Text

2001 Annual Radiological Environmental Operating Report
	ML021360202
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	05/14/2002
From:	Sen G; Vermont Yankee
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BVY 02-33
	Download: ML021360202 (143)
	v • d • e

VERMONT YANKEE NUCLEAR POWER CORPORATION 185 OLD FERRY ROAD, PO BOX 7002, BRA'KFLEBORO, VT 05302-7002 (802) 257-5271 May 14, 2002 BVY 02-33 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271) 2001 Annual Radiological Environmental Operatin2 Report In accordance with Vermont Yankee Technical Specification 6.6.E, attached is a copy of the 2001 Annual Radiological Environmental Operating Report. This report contains a summary and analysis of the radiological environmental data collected for the calendar year 2001.

We trust that the information provided is adequate; however, should you have questions or require additional information, please contact Mr. Sam A. Wender at (802) 258-5650.

Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION

/Gautam Sen Licensing Manager Attachment cc:

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

SUMMARY

OF VERMONT YANKEE COMMITMENTS BVY NO.: 02-33 "2001 Annual Radiological Environmental Operating Report" The following table identifies commitments made in this document by Vermont Yankee.

Any other actions discussed in the submittal represent intended or planned actions by Vermont Yankee. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Licensing Manager of any questions regarding this document or any associated commitments.

VYAPF 0058.04 AP 0058 Original Page 1 of 1 COMMITMENT COMMITTED DATE J

OR "OUTAGE" None N/A i

i

VERMONT YANKEE NUCLEAR POWER STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January - December 2001 May 2002 Prepared by:

Vermont Yankee Nuclear Power Corporation Chemistry Department

Acknowledgment Special thanks to the Vermont Yankee Public Affairs Department for the use of their original water color by William Hays of the power station as seen from the New Hampshire shore of the Connecticut River for the covers of this report.

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

60 6.1 Sampling Program Deviations.....................................................................................

60 6.2 Comparison of Achieved LLDs with Requirements...................................................

61 6.3 Comparison of Results with Reporting Levels...........................................................

62 6.4 Changes in Sampling Locations...................................................................................

63 6.5 Data Analysis by Media Type.....................................................................................

63

7.

QUALITY ASSURANCE PROGRAM....................................................................................

100 7.1 Duke Engineering and Services Laboratory (DE&S)......................................................

100 7.2 Teledyne Brown Engineering Laboratory (TBE)............................................................

108

8.

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

122

9.

SU M M A R Y..............................................................................................................................

124

10.

RE FEREN C E S..........................................................................................................................

125

11.

APPENDIX A, "Explanation of Questionable Data from Year 2000"............................ 126 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......................................................

56 5.3 Environmental TLD Measurements...................................................

58 6.1 Summary of Storm Drain System Sediment Sample Analyses.......

68 6.2 Summary of Storm Drain System Water Sample Analyses............... 68 7.1.1 DESEL Results in the Intralaboratory Process Control Program.......... 103 7.1.2 DESEL Results in the Analytics Inc. Cross Check Program................. 104 7.1.3 Summary of Blind Duplicate Samples Submitted to the DESEL.......... 107 7.2.1 TBE-ES Analytics Environmental Cross Check Program.....................

112 7.2.2 TBE-ES DOE/EML Environmental Cross Check Program............... 115 7.2.3 TBE-ES ERA Environmental Cross Check Program....................... 118 7.2.4 TBE-ES MAPEP Environmental Cross Check Program................... 119 7.2.5 TBE-ES NYELAP Cross Check Program.................................... 120 7.2.6 TBE-ES Bioassay Environmental Cross Check Program.................. 121 8.1 Land Use Census Locations...................................................................

.123 11.1 Year 2002 Questionable Data................................................... 127 11.2 Explanation of Year 2002 Questionable Data................................ 129 ii

LIST OF FIGURES Figure Title Page 4.1 Environmental Sampling Locations in Close Proximity to 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 Plant...................................................................................................

2 1 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....................................................

72 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 2001. 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 2001 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 2001 environmental TLD measurements.

Section 6: Provides the results of the 2001 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 the Duke Engineering &

Services Laboratory and Teledyne Brown Engineering Laboratory. Included are the laboratories' results of the Analytics Intercomparison Program.

Section 8: Summarizes the requirements and the results of the 2001 Land Use Census.

Section 9: Gives a summary of the 2001 Radiological Environmental Monitoring Program.

Appendix A: Provides an explanation of year 2000 Questionable Data listed in the year 2000 report.

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 Chernobyl 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 of the fallout detected today is due to this explosion and the last large scale one, done in November of 1976 (Reference 3).

The radioactivity produced by these detonations was deposited worldwide. The amount of fallout deposited in any given area is dependent on many factors, such as the explosive yield of the device, the latitude and altitude of the detonation, the season in which it occurred, and the timing of subsequent rainfall which washes fallout from the troposphere (Reference 4). Most of this fallout has decayed into stable elements, but the residual radioactivity is still readily detectable in environmental samples worldwide. The two predominant radionuclides are Cesium137 (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 land 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.

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 Vermont Yankee Nuclear Power Station (VYNPS) was designed with specific objectives in mind. These are:

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

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

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

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

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

The current program is designed to meet the intent of NRC Regulatory Guide 4.1, Programs for Monitoring 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 2001, analytical measurements of environmental samples were performed at the Duke Engineering & Services Environmental Laboratory (DESEL) and Teledyne Brown Engineering Laboratory (TBE). TLD badges are posted and retrieved by the Vermont Yankee Chemistry Department, and are analyzed by the DESEL.

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

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

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

4.3 Descriptions of Monitoring Programs 4.3.1 Air Sampling Continuous air samplers are installed at seven locations. (Five are required by the VYNPS ODCM.) The sampling pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute. Airborne particulates are collected by passing air through a 50 mm glass-fiber filter. A dry gas meter is incorporated into the sampling stream to measure the total volume of air sampled in a given interval. The entire system is housed in a weatherproof structure. The filters were collected biweekly through Week Number 40 and then increased to a weekly frequency with the collection of air samples in Week Number 41, 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 biweekly filters and 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 jtCi/sec, weekly air particulate collection 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 biweekly for 1-131.

Whenever the main plant stack effluent release rate of 1-131 is equal to or greater than 0.1 pCi/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 analyzed for gamma-emitting radionuclides. Although not required by the VYNPS ODCM, a gross-beta 7

analysis is performed on each sample. The monthly composite and grab samples are composited by location by the contracted environmental laboratory for a quarterly 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 1-131 analysis is performed to meet the Lower Limit of Detection requirements in the ODCM.

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

4.3.7 Silage 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.

4.3.10 TLD Monitoring Direct gamma radiation exposure is continuously monitored with the use of thermoluminescent dosimeters (TLDs). Specifically, Panasonic UD-801AS1 and UD-814AS1 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-screened container. This container 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 processes them.

9

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

See ODCM Table 3.5.1 for complete footnotes.

Note I - BiWeekly frequency increased to Weekly on Week Number 41 (10/02/02) 10 Collection Analysis Exposure Pathway and/or Number of Routine Collection Analysis Frequenc Sample Media Sample Sampling Frequency TypeFrequency Locations Mode Tp

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 (note 1)

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

TABLE 4.1, cont.

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

See ODCM Table 3.5.1 for complete footnotes.

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

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 1 at each milk Grab At harvest Gamma Isotopic Each sample sampling station

TABLE 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (NON-TLD) IN 2001 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Exposure Station From Plant From Pathway Code Station Description Zone(a)

Stack (km)

Plant I. Airborne AP/CF-11 River Sta. No. 3.3 I

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

3.6 NNW AP/CF-13 Hinsdale Substation I

3.1 E

AP/CF-14 Northfield, MA I

11.6 SSE AP/CF-15 Tyler Hill Road I

3.1 WNW AP/CF-21 Spofford Lake C

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

On-site

2. Waterborne

a. Surface WR-11 River Sta. No. 3.3 I

1.9 SSE WR-21 Rt.9 Bridge C

11.8 NNW

b. Ground WG-1 1 Plant Well I

0.2 On-site WG-12 Vernon Nursing Well I

2.1 SSE WG-13 COB Well I

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

On-site WT-16 Test Well 202 I

On-site WT-17 Test Well 203 1

On-site WT-18 Test Well 204 I

On-site WG-22 Skibniowsky Well C

13.7 N

c. Sediment SE-11 Shoreline Downriver I

0.6 SSE SE-12 North Storm Drain Outfall I

0.1 E

12

TABLE 4.2, cont.

RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (NON-TLD) IN 2001 VERMONT YANKEE NUCLEAR POWER STATION Exposure Pathway

3. Ingestion

a. Milk

b. Fish

c. Mixed Grass

d. Silage Station Code TM-II TM-14 TM-18 TM-22 TM-24 TM-25 TM-26 FH-11 FH-21 TG-11 TG-12 TG-13 TG-14 TG-15 TG-21 TG-40 TC-11 TC-14 TC-18 TC-22 TC-24 TC-25 TC-26 Station Description Miller Farm Brown Farm Blodgett Farm Franklin Farm County Farm Downey-Spencer Cheney Hill Farm Vernon Pond Rt.9 Bridge 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 Cheney Hill Farm Direction From Plant Zone(a)

Stack(km)

I I

C I

I I

C I

I I

C I

I I

C I

I 0.8 2.2 3.6 9.7 21.6 6.9 7.5 0.68b) 11.8 1.9 3.6 3.1 11.6 3.1 16.4 0.8 2.2 3.6 9.7 21.6 6.9 7.5 (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 Distance From Plant Stack W

S SE WSW N

W WNW SSE NNW SSE NNW E

SSE WNW NNE On-site W

S SE WSW N

W WNW

TABLE 4.3 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (TLD) IN 2001 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Station From Plant From Code Station Description Zone IM) (d)

Plan(d)

DR-I River Sta. No. 3.3 I

1.6 SSE DR-2 N. Hinsdale, NH I

3.9 NNW DR-3 Hinsdale Substation I

3.0 E

DR-4 Northfield, MA C

11.3 SSE DR-5 Spofford Lake C

16.5 NNE DR-6 Vernon School I

0.52 WSW DR-7 Site Boundaryýc)

SB 0.28 W

DR-8 Site Boundary SB 0.25 SSW DR-9 Inner Ring I

1.7 N

DR-10 Outer Ring 0

4.5 N

DR-11 Inner Ring I

1.6 NNE DR-12 Outer Ring 0

3.6 NNE DR-13 InnerRing I

1.2 NE DR-14 Outer Ring 0

3.9 NE DR-15 Inner Ring I

1.5 ENE DR-16 Outer Ring 0

2.8 ENE DR-17 Inner Ring I

1.2 E

DR-18 Outer Ring 0

3.0 E

DR-19 Inner Ring I

3.7 ESE DR-20 Outer Ring 0

5.3 ESE DR-21 Inner Ring I

1.8 SE DR-22 Outer Ring 0

3.3 SE DR-23 Inner Ring I

2.0 SSE DR-24 Outer Ring 0

3.9 SSE DR-25 Inner Ring I

1.9 S

DR-26 Outer Ring 0

3.8 S

DR-27 Inner Ring I

1.1 SSW DR-28 Outer Ring 0

2.2 SSW DR-29 Inner Ring I

0.9 SW DR-30 Outer Ring 0

2.4 SW 14

TABLE 4.3, cont.

RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (TLD) IN 2001 VERMONT YANKEE NUCLEAR POWER STATION Distance Direction Station From Plant From Code Station Description Zone(a)

(kM)(d)

Plant~d)

DR-31 Inner Ring I

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 I

1.3 WNW DR-36 Outer Ring 0

4.4 WNW DR-37 Inner Ring I

2.8 NW DR-38 Outer Ring 0

7.3 NW DR-39 Inner Ring 1

3.1 NNW DR-40 Outer Ring 0

5.0 NNW DR-41(o)

Site Boundary SB 0.38 SSW DR-42 (b)

Site Boundary SB 0.59 S

DR-43 )

Site Boundary SB 0.44 SSE DR-44(b)

Site Boundary SB 0.19 SE DR-45 ()

Site Boundary SB 0.12 NE DR-46 (b)

Site Boundary SB 0.28 NNW DR-47 o Site Boundary SB 0.50 NNW DR-48 o Site Boundary SB 0.82 NW DR-49 (b)

Site Boundary SB 0.55 WNW DR-50 (b)

Gov. Hunt House I

0.35 SSW DR-51 (b)

Site Boundary SB 0.26 W

DR-52 (b)

Site Boundary SB 0.24 SW DR-53 (b)

Site Boundary SB 0.21 WSW (a)

I = Inner Ring TLD; 0 = Outer Ring Incident Response TLD; C =Control TLD; SB = Site Boundary TLD.

(b)

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

(c)

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

(d)

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

16

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

(pCi/m 3)

(pCi/Kg)

(pCi/l)

(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/l)

(pCi/m 3)

(pCi/Kg)

(pCi/l)

(pCi/Kg)

(pCi/Kg-dry)

H-3 20,000(a)

Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 3 0 0 0 (b)

Zn-65 300 20,000 Zr-Nb-95 400 1-131 0.9 3

100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300 (a) Reporting Level for drinking water pathways. For non-drinking water, a value of 30,000 pCi/liter may be used.

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

See ODCM Table 3.5.2 for additional explanatory footnotes.

17

N..

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

KM 0

.5 1

1.5 2

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

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

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

2 Figure 4-5 TLD Locations Within 5 Km of Plant 22

Figure 4-6 TLD Locations Greater than 5 Km from the Plant 23

5. RADIOLOGICAL DATA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples that were collected during 2001. 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 2001, Vermont Yankee contracted with two laboratories for the analyses of the environmental samples.

The first laboratory was used primarily during the Is quarter. The second laboratory was used during the 2"d, 3 rd and 4 th quarters of 2001.

The left-most column of Table 5.1 contains the radionuclide of interest, the total number of analyses for that radionuclide in 2001, 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 is not met. This may be due to malfunctions in sampling equipment, which results in low sample volume or delays in analysis at the laboratory. Such cases are 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 2001 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 a posteriori LLD. In previous years, data less than the a posteriori LLD were converted to zero for purposes of reporting the means and ranges.

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

24

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

Each single radioactivity measurement datum in this report is based on a single measurement and is reported as a concentration plus or minus a one standard deviation uncertainty. The standard deviation on each measurement represents only the random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure.

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 and greater than or equal to the aposteriori LLD.

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-II Om, 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, TeI-132, Zn-65 and Zr-95.

Data from direct radiation measurements made by TLDs are provided in Table 5.2 in a format essentially the same as above. The complete listing of quarterly TLD data is provided in Table 5.3.

25

Radiological Environmental Program Summary 2001 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 (WT)

Milk (TM)

Silage (TC)

Mixed Grass (TG)

Fish (FH) 26

AP Table 5.1 Radiological Environmental Program Summary Vermont Yankee Nuclear Power Plant, Vernon, VT (January - December 2001)

Medium: Air Particulate (AP)

UNITS: pCi/cubic meter AP Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station e7

]

None Required Station Number of Analyses 28 40 Non-Routine**

0 Mean 0.1540 0.1673 0.1785 Lan aximum 0.2750 0.2750 0.2750 RangeMinimum 0.0457 0.0884 0.0820 Number Detected***

23 4

4 Total Analyzed 24 4

4 0.05 Station Number of Analyses 27 40 Non-Routine**

0 Mean

-0.0001 0.0001

-0.0003 Rageýaximum -0.0005

-0.0005

-0.0001 Range Minimum

-0.0010

-0.0002

-0.0005 Number Detected***

0 0

0 Total Analyzed 23 4

4

~ijs-37I 0.06 Station Number of Analyses 28 13 Non-Routine**

0 Mean 0.0000 0.0002 0.0001 axim um 0.0004 0.0003 0.0003 R Minimum

-0.0010 0.0001

-0.0001 Number Detected***

0 0

0 Total Analyzed 24 4

4 GRB I

0.01 Station Number of Analyses 216 11 Non-Routine**

0 Mean 0.0215 0.0427 0.0171 Imaximum 0.8093 0.8093 0.0290 Range I Minimum 0.0091 0.0096 0.0100 Number Detected***

185 31 31 Total Analyzed 185 31 31 Wednesday, May 08, 2002 Page 1 of 3 27

AP Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station Number of Analyses 28 Non-Routine**

0 Mean Range imum None Required 0.0020 0.0355 Number Detected***

Total Analyzed Eb-95

]None Required Number of Analyses 27 Non-Routine**

0 Mean Rag aximum Range Minimum Number Detected***

Total Analyzed Ea-226

]

None Required Number of Analyses 28 Non-Routine**

0 Mean R an aximum Range Minimum Number Detected***

Total Analyzed None Required Number of Analyses 21 Non-Routine**

0

-0.0068 2

24 0.0003 0.0032

-0.0024 2

23

-0.0016 0.0118

-0.0121 0

24 Mean Rag aximum Range LMinimum Number D Total Anal Number of Analyses 20 Non-Routine**

0 Mean Maximum Range Afinimum 0.0004 0.0031

)etected***

lyzed None Required

-0.0004 0

18 0.0002 0.0012 Number Detected***

Total Analyzed Wednesday, May 08,2002 Page 2 of 3 28 Station 15 0.0113 0.0355 0.0008 2

4

-0.0027 0.0031

-0.0061 Station 11 0

4 0.0005 0.0024

-0.0021 1

4 0.0002 0.0007

-0.0001 0

4 Station 40 0.0028 0.0118

-0.0010 0

4 0.0017 0.0052

-0.0034 1

4 Station 13 0.0010 0.0030

-0.0001 1

3 Station 14 0.0005 0.0009 0.0002 0

3 0.0003 0.0015

-0.0006 0.0006 0.0012 0.0000 0

17 1

3 0

3

-0.0068 0.0008 0.0118 0.0031

-0.0004

-0.0016

AP Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station

The only radionuclides reported in this table are those with LLD requirements and those for which positive radioactivity was detected. See Section 5 of this report for a discussion of other radionucides that were analyzed

- Non-Routine refers to those radionuclides that exceeded the Reporting Lveles in Technical Specification Table 3.9.4.

- - The fraction of sampling analyses yielding detectable measurements (Le. >3 standard deviations). Note, this does not include measurements that were less than the Minimum Detectable Concentration.

Wednesday, May 08, 2002 Page 3 of 3 29

CF Tahhl5

.. I Radiological Environmental Program Summary Vermont Yankee Nuclear Power Plant, Vernon, VT (January - December 2001)

Medium: Charcoal Cartridge (CF)

UNITS: pCi/cubic meter CF Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station Number of Analyses 216 Non-Routine**

0 Range 0.07 Station 11 0.0005 0.0314

-0.0370 Number Detected***

Tntal A nAIV7Pd 0.0027 0.0182

-0.0221 0

185 0

31

-0.0003 0.0112

-0.0203 0

31

The only radionuclides reported in this table are those with LLD requirements and those for which positive radioactivity was detected. See Section 5 of this report for a discussion of other radionucides that were analyzed.

- Non-Routine refers to those radionuclides that exceeded the Reporting Lveles in Technical Specification Table 3.9.4.

- - The.fraction of sampling analyses yielding detectable measurements (Le. >3 standard deviations).

