United States
Environmental Protection
Agency
Office of Radiation Programs
Eastern Environmental
Radiation Facility
P.O. Box 3009
Montgomery, AL 36193
EPA 520/5-82-008
May 1982
Radiation
&EPA
Assessment of Fallout in The
United States from The
Atmospheric Nuclear Test by
The People's Republic of China
On September 17, 1977
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ASSESSMENT OF FALLOUT IN THE UNITED STATES FROM
THE ATMOSPHERIC NUCLEAR TEST BY
THE PEOPLE'S REPUBLIC OF CHINA ON
SEPTEMBER 17, 1977
J. Michael Smith
David L. Norwood
Ann B. Strong
Jon A. Broadway
July 1979
Publication Date: May 1982
U. S. Environmental Protection Agency
Office of Radiation Programs
Eastern Environmental
Radiation Facility
P. 0. Box 3009
Montgomery, AL 36193
-------
List
of Figures
TABLE OF CONTENTS
[[[
Li s t of Tab 1 es
Foreword
Preface
............................... ...................... ....
[[[ ........
[[[ ..........
Acknowledgement
Abstract
1.0
2.0
3.0
4.0
........................... ....... ............ .... ......
..... .............. ..... ........... ........ ....................
Introduction
Description of Fallout Incidents
Concerns for Fallout
EPA Responsibilities
Purpose and Scope of This Report
............................................ ....... ...
1.1
1.2
1.3
1.4
.. ....... ...............
...................
............................... .
................................... .
EPA Monitori ng
2.1
2.2
2.3
Movement
EPA
Program
................................... ....
ERAMS
.......................................... .........
Airborne Particulates and
Pasteurized Milk Sampling
Sampling
Precipitation
........
........................ .......
of Contaminated
Air Masses
-------
5.0 Air Particulate and Precipitation
Measurements ....................
6.0 Pasteurized Milk
Mea 5 U rem en t s .....................................
7.0 Radiation Dose Assessments ........................................
7.1 Dose Types and Pathways 8.....................................
7.2 EERF Gamma Scanning Procedures ...............................
7.3 Dose Estimates for Individuals ...............................
7.4 Population Dose Calculations .................................
8.0 Health Effects Assessment ........................................~
8.1 Relationship Between Radiation Doses and Health Effects ......
8. 2 Pro j e c t ed He a 1 thE f f e c t s .....................................
9.0 Di scuss i on [[[
9.1
Philosophy Regarding Calculation of Environmental Doses
and Effects.................................................
9.2
9.3
Review of Calculational Uncertainties for Dose Calculations ...
Significance of Estimated Doses and Health Effects ............
1 O. 0 Summa r y and Con c 1 us ion s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
10. 1 Summa ry .............. e 8 . . . . . . . . . . . II . . . . . . . . . . . . . . . . 41 . . . . . . . . . .
10.2 Conclusions [[[
Appendixes
A. Additional Infonnation on Individual and Population
Dose Ca 1 cul at ions.,.........."..".. .... ... . . .". " .". "." ". """
B.
EPA Policy Statement on Relationship Between Radiation Dose
and Effect.".""."""" 8"""..."""...""".."."""".""""".."."..""
References
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LIST OF FIGURES
Figure
1
Environmental Radiation Ambient Monitoring System (ERAMS) air-
borne particulates and precipitation sampling locations .......
2
ERAMS pasteurized milk component sampling locations ...........
3
Estimated path from China to the U.S. of debris at 300 millibar
level (approximately 30,000 ft.) for the Chinese nuclear de ton a-
tion of September 17, 1977 ....................................
4
Approximate path across the U.S. of leading edge of debris at the
300 mill ibar level (approximately 30,000 ft.) from the Chinese
nuclear detonation of September 17, 1977 ......................
5
Distribution of gross beta in airborne particulates (pCi/m3).
Laboratory measurements for September 22, 1977. ...............
6
Distribution of gross beta in airborne particulates (pCi/m3).
Laboratory measurements for September 24, 1977 ................
7
Distribution of gross beta in airborne particulates (pCi/m3).
Laboratory measurements for September 25, 1977.................
8
Distribution of gross beta in airborne particulates (pCi/m3).
Laboratory measurements for September 27, 1977.................
9
Distribution of gross beta in airborne particulates (pCi/m3).
Laboratory measurements for September 29, 1977 ................
iv
Page
5
7
9
10
13
14
15
16
17
-------
Figure
(continued)
10
Distribution of gross beta in airborne particulates (pCi/m3).
Laboratory measurements for October 2, 1977 ...................
11
Distribution of gross beta in airborne particulates (pCi/m3).
Laboratory measurements for October 14, 1977 ..................
12
Average concentration distribution of iodine-131 in milk
(pCi/1) for September 25 - October 1,1977 ....................
13 Average
(pCi/1)
14 Average
( pC i / 1)
15 Average
(pCi/.t)
16 Average
(pC i / .t)
concentration distribution of iodine-131 in milk
for October 2 - 8, 1977 ...............................
concentration distribution of iodine-131 in milk
for October 9 - 15, 1977 ..............................
concentration distribution of iodine-131 in milk
for October 16 - 22, 1977 .............................
concentration distribution of iodine-131 in milk
for October 23 - 29, 1977 .............................
17
Average concentration distribution of iodine-131 in milk (pCi/.t)
for November 6 - 30,1977 .....................................
18
Net iodine-131 concentration in milk as a function of date
AK .............................................
for Anchorage,
19
141~144C ... f. f d f
e concentratlon ln alr as a unctlon 0 ate or
-------
(continued)
Figure
20
Maximum population dose by state for the September 17, 1977,
Chinese nuclear weapons test ..................................
21
Population thyroid dose geographical distribution for the
September 17, 1977, Chinese nuclear weapons test ..............
22
Population lung dose geographical distribution for the
September 17, 1977, Chinese nuclear weapons test ..............
vi
Page
46
47
48
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LIST OF TABLES
Table
1
Milk ingestion and air inhalation rates for reference indi-
viduals in each age group .....................................
')
'-
Maximum individual doses as a function of organ, age, and
state
[[[ .
3
Estimated population and milk consumption for each state
......
4
Age distribution, absolute milk consumption and milk consump-
tion distribution for the U.S. population .....................
5
Population doses as a function of state and organ..............
6
Health effects estimates for the U.S. population for the Chinese
nuclear test of September 17, 1977 ............................
7
Minimum detectable levels (MOL) at the 2-
confidence level
for nuclides detected in milk and air .........................
Al
Dose conversion
fa c tors. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
A2
Integrated radionuclide concentrations in milk and
air ........
A3
Individual doses as a function of state, age group, and
o rg an. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
A4
Calculation of total U.S. milk production
.....................
A5
Estimated population and milk consumption for each state ......
-------
(continued)
Tab 1 es
A6
Milk utilization for 1975 and estimated marketing-to-consumption
times for various milk products ...............................
A7
Food groups for population dose
calculations ..................
viii
Page
109
110
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FOREWORD
The Office of Radiation Programs (ORP) of the U.S. Environmental Pro-
tection Agency (EPA) has a primary responsibility to establish radiation
protection guidance and to interpret existing guides for Federal agencies.
This responsibility was transferred to the Administrator of EPA from the Fed-
eral Radiation Council which was abolished by Reorganization Plan No.3 of
1970. One of ORpls mandates in carrying out this reponsibility is to monitor
and assess the impact on public health and the environment of radiation from
all sources in the United States, both ionizing and nonionizing. Therefore,
ORP has initiated a radiological dose assessment program to determine the
status of radiation data nationwide, to analyze these data in terms of indi-
vidual and population doses, and to provide guidance for improving radiation
data. In addition, this program will provide information to guide the di-
rection of ORP by the analysis of radiation trends, identification of radi-
ation problems, and support for establishing radiation protection guidance.
As a part of this program, ORP operates a system for monitoring levels of
radioactivity in the environment. This system is called the Environmental
Radiation Ambient Monitoring System (ERAMS) and is operated by EPA's Eastern
Environmental Radiation Facility in Montgomery, Alabama. This monitoring
program is designed to provide long-term radioactivity assessment of trends
and seasonal changes and short-term early warning to establish the need for
emergency abatement actions or contingency sampling operations. Sampling
media included in this program are air particulates, precipitation, surface
water, drinking water and pasteurized milk.
Following the atmospheric nuclear weapons test by the People's Republic
of China at 3:00 a.m., EDT, on September 17, 1977, the ERAMS network was fully
activated and frequent samples of air particulates, precipitation, and pasteur-
ized milk were collected for several weeks after each event. Individual and
population doses for the United States were calculated using the levels of
radioactivity measured in these samples. Based on the calculated doses,
ix
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health effects to the population of the United States were estimated. This
report is a summary of EPA's assessment regarding the radiation doses and
potential health effects which may be attributed to radioactive fallout from
these nuclear weapons tests.
Gordon Burley, Acting Director
Office of Radiation Programs
-------
PREFACE
The Eastern Environmental Radiation Facility (EERF) participates in the
identification of solutions to problem areas as defined by the Office of
Radiation Programs. The Facility provides analytical capability for
evaluation and assessment of radiation sources through environmental studies
and surveillance and analysis. The EERF provides technical assistance to
s ta te and 1 oca 1 health depa rtments in the i r rad i 01 og i ca 1 hea 1 th prog rams and
provides special analytical support for Environmental Protection Agency
Regional Offices and other federal government agencies as requested.
This report presents EERF's assessment of the public health impact of
fallout from the atmospheric nuclear test
September 17, 1977.
by (jiliN" on
Charles R. Porter
Director
Eastern
Envi ronmenta 1
Radiation
Facility
xi
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ACKNOWLEDGEMtNT
The authors would 1 ike to express their appreciation to Juanita F. Coley,
Eastern Environmental Radiation Facility, for her assistance in data handling
and analyses for this report.
xii
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ABSTRACT
The People's Republic of China conducted an atmospheric nuclear weapons
test over the Lop Nor testing area in Southwest China at 3: 00 a.m., EDT, on
September 17,1977. Based on past experience, EPA expected that radioactive
fallout from this event might be measureable but not excessive in the United
States. For several weeks following this event, EPA monitored for fallout by
fully activating the Environmental Radiation Ambient Monitoring System
(ERAMS). Fallout radionuclides on airborne particulates, in precipitation,
and in cow's milk were detectable at many sampling locations throughout the
United States.
Maximum individual doses for all nuclides detected in air and milk
following the event were calculated for six organs (bone, liver, thyroid,
kidney, lung, and GI-LLI), total body, and skin. The highest individual dose
131
was for the I-mil k-thyroid pathway. This thyroid dose was a factor of 4
higher than the maximum lung and bone doses and about a factor of 20 higher
than the other doses. U.S. population doses of 150,200 man-rem to the lung,
127,700 man-rem to the thyroid, and 107,600 man-rem to the bone were
calculated. The population doses calculated for the other organs and for total
body and ski n were from one-fourth to one-tenth of the above doses. The
calculated total body population dose was 17,200 man-rem.
EPA has used the calculated population doses and dose-to-risk conversion
factors to estimate excess somatic effects and genetic effects in the U.S.
popul ation because of this test. It was estimated that about 17 cancers and
about 10 deaths might occur as somatic effects during the next 45 years as a
result of these population doses. Across all succeeding generations of the
U.S. population it is estimated that about 3 serious genetic effects might
occur due to this test. These numbers of potential somatic health effects and
genetic effects for the U.S. population are small and will be undetectable
when compared to the estimated 16,500,000 deaths that might occur from other
causes of cancer and the estimated 12,900,000 serious genetic effects that
might occur in the U.S. over the next 45-50 years.
xiii
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1.0
I NTRODUCTI ON
1.1
Description of Fallout Incidents
The People's Republ ic of China detonated a nuclear device in the atmo-
sphere over the Lop Nor testing area in Southwest China on September 17, 1977.
The device was rated as a low yield type with an explosive power equivalent to
20-200 thousand tons of TNT.
Since the detonation was above ground, it was expected that radioactive
materials would be injected into the atmosphere. The prevailing air currents
over China move in an easterly direction. Therefore, within 4 to 7 days these
airborne radioactive materials would be expected to arrive over the North
American Continent. The fastest moving of these air currents of initial
interest usually move at al titudes of 20 to 40 thousand feet. Normally, the
materials carried by these air currents pass over the United States and Canada
within 2 to 4 days after arrival at the west coast. The rest of the radio-
active materials usually remain at the higher altitudes until slowly dropping
down to the ea rth I s su rface as fallout over a peri od of several months or
yea rs .
The Envi ronmenta 1 Protect i on Agency IS experi ence, and that of its prede-
cessor organizations, with atmospheric nuclear testing by the People's
Republic of China (20 tests since October 1964) indicated that radioactive
fallout levels are generally quite low in the United States. However, EPA was
prepared to monitor for any fallout that might occur, although no significant
radioactivity levels were expected.
1.2 Concerns for Fallout
Airborne radioactive materials produced by atmospheric nuclear weapons
testing can cause radioactive exposure to people in several ways. The primary
concern occurs when the radioactive materials come down from the atmosphere as
fallout. Then people may be exposed by inhaling radioactive dust particles
that can deposit in the lung or dissolve and move through the bloodstream to
various organs of the body. People may al so be exposed by ingesting foods
1
-------
containing fallout materials. Milk is the main food of concern because radio-
active depositions on grass can be transferred into cow's milk. Fallout of
dry materials or, more significantly, rainout of radioactive materials could
deposit on large areas of land, including pastures for dairy cattle. Cows
consume large quantities of grass, and some of the radioactive materials that
may be on this grass are transferred within a day or two to the cowls milk.
Times involved in milk production, transport, processing and bottling are such
that nonnally several days would be required for any such potential contam-
ination to reach pasteurized milk that is retailed to consumers.
1.3
EPA Responsibilities
EPA is responsible through its Office of Radiation Programs, for eval-
uating public exposure to all sources of radiation, and for issuing guidance
to control these exposures or to set appropriate exposure standards. Inherent
in this responsibility is the need to detennine the impact of radiation doses
from radioactive fallout. To assess the radiation doses from radionuclides in
the general ambient environment, EPA maintains a monitoring program known as
the Environmental Radiation .Ambient Monitoring System (ERAMS). This system
was alerted for special radiation measurements prior to and during the times
of anticipated fallout from the September 17, 1977, nuclear test. ERAMS is
described in detail later in this report.
In addi ti on, EPA is respons ibil e for notifyi ng State agenci es of the
possibility of radioactive fallout. EPA also keeps State agencies informed on
the national and regional radiological picture and advises them on sur-
veillance or protective actions that they may pursue.
EPA collects infonnation from its own monitoring system, from State
monitoring programs, and from other Federal agencies to assess the national
radiological situation. This infonnation is then relayed to the public by
means of press releases during the time of potential fallout. Other Federal
agencies are also informed of the situation as appropriate.
1.4
Purpose and Scope of This Report
This report represents EPAls assessment of radiation doses due to radio-
active fallout from the atmospheric nuclear test of September 17, 1977.
2
-------
This assessment is based upon data from EPA's national monitoring program for
fallout and focuses on the potential for radiation exposures due to radionu-
clides in pasteurized milk and due to air inhalation and air submersion.
Detailed data on EPA's monitoring measurements are included in Tables 6,
7, 8, and 13 in the April 1978 issue of Environmental Radiation Data (EPA78).
These data were used to assess individual and population doses as discussed in
Section 7. The assessment of population health effects is given in Section 8.
Each of these sections briefly outlines the assessment approach and modelling
parameters. The interpretation of dose and health effects is presented in the
discussion in Section 9.
Specifically, this report presents information on the following items:
(a)
(b)
(c)
(d)
(e)
( f)
(g)
( h)
description of fallout incident
movement of contaminated air masses
EPA's general monitoring program
EPA's specific fallout monitoring efforts
EPA's monitoring results
population dose assessment
potential health effects
interpretation of dose and health effects and
conclusions
2.0 EPA MONITORING PROGRAM
2.1
Environmental Radiation Ambient Monitoring System (ERAMS)
Continuing surveillance of radioactivity levels in the United States is
maintained through EPA's Environmental Radiation Ambient Monitoring System
(ERAMS). This system was formed in July 1973 from the con sol idation and
redirection of separate monitoring networks formerly operated by the U.S.
Public Health Service prior to EPA's formation. These previous monitoring
networks had been oriented primarily to measurements of fallout levels. They
were modified by changing collection and analysis frequencies and sampling
locations and by increasing the analyses for some specific radionuclides. The
3
-------
emphasis of the current system is toward identifying trends in the accumu-
lation of long-lived radionuclides in the environment. However, ERAMS, by
design, is flexible and can provide short-tenn assessments of large scale
events such as fallout.
ERAMS normally involves several thousand individual analyses per year on
samples of air particulates, precipitation, milk, and surface and drinking
water. Samples are collected at about 150 locations in the United States and
its territories, mainly by State and local health agencies. These samples are
forwarded to ORpls Eastern Environmental Radiation Facility (EERF) in
Montgomery, Alabama for analyses. ERAMS data are tabluated quarterly and
issued to the groups involved in the program.*
2.2
Airborne Particulates and Precipitation Sampling
The air monitoring program of ERAMS consists of 22 continuously operating
stations and 46 standby stations located throughout the United States, Puerto
Rico, and the Canal Zone (Fig. 1). At the continuously operating stations,
airborne particulates are collected continuously on filters which are changed
twice weekly. Aliquots of precipitation are also collected twice weekly and
are submitted to EERF for analysis with the air particulate samples. When the
possibility of fallout occurs, the 46 additional standby stations are alerted
and daily sampling is started at all stations. The air particulate samples
are important for estimating the potential population dose from inhalation of
fallout materials. Precipitation samples are collected to monitor rainout of
radioactive materials that may contaminate pasture and crop lands.
*ERAMS data are published quarterly in the EPA publication Environmental
Radiation Data. A summary analysis of ERM~S data will be presented in each
year's publication of EPA's Radiological Quality of the Environment in the
United States. This publication is available from the Office of Radiation
Programs, USEPA, 401 M Street, S.W., Washington, D.C. 20460. Previously.
ERAMS data were published monthly in Radiation Data and Reports. This pub-
lication was terminated in December 1974.
4
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NO
. MT ..
SO
.
Wy
NE
UT CO ..
KS
U1 AZ " " OK
. NM
TX
LEGEND
.. ACTIVE SAMPLING STATION
. STANDBY SAMPLING STATION
Fi g. 1.
Environmental Radiation Ambient Monitoring System (ERAMS) airborne
particulates and precipitation sampling locations
-------
High efficiency, charcoal impregnated, cellulose filters are used for air
particulate collection. Field gross beta measurements are made with a G-M
survey meter at 5 hours and 29 hours after collection to allow subtraction of
naturally occurring radon and thoron daughter products. Field estimates are
reported to the Eastern Environmental Radiation Facility (EERF) via telephone
if the activity level is twice the normal reading for the sampling area.
The filters are then sent to the EERF for more sensitive gross beta
measurements in the laboratory. If the laboratory gross beta activity exceeds
1 pCi/m3, a sodium iodide (NaI) gamma analysis is performed to identify and
1~~ 131 106
quantify the following radionuclides: Ce, I, Ru,
137 95 232 65 60 ~o 1~0 21~ . . .
Cs, Zr-Nb, Th, Zn, Co, K, Ba, and 81. Due to the Slml-
larity of gamma energies and resolution of the NaI crystal, l~lCe may be
present wi th the 1 ~ ~ Ce, and 103 Ru, and 7 Be may be reported wi th
106 R
u.
Precipitation samples from the 22 continuously operating stations are
sent directly to the EERF for gamma analysis whereas aliquots of the precipi-
tation from the 46 standby stations are evaporated to dryness and gross beta
field estimates are made prior to shipment to the EERF.
2.3
Pasteurized Milk Sampling
The milk monitoring program of ERAMS is a cooperative program between the
Environmental Protection Agency's Office of Radiation Programs and the Milk
Sanitation Section of the Food and Drug Administration. Pasteurized milk
samples are normally collected the first week of the month by FDA represen-
tatives at 65 sampling sites, one or more of which are located in each State,
Puerto Rico, and the Canal Zone (Fig. 2). These are composite samples based
on the volume of milk sold by the various milk processors in the sampling
station area and represent more than 80 percent of the milk consumed in major
population centers of the United States. Additional samples may be collected
upon request to respond to events such as fallout from nuclear weapons
tes t i ng .
Gamma analyses are performed on the milk samples as soon as they arrive
at the EERF and results for 1311, 1~0 Ba, 137 Cs, and ~o K are available within
hours after receipt. If samples have 1311 and l~oBa activity levels greater
than 10 pCi/liter or abnormally high 137CS values, then 89Sr, 90Sr analyses
6
-------
'-I
.Minot
.ROPid City
08n"., .
Wichita
.
. """"q".'q".
Oklohomo.
Clly
00110..
~.....
o 'GO - UJO'-
o 1OID1'OO1II048,1..
f---'r-'-,-L-,J
, 100 - 600...
P R..V.I.
S~~~
IS 0 U 14 n..... C':'
I"\"r+r-'--'
tl OHID"~-
o 100
I' ',",
o tOO 100
100
)01)...01..
..
o
" ,
J.OO 400 1010....1."
ALASKA
Fig.
2.
ERM'IS
pasteurized milk
conronent
samplino
loci1tions
-------
are perfonned. The radiostrontium data are usually avai1able within - ~s
after sample receipt at EERF.
131 140 137 90 89
The radionucl ides I, Ba, Cs, Sr, and Sr have been shown in
previous fallout episodes to be sensitve indicators of fission product radio-
act1vity from nuclear detonations. Pasteurized milk constlllptioo is illPDrtant
1n detenn1n1ng population dose resulting fran radionuc1ides that rapidly
transfer from the enviroment through food chains to man. The food chain of
interest begins with particulate deposition on grass forage. The grass fOrage
than is consumed by grazing dairy cows, and the metabolized radionucHdes in
cows are rapidly transferred to mil k, which is processed by the dairy and
ready for public consumption within one to four days after deposition.
3.0 MOVEMENT OF CONTAMINATED AIR MASSES
Since the detonation by the People's Republic of China was above ground,
large amounts of radioactive materials were injected into the atmosphere and
carried in an easterly direction toward the United States. These radioactive
materials, which are nonnally invisible to the eye, typically begin dispersing
laterally and vertically depending on particle sizes and shapes, temperature,
and wind velocity. At each particular altitude, there is a forward region
where contaminated air begins mixing with uncontaminated air. This area is
called the IIleading edgell of the contaminated air mass and can sometimes be
detected by instrument-carrying aircraft. The movement of contaminated air
masses at various altitudes can be predicted on the basis of meteorological
da ta .
Fig. 3 shows the initial trajectory of the radioactive debris from the
Chinese nuclear detonation on September 17,1977. This detonation was a
relatively low-yield explosion, consequently, the majority of the radioactive
material did not penetrate the stratosphere but remained in the troposphere
(i .e., below approximately 35,000 ft.). It took approximately 4 days for the
leading edge of the radioactive air mass in the upper troposphere (30,000 ft.
level) to reach the west coast of the United States and about 2 more days to
cross the United States (see Fig. 4).
The leading edge of the contaminated air mass reached the Pacific coast
of Al aska and Canada 1 ate on September 20 and moved southward over the west
8
-------
or- -
- ~----
9
-------
o
Q:,,,,,,
"'~
HAWAII D
100 200
I I
Milel
P.R. & V.I.
CJ~"'o
G=J
ALASKA
s
,
M1Iel
Figure 4. Approximate path across the United States of the leading edge of debris at the 300 millibar level
(approximately 30,000 ft.) from the Chinese nuclear detonation of September 17, 1977.
o , .
'--L.-'
Miles
o 100 200
II II I I I
Scol~ in Miles
300
I
-------
coast of the Uni ted States. It then moved rapidly across to the Great Lakes
by early morning of September 22 and had reached the east coast late that same
day. Some rainout was detected in a precipitation sample collected September
21 at Anchorage, Alaska, but it was September 26 before measureable rainout
was detected in other areas of the U.S.
Trailing debris at a lower altitude crossed the Pacific more slowly and
was detected on September 25-29 at Honolulu, HI; Denver, CO; Las Vegas, NV;
Cheyenne, WY; Salt Lake City, UT; and Sante Fe, NM. This slower moving debris
had reached Florida by October 2nd and 3rd. Normally, a radioactive air mass
will circle the world after the first pass over the United States and may
still be detectable on its second pass. However, detection of the second pass
of the main cloud was difficult to determine in this case due to the slow
passage of the trail ing debris from the first pass. After the second pass, a
contaminated air mass usually becomes very diffuse and radioactivity is de-
cayed to the point where further passes can not be positively detected.
4.0 EPA FALLOUT MONITORING RESPONSES
The Department of Energy (DOE) on Saturday, September 17, 1977, informed
EPA of the nuclear detonation and also made a public announcement of the test.
The DOE has the responsibility in the Federal government of announcing both
domestic and foreign nuclear detonations along with other pertinent infor-
mation about the detonations.
On September 17, 1977, the National Oceanic and Atmospheric Admin-
istration (NOAA) made the first preliminary prediction of the trajectory of
the leading edge of the contaminated air mass. These predictions were revised
daily as more information became available. The NOAA has the Federal respon-
sibility for predicting the airborne trajectory of the contaminated air masses
and the time of potential radioactive fallout across the United States.
Based on the above information, EPA, on September 17, began notifying
the States and the ERAMS air particulate and precipitation sampling stations
to activate the standby portion of the network and to increase the sampl ing
frequency for the regular sampl ing stations. The entire network was in full
operation by Tuesday, September 20.
11
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Based on an anticipated increase in fallout radioactivity in pasteurized
mil k, EPA requested that the Food and Drug Administration (FDA) notify all
sampl ing stations to collect additional mil k samples. Normally, samples are
collected from all stations the first of each month, but, beginning'September
26, weekly samples were collected at each station.
The EPA monitored the concentrations of radioactivity in air particulates
and precipitation until October 14 and continued weekly collections of
pasteurized milk samples into November 1977. At these times, the concen-
trations of radioactivity in air and milk, respectively. were essentially
normal. Overall, approximately 1100 air particulate samples, 100 precipi-
tation samples, and 500 milk samples were collected for a total of over 3,000
individual measurements. Information was issued through 16 news releases from
September 18 to November 10. These news rel eases indi cated that at no time
did EPA evaluate the fallout situation as warranting any protective actions on
a broad basis, and no such actions were suggested.
5.0 AIR PARTICULATE AND PRECIPITATION MEASUREMENTS
Gross beta field estimates are performed on all air particulate samples
in the field at 5 and 29 hours after collection, and laboratory measurements
are made usually within 3 to 5 days following collection, after the decay of
na tura lly occurri ng short-l i ved radon and thoron daughter products. These
measurements are used as screening mechanisms to determine the need for
additional specific isotopic analyses. Gross beta measurements alone are not
sufficient for dose estimates that require data on concentrations of indi-
vidual isotopes. However, the beta measurements are useful for determining
trends and patterns of fallout in the United States.
The geographical distribution of gross beta radioactivity on airborne
particulates was plotted on the basis of laboratory measurements for each day
between September 21 and October 2 and for October 14. Seven of these distri-
bution plots which show the trend in the level of fallout radioactivity in the
environment over this period are included as Figs. 5 - 11. The contours
denoting separation of radioactivity levels were arrived at by mathematical
interpolation. Variations within the two lower levels are normally seen as
12
-------
w
~ ---'" ~--
---- -~-
- ------=- c: -
&
-
--
0.0 to 0.3 pCi/m3
Fi g. 5.
Distribution of gross beta in airborne particulates (pCi/m3),
Laboratory measurements for September 22, 1977.
-------
+:>
1&
,~ -,:;m:~;::,
..::4
Fi g.
