.      Particulates Strontium-89                     Ci             ND               ND Strontium-90                     Ci             ND               ND Cesium-134                       Ci             ND               ND Cesium-137                       Ci             ND               ND Barium-Lanthanum-140             Ci             ND               ND Manganese-54                   Ci             ND               ND Chromium                     Ci             ND               ND Cobalt-58                       Ci             ND               ND Cobalt-60                       Ci             ND               ND Cerium-141                       Ci             ND               ND Cerium-144                     Ci             ND               ND Zinc-65                         Ci             ND               ND Total for Period                   Ci             ND               ND (1)          (1)
ND     Not Detected at the Plant Stack (1)   There were no batch mode gaseous releases for this reporting period.
11
 
TABLElC Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents-(Routine) Ground Level Releases <2)
Continuous Mode           Batch Mode Quarter                Quarter Nuclides Released               Units             1 (1)           2 (1) 1 (1)         2 (1)
: 1.     Fission Gases Krypton-85                     Ci Krypton-85m                     Ci Krypton-87                     Ci
            .Krypton-88                     Ci Xenon-133                       Ci Xenon-1.35                     Ci Xenon-135m                     Ci Xenon-138                       Ci Unidentified                   Ci Total for Period                 Ci
: 2.       Iodines lodine-131                     Ci Iodine-133                     Ci Iodine-I 35                   Ci Total for Period                 Ci
: 3.       Particulates Strontium-89                   Ci Strontium-90                   Ci
_ Cesium-134                     Ci Cesium- 137                   Ci Barium-Lanthanum-140           Ci Mimganese-54                   Ci Chromium-51                   Ci Cobalt-58                     Ci Cobalt-60                     Ci Cerium-141                     Ci Zinc-65                       Ci Iron-55                       Ci Total for Period                 Ci (1) There were no routine ground level gaseous releases for this reporting period.
(2) No radioactively contaminated\used oil was burned during 2015.
12
 
TABLElC (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - (Routine) Ground Level Releases(2)
Continuous Mode        Batch Mode Quarter              Quarter Nuclides Released                 Units               3 (I)         4 (I) 3 (I)          4 (1)
: 1. Fission Gases Ktypton-85                       Ci Krvoton-85m                       Ci Krvoton-87                       Ci Krvoton-88                       Ci Xenon-133                         Ci Xenon-135                         Ci Xenon-135m                       Ci Xenon-138                         Ci Unidentified                     Ci Total for Period                   Ci                                                       '
: 2.      Iodines lodine-131                       Ci lodine-133                       Ci lodine-135                       Ci Total for Period                   Ci
: 3.      Particulates Strontium-89                     Ci Strontium-90                     Ci Cesium- 134                       Ci Cesium-137                       Ci Barium-Lanthanum- 140             Ci Manganese-54                     Ci Chromium-51                       Ci Cobalt-58                         Ci Cobalt-60                         Ci Cerium-141                       Ci Zinc-65                           Ci Iron-55                           CI Total for Period                   Ci (1) There were no ground level gaseous releases for this reporting period.
(2) No radioactively contaminated used oil was burned during 2015.
13
 
TABLElD Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Non-routine Releases Quarter                    Quarter Nuclides Released                Units              1(1)              2(1)      3(1)        4(1)
: 1.       Fission Gases Krypton-85                     Ci Krypton-85m                     Ci Krypton-87           "        Ci Krypton-88                     Ci Xenon-133                     Ci Xenon-135                     Ci Xenon-135m                    Ci Xenon-138                      Ci Unidentified                  Ci Total for Period                  Ci
: 2.        Iodines lodine-131                    Ci
              . lodine-133                    Ci Iodine-I 35                  Ci Total for Period                  Ci
: 3. '      Particulates Strontium-89                  Ci                                  )
Strontium-90                  Ci Cesium-134                    Ci Cesium- 137                    Ci
\              Barium-Lanthanum-140          Ci Manganese-54                  Ci Chromium-51                  Ci Cobalt-58                    Ci Cobalt-60                    Ci Cerium-141                    Ci Zinc-65                      Ci lron-55                      Cl Total for Period                  Ci (1) There were no non-routine ground level gaseous releases for this reporting period.
14
 
TABLE2A Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Summation of All Releases Est. Total Units      Quarter 1        Quarter 2        Error,%
A. Fission and Activation Products
: 1. Total Release (not includina tritium, aases, alpha)        Ci          ND                ND            N/A    I
: 2. Average Diluted Concentration Durina Period              uCi/ml        ND                ND
: 3. Percent of Aoolicable Limit (1)                            %          ND                ND
: 8. Tritium
: 1. Total Release                                              Ci      8.85E-03        9.05E-03      +/-2.00E+01  I
: 2.
* Averaae Diluted Concentration Durina Period              uCi/ml      1.67E-06        1.66E-06
: 3. Percent of Applicable Limit (1)                            %        5.90E-05        6.03E-05 C. Dissolved and Entrained Gases
: 1. Total Release                                              Ci          ND                ND            N/A    I
: 2. Averaae Diluted Concentration Durina Period              &#xb5;Ci/ml        ND                ND
: 3. Percent of Aoolicable Limit                                %          ND                ND D. Gross Al ha Radioactivit
: 1. Total Release                                              Ci          ND                ND            N/A E. Volume of Waste Release        rior to dilution              Liters                                          N/A I F. Volume of Dilution Water Used During Period                  Liters      3.89E+06        3.89E+06            (3)
ND    Not detected in liquid effluents.
(1)  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 abnorr:nal leakage of tritiated plant water into the underground environment.
The percent of the concentration limits specified in Appendix B to 1OCFR20.1001 - 20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.
(2)  Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015.
(3)  Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.
15
 
TABLE2A (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Summation of All Releases Est. Total Units    Quarter 3        Quarter 4        Error,%
A. Fission and Activation Products
: 1. Total Release (not including tritium, gases, alpha)        Ci        ND                ND            N/A    I
: 2. Average Diluted Concentration Durina Period            &#xb5;Ci/ml        ND                ND
: 3. Percent of Aoolicable Limit (1)                            %          ND                ND B. Tritium
: 1. Total Release                                              Ci      8.02E-03        7.50E-03      +/-2.00E+01  I
: 2. Average Diluted Concentration During Period            &#xb5;Ci/ml    1.46E-06        1.36E-06
: 3. Percent of Aonlicable Limit (1)                            %      5.35E-05        5.00E-05 C. Dissolved and Entrained Gases
: 1. Total Release                                              Ci        ND                ND            N/A    I
: 2. Average Diluted Concentration Durina Period            uCi/ml        ND                ND
: 3. Percent of Aoolicable Limit                                %          ND                ND D. Gross Al ha Radioactivi
: 1. Total Release                                              Ci        ND                ND            N/A E. Volume of Waste Release        rior to dilution              Liters                                        N/A l F. Volume of Dilution Water Used During Period                  Liters    3.89E+06        3.89E+06            (3)
ND    Not detected in liquid effluents.
(1)  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.
The percent of the concentration limits specified in Appendix B to 1OCFR20.1001 - 20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.
(2)  Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015.
(3)  Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.
16
 
TABLE2B Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Routine Releases Continuous Mode          Batch Mode I Nuclides Released                                Units    Quarter 1 I Quarter 2 Quarter 1 I Quarter 2 Strontium-89                                  Ci        -          -        -            -
Strontium-90                                  Ci        -          -        -            -
Cesium-134                                    Ci        -          -        -            -
Cesium-137                                    Ci        -          -        -            -
lodine-131                                    Ci        -          -        -            -
Cobalt-58                                      Ci        -          -        -            -
Cobalt-60                                      Ci        -          -        -            -
lron-59                                        Ci        -          -        -            -
Zinc-6.5                                      Ci        -          -        -            -
Manganese-54                                  Ci        -          -        -            -
Zirconium-Niobium-95                            Ci        -          -        -            -
Molvbdenum-99                                  Ci        -          -        -            -
Technetium-99                                  Ci        -          -        -            -
Barium-Lanthanum-140                          Ci        -          -        -            -
Cerium-141 Other (specify)                                Ci Ci Ci Unidentified                              I    Ci  I Total for Period (above)                      Ci Xe-133                                        Ci Xe-135                                        Ci ND    Not detected in liquid effluents.
Dash indicates no release of this type.
17
 
TABLE2B (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Routine Releases Continuous Mode          Batch Mode I Nuclides Released                                Units    Quarter 3  I Quarter 4 Quarter 3 I Quarter 4 Strontium-89                                  Ci        -          -        -            -
Strontium-90                                  Ci        -          -        -            -
Cesium-134                                    Ci        -          -        -            -
Cesium-137                                    Ci        -          -        -            -
lodine-131                                    Ci        -          -        -            -
Cobalt-58                                      Ci        -          -        -            -
Cobalt-60                                      Ci        -          -        -            -
lron-59                                        Ci        -          -        -            -
Zinc-65                                        Ci        -          -        -            -
Manganese-54                                  Ci        -          -        -            -
2irconium-Niobium-95                            Ci        -          -        -            -
    *Molybdenum-99                                  Ci        -          -        -            -
Technetium-99                                  Ci        -          -        -            -
Barium-Lanthanum-140                          Ci        -          -        -            -
Cerium-141 Other (specify)                                Ci Ci Ci Unidentified                              I    Ci  I Total for Period (above)                      Ci Xe-133                                        Ci Xe-135                                        Ci ND    Not detected in liquid effluents.
Dash indicates no release of this type.
18
 
TABLE3 Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Solid Waste and Irradiated Fuel Shipments Tabl..l fntersv Nucl*u vennontVanb:e Eftluentw WomD/spo,otAm111ot ~
                                                      ' f/ntonds-a-/!irZOJS Sol/d Wart~.o*dlrrodlottdFudSlr/pmonrs A. t,o114W>illi Slllol><d.OlMlto foto-orOl....,.llo** lm.u....tlucl}
a          ~
m!                No..
Cl              Ncl!lt ml                H. ..
                                                            .Q                NC!!!O        N/A ml              No ..          NA Ct              Horic-        NIA
                                                              **3          o.&.iE*OI        tlS!I cf            5.7Sr*02        ti$>>
mJ                Nnne          fl*
Q.              Nan*          NA mJ            *UOfUJS          US!I Cl          1.00[*cS        >JS!I
                                                                                                                              *! .
J:Ji' *!r'''* (;'~i;,~~M:;~~--:'.ii~ij,t>'*;,                      ~*,;i..~iw~~~ ...
_ *- _.                                                                      .....
Nut!'llt.&      PH<<:ttittt*          Nlldld*          ltrci:ntfll                        NutUitl'  P.af'C'ttl.tCU j"
                                                                                                                            -
tultM-t4            O.U'4            c~~ud'MI              U!J<.                        (Dh!i*liQ
                  ~'.\S              LM'll            C,o:b,.11>60          5131-K
                                      .......                                                              Cc1wmU1*
                                                                                                              .......
                                                                                                                              !!<
Colml*M Cftium-U7    ..    .,.,,,.      &deg;""'""'""I tl!Ullrit-ll1 u~
OJm Hldri..i                              ...... "
ltoA<H            .71.1$Ul*
u ...
                  -
OJ!"
              .....,__124          'U"'
11.J&K.
                                                  .....................
H2tld*'1
                                                                              $.-
                                                                              ..,.,.
                                                                              ,,,  .
                                                                                  ,.
* _...__114 A:nrlmc--Ja                ...~-*
                                                        .......              9..1'1!1.
ESllCD lN 1                                                      ffll<l<                  W1 1-~~*''--~--i~~~~.j-~...!!.~~i--.....i.T~N~                              ..i.,_...f.~~~~~k-~~!!f~~~-
:@ij.*{4.lb:~t:lll~
OC,O.a&~.vCf~~~m.
        'n~Yh:t~l;::tml~<'A$,;wtWh~
        "H"-frn~rr$&#xa3;ii;~~          *
        <iOC*G~IJ!l~,tnQ:mtlh" 19


Xenon-135m Xenon-138 Unidentified Total for Period Iodines lodine-131 . lodine-133 Iodine-I 35 Total for Period Particulates Strontium-89 Strontium-90 Cesium-134 Cesium-137 TABLElD Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Non-routine Releases Quarter Units 1(1) 2(1) Ci Ci " Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci ) Ci Ci Ci Barium-Lanthanum-140 Ci Manganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci lron-55 Cl Total for Period Ci (1) There were no non-routine ground level gaseous releases for this reporting period. 14 Quarter 3(1) 4(1)
TABLE2A Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents
-Summation of All Releases Units Quarter 1 Quarter 2 A. Fission and Activation Products 1. Total Release (not includina tritium, aases, alpha) Ci ND ND 2. Average Diluted Concentration Durina Period uCi/ml ND ND 3. Percent of Aoolicable Limit (1) % ND ND 8. Tritium Est. Total Error,% N/A I 1. Total Release Ci 8.85E-03 9.05E-03 +/-2.00E+01 I 2.
* Averaae Diluted Concentration Durina Period uCi/ml 1.67E-06 1.66E-06
: 3. Percent of Applicable Limit (1) % 5.90E-05 6.03E-05 C. Dissolved and Entrained Gases 1. Total Release Ci ND ND N/A 2. Averaae Diluted Concentration Durina Period &#xb5;Ci/ml ND ND 3. Percent of Aoolicable Limit % ND ND D. Gross Al ha Radioactivit
: 1. Total Release Ci ND ND N/A E. Volume of Waste Release rior to dilution Liters N/A I F. Volume of Dilution Water Used During Period Liters 3.89E+06 3.89E+06 (3) ND Not detected in liquid effluents.
(1) 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 abnorr:nal leakage of tritiated plant water into the underground environment.
The percent of the concentration limits specified in Appendix B to 1OCFR20.1001
-20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.
(2) Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015. (3) Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.
15 I TABLE2A (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents
-Summation of All Releases Units Quarter 3 Quarter 4 A. Fission and Activation Products 1. Total Release (not including tritium, gases, alpha) Ci ND ND 2. Average Diluted Concentration Durina Period &#xb5;Ci/ml ND ND 3. Percent of Aoolicable Limit (1) % ND ND B. Tritium Est. Total Error,% N/A I 1. Total Release Ci 8.02E-03 7.50E-03 +/-2.00E+01 I 2. Average Diluted Concentration During Period &#xb5;Ci/ml 1.46E-06 1.36E-06 3. Percent of Aonlicable Limit (1) % 5.35E-05 5.00E-05 C. Dissolved and Entrained Gases 1. Total Release Ci ND ND N/A 2. Average Diluted Concentration Durina Period uCi/ml ND ND 3. Percent of Aoolicable Limit % ND ND D. Gross Al ha Radioactivi
: 1. Total Release Ci ND ND N/A E. Volume of Waste Release rior to dilution Liters N/A l F. Volume of Dilution Water Used During Period Liters 3.89E+06 3.89E+06 (3) ND Not detected in liquid effluents.
(1) 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.
The percent of the concentration limits specified in Appendix B to 1OCFR20.1001
-20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.
(2) Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015. (3) Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.
16 I TABLE2B Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents
-Routine Releases Continuous Mode Batch Mode I Nuclides Released Units Quarter 1 I Quarter 2 Quarter 1 I Quarter 2 Strontium-89 Ci ----Strontium-90 Ci ----Cesium-134 Ci ----Cesium-137 Ci ----lodine-131 Ci ----Cobalt-58 Ci ----Cobalt-60 Ci ----lron-59 Ci ----Zinc-6.5 Ci ----Manganese-54 Ci ----Zirconium-Niobium-95 Ci ----Molvbdenum-99 Ci ----Technetium-99 Ci ----Barium-Lanthanum-140 Ci ----Cerium-141 Other (specify)
I Ci I Ci Ci Unidentified Ci Total for Period (above) Ci Xe-133 Ci Xe-135 Ci ND Not detected in liquid effluents.
Dash indicates no release of this type. 17 TABLE2B (Continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents
-Routine Releases Continuous Mode Batch Mode I Nuclides Released Units Quarter 3 I Quarter 4 Quarter 3 I Quarter 4 Strontium-89 Ci ----Strontium-90 Ci ----Cesium-134 Ci ----Cesium-137 Ci ----lodine-131 Ci ----Cobalt-58 Ci ----Cobalt-60 Ci ----lron-59 Ci ----Zinc-65 Ci ----Manganese-54 Ci ----2irconium-Niobium-95 Ci ----* Molybdenum-99 Ci ----Technetium-99 Ci ----Barium-Lanthanum-140 Ci ----Cerium-141 Other (specify)
I Ci I Ci Ci Unidentified Ci Total for Period (above) Ci Xe-133 Ci Xe-135 Ci ND Not detected in liquid effluents.
Dash indicates no release of this type. 18 TABLE3 Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Solid Waste and Irradiated Fuel Shipments Tabl .. l fntersv Nucl*u vennontVanb:e Eftluentw WomD/spo,otAm111ot ' f/ntonds-a-/!irZOJS Sol/d A. t,o114W>illi Slllol><d.OlMlto foto-orOl....,.llo**
lm.u....tlucl}
a m! No .. Cl Ncl!lt ml H. .. .Q NC!!!O N/A ml No .. NA Ct Horic-NIA **3 o.&.iE*OI tlS!I cf 5.7Sr*02 ti$>> mJ Nnne fl* Q. Nan* NA mJ *UOfUJS US!I Cl 1.00[*cS >JS!I J:Ji' *!r'''*
Nut!'llt.&
PH<<:ttittt*
Nlldld* ltrci:ntfll tultM-t4 O.U'4 U!J<. .....
LM'll C,o:b,.11>60 5131-K Colml*M ....... &deg;""'""'""I Cftium-U7
.,.,,,. tl!Ullrit-ll1 OJm _ .. *-ltoA<H .71.1$Ul*
Hldri..i OJ!" ...... u ... ..... ,__124 'U"' ..................... " $.--11.J&K. _ .. ..,.,. H2tld*'1 ,,, .
* _...__114 A:nrlmc--Ja
... , .. ....... 9..1'1!1.
ESllCD lN
... NutUitl' (Dh!i*liQ Cc1wmU1* ....... 1 ffll<l< W1
..
* 19 * ! . P.af'C'ttl.tCU j" !!< -
TABLE 3 (continued)
TABLE 3 (continued)
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Solid Waste and Irradiated Fuel Shipments EnleJIY NudearVennont Yanlcee E/ffllflll and W-Olsposc/
Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Solid Waste and Irradiated Fuel Shipments Ta~lt'-3 EnleJIY NudearVennont Yanlcee E/ffllflll and W-Olsposc/ An1"Ull Rqiott Jlrlnl oad l'o<mh 4uoJfen:fur 2015 So/Id Wmt., and lrrodi'med Fur:UhlJ11Mflfl II. 5olldW..1~Sl!l,ppodOlf*Slt*lor&deg;",'i'I"' Dhpoool lnotflmll>IO<I l'ucQ J, T~otwa:ne
An1"Ull Rqiott Jlrlnl oad l'o<mh 4uoJfen: fur 2015 So/Id Wmt., and lrrodi'med Fur:UhlJ11Mflfl II.
: 1. < ,;\S!ii\ltdl1oolti1.:?ii&#xa3;w:c,,, <'''<:,"!121"''*"                   ~:r10~.t\iiB&Xi  /i1k1T0inilt..&ilP
Dhpoool lnotflmll>IO<I l'ucQ J, 1 .. < ,;\S!ii\ltdl1oolti1.:?ii&#xa3;w:c,,, <'''<:,"!121"''*"  
        ~fo:ol !!""rf<l""'!'- ....                                 ml             1.45!.0I           t%SS a             3001101           !JS!i.
/i1k1T0inilt..&ilP  
PIYC~..au~.<<lUllElfllftll            fir.               ml                 Ncnc           NIA Cl                 Hn**           N/A c.ln*~~l\.l;f!IUd11c11:b.tU                              mJ                                  II/A 0                 """"
!!""rf<l""'!'-
N&deg;"'           N/A
.... ml 1.45!.0I t%SS a 3001101 !JS!i.
          &deg;'""'""                                                                     ....
fir. ml Ncnc NIA Cl Hn** N/A mJ """" II/A 0 N&deg;"' N/A 4 &deg;'""'"" mJ* Plone NIA Q ,. ... N/A :.a ml NOl>O Ii/A C1 Nooe N/A b ml l.BOfiOJ tis5 0 9.JU*Ol m" c mJ No.,. NIA Cl N-411e 11/11 fif*Olb* ta.g ml 2.JSE!OI us" 0 5.(19&#xa3;.QS i2SK :!. &11...,* cl Molor Nutlldc tomi>MlllO ISV TYl>O of W11u.1. Nudlde P:1rc"ntUl..
                                                                                      ,Plone mJ*                                NIA 4
N'iKUdo 1'1m:ootf11 NU<liile C>rbon 14 :um Ccb1tl*SI UJlil """' Cobol<H D.9. Cul:ri)fl60 nn" Collall"O Ji.ll" Chlomlum-S1 1.)211 Citl.it1:t1*U7 J.Ollt. C0Jr;m.U1 ll20ll "&deg;"'.SS IUSK .,,,.n ,974t'o l.11'1 troon-!9 IU>>I Nldd-63 ll.12" ....... H .. 54 J.IOK Zllic.*6S 1a.uw.
Q                                  N/A
um 1,28% Anbm01Pt*l2*
:.a ~rnm.fll"~"k                                          ml                   NOl>O           Ii/A C1                 Nooe           N/A b   Dtr~~WW.-hft.nJ.rff,                                  ml               l.BOfiOJ           tis5 0               9.JU*Ol           m" c tt1.-t~~nznk.f:tlnllOifH~,d'                            mJ                   No.,.           NIA Cl                 N-411e         11/11 fif*Olb* ta.g                                             ml               2.JSE!OI           us" 0               5.(19&#xa3;.QS         i2SK
0.2"" Antt-...JJ.S  
:!. &11...,* cl Molor Nutlldc tomi>MlllO       ISV TYl>O of W11u.1.
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* (a) (b) (c) (d) (e) (f) (g) TABLE4A Entergy Nuclear Vermont Yankee Maximum* Quarterly and Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 Source Total Body Dose Footnotes Organ Dose Footnotes Beta Air (mrad) Footnotes Gamma Air (mrad) Footnotes (10CFR50, Appendix I) Dose (mrem)(a) 3rd Quarter 9.80E-07 l.OOE-06 8.88E-07 (c) (c) (c) 9.80E-07 l.OOE-06 8.88E-07 (c) (c) (c) l.64E-05 4.24E-05 (g) (t) (d) (d) (d) 0.72 Year(b) 8.31E-07 3.70E-06 (c) (c) 8.31E-07 3.70E-06 (c) (c) (t) (d) "Maximum" means the largest fraction of the corresponding 10CFR50, Appendix I dose design objective.
                                                              *trrte..&#xa3;5             ......
The lettered footnotes indicate the age group, organ, and location of the dose receptor, where appropriate.
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The yearly dose is the sum of the doses for each quarter, or a full annual assessment.
WCS-.WHteCentr<<r..r.tr.tw.ius SS*ft1b:fn$.ilttl1~
The critical age group/organ for the Maximum Exposed Individual (MEI) is the Adult/Total Body and all organs (except Bone) from the release ofH-3 to groundwater.
G'OC. ~ G1tt1t"f~ ~ Ctwt-tlit1tt 20
There were no noble gas releases in this quarter. Maximum direct dose point located on the old west site boundary, approximately 208 meters from the Turbine Building (per ODCM, Rev. 35, Sect. 6.11.1). The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location WNW, 2400 meters from the stack. The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location NW, 2900 meters from the stack. 21 TABLE4B Entergy Nuclear Vermont Yankee Maximum* Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 (40CFR190)
 
Pathway Total Body Maximum Organ (mrem) (mrem) Thyroid (mrem) Direct External (a) (b) 2.88 2.88 2.88 Liquids (c) 3.70E-06 3.70E-06 3.70E-06 Gases (c)' l.07E-04 l.07E-04 l.07E-04 Annual Total ( d) 2.88 2.88 2.88 * (a) (b) (c) (d) 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. No residential shielding credit or occupancy time fraction (i.e., occupancy is assumed to be I00%) 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 I. I 09 (Reference
TABLE4A Entergy Nuclear Vermont Yankee Maximum* Quarterly and Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 (10CFR50, Appendix I)
: 2) and an annual occupancy time of 6760 hours). The direct dose reported here was calculated using the current ODCM methodology 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. Maximum dose to any organ over all age groups for each release. Annual dose 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. 22 Sector N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW TABLE4C Receptor Locations Entergy Nuclear Vermont Yankee Site Boundary (I) Nearest Resident<2 l (meters) (meters) 400 1400 350 1384. 350 1255 400 966 500 933 700 1915 \ 750 1963 850 2044 385 644 300 451 250 418 250 451 300 628 400 1062 550 2253 550 1738 (1) Site boundary locations taken from Table 6.10.2 of the ODCM. Nearest Mille Animal <2 l (meters) --5520 (cows) --------3600 (cows) --------9730 (cows) 820 (cows) ------(2) The location(s) given are based on information from the Vermont Yankee 2015 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.
Dose (mrem)(a) 3rd Source                                                                                Year(b)
Quarter Total Body Dose            9.80E-07      l.OOE-06      8.88E-07        8.31E-07    3.70E-06 Footnotes        (c)           (c)           (c)             (c)           (c)
Organ Dose                  9.80E-07     l.OOE-06     8.88E-07         8.31E-07    3.70E-06 Footnotes        (c)           (c)           (c)             (c)           (c) l.64E-05     4.24E-05 (g)           (t)             (t)
Beta Air (mrad)
Footnotes        (d)           (d)           (d)             (d)
Gamma Air (mrad)
Footnotes 0.72
*      "Maximum" means the largest fraction of the corresponding 10CFR50, Appendix I dose design objective.
(a)    The lettered footnotes indicate the age group, organ, and location of the dose receptor, where appropriate.
(b)    The yearly dose is the sum of the doses for each quarter, or a full annual assessment.
(c)    The critical age group/organ for the Maximum Exposed Individual (MEI) is the Adult/Total Body and all organs (except Bone) from the release ofH-3 to groundwater.
(d)    There were no noble gas releases in this quarter.
(e)    Maximum direct dose point located on the old west site boundary, approximately 208 meters from the Turbine Building (per ODCM, Rev. 35, Sect. 6.11.1).
(f)    The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location WNW, 2400 meters from the stack.
(g)    The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location NW, 2900 meters from the stack.
21
 
TABLE4B Entergy Nuclear Vermont Yankee Maximum* Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 (40CFR190)
Total Body         Maximum Organ                 Thyroid Pathway (mrem)                 (mrem)                     (mrem)
Direct External (a) (b)               2.88                   2.88                     2.88 Liquids (c)                       3.70E-06               3.70E-06                 3.70E-06 Gases (c)'                         l.07E-04               l.07E-04                 l.07E-04 Annual Total (d)                     2.88                   2.88                     2.88
* 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 I00%)
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 I. I 09 (Reference 2) and an annual occupancy time of 6760 hours).
(b)  The direct dose reported here was calculated using the current ODCM methodology 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.
(c)  Maximum dose to any organ over all age groups for each release.
(d)  Annual dose 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.
22
 
TABLE4C Receptor Locations Entergy Nuclear Vermont Yankee Nearest Mille Sector          Site Boundary (I)   Nearest Resident<2l      Animal <2l (meters)            (meters)             (meters)
N                  400                 1400                   --
NNE                  350                 1384.           5520 (cows)
NE                  350                 1255                   --
ENE                  400                 966                   --
E                  500                 933                   --
ESE                  700                 1915
                                                                  \
                                                                                  --
SE                  750                1963            3600 (cows)
SSE                  850                 2044                 --
s                  385                 644                 --
SSW                  300                 451                   --
SW                  250                 418                 --
WSW                    250                 451             9730 (cows) w                  300                 628             820 (cows)
WNW                    400                 1062                 --
NW                    550                 2253                 --
NNW                    550                 1738                   --
(1) Site boundary locations taken from Table 6.10.2 of the ODCM.
(2) The location(s) given are based on information from the Vermont Yankee 2015 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.
* 23
* 23
* Age *Fish Group (kg/yr) Adult 21 Teen 16 Child 6.9 Infant 0 TABLE4D Usage Factors for Environmental Pathways Entergy Nuclear Vermont Yankee* Potable Veg. Leafy Veg. Milk Water (I/yr) (kg/yr) (kg/yr) (I/yr) 730 520 64 310 510 630 42 400 510 520 26 330 330 0 0 330 Regulatory Guide 1.109, Table E-5 (Reference 2). 24 Meat Inhalation (kg/yr) (m 3/yr) 110 8,000 65 8,000 41 3,700 0 1,400 I Variable I YV Agricultural Productivity (kg/m 2) p Soil Surface Density (kiz/m 2) T Transport Time to User (hrs) TB Soil Exposure Time(a)(hrs)
 
TE Crop Exposure Time to Plume (hrs) TH Holdup After Harvest (hrs) QF Animals Daily Feed (kg/dav) FP Fraction of Year on Pasture FS Fraction Pasture Feed When on Pasture(c)
TABLE4D Usage Factors for Environmental Pathways Entergy Nuclear Vermont Yankee*
Note: Footnotes on following page. TABLE4E Environmental Parameters for Gaseous Effluents
Age        *Fish      Potable       Veg.     Leafy Veg. Milk   Meat  Inhalation Group      (kg/yr)      Water       (kg/yr)      (kg/yr)    (I/yr) (kg/yr)   (m3/yr)
* Entergy Nuclear Vermont Yankee Vegetables I Cow Milk Goat Milk . Stored I Leafy I Pasture Stored Pasture Stored 2 2 0.70 2 0.70 2 240 240 240 240 240 240 ----48 48 48 48 131,400 131,400 131,400 131,400 131,400 131,400 1,440 1,440 720 1,440 720 1,440 1,440 24 0 2,160 0 2,160 ---M 50 so 6 6 "' ----(b) --(b) ------1 --1 --25 I Meat I I Pasture I Stored I 0.70 2 240 240 480 480 131,400 131,400 720 1,440 0 2,160 50 50 (b) --1 --
(I/yr)
FG FL FI H * (a) (b) (c) (d) I Variable Fraction of Stored Vegetables Grown in Garden Fraction of Leafy Vegetables Grown in Garden Fraction Elemental Iodine = 0.5 Absolute Humidity=
Adult        21        730         520           64       310     110      8,000 Teen        16        510         630           42       400     65      8,000 Child        6.9        510         520           26       330     41      3,700 Infant        0        330           0             0       330     0      1,400
5.6Cd) TABLE 4E (Continued)
* Regulatory Guide 1.109, Table E-5 (Reference 2).
Environmental Parameters for Gaseous Effluents Entergy Nuclear Vermont Yankee Vegetables I Cow Milk Stored Leafy Pasture Stored 0.76 --------1.0 --------------------From VY ODCM, Table 6.9.l (Reference 1). Goat Milk Meat Stor--' n-ctnre Stored II ----------------------------I ----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 hours (one year) for all pathways.
24
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. 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. For all Method II analyses, an absolute humidity value equal to 5.6 (gm/m 3) shall be used to reflect conditions in the Northeast (
 
