Text

Annual Radiological Environ Operating Rept,For 1996
	ML20138F421
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Site:	Maine Yankee
Issue date:	12/31/1996
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Mainc Yankee REUABLE ELECTRICITY FOR MAINE f>lNCE 1972 .

.ANNUALL~ '

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RADI.OLOGICAL . i .

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ADOCK 05000309 PDR ,

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l Maine Yankee RELIABLE ELECTRICITY FOR MAING SINCE 1972 1

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1996 i

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MAINE YANKEE NUCLEAR POWER STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January - December 1996 4

April 1997 1

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Prepared by:

Yankee Atomic Electric Company Environmental Engineering Depanment 580 Main Street I Bolton, Massachusetts 01740 l

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EXECUTIVE

SUMMARY

l During 1996, as in all previous years of plant operation, a program was conduw o assess i the levels of radiation or radioactivity in the hiaine Yankee environment. Over 700 samples were collected (including TLDs) over the course of the year, with approximately 4000 radionuclide or exposure rate analyses being performed on them. The samples included ground water, estuary water, sediment, marine algae, fish, mussels, clams, crabs, lobsters, grass and milk. In addition to these samples, the air surrounding the plant was sampled continuously and the radiation levels were measured continuously with environmental TLDs.

Low levels of radioactivity from naturally-occurring, fallout and plant emission sources were detected. hiost samples had measurable concentrations of K-40, Be-7, Th-232 or Radon daughter products. These are the most common of the naturally-occurring radionuclides.

hiany milk and sediment samples had fallout radioactivity from atmospheric nuclear weapons tests conducted primarily from the late 1950's through 1980. Several samples had low levels of radioactivity resulting from emissions from hiaine Yankee. These were all collected in the immediate vicinity of the plant or from on-site locations. In all cases, the possible radiological impact was negligible with respect to exposure from natural background radiation. In no case did the detected levels approach or exceed the most restrictive federal regulatory or plant license limits for radionuclides in the environment. Consequently, there was judged to be no environmental or health impact.

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TABLE OF CONTENTS

1. INTRODUCTION . . .. .... . .. .. .... . . . . . .. .I

2. NATURALLY OCCURRING AND h1AN-MADE BACKGROUND l RADIOACTIVITY . . . . . . . . .. ... ..... ... ... . .. 2 2.1 Naturally Occurring Background Radioactivity . . . . . ..... . . 2 2.2 Man-Made Background Radioactivity . . . . . . . ... .. .. .3

3. GENERAL PLANT AND SITE INFORhiATION . . .. . . 5

4. PROGRAhi DESIGN . . . . . ... .. . ... . . ... . 6 4.1 hionitoring Zones . . . . .... .. .. . 7 4.2 Pathways Monitored . . . . . . . . . .. . .. .. 7 4.3 Descriptions of Monitoring Programs . . ...... ... . 8 1

5. RADIOLOGICAL DATA

SUMMARY

TABLES . . . . , . . . . . . . 26 i

6. ANALYSIS OF ENVIRONMENTAL RESULTS .. .. .. .... .. . 43 6.1 Sampling Program Deviations . 43

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6.2 Comparison of Achieved LLDs with Requirements . . 43 !

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l 6.3 Comparison of Results Against Reporting Levels , . . . ... 44 6.4 Data Analysis by Media Type .. .. . .. .. . . . 44 1

7. QUALITY ASSURANCE PROGRAM . ..... . . .. .. 71 7.1 Intralaboratory Quality Control Program . . . . .... . 71 l 7.2 Third Pany Intercomparison Program . . .. .. .. . . 72 7.3 Environmental TLD Quality Assurance Program . . . . .. . 73 7.4 Blind Duplicate Quality Assurance Program .... ...... . 74

8. LAND USE CENSUS .. ... .. . . 83

9. REFERENCES . .... ... . . ... . .. .. . .. . ..... 85 i

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LIST OF TABLES Table Iitig hge 4.1 Radiological Environmental Monitoring Program . .. .. . . .. . 12 4.2 Radiological Environmental Monitoring Locations (Non-TLD)in 1996. .. .. ... . . . . . . . . . . . . . 14 4.3 Radiological Environmental Monitoring Locations (TLD) in 1996. . .. . . . .. . . . . . 16 4.4 Environmental Lower Limit of Detection (LLD)

Sensitivity Requirements . . ... . .. . . . . . . . . . ... . .. . .18 4.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples . .. . . . . . . . . . . . . . ... I 9 5.1 Environmental Radiological Program Summary . .. .. . . . .. 2 8 5.2 Environmental TLD Data Summary . . . .. . . . . .41 5.3 Environmental TLD Measurements . . . . . . . . . .. .42 7.1 Environmental Process Control Analysis Results . .. . 75 7.2 EPA Intercomparison Program Results . . . . . .. .76 7.3 YAEL 1996 Analytics Cross-Check Results .. . .. . . . . .. . . 78 7.4 Summary of Blind Duplicate Samples Submitted .. .. . . . . . . ..82 8.1 1996 Land Use Census Locations .... . . . . .. .. . 84 iv

LIST OF FIGURES Figure Iille Eagg 4,1 Radiological Environmental Sampling Locations Within 1 Kilometer ofMaine Yankee ... .. .. . . . . . . .. .. . . 20 4.2 Radiological Environmental Sampling Locations Within 12 Kilometers of Maine Yankee.. .. . . . . . . .. . 21 l 4.3 Radiological Environmental Sampling Locations ;

Outside 12 Kilometers of Maine Yankee . . . . .22 4.4 Direct Radiation Monitoring Locations Within 1 Kilometer of Maine Yankee . . . . . . .. . 23 4.5 Direct Radiation Monitoring Locations Within 12 Kilometers of Maine Yankee . .. . . 24 4.6 Direct Radiation Monitoring Locations Outside 12 Kilometers of Maine Yankee . . . . .25 6.1 Gross-Beta Measurements on Air Particulate Filters . . ... . . . .51 l (Quarterly Average Concentrations) 6.2 Gross-Beta Measurements on Air Particulate Filters .. . ... . ........ .. 52 l (AP-11 vs. AP-29 Control) l 6.3 Gross-Beta Measurements on Air Particulate Filters . ... . . . . . 53 l (AP-13 vs. AP-29 Control) j i

6.4 Gross-Beta Measurements on Air Paniculate Filters . . . .54 (AP-14 vs. AP-29 Control)

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LIST OF FIGURES ;

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i l 6.5 Gross-Beta Measurements on Air Particulate Filters . . . . . . .

.55 (AP-16 vs. AP-29 Control) J

! 6.6 Cesium-137 in Shoreline Sediment Station SE-16, Old Outfall Area . . . . . . . . . . . . . . . . . . . . . .56 l

6.7 Cesium-137 in Shoreline Sediment Station SE-18, Foxbird Island . .. . .. .. .57 6.8 Cesium-137 in Milk (Annual Average Concentrations) . .. .. 58 1

6.9 Strontium-90 in Milk (Annual Average Concentrations) . . . .59 I

6.10 Exposure Rate at Inner Ring, Outer Ring and Control TLDs... . . 60 1

6.11 Exposure Rate at Inner Ring TLDs, TL 01-04 . . . . . . 61 ;

i 6.12 Exposure Rate at Inner Ring TLDs, TL 05-08 .. . . . . 62 ;

6.13 Exposure Rate at Inner Ring TLDs, TL 09-10,12-13 .. . . 63 4

6.14 Exposure Rate at Inner Ring TLDs, TL 14-16. . .. .. . 64 6.15 Exposure Rate at inner Ring TLDs, TL 17-19. . . . 65 6.16 Exposure Rate at Outer Ring TLDs, TL 11, 20-22. . . . . . . . . 66 6.17 Exposure Rate at Outer Ring TLDs, TL 23-26. . .. . 67 I

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1 LIST OF FIGURES (continued)

Eigurn Iille Eage l 6.18 Exposure Rate at Outer Ring TLDs, TL 27-30. .. .. .. ..... . . .. . .68 ,

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l 6.20 Exposure Rate at Control TLDs, TL 36-38 ... . .. . . . .. ... ... .70 I $

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I. INTRODUCTION This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Maine Yankee Atomic Power Company in the vicinity of the Maine Yankee Nuclear Power Station in Wiscasset, Maine during the calendar year 1996. It is submitted annually in compliance with Appendix C, item no. I of the Offsite Dose Calculation Manual (ODCM) and Technical Specification 5.9.1.5. The remainder of this report is organized as follows:

Section 2: Provides an introduction to the background radioactivity and radiation that is detected in the Maine Yankee environs.

Section 3: Provides a brief description of the Maine Yankee site and its environs.

Section 4: Provides a description of the overall REMP program design. Included is a l

summary of the ODCM requirements for REMP sampling, tables listing routine sampling l and TLD monitoring locations with compass sectors and distances from the plant, and maps showing the location of each of the sampling and TLD monitoring locations. Tables listing Lower Limit of Detection requirements and Reponing Levels are also included.

Section 5: Consists of the summarized data as required by the ODCM, in the format specified by the NRC Branch Technical Position on Environmental Monitoring (Reference 1). Also included are complete environmental TLD data.

Section 6: Provides the results of the 1996 monitoring program. The performance of the program in meeting ODCM requirements is discussed, and the data acquired during the year are analyzed.

Section 7: Provides an overview of the Quality Assurance programs used at the Yankee Atomic Environmental Laboratory. The results of the Laboratory participetion in an Interlaboratory Comparison Program required by Technical Specification 5.8.1.b.3 are also given.

Section 8: Summarizes the requirements and the results of the 1996 Land Use Census.

Section 9: Gives an overall summary of the results of the 1996 Radiological Environmental Monitoring Program.

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2. NATURALLY OCCURRING AND AIAN-MADE BACKGROUND RADIOACTIVITY Radiation or radioactivity potentially detected in the Maine 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 Maine Yankee plam The l

third potential source of radioactivity is due to emissions from the Maine Yankee plant. For the purposes of the Maine 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 sufliciently 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 categon of naturally-occurring radiation and radioactivity is "cosmocenic radioactivity." This is produced through the nuclear interaction of high energy cosmic radiation with elements in the eanh's atmosphere, and to a much lesser degree in the eadh's l 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),

l Hydrogen-3 (H-3 or Tritium), Sodium-22 (Na-22), and Begilium-7 (Be-7). Begllium-7 is the i

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i one most readily detected, and is found on air sampling filters and occasionally in biological media (Reference 2). )

l The third category of naturally-occurring radiation and radioactivity is " cosmic radiation."

This consists of high energy atomic or 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 primary radiation comes mostly from outside of our solar system, and to a l

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 l The second source of" background" radioactivity in the hiaine Yankee environment is from J

" man-made" sources not related to the power plant. The most recent contributor to this l category was the fallout from the Chernobyl accident in April of 1986, which was detected in '

the hiaine 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 t

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. hiuch 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). hiost of this fallout has decayed into stable elements, but the residual radioactivity is still detectable at low levels in environmental samples worldwide. The two predominant radionuclides are

, Cesium-137 (Cs-137) and Strontium-90 (Sr-90). They are found in soil and in vegetation, and since cows and goats graze large areas of vegetation, these radionuclides are also readily

. detected in milk.

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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).

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3. GENERAL PLANT AND SITE INFORMATION !

l The Maine Yankee Nuclear Power Station is located in the town of Wiscasset, Lincoln

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County, Maine, approximately six miles northeast of Bath, Maine. The site vicinity is mral and l lightly populated. i f The plant site is located on Bailey Point, a peninsula bounded to the east by the Back River l and to the west by a shallow inlet known as Bailey Cove. Both of these estuaries flow south i into Montsweag Bay, which is a tidal estuary of the Sheepscot River, (See the maps in Figures i 4.1 to 4.6.) Bailey point is an elongated bedrock ridge with flat or gently rolling topography l

l rising to an average elevation of about 25 feet above sea level (Reference 5).

i The single 900 megawatt PWR (Pressurized Water Reactor) unit at Maine Yankee began commercial operation in 1972. The Radiological Environmental Monitoring Program (REhU')

began preoperational measurements in 1970, two years prior to commercial operation. The REMP has been in continuous operation since that date.

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4. PROGRAM DESIGN The Radiological Environmental Monitoring Program (REMP) for the Maine Yankee Nuclear Power Station 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.

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

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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. !

I The program was initiated in 1970, approximately two years before the plant began commercial operation in 1972. It has been in operation continuously since that time, with improvements made periodically over those years.

Prior to January 1992, the requirements for the Radiological Environmental Monitoring Program (REMP) were given in the Radiological Efiluent Technical Specifications (RETS). In January 1992, the REMP specifications were removed from the RETS and placed in the Offsite Dose Calculation Manual (ODCM) pursuant to NRC Generic Letter 89-01 (Reference 6).

l The REMP is a requirement of Technical Specification 5.8.1.b. The detailed sampling requirements of the REMP are given in Table 2.3 of ODCM Section 2.4. This table is summarized in this report as Table 4.1.

The required sampling locations are identified in Chapter 5 of the ODCM. The locations actually monitored in 1996 are shown on Tables 4.2 and 4.3, as well as Figures 4.1 through 4.6 of this report. The locations in these tables and figures consist of the required locations specified in the ODCM, as well as any regularly sampled locations. Sampling sites that were used on only one occasion during 1996 are not shown in the tables or maps, but are discussed in the text.

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4.1 Monitoring Zones i

The REMP is designed to allow comparison oflevels of radioactivity in samples from the area possibly influenced by the plant to levels found in areas not influenced by the plant. The t

! first area is called Zone 1, and its monitoring locations are called " indicators." The second area is called Zone 2, and its monitoring locations 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 i 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 or 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 direct radiation, airborne, waterborne, and ingestion 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 detailin this section:

Airborne Pathway Air Particulate Sampling i Charcoal Cartridge (Radiciodine) Sampling Mixed Grass Sampling (for airborne deposition)

Waterborne Pathways Estuary Water Sampling ;

Ground Water Sampling Shoreline Sediment Sampling Marine Algae Sampling Ingestion Pathways Milk Sampling Fish and Invertebrate Sampling i l

l Direct Radiation Pathway l TLD Monitoring 7

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l I i 4.3 Descriptions of Monitoring Programs

! 1 4.3.1 Air Sampling l

Continuous air samplers are operated at five locations. The sampling pumps at these locations operate continuously at a flow rate of approximately one to two cubic feet per

! minute. Airborne particulates are collected by passing air through a 47 mm glass-fiber filter.