6.
Distribution of gross beta in airborne particulates
Laboratory measurements for September 24, 1977.
lID
II
0.0
0.0 to 0.3 pCi/m3
0.3 to
1.0 pCi/m3
1.0 to 3.0 pCi/m3
(pCi 1m3).
-------
(J1
g
-
II
u
-....
0.0
to 0.3 pCi/m3
0.3 to
1.0 pCi/m3
1.0
to 3.0 pCi/m3
3.0 to
10.0 pCi/m3
Fig.
7.
Distribution of gross beta in airborne particulates
Laboratory measurements for September 25. 1977.
(pCi/m3).
-------
0"'\
ft
~
to 0.3 pCi/m3
1. 0 pCi /m3
1.0 to 3.0 pCi/m3
3.0 to 10.0 pCi/m3
10.0 to 30.0 pCi/m3
Fig. 8.
Distribution of gross beta in airborne particulates (pCi/m3).
Laboratory measurements for September 27, 1977.
-------
'-J
ft
~
.-
-- ---
.. .
----
...
..
..
0.0 to 0.3 pCi/m3
0.3 to 1.0 pCi/m3
1.0 to 3.0 pCi/m3
3.0
10.0 pCi/m3
to
10.0
to 30.0 pCi/m3
Fi g.
9.
Distribution of gross beta in airborne particulates
Laboratory measurements for September 29, 1977.
(pCi /m3).
-------
0:>
&
. .
Fig.
10.
Distribution of gross beta in airborne
Laboratory measurements for October 2,
particulates
1977 .
..
0.0 to 0.3 pCi/m3
0.3 to
1.0
3.0 to
(pCi/m3).
1.0
pCi/m3
to
3.0 pCi/m3
10.0 pCi/m3
I
i
-------
.
-.-. -
- -- - --
-- - - -
--- - -
-.- - - ~
--- - - --
~
0.0 to 0.3 pCi/m3
-
0.3
to
1. 0 pCi 1m3
Fig.
11.
Distribution of gross beta in airborne particulates
Laboratory measurements for October 14, 1977.
(pCi 1m3) .
-------
ambient background variations. These concentrations are rarely exceeded with-
out the intrusion of a contaminating source such as the Chinese atmospheric
nucl ear test.
In reviewing Figs. 5 - 11, the chronological path of elevated gross-beta
radioactivity levels can be followed across the U.S. Elevated levels of gross
beta radioactivity in air particulates were first noted on September 25 in
Hawaii and the western U.S. This activity was attributed to lower altitude
trail ing debris. U.S. level s peaked in the September 25 - 29 period but
remained elevated in some areas until October 3rd and 4th when this trailing
debris together with the second cloud passage had cleared the United States.
The highest levels of activity were reported in Las Vegas, NV; Cheyenne, WY;
Denver, CO; and Salt Lake City, UTe
A detailed summary of the airborne particulate data is given in Tables 6
and 7 of Report 12, Environmental Radiation Data (EPA78). Table 6 of this
reference includes gamma results for samples with laboratory gross beta
measurements greater than 1 pCi/m3.
With the exception of a precipitation sample collected September 21,
1977, in Anchorage, AK, no measurable activity was detected in rainfall until
September 26 when the trail ing debris was spread across the United States.
Gamma results of these precipitation samples are given in Table 8 of Report
12, Environmental Radiation Data (EPA78).
6.0
PASTEURIZED MILK MEASUREMENTS
Results for pasteurized milk samples collected September 23, 1977 -
December 31, 1977, are presented in Table 13 of Report 12, Environmental
Radiation Data (EPA78). From this data the geographical distributions of
131 I in mil k for each week between September 25 and November 6, for the rest
of November, and for December 1977 were prepared. Six of these distribution
plots which show the trend in the level of 131 I in mil k over this period are
included as Figs. 12-17. By sequentially studying these geographical distri-
butions, the buildup and subsequent decrease of 1311 levels in milk between
September 25 and the fi rst part of November can be observed. Only six
sampling sites had detectable levels (above 10 pCi/!) of 1311 during the first
week of samp 1 e co 11 ect ion. However, du ri ng the second and th i rd weeks,
respectively, 49 and 47 of the 65 stations had 1311 levels exceeding 10 pCi/!.
20
-------
N
t&
---
-
o to 10 pCi/£
Immm 10 to 20 pCi/£
III 20 to 50 pCi/£
Fig. 12.
Average concentration distribution of iodine-131 in milk (pCi/£)
for September 25 - October 1. 1977.
-------
m~:,,:!!!!!I!!!IJl!'~!! . - )~~~f,\(:-:-
"""'''-1 ~". , "J
N
N
[&
Fi g.
13.
. n of
. distributlo
entratlon
Average conc2 8.1977.
for October
iodine-131
1m
.
.
i n mil k
o
10 to
20 to 50
50 to
I
I
I
j
I
i
!
!
i
,
I
I
I
I
I
to
10
pCi/t
20 pCi/t
pCi/t
100 pCi/t
(pCi/t)
-------
N
W
1m
-
.
o to
10 pCijQ,
10 to 20 pCijQ,
20 to
50 to
50 pCi/Q.
100 pCijQ,
Fig.
14.
Average concentration distribution
for October 9 15, 1977.
of
iodine-131
in milk
(pCijQ,)
-------
N
+:>
- --....---
-..........
- - -. -........
-. - - -. - - - - - -. --
- - -- ... - - - --.--
-.... -. -. - -... - -..
-.--.-----,....-._-..
- ---- -----.------.------
- "'",".-," -'-'.'.-.-.'.'.'-'-'.'.'..'.'~_....--
. "." --,...-..-.- _.--------
...- ---- --.------.----- ."---...
.- ... ...._-_..._...~ ......
...- ... .............__...-..
.. .- ....--.-...-.--------
.. -. -- ._.. ---.- -- --- -.. -.,.
. - - - - - .. .. -. -.... -... - -..... .
-- . -- . .......... .- -- ...--.
.. - .- - . -.-- -....... - - - ----
... . -- --.------- -- - -.-..-
-- --- . - .".---...---- __A'"
----.. - . ..-.,.,.,. .- -- .-...-
.....-- .. ----.-.-.------ -----
......- -- .--------- .-- ____A
.".".-.-.-.-":. ".". . . .-.-.-.-.-.-.-.-,',- -.---=--~- .-.'.'.',','
--",.,- " .,."",..,,-_......
.',','.','.',-_. ...'-. . .'.,'.'.....'.'.'.'.'. .'-'--=- ....,','-',-. .
,':':-:':-:':- :-.::: -j"';-:' : ':-:-:-:':-:-:-:-:-:',-:-:';:-.-"-.':-:';':';':':' .'.:
:::::::::::::::--:,-:::~ -:::::::::: .::::::::::::::::-:::::;:;:::::::::::::::::::: - :. '::'.:
.. ..................................................81L............
-- .
&
o
--
mI
-
10 to 20
to
10 pCi/Q,
20 to
. 50 to
pCi/Q,
50 pCi/Q,
100 pCi/Q,
Fi g. 15.
Average concentration distribution
for October 16 - 22. 1977.
of iodine-131
in mil k
(pCi/Q,)
-------
N
U1
-
- - -
- -
I.
lID
II
Fig. 16.
- -
- -
o to 10 pCi/Q,
10 to 20 pCi/Q,
20 to 50 pCi/Q,
Average concentration distribution of iodine-131 in milk (pCi/Q,)
for October 23 - 29, 1977.
-------
1&
- -- - - -
- - -- - --
- - . - --
--~-- --
- - - - --- -.-
-.,0- -. -""--- ----'-~ =-
- ---- - -
~-----~.-.,.-- -
- - ---- - -
"----- '-=------= -
- - - . - ---
. . -
--~ ----
- - - . - -
- . -- - --
N
0'\
o to 10 pCi/.e
Fig. 17.
Average concentration distribution of iodine-131 in milk (pCi/.e)
for November 6 - 30, 1977.
-------
Elevated levels were detected over the entire United States in contrast to the
distribution following the September 26, 1976, detonation when elevated levels
were concentrated in a few areas (EPA77a).
The highest 1311 value obtained for an ERAMS pasteurized milk sample was
119 pCi/ £ at Anchorage, AK, collected September 30, 1977. This level was far
below levels where EPA would recommend consideration of protective action.
In the samples analyzed for radiostrontium, little if any increase was
detected in 90 Sr levels when compared to July 1977 data (EPA77b). However,
many of the 89Sr values showed significant increases, with a high value of 55
pCi/£ recorded for Little Rock, AR, on October 3. In July 1977 almost all of
the 89Sr levels were below the detection limit of 5 pCi/,Q,. These concen-
trations of 89Sr in milk were not considered to be a health hazard.
7.0 RADIATION DOSE ASSESSMENTS*
7.1 Dose Types and Pathways
Radiation doses** to humans from fallout radionuclides occur as a result
of external and internal radiation. Skin and total body external radiation
*EPA has assessed the short-term impact on public health in the United
States which may be attributed to radioactive fallout from the Chinese atmo-
spheric nucl ear test of September 17, 1977. Over the long term, most of the
fallout will be deposited on the earth, contributing to a slight increase in
background levels. This long-term impact is not assessed in this report. The
analysis is also restricted to those environmental pathways for which direct
measurements of radioactivity are available in the medium which transmits
radioactivity or radiation exposure directly to man (for example, milk that is
drunk by man). Furthermore, only the radionucl ides that are measured in the
ERAMS samples are considered in this anlaysis.
**In this report, the term "dose" is used broadly to mean "absorbed dose"
(rads) or "dose equivalent" (rems) and applies only to radiation protection.
The term "dose" refers to either internal or external pathways. For internal
pathways, dose refers to the dose committed during the integration period; and
for external pathways, dose refers to the dose del ivered during the inte-
gration period. Individual doses are reported in mrem and population doses
are reported in man-rems. For 1311, the dose commitment factors for ingestion
are expressed in mrad per pCi ingested. We assumed that 1 mrad of dose is
equal to 1 mrem of dose equivalent for 1311.
27
-------
doses occur due to submersion of people in the air containing fallout radio-
nucl ides and due to irradiation of the body from radionucl ides deposited on
the ground and on vegetation. The only external doses considered in this
report are submersion doses since measured concentrations of radionuclides on
the ground surfaces were not available in the ERAMS data. Internal doses
result from inhalating of air or ingesting food or water containing fallout
radionucl ides. Vegetation contaminated by direct fallout or uptake of de-
posited radionucl ides from the soil may be consumed either directly by humans
or by animals (such as dairy cows) which provide human food. Thus the fallout
radionuclides find their way into the human body by ingestion of foods, either
directly by the vegetation pathway or indirectly by a vegetable to animal
pathway. Historically, consumption of 131 I in cows milk (1311-milk-thyroid
dose pathway) has been the most significant contributor to doses to humans
from fallout radionuclides.
In thi s document, doses are reported for eight organs*. The pathways
contributing to these doses are--
(a) ingestion of radionuclides in pasteurized milk** - the
radionuclides are deposited on grass which is consumed by
dairy cows. Transfer of the radionuclides to milk takes
place within the cows.
(b) inhalation of air particulates*** - the radionuclides are
inhaled and deposited in the lung where they remain or where
they can be dissolved for transfer by the blood to various
body organs. Some inhaled material is transported up the
respiratory tree and then swallowed. The body treats this
fraction of inhaled material as it does ingested material.
(c) submersion in the radionuclides present in air*** - the
radionuclides directly irradiate the receptor.
*Doses are calculated to the organs bone, liver, thyroid, kidney. lung,
and GI-LLI. Doses are also calculated to skin and total body. In discussing
the calculated doses, we include skin and total body in the "organ" category
and, for simplicity. refer to the doses to eight organs.
**Includes 89Sr, 90 Sr, 1311,137 Cs, 140 Ba,140 La. 140 La is assumed to
be in equilibrium with 140Ba.
***Includes 95 Zr,Nb, 103,106Ru, 131 I, 137CS, 140 Ba, 140 La, 141,144Ce.
28
-------
Doses for the meat and leafy vegetable pathways were not calculated for the
following reasons:
Direct measurements of radionuclide levels in meat and leafty
vegetables were not available. Also, the growing season for
many fresh leafy vegetables has ended by late September, October,
and November.
(b) The calculational accuracy of doses for these pathways would
be substantially less than for the milk pathway, since samples
of meat and leafy vegetables are not collected and analyzed
routinely. To calculate these doses, one would have to use
measured air concentrations to predict meat and leafy vegetable
concentrations. Several uncertainties would be encountered in
calculating doses for these pathways which are not encountered
in the calculations summarized in this report. These uncer-
tainties include predicting--
deposition onto grass and leafy vegetables;
fraction of cattle feed represented by fresh grass;
fraction of vegetable consumption represented by
fresh vegetables; and
transfer coefficients to human food.
Radionuclide levels in drinking water samples were not elevated above
background following this event. For this reason, the drinking water pathway
is not included in these calculations. Although, data are available at some
stations on radioactivity in precipitation samples, this pathway was not
included since precipitation does not represent a direct dose pathway to man.
(a)
Due
possible
example,
7.2 EERF Gamma Scanning Procedures
EERF uses primarily sodium iodide gamma scanning for specific nucl ide
analysis of fallout samples. For these procedures, the following nuclides
occur under common peaks:
103 Ru and 106 Ru and 7 Be
95 Zr and 95 Nb
141 Ce and 144 Ce
to the occurrence of these nucl ides under common peaks, it is not
to quantify the amount of a specific nucl ide in a sample. For
the amount of 95Zr + 95 Nb in a sample can be determined, but the
29
-------
amount of 95 Zr alone or 95Nb alone can not be determined. Thus, for each of
these three nuclide groups, the total quantity of all isotopes contributing to
the peak are reported and the dose commitment factor for the nucl ide with the
highest specific dose commitment factor (highest mrem/pCi) is appl ied for the
nucl ide group. This approach is conservative since the assumption is made
that all of the radioactive material contributing to a peak leads to the
highest dose possible for that peak.
7.3
Dose Estimates for Individuals
Maximum* individual doses for eight organs were calculated for four age
groups for each state.
Equations. The equation used for the individual dose calculations is:
9
2
[~(Cpsn}(IRpa)(DCFpnao)] + 24(C3sn)(DCF3nao)
p= 1
(Eq. 1)
10 =\
sao L
n=l
where:
a = summation index for age group (4 age groups)
n = summation index for nuclide (9 nuclides)
o = index for
p = summation
3 for air
s = summation
o rg an
index for pathway (1 for milk, 2 for air inhalation,
submersion)
index for state (51 states; including all states and
DC)
*Since the pasteurized milk samples are composited from several milk
supplies in a state, it is possible that higher doses could have been calcu-
lated for an individual who drinks milk from a single dairy or who drinks
unprocessed milk from a single farm. Also, it is possible that air concen-
trations of radionuclides could be higher at a location other than the
sampling location(s) within a state.
30
-------
IDsao = individual dose for integration period to organ 0, for age group
a, in state s (mrem)*
C = integrated radionuclide
psn
nucl ide n corrected to
or pCi-d/m3 for air)**
IR = intake rate for pathway p and age group a ( /d for mil k; m3/day
pa
for air)
DCF = dose commitment factor*** for pathway p, nucl ide n, age group a,
pnao
and organ 0 (for milk and air inhalation mrem/pCi intake; for
air sumbersion mrem/hr per pCi/m3)
24 = hours in one day
Age groups. For all of the calculations (individual and population dose
calculations) the receptors were divided into four age groups to account for
the variation of dose with age. The age groups described in NRC Regulatory
Guide 1.109 (NRC77) were used as follows:
Infant 0 - 1 year
Child 1 - 12 years
Teenager 12 - 18 years
Adult 18 years and over
concentration for pathway p, state s, and
sample collection date (pci-d/Q, for mil k
Milk pathway. The milk consumption rates for the individual dose calcu-
lations are shown in Table 1 and are based on information in ICRP #23
(ICRP75). The milk consumption rates for each age group are the maximum listed
in Table 125 of ICRP #23 for that age group. The reported consumption rates
*1,000 mrem equa 1 s 1 rem. The rem is the product of
(rads), an assigned quality factor, and other necessary
specific for the radiation considered.
**The curie (Ci) is a measure of radionuclide transformation rate. One
Ci equal s 3.7 x 1010 transformations per second. There are 1012 picocuries
(pCi) per Ci.
the absorbed dose
mod i fyi ng factors
***Dose commitment is the dose that will be delivered during the 50-year
period following radionuclide intake.
31
-------
varied from 0.13 fjd for a female over 60 to If jd for a male 6 months
old. After examining the data on radionuclide levels in pasteurized milk, it
was obvious that radionuclide concentrations in milk started increasing in
late September and were approaching background again by November 10. Thus an
integration period of September 17 - December 1,1977, (75 days) was chosen
for the milk samples.
Inhalation pathway. The air inhalation rates for the individual dose
calculations are shown in Table 1 and are based on information in ICRP #23. The
TABLE 1
Milk ingestion and air inhalation rates for reference individuals in each
age group (ICRP75)
Age group Milk ingestion Air inhalation
rate, fjd 3
rate, m jd
Infant 1.0 2.3
Ch il d 0.58 10.4
Teen 0.47 19.5
Adult 0.33 22.0
32
-------
air inhalation rates for each age group are based on averaging* data given in
1CRP #23 for that age group. There are large variations in breathing rates
depending on age and amount of physical activity. There can be factors of 5
and 13 variation between breathing rate at rest and during maximal exercise
for an adult and a child, respectively. The numbers used are based on 16
hours per day of 1 ight activity and 8 hours per day of rest except for the
infant. The infant breathing rate is based on 10 hours per day of 1 ight
activity and 14 hours per day of rest.
A review of the radionuclide levels in air showed that the highest parti-
culate concentrations generally occurred in a period between September 17 and
October 14. However, the precise integration periods for airborne radio-
nuclides varied from station to station since the integrations were stopped 5
days after the radionuclide concentration in air had returned to near back-
ground levels.
Dose commitment factors. The dose commitment factors used for the inter-
nal dose calculations express the internal dose that will be delivered for a
unit quantity of radionuclide ingested or inhaled. The dose commitment factors
for inhalation and milk ingestion are from NRC Regulatory Guide 1.109 (NRC77),
except for 1311 in milk. These are from Kereiakes (Ke76) and are based
on more recent 1311 thyroid uptake fractions than the factors in Regulatory
Guide 1.109. The dose factors used for external dose calculations express the
external dose rate per unit concentration of radionucl ide in air. The dose
factors for submers i on are from the FESALAP report (AEC73) since they are not
given in Regulatory Guide 1.109. The dose commitment factors and dose factors
used in these analyses are listed in Appendix A. In general, the ratios of
the maximum to minimum values of dose commitment factors or dose factors as
*For the milk pathway, the maximum intake used in the calculations always
occurs for the youngest age within the age group except for the infant for
whom maximum milk consumption occurs at 6 months. The maximum breathing rate
occurs for the oldest age within each age group. Since the largest contri-
bution to individual doses from all pathways should result from 1311 in milk,
we decided to use the maximum milk consumption and the average air consumption
to represent the critical receptor in each age group. This approach should be
slightly conservative.
33
-------
as reported in the 1 iterature are less than 2. However, the International
Commission on Radiological Protection (ICRP) is developing new methods for
comput i ng dose commitment factors. When th i s new methodology becomes ava i 1-
able, variations in dose commitment factors larger than the stated factor of 2
may occur.
Integrated radionuclide concentrations in milk and air. The integrated
milk and air concentrations* used in equation 1 were obtained by fitting a
cubic-spline (Re67) to the radionuclide levels measured in ERAMS samples and
numerically integrating the resulting curve expressing radionuclide levels vs.
time (see Appendix A for additional information). Representative curves
f 13 1 .. .1 k t A h AK d 141 144 C t t.
,or I concentratlons ln ml a nc orage, , an ' e concen ra lons
;, r'~( ,?t Denver, CO. are shown in Figs. 18 and 19. The integrated concen-
trations of the radionuclides detected in milk and air are tabulated for all
ERAMS locations in Appendix A. After the tabulations for the locations in
each state, a state average tabulation is included which is obtained by an
arithmetic average of the data for the locations in each state. For a more
detailed discussion of the representativeness of these integrated milk and air
concentrations see Section 7.4.
Discussion of calculated doses. The state average integrated concen-
trations are used with equation 1 to compute the individual doses discussed in
this report. In Appendix A, we have tabulated, by state, the results of the
individual dose calculations for each age group. The maximum calculated
individual doses for each organ are listed in Table 2 along with the state and
age group for these maximum doses. From a review of the information in this
table, it can be seen that the highest individual dose (20.5 mrem) is for the
thyroid of an infant in Anchorage, AK. The majority of this dose is con-
tributed from 1311 ingested in milk. The maximum bone dose and lung doses are
each approximately 25 percent of the maximum thyroid dose and the maximum
1 iver dose and kidney dose are each approximately 5 percent of the maximum
thyroid dose. Thus, the thyroid dose is dominant, but doses to the bone and
tne lu~g are within an order of magnitude of the thyroid dose.
*Net concentrations for milk; gross concentrations for air, since radio-
nuclide-specific background air concentrations are not available.
34
-------
a
N
a
a
a
OJ
.
a
~ <.D
..........
U
Q.
C
a l{)
',- a
+-> <::T (V)
<0
!-
+->
c
QJ
U
C
a
u a
N
.--
(V)
.--
~
a
17
Sept
Fig. 18.
Date, 1977
concentration in ~i1k as a function of date for Anchorage, AK.
1
Oct
131
Net I
15
1
Nov
15
1
Dec
-------
co
LO
N
..--.
(V)
E 0',
.......
".--
U
0.
C
0
".-- 1.0
+->
'" 1.0 (V)
~
+->
c
Q)
u
c
0
u
Q) (V)
u
o;j-
.q
..-
~
..-
<:;j-
0
17
Sept
1
Oct
15
1
t-Iov
Date,
1977
Fig. 19.
141,144Ce concentration in air as a function of date for Denver, CO.
-------
TABLE 2
Maximum individual doses as a function of organ, age, and state
Organ Age group State Individual*
dose, mrem
Bone Infant Minnesota 4.7
Liver Infant Minnesota 1.2
w
-....j T. body Infant Minnesota 1.0
Thyroid I n fa nt A 1 as ka 20.5
Kidney Infant Minnesota 1.1
Lung Ch il d Colorado 5.7
Gi-lli Adul t Colorado 0.4
Skin Infant Minnesota 1.0
*Gross doses (no background subtracted) are included for the air inhalation and submersion pathways
background levels for specific isotopes in air are not available. The milk pathway contributions are net
values (background subtracted) since background levels for specific isotopes in milk are available. The
submersion dose contribution is the same for all age groups~
since
-------
7.4 Population Dose Calculations
Population dose is computed by summing the individual doses for all
members of a population. It has units of persons times dose (man-rem).
Equation for population dose. The equation used to calculate state
population doses for each organ is:
2
9 4 .. (lOOO)(Clsn)(MCs)(fla)(DCFlnao) '\"'
\ \ L (fd)exp(-.\td)
PD - L L (O)(P) d=l
so - n=l a=l +(.OOl)(C2sn)(Ps)(f2a) l(IR2a)(OCF2nao) + (24)(OCF3nao~
(Eq. 2)
where:
PD = state population dose to organ during the period
so
September 17 - December 1, 1977 (man-rem)
= conversion factor (lbs. - rem/Mlbs.-mrem)
= conversion factor (rem/mrem)
= summation index for food group (2 food groups)
MCs = total fluid milk and fluid milk products consumed in
state during integration period
(man-Mlbs. consumed or committed for consumption)
= fraction of milk used for food group d (dimensionless)
= for milk, fraction of total milk consumption used by age group
a; for air, fraction of total state population in age group a
(dimensionless)
DCF = dose commi tment factor for pathway p, nucl ide n, age group a,
pnao
and organ 0 (for mil k, mrem/pCi ingested; for air inhalation,
mrem/pCi inhaled; for air submersion, mrem/hr per pCi/m3)
A n = radioactive decay constant for nuclide n (d-1)
td = time between sample collection and consumption (d)
D = days in period of integration for milk pathway
p = milk density (lbs/l)
Ps = population in state s (people)
Cpsn' IRpa' 24, and the indexes a, n, 0,
nition as for the individual dose calculations.
is for population dose from milk ingestion and
lation dose from air inhalation and submersion.
State milk and air concentrations. The pasteurized milk portion of the
1000
.001
d
fd
f
pa
p, and s have the same defi-
The first line of equation 2
the second 1 i ne is for popu-
38
-------
ERAMS network includes 63 sampling locations within the United States. Radio-
nuclide levels in milk were reported for at least one sampling location in
each state following the test. The air portion of ERAMS includes 22 regular
sampl ing stations and 43 standby sampl ing locations (a total of 65 sampl ing
locations) within the United States. For five states, radionuclide concen-
trations in air were not reported following the test. In the other states, at
least one sampl ing station per state reported air concentrations. In general
radionuclide concentrations in milk and air* were available for one or more
samples per week for each milk and air location reporting.
The integrated milk and air concentrations of each nuclide at each
location were obtained using a cubic spline and numerical integration tech-
niques as discussed earlier and in Appendix A. For states with only one
sampling location, the integrated milk and air concentrations for that
location were used for the entire state. For the states where there were no
air sampling locations, air concentrations from a nearby location were used as
an estimate of air concentrations in the state. For states with more than one
sampl ing location, an arithmetic average of the data for the locations in the
state was used. There is a limitation in the accuracy of these calculations
since it was assumed that one, or in a few cases two, three, or four, sampling
locations were representative of an entire state. Obviously. the accuracy
could be improved by substantially expanding the sampling network to include
severa 1 1 oca t ions and wi der geograph i ca 1 coverage in each s ta te. However,
while this may be the largest uncertainty in these calculations, a substantial
expansion of the ERAMS sampling network would significantly increase the cost
of the program. Al so, improved accuracy does not seem warranted because
estimates of fallout related health effects are low in this as well as
previous assessments (EPA77a). The use of a single sampling location to
represent milk consumed in each state is supported by the following:
(1) The milk samples are a weighted composite of milk from each
major milk processor supplying an area. The samples are
representative of locally consumed milk whether the pro-
cessor obtained it from local or remote supplies.
*Net concentrations for milk; gross concentrations for air, since radio-
nuclide-specific background air concentrations are not available.
39
-------
( 2)
supply the smaller cities and towns in a state
metropolitan areas where these milk samples were
Many processors
as well as the
taken.
The use of a single sampling location to represent air concentrations in
each state is supported by consideration of the large plume size after
traveling the great distance from the point of formation in China to the U.S.
Thus, the fallout plume may cover several states when it enters the U.S. and
large variations in radionuclide concentrations within a state would not
normally be expected. As mentioned previously, the integrated concentrations
of the radionuclides detected in milk and air are tabulated for each state in
Appendix A (Table A2).
State milk products consumption. The total U.S. milk production of
24,016 million pounds for the integration period was obtained by using the
U.S. Department of Agriculture (USDA) milk production rate data for September,
October, and November 1977 (DOA77). We assumed that the entire domestic milk
production would be consumed within the U.S. The milk consumption within
individual states was estimated by taking the ratio of total state population
to total U.S. population (BOC73) and multiplying by the estimated milk pro-
duction for the U.S. (see Appendix A). These assumptions were discussed with
USDA personnel, who agreed that they are reasonable (DOA78). The estimated
milk consumption for each state is shown in Table 3.
Milk usage. The fraction of the total milk consumption going into
different dairy products was estimated using USDA milk util ization data for
1975 (DOA76). After discussions with USDA dairy personnel (DOA78) regarding
the time between marketing and consumption of various dairy products, we
decided to establish two food groups (described further in Appendix A) as
fo 11 ows :
Food Group 1: Includes butter, ice cream, cheese, canned and condensed
milk, dry milk, and other manufactured products. Fraction of total U.S. milk
consumption (fd) equals 0.52. Marketing-to-consumption time (td) equals 30 d.
