Text

Annual Radiological Environ Operating Rept,Jan-Dec 1998, for Maine Yankee Nuclear Power Station
	ML20206D736
Person / Time
Site:	Maine Yankee
Issue date:	12/31/1998
From:	; DUKE ENGINEERING & SERVICES
To:	;
Shared Package
ML20206D725	List: ML20206D719; ML20206D736; ML20206D756; ML20206D779; ML20206D798;
References
	NUDOCS 9905040225
	Download: ML20206D736 (91)
	v • d • e

y, 5

MAINE YANKEE NUCLEAR POWER STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January - December 1998 l

April 1999 i

l l

i l

Prepared by:

Duke Engineering and Services Environmental Health and Safety l

, 580 Main Street Bolton, Massachusetts 01740

/

9905040225 990429 PDR ADOCK 05000309 PDR

i. R , ,

p 1

EXECUTIVE

SUMMARY

L During 1998, as in'all previous years of plant operation, a program was conducted to

' assess the levels of radiation or radioactivity in the Maine Yankee environment. More than 700

samples were collected (including TLDs) over the course of the year, with approximately 1800 radionuclide or exposure rate analyses being performed on them. The samples collected as part of this program include ground water, estuary water, sediment, marine algte, fish, mussels, clams, crabs, lobsters, mixed v' egetation and milk. In addition to these samples, the air surrounding the

. plant was sampled' continuously and the radiation levels were r. aasured continuously with environmental TLDs.

l

\

I Low levels of radioactivity from naturally-occurring, fallout and plant emission sources were detected. Most 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. Some milk, sediment, and mixed grass samples contained fallout radioactivity from atmospheric nuclear weapons tests conducted primarily from the late 1950's through 1980.- A few saynples had low levels of radioactivity resulting from emissions from Maine 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.

Maine Yankee shutdown in December of 1996. In August 1997 the decision was made to permanently cease power operation. The plant has since begun the process of decommissioning which will eventually involve the disassembly and removal of the plant components and structures. This process will take place in strict conformance with USNRC regulations.

Oversight will also continue from the State of Maine.

The radiological environmental monitoring program for Maine Yankee continued during 1998, unchanged from previous years.

ii l-m.

l TABLE OF CONTENTS

1. INTRO D U CTIO N . . . . . . . . . . .. . . . . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . .

2. NATURALLY OCCURRING AND MAN-MADE BACKGROUND RA D I O A CTIVIT Y . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

2.1 Naturally Occurring Background Radioactivity ............... .... ........ . . ............. 2 2.2 Man-Made B ackground Radioactivity ....... ................. ... ................ ........ ..... 3 l

i

3. GENERAL PLANT AND SITE INFORM ATION ... ............ . .... ...... ................. .. . 5

4. P R O G R AM D E S IGN . . . . . . . . . . . . . . . . . . . . .. .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l 4.1 M o n i t o ri n g Zone s . . . . .. .. . . . . . .. . .... .. . . ... . . . . . . . . ... . . .. . . .. . . ... . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . 7 !

4.2 Pathways M o nitore d . . . . . . . .. . ... .... . . .. .. . .. . .. . . . . . . . . . . . .. . . . .. . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 ]

4.3 Descriptions of Monitoring Programs ................................ ....... .... .... .... ..... . 8 4

l

5. R ADIOLOGICAL DATA SUMM ARY TAB LES .......... .. ......................... ............ 24

6. ANALYSIS OF ENVIRONMENTAL RESULTS...... .. . .............. ........................... 41 6.1 S ampling Program Deviations... .... ........ ......... ................................ ....... .... 41 6.2 Comparison of Achieved LLDs with Requirements ............................. .. ...... 41 6.3 Comparison of Results Against Reporting Levels .... ....... . ...................... ... 42 6.4 Data An alysis by Media Type ................................. .......... .... ..... ... . . . ... . . . . ...... 4 2

7. QUALITY A S S UR ANCE PROG RAM .............. ..... .. ........................................... .. 71 7.1 Intralaboratory Quality Control Program . . .. ... ........... .. ..................... ..... . 71 7.2 Third Party Intercomparison Program .......................... ........ .. ... .................. 72 7.3 Environmental TLD Quality Assurance Program .... . .............................. .... 74 7.4 Blind Duplicate Quality Assurance Program ..... .... ..... . .......... . ................ 74

8. LAN D U S E C EN S U S . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

9. R E FE REN C E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

til

LIST OF TABLES Iable Title Pace 4.1 Radiological Environmental Monitoring Program .................. ..... 12 4.2 Radiological Environmental Monitoring Imcations (Non-TLD) in 1998 ......... ... .......... ............................... 14 4.3 Radiological Environmental Monitoring Locations (TLD) in 199 8 . .......... ... ............ . .. ..... ................. .. .. . 16 4.4 Environmental Lower Limit of Detection (LLD)

S ensitivity Requirements . ...................... . . ... .......... .. ....... .. . ..... .... I8 4.5 Reporting Levels for Radioactivity Concentrations in Environmental S amples ... ................ ...... ...... .... .............. ... . .. .. . 19 5.1 Environmental Radiological Program Summary ............................ 26 5.2 - Environmental TLD Data Summary ............. ........... ............... .... 39 5.3 Environmental TLD Measurements .... .............. ........ .................. 40 l

7.1 Environmental Process Control Analysis Results ........................... 76 l 7.2 EPA Inter-comparison Program Results .......................................... 77 DESEL 1998 Analytics Cross-Check Results ...................... .... .. 78 l 7.3 .i 1

I l

l 7.4 Summary of Blind Duplicate Samples Submitted ........ ........ ........ 81 l

j 1

i i 8.1 1998 Land Use Censu s Locations ....................................... .......... 83

! l l

5V a

L

p l

L LIST OF FIGURES -

Eigurer - Title Page 4.1 Radiological Environmental Sampling Locations Within 1 Kilometer of Maine Yankee ......... .......... ......................... 20 l l

l 4.2 Radiological Environmental Sampling Locations Outside 1 Kilometer of Mair.e Yankee............................................... 21 l

4.3 - Direct Radiation Monitoring Locations Within 1 Kilometers of Maine Yankee ............................................ . 22 i

4.4 Direct Radiation Monitoring Locations ,

Outside 1 Kilometer of Maine Yankee .................. .............. ............ 23 6.1 Gross-Beta Measurements on Air Particulate Filters ......................... 48 (Quarterly Average Concentrations) 6.2 Gross-Beta Measurements on Air Particulate Filters ............. . ......... 49 j (AP-11 vs. AP-29 Control) ,

6.3 Gross-Beta Measurements on Air Particulate Filters ......................... 50 (AP-13 vs. AP-29 Control) 6.4 Gross-Beta Measurements on Air Particulate Filters .............. ......... 51 (AP-14 vs. AP-29 Control) 6.5 Gross-Beta Measurements on Air Particulate Filters

( AP- 16 vs. AP-29 Control)..... ...... ................. ... .......... ..... ........... .... . 5 2 6.6 H-3 in Estuary Water WE-12, Plant Outfall.. ............. ....... ............... 53 6.7 Cesium-137 in Shoreline Sediment Station SE- 16, Old Outfall Area ... ................. . ........................ .... . 54

, v i

p o

l i

! LIST OF FIGURES (continued)

Figure Title Pace 6.8 Cesium-137 in Shoreline Sediment Station SE-18, Foxbird Island.................... ..................... . ..... ..... 55 6.9 Cesium-137 in Milk, 1998......................................................56 6.10 Cesium-137 in Milk Annual Average Concentrations............ ...... 57 6.11 Strontium-90 in Milk,1998 Quarterly Composites.... .... ............... 58 6.12 Strontium-90 in Milk Annual Average Concentrations.... ............. 59 6.13 Exposure Rate at Inner Ring , Outer Ring and Control TLDs........ 60 6.14 Exposure Rate at Inner Ring TLDs, TL01 -04 . . ... ... . . .. .. . . . . . . . . . . . .. . . 61 6.15 Exposure Rate at Inner Ring TLDs, TL 05 -0 8 . ... . . .. . . . . ... . . . . . . . . . . . .. 62 6.16 Exposure Rate at Inner Ring TLDs, TL 09,10,12,13.................... . 63 l

6.17 Exposure Rate at Inner Ring TLDs, TL 14-16 .. ........ .. .. ......... 64 6.18 Exposure Rate at Inner Ring TLDs, TL 17-19 ....... . ............ ... ... 65 6.19 Exposure Rate at Outer Ring TLDs, TL11,20-22........... ....... . ... 66 6.20 Exposure Rate at Outer Ring TLDs, TL23-26 .... ......... ............ .... 67 L

1 vi l

1 i

L t I

r. -

j LIST OF FIGURES (continued)

Figure Title Page 6.21 Exposure Rate at Outer Ring TLDs, TL 27-30 .. ........................... 68 6.22 Exposure Rate at Outer Ring TLDs,TL 31 -3 5 . . . . . ... ... . . ... . . .. . . .. . .. . . . . 69 ;

4 1

6.23 Exposure Rate at Control TLDs, TL 36-38 ................ ............... 70 i

l l

, 1

! 1 1

vii

1. 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 1998. It is submitted annually in compliance with Appendix C, item 1 of the Offsih Dose Calculation manual (ODCM) and Technical Specification 5.7.2. The remainder of this repon 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 design. Included is a summary of the ;

ODCM requirements for REMP sampling, tables listing routine sampling 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 Reporting 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 1998 monitoring program. The performance of the program in meeting ODCM requirements is discussed, and the data acquired during the year is analyzed.

Section 7: Provides an overview of the Quality Assurance programs used at the Duke Engineering and Services Environmental Laboratory. The results of the Laboratory participation in an Interlaboratory Comparison Program required by ODCM section 2.4 are l l

also given.

Section 8: Summarizes the requirements and the results of the 1998 Land Use Census.

Section 9: References 1

l l

l 1

2. NATURALLY OCCURRING AND MAN-MADE BACKGROUND RADIOACTIVITY l

Radiation or radioactivity potentially detected in the Maine Yankee environment can be l grouped into three categories. The first is " naturally-occurring" radiation and radioactivity. The l second is " man-made" radioactivity from sources other than the Maine Yankee plant. The third potential source of radioactivity is due to emissions from the Maine Yankee plant. For the L 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.

i 2.1 Naturally Occurring Background Radioactivity Natural radiation and radioactivity in the environment, which provide the major source of human radiation exposure, may be subdivided into three separate categories: '" primordial radioactivity," "cosmogenic radioactivity" and " cosmic radiation." " Primordial radioactivity" is made up of those radionuclides that were created with the universe and that have a sufficiently long half-life to be still present on the canh. 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 category of naturally-occurring radiation and radioactivity is "cosmoeenic radioactivity." This is produced through the nuclear interaction of high energy cosmic radiation with elements in the earth's atmosphere, and to a much lesser degree in the earth's crust. These radioactive elements are then incorporated into the entire geosphere and atmosphere, including the earth's soil, surface rock, biosphere, sediments, ocean floors, polar ice and atmosphere. The major radionuclides in this category are Carbon-14 (C-14), Hydrogen-3 (H-3 or Tritium),

Sodium-22 (Na-22), and Beryllium-7 (Be-7). Beryllium-7 is the one most readily detected, and is found on air sampling filters and occasionally in biological media (Reference 2).

2

r 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 lesser degree from the sun. We are protected from most of this radiation by the earth's atmosphere, which absorbs the radiation. Consequently, one can see that with increasing elevation one would be exposed to more cosmic radiation as a direct result of a thinner layer of air for protection. This

" direct radiation" is detected in the field with gamma spectroscopy equipment, high pressure ion chambers and thermoluminescent dosimeters (TLDs).

2.2 Man-Made Background Radioactivity The second source of" background" radioactivity in the Maine Yankee environment is from

" man-made" sources not related to the power plant. The most recent contributor to this category was the fallout from the Chemobyl accident in April of 1986, which was detected in the Maine Yankee environment and other parts of the world. A much greater contributor to this category, however, has been fallout from atmospheric nuclear weapons tests. Tests were conducted from 1945 through 1980 by the United States, the Soviet Union, the United Kingdom, China and France, with the large majority of testing occurring during the periods 1954-1958 and 1961-1962.

(A test ban treaty was signed in 1963 by the United States, Soviet Union and United Kingdom, but not by France and China.) Atmospheric testing was conducted by the People's Republic of China as recently as October 1980. Much of the fallout detected today is due to this explosion and the last large scale one, done in November of 1976 (Reference 3).

The radioactivity produced by these detonations was deposited worldwide. The amount of fallout deposited in any given area is dependent on many factors, such as the explosive yield of the device, the latitude and altitude of the detonation, the season in which it occurred, and the timing of subsequent rainfall which washes fallout from the troposphere (Reference 4). Most of this t'allout 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.

3

c j 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). .

1 l

1 I

l l

4 i

1 i

3. GENERAL PLANT AND SITE INFORMATION The Maine Yankee Nuclear Power Station is located in the town of Wiscasset, Lincoln County, Maine, approximately six miles northeast of Bath, Maine. The site vicinity is rural and !

lightly populated.

J The plant site is located on Bailey Point, a peninsula bounded to the east by the Back River and to the west by a shallow inlet known as Bailey Cove. Both of these estuaries flow south into Montsweag Bay, which is a tidal estuary of the Sheepscot River. (See the maps in Figures 4.1 to 4.4) Bailey point is an elongated bedrock ridge with flat or gently rolling topography rising to an average elevation of about 25 feet above sea level (Reference 5).

The single 900 megawatt PWR (Pressurized Water Reactor) unit at Maine Yankee began commercial operation in 1972. The Radiological Environmental Monitoring Program (REMP) began preoperational measurements in 1970, two years prior to commercial operation. The REMP has been in continuous operation since that date.

Maine Yankee shut down in December 1996. In August 1997 the decision was made to permanently cease power operation after 24 years of operation . The plant is currently in the process of dec.ommissioning which will eventually involve the disassembly and removal of the 3 plant components and structures. This process will take place in strict conformance with USNRC regulations. Oversight will also continue from the State of Maine. !

The radiological environmental monitoring program for Maine Yankee continued to operate {

during 1998. l l

l 5

l L

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:

i 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 assuranc:: to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits.

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

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

These objectives will continue to be in force, to varying degrees, throughout decommissioning activities at the Maine Yankea site.

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

Prior to January 1992, the requirements for the Radiological Environmental Monitoring Program (REMP) were stated in the Radiological Effluent 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).

The REMP is a requirement of the ODCM. 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 Section 5 of the ODCM. The locations actually monitored in 1998 are shown on Tables 4.2 and 4.3, as well as Figures 4.1 through 4.4 of this report. The locations in these tables and figures consist of the required locations specified 6

7 l

in the ODCM, as well as any regularly sampled locations. Sampling sites that were used on only one occasion during 1998 are not shown in the tables or maps, but are discussed in the text.

During 1997, the environmental sampling and TLD locations were determined using a differential ,

[ Global Positioning System (GPS), with a typical accuracy of less than 5 meters. The reference point chosen for direction and distance was the plant Primary Vent Stack (PVS).

4.1 Monitoring Zones The REMP is designed to allow comparison of levels of radioactivity in samples from the area possibly influenced by the plant to levels found in areas not influenced by the plant. The 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 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, airbome, waterbome, 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 detail in this section:

Airborne Pathway Air Particulate Sampling Charcoal Cartridge (Radiciodine) Sampling Mixed Vegetation Sampling (for airborne deposition) l -Waterborne Pathways Estuary Water Sampling Ground Water Sampling 7

p

_ . . - - g

p t

J Shoreline Sediment Sampling {

I Marine Algae Sampling Ingestion Pathways Milk Sampling j Fish and Invertebrate Sampling l Direct Radiation Pathway TLD Monitoring )

4.3 Descriptions of Monitoring Programs 4.3.1 Air Sampling i

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 dy-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 it least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months at the Duke Engineering and Services Environmental Laboratorv %SEL) before being analyzed for gross-beta radioactivity. The weekly filters are composited by location at the DESEL for a quarterly gamma spectroscopy analysis.

4.3.2 Charccal 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-131. A dq-gas meter i

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 stmeture. 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 DESEL for an I-131 specific gamma isotopic analysis.

8

1 1

4.3.3 Mixed Vegetation Sampling ,

Although there is no ODCM requirement for mia,ed 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 DESEL, where it is analyzed for gamma-emitting radionuclides.

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 j 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-liter samples are again composited at the Environmental Services labomtory before shipping to the DESEL 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 NaHSO3 to 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 DESEL for a quarterly H-3 analysis.

4.3.5 Ground Water Sampling i

Due to the hydraulic gradient at the Maine Yankee site, whereby the ground water flow is j southward down the peninsula and toward the water on 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 one on-site location and one control location. All ground water samples are preserved with hcl and NaHSO3 to prevent the plate out of l radionuclides on the container walls. Each sample is analyzed for gamma-emitting radionuclides I'

and I!-3.

)

i l

l 1

9 l

1

l 4.3.6 Sediment Sampling l 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. ;

4.3.7 Marine Algae Sampling Mixed samples of Fucus and Ascophyllmn marine algae are collected at least semiannually from a location near the plant diffuser discharge. Each sample is frozen for shipment to the 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 sufficiently far away from the plant to be outside any potential influence from it.

Samples of milk are chilled after collection and shipped to the DESEL on ice. Methimazole and formaldehyde are added to the milk upon receipt at the Laboratory. Each sample is analyzed for gamma-emitting radionuclides and, following chemical separation and puritication, 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 quarterly composited samples.

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

Maine Yankee Environmental Services staff collect samples of fish, crabs, lobsters and Molluscs (blue mussels). All samples are separated by species and are then frozen and delivered to the 10 l

r DESEL, where the edible portions are analyzed for gamma-emitting radionuclides.

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 1998, two seasonal samples of soft-shell clam (Mya arenaria) were collected from two locations within Bailey Cove. The clam samples were frozen and analyzed for gamma emitting radionuclides at the DESEL. These samples are not required by Maine Yankee ODCM.

4.3.10 TLD Monitoring 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 hou, sed 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 DESEL.

4.3.11 Special Monitoring On occasion, special interest samples are taken that are not required as a part of the 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 they appear in Table 4.1 or 4.2 of this report. The analysis results may be discussed in Section 5 of this report, as appropriate.

l i l1

q

,i y n b

( i o

t te e a i

s i

t s n _

y o o _

.si c p p im _

s n a t

ya e.. m m e n l

c o c l eo pC c c iipp o n . ip C i

p lp c -

AaF D m y) m my mm ma r o

L a lr n a al r a a f T S e o S Se t SS S h h t

r i t hc h ra hh h ic c a a c c c c h c

a a uc a au a a a a s E E Ql o E EQ EE E t iu -

i s s l

y e r

a a n s A ie e

e-g r u

e i

s l

e t s r s

y e p p c i

n r ic icp eg lay m ip a ip) p) r nT e a o C to3- to3- o h a

A s t o e o1 o1 t

o c o :f- a s i n sI s1 s e d I ( I ( I r zte I l a a r a

m lu B a m

k o am m u am m m u o -

ic s i 1 t n

m a tr a r s

o ma d3 a1 miir a

t mi ai r t m a i e -

G PG G RI -

GT GT G d a -

r g .

i c

l u

- a r

a m) ny dy _

oc a3 r .in ly h _

g2 o

t ec eu la e r

r e l q ly u e PM a l

oc y lr y ly r n

n h

gT CFi e l ht e a w s

n t r

a L

c n tr a

i m a i

e o u e _

rM e Q u

W M Q S e r a _

e l C n nD i _

1 MyoO )

s es 4 s o a b l

r p 2 E t 8 h r _

L n9 1

2 u 1 B e9 e g ac y p _

A m1 mg n

ihl r n _

u pa t s s e o T en n om u u e v i t

ram t

ri o o o ie a r s g 6

vu itc S u n

u n o puo t

ir -

nd E d le id i

tn mq b h

a i r

=

l o u o oh r r r l

e C a

C (a G G o a

ci r C C g ig u n o q i k

l e or n i ir -

d sa d a r R( s f o

n J f i o ( .

ota c 8 n.