A dry-gas meter is incorporated in the sampling stream to measure the total amount of air sampled in a given interval. The entire air sampling system is housed in a weatherproof structure. The filters are collected weekly and are initially screened at the Maine Yankee Environmental Services Laboratory with a Geiger Mueller-based " beta counter." To allow for the decay of radon daughter products, they are then held for at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months at the Yankee Atomic Environmental Laboratory (YAEL) before being analyzed for gross-beta radioactivity (indicated as GR-B in the data tables). The weekly filters are composited by location at the Laboratory for a quarterly gamma spectroscopy analysis.

4.3.2 Charcoal Cartridge (Radioiodine) Sampling Continuous air samplers are operated at five locations. The sampling pumps at these locations operate continuously at a flow rate of approximately one to two cubic feet per minute. A 60 cc TEDA-impregnated charcoal cartridge is located downstream of the air particulate filter described above. These cartridges are collected and analyzed weekly for I

I-131. A dry-gas meter is incorporated in the sampling stream to measure the total amount of air sampled in a given interval. The entire air sampling system is housed in a weatherproof structure. The filters are collected weekly and are initially screened at the Maine Yankee Environmental Services Laboratory with an Eberline Model RM-14 monitor with an HP-210 GM probe. The filters are shipped to the YAEL for a gamma isotopic analysis (I-131 specific).

4.3.3 Mixed Grass Sampling Although there is no Technical Specification requirement for mixed grass or vegetation sampling, a sample is collected from an on-site location twice during the growing season. To collect this sample, all grass is cut to a height of one inch above ground level from a 4 square-meter plot. The grass is shipped to the YAEL, where it is analyzed for gamma-emitting radionuclides.

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4.3.4 Estuary Water Sampling An automatic compositing sampler is located at the discharge forebay to monitor water discharged to the Back River. (In-plant systems monitor water prior to release to the discharge forebay.) The sampler is controlled by a timer that collects an aliquot of this water at least every two hours. Every week a one-liter sample is gathered from this composited sample. These one-!it:r samples are again composited at the Environmental Services laboratory before shipping to the YAEL at the end of the month. A weekly grab sample is collected at the control location in the Kennebec River. These are composited for a monthly sample at the Environmental Services Laboratory. All estuary water samples are preserved with hcl and NaHSO to 3 prevent the plate out of radionuclides on the container walls. Each monthly composite or grab sample is analyzed for gamma-emitting radionuclides. These are composited again by location at the Laboratory for a quarterly H-3 analysis.

4.3.5 Ground Water Sampling Due to the hydraulic gradient at the Maine Yankee site, whereby the ground water flow is southward down the peninsula and toward the water en the east and west sides, ground water sampling is not required at the Maine Yankee site, pursuant to ODCM Table 2.3.

Nevertheless, grab samples are collected quarterly from the one on-site location and or.e ;

controllocation. All ground water samples are preserved with hcl and NaHSO3 to prevent j the plate out of radionuclides on the container walls. Each sample is analyzed for gamma- l emitting radionuclides and H-3.

4.3.6 Sediment Sampling Shoreline sediment cores are collected semiannually from two locations on Bailey Point.

At each location, six 5 cm I.D. plastic coring tubes are driven into the sediment to a depth of at least fifteen centimeters. The cores are then kept in an upright position and frozen prior to delivery to the Laboratory. At the Laboratory, the frozen cores are cut into 5 cm segments.

For each location, the 0-5 cm segments are blended into a single sample, as are the 5-10 cm and 10-15 cm segments. These composite samples are then analyzed for gamma-emitting radionuclides.

1 i 4.3.7. Marine Algae Sampling Mixed samples ofI'ucus and Asconhvilum marine algae are collected semiannually from a location near the plant diffuser discharge. Each sample is frozen for shipment to the l 9

Laboratory. At the Laboratory, they are analyzed for gamma-emitting radionuclides.

Sampling of this media is not required by ODCM Table 2.3.

4.3.8 Milk Sampling Milk samples are collected on a monthly schedule from three locations. Two locations are chosen as a result of the annual Land Use Census, based on a hypothetical potential dose commitment. The third location is a control, which is located sufTiciently far away from the plant to be outside any potential influence from it.

1 Samples of milk are chilled after collection and shipped to the YAEL on ice. Methimazole i 1

and formaldehyde are added to the milk upon receipt at the Laboratory. 1 I

Each sample is analyzed for gamma-emitting radionuclides and, following chemical separation and purification, an I-131 analysis is performed to meet the Lower Limit of Detection (LLD) specified in the ODCM. Although not required by the ODCM, Sr-89 and Sr-90 analyses are also performed on quanerly composited samples.

4.3.9 Fish and Invertebrate Sampling Samples of commercially important fish and invertebrates are collected semiannually at two locations (near the plant discharge and at a control location on the Sheepscot River). Maine )

Yankee Environmental Services staff collected samples of fish, crabs, lobsters and Molluscs (blue mussels). All samples are separated by species and are then frozen and delivered to the Laboratory, where the edible portions are analyzed for gamma-emitting radionuclides.

j In 1995, the Town of Wiscasset re-opened several clam flats, including Bailey Cove, that

! had been closed to clam digging for many years. During 1996, semiannual samples of soft-shell clam (Mya arenaria) were collected from two locations within Bailey Cove. Sediment samples were also collected from two locations within Bailey cove. These samples were collected by

! the Maine Yankee Environmental Services staff and provided to the State of Maine and the 1

YAEL for radiological analysis. The clam samples were frozen and analyzed for gamma l l

emitting radionuclides at the YAEL. These samples are not required by Maine Yankee's RETS or ODCM.

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j 4.3.10 TLD Monitoring 1 Direct gamma radiation exposure was continuously monitored with the use of thermoluminescent dosimeters (TLDs). Specifically, Panasonic UD-801 ASI and UD-814ASI calcium sulfate dosimeters were 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 tree, fence or utility pole.

The plant staff posts and retrieves all TLDs quarterly. All TLDs are processed at the YAEL.

l 4.3.11 Special Monitoring l On occasion, special interest samples are taken that are not required as a part of the l Radiological Environmental Monitoring Program (REMP). The sample locations vary from ,

year to year and do not appear in Table 2.3 of the Offsite Dose Calculation Manual, nor do i

they appear in Table 4.1 or 4.2 of this repon. The analysis results may be discussed in Section l 5 of this repon, as appropriate.

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TADLE 4.1 Radiological Emironmental 31unitoring Program (as required during 1996 by ODChl Table 2.3)

Collectmn Analysis Exposure Pathway Number of Routine Analysis Analysis Samde Media Sample lecations Sampling Collection Type Frequency M ale frequency

1. Direct Radiation (TLDs) Total Locations: 38 Continuous Quarterly Gamma dose Each 11.D

2. Airtxwne (Particulates and Total Locations: 5 Continuous Weekly Particulate Sample:

Radiciodine) Gross Beta Each Sampic Gamma Isotopic Quarterly Composite (by location)

Radimodine Canister:

1-131 Each Sample

3. Waterborne

a. Estuary Water Total locatnms: 2 Compnsite Monthly Gamma Isotopic Each Sample (aliquot every 2 hrs) Tritium (11-3) Quarterly Composite

b. Ground Water Total lecations: 2 Grab Quarterly Gamma Isotopic Each Sample Tritium (11-3) Each Sample

c. Shorchne Sediment Total Ixcations: 2 Grab Semiannually Gamma Isotopic Each Sample

, Groundwater samples shall be taken when this source is tapped for drinking or irrigation riurposes in areas where hydraulic gradient or recharge properties are suitable fiw contamination.

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TAllLE 4.1 (continued)

Radiological Emironnwntal Monitoring Program (as required during 1996 by ODCM Table 2.3)

Collection Analysis Exposere Pathway Nominal Number of Routine Nominal Analysis Anahsis Sartple Media Sample Locations Sampling Mode Collection Frequency Th 3 Frequency

4. Incestion

a. Mdk Total Iecations: 3 Grab Monthly Gamma Isotopic Each sample I-13I Each sample

b. Fish and Invertebrates Totallecations: 2 Grab Semiannually Gamma Isotopic on edible Each sample (commerciallyor recreatonally (or seasonal if portions important species) appmpriate)

c. Food Products (3 types of bmad Total Locations: 3 Grab Monthly when Gamma Isotopic Each sample leaf recetation)" available I-131 Fach sample I Food Product sanpling performed only if milk sanpling is not done.

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TABLE 4.2 Radiological Environmental Monitoring Locations (non-TLD) in 1996 Man.- Yankee Nuclear Power Station ,

Distance Direction Station From Plant From Exoosure Pathway Code Station Descrintion Zeni (km) Plant

1. Airbome

a. Air Particulate AP/CF-11 Montsweag Brook 1 2.7 NW

& Charcoal Filters AP/CF-13 Bailey Farm (ESL) 1 0.6 NE AP/CF-14 Mason Steam Station 1 4.8 NNE AP/CF-16 Westpon Firchouse 1 1.8 S AP/CF-29 Dresden Substation 2 19.8 N

b. Mixed Grasses TG-ll Bailey Farm (ESL) 1 0.6 NE

2. Waterborne

a. Surface Water WE-12 Plant Outfall I 0.3 SW (Composite Sample)

WE-20 Kennebec River 2 9.8 SW (Grab Sample)

b. Ground Water WG 13 Bailey Farm (ESL) 1 0.6 NE WG-24 Morse Well 2 9.8 W

c. Sediment SE-16 Old Outfall Area 1 0.4 SW SE-18 Foxbird Island 1 0.7 S

d. Clam " MA-16 Old Outfall Area 1 0.4 SW MA-18 Foxbird Island 1 0.7 S

c. Marine Algae AL-11 Long Ledge Area l 1.1 S

3. Ingestion

a. Milk TM-15 Mitman Farm 1 5.8 S TM-18 Chewonki Foundation 1 1.2 WSW TM-25 Hanson Farm 2 16.0 W ESL = Environmental Services Laboratory 14

TABLE 4.2 (continued)

Radiological Environmental Monitoring Locations (non-TLD)in 1996 Maine Yankee Nuclear Power Station Distance Direction Station From Plant From Exoosure Pathway .Cgdg Station Descriotion Zang" (km) Plant

3. Ingestion, continued FH 11 Long Ledge Area 1 1.1 S

b. Fish & MU-l1 Invertebrates CA-Il

" HA-ll FH 24 Sheepscot River 2 11.2 S MU-24 CA-24 HA-24 1

1 = Indicator Stations; 2 = Control Stations

" MA = Sofl-St.'cIl Clams (Afya arenarta).

'" FH = Fish, ML = Mussels, CA = Crabs, HA = Lobsters i

15

TABLE 4.3 Radiological Environmental Monitoring Locations (TLD) in 1996 Maine Yankee Nuclear Power Station

~

Distance Station From Plant Dire: tion .

Code Station Descrintion Z.QDg (km) From Plant ,

TL-1 Old Ferry Rd. I 1.0 N TL-2 Old Ferry Rd. 1 0.8 NNE TL-3 Bailey House (ESL) 1 0.6 NE TL-4 Westport Island, Rt.144 1 1..! ENE TL-5 MY Information Center 1 0.2 E TL-6 Rt.144 & Greenleaf Rd. 1 0.9 E TL-7 Westport Island, Rt.144 1 0.8 ESE TL-8 MY Screenhouse 1 0.2 SE TL-9 Westport Siren 1 0.9 SE TL-10 Bailey Point 1 0.4 SSE TL-ll Mason Station O 4.8 NNE TL-12 Westpon Firehouse 1 1.8 S TL-13 Foxbird Island 1 0.4 SSW TL-14 Eaton Fann 1 0.8 SW TL-15 Eaton Farm 1 0.8 WSW TL-16 Eaton Farm 1 0.7 W TL-17 Eaton Farm Rd. 1 0.6 WNW TL-18 Eaton Farm Rd. 1 0.8 NW TL-19 Eaton Farm Rd. I 1.0 NNW TL-20 Bradford Rd., Wiscasset O 6.5 N TL-21 Federal St., Wiscasset O 7.2 NNE TL-22 Cochran Rd., Edgecomb O 8.3 NE TL-23 Middle Rd., Edgecomb O 7.0 ENE TL-24 River Rd., Edgecomb O 7.8 E TL-25 River Rd. & Rt. 27 0 7.5 ESE TL-26 Rt. 27 & Boothbay RR Museum O 7.8 SE TL-27 Baners Island O 7.0 SSE TL-28 Westport Island, Rt.144 & E. Shore Rd. O 7.7 S TL-29 Harrison's Trailer O 6.3 SSW TL-30 Leeman Farm, Woolwich O 7.6 SW 16

TABLE 4.3 (continued)

Radiological Environmental Monitoring Locations (TLD) in 1996 Maine Yankee Nuclear Power Station Distance Station From Plant Direction Code Station Descriotion Zgg* (knn From Plant TL-31 Barley Neck Rd. O 6.7 WSW TL-32 Baker Farm, Woolwich O 7.2 W TL-33 Rt.127, Woohvich O 7.3 WNW TL-34 Rt.127, Woolwich O 7.9 NW TL-35 Rt.127, Dresden O 9.1 NNW TL-36 Boothbay Harbor Fire Station 2 11.4 SSE TL-37 Bath Fire Station 2 10.4 WSW TL 38 Dresden Substation 2 19.8 N O

I = Inner Ring TLD; O = Outer Ring TLD; 2 = Control TLD.

17

TABLE 4.4 Environmental Lower Limit of Detection (LLD) Sensitivity Requirements Airbome Particulate Fish & Food Sediment Analysis Water or Gas Invertebrates Milk Products (pCi/kg (pCi/l) (pCi/m') (pCi/kg wet) (pCill) (pCi/kg) drv)

Gross-Beta 4 0.01 H-3 2000

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

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

" If no drinking water pathway exists, a value of 15 pCi/l may be used. l (Several other explanatory footnotes are given in ODCM Table 2.4).

18 s

TABLE 4.5 Reporting Levels for Radioactivity Concentrations In EnvironmentalSamples Airbome Particulates Fish &

Analysis Water or Gases invertebrates Milk Food Products (pCi/l) (pCi/m') (pCi/kg) (pCi/l) (pCi/kg) 11-3 20,000

Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 "

I-131 2 "* 0.9 3 100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La.140 200 ** 300 If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

" Parent only.

"* If no drinking water pathway exists, a value of 20 pCi/l may be used.

19

I 3 -

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CA-ll Figure 4.1 Environmental Radiological Sampling Locations Within 1 Kilometer of Maine Yankee 20 l

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Figure 4.2 Environmental Radiological Sampling Locations Within 12 Kilometers of Maine Yankee 21 i

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Outside 12 Kilometers of Maine Yankee 22

~

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,c Figure 4.4 Direct Radiation Monitoring Locations Within 1 Kilometer of Maine Yankee 23 l

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Figure 4.5 Direct Radiation Monitoring Locations l

k'ithin 12 Kilometers of Maine Yankee 24

4

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S Figure 4.6 Direct Radiation Monitoring Locations

! Outside 12 Kilometers of Maine Yankee 25

l l

l l 5. RADIOLOGICAL DATA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples which were collected during 1996. 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.

