ML20029D685
| ML20029D685 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/31/1993 |
| From: | Hebert J Maine Yankee |
| To: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| JRH-94-96, MN-94-41, NUDOCS 9405090266 | |
| Download: ML20029D685 (89) | |
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1 EDISON DRIVE
- AUGUSTA, MAINE 04330 + (207) 622-4868 i
May 2, 1994 i
MN-94-41 JRH-94,
4 UNITED STATES NUCLEAR REGULATORY COMMISSION Region I 4
j 475 Allendale Road King of Prussia, PA 19406 i
Attention:
Mr. Thomas T. Martin, Regional Administrator 1
i
Reference:
(a)
License No. DPR-36 (Docket No. 50-309) i
Subject:
Annual Radiological Environmental Operating Report Gentlemen:
l Pursuant to the requirements of T.S.S.9.1.5, enclosed is the Annual i
Radiological Environmental Operating Report for the Maine Yankee Atomic Power Station. This report contains a summary and analysis of the radiological environmental data collected for calendar year 1993.
The results of the program for'1993 are summarized in.the Executive Summary at the beginning of the report.
4 i
Please contact John Arnold should you have questions or comments on this i
report.
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Very truly yours, M
6James R. Hebert, Manager Licensing & Engineering Support. Department JHA/mwf I
l Enclosure c:""Docusent Control.. Desk i
Mr. J. T. Yerokuii Mr. E. H. Trottier Mr. Patrick J. Dostie American Nuclear Insurers 4
l Mr. Clough Toppan, Maine Division of Health Engineering i
u v u vast 94o5090266 931231 PDR ADDCK 05000309 R
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MAINE YANKEE NUCLEAR POWER STATION ANNUAL RADIO 1DGICAL ENVIRONMENTAL OPERATING REPORT January - December 1993 April 1994 Prepared by:
Yankee Atomic Electric Company Environmental Engineering Department 580 Main Street Bolton, Massachusetts 01740
EXECUTIVE
SUMMARY
During 1993, 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, Over 700 samples were collected (including TLDs) over the course of the year, with approximately 4000 radionuclide or exposure rate analyses being performed on them. The samples included ground water, estuary water, sediment, marine algae, fish, mussels,-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. Although not part of the routine Radiological Environmental Monitoring Program, the results of several samples of silt and debris removed from the Circulating Water System intake bays are discussed.
Low levels of radioactivity from naturally.-occurring, fallout and plant emission sources were detected. Most samples had measurable concentrations of K-40, Be-7, AcTh 228 or Radon daughter products. These are the most common of the naturally-occurring radionuclides. 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 exposure from natural background radiation.
In no case did the detected levels approach or exceed the most restrictive federal regulatory or plant license limits for radionuclides in the environment.
Con'sequently, there was judged to be no environmental or health impact.
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a ni suu se iumu i
siis mu u TABLE OF CONTENTS fait EXECUTIVE
SUMMARY
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TABLE OF CONTENTS.............................................
iii LIST OF TABLES................................................
iv LIST OF FIGURES...............................................
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4 1.
INTRODUCTION..................................................
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2.
NATURALLY OCCURRING AND MAN-MADE BACKGROUND RADIOACTIVITY.....
2 3.
GENERAL PLANT AND SITE INFORMATION............................
5 4.
PROGRAM DESIGN..............
6 5.
RADIOLOGICAL DATA
SUMMARY
TABLES..............................
26 6.
ANALYSIS OF ENVIRONMENTAL RESULTS.............................
44 7.
QUALITY ASSURANCE PROGRAM.....................................
73 8.
IAND US E CENSUS...............
81 9.
REFERENCES 83 i
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IJNST OF TABLES Table Title Engg 4.1 Radiological Environmental Monitoring Program...........
12 4.2 Radiological Environmental Monitoring Locations (Non TLD) in 1993...........................
14 4.3 Radiological Environmental Monitoring Locations (TLD) in 1993...............................
16 4,4 Environmental Lower Limit of Detection (LLD)
Sensitivity Requirements 18 4.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples 19 5.1 Environmental Radiological Program Summary..............
28 5.2 Environmental TLD Data Summary.......................
42 5.3 Environmental TLD Measurements 43 7.1 Summary of Process Control Analysis Results 76 7.2 EPA Intercomparison Analysis Results 77 1
7.3 Summary of EPA Intercomparison Program Results 79 7.4 Summary of Blind Duplicate Samples Submitted............
80 8.1 1993 Land Use Census Locations 82
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l LIST OF FIGURES Ficure Title Eggg 4.1 Radiological Environmental Sampling Locations Within 1 Kilometer of Maine Yankee......................
20 4.2 Radiological Environmental Sampling Locations Within 12 Kilometers of Maine Yankee.....................
21 4.3 Radiological Environmental Sampling Locations outside 12 Kilometers of Maine Yankee 22 4.4 Direct Radiation Monitoring locations Within 1 Kilometer of Maine Yankee 23 4.5 Direct Radiation Monitoring Locations Within 12 Kilometers of Maine Yankee 24 4.6 Direct Radiation Monitoring Locations Outside 12 Kilometers of Maine Yankee 25 6.1 Cross-Bota Measurements on Air Particulate Filters 53 (Quarterly Average Concentrations) 6.2 Gross-Beta Measurements on Air Particulate Filters
'54 (AP-11 vs. AP-29 Control) 6.3 Cross-Beta Measurements on Air Particulate Filters 55 (AP-13 vs. AP-29 Control) 6.4 Cross-Beta Measurements on Air Particulate Filters 56 (AP-14 vs. AP-29 Control) 65 Gross-Beta Measurements on Air Particulate Filters 57 (AP-16 vs. AP-29 Control) 6.6 Cesium-137 in Shoreline Sediment Station SE-16, Old Outfall Area.........................
58
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l L.T8T OF FIGURES (continued)
Firure Title Eggg 6.7 Cesiurn-137 in Shoreline Sedirnent Station SE-18, Foxbird Island...........................
59 6.8 Cesium-137 in Milk (Annual Average Concentrations) 60 6.9 Strontium-90 in Milk (Annual Average Concentrations) 61 l
6.10 Exposure Rate at Inner Ring, Outer Ring and Control TLDs.
62 6.11 Exposure Rate at Inner Ring TLDs, TL 01-04..............
63 6.12 Exposure Rate at Inner Ring TLDs, TL 05-08.........
64 6.13 Exposure Rate at Inner Ring TLDs, TL 09-10, 12-13.......
65 6.14 Exposure Rate at Inner Ring TLDs, TL 14-16..............
66 6.15 Exposure Rate at Inner Ring TLDs, TL 17-19 67 6.16 Exposure Rate at Outer Ring TLDs, TL 11, 20-22..........
68 6.17 Exposure Rate at Outer Ring TLDs, TL 23-26..............
69 6.18 Exposure Rate at Outer Ring TLDs, TL 27-30.....
70 6.19 Exposure Rate at Outer Ring TLDs, TL 31-35..............
71 6.20 Exposure Rate at Control TLDs, TL 36-38.....
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- 1. IlfPRODUCTION This report summarizes the findings of the Radiological-Environmental Monitoring Program (REMP) conducted by Maine Yankee Atomic Power Company in the vicinity of the Maine Yankee Nuclear Power Station in Wiscasset, Maine during the calendar year 1993.
It is submitted annually in compliance with Appendix C, item no. 1 of the Offsite Dose Calculation Manual (ODCM) and Technical Specification 5.9.1.5.
This remainder of this report is organized as follows:
Section 2: Provides an introduction to the background radioactivity and radiation that is detected in the Maine Yankee environs.
Section 3:
Provides a brief description of the Maine Yankee Nuclear Power Station 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 all routine sampling and TLD monitoring locations with compass sectors and distances from the plant, and maps showing the location of j
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.
The tables are in the format specified by the NRC Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1).
Also included are complete environmental TLD data.
Section 6: Provides the results of the 1993 monitoring program. 'The performance of the program in meeting ODCM requirements is discussed, and the data acquired during the year are analyzed.
Section 7:
Provides an overview of the Quality Assurance programs used at the Yankee Atomic Environmental Laboratory.
The results of the EPA Intercomparison Program required by Technical Specification 5.8.1.b.3 are also given.
Section 8:
Summarizes the requirements and the results of the 1993 Land Use Census.
Section 9:
C' ms an overall summary of the results of the 1993 Radiological Environmental Monitoring Program. -
2.
Naturally Occurring and Man-Made Background Radioactivitat j
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.
The third j
potential source of radioactivity is due to emissions from the Maine Yankee plant.
For the purposes of the Maine Yankee REMP, the first two categories are classified as " background" radiation, and are the subject of discussion in this section of the report.
The third category is the one that the REMP is designed to detect and evaluate.
2.1 Naturally Occurring Backcround Radioactivity Natural radiation and radioactivity in the environment, which provide the major source of human radiation exposure, may be subdivided into three separate sub-categories:
" primordial radioactivity", "cosmogenic radioactivity" and " cosmic radiation".
" Primordial radioactivity" is made up of those radionuclides that were created with the universe and that have a sufficiently long half-life to be still present on the earth.
Included in this category are the radionuclides that these elements have decayed into.
A few of the more important radionuclides in this category are Uranium-238 (U-238), Thorium-228 (Th-228), Rubidium-87 (Rb-87),
Potassium-40 (K-40), Radium-226 (Ra-226), and Radon-222 (Rn-222).
Uranium-238 and Thorium-228 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 the air we breath, and its daughter products are detectable on air sampling filters.
Potassium 40 comprises about 0.01 percent of all natural potassium in the earth, and is consequently detectable in most biological substances, including the human body. There are many more primordial radionuclides found in the environment in addition to the major ones discussed above (Reference 2).
The second sub-category of naturally-occurring radiation and radioactivity is "cosmorenic radioactivity".
This is produced through the nuclear interaction of high energy cosmic radiation with elements in the earth's atmosphere, and to a much lesser degree in the earth's crust. These radioactive elements are then incorporated into the entire geosphere and atmosphere, including the earth's soil, surface rock, biosphere, sediments, ocean floors, polar ice and atmosphere.
The major radionuclides in this
category are Carbon 14 (C-14), Hydrogen-3 (H-3 or Tritium), Sodium-22 (Na-22), and Bery111um 7 (Be-7).
Bery111um-7 is the one most readily detected, and is found on air sampling filters and occasionally in biological media (Reference 2).
The third sub-category of naturally-occurring radiation and radioactivity is " cosmic radiation".
This consists of high energy atomic or sub-atomic particles of extra-terrestrial origin and the secondary particles and radiation that are produced through their interaction in the earth's atmosphere. The primary radiation comes mostly from outside of our solar system, and to a lesser degree from the sun.
We are protected from most of this radiation by the earth's atmosphere, which absorbs the radiation.
Consequently, one can see that with increasing elevation one would be exposed to more cosmic radiation as a direct result of a thinner layer of air for protection.
This " direct radiation" is detected in the field with gamma spectroscopy equipment, high pressure ion chambers and thermoluminescent dosimeters (TLDs).
2.2 Man-Made Background Radioactivity The second source of " background" radioactivity in the Maine Yankee environment is from " man-made" sources not related to the, power plant.
The most recent contributor to this category was the fallout from the 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 this category, however, has been fallout from atmospheric nuclear weapons tests. Tests were conducted from 1945 through 1980 by the United States, the Soviet Union, the United Kingdom, China and France, with the large majority of testing occurring during the periods 1954-1958 and 1961-1962.
(A test ban treaty was signed in 1963 by the United States, Soviet Union and United Kingdom, but not by France and China.)
The most recent test, conducted by the People's Republic of China, occurred in October of 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 'atitude 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 3
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j environmental samples worldwide. The two predominant radionuclides are 9
j Cesium-137 (Cs 137) and Strontium-90 (Sr-90). They are found in soil and J
in vegetation, and since cows and goats graze large areas of vegetation, 1
these radionuclides are also readily detected in milk.
Other potential " man-made" sources of environmental " background" j
j radioactivity include other nuclear power plants, coal-fired power plants, j
national defense installations, hospitals, research laboratories and industry. These collectively are insignificant on a global scale when compared to the sources discueced 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 tidal estuary of the Sheepscot River.
(See the maps in Figures 4.1 to 4.6.)
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.
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- 4. PROGRAM DESIGE 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.
The program was initiated in 1970, approximately two years before the plant began commercial operation in 1972.
It has been in operation continuously since that time, with improvements made periodically over those years.
Prior to January 1992, the requirements for the Radiological Environmental Monitoring Program (REMP) were given in the Radiological 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 5.8.1.b.
The detailed sampling requirements of the REMP are given in Table 2.3 of ODCM Section 2.4.
This table is summarized in this report as Table 4.1.
The required sampling locations are identified in Chapter 5 of the ODCM.
The locations actually monitored in 1993 are shown on Tables 4.2 and 4.3, as well as Figures 4.1 through 4.6 of this report. The locations in these tables and figures consist of'the required locations specified in the ODCM, as well as any additional optional sampling locations used in 1993.,
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4.1 Monitorine Zones The REMP is designed to allow comparisen of levels of radioactivity in samples from the area possibly influenced by the plant to levels found in areas not influenced by the plant.
The'first area is called Zone 1, and its monitoring locations are called " indicators." The second area is called Zone 2, and its monitoring locations are called " controls." The distinction between the two zones, depending on the type of sample or sample pathway, is based on one or more of several factors, such as site meteorological history, meteorological dispersion calculations, relative l
direction from the plant, river flow, and distance. Analysis of survey I
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 l
Four pathway categories are monitored by the REMP. They are the Direct Radiation, Airborne, Waterborne, and Ingestion Pathways.
Each of these four categories is monitored by the collection of one or more sample media, which are listed below, and are described in more detail in this section:
Airborne Pathway Air Particulate Sampling Charcoal Cartridge (Radioiodine) Sampling Mixed Grass Sampling (for airborne deposition)
Vaterborne Pathways Estuary Water Sampling Ground Water Sampling Shoreline Sediment Sampling Marine Algae Sampling Ingestion Pathways Milk Sampling Fish and Invertebrate Sampling Direct Radiation Pathway TLD Monitoring l
l 4.3 Descriotions of Monitorine Procrams l
4.3.1 Air Samoline Continuous air samplers are installed at five locations.
The sampling pumps at these locations operate continuously at a flow rate of approxirately one to two cubic feet per minute. Airborne particulates are collected by passing air through a 47 mm glass-fiber filter. A dry-gas meter is incorporated in the sampling stream to measure the total amount of air sampled in a given interval.
The entire air sampling system is housed in a weatherproof structure. The filters are collected weekly and are initially screened at the Maine Yankee Environmental Services Laboratory with a gas flow proportional 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 Yankee Atomic Environmental Laboratory before being analyzed for gross-beta radioactivity (indicated as CR-B in the data tables).
The weekly filters are composited (by location) at the Laboratory for a quarterly gamma spectroscopy analysis.
4.3.2 Charcoal Cartridge (Radiolodine) Samolinz Continuous air samplers are installed 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 in a weatherproof structure.
The filters are collected weekly and are initially screened at the Maine Yankee Environmental Services Laboratory with an Eberline Model RM-14 monitor with an HP-210 pancake probe.
4.3.3 Mixed Grass Samoline j
l Although there is no Technical Specification requirement for mixed grass or vegetation sampling, a sample is collected from an on-site location twice during the growing season. To collect this sample, all grass is cut to a height of one inch above ground level from a 4 square meter plot.
