Text

2004 Annual Radiological Environmental Operating Report
	ML051380157
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png; (DPR-028)
Issue date:	05/11/2005
From:	Devincentis J; Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BVY 05-55
	Download: ML051380157 (103)
	v • d • e

-Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

Vermont Yankee P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302.0500 Tel 802 257 5271 May 11, 2005 BVY 05-55 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271) 2004 Annual Radiological Environmental Operating Report In accordance with Vermont Yankee Technical Specification 6.6.E, attached is a copy of the 2004 Annual Radiological Environmental Operating Report. This report contains a summary and analysis of the radiological environmental data collected for the calendar year 2004.

There are no new regulatory commitments contained in this submittal We trust that the information provided is adequate; however, should you have questions or require additional information, please contact me at (802) 258-4236.

Sincerely, James M. DeVincentis Manager, Licensing Vermont Yankee Nuclear Power Station Attachment (1) cc:

USNRC Region 1 Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS Vermont Department of Public Service Vermont Division of Occupational and Radiological Health

Docket No. 50-271 BVY 05-55 Vermont Yankee Nuclear Power Station 2004 Annual Radiological Environmental Operating Report

ENTERGY NUCLEAR NORTHEAST - VERMONT YANKEE Vermont Yankee Nuclear Power Station ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Year 2004 Preparation coordina ed b CI Ste h hneSkib owskySr.

em Spe st (REMP)

Doe Reviewed by:

/o /

I Stephen C.Mc voy, he st y Supervisor D

Approved for Distribution: d,<-X--

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/It Samuel A.Wender IV, Chemistry Superintendent Date

TABLE OF CONTENTS

1.

INTRODUCTION...........................................

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 Zones...........................................

6 4.2 Pathways Monitored...........................................

6 4.3 Descriptions of Monitoring Programs...........................................

7 5

RADIOLOGICAL DATA

SUMMARY

TABLES..........................................

24

6.

ANALYSIS OF ENVIRONMENTAL RESULTS 44 6.1 Sampling Program Deviations..........................................

44 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..........................................

83 7.1 Framatome ANL Environmental Laboratory (E-LAB)..........................................

83 7.2 Teledyne Brown Engineering Laboratory (TBE)..........................................

84

8.

LAND USE CENSUS..........................................

94

9.

SUMMARY

96

10.

REFERENCES..........................................

97 i

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

Sensitivity Requirements.16 4.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples...........................................

17 5.1 Radiological Environmental Program Summary.................................... 26 5.2 Environmental TLD Data Summary...........................................

41 5.3 Environmental TLD Measurements.........................

.................. 42 6.1 Summary of Storm Drain System Sediment Sample Analyses.............. 50 6.2 Summary of Storm Drain System Water Sample Analyses................... 51 6.3 Summary of Air Compressor Condensate and Manhole Water Tritium Concentrations.........................................

51 7.2.1 TBE-ES Analytics Environmental Cross Check Program..................... 88 7.2.2 TBE-ES DOEIEML Environmental Cross Check Program............... 91 7.2.3 TBE-ES ERA Environmental Cross Check Program....................... 93 7.2.4 TBE-ES MAPEP Environmental Cross Check Program................... 94 8.1 Land Use Census Locations.........................................

95 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 Plant......

21 4.5 TLD Locations Within 5 Kilometers of Plant...

22 4.6 TLD Locations Greater than 5 Kilometers from Plant.23 6.1-6.27 Environmental Program Trend Graphs.56 iii

1. INTRODUCTION This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Vermont Yankee Nuclear Power Corporation in the vicinity of the Vermont Yankee Nuclear Power Station (VYNPS) in Vernon, Vermont during the calendar year 2004. It 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 to the background radioactivity and radiation that is 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 2004 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 2004 environmental TLD measurements.

Section 6: Provides the results of the 2004 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 Teledyne Brown Engineering Laboratory. Included are the laboratory's results of the Analytics Intercomparison Program.

Section 8: Summarizes the requirements and the results of the 2004 Land Use Census.

Section 9: Gives a summary of the 2004 Radiological Environmental Monitoring Program.

1

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 radionuclides that these elements have decayed into.

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).

2

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 to this category was the fallout from the Chemobyl accident in April of 1986, which was detected in the Vermont Yankee environment and other parts of the world. 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 o 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 Cesiuml37 (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 readily 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 industry. These collectively are insignificant on a global scale when compared to the sources discussed above (natural and fallout).

3

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 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.

4

4. PROGRAM DESIGN The Radiological Environmental Monitoring Program (REMP) for the Vennont 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 Radioactivity 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 Procedural Specifications for Thermoluminescence Dosimetry: 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.

5

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 2004, analytical measurements of environmental samples were performed at the Teledyne Brown Engineering Laboratory (TBE) in Knoxville, Tennessee. TLD badges are posted and retrieved by the Vermont Yankee Chemistry Department, and are analyzed by the Framatome ANP 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 6

Direct Radiation Pathway TLD Monitoring 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 were 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 were 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 [tCi/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 1-131.

Whenever the main plant stack effluent release rate of 1-131 is equal to or greater than 0.1 jICi/sec, weekly charcoal cartridge collection 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 7

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.

4.3.4 Ground Water Sampling Grab samples are collected quarterly from 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 the contracted environmental laboratory for gamma-emitting radionuclides.

4.3.6 Milk Sampling When milk animals are identified as being on pasture feed (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 influence from it. 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 I-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 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.

8

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 1-131.

4.3.9 Fish Sampling Fish samples are collected semiannually at two locations (upstream of the plant and in 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.

43.10 TLD Monitoring Direct gamma radiation exposure is continuously monitored with the use of thermoluminescent dosimeters (TLDs). Specifically, Panasonic UD-801ASI 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 Control 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, thirteen more are typically posted at or near the site boundary. The plant staff posts and retrieves all TLDs, while the contracted environmental laboratory (Framatome ANP) processes them.

9

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

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

1. Direct Radiation (TLDs) 40 Continuous Quarterly Gamma dose; Outer Each TLD Ring - dc-dose only, unless gaseous release Control was 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 2

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 See ODCM Table 3.5.1 for complete footnotes.

10

TABLE 4.1, cont.

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

Exposure Pathway Collection An ysis and/or Nominal Noia Sample Media Number of Routine Sampling Comlciona Analysis Analysis Sample Mode Corequeonc Type Frequency LocationsFrqec

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 statio n

See ODCM Table 3.5.1 for complete footnotes.

11

TABLE 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (NON-TLD) IN 2004 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Exposure Station From Plant From Pathway Code Station Description Zone(a)

Stack (km)

Plant

1. Airborne AP/CF-l1 River Sta. No. 3.3 1

1.9 SSE AP/CF-12 N. Hinsdale, NH I

3.6 NNW AP/CF-13 Hinsdale Substation 1

3.1 E

AP/CF-14 Northfield, MA I

11.6 SSE AP/CF-15 Tyler Hill Road 1

3.1 WNW AP/CF-21 Spofford Lake C

16.4 NNE AP/CF-40 Gov. Hunt House I

On-site

2. Waterborne

a. Surface WR-l I River Sta. No. 3.3 1

1.9 SSE WR-21 Rt.9 Bridge C

11.8 NNW

b. Ground WG-1 I Plant Well I

0.2 On-site WG-12 Vernon Nursing Well 1

2.1 SSE WG-13 COB Well 1

0.3 On-site WG-14 Plant Support Bldg (PSB) Well I 0.3 On-site WT-14 Test Well 201 1

On-site WT-16 Test Well 202 1

On-site WT-17 Test Well 203 I

On-site WT-1 8 Test Well 204 1

On-site WG-22 Skibniowsky Well C

13.7 N

c. Sediment SE-I I Shoreline Downriver 1

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 2004 VERMONT YANKEE NUCLEAR POWER STATION Exposure Pathway Station Code Distance From Plant Zone(a)

Stack(km)

Direction From Plant Stack Station Description

3. Ingestion

a. Milk TM-I TM-14 TM-18 TM-22 TM-24 TM-25 Miller Farm Brown Farm Blodgett Farm Franklin Farm County Farm Downey-Spencer Vernon Pond Rt.9 Bridge I

I I

I C

I 0.8 2.2 3.6 9.7 21.6 6.9 0.6(b) 11.8 W

S SE WSW N

W SSE NNW

b. Fish FH-II FH-21 I

C

c. Mixed Grass

d. Silage TG-I I TG-12 TG-13 TG-14 TG-15 TG-21 TG-40 TC-I I TC-14 TC-1 8 TC-22 TC-24 TC-25 River Sta. No. 3.3 N. Hinsdale, NH Hinsdale Substation Northfield, MA Tyler Hill Rd.

Spofford Lake Gov. Hunt House Miller Farm Brown Farm Blodgett Farm Franklin Farm County Farm Downey-Spencer I

I I

C I

1.9 3.6 3.1 11.6 3.1 16.4 0.8 2.2 3.6 9.7 21.6 6.9 SSE NNW E

SSE WNW NNE On-site W

S SE WSW N

W I

I I

I C

I (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).

13

TABLE 4.3 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (TLD) IN 2004 VERMONT YANKEE NUCLEAR POWER STATION Station Code DR-I DR-2 DR-3 DR-4 DR-5 DR-6 DR-7 DR-8 DR-9 DR-10 DR-Il DR-12 DR-13 DR-14 DR-15 DR-16 DR-17 DR-18 DR-19 DR-20 DR-21 DR-22 DR-23 DR-24 DR-25 DR-26 DR-27 DR-28 DR-29 DR-30 Station Description River Sta. No. 3.3 N. Hinsdale, NH Hinsdale Substation Northfield, MA Spofford Lake Vernon School Site Boundary(c)

Site Boundary Inner Ring Outer Ring Inner Ring Outer Ring InnerRing Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Inner Ring Outer Ring Zone(a)

I I

I C

C SB SB I

0 I

0 Distance From Plant (km_ (d) 1.6 3.9 3.0 11.3 16.5 0.52 0.28 0.25 1.7 4.5 1.6 3.6 1.2 3.9 1.5 2.8 1.2 3.0 3.7 5.3 1.8 3.3 2.0 3.9 1.9 3.8 1.1 2.2 0.9 2.4 Direction From Plant(d)

SSE NNW E

SSE NNE WSW W

SSW N

N NNE NNE NE NE ENE ENE E

E ESE ESE SE SE SSE SSE S

S SSW SSW SW SW 14

TABLE 4.3, cont.

RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (TLD) IN 2004 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Station From Plant From Code Station Description Zone(a)

(M(d)

Plant(d)

DR-31 Inner Ring 1

0.71 WSW DR-32 Outer Ring 0

5.1 WSW DR-33 Inner Ring I

0.66 WNW DR-34 Outer Ring 0

4.6 W

DR-35 Inner Ring 1

1.3 WNW DR-36 Outer Ring 0

4.4 WNW DR-37 Inner Ring 1

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-41(b)

Site Boundary SB 0.38 SSW DR-42 (

Site Boundary SB 0.59 S

DR-43 (

Site Boundary SB 0.44 SSE DR-44()

Site Boundary SB 0.19 SE DR-45 Site Boundary SB 0.12 NE DR-46 Site Boundary SB 0.28 NNW DR-47 (

Site Boundary SB 0.50 NNW DR-48 (

Site Boundary SB 0.82 NW DR-49(b Site Boundary SB 0.55 WNW DR-50(b)

Gov. Hunt House 1

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/)

(pCi/m3)

(pCi/Kg)

(pCi/i)

(pCi/Kg) dry)

Gross-Beta 4

0.01 H-3 3000 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 See ODCM Table 4.5.1 for 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/1)

(pCi/m3 )

(pCi/Kg)

(pCi/I)

(pCi/Kg)

(pCi/Kg-dry)

H-3 20,000(a)

Mn-54 1000 30,000 Fc-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 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

j...

t, V

Figure 4-1 Environmental Sampling Locations in Close Proximity to the Plant 18

Iq Figure 4-2 Environmental Sampling Locations Within 5Km of Plant 19

. 1 N

Figure 4-3 Environmental Sampling Locations Greater than 5Km firom Plant 20

k.

Figure 4-4 TLD Locations in Close Proximity to the Plant 21

,.1 Figure 4-5 TLD Locations Within 5 Km of Plant 22

'V Figure 4-6 TLD Locations Greater Than 5 Kmfrom Plant 23

5. RADIOLOGICAL DATA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples that were collected during 2004. 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 2004, 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.

The left-most column of Table 5.1 contains the radionuclide of interest, the total number of analyses for that radionuclide in 2004, 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 station which had the highest mean concentration during 2004 for that radionuclide; and (3) the Control stations, which are beyond the influence of the plant. 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 aposteriori LLD. In previous years, data less than the a posteriori LLD were converted to zero for purposes of reporting the means and ranges.

24

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 aposteriori LLD (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 posteriori LLD for its analysis is averaged with those values above the a posteriori LLD to determine the average of the results. Likewise, the values are reported in ranges even though they are below the a posteriori LLD. 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 aposteriori LLD 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 that were routinely analyzed and reported by the environmental laboratory (in a gamma spectroscopy analysis) were: Th-232, Ag-I 10m, Ba/La-140, Be-7, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59, 1-131, 1-133, K-40, Mn-54, Mo-99, Np-239, Ru-103, Ru-106, Sb-124, Se-75, Tel-132, U-238, 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 2004 Radiological Environmental Operating Report Vermont Yankee Table 5.1:

Sample Medium:

Air Particulate (AP)

Charcoal Cartridge (CF)

River Water (WR)

Ground Water (WG)

Sediment (SE)

Test Well (WNT)

Milk (TM)

Silage (TC)

Mixed Grass (TG)

Fish (FH) 26

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIHE VERMONT YANKEE NUCLEAR POWER PLANT, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 INDICATOR CONTROL LOCATION WVITH IIGIIEST 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)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS AIR PARTICULATE (PCI/CU.METER)

GROSS BETA 364 28 GAMMA BE-7 K-40 CS-134 CS-137 RA-226 Ti1-232 0.01 0.0150 (312/312)

(0.0059/0.0340)

N/A 0.0877 (24/24)

(0.0095/0.1300)

N/A 0.0009 (0/24)

(-0.0172/0.01 11) 0.05

-0.0001 (0/24)

(-0.0013/0.0005) 0.06 0.0000 (0/24)

(-0.0003/0.0003)

N/A 0.0001 (0/24)

(-0.010310.0087)

N/A 40.0001 (0/24)

(-0.0014/0.0013) 0.07

-0.0003 (0/312)

(-0.0179/0.0125)

.0145 (52/52)

(0.0061/0.0258) 0.0926 (4/4)

(0.0802/0.1120) 0.0083 (1/4)

(0.0022/0.0125)

-0.0004 (0/4)

(-0.0013/0.00004)

-0.0002 (0/4)

(-0.0005/-0.0001)

-0.0009 (0/4)

(-0.006010.0025) 0.0008 (0/4)

(.0.0001/0.0017) 0.0011 (0/52)

(-0.0098/0.0118) 0.0158 (52/52)

(0.0075/0.0276) 0.0996 (414)

(0.0759/0.1180) 0.0083 (1/4)

(0.0022/0.0125) 0.0003 (0/4)

(-0.000110.0005) 0.0001 (0/4)

(-0.0001/0.0003) 0.0016 (0/4)

(-0.0036/0.0087) 0.0008 (0/4)

(-0.0001/0.0017) 0.0011 (0/52)

(-0.0098/0.0118) 40 INDICATOR GOVERNOR IfUNT HOUSE ON-SITE 21 CONTROL SPOFFORD LAKE 16.4 MILES NNE OF SITE 40 INDICATOR GOVERNOR HUNT HOUSE ON-SITE 13 INDICATOR IIINSDALE SUBSTATION 3.1 MILES E OF SITE 12 INDICATOR N. HINSDALE, Nil 3.6 MILES NNW OF SITE 21 CONTROL SPOFFORD LAKE 16.4 MILES NNE OF SITE 21 CONTROL SPOFFORD LAKE 16.4 MILES NNE OF SITE 0

40 INDICATOR GOVERNOR HUNT HOUSE ON-SITE 0

0 0

AIR IODINE (PCI/CU.METER) 1-131 364 0

27 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, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 INDICATOR CONTROL LOCATION VITII IlIGHIEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION N NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS RIVER WATER (PCI/LITER)

GROSS BETA 24 2.21 (5/12)

(0.893/8.73) 1.99 (6/12)

(1.03/4.07) 2.21 (5/12)

(0.893/8.73) 11 INDICATOR RIVER STATION NO. 3.3 1.9 MILES SSE OF SITE 0

TRITIUM GAMMA MN-54 8

24 CO-58 FE-59 CO-60 ZN-65 ZR-95 3000

-95.8 (0/4)

(-195/101) 15 0.014 (0/12)

(-1.61/0.646) is

-0.066 (0/12)

(-0.905/0.916) 30 0.360 (0/12)

(-1.30/3.48) 15 0.208 (0/12)

(-0.865/0.923) 30

-0.700 (0/12)

(-4.56/1.68) 15 0.059 (0/12)

(-1.11/1.06)

-91.0 (0/4)

(-s89/n7.3)

-0.343 (0/12)

(-1.70/0.454)

-0.125 (0/12)

(-1.08/0.937)

-0.456 (0/12)

(-3.47/2.16) 0.184 (0/12)

(-1.21/1.79)

-1.26 (0/12)

(-5.25/1.60) 0.107 (0/12)

(-1.10/1.38)

-91.0 (0/4)

(-189n7.3) 0.014 (0/12)

(-1.61/0.646)

-0.066 (0/12)

(-0.905/0.916) 0.360 (0/12)

(-1.30/3.48) 0.208 (0/12)

(-0.865/0.923)

-0.700 (0/12)

(-4.56/1.68) 0.107 (0/12)

(-1.10/1.38) 21 CONTROL RT. 9 BRIDGE 11.8 MILES NNW OF SITE I I INDICATOR RIVER STATION NO. 3.3 1.9 MILES SSE OF SITE I I INDICATOR RIVER STATION NO. 3.3 1.9 MILES SSE OF SITE I I INDICATOR RIVER STATION NO. 3.3 1.9 MILES SSE OF SITE II INDICATOR RIVER STATION NO. 3.3 1.9 MILES SSE OF SITE I I INDICATOR RIVER STATION NO. 3.3 1.9 MILES SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 MILES NNW OF SITE 0

0 0

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

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIHE VERMONT YANKEE NUCLEAR POWER PLANT, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 INDICATOR CONTROL LOCATION WITIT IIIGIIEST 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)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS 1-131 CS-134 CS-137 BA-LA-140 RA226 nTI-232 N/A 0.492 (0/12)

(-2.35/3.39)

Is

-0.477 (0/12)

(-5.80/0.439) 18 0.221 (0/12)

(.0.684/0.950) 15

-0.174 (0/12)

(-1.95/0.950)

N/A 5.06 (0/12)

(-37.2/56.4)

N/A 0.340 (0/12)

(-3.14n.0s) 0.567 (0/12)

(-1.59/2.78)

-1.56 (0/12)

(-10.2/1.24) 0.182 (0/12)

(-0.902/2.33) 0.436 (0/12)

(-0.858/1.96)

-11.0 (0/12)

(.107/61.0)

-3.54 (0/12)

(-20.0/9.36) 0.567 (0/12)

(-1.59/2.78)

-0.477 (0/12)

(.5.80/0.439) 0.221 (0/12)

(40.684/0.950) 0.436 (0/12)

(40.858/1.96) 5.06 (0/12)

(-37.2/56.4) 0.340 (0/12)

(-3.14n.0) 21 CONTROL RT.9 BRIDGE 11.8 MILES NNW OF SITE I I INDICATOR RIVER STATION NO. 3.3 1.9 MILES SSE OF SITE 11 INDICATOR RIVER STATION NO. 3.3 1.9 MILES SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 MILES NNW OF SITE II INDICATOR RIVER STATION NO. 3.3 1.9 MILES SSE OF SITE II INDICATOR RIVER STATION NO. 3.3 1.9 MILES SSE OF SITE 0

0 0

0 GROUND WATER (PCI/LITER)

GROSS BETA 20 4.99 (16/16)

(1.90/8.56) 2.01 (3/4)

(1.07/2.65) 6.40 (4/4)

(5.38/8.56) 11 INDICATOR PLANT WELL 0.2 MILES ON-SITE 0

TRITIUM 20 3000 26.0 (0/16)

(.127/162) 56.3 (0/4)

(20.3/110) 108 (0/4)

(78.2/162) 13 INDICATOR COB WELL 0.3 MILES ON-SITE 0.