The left-most column contains the radionuclide ofinterest, the total number of analyses for that radionuclide in 1996, and the number of measurements which exceeded the Reporting Levels found in Table 2.5 of the ODCM. Measurements exceeding the Reporting Levels are classified as "Non-Routine" metsurements. The second column lists the required Lower Limit of Detection (LLD) for those radionuclides which have detection capability requirements as specified in the ODCM Table 2.4. 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 30-40 percent of the most restrictive required LLD, Occasionally, the required LLD is not met. This is usually due to malfunctions in sampling equipment, which results in low sample volume. Such cases, if any, are addressed in Section 6.2.

l For each radionuclide and media type, the remaining three columns summarize the data for I the following categories of monitoring locations: (1,? the indicator or Zone 1 stations, which are within the range ofinfluence of the plant and which could conceivably be affected by its operation; (2) the station within Zone lor Zone 2 which had the highest mean concentration during 1996 for that radionuclide; and (3) the control or Zone 2 stations, which are beyond the influence of the plant. TLD or direct radiation monitoring stations are grouped into either an Inner Ring, an Outer Ring (for emergency response), or a Control category.

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

The mean value of all concentrations, including negative values and values considered "not detectable" The lowest and highest concentration.

26

The number of detectable measurements divided by the total number of measurements. For example, (4/20) would indicate that 4 of the 20 samples collected in 1996, for that sample type and that radionuclide, contained detectable radioactivity.

A sample is considered to yield a " detectable measurement" when the concentration exceeds three times its associated standard deviation. 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 uncedainties in the analytical procedure.

l The radionuclides reported in this section represent those that: 1) had an LLD requirement in Table 2.4 of the ODCM, or a Reponing Level listed in Table 2.5, or 2) had a positive measurement of radioactivity, whether it was naturally-occurring or man-made; or 3) were of specific interest for any other reason. The radionuclides routinely analyzed and reported by the YAEL for a gamma spectroscopy analysis are: Th-232, Ag-110m, Ba-140, Be-7, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59,1-131, I-133, K-40, Mn-54, Mo-99, Np-239, Ru-103, Ru-106, Sb-124, Se-75, Te-I-132, Zn-65 and Zr-95. In no case did a radionuclide not shown in Table 5.1 appear as a " detectable measurement" during 1996. I Data from direct radiation measurements made by TLDs are provided in Table 5.2 in a i format essentially the same as above. The complete listing of quarterly TLD data is provided l l

in Table 5.3.

l I

i 27

_ ._._ -__ - . . _ _ _ . . .__ . ~.

I l

Table 5.1 l Radiological Environmental Program Surrunary l

Maine Yankee Nuclear Power Station, Wiecaaset, ME J

(January Decemtw 4996) )

MEDIUM. AirParticulates (AP) JNITS: oCi/ cubic meter 19.9.*'..S.'.?P.*... 52 W.?..H,y,y,,g,, gg,q,S,tg,w,,,,,

Radionuclides

Mean Sta. Mean Mean (No. Analysee) Required Range Range Range (Non-Routine **) LLD (No. Detected *") (No, Detected"*) (No. Detected *")

GR-B (265) 0.01 2.0E -2 29 2.1E -2 2.1E -2 (0) ( 9.3 - 35. 6)E -3 ( 1. 0 - 3. 6) E -2 ( 1. 0 - 3. 6) E -2 (212/ 212) (53/ 53) (53/ 53)

Be.7 (20) 9.1E -2 16 9.6E -2 8.7E -2 (0) ( 7. 0 - 10. 8) E -2 ( 8.1 - 10.3)E -2 ( 5.4 - 10.1)E -2 (16/ 16) (4/ 4) (4/ 4)

Mn44 (20) 3.4E -5 14 6.9E -5 -2.8E -4 (0) ( -2,4 - 3. 9) E -4 ( -1.1 - 2. 6) E -4 ( -4.1 - 0.1)E -4 (0/ 16) (0/ 4) (0/ 4)

Co48 (20) 2.0E -4 13 3.5E -4 1.8E -5 (0) ( -3.4 - 9. 6) E -4 ( -2.0 - 9. 6) E -4 ( -5.1 - 4. 7) E -4 (0/ 16) (0/ 4) (0/ 4)

Fe49 (20) -2.25 -4 29 s.3E -4 a.3E -4 (0) ( -2.4 - 3. 6) E -3 ( -9.0 - 24.1) E -4 ( -9.0 - 24.1)E -4 (0/ 16) (0/ 4) (0/ 4)

Co40 (20) 7.7E -5 16 2.3E -4 -1.0E -4 (0) ( -1. 2 - 4.1) E -4 ( -2.5 - 41.0)E -5 ( -2. 6 - 0. 6) E -4 (0/ 16) (0/ 4) (0/ 4)

Cs.134 (20) 0.05 -4.73 -5 29 6.4E -5 6.4E -5 (0) ( -3. 6 - 3.4) E -4 ( -2.1 - 2. 9) E -4 ( -2.1 - 2. 9) E -4 (0/ 16) (0/ 4) (0/ 4)

Cs.137 (20) 0.06 5.5E -5 13 1.7E -4 -2.25 -5 (0) ( -1.0 - 5.2)E -4 ( 0.0 - 0.0)E O ( -3.7 - 4.5)E -4 (0/ 16) (0/ 4) (0/ 4) i l

l l l 28

l l

Tatne 5.1

)

Radiological Environmental Program Sanmary l

Maine Yankee ph Power Station, Wiecesset ME I (January .L4cember ites)

MEDIUM. CharcoalCartrkine (CF) UMTS. oCi/cubicmater l l

.In..d.ic..a.t.o.r..S.t.a.t.i.o.n.s.. .S.t.a.t.io.n..W..it.h..H..ic.h.e.s.t.Me.a..n

. . T . .C.o..n.t.r.o.l.S..ta..tio.n..s.....

Radionuclidee* Mean Sta. Meen Mean l l

(No. Analysee) Required Range Range Range !

(Non-Routine") LLD (No. Detected *") (No. Detected *") (No. Detected *")

1131 (285) 0.07 5.es -4 14 1.ss -3 -s.es -4 (0) ( -2.0 - 2.3)E -2 ( -2.0 - 2.3)s -2 ( -1.s - 1.7)s -2 (o/ 212) (0/ 53) (o/ 53) l l

l

)

l l

i l

l l

l 29 i l

l l

i TaWe 8.1 !

Radiological Environmental Program Summary l

Maine Yankee Nuclear Power Station, ?"------^ ME . I (January . December 1008) i I

MEDIUM. Mined Grass (TO) UNITS. oCito I

l

!ad.'cf."..S!"!.W... .S.Wa.E.?..'fe'!.""a.. 9.2.1.5.*!25...

Radionuclides

Mean Sta. Mean Mean (No. Analyses) Required RanDe Range Range l (Non-Routine") LLD (No. Detected *") (No. Detected *") (No. Detected"*)

Be-7 (2) 2.1E 3 11 2.1E 3 NO DATA (0) ( 3.4 - 39.1)E 2 ( 3.4 - 39.1)E 2 (2/ 2) (2/ 2)

K-40 (2) 5.oE 3 11 5.oE 3 NO DATA (0) ( 4.5 - 5.5)E 3 ( 4.5 - 5.5)E 3 (2/ 2) (2/ 2) 1-131 (2) -6.2E o 11 -6.2E o No DATA (0) ( -9. 4 - -3.1) E o ( -9.4 - -3.1)E o (0/ 2) (0/ 2)

Cs-134 (2) 4.1E -1 11 4.1E -1 NO DATA (0) ( -3.4 - 4.2)E o ( -3.4 - 4.2)E o (o/ 2) (0/ 2)

Cs-137 (2) 3.5E o 11 3.5E o NO DATA (0) ( -5.s - 12.6)E o ( -5. 6 - 12. 5) E o (o/ 2) (0/ 2)

I l

i 1

1 1

l i

i 30 )

1

Table 5.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station. Wiecasset, ME (January . December 1996)

MEDIUM: Estuarv Water fWE) UNITS: oCl/km i

.In..d.ic..a.t.o.r..S.t.a.t.i.o.n.s.... .S.t.a.t.io..n..W..it.h

. .. H..igh.e.s.t.M..e.a..n..

. .C.o..n.t.r.o.l.S..ta.t.io.n..s.

l Radionuclides

Mean Sta. Mean Mean >

(No. Analyses) Required Range Range Range (Non-Routine") LLD (No. Detected *") (No. Detected ***) (No. Detected"*)

H-3 (8) 3000 6.6E 2 12 6.6E 2 8.5E 1 (0) ( 9.8 - 131.1)E 1 ( 9.8 - 131.1)E 1 ( 1.6 - 12.0)E 1 (1/ 4) (1/ 4) (0/ 4)

K.40 (24) 2.1E 2 12 2.1E 2 1.1E 1 (0) ( 1.6 - 3.1)E 2 ( 1.6 - 3.1)E 2 ( -3.0 - 4.9)E 1 (12/ 12) (12/ 12) (0/ 12)

Mn44 (24) 15 -3.5E -1 20 -2.0E -1 -2.0E -1 (0) ( -2. 0 - 0.7) E O ( -1.0 - 0.6) E O ( -1.0 - 0.6)E O (0/ 12) (0/ 12) (0/ 12)

Co48 (24) 15 -4.0E -1 20 1.4E -2 1.4E -2 (0) ( -1.4 - 1.3)E O ( -1.1 - 1.1)E O ( -1.1 - 1.1) E O (0/ 12) (0/ 12) (0/ 12)

Fe40 (24) 30 5.OE -1 12 5.0E -1 -4.6E -1 (0) ( -3.2 - 3.9)E O ( -3.2 - 3.9) E O ( -5.1 - 3.8) E O (0/ 12) (0/ 12) (0/ 12)

Co40 (24) is 1.6E -1 12 1.6E -1 1.2E -2 (0) ( -1.7 - 2.5)E o ( -1.7 - 2.5)E O ( -9. 7 - 14. 3) E -1 (0/ 12) (0/ 12) (0/ 12)

Zn45 (24) 30 -2.8E -1 12 -2.sE -1 -1.2E O (0) ( -3.s - 2.1) E O ( -3.8 - 2.1)E O ( -3.0 - 4.0)E O (0/ 12) (0/ 12) (0/ 12)

Zr48 (24) is -1.4E -1 20 e.3E -2 e.3E -2 (0) ( -3.5 - 2.0) E O ( -3.5 - 2.4)E O ( -3.5 - 2.4)E O (0/ 12) (0/ 12) (0/ 12) 1131 (24) 15 -2.1E -1 12 -2.1E -1 -1.7E o (0) ( -4.2 - 5.5)E O ( -4.2 - 5.5)E o ( -1.1 - 0.3)E 1 (0/ 12) (0/ 12) (0/ 12)

Cs.134 (24) 15 1.5E -1 20 2.1E -1 2.1E -1 (0) ( -1.3 - 2.2)E O ( -1.6 - 2.3)E O ( -1.6 - 2.3)E O (0/ 12) (0/ 12) (0/ 12)

Cs.137 (24) se -4.2E -2 12 -4.2E -2 -9.5E -2 (0) ( -e.7 - 10.3)E -1 ( -0.7 - 10.3) E -1 ( -5. 9 - 9.1) E -1 (0/ 12) (0/ 12) (0/ 12)

Ba.140 (24) 15 -6.7E -1 20 3.5E -1 3.5E -1 (0) ( -4.5 - 2.1)E o ( -3.2 - 3.4)E O ( -3.2 - 3.4) E O (0/ 12) (0/ 12) (0/ 12) 31

t l

l l Table 5.1

! Radiological Environmental Program Summary )

1 Maine Yankee Nuclear Power Station. Wiscasset. ME j (January December 1996) l 1

MEDIUM: Ground Water (WG) UNITS: oCl/ka l

.In..d.ic..a.t.o.r..S.t.a.t.i.o.ns...

~ .S.t.a.t.io.n

. W...it.h..H..igh.e.s.t.M..e.a..n..

.. . .C.o. .n.t.r.o.l.S..ta.tio.n..s.....

Radmuclides* Mean Sta. Mean Mean )

l (No. Analyses) Required Range Range Range (Non-Routine") LLD (No. Detected"*) (No. Detecter **) (No. Detecter")

H.3 6,4E 1 24 1.25 2 1.25 2 (8)

(0) ( -1.7 - i.e)E 2 ( -1. 5 - 5. 7) E 2 ( -1. 5 - 5. 7) E 2 l (0/ 4) (0/ 4) (0/ 4) l Mn44 (8) -7.32 -1 13 -7.3E -1 -1.35 0 ;

(0) ( -1.7 - 0.0)E 0 ( -1.7 - 0.0)E O ( -1.s - -0.5)E O (0/ 4) (0/ 4) (0/ 4) l Co48 (8) -1.0E o 13 -1.05 0 -1.1E 0 (0) ( -2,2 - 0.0)E O ( -2.2 - 0.0)E o ( -2.4 - 0.1)E o (0/ 4) (0/ 4) (0/ 4)

Fe49 (8) 1.0E O 13 1.0E 0 -1.5E O (0) ( -2,1 - 3. 9) E O ( -2.1 - 3.9)E O ( -4.e - 2.1) E O (0/ 4) (0/ 4) (0/ 4) i Co40 (0) 1.0E -2 24 1.7E -1 1.7E -1 l

(0) ( -2.2 - 2.3) E 0 ( -9. e - 9. 9) E -1 ( -9 e - 9. 9) E -1 1 (0/ 4) (0/ 4) (0/ 4)

Zn46 (S) -2.0E O 24 -1.3E -1 -1.3E -1 l (0) ( -4.6 - 0.1)E O ( ~6.0 - 5.1)E O ( -6.0 - 5.1)E O (0/ 4) (0/ 4) (0/ 4) l Zr46 (8) -e.5E -1 24 1.0E 0 1.0E O j (0) ( -4.5 - i.e)E O ( -1.s - 41.2) E -1 ( -1.8 - 41.2)E -1 l (0/ 4) (0/ 4) (0/ 4) 1131 (s) -1.9E o 24 1.4E o 1.4E O (0) ( -3.3 - 0.2)E o ( 3.3 - 27.e)E -1 ( 3.3 - 27.e)E -1 (0/ 4) (0/ 4) (0/ 4)

Cs.134 (8) -9.9E -1 24 1.2E o 1.2E D (0) ( -1. 5 - -0. 6) E 0 ( -2.7 - 30.e)E -1 ( -2.7 - 30 e)E -1 (0/ 4) (0/ 4) (0/ 4)

Cs.137 (s) -5.2E -1 13 -5.25 -1 -6.0E ~1 (0) ( -2.5 - 2.2)E o ( -2.5 - 2.2)E 0 ( -9.1 - -2.e)E -1 (0/ 4) (0/ 4) (0/ 4)

Ba.140 (8) -1.7E O 24 1.1E D 1.1E O (0) ( -4.5 - 1.2)E O ( -5.e - 20.0) E -1 ( -5.8 - 20.033 -1 (0/ 4) (0/ 4) (0/ 4) l 32 I i

l

Table 3.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station, Wiecasse(, ME (January . December 1998)

MEDIUM. 6

.In..d.ic..a.t.o.r..S.t.a.t.io.n.s....

