ML20072C114
| ML20072C114 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 02/28/1983 |
| From: | Birch M, Mcintosh M DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20072C084 | List: |
| References | |
| PROC-830228-04, NUDOCS 8303080324 | |
| Download: ML20072C114 (96) | |
Text
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0FFSITE DOSE CALCULATION MANUAL i
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DUKE POWER NUCLEAR STATIONS t
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TABLE OF CONTENTS SECTION Paga INTRODUCTION iii 1.0 RELEASE RATE CALCULATIONS 1-1 1.1 LIQUID EFFLUENTS 1-1 1.2 GASEOUS EFFLUENTS 1-1 1.2.1 Noble Gases 1-1 1.2.2 Radioiodines, Particulates, and Others 1-2 2.0 RADIATION MONITORING SETPOINTS 2-1 2.1 LIQUID MONITORS 2-1 2.2 GAS MONITORS 2-1 3.0 DOSE CALCULATIONS 3-1 3.1 DOSE MODELS FOR MAXIMUM EXPOSED INDIVIDUAL 3-1 3.1.1 Liquid Effluent 3-1 3.1.2 Gaseous Effluents 3-2 3.1.2.1 Noble Gases 3-2 3.1.2.2 Radioiodines, Particulates, and Others 3-3 Os 3.1.3 Direct Radiation 3-7 3.2 SIMPLIFIED DOSE PROJECTIONS 3-7 3.3 FUEL CYCLE CALCULATIONS 3-8 3.3.1 Milling 3-8 3.3.2 Conversion 3-8 3.3.3 Enrichment 3-8 3.3.4 Fuel Fabrication 3-8 3.3.5 Nuclear Power Production 3-9 3.3.6 Fuel Reprocessing 3-9 Appendix A Oconee Nuclear Station Site Specific Information Appendix B McGuire Nuclear Station Site Specific Information Appendix C Catawba Nuclear Station Site Specific Information i
'~'%
LIST OF TABLES Table 1.2-1 Dose Factors for Noble Gases and Daughters Table 1.2-2 Dose Parameters for Radiciodines and Radioactive Particulate, Gaseous Effluents Table 3.1-1 Bioaccumulation Factors to be Used in the Absence of Site Specific Data Table 3.1-2 Ingestion Dose Factors for Adults Table 3.1-3 Ingestion Dose Factors for Teenager Table 3.1-4 Ingestion Dose Factors for Child Table 3.1-5 Ingestion Dose Factors for Infant Tabla 3.1-6 Inhalation Dose Factors for Adults Table 3.1-7 Inhalation Dose Factors for Teenager Table 3.1-8 Inhalation Dose Factors for Child fable 3.1-9 Inhalation Dose Factors for Infant Table 3.1-10 External Dose Factors for Standing on Contaminated Gr(und Table 3.1-11 Stable Element Transfer Data Table 3.1-12 R Values - Ground Pathway - All Ages Table 3.1-13 R Values - Vegetable Pathway - Adult Table 3.1-14 R Values - Vegetable Pathway - Teenager Table 3.1-15 R Values - Vegetable Pathway - Child
(~'N Table 3.1-16 Rt Values - Meat Pathway - Adult (s,,)
Table 3.1-17 Rt Values - Meat Pathway - Teenager Table 3.1-18 Rt Values - Meat Pathway - Child Table 3.1-19 R Values - Cow Milk Pathway - Adult Table 3.1-20 R Values - Cow Milk Perhway - Teenager Table 3.1-21 R Values - Cow Milk Pathway - Child Table 3.1-22 R Values - Cow Milk Pathway - Infant Table 3.1-23 R Values - Goat Milk Pathway - Adult Table 3.1-24 Rt Values - Goat Milk Pathway - Teenager Table 3.1-25 RfValues-GoatMilkPathway-Child Table 3.1-26 K.' Values - Goat Milk Pathway - Infant Table 3.1-27 Rt Values - Inhalation Pathway - Adult Table 3.1-28 Rt Values - Inhalation Pathway - Teenager Table'3.1-29 Rt Values - Inhalation Pathway - Child Table 3.1-30 R[ Values-InhalationPathway-Infant x
ii
INTRODUCTION V
The Offsite Dose Calculation Manual provides the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents to assure compliance with the dose limitations of the Technical Specifications. These dose limitations assure that:
1) the concentration of radioactive liquid effluencs from the site to the unrest eicted area will be limited to che concentration levels of 10CFR20, Appendix B, Table II; 2) the exposures to any individual from radioactive liquid effluents will not result in doses greater than the design objectives of 10CFR50, Appendix I; 3) the dose rate at any time at the site boundary from radioactive gaseous effluents will be limited to the annual dose limits of 10CFR20 for unrestricted areas; and 4) the exposure to any individual from radioactive gaseous effluents will not result in doses greater than the design objectives of 10CFR50, Appendix I.
The methodology used to assure compliance with the dose limitations described above shall also be used to prepare the radioactive liquid and gaseous effluent
('"N reports required by the Technical Specifications. To assure compliance with 40CFR190 when twice the design objectives of 10CFR50, Appendix I are exceeded,
,s the methodology and parameters to be used in calculating the off-site dose to any individual resulting from the entire fuel cycle except mining and waste management facilities are provided in this Manual.
The Manual also provides the methodology and parameters to be used in the calculation of radioactive liquid and gaseous effluent monitoring instrumen-tation alarm / trip setpoints to assure compliance with the concentration and dose rate limitations of the Technical Specifications. Changes to the method-ology and parameters used in this Manual shall be reviewed by a qualified re-viewer (s) and approved by the Station Manager and the System Radwaste Engineer prior to implementation and shall be audited by the Nuclear Safety Review Board. Changes to this Manual shall be submitted to the Nuclear Regulatory Commission in accordance with plant Technical Specifications.
Normally GASPAR and LADTAP are used for the calculation of offsite doses but this document also describes a method for the calculation of offsite doses when GASPAR and/or LADTAP are not available.
This Manual does not replace any station implementing procedures.
C)
iii l
i 1.0 RELEASE RATE CALCULATIONS The release rate calculations presented in the following sections are site release limits. Sites containing two or more units shall administratively control releases to assure that the release rate calculations limit releases as stated in the Technical Specifications. Administrative controls could limit the number of releases occurring at one time and/or apportion the releaserate bets.een the units.
1.1 LIQUID EFFLUENTS To comply with Technical Specifications and to assure that the concentration of radioactive liquid effluents from the site to the unrestricted area is limited to the concentrations of 10CFR20, Appendix B, Table II, Column 2, the following release rate calculation shall be performed:
n C
f $ F + (a I 1 )
i=1 MPC.I where:
C.
= The concentration of radionuclide, 'i', in undiluted liquid effluent, 1
in pCi/ml.
MPC = the concentration of radionuclide, 'i', from 10CFR20, Appendix B, Table 1
{~'N II, Column 2, in pCi/ml.
/
.sms f
= the undiluted effluent flow from the tank, in gpm.