Food Group 2: Includes fluid milk products, cottage
milk. Fraction of total U.S. milk consumption
Marketing-to-consumption time (td) equals 1 d.
40
cheese, and residual
(fd)
eq ua 1 s
0.48.
-------
TABLE 3
Estimated population and milk consumption for each state
State
Population
(no. of people)
Estimated
milk consumption
(million lbs.)
ALASKA
ALABAMA
ARKANSAS
ARIZONA
CALIFORNIA
COLORADO
CONNECTICUT
D.C.
DELAWARE
FLORIDA
GEORGIA
HAWAII
IOWA
IDAHO
ILLINOIS
INDIANA
KANSAS
KENTUCKY
LOUISIANA
MASSACHUSETTS
MARYLAND
MAINE
MICHIGAN
MINNESOTA
MISSOURI
MISSISSIPPI
MONTANA
NORTH CAROLINA
NORTH DAKOTA
NEBRASKA
NEW HAMPSHIRE
NEW JERSEY
NEW MEXICO
NEVADA
NEW YORK
OHIO
OKLAHOMA
OREGON
PENNSYLVANIA
RHODE ISLAND
SOUTH CAROLINA
SOUTH DAKOTA
TENNESSEE
TEXAS
UTAH
VIRGINIA
VERMONT
WASHINGTON
WISCONSIN
WEST VIRGINIA
WYOMING
US TOTAL
3.820E+OS
3.66SE+06
2.109E+06
2.270E+06
2.lS2E+07
2.S83E+06
3.117E+06
7.020E+OS
S.820E+OS
8.421E+06
4.970E+06
8.870E+OS
2.870E+06
8.310E+OS
1.123E+07
S.302E+06
2.310E+06
3.428E+06
3.841E+06
S.809E+06
4.144E+06
1.070E+06
9.104E+06
3.96SE+06
4. 778E+06
2.3S4E+06
7.S30E+OS
S.469E+06
6.430E+OS
1.SS3E+06
8.220E+OS
7.336E+06
1.168E+06
6.100E+OS
1.808E+07
1.069E+07
2.766E+06
2.329E+06
1.186E+07
9.270E+OS
2.848E+06
6.860E+OS
4.214E+06
1. 249E+07
1. 228E+06
S.032E+06
4.760E+OS
3.612E+06
4.609E+06
1. 821E+06
3.900E+OS
4.274E+Ol
4.100E+02
2.360E+02
2.S40E+02
2.408E+03
2.890E+02
3.487E+02
7.8S4E+Ol
6.S11E+Ol
9.421E+02
S.S60E+02
9.924E+Ol
3.211E+02
9.297E+Ol
1.2S6E+03
S.932E+02
2.S84E+02
3. 83SE+02
4.297E+02
6.499E+02
4.636E+02
1.197E+02
1.019E+03
4.436E+02
S.346E+02
2.634E+02
8.424E+Ol
6.119E+02
7.194E+Ol
1.737E+02
9.196E+Ol
8.207E+02
1. 307E+02
6.82SE+Ol
2.023E+03
1.196E+03
3.09SE+02
2.606E+02
1.327E+03
1.037E+02
3.186E+02
7.67SE+Ol
4. 71SE+02
1. 397E+03
1.374E+02
S.630E+02
S.32SE+Ol
4.041E+02
S.lS6E+02
2.037E+02
4.363E+Ol
2.147E+08
2.402E+04
41
-------
Age dependent milk consumption and population distribution fractions. The
NRC Regulatory Guide 1.109 age groups discussed previously were used for the
population dose calculations. U.S. age-dependent population data for 1968 and
1969 (BOC70) were used to estimate the fraction of the population in each age
group (f2a' Table 4). Using Equation 3, age-dependent per capita milk consump-
tion data (R Table 4) from ICRP #23 (ICRP75) were combined with the age-
a'
dependent population fractions (f2a' Table 4) to obtain the fractional milk
consumption, f1a' for each age group in the U.S. population:
(f 2a) (Ra)
(Eq. 3)
f =
la
4
L(f2a) (Ra)
a = 1
where:
f2a
= age distribution fraction for age
group a (dimensionless)
= reference man average milk consumption
rate for age group a (Q, /d).
R
a
Other data. The food group fractions (fd) were applied to all states and
all age groups, and the age group fractions (f ) were applied to all states
pa
and to both food groups. In real ity, fd is probably a function of state and
age group and f is probably a function of state and food group. Information
pa
was not readily available to define fd and f as functions of these quan-
pa
tities and, considering other uncertainties in the calculation, we believe
that this interaction is not significant.
The population for each state is estimated as of July 1, 1976, and was
taken from the 1978 edition of the Information Please Almanac (IPAn). The
populations used for each state are listed in Table 3. A milk density of 2.3
lbs/t (CRC69) was used. The radiological half-lives and dose commitment fac-
42
-------
TABLE 4
Age distribution, absolute milk consumption, and milk consumption distribution for the U.S. population
Reference man milk Milk consumption
Age group Age distribution consumption (ICRP75) distribution fractions
.j::>. fract ions ( -f/d)
w f2a R fl a
a
Infant (0-1 y) 0.02 0.72 0.04
Child (1-12 y) 0.21 0.46 0.33
Teenage (12-18 y) 0.12 0.38 0.15
Adult (over 18 y) 0.65 0.22 0.48
-------
tors discussed previously and tabulated in Appendix A were applied. The intake
rates for air discussed previously and given in Table 1 were used for the
population dose calculations.
Calculated dose. Using the methods, equation, and data discussed, the
population doses shown in Table 5 were calculated for each state. The lung,
thyroid, and bone doses were the highest of the organ doses ca 1 cul ated. In
general, the highest population doses west of the Mississippi River and in the
Southeast were for the lung. In the eastern section of the Midwest, in the
northern portion of the Southeast, and in the Northeast, the highest popu-
lation doses were generally for the thyroid. In eight states, the population
dose was highest for the bone. The maximum population doses in each state
along with a code letter to indicate the organ are shown in Fig. 20. The
population dose geographical distributions for the thyroid and the lung are
shown in Figs. 21 and 22, respectively.
The highest lung population dose is 18,400 man-rem in California, while
the highest thyroid population dose is 14,000 man-rem in Illinois. The
highest bone population dose is 16,300 man-rem in Illinois. For the total
U.S. population, the highest doses are 150,200 man-rem to the lung, 127,700
man-rem to the thyroid, and 107,600 man-rem to the bone. Doses to the other
organs considered in these calculations were from one-fourth to one-tenth of
these highest doses.
8.0 HEALTH EFFECTS ASSESSMENT
8.1 Relationship Between Radiation Doses and Health Effects
In considering the effects of releasing pollutants to the environment,
the information of primary importance is the effect that the pollutants may
have on human heal tho In the field of radiation protection, the trend has
been for regulatory agencies to set permissible limits on radiation dose
rather than di rectly 1 imiting health impacts. In setting these dose 1 imits,
44
-------
TABLE 5
Population doses (man-rem) as a function of state and organ.
Organ
State Bone Liver T. Body Thyroid Kidney Lung Gi-Lli Skin
ALASKA 4.89E+02 1.25E+02 1.08E+02 6.81E+02 1.16E+02 1. 83E+02 2.43E+Ol 1. 08E+02
ALABAMA 1. 24E+03 2.20E+02 5.59E+01 1. 63E+03 1. 68E+02 2.98E+03 3.45E+02 5.87E+01
ARKANSAS 1.29E+03 1. 95E+02 6.23E+Ol 1. 48E+03 1. 29E+02 1. 50E+03 2.35E+02 6. 38E+01
ARIZONA 8.40E+02 3.00E+02 4.94E+01 9.03E+02 2.09E+02 4.06E+03 3.46E+02 5.33E+01
CALIFORNIA 6.12E+03 2.23E+03 8.54E+02 3.31E+03 1.54E+03 1. 84E+04 1. 78E+03 8. 71E+02
COLORADO 3.49E+03 1. 26E+03 4.31E+02 2.60E+03 8. 92E+02 1.11E+04 8.67E+02 4.41E+02
CONNECTICUT 5.20E+02 7.86E+01 3.llE+01 8.25E+02 4.79E+01 5.15E+02 1.23E+02 3.16E+01
D.C. 3.07E+02 9.41E+01 6.65E+01 4.09E+02 7.92E+01 3.22E+02 3.40E+01 6.67E+01
DELAWARE 9.69E+01 4.98E+01 1. 47E+01 2.69E+02 2.18E+01 1.66E+02 3.02E+01 1. 48E+Ol
FLORIDA 6.22E+03 1. 91E+03 9.78E+02 4.41E+03 1.55E+03 1. 37E+04 1.15E+03 9.91E+02
GEORGIA 2.80E+03 8.73E+02 2.63E+02 2.03E+03 6.57E+02 1.07E+04 9.20E+02 2.73E+02
HAWAII 8.21E+Ol 1.80E+01 6.84E+OO 2.56E+02 1.87E+01 7.46E+02 6.41E+01 7.50E+OO
IOWA 1. 15E+03 1.93r+02 6.81E+01 3.25E+03 1. 26E+02 1.12E+03 1. 70E+02 6.91E+01
IDAHO 3.12E+02 1.26E+02 2.49E+01 5.83E+02 7.84E+01 1.25E+03 1.09E+02 2.61E+01
ILLINOIS 1. 63E+04 3.87E+03 3.47E+03 1.40E+04 3.62E+03 5.88E+03 9. 13E+02 3.47E+03
INDIANA 3.92E+03 9.28E+02 6.55E+02 5.02E+03 8.24E+02 4.35E+03 4.81E+02 6.59E+02
KANSAS 6.58E+02 1.91E+02 4.96E+01 1.00E+03 1.08E+02 1.23E+03 1.45E+02 5.08E+01
KENTUCKY 2.25E+03 5.66E+02 3.89E+02 2.87E+03 4.48E+02 1. 48E+03 2.33E+02 3.90E+02
LOUISIANA 3.87E+02 1. 44E+02 2.58E+01 1. 29E+03 1.09E+02 2.32E+03 1. 97E+02 2. 80E+01
MASSACHUSETTS 1.21E+03 3.35E+02 9.47E+01 2.98E+03 1.91E+02 1.98E+03 2.43E+02 9.66E+Ol
MARYLAND 7.10E+02 2.20E+02 5.48E+01 1.80E+03 1.30E+02 1. 56E+03 1.46E+02 5.63E+01
MAINE 1. 67E+02 2.70E+01 8.16E+OO 4.07E+02 1. 98E+01 2.25E+02 6.99E+01 8.39E+00
MICHIGAN 1.llE+04 2.55E+03 2.07E+03 9.56E+03 2.34E+03 8.07E+03 9.37E+02 2.08E+03
MINNESOTA 6. 64E+03 1.70E+03 1.52E+03 6.55E+03 1.59E+03 2.35E+03 2.96E+02 1. 53E+03
MISSOURI 2. 53E+03 5.59E+02 4.31E+02 2.68E+03 5.19E+02 2.78E+03 3.29E+02 4.33E+02
MISSISSIPPI 1.10E+03 1.00E+02 4.16E+01 1.52E+03 8.44E+01 1.07E+03 2.03E+02 4.26E+01
MONTANA 1. 59E+02 5.75E+01 1. 46E+01 5.68E+02 3.44E+01 4. 55E+02 4.93E+01 1.51E+01
NORTH CAROLINA 2.63E+02 9. 11 E+O 1 2.32E+01 1. 97E+03 6.93E+01 1.20E+03 1. 37E+02 2.43E+01
NORTH DAKOTA 2.68E+02 8.93E+01 5. 57,E+01 1.99E+02 6.94E+01 3. 77E+02 3.63E+01 5.60E+01
NEBRASKA 3.27E+02 9.08E+01 2.12E+01 3.95E+02 5.69E+01 8.55E+02 1. 04E+02 2.20E+01
NEW HAMPSHIRE 7.98E+02 2.19E+02 1.91E+02 5.48E+02 2.01E+02 3.55E+02 3. 92E+01 1. 91E+02
NEW JERSEY 1.22E+03 3.16E+02 9.69E+01 4.00E+03 1. 87E+02 1. 97E+03 2.73E+02 9.87E+Ol
NEW MEXICO 8.97E+02 3.09E+02 9.00E+01 3.61E+02 2.41E+02 4.66E+03 3.55E+02 9.43E+01
NEVADA 3.80E+02 1. 43E+02 2.30E+01 2.88E+02 9. 92E+01 2.02E+03 1.53E+02 2.49E+01
NEW YORK 9.35E+03 2.32E+03 1.60E+03 1.36E+04 1. 86E+03 6.75E+03 9.54E+02 1. 60E+03
OHIO 4.96E+03 1.32E+03 7.42E+02 7.83E+03 1.02E+03 6.62E+03 7.09E+02 7.48E+02
OKLAHOMA 2.29E+03 6.45E+02 5.41E+02 8.06E+02 5.83E+02 1.61E+03 1.30E+02 5.42E+02
OREGON 1. 25E+03 2.78E+02 2.44E+02 1.02E+03 2.68E+02 8.80E+02 1. 36E+02 2.45E+02
PENNSYLVANIA 2.05E+03 7.25E+02 2.17E+02 6.58E+03 3.69E+02 3.49E+03 3.84E+02 2.20E+02
RHODE ISLAND 2.74E+02 4.05E+01 1.41E+01 4.57E+02 2.69E+01 2.84E+02 5.30E+01 1. 44E+01
SOUTH CAROLINA 8.46E+02 2.90E+02 4.94E+01 1.39E+03 2.00E+02 3.50E+03 3. 11E+02 5.28E+Ol
SOUTH DAKOTA 2.19E+02 5.53E+01 1.18H01 3.73E+02 3.66E+01 4.81E+02 6.03E+Ol 1. 23E+01
TENNESSEE 3.21E+03 7.68E+02 4.96E+02 2.97E+03 6.14E+02 2.63E+03 3.45E+02 4.99E+02
TEXAS 7.64E+02 2.36E+02 8.93E+01 2.60E+03 1.86E+02 2.46E+03 2.89E+02 9.16E+01
UTAH 5.05E+02 1.82E+02 3.76E+01 1. 34E+03 1.21E+02 2.08E+03 1. 93E+02 3.96E+01
VIRGINIA 1.20E+03 3.41E+02 2. 34E+02 1.00E+03 3.03E+02 1.85E+03 1. 75E+02 2.36E+02
VERMONT 9.13E+01 2.16E+01 6.29E+00 6.84E+01 1.15E+01 1.01E+02 2.40E+01 6.39E+00
WASHINGTON 8.52E+02 2.79E+02 1. 85E+02 8.81E+02 2.20E+02 8.93E+02 9.98E+01 1. 85E+02
WISCONSIN 2.94E+03 5.47E+02 3.84E+02 4.95E+03 4.80E+02 2.28E+03 3.42E+02 3.85E+02
WEST VIRGINIA 4.27E+02 1. 42E+02 3.22E+01 1.12E+03 8.96E+01 1.30E+03 1. 13E+02 3.34E+01
WYOMING 1.98E+02 7.10E+01 1.14E+01 1.28E+02 4. 92E+01 9.87E+02 7.50E+01 1. 24E+01
TOTAL U. S. 1.08E+05 2.84E+04 1 . 72E+04 1.28E+05 2.30E+04 1. 50E+05 1. 59E+04 1.74E+04
-------
(T)=THYROIO
(L)=LUNG
(B)=BONE
+::>
0"\
NO
377(L)
SO
481 (L)
NE
855(L)
CO
11072(L)
KS
1231 (L)
NM
4664(L)
OK
2294(8)
c>cJ
(j
'i?;6
HAWAII D
TX
2600(T)
CJ~"""
FL
1\J
o 100 200 300 Miles
I' 'I' I. " , I
o 100 200 300 400 Kilometers
o 100 200 Mllel
! I~ 12~ 3~ km 746(L
o 100 200 300 400 Miles
I I, I II ,I
o 200 400 600 ~m
ALASKA
25 0 2.5 50 75 Miles c::;:::::1
1111111/ I' I
2502550 75 km
Figure 20. Maximum population doses (man-rem) by State for the September 17, 1977 Chinese nuclear
weapons test.
-------
~ 10-100
L:...:...:..:.J
~ 1,000-10,000
t«//110,000-20,000
~ 100-1,000
..p.
-....J
()()
w=
"S::>
HAWAII D ~
o 100 200
I I I
M,le'
P R. & V.I.
CJ~">O
CO='
ALASKA
Figure 21. Population thyroid dose (man-rem) geographical distribution for the September 17, 1977 Chinese
nuclear weapons test.
G~:f)
u~
6' M, Ie.
o 100 200
II II I I I
Scol~ In MLles
300
I
-------
.p.
co
100-1,000
I:::::::::::::::::{ 1 000-10,000
........ .
10,000-20,000
ij,
o
L::7~ ">0
G:1
o 100 200
1111 II I
Scale in Miles
300
1
ALASKA
e:::><::.~oCJ~
Figure 22: Population lung dose (man-rem) geographical distribution for the September 17,
nuclear weapons test.
1977 Chinese
-------
the health impact of radiation doses at the levels specified in the limits are
considered. However, the probabilities for occurrence of various maladies due
to radiation releases are not directly discernible without going a step beyond
the dose calculations.
More recently, the radiation protection community has begun to take this
additional step--to relate radiation doses directly to the potential health
impact. In thi s report, EPA has chosen to present both dose estimates and
estimates of the impact on publ ic health as a result of this atmospheric
nuclear weapons test. To estimate the health impacts, dose-to-risk conversion
factors were selected. These factors and the estimated publ ic heal th impact
are presented in Section 8.2. A more detailed discussion of EPA policy on the
relationship between radiation dose and health effects is given in Appendix B.
8.2 Projected Health Effects
Health effects have been estimated for the thyroid, lung, and the re-
mainder of the total body (exclusive of lung and thyroid). The EPA estimates
of increases in occurrence of cancers and deaths due to this fallout event are
1 i sted in Table 6 along with the dose-to-ri sk convers i on factors used to
calculate the risks (EPA73, EPAnc). It is estimated that about 17 cancers
and about 10 deaths might occur over the next 45 years as a result of this
test. A comparison of these projected deaths with the deaths due to natural
occurrence of cancers from all causes lends perspective to these calculations.
In 1975, 365,700 persons in the U.S. died from all types of cancers (MVSR77).
Assuming a constant death rate, one projects the natural occurrence of
16,456,200 deaths from all types of cancer over a 45-year period. Thus the
excess death rate is about one extra death for every 1,600,000 deaths
occurring from all types of cancer. We estimate that there might be 3 serious
genetic effects to all succeeding generations of the U.S. population as a
result of this nuclear test. Considering the current incidence rate of
serious genetic effects of 6% (NAS72). we estimate that there might be about
12,900,000 serious genetic effects from all causes in the U.s. during the next
50 years.
49
-------
TABLE 6
Health effects estimates for the U.S. population for the Chinese nuclear test of September 17, 1977
Organ Somatic health effects per Population dose Estimated somatic health effects
million man-rem estimate (man-rem) during the next 45 years due to
(EPA73, EPAnc) this test*
Cancer Death Cancer Death
Thyroid (1-131) 11t 1.1 5 1.2 .12
1.11 x 10
Thyroid (other
than 1-131) 106 10.6 4 1.8 .18
1.70 x 10
Lung 50 50 5 7.59 7.59
1. 50 x 10
(J1 Total body tt 350 139 1. 72 x 104 6.09 2.49
0
Total estimated somatic
health effects for th i s 16.5 10.2
event
*In addition to the somatic health effects listed in this table, if the
dose is equal to the total body dose, it is estimated that 3 serious genetic
population across all succeeding generations as a result of this test.
tThis thyroid cancer estimate is approximately six times lower than the number used in EPAls previous
analysis of health effects from nuclear weapons tests (EPA77a). The change is the result of two factors:
an increase in the plateau length, as a function of time, for expressing excess thyroid cancers for the
0-2 years old age group; and a factor of ten decrease in the cancer risk per person rad for 1-131 since
beta particles from 1-131 were considered less carcinogenic than photon radiation (EPA77c).
ttExclusive of lung and thyroid health effects.
9The time required for complete expression of these effects is the lifetime of the exposed population.
However, the majority of these effects should be within the next 45 years.
assumption is made that the gonadal
effects might occur to the U.S.
-------
9.0 DISCUSSION
9.1
Philosophy Regarding Calculation of Environmental Doses and Effects
A traditional practice among health physicists has been to estimate high
when calculating doses and health effects in order to develop conservative
criteria for protecting the public health and safety. However, in recent
years, there has been a tendency within the profession to be conservative only
when calculating radiation protection, design, and criteria-setting values.
The goal now when calculating doses and health effects from an actual event is
to produce real istic estimates. Accordingly, the parameters in this report
were selected so as to yield realistic dose estimates.
Another practice, common among engineers, that has been followed in this
study has been to avoid spending time refining the value of one parameter to a
few percent uncertainty when there is another parameter in the calculations
that cannot be so refined. For example, the most uncertain numbers in our
dose calculations probably are the integrated milk and air concentrations,
because they are based on only one (in a few cases two to four) sampl ing
location per state. We have not refined the values of other parameters in the
study because we believe they are more certain than the integrated milk and
air concentrations.
9.2
Review of Calculational Uncertainties for Dose Calculations
For many of the parameters used in these dose calculations, a range of
values were reported in the literature. Realistic values for parameters from
within the range of reported numbers have been chosen instead of values that
would lead to the highest dose estimate.
Discussions of uncertainties in values chosen for these parameters appear
in Section 7. These parametric uncertainties are summarized in the following
discussion.
51
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Laboratory data. In this study, we used available data for the dose
calculations. Even when milk and air concentrations fell below the minimum
detectable levels (MOLls) (see Table 7), we used those concentrations as best
estimates of actual concentrations. Although other methods are available for
treating concentrations that fall below the MOLls, we believe that using
available data produces the most realistic estimates of dose.
To calculate net radionuclide concentrations in milk, we estimated
background concentrations from using ERAMS data for July, August, and
September (prior to September 17) 1977. These months were chosen because they
immediately preceded the weapons test, and, during this period, no nuclear
events had taken place in the world that would have tended to increase
background levels of radionuclides in milk in the United States. However, a
longer time period for establishing background would be preferable, and EPA
intends to pursue a more precise method for determining background. Gross
radionucl ide concentrations for air were used for the calculations since
background radionuclide levels for air were not available.
Sampling locations. It is assumed that one (and in a few cases two,
three, or four) milk* and air sampling locations are representative of an
entire state. The milk samples are composites of consumed milk from several
processors, which makes them more representative of the states than if the
samples were from only one processor. The air concentrations would not be
expected to vary markedly withi!1 a state due to the large size of the plume
after travel ing to the U.S. from China. However, it is bel ieved that the
small number of milk and air samples in each state may be the most limiting
factor regarding the accuracy of these dose calculations. Without samples
from additional locations in each state, it is not possible to quantify the
magnitude of this uncertainty.
*Milk samples were composited for major metropolitan areas.
52
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TABLE 7
Minimum detectable levels (MOL) at the 2-0 confidence level for nuclides
detected in milk and air
Nuclide MOL in milk MOL in air*
(pCi/tJ (pCi/m3)
89Sr 5
90Sr 1
9sZr-9sNb .010
1.0 3 1 0 6 Ru .030
,
131
I 10 .007
137 .007
Cs 10
140 .007
Ba 10
140 .007
La
141 144 .030
' Ce
*1400 m3 sample.
53
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Milk ingestion and air inhalation data. For the individual dose calcu-
lations, the maximum milk ingestion rate listed in ICRP #23 w~s used for each
age group. These maximum ingestion rates were about 1.5 times higher than the
average milk ingestion rates. For the population dose calculations for milk,
actual USDA milk production data for September, October, and November 1977
were used to estimate total consumption during the integration period. Use of
the mil k for fluid consumption and for manufactured products was estimated
using USDA data for calendar year 1975. The milk consumption values should be
relatively free of uncertainty. A slight conservatism was introduced into the
calculation by establishing only two milk usage groups with consumption times
of 1 day for group 1 and 30 days for group 2. Actual consumption times
(DOA78) for some specific products in group 2 were as long as six months.
However, we estimate that this conservatism increases the milk population dose
to be high by less than a factor of 1.5.
To calculate the individual and population doses, from air, we used the
average inhalation rate for each age group. There are large variations in
breathing rates depending on age and amount of physical activity. There can
be factors of 5 and 13 variation between breathing rate at rest and during
maximal exercise for an adult and a child respectively. However, the
breathing rates used are based on about 16 hours per day of light activity and
about 8 hours per day of rest and are believed to be realistic for the bulk of
the U.S. population.
Dose commi tment factors. The dose commitment factors that we used are
age dependent and taken from Regulatory Guide 1.109 (NRC77), Kereiakes et ale
(Ke76), and the FESALAP report (AEC73). We believe these dose commitment
factors to be realistic and within a factor of 2 variation from other dose
commitment factors reported in the literature. However, the International
Commission on Radiological Protection is developing new recommendations for
comput i ng dose commi tment factors. When thi s new methodology becomes ava i 1-
able, variations in dose commitment factors larger than the stated factor of 2
may occur.
In general, uncertainty in dose calculations is minimized when realistic
parameters are used. However, available value of parameters are likely to be
54
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much more realistic for groups than for individuals. For example, one
five-year old may drink substantially more milk than another. If data were
available on only a few fiv~-year olds, the likelihood of uncertainty in dose
calculations would be considerably increased. But, if data were available on
the milk consumption of a large group of five-year olds, a realistic mean milk
consumption of five-year olds could be derived and applied to the dose
calculations. Thus, uncertainty usually decreases for population dose
calculations and increases for individual dose calculations.
9.3 Significance of Estimated Doses and Health Effects
A prudent position for radiation protection is that any amount of
radiation exposure is potentially harmful and that any unnecessary exposure to
ionizing radiation should be discouraged. With this in mind, it would
certainly be preferable to abolish atmospheric nuclear testing in all
countries and thereby avoid this source of unnecessary population dose to the
world's population. However, we believe that the population doses and health
effects to the U.S. population from this nuclear test will be small compared
to other sources of doses and health effects. The health effects to the U.S.
population from this test will be undetectable because of the larger influence
of other sources of the same health effects.
55
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10.0 SUMMARY AND CONCLUSIONS
10.1
Summary
EPA has assessed the short-term* impact on publ ic heal th in the United
States that may be attributed to radioactive fallout from the Chinese
atmospheric nuclear test of September 17, 1977. The initial pass of the cloud
was calculated to reach the western coast of the U.S. on September 21. EPA
activated the standby air particulate and precipitation stations of ERAMS on
September 17 and 18. The frequency of sample collection for the nationwide
pasteurized milk network was increased to a weekly interval and the first milk
samples were collected during the week of September 26, which was early in the
buildup cycle of levels in milk.
Detectable levels of fresh fission products were documented in air,
prec i pita t ion, and mil k samples from the ERAMS program fo 11 owi ng th i s tes t.
Although radioactivity levels in air particulates were quite low, fresh
fission products were detected geographically throughout most of the U.S. and
were significantly higher than those following the test of September 26, 1976
(EPA77a). Elevated levels of 131 I, 140 Sa, and 89 Sr in milk were also detected
throughout most of the U.S., but did not approach levels where EPA would
recommend considerating protective action. EPA continued the special sampling
until it was obvious that there was not going to be a significant buildup of
radionuclides in the environmental samples as a result of this event. Press
releases were issued frequently during the sampling period after this event to
keep the public informed.
