Text

Submittal of 2014 Radioactive Effluent Release Report
	ML15135A240
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	05/12/2015
From:	Chappell C; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BVY 15-037
	Download: ML15135A240 (83)
	v • d • e

SEntergy Entergy Nuclear Operations, Inc.

Vermont Yankee 320 Governor Hunt Road Vernon, VT 05354 Tel: (802) 257-7711 Coley C. Chappell Licensing Manager BVY 15-037 May 12, 2015 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

SUBJECT:

2014 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 2014 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 minor changes made to the ODCM during 2014 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,

Enclosure:

Radioactive Effluent Release Report for 2014 cc listing (next page) 4'ý

BVY 15-037 / page 2 of 2 cc:

Mr. Daniel Dorman, Region 1 Administrator U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Mr. James Kim, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08D15 11555 Rockville Pike Rockville, MD 20852-2378 USNRC Resident Inspector Vermont Yankee 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 Radiation Control Program Attn: Bob Walker, Director Schrafft Center - Suite 1 M21 529 Main Street Charlestown, MA 02129 DHHS/DPHS Dennis P. O'Dowd, Administrator 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 US EPA - Region 1 5 Post Office Square - Suite 100 Boston, Massachusetts 02108

RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2014 INCLUDING ANNUAL RADIOLOGICAL IMPACT ON MAN Entergy Nuclear Vermont Yankee, LLC Docket No. 50-271 License No. DPR-28 Prepared by:

Preparation cor /iated b' Reviewed Approved for

TABLE OF CONTENTS P.r.e 1.0 IN TR O D U C T IO N 2.0 M ETEO RO LO G ICA L D A TA............................................................................................................................

2 3.0 D O SE A SSESSM EN T............

3 3.1 D OSES FROM LIQUID EFFLUENTS 3.2 DOSE-S 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 O N-SITE R ECREATIONAL A CTIVITIES.............................................................................................................

6 R E F E R E N C E S..........................................................................................................................................................

7 APPENDIX A -SUPPLEMENTAL INFORMATION.....................................................................................

A-1 A PPEN D IX B -LIQ U ID HO LD U P TAN KS........................................................................................................

B-1 APPENDIX C -RADIOACTIVE LIQUID EFFLUENT MONITORING IN ST R U M EN TA T IO N...............................................................................................................

C -I APPENDIX D -RADIOACTIVE GASEOUS EFFLUENT MONITORING IN ST R U M EN TA T IO N................................................................................................................

D -I APPENDIX E - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM................................. E-1 A PPEN D IX F - LA N D U SE C EN SU S..................................................................................................................

F-I APPENDIX G -PROCESS CONTROL PROGRAM............................................................................................

G-1 APPENDIX H -OFF-SITE DOSE CALCULATION MANUAL.........................................................................

H-I APPENDIX I - RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE T R EA T M EN T SY STEM S..........................................................................................................

1-1 APPENDIX J - ON-SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE.........................................................

J-1 ii

LIST OF TABLES IA Gaseous Effluents - Summation of All Releases 8

I B Gaseous Effluents - Elevated Releases 10 IC Gaseous Effluents - Ground Level Releases 12 I D 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 2014 (10CFR50, Appendix I) 4B Maximum Annual Off-Site Doses from Direct Radiation and 22 and Liquid and Gaseous Effluents for 2014 (40CFR 190) 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 (2014) Summary of Lower Level Joint Frequency Distribution 28-35 6A to 6H Annual (2014) Summary of Upper Level Joint Frequency Distribution 36-43 iii

Radiological Effluent Release Report for 2014

[Including Annual Radiological Impact on Man]

Entergy Nuclear Vermont Yankee, LLC

1.0 INTRODUCTION

Tables I 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 2014 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 5A through 6H report the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 2014. Radioactive effluents reported in Tables I and 2 were used to determine the dose to the maximum exposed individual for 2014.

Dose commitments resulting from the release of radioactive materials in liquids and gases during the reporting period were estimated in accordance with the plant's Off-Site Dose Calculation Manual (ODCM), Section 10.1 (Reference 1). These dose estimates were made using a "Method I1" analysis as described in the ODCM, and as reported in Tables 4A and 4B of this 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 if the conditions indicated in ODCM 3/4.4, "Total Dose," have been exceeded during the year. Since the conditions indicated in the action statement under ODCM 3/4.4 were not entered into during the year, no additional radiation dose assessment is required.

However, Table 4B does provide the combination of off-site doses and dose commitments from plant effluents and direct radiation sources for the limiting member of the public as a demonstration of compliance with the dose standards of 40 CFR Part 190.

All calculated dose estimates for members of the public at the site boundary or beyond for the 2014 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.

I

2.0 METEOROLOGICAL DATA Meteorological data were collected in 2014 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.

X/Q 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, X/Q 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 routine ground-level releases and therefore no associated dose impact.

Table 4C lists the distances 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 2014 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 Liquid Effluents ODCM 3/4.2.2 limits total body doses (1.5 mrem per quarter, and 3 mrem per year) and organ doses (5 mrem per quarter, and 10 mrem per year) from liquid effluents to a member of the public to those specified in 10 CFR Part 50, Appendix I. By implementing the requirements of 10 CFR Part 50, Appendix I, ODCM 3/4.2.2 assures that the release of radioactive material in liquid 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 2014, 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 2014 was generated and reported in Table 2A.

For the projected ground water flow into the Connecticut River in 2014, the dose impact to the maximum exposed individual (MEI) assumed the following exposure pathways: (1) ingestion of fish (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) potable 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 (3,109 cfs in September 2014) for dilution. All irrigation exposure pathways for the consumption of food products grown with irrigated water occur below Vernon Dam and assume the lowest 2014 quarterly average growing season river flow value (6,157 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 (6,157 cfs in the third quarter) as a conservative estimate of river dilution for all four quarters of the year. The dose models are taken 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 Part 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 of radioactive 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 2014, 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 1 (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 2014, 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.

One unplanned gaseous release of tritium was recorded during the second quarter. On April 17, 2014, during a maintenance activity in the drain pit of the Advanced Offgas (AOG) system, there was a brief 4-hour ground level gaseous release of 2.80E-03 Ci of H-3. The resultant off-site dose from this release was minimal with respect to the routine normal effluent gaseous releases.

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.

4

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 (12) and is available for uptake (see p. 6, Reference 2).

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 (I) greater than 1 percent of the 10 CFR Part 50, Appendix I design objective dose for all radionuclides in the type of effluent being considered, or (2) greater than I 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 much less than those generated naturally or from past weapons testing. Since the time of the earlier publication of Regulatory Guide 1.21 (Revision 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, and therefore has been included in the assessment of dose to the public from gaseous effluent releases for 2014.

The primary exposure pathways associated with Carbon-14 include inhalation and ingestion of food products that have incorporated Carbon-14 (in the form of C0 2) via photosynthesis. A full year's consumption of food products are assumed to be grown from the highest impacted garden during the growing season (2nd and 3rd quarters). It is also assumed that the garden grows sufficient mass to support ingestion throughout the year (i.e., the annual dose to the individual is from consumption during all four quarters).

The resultant organ doses were determined after adding the contributions from all pathways at each location. Doses were calculated for the whole body, GI-tract, bone, liver, kidney, thyroid, lung, and skin for adults, teenagers, children, and infants. The maximum estimated quarterly and annual organ doses to any age group due to iodines and particulates at any of the off-site receptor locations are reported in Table 4A.

These estimated organ doses are well below the 10 CFR Part 50, Appendix I dose criteria of ODCM 3/4.3.3.

Table 4B provides an estimation of the total annual dose impact (including contributions from iodines and particulates) associated with the highest exposed member of the public for demonstration of compliance with the dose standard contained in 40 CFR Part 190 for the uranium fuel cycle.

3.4 Whole Body Doses in Unrestricted Areas From Direct Radiation The major dose in unrestricted areas occurs at the west site boundary, and mainly consists of direct and skyshine radiation from N-16 decay in the Turbine Building steam cycle during power operations.

Because of the orientation of the Turbine Building on the site, andthe shielding effects of the adjacent Reactor Building, only the seven westerly sectors (SSW to NNW) are exposed to any significant direct radiation.

5

A correlation method was derived, based on site boundary exposure rate and in-plant Main Steam Line Radiation Monitor measurements, that allows changes in the N-16 carryover in the main steam flow to be directly related to changes in the site boundary dose. This correlation is documented in section 6.11.1 (Equation 6-27a) of the ODCM. This method was used to calculate direct dose within the area of the maximum site boundary location from radiation sources in the steam cycle.

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, 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 as that for N-16 shine from the Turbine Building.

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 2014, 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.

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 I mrem/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 mrem/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 2014, based on the combined dose from this spreading and all past spreadings.

3.6 On-Site Recreational Activities During 2014, 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 I.

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 10 CFR Part 50, Appendix I," U. S.

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

5.

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

6.

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

7

TABLE IA Entergy Nuclear Vermont Yankee Effluent and Waste Disnosal Annual Ret~ort for 2014 Gaseous Effluents -Summation of All Releases U

Quarter Quarter Est. Total t I 1

1 2

Error, %

A.

Fission and Activation Gases I.

Total release Ci ND ND

+/-2.30E+01

2.

Average release rate for period pCi/sec ND ND N/A

3.

Percent of ODCM limit (1)

ND ND N/A B.

lodines

1.

Total Iodine Ci ND 8.14E-05

+/-1.80E+01

2.

Average release rate for period pCi/sec ND 1.02E-05 N/A

3.

Percent of ODCM limit (3)

(3)

N/A C.

Particulates

1.

Particulates with T-1/2>8 days Ci ND 3.58E-06

+/-1.80E+01

2.

Average release rate for period ItCi/sec ND 4.50E-07 N/A

3.

Percent of ODCM limit (3)

(3)

N/A

4.

Gross alpha radioactivity Ci ND ND N/A D.

Tritium (4)

1.

Total release Ci 5.62E-01 7.34E-0 I

+/-1.80E+01

2.

Average release rate for period pCi/sec 7.07E-02 9.20E-02 N/A

3.

Percent of ODCM limit (3)

(3)

N/A E.

Carbon-14 I.

Total release Ci 1.89E+00 1.91E+00 (5)

Percent of ODCM limit (2) 7.32E+00 7.44E+00 N/A ND = Not Detected (I)

ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage of ODCM 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, lodines, 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.

(5) The total Carbon-14 release is calculated, based on EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." The "Estimated Total Error" is therefore not applicable.

8

TABLE IA (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2014 Gaseous Effluents -Summation of All Releases Unit Quarter Quarter Est. Total 1_3 4

Error, %

A.

Fission and Activation Gases I.

Total release Ci ND ND

+/-2.30E+01

2.

Average release rate for period pCi/sec ND ND N/A

3.

Percent of ODCM limit (1)

ND ND N/A B.

lodines

1.

Total Iodine Ci 1.01E-04 ND

+/-1.80E+01

2.

Average release rate for period jiCi/sec 1.28E-05 ND N/A

3.

Percent of ODCM limit (3)

(3)

N/A C.

Particulates I.

Particulates with T-1/2>8 days Ci ND ND

+/-1.80E+01

2.

Average release rate for period pCi/sec ND ND N/A

'3.

Percent of ODCM limit (3)

(3)

N/A

4.

Gross alpha radioactivity Ci ND ND N/A D.

Tritium (4)

1.

Total release Ci 9.68E-0I 1.89E+00

+/-1.80E+01

2.

Average release rate for period pCi/sec 1.22E-01 2.37E-01 N/A

3.

Percent of ODCM limit (3)

(3)

N/A E.

Carbon-14

1.

Total release Ci 1.95E+00 1.62E+00 (5)

2.

Percent of ODCM limit (2) 7.57E+00 6.29E+00 N/A ND = Not Detected (1) ODCM Control 3.3.2. for the most limiting of beta air or gamma air dose. Percentage of ODCM 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, lodines, 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.

(5) The total Carbon-14 release is calculated, based on EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." The "Estimated Total Error" is therefore not applicable.

9

TABLE IB Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2014 Gaseous Effluents -Elevated Releases Continuous Mode Batch Mode (I)

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)

(I)

2.

lodines Iodine-131 Ci ND 5.10E-06 Iodine-133 Ci ND 7.63E-05 Iodine-135 Ci ND ND Total for Period Ci ND 8.14E-05 (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-51 Ci ND ND Cobalt-57 Ci ND ND Cobalt-58 Ci ND 3.58E-06 Cobalt-60 Ci ND ND Cerium-141 Ci ND ND Zinc-65 Ci ND ND Total for Period Ci ND 3.58E-06 (1)

(1)

ND Not Detected at the plant stack (1)

There were no batch mode gaseous releases for this reporting period.

10

TABLE IB (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disnosal Annual Renort for 2014 Gaseous Effluents -Elevated Releases Continuous Mode Batch Mode (1)

Qu arter 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 (I)

(I)

2.

lodines Iodine-131 Ci ND ND Iodine-133 Ci 1.01E-04 ND Iodine-135 Ci ND ND Total for Period Ci 1.01E-04 ND (1)

(D)

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-51 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 N D (I)

(1)

ND Not Detected at the Plant Stack (1)

There were no batch mode gaseous releases for this reporting period.