F
= the dilution flow from the site discharge structure to unrestricted area receiving waters, in gpm.
a
= recirculation factor at equilibrium; this factor account; for the fraction of discharged water reused by the station; this factor is one for stations on rivers or lakes where discharged water cannot be reused, and varies for sites where water is recirculated and is specified in the appropriate Appendix.
1.2 GASEOUS EFFLUENTS In order to comply with the Technical Specifications and to assure that the dose rate, at any time, in the unrestricted area due to radioactive materials released in gaseous effluents from the site is limited to 1500 mrem /yr to the total body and 13000 mrem /yr to the skin for the noble gases and is limited to $1500 mrem /yr to any organ for all radioiodine and for all radioactive materials in particulates form and radionuclides other than noble gases with half lives greater than 8 days, the following release rate calculations shall be performed. These calculations, when solved for ' f', i.e. flowrate, are the release rates for noble gases and for radioiodines, particulates and other radionuclides with half-lives greater than 8 days. The most conservative of release rates calculated shall control the release rate.
O i V 1-1
1.2.1 Noble Gases s
IK x [(X/Q)Q ]
<500 mrem /yr, and g
g 1
I (Lt + 1.1 M ) [(X/Q)Q ]
<3000 mrem /yr g
g i
where:
K
= The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in eres/yr per pCi/m3 from Table 1.2-1.
L.
= The skin dose factor due to beta emissions for each identified noble gas radioriaclide, in eres/yr per pCi/m3 from Table 1.2-1.
M.
= The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mead /yr per pCi/m3 from Table 1.2-1 (unit con-version constant of 1.1 ares / mrad converts air dose to skin dose).
P
= The dose parameter for radionuclides other than noble gases for the t
inhalation pathway, in ares /yr per pCi/m3 from Table 1.2-2.
The dose factors are based on the critical individual organ and most restric-tive age group (child or infant).
s Q*.
= The release rate of radionuclides, 'i', in gaseous effluent from all release points at the site, in pCi/sec.
X/Q = The highest calculated annual average dispersion parameter for any area at or beyond the unrestricted area boundary.
W
= The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location.
s Q
=kCf+k2 = 4.72E+2 C f i g g
g where:
C. = the concentration of radionuclide, 'i', in undiluted gaseous effluent, in pCi/ml.
f = the undiluted effluent flow, in efm.
3 k = conversion factor, 2.83E+04 ml/ft.
t k2 = conversion factor, 6.0E+01 sec/ min.
1.2.2 Radioiodines, Particulates, and Others s
IPg [W Q ] < 1500 mrem /yr g
1
)
I where the terms are as defined above.
1-2 i
O O
O TABLE 1.2-1 (1 of 1)
DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS
- 4 Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K.
L.
M.
N.
Radionuclide (arem/yr per pCi/m )
(wrem/yr p8r pCi/m )
(arad/yr per pCi/m )
(arad/yr per pCi/m )
3 8
3 3
Kr-83m 7.56E-02**
1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E103 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 i
Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.b6E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03
- The listed dose factors are for radionuclides that may be detected in gaseous effluents.
- 7.56E-02 = 7.56 x 10 2,
DO f)\\i (G
V.
TABLE 1.2.-2 Il of 1)
DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE PARTICULATE, GASEOUS EFFLUENTS
- P(I), DOSE PARAMETERS FOR RADI0 IODINES AND RADI0 ACTIVE PARTICULATES IN GASEOUS EFFLUENTS Pathway Pathway Inhalation Inhalation (arem/yr per (ares /yr per 3
3 Radionuclide Ci/m )
Madionuclide Ci/m )
H3 1.125 E+03 RU 103 6.625 E+05 Alpha Act 1.100 E+08 RU 106 1.432 E+07 P 32 2.605 E+06 AG 110M 5.476 E+06 CR 51 1.698 E+04 CD 115M 2.920 E+05 MN 54 1.576 E+06 SN 123 3.550 E+06 FE 55 1.110 E+05 SN 126 1.120 E+07 FE 59 1.269 E+06 SB 124 3.240 E+06 CO 58 1.106 E+06 SB 125 2.320 E+06 CO 60 7.067 E+06 TE 127H 1.408 E+06 NI 63 8.214 E+05 TE 129M 1.761 E+06 ZN 65 8.399 E+04 CS 134 1.014 E606 RB 86 1.983 E+05 CS 136 1.709 E+05 SR 89 2.157 E+06 CS 137 9.065 E+05 SR 90 1.010 E+08 BA 140 1.743 E+06 Y 91 2.627 E+06 CE 141 5.439 E+05 ZR 95 2.231 E+06 CE 144 1.195 E+07 NB 95 6.142 E+05 I 131 1.624 E+07 MO 99 1.354 E+05 I 133 3.848 E+06
- Table provided by:
H. E. Wangler, RAB:NRR:NRC on 12/8/82
d J
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2.0 RADIATION MONITORING SETPOINTS Effluent radiation monitor alarm / trip setpoints shall be determined using the i
calculations presented in the following sections. The calculations define the relationships between the measured effluent activity, the maximum allowable effluent activity, the effluent flowrate, and the dilution available in the restricted area (as defined for effluent releases in the Technical Specifica-(
tions) which must be controlled to assure that the instantaneous release rate is not exceeded.
The setpoints shall be determined for those monitors listed in the appropriate tables of the Technical Specifications.
2.1 LIQUID MONITORS The fcilowing equation shall be used to calculate liquid radiation monitor setpoints:
4 S NPC y
g 1
where:
2 HPC = the effluent concentration limit implementing 10CFR20 for the site, in pJi/ml.
C = the radioactivity concentration in pCi/ml, in the effluent line prior to dilution and subsequent release, which may be the setpoint and, if so, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10CFR20 in the unrestricted area.
i = the flow measured at the radiation monitor location in gps.
j I
F = the dilution water flow as measured prior to the release point in gpm.
(Note that if no dilution is provided, C 1 MPC. Also, note that when (F) is j
large compared to (f), then F + f E F.)
2.2 GAS MONITORS The following equation shall be used to calculate noble gas radiation monitor setpoints based on Xe-133:
s
(
K (X/Q)Qg < 500 g
D = 4.72E+2 C f (See Section 1.2.1) f where:
the gross activity in undiluted effluent, in pCi/ml.
C =
i the flow from the tank or building and varies for various release f =
sources, in efm.
2-1
.. -.- -..-. -...-... -. _.-.--.-..~ -.
i i
j i
l J..
i K
=
i from Table 1.2-1 for xe-133, 2.94E+2 mrem /yr per pCi/m.
3 X/Q the highest calculated annual average dispersion parameter for
=
I any area at or beyond the unrestricted area boundary for long term I
releases.
1-4 5
i t
l J
1 I
L
^
t
.l i
1 i
j I
1 1
i i
4 4
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p b
i I
2-2 l
(
l l
t--.-,,, - _ _...,, -,.,_., _ _ _ _ _ _ _.. - _. - -..
