TECHNICAL NOTE
OKP/EAD 76 .1
RADIOACTIVE ISOTOPIC CHARACTERIZATION OF THE
ENVIRONMENT NEAR WISCASSET, MAINE USING PRE
AND POST-OPERATIONAL SURVEYS IN THE VICINITY OF
THE MAINE YANKEE NUCLEAR REACTOR
U.S. ENVIRONMENTAL PROTECTION AGENCY
Office of Radiation Programs
-------
RADIOACTIVE ISOTOPIC CHARACTERIZATION OF THE ENVIRONMENT NEAR
WISCASSET, MAINE USING PRE- AND POST-OPERATIONAL SURVEYS IN THE
VICINITY OF THE MAINE YANKEE NUCLEAR REACTOR.
MAY 1976
ENVIRONMENTAL ANALYSIS DIVISION
OFFICE OF RADIATION PROGRAMS
U.S. ENVIRONMENTAL PROTECTION AGENCY
WASHINGTON, D.C. 20460
THIS WORK WAS PERFORMED UNDER ENVIRONMENTAL PROTECTION AGENCY CONTRACT
NUMBER 68-01-2654 BY THE UNIVERSITY OF MAINE, ORONO, MAINE, UNDER THE DIRECTION
OF DR. C. T. HESS, DR. C. W. SMITH, C. H. CHURCHILL AND G. F. BURKE.
-------
PREFACE
The Office of Radiation Programs is concerned with the
evaluation of radiation exposure to man and his environs.
Nuclear power plants release radioactive materials to the
environment from normal operations which become a potential
source of exposure to the population. The Environmental
Analysis Division has responsibilities for evaluating the
environmental and public health impacts resulting from such
releases.
This study was performed on contract to this Division
by the University of Maine for the purpose of isotopic
•characterization of environmental radioactivity outside the
plant site boundary of the Maine Yankee Pressurized Water
Nuclear Power Reactor during 1973. It compares the pre-
operational survey with the postoperational survey to
determine the amount of contamination resulting from
operations of this power reactor.
loyd L. Gal pin
Director
Environmental Analysis Division
Office of Radiation Programs
-------
RADIOACTIVE ISOTOPIC CHARACTERIZATION OF THE ENVIRONMENT
NEAR WISCASSET, MAINE USING PRE- AND POST-OPERATIONAL SURVEYS
IN THE VICINITY OF THE MAINE YANKEE NUCLEAR REACTOR
ABSTRACT
A comparison of identical surveys of the pre- and post-operational
environmental radioactivity is made for the vicinity of the Maine Yankee
Atomic Power Reactor, Wiscasset, Maine. Radionuclides are measured in
laboratory samples of soil, sediment, well water, surface water, estua-
rine water, air particulate, air moisture, and precipitation. Field
measurements of gamma-ray emitting radionuclides and high pressure ion
chamber measurements are also presented. The changes in radionuclide
concentration and dose are evaluated using the Maine Yankee Environmental
Impact Statement. The most significant changes occur for radionuclides
in soils and sediments. Details of the distribution of sediment radio-
nuclides near the outflow of the reactor in Bailey Cove are presented
with dose estimates of 10.6 mrem/year at the sites of greatest specific
activity. Radionuclides in the water were mainly natural 2^Rn ancj
daughters. Tritium concentrations were at minimum detectable level.
Air particulate showed traces of ^Be and ^^ZrNb at fallout levels which
were not significantly different from the preoperational levels. High
pressure ion chamber dose rates ranged from 8.9 to 12.6 uR/hr at the 12
measured sites.
Time variations of radionuclide content were measured for oysters
cultured in the reactor effluent and associated sediments. Doses
calculated for ingestion of radionuclides by consumption of oysters
would be 0.27 mrem/yr for 58Co and 0.004 mrem/yr for 54Mn.
-------
FORWARD
This report presents the procedures and results of an environmental
radioactivity survey in the vicinity of the Maine Yankee Atomic Power
Plant (a 855 MWE pressurized water reactor) 6.4 km south southwest of
Wiscasset, Maine on Bailey Point. Prior to the operation of this facility
measurements of environmental radioactivity were made (1972) on samples of
soil, sediment, well water, surface water, estuarine water, air particulate,
air moisture, and precipitation. The procedures and results of that survey
were reported in "Radiation Data and Reports", volume 15, number 2,
February 1974.
The post-operational survey (1974) represents the follow-up survey to
the pre-operational survey referenced above. The study design employs the
same techniques, environmental media, and sampling sites as the pre-operational
survey. The objective of this dual survey is to assess changes in environmental
radioactivity.
-------
ACKNOWLEDGMENTS
The work reported here represents a cooperative effort by several
institutions and facilities. Essential to this study was the work of
the staff of the Eastern Environmental Radiation Facility, Montgomery,
Alabama for off-site laboratory measurements, with special thanks to
Mrs. Ann B. Strong, Mr. Charles Phillips and Mr. Thomas Reavey. We
gratefully acknowledge the participation by the Ira C. Darling Center
for Oceanographic Research, University of Maine in the estuarine aspects
of this study, the transect study of Bailey Cove and the aquaculture of
the oysters for the uptake modeling, with special thanks to Mr. A. H.
Price and Dr. H. Hidu. Cooperation and assistance by the Maine Yankee
Atomic Electric Company, with special thanks to Mr. V. Thompson, was
gratefully appreciated. We acknowledge the use and cooperation of the
University of Maine Physics Department, Computer Center and Office of
Grant Support. The information included in this report as Appendix D
was part of a study funded by the National Oceanic and Atmospheric
Administration. We appreciate their willingness to have this material
included in this report.
We are especially grateful for the useful discussions throughout
this study with Mr. C. L. Weaver of EPA's Office of Radiation Programs
and for the assistance of Mr. Charles Robbins of the Environmental Analysis
Division who coordinated the publication of this report.
Dr. C. T. Hess
Dr. C. W. Smith
University of Maine
-------
TABLE OF CONTENTS
SECTION
1. INTRODUCTION 1
Purpose of this Study 1.1
Goals for this Study 1.2
Study Design 1-3
2. EXPERIMENTAL PROCEDURES AND ANALYSIS 2
Radionuclides in the Soil and Sediment 2.1
Laboratory Soil and Sediment Measurements and their Analysis 2.11
Field Soil and Sediment Measurements and their Analysis. . . 2.12
Discussion of Soil and Sediment Analysis 2.13
Sediment Transect Survey and Analysis 2.14
Radionuclides in the Water 2.2
Field Water Measurements 2.21
Laboratory Water Measurements and Analysis 2.22
Tritium in the Water, Air Moisture and Precipitation .... 2.23
Discussion of Tritium Measurements 2.24
Radionuclides in the Air Particulate 2.3
Laboratory Air Particulate Measurements and Analysis .... 2.31
Field Air Particulate Measurements and Analysis 2.32
High Pressure Ion Chamber Measurements 2.4
3. APPENDICES 3
Liquid and Gaseous Effluent Inventory A
Prescan Results B
Gamma Ray Dose Calculations C
A Model for Radionuclides in Oysters and Associated Sediments . D
Pre-Operational Laboratory Water Gamma-ray Analysis of the
Dissolved Component
-------
1. INTRODUCTION
1.1 Purpose of the Study
This study consists of a pre-operational (1972) and post-operational
(1974) environmental radioactivity survey in the vicinity of the Maine
Yankee Nuclear Power Reactor (6.4 km S.S.W. of Wiscasset, Maine on Bailey
Point, See Fig. 1). The study measures any changes in the radionuclide
content of the soil, estuarine sediment, estuary, well, and surface water,
air moisture precipitation, and air particulate for this region. The
study identifies the pathways in these environmental media which tend to
collect or reconcentrate radionucl ides and the regions in which reconcen-
tration occurs.
1.2 Goals for this Study
A. To broadly survey several environmental media (soil, sediment,
water, air moisture and air particulate) for changes in radionuclide
content (nuclide by nuclide rather than gross activity) resulting from
the operation and refueling of the Maine Yankee Nuclear Power Reactor.
B. To compare observed changes with the Maine Yankee Semi-annual
Report of Release of Radioactive Materials^ ' and with predictions of
(2)
the Maine Yankee Environmental Impact Statement '.
C. To examine in detail the largest change observed in the study.
-------
-2-
1.3 Study Design
Studies of pressurized water reactors as outlined by Kahn^ , Rowe^
and LentsdT5^ et.al. are based on a combination of knowledge of radio-
nuclide releases, use of very sensitive environmental measurements and a
carefully planned pre-operational survey. This study similarly employs
these features. A nuclide by nuclide comparison of a pre-operational and
post-operational survey of several environmental media forms the overall
structure of this study. Field and laboratory measurements of primarily
gamma-ray emitting radionuclides were used to determine which of the
radionuclides listed in the Semi-annual Report of Release of Radioactive
Materials are being retained in the environment in the vicinity of the
reactor. Tritium, gross beta and gross alpha measurements, along with
high pressure ion chamber measurements also were employed. The major
radionuclide in the liquid effluent is tritium and the major radionucl ides
in the gaseous effluent is 133Xe and tritium. Several other radionuclides
in trace amounts (See Appendix A) are also released in the liquid and
gaseous effluents.
To achieve both the sensitivity and diversity of measurements to
cover this broad survey this study utilized the facilities of the Eastern
Environmental Radiation Facility, Montgomery, Alabama for laboratory measure-
ments for the post-operational survey, the Northeastern Radiological Health
Laboratory, Woburn, Massachusetts for laboratory measurements for the pre-
operations survey and the University of Maine, Department of Physics for
the field measurements and some laboratory measurements for both surveys
The two surveys employ the same sampling sites and as far as possible the
same or similar instrumentation. Details of each measurement are presented
-------
-3-
in the following sections along with the experimental results. Post-
operational and pre-operational results are presented in tables in each
section. Comparisons are made, changes are discussed and conclusions
are presented in each section. The largest change was observed for
sediments in the Bailey Cove estuary and is presented as Section 2.14
Sediment Transect Survey and Analysis.