TABLE4E Environmental Parameters for Gaseous Effluents
* Entergy Nuclear Vermont Yankee I        Vegetables     I         Cow Milk               Goat Milk       I        Meat          I Variable I . Stored I Leafy I         Pasture      Stored    Pasture       Stored I Pasture Stored I
Agricultural Productivity YV      (kg/m2) 2              2         0.70            2       0.70           2       0.70           2 p                                        240          240        240           240       240           240       240         240 Soil Surface Density (kiz/m2)
                                                                                                                                          ~
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     131,400 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/dav)          --           -M 50           so         6             6 "'     50          50 FP    Fraction of Year on Pasture          --           --         (b)           --       (b)           --       (b)          --
FS    Fraction Pasture Feed When on Pasture(c)
                                              --           --           1           --         1             --         1           --
Note: Footnotes on following page.
25
 
TABLE 4E (Continued)
Environmental Parameters for Gaseous Effluents Entergy Nuclear Vermont Yankee I        Vegetables         I       Cow Milk                     Goat Milk                      Meat Variable                      Stored       Leafy         Pasture         Stored                      Stor--'      n-ctnre      Stored  II FG      Fraction of Stored Vegetables          0.76           --           --             --           --             --           --           --
Grown in Garden FL      Fraction of Leafy Vegetables            --           1.0            --             --           --             --             --           --
Grown in Garden FI    Fraction Elemental Iodine = 0.5          --             --           --             --           --             --           --           --
H      Absolute Humidity= 5.6Cd)                --             --           --             --           --             --         I --           --
* From VY ODCM, Table 6.9.l (Reference 1).
(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 hours (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:==
==Reference:==
Health Physics Journal, Volume 39 (August), 1980; Pages 318-320, Pergammon Press).                                                  ,
26
TABLE4F Environmental Parameters for Liquid Releases (Tritium) Via Groundwater Entergy Nuclear Vermont Yankee Variable Potable Water    Aquatic Food      Stored Veg.      Leafy Veg.        Meat  Cow Milk Name      (Units)
                                                        ~
Mixing Ratio      3.23E-06        5.62E-04        3.23E-06        3.23E-06      3.23E-06 3.23E-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)
    ,-
27
TABLE5A VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS A                CLASS FREQUENCY (PERCENT) =    1.15 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE      E  ESE      SE    SSE      s  SSW    SW  WSW      w  WNW    NW  NNW VRBL    TOTAL MPH CALM      4    0    0    0      0    0      0        0    0    0      0    0      0    0    0    0      0      4 (1)  4.00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .00  .00  .00  .00    4.00 (2)  .05    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .00  .00  .00  .00      .05 C-3      2    0    1    1      6    3      2        0    0    0      0    0      0    0    0    4      0      19 (1)  2.00    .00 1. 00 1.00  6.00  3.00  2.00      .00    .00  .00  .00  .00    .00  .00  .00  4.00  .00    19.00 (2)  .02    .00  .01  .01    .07  .03  .02      .00    .00  .00  .00  .00    . 00  .00  .00  .05  .00      .22 .
4-7      1    1    0    5    18  14      3        3    1    0      2    0      1    0    2    3      0      54 (1)  1. 00 1. 00  .00  5.00 18.00 14.00  3.00    3.*00  1. 00  .00  2.00  .00  1. 00  .00  2.00  3.00  .00    54.00 (2)  .01    .01  .00  .06    .21  .16  .03      .03    .01  .00  .02  .00    .01  .00  . 02  .03  .00      . 62 8-12      0    1    0    0      0    8      5        3    1    0      0    1      0    0    0    3      0      22 (1)  .00  1. 00  .00  .00    .00 8.00  5.00    3.00  1. 00  .00  .00  1. 00  .00  .00  .00  3.00  .00    22.00 (2)  .00    .01  .00  .00    .00  .09  .06      .03    .01  .00  .00  .01    .00  .00  .00  .03  .00      .25 13-18      0    0    0    0      0    0      0        0    0    0      0    0      0    1    0    0      0      1 (1)  .00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  1. 00  .00  .00  .00    1. 00 (2)  .00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .01  .00  .00  .00      .01 19-24      0    0    0    0      0    0      0        0    0    0      0    0      0    0    0    0      0      0 (1)  .00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .00  .00  .00  .00      .00 (2)  .00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .00  .00  .00  . .00    .00 GT 24      0    0    0    0      0    0      0        0    0    0      0    0      0    0    0    0      0      0 (1)  .00    .00  .00  .00    .00  .00  .00      .,00  .00  .00  .00  .00  .. 00  .00  .00  .00  .oo      .00 (2)  .00    .00  .00  .00    .00  .00  .00      .00    .00  .00  .00  .00    .00  .00  .00  .00  .00      .00 ALL SPEEDS        7    2    1    6    24  25      10        6    2    0      2    1      1    1    2  10      0    100 (1)  7.00  2.00  1. 00 6.00 24.00 25.00 10.00    6.00  2.00  .00  2.00  1.00  1. 00  1. 00 2.00 10.00  .00  100.00 (2)  .08    .02  .01  .07    .28  .29  .. 11    .07    .02  .00    .02  .01    .01  .01  .02  .11  .00    1.15 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 28
TABLE SB VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS B              CLASS FREQUENCY (PERCENT) =  2.05 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE    E  ESE    SE    SSE      s  SSW    SW  WSW      w  WNW    NW  NNW  VRBL  TOTAL MPH CALM      0    0    0    0    0      0    0      0      0    0    0    0      0    0    0    0    0      0 (1)  .00    .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .00  .00  .00    .00 (2)  .00    .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .00  .00  .00    .00 C-3      4    5    5    2    1      3    0      2      1    0    0    0      0    2    0    2    0    27 (1)  2.25  2.81  2.81  1.12  .56  1. 69  .00  1.12    .56  .00  .00  .00  .00  1.12  .00  1.12  .00  15.17 (2)  .05    .06  .06  .02  .01  .03  .00    .02    .01  .00  .00  .00  .00  .02  .00  .02  .00    .31 4-7    10    2    3    6    19    18  11      15      5    1    0    0      0    1    1    4    0    96 (1)  5. 62 1.12  1. 69 3.37 10.67 10.11  6.18  8.43  2.81  .56  .00  .00  .00  .56  .56  2.25  .00  53.93 (2)  .11    .02  .03  .07  .22  .21  .13    .17    .06  .01  .00  .00  .00  .01  .01  .05  .00  1.10 8-12      2    1    0    0    0      2    4      17      8    0    0    0      2    2    2    5    0    45 (1)  1.12    .56  .00  .00  .00  1.12  2.25  9.55  4.49  .00  .00  .00  1.12  1.12 1.12  2.81  .00  25.28 (2)  .02    .01  .00  .00  .00  .02  .05    .20    .09  .00  .00  .00  .02  .02  . 02  .06  .00    .52 13-18      0    0    0    0    0      0    0      2      2    0    0    0      0    0    0    5    0      9 (1)  .00    .00  .00  .00  .00  .00  .00  1.12  1.12  .00  .00  .00  .00  .00  .00  2.81  .00  5.06 (2)  .00    .00  .00  .00  .00  .00  .00    . 02    .02  .00  .00  .00  .00  .00  .00  .06  .00    .10 19-24      0    0    0    0    0      0    0      0      0    0    0    0      0    0    1    0    0      1 (1)  .00  .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .56  .00  .00    .56 (2)  .00  .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .01  .00  .00    .01 GT 24      0    0    0    0    0      0    0      0      0    0    0    0      0    0    0    0    0      0 (1)  .00  .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .00  .00  .00    .00 (2)  .00  .00  .00  .00  .00  .00  .00    .00    .00  .00  .00  .00  .00  .00  .00  .00  .00    .00 ALL SPEEDS      16    8    8    8    20    23  15      36    16    1    0    0      2    5    4  16    0    178 (1)  8.99  4.49  4.49  4.49 11.24 12.92  8.43 20.22    8.99  .56  .00  .00  1.12  2.81 2.25  8.99  .00 100.00 (2)  .18  .09  .09  .09  .23  .26  .17    .41    .18  .01  .00  .00  . 02  .06  .05  .18'  .00  2.05 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 29
TABLE5C VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS C              CLASS FREQUENCY (PERCENT) =    3.60 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE      E  ESE    SE    SSE      s  SSW    SW  WSW      w  WNW    NW  NNW  VRBL  TOTAL MPH CALM      0    1    0    0    0    5    0      0    0    0    0      0    0    0    0    0    0      6 (1)  .00    .32  .00  .00    .00 1. 60  .00    .00  .00  .00  .00    .00  .00  .00  .00  .00  .00  1. 92 (2)  .00    .01  .00  .00    .00  .06  .00    .00  .00  .00  .00    .00  .00  .00  .00  .00  .00    .07 C-3      6    5    5    5    4    13    7      4    2    0    0      0    0    1    2    0    0      54 (1)  1. 92 1. 60 1. 60 1. 60 1.28  4.15  2.24  1. 28  . 64  .00  .00    .00  .00  .32  . 64  .00  .oo  17.25 (2)  .07    .06  .06  .06    .05  .15  .08    .05  .02  .00  .00    .00  .00  .01  .02  .00  .00    . 62 4-7    13    9    4    10    13    18  25      29    7    2    1      0    0    1    9    18    0    159 (1)  4.15  2.88  1. 28 3.19  4.15  5.75  7.99  9.27  2.24  .64  .32 I  .00  .00  .32  2.88  5.75  .00  50.80 (2)  .15    .10  .05  .11    .15  .21  .29    .33  .08  .02  .01    .00  .00  .01  .10  .21  .00  1. 83 8-12      11    3    2    0    0    2    1      17    19    2    0      0    3    3    6    12    0      81 (1)  3.51    .96  . 64  .00    .00  . 64  .32  5.43  6.07  . 64  .00  -* 00  .96  .96  1. 92 3.83  .00  25.88 (2)  .13    .03  .02  .00    .00  .02  .01    .20  .22  .02  .00    .00  ."03  .03  .07  .14  .00    .93 13-18      1    0    0    0    0    0    0      1    1    0    0      0    1    0    3    6    0      13 (1)  .32    .00  .00  .00    .00  .00  .00    .32  .32  .00  .00    .00  .32  .00  .96  1. 92  .00  4.15 (2)  .01    .00  .00  .00    .00  .00  .00    .01  .01  .00  .00    .00  .01  .00  .03  .07  .00    .15 19-24      0    0    0    0    0    0    0      0    0    0    0      0    0    0    0    0    0      0 (1)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00  .00    .00  .00  .00  .00  .00  .00    .00 (2)  .00    .00  .oo  .00    .00  .00  .00    .00  .00  .00  .00    .00  .00  .*oo  .00  .00  .00    .00 GT 24      0    0    0    0    0    0    0      0    0    0    0      0    0    0    0    0    0      0 (1)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00  .00    .00  .00  .00  .00  .00  .00    .00 (2)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00  .00    .00  .00  .00  .00  .00  .00    .'oo ALL SPEEDS        31    18    11    15    17    38  33      51    29    4    1      0    4    5    20    36    0    313 (1)  9.90  5.75  3.51  4.79  5.43 12.14 10.54 16.29  9.27  1. 28  .32    .00  1. 28 1. 60 6.39 11.50  .00 100.00 (2)  .36    .21  .13  .17    .20  .44  .38    .59  .33  .05  .01    .00  .05  .06  .23  .41  .00  3.60
'(l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO . 95 MPH) 30
TABLE5D VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS D                CLASS FREQUENCY (PERCENT) =    46.37 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE      E  ESE    SE    SSE      s  SSW    SW  WSW      w  WNW    NW  NNW  VRBL  TOTAL MPH CALM      26    19    21    31    49    91    99      74    24    4      4    5    4      1    7    27    0    486 (1)  . 64  .47  .52  .77  1. 21  2.25  2.45    1. 83  .59  .10    .1.0  .12  .10    .02  .17  . 67  .00  12.04 (2)  .30    .22  .24  .36    .56  1. 05 1.14    .85    .28  .05  .05    .06  .05    .01  .08  .31  .00  5.58 C-3    74    41    42    31    55    73    73      94    73    41    22    26    34    47    63  107    0    896 (1)  1. 83 1. 02 1. 04  .77  1. 36  1. 81 1. 81  2.33  1. 81 1. 02  .55    . 64  .84  1.16  1. 56 2.65  .00  22.20 (2)  .85    .47  .48  .36    . 63  .84  .84    1. 08  .84  .47  .25    .30  .39    .54  . 72 1.23  .00  10.30 4-7  120    35    9    9    19    55  119    162    84    26    22    28    62    61  148  244    0  1203 (1)  2.97    .87  .22  .22    .47  1. 36 2.95    4.01  2.08  . 64  .55    . 69 1. 54  1. 51 3.67  6.05  .00  29.81 (2)  1. 38  .40  .10  .10    .22  . 63 1. 37  1. 86  .97  .30  .25    .32  . 71  .70  1. 70 2.80  .00  13.82 8-12    110    19    1    0      1    10    8      89    82    18    17    18  147    150  142  218    0  1030 (1)  2.73    .47  .02  .00    .02  .25  .20    2.21  2.03  .45  .42    .45  3. 64  3. 72 3.52  5.40  .00  25.52 (2)  1.26    .22  .01  .00    .01  .11  .09    1. 02  .94  .21  .20    .21  1. 69  1. 72 1. 63 2.50  .00  11. 84 13-18      21    0    0    0      0    1    0      8    16    2      0    4    67    80    77    96    0    372 (1)  .52    .00  .00  .00    .00  . 02  .00    .20    .40  .05  .00    .10  1. 66  1. 98 1. 91 2.38  .00  9.22 (2)  .24    .00  .00  .00    .00  .01  .00    .09    .18  .02  .00    .05  .77    . 92  .88  1.10  .00  4.27 19-24      0    0    0    0      0    0    0      0    0    0      0    0    4    10    16    17    0      47 (1)  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00  .00    .00  .10    .25  .40  .42  .00  1.16 (2)  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00  .00    .00  .05    .11  .18  .20  .00    .54 GT 24      0    0    0    0      0    0    0      0    0    0      0    0    0      0    2    0    0      2 (1)  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00  .00    .00  .00    .00  .05  .00  .00    .05 (2)  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00  .00    .00  .00    .00  .02  .00  .00    .02 ALL SPEEDS    351  114    73    71  124    230  299    427  279    91    65    81  318    349  455  709    0  4036 (1)  8.70  2.82  1. 81 1. 76 3.07  5.70  7.41 10.58    6.91  2.25  1. 61  2.01  7.88  8.65 11.27 17.57  .00 100.00 (2)  4.03  1. 31  .84  .82  1. 42  2. 64 3.44 4.91    3.21  1. 05  .75    .93  3. 65  4.01 5.23 8.15    .00  46.37 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 31
TABLE SE VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA            STABILITY CLASS E              CLASS FREQUENCY (PERCENT) =    28.16 WIND DIRECTION FROM
(
SPEED      N  NNE    NE  ENE      E  ESE    SE    SSE      s  SSW    SW  WSW      w    WNW    NW  NNW  VRBL    TOTAL MPH CALM      30  - 18    12    12    10  21    64      74    41    32    30    13    11      16  17    25      0    426 (1) 1. 22  .73  .49    .49    .41  .86 2.61    3.02  1. 67  1. 31 1.22  .53  .45    . 65  .69  1. 02    .00  17.38 (2)  .34    .21  .14    .14    .11  .24  .74    .85    .47  .37  .34  .15  .13    .18  .20  .29      .00  4.89 C-3    30    25    12    14    21  31    44      77    79  110  170  145  135      92  104    60      0  1149 (1) 1.22  1. 02  .49    .57    .86  1.26 1. 80  3.14  3.22  4.49  6.94  5.92  5.51    3.75  4.24  2.45      .00  46.88 (2)  .34    .29  .14    .16    .24  .36  .51    .88    .91 1. 26 1. 95 1. 67 1. 55  1. 06 1.19  .69      .00  13.20 4-7    40      8      1    0      3    8    34      53    28    5    14    43    80      59  84  133        0    593 (1) 1. 63  .33  .04    .00    .12  .33 1. 39  2.16  1.14    .20  .57  1. 75 3.26    2.41  3.43  5.43      .00  24.19
        ,(2)  . 46  .09  .01    .00    .03  .09  .39    . 61    .32  .06  .16  .49  .92    .68  .97  1. 53    .00  6.81 8-12      14      1      0    0      0    0    1      16    21    2    1    3    4*6    36  20    52      0    213 (1)  .57    .04  .00    .00  ,oo    .00  .04    . 65    .86  .08  .04  .12  1. 88  1. 47  .82  2.12      .00  8.69 (2)  .16    .01  .00    .00  .* 00  .00  .01    .18    .24  .02  .01  .03  .53    .41  .23  .60      .00  2.45 13-18      4      0    '-o    0      0    0    0      1      1    0    1    0      9    24    4    21      0    65 (1)  .16    .oo  .oo    .00    .00  .00  .00    . 04    .04  .00  .04  .oo  .37    .98  .16  .86      .00  2.65 (2)  .05    .00  .00    .00    .00  .00  .00    .01    .01  .00  .01  .00  .10    .28  .05  .24      .00    .75 19-24      0      0      0    0      0    0    0      0      0    0    0    0      2      0    0      3      0      5 (1)  .00    .00  .00    .00    .00  .00  .00    .00    .00  .00  .00  .00  .08    .00  .00  .12      .00    .20 (2)  .00    .00  .00    .00    .00  .00  .00    .00    .00  .00  .00  .00  .02    .00  .00  .03      .00    .06 GT 24      0      0      0    0      0    0    0      0      0    0    0    0      0      0    0      0      0      0 (1)  .00    .00  .00    .00    .00  .00  .00    .00    .00  .00  .00  .00  .00    .00  .00  .00      .00    .00 (2)  .00    .00  .00    .00  .00    .00  .00    .00    .00  .00  .00  .00  .00    .00  .00  :"'oo    .00    .00 ALL SPEEDS    118      52    25    26    34  60  143    221    170  149  216  204  283    227  229  294        0  2451 (1) 4.81  2.12  1. 02  1. 06 1. 39  2.45 5.83    9.02  6.94  6.08  8.81  8.32 11.55    9. 26 9.34 12.00      .00 100.00 (2) 1. 36  . 60  .29    .30    .39  .69 1. 64  2.54  1. 95  1. 71 2.48  2.34 3.25    2.61  2.63 3.38      .00  28.16
                                                                  '
(l}=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2}=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 32
TABLE 5F VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS F              CLASS FREQUENCY (PERCENT)        14.03 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE      E  ESE    SE    SSE      s  SSW      SW  . WSW    w_  WNW    NW  NNW  VRBL  TOTAL MPH CALM      5    7    5    5      6    12    16      17    28    49    31    26    10      11    13    22    0    263 (1)  .41    .57  .41  .41    .49  .98  1. 31  1. 39 2.29  4.01  2.54    2.13  .82    .90  1. 06 1. 80  .00  21. 54 (2)  .06    .08  .06  .06    .07  .14  .18    .20  .32  .56    .36    .30  .11    .13  .15  .25  .00  3.02 C-3    16    5    5    2      6    8    15      27    53    84  195    173  116      76    40    20    0    841 (1)  1. 31  .41  .41  .16    .49  .66  1. 23  2.21  4.34  6.88 15.97 14.17    9.50    6.22  3.28  1. 64  .00  68.88 (2)  .18    .06  .06  .02    .07  .09  .17    .31  . 61  . 97 2.24 1. 99    1.33    .87  .46  .23  .00  9.66 4-7      4    0    0    0      0    1    3      5    3    12    11    12    14      17    15    17    0    114 (1)  .33    .00  .00  .00    .00  .08  .25    .41  .25  .98    .90    .98 1.15    1. 39 1. 23 1. 39  .00  9.34 (2)  .05    .00  .00  .00    .00  .01  .03    .06  .03  .14    .13    .14  .16    .20  .17  .20  .00  1. 31 8-12      0    0    0    0      0    0    0      0    0    0      0      0    0      0    1    2    0      3 (1)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .08  .16  .00    .25 (2)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .01  .02  .00    .03 13-18      0    0    0    0      0    0    0      0    0    0      0      0    0      0    0    0    0      0 (1)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 (2)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 19-24      0    0    0    0      0    0    0      0    0    0      0      0    0      0    0    0    0      0 (1)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 (2)  .00    .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 GT 24      0    0    0    0      0    0    0      0    0    0      0      0    0      0    0    0    0      0 (1)    .00  .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 (2)    .00  .00  .00  .00    .00  .00  .00    .00  .00  .00    .00    .00  .00    .00  .00  .00  .00    .00 ALL SPEEDS      25    12    10    7    12    21    34      49    84  145    237    211  140    104    69    61    0  1221 (1)  2.05    .98  .82  .57    .98 1. 72 2.78    4.01  6.88 11. 88 19. 41 17.28 11. 47  8.52  5.65  5.00  .00 100.00 (2)  .29    .14  .11  .08    .14  .24  .39    .56  .97 1. 67 2. 72 2.42 1. 61      1.19  .79  .70  .00  14.03 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 33
TABLE5G VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS G              CLASS FREQUENCY (PERCENT)    4. 64 WIND DIRECTION FROM SPEED      N  NNE    NE  ENE      E  ESE    SE    SSE    s  SSW    SW  WSW      w  WNW    NW  NNW  VRBL  TOTAL MPH CALM      6    10    4    1      5    9    10    10    22    19    7    7    4    7    6      5    0    132 (1)  1. 49 2.48  .99  .25  1.24  2.23  2.48    2.48  5.45  4.70  1. 73 1. 73  .99 1. 73 1. 49 1.24    .00  32.67 (2)  .07  .11  .05  .01    .06  .10  .11    .11  .25  .22  .08  .08    .05  .08  .07  .06    .00  1. 52 C-3      5    2    4    2      7    7    5    13    12    29    32    44    30    24    13      8    0    237 (1)  1. 24  .so    .99  .50  1. 73 1. 73 1. 24  3.22  2.97  7.18  7.92 10.89  7.43  5.94  3.22  1. 98  .00  58.66 (2)  .06  .02    .05  .02    .08  .08  .06    .15  .14  .33  .37  .51    .34  .28  .15  .09    .00  2. 72 4-7      1    0    0    0      0    1    0      1    1      5    4    1    8    3    5    5    0      35 (1)  .25  .00  .00  .00  .00  .25  .oo    .25  .25  1.24  .99  .25  1. 98  .74  1.24  1.24    .00  8.66 (2)  .01  .00  .00  .00  .00  .01  .00    .01  .01  .06  .05  .01    .09  .03  .06  .06    .00    .40 8-12      0    0    0    0      0    0    0      0    0      0    0    0    0    0    0      0    0      0 (1)  .00  .00  .00  .00    .00  .00  .oo    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 (2)  .00  .00  .00  .00    .00  .00  .oo    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 13-18      0    0    0    0      0    0    0      0    0      0    0    0    0    0    0      0    0      0 (1)  .oo  .00  .00  .00    .00  .00  .oo    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 (2)  .00  .00  .00  .00    .00  .00  .oo    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 19-24      0    0    0    0      0    0    0      0      0    0    0    0    0    0    0      0    0      0 (1)  .00  .00  .00  .00  .00  .00  .00    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    . 00 (2)  .00  .00  .00  .00  .00  .00  .00    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 GT 24      0    0    0    0      0    0    0      0    0      0    0    0    0    0    0    .0    0      0 (1)  .00  .00  .00  .00    .00  .00  .oo    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 (2)  .00  .00  .00  .00    .00  .00  .00    .00  .00  .00  .00  .00    .00  .00  .00  .00    .00    .00 ALL SPEEDS      12    12    8    3    12    17    15    24    35    53    43    52    42    34    24    18    0    404 (1)  2.97  2.97  1. 98  .74  2.97  4.21  3. 71  5.94  8.66 13.12 10.64 12.87 10.40  8.42  5.94  4.46    .00 100.00 (2)  .14  .14  .09  .03    .14  .20  .17    .28  .40  . 61  .49  .60    .48  .39  .28  .21    .00  4.64
(!)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 34
TABLE SH VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA          STABILITY CLASS ALL            CLASS FREQUENCY (PERCENT) = 100.00 WIND DIRECTION FROM SPEED      N  NNE      NE  ENE      E  ESE    SE    SSE      s  SSW    SW  WSW      w  WNW    NW    NNW  VRBL  TOTAL MPH CALM      71    55    42    49    70  138    189    175  115  104    72    51    29    35    43        79    0  1317 (1)    .82  . 63  .48  .56    .80 1.59  2.17    2.01  1.32  1.19  .83  .59    .33  .40  .49      .91  .00  15.13 (2)    .82  . 63  .48  .56    .80 1. 59 2.17    2.01  1. 32 1.19  .83  .59    .33  .40  .49  __,.-* 91  .00  15.13 C-3  137      83    74    57  100  138    146    217  220  264  419  388    315  242  222      201      0  3223 (1)  1. 57  .95  .85  . 65 1.15  1. 59 1. 68  2.49  2.53  3.03  4.81  4. 4 6 3. 62 2.78  2.55  2.31      .00  37.03 (2)  1. 57  .95  .85  . 65 1.15  1. 59 1. 68  2.49  2.53  3.03  4.81  4.46  3.62  2.78  2.55  2.31      .00  37.03 4-7  189      55    17    30    72  115    195    268  129    51    54    84  165  142  264      424      0  2254 (1)  2.17    .63  .20  .34    .83 1.32  2.24    3.08  1. 48  .59  . 62  . 97  1. 90 1. 63 3.03  4.87      .00  25.90 (2)  2.17    . 63  .20  .34    .83 1. 32 2.24    3.08  1. 48  .59  . 62  . 97  1. 90 1. 63 3.03  4.87      .00  25.90
                            -
8-12    137      25    3    0    1    22    19    142  131    22    18    22  198  191  171      292      0  1394 (1)  1. 57  .29  .03  .00    .01  .25    .22  1. 63 1. 51  .25  .21  .25  2.28  2.19  1. 96  3.36      .00  16.02 (2)  1. 57  .29  .03  .00    .01  .25    .22  1. 63 1. 51  .25  .21  .25  2.28  2.19  1. 96 3.36      .00  16.02 13-18      26      0    0    0    0    1    0      12    20    2      1      4    77  105    84    128      0    460 (1)  .30    .00  .00  .00    .00  .01    .00    .14    .23  .02  .01  .05    .88  1.21  .97  1. 47      .00  5.29 (2)    .30  .00  .00  .00    .00  .01    .00    .14    .23  .02  .01  .05    .88  1.21  .97  1. 47      .00  5.29 19-24      0      0    0    0    0    0    0      0    0    0      0      0    6    10    17        20    0      53 (1)  .00    .00  .00  .00    .00  .00    .00    .00  .oo  .00  .oo  .00    .07  .11  .20      .23  .00    . 61 (2)  .00    .00  .00  .00    .00  .00    .00    .00  .oo  .00  .00  .00    .07  .11  .20      .23  .00    . 61 GT 24      0      0    0    0    0    0    0      0    0    0      0      0    0    0    2        0    0      2 (1)    .00  .00  .00  .00    .00  .00    .00    .00    .oo  .00  .00  .00    .00  .00  .02      .00  .00    .02 (2)    .00  .00  .00  .00    .00  .00    .00    .00    .oo  .00  .00  .00    .00  .00  .02      .00  .00    .02 ALL SPEEDS    560  218    136  136  243  414    549    814  615  443  564  549    790  725  803 1144          0  8703 (1)  6.43  2.50  1. 56 1. 56 2.79  4. 76 6.31    9.35  7.07  5.09  6.48,6.31    9.08  8.33  9.23 13.14      .00 100.00 (2)  6.43  2.50  1. 56 1.56  2.79  4.76  6.31    9.35  7.07  5.09  6.48 '6. 31  9.08  8.33  9.23 13.14      .00 100.00 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 35


