Technical Note
ORP/LV-75-6
INDIVIDUAL AND POPULATION
DOSES FOR 1972 DISCHARGES
FROM THE GINNA NUCLEAR
POWER PLANT , UNIT NUMBER ONE
NOVEMBER 1975
U.S. ENVIRONMENTAL PROTECTION AGENCY
OFFICE OF RADIATION PROGRAMS - LAS VEGAS FACILITY
LAS VEGAS,NEVADA 89114
-------
Technical Note
ORP/LV-75-6
INDIVIDUAL AND POPULATION
DOSES FOR 1972 DISCHARGES
FROM THE GINNA NUCLEAR
POWER PLANT, UNIT NUMBER ONE
Joseph A. Cochran
Thomas R, Horton
NOVEMBER 1975
U.S. ENVIRONMENTAL PROTECTION AGENCY
OFFICE OF RADIATION PROGRAMS - LAS VEGAS FACILITY
LAS VEGAS, 89114
-------
This report has been reviewed by the Office of
Radiation Programs - Las Vegas Facility, EPA,
and approved for publication. Mention of trade
names or commercial products dees not constitute
endorsement or recommendation for use.
-------
PREFACE
The Office of Radiation Programs, U.S. Environmental
Protection Agency, carries out a national program designed
to evaluate population exposure to ionizing and non-ionizing
radiation, and to promote development of controls necessary
to protect the public health and safety. This study was
undertaken to assess the environmental impact of an operating
nuclear power plant on the local population. Readers of
this report are encouraged to inform the Office of Radiation
Programs of any omissions or errors. Comments or requests
or further information are also invited.
Donald W, Hendricks
Director, Office of
Radiation Programs, Las Vegas Facility
-------
CONTENTS
Page
Preface i
List of Figures iv
List of Tables iv
Introduction 1
Summary 1
Conclusion 2
Doses From Radionuclides Released To The 2
Atmosphere
Gamma Cloud Whole Body Dose 2
Air Submersion Skin Surface Dose 4
Thyroid Pose From Iodine Inhalation 4
Milk Pathway Dose 8
Leafy, Green Vegetable Pathway Dose ^
Radionuclides Released And Doses From Il-
liquid Discharges
Liquid Discharge and Receiving Water 11
Concentrations
Fish Ingestion Dose 11
Drinking Water Dose 14
Swimming and Boating Pathway Dose 17
Dose Summary 19
Appendixes
A - AIREM Air Dose Model 22
B - Noble Gas Skin Surface
Submersion Dose Calculation 23
C - Inhalation Dose Calculation 24
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Page
D - Milk Pathway riose 25
E - Vegetable Consumption Dose 26
Calculation
F - Fish Ingestion Dose 27
G - Water Ingestion Dose 27
H - Swimming and Boating Dose 28
References 29
111
-------
LIST OF FIGURES
Number
Page
Number
1
2
3
4
S
6
7
8
9
10
Average Annual Gamma Cloud Whole Body
Dose for 1972 in Millirem
(0-8 Kilometer Distance)
Average Annual Gamma Cloud Whole Body
Dose for 1972 in Millirem
(0-80 Kilometer Distance)
LIST OF TABLES
Reported Gaseous Releases-1972
in Curies
Annual Doses from Gaseous Releases
in 1972
Radioiodine Dose Summary
Maximum Concentrations of Radionuclides
in Station Liquid Discharges and
Receiving Water Adjacent to the Site
Individual Whole Body Dose from
Ingestion of Lake Fish
Dose to Critical Organs from Fish
Ingestion
Whole Body Dose from the Ingestion of
Water
Immersion Dose front Swimming
Summary of Doses from Ginna for 1972
Comparison of Doses and Federal
Regulations
Page
3
9
12
13
15
16
18
20
21
IV
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INTRODUCTION
The R. E. Ginna Nuclear Power Plant, Unit Number One,
is a pressurized water reactor located on the south shore
of Lake Ontario (approximately twenty miles east of Rochester,
New York). The Atomic Energy Commission granted a provisional
license to the Rochester Gas and Electric Corporation on
September 19, 1969, for initial criticality. The license
was amended on March 1, 1972, to allow operation up to a
level of 1,520 megawatts thermal (MWt,). Detailed information
on the operation and effluent releases from this reactor
were obtained from the Final Environmental Statement (FES');
operating reports3'4 and the Environmental Report dated 1972.6
SUMMARY
This report documents the radioactivity releases during
1972 from the Ginna Plant. Doses were calculated or projected
from this release data and compared with current standards.
This report is intended to evaluate the environmental impact
of an operating pressurized water reactor in contrast to
Final Environmental Statement projections. The FES is essentially
a projection of effluents and resulting doses for normal
operating conditions. Conservatism is built into the projections
to insure against underestimating the dose. This report,
however, uses actual effluent data for 1972 and currently
accepted models to predict the most likely doses that occurred
to the local population in 1972.