, _ _ _ _ _ _.., - -,.... ~... _.., - - - - _ -..- ___
3.0 DOSE CALCULATIONS 3.1 DOSE MODELS FOR MAXIMUM EXPOSED INDIVIDUAL 3.1.1 Liquid Effluents Of the possible exposure pathways in the aqu tic environment, only two contribute significantly to the total dose; these pathways are ingestion of potable water and aquatic foods. The dose contributions, from these path-ways, for measured quantities of radioactive materials identified in liquid effluents released to unrestricted areas shall be calculated for the maxi-mum exposed individual in each age group using:
m D = I [A I Atg Cgg g F]
7 ait i
!=1 where:
D = the cumulative dose commitment to the total body or any organ, at I, for an individual of age group, a, from the liquid effluent a
for the total time period I atg, in mrem.
1=1 at = the length of the fth time period over which C and F are g
g g
averaged for all liquid releases, in hours.
Cg= the average concentration of radivenclide, 'i', in undiluted liquid effluent during time period at from any liquid release, in g
pCi/ml.
Fg = the near field average dilution factor for C during any liquid g
effluent release where:
'" =-
F2=F+f where:
a = recirculation factor at equilibrium; this factor accounts for the frac-tion of discharged water reused by the station. This factor is one for stations on rivers or lakes where discharged water cannot be reused I
and varies for sites where water is recirculated.
It is specified in the j
appropriate Appendix.
f = liquid radwaste flow, in gpm.
F = dilution flow, in gpm.
A.
= the site related ingestion dose commitment factor for an individual of age group, a, to the total body or any organ,
'I',
for each identi-fied principal gamma and beta emitter, mrem /hr per pCi/ml.
d A
= 1.14E+05 (U,y/D + U,gBF )DF,17 g
1 3-1 L
l
where:
8 3
1.14E5 = 10 pCi/pCi x 10 ml/kg + 8760 hr/yr.
U,, = Water consumption by age group, A/yr.
infant 330 child 510 teen 510 adult 730 i
D,= Dilution factor from the near field area to the potable water intake.
U,f = fish consumpcion by age group, kg/yr.
infant child 6.9 teen 16 adult 21 BFg = Bioaccumulation factor for radionuclide, 'i', in fish, pCi/kg per pCi/1, from Table 3.1-1.
DF,g7 = Dose conversion factor for radionuclide, 'i', by age group in pre-selected organ, T, in arem/pCi, from Tables 3.1-2, 3.1-3, 3.1-4, and 3.1-5, respectively.
Using the above information, A.I values for the adult have been calculated for each site. This informati$d is s:ovided in the Table "X" 5.0-4 where "X" O
is the appendix for the site in question.
3.1.2 Gaseous Effluents The dose contributions from measured quantities of radioactive materials identified in gaseous effluent released to unrestricted areas shall be cal-culated for the maximum exposed individual using the following equations:
3.1.2.1 Noble Gases For gamma radiation:
s D = 3.17 E-8 I Mg[(576)Q]
g i=1 For beta radiation:
s p = 3.17 E-8 I Ng [(X/Q) Q ]
D g
t=1 where:
3.17E-08 = The inverse of the number of seconds in a year.
M.
= The air dose factor due to gamma emissions for each identified 3
noble gas radionuclide, in mrad /yr per pCi/m from Table 1.2-1.
CI 3-2
l i
N.
= The air dose factor due to beta emissions for each identified d
noble gas radionuclide, in mrad /yr per pCi/m from Table 1.2-1.
3 X/Q = The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary.
s Q
= The release of noble gas radionuclides, 'i', in gaseous effluents, 1
in pCi.
l 3.1.2.2 Radioiodines, Particulates, and Others These calculations apply to all radioiodines, radioactive materials in partic-ulate form and radionuclides other than noble gases with half-lives greater than 8 days:
s 4
D = 3.17 E-8 I Rg [WQ ]
g 1
where:
3.17E-08 = The inverse of the number of seconds in a year.
Q*. = The release of radioiodines, radioactive materials in particulate form 3'
and radionuclides other than noble gases in gaseous effluents, 'i',
in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate.
W = The annual average dispersion or deposition parameter for estimating the dose to an individual at the controlling location.
3 W = (X/Q) for the inhalation pathway, in sec/m.
W = (D7Q) for the food and ground plane pathways, in meters 2, R. = The dose factor for each identified radionuclide, 'i', in m2 (mrem /yr) per 3
pCi/sec or mrem /yr per pCi/m, for each pathway.
(Tables 3.1-12 + 3.1-30) where:
Inhalation Pathway Factor, RI [X/Q]
g Rf [X/Q] = K'(BR), (DFA ), (mres/yr per pCi/m )
3 g
where:
K'
= a constant of unit conversion, 108 pCi/pCi.
3 (BR), = the breathing rate of the receptor of age group (a), in m /yr.
The breathing rates (BR) for the various age groups are tabulated below, as D
given in Regulatory Guide 1.109.
)
t 3-3
Age Group (a)
Breathing Rate (m /yr) 3 Infant 1400 Child 3700 Teen 8000 Adult 8000 (DFA.)* = the maximum organ inhalation dose factor the receptor of age group (a) for the ith radionuclide, in ares /pCi. The total body is con-sidered as an organ in the selection of (DFA.)*.
See Tables 3.1-6, 3.1-7, 3.1-8, and 3.1-9.
Inhalation dose factors (DFA ) for the various age groups are given in g
Tables 3.1-6, 3.1-7, 3.1-8, an8 3.1-9 (taken from Regulatory Guide 1.109 (Rev.1)).
GroundPlanePathwayFactor,Rf[D/Q]
Rf[D/Q]=K'K"(SF)DFG[(1-e-i )/A ] (m2. mee. fyr per pCi/sec) g g
where:
K'
= a constant of unit conversion, 10s pCi/pCi.
K"
= a constant of unit conversion, 8760 hr/ year.
A
= the decay constant for the ith radionuclide, sec1 f
t
= the exposure time, 4.73 x los sec (15 years).
DFG. = the ground plane dose conversion factor for the ith radionuclide (mrem /hr 2
^
per pCi/m ),
SF
= the shielding factor (dimensionless), 0.7 (Regulatory Guide 1.109 (Rev. 1)).
Ground plane dose conversion factors, DFG, are found in Table 3.1-10.
Grass-Cow-MilkPathwayFactor,Rf[D/Q]
l
( * + (1-f f )e"^i h
~
Q (U* )'
ff
-A.t Rf[D/Q]=K'E
,{
F,(r)(DFL ),
F Ps if e
g
.I w
p s
2 (m
mrem /yr per pCi/sec) i where:
l K'
= a constant of unit conversion, 10 pCi/pCi.
8 Q
= the cow's consumption rate, in kg/ day (wet weight), (Regulatory F
i Guide 1.109 (Rev. 1)). (Milk cow = 50, Beef Cattle = 50, Goats = 6).
i I
t 3-4 t
n,., - - - -
/O U
= the receptor's milk consumption rate for age (a), in liters /yr.