Health Physics Journal, Volume 39 (August), 1980; Pages 318-320, Pergammon Press). , 26 Variable Name (Units) Mixing Ratio Transit Time (hrs)* Water Uptake** (animal) (L/day) Feed Uptake**
TABLE6A VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA          STABILITY CLASS A              CLASS FREQUENCY (PERCENT) =    .32 WIND DIRECTION
: a. Average gamma energy: Not Applicable
: a. Average gamma energy: Not Applicable
: b. Average beta energy: Not Applicable
: b. Average beta energy: Not Applicable
: 4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
: 4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
: a. Fission and Activation Gases Continuous stack monitors monitor the gross Noble Gas radioactivity released from the plant stack. Because release rates are normally below the detection limit of these monitors, periodic grab samples are taken and analyzed for the gaseous isotopes present. These are used to calculate the individual isotopic releases indicated in Table lB and the totals of Table lA. The error involved in these steps may be approximately  
: a. Fission and Activation Gases Continuous stack monitors monitor the gross Noble Gas radioactivity released from the plant stack. Because release rates are normally below the detection limit of these monitors, periodic grab samples are taken and analyzed for the gaseous isotopes present. These are used to calculate the individual isotopic releases indicated in Table lB and the totals of Table lA. The error involved in these steps may be approximately +/-23 percent.
+/-23 percent. b. Iodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge.
: b. Iodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. The filters and cartridges are normally removed weekly and are analyzed for Iodine-131, 132, 133, 134, and 135. The error involved in these steps may be approximately +/-18 percent.
The filters and cartridges are normally removed weekly and are analyzed for Iodine-131, 132, 133, 134, and 135. The error involved in these steps may be approximately  
A-2
+/-18 percent. A-2
: c. Particulates The particulate filters described in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximately +/-18 percent.
: c. Particulates The particulate filters described in b. above are also counted for particulate radioactivity.
: d. Tritium ODCM Table 4.3 .1 requires as a minimum that grab samples from the plant stack be taken monthly and analyzed for tritium. The stack tritium collection has been upgraded with silica gel columns and continuous sampling of stack effluents. The error involved in this sample is approximately +/-18 percent.
The error involved in this sample is also approximately  
: e.   \\Taste ()il Prior to issuing the permit to burn a drum of radioactively contaminated waste oil, one liter of the oil is analyzed by gamma spectroscopy to determine concentrations of radionuclides that meet or exceed the LLD for all of the liquid phase radionuclides listed in ODCM Table 4.2.1.
+/-18 percent. d. Tritium ODCM Table 4.3 .1 requires as a minimum that grab samples from the plant stack be taken monthly and analyzed for tritium. The stack tritium collection has been upgraded with silica gel columns and continuous sampling of stack effluents.
Monthly, samples from drums that were issued burn permits are sent to the contracted laboratory for compositing and analysis. The lab analyzes for tritium, alpha, Fe-55, Sr-89, and Sr-90 on the composite sample.
The error involved in this sample is approximately  
The error involved in this sample is approximately +/-15 percent.
+/-18 percent. e. \\Taste ()il Prior to issuing the permit to burn a drum of radioactively contaminated waste oil, one liter of the oil is analyzed by gamma spectroscopy to determine concentrations of radionuclides that meet or exceed the LLD for all of the liquid phase radionuclides listed in ODCM Table 4.2.1. Monthly, samples from drums that were issued burn permits are sent to the contracted laboratory for compositing and analysis.
: f. Liquid Effluents If radioactive liquid effluents are to be released from the facility, they are continuously monitored. Measurements are also required on a representative sample of each batch ofradioactive liquid effluents released. For each batch, station records are retained of the total activity (mCi) released, concentration
The lab analyzes for tritium, alpha, Fe-55, Sr-89, and Sr-90 on the composite sample. The error involved in this sample is approximately  
(&#xb5;Ci/ml) of gross radioactivity, volume (liters), and approximate total.quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River.
+/-15 percent. f. Liquid Effluents If radioactive liquid effluents are to be released from the facility, they are continuously monitored.
Each batch of radioactive liquid effluents to be released is analyzed for gross gamma and gammaisotopic radioactivity. A monthly proportional composite sample, comprising an aliquot of each batch released during a month, is analyzed for tritium and gross alpha radioactivity. A quarterly proportional
Measurements are also required on a representative sample of each batch ofradioactive liquid effluents released.
* composite sample, comprising an aliquot of each batch released during a quarter, is analyzed for Sr-89, Sr-90, and Fe-55.
For each batch, station records are retained of the total activity (mCi) released, concentration
A-3
(&#xb5;Ci/ml) of gross radioactivity, volume (liters), and approximate total.quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River. Each batch of radioactive liquid effluents to be released is analyzed for gross gamma and gammaisotopic radioactivity.
: 5. BATCH RELEASES
A monthly proportional composite sample, comprising an aliquot of each batch released during a month, is analyzed for tritium and gross alpha radioactivity.
: a. Liquid There were no*routine liquid batch releases during the reporting period.
A quarterly proportional
: b. Gaseous There were no routine gaseous batch releases during the reporting period.
* composite sample, comprising an aliquot of each batch released during a quarter, is analyzed for Sr-89, Sr-90, and Fe-55. A-3
: 6. ABNORMAL RELEASES
: 5. BATCH RELEASES a. Liquid There were no*routine liquid batch releases during the reporting period. b. Gaseous There were no routine gaseous batch releases during the reporting period. 6. ABNORMAL RELEASES a. Liguid b. 1) In 2015 there was a continuous release due to the residual radioactivity in groundwater from a previously undetected leak from a subsurface structure.
: a. Liguid
The leak condition was identified through monitoring well data in January 2010. The leak was stopped in February 2010 .. 2) For 2015, the total Tritium radioactivity conservatively estimated to be released to the Connecticut River is 0.0334 Curies. No other plant-related radionuclides were detected in ground water. Gaseous There were no non-routine gaseous releases (measured) during the reporting period. A-4 _,
: 1) In 2015 there was a continuous release due to the residual radioactivity in groundwater from a previously undetected leak from a subsurface structure.
Requirement Response:
The leak condition was identified through monitoring well data in January 2010. The leak was stopped in February 2010 ..
APPENDIXB LIQUID HOLDUP TANKS Technical Specification
: 2) For 2015, the total Tritium radioactivity conservatively estimated to be released to the Connecticut River is 0.0334 Curies. No other plant-related radionuclides were detected in ground water.
: 3. l .A.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.1.A.l, a description of the events leading to this condition is required in the next annual Radioactive Effluent Release Report per ODCM Section 10.1. The limits of Technical Specification 3.1.A.1 were not exceeded during this reporting period. (Note that during 2015 the section numbering of the Technical Specifications changed due to the implementation of an approved License Amendment following permanent shutdown and defueling of the plant, but there were no changes made to the limits in Technical Specification 3.1.A.1 from those previously contained in Technical Specification 3.8.D.l) B-1 APPENDIXC RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Requirement:
: b. Gaseous There were no non-routine gaseous releases (measured) during the reporting period.
Response:
_,
Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.1. If an inoperable radioactive liquid effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3 .1.1, an explanation in the rtext annual Radioactive Effluent Release Report of the reason(s) for delay in correcting the inoperability are required per ODCM Section 10.1. Since the requirements of ODCM Table 3.1.1 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period, no response is required.
A-4
j C-1 APPENDIXD RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Requirement:
 
Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.2. If inoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.1.2, an explanation in the next annual Radioactive Effluent Release Report of the reason(s) for the delay in correcting the inoperability is required per ODCM Section lO.l. Response:
APPENDIXB LIQUID HOLDUP TANKS Requirement Technical Specification 3. l .A.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.1.A.l, a description of the events leading to this condition is required in the next annual Radioactive Effluent Release Report per ODCM Section 10.1.
Since the requirements of ODCM Table 3.1.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no response is required.
Response:  The limits of Technical Specification 3.1.A.1 were not exceeded during this reporting period. (Note that during 2015 the section numbering of the Technical Specifications changed due to the implementation of an NRC-approved License Amendment following permanent shutdown and defueling of the plant, but there were no changes made to the limits in Technical Specification 3.1.A.1 from those previously contained in Technical Specification 3.8.D.l)
D-1 APPENDIXE . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirement:
B-1
The radiological environmental monitoring program is conducted in accordance with ODCM Control 3/4.5.1. With milk samples no longer available from one or more of the sample locations required by ODCM Table 3.5.1, ODCM 10.1 requires the following to be included in the next annual Radioactive Effluent Release Report: (1) identify the cause(s) of the sample(s) no longer being available, (2) identify the new location(s) for obtaining available replacement samples and (3) include revised ODCM figure(s) and table(s) reflecting the new location(s).
 
Response:
APPENDIXC RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.1. If an inoperable radioactive liquid effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3 .1.1, an explanation in the rtext annual Radioactive Effluent Release Report of the reason(s) for delay in correcting the inoperability are required per ODCM Section 10.1.
Milk and silage collection at the Vern-Mont Farm (TM-20) was discontinued in August 2015 due to the permanently shut down and defueled status of the plant. It is noted that this was not a required sampling station in the ODCM. F-1 APPENDIXF LAND USE CENSUS Requirement:
Response:    Since the requirements of ODCM Table 3.1.1 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period, no response is required.                 j C-1
A land use census is conducted in accordance with ODCM Control 3/4.5.2. With a land use census identifying a location(s) that yields at least a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3.3, the new location(s) must be identified in the next Annual Radioactive Effluent Release Report Response:
 
The Land-Use Census was completed during the third quarter of2015. No locations were identified which yielded a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3 .3. See Table 4C for a listing of nearest residents and milk animals in the site area as determined in the 2015 Land Use Census. F-2 APPENDIXG PROCESS CONTROL PROGRAM Requirement:
APPENDIXD RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.2. If inoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.1.2, an explanation in the next annual Radioactive Effluent Release Report of the reason(s) for the delay in correcting the inoperability is required per ODCM Section lO.l.
ODCM Section 10.1 requires that licensee initiated changes to the Process Control Program (PCP) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made. Response:
Response:   Since the requirements of ODCM Table 3.1.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no response is required.
There were no changes made to the Process Control Program during this reporting period. G-1
D-1
\ APPENDIXH OFF-SITE DOSE CALCULATION MANUAL Requirement:
 
Technical Specification 6.7.B.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made effective.
APPENDIXE
Response:
            . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirement:   The radiological environmental monitoring program is conducted in accordance with ODCM Control 3/4.5.1. With milk samples no longer available from one or more of the sample locations required by ODCM Table 3.5.1, ODCM 10.1 requires the following to be included in the next annual Radioactive Effluent Release Report: (1) identify the cause(s) of the sample(s) no longer being available, (2) identify the new location(s) for obtaining available replacement samples and (3) include revised ODCM figure(s) and table(s) reflecting the new location(s).
No revisions were made to the ODCM during the reporting period. H-1 APPENDIX I RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Requirement:
Response:       Milk and silage collection at the Vern-Mont Farm (TM-20) was discontinued in August 2015 due to the permanently shut down and defueled status of the plant. It is noted that this was not a required sampling station in the ODCM.
ODCM Section 10.4 requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.
F-1
Response:
 
There were no licensee-initiated major changes to i:he radioactive waste systems during this reporting period. I-1 APPENDIXJ DISPOSAL OF SEPTIC/SILT/SOIL WASTE Requirement:
APPENDIXF LAND USE CENSUS Requirement: A land use census is conducted in accordance with ODCM Control 3/4.5.2.
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.
With a land use census identifying a location(s) that yields at least a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3.3, the new location(s) must be identified in the next Annual Radioactive Effluent Release Report Response:   The Land-Use Census was completed during the third quarter of2015. No locations were identified which yielded a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3 .3. See Table 4C for a listing of nearest residents and milk animals in the site area as determined in the 2015 Land Use Census.
year and from previous years be reported to the Nuclear Regulatory Commission in the Annual Radioactive Effluent Release Report if disposals occur during the reporting year. Entergy Nuclear Vermont Yankee will report in the Annual Radioactive Effluent Release Report a list of the radiomI;clides present and the total radioactivity associated with the disposal activities oh the Vermont Yankee site. Response:
F-2
There was one on-site disposal spreading of 11,000 gallons of septic waste during October of 2015, and no spreading activities for cooling tower silt or sand/soil type materials.
 
The total radioactivity spread on the 1.9 acres (southern) on-site disposal field from this and previous years was as follows: Activity Spread in 2015 Activity from All Past and Current Disposals Decayed to 10/20/2015 Radionuclide (Ci) (Ci) Mn-54 8.00E-11 1.17E-08 Co-60 2.43E-09 9.67E-06 Zn-65 2.68E-10 3.67E-09 Cs-134 O.OOE+OO 6.68E-10 . Cs-137 l.lOE-10 7.50E-05 The maximum organ dose from all past and current spreading operations totaled l.09E-01 mrem/year.
APPENDIXG PROCESS CONTROL PROGRAM Requirement: ODCM Section 10.1 requires that licensee initiated changes to the Process Control Program (PCP) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made.
This calculated value is within the 1 mrem/year limit applied during the period of operational control of the site. The projected hypothetical "intruder" dose for the period following the loss of operational control of the site area, due to all spreading operations to-date, is 2.08E-01 mrem/year versus a 5 mrem/year dose limit. The "intruder dose" period begins on the date that the plant operating license expires, March 21, 2032. J-1}}
Response:   There were no changes made to the Process Control Program during this reporting period.
G-1
 
APPENDIXH OFF-SITE DOSE CALCULATION MANUAL Requirement: Technical Specification 6.7.B.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made effective.
Response:   No revisions were made to the ODCM during the reporting period.
\
H-1
 
APPENDIX I RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Requirement: ODCM Section 10.4 requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.
Response:   There were no licensee-initiated major changes to i:he radioactive waste systems during this reporting period.
I-1
 
APPENDIXJ ON~SITE    DISPOSAL OF SEPTIC/SILT/SOIL WASTE Requirement:   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 Release Report if disposals occur during the reporting year. Entergy Nuclear Vermont Yankee will report in the Annual Radioactive Effluent Release Report a list of the radiomI;clides present and the total radioactivity associated with the disposal activities oh the Vermont Yankee site.
Response:     There was one on-site disposal spreading of 11,000 gallons of septic waste during October of 2015, and no spreading activities for cooling tower silt or sand/soil type materials. The total radioactivity spread on the 1.9 acres (southern) on-site disposal field from this and previous years was as follows:
Activity from All Past and Current Activity Spread in 2015      Disposals Decayed to 10/20/2015 Radionuclide                 (Ci)                             (Ci)
Mn-54                 8.00E-11                         1.17E-08 Co-60                 2.43E-09                         9.67E-06 Zn-65                 2.68E-10                         3.67E-09 Cs-134               O.OOE+OO                           6.68E-10
              . Cs-137                 l.lOE-10                         7.50E-05 The maximum organ dose from all past and current spreading operations totaled l.09E-01 mrem/year. This calculated value is within the 1 mrem/year limit applied during the period of operational control of the site. The projected hypothetical "intruder" dose for the period following the loss of operational control of the site area, due to all spreading operations to-date, is 2.08E-01 mrem/year versus a 5 mrem/year dose limit. The "intruder dose" period begins on the date that the plant operating license expires, March 21, 2032.
J-1}}

Revision as of 19:54, 30 October 2019

Transmittal of 2015 Radioactive Effluent Release Report
ML16138A549
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 05/12/2016
From: Chappell C
Entergy Nuclear Vermont Yankee
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 16-020
Download: ML16138A549 (61)


Text

Entergy Nuclear Vermont Yankee, LLC

'/ Vermont Yankee

~Entergy 320 Governor Hunt Rd.

Vernon, VT 05354 (802) 257-7711 Coley C. Chappell Manager, Design and Programs BVY 16-020 May 12, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

SUBJECT:

2015 Radioactive Effluent Release Report Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28

Dear Sir or Madam,

In accordance with Vermont Yankee (VY) Technical Specifications (TS) 6.6.D, enclosed is a copy 'of the annual 2015 Radioactive Effluent Release Report.

In addition, VY TS 6.7.B requires reporting of changes to the Off-Site Dose Calculation Manual (ODCM). There were no changes made to the ODCM during 2015 as noted in Appendix H of the subject report.

There are no new regulatory commitments being made in this submittal.

Should you have any questions or require additional information concerning this submittal, please contact me at (802) 451-3374.

Sincerely, t~Mw~

[CCC/TBS]

Enclosure:

Radioactive Effluent Release Report for 2015 cc listing (next page) cc: Mr. Daniel Dorman, Region 1 Administrator

BVY 16-020 I Page 2 of 2 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Mr. Jack D. Parrott, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop T-8F5 11555 Rockville Pike

.Rockville, MD 20852-2378 Mr. Christopher Recchia, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, VT 05620 Vermont Department of Health Division of Radiological Health Attn: Bill Irwin P.O. Box 70 Burlington, VT 05402-0070 Massachusetts Department of Public Health Jack Priest, Director Radiation Control Program 529 Main Street, Suite 1M2A Charlestown, MA 02129 Augustinus Ong, Administrator Department of Health and Human Services Radiological Health Section 29 Hazen Drive Concord, NH 03301-6504 \.*

John Giarrusso Nuclear Preparedness and Planning Manager 400 Worcester Road Framingham, MA 01702 Tony Honnellio Radiation Program Manager, Health and Safety Coordinator EPA, New England, Region 1 5 Post Office Square, Suite 100 (OSRR02-2).

Boston, Massachusetts 02109

RADIOACTIVE EFFLUENT RELEASE REPORT FOR2015 INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN Entergy Nuclear Vermont Yankee, LLC Docket No. 50-271 License No. DPR-28 Prepared by:_,.,,,,..,Y'--"""--L,,.-~~~"""'-""'~=_,,___ _ _ _ ____;/ 6 Is'/ I to

, Clvisol)* Scientist, AREVA, Inc. Date

--b~~~-'--~~~1~1$/td& Date Revie-ived by:_~----.......,....,~--+-+--------*ut:f0 Approved for Distribution:_-1!--L-=:::i~~r==::::::::__ _ _ _ _ _ ___!/ ~kb(?

Date

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TABLE OF CONTENTS

1.0 INTRODUCTION

.............................................................................................................................................. 1 2.0 METEOROLOGICAL DATA ............................................................................................................................ 2 3.0 DOSE ASSESSMENT .................................................................................. :.................................................... 3 3.1 DOSES FROM LIQUID EFFLUENTS ............................... : ................................................................................... 3 3.2 DOSES FROM NOBLE GASES ........................................................................................................................... 4 3 .3 DOSES FROM IODINE-131, IODINE-133, TRITIUM, CARBON-14, AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS .................................................................................. 4 3.4 WHOLE BODY DOSES IN UNRESTRICTED AREAS FROM DIRECT RADIATION ................................................. 5 3 .5 DOSES FROM ON-SITE DISPOSAL OF SEPTIC WASTE, COOLING TOWER SILT AND SOIL ............................... 6 3.6 ON-SITE RECREATIONAL ACTIVITIES ............................................................................................................. 6 REFERENCES .......................................................................................................................................................... 7 APPENDIX A -SUPPLEMENTAL INFORMATION ......................................................................................... A-1*

APPENDIX B -LIQUID HOLDUP TANKS ........................................................................................................ B-1 APPENDIX C -RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ............................................................................................................... C-1 APPENDIX D -RADIOACTIVE GASEOUS EFFLUENT MONITORING '

INSTRUMENTATION ................................................................................................................ D-1 APPENDIX E-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..................................... E-1 APPENDIX F - LAND USE CENSUS .................................................................................................................. F-1 APPENDIX G -PROCESS CONTROL PROGRAM ............................................................................................ G-1 APPENDIX H -OFF-SITE DOSE CALCULATION MANUAL ......................................................................... H-1 APPENDIX I - RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS ............................................................................................................ I-1 APPENDIX J - ON-SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE ............................................................ J-1 11

LIST OF TABLES IA Gaseous Effluents - Summation of All Releases 8 IB Gaseous Effluents - Elevated Releases 10 IC Gaseous Effluents - Ground Level Releases I2 lD Gaseous Effluents - Non-routine Releases 14 2A Liquid Effluents - Summation of All Releases 15 2B Liquid Effluents - Routine Releases 17 3 Solid Waste and Irradiated Fuel Shipments 19 4A Maximum Quarterly and Annual Off-Site Doses from Direct Radiation and 21 Liquid and Gaseous Effluents for 2015 (10CFR50, Appendix I) 4B Maximum Annual Off-Site Doses from Direct Radiation and 22 and Liquid and Gaseous Effluents for 2015 (40CFR190) 4C Receptor Locations 23 4D Usage Factors for Environmental Pathways 24 4E Environmental Parameters for Gaseous 'Effluents 25 4F Environmental Parameters for Liquid Releases (Tritium) Via Groundwater 27 5A to 5H Annual (2015) Summary of Lower Level Joint Frequency Distribution 28-35 6A to 6H Annual (2015) Summary of Upper Level Joint Frequency Distribution 36-43 111

Radiological Effluent Release Report for 2015

[Including Annual Radiological Impact on Man]

Entergy Nuclear Vermont Yankee, LLC

1.0 INTRODUCTION

Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste shipments for the year, 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 the year 2015 in response to the ALARA objectives of 10 CFR Part 50, Appendix I. Also included in Table 4A is the estimate of direct dose from fixed station sources along the limiting west site boundary line. Tables SA through 6H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 2015. Radioactive effluents reported in Tables 1and2 were used to determine the dose to the maximum exposed individual for 2015.

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.l (Reference 1). These dose estimates were made using a "Method II" analysis as described in the ODCM, and as reported in Tables 4A and 4B ofthis report. A "Method II" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 2) and actual measured meteorological data recorded concurrently with the quarterly reporting period.

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 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," is also required to be included in this report ifthe 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 Part 190.

All calculated dose estimates for members of the public at the site boundary or beyond for the 2015 annual reporting period are below the dose criteria of 10 CFR Part 50, Appendix I, and 40 CFR Part 190.

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

1

2.0 METEOROLOGICAL DATA Meteorological data were collected in 2015 from the site's 300-foot meteorological tower located approximately 2,200 feet northwest of the reactor building, and about 1,400 feet from the plant stack. The 300-foot tower is approximately the same height as the primary plant stack (308 feet) and is designed to meet the requirements of Safety Guide 23 (Reference 3) for meteorological monitoring. In mid-2009, the tower was moved to a location approximately 200 feet northwest of the original location.

r.JQ and D/Q values for elevated releases were derived for all receptor points from the site meteorological record for each quarter using a straight-line airflow model. All dispersion factors have been calculated employing appropriate source configuration considerations, as described in Regulatory Guide 1.111 (Reference 4). A source depletion model as described in "Meteorology and Atomic Energy - 1968" (Reference 5) was used to generate deposition factors, assuming a constant deposition velocity of 0. 01 m/sec for all stack (elevated) releases. Changes in terrain elevations in the site environment were also factored into the meteorological models as appropriate.

In the event of a ground-level release, r.JQ and D/Q values would be derived for the site boundary receptor points from the site meteorological record for each quarter using a straight-line airflow model.

During this reporting period, there were no ground-level releases and therefore no associated dose impact.

Table 4C lists the distanc.es from the plant stack to the nearest site boundary, resident, and milk animal in each of the 16 principle compass directions as determined during the 2015 land use census. These locations were used in the calculation of atmospheric dispersion factors. The meteorological model was also executed for each calendar quarter to determine the location of the predicted maximum ground level air concentration from elevated releases from the plant's primary vent stack. These locations were included in the assessment of effluent doses along with identified points of interest from the annual land use census. "

2

3.0 DOSE ASSESSMENT 3.1 Doses From Liguid 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 Part 50, Appendix I. By implementing the requirements of 10 CFR Part 50, Appendix I, ODCM 3/4.2.2 assures that the release ofradioactive material in liquid effluents will be kept "as low as is*

reasonably achievable." . *', *

  • There were no recorded routine liquid radioactive waste discharges during the report period.

However, an abnormal release to the Connecticut River is postulated due to a past leak in an underground pipe tunnel that runs between the Advanced Offgas (AOG) system building and other plant buildings which allowed accumulated piping system leakage to enter the subsurface groundwater adjacent to the plant structures. The existence of the leak was first recognized in January 2010, when a river shoreline Protected Area Boundary monitoring well sample was reported to have detectable tritium. The addition of other monitoring wells and subsequent analysis defined the extent of the affected groundwater plume moving toward the.river and helped locate the source of the leak, which was stopped in February 2010.

\

Estimates of tritium-contaminated ground water released from the site are based on Protected Area Boundary monitoring well data collected throughout 2015, and hydrological modeling of ground water movement in the affected zone impacted by the pipe tunnel leak. 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 2015 was generated and reported in Table 2A.

Forthe projected ground water flow into the Connecticut River in 2015, the dose impact to the maximum exposed individual (MEI) assumed the following exposure pathways: (1) ingestion offish (taken from Vernon Pond), (2) ingestion of vegetables and, fresh leafy produce irrigated by water taken from the river below Vernon Dam, (3) ingestion of milk and meat from animals that were fed irrigated crops and drinking water taken from the river below Vernon Dam, and (4) pota~le water for a hypothetical individual drawing drinking water fed by the river below Vernon Dam. For Vernon Pond (river area adjacent to the plant property), the near shore mixing zone associated with the fish ingestion pathway is conservatively taken as 1% of the minimum recorded monthly river flow (3,107 cfs in September 2015) for dilution. All irrigation exposure pathways for the consumption of food products grown with irrigated water occur below Vernon Dam and assume the lowest 2015 quarterly average growing season river flow value (5394 cfs in the third quarter) for environmental mixing. For the drinking water pathway, river flow mixing is assumed to occur below Vernon Dam and uses the lowest annual quarterly average river flow (5394 cfs in the third quarter) as a conservative estimate ofriver dilution for all four quarters of the year. The dose models are

!aken from Regulatory Guide 1.109 (Reference 2) and use environmental parameters for exposure pathways listed in Tables 4D and 4F. .

The maximum estimated quarterly and annual whole body and organ doses to the limiting age group from liquid releases are reported in Table 4A. These estimated doses are well below the 10 CFR Part 50, Appendix I dose criteria of ODCM 3/4.2.2. Table 4B provides an estimate of the total annual'dose impact (including contribution from liquids) associated with the highest exposed member of the public for demonstration of compliance to the dose standard contained in 40 CFR P~rt 190 for the uranium fuel cycle.

\.

3

3.2 Doses From Noble Gases ODCM 3/4.3.2 limits the gamma air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I. By implementing these, ODCM 3/4.3.2 assures that the releases ofradioactive noble gases in gaseous effluents will be kept "as low as is reasonably achievable."

Dose estimates due to the release of noble gases to the atmosphere are typically calculated at the site boundary, at the nearest resident in each of the sixteen principal compass directions, at the point of highest off-site ground level air concentration of radioactive materials, and at each of the milk animal locations located within five miles of the plant. For 2015, there were no noble gases detected in effluents released from the plant stack.

3.3 Doses From Iodine-131, Iodine-133, Tritium, Carbon-14, and Radionuclides in Particulate Form with Half-Lives Greater Than 8 Days ODCM 3/4.3.3 limits the organ dose to a member of the public from Iodine-131, Iodine-133, Tritium, Carbon-14, and radionuclides in particulate form with half-lives greater than 8 days (hereafter called "iodines and particulates") 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 iodines and particulates in gaseous effluents will be kept "as low as is reasonably achievable."

During 2015, a single frac tank was used on the Vermont Yankee site to temporarily store (outdoors) tritium-contaminated water extracted from onsite groundwater wells. The quantity of tritium released to the atmosphere through the evaporation of water from this frac tank was estimated, and the dose consequence to the maximally exposed individual was calculated.

Exposure pathways that could exist as a result of the planned (routine) release of iodines and particulates to the atmosphere include external irradiation from activity deposited onto the ground surface, inhalation, and ingestion of vegetables, meat and milk. Dose estimates were made at the site boundary and nearest resident in each of the sixteen principal compass directions, as well as all milk animal locations within five miles of the plant. The nearest resident and milk animals in each sector were identified by the most recent annual land use census as required by ODCM 3/4.5.2 (see Table 4C). Conservatively, a vegetable garden was assumed to exist at each milk animal and nearest resident location. Furthermore, the meat pathway was assumed to exist at each milk cow location since this data category is not part of the annual land use census. Doses were also calculated at the point of maximum ground level air concentration of radioactive materials in gaseous effluents and included the assumption that the inhalation, vegetable garden, and ground plane exposure pathways exist for an individual with a 100 percent occupancy factor.

It is assumed that milk and meat animals are free to graze on open pasture during the second and third quarters with no supplemental feeding. This assumption is conservative since most of the milk animals inventoried in the site vicinity are fed stored feed throughout the entire year with only limited grazing allowed during the growing season. It has also been assumed that only 50 percent of the iodine deposited from gaseous effluent is in elemental form (I2) and is available for uptake (seep. 6, Reference 2).

4

During the non-growing season (first and fourth quarters), the milk animals are assumed to receive only stored feed. During the growing season (second and third quarters), all animal feed is assumed to be derived from fresh pasture. Usage factors for gaseous effluents are listed by age group and pathway in Table 4D.

Table 4E provides other dose model parameter assumptions used in the dose assessments.

In June 2009, the NRC issued Revision 2 of Regulatory Guide 1.21 (Reference 6) which introduced the term "principal radionuclide" in a risk-informed or dose context. A radionuclide can be considered a principal radionuclide if it contributes either (1) greater than 1 percent of the 10 CFR Part 50, Appendix I design objective dose for all radionuclides in the type of effluent being c01;1sidered, or (2) greater than 1 percent of the activity of all radionuclides in the type of effluent being considered. In addition to natural production in the environment, Carbon-14 is also produced in nuclear reactors as a function of power output, but at amounts muc11 less than those generated naturally or from past weapons testing. Since the --

time of the e&rlier publication of Regulatory Guide 1.21 (Revision 1) in 1974, commercial nuclear power 1

plants have decreased total radioactive effluents (other than Carbon-14) through improved fuel performance and waste management practices to the point today that Carbon-14 could be considered a principal radionuclide under today's definition. With the plant permanently shut down since December of2014, there was no plant related Carbon-14 production or associated dose impact for 2015.

3.4 Whole Body Doses in Unrestricted Areas From Direct Radiation As opposed to previous years where 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 2015 due to the plant being permanently shut down.

The other fixed sources of direct and scatter radiation to the site boundary are the Independent Spent Fuel Storage Installation (ISFSI), the low level radioactive materials stored in the North Warehouse, the Low Level Waste Storage Pad Facility (no radioactive_ waste material stored on the pad in 2015), and old turbine rotors and casings in the Turbine Storage Facility. The annual dose is based on dose rate measurements in these storage facilities and is projected to impact the same most restrictive site boundary dose location. ,J The estimated direct radiation dose from all major sources combined for the most limiting site boundary location is listed in Table 4A. These site boundary doses assume a 100 percent occupancy factor, and take no credit for the shielding effect of any residential structure.

Table 4B lists the combination of direct radiation doses 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 Part 190. For 2015, this annual dose was below the 25 mrem total body and organ limit, as well as the 75 mrem thyroid limit, of 40 CFR Part 190.

5

-

-::::.-..._. -:*' . - .. ~.

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/soil 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 mrern/year to the whole body and any organ. After the period associated with Vermont Yankee operational control, the dose to the inadvertent intruder is to be limited to 5 mrern/year. The projected dose from on-site disposals of septic waste, cooling tower silt, and sand/soil mixes is given in Appendix J of this report. ..

The dose limits applicable to the on-site spreading of materials were met for the single spreading of septic waste in 2015, based on the combined dose from this spreading and all past spreadings.

3 .6 On-Site Recreational Activities During 2015, no access to the on-site boat launching ramp located north of the intake structure was permitted for employees, their families, and guests. As such, there was no associated dose impact to members of the public.

6

REFERENCES

1. Off-site Dose Calculation Manual (ODCM), Revision 35, Entergy Nuclear Vermont Yankee, LLC, dated October 9, 2014.
2. Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 1.0 CFR Part 50, Appendix I," U.S.

Nuclear Rygulatory Commission, Office of Standards Development, Revision 1, October 1977.

3. Safety Guide 1.23, "Onsite Meteorological Programs," U.S. Atomic Energy Commission, February 17, 1972.
4. Regulatory Guide 1.~-11, "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.