1
-------
CONCLUSION
The operation of the ninna Nuclear Power Plant,
One, during 1972 has produced radioactive effluents which
were eventually released to the environment. Using currently
acceptable models, the maximum individual and population
doses from these releases have been calculated. The resultant
dose values meet the present "Federal recommendations for
"as low as practicable" for light water reactors.
DOSES FROM RADIONUCLIDES RELEASED TO THE ATMOSPHERE
GAMMA CLOUD WHOLE BODY DOSE
Airborne radioactive effluents released from the
2
Ginna plant in 1972 consisted of the following.
Noble gases 1.2 x 104 curies
- 2
Halogens 3,6 x 10 curies
Participates 7.8 x 10"5 curies
Table 1 shows the monthly noble gas and halogen releases,
as reported in the semiannual reports of the licensee '^
for 1972. The external gamma dose is calculated using
a finite cloud modelt assuming that the releases are
continuous. The primary inputs into the model are the
release values from Table 1, joint -Frequency meteorological
data derived from the pre-operational site meteorological
study,6 and the 1970 population projection within a 50-mile
radius of the plant, A description of the air dose model,
AIp.EM, is piven in Appendix A.
2
-------
TABLE I
REPORTED GASEOUS RELEASES - 1972
IN CURIES3*4
NUCLIDE
Jan
Feb
Mar
Apr
May
Jun
Jul
Aug
Sep
i Oct
Nov
Dec
Total
1
2
5
7
1
4
5
1
1
Kr-85
-
. 8X101
-
-
.4X102
. 4X102
ND
. 8X10 *
.6X102
.1X101
. 9X10 *
.6X101
3
.1X10
Xe-133
8
8
3
3
1
3
4
4
1
1
8
I
i
.1X10
.6X102
. 7X103
.1X103
.2X102
ND
. 4X102
.6X1Q2
. 2X102
.3X102
.1X102
.9X101
.oxio1*
Kr-85m
7
7
3
5
5
1
3
1
4
4
.3X10°
.1X10°
.5X10°
.5X10°
ND
ND
.6X10°
.2X101
.3X10°
ND
.OXIO-1
.OXIO-1
.SX101
Xe
9.
1.
9.
6.
3.
3.
7.
3.
1.
6.
4.
-135
i
7X10
OXIO2
2X101
3X1 01
ND
ND
1X10 l
3X1 01
2X10-5
0X10°
0X10°
0X10°
9X10 2
I
1.
8.
2.
2.
5.
4.
3.
1.
7.
2.
4.
5.
3.
-131
9X10"
oxio-4
8X10- 3
2X10-2
6X10- 3
oxio- "
2X10-5
8X10- s
2X10-5
mo-*
OXIO-5
OXIO-6
4X1Q-*
1-133
3. 5X10"
1.5X10-*
1.2X10-"
!
8.0X10-"
ND
ND
2.0X10-5
-------
Table 2 shows both the individual and population dose,
compared with natural background. The maximum individual
whole body dose is 0.065 mrem per year at the plant boundary
(approximately 690 meters west of the reactor site). The
average per capita dose -for the total population within
50 miles of the plant is 7.5 x 10'4 mrem per year which
is equivalent to a population dose of 0.88 person-rem per
year. The Plant-derived gamma doses (shown in Table 2)
include the noble gas and halogen contributions. Particulate
contribution is considered negligible and not included.
The ratio of plant-derived population dose to natural background
is 5.9 x 10" . Natural background is assumed to contribute,
130 mrem per year to each individual.
Figures 1 and 2 show the average annual individual
dose isopleths for the 8 kilometer and 80 kilometer distances.
The figures show that the maximum dose sector is over the
lake northeast of the reactor site (Sector 3).
AIR SUBMERSION SKIN SURFACE HOSE
The maximum individual skin dose from noble gases
was calculated to be 1.4 mrem/yr to an individual at the
west site boundary (690 meters from the plant). The skin
dose is estimated by utilizing the method described in
Appendix B.
THYROID DOSE FROM IODINE INHALATION
The thyroid dose from iodine via the inhalation pathway
4
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TABLE 2
ANNUAL DOSES FROM GASEOUS RELEASES IN 1972
INDIVIDUAL DOSE (mrem/yip
Maximum Doses @ Plant Boundary West
(X/Q = 2.1X10-5)
1. Whole Body 6.5X10"2
2. Skin Dose 1.4X10°
Average Annual Per Capita Dose
within SO mile radius 7.5X10"*
Natural Background Dose 1.5X102
POPULATION DOSEa - 50 Mile Radius CPerson-Rem/yr)
Total Plant Derived Dose S
Total Natural Background Dose 1.5X105
a--Average Annual - Based on a 1970 population within 50 miles
of the Ginna Station of 1.17X106 people.°
-------
Figure 1
Average Annual Gamma Cloud
Whole Body Dose for 1972 in Millirem
(0-8 Kilometer Distance)
-------
Whole
-------
for adults has been calculated in the FES for a non-depleted
cloud. This is conservative because it assumes no deposition
of iodine on the ground between the discharge point and
the location where the dose is being calculated. The AIREM
model calculates a depleted cloud dose using a deposition
velocity of 0.01 meters per second. Table 3 shows a comparison
of the two cases at the maximum property line location.