The grass is shipped to the Laboratory in a plastic bag, where it is analyzed for gamma-emitting radionuclides. -
4.3.4 Estuarv Vater Samoline An automatic compositing sampler is located at the discharge forebay to monitor water discharged to.the Back River.
(In-plant systems monitor water prior to release to the discharge forebay.) The sampler is controlled by a timer that collects an aliquot of this water at least every two hours.
Every week a one-liter sample is gathered from this composited sample. These one-liter samples are again composited at the Environmental Services laboratory before shipping to the Yankee Atomic Environmental Laboratory at the end of the month. A weekly grab sample is collected at the control location in the Kennebec River.
These are composited for a monthly sample at the Environmental Services Laboratory. All estuary water samples are preserved with hcl and NaHS03 to prevent the plate out of radionuclides on the container walls.
Each monthly composite or grab sample is analyzed for gamma-emitting radionuclides. These are composited again (by location) at the Laboratory for a quarterly H-3 analysis.
4.3.5 Cround Water Samoline Due to the hydraulic gradient at the Maine Yankee site, whereby the ground 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 quarterly from the one on-site location and one control location. All ground water samples are preserved with hcl and NaHS03 to prevent the plate out of radionuclides on the container walls.
Each sample is analyzed for gamma emitting radionuclides and H-3.
During 1993, additional ground water samples were collected from on site monitoring wells.
These special samples are discussed in Section 6.4.2.2.
4.3.6 Sediment Sampline Shoreline sediment cores are collected semiannually from two locations on Bailey Point. At each location, six two-inch I.D. plastic coring tubes are driven into the sediment to a depth of at least six inches.
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 two-inch segments.
For each location, the 0-5 cm segments are blended into a single sample, as are the 5-10 cm and 10-15 cm segments. These composite samples are then analyzed for gamma emitting radionuclides. -
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4.3.7.
Marine Algae Samoling Mixed samples of Fucus and Ascophy11um marine algae are collected semiannually from two locations, one near the plant diffuser discharge and one at a control location.
(Neither of these samples is required by ODCM i
Table 2.3.)
Each sample is frozen for shipment to the Laboratory. At the Laboratory, they are analyzed for gamma-emitting radionuclides.
4.3.8 Milk Samoline Milk samples are collected on a monthly schedule from at least three locations.
Two locations are chosen as a result of the annual Land Use Census, based on a hypothetical potential dose commitment. The third location is a control, which is located sufficiently far away from the plant to be outside any potential influence from it.
At the time of sampling, each milk sample is preserved with an appropriate amount of formaldehyde. Methimazole is also added to prevent protein binding of any radioiodine.
Each sample is analyzed for gamma-emitting radionuclides.
Following a chemical separation, a separate low-level I-131 analysis is performed to meet the Lower Limit of Detection requirements in the ODCM.
Although not required by the ODCM, Sr-89 and Sr-90 analyses are also performed on quarterly composited samples.
)
4.3.9 Fish and Invertebrate Samnline Samples of commercially important fish and invertebrates are collected semiannually at two locations (near the plant discharge and at a control location on the Sheepscot River). A commercial lobsterman was contracted in 1993 for the collection of fish (using gill nets), crabs and lobsters.
Mollusc (blue mussel) samples are collected at both sampling locations by Maino Yankee Environmental Services staff. All samples are separated by species type and are then frozen and delivered to the Laboratory, where the edible portions are analyzed for gamma-emitting radionuclides.
4.3.10 TLD Monitorina Direct gamma radiation exposure was continuously measured with the use of thermoluminescent dosimeters (TLDs).
Specifically, Panasonic UD-814 calcium sulfate dosimeters were used, with a total of six elements in place at each monitoring location.
Each pair of dosimeters is sealed in a 1 4
d
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.
i A total of 38 stations, with a quarterly readout schedule, are required by ODCM Table 2.3.
The plant staff posted and retrieved all TLDs, and then processed them on their Panasonic UD-702E TLD reader. l 4
TAsLE 4.1 Radiological E wiroruental Monitoring Program (as re wired during 1993 by CDOE Tabte 2.3)
Collection Analysis Exposure Pathway
- f Muser of Routine Analysis Analysis 88'0I' sample Locations Sampling Cottection Type Frequency Mode Frequency
- 1. Direct Radiation (TLDs)
Total Locations: 38 Continuous Quarterly ca==== dose Each TLD
- 2. Airborne (Particulates Total Locations: 5 Continuous Weekly Particulate Sample:
and Radiofodine)
Gross Seta Each Sample Gasuna Isotopic Quarterly Composite (by location)
Radiciodine Canister:
1-131 Each sample
- 3. Waterborne
- a. Estuary Water Total Locations: 2 Composite Monthly Ganuus Isotopic Each Sample (aliquot every Tritium (N-3)
Quarterly composite 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
- b. Ground Water Total Locations: 2 Grab Quarterly Gamma Isotopic Each Sample Tritium (M-3)
Each sample
- c. shoreline sediment Total Locations: 2 Grab semiamually Gansna Isotopic Each Sample Groundwater samples shall be taken heen this source is tapped for drinking or irrigation purposes in areas W re hydraulic gradiant or recharge properties are suitable for contamination.,
TABLE 4.1 (continued)
Radiological Erwiremental Monitoririg Program (as regaired drinS 1993 by GN38 Table 2.3)
Collection Analysis Exposure Pathway Nominst Ntaber of Routine Nominal Analysis Analysis Sample Ma Sample Locations Sanpting Collection Type FregJency Mode Frequency
- 4. Ingestion
- a. Milk Total Locations: 3 Grab Monthly Games Isotopic Each sample I-131 Each sample b.
Fish and Invertebrates Total Locations: 2 Grab semiennuelty canuma Isotopic on Each sample (comunercially or (or seasonal if edible portions recreationetty appropriate) important species)
- c. Food Products (3 types Total Locations: 3 Grab Monthly when canuma Isotopic Each sample of broad teaf available I-131 Each sample vegetation)**
i Food Product sampling performed only if milk sampling is not done.
j l l
TABLE 4.2 Radiological Environmental Monitoring Incations (non-TLD) in 1993 Maine Yankee Nuclear Power Station Distance From Direction Exposure Station Plant From Pathway Code Station Descriution Z2ng (km)
Plant I
- 1. Airborne
- a. Air Part.
AP/CF-11 Montsweag Brook 1
2.7 NW
& Charcoal AP/CF-13 Bailey Farm (ESL) 1 0.6 NE Filters AP/CF-14 Mason Steam Station 1
4.8 NNE AP/CF-16 Westpart Firehouse 1
1.8 S
AP/CF-29 Dresden Substation 2
19.8 N
- b. Mixed Crasses TG-11 Bailey Farm (ESL) 1 0.6 NE
- 2. Waterborne
- a. Surface WE-12 Plant Outfall 1
0.3 SW Water (Composite Sample)
WE-20 Kennebec River 2
9.8 SW (Grab Sample)
- b. Ground WG-13 Bailey Farm (ESL) 1 0.6 NE Water WC-24 Morse Well 2
9.8 W
- c. Sediment SE-16 Old Outfall Area 1
0.4 E',.
SE-18 Foxbird Island 1
0.7 S
- d. Marine Algae AL-11 Long Ledge Area 1
1.1 S
AL-24 Sheepscot River 2
11.2 S
- 3. Ingestion I
- a. Milk TM-15 Mitman Farm 1
5.8 S
TM-16 Baker Farm 1
7.2 W
TM 18 Chewonki Foundation 1
1.2 USW TM-25 Hanson Farm 2
16.0 W
l _ _ _ _ _ - _ _ - _ _ _ _ _ - - _ _ _ __
)
a l
TABLE 4.2 i
(continued)
Radiological Environmental Monitoring Locations (non-TLD) in 1993 Maine Yankee Nuclear Power Station Distance i
From Direction d
Exposure Station Plant From l
Pathway Code Station Description Z2ng (km)
Plant' t
j
- 3. Ingestion, (continued).
]
- b. Fish &
FH-11 Long Ledge Area 1
1.1 S
j.
Invertebrates MU-11
}
CA-11 HA-ll l
FH-24 Sheepscot River 2
11.2 S
3 MU l CA-24 HA-24 i
k o 1 - Indicator Stations; 2 - Control Stations 4
i i
I
)
l 1
L 3
i
)
i k
i J
-15 T
i 1
TABLE 4.3 Radiological Environmental Monitoring locations (TLD) in 1993 Maine Yankee Nuclear Power Station Distance Station From Plant Direction Code Station Descriotion Zp.ng*
(km)
From Plant TL-1 Old Ferry Rd.
I 1.0 N
TL-2 Old Ferry Rd.
I 0.8 NNE TL-3 Bailey House (ESL)
I 0.6 NE TL-4 Westport Island, Rt. 144 I
1.2 ENE TL-5 MY Information Center I
0.2 E
TL-6 Rt. 144 & Greenleaf Rd.
I 0.9 E
TL-7 Westport Island, Rt. 144 I
0.8 ESE TL 8 MY Screenhouse I
0.9 SE TL 10 Bailey Point I
0.4 SSE TL-11 Mason Station 0
4.8 NNE TL-12 Westport Firehouse I
1.8 S
TL-13 Foxbird Island I
0.4 SSW TL-14 Eaton Farm I
0.8 SW TL-15 Eaton Farm I
0.8 WSW TL-16 Eaton Farm I
0.7 W
TL-17 Eaton Farm Rd.
I 0.6 WNW TL-18 Eaton Farm Rd.
I 0.8 NW TL-19 Eaton Farm Rd.
I 1.0 NNW TL-20 Bradford Rd., Wiscasset 0
6.5 N
TL-21 Federal St., Wiscasset 0
7.2 NNE TL-22 Cochran Rd., Edgecomb 0
8.3 NE TL-23 Middle Rd., Edgecomb 0
7.0 ENE TL-24 River Rd., Edgecomb O
7.8 E
TL-25 River Rd. & Rt. 27 0
7.5 ESE TL-26 Rt. 27 & Boothbay RR Museum 0
7.8 SE TL-27 Barters Island 0
7.0 SSE i
TL-28 Westport Island, Rt. 144 &
O 7.7 S
East Shore Rd.
TL-29 Harrison's Trailer 0
6.3 SSW TL-30 Leeman Farm, Woolwich 0
7.6 SW i
e e
4 i
l a
TABLE 4.3
)
(continued)
Radiological Environmental Monitoring Locations (TLD) in 1993 l
Maine Yankee Nuclear Power Station l
Distance Station From Plant Direction l
Code Station Descriotion Zone *
(km)
From Plant TL-31 Barley Neck Rd.
O 6,7 WSW TL-32 Baker Farm, Woolwich 0
7.2 W
j TL-33 Rt. 127, Woolwich 0
7.3 WNW l
TL-34 Rt. 127, Woolwich O
7.9 NW TL-35 Rt. 127, Dresden O
9.1 NNW TL-36 Boothbay Harbor Fire Station 2'
11.4 SSE l
TL-37 Bath Fire Station 2
10.4 WSW j
TL 38 Dresden Substation 2
19.8 N
1 i
i 8
I i
1 i
j 4
5 4
l 4
5
-17 i
l 4
TARTE 4.4 Environmental Iower Limit of Detection (ILD) Sensitivity Requirements Airborne Fish &
Particulates Inverte-Food Sediment Analysis Water or Gases brates Milk Product (pci/kg (PCi/l)
(pCi/m3)
(pci/kg)
(pCi/l)
(pCi/kg)
-dry)
Gross-Beta 4
0.01 H-3 2000
O.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 If no drinking water pathway exists, a value of 3000 pCi/l may be used.
If no drinking water exists, a value of 15 pci/i may be used.
(Several other explanatory footnotes are given in Tech. Spec. Table 4.8-2.
_.u.
,m.~
m..
...__.m._
.__._._.m.
i L
L TABLE 4.5 i
Reporting Levels for Radioactivity concentrations In Environmental Samples Airborne Fish &
Particulates Inverte-Food Analysis Water or Gases brates Milk Product (PCi/l)
(Pci/m3)
(pci/kg)
(pci/1)
(pci/kg)
H-3 20,000
Zn-65 300 20,000 Zr-Nb-95 400 **
I-131 2 ***
0.9 3
100 I
cs-134 30 10 1000 60 1000 cs-137 50 20 2000 70 2000 Ba-La-140 200 **
300 4
i If no drinking water pathway exists, a value of 30,000 pci/l may be used.
Parent only.
[
i If no drinking water exists, a value of 20 pci/1 may be used.
t,
g TG 11 WG.13 4 @ AP/CF-13 T
A at LITTLE CAK 1SLAl:D 9
INTAKE DISCHARGE FOREBAY WE-12 4
8AllEV N.
g g
e o
5 SE-16 @
@ SE-18 i
E 79 % 3 yg,3 3 WSPORT ISLA!.T 3
AL 11 U
100 200 300 O!5 CHARGE AREA
(
SER)
MA-ll Fu.Tr rt s FH-11@
CA-11 Figure 4.1 Environmental Radiological Sampling Locations Within 1 Kilometer of Maine Yankee 20-
i u
5 e,.
4:LoscTims 1
i 4
e..
WISCASSET e:
.;a..
AP/CF-14
+
@ AP/CF-il
) :. h sts ExtARotMEN2' ZN 7:GURE 4.1 c-NEquASSET LAKE
\\ _' "'..
)
@ 11G-24 d[
o EOGECOM8
'TM16M'.
TM18.O
~~
'l j
g AP/CF-16 WE 20 8
BATH,! 6-.
[
p, WOOLWICH f
5*
.- D y'
. TM 15 @C h-j D
I :
d.
.o' FH 24 g
{
AL 24 C
. MU 24 H A.24 8
4 BOOTHBAY HARBOR
{
. c A.24
,e,
'{
w h:_
g occccerctw r$tAup '-
(f Yk 4
Figure 4.2 Environmental Radiological Sampling Locations 4
Ulthin 12 Kilometers of Maine Yankee 21-l
CAR 0t HCR
- I e RANDOLPH 0
- ~.
.}
2
.l s '.
R1 CHM 0nD e,
'I
- @* ORESDEN j :.
SEE ENT.ARGEMENr ZN TZGURE 4. 2
'NEWCASTL.E.
h c'e OAMARISCOTTA l
'i
,1 V
WISCASSET el
'l l E-g l
I IEDGECOMS ?
cuw r'.
08Rl5TOL TM-25@l'
.F 4
i.
I
/.gl
. :W M
- )-
l i
- BATH e:
5WOOLWJCH.
BRUNSWICK 4'.
I
. or ;.
'1 ]}.,.]. j ll*
f:,
?.
I 4
i s
BOOTHBAY.I l
. HARB0
)
g 4
e.
$~ ~'
~
e. :-~~
~
N 4
l ATLAKTIC OCEAM T
1 0
to c
\\
i l
KILOHCTERS s
Figure 4.3 Environmental Radiological Sampling Locations outside 12 Kilometers of Maine Yankee 22-
N Ag,,
g#
'g
'h TL 19 @
N I@ TL-3 f
~
TL la @
T Q
Y
.j' N T L-17 nGE FOREBAY d.
(
' TL-13
,TL-10 (Q
@ TL-15 h*
4 8A LCV FT.
TL-14 @!
@ TL 9
\\
4 g
+
WE 1 15LAno y
6b i
o too 200 soo Ol5 CHARGE AREA (0!FFUSCR)
- SW S
Figure 4.4 Direct Radiation Monitoring Locations Within 1 Kilometer of Maine Yankee
d l
4
[
Sg gyjj
. j:
N 9
n 5
Ib q.