.r 2 2 2 .

e o 3 5 :

t

: s bL :

s s s s s i mc ui n

o n

io n

o n

o e c

p i i i i r

Nma ta c

ta c

t c

a ta c

o ta c

u o

s S o o o l l x s L L l i l

a l

t a

l a la ht t

o to o to to n T T T T T h e _

w n

e k

t a

e b

d ll .

y n hs a

a ) a w a s s h

i d D e t

t n

s c

e L a e ip tarM P /o T( lu ic

m m ed c n r r e

i d a s

r uap ni o t r e e s

i a ta ta S r o m ia t

P e p

S a

d

(

)

c n W W c ta n a e y d in w E R e ni n l w

m r a n u le r

d n

t rl ox r u o o u x bs e ta ts r h o r

m r ik E. G. S. G W a b c D. A. da .

I 2R 3

y s

ic s n lyeu

. a nqe e c i c cc ii lpp ip pp A :r I mm ma aa mm aa -

s s s s s hh -

hh h c c c c c a a a a a s

EE E EE i

s y

l a

n A e 5 lb i

d c

n is s o y e p ic c c lay p i

p ip nT o o o A to t

o as I

s a

m m3

'1 mo I

s a s mia tr n

I a

m m3 1

Gp o a1 a1 G1 -

Gl -

d m) a3 l a

ny oc f n r nin lyi e g2 t )

o c e a lae hw rl e i l

.mle uq unta Pb ol noi yi c a Noe C r ly ns hla b gT ht ia e a pl I

n n tni i

r n o ms p oa t

i oM C M e r S (o ap Mav nD 1 )

MyoO 4 de a b l

u 3 E.

l i n t n98 1 e9 e ng t

Ba At n

a1 nic mg . il i pn T (c en e t

u i ir ri t omM Ra vndu i t

c S -

E d le l ba b a

h a

l e o r r r a

ci r C G G G gg u i

l o e e ior d sa e a n R( f o os d r n e o t

o hi t n ma u c 3 2 3 is .

NI x g .

s s s n .

lai c n n n i lp np o i o i o

ita t

a ta m im m a c c c a s

oS x o x N l l

L l

I l

k l

a a a t im to to o f T T' T i y

l n

o d

ly d e a m la o r n w o i

o t f

f r

ta o ep y e s a s r e g w ia ec p* n h d e ta er s) y i Iv r t

lp tar 3 PoM ( )n e

c oi o m r ye c

/

ed e t si a s

r nl ua p el p c ta t

vl as t c

s m ut o n d. d ge u

. at a I n o r e p d x S d o n n . i Pv r E o it s

e lt l

i hs i

a

. wd m , .

. o ea ol f

d P

o g

n M F. (u i

l.

b I

I. a b c 4 *

(

TABLE 4.2 )

Radiological Environmental Monitoring Locations (non TLD) in 1998 Maine Yankee Nuclear Power Station l

Distance Direction Station From Plant From Exoosure Pathway Code Station Description Zone * (km) Plant i

1. Airbome

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

& Charcoal Filters AP/CF-13 Bailey Farm (ESL) 1 0.7 .

NE j AP/CF-14 Masoc Steam Station 1 4.8 NNE l AP/CF-16 Westpon Firehouse 1 1.8 S l AP/CF-29 Dresden Substation 2 20.1 N :

1 l

b. Mixed Grasses - TG 11 Bailey Farm (ESL) 1 0.7 NE i

2. Waterborne

a. Surface Water WE-12 Plant Outfall 1 0.3 SSW (Composite Sample)

WE-20 Kennebec River 2 9.5 WSW (Grab Sample)

b. Ground Water WG-13 Bailey Farm (ESL) 1 0.7 NE l

WG-24 Morse Well 2 9.9 W

c. Sediment SE-16 Old Outfall Area 1 0.6 S SE-18 Foxbird Island 1 0.6 S l

d. Clam ** MA-16 Old Outfall Area 1 0.65 S MA-18 Foxbird Island 1 0.65 S

e. Marine Algae AL-11 Long Ledge Area 1 0.9 S 1

3. Ingestion

a. Milk TM 15 Mitman Farm 1 5.5 S TM18 Chewonki Foundation 1 1.9 WSW TM-25 Hanson Farm 2 18.3 W 14 L

TABLE 4.2 j (continued)

Radiological Environmental Monitoring Locations (non TLD) in 1998 Maine Yankee Nuclear Power Station Distance Direction j Station"* From Plant From l Exoosure Pathway Code Station Description Zone" (km) Plant

3. Ingestion, continued FH 11 Long Ledge Area 1 0.9 S

b. Fish & MU-l1 Invenebrates CA-Il HA-11 FH-24 Sheepscot River 2 11.1 S MU 24 CA-24 HA-24

1 = Indicator Stations; 2 = Control Stations

" MA = Soft-Shell Clams (Mya arenaria).

~"* FH = Fish, MU = Mussels, CA = Crabs, HA = Lobsters l ESL = Environmental Services Laboratory 15

T+

i '.

TABLE 4.3 I Radiological Environmental Monitoring Locations (TLD) in 1998 Maine Yankee Nuclear Power Station Distance Station From Plant Direction ]

Code Station Description Zg_ne, (km) From Plant ;

TL-1 Old Ferry Rd. I 0.9 N TL-2 Old Ferry Rd. I 0.8 NNE TL-3 Bailey House (ESL) 1 0.7 NE ;

TL-4 _ Westport Island, Rt.144 I 1.3 ENE l TL-5 MY Information Center I 0.2 - ENE TL-6 Rt.144 & Greenleaf Rd. I. 1.0 E TL-7 Westport Island, Rt.144 I~ 0.9 ESE TL-8 MY Screenhouse 1 0.2 ESE l TL-9 Westport Siren I 0.8 SE j TL-10 Bailey Point I 0.3 SSE TL-11 Mason Station O 4.8 NNE TL-12 Westport Firehouse I 1.7 S

- TL-13 Foxbird Island I 0.3 SSW i TL-14 Eaton Farm I 0.7 SW TL-15 Eaton Farm I 0.8 WSW TL-16 Eaton Farm I 0.7 W TL-17 Eaton Farm Rd. I 0.6 WNW TL-18 Eaton Farm Rd. I 0.8 NW TL-19 Eaton Farm Rd. I 0.9 NNW TL-20 Bradford Rd., Wiscasset O 6.4 N TL-21 Federal St., Wiscasset O 7.1 NNE TL-22 Coci ran Rd., Edgecomb O 8.3 NE TL Middle Rd., Edgecomb O 6.4 ENE TL-24 River Rd., Edgecomb O 7.8 E TL-25 River Rd. & Rt. 27 O 7.7 ESE TL 26 Rt. 27 & Boothbay RR Museum O 7.9 SE TL-27 Barters Island O 7.2 SSE

- TL-28 Westport Island, Rt.144 & E. Shore O 7.9 S Rd.

l TL-29 Harrison's Trailer O 6.2 SSW TL-30 Leeman Farm, Woolwich O 7.8 SW 16

I .,

l TABLE 4.3 (continued)

Radiological Environmental Monitoring Locations (TLD) in 1998 Maine Yankee Nuclear Power Station Distance 1 Station From Plant Direction Code Station Description Zpni n (km1 From Plant TL-31 Barley Neck Rd. O 6.8 WSW TL-32 Baker Farm, Woolwich O 7.3 W TL-33 Rt.127, Woolwich O 7.4 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 12.2 SSE j TL-37 Bath Fire Station 2 10.7 WSW TL-38 Dresden Substation 2 20.1 N

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

I-17

(

l

[ _

t ng ek) 0 0 miy/

5 8 i

de Crd p

1 1 S(

_ )

t

_ s t s e t

dou/gc w n 0 0 0 e od k 6 6 8 _

m e

Fo/ri .

i r PCp

_ u q

(

e _

R y ) .

t l i k/ 5 8 5 d v l i iC 1

1 1 1 e .

i Mp sd

_ t i

s ( u e n e s e b u S ye

) ab -

mya

- D s) et e L t a

l l m -

_ 4 L

( &r w b g 0 0 0 03 0 0 5

i Clpi

/

6 6 3

_ 4 n o hs t ek ir /

3 1 2 1 2 1 I 0 pC E i t

FeivC 0 05 8 .

. L c e np 31 1

B t i(

f f A e oo D

T f

ee u u -

o l a a l

et e vv _

t i )

i m na rl s

a 'm 1 7 5 6 a, a ,

L ouGi bi c rC

/ 0 0

0 0 0 0 0 0 s s t t s s

_ r r t op i i e ir x x AaP w

( ee _

o yy

- L aa l ww t

a hh t t n a pp a

e r r m r) l

e e el n t i 4 0 0 5 0 5 10 5

5 8 5 t aa t

o r aC 0 1 3 3 1 1 I 1 ww W (p 1

i v 2 gg n ii n n E kk n n ii r r a 0 dd s t e 0 5 4 7 4 oo i 4 9 6, 5 9- 1 1 nn -

s y B- 3- 5- 5- 8 6 b 3 3 1

3 1

a f f l

a s s

l I

n e 5- -

n N- 1 s

s L-I I n o M F o Z r 1 C C a

A r C Z B * * -

G

=

t s

c u

dl ) 0 0 -

o/

ri 0 0 00 00 PC 1 1 2 -

d (p -

o F

o -

) _

kl l 0 .

s l

iC i

3 0 6 07 0 d e

n Mp 3 s

o ( u d i

t a e e r b s .

t y u _

n a e e s) m b c y n s et e t

l

/ a oe &rba gw 0 0 0 0 0 0 0 i

C m Cl p 0 0 0 0 0 0, 0 0 p ym 0, l h ek 0, 0, 0, 0 0 /

t ia is rt/ 0 0 0 0 0 1 2 0 0

i Cp -

FeivC 3 1 3 1 2 .

5 i t

vS np 0, 4 cat a l

I ( 0 3

0 2

E i one f o

f o

9 1

L d B am e u

e u

A Rn o s l

a l

a T rr oi e e s na t e ') v v f v rl s m a a s n oua/ 9 0 10 ,

s 0 2 s l

eE br icGiC t s

t s

L veIn it Aa o (p P

r r i x

e i

x e

y y g a a -

i n w w -

t r ht ht o a p a

p p e r) * *

r r R 0

e e 0

0 00 0 0 00 0 0* 0 *

l el 0 0 t t -

t i 0 0 a a -

aC 0, 0 0 3 5 0

W (p 0 1 4 1 3 3 04 2 2 w g

w g

2 n .n -

i yi kl k n n n r oi r i

0 d t d n i

s 4 8 0 5 5

9- 4 7 1 4 oe nr no s

y 3- 5-9 5- 5 6 6 b-1 3

3 3 - f a f 1 1 a I PI l

a 1 n e o o n N- l s

s L- .

n 1 M F C C Z r I C C a A Z B * .

Figure 4.1 1 Environmental Radiological Sampling Locations (within 1 km)

U r .-

MVs I Maine Yankee

.k: .2 L u..s

.~..,.q:m.

J,.:n..~e~:~, ..

.f~ .'- l. r. R

. . ~. ., .. .*,*~s~.

p.

f. /s~

~. .w F.,ain..~M. ..

h. r; . .

.y.'.

A,si+,yi % .h u ; a. .

gu~x .

T.&n.5:k ...e,.

.N.4 4' . ,,ye.r.. ,. ~:i .. s iid5?s8e . n -eq:n n7s.;hu'd.~,:, A f

~ ~

,u.97^7 ruu r:

W-@.a

.m.*::u.*me

. ~yr:rm:~rs.~!?: s*

~

u.m

~ncru~~r

.w~u~m,.

y<rw

.H ,~ ;o a

g; w

! ,3 m., .

.,w~~ ~m:

uw ~:~ s. Lq~~yn!,'~s esen~.~p~qpm.yp:w.sgnui r~ ~

~,nt ;rm>

an

~

~t/ ~rr~.~.1. w.r,1wn. . . ., .. &w.. ' ~ .

a.r... n

.ugp a.m~p~ -syr wu wr.~~~s. ,.

wrnrw . n,u.

w .v. g

<M zug ' :p.- p.s.,i . ~ssm :~s ~ . ,~.. -+:

u .~;:

.u . . ; ~~:~s u. vu~: ::s.~;m weu~~w ~;~r+ h:

I

%y; y;m..)n ,

p;."::. ~sd: ....m e~s ;ueuuuu:mn ;v?nrnn;n mm:m. . .~.uu R...s: as AP!C.EQ,- . ::%..~.0.~ m.m;am.t::n n:asm n..~ma es.u z:u ue. e-am~waumi .uw .su;=.

1 w . ..

r ppm, f :m:n.:Ar:u uw

xa -

mj;p.sm;;r{a:;.

zumy.,

.um.n ,gu~ .~-

pry;:u.:r~p'c.pa.uuuu:t2msa; m am vrwnun,:

p mm,uu.; uum mu g:.u w.uwpw ~sm.:~.._

um,pj;,x sumn.,ua;;gmu.$,

emmp m gaayn.puus.;p;a.a:-c.,u:

g: an nan:r;~.r:ona,mmm-~~

m-a:.s

..r:r y.,a:nm

.u..,~~.vmy.p. x: mn.s~ma y~., a :,u

m. u~ : q:us,,.w.:n

~n . :

.num:; pus.my.:e.su E ~gy .y.n.m.p.m. r::. w mn

..y .,

upwn:m;y,m:

u a.u ur gess .:uuv~.au:.u

.msw ~ u:5.. ;m*

.s a.:n, u.uu;u um .:;

sm u .:!1.s:

1 suuA cpA gmqp,. rg ;.... ux ar :su.um:nw;m m qp;pau...a" :us:

au:.mu.nuw. :n~p~p~~

w.9x.. as uu:.m:nm:

E:.mn;s

mm [.rp:s.ams.a

a m -

qm+su: pssauum~u ~~~..1.~ u.um:m

up wy..

.a..u..;k xy;s..;;p~.g:~.m,a:.,nu.uu:sm s.q<y,,my,m;p:g

amu..~ nep:... ug y y .vg

,ar

.u ~ as ::wn mummam.

wyumu

...~

u :u..

a s, cum,u.am:> ume.m:.a cum ~ ;ay Lw;ff(uu~,.um,nu,~:mzuuzmpwyr,;p:.pwpmamzm

... ,...u~ m.:umw~:m

/ /~;;,=t.:;p; ns a dQ urmmv mp1

~::p v

u:..a;mzm=:y;u~h.:m.u, uumuurz~.

a

wn::d; w:

.u..mruz~ wys~u

~ m~a;y,s ;;Lu; 3y.smy:yp;a./,9<ux;p.r:usua n...am;.y;se:p.h ,gpy g ..wn.a;~-.: s c ~

umu~:-

mmah:u, s u~~ ~ ~

a:

num ~~ ,..~ umm .unu...g m..f...u=a.py;y w:1 mu w um~;.: .. ~ ~.::um:zupmg > ~.: ce}f

/ [mmar g~ unaw+*

s.,h;.p:m";:u:Y uu:n.ss a.

,unet e:uu,pu 4:,m :um g:..nu

a. m ... :uur sum.m :.uwuum,.m:dh,,au~4.yu..u~m

- :r:<uusummpuu~.muu~.:.

u.a a..r: .u.a;yL;;r;yuum.mr.:nu

p ;. .u.p: , u, usm -

mjuq;;u.u.

m.,

wn

- ...~s u: mss .n,su;

..sm:sn a,:.~ ?

anrwn

.e

.a.wrw pu

~.

dm msa.:ug us nd

/ .

",*4%../a.