7

TABLElA Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - Summation of All Releases Quarter Quarter Est. Total Unit 1 2 Error,%

A. Fission and Activation Gases

l. Total release Ci ND ND +/-2.30E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent ofODCM limit (1)  % ND ND NIA B. Iodines
l. Total Iodine Ci ND ND +/-l.80E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent of ODCM limit (3)  % (3) (3) NIA
c. Particulates
l. Particulates with T-112>8 days Ci ND ND +/-l.80E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent of ODCM limit (3)  % (3} (3) NIA
4. Gross alpha radioactivity Ci ND ND NIA D. Tritium (4)
l. Total release Ci 7.34E-02 7.09E-02 +/-l.80E+Ol
2. Average release rate for period µCi/sec 9.63E-03 9.22E-03 NIA
3. Percent ofODCM limit (3)  % (3) (3) NIA E. Carbon-14
l. Total release Ci ND ND NIA
2. Percent of ODCM limit (2)  % 4.99E-04 4.53E-04 NIA ND =Not Detected, or in the case of C-14, no power operations in 2015 leads to a zero estimate of C-14 production/release.

(1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results.

(2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form.

Percentage of ODCM limit calculated using Method I dose results. '

(3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E.

(4) Tritium released through evaporation from the onsite frac tank is included in these totals.

8

TABLE IA (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - Summation of All Releases Quarter Quarter Est. Total Unit 3 4 Error,%

A. Fission and Activation Gases

1. Total release Ci ND ND +/-2.30E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent ofODCM limit (1)  % ND ND NIA B. Iodines
1. Total Iodine Ci ND ND +/-1.80E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent of ODCM limit (3)  % (3) (3) NIA C. Particulates
1. Particulates with T-1/2>8 days Ci ND ND +/-1.80E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent of ODCM limit (3)  % (3) (3) NIA
4. Gross alpha radioactivity Ci ND ND NIA D. Tritium (4)
1. Total release Ci l.14E-01 7.87E-02 +/-1.80E+Ol
2. Average release rate for period µCi/sec 1.46E-02 2.78E-02 NIA
3. Percent ofODCM limit (3)  % (3) (3) NIA E. Carbon-14
1. Total release Ci ND ND NIA
2. Percent ofODCM limit (2)  % 7.29E-04 5.03E-04 NIA ND= Not Detected, or in the case ofC-14, no power operations in 2015 leads to a zero estimate ofC-14 production/release.

(1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results.

(2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form.

Percentage of ODCM limit calculated using Method I dose results. '

(3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E.

(4) Tritium released through evaporation from the onsite frac tank is included in these totals.

9

TABLEIB Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Elevated Releases Continuous Mode Batch Mode (1)

Quarter Quarter Nuclides Released Units 1 2 1 2

1. Fission Gases Argon-41 Ci ND ND Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-133m Ci ND ND Xenon-135 Ci ND ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Unidentified Ci ND ND Total for Period Ci ND ND (1) (1)
2. Iodines lodine-131 Ci ND ND lodine-133 Ci ND ND lodine-135 Ci ND ND Total for Period Ci ND ND (1) (1)
3. Particulates Strontium-89 Ci ND ND I

Strontium-90 Ci ND ND Cesium-134 Ci NP ND Cesium-137 Ci ND ND Barium-Lanthanum-140 Ci ND ND Manganese-54 Ci ND ND Chromium-51 Ci ND ND Cobalt-57 Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci ND ND Cerium-141 Ci ND ND Zinc-65 Ci ND ND Total for Period Ci ND ND (1) (1)

ND Not Detected at the plant stack (1) There were no batch mode gaseous releases for this reporting period.

10

TABLElB (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Elevated Releases Continuous Mode . Batch Mode (1)

Quarter Quarter Nuclides Released Units 3 4. 3 4

1. Fission Gases (

Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-133m Ci ND ND Xenon-135 Ci ND .ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Unidentified Ci ND ND Total for Period Ci ND ND (1) ' (1)

2. Iodines Iodine-131 Ci ND ND Iodine-133 Ci ND ND Iodine-135 Ci ND ND Total for Period Ci ND ND (1) (1)
3. Particulates Strontium-89 Ci ND ND Strontium-90 Ci ND ND Cesium-134 Ci ND ND Cesium-137 Ci ND ND Barium-Lanthanum-140 Ci ND ND Manganese-54 Ci ND ND Chromium Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci ND ND Cerium-141 Ci ND ND Cerium-144 Ci ND ND Zinc-65 Ci ND ND Total for Period Ci ND ND (1) (1)

ND Not Detected at the Plant Stack (1) There were no batch mode gaseous releases for this reporting period.

11

TABLElC Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents-(Routine) Ground Level Releases <2)

Continuous Mode Batch Mode Quarter Quarter Nuclides Released Units 1 (1) 2 (1) 1 (1) 2 (1)

1. Fission Gases Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci

.Krypton-88 Ci Xenon-133 Ci Xenon-1.35 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci

2. Iodines lodine-131 Ci Iodine-133 Ci Iodine-I 35 Ci Total for Period Ci
3. Particulates Strontium-89 Ci Strontium-90 Ci

_ Cesium-134 Ci Cesium- 137 Ci Barium-Lanthanum-140 Ci Mimganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci Iron-55 Ci Total for Period Ci (1) There were no routine ground level gaseous releases for this reporting period.

(2) No radioactively contaminated\used oil was burned during 2015.

12

TABLElC (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - (Routine) Ground Level Releases(2)

Continuous Mode Batch Mode Quarter Quarter Nuclides Released Units 3 (I) 4 (I) 3 (I) 4 (1)

1. Fission Gases Ktypton-85 Ci Krvoton-85m Ci Krvoton-87 Ci Krvoton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci '
2. Iodines lodine-131 Ci lodine-133 Ci lodine-135 Ci Total for Period Ci
3. Particulates Strontium-89 Ci Strontium-90 Ci Cesium- 134 Ci Cesium-137 Ci Barium-Lanthanum- 140 Ci Manganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci Iron-55 CI Total for Period Ci (1) There were no ground level gaseous releases for this reporting period.

(2) No radioactively contaminated used oil was burned during 2015.

13

TABLElD Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Non-routine Releases Quarter Quarter Nuclides Released Units 1(1) 2(1) 3(1) 4(1)

1. Fission Gases Krypton-85 Ci Krypton-85m Ci Krypton-87 " Ci Krypton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci
2. Iodines lodine-131 Ci

. lodine-133 Ci Iodine-I 35 Ci Total for Period Ci

3. ' Particulates Strontium-89 Ci )

Strontium-90 Ci Cesium-134 Ci Cesium- 137 Ci

\ Barium-Lanthanum-140 Ci Manganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci lron-55 Cl Total for Period Ci (1) There were no non-routine ground level gaseous releases for this reporting period.

14

TABLE2A Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Summation of All Releases Est. Total Units Quarter 1 Quarter 2 Error,%

A. Fission and Activation Products

1. Total Release (not includina tritium, aases, alpha) Ci ND ND N/A I
2. Average Diluted Concentration Durina Period uCi/ml ND ND
3. Percent of Aoolicable Limit (1)  % ND ND
8. Tritium
1. Total Release Ci 8.85E-03 9.05E-03 +/-2.00E+01 I
2.
  • Averaae Diluted Concentration Durina Period uCi/ml 1.67E-06 1.66E-06
3. Percent of Applicable Limit (1)  % 5.90E-05 6.03E-05 C. Dissolved and Entrained Gases
1. Total Release Ci ND ND N/A I
2. Averaae Diluted Concentration Durina Period µCi/ml ND ND
3. Percent of Aoolicable Limit  % ND ND D. Gross Al ha Radioactivit
1. Total Release Ci ND ND N/A E. Volume of Waste Release rior to dilution Liters N/A I F. Volume of Dilution Water Used During Period Liters 3.89E+06 3.89E+06 (3)

ND Not detected in liquid effluents.

(1) 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 abnorr:nal leakage of tritiated plant water into the underground environment.

The percent of the concentration limits specified in Appendix B to 1OCFR20.1001 - 20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.

(2) Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015.

(3) Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.

15

TABLE2A (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Summation of All Releases Est. Total Units Quarter 3 Quarter 4 Error,%

A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) Ci ND ND N/A I
2. Average Diluted Concentration Durina Period µCi/ml ND ND
3. Percent of Aoolicable Limit (1)  % ND ND B. Tritium
1. Total Release Ci 8.02E-03 7.50E-03 +/-2.00E+01 I
2. Average Diluted Concentration During Period µCi/ml 1.46E-06 1.36E-06
3. Percent of Aonlicable Limit (1)  % 5.35E-05 5.00E-05 C. Dissolved and Entrained Gases
1. Total Release Ci ND ND N/A I
2. Average Diluted Concentration Durina Period uCi/ml ND ND
3. Percent of Aoolicable Limit  % ND ND D. Gross Al ha Radioactivi
1. Total Release Ci ND ND N/A E. Volume of Waste Release rior to dilution Liters N/A l F. Volume of Dilution Water Used During Period Liters 3.89E+06 3.89E+06 (3)

ND Not detected in liquid effluents.

(1) 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.

The percent of the concentration limits specified in Appendix B to 1OCFR20.1001 - 20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.

(2) Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015.

(3) Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.

16

TABLE2B Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Routine Releases Continuous Mode Batch Mode I Nuclides Released Units Quarter 1 I Quarter 2 Quarter 1 I Quarter 2 Strontium-89 Ci - - - -

Strontium-90 Ci - - - -

Cesium-134 Ci - - - -

Cesium-137 Ci - - - -

lodine-131 Ci - - - -

Cobalt-58 Ci - - - -

Cobalt-60 Ci - - - -

lron-59 Ci - - - -

Zinc-6.5 Ci - - - -

Manganese-54 Ci - - - -

Zirconium-Niobium-95 Ci - - - -

Molvbdenum-99 Ci - - - -

Technetium-99 Ci - - - -

Barium-Lanthanum-140 Ci - - - -

Cerium-141 Other (specify) Ci Ci Ci Unidentified I Ci I Total for Period (above) Ci Xe-133 Ci Xe-135 Ci ND Not detected in liquid effluents.

Dash indicates no release of this type.

17

TABLE2B (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Routine Releases Continuous Mode Batch Mode I Nuclides Released Units Quarter 3 I Quarter 4 Quarter 3 I Quarter 4 Strontium-89 Ci - - - -

Strontium-90 Ci - - - -

Cesium-134 Ci - - - -

Cesium-137 Ci - - - -

lodine-131 Ci - - - -

Cobalt-58 Ci - - - -

Cobalt-60 Ci - - - -

lron-59 Ci - - - -

Zinc-65 Ci - - - -

Manganese-54 Ci - - - -

2irconium-Niobium-95 Ci - - - -

  • Molybdenum-99 Ci - - - -

Technetium-99 Ci - - - -

Barium-Lanthanum-140 Ci - - - -

Cerium-141 Other (specify) Ci Ci Ci Unidentified I Ci I Total for Period (above) Ci Xe-133 Ci Xe-135 Ci ND Not detected in liquid effluents.

Dash indicates no release of this type.

18

TABLE3 Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Solid Waste and Irradiated Fuel Shipments Tabl..l fntersv Nucl*u vennontVanb:e Eftluentw WomD/spo,otAm111ot ~

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TABLE 3 (continued)

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WCS-.WHteCentr<<r..r.tr.tw.ius SS*ft1b:fn$.ilttl1~

G'OC. ~ G1tt1t"f~ ~ Ctwt-tlit1tt 20

TABLE4A Entergy Nuclear Vermont Yankee Maximum* Quarterly and Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 (10CFR50, Appendix I)

Dose (mrem)(a) 3rd Source Year(b)

Quarter Total Body Dose 9.80E-07 l.OOE-06 8.88E-07 8.31E-07 3.70E-06 Footnotes (c) (c) (c) (c) (c)

Organ Dose 9.80E-07 l.OOE-06 8.88E-07 8.31E-07 3.70E-06 Footnotes (c) (c) (c) (c) (c) l.64E-05 4.24E-05 (g) (t) (t)

Beta Air (mrad)

Footnotes (d) (d) (d) (d)

Gamma Air (mrad)

Footnotes 0.72

  • "Maximum" means the largest fraction of the corresponding 10CFR50, Appendix I dose design objective.

(a) The lettered footnotes indicate the age group, organ, and location of the dose receptor, where appropriate.

(b) The yearly dose is the sum of the doses for each quarter, or a full annual assessment.

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

(d) There were no noble gas releases in this quarter.

(e) Maximum direct dose point located on the old west site boundary, approximately 208 meters from the Turbine Building (per ODCM, Rev. 35, Sect. 6.11.1).

(f) The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location WNW, 2400 meters from the stack.

(g) The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location NW, 2900 meters from the stack.

21

TABLE4B Entergy Nuclear Vermont Yankee Maximum* Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 (40CFR190)

Total Body Maximum Organ Thyroid Pathway (mrem) (mrem) (mrem)

Direct External (a) (b) 2.88 2.88 2.88 Liquids (c) 3.70E-06 3.70E-06 3.70E-06 Gases (c)' l.07E-04 l.07E-04 l.07E-04 Annual Total (d) 2.88 2.88 2.88

  • 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 I00%)

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 I. I 09 (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 using the current ODCM methodology 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.

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

(d) Annual dose 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.

22

TABLE4C Receptor Locations Entergy Nuclear Vermont Yankee Nearest Mille Sector Site Boundary (I) Nearest Resident<2l Animal <2l (meters) (meters) (meters)

N 400 1400 --

NNE 350 1384. 5520 (cows)

NE 350 1255 --

ENE 400 966 --

E 500 933 --

ESE 700 1915

\

--

SE 750 1963 3600 (cows)

SSE 850 2044 --

s 385 644 --

SSW 300 451 --

SW 250 418 --

WSW 250 451 9730 (cows) w 300 628 820 (cows)

WNW 400 1062 --

NW 550 2253 --

NNW 550 1738 --

(1) Site boundary locations taken from Table 6.10.2 of the ODCM.

(2) The location(s) given are based on information from the Vermont Yankee 2015 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.

  • 23

TABLE4D Usage Factors for Environmental Pathways Entergy Nuclear Vermont Yankee*

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

(I/yr)

Adult 21 730 520 64 310 110 8,000 Teen 16 510 630 42 400 65 8,000 Child 6.9 510 520 26 330 41 3,700 Infant 0 330 0 0 330 0 1,400

24

TABLE4E Environmental Parameters for Gaseous Effluents

  • Entergy Nuclear Vermont Yankee I Vegetables I Cow Milk Goat Milk I Meat I Variable I . Stored I Leafy I Pasture Stored Pasture Stored I Pasture I Stored I

Agricultural Productivity YV (kg/m2) 2 2 0.70 2 0.70 2 0.70 2 p 240 240 240 240 240 240 240 240 Soil Surface Density (kiz/m2)

~

T Transport Time to User (hrs) -- -- 48 48 48 48 480 480 TB Soil Exposure Time(a)(hrs) 131,400 131,400 131,400 131,400 131,400 131,400 131,400 131,400 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/dav) -- -M 50 so 6 6 "' 50 50 FP Fraction of Year on Pasture -- -- (b) -- (b) -- (b) --

FS Fraction Pasture Feed When on Pasture(c)

-- -- 1 -- 1 -- 1 --

Note: Footnotes on following page.

25

TABLE 4E (Continued)

Environmental Parameters for Gaseous Effluents Entergy Nuclear Vermont Yankee I Vegetables I Cow Milk Goat Milk Meat Variable Stored Leafy Pasture Stored Stor--' n-ctnre Stored II FG Fraction of Stored Vegetables 0.76 -- -- -- -- -- -- --

Grown in Garden FL Fraction of Leafy Vegetables -- 1.0 -- -- -- -- -- --

Grown in Garden FI Fraction Elemental Iodine = 0.5 -- -- -- -- -- -- -- --

H Absolute Humidity= 5.6Cd) -- -- -- -- -- -- I -- --

  • From VY ODCM, Table 6.9.l (Reference 1).

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

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

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

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

Reference:

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

26

TABLE4F Environmental Parameters for Liquid Releases (Tritium) Via Groundwater Entergy Nuclear Vermont Yankee Variable Potable Water Aquatic Food Stored Veg. Leafy Veg. Meat Cow Milk Name (Units)

~

Mixing Ratio 3.23E-06 5.62E-04 3.23E-06 3.23E-06 3.23E-06 3.23E-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

,-

27

TABLE5A VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT) = 1.15 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 (1) 4.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 4.00 (2) .05 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 C-3 2 0 1 1 6 3 2 0 0 0 0 0 0 0 0 4 0 19 (1) 2.00 .00 1. 00 1.00 6.00 3.00 2.00 .00 .00 .00 .00 .00 .00 .00 .00 4.00 .00 19.00 (2) .02 .00 .01 .01 .07 .03 .02 .00 .00 .00 .00 .00 . 00 .00 .00 .05 .00 .22 .

4-7 1 1 0 5 18 14 3 3 1 0 2 0 1 0 2 3 0 54 (1) 1. 00 1. 00 .00 5.00 18.00 14.00 3.00 3.*00 1. 00 .00 2.00 .00 1. 00 .00 2.00 3.00 .00 54.00 (2) .01 .01 .00 .06 .21 .16 .03 .03 .01 .00 .02 .00 .01 .00 . 02 .03 .00 . 62 8-12 0 1 0 0 0 8 5 3 1 0 0 1 0 0 0 3 0 22 (1) .00 1. 00 .00 .00 .00 8.00 5.00 3.00 1. 00 .00 .00 1. 00 .00 .00 .00 3.00 .00 22.00 (2) .00 .01 .00 .00 .00 .09 .06 .03 .01 .00 .00 .01 .00 .00 .00 .03 .00 .25 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1. 00 .00 .00 .00 1. 00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 . .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .,00 .00 .00 .00 .00 .. 00 .00 .00 .00 .oo .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 7 2 1 6 24 25 10 6 2 0 2 1 1 1 2 10 0 100 (1) 7.00 2.00 1. 00 6.00 24.00 25.00 10.00 6.00 2.00 .00 2.00 1.00 1. 00 1. 00 2.00 10.00 .00 100.00 (2) .08 .02 .01 .07 .28 .29 .. 11 .07 .02 .00 .02 .01 .01 .01 .02 .11 .00 1.15 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 28

TABLE SB VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT) = 2.05 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 4 5 5 2 1 3 0 2 1 0 0 0 0 2 0 2 0 27 (1) 2.25 2.81 2.81 1.12 .56 1. 69 .00 1.12 .56 .00 .00 .00 .00 1.12 .00 1.12 .00 15.17 (2) .05 .06 .06 .02 .01 .03 .00 .02 .01 .00 .00 .00 .00 .02 .00 .02 .00 .31 4-7 10 2 3 6 19 18 11 15 5 1 0 0 0 1 1 4 0 96 (1) 5. 62 1.12 1. 69 3.37 10.67 10.11 6.18 8.43 2.81 .56 .00 .00 .00 .56 .56 2.25 .00 53.93 (2) .11 .02 .03 .07 .22 .21 .13 .17 .06 .01 .00 .00 .00 .01 .01 .05 .00 1.10 8-12 2 1 0 0 0 2 4 17 8 0 0 0 2 2 2 5 0 45 (1) 1.12 .56 .00 .00 .00 1.12 2.25 9.55 4.49 .00 .00 .00 1.12 1.12 1.12 2.81 .00 25.28 (2) .02 .01 .00 .00 .00 .02 .05 .20 .09 .00 .00 .00 .02 .02 . 02 .06 .00 .52 13-18 0 0 0 0 0 0 0 2 2 0 0 0 0 0 0 5 0 9 (1) .00 .00 .00 .00 .00 .00 .00 1.12 1.12 .00 .00 .00 .00 .00 .00 2.81 .00 5.06 (2) .00 .00 .00 .00 .00 .00 .00 . 02 .02 .00 .00 .00 .00 .00 .00 .06 .00 .10 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .56 .00 .00 .56 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .01 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 16 8 8 8 20 23 15 36 16 1 0 0 2 5 4 16 0 178 (1) 8.99 4.49 4.49 4.49 11.24 12.92 8.43 20.22 8.99 .56 .00 .00 1.12 2.81 2.25 8.99 .00 100.00 (2) .18 .09 .09 .09 .23 .26 .17 .41 .18 .01 .00 .00 . 02 .06 .05 .18' .00 2.05 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 29

TABLE5C VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT) = 3.60 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 0 1 0 0 0 5 0 0 0 0 0 0 0 0 0 0 0 6 (1) .00 .32 .00 .00 .00 1. 60 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1. 92 (2) .00 .01 .00 .00 .00 .06 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .07 C-3 6 5 5 5 4 13 7 4 2 0 0 0 0 1 2 0 0 54 (1) 1. 92 1. 60 1. 60 1. 60 1.28 4.15 2.24 1. 28 . 64 .00 .00 .00 .00 .32 . 64 .00 .oo 17.25 (2) .07 .06 .06 .06 .05 .15 .08 .05 .02 .00 .00 .00 .00 .01 .02 .00 .00 . 62 4-7 13 9 4 10 13 18 25 29 7 2 1 0 0 1 9 18 0 159 (1) 4.15 2.88 1. 28 3.19 4.15 5.75 7.99 9.27 2.24 .64 .32 I .00 .00 .32 2.88 5.75 .00 50.80 (2) .15 .10 .05 .11 .15 .21 .29 .33 .08 .02 .01 .00 .00 .01 .10 .21 .00 1. 83 8-12 11 3 2 0 0 2 1 17 19 2 0 0 3 3 6 12 0 81 (1) 3.51 .96 . 64 .00 .00 . 64 .32 5.43 6.07 . 64 .00 -* 00 .96 .96 1. 92 3.83 .00 25.88 (2) .13 .03 .02 .00 .00 .02 .01 .20 .22 .02 .00 .00 ."03 .03 .07 .14 .00 .93 13-18 1 0 0 0 0 0 0 1 1 0 0 0 1 0 3 6 0 13 (1) .32 .00 .00 .00 .00 .00 .00 .32 .32 .00 .00 .00 .32 .00 .96 1. 92 .00 4.15 (2) .01 .00 .00 .00 .00 .00 .00 .01 .01 .00 .00 .00 .01 .00 .03 .07 .00 .15 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .*oo .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .'oo ALL SPEEDS 31 18 11 15 17 38 33 51 29 4 1 0 4 5 20 36 0 313 (1) 9.90 5.75 3.51 4.79 5.43 12.14 10.54 16.29 9.27 1. 28 .32 .00 1. 28 1. 60 6.39 11.50 .00 100.00 (2) .36 .21 .13 .17 .20 .44 .38 .59 .33 .05 .01 .00 .05 .06 .23 .41 .00 3.60

'(l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO . 95 MPH) 30

TABLE5D VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT) = 46.37 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 26 19 21 31 49 91 99 74 24 4 4 5 4 1 7 27 0 486 (1) . 64 .47 .52 .77 1. 21 2.25 2.45 1. 83 .59 .10 .1.0 .12 .10 .02 .17 . 67 .00 12.04 (2) .30 .22 .24 .36 .56 1. 05 1.14 .85 .28 .05 .05 .06 .05 .01 .08 .31 .00 5.58 C-3 74 41 42 31 55 73 73 94 73 41 22 26 34 47 63 107 0 896 (1) 1. 83 1. 02 1. 04 .77 1. 36 1. 81 1. 81 2.33 1. 81 1. 02 .55 . 64 .84 1.16 1. 56 2.65 .00 22.20 (2) .85 .47 .48 .36 . 63 .84 .84 1. 08 .84 .47 .25 .30 .39 .54 . 72 1.23 .00 10.30 4-7 120 35 9 9 19 55 119 162 84 26 22 28 62 61 148 244 0 1203 (1) 2.97 .87 .22 .22 .47 1. 36 2.95 4.01 2.08 . 64 .55 . 69 1. 54 1. 51 3.67 6.05 .00 29.81 (2) 1. 38 .40 .10 .10 .22 . 63 1. 37 1. 86 .97 .30 .25 .32 . 71 .70 1. 70 2.80 .00 13.82 8-12 110 19 1 0 1 10 8 89 82 18 17 18 147 150 142 218 0 1030 (1) 2.73 .47 .02 .00 .02 .25 .20 2.21 2.03 .45 .42 .45 3. 64 3. 72 3.52 5.40 .00 25.52 (2) 1.26 .22 .01 .00 .01 .11 .09 1. 02 .94 .21 .20 .21 1. 69 1. 72 1. 63 2.50 .00 11. 84 13-18 21 0 0 0 0 1 0 8 16 2 0 4 67 80 77 96 0 372 (1) .52 .00 .00 .00 .00 . 02 .00 .20 .40 .05 .00 .10 1. 66 1. 98 1. 91 2.38 .00 9.22 (2) .24 .00 .00 .00 .00 .01 .00 .09 .18 .02 .00 .05 .77 . 92 .88 1.10 .00 4.27 19-24 0 0 0 0 0 0 0 0 0 0 0 0 4 10 16 17 0 47 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .10 .25 .40 .42 .00 1.16 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .11 .18 .20 .00 .54 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 2 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .00 .00 .05 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .00 .00 .02 ALL SPEEDS 351 114 73 71 124 230 299 427 279 91 65 81 318 349 455 709 0 4036 (1) 8.70 2.82 1. 81 1. 76 3.07 5.70 7.41 10.58 6.91 2.25 1. 61 2.01 7.88 8.65 11.27 17.57 .00 100.00 (2) 4.03 1. 31 .84 .82 1. 42 2. 64 3.44 4.91 3.21 1. 05 .75 .93 3. 65 4.01 5.23 8.15 .00 46.37 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 31

TABLE SE VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT) = 28.16 WIND DIRECTION FROM

(

SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 30 - 18 12 12 10 21 64 74 41 32 30 13 11 16 17 25 0 426 (1) 1. 22 .73 .49 .49 .41 .86 2.61 3.02 1. 67 1. 31 1.22 .53 .45 . 65 .69 1. 02 .00 17.38 (2) .34 .21 .14 .14 .11 .24 .74 .85 .47 .37 .34 .15 .13 .18 .20 .29 .00 4.89 C-3 30 25 12 14 21 31 44 77 79 110 170 145 135 92 104 60 0 1149 (1) 1.22 1. 02 .49 .57 .86 1.26 1. 80 3.14 3.22 4.49 6.94 5.92 5.51 3.75 4.24 2.45 .00 46.88 (2) .34 .29 .14 .16 .24 .36 .51 .88 .91 1. 26 1. 95 1. 67 1. 55 1. 06 1.19 .69 .00 13.20 4-7 40 8 1 0 3 8 34 53 28 5 14 43 80 59 84 133 0 593 (1) 1. 63 .33 .04 .00 .12 .33 1. 39 2.16 1.14 .20 .57 1. 75 3.26 2.41 3.43 5.43 .00 24.19

,(2) . 46 .09 .01 .00 .03 .09 .39 . 61 .32 .06 .16 .49 .92 .68 .97 1. 53 .00 6.81 8-12 14 1 0 0 0 0 1 16 21 2 1 3 4*6 36 20 52 0 213 (1) .57 .04 .00 .00 ,oo .00 .04 . 65 .86 .08 .04 .12 1. 88 1. 47 .82 2.12 .00 8.69 (2) .16 .01 .00 .00 .* 00 .00 .01 .18 .24 .02 .01 .03 .53 .41 .23 .60 .00 2.45 13-18 4 0 '-o 0 0 0 0 1 1 0 1 0 9 24 4 21 0 65 (1) .16 .oo .oo .00 .00 .00 .00 . 04 .04 .00 .04 .oo .37 .98 .16 .86 .00 2.65 (2) .05 .00 .00 .00 .00 .00 .00 .01 .01 .00 .01 .00 .10 .28 .05 .24 .00 .75 19-24 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 3 0 5 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .08 .00 .00 .12 .00 .20 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .00 .00 .03 .00 .06 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00  :"'oo .00 .00 ALL SPEEDS 118 52 25 26 34 60 143 221 170 149 216 204 283 227 229 294 0 2451 (1) 4.81 2.12 1. 02 1. 06 1. 39 2.45 5.83 9.02 6.94 6.08 8.81 8.32 11.55 9. 26 9.34 12.00 .00 100.00 (2) 1. 36 . 60 .29 .30 .39 .69 1. 64 2.54 1. 95 1. 71 2.48 2.34 3.25 2.61 2.63 3.38 .00 28.16

'

(l}=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2}=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 32

TABLE 5F VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) 14.03 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW . WSW w_ WNW NW NNW VRBL TOTAL MPH CALM 5 7 5 5 6 12 16 17 28 49 31 26 10 11 13 22 0 263 (1) .41 .57 .41 .41 .49 .98 1. 31 1. 39 2.29 4.01 2.54 2.13 .82 .90 1. 06 1. 80 .00 21. 54 (2) .06 .08 .06 .06 .07 .14 .18 .20 .32 .56 .36 .30 .11 .13 .15 .25 .00 3.02 C-3 16 5 5 2 6 8 15 27 53 84 195 173 116 76 40 20 0 841 (1) 1. 31 .41 .41 .16 .49 .66 1. 23 2.21 4.34 6.88 15.97 14.17 9.50 6.22 3.28 1. 64 .00 68.88 (2) .18 .06 .06 .02 .07 .09 .17 .31 . 61 . 97 2.24 1. 99 1.33 .87 .46 .23 .00 9.66 4-7 4 0 0 0 0 1 3 5 3 12 11 12 14 17 15 17 0 114 (1) .33 .00 .00 .00 .00 .08 .25 .41 .25 .98 .90 .98 1.15 1. 39 1. 23 1. 39 .00 9.34 (2) .05 .00 .00 .00 .00 .01 .03 .06 .03 .14 .13 .14 .16 .20 .17 .20 .00 1. 31 8-12 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 0 3 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .08 .16 .00 .25 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .02 .00 .03 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 25 12 10 7 12 21 34 49 84 145 237 211 140 104 69 61 0 1221 (1) 2.05 .98 .82 .57 .98 1. 72 2.78 4.01 6.88 11. 88 19. 41 17.28 11. 47 8.52 5.65 5.00 .00 100.00 (2) .29 .14 .11 .08 .14 .24 .39 .56 .97 1. 67 2. 72 2.42 1. 61 1.19 .79 .70 .00 14.03 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 33