KILOMETER $
j L
@ TL-35 8
TL-20 TL-22,
/
@ TL-34
}
e TL-ll
@ TL 23
\\
1 s
n.33 @ SEE ENLARGEMENr ZN TZGORE 4.$
):,
1 n-1
,t.,
NEquASSET LAKE l f ;"'
', 3{,4 y
. '[
TL.f [-
I e EDGECOMS E
{
Q.. ; ' 'N.
- TL 24 e!
TL-32 @
I f
, @ TL-31.
.4 Tk'37
- R-25 @
. [
. p, i WOOL Cu BATH
. 5,
@ TL-30 g,3 e TL 29 '
Q
\\
}
- ). :
Q.
h h'
.s u
8 BOOTH 8AY HARBOR 1
h e@ TL-36y s,,
/:
.;b'k'#
f
-y
- j n
.[f cEcectTovu l$tfup '
'SSty
.f ):
fcfc.
S-
\\
Figure 4.5 Direct Radiation Monitoring Locations Within 12 Kilometers of Maine Yankee,
idY
, \\
p N
C#"0INE R e
,,ggggg(p
- )
+p
@ EL-3s
- q RICHMOND N
A
-
- DRESD n j
\\,
r
^
GEMENT ZN TZCup.g 4,3 NEWCASTLE, m
-z#
' ~~~~~_
- ~5 I;
t v.
- /
i,
,g3CA S Tl
., g
..* DAMARISCOTTA Y
f 0000!NHAx,
I
$2 p
- EDGE VLanT:
e BR STOL E
yp-A f
- l
_ [:%-
l
. BATHE l If
- cy,
(\\ :
- j lI\\.
l.:
(
- \\- )
i
_l'.
-(5 $
,i 800 BAY,I g
N, d?
HAR R,
/ :\\~ g.
g,-
e
)
.y 1
/
r' E
s%
. '. i..
f_,
.r L.
[l j -
c.-
~
g 10 Miles' N
.'l.
p
/))*)
l I f
- /.
l
^Tz Av7 tc (g,,y 4
7" 0'
0 10 20 EILOMETERs gt g
S 4
Figure 4.6 Direct Radiation Monitoring Locations Outside 12 Kilometers of Maine Yankee 4
5.
RADIOLOGICAL DATA
SUMMARY
TABLES This section summarizes the analytical results of the environmental samples which were collected during 1993.
These results, shown in Table 5.1, are presented in a format similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1).
The results are ordered by sample media type and then by radionuclide.
The units for each media type are also given.
The left-most column contains the radionuclide of interest, the total number of analyses for that radionuclide in 1993, and the number of measurements which exceeded the Reporting Levels found in Table 2.5 of the ODCM. The latter are classified as "Non-routine" measurements.
The second column lists the required Lower Limit of Detection (LLD) for those radionuclides which have detection capability requirements as specified in the ODCM Table 2.4.
The absence of a value in this column indicates that no LLD is specified in the ODCM for that radionuclide in that media.
The target LLD for any analysis is typically 30-40 percent of the most restrictive required LLD. On rare occasions the required LLD is not met.
This is usually due to malfunctions in sampling equipment, which results in low sample volume.
Such cases are addressed in Section 6.2.
For each radionuclide and media type, the remaining three columns summarize the data for the following categories of monitoring locations:
(1) the indicator or Zone 1 stations, which are within the range of influence of the plant and which could conceivably be affected by its operation; (2) the station which had the highest mean concentration during 1993 for that radionuclide; and (3) the control or Zone 2 stations, which are beyond the influence of the plant. Direct radiation monitoring stations (using TLDs) are grouped into an Inner Ring and an Outer Ring (for emergency response),
as well as into a Control or Zone 2 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 below the LLD.
- The standard error of the mean.
- The lowest and highest concentration.
- The number of detectable measurements divided by the total number of measurements.
For example, (4/20) would indicate that four of the twenty samples collected in 1993, for that sample type and that i
radionuclide, contained detectable radioactivity.
A sample is considered to yield a " detectable measurement" when the concentration exceeds three times its associated standard deviation. The j
standard deviation on each measurement represents only the random uncertainty associated with the radioactive decay process (counting
)
statistics), and not the propagation of all possible uncertainties in the analytical procedure.
The radionuclides reported 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 specific interest for any other reason.
The radionuclides that were routinely analyzed and reported by the Laboratory (in a gamma spectroscopy analysis) were: AcTh-228, 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, TeI-132, 2n-65 and Zr-95.
In no case did a radionuclide not shown in Table 5.1 appear as a " detectable measurement" during 1993.
Data from direct radiation measurements made by TLDs are provided in Table 5.2 in a format essentially the same as above.
The complete listing of l
quarterly TLD data is provided in Table 5.3.
)
4 s
TABLE 5.1 ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMART 4
KAINE YANKEE NUCLEAR POWER STATION, WISCASSET, ME (JANUART - DECEMBER 1993) i INDICATOR STATIONS STATION WITH NIGNEST MEAN CONTROL STATIONS 3
RADIDMUCLIDES*
MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
LANGE RANGE 1
(NON ROUTINE)**
LLD No. DETECTED ***
NO.
NO. DETECTED ***
NO. DETECTED **
i Initst: AIR PARTICULATES (AP)
LalTS: pCf/cthic meter Gross (260)
.01
(
2.0 t 0.0)E -2 29
.(
2.1 0.1)E -2
(
2.1
- 0.1)E 2 seta ( 0)
(
5.8 -
35.8)E -3
(
9.6 -
32.2)E 3
(
9.6 -
32.2)E 3 i
(208/208)
( 52/ 52)
( 52/ 52) 1 BE 7
( 20)
(
9.3 2 0.2)E -2 11
(
9.6 t 0.5)E -2
(
9.2 2 0.5)E 2
( 0)
(
7.6 -
11.0)E -2
(
8.6 -
11.0)E -2
(
8.1 -
10.0)E -2 4
( 16/ 16)
( 4/ 4)
( 4/ 4) i MM 54 ( 20)
(
-1.1 0.4)E -4 29
(
6.0 t 7.8)E 5
(
6.0 t 7.8)E -5
( 0)
(
-3.7 -
1.1)E 4
(
1.3 -
2.5)E 4
(
-1.3 -
2.5)E -4
( 0/ 16)
( 0/ 4)
( 0/ 4) 00 58 ( 20)
(
3.2 9.6)E -5 16
(
4.0 t 1.9)E 4
(
-2.3 1 6.7)E -5
( 0)
(
-5.9 -
6.8)E 4
(
1.5 -
6.8)E 4
(
2.1 -
0.9)E 4
( 0/ 16)
( 0/ 4)
( 0/ 4)
FE 59 ( 20)
(
6.2 2 14.0)E -5 11
(
3.72 2.8)E 4
(
1.1 2 3.9)E -4
( 0)
(
-8.1 -
11.4)E 4
(
-1.1 -
11.4)E 4
( 10.0 -
6.7)E -4
( 0/ 16)
( 0/ 4)
( 0/ 4)
CO 60 ( 20)
(
8.5 t 6.1)E -5 11
(
1.8 1.0)E 4
(
9.5 t E3.7)E -6
( 0)
(
-4.3 -
4.9)E -4
(
-4.9 -
42.1)E 5
(
1.6 -
2.2)E 4
( 0/ 16)
( 0/ 4)
( 0/ 4)
CS-134 ( 20)
.05
(
-5.8 4.1)E 5 14
(
3.6 7.8)E 5
(
9.6 2 42.3)E 6
( 0)
(
3.9 -
2.6)E -4
(
7.8 -
26.0)E -5
(
-6.8 -
13.0)E -5
( 0/ 16)
( 0/ 4)
( 0/ 4)
CS-137 ( 20)
.D6
(
1.3 a 4.2)E -5 16
(
1.3 2 1.1)E -4
(
3.7
- 7.5)E -5
( 0)
(
2.9 -
3.8)E -4
(
1.4 -
3.8)E -4
(
1.8 -
1.7)E 4
( 0/ 16)
( 0/ 4)
( 0/ 4)
MEDitMr CHAACOAL CARTRIDGES (CF)
UNITS: pCl/cthic meter 1 131 (260)
.07
(
3.1 2 6.5)E -4 14
(
1.3 2 1.3)E -3
(
3.8 2 14.2)E 4
( 0)
(
2.7 -
2.4)E 2
(
-2.4 -
1.8)E -2
(
-2.7 -
2.3)E 2
( 0/208)
( 0/ 52)
( 0/ 52)
NOTE: Footnotes may be found at the end of Table 5.1.
l r
TABLE 5.1 ENVIRONMENTAL RADIOLOGICAL PROGRAM SuetARY MAINE YANKEE NUCLEAR POWER STATION, WISCASSET, NE (JANUARY - DECENSER 1993)
INDICATOR STATIONS STATION WITN HIGHEST MEAN CONTROL STATIONS
..........e ee **...................
e ****........e RADIONUCLIDES
- MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)**
LLD No. DETECTED ***
No.
NO. DETECTED ***
NO. DETECTED **
MEDIUM: MIXED GRASSES (TC)
UNITS: pCl/kg BE 7 ( 2)
(
3.2 2 0.9)E 3 11
(
3.2 1 0.9)E 3 NO DATA
( 0)
(
2.3 -
4.1)E 3
(
2.3 -
4.1)E 3
( 2/ 2)
( 2/ 2)
( 2)
(
1.0 t 0.5)E 4 11
(
1.0 2 0.5)E 4 NO DATA
( 0)
(
5.4 -
15.1)E 3
(
5.4 -
15.1)E 3
( 2/ 2)
( 2/ 2)
Co-58 ( 2)
(
-8.9
- 4.6)E O 11
(
-8.9 4.6)E O NO DATA
( 0)
(
1.4 -
-0.4)E 1
(
-1.4 -
0.4)E 1
( 0/ 2)
( 0/ 2)
CO-60 ( 2)
(
-9.4 4.5)E 0 11
(
-9.4 4.5)E 0 NO DATA
( 0)
(
1.4 -
-0.5)E 1
(
-1.4 -
0.5)E 1
( 0/ 2)
( 0/ 2) 1-131 ( 2)
(
-2.2 2 1.6)E 1 11
(
2.2 2 1.6)E 1 NO DATA
( 0)
(
-3.8 -
-0.5)E 1
(
-3.8 -
-0.5)E 1
( 0/ 2)
( 0/ 2)
CS-134 ( 2)
(
2.7 e 2.7)E O 11
(
2.72 2.7)E O NO DATA
( 0)
(
0.0 -
5.4)E 0
(
0.0 -
5.4)E O
( 0/ 2)
( 0/ 2)
CS 137 ( 2)
(
1.0 t 0.3)E 1 11
(
1.0 t 0.3)E 1 NO DATA
( 0)
(
7.3 -
13.7)E 0
(
7.3 -
13.7)E 0 r
( 0/ 2)
( 0/ 2)
J NOTE: Footnotes may be found at the end of Table 5.1.
29-
TABLE 5.1 ENVIRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
MAINE YANKEE NUCLEAR POWER STATION, WISCASSET, ME (JANUARY DECEMBER 1993)
INDICATOR STATIONS STATION WITH MICHEST MEAN CONTROL STAil0NS e................e
........................e
- ee...........e RADIONUCLIDES
- MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANCE RANGE (WON ROUTINE)**
LLD No. DETECTED ***
No.
No. DETECTED ***
NO. DETECTED **
EDIlms ESTUARY WATER DE)
LMITS: pCl/kg K-40
( 24)
(
2.5 2 0.1)E 2 12
(
2.5 t 0.1)E 2
(
4.6 a 1.1)E 1
( 0)
(
1.5 -
3.1)E 2
(
1.5 -
3.1)E 2
(
2.3 -
10.4)E 1'
( 12/ 12)
( 12/ 12)
( 6/ 12)
MN 54 ( 24) 15.
(
1.5 a 1.7)E 1 12
(
1.5 t 1.7)E 1
(
7.1 a 23.3)E 2
( 0)
(
-1.0 -
0.9)E 0
(
1.0 -
0.9)E 0
(
-1.4 -
1.2)E O
( 0/ 12)
( 0/ 12)
( 0/ 12)
Co-58 ( 24) 15.
(
1.4 a 3.0)E 1 12
(
1.4 a 3.0)E -1
(
-5.8 a 1.3)E -1
( 0)
(
2.2 -
1.0)E 0
-2,2 -
1.0)E 0
(
1.5 -
0.4)E 0
( 0/ 12)
( 0/ 12)
( 0/ 12)
FE 59 ( 24) 30.
(
-2.9 2 4.7)E -1 12
(
2.9 s 4.7)E -1
(
-7.4 t 6.5)E -1
( 0)
(
-2.9 -
2.6)E 0
(
2.9 -
2.6)E 0
(
4.6 -
4.1)E 0
( 0/ 12)
( 0/ 12)
( 0/ 12)
CO-60 ( 24) 15.
(
-2.8 2 3.4)E 1 20
(
5.9 a 30.3)E 2
(
5.9 2 30.3)E 2 i
( 0)
(
-3.2 -
1.4)E O
(
2.0 -
1.7)E 0
(
2.0 -
1.7)E O
( 0/ 12)
( 0/ 12)
( 0/ 12)
ZN 65 ( 24) 30.
(
-7.42 8.2)E -1 20 (
4.8 t 6.5)E 1
(
4.8 t 4.5)E -1
( 0)
(
-5.3 -
5.2)E O
(
4.6 -
3.9)E O
(
-4.6 -
3.9)E O
( C/ 12)
( 0/ 12)
( 0/ 12)
ZR 95 ( 24) 15.
(
1.9 4.7)E 1 12
(
1.9 2 4.7)E 1
(
2.8 :
5.8)E 1
( 0)
(
-3.2 -
2.2)E O
(
3.2 -
2.2)E 0
(
4.3 -
2.0)E O
( 0/ 12)
( 0/ 12)
( 0/ 12) 1 131 ( 24) 15.
(
8.0 t 5.6)E 1 20
(
1.0 2 0.4)E O
(
1.0 a 0.4)E O
( 0)
(
3.4 -
4.0)E 0
(
8.6 -
40.1)E 1
(
8.6 -
40.1)E 1
( 0/ 12)
( 0/ 12)
( 0/ 12)
CS 134 ( 24) 15.
(
-4.0 a 3.5)E -1 20
(
1.7 a 2.9)E 1
(
-1.7 a 2.9)E 1
( 0)
(
2.5 -
2.2)E O
(
1.7 -
1.5)E 0
(
1.7 -
1.5)E O
( 0/ 12)
( 0/ 12)
( 0/ 12)
CS 137 ( 24) 18.
(
1.3 t 2.7)E 1 20
(
3.2 a 2.8)E -1
(
3.2 t 2.8)E 1 j
( 0)
(
-1.1 -
1,6)E 0
(
1.6 -
1.5)E 0
(
1.6 -
1.5)E O l
( 0/ 12)
( 0/ 12)
( 0/ 12)
NOTE: Footnotes may be fourd at the erd of Table 5.1 Y e
TABLE 5.1 i
ENVIRONMENTAL RADIOLOGICAL PROGRAM SLM4 ART MAINE YANKEE NUCLEAR POWER STATION, WISCASSET, ME (JANUART DECEMSER 1993)
INDICATOR STATIONS ST'ATION WITH NIGNEST MEAN CONTROL STATIONS RADIONUCLIDES
- MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANCE STA.
RANGE RANGE (NON ROUTINE)**
LLD NO. DETECTED ***
No.
NO. DETECTED ***
NO. DETECTED **
EDILM: ESTUARY WATER (E), cent.
tal!TS: pCf/kg BA-140 ( 24) 15.