-------
-4-
2.1 RADIONUCLIDES IN THE SOIL AND SEDIMENT
2.11 Laboratory Soil and Sediment Measurements and Their Analysis
Soil samples were collected at the following sites: (Foxbird
Island, 0,1 km, S.; Eaton Farm, 0.4 km, W.; Bailey Farm, 0.8 km, N.E.;
Young's Creek, 1.0 km, N.; Knight Cemetary, 1.1 km, E.; Westport Fire-
house , 1.8 km, S.; Chewonki Neck (Camp), 1.9 km, S.W.; Cowseagan Narrows,
3.2 km, N.E. and Bluff Head, 4.0 km, S.S.W., see map). Sediment samples
were collected at Foxbird Island, 0.1 km, S, on the outfall side of the
causeway and at Murphy's Corner, 2.8 km, S.W. Soil samples were collected
using a disc-cutter sampler which would cut a cylindrical soil sample
15 cm in diameter by 15 cm deep. Four soil samples this size, each
centered at the corner of a square grid 25 cm on an edge were collected
at each of the nine sites. The four soil samples including surface
vegetation were mixed and the root mats pulverized. The sample was then
screened and all material smaller than 5 mm retained. The sample was
then dried at 110°C for 24 hours. In the case of the sediment samples,
the top two centimeters were collected. These samples were screened and
dried in an identical manner. In each case the samples were divided and
a dry kilogram of the sample material was shipped to the Eastern Environ-
mental Radiation Facility, Montgomery, Alabama for gamma-ray analysis
using a Ge(Li) detector and on-line computer-analyzer. Analysis was
carried out by hand using the Compton continuum subtraction method^ '.
All samples were counted for a nominal 900 minutes (with a nominal 10
persent dead time) with a 2048 channel analysis. The results of the
analysis are listed in Table I. The results of the pre-operational
analysis are listed in Table II.
-------
TABLE I
POST-OPERATIONAL LABORATORY SOIL AND SEDIMENT GAMMA-RAY ANALYSIS
SAMPLE IDENTIFICATION
LOCATION
Foxbird
Island
Eaton
Farm
Bailey
Farm
Young's
Creek
Knight
Cemetery
Westport
Fi rehouse
Chewonki
Neck(Camp)
Cowseagan
Narrows
Bluff
Head
Foxbird
Island
Murphy's
DATE
COLLECTED
8/14/74
8/14/74
8/14/74
8/14/74
8/14/74
8/14/74
8/14/74
8/14/74
8/14/74
8/14/74
8/14/74
DATE
COUNTED
11/16/74
11/18/74
11/20/74
11/18/74
11/19/74
11/17/74
11/14/74
11/15/74
11/19/74
11/15/74
11/20/74
TYPE
soil
soil
soil
tidal
marsh soil
soil
soil
soil
soil
soil
tidal marsh
sediment
tidal flat
sediment
THORIUM
SERIES
228Ac
pCi/kg
±2a
900
±90
1100
±120
1100
±150
1100
±120
1700
±225
800
±90
900
±90
1000
±70
1200
±48
900
±300
900
±90
URANIUM
SERIES
21l)Bi
pCi/kg
±2a
700
±200
1100
±120
1100
±170
800
±70
1300
±180
800
±100
700
±80
1000
±100
1600
±80
900
±270
800
±72
OTHER
NATURAL
40K
pCi/kg
±2a
7300
±950
17400
±1200
17600
±1300
19400
±780
11300
±1300
11800
±700
15100
±600
14300
±570
13300
±530
20500
±1600
18000
±500
RADIONUCLIDES
137Cs
pCi/kg
±2a
4600
±180
2500
±130
1800
±100
700
±50
4000
±160
3200
±100
1500
±50
1300
±50
1200
±50
1000
±130
500
±35
13"CS
DCi/kg
±2o
< 35
< 35
< 35
< 35
< 35
< 35
< 35
< 35
< 35
1000
±130
< 35
58Co
DCi/kg
±2a
< 25
< 25
< 25
< 25
< 25
< 25
< 25
< 25
< 25
21000
±400
< 25
6°CO
3Ci/kg
±2a
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 30
2420
±250
< 30
51»Mn
pCi/kg
±2a
< 15
< 15
< 15
< 15
< 15
< 15
< 15
< 15
< 15
450
±100
< 15
en
i
All measurements based on dry weight
-------
TABLE II
PRE-OPERATIONAL LABORATORY SOIL AND SEDIMENT GAMMA-F
SAMPLE IDENTIFICATION
LOCATION
:oxbird
Island
Eaton
Farm
3a i 1 ey
Farm
Young's
Creek
(night
Cemetery
Jestport
Fi rehouse
^hewonki
Neck(Camp)
Cowseagan
Narrows
Bluff
Head
Foxbird
Island
Murphy's
Corner
DATE
COLLECTED
6/29/72
6/12/72
6/12/72
6/12/72
6/12/72
6/12/72
6/12/72
6/13/72
6/12/72
6/29/72
7/3/72
DATE
COUNTED
7/20/72
7/17/72
7/12/72
7/14/72
6/26/72
6/21/72
7/20/72
7/24/72
6/22/72
7/28/72
7/27/72
TYPE
soil
soil
soil
tidal
marsh
soil
soil
soil
soil
soil
soil
tidal
marsh
sediment
tidal
flat
sediment
THORIUM
SERIES
228Ac
pCi/kg
±2a
1200
±100
340
±120
1240
±300
880
±250
1210
±200
1000
±350
1100
±250
300
±300
660
±300
250
±130
1660
±280
URANIUM
SERIES
21 "Si
pCi/kg
±2a
700
±90
630
±70
810
±150
1075
±120
700
±80
920
±120
1370
±300
730
±180
1100
±180
500
±180
740
±120
OTHER
NATURAL
40K
pCi/kg
±2a
14000
±1000
14900
±400
14600
±1300
18200
±400
11200
±1200
11800
±900
13200
±1200
13400
±1250
11300
±1240
15000
±350
15200
±1200
U\Y ANALYSIS
RADIONUCLIDES
i3?Cs
pCi/kg
. ±2a
940
±85
870
±45
1670
±110
800
±80
4960
±110
1110
±85
3340
±130
2620
±130
2030
±110
350
±32
450
±80
131(Cs
pCi/kg
±2a
< 30
< 15
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 15
< 30
58Co
pCi/kg
±2a
< 25
< 12
< 25
< 25
< 25
< 25
< 25
< 25
< 25
< 12
< 25
60Co
pCi/kg
±2o
< 30
< 15
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 15
< 30
5"Mn
pCi/kg
±2a
< 20
< 10
< 20
< 20
< 20
< 20
< 20
< 20
< 20
< 10
< 20
I
cr>
-------
-7-
The Thorium series as represented by 228Ac is found to be the same
(±2a) as the pre-operational measurements with significant changes only
at Eaton Farm soil. At present there is no obvious explanation of the
difference. The Uranium series as represented by 21/+Bi is found, in all
cases, to be the same (±2a) as pre-operational measurements. The
concentration of 1+0K is found to be the same (±2a) for all cases except
Foxbird Island soil and Foxbird Island sediment. In the case of Foxbird
Island soil, a decrease is observed and for Foxbird Island sediment,
increase is observed. 137Cs is observed to be the same (±2o) in all cases
except Foxbird Island soil, Eaton Farm soil, Westport Firehouse soil,
Chewonki Neck soil, Bluff Head soil, and Foxbird Island sediment. Finally,
134Cs, 58Co, 60Co and 5ltMn are all found to be present in Foxbird Island
sediment. These four isotopes were not present in the sediment at the
time of the pre-operational study.
This change is not in agreement with the Maine Yankee Environmental
(2)
Impact Statement . Specifically, page V-15, states - "Recreational and
other uses of shorelines and waters near the plant will be permitted by the
Applicant. Therefore, direct exposure to radiation from nuclides in the
waters of the bay will be experienced. The individual receiving the highest
radiation dose would probably be one who earns his livelihood by digging
blood and sand worms in the mud flats in the vicinity of the reactor dis-
charge. For this calculation, concentrations of radionuclides deposited on
the mud flats were assumed to result from undiluted effluent water. Such a
person was also postulated to be exposed to the mud flats for 2000 hr/yr.
Based on these assumptions, the dose to the total body from radionuclides
associated with the mud would be about 6 mrem per year for the individual
receiving maximum exposure. Nearly all this exposure is from 13ttCs and
137Cs deposited on the mud flats where the worms are harvested. The exposure
to the hands of the worm diggers would be somewhat higher than their total-
-------
-8-
body exposure since they sift through the mud while harvesting the worms."
We find that over (0.92) of the exposure will come from 54Mn, 58Co and
60Co with the remaining portion (.08) coming from 13ttCs and 137Cs.
Furthermore, high pressure ion chamber measurements at Foxbird Island and
Murphy's Corner show an increase of the intensity over sediment. At Foxbird
Island, for example, this change in intensity is 5.3 (6.58)calc microrem
per hour which comes to a dose change (for the 2000 hr/yr worm digger) of
10.6 (13.6)calc millirem per year. See Section 2.4 High Pressure Ion
Chamber for details of these measurements. The range and extend of radio-
nuclides in the sediment are presented in greater detail in Section 2.14
Sediment Transect Survey and Analysis.
-------
-9-
2.12 Field Soil and Sediment Measurements and their Analysis
As prescribed by our pre-scans of soil samples described in 2.11
radionuclides in the soil were measured in the field at the following, six
locations. (Foxbird Island, 0.1 km, S.; Eaton Farm, 0.4 km, W.; Bailey
Farm, 0.8 km, N.E.; Westport Firehouse, 1.8 km, S.; Chewonki Neck (Camp),
1.9 km, S.W.. On-site sediment measurements were taken at low tide at
Murphy's Corner, 2.9 km, S.W. the location of a tidal mud flat of commercial
importance to the local blood worm industry and Foxbird Island the site of
the outflow. A portable multichannel analyzer system with a 5 cm by 5 cm
Nal(Tl) detector was employed. The portable multichannel analyzer system
consisted of a Northern Scientific, Inc. NS-710 multichannel analyzer
powered by a Cornel 1-Dubilier Powercon sine wave inverted Model 12ESW25 and
a 12 v.d.c., 96 amp-hour battery. The detector, a 5 cm by 5 cm Nal(Tl)
crystal was an integral crystal-photomultiplier assembly by Teledyne
Isotopes, Inc., Model S-88-I with 8.4 percent resolution at the 137Cs
photo-peak. It was powered by a Northern Scientific, Inc. high voltage
battery power pack NS-308 with a matched cable-base assembly NS-309. The
detector was connected to the multichannel analyzer with 50 m of coaxial
cable (RG-59). A 100 Ib. lead shield consisted of a cylinder 28 cm high,
and 18 cm in diameter with a 6 cm diameter concentric hole the full length
of the cylinder. The detector was housed in this shield for each on-site
measurement. The shield was placed on the ground, the detector lowered
into the shield and a 3 cm thick lead cap covered the upper end of the
shield. The lower end of the shield was open to the soil so that the
circular face of the detector was placed on the ground (a 1/8 inch insulating
layer of plywood was used to protect the crystal from thermal shock). All
-------
-10-
field soil and sediment gamma-ray spectra were taken using this top shielded
2 IT geometry^7) It is felt that this geometry has two advantages: (i) it is
reproducible and (ii) it is without bias in that it samples the soil in a
nondestructive non-mixed manner. All field soil and sediment spectra were
taken on one quarter memory (512 channels) for 4000 seconds. At the end of
4 runs the multichannel analyzer was returned to the University of Maine,
Physics Department and the memory outputted into a model KSR-33 teletype.