II

TABLE IC Entergv Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2014 Gaseous Effluents - (Routine) Ground Level Releases (2)

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

lodines Iodine-131 Ci Iodine-133 Ci lodine-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 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 2014.

12

TABLE IC (Continued)

Enterav Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2014 Gaseous Effluents - (Routine) Ground Level Releases(2)

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

lodines Iodine-131 Ci Iodine-133 Ci Iodine-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 2014.

13

TABLE I D Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2014 Gaseous Effluents -Non-routine Releases Quarter Quarter Nuclides Released Units 1(l) 2(2) 3(1) 4(l)

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.

lodines lodine-131 Ci Iodine-133 Ci lodine-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 Iron-55 Cl Total for Period Ci (I) There were no non-routine ground level gaseous releases for this reporting period.

(2) On 4/17/2014, there was an unplanned ground-level release of 2.80E-03 Ci of H-3 from the AOG drain pit.

14

TABLE 2A Entery Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2014 Liquid Effluents - Summation of All Releases Est. Total Units Quarter 1 Quarter 2 1Error, %

A.

Fission and Activation Products

1.

Total Release (not including tritium, gases, alpha)

Ci ND ND N/A

2.

Average Diluted Concentration During Period PiCi/ml ND ND

3.

Percent of Applicable Limit (1)

ND ND B.

Tritium

1.

Total Release Ci 1.26E-02 1.18E-02

+2.OOE+01

2.

Average Diluted Concentration During Period itCi/ml 2.46E-06 2.13E-06

3.

Percent of Applicable Limit (1) 8.87E-05 8.33E-05 C.

Dissolved and Entrained Gases

1.

Total Release Ci ND ND N/A

2.

Average Diluted Concentration During Period P.Ci/ml ND ND

3.

Percent of Applicable Limit ND ND D. Gross Alpha Radioactivity

1.

Total Release Ci ND ND N/A E.

Volume of Waste Release (prior to dilution)

Liters

2)

(2)

N/A F.

Volume of Dilution Water Used During Period Liters 3.89E+06 3.89E+06 3

ND (1)

Not detected in liquid effluents.

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 10CFR20.1001 - 20.2402, Table 2, Column 2 (ODCM Control 3. 2.1)were estimated to be 2.46E-03%, 0.21%, 0.19%, and 0.18% 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 2014.

(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 2014. An Estimated Total Error is not applicable.

15

TABLE2A (Continued)

Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2014 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

2.

Average Diluted Concentration During Period PCi/ml ND ND

3.

Percent of Applicable Limit (1)

ND ND B.

Tritium

1.

Total Release Ci 1.1OE-02 9.88E-03

+2.00E+01

2.

Average Diluted Concentration During Period AiCi/ml 1.90E-06 1.77E-06

3.

Percent of Applicable Limit (1) 7.73E-05 6.93E-05 C.

Dissolved and Entrained Gases

1.

Total Release Ci ND ND N/A

2.

Average Diluted Concentration During Period P.Ci/ml ND ND

3.

Percent of Applicable Limit ND ND D.

Gross Alpha Radioactivity

1. Total Release Ci ND D

N/A E. Volume of Waste Release (prior to dilution)

Liters 2

2 N/A 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 10CFR20.1001 - 20.2402, Table 2, Column 2 (ODCM Control 3. 2.1) were estimated to be 2.46E-03%, 0.21%, 0.19%, and 0.18% 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 2014.

(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 2014. An Estimated Total Error is not applicable.

16

TABLE 2B Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2014 Liquid Effluents - Routine Releases Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-1 37 Ci Iodine-131 Ci Cobalt-58 Ci Cobalt-60 Ci Iron-59 Ci Zinc-65 Ci Manganese-54 Ci Zirconium-Niobium-95 Ci Molybdenum-99 Ci Technetium-99 Ci Barium-Lanthanum-140 Ci Cerium-141 I

Other (specify)

I Ci I

i I

r ;

I Ci Unidentified Ci Total for Period (above)

Ci

[

I I

I ]

Xe-133 Ci Xe-i 35 Ci ND Not detected in liquid effluents.

Dash indicates no release of this type.

17

TABLE 2B (Continued)

Enter~v Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 20.14 Liquid Effluents - Routine Releases Continuous Mode Batch Mode Nuclides Released Units Quarter3 Quarter4 Quarter3 Quarter4 Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Iodine-131 Ci Cobalt-58 Ci Cobalt-60 Ci Iron-59 Ci Zinc-65 Ci Manganese-54 Ci Zirconium-Niobium-95 Ci Molybdenum-99 Ci Technetium-99 Ci Barium-Lanthanum-140 Ci Cerium-141 Other (specify)

Ci 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

TABLE 3 Entergy Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2014 Solid Waste and Irradiated Fuel Shipments A. Sa~d Waite Sipped OSS~M far Sore cm, 9spal biot bru&Mtid fixed

1. Ty"e of Waste,____

$hpt(cm VY forBu, alti ltr Q

C seraa I & 2 Ebi laot Earrn %~

vvb 1...hew hoick.t.

mn3 2.68840

25%

0 4.SBE+01 125%

b. ReitaewWAhfe We. wAipteft me ms

-A-WAn a

Now.

N/A a.~~~~

radua aaau outrdar.

m3 No".

N/A a

No"e N/A Sh nOdl00. proaes so,,, S to t Bairi.

Q~m trers I & 2 fit. Total Errat %

S.p~l.ar % IM. Adal.

ogat.r

.3 Nones N/A J

C.

No".

N/A b

m3~tr Ie.

qepaa.rt n

No".

N/A a

Norm N/A J

c, Canradw cnaipeersamt an reds..u.i m3 Non C.

N::

N/A

~ Ettaa.

o Mjo Nidi.

omos~on(By Type ofWaste(______

S.-I -m.1t.1.*ud lb 0I otCorC,-Wr.trt4, W.

ada~

btri.utOor t

U W.A.

Num~d.

parCent(1)

Nýiold Po=cealf I

Nutlid, LerIn(1 Naetid*

~ca~1 Carbor,14 0.028%

No,,.

None o"

Cob~aS~I 113%

ioe Cb 4lt6 31.4ft_

MharoSlr-1 t.73%

Nbbajmi&4.

0-26%

Nokk.IA 3.01%

Aamnoy 124 0.01%

Iii U.ma.0 0.10%

21-Mb_______________

Zlro~tcx ra.93 1 0 O.

rnA dsta elta,0%o h oa eht 1 dca Vtaw*

urne dsta eV.a im0 So h oa cV

3. Ompowbort of SoldW Waste Si~pmrstas (lt&S aNW,r Noi cfShwrAnao Fr,cm VI rmaosr Modeo TO~O~

~ia~

8.Iiaftid 5.usl Sh~pnerits 1jbiapotl:oaft Noe C Addlleo"i Oeaf (M. & 2nd Quo"es lSugp-neW O

-1 a

oa,,eot I i acora WtOLi"ut 1 Paocesw to8o,1 1Cluui of Sold Waste Shipped AU AU 1type of so~eir Used GO Ys

.t.vA~o~fu~ngno~w~n~e le.

t GR -Gailmatw Rued SCO Besar Creek Oporsflams Was waste Coetlro Swoasita ES1-frylolittor GOC.

- enerw Oeavr coas AU GOC. I jj ý anne 19

TABLE 3 (continued)

Entergv Nuclear Vermont Yankee Effluent and Waste Disposal Annual Report for 2014 Solid Waste and Irradiated Fuel Shipments A. dWest. -q*V 06.1.for holelo 00spd (not beiadted"o

1. Tyw of waft

%*ped*f~oM V, f, 6.4 1.Il ctartet 3 & 4 Ett Toata Etter%

________________________m3 IJ53E+j fO 0

2.78E+01 I

b Non.

Nm MA O

No.*

N/A Sh pp.d f,-r fs~.

or Rv~al t~'t Qan-rr3 & 4

EaTt, t

a soattink r.9%w m3 I'luec0l 115%

560E+04 t25%

b r t~c--wp&U.ft wv".t m~33 2.36E-01 125%

C1 9.,3E-02

3$%

Irodoled

.L-tM,.d.o.

m3 Nom N/A 0

Nor..

N/

Nu.olde hvwnt()

VNucI~da Pawtonq(11 Nueld.

Parook.f

__!-.do

!-Iten(1)

C.nbo-t4 0.03 Cc.ftht8 3.M9 itnes TMMn 3 100 Oft

-Cobolts L.31%

cowblk40 S249%

cobatO4o SS.19%

MorrA.on-%3 2.37%

Chrovtlw-51 3."1%

C10em-It7 0.19%

Co -I.ol3?

L

.91%

Iroo.%

271%

______0__

OA%

Mroeoi 2.12%

3194%

NoWbln,-S CM1 Ntobmwlls9 OAI%

WOW1.6 1.27%

Niek.44O I 63%

Arnilsony.224 0.CLM____

AOAt12

,2%

Anttnr 12S I 0.75-I__________

Arttniony125 014%

ltn.6 993YA____

2nr4s 14's" loconon 00

.33 4111ndodesoriV ft%. o.clidas thataoregrestsr ftit 0.1% of tie toretal otv 3 Catointar ef Sold Wasse 33lNrnam 30 ý a__4`____________

No 01 5h prr'eprrls V~nvy VrmlwPo*1o

'o.o o9.,.

