ML20217N699
| ML20217N699 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/31/1997 |
| From: | DUKE ENGINEERING & SERVICES |
| To: | |
| Shared Package | |
| ML20217N673 | List: |
| References | |
| NUDOCS 9805050401 | |
| Download: ML20217N699 (93) | |
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MAINE YANKEE NUCLEAR POWER STATION l
ANNUAL RADIOLOGICAL ENVIRONMENTAL
[. OPERATING REPORT January - December 1997
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April 1998 f
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Prepared by:
Duke Engineering and Services
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Environmental Health and Safety 580 Main Street Bolton, Massachusetts 01740
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( . EXECUTIVE
SUMMARY
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.During 1997, 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 included f ground water, estuary water, sediment, marine algae, fish, mussels, clams, crabs,' lobsters, grass and milk. In addition to these samples, the air surrounding the plant was sampled continuously
[' 'and the radiation levels were measured continuously with environmental TLDs.
Low levels of radioactivity from naturally-occurring, fallout and plant emission sources were .
detected. 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.
b Many milk and sediment samples had fallout radioactivity from atmospheric nuclear weapons tests conducted primarily from the late 1950's through 1980. Several samples had low levels
[ of radioactivity resulting from emissions from 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 exposme from natural background radiation. In no case b_ 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 voluntarily shutdown in December of 1996 and remained shutdown during 1997. In August 1997 the decision was made to permanently cease power operation.
The plant has begun the process of decommissioning which will eventually involve the b 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 j
[ Maine _ Department of Human Services.
The radiological environmental monitoring program for Maine Yankee continued to L ~ operate during 1997 and will continue throughout the decommissioning period.
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TABLE OF CONTENTS
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- i. INTRO D UCTiON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i
- 2. NATURALLY OCCURRING AND MAN-MADE BACKGROUND RADIOACTIVITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.1 Naturally Occurring Background Radioactivity . . . . . . . . . . . . . . . . . . . . . . . . , 2
- 2.2 Man-Made Background Radioactivity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
- 3. GENERAL PLANT AND SITE INFditMATION . . .* .i . . . . . . '. . . . . . . . . . . . . . . . 'S b
- 4. PR OG RAM DES IG N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 '
- 4.1 Monitoring Zones . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 4.2 Pathways Monitored . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 4.3 Descriptions of Monitoring Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
- 5. RADIOLOGICAL DATA
SUMMARY
TABLES . . . . . . . . . . . . . . . . . . . . . . . . . 24
- 6. ANALYSIS OF ENVIRONMENTAL RESULTS . . . . . . . . . . . . . . . . . . . . . . . . . 41 6.1 Sampling Program Deviations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 f- 6.2 Comparison of Achieved LLDs with Requirements . . . . . . . . . . . . . . . . . . 41 6.3 Comparison of Results Against Reporting 12vels . . . . . . . . . . . . . . . . . . . . 42 6.4 Data Analysis by Media Type . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42
- 7. QUALITY ASSURANCE PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 71 7.1 Intralaboratory Quality Control Program . . . . . . . . . . . . . . . . . . . . . . . . . . . 71 7.2 Third Party Intercomparison Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 72 7.3 . Environmental TLD Quality Assurance Program . . . . . . . . . . . . . . . . . . . . 73 7.4 ~ Blind Duplicate Quality Assurance Program . . . . . . . . . . . . . . . . . . . . . . . . 74 l:
- 8. LAND USE CENS US . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83
- 9. RE FERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 5 iii I-
LIST OF TABLES Table Title Pace 4.1 Radiological Environmental Monitoring Program ........................ 12 4.2 Radiological Environmental Monitoring -
Locations (Non-TLD) in 1997 ..... ................................................. 14 4.3 Radiological Environmental Monitoring Locations (TLD) in - 1997 ..... ...... ... . ..... .. . ............... . ....... .... ........ 16 4.4 Environmental Lower Limit of Detection (LLD)
Sensitivity Requirements ......... ........ . .... .... . ....... ....... ...... .... .. ........ I8 L
4.5 Reporting Levels for Radioactivity Concentrations in Environmental S amples ................. ............ ......................... ....... 19 5.1 Environmental Radiological Program Summary ......... ... .............. 26 i
i l 5.2 Environmental TLD Data Summary ....................................... ....... 39 5.3 Environmental Ti.D Measurements ....................................... ... ... 40 l
7.1 Environmental Process Control Analysis Results ......... ............... . 75 l
l 7.2 EPA Intercomparison Program Results ...................... .. ......... ...... 76 1
i l 7.3 DESEL 1997 Analytics Cross-Check Results .............................. . 78 i-r 7.4 ' Summary of Blind Duplicate Samples Submitted .......................... 82 1
- j. 8.1 1997 Land Use Census Locations .................................................. 84 o.
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i LIST OF FIGURES Figure Title Page l
4.1 Radiological Environmental Sampling Locations Within 1 Kilometer of Maine Yankee ............................................... 20
~ 4.2 Radiological Environmental Sampling Locations Outside 1 Kilometer of Maine Yankee............................................... 21 o <
t 4.3 Direct Radiation Monitoring Locations Within i Kilometers of Maine Yankee ......................... ................. .. 22 4.4 Direct Radiation Monitoring Locations Outside 1 Kilometer of Maine Yankee ................. ........................... 23 1 6.1 Gross-Beta Measurements on Air Particulate Filters ................. ....... 48 l (Quarterly Average Concentrations) i 6.2 Gross-Beta Measurements on Air Particulate Filters ......................... 49 l
(AP-11 vs. AP-29 Control) l 6.3 Gross-Beta Measurements on Air Particulate Filters .............. ........ . 50 (AP-13 vs. AP-29 Control) 4 1
I 6.4 Gross-Beta Measurements on Air Particulate Filters ......................... 51 l (AP-14 vs. AP-29 Control)
, 6.5 Gmcs-Beta Measurements on Air Particulate Filters l ( AP- 16 vs. AP-29 Control)... ... .... . .... ..... ....... . . . .. . .. .......... ............. ..... 52 l
l-6.6 . H-3 in Estuary Water WE-12, Plant Outfall................................ ....... 53 l
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6.7 ' Cesium-137 in Shoreline Sediment Station S E- 16, Old Outfall Area ............................ ................ ......... 54 v
LIST OF FIGURES (continued)
Figure Title Pace 6.8 Cesium-137 in Shoreline Sediment S tation S E- 18, Foxbird Island........ ..... ........... ........ ........... ........ 55 6.9 Cesium-137 in Milk, 1997.........................................................56 6.10 Cesium-137 in Milk Annual Average Concentrations... ......... .... . 57 6.11 Strontium-90 in Milk,1997 Quarterly Composites............ ... .... .. 58 6.12 Strontium-90 in Milk Annual Average Concentrations...... ............ 59 6.13 Exposure Rate at Inner Ring , Outer Ring and Centrol TLDs........ 60 6.14 Exposure Rate at Inner Ring TLDs, TL 01 -04 . .. .. .. . . . . . .. . . . . .. . . . . . . . . 61 6.15 Exposure Rate at Inner Ring TLDs, TL05 -0 8 . . .. . .. .. .. . . . . . . .. . .. .. .. ... 62 6.16 Exposure Rate at Inner Ring TLDs, TL 09,10,12,13... ......... .. ..... 63 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 3xposure Rate at Outer Ring TLDs, TL11,20-22 ....... .................. 66 6.20 Exposure Rate at Outer Ring TLDs, TL23-26 ........ .... ................. 67 vi
LIST OF FIGURES (continued)
Figure Title Pace 6.21 Exposure Rate at Outer Ring TLDs, TL 27-30.............................. 68 6.22 Exposure Rate at Outer Ring TLDs, TL 3 1 -3 5 . .. . . .. . . .. . .. . . . . . . . . . . . .. . .. . 69 6.23 Exposure Rate at Control TLDs, TL 3 6-3 8 . ... .. . . .. . .. . . . . . .. . . . . . . . . . .. . . 70 vii
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l17 INTRODUCTION l
1 This report sumriarizes the findings of the Radiological Environmental Monitoring Program (REMP) coi. ducted by Maine Yankee Atomic Power Company in the vicinity of the -
Maine Yankee Nuclear Power Station in Wiscasset, Maine during the calendar year 19E7. It is submitted annually in compliance with Appendix C, item 1 of the Offsite Dose Calculation
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Manual (ODCM) and Technical Specification 5.7.2. The remain' der of this report is organized as follows:
Sedtion 2: Provides an introduction to the br.ckground radioactivity and radiation that is -
detected in the Maine Yankee environs.
. Section 3: Provides a brief description of the Maine Yankee site and its environs.
. Section 4: Provides a description of the overall REMP program design. Included is a 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 1997 monitoring program. The performance of the
- program in meeting ODCM requirements is discussed, and the data acquired during the year are analyzed.
Section 7: Provides an overview of the Quality Assurance programs used at the Duke Engineering and Services Environmental Laboratory. The results of the Laboratory participation in an Interlaboratory Comparison Program required by ODCM section 2.4 are also given.
Section 8: Summarizes the requirements and the results of the 1997 Land Use Census.
Section 9: References I
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- 2. NATURALLY OCCURRING AND MAN-MADE BACKGROUND RADIOACTIVITY
[ Radiation or radioactivity potentially detected in the Maine Yankee environment can be grouped into three categories. The first is " naturally-occurring" radiation and radioactivity.
The second is " man-made" radioactivity from sources other than the Maine Yankee plant.
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The third potential source of radioactivity is due to emissions from the Maine Yankee plant.
For the purposes of the Maine Yankee REMP, the first two categories are classified as
" background" radiation, and are the subject of discussion in this section of the report. The third category is the one that the REMP is designeA to detect and evaluate.
2.1 Naturally Occurring Background Radioactivity Natural radiation and radioactivity in the environment, which provide the major source of
, human radiation exposure, may be subdivided into three separate categories: " primordial
_ radioactivity," "cosmogenic radioactivity" and " cosmic radiation." " Primordial radioactivity" is made up of those radionuclides that were created with the universe and that have a sufficiently long half-life to be still present on the earth. Included in this category are the
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radionuclides that these elements have decayed into. A few of the more imponant 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).
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The second category of naturally-occurring radiation and radioactivity is "cosmogenic p radioactivity." This is produced through the nuclear interaction of high energy cosmic L
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 canh'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
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the one most readily detected, and is found on air sampling filters and occasionally in biological media (Reference 2).
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 l
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 I 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 l 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" radioaciivity in the Maine Yankee environment is from " man-made" sources not related to the power plant. The most recent contributor to this l
category was the fallout from the Chernobyl accident in April of 1986, which was detected in the Maine Yankee environment and other parts of the world. A much greater contributor to I 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 l Kingdom, China and France, with the large majority of testing occurring during the periods 1954-1958 and 1961-1962. (A test ban treaty was signed in 1963 by the United States, Soviet Union and United Kingdom, but not by France and China.) Atmospheric testing was conducted by the People's Republic of China as recently as October 1980. Much of the fallout detected today is due to this explosion and the last large scale one, done in November of 1976 (Reference 3).
The radioactivity produced by these detonations was deposited worldwide. The amount of fallout deposited in any given area is dependent on many factors, such as the explosive yield of the device, the latitude and altitude of the detonation, the season in which it occurred, and the timing of subsequent rainfall which washes fallout from the troposphere (Reference 4).
Most of this fallout has decayed into stable elements, but the residual radioactivity is still detectable at low levels in environmental samples worldwide. The two predominant radionuclides are Cesium-137 (Cs-137) and Strontium-90 (Sr-90). They are found in soil and in vegetation, and since cows and goats graze large areas of vegetation, these radionuclides are also readily detected in milk.
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Other potential ." man-made" sources of environmental " background" radioactivity include other nuclear power plants, coal-fired power plants, national defense installations, hospitals, research laboratories and industry. These collectively are insignificant on a global scale when
(. compared to the sources discussed above (natural and fallout).
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- 3. GENERAL PLANT AND SITE INFORMATION 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.
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 tida! 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 voluntarily shutdown in >ecember 1996 and remained shutdown during 1997. In August 1997 the decision was made to permanently cease power operation after 24 years of operation . The plant has 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 Depanment of Human Services.
The radiological environmental monitoring program for Maine Yankee continued to operate during 1997 and will continue throughout the decommissioning period.
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- 4. PROGRAM DESIGN The Radiological Environmental Monitoring Program (REMP) for the Maine Yankee Nuclear Power Station was designed with specific objectives in mind. These are:
To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the operation of the station.
= - To provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits.
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 Yankee site.
The program was initiated in 1970, approximately two years before the plant begra commercial operation in 1972. It has been in operation continuously since that time, with improvements made periodically over those years. .
Prior to January 1992, the requirements for the Radiological Environmental Monitoring Program (REMP) were 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 Technical Specification 5.6.2.b. The detailed sampling requirements of the REMP are given in Table 2.3 of ODCM Section 2.4. This table is ~
summarized in this report as Table 4.1.
The required sampling locations are identified in Chapter 5 of the ODCM. The locations actually monitored in 1997 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 in the ODCM, as well as any regularly sampled locations. Sampling sites that were 6
used on only one occasion during 1997 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). These more accurate values are now reflected in Table 4.2 and do not represent a change in location from previous years.
4.1 Monitoring Zones The REMP is designed to allow comparison oflevels of radioactivity in samples from the area possibly infiuenced 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 facors, 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, waterborne, and ingestion pathways. Each of these four categories is monitored by the collection of one or more sample media, which are listed below, and are described in more detail in this section:
Airborne Pathway Air Particulate Sampling Charcoal Cartridge (Radioiodine) Sampling Mixed Grass Sampling (for airbome deposition)
Waterbome Pathways Estuary Water Sampling Ground Water Sampling Shoreline Sediment Sampling Marine Algae Sampling 7
I Il Ingestion Pathways Milk Sampling Fish and Invertebrate Sampling f.-
Direct Radiation Pathway TLD Monitoring - J !
