Text

2011 Annual Radiological Environmental Operating Report
	ML12138A064
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	05/14/2012
From:	Wanczyk R; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BVY 12-034
	Download: ML12138A064 (120)
	v • d • e

r-Entergy Nuclear Operations, Inc.

Vermont Yankee 320 Governor Hunt Road Entergy Vernon, VT 05354 Tel 802 257 7711 Robert J. Wanczyk Licensing Manager BVY 12-034 May 14, 2012 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Subject:

2011 Annual Radiological Environmental Operating Report Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28

Dear Sir or Madam,

In accordance with Vermont Yankee Technical Specification 6.6.E, attached is a copy of the 2011 Annual Radiological Environmental Operating Report. This report contains a summary and analysis of the radiological environmental data collected for the calendar year 2011.

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) 451-3166.

[RJW/JTM]

Attachment 1: Annual Radiological Environmental Operating Report - Year 2011 cc listing (next page)

BVY 12-034 / page 2 of 2 cc: Mr. William Dean, Region 1 Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Richard Guzman, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC 320 Governor Hunt Road Vernon, Vermont 05354 Ms. Elizabeth Miller, 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 John Giarrusso Nuclear Preparedness and Planning Manager 400 Worcester Road Framingham, MA 01702 DHHS/DPHS Dennis P. O'Dowd, Administrator Radiological Health Section 29 Hazen Drive Concord, NH 03301-6504 Tony Honnellio Radiation Program Manager US EPA - Region 1 5 Post Office Square - Suite 100 Boston, Massachusetts 02108

ENTERGY - VERMONT YANKEE Vermont Yankee Nuclear Power Station ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Year 2011 Prepared by:

Stephevn Skibniowsky, 9r. Environmenta jalist (REMP) " Da e Reviewed by:

Rick Heatli waite,

Supervisor Date Approved for Distribution: *//.

U /S'*'6 ID, f'Jeffery A.Hardy, Chemistry Manager Date

TABLE OF CONTENTS

1. IN TR O D U C TION ................................................................................................................ 1

2. BACKGROUND RADIOACTIVITY ................................................................................. 2 2.1 Naturally Occurring Background Radioactivity ......................................................... 2 2.2 Man-Made Background Radioactivity ........................................................................ 3

3. GENERAL PLANT AND SITE INFORMATION .............................................................. 4

4. PROGRAM DESIGN ..................................................................................................... 5 4.1 Monitoring Z ones ................................................................................................... 6 4.2 Pathw ays M onitored .................................................................................................. 6 4.3 Descriptions of Monitoring Programs ......................................................................... 7 5 RADIOLOGICAL DATA

SUMMARY

TABLES ........................................................... 24

6. ANALYSIS OF ENVIRONMENTAL RESULTS ............................................................ 43 6.1 Sampling Program Deviations ................................................................................. 43 6.2 Comparison of Achieved LLDs with Requirements ................................................. 45 6.3 Comparison of Results with Reporting Levels ......................................................... 45 6.4 Changes in Sampling Locations .............................................................................. 46 6.5 Data Analysis by Media Type ................................................................................. 46

7. QUALITY ASSURANCE PROGRAM .......................................................................... 84 7.1 AREVA NP INC. Environmental Laboratory ......................................................... 84 7.2 Teledyne Brown Engineering-Environmental Services (TBE-ES) Laboratory ....... 86 7.3 Entergy James A. Fitzpatrick Environmental Laboratory (JAFEL) ........................... 89

8. L AN D U SE C EN SU S ........................................................................................................... 110

9. S UMM ARY ......................................................................................................................... 112 10 . REF E REN CE S ..................................................................................................................... 114 i

LIST OF TABLES Table Title 4.1 Radiological Environmental Monitoring Program ........................... 10 4.2 Radiological Environmental Monitoring Locations (N on-TLD ) ...................................................................... 12 4.3 Radiological Environmental Monitoring Locations (T LD ) ............................................................................. 14 4.4 Environmental Lower Limit of Detection (LLD)

Sensitivity Requirem ents ................................................................. 16 4.5 Reporting Levels for Radioactivity Concentrations in Environm ental Sam ples ............................................................... 17 5.1 Radiological Environmental Program Summary ............................... 26 5.2 Environmental TLD Data Summary ................................................. 40 5.3 Environmental TLD Measurements ................................................. 42 6.1 Summary of Storm Drain System Sediment Sample Analyses ....... 50 6.2 Summary of Storm Drami System Water Sample Analyses .............. 51 6.3 Summary of Air Compressor Condensate and Manhole Water Tritium Concentrations .............................................. 52 7.3.1 JAFEL Error Resolution ......................................................... 91 7.3.2 JAFEL Numerical Results Tables .............................................. 93 8.1 Land Use Census Locations .................................................. 111 ii

LIST OF FIGURES Figure Title Page 4.1 Environmental Sampling Locations in Close Proximity to the Plant ............................................................ 18 4.2 Environmental Sampling Locations Within 5 Kilometers of Plant ................................................................ 19 4.3 Environmental Sampling Locations.

Greater than 5 Kilometers from Plant ................................................... 20 4.4 TLD Locations in Close Proximity to the P lant ........................................................................................ .. 21 4.5 TLD Locations Within 5 Kilometers of P lant .............................................................................................. . . 22 4.6 TLD Locations Greater than 5 Kilometers from Plant .......................................................................................... . . 23 6.1-6.27 Environm ental Program Trend Graphs ................................................. 56 iii

1. INTRODUCTION This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Entergy-Vermont Yankee in the vicinity of the Vermont Yankee Nuclear Power Station (VYNPS) in Vernon, Vermont during the calendar year 2011. The analyses of samples collected indicated that no plant-generated radioactive material was found in any location off site. In all cases, the possible radiological impact was negligible with respect to exposure from natural background radiation. In no case did the detected levels exceed the most restrictive federal regulatory or plant license limits for radionuclides in the environment. Measured values were several orders of magnitude below reportable levels listed in Table 4.5 of this report. Except for sample deviations listed in Section 6.1, all other samples were collected and analyzed as required by the program.

This report is submitted annually in compliance with plant Technical Specification 6.6.E. The remainder of this report is organized as follows:

Section 2: Provides an introductory explanation of background radioactivity and radiation detected in the plant environs.

Section 3: Provides a brief description of the Vermont Yankee Nuclear Power Station site and its environs.

Section 4: Provides a description of the overall REMP program design. Included is a summary of the Vermont Yankee Nuclear Power Station (VYNPS) Off-Site Dose Calculation Manual (ODCM) requirements for REMP sampling, tables listing all locations sampled or monitored in 2011 with compass sectors and distances from the plant, and maps showing each REMP location. Tables listing Lower Limit of Detection requirements and Reporting Levels are also included.

Section 5: Consists of the summarized data as required by the VYNPS ODCM. The tables are in a format similar to that specified by the NRC Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). Also included is a summary of the 2011 environmental TLD measurements.

Section 6: Provides the results of the 2011 monitoring program. The performance of the program in meeting regulatory requirements as given in the ODCM is discussed, and the data acquired during the year are analyzed.

Section 7: Provides an overview of the Quality Assurance programs used at AREVA Framatome ANP Environmental Laboratory, Teledyne Brown Engineering and Entergy James A. Fitzpatrick Environmental Laboratory.

Section 8: Summarizes the requirements and the results of the 2011 Land Use Census.

Section 9: Gives a summary of the 2011 Radiological Environmental Monitoring Program.

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2. BACKGROUND RADIOACTIVITY Radiation or radioactivity potentially detected in the Vermont Yankee environment can be grouped into three categories. The first is "naturally-occurring" radiation and radioactivity. The second is "man-made" radioactivity from sources other than the Vermont Yankee plant. The third potential source of radioactivity is due to emissions from the Vermont Yankee plant. For the purposes of the Vermont Yankee REMP, the first two categories are classified as "background" radiation, and are the subject of discussion in this section of the report. The third category is the one that the REMP is designed to detect and evaluate.

2.1 Naturally Occurring Background Radioactivity Natural radiation and radioactivity in the environment, which provide the major source of human radiation exposure, may be subdivided into three separate categories: "primordial radioactivity,"

"cosmogenic radioactivity" and "cosmic radiation." "Primordial radioactivity" is made up of those radionuclides that were created with the universe and that have a sufficiently long half-life to be still present on the earth. Included in this category are the newly-formed "daughter" radionuclides descending from these original elements. A few of the more important radionuclides in this category are Uranium-238 (U-238), Thorium-232 (Th-232), Rubidium-87 (Rb-87), Potassium-40 (K-40), Radium-226 (Ra-226), and Radon-222 (Rn-222). Uranium-238 and Thorium-232 are readily detected in soil and rock, whether through direct field measurements or through laboratory analysis of samples. Radium-226 in the earth can find its way from the soil into ground water, and is often detectable there. Radon-222 is one of the components of natural background in air, and its daughter products are detectable on air sampling filters.

Potassium-40 comprises about 0.01 percent of all natural potassium in the earth, and is consequently detectable in most biological substances, including the human body. There are many more primordial radionuclides found in the environment in addition to the major ones discussed above (Reference 2).

The second sub-category of naturally-occurring radiation and radioactivity is "cosmogenic radioactivity."

This is produced through the nuclear interaction of high energy cosmic radiation with elements in the earth's atmosphere, and to a much lesser degree, in the earth's crust. These radioactive elements are then incorporated into the entire geosphere and atmosphere, including the earth's soil, surface rock, biosphere, sediments, ocean floors, polar ice and atmosphere. The major radionuclides in this category are Carbon-14 (C-14), Hydrogen-3 (H-3 or Tritium), Sodium-22 (Na-22), and Beryllium-7 (Be-7). Beryllium-7 is the one most readily detected, and is found on air sampling filters and occasionally in biological media (Reference 2).

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The third sub-category of naturally-occurring radiation and radioactivity is "cosmic radiation." This consists of high energy atomic and sub-atomic particles of extra-terrestrial origin and the secondary particles and radiation that are produced through their interaction in the earth's atmosphere. The majority of this radiation comes from outside of our solar system, and to a lesser degree from the sun. We are protected from most of this radiation by the earth's atmosphere, which absorbs the radiation.

Consequently, one can see that with increasing elevation one would be exposed to more cosmic radiation as a direct result of a thinner layer of air for protection. This "direct radiation" is detected in the field with gamma spectroscopy equipment, high pressure ion chambers and thermoluminescent dosimeters (TLDs).

2.2 Man-Made Background Radioactivity The second source of "background" radioactivity in the Vermont Yankee environment is from "man-made" sources not related to the power plant. The most recent contributor (prior to year 2011) to this category was the fallout from the Chernobyl accident in April of 1986, which was detected in the Vermont Yankee environment and other parts of the world. Some smaller amounts of radioactivity were detected in the environment following the Fukushima Daiichi plants accidents in March 2011. A much greater contributor to this category, however, has been fallout from atmospheric nuclear weapons tests.

Tests were conducted from 1945 through 1980 by the United States, the Soviet Union, the United Kingdom, China and France, with the large majority of testing occurring during the periods 1954-1958 and 1961-1962. (A test ban treaty was signed in 1963 by the United States, Soviet Union and United Kingdom, but not by France and China.) Atmospheric testing was conducted by the People's Republic of China as recently as October 1980. Much of the fallout detected today is due to this explosion and the last large scale one, done in November of 1976 (Reference 3).

The radioactivity produced by these detonations was deposited worldwide. The amount of fallout deposited in any given area is dependent on many factors, such as the explosive yield of the device, the latitude and altitude of the detonation, the season in which it occurred, and the timing of subsequent rainfall which washes fallout from the troposphere (Reference 4). Most of this fallout has decayed into stable elements, but the residual radioactivity is still readily detectable in environmental samples worldwide. The two predominant radionuclides are Cesium-137 (Cs-137) and Strontium-90 (Sr-90). They are found in soil and in vegetation, and since cows and goats graze large areas of vegetation, these radionuclides are also often detected in milk.

Other potential "man-made" sources of environmental "background" radioactivity include other nuclear power plants, coal-fired power plants, national defense installations, hospitals, research laboratories and 3

industry. These, collectively, are insignificant on a global scale when compared to the sources discussed above (natural and fallout).

3. GENERAL PLANT AND SITE INFORMATION The Vermont Yankee Nuclear Power Station is located in the town of Vernon, Vermont in Windham County. The 130-acre site is on the west shore of the Connecticut River, immediately upstream of the Vernon Hydroelectric Station. The plant site is bounded on the north, south and west by privately-owned land, and on the east by the Connecticut River. The surrounding area is generally rural and lightly populated, and the topography is flat or gently rolling on the valley floor.

Construction of the single unit 540 megawatt BWR (Boiling Water Reactor) plant began in 1967. The pre-operational Radiological Environmental Monitoring Program, designed to measure environmental radiation and radioactivity levels in the area prior to station operation, began in 1970. Commercial operation began on November 30, 1972. An Extended Power Uprate, conducted in 2006, resulted in the present generation capacity of 650 megawatts electric.

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4. PROGRAM DESIGN The Radiological Environmental Monitoring Program (REMP) for the Vermont Yankee Nuclear Power Station (VYNPS) was designed with specific objectives in mind. These are:

To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the operation of the station.

To provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits.

To verify the adequacy and proper functioning of station effluent controls and monitoring systems.

To provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or accidental releases of radioactive material.

The program was initiated in 1970, approximately two years before the plant began commercial operation. It has been in operation continuously since that time, with improvements made periodically over those years.

The current program is designed to meet the intent of NRC Regulatory Guide 4.1, Programs for Monitoring Radioactiviti, in the Environs of Nuclear Power Plants: NRC Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants: the NRC Radiological Assessment Branch Technical Position of November 1979, An Acceptable Radiological Environmental Monitoring Program; and NRC NUREG-0473, Radiological Effluent Technical Specifications for BWRs. The environmental TLD program has been designed and tested around NRC Regulatory Guide 4.13, Performance. Testing and ProceduralSpecificationsfor Thermoluminescence Dosimetr: Environmental Applications. The quality assurance program is designed around the guidance given in NRC Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment.

The sampling requirements of the REMP are given in the Off-Site Dose Calculation Manual Table 3.5.1 and are summarized in Table 4.1 of this report. The identification of the required sampling locations is given in the Off-Site Dose Calculation Manual (ODCM), Chapter 7. These sampling and monitoring locations are shown graphically on the maps in Figures 4.1 through 4.6 of this report.

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The Vermont Yankee Chemistry Department conducts the radiological environmental monitoring program and collects all airborne, terrestrial and ground water samples. VYNPS maintains a contract with Normandeau Associates to collect all fish, river water and river sediment samples. In 2011, analytical measurements of environmental samples were performed at the Entergy Nuclear Northeast J. A.

Fitzpatrick N.P.P Environmental laboratory in Oswego, New York. TLD badges are posted and retrieved by the Vermont Yankee Chemistry Department, and were analyzed by the AREVA NP INC.

Environmental Laboratory in Westborough, Massachusetts.

4.1 Monitoring Zones The REMP is designed to allow comparison of levels of radioactivity in samples from the area possibly influenced by the plant to levels found in areas not influenced by the plant. Monitoring locations within the first zone are called "indicators." Those within the second zone are called "controls." The distinction between the two zones, depending on the type of sample or sample pathway, is based on one or more of several factors, such as site meteorological history, meteorological dispersion calculations, relative direction from the plant, river flow, and distance. Analysis of survey data from the two zones aids in determining if there is a significant difference between the two areas. It can also help in differentiating between radioactivity and radiation due to plant releases and that due to other fluctuations in the environment, such as atmospheric nuclear weapons test fallout or seasonal variations in the natural background.

4.2 Pathways Monitored Four pathway categories are monitored by the REMP. They are the airborne, waterborne, ingestion and direct radiation pathways. Each of these four categories is monitored by the collection of one or more sample media, which are listed below, and are described in more detail in this section:

Airborne Pathway Air Particulate Sampling Charcoal Cartridge (Radioiodine) Sampling Waterborne Pathways River Water Sampling Ground Water Sampling Sediment Sampling Ingestion Pathways Milk Sampling Silage Sampling Mixed Grass Sampling Fish Sampling Direct Radiation Pathway TLD Monitoring 6

4.3 Descriptions of Monitoring Programs 4.3.1 Air Sampling Continuous air samplers are installed at seven locations. (Five are required by the VYNPS ODCM.) The sampling pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute. Airborne particulates are collected by passing air through a 50 mm glass-fiber filter. A dry gas meter is incorporated into the sampling stream to measure the total volume of air sampled in a given interval. The entire system is housed in a weatherproof structure. The filters are collected on a weekly frequency and, to allow for the decay of radon daughter products, the analysis for gross beta radioactivity is delayed for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The weekly filters are composited by location at the environmental laboratory for a quarterly gamma spectroscopy analysis.

If the gross-beta activity on an air particulate sample is greater than ten times the yearly mean of the control samples, ODCM Table 3.5.1, Note c, requires a gamma isotopic analysis on the sample.

Whenever the main plant stack effluent release rate of 1-131 is equal to or greater than 0.1 juCi/sec, weekly air particulate collection from the plant stack is required by ODCM Table 3.5.1, Note h.

4.3.2 Charcoal Cartridge (Radioiodine) Sampling Continuous air samplers are installed at seven locations. (Five are required by the ODCM Table 3.5.1.)

The sampling pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute. A 60 cc TEDA-impregnated charcoal cartridge is located downstream of the air particulate filter described in Section 4.3.1 above. A dry gas meter is incorporated into the sampling stream to measure the total volume of air sampled in a given interval. The entire system is housed in a weatherproof structure. These cartridges are collected and analyzed weekly for I- 131.

Whenever the main plant stack effluent release rate of 1-131 is equal to or greater than 0.1 IlCi/sec, weekly charcoal cartridge collection from the plant stack is required, pursuant to ODCM Table 3.5.1, Note h.

4.3.3 River Water Sampling An automatic compositing sampler is maintained at the downstream sampling location by the Vermont Yankee Chemistry Department staff. Normandeau Associates personnel maintain the pump that delivers river water to the sampler. The sampler is controlled by a timer that collects a frequent aliquot of river water. An additional grab sample is collected monthly at the upstream control location. Each sample is analyzed for gamma-emitting radionuclides. Although not required by the VYNPS ODCM, a gross-beta analysis is also performed on each sample. The monthly composite and grab samples are composited by location by the contracted environmental laboratory for a quarterly tritium (H-3) analysis.

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4.3.4 Ground Water (Deep Well Potable Water) Sampling Grab samples are collected quarterly from up to four indicator locations and one control location. Only one indicator and one control are required by the VYNPS ODCM. Each sample is analyzed for gamma-emitting radionuclides and H-3. Although not required by the VYNPS ODCM, a gross-beta analysis is also performed on each sample.

4.3.5 Sediment Sampling River sediment grab samples are collected semiannually from the downriver location and at the North Storm Drain Outfall by Normandeau Associates. Each sample is analyzed at an offsite environmental laboratory for gamma-emitting radionuclides.

4.3.6 Milk Sampling When milk animals are identified as being on pasture (May through October), milk samples are collected twice per month from that location. Throughout the rest of the year, and for the full year where animals are not on pasture, milk samples are collected on a monthly schedule. Three locations are chosen as a result of the annual Land Use Census, based on meteorological dispersion calculations. The fourth location is a control, which is located sufficiently far away from the plant to be outside any potential plant influence. Other samples may be collected from locations of interest.

Immediately after collection, each milk sample is refrigerated and then shipped to the contracted environmental laboratory. Each sample is analyzed for gamma-emitting radionuclides. A separate low-level 1-131 analysis is performed to meet the Lower Limit of Detection requirements in the ODCM.

Although not required by the ODCM, Sr-89 and Sr-90 analyses are also performed on quarterly composited samples.