The highest doses calculated and presented in the report are for lung,
thyroid, and bone. The maximum calculated individual doses were 20.5 mrem to
the thyroid (infant, Alaska), 5.7 mrem to the lung (child, Colorado), and 4.7
mrem to the bone (infant, Minnesota). The highest State lung population dose
is 18,400 man-rem in Cal ifornia, while the highest State thyroid population
*Over the longterm, most of
contributing to a slight increase
is not assessed in this report.
the fallout will be deposited on the earth,
in background levels. This long-term impact
56
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dose is 14,000 man-rem in Illinois. The highest state bone population dose is
16,300 man-rem in Illinois. For the total U.S. population, the highest doses
are 150,200 man-rem to the lung, 127,700 man-rem to the thyroid, and 107,600
man-rem to the bone. Doses to the other organs are one-fourth to one-tenth
the magnitude of these highest doses. The total body population dose for the
U.S. is 17,200 man-rems. We estimate that about 17 cancers and 10 deaths might
occur as somatic effects during the next 45 years as a resul t of these
population doses. Across all succeeding generations of the U.S. population,
we estimate that about 3 serious genetic effects might occur due to this test.
These numbers of potential health and genetic effects for the U.S. population
are small and will be undetectable when compared to the estimated 16,500,000
deaths that might occur from other causes of cancer and the estimated
12,900,000 serious genetic effects that might occur in the U.S. over the next
45-50 years. Our assessment of potential health and genetic effects resulting
from short-term fallout from this event indicates that it will not
significantly affect the United States population.
10.2 Conclusions
The major conclusion that can be drawn from evaluation of potential
radiological health effects of the fallout from the September 1977 nuclear
weapons test by the People's Republic of China is that this test will not
contribute significant somatic and genetic effects in the United States. Any
somatic and genetic effects due to this test will be masked by the occurrence
of these effects from other causes.
57
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APPENDIX A
Additional Information on Individual
and Population Dose Calculations
-------
This appendix provides details related to the dose calculations presented
in th is report.
AI.
Dose conversion factors
The age-dependent dose commitment factors for inhalation and milk
ingestion are from Regulatory Guide 1.109 (NRC77), except for 1311 in mil k.
These are from Kereiakes et ale (Ke76) and are based on more recent 1311
thyroid uptake fractions than the factors in Regulatory Guide 1.109. In cases
where the dose commitment factor was not given for an organ for a particular
nuclide, the total body dose commitment factor was used for that organ.
The dose factors for submersion are from the FESALAP report (AEC73) since
they are not given in Regulatory Guide 1.109. In the FESALAP report, dose
factors are listed only for total body and skin. The total body dose factors
were used for the six organs that were not addressed in the FESALAP report.
All of the dose conversion factors used in this report are tabulated in Table
AI.
A.2
Integrated radionuclide concentrations in milk and air
The procedure used to integrate the raw data consisted of smoothing the
data by the use of a cubic spline function and then analytically integrating
the spline function. Using the spline in this manner provided not only a good
method of integration but also a set of smooth curves for plotting purposes.
The smoothing routine used was a modification of one designed by Reinsch
(Re67). Reinsch found the spline that minimized the integral of the square of
the second derivative over the interval of interest. The spl ine was subject
to the cons tra i nt that the sum of the squares of the ratio of the expected
values less the actual values to the errors were less than some user specified
"slack parameter. II For example, a slack parameter of 0.0 would require exact
interpolation.
This method was modified to accommodate the fact that Reinsch's method
breaks down when the distance between successive abs'Cissa values is widely
59
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TABLE Al
Dose conversion factors
Units are mrem/pCi for air inhalation and milk ingestion.
Units are mrem/h per pCi/m**3 for air 8ubmersion~
Pathway: Milk
Organ
Age Nuclide Halflife, d BODe Li ver T. Body Thyroid Kidney Lung Gi -L11 Skin
INFANT 1-131 8.0SE+00 3.S9E-OS 4.23E-OS 1.86E-OS 9.9SE-03 4.94E-OS 1. 86E-OS 1. SlE-06 1. 86E-OS
BA-140 1. 28E+Ol 1. 7lE-04 1. 71E-07 8.8lE-06 8.81E-06 4.06E-08 1. OSE-07 4. 20E-OS 8.8lE-06
CS-13 7 1.10E+04 S. 22E-04 6.11E-04 4.33E-OS 4.33E-OS 1.64E-04 6.64E-OS 1. 9lE-06 4.33E-OS
K-40 4.60E+ll O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
SR-90 1 .03E+04 1. 8SE-02 4. 7lE-03 4. 7lE-03 4. 7lE-03 4.71E-03 4. 7lE-03 2.3lE-04 4. 7lE-03
SR-89 S. 20E+Ol 2.S1E-03 7.20E-OS 7.20E-OS 7.20E-OS 7.20E-OS 7.20E-OS S .16E-OS 7.20E-OS
LA-140 1.67E+OO 1.12E-08 8.32E-09 2.14E-09 2.14E-09 2.14E-09 2.14E-09 9. 77E-OS 2.14E-09
CE-141,144 2. 84E+02 2.98E-06 1.22E-06 1. 67E-07 1. 67E-07 4.93E-07 1. 67E-07 1. 7lE-04 1. 67E-07
RUI03,106,BE7 3.67E+02 2.41E-OS 3.01E-06 3.01E-06 3.01E-06 2.8SE-OS 3.01E-06 1.83E-04 3.01E-06
ZR,NB-9S 6. S8E+Ol 2.06E-07 S.02E-08 3.S6E-08 3.S6E-08 S.41E-08 3.S6E-08 2.S0E-OS 3.S6E-08
BI-214 S .8SE+OS O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
CHILD 1-131 8.0SE+OO 1. 73E-OS 1. 73E-OS 9.83E-06 3.61E-03 2.84E-OS 9.83E-06 1. S4E-06 9.83E-06
BA-140 1. 28E+Ol 8.31E-OS 7.28E-08 4.8SE-06 4.8SE-06 2.37E-08 4.34E-08 4.21E-OS 4.8SE-06
CS-137 1.10E+04 3.27E-04 3.13E-04 4.62E-OS 4.62E-OS 1. 02E-04 3.67E-OS 1.96E-06 4.62E-OS
K-40 4. 60E+ll O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
SR-90 1. 03E+04 1. 70E-02 4.31E-03 4.31E-03 4.31E-03 4.31E-03 4.31E-03 2.29E-04 4.31E-03
SR-89 S. 20E+Ol 1.32E-03 3. 77E-DS 3. 77E-OS 3. 77E-OS 3. 77E-OS 3. 77E-OS S.llE-OS 3. 77E-OS
LA-140 1. 67E+OO 1.01E-08 3.S2E-09 1.19E-09 1.19E-09 1.19E-09 1.19E-09 9.84E-OS 1.19E-09
CE-141,144 2.84E+02 2.08E-06 6.S2E-07 1. II E-07 1.11E-07 3.61E-07 1. llE-07 1. 70E-04 1.11E-07
RUI03,l06,BE7 3.67E+02 1.17E-OS 1. 46E-06 1. 46E-06 1.46E-06 1. S8E-OS 1.46E-06 1.82E-04 1. 46E-06
ZR,NB-9S 6.S8E+Ol 1.16E-07 2.SSE-08 2.27E-08 2. 27E-08 3.6SE-08 2.27E-08 2.66E-OS 2.27E-08
BI-214 S.8SE+OS O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
TEEN 1-131 8.0SE+OO S.8SE-06 8.19E-06 4.40E-06 1. S9E-03 1.41E-OS 4.40E-06 1.62E-06 4.40E-06
BA-140 1. 28E+Ol 2.83E-OS 3.48E-08 1.82E-06 1.82E-06 1.18E-08 2.33E-08 4.38E-OS 1.82E-06
CS-137 1.lOE+04 1.12E-04 1. 49E-D4 S.19E-OS S.19E-OS S.07E-OS 1. 97E-OS 2.12E-06 S.19E-OS
K-40 4.60E+ll O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
SR-90 1.03E+04 8. 30E-03 2.0SE-03 2.0SE-03 2.0SE-03 2. OSE-03 2.0SE-03 2.33E-04 2.0SE-03
SR-89 S. 20E+Ol 4.40E-04 1.26E-OS 1.26E-OS 1. 26E-OS 1. 26E-OS 1. 26E-OS S.24E-OS 1. 26E-OS
LA-140 1. 67E+OO 3.48E-09 1. 72E-09 4.SSE-IO 4.SSE-IO 4.SSE-1O 4.SSE-IO 9.82E-OS 4.SSE-IO
CE-141,144 2.84E+02 6.96E-07 2.88E-07 3.74E-08 3.74E-08 1. 72E-07 3.74E-08 1.7 SE-04 3.74E-08
RUI03,106,BE7 3.67E+02 3.92E-06 4.94E-07 4.94E-07 4.94E-07 7.S6E-06 4.94E-07 1.88E-04 4.94E-07
ZR,NB-9S 6. S8E+Ol 4.12E-08 1. 24E-D8 8.94E-09 8.94E-09 1. 9lE-08 8.94E-09 3.00E-OS 8.94E-09
BI-214 S.8SE+OS O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
ADULT 1-131 8. OSE+OO 4.16E-06 S.96E-06 3. 4lE-06 1.11E-03 1. 02E-OS 3.41E-06 1.S7E-06 3.41E-06
BA-140 1. 28E+Ol 2.03E-OS 2.SSE-08 1.34E-06 1.34E-06 8.68E-09 1.46E-08 4.18E-OS 1.34E-06
CS-137 1.lOE+04 7.98E-OS 1.09E-04 7.1SE-OS 7.1SE-OS 3.71E-OS 1. 23E-OS 2.10E-06 7.1SE-OS
K-40 4.60E+ll O.OOE-Ol O.OOE-Dl O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
SR-90 1.03E+04 7.61E-03 1. 86E-03 1.86E-03 1. 86E-03 1. 86E-03 1.86E-03 2. 19E-04 1.86E-03
CC:-89 5.20E+Ol 3.09E-04 R.B5[-06 Po. 5,"-06 8.8SE-06 8.85E-06 8.85E-06 4.94E-05 8.85E-06
LA-140 1.67E+00 2.50E-09 1.26E-09 3.34F-IO 3.34E-IO 3.34E-IO 3.34E-IO 9.25E-05 3.34E-IO
CE-141,144 2. 84E+02 4.89E-07 2.04E-07 2.62E-08 2.62E-08 1. 2lE-07 2.62E-08 1. 65E-04 2.62E-08
RUI03 ,106 ,BE7 3.67E+02 2.75E-06 3.48E-D7 3.48E-07 3.48E-D7 S.31E-06 3.48E-07 1.78E-04 3.48E-07
ZR,NB-9S 6. 58E+Ol 3.04E-08 9.76E-09 6.6lE-09 6.61E-09 1.54E-08 6.6lE-09 2.l0E-OS 6.6lE-09
61-214 S.85E+05 O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
60
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TABLE AI (Contmued)
Pathway: Air inhalation
Organ
Age Nuclide Halflife,d Bone Liver T. Body Thyroid Kidney Lung Gi-Lli Skin
INFANT 1-131 8.05E+OO 2.71E-05 3.05E-05 1.40E-05 1. 06E-02 3.70E-05 1.40E-05 7.56E-07 1. 40E-05
BA-140 1. 28E+01 4.00E-05 4.00E-08 2. OlE-06 2. OlE-06 9.59E-09 1. 14E-03 2.74E-05 2.07E-06
CS-13 7 1.10E+04 3.92E-04 4.37E-04 3.25E-05 3.25E-05 1.23E-04 5.09E-05 9.53E-07 3.25E-05
K-40 4.60E+11 O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol 0.00E-01 O.OOE-Ol
SR-90 1. 03E+04 2. 92E-02 1.85E-03 1. 85E-03 1.85E-03 1. 85E-03 8.03E-03 9.36E-05 1.85E-03
SR-89 5. 20E+Ol 2.84E-04 8.15E-06 8.15E-06 8.15E-06 8.15E-06 1.45E-03 4.57E-05 8.15E-06
LA-140 1. 67E+OO 3.61E-07 1.43E-07 3.68E-08 3.68E-08 3.68E-08 1. 21E-04 6.06E-05 3.68E-08
CE-141,144 2.84E+02 2.28E-03 8.65E-04 1.26E-04 1. 26E-04 3.84E-04 7.03E-03 1.06E-04 1.26E-04
RU103.106,BE7 3.67E+02 6.20E-05 7. 77E-06 7. 77E-06 7. 77E-06 7.61E-05 8.62E-03 1.17E-04 7. 77E-06
ZR,NB-95 6. 58E+Ol 8.24E-05 1.99E-05 1.45E-05 1.45E-05 2.22E-05 1.25E-03 1.55E-05 1.45E-05
BI-214 5.85E+05 0.00E-01 O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
CHILD 1-131 8.05E+00 1. 30E-05 1. 30E-05 7.37E-06 4.39E-03 2.13E-05 7.37E-06 7.68E-07 7.37E-06
BA-140 1. 28£+01 2.00E-05 1.75E-08 1. 17E-06 1.17E-06 5. 71E-09 4.71E-04 2.75E-05 1. 17E-06
CS-13 7 1.10E+04 2.45E-04 2.23E-04 3.47E-05 3.47E-05 7.63E-05 2.81E-05 9.78E-07 3.47E-05
K-40 4.60E+11 0.00E-01 O.OOE-Ol 0.00E-01 0.00E-01 0.00E-01 O.OOE-Ol O.OOE-Ol O.OOE-Ol
SR-90 1.03E+04 2.73E-02 1. 74E-03 1.74E-03 1.74E-03 1.74E-03 4.00E-03 9.28E-05 1. 74E-03
SR-89 5. 20E+Ol 1. 62E-04 4.66E-06 4.66E-06 4.66E-06 4.66E-06 5.83E-04 4.52E-05 4.66E-06
LA-140 1. 67E+OO 1. 74E-07 6.08E-08 2.04E-08 2.04E-08 2.04E-08 4.94E-05 6.10E-05 2.04E-08
CE-141,144 2. 84E+02 1. 83E-03 5. 72E-04 9.77E-05 9. 77E-05 3.17E-04 3.23E-03 1.05E-04 9. 77E-05
RU103,106.BE7 3.67E+02 3.68E-05 4.57E-06 4.5lE-06 4.57E-06 4.97E-05 3.87E-03 1.16E-04 4.57E-06
ZR.NB-95 6.58E+Ol 5.13E-05 1. 13E-05 1.00E-05 1.00E-05 1.61E-05 6.03E-04 1.65E-05 1.00E-05
BI-214 5.85E+05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 O.OOE-Ol 0.00E-01 O.OOE-Ol 0.00E-01
TEEN 1-131 8.05E+OO 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 3.30E-06 8.11E-07 3.30E-06
BA-140 1. 28E+01 6.84E-06 8.38E-09 4.40E-07 4.40E-07 2.85E-09 2.55E-04 2.86E-05 4.40E-07
CS-137 1.10E+04 8.38E-05 1.06E-04 3.89E-05 3.89E-05 3.80E-05 1. 51E-05 1.06E-06 3.89E-05
K-40 4.60E+11 O.OOE-Ol O.OOE-Ol 0.00E-01 0.00E-01 O.OOE-Ol O.OOE-Ol 0.00E-01 O.OOE-Ol
SR-90 1.03E+04 1. 35E-02 8.35E-04 8.35E-04 8.35E-04 8.35E-04 2.06E-03 9.56E-05 8.35E-04
SR-89 5.20E+01 5.43E-05 1. 56E-06 1.56E-06 1.56E-06 1.56E-06 3.02E-04 4.64E-05 1.56E-06
LA-140 1. 67E+00 5.99E-08 2.95E-08 7.82E-09 7.82E-09 7.82E-09 2.68E-05 6.09E-05 7.82E-09
CE-141,144 2.84E+02 6.11E-04 2.53E-04 3.28E-05 3.28E-OS 1. 51E-04 1.67E-03 1.08E-04 3.28E-05
RU103.106.BE7 3.67E+02 1.23E-05 1.55E-06 1.55E-06 1.55E-06 2.38E-05 2.01E-03 1.20E-04 1. 55E-06
ZR.NB-95 6. 58E+Ol 1. 82E-05 5. 73E-06 3.94E-06 3.94E-06 B.42E-06 3.36E-04 1.86E-05 3.94E-06
BI-214 5.85E+05 O.OOE-Ol O.OOE-Ol O.OOE-Ol 0.00E-01 0.00E-01 O.OOE-Ol 0.00E-01 O.OOE-Ol
ADULT 1-131 8.05E+OO 3. 15E-06 4.47E-06 2.56E-06 1.49E-03 7.67E-06 2.56E-06 7.85E-07 2.56E-06
BA-140 1. 28E+Ol 4.88E-06 6.13E-09 3.21E-07 3.21E-07 2.09E-09 1. 59E-04 2.73E-05 3.21E-07
CS-137 1.10E+04 5.98E-05 7. 77E-05 5.36E-05 5.36E-05 2.7BE-05 9.41E-06 1.05E-06 5.36E-05
K-40 4.60E+11 O.OOE-Ol O.OOE-Ol O.OOE-Ol 0.00E-01 O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
SR-90 1. 03E+04 1. 24E-02 7.62E-04 7.62E-04 7.62E-04 7. 62E-04 1.20E-03 9.02E-05 7.62E-04
SR-89 5. 20E+Ol 3.80E-05 1. 09E-06 1. 09E-06 1.09E-06 1. 09E-06 1. 75E-04 4.37E-05 1.09E-06
LA-140 1.67E+00 4.30E-08 2.17E-08 5. 73E-09 5. 73E-09 5. 73E-09 1.70E-05 5.73E-05 5.73E-09
CE-141.144 2.84E+02 4.29E-04 1.79E-04 2.30E-05 2.30E-05 1. 06E-04 9.73E-04 1 .02E-04 2.30E-05
RU103,106.BE7 3.67E+02 8.64E-06 1.09E-06 1.09E-06 1. 09E-06 1.67E-05 1.18E-03 1.14E-04 1.09E-06
ZR,NB-95 6.58E+Ol 1.34E-05 4.30E-06 2. 91E-06 2.91E-06 6. 77E-06 2.22E-04 1. 88E-05 2. 91E-06
BI-214 5.85E+05 0.00E-01 O.OOE-Ol O.OOE-Ol 0.00E-01 0.00E-01 O.OOE-Ol O.OOE-Ol 0.00E-01
61
-------
TABLE A I (ContlOued)
Pathway: Air submersion
Organ
Age Nuclide Halflife.d Bone Liver T. Body Thyroid Kidney Lung Gi-Lli Skin
INFANT 1-131 8.05E+OO 3.10E-07 3.10E-07 3.10E-07 3.10E-07 3.10E-07 3.10E-07 3.10E-07 4.90E-07
BA-140 1. 28E+Ol 2.20E-07 2.20E-07 2.20E-07 2.20E-07 2.20E-07 2. 20E-07 2.20E-07 4.40E-07
CS-137 1.10E+04 4.70E-07 4. 70E-07 4.70E-07 4.70E-07 4.70E-07 4.70E-07 4.70E-07 7.00E-07
K-40 4. 60E+11 O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
SR-90 1.03E+04 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 1. 30E-07
SR-89 5.20E+Ol 2.10E-09 2.10E-09 2.10E-09 2.10E-09 2.10E-09 2.10E-09 2.10E-09 4.90E-07
LA-140 1.67E+OO 1.90E-06 1.90E-06 1.90E-06 1. 90E-06 1. 90E-06 1.90E-06 1. 90E-06 2.70E-06
CE-141,144 2.84E+02 5.90E-08 5.90E-08 5.90E-08 5. 90E-08 5.90E-08 5.90E-08 5.90E-08 1. 20E-06
RUI03.106,BE7 3.6 7E+02 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 1.50E-06
ZR,NB-95 6.58E+Ol 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 8,40E-07
BI-214 5.85E+05 O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
CHILD 1-131 8.05E+OO 3.10E-07 3.10E-07 3.10E-07 3.10E-07 3.10E-07 3.10E-07 3.10E-07 4.90E-07
BA-140 1.28E+Ol 2.20E-07 2.20E-07 2.20E-07 2.20E-07 2.20E-07 2.20E-07 2. 20E-07 4.40E-07
CS-137 1. 10E+04 4.70E-07 4.70E-07 4.70E-07 4.70E-07 4.70E-07 4.70E-07 4.70E-07 7.00E-07
K-40 4. 60E+11 O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
SR-90 1. 03E+04 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 1.30E-07
SR-89 5. 20E+Ol 2.10E-09 2.10E-09 2.10E-09 2.10E-09 2.10E-09 2.10E-09 2.10E-09 4.90E-07
LA-140 1. 67E+OO 1.90E-06 1.90E-06 1.90E-06 1. 90E-06 1.90E-06 1.90E~06 1.90E-06 2.70E-06
CE-141,144 2. 84E+02 5. 90E-08 5.90E-08 5.90E-08 5.90E-08 5.90E-08 5.90E-08 5.90E-08 1. 20E-06
RUI03,106.BE7 3.67E+02 4.10E-07 4.10E-07 4.lOE-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 1.50E-06
ZR,NB-95 6.58E+Ol 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 8.40E-07
BI-214 5.85E+05 O.OOE-Ol 0.00E-01 O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
TEEN 1-131 8.05E+OO 3.10E-07 3.10E-07 3.10E-07 3.10E-07 3.10E-07 3.lOE-07 3.10E-07 4.90E-07
BA-140 1. 28E+Ol 2.20E-07 2.20E-07 2.20E-07 2.20E-07 2.20E-07 2.20E-07 2. 20E-07 4.40E-07
CS-137 1. 10E+04 4.70E-07 4.70E-07 4. 70E-07 4. 70E-07 4. 70E-07 4. 70E-07 4.70E-07 7.00E-07
K-40 4.60E+11 0.00E-01 O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
SR-90 1. 03E+04 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 1.30E-07
SR-89 5. 20E+Ol 2.10E-09 2.10E-09 2.10E-09 2.10E-09 2.10E-09 2.lOE-09 2.10E-09 4.90E-07
LA-140 1.67E+OO 1.90E-06 1. 90E-06 1. 90E-06 1. 90E-06 1.90E-06 1. 90E-06 1. 90E-06 2.70E-06
CE-141.144 2. 84E+02 5.90E-08 5.90E-08 5.90E-08 5.90E-08 5.90E-08 5.90E-08 5.90E-08 1. 20E-06
RUI03,106,BE7 3.67E+02 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 1. 50E-06
ZR,NB-95 6. 58E+Ol 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 8.40E-07
BI-214 5.85E+05 U.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
ADULT 1-131 8.05E+00 3.10E-07 3.10E-07 3.10E-07 3.10E-07 3.10E-07 3.10E-07 3.10E-07 4.90E-07
BA-140 1.28E+Ol 2.20E-07 2.20E-07 2.20E-07 2.20E-07 2.20E-07 2.20E-07 2.20E-07 4.40E-07
CS-137 1.10E+04 4.70E-07 4.70E-07 4.70E-07 4.70E-07 4. 70E-07 4.70E-07 4.70E-07 7.00E-07
K-40 4. 60E+11 O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol
SR-90 1.03E+04 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 2.40E-I0 1. 30E-07
SR-89 5. 20E+Ol 2.10E-09 2.10E-09 2.10E-09 2.10E-09 2.10E-09 2.10E-09 2.10E-09 4.90E-07
LA-140 1.67E+OO 1.90E-06 1.90E-06 1.90E-06 1. 90E-06 1. 90E-06 1. 90E-06 1. 90E-06 2. 70E-06
CE-141,144 2. 84E+02 5.90E-08 5.90E-08 5.90E-08 5.90E-08 5.90E-08 5.90E-08 5.90E-08 1.20E-06
RUI03,106.BE7 3.6 7E+02 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 4.10E-07 1.50E-06
ZR,NB-95 6. 58E+Ol 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 6.80E-07 8.40E-07
BI-214 5. 85E+05 O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-Ol O.OOE-ol O.OOE-Ol 0.00E-01
62
-------
variant. To be precise, when an interval between successive abscissa values
is over twice the length of the sum of the two adjacent intervals, the mid-
point of the line segment connecting the points corresponding to these
abscissa values was added to the actual data points for curve fitting
purposes.
In calculating net radionucl ide concentrations in milk, estimates of
background concentrations were established using ERAMS data for July, August,
and September (prior to September 17) 1977. These months were chosen because
they immediately preceded the weapons test, and, during this period, no events
had taken pl ace in the worl d which woul d have tended to increase background
levels of radionuclides in milk in the United States. Gross radionuclide
concentrations for air were used for the calculations since background
radionuclide levels for air were not available. The integrated radionuclide
concentrations for air and milk at each location and the average integrated
concentrations for each state are listed in Table A2.
A.3
Results of individual dose calculations
The doses for an individual in each age group in each state
in Table A3. These doses were calculated using the equation and
in the text.
are tabulated
methods discussed
A4.
Estimation of milk consumption and population for each state
The milk production in the U.S. for the period of integration (September
17 - December 1, 1977) was calculated using USDA milk production data (DOA77)
as shown in Table A4.