Friday, May 03, 2002 Page 1 of I 30 0.0182

-0.0370

-0.0221

WR Tahl.5. I Radiological Environmental Program Summary Vermont Yankee Nuclear Power Plant, Vernon, VT (January - December 2001)

Medium: River Water (WR)

UNITS: pCi/L WR Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station

ýa-La-140 15 Station Number of Analyses 24 11 Non-Routine**

0 Alma" 1.3288 1.3288 1.7647 Mri-m um 5.9700 5.9700 12.5000 Minimvm

-2.7700

-3.0400 Number Detected***

0 0

0 Total Ainv7apd 12 12 12

ýe-7 None Required Station Number of Analyses 24 11 Non-Routine**

0 Mon" 3.9782 3.9782

-0.3203 R f/tnriinum 23.3000 23.3000 31.5000 Animum

-10.4000

-23.8000 Number Detected***

1 1

0 Tntal A nalv7pd 12 12 12 lCo-58 15 Station Number of Analyses 24 11 Non-Routine**

0 "Mpan

-0.3150

-1.0716 Wnla*im m 2.9600 2.9600 1.2400 Rannii Rininm

-3.0500

-4.7200 Number Detected***

0 0

0 Total A n-nIv7d 12 12 12

[Co-60 15 Station Number of Analyses 24 21 Non-Routine**

0 Mloan" 0.0713 0.4568 0.4568 I fnyim,,in 1.5900 3.6000 3.6000 Ranap rlimrn

-2.2020

-1.9700

-1.9700 Number Detected***

0 0

0 Total A nalv7t.d 12 12 12 Tuesday, May 07, 2002 Page 1 of 4 31

WR Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station ICs-1342 15 Station Number of Analyses 24 11 Non-Routine**

0 "wl'n 1.0875 1.0875

-0.4015 it lim 18.7000 18.7000 1.6540 Afinirnuln

-2.6900

-2.9500 Number Detected***

1 1

0 Tnta. A n.lwv7od 12 12 12 Cs-137 18 Station Number of Analyses 24 11 Non-Routine**

0

Algn, 0.6974 0.6974 0.7195 rl rn3.7500 3.7500 4.3200 Ranar 1 AMiimum

-0.9128

-1.2790 Number Detected***

0 0

0 Tntnl A naiv770d 12 12 12

[Fe-59 J 30 Station Number of Analyses 24 11 Non-Routine**

0 Mpan 1.0736 1.0736 1.6978 IM,,vi,,,m 5.6500 5.6500 7.6000 Rnnao Afinimihrn

-2.4500

-2.7100 Number Detected***

0 0

0 Tat" A n*Ivv7pd 12 12 12 F 1111 4

Station Number of Analyses 24 11 Non-Routine**

0 won" 1.5856 1.5856 1.7095 a lfarinum 2.7000 2.7000 3.9422 InnJ j Minirn,,M 0.6075 0.6075 0.1755 Number Detected***

5 5

B Tntnl A nalv7od 12 12 12 ZH-3 Z

3000 Station Number of Analyses 8

11 Non-Routine**

0 UIP"nn 86.5238 86.5238 116.3163 AA'arimium 227.0952 227.0952 356.2651

Rnn, mi;rum 11.0000 11.0000 22.0000 Number Detected***

0 0

0 Tatal A "Y'V7Pd 4

4 4

Tuesday, May 07, 2002 Page 2 of 4 32

WR Radionuclides*

k-131 I

Number of Analyses 24 Non-Routine**

0 MeOan Rtanv,,p waI A m...

Required LLD Indicator Station Station with Highest Mean Control Station None Required Station 11 0.3335 8.3200

-K AmnA Number Detected***

Totti A naivrPd

[n-54 15 Number of Analyses 24 Non-Routine**

0 Mean Ranow rmu 0.2151 2.6800

-0.8800 Number Detected***

Tntal A nfllv7,pd 0.3335 8.3200

..K Alflf 0

12 0.6086 7.4000 4.2100 0

12 0

12 Station 21 0.5221 3.3500

-1.2900 0

12 0.5221 3.3500

-1.2900 0

12 0

12 None Required kb-95 Number of Analyses 24 Non-Routine**

0 R GI wP im um Number Detected***

Tntal A nniv7,pd ka-226 Number of Analyses 24 Non-Routine**

0 Raowlarimiim None Required 9.9392 89.7fl00

-42.1000l Th-228 Number of Analyses 24 Non.Routine**

0 Ran Alar ffiliavmnm None Required 1.1215 8.9790

-4.6200 Tuesday, May 07, 2002 Station 11 0.6608 2.5700

-1.9800 0.6608 2.5700 0

12

-1.9800 0

12 1.1651 6.1500

-1.8300 1

12 Station 11 Number Detected***

Total A nalv7od 9.9392 B9.7000 1

12

-42.1000 1

12

-10.3192 59.9000

-99.1000 0

12 Station 11 Number Detected***

Tntal A nnIv7pd 0

12 1.1215 8.9790

-4.6200 0

12 1.5437 14.1000

-17.3000 1

12 Page 3 of 4 33 HIni~mil~mJ#B

-5.

.4100 AR"imy'IM

-1.9800

-1.9800 897000 89.7000 S.

m j"I

-42.

.1000

WR Radionuclides*

I ITh-232 I

Number of Analyses 18 Non-Routine**

0 RoPn n Rl'nna

& [Inl;mIM

?equired LLD Indicator Station Station with Highest Mean Control Station None Required Station 11 4.9006 15.8000

-6.3000 Number Detected***

Total A nalv7d 30 kn-65 Number of Analyses 24 Non-Routine**

0 2

9 4.9006 15.8000

-6.3000 2

9 1.4461 11.7000

-3.3600 1

9 Station 11 on FInff...

Number Detected***

Total A nalv7pd 15 kr-95 Number of Analyses 24 Non-Routine**

0 Ran nor Number Detected***

Total A nnlhed

The only radionuclides reported in this table are those with LLD requirements and those for which positive radioactivity was detected. See Section 5 of this report for a discussion of other radionucides that were analyzed.

- Non-Routine refers to those radionuclides that exceeded the Reporting Lveles in Technical Specification Table 3.9.4.

- - The fractionof sampling analyses yielding detectable measurements (ie. >3 standard deviations).

Tuesday, May 07, 2002 Page 4 of 4 34 0.0931 6.9770

-3.8100 0

12 0.0931 6.9770

-3.8100 0

12

-3.0627 4.3410

-13.2000 0

12 Station 21

-0.0595 4.2400

-5.5600 0

12 0.5004 3.1800

-3.4300 0

12 0.5004 3.1800

-3.4300 0

12 WR I

WG Table 5.1 Radiological Environmental Program Summary Vermont Yankee Nuclear Power Plant, Vernon, VT (January - December 2001)

Medium: Ground Water (WG)

UNITS: pCilL WG Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station ka-La-140]

15 Station Number of Analyses 29 12 Non-Routine**

0 Mean 0.4159 2.3803 2.0620 Maximum 8.2300 8.2300 11.3000 Range Minimum

-6.3100

-0.6280

-1.9300 Number Detected***

0 0

0 Total Analyzed 23 6

6 jCo-58 15 Station Number of Analyses 25 13 Non-Routine**

0 Mean

-0.8229

-0.3707

-1.3032 IMaximum 3.6690 0.7795 0.2810 Range IMinimum

-3.4900

-1.5300

-2.3890 Number Detected***

0 0

0 Total Analyzed 20 5

5 ICo-60 15 Station Number of Analyses 25 12 Non-Routine**

0 Mean

-0.1622 0.6041 0.2804 LMaximum 1X5500 1.5500 1.4700 Range I Minimum

-1.7100

-1.0700

-1.2110 Number Detected***

0 0

0 Total Analyzed 20 5

5 1s-134 15 Station Number of Analyses 25 11 Non-Routine**

0 Mean

-0.5865 0.1235

-1.2343 4Iaximum 2.5170 1.8600

-0.2367 Range Minimum

-11.6000

-0.7106

-1.9300 Number Detected***

0 0

0 TotalAnalyzed 20 5

5 Tuesday, May 07, 2002 Page 1 of 4 35

WG Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station jCs-13 7 Number of Analyses 25 Non-Routine**

0 Mean Range aimum I Minimum 18 Station 14 0.2266 3.3400 Number Detected***

Total Analyzed 4

0.4488 3.3400

-3.9400

-3.9400 0

20

-0.0022 4.3000

-2.2750 0

5 Station 11 Mean 4.6030 8.0566

-2.9884 Lwaximum 14.9418 14.9418 3.3000 n

A/f;j 1nm

-9.7000 3.2000

-26.0000 Number Detected***

Total Analyzed JH il Number of Analyses 25 Non-Routine**

0 Mean Range Minimum Number Detected***

Total Analyzed 12 20 3000 42.5638 307.0388

-85.0000 0

20 2

5 5

5 Station 22 128.8362 338.1003 4.8000 0

5 128.8362 338.1003 4.8000 0

5 0

5 V-131 1

Number of Analyses 25 Non-Routine**

0 Mopan None Required R Maximum RangeI Minimum Number Detected***

Total Analyzed Tuesday, May 07, 2002 0.5608 12.7000

-12.8000 0

20 Number of Analyses 25 Non-Routine**

0 Range Station 12 4.3350 12.7000 0.1840 0

5 2.3909 8.5200

-1.8980 0

5 Page 2 of 4 36 1 Minimum

WG Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station kn-54 Number of Analyses 25 Non-Routine**

0 Mean Range Maxiimum 15 Station 13 0.0467 2.1700

-1.5000 Number Detected***

Total Analyzed 0.1593 0.9190

-1.0412 0.9780

-0.4800 0

20 0

5 0

5 IRa-226I Number of Analyses 25 Non-Routine**

0 None Required 11.9948 uran Range Minimum Number Detected***

Total Analyzed 83.6200

-74.1000 0

20 ITh-232I Number of Analyses 15 Non-Routine**

0 Range None Required Station 14 Mean 8.3566 13.2800

-4.2437 Maximum 33.2000 33.2000

-0.5710 1Minimum

-7.9400

-2.2500

-6.1100 Number Detected***

Total Analyzed kn-TII1 30 Number of Analyses 25 Non-Routine**

0 Mean Rag aximum Rag Minimum Total Analyzed Tuesday, May 07, 2002 2

12 1

3 0

3 Station 13 0.1753 6.9430

-7.3500 1.8606 6.0500

-2.8830 0

20

-3.2348 1.3620

-10.4300 0

5 0

5 Page 3of 4 37 Station 13 36.1152 80.8000

-1.4440 0

5 11.6180 57.6000

-42.7000 0

5 I Minimum

-1.5000

-0.4800

-3.3100 83.6200 80.8000

-741000

-1.4440

WG Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station ir-95 Number of Analyses 25 Non-Routine**

0 Ra ean Range Ria-ximum I minimumir Number Detected***

Total Analyzed Station

-0.7564 2.9700

-2.9980 22 0.4611 4.1100

-1.2800 0

20 0.4611 4.1100

-1.2800 0

5 0

5

The only radionuclides reported in this table are those with LLD requirements and those for which positive radioactivity was detectedL See Section 5 of this report for a discussion of other radionucides that were analyzed.

- Non-Routine refers to those radionuclides that exceeded the Reporting Lveles in Technical Specification Table 3.9.4.

- - The fraction of sampling analyses yielding detectable measurements (ie. >3 standard deviations). Note, this does not include measurements that were less than the Minimum Detectable Concentration.

Tuesday, May 07, 2002 Page 4 of 4 38 15

-2.9980

SE Tnhl* *5. 1 Radiological Environmental Program Summary Vermont Yankee Nuclear Power Plant, Vernon, VT (January - December 2001)

Medium: Sediment (SE)

UNITS: pCi/Kg SE Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station Ie-7 I

Number of Analyses Non-Routine**

None Required 56 0

Range Number Detected***

Total Analyzed ICe-141 I

Number of Analyses 55 Non-Routine**

0 I

Range 11fiinim,,m None Required 44.2552 213.0000

-137.9000 0

55 C6o-60 I

Number of Analyses 56 Non-Routine**

0 Range f,...-

Cs-134 J

Number of Analyses 56 Non-Routine**

0 None Required 150 Uponrmin Range Mnnin Number Detected***

Total Analyzed Wednesday, May 08, 2002 Station 15 12.4174 71.7500

-23.8200 0

56 Station 29 1.4145 46.2400

-54.3600 0

566 39 Station 23 251.5309 1090.0000

-237.0000 4

56 690.7500 717.5000 664.0000 0

2 No Data No Data No Data 0

0 Station 39 Number Detected***

Total Analyzed 118.9500 213.0000 24.9000 0

2 No Data No Data Nn flati.

0 0

M I-23.l20l0 14*l Number Detected***

Total Analyzed 45.0750 71.7500 18.4000 No Data No Data 0

2 No Data 0

0 24.5850 26.0000 23.1700 0

2 No Data No Data No Data 0

0 Page 1 of 3 24.9000 No Data 12A174 71.7500 No Data

SE Radionuclides*

R 1Cs-137 1

Number of Analyses 56 Non-Routine**

0 Iequired LLD Indicator Station Station with Highest Mean Control Station 180 Station 14 "MOnn 137.4770 189.0000 No Data I -;rrimum 219.0000 194.0000 No Data I

29.1400 184.0000 No Data Range IK-40 I

Number of Analyses 56 Non-Routine**

0 Up1onn Range ka-226 Number ofAnalyses 56 Non-Routine**

0 Range Th-228 I

46 56 2

2 Station 49 15681.446 19200.000 7913.0000 56 56 18415.0000 19100.0000 17730.0000 2

2 Station 43

""On 1980.3220 3280.0000 No Data Ha,*milm 4060.0000 4060.0000 No Data I Minimum 81.5300 2500.0000 No Data Number of Analyses 58 Non-Routine**

0 44 56 2

2 Station 38 Range Number Detected***

Total Analyzed

[Th-232 I

None Required Number of Analyses 27 Non-Routine**

0 IMonn 111"mrim iut Range &fi~imum Number Detected***

Total Analyzed Wednesday, May 08, 2002 Page 2of3 40 Number Detected***

Total Analyzed None Required 0

0 Number Detected***

Total Analyzed None Required No Data No Data No flak, 0

0 Number Detected***

Total Analyzed None Required 0

0 1081.7034 1380.0000 544.4000 58 58 1298.0000 1320.0000 1276.0000 No Data No Data No Data 2

2 Station 27 0

0 1205.5185 1420.0000 933.0000 27 27 1420.0000 1420.0000 1420.0000 1

1 No Data No Data No Data 0

0

SE Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station

The only radionuclides reported in this table are those with LLD requirements and those for which positive radioactivity was detected. See Section 5 of this report for a discussion of other radionucides that were analyzed.

- Non-Routine refers to those radionuclides that exceeded the Reporting Lveles in Technical Specification Table 3.9.4.

- - The fraction of sampling analyses yielding detectable measurements (Le. >3 standard deviations). Note, this does not include measurements that were less than the Minimum Detectable Concentration.

Wednesday, May 08, 2002 Page 3 of 3 41

WT Thp. 5. 1 Radiological Environmental Program Summary Vermont Yankee Nuclear Power Plant, Vernon, VT (January - December 2001)

Medium: Test Wells (WT)

UNITS: pCi/L WT Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station ja-La-140 I Number of Analyses 8

Non-Routine**

0 R 7n ori n

WIMi-,..-

None Required

-0.3672 5.5800

-4.9500 Ze-7 I

Number of Analyses 8

Non-Routine**

0 Alpizn R

hn ro None Required 13.5600

-23.1000 None Required lCo -58 I

Number of Analyses 8

Non-Routine**

0 U01n"p Number Detected***

Total A nlflIv,,d None Required ICo-60 Number of Analyses 8

Non-Routine**

0 Rano p Number Detected***

Total A nlvIiV7Pd Tuesday, May 07, 2002 Station 14 Number Detected***

Tntal A nlov7pd 0

8 4.8100 5.5800 4.0400 0

2 No Data No Data No Data 0

0 Station 18 Number Detected***

Total A nal77Pd 1

8 16.5950 34.1000

-0.9100 0

2 No Data No Data No Data 0

0 Station 18

-0.8532 0.7030

-2.4800 0

8 0.1525 0.7030

-0.3980 0

2 No Data No Data No flnln 0

0 Station 18

-0.0941 2-1600

-2.3500 0

8 1.5435 2.1600 0.9270 0

2 No Data No Data No Data 0

0 Page 1 of 5 42

WT Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station None Required jCs-I134I Number of Analyses 8

Non.Routine**

0 n

Minimum Number Detected***

Totml A nalv7,'d Station 17

-4.0470 2.5400

-1 9.1 000 0

8

-1.0450 1.1900

-3.2800 0

2 No Data No Data No Data 0

0 Ic-13377]

None Required Number of Analyses 8

Non-Routine**

0 UAponn I A41yimnm Ron ne' ~minmumn Number Detected***

Total A nflve'd lEu-1-54 INone Required Number of Analyses 8

Non-Routine**

0 Mea nn I

Tt4nrln ii imn Ran.rp tI Minimum Number Detected***

Total A nalv7d ke-59 INone Required Number of Analyses 8

Non-Routine**

0 Station 18 2.0326 2.9300 No Data 5.3900 4.7200 No Data

-0.5650 1.1400 No Data 0

8 0

2 Station 14 A q917 20.3000

-2.5500 1

8 1n.Rq.5e 20.3000 1.4900 1

2 Station 17 Ma-nn 1.8609 4.6900 O.IMn7,,M 10.8000 10,8000 Ran Min" m

-3.1200

-1.4200 Number Detected***

0 0

Total A nlwfled 8

2 Tuesday, May 07, 2002 43 0

0 No Dlata 10 SMNo Data No Data No Data 00 0

No Data No Data No Data 0

0 Page 2 of 5

WT Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station IGR-B I

None Required Number of Analyses 8

Non-Routine**

0 Station 17 Maon 34.7375 51.7000 No Data iLfayim "m 97.0000 97.0000 No Data 1Minim r 2.9000 6.4000 No Data Number Detected***

Tntnl A nalwe7d 8

8 2

2 Number of Analyses 8

Non-Routine**

0 Rano*

i None Required Number Detected***

Total A nnlv7pd 7-13111 None Required Number of Analyses 8

Non-Routine**

0 Rannof Station 14

-24.3750 92.0000

-200.0000 1

8 21.0000 58.0000

-16.0000 0

2 No Data No Data No Data 0

0 Station 14 "opn" 1.4125 7.4050 No Data i]/larimm 9.5100 9.5100 No Data

[Minimm

-7.7000 5.3000 No Data Number Detected***

Tntal A nnlv7,d None Required Wn -54 I

Number of Analyses 8

Non-Routine**

0 Ran Mrnw Number Detected***

Total A nalw*h d Tuesday, May 07, 2002 0

8 0

2 0

0 Station 17 0.9249 2.8900

-1 _AgOG 0

8 2.4850 2.8900 2.0800 0

2 No Data No Data No Data 0

0 Page 3 of 5 44 Ran poo 0

0 Sl*m mIEmIW.....

m 0

0

-15900

WT Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station

ýb-95 None Required Number of Analyses 8

Non-Routine**

0 Station 16 Mon" 1.7859 3.4430 No Data 7.4400 7.4400 No Data S;-1.0900

-0.5540 No Data Number Detected***

Tatal A no1v71pd None Required ITe-132 I

Number of Analyses 8

Non-Routine**

0 Rawopa Number Detected***

Tnatl A nnlv.d None Required ITh-228 Number of Analyses 8

Non.Routine**

0 Ronon Number Detected***

Total A noulv77pd None Required ITh-232 _]

Number of Analyses 8

Non-Routine**

0 Ht an R nnow i t ii...

Number Detected***

Tntol A nAlv7pd 1

8 1

2 Station 18 27.0400 71.2000

-4.ngflf 8

33.3050 71.2000 4.5900 0

2 Station 16 2.5946 5.6100 fln3'='7 1

8 3.3050 5.6100 1-n.on 0

2 Station 14 3.1850 18.9000

.17_ Anfn 1

8 14.8000 18.9000 1 fl_7000 1

2 Page 4 of 5 45 Ranao 0

0 No Data No Data No Data 0

0 No Data No Data Mn 1)nfa 0

0 No Data No Data ANn IDnta 0

0 Tuesday, May 07, 2002 0

0

-4.5900 00337 10000 No Data

-17.0000 No Data l

WT Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station None Required Number of Analyses 8

Non-Routine**

0 Mov

[tln"mn Number Detected***

Tntal A nnl-o7d kr-95 JNone Required Number of Analyses 8

Non-Routine**

0

-5.1015 1.3900

-13.3000 0

8 Station 17 0.8040 1.3900 0.2180 0

2 Station 18 LPonn

-0.3654 2.2700 No Data Mlniminm 2.3800 2.3800 No Data Minf/nimyM

-5.0500 2.1600 No Data Number Detected***

Tntal A nnavh7d 0

8 0

2

The only radionuclides reported in this table are those with LLD requirements and those for which positive radioactivity was detected. See Section 5 of this report for a discussion of other radionucides that were analyzed.