. .S.t.a.t.io.n..W..it.h..H..igh.e.s.t.M..e.a..n..

. . .. . C.o..n.t.ro.l.S..ta..tio.n..s.....

Radionuclides

Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine") LLD (No. Detected ***) (No. Detected"*) (No. Detected ***)

Be-7 (12) 1.6E 2 18 2.45 2 NO DATA (0) ( -3.4 - 10.0)E 2 ( -2. 6 - 10.0) E 2 (0/ 12) (0/ 6)

K-40 (12) 1.9E 4 18 2.0E 4 NO DATA (0) ( 1.7 - 2.1)E 4 ( 1.8 - 2.1)E 4 (12/ 12) (6/ 6)

Co48 (12) 3.13 0 18 1.1E 1 NO DATA (0) ( -3.2 - 4.8) E 1 ( -3.2 - 4.8)E 1 (0/ 12) (0/ 6)

Co40 (12) 2.8E 1 18 3.5E 1 NO DATA (0) ( -3.2 - 5. 9) E 1 ( 1.8 - 5.975 1 (0/ 12) (0/ 6)

Cs-134 (12) 150 6.75 0 18 1.5E 1 NO DATA (0) ( -5.4 - 5.0)E 1 ( -6.0 - 50.1) E O (0/ 12) (0/ 6)

Cs.137 (12) 180 1.9E 2 18 2.2E 2 NO DATA (0) ( 1.4 - 2.7) E 2 ( 1. 5 - 2. 7) E 2 (12/ 12) (6/ 6)

Th.232 (12) 8.7E 2 18 9.0E 2 NO DATA (0) ( 6.8 - 10.1)E 2 ( 7.2 - 9.9)E 2 (12/ 12) (6/ 6) l l

l l

33

Table 5.1 Radiological Environmental Program Samunery Maine Yankee Nuclear Power Station, Wiecesset, ME (January. December 1998)

MEDIUM Marine Ainae (AL) UNITS: oCi/ka D.N.T.8.D... 8.D..D U.D..D.. bd.8.Y.D.....

Radeonuchdes* Mean Sta. Meen . Mean (No. Analysee) Required Range Range Range (Non-Routine **) LLD (No. Detected ***) (No. Datarde**) (No. Detected ***)

Be-7 F) s.75 1 11 e.7E 1 NO DATA (0) ( -2.3 - 24.2)E 1 ( -2.3 - 24.2)E 1 (0/ 7) (0/ 7)

K-40 F) 5.8E 3 11 5.sE 3 NO DATA (0) ( 4. 6 - 6.8) E 3 ( 4. 6 - 6.8)E 3 (7/ 7) (7/ 7)

Mn44 F) 3.5E O 11 3.5E O NO DATA (0) ( -7.3 - 9.2)E O ( -7.3 - 9.2)E O (0/ 7) (0/ 7)

Co4B F) 2.5E 0 11 2.55 0 NO DATA (0) ( -4.5 - 11.4)E O ( -4.5 - 11.4)E O (0/ 7) (0/ 7)

Fe49 F) 1.1E 1 11 1.1E 1 NO DATA (0) ( -5.1 - 11.5)E 1 ( -5.1 - 11. 5) E 1 (0/ 7) (0/ 7)

Co40 F) 2.7E 1 11 2.7E 1 NO DATA (0) ( -1. 3 - 5.5) E 1 ( -1.3 - 5.5)E 1 (3/ 7) (3/ 7)

Zn46 F) 9.1E O 11 9.1E O NO DATA (0) ( -7.3 - 36.4)E o ( -1.3 - 36.4)E o (0/ 7) (0/ 7)

Ag.110M F) 1.2E O 11 1.2E O NO DATA (0) ( -1. 5 - 1.e) E 1 ( -1.5 - 1.e)E 1 ;

(0/ 7) (0/ 7) ,

1 Sb.124 F) -9.4E O 11 -9.4E O NO DATA l (0) ( -2.5 - 0.3)E 1 ( -2.5 - 0.3)E 1 )

(0/ 7) (C/ 7)

-2.9E O -2.9E O NO DATA f Cs-134 F) 11 (0) ( -1.6 - 0.5)E 1 ( -1.6 - 0.5)E 1 l (0/ 7) (0/ 7) l 2.5E O 2.55 0 NO DATA I Cs.137 F) 11 (0) ( -7.e - 12.9)E o ( -7. e - 12. 9) E O (0/ 7) (0/ 7)

I i 34 I

l

[ Table 5.1

! Rad 6ological Environmental Program Surreviary Maine Yankee Nuclear Power Station. 7" :-- O ME (January . December 1998)

MEDIUM. Milk (TM) UNITS: oCilka l

U.Y.Y.0.t,g,,, ,S,g,g,,{g,,g,, ,g,s,g,,,,,

Radionuclides

Mean Sta. Mean Mean l

(No. Analyses) Required Range Range Range (Non-Routine") LLD (No. Detected"*) (No. Detecter") (No. Detecter **)

l l K.40 (31) 1.4E 3 15 1.7E 3 1.3E 3 (0) ( 1.1 - 1. 8) E 3 ( 1. 5 - 1. e) E 3 ( 1.2 - 1.4)E 3 l

(19/ 19) (7/ 7) (12/ 12)

Sr.80 (11) 1.7E O 13 2.3E 0 -5.52 -1 (0) ( -1.4 - 4.5)E O ( -1.4 - 4.5)E O ( -2. 3 - 1. 5) E o (0/ 7) (0/ 4) (0/ 4)

Sr.80 (11) 2.9E O 15 4.4: 9 2.1E 0 (0) ( 1.3 - 5.4)E o ( 2.s - 3.4)E O ( 5.1 - 35.6)E -1 (7/ 7) ',3/ 3) (2/ 4) 1-131 (31) 1 5.e5 -4 15 2.7E -2 4.5E -3 l

(0) ( -1. 4 - 1. 0) E -1 ( -3.3 - 10.5)E -2 ( -5. 9 - 13. 9) E -2 (0/ 19) (0/ 7) (0/ 12)

[ Cs.134 (31) 15 -9.5E -1 25 -2.9E -1 -2.9E -1 (0) ( -2. 9 - 1. 5) E O ( -3.s - 2.1) E O ( -3. e - 2.1) E O (0/ 19) (0/ 12) (0/ 12) i Cs-137 (31) se 9.eE O is 2.0E 1 3.2E 0 (0) ( 1.3 - 4 9. 6) E O ( 5.1 - 49.6)E O ( -1. 9 - e.1) E O )

l (7/ 19) (7/ 7) (3/ 12)

Ba.140 (31) 15 e.4E -2 is 2.21 -1 -2.5E -1 (0) ( -2.6 - 3.0)E O ( -1. 7 - 3.0) E O ( -3.0 - 1.6)E O (0/ 19) (0/ 12) (0/ 12) 35 1 l

l i

i I

Table C.1 l

Rad 6ological Environmen(al Program Summary Maine Yankee Nuclear Power Station. Wiecasset. ME (January. December 1906)

MEDIUM: Fish (FH) UNITS. oCita

.Ir.d..c..a.t.o.r..S.t.a.t.i.o.n.e.... .S.t.a.t.i.o.n. W..it.h..H..igh.e.s.t.M..e.a..n..

.. . .C.o..n.t.r.o.l.Sta..tio.n..e..

Radeonuclides* Mean Sta. Mean Mean (No. Anahoes) Required Range Range Range

, (Non-Routine **) LLD (No. Detected"*) (No. Detected *") (No. Detected"*)

l Be.7 (4) -2.45 1 24 -2.35 1 -2.3E 1 l (0) ( -9.0 - 4.3)E 1 ( -8,5 - 3.9) E 1 ( -8,5 - 3. 9) E 1 (0/ 2) (0/ 2) (0/ 2)

K 40 (4) 2.95 3 11 2.9E 3 2.8E 3 (0) ( 2.7 - 3.1)E 3 ( 2.7 - 3.1) E 3 ( 2.0 - 2.8)E 3 (2/ 2) (2/ 2) (2/ 2) f Mn44 (4) 130 6.5E O 11 6.5E 0 5.5E O (0) ( 1. 6 - 11. 3) E O ( 1.6 - 11.3)E O 6 3.6 - 7.4)E o (0/ 2) (0/ 2) (0/ 2) l Co48 (4) 130 -5.05 0 11 -5.0E O -9.35 0 (0) ( -5. 8 - -4.3) E O ( -5.8 - -4. 3) E O ( -1.6 - -0.3)E 1 (0/ 2) (0/ 2) (0/ 2)

Fe48 (4) 260 -1.3E 1 24 1.75 1 1.7E 1 (0) ( -1.4 - -1.3)E 1 ( 1.2 - 32.6)E O ( 1.2 - 32. 6) E O (0/ 2) (0/ 2) (0/ 2)

Co40 (4) 130 1.1E 1 11 1.1E 1 -7.2E O (0) ( 4.9 - 16.6)E O ( 4. 9 - 16. 6) E O ( -1.2 - -0.3)E 1 (0/ 2) (0/ 2) (0/ 2)

Zn46 (4) 260 -2,1E 1 24 6.4E O 6.4E O (0) ( -2.7 - -1.5)E 1 ( -1.5 - 2.8)E 1 ( -1. 5 - 2.0) E 1 (0/ 2) (0/ 2) (0/ 2)

Ag.110M (4) 1.3E 0 11 1.3E 0 -1.75 0 (0) ( -1.8 - 4.4)E O ( -1.8 - 4.4) E D ( -4. 5 - 1.1) E O (0/ 2) (0/ 2) (0/ 2)

Sb-124 (4) -2.5E O 24 9.5E -1 9.5E -1 (0) ( -2. 6 - 2.1) E 1 ( -4.9 - 6.8)E O ( -4.9 - 6.8)E o (0/ 2) (0/ 2) (0/ 2)

Cs-134 (4) 130 1.7E O 24 3.7E O 3.7E O (0) ( -7.3 - 10. 6) E O ( -6.5 - 13.9)E O ( -6.5 - 13. 9) E O (0/ 2) (0/ 2) (0/ 2)

Co-137 (4) 150 1.1E 1 11 1.15 1 4.1E O l

(0) ( 7.4 - 14.3)E o ( 7. 4 - 14.3) E o ( ~7.1 - 74.9)E -1 l (0/ 2) (0/ 2) (0/ 2) i

! 36 1

l l

Table 5.1 l

r Radiological Environmental Program Summary l

Maine Yankee Nuclear Power Station. 7"-----t ME (January December 1988)

MEDIUM: Cruotaceans (CR) UNITS: oCWka l .In.d.ic..a.t.o.r..S.t.a.t.i.o.n.s..

. .S.t.a.t.io.n..W..it.h..H..igh.e.s.t

. . .. . .M..e.a..n.. C.o..n.t.r.o.l.S..ta.tio.n..s.....

Radionuclides

Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine") Lt.D (No. Detected *") (No. Detected ***) (No. Detected"*)

l i Be./ (8) 3.0E O 24 2.0E 1 2.0E 1 l (0) ( -4 . 3 - 11. 3) E 1 ( 6.1 - 42.7)E O ( 6.1 - 42.7) E O (0/ 4) (0/ 4) (0/ 4) l K-40 (8) 2.4E 3 11 2.4E 3 1.9E 3 (0) ( 2.0 - 3.0)E 3 ( 2.0 - 3.0)E 3 ( 1.6 - 2.4)E 3 (4/ 4) (4/ 4) (4/ 4)

Mn44 (8) 130 -9.1E O 24 -5.3E -2 -5.3E -2 (0) ( -2,1 - 0.1)E 1 ( -1.1 - 1.0) E 1 ( -1.1 - 1.0)E 1 (0/ 4) (0/ 4) (0/ 4)

Co48 (8) 130 -7.1E 0 24 7.5E -1 7.5E -1 (0) ( -2.2 - 0.3)E 1 ( -1.0 - 1. 7) E 1 ( -1. 0 - 1. 7) E 1 (0/ 4) (0/ 4) (0/ 4)

Fe48 (8) 260 -5.6E O 11 -5.6E O -1.5E 1 (0) ( -3.0 - 4.8)E 1 ( -3,0 - 4.8) E 1 ( -7.0 - 0.6) E 1 i (0/ 4) (0/ 4) (0/ 4) I l

Co40 (8) 130 -6.9E o 24 9.7E O 9.7E 0 (0) ( -2.6 - 1.3)E 1 ( -5.5 - 25.7) E O ( -5.5 - 25. 7) E O

. (0/ 4) (0/ 4) (0/ 4) l Zn46 (8) 260 -5.0E O 11 -5.0E O -7.8E o (0) ( -6.2 - 2.3): 1 ( -6.2 - 2.3) E 1 ( -1. 9 - 0. 8) E 1 (0/ 4) (0/ 4) (0/ 4)

Ag-110M (8) 8.9E O 11 8.9E o -4.8E O (0) ( 3.3 - 15. 6) E O ( 3.3 - 15. 6) E O ( -2. 4 - 2.7) E 1 I (0/ 4) (0/ 4) (0/ 4) j Sb-124 (8) 1.3E 1 11 1.3E 1 4.1E O ;

(0) ( -1.1 - 4. 5) E 1 ( -1.1 - 4.5)E 1 ( -5.0 - 6.0)E 1 (0/ 4) (0/ 4) (0/ 4) ,

1 Cs-134 (8) 130 5.4E O 24 1.35 1 1.3E 1 (0) ( -2. 9 - 22.7) E O ( 0.0 - 30.1)E O ( 0.0 - 30.1)E O (0/ 4) (0/ 4) (0/ 4)

Cs-137 (8) 150 -1.5E O 24 -1.0E o -1.0E 0 !

l (0) ( -1. 7 - 0. 9) E 1 ( -1.7 - 1.0)E 1 ( -1.7 - 1.0)E 1 l (0/ 4) (0/ 4) (0/ 4) l i

I i

37 l

l l

Table 5.1 i l

Radiological Environmental Program Summary Maine Yankee Nuclear Power Station, ?"---- -; ME (January Decemberiets) j l