a Truck E$-BCD 1TN 7

0 TAIx ES 2& TN 3

0 TrCk WC5 (M3) 4 x____

Y rurk

______WCS (CWV) 3 Truck

_wCS(CCwP 9

0 Truck ESCIat" 7

0

~~~~Truk 9%AI____

Bulks'y for role.., to letruf.11 B. lrr*fltW Fuel Slillm"~ IOopeosf*

NOM.

5tr~n-4tto5r~tr~nu~o.

V. Ott P'yytts VIy mj B*1 Prl~swr,ý to 9,,'..

SoCtd&.týo Ai ow Absorbom Urod

,o.

n ne GR - Gagahe, Rood Cýot~. ev, SCO --Bowr Cro), Opera&ot GOC.. W816C."se 01 1 a 'd V

20

TABLE4A Entergy Nuclear Vermont Yankee Maximum* Quarterly and Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2014 (IOCFR50, Appendix 1)

F

-Dose (mrem)(a)

Sore1st 2nd 3rd 4ffh F

Source IQuarter Quarter Quarter Quarter Year(b)

Liquid Effluents Total Body Dose 1.33E-06 1.25E-06 1.16E-06 1.04E-06 4.80E-06 Footnotes (c)

(c)

Organ Dose 1.33E-06 1.25E-06 1.16E-06 1.04E-06 4.80E-06 Footnotes (c)

(c)

Airborne Effluents lodines, H-3, C-14 2.92E-01 2.93E-01 2.94E-0 I 2.92E-01 1.17E+00 and Particulates Footnotes (f)

(f)

Noble Gases Beta Air (mrad)

I.

Footnotes (d)

(d)

Gamma Air (mrad) j Footnotes (d)

(d)

Direct Radiation 4.17 4.18 4.31 3.76 16.41 (e)

"Maximum" means the largest fraction of the corresponding I0CFR50, 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 from the release of H-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/Bone, at a location WNW, 2400 meters from the stack.

21

TABLE 4B Entergy Nuclear Vermont Yankee Maximum* Annual Off-Site Doses from Direct Radiation and Liquid and Gaseous Effluents for 2014 (40CFR190)

Total Body Maximum Organ Thyroid Pathway_(mrem)

(Tmrem)

(mrem)

Direct External (a) (b) 16.41 16.41 16.41 Liquids (c) 4.80E-06 4.80E-06 4.80E-06 Gases (c)'

2.35E-01 1.17E+00 2.35E-01 Annual Total (d) 16.6 17.6 16.6 The location of the projected maximum individual doses from combined direct radiation plus liquid and gaseous effluents correspond to residences at the southwest boundary relative to the Turbine Hall.

(a)

No residential shielding credit or occupancy time fraction (i.e., occupancy is assumed to be 100%)

is used. Expected direct external radiation doses would be reduced by approximately 54% with a realistic residential shielding credit and occupancy time (i.e., by using a 0.7 shielding factor from Regulatory Guide 1.109 (Reference 2) and an annual occupancy time of 6760 hours0.0782 days 1.878 hours 0.0112 weeks 0.00257 months ).

(b)

The direct dose reported here was calculated 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 Sector Site Boundary (I)

Nearest Resident(2 )

earest Milk (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 Vermont Yankee UFSAR Figure 2.2-5.

The location(s) given are based on information from the Vermont Yankee 2014 Land Use Census and are relative to the plant stack. Gardens are assumed to be present at all resident locations.

(1)

(2) 23

TABLE 4D Usage Factors for Environmental Pathways Entergy Nuclear Vermont Yankee*

Age Fish Potable Veg.

Leafy Veg.

Milk Meat Inhalation Watert Group (kg/yr)

([/yr)

(kg/yr)

(l/yr)

(kg/yr)

(m3/yr)

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

330 0

0 330 0

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

24

TABLE4E Environmental Parameters for Gaseous Effluents

Entergy Nuclear Vermont Yankee Vegetables Cow Milk Goat Milk Meat Variable Stored Leafy Pastur P asture Pasture StoredI Pasture Stored YV I Agricultural Productivity 0.70 2

0.70 2

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

Transport Time to User (hrs) 48 48 48 48 480 480 TB Soil Exposure Tilne"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 QF Animals Daily Feed (kg/day) 50 50 6

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

(b)

FS Fraction Pasture Feed When on 1

1 1

Pasture"c)

Note: Footnotes on following page.

25

TABLE 4E (Continued)

Environmental Parameters for Gaseous Effluents Entergy Nuclear Vermont Yankee Vegetables Cow Milk i

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

Absolute Humidity = 5.6 d,......

From VY ODCM, Table 6.9.1 (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 0.211 hours 0.00126 weeks 2.8918e-4 months (one year) for all pathways.

(b)

For Method 1I 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 11 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/rn3) shall be used to reflect conditions in the Northeast (

Reference:

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

26

TABLE 4F 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 2.83E-06 5.61E-04 0

2.83E-06 2.83E-06 2.83E-06 Transit Time (hrs)*

12 24 0

0 0

0 Water Uptake**

50.0 60.0 (animal) (L/day)

Feed Uptake**

50.0 50.0 (animal) (kg/day)

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

- Values are from Regulatory Guide 1.109, Table E-3 (Reference 2) 27

TABLE 5A VERMONT YANKEE JAN 14 -

DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS A CLASS FREQUENCY (PERCENT)

=

1.45 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

0 0

1 0

0 0

1 0

9 (1) 4.72

.00

.79

.00

.79

.00

.79

.00 7.09 (2)

.07

.00

.01

.00

.01

.00

.01

.00

.10 C-3 3

2 2

1 4

1 1

0 1

0 0

4 0

19 (1) 2.36 1.57 1.57

.79 3.15

.79

.00

.79

.00

.00 3.15

.00 14.96 (2)

.03

.02

.01

.05

.01

.00

.01

.00

.05

.00

.22 4-7 9

3 2

1 6

9 3

1 0

0 0

0 5

10 0

49 (1) 7.09 2.36 1.57

.79 4.72 7.09 2.36

.79

.00

.00 3.94 7.87

.00 38.58 (2)

.10

.03

.02

.01

.07

.10

.03

.01

.00

.06

.11

.00

.56 8-12 9

1 0

0 2

4 3

4 0

1 1

0 0

0 1

14 0

40 (1) 7.09

.79

.00

.00 1.57 3.15 2.36 3.15

.00

.79

.00

.79 11.02

.00 31.50 (2)

.10

.01

.00

.02

.05

.03

.05

.00

.01

.00

.01

.16

.00

.46 13-18 1

0 0

4 0

5 (1)

.79

.00

.00 3.15

.00 3.94 (2)

.01

.00

.05

.00

.06 19-24 2

0 0

0 1

2 0

5 (1) 1.57

.00

.79 1.57

.00 3.94 (2)

.02

.00

.01

.02

.00

.06 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 30 6

4 2

12 15 7

6 1

1 1

0 0

0 7

35 0

127 (1) 23.62 4.72 3.15 1.57 9.45 11.81 5.51 4.72

.79

.00

.00 5.51 27.56

.00 100.00 (2)

.34

.07

.05

.02

.14

.17

.08

.07

.01

.00

.08

.40

.00 1.45 (1)=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 5B VERMONT YANKEE JAN 14 -

DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS B CLASS FREQUENCY (PERCENT)

=

2.45 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

0 0

0 1

1 0

0 0

1 0

5 (1)

.93

.00

.47

.00

.47

.00 2.33 (2)

.02

.00

.01

.00

.01

.00

.06 C-3 1

2 0

1 3

1 1

2 2

0 0

1 0

15 (1)

.47

.93

.00

.47 1.40

.47

.93

.00

.47

.00

.47

.00 6.98 (2)

.01

.02

.00

.01

.03

.01

.02

.00

.01

.00

.01

.00

.17 4-7 15 4

7 6

9 10 7

5 5

2 1

1 2

2 3

22 0

101 (1) 6.98 1.86 3.26 2.79 4.19 4.65 3.26 2.33 2.33

.93

.47

.93

.93 1.40 10.23

.00 46.98 (2)

.17

.05

.08

.07

.10

.11

.08

.06

.02

.01

.02

.03

.25

.00 1.15 8-12 13 3

0 0

0 9

2 11 5

1 1

1 0

0 3

22 0

71 (1) 6.05 1.40

.00

.00 4.19

.93 5.12 2.33

.47

.00

.00 1.40 10.23

.00 33.02 (2)

.15

.03

.00

.10

.02

.13

.06

.01

.00

.03

.25

.00

.81 13-18 3

0 0

1 0

0 3

0 0

1 0

11 0

19 (1) 1.40

.00

.47

.00

.00 1.40

.00

.47

.00 5.12

.00 8.84 (2)

.03

.00

.01

.00

.03

.00

.01

.00

.13

.00

.22 19-24 1

0 0

0 1

2 0

4 (1)

.47

.00

.47

.93

.00 1.86 (2)

.01

.00

.01

.02

.00

.05 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 35 9

7 7

13 22 10 18 15 3

2 2

2 4

7 59 0

215 (1) 16.28 4.19 3.26 3.26 6.05 10.23 4.65 8.37 6.98 1.40

.93

.93 1.86 3.26 27.44

.00 100.00 (2)

.40

.10

.08

.15

.25

.11

.21

.17

.03

.02

.05

.08

.67.

.00 2.45 (1)=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

TABLE 5C VERMONT YANKEE JAN 14 -

DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS C CLASS FREQUENCY (PERCENT)

=

4.41 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

1 0

0 0

0 1

0 0

3 (1)

.00

.26

.00

.26

.00

.26

.00

.78 (2)

.00

.01

.00

.01

.00

.01

.00

.03 C-3 2

6 4

8 9

4 3

0 0

2 1

1 0

0 3

4 0

47 (1)

.52 1.55 1.04 2.07 2.33 1.04

.78

.00

.52

.26

.00

.78 1.04

.00 12.18 (2)

.02

.07

.05

.09

.10

.05

.03

.00

.02

.01

.00

.03

.05

.00

.54 4-7 23 7

4 10 18 25 17 13 5

2 2

3 1

2 11 30 0

173 (1) 5.96 1.81 1.04 2.59 4.66 6.48 4.40 3.37 1.30

.52

.78

.26

.52 2.85 7.77

.00 44.82 (2)

.26

.08

.05

.11

.21

.29

.19

.15

.06

.02

.03

.01

.02

.13

.34

.00 1.98 8-12 20 2

0 1

1 7

8 15 10 1

4 3

5 11 10 32 0

130 (1) 5.18

.52

.00

.26

.26 1.81 2.07 3.89 2.59

.26 1.04

.78 1.30 2.85 2.59; 8.29

.00 33.68 (2)

.23

.02

.00

.01

.08

.09

.17

.11

.01

.05

.03

.06

.13

.11

.37

.00 1.48 13-18 2

0 0

3 2

1 0

0 2

4 5

9 0

28 (1)

.52

.00

.78

.52

.26

.00

.52 1.04 1.30 2.33

.00 7.25 (2)

.02

.00

.03

.02

.01

.00

.02

.05

.06

.10

.00

.32 19-24 0

0 0

4 0

4 (1)

.00

.00 1.04

.00 1.04 (2)

.00

.05

.00

.05 GT 24 0

0 0

1 0

1 (1)

.00

.26

.00

.26 (2)

.00

.01

.00

.01 ALL SPEEDS 47 15 8

19 28 37 28 31 17 6

7 7

9 17 30 80 0

386 (1) 12.18 3.89 2.07 4.92 7.25 9.59 7.25 8.03 4.40 1.55 1.81 1.81 2.33 4.40 7.77 20.73

.00 100.00 (2)

.54

.17

.09

.22

.32

.42

.32

.35

.19

.07

.08

.10

.19

.34,

.91

.00 4.41 (1)=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

TABLE 5D VERMONT YANKEE JAN 14 -

DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT)

=

48.60 WIND DIRECTION FROM SPEED N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL MPH CALM 6

1 0

0 2

4 3

5 7

1 2

2 1

2 3

6 0

45 (1)

.14

.02

.00

.05

.09

.07

.12

.16

.02

.05

.02

.05

.07

.14

.00 1.06 (2)

.07

.01

.00

.02

.05

.03

.06

.08

.01

.02

.01

.02

.03

.07

.00

.51 C-3 79 48 45 57 59 57 53 63 61 50 48 21 40 51 79 107 0

918 (1) 1.86 1.13 1.06 1.34 1.39 1.34 1.25 1.48 1.43 1.17 1.13

.49

.94 1.20 1.86 2.51

.00 21.56 (2)

.90

.55

.51

.65

.67

.65

.61

.72

.70

.57

.55

.24

.46

.58

.90 1.22

.00 10.48 4-7 135 37 14 19 54 101 158 267 114 39 35 41 72 95 216 265 0

1662 (1) 3.17

.87

.33

.45 1.27 2.37 3.71 6.27 2.68

.92

.82

.96 1.69 2.23 5.07 6.23

.00 39.04 (2) 1.54

.42

.16

.22

.62 1.15 1.80 3.05 1.30

.45

.40

.47

.82 1.08 2.47 3.03

.00 18.97 8-12 143 7

0 0

11 27 23 144 115 23 18 30 132 192 116 241 0

1222 (1) 3.36

.16

.00

.26

.63

.54 3.38 2.70

.54

.42

.70 3.10 4.51 2.72 5.66

.00 28.71 (2) 1.63

.08

.00

.13

.31

.26 1.64 1.31

.26

.21

.34 1.51 2.19 1.32 2.75

.00 13.95 13-18 37 0

0 0

3 7

21 1

0 1

53 90 75 83 0

371 (1)

.87

.00

.07

.16

.49

.02

.00

.02 1.25 2.11 1.76 1.95

.00 8.72 (2)

.42

.00

.03

.08

.24

.01

.00

.01

.61 1.03

.86

.95

.00 4.24 19-24 2

0 0

3 3

0 0

0 1

2 8

19 0

38 (1)

.05

.00

.07

.00

.02

.05

.19

.45

.00

.89 (2)

.02

.00

.03

.00

.01

.02

.09

.22

.00

.43 GT 24 0

0 0

1 0

1 (1)

.00

.02

.00

.02 (2)

.00

.01

.00

.01 ALL SPEEDS 402 93 59 76 126 189 240 489 321 114 103 95 299 432 497 722 0

4257 (1) 9.44 2.18 1.39 1.79 2.96 4.44 5.64 11.49 7.54 2.68 2.42 2.23 7.02 10.15 11.67 16.96

.00 100.00 (2) 4.59 1.06

.67

.87 1.44 2.16 2.74 5.58 3.66 1.30 1.18 1.08 3.41 4.93 5.67 8.24

.00 48.60 (1)=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 5E VERMONT YANKEE JAN 14 -

DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT)

=

27.41 WIND DIRECTION FROM SPEED N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL MPH CALM 20 0

1 1

2 1

5 3

3 1

7 4

6 5

4 2

0 65 (1)

.83

.00

.04

.08

.04

.21

.12

.04

.29

.17

.25

.21

.17

.08

.00 2.71 (2)

.23

.00

.01

.02

.01

.06

.03

.01

.08

.05

.07

.06

.05

.02

.00

.74 C-3 56 20 31 18 19 27 36 60 106 119 172 149 140 137 120 89 0

1299 (1) 2.33

.83 1.29

.75

.79 1.12 1.50 2.50 4.41 4.96 7.16 6.21 5.83 5.71 5.00 3.71

.00 54.10 (2)

.64

.23

.35

.21

.22

.31

.41

.69 1.21 1.36 1.96 1.70 1.60 1.56 1.37 1.02

.00 14.83 4-7 48 4

0 1

12 16 59 95 62 21 21 29 54 53 112 145 0

732 (1) 2.00

.17

.00

.04

.50

.67 2.46 3.96 2.58

.87

.87 1.21 2.25 2.21 4.66 6.04

.00 30.49 (2)

.55

.05

.00

.01

.14

.18

.67 1.08

.71

.24

.33

.62

.61 1.28 1.66

.00 8.36 8-12 19 0

0 0

0 1

9 35 28 0

3 4

35 26 27 67 0

254 (1)

.79

.00

.04

.37 1.46 1.17

.00

.12

.17 1.46 1.08 1.12 2.79

.00 10.58 (2)

.22

.00

.01

.10

.40

.32

.00

.03

.05

.40

.30

.31

.76

.00 2.90 13-18 9

0 0

2 8

0 0

0 6

6 7

12 0

50 (1)

.37

.00

.08

.33

.00

.25

.29

.50

.00 2.08 (2)

.10

.00

.02