The teletype provided a listing of the counts in each channel and a punched
paper tape. The punched paper tapes were converted into cards and the
gamma spectra analyzed at the University of Maine Computer Center. The
least squares method was used to obtain the best estimates of the amounts
of each radionuclide present in each sample and an evaluation of the errors
of these results. The computer program used was the Oak Ridge National
Laboratory spectrum fitting program, Alpha-M^9' It employs the least squares
method to analyze the data for which a "best fit" is mathematically computed
such that the sum of the squares of the deviations between the actual spectra
and the. "best fit" is minimized. The program also uses automatic gain
shift and automatic threshold shift routines to optimize the fit. The
program works with a library of standard spectra from which it synthesizes
the "best fit" spectra. The library used for the analysis of the soil and
sediment on-site spectra was composed of standard spectra for k°K, 137Cs,
the 232Th series, 13l+Cs, 58Co, 60Co, and the 238U series. Output from the
program consists of the estimated amount of each standard spectra needed to
synthesize the sample spectrum, the estimated error in the amount used for
each library standard, the gain shift (if any) used to match the spectrum to
the standards, the threshold or zero shift (if any) used to match the
spectrum to the standards, the residuals for each channel and a listing of
suspicious channels whose residuals lie outside two standard deviations.
-------
-11-
In all cases convergence was obtained in less than 20 iterations. The
results of the analysis are listed in Table III. Table IV lists results
from the pre-operation survey.
One can see that in general all spectra contained Lf°K, and the natural
decay series for 232Th and 238U. A significant amount of 137Cs, a non-
natural isotope, is contained in all spectra. The field measurements at
Foxbird Island tidal mud flats indicates 58Co, and 60Co at this site.
Comparison of the levels of natural isotopes 232Th, 238U and 40K and 137Cs
which is partly due to fallout are similar to pre-operational levels: with
the exception of the Foxbird Island measurement which had more 238U, 232Th
and less 137Cs, and may be due to disturbances done by nearby construction
of a diffuser for the reactor. Eaton Farm also shows more 238U series and
is not explained.
Measurements at Foxbird Island and Murphy's Corner show 58Co and 60Co.
60Co was also measured at Bailey Farm and Knight Cemetery while 58Co was
measured at Eaton Farm. These cobalt isotopes were not present at the time
of the pre-operational study. Measurements at Foxbird Island indicate 238U
and 232Th has increased and 137Cs decreased as compared to the pre-operational
study. These changes in these three isotopes were probably caused by the
extensive dust due to construction dredging trucking and back filling with
estuarine sediment during construction of the diffuser channel and head
basin.
-------
TABLE III
POST-OPERATIONAL FIELD SOIL AND SEDIMENT GAMMA-RAY ANALYSIS
LOCATION
:oxbird
Island
iaton
Farm
Jailey
-arm
Knight
Cemetery
Murphy's
Corner
Foxbird
Island
DATE
MEASURED
8/24/74
8/22/74
8/22/74
8/22/74
8/22/74
8/24/74
TYPE
soil
soil
soil
soil
sedi-
ment
sedi -
ment
232Th
pCi/kg
±2a
2000
±70
2300
±80
2100
±95
3100
±80
1300
±40
1500
±60
238u
pCi/kg
±2a
1250
±120
1300
±120
1000
±130
660
±120
280
±50
580
±80
•fOK
pCi/kg
±2a
17400
±750
24700
±740
18600
±880
23200
±790
11000
±370
16500
±470
137Cs
pCi/kg
±2a
3800
±230
2800
±260
3380
±370
6900
±310
590
±130
1400
±200
58Co
pCi/kg
±2a
< 30
210
±30
< 30
< 30
180
±30
730
±20
6°Co
pCi/kg
±2a
150
±90
< 75
60
±90
150
±80
70
±40
100
±70
IN}
I
-------
TABLE IV
PRE-OPERATIONAL FIELD SOIL AND SEDIMENT GAMMA-RAY ANALYSIS
-OCATION
:oxbird
Island
iaton
Farm
Bailey
Farm
Young's
Creek
Knight
Cemetery
destport
Fi rehouse
Chewonki
Neck (Camp)
Cowseagan
Narrows
Bluff
Head
Murphy ' s
Corner
DATE
MEASURED
6/29/72
6/26/72
6/27/72
6/27/72
6/27/72
6/27/72
6/26/72
6/27/72
6/28/72
7/3/72
TYPE
soil
soil
soil
soil
soil
soil
soil
soil
soil
sediment
THORIUM
SERIES
pCi/kg
1600
±100
2400
±100
2000
±100
1600
±400
3100
±300
1500
±100
1900
±100
1700
±100
2000
±100
1400
±100
URANIUM
SERIES
pCi/kg
600
±100
700
±100
800
±200
600
±200
600
±200
500
±100
500
±150
500
±100
800
±300
400
±200
if oK
pCi/kg
14000
±3500
21000
±5000
16000
±6000
14000
±9000
20000
±6000
14000
±3000
20000
±4000
15000
±3000
16000
±5000
9000
±4000
i3?Cs
pCi/kg
3590
±800
5600
±2700
3300
±600
4000
±1400
9500
±1600
7600
±2000
5000
±1100
5400
±800
6300
±1400
7000
±1900
58Co
pCi/kg
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 30
< 30
6°CO
pCi/kg
< 75
< 75
< 75
< 75
< 75
c 75
< 75
< 75
< 75
< 75
-------
-14-
2.14 Sediment Transect Survey and Analysis
As a result of the high readings for the pre-scan and in situ
gamma-ray measurements of sediment from Foxbird Island and as a result
of suggestions from our collaborator Mr. Charles Phillips of Eastern
Environmental Radiation Facility, Montgomery, Alabama, we decided to make
a survey along tidal transects of the sediments in Bailey Cove. Using
the cooperative efforts of the Ira C. Darling Center for marine research
and members of the bloodwoorm research project, under the direction of
Marine Biologist A. H. Price, 50 samples of estuarine sediments were
collected at 50 ft. transects in Baily Cove adjacent to the outflow of
the reactor. The locations of the sites are shown in Figure 2. These
sediments were counted for 5000 sec. using the University of Maine,
Physics Department's Ge(Li) detector and low background shield. Results
of the determination of the concentration of gamma-ray emitting isotopes
in the sediment is shown in pCi/kg. Figures 3 and 4 illustrate activity
maps for 58Co and 60Co, respectively. It should be noted that the highest
levels of radioactivity are for the outflow site (29) and for the upper
reaches of the cove. The constant picocurie lines seem to follow the
flow of water out of the cove at low tide and into the upper cove at high
tide and thus suggest that the isotopes are transported by the outflow
water and reconcentrated into the sediments. This reconcentration is
consistent with a diffusion theory for fallout radionuclides in sediments
as suggested by Lerman and with chemical precipitation of 58Co in the
effluent of reactors as suggested by Fukui . Comparison of the average
flow velocities of the water from the outflow suggests sedimentation as
another mechanism which reconcentrates the nuclides. Some indication of
-------
15
Figure 2, Site Locations
for Sediment Transect
Bailey Cove
175 meters
-------
(K
V-/IOO
1780s
3160 5620
3, Activity Map
58Co(pCi/kg)
n
Sediment, Bailey Cove
175
meters
-------
17
Figure 4, Activity Map
for 60Co(pCi/kg) in
Sediment, Bailey Cove
175 meters
-------
-18-
this may be seen in the reduced level of nuclides along the most direct
channel of the outflow. The radionuclides 13ifCs, 137Cs, and 60Co bear
this out by having similar behavior to the 58Co. Since the Maine Yankee
(2)
Environmental Impact Statement ' does not specify range or distribution
guidelines or estimates no comparison is made. However, implicit in the
I 10)
modelv ' upon which the dose calculations were based is an assumption of
uniform distribution of effluent discharge. This is not the case in the
vicinity of Maine Yankee as shown by this transect survey in Bailey Cove.
One radioactive particle containing 7700 pCi of 60Co was observed in the
sediment transect #19 and had a total activity (58Co, 530 pCi: l+6Sc,
670 pCi: 54Mn, 120 pCi) of more than 9000 pCi in a mass less than 20 y
grams. Photographs and x-rays powder patterns were made and it was found
to be cubic cobalt, alpha iron, nickel, alpha and gamma manganese and
possibly chromium and vanadium. This stainless steel like composition
suggests reactor origin. The particle was also checked for the oxides,
chlorides, nitrates, sulphates and hydroxides of these metals with negative
results(13).
-------
-19-
2.2 RADIONUCLIDES IN THE WATER
2.21 Field Hater Measurements
Based upon the data obtained during the pre-operational field
water measurements, the post-operational measurements showed no detectable
amount of gamma activity above background. It is felt that field
measurement of in-situ water with portable multichannel analyzer-detector
equipment is significantly less sensitive than laboratory measurement and
yields no additional information. Laboratory measurement, with the advantages
larger detectors and massive shielding together with the practicality of
longer measuring time, outweighs the advantages of preserving temperature,
particulate and salinity gradients as is done in the laboratory water
measurement.
2.22 Laboratory Water Measurements and Their Analysis
Water samples were collected at the following seven sites Foxbird
Island, 0.1 km, S.; Eaton Farm, 0.4 km, W.; Bailey Farm, 0.8 km, N.E.;
Young's Creek, 1.0 km, N.; Chewonki Neck (Camp), 1.9 km, S.W.; Cowseagan
Narrows, 3.2 km, N.E.; and Bluff Head, 4.0 km, S.S.W., see map Figure 1.
Each water sample was separated,by filtering the dissolved and the un-
dissolved solids into two components. This separation was done in the
field at the time of collection. The water was filtered using a Millipore
high pressure filtering unit. A Milipore 90 mm filter holder was loaded
with a Whatman No. 1 paper filter, a Millipore AP3207500 spacer, a Millipore
SCWP09025 cellulose ester 8.0y filter, a Mi Hi pore AP3207500 spacer and a
Millipore HAWP09025 cellulose ester 0.45y filter for each water sample.