MEDIUM. Mussel (MU) UNITS: oCl4a M.T..b.D... .b.D..D..U.D..D.. .C,g,q,S,g,,,,,

Radionuclides

Mean Sta. Mean Mean l

(No. Analyses) Required Range Range Range j (Non-Routine") LLD (No. Detecter") (No. Detecter") (No. Detecter")

Be.7 (4) 3.%E 1 24 1.2E 2 1.25 2 1 (0) ( 1.4 - 4.e)E 1 ( -1. s - 2 6. 0)

1 ( -1.s - 26.0)E 1 1 (0/ 2) (0/ 2) (0/ 2) i K.40 (4) 7.12 2 24 7.e5 2 7.e5 2 ,

(0) ( 6. 6 - 7.7) E 2 ( 5.7 - 9.9)E 2 ( 5.7 - 9. 9) E 2 (1/ 2) (1/ 2) (1/ 2) 1 I

Mn44 (4) 130 -1.65 0 24 -1.2E o -1.2E o j (0) ( -2.6 - -0.6)E O ( -3.7 - 1.3)E O ( -3.7 - 1.3)E O i (0/ 2) (0/ 2) (0/ 2)

Co48 (4) 130 -2.6E O 11 -2.6E O -e.53 0 l (0) ( -9. 9 - 4. 6) E O ( -9.9 - 4.6)E O ( -1.1 - -0. 6) E 1 j (0/ 2) (0/ 2) (0/ 2) '

Fe48 (4) 26o 2.5E 1 11 2.5E 1 -1.65 1 (0) ( 1.1 - 4.0)E 1 ( 1.1 - 4.0)E 1 ( -3.1 - -0.2)E 1 (0/ 2) (o/ 2) (o/ 2)

Co40 (4) 130 1.75 1 11 1.7E 1 -7.eE O (0) ( 1.7 - 1.7)E 1 ( 1. 7 - 1.7) E 1 ( -1.1 - -0. 5) E 1 (0/ 2) (0/ 2) (0/ 2)

Zn45 (4) 260 -e.2E o 11 -e.2E o -e 5E o (0) ( -1. s - o .1) E 1 ( -1.s - c.1)E 1 ( -3. 6 - 1. 9) E 1 (0/ 2) (0/ 2) (0/ 2)

Ag.110M (4) s.oE o 24 1.eE 1 1.e5 1 (0) ( -e.5 - 24.4)E o ( 3. s - 31.7) E o ( 3. s - 31. 7) E o (0/ 2) (0/ 2) (0/ 2)

Sb.124 (4) 9.6E O 11 9.6E O 1.7E O l (0) ( -3.2 - 22.4)E o ( -3.2 - 22.4)E o ( -1.3 - 1. 7) E 1

! (0/ 2) (0/ 2) (0/ 2) l Co.134 (4) 130 -1.1E 1 24 -3.eE O -3.8E O l (0) ( -2.1 - -0.2)E 1 ( -6. 9 - -0. e) E O ( -6. 9 - -0.8) E O f (0/ 2) (0/ 2) (0/ 2) l Cs.137 (4) 150 -2.1E O 11 -2.1E O -2.72 O (0) ( -4.2 - 0.0)E o ( -4.2 - 0.o)E o ( -4.4 - -1.0)E o (0/ 2) (o/ 2) (0/ 2) t i

e l

38

l i

Table 5.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station,7"- - ". ME l

(January .Decomtwr 1996) l MEDIUM: Soft ShellClams (MA) UNITS: oCl4m

.In.d.ic..a.t.o.r..S.t.a.t.i.o.n.s....

.S.t.a.t.i.o.n..W...it.h..H..igh.e.s.t.M..e.a..n..

.. . .C.o..n.t.r.o.l.S..ta..tio.n..s.....

Radionuclides

Mean Sta. Mean Mean (No. Analyses) Required Range Rarge Range (Non-Routine") LLD (No. Detected *") (No. Detecter") (No. Detecter")

Be.7 (4) -9.5E 1 16 -4.7E 1 No DATA (0) ( -2. s - 0.1) E 2 ( -1.0 - 0.1) E 2 (0/ 4) (0/ 2)

K-40 (4) 7.4E 2 it e.5E 2 No DATA (0) ( 2.5 - 11.4)E 2 ( 5.6 - 11.4)E 2 (2/ 4) (1/ 2)

Mn44 (4) 9.eE -1 16 1.1E 1 No DATA (0) ( -1.5 - 1.1) E 1 ( 1.1 - 1.1)E 1 (0/ 4) (0/ 2)

Co48 (4) 7.2E O 1s 7.5E O No DATA (0) ( -6.5 - 21.4)E O ( - 6. 5 - 21. 4 ) E O (0/ 4) (0/ 2)

Fe49 (4) -4.6E 0 1s e.5E O No DATA (0) ( -2.5 - 2.2) E 1 ( -4.s - 21.7) E D (0/ 4) (0/ 2)

Co40 (4) 5.3E o 16 6.6E o No DATA (0) ( -4.0 - 13.2)E O ( 0.0 - 13.2)E O (0/ 4) (0/ 2)

Zn45 (4)

-4,5E -1 1s 7.9E o No DATA (0) ( -1.4 - 2.2)E 1 ( -5.8 - 21.5) E O (0/ 4) (0/ 2)

Ag.110M (4) 1.6E 1 18 3.4E 1 NO DATA (0) ( -1.1 - 6. s)1'.1 ( 1.0 - 67.7)E o (0/ 4) (0/ 2)

Sb-124 (4) -6.3E O 18 1.2E 1 No DATA (0) ( -3.0 - 2.0) E 1 ( 3.7 - 20.4)E O (0/ 4) (0/ 2)

Cs-134 (4) -3.eE o is -5.9E -1 No DATA (0) ( -e.2 - 4.7)E o ( -5. 9 - 4.7) E O (0/ 4) (0/ 2)

Cs.137 (4) -3.7E -1 18 1.2E 1 No DATA (0) ( -2.2 - 2.5)E 1 ( 0.0 - 24960.0)E -3 (0/ 4) (0/ 2) 1 e

39 l

I l 1 l

l

[

Footnotes to Table 5.1:

l The only radionuclides reported in this table are those with LLD requirements and those for which positive radioactivity was de'ected.

l See Section 5 of this report for a discussion of other radionuclides that were analyzed.

t Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 2.5.

The fraction of sample analyses yielding detectable measurements (i.e. > 3 standard deviations)is shown in parentheses.

I t

i i

40 1

l l

t t

TABLE 5.2 ENVIRONMENTAL TLD DATA

SUMMARY

MAINE YANKEE NUCLEAR POWER STATION, WISCASSET, ME (JANUARY - DECEMBER 1996) l INNER RING TLDs OUTER RING TLDs STATION WITilll!GIIEST MEAN CONTROL TLDs I eeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeeeee sese,eeeeeeeeeeeeeeeeeeeeeeeeee seeeeeeeeeeeeeeeeee I

MEAN* MEAN* MEAN* MEAN*

RANGE

RANGE

STA. RANGE

RANGE *

(NO MEASUREMEWS)** (NO. AEASUREMENTS)** NO. (No MEASUREMENTS)** (NO AEASURENENTS)**

6.9 i 0.8 7.4

0.9 23 9.5

0.4 7.9

1.0 4.9 - 9.2 5.9 10.4 9.1 10.4 6.59.5 (71) (68) (4) (12)

Units are micro-R per hour.

" Each " measurement"is based typically on quarterly readings from six TLD clements. ,

NOTE: S.D. - Standard Deviation; S.E. - Standard Error of the Mean. I l

l l

l

\

l l

l 1

l l

41

. . _ - _ _ . . ___m. .._ - _ _ . ___.m . - _ - _ _ _ . _ _ _ _ . _ . _ . - _ . _ .

Y l

l TABLE 53 5 ENVIRONMENTAL TLD MEASUREMENTS ,

! 1996 '

! (Micro-R per llour) i i :

Sta. IST QUARTER 2ND QUARTER 3RD QUARTER 4Til QUARTER ANNUAL AVE. ,

No. Description EXP, S D. EXP. S.D. EXP. S.D. EXP. S D. EXP. S.E.

]

TbOI Old Ferry Rd. 6.6

0.4 6.9*03 8.2*03 7.4

0.2 73

03 L O2 Old Ferry Rd. 6.1

0.4 6.0*03 73 *0.4 6.9

0.2 6.6*03 l L O3 Bailey llouse (ESL) 6.2

0.2 63 *0.2 7.4

0.4 7.0

0.4 6.7*03 i TL-04 Westport Ist/Rt.144 4.9

0.2 5.5

0.2 6.9*03 5.9

0.2 5.8

0.2 !

TL-05 MY Information Cent. 7.0

0.5 7.0*03 7.9*03 7.4

0.2 73

03 )

! Tbo6 Rt.144/GreenleafRd. 7.0*03

8.0*03 7.7

0.2 7.6*03 )

TL 07 Westport Ist/Rt.144 6.2

0.2 6.6

0.2 73 *0.5 7.0

0.2 6.8* 03 i TL-08 MY Screenhouse 6.4

0.2 6.1*03 7.1

0.4 6.8

0.2 6.6*03 TL-09 Westport 1st/Rt.144 6.2* 03 6.8*03 7.6*03 7.1

0.2 6.9* 03 ,

Tblo DaileyPt. 6.5*03 6.1*03 7.1*03 6.8* 03 6.6*03 !

Tbli Mason Station 7.1

0.4 73 *03 8.1

0.5 7.7

0.2 7.6*03 l Tbl2 Westport Firehouse 6.4.* 0.2 6.6

0.2 73 *03 7.1

0.2 6.9*03 Tbl3 Foxbird Island 7.5*03 7.2

0.2 8.1*03 7.8

0.2 7.7*03 E l4 Eaton Farm 6.1* 03 5.9*03 73 *03 6.6

0.4 6.5*03 L I5 Eaton Farm 5.4*03 5.4

0.2 6.6*03 5.9

0.2 5.8

0.2 L16 Eaton Farm 63 *03 6.9*03 7.9

0.4 73

03 7.1*03 Tb17 Eaton Farm Rd. 7.7

1.0 8.1

0.4 9.2

0.4 8.6

0.2 8.4

0.5 Tb18 Eaton Farm Rd. 6.7

0.4 6.8

0.2 7.8*03 73 *0.2 7.2* 03 L19 Eaton Farm Rd. 63 *03 6.1

0.2 73

03 6.9*03 6.7*03 TL-20 Bradford Rd. 6.4

0.2 6.6*03 7.2*03 7.4

0.7 6.9

0.4 Tb21 Federal St. 6.4

0.2 6.4*03 7.4

0.4 6.7

0.2 6.7*03 4 22 Cochran Rd. 6.9*03 6.9

0.2 7.8

0.4 7.5

0.2 73 *03 L 23 Middle Rd. 9.1

0.4 9.1*03 10.4

0.6 9.5* 03 9.5

0.4 TI-24 River Rd. 73 *0.7 7.5

0.4 8.2*03 7.6

0.2 7.7

0.4 L 25 River Rd/Rt.27 6.9 e 0.4 73 *0.2 8.1*03 7.8

0.4 7.5*03 L26 Ihthbay RR Museum 7.1*03 6.9

0.2 7.9

0.4 7.4

0.4 73

03 TL-27 Barters Island 6.6*03 6.8*03 7.7*03 7.2

0.2 7.1*03 L2B Rt.144 E. Shore Rd. 6.1*03 6.6

0.4 73 *0.4 6.9

0.2 6.7*03 TL-29 Ilarrison's Trailer 6.4* 03 6.5

0.4 73 *03 6.9

0.2 6.8*03 L 30 Leeman Farm 7.9

0.4 8.0*03 8.8

0.4 8.4* 03 83 i 0.4 L 31 Barley Neck Rd. 8340.5 8.2

0.2 93 *0.4 8.8

0.2 8.7*03 Tb32 Baker Farm 7.0

0.2 7.6

6.2 8.5*03 7.8

0.2 7.7* 03 4 33 Rt.127 63 *03 6.8

0.2 7.8

0.4 7.1*03 7.0* 03 TL-34 Rt.127 63 *03 6.6

0.2 8.0

0.4 7.0

0.2 7.0*03 TL-35 Rt.127 5.9

0.2 6.2

0.2 7.5

0.4 6.8

0.2 6.6* 03 L 36 Boothb IIbr. Fire Sta. 6.6

0.8 6.5

0.2 8.2

0.4 7.0

0.2 7.1

0.4 TL 37 Dath Fire Sta. 8.8*03 8.7

0.4 9.5

0.4 9.2*03 9.1* 03 L38 Dresden Substation 7.1*03 7.2*03 8.1

0.4 7.7

0.2 7.5*03

TLD lost, apparently due to vandalism.

NOTE. S.D. - Standard Deviation; S.E. - Standard Error of the Mean.

l I

42 l

i

, , _ . . - . - ,x ._. ,, , . , _ . . . . _, - . . _ _ _ , - _ ..I

l I

6. ANALYSIS OF ENVIRONMENTAL RESULTS l

6.1 Sampling Program Deviations l TabJr 2.3 of the Offsite Dose Calculation Manual (ODCM) allows for deviations in the REMP unpling schedule "if specimens are unobtainable due to hazardous conditions, to seasonal unavailability or to malfunction of sampling equipment." Such deviations do not

]

l compromise the program's effectiveness and in fact are considered insignificant with respect to what is normally anticipated for any radiological environmental monitoring program. The 1

! specific deviations for 1996 were as follows: I The TLDs at location TL-06 were missing at the time of the second quarter collection, apparently due to vandalism.

The following short power outages occurred at air sampling stations during 1996:

a) During the week ending Jan. 31,1996 at station AP/CF-13,7.26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months .

b) During the week ending Jan. 31,1996 at station AP/CF-16,7.07 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months . ,

c) During the week ending Jan. 31,1996 at station AP/CF-29,1.06 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Due to a limited supply of milk for the REMP program, location TM-15 provided samples I from June through December during 1996 starting with week 24 and ending with a sample submitted in week 50.

6.2 Comparison of Achieved LLDs with Requirements Table 2.4 of the ODCM gives the required Lower Limits of Detection (LLDs) for environmental sample analyses. (This table is duplicated in Table 4.4 of this report.) i Occasionally 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 Appendix C,Section I requires a discussion of the situation. At the YAEL, the target LLD for any analysis is typically 30-40 percent of the most restrictive required LLD. Expressed differently, the typical sensitivities achieved for each analysis are at least 2.5 to 3 times greater than that required by the Maine Yankee ODCM.