.09

.00

.07

.08

.14

.00

.57 19-24 0

0 0

0 1

0 0

1 (1)

.00

.04

.00

.04 (2)

.00

.01

.00

.01 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 152 24 32 20 33 45 109 195 208 141 203 186 241 227 270 315 0

2401 (1) 6.33 1.00 1.33

.83 1.37 1.87 4.54 8.12 8.66 5.87 8.45 7.75 10.04 9.45 11.25 13.12

.00 100.00 (2) 1.74

.27

.37

.23

.38

.51 1.24 2.23 2.37 1.61 2.32 2.12 2.75 2.59 3.08 3.60

.00 27.41 (1)=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 14 -

DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT)

=

11.94 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

1 5

2 1

1 0

12 (1)

.00

.10

.48

.19

.10

.00

.10

.00 1.15 (2)

.00

.01

.06

.02

.01

.00

.01

.00

.14 C-3 28 12 8

14 9

3 17 27 55 90 167 179 151 72 51 24 0

907 (1) 2.68 1.15

.76 1.34

.86

.29 1.63 2.58 5.26 8.60 15.97 17.11 14.44 6.88 4.88 2.29

.00 86.71 (2)

.32

.14

.09

.16

.10

.03

.19

.31

.63 1.03 1.91 2.04 1.72

.82

.58

.27

.00 10.36 4-7 3

2 0

0 1

4 3

12 12 12 18 9

12 17 11 10 0

126 (1)

.29

.19

.00

.10

.38

.29 1.15 1.15 1.15 1.72

.86 1.15 1.63 1.05

.96

.00 12.05 (2)

.03

.02

.00

.01

.05

.03

.14

.21

.10

.14

.19

.13

.11

.00 1.44 8-12 0

0 0

1 0

0 0

1 (1)

.00

.10

.00

.10 (2)

.00

.01

.00

.01 13-18 0

0 0

0 (1)

.00

.00 (2)

.00

.00 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 31 14 8

14 10 7

20 39 68 103 190 190 164 91 62 35 0

1046 (1) 2.96 1.34

.76 1.34

.96

.67 1.91 3.73 6.50 9.85 18.16 18.16 15.68 8.70 5.93 3.35

.00 100.00 (2)

.35

.16

.09

.16

.11

.08

.23

.45

.78 1.18 2.17 2.17 1.87 1.04

.71

.40

.00 11.94 (1)=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

TABLE 5G VERMONT YANKEE JAN 14 -

DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 35.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT)

=

3.73 WIND DIRECTION FROM SPEED N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL MPH CALM 1

1 0

0 1

1 0

0 0

2 0

0 0

6 (1)

.31

.00

.31

.00

.61

.00

.00 1.83 (2)

.01

.00

.01

.00

.02

.00

.07 C-3 15 6

7 2

6 5

6 11 14 26 43 50 36 17 16 11 0

271 (1) 4.59 1.83 2.14

.61 1.83 1.53 1.83 3.36 4.28 7.95 13.15 15.29 11.01 5.20 4.89 3.36

.00 82.87 (2)

.17

.07

.08

.02

.07

.06

.07

.13

.16

.30

.49

.57

.41

.19

.18

.13

.00 3.09 4-7 2

0 0

2 8

4 8

1 3

4 10 6

0 48 (1)

.61

.00

.61 2.45 1.22 2.45

.31

.92 1.22 3.06 1.83

.00 14.68 (2)

.02

.00

.02

.09

.05

.09

.01

.03

.05

.11

.07

.00

.55 8-12 0

0 0

0

.0 0

1 1

0 2

(1)

.00

.31

.00

.61 (2)

.00

.01

.00

.02 13-18 0

0 0

0 (1)

.00

.00 (2)

.00

.00 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 18 7

7 2

7 6

6 13 22 32 51 51 39 21 27 18 0

327 (1) 5.50 2.14 2.14

.61 2.14 1.83 1.83 3.98 6.73 9.79 15.60 15.60 11.93 6.42 8.26 5.50

.00 100.00 (2)

.21

.08

.02

.08

.07

.15

.25

.37

.58

.45

.24

.31

.21

.00 3.73 (1)=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 5H VERMONT YANKEE JAN 14 -

DEC 14 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 35 2

1 1

6 9

8 9

11 5

14 8

9 8

8 11 0

145 (1)

.40

.02

.01

.07

.10

.09

.10

.13

.06

.16

.09

.10

.09

.13

.00 1.66 (2)

.40

.02

.01

.07

.10

.09

.10

.13

.06

.16

.09

.10

.09

.13

.00 1.66 C-3 184 96 97 101 109 98 117 163 239 287 431 400 367 278 269 240 0

3476 (1) 2.10 1.10 1.11 1.15 1.24 1.12 1.34 1.86 2.73 3.28 4.92 4.57 4.19 3.17 3.07 2.74

.00 39.68 (2) 2.10 1.10 1.11 1.15 1.24 1.12 1.34 1.86 2.73 3.28 4.92 4.57 4.19 3.17 3.07 2.74

.00 39.68 4-7 235 57 27 37 100 165 247 395 206 80 85 84 144 173 368 488 0

2891 (1) 2.68

.65

.31

.42 1.14 1.88 2.82 4.51 2.35

.91

.97

.96 1.64 1.98 4.20 5.57

.00 33.01 (2) 2.68

.65

.31

.42 1.14 1.88 2.82 4.51 2.35

.91

.97

.96 1.64 1.98 4.20 5.57

.00 33.01 8-12 204 13 0

1 14 48 45 209 158 26 27 38 172 230 158 377 0

1720 (1) 2.33

.15

.00

.01

.16

.55

.51 2.39 1.80

.30

.31

.43 1.96 2.63 1.80 4.30

.00 19.64 (2) 2.33

.15

.00

.01

.16

.55

.51 2.39 1.80

.30

.31

.43 1.96 2.63 1.80 4.30

.00 19.64 13-18 52 0

0 0

0 1

3 12 34 2

0 1

61 101 87 119 0

473 (1)

.59

.00

.01

.03

.14

.39

.02

.00

.01

.70 1.15

.99 1.36

.00 5.40 (2)

.59

.00

.01

.03

.14

.39

.02

.00

.01

.70 1.15

.99 1.36

.00 5.40 19-24 5

0 0

3 4

0 0

0 1

2 10 27 0

52 (1)

.06

.00

.03

.05

.00

.01

.02

.11

.31

.00

.59 (2)

.06

.00

.03

.05

.00

.01

.02

.11

.31

.00

.59 GT 24 0

0 0

2 0

2 (1)

.00

.02

.00

.02 (2)

.00

.02

.00

.02 ALL SPEEDS 715 168 125 140 229 321 420 791 652 400 557 531 754 792 900 1264 0

8759 (1) 8.16 1.92 1.43 1.60 2.61 3.66 4.80 9.03 7.44 4.57 6.36 6.06 8.61 9.04 10.28 14.43

.00 100.00 (2) 8.16 1.92 1.43 1.60 2.61 3.66 4.80 9.03 7.44 4.57 6.36 6.06 8.61 9.04 10.28 14.43

.00 100.00 (1)=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

TABLE 6A VERMONT YANKEE JAN 14 DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS A

CLASS FREQUENCY (PERCENT)

.07 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

4 (1) 66.67

.00

.00 66.67 (2)

.05

.00

.05 C-3 0

0 0

1 0

0 0

1 (1)

.00

.00 16.67

.00

.00 16.67 (2)

.00

.01

.00

.01 4-7 0

0 0

0 (1)

.00

.00 (2)

.00

.00 8-12 0

0 0

0 1

0 0

1 (1)

.00

.00 16.67

.00

.00 16.67 (2)

.00

.01

.00

.01 13-18 0

0 0

0 (1)

.00

.00 (2)

.00

.00 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 4

0 0

1 0

0 0

0 1

0 0

6 (1) 66.67

.00

.00 16.67

.00

.00 16.67

.00

.00 100.00 (2)

.05

.00

.01

.00

.01

.00

.07 (1)=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

TABLE 6B VERMONT YANKEE JAN 14 -

DEC 14 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 MPN CALM 0

0 0

1 0

0 0

1 (1)

.00

.00 5.00

.00

.00 5.00 (2)

.00

.01

.00

.01 C-3 1

0 0

0 1

0 0

0 1

0 0

4 (1) 5.00

.00

.00 5.00

.00

.00 5.00

.00

.00 20.00 (2)

.01

.00

.01

.00

.01

.00

.01

.00

.05 4-7 0

0 1

0 0

1 2

0 0

4 (1)

.00

.00 5.00

.00

.00 5.00 10.00

.00

.00 20.00 (2)

.00

.01

.00

.01

.02

.00

.05 8-12 1

0 0

1 1

1 0

0 0

1 0

6 (1) 5.00

.00

.00 5.00 5.00 5.00

.00 5.00

.00

.00 5.00

.00 30.00 (2)

.01

.00

.01

.00

.01

.00

.01

.00

.07 13-18 1

0 0

0 1

0 0

1 0

3 (1) 5.00

.00

.00 5.00

.00

.00 5.00

.00 15.00 (2)

.01

.00

.01

.00

.01

.00

.03 19-24 0

0 0

1 0

1 (1)

.00

.00 5.00

.00 5.00 (2)

.00

.01

.00

.01 GT 24 0

0 0

1 0

1 (1)

.00

.00 5.00

.00 5.00 (2)

.00

.01

.00

.01 ALL SPEEDS 3

0 1

1 2

3 3

1 1

0 0

0 1

4 0

20 (1) 15.00

.00 5.00 5.00 10.00 15.00 15.00 5.00 5.00

.00

.00 5.00 20.00

.00 100.00 (2)

.03

.00

.01

.02

.03

.01

.00

.01

.05

.00

.23 (1)=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

TABLE 6C VERMONT YANKEE JAN 14 DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS C

CLASS FREQUENCY (PERCENT)

=

1.18 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

2 (1)

.00

.97

.00

.97

.00

.00 1.94 (2)

.00

.01

.00

.01

.00

.02 C-3 2

0 1

1 0

0 0

0 1

1 0

8 (1) 1.94

.00

.97

.00

.97

.00

.97

.00

.97

.00 7.77 (2)

.02

.00

.01

.00

.01

.00

.01

.00

.01

.00

.09 4-7 3

2 0

4 4

9 3

1 0

0 0

1 0

0 0

1 0

28 (1) 2.91 1.94

.00 3.88 3.88 8.74 2.91

.97

.00

.97

.00

.97

.00 27.18 (2)

.03

.02

.00

.05

.10

.03

.01

.00

.01

.00

.01

.00

.32 8-12 5

3 0

0 1

8 2

6 3

0 0

0 2

10 0

40 (1) 4.85 2.91

.00

.97 7.77 1.94 5.83 2.91

.00

.00 1.94 9.71

.00 38.83 (2)

.06

.03

.00

.01

.09

.02

.07

.03

.00

.02

.11

.00

.46 13-18 5

1 0

0 0

2 0

1 0

0 0

0 1

4 0

14 (1) 4.85

.97

.00

.00 1.94

.00

.97

.00

.97 3.88

.00 13.59 (2)

.06

.01

.00

.02

.00

.01

.00

.01

.05

.00

.16 19-24 0

0 0

1 0

0 0

6 0

7 (1)

.00

.97

.00

.00 5.83

.00 6.80 (2)

.00

.01

.00

.07

.00

.08 GT 24 0

0 0

4 0

4 (1)

.00

.00 3.88

.00 3.88 (2)

.00

.05

.00

.05 ALL SPEEDS 15 6

1 4

6 20 5

9 4

1 0

0 5

26 0

103 (1) 14.56 5.83

.97 3.88 5.83 19.42 4.85 8.74 3.88

.97

.00

.97

.00

.00 4.85 25.24

.00 100.00 (2)

.17

.07

.01

.05

.07

.23

.06

.10

.05

.01

.00

.01

.00

.06

.30

.00 1.18 (1)=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

TABLE 6D VERMONT YANKEE JAN 14 -

DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT)

=

55.39 WIND DIRECTION FROM SPEED N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL MPH CALM 11 0

2 1

4 3

1 7

12 4

6 11 15 3

2 40 0

122 (1)

.23

.00

.04

.02

.08

.06

.02

.14

.25

.08

.12

.23

.31

.06

.04

.82

.00 2.51 (2)

.13

.00

.02

.01

.05

.03

.01

.08

.14

.05

.07

.13

.17

.03

.02

.46

.00 1.39 C-3 50 39 41 39 45 50 58 47 18 18 12 8

9 19 29 61 0

543 (1) 1.03

.80

.85

.80

.93 1.03 1.20

.97

.37

.25

.16

.19

.39

.60 1.26

.00 11.19 (2)

.57

.45

.47

.45

.51

.57

.66

.54

.21

.14

.09

.10

.22

.33

.70

.00 6.20 4-7 102 40 31 24 47 80 143 162 84 31 21 19 27 40 70 282 0

1203 (1) 2.10

.82

.64

.49

.97 1.65 2.95 3.34 1.73

.64

.43

.39

.56

.82 1.44 5.81

.00 24.79 (2) 1.16

.46

.35

.27

.54

.91 1.63 1.85

.96

.35

.24

.22

.31

.46

.80 3.22

.00 13.73 8-12 123 19 7

8 11 48 92 201 229 48 40 39 106 145 99 299 0

1514 (1) 2.54

.39

.14

.16

.23

.99 1.90 4.14 4.72

.99

.82

.80 2.18 2.99 2.04 6.16

.00 31.20 (2) 1.40

.22

.08

.09

.13

.55 1.05 2.29 2.61

.55

.46

.45 1.21 1.66 1.13 3.41

.00 17.29 13-18 125 7

0 1

5 15 16 52 129 17 10 17 ii 187 79 296 0

1067 (1) 2.58

.14

.00

.02

.10

.31

.33 1.07 2.66

.35

.21

.35 2.29 3.85 1.63 6.10

.00 21.99 (2) 1.43

.08

.00

.01

.06

.17

.18

.59 1.47

.19

.11

.19 1.27 2.13

.90 3.38

.00 12.18 19-24 48 0

0 0

0 1

2 6

40 2

0 1

25 50 37 123 0

335 (1)

.99

.00

.02

.04

.12

.82

.04

.00

.02

.52 1.03

.76 2.54

.00 6.90 (2)

.55

.00

.01

.02

.07

.46

.02

.00

.01

.29

.57

.42 1.40

.00 3.82 GT 24 5

0 0

0 8

0 0

0 1

1 6

47 0

68 (1)

.10

.00

.16

.00

.02

.12

.97

.00 1.40 (2)

.06

.00

.09

.00

.01

.07

.54

.00

.78 ALL SPEEDS 464 105 81 73 112 197 312 475 520 120 89 95 294 445 322 1148 0

4852 (1) 9.56 2.16 1.67 1.50 2.31 4.06 6.43 9.79 10.72 2.47 1.83 1.96 6.06 9.17 6.64 23.66

.00 100.00 (2) 5.30 1.20

.92

.83 1.28 2.25 3.56 5.42 5.94 1.37 1.02 1.08 3.36 5.08 3.68 13.11

.00 55.39 (1)=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

TABLE 6E VERMONT YANKEE JAN 14 -

DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (PERCENT)

=

30.45 WIND DIRECTION FROM SPEED N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW VRBL TOTAL MPH CALM 23 1

2 1

1 4

7 4

3 0

2 1

1 13 0

66 (1)

.86

.04

.07

.04

.15

.26

.15

.11

.00

.11

.00

.07

.04

.49

.00 2.47 (2)

.26

.01

.02

.01

.05

.08

.05

.03

.00

.03

.00

.02

.01

.15

.00

.75 C-3 95 71 58 59 62 81 92 49 29 20 16 11 8

23 36 94 0

804 (1) 3.56 2.66 2.17 2.21 2.32 3.04 3.45 1.84 1.09

.75

.60

.41

.30

.86 1.35 3.52

.00 30.15 (2) 1.08

.81

.66

.67

.71

.92 1.05

.56

.33

.23

.18

.13

.09

.26

.41 1.07

.00 9.18 4-7 102 11 4

4 18 38 116 146 61 23 11 21 25 32 69 256 0

937 (1) 3.82

.41

.15

.67 1.42 4.35 5.47 2.29

.86

.41

.79

.94 1.20 2.59 9.60

.00 35.13 (2) 1.16

.13

.05

.21

.43 1.32 1.67

.70

.26

.13

.24

.29

.37

.79 2.92

.00 10.70 8-12 41 3

0 1

0 9

29 86 68 19 11 16 54 43 54 178 0

612 (1) 1.54

.11

.00

.04

.00

.34 1.09 3.22 2.55

.71

.41

.60 2.02 1.61 2.02 6.67

.00 22.95 (2)

.47

.03

.00

.01

.00

.10

.33

.98

.78

.22

.13

.18

.62

.49

.62 2.03

.00 6.99 13-18 10 0

0 0

3 13 36 2

6 4

30 20 20 58 0

202 (1)

.37

.00

.11

.49 1.35

.07

.22

.15 1.12

.75

.75 2.17

.00 7.57 (2)

.11

.00

.03

.15

.41

.02

.07

.05

.34

.23

.66

.00 2.31 19-24 3

0 0

3 4

1 0

0 6

3 6

16 0

42 (1)

.11

.00

.11

.15

.04

.00

.22

.11

.22

.60

.00 1.57 (2)

.03

.00

.03

.05

.01

.00

.07

.03

.07

.18

.00

.48 GT 24 0

0 0

1 1

2 0

4 (1)

.00

.04

.07

.00

.15 (2)

.00

.01

.02

.00

.05 ALL SPEEDS 274 86 64 65 81 132 247 301 201 65 47 52 125 123 187 617 0

2667 (1) 10.27 3.22 2.40 2.44 3.04 4.95 9.26 11.29 7.54 2.44 1.76 1.95 4.69 4.61 7.01 23.13

.00 100.00 (2) 3.13

.98

.73

.74

.92 1.51 2.82 3.44 2.29

.74

.54

.59 1.43 1.40 2.13 7.04

.00 30.45 (1)=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

TABLE 6F VERMONT YANKEE JAN 14 -

DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT)

=

10.81 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

1 1

0 3

1 4

3 1

2 0

0 0