mu

~

um-:w&.

~~~-

upgu,u;:;u ..:.m~

esm ~

um

~w-u;;;p;;.g;;vpjug;y:3.a:m;y;-1 u..,m:c~. ... . ..a.msmuzm us

umsmxw

mum;muurp

,,w..:n..

mpu:~,,:n- -

maa p ;umy;n;a~. ..:::

~.s:.- ::

.un

-: ~m .:.m.C;mh w~

~ E4 l 35!!'N!!9 : IIi! I'j!c 55 9

%mys:=!NNi$.uy,;$53N.j5!!In m Np :n amu Fi!i ! !!}!N:e, eM:J;5di!! . Isi.fdidi sh..=,1 a ur.i::a-s

.aw : m:i'53$ffi.fe msus uu - m ..... ,u ..:. un;p:-,.uaau mu s.rn.n u -::r. : ,

u e.h re.u~v: uu. =. ast

m

~: :%.a: uu.uu..hu nu y /ncm~ps g'E.au :n mu

.a mux: .rd.L u.s..e;e

4: ::pv :s a:mu;.u qq,jj;uu,uuupmr mn;gn:gr~: ;;, : ~.v m.aa.5, maa .g.

zam u umunggt ,a,. uu.~.awsup nu u..aurg;

.m.,n.:

ygsg,a. rru:::qj;pjma ms :;cqpmwp u, .y ,: r: ::

spu:.fh=,u; umuwww = :,..m,wu.

~

~p~u..uy., .:n, m 1 u:n.mw:~.x Au. u mau; up t

.~ym. un.!m..x .u v.-m..;pe, ~m.

n=v,,~ sum ~uay4.u :, ~ - ...t um.yumum uuu:n. maw.

g ws:~ n ~ m , u" ~ ::~. p: u u u::yim.m: sj,u :

. .. 2: *

g~ asp m,.xm.u,\,

m..,,g ,em;ymm mu m mz~~ ~p;;m.nsyj;;,

..wma.~,.y~s.r. :u;p;u:a.:5;;,;a=:.m.m.~m,.nnu.s1..mu

p :u;.uu.,auwu;;~~ um mu. ~~

m.

mnvum:

e.:

}1

r.

~=i.v.x mzm n. "

f !Ni n"n~,'!pi n~:~uuf mu;y!idf iEE!! ir !!!!!!

?~;j!?#E!idi!;:...I~'!!![EiliN!i!EiL u w nurtm !!MlEEi!S~!!!!Qi:l9fIMI, xmn wg- mmu zw ,u u'i!]E:' .uMi

u,

~.,u. 3

~un m,u m;u: 21~. :n..u.

r!mm: nud:::p 12~a;?uq=my:;;, u.a a up:us.r.?injua~;uuy :%a m. ..: puaw:n. .um m ~p le$.u smuun ;mmu.: uun.m:nm.asc:~n:~rw=:: uammm u .em-

,mex . wjpu,, .....~um wa :

i mru .- ,a. .ss s'e.mn;f .~mx, am.uuuu.

5%

"~tha,~m.muis:qv;gg muygni:nnum~..p.axps. :m q;pm;;;:q,mp.;m ju .uu..su,. u e

m :~~

um'.- muzye

.z,.,

.mqps#,-

sku M,~.umu&. unas c

mzqpu.f w ap..

a;;y;.

. a : umara:

nuu;;p;wum sus.&.. mu,. .:mr 'Xy;;m: m,.y mypyn.;;nmuum.u.

h:=m;mr. lLyuu.;..yw, u .

u.uuun ut,u!h..,umu vmym;; ump Mam, e Yukee ~a:=ma wx t:~ ':- awnwus "

ms:w .

mw m uu:n.~u.ey ut:sune;;p;m u .~~ai i munm u:=.mumu=c muhuw : p

q;upn.w.u.z=.-~w.

umzm m,.x.~an, un munq mu. u..mm.~~

Nm:a g;n.

uu

. ;. qt;pm.ugw:uu,.xeu.,

~:n..-

u, .m~

.=u,=~m.ur,..ux x .uw~m=m:nb;&m,;

u

,e~.u.~uuu:p, n e ~~~; g,aa.e;p. ~;u uun irmm;;.ann..~u

~: .~.,

r:s.sp~qua..

av ;mu.

u,:uy:;~5; m.~.r~ ..

ny ~:

..m..m,.r%m, mm. u

~ ~. ~

t ...,u,:..

u a. .,mi,-

n

~w.., . nn.....,,..- . , , , ,

utm . . , .;n';undi . 3-a:

-u. '

ya,y;.,9..w~>.w.a..n3j.,agm:wwummum:h

.u;::m r m:mH;f'.,,,.

mmy ~w 5!!!5.~rsxydlil;.u..e:

,?w ~ ~ e~ums:us.w?'pl51 ~ s umya, m...:9,,u.;.;.y r

~ .w,=:=mu h:

g auurmb,:urim.musmus m:mism.mu:u.,s;g:nm g-~wZn:

nm~~ r.~: m,yy;mqp:un .tes:~rew

?.m .:m.

pu .ut u.. uur p

.wqm"r~ :af.g:m

a;,ru +Mm..gn!%y&. %. wu~rmu

,-pr : .rw f.~s

~

a smuvu m J.1,mM.^ ;;g;p: s , y;:: r u-a..:.n. ,.: n ' :m y ~. : n ydur :.. ;u ~ mu. ~dr ~uiM;z. sM ms ~ ~,w ~dys

~'s .:me;.~

u ,p:: urv~; h :~ u. .

a : : S*~

u ,~~.v.u. ~:s

.s-a. nummm:w 50.u ,h:ru unt" "u,rpu th mv um:m;j;mw

,/j..

y~sr .nyn,:

~o ur~pae y: wq *I n nu ;swu m ..m wm m eh5y! uminew;~. nmus .sm : % ;u; ;

~::w;p, ;mm:

e.~.s!.

~m.uv:r ~ .u. .:~.u my :wm~xmm.g;;uhm: m

t s:a.

n; w ;..': ; .r~u :u. u :=> gm~.

mmu, j; ow unmure;uyum rum m p;umm n u zu 1 q:a:::p ..a4 uunmm ms:- em& ~ss

..u%.a.

uu wsm, , : un ;,-uumu1 y

~e ume Mu~r;s,~u m; au um.szu e sm~. ~~

u ;g:

an.ks.- + ,,un uu:nu. m ....un. w mx;rsu~ mmar.nunwu~w~. s ~~ : vru ..:., ,: M... .~uu -

~m tw m k: h:: ..:..~~~-

qa

m)

.~ . ~ : 5 ::my 4,..: m a,a.s a n: ~mm ra ;ku -

v: u m .:;mdum,.a ...~.. ~ y m: m1 ~s:

nyms=mg as n y: muu.:xw .:: mye~;wp~- m::: a!!:mer:wmfu,~.<,vy.

uu.:g, ~,. u w~

w:s w r,: n mus -

~u~:a.y w:;ua meurum p ~m m.,,.uu ..um ,zam, ~m~- u mp r uuuw . a p

,u .uspi: u

~ ~~e.,:.n. :m: ~

e q ;?! s,a u ~n: : ,,~.. u:wu m . c,. a.

a:

2nw b;w&.uu:;,

n v~~ uup 5.anu ~ sw :

, ,~.u yr;p.s u, ,; sM~u

~--

,mmn::w mt.p;~11, pc. .: m:.~.. ~- ,n mu ~ih?q1;pm.. . +u y ze p: :?d u...u,ph,

.~...

~~~e~ m .ugg ~,,n u nH.~ . y:s us::w:v .uur - .vu:.w ::....-;;;m:~.pr m~m rn 4:;.mx u emua m: 4 mm:~uhur.w w'mt

-.. c:p:- :ur..#

~ an -~ uqi .l.d.. q. %m;s muumu ush %

puu :e H.pmu

~kmms m: 4 H e

~u -

u;g se ne:sg

n nz smu. num

.wmnawrs:~..;,ntgn.e. umu::~yu uu: mp .

..vs::~,nu. m.s

.3~,

e r

x:mw=r: w;n~: s uu : h:gu r.-mahurm.m.,

en.s:m:

~

~m:-

ume.ur mEsm un !b

,~: ~. gw u..a ; t~~run

b. u.yusswmm;pwre ,.mm:nup;m~u vsr -~-d .n erruv c:nm

~w*)f.h:.:

i.~,.. ..rs > tau;m.s :- ~ ~~ c:. n.,m.. ~ . ~ .

-~~ ~ syv q;m: :.,~.

nwe - <

q: .Hv en f

I ren~; n 1.

.:sw~hn.

my v;':s~,

m.u w:e,1 ? r,hu-~~m sm hre.5 ~.vs w ;u...

"fru nur u :,p;:w uuu e --:4 m ua"sm' .sm n rm asm?wua*~ wee 4

, ". e-:.:.~ws-aa .,~ spe.~.~~

car s ~.w>~::nus m v., ~:,,p~ ,;m :

- ~;,~r me

%r:musu u: ::a ::- .

~.

a h em:~a,:m.~.w$8 u;sc

-% r: ~ < umurh,m :w :-a .:ar zwm: usu : ::p, \n,u;w

~:4.m su: p,r mye ar n,

~-.

uwraf pu.luw:~m mz~b c~ su, q. m : y4,, . up.

yu.a:.. : ;..en : u.ps,uu, a =g su w- u n m.m:g:

n:n nu;r u w?!

u -~

?%rhr i..em s-

%rwsr+m um puu.;~pu :2,e sup gm .u;m: 5 u .,r : re n$nxn-

~~

u: :.: ,estm uhe > ww

4

~5

%v zer 'H ~ n.. , ~t m :E',z!h.~

m. us-n s"W;.:ti.g*

PC ' u .: !..- ; ?:h. ;5-

7.P:wm e t'r.u='"u su m d"u .

., .h -

mu ,.mm a:m :Wu : u

. . . . . hn :: .r:ru hu e ~u :wna : :

emu um..c,. r.*r. ,~=~'e, n q:.~u r3' (. my.qu ~mm stgh a. ~ c gu tary 1':H..=::

~

sm

h. ~ap::: 4m, y c ,n u.

er m;,n.e.-

e s.

~u,~w .v .m 1 mu mu n

]

~

~~: .:w . h~r: :.:vu n :~ .. ~- :

u

,w.u

, e,,p.u . u:.s;~~.ws:us

~m zwumr~a:um.

~

usu u 1;p'n n - ~ ~

.. ~ . ::~,u. .

i. : u:.

1

., aa. %

tip: v..:.dxm.ur-r em :n: :sm,m a

utu

.~m=m: m.x a?w:~~ :: r;~r m: --

~ .m

,... .a)i m~.

mi :tu- eq:.m :qu

= :m ..a y

pu:

.m v e,amue.

p

u. uuamurs.

n 1m: gpw:: sm;.. .mu um:,r:urm

n

~e% ~v~

s~ uxams n . e- -

. m. v:r : n~ pra) 3;ur mguan;p?; -

p.u. n que- . .m <~- ,:uuwn mrm1 mu , rm~ .- :nF3 sm:umuw

.m

~w 1 y: mq m==m,u, ow F:ve,.

r :n: , a y: u py j,=.. . . . m n:g;uz mun :m::=.;a.u

~ ~ ~ -

m ua .~=~'+um.;p;w, u (c a j, ~w:w ~; :..1. u " :r m

, u ~ : : ..

ag

/a~a, .e. . m. s ,w b2 n,d v ~. : mn - psu:ww:str=~

u w~ :. ~~ a.ssr,~z 1 s- 'u-. u -mu us. u,,sur v~ nuw:u :mmi: m;,- .~-sm1,;,p a:n sw um.~s

'mme; n

~w v, s,ps;- : -

un. a :

ung uuy:1-uum .muur ik = c.. imh,r. .xw ...u~~s. - , . . . .

e u n.u:pm,mmpua:ammen;114u<+ ' ~;punc~; u xr: u. ar~c : mws

..~.,~ u ma ~ = SM 8 +a - = sx wrw ,: :: mmu;s yu .uu r~u~umt

. . . ~

%p;p sw w~uay.a yu.. ~u~an.m" : m'~; :y::nmur u.=w '

us g b:r w;mu. nw- u~s am :.um ~ mm ~ n.~yu~ ==m: .psur.m..~namruqr:;;au: . m n.' -;nu 2

~ ~ ~

ur.:

w ~+~ mu g a. : ~ ~,~d :uru:mme~ . - - :, wmm,. m- : ..u: -

.~. et: c:p .x,u.~

r~umf,

ry

~g v.. ,;m.:.e.a

u= :'

~n rw. e.q:~p: r ue ;.,)cm

. =~p:n: :mM:muy m ~r w- mn un m=

umurmmvu : w .

W .