63
-------
TABLE A2
Integrated radionuclide concentrations in milk and air
Pathway
Location
Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
1-131 NO DATA O.OOE-Ol
BA-140 NO DATA 8.62E-03
CS-137 NO DATA 2.69E-02
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA O.OOE-Ol
RUI03,106,BE7 NO DATA 1.07E+OO
ZR,NB-95 NO DATA 5.35E-Ol
BI-214 NO DATA 4.13E-02
1-131 NO DATA 7.10E-Ol
BA-140 NO DATA 1.25E+OO
CS-137 NO DATA 6.75E-03
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 1.16E+Ol
RUI03,106,BE7 NO DATA 2.59E+OO
ZR,NB-95 NO DATA 9.06E-Ol
BI-214 NO DATA 9.35E-02
1-131 NO DATA O.OOE-Ol
BA-140 NO DATA 1.26E+OO
CS-137 NO DATA 2.51E-02
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 3.75E+OO
RUI03,106,BE7 NO DATA 2.76E+OO
ZR,NB-95 NO DATA 2.12E+OO
BI-214 NO DATA 9.58E-03
1-131 1.99E+03 NO DATA
BA-140 4.60E+02 NO DATA
CS-137 2.23E+02 NO DATA
K-40 2.97E+03 NO DATA
SR-90 1.42E+02 NO DATA
SR-89 3.06E+02 NO DATA
LA-140 5.29E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
64
AK:ANCHORAGE
AK:FAIRBANKS
AK:JUNEAU
AK:PALMER
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
ALASKA 1-131 1. 99E+03 2.36E-Ol
BA-140 4.60E+02 8.39E-Ol
CS-137 2.23E+02 1.95E-02
K-40 2.97E+03 NO DATA
SR-90 1.42E+02 NO DATA
SR-89 3.06E+02 NO DATA
LA-140 5.29E+02 NO DATA
CE-141,144 NO DATA 5.11E+OO
RUI03,106,BE7 NO DATA 2.14E+OO
ZR,NB-95 NO DATA 1.18E+OO
B1-214 NO DATA 4.81E-02
AL:MONTGOMERY 1-131 5.39E+02 6.93E-Ol
BA-140 5.64E+02 2.84E+OO
CS-137 O.OOE-Ol O.OOE-Ol
K-40 1.40E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 4.51E+02 NO DATA
LA-140 6.49E+02 NO DATA
CE-141,144 NO DATA 1.16E+Ol
RUI03,106,BE7 NO DATA 1.60E+Ol
ZR,NB-95 NO DATA 3.09E+OO
B1-214 NO DATA 5.77E-Ol
ALABAMA 1-131 5.39E+02 6.93E-Ol
BA-140 5.64E+02 2.84E+OO
CS-137 O.OOE-Ol O.OOE-Ol
K-40 1.40E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 4.51E+02 NO DATA
LA-140 6.49E+02 NO DATA
CE-141,144 NO DATA 1.16E+Ol
RUI03,106,BE7 NO DATA 1.60E+Ol
ZR,NB-95 NO DATA 3.09E+OO
B1-214 NO DATA 5.77E-Ol
AR:L1TTLE ROCK 1-131 8.49E+02 l.OOE+OO
BA-140 7.97E+02 3.11E+OO
CS-137 1.65E+02 O.OOE-Ol
K-40 5.04E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.04E+03 NO DATA
LA-140 9.16E+02 NO DATA
CE-141,144 NO DATA 1.22E+01
RUI03,106,BE7 NO DATA 1.19E+Ol
ZR,NB-95 NO DATA 2.25E+OO
B1-214 NO DATA O.OOE-Ol
65
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
ARKANSAS 1-131 8.49E+02 1.OOE+OO
BA-140 7.97E+02 3.11E+OO
CS-137 1.65E+02 O.OOE-Ol
K-40 5.04E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1. 04E+03 NO DATA
LA-140 9.16E+02 NO DATA
CE-141,144 NO DATA 1.22E+Ol
RUI03,106,BE7 NO DATA 1.19E+Ol
ZR,NB-95 NO DATA 2.25E+OO
BI-214 NO DATA O.OOE-Ol
AZ: PHOENIX 1-131 3.39E+02 3.42E+OO
BA-140 4.55E+02 9.08E+OO
CS-137 O.OOE-Ol O.OOE-Ol
K-40 9.47E+02 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.93E+Ol NO DATA
LA-140 5.23E+02 NO DATA
CE-141,144 NO DATA 2.88E+Ol
RUI03,106,BE7 NO DATA 3.27E+Ol
ZR,NB-95 NO DATA 5.60E+OO
BI-214 NO DATA O.OOE-Ol
ARIZONA 1-131 3.39E+02 3.42E+OO
BA-140 4.55E+02 9.08E+OO
CS-137 O.OOE-Ol O.OOE-Ol
K-40 9.47E+02 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.93E+Ol NO DATA
LA-140 5.23E+02 NO DATA
CE-141,144 NO DATA 2.88E+Ol
RUI03,106,BE7 NO DATA 3.27E+Ol
ZR,NB-95 NO DATA 5.60E+OO
BI-214 NO DATA O.OOE-Ol
CA:BERKELEY 1-131 NO DATA 2.37E-Ol
BA-140 NO DATA 1.71E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 7.76E+OO
RUI03,106,BE7 NO DATA 1. 09 E+ 01
ZR,NB-95 NO DATA 2.48E+OO
BI-214 NO DATA 1.61E-Ol
66
-------
TABLE A2 (Continued)
Location Pathway
Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
CA:LOS ANGELES 1-131 1. 93E+02 8.36E-Ol
BA-140 2.76E+02 3.87E+OO
CS-137 1.83E+02 O.OOE-Ol
K-40 8.58E+02 NO DATA
SR-90 3.77E+Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 3.19E+02 NO DATA
CE-141,144 NO DATA 1. 75E+Ol
RUI03,106,BE7 NO DATA 2.07E+Ol
ZR,NB-95 NO DATA 4.66E+OO
BI-214 NO DATA O.OOE-Ol
CA:SACRAMENTO 1-131 O.OOE-Ol NO DATA
BA-140 6.46E+02 NO DATA
CS-137 9.77E+Ol NO DATA
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 3.17E+Ol NO DATA
LA-140 7.43E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
CA:SAN FRANCISCO 1-131 1. 87E+02 NO DATA
BA-140 4.92E+02 NO DATA
CS-137 2.19E+02 NO DATA
K-40 3.67E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.93E+Ol NO DATA
LA-140 5.66E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
CALIFORNIA 1-131 1.26E+02 5.36E-Ol
BA-140 4.71E+02 2.79E+OO
CS-137 1. 66E+02 O.OOE-Ol
K-40 1.50E+03 NO DATA
SR-90 1. 25E+Ol NO DATA
SR-89 2.03E+Ol NO DATA
LA-140 5.42E+02 NO DATA
CE-141,144 NO DATA 1. 26E+Ol
RUI03,106,BE7 NO DATA 1.58E+Ol
ZR,NB-95 NO DATA 3.57E+OO
BI-214 NO DATA 8.05E-02
67
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
CO:DENVER 1-131 6.47E+02 9.94E+OO
BA-140 3.13E+02 2.34E+Ol
CS-137 3.56E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 5.37E+Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 3.61E+02 NO DATA
CE-141,144 NO DATA 7.48E+Ol
RUI03,106,BE7 NO DATA 7.02E+Ol
ZR,NB-95 NO DATA 1.14E+Ol
BI-214 NO DATA O.OOE-Ol
COLORADO 1-131 6.47E+02 9.94E+OO
BA-140 3.13E+02 2.34E+Ol
CS-137 3.56E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 5.37E+Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 3.61E+02 NO DATA
CE-141,144 NO DATA 7.48E+Ol
RUI03,106,BE7 NO DATA 7.02E+Ol
ZR,NB-95 NO DATA 1.14E+Ol
BI-214 NO DATA O.OOE-Ol
CT:HARTFORD 1-131 3.25E+02 3.18E-Ol
BA-140 4.94E+02 1.15E+OO
CS-137 1.05E+02 O.OOE-Ol
K-40 3.57E+02 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 3.10E+02 NO DATA
LA-140 5.68E+02 NO DATA
CE-141,144 NO DATA 1.35E+OO
RUI03,106,BE7 NO DATA 3.81E+OO
ZR,NB-95 NO DATA 8.61E-Ol
BI-214 NO DATA O.OOE-Ol
CONNECTICUT 1-131 3.25E+02 3.18E-Ol
BA-140 4.94E+02 1.15E+OO
CS-137 l.05E+02 O.OOE-Ol
K-40 3.57E+02 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 3.10E+02 NO DATA
LA-140 5.68E+02 NO DATA
CE-141,144 NO DATA 1.35E+OO
RUI03,106,BE7 NO DATA 3.81E+OO
ZR,NB-95 NO DATA 8.61E-Ol
BI-214 NO DATA O.OOE-Ol
68
-------
TABLE A2 (Continued)
Location Pathway
Nuclide Milk Air
(pCi-djliter) (pCi-djrn**3)
DC:WASHINGTON 1-131 5.77E+02 1.55E+OO
BA-140 3.40E+02 3.21E+OO
CS-137 1.38E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 4.49E+Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 3.92E+02 NO DATA
CE-141,144 NO DATA 6.66E+OO
RUI03,106,BE7 NO DATA 6.17E+OO
ZR,NB-95 NO DATA 5.04E-Ol
BI-214 NO DATA O.OOE-Ol
D.C. 1-131 5.77E+02 1.55E+OO
BA-140 3.40E+02 3.21E+OO
CS-137 1.38E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 4.49E+Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 3.92E+02 NO DATA
CE-141,144 NO DATA 6.66E+OO
RUI03,106,BE7 NO DATA 6.17E+OO
ZR,NB-95 NO DATA 5.04E-Ol
BI-214 NO DATA O.OOE-Ol
DE:WILMINGTON 1-131 5.56E+02 5.94E-Ol
BA-140 7.08E+02 2.15E+OO
CS-137 5.04E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.26E+02 NO DATA
LA-140 8.13E+02 NO DATA
CE-141,144 NO DATA 3.16E+OO
RUI03,106,BE7 NO DATA 5.94E+OO
ZR,NB-95 NO DATA 8.94E-Ol
BI-214 NO DATA O.OOE-Ol
DELAWARE 1-131 5.56E+02 5.94E-Ol
BA-140 7.08E+02 2.15E+OO
CS-137 5.04E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.26E+02 NO DATA
LA-140 8.13E+02 NO DATA
CE-141,144 NO DATA 3.16E+OO
RUI03,106,BE7 NO DATA 5.94E+OO
ZR,NB-95 NO DATA 8.94E-Ol
BI-214 NO DATA O.OOE-Ol
69
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/rn**3)
FL:JACKSONVILLE 1-131 NO DATA 1. 58E+OO
BA-140 NO DATA 4.96E+OO
CS-137 NO DATA O.OOE-01
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 2.25E+Ol
RUI03,106,BE7 NO DATA 1.92E+Ol
ZR,NB-95 NO DATA 3.58E+OO
BI-214 NO DATA O.OOE-Ol
FL:MIAMI 1-131 NO DATA 2.56E+OO
BA-140 NO DATA 7.93E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 3.51E+Ol
RUI03,106,BE7 NO DATA 3.03E+Ol
ZR,NB-95 NO DATA 5.12E+OO
BI-214 NO DATA O.OOE-Ol
FL:TAMPA 1-131 4.46E+02 NO DATA
BA-140 3.62E+02 NO DATA
CS-137 O.OOE-Ol NO DATA
K-40 1.01E+03 NO DATA
SR-90 5.13E+Ol NO DATA
SR-89 1. 09E+Ol NO DATA
LA-140 4.16E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
FLORIDA 1-131 4.46E+02 2.07E+OO
BA-140 3.62E+02 6.44E+OO
CS-137 O.OOE-Ol O.OOE-Ol
K-40 1.01E+03 NO DATA
SR-90 5.13E+Ol NO DATA
SR-89 1. 09E+Ol NO DATA
LA-140 4.16E+02 NO DATA
CE-141,144 NO DATA 2.88E+Ol
RUI03,106,BE7 NO DATA 2.47E+Ol
ZR,NB-95 NO DATA 4.35E+OO
BI-214 NO DATA O.OOE-Ol
70
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
GA:ATLANTA 1-131 2.25E+02 5.26E+00
BA-140 5.07E+02 1.31E+Ol
CS-137 O.OOE-Ol O.OOE-Ol
K-40 4.99E+02 NO DATA
SR-90 1.49E+Ol NO DATA
SR-89 1.32E+02 NO DATA
LA-140 5.83E+02 NO DATA
CE-141,144 NO DATA 3.21E+Ol
RUI03,106,BE7 NO DATA 4.09E+Ol
ZR ,NB-9 5 NO DATA 3.71E+00
BI-214 NO DATA O.OOE-Ol
GEORGIA 1-131 2.25E+02 5.26E+00
BA-140 5.07E+02 1. 31E+Ol
CS-137 O.OOE-Ol O.OOE-Ol
K-40 4.99E+02 NO DATA
SR-90 1.49E+Ol NO DATA
SR-89 1.32E+02 NO DATA
LA-140 5.83E+02 NO DATA
CE-141,144 NO DATA 3.21E+Ol
RUI03,106,BE7 NO DATA 4.09E+Ol
ZR,NB-95 NO DATA 3.71E+00
BI-214 NO DATA O.OOE-Ol
Hl:HONOLULU 1-131 2.39E+02 2.85E+00
BA-140 1. 66E+02 7.89E+00
CS-137 8.14E+Ol O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1. 38E+02 NO DATA
LA-140 1.89E+02 NO DATA
CE-141,144 NO DATA 1.18E+00
RUI03,106,BE7 NO DATA 2.50E+Ol
ZR,NB-95 NO DATA 2.82E+00
BI-214 NO DATA O.OOE-Ol
HAWAII 1-131 2.39E+02 2.85E+00
BA-140 1.66E+02 7.89E+00
CS-137 8.14E+Ol O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.38E+02 NO DATA
LA-140 1.89E+02 NO DATA
CE-141,144 NO DATA 1.18E+00
RUI03,106,BE7 NO DATA 2.50E+Ol
ZR,NB-95 NO DATA 2.82E+00
BI-214 NO DATA O.OOE-Ol
71
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pC i -d 1m * * 3 )
IA:DES MOINES 1-131 1.45E+03 NO DATA
BA-140 2.72E+02 NO DATA
CS-137 2.07E+02 NO DATA
K-40 1.52E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 7.25E+02 NO DATA
LA-140 3.13E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
IA:IOWA CITY 1-131 NO DATA 6.25E-Ol
BA-140 NO DATA 1. 74E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 5.62E+OO
RUI03,106,BE7 NO DATA 7.12E+OO
ZR,NB-95 NO DATA 1. 61E+OO
BI-214 NO DATA O.OOE-Ol
IOWA 1-131 1.45E+03 6.25E-Ol
BA-140 2.72E+02 1.74E+OO
CS-137 2.07E+02 O.OOE-Ol
K-40 1.52E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 7.25E+02 NO DATA
LA-140 3.13E+02 NO DATA
CE-141,144 NO DATA 5.62E+OO
RUI03,106,BE7 NO DATA 7.12E+OO
ZR,NB-95 NO DATA 1. 61E+OO
BI-214 NO DATA O.OOE-Ol
ID:BOISE 1-131 NO DATA 9.83E-Ol
BA-140 NO DATA 2.56E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 1.33E+Ol
RUI03,106,BE7 NO DATA 8.44E+OO
ZR,NB-95 NO DATA 2.28E+OO
BI-214 NO DATA O.OOE-Ol
72
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
ID:IDAHO FALLS 1-131 7.21E+02 6.38E+00
BA-140 4.31E+02 1.39E+Ol
CS-137 2.40E+02 O.OOE-Ol
K-40 1.13E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 6.07E+Ol NO DATA
LA-140 4.96E+02 NO DATA
CE-141,144 NO DATA 3.81E+01
RUI03,106,BE7 NO DATA 4.33E+Ol
ZR,NB-95 NO DATA 9.77E+00
BI-214 NO DATA O.OOE-Ol
IDAHO 1-131 7.21E+02 3.68E+00
BA-140 4.31E+02 8.23E+00
CS-137 2.40E+02 O.OOE-Ol
K-40 1.13E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
5R-89 6.07E+Ol NO DATA
LA-140 4.96E+02 NO DATA
CE-141,144 NO DATA 2.57E+Ol
RUI03,106,BE7 NO DATA 2.58E+Ol
ZR,NB-95 NO DATA 6.02E+00
BI-214 NO DATA O.OOE-Ol
IL:CHICAGO 1-131 1. 25E+03 NO DATA
BA-140 7.09E+02 NO DATA
C5-137 2.11E+02 NO DATA
K-40 1.78E+02 NO DATA
5R-90 1.56E+02 NO DATA
5R-89 5.00E+02 NO DATA
LA-140 8.16E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
IL:WHEATON 1-131 NO DATA 1.52E-02
BA-140 NO DATA 9.04E-01
C5-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
5R-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 3.65E+00
RUI03,106,BE7 NO DATA 4.02E+00
ZR,NB-95 NO DATA 8.52E-01
BI-214 NO DATA 0.00E-01
73
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
ILLINOIS I-131 1.25E+03 1.52E-02
BA-140 7.09E+02 9.04E-Ol
CS-137 2.11E+02 O.OOE-Ol
K-40 1.78E+02 NO DATA
SR-90 1.56E+02 NO DATA
SR-89 5.00E+02 NO DATA
LA-140 8.16E+02 NO DATA
CE-141,144 NO DATA 3.65E+OO
RUI03,106,BE7 NO DATA 4.02E+OO
ZR,NB-95 NO DATA 8.52E-Ol
BI-214 NO DATA O.OOE-Ol
IN: INDIANAPOLIS I-131 l.07E+03 6.29E-Ol
BA-140 4.91E+02 2.10E+OO
CS-137 5.54E+Ol O.OOE-Ol
K-40 3.42E+03 NO DATA
SR-90 5.73E+Ol NO DATA
SR-89 3.75E+02 NO DATA
LA-140 5.64E+02 NO DATA
CE-141,144 NO DATA 1.17E+Ol
RUI03,106,BE7 NO DATA 1.27E+Ol
ZR,NB-95 NO DATA 3.21E+OO
BI-214 NO DATA O.OOE-Ol
INDIANA I-131 1.07E+03 6.29E-Ol
BA-140 4.91E+02 2.10E+OO
CS-137 5.54E+Ol O.OOE-Ol
K-40 3.42E+03 NO DATA
SR-90 5.73E+Ol NO DATA
SR-89 3.75E+02 NO DATA
LA-140 5.64E+02 NO DATA
CE-141,144 NO DATA 1.17E+Ol
RUI03,106,BE7 NO DATA 1.27E+Ol
ZR,NB-95 NO DATA 3.21E+OO
BI-214 NO DATA O.OOE-Ol
KS:TOPEKA I-131 NO DATA 1.26E+OO
BA-140 NO DATA 2.72E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 9.68E+OO
RUI03,106,BE7 NO DATA 8.48E+OO
ZR,NB-95 NO DATA 1.99E+OO
BI-214 NO DATA O.OOE-Ol
74
-------
TABLE A2 (Continued) ,/
Pathway
Location Nuclide Milk Air
(pCi-d/liter) ( pC i -d 1m * * 3 )
KS:WICHITA 1-131 4.91E+02 NO DATA
BA-140 3.68E+02 NO DATA
CS-137 2.50E+02 NO DATA
K-40 9.39E+02 NO DATA
SR-90 O.OOE-01 NO DATA
SR-89 3.16E+02 NO DATA
LA-140 4.23E+02 NO DATA
CE-141,144 NO DATA NO DATA
RU103,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
KANSAS 1-131 4.91E+02 1.26E+OO
BA-140 3.68E+02 2.72E+OO
CS-137 2.50E+02 O.OOE-01
K-40 9.39E+02 NO DATA
SR-90 O.OOE-01 NO DATA
SR-89 3.16E+02 NO DATA
LA-140 4.23E+02 NO DATA
CE-141,144 NO DATA 9.68E+OO
RU103,106,BE7 NO DATA 8.48E+OO
ZR,NB-95 NO DATA 1. 99E+OO
BI-214 NO DATA O.OOE-01
KY:FRANKFORT 1-131 NO DATA 3.62E-01
BA-140 NO DATA 1.26E+OO
CS-137 NO DATA O.OOE-01
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 5.18E+OO
RU103,106,BE7 NO DATA 6.04E+OO
ZR,NB-95 NO DATA 1.74E+OO
BI-214 NO DATA O.OOE-01
KY:LOUISVILLE 1-131 9.49E+02 NO DATA
BA-140 6.10E+02 NO DATA
CS-137 3.21E+02 NO DATA
K-40 O.OOE-01 NO DATA
SR-90 4.84E+01 NO DATA
SR-89 4.45E+02 NO DATA
LA-140 7.01E+02 NO DATA
CE-141,144 NO DATA NO DATA
RU103,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
75
-------
TF.BLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
KENTUCKY 1-131 9.49E+02 3.62E-Ol
BA-140 6.10E+02 1.26E+OO
CS-137 3.21E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 4.84E+Ol NO DATA
SR-89 4.45E+02 NO DATA
LA-140 7.01E+02 NO DATA
CE-141,144 NO DATA 5.18E+OO
RUI03,106,BE7 NO DATA 6.04E+OO
ZR,NB-95 NO DATA 1. 74E+OO
BI-214 NO DATA O.OOE-Ol
LA:NEW ORLEANS 1-131 4.28E+02 2.25E-Ol
BA-140 1. 61E+02 2.93E+OO
CS-137 O.OOE-Ol O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 1.87E+02 NO DATA
CE-141,144 NO DATA 7.86E+OO
RUI03,106,BE7 NO DATA 1.25E+Ol
ZR,NB-95 NO DATA 2.30E+OO
BI-214 NO DATA O.OOE-Ol
LOUISIANA 1-131 4.28E+02 2.25E-Ol
BA-140 1.61E+02 2.93E+OO
CS-137 O.OOE-Ol O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 1.87E+02 NO DATA
CE-141,144 NO DATA 7.86E+OO
RUI03,106,BE7 NO DATA 1.25E+Ol
ZR,NB-95 NO DATA 2.30E+OO
BI-214 NO DATA O.OOE-Ol
MA:BOSTON 1-131 6.50E+02 NO DATA
BA-140 2.35E+02 NO DATA
CS-137 1.97E+02 NO DATA
K-40 2.71E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.68E+02 NO DATA
LA-140 2.70E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
76
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) ( pC i -d 1m * * 3 )
MA:LAWRENCE 1-131 NO DATA 2.72E-Ol
BA-140 NO DATA 1. 44E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 5.66E+OO
RUI03,106,BE7 NO DATA 5.76E+OO
ZR,NB-95 NO DATA 1.90E+OO
BI-214 NO DATA O.OOE-Ol
MASSACHUSETTS 1-131 6.50E+02 2.72E-Ol
BA-140 2.35E+02 1. 44E+OO
CS-137 1.97E+02 O.OOE-Ol
K-40 2.71E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.68E+02 NO DATA
LA-140 2.70E+02 NO DATA
CE-141,144 NO DATA 5.66E+OO
RUI03,106,BE7 NO DATA 5.76E+OO
ZR,NB-95 NO DATA 1.90E+OO
BI-214 NO DATA O.OOE-Ol
MD:BALT1MORE 1-131 4.87E+02 1. 55E+OO
BA-140 4.41E+Ol 3.21E+OO
CS-137 1.43E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.74E+02 NO DATA
LA-140 5.17E+Ol NO DATA
CE-141,144 NO DATA 6.66E+OO
RUI03,106,BE7 NO DATA 6.17E+OO
ZR,NB-95 NO DATA 5.04E-Ol
BI-214 NO DATA O.OOE-Ol
MARYLAND 1-131 4.87E+02 1.55E+OO
BA-140 4.41E+Ol 3.21E+OO
CS-137 1.43E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1. 74E+02 NO DATA
LA-140 5.17E+Ol NO DATA
CE-141,144 NO DATA 6.66E+OO
RUI03,106,BE7 NO DATA 6.17E+OO
ZR,NB-95 NO DATA 5.04E-Ol
BI-214 NO DATA O.OOE-Ol
77
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/rn**3)
ME:AUGUSTA 1-131 NO DATA 3.44E-Ol
BA-140 NO DATA 9.12E-Ol
CS-137 NO DATA 2.55E-03
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 4.70E+OO
RUI03,106,BE7 NO DATA 2.53E+OO
ZR,NB-95 NO DATA 1.43E+OO
BI-214 NO DATA 9.57E-02
ME:PORTLAND 1-131 4.81E+02 NO DATA
BA-140 1.16E+03 NO DATA
CS-137 O.OOE-Ol NO DATA
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.90E+02 NO DATA
LA-140 1.33E+03 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
MAINE 1-131 4.81E+02 3.44E-Ol
BA-140 1.16E+03 9.12E-Ol
CS-137 O.OOE-Ol 2.55E-03
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.90E+02 NO DATA
LA-140 1. 33E+03 NO DATA
CE-141,144 NO DATA 4.70E+OO
RUI03,106,BE7 NO DATA 2.53E+OO
ZR, NB-9 5 NO DATA 1.43E+OO
BI-214 NO DATA 9.57E-02
M1:DETROIT 1-131 1. 20E+03 NO DATA
BA-140 6.54E+02 NO DATA
CS-137 2.36E+02 NO DATA
K-40 O.OOE-Ol NO DATA
SR-90 8.44E+Ol NO DATA
SR-89 4.69E+02 NO DATA
LA-140 7.52E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
78
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/rn**3)
MI:GRAND RAPIDS 1-131 9.26E+02 NO DATA
BA-140 3.99E+02 NO DATA
CS-137 O.OOE-Ol NO DATA
K-40 1. 59E+O 3 NO DATA
SR-90 1. 38E+02 NO DATA
SR-89 6.78E+02 NO DATA
LA-140 4.60E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
MI:LANSING 1-131 NO DATA 7.48E-Ol
BA-140 NO DATA 2.84E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 1. 06E+Ol
RUI03,106,BE7 NO DATA 1.24E+Ol
ZR,NB-95 NO DATA 2.41E+OO
BI-214 NO DATA O.OOE-Ol
MICHIGAN 1-131 1. 06E+03 7.48E-Ol
BA-140 5.26E+02 2.84E+OO
CS-137 1.18E+02 O.OOE-Ol
K-40 7.95E+02 NO DATA
SR-90 1.11E+02 NO DATA
SR-89 5.73E+02 NO DATA
LA-140 6.06E+02 NO DATA
CE-141,144 NO DATA 1.06E+Ol
RUI03,106,BE7 NO DATA 1.24E+Ol
ZR,NB-95 NO DATA 2.41E+OO
BI-214 NO DATA O.OOE-Ol
MN:M1NNEAPOLIS 1-131 1. 68E+03 2.39E-Ol
BA-140 5.05E+02 1.60E+OO
CS-137 2.87E+02 8.94E-03
K-40 2.67E+03 NO DATA
SR-90 1.96E+02 NO DATA
SR-89 3.15E+02 NO DATA
LA-140 5.82E+02 NO DATA
CE-141,144 NO DATA 3.51E+OO
RUI03,106,BE7 NO DATA 3.84E+OO
ZR,NB-95 NO DATA 1.34E+OO
BI-214 NO DATA O.OOE-Ol
79
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
MINNESOTA 1-131 1.68E+03 2.39E-Ol
BA-140 5.05E+02 1.60E+OO
CS-137 2.87E+02 8.94E-03
K-40 2.67E+03 NO DATA
SR-90 1.96E+02 NO DATA
SR-89 3.15E+02 NO DATA
LA-140 5.82E+02 NO DATA
CE-141,144 NO DATA 3.51E+OO
RUI03,106,BE7 NO DATA 3.84E+OO
ZR,NB-95 NO DATA 1. 34E+OO
BI-214 NO DATA O.OOE-Ol
MO:JEFFERSON CI 1-131 NO DATA 4.25E-Ol