2 1

0 0

24 (1)

.53

.11

.00

.32

.11

.42

.32

.11

.21

.00

.21

.11

.00

.00 2.53 (2)

.06

.01

.00

.03

.01

.05

.03

.01

.02

.00

.02

.01

.00

.27 C-3 42 31 22 25 39 34 46 30 16 4

18 8

12 18 19 34 0

398 (1) 4.44 3.27 2.32 2.64 4.12 3.59 4.86 3.17 1.69

.42 1.90

.84 1.27 1.90 2.01 3.59

.00 42.03 (2)

.48

.35

.25

.29

.45

.39

.53

.34

.18

.05

.21

.09

.14

.21

.22

.39

.00 4.54 4-7 39 4

2 3

4 22 57 55 24 15 15 10 15 21 35 63 0

384 (1) 4.12

.42

.21

.32

.42 2.32 6.02 5.81 2.53 1.58 1.58 1.06 1.58 2.22 3.70 6.65

.00 40.55 (2)

.45

.05

.02

.03

.05

.25

.65

.63

.27

.17

.11

.17

.24

.40

.72

.00 4.38 8-12 7

0 0

2 10 20 9

6 3

2 15 13 10 32 0

129 (1)

.74

.00

.21 1.06 2.11

.95

.63

.32

.21 1.58 1.37 1.06 3.38

.00 13.62 (2)

.08

.00

.02

.11

.23

.10

.07

.03

.02

.17

.15

.11

.37

.00 1.47 13-18 1

0 0

0 2

2 1

1 1

2 0

12 (1)

.11

.00

.21

.11

.21

.00 1.27 (2)

.01

.00

.02

.01

.02

.00

.14 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 94 36 25 28 46 59 117 108 52 29 37 21 43 55 66 131 0

947 (1) 9.93 3.80 2.64 2.96 4.86 6.23 12.35 11.40 5.49 3.06 3.91 2.22 4.54 5.81 6.97 13.83

.00 100.00 (2) 1.07

.41

.29

.32

.53

.67 1.34 1.23

.59

.33

.42

.24

.49

.63

.75 1.50

.00 10.81 (1)=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) 41

TABLE 6G VERMONT YANKEE JAN 14 -

DEC 14 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS G CLASS FREQUENCY (PERCENT)

=

1.87 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

1 (1)

.00

.61

.00

.61 (2)

.00

.01

.00

.01 C-3 4

1 4

1 2

3 4

4 4

2 2

2 1

4 3

6 0

47 (1) 2.44

.61 2.44

.61 1.22 1.83 2.44 2.44 2.44 1.22 1.22 1.22

.61 2.44 1.83 3.66

.00 28.66 (2)

.05

.01

.05

.01

.02

.03

.05

.02

.01

.05

.03

.07

.00

.54 4-7 4

0 0

0 5

12 9

3 8

11 6

3 4

7 0

72 (1) 2.44

.00

.00 3.05 7.32 5.49 1.83 4.88 6.71 3.66 1.83 2.44 4.27

.00 43.90 (2)

.05

.00

.06

.14

.10

.03

.09

.13

.07

.03

.05

.08

.00

.82 8-12 1

0 0

0 5

6 4

4 5

3 3

5 4

1 0

41 (1)

.61

.00

.00 3.05 3.66 2.44 2.44 3.05 1.83 1.83 3.05 2.44

.61

.00 25.00 (2)

.01

.00

.06

.07

.05

.06

.03

.06

.05

.01

.00

.47 13-18 1

0 0

0 1

1 0

0 0

3 (1)

.61

.00

.61

.00

.00 1.83 (2)

.01

.00

.01

.00

.03 19-24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 GT 24 0

0 0

0 (1)

.00

.00 (2)

.00

.00 ALL SPEEDS 10 1

4 1

2 3

14 22 18 10 15 16 10 12 12 14 0

164 (1) 6.10

.61 2.44

.61 1.22 1.83 8.54 13.41 10.98 6.10 9.15 9.76 6.10 7.32 7.32 8.54

.00 100.00 (2)

.11

.01

.05

.01

.02

.03

.16

.25

.21

.11

.17

.18

.11

.14

.16

.00 1.87 (1)=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

TABLE 6H VERMONT YANKEE JAN 14 -

DEC 14 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 43 2

5 2

8 9

12 14 17 6

9 11 17 6

6 53 0

220 (1)

.49

.02

.06

.02

.09

.10

.14

.16

.19

.07

.10

.13

.19

.07

.61

.00 2.51 (2)

.49

.02

.06

.02

.09

.10

.14

.16

.19

.07

.10

.13

.19

.07

.61

.00 2.51 C-3 194 142 126 124 150 170 201 131 67 44 48 29 30 64 89 196 0

1805 (1) 2.21 1.62 1.44 1.42 1.71 1.94 2.29 1.50

.76

.50

.55

.33

.34

.73 1.02 2.24

.00 20.61 (2) 2.21 1.62 1.44 1.42 1.71 1.94 2.29 1.50

.76

.50

.55

.33

.34

.73 1.02 2.24

.00 20.61 4-7 250 57 38 35 73 150 326 376 178 72 55 62 73 96 178 609 0

2628 (1) 2.85

.65

.43

.40

.83 1.71 3.72 4.29 2.03

.82

.63

.71

.83 1.10 2.03 6.95

.00 30.00 (2) 2.85

.65

.43

.40

.83 1.71 3.72 4.29 2.03

.82

.63

.71

.83 1.10 2.03 6.95

.00 30.00 8-12 178 25 7

10 13 68 138 320 313 77 59 60 178 206 170 521 0

2343 (1) 2.03

.29

.08

.11

.15

.78 1.58 3.65 3.57

.88

.67

.69 2.03 2.35 1.94 5.95

.00 26.75 (2) 2.03

.29

.08

.11

.15

.78 1.58 3.65 3.57

.88

.67

.69 2.03 2.35 1.94 5.95

.00 26.75 13-18 143 8

0 1

5 17 19 66 169 22 17 22 142 208 101 361 0

1301 (1) 1.63

.09

.00

.01

.06

.19

.22

.75 1.93

.25

.19

.25 1.62 2.37 1.15 4.12

.00 14.85 (2) 1.63

.09

.00

.01

.06

.19

.22

.75 1.93

.25

.19

.25 1.62 2.37 1.15 4.12

.00 14.85 19-24 51 0

0 0

0 1

2 9

44 4

0 1

31 53 43 146 0

385 (1)

.58

.00

.01

.02

.10

.50

.05

.00

.01

.35

.61

.49 1.67

.00 4.40 (2)

.58

.00

.01

.02

.10

.50

.05

.00

.01

.35

.61

.49 1.67

.00 4.40 GT 24 5

0 0

0 8

0 0

0 1

2 7

54 0

77 (1)

.06

.00

.09

.00

.01

.02

.08

.62

.00

.88 (2)

.06

.00

.09

.00

.01

.02

.08

.62

.00

.88 ALL SPEEDS 864 234 176 172 249 415 698 916 796 225 188 185 472 635 594 1940 0

8759 (1) 9.86 2.67 2.01 1.96 2.84 4.74 7.97 10.46 9.09 2.57 2.15 2.11 5.39 7.25 6.78 22.15

.00 100.00 (2) 9.86 2.67 2.01 1.96 2.84 4.74 7.97 10.46 9.09 2.57 2.15 2.11 5.39 7.25 6.78 22.15

.00 100.00 (1)=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 1A.

ODCM DOSE AND DOSE RATE LIMITS -

ODCM Controls Dose Limit

a.

Noble Gases 3/4.3.1 3/4.3.1 3/4.3.2 3/4.3.2 3/4.3.2 3/4.3.2 Total body dose rate Skin dose rate Gamma air dose Gamma air dose Beta air dose Beta air dose 500 mrem/yr 3000 mrem/yr 5 mrad in a quarter 10 mrad in a year 10 mrad in a quarter 20 mrad in a year

b.

lodine-131, lodine-1 33, Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 3/4.3.1 3/4.3.3 3/4.3.3 Organ dose rate Organ dose Organ dose 1500 mrem/yr 7.5 mrem in a quarter 15 mrem in a year

c.

Liquids 3/4.2.2 Total body dose 3/4.2.2 Total body dose 3/4.2.2 Organ dose 3/4.2.2 Organ dose 1.5 mrem in a quarter 3 mrem in a year 5 mrem in a quarter 10 mrem in a year 2A.

ODCM LIMITS - CONCENTRATION ODCM Control

a.

Noble Gases Limit No ECL Limits

b.

lodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days No ECL Limits A-I

c.

Liquids 3/4.2.1 Sum of the fractions of ECL excluding noble gases (IOCFR20, Appendix B, Table 2, Column 2):

< 1.OE+01 3/4.2.1 Total noble gas concentration:

< 2E-04 jiCi/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 l B and the totals of Table IA. The error involved in these steps may be approximately +/-23 percent.

b.

lodines 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.

Waste Oil Prior to issuing the permit to bum 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 of radioactive liquid effluents released. For each batch, station records are retained of the total activity (mCi) released, concentration (jiCi/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 gamma isotopic 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.

Liquid

1) In 2014 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 2014, the total Tritium radioactivity conservatively estimated to be released to the Connecticut River is 0.0454 Curies. No other plant-related radionuclides were detected in ground water.

b.

Gaseous There was one unplanned gaseous ground-level release (measured) during the reported period. On April 17, 2014, during a maintenance activity in the drain pit of the Advanced Offgas system, there was a brief 4-hour release of 2.80E-03 Ci of H-3.

A-4

APPENDIX B LIQUID HOLDUP TANKS Requirement

Response

Technical Specification 3.8.D. I 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 3.8.D. 1, 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 3.8.D.1 were not exceeded during this reporting period.

B-I

APPENDIX C 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 next 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.

C-1

APPENDIX D 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 10. 1.

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

APPENDIX E Requirement:

Response

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 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).

The Brown Farm in Vernon, Vermont (formerly REMP sampling location TM-

14) ceased dairy operations and milk production. The farm is currently engaged in equestrian activities in lieu of milk production. The former control location, County Farm (TM-24) also ceased operations and is no longer providing milk samples. No additional farms were added to the REMP program due to the forecast and now shutdown status of the plant. The following page shows the update to Table 7.1 of the ODCM showing the removal of these locations from the list Radiological Environmental Monitoring Stations. The maps in the ODCM continue to show the location of these farms for historical purposes.

E-1

I'ahlu 7.1 Radiolomzica) 1;virojuiciietal kionitoriuiu Statioiis~'t Exposure P~athiway and/or Sainple DirectionM 5

SamnpleLI ocationl mnd Desisnated Code (b l')i,-lance (kin)l 5,

AIRBORNE (Radioiodinie and Particulate)

AP/CF-I1 River Station No. 3-3 APfCF-12 N. Hinsdale, NH-

..\\I'CF-13 Hinsdale Substation AP/CF-14 Noillifield, MA'9)

A1/CF-15 Tyler Hill Road"')

AP/CF-21 Spoftord Lake('A

2.

WATERBORNE

a. Surface WR-1 1 River Station No. 3-3 WR-21 Rt. 9 Bridge()

1.88 3.61 3.05 11.61 3.14 16.36 SSE NNW E

SSE WNW NNE 1.88 Downriver 1 1.83 Upriver b, Ground WG-1 I WG-12 WG-13 WG-14 WG-22 Plant Well Vernon Nursing Well COB well(,)

Plant Support Bldg Well"'

Copeland WellO>

0.24 2.13 0.26 0.27 13.73 On-Site SSE On-Site On-Site N

e. Sediment From Shoreline SE-11 Shoreline Downriver SE-12 North Storm Drain Out fall(3) 0.57 SSE 0.13 1

3.

INGESTION

a. NilIk '

m TN-11 NMiller Farm TM-I18 Blodgett Faaim TM-22 Franklin Farm(4) 0.82 W

3.60 SE 9.73 WSW I

b, Mixed T-I I Grasses T'G-12

'I'-13 TG-14 TG-15 River Station No. 3-3 N. Hinsdale, NH Hinsdale Substation Nortlhfield. MA" Tyler Hill Rd.(")

1.88 3.61 3.05 11.61 3.07 SSE NNW E

SSE WNW Otf-Sie Doso Calculation Manual Seclion 7 Rev. 35 Page 4 ot 12 Vermont Yankee Nuclear Power Station E-2

Exposune Palhway and/or Simptle C. Silage TABLE 7.1 (Continued)

TG-21 Spofford LakeP Sample Location Distance mid Desipnated Codet '

T[C-i 1 Miller Farn TC-18 16.36 NNE 0.82 W

Blodgett Fann 3.60 9.73 WSW (6)

(6) 11.83 Upriver SE TC(-22 Franklin Farnu)

d. Fish F11-1Il Vertimn Pond FH-21 Rt. 9 IRridge'!9 )

4.

DIRECT RA DIATION DR-]

DR-2 DR-3 l)R-4 DR-5 l)R-6 1)R-7 I)R-8 I)R-9 DR-10 DR-ITI DR-12 DR-13 DR-14 DR-I15 DR-.16 DR-17 DR-18 I)R-19 DR-*20 DR-21 DR-22 DR-23 DR-24 i)R-25 River Station No. 3-3 N. Hinsdale, NIT Hinsdale Substation Norlhlield, MAX9 Spolford L.ake M Vernon School Site Boundary(7)

Site Boundary Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring hiner Ring Outer Ring inner Ring Outer Ring Tiroer Ring Outer Ring Imner Ring Outer Ring himer Ring Outer Ring Inner Ring 1.61 3.88 2.98 11.34 16.53 0.52 0.28 0.25 1.72 4.49 1.65 3.58 1.23 3.88 1.46 2.84 1.24 2.97 3.65 5.33 I.S2 3.28 1.96 3.89 1.91 SSE NNW E

SSE NNE WSW W

SSW N

N NNE NNE NE NE ENE ENE E

E

[SE ESE SE SE SSE SSE S

Off-Sihe Dose Calculafion Manual Section 7 Rev. 35 Page 5 of 12 Vermont Yankee Nuclear Power Station E-3

TABLE 7.1 (Continued)

Exlnosure Pathwvay and/for Samnle Dircefion' 5)

Sample I A)Catiofl muid Dosipti'ated Code~z' Distance DIZ-26 DR-27 DR-28 l)R-29 DR-3t)

DR-31I l)R-32 1)R-33 DR-34

[)R-35 DR-36 DR-37 DR-38 DR-39 l)R-40 Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer R ing Inner Ring Outer Ring.

Inner Ring Outer Ring Inner Ring Outer Ring 3.77 1.10 2.23 0.92 2.36 0371 5.09 0.66 4.61

.1.30 4.43 2.76 7.34 3.13 5.05 S

SSW sSSW SIX SW WSW WSW WVNW W

WNW WVNW NW NWV NNW NN W (I)

Sample locations are shown on Figures 7.1 to 7.6.

(2)

Station Nos. 10 through 19 are indicator stations. Station Nos. 20 through 29 are control stations (tro all except milk, silage and the direct radiation stations).

(3)

To be sampled and analyzed semiannually.

(4)

(5)

Non-requircd Control station.

Distatce and direction firom the center of the Turbine, Building for direct radiation monitors-from the plant stack for all others.

(6)

Fish samples are collected from anywhere in Vernon Pond, which is adjacent to the plant (see F:igure 7-1).

(7)

DR-7 satisfies Control 'fable 3.5.1 for an inner ring direct radiation monitoring location.

However. it is averaged as a Site Boundaryv TLD due to its close proximity to the plant.

(8)

In accordance with Control Table 3.5. 1. notation a., samples will be collected on the required schedule as availability of milk permits. All deviations from the sample schedule will he reported in the Annual Radiological Environmental Operating Report.

(9)

Control stations Off-Sile Dosu Calculation Manual Section 7 Rev. 35 Page 6 of 12 Vermont Yankee Nuclear Power Station E-4

APPENDIX F LAND USE CENSUS Requirement:

Response

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.

The Land Use Census was completed during the third quarter of 2014. 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.

F-I

APPENDIX G PROCESS CONTROL PROGRAM Requirement:

Response

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.

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

G-I

APPENDIX H 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

During the reporting period, Revision 35 was made to the ODCM.

The major changes included in Revision 35 to the ODCM were:

Section 3/4 was revised to delete a reference requirement to Note 5 in Section 2 of Table 3.1.2 (Gaseous Effluent Monitoring Instrumentation). It was determined that Note 5 was in conflict with Note 2 for Section 2 and therefore should be removed as a requirement for Section 2 (CR-VTY-2013-04078 CA-0002).

In Sections 2, 3/4, 6, 8 and 10, the word "operable" was found to be inappropriate and was replaced by the word "functional". Additionally, the word "inoperable" was replaced with the word "non-functional" and the word "operability" was replaced by "functionality" (EN-OP-104 and NRC Inspection Guide 9900) (CR-VTY-2013-04078 CA-0002).

In the tables of Section 7 of the Offsite Dose Calculation Manual, it was determined that the out-of-business dairy farms which had provided milk for the REMP but were no longer functional, should be eliminated from the description (WT-WTVTY-201 I-00116).

Section 9 of the Offsite Dose Calculation Manual was revised to eliminate the references to the Off Gas "30 minute" delay line. This was previously evaluated under CR-VTY-2010-1676 and it was determined that the reference to the "30 minute" should be removed. (WT-WTVTY-2009-00009 CA-00 10).

The revised ODCM pages have been included in the following pages of this Appendix.

H-I

REVISION

SUMMARY

(Continued) 7/08/2011 34 Four main sections of the ODCM were modified with significant changes to incorporate the contaminated groundwater discharge pathway to the Connecticut River:

o Section 3 / 4 was revised to include the subsurface groundwater pathway in the Liquids Discharge description.

Groundwater monitoring wells used to determine the extent of these releases are listed. The Southwest Well was added as Ground (Potable Drinking) Water sample location in the REMP description of Section 3 / 4.

o Section 5 was revised to include a description of the determination of plant generated radionuclide concentrations in groundwater discharges.

o Section 6 was revised to include methods for calculating radiation dose from plant generated radionuclides in groundwater discharges.

o Section 9 was revised to include the method for determination of groundwater flows in the 17 identified streamtubes flowing from the plant site to the Connecticut River.

In addition to revisions of four main sections of the ODCM, the Table of Contents, Definitions and References Sections of the ODCM were revised to reflect the additional subsections, figures, tables, definitions and references in the ODCM.

+

I.

10/09/14 35 o

Section 3/4 was revised to delete a reference requirement to Note 5 in Section 2 of Table 3.1.2 (Gaseous Effluent Monitoring Instrumentation). It was determined that Note 5 was in conflict with Note 2 for Section 2 and therefore should be removed as a requirement for Section 2 (CR-VTY-2013-04078 CA-0002).

o Also, in Sections 2, 3/4, 6, 8 and 10, the word "operable" was found to be inappropriate and should be replaced by the word "functional". Additionally, the word "inoperable" by the word "non-functional" and the word "operability" was replaced by "functionality" (EN-OP-104 and NRC Inspection Guide 9900) (CR-VTY-2013-04078 CA-0002).

o In the tables of Section 7 of the Offsite Dose Calculation Manual, it was determined that the out-of-business dairy farms which had provided milk for the REMP but were no longer functional, should be eliminated from the description (WT-WTVTY-201 1-00116).

Section 9 of the Offsite Dose Calculation Manual was revised to eliminate the references to the Off Gas "'30 minute" delay line. This was previously evaluated under CR-VTY-2010-1676 and it was determined that the reference to the "30 minute" should be removed. (WT-WTVTY-2009-00009 CA-00 10)

Off-Site Dose Calculation Manual Rev. 35 Page iii of xi Vermont Yankee Nuclear Power Station H-2 I

TABLE 2.1.1 Definitions Gaseous Radwaste Treatment System - The Augmented Off-Gas System (AOG) is the gaseous radwaite treatment system which has been designed and installed to reduce radioactive gascous effluents by collecting primary coolant system off-gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

2.

Groundwater - For purposes of the ODCM, groundwater is defined as subsurface water which is either shallow, deep or in bedrock layers. Shallow and deep groundwater wells are sampled to determine the flow rate and contamination concentrations of groundwater flowing to the Connecticut River above or on the bedrock layer. Bedrock groundwater wells, utilized for drinking water purposes both on and off the plant site, are monitored for radioactive contamination as part of the REMP.

3.

Hot Standby - Hot standby means operation with the reactor critical and the main steam line isolation valves closed.

4.

Immediate - Immediate means that the required action will be initiated as soon as practicable considering the safc operation of the unit and the importance of the required action.

5.

Instrument Calibration - An instrument calibration means the adjustment of an instrument signal output so that it corresponds, within acceptable range and accuracy, to a known value(s) of the parameter which the instrument monitors. Calibration shall encompass the entire instrument including actuation, alarm, or trip. Response time as specified is not part of the routine instrument calibration but will be checked once per operating cycle.

6.

Instrument Check - An instrument check is qualitative determination of acceptable operability by observation of instrument behavior during operation. This determination shall include, where possible, comparison of the instrument with other independent instruments measuring the same variable.

7.

Instrument Functional Test - An instrument functional test shall be:

a.

Analog channels - the injection of a signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.

b.

Bistable channcls - the injection of a signal into the sensor to verify the functionality including alarm and/or trip functions.

Off-Site Dose Calculation Manual Section 2.0 Rev. 35 Page 2 of 1 I Vermont Yankee Nuclear Power Station H-3

TABLE 2.1.1 (Continued)

8.

Off-Site Dose Calculation Manual (ODCM) - A manual containing the current methodology and parameters used in the calculation of off-site doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduction of the environmental radiological monitoring program. The ODCM shall also contain (1) the Radioactive Effluent Controls (including the Radiological Environmental Monitoring) Program required by Technical Specification 6.7.D, and (2) descriptions of the information that should be included in the annual Radioactive Effluent Release Report and Annual Radiological Environmental Operating Report required by Technical Specifications 6.6.D and 6.6.E, respectively.

9.

Refueling Outage - Refueling outage is the period of time between the shutdown of the unit prior to a refueling and the startup of the plant subsequent to that refueling. For the purpose of designating frequency of testing and surveillance, a refueling outage shall mean a regularly scheduled refueling outage; however, where such outages occur within 8 months of the completion of the previous refueling outage, the required surveillance testing need not be performed until the next regularly scheduled outage.

10.

Site Boundary - The site boundary is shown in Plant Drawing 5920-6245.

II.

Source Check - The qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

12.

Streamtube(s) - Defined as flows of subsurface groundwater (having discrete width, depth and flow rate characteristics) in either the shallow or deep layers of permeable soils above the bedrock layer at the plant site. Streamtube flows are from west to east, towards the Connecticut River, and are assumed to discharge into the Connecticut River.

13.

Surveillance Frequency - Unless otherwise stated in these specifications, periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified surveillance intervals. These intervals may be adjusted plus 25%. The operating cycle interval is considered to be 18 months and the tolerance stated above is applicable.

14.

Surveillance Interval - The surveillance interval is the calendar time between surveillance tests, checks, calibrations, and examinations to be performed upon an instrument or component when it is required to be functional. These tests unless otherwise stated in these specifications may be waived when the instrument, component, or system is not required to be functional, but these tests shall be performed on the instrument, component, or system prior to being required to be functional.

Off-Site Dose Calculation Manual Section 2.0 Rev. 35 Page 3 of II Vermont Yankee Nuclear Power Station H-4

3/4.0 EFFLUENT AND ENVIRONMENTAL CONTROLS This section includes the effluent and environmental controls that were originally part of the Vermont Yankee Technical Specifications. These controls were relocated into the ODCM without any substantial changes, in accordance with NRC Generic Letter 89-01. Text and tables were reformatted to the style of the ODCM. The various controls were renumbered from the original numbering scheme of the Technical Specifications. A cross-reference of the old Technical Specifications section to the new ODCM section is presented in Table 1. 1.8.

3/4.1 INSTRUMENTATION 3/4.1.1 Radioactive Liquid Effluent Instrumentation CONTROLS 3.1.1 The radioactive liquid effluent monitoring instrumentation channel shall be functional in accordance with Control Table 3. 1.1 with their alarm setpoints set to ensure that the lim-its of Control 3.2.1 are not exceeded.

APPLICABILITY:

During periods of release through monitored pathways as listed on Table 3.1. 1.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of Control 3.2.1 are met, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or change the setpoint so that it is acceptably conservative or declare the channel non-functional.

b.

With one or more radioactive liquid effluent monitoring instrumentation channels non-functional, take the action shown in Table 3.1.1.

SURVEILLANCE REQUIREMENTS 4.1. L.a Each radioactive liquid effluent monitoring instrumentation channel shall be tested and calibrated as indicated in Table 4. 1. 1.

4. 1..b The setpoints for monitoring instrumentation shall be determined in accordance with the ODCM (Section 8. I).

Off-Site Dose Calculation Manual Section 3/4 Rev. 35 Page I of 47 Vermont Yankee Nuclear Power Station H-5

TABLE 3.1.1 Liquid Effluent Monitoring Instrumentation Minimum Channels Functional Notes I.

Gross Radioactivity Monitors not Providing Automatic Termination of Release

a.

Liquid Radwaste Discharge Monitor 1*

1,4 (RM-17-350)

b.

Service Water Discharge Monitor 1

2,4 (RM-17-35 1)

2.

Flow Rate Measurement Devices

a.

Liquid Radwaste Discharge Flow Rate 1*

3,4 Monitor (FIT-20-485/442)

During releases via this pathway Off-Site Dose Calculation Manual Section 3/4 Rev. 35 Page 2 of 47 Vermont Yankee Nuclear Power Station H-6

TABLE 3.1.1 NOTATION NOTEI NOTE 2 NOTE 3 NOTE 4 With the number of channels functional less than required by the minimum channels functional requirement, effluent releases may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Control 4.2. 1, and

b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

With the number of channels functional less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided that, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 microcurie/ml.

With the number of channels functional less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves may be used to estimate flow.

With the number of channels functional less than required by the minimum channels functional requirement, exert reasonable efforts to return the instrument(s) to functional status prior to the next release.