The maximum individual for the iodine inhalation dose
is a four-year old child.7 The property line dose for
this child is 8.1 x 10~2 mrem per year, using the depleted
cloud model.
The population dose is based upon the adult. For
1972 the average per capita dose was 1.3 x 10~-> mrem per
year, which is equivalent to 1.5 x 1Q~2 person-rem per
year for the population within SO miles of the plant.
Appendix C contains a description of the equations
used to calculate the inhalation dose.
MILK PATHWAY DOSE
The closest dairy herd is 4,700 meters (2.9 miles)
WSW of the plant, and the hypothetical location for a dairy
herd to give a maximum dose from milk is at the plant
boundary (690 meters west of the discharge point) . Table 3
shows the dose for both locations. Using the depleted cloud
model, the maximum milk pathway dose at the nearest herd
location is 7.7 x 10~2 mrem per year. The hypothetical
8
-------
TABLE 3
RADIOIODINE DOSE SUMMARY (mrem/yr)
PATHWAY
LOCATION
DEPLETED
NONDEPLETED
Adult Thyroid
(Inhalation)
690 meters West 1.7X10
(X/Q ffi 2.1X10"6)
Child Thyroid
(Milk)
Child Thyroid
(Milk)
4 Yr. Child Thyroid 690 meters West
(Vegetable) (x/Q = 2.1X10"6)
_ 2
4 Yr0 Child Thyroid 690 meters West 8.1X10"z
(Inhalation) (x/Q » 2.1X10"6)
690 meters West 7.0X10°
(X/Q = 2olX10"s)
4667 meters WSW 7.7X10"2
(X/Q « 4. 5X10" 8)
2.0X10
9,5X10'
8.0X10°
107X10
6.8X10
- 2
-------
maximum milk pathway dose from a herd at the west property
line is 7.0 mrem per year. The depleted and non-depleted
cases are given for comparison. All cases are calculated
for a two-gram thyroid, a milk consumption of one liter
per day, and cow pasturage of five months annually. For
deposition calculations, the depleted cloud dose becomes
significantly different from the non-depleted cloud as the
distance from the plant increases.
The thyroid dose from 131-iodine through the milk pathway
is dependent on many factors that convert the airborne effluents
(Q) to a dose. This conversion generally results in a
spectrum of doses being generated from the same 0 and X/Q
values related to the particular conversion factors used
by each individual calculating the dose. Appendix D contains
a description of the dose calculation for the milk pathway
in enough detail to allow comparison of the factors used
in this report with other approaches.
LEAFY, GREEN VEGETABLE PATHWAY DOSE
Normally, the thyroid dose from ingestion of leafy
green vegetables contaminated with radioiodine is not the
critical thyroid dose. The maximum individual would be
a four-year-old child consuming leafy, green vegetables at
the site boundary (690 meters west of the plant). Assuming
this child consumes these vegetables three months out of
the year, the estimated thyroid dose is 6.8 x 10"2 mrem/yr.
10
-------
A description of the dose calculation for this pathway
is found in Appendix E.
RADIONUCLIDES RELEASED AND DOSES FROM LIQUID DISCHARGES
LIQUID DISCHARGE AND RECEIVING WATER CONCENTRATIONS
The liquid discharges of significant radionuclides
in 1972 are shown in the first two columns of Table 4 3*4.
The total release for the year was 0.38 curies excluding
tritium. The release from tritium was 200 curies. Table
4 also shows concentration of all nuclides in the discharge
canal (calculated on the basis of an annual canal flow of
7.24 x ID11 liters of water3*4). The receiving water
concentrations are based on a factor of ten dilution of
the canal flow *.