Q ap j
ap (liters /yr) - Infant 330 U
- Child 330
- Teen 400
- Adult 310 (Regulatory Guide 1.109 (Rev. 1))
Y
= the agricultural productivity by unit area of pasture feed grass, P
2 in kg/m, 0.7.
Y
= the agricultural productivity by unit area of stored feed, in 8
2 kg/m, 2.0.
F,
= the stable element transfer coefficients, in days / liter, Table 3,1-11.
r
= fraction of deposited activity retained on cow's feed grass, r = 1 for radioiodine and r = 0.2 for particulates (Regulatory Guide 1.109).
(DFL.)* = the maximum organ ingestion dose factor for the ith radionuclide for the receptor in age group 'a',
in mrem /pci. See Tables 3.1-2, 3.1-3, 3.1-4, and 3.1-5.
~1 A
= the decay constant for the ith radionuclide, in sec g
A
= the decay constant for removal of activity on leaf and plant surfaces 7
~1 by weathering, 5.73 x 10 sec (corresponding to a 14 day half-life).
3 e
(,
t
= the trans ort time from pasture to cow, to milk, to receptor, in sec, g
1.73 x 10 (2 days).
t
= the transport time from pasture, to harve.5,., te cow, tc milk, to re-h ceptor, in sec, 7.78 x 10s (90 days).
f
= fraction of the year that the cow is on pas.ture fdimensicaless), 1.0.
l f
= fraction of the cow feed that is pasture grass while the cow is on s
pasture (dimensionless), 1.0.
E
= an adjustment fraction which accounts for the fraction of radionu-clides in elemental form which contribute dose for this pathway, E = 0.5 for radioiodine, E = 1.0 for all others.
The concentration of tritium in milk is based n the airborne concentration C
rather than the deposition. Therefore, the R is based on (X/Ql:
g Rh[X/Q]=K'K'"FQUm F ap(DFL.)a [0.75(0.5/H)] (mrem /yr per pCi/m )
3 1
t where:
K'"
= a constant of unit conversion, 103 gm/kg.
3 H
= absolute humidity of the atmosphere, 8 gm/m, (Regulatory Guide 1.109) 3-5
O 0.75 = the fraction of total feed that is water.
0.5
= the ratio of the specific activity of the feed grass water to the atmos-pheric water.
Grass-Cow-Meat Pathway Factor, R" [D/Q]
The integrated concentration in meat follows in a similar manner to the develop-ment for the milk pathway, therefore:
R" [D/Q] = K' p *P) ff (1-f f Je'^i h
-A.t t
Q (U PS ps if F (r)(DFL.)a Y,
Y e
1 Ai+A f
1 w
p s
(m2. ares /yr per pCi/sec) where:
F = the stable element transfer coefficients, in days /kg, Table 3.1.'1.
g U
= the receptor's meat consumption rate for age (a), in kg/yr.
ap (kg/yr) - Infant U
0
- Child 41
- Teen 65
- Adult 110 Taken from Regulatory Gnide 1.109 (Rev. 1).
t
= the transport time from pasture to recept.or, in sec.
g t
= the transport time from crop field to receptor, in sec.
h The concentration of tricium in meat is based on its airborne concentration g
rather than the deposition. Therefore, the R is based on [X/Q]:
g R [X/Q] = K'K'"F Q U,p(DFL ), [0.75(0.5/H)] (mrem /yr per pCi/m )
3 fp g
where all terms are defined above.
Vegetation Pathway Factor, R [D/Q]
l The integrated concantration in vegetation consumed by man follows the expres-sion developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differs only in the time petiod between harvest and consumption, therefore:
-A.t
-A.t RY[D/Q]=K'
(#)
b 3
ih 1
Y (A + A )
(DFL.)a Ufe
+Ufe l
t aL ag y g y
(m2. airem/yr per pCi/sec) 1 where:
Q K' = a constant of unit conversion, 108 i
pCi/pCi.
3-6 I
U = the consumption rate of fresh leafy vegetation by the receptor in age x
group (a), in kg/yr.
(kg/hr) - Infant 0
L =
- Child 26
- Teen 42
- Adult 64 U = the consumption rate of stored vegetation by the receptor in age group (a), in kg/yr.
- Child 520 Teen 630
- Adult 520 fg = the fraction of the annual intake of fresh leafy vegetation grown locally.
f = the fraction of the annual intake of stored vegett, tion grown locally.
g g = the average time between harvest of leafy vegetation and its consumption, t
4 in seconds, 8.6 x 10 (1 day).
h = the average time between harvest of stored vegetation and its consumption, t
in seconds, 5.18 x 10s (60 days).
2 Y = the vegetation area density, 2.0 kg/m,
-~
v (G
and all other factors are previously defined.
Theconcentrationoftritiuminvegetationisbasegontheairborneconcentra-tion rather than the deposition. Therefore, the R is based on [X/Q]:
g RY[X/Q]=K'K'"
3 3
Uf (DFL.)a
[0.75(0.5/H)] (mrem /yr per pCi/m ).
,at+Uf 1
ag, I
All terms defined previously.
3.1.3 Direct Radiation Direct radiation is that radiation from confined sources and does not include any external component from radioactive effluents. The point kernel method has been used to calculate offsite dose rates from radioactive materials stored in the refueling water storage tanks, reactor makeup water storage tanks, and temporary on-site radwaste storage tanks. Dose calculations using this method performed for Duke Nuclear Stations indicate direct radiation doses are much less than 0.01 mrem /yr. and, therefore, makes a negligible contribution to individual dose. Direct radiation doses will not be calculated routinely.
3.2 SIMPLIFIED DOSE PROJECTIONS To estimate the cumulative dose contributions to the maximum exposed individ-ual for 31 day dose projection calculations, the calculations presented in Section 3.1 can be simplified. The simplified calculations would be for an v
individual in the critical population using only data for the critical pathway l
3-7
()s and critical radionuclide(s). Critical per.ulations, critical pathways, and (s,
critical radionuelides have been determined for each Duke Nuclear Station from the dose calculations performed to evaluate compliance with Appendix I to 10CFR50.
Simplified 31-day dose projection calculations are presented in the section on site specific information.
3.3 FUEL CYCLE CALCULATIONS In accordance with the requirements of 40CFR190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millireas to the total body or any organ with the exception of the thyroid which is limited to 75 millirems.
In accordance with the requirements of the Technical Specifications, the annual dose commitment shall also be calculated any time that one of the quarterly dose limits of the Technical Specifications is exceeded; these annual dose commitments may not just be calculated for the calendar year.
The " Uranium fuel cycle" is defined in 40CFR Part 190.02(b) as:
" Uranium fuel cycle means the operations of milling or uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fab-rication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the pro-duction of electrical power for public use utilizing nuclear energy, r"~
but excludes mining operations, operations at waste disposal sites,
(,j) transportation of any radioactive material in support of these opera-tions, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle."