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, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 INDICATOR CONTROL LOCATION WIT!! IIIGIIEST 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)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS 1-131 GAMMA MN-54 20 20 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 N/A 0.001 (0/16)

(-0.247/0.137) 15

-0.513 (0/16)

(-2.20/1.61) 15

-0.470 (0/16)

(-2.31/0.924) 30 0.387 (0/16)

(-4.51/6.02) 15 0.305 (0/16)

(-2.53/2.68) 30

-1.08 (0/16)

(-6.25/2.27)

N/A 1.10 (0/16)

(-2.08/5.49) 15 0.489 (0/16)

(-3.03/5.09)

-0.002 (0/4)

(-0.075/0.063) 0.103 (0/4)

(-0.726/0.956)

-0.709 (0/4)

(-1.90/-0.060)

-1.07 (0/4)

(-2.45/0.872) 1.09 (0/4)

(0.215/1.85)

-1.64 (0/4)

(-5.45/0.215)

-0.390 (0/4)

(-2.29/1.59) 0.507 (0/4)

(-0.519/1.45) 0.085 (0/4)

(0.049/0.137) 0.103 (0/4)

(-0.726/0.956)

-0.238 (0/4)

(-0.843/0.378) 1.38 (0/4)

(0.408/3.15) 1.09 (0/4)

(0.215/1.85) 0.855 (0/4)

(-0.413/2.27) 2.21 (0/4)

(0.384/5.49) 2.00 (0/4)

(-0.109/5.09) 13 INDICATOR COB WELL 0.3 MILES ON-SITE 22 CONTROL SKJIBNIOWSKY WELL 13.7 MILES N OF SITE 13 INDICATOR COB WELL 0.3 MILES ON-SITE II INDICATOR PLANT WELL 0.2 MILES ON-SITE 22 CONTROL SKIBNIOWSKY WELL 13.7 MILES N OF SITE 12 INDICATOR VERNON NURSING WELL 2.1 MILES SSE OF SITE 11 INDICATOR PLANT WELL 0.2 MILES ON-SITE 12 INDICATOR VERNON NURSING WELL 2.1 MILES SSE OF SITE 0

0 0

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, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 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)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS CS-134 CS-137 BA-LA-140 RA226 TH-232 RA-228 I5

-1.16 (0/16)

(-7.68/1.97) 18

-0.614 (0/16)

(-2.33/1.22) 15

-0.233 (0/16)

(-2.10/1.81)

N/A 0.259 (4/16)

(-0.532/1.61)

N/A 1.02 (0/16)

(-4.77/4.99)

N/A 1.33 (5/16)

(-0.132/3.64)

N/A 311 (4/30)

(.270/2540)

N/A 15637 (30/30)

(10100/20900) 0.361 (0/4)

(-0.251/0.721) 0.653 (0/4)

(.1.62/1.91) 0.058 (0/4)

(-0.476/1.08)

-0.172 (0/4)

(-0.695/0.161) 0.028 (0/4)

(-4.71/4.88) 0.553 (1/4)

(-0.084/1.61) 320 (1/2)

(203/436) 13150 (2/2)

(12900/13400) 0.361 (0/4)

(-0.251/0.721) 0.653 (0/4)

(-1.62/1.91) 0.580 (0/4)

(.0.690/1.81) 1.10 (3/4)

(0.313/1.61) 2.16 (0/4)

(-2.43/4.00) 2.61 (4/4)

(1.55/3.64) 1497 (1/2)

(453/2540) 18550 (2/2)

(16200n20900) 22 CONTROL SKIBNIOWSKY WELL 13.7 MILES N OF SITE 22 CONTROL SKIBNIOWSKY WELL 13.7 MILES N OF SITE 12 INDICATOR VERNON NURSING WELL 2.1 MILES SSE OF SITE 13 INDICATOR COB WELL 0.3 MILES ON-SITE 12 INDICATOR VERNON NURSING WELL 2.1 MILES SSE OF SITE 13 INDICATOR COB WELL 0.3 MILES ON-SITE 17 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 30 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 0

0 0

SEDIMENT (PCI/KG DRY)

GAMMA BE-7 32 0

0 K-40 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 POWVER PLANT, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 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)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS MN-54 CO-60 NB-95 CS.134 CS-137 N/A 7.54 (0/30)

(-34.4/28.8)

N/A 9.29 (0/30)

(- 18.5n7.4)

N/A 6.17 (0/30)

(.82.2/90.6) 150 1.51 (0/30)

(-25.9/28.5) 180 128 (25/30)

(30.3/196) 15.7 (0/2)

(5.85/25.5) 9.19 (0/2)

(2.78/15.6) 45.9 (0/2)

(34.2/57.5) 4.40 (0o2)

(-1.12/9.91) 48.6 (1/2)

(18.8/78.3) 21.5 (0/2)

(21.0/21.9) 43.6 (on)

(7.77n9.4) 69.1 (0/2)

(47.5/90.6) 21.9 (0/2)

(15.2/28.5) 166 (2/2)

(136/196) 30 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 17 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 19 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 18 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 13 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 0

0 0

166 (2/2)

(158/174)

BA-LA-140 RA-226 N/A

-149 (0/30)

(-793/271)

N/A 2155 (22/30)

(964/3410)

-64.7 (0/2)

(-66.1/-63.3) 1415 (1/2)

(1350/1480) 105 (0/2)

(-60.4/271) 3035 (2/2)

(2660/3410) 25 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 30 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 30 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 0

0 0-32 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIHE VERMONT YANKEE NUCLEAR POWER PLANT, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 INDICATOR CONTROL LOCATION WIT IIIGIIEST 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)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS AC-228 TH-228 TH-232 U-238 N/A 2083 (29/30)

(897/4560)

N/A 3207 (29/30)

(1740/4630)

N/A 1123 (30/30)

(658/1490)

N/A 1289 (0/30)

(-1920/5820)

N/A 21.4 (8/8)

(7.51/41.9)

N/A 49.5 (0/8)

(.69.4/159)

N/A 24.6 (1/8)

(.2.75/81.0)

N/A

-0.123 (0/8)

(-1.06/0.446) 1454 (1/2)

(997/1910) 2145 (2n2)

(1790/2500) 709 (2/2)

(600/817)

-839 (0/2)

(.1030/.647)

N/A N/A N/A N/A 3300 (2/2)

(2040/4560) 3895 (2/2)

(3370/4420) 1375 (2/2)

(1260/1490) 2998 (0/2)

(176/5820) 38.1 (2/2)

(34.3/41.9) 104 (0/2)

(49.6/159) 43.9 (1/2)

(6.71/81.0) 0.021 (0/2)

(-0.296/0.338) 19 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 24 INDICATOR NORTH STORM DRAIN OUTFALL 0.2 MILES EOF SITE 35 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 30 INDICATOR NORTH STORM DRAIN OUTFALL 0.1 MILES E OF SITE 14 INDICATOR TEST WELL 201 ON-SITE 28 INDICATOR TEST WELL 204 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 17 INDICATOR TEST WELL 203 ON-SITE TEST WELLS (PCI/LITER)

GROSS BETA 8

TRITIUM GAMMA K-40 8

MN-54 0

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

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIHE VERMONT YANKEE NUCLEAR POWER PLANT, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 INDICATOR CONTROL LOCATION WIThI lHlGITEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR T'PES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS CO-58 FE-59 CO-60 NB-95 1.131 CS-134 CS-137 BA-LA-1 40 N/A

-0.401 (0/8)

(-1.12/0.149)

N/A 0.212 (0/8)

(-1.14/3.00)

N/A 0.422 (0/8)

(-0.357/2.82)

N/A 0.324 (0/8)

(-0.987/2.76)

N/A 0.044 (0/8)

(-0.710/1.14)

N/A

-3.95 (0/8)

(-12.7/0.389)

N/A 0.051 (0/8)

(-0.626/0.638)

N/A N/A N/A N/A

-0.181 (0/2)

(-0.381/0.019) 1.48 (0/2)

(-0.049/3.00) 1.36 (0/2)

(-0.091/2.82) 1.83 (0/2)

(0.902/2.76) 17 INDICATOR TEST WELL 203 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 14 INDICATOR TEST WELL 201 ON-SITE 17 INDICATOR TEST WELL 203 ON-SITE 14 INDICATOR TEST WELL 201 ON-SITE 14 INDICATOR TEST WELL 201 ON-SITE 14 INDICATOR TEST WELL 201 ON-SITE 16 INDICATOR TEST WELL 202 ON-SITE 0

0 0

0 NIA 0.538 (0/2)

(-0.065/1.14) 0 N/A 0.034 (o)

(-0.241/0.308) 0 N/A 0.232 (0/2)

(-0.175/0.638) 0 NIA

-0.328 (0/8)

(-1.66/0.805)

N/A 0.447 (0/2)

(0.088/0.805) 0-34 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, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 INDICATOR CONTROL LOCATION WITII }IIGCIEST 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)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS MILK (PCI/LITER) 1-131 SR-89 SR.90 GAMMA BE-7 106 24 24 106 I

.049 (0/88)

(-0.237/0.423)

N/A 1.61 (0/20)

(.2.15/4.77)

N/A 1.39 (13/20)

(-0.256/4.59)

N/A 2.04 (0/88)

(-17.0/20.0)

N/A 1448 (88/88)

(1150/2130) 15

-1.24 (0/88)

(.9.34/4.26) 18 0.822 (3/88)

(-2.54/8.43) i5

-0.300 (0/88)

(-7.73/3.26) 0.069 (0/18)

(-0.156/0.315) 0.844 (0/4)

(-0.551/2.76) 1.31 (4/4)

(0.926/1.81) 2.06 (0/18)

(-12.4/15.9) 1410 (18/18)

(1300/1690)

-2.56 (0/18)

(-8.20/1.72) 0.405 (0/18)

(-2.39/1.82) 40.485 (0/18)

(.3.46/1.27) 0.081 (0/16)

(-0.237/0.423) 2.69 (0/4)

(1.34/3.93) 3.31 (4/4)

(2.29/4.59) 3.39 (0/18)

(-8.95/19.3) 1815 (16/16)

(1440/2130)

-0.448 (0/16)

(-4.67/4.26) 3.15 (3/16)

(0.467/8.43) 0.150 (0/16)

(.1.10/1.55) 25 INDICATOR DOWNEY-SPENCER FARM 6.9 MILES W OF SITE 18 INDICATOR BLODGETT FARM 3.6 MILES SE OF SITE 25 INDICATOR DOWNEY-SPENCER 6.9 MILES W OF SITE 22 INDICATOR FRANKLIN FARM 9.7 MILES WSW OF SITE 25 INDICATOR DOWNEY-SPENCER 6.9 MILES W OF SITE 25 INDICATOR DOWNEY-SPENCER 6.9 MILES W OF SITE 25 INDICATOR DOWNEY-SPFNCER 6.9 MILES W OF SITE 25 INDICATOR DOWNEY-SPENCER 6.9 MILES W OF SITE 0

0 0

0 K40 CS-134 CS-137 BA-LA140 0

0 0

0 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, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 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)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS RA-226 AC-228 TH-228 TH-232 N/A

-0.612 (0/88)

(-93.2/81.5)

N/A

-0.613 (0/88)

(-14.2/13.2)

N/A

-32.8 (0/88)

(.142/147)

N/A

-0.022 (0/88)

(-12.5/11.5) 60

-1.07 (0/4)

(-5.99/2.38) 7.49 (0/I8)

(-22.6/35.6)

-2.22 (0/18)

(-14.1/15.3)

-27.8 (0/18)

(.143/67.0)

-3.02 (0/18)

(-13.0/3.06) 2.15 (0/1)

N/A 16.8 (0/18)

(-17.7/54.2) 0.351 (0/18)

(-8.23/10.7)

-21.5 (0/18)

(-92.7/69.6) 0.884 (0/18)

(-8.77/9.54) 2.38 (0/1)

N/A II INDICATOR MILLER FARM 0.8 MILES W OF SITE 14 INDICATOR BROWN FARM 2.2 MILES S OF SITE 14 INDICATOR BROWN FARM 2.2 MILES S OF SITE 14 INDICATOR BROWN FARM 2.2 MILES S OF SITE 22 INDICATOR FRANKLIN FARM 9.7 MILES WSW OF SITE 0

0 0

0 SILAGE (PCI/KG) 1-131 5

0 GAMMA BE-7 K-40 CS-134 5

N/A 658 (3/4)

(38.3/912)

N/A 5912 (4/4)

(I 140/15600) 60

-14.7 (0/4)

(-25.2/-8.94) 1280 (1/l)

NIA 3680 (1/1)

NIA

-44.0 (0/1)

N/A 1280 (1/1)

N/A 15600 (1/1)

N/A

-8.94 (0/1)