FISH INGESTION DOSE
The maximum fish ingestion dose is based upon fish
residing in discharge canal water, and the maximum individual
is assumed to consume 50 grams of fish per day. Table 5
shows the contribution of each radionuclide to the maximum
dose. The calculations described in Appendix F are from
Fowler, et al.,9 using concentration factors from Thompson,
et al. 10
11
-------
TABLE 4
MAXIMUM CONCENTRATIONS OF RADIONUCLIDES IN
STATION LIQUID DISCHARGES AND
RECEIVING WATER ADJACENT TO THE SITE
NUCLIDE
1-131
Cs-137
Cs-134
Co-60
Cr-51
Mn-54
Ag-HOm
Ru~106
Co-58
Nb-95
Ce-144
Ru-103
H-3
RELEASE
Ci/yr
4,5X1Q~3
7oOX10~2
4.4X10"2
4.2X10"2
3.1X10"3
2.5X10"3
3.3X10"3
8.9X10-3
7.9X10"3
loZXIO"1
3.8X10"2
3.2X10'2
20OX10+2
CONCo IN DISCHARGE3
CANAL yCi/cc (Cw)
6.3X10'12
9.7X10"11
eaxio"11
s.sxitr11
4.3X10"12
3,SX10-12
4,6X10~12
1.2X10'11
1.1X10"11
1.7X10"10
5..3X10-11
4.4X10"11
2.8X10"7
CONC0 IN RECEIVING13
WATER yCi/cc (Cw1 )
6.3X10'13
9.7X10"12
6.1X10'12
5.8X10-12
4.3X10~13
3.5X10"13
4.6X10'1 3
1.2X10'12
1.1X10'12
1.7X10'11
S»3X10-12
404X10-12
2o8X10~8
a - Annual discharge to Ciinal for 1972, 7.24X1011 liters from Safety
Guide 21 Data for 19723»4
b ~ Based on a dilution factor of 10 from the Final Environmental
Statement, Docket 50-244 USAEC1
12
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TABLE 5
INDIVIDUAL WHOLE BODY DOSE FROM
INGESTION OF LAKE FISH
NUCLIDE
1-1
Cs-
Cs-
Co-
Cr-
Mn-
Ag-
Ru-
Co-
Nb-
Ce-
Ru-
H-3
31
137
134
60
51
54
110m
106
58
95
144
103
MPCw 168hr
WK
WB Dose pCi
cc
2X10"3
2X10""
9X10"S
1X10"3
2X10"1
8X10"3
7X10"2
2X10"2
4X10"3
4X10°
3X10"1
8X10" 2
5X10" 2
CONC. FACTOR
(CF) gma
1.
4.
4.
2.
4.
1.
2.
1.
2.
3.
2.
1.
9 =
cc
5X101
OX102
OX102
OX101
0X1 01
OX102
3X10°
OX101
OX101
oxio1*
5X101
OX101
OX101
TOTALS
MAX. WBb
DOSE mrem
5.
2,
3.
1.
1.
5.
1.
6.
6.
1.
5.
60
5.
5.
yr
4X10"6
2X10"2
OX10"2
3X10"^
3X10"6
OX10"6
7X10"8
8X1Q-7
3X10-5
5X10""
OX10"7
3X10"7
7X10""
3X10"2
EXPECTED
WBC
DOSE mrem
yr
5.
2.
3.
1.
1.
5.
1.
6.
6.
I.
5.
6.
5.
5.
4X10"
2X10"
0X10"
3X10"
3X10"
0X10"
7X10"
8X10"
3X10"
5X10"
0X10"
3X10"
7X10"
3X10"
7
3
3
5
7
7
9
e
7
s
8
a
s
3
a -Thompson, S. E.,etal., (1972)10
b - Dose (mrem/yr)= 1.14X102.(Cw).CF / (MPCw)
c - Dose (mrem/yr)= 1.14X102.(Cw1).CF / (MPCw)
13
-------
The total whole body dose from canal derived fish is
2
5.3 x 10" mrem per year to the maximum individual. The
more realistic dose to a maximum individual would be from
fish in the receiving waters near the canal. This dose is
5.3 x 10" mrem per year, or a factor of ten less than the
discharge canal derived, dose.
The annual per capita population dose from fish ingestion
S 2
is 1.2 x 10" mrem per year which is equivalent to 1.5 x 10"
person-rent per year for the population within 50 miles of the
plant. The population dose assumes each member of the
population consumed 441 grams of fish per year. The dosages
take into account a dilution factor of 100 for receiving waters
relative to canal discharge levels.
Table 6 shows the maximum critical organ dose from fish
ingestion, both for the discharge canal and adjacent receiving
waters. The critical organ with the highest dose is the
lower large intestine with a maximum annual dose of 2.0 x
_ i
10 mrem.
DRINKING WATER DOSE
The whole body dose from drinking water to the maximum
individual is shown in Table 7 (according to calculations
from Appendix G). The maximum dose of 3.4 x 10~ mrem per year
is based upon a daily intake of 2,2 liters of water from the
canal discharge. The expected dose assumes the same intake
by the maximum individual from receiving waters adjacent to the
discharge canal.