(
6.2 t 5.7)E 1 12
(
-6.2 2 5.7)E 1
(
1.1 t 0.6)E 0
( 0)
(
-3.3 -
3.3)E O
(
-3.3 -
3.3)E O
(
-5.4 -
1.1)E 0
( 0/ 12)
( 0/ 12)
( 0/ 12)
N3
( 8) 3000.
(
3.7 t 1.5)E 2 12
(
3.7 t 1.5)E 2
(
1.8 t 1.2)E 2
( 0)
(
-4.6 -
66.6)E 1
(
4.6 -
66.6)E 1
(
-3.9 -
38.7)E 1
( 1/ 4)
( 1/ 4)
( 0/ 4)
EDILM: GROUIC WATER (WG)
UNITS: pCl/kg BE-7
( 13)
(
4.0 t 5.7)E O 51
(
3.9 2 1.1)E 1
(
2.1 t 3.4)E O
( 0)
(
1.6 -
3.9)E 1
(
-1.1 -
0.5)E 1
( 1/ 9)
( 1/ 1)
( 0/ O MN-54 ( 13)
(
2.6 2 4.4)E -1 58
(
2.1 2 1.7)E O
(
6.9 t 5.2)E *1
( 0)
(
2.4 -
2.1)E 0
(
1.6 -
0.7)E D
( 0/ 9)
( 0/ 1)
( 0/ 4)
Co-58 ( 13)
(
-9.4 t 3.1)E 1 52
(
8.8 t 13.5)E 1
(
9.4 2 8.1)E 1
( 0)
(
-2.1 -
0.9)E 0
(
3.1 -
0.3)E O
( 0/ 9)
( 0/ 1)
( 0/ 4)
FE 59 ( 13)
(
8.9 2 7.2)E -1 58
(
3.7 t 4.4)E O
(
4.4
- 15.0)E -1
( 0)
(
-3.2 -
3.7)E O
(
-2.1 -
4.7)E O
( 0/ 9)
( 0/ 1)
( 0/ 4)
Co 60 ( 13)
(
4.3 t 4.3)E 1 64
(
2.0 t 1.3)E 0
(
4.5 2 6.2)E -1
( 0)
(
1.8 -
2.0)E 0
(
1.0 -
1.9)E O
( 0/ 9)
( 0/ 1)
( 0/ 4)
ZN 65 ( 13)
(
1.7 t 9.9)E -1 52
(
5.5 2 2.3)E O
(
2.1 2 0.8)E O
( 0)
(
-2.3 -
5.5)E O
(
2.3 -
37.3)E 1
( 0/ 9)
( 0/ 1)
( 0/ 4) 2R 95 ( 13)
(
5.8 5.3)E 1 58
(
1.2 t 3.0)E D
(
-1.4 2 13.4)E -1
( 0)
(
2.8 -
1.5)E O
(
-3.8 -
2.5)E 0
( 0/ 9)
( 0/ 1)
< 0/ 4)
NOTE: Footnotes may be found at the end of Table 5.1...
1 TABLE 5.1 ENVIRONMENTAL RADIOLOGICAL PROGRAM SLM4ARY MAINE YANKEE NUCLEAR POWER STAfl0N, WISCASSET, NE (JANUART DECEMBER 1993)
INDICATOR STATIONS STATION WITN HIGHEST MEAN CONTROL STATIONS RADIDWUCLIDES*
MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)**
LLD NO. DETECTED ***
No.
No. DETECTED ***
No. DETECTED **
EDilm (20 Lac WATER (E), cant.
LallTS: pcl/kg 1-131 ( 13)
(
5.9
- 8.2)E -1 51
(
2.7 2 2.1)E O
(
1.1 2 0.7)E O
( 0)
(
-4.4 -
.t.8)E 0
(
3.9 -
25.2)E -1
( 0/ 9)
( 0/ 1)
( 0/ 4)
CS-134 ( 13)
(
4.1 1 5.2)E -1 51
(
1.9 a 1.4)E 0
(
1.1 2 4.3)E 1
( 0)
(
-3.0 -
1.9)E D
(
1.1 -
0.9)E O
( 0/ 9)
( 0/ 1)
( 0/ 4)
CS-137 ( 13)
(
7.1 2 7.8)E -1 51
(
3.5 t 1.4)E 0
(
-1.8 2 0.6)E O
( 0)
(
-3.5 -
3.5)E 0
(
-3.5 -
-0.4)E O
( 0/ 9)
( 0/ 1)
( 0/ 4)
EA-140 ( 13)
(
2.0 t 6.2)E -1 58
(
4.3 2 3.4)E O
(
2.0 t 0.7)E 0
( 0)
(
1.5 -
4.3)E O
(
-3.7 -
-0.5)E 0
( 0/ 9)
( 0/ 1)
( 0/ 4)
H3
( 13)
(
1.0 t 1.0)E 2 54
(
6.4 s 1.1)E 2
(
-1.6 t 9.2)E 1
( 0)
(
3.5 -
6.4)E 2
(
1.9 -
2.1)E 2
( 2/ 9)
( 1/ 1)
( 0/ 4)
EDILM: SEDIENT (SE) tallTS: pCl/kg (dry)
BE-7
( 12)
(
9.3 2 7.2)E 1 18 (
1.3 a 1.0)E 2 NO DATA
( 0)
(
3.7 -
4.1)E 2
(
2.0 -
4.1)E 2
( 0/ 12)
( 0/ 6)
( 12)
(
2.0 t 0.0)E 4 18 (
2.0 t 0.1)E 4 No DATA
( 0)
(
1.0 -
2.3)E 4
(
1.0 -
2.3)E 4
( 12/ 12)
( 6/ 6)
CO-58 ( 12)
(
1.1 2 0.7)E 1 16
(
6.8 2 6.1)E D NO DATA
( 0)
(
5.0 -
2.3)E 1
(
2.1 -
2.3)E 1
( 0/ 12)
( 0/ 6)
CO 60 ( 12)
(
1.71 0.7)E 1 16 (
2.7 1 0.8)E 1 NO DATA
( 0)
(
2.3 -
5.2)E 1
(
3.9 -
51.5)E O
( 0/ 12)
( 0/ 6) l
,1 i
NOTE: Footnotes may be found at the end of Table 5.1.
4 32-4 a
i i
l
TABLE 5.1 ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMMART MAINE YANIEE NUCLEAR POWER STATION, WISCASSET, ME (JANUARY
- DECEM8ER 1993) d INDICATOR STATIONS STATION WITH HIGNEST MEAN CONTROL STATIONS RADIONUCLIDES
- MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANCE RANCE I
(NON-ROUTINE)**
LLD NO. DETECTED ***
No.
No. DETECTED ***
NO. DETECTED **
MEDIUM: SEDIIE:NT (SE), Cont.
UNITS: pCl/kg (dry) 4 CS 134 ( 12) 150.
(
5.3 t 4.1)E O 16
(
8.6 s 6.1)E O No DATA
( 0)
(
1.0 3.0)E 1
(
8.2 -
30.5)E 0
( 0/ 12)
( 0/ 6) i CS 137 ( 12) 180.
(
2.1 0.2)E 2 18
(
2.2 2 0.3)E 2 No DATA i
( 0)
(
1.3 -
3.7)E 2
(
1.6 -
3.7)E 2
( 12/ 12)
( 6/ 6)
J ACTH228 ( 12)
(
7.7 2 0.3)E 2 18
(
7.9 1 0.3)E 2 NO DATA
( 0)
(
5.9 -
10.0)E 2
(
7.0 -
8.7)E 2
( 12/ 12)
( 6/ 6)
IOttM: MARINE ALCAE (AL)
LMITS: pCl/kg BE-7
( 2)
(
1.4 2 0.7)E 2 11
(
1.4 a 0.7)E 2 NO DATA
( 0)
(
7.1 -
21.2)E 1
(
7.1 -
21.2)E 1
( 1/ 2)
( 1/ 2)
K 40
( 2)
(
5.7 0.0)E 3 11
(
5.72 0.0)E 3 NO DATA a
( 0)
(
5.6 -
5.7)E 3
(
5.6 -
5.7)E 3 2
( 2/ 2)
( 2/ 2)
MN 54 ( 2)
(
1.7 s 3.0)E O 11
(
1.7 a 3.0)E 0 No DATA
( 0)
(
1.2 -
4.7)E O
(
1.2 -
4.7)E O
( 0/ 2)
( 0/ 2) i co-58 ( 2)
( 10.0 a 1610.0)E 3 11
( 10.0 s 1610.0)E 3 No DATA
( 0)
(
1.6 -
1.6)E O
(
1.6 -
1.6)E O
( 0/ 2)
( 0/ 2) j FE 59 ( 2)
(
2.0 s 1.5)E O 11
(
2.0
- 1.5)E O No DATA
( 0)
(
4.8 -
34.4)E 1
(
4.8
- 34.4)E 1 4
( 0/ 2)
( 0/ 2)
CO-60 ( 2)
(
1.3 2 6.7)E 0 11
(
1.3 a 6.7)E 0 No DATA
( 0)
(
-5.3 -
8.0)E 0
(
5.3 -
8.0)E 0
( 0/ 2)
( 0/ 2)
NOTE: Footnotes may be fourd at the end of Table 5.1.
j 4
-33 i
I i
Y
~_
TAsLE 5.1 ENVIRONNENTAL RADIOLOGICAL PROGRAM Sul#4ARY MAINE YANKEE NUCLEAR POWER STATION, WISCASSET, ME (JANUARY - DECEMBER 1993) 1 INDICATOR STATIONS STATION WITH NIGNEST MEAN
-CONTROL STATIONS I
LADIONUCLIDES*
MEAN MEAN MEAN (MO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (WON ROUTINE)**
LLD No. DETECTED ***
Wo.
No. DETECTED ***
Wo. DETECTED **
85311m: MARIIE ALGAE (AL), cent.
LMITS: pCl/kg ZN-65 ( 2)
(
3.6 11.5)E 0 11
(
3.6 s 11.5)E 0 no DATA
( 0)
(
-7.9 -
15.1)E D
(
7.9 -
15.1)E O
( 0/ 2)
( 0/ 2)
ZR-95 ( 2)
(
3.8 s 3.0)E 0 11
(
3.8 2 3.0)E O E0 DATA
( 0)
(
8.1 -
68.6)E 1
(
8.1
- 68.6)E 1
( 0/ 2)
( 0/ 2)
AG 110M( 2)
(
-4.2 a 3.3)E 0 11
(
-4.2 a 3.3)E D NO DATA
( 0)
(
7.5 -
0.9)E 0
(
7.5 -
0.9)E O
( 0/ 2)
( 0/ 2)
S8 124 ( 2)
(
-1.6 t 0.0)E 1 11
(
1.6 s 0.0)E 1 NO DATA
( 0)
(
-1.6 -
1.6)E 1
(
-1.6 -
1.6)E 1
( 0/ 2)
( 0/ 2)
CS 134 ( 2)
(
3.5 1 0.3)E O 11
(
-3.5 s 0.3)E 0 NO DATA
( 0)
(
-3.9 -
-3.2)E O
(
3.9 -
3.2)E O
( 0/ 2)
( 0/ 2)
CS 137 ( 2)
(
2.4 2 2.7)E O 11
(
2.4 a 2.7)E O NO DATA
( 0)
(
-3.1 -
50.9)E ~1
(
3.1 -
50.9)E 1
( C/ 2)
( 0/ 2)
ACTH228 ( 2)
(
3.3 2 4.3)E 1 11
(
3.3 4.3)E 1 NO DATA
( 0)
(
1.0 -
7.6)E 1
(
1.0 -
7.6)E 1 l
( 1/ 2)
( 1/ 2)
NOTE: Footnotes may be found at the end of Table 5.1.
34
i TABLE 5.1 ENVIRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
MAlWE YANKEE NUCLEAR POWER STATION, WISCASSET, ME (JANUARY - DECEMSER 1993) 1 INDICATOR STATIONS STATION WITN WICHEST MEAN CONTROL STATIONS
........t................
RADIONUCLIDES
- MEAN MEAN MEAN (No. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)"
LLD NO. DETECTED *"
NO.
NO. DETECTED ***
Wo. DETECTED **
j sEDIUM: MILK (TM)
UNITS: pCl/kg l
SR-89 ( 15)
(
7.4 4.4)E 1 25
(
4.2 1 3.8)E -1
(
4.2 2 3.8)E -1
( 0)
(
3.3 -
0.9)E 0
(
-5.4 -
11.9)E.1
(
5.4 -
11.9)E *1
( 0/ 11)
( 0/ 4)
( 0/ 4)
SR 90 ( 15)
(
5.3 2 0.8)E O 16 (
8.1 2 0.6)E O
(
3.6 2 0.8)E D
( 0)
(
1.4 -
9.4)E 0
(
7.2 -
9.4)E 0
(
1.6 -
5.4)E O
( 11/ 11)
( 4/ 4)
( 3/ 4)
K 40
( 43)
(
1.4 2 0.0)E 3 15
(
1.5 t 0.1)E 3
(
1.4 2 0.0)E 3
( 0)
(
1.1 -
1.7)E 3
(
1.2 -
1.7)E 3
(
1.2 -
1.5)E 3
( 31/ 31)
( 8/ 8)
( 12/ 12) 1-131 ( 43) 1.0
(
4.9 1 2.4)E *2 16 (
9.4 2 4.3)E 2
(
3.0 1 3.3)E 2
( 0)
(
2.9 -
4.5)E 1
(
5.8 -
45.0)E 2
( 10.0 -
23.0)E -2
( 0/ 31)
( 0/ 12)
( 0/ 12)
CS 134 ( 43) 15.
(
-6.2 2.7)E 1 16 (
3.4 2 3.0)E -1
(
7.9 t 4.1)E 1
( 0?
(
-4.2 -
2.2)E 0
(
-1.5 -
2.1)E O
(
2.9 -
1.4)E O
( 0/ 31)
( 0/ 12)
( 0/ 12)
CS-137 ( 43) 18.
(
5.82 0.7)E 0 16 (
6.2 a 0.8)E O
(
2.6 2 0.7)E 0
( 0)
(
3.3 - 175.0)E -1
(
1.5 -
13.4)E 0
(
7.6 -
60.8)E -1
( 21/ 31)
( 10/ 12)
( 3/ 12)
BA-140 ( 43) 15.
(
4.4 2 37.1)E 2 25
(
2.8 t 5.4)E 1
(
2.8 t 5.4)E -1
( 0)
(
-5.9 -
3.6)E O
(
-2.4 -
4.1)E O
(
2.4
- 4.1)E O
( 0/ 31)
( 0/ 12)
( 0/ 12)
NOTE: Footnotes may be found at the end of Table 5.1. 1
i TABLE 5.1 l
ENVIRONMENTAL RADIOLOGICAL PROGRAM SUIO4 ART MAINE YANKEE NUCLEAR POWER STATION, WISCASSET, ME l
(JANUART
- DECEMBER 1993)
INDICATOR STATIONS STATION WITH NIGHEST MEAN CONTROL STATIONS eeeeeeeeeeeeeeeeee eeeeee...eeeeee**eeeeeeee RADIONUCLIDES
- MEAN MEAN MEAN (No. ANALYSES) REQUIRED RANGE STA.
RANCE RANGE (NON ROUTINE)**
LLO NO. DETECTED ***
NO.