Ms: s ~mmu ~m:,$6..u r 4 ~$u:y;r~mmz m u

~;ue ...:mun: zum).a),y:m:wr ma? m vA uu v.n=~vu Fdm,4 . 6,;m ~ ;ygn,an y ~

su.~ +

s g;p x==m, mmmt i w:+ u~hr.m:n

~~~ . ~- .~~m.

.%w%. .pw .a sm em unu m; m wn: u .u: pwr;m ummm ru..w ..~/ m.mn:uur p

~~

w :aw~~~ ~ ~mw; mj:u;r=unu:.mkw!~ n= mi;;g. :=um.g #

E.;.m.

~-

n~w ~up.a urm~gr":. .w:p g j 1=:n .m mxhm :

w,.

smem u w:..

> 1:pm

umq na: u/m.ummpc=nume==mm:nn~m=,.ju;p:n

..y xyp=wmzmemj,eaacpj"*mygm :uxm m::xzm ..nzu:,ummsmmuers nurg :e~.,x:.::.=

\

/ \sust . ,2 u m. w=yp;m,u.= = fu um mum; ..rr : : . . '~u uu ig w- 'u. emum)g mm ti=ew hm a~r.

um u w=b:. ~ w.: p: # :m. j;i~p::gt u~

um==

su uv w" .m..~.

s~.,~ ,~mdMhng;asmu..u~~-

yay::,. uxux m.

m..mn 1 l y euw -

.u;j ~jmn.:ur::mugu

~x

u . my.. . umun == mun=mgurn;am.....

n. . ?mumummm .: i m u ::m=,am. mm. y==wu,u

au . rs:r-n..a

m- u a 'r"!:uy. .; . -

~n:yju., Yy).rmx, =~m~;,mg. =m v w nxx u l

$~ .m ,u ~<y ~n -

r.e u.am gj:: me mmmet .m.=s:mr fgwwuum m~: : r.ur ,

s ah; :ha S .hik ~u ~ '":"Lwpa ungis r n;p;.. mmu v

1/w -+:y : v"#se reu.a. : ~~r~ & : >~.?.g.. si~nx swua t== .m n ,.:w,m ..u. .d. usan

'u

...~t m s.=mm:pu y,. w .:,un : : an a ww.-

Seglq

.q-pj pw+mmu = mptm.m:ww= mmr ~a gr.- ,

n,.H .~.ue:e.r uam~ ~=~;. as.m"..

vgm . , : d,pu,r,=a r:.c*pmxm :m mmm =pm.

~er :- -

m y:~um-: w ~=m mnmm =:=~ p: :~;p...x.a~q;g;je ~~d:d~ m:m"Tpam.,ug ww k

ww m

? i n .. ..umam.~ s mw i

~ uE ;:; u~'u=m=q=p.m=umgu u h ,n d sw;%sya) 7 mu. x(rus;pm=~..

~~pu.uwn~inhuj$$1!P 1- mmh:d h mm.h=e $O0 feet P. w::by.

- m ~, muxxu==~n ~;pr?!qk!an'm

~; ~s mm,~=m. m:

u~

.uu i

.F.~ .u she, nh~:w i >

~L

+

w~,n r h: Fn::nenu"mn ;s=~~u. ump w~ mumw v.::

sj s yyr.y=:~n s

, y v cyW pu . u. An:m.m ww : m.u=.=y mw mu =mv ~

m

~,gsg

, a ~s a....u .m g As: .~umu : r =. ,~v.umx.. .

~

f<p~x LV~: ., m :n;~ . u .a.w~,

~.~;..m..?.w'rg::m.mw..- . '

..s., d...,s.w,:.:.

+: Fd.u~m~.m.. m..~. "~m ".

v..a x v x~x. L yyO M~.7

- L" O'**Q. ~ R4~ l,:s g . . 'l 7 gA Mir

N A*"

, 63 se S' .".".".,.......aRq' '.5""~~ .~~.p..~w v""*".,"*

a - ",*;. ". .~. y". .'A%"W"",u."&~ PJ .

s n,

roxa.x qwl. e* ..a I . y .i amn. g .

. uw n. .. .. n nmu aq:,s. ;a f4 . ~wm> Q=gy. ;p 5

w .f:3.p t

nuv..umm m.am -:awnmi >,m tm m aw. saxeszwamu ~ /- w=.~u.9 an :~ h;. ~ ~xuwg.w. x ,

I nw =u=s m . x: =qvu=sm:mmm m.,mazu. idi.ifwu..vymuu m.umuanc x;;~.?

\

.w Y~. . :::m.. a. .~.y.. ..w.s-.~u :x a..n.u.,m

. ~~ n,~=~~um. a. mwusru u ~,.m, e. w@u.*'a,?~ mu.a,m..=,n'Nm.n...

l C }Q G@ f yp&r. wha)%n,u=u.~. ,

m.~

Mg s,w~%ub @rVQ,un : 2%m

, ~.

a* V~~

VAm mx~"Way r*: .v:m.~,.~

M")%Wubp s..Dn,0%'stt 1

i 1

20 t

Figure 4.2 Environmental Radiological Sampling Locations (outside 1 km) u , .m e v ,; we w,g */

a

.i.e. ruin i

< 4r % f,. - Maine Yankee -

,c, j .g.s-

/ . e f.y y rn -

G*h*aar G 2 ,/ C@gonf S%

t; E ,wnn.n y f tw U se - N. [I

E${I b o, e

e. sr~ 4

4 y r ey v- ~

l

, _ yg& >>

p ,. G _, , , .

.#. - .m + m ,,

a r#~

A ,,9 i /

~

.R'd = ad @

t' 3 #

- \, J

N aboro % 1 1?k a '5 .

if?f4

<; / pdiik.

j $'

s

~

p eu Q. f. n %b 4

.h s f .v ]y , '#"., .~ a 1 ce

@i , p

i, 8 mMscoca 3"y Qf ,

/@

p y e ,

er AP %p

& *** g [4 f$ 4 t"dW bt,;gf h2 i

8 55*>'aham 7~' .,

M $5 a

I'M .

L sl

-m Ar.u -

A *u')

-w.

c*** / **L 4

'.*f h58,

1

.--- 4

/ b*

,y

&s.

' p i s 4@ ' fbfb?<.y AtQ' 5

act (1 gm.;:s e

a

,, .a of

J 1 ./

.saa pyd tw p%gby vgz sq sq Yankea.w.=me, y ,w.wa. e gglpy

i .

&g .

9

h. jr@

g8 ,, 4 TM~yJ, @h

.t a TM4t$,ReAPICF- W'/ #

f M

~

j5 '

NMl9p ' /% 'r '* 46$h4

'" T 45Ey0%8?mUNS f

I e/i( pf f

IbdDNN

) @;y , Q-nw(

"g = t / [

' ' .' W E-20tt [

e

. i j$$$!h e m->>

A,gl' jf i) F pQ a apn..' % -~%ig t ;sM ea pp $. y Q,

&-J,(~~N

W > .(2

.c ge,Treven ', @ , if,,"

g *cnnm.,,o .s

/m*g G

gf%

Wa . ?-b d

. s>g/w

- 'E ) * .Soothbey

-a ,fppgi uw:hf' y

<! aw' yp,j ' e.x-" ' %%M mm

,. a.

.a e ,d ~n >% s< +\ % g

,, , 'saum artna 8 $ i Nx . n a n @$

8/slSE g2 9w yl* tII%~ ,7

}rW y* )( ~ [ N *) 45 'MU'CA

, l p Y KAde, Nk{}Qlif5b y. Q es

}'Q; w, :: s: au , y&. &&nt"!f&lhg s&b?h"' Q~Qjj;f'>f&.

d.w n* .

3 f,>r ?! -:. . - -M ~ ~m

($y

EQ'b), ff * ?jyac'>s

7 x; t i hf 4 T . *$$h $ %&,.c 4 is M .e*" '

tt;;[ py . tsannoo,t 4

\'Asf. fgN$y"v a x wpd ; .*:^'"?h?ks.gg'^. ,

k s.,) , d'i' I"b J!' Id h h wwy b ik MN N$bk

, h Al.

my t dier-2MBEREBBlELM 94sd =

ne H9s iBMimsRNmen,ASdn p -

r -

aw$weswm Papa o $ a- :

Mas a.

m~g#1Aif,:yk

$a ^ ~ pa x e$Y h he%re #n " b?

m ?

se d % m?9 gens m , sm ;

eg :

mw~4p%ew ,

.;m=febg#t ::pe 7: 9 fND Def ye6l@ce

~

s

a. 4 M*6 ' r

4@dD-@Cq92.gp' %%rM

%f 43WsM Q we WOyh.9a 4 m@@m@5m.+Rd"ak.se4EE fM = ew a A E Lxi!!AJMN~ yhgg4 W 4 %.,_?g s -- ~

seJl%VdNY%%:thihO *ilpC d*i@44d .w- A sr4M+00

.gf grm. . g. #14+ Ws 4 - ., .

4l

%;l 21

Figura 43 Direct Radiation Monitoring Locations (within 1 km)

/ N/ we am Maine Yankee jwme gi ~gjg 2 VIyRA

[Diph':*t.%' W' y?,j

.e

[d /L v: 34

v k.

t. m

. ,,y.

l

- N

[ v x

y

/ w# M yti

.. k J' +

Q@.-cse

>i.WW.f" '

Tl# W T1 ,1 ' ?tA22^:'. """%.

-QSt% PM g p lNN, [mm'rd

.KLyh

.'.. N. .y An 2 x .; :M:.. yT.3;Ql ys.

W

.? : , ,b.,j..;h .,w 4.,..fcacq -

)

b%* $w..

s e.n &j;/. b~ :

ps :

h N $

$ I

'{&@I%n$[44Y:l:q:b df:v%R'QJ^/d:;g?;:?D.p$:7 ' i .f g Q gg [:% M'.$ 'J y:: ,c 1.$ g 8 \

f;h ... ?:

W. sv y%fW[$f.74. %M & DGcen% - <y

\

fg5 t f:{

a.Ib '::i* :.?, :ll.

< ,R,%.Q: .4[(

cQ_A .; f.a gf r' ,.....

?{t['

.t.

j;e;s.:i;;}:cM 7

)

u^ ^^

,f t' W'f$tt x..:~W^: v p v. :s.

q ':0 * ;,:N 6Lk:t l.j,f:t' -

.y

= ' '

' , .g"'MQ .y 7:}

h %g!~n- 4 A. Y.fM.e : FpwY1q, l Ng ; .g .w .v $

, 17 .

29 < w w. p x.3:

M e s.A gj4(r:w g l

L =

a h.f M. w"M; M d k M-

y1-3.%

A. 4-- .: .'b.,.. <% ' hY-D.

'.[k I

-4 9,

} } ;

W'4:n; ::

f.y s,..; , f ,_,q' ryY'.,&. ;^

%ift^f.;: -/4e .. . k::

.%qgl:&::%,;'3:

... ?MQ A+W :

7 kh.f g Ni '

f?NS g,3 g?

(

8 A pM@h. .Mk./

w Mgjng y&MkOC

/ p[gM.2 5@hmy"Tbah NN#N % MNO \ j

/

^ y

? M :.< ,

b5:IIM ^ . i'$N- b:![

I ofDANks I

N' ~ IY,' ..'-

f O'W'W.:^

c.

W.s.^

.WAN..+Y.,9 . > : +v dj FR.y ;^::"4 <:4%d :% y:.:.g:q 94

> :w;.sj.@lk

._ ;,afw n., a.,

l y; h Y'y f v/;g.g;ff Y'

hY Q g

wM % ge#.:. %.%w?:?>,.Fa

[<t.h O t,.>%

< c.a

.:3.s:1* e5 4

-f:P g :y *.s y'.sv Q' ;"! .%

33 tr.m Wf T"*h+. lJ.4w.

v.-

' #.4w'w-i-"lyt'*.r',3';y .

b

#,# 9.s^v!:g"'V.:f'";

i :

- ' y W. Kf:% h.&jfi

^

, *;'Q*^ '

Dit 0 % ;hjk:KM:?,? ? 11 v g:

m[g%u d61 A:'

P%

fig! ;il+.,

NF^ iap^c:p#& v M1

4..;

a; .n.mxs$:1-w;.<

.w D-

.: : q-; ~ ^

a q:9:.tw or n

s m *x : . , <.6.v- s g p.z y-:

,.v.F 44.. . wt M: y,. -@:s w *Lf.c , 3,3

. :sW e.y , x;v ' ,;:. ' z :j-

e, .%:;S * . R 1.42:

- -^j _ %2j?pe!!(s, y.y;w: v. o d

^M'f rP9 fTh

?n.

N y .: ..?I? .fQ#Y*Yfp.psrd?'+]:[_3; f

y gyp,,,y 9.,45 ,hid>h:%[MT;.f4hi$h?M;h;?E[fhg I

NNikk

$^ iZ Wi mA-Q'+>" k g %7f:E+YE.[Y(s:7slNAU:?MhN}w:+

bi: '4i?

2:$:Y 3 d$@;A[]:

C y

/

c i:iE. 4WT.^Of i.49':&i:W'Nej"j'..[y ". - f $

4^W:s^I.[@[a:+

V }.;%m;f 4 J. b/ f ~h;# gh,

%;a w . 4:sy ~

g'Q, ...,.y..- -.s r %/ ^ 'fi nt ./.

O';;$

^YW n. f ;S I .. fN k.hb W. 2 NO 3 ak;:%j.Y'-

9 +qi ys~ .~ m;s.s :m h":.$mNDib;;.y$.-

+;y

4. m js MQJ( hyi

y. $m:S- .:

er p.'? >

4 y ser.'m.s?.D re e 9s ,ms M.n .w.gsgn.a:., r=

$qhgn%h i

, qp-u y '

l> VYo .

.at ?:gM e b 13 YY . N: $p$$$i$klg%7Ei'j

'whWW f:

h?t;%f f.lif.jif.?

a

>j' QimR

%yA-My Cd;M -Mgg;, + %

N #4:t W D; cv3 Qh "MM, .Q tis .

M

'fM lI:p[ >.*%N&A(~.* m.tr.pgY$3$/it

w .&:m:n Q;Y 4,f b[l h G?

'N -

e..d;*ie t J

wcq' Nl#h~$ p.

L - N:: h 'Sm 4 ,

y:.%u

' :; ag Am. ..~+ p _x. e., . sw:xm. . 3sW "

. rw -

g

'pg '"!I%:!Nh. N[ff I,'%w: > h I:;;$f

. ., ;+;7*f, M.';$

'~

g

+ mu W2 < 1.r,.%g;W;s

e. :.

n R.Hb%a

'. ?> .x Win: .-

\

nMsf%,::.W '!" f hf:ku "FWW .. L

. A$?.iM?Yi2

$6dMT4 5 Ockl.,Cg& NQN#2 %

l&lW:4M5&

x .s.Qw.

W$%kW uW:%% ; 2 @Q:% NM hlQ

$dM/TNs$fM.m$hd U:Y & +/

p 'y d:Md Scale as. g n m~

a aw ww ..w .%

tw p p u. m, h

Sp - 2% M:.e. b;pP . , .,s .. . +m N @.s&

l 1000 Feetl

& , K' w r }.f[ . .

M;h: Mh' 7'Wcwm 4:fm m. .

m a: r.

hMMI:,.):kN =

e w N d'"e:c A.bD.[5D:g;y:

4 w . M.-mn.,vr:rw'?N hb u '

8 Powns i 500 Wters .

ws.mm%pshw e

M$ y ANy;;n:. + - a Iw Me*u:qf;D v M ';L M e m. v-- - - - D:N>W v'

't%":V; D- Ci4*y~

/ I oM6%@iNZIdYfdM:NY wn rWwm mehIeh%e;%%$;yd,@@$k.W' er d ehm o sOM [.

l 22

T I Figure 4.4 Direct Radiation Monitoring Locations (outside 1 km) n,.y -

a d ;

, o /;- Maine Yankee y"9 * , > ,h ar r-" ,. J

.Mu~4 G ~ ,.r Gm.: '

4 T f!N gi'!fg'" ~~

l

" , ,#[,sr# ,;y. piirr I wm , fauth GaWer G j

am: i;,

g

.' 3 sis f ,Whftsfie*[ ,rQ@

P .r e # '.

. l 4 V ir I

(

b s e

n.

gha4, 1

i g

hTL 3N . .N

l s' ,

.s l

/' G e s p *a / e

e.

m *-

g -

p} pe GD 7 e" 7

)' e *

(* '$ N h, ./(d

% ,f s >

e* t Y e .f

.t== sng 3

\ $J n N, ! .

< j*0 t:

e

,' R@:.

~k n. %m:

}[. p..bg,/

e:n1 u.

p 9.=,r jo t s mam ,

d# .kHistr* j' ( 13 r f*

M; s[E+r gi [g;dN!1I s~ ,, N m sk / mulacotta f;3

%jlh p.: .('-

Dim'{ s 'r gJyv cW

~ w!!3="

-s'. .,a~=n

' .w *.

g p"'IP IL 35 S I 4 bE!i!EEN a .mnh m k,: in Tb?[ e L , I 9y &r?.

u i%. If, w%unt -

p". %:m Mit {"*

+~' @ wgg.

msws y f' eggqryl j q w 54

~

Hu.fik y

. , y 16'r w.x is @ &)x, :E '

h. g y Ed $E pu.

y'AWSINM nr9ms

[ y$. snil' N 3 h,;j.[;.i 37 ,;gg zu di!E.

g'gf_fifh!

'91?e # h33 M N 23 ,

f.c.zw snamun~

yy sqqwsau, gig j* ~s f.mm. ", ,g f G V

if ims ..

7 nr!ei!;fsljy!yr $2st i Mlil .

ek a p.ine -' Y' *Edgemmb r e

- w tpoi, dstol w:m:m=~e.= m:

P T" a

sa![gt ,

Jd r' h.* N3 4

' :~MlE!fdj!E@dssf/M 4d ~.~~2 k".1

'J85

(

.+

shr:r!%~=~.~m Qi.n.s!Mrs!!M f' $.y' .!.

s 4fr y gen w. ram ~

6;F 12 - .r f N'anss fu.am..n..',sM.Ws U..

f r. a2D . x .s a ,

hm d.,N W*J:NdSD r ~ ~ ~

-k

3d. *shh!N!df . /hkij '

)v.M~M i. r '

.#Af

$~ 'e y sg'./ E '

p .r dan . sny .3 . ihed = s~n m +me! un N/ c.; d i Y NN

h A.=h [rk yghi 4 '

+ 5 As e

e

/

-? . ws, gc 8

n ,4.se,r.m W air i 4!m 29 ~ y

./ , pr; yM

.w~, hwQ

i 3 cp naquid

.' m.ans:nig!!s,z;s.

ju =/ gyp.,.mn . u.fpu,.

d HEW" "B.d&-

inn g ? }- 26 , - .r"Wi fr e GiiDia,- 30e ida gJ E , Tt.-27. , 4's . s s

.'k ."i G >Sf.sE"gyeeC0:Wl3:.a,v4HMs r i

.us-ham.s.,e' ns:w'".ue~r ~f m'l t ! !~,

Vy'T s -d ga. .@.

3

>r s"W$y b de

h% . a>p~9m' :: a l MWf. ~1 I*.?sik, . sf at

~

n' w

~wsw r

st Ef. y 4l 9 eta:,E.

f '. gi 4, Im -.+#g Vs.s Soothboy sy..n ssen't.m.nen ~nte."de=:n:

4

,,HTEm*'%:m, .

G,.,d.>!F,.. u, .N. s..,wsu. n .. .,~,,:G.:~

. .f .4 > A'26 e .;s.:L w:

1 asq s u:

.se = sn

~n

,%f 4*s i A.

+

f . GWmm..4 M i ., . g Pr

,s e*4ns. a J.un"%z% ~ <

/,umuwmp.es-zem-~

rs p eu:.

n.~

,,p;@'W sp- s';fidj:

' .r

'54 4 m/ m.~ww . .s .w.w;i-7;r;;;'

e.!!.shf;/!d?f,3;i,'.;$ n

< .s.6 K"r.un$ ' g , Zlis.sy- S.outh .s m 6..ttstol u.a s;* a,

,,,. 4 x n ,

w w

f r.

-~m- P TL46 .eseyvgied;r un5nv jh

+M . p'r.~as .* $rusedeir!w'~w

1. 4 %hsq. sus'anagi vas dej;%s+.~

4 "

g8 $(5~y' SiSP.oh M'j ("Ha O% !f'fi,$ t hi'4. * 't m 'P0 4 n.s A li&EH'r ~ ;."; 931~:w" Y2

.ypt W? j'? 48r%f 4

' 'insiim*IUnh ,,..' " :/,~.F#V ~4 s ms t So'othbei Harbor dissi~

f '

Soothboy Harbors $jjrg m !T.iW!?insiNE!"'

fj gjj$ Jf 8 s!5 ',is.

istsk, af #g #">'. *mim d#q!-E l st5!umscr ;;E22""iniP!C hI[i/

F re"2 6,f" f g;J i y

,li ,#

1 ,

y:.,m;=r~

5 P:

Js4;s[

n=w

'~ 4 . =.a. t sr. 4!fss9;V' UnsEf pH3N..!Asi!

n H nim!

i MieFIirg~! t ? $;u ts'ini:dn"fe'.

.;hinisid=inemiama;g =.4 rass

.um+V

- m M :l m

., ig, v.,~un t ' , , (,4y 4mz sf est Sccthporlpis.s e ~~g3 ir s

TEPi./'r,w!M.ss%r>ws!

F~~ E~ tpm, u!2!!=+pfjs%.~'r

~~.RE' J xuuu~d~~ p .i;;4.~;:a- Mpg.d..

~=mj b.4 s-19 .,jj g p.ms# ~ n.~r-~wa s(~uzm ~ a~~

' .! . sg} b bas. 'I/5 G J hfbiN!Nf i$5 !!h h kSbb!Nrsv.gm-~ N:hh!E$ .~~~. b .r!2if N!$

Y[' y' y 'T'. } jiUik foeory.te@!EU ! 6!jf Wiiiid[:ihhsk Id55!!? i k!! fia!0!St I !Gi :!L f[ [frki! ifs! 's!f

' I DNNT[p$0/$re!

ymanwa.

I 5 s a;,$5bM- EIN,h.m.$;!!!U$i!@E M,.r4&'Idh,,,+d.$.u ;i == x.. tin ~5.

s, . .t yrp$P[ GiiiD - 1 ,

u=mse r -

dj hh Thf 4id M

agesh~$ip i !! ;

sem=mu s

@J. .

.A r4 a e;e

- ,;s.b w.

w g& cyA vg.siumoneumragme%;ii!A m en memege:2 . mum

~

einer ~ .anm eg_ , ,

- i.. . .e a - =ea=> msisima:

2 as

.$.ua!i s /

. s.'ki

.b s, .) d i !w eire ii mwnm=mers.

j M!M, k ar 3EN,w$!kNNh!55 xuummm...~..T' .1& '" ni adli!!5"14h!

S

+x ;fd! h!S!NN!'!!:!"l:~NN!E es u r,,,, . ..

W mw x nmmmmnwnmmn

/

"~ y a fras.s#

as,:#!Sid digizz ; nysiN;f;fmmiuWtjhuW u P"!kMHj;uS;;u;j6mm

~ . .. . ...n :nzrgynssisw umfy/xwsst i dy mg -Jy,;

___2g~

r i

ir

.ssi , "w ""!6n:mijygfW@j?n'y t

kn t

,~iU"* 3 .s=wmum'?w 4 ~n =siYmW~~~

"==d%n%;d! n='4 =u.u=~hn4;,m,37gggggyfj =r m==~grm="snxamsh ,w,,gsyw,uu;.mua:,i :

s: MQGnwdy.se n * ~:nnurf k' is d y gi.f4BMif42ifin?s%?nm irn

~shnNk.wE hn'))Mhn ,1g , %,d.x:.=mirgny;;m :myyylsm2MmigignHb,dFy:n;;&=.s=ng:f&samy"gy}g- m ~~syin~v mg .

i aw~/L ,..mz ux

.s~ .. mm mum I

au EW

...g; Cimm~ fag.2sm g ~~gmP

s. !ENsmiHP*

mW~ &gE=HEmd!pgmFA s" EL;r,. -mz~hMiV'6)fL,%j(-QnM!%)fimM*innN.w...gb!;g

% M~mdssHMd Sir .T.4HS!!

e HMH;;up.rggu r

g g l

e bgg--

i 10fmuw~%ra;n JrM4#iHi%.. mx~

d [s$"ifsfMiiErs/dm'HE:,

m :=

"mH*N""isl<jfsniWalnumif"si E.! !M dWiiH.nm!S5hsinns mmmuum=m=hm.gss:iiirsh"!Ennyjsi!5pisin!#g'~cWifr!rd v;u~ .=ummxy'um--

3 f ~. ~~@$4 i

.. p, m:;p~umg":m iines!ai% . ag*?

' ' ' mm m "s ,

= rig *- ~! ' ' "

r 3 gjn;rsimyt! !

""""sm I"1";jiksf="s'"

m

~

l 5 Miles ,

Y r '! .g 4,;rg~., ' -

ms m - mumm-nu l s w~~~

~ x, e~. in.y ,xu w~ u~

Emysm ex o #,iux x, r~. re s s 2mr mr n sm ,

f j ~ ~E'M =~ ,

u e -

" ' mme r m' " " '

Mt;m kuu n.u n.a vu__.~,%Ms ~ , g%e ~ ,~ Tr . .. , ... ... ~.,. . =r r~:m22 w za+~~ 2%,,,m4:w. im.~ - . ,~,

23

7-V 5.- RADIOLOGICAL DATA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples, which were conected during 1998. 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 L radionuclide. The units for each media type are also given.

The left-most column contains the radionuclide of interest, the total number of analyses for

!' that radionuclide in 1998, 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" measurements. 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.

For each radionuclide and media type, the remaining three columns summarize the data for the following categories of monitoring locations: (1) the indicator or Zone 1 stations, which are within the range of influence of the plant and which could conceivably be affected by its operation; (2) the station within Zone 1 or Zone 2 which had the highest mean concentration during 1998 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.

24 f

l l

l

- 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 1998, for that sample type and that radionuclide, contained detectable radioactivity.

A sample is considered to yield a " detectable measurement" when the concentration exceeds j three times its associated standard deviation. The standard deviation on each measurement represents only_the random uncertainty associated with the radioactive decay process (counting l