4.3 Descriptions of Monitoring Programs 4.3.1 - AirSampling 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 nun glass-fiber filter.
' A' dry-gas meter is incorporated in the sampling stream to measure the total amount of air sampled m a given mterval.- The entire air sampjing system is housed in a weatherproof structure. The filters are collected weekly and are initially screened at the Maine Yankee .
Environmental Services Laboratory with a Geiger Mueller-based " beta counter." To allow for the decay of radon daughter products, they are then held for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> at the Duke Engineering and Services Environmental Laboratory (DESEL) before being analyzed for gross beta radioactivity. The weekly filters are composited by location at the Laboratory for a quarterly' gamma spectroscopy analysis.
4.3.2 Charcoal Cartridge (Radiolodine) Sampling c- 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 dry-gas meter is incorporated in the sampling stream to measure the total amount of air sampled in a given interval. The entire air sampling system is housed . 2 weatherproof structure.
- ThE filters are collected weekly and are initially screened at the Maine Yankee Envirmimental Services Laboratory with an Eberline Model RM-14 monitor with an HP-210 GM probd. The filters are shipped to the DESEL for an I-131 specific gamma isotopic J analysis.
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4.3.3 Mixed Grass Sampling Although there is no ODCM requirement for mixed grass or vegetation sampling, a sample is collected from an on-site location twice during the growing season. To collect this ii sarnple, all grass is cut to a height of one inch above ground level from a 4 square-meter plot. 9 The grass is shipped to the DESEL, where it is analyzed for gamma-emitting radionuclides.
4.3.4 Estuary Water Sampling An antomatic compositing sampler is located at the discharge forebay to monitor water discharged to the Back River. (In-plant systems monitor water prial to release to the discharge forebay.) The sampler is controlled by a timer that collects an aliauot 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 laboratory 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 ibe Environmental Services Laboratory. Al; estuary water samples are preserved with hcl and NaHSO to 3 prevent the plate out of radionucEdes on the container wahs. Each monthly composite or grab sample is analyzed for gamma-emitting radionuclides. These are composited again by location at the Laboratory for a quarterly H-3 analysis.
4.3.5 Ground Water Sampling Due to the hydraulic gradient at the Maine Yankee site, whereby the grour,d water flow is 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 quanerly from the one on-site location and one control location. All ground water samples are preserved with hcl and NaHSO3 to prevent the plate out of radionuclides on the container walls. Each sample is analyzed for gamma-emitting radionuclides and H-3.
4.3.6 Sediment Sampling Shoreline sediment cores are collected semiannually from two locations on Bailey Point.
At each location, six 5 cm I.D. plastic coring tubes are driven into the sediment to s 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 9
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and 1015 cm segments. These composite samples are then analyzed for gamma-emitting radionuclides.
[ 43.7 Marine Algae Sampling Mixed samples of Fucus and Ascophyllum marine algae are collected at least semiannually l
. 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 i
Milk samples are collected on a monthly schedule from three locations. Two locations are chosen as a result of the annual Land ilse Census, based on a hypothetical potential dose commitment. The third location is a control, which is located sufficiently far away from the f plant to be outside any potential influence from it.
Samples of milk are chilled after collection and shipped to the DESEL on ice.
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' 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 purification, an I-131 analysis is performed to meet the Lower Limit of Detection (LLD) specified in the ODCM. Although not required by the ODCM, Sr-89 and Sr-90 analyses are also perfornmd on quarterly composited samples.
43.9 Fish and Invertebrate Sampling l Samples of commercially important fish and invertebrates are collected two tinies seasonally at two locations (near the plant discharge and at a control location on the Sheepscot
- l. 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 DESEL, where the edible portions are analyzed for gamma-emitting 4
radionuclides.
i 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 1997, 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 10
samples are not required by Maine Yankee ODCM.
i 4.3.10 TLD Monitoring _
Direct gamma radiation exposure was continuously monitored with the use of thermoluminescent dosimeters (TLDs). Specifically, Panasonic UD-801 AS' and UD-814ASI calcium sulfate dosimeters were used, with a total of five elements in place at each monitoring location. Each pair of dosimeters is sealed in a plastic bag, which is in turn housed in a plastic-screened container. This container is attached to an object such as a tree, fence or utility pole. The plant staff posts and retrieves all TLDs quarterly. All TLDs are processed at the 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.
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Radiological Environmental Monitoring Locations (non TLD) in 1997 Maine Yankee Nuclear Power Station Distance Direction Station From Plaat From Exposure Pathway Code Station Description Zgag* (km) Plant
- l. ' Airborne
- a. AirParticulate AP/CF-11 Montsweag Brook 1 2.7 NW-
& Charcoal Filters AP/CF 13 Bailey Farm (ESL) 1 0.7 NE AP/CF-14 Mason Steam Station .1 4.8 NNE
{- AP/CF-16 Westport Firehouse 1 1.8 S 1: '
AP/CF 29 Dresden Substation 2 20.1 N
- b. Mixed Grasses TG 11 Bailey Farm (ESL) 1 0.7 NE
- 2. Waterbome
- a. Surface. Water WE-12 Plant Outfall 1 0.3 SSW j (Composite Sample)
]' WE-20 Kennebec River 2 9.5 WSW (Grab Sample)
- b. Ground Water WG 13 Bailey Farm (ESL) 1 0.7 NE WG-24 Morse Well 2 9.9 W
- 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
- 3. Ingestion -
- a. Milk TM 15 Mitman Farm 1 5.5 S TM-18 Chewonki Foundation 1 1.9 WSW i TM-25 Hanson Farm 2 18.3 W
' ESL = Environmental Services Laboratory
( 14
[-
[_ TABLE 4.2 (continued)
Radiological Environmental Monitaring Locations (non-TLD) in 1997
[
Maine Yankee Nuclear Power Station
[
Distance Direction Station From Plant From Exposure Pathway '
- Cgde. Station Description . ZQnc am) EJanL
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- 3. Ingestion, continued FH 11 Long Ledge Area 1 0.9 S
- b. Fish & M U-Il
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- 'l = Indicator Stations; 2 = Control Stations
- , MA = Soft-Shell Clams (Mya arenaria).
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TABLE 4.3 Radiological Environmental Monitoring Locations (TLD) in 1997 -
Maine Yankee Nuclear Power Station Distance Station From Plant Direction Code Station Description ZQng (km) From Plant
. TL-1 Old Ferry Rd. I 0.9' N TL-2 Old Feny Rd. I 0.8 NhT TL-3 Bailey House (ESL) I 0.7 NE TL-4 Wes port Island, Rt.144 I 1.3 ENE TL-5 MY Information Center - I 0.2 ENE TL-6 Rt.144 & Greenleaf Rd. I 1.0 E L7 Westpon Island, Rt.144 I 0.9- ESE I
TL-8 MY Screenhouse I 0.2 ESE TL-9 Westpon Siren I 0.8 SE L 10 Bailey Point I 0.3 SSE L 11 Mason Station O 4.8 NNE TL 12 Westport Firehouse I 1.7 S L 13 Foxbird Island I 0.3 SSW L 14 Eaton Farm I 0.7 SW TL-15 Eaton Farm I 0.8 WSW TL-16 Eaton Farm I 0.7 W L I7 Eaton Fann 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 Sr., Wiscasset O 7.1 NNE L 22 Cocivan Rd., Edgecomb O 8.3 NE TL-23 Middle Rd., Edgecomb O 6.4 ENE TL-24 River Rd., Edgecomb O 7.8 E TL-25 River Rd. & Rt. 27 0 7.7 ESE TL-26 Rt. 27 & Boothbay RR Museum O 7.9 SE L 27 Barters Island O 7.2 SSE TL-28 Westpon Island, Rt.144 & E. Shore O 7.9 S Rd.
TL-29 Harrison's Trailer O 6.2 SSW L30 Leeman Farm, Woolwich O 7.8 SW 16 N
l l
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TABLE 4.3 (continued)
Radiological Environmental Monitoring Locations (TLD) In 1997 Maine Yankee Nuclear Power Station t
h Distance p
Station From Plant Direction Code Station Description Zont (km) From Plant TL-31 Barley Neck F O 6.8 WSW TL-32 Baker Farm, W . O 7.3 W I Rt.127, Woolwi...
TL-33 O 7.4 WNW TL-34 Rt.127. Woolwich O 7.9 NW TL-35 Rt.127, Dresden O 9.1 NNW I TL-36 TL-37 Boothbay Harbor Fire Station Bath Fire Station 2
2 12.2 10.7 SSE WSW TL-38 Dresden Substation 2 20.1 N
- . I = Inner Ring TLD: O = Outer Ring TLD; 2 = Control TLD. 1 a ' TL-1 was moved 40 meters from the 1996 location to place it more centrally in the North Sector.
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- 5. RADIOLOGICAL DATA
SUMMARY
TABLES This section summarizes the analytical results of the enviioiimental samples which were collected during 1997. These results, shown in Table 5.1, ere prescated in a format similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). The results are ordered by sample media type and then by radionuclide. The units for each media type are also given. i The left-most column contains the radionuclide ofinterest, the total number of analyses for that radionuclide in 1997, 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 l 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 i 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 I stations, which are within the range ofinfluence 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 1997 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 ( I
/ l d
)t The number of detectable measurements divided by the total number of measurements. For example, (4/20) would indicate that 4 of the 20 samples ; j collected in 1997, for that sample type and that radionuclide, contained detectable radioactivity.
A sample is considered to yield a " detectable measurement" when the concentration exceeds three times its associated standard deviation. The standard deviation on each - 1
)
measurement represents only the random uncertainty associated with the radioactive decay
]
process (counting statistics), and not the propagation of all possible uncenainties in the j analytical procedure.