N/A 24 CONTROL COUNTY FARM 21.6 MILES N OF SITE 22 INDICATOR FRANKLIN FARM 9.7 MILES WSW OF SITE 22 INDICATOR FRANKLIN FARM 9.7 MILES WSW OF SITE 0

0 0

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, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 INDICATOR CONTROL LOCATION WIT1 ((IGHEST ANNUAL M EAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION #

NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F)

(F)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS CS-137 TH-232 80 8.18 (0/4)

(1.03/27.9)

N/A 38.3 (0/4)

(4.48/137)

MIXED GRASS (PCI/KG) 1-131

-10.2 (0/1)

N/A

-24.5 (0/1)

N/A 3.89 (0/3)

(-1.25/9.02) 1691 (3/3)

(302/4010) 27.9 (0/1)

N/A 137 (0/1)

N/A 6.09 (0/3)

(-1.66/14.0) 2074 (3/3)

(791/4380) 22 INDICATOR FRANKLIN FARM 9.7 MILES WSW OF SITE 22 INDICATOR FRANKLIN FARM 9.7 MILES WSW OF SITE 40 INDICATOR GOVERNOR HUNT HOUSE ON-SITE 12 INDICATOR N. HINSDALE, NH 3.6 MILES NNW OF SITE 0

0 0

21 21 60 0.529 (0/18)

(-14.3/18.7)

N/A 1574 (18/18)

(202/4380)

GAMMA BE-7 0

K40 NIA 6534 (18/18)

(2850/9480)

CS-134 CS-137 AC-228 60

-12.3 (0/18)

(43.1/3.44) 80 6.88 (1/18)

(-3.39/67.8)

N/A 68.1 (1/18)

(-4.27/550) 6123 (3/3)

(4990/8040)

-1.07 (0/3)

(-3.24/2.45) 0.570 (0/3)

(-3.57/3.47) 65.8 (0/3)

(19.1/94.7) 7493 (3/3)

(5390/9480) 1.15 (0/3)

(-0.624/3.44) 27.2 (1/3)

(3.38/67.8) 189 (0/3)

(7.16/550)

II INDICATOR RIVER STA. NO. 3.3 1.9 MILES SSE OF SITE 13 INDICATOR HINSDALE SUBSTATION 3.1 MILES E OF SITE 12 INDICATOR N. HINSDALE, NH 3.6 MILES NNW OF SITE 13 INDICATOR HINSDALE SUBSTATION 3.1 MILES E OF SITE 0

0 0

0 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, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWVER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 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)

NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS TH-228 TH-232 N/A

-165 (0/18)

(-734/319)

N/A 19.4 (0/18)

(-8.53/47.3) 83.0 (0/3)

(.81.9/181) 22.3 (0/3)

(11.4/40.9) 127 (0/3)

(23.5/319) 37.8 (0/3)

(29.6/47.3) 13 INDICATOR HINSDALE SUBSTATION 3.1 MILES E OF SITE 12 INDICATOR N. HINSDALE, NIH 3.6 MILES NNW OF SITE 0

0 FISH (PCI/KG)

GAMMA K-40 4

N/A 3185 (2/2)

(3100/3270)

MN-54 CO.58 FE-59 CO-60 ZN-65 130

-6.96 (0/2)

(-12.9/-1.01) 130

-11.6 (0/2)

(-13.1/-10-1) 260 0.150 (0/2)

(-27.6/27.9) 130 6.87 (0/2)

(0.840/12.9) 260

-16.6 (0/2)

(-26.0/.7.15) 3600 (2/2)

(3530/3670) 2.90 (0/2)

(2.77/3.03) 1.84 (0/2)

(0.280/3.39) 5.59 (0/2)

(-1.82/13.0)

-5.32 (0/2)

(-8.58/-2.05)

-5.25 (0o2)

(-7.51/-2.99) 3600 (212)

(3530/3670) 2.90 (0/2)

(2.77/3.03) 1.84 (0/2)

(0.280/3.39) 5.59 (0o2)

(-1.82/13.0) 6.87 (0/2)

(0.840/12.9)

-5.25 (0/2)

(-7.51/-2.99) 21 CONTROL RT. 9 BRIDGE 11.8 MILES NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 MILES NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 MILES NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 MILES NNW OF SITE I I INDICATOR VERNON POND 0.6 MILES SSE OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 MILES NNW OF SITE 0

0 0

0 38 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 5.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR TIHE VERMONT YANKEE NUCLEAR POWER PLANT, 2004 Name of Facility: VERMONT YANKEE NUCLEAR POWER PLANT DOCKET NUMBER:

50-271 Location of Facility: VERNON, VT REPORTING PERIOD:

2004 INDICATOR CONTROL LOCATION WITII GlIIEST 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)

NAME NONROUTiNE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)

(LLD)

MEASUREMENTS CS-134 CS-137 TI1-232 130

-12.8 (0/2)

(-27.9/2.40) 150 11.2 (0/2)

(8.21114.2)

N/A

-20.2 (0/2)

(.53.1/12.7) 2.65 (0/2)

(.10.4/15.7) 23.9 (0/2)

(19.1/28.7)

-4.40 (on)

(-30.8/22.0) 6.2 (818)

(5.6/6.9) 2.65 (0o2)

(-10.4/15.7) 23.9 (0/2)

(19.1/28.7)

-4.40 (0/2)

(.30.8/22.0) 7.7 (4/4)

(6.8/8.1) 21 CONTROL RT. 9 BRIDGE 11.8 MILES NNW OF SITE 21 CONTROL RT. 9 BRIDGE 11.8 MILES NNW OF SITE 21 CONTROL RT. 9 BRIDGE I 1.8 MILES NNW OF SITE DR-08 INDICATOR SITE BOUNDARY 0.25 MILES SSW OF SITE 0

0 0

0 DIRECT RADIATION TLD-QUARTERLY (MILLI-ROENTGEN/STD.MO.

159 N/A 6.5 (151/151)

(4.9/8.55) 39 FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

Environmental TLD Data 2004 Radiological Environmental Operating Report Vermont Yankee Nuclear Power Station, Vernon, Vermont Tables:

5.2 - Data Summary 5.3 - Measurements 40

TABLE 5.2 ENVIRONMENTAL TLD DATA

SUMMARY

VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY - DECEMBER 2004)

INNER RING TLD MEAN' RANGE' (NO. MEASUREMENTS)-

OUTER RING TLD MEAN' RANGE' (NO. MEASUREMENTS)-

OFFSITE STATION WITH HIGHEST MEAN STA.NO MEAN' RANGE' (NO. MEASUREMENTS)*

CONTROL TLDs MEAN*

RANGE-(NO. MEASUREMENTS)-

6.4 5.7 i

0.4 7.2 84 6.5

+/-

0.6 5.3 7.4 64 DR-36 7.4

+/- 0.8 6.6 8.6 4

6.2 +/- 0.37 5.9 6.5 8

SITE BOUNDARY TLD WITH HIGHEST MEAN STA.NO. MEAN' RANGE' (NO. MEASUREMENTS)*

DR-45 13.9+/-3 11.45 -18.2 4

SITE BOUNDARY TLD MEAN' RANGE-(NO. MEASUREMENTS)-

8.0

+/-

1.9 6.2 13.9 56 Units are in micro-R per hour.

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

41

TABLE 5.3 ENVIRONMENTAL TLD MEASUREMENTS 2004 (Mlcro-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 5.73