For each analysis having an LLD requirement in ODCM Table 2.4, the aposteriori (after l 43 l

t l l the fact) LLD calculated for that analysis was compared with the required LLD. During 1996, over 1000 analyses had an LLD requirement listed in Table 2.4. All met the requirements.

6.3 Comparison of Results Against Reporting Levels l

Section 2.4.3.3 of the ODCM requires the notification of the NRC (via the Annual l Radioactive Efiluent Release Report) whenever a Reporting Level in ODCM Table 2.5 is :

exceeded. Reporting Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10.CFR 50, Appendix L It should be noted that environmental concentrations are averaged over calendar quarters for the purposes of this comparison, and that Reporting Levels apply only to measured levels of radioactivity due to plant efiluents.

During 196, no Reponing Levels were exceeded.

l 6.4 Data Analysis by Media Type !

l The 1996 REMP data for each media type is discussed below. Whenever a specific j measurement result is presented, it is given as the concentration plus or minus one standard deviation. This standard deviation represents only the random uncenainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure. A sample is considered to yield a " detectable measurement" when the concentration exceeds three times its associated standard deviation. ,

With respect to data plots, it should be noted that all values for a given graph are plotted, whether or not they are considered statistically significant (detectable).

6.4.1 Airborne Pathways 6.4.1.1 Air Particulates The weekly air particulate filters from each of the five sampling sites were analyzed for gross-beta radioactivity. At the end of each quaner, the thirteen weekly filters from each ;

sampling site were composited for a gamma analysis. The results of the weekly air particulate l sampling program are shown in Table 5.1 and Figures 6.1 through 6.5. I As shown in Figure 6.1, there has been no significant difference between the quanerly 1 average concentration at the indicator (near-plant) stations and the control (distant from plant) stations. Also notable is a distinct annual cycle, with the minimum concentration in the second

( 44 i

quarter, and the maximum concentration in the first quarter.

Figures 6.2 through 6.5 show the weekly gross beta concentration at each air particulate sampling location alongside the control air particulate sampling location at AP-29 (Dresden Substation) for the same period. It can be readily seen that the gross-beta measurements on air particulate filters fluctuate significantly over the course of a year. The measurements from control station AP-29 vary similarly, indicating that these fluctuations are due to regional changes in naturally-occurring airborne radioactive materials, and not due to hiaine Yankee operations. Table 5.1 shows that the mean gross beta concentrations from indicator stations are approximately equal to those from control locations, further supporting this conclusion.

The only other radionuclide detected on air particulate filters was Be-7, a naturally-occurring cosmogenic radionuclide.

6.4.1.2 Charcoal Cartridges The weekly charcoal cartridges from the five air sampling sites were analyzed for I-131.

The results of these analyses are summarized in Table 5.1. In 1996, as in previous years, no I-131 was detected in any charcoal cartridge. .

6.4.1.3 Mixed Grasses Although not required by the hiaine Yankee ODChi, mixed grass samples were collected twice at the Bailey Farm during 1996. No radionuclides attributable to hiaine Yankee operations were detected in either sample. Naturally-occurring K-40 and Be-7 were detected in both samples, as expected.

6.4.2 Waterborne Pathways 6.4.2.1 Estuary Water Aliquots of estuary water were automatically collected in the discharge canal outfall every two hours during 1996. These composited samples were collected monthly and sent to the YAEL for analysis. hionthly grab samples were also collected at the control location.

Table 5.1 shows that naturally-occurring K-40 was detected in samples collected at the WE-12 (plant outfall), as is typical with estuary water. The monthly samples were composited each l

45

% e v - -' g

r quarter, by station, for Tritium (H-3) analyses. One of the four samples at station WE-12 l

showed detectable levels of H-3 (1310

290 pCi/kg). The monthly samples that comprised the third quarter composite were analyzed separately for H-3 with the week 29 sample indicating a H-3 concentration of 2410 350 pCi/kg. In accordance with Table 5.1 of the ODChi, a dilution factor of 10 is applied to this concentration since the sample was taken from the discharge forebay, prior to release to the Back River via the underwater diffusers. The resulting environmental H-3 concentrations of 131 pCi/kg for the composite and 241 pCi/kg for the week 39 sample may be compared to the NRC Reporting Level for H-3 for the non-drinking water pathway of 30,000 pCi/kg. The hiaine Yankee ODChi would require notification to the NRC in the Annual Radioactive Emuent Release Report if this Reponing Level had been exceeded.

6.4.2.2 Ground Water Although not required by the hiaine Yankee ODChi, quarterly ground water samples were collected from the well at the Environmental Senices building and at a control site. The results of the gamma isotopic and H-3 analyses are shown in Table 5.1. None of these off-site l samples contained detectable radioactivity. l 6.4.2.3 Shoreline Sediment Semiannual sediment core samples were collected from two on-site locations during 1996.

Each set of samples was segmented by depth (0-5,5-10,10-15 cm) and analyzed for gamma-emitting radionuclides. The results are presented in Table 5.1. As would be expected, naturally-occurring K-40 and Th-232 were detected in all samples. I In addition, Cs-137 was detected in all twelve of the segments. Although some Cs-137 is expected to be present from worldwide weapons testing fallout, much ofit is due to early plant operations. In the early years of plant operation, routine liquid effluents were discharged in the sediment collection area. Due to poor diffusion with this method, an underwater diffuser was installed, and now the liquid efiluents are discharged into the Back River. The Cs-137 levels in sediment are plotted in Figures 6.6 and 6.7. These graphs show that the levels have not changed significantly over the past several years.

Although there is no Reponing Level for Cs-137 in sediment samples, one might appreciate the negligible dosimetric consequence when the measured concentrations are conservatively l

46

compared against the reporting levels for the fish ingestion pathway. The mean and maximum Cs-137 measurements were 190 and 271 pCi/kg (dry), respectively, both under the Cs-137 Reponing Level in fish of 2000 pCi/kg.

6.4.2.4 Marine Algae Although not required by the Maine Yankee ODCM, mixed samples ofFucus and Ascophy//um marine algae (" seaweed") were collected at Long Ledge in March, April, May, July, August and September of 1996. All samples were analyzed for gamma-emitting radionuclides. Results are listed in Table 5.1. As expected, naturally-occurring K-40 was detected on all samples. Co-60, which is attributable to plant operations, was detected in the March, April and May samples, with a three month average concentration of 49.5 pCi/kg.

Marine Algae does not represent a direct ingestion pathway to man, hence there is no dose potential. In order to put this Co-60 concentration in perspective it may be compared to the NRC Reporting Level for Co-60 of two edible products, that ofwater at 300 pCi/kg and that of fish and invertebrates at 10,000 pCi/kg.

6.4.3 Ingestion Pathways 6.4.3.1 Milk Milk samples obtained from either cows or goats from three farms were collected monthly (or as available) during 1996. Each sample was analyzed for 1-131 and other gamma-emitting l

radionuclides. The samples were composited quarterly by location and analyzed for Sr-89 and Sr-90.

The Cs-137 concentration at TM-15 for October and November were higher than normal l

(49.6 pCi/kg and 46.7 pCi/kg, respectively compared to an average concentration of 2.4 !

pCi/kg). Although this concentration was lower than the Reporting Level of 70 pCi/kg, it was j higher than the average concentration and an investigation was conducted. Initially, plant I emissions were evaluated to determine their impact on the Cs-137 concentration in milk and l were determined to have an insignificant impact. During discussions between the Environmental Services staff and the owner at TM-15 it became known that the goats had been allowed to graze and forage in an open field and woodland from September until mid November. Previously, the goats were routinely fed stored feed. In December, feed (hay and l mixed grain) and new growth (leaves, twigs, acorn) was collected from the area where the t 47 l

goats may have foraged. Goat cheese was also collected. These samples were rande.nly split between the State of Maine Public Health Lab and the Yankee Atomic Environmental Lab for gamma isotopic analysis. Cs-137 was not detected in any of the vegetation samples analyzed at the Yankee Lab (MDC values ranged between 30 - 60 pCi/kg) but was reported to be present in samples analyzed at the State Lab. This difference is thought to be attributable to the non-homogeneity of the samples and differences in detection limits. Cs-137 was detected in the goat cheese at 19.1

4.3 pCi/kg.

One additional milk sample was obtained six weeks after the goats returned to eating only stored feed and showed a decline in the Cs-137 concentration to 14.4

1.5 pCi/kg. Additional milk samples have not been available to confirm a continuing decrease in the Cs-137 levels.

Sr-90 was detected in seven out of seven indicator samples and two out of four control samples. Although this radionuclide, and Sr-89, are a by-product of plant operations, the levels detected in milk are consistent with that expected from worldwide fallout from nuclear weapons tects. These two radionuclides 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 may be fcund in soil and vegetation, as well as anything that feeds upon vegetation, directly or indirectly. Considerable variation is found to occur in milk samples from one farm to another, depending on the soil, vegetation and farming practices at each location. The increase in the annual average Sr-90 concentration at TM-15 is consistent with what would be expected following the start of grazing and foraging at that site in September.

6.4.3.2 Fish & Invertebrates !

Semiannual samples of fish and invenebrates were collected from two locations during 1996. Finfish (striped bass) were collected from FH-11 and FH-24. Crustacean (CR) samples consisted oflobsters (HA) and rock crabs (CR) and blue mussels (MU) were also cellected I from locations 11 and 24. Soft-shell clams (MJ u arenaria - MA) were collected from two l locations within Bailey Cove. The edible portions of each of these were analyzed for gamma- l emitting radionuclides. As expected in biological matter, naturally-occurring K-40 was detected in 16 out of 20 samples. No other radionuclides were detected.

l l l

48 1

I I

i l

l 6.4.4 Direct Radiation Pathway Direct radiation is continuously measured at 38 locations surrounding the Maine Yankee plant with the use of thermoluminescent dosimeters (TLDs). These are collected every calendar quaner for readout at the YAEL.

As can be seen in Figures 6.10 to 6.20, there is a distinct annual cycle at both indicator and controllocations. 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. DifTering amounts of these naturally-occurring radionuclides in the underlying soil, rock or nearby building ma'.eiials result in different radiation levels between one field site and another. It can be seen from Figure 6.17 that the TLD at Middle Road in Edgec.amb (TL-23) has historically given slightly elevated readings. This is apparently due to its clo~ oroximity to a ledge outcrop, making it the station with the highest annual exposure in 1996. .' similar situation occurred at the Westpor' Siren (TL-09). To prevent vandalism of the TLD, it was moved to a less conspicuous area not far from the original site at the start of the third quarter of 1993. This site was closer to a rock outcrop, and the exposures increased slightly. The TLD location was subsequently moved to another nearby location, and the exposure rates dropped (see Figure 6.13). l From Tables 5.2 and 5.3, as well as from Figure 6.10, it can be seen that the Inner and Outer Ring TLD mean exposure rates were not substantially different in 1996, and that the Control TLD mean exposure rate was slightly greater than that at the Inner and Outer Rings.

TLDs are also located on-site in the area bordering the western security fence and mudflats i along Bailey Cove. These TLDs are not considered part of the radiological environmental I monitoring program as defined in ODCM Table 2.3, however, the effective dose in this area I based on the TLD results are reported in the Maine Yankee " Estimated Dose and Meteorological Summary Report" pursuant to Technical Specification 5.9.1.6.2.

6.4.5 Silt from Circulating Water System Intake Bays Maine Yankee's Circulating Water System provides water for condenser cooling, drawn from the adjacent Back River. During the 1993 and 1995 refueling outages, silt and mussel shells were removed from the Circulating Water System Intake Bays. This material

! accumulates as a normal consequence of water use, and contains trace levels of radioactivity i

i

. -. - - - - - . _ - - . - - _ . - - . . - - - . - - . . . - . - . - . . ~ . - .~

which are attributable to licensed Maine Yankee liquid effluents. The material also contains a small amount of sediment from the one-time cleaning of the Service Water pipes. This material is being handled on-site under a license issued by the Maine Department of Environmental Protection.

t !

l \

l Although no additional silt was spread in this area during 1996, one sample was collected in l

l November and submitted to the Yankee Atomic Environmental Lab for gamma isotopic analysis. This sample contain'ed detectable levels ofonly naturally occurring K-40 and Th-232.

l I

h i

2 l

l l

I I

l l

4 i

50

.= -_ - -. . _. . _ . _

l 1' 1

FIGURE 6.1 GROSS-BETA MEASUREMENTS ON AIR PARTICULATE FILTERS ;

QUARTERLY AVERAGE CONCENTRATIONS i 0.06 _

0.0S 0.05i -0.05 n 0.04 - -0.04 E -

$ 0.03i -0.03 h -

x ,x -

0.02 ,

-0.02 0.01 - - 0.01 O' .

, . , . 0 1987 1989 1991 1993 1995 1997

-e- Indicator Stations x- Control Stations l

1 1

l l 51 l

?

FIGURE 6.2 l GROSS-BETA MEASUREMENTS l

ON AIR PARTICULATE FILTERS l

0.06 , 0.06 0.05i -0.05 1i5 0.042 -0.04 lii :

E -

x. . x o '

x 25 3 0.03 ~ x

/ ',

, -0.03

.. X

X S : '.

+

X. .

o" '

~

X -0.02 0.025 ,

x 0.01 { - 0.01 W

~

0 .

. , , . O Dec Feb Apr Jun Aug Oct Dec 1996

--e- AP 11 Montsweag Brook i

x- AP-29 Dresden Substation (control) l l

l F

52

l i

FIGURE 6.3 .

GROSS-BETA MEASUREMENTS l ON AIR PARTICULATE FILTERS 0.06 _ 0.06 0.05i -0.05 li; 0.04- -0.04

x E

x o .- ;.

25 0.03 -- x' .

x -0.03 i

~

5 X.

o" -

X

! 0.02i

.l -0.02 i

. . x !

, \

1 0.01 -- -0.01 1 i

\

O' .

. O Dec Feb Apr Jun Aug Oct Dec 1996 l

-e- AP 13 Bailey Farm (ESL) !

-x AP-29 Dresden Substation (control) l 53 w

FIGURE 6.4 1

l GROSS-BETA MEASUREMENTS :

l ON AIR PARTICULATE FILTERS ;

0.06 _ 0.06 f . .

1 0.052 -0.05 iii 0.04- -0.04 5 : x E . - ,

o . x 2i 0.03-x 9 -0.03 M -

Y l x

0 : : 1

,6

. .Mx',

-0.02 0.02 -- . l

x. x .

0.01 -0.01 l

O' . , .

. , , . O Dec Feb Apr Jun Aug Oct Dec 1996

-D- AP-14 Mason Steam Station x- AP-29 Dresden Substation (control) l l

l l

l

)

l 54

P 1

FIGURE 6.5 l GROSS-BETA MEASUREMENTS i ON AIR PARTICULATE FILTERS l

l 0.06 0.06 0.05 f ' 0.05 5 0.042 - 0,04 e . -

E -

D o :. '

x 0.032 -0.03

5 .