Based on this definition of the fuel cycle and the information in 10CFR51 Table S-3 and WASH-1248, the radiological impact of the following operations has been assessed for Duke Nuclear Stations:
3.3.1 Milling No milling operations occur within fifty miles of any Duke Nuclear Station.
The increment of dose from milling operations to any individual within fifty l
miles of any Duke Nuclear Station is negligible.
3.3.2 Conversion No uranium hexafluoride production occurs within fifty miles of any Duke Nuclear Station. The increment of dose from UFs production to any individual within fifty miles of any Duke Nuclear Station is negligible.
3.3.3 Enrichment j
No uranium enrichment operations occur within fifty miles of any Duke Nuclear Station. The increment of dose from enrichment operations to any individual within fifty miles of any Duke Nuclear Station is negligible.
s 3-8 l
3.3.4 Fuel Fabrication No fuel fabrication operations occur within fifty miles of any Duke Nuclear Station. The increment of dose from fabrication operations to any individual within fifty miles of any Duke Nuclear Station is negligible.
3.3.5 Nuclear Power Production The production of electricity for public use using light-water-cooled nuclear power stations results in increments of dose to individuals within fifty miles of any station due to liquid and gaseous effluent releases and direct. radiation or skyshine. The increments of dose resulting from liquid and gaseous effluent releases will be calculated using the methodology presented in Sections 3.1.1 and 3.1.2.
The dose from direct radiation, skyshine, and radiation from the station storage facilities has been estimated using conservative assumptions (see Section 3.1.3), the estimates of this dose will be presented in the section on site specific information.
In certain situations more than one nuclear power station site may contri-bute to the doses to be considered in making fuel cycle dose assessments in accordance with 40CFR190. Situations involving more than one station will be presented in the section on site specific information.
3.3.6 Fuel Reprocessing No fuel reprocessing optrations occur within fifty miles of any Duke Nuclear
(s Station. The increment of dose from reprocessing operations to any individual 4
(s,jj within fifty miles of any Duke Nuclear S.tation is negligible.
To summarize, only dose increments from nuclear power production operations (Section 3.3.5) need be considered in calculations to demonstrate compliance with the requirements of 40CFR190.
O l
3-9
TABLE 3.1-1*
(1 of 1)
BI0 ACCUMULATION FACTORS T6 BE USED IN THE ABSENCE OF SITE-SPECIFIt. DATA 0"
(pCi/kg per pCi/ liter)
FRESHWATER ELEMENT FISH INVERTEBRATE H
9.0E-01 9.0E-01 Na 1.0E-02 2.0E 02 Cr 2.0E 02 2.0E 03 Mn 4.0E 02 9.0E 04 Fe 1.0E 02 3.2E 03 Co 5.0E 01 2.0E 02 Ni 1.!15 02 1.0E 02 Cu 5.0E 01 4.0E 02 Zn 2.0E 03 1.0E 04 Br 4.2E 02 3.3E 02 Rb 2.0E 03 1.0E 03 Sr 3.0E 01 1.0E 02 Y
2.5E 01 1.0E 03 Zr 3.3E 00 6.7E 00 Nb 3.0E 04 1.0E 02 Mo 1.0E 01 1.0E 01 Tc 1.5E 01 5.0E 00 Ru 1.0E 01 3.0h 02 Rh 1.0E 01 3.0E 02 Te 4.0E 02 6.1E 03 I
1.5E 01 5.0E 00 Cs 2.0E 03 1.0E 03 Ba 4.0E 00 2.0E 02 La 2.5E 01 1.0E 03 Ce 1.0E 00 1.0E 03 Pr 2.5E 01 1.0E 03 Nd 2.5E 01 1.0E 03 W
1.2E 03 1.0E 01 Np 1.0E 01 4.0E 02
- Table taken from Regulatory Guide 1.109 (Rev.1)
TABLE 3.1-1 (1 of 1)
b l
TABLE 3.1-2*
(1 of 3)
INGESTION DOSE FACTORS FOR Al% TS
[
(. MREM PER FCI INGESTED)
NUCLIDE BONE-LIVER T. BODY THYROID KIDNEY LUNG GI-LLI.
H 3
NO DATA-1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 l
- MN 54 NO DATA-4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA-1.40E-05 MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA
'3.67E-06 3
FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 l
}
FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 4
4' CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 i
CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA' 7.10E-06 6
ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 i
ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 i
BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E NO DATA NO DATA NO DATA 2.19E-04
)
SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90-9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 l
ZR 95 3.04E-08 9.75E-09 6.60E-09 No DATA 1.53E-08 NO DATA 3.09E-05
[
ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 i
i i
- Table taken from Regulatory Guide 1.109 (Rev. 1)
TABLE 3.1-2 (1 of 3) i
TABLE 3.1-2 (2 of 3)
INGESTION DOSE FACTORS FOR ADULTS
[N (MREM PER PCI INGESTED)
\\- J NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU 103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU 105 1.54E-08 40 DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06
-n_
RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG 110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE 125M 2.68E-0:
9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-06 NO DATA 2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.682-06 TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05 e'%
I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06
(
)
I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06
~
I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-05 CS 134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS 136 6.51E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS 137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA 139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA 140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA 141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA 142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA 140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05
/
TABLE 3.1-2
(-]/
(2 of 3) i i
I TABLE 3.1-2 (3 of 3)
INGESh 0N DOSE FACTORS FOR ADULTS h
(MREM PER FCI INGESTED) v NUCLIDE' BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI CE 143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR 144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 6.29E-09. 7.27E-09 4.35E-10 NO DATA 4.2d-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 N)
TABLE 3.1-2 (3 of 3) l lu
.~
l TABLE 3.1-3*
2 i
(1 of 3)
INGESTION DOSE FACTORS FOR TEENAGr.R (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI T
H 3
NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 i
NA 24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 CR 51 NO DATA NO DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN 54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 NN 56 NO DATA 1.58E-07 2.81E-08 NO DATA 2.00E-07 NO DATA 1.04E-05
~
FE 55 3.78E-06 2.68E-06 6.25E-07 NO DATA NO DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 CO 58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 CO 60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 NI 63 1.77E-04 1.25E-05 6.00E-06 NO DATA NO DATA NO DATA 1.99E-06 NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-07 CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 ZN 65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ZN 69 1.47E-08 2.80E-08 1.96E-09 NO DATA 1.83E-08 NO DATA 5.16E-08 i
BR 83 NO DATA NO DATA 5.74E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA LT E-24 i
BR 85 NO DATA NO DATA 3.05E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.98E-05 1.40E-05 NO DATA NO DATA NO DATA 4.41E-06 RB 88 NO DATA 8.52E-08 4.54E-08 NO DATA NO DATA NO DATA 7.30E-15 RB 89 NO DATA 5.50E-08 3.89E-08 NO DATA NO DATA NO DATA 8.43E-17 SR 89 4.40E-04 NO DATA 1.26E-05 NO DATA NO DATA NO DATA-5.24E-05 SR 90 8.30E-03 NO DATA 2.05E-03 NO DATA NO DATA NO DATA 2.33E-04 SR 91 8.07E-06 NO DATA 3.21E-07 F0 DATA NO DATA NO DATA 3.66E-05 SR 92 3.05E-06 NO DATA 1.30E-07 NO DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E-98 NO DATA 3.69E-10 NO DATA NO DATA NO DATA 1.13E-04 1
Y 91M 1.29E-10 NO DATA 4.93E-12 NO DATA NO DATA NO DATA 6.09E-09 Y 91 2.01E-07 NO DATA 5.39E-09 NO DATA NO DATk NO DATA 8.24E-05 Y 92 1.21E-09 NO DATA 3.50E-11 NO DATA NO DATA NO DATA 3.32E-05
- Taken from Regulatory Guide 1 109 (Rev. 1)
E A
i TABLF. 3.1-3 t
(1 of 3)
LO i
8 1~
~ - ~ ~ ~. -. ---
-,-,,._n
,._a n.