]
The radionuclides reponed in this section represent those that: 1) had an LLD requirement
]
in Table 2.4 of the ODCM, or a Reporting level listed in Table 2.5, or 2) had a positive measurement of radioactivity, whether it was naturally-occurring or man-made; or 3) were of i specific interest for any other reason. The radionuclides routinely analyzed and reported by the DESEL for a gamma spectroscopy analysis are: Th-232, Ag-110m, Ba-140, Be-7, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59, I-131. I-133, K-40, Mn-54, Mo-99, Np-239, Ru-103, Ru-106, Sb-124, Se-75, Te-I-132, Zn-65 and Zr-95. In no case did a radionuclide not shown in Table 5.1 appear as a " detectable measurement" during 1997. j' ' Data from direct radiation measurements made by TLDs are provided in Table 5.2 in a J format essentially the same as above. The complete listing of quarterly TLD data is provided - ) in Table 5.3. t i l 25
l\- Radiological Environ Pr am Summary i Maine Yankee Nuclear Power Station, Wiscosset, ME ' (January. December 1997) umDM Air Particulatas (AP) UNITS: oCl/caab!c matar l
!atca.PI.sta,i,9,s , ,s,iatio9, m sia3pg ,y,3an
,, . , , ,, C=po,i,stap,n.,,,,
Radionucides* Mean Sta. Mean Mean (No, Analysas) Required Range Range Range. (Nort Routine") LLD (No. Detected *") (No. Detected"*) (No. Detected"*) , I GR-8 (200) 0.01 2.2E -2 29 2.3E 2.3E -2 I (0) - ( 9.4 - 37.7)E -3 ( .1.2 - 4.4)E -2 ( 1.2 - 4.4)E -2 (200/ 20s) (52/ 52) (52/ 52) , l Be-7 (20) 9.5E -2' 13 1.05 -1 1.0E -1 ' p) ( 5.0 r14.0)E -2 ( 7.5 - 14.0)E -2 ( 6.4 - 14.6)E -2 (16/ 16) (4/ 4) (4/ 4) j i Mn (20) -e.05 -5 13 2.6E -5 -9.3E -5 l p) ( -4.7 - 2.4)E -4 ( -3.s - 2.4)E -4 ( -4.7 - 2.6)E -4 ) (0/ 16) (0/ 4) (0/ 4) Co 68 (20) -3.3E -5 13 4.1E -4 -2.sE -4 p) ( -6.4 - 6.s)E -4 ( 2.6 - 6.s)E -4 ( -4.0 - -1.6)E -4 (0/ 16) (0/ 4) (0/ 4) i Fe 69 (20) -1.2E -3 13 -e.1E -5 -2.9E -4 p) ( -5.6 - 1.3)E -3 ( -1.5 - 1.2)E -3 ( -2.9 - 1.3)E -3 (0/ 16) (0/ 4) (0/ 4) Co 60 (20) 1.7E -4 16 2.9E -4 2.2E -4 p) ( -3.5 - 6.6)E -4 ( 1.2 - 6.6)E -4 ( 0.0 - 3.7)E -4 (0/ 16) (0/ 4) (0/ 4) Cs-134 (20) 0.05 1.6E -5 13 6.1E -5 -2.0E ~4 p) ( -3.9 - 3.7)E -4 ( -3.2 - 3.3)E -4 ( -4.2 - 1.4)E -4 (0/ 16) (0/ 4) (0/ 4) Cs-137 (20) 0.06 0.0E o 14 s.5E -5 -2.1E'-4 i (0) ( -3.6 - 3.6)E -4 ( -1.5 - 2.3)E -4 ( -4.1 - 0.6)E -4 (0/ 16) (0/ 4) (0/ 4) I 26
~
Table 5.1 Radiological Environmental Program Summary - Maine Yankee Nuclear Power Station, Wiecasset, ME (January - Decembv 1997) - MEQlUM. CharcoalCartridae ICF) UNITS: oCl/ cubic meter
!ad.'.c*!5.s,ta,tjon, ,, ta y,on wg, Hig
,s,, es
, ,g,,,t,,y,gan, p,on,ty,ol,S, tag,o,ns,,,, i Radionuclides
- Mear. Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine") LLD (No. Detected *") (No. Detected *") (No. Detected *")
1-131 (260) 0.07 -5.es -4 11 1.0E -3 -1.3s -3 (0) ( -2.5 - 2.21s -2 ( -1.9 - 1.7)s -2 ( -2.2 - 1.3)s -2 (0/ 20s) (0/ 52) (0/ 52) I 27
L [- Table 5.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station, Wiscasset, ME (January. December 1997) MggUM: Mixed Grass (TG) UNITS: oCl/ka
!adic*E.S.ta.'.T.5.. .s,tatipnyg,sisy,7,st,ugan
, , , , go,tfqi,s,ta,p.o,n..,
Radionuclides
- Mean sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine") LLD (No. Detected"*) (No. Detected *") (No. Detected ***)
Be-7 (2) 1.55 3 - 11 1.5E 3 No DATA (0) ( 2.0 - 28.3)E 2 ( 2.0 - 28.3)E 2 (2/ 2) (2/ 2) K-40 (2) 5.7E 3 11 5.75 3 No DATA (0) ( 5.6 - 5.7)E 3 ( 5.6 - 5.7)E 3 (2/ 2) (2/ 2). 1-131 (2) 1.as 0 11 1.es 0 No DATA (0) ( -6.1 - 9.6)E O ( -6.1 - 9.6)E O (0/ 2) (0/ 2) Cs-134 (.* f 6.5E O 11 6.5E 0 .No DATA (0) 4 2.7 - 10.4)E 0 ( 2.7 - 10.4)E O (0/ 2) (0/ 2) Cs 137 (2) -1.3E O 11 -1.3E 0 No DATA (0) ( -3.3 - 0.7)E 0 ( -3.3 - 0.7)E 0 (0/ 2) (0/ 2) { [ [ [ [ 28 [ 5
Table 5.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station, Wiscasset. ME (January. December 1997) MEDIUM: Estuarv Water (WE) UNITS: oCl/kg
.IY.I.ca,t,g,S,ta,g,n,s,, ,,Sta p,on Wjg,y,ighest Mean
, ,, C,ontrol S,tations , ,
Radionuclides
- Mean Sta. Mean Mean (No. Analyses) Required Range Rango Range (Non-Routine") LLD (No. Detected"*) (No. Detected"*) (No. Detected"*)
H4 (8) 2000 1.2E 3 12 1.25 3 1.3E 2 (0) ( 3.3 - 20.5)E 2 ( 3.3 - 20.5)E 2 ( -8.0 - 27.8)E 1 (3/ 4) (3/ 4) (0/ 4) K-40 (24) 2.2E 2 12 2.2E 2 3.85 1 I (0) ( 1.2 - 2.7)E 2 (12/ 12) ( 1.2 - 2.7)E 2 (12/ 12) ( -4.7 - 110.3)E 0 (4/ 12) Mn-54 (24) 15 -e.4E -2 20 -1.9E -2 -1.9E -2 I (0) ( -1.3 - 1.1)E o (0/ 12) ( -1.3 - 1.9)E o (0/ 12) ( -1.3 - 1.9)E 0 (0/ 12) Co 58 (24) is -4.4E -1 20 -4.1E -1 -4.1E -1 I (0) ( -2.2 - 1.8)E o (0/ 12) ( -1.4 - 0.3)E o (0/ 12) ( -1.4 - 0.3)E O (0/ 12) Fe-59 (24) 30 2.0E -1 20 7.9E -1 7.9E -1 I (0) ( -3.6 - 5.3)E O (0/ 12) ( -2.7 - 4.2)E O (0/ 12) ( -2.7 - 4.2)E 0 (0/ 12) Co40 (24) 15 1.2E -1 20 3.2E -1 I 3.2E -1 (0) ( -e.8 - 15.4)E -1 ( -8.3 - 14.2)E -1 ( -8.3 - 14.2)E -1 (0/ 12) (0/ 12) (0/ 12) Zn45 (24) 30 -3.5E -1 20 9.6E -1 9.6E -1 I (0) ( -5.8 - e.7)E 0 (0/ 12) ( -2.s - 12.4)E 0 (0/ 12) ( -2.s - 12.4)E o (0/ 12) Zr-95 15 I (24) 5.6E -1 20 5.9E -1 5.9E -1 (0) ( -9.3 - 33.7)E -1 ( -1.3 - 2.6)E O ( -1.3 - 2.6)E O (0/ 12) (0/ 12) (0/ 12) l131 1.1E o I (24) 15 12 1.1E O -9.4E -1 (0) ( -3.5 - 7.1)E 0 ( -3.5 - 7.1)E O ( -5.8 - 3.2)E O (0/ 12) (0/ 12) (0/ 12) 15 1E Cs-134 (24) 9.4E -2 12 9.4E -2 -1.5E -1 (0) ( -1.2 - 2.0)E O ( -1.2 - 2.0)E O ( -1.0 - 1.4)E O (0/ 12) (0/ 12) (0/ 12) Cs 137 (24) is 3.7E -1 12 3.7E -1 -1.0E ~1 [ (0) ( -5.4 - 18.2)E -1 (0/ 12) ( -5.4 - 1s.2)E -1 (0/ 12) ( -1.4 - 1.5)E o (0/ 12) Ba-140 (24) 15 -8.6E -1 20 -7.0E -1 -7.0E -1 (0) ( -5.0 - 3.0)E O ( -2.4 - 2.5)E 0 ( -2.4 - 2.5)E O (0/ 12) (0/ 12) (0/ 12) F 29 4 -
f l- Table 5.1 ( Radiological Environmental Program Summary Maine Yankee Nuclear Power Station, Wiscasset, ME l (January - December 1997) . ! I MEDIUM. Ground Water (WG) UNITS: oCygg Id.Y.0.'. .Y.I ".s,,
. ,S,y,ig,g,y, igg,est,,y,ean,
, , ,, , g,onk,o,1,p,go,ns,, ,
j Radionuclides
- Msan Sta. Mean Mean
]
(No. Analyses) Required Range Range Range (Non-Routine") LLD
]
l-(No. Detected"*) (No. Detected *") (No. Detected"*) H4 (8) 1.25 2 13 1.as 2 -s.0 1 l (0) ( 0.0 - 2.s) 2 ( 0.0 - 2.s)E 2 ( -1.s - 0.s)E 2 l (0/ 4) (0/ 4) (0/ 4) Mn44 (8) -7.2s -1 24 4.25 -1 4.2s -1 (0) ( -1.7 - -0.1)s 0 ( -3.6 - 14.4)s -1 ( -3.s - 14.4) -1 l (0/ 4) (0/ 4) (0/ 4) Co-54 (8) 3.ss -1 13 3.ss -1 -1.sE -1 l ( -1.5 - 1.7)E 0 (0) ( -1.5 - 1.7)E O ( -6.1 - 1.s)E -1 (0/ 4) (0/ 6) (0/ 4) i Fe49 (8) -3.7E O 24 -7.es -1 -7.sE ! (0) ( -1.1 - 0.5) 1 ( -4.1 - 2.5)E o ( -4.1 - 2.s) 0 (0/ 4) (0/ 4) (0/ 4) j Co40 (8) 1.sa 0 13 1.es 0 7.9s -1 i (0) ( 3.0 - 44.1)E -1 ( 3.0 - 44.1)E -1 ( -2.3 - 120.3): -2 I (0/ 4) (0/ 4) (0/ 4) Zn45 (8) 3.2E O 24 s sz o s.ss 0 (0) ( -2.s - 12.4): 0 ( -s.0 - 147.7)c -1 ( -s.O - 147.7): -1 (0/ 4) (0/ 4) (0/ 4) Zr 95 (8) 1.1E O 13 1.1E o 6.es -1 (0) ( -1.1 - 3.3)E 0 ( -1.1 - 3.3)E O ( -1.3 - 1.9)E 0 (0/ 4) (0/ 4) (0/ 4) 6-131 (8) s.4E -1 13 s.4E -1 -5.7E -1 (0)- ( -1.5 - 2.s)s 0 ( -1.s - 2.s)E O ( -1.5 - 0.4)E o (0/ 4) (0/ 4) (0/ 4) l Co-134 (8) -1.1E -1 24 1.sE -1 1.ss -1 (0) ( -e.3 - 6.5)s -1 ( -5.3 - 12.9) -1 ( -5.3 - 12.9)E -1 (0/ 4) (0/ 4) (0/ 4) Cs-137 (8) -1.sE O 24 -4.ss -1 -4.es -1 (0) ( -2.9 - 0.3): 0 ( -9.2 - 1.0)E -1 ( -9.2 - 1.0): -1 (0/ 4) (0/ 4) (0/ 4) Ba-140 (8) 2.sz -1 13 2.ss -1 -1.9s -1 (0) ( -3.6 - 2.5)E o ( -3.s - 2.5)E o ( -1.s - 0.5)E 0 (0/ 4) (0/ 4) (0/ 4) 30 l [
)
Table 6.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station. Wiscasset, ME (January December 1997) MEDIUM. Sediment (SE) UNITS: DC]dg
'."d.'ca.M38.M.S.. S,tauon,, sug, Highest y,ean
,,, ,, ,, g,ont,m,1,St,a,tio,ns,,,,
Radionuclides
- Mean Sta. Mean Mean
-(No. Analyses) Required R ege Range Range (Non-Routine") LLD (No. Detected"*) (No. Detected *") (No. Detected"*)
Be-7 (12) 1.6E 2 16 1.6E 2 No DATA (0) ( -1.4 - 6.2)E 2 ( -2.6 - 62.2)E 1 (1/ 12) (1/ 6) K-40 (12) 2.1E 4 18 2.2E 4 No DATA (0) ( 1.7 -~2.3)E 4 ( 2.0 - 2.3)E 4 (12/ 12) (6/ 6) Co-68 (12) -7.7E 0 16 2.3E O No DATA (0) ( -6.s - 3.2)E 1 ( -3.9 - 2.5)E 1 (0/ 12) (0/ 6) Co-60 (12) 3.0E 1 16 3.5E 1 No DATA (0) ( -2.0 - 10,5)E 1 ( -1.6 - 7.3)E 1 (0/ 12) (0/ 6) 1 Cs-134 (12) 150 -e.2E O 16 -5.4E o no DATA (0) ( -e.2 - 4.1)E 1 ( -3.3 - 4.1)E 1 (0/ 12) (0/ 6) Cs-137 (12) 180 2.3E 2 16 2.eu 2 No DATA (0) ( 6.4 - 36.4)E 1 ( 1.2 - 3.0)E 2 (10/ 12) (5/ 6) Th-232 (12) s.98 2 18 9.3E 2 No DATA (0) ( 6.2 - 12.5)E 2 ( 7.6 - 12.5)E 2 (12/ 12) (6/ 6) l l 1 31
1 Table 5.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station, Wiscasset, ME (January - December 1997) MEDIUMr Marine Alona (Au UNITS: oCl/km
!a.d.i.c*!o'.S.t*t.5*$..
. . S!*!ioa.59.H,igges{,y,ean
. ,, Co,gg,1,S,ta{ogs,,,,
Radionuclides
- Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine **) LLD (No. Detected ***) (No. Detected ***) (NO. Detected ***)
Be-7 (10) 9.0E 1 11 9.0E 1 NO DATA (0) ( -2.8 - 18.8)E 1 ( -2.8 - 18.8)E 1 (0/ 10) (0/ 10) K 40 (10) 4.5E 3 11 4.5E 3 NO DATA (0) ( 3.6 - 5.9)E 3 ( 3.6 - 5.9)E 3 (10/ 10) (10/ 10) Mn-64 (10) 2.3E -1 11 2.3E -1 NO DATA (0) ( -6.7 - s.7)E 0 ( -6.7 - s.7)E O (0/ 10) -(0/ 10) Co-58 (10) -4.5E 0 11 -4.5E O NO DATA (0) ( -1.6 - 1.3)E 1 ( -1.6 - 1.3)E 1 (0/ 10) (0/ 10) Fe-59 (10) -1.1E 1 11 -1.1E 1 NO DATA (0) - ( -6.5 - 2.3)E 1 ( -6.5 - 2.3)E 1 (0/ 10) (0/ 10) Co-60 (10) 7.6E 0 11 7.6E O No DATA (0) ( -2.3 - 25.1)E O ( -2.3 - 25.1)E O (0/ 10) (0/ 10) Zn 65 (10) -3.1E 1 11 -3.1E 1 NO DATA (0) ( -7.7 - 0.5)E 1 ( -7.7 - 0.5)E 1 (0/ 10) (0/ 10) Ag 110M (10) 4.0E 0 11 4.0E O NO DATA (0) ( -2.s - 2.s)E 1 ( -2.s - 2.s)E 1 (0/ 10) (0/ 10) Sb-124 (10) -3.9E O 11 -3.9E 0 NO DATA (0) ( -2.0 - 0.7)E 1 ( -2.0 - 0.7)E 1 (0/ 10) (0/ 10) Cs-134 (10) 1.0E 0 11 1.0E O NO DATA (0) ( -6.3 - 13.0)E o ( -6.3 - 13.0)E O (0/ 10) (0/ 10) Cs-137 (10) 5.9E O 11 5.9E O NO DATA (0) ( -2.9 - 15.2)E O ( -2.9 - 15.2)E O (0/ 10) (0/ 10) 32 e N
Table 5.1 Radiological Environmental Program Summary Maine Yankee Nuclear Power Station. Wiscasset, ME (January December 1997) MEQiUM: Milk (TM) UNITS: oCl/ko Station With Highest Mean
.In.d.i.c.a.t.o..r.S..t.a.t.io..n.s...