Ten liters of water from each site was filtered using the above arrangement.
-------
-20-
The filtered water (dissolved component) was placed in one gallon plastic
shipping containers to which 40 ml of nitric acid was added to stabilize
the sample. Prior to acidification a 50 ml sample from each site was
placed in a plastic bottle for tritium analysis, (see section 2.23). The
dissolved component, (one gallon samples) and the undissolved component
(filters) were sent to the Eastern Environmental Radiation Facility,
Montgomery, Alabama for gamma-ray analysis.
The dissolved component was gamma-ray analyzed using a Nal(Tl)
detector and 3.5 liter Marinelli beaker geometry in a massive shield.
The results of this analysis show no detectable gamma activity in the
dissolved component. (See Appendix E for pre-operational laboratory
dissolved water component).
The undissolved component was analyzed in the following manner. The
filters were weighed before use. After use they were dried and reweighed
to determine the amount of undissolved material. The filters were sent
to the Eastern Environmental Radiation Facility, Montgomery, Alabama for
gamma-ray analysis. The three filters for each site were first measured
for gross alpha and gross beta activity and then counted in a 40 ml Nal(Il)
well-crystal 10 cm x 13 cm with 3 cm deep well. The results of these
measurements are presented in Table V. Table VI lists the results for
the pre-operational survey.
-------
TABLE V
POST-OPERATIONAL LABORATORY WATER MEASUREMENT
UNDISSOLVED COMPONENT (FILTER) COLLECTED 8/14/74
LOCATION
Foxbird
Island
Eaton
Farm
Bailey
Farm
Long Ledge
Creek
(Young's Creek)
Chewonki
Neck (Camp)
Cowseagan
Narrows
Bluff
Head
WATER
TYPE
estuarine
well
well
surface
well
estuarine
estuarine
SAMPLE
MASS
(GRAMS)
0.165 ±
0.015
0.005 ±
0.015
0.002 ±
0.015
0.621 ±
0.045
0.005 ±
0.015
0.122 ±
0.015
0.149 ±
0.015
GROSS ALPHA
pCi/10 liters
±2a
ND
18.9 ± 85%
60.7 ± 33%
2.1 ± 59%
6.2 ± 66%
ND
ND
GROSS BETA
pCi/10 liters
±2a
1.4 ± 81%
2.6 ± 39%
21.1 ± 22%
4.8 ± 59%
1.6 ± 57%
1.3 ± 69%
ND
GROSS GAMMA
pCi/10 liters
±2a
ND
ND
ND
ND
ND
ND
ND
I
no
-------
TABLE VI
PRE-OPERATIONAL LABORATORY WATER MEASUREMENT
UNDISSOLVED COMPONENT (FILTER) COLLECTED 6/13/72
LOCATION
Foxbird
Island
Eaton
Farm
Bailey
Farm
Long Ledge
Creek
(Young's Creek)
Chewonki Neck
Camp
Cowseagan
Narrows
Bluff
Head
WATER
TYPE
estuarine
well
wel 1
surface
well
estuarine
estuarine
SAMPLE
MASS
(GRAMS)
0.131 ±
0.005
0.000 ±
0.005
0.007 ±
0.005
0.045 ±
0.005
0.002 ±
0.005
0.114 ±
0.005
0.163 ±
0.005
228Ac
< 45
< 45
200
±45
< 45
< 45
< 45
< 45
212Bi
100
±20
< 10
< 10
< 10
< 10
< 10
< 10
20871
< 25
< 25
< 25
< 25
< 25
30
±25
70
±25
214pb
< 10
30
±25
< 10
< 10
< 10
< 10
< 10
2i^B1
< 10
< 10
< 10
< 10
< 10
< 10
< 10
"°K
< 25
< 25
< 25
< 25
< 25
< 25
< 25
I
ro
ro
-------
-23-
2,22 Discussion of the Water Gamma-Ray Analysis
Several observations can be made from the data in Table V. The well
water in this region of Maine contains considerable dissolved 222Rn. This
is due primarily to leaching from uranium oxide in the pegmatite deposits
in the area. This is also reflected in the alpha and beta activity in
the well water from the sites measured (Eaton Farm, Bailey Farm and to
some extent Chewonki Neck Camp). Irr general the water measurements at all
sites show no significant change from the pre-operational survey shown in
Table VI and, with the exception of the well water, have typical activities
for this type of environmental media. The specific activity of the undissolved
component in the estuarine water is of the same magnitude as the specific
activity in the estuarine sediments. The specific activity of the well
water samples was about two orders of magnitude greater but from the pre-
operational survey this is known to be of natural origin.
2.23 Tritium in the Water, Air Moisture and Precipitation
2.231 Tritium in the Water
Tritium in the water was measured in samples collected at the following
seven locations, Foxbird Island, 0.1 km, S.; Eaton Farm, 0.4 km, W.;
Bailey Farm, 0.8 km, N.E.; Young's Creek, 1.0 km, N.; Chewonki Neck (Camp)
1.9 km, S.W.; Cowseagan Narrows, 3.2 km, N.E. and Bluff Head, 4.0 km, S.S.W.;
(see Fig. 1). Each water sample was filtered as described in section 2.2.
A 50 milliliter sample from each site was sent to the Eastern Environmental
Radiation Facility, Montgomery, Alabama for tritium analysis using the direct
counting liquid scintillation method. The samples were counted in a low
background chamber. The results of these post-operational measurements are
presented in Table VII. Pre-operational measurements are presented in
Table VIII.
-------
-24-
TABLE VII
POST-OPERATIONAL TRITIUM IN WATER
LOCATION
Foxbird
Island
Eaton
Farm
Bailey
Farm
Long Ledge
Creek
(Young's Creek)
Chewonki
Neck (Camp)
Cowseagan
Narrows
Bluff
Head
DATE
COLLECTED
8/15/74
8/15/74
8/15/74
8/15/74
8/15/74
8/15/74
8/15/74
TYPE
estuarine
well
well
surface
well
estuarine
estuarine
ACTIVITY
nCi/l±2a
0.2 ± 0.2
<0.2
0.2 ± 0.2
0.3 ± 0.2
0.2 ± 0.2
< 0.2
< 0.2
INTERPRETED
RESULT
at m.d.l .
below m.d.l .
at m.d.l .
above m.d.l .
at m.d.l .
below m.d.l .
below m.d.l .
The minimum detectable level (m.d.l.) for the analysis of tritium is 0.2 nCi/1.
-------
-25-
TABLE VIII
PRE-OPERATIONAL TRITIUM IN WATER
LOCATION
Foxbird
Island
Eaton
Farm
Bailey
Farm
Young's
Creek
Chewonki
Neck(Camp)
Cowseagan
Narrows
Bluff
Head
DATE
COLLECTED
6/13/72
6/13/72
6/13/72
6/13/72
6/13/72
6/13/72
6/13/72
TYPE
estuarine
well
well
surface
well
estuarine
estuarine
ACTIVITY
nCi/l±2a
0.39 ± 0.2
0.40 ± 0.2
0.34 ± 0.2
0.14 ± 0.2
0.30 ± 0.2
0.09 ± 0.2
0.40 ± 0.2
INTERPRETED
RESULT
zero
zero
zero
zero
zero
zero
zero
-------
-26-
TABLE IX
POST-OPERATIONAL TRITIUM IN AIR MOISTURE
LOCATION
Eaton
Farm
Bailey
Farm
Westport
Fi rehouse
DATE
COLLECTED
8/27/74
8/27/74
8/27/74
WATER
QUALITY
MEASURED
32.8 ml
33.0 ml
25.4 ml
AIR
VOLUME
1280 1
1990 1
1730 1
MEASURED
RESULTS ±2o
nCi/1 WATER
< 0.2
< 0.2
< 0.2
INTERPRETED
RESULTS
nCi/1
zero
zero
zero
TABLE X
PRE-OPERATIONAL TRITIUM IN AIR MOISTURE
LOCATION
Eaton
Farm
Bailey
Farm
Westport
Fi rehouse
DATE
COLLECTED
6/29/72
6/15/72
6/27/72
WATER
QUALITY
MEASURED
33.7 ml
33,1 ml
33.4 ml
AIR
VOLUME
2502.7 1
2000.0 1
2500.0 1
MEASURED
RESULTS ±2a
nCi/1 WATER
0.60 ± 0.2
19.1 ± 0.2
0.60 ± 0.2
INTERPRETED
RESULTS
nCi/1
0.6
19.1
0.6
-------
-27-
TABLE XI
POST-OPERATIONAL TRITIUM IN PRECIPITATION
LOCATION
Eaton
Farm
Bailey
Farm
Knight
Cemetery
DATE
COLLECTED
8/27/74
8/27/74
4/9/74
TYPE
RAIN
RAIN
SNOW
MEASURED RESULTS
nCi/l±2a
< 0.2
0.3 ± 0.2
< 0.2
INTERPRETED
RESULTS
nCi/1
zero
0.3
zero
TABLE XII
PRE-OPERATIONAL TRITIUM IN PRECIPITATION
LOCATION
Eaton
Farm
Bailey
Farm
Knight
Cemetery
Westport
Fi rehouse
DATE
COLLECTED
6/30/72
6/30/72
3/11/72
3/11/72
TYPE
RAIN
RAIN
SNOW
SNOW
MEASURED RESULTS
nCi/U2a
0.40 ± 0.2
1.10 ± 0.2
0.26 ± 0.2
0.17 ± 0.2
INTERPRETED
RESULTS
nCi/1
zero
1.1
zero
zero
-------
-28-
2.232 Tritium in the Air Moisture
Tritium in the air moisture was measured in samples collected at the
following three sites, Eaton Farm, 0.4 km, W.; Bailey Farm, 0.8 km, N.E.;
and Westport Firehouse, 1.8 km, S. Air moisture samples were collected
by drawing nominally 2000 liters of air through a plastic cylinder (8 cm
(14 }
diameter by 24 cm long) containing a desiccantv ' . The desiccant used
was indicator type Dryrite. The cylinder of desiccant was weighed before
the air was pulled through and weighed afterward to insure the collection
of between twenty and thirty milliliters of air moisture. Nominal collection
time was between two and four hours depending on the relative humidity.