BA-140 NO DATA 2.73E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 6.36E+OO
RUI03,106,BE7 NO DATA 1.02E+Ol
ZR,NB-95 NO DATA 2.77E+OO
BI-214 NO DATA O.OOE-Ol
MO:KANSAS CITY 1-131 4.64E+02 NO DATA
BA-140 3.62E+02 NO DATA
CS-137 3.97E+Ol NO DATA
K-40 4.31E+02 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.70E+02 NO DATA
LA-140 4.17E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
MO:ST. LOUIS 1-131 7.50E+02 NO DATA
BA-140 5.34E+02 NO DATA
CS-137 O.OOE-Ol NO DATA
K-40 O.OOE-Ol NO DATA
SR-90 8.59E+Ol NO DATA
SR-89 4.16E+02 NO DATA
LA-140 6.14E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
80
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
MISSOURI 1-131 6.07E+02 4.25E-Ol
BA-140 4.48E+02 2.73E+00
CS-137 1. 98E+Ol O.OOE-Ol
K-40 2.15E+02 NO DATA
SR-90 4.29E+Ol NO DATA
SR-89 2.93E+02 NO DATA
LA-140 5.15E+02 NO DATA
CE-141,144 NO DATA 6.36E+00
RUI03,106,BE7 NO DATA 1.02E+Ol
ZR,NB-95 NO DATA 2.77E+00
BI-214 NO DATA O.OOE-Ol
MS:JACKSON 1-131 8.10E+02 6.05E-Ol
BA-140 7.26E+02 2.21E+00
CS-137 O.OOE-Ol O.OOE-Ol
K-40 2.10E+00 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 9.16E+02 NO DATA
LA-140 8.34E+02 NO DATA
CE-141,144 NO DATA 6.33E+00
RUI03,106,BE7 NO DATA 8.68E+00
ZR,NB-95 NO DATA 1.78E+00
BI-214 NO DATA O.OOE-Ol
MISSISSIPPI 1-131 8.10E+02 6.05E-Ol
BA-140 7.26E+02 2.21E+00
CS-137 O.OOE-Ol O.OOE-Ol
K-40 2.10E+00 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 9.16E+02 NO DATA
LA-140 8.34E+02 NO DATA
CE-141,144 NO DATA 6.33E+00
RUI03,106,BE7 NO DATA 8.68E+00
ZR,NB-95 NO DATA 1.78E+00
BI-214 NO DATA O.OOE-Ol
MT:HELENA 1-131 9.48E+02 6.92E-Ol
BA-140 4.18E+02 1. 97E+00
CS-137 2.30E+02 O.OOE-Ol
K-40 5.77E+Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.59E+02 NO DATA
LA-140 4.81E+02 NO DATA
CE-141,144 NO DATA 8.84E+00
RUI03,106,BE7 NO DATA 1.15E+Ol
ZR,NB-95 NO DATA 2.85E+00
BI-214 NO DATA 7.26E-03
81
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) ( pC i -d 1m * * 3 )
MONTANA 1-131 9.48E+02 6.92E-Ol
BA-140 4.18E+02 1. 97E+OO
C8-137 2.30E+02 O.OOE-Ol
K-40 5.77E+Ol NO DATA
8R-90 O.OOE-Ol NO DATA
8R-89 1.59E+02 NO DATA
LA-140 4.81E+02 NO DATA
CE-141,144 NO DATA 8.84E+OO
RUI03,106,BE7 NO DATA 1.15E+Ol
ZR,NB-95 NO DATA 2.85E+OO
BI-214 NO DATA 7.26E-03
NC:CHARLOTTE 1-131 4.68E+02 1.42E-Ol
BA-140 2.08E+02 9.19E-Ol
C8-137 2.49E+Ol O.OOE-Ol
K-40 O.OOE-Ol NO DATA
8R-90 O.OOE-Ol NO DATA
8R-89 2.22E+Ol NO DATA
LA-140 2.38E+02 NO DATA
CE-141,144 NO DATA O.OOE-Ol
RUI03,106,BE7 NO DATA 3.97E+OO
ZR,NB-95 NO DATA 9.61E-Ol
BI-214 NO DATA O.OOE-Ol
NC:WILMINGTON 1-131 NO DATA 1.68E-Ol
BA-140 NO DATA 1.12E+OO
C8-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
8R-90 NO DATA NO DATA
8R-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 4.95E+OO
RUI03,106,BE7 NO DATA 5.65E+OO
ZR,NB-95 NO DATA 9.59E-Ol
BI-214 NO DATA 2.20E-Ol
NORTH CAROLINA 1-131 4.68E+02 1. 55E-Ol
BA-140 2.08E+02 1. 01E+OO
C8-137 2.49E+Ol O.OOE-Ol
K-40 O.OOE-Ol NO DATA
8R-90 O.OOE-Ol NO DATA
8R-89 2.22E+Ol NO DATA
LA-140 2.38E+02 NO DATA
CE-141,144 NO DATA 2.47E+OO
RUI03,106,BE7 NO DATA 4.81E+OO
ZR,NB-95 NO DATA 9.60E-Ol
BI-214 NO DATA 1.10E-Ol
82
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
ND:B1SMARK 1-131 NO DATA 3.35E-Ol
BA-140 NO DATA 1. 75E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 8.07E+OO
RUI03,106,BE7 NO DATA 9.39E+OO
ZR,NB-95 NO DATA 2.73E+OO
BI-214 NO DATA 3.44E-02
ND:M1NOT 1-131 2.82E+02 NO DATA
BA-140 3.21E+02 NO DATA
CS-137 2.23E+02 NO DATA
K-40 O.OOE-Ol NO DATA
SR-90 3.85E+Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 3.69E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
NORTH DAKOTA 1-131 2.82E+02 3.35E-Ol
BA-140 3.21E+02 1. 75E+OO
CS-137 2.23E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 3.85E+Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 3.69E+02 NO DATA
CE-141,144 NO DATA 8.07E+OO
RUI03,106,BE7 NO DATA 9.39E+OO
ZR,NB-95 NO DATA 2.73E+OO
BI-214 NO DATA 3.44E-02
NE:L1NCOLN 1-131 NO DATA 2.47E-Ol
BA-140 NO DATA 2.32E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 9.26E+OO
RUI03,106,BE7 NO DATA 9.59E+OO
ZR,NB-95 NO DATA 2.13E+OO
BI-214 NO DATA O.OOE-Ol
83
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
NE:OMAHA I-131 3.10E+02 NO DATA
BA-140 5.48E+02 NO DATA
CS-137 9.89E+Ol NO DATA
K-40 1. 56E+04 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.85E+02 NO DATA
LA-140 6.30E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
NEBRASKA I-131 3.10E+02 2.47E-Ol
BA-140 5.48E+02 2.32E+OO
CS-137 9.89E+Ol O.OOE-Ol
K-40 1. 56E+04 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1. 85E+02 NO DATA
LA-140 6.30E+02 NO DATA
CE-141,144 NO DATA 9.26E+OO
RUI03,106,BE7 NO DATA 9.59E+OO
ZR,NB-95 NO DATA 2.13E+OO
BI-214 NO DATA O.OOE-Ol
NH:MANCHESTER I-131 5.65E+02 3.44E-Ol
BA-140 3.58E+02 9.12E-Ol
CS-137 1.68E+02 2.55E-03
K-40 1.22E+03 NO DATA
SR-90 1.19E+02 NO DATA
SR-89 8.63E+OO NO DATA
LA-140 4.12E+02 NO DATA
CE-141,144 NO DATA 4.70E+OO
RUI03,106,BE7 NO DATA 2.53E+OO
ZR,NB-95 NO DATA 1.43E+OO
BI-214 NO DATA 9.57E-02
NEW HAMPSHIRE I-131 5.65E+02 3.44E-Ol
BA-140 3.58E+02 9.12E-Ol
CS-137 1. 68E+02 2.55E-03
K-40 1.22E+03 NO DATA
SR-90 1.19E+02 NO DATA
SR-89 8.63E+OO NO DATA
LA-140 4.12E+02 NO DATA
CE-141,144 NO DATA 4.70E+OO
RUI03,106,BE7 NO DATA 2.53E+OO
ZR,NB-95 NO DATA 1.43E+OO
BI-214 NO DATA 9.57E-02
84
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-djliter) (pCi-djm**3)
NJ:TRENTON 1-131 6.98E+02 2.51E-Ol
BA-140 2.79E+02 1.60E+OO
CS-137 1.60E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.34E+02 NO DATA
LA-140 3.20E+02 NO DATA
CE-141,144 NO DATA 3.59E+OO
RUI03,106,BE7 NO DATA 5.28E+OO
ZR,NB-95 NO DATA 8.45E-Ol
BI-214 NO DATA O.OOE-Ol
NEW JERSEY 1-131 6.98E+02 2.51E-Ol
BA-140 2.79E+02 1.60E+OO
CS-137 1.60E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.34E+02 NO DATA
LA-140 3.20E+02 NO DATA
CE-141,144 NO DATA 3.59E+OO
RUI03,106,BE7 NO DATA 5.28E+OO
ZR,NB-95 NO DATA 8.45E-Ol
BI-214 NO DATA O.OOE-Ol
NM:ALBUQUERQUE 1-131 3.10E+02 NO DATA
BA-140 1.94E+02 NO DATA
CS-137 O.OOE-Ol NO DATA
K-40 O.OOE-Ol NO DATA
SR-90 2.19E+Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 2.22E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
NM:SANTA FE 1-131 NO DATA O.OOE-Ol
BA-140 NO DATA 1.66E+Ol
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 4.89E+Ol
RUI03,106,BE7 NO DATA 8.44E+Ol
ZR,NB-95 NO DATA 1.51E+Ol
BI-214 NO DATA 3.89E+Ol
85
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/1iter) (pCi-d/m**3)
NEW MEXICO 1-131 3.10E+02 O.OOE-01
BA-140 1.94E+02 1.66E+01
CS-137 O.OOE-01 O.OOE-01
K-40 O.OOE-01 NO DATA
SR-90 2.19E+01 NO DATA
SR-89 O.OOE-01 NO DATA
LA-140 2.22E+02 NO DATA
CE-141,144 NO DATA 4.89E+01
RU103,106,BE7 NO DATA 8.44E+01
ZR,NB-95 NO DATA 1. 51E+01
BI-214 NO DATA 3.89E+01
NV:LAS VEGAS 1-131 1.18E+02 9.70E+OO
BA-140 6.06E+01 2.03E+01
CS-137 1.71E+01 O.OOE-01
K-40 O.OOE-01 NO DATA
SR-90 1.OOE-01 NO DATA
SR-89 3.00E+OO NO DATA
LA-140 7.00E+01 NO DATA
CE-141,144 NO DATA 5.06E+01
RU103,106,BE7 NO DATA 6.13E+01
ZR,NB-95 NO DATA 1. 50E+01
BI-214 NO DATA O.OOE-01
NEVADA 1-131 1.18E+02 9.70E+OO
BA-140 6.06E+01 2.03E+01
CS-137 1. 71E+01 O.OOE-01
K-40 O.OOE-01 NO DATA
SR-90 1.OOE-01 NO DATA
SR-89 3.00E+OO NO DATA
LA-140 7.00E+01 NO DATA
CE-141,144 NO DATA 5.06E+01
RU103,106,BE7 NO DATA 6.13E+01
ZR,NB-95 NO DATA 1. 50E+01
BI-214 NO DATA O.OOE-01
NY:ALBANY 1-131 NO DATA 5.44E-01
BA-140 NO DATA 1.28E+OO
CS-137 NO DATA O.OOE-01
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 2.90E+OO
RU103,106,BE7 NO DATA 3.01E+OO
ZR,NB-95 NO DATA 7.55E-01
81-214 NO DATA O.OOE-01
86
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pC i-d/rn* * 3)
NY:BUFFALO 1-131 8.84E+02 NO DATA
BA-140 2.53E+02 NO DATA
C8-137 3.64E+02 NO DATA
K-40 O.OOE-Ol NO DATA
8R-90 4.90E+Ol NO DATA
8R-89 4.16E+02 NO DATA
LA-140 2.92E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
B1-214 NO DATA NO DATA
NY:NEW YORK 1-131 l.03E+03 2.78E-01
BA-140 6.45E+02 l.61E+OO
C8-137 2.23E+02 O.OOE-01
K-40 O.OOE-Ol NO DATA
8R-90 O.OOE-Ol NO DATA
8R-89 5.33E+02 NO DATA
LA-140 7.42E+02 NO DATA
CE-141,144 NO DATA 6.36E+OO
RU103,106,BE7 NO DATA 8.27E+OO
ZR,NB-95 NO DATA l.86E+OO
B1-214 NO DATA O.OOE-OO
NY:N1AGARA FALL 1-131 NO DATA O.OOE-Ol
BA-140 NO DATA 1.61E+OO
C8-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
8R-90 NO DATA NO DATA
8R-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 2.71E+OO
RUI03,106,BE7 NO DATA 6.52E+OO
ZR,NB-95 NO DATA 2.03E+OO
B1-214 NO DATA O.OOE-OO
NY:8YRACU8E 1-131 6.95E+02 5.08E-01
BA-140 2.44E+02 1.68E+OO
C8-137 1.48E+02 O.OOE-Ol
K-40 3.80E+03 NO DATA
8R-90 6.36E+01 NO DATA
SR-89 l.44E+02 NO DATA
LA-140 2.82E+02 NO DATA
CE-141,144 NO DATA 4.38E+OO
RUI03,106,BE7 NO DATA 5.39E+OO
ZR,NB-95 NO DATA 1. 38E+OO
B1-214 NO DATA O.OOE-Ol
87
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-djliter) (pCi-djrn**3)
NEW YORK 1-131 8.69E+02 3.32E-Ol
BA-140 3.80E+02 1.54E+OO
CS-137 2.45E+02 O.OOE-Ol
K-40 1. 26E+03 NO DATA
SR-90 3.75E+Ol NO DATA
SR-89 3.64E+02 NO DATA
LA-140 4.38E+02 NO DATA
CE-141,144 NO DATA 4.08E+OO
RUI03,106,BE7 NO DATA 5.79E+OO
ZR,NB-95 NO DATA 1. 50E+O 0
B1-214 NO DATA O.OOE-OO
OH:C1NC1NNAT1 1-131 9.20E+02 NO DATA
BA-140 3.77E+02 NO DATA
CS-137 8.79E+Ol NO DATA
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 3.99E+02 NO DATA
LA-140 4.34E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
B1-214 NO DATA NO DATA
OH:CLEVELAND 1-131 7.79E+02 NO DATA
BA-140 2.53E+02 NO DATA
CS-137 2.57E+02 NO DATA
K-40 6.26E+02 NO DATA
SR-90 5.47E+Ol NO DATA
SR-89 1. 66E+02 NO DATA
LA-140 2.91E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
B1-214 NO DATA NO DATA
OH:COLUMBUS 1-131 NO DATA 6.29E-Ol
BA-140 NO DATA 2.10E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 1.17E+Ol
RUI03,106,BE7 NO DATA 1.27E+Ol
ZR,NB-95 NO DATA 3.21E+OO
B1-214 NO DATA O.OOE-Ol
88
-------
TABLE A2 (Continued)
Location Pathway
Nuclide Milk Air
(pCi-d/liter) (pCi-d/rn**3)
OH:PAINESVILLE 1-131 NO DATA 8.99E-Ol
BA-140 NO DATA 1.82E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 7.48E+OO
RUI03,106,BE7 NO DATA 6.89E+OO
ZR,NB-95 NO DATA 1. 56E+OO
BI-214 NO DATA 1.17E-02
OHIO 1-131 8.49E+02 7.64E-Ol
BA-140 3.15E+02 1. 96E+OO
CS-137 1. 72E+02 O.OOE-Ol
K-40 3.13E+02 NO DATA
SR-90 2.73E+Ol NO DATA
SR-89 2.82E+02 NO DATA
LA-140 3.62E+02 NO DATA
CE-141,144 NO DATA 9.59E+OO
RUI03,106,BE7 NO DATA 9.79E+OO
ZR,NB-95 NO DATA 2.38E+OO
BI-214 NO DATA 5.85E-03
OK:OKLAHOMA CITY 1-131 1.05E+02 4.78E-Ol
BA-140 6.89E+Ol 1.80E+OO
CS-137 1.68E+02 O.OOE-Ol
K-40 6.81E+03 NO DATA
SR-90 9.97E+Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 7.78E+Ol NO DATA
CE-141,144 NO DATA 5.56E+OO
RUI03,106,BE7 NO DATA 7.78E+OO
ZR,NB-95 NO DATA 1.83E+OO
BI-214 NO DATA O.OOE-Ol
OKLAHOMA 1-131 1.05E+02 4.78E-Ol
BA-140 6.89E+Ol 1.80E+OO
CS-137 1.68E+02 O.OOE-Ol
K-40 6.81E+03 NO DATA
SR-90 9.97E+Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 7.78E+Ol NO DATA
CE-141,144 NO DATA 5.56E+OO
RUI03,106,BE7 NO DATA 7.78E+OO
ZR,NB-95 NO DATA 1.83E+OO
B1-214 NO DATA O.OOE-Ol
89
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-djliter) (pCi-djm**3)
OR: PORTLAND I-131 4.39E+02 1.25E-Ol
BA-140 6.30E+02 9.65E-Ol
CS-137 5.44E+OO 2.00E-02
K-40 O.OOE-01 NO DATA
SR-90 5.29E+01 NO DATA
SR-89 2.09E+02 NO DATA
LA-140 7.25E+02 NO DATA
CE-141,144 NO DATA 3.58E+OO
RUI03,106,BE7 NO DATA 5.70E+OO
ZR,NB-95 NO DATA 1.63E+OO
BI-214 NO DATA l.89E-Ol
OREGON I-131 4.39E+02 l.25E-Ol
BA-140 6.30E+02 9.65E-01
CS-137 5.44E+OO 2.00E-02
K-40 O.OOE-01 NO DATA
SR-90 5.29E+01 NO DATA
SR-89 2.09E+02 NO DATA
LA-140 7.25E+02 NO DATA
CE-141,144 NO DATA 3.58E+OO
RU103,106,BE7 NO DATA 5.70E+OO
ZR,NB-95 NO DATA 1. 63E+OO
BI-214 NO DATA 1.89E-01
PA:HARRISBURG I-131 NO DATA 5.41E-Ol
BA-140 NO DATA 2.41E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 7.17E+OO
RUI03,106,BE7 NO DATA 9.47E+OO
ZR,NB-95 NO DATA 2.44E+OO
BI-214 NO DATA O.OOE-01
PA:PHILADELPHIA I-131 6.35E+02 NO DATA
BA-140 O.OOE-01 NO DATA
CS-137 l.83E+02 NO DATA
K-40 1.10E+03 NO DATA
SR-90 O.OOE-01 NO DATA
SR-89 1.13E+02 NO DATA
LA-140 O.OOE-Ol NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
90
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
PA:PITTSBURGH I-131 7.72E+02 O.OOE-Ol
BA-140 1.30E+02 1. 74E+Ol
CS-137 4.04E+02 2.28E-Ol
K-40 5.02E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 3.17E+02 NO DATA
LA-140 1. 50E+02 NO DATA
CE-141,144 NO DATA O.OOE-Ol
RUI03,106,BE7 NO DATA O.OOE-Ol
ZR,NB-95 NO DATA 2.00E+OO
BI-214 NO DATA 1.83E+Ol
PENNSYLVANIA I-131 7.03E+02 2.70E-Ol
BA-140 6.50E+Ol 9.90E+OO
CS-137 2.93E+02 1.14E-Ol
K-40 3.06E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.15E+02 NO DATA
LA-140 7.50E+Ol NO DATA
CE-141,144 NO DATA 3.58E+OO
RUI03,106,BE7 NO DATA 4.73E+OO
ZR,NB-95 NO DATA 2.22E+OO
BI-214 NO DATA 9.15E+OO
RI:PROVIDENCE I-131 6.19E+02 4.04E-Ol
BA-140 5.31E+02 1.23E+OO
CS-137 1.01E+02 O.OOE-Ol
K-40 5.62E+02 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 5.22E+02 NO DATA
LA-140 6.11E+02 NO DATA
CE-141,144 NO DATA 4.79E+OO
RUI03,106,BE7 NO DATA 5.44E+OO
ZR,NB-95 NO DATA 1.19E+OO
BI-214 NO DATA O.OOE-Ol
RHODE ISLAND I-131 6.19E+02 4.04E-Ol
BA-140 5.31E+02 1.23E+OO
CS-137 1. OlE+02 O.OOE-Ol
K-40 5.62E+02 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 5.22E+02 NO DATA
LA-140 6.11E+02 NO DATA
CE-141,144 NO DATA 4.79E+OO
RUI03,106,BE7 NO DATA 5.44E+OO
ZR,NB-95 NO DATA 1.19E+OO
BI-214 NO DATA O.OOE-Ol
91
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) ( pC i -d 1m * * 3 )
SC:CHARLESTON 1-131 5.65E+02 NO DATA
BA-140 4.07E+02 NO DATA
CS-137 O.OOE-Ol NO DATA
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 5.86E+Ol NO DATA
LA-140 4.68E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
SC:COLUMBIA 1-131 NO DATA 1.33E+OO
BA-140 NO DATA 4.36E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 2.19E+Ol
RUI03,106,BE7 NO DATA 2.08E+Ol
ZR,NB-95 NO DATA 4.09E+OO
BI-214 NO DATA O.OOE-Ol
SOUTH CAROLINA 1-131 5.65E+02 1.33E+OO
BA-140 4.07E+02 4.36E+OO
CS-137 O.OOE-Ol O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 5.86E+Ol NO DATA
LA-140 4.68E+02 NO DATA
CE-141,144 NO DATA 2.19E+Ol
RUI03,106,BE7 NO DATA 2.08E+Ol
ZR,NB-95 NO DATA 4.09E+OO
BI-214 NO DATA O.OOE-Ol
SD:PIERRE 1-131 NO DATA 9.03E-Ol
BA-140 NO DATA 2.14E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 1.56E+Ol
RUI03,106,BE7 NO DATA 9.22E+OO
ZR,NB-95 NO DATA 2.47E+OO
BI-214 NO DATA O.OOE-Ol
92
-------
TABLE A2 (Continued)
Location Pathway
Nuclide Milk Air
(pCi-djliter) (pCi-djrn**3)
SD:RAPID CITY 1-131 6.60E+02 NO DATA
BA-140 7.21E+02 NO DATA
CS-137 3.58E+Ol NO DATA
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.77E+02 NO DATA
LA-140 8.28E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
SOUTH DAKOTA 1-131 6.60E+02 9.03E-Ol
BA-140 7.21E+02 2.14E+OO
CS-137 3.58E+Ol O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.77E+02 NO DATA
LA-140 8.28E+02 NO DATA
CE-141,144 NO DATA 1.56E+Ol
RUI03,106,BE7 NO DATA 9.22E+OO
ZR,NB-95 NO DATA 2.47E+OO
BI-214 NO DATA O.OOE-Ol
TN: CHATTANOOGA 1-131 3.76E+02 NO DATA
BA-140 9.85E+OO NO DATA
CS-137 2.53E+02 NO DATA
K-40 2.49E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 3.59E+02 NO DATA
LA-140 9.95E+OO NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
TN:KNOXVILLE 1-131 8.61E+02 NO DATA
BA-140 5.75E+02 NO DATA
CS-137 2.64E+02 NO DATA
K-40 1.41E+03 NO DATA
SR-90 1.51E+02 NO DATA
SR-89 9.70E+Ol NO DATA
LA-140 6.62E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
93
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/rn**3)
TN:MEMPHIS 1-131 1.00E+03 NO DATA
BA-140 9.89E+02 NO DATA
CS-137 1. 64E+02 NO DATA
K-40 1.29E+03 NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.14E+03 NO DATA
LA-140 1. 14 E+ 0 3 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
TN:NASHVILLE 1-131 NO DATA 8.10E-Ol
BA-140 NO DATA 2.04E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 1.10E+Ol
RUI03,106,BE7 NO DATA 7.43E+OO
ZR,NB-95 NO DATA 1. 43E+OO
BI-214 NO DATA O.OOE-Ol
TENNESSEE 1-131 7.45E+02 8.10E-Ol
BA-140 5.24E+02 2.04E+OO
CS-137 2.27E+02 O.OOE-Ol
K-40 1.73E+03 NO DATA
SR-90 5.03E+Ol NO DATA
SR-89 5.32E+02 NO DATA
LA-140 6.03E+02 NO DATA
CE-141,144 NO DATA 1.10E+Ol
RUI03,106,BE7 NO DATA 7.43E+OO
ZR,NB-95 NO DATA 1.43E+OO
BI-214 NO DATA O.OOE-Ol
TX:AUSTIN 1-131 3.09E+Ol 9.00E-02
BA-140 2.70E+02 1. 23E+OO
CS-137 O.OOE-Ol O.OOE-Ol
K-40 1.85E+03 NO DATA
SR-90 1. OOE+OO NO DATA
SR-89 1.OOE+OO NO DATA
LA-140 3.13E+02 NO DATA
CE-141,144 NO DATA 5.54E+OO
RUI03,106,BE7 NO DATA 7.52E+OO
ZR,NB-95 NO DATA 2.03E+OO
BI-214 NO DATA O.OOE-Ol
94
-------
TABLE A2 (Continued)
Location
TX:DALLAS
TX:EL PASO
TEXAS
UT:SALT LAKE CITY
Nuclide
1-131
BA-140
CS-137
K-40
SR-90
SR-89
LA-140
CE-141,144
RUI03,106,BE7
ZR,NB-95
BI-214
1-131
BA-140
CS-137
K-40
SR-90
SR-89
LA-140
CE-141,144
RUI03,106,BE7
ZR,NB-95
BI-214
1-131
BA-140
CS-137
K-40
SR-90
SR-89
LA-140
CE-141,144
RU103,106,BE7
ZR,NB-95
B1-214
1-131
BA-140
CS-137
K-40
SR-90
SR-89
LA-140
CE-141,144
RUI03,106,BE7
ZR,NB-95
BI-214
Milk
(pCi-d/liter)
4.82E+02
1.45E+02
1. 66E+Ol
O.OOE-01
3.07E+OO
3.07E+01
1. 67E+02
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
2.56E+02
2.07E+02
8.30E+OO
9.25E+02
2.03E+OO
1. 58E+01
2.40E+02
NO DATA
NO DATA
NO DATA
NO DATA
1.22E+03
6.45E+02
1.89E+02
1.40E+03
O.OOE-01
1.47E+02
7.41E+02
NO DATA
NO DATA
NO DATA
NO DATA
Pathway
Air
(pCi-d/m**3)
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
NO DATA
4.18E-01
O.OOE-01
2.91E-01
NO DATA
NO DATA
NO DATA
NO DATA
O.OOE-01
O.OOE-Ol
O.OOE-01
O.OOE-Ol
2.54E-Ol
6.15E-01
1.45E-Ol
NO DATA
NO DATA
NO DATA
NO DATA
2.77E+OO
3.76E+OO
1. OlE+OO
O.OOE-Ol
4.22E+OO
1.19E+Ol
O.OOE-01
NO DATA
NO DATA
NO DATA
NO DATA
2.56E+Ol
3.14E+01
7.58E+OO
O.OOE-Ol
95
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pCi-d/m**3)
UTAH 1-131 1.22E+03 4.22E+OO
BA-140 6.45E+02 1.19E+01
C8-137 1. 89E+02 O.OOE-Ol
K-40 1. 40E+03 NO DATA
8R-90 O.OOE-Ol NO DATA
8R-89 1.47E+02 NO DATA
LA-140 7.41E+02 NO DATA
CE-141,144 NO DATA 2.56E+Ol
RUI03,106,BE7 NO DATA 3.14E+Ol
ZR,NB-95 NO DATA 7.58E+OO
BI-214 NO DATA O.OOE-Ol
VA:LYNCHBURG 1-131 NO DATA 7.89E-Ol
BA-140 NO DATA 2.47E+OO
C8-137 NO DATA O.OOE-01
K-40 NO DATA NO DATA
8R-90 NO DATA NO DATA
8R-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 1.lOE+Ol
RUI03,106,BE7 NO DATA 1.15E+Ol
ZR,NB-95 NO DATA 2.22E+OO
BI-214 NO DATA O.OOE-Ol
VA:NORFOLK 1-131 1.79E+02 2.67E-Ol
BA-140 1. 83E+02 O.OOE-Ol
C8-137 O.OOE-Ol 1. 58E-Ol
K-40 2.50E+03 NO DATA
8R-90 2.27E+Ol NO DATA
8R-89 O.OOE-Ol NO DATA
LA-140 2.11E+02 NO DATA
CE-141,144 NO DATA O.OOE-Ol
RUI03,106,BE7 NO DATA O.OOE-Ol
ZR,NB-95 NO DATA 3.85E-Ol
BI-214 NO DATA O.OOE-Ol