. . . . . . . . . . . . . . . . . . . . . . . . . . . C..o..ntro.l.S.. tat.io.ns...
Radionuclides
- Mean Sta. Mean Mean (No. Analyses) F.equired Range Range Range (Non Routine") LLD (No. Detected"*) (No. Detected"*) (No. Detected"*)
K-40 (32) 1.4E 3 15 1.6E 3 1.3E 3 (0) ( 6.7 - 17.2)E 2 ( 1.4 - 1.7)E 3 ( 1.1 - 1.4)E 3 (20/ 20) (7/ 7) (12/ 12) Sr89 (11) -9.2E -1 18 3.5E -1 3.3E -1 (0) ( -5.7 - 3.0)E O ( -9.0 - 30.0)E -1 ( -1.5 - 2.6)E O (0/ 7) (0/ 4) (0/ 4) Sr-90 (11) 4.1E O 15 5.9E O 2.7E O (0) ( 2.3 - 7.6)E O ( 4.2 - 7.6)E O ( 2.3 - 3.4)E O (7/ 7) (3/ 3) (4/ 4) 1-131 (32) 1 9.7E -3 25 2.3E -2 2.3E -2 (0) ( -4.6 - 14.3)E -2 ( -4.6 - 10.8)E -2 ( -4.6 - 10.8)E -2 (0/ 20) (0/ 12) (0/ 12) Cs 134 (32) 15 2.9E -1 18 3.6E -1 -5.6E -1 (0) ( -1.8 - 4.5)E o ( -1.8 - 4.5)E 0 ( -2.4 - 0.9)E 0 (0/ 20) (0/ 13) (0/ 12) Cs-137 (32) is 7.0E o 15 1.0E 1 1.6E O (0) ( 2.6 - 172.63E -1 ( 5.0 - 17.3)E O ( -2.2 - 4.1)E 0 (11/ 20) (6/ 7) (0/ 12) Ba.140 (32) 15 1.9E -1 18 3.6E -1 -8.5E -1 (0) ( -2.6 - 4.9)E O ( -1.8 - 4.9)E O ( -4.1 - 1.9)E O (0/ 20) (0/ 13) (0/ 12) 33
Table 5.1 Radiological Environmental Program Summary Maine Yanisse Nuclear Power Station. Wiecesset. ME (January. December 1997) . nasrmaat Flah fFH) ' UNITS; nclAm 8 8'*a.".Hga,{,Mu,n,
!a.?ca.RL )*.8=.t Cm,t,ml,St,ay,og,,,,
Radionucedes* Mean Sta. Mean Mean - (No. Analyses) Required Range. Range Range (Non4toutine") LLD (No. Detected ***) (No. Detected ***) (No. Detected ***) Be-7 (4) 3.4E 1 24 5.e5 1 5.sE 1 - (0) ( -5.1 - 11. 9 ) F 1 ( 3.1 - 8.5)'S 1 ( 3.1 - 8.5)E 1 (0/ 2) (0/ 2) .(0/ 2). K-40 (4) 2.8E 3 11 2.8E 3 2.7E 3 (0) ( 2.4 - 3.2)E 3 ( 2.4 - 3.2)E 3 ( 2.2 - 3.2)E 3 (2/ 2) (2/ 2) (2/ 2) Mn-54 (4) 130 -1.4E 1 24 5.3E o 5.3E 0 p) ( -2.3 - -0.5)E 1 ( -3.5 - 14.1)E O ( -3.5 - 14.1)E O , (0/ 2) (0/ 2) (0/ 2) Co-58 (4) 130 3.0E -1 24 2.sE o 2.sE O (0) ( -4.3 - 4.9)E O ( -s.0 - 13.3)E o ( -s.O - 13.3)E O (0/ 2) (0/ 2) (0/ 2) Fe-50 (4) 250' 7.9E o 24 2.1E 1 2.1E 1 (0) ( -1.2 - 2.8)E 1 ( 1.7 - 2.5)E 1 ( 1.7 - 2.5)E 1 (0/ 2) (0/ 2) (0/ 2) Co-00 (4) 130 1.5E 0 11 1.5E O -7.1E 0 (0) ( -1.2 - 1.5)E 1 ( -1.2 - 1.5)E 1 ( -2.7 - 1.2)E 1 (0/ 2) (0/ 2) (0/ 2) Zn 45 (4) 250 -3.9E 1 24 -1.9E 1 -1.9E 1 (0) ( -5.4 - -1.3)E 1 ( -3.2 - -0. 7) E 1 ( -3.2 - -.$.7)E 1 (0/ 2) (0/ 2) ;0/ 2) Ag-110M (4) 3.3E -1 11 -3.3E -1 -7.2E O (0) ( -8.8 - 2.1)E -1 ( -0.8 - 2.1)E ( ~2.3 - 0.9)E 1 (0/ 2) (0/ 2) (0/ 2) Sb-124 - (4) 1.43 1 11 1.43 1 -4.3E 1 p) ( 7.9 - 20.7)E o ( 7.9 - 20.7)E o ( -s.0 - -2.5)E 1 (0/ J) (0/ 2) (0/ 2) Co 134 (4) 130 1.0E 1 11 1.0E 1 8.5E 0 (0) ( 1.5 - 18.8)E o ( 1.5 - 1s 8)E o ( 5.1 - 11.9)E O (0/ 2) (0/ 2) (0/ 2) Cs-137 (4) 150 -1.05 1 24 7.7E -1 7.75 -1 p)' ( -1.9 - -0.2)E 1 ( -4.4 - 5.9)E o ( -4.4 - 5.9)E o (0/ 2) (0/ 2) (0/ 2) 34
' Table 5.1 Radiological Environmental Progrant Summary Meine Yankee Nuclear Power Station. Wiscasset. ME (January. December 1997)
![ usrWUM: I ah=h and Rock Crab (CR) UNITS: nCl/ka
- .In..d.i.c.a.t.o..r.St.a.tio..n.s. .S.t.a.tio.n.
.. Wit.h..H...gh..es.t..M..e.a..n.
. . C. .o. .n.t.r.o.l. S.ta.t.io.n. s. . . .
Radionuclides
- Mean Sts. Mean. Mean (No. Analyses) - Required Range Range Range (Non-Routme") ~LLD ~ (No. Detected *") (No. Detected"*) (No. Detected"*)
Be.7 (8) .7.95 1 11 7.9E 1 -3.7E o (0) '( -3.1 - 19.8)E 1 < -3.1 - 19.s)E i ( -1.1 - 0.6)E 2 l (0/ 4) (0/ 4) (0/ 4) K-40 (8)- 2.2E 3 11 2.25 3 2.iE 3 (0) ( '1.7 - 3.0)E 3 (' 1.7 - 3.0)E 3 ( 1.9 - 2.3)E 3 (4/ 4) (4/ 4) (4/ 4) Mn-54 (8) '130 1.2E O 11 1.2E 0 -7.6E 0 j (0) ( -1.2 - 2.2)E 1 ( -1.2 - 2.2)E 1 ( -1.5 - -0.1)E 1 ! (0/ 4) (0/ 4) (0/ 4) Co-58 (0) 130 -9.0E -1 11 -9.0E -1 -2.9E O (0) ( -1.1 - 1.1)E 1 ( -1.1 - 1.1)E 1 ( -1.9 - 0.7)E i (0/ 4) (0/ 4) (0/ 4) Fe.59 (8) 260 1.0E 1 11 1. 05 1 2.9E O (0) ( -1.0 - 3.0)E 1 ( -1.8 - 3.0)E 1 ( -1.6 - 1.9)E 1 (0/ 4) (0/ 4) (0/ 4) Co60 (8) 130 1.1E 1 11 - 1.1E 1 4.2E O
-(0) ( -1.4 - 4.6)E 1 ( -1.4 - 4.6)E 1 ( -4.6 - 19.4)E O (0/ 4) (0/ 4) (0/ 4)
Zn45 (8) 260 -1.7E 1 11 -1.7E 1 -1.sE 1 (0) ( -3.4 - 1.3)E 1 ( -3.4 - 1.3)E 1 ( -3.5 - -0.5)E 1 l (0/ 4) (0/ 4) (0/ 4) Ag.110M (8) 6.5E o 24 1. 4 E 1 - 1.4E 1 (0) ( -1.3 - 3.3)E 1 ( 1.9 - 25.3)E 0 ( 1.9 - 25.3)E 0 (0/ 4) (0/ 4) (0/ 4) Sb.124 -(8) -!,.75 1 24 6.sE o 6.sE o (0) ('-5.1 - 1.7)E 1 ( -1.6 - 4.8)E 1 ( -1.6 - 4.0)E 1 (0/ 4) (0/ 4) (0/ 4) Cs.134 (8) 130 -3.4E o 24 1.3E O 1.3E O (0) ( -1.6 - 0.6)E 1 ( -8.9 - 18.4)E O ( -e.9 - 18.4)E O (0/ 4) (0/ 4) (0/ 4) Co.137 - (8) 150 -9.4E 0 24 -1.1E 0 -1.1E 0
'- ( -1.s - -0.2)E 1 ( -2.7 - 2.3)E i ( -2.7 - 2.3)E 1 (0)
(0/ 4) (0/ 4) (0/ 4) 35 l
l l l l l Table 5.1 l l- Radiological Environmental Program Summary j Maine Yankee Nuclear Power Station, Wiscasset, ME .j (January December 1997) ,
. MEDIUM: Mussel (MU) - UNITS: nCl/ka
'ai8.Tf.M.s,9,nen,s,,
. ,s,tauon g,y,i93est,yeen
, , 9,ontf,o,i,s,tatons ,,,
Radionuclides
- Mean . Sta. Mean Mean (No. Analyses) - Required Range. Range Range
- (Non-Roubne") LLD- (No. Detected *") . (No. Detected *") (No. Detected *")
1 Be-7 (4) -1.ps 1 24 1.55 1 1.5E 1 (0) ( -5.1 - 1.2)E 1. ( 1.1 - 1.9)E 1 ( 1.1 - 1.9)E 1 (0/ 2) (0/.2) (0/ 2) K-40 (4) 1.2s 3 11 1.2s 3 7.3s 2 (0) ( s.0 - 14.0)E 2 ( p.0 - 14.0)E 2 ( 5.3 - 9.4)E 2 j (2/ 2) (2/.2) (1/ 2) ; Mn44 (4) 130 -1.3s 0 24 -3.7s -1 -3.7s -1 (0) ( -2.0 - -0.6)s 0 ( -5.2 - 4.5)E o ( -5.2 - 4.5)E O (0/ 2) (0/ 2) (0/ 2) Co-58 (4) 130 -6,7s 0 24 -3.2E O - -3.2E 0 (0) ( -1.s - 0.5)E 1 ( -2.1 - 1.5)E 1 ( -2.1 - 1.5): 1 (0/ 2) (0/ 2) (0/ 2) Fe-69 (4) 260 1.0E 0 11 1.Os 0 -1.ss 1 (0) ( -3.s - 5.9)s 0 ( -3.9 - 5.3)E o ( -7.2 - 3.6)E 1 (0/ 2) (0/ 2) (0/ 2) Co40 (4) 130 9.6E 0 11 9.6E O -5.2E 0 (0) ( -1.4 - 3.3)E 1 ( -1.4 - 3.3)E 1 ( -1.0 - 0.0)E 1 (0/ 2) (0/ 2) (0/ 2) Zn46 (4) 260 6.15 0 11 6.1E O . -9.05 0 (0) ( -4.s - 1s.2)s 0 ( -6.9 - 19.2)s 0 ( -9.4 - -s.6): 0 (0/ 2) (0/ 2) (0/ 2) Ag-110M (4) 1.6E 1 11 1.6E 1 -4.75 0 (0) ( 1.2 - 1.3)u 1 ( 1.2 - 1.3)E 1 ( -2.3 - 1.3)E 1 (0/ 2) (0/ 2) (0/ 2) Sb.124 (4) 7.as 0 24 1.7s l' 1.7s 1 (0) ( -3. 5 -. 5. 0 ) E 1 ( -1.2 - 4.7): 1 ( -1.2 - 4.7)E 1 (0/ 2) (0/ 2) (0/ 2)
. Cs.134 (4) 130 1.is 1 11 1.is 1 8.es -1 (0) ( 6.0 - 15.4)E O ( 6.0 - 15.4)E O ( -6.3 - s.1)E 0 (0/ 2) (0/ 2) (0/ 2)
Cs-137 (4) 150 -5.sE o 11 ' -5.ss 0 -9.es 0 (0) ( -1.2 - 0.0): 1 ( -1.2 - 0.0)E 1 ( -1.2 - -0.7)E i (0/ 2) (0/ 2) (0/ 2) 36
'l Table 5.1 j Radiological Environmental Program Summary
]
Maine Yankee Nucioat Power Station, Wiscosset, ME j
' (January. December 1997) .
l ' MEDIUM: Soft Shell Clams (MA) UNITS: oCl/km l I ' 1
' .In..d.i.c.a.t.o..r.S..ta.t.io..n.s...
. S.tatio.n..W...ith Highest Mean
. . . . . . . . . . . . . . . . . . . . . . . C. o..nt.r.o.l.S.t.a.t.io.ns.....