--n m-
,.,.._-.,_..--,,m
TABLE 3.1-3 (2 of 3)
INGESTION DOSE FACTORS FOR TEENAGER (MREM PER PCI INGESTED)
NUCLIDE B0NE LIVER T.B0DY THYROID KIDNEY LUNG GI-LLI Y 93 3.83E-09 NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 ZR 95 4.12E-08 1.30E-00 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ZR 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.11E-10 NO DATA 1.27E-04 NB 95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 MO 99 NO DATA 6.03E-06 1.15E-06 NO DATA 1.38E-05 NO DATA 1.08E-05 TC 99M 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.38E-08 5.14E-10 6.08E-07 TC 101 3.60E-10 5.12E-10 5.03E-09 NO DATA 9.26E-09 3.12E-10 8.75E-18 RU 103 2.55E-07 NO DATA 1.09E-07 NO DATA 8.99E-07 NO DATA 2.13E-05 RU 105 2.18E-08 NO DATA 8.46E-09 NO DATA 2.75E-07 NO DATA 1.76E-05 RU 106 3.922-06 NO DATA 4.94E-07 NO DATA 7.56E-06 NO DATA 1.88E-04 AG 110M 2.05E-07 1.94E-07 1.18E-07 NO DATA 3.70E-07 NO DATA 5.45E-05 TE 125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 NO DATA NO DATA 1.13E-05 TE 127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05 TE 127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 NO DATA 1.22E-05 TE 12?M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 NO DATA 6.12E-05 TE 129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 NO DATA 2.45E-07 TE 131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 NO DATA 9.39E-05
~g TE 131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 NO DATA 2.29E-09 (d
TE 132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 I 130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 NO DAIA 2.29E-06 I 131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 I 132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 NO DATA 3.18E-07 I 133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 NO DATA 2.58E-06 I 134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 NO DATA 5.10E-09 I 135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 NO DATA 1.74E-06 CS 134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 CS 136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1.84E-05 2.90E-06 2.72E-06 CS 137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 CS 138 7.76E-08 1.49E-07 7.45E-08 NO DATA 1.10E-07 1.28E-08 6.76E-11 BA 139 1.39E-07 9.78E-11 4.05E-09 NO DATA 9.22E-11 6.74E-11 " 24E-06 O
TABLE 3.1-3 (2 of 3)
TABLE 3.1-3 (3 of 3)
INGESTION DOSE FACTORS FOR TEENAGER (MREM PER PCI INGESTED)
NUCLIDE
. BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI BA 140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 BA 141 6.71E-08 5.01E-11 2.24E-08 NO DATA 4.65E-11 3.43E-11 1.43E-13 BA 142 2.99E-08 2.99E-11 1.84E-09 NO DATA 2.53E-11 1,99E-11 9.18E-20
.LA 140 3.48E-09 1.71E-09 4.55E-10 NO DATA NO DATA NO DATA 9.82E-05 LA 142 1.79E-10 7.95E-11 1.98E-11 NO DATA NO DATA NO DATA 2.42E-06 CE 141 1.33E-08 8.88E-09 1.02E-09 NO DATA 4.18E-09 NO DATA 2.54E-05 CE 143 2.35E-09 1.71E-06 1.91E-10 NO DATA 7.67E-10 *!0 DATA 5.14E-05 CD 144 6.96E-07 2.88E-07 3.74E-08 NO DATA 1.72E-07 NO DATA 1.75E-04 PR 143 1.31E-08 5.23E-09 6.52E-10 NO DATA 3.04E-09 NO DATA 4.31E-05 PR 144 4.30E-11 1.76E-11 2.18E-12 NO DATA 1.01E-11 NO DATA 4.74E-14 ND 147 9.38E-09 1.02E-08 6.11E-10 NO DATA 5.99E-09 NO DATA 3.68E-05 W 187 1.46E-07 1.19E-07 4.17E-08 NO DATA NO DATA NO DATA 3.22E-05 NP 239 1.76E-09 1.66E-10 9.22E-11 NO DATA 5.21E-10 NO DATA 2.67E-05 O
TABLE 3.1-3 O
(3 of 3)
- - ~ -.
TABLE 3.1-4*
(1 of 3)
INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED)
NUCLIDE.
BONE LIVER T. BODY THYROID KIDNEY LUNG
.GI-LLI H
3-NO DATA '2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 NA 24 5.80E-06 :5.80E-06 5.SOE-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 CR 51
_NO DATA NO DATA 8.90E-09 4.94E-09 1.35E-0!? 9.02E-09 4.72E-07 L
MN 54
'NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06
,MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 NO DATA
'4.84E-05
..m
'FE 55 1.'15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.ME-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 CO 58 NO DATA 1.80E-06 5.51E-06' NO DATA NO DATA NO DATA 1.05E-05 CO 60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 NI 63 5.38E-04 2.88E-05 1.83E-05 NO DATA NO DATA NO DATA 1.94E-06 l
NI 65 2.22E-06 2.09E-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 NO DATA 1.15E "
ZN 65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ZN 69 4.38E-08 6,33E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA 1.71E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.98E-07 NO DATA NO DATA.
NO DATA LT E-24 BR 85 NO DATA NO DATA 9.12E-09 NO DATA NO DATA NODATA LT E-24 BR 86 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31E-06 RB 88 NO DATA 1.90E-07 1.32E NO DATA NO DATA ' NO DATA 9.32E-09 RB 89 NO DATA 1.17E-07 1.04E-07 NO DATA NO DATA NO DATA 1.02E-09 SR 89 1.32E NO DATA 3.77E-05 NO DATA NO DATA NO DATA 5.11E-05 SR 90 1.70E-02 NO DATA 4.31E-03 NO DATA NO DATA NO DATA-2.29E-04 SR 91 2.40E-05 NO DATA 9.06E-07 NO DATA NO DATA NO DATA 5.30E-05 SR 92 9.03E-06 NO DATA 3.62E-07 NO DATA NO DATA NO DATA 1.71E-04 Y 90 4.11E-08 NO DATA 1.10E-09 NO DATA NO DATA NO DATA 1.17E-04 Y 91M 3.82E-10 NO DATA 1.39E-11 NO DATA NO DATA NO DATA 7.48E-07 Y 91 6.02E-07 NO DATA 1.61E-08 NO DATA NO DATA NO DATA 8.02E-05 Y 92 3.60E-09 NO DATA 1.03E-10 NO DATA NO DATA NO DATA 1.04E-04
- Taken from Regulatory Guide 1.109 (Rev. 1).