- Non-Routine refers to those radionuclides that exceeded the Reporting Lveles in Technical Specification Table 3.9.4.

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

Tuesday, May 07, 2002 Page 5 of 5 46 No Data No Data No Data 0

0 Rrnmw 0

0

TM Tahip.5.1 Radiological Environmental Program Summary Vermont Yankee Nuclear Power Plant, Vernon, VT (January - December 2001)

Medium: Milk (TM)

UNITS: pCi/L TM Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station a-La-140 15 Station Number of Analyses 144 11 Non-Routine**

0 Moan 0.0546 0.9155

-0.2868 aJnrmum 7.5000 7.5000 6.6400 Range Minlml

-11.1000 4.0687

-7.1000 Number Detected***

0 0

0 Total Analyzed 125 18 19 ICo-57iJ None Required Station Number of Analyses 143 22 Non-Routine**

0 0.0136 0.3381

-0.4857 Rang Mnrim u3.7600 2.3310 2.7810 Range Minimm

-4.7600

-2.0230

-4.7500 Number Detected***

0 0

0 Total Analyzed 125 31 18 ICs-134 15 Station Number of Analyses 141 18 Non-Routine**

0

""n

-0.4241 0.0135

-1.3629 R

Ma rimnt m 3.4130 3.0400 2.1590 Range in um

-10.8000

-3.1970

-10.1000 Number Detected***

0 0

0 Total Analyzed 124 21 17 EIs-137 1

18 Station Number of Analyses 142 25 Non-Routine**

0 loln 1.4010 3.0627 0.9162 a nimgum 6.5300 5.7600 4.4700 RangeM im

-2.6400 0.9745

-1.6820 Number Detected***

1 0

0 Total Analyzed 124 14 18 Tuesday, May 07, 2002 Page 1 of 3 47

TM Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station 11-131 1

Number of Analyses 144 Non-Routine**

0 Range 1

Station 22 0.0719 0.8023

.-0.3816 Number Detected***

Total Analyzed 0.0911 0.8023

-0.1307 0

126 0.0882 0.5850

-0.0757 0

18 0

32 IK-40 I Number of Analyses 144 Non-Routine**

0

]D'J o,7M Range [A;r;:t..

Number Detected***

Total Analyzed None Required 1412.3492 2300.0000 853.0000 126 126 Ir-89 I Number of Analyses 30 Non-Routine**

0 "0/7 aNJ Range Number Detected***

Total Analyzed None Required

-0.4726 5.6491

-F,.4530 0

26 None Required Range M

Number Detected***

Total Analyzed Tuesday, May 07, 2002 1.8506 5.7167

-2.6287 21 26 Page 2 of 3 48 Station 25 1727.0000 2070.0000 853.0000 15 15 1363.1111 1602.0000 1200.0000 18 18 Station 25 EIsriIZ 2.5123 5.6491

-2.2000 Number of Analyses 30 Non-Routine**

0 kDrý l

0 4

-0.8642 2.2107

-4.6476 0

4 Station 26 2.5728 3.5964 1.4000 4

4 0.9633 3.0905

-0.8175 3

4 0.0719 0.0911 0.8023 0.8023

-0.3816

-0.1307 I IFW........

F......

5............

TM Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station

[Th-228

]

Number of Analyses 144 Non-Routine**

0

?bA-m None Required 0.6113 16.3000 Range

-12'9600 Number Detected***

Total Analyzed ITh-232

]

None Required Number of Analyses 74 Non-Routine**

0

&f,0,n7 Range I 1

126 4.6489 33.5000

-is imnn Number Detected***

Total Analyzed 4

65 0

12

The only radionuclides reported in this table are those with LLD requirements and those for which positive radioactivity was detected. See Section 5 of this report for a discussion of other radionucides that were analyzed.

- Non-Routine refers to those radionuclides that exceeded the Reporting Lveles in Technical Specification Table 3.9.4.

- - The fraction of sampling analyses yielding detectable measurements (ie. >3 standard deviations). Note, this does not include measurements that were less than the Minimum Detectable Concentration.

Tuesday, May 07, 2002 Page 3 of 3 49 Station 11 1.7855 16.3000

-7.2500 1

18 3.5072 16.8700

-12.3000 1

18 Station 26 7.9666 21.3000

_n A~rn 3.5190 13.7000

_12 Oann 0

9 16.3000 16.3000

-12.9600

-7.2500 aýLMUZZIIM

V

TC Table... I Radiological Environmental Program Summary Vermont Yankee Nuclear Power Plant, Vernon, VT (January - December 2001)

Medium: Silage (TC)

UNITS: pCi/Kg TC Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station None Required 7

0 483.6167 1280.0000

-15.1000 4

6 Station 18 1280.0000 1280.0000 1280.0000 183.0000 183.0000 183.0000 1

1 1

1 Number of Analyses 6

Non-Routine**

0 None Required 44.9800 Range Number Detected***

Tatal A nnlv7ipd 77.1000 8.9000 2

5 Number of Analyses 6

Non-Routine**

0 Range En 60 Number Detected***

Tatal A nalv*pd Number of Analyses 7

Non-Routine**

0 A*PfoInn 80 Range I Mnimuzm Number Detected***

Tatal A nalvTd.d Wednesday, May 08, 2002 Number of Analyses Non-Routine**

Range I Number Detected***

Total A nAIv7Pd Station 26 77.1000 77.1000 77.1000 1

1 151.0000 151.0000 151.0000 1

1 Station 22

-16.9628 5.2200

-62.9000 0

5 5.2200 5.2200 5.2200 0

1

-12.1000

-12.1000 0

1 Station 25 13.8570 58.5000 nA'~Lf 1

6 58.5000 58.5000

8.5000 9.8300 9.8300 9.8300 1 1 1

1 Page I of 2 50 v.vvlv 585000 58.5000 05340 585000

TC Radionuclides*

V1131 I

Number of Analyses Non-Routine**

MeaRn Alarimum Range

,,t.,,

Required LLD Indicator Station Station with Highest Mean Control Station 60 7

0 Station 25 9.6667 57.9000

-2n 9nnn 57.9000 57.9000 47 Qnnn 24.7000 24.7000 OA 7nMlf Number Detected***

Total A nalv7ed Number of Analyses Non-Routine**

None Required 7

0

""02 4442.1667 8470.0000 5450.0000 Ijn rim um 8470.0000 8470.0000 5450.0000 Range I Minimm 953.0000 8470.0000 5450.0000 Number Detected***

6 1

1 Total A nalv7tPd 6

1 1

Number of Analyses Non.Routine**

MPiLnnl Range Number Detected***

Total A nalV7Pd Number of Analyses Non-Routine**

Al,,,,.

R ang e a 4;.r;m,,m Number Detected***

Total A nwlvod None Required 7

0 None Required 7

0

The only radionuclides reported in this table are those with LLD requirements and those for which positive radioactivity was detected. See Section 5 of this report for a discussion of other radionucides that were analyzed.

- Non-Routine refers to those radionuclides that exceeded the Reporting Lveles in Technical Specification Table 3.9.4.

- - The fraction of sampling analyses yielding detectable measurements (ie. >3 standard deviations).

Wednesday, May 08, 2002 Page 2 of2 51 0

6 0

1 Station 25 0

1 Station 11 29.9617 70.3000 703000 70.3000 70.3000 7n -fnnn 2

6 1

1 14.4000 14.4000 14.4000 1

1 Station 25 38.9867 87.5000

-9.0800 1

6 87.5000 87.5000 87.5000 1

1 36.7000 36.7000 36.7000 1

1

[ #WmDP..........

38700 70.3000 38.9867 I

MiWiB*

-90800 w

TG Tahl.5-1 Radiological Environmental Program Summary Vermont Yankee Nuclear Power Plant, Vernon, VT (January - December 2001)

Medium: Mixed Grass (TG)

UNITS: pCi/Kg TG Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station None Required Number of Analyses 30 Non-Routine**

0 Range Number Detected***

Total A nalv7.d 60 Number of Analyses 30 Non-Routine**

0 AL~rn.

Range l...

I IUUrlm.. N220

-be58tete00 Number Detected***

Total A nilj.V7Pd 80 1934.6154 4460.0000 219.0000 26 26 Station 12 3725.0000 4460.0000 3200.0000 4

4 2012.5000 2950.0000 850.0000 4

4 Station 13

-3.8529 14.8900

.9g-9nnflf 0

26 Number of Analyses 28 Non-Routine**

0 9.0185 27.2000

-3.1600 Number Detected***

Total A nalv7ed 3

24

-0.1710 5.2400

.-5.8800

-9.8350 4.7500

-30.2000 0

4 0

4 Station 13 15.4450 27.2000 4.2800 2

4 7.1550 12.3000 2.3000 0

4 Number of Analyses 30 Non-Routine**

0 Range 60 Number Detected***

Total A nnlv7pd Wednesday, May 08, 2002 Page I of 2 52 Range I Minimum Station 14 3.1186 80.1000

-29.3000 0

26 13.7225 80.1000

-10.3000 0

4 2.3275 18.4000

-12.1000 0

4 27.2000

-3.1600 v-K1

TG Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station None Required Number of Analyses 30 Non-Routine**

0 A*Dlfna Range Number Detected***

Tntnl A naiv7ed None Required Number of Analyses 30 Non-Routine**

0 Station 14 5014.2308 8280.0000 1900.0000 26 26 5632.5000 8280.0000 1900.0000 4

4 Station 11 AtfrP7 15.2060 27.8240 Marimur 83.8100 83.8100 M i;nimum

-13.2000 8.0600 Number Detected***

TntfiY A nfalV7&d 4

26 1

5 None Required Number of Analyses 27 Non-Routine**

0 A, rpnn 35.5039 Range Number Detected***

Tatnl A nflwV7&d 89.9000 2.9200 3

23

The only radionuclides reported in this table are those with LLD requirements and those for which positive radioactivity was detected. See Section 5 of this report for a discussion of other radionucides that were analyzed.

- Non-Routine refers to those radionuclides that exceeded the Reporting Lveles in Technical Specification Table 3.9.4.

- - The fraction of sampling analyses yielding detectable measurements (Le. >3 standard deviations). Note, this does not include measurements that were less than the Minimum Detectable Concentration.

Wednesday, May 08, 2002 Page 2 of 2 53 tz 4720.0000 7030.0000 2760.0000 4

4 Range 3.3000 18.5000 28.4000 0

4 Station 14 66.8000 77.8000 41.1000 1

4 44.5050 108.0000 1.8200 0

4

FH T

Ih1*

.* 1 Radiological Environmental Program Summary Vermont Yankee Nuclear Power Plant, Vernon, VT (January - December 2001)

Medium: Fish (FH)

UNITS: pCi/Kg FH Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station 130 Station Number ofAnalyses 4

21 Non-Routine**

0 Mean

-19.5760

-2.6000

-2.6000 Unr4m"m

-6.7520 10.1000 10.1000 Range 1 imn

-32.4000

-15.3000

-15.3000 Number Detected***

0 0

0 Total A nalvwod 2

2 2

130 Station Number of Analyses 4

11 Non-Routine**

0

""on 16.9350 16.9350

-2.4950

-;rn, 23.5700 23.5700 1.7400 Range 1 Minimum 10.3000 10.3000

-6.7300 Number Detected***

0 0

0 Total A nBlv7,ld 2

2 2

130 Station Number of Analyses 4

11 Non-Routine**

0

)Ijan

-9.8885

-12.1050 Mn "ri, m i1.0230 1.0230

-4.5300 Range

-;,;,,in 20.8000

-20.8000

-19.6800 Number Detected***

0 0

0 Tntal A nalv7pd 2

2 2

C0-137 I 150 Station Number of Analyses 4

11 Non-Routine**

0 Me""

23.1850 23.1850 17.1750 SMn-r;i,m 25.5000 25.5000 20.8000 Range &iinim, int 20.8700 20.8700 13.5500 Number Detected***

1 1

1 Total A nalv7pd 2

2 2

Tuesday, May 07, 2002 Page I of 2 54

FH Radionuclides*

Required LLD Indicator Station Station with Highest Mean Control Station

ýe-59 I Number of Analyses 4

Non-Routine**

0 260 Station 11 Range iMinim Number Detected***

Total A na.v7,Pd IK-40 None Required Number of Analyses 4

Non-Routine**

0 IW17non Range Number Detected***

Total A nMaiWvd 130

ýWn-54 I

Number of Analyses 4

Non-Routine**

0 Range I Number Detected***

Total A nalv,7d 260 kn-65 I

Number of Analyses 4

Non-Routine**

0 Station 21 A101n 6.8050 39.0435 39.0435 12.5300 71.3000 71.3000 Range nin i

1.0800 6.7870 6.7870 Number Detected***

0 1

1 Tntnl A nalv7.-d 2

2 2

The only radionuclides reported in this table are those with LLD requirements and those for which positive radioactivity was detected. See Section 5 of this report for a discussion of other radionucides that were analyzed.

- Non-Routine refers to those radionuclides that exceeded the Reporting Lveles in Technical Specification Table 3.9.4.

- - The fraction of sampling analyses yielding detectable measurements (Le. >3 standard deviations).

Tuesday, May 07, 2002 Page 2 of 2 55 30.5470 60.1100 0.9840 30.5470 60.1100 0.9840 0

2 0

2 13.9695 25.0000 2.9390 0

2 Station 11 3088.5000 3240.0000 2937.0000 2

2 3088.5000 3240.0000 "2937.f000 2

2 2853.0000 3320.0000 2386.0000 2

2 Station 11 1.4435 4.1300

-1.2430 0

2 1.4435 4.1300

-1.9430 0

2

-0.1065 7.6500

-7.8630 0

2 60.1100 60.1100 0.9840........

I*mmmflffmBBwmm 1.4435 1.4435 SI*fmJDmlJJJBJDm

-12430

Environmental TLD Data 2001 Radiological Environmental Operating Report Vermont Yankee Tables:

5.2 - Data Summary 5.3 - Measurements 56

TABLE 5.2 ENVIRONMENTAL TLD DATA

SUMMARY

VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY - DECEMBER 2001)

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

MEAN*

RANGE*

(NO. MEASUREMENTS)**

(NO. MEASUREMENTS)-

STA.NO MEAN*

RANGE*

(NO. MEASUREMENTS)-

MEAN*

RANGE*

(NO. MEASUREMENTS)*

DR-36 7.6

+

0.4 5.9 8.4 4

SITE BOUNDARY TLD WITH HIGHEST MEAN STA.NO. MEAN*

RANGE*

(NO. MEASUREMENTS)

DR-45 12.0 +

0.7 11.5 -

12.5 4

SITE BOUNDARY TLD MEAN*

RANGE*

(NO. MEASUREMENTS)*

7.9 0.41 6.4 12.0 56 Units are in micro-R per hour.

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

57 6.4

+/- 0.3 5.0 7.5 83 6.5

+

0.4 5.5 7.6 63 6.4

+ 0.35 6.2 6.7 8

TABLE 5.3 ENVIRONMENTAL TLD MEASUREMENTS 2001 (Micro-R per Hour)

ANNUAL Sta.

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

No.

Description EXP.

S.D.

EXP.

S.D.

EXP.

S.D.

EXP.

S.D.

EXP.

DR-01 River Sta. No. 3.3 5.6 +/- 0.4 6.3 +/- 0.3 6.2 +/- 0.5 6.4 +/- 0.2 6.1 DR-02 N Hinsdale, NH 5.3 +/- 0.4 7.0 +/- 0.4 6.9 +/- 0.4 6.8 +/- 0.2 6.5 DR-03 Hinsdale Substation 6.1

+/- 0.4 8.0 +/- 0.4 7.9 +/- 0.4 7.9 +/- 0.5 7.5 DR-04 Northfield, MA 5.4 +/- 0.4 6.7 +/- 0.3 6.4 +/- 0.3 6.4 +/- 0.3 6.2 DR-05 Spofford Lake, NH 5.5 +/- 0.5 7.0 +/- 0.4 7.1

+/- 0.4 7.0 +/- 0.3 6.7 DR-06 Vernon School 5.4 +/- 0.4 6.9 +/- 0.3 6.8 +/- 0.3 6.9 +/- 0.3 6.5 DR-07 Site Boundary 6.3

+/- 0.5 7.9 +/- 0.3 7.9 +/- 0.3 8.2 +/- 0.3 7.6 DR-08 Site Boundary 7.4 +/- 0.5 8.5 +/- 0.3 8.4 +/- 0.4 8.4 +/- 0.4 8.2 DR-09 Inner Ring 5.3 +/- 0.3 6.5 +/- 0.3 6.0

+/- 0.3 6.5 +/- 0.3 6.0 DR-10 Outer Ring 4.6 +/- 0.4 5.9 +/- 0.3 5.6 +/- 0.3 6.1

+/- 0.3 5.5 DR-11 Inner Ring 5.0

+/- 0.4 6.3 +/- 0.3 6.1

+/- 0.3 6.2 +/- 0.2 5.9 DR-12 Outer Ring 4.8 +/- 0.4 6.2 +/- 0.3 5.9 +/- 0.3 5.9 +/- 0.3 5.7 DR-13 Inner Ring 5.7

+/- 0.5 6.9 +/- 0.3 6.5 +/- 0.3 6.5 +/- 0.3 6.4 DR-14 Outer Ring 5.5

+/- 0.4 8.1

+/- 0.4 7.8 +/- 0.4 8.0 +/- 0.4 7.3 DR-15 Inner Ring 5.8

+/- 0.5 7.2 +/- 0.3 6.8 +/- 0.5 6.6 DR-16 Outer Ring 6.3

+/- 0.5 7.3

+/- 0.3 7.0 +/- 0.4 7.4 +/- 0.2 7.0 DR-17 Inner Ring 4.9

+/- 0.4 6.4 +/- 0.3 6.4 +/- 0.3 6.6 +/- 0.3 6.1 DR-18 Outer Ring 5.3

+/- 0.4 7.0 +/- 0.7 6.7 +/- 0.4 6.7 +/- 0.3 6.4 DR-19 Inner Ring 5.7

+/- 0.4 7.6

+/- 0.4 7.7 +/- 0.4 7.6 +/- 0.4 7.2 DR-20 Outer Ring 5.5

+/- 0.4 7.3 +/- 0.3 7.7 +/- 0.4 7.8 +/- 0.3 7.1 DR-21 Inner Ring 5.4

+/- 0.3 6.9

+/- 0.3 6.8 +/- 0.4 6.9 +/- 0.2 6.5 DR-22 Outer Ring 5.7 +/- 0.4 6.8

+/- 0.3 6.7 +/- 0.3 6.9 +/- 0.3 6.5 DR-23 Inner Ring 5.4

+/- 0.4 6.4

+/- 0.3 6.5 +/- 0.4 6.6 +/- 0.2 6.2 DR-24 Outer Ring 4.9 +/- 0.3 6.1

+/- 0.4 6.0 +/- 0.3 6.1

+/- 0.3 5.8 DR-25 Inner Ring 5.6

+/- 0.4 7.0

+/- 0.3 6.7 +/- 0.3 6.7 +/- 0.3 6.5 DR-26 Outer Ring 5.0 +/- 0.4 6.7

+/- 0.3 6.8 +/- 0.3 7.0 +/- 0.3 6.4 DR-27 Inner Ring 5.4

+/- 0.3 7.0

+/- 0.3 6.6 +/- 0.4 6.9 +/- 0.2 6.5 DR-28 Outer Ring 5.1

+/- 0.3 6.6 +/- 0.6 6.9 +/- 0.4 6.4 +/- 0.3 6.3 DR-29 Inner Ring 5.7

+/- 0.4 6.6

+/- 0.3 6.9 +/- 0.3 6.8 +/- 0.2 6.5 DR-30 Outer Ring 5.8

+/- 0.4 6.7

+/- 0.3 7.0 +/- 0.4 6.9 +/- 0.3 6.6 DR-31 Inner Ring 5.5

+/- 0.5 7.1

+/- 0.4 6.8 +/- 0.4 7.1

+/- 0.3 6.6 DR-32 Outer Ring 5.1

+/- 0.4 6.9

+/- 0.3 7.1

+/- 0.4 7.2 +/- 0.2 6.6 DR-33 Inner Ring 5.4

+/- 0.4 7.0

+/- 0.3 7.0 +/- 0.3 7.2 +/- 0.2 6.6 DR-34 Outer Ring 5.6

+/- 0.4 7.4

+/- 0.3 7.1

+/- 0.3 7.4 +/- 0.3 6.9 DR-35 Inner Ring 5.7

+/- 0.4 7.0

+/- 0.5 6.7 +/- 0.3 6.8 +/- 0.3 6.6 DR-36 Outer Ring 5.9

+/- 0.4 7.9

+/- 0.4 8.4 +/- 0.4 8.4 +/- 0.3 7.6 DR-37 Inner Ring 5.1

+/- 0.5 6.9

+/- 0.3 6.8 +/- 0.3 6.9 +/- 0.3 6.4 DR-38 Outer Ring 7.3

0.4 7.6 +/- 0.4 7.5 +/- 0.3 7.5 DR-39 Inner Ring 5.1 0.4 7.1

+/- 0.3 6.8 +/- 0.4 7.1

+/- 0.3 6.5 DR-40 Outer Ring 5.4

+/-- 0.5 6.7

+/- 0.4 6.8 +/- 0.3 6.9 +/- 0.4 6.4

Data not available due to missing TLD.