}
q l Radionuclides *. Mean Sta. Mean Mean ' l (No. Analyses) Required Range- Range Range j (Non-Routine") . LLD (No. Detected"*) - (No. Detected *") (No. Detected *") Be 7 (4) 3.05 1 18 1.5E 2 No DATA j (0) ( -1.2 - 1.7)E 2 ( 1.3 - 1.7)E 2 l (0/ 4) < (0/ 2) K4 (4) 1.4E 3 16 1.4E 3 No DATA (0) ( 9.5 - 17.3)E 2 ( 1.1 - 1.7)E 3
-(4/ 4) (2/ 2)
Mn-54 (4) -4.65 0 18 -6.0E -1 No DATA (0) ( -2.4 - 0.7)E 1 ( -1.6 - 0.4)E O (0/ 4) (0/ 2)
-Co48 (4) -5.45 -1 18 1.8E 0 No DATA j (0) ( -1.1 - 0.6)E 1~ ( 1.4 - 2.2)E O (0/ 4) (0/ 2)
- j. Fe49 (4) -4.05 0 18 7.3E 0 No DATA ]
(0) ( -4.9 - 1.s)E 1 ( 1.1 - 13.6)E O ! ! (0/ 4) (0/ 2) j Co40 (4) 1.2E 1 18 1.55 1 No DATA (0) ( 7.3 - 21.5)E o ( 7.7 - 21.6)E O I -(0/ 4) (0/ 2) l ' Zn-65 (4) 2.5E O 16 5.38 0 No DATA (0) ( -1.3 - 1.3)E 1 ( 4.3 - 6.2)E O (0/ 4) t.0/ 2)
- Ag-110M (4) 1.35 1 18 2.05 % No DATA (0) ( 2.2 - 2s.13E 0 ( 1.2 2.8)E 1 (0/ 4) (0/ 2)
Sh t94 (4) 1.3E 1 18 2.35 1 No DATA (0) ( -1.3 - 3.1)E 1 ( 1.6 - 3.1)E 1 (0/ 4) (0/ 2) ! Cs-134 (4) 1.6E o 18 2.5E o No DATA (0) ( -1.1 - 1.3)E 1 ( -7.9 - 12.9)E O (0/ 4) (0/ 2) l- Cs 137 (4) -1.3E 1 18 -8.6E 0 No DATA (0) ( -2.9 - -0.3)E 1 ( -1.4 - -0.3)E 1 (0/ 4) (0/ 2) 37
j (: 3' , 't j Ibotnotes to Table 5.1: q l j
* ~ 1he only radionuclides reported in this table are those with Reporting Level or LLD requirements and those for wNch positive l
radioactivity was detected. See Section 5 of this report for a discussion of othet radionuclides that were analyzed. - 1 I i
" Non-Routine refers in those radionuclides that exceeded the Reporting Levels ln ODCM Table 2.5.
. -j
"* The fraction of sample analyses yielding detectable measurements (i.e. > 3 standard deviations)it shown in parentheses. ,
i
.i i
)
q
> .i 4
f
.f' f
, o 1
,, .l .;
e f
.a I i 38
h , TABIM.2
~
ENVIRONMENTALTLD DATA
SUMMARY
MAINE YANKEE NUCLEAR POWER STATION, WISCASSET. ME
, , (JANUARY DECEMBER 1997) i INNER RING TLDs OUTER RING TLDs STATION WITH HIGHEST MEAN CONTROLTLDs' MEAN 2 S.D.* MEAN
- S.D? MEAN 2 S.D.* ' MEAN
- S.D?
RANGE
- RANGE *- 'STA. RANGE
- RANGE *
(NO. ME UUREMENTS)** (NO. MEASUREMENTS)** NO. (NO. MEASUREMENTS)" ' (NO. MEASUREMENTS)** 7.120,7- 7.520.8 23 9.420.6 8.0 1.0 53*9.2 5.9 10.2 8.8 10.2' 6.7 - 9.5
. (72) , (68) (4) (12)
Units are micro-R per hour. [.. I. ** . Each " measurement
- is based on quanerly readings from six TLD elements.
NOTE: 5.D. = standard deviation. p L { [ [ w- I r 39 I
, i
() TABLE 5J ENVIRONMENTALTLD MEASUREMENTS 4 1997 (Micro.R per Hour) -
' Sta. ' <
' IST QUARTER . 2ND QUARTER 3RD QUARTER 4TH QUARTER ' ANNUAL AVE '
Description - No. : EXP. S.D.' EXP. S.D. EXP.' S.D. EXP. S.D. EXP. S.E. E 01 Old Ferry Rd. 7.1*03 7.5 0.5 8.220.3 7.420.3: 7.6 03 h E 02 Old Ferry Rd. 6.5*03 6.620.4 7.8203 7.120.2- 7.0203
. TL 03 Bailey House (ESL) 6.7
- 0.3 t 6.820.3 7.6 s 0.4 6.8 0.2 7.020.3 TL-04 Westport Ist/Rt.144 53 *03 6.0 0.3 ' 7.420.3 5.8
- 0.4 6.120.6 E03 MYInformationCent. 7.420.4 7.0 0.4 8.020.3 '7.420.3 '7.4 0.2 7320.4-
. E 06 Rt.144Kireenicaf Rd. - 7.620.4 8.220.4 7.520.3 ~ 7.6 0.2 TL.07 : WestportIst/Rt.144 6.6
- 0.4 6.920.4 7.8
- 0.4 7.0 0.2 - 7.120.3 TL-08 MY Screenhouse 6.720.3 6.420.3 7.320.3 7.1 0.7 6.920.2 E09 /Westportist/Rt.144 6.5 t 0.3 7.020.3 8.020.4 7.120.3 7.1 0.4
.. E10 Bailey Pt. 6.6 0.3 6.4 0.4 7.2 03 6.8*03 6.8 0.1 E li Mason Station 7.420.3 8.0
- 0.4 8.420.3 7.7 0.4 7.920.3 E 12 Westport Firchouse 6.7 s 0.3 6.9
- 0.4 - 7.720.4 7.020.4 7.1203 L13 L Foxbird Island 7.820.3 7.720.4 8320.4 7.7203 7.9
- 0.1 ;
, - El4 Eaton Farm 6.1203 6.520.3 7.5
- 0.3 6.620.4 6.7
- 0.4
[ E 15 Eaton Farm 5.720.4 6.020.4 6.6 s 0.2 5.8
- 0.2 6.020.3-L: TL 16 ' Eaton Farsa 6.7
- 0.3 7.120.3 7.8
- 0.3 6.920.2 7.120.3 E l7 Eaton Farm Rd. 8.020.4 8.720.4 9.220.3 8.4 : 0.4 8.5203 L18 ' Eaton Farm Rd. 6.7203 7.120.4, 8.220.6- 7.420.4- 7.320.4
() . E19 Eaton Farm Rd. L 20 Bradford Rd. 6.4 a 0.4 6.420.4 6.5 03 6.8
- 0.3 8.020.4 7.2 0.3 7.4
- 0.3 ' 7.120.4 6.920.5 6.8
- 0.2 L 21 Federal St. 6.8203 6.7
- 0.4 7.320.4 6.620.2 6.8 0.2 L22 Cochran Rd. 6.8
- 0.3 7.020.4 7.9 0.3 6.9203 7.2203 i TI 23 Middle Rd. 8.820.5 9.520.4 10.220.4 9.0 03 9.420.4 E24 River Rd." 7.720.5 7.5 0.3 8.4 z 0.4 - 7.5
- 0.4 7.8 0.2
. E 25 River RdlRt.27 73 a 0.5 7.6 0.4 8.220.4 73 *0.4 7.620.2-TL 26 Boothbay RR Museum 7.720.3 7.420.4 8.0 s 0.4 7.820.3 7.720.1
; E27 Baners Island 7.020.3 7.0 03 7.9 03 7.220.3 7.320.3 TL-28 RL144/E. Shore Rd. - 6.5203 7.020.4 7.620.4 6.8
- 0.4 7.020.3 E 29 Harrison's Trailer 6.720.4
( E 30 Leeman Farm 6.7
- 0.3 -
8.120.5 8.3 a 0.4 7.320.3 8.8 0.4 6.7203 8.120.5 6.9
- 0.2 ~
8320.2 L3I ; Barley Neck Rd. 8.620.4 8.620.4 9.120.4 8.5 t 03 8.720.2
-: ~ E 32 Baker Farm 7.1
- 0.4 8.0 a 0.4 8.5203 8.020.4 7.90.4
[i E 3) ~ Rt.127? 6.520.4 7.2203 7.7* 03 6.9
- 0.4 7.1 0.3
' L34 Rt.127 6.6203 7.0 0.3 7.9203 6.520.4 7.020.4 E 35' Rt.127- 5.9 e 0.3 6.5 0.3 7.8 0.3 6.320.3 6.620.5 L 36 Boothb.Hbr. Fire Sta. 7.220.5 6.720.3 7.120.2 7.7
- 0.4 7.220.2 L37 : Bath Fire Sta. 9.520.4 9.220.4 9.520.5 9.120.4 9.320.1 E38 ' Dresden Substation 7.1 a 0.3 7.320.4 8.420.3 7.520.4 7.6 0.3 NOTE:
EXP = Exposure Rate in microR/hout S.D.'= Standard Deviation: S.E. = Standard Error of the Mean. L 40 L. m
I {-.
- 6. ANALYSIS OF ENVIRONMENTAL RESULTS 6.1 Sampling Program Deviations f
Table 2.3 of the Offsite Dase Calculation Manual (ODCM) allows for deviations in the REMP sampling schedule "if specimens are unobtainable due to hazardous conditions, to seasonal unavailability.or to malfunction of sampling equipment." Such deviations do not compromise the program's effectiveness and in fact are considered insignificant with respect f.. to what is normally anticipated for any radiological environmental monitoring program. The specific deviations for 1997 were as follows: [
= The following short power outages occurred at air sampling stations during 1997:
a) During the week ending Mar. 14,1997 at station AP/CF 11,2 hours, b) During the week ending Mar. 14,1997 at station AP/CF-13,2 hours.
- f. c) During the week ending Mar. 14,1997 at station AP/CF-16, I hour.
d) During the week ending Mar. 14,1997 at station AP/CF-29, I hour. e) During the week ending Apr. 04,1997 at station AP/CF-16, I hour. f) During the week ending Nov. 07,1997 at station AP/CF-11,13.7 hours. g) During the week ending Nov. 07,1997 at station AP/CF-13,3.1 hours
!l h) During the week ending Nov. 07,1997 at station AP/CF-16,13.2 hours I) During the week ending Nov. 07,1997 at station AP/CF-29,2.45 hours I
= Location TM-15 provided samples from April through October during 1997 staning with week 16 (4-15-97) and ending with a sample submitted in week 42 (10-16-97). This is an expected seasonal occurrence and is not considered a program deviation.
{- 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 achievable due to a situation such as a low sample volume caused b 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 . ( 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 41 I s . . .
r ( b L l , . Yankes ODCM. a
)
l 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 1997, { over 1000 analyses had an LLD requirement listed in Table 2.4. All met the required LLD.. 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 Effluent Release Report) whenever a Reporting Level in ODCM Table 2.5 is - exceeded. Reporting Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I. 'It should be noted that environmental concentrations are averaged over calendar quarters fcr the purposes of this comparison, and that Reporting Levels apply only to measured levels of radiot:aivity due to plant effluents.
~ During 1997, no Reporting Levels were exceeded.
6.4 Data Analysis by Media Type
. The'1997 REMP data for each media type is discussed below. Whenever a specific -
measurement result is presented,it is given as the concentration plus or minus one standard
- deviation. This standard deviation represents only the randont uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible
. uncertainties in the analytical procedure. A' sample is consideed to yield a " detectable measurement" when the concentration exceeds three times its associated standard deviation.
With respect to data plots, it should be noted that all values for a given graph are plotted, whether or not they are considered statistically.significant (detectable). 6.4.1 Airborne Pathways 6.4.1.1 : Air Particulates The weekly air particulate filters from each of the five sampling sites were analyzed for gross-beta radioactivity 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, 42 i
l I
As shown in Figure 6.1, there has been no significant difference between the 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 quaner. Figures 6.2 through 6.5 show the weekly gross beta concentration at each air particulate sampling location alongside the control air paniculate sampling location at AP-29 (Dresden Substation) for the same period. It can be readily seen that the gross-beta measurements on air i 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 approximately 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-I occurring cosmogenic radionuclide. 6.4.1.2 Charcoal Cartridges The weekly charcoal cantidges from the five air sampling sites were analyzed for I-131. The results of these analyses are summarized in Table 5.1. In 1997, as in previous years, no I-131 was detected in any charcoal cartridge. 6.4.1.3 Mixed Grasses I Although not required by the Maine Yankee ODCM, mixed grass samples were collected twice at the Bciley Farm during 1997. No radionuclides attributable to Maine Yankee I operations were detected in either sample. Naturally-occurring K-40 and Be-7 were detected in both samples, as expected. 6.4.2 Waterborne Pathways I 6.4.2.1 Estuary Water Aliquots of estuary water were automatically collected in the discharge canal outfall every two hours during 1997. These composited samples were collected monthly and sent to the DESEL l for analysis. Monthly grab samples were also collected at the control location. i e
I 1 1 Table 5.1 shows that naturally-occurring K-40 was detected in samples collected at the WE-12 I (plant outfall), as is typical with estuary water. The monthly samples were composited each quarter, by station, for Tritium (H-3) analyses. Three out of four samples at v.ation WE-12 showed detectable levels of H-3 ranging from 1087
- 286 pCi/kg to 2050
- 301 pCi/kg with a mean concentration of 1200 pCi/kg. Figure 6.6 provides a trend plot for quarterly 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 I as defmed 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 l the discharge forebay, prior to release to the Back River via the underwater diffusers. The resulting environmental H-3 concentration of 205 pCi/kg for the composite sample may be compared to the NRC Reporting Level for H-3 for the non-drinking water pathway of 30,000 I pCi/kg. The Maine Yankee ODCM would require notification to the NRC in the Annual Radioactive Efiluent Release Report if this Reporting Level had been exceeded. The increase in the H-3 concentration in the forebay water from previous years is attributed to the reduction in dilution water flow without the circulating water pumps operating.