. L<

j :

x i

o" -

l 0.02i x',' -0.02 l

- x !

0.01 { -0.01 O' . , ,

., . O Dec Feb Apr Jun Aug Oct Dec 1996

-e- AP-16 Westport Firehouse

-x- AP-29 Dresden Subs % tion (control) l l

i 55

I

~

l l

j FIGURE 6.6 i CESIUM-137 IN SHORELINE SEDIMENT j STATION SE-16,OLD OUTFALL AREA .

! 600 600 1 : ,

i : l j 500 _

-500 l l :

~

l 400-' -400 y

i u -

~

1 5 300- -300

! 5 :

O -

g .. ___ __

5/93 10/93 5/94 10/94 5/95 10/95 5/96 10/96 j Month / Year E 0-Sem i

E 5- 10 cm O 10 - 1s em 56

. _ . _ - .. - - - - - - = ..- . - . - . - . . . . _ - . - . _ _ -

l I .

I j

j i 1 FIGURE 6.7

! CESIUM-137 IN SHOREUNE SEDIMENT STATION SE-18, FOXBIRDISLAND 600 ,

600

~

j 500-- -500 l 4002 -400

p

2.

y 300-- -300 1 q :

2002 -200

~

100

-100

]

0-- i i i i i i --O j 5/93 10/93 5/94 10/94 5/95 10/95 5/96 10/96 Month / Year

.1 E 0-5cm E 5-10cm

[] 10 - 15 cm 57 l

FIGURE 6.8 CESIUM -137 IN MILK ANNUAL AVERAGE CONCENTRATIONS 40 40

[ _

30 -30 en -

hc. 20- -

-20 10 -10 W*

0 ,

, 0 1986 1988 1990 1992 1994 1996

-e- TM-15 Mitman Farm

-o- TM-18 Chewonki Foundation A TM-25 Hanson Farm 58

FIGURE 6.9 -

STRONTIUM -90 IN MILK ANNUAL AVERAGE CONCENTRATIONS 25 ,

25

-20 20f 15- -15 y :

~

S :

-10 10-

~ ~

O .

, 0 1986 1988 1990 1992 1994 1996 .

--o- TIA15 Mitman Farm

-o- TM-18 Chewonki Foundation e TM-25 Hanson Farm 59

FIGURE 6.10 EXPOSURE RATE AT INNER RING, OUTER RING AND CONTROLTLDS 25 25

~

20- -20

~

5

$ 15- ~

-15 b

a. -

T :

._.@10- -10 .

'.x 2

'x -

x- -

y ,

5- -5 O . . . , . . ,

i . . . , 0 1992 1993 1994 1995 1996 1997 Retrieval Data

-x- Contro! ,

e Inner Ring

-e- Outer Ring 60

FIGURE 6.11 EXPOSURE RATE AT INNER RING TLDS, TL 01-04 25 ,

25 20f -20 5 .

$ 15- -

-15 m ~

D.

9

$ 10- -10

/ /

5- -5 0 . . .

. . . , . . . , . . ,'O 1992 1993 1994 1995 1996 1997 Retrieval Date

-e- TL-01 Old Ferry Road x TL-02 Old Ferry Road

~

A TL-03 Bailey House (ESL) o TL-04 Westport Island, Rt.144

~

61

1 FIGURE 6.12 EXPOSURE RATE AT INNER RING TLDS, TL 05 - 08 _

25 25 20 -- -20 E : f

$ 15- -

-15 m

a. -

cr h10- -10 5 : , ~

.y 5- -5 0 . . .

i . . .

i 0 1992 1993 1994 1995 1996 1997 Retrieval Date

-e- TL-05 MY Information Center

-te- TL-06 Rt.144 & Greenleaf Road

-c- TL-07 Westport Island. Rt.144

-o- TL-08 MY Screenhouse 62

FIGURE 6.13 EXPOSURE RATE AT INNER RING TLDS, TL 09-10,12-13 25 25 5

20- -20 5 5

$ 15- -

-15

? 5

a. -

tr o

b 10- -10

'x,, j[ -

5- -5 0 . . . , . .

i i

i i 0 1992 1993 1994 1995 1996 1997 Retrieval Date

-e- TL-09 Westport Siren

--x- TL-10 Bailey Point e TL-12 Westport Firehouse o TL-13 Foxbird Island 63

FIGURE 6.14 EXPOSURE RATE AT INNER RING TLDS, TL 14-16 25 25 es 20 -20 5 5

-E 15- -

-15 m

a. -

C h10- -10 5 -5 0 . . .

i . . . , . . . , 0 1992 1993 1994 1995 1996 1997 Retrieval Date

+ TL-14 Es. ton Farm x TL-15 Eaton Farm e TL-16 Eaton Farm 64 l

FIGURE 6.15 EXPOSURE RATE AT INNER RING TLDS, TL 17 - 19 25 25 20 -20 5 .'.

$ 15- -

-15 m

a -

T .'.

$ 10- -10 1 -

r i e 5- -5 0 .

..,.. ,.. ,...,.. , 0 1992 1993 1994 1995 1996 1997 Retrieval Date

+ TL-17 Eaton Farm

-x- TL-18 Eaton Farm =

4 TL-19 Eaton Farm 65

FIGURE 6.16 EXPOSURE RATE AT INNER RING TLDS, TL 11,20-22 25 25

-20 20f 5

$ 15- -15 g -

a. -

C h10- -10 5 : N-

- [g Y

^ u - 21 5; -

-5 O . . , . ,

, . . . , . . . , . . . , 0 1992 1993 1994 1995 1996 1997 Retrieval Date

-e- TL-11 Mason Station

-x- TL-20 Bradford Road, Wiscasset ,

4 TL-21 Federal Street, Wiscasset c TL-22 Cochran Road, Edgecomb 66

FIGURE 6.17 EXPOSURE RATE AT OllTER RINGTLDS, TL23-26 25 25 20- -20 5

$ 15- -

-15 a

o. -

~

CC s

/

5 -- -5 0 , . . , . . .

i 0 1992 1993 1994 1995 1996 1997 Retrieval Date

-e- TL-23 Middle Road, Edgecomb x TL-24 River Roed, Edgecomb e Ti -25 River Road & Rt. 27 e TL-2G Rt. 27 & Boothbay RR Museum 67

'l 5

i FIGURE 6.18 !

EXPOSURE RATE AT OUTER RING TLDS, TL 27-30 25 25

\

- \

20f -20 Ei :

$ 15- -15 i :

x -

6 -

t5 10- -10 gP' e 5- , -5 i

1 0 . . .

i 0 i I

1992 1993 1994 1995 1996 1997 Retrieval Date

-e- TL-27 Barters Island

-x- TL-28 Westport Island, Rt.144 & East Shore Road !

e TL-29 Harrison's Trailer o TL-30 Leeman Farm, Woolwich I

68

I r

l l

l FIGURE 6.19 EXPOSURE RATE AT OUTER RING TLDS, TL 31-35 25 25 ,

. ?

20 -20 I 15- -15 m . .

x -

f= 10f -10 5-.

-5 O . . .

. . . , . . . , . . . , 0 1992 1993 1994 1995 1996 1997 i RetrievalDate i

-e- TL-31 Barley Neck Road, WooWeh i

--x- TL-32 Baker Farm, WooWeh i I

--a- TL 33 Route 127 WooWeh

--o- TL-34 Route 127, WooWeh

+ TL-35 Route 127 Woolwich t I

69 ;

. t

i 1

l l FRURE 6.20 ;

EXPOSURE RATE AT CONiSCc RINGTLDS, TL36-38 25 25 i

. i I

20- .

-20 !

i u -

s .

0 ,

I 15- -15 4 u -

g .

x -

$ 10_'

o x -10 3 -

^

^ ^

A w W b -

~

{

5- -5 v

0 . . .

, O i 1992 1993 1994 1995 1996 1997 Retrieval Date ;

i

-e- TL-36 Boothbay Harbor Fire Station l x TL-37 Bath Fire Station l e TL-38 Dresden Substation 1

I

! 70 l

l 1

7. QUALITY ASSURANCE PROGRAM The quality assurance program at the YAEL 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, reduction, evaluation and reponing of data, as well as the record keeping of the final results. Quality control, as pan of the quality assurance program, provides a means to control and measure the characteristics of measurement equipment and processes, relative to established requirements.

The YAEL 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 approved and 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 and retraining system. Monitoring programs include the Intralaboratory ;uality Control Program l administered by the Laboratory QA Officer (used in conjunction with the National Institute l Standards and Technology's Measurement Assurance Program, NIST MAP) and third party i interlaboratory programs administered by the EPA and Analytics, Inc. Together these programs are targeted to supply QC/QA sources at 3% of the routine sample analysis load. In addition the Laboratory Quality Control Audit Committee conducts a blind duplicate quality assurance program.

7.1 Intralaboratory Quality Control Program I

l The YAEL conducts an extensive intralaboratory quality control program to assure the ,

j validity and reliability of environmental analytical data. Process check samples are either l samples submittcd in duplicate to evaluate the precision of the measurements or are " spiked" with a known quantity of radioactive material to assess the bias in the measurement. The program is administered by the Laboratory QA Officer. A summary of the program process j check results may be found in Table 7.L For each of the three results falling in category 4 of l the Bias Criteria, the mean bias for the set was within 15% and no further action was required.

71

- . . . - - -. _ .~ -- - - - - _ - _ - - --

i 7.2 Third Party Intercomparison Program I l

To further v tr;r vthe accuracy and precision of the Laboratory analyses the YAEL participates in tuo independent third parties intercomperison programs. At the end of 1995 ,

the U.S. Environcier.tal Protection Agency stopped its Environmental Intercomparison Studies Program. To replace the mix of radionuclides and matrices which comprised this one program l the Laboratory now participates in two third party programs, the U.S. EPA Performance Evaluation Study for radionuclides in water and the Analytics Inc. Environmental Cross Check Program for radionuclides in milk, water and on air filters. Participation in such programs and the reporting of results in this report is p.irsuant to Maine Yankee ODCM Section 2.4.5 and Technical Specification 5.8.1.b.3.

Each sample supplied by the EPA or Analytics is analyzed in triplicate and the results are returned to the EPA or Analytics within a specified time frame. When the known values are returned to the Laboratory, the :esults are evaluated against specific Laboratory acceptance -

criteria and the EPA results tre also evaluated against the EPA controllimits. When the results of the cross-check analysis fall outside of the acceptance criteria or control limit, an investigation is initiated to determine the cause'of the problem and if appropriate, corrective ;

measures are taken. j l

For the EPA Intercomparison Program,26 sample sets in a water matrix were analyzed.

The analyses included gamma-emitting radionuclides, gross alpha, gross-beta, Sr-89, Sr-90, low level I-131, tritium (H-3), Ra-226, Ra-228 and Natural Uranium. Table 7.2 provides a summary of the results for 1996.

One result did not fall within the EPA control limits and is described below:

The mean value for Gross Alpha in water (Reference date 7/19/96) of 10.82 pCi/L failed to fall within the EPA control limits of 13.8 - 35 pCi/L. An investigation was conducted (YLCAR IG-02-96) which indicated that the deposition of solids during processing was i the likely root of the problem (EL 608/96). Subsequent processing of an EPA gross alpha set ( Reference date 10/25/96) and a process check set (Reference date 01/22/97)

yicided a mean bias of +1.6% and -2.9%, respectively. The Laboratory is continuing to j j investigate the development of a mass correction curve. l t ;

l l

For the Analytics Inc. Cross Check Program,18 sample sets in water, milk and air filter !

matrices were analyzed. The analyses included gamma-emitting radionuclides, gross alpha, gross-beta, Sr-89, Sr-90, low level I-131, tritium (H-3), Ra 226, Ra-228 and Natural Uranium.

Table 7.3 provides a summary of the results for 1996.

The Analyticsfresults which failed to meet the criteria for acceptance are discussed below. l

+ YAEL Inquiry 3-96 was issued in response to the failure of the results for Mn-54 and ;

Fe-39 in sample set E0717-162 (Reference date 2nd quarter,1996) to meet the '!

acceptance criteria of *15%. The investigation determined that the root cause was differences in the filter spiking techniques used at the Laboratory and Analytics (EL I 522/96 and EL 614/96). A mixed gamma filter calibration source was purchased and j used to set up a calibration curve for the Analytics filter geometry. The mean bias was re-evaluated for all nuclides and was found to be +2.9%. No further action is ,

considered necessary. !

The reported mean bias for the gross beta on air filter set E0902-162 failed to meet the ;

criteria for agreement of *15%. YLCAR IG06-97 was issued on 3/18/97.

l 7.3 Environmental TLD Quality Assurance Program ,

?

i Performance documentation of the routine processing of the Panasonic environmental TLDs (thermoluminescent dosimeter) program at the YAEL is provided by the dosimetry quality j assurance testing program. This program includes the National Voluntary Laboratory i Accreditation Program, independent third party performance testing by Battelle Pacific Northwest Labs and internal performance testing conducted by the Laboratory Quality I Assurance Officer. Under these programs, dosimeters are irradiated to ANSI specified testing ;

criteria and submitted for processing to the Dosimetry Services Group as " unknowns". The l

bias and precision of TLD processing is measured against this standard and is used to indicate i trends and changes in performance. Instrumentation checks, although routinely performed by i 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 i the doses are known to the processor.

?

The YAEL processed 3232 environmental TLDs during 1996. Ninety-six independent I performance tests were conducted. Of these 96 TLDs,72 were submitted by the Dosimetry 73

. ~ . ~- - . ,

performance tests were conducted. Of these 96 TLDs,72 were submitted by the Dosimetry QA Oflicer and 24 were submitted as part of Battelle Pacific Northwest Laboratories testing program. All of these, or 100% met the acceptance criteria for accuracy and precision with an average bias during the first half of 1996 of 0.7*2.6 and -3.8*5.0 during the second half of ,

1996.

i 7.4 Blind Duplicate Quality Assurance Program The Laboratory Quality Control Audit Committee (LQCAC)is comprised of one member from each of the five sponsor power plants that are serviced by the YAEL. Two of the primary functions of the LQCAC are to conduct an annual audit of Laboratory operations and to coordinate the Blind Duplicate Quality Assurance Program. Under the Blind Duplicate Quality Assurance Program, paired samples are submitted from the five plants, including the Maine Yankee Nuclear Power Station. They are prepared from homogeneous environmental l

media at each respective plant, and are sent to the Laboratory for analysis. They are " blind" in that the identification of the matching sample is not identified to the Laboratory. The LQCAC analyzes the results of the paired analyses to evaluate precision in Laboratory measurements.