The desiccant cylinders were sealed and sent to the Eastern Environmental
Radiation Facility in Montgomery, Alabama for tritium analysis. Water
was exchanged with the desiccant moisture in a closed system. The resulting
samples were processed for liquid scintillation tritium analysis in the
usual way. The results of these measurements indicate the level for
tritium in the air moisture was below the minimum detectable level of
0.2 nCi/1 at all locations sampled on the data sampled (8/27/74).
2.233 Tritium in Precipitation
Tritium in precipitation was measured in two snow samples collected at
Knight Cemetery, l.l km, E. on April 9, 1974 and rain samples collected at
Eaton Farm, 0.4 km, W. and Bailey Farm, 0.8 km, N.E. on August 27, 1974.
These samples were filtered in the same manner used for the water samples.
(See section 2.22) Fifty mi 11iliter samples were sent to the Eastern
Environmental Radiation Facility, Montgomery, Alabama for tritium analysis
using the liquid scintillation method. (See section 2.231) The results
-------
-29-
of the analysis of tritium activity in the rain at Eaton Farm showed
it to be below the minimum detectable level of 0.2 nCi/liter and the level
at Bailey Farm to be 0.3 ± 0.2 nCi/liter, greater than the minimum detectable
level. Tritium activity in the snow samples was below the minimum detectable
level.
2.24 Discussion of Tritium Measurements
The purpose of tritium measurements in this study is to document
typical values for the HTO component in water, air moisture and precipitation
In general the results of tritium analysis indicate no significant change.
There is no evidence of an accumulation of tritium in the interchangeable
environmental reservoirs such as wells, surface water or the Montsweag Bay
(2)
estuary. Even though the Maine Yankee Environmental Impact Statement^
lists a bioaccumulation factor of 1 for tritium, the authors feel that in
light of the fact that tritium is one of the major radionuclide in the
liquid and gaseous effluent, that tritium monitoring should be carried out
on a regularly scheduled basis for a period of one half life (12.5 years)
in order to check for possible long term accumulation. The only
significant correlation between the pre-operational survey for tritium and
the post-operational survey is that the rain samples at the Bailey Farm
location contain tritium above the minimum detectable level. The large
amount of tritium in the air moisture observed on 6/15/72 in the pre-
operational survey was not observed in the post-operational study.
-------
-30-
2.3 Radionuclides in Air Particulates
2.31 Field Air Particulate Measurements and Analysis
Radionuclides in air participates were measured at three sites:
Eaton Farm, Bailey Farm and Westport Firehouse. A Staplex large volume
air sampler was used in conjunction with a 20.5 cm (8 1/16 inch) by
25.4 cm (10 inch) filter holder. Nuclear Associates, Inc. fiberglass
3
filters number 08-780 were used. Approximately 3400 ft of air were
filtered at each site. The filter was folded three times (8 layers) and
placed on the circular surface of the Nal(Tl) detector assemble used for
the soil and sediment field measurements, and covered with a 3 cm lead
shield. All air particulate field data were counted as soon after
collection as possible (normally within a few minutes) on quarter
memory (512 channels) for 2000 seconds. The multichannel analyzer was
outputted on the teletype. Qualitative analysis shows that the bulk of
the activity was due to daughters of 222Rn and 220Rn. After a period
of 24 hours the activity of particulate on the filters was found to be
long halflife radon daughters.
2.32 Laboratory Air Particulate Measurements
Air particulates for laboratory analysis were also collected at these
same sites (Easton Farm, Bailey Farm, Westport Firehouse). A Millipore
pump type XX6000000 was used to pull air through a 47 mm diameter Mi Hi pore
absolute aerosol 0.8 urn filter, type AAWP4700. The throughput of this
system was metered for all runs and a calibrated gas flow meter, American
Meter Company Model 10-300-PR1264. The meter, pump, and filter holder
were housed in an instrument box with a rubber hose from the filter holder
to the outside. A nominal sampling time was 100 hours, with a nominal sampling
-------
-31-
volume being 200,000 liters. The filters were weighed before and after
collection. They were packaged carefully in separate plastic boxes and
sent to the Eastern Environmental Radiation Facility; Montgomery, Alabama,
for gamma-ray analysis. Each sample was counted for gamma-rays in the
40 ml Nal(Tl) well-counter which is 11 cm x 15 cm and has a 3 cm well.
The results of these measurements are given in Table XIII. The gross-
alpha measurements were counted in an internal proportional counter and
the gross-beta measurements were counted in a low background beta counter.
The results of these measurements are also given in Table XIII. The
pre-operational measurements are listed in Table XIV.
-------
-32-
Discussion of the Air Participate Results
The short term field air particulate collections and measurements
reveal the presence of 220Rn and 222Rn as the most important source of
activity, essentially identical to the pre-operational study of 1972.
Large volume laboratory air particulate measurements as presented
in TABLES XIII and XIV show no significant changes.
2.4 High Pressure Ion Chamber
2.41 High Pressure Ion Chamber Measurements
High pressure ion chamber measurements had been carried out in 1971
by Wesley R. Van Pelt of Environmental Analysis, Inc. for Maine Yankee.
Due to the relevance for population dose calculations and for comparison
with the gamma-ray field studies, high pressure ion chamber measurements
were carried out in collaboration with Mr. Charles Phillips of the Eastern
Environmental Radiation Facility, Montgomery, Alabama. Both studies
employed calibrated Reuter Stokes high pressure ion chambers. In the
present study the ion chamber was RSS-111 (Reuter Stokes environmental
monitor), with Rustrak Recorder. The monitor was placed 1 meter above the
surface at 11 soil sites and 2 sediment sites. The soil sites were Foxbird
Island, 0.1 km, S.; Eaton Farm, 0.4 km, W.; Bailey Farm, 0.8 km, N.E.;
Young's Creek, 1.0 km, N.; Knight Cemetery, 1.1 km, E.; Westport Firehouse,
1.8 km, S.; Chewonki Neck (Camp) 1.9 km, S.W.; Cowseagan Narrows, 3.2 km,
N.E.; Bluff Head, 4.0, S.S.W.; Cromwells 1.0 km, E.; and sediment sites
Foxbird Island, 0,1 km, S.; and Murphy's Corner, 2.8 km, S.W.. The results
of these measurements are shown in Table XV. Table XV lists high pressure
ion chamber measurements of dose rate (yR/hr) for the post-operational and
(15)
pre-operational surveys. The most significant change occured at the
-------
-33-
Foxbird Island (sediment) site at 42 percent increase in dose rate was
measured. The last column lists post-operational calculated dose rate
based upon laboratory measurement of specific activity for all significant
gamma emitting radionuclides observed. The method used, due to Beck, is
(16)
discussed in Appendix C
-------
-34-
TABLE XIII
POST-OPERATIONAL AIR PARTICULATE ANALYSIS
.OCATION
Bailey
Farm
Eaton
Farm
Westport
Fi rehouse
COLLECTION
DATE
8/19/74
8/22/74
8/27/74
AIR VOLUME
LITERS
166,230
197,350
191,960
PARTICULATE
MASS
(GRAMS)
0.016 ±
0.001
0.004 ±
0.001
0.005 ±
0.001
a-ACTIVITY
pCi/FILTER
±2a
5.3 ± 68%
6.0 ± 70%
7.7 ± 55%
8- ACTIVITY
pCi/FILTER
±2a
29.3 ± 73%
25.4 ± 10%
4.4 ± 11%
Y-ACTIVITY
pCi/FILTER
±2o
34 ± 37%
(7Be)
4 ± 18%
(95ZrNb)
NONE
TABLE XIV
PRE-OPERATIONAL AIR PARTICULATE ANALYSIS
.OCATION
Bailey
Farm
Eaton
Farm
Westport
Fi rehouse
COLLECTION
DATE
6/19/72
7/5/72
6/29/72
AIR VOLUME
LITERS
97,740
86,730
101,810
PARTICULATE
MASS
(GRAMS)
0.002 ±
0.001
0.001 ±
0.001
0.004 ±
0.001
Y-ACTIVITY
ZrNb
<15 pCi ZrNb
< 5 pCi
<15 pCi
Y-ACTIVITY (7Be)
<200 pCi
< 50 pCi
<200 pCi
-------
TABLE XV
COMBINED PRE-OPERATIONAL AND POST-OPERATIONAL
HIGH PRESSURE ION CHAMBER MEASUREMENTS
SITE NAME
(measured over
soil unless
otherwise noted)
Foxbird Island
Eaton Farm
Bailey Farm
Young's Creek
Knight Cemetery
Westport Fi rehouse
Chewonki Neck Camp
Cowseagan Narrows
Bluff Head
Foxbird Island
(sediment)
Murphy's Corner
(sediment)
Cromwells
POST-OPERATIONAL
MEASUREMENTS
DATE
8/24/74
8/22/74
8/22/74
8/22/74
8/22/74
8/22/74
8/22/74
8/22/74
8/22/74
8/24/74
8/22/74
8/22/74
POST-OPERATIONAL
DOSE RATE
uR/hr
10.1
10.2
9.7
9.7
11.2
9.5
9.9
10.2
10.8
12.6
8.9
9.1
PRE-OPERATIONAL
MEASUREMENTS
DATE
-
9/20/71
9/20/71
-
-
9/21/71
-
-
-
9/21/71
9/21/71
-
PRE-OPERATIONAL
DOSE RATE
pR/h'r
-
9.5
9.5
-
-
11.4
-
-
-
7.3
7.91
-
POST-OPERATIONAL
CALCULATED DOSE
RATE (pR/hr)
8.9
12.0
12.0
11.7
13.0
9.6
10.2
10.9
12.3
14.51
10.8
-
-------
-36-
APPENDIX A
LIQUID EFFLUENT INVENTORY IN CURIES
TABLE XVI
140BaLa
133!
131!
133Xe
135Xe
137Cs
13-,Cs
60Co
58Co
5ICr
5"Mn
103Ru
9°Sr
"Mo
95Zr
95Nb
59 Fe
97Zr
UN
i33mXe
"Co
89Sr
3H
JULY-DEC 72
NDA
NDA
4.12 x 10"3
1.49 x 10"3
NDA
NDA
NDA
2.04 x 10"4
5.48 x 10"3
NDA
8.06 x 10"4
NDA
LOST
1.5 x 10"5
-
-
1.5 x 10"5
1.34 x 10"3
-
9.22
JAN-JUNE 73
NDA
NDA
1.62 x 10"3
7.05 x 10"2
NDA
NDA
NDA
3.34 x 10"3
6.56 x 10'2
2.68 x 10"2
1.12 x 10~2
NDA
NDA
NDA
3.1 x 10"3
2.9 x 10"3
5.95 x 10"3
-
-
-
-
75.67
JULY-DEC 73
NDA
NDA
4.12 x 10"3
1.49 x 10"3
NDA
NDA
NDA
2.04 x 10"4
5.48 x 10"3
NDA
8.06 x 10'4
NDA
LOST
1.50 x 10"5
.