58

TABLE 5.3 ENVIRONMENTAL TLD MEASUREMENTS 2001 (Micro-R per Hour)

Sta.

No.

Description 1ST QUARTER EXP.

S.D.

2ND QUARTER 3RD QUARTER 4TH QUARTER EXP.

S.D.

EXP.

S.D.

EXP.

S.D.

ANNUAL AVE.

EXP.

Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Governor Hunt House Site Boundary Site Boundary DR-53 Site Boundary 5.6 5.2 5.7 7.6 11.5 7.2 6.0 5.5 5.4 6.0 6.6 7.3

+/-

0.4 0.4 0.4 0.5 0.9 0.5 0.5 0.4 0.4 0.4 0.5 0.7 7.8 6.9 7.4 8.1 12.4 8.9 7.9 7.1 6.7 7.1 8.0 8.4

+/-

0.3 0.3 0.3 0.4 0.4 0.4 0.3 0.4 0.4 0.5 0.3 0.4 7.8 7.0 7.5 8.1 11.6 9.1 8.3 7.3 6.6 7.1 8.6 9.0

+/-

0.4 0.4 0.4 0.5 0.7 0.5 0.4 0.4 0.4 0.4 0.5 0.4 7.7 6.9 7.6 8.0 12.5 9.1 8.3 7.3 6.7 6.9 8.6 8.8

+/-

0.3 0.3 0.2 0.3 0.6 0.5 0.4 0.3 0.3 0.3 0.4 0.4 7.6 +/- 0.6 9.1

+/-

0.5 9.7 +/- 0.5 9.6 +/- 0.4 59 DR-41 DR-42 DR-43 DR-44 DR-45 DR-46 DR-47 DR-48 DR-49 DR-50 DR-51 DR-52 7.2 6.5 7.1 8.0 12.0 8.6 7.6 6.8 6.4 6.8 7.9 8.4 9.0

6.

ANALYSIS OF ENVIRONMENTAL RESULTS 6.1 Sampling Program Deviations Off-site Dose Calculation Manual Control 3.5.1 allows for deviations "if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons." In 2001, several deviations were noted in the REMP. These deviations did not compromise the program's effectiveness and in fact, with the exception of the loss of a set of air samples during shipment, are considered typical with respect to what is normally anticipated for any radiological environmental monitoring program. The specific deviations for 2001 were:

a) The power at the air sample station in North Hinsdale (AP/CF-12) was disconnected by Public Service Company of New Hampshire. The company had been asked to disconnect the power at an abandoned air station and mistakenly disconnected it at this location. This problem was discovered on 12/27/00 during the 4th quarterly environmental TLD changeout. The sampling station only missed 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months of sampling time from 12/26/00 until 1/9/01 when the air samples were then collected.

b) The outer ring TLD in the NW sector, DR-38 was reported missing for the 1st quarter of the year on March 29, 2001 during the TLD changeout surveillance.

Deep snow encountered during the collection hindered the technician's search for the lost TLD. No sign of the TLD or its holder was identified.

c) Upon observing high river water conditions on April 24, 2001, as a result of winter snowmelt runoff, the technician investigated the operability of the river water pump supplying water to the River Water Sample Compositor (WR 11 - Station 3-3). He found that the pump was out of service and therefore no flow was reaching the sample compositor. Daily grab samples were immediately initiated until the river level receded and the river water pump could be restored to service.

d) Failure of a Ground Fault Interrupter resulted in the loss of power to the Northfield, Massachusetts Air Sample Station (AP/CF 14). The failure was discovered by the technician during route sample collection on May 29, 2001 and power was restored on June 12, 2001. A loss of approximately 475 hours0.0055 days 0.132 hours 7.853836e-4 weeks 1.807375e-4 months of sample collection was experienced during this period.

e) Power at the Air Sample Station (AP/CF 11 - River Station) and the River Water Sample Compositor(WR 11 - Station 3-3) was shutdown for approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months on August 11, 2001 due to a scheduled power outage for the area. No air sample volume or river water composite was collected during this three hour period. This event was discovered by the technician during routine sample collection on August 12, 2001.

f)

During a lightning storm on August 12, 2001 water supply was lost for a short period (not more than 2 sample cycles) to the River Water Sample Compositor (WR 11 - Station 3-3). This event was discovered when thermal data ceased to be transmitted to the plant computer from this sample station.

g) Environmental Air Samples collected on August 7, (Week 32) 2001 were discovered to be lost during sample shipment and receipt at the vendor laboratory.

Air Particulate/Charcoal Filter (AP/CF) samples for all of the seven stations (AP/CF 11, 12, 13, 14, 15, 21 and 40) collected on that date were 60

sent to the vendor laboratory but were not received by the laboratory. An investigation of the event led to the implementation of significant changes in sample shipment practices.

h) The inner ring TLD in the ENE sector, DR-15 was reported missing for the 3Pd quarter of the year on October 1, 2001 during the TLD changeout surveillance. No sign of the TLD or its holder was evident following an area search by the technician.

i) The following data indicates the percentage of time that each air sampling station operated during year 2001. The data was based on an electric timer at each station. This data indicates that any power interruptions did not result in a significant loss of data for the airborne contaminant sampling program. Location AP/CF is not a location required by the ODCM. Minor power interruptions are expected due to minor maintenance repairs during the year.

AP/CF #

1* Quarter 2"E Quarter 3 rd Quarter 4' Quarter 11 97.6%

100.0%

99.7%

100.0%

12 95.6%

89.5%

100.0%

13 100.0%

100.0%

14 99.9%

76.4%

99.3%

100.0%

15 99.8%

99.9%

86.0%

100.0%

21 100.0%

98.2%

86.1%

100.0%

40 100.0%

100.0%

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. In such a case, ODCM 10.2 requires a discussion of the situation. At the contracted environmental laboratory, the target LLD for any analysis is, for the majority, 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 2001, there were several samples where the a posteriori LLD exceeded a corresponding LLD requirement. All but five of the analyses appeared to have had delays in counting at the contractor laboratory, which resulted in the analyses not meeting the target LLD. The Terrestrial Vegetation samples (TG) collected in week 47 were of insufficient weight to allow the laboratory to achieve the 1-131 LLD for vegetation. The growth of grass in the month of November is severely curtailed due to advancing cold weather. The following table lists the samples and the isotope measured that did not meet the required LLD of Table 4.5.1 of the ODCM.

61

Media Station # Week #

Nuclide Activity I Std Dev MLL CF 15 36 1-3 13E0

.050

.3-17.0=E0 WR 11 24 BaL-4 1.0E+00 9.4E+0 2.62E+01 1.50E+01 WG-14

-a-7W-140 -6.3TET+0 7.U5E-+0 T.72E+T0 1.50ET0 W

13 18 GR-B 1.00E+01 1.70E+01 5.0UE+01 4.00ET+O W

14 1

R-

-70E0 1.520 5.00U+01 4.E+00 WG 22 18

-GR-B F-2.050 1.3=15005

.0+0 TM 14 27 Ba-La-140 1.16E+00 4.39F=+00 1.581E+01 1.50E=+1 T

1 27 a+

4.14E+00 1.67E+01 71.50ET+01 TM 18 27 Ta-L7a-140-E7

+0 4T0ET+0 1.67FE+01 1.50E+01 TM

-22 29 Ba-La-140 5.98E-01 6.60E5+00 1.84F5+01 1-.750=+

TC 25 42 T1-31 579E+0T q4745+1 1T.5 6O.0E+u1 T

12 47 1-13 17ETT 2-ET+

6,14E+1 6.OE+01 T-

-- 47 W-131

-133E+1TT T801ET+0

-fE+M 2

6.0U0+1 TG 15 47 1-131 27+0 51E+

.854E+

+0E+

TG 21 47 1-1W 184E+0 E

1 1.7+2 6.00 ME+

__TG 14 77

-31 8.0_11+01 6.60E5+01

+

.9 26.00+1 Several other samples submitted to the second laboratory failed to meet the required LLDs, but the samples were not from locations required by the ODCM. Those missed LLD analyses are not included in this table. They were from locations voluntarily added as enhancements to the program. It should be noted that changes were made in the way that samples are prioritized at the vendor laboratory and during the month of December, delays in sample counting were minimized. That trend is continuing in the ensuing year.

6.3 Comparison of Results with Reporting Levels ODCM Section 10.3.4 requires written notification to the NRC within 30 days of receipt of an analysis result whenever a Reporting Level in ODCM Table 3.5.2 is exceeded.

Reporting Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I.

Environmental concentrations are averaged over the calendar quarters for the purposes of this comparison. The Reporting Levels are intended to apply only to measured levels of radioactivity due to plant effluents. During 2001, no analytical result exceeded a corresponding reporting level requirement in Table 3.5.2 of the ODCM.

62 eýAriaý ýyws NoM6e! Hn-6-'ýeR ýquir6d

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 200 1.

One sampling location was suggested in the Land Use Census assessment. A new dairy farm located on the east bank of the Connecticut River south in lower Hinsdale New Hampshire started operations in late summer, 2001. Subsequent evaluation of this new farm indicated that although it was not in "...at least a 20% greater dose commitment than the values currently being calculated in accordance with the ODCM Control 4.3.3.", it did rank as number two on the list of all farms included in the Land Use Census. With this in mind, we have attempted to establish a method of collecting sample from the bulk tank at this dairy since late in 2001. At this time, no samples have been obtained due to configuration of the bulk tank and deterioration of the bottom valve that prohibits opening the valve unless it is connected to a milk collection truck. During the last discussion with the farmers, they indicated that they were in the process of obtaining a new bulk tank with new valve. They hoped to have this tank in place by early summer of 2002. Following a successful trial sample collection from this farm, this new location will be added to the ODCM and routine samples will ensue.

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 has not previously been included in this report.

6.5 Data Analysis by Media Type The 2001 REMP data for each media type is discussed below. Whenever a specific measurement result is presented, it is given as the concentration plus or minus one standard deviation. This standard deviation represents only the random uncertainty associated with the radioactive decay process (counting statistics),

and not the propagation of all possible uncertainties in the analytical procedure. 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".

63

6.5.1 Airborne Pathways 6.5.1.1 Air Particulates 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 second year that the results for the on-site air particulate station, Gov. Hunt (AP

40) have been included.

Gross beta activity was detected in all air particulate filters that were analyzed. As noted in Section 6.1, one set of air particulate and charcoal filters was lost during the delivery process to the vendor laboratory.

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 with the exception of a single, relatively higher value obtained from one sample at AP-1 1(River Station). Also 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 unusual gross beta concentration identified on AP-11 during the first quarter of 2001. It can also 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 five 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 27 of 28 filter sets analyzed. K-40 was detected on a total of 2 out of 28 analyzed. Ra-226 was detected once out of 28. Th-228 and 232 were detected once each out of 28 analyzed. Nb-95, a plant related nuclide, was detected two times in 28 analyses. It is believed that this nuclide is a result of sample contamination at the analytical lab since this nuclide is not seen in plant effluents.

64

6.5.1.2 Charcoal Cartridges Charcoal cartridges from each of the seven air sampling sites were analyzed for 1-131 each time they were collected. The results of these analyses are summarized in Table 5.1. As in previous years, no 1-131 was detected in any charcoal cartridge. This is the second year that the results for the on-site air iodine sampling station, Gov. Hunt (CF-40) have been included.

6.5.2 Waterborne Pathways 6.5.2.1 River Water Aliquots of river water were automatically collected periodically from the Connecticut River downstream from the plant discharge area and hydro station, location WR-11.

Monthly grab samples were also collected at the upstream control location, also on the Connecticut River, location WR-21.

The composited samples at WR-I 1 were collected monthly and sent along with the WR-21 grab samples to the contracted environmental laboratory for analysis. Table 5.1 shows that gross-beta measurements were positive in 5 out of 12 indicator samples and 6 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 2000.

One sample had a very small amount of detectable Cs-134 (just 25% higher than the required LLD in Table 4.4) at 18.7 E+00 + 1.51E+00 pCi/liter. This nuclide is considered to be plant-related activity, however, subsequent samples failed to identify any further Cs-134.. Vermont Yankee has not made routine radioactive liquid releases to the Connecticut River since 1982.

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 Quarterly ground water samples were collected from four indicator locations (only one is required by VYNPS ODCM) and one control location during 2001. 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 12 out of 20 indicator samples and in 2 out of 5 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-1 1, were consistent with that detected in previous years. Naturally occurring Th-228 was also detected in one sample No other gamma-emitting radionuclides or tritium were detected in any 65

of the samples.

6.5.2.3 Sediment Semi-annual river sediment grab samples were collected from two indicator locations during 2001. 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 2001, 26 locations were sampled at SE-12 during each of the semi-annual collections. Two samples were collected at SE-Il during the year. As would be expected, naturally occurring Potassium-40 (K-40) was detected in all of the samples. Radium-226 (Ra-226) was detected in 44 of 56 samples. Thorium-228 (Th-228) was detected in 58 of 58 samples analyzed. Thorium-232 (Th 232) was detected 18 samples analyzed. Cesium-137 (Cs-137) was detected in 46 out of 56 of the indicator 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 although it often has been detected in recent years at very low levels. Co-60 is sometimes present at the North Storm Drain Outfall sampling location as a result of the presence of plant related radionuclides in the onsite storm drain system. See section 6.5.2.6 for more information.

6.5.2.4 Test Wells 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 2001. The test well locations are shown on Figure 4.1 and the results are summarized in Table 5.1 under the media category, Test Well (WT). In 2001, 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 20 to 130 pCi/kg.

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 66

2001 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 2001 for a total of 26 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-95, which is also designated by the plant as Manhole 12.

Water samples were taken from the storm drain system at various access points in 2001 including Manholes MH-8, MH-11H, MH-12A, MFH-13, and MH-14. Table 6-2 summarizes the analytical results of water samples from the storm drain system in 2001. Nb-95 was detected in trace amounts in just one of the samples. Naturally-occurring Th-228 was detected in three of the samples. Low levels of gross beta activity were detected in 21 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 are estimates of the total body and maximum organ dose equaling 3.2% and 1.6% of the corresponding Technical Specification dose limits respectively. Therefore, there was no significant dose impact from plant-related radionuclides in the storm drain system in 1998. The sampling conducted in 2001 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.

67

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 24/24 7.3 E3 (0.18-43.5)E3 MH-12 (SE-95)

K-40 24/24 1.0E4 (0.17-1.48)E4 MH-11F (SE-98)

Th-232 17/24 5.3 E 2 (1.06-8.47) E2 MH-1 IF (SE-98)

Th-228 23/24 4.7 E 2 (0.10-0.71) E3 MH-1IF (SE-98)

Mn-54 6/24 6.2 E 1 (1.7-11.5) E 1 MH-12 (SE-95)

Ra-226 19/24 1.2 E 3 (0..12-3.72) E 3 MH-12 (SE-95)

Cs-134 4/24 3.3 E 1 (1.2-4.8) E 1 MH-11E (SE-99)

Cs-137 20/24 1.6 E 3

(.015-5.2) E 3 MH-12 (SE-95)

Zn-65 6/24 1.4 E 2 (0.46-1.98)E 2 MH-12 (SE-95)

Ag-1 10m 1/24 2.2E 1 NA MH-12A (SE-92)

Co-57 1/24 2.7 E I NA MH-1iF (SE-98)

Sb-124 2/24 3.8 E 1 (1.48-6.08)E 1 MH-12 (SE-95)

Ru-103 1/24 3.OE 1 NA MH-12A (SE-92)

Nb-95 3/24 3.9 E 1 (2.6-5.7)E 1 MH-12A (SE-92)

Co-60 12/24 9.6 E 2 (0..13-2.94) E 3 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.

Table 6.2 Summary of Storm Drain System Water Sample Analyses*

Isotope No. Detected **

Mean Range Station With Highest (pCi/kg)

(pCi/kg)

Detected Concentration Gross Beta 21/26 4.1 EO (1.5-6.3)E0 MH-12A (WW-12)

Nb-95 1/26 7.4 E 0 NA MH-14 (WW-10)

Th-228 3/26 6.0 E0 (4.7-6.9) E 0 MH-14 (WW-10)

H-3 1/26 9.7 E 1 NA MH-14 (WW-10) 68 Radionuclides that were not detected in any sample are not listed The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations).

6.5.3 Ingestion Pathways 6.5.3.1 Milk Milk samples from cows or goats at several local farms were collected monthly during 2001.

Semi-monthly 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. Naturally-occurring Th-232 and Th-228 were detected in a few of the samples. Also expected was Sr-90. Sr-90 was detected in 21 out of 28 indicator samples and 3 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 1 of 124 samples in 2001. 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 A silage sample was collected from each of the required milk sampling stations during October.