4.3.7 Silage (Chopped Corn or Grass) Sampling Silage samples are collected at the milk sampling location at the time of harvest, if available. The silage from each location is shipped to the contracted environmental laboratory where it is analyzed for gamma-emitting radionuclides. Although not required by the ODCM, the silage samples are analyzed for low-level 1-13 1.

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4.3.8 Mixed Grass Sampling At each air sampling station, a mixed grass sample is collected quarterly, when available. Enough grass is clipped to provide the minimal sample weight needed to achieve the required Lower Limit of Detection (LLD). The mixed grass samples are analyzed for gamma-emitting radionuclides. Although not required by the ODCM, the grass samples are analyzed for low-level 1-13 I.

4.3.9 Fish Sampling Fish samples are collected semiannually at two Connecticut River locations (upstream of the plant and in the Vernon Pond) by Normandeau Associates. The samples are frozen and delivered to the environmental laboratory where the edible portions are analyzed for gamma-emitting radionuclides.

4.3.10 TLD Monitoring Direct gamma radiation exposure is continuously monitored with the use of thermoluminescent dosimeters (TLDs). Specifically, Panasonic UD-801 AS1 and UD-814ASI calcium sulfate dosimeters are used, with a total of five elements in place at each monitoring location. Each pair of dosimeters is sealed in a plastic bag, which is in turn housed in a plastic screen cylinder. This cylinder is attached to an object such as a fence or utility pole.

A total of 40 stations are required by the ODCM. Of these, 24 must be read out quarterly, while those from the remaining 16 incident response (outer ring) stations need only be de-dosed (annealed) quarterly, unless an ODCM gaseous release limit was exceeded during the period. Although not required by the ODCM, the TLDs from the 16 outer ring stations are read out quarterly along with the other stations' TLDs. In addition to the TLDs required by the ODCM, more than thirteen are typically posted at or near the site boundary. The plant staff posts and retrieves all TLDs, while the contracted environmental laboratory (Stanford Dosimetry) provides processing.

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TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (as required by ODCM Table 3.5.1)*

I. Direct Radiation (TLDs) 40 Continuous Quarterly Gamma dose - Once Quarterly - Each per quarter TLD Outer Ring Incident Response - de-dose only quarterly, unless gaseous release Controls were exceeded.

2. Airborne (Particulates 5 Continuous Weekly Particulate Sample:

and Radioiodine) Gross Beta Each Sample Gamma Isotopic Quarterly Composite (by location)

Radioiodine Canister: Each Sample 1-131

3. Waterborne

a. Surface water 2 Downstream. Monthly Gamma Isotopic Each Sample Automatic Tritium (H-3) Quarterly Composite composite Upstream: grab

b. Ground water 3 Grab Quarterly Gamma Isotopic Each Sample Tritium (H-3) Each Sample

c. Shoreline Sediment 2 Downstream: grab Semiannually Gamma Isotopic Each Sample N. Storm Drain Outfall: grab 0 See ODCM Table 3.5.1 for complete footnotes.

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TABLE 4.1, cont.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (as required by ODCM Table 3.5.1)*

Exposure Pathway Collection Analysis and/or Nominal Nominal Sample Media Number of Routine Sampling Collection Analysis Analysis Sample Mode Frequency Type Frequency Locations

4. Ingestion

a. Milk 4 Grab Monthly Gamma Isotopic Each sample (Semimonthly 1-131 Each sample when on pasture)

b. Fish 2 Grab Semiannually Gamma Isotopic on Each sample edible portions

c. Vegetation Grass sample I at each air Grab Quarterly when Gamma Isotopic Each sample sampling available station Silage sample I at each milk Grab At harvest Gamma Isotopic Each sample sampling station

See ODCM Table 3.5. I for complete footnotes.

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TABLE 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (NON-TLD) IN 2011 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Exposure Station From Plant From Pathway Code Station Description Zone(a) Stack (kin) Plant I. Airborne AP/CF-l I River Sta. No. 3.3 I 1.9 SSE AP/CF- 12 N. Hinsdale, NH I 3.6 NNW AP/CF- 13 Hinsdale Substation I 3.1 E AP/CF-14 Northfield, MA I 11.6 SSE AP/CF- 15 Tyler Hill Road I 3.1 WNW AP/CF-2 I Spofford Lake C 16.4 NNE AP/CF-40 Gov. Hunt House I -- On-site

2. Waterborne

a. Surface WR- I I River Sta. No. 3.3 I 1.9 SSE WR-21 Rt.9 Bridge C 11.8 NNW

b. Ground WG-1 1 Plant Well I 0.2 On-site WG-12 Vernon Nursing Well 1 2.1 SSE WG-14 Plant Support Bldg (PSB) Well I 0.3 On-site WG-15 Southwest Well I 0.3 On-site WT-14 Test Well 201 I -- On-site WT-16 Test Well 202 I -- On-site WT-17 Test Well 203 I -- On-site WT- 18 Test Well 204 I -- On-site WG-22 Copeland Well C 13.7 N

c. Sediment SE-1 I Shoreline Downriver I 0.6 SSE SE-12 North Storm Drain Outfall I 0.1 E 12

TABLE 4.2, cont.

RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (NON-TLD) IN 2011 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Exposure Station From Plant From Pathway Code Station Description Zone*l) Stack(km) Plant Stack

3. Ingestion

a. Milk TM-I I Miller Farm I 0.8 W TM-14 Brown Farm I 2.2 S TM-18 Blodgett Farm I 3.6 SE TM-20 Dunklee Farm (Vern-Mont) C 5.5 S TM-22 Franklin Farm C 9.7 WSW TM-24 County Farmic) C 21.6 N I 0.6 N*

b. Fish FH-1I Vernon Pond SSE FH-21 Rt.9 Bridge C 11.8 NNW

c. Mixed Grass TG-1 1 River Sta. No. 3.3 I 1.9 SSE TG-12 N. Hinsdale, NH I 3.6 NNW TG-13 Hinsdale Substation I 3.1 E TG-14 Northfield, MA I 11.6 SSE TG-15 Tyler Hill Rd. I 3.1 WNW TG-21 Spofford Lake C 16.4 NNE TG-40 Gov. Hunt House I On-site

d. Silage TC-1 1 Miller Farm I 0.8 W TC-14 Brown Farm I 2.2 S TC- 18 Blodgett Farm I 3.6 SE TC-20 Dunklee Farm (Vein-Mont) C 5.2 S TC-22 Franklin Farm C 9.7 WSW (a) I = Indicator Stations; C = Control Stations (b) Fish samples are collected anywhere in Vernon Pond, which is adjacent to the plant (see Figure 4.1).

(c) County Farm ceased operations on May 4, 2011.

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TABLE 4.3 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (TLD) IN 2011 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Station From Plant From Code Station Description Zone"a" (km) (d) Plantid)

DR-I River Sta. No. 3.3 I 1.6 SSE DR-2 N. Hinsdale, NH I 3.9 NNW DR-3 Hinsdale Substation I 3.0 E DR-4 Northfield, MA C 11.3 SSE DR-5 Spofford Lake C 16.5 NNE DR-6 Vernon School I 0.52 WSW DR-7 Site Boundaryic( SB 0.28 W DR-8 Site Boundary SB 0.25 SSW DR-9 Inner Ring I 1.7 N DR- 10 Outer Ring 0 4.5 N DR-1 I Inner Ring I 1.6 NNE DR-12 Outer Ring 0 3.6 NNE DR-13 InnerRing I 1.2 NE DR-14 Outer Ring 0 3.9 NE DR-I5 Inner Ring I 1.5 ENE DR-16 Outer Ring 0 2.8 ENE DR-17 Inner Ring I 1.2 E DR- 18 Outer Ring 0 3.0 E DR-19 Inner Ring 1 3.7 ESE DR-20 Outer Ring 0 5.3 ESE DR-21 Inner Ring I 1.8 SE DR-22 Outer Ring 0 3.3 SE DR-23 Inner Ring I 2.0 SSE DR-24 Outer Ring 0 3.9 SSE DR-25 Inner Ring I 1.9 S DR-26 Outer Ring 0 3.8 S DR-27 Inner Ring I 1.1 SSW DR-28 Outer Ring 0 2.2 SSW DR-29 Inner Ring I 0.9 SW DR-30 Outer Ring 0 2.4 SW 14

TABLE 4.3, cont.

RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (TLD) IN 2011 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Station From Plant From Code Station Description Zone" (kM)(d) Plant(dl DR-31 Inner Ring I 0.71 wsw DR-32 Outer Ring 0 5.1 WSW DR-33 Inner Ring 1 0.66 WNW DR-34 Outer Ring 0 4.6 W DR-35 Inner Ring I 1.3 WNW DR-36 Outer Ring 0 4.4 WNW DR-37 Inner Ring I 2.8 NW DR-38 Outer Ring 0 7.3 NW DR-39 Inner Ring I 3.1 NNW DR-40 Outer Ring 0 5.0 NNW DR-41Ib) Site Boundary SB 0.38 SSW DR-42(b) Site Boundary SB 0.59 S DR-43 (b) Site Boundary SB 0.44 SSE DR-44(b) Site Boundary SB 0.19 SE DR-45

Site Boundary SB 0.12 NE DR-46 (b) Site Boundary SB 0.28 NNW DR-47(b' Site Boundary SB 0.50 NNW DR-48 "b' Site Boundary SB 0.82 NW DR-49 b) Site Boundary SB 0.55 WNW DR-50 Gov. Hunt House I 0.35 SSW DR-51 b) Site Boundary SB 0.26 W DR-52 (b) Site Boundary SB 0.24 SW DR-53 (b) Site Boundary SB 0.21 WSW (a) I = Inner Ring TLD; 0 = Outer Ring Incident Response TLD; C =Control TLD; SB = Site Boundary TLD.

(b) This location is not considered a requirement of ODCM Table 3.5.1.

(c) DR-7 satisfies ODCM Table 3.5.1 for an inner ring direct radiation monitoring location. However, it is averaged as a Site Boundary TLD due to its close proximity to the plant.

(d) Distance and direction is relative to the center of the Turbine Building for direct radiation monitors.

15

TABLE 4.4 ENVIRONMENTAL LOWER LIMIT OF DETECTION (LLD) SENSITIVITY REQUIREMENTS Airborne Particulates Sediment Water or Gases Fish Milk Vegetation (pCi/Kg -

Analysis (pCi/I) (pCi/m 3) (pCi/Kg) (pCi/I) (pCi/Kg) dry)

Gross-Beta 4 0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 0.07 1 60 Cs- 134 15 0.05 130 15 60 150 Cs- 137 18 0.06 150 18 80 180 Ba-La-140 15 15

If no drinking water pathway exists, a value of 3000 pCi/liter may be used.

See ODCM Table 4.5.1 for additional explanatory footnotes.

16

TABLE 4.5 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulates or Gases Fish Milk Food Product Sediment Analysis Water (pCi/m 3) (pCi/Kg) (pCi/I) (pCi/Kg) (pCi/Kg-dry)

___________ (pCi/l) __ _ _ _ __ _ _ _ _

H-3 20,000(a)

Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 10,000 3000(b, Co-60 300 Zn-65 300 20,000 Zr-Nb-95 400 1-131 0.9 3 100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300 (a) Reporting Level for drinking water pathways. For non-drinking water, a value of 30,000 pCi/liter may be used.

(b) Reporting Level for grab samples taken at the North Storm Drain Outfall only.

See ODCM Table 3.5.2 for additional explanatory footnotes.

17

N W TC-11*Ai ""

TM-II1 I WSW ' /

S ool Ve on iemnentar n CFes PrxiiynoPln "W

sw. -- ... .

Verno DSS SS

/0 Figure 4.1 Environmental Sampling Locations In Close Proximity to Plant 18

NWN NNEN I 5,W NN

/A TC- IN F

Figure 4.2 Environmental Sampling Locations WithAi 5 Km of Plant 19

TM-24 TC-24 I

A w

wsw \

Wi'

/

SW\

~ /

SSW Miles 0 1 2 3 4 Figure 4.3 Environmental Sampling Locations Greater than 5 Km from Plant 20

Figure 4.4 Thermoluminescent Dosimeter Locations In Close Proximity to Plant 21

NW,

/ R-2 WNW/I 0-360 R-~

DR-D 3 SW Miles 0 .2 .4 .6 .8 Figure 4.5 Thermoluminescent Dosimeter Locations Within 5 Km of Plant 22

N N

NNW NW / ,

\,

ýf If I

.1 Sw\ /

SSW Figure 4.6 Thermoluminescent Dosimeter Locations Greater than 5 Km from Plant 23

5. RADIOLOGICAL DATA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples that were collected during 2011. These results, shown in Table 5.1, are presented in a format similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). The results are ordered by sample media type and then by radionuclide. The units for each media type are also given.

In 2011, Vermont Yankee contracted with one laboratory, for primary analyses of the environmental samples. A second laboratory was used to cross-check the first laboratory for selected samples and to analyze other samples for hard-to-detect radionuclides (such as Strontium-89 and 90).

The left-most column of Table 5.1 contains the radionuclide of interest, the total number of analyses for that radionuclide in 2011 and the number of measurements which exceeded the Reporting Levels found in Table 3.5.2 of the VYNPS Off-site Dose Calculation Manual. The latter are classified as "Non-routine" measurements. The second column lists the required Lower Limit of Detection (LLD) for those radionuclides that have detection capability requirements as specified in the ODCM Table 4.5.1. The absence of a value in this column indicates that no LLD is specified in the ODCM for that radionuclide in that media. The target LLD for any analysis is typically 50 percent of the most restrictive required LLD.

Occasionally the required LLD may not be met. This may be due to malfunctions in sampling equipment or lack of sufficient sample quantity which would then result in low sample volume. Delays in analysis at the laboratory could also be a factor. Such cases, if and when they should occur, would be addressed in Section 6.2.

For each radionuclide and media type, the remaining three columns summarize the data for the following categories of monitoring locations: (1) the Indicator stations, which are within the range of influence of the plant and which could be affected by its operation; (2) the Control stations, which are beyond the influence of the plant; and (3) the station which had the highest mean concentration during 2011 for that radionuclide. Direct radiation monitoring stations (using TLDs) are grouped into Inner Ring, Outer ring, Site Boundary and Control.

In each of these columns, for each radionuclide, the following statistical values are given:

The mean value of all concentrations, including those results that are less than the a posteriori LLD for that analysis.

The minimum and maximum concentration, including those results that are less than the a posteriori LLD. In previous years, data less than the a posterioriLLD were converted to zero for purposes of 24

reporting the means and ranges.

The "Number Detected" is the number of positive measurements. A measurement is considered positive when the concentration is greater than three times the standard deviation in the concentration and greater than or equal to the a posterioriLLD (Minimum Detectable Concentration or MDC).

The "Total Analyzed" for each column is also given.

Each single radioactivity measurement datum in this report is based on a single measurement of a sample.

Any concentration below the a posterioriLLD for its analysis is averaged with those values above the a posterioriLLD to determine the average of the results. Likewise, the values are reported in ranges even though they are below the a posterioriLLD. To be consistent with normal data review practices used by Vermont Yankee, a "positive measurement" is considered to be one whose concentration is greater than three times its associated standard deviation, is greater than or equal to the a posterioriLLD and satisfies the analytical laboratory's criteria for identification.

The radionuclides reported in this section represent those that: 1) had an LLD requirement in Table 4.5.1 of the ODCM, or a Reporting Level listed in Table 3.5.2 of the ODCM, or 2) had a positive measurement of radioactivity, whether it was naturally-occurring or man-made; or 3) were of special interest for any other reason. The radionuclides routinely analyzed and reported by the environmental laboratory (in a gamma spectroscopy analysis) were: Th-232, Ba/La- 140, Be-7, Co-58, Co-60, Cs- 134, Cs- 137, Fe-59, K-40, Mn-54, Zn-65 and Zr-95.

Data from direct radiation measurements made by TLDs are provided in Table 5.2. The complete listing of quarterly TLD data is provided in Table 5.3.

25

Radiological Environmental Program Summary 2011 Radiological Environmental Operating Report Vermont Yankee Table 5.1:

Sample Medium: Air Particulate (AP)

Sample Medium: Charcoal Cartridge (CF)

Sample Medium: River Water (WR)

Sample Medium: Ground Water (WG)

Sample Medium: Sediment (SE)

Sample Medium: Test Well (WT)

Sample Medium: Milk (TM)

Sample Medium: Silage (TC)

Sample Medium: Mixed Grass (TG)

Sample Medium: Fish (FH) 26

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATES GR-B 362 0.01 0.0128 0.0120 0.0137 12 INDICATOR 0 (PCI/CU. METERS) (310/310) (52/52) (52/52) N. HINSDALE, NH (0.002/0.057) (0.002/0.041) (0.002/0.043) 3.6 KILOMETERS NNW OF SITE GAMMA 28 BE-7 N/A 0.0923 0.1067 0.1067 21 CONTROL 0 (24/24) (4/4) (4/4) SPOFFORD LAKE (0.0549/0.1473) (0.0896/0.1189) (0.0896/0.1189) 16.4 KILOMETERS NNE OF SITE K-40 N/A 0.0283 0.0269 0.0320 15 INDICATOR 0 (3/24) (0/4) (1/4) TYLER HILL ROAD

(<0.0089/0.0524) (<0.0207/<0.0362) (<0.0233/0.0524) 3.1 KILOMETERS WNW OF SITE CS-134 30 0.0028 0.0029 0.0036 14 INDICATOR 0 (0/24) (0/4) (0/4) NORTHFIELD, MA

(<0.0019/<0.0047) (<0.0023/<0.0039) (<0.0028/<0.0047) 11.6 KILOMETERS SSE OF SITE CS-137 0.06 0.0019 0.0017 0.0024 40 INDICATOR 0 (0/24) (0/4) (0/4) GOV. HUNT HOUSE

(<0.00 11/<0.0029) (<0.0005/<0.0022) (<0.0022/<0.0026) ON SITE RA-226 N/A 0.0271 0.0286 0.0302 14 INDICATOR 0 (0/24) (0/4) (0/4) NORTHFIELD, MA

(<0.0141/<0.0369) (<0.0205/<0.0383) (<0.0181/<0.0369) 11.6 KILOMETERS SSE OF SITE ACTH-228 N/A 0.0075 0.0060 0.0090 12 INDICATOR 0 (0/24) (0/4) (0/4) N. HINSDALE, NH

(<0.0018/<0.0129) (<0.0026/<0.0083) (<0.0052/<0.0129) 3.6 KILOMETERS NNW OF SITE AIR IODINE GAMMA 361 (PCI/ M3) 1-131

40 0.0311 0.0335 0.0335 21 CONTROL 0 (10/309) (2/52) (2/52) SPOFFORD LAKE

(<0.0061/0.1090) (<0.0182/0.0830) (<0.0182/0.0830) 16.4 KILOMETERS NNE OF SITE 27

Positive 1-131 is attributed to the Fukushima incident.

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS RIVER WATER GR-B 24 4 2.36 1.32 2.36 II INDICATOR 0 (PCIILITER) (12/12) (11/12) (12/12) RIVER STA. NO. 3.3 (0.860/7.00) (0.700/3.10) (0.860/7.00) 1.9 KILOMETERS SSE OF SITE H-3 3000 420 420 420 II INDICATOR 0 (0/4) (0/4) (0/4) RIVER STA. NO. 3.3

(<408/<433) (<408/<433) (<408/<433) 1.9 KILOMETERS SSE OF SITE Stations 11 and 21 have the same average, minimum and maximum values.