+/-

0.27 5.38

+/-

0.35 6.41

+/-

0.35 6.08

+/-

0.24 5.9 DR-02 N Hinsdale. NH 5.95

+/-

0.31 5.96

+/-

0.34 6.93

+/-

0.32 6.79

+/-

0.31 6.4 DR-03 Hinsdale Substation 6.75

+/-

0.36 6.84

+/-

0.36 7.57

+/-

0.29 7.38

+/-

0.32 7.1 DR-04 Northfield. MA 5.65

+/-

0.38 5.55

+/-

0.30 6.46

+/-

0.35 6.09

+/-

0.36 5.9 DR-05 Spofford Lake, NH 6.13

+/-

0.35 6.13

+/-

0.38 6.92

+/-

0.51 6.67

+/-

0.34 6.5 DR-06 Vernon School 6.08

+/-

0.48 5.96

+/-

0.41 6.96

+/-

0.28 6.51

+/-

0.27 6.4 DR-07 Site Boundary 6.90

+/-

0.33 6.68

+/-

0.41 8.25

+/-

0.45 7.77

+/-

0.41 7.4 DR-08 Site Boundary 7.74

+/-

0.57 6.82

+/-

0.39 8.09

+/-

0.37 8.08

+/-

0.46 7.7 DR-09 Inner Ring 5.88

+/-

0.42 5.53

+/-

0.42 6.22

+/-

0.35 5.84

+/-

0.33 5.9 DR-10 Outer Ring 5.26

+/-

0.28 4.90

+/-

0.30 5.55

+/-

0.24 5.42

+/-

0.38 5.3 DR-11I Inner Ring 5.45

+/-

0.30 5.37

+/-

0.32 6.05

+/-

0.27 6.04

+/-

0.24 5.7 DR-12 Outer Ring 5.33

+/-

0.40 5.22

+/-

0.32 5.99

+/-

0.30 5.89

+/-

0.37 5.6 DR-13 Inner Ring 5.93

+/-

0.47 5.76

+/-

0.42 6.55

+/-

0.27 6.50

+/-

0.30 6.2 DR-14 Outer Ring 6.70

+/-

0.38 6.98

+/-

0.40 7.65

+/-

0.36 7.52

+/-

0.34 7.2 DR-15 Inner Ring 6.38

+/-

0.57 6.14

+/-

0.38 6.85

+/-

0.39 6.85

+/-

0.38 6.6 DR-16 Outer Ring 6.92

+/-

0.44 6.36

+/-

0.38 7.24

+/-

0.41 7.31

+/-

0.44 7.0 DR-17 Inner Ring

0

+/-

0.00 5.60

+/-

0.39 6.46

+/-

0.39 6.22

+/-

0.34 6.1 DR-18 Outer Ring 5.97

+/-

0.38 5.99

+/-

0.34 7.38

+/-

0.32 6.81

+/-

0.42 6.5 DR-19 Inner Ring 7.23

+/-

0.83 6.93

+/-

0.36 7.23

+/-

0.43 7.31

+/-

0.55 7.2 DR-20 Outer Ring 6.59

+/-

0.33 6.83

+/-

0.40 7.37

+/-

0.46 7.32

+/-

0.38 7.0 DR-21 Inner Ring 5.73

+/-

0.41 6.12

+/-

0.34 7.01

+/-

0.59 6.60

+/-

0.35 6.4 DR-22 Outer Ring 6.20

+/-

0.30 5.87

+/-

0.32 7.06

+/-

0.29 6.88

+/-

0.37 6.5 DR-23 Inner Ring 6.00

+/-

0.30 5.64

+/-

0.31 6.54

+/-

0.26 6.04

+/-

0.39 6.1 DR-24 Outer Ring 5.53

+/-

0.41 5.24

+/-

0.32 6.31

+/-

0.42 5.67

+/-

0.34 5.7 DR-25 Inner Ring 6.09

+/-

0.52 5.95

+/-

0.37 6.80

+/-

0.38 6.50

+/-

0.34 6.3 DR-26 Outer Ring 5.75

+/-

0.35 6.30

+/-

0.44 7.31

+/-

0.46 6.85

+/-

0.32 6.6 DR-27 Inner Ring 5.72

+/-

0.35 6.20

+/-

0.42 7.13

+/-

0.43 6.40

+/-

0.52 6.4 DR-28 Outer Ring 5.82

+/-

0.38 5.93

+/-

0.35 6.94

+/-

0.48 6.17

+/-

0.44 6.2 DR-29 Inner Ring 6.09

+/-

0.37 6.40

+/-

0.41 7.56

+/-

0.46 6.90

+/-

0.43 6.7 DR-30 Outer Ring 5.62

+/-

0.34 5.88

+/-

0.41 7.01

+/-

0.39 6.33

+/-

0.54 6.2 DR-31 Inner Ring 5.87

+/-

0.38 6.44

+/-

0.54 7.09

+/-

0.29 6.66

+/-

0.54 6.5 DR-32 Outer Ring 5.58

+/-

0.38 5.65

+/-

0.32 6.88

+/-

0.37 6.30

+/-

0.30 6.1 DR-33 Inner Ring 6.18

+/-

0.37 6.14

+/-

0.34 7.23

+/-

0.33 6.82

+/-

0.35 6.6 DR-34 Outer Ring 5.75

+/-

0.35 627

+/-

0.38 7.08

+/-

0.53 6.83

+/-

0.53 6.5 DR-35 Inner Ring 6.09

+/-

0.31 6.08

+/-

0.36 6.84

+/-

0.51 6.42

+/-

0.33 6.4 DR-36 Outer Ring 6.63

+/-

0.30 6.98

+/-

0.42 8.55 5 0.87 7.61

+/-

0.31 7.4 DR-37 Inner Ring 5.32

+/-

0.38 5.99

+/-

0.33 7.03

+/-

0.29 6.58

+/-

0.41 6.2 DR-38 Outer Ring 6.42 0.35 6.65

+/-

0.48. 7.61

+/-

0.29 7.26

+/-

0.39 7.0 DR-39 Inner Ring 5.99

+/-

0.36 6.17

+/-

0.44 7.08

+/-

0.39 6.86

+/-

0.26 6.5 DR-40 Outer Ring 6.21

+/-

0.35 6.08

+/-

0.43 7.14

+/-

0.31 6.76

+/-

0.25 6.6

- TLD missing 42

TABLE 5.3 (cont.)

ENVIRONMENTAL TLD MEASUREMENTS 2004 (Micro-R per Hour)

Sta.

No.

Description 1ST QUARTER EXP.

S.D.

2ND QUARTER EXP.

S.D.

3RD QUARTER EXP.

S.D.

4TH QUARTER EXP.

S.D.

ANNUAL AVE.

EXP.

DR-41 Site Boundary DR-42 Site Boundary DR-43 Site Boundary DR-44 Site Boundary DR-45 Site Boundary DR-46 Site Boundary DR-47 Site Boundary DR-48 Site Boundary DR-49 Site Boundary DR-50 Governor Hunt House DR-51 Site Boundary DR-52 Site Boundary DR-53 Site Boundary 6.18 5.66

+/-

6.28

+/-

8.47

+/-

12.29 7.95

+/-

6.60

+/-

5.55

+/-

5.65

+/-

6.21

+/-

6.47

+/-

7.88

+/-

0.45 0.33 0.35 0.54 1.50 0.73 0.51 0.38 0.42 0.51 0.42 0.41 6.60 6.10

+/-

6.61

+/-

6.38

+/-

11.45

+/-

7.83

+/-

6.96

+/-

6.45

+/-

5.65

+/-

6.22

+/-

7.01

+/-

7.27

+/-

0.39 0.42 0.39 0.34 0.88 0.48 0.39 0.42 0.31 0.37 0.38 0.44 7.99

+/-

7.22

+/-

7.63

+/-

8.65

+/-

13.75

+/-

9.56

+/-

8.36

+/-

7.43

+/-

6.80

+/-

7.64

+/-

8.55

+/-

9.48

+/-

0.27 0.33 0.39 0.32 0.77 0.40 0.39 0.40 0.27 0.44 0.41 0.45 8.73

+/-

6.77

+/-

7.56

+/-

8.56

+/-

18.20

+/-

9.16

+/-

8.07

+/-

6.97

+/-

6.51

+/-

7.22

+/-

8.04

+/-

8.81

+/-

0.39 0.38 0.28 0.55 1.58 0.45 0.44 0.48 0.31 0.43 0.49 0.71 7.4 6.4 7.0 8.0 13.9 8.6 7.5 6.6 6.2 6.8 7.5 8.4 8.90

+/-

0.73 7.76

+/-

0.45 10.12

+/-

0.46 9.44

+/-

0.47 9.1 43

6.

ANALYSIS OF ENVIRONMENTAL RESULTS 6.1 Sampling Program Deviations Off-site Dose Calculation Manual Table 3.5.1, Note a., allows for deviations "...if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons." In 2004, five 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 monitoring program. The specific deviations for 2004 were:

a) Failure of the water pump supplying river water to the Downstream River Station River Water Composite sampler (Station #WR-1 1). The pump was discovered to be out of service on January 6 h, 2004 and was replaced and restored to service on February 17, 2004. During the period that the pump was out of service, compensatory river water samples were collected on a daily basis and utilized as part of the monthly composite sample from this station. This failure was documented in CR-VTY-2004-00045 and LO-VTYLO-2004-00123, CA#01.

b) Failure of an air sample station to collect required air samples at Station AP/CF 13 was discovered during the weekly air sample collection on August 171, 2004. The air sample station breaker had tripped. Power was lost for approximately 116 hours0.00134 days 0.0322 hours 1.917989e-4 weeks 4.4138e-5 months during the previous weekly sample collection period. This breaker trip appeared to have occurred during a moderately severe thunderstorm and most likely was a result of a power surge to the station. The breaker was reset and the station operated normally following reset. This power outage was documented in CR-VTY-2004-02625 and LO-VTYLO-2004-00438, CA#01.

c) A slight reduction in air sample time (approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months out of the 168 hour0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months week) was noted at two environmental air sample collections stations (Station 11-South River Station, Vernon and Station 15 -Tyler Hill Road, Vernon) during the weekly sample collection on 10/26/04. A relay had failed at the Vernon Hydro Station on the evening of 10/25/04 and the entire town of Vernon was without power for approximately two hours. This event was documented in CR-VTY-2004-03276, CA #01 and LO-VTYLO-2004-00570, CA#01.

d) A slight reduction in air sample time (approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months out of the 168 hour0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months week) was noted at two environmental air sample collections stations (Station 12-North Hinsdale and Station 13 -

Hinsdale Substation) during the weekly sample collection on 11/30/04. Transmission equipment problems at the Chestnut Street Substation in Hinsdale NH had occurred on November 2 8%, 2004 resulting in power loss for a section of Hinsdale New Hampshire including the two air sample stations. This event was documented in CR-VTY-2004-03589, CA #01 and LO-VTYLO-2004-00621, CA#01.

e) The water pump supplying river water to the Downstream River Station River Water Composite sampler (Station #WR-I 1) was discovered to be out of service on December 7%, 2004 and was restored to service on December 9%, 2004. During the period that the pump was out of service, compensatory river water samples were collected on a daily basis and utilized as part of the monthly composite sample from this station. This failure was documented in CR-VTY-2004-03653 and LO-VTYLO-2004-00665, CA#01 44

f) The following data indicates the percentage of time that each air sampling station operated during year 2004. The data was based on a comparison of the readings from an electric timer at each station and the clock time of sample collection. This data indicates that any power interruptions did not result in a significant loss of data for the airborne contaminant sampling program. Third quarter performance of Station 13 was impacted by a breaker trip as referenced in Section 6.1.b) above.

Fourth quarter performance of Stations 11, 15, 12 and 13 were affected by short outages as described in Sections 6.1.c and 6.1.d above. These outages are reflected in the percentages listed below.

AP/CF #

1" Quarter 2 nd Quarter 3rd Quarter 4th Quarter 1 1 100%

100%

99.9%

12 100%

100%

99.9%

13 100%

100%

94.7%

99.9%

14 100%

100%

15 100%

100%

99.9%

21 100%

100%

40 100%

100%

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 aposteriori (after the fact) LLD calculated for that analysis was compared with the required LLD. During 2004, all sample analyses performed for the REMP program achieved an aposteriori LLD 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.

45

Environmental concentrations are averaged over the calendar quarters for the purposes of this comparison. The Reporting Levels are intended to apply only to measured levels of radioactivity due to plant effluents. During 2004, 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 2004.

This year Vermont Yankee is continuing to add data from the on-site air sampling station, AP/CF 40, at the Governor Hunt House. This location has been used continuously as a demonstration since early in the program, but the data had not previously been included in this report.

6.5 Data Analysis by Media Type The 2004 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, we had converted values that were less than the MDC 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. This is the fourth year that the results for the on-site air particulate station, Gov. Hunt (AP-

40) have been included.

46

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 second quarter, and the maximum concentration in the first 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. K40 was detected on a total of I out of 28 analyzed.

6.5.1.2 Charcoal Cartridges (CF)

Charcoal cartridges from each of the seven air sampling sites were analyzed for I-1 31 each time they were collected. The results of these analyses are summarized in Table 5.1. As in previous years, no I-131 was detected.in any charcoal cartridge. This is the fourth year that the results for the on-site air iodine sampling station, Governor Hunt House (CF40) have been included.

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-1 1, 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-1 I were collected monthly and sent along with the WR-21 grab samples to the contracted environmental laboratory for analysis. Table 5.1 shows that gross-beta measurements were 47

positive in five out of 12 indicator samples and six 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 2004.

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.

6.5.2.2 Ground 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 2004. WG-13 (COB Well), an on-site well location, has been routinely sampled since the second half of 1996. In 1999, WG-14 (PBS Well) another on-site well location was added to the program. Table 5.1 and Figure 6.9 show that gross-beta measurements were positive in 16 out of 16 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-11, were consistent with those detected in previous years. Naturally occurring Ra-226 was also detected in four 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 2004. 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 2004, 15 locations were sampled at SE-12 during each of the semi-annual collections. Two samples were collected at SE-I during the year. Be-7 was detected in 5 of 32 samples analyzed. As would be expected, naturally-occurring Potassium-40 (K-40) was detected in all of the samples. Radium-226 (Ra-226) was detected in 23 of 32 samples. Thorium-228 (Th-228) was detected in 31 of 32 samples analyzed. Thorium-232 (Th-232) was detected in 32 samples analyzed. Cesium-137 (Cs-137) was detected in 25 out of 30 of the indicator samples and one out of two control samples. The levels of Cs-137 measured at both locations were consistent with what has been measured in the previous several years and with those detected at other New England locations. Cobalt-60 (Co-60) was not detected this year. Other plant-related radionuclides are reported in trace quantities in Table 5.1 SE. Also see section 6.5.2.6 for more information.

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 2004. The test well 48

locations are shown on Figure 4.1 and the results are summarized in Table 5.1 under the media category, Test Well (WT). In 2004, two 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 8 samples collected with levels ranging from 8 to 42 pCi/kg. K-40 was also detected in I of the 8 samples. No other radionuclides were detected.