1.5 x 10"5
-
-
-
-
771. 9
JAN-JUNE 74
6.09 x 10"5
2.93 x 10"3
2.76 x 10"1
11.7
7.78 x 10"3
6.15 x 10"3
2.53 x 10~3
5.41 x 10"3
2.17 x 10~2
3.78 x 10~2
1.99 x 10"3
NDA
1.40 x 10"5
2.30 x 10"3
1.54 x 10"3
2.62 x 10"3
_
-
6.48 x 10"5
9.38 x 10"6
-
115
JULY-DEC 74
NDA
8.20 x 10"2
1.04 x 10~2
NDA
9.81 x Kf1
7.31 x 10"1
1.46 x 10"2
2.60 x 10"1
_
NDA
-
NDA
_
_
1.19 x 10"3
_
-
-
NDA
2.94 x 10"5
104
6.09 x 10"&
2.93 x 10"3
0.37
11.78
7.78 x 10"3
9.9 x 10"1
7.3 x 10"1
2.3 x 10"2
3.58 x 10"1
4.04 x 10"1
1.48 x 10"2
NDA
1.40 x 10"5
2.33 x 10"3
4.64 x 10"3
5.52 x 10"3
7.14 x 10"3
3.0 x 10'5
1.34 x 10"3
6.48 x 10"5
9.38 x 10"6
2.94 x 10"5
3.81 x 102
-------
-37-
TABLE XVI
GASEOUS EFFLUENT INVENTORY IN CURIES
137Cs
140BaLa
90Sr
13l)Cs
89Sr
58Co
6°Co
5l*Mrr
110Ag
"Co
"Mo
131!
133!
135!
85Kr
133Xe
88 Kr
87 Kr
138Xe
35mXe
41 Ar
33mXe
3imXe
88 Rb
85mKr
i35Xe
51Cr
95Nb
OCT-DEC 72
NDA
NDA
NDA
NDA
_
-
-
1.71 x 10"6
NDA
NDA
2.05
NDA
NDA
NDA
NDA
NDA
7.1 x 10"2
-
-
NDA
_
_
-
JAN-JUNE 73
NDA
NDA
NDA
NDA
3.9 x 10"6
-
-
-
-
9.39 x 10"6
NDA
NDA
6.3 x 10"3
6.36
NDA
NDA
NDA
NDA
NDA
-
8.9 x 10"2
NDA
NDA
_
-
JULY-DEC 73
NUA
NDA
NDA
NDA
8.91 x 10"5
-
-
-
-
1.62 x 10"3
3.28 x 10'4
NDA
1.505
151.56
NDA
NDA
NDA
NDA
1.00 x 10'1
-
NDA
-
NDA
1.27 x 10"1
-
-
JAN-JUNE 74
3.51 x 10"5
NDA
1.37 x 10"5
2.3 x 10"5
5.1 x 10"6
2.2 x 10"8
2.9 x 10"6
6.58 x 10'2
3.00 x 10"2
5.79 x 10"3
3.50 x 102
3.81 x 103
NDA
NDA
NDA
NDA
NDA
4.91 x 101
NOA
NDA
1.90 x 102
8.4 x 10"6
1.78 x 10'6
JULY-DEC 74
NDA
NDA
_
NDA
3.32 x 10"4
1.72 x 10"4
NDA
NDA
2.10 x 10"5
2.90 x 10"6
4.98 x 10"2
1.48 x 10"3
NDA
4.36 x 102
2.41 x 103
NDA
NDA
NDA
NDA
NDA
3.30
7.78 x 101
NDA
B.50 x 10"1
-
-
-------
-38-
APPENDIX B
PRE-SCAN RESULTS
The purpose of a pre-scan is to determine the optimum locations for
the field studies. For this reason, the pre-scan was planned to take
place early in the field studies and to provide usable results during the
first week of the study. As is mentioned in section 2.11 of off-site soil
measurements and their analysis, gamma-ray pre-scans were taken on kilogram
samples from nine soil and two sediment sites. Samples were counted for
5000 seconds using the University of Maine Department of Physics Ge(Li)
detector with low background shield. The lists of counts were then compared
with lists of counts taken on pre-operational samples, collected in 1972.
The examination of these lists provided the information for choosing the
field locations. Later, punched tapes of these spectra were analyzed at
the University of Maine Computer Center. The results of these analysis are
shown in Table XVIII. Radionuclide concentrations are shown in picocuries
per kilogram of sample. The first five columns of this table contain
concentrations of natural isotopes: 228Ac, 208T1 of the Thorium series,
214Pb, 214Bi of the Urnaium series, and 1+0K. The remaining columns of
concentrations are of man-made fallout or reactor origin. Trace amounts of
46Sc or 65Zn were observed at Foxbird Island, Eaton Farm, Bailey Farm,
Young's Creek, Knight Cemetery, Bluff Head, and Murphy's Corner, but could
not be quantitatively determined due to interference from 21l+Bi. The
radionuclides 95Nb-95Zr (200 pCi/kg) were observed at Foxbird Island, Bailey
Farm, Young's Creek, Knight Cemetery, Westport Firehouse, Bluff Head, Murphy's
Corner and Foxbird Island sediment, and 131I (300 pCi/kg) may have been
observed in Murphy's Corner sediment. Errors are quoted under each number
and represent ±lo.
The site which showed largest amounts of man-made radionuclides was
-------
-39-
Foxbird Island (sediment). There was on archival pre-scan result for this
sample and Murphy's Corner sediment since there were no archival samples.
In all other cases, pre-operational and post-operation samples were
available and results are given in pairs in the table. Dashes in the table
mean that results were below the minimum detectable limit. As a result of
studying the pre-scan results (using the original lists) we selected for
field studies: Foxbird Island soil and sediment, Eaton Farm, Bailey Farm,
Knight Cemetery, soils and Murphy's Corner sediment.
-------
TABLE XVIII PRE-SCAN RADIONUCLIDES pCi/kg ± lo
LOCATION
Foxbird
Island
Eaton
Farm
Bailey
Farm
Young's
Creek
Knight
Cemetery
Westport
Firehouse
Chewonki
Neck Camp
Cowseagan
Narrows
Bluff
Head
Murphy
Corner
Foxbird
Island
DATE OF
COLLECTION
6/29/72
8/14/74
6/12/72
8/14/74
6/12/72
8/14/74
6/12/72
8/14/74
6/12/72
8/14/74
6/12/72
8/14/74
6/12/72
8/14/74
6/13/72
8/14/74
6/12/72
8/14/74
8/14/74
8/14/74
DATE OF
MEASUREMENT
8/15/73
8/17/74
8/14/73
8/19/74
8/14/73
8/17/74
8/16/73
8/19/74
9/21/73
8/17/74
8/17/73
8/19/74
9/19/73
8/20/74
8/17/73
8/19/74
8/21/73
8/17/74
8/20/74
8/20/74
TYPE
soil
soil
soil
soil
soil
soil
tidal marsh
soil
tidal marsh
soil
soil
soil
soil
soil
soil
soil
soil
soil
soil
Sed.
Sed.
228Ac
600
±400
600
±400
1100
±200
1300
±300
1400
±300
700
±200
1200
±200
1400
±300
2400
±400
1700
±500
1100
±200
400
±200
1300
±300
600
±200
700
±300
1000
±200
1900
±300
1300
±300
1100
±200
600
±100
208T1
600
±200
1400
±200
1200
±200
1600
±200
700
±200
1400
±200
1800
±300
1600
±200
1400
±200
800
±200
1100
±200
1300
±300
700
±200
900
±300
1100
±200
1100
±200
1500
±200
1100
±200
1400
±300
2mpb
1000
±100
700
±500
1100
±200
1400
±200
2000
±200
1000
±100
1600
±200
1000
±100
1600
±200
1400
±200
1700
±200
1200
±200
1500
±200
800
±100
1600
±200
1700
±200
2000
±200
1300
±200
1300
±200
±37°0°0
21"Bi
700
±200
700
±200
900 '
±100
800
±200
900
±100
800
±100
800
±100
800
±200
1400
±300
1100
±200
1000
±100
700
±200
1200
±200
600
±200
800
±200
700
±100
1600
±200
1100
±200
1000
±200
2000
±200
4°K
11000
±1000
10000
±1000
15000
±1200
15000
±1200
17000
±1400
15000
±1200
18000
±1100
14000
±1300
13000
±1400
10000
±1200
10000
±900
11000
±1300
16000
±1400
10000
±1200
17000
±1700
10000
±1000
12000
±1100
12000
±1100
12000
±1000
8000
±900
137Cs
800
±100
5400
±400
1900
±100
1900
±100
1300
±100
1800
±100
500
±100
800
±100
6200
±300
3600
±200
1300
±100
2200
±200
5000
±300
1700
±100
4000
±200
2500
±200
1800
±200
400
±200
910
±100
58Co
-
-
-
80
±50
-
50
±50
-
120
±64
80
±50
100
±40
19000
±400
60,,
Co
60
±30
-
-
-
70
±50
60
±50
40
±50
30
±20
160
±70
90
±44
40
±50
30
±50
:
20
±30
±8l88
u,cs
200
±60
600
±80
4dO
±70
200
±60
300
±60
100
±100
300
±60
300
±60
600
±80
300
±60
300
±60
100
±30
300
±60
200
±60
81
±20
100
±30
400
±70
400
±70
1000
±80
5"Mn
-
20
±30
-
-
-
-
-
25
±30
20
±30
-
200
±60
o
I
-------
-41-
APPENDIX C
Calculation of Dose Rate at One Meter from Gamma-Ray Emitting
Soils and Sediments
Calculation of gamma-ray dose rate due to a plane source such as soil
or sediment is of practical importance. The factors for conversion from
the isotope concentration of the plane medium to dose at one meter above
the surface for 40K, 137Cs, 60Co, 232Th-series and 238U-series are found
in a paper due to Beclo1 '17). Two new factors, using Beck's Table 7 and
branching ratios from the literature, are calculated for 58Co and 134Cs.
These eight factors are presented in Table XIX. Dose Calculations for
eleven sites are presented in Table XV. The cosmic ray contribution is
included using ionization chamber data gathered by W. Van Pelt^15' over
water in 1971.