GAMMA 24 MN-54 15 2.27 3.97 3.97 21 CONTROL (0/12) (0/12) (0/12) RT. 9 BRIDGE

(<1.53/<3.04) (<2.87/<4.83) (<2.87/<4.83) 11.8 KILOMETERS NNW OF SITE CO-58 7.5 2.62 4.25 4.25 21 CONTROL (0/12) (0/12) (0/12) RT. 9 BRIDGE

(<1.75/<3.76) (<2.52/<5.09) (<2.52/<5.09) 11.8 KILOMETERS NNW OF SITE FE-59 30 7.39 11.9 11.9 21 CONTROL (0/12) (0/12) (0/12) RT. 9 BRIDGE

(<5.44/<9.58) (<6.95/<17.1) (<6.95/<17.1) 11.8 KILOMETERS NNW OF SITE CO-60 15 2.35 4.53 4.53 21 CONTROL (0/12) (0/12) (0/12) RT. 9 BRIDGE

(<1.5/<3.08) (<2.8/<7.12) (<2.8/<7.12) 11.8 KILOMETERS NNW OF SITE ZN-65 30 4.46 9.77 9.77 21 CONTROL (0/12) (0/12) (0/12) RT. 9 BRIDGE

(<1.94/<6.50) (<5.46/<13.7) (<5.46/<13.7) 11.8 KILOMETERS NNW OF SITE ZR-95 15 4.47 7.48 7.48 21 CONTROL (0/12) (0/12) (0/12) RT. 9 BRIDGE 28 (<3.37/<5.48) (<4.56/<10.6) (<4.56/<10.6) 11.8 KILOMETERS NNW OF SITE FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS RIVER WATER 1-131 15 10.1 7.79 10.1 11 INDICATOR (PCI/LITER) (0/12) (0/12) (0/12) RIVER STA. NO. 3.3

(<4.95/<14.9) (<4.29/<12. 5) (<4.95/<14.9) 1.9 KILOMETERS SSE OF SITE CS-134 15 1.78 4.35 4.35 21 CONTROL (0/12) (0/12) (0/12) RT. 9 BRIDGE

(<1.01/<2.59) (<1L95/<6.42) (<1,95/<6,42) 11.8 KILOMETERS NNW OF SITE CS-137 15 2.29 4.26 4.26 21 CONTROL (0/12) (0/12) (0/12) RT. 9 BRIDGE

(<1.33/<3.42) (<2.62/<5.5) (<2.62/<5.5) 11.8 KILOMETERS NNW OF SITE RA-226 N/A 87.5 104 104 21 CONTROL (11/12) (6/12) (6/12) RT. 9 BRIDGE (60.9/135) (76.3/139) (76.3/139) 11.8 KILOMETERS NNW OF SITE BA-LA-140 15 8.07 7.18 8.07 11 INDICATOR (0/12) (0/12) (0/12) RIVER STA. NO. 3.3

(<5.08/<11.0) (<4.23/<9.67) (<5.08/<11.0) 1.9 KILOMETERS SSE OF SITE GROUND WATER GR-B 17 2 4.35 1.21 9.59 15 INDICATOR (PCI/LITER) (13/13) (3/4) (1/1) SOUTHWEST WELL (1.78/9.59) (<0.870/1.50) N/A 0.1 KILOMETERS ON SITE H-3 28 1500 441 417 465 15 INDICATOR 0 (0/24) (0/4) (0/12) SOUTHWEST WELL

(<379/<525) (<410/<423) (<379/<525) 0.1 KILOMETERS ON SITE 1-131 17 0.590 0.682 0.682 22 CONTROL 0 (0/13) (0/4) (0/4) COPELAND WELL

(<0.446/<0.830) (<0.512/<0.891) (<0.512/<0.891) 13.7 KILOMETERS N OF SITE 29 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER GAMMA 28 (PCI/LITER) MN-54 7.5 3.83 5.93 5.93 22 CONTROL 0 (0/24) (0/4) (0/4) COPELAND WELL

(<1.03/<9.31) (<2.54/<8.90) (<2.54/<8.90) 13.7 KILOMETERS N OF SITE CO-58 7.5 3.75 6.00 6.00 22 CONTROL 0 (0/24) (0/4) (0/4) COPELAND WELL

(<1.17/<7.38) (<2.78/<8.87) (<2.78/<8.87) 13.7 KILOMETERS N OF SITE FE-59 15 10.4 16.2 16.2 22 CONTROL 0 (0/24) (0/4) (0/4) COPELAND WELL

(<2.33/<24.6) (<6.20/<26.0) (<6.20/<26.0) 13.7 KILOMETERS N OF SITE CO-60 7.5 4.12 6.08 6.13 14 INDICATOR (0/24) (0/4) (0/4) PSB WELL

(<0.910/<9.10) (<2.50/<9.70) (<2.13/<9.10) 0.3 KILOMETERS ON SITE ZN-65 15 6.92 9.46 9.46 22 CONTROL 0 (0/24) (0/4) (0/4) COPELAND WELL

(<1.87/<13.0) (<5.39/< 13.7) (<5.39/<13.7) 13.7 KILOMETERS N OF SITE ZR-95 15 7.54 9.49 10.4 14 INDICATOR 0 (0/24) (0/4) (0/4) PSB WELL

(<2.26/< 14.7) (<4.62/< 13. 1) (<4.06/< 14.7) 0.3 KILOMETERS ON SITE CS-134 7.5 3.83 4.09 5.35 14 INDICATOR (0/24) (0/4) (0/4) PSB WELL

(<0.967/<9.47) (<2.42/<5.77) (<2.03/<9.47) 0.3 KILOMETERS ON SITE CS-137 9 3.61 5.92 5.92 22 CONTROL 0 (0/24) (0/4) (0/4) COPELAND WELL

(<1.04/<5.28) (<2.54/<9.35) (<2.54/<9.35) 13.7 KILOMETERS N OF SITE 30 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS GROUND WATER BA-LA-140 7.5 9.28 9.63 9.63 22 CONTROL (PCI/LITER) (0/24) (0/4) (0/4) COPELAND WELL

(<5.21/<34.2) (<5.46/< 14.8) (<5.46/<14.8) 13.7 KILOMETERS N OF SITE RA-226 2 38.7 0.160 77.2 15 INDICATOR 0 (2/24) (1/4) (0/12) SOUTHWEST WELL

(<0.099/<131) (0.087/<0.232) (<25.1/<131) 0.1 KILOMETERS ON SITE SEDIMENT GAMMA 36 (PCI/KG WET) BE-7 N/A 1114 1011 1995 17 INDICATOR (3/34) (0/2) (2/2) NORTH STORM DRAIN OUTFALL

(<410/2770) (<882/<1140) (1220/2770) 0.1 KILOMETER E OF SITE K-40 N/A 20671 13850 26150 29 INDICATOR (34/34) (2/2) (2/2) NORTH STORM DRAIN OUTFALL (9930/31600) (13200/14500) (23300/29000) 0.1 KILOMETER E OF SITE MN-54 N/A 77.6 69.0 103 19 INDICATOR (0/34) (0/2) (0/2) NORTH STORM DRAIN OUTFALL

(<37.1/<128) (<62.0/<76.0) (<78.8/<128) 0.1 KILOMETER E OF SITE CO-60 N/A 73.7 56.2 113 13 INDICATOR (1/36) (0/2) (1/2) NORTH STORM DRAIN OUTFALL

(<32.3/151) (<44.3/<68.1) (<74.5/151) 0.1 KILOMETER E OF SITE NB-95 N/A 125 116 153 23 INDICATOR (0/36) (0/2) (0/2) NORTH STORM DRAIN OUTFALL

(<50.2/<176) (<103/<129) (<141/<164) 0.1 KILOMETER E OF SITE CS-134 150 61.4 57.2 71.4 22 INDICATOR (0/36) (0/2) (0/2) NORTH STORM DRAIN OUTFALL

(<28.2/<74.2) (<54.8/<59.6) (<68.9/<73.8) 0.1 KILOMETER E OF SITE 31 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT CS-137 180 132 70.5 203 19 INDICATOR (PCI/KG WET) (24/36) (0/2) (2/2) NORTH STORM DRAIN OUTFALL

(<59.3/232) (<60.8/<80.1) (178/228) 0. 1KILOMETER E OF SITE BA-LA- 140 N/A 1066 1027 1395 18 INDICATOR (0/36) (0/2) (0/2) NORTH STORM DRAIN OUTFALL

(<249/<2300) (<514/<1540) (<490/<2300) 0.1 KILOMETER E OF SITE RA-226 N/A 2570 1520 3400 13 INDICATOR (28/36) (1/2) (2/2) NORTH STORM DRAIN OUTFALL

(<1130/3680) (<1280/1730) (3290/3510) 0.1 KILOMETER E OF SITE AC-228 N/A 2275 1845 3515 31 INDICATOR (29/36) (2/2) (2/2) NORTH STORM DRAIN OUTFALL

(<216/4560) (1600/2090) (3090/3940) 0.1 KILOMETER E OF SITE TH-228 N/A 1599 987 1960 29 INDICATOR (36/36) (2/2) (2/2) NORTH STORM DRAIN OUTFALL (798/2100) (984/990) (1950/1970) 0.1 KILOMETER E OF SITE TH-232 N/A 1376 763 1725 25 INDICATOR (36/36) (2/2) (2/2) NORTH STORM DRAIN OUTFALL (694/1870) (712/814) (1580/1870) 0.1 KILOMETER E OF SITE U-238 N/A 7578 6595 9395 23 INDICATOR (0/36) (0/2) (0/2) NORTH STORM DRAIN OUTFALL

(<4050/<11100) (<6500/<6690) (<9130/<9660) 0.1 KILOMETER E OF SITE TEST WELLS GR-B 20 4 9.91 N/A 16.2 14 INDICATOR (PCI/LITER) (20/20) (5/5) TEST WELL 201 (5.12/22.5) (12.0/22.5) ON SITE 32 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS TEST WELLS H-3 20 3000 473 N/A 481 18 INDICATOR 0 (PCI/LITER) (0/20) (0/5) TEST WELL 204

(<425/<549) (<444/<540) ON SITE GAMMA 20 K-40 N/A 29.1 N/A 35.6 18 INDICATOR (4/20) (3/5) TEST WELL 204

(<7.97/<72.2) (<8.63/45.0) ON SITE MN-54 15 1.61 N/A 1.74 18 INDICATOR 0 (0/20) (0/5) TEST WELL 204

(<0.886/<3.97) (<0.987/<3.97) ON SITE CO-58 15 1.77 N/A 1.90 18 INDICATOR 0 (0/20) (0/5) TEST WELL 204

(<1. 15/<3.69) (<1.24/<3.69) ON SITE FE-59 30 4.14 N/A 4.46 18 INDICATOR 0 (0/20) (0/5) TEST WELL 204

(<2.44/<7.73) (<2.89/<7.73) ON SITE CO-60 15 1.58 N/A 1.76 14 INDICATOR 0 (0/20) (0/5) TEST WELL 201

(<0.839/<4.46) (<0.839/<4.46) ON SITE NB-95 15 2.02 N/A 2.19 18 INDICATOR 0 (0/20) (0/5) TEST WELL 204

(<1.11/<4.39) (<1.38/<4.35) ON SITE 1-131 15 16.2 N/A 18.0 14 INDICATOR 0 (0/20) (015) TEST WELL 201

(<3.46/<69.8) (<4.02/<69.8) ON SITE 33 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS TEST WELLS CS-134 15 1.49 N/A 1.62 18 INDICATOR 0 (PCI/LITER) (0/20) (0/5) TEST WELL 204

(<0.790/<3.81) (<0.881/<3.81) ON SITE CS-137 18 1.67 N/A 1.73 18 INDICATOR 0 (0/20) (0/5) TEST WELL 204

(<0.966/<4.0 I) (<1.01/<4.00) ON SITE BA-LA-1 40 15 7.37 N/A 7.52 14 INDICATOR 0 (0/20) (0/5) TEST WELL 201

(<3.01/<14.9) (<3.36/< 14.8) ON SITE MILK 1-131

95 1 0.566 0.635 0.720 24 CONTROL 0 (PCI/LITER) (3/54) (2/41) (1/5) COUNTY FARM (0.410/<0.972) (0.426/<0.967) (0.581/<0.967) 21.6 KILOMETERS N OF SITE SR-89 22 10 5.13 5.19 5.58 24 CONTROL 0 (0/12) (0/10) (0/2) COUNTY FARM

(<3.31/<6.57) (<3.37/<6.31) (<5.58/<5.58) 21.6 KILOMETERS N OF SITE SR-90 22 2 0.940 1.31 1.86 22 CONTROL 0 (2/12) (4/10) (4/4) FRANKLIN FARM

(<0.723/1.28) (<0.642/2.71) (0.846/2.71) 9.7 KILOMETERS WSW OF SITE GAMMA 95 BE-7 N/A 50.7 54.0 55.6 20 CONTROL 0 (0/54) (0/41) (0/18) DUNKLEE FARM

(<38.1/<69.5) (<38.8/<81.2) (<42.5/<71.9) 5.5 KILOMETERS S OF SITE K-40 N/A 1477 1597 1630 20 CONTROL 0 (54/54) (41/41) (18/18) DUNKLEE FARM (1256/1768) (1361/1853) (1486/1853) 5.5 KILOMETERS S OF SITE 34

Positive 1-131 is attributed to the Fukushima incident.

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK CS-134 15 6.03 6.62 7.44 20 CONTROL 0 (PCI/LITER) (0/54) (0/41) (0/18) DUNKLEE FARM

(<3.51/<9.88) (<3.70/<10.6) (<4.51 /<9.99) 5.5 KILOMETERS S OF SITE CS-137 18 6.44 7.02 7.44 24 CONTROL 0 (0/54) (0/41) (0/5) COUNTY FARM

(<4.25/<9.29) (<4.67/<10.0) (<6.10/<9.01) 21.6 KILOMETERS N OF SITE RA-226 N/A .140 158 162 18 INDICATOR (14/54) (11/41) (3/18) BLODGETT FARM (64.9/<207) (98.6/266) (125/<207) 3.6 KILOMETERS SE OF SITE BA-LA- 140 N/A 7.61 8.45 9.38 24 CONTROL 0 (0/54) (0/41) (0/5) COUNTY FARM

(<4.65/< 12.3) (<4.63/< 13.2) (<6.16/<13.2) 21.6 KILOMETERS N OF SITE SILAGE 1-131 5 N/A 22.4 38.8 57.0 22 CONTROL 0 (PCI/KG) (0/3) (0/2) (0/1) FRANKLIN FARM

(<16.5/<32.9) (<20.6/<57.0) N/A 9.7 KILOMETERS WSW OF SITE GAMMA 5 BE-7 N/A 582 478.0 1310 14 INDICATOR 0 (2/3) (1/2) (1/1) BROWN FARM (126/1310) (<193/762) N/A 2.2 KILOMETERS S OF SITE K-40 N/A 3917 13130 22140 22 CONTROL (3/3) (2/2) (1/1) FRANKLIN FARM (2437/5739) (4119/22140) N/A 9.7 KILOMETERS WSW OF SITE CS-134 N/A 30.0 31.9 45.0 I I INDICATOR 0 (0/3) (0/2) (0/1) MILLER FARM

(<22.1/<45.0) (< 19. 1/<44.6) N/A 0.8 KILOMETERS W OF SITE 35 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SILAGE CS-137 N/A 24.2 44.6 66.5 22 CONTROL 0 (PCI/KG) (0/3) (0/2) (0/I) FRANKLIN FARM

(<17,5/<33.0) (<22.7/<66.5) N/A 9.7 KILOMETERS WSW OF SITE ACTH-228 N/A 103 156 238 22 CONTROL 0

.(0/3) (0/2) (0/1) FRANKLIN FARM

(<71.9/<151) (<74.4/<238) N/A 9.7 KILOMETERS WSW OF SITE MIXED GRASS 1-131 21 N/A 44.4 49.2 55.2 II INDICATOR 0 (PCI/KG) (0/18) (0/3) (0/3) RIVER STA. NO. 3.3

(<28.8/<59.1) (<44.7/<52.7) (<50.4/<59.1) 1,9 KILOMETERS SSE OF SITE GAMMA 21 BE-7 N/A 1915 3389 3411 15 INDICATOR 0 (15/18) (2/3) (3/3) TYLER HILL RD.

(<287/8878) (<322/8524) (564/8878) 3.1 KILOMETERS WNW OF SITE K-40 N/A 7056 6830 8629 14 INDICATOR 0 (18/18) (3/3) (3/3) NORTHFIELD, MA (4008/10500) (4756/8290) (6552/10500) 11.6 KILOMETERS SSE OF SITE CS-134 30 45.3 46.6 50.6 40 INDICATOR 0 (0/18) (0/3) (0/3) GOV. HUNT HOUSE

(<31.3/<58.7) (<40.6/<51.9) (<43.8/<57.7) ON SITE CS-137 40 44.2 48.1 50.8 II INDICATOR 0 (0/18) (0/3) (0/3) RIVER STA. NO. 3.3

(<32.0/<57.6) (<35.1/<68.1) (<48.3/<53.7) 1.9 KILOMETERS SSE OF SITE RA-226 N/A 781 867 913 11 INDICATOR 0 (8/18) (1/3) (1/3) RIVER STA. NO. 3.3 (564/1034) (608/<1 040) (833/<960) 1.9 KILOMETERS SSE OF SITE 36 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MIXED GRASS ACTH-228 N/A 152 195 195 21 CONTROL 0 (PCI/KG) (0/18) (0/3) (0/3) SPOFFORD LAKE

(<101/<189) (<184/<206) (<184/<206) 16.4 KILOMETERS NNE OF SITE FISH GAMMA 32 N/A (PCI/KG) K-40 3093 3239 3239 21 CONTROL 0 (16/16) (16/16) (16/16) RT. 9 BRIDGE (2140/4292) (1740/4940) (1740/4940) 11.8 KILOMETERS NNW OF SITE MN-54 130 34.7 34.2 34.7 II INDICATOR 0 (0/16) (0/16) (0/16) VERNON POND

(<16. 1/<49.6) (<15.01<51.1) (<16. 1/<49.6) 0.6 KILOMETERS SSE OF SITE CO-58 130 44.6 44.4 44.6 II INDICATOR (0/16) (0/16) (0/16) VERNON POND

(<28.3/<61.9) (<25.6/<57.9) (<28.3/<61.9) 0.6 KILOMETERS SSE OF SITE FE-59 260 115 112 115 11 INDICATOR 0 (0/16) (0/16) (0/16) VERNON POND

(<61.6/<128) (<85.8/<130) (<61.6/<128) 0.6 KILOMETERS SSE OF SITE CO-60 130 30.3 32.5 32.5 21 CONTROL 0 (0/16) (0/16) (0/16) RT. 9 BRIDGE

(<13.3/<47.8) (<12.6/<63.3) (<12.6/<63.3) 11.8 KILOMETERS NNW OF SITE ZN-65 260 75.0 70.6 75.0 11 INDICATOR (0/16) (0/16) (0/16) VERNON POND

(<36.9/<1 15) (<33.7/<107) (<36.9/<1 15) 0.6 KILOMETERS SSE OF SITE CS-134 130 38.8 33.2 38.8 II INDICATOR 0 (0/16) (0/16) (0/16) VERNON POND

(<1 5.4/<62.8) (<13.4/<49.7) (<1 5.4/<62.8) 0.6 KILOMETERS SSE OF SITE 37 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) " MEASUREMENTS FISH CS-137 150 44.4 45.1 45.1 21 CONTROL 0 (PCI/KG) (0/16) (0/16) (0/16) RT. 9 BRIDGE

(<13.9/<74.5) (< 16.4/<70.6) (<16.4/<70.6) 11.8 KILOMETERS NNW OF SITE TRITIUM 16 N/A 419 411 419 II INDICATOR (0/8) (0/8) (0/8) VERNON POND