statistics), and not the propagation of all possible uncertainties in the analytical procedure.

The radionuclides reported in this section represent those that: 1) had an LLD requirement l in Table 2.4 of the ODCM, or a Reponing Level listed in Table 2.5, or 2) had a positive i 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 DESEL for a gamma spectroscopy analysis are: Ac-Th-228, Ag-110m, Ba-140, Be-7, Ce-141,

! Cc-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59, I-131,1-133, 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 1998.

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

1

(

l 25

[

Table 5.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station, Wiscasset. ME (January- December 1998)

MEDIUM: Air Particulates (AP) UNITS: oCl/cuble meter

!aica.!!.sja,p,5,, siation wg,sig9est,yf,an

- C,9,nyoi s,ta,tions, ,

Radionuclides

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

GR-B (258) 0.01 2.1E -2 11 2.1E -2 2.1E -2 j (0) ( 7.s - 40.9)E -3 ( 9.0 - 40.4)E -3 ( 7. 6 - 41.9 ) E -3 I (20s/ 20s) (52/ 52) (50/ 50) l Be-7 s.5E -2 13 s.9E -2 s.6E -2 I (20)

( 6.5 - 11.1)E -2 ( 7.s - 11.1)E -2 ( 3.9 - 12.3)E -2 (0)

(16/ 16) (4/ 4) (4/ 4) !

\

2.sz -5 13 1.9E -4 -1.9E -4 Mn-54 (20)

(0) ( -4.s - 5.s)E -4 ( -s.2 - 57.5)E -5 ( -s.1 - 3.6)E -4 (0/ 16) (0/ 4) (0/ 4)

Co-58 6.7E -5 13 3.3E -4 ~4.1E -4 (20)

(0) ( -6.0 - 10.4)E -4 ( -2.9 - 10.4)E -4 ( -1.7 - 0.5)E -3 (0/ 16) (0/ 4) (0/ 4)

Fe-59 -7.9E -4 29 1.2E -4 1.2E -4 (20)

( -5.0 - 2.0)E -3 ( -2.6 - 3.2)E -3 ( -2.6 - 3.2)E -3 (0)

(0/ 16) (0/ 4) (0/ 4) 1.3E -4 14 2.1E -4 -s.2E -5 Co-60 (20)

(0) ( -2.1 - 5.3)E ~4 ( -9.3 - 52.9)E -5 ( -3.6 - 1.s)E -4 (0/ 16) (0/ 4) (0/ 4) 0.05 4.7E -5 16 3.1E -4 1.7E -4 Cs-134 (20)

(0) ( -4.3 - 5.4)E -4 ( -s.2 - 54.3)E -5 ( -6.3 - 51.9)E -5 (0/ 16) (0/ 4) (0/ 4) 0.06 -1.2E -5 29 1.3E -4 1.3E -4 Cs-137 (20)

(0) ( -2.7 - 2.5)E -4 ( -2.6 - 4.9)E -4 ( -2.6 - 4.9)E -4 (0/ 16) to/ 4) (0/ 4) i 1

'6 i

I L

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

MEDIUM: Charcoal Cartridae (CF) UNITS: oCl/ cubic meter i.n.d..ic.a.t.o.r..Sta..t.io..n.s.

Station With H.ighes.t Mean

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

Radionuclides

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

1131 0.07 -1.1E -4 29 5.is -3 5.12 -3 (260)

. (0) ( -2.6 - 2.7)s -2 ( -2.3 - 33.s13 -2 ( -2.3 - 33.8)E -2 (0/ 208) (0/ 52) (0/ 52)

l l

l I

l 27

77 Table 5.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station, Wiscasset, ME l (January. December 1998) l i

I MEDIUM: Mixed Grass (TG) UNITS: oC1/km

!0.5.ca2.sja,9,ns,, stay,m,m si. ,,9, pst,,y,e,an,,

p,9n,1,r,oi s,tapns,,,,

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

l 1.0E 3 11 2.0E 3 No DATA l Be 7 (4)

(0) ( 9.8 - 341.4)E 1 ( 5.2 - 34.1)E 2 (2/ 4) (2/ 2) l s.1E 3 18 1.0E & No DATA K-40 (4)

(0) ( 5.7 - 12.7)E 3 ( 7.5 - 12.7)E 3 (4/ 4) (2/ 2) 1.9E 1 11 2.0E 1 No DATA i

1-131 (4)

( 4.0 - 29.4)E O ( 1.6 - 2.5)E 1 I (0)

(0/ 4) (0/ 2)

-1.3E 0 18 2.4E O No DATA Cs 134 (4)

(0) ( -1.1 - 0.5)E 1 ( -7.6 - 54.8)E -1 (0/ 4) (0/ 2) 3.1E 1 18 6.2E 1 No DATA Cs-137 (4)

(0) ( -3.9 - 100.8)E O ( 2.3 - 10.1)E 1 (3/ 4) (2/ 2)

I t

I 28 i

L_

Toble 5.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station. Wiscosset. ME (January December 1998)

MEDIUM! Estuarv Water (WE) UNITS: oCl/ka

!aff*.t.5.s,ta,u,o,n, ,, s,tation wm,Higgest,,y,ean gg,n,tf,o,1,S,t,atyns ,,,

Radionuclides

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

H-3 (8) 3000- 3.0E 2 12 3.0E 2 -8.4E 1 (0) ( -7.9 - 121.3)E 1 ( -7. 9 - 121. 3 ) E 1 ( -2.4 - 0.4)E 2 (1/ 4) (1/ 4) (0/ 4) k-40 (24) 2.1E 2 12 2.1E 2 2.4E 1 (0) ( 1.2 - 2.s)E 2 ( 1.2 - 2.e)E 2 ( -1.s - 9.s)E 1 I

(12/ 12) (12/ 12) (3/ 12) 15 1.0E -1 12 1.0E -1 -1. 8E -1 Mn-54 (24) s (0) ( -9.5 - 16.3)E -1 ( -9.5 - 16.3)E -1 ( -2.2 - 0.9)E o .

(0/ 12) (0/ 12) (0/ 12) !

15 -2.5E -1 12 -2.5E -1 -5.6E -1 Co 58 (24)

(0) ( -1.4 - 0.9)E o ( -1.4 - 0. 9 ) E o ( -2.0 - 0.4)E o (0/ 12) (0/ 12) (0/ 12)

Fe-59 30 -1.0E -1 20 4.3E -1 4.3E -1 (24)

(0) ( -3.3 - 3.2)E o ( -1.7 - 4.2)E 0 ( -1.7 - 4.2)E o (0/ 12) (0/ 12) (0/ 12) 15 4.EE -1 4.6E -1 3.5E -1 Co40 (24) 12 (0) ( -9.5 - 12.1)E -1 ( -9.5 - 12.1)E -1 ( -1.3 - 1.9)E 0 (1/ 12) (1/ 12) (0/ 12)

Zn45 30 -1.2E o 20 -3.3E -1 -3.3E -1 (24)

(0) ( -4.5 - 1.3)E o ( -3.5 - 3.0)E O ( -3.5 - 3.0)E 0 (0/ 12) (0/ 12) (0/ 12)

Zr 95 15 -5.3E -1 20 2.3E -1 2.3E -1 (24)

(0) ( -2.6 - 2.1)E 0 ( -1.6 - 2.7)E O ( -1.6 - 2.7)E O (0/ 12) (0/ 12) ( 0 / .i.2 )

1-131 (24) 15 1.4E O 12 1.4E O 3.0E -1 (0) ( -2.5 - 4.9)E O ( -2.5 - 4.9)E O ( -4.5 - 6.3)E O (0/ 12) (0/ 12) (0/ 12) l 15 -1.0E -1 20 -6.3E -2 -6.3E -2 ]

Cs 134 (24) I (0). ( -1.3 - 1.5)E o ( -2.0 - 0.7)E o ( -2.0 - 0.7)E o (0/ 12) (0/ 12) (0/ 12) 2.5E -1 12 2.5E -1 -6.3E -1 Cs-137 (24)

(0) ( -7.s - 1s.2)E -1 ( -7.e - 1s.2)E -1 ( -2.4 - 0.9)E o (0/ 12) (0/ 12) (0/ 12) 15 -3.9E -1 20 -3.1E -1 -3.12 -1 Ba 140 (24)

(0) ( -4.1 - 4.5)E o ( -3.5 - 2.0)E 0 ( -3.5 - 2.0)E 0 (0/ 12) (0/ 12) (0/ 12) 29 l

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

MEDIUM: Ground Water DNG) UNITS: oCl/ka

'Y.I.C.#..$.

.Y.k0.ns,,, S,g,g,g,y,igge,s,1 y,e,g, C,g,n,t,r,o,1,S,g,i,o,ns,,,,

Radionuclides

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

H3 (8) 1.4E 2 13 1.4E 2 6.0E 1 (0) ( -1.4 - 6.7)E 2 ( -1.4 - 6.7)E 2 ( -3.9 - 23.2)E 1 (0/ 4) (0/ 4) (0/ 4)

-1.1E O 24 -3.9E -i -3.9E -1 Mn-54 (8)

(0) ( -2.0 - 0.4)E O ( -1.2 - 0.5)E O ( *1.2 - 0.5)E 0 (0/ 4) (0/ 4) (0/ 4)

-1.1E O 24 -5.22 -1 -5.2E -1 Co-58 (8)

(0) ( -2.2 - -0.2)E o ( -1.4 - 0.3)E O ( -1.4 - 0.3)E O (0/ 4) (0/ 4) (0/ 4)

-1.2E O 24 -5.1E -1 -5.1E -1 Fe-59 (8)

(0) ( -5.5 - 2.5)E o ( -4.s - 2.0)E O ( -4.s - 2.0)E O (0/ 4) (0/ 4) (0/ 4) 13 2.6E -1 -1.1E ~1 Co40 (8) 2.6E -1 (0) ( -2.0 - 10.2)t -1 ( -2.0 - 10.2)E -1 ( -1.1 - 1.3)E O '

(0/ 4) (0/ 4) (0/ 4) 1.2E O 13 1.2E O 4.5E -1 Zn45 (8)

(0) ( -3.1 - 7.1)E O ( -3 1 - 7.1)E 0 ( -5.4 - 5.3)E O (0/ 4) (0/ 4) (0/ 4) 1.4E -1 24 1.4E O 1.4E 0 Zr-95 (8)

( -2.4 - 3.2)E 0 ( 0.0 - 3.6)E 0 ( o.o . 3,g}g o (0)

(0/ 4) gaf 4)

(0/ 4) l-131 -1.sE o 24 -1.0E O -1.0E 0 (8)

(0) ( -4.6 - 0.4)E O ( -4.9 - 1.1)E o ( -4.9 - 1.1)E o I (0/ 4) (0/ 4) (0/ 4)

Cs-134 (8) -2.5E -1 24 2.4E -1 2.4E -1 (0) ( -1.1 - 0.9)E o ( -1.1 - 1.3)E o ( -1,1 - 1.3)E 0 (0/ 4) (0/ 4) (0/ 4)

-s.4E -1 24 2.6E ~1 2.6E -1 Cs 137 (8)

( -2.7 - 0.8)E o ( -2.4 - 3.0)E o ( -2.4 - 3.0)E O (0)

(0/ 4) (0/ 4) (0/ 4) 1.6E 0 13 1.6E O -2.9E -1 Ba-140 (8)

(0) ( -5.0 - 35.5)E -1 ( -5.0 - 35.5)E -1 ( -1.5 - 2.0)E o (0/ 4) (0/ 4) (0/ 4) 30

Tabli 5.1 Radiological Environmental Program Summary .

Malne Yankee Nuclear Power Station, Wiscasset, ME (January December 1998)

MEDIUM: Sediment (SE) UNITS! oC1/ka s,tatimyg,signey,y,e,a,q c,m,if,o,i,s,i,ap,ns ,,,

!ad.ifE5.8.'*.t!".'.. , ,,,

Radionuclides

Mean Sta. Mean Mean

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

Be-7 s.5E o 18 4.25 i No DATA (12)

-(0) ( -3.s - 3.5)E 2 ( -3.s - 3.5)E 2-(0/ 12) (0/ 6)

K-40 2.0E 4 16 2.0E 4 NO DATA (12)

(0) ( 1.7 - 2.1)E 4 ( 1.1 - 2.1)E 4 (12/ 12) (6/ s)

Co-58 5.0E -1 18 1.25 i No DATA (12) i (0) ( -3.s - 3.2)E 1 ( -2.8 - 3.2)E 1 (0/ 12) (0/ s)

1. 9 E 1 - 16 2.0E 1 No DATA Co40 (12)

(0) ( -2.5 - 11.0)E 1 ( -5.7 - 32.5)E o (0/ 12) (0/ s) 150 -2.0E o 18 3.2E o No DATA Cs 134 (12)

(0) ( -3.5 - 2.3)E 1 ( -2.4 - 2.3)E 1 (0/ 12) (0/ s) 180 1.sE 2 16 1.8E 2 No DATA Cs-137 (12)

(0) ( 5.2 - 25.5)E 1 ( 5.2 = 2$.2)E 1 .

(10/ 12) (5/ s) l 8.9E 2 16 9.15 2 No DATA Th-232 (12)

(0) ( s.5 - 11.2)E 2 ( 7.6 - 11.2)E 2 (12/ 12) (s/ s) 31

e-Table 5.1 Radiological Environmental Program Summary Meine Yankee Nuclear Power Station, Wiscosset, ME (January December 1998)

MEDIUM! Marine Alane (AL) UNITS! nCl/km

'ad.1..5.s,ta,t!on,s,, ,s,tation wg,Higf,*st,,y,ean, C,g,n,tfp,1,S, tat,yps,,,,

Radionuclides

Mean Sta. Mean Mean (No. Analyses) ' Required Range Range Range (Non-Routine") LLO (No. Detected *") (No. Detected"*) (No. Detecteo"*)

1.5E 2 13 1. sE 2 ' No DATA Be-7 (13)

(0) ( 4.1 - 34.6)E 1 (1/ 13) (0/ 1) 5.2E 3 16 6.7E 3 No DATA K-40 (13)

(0) ( 3.0 - 6.s)E 3 (13/ 13) (1/ 1) 5.sE -2 11 2.7E O No DATA Mn-54 (13)

(0) ( -1.4 - 1.2)E i ( -9. 5 - 11. 7 ) E o (0/ 13) (0/ 10)

-3.0E o 16 6.3E O No DATA Co 58 (13)

(0) ( -1.0 - 0.7)E 1 (0/ 13) (0/ 1)

-s.sE O 16 4.9E 1 No DATA Fe-59 (13)

(0) ( -6.s - 4.9)E i (0/ 13) (0/ 1) 1.1E 1 11 1.5E 1 No DATA-Co-60 (13) .

(0) ( -3.,2 - 69.5)E o ( -5.2 - Ess.0)E -1 (0/ 13) (0/ 10)

-5.0E 0 44 1.5E 1 No DATA Zn-65 (13)

(0) ( -3.0 - 2.4)E 1 (0/ 13) (0/ 1)

-4.st 0 14 1.0E 1 No DATA Ag 110M (13)

(0) ( -4.1 - 1.0)E 1 (0/ 13) (0/ 1) ,

-7.sE O 14 5.4E O No DATA

$b 124 (13)

(0) ( -2.6 - 0.8)E 1 (0/ 13) (0/ 1) pl 2.5E O 13 1.2E 1 No DATA Cs-134 (13) !

(0) ( -9.7 - 24.9)E O (0/ 13) (0/ 1) l

.i

-1.4E O 13 2.9E o No DATA -

Cs 137 (13)

(0) (- .0 - 0.9)E 1 .

(0/ 13) (0/ 1) i i

32 f

i:

I:

l l

I 1

l Table 5.1 I

Radiological Environmental Program Summary f

Maine Yankee Nuclear P0wer Station, Wiscosset. ME i (January. December 1998) l MEDIUMr Milk fTM) UNITS: oCl/ka l

Station Wi I.n..d.ic.a.t.o.r..Sta.t.io..n.s...

. . ............th Highes.t..Mean

. . . . . . . . . . . . . . . C..o..n.t.r.o.l.S..t.a.t.i.o.n.s ...

Radionuclides

Mean Sta. Mean Mean (No. Analyses) Required Range Range Range ;

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

1.5E 3 15 1.sE 3 1.2E 3 K-40 _ (28)

( 9.8 - 20.0)E 2 ( 1.5 - 2.0)E 3 ( 9.5 - 14.8)E 2 (0)

(16/ 16) (5/ 5) (12/ 12)

Sr.49 (11) 9.4E 2 18 1.2E 0 -4.33 -1 (0) ( -3.7 - 5.2)E o ( -1.1 - 5. 2 ) E O ( -4.4 - 2.3)E O (0/ 7) (0/ 4) (0/ 4)

Sr.90 3.sE O -

15 5.0E 0 3.4E O (11)

( 1.9 - 5.4)E O ( 2.6 - s.4)E o ( 3.1 - 3.7)E o '

(0)

(7/ 7) (3/ 3) (4/ 4) 1 2.5E -2 15 s.4E -2 3.9E -2 1131 (27)

(0) ( -7.s - 22.0)E -2 ( 3.7 - 219.9)E -3 ( -9.5 - 42.3)E -2 (0/ 16) (0/ 5) (0/ 11) 15 -5.6E -1 15 2.3E -1 -2.0E -1 Cs.134 (28)

(0) ~ ( -2.3 - 2.s)E O ( -2.3 - 2.s)E o ( -2.5 - 1.0)E O (0/ 16) (0/ 5) (0/ 12) j 1

is 3.3E O 25 5.6E 0 5.6E O Cs.137 (28)

( -e.2 - 93.7)E -1 ( 2.1 - 10.s)E O ( 2.1 - 10.s)E O (0)

(2/ 15) (4/ 12) (4/ 12) 15 -2.sE -1 18 -9.7E -2 -4.32 -1 Bs.140 (28)

(0) ( -4.5 - 3.5)E o ( -4.5 - 3.5)E 0 ( -3.3 - 3.5)E O i (0/ 16) (0/ 11) (0/ 12) 33

r I

Table 5.1 Radlological Environmental Program Summary Maine Yankee Nuclear Power Station, Wiscasset. ME (January December 1998)

MEDIUM: Flah (FH) UNITS: nCl/km Station With High

.In..d.i.c.a.t.o.r

. . . Sta.t.io..n.s... .. ........ .. . . . ... ..

e s.t.

. .Me a..n C..o..n.t.r.o.l.S.t.a.t.io.n.s.....

Radionuclides

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

Be-7 (4) 2.3E 1 11 2.3E 1 -9.25 1 (0) ( 0.0 - 4.5)E 1 ( 0.0 - 4.5)E 1 ( -1.2 - -0.6)E 2 (0/ 2) (0/ 2) (0/ 2)

X-40 (4) 2.4E 3 .

11 2.4E 3 2.2E 3 (0) ( 2.3 - 2.5)E 3 ( 2.3 - 2.5)E 3 ( 2.1 - 2.3)E 3 (2/ 2) (2/ 2) (2/ 2) 130 1.4E 1 ,1.4E 1 7.5E o Mn.54 (4) 11 (0) ( 4.1 - 24.0)E o ( 4.1 - 24.0)E O ( 5.5 - 9.6)E 0 (0/ 2) (0/ 2) (0/ 2)

Co-58 130 -4.7E 0 24 -2.6E -1 -2.sE -1 (4)

(0) ( -6.2 - -3.1)E O ( -3.7 - 3.2)E 0 ( -3.7 - 3.2)E O (0/ 2) (0/ 2) (0/ 2)

Fe-59 (4, 240 -3.9E 1 24 -2.6E 1 -2.sz 1 (0) ( -5.7 - -2.2)E 1 ( -3.s - -1.4) 1- ( -3.s - -1.4)E 1 (0/ 2) (0/ 2) (0/ 2)

Co-60 (4) 130 -1.0E 1 24 1.sE O 1.sE O

'(0) ( -2.4 - 0.3)E 1 ( -3.4 - 7.0)E 0 ( -3.4 - 7.0)E O (0/ 2) (0/ 2) (0/ 2)

Zn.65 (4) 250 -3.6E O 11 -3.6E O -3.1E 1 (0) ( -2.s - 1.9)E 1 ( -2.s - 1.9)E 1 ( -3.4 - -2.s)E 1 (0/ 2) (0/ 2) (0/ 2)

Ag.110M (4) -4.3E 0 24 1.2E 1 1.22 1 (0) ( -s.1 - -2.4)E o ( 5.7 - 1s.0)E O ( 5.7 - 1s.0)E 0 (0/ 2) (0/ 2) (0/ 2)

Sb-124 . {4) -3.1E O 11 -3.1E O -1.0E 1 (0) ( -2.7 - 2.1)E 1 ( -2.7 - 2.1)E 1 ( -2.6 - 0.5)E 1 (0/ 2) (0/ 2) (0/ 2)

Cs.134 (4) 130 -5.2E o 24 3.3E O 3.3E O (0) ( -1.0 - 0.0)E 1 ( -2.3.- e.9)E O ( -2.3 - s.9)E O (0/ 2) (0/ 2) (0/ 2)

Cs.137 (4) 150 9.7E o 24 1.1E 1 1.12 1 (0) ( s.s - 10.6)E o ( s.9 - 12.8)E o ( s.9 - 12.s)E o (0/ 2) (0/ 2) (0/ 2) l 34

l' l Table 5.1 Radiological Environmental Program Summary Malne Yankee Nuclear Power Station, Wiseasset, ME (January December 1998) l f'

MEDIUt4 Lobster and Rock Crab (CR) UNITS! oct/ka I n.d.ic.a.t.o.r..S..ta..t.io..n.s...

S.tatio.n With Highes.t..Mean

. . . . . . . . . . . . . . . . . . . . ...... C..o..nt.r.o.l.S. t.a.t.i.o.n.s.....

Radionuclides

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

Be.7 (8) -6.0E 0 24 4.1E =1 4.1E -1 (0) ( -1.3 - 0.6)E 2 ( -5.4 - 6.9)E 1 ( -5.4 - 6.9)E 1 (0/ 4) (0/ 4) (0/ 4)

K.40 1.sE 3 24 2.2E 3 2.2E 3 (8)

( 1. 5 - 1. 9 ) E 3 ( 1.4 - 3.2)E 3 ( 1.4 - 3.2)E 3 (0)

(4/ 4) (4/ 4) (4/ 4) 130 -3.2E o 24 1.0E 0 1.0E o Mn-54 (8) '

(0) ( -1.7 - 1.1)E 1 ( -2.3 - 4.0)E 0 ( -2.3 - 4.0)E O (0/ 4) (0/ 4) (0/ 4)

Co-58 130 -s.7E 0 24 4.6E o 4.6E o (8)

(0) ( -2.9 - 1.0)E 1 ( -3.s - 16.3)E o ( -3.s - 16.3)E o (0/ 4) (0/ 4) (0/ 4) 260 -1.3E 1 11 -1.3E 1 -1.6E 1 Fe.59 (8)

(c) ( -7.3 - 4.5)E 1 ( -7.3 - 4.5)E 1 ( -7.4 - 4.2)E 1 (0/ 4) (0/ 4) (0/ 4) 130 -2.1E O 24 s.0E o s.0E O Co40 (8)

(0) ( -2.1 - 1.5)E 1 ( 2.2 - 15.0)E O ( 2.2 - 15.0)E o (0/ 4) (0/ 4) (0/ 4) 260 4.1E O 24 5.ss o 5.sE 0 Zn45 (8)

(0) ( -1.3 - 1.3)E 1 ( -2.2 - 3.6)E 1 ( -2.2 - 3.5)E 1 (0/ 4) (0/ 4) (0/ 4)

-2.9E o 11 -2.9E o -1.0E 1 Ag 110M (8)

(0) ( -1.4 - 1.0)E 1 ( -1.4 - 1.0)E 1 ( -3.1 - 0.0)E 1 (0/ 4) (0/ 4) (0/ 4)

-1.2E 1 24 3.5E 1 3.5E 1 Sb.124 (8)

(0) ( -2.7 - 0.4)E 1 ( -s.6 - 96.3)E o ( -e.6 - 96.3)E o I (0/ 4) (0/ 4) (0/ 4) 130 9.4E -1 11 9.4E -1 =1.2E 1 Cs.134 (8)

( -s.4 - 14.0)E o ( -2.4 - 0.0)E 1 (0) _ ( -s.4 - 14.0)E o (0/ 4) (0/ 4) (0/ 4) f 150 4.7E o 11 4.7E o -7.5E -1 Cs.137 (8) l (0) ( -2.1 - 10.5)E o ( -2.1 - 10.5)E o ( -6.5 - 3.5)E o j l (0/ 4) (0/ 4) (0/ 4) l L

35 i

i I

I

(

l Table 5.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station, Wiseasset, ME i (January. December 1998)

MEDIUM: Soft SheII Clams (MA1 tJNITS: OCl/ka_

l

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

S. tat.io.n With H..ighes.t..Mean

. . . . . . . . . . . . . . . . ...... C..o. .nt.r.o.l.S. .t.a.t.i.o.n.s.. . ..

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

2.0E 1 16 3.72 1 NO DATA l Be.7 (4)

(0) ( -3.0 - 10.4)E 1 ( -3.0 - 10.4)E 1 (0/ 4) (0/ 2)

K.40 1.0E 3 18 1.0E 3 NO DATA (4)

( 1.0 - 1.1)E 3 ( 1.0 - 1.1)E 3 (0)

(4/ 4) (2/ 2) 1.4E o 16 9.4E 0 No DATA Mn.54 .(4)

(0) ( -s.s - 14.4)E o ( 4.3 - 14.4)E o (0/ 4) (0/ 2) 4.sE o 18 6.2E o No DATA Co-58 (4)

(0) ( 1.6 - 7.41E 0 ( 4.9 - 7.4)E o (0/ 4) (0/ 2)

-2.3E 1 18 7.0E O NO DATA Fe-59 . (4)

(0) ( -7.7 - 3.4)E 1 ( -2.0 - 3.4)E 1 (0/ 4) (0/ 2)

Co40 (4) 1.2E 1 16 1.5E 1 NO DATA (0) ( -3.7 - 26.3)E O ( 4.1 - 26.3)E o (0/ 4) (0/ 2)

-2.is 1 16 5.9E O No DATA Zn45 (4)

(0) ( -4.0 - -0.2)E 1 ( -9.5 - -2.2)E O (0/ 4) (0/ 2)

Ag.110M (4) 7.5E O 16 1.2E i NO DATA (0) ( 1.0 - 16.8)E O ( 7.0 - 16.8)E O (0/ 4) (0/ 2) 5.2E -1 16 1.5E 1 NO DA1A Sb.124 (4)

(0) ( -1.5 - 2.0)E 1 ( 9.6 - 19.7)E o (0/ 4) (0/ 2)

-1.28 1 16 -1.0E 1 HO DATA Cs.134 (4)

(0) ( -1.s - -1.0)E 1 ( -1.1 - -1.0)E 1 (0/ 4) (0/ 2)

-6.8E -1 18 3.22 0 NO DATA Cs.137 (4) l (0) ( -5.4 - 6.4)E o ( 0.0 - s.4)E O (0/ 4) (0/ 2) 36