TABLE5G VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT) 4. 64 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 6 10 4 1 5 9 10 10 22 19 7 7 4 7 6 5 0 132 (1) 1. 49 2.48 .99 .25 1.24 2.23 2.48 2.48 5.45 4.70 1. 73 1. 73 .99 1. 73 1. 49 1.24 .00 32.67 (2) .07 .11 .05 .01 .06 .10 .11 .11 .25 .22 .08 .08 .05 .08 .07 .06 .00 1. 52 C-3 5 2 4 2 7 7 5 13 12 29 32 44 30 24 13 8 0 237 (1) 1. 24 .so .99 .50 1. 73 1. 73 1. 24 3.22 2.97 7.18 7.92 10.89 7.43 5.94 3.22 1. 98 .00 58.66 (2) .06 .02 .05 .02 .08 .08 .06 .15 .14 .33 .37 .51 .34 .28 .15 .09 .00 2. 72 4-7 1 0 0 0 0 1 0 1 1 5 4 1 8 3 5 5 0 35 (1) .25 .00 .00 .00 .00 .25 .oo .25 .25 1.24 .99 .25 1. 98 .74 1.24 1.24 .00 8.66 (2) .01 .00 .00 .00 .00 .01 .00 .01 .01 .06 .05 .01 .09 .03 .06 .06 .00 .40 8-12 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .oo .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 . 00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .0 0 0 (1) .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 12 12 8 3 12 17 15 24 35 53 43 52 42 34 24 18 0 404 (1) 2.97 2.97 1. 98 .74 2.97 4.21 3. 71 5.94 8.66 13.12 10.64 12.87 10.40 8.42 5.94 4.46 .00 100.00 (2) .14 .14 .09 .03 .14 .20 .17 .28 .40 . 61 .49 .60 .48 .39 .28 .21 .00 4.64

(!)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 34

TABLE SH VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 71 55 42 49 70 138 189 175 115 104 72 51 29 35 43 79 0 1317 (1) .82 . 63 .48 .56 .80 1.59 2.17 2.01 1.32 1.19 .83 .59 .33 .40 .49 .91 .00 15.13 (2) .82 . 63 .48 .56 .80 1. 59 2.17 2.01 1. 32 1.19 .83 .59 .33 .40 .49 __,.-* 91 .00 15.13 C-3 137 83 74 57 100 138 146 217 220 264 419 388 315 242 222 201 0 3223 (1) 1. 57 .95 .85 . 65 1.15 1. 59 1. 68 2.49 2.53 3.03 4.81 4. 4 6 3. 62 2.78 2.55 2.31 .00 37.03 (2) 1. 57 .95 .85 . 65 1.15 1. 59 1. 68 2.49 2.53 3.03 4.81 4.46 3.62 2.78 2.55 2.31 .00 37.03 4-7 189 55 17 30 72 115 195 268 129 51 54 84 165 142 264 424 0 2254 (1) 2.17 .63 .20 .34 .83 1.32 2.24 3.08 1. 48 .59 . 62 . 97 1. 90 1. 63 3.03 4.87 .00 25.90 (2) 2.17 . 63 .20 .34 .83 1. 32 2.24 3.08 1. 48 .59 . 62 . 97 1. 90 1. 63 3.03 4.87 .00 25.90

-

8-12 137 25 3 0 1 22 19 142 131 22 18 22 198 191 171 292 0 1394 (1) 1. 57 .29 .03 .00 .01 .25 .22 1. 63 1. 51 .25 .21 .25 2.28 2.19 1. 96 3.36 .00 16.02 (2) 1. 57 .29 .03 .00 .01 .25 .22 1. 63 1. 51 .25 .21 .25 2.28 2.19 1. 96 3.36 .00 16.02 13-18 26 0 0 0 0 1 0 12 20 2 1 4 77 105 84 128 0 460 (1) .30 .00 .00 .00 .00 .01 .00 .14 .23 .02 .01 .05 .88 1.21 .97 1. 47 .00 5.29 (2) .30 .00 .00 .00 .00 .01 .00 .14 .23 .02 .01 .05 .88 1.21 .97 1. 47 .00 5.29 19-24 0 0 0 0 0 0 0 0 0 0 0 0 6 10 17 20 0 53 (1) .00 .00 .00 .00 .00 .00 .00 .00 .oo .00 .oo .00 .07 .11 .20 .23 .00 . 61 (2) .00 .00 .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .07 .11 .20 .23 .00 . 61 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 2 (1) .00 .00 .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .02 .00 .00 .02 (2) .00 .00 .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .02 .00 .00 .02 ALL SPEEDS 560 218 136 136 243 414 549 814 615 443 564 549 790 725 803 1144 0 8703 (1) 6.43 2.50 1. 56 1. 56 2.79 4. 76 6.31 9.35 7.07 5.09 6.48,6.31 9.08 8.33 9.23 13.14 .00 100.00 (2) 6.43 2.50 1. 56 1.56 2.79 4.76 6.31 9.35 7.07 5.09 6.48 '6. 31 9.08 8.33 9.23 13.14 .00 100.00 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 35

TABLE6A VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT) = .32 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 4 0 0 0 0 0 0 0 0 0 0 0 . 0 0 0 0 0 4 (1) 14.29 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 14.29 (2) .05 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 C-3 1 1 0 0 0 1 0 1 1 0 0 0 0 0 1 1 0 7 (1) 3.57 3.57 .00 .00 .00 3.57 .00 3.57 3.57 .00 .00 .00 .00 .00 3.57 3.57 .00 25.00 (2) .01 .01 .00 .00 .00 .01 .00 .01 .01 .00 .00 .00 .00 .00 .01 .01 .00 .08 4-7 0 0 0 1 0 0 5 3 2 0 0 0 0 0 0 0 0 11 (1) .00 .00 .00 3.57 .00 .00 17.86 10.71 7.14 .00 .00 .00 .00 .00 .00 .00 .00 39.29 (2) .00 .00 .00 .01 .00 .00 .06 .03 .02 .00 .00 .00 .00 .00 .00 .00 .00 .13 8-12 1 1 0 0 0 0 1 0 0 0 0 0 0 0 1 1 0 5 (1) 3.57 3.57 .00 .00 .00 .00 3.57 .OD .00 .00 .00 .00 .00 .00 3.57 3.57 .00 17.86 (2) .01 .01 .00 .DO .00 .00 .01 .OD .00 .00 .00 .00 .00 .00 .01 .01 .00 .06 13-18 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 1 (1) .OD .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 3.57 .00 .00 .00 .00 3.57 (2) .00 .00 .00 .00 .00 .00 .00 .OD .00 .00 .'00 .00 .01 .00 .00 .00 .00 .01 19-24 0 D 0 0 0 0 0 0 D 0 0 0 0 0 0 0 0 0 (1) .00 .OD .00 .00 .00 .DO .00 .00 .OD .00 .00 .00 .00 .00 .00 .00 .00 .DO (2) .00 .00 .DO .00 .00 .DO .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .OD GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .DO .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 6 2 0 1 0 1 6 4 3 0 0 0 1 0 2 2 0 28 (1) 21. 43 7 .14 .00 3.57 .00 3.57 21.43 14.29 10.71 .00 .00 .00 3.57 .00 7.14 7.14 .DO 100.0D (2) .07 .02 .00 .01 .OD .01 .07 .05 .03 .OD .00 .00 .01 .DD .02 .02 .DO .32 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 36

TABLE6B VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT) .23 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 4-7 1 1 0 0 0 0 2 0 0 0 0 0 0 0 1 1 0 6 (1) 5.00 5.00 .00 .00 .00 .00 10.00 .00 .00 .00 .00 .00 .bo .00 5.00 5.00 .00 30.00 (2) .01 .01 .00 .00 .00 .00 .02 .00 .00 .00 .00 .00 .00 .00 .01 .01 .DO .07 8-12 3 0 0 0 0 1 0 0 0 0 0 0 1 0 0 2 0 7 (1). 15.00 .00 .00 .00 .00 5.00 .00 .00 .00 .00 .00 .00 5.00 .00 .00 10.00 .00 35.00 (2) .03 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .01 .00 .00 .02 .00 .08 13-18 0 0 0 0 0 1 0 0 0 0 0 0 . 0 0 1 4 0 6 (1) .00 .00 .00 .00 .00 5.00 .00 .00 .00 .00 .00 .00 .00 .00 5.00 20.00 .00 30.00 (2) .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .01 .05 .00 .07 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 5.00 .00 5.00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 GT 24 0 0. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 4 1 0 0 0 2 2 0 0 0 0 0 1 0 2 8 0 20 (1) 20.00 5.00 .00 .00 .00 10.00 10.00 .00 .00 .00 .00 .00 5.00 .00 10.00 40.00 .00 100.00 (2) .05 .01 .00 .00 .00 .02 .02 .00 .00 .00 .00 .00 .01 .00 .02 .09 .00 .23 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO . 95 MPH) 37

TABLE6C VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT) 1. 59 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 1 0 0 1 1 1 1 0 1 0 0 0 0 0 0 1 0 7 (1) . 72 .00 .00 .72 . 72 . 72 . 72 .00 .72 .00 .00 .00 .00 .00 .00 . 72 .00 5.07 (2) .01 .00 .00 .01 .01 .01 .01 .00 .01 .00 .00 .00 .00 .00 .00 .01 .00 .08 4-7 3 3 2 1 1 9 5 0 0 0 0 0 0 0 1 8 0 33 (1) 2.17 2.17 1. 45

  • 72 .72 6.52 3. 62 .00 .00 .00 .00 .00 .00 .00 . 72 5.80 .00 23.91 (2) .03 .03 .02 .01 .01 .10 .06 .00 .00 .00 .00 .00 .00 .00 .01 .09 '. 00 .38 8-12 10 2 4 2 1 7 5 4 0 0 0 1 0 3 3 17 0 59 (1) 7.25 1. 45 2.90 1. 45 . 72 5.07 3. 62 2.90 .00 .00 .00 . 72 .00 2.17 2.17 12.32 .00 42.75 (2) .11 .02 .05 .02 .01 .08 .06 .05 .00 .00 .00 .01 .00 .03 .03 .20 .00 . 68 13-18 8 2 0 0 0 1 2 1 1 0 0 0 1 1 1 10 0 28 (1) 5.80 1. 45 .00 .00 .00 . 72 1. 45 . 72 . 72 .00 .00 .00 . 72 . 72 . 72 7.25 .00 20.29 (2) .09 .02 .00 .00 .00 .01 . 02 .01 .01 .00 .00 .00 .01 .01 .01 .11 .00 .32 19-24 0 0 0 0 0 0 1 0 3 0 0 0 0 0 0 7 0 11 (1) .00 .00 .00 .00 .00 .00 . 72 .00 2.17 .00 .00 .00 .00 .00 .00 5.07 .00 7.97 (2) .00 .00 .00 .00 .00 .00 .01 .00 .03 .00 .00 .00 .00 .00 .00 .08 .00 .13 GT 2.4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

,-,

ALL SPEEDS 22 7 6 4 3 18 14 5 5 0 0 1 1 4 5 43 0 138 (1) 15. 94 5.07 4.35 2.90 2.17 13.04 10.14 3.62 3.62 .00 .00 .72 .72 2.90 3.62 31.16 .00 100.00 (2) .25 .08 .07 .05 .03 .21 .16 .06 .06 .00 .00 .01 .01 .05 .06 .49 .00 1. 59 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 38

TABLE6D VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT) = 52.26 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 5 2 0 1 3 2 16 3 1 1 0 0 1 0 0 6 0 41 (1) .11 .04 .00 .02 .07 .04 .35 .07 .02 .02 .00 .00 .02 .00 .00 .13 .00 .90 (2) .06 .02 .00 .01 .03 .02 .18 .03 .01 .01 .00 .00 .01 .00 .00 .07 .00 .47 C-3 55 32 37 39 49 . 46 85 59 23 8 10 9 5 16 29 55 0 557 (1) 1.21 .70 .81 .86 1. 08 1. 01 1. 87 1. 30 .51 .18 .22 .20 .11 .35 . 64 1.21 .00 12.25 (2) .63 .37 .43 .45 .56 .53 .98 .68 .26 .09 .11 .10 .06 .18 .33 .63 .00 6.40 4-7 90 36 27 22 45 131 203 158 71 19 14 14 17 19 64 173 0 1103 (1) 1. 98 .79 .59 .48 .99 2.88 4.46 3.47 1.56 .42 .31 .31 .37 . 42 1. 41 3.80 .00 24.25 (2) 1. 03 .41 .31 .25 .52 1. 51 2.33 1. 82 .82 .22 .16 .16 .20 .22 .74 1. 99 .00 12.67 8-12 113 38 11 6 14 36 113 234 247 49 28 36 109 123 68 249 0 1474 (1) 2.48 .84 .24 .13 .31 .79 2.48 5.15 5.43 1. 08 . 62 .79 2.40 2.70 1. 50 5.47 .00 32. 41 (2) 1. 30 .44 .13 .07 .16 .41 1. 30 2.69 2.84 .56 .32 .41 1.25 1. 41 .78 2.86 .00 16.94 13-18 93 16 3 1 4 9 8 54 134 16 8 8 134 137 109 212 0 946 (1) 2.04 .35 .07 .02 .09 .20 .18 1.19 2.95 .35 .18 .18 2.95 3.01 2.40 4.66 .00 20.80 (2) 1. 07 .18 .03 .01 .05 .10 .09 . 62 1. 54 .18 .09 .09 1. 54 1. 57 1. 25 2.44 .00 10.87 19-24 34 3 0 0 0 0 1 5 19 1 1 2 52 52 50 114 0 334 (1) .75 .07 .00 .00 .00 .00 .02 .11 .42 .02 .02 .04 1.14 1.14 1.10 2.51 .00 7.34 (2) .39 .03 .00 .00 .00 .00 .01 .06 .22 .01 .01 .02 . 60 .60 .57 1. 31 .00 3.84 GT 24 1 1 0 0 0 0 0 0 1 0 0 2 4 5 21 58 0 93 (1) .02 .02 .00 .00 .00 .00 .00 .00 .02 .00 .00 .04 .09 .11 .46 1.28 .00 2.04 (2) .. 01 .01 .00 .00 .00 .00 .00 .00 .01 .00 .00 .02 .05 .06 .24 . 67 .00 1. 07 ALL SPEEDS 391 128 78 69 115 224 426 513 496 94 61 71 322 352 341 867 0 4548 (1) 8.60 2.81 1. 72 1. 52 2.53 4.93 9. 37 11. 28 10. 91 2.07 1. 34 1. 56 7.08 7.74 7.50 19.06 .00 100.00 (2) 4.49 1. 47 .90 .79 1. 32 2.57 4.89 5.89 5.70 1. 08 .70 .82 3.70 4.04 3.92 9.96 .00 52.26 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO . 95 MPH)

(

39

TABLE6E VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT) 30.52 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 3 4 2 1 4 9 13 3 2 1 0 1 1 1 0 2 0 47 (1) .11 .15 .08 .04 .15 .34 .49 .11 .08 .04 .00 .04 .04 .04 .00 .08 .00 1. 77 (2) .03 .05 .02 .01 .05 .10 .15 .03 .02 .01 .00 .01 .01 .01 .00 .02 .00 .54 C-3 95 73 56 35 86 91 100 51 37 18 10 10 10 23 43 81 0 819 (1) 3.58 2.75 2.11 1.32 3.24 3.43 3.77 1. 92 1. 39 .68 .38 .38 .38 .87 1. 62 3.05 .00 30.84 (2) 1. 09 .84 . 64 .40 .99 1. 05 1.15 .59 .43 .21 .11 .11 .p .26 .49 .93 .00 9.41 4-7 88 11 6 6 18 50 172 142 35 26 16 21 23 26 55 271 0 966 (1) 3.31 .41 .23 .23 . 68 1. 88 6.48 5.35 1. 32 .98 . 60 .79 .87 .98 2.07 10.20 .00 36.37 (2) 1. 01 .13 .07 .07 .21 . 5*7 1. 98 1. 63 .40 .30 .18 .24 .26 .30 .63 3.11 .00 11.10 8-12 37 6 0 0 1 4 38 57 63 18 9 19 70 55 40 191 0 608 (1) 1. 39 .23 .00 .00 .04 .15 1. 43 2.15 2.37 .68 .34 . 72 2. 64 2.07 1. 51 7.19 .00 22.89 (2) .43 .07 .00 .DO .01 .05 .44 . 65 . 72 .21 .10 .22 .80 . 63 .46 2.19 .00 6.99 13-18 16 0 0 0 0 0 1 5 22 6 4 5 32 24 9 64 0 188 (1) . 60 .00 .00 .DO .OD .OD .04 .19 .83 .23 .15 .19 1. 20 .90 .34 2.41 .00 7.08 (2) .18 .00 .00 .00 .00 .00 .01 .06 .25 .07 .05 .06 .37 .28 .10 .74 .00 2.16 19-24 1 0 0 0 0 0 0 0 2 1 0 1 2 7 1 10 0 25 (1) .04 .00 .00 .00 .00 .00 .00 .00 .08 .04 .DO .04 .08 .26 .04 .38 .00 . 94 (2) .01 .00 .00 .00 .00 .00 .00 .00 .02 .01 .00 .01 .02 .08 .01 .11 .DO .29 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 3 (1) .00 .00 .00 .00 .OD .DO .DO .DO .00 .OD .00 .OD .OD .DO .DO .11 .00 .11 (2) .00 .DO .DO .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .03 .00 .03 ALL SPEEDS 240 94 64 42 109 154 324 258 161 70 39 57 138 136 148 622 0 2656 (1) 9.04 3.54 2.41 1. 58 4.10 5.80 12.20 9. 71 6.06 2. 64 1. 47 2.15 5.20 5.12 5.57 23.42 .DO 100.00 (2) 2.76 1. 08 .74 .48 1.25 1. 77 3. 72 2.96 1. 85 .80 .45 . 65 1. 59 1. 56 1. 70 7.15 .00 30.52 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 40

TABLE6F VERMONT YANKEE JAN lS - DEC lS METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) 12.S7 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 2 1 0 1 3 3 2 0 1 1 1 0 0 0 1 1 0 17 (1) .18 .09 .00 .09 .27 .27 .18 .00 .09 .09 .09 .00 .00 .00 .09 .09 .00 1. SS

(.2) .02 .01 .00 .01 .03 .03 .02 .00 .01 .01 .01 .00 .00 .00 .01 .01 .00 .20 C-3 40 29 37 22 29 39 43 42 20 22 13 s 14 9 24 40 0 428 (1) 3.66 2.6S 3.38 2.01 2. 6S 3. S6 3.93 3.84 1. 83 2.01 1.19 .46 1.28 .82 2.19 : 3. 66 .00 39.12 (2) .46 .33 .43 .2S .33 .4S .49 .48 .23 .2S .lS .06 .16 .10 .28 .46 .00 4.92 4-7 3S s 0 6 13 28 9S 62 34 8 19 lS 16 14 37 94 0 481 (1) 3.20 .46 .00 .SS 1.19 2.S6 8. 68 S.67 3.11 .73 1. 74 1.37 1. 46 1.28 3.38 8.S9 .00 43.97 (2) .40 .06 .00 .07 .lS .32 1. 09 . 71 .39 .09 .22 .17 .18 .16 .43 1. 08 .00 S.S3 8-12 4 0 0 0 0 6 21 lS 12 8 3 9 13 14 7 46 0 1S8 (1) .37 .00 .00 .00 .00 .SS 1. 92 1. 37 1.10 .73 .27 .82 1.19 1. 28 . 64 4.20 .00 14.44 (2) .OS .00 .00 .00 .00 .07 .24 .17 .14 .09 .03 .10 .ls .16 .08 .S3 .00 1. 82 13-18 1 0 0 0 0 0 0 0 1 0 0 0 3 0 0 s 0 10 (1) .09 .00 .00 .00 .00 .00 .00 .00 .09 .00 .00 .00 .27 .00 .00 .46 .00 .91 (2) .01 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .03 .00 .00 .06 .00 .11 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 . 0.0 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 82 3S 37 29 4S 76 161 119 68 39 36 29 46 37 69 186 0 1094 (1) 7.SO 3.20 3.38 2. 6S 4 .11 6.9S 14. 72 10.88 6.22 3.S6 3.29 2. 6S 4.20 3.38 6.31 17.00 .00 100.00 (2) . 94 .40 .43 .33 .S2 .87 1. 8S 1. 37 .78 .4S .41 .33 .S3 .43 .79 2.14 .00 12.S7 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2) =PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .9S MPH) 41

TABLE6G VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 ~T WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT) = 2.52 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 0 0 0 0 1 0 0 0 1 0 0 0 0 0 0 0 0 2 (1) .00 .00 .00 .00 .46 .00 .00 .00 .46 .00 .00 .00 .00 .00 .00 .00 .00 .91 (2) .00 .. 00 .00 .00 .01 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .02 C-3 4 2 2 4 2 4 6 8 4 1 4 7 3 3 9 6 0 69 (1) 1. 83 .91 .91 1. 83 .91 1. 83 2.74 3.65 1. 83 .46 1. 83 3.20 1. 37 1. 37 4.11 2.74 .00 31. 51 (2) .05 .02 .02 .05 .02 .05 .07 .09 .05 .01 .05 .08 .03 .03 .10 .07 .00 .79 4-7 3 0 1 1 3 3 12 13 9 8 5 9 6 5 9 8 0 95

. (1) 1. 37 .00 .46 .46 1. 37 1. 37 5.48 5.94 4.11 3.65 2.28 4 .11 2.74 2.28 4.11 3.65 .00 43.38 (2) .03 .00 .01 .01 .03 .03 .14 .15 .10 .09 .06 .10 .07 .06 .10 .09 .00 1. 09 8-12 1 0 0 0 0 0 1 4 2 2 6 9 10 8 4 4 0 51 (1) .46 .00 .00 .00 .00 .00 .46 1. 83 .91 .91 2.74 4.11 4.57 3.65 1. 83 1. 83 .00 23.29 (2) .01 .00 .00 .00 .00 .00 .01 .05 .02 .02 .07 .10 .11 .09 .05 .05 .00 .59 13 0 0 0 0 0 0 0 0 0 0 0 0 - 1 1 0 0 0 2 (1) - . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .46 .46 .00 .00 .00 .91 (2) .00 .00 .00 .00 .00 - . 00 .00 .00 .00 .00 .00 .00 .01 .01 .00 .00 .00 .02 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .bo .00 .00 .00 .00 . 00- .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 8 2 3 5 6 7 19 25 16 11 15 25 20 17 22 18 0 219 (1) 3.65 .91 1. 37 2.28 2.74 3.20 8. 68 11. 42 7.31 5.02 6.85 11.42 9.13 7.76 10.05 8.22 .00 100.00 (2) .09 .02 .03 .06 .07 .08 .22 .29 .18 .13 .17 .29 .23 .20 .25 .21 .00 2.52 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 42

TABLE6H VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) 100.00 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 14 7 2 3 11 14 31 6 5 3 1 1 2 1 1 9 0 111 (1) .16 .08 .02 .03 .13 .16 .36 .07 .06 .03 .01 .01 .02 .01 .01 .10 .00 1. 28 (2) .16 .08 .02 .03 .13 .16 .36 .07 .06 .03 .01 .01 .02 .01 .01 .10 .00 1.28 C-3 196 137 132- 101 167 182 235 161 86 49 37 31 32 51 106 184 0 1887 (1) 2.25 1. 57 1. 52 1.16 1. 92 2.09 2.70 1. 85 .99 .56 .43 .36 .37 .59 1.22 2.11 .00 21. 68 (2) 2.25 1. 57 1. 52 1.16 1. 92 2.09 2.70 1. 85 .99 .56 .. 43 .36 .37 .59 1.22 2.11 .00 21. 68 4-7 220 56 36 37 80 221 494 378 151 61 54 59 62 64 167 555 0 2695 (1) 2.53 . 64 .41 .43 .92 2.54 5.68 4.34 1. 74 .70 . 62 . 68 . 71 .74 1. 92 6.38 .00 30.97 (2) 2.53 . 64 .41 .43 .92 2.54 5.68 4.34 1. 74 .70 . 62 . 68 .71 .74 1. 92 6.38 .00 30.97 8-12 169 47 15 8 16 54 179 314 324 77 46 74 203 203 123 510 0 2362 (1) 1. 94 .54 .17 .09 .18 . 62 2.06 3.61 3. 72 .88 .53 .85 2.33 2.33 1. 41 5.86 .00 27.14 (2) 1. 94 .54 .17 .09 .18 . 62 2.06 3. 61 3.72 .88 .53 .85 2.33 2.33 1. 41 5. 86 .00 27.14 13-18 118 18 3 1 4 11 11 60 158 22 12 13 172 163 120 295 0 1181 (1) 1. 36 .21 .03 .01 .05 .13 .13 .69 1. 82 .25 .14 .15 1. 98 1. 87 1. 38 3.39 .00 13.57 (2) 1. 36 .21 .03 .01 .05 .13 .13 .69 1. 82 .25 .14 .15 1. 98 1. 87 1. 38 3.39 .00 13.57 19-24 35 3 0 0 0 0 2 5 24 2 1 3 54 59 51 132 0 371 (1) .40 .03 .00 .00 .00 .00 .02 .06 .28 .02 .01 .03 . 62 . 68 .59 1.52 .00 4.26 (2) .40 .03 .00 .00 .00 .00 .02 .06 .28 .02 .01 .03 . 62 . 68 .59 1. 52 .00 4.26 GT 24 1 1 0 0 0 0 0 0 1 0 0 2 4 5 21 61 0 96 (1) .01 .01 .00 .00 .00 .00 .00 .00 .01 .00 .00 .02 .05 .06 .24 .70 . 00 .. 1.10 (2) .01 .01 .00 .oo . 00 .00 .00 .00 .01 .00 . 00 . .02 .05 .06 .24 .70 .00 1.10 ALL SPEEDS 753 269 188 150 278 482 952 924 749 214 151 183 529 546 589 1746 0 8703 (1) 8. 65 3.09 2.16 1. 72 3.19 . 5.54 10.94 10. 62 8.61 2. 46 1. 74 2.10 6.08 6.27 6.77 20.06 .00 100.00 (2) 8. 65 3.09 2.16 1. 72 3.19 5.54 10.94 10. 62 8. 61 2.46 1. 74 2.10 6.08 6.27 6.77 20.06 .00 100.00 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO . 95 MPH) 43

APPENDIX A SUPPLEMENTAL INFORMATION Facility: Vermont Yankee Nuclear Power Station Licensee: Entergy Nuclear Vermont Yankee lA. ODCM DOSE ANO DOSE RATE LIMITS -

ODCM Controls Dose Limit

a. Noble Gases 3/4.3.1 Total body dose rate 500 mrem/yr 3/4.3. l Skin.dose rate 3000 mrem/yr 3/4.3.2 Gamma air dose 5 mrad in a quarter 3/4.3.2 Gamma air dose 10 mrad in a year 3/4.3.2 Beta air dose 10 mrad in a quarter 3/4.3.2 Beta air dose 20 mrad in a year
b. Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 3/4.3..1 Organ dose rate 1500 mrem/yr 3/4.3.3 Organ dose 7.5 mrem in a quarter

'* 3/4.3.3 Organ dose 15 mrem in a year

c. Liquids 3/4.2.2 Total body dose 1.5 mrem in a quarter 3/4.2.2 Total body dose 3 mrem in a year 3/4.2.2 Organ dose 5 mrem in a quarter 3/4.2.2 Organ dose 10 mrem in a year 2A. ODCM LIMITS-CONCENTRATION ODCM Control
a. Noble Gases No ECL Limits
b. Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days No ECL Limits A-1
c. Liquids 3/4.2.1 Sum of the fractions of ECL excluding noble gases (1 OCFR20, Appendix B, Table 2, Column 2): _:::: l.OE+Ol 3/4.2. l Total noble gas concentration: _:::: 2E-04 µCi/cc
3. AVERAGE ENERGY

\

Provided below are the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable.

a. Average gamma energy: Not Applicable
b. Average beta energy: Not Applicable
4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
a. Fission and Activation Gases Continuous stack monitors monitor the gross Noble Gas radioactivity released from the plant stack. Because release rates are normally below the detection limit of these monitors, periodic grab samples are taken and analyzed for the gaseous isotopes present. These are used to calculate the individual isotopic releases indicated in Table lB and the totals of Table lA. The error involved in these steps may be approximately +/-23 percent.
b. Iodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. The filters and cartridges are normally removed weekly and are analyzed for Iodine-131, 132, 133, 134, and 135. The error involved in these steps may be approximately +/-18 percent.

A-2

c. Particulates The particulate filters described in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximately +/-18 percent.
d. Tritium ODCM Table 4.3 .1 requires as a minimum that grab samples from the plant stack be taken monthly and analyzed for tritium. The stack tritium collection has been upgraded with silica gel columns and continuous sampling of stack effluents. The error involved in this sample is approximately +/-18 percent.
e. \\Taste ()il Prior to issuing the permit to burn a drum of radioactively contaminated waste oil, one liter of the oil is analyzed by gamma spectroscopy to determine concentrations of radionuclides that meet or exceed the LLD for all of the liquid phase radionuclides listed in ODCM Table 4.2.1.

Monthly, samples from drums that were issued burn permits are sent to the contracted laboratory for compositing and analysis. The lab analyzes for tritium, alpha, Fe-55, Sr-89, and Sr-90 on the composite sample.

The error involved in this sample is approximately +/-15 percent.

f. Liquid Effluents If radioactive liquid effluents are to be released from the facility, they are continuously monitored. Measurements are also required on a representative sample of each batch ofradioactive liquid effluents released. For each batch, station records are retained of the total activity (mCi) released, concentration

(µCi/ml) of gross radioactivity, volume (liters), and approximate total.quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River.

Each batch of radioactive liquid effluents to be released is analyzed for gross gamma and gammaisotopic radioactivity. A monthly proportional composite sample, comprising an aliquot of each batch released during a month, is analyzed for tritium and gross alpha radioactivity. A quarterly proportional

  • composite sample, comprising an aliquot of each batch released during a quarter, is analyzed for Sr-89, Sr-90, and Fe-55.

A-3

5. BATCH RELEASES
a. Liquid There were no*routine liquid batch releases during the reporting period.
b. Gaseous There were no routine gaseous batch releases during the reporting period.
6. ABNORMAL RELEASES
a. Liguid
1) In 2015 there was a continuous release due to the residual radioactivity in groundwater from a previously undetected leak from a subsurface structure.

The leak condition was identified through monitoring well data in January 2010. The leak was stopped in February 2010 ..

2) For 2015, the total Tritium radioactivity conservatively estimated to be released to the Connecticut River is 0.0334 Curies. No other plant-related radionuclides were detected in ground water.
b. Gaseous There were no non-routine gaseous releases (measured) during the reporting period.

_,

A-4

APPENDIXB LIQUID HOLDUP TANKS Requirement Technical Specification 3. l .A.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.1.A.l, a description of the events leading to this condition is required in the next annual Radioactive Effluent Release Report per ODCM Section 10.1.

Response: The limits of Technical Specification 3.1.A.1 were not exceeded during this reporting period. (Note that during 2015 the section numbering of the Technical Specifications changed due to the implementation of an NRC-approved License Amendment following permanent shutdown and defueling of the plant, but there were no changes made to the limits in Technical Specification 3.1.A.1 from those previously contained in Technical Specification 3.8.D.l)

B-1

APPENDIXC RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.1. If an inoperable radioactive liquid effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3 .1.1, an explanation in the rtext annual Radioactive Effluent Release Report of the reason(s) for delay in correcting the inoperability are required per ODCM Section 10.1.