(<83.8/<696) (<84.6/<689) (<83.8/<696) 0.6 KILOMETERS SSE OF SITE AM-24I 32 N/A 5.16 4.57 5.16 11 INDICATOR (0/16) (0/16) (0/16) VERNON POND

(<1.95/<10.6) (<0.774/<8.77) (<1.95/<10.6) 0.6 KILOMETERS SSE OF SITE CM-242 32 N/A 2.82 2.65 2.82 11 INDICATOR (0/16) (0/16) (0/16) VERNON POND

(<0.642/<6.04) (<0.728/<8.56) (<0.642/<6.04) 0.6 KILOMETERS SSE OF SITE CM-243/244 32 N/A 4.85 5.41 5.41 21 CONTROL (0/16) (0/16) (0/16) RT. 9 BRIDGE

(<0.772/<10.8) (<2.10/<20.2) (<2. 10/<20.2) 11.8 KILOMETERS NNW OF SITE FE-55 32 N/A 1604 1758 1758 21 CONTROL (0/16) (0/16) (0/16) RT. 9 BRIDGE

(<616/<3510) (<427/<4060) (<427/<4060) 11.8 KILOMETERS NNW OF SITE NI-63 32 N/A 196 192 196 11 INDICATOR (0/16) (0/16) (0/16) VERNON POND

(<110/<331) (<102/<306) (<110/<331) 0.6 KILOMETERS SSE OF SITE PU-238 32 N/A 7.40 13.3 13.3 21 CONTROL (0/16) (0/16) (0/16) RT. 9 BRIDGE

(<0.988/<24.1) (<2.67/<97.5) (<2.67/<97.5) 11.8 KILOMETERS NNW OF SITE 38 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE VERMONT YANKEE NUCLEAR POWER PLANT, 2011 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER: 50-271 Location of Facility: VERNON, VT REPORTING PERIOD: 2011 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS FISH PU-239/240 32 N/A 5.18 5.70 5.70 21 CONTROL 0 (PCI/KG) (0/16) (0/16) (0/16) RT. 9 BRIDGE

(<1.77/<15.2) (<2.26/< 13.8) (<2.26/<13.8) 11.8 KILOMETERS NNW OF SITE PU-241 32 N/A 823 920 920 21 CONTROL 0 (0/16) (0/16) (0/16) RT. 9 BRIDGE

(<403/<2270) (<488/<2230) (<488/<2230) 11.8 KILOMETERS NNW OF SITE PU-242 32 N/A 3.11 3.33 3.33 21 CONTROL (0/16) (0/16) (0/16) RT. 9 BRIDGE

(<0.988/<12.4) (<1.14/<8.89) (<1. 14/<8.89) 11.8 KILOMETERS NNW OF SITE SR-89 32 N/A 104 101 104 11 INDICATOR 0 (0/16) (0/16) (0116) VERNON POND

(<57.6/<182) (<63.6/<I185) (<57.6/<182) 0.6 KILOMETERS SSE OF SITE SR-90 32 N/A 41.8 41.4 41.8 II INDICATOR (2/16) (6/16) (2/16) VERNON POND

(<18.8/76.6) (<22.5/58.4) (<18.8/76.6) 0.6 KILOMETERS SSE OF SITE DIRECT RADAIATION TLD-QUARTERLY 212 N/A 7 6 13 DR-45 INDICATOR 0 (MILLI-ROENTGEN/QTR.) (204/204) (8/8) (4/4) SITE BOUNDARDY (5/15) (5/7) (12/15) 0.12 KILOMETERS NE OF SITE

REMP samples obtained from this air iodine and milk locations during 2011 identified detectable concentrations of isotopes that could be related to operation of Entergy Vermont Yankee.

Given the following facts, the detectable concentrations are not a result of Entergy Vermont Yankee operation:

(1) The quantities of radioactive airborne effluents from Entergy Vermont Yankee during 2011 did not increase significantly compared to year 2010.

(2) Prior REMP sample results have not detected the presence of these isotopes in air and milk samples collected in support of the Entergy Vermont Yankee REMP.

(3) The concentrations being detected in the indicator samples were also identified in the control samples for from Entergy Vermont Yankee.

As such, the atypical detection of these radionuclides in both indicator and control samples is credibly attributed to the trans-Pacific transport of airborne releases from Dai-lchi, Fukushima following the March 11, 2011 Tohoku earthquake and is not related to the operations of Entergy Vermont Yankee.

39 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.2 ENVIRONMENTAL TLD DATA

SUMMARY

VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY - DECEMBER 2011)

OFFSITE STATION INNER RING TLD OUTER RING TLD WITH HIGHEST MEAN CONTROL TLDs MEAN* MEAN* STA.NOJ MEAN* MEAN*

RANGE* RANGE* RANGE* RANGE*

(NO. MEASUREMENTS)' (NO. MEASUREMENTS)- (NO. MEASUREMENTS)- (NO. MEASUREMENTS)*"

6.37

0.31 6.45

0.32 DR36 7.42 t 0.47 6.50 +/- 0.29 5.32 to 7.87 4.98 to 7.74 7.39 to 8.65 5.27 to 7.12 76 68 4 8 SITE BOUNDARY TLD WITH HIGHEST MEAN SITE BOUNDARY TLD STA.NO./ MEAN* MEAN*

RANGE* RANGE (NO. MEASUREMENTS)- (NO. MEASUREMENTS)"

DR45 13.23 +/- 1.32 8.11 +/- 0.38 11.84 to 14.89 4.82 to 14.89 4 60

Units are in micro-R per hour.

Each "measurement" is typically based on quarterly readings from five TLD elements.

40

TABLE 5.3 ENVIRONMENTAL TLD MEASUREMENTS 2011 (Micro-R per Hour)

ANNUAL Sta. 1ST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER AVE.

No. Description EXP. S.D. EXP. S.D. EXP. S.D. EXP. S.D. EXP.

DR-01 River Sta. No. 3.3 5.76 + 0.20 6.02 + 0.30 5.82 + 0.23 6.32 + 0.30 6.0 DR-02 N Hinsdale, NH 5.61 + 0.21 6.99 + 0.36 6.78 + 0.36 7.44 + 0.28 6.7 DR-03 Hinsdale Substation 6.06 + 0.25 7.46 + 0.23 7.14 + 0.37 7.67 + 0.37 7.1 DR-04 Northfield, MA 5.10 + 0.24 5.99 + 0.22 5.53 + 0.29 6.45 + 0.24 5.8 DR-05 Spofford Lake, NH 5.27 + 0.26 6.81 + 0.25 6.47 + 0.32 7.12 + 0.29 6.4 DR-06 Vernon School 5.82 + 0.29 6.80 + 0.27 6.57 + 0.34 7.09 + 0.32 6.6 DR-07 Site Boundary 6.81 + 0.24 8.37 + 0.38 7.79 + 0.29 8.00 + 0.28 7.7 DR-08 Site Boundary 7.98 + 0.28 9.17 + 0.35 8.38 + 0.30 8.47 + 0.34 8.5 DR-09 Inner Ring 5.75 + 0.49 6.28 + 0.32 5.74 + 0.35 6.98 + 0.33 6.2 DR-10 Outer Ring 5.00 + 0.28 5.58 + 0.24 4.98 + 0.31 .5.85 + 0.26 5.4 DR-11 Inner Ring 5.38 + 0.26 6.11 + 0.29 5.53 + 0.22 6.28 + 0.31 5.8 DR-12 Outer Ring 5.41 + 0.35 5.74 + 0.24 5.61 + 0.28 6.00 + 0.30 5.7 DR-13 Inner Ring 5.87 + 0.44 6.73 + 0.33 5.90 + 0.32 7.07 + 0.21 6.4 DR-14 Outer Ring 6.14 + 0.41 7.74 + 0.36 6.97 + 0.35 7.73 + 0.37 7.1 DR-15 Inner Ring 6.38 + 0.40 6.88 + 0.25 6.20 + 0.28 6.72 + 0.28 6.5 DR-16 Outer Ring 6.63 + 0.32 6.99 + 0.28 6.60 + 0.33 7.52 + 0.49 6.9 DR-17 Inner Ring 5.43 + 0.28 6.36 + 0.32 5.76 + 0.33 6.42 + 0.22 6.0 DR-1 8 Outer Ring 5.67 + 0.27 6.63 + 0.26 6.13 + 0.48 6.89 + 0.49 6.3 DR-19 Inner Ring 5.99 + 0.27 7.40 + 0.32 7.07 + 0.29 7.87 + 0.28 7.1 DR-20 Outer Ring 6.07 + 0.33 7.28 + 0.32 6.56 + 0.37 7.39 + 0.43 6.8 DR-21 Inner Ring 5.32 + 0.30 6.59 + 0.32 6.36 + 0.32 7.05 + 0.29 6.3 DR-22 Outer Ring 5.92 + 0.24 6.92 + 0.48 6.29 + 0.31 7.19 + 0.47 6.6 DR-23 Inner Ring 5.74 + 0.21 5.87 + 0.33 5.71 + 0.22 6.29 + 0.31 5.9 DR-24 Outer Ring 5.12 + 0.19 5.97 + 0.23 5.40 + 0.42 6.36 + 0.22 5.7 DR-25 Inner Ring 5.68 + 0.29 6.37 + 0.30 5.69 + 0.25 6.88 + 0.28 6.2 DR-26 Outer Ring 5.32 + 0.25 6.84 + 0.30 6.41 + 0.32 6.99 + 0.26 6.4 DR-27 Inner Ring 5.72 + 0.62 6.32 + 0.29 5.84 + 0.22 6.64 + 0.23 6.1 DR-28 Outer Ring 5.77 + 0.29 6.76 + 0.27 6.38 + 0.25 6.98 + 0.22 6.5 DR-29 Inner Ring 5.94 + 0.29 6.60 + 0.35 6.11 + 0.27 7.30 + 0.39 6.5 DR-30 Outer Ring 5.46 + 0.22 6.65 + 0.26 6.17 + 0.30 7.00 + 0.34 6.3 DR-31 Inner Ring 5.57 + 0.25 6.48 + 0.41 6.36 + 0.40 7.01 + 0.31 6.4 DR-32 Outer Ring 5.40 + 0.23 6.27 + 0.30 5.97 + 0.32 6.48 + 0.33 6.0 DR-33 Inner Ring 5.97 + 0.26 6.47 + 0.27 6.49 + 0.29 7.33 + 0.41 6.6 DR-34 Outer Ring 5.87 + 0.31 6.89 + 0.28 6.69 + 0.32 6.99 + 0.39 6.6 DR-35 Inner Ring 5.63 + 0.35 6.33 + 0.27 6.06 + 0.36 6.62 + 0.43 6.2 DR-36 Outer Ring 7.20 + 0.83 7.70 + 0.32 7.07 + 0.39 7.70 + 0.32 7.4 DR-37 Inner Ring 5.52 + 0.31 6.73 + 0.28 6.71 + 0.30 7.01 + 0.25 6.5 DR-38 Outer Ring 5.69 + 0.28 6.72 + 0.36 6.56 + 0.37 7.27 + 0.27 6.6 DR-39 Inner Ring 6.10 + 0.51 6.58 + 0.29 6.77 + 0.33 7.10 + 0.29 6.6 DR-40 Outer Ring 6.05 + 0.31 6.70 + 0.26 6.33 + 0.34 7.10 + 0.33 6.5 Note: Blank spaces indicate missing TLDs 41

TABLE 5.3 (cont)

ENVIRONMENTAL TLD MEASUREMENTS 2011 (Micro-R per Hour)

ANNUAL Sta. 1ST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER AVE.

No. Description EXP. S.D. EXP. S.D. EXP. S.D. EXP. S.D. EXP.

DR-07 Site Boundary 6.81 + 0.24 8.37 + 0.38 7.79 + 0.29 8.00 + 10.28 7.7 DR-08 Site Boundary 7.98 + 0.28 9.17 + 0.35 8.38 + 0.30 8.47 + 0.34 8.5 DR-41 Site Boundary 6.41 + 0.29 7.16 + 0.26 7.18 + 0.35 7.20 + 0.28 7.0 DR-42 Site Boundary 5.58 + 0.28 6.89 + 0.45 6.75 + 0.25 7.04 + 0.31 6.6 DR-43 Site Boundary 6.40 + 0.40 7.69 + 0.38 7.50 + 0.33 7.80 + 0.43 7.4 DR-44 Site Boundary 9.51 + 0.47 9.63 + 0.39 8.77 + 0.37 9.23 + 0.50 9.3 DR-45 Site Boundary 14.89 + 0.67 12.60 + 0.45 11.84 + 0.82 13.61 + 0.79 13.2 DR-46 Site Boundary 8.48 + 0.34 8.91 + 0.44 8.54 + 0.41 9.20 + 0.51 8.8 DR-47 Site Boundary 6.99 + 0.24 7.50 + 0.27 7.74 + 0.35 8.08 + 0.34 7.6 DR-48 Site Boundary 4.82 + 0.27 5.93 + 0.19 5.68 + 0.26 6.45 + 0.38 5.7 DR-49 Site Boundary 5.52 + 0.24 6.04 + 0.26 6.14 + 0.35 6.48 + 0.26 6.0 DR-50 Governor Hunt House 6.25 + 0.26 7.09 + 0.31 7.01 + 0.27 7.44 + 0.22 7.0 DR-51 Site Boundary 7.11 + 0.28 8.55 + 0.39 8.19 + 0.35 8.64 + 0.50 8.1 DR-52 Site Boundary 8.81 + 0.40 9.47 + 0.30 9.39 + 0.40 9.21 + 0.58 9.2 DR-53 Site Boundary 8.98 + 0.47 10.18 + 0.47 9.68 + 0.41 9.76 + 0.35 9.7 42

6. ANALYSIS OF ENVIRONMENTAL RESULTS 6.1 Sampling Program Deviations Off-site Dose Calculation Manual Control 3.5.1 allows for deviations "if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons." In 2011, eleven deviations were noted in the REMP. These deviations did not compromise the program's effectiveness and are considered typical with respect to what is normally anticipated for any radiological environmental program. The specific deviations for 2011 were:

a) The South River Station River Water pump which provides a river water sample to the composite sampler at this location was found to be out of service on March 18, 2011. It was determined that the water pump had ceased function as a result a short-term interruption of electrical service to the station as a result of a winter storm. When the electrical power was restored the cold weather had frozen the water lines from the river to the sample station. The water lines were thawed and the pump restored to service on March 23, 2011.

b) Radioiodine (Iodine-131) was indentified on one offsite environmental station (North Hinsdale APCF-12) charcoal filter for the week ending March 29, 2011. The cartridge was collecting sample from March 22 through March 29, 2011. The measured concentration of Iodine-131 was approximately 0.05 picocuries per cubic meter of collected air volume. This activity was attributed to the recent accident at Fukushima Daiichi Nuclear Power Station in Japan since no increase in radioiodines was measured in the reactor coolant at Vermont Yankee prior to the collection of this sample.

c) All of the charcoal cartridges removed from Vermont Yankee's Offsite Environmental Air Sample Stations on April 5, 2011 (continuously collecting sample volume from March 29, 2011 through April 5, 2011) were found to have detectable levels of Iodine- 131. The highest concentration of all of the seven filters was found at the Governor Hunt House station (APCF-40) located at the western edge of the Vermont Yankee Owner Control Area. Each of the Control Location Stations (Spofford New Hampshire and Northfield Massachusetts) as well as the other four Indicator Stations were found to have measurable concentrations of Iodine-131. The highest concentration of the seven samples was measured at 0.109 picocuries per cubic meter of air sampled. This is approximately 12.1 percent (%)

of the required reporting level for air samples. This activity was attributed to the recent accident at Fukushima Daiichi Nuclear Power Station in Japan since no increase in radioiodines was measured in the reactor coolant at Vermont Yankee prior to the collection of this sample.

d) Four of the five dairies' milk samples collected on April 5, 2011 were found to have detectable levels of Iodine-131. The highest concentration of all of the four positive milk samples was measured at 0.777 picocuries per liter of milk. The samples concentrations for Iodine-131 ranged from the highest at 0.777 picocuries per liter of milk to the lowest at 0.410 picocuries per liter of milk. Iodine- 131 was measured in both Control and Indicator dairies supplying milk samples to the Vermont Yankee Radiological Environmental Monitoring Program (REMP). The Vermont Yankee Offsite Dose Calculation Manual Table 3.5.2 specifies a reporting level of 3.0 picocuries per liter of milk sampled.

The highest concentration of the seven samples was measured at 0.777 picocuries per cubic meter of air sampled. This is approximately 25.9 percent (%) of the required reporting level for milk samples in VY ODCM Table 3.5.2. This activity was attributed to the recent accident at Fukushima Daiichi 43

Nuclear Power Station in Japan since no increase in radioiodines was measured in the reactor coolant at Vermont Yankee prior to the collection of this sample.

e) Four of the seven charcoal cartridges removed from Vermont Yankee's Offsite Environmental Air Sample Stations on April 12, 2011 (continuously collecting sample volume from April 5th, 2011 through April 12, 2011) were found to have detectable levels of Iodine-131. The highest concentration of all of the four filters was found at the Tyler Hill Road (Vernon) station (APCF-15) located west of the Vermont Yankee plant site. One of the Control Location Stations (Spofford New Hampshire) as well as two other Indicator Stations (River Station-APCF-1 1 and Hinsdale Substation-APCF- 13) were found to have measurable concentrations of Iodine- 131. The Vermont Yankee Offsite Dose Calculation Manual Table 3.5.2 specifies a reporting level of 0.900 picocuries per cubic meter of air sampled. The highest concentration of the four samples was measured at 0.0430 picocuries per cubic meter of air sampled. This is approximately 4.8 percent (%) of the required reporting level for Iodine-131 found in air samples. This activity was attributed to the recent accident at Fukushima Daiichi Nuclear Power Station in Japan since no increase in radioiodines was measured in the reactor coolant at Vermont Yankee prior to the collection of this sample.

f) The South River Station-River Water Composite Sampler was not receiving water sample from the Connecticut River on April 10, 2011. There was no water flow to the River Water Composite Sampler at the South River Station (Station #3-3) located off Stebbins Road in Vernon, Vermont.

The submersible pump was found to be fouled with river silt and the line from the pump to the sampler was also clogged with silt due to elevated silt levels in the river from spring melting conditions. The lines were cleared and the pump replaced and the station was restored to full function on May 12, 2011.

g) The South River Station-River Water Composite Sampler Submersible Pump was removed from service for a short period due to noisy South River Station Temperature Monitor data on May 19, 2011. This action was taken because the primary temperature monitor was providing a noisy signal while the submersible pump is operating. The backup downstream river temperature monitor, to be utilized in the event that data is unavailable from the primary temperature monitor, has been out of service for an extended period. The temperature monitor was replaced and the submersible pump was restored to service on May 19, 2011.

h) The South River Station - River Water Composite Sampler Submersible Pump was found out of service on 6/14/2011. The submersible pump was replaced following removal of silt from the sample tube. This replacement was completed on 6/15/2011 and river water sample flow was restored to the River Water Composite Sampler. The submersible pump was found to have failed as a result of silting of the steel pump deployment tube. The silting of the tube occurred during a period of high river water level due to recent heavy rainfall events over much of Vermont and New Hampshire.

i) The South River Station - River Water Composite Sampler Submersible Pump was found out of service on October 9, 2011. The pump controller was found to have failed due to a power surge and was replaced. River water sample flow was restored to the River Water Composite Sampler following this replacement on October 9, 2011.

j) During a review of the air sample collection data for week #44, year 2011, it was determined that three air sample stations were not collecting air sample volume for a period of time following a significant snowstorm in the area on October 29, 2011. The remaining four air sample stations did not lose power supply and lost no sample collection time during the same week. APCF- 12 (located in North Hinsdale, NH) was out of power for approximately 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . APCF-14 (Located in Northfield Massachusetts) was out of power for approximately 29.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . APCF-15 (located on Tyler Hill 44

Road in Vernon, Vermont) was out of power for approximately 3.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months . All three sample stations were performing sample collection properly when weekly samples were collected on 11/1/2011.

k) Continuous environmental air sample collection at the offsite environmental air sample station (APCF-14) located in Northfield Massachusetts was interrupted during Week 49 in year 2011. A fuse was found to have failed at the offsite environmental air sample station. This resulted in a loss of sample collection for a period of approximately 77 hours8.912037e-4 days 0.0214 hours 1.273148e-4 weeks 2.92985e-5 months during week 49. The technician replaced the blown fuse and the sample station then functioned normally with no observable problems.