Each of these was analyzed for gamma-emitting radionuclides and 1-131. As expected with all biological media, naturally-occurring K-40 was detected in all samples. Naturally-occurring Be-7 was also detected in 6 of the 7 samples. Th-228, also naturally-occurring, was detected in 3 of seven samples. Th-232, also naturally-occurring, was detected in 3 of seven samples. Bi-214, a naturally-occurring Ra-226 daughter, was detected in 3 of the 6 samples. Cs-137 was detected in 2 of seven samples. No 1-131 was detected in any sample.

69

6.5.3.3 Mixed Grass Mixed grass samples were collected at each of the air sampling stations on four occasions during 2001. As expected with all biological media, naturally-occurring K-40 and Be-7 were detected in all samples. Th-228 and Th-232 were detected in 4 and 3 of the 26 indicator stations samples.

Cs-137 was detected in 3 of the 24 indicator 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 27.2 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 inadvertently collected with the grass samples.

No other gamma emitting radionuclides were detected in any of the samples collected in 2001.

6.5.3.4 Fish Semiannual samples of fish were collected from two locations in the Spring and Fall of 2001.

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 again detected in this year's samples although it was not detected in year 2000. 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 2001 and previous years are typical of concentrations attributable to global nuclear weapons testing fallout.

Zn-65 was also identified in a fish sample from FH-21, the Rte.9 Bridge Control Sample point at a level of 71.3 + 20.2 pCi/Kg with an MDC of 63.3 pCi/kg. This value is 27% of the LLD for Zn-65 in Fish required in Table 4.4 (ODCM Table 4.5.1). The source of this activity is, of course, from the power production process. However, it is possible that the presence of Zn-65 may have been the result of cross-contamination from the analytical laboratory, since Zn-65 has not been seen in fish samples from Vermont Yankee in the past.

No other radionuclides were detected.

70

6.5.4 Direct Radiation Pathway Direct radiation was continuously measured at 53 locations surrounding the Vermont Yankee plant with the use of thermoluminescent dosimeters (TLDs). In 1999, DR-53 was added on the site boundary. The TLDs are collected every calendar quarter for readout at the environmental laboratory. The complete summary of data may be found in Table 5.3.

From Tables 5.2 and 5.3 and Figure 6.13, it can be seen that the Inner and Outer Ring TLD mean exposure rates were not significantly different in 2001. 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 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 DR-45 had a higher average exposure rate than any other station. This location is on-site, and the higher exposure rates are due to plant operations and activities in the immediate vicinity of this TLD.

There is no significant dose potential to the surrounding population or any real individual from these sources since they are located on the back side of the plant site, between the facility and the river. The same can be said for station DR-46, which has shown higher exposure rates in previous years.

71

Environmental Program Trend Graphs 2001 Radiological Environmental Operating Report Vermont Yankee Graphs:

6.1 - Gross Beta Measurements on Air Particulate Filters (Average Concentrations) 6.2 - Gross Beta Measurements on Air Particulate Filters (11) 6.3 - Gross Beta Measurements on Air Particulate Filters (12) 6.4 - Gross Beta Measurements on Air Particulate Filters (13) 6.5 - Gross Beta Measurements on Air Particulate Filters (14) 6.6 - Gross Beta Measurements on Air Particulate Filters (15) 6.7 - Gross Beta Measurements on Air Particulate Filters (40) 6.8 - Gross Beta Measurement on River Water (Average Concentrations) 6.9 - Gross Beta Measurement on Ground Water (Average Concentrations) 6.10 - Cesium-137 in Milk (Annual Average Concentrations) 6.11 - Strontium 90 in Milk (Annual Average Concentrations) 6.12 - Cesium-137 in Fish (Annual Average Concentrations) 6.13 - Exposure Rate at Inner Ring, Outer Ring, and Control TLDS 6.14 - Exposure Rate at Indicator TLDS, DR01-03 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 72

1 - Gross Beta ivMeasurements on Air Particulate F Concentrations rS - Q~uarterly Avel

-Indicator Stations mUControl Stations

-I---

I I

08/22/01

--4--AP-1I River Station --

AP-21 Spofford Lake NI-I 02/03101 03/25/01 05/14/01 07/03/01 10/11/01 11/30/01 01/1

Oss

--.AP-12 N. Hinsdale m-AP-21 Spofford Lake NH Aj

-AA

-*-AP-13 Hinsdale Substation ---

AP-21 Spofford Lake NH

-*-AP'-14 Northtield MA

-- AP-21 Spofford Lake NH

AP-15 Tyler Hill Road --

AP-21 Spofford Lake NH 2VV

AP-40 Governor Hunt House m AP-21 Spofford Lake NH

- i-igure 6.8 Gross Beta Measurements on River Water Semi-Annual Aver Conc

--46WR-1 1 River Station m-

-WR-21 Rt. 9 Bridge

m-igure o.9 ross Beta Measurements on Ground Water Semi Annual Average Concentrations Aiv' 41 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 20

WG-1 1 Plant Well WG-12 Vernon Nursing Well -&--WG-22 Skibniowsky Well--X-WG-13 COB Well-)--WG-14 Engineering Building mom Ig*

gs,*11"'W

1992 1.

1994 1998 1999 TM-11 Miller (cow)

TM-14 Brown (cow)

-ATM-18 Blodgett (Cow)

--- TM-22 Franklin (cow)

TM-25 Downey-Spencer (goat) ---

TM-26 Cheney Hill (cow) 2000 2001

-X-TM-24 County Farm (Control)

I

1991 1992 1993 1994 1995 1996 1997 1998 1999 4TM-11 Miller Farm (cow)

E TM-14 Brown Farm (cow)

A TM-18 Blodgett Farm (cow)

-TM-22 Franklin Farm (cow)

TM-25 Downey-Spencer (goat) ---

TM-26 Cheney Hill Farm (cow) 2000 2001 X

I M-24 County I-arm (Control)

-FH-11 Vernon Pond ---

FH-21 Rt. 9 Bridge (Control)

igure 6.13 - Exposure Rate at Inner Ring, Outer Ring and Control TLE

-4Control M-Inner Ring -s--Outer Ring

-4DR-01 River Station No. 3.3 MED

-02 North Hinsdale, NH At DR-03 Hinsdale Substation I

4 DR-06 Vernon School is DR-50 Gov. Hunt House r7?,

I

-DR-07 Site Boundary --a--DR-08 Site Boundaary -r-DR-41 Site Boundary --X-DR-42 Site Boundary

e Boundary -U-DR-44 Site Boundary ---

DR-45 Site Boundary -)-DR-46 Site Boundary S

it S

54S51/2i SSSStISSSSSSXSSSStSSSSSSSUS&

SiiSSiSiSSX

,.tr co Q0 0DR-43

- UD--47 Site Boundary0 DU-48 Site Boundary -ADR-49 Site Boundary -X---DR-51 Site Boundary

)K-DR-52 Site Boundary -DR-53 Site Boundary

TLDs DR09, 11, 13 & 15 I sDR-09 Inner Ring U-DR-11 Inner ng --A--DR-13 Inner Ring ---

DR-15 Inner Ring 77,Y.4AN~,4.

lOSUl

-DR-17 Inner Ring -m--DR-19 Inner Ring -A-DR-21 Inner Ring -X-DR-23 Inner Ring

(0 DR-25 Inner Ring --.- DR-27 Inner Ring A DR-29 Inner Ring x DR-31 Inner Ring I

I

"igure 6.22 - Expos (0

4 DR-33 Inner Ring m DR-35 Inner Ring A

DR-37 Inner Ring -X-DR-39 Inner Ring I

(D Cil s DR-100uterRing M DR-120uterRing A DR-140uterRing X

DR-160uterRin

C0 0) s4DR-18 Outer Ring -a--DR-20 Outer Ring -A-DR-22 Outer Ring -X--DR-24 Outer Ring V

a*

.%A.ina'

'nr.r

'W S4S444Sfl

(0

"-4I DuR-26 Outer Ring U DR-28 Outer Ring AtDR-30O outer Ring - -X-DR-32 Outer Ring

O0 s-DR-34 Outer Ring ---

DR-36 OuterRing --k-DR-38 Outer Ring -X-DR-40 Outer Ring

IsDR-04 Northfield, MA --M DR-05 Spofford Lake, NH a

4.,.aaaa aa.*.,..A6a,

2,.ss4tMt.a AA

7 QUALITY ASSURANCE PROGRAM 7.1 Duke Engineering and Services Laboratory (DE&S)

The quality assurance program at the Duke Engineering & Services Environmental Laboratory (DESEL) is designed to serve two overall purposes: 1) Establish a measure of confidence in the measurement process to assure the licensee, regulatory agencies and the public that analytical results are accurate and precise; and 2) Identify deficiencies in the sampling and/or measurement process to those responsible for these operations so that corrective action can be taken. Quality assurance is applied to all steps of the measurement process, including the collection, measurement and reporting of data, as well as the record keeping of the final results. Quality control, as part of the quality assurance program, provides a means to control and measure the characteristics of the measurement equipment and processes, relative to established requirements.

The DESEL employs a comprehensive quality assurance program designed to monitor the quality of analytical processing to ensure reliable environmental monitoring data. The program includes the use of controlled procedures for all work activities, a nonconformance and corrective action tracking system, systematic internal audits, audits by external groups, a laboratory quality control program, and a staff training program. Monitoring programs include the Intralaboratory Quality Control Program administered by the Laboratory QA Officer (used in conjunction with the National Institute of Standards and Technology Measurement Assurance Program, NIST MAP) and a third party interlaboratory program administered by Analytics, Inc. Together these programs are targeted to supply QC/QA sources at 5% of the client sample analysis load. In addition the Laboratory Quality Control Audit Committee administers a blind duplicate program conducted through client environmental monitoring programs.

This summary reports all interlaboratory known values or intralaboratory results received by DESEL on or before December 31, 2001.

7.1.1 Intralaboratory Quality Control Program The DESEL QA Officer administers an extensive intralaboratory quality control program in which process check samples are submitted for analysis. These samples are submitted either in duplicate to evaluate the precision of a measurement process or are "spiked" with a known amount of radioactive material to assess the bias in the measurement. Table 7.1.1 contains the summary of the process check results for January to December 2001. Of the analyses, 99% passed the bias criteria and 100% of the results evaluated for precision were acceptable.

7.1.2 Third Party Intercomparison Program The DESEL participates in a third party intercomparison program managed by Analytics Inc. to satisfy the requirement of the Environmental Technical Specification/ODCM. The DESEL Analytics program was originally used to augment the EPA Intercomparison Program that it now replaces. The current program is designed to be comparable to the pre-1996 EPA PE Program in terms of the number of 100

samples, matrices and nuclides. The results for the 4th quarter 2000 through the 3rd quarter 2001 are summarized in Table 7.1.2. Each sample is analyzed in triplicate and the results are evaluated against the acceptance criteria described in the DESEL Manual 100-Laboratory Quality Assurance Plan. The DESEL acceptance criteria is summarized at the end of Table 7.1.2. This acceptance protocol is used for all interlaboratory programs with no pre-set acceptance criteria. When results fall outside of the acceptance criteria, an investigation is initiated to determine the cause of the problem and if appropriate, corrective measures are taken.

Three Analytics results fell in the 'non-agreement' category and were under investigation for their failure at the time of this report.

7.1.3 Blind Duplicate Program The Laboratory Quality Control Audit Committee (LQCAC) is comprised of representatives from several New England DESEL clients. Two of the primary functions of the LQCAC have been to conduct an annual audit of Laboratory operations and to coordinate the Blind Duplicate Quality Assurance Program.

Under the Blind Duplicate Quality Assurance Program, samples are split from homogeneous environmental media by the client and sent to the DESEL for analysis. They are "blind" in that the identification of the matching sample is not identified to the Laboratory. The LQCAC analyses the results of the paired analyses to evaluate the precision of the Laboratory measurements.

Participating clients submitted a total of 31 paired samples in 2001. The measurements evaluated include twenty-five gamma emitting radionuclides, H-3, Sr-89, Sr-90, 1-131 and gross-beta. All measurements are evaluated, whether the results are statistically positive or not, and whether the net concentration is positive or negative. During 2001, 99.4% of the results passed the acceptance criteria.

The samples submitted as part of this program are listed in Table 7.1.3.

7.1.4 Environmental TLD Quality Assurance Program Performance documentation of the routine processing of the Panasonic environmental TLDs (thermoluminescent dosimeter) program at the DESEL 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 Group 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.

101

Eighty-four performance tests were conducted in 2001 by DESEL 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 84 100 100 Summary of Third Party Testing Dosimeter Type Exposure Period NVLAB Category Free in Air

% (Bias +/- SD) 1B3 + S*

Panasonic Environmental Q4/2000 IV, high energy

-1.7 +/-0.08 0.025 "Q1/2001 IV, high energy 8.8+/- 1.2 0.100 Q2/2001 IV, high energy

-2.9 +/- 1.3 0.042 Q3/2001 IV, high energy 6.4 +- 1.3 0.079 Note:

Results are expressed as the delivered exposure for environmental TLD. NVLAB Category IV, High energy photons (Cs-137 or Co-60).

American National Standards Institute (ANSI) Performance Statistic as referenced in the Dosimetry Services Semi-Annual QA Status Report.

102

TABLE 7.1.1 DESEL RESULTS IN THE INTRALABORATORY PROCESS CONTROL PROGRAM January - December 2001 Media Bias Criteria (1)

Precision Criteria (2)

Analysis 1

2 3

4 1

2 3

4

1. Air Particulate Alpha 9

0 0

0 9

0 0

0 Beta 3

3 3

0 9

0 0

0 Gamma 11 7

8 1

25 2

0 0

Sr89 0

0 2

3 3

0 2

0 Sr90 2

1 2

0 4

1 0

0 II. Milk Gamma 85 29 5

1 109 9

2 0

lodine-LL 7

5 0

0 11 1

0 0

Sr89 0

0 0

0 3

0 0

0 Sr90 3

0 0

0 3

0 0

0 IV. Water Gross Alpha 2

4 0

0 6

0 0

0 Gross Beta 1

2 2

1 3

1 2

0 Gamma 36 16 5

3 48 7

3 2

Tritium 4

1 1

0 4

1 0

0 Iodine-LL 4

1 1

0 4

2 0

0 Strontium-89 3

0 0

0 3

0 0

0 Strontium-90 3

0 0

0 3

0 0

0 Am-241 1

0 2

1 0

0 Cm-243/4 0

1 2

0 3

0 0

0 Np-237 0

0 2

1 0

2 1

0 Pu-238 2

1 0

0 3

0 0

0 Pu-239 2

1 0

0 2

1 0

0 Radium 226 3

0 0

0 3

0 0

0 Radium-228 3

0 0

0 3

0 0

0 Total Number in Range 184 72 35 13 294 29 10 2

% of Total Processed 60.5 23.7 11.5 4.3 96.7 11.4 3.3 0.7 Sum of Analyses 304 304 (I) Percent Bias Criteria by Bias Category Bias Category = 1 > 0% and <= 5%

Bias Category = 2 > 5% and <= 10%

Bias Category 3 > 10% and < = 15%, or within 2 sigma of known Gross alpha and beta, Sr 89190 > 10% and < = 25%

Transuranics > 10% and < = 20%

Bias Category = 4 Outside Criteria (2) Percent Precision Criteria by Precision Category Precision Category = 1 > 0% and < = 5%

Precision Category = 2 > 5% and < = 10%

Precision Category = 3 > 10% and < = 15%, or within 2 sigma of mean Precision Category = 4 Outside Criteria 103

TABLE 7.1.2 DESEL 2001 ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample Reported Known DESEL/

Number Year Media Nuclide Units Value Value Analytics Evaluation E2477-162 4th/00 Filter Sr-89 pCi 59.57 85 0.70 Non-Agreement

E2477-162 4thl00 Filter Sr-90 pCi 42.4 41 1.03 Agreement E2478-162 4th/00 Filter Gross Alpha pCi 20.27 21 0.97 Agreement E2478-162 4th/00 Filter Gross Beta pCi 136.07 114 1.19 Agreement E2479-162 4th/00 Water H-3 pCi/L 9656.67 10082 0.96 Agreement E2480-162 4thf00 Milk 1-131 pCi/L 86.23 85 1.01 Agreement E2480-162 4th/00 Milk 1-131LL pCi/L 88.87 85 1.05 Agreement E2480-162 4th/00 Milk Ce-141 pCi/L 361.63 356 1.02 Agreement E2480-162 4th/00 Milk Cr-51 pCi/L 521.33 503 1.04 Agreement E2480-162 4th/00 Milk Cs-1 34 pCi/L 84.27 85 0.99 Agreement E2480-162 4th/00 Milk Cs-1 37 pCi/L 203.77 199 1.02 Agreement E2480-162 4th/00 Milk Co-58 pCi/L 79 76 1.04 Agreement E2480-162 4th/00 Milk Mn-54 pCi/L 161.5 152 1.06 Agreement E2480-162 4th/00 Milk Fe-59 pCi/L 92.6 82 1.13 Agreement E2480-162 4th/00 Milk Zn-65 pCi/L 147.63 148 1.00 Agreement E2480-162 4th/00 Milk Co-60 pCi/L 184.63 184 1.00 Agreement E2592-162 Ist/O1 Water 1-131 pCi/L 88 90 0.98 Agreement E2592-162 I st/O1 Water 1-131 LL pCiIL 89 90 0.99 Agreement E2592-162 1st/O1 Water Ce-141 pCi/L 100 94 1.06 Agreement E2592-162 1st/O1 Water Cr-51 pCi/L 236 242 0.98 Agreement E2592-162 1st/01 Water Cs-1 34 pCi/L 120 129 0.93 Agreement E2592-162 1st/01 Water Cs-137 pCiIL 97 102 0.95 Agreement E2592-162 lstIO1 Water Co-58 pCi/L 48 48 1.00 Agreement E2592-162 1st/O1 Water Mn-54 pCi/L 103 101 1.02 Agreement E2592-162 1st/O1 Water Fe-59 pCi/L 88 84 1.05 Agreement E2592-162 1st/O1 Water Zn-65 pCi/L 187 186 1.01 Agreement E2592-162 1st/O1 Water Co-60 pCi/L 144 147 0.98 Agreement E2593-162 1st/01 Water Gross Alpha pCi/L 40 39 1.03 Agreement E2593-162 1st/01 Water Gross Beta pCi/L 300 268 1.12 Agreement E2598A-162 1st/01 Filter Gross Alpha pCi 30 30 1.00 Agreement E2598A-162 1st/01 Filter Gross Beta pCi 229 211 1.18 Agreement E2595-162 Ist/O1 Milk 1-131 pCifL 78 77 1.01 Agreement E2595-162 1st/O1 Milk 1-131LL pCi/L 74 77 0.96 Agreement E2595-162 1st/01 Milk Ce-141 pCi/L 166 162 1.02 Agreement E2595-162 Ist/01 Milk Cr-51 pCi/L 455 418 1.09 Agreement E2595-162 1st/O1 Milk Cs-134 pCi/L 217 223 0.97 Agreement

CR 01-16 Issued, Sr-89:90 ratio below DESEL standard 1:1 requirement.