Response: Since the requirements of ODCM Table 3.1.1 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period, no response is required. j C-1

APPENDIXD RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.2. If inoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.1.2, an explanation in the next annual Radioactive Effluent Release Report of the reason(s) for the delay in correcting the inoperability is required per ODCM Section lO.l.

Response: Since the requirements of ODCM Table 3.1.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no response is required.

D-1

APPENDIXE

. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirement: The radiological environmental monitoring program is conducted in accordance with ODCM Control 3/4.5.1. With milk samples no longer available from one or more of the sample locations required by ODCM Table 3.5.1, ODCM 10.1 requires the following to be included in the next annual Radioactive Effluent Release Report: (1) identify the cause(s) of the sample(s) no longer being available, (2) identify the new location(s) for obtaining available replacement samples and (3) include revised ODCM figure(s) and table(s) reflecting the new location(s).

Response: Milk and silage collection at the Vern-Mont Farm (TM-20) was discontinued in August 2015 due to the permanently shut down and defueled status of the plant. It is noted that this was not a required sampling station in the ODCM.

F-1

APPENDIXF 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 Response: The Land-Use Census was completed during the third quarter of2015. No locations were identified which yielded a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3 .3. See Table 4C for a listing of nearest residents and milk animals in the site area as determined in the 2015 Land Use Census.

F-2

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

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

G-1

APPENDIXH OFF-SITE DOSE CALCULATION MANUAL Requirement: Technical Specification 6.7.B.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made effective.

Response: No revisions were made to the ODCM during the reporting period.

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H-1

APPENDIX I RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Requirement: ODCM Section 10.4 requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.

Response: There were no licensee-initiated major changes to i:he radioactive waste systems during this reporting period.

I-1

APPENDIXJ ON~SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE Requirement: 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 Release Report if disposals occur during the reporting year. Entergy Nuclear Vermont Yankee will report in the Annual Radioactive Effluent Release Report a list of the radiomI;clides present and the total radioactivity associated with the disposal activities oh the Vermont Yankee site.

Response: There was one on-site disposal spreading of 11,000 gallons of septic waste during October of 2015, and no spreading activities for cooling tower silt or sand/soil type materials. The total radioactivity spread on the 1.9 acres (southern) on-site disposal field from this and previous years was as follows:

Activity from All Past and Current Activity Spread in 2015 Disposals Decayed to 10/20/2015 Radionuclide (Ci) (Ci)

Mn-54 8.00E-11 1.17E-08 Co-60 2.43E-09 9.67E-06 Zn-65 2.68E-10 3.67E-09 Cs-134 O.OOE+OO 6.68E-10

. Cs-137 l.lOE-10 7.50E-05 The maximum organ dose from all past and current spreading operations totaled l.09E-01 mrem/year. This calculated value is within the 1 mrem/year limit applied during the period of operational control of the site. The projected hypothetical "intruder" dose for the period following the loss of operational control of the site area, due to all spreading operations to-date, is 2.08E-01 mrem/year versus a 5 mrem/year dose limit. The "intruder dose" period begins on the date that the plant operating license expires, March 21, 2032.

J-1

Entergy Nuclear Vermont Yankee, LLC

'/ Vermont Yankee

~Entergy 320 Governor Hunt Rd.

Vernon, VT 05354 (802) 257-7711 Coley C. Chappell Manager, Design and Programs BVY 16-020 May 12, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

SUBJECT:

2015 Radioactive Effluent Release Report Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28

Dear Sir or Madam,

In accordance with Vermont Yankee (VY) Technical Specifications (TS) 6.6.D, enclosed is a copy 'of the annual 2015 Radioactive Effluent Release Report.

In addition, VY TS 6.7.B requires reporting of changes to the Off-Site Dose Calculation Manual (ODCM). There were no changes made to the ODCM during 2015 as noted in Appendix H of the subject report.

There are no new regulatory commitments being made in this submittal.

Should you have any questions or require additional information concerning this submittal, please contact me at (802) 451-3374.

Sincerely, t~Mw~

[CCC/TBS]

Enclosure:

Radioactive Effluent Release Report for 2015 cc listing (next page) cc: Mr. Daniel Dorman, Region 1 Administrator

BVY 16-020 I Page 2 of 2 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Mr. Jack D. Parrott, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop T-8F5 11555 Rockville Pike

.Rockville, MD 20852-2378 Mr. Christopher Recchia, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, VT 05620 Vermont Department of Health Division of Radiological Health Attn: Bill Irwin P.O. Box 70 Burlington, VT 05402-0070 Massachusetts Department of Public Health Jack Priest, Director Radiation Control Program 529 Main Street, Suite 1M2A Charlestown, MA 02129 Augustinus Ong, Administrator Department of Health and Human Services Radiological Health Section 29 Hazen Drive Concord, NH 03301-6504 \.*

John Giarrusso Nuclear Preparedness and Planning Manager 400 Worcester Road Framingham, MA 01702 Tony Honnellio Radiation Program Manager, Health and Safety Coordinator EPA, New England, Region 1 5 Post Office Square, Suite 100 (OSRR02-2).

Boston, Massachusetts 02109

RADIOACTIVE EFFLUENT RELEASE REPORT FOR2015 INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN Entergy Nuclear Vermont Yankee, LLC Docket No. 50-271 License No. DPR-28 Prepared by:_,.,,,,..,Y'--"""--L,,.-~~~"""'-""'~=_,,___ _ _ _ ____;/ 6 Is'/ I to

, Clvisol)* Scientist, AREVA, Inc. Date

--b~~~-'--~~~1~1$/td& Date Revie-ived by:_~----.......,....,~--+-+--------*ut:f0 Approved for Distribution:_-1!--L-=:::i~~r==::::::::__ _ _ _ _ _ ___!/ ~kb(?

Date

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TABLE OF CONTENTS

1.0 INTRODUCTION

.............................................................................................................................................. 1 2.0 METEOROLOGICAL DATA ............................................................................................................................ 2 3.0 DOSE ASSESSMENT .................................................................................. :.................................................... 3 3.1 DOSES FROM LIQUID EFFLUENTS ............................... : ................................................................................... 3 3.2 DOSES FROM NOBLE GASES ........................................................................................................................... 4 3 .3 DOSES FROM IODINE-131, IODINE-133, TRITIUM, CARBON-14, AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS .................................................................................. 4 3.4 WHOLE BODY DOSES IN UNRESTRICTED AREAS FROM DIRECT RADIATION ................................................. 5 3 .5 DOSES FROM ON-SITE DISPOSAL OF SEPTIC WASTE, COOLING TOWER SILT AND SOIL ............................... 6 3.6 ON-SITE RECREATIONAL ACTIVITIES ............................................................................................................. 6 REFERENCES .......................................................................................................................................................... 7 APPENDIX A -SUPPLEMENTAL INFORMATION ......................................................................................... A-1*

APPENDIX B -LIQUID HOLDUP TANKS ........................................................................................................ B-1 APPENDIX C -RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ............................................................................................................... C-1 APPENDIX D -RADIOACTIVE GASEOUS EFFLUENT MONITORING '

INSTRUMENTATION ................................................................................................................ D-1 APPENDIX E-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..................................... E-1 APPENDIX F - LAND USE CENSUS .................................................................................................................. F-1 APPENDIX G -PROCESS CONTROL PROGRAM ............................................................................................ G-1 APPENDIX H -OFF-SITE DOSE CALCULATION MANUAL ......................................................................... H-1 APPENDIX I - RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS ............................................................................................................ I-1 APPENDIX J - ON-SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE ............................................................ J-1 11

LIST OF TABLES IA Gaseous Effluents - Summation of All Releases 8 IB Gaseous Effluents - Elevated Releases 10 IC Gaseous Effluents - Ground Level Releases I2 lD Gaseous Effluents - Non-routine Releases 14 2A Liquid Effluents - Summation of All Releases 15 2B Liquid Effluents - Routine Releases 17 3 Solid Waste and Irradiated Fuel Shipments 19 4A Maximum Quarterly and Annual Off-Site Doses from Direct Radiation and 21 Liquid and Gaseous Effluents for 2015 (10CFR50, Appendix I) 4B Maximum Annual Off-Site Doses from Direct Radiation and 22 and Liquid and Gaseous Effluents for 2015 (40CFR190) 4C Receptor Locations 23 4D Usage Factors for Environmental Pathways 24 4E Environmental Parameters for Gaseous 'Effluents 25 4F Environmental Parameters for Liquid Releases (Tritium) Via Groundwater 27 5A to 5H Annual (2015) Summary of Lower Level Joint Frequency Distribution 28-35 6A to 6H Annual (2015) Summary of Upper Level Joint Frequency Distribution 36-43 111

Radiological Effluent Release Report for 2015

[Including Annual Radiological Impact on Man]

Entergy Nuclear Vermont Yankee, LLC

1.0 INTRODUCTION

Tables 1 through 3 list the recorded radioactive liquid and gaseous effluents and solid waste shipments for the year, 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 the year 2015 in response to the ALARA objectives of 10 CFR Part 50, Appendix I. Also included in Table 4A is the estimate of direct dose from fixed station sources along the limiting west site boundary line. Tables SA through 6H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 2015. Radioactive effluents reported in Tables 1and2 were used to determine the dose to the maximum exposed individual for 2015.

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.l (Reference 1). These dose estimates were made using a "Method II" analysis as described in the ODCM, and as reported in Tables 4A and 4B ofthis report. A "Method II" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 2) and actual measured meteorological data recorded concurrently with the quarterly reporting period.

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 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," is also required to be included in this report ifthe 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 Part 190.

All calculated dose estimates for members of the public at the site boundary or beyond for the 2015 annual reporting period are below the dose criteria of 10 CFR Part 50, Appendix I, and 40 CFR Part 190.

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

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2.0 METEOROLOGICAL DATA Meteorological data were collected in 2015 from the site's 300-foot meteorological tower located approximately 2,200 feet northwest of the reactor building, and about 1,400 feet from the plant stack. The 300-foot tower is approximately the same height as the primary plant stack (308 feet) and is designed to meet the requirements of Safety Guide 23 (Reference 3) for meteorological monitoring. In mid-2009, the tower was moved to a location approximately 200 feet northwest of the original location.

r.JQ and D/Q values for elevated releases were derived for all receptor points from the site meteorological record for each quarter using a straight-line airflow model. All dispersion factors have been calculated employing appropriate source configuration considerations, as described in Regulatory Guide 1.111 (Reference 4). A source depletion model as described in "Meteorology and Atomic Energy - 1968" (Reference 5) was used to generate deposition factors, assuming a constant deposition velocity of 0. 01 m/sec for all stack (elevated) releases. Changes in terrain elevations in the site environment were also factored into the meteorological models as appropriate.

In the event of a ground-level release, r.JQ and D/Q values would be derived for the site boundary receptor points from the site meteorological record for each quarter using a straight-line airflow model.

During this reporting period, there were no ground-level releases and therefore no associated dose impact.

Table 4C lists the distanc.es from the plant stack to the nearest site boundary, resident, and milk animal in each of the 16 principle compass directions as determined during the 2015 land use census. These locations were used in the calculation of atmospheric dispersion factors. The meteorological model was also executed for each calendar quarter to determine the location of the predicted maximum ground level air concentration from elevated releases from the plant's primary vent stack. These locations were included in the assessment of effluent doses along with identified points of interest from the annual land use census. "

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3.0 DOSE ASSESSMENT 3.1 Doses From Liguid 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 Part 50, Appendix I. By implementing the requirements of 10 CFR Part 50, Appendix I, ODCM 3/4.2.2 assures that the release ofradioactive material in liquid effluents will be kept "as low as is*

reasonably achievable." . *', *

  • There were no recorded routine liquid radioactive waste discharges during the report period.

However, an abnormal release to the Connecticut River is postulated due to a past leak in an underground pipe tunnel that runs between the Advanced Offgas (AOG) system building and other plant buildings which allowed accumulated piping system leakage to enter the subsurface groundwater adjacent to the plant structures. The existence of the leak was first recognized in January 2010, when a river shoreline Protected Area Boundary monitoring well sample was reported to have detectable tritium. The addition of other monitoring wells and subsequent analysis defined the extent of the affected groundwater plume moving toward the.river and helped locate the source of the leak, which was stopped in February 2010.

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Estimates of tritium-contaminated ground water released from the site are based on Protected Area Boundary monitoring well data collected throughout 2015, and hydrological modeling of ground water movement in the affected zone impacted by the pipe tunnel leak. 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 2015 was generated and reported in Table 2A.

Forthe projected ground water flow into the Connecticut River in 2015, the dose impact to the maximum exposed individual (MEI) assumed the following exposure pathways: (1) ingestion offish (taken from Vernon Pond), (2) ingestion of vegetables and, fresh leafy produce irrigated by water taken from the river below Vernon Dam, (3) ingestion of milk and meat from animals that were fed irrigated crops and drinking water taken from the river below Vernon Dam, and (4) pota~le water for a hypothetical individual drawing drinking water fed by the river below Vernon Dam. For Vernon Pond (river area adjacent to the plant property), the near shore mixing zone associated with the fish ingestion pathway is conservatively taken as 1% of the minimum recorded monthly river flow (3,107 cfs in September 2015) for dilution. All irrigation exposure pathways for the consumption of food products grown with irrigated water occur below Vernon Dam and assume the lowest 2015 quarterly average growing season river flow value (5394 cfs in the third quarter) for environmental mixing. For the drinking water pathway, river flow mixing is assumed to occur below Vernon Dam and uses the lowest annual quarterly average river flow (5394 cfs in the third quarter) as a conservative estimate ofriver dilution for all four quarters of the year. The dose models are

!aken from Regulatory Guide 1.109 (Reference 2) and use environmental parameters for exposure pathways listed in Tables 4D and 4F. .

The maximum estimated quarterly and annual whole body and organ doses to the limiting age group from liquid releases are reported in Table 4A. These estimated doses are well below the 10 CFR Part 50, Appendix I dose criteria of ODCM 3/4.2.2. Table 4B provides an estimate of the total annual'dose impact (including contribution from liquids) associated with the highest exposed member of the public for demonstration of compliance to the dose standard contained in 40 CFR P~rt 190 for the uranium fuel cycle.

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3.2 Doses From Noble Gases ODCM 3/4.3.2 limits the gamma air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released in gaseous effluents from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I. By implementing these, ODCM 3/4.3.2 assures that the releases ofradioactive noble gases in gaseous effluents will be kept "as low as is reasonably achievable."

Dose estimates due to the release of noble gases to the atmosphere are typically calculated at the site boundary, at the nearest resident in each of the sixteen principal compass directions, at the point of highest off-site ground level air concentration of radioactive materials, and at each of the milk animal locations located within five miles of the plant. For 2015, there were no noble gases detected in effluents released from the plant stack.

3.3 Doses From Iodine-131, Iodine-133, Tritium, Carbon-14, and Radionuclides in Particulate Form with Half-Lives Greater Than 8 Days ODCM 3/4.3.3 limits the organ dose to a member of the public from Iodine-131, Iodine-133, Tritium, Carbon-14, and radionuclides in particulate form with half-lives greater than 8 days (hereafter called "iodines and particulates") 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 iodines and particulates in gaseous effluents will be kept "as low as is reasonably achievable."

During 2015, a single frac tank was used on the Vermont Yankee site to temporarily store (outdoors) tritium-contaminated water extracted from onsite groundwater wells. The quantity of tritium released to the atmosphere through the evaporation of water from this frac tank was estimated, and the dose consequence to the maximally exposed individual was calculated.

Exposure pathways that could exist as a result of the planned (routine) release of iodines and particulates to the atmosphere include external irradiation from activity deposited onto the ground surface, inhalation, and ingestion of vegetables, meat and milk. Dose estimates were made at the site boundary and nearest resident in each of the sixteen principal compass directions, as well as all milk animal locations within five miles of the plant. The nearest resident and milk animals in each sector were identified by the most recent annual land use census as required by ODCM 3/4.5.2 (see Table 4C). Conservatively, a vegetable garden was assumed to exist at each milk animal and nearest resident location. Furthermore, the meat pathway was assumed to exist at each milk cow location since this data category is not part of the annual land use census. Doses were also calculated at the point of maximum ground level air concentration of radioactive materials in gaseous effluents and included the assumption that the inhalation, vegetable garden, and ground plane exposure pathways exist for an individual with a 100 percent occupancy factor.

It is assumed that milk and meat animals are free to graze on open pasture during the second and third quarters with no supplemental feeding. This assumption is conservative since most of the milk animals inventoried in the site vicinity are fed stored feed throughout the entire year with only limited grazing allowed during the growing season. It has also been assumed that only 50 percent of the iodine deposited from gaseous effluent is in elemental form (I2) and is available for uptake (seep. 6, Reference 2).

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During the non-growing season (first and fourth quarters), the milk animals are assumed to receive only stored feed. During the growing season (second and third quarters), all animal feed is assumed to be derived from fresh pasture. Usage factors for gaseous effluents are listed by age group and pathway in Table 4D.

Table 4E provides other dose model parameter assumptions used in the dose assessments.

In June 2009, the NRC issued Revision 2 of Regulatory Guide 1.21 (Reference 6) which introduced the term "principal radionuclide" in a risk-informed or dose context. A radionuclide can be considered a principal radionuclide if it contributes either (1) greater than 1 percent of the 10 CFR Part 50, Appendix I design objective dose for all radionuclides in the type of effluent being c01;1sidered, or (2) greater than 1 percent of the activity of all radionuclides in the type of effluent being considered. In addition to natural production in the environment, Carbon-14 is also produced in nuclear reactors as a function of power output, but at amounts muc11 less than those generated naturally or from past weapons testing. Since the --

time of the e&rlier publication of Regulatory Guide 1.21 (Revision 1) in 1974, commercial nuclear power 1

plants have decreased total radioactive effluents (other than Carbon-14) through improved fuel performance and waste management practices to the point today that Carbon-14 could be considered a principal radionuclide under today's definition. With the plant permanently shut down since December of2014, there was no plant related Carbon-14 production or associated dose impact for 2015.

3.4 Whole Body Doses in Unrestricted Areas From Direct Radiation As opposed to previous years where 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 2015 due to the plant being permanently shut down.

The other fixed sources of direct and scatter radiation to the site boundary are the Independent Spent Fuel Storage Installation (ISFSI), the low level radioactive materials stored in the North Warehouse, the Low Level Waste Storage Pad Facility (no radioactive_ waste material stored on the pad in 2015), and old turbine rotors and casings in the Turbine Storage Facility. The annual dose is based on dose rate measurements in these storage facilities and is projected to impact the same most restrictive site boundary dose location. ,J The estimated direct radiation dose from all major sources combined for the most limiting site boundary location is listed in Table 4A. These site boundary doses assume a 100 percent occupancy factor, and take no credit for the shielding effect of any residential structure.

Table 4B lists the combination of direct radiation doses 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 Part 190. For 2015, this annual dose was below the 25 mrem total body and organ limit, as well as the 75 mrem thyroid limit, of 40 CFR Part 190.

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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/soil 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 mrern/year to the whole body and any organ. After the period associated with Vermont Yankee operational control, the dose to the inadvertent intruder is to be limited to 5 mrern/year. The projected dose from on-site disposals of septic waste, cooling tower silt, and sand/soil mixes is given in Appendix J of this report. ..

The dose limits applicable to the on-site spreading of materials were met for the single spreading of septic waste in 2015, based on the combined dose from this spreading and all past spreadings.

3 .6 On-Site Recreational Activities During 2015, no access to the on-site boat launching ramp located north of the intake structure was permitted for employees, their families, and guests. As such, there was no associated dose impact to members of the public.

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REFERENCES

1. Off-site Dose Calculation Manual (ODCM), Revision 35, Entergy Nuclear Vermont Yankee, LLC, dated October 9, 2014.
2. Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 1.0 CFR Part 50, Appendix I," U.S.

Nuclear Rygulatory Commission, Office of Standards Development, Revision 1, October 1977.

3. Safety Guide 1.23, "Onsite Meteorological Programs," U.S. Atomic Energy Commission, February 17, 1972.
4. Regulatory Guide 1.~-11, "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.

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TABLElA Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - Summation of All Releases Quarter Quarter Est. Total Unit 1 2 Error,%

A. Fission and Activation Gases

l. Total release Ci ND ND +/-2.30E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent ofODCM limit (1)  % ND ND NIA B. Iodines
l. Total Iodine Ci ND ND +/-l.80E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent of ODCM limit (3)  % (3) (3) NIA
c. Particulates
l. Particulates with T-112>8 days Ci ND ND +/-l.80E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent of ODCM limit (3)  % (3} (3) NIA
4. Gross alpha radioactivity Ci ND ND NIA D. Tritium (4)
l. Total release Ci 7.34E-02 7.09E-02 +/-l.80E+Ol
2. Average release rate for period µCi/sec 9.63E-03 9.22E-03 NIA
3. Percent ofODCM limit (3)  % (3) (3) NIA E. Carbon-14
l. Total release Ci ND ND NIA
2. Percent of ODCM limit (2)  % 4.99E-04 4.53E-04 NIA ND =Not Detected, or in the case of C-14, no power operations in 2015 leads to a zero estimate of C-14 production/release.

(1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results.

(2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form.

Percentage of ODCM limit calculated using Method I dose results. '

(3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E.

(4) Tritium released through evaporation from the onsite frac tank is included in these totals.

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TABLE IA (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - Summation of All Releases Quarter Quarter Est. Total Unit 3 4 Error,%

A. Fission and Activation Gases

1. Total release Ci ND ND +/-2.30E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent ofODCM limit (1)  % ND ND NIA B. Iodines
1. Total Iodine Ci ND ND +/-1.80E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent of ODCM limit (3)  % (3) (3) NIA C. Particulates
1. Particulates with T-1/2>8 days Ci ND ND +/-1.80E+Ol
2. Average release rate for period µCi/sec ND ND NIA
3. Percent of ODCM limit (3)  % (3) (3) NIA
4. Gross alpha radioactivity Ci ND ND NIA D. Tritium (4)
1. Total release Ci l.14E-01 7.87E-02 +/-1.80E+Ol
2. Average release rate for period µCi/sec 1.46E-02 2.78E-02 NIA
3. Percent ofODCM limit (3)  % (3) (3) NIA E. Carbon-14
1. Total release Ci ND ND NIA
2. Percent ofODCM limit (2)  % 7.29E-04 5.03E-04 NIA ND= Not Detected, or in the case ofC-14, no power operations in 2015 leads to a zero estimate ofC-14 production/release.

(1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage ofODCM limit calculated using Method I dose results.

(2) ODCM Control 3.3.3. for dose from 1-131, 1-133, Tritium, Carbon-14 and radionuclides in particulate form.

Percentage of ODCM limit calculated using Method I dose results. '

(3) Per ODCM Control 3.3.3, the dose contribution from Tritium, Iodines, and particulates are included with Carbon-14 in Part E.

(4) Tritium released through evaporation from the onsite frac tank is included in these totals.

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TABLEIB Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Elevated Releases Continuous Mode Batch Mode (1)

Quarter Quarter Nuclides Released Units 1 2 1 2

1. Fission Gases Argon-41 Ci ND ND Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-133m Ci ND ND Xenon-135 Ci ND ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Unidentified Ci ND ND Total for Period Ci ND ND (1) (1)
2. Iodines lodine-131 Ci ND ND lodine-133 Ci ND ND lodine-135 Ci ND ND Total for Period Ci ND ND (1) (1)
3. Particulates Strontium-89 Ci ND ND I

Strontium-90 Ci ND ND Cesium-134 Ci NP ND Cesium-137 Ci ND ND Barium-Lanthanum-140 Ci ND ND Manganese-54 Ci ND ND Chromium-51 Ci ND ND Cobalt-57 Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci ND ND Cerium-141 Ci ND ND Zinc-65 Ci ND ND Total for Period Ci ND ND (1) (1)

ND Not Detected at the plant stack (1) There were no batch mode gaseous releases for this reporting period.

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TABLElB (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Elevated Releases Continuous Mode . Batch Mode (1)

Quarter Quarter Nuclides Released Units 3 4. 3 4

1. Fission Gases (

Krypton-85 Ci ND ND Krypton-85m Ci ND ND Krypton-87 Ci ND ND Krypton-88 Ci ND ND Xenon-133 Ci ND ND Xenon-133m Ci ND ND Xenon-135 Ci ND .ND Xenon-135m Ci ND ND Xenon-138 Ci ND ND Unidentified Ci ND ND Total for Period Ci ND ND (1) ' (1)

2. Iodines Iodine-131 Ci ND ND Iodine-133 Ci ND ND Iodine-135 Ci ND ND Total for Period Ci ND ND (1) (1)
3. Particulates Strontium-89 Ci ND ND Strontium-90 Ci ND ND Cesium-134 Ci ND ND Cesium-137 Ci ND ND Barium-Lanthanum-140 Ci ND ND Manganese-54 Ci ND ND Chromium Ci ND ND Cobalt-58 Ci ND ND Cobalt-60 Ci ND ND Cerium-141 Ci ND ND Cerium-144 Ci ND ND Zinc-65 Ci ND ND Total for Period Ci ND ND (1) (1)

ND Not Detected at the Plant Stack (1) There were no batch mode gaseous releases for this reporting period.

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TABLElC Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents-(Routine) Ground Level Releases <2)

Continuous Mode Batch Mode Quarter Quarter Nuclides Released Units 1 (1) 2 (1) 1 (1) 2 (1)

1. Fission Gases Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci

.Krypton-88 Ci Xenon-133 Ci Xenon-1.35 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci

2. Iodines lodine-131 Ci Iodine-133 Ci Iodine-I 35 Ci Total for Period Ci
3. Particulates Strontium-89 Ci Strontium-90 Ci

_ Cesium-134 Ci Cesium- 137 Ci Barium-Lanthanum-140 Ci Mimganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci Iron-55 Ci Total for Period Ci (1) There were no routine ground level gaseous releases for this reporting period.

(2) No radioactively contaminated\used oil was burned during 2015.

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TABLElC (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents - (Routine) Ground Level Releases(2)

Continuous Mode Batch Mode Quarter Quarter Nuclides Released Units 3 (I) 4 (I) 3 (I) 4 (1)

1. Fission Gases Ktypton-85 Ci Krvoton-85m Ci Krvoton-87 Ci Krvoton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci '
2. Iodines lodine-131 Ci lodine-133 Ci lodine-135 Ci Total for Period Ci
3. Particulates Strontium-89 Ci Strontium-90 Ci Cesium- 134 Ci Cesium-137 Ci Barium-Lanthanum- 140 Ci Manganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci Iron-55 CI Total for Period Ci (1) There were no ground level gaseous releases for this reporting period.

(2) No radioactively contaminated used oil was burned during 2015.

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TABLElD Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Gaseous Effluents -Non-routine Releases Quarter Quarter Nuclides Released Units 1(1) 2(1) 3(1) 4(1)

1. Fission Gases Krypton-85 Ci Krypton-85m Ci Krypton-87 " Ci Krypton-88 Ci Xenon-133 Ci Xenon-135 Ci Xenon-135m Ci Xenon-138 Ci Unidentified Ci Total for Period Ci
2. Iodines lodine-131 Ci

. lodine-133 Ci Iodine-I 35 Ci Total for Period Ci

3. ' Particulates Strontium-89 Ci )

Strontium-90 Ci Cesium-134 Ci Cesium- 137 Ci

\ Barium-Lanthanum-140 Ci Manganese-54 Ci Chromium-51 Ci Cobalt-58 Ci Cobalt-60 Ci Cerium-141 Ci Zinc-65 Ci lron-55 Cl Total for Period Ci (1) There were no non-routine ground level gaseous releases for this reporting period.

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TABLE2A Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Summation of All Releases Est. Total Units Quarter 1 Quarter 2 Error,%

A. Fission and Activation Products

1. Total Release (not includina tritium, aases, alpha) Ci ND ND N/A I
2. Average Diluted Concentration Durina Period uCi/ml ND ND
3. Percent of Aoolicable Limit (1)  % ND ND
8. Tritium
1. Total Release Ci 8.85E-03 9.05E-03 +/-2.00E+01 I
2.
  • Averaae Diluted Concentration Durina Period uCi/ml 1.67E-06 1.66E-06
3. Percent of Applicable Limit (1)  % 5.90E-05 6.03E-05 C. Dissolved and Entrained Gases
1. Total Release Ci ND ND N/A I
2. Averaae Diluted Concentration Durina Period µCi/ml ND ND
3. Percent of Aoolicable Limit  % ND ND D. Gross Al ha Radioactivit
1. Total Release Ci ND ND N/A E. Volume of Waste Release rior to dilution Liters N/A I F. Volume of Dilution Water Used During Period Liters 3.89E+06 3.89E+06 (3)

ND Not detected in liquid effluents.

(1) 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 abnorr:nal leakage of tritiated plant water into the underground environment.

The percent of the concentration limits specified in Appendix B to 1OCFR20.1001 - 20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.

(2) Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015.

(3) Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.

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TABLE2A (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Summation of All Releases Est. Total Units Quarter 3 Quarter 4 Error,%

A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) Ci ND ND N/A I
2. Average Diluted Concentration Durina Period µCi/ml ND ND
3. Percent of Aoolicable Limit (1)  % ND ND B. Tritium
1. Total Release Ci 8.02E-03 7.50E-03 +/-2.00E+01 I
2. Average Diluted Concentration During Period µCi/ml 1.46E-06 1.36E-06
3. Percent of Aonlicable Limit (1)  % 5.35E-05 5.00E-05 C. Dissolved and Entrained Gases
1. Total Release Ci ND ND N/A I
2. Average Diluted Concentration Durina Period uCi/ml ND ND
3. Percent of Aoolicable Limit  % ND ND D. Gross Al ha Radioactivi
1. Total Release Ci ND ND N/A E. Volume of Waste Release rior to dilution Liters N/A l F. Volume of Dilution Water Used During Period Liters 3.89E+06 3.89E+06 (3)

ND Not detected in liquid effluents.

(1) 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.

The percent of the concentration limits specified in Appendix B to 1OCFR20.1001 - 20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 0.17%, 0.17%, 0.15%, and 0.14% for the first, second, third, and fourth quarters, respectively.

(2) Leakage of contaminated plant water to subsurface areas was stopped in February 2010. The release of contaminated ground water to the Connecticut River is based on site boundary monitoring well data collected during 2015.