NO. DETECTED ***
No. DETECTE0**
IEDitsl FISN (FM) tallTS: pC1/kg I
K 40 ( 4)
(
2.7
- 0.5)E 3 24
(
2.8 2 0.5)E 3
(
2.8 s 0.5)E 3 i
( 0)
(
2.3 -
3.2)E 3
(
2.3 -
3.3)E 3
(
2.3 -
3.3)E 3
( 2/ 2)
( 2/ 2)
( 2/ 2)
MN 54 ( 4) 130.
(
3.2 e 0.6)E O 11
(
-3.2 s 0.6)E O
(
-3.7 2 5.0)E O l
( 0)
(
3.8 -
2.6)E O
(
3.8 -
-2.6)E O
(
-8.8 -
1.3)E 0
( 0/ 2)
( 0/ 2)
( 0/ 2)
Co 58 ( 4) 130.
(
8.0 a 4.3)E 0 11
(
8.0 4.3)E D
(
6.3 a 0.6)E D
( 0)
(
3.8 -
12.3)E 0
(
3.8 -
12.3)E 0
(
-6.9 -
-5.6)E 0
( 0/ 2)
( 0/ 2)
( 0/ 2) i
]
FE 59 ( 4) 260.
(
2.3 a 1.9)E 1 11
(
2.3 t 1.9)E 1
(
3.2 1 13.5)E 0 j
( 0)
(
3.5 -
41.8)E 0
(
3.5 -
41.8)E O
(
1.7 -
-1.0)E 1 j
( 0/ 2)
( 0/ 2)
( 0/ 2) co-60 ( 4) 130.
(
-2.9
- 1.3)E O 24
(
4.9 t 0.7)E 0
(
4.9 s 0.7)E O
( 0)
(
-4.1 -
1.6)E 0
(
4.2 +
5.5)E O
(
4.2 -
5.5)E O
( 0/ 2)
( 0/ 2)
( 0/ 2) 5 ZN 65 ( 4) 260.
(
7.2 t 4.0)E O 24
(
7.5 2 0.4)E O
(
7.5 s 0.4)E 0
( 0)
(
3.3 -
11.2)E O
(
7.1 -
7.8)E O
(
7.1 -
7.8)E O a
( 0/ 2)
( 0/ 2)
( 0/ 2)
AG 110M( 4)
(
9.5 s 6.2)E 0 24
(
-3.0 a 7.9)E D
(
-3.0 s 7.9)E O
( 0)
(
- 1.6 -
0.3)E 1
(
-1.1 -
0.5)E 1
(
-1.1 -
0.5)E 1
( 0/ 2)
( 0/ 2)
( 0/ 2)
$8 124 ( 4)
(
-6.3 t 6.3)E O 24 (
2.5 s 2.5)E O
(
-2.5 s 2.5)E 0
( 0)
(
1.3 -
0.0)E 1
(
5.0 -
0.0)E 0
(
-5.0 -
0.0)E O
( 0/ 2)
( 0/ 2)
( 0/ 2)
CS 134 ( 4) 130.
(
-4.2 s 3.6)E O 24 (
7.2 :
$5.6)E ~1
(
7.2 a 55.6)E ~1 j
( 0)
(
7.5 -
0.6)E 0
(
6.3 -
4.8)E O
(
6.3 -
4.8)E O
( 0/ 2)
( 0/ 2)
( 0/ 2) j CS 137 ( 4) 150.
(
1.7 s 5.1)E 0 24
(
7.0 t 8.2)E 0
(
7.0 s 8.2)E 0
( 0)
(
-3.4 -
6.9)E 0
(
1.2 -
15.2)E 0
(
1.2 -
15.2)E 0 3
( 0/ 2)
( 0/ 2)
( 0/ 2)
NOTE: Footnotes may be found at the end of Table 5.1.
36-
TABLE 5.1 ENVIRONMENTAL RADIOLOGICAL PROGRAM SUD04ARY MAINE YANKEE NUCLEAR POWER STATION, WISCASSET, ME (JANUARY - DECEMBER 1973)
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS RADIONUCLIDES
- MEAN MEAN MEAN (No. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON-ROUTINE)**
LLD Wo. DETECTED ***
NO.
No. DETECTED"*
Wo. DETECTED **
MEDIUM: CRUSTAcDuts (CR)
UNITS: pCl/kg K.40
( 9)
(
2.2 t 0.2)E 3 24
(
2.3 2 0.5)E 3
(
2.3
- 0.5)E 3
( 0)
(
1.9 -
2.8)E 3
(
1.4 -
3.4)E 3
(
1.4 -
3.4)E 3
( 5/ 5)
( 4/ 4)
( 4/ 4)
MN 54 ( 9) 130.
(
3.0 2 2.6)E 0 24 (
3.2 2 2.8)E O
(
3.2 2 2.8)E O
( 0)
(
5.9 -
10.0)E 0
(
1.4 -
11.2)E O
(
1.4 -
11.2)E O
( 0/ 5)
( 0/ 4)
( 0/ 4)
CO 58 ( 9) 130.
(
2.5
- 3.8)E 0 24
(
-1.8
- 1.7)E O
(
1.8
- 1.7)E O
( 0)
(
1,1 -
0.8)E 1
(
-5.5 -
2.8)E O
(
5.5 -
2.8)E O
( 0/ 5)
( 0/ 4)
( 0/ 4)
FE 59 ( 9) 260.
(
-4.4 2 3.7)E O 11
(
-4.4 1 3.7)E O
(
-6.2 2 8.9)E 0
( 0)
(
1.9 -
0.3)E 1
(
1.9 -
0.3)E 1
(
2.9 -
1.3)E 1
( 0/ 5)
( 0/ 5)
( 0/ 4)
CO 60 ( 9) 130.
(
5.0 2 2.2)E O 11
(
5.0 e 2.2)E O
(
4.5 2 0.5)E 'O
( 0)
(
4.6 - 130.0)E -1
(
4.6 - 130.0)E 1
(
).2 -
5.4)E O
( 0/ 5)
( 0/ 5)
( 0/ 4)
ZN 65 ( 9) 260.
(
7.4 4 11.4)E O 11
(
7.4 4 11.4)E O
(
5.9 2 6.3)E D
( 0)
(
3.0 -
3.9)E 1
(
3.0
- 3.9)E 1
(
-4.8 -
23.5)E 0
( 0/ 5)
( 0/ 5)
( 0/ 4)
AG-110M( 9)
(
3.0 2 1.1)E 1 11
(
3.0 t 1.1)E 1
(
1.0 2 0.9)E 1
( 0)
(
5.6 -
67.5 )E D
(
5.6 -
67.5)E O
(
2.9 -
1.5)E 1
( 3/ 5)
( 3/ 5)
( 0/ 4)
SS-124 ( 9)
(
1.6 t 1.0)E 1 11
(
1.6 2 1.0)E 1
(
2.4 2 11.4)E D
( 0)
(
0.0 -
5.3)E 1
(
0.0 -
5.3)E 1
(
2.8 -
2.7)E 1
( 0/ 5)
( 0/ 5)
( 0/ 4)
CS 134 ( 9) 130.
(
5.72 3.4)E 0 11
(
5.7
- 3.4)E 0
(
-5.9 1 6.1)E D
( 0)
(
1.3 -
0.7)E 1
(
1.3 -
0.7)E 1
(
-2.2 -
0.6)E 1
( 0/ 5)
( 0/ 5)
( 0/ 4)
CS-137 ( 9) 150.
(
4.6 2 3.6)E O 24
(
1.0 t 0.4)E 1
(
1.0 2 0.4)E 1
( 0)
(
1.2 -
0.7)E 1
(
3.7 - 174.0)E 1
(
3.7 - 174.0)E *1
( 0/ 5)
( 0/ 4)
( 0/ 4)
I NOTE: Footnotes may be found at the end of Table 5.1. '
4
TABLE 5.1 ENVIRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
MAINE YANKEE NUCLEAR POWER STATION, WISCASSET, NE (JANUARY - DECEMBER 1993) i INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS e...........eeeeee eeeeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeee RADIONUCLIDE$*
MEAN MEAN MEAN 4
(NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)**
LLD No. DETECTED *"
NO.
NO. DETECTED ***
NO. DETECTED **
IEDILM IRJSSELS (IRJ) tmITS:
gCl/kg BE 7 ( 3)
( a3.3 2 4.4)E 1 11
(
3.3 1 4.4)E 1
(
3.4 2 7.4)E 1 3
( 0)
(
7.7 -
1.1)E 1
(
-7.7 -
1.1)E 1
( 0/ 2)
( 0/ 2)
( 0/ 1) j K 40
( 3)
(
1.2 2 0.1)E 3 11
(
1.2 0.1)E 3
(
8.5 2 2.2)E 2 1
( 0)
(
1.1 -
1.3)E 3
(
1.1 -
1.3)E 3 j
( 2/ 2)
( 2/ 2)
( 1/ 1) j MW-54 ( 3) 130.
(
1.3 2 0.6)E 1 24
(
9.9 t 8.0)E 0
(
9.9
- 8.0)E 0
( 0)
(
-2.0 -
0.7)E 1
( 0/ 2)
( 0/ 1)
( 0/ 1)
Co-58 ( 3) 130.
(
-5.3 2 2.1)E 0 11
(
-5.3 2 2.1)E D
(
-5.8 8.8)E O
( 0)
(
7.3 -
3.2)E O
(
-7.3 -
3.2)E O
( 0/ 2)
( 0/ 2)
( 0/ 1)
FE 59 ( 3) 260.
(
1.3 a 0.8)E 1 11
(
1.3 2 0.8)E 1
(
-1.2 2 2.0)E 1
( 0)
(
4.7 -
20.9)E D
(
4.7 -
20.9)E O
( 0/ 2)
( 0/ 2)
( 0/ 1)
CO 60 ( 3) 130.
(
9.4 2 9.7)E 0 11
(
9.4 9.7)E 0
(
0.0 1 1.1)E 1
( 0)
(
2.5 - 191.0)E 1
(
2.5 191.0)E -1
( 0/ 2)
( 0/ 2)
( 0/ 1)
ZN 65 ( 3) 260.
(
1.5 2 0.8)E 1 11
(
1.5 2 0.8)E 1
(
3.7 2 1.9)E 1 4
( 0)
(
2.3 -
-0.8)E 1
(
2.3
-0.8)E 1
( 0/ 2)
( 0/ 2)
( 0/ 1)
AG 110M( 3)
(
1.3 2 0.3)E 1 24
(
1.2 1 1.1)E 1
(
1.2 1.1)E 1
( 0)
(
1.6 -
1,1)E 1
( 0/ 2)
( 0/ 1)
( 0/ 1) s
$8 124 ( 3)
(
9.2 e 9.2)E O 11
(
9.2 2 9.2)E O
(
2.2 2 2.5)E i
( 0)
(
0.0 -
1.9)E 1
(
0.0 -
1.9)E 1
( 0/ 2)
( 0/ 2)
( 0/ 1)
POTE: Footnotes may be fomd at the end of Table 5.1.. - -..
TABLE 5.1 ENVIRONMENTAL RADIOLOGICAL PROGRAM SLM4ARY 3
MAINE YANKEE MUCLEAR POWER STATidi, WISCASSET, ME (JANUARY DECEM8ER 1993) 1 INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS RADIONUCLIDES
- MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)"
No.
No. DETECTED"*
No. DETECTED **
IEDitat: ItJSSELS (IRJ), cont.
LallTS: pCl/kg CS.134 ( 3) 130.
(
1.6 a 1.2)E. 1 11
(
-1.6 2 1.2)E 1
(
-1.7 a 1.1)E 1 4
3
( 0)
(
2.9 -
-0.4)E 1
(
-2.9
-0.4)E 1
( 0/ 2)
( 0/ 2)
( 0/ 1)
CS-137 ( 3) 150.
(
1.3 0.3)E 1 24
(
4.6 t 10.1)E D
(
4.6 2 10.1)E 0
( 0)
(
1.5 -
1.0)E 1
( 0/ 2)
( 0/ 1)
( 0/ 1)
IED!Lat: SILT FRG4 INTAKE tallTS: pcl/kg BE 7 ( 11)
(
6.4 1 1.4)E 2 04
(
9.3 0.2)E 2 No DATA
( 0)
(
6.1 - 175.0)E 1
(
9.1 -
9.5)E 2
( 9/ 11)
( 2/ 2)
K 40 ( 11)
(
1.1 2 0.2)E 4 06 (
2.1 2 0.1)E 4 NO DATA
( 0)
(
4.2 -
21.0)E 3
( 11/ 11)
( 1/ 1)
MN 54 ( 11)
(
3.7 1 2.7)E O 02
(
4.1 2 39.1)E -1 NO DATA
( 0)
(
2.3 0.7)E 1
(
-7.1 -
6.2)E D
( 0/ 11)
( 0/ 3)
CO-58 ( 11)
(
1.9 t 1.0)E 1 02 (
4.8
- 1.2)E 1 NO DATA
( 0)
(
1.6 -
8.0)E 1
(
2.5 -
6.3)E 1
( 4/ 11)
( 3/ 3)
FE 59 ( 11)
(
6.5 8.1)E O 04
(
4.71 2.8)E 1 NO DATA
( 0)
(
2.9 -
7.6)E 1
(
1.9 -
7.6)E 1
( 0/ 11)
( 0/ 2)
CO-60 ( 11)
(
5.0 t 1.8)E 1 04
(
1.4 2 0.8)E 2 NO DATA
( 0)
(
0.0 -
2.2)E 2
(
5.7 -
22.4)E 1
( 8/ 11)
( 2/ 2)
ZN 65 ( 11)
(
3.5 a 54.5)E 1 04
(
1.1 2 2.9)E 1 No DATA
( 0)
(
1.9 -
4.0)E 1
(
1.8 -
4.0)E 1
( 0/ 11)
( 0/ 2)
NOTE: Footrvates may be found at the end of Table 5.1.
39
TABLE 5.1 ENVIRONNENTAL RADIOLOGICAL PROGRAM SUDMARY MAlWE YANKEE NUCLEAR POWER STAfl0N, WISCASSET, ME (JANUARY - DECEMBER 1993)
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS e.................
RADIONUCLIDES
- MEAN MEAN MEAN (No. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE i
(NON ROUTINE)**
LLD No. DETECTED ***
No.
No. DETECTED ***
NO. DETECTED **
]
86!LM: SILT SPREAD ON-SITE, cent.
LAIITS: pCl/kg i
ZR 95 ( 11)
(
1.7 2 0.8)E 1 04
(
5.0 t 2.7)E 1 NO DATA
( 0)
(
1.2 -
7.7)E 1
(
2.3 -
7.7)E 1
( 0/ 11)
( 0/ 2)
AG-110N( 11)
(
1.9 2 0.6)E 1 04
(
3.9 2 1.6)E 1 NO DATA
( 0)
(
1.9 -
5.5)E 1
(
2.3 -
5.5)E 1
( 3/ 11)
( 1/ 2) 1 131 ( 11)
(
-9.2 2 6.7)E O 01
(
1.62 1.5)E 1 No DATA
( 0)
(
-5.7 -
1.6)E 1
( 0/ 11)
( 0/ 1)
CS 134 ( 11)
(
3.5 t 2.0)E O 06
(
1.3 2 0.8)E 1 NO DATA
( 0)
(
-8.1 -
13.3)E O
( 0/ 11)
( 0/ 1)
CS 137 ( 11)
(
7.3 t 2.0)E 1 04
(
1.6 2 0.8)E 2 NO DATA
( 0)
(
7.7 - 237.0)E 0
(
8.2 -
23.7)E 1
( 8/ 11)
( 2/ 2)
RA-140 ( 11)
(
6.4 2 3.7)E O 05
(
2.1 1 1.8)E 1 NO DATA
( 0)
(
1.1 -
2.2)E 1
( 0/ 11)
( 0/ 1)
ACTH228 ( 11)
(
4.6 1 0.6)E 2 06 (
8.5 t 0.6)E 2 NO DATA
( 0)
(
2.6 -
8.5)E 2
( 11/ 11)
( 1/ 1)
NOTE: Footnotes may be found at the end of Table 5.1.