6.5.2.5 Storm Drain System The presence of plant-related 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 I&E 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 2004 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 2004 for a total of 16 samples. All samples were analyzed for gamma emitting isotopes. Table 6-1 summarizes the analytical results of the sediment samples. Naturally occurring isotopes K-40, Th-228, Th-232, Ra-226, and Be-7 were found in most of the 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.

Water samples were taken from the storm drain system at various access points in 2004 including Manholes MH-8, MH-I IH, MH-12A, MH-13, and MH-14. Table 6-2 summarizes the analytical results of water samples from the storm drain system in 2004. Nb-95 was detected in trace amounts in just two of the samples. Naturally-occurring Th-232 was detected in two of the samples. Low levels of gross beta activity were detected in 23 out of 26 samples analyzed at concentrations that are typical of any environmental water sample. Tritium (H-3) was detected in only one of the 26 samples analyzed at a very low level of activity.

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 49

are estimates of the total body aind 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 2004 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.

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 Be-7 16/16 9.8 E 2 (0.51 - 2.02) E 3 MH-12A (SE-92)

K-40 16/16 1.1 E4 (0.93 - 1.32) E 4 MH-12A (SE-92)

Th-232 16/16 5.6 E 2 (4.56 - 6.33) E 2 MH-12A (SE-92)

Th-228 15/16 1.7 E 3 (0.83 - 2.27) E 3 MH-12A (SE-92)

Mn-54 0/16 3.4 E 0.

NA MH-12A (SE-92)

Ra-226 8/16 1.2 E 3 (0.98 - 1.43) E 3 MH-12A (SE-92)

Cs-134 0116 2.6 E 0 NA MH-12A (SE-92)

Cs-137 9/16 1.2 E 2 (0.17 - 3.01) E 2 MH-12 (SE-95)

Zn-65 0/16 2.5 E 0 NA MH-12A (SE-92)

Ag-I lOIm 0116 1.7 E 0 NA MH-12A (SE-92)

Ac-228 15/16 9.5 E 2 (0.65 - 1.32) E 3 MH-12A (SE-92)

Ce-144 0/16 8.8 E 0 NA MH-12A (SE-92)

Nb-95 0/16 1.7 E 1 NA MH-12A (SE-92)

Co-60 3/16 2.8 E2 (1.82-4.42)E2 MH-12 (SE-95)

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.

50

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 Be-7 0/26 1.9 E 0 NA MH-14 (WW-10)

Gross Beta 23/26 6.3 E 0 (0.33 -3.01) E I MH-12A (WW-12)

Cs-134 0/26

-1.5 E 0 NA MH-14 (WW-10)

Cs-137 0/26 1.2 E-1 NA MH-12A (WW-12)

K-40 2/26 3.7 E 2 NA MH-14 (WW-10)

Mo-99 0/26 7.1 E 0 NA MH-14 (WW-I0)

Nb-95 0/26 3.3 E-2 NA MH-12A (WW-12)

Ra-226 0/26

-8.7 E 0 NA MH-12A (WW-12)

Th-232 0/26

-9.6 E-1 NA MH-14 (WW-10)

H-3 1/26 2.6 E 2 NA MH-14 (WW-10)

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 I OCFR50.75(g) and is presented here in response to ER_95-0704_04 commitments.

Table 63 Summary of Air Compressor Condensate and Manhole Water Tritium Concentrations*

Sample No.

Mean Range Location Detected**

(microcuries/ml)

(microcuries/mi)

Air Compressor Condensate 8/8 4.13E-5 (0..02-1.04) E-4 Manhole l lH 6/13 3.20E-6 (0.07 - 1.80) E-5 Manhole 13 8/15 5.49E-6 (0.07 - 1.80) E-5 Manhole 8 1/12 7.56E-7 (0..69 - 1.60) E-6 Manhole 14 0/51 None Detected None Detected Reported per ER 950704_04.

- The fraction of sample analyses yielding detectable measurements 51

6.53 Ingestion Pathways 6.53.1 Milk (TIM)

Milk samples from cows or goats at several local farms were collected monthly during 2004. 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 13 out of 20 indicator samples and 4 out of 4 control samples. Although Sr-90 is a by-product of nuclear power plant operations, the levels detected in milk are consistent with that expected 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 detected in 3 of 106 samples in 2004. 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.

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 1-13 1. As expected with all biological media, naturally-occurring K-40 was detected in all samples. Naturally-occurring Be-7 was also detected in 3 of the 5 samples. Cs-137 was not detected in any of the five samples. No I-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 on three occasions during 2004.

As expected with all biological media, naturally-occurring K40 and Be-7 were detected in all samples.

Naturally-occuring Ac-228 was detected in one sample.

52

Cs-137 was detected in I of the 21 stations, although at extremely low levels. The required LLD for this Cs-137 in this sample type is 80 pCi/kg and the highest measurement was 68 pCi/kg. Although not common, Cs-137 has been detected in mixed grass samples occasionally. It is likely that it is present in a small amount of soil that was attached to the grass samples.

6.5.3.4 Fish (Fil)

Semiannual samples of fish were collected from two locations in the Spring and Fall of 2004. 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 samples.

As shown in Table 5.1, Cs-137 was not detected in this year's samples. It should be noted that most 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 2004 and previous years are typical of concentrations attributable to global nuclear weapons testing fallout.

No other radionuclides were detected.

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). One exception to this program occurred in year 2004.

A TLD was missing from Station DR-17 at the end of the first quarter and another TLD, DR-36, was found to be missing at the end of the fourth quarter. These events are further described in Section 6.1.

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 2004. 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 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 53

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.

Upon examining Figure 6.17, as well as Table 5.2, it is evident that in recent years, station DR45 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 DR46, which has shown higher exposure rates in previous years.

54

Environmental Program Trend Graphs 2004 Radiological Environmental Operating Report Vermont Yankee Nuclear Power Station, Vernon, Vermont 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-1 37 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, DRO1-03 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 55

Figure 6.1 - Gross Beta Measurements on Air Particulate Filters

- Quarterly Average Figure 6.1 - Gross Beta Measurements on Air Particulate Filters - Quarterly Average Concentrations A

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Figure 6.2 - Gross Beta Measurements on Air Particulate Fitters 0.03 0.025 0.02 0.015 0.0 0.005 2004 Week Number I -~04-AP Ai Rvr StIn I~P2 pfodtaeH 57

Figure 6.3 - Gross Beta Measurements on Air Particulate Filters 0.03 0.025 0.02 5> 0.015 A.

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59

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a.

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C) -

10 W.% CMOsX O

2004 Week N e r X

O v M X K

X N

O 2004 Week Number

--- :0AP-14 Norhlk MS

-*AP2 Spffw Lak NHti 60

Figure 6.6 - Gross Beta Measurements on Air Particulate Filters 0.03 0.025 0.02 0.

E U

C) 0.01 0.005 0

2004 Week Number

[I -AP-1 TyerHIR Rod

-*-AP-21 Spofford Lake NH 61 c-OG

Figure 6.7 - Gross Beta Measurements of Air Particulate Filters 0.03 0.025 0.02 8 0.015 IU U

0.01 0.005 0

)C)--M0 400 C

rj N

.IW.

.II 1

2004 Week Number j

7 r

7 5

I IAP0 Governor 6ffOr ouse.

IAP2 Sp?4rdL 4

N 62

Figure 6.8 - Gross Beta Measurements on River Water Semi-Annual Average Concentration 4

3.5 3

2.5 Ib-0CJ

U v.

2 7777777

I 1.5 1

0.5 0

1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 Year r= WR-ie tto 33

-W

-1R9B~g 3

63 CONc

Figure 6.9 - Gross Beta Measurements on Ground Water Semi-Annual Average Concentrations 10.0 9.0 8.0 6.0 I.0 0.

4.0 3.0 2.0

-.0 1 0.0 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 Year WG-1 PW eW En 64

Figure 6.10 - Cesium 137 in Milk - Annual Average Concentration 5.0 4.5 4.0 -

3.5 3.0-

~2.5 2.0 1.5 1.0 0.5 0.0 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 Year iX Z.E.g.$.

A C0,

f. St:. SE. i. - - ;TM -

Brow (v

o;;w, }-, ; SS: 5 SX

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-. P 4 2

- T M 4

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,0

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0 d C h n e j m 65

Figure 6.11 - Strontium 90 in Milk - Annual Averge Concentrations 4.0 - _

3.5 ~-

3.0-2.5 I.,

0.

1.02 0

0.5 -

0.0 -

1992

-- TII tMIWsr

-*-TM-2 Frnk 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 Year

-*To4 rw 0;-0:0$;;_1(Cow) 00000 TM-0118} 8bddtm(cow)

-*-TM2406ury ar (c0o) hin Farm(ow 4 TM2 DA ny-pftc (g0t

+2-T-6 Ago~

KI Ji2;505 0 ; 00$9 0t

i0;-00Q 66 C II

Figure 6.12 - Cesium 137 in Fish -Annual Average Concentrations 40.0 35.0 30.0 25.0 20.0 15.0 10.0 5.0 0.0 is 4 ;A tubes N

Y77%2 NX j

192 1993 1994 1995 1996 1997 1998 1999 2000 2001 Year 2002 2003 2004

FH-11 I e n n P n

-U 2

9 B g ( Control

_.. L X,

E X:

67 Cvz

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

7.0 6.5 4 0

U.

= 6.0

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4.5 -

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68

Figure 6.14 - Exposure Rate at Indicator TLDs, DROI-03 9.0 iI 8.5 8.0 7.5 S 7.0 0

.5 0

m 6.5 2

0I 6.0 5.5 5.0 4.5 e

IX I

4.0 1995 1996 1997 1998 1999 2000 Retrieval Date 2001 2002 2003 2004 2005 L: --

i Rlive Stat hilon N. 33

-- r-NorthHl~nsdOOe, rN D R -: 3 H l n da l ~

i s uit a ti 5 \\

E

?

69 C1 (A

Figure 6.15 - Exposure Rate at Indicator TLDs, DR06 & DR-50 8.0 7.5 7.0

, 6.5 0

S a 6.0 m

E 5.5 5.0 4.5 41 I

4.0 1995 1996 1997 1998 1999 2000 Retrieval Date 2001 2002 2003 2004 2005

[I D "-0 Veo n A

- U - D R -6 0 G v H t o u s e 70 c5

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

IL

.*[

,V,

, I X

,w 8.5 8

7.5 so7 0

= 6.5 0

JL

-77

,4

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=-

20 2003 I

I 1995 1996 1997 1998 1999 2000 Retrieval Date 2001 2002 2004 2005

-AdR 0Boundary'I St o

I

0*:

O :a r OR-41 Site Boundar I * -D-I Ste8o nd1 71 CJ&

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

12-9 8

7 5

4-1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005

____Retrieval Date 72

Figure 6.18 - Exposure Rate at Site Boundary TLDs DR47-49 & 51-53 11 10 9

h..

0 00.