(3) Dilution due to groundwater flow through the affected subsurface plume area toward the Connecticut River was estimated to be 7.83 gpm (or 3.89E+06 liters per quarter) during 2015. An Estimated Total Error is not applicable.

16

TABLE2B Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Routine Releases Continuous Mode Batch Mode I Nuclides Released Units Quarter 1 I Quarter 2 Quarter 1 I Quarter 2 Strontium-89 Ci - - - -

Strontium-90 Ci - - - -

Cesium-134 Ci - - - -

Cesium-137 Ci - - - -

lodine-131 Ci - - - -

Cobalt-58 Ci - - - -

Cobalt-60 Ci - - - -

lron-59 Ci - - - -

Zinc-6.5 Ci - - - -

Manganese-54 Ci - - - -

Zirconium-Niobium-95 Ci - - - -

Molvbdenum-99 Ci - - - -

Technetium-99 Ci - - - -

Barium-Lanthanum-140 Ci - - - -

Cerium-141 Other (specify) Ci Ci Ci Unidentified I Ci I Total for Period (above) Ci Xe-133 Ci Xe-135 Ci ND Not detected in liquid effluents.

Dash indicates no release of this type.

17

TABLE2B (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Liquid Effluents - Routine Releases Continuous Mode Batch Mode I Nuclides Released Units Quarter 3 I Quarter 4 Quarter 3 I Quarter 4 Strontium-89 Ci - - - -

Strontium-90 Ci - - - -

Cesium-134 Ci - - - -

Cesium-137 Ci - - - -

lodine-131 Ci - - - -

Cobalt-58 Ci - - - -

Cobalt-60 Ci - - - -

lron-59 Ci - - - -

Zinc-65 Ci - - - -

Manganese-54 Ci - - - -

2irconium-Niobium-95 Ci - - - -

  • Molybdenum-99 Ci - - - -

Technetium-99 Ci - - - -

Barium-Lanthanum-140 Ci - - - -

Cerium-141 Other (specify) Ci Ci Ci Unidentified I Ci I Total for Period (above) Ci Xe-133 Ci Xe-135 Ci ND Not detected in liquid effluents.

Dash indicates no release of this type.

18

TABLE3 Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Solid Waste and Irradiated Fuel Shipments Tabl..l fntersv Nucl*u vennontVanb:e Eftluentw WomD/spo,otAm111ot ~

' f/ntonds-a-/!irZOJS Sol/d Wart~.o*dlrrodlottdFudSlr/pmonrs A. t,o114W>illi Slllol><d.OlMlto foto-orOl....,.llo** lm.u....tlucl}

a ~

m! No..

Cl Ncl!lt ml H. ..

.Q NC!!!O N/A ml No .. NA Ct Horic- NIA

    • 3 o.&.iE*OI tlS!I cf 5.7Sr*02 ti$>>

mJ Nnne fl*

Q. Nan* NA mJ *UOfUJS US!I Cl 1.00[*cS >JS!I

  • ! .

J:Ji' *!r* (;'~i;,~~M:;~~--:'.ii~ij,t>'*;, ~*,;i..~iw~~~ ...

_ *- _. .....

Nut!'llt.& PH<<:ttittt* Nlldld* ltrci:ntfll NutUitl' P.af'C'ttl.tCU j"

-

tultM-t4 O.U'4 c~~ud'MI U!J<. (Dh!i*liQ

~'.\S LM'll C,o:b,.11>60 5131-K

....... Cc1wmU1*

.......

!!<

Colml*M Cftium-U7 .. .,.,,,. °""'""'""I tl!Ullrit-ll1 u~

OJm Hldri..i ...... "

ltoA<H .71.1$Ul*

u ...

-

OJ!"

.....,__124 'U"'

11.J&K.

.....................

H2tld*'1

$.-

..,.,.

,,, .

,.

  • _...__114 A:nrlmc--Ja ...~-*

....... 9..1'1!1.

ESllCD lN 1 ffll<l< W1 1-~~*--~--i~~~~.j-~...!!.~~i--.....i.T~N~ ..i.,_...f.~~~~~k-~~!!f~~~-

@ij.*{4.lb:~t:lll~

OC,O.a&~.vCf~~~m.

'n~Yh:t~l;::tml~<'A$,;wtWh~

"H"-frn~rr$£ii;~~ *

<iOC*G~IJ!l~,tnQ:mtlh" 19

TABLE 3 (continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2015 Solid Waste and Irradiated Fuel Shipments Ta~lt'-3 EnleJIY NudearVennont Yanlcee E/ffllflll and W-Olsposc/ An1"Ull Rqiott Jlrlnl oad l'o<mh 4uoJfen:fur 2015 So/Id Wmt., and lrrodi'med Fur:UhlJ11Mflfl II. 5olldW..1~Sl!l,ppodOlf*Slt*lor°",'i'I"' Dhpoool lnotflmll>IO<I l'ucQ J, T~otwa:ne

1. < ,;\S!ii\ltdl1oolti1.:?ii£w:c,,, <'<:,"!121"*" ~:r10~.t\iiB&Xi /i1k1T0inilt..&ilP

~fo:ol !!""rf<l""'!'- .... ml 1.45!.0I t%SS a 3001101 !JS!i.

PIYC~..au~.<<lUllElfllftll fir. ml Ncnc NIA Cl Hn** N/A c.ln*~~l\.l;f!IUd11c11:b.tU mJ II/A 0 """"

N°"' N/A

°'""'"" ....

,Plone mJ* NIA 4

Q N/A

.a ~rnm.fll"~"k ml NOl>O Ii/A C1 Nooe N/A b Dtr~~WW.-hft.nJ.rff, ml l.BOfiOJ tis5 0 9.JU*Ol m" c tt1.-t~~nznk.f:tlnllOifH~,d' mJ No.,. NIA Cl N-411e 11/11 fif*Olb* ta.g ml 2.JSE!OI us" 0 5.(19£.QS i2SK
!. &11...,* cl Molor Nutlldc tomi>MlllO ISV TYl>O of W11u.1.

Nudlde P:1rc"ntUl.. N'iKUdo 1'1m:ootf11 NU<liile Por<mrlll .,,,_ Po1m11U1 C>rbon 14 :um UJlil toti-.i 10.s'!K Cobol<H D.9.

Ccb1tl*SI Cul:ri)fl60 nn" """' O:Wm-Sl? %Q.ft$10 Collall"O Ji.ll" Chlomlum-S1 1.)211 Mi~...- 5111' Citl.it1:t1*U7 J.Ollt. C0Jr;m.U1 ll20ll Z>titH .., .l"'

"°"'.SS IUSK .,,,.n ,974t'o MIM~54 l.11'1 troon-!9 IU>>I Nldd-63 ll.12" . . . . . . .H . .54 J.IOK Zllic.*6S 1a.uw. Mo&lu~!JJ um H!~J 1,28%

Anbm01Pt*l2* 0.2""

Antt-...JJ.S a*1s~

  • trrte..£5 ......

(11 *ncfudrs (ITl!y1bDH" nud?dd thi1 .11egruitt th.an u.1\1of1M totaJ Kf1WV x Truck Glt*Qi~t<Rwd U:-0,. 9't-~t Ctte\ 0pt"O-l1ont.

WCS-.WHteCentr<<r..r.tr.tw.ius SS*ft1b:fn$.ilttl1~

G'OC. ~ G1tt1t"f~ ~ Ctwt-tlit1tt 20

TABLE4A Entergy Nuclear Vermont Yankee Maximum* Quarterly and Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 (10CFR50, Appendix I)

Dose (mrem)(a) 3rd Source Year(b)

Quarter Total Body Dose 9.80E-07 l.OOE-06 8.88E-07 8.31E-07 3.70E-06 Footnotes (c) (c) (c) (c) (c)

Organ Dose 9.80E-07 l.OOE-06 8.88E-07 8.31E-07 3.70E-06 Footnotes (c) (c) (c) (c) (c) l.64E-05 4.24E-05 (g) (t) (t)

Beta Air (mrad)

Footnotes (d) (d) (d) (d)

Gamma Air (mrad)

Footnotes 0.72

  • "Maximum" means the largest fraction of the corresponding 10CFR50, Appendix I dose design objective.

(a) The lettered footnotes indicate the age group, organ, and location of the dose receptor, where appropriate.

(b) The yearly dose is the sum of the doses for each quarter, or a full annual assessment.

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

(d) There were no noble gas releases in this quarter.

(e) Maximum direct dose point located on the old west site boundary, approximately 208 meters from the Turbine Building (per ODCM, Rev. 35, Sect. 6.11.1).

(f) The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location WNW, 2400 meters from the stack.

(g) The critical age group/organ for the MEI is the Child/all organs (except Bone), at a location NW, 2900 meters from the stack.

21

TABLE4B Entergy Nuclear Vermont Yankee Maximum* Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2015 (40CFR190)

Total Body Maximum Organ Thyroid Pathway (mrem) (mrem) (mrem)

Direct External (a) (b) 2.88 2.88 2.88 Liquids (c) 3.70E-06 3.70E-06 3.70E-06 Gases (c)' l.07E-04 l.07E-04 l.07E-04 Annual Total (d) 2.88 2.88 2.88

  • 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 I00%)

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 I. I 09 (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 using the current ODCM methodology 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.

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

(d) Annual dose 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.

22

TABLE4C Receptor Locations Entergy Nuclear Vermont Yankee Nearest Mille Sector Site Boundary (I) Nearest Resident<2l Animal <2l (meters) (meters) (meters)

N 400 1400 --

NNE 350 1384. 5520 (cows)

NE 350 1255 --

ENE 400 966 --

E 500 933 --

ESE 700 1915

\

--

SE 750 1963 3600 (cows)

SSE 850 2044 --

s 385 644 --

SSW 300 451 --

SW 250 418 --

WSW 250 451 9730 (cows) w 300 628 820 (cows)

WNW 400 1062 --

NW 550 2253 --

NNW 550 1738 --

(1) Site boundary locations taken from Table 6.10.2 of the ODCM.

(2) The location(s) given are based on information from the Vermont Yankee 2015 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.

  • 23

TABLE4D Usage Factors for Environmental Pathways Entergy Nuclear Vermont Yankee*

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

(I/yr)

Adult 21 730 520 64 310 110 8,000 Teen 16 510 630 42 400 65 8,000 Child 6.9 510 520 26 330 41 3,700 Infant 0 330 0 0 330 0 1,400

24

TABLE4E Environmental Parameters for Gaseous Effluents

  • Entergy Nuclear Vermont Yankee I Vegetables I Cow Milk Goat Milk I Meat I Variable I . Stored I Leafy I Pasture Stored Pasture Stored I Pasture I Stored I

Agricultural Productivity YV (kg/m2) 2 2 0.70 2 0.70 2 0.70 2 p 240 240 240 240 240 240 240 240 Soil Surface Density (kiz/m2)

~

T Transport Time to User (hrs) -- -- 48 48 48 48 480 480 TB Soil Exposure Time(a)(hrs) 131,400 131,400 131,400 131,400 131,400 131,400 131,400 131,400 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/dav) -- -M 50 so 6 6 "' 50 50 FP Fraction of Year on Pasture -- -- (b) -- (b) -- (b) --

FS Fraction Pasture Feed When on Pasture(c)

-- -- 1 -- 1 -- 1 --

Note: Footnotes on following page.

25

TABLE 4E (Continued)

Environmental Parameters for Gaseous Effluents Entergy Nuclear Vermont Yankee I Vegetables I Cow Milk Goat Milk Meat Variable Stored Leafy Pasture Stored Stor--' n-ctnre Stored II FG Fraction of Stored Vegetables 0.76 -- -- -- -- -- -- --

Grown in Garden FL Fraction of Leafy Vegetables -- 1.0 -- -- -- -- -- --

Grown in Garden FI Fraction Elemental Iodine = 0.5 -- -- -- -- -- -- -- --

H Absolute Humidity= 5.6Cd) -- -- -- -- -- -- I -- --

  • From VY ODCM, Table 6.9.l (Reference 1).

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

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

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

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

Reference:

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

26

TABLE4F Environmental Parameters for Liquid Releases (Tritium) Via Groundwater Entergy Nuclear Vermont Yankee Variable Potable Water Aquatic Food Stored Veg. Leafy Veg. Meat Cow Milk Name (Units)

~

Mixing Ratio 3.23E-06 5.62E-04 3.23E-06 3.23E-06 3.23E-06 3.23E-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

,-

27

TABLE5A VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT) = 1.15 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 (1) 4.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 4.00 (2) .05 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 C-3 2 0 1 1 6 3 2 0 0 0 0 0 0 0 0 4 0 19 (1) 2.00 .00 1. 00 1.00 6.00 3.00 2.00 .00 .00 .00 .00 .00 .00 .00 .00 4.00 .00 19.00 (2) .02 .00 .01 .01 .07 .03 .02 .00 .00 .00 .00 .00 . 00 .00 .00 .05 .00 .22 .

4-7 1 1 0 5 18 14 3 3 1 0 2 0 1 0 2 3 0 54 (1) 1. 00 1. 00 .00 5.00 18.00 14.00 3.00 3.*00 1. 00 .00 2.00 .00 1. 00 .00 2.00 3.00 .00 54.00 (2) .01 .01 .00 .06 .21 .16 .03 .03 .01 .00 .02 .00 .01 .00 . 02 .03 .00 . 62 8-12 0 1 0 0 0 8 5 3 1 0 0 1 0 0 0 3 0 22 (1) .00 1. 00 .00 .00 .00 8.00 5.00 3.00 1. 00 .00 .00 1. 00 .00 .00 .00 3.00 .00 22.00 (2) .00 .01 .00 .00 .00 .09 .06 .03 .01 .00 .00 .01 .00 .00 .00 .03 .00 .25 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1. 00 .00 .00 .00 1. 00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 . .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .,00 .00 .00 .00 .00 .. 00 .00 .00 .00 .oo .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 7 2 1 6 24 25 10 6 2 0 2 1 1 1 2 10 0 100 (1) 7.00 2.00 1. 00 6.00 24.00 25.00 10.00 6.00 2.00 .00 2.00 1.00 1. 00 1. 00 2.00 10.00 .00 100.00 (2) .08 .02 .01 .07 .28 .29 .. 11 .07 .02 .00 .02 .01 .01 .01 .02 .11 .00 1.15 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 28

TABLE SB VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT) = 2.05 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 4 5 5 2 1 3 0 2 1 0 0 0 0 2 0 2 0 27 (1) 2.25 2.81 2.81 1.12 .56 1. 69 .00 1.12 .56 .00 .00 .00 .00 1.12 .00 1.12 .00 15.17 (2) .05 .06 .06 .02 .01 .03 .00 .02 .01 .00 .00 .00 .00 .02 .00 .02 .00 .31 4-7 10 2 3 6 19 18 11 15 5 1 0 0 0 1 1 4 0 96 (1) 5. 62 1.12 1. 69 3.37 10.67 10.11 6.18 8.43 2.81 .56 .00 .00 .00 .56 .56 2.25 .00 53.93 (2) .11 .02 .03 .07 .22 .21 .13 .17 .06 .01 .00 .00 .00 .01 .01 .05 .00 1.10 8-12 2 1 0 0 0 2 4 17 8 0 0 0 2 2 2 5 0 45 (1) 1.12 .56 .00 .00 .00 1.12 2.25 9.55 4.49 .00 .00 .00 1.12 1.12 1.12 2.81 .00 25.28 (2) .02 .01 .00 .00 .00 .02 .05 .20 .09 .00 .00 .00 .02 .02 . 02 .06 .00 .52 13-18 0 0 0 0 0 0 0 2 2 0 0 0 0 0 0 5 0 9 (1) .00 .00 .00 .00 .00 .00 .00 1.12 1.12 .00 .00 .00 .00 .00 .00 2.81 .00 5.06 (2) .00 .00 .00 .00 .00 .00 .00 . 02 .02 .00 .00 .00 .00 .00 .00 .06 .00 .10 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .56 .00 .00 .56 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .01 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 16 8 8 8 20 23 15 36 16 1 0 0 2 5 4 16 0 178 (1) 8.99 4.49 4.49 4.49 11.24 12.92 8.43 20.22 8.99 .56 .00 .00 1.12 2.81 2.25 8.99 .00 100.00 (2) .18 .09 .09 .09 .23 .26 .17 .41 .18 .01 .00 .00 . 02 .06 .05 .18' .00 2.05 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 29

TABLE5C VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT) = 3.60 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 0 1 0 0 0 5 0 0 0 0 0 0 0 0 0 0 0 6 (1) .00 .32 .00 .00 .00 1. 60 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1. 92 (2) .00 .01 .00 .00 .00 .06 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .07 C-3 6 5 5 5 4 13 7 4 2 0 0 0 0 1 2 0 0 54 (1) 1. 92 1. 60 1. 60 1. 60 1.28 4.15 2.24 1. 28 . 64 .00 .00 .00 .00 .32 . 64 .00 .oo 17.25 (2) .07 .06 .06 .06 .05 .15 .08 .05 .02 .00 .00 .00 .00 .01 .02 .00 .00 . 62 4-7 13 9 4 10 13 18 25 29 7 2 1 0 0 1 9 18 0 159 (1) 4.15 2.88 1. 28 3.19 4.15 5.75 7.99 9.27 2.24 .64 .32 I .00 .00 .32 2.88 5.75 .00 50.80 (2) .15 .10 .05 .11 .15 .21 .29 .33 .08 .02 .01 .00 .00 .01 .10 .21 .00 1. 83 8-12 11 3 2 0 0 2 1 17 19 2 0 0 3 3 6 12 0 81 (1) 3.51 .96 . 64 .00 .00 . 64 .32 5.43 6.07 . 64 .00 -* 00 .96 .96 1. 92 3.83 .00 25.88 (2) .13 .03 .02 .00 .00 .02 .01 .20 .22 .02 .00 .00 ."03 .03 .07 .14 .00 .93 13-18 1 0 0 0 0 0 0 1 1 0 0 0 1 0 3 6 0 13 (1) .32 .00 .00 .00 .00 .00 .00 .32 .32 .00 .00 .00 .32 .00 .96 1. 92 .00 4.15 (2) .01 .00 .00 .00 .00 .00 .00 .01 .01 .00 .00 .00 .01 .00 .03 .07 .00 .15 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .*oo .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .'oo ALL SPEEDS 31 18 11 15 17 38 33 51 29 4 1 0 4 5 20 36 0 313 (1) 9.90 5.75 3.51 4.79 5.43 12.14 10.54 16.29 9.27 1. 28 .32 .00 1. 28 1. 60 6.39 11.50 .00 100.00 (2) .36 .21 .13 .17 .20 .44 .38 .59 .33 .05 .01 .00 .05 .06 .23 .41 .00 3.60

'(l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO . 95 MPH) 30

TABLE5D VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT) = 46.37 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 26 19 21 31 49 91 99 74 24 4 4 5 4 1 7 27 0 486 (1) . 64 .47 .52 .77 1. 21 2.25 2.45 1. 83 .59 .10 .1.0 .12 .10 .02 .17 . 67 .00 12.04 (2) .30 .22 .24 .36 .56 1. 05 1.14 .85 .28 .05 .05 .06 .05 .01 .08 .31 .00 5.58 C-3 74 41 42 31 55 73 73 94 73 41 22 26 34 47 63 107 0 896 (1) 1. 83 1. 02 1. 04 .77 1. 36 1. 81 1. 81 2.33 1. 81 1. 02 .55 . 64 .84 1.16 1. 56 2.65 .00 22.20 (2) .85 .47 .48 .36 . 63 .84 .84 1. 08 .84 .47 .25 .30 .39 .54 . 72 1.23 .00 10.30 4-7 120 35 9 9 19 55 119 162 84 26 22 28 62 61 148 244 0 1203 (1) 2.97 .87 .22 .22 .47 1. 36 2.95 4.01 2.08 . 64 .55 . 69 1. 54 1. 51 3.67 6.05 .00 29.81 (2) 1. 38 .40 .10 .10 .22 . 63 1. 37 1. 86 .97 .30 .25 .32 . 71 .70 1. 70 2.80 .00 13.82 8-12 110 19 1 0 1 10 8 89 82 18 17 18 147 150 142 218 0 1030 (1) 2.73 .47 .02 .00 .02 .25 .20 2.21 2.03 .45 .42 .45 3. 64 3. 72 3.52 5.40 .00 25.52 (2) 1.26 .22 .01 .00 .01 .11 .09 1. 02 .94 .21 .20 .21 1. 69 1. 72 1. 63 2.50 .00 11. 84 13-18 21 0 0 0 0 1 0 8 16 2 0 4 67 80 77 96 0 372 (1) .52 .00 .00 .00 .00 . 02 .00 .20 .40 .05 .00 .10 1. 66 1. 98 1. 91 2.38 .00 9.22 (2) .24 .00 .00 .00 .00 .01 .00 .09 .18 .02 .00 .05 .77 . 92 .88 1.10 .00 4.27 19-24 0 0 0 0 0 0 0 0 0 0 0 0 4 10 16 17 0 47 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .10 .25 .40 .42 .00 1.16 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .11 .18 .20 .00 .54 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 2 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .00 .00 .05 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .00 .00 .02 ALL SPEEDS 351 114 73 71 124 230 299 427 279 91 65 81 318 349 455 709 0 4036 (1) 8.70 2.82 1. 81 1. 76 3.07 5.70 7.41 10.58 6.91 2.25 1. 61 2.01 7.88 8.65 11.27 17.57 .00 100.00 (2) 4.03 1. 31 .84 .82 1. 42 2. 64 3.44 4.91 3.21 1. 05 .75 .93 3. 65 4.01 5.23 8.15 .00 46.37 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 31

TABLE SE VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT) = 28.16 WIND DIRECTION FROM

(

SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 30 - 18 12 12 10 21 64 74 41 32 30 13 11 16 17 25 0 426 (1) 1. 22 .73 .49 .49 .41 .86 2.61 3.02 1. 67 1. 31 1.22 .53 .45 . 65 .69 1. 02 .00 17.38 (2) .34 .21 .14 .14 .11 .24 .74 .85 .47 .37 .34 .15 .13 .18 .20 .29 .00 4.89 C-3 30 25 12 14 21 31 44 77 79 110 170 145 135 92 104 60 0 1149 (1) 1.22 1. 02 .49 .57 .86 1.26 1. 80 3.14 3.22 4.49 6.94 5.92 5.51 3.75 4.24 2.45 .00 46.88 (2) .34 .29 .14 .16 .24 .36 .51 .88 .91 1. 26 1. 95 1. 67 1. 55 1. 06 1.19 .69 .00 13.20 4-7 40 8 1 0 3 8 34 53 28 5 14 43 80 59 84 133 0 593 (1) 1. 63 .33 .04 .00 .12 .33 1. 39 2.16 1.14 .20 .57 1. 75 3.26 2.41 3.43 5.43 .00 24.19

,(2) . 46 .09 .01 .00 .03 .09 .39 . 61 .32 .06 .16 .49 .92 .68 .97 1. 53 .00 6.81 8-12 14 1 0 0 0 0 1 16 21 2 1 3 4*6 36 20 52 0 213 (1) .57 .04 .00 .00 ,oo .00 .04 . 65 .86 .08 .04 .12 1. 88 1. 47 .82 2.12 .00 8.69 (2) .16 .01 .00 .00 .* 00 .00 .01 .18 .24 .02 .01 .03 .53 .41 .23 .60 .00 2.45 13-18 4 0 '-o 0 0 0 0 1 1 0 1 0 9 24 4 21 0 65 (1) .16 .oo .oo .00 .00 .00 .00 . 04 .04 .00 .04 .oo .37 .98 .16 .86 .00 2.65 (2) .05 .00 .00 .00 .00 .00 .00 .01 .01 .00 .01 .00 .10 .28 .05 .24 .00 .75 19-24 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 3 0 5 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .08 .00 .00 .12 .00 .20 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .00 .00 .03 .00 .06 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00  :"'oo .00 .00 ALL SPEEDS 118 52 25 26 34 60 143 221 170 149 216 204 283 227 229 294 0 2451 (1) 4.81 2.12 1. 02 1. 06 1. 39 2.45 5.83 9.02 6.94 6.08 8.81 8.32 11.55 9. 26 9.34 12.00 .00 100.00 (2) 1. 36 . 60 .29 .30 .39 .69 1. 64 2.54 1. 95 1. 71 2.48 2.34 3.25 2.61 2.63 3.38 .00 28.16

'

(l}=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2}=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 32

TABLE 5F VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) 14.03 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW . WSW w_ WNW NW NNW VRBL TOTAL MPH CALM 5 7 5 5 6 12 16 17 28 49 31 26 10 11 13 22 0 263 (1) .41 .57 .41 .41 .49 .98 1. 31 1. 39 2.29 4.01 2.54 2.13 .82 .90 1. 06 1. 80 .00 21. 54 (2) .06 .08 .06 .06 .07 .14 .18 .20 .32 .56 .36 .30 .11 .13 .15 .25 .00 3.02 C-3 16 5 5 2 6 8 15 27 53 84 195 173 116 76 40 20 0 841 (1) 1. 31 .41 .41 .16 .49 .66 1. 23 2.21 4.34 6.88 15.97 14.17 9.50 6.22 3.28 1. 64 .00 68.88 (2) .18 .06 .06 .02 .07 .09 .17 .31 . 61 . 97 2.24 1. 99 1.33 .87 .46 .23 .00 9.66 4-7 4 0 0 0 0 1 3 5 3 12 11 12 14 17 15 17 0 114 (1) .33 .00 .00 .00 .00 .08 .25 .41 .25 .98 .90 .98 1.15 1. 39 1. 23 1. 39 .00 9.34 (2) .05 .00 .00 .00 .00 .01 .03 .06 .03 .14 .13 .14 .16 .20 .17 .20 .00 1. 31 8-12 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 0 3 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .08 .16 .00 .25 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .02 .00 .03 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 25 12 10 7 12 21 34 49 84 145 237 211 140 104 69 61 0 1221 (1) 2.05 .98 .82 .57 .98 1. 72 2.78 4.01 6.88 11. 88 19. 41 17.28 11. 47 8.52 5.65 5.00 .00 100.00 (2) .29 .14 .11 .08 .14 .24 .39 .56 .97 1. 67 2. 72 2.42 1. 61 1.19 .79 .70 .00 14.03 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 33

TABLE5G VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT) 4. 64 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 6 10 4 1 5 9 10 10 22 19 7 7 4 7 6 5 0 132 (1) 1. 49 2.48 .99 .25 1.24 2.23 2.48 2.48 5.45 4.70 1. 73 1. 73 .99 1. 73 1. 49 1.24 .00 32.67 (2) .07 .11 .05 .01 .06 .10 .11 .11 .25 .22 .08 .08 .05 .08 .07 .06 .00 1. 52 C-3 5 2 4 2 7 7 5 13 12 29 32 44 30 24 13 8 0 237 (1) 1. 24 .so .99 .50 1. 73 1. 73 1. 24 3.22 2.97 7.18 7.92 10.89 7.43 5.94 3.22 1. 98 .00 58.66 (2) .06 .02 .05 .02 .08 .08 .06 .15 .14 .33 .37 .51 .34 .28 .15 .09 .00 2. 72 4-7 1 0 0 0 0 1 0 1 1 5 4 1 8 3 5 5 0 35 (1) .25 .00 .00 .00 .00 .25 .oo .25 .25 1.24 .99 .25 1. 98 .74 1.24 1.24 .00 8.66 (2) .01 .00 .00 .00 .00 .01 .00 .01 .01 .06 .05 .01 .09 .03 .06 .06 .00 .40 8-12 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 13-18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .oo .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 . 00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 .0 0 0 (1) .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 12 12 8 3 12 17 15 24 35 53 43 52 42 34 24 18 0 404 (1) 2.97 2.97 1. 98 .74 2.97 4.21 3. 71 5.94 8.66 13.12 10.64 12.87 10.40 8.42 5.94 4.46 .00 100.00 (2) .14 .14 .09 .03 .14 .20 .17 .28 .40 . 61 .49 .60 .48 .39 .28 .21 .00 4.64

(!)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 34

TABLE SH VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 71 55 42 49 70 138 189 175 115 104 72 51 29 35 43 79 0 1317 (1) .82 . 63 .48 .56 .80 1.59 2.17 2.01 1.32 1.19 .83 .59 .33 .40 .49 .91 .00 15.13 (2) .82 . 63 .48 .56 .80 1. 59 2.17 2.01 1. 32 1.19 .83 .59 .33 .40 .49 __,.-* 91 .00 15.13 C-3 137 83 74 57 100 138 146 217 220 264 419 388 315 242 222 201 0 3223 (1) 1. 57 .95 .85 . 65 1.15 1. 59 1. 68 2.49 2.53 3.03 4.81 4. 4 6 3. 62 2.78 2.55 2.31 .00 37.03 (2) 1. 57 .95 .85 . 65 1.15 1. 59 1. 68 2.49 2.53 3.03 4.81 4.46 3.62 2.78 2.55 2.31 .00 37.03 4-7 189 55 17 30 72 115 195 268 129 51 54 84 165 142 264 424 0 2254 (1) 2.17 .63 .20 .34 .83 1.32 2.24 3.08 1. 48 .59 . 62 . 97 1. 90 1. 63 3.03 4.87 .00 25.90 (2) 2.17 . 63 .20 .34 .83 1. 32 2.24 3.08 1. 48 .59 . 62 . 97 1. 90 1. 63 3.03 4.87 .00 25.90

-

8-12 137 25 3 0 1 22 19 142 131 22 18 22 198 191 171 292 0 1394 (1) 1. 57 .29 .03 .00 .01 .25 .22 1. 63 1. 51 .25 .21 .25 2.28 2.19 1. 96 3.36 .00 16.02 (2) 1. 57 .29 .03 .00 .01 .25 .22 1. 63 1. 51 .25 .21 .25 2.28 2.19 1. 96 3.36 .00 16.02 13-18 26 0 0 0 0 1 0 12 20 2 1 4 77 105 84 128 0 460 (1) .30 .00 .00 .00 .00 .01 .00 .14 .23 .02 .01 .05 .88 1.21 .97 1. 47 .00 5.29 (2) .30 .00 .00 .00 .00 .01 .00 .14 .23 .02 .01 .05 .88 1.21 .97 1. 47 .00 5.29 19-24 0 0 0 0 0 0 0 0 0 0 0 0 6 10 17 20 0 53 (1) .00 .00 .00 .00 .00 .00 .00 .00 .oo .00 .oo .00 .07 .11 .20 .23 .00 . 61 (2) .00 .00 .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .07 .11 .20 .23 .00 . 61 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 2 (1) .00 .00 .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .02 .00 .00 .02 (2) .00 .00 .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .02 .00 .00 .02 ALL SPEEDS 560 218 136 136 243 414 549 814 615 443 564 549 790 725 803 1144 0 8703 (1) 6.43 2.50 1. 56 1. 56 2.79 4. 76 6.31 9.35 7.07 5.09 6.48,6.31 9.08 8.33 9.23 13.14 .00 100.00 (2) 6.43 2.50 1. 56 1.56 2.79 4.76 6.31 9.35 7.07 5.09 6.48 '6. 31 9.08 8.33 9.23 13.14 .00 100.00 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 35