40
l Footnotes to Table 5.1:
The only radionuclides reported in this table are those with LLD regstrements and those for which positive radioactivity was detected. See Section 5 of this report for a discussion of other radionuclides that were analyzed.
i Non Routine refers to those radionuclides that exceeded the Reporting Levels in Technical specification Table 4.8-3.
- The fraction of semple anstyses yielding detectable measurements (i.e. > 3 standard deviations) is shown in parentheses.
1 1
'l i
l...
I TABLE 5.2 ENVIRONMENTAL TLD DATA SUMMART MAINE YANKEE NUCLEAR POWER STATION, WISCASSET, ME (JANUART - DECENSER 1993) j i
l INNER RING TLos ALTER RING TLDs STATION WITH NIGHEST MEAN CONTROL TLDs MEAN MEAN MEAN MEAM RANCE RANGE
$TA.
RANGE RANGE (MO. MEASUREMENTS)
(NO. MEASUREMENTS)
MO.
(No. MEASUREMENTS)*
(NO MEASUREMENTS) 7.4 1.1 7.3 1.1 09 9.8
- 2.2 8.0 a 1.4 4.6 - 11.6 5.1 - 10.4 7.2 11.6 6.3 - 10.5 (71)
(68)
(3)
(12)
- Each " measurement" is based typically on q'arterly readings from six TLD elements.
-42 1
4 1
TABLE 5.3 4
ENVIRONMENTAL TLD MEASUREMENTS
)
1993 f
(Micro R per Hour) j ANNUAL Sta.
1ST QUARTER 2ND QUARTER' 3RD QUARTER 4TH QUARTER AVE.
l No.
Description EXP.
5.0.
EXP.
S.D.
EXP.
S.D.
EXP.
S.D.
EXP.
j TL 01 Old Ferry Rd.
6.3 e 0.3 7.4 0.2 8.6 2 0.3 7.8 2 0.2 7.6 TL 02 old Ferry Rd.
6.1 0.2 7.1 2 0.3 8.4 a 0.3 7.3 a 0.2 7.3 TL-03 Bailey House (ESL) 6.3 2 0.4 7.3 a 0.2 8.3 2 0.4 7.3 2 0.2 7.3 TL-04 Westport lat./Rt.144 4.6 & 0.2 6.5 0.2 7.9 2 0.3 6.2 a 0.3 6.3 TL-05 MY Information Cent.
7.0 t 0.3 7.5 t 0.3 9.0 t 0.3 8.1 0.3 7.9 1
TL-06 Rt.144/Greenleaf Rd.
7.2 2 0.2 7.8 0.2 8.9 0.2 8.0 t 0.3 8.0 TL 07 Westport Isl./Rt.144 6.1 s 0.1 7.8 0.3 8.6 0.4 7.9 0.2 7.6 TL 08 MT Screenhouse 6.5 0.4 6.9
- 0.3 7.9 2 0.3 7.1 1 0.2 7.1 TL 00 Westport lat./Rt.144 7.1 2 0.4 11.6 2 0.4 10.5 0.2 9.8 TL 10 Bailey Pt.
6.4 s 0.3 6.6 2 0.3 7.8 s 0.2 7.1 t 0.2 7.0 TL-11 Mason Station 6.5 t 0.2 8.0 t 0.2 9.0 2 0.2 7.9 0.2 7.9 I
TL 12 Westport Firehouse 6.5.s 0.3 7.3 2 0.3 8.3 a 0.2 7.7 0.2 7.4 i
TL-13 Foxbird Island 7.0 t 0.2 7.8 2 0.3 8.8 2 0.2 8.0 2 0.2 7.9 TL 14 Eaton Fare 5.0 2 0.4 6.7 0.8 7.9 2 0.3 6.9 2 0.3 6.9 TL 15 Eaton Farm 5.1 2 0.4 6.4 1 0.3 7.3 a 0.1 6.4 2 0.1 6.3 TL 16 Eaton Farm 5.9 e 0.1 7.2 a 0.2 8.3 2 0.2 7.3 2 0.3 7.1 l
TL-17 Eaton Farm Rd.
6.6 2 0.1 8.5 2 0.3 9.5 2 0.3 8.6 0.2 8.3 1
TL 18 Eston Farm ad.
5.8 0.3 7.3 2 0.1 8.2 2 0.2 7.4 s 0.2 7.2 TL 19 Eaton Farm Rd.
5.8 t 0.3 6.7 2 0.2 7.8 2 0.2 6.7 2 0.2 6.7 TL 20 gradford Rd.
5.3 2 0.1 7.0 t 0.2 7.7 e 0.1 7.6 2 1.1 6.9 TL-21 Federal St.
5.5 2 0.2 7.3 2 0.2 7.9 0.3 7.2 2 0.3 7.0 TL-22 Cochran Rd.
5.8 0.2 7.3 2 0.4 8.3 2 0.3 7.7 0.4 7.3 I
TL 23 Middle Rd.
7.3 2 0.1 9.1 2 0.2 10.4 2 0.6 9.5 2 0.5 9.1 4
TL 24 River Rd.
6.2 0.3 7.4 2 0.3 8.1 0.3 7.6 2 0.2 7.3
)
TL-25 River Rd./Rt.27 5.8 s 0.2 7.5 t 0.2 8.3 a 0.1 7.5 2 0.3 7.3 TL-26 Boothbay RR Museun 6.3 a 0.3 7.6 0.2 8.1 a 0.3 7.6 2 0.2 7.4 TL 27 sorters latand 5.9 0.2 7.0 2 0.2 8.1 0.3 7.5 t 0.1 7.1 TL-28 Rt.144/E. Shore Rd.
5.1 s 0.3 7.0 2 0.1 7.5
- 0.2 6.8 0.3 6.6 a
TL 29 Harrison's Trailer 5.9 0.3 6.6 2 0.2 7.3 a 0.2 6.9 0.2 6.7 TL 30 Leeman Fa n 7.0 t 0.1 8.3 2 0.4 8.8 0.2 8.3 2 0.2 8.1 i
I TL-31 Barley Neck Rd.
7.4 2 0.4 8.0 2 0.2 9.1 0.2 8.8 0.2 8.3 i
TL-32 Baker Farm 6.0 t 0.3 7.7 s 0.3 8.6 2 0.2 7.6 2 0.2 7.5 TL-33 Rt.127 5.5 2 0.3 7.0 t 0.5 7.8 2 0.2 7.0 t 0.2 6.8 TL 34 Rt.127 5.5 2 0.3 7.0 2 0.2 8.0 s 0.2-6.9 2 0.4 6.9 TL-35 Rt.127 5.4 2 0.2 6.6 2 0.1 7.9 0.2 6.9 s 0.2 6.7 TL-36 Boothb.Hbr. Fire Ste.
6.5 0.1 6.6 2 0.1 7.2 s 0.2 7.1 a 0.2 6.9 J
TL-37 Bath Fire Sta.
10.5 t 0.1 9.9 2 0.3 9.3 0.2 9.2 a 0.3 9.7 TL-38 Dresden Substation 6.3 2 0.3 7.5 t 0.1 8.3 1 0.1 7.8 0.4 7.5
- TLD tost, apparently due to vandalism.
1 a
43 4
d
2 4
6.
ANALYSIS OF ENVIRONMENTAL RESULTS 6.1 Samoling Program Deviations I
Table 2.3 of the Offsite Dose Calculation Manual (ODCM) allows for deviations in the REMP 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 i
effectiveness and in fact are considered insignificant with respect to what is normally anticipated for any radiological environmental monitoring program.
The specific deviations for 1993 were as follows:
e The TLDs at station TL-09 were lost for the second quarter of 1993.
The apparent cause was vandalism.
e The following short power outages occurred at air sampling stations
]
during 1993:
a) 3.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the week of February 5-12 at AP/CF-16; b) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the week of April 16-23 at AP/CF-14; c) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during the week of May 21-28 at AP/CF-16; d) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during the week of June 4-11 at AP/CF-13 and AP/CF-16; e) 2.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during the week of June 11-18 at AP/CF-29; f) 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> during the week of July 16-23 at AP/CF-14; g) 2 l
hours during the week of September 10-17 at AP/CF-29; and h) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
]
during the week of November 26 to December 3 at AP/CF-16.
1 e Milk was not available at the Mitman location (TM-15) on the following sample dates: February 4, March 3 and April 1, 1993, i
e A milk sample was not available at the Chewonki location (TM-18) on 4
October 7, 1993 due to the death of the milk cow.
The following interruptions occurred in the automatic sampling of estuary water at the Plant Outfall location (WE-12) during 1993:
a) Five days of l
sampling were lost during the period February 12-19 due to a malfe.setion of the suction line (the suction line was replaced); b) Six days sare
]
lost during the period April 9-16 when the switch was accidentally set to 0FF; c) Six days were lost during the period May 28 - June 7 due to a 4
malfunction of the suction line (the suction line was replaced); d) Two j
days were lost during the period June 7-11 due to a power outage; e) One-half day was lost during the period August 27 - September 3 due to an automatic shutoff of the unit when the sample bottle was full (the setting for sample volume was decreased); f) One-half day was lost during the period October 1-8 due to a power outage; g) Two days were lost during the period October 8-15 due to an automatic shutoff of the unit a
1 i
)
1
d when the sample bottle was full (the setting for the sample volume was decreased); h) Several hours were lost during the period' October 22-29, apparently due to an automatic shutoff of the unit when the sample bottle j
was full (the setting for the sample volume was decreased); and i)
Between three and four days were lost due to freezing of the suction line j
(the suction line was replaced and heat tape was installed on the line).
- The mussel sample collected at the control location MU-24 on September 27, 1993 was destroyed en route to the analytical laboratory by UPS.
e i,
6.2 Comnarison of Achieved LLDs with Reauirements 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.) On occasion, an LLD is not achievable due to a situation such as a low sample volume caused by sampling equipment malfunction.
In such a case, ODCM Appendix C, Section 1 requires a discussion of the situation. At the Yankee Atomic Environmental Laboratory, the target LLD j
for any analysis is typically 30-40 percent of the most restrictive required LLD.
Expressed differently, the typical sensitivities achieved for each analysis are at least 2.5 to 3 times greater than that required by the Maine Yankee ODCM.
4 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 j
with the required LLD.
Of the over 3700 analyses performed during 1993, of I
which approximately 1200 had an associated LLD in Table 2.4, all met'the i
required LLD.
1 4
1 6.3 Comparison of Results Against Reportine Levels
}
Section 2.4.3.3 of the ODCM requires the notification of the NRC (via the i
Semiannual 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 l
50, Appendix 1.
It should be noted that environmental concentrations are j
averaged over calendar quarters for the purposes of this comparison, and that Reporting Levels apply only to measured levels of radioactivity due to plant effluents. During 1993, no Reporting Levels were exceeded.
i 1 :
I i
\\
)
6.4 Data Analysis by Media Tvve
]
The 1993 REMP data for each media type is discussed below. Whenever a specific measurement result is presented, it is given as the concentration plus or minus one standard deviation.
This standard deviation represents only the random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure. A sample is considered to yield a " detectable measurement" when the concentration exceeds three times its associated standard deviation.
With respect to data plots, it should be noted that all values for a given graph are plotted, whether or not they are considered statistically significant.
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 Bross-beta radioactivity. 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 are shown in Table 5.1 and Figures 6.1 through 6.5.
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 quarter.
The peak seen in the second quarter of 1986 is airborne contamination resulting from the Chernobyl accident, as detected by the Maine Yankee monitoring program.
Figures 6.2 through 6.5 show the weekly gross beta concentration at each air particulate sampling location alongside the same for the control air particulate sampling location at AP-29 (Dresden Substation).
It can be readily seen that the gross-beta measurements on air particulate filters fluctuate significantly over the course of a year.
The measurements from control station AP-29 vary similarly, indicating that these fluctuations are due to regional changes in naturally-occurring airborne radioactive materials, and not due to Maine Yankee operations. Table 5.1 shows that the mean concentrations from indicator stations are approximately equal to those from control locations, further supporting this conclusion.
The only other radionuclide detected on air particulate filters was Be-7, a
. _ - _ _ -.- - ~. _ _ _. _ _ _
f naturally-occurring cosmogenic radionuclide.
6,4.1.2 Charcoal Cartridres The weekly charcoal cartridges from each of the five air sampling sites were analyzed for I-131.
The results of these analyses are summarized in Table 5.1.
As in previous years, no I-131 was detected in any charcoal cartridge during 1993.
6.4.1.3 Mixed Grasses Although not required by the Maine Yankee ODCM, mixed grass samples were collected twice at the Environmental Services facility during 1993. No radionuclides attributable to Maine Yankee operations were detected in either sample.
Naturally-occurring K-40 and Be 7 were detected in all three samples, as expected.
6.4.2 Waterborne Pathways 6.4,2.1 Estuarv Vater Aliquots of estuary water were automatically collected in the discharge canal outfall every two hours during 1993.
These composited samples were collected monthly and sent to the Yankee Atomic Environmental Laboratory for analysis. Monthly grab samples at the control location were also collected. Table 5.1 shows that naturally-occurring K-40 was detected in most samples, as is typical with sea water.
No gamma-emitting radionuclides attributable to Maine Yankee operations were detected in any of the samples.
For each sampling site, the monthly samples were composited into qua'rterly samples for Tritium (H-3) analyses.
One of the.four samples at station WE-12 (Discharge Canal Outfall) showed detectable levels of H-3 due to plant operations.
The concentration for this sample, which was collected over the first quarter of 1993, was 670 i 210 pCi/kg.
In accordance with Table j
5.1 of the ODCM, a dilution factor of 10 is applied to this concentration since the samples were taken from the discharge. forebay, prior to release to the Back River via the underwater diffusers.
The resulting maximum concentrations of 67 pC1/kg may be compared against the NRC Reporting Level of 30,000 pCi/kg.
(If this Reporting Level was reached, the Maine Yankee 47
i ODCM would require notification to the NRC in the Semiannual Effluent Release Report.)
6.4.2.2 Ground Water Although not required by the Maine Yankee ODCM, quarterly ground water samples were collected from the well at the Environmental Services building and at a control site.
The results of the gamma and H-3 analyses are shown in Table 5.1.
No H 3 or gamma-emitting radionuclides were detected in any 1
of these samples.
In 1989 several ground water monitoring wells were installed on the Maine Yankee site to monitor the effects of a sodium chromate spill in 1988.
4 (These are not part of the Radiological Environmental Monitoring Program, and are not shown on the maps in section 4.)
An additional monitoring well was installed in 1992 for the closure of the ferrous sulfate tank.
To characterize the ground water in the vicinity of the Maine Yankee facility, a series of ground water samples was collected in June of 1993 at these wells, and a single plant well sample was collected in September. These results are summarized in Table 5.1, along with the routine quarterly ground water samples collected from WG-13 and WG-24.
No gamma-emitting radionuclides, other than Be-7 (a naturally-occurring cosmogenic radionuclide) in one sample, were detected.
H-3 was detected, however, in two of the nine on-2ite samples.