l i Table 5.1 l Radiological Environmental Program Summary l Maine Yankee Nuclear Power Station, Wiscasset. ME (January. December 1998)

MFolUMt Munnel (MU) UNITS! oCUka

!ad.ic.f.t.8.?.8a.".. Sta?.=.*2.0.'99.=t ..Y.ta.a. c.=?o.'.S.t*t9.a'....

Radionuclides

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

i Be-7 7.3E 1 11 7.3E 1 -1.7E 1 (3)

(0) ( 2.0 - 12.7)E 1 ( 2.0 - 12.7)E 1 (0/ 2) (0/ 2) (0/ 1) l K 40 (3) 1.25 3 24 1.5E 3 1.5E 3 l (0) ( 1.2 - 1.3)E 3 (2/ 2) (1/ 1) (1/ 1) 130 -5.sE o 24 -4.1E o -4.1x 0 Mn-54 (3)

(0) ( -e.9 - -2.9)E O (0/ 2,- (0/ 1) (0/ 1) 130 -e.4E -1 11 -s.4E -1 -3.4E 1 Co 58 (3)

(0) ( -5.9 = 4.2sE O ( -5.9 - 4.2)E O io/ 2) (0/ 2) (0/ 1) 260 -2.JE 1 24 3.sE 1 3.sE 1 Fe-59 (3)

(0) ( 'J.7 - -1.5)E 1 (0/ 2) (0/ 1) (0/ 1)

Co-60 130 1.1E 1 11 1.15 1 1.2E O (3)

(0) ( 6.s - 15.4)E O ( 6.s - 15.4)E O (0/ 2) (0/ 2) (0/ 1) 26r -1.3E 1 24 -1.5E o -1.5E o Tr.45 (3)

(6) ( -2.1 - -0.8)E 1 (0/ 2) (0/ 1) (0/ 1)

-3.2E o 11 -s.2E o -1.7E 1 Ag 110M (3)

(0) ( -3.5 - -s.0)E 0 ( -3.5 - -9.0 3 E 0 (0/ 2) (0/ 2) (0/ 1)

-5.0E o 24 7.65 -1 7.6E -1 Sb-124 (3)

I- (0) ( -1.3 - 0.3)E 1 (0/ 2) (0/ 1) (0/ 1) 130 -1.25 1 24 2.0E 1 2.0E 1 Cs 134' (3)

(C) ( -1.4 - -1.0)E 1 (0/ 2) (0/ 1) (0/ 1) 150 -3.6E o 24 2.1E 0 2.15 0 Cs.137 (3)

(0) ( -1.5 - c.s)E 1 (0/ 2) (0/ 1) (0/ 1) i l

1 l

37 l

l l 1

' Footnotes to Table 5.1:

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

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

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

l l

j l

1 i

1 l

l l

i l

t l

l l

i 38 L-

I l

TABLE 5.2 ENVIRONMENTAL TLD DATA

SUMMARY

MAINE YANKEE NUCLEAR POWER STATION, WISCASSET, ME OANUARY DECEMBER 1998)

INNER RING TLDs OLTTER RING 1LDs STATION WrrH HIGHEST MEAN CONTROL TLDs eeeeeeeeeeeeeeeeeeeeeee seeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeeeeeeeees eeeeeeeeeeeeeeeeee MEAN 2 5.D.* MEAN

S.D.* MEAN 2 5.D.* MEAN

S.D.*

RANGE

RANGE

STA. RANGE

RANGE *

(NO. MEASUREMENTS)** (NO. MEASUREMENTS)** NO. (NO. MEASUREMENTS)" (NO. MEASUREMENTS)"

7.3 0.9 7.5 t 0.9 23 9.5 t 0.6 8.0 t 1.2 5.2 - 9.6 5.9 . 10.2 8.8 - . 10.2 6.7 . 10.1 i (72) (68) (4) (12) {

l

\

Units are micro-R per hour.

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

NOTE: S.D. = standard deviation.

{

l 39

F TABLE S.3 i

Environmental TLD Hessurements 1998 (Micro-R per hour) sea, 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Ave.

No. Description Exp. S.D. Exp. S.D. Exp. S.D. Exp. S.D. Exp. S.E.

TL-01 Old Ferry Rd. 7.6 +,'O.3 8.4 1 0.4 8.5 f, 0.'4 7.7 g 0.5 8.1 + 0.4 TL-04 Old Terry Rd. 6.3 1 0.3 6.8 f, 0.4 7.8 0.3 6.5 3, 0.3 6.9 +, 0.3 TL-03 Bailey House , (ESL) 6.5 0.3 7.0 1- 0.2 7.6 0.3 6.7 0.4 6.9 +, 0.3 TL-04 Westport Is1./Rt. 144 5.2 ;, 0.3 6.1 f, 0.4 5.8 1 0.2 5.5 ;, 0.4 5.7 + 0.3 TL-05 MY Information Center 6.9 1 0.3 7.6 . 0.4 9.6 + 0.6 7.2 f, 0.5 7.8 1 0.4 7.7 0.4 7.4 + 0.4 0.3 TL-06 Rt. 144/Greenleaf Rd. 7.2 1 0.3 +, 8.3 ;, 0.3 7.6 f, TL-07 Westport Is1./Rt. 144 6.5 1 0.2 7.9 +,, 0.1 7.9 : 0.3 6.7 ;, 0.4 7.2 + 0.4 6.9 0.4 7.4 1 0.3 0.4 6.7 +, 0.4 TL-06 MY Screenhouse 6.3 1 0.3 ;, 6.4 ;,

Tk-09 Westport Is1./Rt. 144 9.0 + 1.4 7.3 f,, 0.6 7.6 +, 0.4 6.8 1 0.4 7.7 0.7 TL-10 Bailey Point 6.4 +, 0.3 6.8 1 0.5 7.6 1 0.4 6.3 1 0.4 6.8 1 0.4 TL-11 Mason Station 7.3 + 0.3 7.9 1 0.5 8.1 ;, 0.4 7.6 ,+ 0.4 7.7 + 0.4 l TL-12 Westport Firehouse 6.5 + 0.2 7.2 0.3 7.6 f, 0.5 7.0 1 0.4 7.1 1 0.4 TL-13 Foxbird Island 7.4 +, 0.3 7.9 +

0.4 8.8 1 0.5 7.7 1 0.5 7.9 3, 0.4 6.1 0.2 7.2 0.3 7.1 1 0.4 6.3 1 0.4 6.7 0.3 TL-14 Eaton Fara f, t TL-15 Eaton Farm . 5.4 +, 0.3 7.0 f, 0.3 8.0 f, 0.5 6.9 : 0.5 6.8 ;, 0.4 7.5 + 0.4 8.9 +, 0.5 +

6.9 ,, 0.4 7.9 + 0.5

.TL-16 Eaton Farm 8.3 ;, 0.8 0.3 9.0 t 0.5 8.3 0.4 0.4 TL-17 Eaton Farm Rd. 7.8 1 0.4 8.8 f, f, 8.5 f, TL-18 Eaton Farm Rd. 6.8 f, 0.3 7.8 1 0.8 8.1 1 0.5 7.1 0.4 7.5 1 0.5 !

I TL-19 Eaton Farm Rd. 6.9 + .0.4 1.5 1 0.4 8.1 +, 0.4 6.6 + 0.5 7.3 f, 0.4 7.2 0.3 7.4 1 0.4 6.5 f, 0. 5 6.8 +, 0.4 TL-20 Bradford Rd. 6.2 ;, 0.3 f, TL-21 Federal St. 6.4 +, 0.2 7.0 t 0.4 7.6 1 0.4 6.4 f, 0.4 6.8 ;, 0.3 TL-22 Cochran Rd. 6.3 + 0.2 7.6 f, 0.4 8.0 f,, 0.3 6.8 1 0.5 7.2 1 0.3 ,

TL-23 Middle Rd. 8.8 +,, 0.3 9.7 ;, 0.4 -10.2 1 0.7 9.3 1 0.5 9.5 1 0.5 7.8 + 0.4 8.3 0.4 7.3 3, 0.4 7.6 0.4 TL-24 River rd. 7.0 ;, 0.3 ,

f, 7.7 0.4 8.2 + 0.6 7.3 +, 0.4 7.5 f, 0.4 TL-25 River Rd./Rt. 27 6.9 1 0 . *2 TL-26 Boothbay RR Museum 7.0 f, 0.2 s.7 1 0.3 8.1 0.4 7.3 3, 0.5 7.5 , + 0.4 TL-27 Barters Island 6.5 f, 0.3 7.2 +

0.4 7.9 1 0.3 6.8 +

0.4 7.1 g 0.3 TL-28 Rt. 144/E. Shore Rd. 6.2 f,, 0.2 7.3 1 0.3 7.5 f, 0.3 6.4 f, 0.4 6.9 1 0.3 TL-29 Harrison's Trailer 6.4 f, 0.3 7.0 1 0.5 7.4 0.5 6.7 +, 0.4 6.8 1 0.4 TL-30 Leeman Farm 7.8 3 0.4 8.4 + 0.5 9.0 1 0.5 8.3 ;, 0.5 8.4 1 0.4 TL-31 Barley Neck Rd. 8.1 1 0.2 8.9 f, 0.6 9.2 1 0.4 8.6 1 0.5 8.7 : 0.4 9.0 +, 0.6 7.8 + 0.4 8.4 g 0.5 7.3 1 0.4 8.1 f, 0.5 TL-32 Baker Farm 6.5 , + 0.2 7.2 f, 0.3 7.9 1 0.4 6.8 f, 0.4 7.1 +, 0.3 TL-33 Rt.127 TL-34 Rt. 127 6.2 1 0.3 7.3 ;, 0.2 8.0 1 0.4 6.7 1 0.4 7.0 1 0.3 TL-3 5 ' Rt . 127 5.9 3, 0.2 6.8 . f, 0.3 7.9 10.3 6.2 f, 0.4 6.1 1 0.3 I

TL-36 Boothbay Hbr. Fire Sta. 6.8 f, 0.2 7.1 f, 0.4 7.0 1 0.4 1.0 + 0.4 7.0 1 0.4 9.3 0.5 9.4 1 0.5 9.4 +, 0.4 TL-37 Bath Fire Sta. 9.0 1 0.3 1 10.1 f, 0.4 7.8 0.3 0.4 7.6 +, 0.3 TL-38 Dresden Station 6.7 1 0.3 1 8.3 + 0.3 7.5 f, Notes

Exp. = Exposure Rate in micro-R/hr S.D. = Standard Deviation S.E. = Stand rd Error of the Mean 40 l-u

p L 6. ANALYSIS OF ENVIRONMENTAL RESULTS L

L 6.1. Sampling Program Deviations l

Table 2.3 of the Offsite Dose Calculation Manual (ODCM) allows for deviations in the REMP

. sampling schedule "if spec,imens are unobtainable due to hazardous conditions, to seasonal l unavailability or to malfunction of sampling equipment." Such deviations do not compromise the

~

. program's effectiveness and in fact are considered insignificant with respect to wh'at is normally

- anticipated for any radiological environmental monitoring program. The specific deviations for 1998 were as follows:

l

- The following short power outages or interruptions occurred at air sampling stations during

-1998:

a)' During the week ending Jan. 17,1998 at station AP/CF-29,170.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , b) During the week ending June 6,1998 at station AP/CF-29,58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months .

c) During the week ending July 25,1998 at station AP/CF-29,163 hours0.00189 days 0.0453 hours 2.695106e-4 weeks 6.20215e-5 months .

d) During the week ending Sept. 5,1998 at station AP/CF-13,16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months .

During the third quaner,TL-16 at the Eaton Farm was discovered missing. It was replaced upon discovery, but approximately 60 days of monitoring results were lost as a result of the missing TLD.

- Samples were only available from Location TM-15 from June through October during 1998.

This is an expected seasonal occurrence and is not considered a program deviation.

- In February, milk was not available from the indicator station (TM-18) because of the cows calving. In anticipation of this, samples of the cows feed stock (mixed grasses) was collected

. during January and February.

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.)

Occasionally an LLD is not achievab'e due to a situation such as a low sample volume caused by sampling equipment malfunction. In such a case, ODCM Appendix C, Section 1 requires a discussion of the situation. - At the DESEL, the target LLD for any analysis is typically 30-40

(_

41 i

L-

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 a posteriori(after the fact) LLD calculated for that analysis was compared with the required LLD. During 1998, over 1000 analyses had an LLD requirement listed in Table 2.4. Only faur sample analyses did not meet the required LLD. Three of the four analyses were Gross 8 eta analyses for Air Particulate Station 29 for weeks 2,29 and 50. The founh analysis was an I-131 Charcoal Filter analysis for Station 29, week 29. These analyses did not meet the required LLD due to low sample volume j because of sampling interruption caused by power outages.

6.3 Comparison of Results Against Reporting Levels Section 2.4.3.3 of the ODCM requires the notification of the NRC (via the Annual Radioactive x i

Effluent Release Repon) whenever a Reporting Level in ODCM Table 2.5 is exceeded. Reponing Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I. It should be noted that environmental concentrations are averaged over l calendar quarters for the purposes of this comparison, and that Reporting Levels apply only to measured levels of radioactivity due to plant effluents. During 1998. no Reporting Levels were exceeded.

6.4 Data Analysis by Media Type l l

The 1998 REMP data for each media type is discussed below. Whenever a specific l measurement result is presented, it is given as the concentration plus or minus one standard ]

deviation. This standard deviation represents only the random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure. 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).

42

p l

L l

l 6.4.1 Airborne Pathways 1 .

1 6.4.1.1 Air Particulates !

The weekly air particulate filters from each of the five sampling sites were analyzed for gross-beta radioactivity and are designated GR-B in Table 5.1. At the end of each quarter, the thirteen weekly filters from each sampling site were composited for a gamma analysis. The results of the weekly air particulate sampling program provided in Table 5.1 and are plotted in Figure 6.1 through Figure 6.5. As shown in Figure 6.1, there has been no significant difference between the l quarterly 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 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 madily 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 Maine Yankee activities. Table 5.1 shows that the mean gross beta concentrations from indicator stations are equal to those from control locations, further supporting this conclusion. The only gamma emitting 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 i results of these analyses are summarized in Table 5.1. In 1998, as in previous years, no I-131 was detected in any charcoal cartridge.

6.4.1.3 Mixed Grasses

' Although not required by the Maine Yankee ODCM, mixed grass samples were collected twice l

at the Bailey Farm during 1998. The sample collected in June contained trace levels of Cs-137.

However, there is no correlation with plant gaseous effluents, in which there was no Cs-137 43 l

l

(

l detected. Although it is the first time since 1986 that Cs-137 has been detected at this location, it is not uncommon to find Cs-137 in this media as a result of past nuclear weapons testing.

Naturally-occurring K-40 and Be-7 were also detected in both samples, as expected.

According to Table 2.3 in the ODCM, food products may be substituted for milk when milk is unavailable. For the Chewonki milk sampling location (TM-18), milk was unavailable during the month of February because of the cows calving. In anticipation of this, samples of the cows feed stock (mixed grasses) was collected during January and February. As expected, Cs-137 and l K-40 were detected in these samples.

6.4.2 Waterborne Pathways 6.4.2.1 Estuary Water l Aliquots of estuary water were automatically collected in the discharge canal outfall every two hours during 1998. These composited samples were collected monthly and sent to the DESEL l j for analysis. Monthly grab samples were also collected at the control location. Table 5.1 shows I that naturally-occurring K-40 was detected in samples collected at the WE-12 (plant outfall), as is typical with estuary water. A trace amount of Co-60 (0.71 0.18 pCi/l) was identified in the plant outfall sample for July. Co-60 was the predominant gamma emitting isotope in the liquid j radwaste discharges during the month of July. The most likely cause for the detection is the low j dilution flows. The monthly samples were composited each quarter, by station, for Tritium (H-3) analyses. One out of the four samples taken at station WE-12 showed a detectable level of H-3 l

l of1210 270 pCi/kg. Figure 6.6 provides a trend plot for quanerly composite H-3 concentrations at WE-12. All concentrations are plotted regardless of whether they are considered " detectable" or "not detectable". Those concentrations determined to be positive as defined in Section 5 are indicated with a black symbol. In accordance with Table 5.1 of the ODCM, a dilution factor of 10 is applied to this concentration since the sample was taken from the discharge forebay, prior j f i to release to the Back River via the underwater diffusers. The resulting environmental H-3 l

I L concentration of 121 pCi/kg for the composite sample is well below the NRC Reponing level for \

H-3 for the non-drinking water pathway of 30,000 pCi/kg. The Maine Yankee ODCM would !

require notification to the NRC in the Annual Radioactive Effluent Release Report if this Reporting Level had been exceeded. The increase in the H-3 concentration in the forebay water l from previous years is attributed to the reduction in dilution water flow without the circulating water pumps operating.

l 1

I 44 j l

I l

7 6.4.2.2 Ground Water j l

i Although not required by the Maine Yankee ODCM, quarterly ground water samples were collected from the well at the Environmental Services building and at a control location. The results of the gamma isotopic and H 3 analyses are shown in Table 5.1. None of these off-site samples contained detectable radioactivity.

l l

l 6.4.2.3 Shoreline Sediment Semiannual sediment core samples were collected from two on-site locations during 1998.

l Each set of samples was segmented by depth (0-5,5-10,10-15 cm) and analyzed for gamma-emitting radionuclides. The results presented in Table 5.1 show that as expected, naturally-l l

occurring K-40 and Th-232 was detected in all samples.

L In addition, Cs-137 was detected in ten out of the twelve segments. Although some Cs-137 is expected to be present from worldwide weapons testing fallout, much of the Cs-137 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 l diffuser was installed, and now the liquid effluents are discharged into the Back River. The Cs- )

137 levels in each sediment core section are plotted in Figures'6.7 and 6.8. These graphs show a range of Cs 137 concentrations across core sections. The two figures show that the levels have not changed significantly over the past several years. l Although there is no Reporting Level for Cs-137 in sediment samples, one might appreciate the negligible dosimetric consequence when the measured concentrations are conservatively j i

compared against the reporting levels for the fish ingestion pathway. The mean and maximum '

' Cs-137 measurements were 179 and 255 pCi/kg (dry), respectively, both under the Cs-137 Reporting Level in fish of 2000 pCi/kg.