104

TABLE 7.1.2 (continued)

DESEL 2001 ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample Reported Known DESELI Number Year Media Nuclide Units Value Value Analytics Evaluation E2595-162 1st/01 Milk Cs-1 37 pCi/L 173 176 0.98 Agreement E2595-162 1 st/01 Milk Co-58 pCi/L 86 82 1.05 Agreement E2595-162 1st/O1 Milk Mn-54 pCi/L 185 175 1.06 Agreement E2595-162 1st/O1 Milk Fe-59 pCi/L 151 146 1.03 Agreement E2595-162 1st/O1 Milk Zn-65 pCi/L 328 322 1.02 Agreement E2595-162 1st/O1 Milk Co-60 pCi/L 252 254 0.99 Agreement E2597-162 1st/O1 Water Am-241 pCi/L 5.6 6.0 0.93 Agreement E2597-162 1st/O1 Water Pu-238 pCiIL 7.2 7.5 0.96 Agreement E2597-162 1 st/01 Water Pu-239 pCi/L 5.5 5.5 1.00 Agreement E2597-162 1st/01 Water Np-237 pCi/L 9.6 7.9 1.22 Non-Agreement (1)

E2597-162 1st/01 Water Cm-244 pCi/L 5.6 6.3 0.89 Agreement E2594-162 1st/01 Water Ra-226 pCi/L 51 50 1.02 Agreement E2594-162 1st/01 Water Ra-228 pCi/L 63 63 1.00 Agreement E2670-162 2ndl01 Milk 1-131 pCi/L 63 69 0.91 Agreement E2670-162 2nd/01 Milk 1-131 LL pCi/L 66 69 0.96 Agreement E2670-162 2nd/01 Milk Ce-141 pCi/L 165 163 1.01 Agreement E2670-162 2nd/01 Milk Cr-51 pCi/L 228 224 1.02 Agreement E2670-162 2nd/01 Milk Cs-134 pCi/L 131 134 0.98 Agreement E2670-162 2nd/01 Milk Cs-1 37 pCiIL 128 121 1.06 Agreement E2670-162 2nd/l01 Milk Co-58 pCi/L 97 96 1.01 Agreement E2670-162 2nd/01 Milk Mn-54 pCi/L 154 150 1.03 Agreement E2670-162 2nd/01 Milk Fe-59 pCi/L 91 88 1.03 Agreement E2670-162 2nd/01 Milk Zn-65 pCi/L 180 182 0.99 Agreement E2670-162 2nd/01 Milk Co-60 pCi/L 138 135 1.03 Agreement E2666-162 2nd/01 Filter Ce-141 pCi/L 91 96 0.95 Agreement E2666-162 2nd/01 Filter Cr-51 pCiIL 130 132 0.98 Agreement E2666-162 2nd/01 Filter Cs-1 34 pCi/L 74 79 0.94 Agreement E2666-162 2nd/01 Filter Cs-1 37 pCi/L 77 71 1.08 Agreement E2666-162 2nd/01 Filter Co-58 pCi/L 57 57 1.00 Agreement E2666-162 2nd/01 Filter Mn-54 pCi/L 99 88 1.13 Agreement E2666-162 2nd/01 Filter Fe-59 pCi/L 58 51 1.14 Agreement E2666-162 2nd/01 Filter Zn-65 pCi/L 118 107 1.10 Agreement E2666-162 2nd/01 Filter Co-60 pCi/L 77 79 0.97 Agreement E2669-162 2nd/01 Water H-3 pCi/L 7007 7494 0.94 Agreement E2667-162 2nd/01 Filter Sr-89 pCi 89 84 1.06 Agreement E2667-162 2nd/01 Filter Sr-90 pCi 75 64 1.17 Agreement E2806-162 3rd/01 Water 1-131 pCi/L 63 60 1.05 Agreement (1) - Np-237 failed high due to glassware contamination. CR 0141 issued.

105

TABLE 7.1.2 (continued)

DESEL 2001 ANALYTICS RADIOLOGICAL ENVIRONMENTAL CROSS-CHECK PERFORMANCE EVALUATION Ratio Sample Quarter/ Sample Reported Known DESEL/

Number Year Media Nuclide Units Value Value Analytics Evaluation E2806-162 3rd/01 Water 1-131LL pCi/L 62 60 1.04 Agreement E2806-162 3rd/01 Water Ce-141 pCi/L 96 88 1.09 Agreement E2806-162 3rd/01 Water Cr-51 pCi/L 275 265 1.04 Agreement E2806-162 3rd/01 Water Cs-1 34 pCi/L 113 116 0.97 Agreement E2806-162 3rd/01 Water Cs-1 37 pCi/L 234 232 1.01 Agreement E2806-162 3rd/01 Water Co-58 pCi/L 132 128 1.03 Agreement E2806-162 3rd/01 Water Mn-54 pCi/L 153 149 1.03 Agreement E2806-162 3rd/01 Water Fe-59 pCiiL 66 62 1.06 Agreement E2806-162 3rd/01 Water Zn-65 pCi/L 184 184 1.00 Agreement E2806-162 3rd/01 Water Co-60 pCi/L 195 193 1.01 Agreement E2805-162 3rd/01 Water Gross Alpha pCi/L 84 78 1.08 Agreement E2805-162 3rd/01 Water Gross Beta pCi/L 175 205 0.85 Agreement E2808-162 3rd/01 Filter Gross Alpha pCi 51 50 1.02 Agreement E2808-162 3rd/l01 Filter Gross Beta pCi 136 133 1.02 Agreement E2809-162 3rd/01 Milk 1-131 pCi/L 90 91 0.99 Agreement E2809-162 3rd/01 Milk 1-131LL pCi/L 91 91 1.00 Agreement E2809-162 3rd/01 Milk Ce-141 pCi/L 131 121 1.08 Agreement E2809-162 3rd/01 Milk Cr-51 pCiIL 374 366 1.02 Agreement E2809-162 3rdl01 Milk Cs-134 pCi/L 157 160 0.98 Agreement E2809-162 3rd/01 Milk Cs-137 pCi/L 323 319 1.01 Agreement E2809-162 3rd/01 Milk Co-58 pCi/L 182 177 1.03 Agreement E2809-162 3rd/01 Milk Mn-54 pCi/L 211 205 1.03 Agreement E2809-162 3rd/l01 Milk Fe-59 pCi/L 87 86 1.01 Agreement E2809-162 3rdl01 Milk Zn-65 pCi/L 261 254 1.03 Agreement E2809-162 3rd/01 Milk Co-60 pCi/L 274 266 1.03 Agreement E2807-162 3rd/01 Water Sr-89 pCi/L 87 85 1.02 Agreement E2807-162 3rd/01 Water Sr-90 pCi/L 61 59 1.03 Agreement E2810-162 3rd/01 Milk Sr-89 pCi/L 121 75 1.61 Non-Agreement (2)

E2810-162 3rd/l01 Milk Sr-90 pCi/L 49 50 0.98 Agreement (2) - Sr-89 failed high, investigation ongoing. CR 02-01 issued.

106

TABLE 7.1.3

SUMMARY

OF BLIND DUPLICATE SAMPLES SUBMITTED TO THE DESEL January - December 2001 TYPE OF SAMPLE NUMBER OF PAIRED SAMPLES SUBMITTED Milk 8

Ground Water 2

Surface Water 14 Algae 2

Mussels 4

Food Product 1

TOTAL 31 FAILURES / TOTAL ANALYSIS TYPE ANALYSES Gamma 4/775 Gross Beta 1/5 1-131 low level 0/8 Sr-89 0/4 Sr-90 0/4 H-3 0/5 TOTAL 5/801 107

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 bioassay, effluent (10CFR Part 50), and waste characterization (1 OCFR 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).

The last year that EPA provided drinking water Performance Evaluation (PE) samples for analysis was 1998. Anticipating the elimination of the EPA's Interlaboratory Cross Check Program, TBE-ES instituted a replacement cross-check program that is managed by Analytics, Inc and ERA. The overall scope of the Analytics and ERA replacement programs was designed to be comparable with the pre-1996 US EPA PE Program in terms of sample number, matrices and nuclides. On May 20, 2001, NIST NVLAP granted accreditation to ERA's Proficiency Testing Program, which completed the process of replacing the US EPA EMSL-LV Nuclear Radiation Assessment Division program discontinued in 1998. The number of samples evaluated by media type between air filters, water and milk was modified from the post-1996, predominantly drinking water-based EPA Program. This considered an enhancement to the Cross-Check program since it better reflects the clients' radiological environmental Monitoring Program (REMP) media mix presently processed by TBE-ES 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, NYELAP and the Bioassay Environmental Radioactivity Cross Check Program (BERCCP).

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) 108

are either actual samples submitted in duplicate in order to evaluate the accuracy of laboratory measurements, or blank samples which have been "spiked" with a known quantity of a radioisotope that is of interest to laboratory clients. These QC samples which represent either "single" or "double-blind" unknowns, are intended to evaluate the entire radiochemical and radiometric process.

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

7.2.1.3 QA Program (Internal and External Audits)

During each reporting period at least one internal assessment is conducted in accordance with the pre-established TBE-ES Quality Control and Audit Assessment Schedule. In addition, the laboratory may be audited by prospective customers during a pre-contract audit, and/or by existing clients who wish to conduct periodic audits in accordance with their contractual arrangements. The Nuclear Utilities Procurement Issues Committee (NUPIC) conducts audits of TBE-ES as a function of a Utilities Radiological Environment Measurement Program (REMP).

Since relocating from Westwood, New Jersey to Knoxville, Tennessee, the laboratory has hosted the NUPIC, Vermont Yankee Nuclear Power Station, Nebraska Public Power, BWX Technologies, the State of Tennessee, Westinghouse, Inc. the National Laboratory Accreditation Program (NELAP), Boeing Rocketdyne and others for onsite audits. These audits were each comprehensive reviews of TBE-ES's Quality and Technical programs used to assess the laboratory's ability to produce accurate and defensible data for our clients. 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.

109

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, thirty-five nuclides associated with eight media types were analyzed by means of the Laboratory's internal process control, Analytics, DOE, ER, NYELAP and Bioassay Cross Check 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 Attachment A. Below is a synopsis of the media types evaluated:

Air Filter Charcoal (Air Iodine)

Gas Milk Sediment/Soil Urine Vegetation Water 7.2.2.1.2 Analytics Environmental Cross-Check Program During this semi-annual period, the Analytics Cross-Check Program provided environmental samples for bias and precision checks.

7.2.2.1.3 Summary of Participation in the Department of Energy (DOE) Monitoring Programs During this reporting period, a combination of four different media types and twenty-one different radionuclides were analyzed against the DOE Quality Assessment Program (DOE QAP 9909). There were two "non-agreement" evaluations reported for total Uranium in filters. Upon review of the reported filter matrix, it was determined that the reported evaluation units were incorrect.

When the correct units of Bq/filter were calculated and compared, the results were acceptable. Thirteen warnings were issued for several radionuclides and matrices as shown in the attached tables.

TBE-ES participated in the semi annual Mixed Analyte Performance Evaluation Program (MAPEP) for liquid analyses (MAPEP-00-W8). All seven analytes evaluated were acceptable. For soil analysis, (MAPEP-01-S8) all eight analytes evaluated were acceptable.

7.2.2.1.4 Summary of Participation in the NYELAP During this reporting period, water media for three nuclides were analyzed for the NYELAP. Two results were acceptable and one result was not acceptable. A Non Conformance Report investigation determined that a calculation error had occurred. When corrected the results were within warning limits.

110

7.2.2.1.5 Summary of participation in the ERA Program During this reporting period, a water media of thirteen nuclides was analyzed under ERA criteria. All results were acceptable.

7.2.2.1.6 Summary of participation in the BERCCP During this reporting period, one media type and two nuclides were analyzed utilizing BERCCP criteria. All results were acceptable.

7.2.2.2 Intra-Laboratory Process Control Program The TBE-ES Laboratory's internal process control program evaluated 1158 individual samples.

Of the 1158 internal process control analyses evaluated, 34 spikes failed the laboratory's QC acceptance criteria of 70% - 130% recovery. Non Conformance Reports were issued to investigate the cause and determine corrective action for identified failures.

7.2.2.2.1 Analytical Blanks During this reporting period, all but one of the 579 environmental analytical blanks analyzed reported no statistically positive activity.

7.2.2.2.2 Instrument Backgrounds One hundred percent of the backgrounds processed between January and December 2001 reported no statistically significant positive activity.

7.2.2.2.3 Control Charts Control Charts for gamma instrumentation are prepared and maintained.

7.2.2.2.4 Duplicates All forty-five duplicate sets analyzed were within client requirements.

111

Table 7.2.1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)

Identification Reported Known Ratio Month/Year Number Matrix Nuclide Units Value Value TBE/Analytics Evaluation March, 2001 May, 2001 E2584-93 Milk 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 A14428-55 Water Sr-89 Sr-90 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 75 166 433 212 165 81 172 151 314 254 77 162 418 223 176 82 175 146 322 254 uCi/mL 2.50E-03 2.95E-03 uCi/mL 2.OOE-04 2.27E-04 A14429-55 Water Gr-Alpha uCi/mL 1.70E-04 1.45E-04 Al 4434-55 Water Fe-55 June, 2001 August, 2001 August, 2001 August, 2001 2707 2708 2709 Charcoal Charcoal Charcoal E2755-396 Milk E2757-396 AP Filter E2756A-396 Charcoal 1-131 1-131 1-131 Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Cs-1 34 Cs-1 37 Ce-141 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 1-131 uCi/mL 2.40E-04 2.53E-04 pCi pCi pCi pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi 112 104.5 84.8 99.6 131 68 53 134 172 76 141 126 72 79 100 109 140 72 161 51 200 148 81 72 92 124 68 50 132 162 86 128 120 76 74 90 125 116 66 134 49 158 128 87 93 0.97 1.03 1.04 0.95 0.94 0.99 0.98 1.03 0.98 1.00 0.85 0.88 1.17 0.95 1.29 1.18 1.08 1.06 1.00 1.06 1.02 1.06 0.88 1.10 1.05 0.95 1.07 1.11 0.87 1.21 1.09 1.20 1.04 1.27 1.16 0.94 A

A A

A W

A A

W A

A A

W A

A

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 Month/Year Number Matrix Nuclide Units Value Value TBE/Analytics Evaluation September, 2001 A14734-148 Liquid September, 2001 A14735-148 Gas September, 2001 A14736-148 Charcoal September, 2001 A14737-148 Air Filter September, 2001 E2772-396 Milk September, 2001 E2773-396 September, 2001 E2774-396 Sr-89 Total uCi 1.30E-03 1.55E-03 Sr-90 Total uCi 1.OOE-04 1.12E-04 Xe-1 33 Total uCi 0.606 Kr-85 Total uCi 8.53 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 1-131 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 Air Filter Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Total uCi 0.483 Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi Total uCi pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 4.99E-02 1.68E-01 2.47E-02 5.18E-02 4.60E-02 3.96E-02 2.99E-02 5.22E-02 4.71 E-02 100 126 349 147 321 190 205 85 246 261 68.6 68.6 pCi pCi pCi pCi pCi pCi pCi pCi pCi 118 362 135 350 184 230 100 305 267 0.585 8.42 0.495 5.25E-02 1.85E-01 2.97E-02 5.73E-02 4.75E-02 4.02E-02 2.92E-02 5.12E-02 4.83E-02 91 121 366 160 319 177 205 86 254 266 67 116 351 153 307 170 197 82 244 255 113 0.84 0.89 1.04 1.01 0.98 0.95 0.91 0.83 0.90 0.97 0.99 1.02 1.02 0.98 1.10 1.04 0.95 0.92 1.01 1.07 1.00 0.99 0.98 0.98 1.02 1.02 1.03 0.88 1.14 1.08 1.17 1.22 1.25 1.05 A

A A

W W

A

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 Month/Year Number Matrix Nuclide Units Value Value TBE/Analytics Evaluation September, 2001 A14738-148 Liquid September, 2001 A14286-148 Liquid December, 2001 December, 2001 December, 2001 December, 2001 E2980-396 E-2981-396 E-2983-396 Milk Milk Gr-Alpha Total uCi 5.80E-04 4.67E-04 Gr-Alpha uCi/cc 1.70E-04 1.45E-04 H-3 uCi/cc 2.92E-03 1.77E-03 Sr-89 Sr-90 Fe-55 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Air Filter Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E-2982-396 Charcoal 1-131 pCiJL pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi 75 44 108 50 352 468 173 312 92 148 101 192 322 185 190 74 163 46 80 57 119 165 85 59 99 61 379 497 199 318 90 149 102 206 353 181 237 95 152 43 71 49 99 169 89 92 114 1.24 1.17 1.65 0.96 0.75 1.09 0.82 0.93 0.94 0.87 0.98 1.02 0.99 0.99 0.93 0.93 1.02 0.80 0.78 1.07 1.07 1.13 1.16 1.2 0.98 0.93 A

A A

A W

A A

A W

A A

A

Table 7.2.2 DOEIEML ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 3)

Identification Reported Known Ratio Month/Year Number Media Nuclide Units Value Value TBE/EML Evaluation QAP 103 Air Filter Mn-54 Co-60 Cs-1 34 Cs-1 37 Pu-238 Pu-239 Am-241 Gr-Alpha Gr-Beta Sr-90 QAP 103 Soil K-40 Cs-137 Pu-239/40 Sr-90 March, 2001 March, 2001 March, 2001 March, 2001 May, 2001 Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/kg Bq/kg Bq/kg Bqfkg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/L Bq/L Bq/L Bq/L BqfL Bq/L Bq/L Blq/L Bq/L 6.96 19.4 2.59 9.52 0.23 0.17 0.93 3.33 2.26 7.46 464.8 1696 24.32 80.8 728 34 1005 10.54 7.03 2.26 1283 100.3 75.8 1600 1200 1.78 1.99 2.2 4.57 61.0 6.52 19.44 2.83 8.76 0.215 0.136 0.486 3.97 2.58 7.1 468 1740 25.6 69 603 30.4 842 9.58 6.17 3.69 1330 98.2 73 1900 1297 1.58 1.64 1.67 4.4 79.3 1.07 1.00 0.92 1.09 1.07 1.25 1.91 0.84 0.88 1.05 0.99 0.97 0.95 1.17 1.21 1.12 1.19 1.10 1.14 0.61 0.96 1.02 1.04 0.84 0.93 1.13 1.21 1.32 1.04 0.77 A

A A

W W

A W

A A

W A

A A

W W

W A

W 115 QAP 103 Vegetation K-40 Co-60 Cs-1 37 Pu-239 Am-241 Cm-244 Sr-90 QAP 103 Water Co-60 Cs-1 37 Gr-Alpha Gr-Beta Pu-238 Pu-239 Am-241 Sr-90 H-3

Table 7.2.2(cont.)

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

Identification Reported Known Ratio Month/Year Number Media Nuclide Units Value Value TBE/EML Evaluation QAP 2009 Air Filters Mn-54 Co-57 Co-60 Cs-1 37 Gr-Alpha Gr-Beta QAP 2009 Soil K-40 Cs-1 37 Pb-212 Bi-214 Pb-214 Ac-228 U-234 U-238 June, 2001 June, 2001 June, 2001 June, 2001 Air Filters Mn-54 Co-60 Sr-90 Cs-1 34 Cs-1 37 Pu-238 Pu-239 Am-241 Gr-Alpha Gr-Beta September, 2001 QAP 0109 Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/L Bq/L Bq/L Bq/L Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter Bq/filter QAP 2009 Vegetation K-40 Co-60 Cs-1 37 QAP 2009 Water Co-60 Cs-1 37 U-234 U-238 1.15 1.05 1.04 1.11 0.98 1.18 1.18 1.14 1.20 1.01 1.08 1.06 0.75 0.75 1.29 1.05 1.10 1.03 1.03 0.81 0.87 49.5 15.2 8.79 8.26 2.31 1.79 839.2 1164 95.5 84.0 92.9 84.8 117 122 827.4 34.4 949.4 75.7 69.3 0.39 0.32 97.1 18.8 2.56 12.7 20.8 0.0595 0.287 0.089 5.42 12.0 43.2 14.5 8.43 7.41 2.35 1.52 713 1020 79.3 83.3 86.3 80.2 157 163 639 32.8 867 73.7 67.0 0.481 0.368 81.15 17.5 3.481 12.95 17.1 0.071 0.2291 0.088 5.362 12.77 A

A A

A W

W W

A A

W W

A A

W A

W W

W A

A A

1.197 1.074 0.735 0.981 1.216 0.838 1.253 1.011 1.011 0.94 116

Table 7.2.2(cont.)