14
-------
TABLE 6
DOSE TO CRITICAL ORGANS
FROM FISH INGESTION
CRITICAL ORGAN
Muscle
Spleen
Bone
Liver
Lower Large
Intestine
Thyroid
Body Tissue
RADIONUCLIDES
CONSIDERED
Cs-137
Cs-137
Ce-144
Cs-137, Mn-54,
Ce-144
Co-60, Co-58,
Cr-Sl, Mn-54,
Ag - 1 1 Om ,
Ru-106,
Ru-103,
Nb-95,
Ce-144
1-131
H-3
MAX. ORGAN
DOSE (mrem/yr)
2.2 x 10"2
2.2 x 10"2
1.9 x 10~6
2.2 x 10"2
2.0 x 10"
5.4 x 10"
9.6 x 10""
EXPECTED ORGAN
DOSE (mrem/yr)
2.2 x 10"3
2.2 x lO'3
1.9 x 10'7
2.2 x 10"3
2.0 x 10"
5.4 x 10"
9.6 x 10"
15
-------
TABLE 7
WHOLE BODY DOSE FROM THE
INGESTION OF WATER (mrem/yr)
ISOTOPE
1-133
Cs-137
Cs-134
Co-60
Cr-51
Mn-54
Ag-llOm
Ru-106
Co- 58
Nb-95
Ce-144
Ru-103
H-3
TOTAL :
MAX. DOSE
DISCHARGE CANAL
1.6 x 1(T5
2.4 X 10'3
3.4 x 10~3
2.9 x ICT*
1.1 x 10~7
2.2 x 1(T6
3.3 x 10~7
3.0 x 10'6
1.4 x 1C'5
2.1 x 10~7
8.8 x 1CT7
2.8 x 1CT6
2.8 x 10"2
3.4 x 10"2
1
EXPECTED DOSE
RECEIVING WATER
1.6 X 10~6
2.4 x 1Q~*
3.4 x 10-*
2.9 x 1(TS
1.1 x 1(T8
2.2 x 1(T7
3.3 x 10'8
3.0 x 10'7
1.4 x 10'6
2.1 x 10~8
8.8 x 10'8
2.8 x 10'7
2.8 x 10"3
3.4 x 10~3
16
-------
The population dose due to drinking water is based
upon the total domestic water supply of 6.7 x 107 gpd^
for a 50-mile radius and at a usage of 100 gpd per person.
The affected population is 6.7 x 10 persons. This gives
an equivalent of 0.23 person-rem per year or an annual
per capita dose of 1.9 x 10"4 mrem for the total population
within 50 miles of the plant. Since the domestic water
intakes are generally some distance from the Ginna plant,
a dilution of 100 for the discharge canal was assumed.
SWIMMING AND BOATING PATHWAY DOSE
The swimming dose rate in mrem per hour is derived
from the receiving waters concentrations in Table 4,
The water concentration is multiplied by the dose factors
listed in Table 8. The total dose is calculated to
be 9.0 x 10~8 mrem per hour according to Appendix H.
Assuming that the maximum individual swims 100 hours
per year, the maximum dose is 9.0 x 10"^ mrem per year.
Assuming that only 25 percent of the population swims,
one hour of swimming per individual per year-'- gives
an annual per capita dose of 2.3 x 10"^ mrem. This dose
is equivalent to 2.7 x 10"^ person-rem for the population
within 50 miles of the plant.
The dose rate from boating is assumed to be a factor
of 100 less than the swimming dose rate or equal to 9.0
x 10"10 mrem per hour. Assuming the maximum individual
17
-------
TABLE 8
IMMERSION DOSE FROM SWIMMING
ISOTOPE
1-131
Cs-137
Cs-134
Co-60
Cr-51
Mn-54
Ag-llOm
Ru-106
Co-58
Nb-95
Ce-144
Ru-103
H-3b
TOTAL :
DOSE FACTORa
mrem-cc/yCi-hr
6.8 x 10*
1.0 x 103
2,9 x 103
4.6 x 103
5.2 x 101
1.5 x 103
6.0 x 103
3.8 x 10Z
1.8 x 103
1.4 x 103
3.0 x 103
8.9 x 102
<; i.o x 10°
—
DOSE
(mrem/hr)
4.3 x 10-1»
9.7 x IQ'9
1.8 x ID'8
2.7 x 10"8
2.2 x 10"11
5.3 x 10~10
2.8 x 10-9
4.6 x 10-10
2.0 x 10-9
2.4 x 10-8
1.6 x 10-10
3.9 x 10-9
< 1.0 x 10-12
9.0 x 1Q-8
a - From HERMES - 1971
b - Beta dose to skin
18
-------
boats for 500 hours per year, the maximum dose is 4.5 x 10" mrem
per ysar. Assuming that only 25 percent of the population is
involved in boating, five hours of boating per individual per
9
year gives an annual per capita dose of 1.1 x 10~ mrem. This
dose is equivalent to a dose of 1.3 x 10" per person-rem for
the population within a 50 mile radius of the plant.