I) Air sample station outages during 2011 are reflected in the air sample collection time percentages listed below.

AP/CF # 1 st Quarter 2 nd Quarter 3 rd Quarter 4th Quarter 11 100% 99.7% 100% 99.7%

12 99.9% 99.5% 99.7% 99.7%

13 100% 99.9% 100% 98.5%

14 87.4% 100% 87.4% 84.8%

15 99.9% 99.6% 100% 99.7%

21 99.3% 100% 100% 99.8%

40 100% 100% 98.9% 99.6%

6.2 Comparison of Achieved LLDs with Requirements Table 4.5.1 of the VYNPS ODCM (also shown in Table 4.4 of this report) gives the required Lower Limits of Detection (LLDs) for environmental sample analyses. On occasion, an LLD is not achievable due to a situation such as a low sample volume caused by sampling equipment malfunction or limited sample availability. In such a case, ODCM 10.2 requires a discussion of the situation. At the contracted environmental laboratory, the target LLD for the majority of analyses is 50 percent of the most restrictive required LLD. Expressed differently, the typical sensitivities achieved for each analysis are at least 2 times greater than that required by the VYNPS ODCM.

For each analysis having an LLD requirement in ODCM Table 4.5.1, the a posteriori(after the fact) LLD calculated for that analysis was compared with the required LLD. During 2011, all sample analyses performed for the REMP program achieved an a posterioriLLD less than the corresponding LLD requirement.

6.3 Comparison of Results with Reporting Levels ODCM Section 10.3.4 requires written notification to the NRC within 30 days of receipt of an analysis result whenever a Reporting Level in ODCM Table 3.5.2 is exceeded. Reporting Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I.

Environmental concentrations are averaged over the calendar quarters for the purposes of this 45

comparison. The Reporting Levels are intended to apply only to measured levels of radioactivity due to plant effluents. During 2011, no analytical result exceeded a corresponding reporting level requirement in Table 3.5.2 of the ODCM.

6.4 Changes in Sampling Locations The Vermont Yankee Nuclear Power Station Off-Site Dose Calculation Manual Section 10.2 states that 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." There were no required sampling location changes due to the Land Use Census conducted in 2011.

Milk collection from Dunklee Farm (Vern-Mont Farm in Vernon) commenced in April, 2010 at the request of the farm owner. At this time, all dairy farms in Vernon are supplying milk for analysis.

County Farm, located in Westmoreland, New Hampshire, ceased operations on May 4, 2011 as a result of completion of the new County Correctional Facility in Marlborough, New Hampshire.

6.5 Data Analysis by Media Type The 2011 REMP data for each media type is discussed below. Whenever a specific measurement result is presented, it is given as the concentration in the units of the sample (volume or weight). An analysis is considered to yield a "detectable measurement' when the concentration exceeds three times the standard deviation for that analysis and is greater than or equal to the Minimum Detectable Concentration (MDC) for the analysis. With respect to data plots, all net concentrations are plotted as reported, without regard to whether the value is "detectable" or "non-detectable." In previous years, values that were less than the MDC were converted to zero.

6.5.1 Airborne Pathways 6.5.1.1 Air Particulates (AP)

The periodic air particulate filters from each of the seven sampling sites were analyzed for gross-beta radioactivity. At the end of each quarter, the filters from each sampling site were composited for a gamma analysis. The results of the air particulate sampling program are shown in Table 5.1 and Figures 6.1 through 6.7.

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Gross beta activity was detected in all air particulate filters that were analyzed. As shown in Figure 6.1, there is no significant difference between the quarterly average concentrations at the indicator (near-plant) stations and the control (distant from plant) stations. Notable in Figure 6.1 is a distinct annual cycle, with the minimum concentration in the fourth quarter, and the maximum concentration in the third quarter.

Figures 6.2 through 6.7 show the weekly gross beta concentration at each air particulate sampling location compared to the control air particulate sampling location at AP-21 (Spofford Lake, NH). Small differences are evident and expected between individual sampling locations. Figure 6.2 clearly demonstrates the distinct annual cycle, with the minimum concentration in the second quarter, and the maximum concentration in the first quarter. It can be seen that the gross-beta measurements on air particulate filters fluctuate significantly over the course of a year. The measurements from control station AP-21 vary similarly, indicating that these fluctuations are due to regional changes in naturally-occurring airborne radioactive materials, and not due to Vermont Yankee operations.

There were two naturally-occurring gamma-emitting radionuclides detected on the air particulate filters during this reporting period. Be-7, a naturally-occurring cosmogenic radionuclide, was detected on 28 of 28 filter sets analyzed. K-40 was detected on three out of 28 analyzed. Ra-226 and AcITh-228 were not detected in the 28 filter sets analyzed.

6.5.1.2 Charcoal Cartridges (CF)

Charcoal cartridges from each of the seven air sampling sites were analyzed for 1-131 each time they were collected. The results of these analyses are summarized in Table 5.1. As in previous years, no 1-131 attributable to the operation of Entergy Vermont Yankee was detected in any charcoal cartridge. The I-131 detected in 12 out of 361 samples is directly attributed to the trans-Pacific transport of airborne releases from Dai-Ichi Fukushima following the March 11, 2011 Tohoku earthquake.

6.5.2 Waterborne Pathways 6.5.2.1 River Water (WR)

Aliquots of river water were automatically collected periodically from the Connecticut River downstream from the plant discharge area and hydro station, location WR- 11, with the exception of the two events of short duration when the sampling equipment was out of service (see Section 6.1). Monthly grab samples were also collected at the upstream control location, also on the Connecticut River, location WR-21. The composited samples at WR-I 1 were collected monthly and sent along with the WR-21 grab samples to 47

the contracted environmental laboratory for analysis. Table 5.1 shows that gross-beta measurements were positive in 12 out of 12 indicator samples and 11 out of 12 control samples, as would be expected, due to naturally-occurring radionuclides in the water. As seen in Figure 6.8, the mean concentration of the indicator locations was similar to the mean concentration at the control location in 2011.

For each sampling site, the monthly samples were composited into quarterly samples for H-3 (Tritium) analyses. None of the samples contained detectable quantities of H-3.

There was one naturally-occurring gamma-emitting radionuclides detected in river water samples during this reporting period. Ra-226, a naturally-occurring primordial radionuclide, was detected in 17 of 24 samples analyzed.

6.5.2.2 Ground Water - Potable Drinking Water (WG)

Quarterly ground water (deep wells supplying drinking water to the plant and selected offsite locations) samples were collected from four indicator locations (only one is required by VYNPS ODCM) and one control location during 2011. In 1999, WG-14 (PBS Well) another on-site well location was added to the program. In July 2011, WG-15 (Southwest Well) was added to the ODCM as a quarterly sample location. Table 5.1 and Figure 6.9 show that gross-beta measurements were positive in 13 out of 13 indicator samples and in 3 out of 4 control samples. The beta activity is due to naturally-occurring radionuclides in the water. The levels at all sampling locations, including the higher levels at station WG-13, were consistent with those detected in previous years. Naturally occurring Ra-226 was also detected in three samples and is naturally-occurring. No other gamma-emitting radionuclides or tritium were detected in any of the samples.

6.5.2.3 Sediment (SE)

Semi-annual river sediment grab samples were collected from two indicator locations during 2011. The North Storm Drain Outfall location (SE- 12) is an area where up to 40 different locations can be sampled within a 20 ft by 140 ft area. In 2011, 18 locations were sampled at SE- 12 during each of the semi-annual collections. Two samples were collected at SE-i 1 during the year. Be-7 was detected in three of the 36 samples analyzed. As would be expected, naturally-occurring Potassium-40 (K-40) was detected in all of the samples. Cobalt-60 was detected in one of the 36 samples. Radium-226 (Ra-226) was detected in 29 of 36 samples. Actinium-228 was detected in 31 of 36 samples. Thorium-228 (Th-228) was detected in all 36 samples analyzed. Thorium-232 (Th-232) was detected in all 36 samples analyzed. Urainium-238 (U-238) was not detected in any of the 36 samples. Cesium- 137 (Cs- 137) was detected in 24 out of 34 of the indicator samples and none of the two control samples. The levels of Cs-137 measured were consistent with what has been measured in the previous several years and with those detected at other 48

New England locations as a result of mid 1 9 th century weapons testing fallout around the globe. Section 2.2 provides more information on the results of weapons testing on environmental contamination.

6.5.2.4 Test Wells (WT)

During 1996, sampling was initiated at test wells around the outer edges of an area in the south portion of the VYNPS site where septic sludge is spread. This sampling continued through 2011. The test well locations are shown on Figure 4.1 and the results are summarized in Table 5.1 under the media category, Test Well (WT). In 2011, five samples were taken at each of the four locations and all were analyzed for gamma isotopic, gross beta and H-3 activity.

Prior to the gross beta analysis, each sample was filtered through a 0.45 micron Gelman Tuffryn membrane filter. Gross beta activity was detected in all 20 samples collected with levels ranging from 5.12 to 22.5 pCi/kg. K-40 was also detected in four of the 20 samples. No other radionuclides were detected.

6.5.2.5 Storm Drain System The presence of plant-generated radionuclides in the onsite storm drain system has been identified in previous years at Vermont Yankee (VY). As a consequence, a 50.59 evaluation of radioactive materials discharged via the storm drain system was performed in 1998. This assessment was in response to Information and Enforcement Bulletin No. 80-10 and NRC Information Notice No. 91-40. The evaluation demonstrated that the total curies released via the VYNPS storm drain system are not sufficient to result in a significant dose (i.e. dose does not exceed 10% of the technical specification objective of 0.3 millirem per year to the total body, and 1.0 millirem per year to the target organ for the maximally exposed receptor). Water and sediment in the onsite storm drain system was routinely sampled throughout 2011 at various points. The results of this sampling are summarized below.

Sediment samples were taken from the storm drain system at onsite manhole locations in 2011 for a total of 10 samples. All samples were analyzed for gamma emitting isotopes. Table 6-1 summarizes the analytical results of the sediment samples. The naturally-occurring isotope Ra-226 was found in 8 of 10 samples as expected. The highest detected concentration for all plant-related radionuclides that were detected in sediment samples was found in sample SE-92 which is also designated by the plant as Manhole 12A.

No Cobalt-60 or Cesium-137 was detected in 2011.

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Table 6.1 Summary of Storm Drain System Sediment Sample Analyses*

Isotope No. Detected** Mean Range Station With Highest (pCi/kg) (pCi/kg) Detected Concentration Ra-226 8/10 1.33 E 3 (1.01- 1.79)E3 MH-12A (SE-92)

Cs-137 0/10 NA NA Mn-54 0/10 NA NA Co-60 2/10 4.9 E 1 (2.75 -6.67) E I MH-12A (SE-92)

Zn-65 0/10 NA NA

Radionuclides that were not detected in any sample are not listed

- The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations).

The mean and the range are determined only from the samples where activity was >3 standard deviations.

Water samples were taken from the storm drain system at various access points in 2011 including Manholes MH-8, MH-1 IH, MH-12A, MH-13, and MH-14. Table 6-2 summarizes the analytical results of water samples from the storm drain system (MH-12A and MH-14) in 2011. Naturally-occurring Ra-226 was detected in 15 of the 20 samples. Low levels of gross beta activity were detected in all of the 20 samples analyzed, at concentrations that are typical of any environmental water sample. Tritium (H-3) was not detected in the 20 samples analyzed.

In 1998, an additional dose assessment was performed that incorporated all of the 1998 storm drain system analytical results (including both sediment and water). The dose assessment was performed using the maximum measured concentration of radionuclides in 1998, and a conservative estimate of the volume of sediment and water discharged via the storm drain system. The results of this dose assessment are estimates of the total body and maximum organ dose equaling 3.2% and 1.6% of the corresponding Technical Specification dose limits respectively. Therefore, there was no significant dose impact from plant-related radionuclides in the storm drain system in 1998. The sampling conducted in 2011 indicates that the presence of radionuclides in the storm drain system has not changed significantly. Therefore, the storm drain system remains an insignificant impact to dose. The VYNPS staff will continue to monitor the presence of plant related radionuclides in the storm drain system.

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Table 6.2 Summary of Storm Drain System Water Sample Analyses*

Isotope No. Detected ** Mean Range Station With Highest (pCi/L) (pCi/L) Detected Concentration Gross Beta 20/20 3.8 E 0 (1.1 - 12.9) E 0 MH-12A (WW-12)

H-3 0/20 NA NA Ra-226 15/20 1.1E 2 (0.57- 1.71)E2 MH-12A (WW-12) 1-131 0/20 NA NA _

Cs- 134 0/20 NA NA Cs- 137 0/0 NA NA ZrNb-95 0/20 NA NA Co-58 0/20 NA NA Mn-54 0/20 NA NA Zn-65 0/20 NA NA Fe-59 0/20 NA NA Co-60 0/20 NA NA Ba/La-140 0/20 NA NA

Radionuclides that were not detected in any sample are not listed

- The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations).

6.5.2.6 Air Compressor Condensate and Manhole Sampling Results The presence of tritium in station air compressor condensate and manholes (Storm Drain System) has been identified since 1995 (ER_95-0704). An evaluation has been performed (S.R.1592) which states

"...leakage of tritium found in the storm drains (manholes) to ground water beneath the site will be transported by natural ground water gradient to the Connecticut River. However, at the current measured concentrations and postulated leak rate from the storm drains, the offsite dose impact is not significant

(<2.4E-5 mrem/year)." Data provided in Table 6.3 will be filed under the requirements of IOCFR50.75(g) and is presented here in response to ER_95-0704_04 commitments. Because of revisions in the security arrangements at the plant site, there was no water available for collection in Manholes 13 and 8 during 2011. Only one sample was available from Manhole 1IH during 2011. Air compressor condensate is now routed to the plant radwaste system to be polished and reused in plant systems.

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Table 6.3 Summary of Air Compressor Condensate and Manhole Water Tritium Concentrations*

Sample No. Mean Range Location Detected** ( microcuries/ml ) (microcuries/mi)

Air Compressor Condensate 6/6 4.02E-5 (1.88- 9.50) E-5 Manhole I IH 0/1 NA NA Manhole 13 0/0 No Sample Available No Sample Available Manhole 8 0/0 No Sample Available No Sample Available

Reported per ER_950704_04.

- The fraction of sample analyses yielding detectable measurements 6.5.2.7 Groundwater Monitoring Wells Samples Results (WS)

Leakage from primary system piping between the Augmented Off Gas (AOG) Building and the Turbine Building was identified early in 2010. A large pool of subsurface water became contaminated with Tritium as a result of this leak. A large number of new groundwater sample wells were installed and a significant effort was mounted to find the leak and fix it. Presently, mitigation efforts have resulted in the extraction of more than 300000 gallons of trititated water from this subsurface pool. Dose calculations have been performed assuming that this under ground plume of contaminated water is moving towards and into the Connecticut River. The dose impacts and other details of this event are provided in the year 2011 Annual Radioactive Effluent Release Report.

6.5.3 Ingestion Pathways 6.5.3.1 Milk (TM)

Milk samples from cows at several local farms were collected monthly during 2011. Twice-per-month collections were made during the "pasture season" since the milking cows or goats were identified as being fed pasture grass during that time. Each sample was analyzed for 1-131 and other gamma-emitting radionuclides. Quarterly composites (by location) were analyzed for Sr-89 and Sr-90.

As expected, naturally-occurring K-40 was detected in all samples. Also expected was Sr-90. Sr-90 was detected in two out of 12 indicator samples and four out of 10 control samples. Although Sr-90 is a by-product of nuclear power plant operations, the levels detected in milk are consistent with that expected 52

from worldwide fallout from nuclear weapons tests, and to a much lesser degree from fallout from the Chernobyl incident. The Sr-90 levels shown in Table 5.1 and Figure 6.11 are consistent with those detected at other New England farms participating in other plant environmental monitoring programs.

This radionuclide and Cs-137 are present throughout the natural environment as a result of atmospheric nuclear weapons testing that started primarily in the late 1950's and continued through 1980. They are found in soil and vegetation, as well as anything that feeds upon vegetation, directly or indirectly. The detection of Cs-137 in environmental milk samples is expected and has been detected in previous years.

Cs- 137 was not detected in any of the 95 samples in 2011. See Figure 6.10. It should be noted here that most of the Cs- 137 concentrations and many of the Sr-90 concentrations shown on Figures 6.10 and 6.11, respectively, are considered "not detectable." All values have been plotted, regardless of whether they were considered statistically significant or not. As shown in these figures, the levels are also consistent with those detected in previous years near the VYNPS plant. There is also little actual difference in concentrations between farms. As in previous years, no 1-131 attributable to the operation of Entergy Vermont Yankee was detected in any milk sample. The 1-131 detected in five out of 95 samples is directly attributed to the trans-Pacific transport of airborne releases from Dai-Ichi Fukushima following the March 11, 2011 Tohoku earthquake.

6.5.3.2 Silage (TC)

A silage sample was collected from each of the required milk sampling stations during October. Each of these was analyzed for gamma-emitting radionuclides and 1-131. As expected with all biological media, naturally-occurring Be-7 was detected in three of five samples and K-40 was detected in all samples.

Naturally-occurring Ra-226 was detected in two of the five samples. No Cs- 137 or 1-131 was detected in any sample.

6.5.3.3 Mixed Grass (TG)

Mixed grass samples were collected at each of the air sampling stations during three of the four quarters of 2011. As expected with all biological media, naturally-occurring Be-7 was detected in 17 of the 21 samples. Naturally-occurring K-40 was detected in all samples. Naturally-occurring Ra-226 was detected in nine of the 21 samples. Cs-137 was not detected in any of the samples.

6.5.3.4 Fish (FH)

Semiannual samples of fish were collected from two locations in both spring and fall of 2011 for the VY 53

REMP. Fish were also collected in response to the detection of tritium in subsurface water under the plant site in January, 2010. Several species are collected such as Walleye, Small Mouth Bass, Large Mouth Bass, Yellow Perch, White Perch, and Rock Bass. The edible portions of each of these were analyzed for gamma-emitting radionuclides. As expected in biological matter, naturally-occurring K-40 was detected in all 32 samples. In addition to the analysis of edible portions, the inedible portions were also analyzed in response to the tritium leak. These fish were also analyzed for Gross Beta, H-3, Am-241, Cm-242, Cm-243/244, Fe-55, Ni-63, Pu-2328, Pu-239/240, Pu-241, Pu-242, Sr-89 and Sr-90.

Strontium 90 was detected in some of the inedible portions (bones, guts and skin are included in the

'inedible' portion). This is the second year in the VY REMP program that fish has been analyzed for Hard-to-Detects such as Strontium-90. The results were compared to studies done in the Hudson River by New York State officials and it was concluded that the Strontium-90 detected is a result of weapons-testing era fallout to the environment and not produced by nuclear power plants.