TABLE 3.1-4 (1 of 3)
O
TABLE 3.1-4 (2 of 3)
INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTEb)
(
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI Y 93 1.14E-08 NO DATA 3.13E-10 NO DATA NO DATA NO DATA 1.70E-04 ZR 95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ZR 97 6.99E-09 1.01E-09 5.96E-10 NO DATA 1.45E-09 NO DATA 1.53E-04 NB 95 2.25E-08 8.76E-09 6.26E-09 NO DATA S.23E-09 NO DATA 1.62E-05 MO 99 NO DATA 1.33E-05 3.29E-06 NO DATA 2.84E-05 NO DATA 1.10E-05 TC 99M 9.23E-10 1.81E-09 3.00E-08 NO DATA 2.63E-08 9.19E-10 1.03E-06 TC 101 1.07E-09 1.12E-09 1.42E-08 NO DATA 1.91E-08 5.92E-10 3.56E-09 RU 103 7.31E-07 NO DATA 2.81E-07 NO DATA 1.84E-06 NO DATA 1.89E-05 RU 105 6.45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.21E-05 RU 106 1.17E-05 NO DATA 1.46E-06 NO DATA 1.58E-05 NO DATA 1.82E-04 AG 110M 5.39E-07 3.84E-07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TE 125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.10E-05 TE 127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 NO DATA 2.34E-05 TE 127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 NO DATA 1.84E-05 TE 129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 TE 129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 NO DATA 8.34E-06 TE 131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 NO DATA 1.01E-04 TE 131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 gs
\\
)
'-Jr TE 132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 NO DATA 4.50E-05 I 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06 I 131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 I 132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 NO DATA -
1.73E-06 I 133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 NO DATA 2.95E-06 I 134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 NO DATA 5.16E-07 I 135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 NO DATA 2.40E-06 CS 134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 CS 136 2.35E-05 6.46E-05 4.18E-05 NO DATA 3.44E-05 5.13E-06 2.27E-06 CS 137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 CS 138 2.28E-07 3.17E-07 2.01E-07 NO DATA 2.23E-07 2.40E-08 1.46E-07 BA 139 4.14E-07 2.21E-10 1.20E-08 NO DATA 1.93E-10 1.30E-10 2.39E-05 TABLE 3.1-4
( s)
(2 of 3)
TABLE 3.1-4 (3 of 3)
INGESTION DOSE FACTORS FOR CHILD
'~'
(MREM PER PCI INGESTED)
NUCLIDE BONE LIVER-T. BODY THYROID KIDNEY LUNG GI-LLI BA 140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 BA 141 2.00E-07 1.12E-10 6.51E-09
.NO DATA 9.69E-11 6.58E-10 1.14E-07 BA 142 8.74E-08 6.29E-11 4.88E-09 NO DATA 5.09E-11 3.70E-11 1.14E-09 LA 140 1.01E-08 3.53E-09 1.19E-09 NO DATA NO DATA NO DATA 9.84E-05 LA 142 5.24E-10 1.67E-10 5.23E-11 NO DATA NO DATA NO DATA 3.31E-05 CE 141 3.97E-08 1.98E-08 2.94E-09 NO DATA 8.68E-09 NO DATA 2.47E-05 CE 143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1.59E-09 NO DATA 5.55E-05 CE 144 2.08E-06 6.52E-07 1.11E-07 NO DATA 3.61E-07 NO DATA 1.70E-04 PR 143 3.93E-08 1.18E-08 1.95E-09 NO DATA 6.39E-09 NO DATA 4.24E-05 PR 144 1.29E-10 3.99E-11 6.49E-12 NO DATA 2.11E-11 NO DATA 8.59E-08 ND 147 2.79E-08 2.26E-08 1.75E-09 NO DATA 1.242-08 NO DATA 3.58E-05 W 187 4.29E-07 2.54E-07 1.14E-07 NO DATA NO DATA NO DATA -3.57E-05 NP 239 5.25E-09 3.77E-10 2.65E-10 NO DATA 1.09E-09 NO DATA 2.79E-05 V
i TABLE 3.1-4 O
(3 of 3) i
~
TABLE 3.1-5*
(1 of 3)
INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)
NUCLIDE LONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H
3 NO DATA. 3.08E-07 3.08E-07 3'.08E-07 3.08E-07 3.08E-07 3.08E-07 NA 24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1
l CR 51 NO DATA NO DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MN-54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 I
MN 56 NO DATA 8.18E-07 1.41E-07 NO DATA 7.03E-07 NO DATA 7.43E-05 FE 55-1.39E-05 8.98E-06 2.40E-06 NO DATA NO DATA 4.39E-06 1.14E-06 q.
FE 59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 4
l CO 58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 L
\\
CO 60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 f
NI 63 6.34E-04 3.92E-05 2.20E-05 NO DATA NO DATA NO DATA 1.95E-06 NI 65 4.70E-06 5.32E-07 2.42E-07 NO DATA NO DATA NO DATA 4.05E-05 CU 64 NO DATA 6.09E-07 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-05 ZN 65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ZN 69 9.33E-08 1.68E-07 1.25E 38 NO DATA 6.98E-08 NO DATA 1.37E-05 i
BR 83 NO DATA NO DATA 3.63E-07 NO DATA NO DATA NO DATA LT E-24 i.
BR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24 i
BR 85 NO DATA NO DATA 1.94E-08 NO DATA NO DATA NO DATA LT E-24
(
RB 86 NO DATA 1.70E-04 8.40E-05 NO DATA NO DATA NO DATA 4.35E-06 RB 88 NO DATA 4.98E-07 2.73E-07 NO DATA NO DATA NO DATA 4.85E-07 1
RB 89 NO DATA 2.86E-07 1.97E-07 NO DATA NO DATA NO DATA 9.74E-08 SR 89 2.51E-03 NO DATA 7.20E-05 NO DATA FO DATA NO DATA 5.16E-05 l
SR 90 1.85E-02 NO DATA 4.71E-03 NO DATA NO DATA NO DATA 2.31E-04 f'
SR 91 5.00E-05 NO DATA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 SR 92 1.92E-05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 NO DATA 2.33E-09 NO DATA NO DATA NO DATA 1.20E-04 Y 91M 8.10E-10 NO DATA 2.76E-11 NO DATA NO DATA NO DATA 2.70E-06 j.