VIRGINIA 1-131 1.79E+02 5.28E-Ol
BA-140 1.83E+02 1.23E+OO
C8-137 O.OOE-Ol 7.90E-02
K-40 2.50E+03 NO DATA
8R-90 2.27E+Ol NO DATA
8R-89 O.OOE-Ol NO DATA
LA-140 2.11E+02 NO DATA
CE-141,144 NO DATA 5.50E+OO
RUI03,106,BE7 NO DATA 5.75E+OO
ZR,NB-95 NO DATA 1.30E+OO
BI-214 NO DATA O.OOE-Ol
96
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pC i-d/rn* * 3)
VT:BURL1NGTON 1-131 1. 58E+02 3.44E-Ol
BA-140 7.25E+02 9.12E-Ol
CS-137 1.54E+02 2.55E-03
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.52E+02 NO DATA
LA-140 8.34E+02 NO DATA
CE-141,144 NO DATA 4.70E+OO
RUI03,106,BE7 NO DATA 2.53E+OO
ZR,NB-95 NO DATA 1.43E+OO
BI-214 NO DATA 9.57E-02
VERMONT 1-131 1.58E+02 3.44E-Ol
BA-140 7.25E+02 9.12E-Ol
CS-137 1.54E+02 2.55E-03
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 2.52E+02 NO DATA
LA-140 8.34E+02 NO DATA
CE-141,144 NO DATA 4.70E+OO
RUI03,106,BE7 NO DATA 2.53E+OO
ZR,NB-95 NO DATA 1.43E+OO
BI-214 NO DATA 9.57E-02
WA:SEATTLE 1-131 3.78E+02 1. 21E-Ol
BA-140 2.22E+02 7.94E-Ol
CS-137 4.54E+Ol 1. 38E-02
K-40 1.64E+03 NO DATA
SR-90 4.24E+Ol NO DATA
SR-89 O.OOE-Ol NO DATA
LA-140 2.56E+02 NO DATA
CE-141,144 NO DATA 3.21E+OO
RUI03,106,BE7 NO DATA 3.23E+OO
ZR, NB-9 5 NO DATA 1.16E+OO
BI-214 NO DATA 9.25E-02
WA:SPOKANE 1-131 1.18E+02 2.76E-Ol
BA-140 2.37E+02 6.11E-Ol
CS-137 2.11E+02 4.85E-03
K-40 1.95E+03 NO DATA
SR-90 3.90E+OO NO DATA
SR-89 4.00E+OO NO DATA
LA-140 2.73E+02 NO DATA
CE-141,144 NO DATA 3.90E+OO
RUI03,106,BE7 NO DATA 3.58E+OO
ZR,NB-95 NO DATA 9.16E-Ol
BI-214 NO DATA 8.15E-02
97
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) (pC i-d/rn* * 3)
WASHINGTON 1-131 2.48E+02 1.98E-Ol
BA-140 2.29E+02 7.02E-Ol
CS-137 1. 28E+02 9.32E-03
K-40 1.79E+03 NO DATA
SR-90 2.31E+Ol NO DATA
SR-89 2.00E+OO NO DATA
LA-140 2.64E+02 NO DATA
CE-141,144 NO DATA 3.55E+OO
RUI03,106,BE7 NO DATA 3.40E+OO
ZR,NB-95 NO DATA 1.03E+OO
BI-214 NO DATA 8.70E-02
WI:MADISON 1-131 NO DATA 4.61E-Ol
BA-140 NO DATA 1.70E+OO
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 6.60E+OO
RUI03,106,BE7 NO DATA 7.73E+OO
ZR,NB-95 NO DATA 2.06E+OO
BI-214 NO DATA O.OOE-Ol
WI:MILWAUKEE 1-131 1.30E+03 NO DATA
BA-140 4.86E+02 NO DATA
CS-137 9.06E+Ol NO DATA
K-40 8.58E+02 NO DATA
SR-90 3.45E+Ol NO DATA
SR-89 6.79E+02 NO DATA
LA-140 5.59E+02 NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
81-214 NO DATA NO DATA
WISCONSIN 1-131 1. 30E+03 4.61E-Ol
BA-140 4.86E+02 1.70E+OO
CS-137 9.06E+Ol O.OOE-Ol
K-40 8.58E+02 NO DATA
SR-90 3.45E+Ol NO DATA
SR-89 6.79E+02 NO DATA
LA-140 5.59E+02 NO DATA
CE-141,144 NO DATA 6.60E+OO
RUI03,106,BE7 NO DATA 7.73E+OO
ZR,N8-95 NO DATA 2.06E+OO
81-214 NO DATA O.OOE-Ol
98
-------
TABLE A2 (Continued)
Pathway
Location Nuclide Milk Air
(pCi-d/liter) ( pC i -d 1m * * 3 )
WV:CHARLESTON 1-131 7.66E+02 6.29E-Ol
BA-140 1.14E+02 2.10E+OO
CS-137 1. 50E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1.71E+02 NO DATA
LA-140 1.31E+02 NO DATA
CE-141,144 NO DATA 1.17E+Ol
RUI03,106,BE7 NO DATA 1.27E+Ol
ZR,NB-95 NO DATA 3.21E+OO
BI-214 NO DATA O.OOE-Ol
WEST VIRGINIA 1-131 7.66E+02 6.29E-Ol
BA-140 1.14E+02 2.10E+OO
CS-137 1. 50E+02 O.OOE-Ol
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 1. 71E+02 NO DATA
LA-140 1. 31E+02 NO DATA
CE-141,144 NO DATA 1.17E+Ol
RUI03,106,BE7 NO DATA 1. 27E+Ol
ZR,NB-95 NO DATA 3.21E+OO
BI-214 NO DATA O.OOE-Ol
WY:CHEYENNE 1-131 NO DATA 8.36E+OO
BA-140 NO DATA 1.72E+Ol
CS-137 NO DATA O.OOE-Ol
K-40 NO DATA NO DATA
SR-90 NO DATA NO DATA
SR-89 NO DATA NO DATA
LA-140 NO DATA NO DATA
CE-141,144 NO DATA 3.98E+Ol
RUI03,106,BE7 NO DATA 4.63E+Ol
ZR,NB-95 NO DATA 8.90E+OO
BI-214 NO DATA O.OOE-Ol
WY:LARAMIE 1-131 O.OOE-Ol NO DATA
BA-140 O.OOE-Ol NO DATA
CS-137 2.57E+OO NO DATA
K-40 O.OOE-Ol NO DATA
SR-90 O.OOE-Ol NO DATA
SR-89 5.66E+Ol NO DATA
LA-140 O.OOE-Ol NO DATA
CE-141,144 NO DATA NO DATA
RUI03,106,BE7 NO DATA NO DATA
ZR,NB-95 NO DATA NO DATA
BI-214 NO DATA NO DATA
99
-------
TABLE A2 (Continued)
Pathway
Location
Nuclide
Milk
(pCi-d/liter)
Air
( pC i -d 1m * * 3 )
WYOMING
1-131
BA-140
CS-137
K-40
SR-90
SR-89
LA-140
CE-141,144
RUI03,106,BE7
ZR,NB-95
BI-214
O.OOE-Ol
O.OOE-Ol
2.57E+OO
O.OOE-Ol
O.OOE-Ol
5.66E+Ol
O.OOE-Ol
NO DATA
NO DATA
NO DATA
NO DATA
8.36E+OO
1.72E+Ol
O.OOE-Ol
NO DATA
NO DATA
NO DATA
NO DATA
3.98E+Ol
4.63E+Ol
8.90E+OO
O.OOE-Ol
100
-------
TABLE A3
Indivldual dose (mrem) as a function of state, age 9 rou p, and 0 ("g a n
Organ
State Age Bone LIver T. Body Thyroid Kidney Lung Gl Lli Skin
ALASKA INFANT 3.69E+00 9.22E-Ol 7.43E-Ol 2.05E+Ol 8.31E-Ol 8.74E-01 1.25E-01 7.43E-Ol
CHILD 1.82E+00 4.53E-Ol 3.86E-01 4.55E+00 4.26E-Ol 6.47E-Ol 8.00E-02 3.86E-Ol
TEEN 7.03E-Ol 1. 81£-01 1.52E-Ol 1.64E+00 1.74E-Ol 4 . 0 7 E- 0 1 7.55E-02 1.52E-Ol
ADULT 4.49E-Ol 1. 20E-Ol 9.86E-02 8.33E-Ol 1.11E-Ol 2.65E-Ol 5.68E-02 9.88E-02
ALABAMA INFANT 1.31E+00 7.92E-02 5.15E-02 5.42E+00 7.26E-02 5.64E-01 1.19E-01 5.23E-02
CHILD 6.07E-Ol 8.58E-02 2.77E-02 1.18E+00 6.62E-02 1.08E+00 9.82E-02 2.85E-02
TEEN 2.46£-01 6.31E-02 1.27E-02 4.39E-Ol 4.87£-02 1.04E+00 1.18E-Ol 1.35E-02
ADULT 1.64E-01 4.90E-02 8.93E-03 2.28E-Ol 3.69E-02 6.91E-Ol 1.05E-01 9.69E-03
ARKANS.~S INFANT 2.93E+00 2.37E-Ol 1.09E-Ol 8.56E+00 1.57E-Ol 5.50E-Ol 1.85E-01 1.10E-Ol
CHILD 1.11E+00 1.35E-Ol 4.77E-02 1.87E+00 9.37E-02 9.50E-Ol 1.33E-Ol 4.84E-02
TEEN 3.86E-01 8.21E-02 2.12E-02 6.90E-Ol 5.79E-02 9.04E-01 1.41E-Ol 2.19E-02
ADULT 2.36E-01 5.95E-02 1.51E-02 3.58E-01 4.14E-02 5.97E-Ol 1.17E-01 1.58E-02
ARI ZONA INFANT 3.22E-Ol 7.54E-02 2.22E-02 3.47E+00 5.11E-02 1.16E+00 8.94E-02 2.39E-02
CHILD 6.14E-Ol 1.79E-01 3.62E-02 9.00E-01 1.20E-Ol 2.37E+00 1.17E-01 3.79E-02
TEEN 3.68E-01 1.46E-01 2.19E-02 3.96E-01 1.05E-Ol 2.30E+00 1.79E-01 2.37E-02
ADULT 2.88E-01 1.16E-Ol 1. 72E-02 2.53E-01 8.23E-02 1.53E+00 1.78E-01 1.89E-02
CALIFORNIA INFANT 5.25E-01 1.94E-01 7.87E-02 1.35E+00 1.09E-01 6.09E-01 8.52E-02 7.95E-02
CHILD 4.44E-01 1.40E-Ol 5. 27E-02 3.42E-01 9.46E-02 1.13E+00 7.96E-02 5.34E-02
TEEN 2.25E-01 8.79E-02 2.61E-02 1.40E-01 6.25E-02 1.08E+00 1.04E-01 2.69E-02
ADULT 1.65E-Ol 6.48E-02 1.93E-02 8.32E-02 4.64E-02 7.11£-01 9.59E-02 2.01E-02
COLORADO INFANT 1. 66E+00 6.50E-Ol 3.08E-Ol 6.98E+00 4.24E-Ol 2.98E+00 1.03E-Ol 3.12E-01
CHILD 2.08E+00 6.58E-Ol 2.31E-Ol 2.04E+00 4.54E-Ol 5.67E+00 2.13E-Ol 2.35E-01
TEEN 1.15E+00 4.54E-Ol 1.15E-Ol 9.51E-Ol 3.22E-01 5.44E+00 3.70E-01 1.19E-01
ADULT 8.74E-01 3.47E-01 8.44E-02 6.46E-Ol 2.44E-Ol 3.60E+00 3.84E-01 8.85E-02
CONNECTICUT INFANT 9.37E-01 1.03E-Ol 3.78E-02 3.27E+00 5.76E-02 1.38E-Ol 9.44E-02 3.80E-02
CHILD 3.12E-01 3.75E-02 1.46E-02 7.08E-Ol 2.50E-02 2.21E-Ol 6.07E-02 1.47E-02
TEEN 9.47E-02 1.74E-02 6.63E-03 2.60E-Ol 1.25E-02 2.08E-O) 5.71E-02 6.78E-03
ADULT 5.21E-02 1.09E-02 4.89E-03 1. 34E-Ol 8.08E-03 1.38E-Ol 4.32E-02 5.03E-03
D.C. INFANT 1.02E+00 3.34E-01 2.33E-Ol 6.00E+00 2.70E-Ol 4.71E-Ol 6.77E-02 2.34E-Ol
CHILD 6.21E-Ol 1.83E-01 1.28E-Ol 1.40E+00 1.56E-01 6.10E-Ol 5.31E-02 1.28E-Ol
TEEN 2.70E-01 8.86E-02 5.28E-02 5.38E-01 7.34E-02 5.24E-01 6.11E-02 5.32E-02
ADULT 1.84E-01 6.03E-02 3.54E-02 2.97E-Ol 4.94E-02 3.45E-Ol 5.30E-02 3.58E-02
DELAWARE INFANT 7.38E-01 3.47E-01 4.87E-02 5.59E+00 1. 23E-01 2.30E-Ol 1.20E-Ol 4.89E-02
CHILD 2.95E-Ol 1.19E-Ol 2.52E-02 1.21E+00 5.56E-02 3.78E-Ol 8.00E-02 2.54E-02
TEEN 1.03E-01 5.42E-02 1 .7 2E- 0 2 4.53E-01 2.89E-02 3.59E-Ol 7.83E-02 1.75E-02
ADULT 6.32E-02 3.24E-02 1. 51E-02 2.38E-Ol 1.83E-02 2. 37E-Ol 6.10E-02 1.54E-02
FLORIDA INFANT 1.21E+00 3.20E-Ol 2.63E-Ol 4.74E+00 2.95E-Ol 1.24E+00 8.36E-02 2.65E-Ol
CHILD 1.10E+00 3.07E-Ol 1.64E-Ol 1.19E+00 2.45E-Ol 2.15E+00 1.04E-Ol 1.65E-Ol
TEEN 5.61E-Ol 1. 95E-Ol 7.08E-02 4.77E-01 1.50E-Ol 2.02E+00 1.57E-01 7.23E-02
ADULT 4.12E-Ol 1.47E-01 4.82E-02 2.79E-Ol 1.11E-Ol 1.34E+00 1. 55E-Ol 4.97E-02
101
-------
TABLE A3 (ContInued)
Orga n
State Age Bone Live r T. Body Thyroid Kidney Lung Gi - Lli Skin
GEORGIA INFANT 8.79E-01 1.55E-01 9.93E-02 2.46E+00 1.28E-01 1. 46E+00 1.09E-01 1.0lE-01
CHILD 9.07E-01 2.37E-01 7.90E-02 7.89E-01 1. 73E-01 2.85E+00 1.41E-01 8.10E-02
TEEN 4.89E-01 1.77E-01 3.92E-02 3.94E-01 1.32E-01 2.75E+00 2.15E-01 4.12E-02
ADULT 3.69E-01 1.39E-01 2.85E-02 2.83E-01 1.02E-01 1.82E+00 2.13E-01 3.05E-02
HAWAII INFANT 4.37E-01 7.33E-02 2.07E-02 2.46E+00 4.13E-02 5.64E-01 4.10E-02 2.15E-02
CHILD 1.67E-01 2.95E-02 1.04E-02 6.39E-01 3.0lE-02 1.11E+00 5.38E-02 1.11E-02
TEEN 5.84E-02 1.50E-02 5.77E-03 2.85E-01 2.08E-02 1.08E+00 8.26E-02 6.53E-03
ADULT 3.58E-02 9.95E-03 4.62E-03 1. 85E-01 1.54E-02 7.17E-01 8.21E-02 5.37E-03
IOWA INFANT 2.06E+00 2.52E-01 9.25E-02 1.45E+01 1.64E-01 3.34E-01 8.56E-02 9.28E-02
CHILD 7.33E-01 1.0ZE-01 3.68E-02 3.09E+00 7.47E-02 5.23E-01 6.32E-02 '3.72E-02
TEEN 2.38E-01 5.27E-02 1.67E-02 1.12E+00 3.92E-02 4.91E-01 6.94E-02 1.70E-02
ADULT 1.38E-01 3.51E-02 1.20E-02 5.62E-01 2.57E-02 3.24E-01 5.83E-02 1.24E-02
IDAHO INFANT 5.18E-01 2.34E-01 4.07E-02 7.29E+00 1.08E-01 1.00E+00 8.57E-02 4.22E-02
CHILD 6.25E-01 2.08E-01 4.19E-02 1.72E+00 1. 28E-01 1. 99E+00 1.05E-01 4.34E-02
TEEN 3.49E-01 1.49E-01 2.65E-02 6.95E-01 1.01E-01 1. 94E+00 1.56E-01 2.80E-02
ADULT 2.67E-01 1.13E-01 2.16E-02 4.05E-01 7.70E-02 1.28E+00 1.53E-01 2.30E-02
ILLINOIS INFANT 4.44E+00 9.60E-01 8.11E-01 1.32E+01 8. 71E-01 9.52E-01 1.76E-01 8.11E-01
CHILD 2.08E+00 4.74E-01 4.20E-01 3.03E+00 4.48E-01 7.07E-01 1.10E-01 4.20E-01
TEEN 7.8lE-01 1.91E-01 1. 64E-01 1.10E+00 1.79E-01 4.44E-01 1.01E-01 1. 64E-01
ADULT 4.90E-01 1.22E-01 1.06E-01 5.63E-01 1.14E-01 2.89E-01 7.41E-02 1.06E-01
INDIANA INFANT 2.22E+00 4. 00E-01 3.27E-01 1.10E+01 3.72E-01 7.76E-01 1.17E-01 3.28E-01
CHILD 1.13E+OO 2.43E-01 1.74E-01 2.44E+00 2.18E-01 1.09E+00 9.34E-02 1.74E-01
TEEN 4.58E-01 1. 24E-01 6.98E-02 8.90E-01 1. 07E-01 9.71E-01 1.09E-01 7.05E-02
ADULT 3.03E-01 8.73E-02 4.57E-02 4.57E-01 7.33E-02 6.41E-01 9.57E-02 4.64E-02
KANSAS INFANT 1.06£+00 2.16E-01 4.92E-02 4.96E+00 9.84E-02 3.86E-01 7.94E-02 4.97E-02
CHILD 5.01E-01 1.16E-01 2.82E-02 1.11E+OO 6.68E-02 7.08E-01 6.53E-02 2.87E-02
TEEN 2.04E-01 6.98E-02 1.62E-02 4.27E-01 4.43E-02 6.80E-01 7.8lE-02 1.67E-02
ADULT 1.36E-01 4.97E-02 1.30E-02 2.34E-01 3.20E-02 4.49E-01 6.92E-02 1.35E-02
KENTUCKY INFANT 2.35E+00 5.07E-01 2.99E-01 9. 73E+OO 3.65E-01 5.11E-01 1.33E-01 2.99E-01
CHILD 1. 02E+00 2.30E-01 1.52E-01 2.15E+00 1.86E-01 5.77E-01 8.94E-02 1.53E-01
TEEN 3.73E-01 1.01E-01 6.33E-02 7.84E-01 8.17E-02 4.77E-01 8.87E-02 6.37E-02
ADULT 2.32E-01 6.53E-02 4.29E-02 4.0lE-01 5.29E-02 3.14E-01 6.96E-02 4.32E-02
LOUISIANA INFANT 8.68E-02 3.43E-02 1.22E-02 4.27E+00 3.06E-02 3.97E-01 3.14E-02 1.27E-02
CHILD 1. 69E-01 5.21E-02 1. 20E-02 9.16E-01 4.00E-02 7.99E-01 4.01E-02 1. 25E-02
TEEN 1.0lE-01 4.13E-02 6.83E-03 3.34E-01 3. 24E-02 7. 77E-01 6.07E-02 7.40E-03
ADULT 7.94E-02 3.25E-02 5.20E-03 1. 69E-01 2. 49E-02 5.15E-01 6.00E-02 5.77E-03
MASSACHUSETTS INFANT 8.70E-01 1.79E-01 4.39E-02 6.51E+00 9.00E-02 2.60E-01 5.46E-02 4.42E-02
CHILD 3.72E-01 8.25E-02 2 . 19 E- 0 2 1.39£+00 5.03E-02 4.55E-01 4.39E-02 2.22E-02
TEEN 1. 40E-01 4.63E-02 1. 20E-02 5.06E-01 3.04E-02 4.35E-01 5.16E-02 1.23E-02
ADULT 9.03E-02 3.19E-02 9.52E-03 2.56E-01 2.11E-02 2.87E-01 4.52E-02 9.84E-03
102
-------
TABLE A3 (Continued)
Organ
State Age Bone Liver T. Body Thyroid Kidney Lung Gi Lli Skin
MARYLAND INFANT 5.73E-Ol 1.34E-Ol 3.04E-02 4.91E+00 6.73E-02 2.71E-Ol 2.05E-02 3.08E-02
CHILD 2.98E-Ol 7.49E-02 1.79E-02 1.11E+OO 4.60E-02 5.0lE-Ol 2.56E-02 1.83E-02
TEEN 1.27E-Ol 4.63E-02 1.03E-02 4.28E-Ol 3.06E-02 4.81E-Ol 3.87E-02 1.06E-02
ADULT 8.72E-02 3.33E-02 8.22E-03 2.37E-Ol 2.21E-02 3.18E-Ol 3.81E-02 8.59E-03
MAINE INFANT 7.18E-Ol 4.38E-02 3.44E-02 4.82E+00 4.22E-02 1.55E-Ol 1.91E-Ol 3.46E-02
CHILD 2.98E-Ol 3.74E-02 1.53E-02 1.03E+00 2.93E-02 2.80E-Ol 1.19E-Ol 1. 55E-02
TEEN 1.13E-Ol 2.65E-02 6.40E-03 3.77E-Ol 1.97E-02 2.68E-Ol 1.07E-Ol 6.61E-03
ADULT 7.33E-02 2.03E-02 4.23E-03 1. 9lE-Ol 1.44E-02 1.78E-Ol 7.81E-02 4.44E-03
MICHIGAN INFANT 3.74E+00 7.04E-Ol 5.98E-Ol 1.12E+Ol 6.49E-Ol 1.02E+00 1.45E-Ol 5.99E-Ol
CHILD 1.80E+00 3.87E-Ol 3.13E-Ol 2.57E+00 3.57E-Ol 1.18E+00 1.08E-Ol 3.14E-Ol
TEEN 6.99E-Ol 1.76E-Ol 1.24E-Ol 9.42E-Ol 1.58E-Ol 9.75E-Ol 1.20E-Ol 1.24E-Ol
ADULT 4.49E-Ol 1.19E-Ol 8.02E-02 4.93E-Ol 1.05E-Ol 6.42E-Ol 1.02E-Ol 8.09E-02
MINNESOTA INFANT 4.73E+00 1. 20E+00 9.95E-Ol 1.77E+Ol 1.08E+00 1.14E+00 1.45E-Ol 9.95E-Ol
CHILD 2.34E+00 5.87E-Ol 5.20E-Ol 4.04E+00 5.55E-Ol 8.01E-Ol 9.20E-02 5.20E-Ol
TEEN 9.00E-Ol 2.35E-Ol 2.04E-Ol 1.47E+00 2.21E-Ol 4.79E-Ol 8.59E-02 2.04E-Ol
ADULT 5.72E-Ol 1.49E-Ol 1.32E-Ol 7.53E-Ol 1. 40E-Ol 3.11E-Ol 6.42E-02 1.32E-Ol
MISSOURI INFANT 1. 67E+00 2.74E-Ol 2.42E-Ol 6.28E+00 2.64E-Ol 5.56E-Ol 9.99E-02 2.42E-Ol
CHILD 8.07E-Ol 1.62E-Ol 1.26E-Ol 1. 41E+00 1.52E-Ol 7.73E-Ol 7.60E-02 1.27E-Ol
TEEN 3.17E-Ol 7.91E-02 5.01E-02 5.17E-Ol 7.18E-02 6.83E-Ol 8.54E-02 5.05E-02
ADULT 2.05E-Ol 5.49E-02 3.24E-02 2.68E-Ol 4.87E-02 4.52E-Ol 7.29E-02 3.29E-02
MISSISSIPPI INFANT 2.49E+00 1.13E-Ol 8.96E-02 8.15E+00 1.13E-Ol 3.67E-Ol 1.65E-Ol 9.01E-02
CHILD 8.70E-Ol 6.67E-02 3.39E-02 1.75E+00 5.93E-02 6.09E-Ol 1.12E-Ol 3.44E-02
TEEN 2.80E-Ol 4.05E-02 1.24E-02 6.38E-Ol 3.40E-02 5.76E-Ol 1.12E-Ol 1.28E-02
ADULT 1.62E-Ol 2.98E-02 7.62E-03 3.23E-Ol 2.39E-02 3.81E-Ol 8.90E-02 8.04E-03
MONTANA INFANT 6.74E-Ol 2.10E-Ol 4.58E-02 9.48E+00 1.06E-Ol 4.29E-Ol 8.03E-02 4.64E-02
CHILD 3.70E-Ol 1.08E-Ol 2.63E-02 2.04E+00 6.86E-02 8.01E-Ol 6.83E-02 2.69E-02
TEEN 1.63E-Ol 6.53E-02 1.53E-02 7.47E-Ol 4.49E-02 7.72E-Ol 8.35E-02 1.59E-02
ADULT 1.13E-Ol 4.62E-02 1.23E-02 3.81E-Ol 3.20E-02 5.11E-Ol 7.49E-02 1.29E-02
NORTH CAROLINA INFANT 1.35E-Ol 4.18E-02 1.4lE-02 4.67E+00 3.20E-02 1.53E-Ol 3.60E-02 1.43E-02
CHILD 8.62E-02 2.49E-02 7.35E-03 9. 92E-Ol 2.06E-02 2.92E-Ol 2.88E-02 7.55E-03
TEEN 4.12E-02 1. 62E-02 3.78E-03 3.58E-Ol 1.36E-02 2.82E-Ol 3.36E-02 3.98E-03
ADULT 2.97E-02 1.19E-02 2.79E-03 1.79E-Ol 9. 73E-03 1.87E-Ol 2.95E-02 2.99E-03
NORTH DAKOTA INFANT 9.38E-Ol 3.46E-Ol 2.02E-Ol 3.01E+00 2.41E-Ol 5.31E-Ol 6.41E-02 2.02E-Ol
CHILD 5.99E-Ol 1. 89E-Ol 1.14E-Ol 7.18E-Ol 1.46E-Ol 7.77E-Ol 5.58E-02 1.14E-Ol
TEEN 2.67E-Ol 9.44E-02 4.92E-02 2.71E-Ol 7.31E-02 6.97E-Ol 6.94E-02 4.97E-02
ADULT 1. 84E-Ol 6.47E-02 3.40E-02 1.48E-Ol 5.02E-02 4.61E-Ol 6.28E-02 3.45E-02
NEBRASKA INFANT 6.72E-Ol 1.06E-Ol 3.13E-02 3.12E+00 5.50E-02 3.78E-Ol 1.00E-Ol 3.18E-02
CHILD 3.72E-Ol 8.11E-02 2.03E-02 6.79E-Ol 5.11E-02 7.30E-Ol 7.81E-02 2.08E-02
TEEN 1.66E-Ol 5.56E-02 1.12E-02 2.51E-Ol 3.78E-02 7.06E-Ol 8.94E-02 1.17E-02
ADULT 1.16E-Ol 4.18E-02 8.70E-03 1. 30E-Ol 2.84E-02 4.67E-Ol 7.73E-02 9.23E-03
103
-------
TABLE A3 (Continued)
Organ
State Age BQne Liver T. Body Thyroid Kldney Lung Gi - Lli Skin
NEW HAMPSHIRE INFANT 2.42E+00 6.97E-Ol 5.84E-Ol 6.20E+00 6.21E-Ol 7.15E-Ol 8.64E-02 5.84E-Ol
CH ILD 1. 3 3E+00 3.62E-Ol 3.12E-Ol 1. 51E+00 3.34E-Ol 5.78E-Ol 5.78E-02 3.12E-Ol
TEEN 5.39E-Ol 1.52E-Ol 1.24E-Ol 5.57E-Ol 1.38E-Ol 3.84E-Ol 5.71E-02 1.24E-Ol
ADULT 3.53E-Ol 9.90E-02 8.04E-02 2.98E-Ol 8.92E-02 2.51E-Ol 4.48E-02 8.07E-02
NEW JERSEY INFANT 7.64E-Ol 1. 52E-Ol 4.05E-02 6.98E+00 8.18E-02 2.10E-Ol 5.89E-02 4.07E-02
CHILD 3. OlE-Ol 6.30E-02 1.83E-02 1.49E+00 4.09E-02 3.59E-Ol 4.38E-02 1.85E-02
TEEN 1.07E-Ol 3.34E-02 9.60E-03 5.39E-Ol 2.31E-02 3.42E-Ol 4.82E-02 9.85E-03
ADULT 6.63E-02 2.23E-02 7.47E-03 2.71E-Ol 1. 55E-02 2.26E-Ol 4.06E-02 7.72E-03
NEW MEXICO INFANT 7.24E-Ol 2.17E-Ol 1. 28E-Ol 3. 2lE+00 1.78E-Ol 2.66E+00 7.28E-02 1.32E-Ol
CHILD 1.20E+00 3.56E-Ol 1.14E-Ol 7.61E-Ol 2.69E-Ol 5.27E+00 1.84E-Ol 1.17E-01
TEEN 7.0lE-01 2.69E-Ol 5.83E-02 2.89E-Ol 2.10E-01 5.11E+00 3.33E-Ol 6.20E-02
ADULT 5.42E-01 2.11E-Ol 4.30E-02 1.56E-Ol 1.63E-Ol 3.38E+00 3.50E-Ol 4.66E-02
NEVADA INFANT 3.13E-Ol 1.20E-Ol 2.19E-02 1.43E+OO 6.74E-02 2.13E+00 4.15E-02 2.51E-02
CHILD 1.01E+00 3.13E-Ol 5.96E-02 7.48E-Ol 2.07E-01 4.36E+00 1.45E-Ol 6.28E-02
TEEN 6.31E-Ol 2.57E-Ol 3.81E-02 4.72E-Ol 1.84E-Ol 4.25E+00 2.73E-Ol 4.13E-02
ADULT 4.99E-Ol 2.05E-Ol 3.05E-02 3.91E-Ol 1.46E-Ol 2.82E+00 2.90E-Ol 3.36E-02
NEW YORK INFANT 1.86E+00 3.98E-Ol 2.35E-Ol 8.88E+00 2.91E-Ol 4.25E-Ol 9.09E-02 2.35E-01
CHILD 8.04E-Ol 1.80E-Ol 1.19E-Ol 1.95E+00 1.47E-01 5.00E-Ol 6.34E-02 1.19E-01
TEEN 2.93E-01 7.95E-02 4.95E-02 7.09E-01 6.5lE-02 4.20E-Ol 6.58E-02 4.97E-02
ADULT 1. 82E-01 5.11E-02 3.35E-02 3.62E-Ol 4.21E-02 2.77E-Ol 5.33E-02 3.37E-02
OHIO INFANT 1.44E+00 3.10E-Ol 1.78E-Ol 8.63E+00 2.30E-Ol 5.38E-Ol 7.65E-02 1 .79 E- 0 1
CHILD 7.31E-Ol 1.72E-Ol 9.56E-02 1.90E+00 1.36E-Ol 8.24E-Ol 6.48E-02 9.6lE-02
TEEN 2.99E-Ol 9.15E-02 4.11E-02 7.01E-Ol 7.13E-02 7. 53E-Ol 7.92E-02 4.16E-02
ADULT 1.99E-Ol 6.40E-02 2.82E-02 3.63E-Ol 4.92E-02 4.98E-Ol 7.10E-02 2.88E-02
OKLAHOMA INFANT 1.98E+00 5.88E-Ol 4.81E-Ol 1.54E+00 5.09E-Ol 7.37E-Ol 3.78E-02 4.92E-Ol
CHILD 1.13E+00 3.15E-Ol 2.61E-Ol 5.02E-Ol 2.84E-Ol 7.74E-Ol 3.61E-02 2.61E-Ol
TEEN 4.68E-Ol 1.36E-Ol 1.05E-Ol 2.00E-Ol 1. 21E-Ol 6.05E-Ol 4.79E-02 1.05E-Ol
ADULT 3.10E-Ol 8.99E-02 6.86E-02 1.23E-Ol 7.99E-02 3.98E-Ol 4.47E-02 6.90E-02
OREGON INFANT 1.65E+00 2.94E-Ol 2.80E-Ol 4.64E+00 2.91E-Ol 4.51E-Ol 1.24E-Ol 2.80E-Ol
CHILD 7.89E-Ol 1.64E-Ol 1.45E-Ol 1.07E+00 1.60E-Ol 5.04E-Ol 8.18E-02 1.46E-Ol
TEEN 3.04E-Ol 7.25E-02 5.65E-02 3.88E-Ol 6.88E-02 4.09E-Ol 7.98E-02 5.68E-02
ADULT 1.95E-Ol 4.87E-02 3.62E-02 2.01E-Ol 4.54E-02 2.70E-Ol 6.20E-02 3.64E-02
PENNSYLVANIA INFANT 7.50E-Ol 2.32E-Ol 4.32E-02 7.04E+00 1.03E-Ol 2.32E-Ol 2.58E-02 4.35E-02
CHILD 3.04E-Ol 8.73E-02 2.12E-02 1.50E+00 4.86E-02 3.89E-Ol 2.62E-02 2.15E-02
TEEN 1.09E-Ol 4.30E-02 1.29E-02 5.47E-Ol 2.63E-02 3.72E-Ol 3.60E-02 1.32E-02
ADULT 6.78E-02 2.74E-02 1.08E-02 2.77E-Ol 1.73E-02 2.48E-Ol 3.42E-02 1.11E-02
RHODE ISLAND INFANT 1.50E+00 1.35E-Ol 5.98E-02 6.22E+00 9.0lE-02 2.48E-Ol 1.13E-Ol 6.0lE-02
CHILD 5.45E-Ol 6.50E-02 2.45E-02 1.34E+00 4.66E-02 4.11E-Ol 7.64E-02 2.48E-02
TEEN 1.81E-Ol 3.66E-02 1.07E-02 4.86E-Ol 2.66E-02 3.89E-Ol 7.66E-02 1.10E-02
ADULT 1.07E-Ol 2.56E-02 7.59E-03 2.47E-Ol 1.83E-02 2.57E-Ol 6.06E-02 7.88E-03
104
-------
_TABLE A3 (Continued)
Organ
State Age Bone Liver T. Body Thyroid KIdney Lung Gi Lli Skin
-
SOUTH CAROLINA INFANT 3.56E-01 7.28E-02 2.56E-02 5.67E+00 5.58E-02 8.05E-01 7.84E-02 2.68E-02
CHILD 4.98E-01 1. 39E-01 2.98E-02 1.27E+00 9.49E-02 1.63E+00 9.02E-02 3.10E-02
TEEN 2.87E-01 1.12E-01 1. 73E-02 4.86E-01 7.95E-02 1.58E+00 1.31E-01 1.85E-02
ADULT 2.22E-01 8.89E-02 1.33E-02 2.63E-01 6.20E-02 1.04E+00 1.27E-01 1.45E-02
SOUTH DAKOTA INFANT 9.45E-01 1.01E-01 4.51E-02 6.62E+00 7.42E-02 4.83E-01 1.33E-01 4.58E-02
CHILD 5.63E-01 1.13E-01 2.96E-02 1.45E+00 7.60E-02 9.32E-01 1.03E-01 3.03E-02
TEEN 2.60E-01 8.45E-02 1.52E-02 5.39E-01 5.78E-02 9.00E-01 1.17E-01 1.59E-02
ADULT 1.85E-01 6.55E-02 1.12E-02 2.82E-01 4.39E-02 5.95E-01 1.01E-01 1.19E-02