As shown in Table 5.1, Cs-137 was not detected in this year's samples. It should be noted that the majority of the Cs-137 concentrations plotted in Figure 6.12 are considered "not detectable." All values were plotted regardless of whether they were considered statistically significant or not. The Cs- 137 levels plotted for 2011 and previous years are typical of concentrations attributable to global nuclear weapons testing fallout.

6.5.4 Direct Radiation Pathway Direct radiation was continuously measured at 53 locations surrounding the Vermont Yankee plant with the use of thermoluminescent dosimeters (TLDs).

In 1999, DR-53 was added on the site boundary. The TLDs are collected every calendar quarter for readout at the environmental laboratory. The complete summary of data may be found in Table 5.3.

From Tables 5.2 and 5.3 and Figure 6.13, it can be seen that the Inner and Outer Ring TLD mean exposure rates were not significantly different in 2011. This indicates no significant overall increase in direct radiation exposure rates in the plant vicinity. It can also be seen from these tables that the Control TLD mean exposure rate was not significantly different than that at the Inner and Outer Rings. Figure 6.13 also shows an annual cycle at both indicator and control locations. The lowest point of the cycle occurs usually during the winter months. This is due primarily to the attenuating effect of the snow cover on radon emissions and on direct irradiation by naturally-occurring radionuclides in the soil. Differing amounts of these naturally-occurring radionuclides in the underlying soil, rock or nearby building materials result in different radiation levels between one field site and another.

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Upon examining Figure 6.17, as well as Table 5.2, it is evident that in recent years, station DR-45 had a higher average exposure rate than any other station. This location is on-site, and the higher exposure rates are due to plant operations and activities in the immediate vicinity of this TLD. There is no significant dose potential to the surrounding population or any real individual from these sources since they are located on the back side of the plant site, between the facility and the river. The same can be said for station DR-46, which has shown higher exposure rates in previous years.

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Environmental Program Trend Graphs 2011 Radiological Environmental Operating Report Vermont Yankee Graphs:

6.1 - Gross Beta Measurements on Air Particulate Filters (Average Concentrations) 6.2 - Gross Beta Measurements on Air Particulate Filters (11) 6.3 - Gross Beta Measurements on Air Particulate Filters (12) 6.4 - Gross Beta Measurements on Air Particulate Filters (13) 6.5 - Gross Beta Measurements on Air Particulate Filters (14) 6.6 - Gross Beta Measurements on Air Particulate Filters (15) 6.7 - Gross Beta Measurements on Air Particulate Filters (40) 6.8 - Gross Beta Measurement on River Water (Average Concentrations) 6.9 - Gross Beta Measurement on Ground Water (Average Concentrations) 6.10 - Cesium-137 in Milk (Annual Average Concentrations) 6.11 - Strontium 90 in Milk (Annual Average Concentrations) 6.12 - Cesium-137 in Fish (Annual Average Concentrations) 6.13 - Exposure Rate at Inner Ring, Outer Ring, and Control TLDS 6.14 - Exposure Rate at Indicator TLDS, DRO 1-03 6.15 - Exposure Rate at Indicator TLDS, DR 06,50 6.16 - Exposure Rate at Site Boundary TLDS, DR 07 - 08, 41 - 42 6.17 - Exposure Rate at Site Boundary TLDS, DR 43-46 6.18 - Exposure Rate at Site Boundary TLDS, DR 47-49, 51-53 6.19 - Exposure Rate at Inner Ring TLDS, DR 09-15(odd) 6.20 - Exposure Rate at Inner Ring TLDS, DR-17-23 (odd) 6.21 - Exposure Rate at Inner Ring TLDS,DR 25-31 (odd) 6.22 - Exposure Rate at Inner Ring TLDS, DR 33-39 (odd) 6.23 - Exposure Rate at Outer Ring TLDS, DR 10 - 16 (even) 6.24 - Exposure Rate at Outer Ring TLDS, DR 18-24 (even) 6.25 - Exposure Rate at Outer Ring TLDS, DR 26-32 (even) 6.26 - Exposure Rate at Outer Ring TLDS, DR 34-40 (even) 6.27 - Exposure Rate at Control TLDS, DR 04-05 56

Figure 6.1 - Gross Beta Measurements on Air Particulate Filters - Quarterly Average Concentrations 0.04 0.035 0.03 0.025 E

r: 0.02 00.015 0.01 0.005 0 -

1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Year 57

Figure 6.2 - Gross Beta Measurements on Air Particulate Filters 0.045 0.04 0.035 0.03 6-0.025 E

0.02 a.

0.015 0.01 0.005 0

2011 Week Number 58

Figure 6.3 - Gross Beta Measurements on Air Particulate Filters 0.05 0.045 0.04 0.035 0.03 E

.0 0.025

0. 0.02 0.015 0.01 0.005 A

0 2011 Week Number AP-1 2 North Hinsdale -4*-AP-21 Spofford Lake N 59

Figure 6.4 - Gross Beta Measurements on Air Particulate Filters 0.045 0.04 0.035 0.03 0

.bI 0 0.025 E

0.02 C.,

0.

0.015 0.01 0.005 (A

0 2011 Week Number AP-13 Hinsdale Substation -41ý-AP-21 Spofford Lake NH 60

Figure 6.5 - Gross Beta Measurements on Air Particulate Filters 0.06 0.05 0.04 E

0.03 0.

0.02 0.01 0

2011 Week Number

--*--AP-14 Northfield MA AP-21 Spofford Lake NH 61

Figure 6.6 - Gross Beta Measurements on Air Particulate Filters 0.045 0.04 0.035 0.031 0.025 0

2 e0.02 CL0.015 0.01 Y

0.005 2011 Week Number 7

AP-1 5 Tyler Hill Road AP-21 Spofford Lake NH !

62

Figure 6.7 - Gross Beta Measurements of Air Particulate Filters 0.05 0.045 0.04 0.035 0.03 E

0.025 0.02 0.015 0.01 0.005 A3 0

2011 Week Number I

--*-AP-40 Govemor Hunt House --o-AP-21 SKfford Lake NH 63

Figure 6.8 - Gross Beta Measurements on River Water Semi-Annual Average Concentration 4.00 3.50 3.00 2.50 2.00 a.

1.50 1.00 0.50 0.00 !I 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Year WR-I 1 River Statim (3-3) WR-21 Rt9 Bfte 64

Figure 6.9 - Gross Beta Measurements on Ground Water Semi-Annual Average Concentrations 10.0 9.0 8.0 7.0 6.0

~5.0 4.0 3.0 2.0 1.0 0.01 ! I 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 65

Figure 6.10 - Cesium 137 in Milk - Annual Average Concentration 10.0 9.0 8.0 7.0 -

6.0 -

5.-

4.0 3.0 2.0 1.0 0.0 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Year 66

Figure 6.11 - Strontium 90 in Milk - Annual Averge Concentrations 4.0 3.5 3.0 2.5 2.0 1.5 1.0 -

0.5 0.0 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Year 67

Figure 6.12 - Cesium 137 in Fish - Annual Average Concentrations 80.0 70.0 60.0 50.0 40.0 a.

30.0 20.0 10.0 0.0 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 Year 4 FH-1 I Vernon Pond --M- FH-21 Rt 9 Bridge (Conb 68

Figure 6.13 - Average Exposure Rate at Inner Ring, Outer Ring and Control TLDs 9.0 8.5 8.0 7.5 7.0 0

.6.5 S6.0 5.5 5.0 4.5 4.0 -

1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date

--*-COMMI M Inner Ring OLder Ring 69

Figure 6.14 - Exposure Rate at Indicator TLDs, DROI-03 10.0 9.5 9.0 8.5 8.0 0 7.5

& 7.0 2 6.5 6.0 5.5 5.0 4.5 4.0 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date 70

Figure 6.15 - Exposure Rate at Indicator TLDs, DR06 & DR-50 10.0 9.5 9.0 8.5 8.0 7.5 -

- 7.0 U* 6.5 6.0 5.5 5.0-4.5 4.0 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date DR-06 ~ Reriva Datecoo 0 R-0Gv Hn os 71

Figure 6.16 - Exposure Rate at Site Boundary TLDs DR07, 08,41 & 42 117 10 9-8-

7-1._

6-5-

4-1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date

--*.--DR-07 Site Boundary DR-08 She Boundary DR-41 She Boundary X DR-42 Site Boundety 72

Figure 6.17 - Exposure Rate at Site Boundary TLDs - DR43 thru 46 19 18 17 16 15 14-Ik= 13 0

12 OF 11 9

8 7

6 5

4 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 PgOrinnli rln**

73

Figure 6.18 - Exposure Rate at Site Boundary TLDs DR47-49 & 51-53 12 11 10 i8 S7 6-4 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 20'09 2010 2011 2012 Retrieval Date 74

Figure 6.19 - Exposure Rate at Inner Ring TLDs DR09, 11, 13 & 15 9

8 57 0X I

5 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date 75

Figure 6.20 - Exposure Rate at Inner Ring TLDs DRI7, 19, 21 & 23 11 10 9

0. 8 1.

6 5

1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date DR-17 InerRingDR-9 nnerRin DR21 InerRin DR-3 InerRin 76

Figure 6.21 - Exposure Rate at Inner Ring TLDs DR25, 27, 29 & 31 8.5 7.5

-* 7

-6.5 5.5 5

4.5 4 -

1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date DR-25 inner Ring --M- DR-27 Inner Ring DR-29 Inner Ring DR-31 Inner Ring 77

Figure 6.22 - Exposure Rate at Inner Ring TLDs DR33, 35, 37 & 39 10 9

8 S7 6

5 4

1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date DR-33 Inner Ring --W- DR-35 Inner Ring DR-37 Inner Ring x DR-39 Inner Ring 78

Figure 6.23 - Exposure Rate at Outer Ring TLDs DRIO, 12,14 & 16 10 9

8 0

7 IL 6

5 41 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date DR-1 0 Outer RWg DR-1 2 Outer RIM DR-14 Outer Ring DR-1 6 Outer Ring 79

Figure 6.24 - Exposure Rate at Outer Ring TLDs DRI8, 20, 22 & 24 10.5 10 9.5 9

8.5 0 8

-- 7.5 2 7 6.5 6

5.5 -

5 4.5 4

1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date 80

Figure 6.25 - Exposure Rate at Outer Ring TLDs DR26, 28, 30 & 32 9

8.5 7.5

7 0

6.5 5.5 5

4.5 4

1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date DR26 utr Rng DR-28 Outr Rin R3 ueigD-2OtrRn 81

Figure 6.26 - Exposure Rate at Outer Ring TLDs DR 34, 36, 38 & 40 10 9.5 9

8.5 8

0 7.5 6.5 6

5.5 5

4.5 4

1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date R-34 Outer Ring -W RWOtrRn R3 ue ig mD-0OtrRn 82

Figure 6.27 - Exposure Rate at Control TLDs DR04 & 05 9-8.5 8-7.5

= 7 0

6.5 6

5.5 5-4.5 4

1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 Retrieval Date DR-04 Northfield, MA - DR-05 Spofford Lake, NH 83

7 QUALITY ASSURANCE PROGRAMS 7.1 Environmental Dosimetry Company The TLD systems at the Environmental Dosimetry Company (EDC) are calibrated and operated to ensure consistent and accurate evaluation of TLDs. The quality of the dosimetric results reported to EDC clients is ensured by in-house performance testing and independent performance testing by EDC clients, and both internal and client directed program assessments.

The purpose of the dosimetry quality assurance program at EDC is to provide performance documentation of the routine processing of EDC dosimeters. Performance testing provides a statistical measure of the bias and precision of dosimetry processing against a reliable standard, which in turn points out any trends or performance changes. Two programs are described below.

7.1.1 QC Program Dosimetry quality control tests are performed on EDC Panasonic 814 Environmental dosimeters. These tests include: (1) the in-house testing program coordinated by the EDC QA Officer and (2) independent test perform by EDC clients. In-house test are performed using six pairs of 814 dosimeters, a pair is reported as an individual result and six pairs are reported as the mean result. Results of these tests are described in this report.

Excluded from this report are instrumentation checks. Although instrumentation checks represent an important aspect of the quality assurance program, they are not included as process checks in this report. Instrumentation checks represent between 5-10% of the TLDs processed.

7.1.2 QA Program An internal assessment of dosimetry activities is conducted annually by the Quality Assurance Officer. The purpose of the assessment is to review procedures, results, materials or components to identify opportunities to improve or enhance processes and/or services.

7.1.3 Environmental TLD Quality Assurance Program Results of performance tests conducted are summarized and discussed in the following sections. Summaries of the performance tests for the reporting period are given in Tables 1 through 3.

Table 1 provides a summary of individual dosimeter results evaluated against the EDC internal acceptance criteria for high-energy photons only. During this period, 100% (72/72) of the individual dosimeters, evaluated against these criteria met the tolerance limits for accuracy (+/-15.0%) and 100% (72/72) met the criterion for precision (+/-12.8%).

Table 2 provides the Bias + Standard deviation results for each group (N=6) of dosimeters evaluated against the internal tolerance criteria. Overall, 100%

(12/12) of the dosimeter sets evaluated against the internal tolerance performance criteria met these criteria.

84

Table 3 presents the independent blind spike results for dosimeters processed during this annual period. All results passed the performance acceptance criterion.

Table 1 Percentage of Individual Analyses that passed EDC Internal Criteria January - December 201 1(l)(2)

Dosimeter Type Number % Passed Bias Criteria % Passed Precision Criteria Tested Panasonic Environmental 72 100 100 (1) This table summarizes results of tests conducted by EDC.

(2) Environmental Dosimeter results are free in air.

Table 2 Mean Dosimeter Analyses (N=6)

January - December 201 l0)(2)

Process Date Mean Bias % Standard Deviation % Tolerance Limit +/- 15%

04/22/2011 3.0 1.9 Pass 05/2/2011 8.0 1.4 Pass 05/18/2011 0.2 1.4 Pass 07/21/2011 6.2 0.6 Pass 08/5/2011 5.4 0.6 Pass 08/16/2011 7.0 1.1 Pass 10/14/2011 -1.6 1.7 Pass 11/07/2011 0.4 0.8 Pass 01/19/2012 -1.0 1.3 Pass 01/22/2012 -3.1 1.8 Pass 01/29/2012 4.9 1.2 Pass 02/09/2012 -1.6 1.5 Pass (1) This table summarizes results of tests conducted by EDC for TLDs issued in 2011 (2) Environmental Dosimeter results are free in air.

Table 3 Summary of Independent Dosimeter Testing January-December 201 {1()(2)

Issuance Period Client Mean Bias % Standard Deviation % Pass/Fail Ist Qtr. 2011 Millstone -1.3 1.0 Pass 2'n Qtr. 2011 Millstone -5.0 1.3 Pass 2 nd Qtr. 2011 Seabrook 2.0 1.8 Pass 3 rd Qtr. 2011 Millstone -2.1 2.9 Pass 4t' Qtr. 2011 Millstone 7.8 2.8 Pass 4u' Qtr. 2011 Seabrook 1.7 2.0 Pass (1) Performance criteria are +/- 30%.

(2) Blind spike irradiations using Cs-137 85

7.2 Teledyne Brown Engineering Laboratory -Environmental Services (TBE-ES) 7.2.1 Operational Quality Control Scope 7.2.1.1 Inter-laboratory The TBE-ES Laboratory QC Program is designed to monitor the quality of analytical processing associated with environmental, effluent (10CFR Part 50), and waste characterization (10CFR Part

61) samples.

Quality Control of environmental radioanalyses involves the internal process control program and independent third party programs administered by Analytics, Inc and Environmental Resource Associates (ERA).

TBE-ES participates in the Quality Assessment Program (QAP) administered by the Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP). The MAPEP is a set of performance evaluation samples (e.g. water, soil, air filters, etc.) designed to evaluate the ability and quality of analytical facilities performing sample measurements which contain hazardous and radioactive (mixed) analytes.

Quality Control for radioanalyses during this reporting period was divided among internal process check samples, third party process checks prepared by Analytics, Inc. (which was submitted by users or secured directly by TBE-ES for QC purposes), ERA, and DOE's MAPEP.

7.2.1.2 Intra-laboratory The internal Quality Control program is designed to include QC functions such as instrumentation checks (to ensure proper instrument response), blank samples (to which no analyte radioactivity has been added), instrumentation backgrounds, duplicates, as well as overall staff qualification analyses and process controls. Both process control and qualification analyses samples seek to mimic the media type of those samples submitted for analyses by the various laboratory clients. These process controls (or process checks) are either actual samples submitted in duplicate in order to evaluate the accuracy of laboratory measurements, or blank samples which have been "spiked" with a known quantity of a radioisotope that is of interest to laboratory clients. These QC samples, which represent either "single" or "double-blind" unknowns, are intended to evaluate the entire radiochemical and radiometric process.

To provide direction and consistency in administering the quality assurance program, TBE-ES has developed and follows an annual quality control and audit assessment schedule. The plan describes the scheduled frequency and scope of Quality Assurance and Control considered necessary for an adequate QA/QC program conducted throughout the year. The magnitude of the process control program combines both internal and external sources targeted at 5% of the routine sample analysis load.

7.2.1.3 QA Program (Internal and External Audits)

During each reporting period at least one internal assessment is conducted in accordance with the pre-established TBE-ES Quality Control and Audit Assessment Schedule. In addition, the laboratory may be audited by prospective customers during a pre-contract audit, and/or by existing clients who wish to conduct periodic audits in accordance with their contractual 86

arrangements. The Nuclear Utilities Procurement Issues Committee (NUPIC) conducts audits of TBE-ES as a function of a Utilities Radiological Environment Measurement Program (REMP).

TBE-ES Laboratory-Knoxville has successfully completed the New York State Department of Health's Environmental Laboratory Approval Program (NELAP), Nuclear Fuel Services, Manufacturing Sciences Corporation and State of Tennessee audits. These audits were each a comprehensive review of TBE-ES's Quality and Technical programs used to assess the laboratory's ability to produce accurate and defensible data. No significant deficiencies, which would adversely impact data quality, were identified during any of these audits. Administrative findings identified during these inspections are usually addressed promptly, according to client specifications.

7.2.2 Analytical Services Quality Control Synopsis 7.2.2.1 Results Summary 7.2.2.1.1 Environmental Services Quality Control During this annual reporting period, twenty-seven nuclides associated with six media types were analyzed by means of the laboratory's internal process control, Analytics, ERA and DOE quality control programs. Media types representative of client company analyses performed during this reporting period were selected. The results for these programs are presented in Table 7.2. Below is a synopsis of the media types evaluated:

Air Filter

" Charcoal (Air Iodine)

Milk

Soil

Vegetation

Water 7.2.2.1.2 Analytics Environmental Cross-Check Program Thirteen nuclides were evaluated during this reporting period. All but one of the environmental samples performed were within the acceptable criteria. The Analytics March Cr-51 in milk was higher than the known value, resulting in a found to known ratio of 1.34. There was a slightly high bias in all the gamma activities for that milk sample. The June Analytics milk sample did not show a high bias. No further action was required.

7.2.2.1.3 Summary of Participation in the Department of Energy (DOE) Monitoring Program TBE-ES participated in the semi annual Mixed Analyte Performance Evaluation Program (MAPEP) for liquid, air particulate, soil, and vegetation analyses (MAPEP-Series 22 and 23). During this reporting period, 18 nuclides were evaluated. All but four of the 18 environmental analytical results were within the acceptable criteria. In one air particulate sample, the gross alpha result was lower than the known value. The air particulate filter had been counted on the wrong side.

87

Sr-90 in soil, air particulate and vegetation were not reported and were evaluated as failed by MAPEP.

7.2.2.1.5 Summary of participation in the ERA Program During this reporting period, 13 nuclides were analyzed under ERA criteria. All but two of the environmental analytical results were acceptable. The gross alpha in water result exceeded the upper control limit. The solids on the planchet exceeded 100 mg, which was beyond the range of the efficiency curve.