The maximum concentration of 640 i 110 I
pCi/kg from on-site well no. B-205 did not exceed the Reporting Level for H-3 in drinking water of 20,000 pCi/kg as given in Table 2.5 of the ODCM.
6.4.2.3 Shoreline Sediment d
i Semiannual sediment core samples were collected from two on-site locations during 1993.
Each set of samples was segmented by depth (0-5, 5-10, 10-15 cm) and analyzed for gamma-emitting radionuclides. As would be expected, naturally-occurring K-40 and Ac-Th-228 were detected in all samples.
In addition to the above radionuclides, Cs-137 was detected in all twelve of the segments. Although some Cs-137 is expected to be present from worldwide weapons testing fallout, much of it is due to early plant operations.
In the early years of plant operation, routine liquid effluents were discharged in the sediment-collection area.
Due to poor diffusion with this method, an underwater diffuser was installed, and now the liquid effluents are discharged into the Back River.
The Cs-137 levels.-
a t
in sediment are plotted in Figures 6.6 and 6.7.
These graphs show that the l
1evels have not changed significantly over the past several years.
I Although there is no Reporting Level for Cs-137 in sediment samples, one might appreciate the negligible dosimetric consequence when the measured j
concentrations are compared against the reporting levels for fish (which, l
unlike sediment, are assumed to be eaten by the public).
The mean and maximum Cs-137 measurements were 210 and 370 pCi/kg (dry), respectively, well under the Cs-137 Reporting Level in fish of 2000 pCi/kg (wet).
6.4.2.4 Marine Alzae Although not required by the Maine Yankee ODCM, mixed samples of Pucus and j
Ascochv11um marine algae (" seaweed") were collected at Long Ledge in June i
and September of 1993. All samples were analyzed for gamma-emitting j
radionuclides. As expected, naturally-occurring K 40 was detected on all s ample s. Naturally occurring Be 7 and Ac-Th-228 were each detected in one j
sample. No gamma emitting radionuclides attributable to plant operations were detected on these samples.
1 6.4.3 Ingestion Pathways I
6.4.3.1 Milk i
Milk samples (consisting of either cow or goat milk) from several farms
)
were collected monthly during 1993. Although samples are only required from three locations by the Maine Yankee ODCM, they were collected from up i
to four locations during 1993.
Each sample was analyzed for I-131 and j
other gamma-emitting radionuclides. Quarterly composites (by location) j were analyzed for Sr-89 and Sr-90.
i j
As was expected, naturally-occurring K-40 was detected in all samples.
(
Also expected was Cs-137 and Sr-90.
Cs-137 was detected in 21 out of 31 l
indicator samples and 3 out of 12 controls.
Sr-90 was detected in all l
indicator samples and 3 out of 4 controls. Although both are a by-product of plant operations, the levels detected in milk are due to worldwide fallout from nuclear weapons tests, and to a much lesser degree from fallout from the Chernobyl incident.
These two. radionuclides are present throughout the natural environment as a r sult of atmospheric nuclear weapons testing that started primarily in the late 1950's and continued through 1980.
They may be found in soil and vegetation, as well as t
49-I i
,r 1
e
__...~,--m.,..,.--
i-.... ~.. - -. --
... -. - - -... ~
J l
4 1
anything that feeds upon vegetation, directly or indirectly.
Considerable variation is found to occur in allk samples from one farm to another, depending on the soil, vegetation and farming practices at each location.
j The Cs 137 and Sr-90 levels shown in Table 5.1 and Figures 6.8 and 6.9 are consistent with those detected at other New England farms that are monitored as part of other Yankee affiliated environmental monitoring
]
programs.
i 1
1 6.4.3.2 Fish & Invertebrates Semiannual samples of fish and invertebrates were collected from two j
locations during 1993. On June 30, striped bass were collected from FH-11 and mackerel from FH 24.
On September 28, flounder were collected from FH-11 and mackerel from FH 24.
Invertebrate samples consisted of lobsters, rock crabs and blue mussels.
The edible portions of each of these were analyzed for gamma-emitting radionuclides. As expected in biological 4
matter, naturally occurring K 40 was detected in all samples, i
Three of the four crab samples from Long Ledge contained Ag-110m.
The measured concentrations were:
40.4 9.5 pCi/kg on June 30, 24.3 1 6.0 l
pCi/kg on September 27, and 67 17 pCi/kg on October 25.
These levels are consistent with the low-levels of Ag 110m detected in marine algae and 3
crabs at this location during 1992.
To put this level in perspective, the j
dose was calculated, using USNRC Regulatory Guide 1.109 (Reference 7) t methodology, for a hypothetical individual who consumes a large but j
credible amount of these crabs (5 kilograms per year) at the maximum 1993 I
concentration of 67 pCi/kg Ag 110m.
The resulting. dose was 0.02 mrem per year. This may be compared to an estimated 200 mrem per year received by the average individual from natural background radiation each year
)
(Reference 4).
1 Neither of the two lobster samples collected from this location in 1993
[
showed detectable levels of Ag-110m or any other gamma-emitting radionuclide.
i 6.4.4 Direct Radiation Pathway l
Direct radiation is continuously measured at 38 locations surrounding the Maine Yankee plant with the use of thermoluminescent dosimeters (TLDs).
These are collected every calendar quarter for readout at the Maine Yankee Environmental Services Laboratory.. - -
,~
l t
l 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 naturally-occurring radionuclides in the underlying soil, rock or nearby j
building materials result in different radiation levels between one field site and another.
This explains why the control TLD station at the Bath'
{
Fire Station (TL-37, 7.0 km from the plant), which has been located close to a brick building, has historically had the highest mean exposure (see also Figure 6.20).
It is located near a brick building. At the beginning of the second quarter of 1993, it was moved further away from the building, and the measured quarterly exposure decreased slightly.
It can be seen from Figure 6.17 that the TLD at Middle Road in Edgecomb (TL-23) has historically given slightly elevated readings. This is apparently due to its close proximity to a ledge outcrop. A similar situation has recently occurred at Westport Siren (TL-09). To prevent vandalism of the TLD, it was moved to a less conspicuous area not far from the original site at the start of the third quarter of 1993.
The new site is closer to a rock outcrop, and consequently the exposures have increased slightly (see Figure 6.13), making it the station with the highest annual mean exposure (see Table 5.2).
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 significantly different in 1993.
This indicates no significant overall increase in direct radiation exposure rates in the plant vicinity.
It can also be seen I
from these tables that the Control TLD mean exposure rate was not significantly different than that at the Inner and Outer Rings.
6.4.5 Silt from Circulating Water System Intake Bavs Maine Yankee's Circulating Water System provides ocean water for condenser cooling, drawn from the adjacent Back River.
During the 1993 refueling l
outage, approximately 10 to 20 cubic yards of silt and mussel shells were removed from the Circulating Water System Intake Bays.
This material accumulates as a normal consequence of water use, and contains trace levels of radioactivity which are attributable to licensed Maine Yankee liquid effluents. This material is being handled on site under a license issued by the Maine Department of Environmental Protection.
(The samples locations are not shovn on the maps in Section 4 since the samples were not part of the Radiological Environmental Monitoring Program.) This material also contains a small amount of sediment from the one-time cleaning of the Service Water pipes.
Several hadionuclides identified at low levels (see Table 6.1) are attributable to plant effluents, namely Co-58, Co-60, Ag-110m and Cs-137, although it is likely that at least some of the Cs-137 may be due to nuclear weapons testing fallout. The Be-7, K-40 and AcTh-228 are all naturally-occurring radionuclides.
j' 4
b 1
i I
L r
f 1
I I
J l
Figure 6.1 Gross-Beta Measurements on Air Particulate Filters Quarterly Average Concentrations 0.16 0.16 Chernobyl 0.12-
-0.12 O
E f
3 0.08-
- 0. 08-
.O D
~
b a.
0.04-
- 0.04 b E *'g
- 8 d
Ed g %gM g[g 8
as lir g
g gg g
0 0
1984 1986 1988 1990 1992 1994
-t3-Indicator Stations
-w-Control Station 1
]
i Figure 6.2 Gross-Beta Measurements on Air Particulate Filters 0.06 0.06 0.05
-0.05 ka 3
0.04 2
- 0.04 o
5 O
Q U
g 0.03-
-0.03 3
D k
x x
hx
.XJ d
0.02 2
~ /g M
%/
- 0.02 L
ct g
W D
a f-0.01i
[
c*
- 0.01 g
0 O
Dec Feb Apr Jun Aug Oct Dec 1993
-cj-AP-11 Montsweag Brook
-x - AP-29 Dresden Substation (Control) i Figure 6.3 Gross-Beta Measurements on Air Particulate Filters 0.06 C 06 0.05-
- 0.05 y
~
O 0.04-
- 0.04 y
0.03-
- 0.03 1
xx R
x a
D Op y
o' g
9 Q.
s 9-a @xW 8l h,
/
[- 0. 02 o(
F
- I d
0.02 -
X P
(
0 1
~
h
- 0.01 0.01 -
g 0
~ 0 0
i i
i Dec Feb Apr Jun Aug Oct Dec' i
1993 j
-e-AP-13 Bailey Fa rm (ESL)
-x - AP-29 Dresden Substation (Control) 4
}
l.. _
Figure 6.4 Gross-Beta Measurements on Air Particulate Filters i
0.06 0.06 0.05-0.05 U
~
g 0.04-
- 0.04 E
U X
j 0.03-
- 0.03 x
o x
a
?
~
,X
- gg k 0.02 k-h0.02 1
[
a d
Nidi o
$pd R
- 0.01 0.01-0 0
~
o Dec Feb Apr Jun Aug Oct Dec 1993
-c}-
AP-14 Mason Steam Station
-x - AP-29 Dresden Substation (Control) 1
' l
Figure 6.5 Gross-Beta Measurements on Air Particulate Filters 0.06 0.06 0.05-
- 0.05 4;
0.04-
- 0.04 c)
E U
X j
0.03-tg
- 0.03 0.02 -
N
- 0.02 g 9*>/ Ah/
i O
0 0.01-m Q
- 0.01 0
0
'O Dec Feb Apr Jun Aug Oct Dec 1993 9 AP-16 Westport Firehouse x.
AP-29 Dresden Substation (Control) - -
1 l
1 1
i
?
I i
Figure 6,6 l
Cesium-137 in Shoreline Sediment i
Station SE-16, Old Outfall Area l
600 600 500
- 500 l
i 400-
-400 l
t 4
i 3
l
}
300-
-300 u
~
l N
.a i
A 200-
-200 n,
o l
S/90 10/90 5/91 10/91 5/92 10/92 5/93 10/93 5
i Month / Year l
1 E o - 5 cm i
E 5 - 10 cm j
O 10 - 15 cm I
3 1
1 l,
4 i !
j i
Figure 6.7 Cesium-137 in Shoreline sediment l
Station SE-18, Foxbird Island 600 600 e
- 500 500
'400 400 g
t e
300-
- 300 200-200
""d R-l""
5/90 10/90 5/91 10/91 5/92 10/92 5/93 10/93 Month / Year M o - 5 cm 3 5 - 10 cm C 10 - 15 cm 1
Figure 6.8 Cesium-137 in Milk Annual Average Concentrations 40 40 30-
-30 o
~
x 3 20 -
,0x
-20 0
/
N
/
\\
/
O Q
k 10 --
-10
~
J
~
B" N 0;
0 i
1983 1985 1987 1989 1991 1993 4
4
-e--
TM-15 Mitman Farm i
-e-TM-16 Baker Farm v TM-18 Chewonki Foundation 6
TM-25 Hanson Farm i
Figure 6.9 Strontium-90 in Milk Annual Average Co'ncentrations 25 25 i
20-
-20 1
~
l
-15 15-i s
10-
\\
-10
\\_,
g
~
O
\\
5-N
-5 h
0 0
1983 1985 1987 1989 1991 1993
--{y-TM-15 Mitman Farm
-O--
TM-16 Baker Farm TM-18 Chewonki Foundation c.
TM-25 Hanson Farm 1
Figure 6.10 Exposure Rato at Inner Ring, Outer Ring and Control TLD'S 1
25 25 20-
' 20 u
~
D O*
15-
_15 u
Gl O.
a:
i
-10 0
10-3
\\
[i%
5-
-5 0
0 i
i i
1989 1990 1991 1992 1993 1994 Retrieval Date
-c-Inner Ring 4
Outer Ring X-Control Figure 6.11 Exposure Rate at Inner Ring TLDS, TL 01-04 25 25 20--
-20 0
15)
-15
~
c.
C4 o
10-3
-10 5-
/
-5 0
0 i 1989 1990 1991 1992 1993 1994 Retrieval nate TL-01 Old Ferry Road x
TL-02 old Ferry Road
--g--
TL-03 Bailey House (ESL)
TL-04 Westport Island, Rt.144
Figure 6.12 Exposure Rate at Inner Ring TLDS, TL 05-08 25 25 20-
-20 u
o O
15-
-15 oc.
10
-10
$l g g ~, kWd%4 yA 5-
-5 0
,,,o 1989 1990 1991 1992 1993 1994 Retrieval Date t3-TL-05 MY Information Center x
TL-06 Rt. 144 and Greenleaf Road e
TL-07 Westport Island, Rt. 144 c
TL-08 MY Screenhouse l 1
Figure 6.13 Exposure Rate at Inner Ring TLDS, TL 09-10, 12-13 25 25
~
20-
-20 u
1 3
l S
)
15-
-15 10-
[
D
-10 0
,.,A O AW5g mp
.~
- n 2:
g j
5_
-5 M
0 0
i i
1989 1990 1991 1992 1993 1994 Retrieval Date
--c}-
TL-09 Westport Siren
-c TL-10 Baily Point 6
TL-12 Westport Firehouse o
TL-13 Foxbird Island l
l i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _. _ _ - - _ _ - _ - - - - _ _ _ - - - _ _ _ _ _ -
1
4 Figure 6.14 Exposure Rate at Inner Ring TLDS, TL 14-16 t
25 25 i
20-
-20 1
y 0
O i
15-
-15
^
W t
0 a:
~
o 10-
-10 u
g'N
'q p k O
0 i
i 1989 1990 1991 1992 1993 1994 Retrieval Date 4
-c-TL-14 Eaton Farm
-x-TL-15 Eaton Farm f
-e TL-16 Eaton Farm 4
-se-
l Figure 6.15 Exposure Rate at Inner Ring TLDS, TL 17-19 25 25 2,0-
-20 W
S
- n 15-
-15 p
c)
Q.
l b
eyQ %N%"f%,
-5 5-O 0
i 1989 1990 1991 1992 1993 1994 Retrieval Date
--o-TL-17 Ea ton Fa rm x
TL-18 Eaton Farm
-n--
TL-19 Eaton Farm i
Figure 6.16 Exposure Rate at Outer Ring TLDS, TL 11, 20-22 25 25 20-
-20 l
I h
o*
15-
-15 u
a:
g 10--
NN
-10 o
9'
~
O 0
i i
1989 1990 1991 1992 1993 1994 Retrieval Date
-e-TL-11 Mason Station x
TL-20 Bradford Road, Wiscasset l
6 TL-21 Federal Street, Wiscasset c.
TL-22 Cochran Road, Edgecomb Figure 6.17 Exposure Rate at Outer Ring TLDS, TL 23-26 25 25 20-
-20 u
D O*
15-
-15 u
s
~
\\
C3 o
10-x
,e- -
-10 T4 g
g 5-
-5 Oj 0
1989 1990 1991 1992 1993 1994 Retrieval Date I
-e-TL-23 Middle Road, Edgecomb x
TL-24 River Road, Edgecomb
--n--
TL-25 River Road and Route 27 l
c.