I 6.4.2.2 Ground Water Although not required by the Maine Yankee ODCM, quarterly ground water amples were collected from the well at the Environmental Services building and at a control location. The l results of the gamma isotopic and H-3 analyses are shown in Table 5.1. None of these off site samples contained detectable radioactivity. 6.4.2.3 Shoreline Sediment Semiannual sediment core samples were collected from two on-site locations during 1997. 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 occurring K-40 and Th-232 was detected in all samples and Be-7 in one out of twelve samples. I In addition, Cs-137 was detected in ten 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 efiluents were
[ discharged in the sediment collection area. Due to poor diffusion with this method, an underwater diffuser was installed, and now the liquid effluents are discharged into the Back [ . 44 +
L River. The Cs-137 levels in each sediment core section are plotted in Figures 6.7 and 6.8. [ These graphs dow a range of Cs-137 concentrations across core sections. ;The mean ! concentration for~ 1997 increased slightly but is bounded by mean concentrations previously. reported (mean concentration during 1990 to 1996 ranged from-170 to 300 pCi/kg) and shows that the levels have not changed significantly over the past several years. 1
- i. I Although there is no Reporting Level for Cs-137 in sediment samples, one might appreciate
- the negligible dosimetdc consequence when the measured concentrations are conservatively
' ~ compared against the reporting levels for the fish ingestion pathway. The mean and maximum Cs-137 measurements were 230 and 364 pCi/kg (dry), respectively, both under the Cs-137 Reporting Level in tish of 2000 pCi/kg. 6.4.2A Marine Algae Although not required by the Maine Yankee ODCM, mixed samples of Fucus and Ascophyllum marine algae (seaweed) were collected at Long Ledge each month starting in
' March and continuing through December 1997. All ten samples were analyzed for gamma-emitting radionuclides. As expected, naturally-occurring K-40 was detected on all samples. j No other gamma emitting radionuclides were detected in any of the samples. I 6.4.3 Ingestion Pathways ,6.4.3.1 Milk 1
1 Milk samples were collected at least once per month during 1997 at one indicator and one control location. Milk was also collected at a second indicator station when milk became available in April through October,1997. Each sample was analyzed for I-131 and other gamma-emitting radionuclides. Although not an ODCM requirement, the samples were composited quarterly by location and analyzed for Sr-89 and Sr-90. Cs-137 was detected in 11 of the 20 indicator samples. The goat milk from TM-15 had the highest Cs-137 mean at 10 pCi/kg, with a range of 5.0 to 17.3 pCi/kg. Figure 6.9 shows the Cs-137 concentration in goat and cow milk for 1997 with a general decreasing trend observed for the goat milk samples. Figure 6.10 shows a decrease in the goat milk mean Cs-137 l l 45
1 L p concentration for 1997 from the levels observed in 1996. The Cs-137 in cow milk are similar l to concentrations reported in previous years. All Cs-137 concentrations, whether considered - L " detectable" or "non-detectable", are plotted in Figure 6.9.- Figure 6.11 shows the Sr-90 concentrations in quarterly composited goat and cow milk for 1997.' An increase in the 1997 mean Sr-90 concentration in goat milk is indicated in Figure 6.12. This increase, compared to 1996, is also likely due to the change in eating habits observed in late 1996. The amount of strontium in milk is a function of many dietary factors, L pnmanly calcium concentration and 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' l concentrations of Cs-137 and Sr-90 and changes in the goats eating habits confirmed in 1996. l A detailed discussion of the noted increase in the goat milk concentrations can be found in the 1996 Annual Environmental Operating Report. 6.4.3.2 Fish & Invertebrates I Semiannual samples of fish (FH) and invenebrates (Lobster (HA), rock crab (CA) and blue mussel (MU)) were collected from locations -11 and -24 during 1997.- The media code for the combined category of lobster and rock crab has been designated as CR in Table 5.1. Soft-shell clams (Mya arenaria - MA) were collected from two locations within Bailey Cove. The edible ponions of each of these biota were analyzed for gamma-emitting radionuclides. 1 As expected in biological matter, naturally-occurring K-40 was detected in 19 out of 20 fish and invertebrate samp'les. No other radionuclides were detected. l 6.4.4 Direct Radiation Pathway { l l t Direct radiation is continuously measured at 38 locations surrounding the Maine Yankee 1
- plant with the use of thermoluminescent dosimeters (TLDs). These are collected every ,
calendar quarter 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
. control locations. The lowest point of the cycle occurs during the winter months. This is due primarily to the attenuating effect of the snow cover on radon emissions and on direct
' irradiation by naturally-occurring radionuclides in the soil. Differing amounts of these i naturally-occurring radionuclides in the underlying soil, rock or nearby building materials L
46
1 l result in different radiation levels between one field site and'another, It can be seen from - Figure 6.17 that the TLD at Middle Road in Edgecomb (TL-23) has historically given slightly. I elevated readings. This is apparently due to its close proximity to a ledge outcrop, mak.ing it ithe station with the highest annual exposure in 1997. A'similar situation occurred previously in 1993 at the Westport Siren (TL-09). In this situation, to prevent vandalism of the TLD, the L TLD was moved to a less conspicuous area not far from the original site at the start of the L third quaner of 1993. This site was closer to a rock outcrop, and the exposures increased j slightly. The TLD location was subsequently moved to another nearby location, and the exposure rates dropped (see Figure 6.13)._ l . From Tables 5.2 and 5.3, as well as from Figure 6.10, it can be seen that the Inner and Outer Ring TLD mean exposure rates were not substantially different in 1997, and that the Control TLD mean exposure rate was slightly greater than that at the Inner and Outer Rings. < TLDs are also located on-site in the area bordering the westem security fence and mudflats along Bailey Cove. These TLDs are not considered part of the radiological environmental monitoring program as defined in ODCM Table 2.3, however, the effective dose in this area based on the TLD results are reported in the Maine Yankee " Estimated Dose and p Meteorological Summary Report" pursuant to ODCM Appendix C, item 3. ( 6.4.5 Silt from Circulating Water System Intake Bays L Maine Yankee's Circulating Water System provides water for condenser cooling, drawn from the adjacent Back River. During the 1993 and 1995 refueling outages, silt and mussel l . shells were removed from the Circulating Water System Intake Bays. This material L accumulates as a normal consequence of water use, and contains trace levels of radioactivity - L which are attributable to licensed Maine Yankee liquid effluents. The material also contains a L small amount of sediment from the one-time cleaning of the Service Water pipes. This i material is being handled on-site under a license issued by the Maine Department of Environmental Protection. l l Some additional silt was spread in 1997, and one sample was taken in November after spreading and sent to DESEL for gamma isotopic analysis. Only naturally occurring radionuclides were detected: K-40 measured at 22,400
- 1,300 pCi/kg and AcTh-228 at 900 130 pCi/kg.
47
l l FIGURE 6.1 j GROSS-BETA MEASUREMENTS ON AIR PARTICULATE FILTERS : i QUARTERLY AVERAGE CONCENTRATIONS 0.16 0.16 . 1 0.12- -0.12 g . 1 0.08- . -0.08 {$ : ! Q . O.042 - 0.04 0 .
, . 0 1988 1990 1992 1994 1996 1998
-e- Indicator Stations
-x- Control Stations 48
1
- l
[ I FIGURE 6.2 {- GROSS-BETA MEASUREMENTS ON AIR PARTICULATE FILTERS 0.06 0.06 f 0.05 .- 0.05 c : x l- O.04- :- -0.04 [ Y5 0.03{ h
.x* -0.03 8 9 7:' 1 y
[ 0.02 - '
- '.' -0.02
. ,l i .
- x
[ 0.01- -0.01
~
0 . i
. , . . 'O
[. . Dec Feb Apr Jun Aug. Oct Dec j 1997
-c- - AP 11 Montsweag Brook 1 x AP-29 Dresden Substation (control) f.
f ) 49
FIGURE 6.3 GROSS-BETA MEASUREMENTS ON AIR PARTICULATE FILTERS 0.06 ;0.06 0.055 -0.05
- x g 0.04-l: -0.04 3 : :: x
$ 0.03f x : ', '
,x -0.03 1
O x - x 0.02 - -0.02 x 0.01 5 -0.01 O' . , , i . i . i . O Dec Feb Apr Jun Aug Oct Dec 1997
-e- AP-13 Bailey Farm (ESL) x - AP-29 Dresden Substation (control)
I 50 l -U
[ I. [: FIGURE 6.4
- j. GROSS-BETA MEASUREMENTS ON AIR PARTICULATE FILTERS
{ 0.06 0.06 [- 0.05 -
-0.05
- Y
[.L g 0.04- :: _- 0.04 I :
. x.
I'-
-0.03 O.03- .x X, s .
N '
- x .
F x ( 0.02- ,. ,,
-0.02 s
X X 0.01 - - 0.01 { [- Oi .
.. O Dec Feb Apr Jun Aug Oct Dec 1997 f -e- AP-14 Mason Steam Station
-x AP-29 Dresden Substation (control)
[f ( l 51
i t i
- FIGURE 6.5 l~ GROSS-BETA MEASUREMENTS i ON AIR PARTICULATE FILTERS O.06 0.06 l-0.052 -0.05 l :
- Y
- g . 0.04 , j; -0.04 :
l I : ji x : ; o . l Ti 0.03- 1 x -0.03 4 4-
. x ~
' x x '. -
(8 0.02- . x l
-0.02
. x x '
O.01 . -0.01
'O' . , .
i i 0 ! Dec Feb Apr Jun Aug Oct Dec 1997 t i l l AP 16 Westport Rrehouse x- AP-29 Dresden Substation (control) l I~ S2
c.- l FIGURE 6.6
- 1 H-3 IN ESTUARYWATER WE-12, PLANTOUTFALL l
l 3200- 3200 l
.2800- -2800 l l
2400- -2400 l 2000- .2000 I g 1600- -1600 l S 1200- '1200 800- -800 l 400- -400 0- -0
-400 .
, . ., . , -400 1987 1989 1991 1993 1995 1997 a WE-12 Plant Outfall
-s WE-12 Positive Concentrations l l
l l l 53
I FIGURE 6.7 CESlUM-137 IN SHORELINE SEDIMENT STATION SE-16, OLD OUTFALL AREA 600 600 500, -500 l 400- -400
~
[ ! 5 3002 -300 0 - - 5/94 10/94 5/95 10/95 5/96 10/96 5/97 10/97 Month / Year E 0-Sem E 5 - 10 cm O 10-15cm 54
i FIGURE 6.8 CESilW.-137 IN SHOREUNE SEDIMENT STATION SE-18, FOXBIRDISLAND 600 600 500 -500 400 -400 6 - 300 -300 200 -200 0 7 , -- 5/94 10/94 5/95 10/95 5/96 10/96 5/97 10/97 Month / Year M 0-Sem E 5 - 10 cm O 10- 15 cm 55
FIGURE 6.9 CE3lUM-137IN MILK 40 , _ 40 30 -30 1 ' 20l -20 a . . f - . I R : . 10- -10
~
U l . 0 0 I .
~
-10 . ,
, , , -10 I Jan Apr Jul Oct Jan 1997 l
. m.,s o- e..
l e-. ro.,e cs. exi s..ee.1, e i e m.2s s g.. I; I 56 [ _ L-e
[ 4 [. FIGURE 6.10 CESIUM-137 IN MILK ANNUAL AVERAGE CONCENTRATIONS 40 40 {- : 30- -30 [- . m [ h -20 g . [. 10 -10 ( { 0 l 1987 1989 w &'1991 1993 1995 1997 0 {
-e- TM-15 Mitman Farm
(
-e- TM-18 Chewonki Foundation e TM-25 Hanson Farm
( [ 57 f I L '. s .. . - _ _ _ - _ -
I p FIGURE 6.11 { STRONTIUM -90 IN MILK QUARTERLYCOMPOSITES 25 _ , 25 f 20 -20 15- an - f 5 - - oQ. - 10- -10 5- -5
~
o O . . , . ,
, . . , . . O Jan Apr Jul Oct Jan l 1997
-e- TM-15 Mitman Farm
-e- TM 18 Chewonki Foundation a TM-25 h'anson Farm f.
58 l
I - { FIGURE 6.12 STRONTIUM -90 IN MILK ANNUAL AVERAGE CONCENTRATIONS 25 . 25 20- -20 t { : _
-. - ci, 15 - .
-15 10-.
-10
~
a -5 5f 0 .
. 0 1987 1989 1991 1993 1995 1997
-e- TM-15 MRman Fann
-o- TM 18 Chewonki Foundation e TM-25 Hanson Farm f' .
p i 59 i l' r 4 .
FIGURE 6.13 EXPOSURE RATE AT INNER RING, OUTER RING ANDCONTROLTLDS 25 25 205 ,
-20 ,
I 15 -15 l u . 1 g e 4 10- -10 g Q.._ 5- -5 O . . , . . . i . . , 0 1993 1994 1995 1996 1997 1998 RetrievalDate
-e- Control a inner Ring
- x - Outer Ring l
l r 60
I I FIGURE 6.14 i EXPOSURE PATE AT INNER RING TLDS, TL 01-04 25 25 I 20
-20 I a
$ 15- -15 I x 5
a. l ,h10-~ 2
~
-10
'I v 5- -5 O . . , . . , . i i O 1993 1994 1995 1996 1997 1998 RetrievalDate I -e- TL-01 Old Ferry Road v TL-02 Old Ferry Road e TL-03 Bailey House (ESL) f i o TL-04 Westport Island, Rt.144 I I I I .g 61
i FIGURE 6.15 EXPOSURE RATE AT INNER RING TLDS, TL 05 - 08 25 , 25 20 -20 u 8 I 15- -15 k - g . . 6 - b 10-~
-10 E
. ~
_, y ;;;'u 5-.