DOSE SUMMARY
Table 9 lists the dose summary for the pathways discussed
throughout this report. The maximum individual doses listed
in the table are based on the most likely situation rather
than on the most conservative situation possible. Pathway
locations and descriptions are given in the footnotes of the
table. The population dose values given in the last two columns
of Table 9 assume an adult population distributed within a
50-mile radius of the plant according to the 1970 population
figures . The total population doses for 1972 from Table
2
9 are 1.1 person-rem to the whole body and 1.5 x 10~ person-
rem to the thyroid.
Table 10 is a comparison of the dose summary to applicable
Federal regulations. The Appendix I design objectives are
the primary guides to meet the criterion "as low as practicable"
for radioactive material in light-water-cooled nuclear power
reactor effluents. The 1972 Ginna release data meet the Appendix
I recommendations for all modes of discharge and doses.
19
-------
TABLE 9
SUMMARY OF DOSES FROM GINNA FOR 1972
PATHWAY
Noble Gas Discharge
a. Whole Body
b. Skin
Swimming
Boating
Water Ingestion
Fish Ingestion
Iodine -Thyroid
(Inhalation
Pathway)
Iodine-Child
Thyroid (Milk
Pathway)
Iodine-Thyroid
(Vegetable Pathway
nondepleted cloud)
Natural Background
MAXIMUM
INDIVIDUAL
(mrem/yr)
6.5 x 10-2a
1.4a
9.0 x 10~«b
4.5 x 10-?c
3.4 x 10~2d
5.3 x 10-2e
8.1 x 10"2f
7.7 x 10-28
6.8 x 10~z£
1.3 x 102
AVERAGE
PER CAPITA
(mrem/yr)
7.5 x 10~ V
2.3 x 10-8
1.1 X ID'S
1.9 x 1Q-"
1.2 x ID'5
1.3 x IQ-sh
_ _ _
- - -
1.3 x 10
POPULATION
DOSE - 50 MILES
(person-rem)
8.8 x ID-1
2.7 x 10-5
1.3 x 10-6
2.3 x 10-i
1.5 x 10-2
1.5 x 10"2h
— _
. — _
1.6 x 105
•A -- 690 meters W, x/Q = 2.1 x 10" sec/ms
b -- Assumes 100 hours per year in receiving waters
c -- Assumes 500 hours per year in receiving waters
d -- Assumes 2.2 liters per day intake of receiving waters
e -- Assumes 50 grams of fish per day from receiving waters consumed
f -- 690 meters W, x/Q = 2.1 x 10"6 sec/m3, 4-year-old child,
depleted cloud
g -- 4667 meters WSW, x/Q = 4.5 x 10"8 sec/m3, 6-month-old child,
depleted cloud
h -- Assumes an adult thyroid
20
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TABLE 10
COMPARISON OF DOSES AND FEDERAL REGULATIONS
12
REGULATION
EFFLUENT MODE
RECOMMENDED LF.VEL
1972 GINNA RELEASE
App. I
App. I
App. I
App. I
A.pp. I
App. I
App, I
Liquids3
Liquidsb
Gamma Dose in Air
Beta Dose in Air
Air (Whole Body-
Critical Organ)
Air (Skin-Critical
Organ)
(Radioiodine
and Participates )
<3 mreni/yr/reactor
<10 mrem/yr/reactor
<100 x 10*mrad/yr/
reactor
<2.0 x lO'mrad/yr/
reactor
<5 mrem/yr/reactor
<15 mrem/yr/reactor
<15 mrem/yr/reactor
5.3 x 10~2 mrem/yr
2.0 x 10"1 mrem/yr
6.5 x 10"2 mrad/yr
1.4 mrad/yr
6.5 x 10"2 mrem/yr
1.4 mrad/yr
7.7 x 10"z mrem/yr
a--Whole body from all pathways
b--Any organ from all pathways
21
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APPENDIX A
AIREM--AIR DOSE MODEL5
The following is abstracted from the program manual.
"A Program to Calculate Airborne Pathway Radiation Doses
Sum of doses to up to four critical organs are treated.
Population doses are also calculated.
Radionuclide decay during time of flight is included.
First daughter product ingrowth and deposition is included.
Doses are calculated for those dose modes where the
product of the ground concentration and a dose conversion
factor equals dose. This includes inhalation transpiration,
and skin external beta doses. External gamma whole body
doses are calculated using a sector averaged finite cloud
method. External whole body gamma doses are calculated
using dose integrals calculated with a corrected and
slightly modified version of R. E. Cooper's EGAD
(R. E. Cooper, "EGAD - A Computer Program to Compute Dose
Integrals from External Gamma Emitters/' TID-4500, UC-32,
Savannah River Laboratory, Sept. 1972)'. A table of dose
integrals is generated for each facility according to the
stack height and the mean lid height for the facility. This
table is then interpolated according to energy and sigma Z.
Cloud depletion and ground deposition are included.