6.4.2.4 Marine Algae Although not required by the Maine Yankee ODCM, mixed samples of Fucus and Ascophyllum marine algae (seaweed) were collected at Long Ledge every month except for April and October of 1998. In March, algae samples were also collected at three additional sites Maine Yankee Dock, Hanison's Dock, and the Causeway. These samples were taken due to concems raised over the discharge of processed chemical cleaning waste in the liquid waste stream. All samples were 45 i

analyzed for gamma-emitting radionuclides. As expected, only naturally-occurring K-40 and Be-7 were detected on the samples. No other gamma emitting radionuclides were detected in any of the samples.

6.4.3 Ingestion Pathways 6.4.3.1 Milk l

Milk samples were collected monthly when available during 1998 at two indicator and one control location. In February, milk was not available from the indicator station (TM-18) because ,

of the cows calving. As discussed in the section 6.4.1.3, samples of the cow's feed stock (mixed l l

grass) were collected with the January milk sample and as a substitute for the milk in February.

Milk was also coilected at a second indicator station when milk became available in June through October,1998. Each sample was analyzed for I-131 and other gamma-emitting radionuclides. I Although not an ODCM requirement, the samples were composited quarterly by location and analyzed for Sr-89 and Sr-90. I

. Cs-137 was detected in 2 of the 16 indicator samples and 4 of the 12 control samples. Of the )

two indicator stations, the goat milk from TM-15 had the highest Cs-137 mean concentration at l 5.5 pCi/kg with a range of 2.9 to 9.4 pCi/kg. The mean Cs-137 concentration for the control l station was also 5.6 pCi/kg, with a range of 2.1 to 10.8 pCi/kg. Figures 6.9 and 6.10 show the Cs-137 concentration in goat and cow milk for 1998. The Cs-137 concentrations in cow milk are '

similar to previous years and the Cs-137 concentration in goat milk has continued to decline. All Cs-137 concentrations, whether considered " detectable" or "non-detectable", are plotted in Figure 6.9. .J Figure 6.1I shows the Sr-90 concentrations in quarterly composited goat and cow milk for 1998. A slight decrease in the 1998 mean Sr-90 concentration in goat milk is indicated in Figure 6.12. The amount of strontium in milk is a function of many dietary factors, primarily calcium concentration and the degree of mineral exchange in the bones, and may be observed in the milk once an uptake has occurred. Neither the cesium or strontium in the goat milk is attributable to plant activities but rather is due to residual weapons fallout concentrations of Cs-137 and Sr-90 ,

and changes in the goats' eating habits.

i f 46

r 6.4.3.2 Fish & Invertebrates Semiannual samples of fish (FH) and invertebrates (Lobster (HA), rock crab (CA) and blue mussel (MU)) were collected from locations -11 and -24 during 1998. The media code for the combined category of lobster and rock crab has been designated as CR in Table 5.1. Soft-shell ,

l I

clams (Mya arenaria - MA) were collected from two locations within Bailey Cove. The edible portions of each of these biota were analyzed for gamma-emitting radionuclides. As expected in biological matter, naturally-occurring K-40 was detected in 19 out' of 19 fish and invertebrate l samples. No other radionuclides were detected.

I 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 quarter l for readout at the DESEL.

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 j

by naturally-occuning radionuclides in the soil. Differing amounts of these naturally-occurring radionuclides in the underlying soil, rock or nearby building materials result in different radiation l levels between one field site and another. It can be seen from Figure 6.20 that the TLD at Middle Road in Edgecomb (TL-23) has historically given slightly elevated readings. This is apparently l

due to its close proximity to a ledge outcrop, making it the station with the highest annual exposure in 1998 4 The first quarter 1998 exposure results for TL-09 at the Westport Siren were greater than 2 standard deviations higher than the four year average for that location. The probable cause was -

that water had leaked into the plastic wrapper and wet the badges, resulting in higher than normal readings. For the third quarter, the result for ' station TL-05 was also high with a reading of 9.6 l uR/hr. However, this value falls within the range for the control stations TL-36 to TL-38 whose values range from 6.8 to 10.1 uR/hr.

From Tables 5.2 and 5.3, as well as from Figure 6.13, it can be seen that the Inner and Outer l Ring TLD mean exposure rates were not substantially different in 1998, and that the Control TLD mean exposure rate was slightly greater than that at the Inner and Outer Rings.

f 47 l

n..

I l

l FIGURE 6.1 l

1 GROSS-BETA MEASUREMENTS ON AIR PARTICULATE FILTERS QUARTERLY AVERAGE CONCENTRATIONS 0.16 0.16 0.12- -0.12 .

1 5e >

E l

$a 0.08- -0.08 S

R 0.04- -0.04 0 i i i i i 0 l 1/1/88 1/1/90 1/1/92 1/1/94 1/1/96 1/1/98 i

l

-e- Indicator Stations

- x- Control Stations 48 l

s-i FIGURE 62 GROSS-BETA MEASUREMENTS ON AIR PARTICULATE FILTERS 0.06 0.06 0.05 { 0.05 5- 0.04 - -0.04 m . :

E . -

O -

X -

25 0.03 - l', x , -0.03 Y b Y .\ ' .. ' ,

b o" x x 5, x 'x; 0.02 '.

0.02 x j 0.01 5 g h0.01

~

0 , .

i . . , . . . . 0 Dec Feb Apr Jun Aug Oct Dec Feb 1998 e- AP 11 Montsweag Brook

- x - AP-29 Dresden Substation (control) 49

FIGURE 6.3 GROSS-BETA MEASUREMENTS ON AIR PARTICULATE FILTERS 0.06 _ 0.06 0.05 0.05 I

~

5 0.042 -0.04 15 E f o -

x -

g 0.03- j;,x, xr -0.03

3 x.

O xK

~

O 02 . ' ' ,l ' A -0.02 x

0.01 - - 0.01

~

0 .

i .

. 0 Dec Feb Apr Jun Aug Oct Dec Feb i

1998

-t2- AP-13 Bailey Farm (ESI.)

- x - AP-29 Dresden Substation (control)

I 50

nb I l l

FIGURE 6.4 GROSS-BETA MEASUREMENTS ON AIR PARTICULATE FILTERS 0.06 _ _ 0.06 f

0.05- -- 0.05 !

l 5 0.04 2 d -0.04 1 m . , : I E - -

o -

x -

Zi 0.03 - l', xy x x 7003 l

3 - .. '. ., ,X 4

-8 : J '.

o" .

. x .' X 'x, l' l3 *

-0.02 I 0.02 , .

x l . .

.l : ,

0.01 - - 0.01 1 x -

l

: l 0 1

. . . , . . . . . . . 0

, Dec Feb Apr Jun Aug Oct Dec Feb l

1998 1

i i

-t2- AP-14 Mason Steam Station !

- x - AP-29 Dresden Substation (control) 51

p FIGURE 6.5 GROSS-BETA MEASUREMENTS ON AIR PARTICULATE FILTERS 0.06 _ _ 0.06 0.05- h 0.05

' D 5 0.04- 0.04 E

E f .

O -

X -

l 3m 0.03- -

l: x x rp

,X 7003

8 x- -

o" .

x. , X -

0.02- l' x, x h 0.02 .

l x

j 0.01- ,

. 0.01 0 .

i i .

. O Dec Feb Apr Jun Aug Oct Dec Feb i

1998

-t2- AP-16 Westport Firehouse

- x - AP-29 Dresden Substation (control) 52

FIGURE 6.6 H-3 lN ESTUARY WATER WE-12, PLANT OLTTFALL 3200 3200 2800 -2800 24005 .

-2400 2000k ,

[2000 cn 16002

[1600 I 1200; -1200 800 2 -

0

[800 400k '

f400 Oj 0 7

-400 .

i i .

i i ~ -400 1988 1990 1992 1994 1996 1998

-t2- WE-12 Plant Outfall <

l

- m- WE 12 Positive Concentrations 53 L

FIGURE 6.7 CESIUM-137 IN SHOREUNE SEDIMENT STATION SE-16,OLDOUTFALL AREA 600 _ _

600 500i -500 400 '400 7

g . .

E : :

cn 300- -

-300

n. .

200, $ _

j' -200

= :, -

S1? ,

1002 [ 7 jE Q l jff] E I'N

'7 100

% s s

$ s s ,

d \ g '

0 i i , ,

i i 0 5/95 10/95 5/96 10/96 5/97 10/97 5/98 10/98 Month / Year E 0-Sem O 5 - 10 cm l 8 10 - 15 cm 54

FIGURE 6.8 CESIUM-137 IN SHOREUNE SEDIMENT STATION SE-18, FOXBIRD ISLAND 600 600 500 500 400 -

h400 n

p : 1 .

5 300' :s': '300

.c y :

Q .

200- s h200 0 i i i i i i i 5/95 10/95 5/96 10/96 5/97 10/97 5/98 10/98 i

Month / Year E 0-sem O s-1ocm O 10 - 15 cm 55

i~

l;

^

! FIGURE 6.9 CESIUM-137 IN MILK i

l.

40l, 40 2

l 30d - 30

\ . {

- 20 1 x

20 _-

s..

.a .

\

U. ..

a lo_ , -10 A a a :.

3 .

.0-

z . e4 m- " N/ :

-0 1

- q

-10 -10 >

Jan Mar May Jul Sep Nov Jan 1998

, -a- TM-15 Mitman Farm

-e - TM-18 Chewonki Foundation ,

t

--n- TM 25 Hanson Farm ,

i I

56 I

4

r::

1 FIGURE 6.10 CESIUM -137 IN MILK ANNUAL AVERAGE CONCENTRATIONS 1

40 40 j

. j

- t 30 - - 30 c

Cn ..

5 20 - o 20 O 7

o. -

. i 10 - o 10 x 7

'Na Aw _Ah S yo

~

l

[ o / -

0 0 l 1988 1990 1992 1994 1996 1998

-o- TM-15 Mitman Farm

--o- TM-18 Chewonki Foundation

--a- TM-25 Hanson Farm 57 l 1

I L

s a

FIGURE 6.11

. STRONTIUM-90 IN MILK'

.25 25 J -

.20-- -20

- 15 '

'15 .

D .

.x. .

s -

a .

- u. .

" '10-- - 10

.. O~g -

5- -5

. w-

~-p C" -

. 1 0 0 l Jan Apr .Jul Oct Jan I

1998 J

-D- TM-15 Mitman Farm

-er- TM-18 Chewonki Foundation i

l

-a- TM-25 Hanson Farm ,

58 l

s' l'

l l

l FIGURE 6.12 STRONTIUM-90 IN MILK ANNUAL AVERAGE CONCENTRATIONS 25 ,

25

~

20 - 20 152 .

-15 m .

g .

o. .

10-- -10

~

a / 4 M m"D6

- /

. a .

O O 1988 1990 1992 1994 1996 1998 m- TM 15 Mitman Farm l

1- TM-18 Chewonki Foundation

-n- TM-25 hanson Farm i

i 59

n -

l l

1 FIGURE 6.13 EXPOSURE RATE AT INNER RING, OUTER RING AND CONTROLTLDS 25 25

. 1 i

20- -20 Ei : :

$ 15- -15 E. -

g .

~

l g

31il==g pp5 go pH Q Q, 5- -5

~

0 0 1994 1995 1996 1997 1998 1999 Retrieval Date l

m- Control

--a- Inner Ring

- x - Outer Ring i

60 l 1

!- l i

b.

l

)

FIC'JRE 6.14 l 1

EXPOSURE RATE AT INNER RING TLDS, TL 01- 04 25 25 20 1 20 g .

Iu 15- ,

-15 g .

- i E

-10

. 10f. ,

o ,

0, 0 1994 1995 1996 1997 1998 1999 Retrieval Date

-c- TL-01 Old Ferry Road

-x- TL-02 Old Ferry Road e ' TL-03 Bailey House (ESL) v TL-04 Westport Island, Rt.144 1

61 w

FIGURE 6.15 EXPOSURE RATE AT INNER RING TLDS, TL 05 - 08 25 -

- 25 20- -20 s .

g .

-15 I 15- ,

g .

h10 a -10 5-

% &MW Wh5%Y :

-5 0 0 1994 1995 1996 1997 1998 1999 Retrevial Date

-c- TL-05 MY Information Center

-x- TL-06 Rt.144 & Greenleaf Road e TL-07 Westport Island, Rt.144

-o- TL-08 MY Screenhouse 62 r.

l L.

i.

i l

l FIGURE 6.16 EXPOSURE RATE AT INNER RING TLDS, TL 09-10,12-13 25 25 l

~

201 - 20 J

1 g

t 15- -15 u

8,. .- -

g .

~

h10N -10

'8~~ wp Sk7gMbMNN j,

-5 5- _

~

0 0 1994 1995 1996 1997 1998 1999 )

i Retrieval Date j

-c- TL-09 Westport Siren

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

63 i

l

FIGURE 6.17 EXPOSURE RATE AT INNER RING TLDS, TL 14-16 25 ,

25 20 - - 20

~

Ei .

$ 15- -15

g. : :

g .

h10 -10 5 Ill -5 0 0 1994 1995 1996 1997 1998 1999 Retrieval Date

-c- TL-14 Eaton Farm

,t TL 15 Eaton Farm ,

i

-n- TL 16 Eaton Farm 64 l

E i

i I

i l

l

! FIGURE 6.18 EXPOSURE RATE AT INNER RING TLDS, TL 17 - 19

--- 25 l 25 ,

i 20 -- - 20 u s I8_15- -15 m -

8.

-x

. h10- --10 54 1 A$spkMSNWNE

-5 i

0 0 .

1994 1995 1996 1997 1998 1999 l

Retrieval Date ]

-c- TL 17 Eaton Farm ,

-x- TL-18 Eaton Farm

-n- TL 19 Eaton Farm ;

i 65 L

t-

l p

1 FIGURE 6.19 )

EXPOSURE RATE AT OUTER RING TLDS, TL 11,20-22 l

25 25 , l 20- -20 u _r .

g . .

I 15 - -15 m . .

g . .

g. .

6 -10 t3 10 -

k '

~

5- -5 0 ,

0 1994 1995 1996 1997 1998 1999 RetrievalDate

-c- TL-11 Mason Station .

-x- .TL-20 Bradford Road, Wiscasset e TL-21 Federal Street, Wiscasset l

i o TL-22 Cochran Road, Edgecomb t

66 f.

re

)

FIGURE 620 l l

EXPOSURE RATE ATOUTER RING TLDS, TL 23-26 ,

25 25

~

202 -20

: I 6.

g .

I 15- -15 g .

1 cc

..' .D .

O _g ,,,0 4 gD %_g N.-0

- h 6' 8 w W ._ g > 5%-S # i g N:

s 5 -- -5 0 0 i

.1994 1995 1996 1997 1998 1999 ,

1 Retrieval Date

-c-- TL 23 Middle Road, Edgecomb

-x- TL-24 River Road, Edgecomb e TL-25 River Road & Rt. 27 0 TL-26 Rt. 27 & Boothbay RR Museum 67

~

g.

FIGURE 6.21 EXPOSURE RATE ATOLTTER RINGTLDS, TL27-30 25 , 25

]' : I 20 -

-20 8

I 15 - -15 w . .

R - -

I g . .

h10- -10 E i ro MN:

5 pY s

gTyg x

egd4fegAW t o

Ah=MgA*E%g: f

-5

~

? -

J -

0 0 i 1994 1995 1996 1997 1998 1999 Retrieval Date i

--c- TL 27 Barters Island

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

-c- TL 29 Harrison's Trailer !

v- TL-30 Leeman Farm, Woolwich l

68 l

l-i

]

1 1

1 l

FIGURE 6.22 j l

EXPOSURE RATE ATOUTER RINGTLDS, TL31 -35 1 25 25

. 1 20- -- 20 l g .

15- 15 l E

[ .

x -

h '10 -10 5- -5 0 0

. 1994 1995 1996 1997 1998 1999 Retrieval Date 2 --c- TL 31 Barley Neck Road, Woolwich

-x- TL-32 Baker Farm, Woolwich n- TL-33 Route 127,Woolwich

-o- TL 34 Route 127,Woolwich l -c- TL 35 Route 127,Woolwich 1;

i 69 I-L L

p

[.

l l-FIGURE 6.23 EXPOSURE RATE ATCONTROL RING TLDS, TL36-38 l

25 25

~

20 -20

- \

y g .

Iw 15- -15 R -

~

cc - .

g .

.y 10 - 3 ,-10 MA=5MMi h A -5 5- -

0 0 1994 1995 1996 1997 1998 1999 Retrieval Date

-c- TL-36 Boothbay Harbor Fire Station .

\

i

-x- TL-37 Bath Fire Station l

--n- TL-38 Dresden Substation j l

,0 p

1 7, QUALITY ASSURANCE PROGRAM [

l The quality assurance program at the Duke Engineering & Services Laboratory is designed ;

to serve two overall purposes: 1) Establish a measure of confidence in the measurement process i to assure the licensee, regulaton 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 l reporting of data, as well as the record keeping of the final results. Quality control, as part of the j quality assurance program, provides a means to control and measure the characteristics of )

measurement equipment and processes, relative to established requirements.

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

program.

l This summary reports all interlaboratory known values or intralaboratory results received by l the DESEL on or before January 31,1999.

7.1 Intralaboratory Quality Control Program The Duke Engineering & Services Laboratory conducts an extensive intralaboratory quality control program to assure the validity and reliability of environmental analytical data. This program involves the submittal of occasional process check samples. These samples may be submitted as duplicates to evaluate the precision of the measurements or may be " 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 check results may be found in Table 7.1 71 m

Two low level iodine-131 (chemistry followed by beta-gamma coincidence counting) results -

L fell into category 4 for bias and precision and contributed to the issuance of CR98-009. One gamma result fell into category 4 of the Bias Criteria. However, since the mean bias for this set

).

was within 15%, no further action was required.

L L e ' Two low-level iodine-131 in milk results fell outside the acceptance criteria for bias and j precision. The'mean bias for the set was within 15% of the known value. The DESL

. confirmed the iodine-131 activity by gamma analysis to be within 5% of the mean. Inquiry 6-98 was issued to investigate the first precision outlier which occurred in September, but was subsequently changed to CR98-009 following the occurrence of the second failure in l October and a review of the Analytics low-level iodine 131 which indicated two additional outliers. CR98-009 was issued in December 1998.

l 1

7.2 Third Party Intercomparison Program To funher verify the accuracy and precision of the Laboratory analyses, the Duke Engineering

& Services Laboratory (DESEL) participates in two independent third parties intercomparison programs.