TL-26 Rt. 27 and Boothbay RR Museum
! l
._ --- J
Figure 6.18 Exposure Rate at Outer Ring TLDS, TL 27-30 25 25 G
20-
-20 5
O*
y 15-
-15 e
.{
a o
5-x
-5
~
Oj 0
1989 1990 1991 1992 1993 1994 Retrieval Date
-c-TL-27 Barters Island x
TL-28 Westport Island, Rt 144 & East Shore Rd 6
TL-29 Harrison's Trailer c.
TL-30 Leeman Farm, Woolwich
Figure 6.19 Exposure Rate at Outer Ring TLDS, TL 31-35 25 25 20
-20 u
5
~
5
-15 15 u
O Q.
a:
la 10-A~S
-10 l
M 0
0 1989 1990 1991 1992 1993 1994 Retrieval Date
--g-TL-31 Barley Neck Road, Woolwich x
TL-32 Baker Farm, Woolwich i
-e TL-33 Route 127, Woolwich l
t TL-34 Route 127, Woolwich
-v-TL-35 Route 127, Woolwich I _ _
Figure 6.20 Exposure Rate at Control TLDS, TL 36-38 25 25 i
1 20-
-20 u
i a
O 15-
-15 u
C)"
N 10-Y
-10 0
0 0
i 1989 1990 1991 1992 1993 1994 Retrieval Date l
-t3--
TL-36 Boothbay Harbor Fire Station x
TL-37 Bath Fire Station j
i
-g-TL-38 Dresden Substation j \\
7.
OUALITY ASSURANCE PROGRAM The quality assurance program at the Yankee Atomic Environmental Laboratory is designed to serve two overall purposes:
- 1) Establish a measure of confidence in the measurement process to assure the licensee, regulatory agencies and the public that the analytical results are accurate and precise; and 2) Identify deficiencies in the sampling and/or measurement process to those responsible for these operations so that corrective action can be taken. Quality assurance is applied to all steps of the measurement process, including the collection, reduction, evaluation and reporting of data, as well as the record keeping of the final results. Quality control is a part of the qu'ality assurance program.
It provides a means to control and measure the characteristics of measurement equipment and processes, relative to established requirements.
The Yankee Atomic Environmental Laboratory employs a thorough quality assurance program to ensure reliable environmental monitoring data.
The program includes the use of written, approved and controlled procedures for all work activities, a nonconformance and corrective action tracking system, systematic internal audits, audits from external groups, a
laboratory quality control program, and a complete training and retraining system. The Intralaboratory Quality Control program at the Laboratory and the EPA third party interlaboratory program are discussed in more detail below. Also discussed is the blind duplicate quality assurance program conducted by the Laboratory Quality Control Audit Committee.
7.1 Intralaboratorv Ouality Control Program The Yankee Atomic Environmental Laboratory conducts an extensive intralaboratory quality control program to assure the validity and l
reliability of non TLD analytical data.
Included are the internal process control program and the National Institute of Standards and Technology (NIST) Measurement Assurance Program.
These together comprise approximately five percent of the laboratory sample throughput.
The records of the quality control program are reviewed by the responsible I
cognizant individual, and corrective measures are taken whenever applicable.
l For the internal process control program and the NIST Measurement Assurance Program, there were 334 analyses for accuracy and 179 for precision in 1993. Of the 334 analyses for accuracy reviewed during this period, 95.2%
met the Laboratory acceptance criteria for accuracy, while 4.8% (16 out of l l
1 1
334 analyses) were identified as outside the Laboratory acceptance criteria.
Of the 179 analyses for precision during 1993, 99.4% met the Laboratory acceptance criteria for precision, while 0,6% (1 out of 179 analyses) were identified as outside the YAEL acceptance criteria. Table 7.1 shows a summary of the results of this program.
7.2 EPA Intercomoarison Program To further verify the accuracy and precision of the Laboratory analyses via an independent outside third party, the Yankee Atomic Environmental Laboratory participates in the U.S. Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies Program for those available species and matrices routinely analyzed by the Laboratory.
Participation in this program is required by Maine Yankee Technical Specification 5.8.1.b.3, and ODCM Section 2.4.5.
Each sample supplied by the EPA is analyzed in triplicate, and the results are returned to the EPA within a specified time frame. When the know values are returned to the Laboratory, the Laboratory and EPA results are then evaluated against specific Laboratory and EPA acceptance criteria. When the results of the cross check analysis fall outside of the control limit, an investigation is made to determine the cause of the problem and corrective measures are taken, as appropriate.
Results of this program are provided in this report in compliance with ODCM Section 2.4.5.
For the EPA Intercomparison Program, there were 129 analyses for accuracy on 23 sample sets.
The samples consisted of water, milk and air particulate filters.
The analyses were for gamma emitting radionuclides, gross-beta, strontium, iodine, plutonium and tritium.
Tables 7.2 and 7.3 shows a summary of the results for 1993.
Of the 129 analyses for accuracy, all but two met the EPA mean value control limits.
The results of the two measurements that did not meet the EPA mean value criteria are given below:
e For the set of Ba 133 measurements for the water sample with EPA Reference Date of 6-/11/93, the YAEL mean value of 59.36 pci/L fell below of the EPA control limit of 81.7 116.3 pCi/L.
This radionuclide is not in the gamma software library.
Consequently, the Ba-133 results for the EPA sample set were calculated manually using the 356 kev photopeak. A review of the sample paperwork indicated that the hand calculated radioactivity concentrations did not incorporate the 60 percent gamma ray abundance factor required for the 356 kev photopeak. A recalculation of 74
the Ba 133 activity concentration using this factor yielded a mean value j
within the EPA control limits, e For the set of Ru-106 measurements for the water sample with EPA j
Reference Date of 11/12/93, the YAEL mean value of 165.53 pCi/L fell below the EPA control limit of 166.3 235.7 pCi/L. The YAEL considers the
]
EPA known value to be suspect since the grand mean of 175.18 pC1/L is 12.8 percent below the EPA stated known value of 201 pCi/L. Assuming the j
grand mean is the actual activity concentration, the YAEL mean result of 165.53 pCi/L would have a bias difference of only -5.5 percent. A subsequent internal process check analysis of an EPA Ru-106 standard supplied by the EPA to validate the process indicated a mean value within 2 percent of the known.
The process is considered in compliance at this time.
7.3 Blind Duplicate Ouality Assurance Procram i
The Laboratory Quality Control Audit Committee (LQCAC) is comprised of one member from each of the five power plants that are serviced by the Yankee Atomic Environmental Laboratory. Two of the primary functions of the 14CAC are to conduct an annual audit of Laboratory operations and to coordinate 2
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 1
are sent to the Laboratory for analysis.
They are " blind" in that the identification of the matching sample is not identified to the Laboratory.
The 14CAC analyzes the results of the paired analyses to evaluate precision j
in Laboratory measurements.
A total of 50 paired samples were submitted under this program by the five
{
participating plants during 1993.
Paired measurements were evaluated for j
26 gamma emitting radionuclides, H 3, Sr-89, Sr-90, I-131 and gross-beta.
All measurements were evaluated, whether the results were considered j
statistically positive or not, and whether the net concentration was positive or negative. Of the 1308 paired duplicate measurements evaluated in 1993, 1305 (99.8%) fell within the established acceptance criteria.
With the three paired measurements that did not meet the acceptance criteria, none had radioactivity that was considered statistically positive. The samples submitted through this program are listed in Table 7.4.
1 75-l i
i
TABLE 7.1
SUMMARY
OF PROCESS CONTROL ANALYSIS RESULTS January - December 1993 ACCURACY PRECISION i
SAMPLE MEDIA NUMBER NUMBER
)
ANALYSES ANALYSES NUMBER OF OUTSIDE NUMBER OF OUTSIDE ANALYSES ACCEPTANCE ANALYSES ACCEPTANCE CRITERIA CRITERIA AIR CHARCOAL Gamma 104 1
0 0
AIR FILTER Beta 103 0
16 0
Gamma 0
0 0
0 Strontium 0
0 0
0 MILK Camma 30 0
33 0
Iodine 20 3
20 0
Strontium 16 4
16 0
WATER Cross-Beta 9
1 9
0 Camma 3
0 3
0 Iodine 11 1
11 0
Strontium 16 1
16 0
Tritium 13 0
12 0
SOIL / SEDIMENT Gamma 0
0 30 0
TOTAL 325 11 166 0
76
l l
l TABLE 7.2 l
EPA INTERCOMPARISON ANALYSIS RESULTS January - December 1993 EPA Ref, Sample Nuclide YAEL EPA Date Type Mean Control (pCi/1)
Limits (PCi/1) 10-20-92 Water Co-60 13.54 6.30-23.70 Cs 134 5.06 0.00 13.70 Cs-137 7.56 0.00 16.70 10-20-92 Water Sr 90 13.27 1.30-18.70 1-15 93 Water Sr 89 12.11 6.30-23.70 Sr 90 9.03 1.30-18.70 1-22-93 Water Pu 239 18.77 16.50-23.50 2-5-93 Water I-131 109.43 82.70-117.30 4-20-93 Water Co-60 38.70 30.30 47.70 Cs-134 25.83 18.30-35.70 Cs-137 31.60 23.30-40.70 6-4 93 Water H3 10603.1 8136.80-11551.2 6 11 93 Water Cs-134 5.05 0.00-13.70 Ru 106 99.54 98.20 139.80 Cs-137 4.62 0.00 13.70 Zn 65 107.15 85.70-120.30 Co 60 13.82 6.30-23.70 Ba 133 59.36' 81.70-116.30 7-23 93 Water Beta 42.32 31.00-55.00 8-27-93 Part. Filter Beta 46.24 38.30-55.70
- This mean value did not meet the EPA Control Limits.
See text for j
explanation.. _ - -
TABLE 7.2, continued EPA INTERCOMPARISON ANALYSIS RESULTS January - December 1993 EPA Ref.
Sample Nuclide YAEL EPA Date Type Mean Control (pCi/1)
Limits (pci/1) 8 27-93 Part. Filter Sr 90 18.84 10.30-27.70 8-27 93 Part. Filter Cs-137 9.07 0.30 17.70 9-24-93 Milk I-131 119.73 99,20-140.80 Cs-137 49.02 40.30-57.70 9-24-93 Milk I-131 125.96 99.20-140.80 9-24 93 Milk Sr-89 27.91 21.30-38.70 Sr-90 22.75 16.30-33.70 9-24 93 Milk K-40 1411.37 1278.77-1521.80 10-8-93 Water I-131 118.49 96.20-137.80 10-8 93 Water I-131 121.81 96.20-137.80 10 19-93 Water Sr 89 12.59 6.30-23.70 Sr-90 8.85 1.30 18.70 10 19-93 Water Co-60 9.86 1.30-18.70 Cs-134 10.09 3.30-20.70 Cs-137 10.72 1.30-18.70 i
10-29 93 Water Beta 17.10 6.30-23.70 1
11-5 93 Water M3 7164.08 6114.10-8681.90 11 12-93 Water Co 60 29.94 21.30-38.70 Zn 65 152.32 124.00-176.00 Ru-106 165.53*
166.30 235.70 Cs 134 57.10 50.30-67.70 Cs-137 41.85 31.30 48.70 Ba-133 79.97 65.10-92.90
- This mean value did not meet the EPA Control Limits.
See text for explanation.
i TABLE 7.3
SUMMARY
OF EPA INTERCOMPARISON PROGRAM RESULTS January - December 1993
)
NO. OF NO. OUTSIDE SAMPLE MEDIA SAMPLES NO OF EPA CONTROL ANALYZED
- ANALYSES LIMITS **
AIR FILTER Beta 1
3 0
1 Gamma 1
3 0
3 0
MILK Gamma 1
9 0
l Iodine 1
3 0
6 0
VATER Gross-Beta 2
6 0
Gamma 5
66 2
Iodine 2
6 0
3 0
15 0
Tritium 2
6 0
The number of EPA samples that were analyzed for the specified radionuclide.
Each of these samples was analyzed in triplicate.
The number of mean values (from triplicate samples) outside EPA
)
Control Limits. 1 4
TABLE 7.4
SUMMARY
OF BLIND DUPLICATE SAMPLES SUBMITTED January - December 1993 TYPE OF SAMPLE NUMBER OF PAIRED SAMPLES SUBMITTED Cow Milk 20 Ground Water 7
River Vater 4
Estuary Water 4
Sea Water 8
Irish Moss 2
Mussels 4
Food Product -
1 Cranberries TOTAL 50 8.
IJ00D USE CENSUS q
Maine Yankee Technical Specification 5.8.1.b.2 requires that a Land Use Census be conducted annually, pursuant to the details given in Section 2.4.4 of the Offsite Dose Calculation Manual (ODCM).
The Census identifies the locations of the nearest milk animal, the nearest residence and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles of the plant.
The 1993 Land Use Census was conducted between the required dates of June 1 and October 1.
Purso,-nt 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 1993 Census, one such milk animal location was identified.
This location was not added to the milk sampling program, however, since it had been shown in the past to be unreliable with regard to supplying milk samples (Reference 8).
Consequently no changes were made in the milk sampling program.
The results of the 1993 Land Use Census are included in this report in compliance with ODCM Section 2.4.4.3 and ODCM Appendix C, Part 1.
The locations identified during the census may be found in Table 8.1.
! I l
l
1 TABLE 8.1 1993 LAND USE CENSUS LOCATIONS SECTOR NEAREST NEAREST RESIDENCE CARDEN NEAREST MILK ANIMAL Km (Mi)
Km (Mi)
Km (Mi)
N 1.3 (0.8) 1.3 (0.8)
NNE 2.3 (1.45) 2.5 (1.6)
NE 1.3 (0.8) 1.3 (0.8) 5.5 (3.4) (Goats)
ENE 0.9 (0.6) 1.2 (0.7)
E 0.9 (0.6) 0.9 (0.6)
- ESE 1.4 (0.9) 1.4 (0.9)
SE 0.7 (0.4)
- 3.2 (2.0)
SSE 0.9 (0.6) 0.9 (0.6)
- S 1.7 (1.1) 2.7 (1.7) 5.6 (3.5) (Goats)
SSW 3.0 (1.9) 5.1 (3.2)
SW 1.4 (0.9) 1.4 (0.9) 7.9 (4.9) (Cows)
USW 1.0 (0.65) 1.1 (0.7) 1.9 (1.2) (Cows)
- W 2.6 (1.6) 2.6 (1.6) 7.2 (4.5) (Cows)
WNW 0.8 (0,5) 2.8 (1.7)
NW 2.0 (1.3) 2.0 (1.3)
NNV 1.1 (0.7) 1.1 (0.7)
The nearest residence, garden or milk animal to Maine Yankee.
No location was identified within 5 miles of the plant.
[
9.
REFERENCMd 1.
USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.
2.
NCRP Report No. 94, Exposure of the Pooulation in the United States and Canada from Natural Backcround Radiation, National Council on Radiation Protection and Measurements, 1987.
3.
Ionizine Radiation-Sources and Biolocical Effects, United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR),
1982 Report to the General Assembly, 4.
Kathren, Ronald L.,
Radioactivity and the Environment - Sources.
l s
Distribution. and Surveillance, Harwood Academic Publishers, New York, 1984.
5.
Maine Yankee Final Safety Analysis Report.
6.
NRC Ceneric Letter 89-01,
Subject:
Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and l
2 the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program. Dated January 31, 1989.
7.
USNRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977.
8.
Maine Yankee 1992 Annual Radiological Environmental Operating
- Report, l l