The Sr-89 in water sample was evaluated as failed with a ratio of 1.16. TBE considers this an acceptable result. No action was taken.

7.2.2.2 Intra-Laboratory Process Control Program The TBE-ES Laboratory's internal process control program evaluated 5731 individual samples.

7.2.2.2.1 Spikes All but two of the 1562 environmental spikes were analyzed with statistically appropriate activity reported for each spike. The affected work orders were reanalyzed or a case narrative documented the reason the sample could not be reanalyzed.

7.2.2.2.2 Analytical Blanks During this reporting period, all of the 1562 environmental analytical blanks analyzed reported less than MDC.

7.2.2.2.3 Duplicates All but one of 2607 duplicate sets analyzed were within acceptable limits. The duplicate set was rerun with acceptable results.

7.2.2.2.4 Non-Conformance Reports There were 16 non-conformance reports issued for this reporting period. No ENNVY data was impacted by the non-conformance in each of these cases.

88

7.3 J.A. FITZPATRICK ENVIRONMENTAL LABORATORY - QUALITY ASSURANCE /

QUALITY CONTROL PROGRAM 7.3.1. PROGRAM DESCRIPTION The Offsite Dose Calculation Manual (ODCM), Part 1, Section 5.3 requires that the licensee participate in an Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected and for which comparison samples are commercially available. Participation in an Interlaboratory Comparison Program ensures that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring. To fulfill the requirement for an Interlaboratory Comparison Program, the JAF Environmental Laboratory has engaged the services of Eckert & Ziegler Analytics, Incorporated in Atlanta, Georgia.

Analytics supplies sample media as blind sample spikes, which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are prepared and analyzed by the JAF Environmental Laboratory using standard laboratory procedures. Analytics issues a statistical summary report of the results. The JAF Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance.

The JAF Environmental Laboratory also analyzes laboratory blanks. The analysis of laboratory blanks provides a means to detect and measure radioactive contamination of analytical samples.

The analysis of analytical blanks also provides information on the adequacy of background subtraction. Laboratory blank results are analyzed using control charts.

89

7.3.2 PROGRAM SCHEDULE SAMPLE PROVIDER VIEER SAMPLE LABORATORY ECPERT MEDI ANAYSISECKERT & ZIEGLER MEDIA ANALYSIS ANALYTICS Water Gross Beta 3 Water Tritium 5 Water 1-131 4 Water Mixed Gamma 4 Air Gross Beta 3 Air 1-131 4 Air Mixed Gamma 2 Milk 1-131 3 Milk Mixed Gamma 3 Soil Mixed Gamma 1 Vegetation Mixed Gamma 2 TOTAL SAMPLE INVENTORY 34 7.3.3 ACCEPTANCE CRITERIA Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The sample evaluation method is discussed below.

7.3.3.1 SAMPLE RESULTS EVALUATION Samples provided by Analytics are evaluated using what is specified as the NRC method.

This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the Vendor Laboratory Known value (reference result).

90

An Environmental Laboratory analytical result is evaluated using the following calculation:

The value for the error resolution is calculated.

The error resolution = Reference Result Reference Results Error (1 sigma)

Using the appropriate row under the Error Resolution column in Table 8.3.1 below, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

Ratio OC Result of Agreement Reference Result If the value falls within the agreement interval, the result is acceptable.

TABLE 7.3.1 ERROR RESOLUTION RATIO OF AGREEMENT

<4 No Comparison 4 to 7 0.5 to 2.0 8 to 15 0.6 to 1.66 16 to 50 0.75 to 1.33 51 to 200 0.8 to 1.25

>200 0.85 to 1.18 This acceptance test is generally referred to as the "NRC" method. The acceptance criteria is contained in Procedure EN-CY-102. The NRC method generally results in an acceptance range of approximately + 25% of the Known value when applied to sample results from the Eckert & Ziegler Analytics Interlaboratory Comparison Program. This method is used as the procedurally required assessment method and requires the generation of a deviation from QA/QC program report when results are unacceptable.

91

7.3.4 PROGRAM RESULTS

SUMMARY

The Interlaboratory Comparison Program numerical results are provided on Table 7.2.2.

7.3.4.1 ECKERT & ZIEGLER ANALYTICS QA SAMPLES RESULTS Thirty-four QA blind spike samples were analyzed as part of Analytics 2011 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

Air Charcoal Cartridge: 1-131

Air Particulate Filter: Mixed Gamma Emitters, Gross Beta

" Water: 1-131, Mixed Gamma Emitters, Tritium, Gross Beta

Soil: Mixed Gamma Emitters

Milk: 1-131, Mixed Gamma Emitters

Vegetation: Mixed Gamma Emitters The JAF Environmental Laboratory performed 133 individual analyses on the 34 QA samples. Of the 133 analyses performed, 133 were in agreement using the NRC acceptance criteria for a 100% agreement ratio.

There were no nonconformities in the 2011 program.

92

7.3.4.2 NUMERICAL RESULTS TABLES TABLE 7.3.2 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filter SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi +/-1 sigma pCi 1 sigma RATIO (1) 06/16/2011 E7633-05 Filter 93.2 - 1.4 GROSS 91.1 1.3 85.5 1.43 1.08 A BETA 91.7 11.4 Mean = 92.0 - 0.8 06/16/2011 E7618-09 Filter 76.1 11.2 GROSS 79.3 - 1.3 BETA 76.4 - 1.2 Mean = 77.3 - 0.7 12/08/2011 E8254-05 Filter 101.2 - 2.7 99.6 - 2.7 100.8 - 2.7 99.8 + 2.7 98.9 + 2.7 GROSS 97.9 + 2.7 2.8 89.6 1.5 1.11 A 105.4 108.3 +/-- 2.8 99.7 + 2.7 91.4 +/- 2.7 91.4 +/- 2.7 98.1 +1 2.8 Mean = 99.4 - 0.8 t 1I) KatIo = KeportecuAnaIytlics. f1-IXccepLUIJIC

Sample provided by Analytics, Inc. U=Unacceptable 93

TABLE 7.3.2 (Continued)

Tritium Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi/liter+1 sigma pCiIliter 1 sigma RATIO (1) 3/17/2011 E7476-05 Water H-3 4314 + 163 4673 166 4530 + 75.7 1.00 A 4650 + 166 Mean 4546 + 95 6/16/2011 E7632-05 Water H-3 833 + 134 923 + 135 905 + 15.1 0.98 A 908 + 135 Mean = 888 4 78 9/15/2011 E8121-05 Water H-3 915 + 131 1002 132 792 + 132 1.21 A 957 + 132 Mean = 958 + 76 12/8/2011 E8181-09 Water H-3 10617 + 209 10199 208 !

10900 + 182 0.94 A 10082 + 211 Mean = 10299 + 121 12/8/2011 E8182-09 Water H-3 10339 + 206 10320 + 208 10900 + 182 0.94 A 10090 + 210 Mean = 10250 + 120 (I) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics., Inc. U=Unacceptable 94

TABLE 7.3.2 (Continued)

Gross Beta Analysis of Water REFERENCE LAB*

SAMPLE JAF ELAB RESULTS pCi/liter +l RATIO DATE ID NO. MEDIUM ANALYSIS pCi/liter +/- I sigma sigma (1) 03/17/2011 E7479-05 Water 250.6 - 2.50 252.2 + 2.50 GROSS BETA 253.6 - 2.50 247 + 4.13 1.02 A 255.2 - 2.50 Mean = 252.9 + 1.30 06/16/2011 E7638-05 Water 233.0 - 2.40 232.0 - 2.40 GROSS BETA 251 +/- 4.18 0.93 A 234.0 - 2.40 Mean = 233.0 - 1.39 09/15/2011 E8126-05 Water 253.8 - 3.30 GROSS BETA 256.9 3.30 249 +/- 4.16 1.02 A 250.4 :- 3.30 Mean= 253.7 - 1.90 (1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable 95

TABLE 7.3.2 (Continued) 1-131 Gamma Analysis of Air Charcoal SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi +/-1 sigma pCi +/-1 sigma RATIO (1) 3/17/2011 E7437-09 Air 96.3 + 3.3 97.3 + 1.5 1-131 98 98 + 3.2 3.2 96.2 + 1.61 1.01 A Mean = 97.2 + 1.57 6/16/2011 E7636-05 Air 95.3 + 2.7 1-131 100 2.7 86.7 + 1.45 1.08 A 86.1 + 2.8 Mean = 93.8 + 1.57 9/15/2011 E8125-05 Air 80.5 + 3 1-131 83.2 3.2 80.5 11.34 1.03 A 84.0 +/- 3.1 Mean = 82.6 - 1.80 9/15/2011 E8127-09 Air 72.3 - 4.3 72.1 + 4.5 1-131 80.6 4.6 80.5 - 1.34 0.93 A Mean =

80.6 75.0 +

2.6 4

2.60 (1) Ratio = Keported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable 96

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM IANALYSIS pCi/liter +1 sigma pCi/liter A-1 sigma RATIO (1) 3/17/2011 E7477-05 Water 186 4- 18.5 205 A- 10 Cr-51 196.0 A- 3.27 1.04 A 222 A- 25.7 Mean= 204 !1.1 94 - 3.32 Cs-134 92 2.32 85.6 A- 1.43 1.08 A 91 A- 5.06 Mean = 92.2 A- 2.2 143 - 3.86 Cs-137 142 2.49 135.0 - 2.25 1.04 A 134 - 5.55 Mean = 140 A- 2.4 81i 2.96 C-877 :1- 1.97 Co-58 774 4- 4 4.54 74.4 1.24 1- 1.04 A Mean = 77.2 A- 1.9 187 + 4.33 Mn-54 183 2.82 175.0 A- 2.92 1.06 A 189 A 6.38 Mean = 186 A- 2.7 121 A- 4.09 128 A- 2.83 Fe-59 115 115 4- 6.22 6.221 115.0 A- 1.91 1.05 A Mean = 121.0 A: 2.7 198 A: 7.05 Zn-65 191 4.62 172.0 A- 2.87 1.12 A 187 + 10.3 Mean = 192 A: 4.4 117 + 2.65 Co-60 115 A 1.8 113.0 + 1.88 1.03 A 116 A: 3.97 Mean = 116 A: 1.7 92.6 A- 3.25 1-131 95.9 2.12 94.0 A: 1.57 1.01 A 95.3 A- 4.53 Mean = 94.6 A: 1.99 90 A: 0.95 A:

84.1 2.19 1-131** A: 94.0 A: 1.57 0.94 A 90.9 2.14 A:

Mean 88.3 1.1 (1) Ratio ý Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

97

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE I JAF ELAB RESULTS REFERENCE LAB*

DATE IDNO. MEDIUM IANALYSISI pCi/liter+l sigma I pCi/liter++/- sigma RATIO(I) 6/16/2011 1 E7617-09 Water 92 + 7.08 92 -1 7.37 Ce- 141 88 A- 7.26 94 1.56 1- 0.95 A 87 A:t 7.68 A- 4.26 Mean 89.6 197 A- 31.8 183 A- 36.8 Cr-51 267 A: 32.1 241 A: 4.03 0.96 A 277 A: 45.4 Mean 231 A: 22.2 211 A: 11.8 222 11.6 1-Cs-134 208 A- 10.6 222 A- 3.71 0.98 A 225 A: 13.9 Mean= 217 A: 7.2 168 A- 5.77 156 A: 5.73 Cs-137 164 A: 5.25 161 A: 2.7 1.00 A 156 A- 6.66 Mean 161 A: 3.5 190 + 6.17 175 A: 5.95 Co-58 188 + 5.93 177 + 2.96 1.04 A 183 + 7.07 Mean 184 A: 3.7 165 A: 5.71 183 + 6.12 Mn-54 169 A: 5.41 161 A: 2.69 1.07 A 174 A: 7.25 Mean= 173 A: 3.7 157 A: 6.81 145 A: 6.86 Fe-59 173 A: 8.93 144 A- 2.41 1.10 A 155 A: 6.68 Mean = 158 A- 4.4 316 + 12.4 298 A 12.1 Zn-65 323 A: 12.0 305 A- 5.09 1.03 A 316 A: 15.3 Mean 313 A: 7.7 226 : 5.07 232 + 5.17 Co-60 243 A: 4.79 228 A: 3.8 1.02 A 225 A: 6.21 Mean 232 A: 3.2 110 A: 7.24 101 A: 7.44 1-131 106 + 7.37 101 A: 1.68 1.07 A 115 A: 9.22 Mean 108 A: 3.9 97.3 A: 1.33 97.8 A: 1.52 1-131** A: 101 1.68 1- 0.96 A 94.3 1.47 Mean = 96.5 A- 0.8 (I) Ratio = Reported/Analytics.

(1) Ratio = Reported/Anal, tics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis 9 8

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM IANALYSIS1 pCi/liter +/-1 sigma I pCi/liter +/-1 sigma I RATIO (I) 9/15/2011 1 E8122-05 Water 47.5 + 4.7 52.8 + 4.9 Ce-141 53.2 + 0.89 1.00 A 59.9 + 4.2 Mean= 53.4 - 2.7 165.0 + 23.9 Cr-51 175.0 23.5 180.0 + 3.01 0.97 A 184.0 + 19.8 Mean = 175.0 - 13.0 98.6 + 7.0 88.6 +/-- 7.8 Cs-134 97.5 97.5 + 6.7 6.7 102.0 11.71 0.93 A Mean = 94.9 + 4.1 91.0 + 3.7 Cs-137 94.1 4.5 90.7 + 1.51 1.00 A 88.0 + 3.5 Mean = 91.0 + 4.1 75.9 + 3.6 83.7 +- 4.4 Co-58 77.7 + 1.30 1.05 A 84.3 + 3.4 Mean = 81.3 - 2.2 117.0 + 4.3 Mn-54 118.0 4 120.0 2.01 1.01 A 128.0 + 3.9 Mean = 121.0 + 2.5 51.7 + 3.8 44.4 + 4.3 Fe-59 47 47.3 +.3 3.6 43.7 0.73 1.09 A Mean = 47.8 + 2.3 149.0 + 7.9 Zn-65 143.0 1 8.9 144.0 2.40 1.02 A 148.0 + 7.0 Mean = 147.0 + 4.6 124.0 - 3.3 122.0 4- 3.8 Co-60 123.0 123.0 4- 3.0 3.0 125.0 2.09 0.98 A Mean = 123.0 - 1.9 85.9 - 4.5 1-131 82.0 5.2 79.9 1.33 1.03 A 79.1 - 4.1 Mean = 82.3 - 2.7 79.3 - 1.0 76.1 + 1.3 1-131** 79.9 1.33 0.97 A 76.3 + 1.3 J. J Mean= 77.2 0.7 (I) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

99

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Water SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE IDNO. IMEDIUM JANALYSIS1 pCilliter1l sigma pCilliter+/-l sigma RATIO (1) 12/8/2011 1 E8183-09 I Water 501 40.8 612 38.1 Cr-51 566 36.1 566 +/- 9.45 0.99 A 589 34.9 546 37.7 Mean = 563 25.5 159 +/- 13.4 168 +/- 11.7 Cs-134 170 + 9.3 178 + 10.8 171 2.86 0.99 A 174 +/- 10.7 Mean= 169.8 + 7.6 216 + 7.5 213 +/- 6.7 Cs-137 209 212 +/-- 5.7 5 210 3.5 1.03 A 212 4- 6 228 +/- 6.5 Mean= 215.6 +/- 4.4 229 +/- 7.8 236 - 7 Co-58 224 5 221 3.69 1.04 A 221 - 6.3 237 + 6.5 Mean 229.4 - 4.5 249 +/- 8.1 264 + 7.2 Mn-54 269 + 6.2 261 +/- 6.6 241 4.02 1.08 A 262 +/- 6.9 Mean- 261 + 4.8 214 + 8.5 203 + 77.3 Fe-59 203 + 6.4 183 3.06 1.11 A 204 + 7 188 +/- 7.3 Mean= 202.4 - 4.9 320 + 14.4 311 +/- 12.7 Zn-65 330 30 + 10.3 11.3 291 4.87 1.08 A 306 +/- 11.3 307 + 12.2 Mean= 314.8 - 8.3 286 +/- 6.5 287 +/- 5.7 Co-60 282 288 + 4.8 5.2 270 4.51 1.06 A 288 +/- 5.2 287 - 5.5 Mean 286 +/- 3.8 92.5 + 5.5 100.0 - 5.3 99.6 +- 5.5 1-131 84.9 4- 55.4 88.7 +/- 1.48 1.05 A 86.6 + 5.6 Mean = 92.7 +/- 3.6 107 +/- 1.9 116 + 2.1 1-131** 108 + 2.8 88.7 1.48 1.25 A 111 -1 2.5 Mean 110.5 4- 1.3 (I) Ratio = Reported/Analytics. A=Acceptable U=Unacceptable

Sample provided by Analytics, Inc. ** Result detdr0ihed by Resin Extraction/Gamma Spectral Analysis.