At the end of 1995 the U.S. Environmental Protection Agency stopped its Environmental Intercomparison Studies Program. At that time, the DESL replaced the mix of radionuclides and matrices (milk, water and air filters) which had comprised the EPA program with another third party QA program managed by Analytics Inc. The Laboratory continued to participate in the EPA drinking water Performance Evaluation (PE). This year (1998) is the last year during which the

. EPA will provide PE samples for analysis. The overall scope of the program managed by Analytics was designed to be comparable to the pre-1996 EPA program and reflects the mix of client REMP media processed by the DESL.

~ Participation in such programs and the reporting of results in this report is pursuant to Maine Yankee ODCM section 2.4.

Each sample supplied by tiie EPA or Analytics is analyzed in triplicate and the results are L returned to the EPA or Analytics within a specified time frame. The known values from Analytics

. are evaluated against the Laboratory acceptance criteria described in the DESL Manual 100 -

Laboratory QA Plan , and the EPA results are evaluated against the EPA control limits. When the 72 l

I l L

1 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.

]

EPA PE Procram: During 1998, the DESL analyzed 13 sample sets, representing 34 nuclides, for the EPA PE Program. The analyses included gamma-emitting radionuclides, gross alpha, !

l gross-beta, strontium-89 and 90, low level iodine-131, tritium, radium-226 and 228 and natural l uranium. Table 7.2 provides a summary of the results for 1998. One set of EPA gross alpha analyses (reference date 1/30/98) fell outside the EPA control limits. ,.

l 1

e Inquiry 3-98 was issued to address the failure of the 1/30/98 gross alpha samples.

DESL mean value: 9.8 pCi/L EPA known value: 30.50 7.60 pCi/L 1 i

EPA control limits: 17.30 - 43.70 pCi/L !

, )

The DESL had previously determined the root cause of the low bias in gross alpha i l

analysis to be sample evaporation and the amount of solids present in the sample. ;

Follow-up analyses of the EPA samples (EL 189-98) produced results that were within j

+6.6% and +5.9% of the EPA known value, with and without salts respectively.

l To provide additional assurance that the root cause for the low bias in the gross alpha analysis was identified, the DESL requested and processed a back-up sample from the 1/30/98 PE sample (A79087-A79089). This analysis resulted in the following results:

DESL mean value: 17.92 pCi/L EPA known value: 30.50 7.60 pCi/L EPA controllimits: 17.30 - 43.70 pCi/L The Laboratory Quality Assurance Review Committee (LQARC) determined that no further action was necessary because these results were within the EPA control limits.

ANALYTICS Program: 14 sample sets in water, milk and air filter matrices were analyzed as part of the Analytics Inc. Cross Check Program. The analyses included gamma-emitting radionuclides, gross alpha, gross-beta, strontium-89 and 90, low level iodine-131, tritium, Radium-226 and 228, plutonium-238 and 239 and uranium-234 and 238. Table 7.3 provides a summary of the results for 1998.

73

W I

e ' All DESL mean value results met the acceptance criteria for bias. However, two low level iodine-131 results with the following precision,-14.4 % for milk and -16.8% for water, contributed to the change of Inqui y 6-98 to CR 98-009.

- 7.3 : Environmental TLD Quality Assurance Program l

Performance documentation of the routine processing of the Panasonic environmental TLDs (thermoluminescent dosimeter) program at the Duke Engineering & Services Laboratory is provided by the dosimetry quality assurance testing program. This program includes the National l

' Voluntary Laboratory Accreditation Program, independent third party performance testing by Batt:lle Pacific Northwest Labs and internal performance testing conducted by the Laboratory QA Officer. Under these programs, dosimeters are irradiated to ANSI specified testing criteria and submitted for processing to the Dosimetry Services Group as " unknowns". The bias and precision of TLD processing is measured against this standard and is used to indicate trends and changes in performance. Instrumentation checks, although rout'inely performed by the Dosimetry Services Group and representing between 5-10% of the TLDs processed, are not presented in this report because they do not represent a true process check sample since the doses are known to the processor.

I The DESEL processed 3576 environmental TLDs during 1998. Ninety-six independent performance tests were conducted (2.7% QC). Of these, the QA Officer submitted 72 to the Dosimetry Services Group and 24 were submitted as part of Battelle Pacific Northwest Laboratories testing program. One hundred percent of these met the acceptance criteria for accuracy and precision with a mean bias during the first half of 1998 of-0.1 2.5% and -1.9 3.3% during the second half of 1998.

During 1998, a special study was conducted to evaluate the dosimeter mean bias response as a function of depth and dose level. The process was standardized by "binning" the dose levels into 100 mR increments starting with 0 mR out to 400 mR for high energy photon irradiations (NVLAB Category IV). The environmental TLD percent bias was 0.81,0.83 and -2.80 at dose levels of 0-100mR, >100-200mR and >300-400mR, respectively.

7.4 Blind Duplicate Quality Assurance Program

' The Laboratory Quality Control Audit Committee (LQCAC) is comprised of one member from each of the five New England power plants that are serviced by the Duke Engineering & Services l 74 f

l

e Laboratory. 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 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 evaluates the results of the paired measurements for precision.

Fifty-five paired samples were submitted under this program by the five participating plants during 1998. Paired measurements were evaluated for twenty-five gamma emitting radionuclides, H-3, Sr-89, Sr-90, I-131 and gross-beta. All measurements are evaluated, whether the results are statistically positive or not, and whether the net concentration is positive or negative. Of the 1492 paired measurements evaluated in 1998,1486 or 99.6% fell within the established acceptance ciiteria.

The samples submitted as part of this program are listed in Table 7.4.

l 75 L

TABLE 7.1 - Duke Engineering & Services Ensironmental Laboratory ,

1998 Environmental Process Control Results Media Bias Criteria (1) Precision Criteria (2)

Analysis 1 2 3 4 1 2 3 4 1 A'r Charcoal Gamma 51 2 (1- Air Filter Beta 107 i Gamma 1 2 1 2 111. Milk Gamma 21 10 2 29 4 lodine (LL) 3 2 2 2 1 4 2 2 IV Water Gross Alpha Gross Beta Gamma 9 5 3 1 36 18 10 lodine (LL)

Radium Tntium 3 3 Strontium V Sediment / Soil Gamma 26 14 6 VI Vegetation Gamma 2 Total Number in Range 192 25 7 3 98 42 18 2 Percentage of 85 11 3 I i 26 11 1 Total Processed 61 Sum of Analyses 227 160 (1) Percent Dias Criteria by Dias Category (2) Percent Precision Criteria by Precision Category Dias Category = 1 > 0% and <= 5% Precision Category = 1 >0% and <= 5%

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

Dias Category = 3 > 10% and <= 15% Precision Category = 3 >10% and <= 15%

gross alpha, Sr8990 > 10% and<= 25% gross alpha, Sr89/90 > 10% and <= 25%

transuranics > 10% and <= 20% transuranics > 10% and <= 20%

Bias Category = 4 Outside Cntena Precision Category = 4 Outside Criteria (LL)=todine Low Lesel Analysis I

76 l

~

-Table 7.2 - Duke Engineering & Services Environmental Laboratory 1998 EPA Cross Check Program Results LOWER UPPER NUCLIDE MEDIA' REFERENCE DESL CONTROL CONTROL DATE MEAN* LIMIT

LIMIT

Sr90 Water 01/16/98 28.4 23.3 40.7 Alpha Water 01/30/98 9.8 # 17.3 43.7 Beta - Water 01/30/98 7.3 0.0 13.7 1131LL Water 02/06/98 108.9 86.7 123.1 Ra-226 Water 02/13/98 16.8 11.8 20.2 Ra-228 Water 02/13/98 33.7 18.9 47.7 Natual U . Water 02/13/98 28.9 26.8 37.2 H3 Water 03/13/98 .2095 1551 2759 Sr-90 Water 04/21/98 15.5 9.3 26.7 Co-60 Water 04/21/98 48.2 41.3 58.7 Cs-134 Water 04/21/98 21.2 13.3 30.7 Cs-137 Water 04/21/98 9.1 1.3 18.7 Ra-226 Water 04/21/98 17.4 11 19 Ra-228 Water 04/21/98 9.0 5.3 13.3 Natural U Water - 04/21/98 4.1 0.0 10.2 Cs-134 Water 06/05/98 27.9 22.3 39.7 Cs-137 Water 06/05/98 35.1 26.3 43.7 Zn 65 Water 06/05/98 103.9 86.7 121.3 Co-60 Water 06/05/98 11.8 3.3 20.7 Ba-133 Water 06/05/98 37.6 31.3 48.7 Natural U Water 06/12/98 3.4 0.0 -8.2 Ra 226 Water 06/12/98 4.7 3.7 6.1 Ra-228 Water 06/12/98 2.4 1.2 3.0 Sr 29 Water 07/17/98 20.8 12.3 29.7 Sr 90 Water 07/17/98 8.1 - 0.0 15.7 Beta - Water 07/24/98 13.5 4.5 23.4 Alpha Water 07/24/98- 5.4 0.0 15.9 H3 Water 08/07/98 17551 14873 21119 Ra-226 Water 09/18/98 1.7 1.2 2.2 Ra 228 Water 09/18/98 6.2 3.3 f.1 Natural U Water 09/18/98 8.5 3.9 14.3 1131LL Water 09/11/98 5.6 2.6 9.6

Units in pCi/ Liter 77

7.

1998 ANALYTICS Cross Check Program Results Sample: E1337162 Gamma, Nat U Quarter: 1st,1998 Radium, Plutnium ,

El338-162 Alpha, Beta Media: Water Units: pCi/L Ratio Nuclide Reported Known DESU Evaluation Value Value Analytics Cr 51 171 167 1.02 Agreement Mn 54 til 111 1.00 Agreement Fe-59 82 79 1.04 Agreement Co-60 70 71 0.99 Agret 2n-65 120 118 1.02 Agreement 1-131 90 90 1.00 Agreement 1131LL 92 90 1.02 Agreement Cs-134 68 70 0.97 Agreement Cs 137 136 134 1.01 Agreement Cc-141 59 58 1.02 Agreement Alpha 42 38 1.11 Agreement '

Beta 308 269 1.14 Agreement Ra-226 56 53 1.06 Agreement Ra 228 47 46 1.02 Agreement Pu-238 72 75 0.96 Agreement Pu 240 43 42 1.02 Agreement U-234 30 29 1.03 Agreement U-238 31 30 1.03 Agreement Sample: E1340-162 Gamma Quarter: 1st,1998 E1341 162 Strontium Media: Milk Units: pCi/L Ratio Nuclide Reported Known DESU Evaluation Value Value Analytics Cr-51 204 201 1.01 Agreement Mn-54 139 133 1.05 Agreement Fe 59 100 95 1.05 Agreement Co-60 86 85 1.01 Agreement Zn-65 147 142 1.04 Agreement 1 131 84 82 1.02 Agreement 1-13 t LL 83 82 1.01 Agreement Cs-134 83 84 0.99 Agreement Cs 137 171 161 1.06 Agreement Cc141 73 70 1.04 Agreement Sr 89 55 53 1.04 Agreement Sr90 45 44 1.02 Agreement 78

[ Table 7.3 - Duke Engineering & Services Environmental Laboratory

~1998 ANALYTICS Cross Check Program Results. j g (continued) t l

l-l Sample: E1421 162 Gamma Quarter: 2nd,1998 Media: Milk ' Units: pCi/L Ratio ;

Nuclide Reported ' Known DESU - Eva'uation j Value Value Analytics 4

1 Cr-51 128 132 0.97 Agreement . l f Mn-54 111 106 1.05 Agreement

, Fe-59 46 45 1.02 Agreement -

l Co-60 144 143 1.01 Agreement Zn 65 124 122 1.02 Agreement I-131 71 67 1.% Agreement l 1131LL 67 67 1.00 Agreement Cs-134 97 95 1.02 Agreement Cs-137 74 70 1.06 - Agreement Cc 141 102 99 1.03 Agreement l

Sample: E1417162 Gamma Quarter: 2nd,1998 E1418162 Strontium E1419-162 Alpha, Beta

Media: Filter Units:' pCi/ Filter Ratio Nuct'de i Reported Known DESU - Evaluation Value Value Analytics Cr 51 111 113 0.98 Agreement Mn 54 96 91 1.05 Agreement !

Fe-59 43 39 1.10 Agreement Co-60 . 116 124 0.94 Agreement Zn 65 114 105 - 1.09 Agreement Cs-134 84 82 1.02 Agreement Cs137- 62 61 1.02 Agreement Ce-141 80 85 0.94 Agreement Alpha 36 36 1.00 Agreement Beta 220 212 1.04 Agreement l~ Sr-89 140 142_ 0.99 Agreement Sr-90 49 51 0.96 Agreement l_

79 c:

Table 9.3. Duke Engineering & Services Environrnental Laboratory

[? 1998 ANALYTICS Cross Check Program Results (continued)

Sample: E1420162 Gamma Quaner 2nd,1998 i hiedia: . Waser . Unies pCit I Ratio f

Reponed - Knoma DESL/ ~ Evaluation

~

Nuclide

- Value Value Analwies H-3 5697 - 6007 0 95 - Agreement i i l

1

$ ample. E1537162 Gamma Quaner. 3rd,1998 E1538-162 Strontium kledia. Atilk ' Umts: pCil-l Ratio l

Known Esaluation j Nuclide Reponed . DESLI Value Value Anahtics Cr 51 180 186 0 97 . Agreement i hin-54 77 74 1 04 Agrument Fe-59 66 63 . 1 05 Agrument Co-60 146 148 0 99 Apeement Zn 65 201 195 1 03 Agreement I-131 96 90 1 07 Apeement I13tLL 87 90 0 97 Agreement *

. Ca 134 80 82 0 98 Agreement Cs137 134 134 1 00 Agreement Ce 141 145 146 0 99 Agreement St-89 62 St i 22 Agreement Sr 90 72 81 0 89 Agreement

! Sample- E1534162 Gamna Quaner 3rd.1998 E1535-162 Strontium El536162 Alpha. Beta kledia Waier l'aits. PCit Ratio Nuclide Renoned Knonn DEST > Evaluation Value Value Anali tes -

Alpha 61 66 0 92 Agreement Beta 190 198 0% Agreement Sr-89 83 84 0 99 Agreement

$r 90 47 51 0 92 Agreement Cr 51 172 165 1.04 Agreement kin 54 66 66 1 00 Agreement Fe 59 59 55 1 07 Agreement Co 60 129 131 0 98 Agnement Zn-65 175 173 1.01 Agreement 1131LL 78 79 0 99 Agreement

l-131- 82 79 1 04 Agreement Cs 134 78 73 0 97 Agreement Cs137 117 119 0 98 Agreement

{-

Ce 141 129 129 1 00 Agreement

Accuracy within agreement entena, but precision result comerhaed to CR98-009 l- 80 i-l-

l l'

L

( = --

TABLE 7.4

SUMMARY

OF BLIND DUPLICATE SAMPLES SUBMITTED January - December 1998 l

TYPE OF SAMPLE NUMBER OF PAIRED SAMPLES SUBMITTED l

Cow Milk 26 Ground Water 8 Surface Water 16 Irish Moss 2 Mussels 4 Food Product Cranberries 1 TOTAL 57 f

i l

81 L

-8. LAND USE CENSUS -

Maine Yankee' ODCM section 2.4.4 requires that a Land Use Census be conducted annually. The Census identifies the locations of the nearest milk animal, 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 plant. The 1998 Land

. Use Census was conducted on August 27,1998.

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 1998 Census, no such new milk animal location was identified.

Consequently, no changes were made in the milk sampling program. ,

The results of the 1998 Land Use Census are included in this report in compliance with ODCM Section 2.4.4.3 and ODCM Appendix C, item 1. The locations identified during the Census may be found in Table 8.1.

82

N l

f. I TABLE 8.1 i

1998 LAND USE CENSUS LOCATIONS l SECTOR NEAREST. NEAREST NEAREST MILK i RESIDENCE- GARDEN ANIMAL f Km (Mi) Km (Mi) Km(Mi) f.

l l N 1.26(0.78) 1.26 (0.78)

I NNE 2.23 (1.38) 2.40 (1.49)' 2.65 (1.6)(Cows) f'

! NE 1.27 (0.79) 2.18 (1.35)

.ENT 0.92 (0.57)*** 1.20 (0.74) 0.90 (0.56)*, **

E 0.90 (0.56) l ESE 1.40 (0.87) 0.90(0.56)

SE 0.70(0.40)* 0.90 (0.60)

SSE 0.90 (0.60) 0.90 (0.60)

S 1.70 (1.10) 1.70 (1.10)*" 5.53 (3.5) (Goats)

SSW 3.00 (1.90) 5.00 (3.10) i SW- 1.50 (0.93) 1.57 (0.98) 7.90 (4.9)(Cows)

WSW 0.96 (0.60) 1.e 4 (1.20) 1.88 (1.17)(Cows)

W 0.81 (0.50) - 2.71 (1.68)

-WNW l.90 (1.18) 1.87 (1.16)*"

NW l.93 (1.20) 1.93 (1.20) ,

l NNW 1.06 (0.66) 1.18 (0.73)- 8.10 (>5) (Cows)

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

" No location was identified within 5 miles of the plant.

" New in 1998 I-83

9. REFERENCES

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

l

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

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

4. Kathren, Ronald L., Radioactivity and the Environment - Sources, Distribution, and Surveillance, Hanvood 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 1

Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.

i 1

84 l l

l

ML20206D736

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Subject:

Navigation menu

ML20206D736

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Subject:

Navigation menu

Search