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

Identification Reported Known Ratio Month/Year Number Media Nuclide Units Value Value TBE/EML Evaluation September, 2001 QAP 0109 September, 2001 QAP 0109 September, 2001 QAP 0109 Soil K-40 Sr-90 Cs-1 37 Pu-239 Vegetation K-40 Co-60 Sr-90 Cs-1 37 Pu-239 Water H-3 Co-60 Ni-63 Sr-90 Cs-1 37 Pu-238 Pu-1 39 Am-241 Gr-Alpha Gr-Beta Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bqlkg Bq/kg Bq/kg Bqlkg Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 673.0 29.6 680.5 7.42 1090.0 39.8 1253.0 1235.0 11.6 212.3 207.3 50.7 4.76 47.7 1.21 1.86 0.763 1333.0 8533.0 623.33 30.596 612.33 8.948 898.67 35.3 1612.8 1030.0 11.022 207.0 209.0 45.25 3.729 45.133 1.0882 1.628 0.7597 1150.0 7970.0 1.080 0.967 1.111 0.829 1.213 1.127 0.777 1.199 1.052 1.026 0.992 1.1 1.276 1.057 1.112 1.143 1.004 1.159 1.071 A

A A

W A

A A

A W

W A

117

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 Ratio Month/Year Number Media Nuclide Units Value Value TBE/EML Evaluation February, 2001 Rad-29 September, 2001 Rad-38 August, 2001 Rad-39 September, 2001 Rad-40 August, 2001 Rad-41 September, 2001 Rad-42 December, 2001 12130109 Liquid Co-60 Cs-1 34 Cs-1 37 Liquid Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L Liquid Total U pCi/L Ra-226 pCi/L Liquid Sr-89 Sr-90 pCi/L pCi/L Liquid Gr-Alpha pCi/L Gr-Beta pCi/L Liquid H-3 pCi/L Liquid 1-131 95.5 91.1 60.5 59.8 48 45 35.5 47.6 15.5 206 35.4 36 46.8 15.9 197 36.2 60.3 52.9 14.7 15.4 26.4 31.2 28.2 25.9 15.2 17.8 52.0 53.0 2370 2730 pCi/L 3.77 4.38 118 1.05 1.01 1.07 0.99 1.02 0.97 1.05 0.98 1.14 0.95 0.85 1.09 0.85 0.98 0.87 0.86 A

A A

A

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

Identification Reported Known Acceptance Month/Year Number Matrix Nuclide Units Value Value Range Evaluation March, 2001 November, 2001 00-W8 01-S8 01-S8 Liquid Mn-54 Co-57 Co-60 Zn-65 Cs-1 34 Cs-1 37 Zn-65 Soil Soil Mn-54 Co-57 Co-60 Zn-65 Cs-1 34 Cs-1 37 Ni-63 Sr-90 Bq/L Bq/L Bq/L Bq/L Bq/L BqIL BqIL Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bqlkg Bq/kg Bq/kg 3.04 92.4 2.20 4.65 260 91.5 4.65 217 97.2 1280 408.3 87.4 1233 569 170 2.87 95.5 2.19 4.59 283 94.4 4.59 203 103 1270 382 91.1 1240 550 2.01-3.73 66.85-124.15 1.53-2.85 3.21-5.97 198.1 -367.9 66.08 - 122.72 3.21-5.97 142.1-263.9 72.10-133.9 889-1651 267.4-496.6 63.77-118.43 868-14612 385-715 209 146.3-271.7 119 A

A A

Table 7.2.5 NYELAP ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE 1 OF 1)

Identification Reported Known Acceptance Month/Year Number Matrix Nuclide Units Value Value Range Evaluation May, 2001 4218 Water Gr-Alpha pCi/L 33.8 41 20.5-61.5 A

Gr-Beta pCiIL 73.9 68 47.6 - 88.4 A

120

Table 7.2.6 BIOASSAY ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE QC SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (PAGE I OF 1)

Identification Reported Known Ratio Month/Year Number Matrix Nuclide Units Value Value TBE/WZ Evaluation July, 2001 Urine Cs-137 pCi/g 48.2 46.8 1.03 A

Cs-137 pCi/g 91.3 93.6 0.98 A

Cs-137 pCilg 613 612 1.00 A

Co-60 pCi/g 39.6 38.1 1.04 A

Co-60 pCilg 79.6 77.1 1.03 A

Co-60 pCi/g 544 560 0.97 A

121

8.

Land Use Census VYNPS Off-site Dose Calculation Manual 3/4.5.2 requires that a Land Use Census be conducted annually between the dates of June 1 and October 1. The Census identifies the locations of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of five miles of the plant. It also identifies the nearest milk animal (within three miles of the plant) to the point of predicted highest annual average D/Q value due to elevated releases from the plant stack in each of the three major meteorological sectors. The 2001 Land Use Census was conducted in August of 2001 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 1 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. For the 2001 Census, no such locations were identified.

Pursuant to ODCM 3.5.2.a, a dosimetric analysis is performed, using site specific meteorological data, to determine which milk animal locations would provide the optimal sampling locations. If any location has a 20% greater potential dose commitment than at a currently sampled location, the new location is added to the routine environmental sampling program in replacement of the location with the lowest calculated dose (which is eliminated from the program). The 2001 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 ranking of all farms included in the Land Use Census yielded a new farm, Ameral/McGovern that ranked number two out of numbers 1, 3, 4, 5, 7 and 9. A recommendation was made to add this farm to the collection program if possible. The farm owners were contacted and were agreeable to allowing Vermont Yankee to collect milk samples from their dairy, however, at this time, no sample has been collected due to bulk tank equipment malfunctions. A new bulk tank is due to be installed in the spring/summer of 2002 and, following successful test collections, the farm will be added to the ODCM as a required sample location.

The results of the 2001 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.

122

TABLE 8.1 2001 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 W

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.

123

9.

SUMMARY

During 2001 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 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 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.

124

10. REFERENCES

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

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

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

4. Kathren, Ronald L., Radioactivity and the Environment - Sources, Distribution, and Surveillance, 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 Groundwater Migration, February 1983.

125

Appendix A Review and Explanation of Questionable Data Listed in the Year 2000 VYNPS Annual Radioloeical Environmental Qperating Repot During the preparation of data for inclusion in the year 2000 Vermont Yankee Annual Radiological Environmental Operating Report, it was determined that a small subset of data was questionable, based upon known plant release information and the thirty year history of environmental monitoring in the Vermont Yankee environs. This data was listed in the year 2000 report as "Questionable" and a commitment was made to review the data and provide a summary of this review as part of the year 2001 report.

This appendix provides Table 1, a listing of the questionable data as it appeared in the year 2000 report, and Table 2, a review of each questionable datum by the environmental laboratory.

In summary, the large majority of questionable data was eventually determined to be erroneous and the nuclides previously specified as detected, now classified as not detected. The remaining data that is determined to be accurate appears to be possibly linked to cross-contamination of samples during the sample prep process at the vendor lab. The vendor laboratory is involved in analysis of samples from many different sources.

In any event, the presence of these radionuclides in the Vermont Yankee environment has not been confirmed by resample.

126

Appendix A, Table 1 Questionable Data Eliminated from Year 2000 Table 5.1 Summary I

Year Test I

Activity 1 Std Dev 2000 CO-57 1.66E+01 1.46E+00 Media Station Week TM 11 31 31 31 TM 14 25 25 25 TM 16 33 TM 16 38 TM 22 29 TM 22 31 TM 24 33 33 TM 26 27 AP 15 2nd Qtr EU-154 ZR-95 NB-95 NP-239 ZR-95 MO-99 CR-51 MO-99 CO-60 CO-60 MO-99 MO-99 3.08E+01 1.83E+01 3.50E+00 4.40E+03 6.50E+00 2.90E+01 3.96E+03 1.30E+01 4.87E+00 3.30E+00 6.30E+01 1.40E+02 3.11E+00 4.01E+00 1.OOE+00 9.OOE+02 2.OOE+00 7.50E+00 1.30E+03 4.OOE+00 1.24E+00 1.05E+00 1.70E+01 3.55E+01 IMDC 4.35E+00

9.07E+00

9.62E+00

3.00E+00 3.OOE+03

7.OOE+O0

3.OOE+01 3.75E+03 1.OOE+01 Duplicate at 1st lab - ND 4.16E+00 Duplicate at 1st lab - ND 4.OOE+00 Control location 6.OOE+01 Control location 1.00E+02 2000 CO-60 9.80E-04 1.95E-04 8.OOE-04 WG 11 32 2000 2000 WG 12 32 2000 2000 WG 14 32 2000 2000 2000 2000 2000 2000 WG 22 32 2000 SE 14 17 2000 2000 SE 18 17 2000 2000 SE 24 17 2000 SE 25 17 2000 2000 2000 SE 35 17 2000 SE 39 17 2000 SE 44 17 2000 2000 SE 49 17 2000 SE 50 17 2000 WR 11 33 2000 2000 WR 21 29 2000 2000 WR 21 33 2000 FH 11 19 2000 2000 2000 2000 WT 14 14 2000 WW 10 23 2000 WW WW 10 12 31 15 ND means not detected 2000 2000 CS-137 MO-99 CS-137 CO-60 CS-137 EU-154 AG-110M CO-57 CO-60 SE-75 CS-137 CO-57 EU-154 CO-57 EU-154 NB-95 CO-57 EU-154 NB-95 CO-57 NB-95 CO-57 EU-154 NB-95 CE-141 CS-134 ZN-65 CO-57 EU-154 CS-134 CO-57 CO-60 NP-239 ZR-95 MO-99 ZR-95 CS-137 MO-99 NB-95 MO-99 MO-99 3.21E+00 1.94E+04 6.42E+00 5.86E+00 1.73E+01 1.59E+01 1.02E+01 8.87E+00 3.01E+01 3.86E+01 7.79E+00 8.57E+01 1.53E+02 9.11E+01 2.07E+02 1.18E+02 1.02E+02 1.67E+02 1.58E+02 8.88E+01 1.85E+02 8.38E+01 1.52E+02 1.73E+02 5.33E+02 1.16E+01 3.34E+01 1.55E+01 2.92E+01 1.81E+01 4.10E+01 3.60E+02 8.90E+07 4.90E+01 1.30E+02 7.20E+00 2.60E+00 9.40E+02 3.10E+00 2.40E+02 3.70E+04 9.30E-01 4.51E+03 1.13E+00 1.03E+00 1.87E+00 2.43E+00 1.84E+00 1.17E+00 2.28E+00 6.45E+00 1.39E+00 1.97E+01 3.50E+01 2.05E+01 3.66E+01 3.42E+01 1.86E+01 3.38E+01 4.35E+01 1.74E+01 5.55E+01 1.74E+01 3.13E+01 5.1OE+01 1.54E+02 2.57E+00 8.05E+00 1.64E+00 3.30E+00 2.90E+00 4.50E+00 1.50E+01 3.OOE+06 1.50E+01 3.10E+01 2.10E+00 8.5E-01 2.60E+02 9.50E-01 6.50E+01 6.50E+03 3.05E+00 Duplicate at both labs - N 5.72E+03 Duplicate at both labs - N 3.81E+00 3.27E+00 6.45E+00 8.03E+00

5.98E+00

3.93E+00

7.96E+00 6.31E+00

4.71E+00 Control location 5.62E+01

9.99E+01

5.89E+01

1.07E+02

1.17E+02 5.46E+01

9.79E+01

1.42E+02 5.07E+01 1.86E+02 5.05E+01

9.05E+01

1.71E+02 4.86E+02 7.71E+00 2.55E+01 4.86E+00 *Control location 9.68E+00 *Control location 8.93E+00 Control location 2.OOE+01

6.OOE+01 1.OOE+07

5.OOE+01

1.OOE+02 7.OOE+00

Storm drain water 3.OOE+00 9.OOE+02 3.OOE+00 2.OOE+02 Storm drain water 2.OOE+04 Storm drain water

Not detected in reactor coolant in 2000 127 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000 2000

Appendix A, Table 1 (cont.)

Questionable Data Eliminated from Year 2000 Table 5.1 Summary-continued Media Station Week Year Test Activity 1 Std Dev MDC WW SE SE 12 95 95 36 18 27 2000 2000 2000 SE 98 31 2000 2000 SE 99 15 2000 MO-99 NB-95 CE-141 ZR-95 NB-95 ZR-95 NB-95 ZR-95 7.80E+00 9.10E+01 1.63E+03 6.94E+01 3.60E+01 1.00E+02 3.50E+01 1.40E+02

Not detected in reactor coolant in 2000 2.30E+00 2.70E+01 3.57E+02 6.55E+00 9.OOE+00 2.00E+01 5.50E+00 1.00E+01 8.00E+00 Storm drain water 9.OOE+01 Storm drain sediment 2.02E+03 Storm drain sediment 3.07E+01

3.OOE+01 Storm drain sediment 7.OOE+01

2.OOE+01 Storm drain sediment 4.OOE+01

ND means not detected In all cases, these isotopes in the above table have not been detected in prior years in these sample media.

128

Appendix A, Table 2 - CALENDAR YEAR 2000: VERMONT YANKEE NON-REPORTABLE DATA VY #

Analyte Explanation TMI 13100 CO-57 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 below). No photopeak was identified, consequently Co-57 is NOT DETECTED. The forced activity is -2.51 +/- 2.21 pCi/L (95% C.L.) with an MDA of 5.93 pCi/L.

EU-1 54 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 below). No photopeak was identified, consequently Eu-154 is NOT DETECTED. The forced activity is -5.25 +/- 4.63 pCi/L (95% C.L.) with an MDA of 12.4 pCi/L.

ZR-95 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 below). No photopeak was identified, consequently Zr-95 is NOT DETECTED. The forced activity is 2.92 +/- 6.46 pCi/L (95% C.L.) with an MDA of 9.62 pCi/L.

TM142500 NB-95 Nb-95 has only one photon to quantify its activity @ 765.86 keY. The photon energy was not identified on the gamma-ray raw data printout, thus the nuclide is considered "NOT DETECTED".

The MDA calculated for this photon energy is 3.49 pCi/L, and the forced activity calculation gives a value just below the MDA, 3.46 +/- 1.95 pCi/L (95%C.L.)

NP-239 Np-239, with a half-life of 2.36 days, has several photon energies (I.e. 103.8 keV, 106.1 keV, and 277.6 keV. Only the 277.6 keV photon was indicated on the gamma-ray raw data printout. If present, the 103.8 & 106.1 keV photon energies should have also been indicated. In addition, the 1 sigma error value for the 277.6 keV photon is greater than 30% of the net activity. The elapsed time interval between sampling and counting was - 16 days, approximately 7.2 half-lives of Np-239 providing a decrease through decay of two orders of magnitude. Np-239 is considered to be NOT DETECTED although the forced activity calculation of 4420 +1-1820 pCi/L (95% C.L.) exceeds the MDA value of 3170 pCilL.

ZR-95 Zr-95 has two photon energies that may be used for quantification, 724.2 and 756.7 keV. Neither of these energies were indicated on the gamma-ray raw data printout. The nuclide is considered to be NOT DETECTED. The estimated MDA for Zr-95 using the most abundant photon energy (756.7 keY) is 7.12 pCi/L and the forced activity calculated value is 6.48 +/- 4.02 pCi/L (95% C.L.),

a value below the estimated MDA.

TM163300 MO-99 The main photon energy for Mo-99 is 140.5 keV and is not identified in the gamma raw data printout; therefore, it is considered NOT DETECTED. The MDA is estimated to be 25.1 pCi/L and the forced activity is 29.3 +/- 14.8 pCi/L (95% C.L.)

TM 163800 CR-51 This sample was collected 9/20/00 and counted 3/15/01, giving an elapsed time interval between collection and counting of 176 days or 6.35 half-lives. Through radioactive decay, any activity associated with Cr-51 would diminish by two orders of magnitude from that originally present and would indeed be unlikely to be detected at environmental levels. Examination of the gamma-ray spectra did not reveal a Cr-51 photo peak occurring @ 320.1 keV. There was, however, a small unidentified peak occurring at 318.7 keV. The estimated MDA was 3750 pCi/L and the forced activity calculated value was 3957 +/- 2446 pCiIL (95% C.L.). The higher forced activity value occurred due to the Cr-51 region of interest (ROI) overlapping into the photon energy @ 318.7 keV. As stated on the raw data printout, Cr-51 is NOT DETECTED.

I_

1 129

Appendix A, Table 2 - CALENDAR YEAR 2000: VERMONT YANKEE NON-REPORTABLE DATA VY #

Analyte Explanation TM222900 MO-99 Mo-99 (2.75 d half-life) decaying to its metastable daughter, Tc-99m (6 hr half-live), has a primary photon energy at 140.5 keV. Additional photon energies due to Mo-99 occur at 181.1 & 739.6 keV, but with much lower intensity. Only the photon energy at 140.5 keV was indicated on the gamma ray raw data analysis printout and it had a 1 sigma error value of +/- 48%. The estimated MDA was 13.4 pCiIL and the calculated forced activity was 13.3 +/- 7.87 (95% C.L.). Mo-99 should be considered to be NOT DETECTED.

TM223100 CO-60 The sample was counted at the Westwood, NJ laboratory on a detector having a trace of Co-60 in the background. The peak search routine using a sensitivity of 3.00 and a 95% confidence rejection criteria did not list Co-60 on the gamma-ray raw data printout; therefore, Co-60 is considered NOT DETECTED. The estimated MDA for the photon energy @ 1173.2 was 4.52 pCi/L and for the 1332.5 keV photon was 4.16 pCiL. The forced activity calculation for each of the respective energies was 3.85 pCiIL and 4.87 pCi/L. The higher forced activity calculation is due to the presence of background Co-60.

TM243300 CO-60 Examination of the gamma-ray analysis raw data printout indicates no photon energies associated with Co-60; therefore, this radionuclide is NOT DETECTED. The MDA for Co-60 is estimated to be 3.78 pCi/L and the forced activity calculation is 3.31 +/- 2.14 pCiIL (95% C.L.).

MO-99 Examination of the gamma-ray analysis raw data printout indicates no photon energies associated with Mo-99; therefore, this radionuclide is NOT DETECTED. The MDA for Mo-99 is estimated to be 57.1 pCiIL and the forced activity calculation is 63.3 +/- 33.7 (95% C.L.).

TM262700 MO-99 Examination of the gamma-ray analysis raw data printout indicates no photon energies associated with Mo-99; therefore, this radionuclide is NOT DETECTED. The estimated MDA for Mo-99 is 122 pCi/L and the forced activity calculation provides 143 +/- 71.3 pCiL (95% C.L.)

AP15_2ndQ CO-60 Co-60 has two photon energies, one at 1173.2 and the other at 1332.5 keV. Both peaks are present on the hardcopy printout, with the 1173 peak having a one sigma uncertainty of 36.6% and the 1332.5 keV peak uncertainty of 21.5%. Based on the presence of both photon eneries, the Co 60 value is 1.01 9E-03 +/- 4.389E-04 pCi/i 3 and the MDA value is 7.59E-04 pCi/m 3. Co-60 is detected.