1/73 up to four expansion coefficients for deposition
velocity as a function of wind speed for each stability
class is used in the deposition and cloud depletion
calculation.
A sector averaged Gaussian diffusion model is used.
A single diffusion equation is solved repeatedly for each
sector (16) , radius (12) , stability class (6), and radio-
nuclide (20). (Numbers in parentheses are maximum numbers.)
Plume rise is not yet automatically included.
Dose due to standing in a field of radionuclides is not
yet included. Normally, such are trivially small.
(Dose and man-rem are outputs,)
Picocuries per square meter on the ground are also output.
The printout of this program is formatted for 16 sectors
But less can be run."
22
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APPENDIX B
NOBLE GAS SKIN SURFACE SUBMERSION DOSE CALCULATION13
Dose (mrem/yr) = (curies/yr) x -^ (sec/m3) x (dose conversion factor)
500 mrem/yr Ivr
Dose conversion factor - MpC(yci/cc) x 3.15 x 10' sec
Annual Conversion Skin Surface
Discharge x factor Submersion
Nuclide (Ci/yr) 77- (sec/ra3) mrem/sec dose (mr/yr)
^ yCi/cc
44.6 x 2.1x10"* x 159 = .015
485.14 x 2.1xlO"$ x 159 » .162
133Xe 10130.1 x Z.lxlO"6 x 52.8 = 1.12
8SKr 1143.62 x 2.1xlO"6 x 52.8 = .127
= Total Skin Surface Submersion Dose Rate = 1.42
23
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APPENDIX E
VEGETABLE CONSUMPTION DOSE CALCULATION14
By using the following equations, the thyroid dose
due to consumption of radioiodine contaminated leafy green
vegetables can be estimated:
DE 4 yr = 120-x'CF for a four-year old child
DE adult= 30-x-CF for an adult
WHERE: DE = thyroid dose equivalent rate
X - (pCi/m3) = Q (Ci/yr) x^X/Q(sec/m3)
3.17 x 10* pCi-Yr
Ci-sec
CF = fraction of a year in which vegetables
are consumed
A factor exp (~O.Q86t) should be included in this
calculation if a decay period is assumed between harvest
and ingestion (t is in days}.
26
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APPENDIX F
F. FISH INGESTION DOSE9*10
The fish ingestion dose is calculated for each nuclide
using the following equation:
np.rmrem) = i . 14 x 102 x (C ) (C.)/ (MDC )
v yr w f w
WHERE: C = water concentration in yCi/cc
w
Cf = concentration factor in Uli/gm
± pCi/cc
MFC = 168 hr maximum permissible concentration
w in pCi/cc
This equation applies to any critical organ when the
MFC is selected for that particular organ.
APPENDIX G
WATER INGESTION DOSE9
The water ingestion dose is calculated similarly to
the fish ingestion dose.
(Cd) (D)
- 5 x 103
(MFC )
w
WHERE: GJ - discharge concentration in pCi/cc
D = the dilution factor for the receiving waters
MFC,, ~ 168 hour maximum permissible concentration
W
in pCi/cc
27
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APPENDIX H
SWIMMING AND BOATING DOSE H
The dose from swimming is calculated using the
following equation:
= (Cd) (D) (DFs)
WHERE: C, = discharge concentration in ^Ci/cc
D = the dilution factor for the receiving
waters
DF = swimming dose factor in mr,em/hr
s pCi/cc
The boating dose is calculated in the same manner^ and
it is assumed the boating dose factor (DF^) is a factor
100 less than the swimming dose factor (DF ) .
28
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DEFERENCES
1 . Final Environmental Statement, R. E. Ginna Nuclear Power
Plant, TInTt~I, n.S. Atomic Energy Commision, Directorate
of Licensing, Washington, B.C., Bocket number 50-244,
December 1973.
2 • Deport on Releases of Radioactivity in Effluents and Solid
Wa^te from Nuclear Power Plants for 1972, IT.S. Atomic
Energy rommission, Directorate of Regulatory Operations,
Washington, B.C., August 1973.
3 . Semiannual Report for the Period of January to June, 1972 ,
Rochester Gas and Electric Corporation, docket Number
50-244, pp. 17-18, 1972.
4. Semiannual Report for the Period of July to December, 1972,
Rochester Gas and Electric Corporation, Boclcet Number
50-244, pp. 74-75, 1973.
5. Martin, J. A., Jr., C. B. Nelson, and P. A. Tuny, AIREM
Program Manual -A Computer Code for Calculating poses,
and Ground depositions T)ue 'to Atmospheric Emissions of
Radi onucl i d ejs , "TtTS^ Environmental Protection Agency, Office
or" R"adiation Programs, Field Operations Division, Washington,
n.C. 20460, May 1974, EPA-520/1-74- 004 .