Forty-nine paired samples were submitted under this program by the five participating plants during 1996. Paired measurements were evaluated for twenty-five gamma emitting radionuclides, H-3, Sr-89, Sr-90,1-131, Ra-226 and gross-beta. All measurements are evaluated, whetha the results are statistically positive or not, and whether the net ,

concentration is positive or negative. Of the 1283 paired measurements evaluated in 1996, ;

1273 (99.2%) fell within the established acceptance criteria. Only one of the ten measurements falling outside the acceptance is considered to have statistically positive gross beta activity and is being addressed by the Laboratory as corrective action YLCAR IG07-97.

The samples submitted through this program are listed in Table 7.4.

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l Table 7.2 Yankee Atomic Environmental Laboratory ;

1996 EPA Intercomparison Program I LOWER UPPER REFERENCE E-LAB CONTROL CONTROL MICLIDE MEDIA _DATE_ MEAN* LIM!T* LIMIT

Co-60 Water 10/17/95 47.36 40.3 57.7 Cs-134 Water 10/17/95 36.96 31.3 48.7 Cs 137 Water 10/17/95 29.86 21.3 38.7 Nat U Water 10/17/95 26 5 21.8 32.2 Ra-226 Water 10/17/95 26 18 4 31.2 Ra-228 Water 10/17/95 21.1 11.7 29.7 Sr-89 Water 10/17/95 22.53 11.3 28.7 Sr-90 Water 10/17/95 9.74 1.3 18.7 lBa-133 Water 11/03/95 94.1 81.7 116.3 iCo-60 Water 11/03/95 58.77 51 3 68.7 iCs-134 W ater 11/03/95 36.55 31.3 48.7 lCs-137 Water 11/03/95 50.77 40.3 57.7 Sr-89 Water 01/23/96 79.2 64.3 81.7 Sr-90 Water 01/23/96 4.65 0 13.7 Zn-65 Water 11/03/95 126.6 102.4 147.6 H-3 Water 03/08/96 23429.8 181851 25818.9 Co-60 Water 04/16/96 31.4 22.3 39.7 Cs 134 Water 04/16/96 43.03 37.3 54.7 Cs-137 Water 04/16/96 49.02 41.3 58.7 INat. U Water 04/16/96 55.47 48.3 68.5

'ka-226 Water 04/16/96 3.6 2.1 3.9 Ra 228 Water 04/16/96 5.14 2.7 7.3 Sr-89 Water 04/16/96 46.07 34.3 51.7 Sr-90 Water 04/16/96 14.73 7.3 24.7 Ba-133 Water 06/07/96 734.63 614.9 875.1 Co-60 Water 06/07/96 95.99 90.3 107.7 Cs 134 Water 06/07/96 76.35 70.3 87.7 Cs 137 Water 06/07/96 198.1 179.7 214.3 Zn-65 Water 06/07/96 303.43 248 352 Nat. U W ater 06/21/96 19.02 15 25.4 Ra 226 W ater 06/21/96 5.39 3.7 6.1

{Ra 228 Water 06/21/96 8.07 5 13 l I

Units in pCi/ Liter 76 l '

l

Table 7.2, continued Yankee Atomic Environmental Laboraton 1996 EPA Intercomparison Program LOWER UPPER REFERENCE E-LAB CONTROL CONTROL LE!CLlDS MEDIA DATE MEAN* L M T' LIMIT

Sr-89 Water 07/12/96 24.37 16.3 33.7 Sr-90 Water 07/12/96 11.92 33 20.7 Alpha Water 07/19/96 10.82 13.8 35 Beta Water 07/19/96 40.53 36.1 53.5 H3 Water 08/09/96 10227.8 8991.4 12766.6 Nat. U Water 09/27/96 9.68 4.9 15.3 Ra-226 W ater 09/27/96 13.22 10.4 17.6 Ra-228 Water 09/27/96 6.24 2.6 6.8 1-131LL Water 10/04/96 28.24 16.6 37.4 Co-60 Water 10/15/96 13.71 6.3 23.7 Cs-134 Water 10/15/96 18.99 11.3 28.7 Cs-137 Water 10/15/96 30.02 21.3 38.7 Nat. U Water 10/15/96 38.74 33.8 48 Ra 226 W ater 10/15/96 9.07 7.3 12.5 Ra-228 W ater 10/15/96 6.67 2.8 7.4 '

Sr-89 Water 10/15/96 11.8 1.3 18.7 Sr-90 Water 10/15/96 22.93 16.3 33.7 Alpha Water 10/25/96 10.47 1.6 19 Beta Water 10/25/96 34.6 28.2 47.2 Ba-133 Water 11/08/96 60.94 53.6 74.4 Co-60 Water i1/08/96 43.68 35.3 52.7 Cs 134 Water 11/08/96 10.65 2.3 19.7 Cs-137 Water 11/08/96 19.74 10.3 27.7 7;i-65 Water 11/08/96 34.46 26.3 43.7 Nat U Water 12/06/96 4.71 0 10.2 Ra 226 Water 12/06/96 18.62 14.9 25.3 Ra-228 Water 12AM/96 10.5 5.7 14.7

Units in pCi/ Liter l

i l

l 4

77 l i

l l

Table 7.3 YAEL 1996 ANALYTICS CROSS-Cl3ECK RESULTS

_ l l

Sample: E0642162 Quaner: I st,1996 l E0645-162 Sr89/90 l

Media: Milk Units: pCi/L !

Ratio I Nuclide Reported Known YAEU Evaluation Value Value Analytics Cr-51 875 858 1.02 Agreement Mn-54 88 84 1.05 Agreement Co-58 132 128 1.03 Agreement Fe-59 235 223 1.05 Agreement Co-60 207 204 1.01 Agreement Zn-65 267 260 1.03 Agreement Sr-89 35 31 1.13 Agreement Sr-90 17 16 1.06 Agreement 1 131 11 13 0.85 Agreement I-131LL 11.8 13 0.9i Agreement Cs 134 155 154 1.01 Agreement Cs-137 170 170 1 Agreement Ce-141 237 234 1.01 Agreement l

Sample: E0643-162 Quarter: !st,1996 E0641-162 Alpha / Beta E0644-162 Ra/U Media: Water Units: pCi/L Ratio Nuclide Reported Known YAEU Evaluation Value Value Analytics r--

Alpha 12 10 1.2 Agreement Beta 118 107 1.03 Agreement Cr-51 328 322 1.02 Agreement Mn-54 30 31 0.97 Agreement Co-58 48 48 1 Agreement Fe-59 85 83 1.02 Agreement Co-60 73 76 0.96 Agreement l

Zn-65 9Q 97 0.93 Agreement 1-131 34 36 0.94 Agreement Cs-134 55 58 0.95 Agreement Cs-137 63 64 0.98 Agreement Cc-141 88 88 l Agreement il Ra-226 68 70 0,97 {

, l' Agreement ;

7 Ra-228 3 49 49 l 1 Agreement 11-234 1 40 40 l 1 Agreement l

! l J-2 3)( 42 41 ! 1 02 Agr eement

.=======:=:=---- -

== -

78

Table 7.3 continued YAEL 1996 ANALYTICS CROSS-CHECK RESULTS Sample: E0717162 Quarter: 2nd,1996 E0716-162 Alpha /lleta E0719-162 Sr89/90 Media: Air Filter Units: pCi/ Filter Ratio Nuclide Reported Known YAEU Evaluation Value Value AnaMies Alpha 41 40 1.03 Agreement 3

Deta 185 179 1.03 Agreement Cr-51 1071 953 1.12 Agreement Mn-54 597 508 1.18 Non-Agreement Co-58 176 157 1.12 Agreement Fe-59 151 131 1.15 Non-Agreement Co-60 153 142 1.08 Agreement Zn-65 110 98 1.12 Agreement Sr-89 <MDC 44 pCi/ Filter -------

Sr-90 57 64 0.89 Agreement Cs 134 281 282 1 Agreement Cs-137 797 694 1.15 Agreement i Cc-141 380 363 1.05 Agreement j l

Sample: E0718-162 Quarter: 2nd,1996 E0720-162 Media: Milk Units: pCi/L Water H3 I Ratio Nuclide Reported Known YAEU Evaluation Value Value Anahties H-3 4580 4915 0.93 Apeement K-40 1350 1269 1.06 Agreement Cr-51 581 563 1.03 Apeement Mn-54 311 300 1.04 Agreement ,

Co-58 93 93 Apcement 1

j Fe-59 82 , 77 1.06 Agreement i Co-60 84 84 1 Apeement

{ l Zn.65 53 58 0.91 Ageement

{

! l 131 16 15 1.07 Aptement ll l

! Cs-134 167 166 1.01 Agreement ll Cs 137 '

l 409 410 1 Apeement j j Ce-141 219 215 1.02 Ap eement j l

l 79 i

l l

i Table 7.3 continued YAEL 1996 ANALYTICS CROSS-CHECK RESULTS l Sample: E0818-162 Quarter: 3rd,1996 E0820-162 Sr89/90 l Media: Milk Units: pCi/L Ratio Nuclide Reported Known YAEl> Evaluation Value Value Analytics Cr 51 514 486 1.06 Agreement Mn54 189 180 1.05 Agreement Co-58 132 131 1.01 Agreement Fe-59 40.8 37 1.1 Agreement Co-60 118 114 1.04 Agreement Zn 65 73 70 1.04 Agreement Sr-89 54 50 1.08 Agreement Sr 90 22 22 1 Agreement I-131 24.5 24 1.02 Agreement Cs-134 226 222 1.02 Agreement '

Cs-137 176 169 1.04 Agreement Cc-141 325 318 1.02 Agreement Sample: E0819-162 Quarter: 3rd,1996 E0817-162 Alpha / Beta E0821-162 Sr89/90 Media: Water Units: pCi/L Ratio Nuclide Reported Known YAEll Evaluation Value Value Analytics Alpha 77 74 1.04 Agreement Beta 77 70 1.1 Agreement j Cr-51 650 646 1.01 Agreement Ma-54 248 239 1.04 Agreement Co-58 172 174 0.99 Agreement Fe-59 51 50 1.02 Agreement Co-60 155 151 1.03 Agreement Zn-65 98 93 1.05 Agreement Sr-89 47 40 1.18 Agreement Sr-90 36 35 1.03 Agreement 1-131 49 50 0.98 Agreement Cs-134 299 295 1.01 Agreement Cs-137 226 225 l Agreement j Cc-141 420 423 0 99 Agreement l

l 80

l 1

Table 7.3 continued YAEL 1996 ANALYTICS CROSS-CIIECK RESULTS l

i Sample:/ Media E0901-162 Milk Quarter: 4th,1996 E0902-162 Filter Sr-89,90 E0903162 Water H-3 Units: pCi/L pCi/ Filter Ratio Nuclide Reported Known YAEU Evaluation Value Value Anahties Alpha 75 80 0.94 Agreement Beta 199 170 1.17 Non-Agreement H-3 2440 2686 0.91 Agreement Cr-51 202 214 0.94 Agreement Mn-54 217 206 1.05 Agreement Co 58 120 121 0.99 Agreement Fe-59 52 49 1.06 Agreement Co-60 113 110 ; 1.03 Agreement '

Zn-65 94 93 l.01 Agreement Sr-89 102 96 l

1.06 Agreement Sr-90 72 77 0.94 Agreement 1-131 65 59 1.10 Agreement I-131LL 56 59 0.95 Agreement Cs-134 168 175 0.96 Agreement Cs-137 194 195 0.99 Agreement Cc-141 278 277 1.00 Agreement i

81

l l

~

i

)

l Table 7.4 j Summary of Blind Duplicate Samples January December 1996 1

l Sample Type Number of Paired Samples Submitted ;

I Cow milk 21 Ground Water 6 Surface Water 15 Algae 2 j Mussels 4 Food Crop 1 TOTAL 49 l

l I

i 82

I i

8. LAND USE CENSUS i Maine Yankee Technical Specification 5.8.1.b.2 requires that a Land Use Census be l conducted annually, pursuant to the details given in Section 2.4.4 of the Offsite Dose I Calculation Manual (ODCM). The Census identifies the locations of the nearest milk animal, l the nearest residence and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles of the l plant. The 1996 Land Use Census was conducted between the required dates ofJune 1 and l October 1.

1

\

l Pursuant to Section 2.4.4 of the ODCM, 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 twice the potential dose commitment of 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). For the 1996 Census, no such new milk animal location was identified.

Consequently no changes were made in the milk sampling program.

The results of the 1996 Land Use Census are included in this report in compliance with

! ODCM Section 2.4.3.4 and ODCM Appendix C, Part 1. The locations identified during the Census may be found in Table 8.1.

I i

1 1

I l

l l 1 l l 83

TABLE 8.1 1996 LAND USE CENSUS LOCATIONS SECTOR NEAREST NEAREST NEAREST MILK RESIDENCE GARDEN ANIMAL Km (Mi) Km (Mi) Km (Mi)

N 1.3 (0.8) 1.3 (0.8) "

NNE 2.3 (1.45) 2.3 (1.45) 2.6 (1.6)(Cows)

NE 1.3 (0.8) 1.3 (0.8) **

ENE 0.9 (0.6) 1.2 (0.76) **

E 0.9 (0.6) 0.9 (0.6) "

ESE 1.4 (0.9) 1.4 (0.9) **

SE 0.7 (0.4)* 0.9 (0.6) "

SSE 0.9 (0.6) 0.9 (0.6) **

S 1.7 (l.1) 2.7 (l.7) 5.6 (3.5)(Goats)

SSW 3.0 (1.9) 5.0 (3.1) "

SW l.4 (0.9) 1.4 (0.9) 7.9 (4.9)(Cows)

WSW 0.8 (0.5) 0.8 (0.5) 1.9 (1.2) (Cows)

W 0.8 (0.5) 0.8 (0.5)* ** '

1 WNW 0.8 (0.5) 2.8 (1.7) **

NW 2.0 (l.3) 2.0 (l.3) "

NNW l .2 (0.7) 1.2 (0.75) 8.1 (>5)(Cows)

The nearest residence, garden or milk animal to Maine Yankee.

No location was identified within 5 miles of the plant.

1 l

84

l l

9. 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 UnitedStates and Cimada from NaturalBackgroundRadiation, National Council on Radiation Protection and l l Measurements,1987.

3. loni:ing Radiation: Sources andBiologicalEffects, United Nations Scientific ;

Committee on the EfTects of Atomic Radiation (UNSCEAR),1982 Repon to the General Assembly.

t

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

- S. Maine Yankee Final Safety Analysis Report.

6. NRC Generic Letter 89-01,

Subject:

Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program. Dated January 31, 1989.

7. USNRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Efiluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.

l I

I 85 i l

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