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk I SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. I MEDIUM jANALYSISI pCi/liter +1 sigma pCi/liter +1 sigma RATIO (1) 3/17/2011 1 E7438-09 I MILK 264.0 + 41.3 312.0 - 23.2 Cr-51 298 1 4.98 0.97 A 295.0 - 55.9 Mean 290.3 - 16.0 135.0 + 7.5 Cs-134 133.0 4 130 - 2.18 1.04 A 136.0 - 9.8 Mean = 134.7 - 3.1 206.0 - 8.8 208.0 +- 5.0 Cs-137 219.0 219.0 4- 5.0 10.6 205 - 3.43 1.03 A Mean= 211.0 - 3.5 Co-58 126.0 + 7.2 122.0 4.0 113 - 1.89 1.07 A 116.0 - 9.3 Mean= 121.3 - 2.9 Mn-54 282.0 - 10.0 275.0 279.0 +- 5.6 2.0 266 - 4.45 1.05 A 279.0 4- 12.0 Mean= 278.7 - 5.5 Fe-59 174.0 - 10.7 184.0 6.0 175 - 2.91 1.06 A 198.0 +/- 14.0 Mean= 185.3 - 6.2 Zn-65 275.0 - 17.1 287.0 2.0 +- 9.6 261 - 4.36 1.13 A 324.0 4- 21.3 Mean = 295.3 - 9.6 Co-60 184.0 - 6.6 169.0 3.6 172 + 2.87 1.00 A 161.0 +/- 7.8 Mean= 171.3 - 3.6 1-131 108.0 + 8.4 104.0 4.5 97 - 1.62 1.07 A 97.5 - 9.5 Mean = 103.2 - 4.5 1-131** 95.4 - 6.5 103.0 - 2.6 97 - 1.62 1.00 A 91.8 - 3.6 Mean 96.7 - 2.6 (1) Ratio Reported/Analytics. A=Acceptable (I.) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc. U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

101

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. I MEDIUM IANALYSIS1 pCi/liter +I sigma pCi/liter +/-1 sigma IRATIO (1) 6/16/2011 1 E7634-05 I MILK 86.1 + 5.9 85.7 i 8.0 Ce-141 80 = 1.33 1.07 A 84.7 - 7.2 Mean= 85.5 - 4.1 209.0 + 26.4 Cr-51 221.0 + 42.4 206 - 3.44 1.08 A 238.0 - 37.0 Mean = 222.7 - 20.7 181.0 - 9.4 Cs-134 179.0 12.5 190 - 3.17 0.91 A 159.0 - 13.1 Mean = 173.0 - 6.8 135.0 - 4.7 145.0 +- 6.5 Cs-137 136.0 136.0 +/- 6.4 6.4 138 - 2.3 1.00 A Mean = 138.7 - 3.4 158.0 + 4.9 153.0 +- 6.6 Co-58 153.0 153.0 4- 7.0 7.0 152.0 + 2.53 1.02 A Mean = 154.7 - 3.6 136.0 - 4.8 Mn-54 141.0 6.8 138 - 2.3 1.00 A 138.0 + 6.5 Mean = 138.3 + 3.5 133.0 - 5.6 Fe-59 145.0 8.6 123 - 2.06 1.10 A 127.0 - 7.7 Mean = 135.0 - 4.3 266.0 - 10.0 Zn-65 262.0 14.4 261 + 4.35 1.01 A 261.0 + 13.8 Mean = 263.0 + 7.4 196.0 - 4.1 Co-60 196.0 5 195 - 3.25 1.02 A 205.0 - 5.7 Mean = 199.0 - 3.1 112.0 - 5.24 1-131 92.3 7.65 103 +/- 1.72 0.99 A 101.0 - 8.95 Mean = 101.8 + 4.3 92.3 1 1.2 89.8 + 1.7 1-131** 103 +- 1.72 0.89 A 92.5 - 1.3 Mean 91.5 - 0.8 (1) Ratio = Reported/Analytics. A=Acceptable (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc. U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

102

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk DATE I SAMPLE ID NO. ]S [MEDIUM ANALYSIS JAF ELAB +IRESULTS pCi/liter sigma REFERENCE LAB*

pCi/liter +1 sigma I RATIO (1) 9/15/2011 1 E8124-05 I MILK 79.2 4- 7.5 64.7 5.2 Ce-141 67 + 1.11 1.07 A 69.8 6.4 Mean = 71.2 3.7 187.0 - 35.5 Cr-51 243.0 25.8 226 + 3.78 0.96 A 224.0 + 29.3 Mean = 218.0 - 17.6 112.0 - 11.7 Cs-134 124.0 8.5 128 - 2.14 0.92 A 116.0 + 9.5 Mean = 117.3 - 5.8 111.0 + 6.0 Cs-137 111.0 4 114 - 1.9 0.99 A 115.0 - 4.9 Mean = 112.3 + 3.0 104.0 +/- 5.8 Co-58 107.0 4 98 - 1.63 1.04 A 93.1 - 4.5 Mean = 101.4 - 2.9 168.0 - 6.9 Mn-54 157.0 5.1 151 - 2.52 1.06 A 154.0 - 5.6 Mean = 159.7 - 3.4 61.9 + 7.0 Fe-59 65.8 5 -4.9 0.915 1.11 A 55.2 - 5.4 Mean = 61.0 + 3.4 194.0 - 13.6 Zn-65 191.0 9 180 + 3.01 1.08 A 199.0 - 10.6 Mean = 194.7 + 6.5 159.0 - 5.3 165.0 +- 4.1 Co-60 155.0 155.0 4- 44.4 157 - 2.62 1.02 A Mean = 159.7 + 2.7 86.9 + 6.6 1-131 97.9 5 89.2 + 1.49 1.06 A 97.7 - 5.8 Mean = 94.2 - 3.4 79.8 1.1 79.5 1.0 1-131** 89.2 - 1.49 0.89 A 78.5 1.6 Mean 79.3 0.7 (1) Ratio = Reported/Analytics. A=Acceptable (1) Ratio = Reported/Analytics.

Sample provided by Analytics, Inc. U=Unacceptable

- Result determined by Resin Extraction/Gamma Spectral Analysis.

103

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filter 1 [REFERENCE SAMPLE JAF ELAB RESULTS LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi +1 sigma pCi +/-1 sigma (1) 3/17/2011 E7478-05 FILTER 221.0 4-15.9 224.0 18.0 Cr-51 4-230 + 3.84 0.98 A 233.0 13.7 Mean = 226.0 9.2 117.0 +/- 4.5 Cs-134 111.0 +/- 101 +/- 1.68 1.13 A 115.0 + 3.8 Mean = 114.0 +/- 2.6 169.0 +/- 4.5 159.0 +- 4.8 Cs-137 158 +/- 2.64 1.04 A 165.0 - 3.8 Mean = 164.0 - 2.5 90.0 - 3.5 84.0 4- 4.1 Co-58 87.3 +/- 1.46 1.01 A 90.0 - 3.2 Mean = 88.1 - 2.1 211.0 + 5.2 221.0 4- 5.8 Mn-54 205 + 3.43 1.06 A 218.0 - 4.5 Mean = 217.0 - 3.0 144.0 - 5.2 138.0 4- 6.1 Fe-59 134 1 2.24 1.09 A 156.0 +/- 4.6 Mean = 146.0 +/- 3.1 226.0 +/- 8.8 212.0 4- 9.8 Zn-65 201 - 3.36 1.07 A 208.0 +/- 7.6 Mean= 215.0 + 5.0 127.0 +/- 3.4 132.0 +/- 3.8 Co-60 132 2.21 0.98 A 130.0 +/- 2.9 Mean= 130.0 +/- 1.9 (1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable 104

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filter I SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. I MEDIUM ANALYSISI pCi +/-1 sigma pCi +1 sigma I RATIO (1) 9/15/2011 E8123-05 FILTER 6.84E+0 i 4- 2.80E+00 7.11E+01 4- 2.70E+00 Ce-141 6.96E+01 +/- 1.16E+00 1.02 A 7.35E+0I 2.80E+00 Mean= 7.10E+01 I .60E+00 2.17E+02 - 1.84E+01 Cr-51 2.32E+02 79E+01 2.36E+02

.. + 3.94E+00 0.96 A 2.28E+02 - 1.80E+01 Mean= 2.26E+02 - 1.05E+01 1.15E+02 - 8.70E+00 Cs-134 1.15E+02 8.50E+00 1.34E+02 + 2.23E+00 0.85 A 1.11E+02 + 8.20E+00 Mean = 1.14E+02 +/- 4.89E+00 1.24E+02 +/- 4.30E+00 Cs-137 1.14E+02 +/- 4.20E+00 I 19E+02 +/- 1.98E+00 0.99 A 1.15E+02 +/- 4.OOE+00 Mean= 1.18E+02 +/- 2.41E+00 1.04E+02 +/- 4.10E+00 Co-58 1.08E+02 +/- 4.10E+00 1.02E+02 +/- 1.70E+O0 1.05 A 1.08E+02 +/- 4.OOE+00 Mean = 1.07E+02 +/- 2.35E+00 1.75E+02 + 5.20E+00 Mn-54 1.67E+02 +/- 5.1OE+00 1.57E+02 +/- 2.63E+00 1.11 A 1.79E+02 +/- 4.80E+00 Mean = 1.74E+02 +/- 2.91E+00 6.17E+01 +/- 4.90E+00 Fe-596.86E+01 4- 4.80E+00 Fe-59 6.35E+01+ +/-- 4.80E+00 4.30E+00 5.72E+01 +/- 9.55E-01 1.13 A Mean= 6.46E+0 I +/- 2.70E+00 1.97E+02 +/- 1.01E+01 Zn-65 2.18E+02 +/- 9.80E+00 1.88E+02 +/- 3.14E+00 1.13 A 2.25E+02 +/- 9.OOE+00 Mean = 2.13E+02 +/-- 5.57E+00 1.61E+02 4.20E+00 1.59E+02 4. 10E+00 Co-60 I1.64E+02 +/- 2.74E+00 0.98 A 1.64E+02 5:1 3.90E+00 Mean = 1.61E+02 4- 2.35E+00 (1) Ratio = Reported/Analytics. A=Acceptable 105

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Soil I SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. IMEDIUM JANALYSIS1 pCi/g +1 sigma pCi/g +/- siigma I RATIO (1) 6/16/2011 1 E7635-05 I SOIL Ce-141 0.189 + 0.022 0.189 0.020 0.154 + 0.003 1.24 A 0.193 0.021

+ 0.012 Mean= 0.190 Cr-51 0.316 + 0.010 0.365 0.009 0.397 +/- 0.007 0.86 A 0.342 + 0.009 Mean = 0.341 + 0.005 Cs-134 0.358 + 0.003 0.363 0.343 + 0.003 0.004 0.366 + 0.006 0.97 A 0.349 + 0.004 Mean = 0.357 + 0.002 Cs-137 0.308 + 0.019 0.354 0.019 0.355 + 0.006 0.95 A 0.347 + 0.021 Mean = 0.336 + 0.011 Co-58 0.292 + 0.018 0.295 0.290 +- 0.017 0.020 0.292 + 0.005 1.00 A 0.290 4- 0.020 Mean = 0.292 + 0.011 Mn-54 0.304 - 0.017 0.281 0.017 0.266 + 0.004 1.09 A 0.285 + 0.020 Mean = 0.290 - 0.010 Fe-59 0.233 - 0.020 0.253 0.243 +/-- 0.02 1 0.023 0.238 + 0.004 1.03 A 0.248 + 0.023 Mean = 0.245 - 0.012 Zn-65 0.522 - 0.033 0.557 0.553 +- 0.034 0.039 0.502 - 0.008 1.08 A 0.553 + 0.039 Mean = 0.544 4- 0.020 Co-60 0.402 0.015 0.386 0.015 0.375 + 0.006 1.03 A 0.369 + 0.017 Mean 0.386 0.009 (1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable 106

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation SAMPLE JAF ELAB RESULTS REFERENCE LAB*

DATE ID NO. MEDIUM ANALYSIS pCi/g +/-1 sigma pCi/g +! sigma I RATIO (1) 6/16/2011 1 E7637-05 VEG Ce-141 0.274 4- 0.013 0.270 A- 0.015 0.307 - 0.005 0.92 A 0.304 A- 0.014 Mean 0.283 0.008 Cr-51 0.739 + 0.073 0.767 0.088 0.792 + 0.013 1.00 A 0.863 + 0.071 Mean = 0.790 4. 0.045 Cs-134 0.664 + 0.035 0.660 0.004 0.729 + 0.012 0.89 A 0.629 - 0.003 Mean = 0.651 + 0.012 Cs-137 0.494 - 0.016 0.506 0.019 0.530 A- 0.009 0.95 A 0.511 - 0.015 Mean = 0.504 + 0.010 Co-58 0.579 4. 0.017 0.556 0.019 0.583 A: 0.010 0.99 A 0.595 A- 0.015 Mean = 0.577 + 0.010 Mn-54 0.520 + 0.017 0.512 0.019 0.530 A- 0.009 0.96 A 0.487 + 0.015 Mean = 0.506 - 0.010 Fe-59 0.487 4. 0.019 0.5 0.414 +: 0.023 0.017 0.474 A- 0.008 1.03 A 0.470 4- 0.01!7 Mean = 0.490 + 0.011 Zn-65 1.100 + 0.037 0.941 0.043 1.000 + 0.017 1.01 A 0.983 A- 0.031 Mean = 1.008 A- 0.022 Co-60 0.718 4- 0.015 0.716 A- 0.017

1- 0.748 -: 0.013 0.94 A 0.680 0.013 0.705 4- 0.009 Mean =

(1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable 107

TABLE 7.3.2 (Continued)

INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Vegetation REFERENCE SAMPLE JAF ELAB RESULTS LAB* RATIO DATE ID NO. MEDIUM ANALYSIS pCi/g+I sigma pCi/g +I sigma (1) 9/15/2011 E8128-09 VEG 0.151 4- 0.013 0.167 0.017 Ce- 141 0.169 +/- 0.003 0.95 A 0.163 0.015 Mean 0.160 0.009 0.632 + 0.082 Cr-51 0.553 0.114 0.573 +/- 0.010 1.07 A 0.662 - 0.009 Mean = 0.616 + 0.047 0.332 - 0.029 Cs-134 0.343 0.032 0.325 +/- 0.005 0.97 A 0.271 - 0.033 Mean = 0.315 - 0.018 0.299 - 0.014 Cs-137 0.256 0.016 0.288 +/- 0.005 0.97 A 0.281 - 0.016 Mean = 0.279 + 0.009 0.273 :- 0.014 Co-58 0.256 0.016 0.247 +/- 0.004 1.06 A 0.258 - 0.016 Mean = 0.262 - 0.009 0.400 + 0.016 Mn-54 0.430 0.020 0.382 +/- 0.006 1.04 A 0.366 - 0.019 Mean = 0.399 - 0.011 0.158 - 0.016 Fe-59 0.155 0.021 0.139 +/-- 0.002 1.01 A 0.109 - 0.019 Mean = 0.141 - 0.011 0.419 - 0.029 Zn-65 0.493 0.039 0.457 +/- 0.008 1.01 A 0.477 - 0.036 Mean = 0.463 + 0.020 0.388 4- 0.013 0.366 0.015 Co-60 0.397 +/- 0.007 0.96 A 0.395 0.015 Mean 0.383 0.008 (1) Ratio = Reported/Analytics. A=Acceptable

Sample provided by Analytics, Inc. U=Unacceptable 108

7.

3.5 REFERENCES

7.3.5.1 Radioactivity and Radiochemistry, The Counting Room: Special Edition, 1994 Caretaker Publications, Atlanta, Georgia.

7.3.5.2 Data Reduction and Error Analysis for the Physical Sciences, Bevington P.R., McGraw Hill, New York (1969).

109

8. Land Use Census The Vermont Yankee Nuclear Power Station Off-site Dose Calculation Manual 3/4.5.2 requires that a Land Use Census be conducted annually between the dates of June 1 and October 1. The census identifies the locations of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of five miles of the plant. The census also identifies the nearest milk animal (within three miles of the plant) to the point of predicted highest annual average D/Q (deposition factor for dry deposition of elemental radionuclides and other particulates) value due to elevated releases from the plant stack in each of the three major meteorological sectors. The 2011 Land Use Census was conducted in the summer of 2011 in accordance with the ODCM.

Following the collection of field data and in compliance with Off-site Dose Calculation Manual (ODCM)

Section 10.1, a dosimetric analysis would be performed to compare the census locations to the "critical receptor" identified in the ODCM. This critical receptor is the location that is used in the Method I screening dose calculations found in the ODCM (i.e. the dose calculations done in compliance with ODCM Surveillance 4.3.3). If a census location has a 20% greater potential dose than that of the critical receptor, this fact must be announced in the annual Radioactive Effluent Release Report for that period. A re-evaluation of the critical receptor would also be done at that time. No changes in the census data from year 2008 occurred in the 2011 census; therefore no revisions of the 2008 calculations were required.

Pursuant to ODCM 3.5.2.a, a dosimetric analysis would be performed, using site specific meteorological data, to determine which milk animal locations would provide the optimal sampling locations. If any location had experienced a 20% greater potential dose commitment than at a currently sampled location, the new location would be added to the routine environmental sampling program in replacement of the location with the lowest calculated dose (which is eliminated from the program). The 2011 Land Use Census did not identify any locations, meeting the criteria of ODCM Table 3.5.1, with a greater potential dose commitment than at currently sampled locations. No changes to the Radiological Environmental Monitoring Program (REMP) were required based on the Land Use Census.

The results of the 2011 Land Use Census are included in this report in compliance with ODCM 4.5.2 and ODCM 10.2. The locations identified during the census may be found in Table 8.1.

110

TABLE 8.1 2011 LAND USE CENSUS LOCATIONS*

SECTOR NEAREST RESIDENCE NEAREST MILK ANIMAL Km (Mi) Km (Mi)

N 1.4 (0.9) ----

NNE 1.4 (0.9) 5.5 (3.4) Cows NE 1.3 (0.8) ----

ENE 1.0 (0.6)

E 0.9(0.6)

ESE 1.9(1.1) ----

SE 2.0 (1.2) 3.6 (2.2) Cows**

SSE 2.1 (1.3) ----

S 0.6(0.4) 2.2 (1.4) Cows**

SSW 0.5 (0.3) ----

SW 0.4 (0.3) 8.2 (5.1) Cows WSW 0.5 (0.3) ----

W 0.6 (0.4) 0.8 (0.5) Cows WNW 1.1 (0.7) ----

NW 2.3(1.4)

NNW 1.7(1.0)

Sectors and distances are relative to the plant stack as determined by a Global Positioning System survey conducted in 1997.

- Location of nearest milk animal within 3 miles of the plant to the point of predicted highest annual average D/Q value in each of the three major meteorological sectors.

111

9.

SUMMARY

During 2011 as in all previous years of plant operation, a program was conducted to assess the levels of radiation or radioactivity in the Vermont Yankee Nuclear Power Station environment. Over 1000 samples were collected (including TLDs) over the course of the year, with a total of over 2700 radionuclide or exposure rate analyses performed. The samples included groundwater, river water, sediment, fish, milk, silage, mixed grass, storm drain sediment, and storm drain water. In addition to these samples, the air surrounding the plant was sampled continuously and the radiation levels were measured continuously with environmental TLDs.

Three of the objectives of the Radiological Environmental Monitoring Program (REMP) are:

To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the operation of the station.

To provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits.

To verify the adequacy and proper functioning of station effluent controls and monitoring systems..

Low levels of radioactivity from three sources (discussed below) were detected in samples collected off-site as a part of the radiological environmental monitoring program. Most samples had measurable levels of naturally-occurring K-40, Be-7, Th-232 or radon daughter products. These are the most common of the naturally-occurring radionuclides.

Samples of milk and sediment contained fallout radioactivity such as Cs-137 and Sr-90 from atmospheric nuclear weapons tests conducted primarily from the late 1950s through 1980.

Tritium, at concentrations significantly higher than background levels, was detected in on-site groundwater monitoring wells installed in 2007 and in 2010 in response to industry events and the discovery of primary system leakage from underground Augmented Off Gas (AOG) System condensate return piping into the subsurface groundwater pool under the plant site. The leakage from this piping was terminated in early February, 2010. Extensive sampling and analysis was performed on groundwater samples and other media throughout all of year 2011. Further steps to remediate the contamination of the subsurface groundwater layer under the plant site are underway. More detail of this event is provided in 112

the 2011 Annual Radioactive Effluent Release Report.

Finally, the accidents at the Fukushima Daiichi nuclear power stations in Japan in early 2011 led to brief but measurable plant-generated radioactive materials in environmental samples collected from around the United States and the planet. REMP samples obtained from Vermont Yankee environmental air sample stations and local dairies during 2011 identified detectable concentrations of isotopes that could be related to operation of Entergy Vermont Yankee. Given the following facts, it is concluded that the detectable concentrations are not a result of Entergy Vermont Yankee operation:

(1) The quantities of radioactive airborne effluents from Entergy Vermont Yankee during 2011 did not increase significantly compared to year 2010.

(2) Prior REMP sample results have not detected the presence of these isotopes in air and milk samples collected in support of the Entergy Vermont Yankee REMP.

(3) The concentrations being detected in the indicator samples were also identified in the control samples from Entergy Vermont Yankee.

As such, the atypical detection of these radionuclides in both indicator and control samples is credibly attributed to the trans-Pacific transport of airborne releases from Fukushima Daiichi following the March 11, 2011 Tohoku earthquake and is not related to the operations of Entergy Vermont Yankee.

113

10. REFERENCES

1. USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.

2. NCRP Report No. 94, Exposure of the Population in the United States and Canadafrom Natural BackgroundRadiation, National Council on Radiation Protection and Measurements, 1987.

3. Ionizing Radiation: Sources and Biological Effects, United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 1982 Report to the General Assembly.

4. Kathren, Ronald L., Radioactivityand the Environment - Sources, Distribution,and Surveillance, Harwood Academic Publishers, New York, 1984.

5. Till, John E. and Robert H. Meyer, ed., RadiologicalAssessment - A Textbook on Environmental Dose Analysis, NUREG/CR-3332, U.S. Nuclear Regulatory Commission, Washington, D.C.,

1983.

6. NUREG/CR-3130, Influence of Leach Rate and Other Parameterson Groundwater Migration, February 1983.

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BVY 12-034, 2011 Annual Radiological Environmental Operating Report

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