6 . Rochester Gas and Electric Corporation, R. E. Ginna Nuclear
Power Plant. Unit 1? Environmental Report, U.S. Atomic
Energy rommission, Docket Number 50-244, Washington, B.C.,
August 1972.
7. Fowler, T. W. , et al., HIS Guidelines- -Guideline Number 4--
Thyroid Hose Equivalent ~HR°JTte~'TVue to the Inhalation o^ ISlj",
U.S . Hnvironmental" Protection Agency, Office of Radiation
Programs, Technology Assessment Division, Washington, B.C.,
October 15, 1973, (Unpublished).
8. Fowler, T. W. , et al., FIS Huidel ines - - Huidel ine Number
'
5-- Thyroid ^pse EquiyaTent R'ate^ue to the Ingestion of
I31j ^ia the Milk Pathway? TT«S". Environmental Protection
AgencyT Office of "Radiation Programs, Technology Assessment
Division, Washington, B.f., October 16, 1973, (Unpublished).
Fowler, T. W. , et al., EIS Guidelines- -Huideline Number
8- -Liquid Discharge Dose RaTejComputat ion -~fi~r inking Water
and Fish Tngestion, Ti.S~ Environmen'tal Protection Agency,
Office of Radiation Programs, Technology Assessment Bivision,
Washington, B.C., June 1973, (Unpublished).
29
-------
10. Thompson, S. H. , et al., Concentration Factors of Chemical
Elements in Edible Aquatic"Organismst Lawrence Livermore
Laboratory, Livermore, California,1JCRL-50564, Rev. 1,
October 1972.
11. Fletcher, J. F. and W. L. Dotson, HERMES--A Digital
Computer Code for Estimating Regional Radiological
FffecTsfrom the Nuclear Power IndHstry, Hanfor3
Engineering Development Laboratory,U.S. AEC, Richland,
Washington, HEDL-TME-71-168, IIC-80, December 1971.
12. Title 10 Code ofFederal Regulations, Part 50j Appendix I.
13. Fowler, T. W., EIS Guidelines-Guideline Number 3--Air
Submersion Skin Surface Dose Rate from Noble Gase_s,
TOTEnvironmental Protection Agency, OTfice ofRadiation
Programs, Technology Assessment Division, Washington, D.C.,
May 9, 1973, (Unpublished).
14. Zoon, R. A., EIS Guidelines--Guideline Number 13--Thyroid
Dos e^_Equiya lent Rate from Ingest ion of Leafy Green
VegFtablFs Contaminated witE fbdine-131. U.S., Environmental
Protection Agency, Office of Radiation Programs, Technology
Assessment Division, Washington, B.C., August 1973,
(unpublished).
30
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TECHNICAL REPORT DATA
(Please read laaniclions on the reverse before completing/
1 REPORT NO, 2. 3, RECIF
QRP/LV-75-3
4. TITLE ANO SUBTITLE 5. HEPO
Individual and Population Doses for 1972 Nov
Discharges From the Ginna Nuclear Power e. PERF<
Plant, Unit Number One
7, AUTHOR(S) 8. PEHF
Joseph A. Cochran and Thomas R. Horton
9, PERFORMING ORGANIZATION NAME AND ADDRESS 10. PRO
Office of Radiation Programs-Las Vegas Facility
U.S. Environmental Protection Agency 11. CON
Las Vegas, Nevada 89114
12. SPONSORING AGENCY NAME AND ADDRESS 13. TYP
Tech
Same as #9 '4-SP0'
lENT'S ACCESSION-NO.
RT DATE
smber 1975
DRMING ORGANIZATION CODE
DRMING ORGANIZATION REPORT NO.
QRAM ELEMENT NO.
TRACT/GRANT NO,
E OF REPORT AND PERIOD COVERED
rticsl Not** — Final
MSORING AGENCY CODE
15. SUPPLEMENTARY NOTES
16. ABSTRACT
This report presents the results of a study to determine the dose
to the population in the vicinity of the Ginna Nuclear Power Plant
(located in New York State) based upon 1972 discharge data. Doses
calculated from release data are compared with current standards.
This report fulfills the need to document the actual environmental
impact of operating nuclear power reactors in contrast to Final
Environmental Statement (FES) projections.
17, KEY WORDS AND DOCUMENT ANALYSIS
a. DESCRIPTORS b. IDENTIFIERS/OPEN ENDi
Nuclear Reactors Ginna Nuclear
Nuclear Radiation Power Plant
Environmental Surveys Environmental
Dosimetry Radioactivi
13, DISTRIBUTION STATEMENT 19. SECURITY CLASS (Thi$~l
Unclassified
„ , . «, . , • 20, SECURITY CLASS (This I
Release to Public
„, .__ Unclassified
O TERMS c. COS ATI Field/Group
1809
1808
0510
0618
ty
leportj 21. NO. OF PAGES
37
•sage) 22. PRICE
EPA Form 2220-1 (9-73)
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