-------
-42-
TABLE XIX
Factors for Computation of Dose Rate at 1 Meter due to Gamma-Ray
Emitting Radionuclides in Soil and Sediment
Isotope
Natural
/
Man Made
40K
238U-Series
232Th-Series
137Cs
58Co
60Co
54Mn
131tCs
Factor
(yR/h per pCi/g)
0.179
1.82
2.82
(pR/h per mCi/km )
X10"3
4.29
7.25
18.0
6.3
11.4
-------
-43-
TABLE XX
POST-OPERATIONAL LABORATORY RESULTS USED IN CALCULATION OF
DOSE RATE (uR/h) 1 METER ABOVE GROUND
LOCATION
Foxblrd
Island
(soil)
Eaton ' s
Farm
(soil)
Bailey's
Farm
Young's
Creek
(soil)
Knight
Cemetery
(soil)
Westport
Fi rehouse
(soil)
Chewonki
Neck (Camp)
(So'il)
Cowseagan
Narrows
(soil)
Bluff
Head
(soil)
Foxbird
Island
(sed.)
Murphy's
Corner
(sed.)
"°K
1.30
3.14
3.15
3.47
2.02
2.11
2.70
2.55
2.38
3.67
3.22
238U-series
1.24
2.00
2.00
1.45
2.36
1.45
1.27
1.82
2.91
1.64
1.45
232Th--series
2.53
3.10
3.10
3.10
4.79
2.25
2.53
2.82
3.38
2.54
2.53
137Cs
.22
.12
.05
.03
.19
.15
.07
.06
.06
.06
.02
TOTAL
GAMMA-RAY
DOSE RATE
5.29
8.36
8.30
8.05
9.36
5.96
6.57
7.25
8.73
7.91
7.20
COSMIC
RAY*
3.60
3.60
3.60
3.60
3.60
3.60
3.60
3.60
3.60
3.60
3.60
GRAND
TOTAL1"
8,89
11.96
11.90
11.65
12.96
9.56
10.17
10.85
12.33
14.45
10.80
*Taken over water in 1971 by W. Van Pelt
Deluding 13ltCs, 58Co, 60Co and 5l+Mn (2.93yR/h)
-------
-44-
APPENDIX D
A Model for Radionuclides in Oysters and Associated Sediments*
INTRODUCTION
The variation of the concentration of gamma-ray emitting radionuclides
has been observed and modeled in a stable population of American oysters
(C. virginica), and associated estuarine sediments during 12 months at four
sites in the Montsweag Estuary in the effluent of the Maine Yankee Nuclear
Power Reactor and at a control site in the Damariscotta Estuary. Gamma-
ray peaks have been observed at 0.810 MeV (58Co), 1.173 and 1.332 MeV (60Co),
1.732 (40K), 0.835 MeV (54Mn), 0.765 MeV (95Nb), 0.238 MeV (212Pb), and
0.662 MeV (137Cs) using a Ge(Li) detector. The concentration of the most
abundant man-made isotopes 58Co, 60Co, and 54Mn have been compared at selected
sites with a mathematical model for the accumulation and loss of these
nuclides by the oysters and sediments.
PREVIOUS WORK
Radionuclide accumulation and loss have been studied in oysters by
Seymour^18', Jefferies and Preston^19', Naidu and Seymour^20', Nelson and
Seymour^ , Wolf^ , Lowman, Rice and Richards^^'; and radionuclide
accumulation has been studied in sediments by Heft, Phillips, Ralston, and
Steel^ ', Noshkin and Bowen^ ' and Lentsch, et. al.^ ' among others.
Models, field studies and laboratory studies of accumulation and depuration
have been undertaken for radionuclides in reactor effluent for 137Cs and
60Co in the marine clam, Harrison^ '; 58Co in the mussel, Mytilus edulis,
Shimizu et. al.^28' ; Teleost and Elasmobranch fish, Pentreath^29', and for
several organisms by Lowman, et. al. .
*This work was supported in part by a grant from the National Oceanic and
Atmospheric Administration, number 04-3-158-63.
-------
-45-
Mathematical models for accumulation of radionuclides, are usually
based on a constant source of radionuclides, a condition which is generally
convenient and applicable for laboratory studies however, must provide for
the time variation of the sources of radionuclides since in the case of
nuclear reactors the liquid, radionuclide effluents are usually released
according to some schedule with waiting periods between releases, as
discussed by Heft et.al.^2 '. This variation of source intensity can be
included in the mathematical model by driving the first order linear
differential equation for accumulation and decay with a time varying function
representing the release schedule^1'. This model corresponds mathematically
to an impulsively driven relaxator with characteristic relaxation times for
the various mechansims of accumulation and decay.
EXPERIMENTAL DESIGN
Five groups of American oysters were grown: 4 Montsweag Estuary
locations (intake of the reactor SI, outflow of the reactor S2, upper cove
S3 and 0.58 km, N., Long Ledge S4, 1.29 km. S.) and at a control site
located on the Damariscotta Estuary S5. At approximately two month intervals,
the live oysters were removed from their trays, and transported to the
Ge(Li) detector enclosed in a low background shield. Approximately 1 liter
of live oysters were counted for 5000 seconds and the resulting data were
(8)
computer processed using the Compton continuum subtraction method .
After counting, the oysters were returned to their original locations. The
concentrations of radionuclides were determined using standard techniques
to calibrate the multichannel analyzer-detector-shield system.
-------
-46-
Seven sediment sites were chosen (intake sediment Ml, outflow M2, Upper
cove M3, Long Ledge M4, Murphy Corner, M5, 2.98 km S.W., Oak Island M6,
2.90 km S.W., and Bluff Head M7, 4.39 km S.W.) At approximately two month
intervals, 2 Kg sediment samples were collected at each of the sites and
gamma-ray analyzed in the same manner as the oysters.
THEORY
The uptake of radionuclides may be described by a first order linear
differential equation
dN
where -rr is the rate of increase in atoms of nuclide N, AN is the rate of
dt
loss due to radioactive decay, and R(t) is the rate of introduction of
nuclides from an external source (i.e. the nuclear reactor release schedule)
Depuration is included by writing a term XpN which describes the ("Biological
Decay") observed experimentally by Seymour^ '.
-+ AN + ApN = R(t). 2)
The solution to Eq. 1 may be written
N = e"U\ eUR(t) dt + ce"Xt. 3)
We assume that releases of nuclides are made on a sequence of m times,
{t., tp, t_, .......... t } and the amount of nuclide released is given by a
function f(t) which for times greater than or equal to t, but less than t?
is given by f 6(t-tJ, and for times greater than or equal to t? but less
than t,. by f,<5(t-t,J and so on up to times greater than .t . The fraction
o L. C- rn
of the nuclide which was released and is retained is given by U, so that
for the accumulation N(t)
-------
-47-
N(t) = e-At C Ve extf (t_ } +
J ! !
o
e-At (JV eAtV(t-tJ U d t + c e~ t. 5)
If U. is a constant ratio of retention for all time, we can construct a
table of functions for the times between the release time.
o < t < t1 N(t) = ce"At
t, < t < t, N(t) = Uf^-^*-*^ + ce'At
t2 < t < t3 N(t) = Uf2e'A(t-t2) + U^e'^-V + ce'At
These equations may be interpreted as a gradual decay of isotopes from the
release-time until the next release-time. Sudden increases occur at each
release-time. Graphs of two typical cases are shown in Fig. 5, which shows
the results for a half life (58Co) comparable to two release intervals,
as well as a half life (50Co) comparable to 60 release intervals.
OYSTER RESULTS
The concentration expressed in pCi of the radionuclide 58Co is shown
per gram of oysters in Fig. 6. The broken lines represent the experimental
values for this isotope in the four Montsweag Estuary sites and the Damari-
scotta Estuary control site from June 73 through July 74. The theoretical
results are shown with a solid line from May 73 through June 74. The same
peak found in the theory is evident at the outflow, Long Ledge and intake
sites and a small increase may be seen in the control site in October. The
best agreement occurs (comparison may be made) between the outflow site and
the theory. It is evident that the oysters show a faster decrease in activity
in Dec. 73 through Feb. 74 than that predicted by theory. This may be
-------
-48-
140 n
o
o
UJ
CE
n
o
120-
40-
FEB APR JUN AUG OCT DEC FEB
TIME IN MONTHS 1973- 1974
APR
JUN
Figure 5, Calculated Accumulation of 58Co and 60Co as a Function of Time
The solid line shows the theoretical accumulation of 58Co in millicuries
versus month of year from Feb. 1973 through July, 1973. The dashed line
shows the theoretical accumulation of60Co in millicuries versus month of the
year from Feb. 1973 through June, 1974.
-------
-49-
AUG OCT DEC FEB APR
AUG OCT DEC FEB APR JUN
TIME IN MONTHS (1973-1974)
AUG
Figure 6. Calculated and Measured Accumulation of 58Co as a Function of Time
The upper half shows the radionuclide 58Co in oysters at site SI
(intake) triangle and dot-dash, site S2 (outflow) square and dash, site S3
(Upper cove) circle and dot-dash, site S4 (Long Ledge) triangle and dot,
SC (control site) hexagon dash-dot-dot, and theoretical curve for outflow
site with filled circle and solid line, versus time in montns, for the years
1973-1974. The lower half shows the radionuclides 58Co in sediments at
sediments sites Ml (intake) with triangle dash-dat, M2 (outflow) with square
dash, M3 (Upper cove) circle dash-dot, M4 (Long ledge) with triangle dot and
theoretical curve for outflow site with cricle solid line versus time in
months from Aug. 1973-July, 1974;
-------
-50-
explained as the depuration of isotopes from the oysters during these
months.
The concentration of the radionuclide 51tMn for the outflow site
was found to be practically flat during this time and compare favorably
with theory within statistical errors in the measurement. In addition to
the 58Co and 54Mn results, small amounts of 60Co are observed in Oct. 73
at the outflow, Jan. 74 at Long Ledge and Oct. 73 and Jan. 74 at Upper
Cove. Small amounts of 5ttMn is also observed on July 73, Dec. 73 and
Jan. 74 at Long Ledge and Jan. 74 at the control site. The naturally
occurring isotope t*°K is observed at all sites for all measurements and
its variation is correlated with variation in the salinity.