TABLE6A VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT) = .32 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 4 0 0 0 0 0 0 0 0 0 0 0 . 0 0 0 0 0 4 (1) 14.29 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 14.29 (2) .05 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 C-3 1 1 0 0 0 1 0 1 1 0 0 0 0 0 1 1 0 7 (1) 3.57 3.57 .00 .00 .00 3.57 .00 3.57 3.57 .00 .00 .00 .00 .00 3.57 3.57 .00 25.00 (2) .01 .01 .00 .00 .00 .01 .00 .01 .01 .00 .00 .00 .00 .00 .01 .01 .00 .08 4-7 0 0 0 1 0 0 5 3 2 0 0 0 0 0 0 0 0 11 (1) .00 .00 .00 3.57 .00 .00 17.86 10.71 7.14 .00 .00 .00 .00 .00 .00 .00 .00 39.29 (2) .00 .00 .00 .01 .00 .00 .06 .03 .02 .00 .00 .00 .00 .00 .00 .00 .00 .13 8-12 1 1 0 0 0 0 1 0 0 0 0 0 0 0 1 1 0 5 (1) 3.57 3.57 .00 .00 .00 .00 3.57 .OD .00 .00 .00 .00 .00 .00 3.57 3.57 .00 17.86 (2) .01 .01 .00 .DO .00 .00 .01 .OD .00 .00 .00 .00 .00 .00 .01 .01 .00 .06 13-18 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 1 (1) .OD .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 3.57 .00 .00 .00 .00 3.57 (2) .00 .00 .00 .00 .00 .00 .00 .OD .00 .00 .'00 .00 .01 .00 .00 .00 .00 .01 19-24 0 D 0 0 0 0 0 0 D 0 0 0 0 0 0 0 0 0 (1) .00 .OD .00 .00 .00 .DO .00 .00 .OD .00 .00 .00 .00 .00 .00 .00 .00 .DO (2) .00 .00 .DO .00 .00 .DO .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .OD GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .DO .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .oo .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 6 2 0 1 0 1 6 4 3 0 0 0 1 0 2 2 0 28 (1) 21. 43 7 .14 .00 3.57 .00 3.57 21.43 14.29 10.71 .00 .00 .00 3.57 .00 7.14 7.14 .DO 100.0D (2) .07 .02 .00 .01 .OD .01 .07 .05 .03 .OD .00 .00 .01 .DD .02 .02 .DO .32 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 36

TABLE6B VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT) .23 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 4-7 1 1 0 0 0 0 2 0 0 0 0 0 0 0 1 1 0 6 (1) 5.00 5.00 .00 .00 .00 .00 10.00 .00 .00 .00 .00 .00 .bo .00 5.00 5.00 .00 30.00 (2) .01 .01 .00 .00 .00 .00 .02 .00 .00 .00 .00 .00 .00 .00 .01 .01 .DO .07 8-12 3 0 0 0 0 1 0 0 0 0 0 0 1 0 0 2 0 7 (1). 15.00 .00 .00 .00 .00 5.00 .00 .00 .00 .00 .00 .00 5.00 .00 .00 10.00 .00 35.00 (2) .03 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .01 .00 .00 .02 .00 .08 13-18 0 0 0 0 0 1 0 0 0 0 0 0 . 0 0 1 4 0 6 (1) .00 .00 .00 .00 .00 5.00 .00 .00 .00 .00 .00 .00 .00 .00 5.00 20.00 .00 30.00 (2) .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .01 .05 .00 .07 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 5.00 .00 5.00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .01 GT 24 0 0. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 4 1 0 0 0 2 2 0 0 0 0 0 1 0 2 8 0 20 (1) 20.00 5.00 .00 .00 .00 10.00 10.00 .00 .00 .00 .00 .00 5.00 .00 10.00 40.00 .00 100.00 (2) .05 .01 .00 .00 .00 .02 .02 .00 .00 .00 .00 .00 .01 .00 .02 .09 .00 .23 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO . 95 MPH) 37

TABLE6C VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT) 1. 59 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C-3 1 0 0 1 1 1 1 0 1 0 0 0 0 0 0 1 0 7 (1) . 72 .00 .00 .72 . 72 . 72 . 72 .00 .72 .00 .00 .00 .00 .00 .00 . 72 .00 5.07 (2) .01 .00 .00 .01 .01 .01 .01 .00 .01 .00 .00 .00 .00 .00 .00 .01 .00 .08 4-7 3 3 2 1 1 9 5 0 0 0 0 0 0 0 1 8 0 33 (1) 2.17 2.17 1. 45

  • 72 .72 6.52 3. 62 .00 .00 .00 .00 .00 .00 .00 . 72 5.80 .00 23.91 (2) .03 .03 .02 .01 .01 .10 .06 .00 .00 .00 .00 .00 .00 .00 .01 .09 '. 00 .38 8-12 10 2 4 2 1 7 5 4 0 0 0 1 0 3 3 17 0 59 (1) 7.25 1. 45 2.90 1. 45 . 72 5.07 3. 62 2.90 .00 .00 .00 . 72 .00 2.17 2.17 12.32 .00 42.75 (2) .11 .02 .05 .02 .01 .08 .06 .05 .00 .00 .00 .01 .00 .03 .03 .20 .00 . 68 13-18 8 2 0 0 0 1 2 1 1 0 0 0 1 1 1 10 0 28 (1) 5.80 1. 45 .00 .00 .00 . 72 1. 45 . 72 . 72 .00 .00 .00 . 72 . 72 . 72 7.25 .00 20.29 (2) .09 .02 .00 .00 .00 .01 . 02 .01 .01 .00 .00 .00 .01 .01 .01 .11 .00 .32 19-24 0 0 0 0 0 0 1 0 3 0 0 0 0 0 0 7 0 11 (1) .00 .00 .00 .00 .00 .00 . 72 .00 2.17 .00 .00 .00 .00 .00 .00 5.07 .00 7.97 (2) .00 .00 .00 .00 .00 .00 .01 .00 .03 .00 .00 .00 .00 .00 .00 .08 .00 .13 GT 2.4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

,-,

ALL SPEEDS 22 7 6 4 3 18 14 5 5 0 0 1 1 4 5 43 0 138 (1) 15. 94 5.07 4.35 2.90 2.17 13.04 10.14 3.62 3.62 .00 .00 .72 .72 2.90 3.62 31.16 .00 100.00 (2) .25 .08 .07 .05 .03 .21 .16 .06 .06 .00 .00 .01 .01 .05 .06 .49 .00 1. 59 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 38

TABLE6D VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT) = 52.26 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 5 2 0 1 3 2 16 3 1 1 0 0 1 0 0 6 0 41 (1) .11 .04 .00 .02 .07 .04 .35 .07 .02 .02 .00 .00 .02 .00 .00 .13 .00 .90 (2) .06 .02 .00 .01 .03 .02 .18 .03 .01 .01 .00 .00 .01 .00 .00 .07 .00 .47 C-3 55 32 37 39 49 . 46 85 59 23 8 10 9 5 16 29 55 0 557 (1) 1.21 .70 .81 .86 1. 08 1. 01 1. 87 1. 30 .51 .18 .22 .20 .11 .35 . 64 1.21 .00 12.25 (2) .63 .37 .43 .45 .56 .53 .98 .68 .26 .09 .11 .10 .06 .18 .33 .63 .00 6.40 4-7 90 36 27 22 45 131 203 158 71 19 14 14 17 19 64 173 0 1103 (1) 1. 98 .79 .59 .48 .99 2.88 4.46 3.47 1.56 .42 .31 .31 .37 . 42 1. 41 3.80 .00 24.25 (2) 1. 03 .41 .31 .25 .52 1. 51 2.33 1. 82 .82 .22 .16 .16 .20 .22 .74 1. 99 .00 12.67 8-12 113 38 11 6 14 36 113 234 247 49 28 36 109 123 68 249 0 1474 (1) 2.48 .84 .24 .13 .31 .79 2.48 5.15 5.43 1. 08 . 62 .79 2.40 2.70 1. 50 5.47 .00 32. 41 (2) 1. 30 .44 .13 .07 .16 .41 1. 30 2.69 2.84 .56 .32 .41 1.25 1. 41 .78 2.86 .00 16.94 13-18 93 16 3 1 4 9 8 54 134 16 8 8 134 137 109 212 0 946 (1) 2.04 .35 .07 .02 .09 .20 .18 1.19 2.95 .35 .18 .18 2.95 3.01 2.40 4.66 .00 20.80 (2) 1. 07 .18 .03 .01 .05 .10 .09 . 62 1. 54 .18 .09 .09 1. 54 1. 57 1. 25 2.44 .00 10.87 19-24 34 3 0 0 0 0 1 5 19 1 1 2 52 52 50 114 0 334 (1) .75 .07 .00 .00 .00 .00 .02 .11 .42 .02 .02 .04 1.14 1.14 1.10 2.51 .00 7.34 (2) .39 .03 .00 .00 .00 .00 .01 .06 .22 .01 .01 .02 . 60 .60 .57 1. 31 .00 3.84 GT 24 1 1 0 0 0 0 0 0 1 0 0 2 4 5 21 58 0 93 (1) .02 .02 .00 .00 .00 .00 .00 .00 .02 .00 .00 .04 .09 .11 .46 1.28 .00 2.04 (2) .. 01 .01 .00 .00 .00 .00 .00 .00 .01 .00 .00 .02 .05 .06 .24 . 67 .00 1. 07 ALL SPEEDS 391 128 78 69 115 224 426 513 496 94 61 71 322 352 341 867 0 4548 (1) 8.60 2.81 1. 72 1. 52 2.53 4.93 9. 37 11. 28 10. 91 2.07 1. 34 1. 56 7.08 7.74 7.50 19.06 .00 100.00 (2) 4.49 1. 47 .90 .79 1. 32 2.57 4.89 5.89 5.70 1. 08 .70 .82 3.70 4.04 3.92 9.96 .00 52.26 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO . 95 MPH)

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39

TABLE6E VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT) 30.52 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 3 4 2 1 4 9 13 3 2 1 0 1 1 1 0 2 0 47 (1) .11 .15 .08 .04 .15 .34 .49 .11 .08 .04 .00 .04 .04 .04 .00 .08 .00 1. 77 (2) .03 .05 .02 .01 .05 .10 .15 .03 .02 .01 .00 .01 .01 .01 .00 .02 .00 .54 C-3 95 73 56 35 86 91 100 51 37 18 10 10 10 23 43 81 0 819 (1) 3.58 2.75 2.11 1.32 3.24 3.43 3.77 1. 92 1. 39 .68 .38 .38 .38 .87 1. 62 3.05 .00 30.84 (2) 1. 09 .84 . 64 .40 .99 1. 05 1.15 .59 .43 .21 .11 .11 .p .26 .49 .93 .00 9.41 4-7 88 11 6 6 18 50 172 142 35 26 16 21 23 26 55 271 0 966 (1) 3.31 .41 .23 .23 . 68 1. 88 6.48 5.35 1. 32 .98 . 60 .79 .87 .98 2.07 10.20 .00 36.37 (2) 1. 01 .13 .07 .07 .21 . 5*7 1. 98 1. 63 .40 .30 .18 .24 .26 .30 .63 3.11 .00 11.10 8-12 37 6 0 0 1 4 38 57 63 18 9 19 70 55 40 191 0 608 (1) 1. 39 .23 .00 .00 .04 .15 1. 43 2.15 2.37 .68 .34 . 72 2. 64 2.07 1. 51 7.19 .00 22.89 (2) .43 .07 .00 .DO .01 .05 .44 . 65 . 72 .21 .10 .22 .80 . 63 .46 2.19 .00 6.99 13-18 16 0 0 0 0 0 1 5 22 6 4 5 32 24 9 64 0 188 (1) . 60 .00 .00 .DO .OD .OD .04 .19 .83 .23 .15 .19 1. 20 .90 .34 2.41 .00 7.08 (2) .18 .00 .00 .00 .00 .00 .01 .06 .25 .07 .05 .06 .37 .28 .10 .74 .00 2.16 19-24 1 0 0 0 0 0 0 0 2 1 0 1 2 7 1 10 0 25 (1) .04 .00 .00 .00 .00 .00 .00 .00 .08 .04 .DO .04 .08 .26 .04 .38 .00 . 94 (2) .01 .00 .00 .00 .00 .00 .00 .00 .02 .01 .00 .01 .02 .08 .01 .11 .DO .29 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 3 (1) .00 .00 .00 .00 .OD .DO .DO .DO .00 .OD .00 .OD .OD .DO .DO .11 .00 .11 (2) .00 .DO .DO .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .03 .00 .03 ALL SPEEDS 240 94 64 42 109 154 324 258 161 70 39 57 138 136 148 622 0 2656 (1) 9.04 3.54 2.41 1. 58 4.10 5.80 12.20 9. 71 6.06 2. 64 1. 47 2.15 5.20 5.12 5.57 23.42 .DO 100.00 (2) 2.76 1. 08 .74 .48 1.25 1. 77 3. 72 2.96 1. 85 .80 .45 . 65 1. 59 1. 56 1. 70 7.15 .00 30.52 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 40

TABLE6F VERMONT YANKEE JAN lS - DEC lS METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) 12.S7 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 2 1 0 1 3 3 2 0 1 1 1 0 0 0 1 1 0 17 (1) .18 .09 .00 .09 .27 .27 .18 .00 .09 .09 .09 .00 .00 .00 .09 .09 .00 1. SS

(.2) .02 .01 .00 .01 .03 .03 .02 .00 .01 .01 .01 .00 .00 .00 .01 .01 .00 .20 C-3 40 29 37 22 29 39 43 42 20 22 13 s 14 9 24 40 0 428 (1) 3.66 2.6S 3.38 2.01 2. 6S 3. S6 3.93 3.84 1. 83 2.01 1.19 .46 1.28 .82 2.19 : 3. 66 .00 39.12 (2) .46 .33 .43 .2S .33 .4S .49 .48 .23 .2S .lS .06 .16 .10 .28 .46 .00 4.92 4-7 3S s 0 6 13 28 9S 62 34 8 19 lS 16 14 37 94 0 481 (1) 3.20 .46 .00 .SS 1.19 2.S6 8. 68 S.67 3.11 .73 1. 74 1.37 1. 46 1.28 3.38 8.S9 .00 43.97 (2) .40 .06 .00 .07 .lS .32 1. 09 . 71 .39 .09 .22 .17 .18 .16 .43 1. 08 .00 S.S3 8-12 4 0 0 0 0 6 21 lS 12 8 3 9 13 14 7 46 0 1S8 (1) .37 .00 .00 .00 .00 .SS 1. 92 1. 37 1.10 .73 .27 .82 1.19 1. 28 . 64 4.20 .00 14.44 (2) .OS .00 .00 .00 .00 .07 .24 .17 .14 .09 .03 .10 .ls .16 .08 .S3 .00 1. 82 13-18 1 0 0 0 0 0 0 0 1 0 0 0 3 0 0 s 0 10 (1) .09 .00 .00 .00 .00 .00 .00 .00 .09 .00 .00 .00 .27 .00 .00 .46 .00 .91 (2) .01 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .03 .00 .00 .06 .00 .11 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 . 0.0 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 82 3S 37 29 4S 76 161 119 68 39 36 29 46 37 69 186 0 1094 (1) 7.SO 3.20 3.38 2. 6S 4 .11 6.9S 14. 72 10.88 6.22 3.S6 3.29 2. 6S 4.20 3.38 6.31 17.00 .00 100.00 (2) . 94 .40 .43 .33 .S2 .87 1. 8S 1. 37 .78 .4S .41 .33 .S3 .43 .79 2.14 .00 12.S7 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2) =PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .9S MPH) 41

TABLE6G VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 ~T WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT) = 2.52 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 0 0 0 0 1 0 0 0 1 0 0 0 0 0 0 0 0 2 (1) .00 .00 .00 .00 .46 .00 .00 .00 .46 .00 .00 .00 .00 .00 .00 .00 .00 .91 (2) .00 .. 00 .00 .00 .01 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .02 C-3 4 2 2 4 2 4 6 8 4 1 4 7 3 3 9 6 0 69 (1) 1. 83 .91 .91 1. 83 .91 1. 83 2.74 3.65 1. 83 .46 1. 83 3.20 1. 37 1. 37 4.11 2.74 .00 31. 51 (2) .05 .02 .02 .05 .02 .05 .07 .09 .05 .01 .05 .08 .03 .03 .10 .07 .00 .79 4-7 3 0 1 1 3 3 12 13 9 8 5 9 6 5 9 8 0 95

. (1) 1. 37 .00 .46 .46 1. 37 1. 37 5.48 5.94 4.11 3.65 2.28 4 .11 2.74 2.28 4.11 3.65 .00 43.38 (2) .03 .00 .01 .01 .03 .03 .14 .15 .10 .09 .06 .10 .07 .06 .10 .09 .00 1. 09 8-12 1 0 0 0 0 0 1 4 2 2 6 9 10 8 4 4 0 51 (1) .46 .00 .00 .00 .00 .00 .46 1. 83 .91 .91 2.74 4.11 4.57 3.65 1. 83 1. 83 .00 23.29 (2) .01 .00 .00 .00 .00 .00 .01 .05 .02 .02 .07 .10 .11 .09 .05 .05 .00 .59 13 0 0 0 0 0 0 0 0 0 0 0 0 - 1 1 0 0 0 2 (1) - . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .46 .46 .00 .00 .00 .91 (2) .00 .00 .00 .00 .00 - . 00 .00 .00 .00 .00 .00 .00 .01 .01 .00 .00 .00 .02 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .bo .00 .00 .00 .00 . 00- .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 8 2 3 5 6 7 19 25 16 11 15 25 20 17 22 18 0 219 (1) 3.65 .91 1. 37 2.28 2.74 3.20 8. 68 11. 42 7.31 5.02 6.85 11.42 9.13 7.76 10.05 8.22 .00 100.00 (2) .09 .02 .03 .06 .07 .08 .22 .29 .18 .13 .17 .29 .23 .20 .25 .21 .00 2.52 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH) 42

TABLE6H VERMONT YANKEE JAN 15 - DEC 15 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) 100.00 WIND DIRECTION FROM SPEED N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW VRBL TOTAL MPH CALM 14 7 2 3 11 14 31 6 5 3 1 1 2 1 1 9 0 111 (1) .16 .08 .02 .03 .13 .16 .36 .07 .06 .03 .01 .01 .02 .01 .01 .10 .00 1. 28 (2) .16 .08 .02 .03 .13 .16 .36 .07 .06 .03 .01 .01 .02 .01 .01 .10 .00 1.28 C-3 196 137 132- 101 167 182 235 161 86 49 37 31 32 51 106 184 0 1887 (1) 2.25 1. 57 1. 52 1.16 1. 92 2.09 2.70 1. 85 .99 .56 .43 .36 .37 .59 1.22 2.11 .00 21. 68 (2) 2.25 1. 57 1. 52 1.16 1. 92 2.09 2.70 1. 85 .99 .56 .. 43 .36 .37 .59 1.22 2.11 .00 21. 68 4-7 220 56 36 37 80 221 494 378 151 61 54 59 62 64 167 555 0 2695 (1) 2.53 . 64 .41 .43 .92 2.54 5.68 4.34 1. 74 .70 . 62 . 68 . 71 .74 1. 92 6.38 .00 30.97 (2) 2.53 . 64 .41 .43 .92 2.54 5.68 4.34 1. 74 .70 . 62 . 68 .71 .74 1. 92 6.38 .00 30.97 8-12 169 47 15 8 16 54 179 314 324 77 46 74 203 203 123 510 0 2362 (1) 1. 94 .54 .17 .09 .18 . 62 2.06 3.61 3. 72 .88 .53 .85 2.33 2.33 1. 41 5.86 .00 27.14 (2) 1. 94 .54 .17 .09 .18 . 62 2.06 3. 61 3.72 .88 .53 .85 2.33 2.33 1. 41 5. 86 .00 27.14 13-18 118 18 3 1 4 11 11 60 158 22 12 13 172 163 120 295 0 1181 (1) 1. 36 .21 .03 .01 .05 .13 .13 .69 1. 82 .25 .14 .15 1. 98 1. 87 1. 38 3.39 .00 13.57 (2) 1. 36 .21 .03 .01 .05 .13 .13 .69 1. 82 .25 .14 .15 1. 98 1. 87 1. 38 3.39 .00 13.57 19-24 35 3 0 0 0 0 2 5 24 2 1 3 54 59 51 132 0 371 (1) .40 .03 .00 .00 .00 .00 .02 .06 .28 .02 .01 .03 . 62 . 68 .59 1.52 .00 4.26 (2) .40 .03 .00 .00 .00 .00 .02 .06 .28 .02 .01 .03 . 62 . 68 .59 1. 52 .00 4.26 GT 24 1 1 0 0 0 0 0 0 1 0 0 2 4 5 21 61 0 96 (1) .01 .01 .00 .00 .00 .00 .00 .00 .01 .00 .00 .02 .05 .06 .24 .70 . 00 .. 1.10 (2) .01 .01 .00 .oo . 00 .00 .00 .00 .01 .00 . 00 . .02 .05 .06 .24 .70 .00 1.10 ALL SPEEDS 753 269 188 150 278 482 952 924 749 214 151 183 529 546 589 1746 0 8703 (1) 8. 65 3.09 2.16 1. 72 3.19 . 5.54 10.94 10. 62 8.61 2. 46 1. 74 2.10 6.08 6.27 6.77 20.06 .00 100.00 (2) 8. 65 3.09 2.16 1. 72 3.19 5.54 10.94 10. 62 8. 61 2.46 1. 74 2.10 6.08 6.27 6.77 20.06 .00 100.00 (l)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (2)=PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PERIOD C= CALM (WIND SPEED LESS THAN OR EQUAL TO . 95 MPH) 43

APPENDIX A SUPPLEMENTAL INFORMATION Facility: Vermont Yankee Nuclear Power Station Licensee: Entergy Nuclear Vermont Yankee lA. ODCM DOSE ANO DOSE RATE LIMITS -

ODCM Controls Dose Limit

a. Noble Gases 3/4.3.1 Total body dose rate 500 mrem/yr 3/4.3. l Skin.dose rate 3000 mrem/yr 3/4.3.2 Gamma air dose 5 mrad in a quarter 3/4.3.2 Gamma air dose 10 mrad in a year 3/4.3.2 Beta air dose 10 mrad in a quarter 3/4.3.2 Beta air dose 20 mrad in a year
b. Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 3/4.3..1 Organ dose rate 1500 mrem/yr 3/4.3.3 Organ dose 7.5 mrem in a quarter

'* 3/4.3.3 Organ dose 15 mrem in a year

c. Liquids 3/4.2.2 Total body dose 1.5 mrem in a quarter 3/4.2.2 Total body dose 3 mrem in a year 3/4.2.2 Organ dose 5 mrem in a quarter 3/4.2.2 Organ dose 10 mrem in a year 2A. ODCM LIMITS-CONCENTRATION ODCM Control
a. Noble Gases No ECL Limits
b. Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days No ECL Limits A-1
c. Liquids 3/4.2.1 Sum of the fractions of ECL excluding noble gases (1 OCFR20, Appendix B, Table 2, Column 2): _:::: l.OE+Ol 3/4.2. l Total noble gas concentration: _:::: 2E-04 µCi/cc
3. AVERAGE ENERGY

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Provided below are the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable.

a. Average gamma energy: Not Applicable
b. Average beta energy: Not Applicable
4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
a. Fission and Activation Gases Continuous stack monitors monitor the gross Noble Gas radioactivity released from the plant stack. Because release rates are normally below the detection limit of these monitors, periodic grab samples are taken and analyzed for the gaseous isotopes present. These are used to calculate the individual isotopic releases indicated in Table lB and the totals of Table lA. The error involved in these steps may be approximately +/-23 percent.
b. Iodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. The filters and cartridges are normally removed weekly and are analyzed for Iodine-131, 132, 133, 134, and 135. The error involved in these steps may be approximately +/-18 percent.

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c. Particulates The particulate filters described in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximately +/-18 percent.
d. Tritium ODCM Table 4.3 .1 requires as a minimum that grab samples from the plant stack be taken monthly and analyzed for tritium. The stack tritium collection has been upgraded with silica gel columns and continuous sampling of stack effluents. The error involved in this sample is approximately +/-18 percent.
e. \\Taste ()il Prior to issuing the permit to burn a drum of radioactively contaminated waste oil, one liter of the oil is analyzed by gamma spectroscopy to determine concentrations of radionuclides that meet or exceed the LLD for all of the liquid phase radionuclides listed in ODCM Table 4.2.1.

Monthly, samples from drums that were issued burn permits are sent to the contracted laboratory for compositing and analysis. The lab analyzes for tritium, alpha, Fe-55, Sr-89, and Sr-90 on the composite sample.

The error involved in this sample is approximately +/-15 percent.

f. Liquid Effluents If radioactive liquid effluents are to be released from the facility, they are continuously monitored. Measurements are also required on a representative sample of each batch ofradioactive liquid effluents released. For each batch, station records are retained of the total activity (mCi) released, concentration

(µCi/ml) of gross radioactivity, volume (liters), and approximate total.quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River.

Each batch of radioactive liquid effluents to be released is analyzed for gross gamma and gammaisotopic radioactivity. A monthly proportional composite sample, comprising an aliquot of each batch released during a month, is analyzed for tritium and gross alpha radioactivity. A quarterly proportional

  • composite sample, comprising an aliquot of each batch released during a quarter, is analyzed for Sr-89, Sr-90, and Fe-55.

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5. BATCH RELEASES
a. Liquid There were no*routine liquid batch releases during the reporting period.
b. Gaseous There were no routine gaseous batch releases during the reporting period.
6. ABNORMAL RELEASES
a. Liguid
1) In 2015 there was a continuous release due to the residual radioactivity in groundwater from a previously undetected leak from a subsurface structure.

The leak condition was identified through monitoring well data in January 2010. The leak was stopped in February 2010 ..

2) For 2015, the total Tritium radioactivity conservatively estimated to be released to the Connecticut River is 0.0334 Curies. No other plant-related radionuclides were detected in ground water.
b. Gaseous There were no non-routine gaseous releases (measured) during the reporting period.

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APPENDIXB LIQUID HOLDUP TANKS Requirement Technical Specification 3. l .A.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.1.A.l, a description of the events leading to this condition is required in the next annual Radioactive Effluent Release Report per ODCM Section 10.1.

Response: The limits of Technical Specification 3.1.A.1 were not exceeded during this reporting period. (Note that during 2015 the section numbering of the Technical Specifications changed due to the implementation of an NRC-approved License Amendment following permanent shutdown and defueling of the plant, but there were no changes made to the limits in Technical Specification 3.1.A.1 from those previously contained in Technical Specification 3.8.D.l)

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APPENDIXC RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.1. If an inoperable radioactive liquid effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3 .1.1, an explanation in the rtext annual Radioactive Effluent Release Report of the reason(s) for delay in correcting the inoperability are required per ODCM Section 10.1.

Response: Since the requirements of ODCM Table 3.1.1 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period, no response is required. j C-1

APPENDIXD RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Table 3.1.2. If inoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.1.2, an explanation in the next annual Radioactive Effluent Release Report of the reason(s) for the delay in correcting the inoperability is required per ODCM Section lO.l.

Response: Since the requirements of ODCM Table 3.1.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no response is required.

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APPENDIXE

. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirement: The radiological environmental monitoring program is conducted in accordance with ODCM Control 3/4.5.1. With milk samples no longer available from one or more of the sample locations required by ODCM Table 3.5.1, ODCM 10.1 requires the following to be included in the next annual Radioactive Effluent Release Report: (1) identify the cause(s) of the sample(s) no longer being available, (2) identify the new location(s) for obtaining available replacement samples and (3) include revised ODCM figure(s) and table(s) reflecting the new location(s).

Response: Milk and silage collection at the Vern-Mont Farm (TM-20) was discontinued in August 2015 due to the permanently shut down and defueled status of the plant. It is noted that this was not a required sampling station in the ODCM.

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APPENDIXF 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 Response: The Land-Use Census was completed during the third quarter of2015. No locations were identified which yielded a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to ODCM Control 4.3 .3. See Table 4C for a listing of nearest residents and milk animals in the site area as determined in the 2015 Land Use Census.

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

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

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APPENDIXH OFF-SITE DOSE CALCULATION MANUAL Requirement: Technical Specification 6.7.B.1 requires that licensee initiated changes to the Off-Site Dose Calculation Manual (ODCM) be submitted to the Commission in the annual Radioactive Effluent Release Report for the period in which the change(s) was made effective.

Response: No revisions were made to the ODCM during the reporting period.

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APPENDIX I RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Requirement: ODCM Section 10.4 requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.

Response: There were no licensee-initiated major changes to i:he radioactive waste systems during this reporting period.

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APPENDIXJ ON~SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE Requirement: 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 Release Report if disposals occur during the reporting year. Entergy Nuclear Vermont Yankee will report in the Annual Radioactive Effluent Release Report a list of the radiomI;clides present and the total radioactivity associated with the disposal activities oh the Vermont Yankee site.

Response: There was one on-site disposal spreading of 11,000 gallons of septic waste during October of 2015, and no spreading activities for cooling tower silt or sand/soil type materials. The total radioactivity spread on the 1.9 acres (southern) on-site disposal field from this and previous years was as follows:

Activity from All Past and Current Activity Spread in 2015 Disposals Decayed to 10/20/2015 Radionuclide (Ci) (Ci)

Mn-54 8.00E-11 1.17E-08 Co-60 2.43E-09 9.67E-06 Zn-65 2.68E-10 3.67E-09 Cs-134 O.OOE+OO 6.68E-10

. Cs-137 l.lOE-10 7.50E-05 The maximum organ dose from all past and current spreading operations totaled l.09E-01 mrem/year. This calculated value is within the 1 mrem/year limit applied during the period of operational control of the site. The projected hypothetical "intruder" dose for the period following the loss of operational control of the site area, due to all spreading operations to-date, is 2.08E-01 mrem/year versus a 5 mrem/year dose limit. The "intruder dose" period begins on the date that the plant operating license expires, March 21, 2032.

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