WG1 13200 CS-137 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG1 23200 below). Cs-1 37 is NOT DETECTED. MDA is 3.61 pCiIL and the forced activity calculated value is -1.71 +/- 2.08 pCi/L (95% C.L.).

MO-99 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 below). Mo-99 is NOT DETECTED. MDA is 7350 pCi/L and the forced activity calculated value is -1446 +1-5229 pCi/L (95% C.L.).

130

Appendix A, Table 2 - CALENDAR YEAR 2000: VERMONT YANKEE NON-REPORTABLE DATA VY #

Analyte Explanation WG123200 CO-60 The Canberra Gamma-ray spectrometry software includes a feature for reporting an estimate of the minimum detectable activity (MDA) which uses a selected region where a particular gamma ray energy occurs in the absence of a peak, or uses the region of interest underlying a peak, if one is present. In addition, the software also includes a feature for statistically distinguishing non significant gamma-ray energy photopeaks in the Compton continuum. This is referred to as critical level testing. This feature allows the operator to select the desired confidence interval (i.e. the 95% confidence level) to statistically omit reporting false-positive or non-significant peaks present in the spectrum. When this test is invoked, the observed signal (i.e. peak) must exceed some critical level to be accepted as a valid peak. Peak areas not exceeding this critical level will be ignored. However, when this feature is invoked, if the peak is not accepted as significant, the forced activity calculation utilizes the same peak region of interest, and calculates a value based on the total underlying counts in the spectrum before correcting for background. This forced activity value may then be larger than the estimated detection level value, indicating that the activity may have been present above the MDA value. The use of critical peak test has now been disengaged, and some spectra originally reduced using this feature require reprocessing to obviate the above problem. This is one of the values that needs correction. Co-60 is considered NOT DETECTED. The calculated activity for Co-60 is 0.538 +/- 1.88 pCi/L (95% C.L.) with an MDA of 4.60 pCiIL.

CS-1 37 See discussion above for Co-60. Cs-1 37 is NOT DETECTED. The calculated activity for Cs-1 37 is 0.744 +/- 2.05 pCi/L (95% C.L.) with an MDA of 5.11 pCi/L.

WG143200 CS-137 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 above). Cs-137 is NOT DETECTED. The calculated activity for Cs-137 is 0.822 +1 3.11 pCi/L (95% C.L.) with an MDA of 7.92 pCi/L.

EU-1 54 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 above). Eu-154 is NOT DETECTED. The calculated activity for Eu-154 is 0.584+1 4.29 pCi/L (95% C.L.) with an MDA of 11.5 pCi/L.

AG-110m Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 above). Ag-110m is NOT DETECTED. MDA = 5.98 pCi/L with a forced activity of 0.233 +/- 1.11 (95% C.L.)

C0-57 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 above). Co-57 is NOT DETECTED. MDA = 5.54 pCi/L with a forced activity of 0.269

+1-2.24 pCi/L (95% C.L.)

CO-60 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 above). Co-60 is considered NOT DETECTED. MDA = 8.65 pCi/L with a calculated activity of 1.02 +/- 3.95 pCi/L (95% C.L.)

WG143200 SE-75 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 above). Se-75 is NOT DETECTED. MDA = 6.31 pCi/L with a forced activity of -4.82

+/-4.54 pCi/L (95% C.L.)

WG223200 CS-137 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 above). Cs-137 is NOT DETECTED. The calculated activity for Cs-137 is 0.685+/

2.37 pCi/L (95% C.L.) with an MDA of 6.23 pCi/L.

131

Appendix A, Table 2 - CALENDAR YEAR 2000: VERMONT YANKEE NON-REPORTABLE DATA VY #

Analyte Explanation SE141700 CO-57 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 above). Co-57 is NOT DETECTED. MDA = 79.9 pCi/kg with a forced activity of -7.10

+/- 22.6 pCi/kg (95% C.L.)

EU-1 54 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 above). Eu-154 is NOT DETECTED. MDA = 144 pCi/kg with a forced activity of -12.8

+/- 40.6 pCi/kg (95% C.L.)

SE181700 0O-57 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WGI 23200 above). The result fell below the estimated MDA. Final reported values are 1.96 +1 24.0 pCi/Kg (95% C. L.) with the MDA = 80.5 pCi/Kg. Co-57 is NOT DETECTED.

EU-154 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 above). The result fell below the estimated MDA. Eu-154 is NOT DETECTED. Final reported values are 3.51 +/- 43.1 pCi/Kg with an MDA of 144 pCi/Kg.

SE241700 NB-95 There is no Nb-95 peak detected at 765.2 keV on the gamma-ray printout; therefore, Nb-95 is NOT DETECTED. The MDA is 0.117 pCi/unit and the forced calculated activity is 0.118 +/- 0.0683 pCi/unit (95% C.L.) The forced calculated activity is higher than the MDA due to the presence of a Bi-214 peak at 768 keV adjacent to the Nb-95 region of interest SE251700 CO-57 A gamma-ray photon was present @ 122/123 keV on the spectrum along with a 136 keV photon energy associated with C0-57. When reprocessed, only the 122 keV photon was indicated on the printout. The activity reported is (2.98 +/-42.8)E-03 pCi/g (95% C.L.) The MDA value is 4.76 E-02 pCi/g, a value considerably larger than the reported activity, consequently Co-57 is considered NOT DETECTED.

EU-1 54 Two photon energies associated with Eu-I 54 were present: 123 keV and 1274 keV. Both energies indicated approximately the same activity values present: 0.166 & 0.160 pCi/g. A photon energy

@ 1004 was not present. The reported activity is 0.160 +/- 0.065 pCi/g. The MDA estimated value is 0.0836 pCi/g. Therefore, since the reported value exceeds the MDA value and the peaks were identified, Eu-1 54 is considered DETECTED. We assume that this nuclide is the result of analytical cross contamination since this nuclide is not measured in any effluent at Vermont Yankee.

SE251700 NB-95 Nb-95 has one photon energy useful for quantification at 765.8 keV and was not present in the spectrum. The MDA estimated value is 0.142 pCi/g and the forced activity calculated value is (

1.60 +/- 2.84)E-02 pCi/g. Nb-95 is considered NOT DETECTED.

SE351700 CO-57 Sample was reprocessed with the 95% significance test removed (See discussion for Co-60 in WG123200 above). The result fell below the estimated MDA. Final reported values is (-4.08 +1 4.10)E-02 pCi/g (95% C. L.) with the MDA = 7.02E-02 pCi/g. Co-57 is NOT DETECTED.

SE391700 NB-95 Nb-95 has only one photon to quantify it's activity @ 765.86 keV. The photon energy was not identified on the gamma-ray raw data printout, thus the nuclide is considered "NOT DETECTED".

An adjacent peak at 768.4 keV from Bi-214 likely interferes with the region of interest for the calculated forced activity producing a value of nearly the same activity.

132

Appendix A, Table 2 - CALENDAR YEAR 2000: VERMONT YANKEE NON-REPORTABLE DATA VY #

Analyte Explanation SE441700 CO-57 Co-57 has two photon energies appropriate for quantifying its presence: one at 122.1 keV and the other at 136.5 keV. Only the 122.1 keV energy was present. The sample was reprocessed without invoking the 95% Critical test, and the Co-57 value reported was (1.47+1-2.27)E-02 pCi/g (95% C.L.). The estimated MDA is 6.43E-02 pCi/g. Therefore, Co-57 is consisered NOT DETECTED.

EU-154 Eu-i 54 has several photon energies and only the 123.1 keV photon was present. The sample was reprocessed without invoking the 95% Critical test, and the Eu-1 54 reported value is (2.63 +/

4.07)E-02 pCi/g (95% C.L.). The estimated MDA is 1.13E-01 pCVg; consequently Eu-154 is consisered NOT DETECTED.

SE491700 NB-95 The sample was reprocessed without invoking the 95% Critical test. The MDA estimated value for Nb-95 is 1.71 E-01 pCi/g and the forced activity calculated value is 2.80 +1-5.02 pCi/g (95% C. L.).

Nb-95 is considered NOT DETECTED.

CE-141 CS-134 ZN-65 CO-57 EU-154 CS-134 CO-57 Ce-141 has only one useful gamma-ray energy for quantification at 145.4 keV and there is not a well defined peak on the spectrum. In addition, there is no peak identified on the hard copy printout for this energy. The estimated MDA is 0.486 pCi/unit and the forced activity calculated is 0.533 +/-0.308 pCi/unit (95% C.L.). That the forced activity is higher than the MDA may be due to a nearby energy line -143 keV which apparently overlaps into the Ce-141 region of interest producing a higher forced activity. Ce-141 should be considered NOT DETECTED.

The spectra was reanalyzed and the follwing data was obtained: Cs-1 34 photopeak was absent, consequently Cs-1 34 is NOT DETECTED. The MDA is 8.65 pCi/L and the forced activity is 0.190

+/- 5.90 pCi/L (95% C.L.).

Zn-65 has a photon energy @ 1115.5 keV which is not observed in the spectra, consequently it is NOT DETECTED. However, a diffuse peak @ 1119.3 keV was present, associated with Bi-214.

The MDA for Zn-65 is 25.5 keV and the forced activity is calculated to be 33.4 +/- 16.1 pCi/L. The forced activity is higher than the MDA value due to the decay correction for Zn-65 (1.92) as well as the region of interest for the forced activity overlapping into the Bi-214 peak region.

The sample was reprocessed without invoking the 95% Critical test. The estimated MDA for Co-57 is 6.39 pCi/L and the forced activity calculated value is (7.3 +/- 23.2)E-01 pCi/L (95% C.L.);

consequently Co-57 is considered NOT DETECTED.

Eu-1 54 had a forced activity value of 1.75 +1-3.77 pCi/L (95% C.L) and the estimeated MDA is 12.7 pCi/L. Consequently, Eu-1 54 is considered NOT DETECTED.

The spectrum was examined for Cs-1 34 and no photon energy @ 604.7 keV was present. The spectrum was reprocessed and Cs-134 was NOT DETECTED. The estimated MDA value is 9.37 pCi/L and the forced activity calculated value is -5.26 +/-6.62 pCi/L.

Co-57 has two photon energies, @ 122.1 keV and 136.5 keV. A peak is reported on the gamma ray raw data printout @ 120.67 keV, within 2 keV tolerance for identification of Co-57. However, there is no 136.5 keV photon indicated. The 120 keV peak has 873 net counts, and if Co-57 were present, the expected counts for the 136.5 keV photon energy would be - 100 counts. Since this energy is not reported, the Co-57 is considered NOT DETECTED.

133 SE501700 WR113300 WR113300 WR212900 WR213300 FHl11900

Appendix A, Table 2 - CALENDAR YEAR 2000: VERMONT YANKEE NON-REPORTABLE DATA VY #

Analyte Explanation CO-60 Co -60 has two photon energies available for quantification: 1173.2 and 1332.5 keV. Neither of these are indicated on the gamma-ray raw data printout, thus Co-60 is considered NOT DETECTED. The MDA for Co-60 is 56.4 pCi/Kg and the forced activity calculated value is 361 +I 25.3 pCi/Kg (95% C.L.). The sensitivity threshold for peak acceptance was set at 5 and there may likely be Co-60 in the background giving an elevated forced activity calculation.

NP-239 Np-239, with a half-life of 2.36 days, has several photon energies (I.e. 103.8 keV, 106.1 keV, and 277.6 keV. Only the 277.6 keV photon was indicated on the gamma-ray raw data printout. There is also an interfering natural photon energy at 277.3 keV from TI-208. With its short half-life, Np 239 would have decayed for 16 half-lives. For these reasons, Np-239 is considered NOT DETECTED.

ZR-95 Zr-95 has two photon energies available for quantification, 724.2 keV & 756.7 keV. Neither of these two peaks are indicated on the gamma-ray raw data printout, thus Zr-95 is considered NOT DETECTED. The MDA is 52.0 pCi/Kg and the forced activity calculated is 49.2 +/- 29.5 pCi/Kg (95% C.L.).

MO-99 ZR-95 C.5-127 MO-99 NB-95 MO-99 Mo-99 (2.75 d half-life) decaying to its metastable daughter, Tc-99m (6 hr half-live), has a primary photon energy at 140.5 keV for quantification. This energy is not present in the gamma-ray raw data printout consequently it is considered NOT DETECTED. The calculated MDA is 106 pCi/L and the forced activity calculation is 127 +1-61.8 pCi/L (95% C.L.).

Zr-95 has two gamma photons suitable for quantification, one @ 724.2 keV and the other @ 756.7 keV with photon intensities of 44.1% and 54.5%, respectively. Only the photon energy @ 724.2 keV was detected giving a value of 6.74 +/- 5.69 pCi/unit (95% C.L.). The MDA calculated as 7.44 pCilunit. With only one line identified, 3 sigma exceeding the net activity, and the net activity less than the MDA, all indicate NON DETECTION.

The Cs-1 37 photon energy @ 661.6 keV was not identified consequently Cs-1 37 is considered NOT DETECTED though a calculated MDA of 2.95 pCi/unit and a forced activity of 2.63 +1-1.70 pCi/unit (95% C.L.) is provided.

Mo-99 (2.75 d half-life) decaying to its metastable daughter, Tc-99m (6 hr half-live), has a primary photon energy at 140.5 keV for quantification. This energy is not present in the gamma-ray raw data printout consequently it is considered NOT DETECTED. The MDA was calculated as 883 pCi/unit and the forced activity calculation provided a value of 936 +/- 519 pCi/unit (95% C.L.).

Nb-95 has only one photon to quantify it's activity @ 765.86 keV. The photon energy was not identified on the gamma-ray raw data printout, thus the nuclide is considered "NOT DETECTED".

An adjacent peak at 768.4 keV from Bi-214 likely interferes with the region of interest for the calculated forced activity. The calculated MDA is 3.31 pCi/unit and the forced activity is 3.07 +1 1.89 pCi/unit (95% C.L.).

Mo-99 has a primary photon energy at 140.5 keV which is not present in the gamma-ray analysis raw data printout-There is a photon energy listed @ 138.31 keV, just out of the range for the 2.00 keV acceptance tolerance to be identified as Mo-99. The one sigma uncertainty associated with this photon energy is +/- 72.7%. Thus, Mo-99 is considered NOT DETECTED. The MDA for Mo 99 is 221 pCi/L and the forced calculated activity is 236 +A-131 pC/L (95% C.L.)

134 WT141400 WVVW102300 WW103100

Appendix A, Table 2 - CALENDAR YEAR 2000: VERMONT YANKEE NON-REPORTABLE DATA VY #

Analyte Explanation WW121500 MO-99 Mo-99 has one primary photon energy for identification and quantification @ 140.5 keV. There are a few lesser intense photon energies available for confirmation @ 181.0, 366.4 and 739.6 keV.

Examination of the gamma-ray raw data printout reveals a photon energy @ 139.11 keV within the 2.0 keV energy tolerance for acceptance as Mo-99. Associated with the photon energy were 505 counts accumulated over a counting period of 4222 minutes. There were no other counts associated with the other Mo-99 photon energies. The elapsed time between sample collection and counting was approximately 38 days, allowing for nearly 14 half-lives decay. Decay over ten half-lives reduces activity to 0.1% of its original amount, thus it is extremely unlikely that any detectable Mo-99 would be present after 14 half-lives. Consequently, Mo-99 is considered NOT DETECTED even though the calculated forced activity exceeds the MDA.

WW1 23600 MO-99 The data provided for this sample was for Zr-95; not Mo-99. Examination of the Zr-95 data ZR-95 provided the following: Zr-95 has two photon energies useful for quantification: one @ 724.2 keV and the other at 756.7 keV. Neither of these two energies were listed as identified on the gamma ray analysis printout. Therefore, Zr-95 should be considered as NOT DETECTED. The estimated MDA for Zr-95 is 7.94 pCi/unit and the forced activity is 7.75 +1-pCi/unit.

NB-95 CE-141 ZR-95 ZN-65 NB-95 A photon energy of 765.8 keV is indicated on the gamma-ray analysis printout corresponding to Nb

95. The quantified value is (8.45 +/- 6.47)E-02 pCi/gm. The percent one sigma error is 38.3% and the MDA is 9.48E-02 pCi/gm, consequently Nb-95 is considered NOT DETECTED. The reported forced activity value is (9.06+/-5.39)E-02 pCilgm. The spectral data resides on the ND6600 equipment which is out of service and cannot be polled, consequently it is unavailable for examination. The forced activity is likely higher than the quantified value doe to the nearby overlapping region of interest of Bi-214 at 768.4 keV.

Ce-141 has only one useful gamma-ray energy for quantification at 145.4 keV. Examination of the spectra indicated a gamma-ray energy peak at 143.8 keV assoicated with U-235 and not Ce-141.

When reprocessed the activity is (1.63 +1-.714)E03 pCi/unit and the MDA is 2.02 E03 pCi/unit. Ce 141 is considered NOT DETECTED.

The data provided for this sample was for Zn-65 not Zr-95. Examination of the Zn-65 data provided: Zn-65 has only one photon energy suitable for identification and quantification at 1115.5 keV. Examination of the spectra indicates a peak at this energy with 311 net peak counts. The calculated activity is(6.94 +/- 1.31)EO1 pCi/unit and the estimated MDA is 30.7 pCi/unit. Zn-65 is considered DETECTED.

Examination of the gamma-ray printout indicates that the energy calibration may be low-the gamma energy corresponding to the 511 annihilation peak is at 508.42 keV and the Bi-214 photon energy @ 609.3 keV is given as 607.04 keV. Likewise the 911.2 keV and 969.0 keV photon energies associated with Ac-228 occurs at 909.34 and 967.43 keV. NB-95 has one gamma-ray energy available for identification and quantification @ 765.9 keV. The gamma-ray printout indicates a photon energy @ 767.10 keV, and given the low energy calibration, would more likely correspond to 769.4 keV and is therfore not likely Nb-95. Nb-95 is considered as NOT DETECTED.

135 SE951800 SE952700 SE983100

Appendix A, Table 2 - CALENDAR YEAR 2000: VERMONT YANKEE NON-REPORTABLE DATA VY #

Analyte Explanation ZR-95 The energies associated with Zr-95 are 724.2 & 756.& keV, but only one is listed on the printout for Zr-95 @ 725.01 keV and is unlikely from Zr-95 due to the low energy calibration. That is, the photon energy at 725.01 should likely be closer to an energy corresponding to 727.3 keV (609.3 607.0=2.3+725.02=727.3 keV). In addition there is no indication of the other Zr-95 photon energy

@ 756.7 keV. Therefore, Zr-95 is NOT DETECTED.

SE991500 NB-95 Examination of the gamma-ray analysis printout indicates a photon energy @ 767.09, within the 2 keV energy tolerance of acceptance of Nb-95 @ 765.8 keV. But Bi-214, a natural gamma emmitter associated with Ra-226 daughters has a photon energy @ 768.4 keV, which unless corrected for, could be identified as Nb-95. Because of the presence of Ra-226, it is likely that the photon energy at 767.09 is associated with Bi-214 and, therefore, Nb-95 is NOT DETECTED.

ZR-95 Zr-95 has two photon energies useful for identification and quantification, 724.2 and 756.7 keV.

There is a photon energy listed on the printout @ 726.14 just within the 2 keV acceptance range for Zr-95. There is no indication of the other Zr-95 photon energy @ 756.7 keV being present. A photon energy for Bi-212, a natural radionuclide, occurs @ 727.3 keV and could overlap into the forced activity calculation for Zr-95 given an elevated value greater than the MDA value.

Therefore, Zr-95 is considered NOT DETECTED.

136

ML021360202

Contents

Text

Subject:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

ML021360202

Text

Subject:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search