Off-Site Dose Calculation Manual Section 3/4 Rev. 35 Page 3 of 47 Vermont Yankee Nuclear Power Station H-7

3/4.1 INSTRUMENTATION 3/4.1.2 Radioactive Gaseous Effluent Instrumentation CONTROLS 3.1.2 The gaseous process and effluent monitoring instrumentation channels shall be functional in accordance with Control Table 3.1.2 with their alarm/trip setpoints set to ensure that the limits of Controls 3.3. l.a, and Technical Specifications 3.8.J.I and 3.8.K. I (Control 3.3.7) are not exceeded.

APPLICABILITY:

As shown in Table 3.1.2.

ACTION:

a.

With a gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of Control 3.3.1.a and Technical Specification 3.8.K. I are met, immediately take actions to suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel non-functional, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels functional, take actions noted in Table 3.1.2.

SURVEILLANCE REQUIREMENTS 4.1.2.a Each gaseous process or eftluent monitoring instrumentation channel shall be tested and calibrated as indicated in Table 4.1.2.

4.1.2.b The setpoints for monitoring instrumentation shall be determined in accordance with the ODCM (Section 8.2).

OtffSite Dose Calculation Manual Section 3/4 Rev. 35 Page 6 of 47 Vermnont Yankee Nuclear Power Station H-8

TABLE 3.1.2 Gaseous Effluent Monitoring Instrumentation Minimum Channels Instrument Functional Not.s I.

Steam Jet Air Ejector (SJAE)

a.

Noble Gas Activity Monitor

7, 8, 9 (RM-I 7-150A/B)

2.

Augmented Off-Gas System

a.

Noble Gas Activity Monitor Between the 2, 6, 7 Charcoal Bed System and the Plant Stack (Providing Alarm and Automatic Termination of Release)

(RAN-OG-3127, RAN-OG-3128)

b.

Flow Rate Monitor I

1,5,6 (FI-OG-2002, FI-OG-2004, FI-OG-2008)

c.

Hydrogen Monitor 1

3,5.6 (H2AN-OG-292 I A/B, H2AN-OG-2922A/B)

3.

Plant Stack

a.

Noble Gas Activity Monitor 1

5, 7, 10 (RM-17-156, RM-17-157)

b.

Iodine Sampler Cartridge I

4, 5

c.

Particulate Sampler Filter 1

4, 5

d.

Sampler Flow Integrator I

I,5 (FI-17-156/157)

e.

Stack Flow Rate Monitor 1

1. 5 (FI-108-22)

This instrumentation channel(s) is required to support compliance with rechnical Specification 3.8.K.

Off-Site Dose-Calculation Manual Section 314 Rev. 35 Page 7 of 47 Vcrnnnt Yankee Nuclear Power Station H-9

TABLE 3.1.2 NOTATION NOTE I - With the number of channels functional less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

NOTE 2 - With the number of channels functional less than required by the minimum channels functional requirement, effluent releases via this pathway may continue for a period of up to 7 days provided that at least one of the stack monitoring systems is functional and off-gas system temperature and pressure are measured continuously.

NOTE 3 - With the number of channels functional less than required by the minimum channels functional requirement, operation of the AOG System may continue provided gas samples are collected at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or an orderly transfer of the off-gas effluents from the operating recombiner to the standby recombiner shall be made.

NOTE 4

- With the number of channels functional less than required by the minimum channels functional requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment.

NOTE 5 - With the number of channels functional less than required by the minimum channels functional requirement, exert reasonable efforts to return the instrument(s) to functional status within 30 days.

NOTE 6 - During releases via this pathway.

NOTE 7 - The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Off-Site Dose Calculation Manual (ODCM).

NOTE 8 - Minimum channels Functional required only during operation of the Steam Jet Air Ejector.

NOTE 9 - With the number of channels fuinctional less than required by the minimum channels functional requirement, gases from the SJAE may be released to the environment for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided:

I.

The AOG System is not bypassed; and

2.

The AOG System noble gas activity monitor is functional.

NOTE 10- With the number of channels functional less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Off-Site Dose Calculation Manual Section 3/4 Rev. 35 Page 8 of 47 Vermont Yankee Nuclear Power Station H-10

6.4 Method to Calculate the Total Body Dose Rate From Noble Gases Effluent Control 3.3.1 limits the instantaneous dose rate at any time to the total body from all release sources of noble gases at any location at or beyond the site boundary equal to or less than 500 rnrem/year.

Use Method I first to calculate the Total Body Dose Rate from the peak release rate via both elevated and ground level release points. The dose rate limit of Control 3.3.l.a is the total contribution from both ground and elevated releases occurring during the period of interest.

Use Method [I if Method I predicts a dose rate greater than the Control limit (i.e., use of actual meteorology over the period of interest) to determine if, in fact, Control 3.3.1 had actually been exceeded during a short time interval.

Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant stack noble gas activity monitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off-site dose rate limit of Control 3.3.1, or a value below it, taking into account the potential contribution of releases from all ground level sources.

Determinations of dose rates for compliance with Control (3.3.1) are performed when the effluent monitor alarm setpoint is exceeded and the corrective action required by Control 3.3.1 is unsuccessful, or as required by the notations to Control Table 3.1.2 when the stack noble gas monitor is non-functional.

Off-Site Dose Calculation Manual Section 6 Rev. 35 Page 12 of 56 Vermont Yankee Nuclear Power Station H-II

6.5 Method to Calculate the Skin Dose Rate from Noble Gases Effluent Control 3.3. I limits the instantaneous dose rate at any time to the skin from all release sources of noble gases at any location at or beyond the site boundary to 3,000 mrem/year.

Use Method I first to calculate the Skin Dose Rate from both elevated and ground level release points to the atmosphere. The dose rate limit of Control 3.3..a is the total contribution from both ground and elevated releases occurring during the period of interest. Method I applies at all release rates.

Use Method 11 if Method I predicts a dose rate greater than the Control limits (i.e., use of actual meteorology over the period of interest) to determine if, in fact, Control 3.3.1 had actually been exceeded during a short time interval.

Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant stack noble gas activity monitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off-site Control dose rate limit, or a value below it, taking into account the potential contribution releases from all ground level sources.

Determinations of dose rate for compliance with Control (3.3.1) are performed when the effluent monitor alarm setpoint is exceeded and the corrective action required by Control 3.3.1 is unsuccessful, or as required by the notations to Control Table 3.1.2 when the stack noble gas monitor is non-functional.

Off-Site Dose Calculation Mavanual Section 6 Rev. 35 Page 17of56 Vermont Yankee Nuclear Power Station H-12

Table 7.1 Radiological Environmental Monitoring StationsIl)

Exposure Pathway Sample Location Distance and/or Sample and Designated Code(2)

(km)(5)

Direction(5) 1.

AIRBORNE (Radioiodine and Particulate)

AP/CF-I 1 River Station No. 3-3 1.88 SSE AP/CF-12 N. Hinsdale, NH 3.61 NNW AP/CF-13 Hinsdale Substation 3.05 E

AP/CF-14 Northfield, MA(9) 11.61 SSE AP/CF-15 Tyler Hill Roadt 4) 3.14 WNW AP/CF-21I Spofford Lake19) 16.36 NNE

2.

WATERBORNE

a. Surface WR-II River Station No. 3-3 1.88 Downriver WR-21 Rt. 9 Bridge!9 )

11.83 Upriver

b. Ground WG-l I Plant Well 0.24 On-Site WG-12 Vernon Nursing Well 2.13 SSE WG-13 COB Well(4 0.26 On-Site WG-14 Plant Support Bldg Well14) 0.27 On-Site WG-22 Copeland Well(9 )

13.73 N

c. Sediment SE-I I Shoreline Downriver 0.57 SSE From SE-12 North Storm 0.13 E

Shoreline Drain Outfall(3)

3.

INGESTION

a. Milk '*

TM-I I Miller Farm 0.82 W

TM-18 Blodgett Farm 3.60 SE TM-22 Franklin Farm(4) 9.73 WSW

b. Mixed TG-1 I River Station No. 3-3 1.88 SSE Grasses TG-12 N. Hinsdale, NH 3.61 NNW TG-13 Hinsdale Substation 3.05 E

TG-14 Northfield. MA\\(()

11.61 SSE TG-15 Tyler Hill Rdi4) 3.07 WNW Off-Site Dose Calculation Manual Section 7 Rev. 35 Page 4 of 12 Vermont Yankee Nuclear Power Station H-13

TABLE 7.1 (Continued)

TG-21 Spofford Lake(9) 16.36 NNE Exposure Pathway Sample Location Distance and/or Sample and Designated Code(2.)

Direction(5)

c. Silage TC-I I Miller Farm 0.82 W

TC-18 Blodgett Farm 3.60 SE TC-22 Franklin Farm(4) 9.73 WSW

d. Fish FH-I I Vernon Pond (6)

(6)

FH-21 Rt. 9 Bridge(9 )

11.83 Upriver

4.

DIRECT RADIATION DR-I River Station No. 3-3 1.61 SSE DR-2 N. Hinsdale, NH 3.88 NNW DR-3 Hinsdale Substation 2.98 E

DR-4 Northfield, MA(9) 11.34 SSE DR-5 Spofford Lake(9) 16.53 NNE DR-6 Vernon School 0.52 WSW DR-7 Site Boundary(7) 0.28 W

DR-8 Site Boundary 0.25 SSW DR-9 Inner Ring 1.72 N

DR-I 0 Outer Ring 4.49 N

DR-II Inner Ring 1.65 NNE DR-12 Outer Ring 3.58 NNE DR-13 Inner Ring 1.23 NE DR-14 Outer Ring 3.88 NE DR-15 Inner Ring 1.46 ENE DR-16 Outer Ring 2.84 ENE DR-17 Inner Ring 1.24 E

DR-18 Outer Ring 2.97 E

DR-19 Inner Ring 3.65 ESE DR-20 Outer Ring 5.33 ESE DR-21 Inner Ring 1.82 SE DR-22 Outer Ring 3.28 SE DR-23 Inner Ring 1.96 SSE DR-24 Outer Ring 3.89 SSE DR-25 Inner Ring 1.91 S

Off-Site Dose Calculation Manual Section 7 Rev. 35 Page 5 of 12 Vernont Yankee Nuclear Power Station H-14

Usually Fd/F,, is greater than DFmin (i.e., there is more dilution than necessary to comply with Equation 8-7). The response of the liquid radwaste discharge monitor at the setpoint is therefore:

(8-1)

DF S

R setpoint -

DF SI Cmi (Cps) 0#)

cp -m)

(j.m )

8.1.2 Service Water Discharge Monitor (RM-17-35 1 The service water pathway shown on Figure 9-1 is continuously monitored by the service water discharge monitor (RM-17-35 1). The water in this line is not radioactive under normal operating conditions. The alarm setpoint on the Service Water Monitor (SWM) is set in accordance with the monitor's ability to detect dilute concentrations of radionuclide mixes that are based on measured nuclide distributions in reactor coolant. From routine coolant sample gamma isotopic analyses, a Composite Maximum Permissible Concentration (CMPC) is calculated as follows:

C(f1 /MPC1 + f2/MPC2...) = C/CMPC or CMPC = l/(f,/MPCI + f2/MPC2...)

(8-22) where:

C

=

Total concentration of detected radioactivity in reactor coolant sample (ILtCi/ml)

=

Fraction of total radionuclide concentration represented by the ith radionuclide in the mix MPCi =

Maximum Permissible Concentration limit for radionuclide "i' as listed in IOCFR20.106, Appendix B, Table II, Column 2 (ICi/rnl)

The Composite Effluent Concentration Limit (CECL) is also calculated using the equation above by substituting the appropriate ECL value from IOCFR20.1001-20.2402, Appendix B, Table 2, Column 2, for MPC. If the SWM's minimum achievable alarm setpoint is higher than the required CMPC equivalent count rate (or the CECL equivalent count rate if it is lower than the CMPC count rate), the monitor is declared non-functional, and daily SWM grab samples are collected and analyzed until the calculated coolant CMIPC (or CECL) equivalent count rate is above the SWM's alarm setpoint.

Off-Site Dose Calculation Manual Section 8 Rev. 35 Page 8 of 22 Vermont Yankee Nuclear Power Station H-15

Hydrogen control is accomplished by providing redundant hydrogen analyzers on the outlet from the Recombiner System. These analyzers initiate recombiner system shutdown and switchover if the hydrogen concentration at the system outlet exceeds 2% by volume. During an automatic shutdown, two main air process valves close to isolate tile recombiner system.

Additionally, the recombiner bed temperatures and recombiner outlet temperature provide information about recombiner performance to insure that inflammable hydrogen mixtures do not go beyond the recombiner.