TENNESSEE INFANT 2.56E+00 4.68E-01 3.07E-01 7. 73E+OO 3.61E-01 6.39E-01 1. 21£-01 3.08E-01
CHILD 1.19E+00 2.52E-01 1.61E-01 1.75E+00 2.04E-01 8.34E-01 9.26E-02 1.62E-01
TEEN 4.61E-01 1.25E-01 6.67E-02 6.51E-01 9.84E-02 7.24E-01 1.00E-01 6.73E-02
ADULT 2.97E-01 8.59E-02 4.49E-02 3.44E-01 6.66E-02 4.77E-01 8.38E-02 4.54E-02
TEXAS INFANT 1. 42E-01 3.25E-02 1.87E-02 2.57E+00 2.80E-02 1.40E-01 3.57E-02 1.89E-02
CHILD 1.02E-01 2.67E-02 1.09E-02 5.58E-01 2.16E-02 2.61E-01 2.77E-02 1.11E-02
TEEN 4.98E-02 1.79E-02 5.13E-03 2.05E-01 1.43E-02 2.50E-01 3.16E-02 5.31E-03
ADULT 3.62E-02 1.35E-02 3.68E-03 1.06E-01 1.04E-02 1.66E-01 2.72E-02 3.81£-03
UTAH INFANT 7.64E-01 2.30E-01 5.61E-02 1.23E+01 1. 31£-01 1.14E+00 1.26E-01 5.78E-02
CHILD 6.99E-01 2.06E-01 4.64E-02 2.79E+00 1.38E-01 2.24E+00 1.35E-01 4.80E-02
TEEN 3.70E-01 1.48E-01 2.74E-02 1.09E+00 1.06E-01 2.18E+00 1.90E-01 2.90E-02
ADULT 2.78E-01 1.13E-01 2.16E-02 6.05E-01 8.05E-02 1.45E+00 1.82E-01 2.33E-02
VIRGINIA INFANT 4.88E-01 1.26E-01 1.14E-01 1. 9 OE+OO 1.22E-01 3.20E-01 3.69E-02 1.14E-01
CHILD 3.43E-01 9.21E-02 6.45E-02 4.62E-01 8.13E-02 4.88E-01 3.33E-02 6.48E-02
TEEN 1. 59E-01 5.03E-02 2.64E-02 1.79E-01 4.24E-02 4.42E-01 4.24E-02 2.67E-02
ADULT 1.12E-01 3.65E-02 1.74E-02 1.00E-01 2.99E-02 2.92E-01 3.88E-02 1.78E-02
VERMONT INFANT 8.68E-01 1.29E-01 3.57E-02 1.61E+00 5.60E-02 1.64E-01 1.21£-01 3.59E-02
CHILD 3.50E-01 6.35E-02 1.77E-02 3.63E-01 3.44E-02 2.83E-01 8.18E-02 1.79E-02
TEEN 1. 28E-01 3.64E-02 9.48E-03 1.40E-01 2.16E-02 2.69E-01 7.68E-02 9.69E-03
ADULT 8.03E-02 2.54E-02 7.49E-03 7.64E-02 1.54E-02 1.78E-01 5.78E-02 7.70E-03
WASHINGTON INFANT 5.68E-01 2.0 5E-01 1.23E-01 2.59E+00 1.46E-01 2.52E-01 4.35E-02 1.23E-01
CHILD 3.37E-01 1.05E-01 6.74E-02 5.94E-01 8.34E-02 3.29E-01 3.26E-02 6.76E-02
TEEN 1.45E-01 5.01£-02 2.87E-02 2.21E-01 3.93E-02 2.84E-01 3.61E-02 2.89E-02
ADULT 9.83E-02 3.36E-02 1.97E-02 1.17E-01 2.64E-02 1.87E-01 3.06E-02 1.99E-02
WISCONSIN INFANT 2.56E+00 3.35E-01 2.46E-01 1.32E+01 2.98E-01 5.12E-01 1.24E-01 2.46E-01
CHILD 1. 04E+00 1.71E-01 1.20E-01 2.86E+00 1.54E-01 6.65E-01 8.73E-02 1.20E-01
TEEN 3.71E-01 8.18E-02 4.74E-02 1.03E+00 7.16E-02 5.81E-01 9.12E-02 4.78E-02
ADULT 2.28E-01 5.55E-02 3.08E-02 5.21E-01 4.74E-02 3.83E-01 7.43E-02 3.12E-02
WEST VIRGINIA INFANT 6.19E-01 1. 60E-01 3.80E-02 7.66E+00 8.71£-02 4.93E-01 3.46E-02 3.87E-02
CHILD 4.03E-01 1.09E-01 2.56E-02 1. 65E+00 7.13E-02 9.46E-01 4.51£-02 2.62E-02
TEEN 1. 91E-01 7.32E-02 1.47E-02 6.08E-01 5.09E-02 9.14E-01 7.02E-02 1.54E-02
ADULT 1. 38E-01 5.44E-02 1.16E-02 3.12E-01 3.77E-02 6.05E-01 6.98E-02 1.23E-02
105
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~~BLE A3 (Conunued)
Organ
State Age Bone Liver T. Body Thyroid Kidney Lung Gi Lli Skin
-
WYOMING INFANT 3.63E-OI 8.75E-02 1.80E-02 2.22E-OI 4.97E-02 1.64E+OO 2.73E-02 2.05E-02
CH ILD 8.29E-OI 2.44E-OI 4.65E-02 4.28E-OI 1.6IE-OI 3.34E+OO 1. 08E-OI 4.90E-02
TEEN 5.04E-OI 2.0IE-OI 2.94E-02 3.27E-OI 1.43E-OI 3.26E+OO 2.07E-OI 3.19E-02
ADULT 3.96E-OI 1. 6IE-OI 2.35E-02 2. 97E-OI 1.l4E-OI 2.I6E+OO 2.2IE-OI 2.59E-02
106
-------
TABLE A4
Calculation of total U.S. milk production
Month
(1977)
Mil k produced in
U.S. during month
(Mlbs)
Fraction of month
included in
integration period
Milk produced in
U.S. during
integration period
(Mlbs)
September 9907 13.5/30 4458.2
October 9902 31/31 9902
November 9497 30/30 9497
December 9497* 0.5/30 158.3
Total U.S. mil k product ion 24015.5 Ml bs
We assumed that all of this milk was or would be consumed in the U.S.
The 1976 population data (IPA77) shown in Table A5 were used to determine the
fraction of the U.S. population in each state. These fractions were multi-
plied by the total milk production of 24015.5 Mlbs. to obtain the estimated
milk consumption for each state. These data are shown in Table A5.
*December data was not available at the time of preparation of this
report, so November data were used.
107
-------
TAI>LI:: AJ
State
Estimated population and milk consumption for each state
Fraction of 1976 U.S.
population
1976 state
population
Estimated
milk consumption
(Mlbs. )
ALASKA
ALABAMA
ARKANSAS
ARIZONA
CALIFORNIA
COLORADO
CONNECTICUT
D.C.
DELAWARE
FLORIDA
GEORGIA
HAWAII
IOWA
IDAHO
ILLINOIS
INDIANA
KANSAS
KENTUCKY
LOUISIANA
MASSACHUSETTS
MARYLAND
MAINE
MICHIGAN
MINNESOTA
MISSOURI
MISSISSIPPI
MONTANA
NORTH CAROLINA
NORTH DAKOTA
NEBRASKA
NEW HAMPSHIRE
NEW JERSEY
NEW MEXICO
NEVADA
NEW YORK
OHIO
OKLAHOMA
OREGON
PENNSYLVANIA
RHODE ISLAND
SOUTH CAROLINA
SOUTH DAKOTA
TENNESSEE
TEXAS
UTAH
VIRGINIA
VERMONT
WASHINGTON
WISCONSIN
WEST VIRGINIA
WYOMING
US TOTAL
]82000.
]665000.
2109000.
2270000.
21520000.
258]000.
]117000.
702000.
582000.
8421000.
4970000.
887000.
2870000.
831000.
11229000.
5302000.
2310000.
3428000.
3841000.
5809000.
4144000.
1070000.
9104000.
3965000.
4778000.
2354000.
75]000.
5469000.
643000.
155]000.
822000.
7336000.
1168000.
610000.
18084000.
10690000.
2766000.
2]29000.
11862000.
927000.
2848000.
686000.
4214000.
12487000.
1228000.
50]2000.
476000.
3612000.
4609000.
1821000.
]90000.
214658000.
0.0018
0.0171
0.0098
0.0106
0.100]
0.0120
0.0145
0.0033
0.0027
0.0392
0.0232
0.0041
0.0134
0.0039
0.0523
0.0247
0.0108
0.0160
0.0179
0.0271
0.0193
0.0050
0.0424
0.0185
0.0223
0.0110
0.0035
0.0255
0.0030
0.0072
0.0038
0.0342
0.0054
0.0028
0.0842
0.0498
0.0129
0.0108
0.0553
0.0043
0.0133
0.0032
0.0196
0.0582
0.0057
0.0234
0.0022
0.0168
0.0215
0.0085
0.0018
4.274E+Ol
4.100E+02
2.360E+02
2.540E+02
2.408E+03
2.890E+02
3.487E+02
7.854E+Ol
6.511E+Ol
9.421E+02
5.560E+02
9.924E+Ol
3.211E+02
9.297E+Ol
1.256E+03
5.932E+02
2.584E+02
3.835E+02
4.297E+02
6.499E+02
4.636E+02
1.197E+02
1.019E+03
4.436E+02
5.346E+02
2.634E+02
8.424E+Ol
6.119E+02
7.194E+Ol
1. 737E+02
9.196E+Ol
8.207E+02
1.307E+02
6.825E+Ol
2.023E+03
1.196E+03
3.095E+02
2.606E+02
1.327E+03
1.037E+02
3.186E+02
7.675E+Ol
4.715E+02
1.397E+03
1.374E+02
5.630E+02
5.325E+Ol
4.041E+02
5.156E+02
2.037E+02
4.363E+Ol
2.402E+04
108
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A5.
Estimation of food group fractions and marketing-to-consumption delay
times
Table A6 lists USDA milk utilization data for 1975 (DOA76). A verbal estimate
of the delay times between marketing and consumption of the dairy products was
obtained from USDA personnel (DOA78). These times are al so shown in Table A6.
Based on a review of this data, it was decided that sufficient precision would
be maintained in the calculations if two food groups were established. The
food groups established are described in Table A7.
TABLE A6
Milk utilization for 1975 and estimated marketing-to-consumption times for
various milk products (DOA78, DOA76)
Product 1975 Usage, Estimated Marketing-to-
Ml bs Consumption Time, d
Manufactu red Products
1. Creamery butter 19 , 6 03 14dmin., 30 d average
2. Cheese 24,080 30 d min, 1-6 mo. average
3. Cottage Cheese 1,049 1 week
4. Evaporated and
dry whole milk 3,008 6 mo. average
5. Ice cream & other
frozen dairy products 12,042 14 d min., 1-6 mo. average
6. Other manufactured
products 821
Fluid Products
7. Sold by dealers & producers
8. Used for human consumption
where produced
9. Residual
51,400
1 day
1 , 6 54
406
114,063
1 day
109
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TABLE A7
Food groups for population dose calculations
Food Group Description
Fraction
for 1975
Usage
Estimated
Marketing-to-
Consumption
Time, d
1.
0.52
30 d
Includes creamery butter, cheese,
ice cream, canned and condensed milk,
dry milk, and other manufactured pro-
ducts (includes items 1, 2, 4, 5, & 6
for a total of 59,554 Mlbs)*
2.
Includes cottage cheese, and all
fluid milk products (includes items
3, 7, 8, & 9 for a total of 54,509
Mlbs)*
0.48
1 d
*See "items" in Table A6.
110
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APPENDIX B
EPA Policy Statement on Relationship Between Radiation Dose
and Effect
-------
The need to assess environmental radiation impacts in tenns of health
effects has led EPA to establish a policy for relating radiation dose to
heal th effects. The following pol icy statement was publ ished in the Federal
Register on July 9, 1976 (EPA76):
"The actions taken by the Environmental Protection Agency to protect
public health and the environment require that the impacts of contaminants in
the environment or released into the environment be prudently examined. When
these contaminants are radioactive materials and ionizing radiation, the most
important impacts are those ultimately affecting human health. Therefore the
Agency believes that the public interest is best served by the Agency
providing its best scientific estimates of such impacts in terms of potential
ill health.
"To provide such estimates, it is necessary that judgments be made which
relate the presence of ionizing radiation or radioactive materials in the
environment, i.e., potential exposure, to the intake of radioactive materials
in the body, to the absorption of energy from the ionizing radiation of
different qualities, and finally to the potential effects on human health. In
many situations, the levels of ionizing radiation or radioactive materials in
the environment may be measured directly, but the determination of resultant
radiation doses to humans and their susceptible tissues is generally derived
from pathway and metabolic models and calculations of energy absorbed. It is
also necessary to formulate the relationships between radiation dose and
effects; relationships derived primarily from human epidemiological studies
but also reflective of extensive research utilizing animals and other
biological systems.
"Although much is known about radiatiQn dose-effect relationships at high
levels of dose, a great deal of uncertainty exists when high level dose-effect
relationships are extrapolated to lower levels of dose, particularly when
given at low dose rates. These uncertainties in the relationships between
dose received and effect produced are recognized to relate, among many
factors, to differences in quality and type of radiation, total dose, dose
distribution, dose rate, and radiosensitivity. including repair mechanisms,
sex, variations in age, organ, and state of health. These factors involve
112
-------
complex mechanisms of interaction among biological ~
systems~ the study of which is part of the continuing
scientific knowledge.
"Because of these many uncertainties~ it is necessary to rely upon the
considered judgments of experts on the biological effects of ionizing
radiation. These findings are well-documented in publ ications by the United
Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR)~ the
National Academy of Sciences (NAS)~ the International Commission on
Radiological Protection (ICRP) and the National Council on Radiation
Protection and Measurements (NCRP) ~ and have been used by the Agency in
formulating a policy on relationship between radiation dose and effect.
"It is the present policy of the Environmental Protection Agency to
assume a linear, nonthreshold relationship between the magnitude of the
radiation dose received at environmental levels of exposure and ill, health
produced as a means to estimate the potential health impact of actions it
takes in developing radiation protection as expressed in criteria, guides, or
standards. This policy is adopted in conformity with the generally accepted
assumption that there is some potential ill health attributable to any
exposure to ionizing radiation and that the magnitude of this potential ill
health is directly proportional to the magnitude of the dose received.
"In adopting this general pol icy, the Agency recognizes the inherent
uncertainties that exist in estimating health impact at the low levels of
exposure and exposure rates expected to be present in the environment due to
human activities, and that at these levels, the actual health impact will not
be distinguishable from natural occurrences of ill health, either
statistically or in the forms of ill health present. Also, at these very low
levels, meaningful epidemiological studies to prove or disprove this
relationship are difficult, if not practically impossible, to conduct.
However, whenever new information is forthcoming, this policy will be reviewed
and updated as necessary.
lilt is to be emphasized that this pol icy has been establ ished for the
purpose of estimating the potential human health impact of Agency actions
regarding radiation protection, and that such estimates do not necessarily
constitute identifiable health consequences. Further, the Agency
implementation of this policy to estimate potential human health effects
chemical, and physical
endeavor to acquire new
113
-------
presupposes the premise that, for the same dose, potential radiation effects
in other constituents of the biosphere will be no greater. It is generally
accepted that such constituents are no more radiosensitive than humans. The
Agency believes the policy to be a prudent one.
IIIn estimating potential health effects, it is important to recognize
that the exposures to be usually experienced by the publ ic will be annual
doses that are small fractions of natural background radiation to, at most, a
few times this level. Within the United States, the natural background
radiation dose equivalent varies geographically between 40 and 300 mrem per
year. Over such a relatively small range of dose, any deviations from
dose-effect linearity would not be expected to significantly affect actions
taken by the Agency, unless a dose-effect threshold exists.
IIWhile the utilization of a linear, nonthreshold relationship is useful
as a generally appl icable pol icy for assessment of radiation effects, it is
also EPAls policy in specific situations to utilize the best available
detailed scientific knowledge in estimating health impact when such
information is available for specific types of radiation, conditions of
exposure, and recipients of the exposure. In such situations, estimates may
or may not be based on the assumptions of linearity and a nonthreshold dose.
In any case, the assumptions will be stated explicitly in any EPA radiation
protection actions.
liThe linear hypothesis by itself precludes the development of acceptable
levels of risk based solely on health considerations. Therefore, in
establishing radiation protection positions, the Agency will weigh not only
the health impact, but also social, economic, and other considerations
associated with the activities addressed.1I
114
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AEC73
BOC70
BOC73
CRC69
DOA76
DOA77
DOA78
REFERENCES
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Concerning Proposed Rule Making Action: Numerical Guides for
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in Light-Water-Cooled Nuclear Power Reactor Effluents," Volume
2, Analytical Models and Calculations", USAEC Rep. WASH-1258,
(Springfield, VA: NTIS).
u.s. Bureau Of The Census, 1970, Statistical Abstract of The United
States: 1970, 91st edition, (Washington, D.C.: USBS).
u.S. Bureau Of The Census, 1973, Statistical Abstract of the United
States: 1973, 94th Edition, (Washington, D.C.: USBS).
The Chemical Rubber Company, 1969.
50th edition, (Cleveland, OH).
Handbook of Chemistry & Physics,
u.S. Department Of Agriculture, 1976, "Milk Production, Disposition,
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Rep. Da 1-2 (76), Crop Reporting Board, Statistical Reporting
Service, (Washington, D.C.: USDA).
U.S. Department Of
Da 1-1, (October,
Board, Statistical
Agriculture, 1977, "Milk Production," USDA Rep.
November, and December 1977), Crop Reporting
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Personal Communication, 1978, Dairy Division, Agricultural
Marketing Service, U.S. Department of Agriculture, to J.M.
U.S. Environmental Protection Agency.
Sm it h -
115
-------
EPA73
EPA76
EPA77a
EPA77b
EPA77c
EPA78
ICRP75
IPA77
u.s. Environmental Protection Agency, 1973, "Environmental Analysis
of the Uranium Fuel Cycle, Part II - Nuclear Power Reactors and
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(Washington, DC.: USEPA).
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USEPA) .
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Data, Report 11, Eastern Environmental Radiation Facility.
(Montgomery, AL: USEPA).
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Galpin From: Neal S. Nelson, Ph.D., "1-131 Risk from Chinese
Bomb Fallout - 1977," Office of Radiation Programs, Criteria
and Standards Division. (Washington, D.C.: USEPA).
U.S. Environmental Protection Agency, 1978, Environmental Radiation
Data, Report 12, Eastern Environmental Radiation Facility, (Mont-
gomery. AL: USEPA).
International Commission on Radiological Protection, 1975, ICRP
Publication 23: Report of the Task Group on Reference Man,
(Elmsford, NY: Pergamon Press).
Information Please Publishing Co., 1977, Information Please Almanac,
Atlas, and Yearbook, 32nd Edition, (New York, NY)
116
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Ke76
MVSR77
NAS72
NRC77
Re67
Kereiakes, J.G., Feller, P.A., Ascoli, F.A., Thomas, S.R., Gel ford,
M.J. and Saenger, E.L., 1976, "Pediatric Radiopharmaceutical
Dosimetry" in: Radiopharmaceutical Dosimetry Symposium Proceedings.
(Edited by R. J. Cloutier, J. L. Coffey, W.S. Snyder and E.E. Watson)
Oak Ridge, TN, 26-29 April 1976, USHEW Pub. (FDA) 76-8044,
pp. 77-91, U.S. Department of Health, Education, and Welfare
(Springfield, VA: NTIS).
Monthly Vital Statistics Report, February 1977, "Advanced Report
on Final Mortality Statistics for 1975," Vol. 25, No. l1(Supple-
ment).
National Academy Of Sciences, 1972, The Effects on Populations of
Exposure to Low Levels of Ionizing Radiation. Report of the
Advisory Committee on the Biological Effects of Ionizing
Radiations, National Research Council, (Washington, O.C.: NAS).
U.S. Nuclear Regulatory Commission, 1977, "Calculation of Annual
Doses to Man from Routine Releases of Reactor Effluents for the
Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1."
Regulatory Guide 1.109, Revision 1 (Washington, D.C.: USNRC).
Reinsch, C.H., 1967,
Mathematik, Vol. 10,
Germany) .
"Smoothing by Spline Functions," Numerische
pp. 177-183, Springer-Verlag, (Berlin, West
117
AU GAFS, AL (825196) 300
-------
United States
Environmental Protection
Agency
Office of Radiation Programs
Eastern Environmental
Radiation Facility
P.O. Box 3009
Montgomery AL 36193
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Fees Pa id
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