0 h.0 8

7 6

5 4

1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 Retrieval Date 2005

_1t B-o ncarn but

_f r

In In e Zi 7

=

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Figure 6.19 - Exposure Rate at Inner Ring TLDs DRO9, 11, 13 & 15 9

8 To 7 0

2bi 16 5

4 - 777--

tz

N6 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 Retrieval Date 77

~

.7 E

4 4 e..

.. S, U A:: < 7:,.,V ^r.,

I:^

) S

~ ~

P I Ineroiny DR-3 n**r in

-*(--

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74

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

8 z7 a

j6 5

1 t

t :,

:4

,

i

'

m

o

4

,

I I , 4

4

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1.

,

I

11 I I

I 4

1995 1996 1997 1998 1999 2000 Retrieval Date 2001 2002 2003 2004 2005

-+-0R47 Inner Ring 777777777777-7'7777 ----------

I I

I I I

I

-U-DR1049inner Ring

t., InerRifng; I I 0

DR-nn rR n

=. _

L C

3 75 C, --, (

Figure 6.21 - Exposure Rate at Inner Ring TLDs DR25, 27, 29 & 31 9

8.5 8

7.5

1.

7 a2

.2 I

6 5.5 5

4.5 4

1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 Retrieval Date 2005 L -14 W WI2 I n Rng i *s-Df27 er R:ing DII'R-l Inne:ARi D31 Inner tRing]X 76 C-Z}

Figure 6.22 - Exposure Rate at Inner Ring TLI~s DR33, 35, 37 & 39 9

8.5 8

7.5 1777-11 I I I

- I -

I I 1

11

;, I, ' I I I I ,

4 4

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77~I 1995 1996 1997 1998 1999 2000 Retrieval Date 2001 2002 2003 2004 2005 DI-33 Inner Ring

-U-DR3 Ine Rn DR-3' I*erRin R3 inrRn 77

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

8.5 8

7.5 I-;

7 a

I-0a 6.5 h.0 6

5.5 5

4.5 4 -k-1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 Retrieval Date 2005

_ D R-1 so ter Rs ng U DR=12 O0 e Ringu DR-.14 Outer Rin DR-1 Outer 78 C'_b3

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

8.5 8

7.5 L-T 7

0X I.

i 6.5 1

6

'ZX T7. 1 r77IW77r'!

IL j

,j I

5.5 5

4.5 4

I I

1995 1996 1997 1998 1999 2000 Retrieval Date 2001 2002 2003 2004 2005

--- D R 1 8 O u e Ri g-D R 2 0 O u erR ing D R -22 O uter Ri ng -*-

R -2 O ut r in

\\E L..I 79 C-Z5

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

8.5 8

7.5 ~77 6.5 6-5.5 5

4.5 4

1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 Retrieval Date 8-OR2 Oue Rin

~-D-8OtrRn R3 utr~n R

OtrRn 80

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

8.5 8

I-o 7.5 0C 7

I-e

.o 6.5 6

5.5 5

4.5

-77777777

0 Er 2777 I

I I

I 1995 1996 1997 1998 1999 2000 Retrieval Date 2001 2002 2003 2004 2005

,,..,Outer Rin O:ts Ring~w.,

-, 0; f :

DR 3 Oue Rin

7) 4

_ue

_igj 81 CZ&

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

8.5

I I I

I I

Z , m I I I I I I

8 7.5 7

0 I-6.5 0

N.

6 5.5 5

4.5

77

-LLLL

L 777 I

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Y:- ,

1995 1996 1997 1998 1999 2000 Retrieval Date 2001 2002 2003 2004 2005 I

-- DR-04 Northfie MA viewDR-0 ofrdV~w t INH

_- -j 82 cz7

7 QUALITY ASSURANCE PROGRAM 7.1 Framatome ANP Environmental Laboratory (E-LAB) - Environmental TLD Quality Assurance Program Routine quality control (QC) testing was performed for each type of dosimeter issued by the Framatome ANP E-LAB Dosimetry Services Section. The dosimeter types included Panasonic 808 and 814 whole body dosimeters, combination 808/814 neutron dosimeters, extremity dosimeters and Panasonic environmental dosimeters. QC dosimeters were irradiated in-house as well as by a third party. All testing methods used by the accredited third-party tester conform to ANSIN13.11-2001 orANSIN13.32-1995.

Performance documentation of the routine processing of the Panasonic environmental TLDs (thermoluminescent dosimeter) program at the Framatome ANP E-LAB Dosimetry Services Section is provided by the dosimetry quality assurance testing program. This program includes the National Voluntary Laboratory Accreditation Program, independent third party performance testing by Battelle Pacific Northwest Labs and internal performance testing conducted by the Laboratory QA Officer. Under these programs, dosimeters are irradiated to ANSI specified testing criteria and submitted for processing to the Dosimetry Services Group as "unknowns".

The bias and precision of TLD processing is measured against this standard and is used to indicate trends and changes in performance. Instrumentation checks, although routinely performed by the Dosimetry Services Section and representing between 5-10% of the TLDs processed, are not presented in this report because they do not represent a true process check sample since the doses are known to the processor.

Ninety performance tests were conducted in 2004 by Framatome ANP E-LAB Dosimetry Services Section and the third party tester. Of these, 100% of the dosimeter evaluations met the acceptance criteria for bias (+/- 20.1%) and precision (+/-12.8%). Third Party QC results are summarized below.

Dosimeter Type Number Free in Air Tested

% passed bias criteria

% passed precision criteria Panasonic Environmental 90 100 100 Summary of Third Party Testing Dosimeter Type Exposure Period ANSI Category

% (Bias + SD)

Panasonic Environmental Q4/2003 II, high energy 4.2 + 0.8 Panasonic Environmental Q1/2004 II, high energy

-0.3 + 1.0 Panasonic Environmental Q2/2004 II, high energy 2.8 1 1.4 Panasonic Environmental Q3f2004 II, high energy 1.6 h 0.3 American National Standards Institute (ANSI) Performance Statistic as referenced in the Dosimetry Services Semi-Annual QA Status Report.

Note: Results are expressed as the delivered exposure for environmental TLD. ANSI HPS N13.29-1995 (Draft)

Category 11, High energy photons (Cs-137 or Co-60).

83

7.2 Teledyne Brown Engineering Laboratory -Environmental Services (TBE-SE) 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 (I OCFR 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) Environmental Measurements Laboratory (EML) and the 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. TBE-ES also participates in the New York State Department of Health Environmental Laboratory Approval Program (NYELAP).

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, DOE's EML, MAPEP, and NYELAP.

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.

84

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 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 NELAC, Westinghouse, State of Tennessee, Duratek, and the Department of Energy 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-five 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 Tables 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 88 environmental analyses performed were within the acceptable criteria. In one sample, low Iron-59 activity resulted in poor accuracy. The known and found values with error bars overlap at the 95% confidence level. Analytics concurred that, with the low counts and large error associated with the measurement, the results were reasonably accurate and would not be considered a failed cross check at a ration of 1.31 for an environmental level. No further action was required.

85

7.2.2.1.3 Summary of Participation in the Department of Energy (DOE) Monitoring Programs TBE-ES participated in the EML program. During this reporting period, 13 nuclides were evaluated. All but one of the 24 environmental analyses were within acceptable criteria. In one sample, an incorrect efficiency resulted in high Gross Alpha activity. When counted with the correct efficiency based on Th-239 on a Styrofoam disk, the result of 1.16 Becquerel per filter (Bq/filter) compared well to the known activity of 1.2 Bq/filter. No further action was required.

TBE-ES participated in the semi annual Mixed Analyte Performance Evaluation Program (MAPEP) for liquid, air particulate, and soil analyses (MAPEP-00-W8).

During this reporting period, 10 nuclides were evaluated. All but one of the 31 environmental analyses performed were within the acceptable criteria. In one sample, too small an aliquot resulted in a large uncertainty and a high activity.

When reanalyzed with a larger aliquot, the result of 96.4 Becquerel per liter (Bq/L) agreed with the known activity of 82.9 BqIL. No further action was required.

7.2.2.1.5 Summary of participation in the ERA Program During this reporting period, II nuclides were analyzed under ERA criteria. All but one of the 22 environmental analytical results were acceptable. In one sample, failure to use the absorber when counting the Sr-89 mount resulted in a Sr-89 activity three times greater than the know activity. When recounted with the absorber, the correct result of 41.5 Pico Curies per Liter (pCi/L) compared well to the known activity of 45.9 pCiAL. No further action was required.

7.2.2.2 Intra-Laboratory Process Control Program The TBE-ES Laboratory's internal process control program evaluated 1899 individual samples.

7.2.2.2.1 Spikes All 811 environmental spikes were analyzed with statistically appropriate activity reported for each spike.

7.2.2.2.2 Analytical Blanks During this reporting period, all but 16 of the 811 environmental analytical blanks analyzed reported less than MDC. The activity detected for the 16 blanks is indistinguishable from natural background.

86

7.2.2.2.3 Duplicates All 277 duplicate sets analyzed were within acceptable limits.

7.2.2.2.4 Non-Conformance Reports There were 13 non-conformance reports issued for this reporting period. No ENNVY data was impacted by the non-conformance in each of these cases.

87

Table 7.2.1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE I OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b)

TBE/Analytics Evaluation (d)

March, 2004 E4128-396 Milk Sr-89 Sr-90 pCi/L pCI/L 91 13 103 12 0.88 1.08 A

A E4129-396 Milk 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCUL pCVL pCiVL pCUL pCUL pCi/L pCi/L pCVL pCi/L pCUL pCi pC!

pci pci pci pC!

pCi pci pCi 77 77 340 76 176 113 110 65 132 144 87 325 87 185 117 105 59 179 145 78 85

327 90 185 112 114 57 143 153 88 338 93 192 116 118 59 148 159 0.99 0.91 1.04 0.84 0.95 1.01 0.96 1.14 0.92 0.94 0.99 0.96 0.94 0.96 1.01 0.89 1.00 1.21 0.91 A

A A

W A

E4131-396 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 March, 2004 E4130-396 Charcoal 1-131 pCi 88 97 0.91 A

June, 2004 E4213-396 Milk Sr-89 Sr-90 pCUL 77.9 87.7 pCUL 12.0 12.7 0.89 0.95 A

A E4214-396 Milk E4216-396 AP 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCVL pCi/L pCVL pCiUL pCUL pCi/L pCU/L pCU/L pCUL pCUL pCi pc!

pC!

pci pC!

pCi pCi pCi pCi 53.7 145 212 85.2 145 45.7 68.2 44.4 102 162 116 160 68.6 108 33.1 51.1 44.0 69.1 123 58.2 157 228 101 156 46.2 70.5 44.5 99.3 172 118 172 76.3 118 39.4 53.3 33.6 75.1 130 0.92 0.92 0.93 0.84 0.93 0.99 0.97 1.00 1.03 0.94 0.98 0.93 0.90 0.92 0.84 0.96 1.31 0.92 0.95 A

A A

A N (1)

A A

88

Table 7.2.1 (cont)

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)

June, 2004 (cont.) E4215-396 Charcoal 1-131 pci 71.8 82.0 0.88 A

September, 2004 E4323-396 Milk E4324-396 Milk September,2004 E4326-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCiUL 93.9 102 pCUL 24.0 24.5 pCi/L pCUL pCUL pCVL pCUL pCUL pCiIL pCVL pCiVL pCiIL pCi pCi pci pC!

pCi pCi pcI pCi pci pCi 81.9 214 196 77.3 192 86.2 163 87.4 168 108 149 122 50.3 112 54.8 102 47.6 111 69.0 83.5 235 210 90.6 202 89.0 171 86.1 167 118 148 132 57.1 127 56.0 108.0 54.2 106 74.1 0.92 0.98 0.98 0.91 0.93 0.85 0.95 0.97 0.96 1.02 1.00 0.92 1.01 0.92 0.88 0.88 0.98 0.95 0.88 1.05 0.93 0.94 E4325-396 Charcoal 1-131 70.3 74.9 October, 2004 E4407-396 Milk Sr-89 Sr-90 pCVL 91.7 98.6 pC11L 11.9 11.3 0.93 1.05 A

A E4408-396 Milk 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCUL pCUL pC&L pCU/L pCUL pCUL pCiUL pCiUL pCU/L pCU/L 58.3 140 374 143 120 140 135 124 198 166 66.7 155 379 170 126 146 136 121 196 175 0.87 0.91 0.99 0.84 0.95 0.96 1.00 1.02 1.01 0.95 A

A A

A 89

Table 7.2.1 (cont)

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a) Value (b)

TBE/Analytics Evaluation (d)

October, 2004 (cont.)