Should a number of unlikely events occur, it would be hypothetically possible for a hydrogen explosion to occur in the off-gas system. Such an explosion within the recombiner system could propagate into the large delay pipe, through the condenser/dryer subsystem, and into the charcoal absorber tanks. However, the recombiner/adsorber subsystems, piping, and vessels are designed to withstand hydrogen detonation pressures of 500 psi at a minimum so that no loss of integrity would result. Furthermore, the seven tanks of charcoal would significantly attenuate a detonation shock wave and prevent damage to the downstream equipment.

During normal operation, the dryer/adsorber subsystem may be bypassed if it becomes unavailable provided the releases are within effluent Control limits. With the dryer/adsorber subsystem bypassed, the air ejector off-gas exhausts through the recombiner/condenser subsystems, and the delay pipe.

The off-gas mixture combines with steam at the air ejector stage to prevent an inflammable hydrogen mixture of 4% by volume from entering the downstream hydrogen recombiners. Approximately 6,400 lb/hr of steam introduced at the second stage air ejector reduces the concentration of hydrogen to less than 3% by volume.

The recombiner subsystem consists of a single path leading from the hydrogen dilution steam jet ejectors to two parallel flow paths for hydrogen recombination. Each recombination subsystem is capable of operating independently of the other and each is capable of handling the condenser off-gas at a startup design flow of 1,600 lb/hr air and the normal off-gas design flow rate of 370 lb/hr. The major components of each recombiner flow path are a preheater, a hydrogen-oxygen recombiner, and a desuperheating condenser.

Off-Site Dose Calculation Manual Section 9 Rev. 35 Pag.e 5 of 16 Vermont Yankee Nuclear Power Station H-16

With the limits of Control 3.4.1 being exceeded during the calendar year, the Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed real member(s) of the public from reactor releases (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

The Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to site boundary of radioactive materials in gaseous and liquid effluents made during the reporting period.

With the quantity of radioactive material in any outside tank exceeding the limit of Technical Specification 3.8.D. 1, describe the events leading to this condition in tile next Radioactive Effluent Release Report.

If non-fucntional radioactive liquid effluent monitoring instrumentation is not returned to functional status prior to the next release pursuant to Note 4 of Control Table 3. 1. 1, explain in the next Radioactive Effluent Report the reason(s) for delay in correcting the inoperability.

If non-functional gaseous effluent monitoring instrumentation is not returned to functional status within 30 days pursuant to Note 5 of Control Table 3.1.2, explain in tile next Radioactive Effluent Release Report the reason(s) for delay in correcting the inoperability.

With milk samples no longer available from one or more of the sample locations required by Control Table 3.5. 1, identify the cause(s) of the sample(s) no longer being available, identify the new location(s) for obtaining available replacement samples, and include revised ODCM figure(s) and table(s) reflecting the new location(s) in the next Radioactive Effluent Release Report.

With a land use census identifying one or more locations which yield at least a 20 percent greater dose or dose commitment than the values currently being calculated in Control 4.3.3, identify the new location(s) in the next Radioactive Effluent Release Report.

Changes made during the reporting period to the Process Control Program (PCP) and to the Off-Site Dose Calculation Manual (ODCM), shall be identified in the next Radioactive Effluent Release Report.

Off-Site Dose Calculation Manual Section 10 Rev. 35 Page 2 of 7 Vermont Yankee Nuclear Power Station H-17

10.2 Environmental Radiological Monitoring The Annual Radiological Environmental Operating Report covering the operation of the unit during previous calendar year shall be submitted by May 15th of each year.

The report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period.

The material provided shall be consistent with the objectives outlined in the ODCM and in 10CFR 50, Appendix 1. Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include summarized and tabulated results of all radiological environmental samples taken during the report period pursuant to Table 7-1 and Figures 7-i through 7-6. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

With the level of radioactivity in an environmental sampling mnedia at one or more of the locations specified in Control Table 3.5.1 exceeding the reporting levels of Control Table 3.5.2, the condition shall be described in the next Annual Radiological Environmental Operating Report only if the-measured level of radioactivity was not the result of plant eftluents. With the radiological environmental monitoring program not being conducted as specified in Control Table 3.5. 1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence shall be included in the next Annual Radiological Environmental Operating Report.

The Annual Radiological Environmental Operating Report shall also include the results of the land use census required by Control 3.5.2. A summary description of the radiological environmental monitoring program including a map of all sampling locations keyed to a table giving distances and directions from the reactor shall be in the reports. If new environmental sampling locations are identified in accordance with Control 3.5.2, the new locations shall be identified in the next Annual Radiological Environmental Operating Report.

The reports shall also include a discussion of all analyses in which the LLD required by Control Table 4.5. I was not achievable.

The results of license participation in the intercomparison program required by Control 3.5.3 shall be included in the reports. With analyses not being performed as required by Control 3.5.3, the corrective actions taken to prevent a recurrence shall be reported to the Commission in the next Annual Radiological Environmental Operating Report.

Off-Site Dose Calculation Manual Section 10 Rev. 35 Page 3 of 7 Vermont Yankee Nuclear Power Station H-18

10.3 ISFSI Reporting Requirements In accordance with IOCFR72.44(d)(3), the Annual Independent (Interim) Spent Fuel Storage Installation Radiactive Effluent Control Program Report (AISFSIRECPR) will be generated and issued by February 28th of each year.

Since it has been determined by Holtec International in their Final Safety Analysis Report (Reference I) that the Holtec HI-STORM 100 Cask System does not create any radioactive materials or have any radioactive waste treatment systems, specific operating procedures for the control of radioactive effluents are not required.

Specification 3. 1. I, Multi-Purpose Canister (MPG), provides assurance that there are no radioactive eftluents from the SFSC.

In light of the information presented in the previous paragraphs, the AISFSIRECPR, to be issued by February 28th of each year, shall state that no radioactive effluents were discharged from the Independent (Interim) Spent Fuel Storage Installation and therefore no ISFSI-specific monitoring program is in place at Vermont Yankee and there are no ISFSI-specific data to report for the previous calendar year reporting period.

10.4 Special Reports Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report.

10.4.1 Liquid Effluents (Controls 3.2.2 and 3.2.3)

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the limits of Control 3.2.2, prepare and submit to the Commission within 30 days a special report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to assure that subsequent releases will be in compliance with the limits of Control 3.2.2.

With liquid radwaste being discharged without processing through appropriate treatment systems and estimated doses in excess of Control 3.2.3, prepare and submit to the Commission within 30 days a special report which includes the following information:

(I) explanation of why liquid radwaste was being discharged without treatment, identification of any non-functional equipment or subsystems, and the reasons for the non-functionality; (2) action(s) taken to restore the non-functional equipment to functional status; and (3) summary description of action(s) taken to prevent a recurrence.

Off-Site Dose Calculation Manual Section 10 Rev. 35 Page 4 of 7 Vermont Yankee Nuclear Power Station H-19

10.4.2 Gaseous Effluents (Controls 3.3.2, 3.3.3, 3.3.4 and 3.3.5)

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the limits of Control 3.3.2, prepare and submit to the Commission within 30 days a special report which identifies the cause(s) for exceeding the limit(s) and the corrective action(s) taken to assure that subsequent releases will be in compliance with the limits of Control 3.3.2. With the calculated dose from the release of Iodine-131, Iodine-133, tritium, and/or radionuclides in particulate form exceeding any of the limits of Control 3.3.3, prepare and submit to the Commission within 30 days a special report which identifies the cause(s) for exceeding the limit(s) and the corrective action(s) taken to assure that subsequent releases will be in compliance with the limits of Control 3.3.3.

With gaseous radwaste being discharged without processing through appropriate treatment systems as defined in Control 3.3.4 for more than seven (7) consecutive days, or in excess of the limits of Control 3.3.5, prepare and submit to the Commission within 30 days a special report which includes the following infornation:

(1) explanation of why gaseous radwaste was being discharged without treatment (Control 3.3.4). or with resultant doses in excess of Control 3.3.5, identification of any non-functional equipment or subsystems, and the reasons for the non-functionality; (2) action(s) taken to restore the non-functional equipment to functional status; and (3) summary description of action(s) taken to prevent a recurrence.

10.4.3 Total Dose (Control 3.4. 1)

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding the limits of Control 3.4. 1, prepare and submit to the Commission within 30 days a special report which defines the corrective action(s) to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Control 3.4.1 and includes the schedule for achieving conformance with these limits.

This special report, required by I OCFR Part 20.2203(a)(4), shall include an analysis that estimates the radiation exposure (dose) to a member of the public from station sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated doses exceed any of the limits of Control 3.4. 1, and if the release condition resulting in violation of 40CFR Part 190 has not already been corrected, the special report shall include a request for a variance in accordance with the provisions of 40CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

Off-Site Dose Calculation Manual Section 10 Rev. 35 Page 5 of 7 Vennont Yankee Nuclear Power Station H-20

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 the radioactive waste systems during this reporting period.

I-i

6-A APPENDIX J ON-SITE DISPOSAL OF SEPTIC/SILT/SOIL WASTE Requirement:

Response

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 radionuclides present and the total radioactivity associated with the disposal activities on the Vermont Yankee site.

There was one on-site disposal spreading of 11,000 gallons of septic waste during October of 2014, 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:

Radionuclide Mn-54 Co-60 Zn-65 Cs-134 Cs-137 Activity Spread in 2014 (Ci) 1.832E-10 8.987E-09 4.503E-10 Activity from All Past and Current Disposals Decayed to 10/7/2014 (C i) 2.72E-08 1.11 E-05 1.08E-08 0.OOOE+00 2.907E-10 9.46E-10 7.68E-05 The maximum organ dose from all past and current spreading operations totaled 1.12E-01 mrem/year. This calculated value is within the I 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 15-037, Submittal of 2014 Radioactive Effluent Release Report

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BVY 15-037, Submittal of 2014 Radioactive Effluent Release Report

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