-5 O . . , . . .
i 0 1993 1994 1995 1996 1997 1998 Rete /alDate
--e- R-05 MY Information Center
-x- TL-06 Rt.144 & Greenleaf Road
-tr- TL-07 Westport 1* Lid, Rt.144 o TL-08 MY Screenhousa L
I 62 I m F*" - W
[- [ FIGURE 6.16 EXPOSURE RATE AT INNER RING TLDS, TL 09-10,12-13 [
'25 '
25 (. 5 20 -20 8 I 15- -15 [. cc h.10- -10 5 -
~
5- -5 I : . O . . . i 0 b~ 1993 1994 1995 1996 1997 1998 RetrievalDate
-e- TL-09 Westport Siren v TL 10 Bailey Point A TL-12 Westport Firehouse o TL-13 Foxbird Island
( [ ] 63 r s .. .
l FIGURE 6.17 l-EXPOSURE RATE AT INNER RING TLDS, TL 14-16 25 , 25 1 20-.
-20 l.
N I 15- -15 6
- g . .
o'10- -10 5 : : x 5 -5
- O . . . , . . . , . .
.i i 0 1993 1994 1995 1996 1997 1998 Retrieva1Date a TL-14 Eaton Farm
+ TL-15 Eaton Farm e TL-16 Eaton Farm l
I 64 l
FIGURE 6.18 EXPOSURE RATE AT INNER RING TLDS, TL 17- 19 25 25 20- -20 15- a x h10- -10 5-
/ a
& -5 0 . . , . . . , . . . , . . . , . . .
i 0 1993 1994 1995 1996 1997 1998 RetrievalDato
-e- TL-17 Eaton Farm x TL-18 Eaton Farrn a TL-19 Eaton Farrn I'
i f 65 r L
- r. i l l l
l FIGURE 6.19
. EXPOSURE RATE AT OUTER RINGTLDS, TL 11,20-22 25 ,
c25 I 20 20 _ 1
'8 -
-15
.r 15-m .
R . . x - A - . 8.10- -10 r, . .
~
bI . .o a ro 5- -S
~
0 . . i . . .
-i 0 1993 1994 1995 1996 1997 1998 RetrievalDate
-e- TL 11 Mason Station
-x- TL-20 Bradford Road, Wiscasset e TL 21 FederalStreet, Wiscasset o TL-22 Cochran Road, Edgecomb l
I 66
i i FIGURE 6.20 EXPOSURE RATE ATOUTER RINGTLDS, TL23-26 25 , 25
'20f -20 u
8
-z 15- u .
- 8. - -
l
-E l
'10 -10
'
- WE, 5-
. y &- - ..
-5
' ~
O . . . i i 0 1993- 1994 1995 1996 1997 - 1998 Retrieval Date
-e- TL-23 Middle Road, Edgecomb j
--x- TL-24 Rivor Road, Edgecomb j e TL-25 River Road & Rt.27 ll
-o- TL-26 Rt.27 & Boothbay RR Museum l
t l i 67
FIGURE 621 EXPOSURE RATE ATOUTER RINGTLDS, TL27-30 25 25
~
1 20 -20 I . g I 15- -15 I N. - - cc - l b10- -10 i 5- -5
~
I ~ 0 i . .
. 0 1993 1994 1995 1996 1997 1998 RebievalDate I -e- TL 27 Barters Island e TL-28 Westport Island, Rt.144 & East Shore Road e TL-29 Harrison's Trailer
--o- R-30 Leeman Farm, Woolwich
[ W 68
FIGURE 6.22 EXPOSURE RATE AT OUTER RING TLDS, TL31 -35 j. 25 25 , 20 -20 m - 8
~
I 15- -15 k - cc h10- -10 5 : a S- -
-5 O . . .
i . . . , . . . i 0 1993 1994 1995 1996 1997 1998 RetrievalDate
-e- TL 31 Barley Neck Road, Woolwich
-x- TL-32 Baker Farm, Woolwich A TL 33 Route 127, Woolwich
--o- TL-34 Route 127, Woolwich
-e- TL-35 Route 127, Woolwich 69 f
I -
FIGURE 6.23 EXPOSURE RATE ATCONTROL RINGTLDS, TL36-38 1 25 , 25 1
\
4 20- -20 1 i u I8 15I -15 u - .
- 8. -
10 -10 i W u w w 2 u u ::M w 5- -5 l 0 . . . . . . . . .
- i. . .
i 0 1993 1994 1995 1996 1997 1998 RetrievalDate
-e- TL 36 Boothbay Harbor Fire Station
-x- TL-37 Bath Fire Station a TL-38 Dresden Substation 70 t
a [
'i!
7 (7.' QUALITY ASSURANCE PROGRAM
. The quality assurance program at the Duke Engineering & Services Laboratory is designed f to serve two overall purposes: 1) Establish a measure of confidence in the measurement process to assure the licensee, regulatory agencies and the public that analytical results are
[ accurate and precise; and 2) Idhntifyl deficiencies in the sampling and/or measurement process
. 'to those responsible for these operations so that corrective action can be taken. Quality j~ assurance is applied to all steps of the measurement process, including the collection, reduction, evaluation and mporting of data, as well as the record keeping _of the final results.
Quality control, as part of the quality assurance program, provides a means to control and b measure the characteristics of measurement equipment and processes, relative to established requirements. b The Duke Engineering & Services Laboratory employs a comprehensive quality assurance program. designed to monitor the quality of analytical processing to ensure mliable
- environmental monitoring data. The program includes the use of approved and controlled procedures for all work activities, a nonconformance and corrective action tracking system,
[ systematic intemal audits, audits by extemal groups, a laboratory quality control program, and
. a staff training and retraining system. Monitoring programs include the Intralaboratory Quality Control Program administered by the Laboratory QA Officer (used in conjunction -
{ with the National Institute Standards and Technology's Measurement Assurance Program, NIST MAP) and third party interlaboratory programs administered by the EPA and Analytics, . b Inc. Together these programs 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 program. (
; 7.1 Intralaboratory Quality Control Program
- The Duke Engineering & Services Laboratory conducts an extensive intralaboratory quality b control program to assure the validity and reliability of environmental analytical data. Process check samples are either samples submitted in duplicate to evaluate the precision of the -
measurements or are " spiked" with a known quantity of radioactive material to assess the bias { in the measurement. The program is adrainistered by the Laboratory QA Officer. A summary
. of the program process check results may be found in Table 7.1. For the gamma and tritium i results falling in category 4 of the Bias Criteria, the mean bias for each set of results was
- within *15% and no further action was required. The failure of the charcoal filter analysis
[ 71 r
resulted in CR97-0184 which was closed following the satisfactory completion of a root cause l analysis. 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. ' To replace the mix of radionuclides and matrices which comprised this one program the Laboratory now participates in two third party programs, the U.S. EPA Performance Evaluation Study for radionuclides in water and the Analytics Inc. Environmental Cross Check Program for radionuclides in milk, water and on air filters. Participation in such programs and the reporting of results in this report is pursuant to Maine Yankee ODCM section 2.4. Each sample supplied by the EPA or Analytics is analyzed in triplicate and the results are returned to the EPA or Analytics within a specified time frame. The known values from Analytics are evaluated against the Laboratory acceptance criteria and the EPA results are ! evaluated against the EPA control liinits. When the results of the cross-check analysis fall outside of the acceptance criteria or control limit, an investigation is initiated to determine the cause of the problem and if appropriate, corrective measures are taken. For the EPA Intercomparison Program,24 sample sets in a water matrix were analyzed. The analyses included gamma-emitting radionuclides, gross alpha, gross-beta, Sr-89, Sr-90, low level I-131, tritium (H-3), Ra-226, Ra-228 and Natural Uranium.' Table 7.2 provides a summary of the results for 1997. I l Two mean values for Radium-228 in water did not fall within the EPA control limits. Both ! sample sets were spiked at or near the MDA for the technique in question. Applying only a bias criterion when testing at or near the MDA should be avoided. In both cases, an acceptable range of values around the mean was determined (at the 95% confidence level, CL). The known value was then compared to the range around the mean and in both cases the r . EPA known value fell within the range and no further action was necessary. t . p
- Radium-228 in water Reference date: 4/15/97 DESEL Mean: 4.82 pCi/L Range @ 95%CL: 4.8
- 2.4 pCi/L EPA known value of 3.lpCi/L falls within this range.
72 i i 1 ( ;
i a Radium-228 in water Reference date 6/13/97 1 DESEL Mean: 4.57 pCi/L Range @ 95% CL: 4.6 2.0 pCi/L EPA known value of 3.lpCi/L falls within this range. For the Analytics Inc. Cross Check Program,18 sample sets in water, milk and air filter I matrices were analyzed. The analyses included gamma-emitting radionuclides, gross alpha, gross-beta, Sr-89. Sr-90, low level I-131, tritium (H-3), Ra-226, Ra-223 and Natural Uranium. Table 7.3 provides a summary of the results for 1997. Gnc Analytics result failed to meet the criteria for acceptance .
- DESEL CR97-0172 was is' ued s because the 16.2% mean bias for Zn-65 on air particulate filter exceeded the performance criteria of
- 15%. This investigation is in progress.
I 7.3 Environmental TLD Quality Assurance Program 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 Voluntary Laboratory Accreditation Program, independent third party performance testing by Battelle Pacific Northwest Labs and internal performance testing conducted by the Latsratory QA Officer. Under these programs, Pacific Northwest Labs and internal performance testing conducted by the Laboratory QA Officer. Under these programs, I 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. l Instrumentation checks, although routinely performed by the Dosimetry Services Group and representing between 5-10% of the TLDs processed, are not presented in this report because 7 they do not represent a true process check sample since the doses are known to the processor. l The DESEL processed 3304 environmental TLDs during 1997. Ninety-five independent l performance tests were conducted. Of these,71 were submitted to the Dosimetry Services Group by the QA Officer and 24 were submitted as part of Battelle Pacific Northwest i 73
a t Laboratories testing program. One hundred percent of these met the acceptance criteria for accuracy and precision with an average percent bias during the first half of 1997 of 3.5 3.9 and 1.5
- 3.4 during the second half of 1997.
1 7.4 Blind Duplicate Quality Assurance Program The Laboratory Quality Control Audit Committee (LQCAC) is comprised of one member 1 from each of the five New England power plants that are serviced by the Duke Engineering & Services 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 , I 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 1997. Paired measurements were evalueted 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 1435 paired measurements evaluated in 1997,1426 or 99.4% fell within the established acceptance criteria. I The samples submitted as part of this program are listed in Table 7.4. I [ [ 74 L e 9 .