SEDIMENT RESULTS
The concentration expressed in pCi of 58Co per gram of sediments is
shown in Fig. 6. The broken lines represent the experimental values for
this isotope in four Montsweag Estuary sites from Sept. 73 through July
74. The solid line represents the theory for the time from Aug. 73
through June 74. The best comparison can be made fro the outflow site
which has the largest concentration and shows a broad peak in the months
Sept. 73 through Jan. 74. The decrease of 58Co during Jan - Feb. 74, is
more rapid than theory predicts and represents depuration due to loss of
radioactivity from the sediments. The other sites had a factor of 10 less
isotope than this site, and insufficient data for further conclusions.
The radionuclides tt°K, 58Co, 60Co, 54Mn observed in the outflow
sediment may be averaged, and compared. These radionuclides are expressed
in picocuries/gram of sediment and are averaged for monthly values for the
time period Aug. 73 - March 74. The average values in order of decreasing
concentration are 40K, 5.7 pCi/gm, 58Co, 4.9 pCi/gm, 60Co, 0.8 pCi/gm,
-------
-51-
and 54Mn, 0.2 pCi/gm. All of these isotopes have maximum values in the
month of Nov. 73. Most of the isotopes show a decrease in the month of
Dec. 73 which is correlated with a salinity drop in the estuary. The
decreases in both 60Co and 5ttMn may be interpreted as the combined effect
of radioactive decay and depuration. The effective depuration rate for the
outflow sediment during this time was 150 ± 30 days for 60Co. The depuration
rate for the 51+Mn is 180 ± 50 days.
The radionuclides 95Nb, 212Pb, 137Cs in the outflow sediment may also
be averaged and compared. In order of decreasing concentration, these are
95Nb, 0.8 pCi/gm, 212Pb, 0.4 pCi/gm and 137Cs, 0.2 pCi/gm. These radio-
nuclides show a maximum during the month of Nov. 73 for 95Nb and March 74
for the 212Pb and 137Cs. Since the initial values of 212Pb, 137Cs and
95Nb95Zr in soil and sediments measured prior to the plant operations were
large, comparison with theory is not attempted for these nuclides. The
sediment sites, M5 M6, and M7 showed only lf°K, 212Pb and 137Cs.
DETERMINATION OF UPTAKE RATIO U
Since theory and experiment seem to agree, it is possible to divide
the radionuclide in oysters or sediments (Fig. 6) by the calculated
accumulation (Fig. 5) to form an uptake ratio U. The values for U indicate
that most of the radioactivity is concentrated in the region of outflow,
decreasing rapidly with distance. There is also variation of concentration
from radionuclide to radionuclide with 58Co strongest, 60Co weaker and
54Mn weakest for both sediments and oysters.
-------
-52-
SUMMARY OF APPENDIX D
Oysters have been grown in the effluent of a nuclear reactor and
have been used in a longitudinal study of radionuclide uptake and depuration
The radionuclides 58Co, 60Co and 54Mn have been observed experimentally in
the oysters and associated sediments. At selected sites, the variation
of radionuclides in both oysters and sediments was found to be in good
agreement with predictions of a mathematical model, which incorporates
radioactive decay and a time dependent driving source of radionuclides
due to the liquid effluent release from the reactor. Values for an average
uptake ratio U, are then calculated for selected sites. Maximum values
of 58Co of 800 pCi/kg results in an annual dose rate of 0.27 mrem/year;
Maximum values of 51tMn of 12 pCi/kg results in an annual dose rate of
0.004 mrem/year.
-------
-53-
PRE-OPERATIONAL LABORATORY WATER GAMMA-RAY ANALYSIS
OF THE DISSOLVED COMPONENT
APPENDIX E
TABLE XXI
LOCATION
Foxbird
Island
Eaton
Farm
Bailey
Farm
Young's
Creek
Chewonki
Neck(Camp)
Cowseagan
Narrows
Bluff
Head
TYPE
estuarine
well
well
surface
well
estuarine
estuarine
DATE
COLLECTED
6/13/72
/13/72
6/13/72
6/13/72
6/13/72
6/13/72
6/13/72
6/13/72
6/13/72
DATE
COUNTED
6/22/72
6/22/72
6/22/72
6/29/72
6/22/72
6/22/72
6/27/72
6/22/72
6/22/72
40K
gm/l±2a
0.18
±0.06
<0.10
<0.10
<0.10
<0.10
<0.10
<0.10
0.19
±0.06
0.16
±0.06
137Cs
pCi/l±2o
<2.0
<2.0
<2.0
<2.0
<2.0
<2.0
<2.0
<2.0
<2.0
222Rn
pCi/l±2a
<4.0
<4.0
81.0 ± 13.0
<4.0
<4.0
98.2 ± 19.2
<4.0
<4.0
<4.0
(All samples were counted for 50 minutes in a 3.5 liter Marinelli beaker geometry)
-------
-54-
REFERENCES
1. Maine Yankee Atomic Power Company Wiscassett, Maine, "Semi-Annual
Report of Release of Radioactive Materials", 1972-1975.
2. Maine Yankee Atomic Power Company, Wiscassett, Maine, "Maine Yankee
Environmental Impact Statement", 1974.
3. Kahn, B., "Radionuclides in the Environment at Nuclear Power Stations",
AEC Proceedings CONF-710501-P1, 30-36 (1971).
4. Rowe, W. D., U. S. Environmental Protection Agency Office of Radiation
Programs, "Environmental Radioactivity Surveillance Guide" ORP/SID 72-2
(1972).
5. Lentsch, J. W., et. al., "Stable Manganese and Manganese-54 Distributions
in the Physical and Biological Components of the Hudson River Estuary",
in AEC Proceedings Conf-710501-Pl, 752-768 (1971).
6. Hess, C. T., C. W. Smith, H. Kelley, F. C. Rock, "A Radioactive Isotopic
Characterization of the Environment Near Wiscassett, Maine: A Pre-
Operational Survey in the Vicinity of the Maine Yankee Nuclear Reactor",
Rad. Data. Rep. 15_, 39-52 (1974).
7. Hess, C. T., C. W. Smith, "Calibration Method for In-Situ Environmental
Radiation Measurements Using Top Shielded 2-n Geometry." Bull. Am. Phys.
Soc. Series II, JL8_, 242 (1973).
8. CoveTl, D. F. Anal. Chem. 3l_, 1785 (1959).
9. Schonfeld, E., "Alpha-A Computer Program for the Determination of
Radioisotopes by Least Squares Resolution of the Gamma-Ray Spectra",
ORNL-3810 (July, 1965).
10. Lerman, A., "Time to Chemical Steady-States in Lakes and Oceans, in:
Non-Equilibrium Processes in Natural Water Systems, J. D. Hem. Symp.
Chair., Amer. Chem. Soc. Adv. Chem. Ser. 106: 30-76 (1971).
11. Fukai, R., C. N. Murray, "Environmental Behavior of Radiocobalt and
Radiosilver Released for Nuclear Power Stations into Aquati.c Systems",
IAEA-SM-172/42, 217-241 (1973).
12. Freke, A. M., "A Model for the Approximate Calculation of Safe Rates of
Discharge of Radioactive Wastes into Marine Environments", Health Physics
13, 743-758 (1967).
13. Cutshall, N., C. Osterberg, "Radioactive Particle in Sediment from
the Columbia River", Sci. 144, 536-537 (1964).
14. Cochran, J. A., D. G. Smith, P. J. Magno, B. Shlein, "An Investigation
of Airborne Radioactive Effluent from an Operating Nuclear Fuel
Reprocessing Plant". BRH/NERHL 70-3, p. 26, (1970).
-------
-55-
15. Van Pelt, W. R., "Environmental Radiation Survey for Maine Yankee
Atomic Electric Company", Westboro, Massachusetts, (1971).
16. Beck, H. L., "The Physics of Environmental Gamma Radiation Fields".
Second International Symposium on the Natural Radiation Environment,
Houston, Texas, (1972).
17. Beck, H. L., J. De Campo, C. Gogolak, "In Situ Ge (Li) and Nal(tl)
Gamma-Ray Spectrometry", HASL-258 (1972"T
18. Seymour, A. H., "Accumulation and Loss of Zinc-65 by Oysters in a
Natural Environment in Disposal of Radioactive Wastes into Seas,
Oceans and Surface Waters", Int. Atomic. Eng. Agency, Vienna
605-619 (1966).
19. Jefferies, D. F., and A. Preston, "Summary of Field Studies in the
United Kingdom", in Proc. Seminar on Marine Radioecology, Paris
CONF-681225, 67-71 (1969).
20. Naidu, J. R., and A. H. Seymour, "Accumulation of Zinc by Oysters in
Willapa Bay, Washington", in Proc. Symp. on Mollusca, II Mar. Biol.
Assoc. India, Symp. Ser. 3, p. 463-474 (1969).
21. Nelson, V. A., A. H. Seymour, "Oyster Research with Selected Radio-
nuclides a Review of Selected Literature", Proc. Nat. Shellfish
Assoc. 62_, 89-94 (1972).
22. Wolf, D. A. "Levels of Stable Zn and 65Zn in Crassostrea virginica
from North Carolina", J. Fish, Res. Bd. Canada, 27_, 47=57 (1970).
23. Lowman, F., T. R. Rice, F. A. Richards, "Accumulation and' Re-
distriubtion of Radionuclides by Marine Organisms in Radioactivity
in the Marine Environment, National Acad. of Sciences, Washington,
UTT:(1971).
24. Heft, R. E., W. A. Phillips, H. R. Ralston, W. S. Steel, "Radionuclide
Transport Studies in the Humbolt Bay Marine Environment" IAEA-SM-158/26,
595, (1973).
25. Noshkin, V. E., V. T. Bowen, "Concentrations and Distributions of
Long-lived Fallout Radionuclides in Open Ocean Sediments in "Radioactive
Contamination of the Marine Environment" IAEA, Vianna, (1973).
26. Lentsch, J. W., et. al., Ibid.
27. Harrison, F. L., "Accumulation and Loss of Cobalt and Caesium by the
Marine Clam Mia arenaria under Laboratory and Field Conditions" IAEA-
SM- 158/28 45TT1973).
28. Shimizu, M., T. Kajihara, I.Suyama, Y. Hiyama, "Uptake of 58Co by
Mussel Mytilus edulis, J. Radiat. Res., 12, 17 (1971).
-------
-56-
29. Pentreath, R. J., "Roles of Food and Water in the Accumulation of
Radionuclides by Marine Telost and Elasmobranch Fish" IAEA-SM-158/26
421 (1973).
30. Lowman, R., T. R. Rice, F- A. Richards, Ibid.
GPO 904-363
------- |