E4410-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi pCi 77.0 156 76.6 58.9 68.6 63.2 65.2 99.7 80.1 79.1 187 83.5 62.0 71.8 66.7 59.7 96.3 85.9 0.97 0.84 0.92 0.95 0.96 0.95 1.09 1.04 0.93 A

A A

E4409A-396 Charcoal 1-131 pCi 80.9 83.3 0.97 A

(1) The Analytics ifterhad very low activity and was counted longer then two days. This resulted In poor accuracy as demonstrated by the verylarge enrrtefm. Dan Montgomery ofAnalytics concurred that, with the low counts andlarge error, the results were reasonably accurate and wouldnot be considered a failed cross check at 1.31 foran environmentallevel sample. NCR 04-16 (a) Teledyne Brown Engineering reported result.

(b) The Analytics known value Is equal to 100% of the parameter present In the standard as determined by gravimetric and/or volumetric measurements made during standardpreparation.

(c) Ratio of Teledyne Brown Engineering to Analytics results.

(d) Analytics evaluation based on TBE internal QC limits: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20.

W-Acceptable with waming. Reported result falls within 0.70-0.80 or 1.20-1.30. N = Not Acceptable. Reported result falls outside the ratio limits of c 0.70 and > 1.30.

90

Table 7.2.2 DOE/EML ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

Identification Reported Known Ratio (c)

Month/Year Number Media Nuclide Units Value (a) Value (b)

TBE/EML Evaluation (d)

March, 2004 (2)

QAP 60 (QAP 0403)

AP Co-60 Sr-90 Cs-1 34 Cs-137 Gr-A Gr-B Soil K-40 Sr-90 Cs-137 Bi-212 Pb-212 Bi-214 Pb-214 Ac-228 Th-234 Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/kg Bqlkg Bq/lkg Bq/kg Bq/kg Bqlkg Bqlkg Bq/kg Bq/kg 33.5 1.8 18.7 24.8 1.8 2.88 583 42.1 1429 52.6 50.1 57.6 61.4 49.4 114.9 35.4 1.76 18.2 26.4 1.2 2.85 539 51.0 1323 50.43 47.73 58.4 61.0 49.0 84.0 1.08 0.83 1.08 1.04 1.05 0.99 1.01 1.01 1.37 A

A A

0.95 1.02 1.03 0.94 1.50 1.01 A

A A

A N (1)

A Vegetation K-40 Bq/kg 807.5 720.0 1.12 Co-60 Bq/kg 14.2 14.47 0.98 Sr-90 Bq/kg 685 734.0 0.93 Cs-1 37 Bq/kg 637.3 584.67 1.09 Water Co-60 BqIL 159.7 163.2 0.98 Sr-90 Bq/L 4.74 4.76 1.00 Cs-137 BqtL 50.6 51.95 0.97 Gr-A Bq/L 394.0 326.0 1.21 Gr-B Bq/L 1200.0 1170.0 1.03 (1) Incorrect efficiency used vhen recalculated with the correct efficiency, the Gross Alpha activity of 1. 16 Bqilter compared well with the value of 1.2 Bqolter. NCR 04-14 (2) DOE discontinued the EML quality essessment program. MAPEP has expanded their perfomnmance test program to indude water, soil, AP and vegetation samples.

(a) Teledyne Brown Engineering reported result.

(b) The DOEIEML known value is equal to 100% of the parameterpresent In the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) Ratio of Teledyne Brown Engineering to DOEZEML results (a) DOE/EML evaluation: Azacceptable, WFacceptable with warning, N=not acceptable.

A A

A W

A 91

Table 7.2.3 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b) Control Limits Evaluation (c)

May, 2004 Rad 57 Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B H-3 pCUL pCUL pCUL pCUL pCUL pCVL pCUL pCUL pCUL pCUL 139 11.3 93.9 43.3 79.3 42.4 81.9 39.9 62.5 33500 45.9 11.6 101 50.5 82.5 41.6 75.2 38.8 59.6 30900 37.2 - 54.6 2.94 - 20.3 83.5-118 41.8-59.2 73.8-91.2 32.9 - 50.3 62.2 - 88.2 22.0 - 55.6 42.3 - 76.9 25600- 36200 N (1)

A A

A August, 2004 Rad 58 Water 1-131 pCI/L 9.09 9.29 5.83 - 12.8 December, 2004 Rad 59 Water Sr-89 Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 pCVL pCi/L pCUL pCVL pCUL pCUL pCVL pCUL pCUL pCUL pCUL 44.0 35.3 73.9 37.8 58.3 11.5 51.3 23.9 33.9 19.2 22900 45.7 36.6 78.4 42.9 60.1 11.7 50.9 31.7 36.3 22.1 20700 37.0 - 54.4 27.9 - 45.3 64.8 - 92.0 34.2 - 51.6 51.4 - 68.8 3.04 - 20.4 42.1 - 59.7 18.0 - 45.4 27.6 - 45.0 16.9 - 27.3 17100 - 24300 A

A A

A W

A A

A (1) The stronfium-89 mount was counted without the absorber. When recounted using the absorber the Sr-89 result of 41.5 pCiL agreed well with the ERA known value of 45.9 pCi/L NCR 04-13 (a) Teledyne Brown Engineering reported result.

(b) The ERA known value Is equalto 100I of the parameterpresent In the standard as determinedbygravimetric and/or volumetric measurements made during standardpreparation.

(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Umits. NA=not acceptable. Reported result falls outside of the Control Umits. CE=check for Error. Reported result falls within the Control Umits and outside of the Warning Limit.

92

Table 7.2.4 MAPEP ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE I OF 1)

I Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b)

Control Limits Evaluation (c)

January, 2004 03-Wl1 Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 289.1 118.7 164 121.1 425.3 152.6 16.4 303.3 322.0 124.0 173.0 121.8 379.0 155.0 17.7 320.0 225.40 - 418.60 86.80- 161.20 121.10 - 224.90 85.26-158.34 265.30 - 492.70 108.50 - 201.50 12.39 - 23.01 224.00 - 416.00 A

A A

A July, 2004 MaW12 Water Cs-134 Cs-137 Co-60 H-3 Mn-54 Sr-90 Zn-65 GrW12 Water Gr-A Gr-B Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 177 237 160 109 262 6.79 217 208 250 163 82.9 267 7.4 208 145.60 -270.40 175.00 - 325.00 114.10 - 211.90 58.10- 107.90 186.90 - 347.10 4.90 - 9.10 145.60 - 270.40 BqtL 0.836 1.24

>0.0 - 2.40 Bq/L 4.95 4.07 2.05 - 6.15 A

A A

N (1)

A A

A W

A A

A RdF12 GrF12 AP Cs-134 Cs-137 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 2.19 1.87 2.28 3.06 0.909 4.53 2.9 1.96 2.35 3.03 0.83 4.11 2.03 - 3.77 1.40 - 2.60 1.61 - 2.99 2.10 - 3.90 0.56-1.04 2.80 - 5.20 AP Gr-A Gr-B Bq/sample 0.126 0.37

>0.0 - 0.80 Bq/sample 1.34 1.21 0.60- 1.80 MaS12 Soil Cs-134 Cs-137 Co-60 Mn-54 K-40 Zn-65 Bq/kg Bq/kg Bqfkg Bqfkg Bq/kg Bqlkg 327.7 786.0 509.3 477 609 727 414 836 518 485 604 699 290.08 - 538.72 585.34 - 1,088 362.60 - 673.40 339.29 - 630.11 422.80 - 785.20 489.51 - 909.09 W

A A

A (1) All raw data looked normal for the sample. Evaluating the results based on the + 20 Bq/L uncertainty, the result easily overlaps the known value et the 95% confidence level The sample was rerun with a larger ariquot to Improve socuracy and lower the uncertainty.

The H-3 result of 96.4 + 7.75 Bq/ was within the acceptance range. NCR 04-19 (a) Teledyne Brown Engineering reported result.

(b) The MAPEP known value Is equal to 100Ye of the parameterpresent In the standard as determined by gravimetric and/or volumetfic measurements made during standard preparation.

(c) DOE/MAPEP evaluation: A=acceptable, W=accsptable with warning, N=not acceptable.

93

8. Land Use Census The ENNVY Off-site Dose Calculation Manual 3/4.5.2 requires that a Land Use Census be conducted annually between the dates of June I 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 DIQ value due to elevated releases from the plant stack in each of the three major meteorological sectors. The 2004 Land Use Census was conducted in the summer of 2004 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 is 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 from year 2001 occurred for the 2004 census, therefore no such revision of the 2001 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 2004 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 2004 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.

94

TABLE 8.1 2004 LAND USE CENSUS LOCATIONS*

SECTOR NEAREST RESIDENCE NEAREST MILK ANIMAL Km (Mi)

Km (Mi)

N 1.5 (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 2.8 (1.8)

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

SSE 2.1(1.3)

S 0.5 (0.3) 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) 9.6 (6.0) Goats X.

0.6(0.4) 0.8 (0.5) Cows WNW 1.1 (0.7) 7.5 (4.7) Cows NW 2.6(1.6)

NNW 2.6 (1.6)

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.

95

9.

SUMMARY

During 2004 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 800 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 ground water, 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.

Many samples (particularly milk, river water, mixed grass, and sediment) had fallout radioactivity such as Cs-137 and Sr-90 from atmospheric nuclear weapons tests conducted primarily from the late 1950s through 1980.

Several samples from onsite locations (from the plant storm drain system) had low levels of radioactivity resulting from emissions from the Vermont Yankee plant. 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.

In fact, measured values were several orders of magnitude below reportable levels listed in Table 4.5.

96

10. REFERENCES

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

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

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

4. Kathren, Ronald L., Radioactivity and the Environment - Sources, Distribution, and Suin'eillance, Harwood Academic Publishers, New York, 1984.

5. Till, John E. and Robert H. Meyer, ed., Radiological Assessment - 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 Parameters on Groundwvater Migration, February 1983.

97

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