. _ ^-
f-l
~
4 0 0
~
%0 %5% 1 a y5 1 r
. - r = i e
- 3 4 2 6 o g < = = <i r t
)
I 7 1 e <d a d d nC 2 t C an n a e d ( a a%is n%%0 i r o 5 t e e i0 1 u s i>>>O i y' r c r o C e r t P 1 23 4 a' r 2 0 I 'I 2 4 I y = = = = o W 1 1 3 b y ry y y r r r b a a go gog og ir o L P e e e e e it t t t t l r a a a a t a s CCCCC nl t n n n n n eu o o o o o mse i iiii i s s s s i si 6 c 4 e ric e reic c c 1 3 5 2 i mR r l 1 l I 4 2 5 4 r P PPPP r er e v o i r ) nt 2 En o ll llll llI llI ( s
. cs s eC . rdec 4 1 2 I 4 2 e
Sr o P Ql gt a 5 7 n n i r e em e i n no 3 5 l I I 7 1 8 gr ni v ) En I ( eE a k 7 i r u9 e D9 1 kr u C 2 0 1 s 2 1 I 1 I 1 5 2 2 1 7 i a B % l E. y% r
%50 1 a
B o5 1
= i g = < er A e t
a < < d
= t i
T C dn dn aC n r I 6 9 2 8 8 s a e 3 0 5 7 2 l 2 6 7 0 ia a%d By % 0 5 %0isu 1 1 2 1 t b > > > O ll a a i -e i r l s g e l 2 3 4 a h p a o n ir = = = = t _ o c t e U S
/ a r a r a lA B :
a R C y ryr yr yr a e a e. 6 8 m l a - : is h m t m s s 2 2 u r 0 - m n : s e s o o o o u 89 l . a d ia g r e g g gt 1 - s i a m s s . 2 i s i y C m F k m 31 e n o . 3 i t 0-m r e B ta te teae t t d a 1 - f s ly e la r a a m a - : a e r e a l t a r r 1 a ir r r d o s a a
- a M An iA G R R T N S S B i G G G G e G b e n t
CCCC iA G M I w I S m u e g c o A s s s s a r a a a a
^ I
. I I
I. I v. V. N l t n P e al f o bBBBB i i ii I i t a c m I r t o e o u 1) _ ll!I T P T< S ( f
a Table 7.2 - Duke Engineering & Servicts Environmental Laboratory ' 1997 EPA Cross Check Program Results LOWER UPPER NUCLIDE MEDIA ' REFERENCE E-LAB CONTROL CONTROL j DATE MEAN* LIMIT
- LIMIT
- Sr-89 ' Water 01/17/97 11.5 3.3 20.7 Sr-90 Water 01/17/97 22.8 16.3 33.7 Alpha: Water 01/31/97 4.3 0.0 13.9 Beta Water 01/31/97 13.6 6.0 23.4 j 1-131LL - Water 02/07/97 86.9 70.4 101.6 l Ra-226 Water 02/14/97 6.3 4.3 7.5 f
Ra-228 Water 02/14/97 9.4 4.6 11.8 ' i Natual U - Water 02/14/97 25.3 21.8 32.2 H-3 Water 03/07/97 7611.5 6529.4 9270.6 i Sr 89 Water G4/15/97 24.1 15.3 32.7 Sr-90 Water 04/15/97 11.0 4.3 21.7 Co-60 W ater 04/15/97 21.1 12.3 29.7 - Cs-134 Water 04/15/97 30.0 22.3 39.7 Cs-137 Water 04/15/97 21.2 13.3 30.7 Ra-226 Water 04/15/97 13.9 9.5 16.5 l Ra-228 Water 04/15/97 4.8 1.7 4.5 l l Natural U Water 04/15/97 23.3 18.8 '29.2 Cs-134 Water 06/06/97 20.4 13.3 30.7 Cs-137 Water 06/06/97- 48.8 40.3 57.7 Zn-65 Water 06/06/97 98.6 82.7 117.3 Co-60 Water 06/06/97 18.0 9.3 26.7 Ba-133 Water 06/06/97 21.5 16.3 33.7 Natural U Water 06/13/97 33.9 33.4 47.2 Ra-226 ' Water 06/13/97 3.4 2.1 3.9 Ra-228 Water 06/13/97 4.6 1.7 4.5 Sr-89 Water 07/1I/97 42.8 35.3 52.7 Sr-90 Water 07/I1/97 14.8 7.3 24.7 Beta Water 07/18/97 15.2 7.0 25.9 Alpha Water 07/18/97 2.8 0.0 11.8 H-3 Water 08/08/97 9294.0 9099.8 12920.2 Ra-226 Water 09/12/97 19.8 14.8 25.2 Ra-228 Water 09/12/97 8.4 4.5 11.5
- Units in pCi/ Liter r
76
1 i Table 7.2 - Duke Engineering & Services Environmental Laboratory 1997 EPA Cross Check Program Results
} LOWER UPPER NUCLIDE MEDIA REFERENCE E-LAB CONTROL CONTROL I DATE MEAN* LIMIT
- LIMIT
- Natural U Water. 09/12/97 4.4 0.0 10.3 I 1-131LL Water 09/19/97 10.7 0.0 20.4 Ra-226 Water 10/21/97 5.5 3.6 6.4 Ra-228 Water 10/21/97 4.8 2.7 7.3 I Natural U Water 10/21/97 29.5 25.8 36.2 Sr-89 Water 10/21/97 36.7 27.3 44.7 Sr-90 Water 10/21/97 20.7 i Co-60 Water 10'21/97 9.0 13.3 1.3 30.7 18.7 Cs 134 Water 10,21/97 39.6 32.3 49.7 Cs-137 Water 10/21/97 33.6 25.3 42.7 I Alpha Water 10/31/97 8.8 6.0 23.4 Beta Water 10/31/97 47.0 '40.2 57.6 Co-60 Water 11/07/97 27.7 18.3 35.7 I Zn-65 Water 11/07/97 75.4 61.1 88.9 Cs-134 Water 11/07/97 10.4 1.3 18.7 Cs-137 Water 11/07/97 77.1 65.3 82.7 Ba-l33 Water 11/07/97 97.6 81.7 116.3 I
- Units in pCi/ Liter s
I l I I t L 77
Tcble 7.3 - Duke Engineering & S:rvices Environmentti Laboratory 1 1997 ANALYTICS Cross Check Program Results l Sample: E0978162 Gamma Quarter: 1st,1997 E0981 162 Strontium Media: Milk Units: pCi/L Ratio Nuclide Reported Known YAEU Evaluation Value Value Analytics l Cr-51 403 387 1.04 Agreement Mn-54 177 176 1.01 Agreement Co-58 80 79 1.01 Agreement I Fe-59 150 144 1.04 Agreement Co-60 176 176 1.00 Agreement ls Zn-65 Sr-89 178 24 165 25 1.08 - 0.96 Agreement Agreement Sr-90 18 19 0.95 Agreement l-131 23 20 1.15 Agreement I 1-131LL 21 20 1.05 Agreement Cs-134 143 143 1.00 Agreement Cs-137 117 114 Agreement i 1.03 Cc-141 232 232 1.00 Agreement i Sample: E0977-162 Alpha, Beta Quarter: 1st,1997 I E0979-162 Gamma Ra,U E0980-162 Media: Water Units: pCi/L Ratio 1 Nuclide Reported Known YAEU Evaluation Value Value Analytics Cr-51 433 419 1.03 Agreement Mn 54 193 190 1.02 Agreement Co-58 84 86 0.98 Agrectnent Fe-59 160 155 1.03 Agreement Co-60 190 190 1.00 Agreement Zn-65 185 179 1.03 Agreement [- 1-131 26 25 1.04 Agreement 1-131LL 25 25 1.00 Agreement Cs-134 151 155 0.97 Agreement Cs-137 124 123 1.01 Agreement Cc-141 249 251 0.99 Agreement Alpha 103 97 1.06 Agreement Beta 132 144 0.92 Agreement Ra 226 52 53 0.98 Agreement Ra-228 60 59 1.02 Agreement l . U-234 41 42 0.98 Agreement U:238 42 'i _.44 _f J95__ Agreement j 78
Table 7.3 - Duke Engineering'& Services Environmental Laboratory 1997 ANALYTICS Cross Check Program Results Sample: E1072-162 - Alpha, Beta - Quarter: 2nd,1997 Gamma Strontium Media: Air Filter Units: pCi/ filter Ratio Nuclide . Reported 'Known YAEU. Evaluation Value - Value Analyjt es Cr-51 -208 213 0.98 - Agreement Mn 54 98 91 1.08 . Agreement
' Co-58 81 83 0.98 Agreement Fe 59 - 88 81 1.09 Agreement Co-60 108 121 0.89 Agreement Zn-65 176 -151 1,17 Non-Agreement Cs-134 84 '88 0.95 Agreement Cs-137 137 124 1.10 Agreement Cc 141 134 142 0.94 - Agreement Alpha. 70 65 1.08 - Agreement Beta 127 135 0.94 Agreement
. St-89 100 94 1.06 Agreement Sr-90 84' 92 0.91 Agreement Sample: E1073-162 Gamma Quarter: 2nd,1997 E1075-162 Tritium Media: Milk Gamma Units: pCi/L
' W ater Tritium Ratio Nuclide Reported Known .YAEU- Evaluation Value Value Analytics Cr 51 325- 319 1.02 Agreement Mn-54 144 137 1.05 Agreement Co-58 127 124 1.02 Agreement Fe 59 130 122 1.07 Agreement Co-60 168 168 1.00 Agreement Zn-65 245 225 1.09 Agreement 1-131. 57 61 0.93 Agreement 1-131LL 62 61 1.02 Agreement Cs-134 129 131 0.98 Agreement Cs-137 200 185 1.08 Agreement
. Cc-141 214 213 1.00 Agreement
(_ ' H-3 1897 l 1313_ _ . 0.91 Agreement _g 79
I-l Table 7.3 - Duke Engineering & Services Environmental Laboratory
- 1997 ANALYTICS Cross Check Program Results i
Sample: El169-162 - Alpha, Beta Quarter: 3rd,1997 l Ell 71 162 Gamma Ell 73-162 Strontium Mediai . Water Units: pCi/L
' Ratio .
Nuclide . Reported Known' YAEll Evaluation Value Value Analytics Cr 51 240 239 1.00 Agreement ! Mn' 54 72 69 1.04 Agreement Co-58 49 47 1.04 Agreement .
' Fe-59 99 94 1.05 Agreement j
Co-60 155 155 1.00 Agreement ' Zn-65 157 154 1.02 Agreement I-131 99. 94. 1.05 Agreement .;
, 1131LL 97 94 1.03 Agreement . l Cs-134 80 -80 1.00 ; Agreement .
Cs-137 . 84 84 - 1.00 Agreement Ce-141 66 60 1,10 Agreement
~'
Alpha 51 48 1.06 Agreemerit Beta - 298. 291 1.02 Agreement . Sr 17 15 1.13 Agreement Sr-90 " 14 15 1 0.93 ' Agreement l 1 1 l !
- l. Sample: Ell 70-162 Gamma Quarter: 3rd,1997 Ell 72162 Strontium Media: Milk Units: pCi/L j 1
Ratio ! Nuclide Reported Known YAEL' Evaluation ! Value Analytics Value Cr-51 313 304 1.03 Agreement l_ p Mn-54 93 88 1.06 Agreement Co-58 64 60 1.07 Agreement Fe-59 126 119 1.06 Agreement Co-60 ' 201 197 1.02 Agreement ! Zn 65 204 196 1.04 Agreement ! I-131 97 87 1.11 Agreement 1131LL 89 87 1.02 Agreement Cs-134 104 102 1.02 Agreement Cs-137 110 107 1.03 Agreement Ce.141 - 78 77 1.01 Agreement Sr-89 15 15 1.00 Agreement Sr-90" 15 14 1.07 Agreement ; 80
1 Table 7.3 - Duks Engineering & Services Environmental Laboratory
'1997 ANALYTICS Cross Check Program Results Sample: E1244-162 - Gamma Quarter: 4th,1997 -
Media: Milk Units: pCi/L Ratio Nuclide Reported - .Known YAEU Evaluation Value - Value Analytics Cr-51 205' 195 1.05- Agreement Mn-54 ' 83 80 1.04 Agreement Co-58 56 52 1.08' Agreement Fe 59 62 57 '.1.09 Agreement Co-60 96 94 1.02 Agreement Zn-65 144 141 1.02- Agreement 1-131 42 39 1.08 Agreenent I131LL 38 39 0.97 Agreement Cs-134 102 100 1.02 Agreement Cs-137 109 103 1.06 Agreement Ce-141 103 98 . 1.05 Agreement Sample: E1243-162 Alpha, Beta - Quarter: 4th,1997 E1245162 ' Strontium Media: Air Filter Units: pCi/ Filter Ratio Nuclide Reported Known YAEU Evaluation Value Value Analytics Alpha 72 72 1.00 Agreement Beta 245 238 1.03 Agreement Sr89 167 182 0.92 Agreement Sr-90 101 110 0.92 Agreement Sample: E1246-162 Tritium Quarter: 4th,1997 Media: Water Units: pCi/L Ratio Nuclide Reported Known YAEU Evaluation Vnlue Value Analgics H 1017 1076 0.95 Agreement 81
f TABLE 7.4 (
SUMMARY
OF BLIND DUPLICATE SAMPLES SUBMITTED January . December 1997 TYPE OF SAMPLE NUMBER OF PAIRED SAMPLES SUBMITTED { Cow Milk 25 Ground Water 7 f Surface Water 16 Irish Moss 2 { Mussels 4 Food Product - Cranberries 1 TOTAL 55
. I.
r l l^ 82 f t
- 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 cf 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 1997 Land Use Census was condt cted between the required dates of June 1 and October 1.
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 1997 Census, no such new milk animal location was identified. Consequently no changes were made in the milk sampling program. The results of the 1997 Land Use Census are included in this report in compliance with ODCM Section 2.4.3.4 and ODCM Appendix C, item 1. The locations identified during the Census may be found in Table 8.1. 83
f TABLE 8.1 1997 LAND USE CENSUS LOCATIONS f SECTOR NEAREST NEAREST NEAREST MILK { RESIDENCE GARDEN ANIMAL Km (Mi) Km (Mi) Km (Mi) N 1.26(0.78) 1.26 (0.78) ** NNE 2.23 (1.38)*" 2.40(l.49) 2.6 (1.6) (Cows) {. NE ** 1.27 (0.79) 2.18 (1.30)"* ENE 1.20 (0.74)"* 1.20 (0.75)"* ** E 0.9 (0.6) 0.9 (0.6)* " ESE 1.4 (0.9) 2.6 (1.6)"* " SE 0.7 (0.4)* 0.9 (0.6)* ** SSE 0.9 (0.6) 0.9 (0.6)* ** S 1.7 (1.1) 2.7 (1.7)"* 5.53 (3.43)(Goats) SSW 3.0 (1.9) 5.0 (3.1) ** { SW l.50 (0.93) 1.57(0.98) 7.9 (4.9) (Cows) WSW 0.96 (0.60)*" 1.94 (1.20)"* 1.88 (1.17) (Cows) * { W 0.81 (0.50)*" 2.71 (1.68)"* ** WNW l .90 (1.18)*" 2.81 (1.75) ** { NW l .93 (l .20)*" 1.93 (l.20) ** NNW l .06 (0.66)"* 1.18 (0.73) 8.1 (>5) (Cows) The nearest residence, garden or milk animal to Maine Yankee. No location was identified within 5 miles of the plant.
"* New in 1997
[ Note: Distances listed in #.## format were determined through differential global positioning survey. I 1 84 r [
- 9. REFERENCES I 1. USNRC Radiological Assessment Branch Technical Position,"An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.
- 2. NCRP Re ; ort No. 94, Exposure of the Population in the United States and Canadafrom Natural Backgrou.id Radiation, National Council on Radiation Protection and i Measurements,1987.
- 3. Ionizing Radiation: Sources and Biological Effects, United Nations Scientific I Committee on the Effects of Atomic Radiation (UNSCEAR),1982 Report to the General Assembly.
- 4. Kathren, Ronald L., Radioactivity and the Environment - Sources, Distribution, and Surveillance, Harwood Academic Publishers, New York,1984.
- 5. Maine Yankee FinalSafety 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 l Offsite Dose Calculation Manual or to the Process Control Program. Dated January 31, 1989.
- 7. USNRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1997.
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