Y 91 1.13E-06 NO DATA 3.01E-08 NO DATA NO DATA NO DATA 8.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04 i
l-
- Taken from Regulatory Guide 1.109 (Rev. 1) l l
1' TABLE 3.1-5
}
(1 of 3) t J
..--m
- ~,,,
..--,g,,
-,,n
,r---+
-o,=
w~,-, -,,,
,---,m-,mn---,,-ne. - -
,,..-,n
-,e.,,-,. -,
,,.-,,,,s_,.
TABLE 3.1-5 (2 of 3)
INGESTION DOSE FACTORS FOR INFANT (V]
(MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T. BODY THYR 01D KIDNEY LUNG GI-LLI Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA 1.92E-04 ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-06 NO DATA 2.50E-05 ZR 97 1.48E-08 2.54E-09 1-16E-09 NO DATA 2.56E-09 NO DATA 1.62E-04 NB 95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 MO 99 NO DATA 3.40E-05 6.63E-06 NO DATA 5.08E-05 NO DATA 1.12E-05 TC 99M 1.92E-09 3.96E-09 5.10E-08 NO DATA 4.26E-08 2.07E-09 1.15E-06 TC 101 2.27E-09 2.86E-09 2.83E-08 NO DATA 3.40E-08 1.56E-09 4.86E-07 RU 103 1.48E-06 NO DATA 4.95E-07 NO DATA 3.08E-06 NO DATA 1.80E-05 RU 105 1.36E-07 NO DATA 4.58E-08 NO DATA 1.00E-06 NO DATA 5.41E-05 RU 106 2.41E-05 NO DATA 3.01E-06 NO DATA 2.85E-05 NO DATA 1.83E-04 AG 110M 9.96E-07 7.27E-07 4.81E-07 NO DATA 1.04E-06 NO DATA 3.77E-05 TE 125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 NO DATA NO DATA 1.11E-05 TE 127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 TE 127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE 129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 TE 129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 NO DATA 2.27E-05 TE 131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04
(N TE 131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 NO DATA 7.11E-06
\\ J TE 132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 NO DATA 3.81E-05 I 130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 NO DATA 2.83E-06 I 131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 I 132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-07 NO DATA 2.73E-06 I 133 1.25E-05
- 1. 82E-05 5.33E-06 3.31E-03 2.14E-05 NO DATA 3.08E-06 I 134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 NO DATA 1.84E-06 I 135 3.64E-06 7.24E-06 2.64E-05 6.49E-04 8.07E-06 NO DATA 2.62E-06 CS 134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 CS 136 4.59E-05 1.35E-04 5.04E-05 NO DATA 5.38E-05 1.10E-05 2.05E-06 CS 137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 CS 138 4.81E-07 7.82E-07 3.79E-07 NO DATA 3.90E-07 6.09E-08 1.25E-06 BA 139 8.81E-07 5.84E-10 2.55E-08 NO DATA 3.51E-10 3.54E-10 5.58E-05 TABLE 3.1-5 C'N)
(2 of 3)
TABLE 3 1-5 (3 of 3)
INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI BA 140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 BA 141 4.25E-07 2.91E-10 1.34E-08 NO DATA 1.75E-10 1.77E-10 5.19E-06 BA 142 1.84E-07 1.53E-10 9.06E-09 NO DATA 8.81E-11 9.26E-11 7.59E-07 LA 140 2.11E-08 8.32E-09 2.14E-09 NO DATA NO DATA NO DATA 9.77E-05 LA 142 1.10E-09 4.04E-10 9.67E-11 NO DATA NO DATA NO DATA 6.86E-05 CE 141 7.87E-08 4.80E-08 5.65E-09 NO DATA 1.48E-08 NO DATA 2.48E-05 CE 143 1.48E-08 9.82E-06 1.12E-09 NO DATA 2.86E-09 NO DATA 5.73E-05 CE 144 2.98E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.71E-04 PR 143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E-05 PR 144 2.74E-10 1.06E-10 1.38E-11 NO DATA 3.84E-11 NO DATA 4.93E-06 ND 147 5.53E-08 5.68E-08 3.48E-09 NO DATA 2.19E-08 NO DATA 3.60E-05 W 187 9.03E-07 6.28E-07 2.17E-07 NO DATA NO DATA NO DATA 3.69E-05 NP 239 1.11E-08 9.93E-10 5.61E-10 NO DATA 1.98E-09 NO DATA 2.87E-05
(N
\\seJ TABLE 3.1-5 (3 of 3)
TABLE 3.1-6*
(1 of 1)
INHALATION DOSE FACTORS FOR ADULTS (MREM PER PCI INHALED)
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H
3 NO DATA 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 CR 51 NO DATA NO DATA 1.25E-08 7.44E-09 2.85E-09 1.805-06 4.15E-07 MN 54 NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.75E-04 9.67E-06 FE 55 3.07E-06 2.12E-06 4.93E-07 NO DATA NO DATA 9.01E-06 7.54E-07 FE 59 1.47E-06 3.47E-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 C0 58 NO DATA 1.98E-07 2.59E-07 NO DATA NO DATA 1.16E-04 1.33E-05 CO 60 NO DATA 1.44E-06 1.65E-06 NO DATA NO DATA 7.46E-04 3.56E-05 ZN 65 4.05E-06 1.29E-05 5.82E-06 NO DATA 8.62E-06 1.08E-04 6.68E-06 SR 89 3.80E-05 NO DATA 1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05 SR 90 1.24E-02 NO DATA 7.62E-04 NO DATA NO DATA 1.20E-03 9.02E-05 ZR 95 1.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.21E-06 1.88E-05 SB 124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 NO DATA 3.10E-04 5.08E-05 I 131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07 I 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 1.11E-06 CS 134 4.66E-05 1.06E-04 9.10E-05 NO DhTA 3.59E-05 1.22E-05 1.30E-06 CS 136 4.88E-06 1.83E-05 1.38E-05 NO DATA 1.07E-05 1.50E-06 1.46E-06 CS 137 5.98E-05 7.76E-05 5.35E-05 NO DATA 2.78E-05 9.40E-06 1.05E-06
~
BA 140 4.88E-06 6.13E-09 3.21E-07 NO DATA 2.09E-09 1.59E-04 2.73E-05 CE 141 2.49E-06 1.69E-06 1.91E-07 NO DATA 7.83E-07 4.52E-05 1.50E-05 CE 144 4.29E-04 1.79E-04 2.30E-05 NO DATA 1.06E-04 9.72E-04 1.02E-04
- Table taken from NUREG-0597 i
l TABLE 3.1-6 (1 of 1) i
()
TABLE 3.1-7*
(1 of 1)
INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALE.7)
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H
3 NO DATA 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 CR 51 NO DATA NO DATA 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN 54 NO DATA 6.39E-06 1.05E-06 NO PATA 1.59E-06 2.48E-04 8.35E-06 FE 55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-07 FE 59 1.99E-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 C0 58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 CO 60 NO DATA 1.89E-06 2.48E-06 NO DATA NO DATA 1.09E-03 3.24E-05 ZN 65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06 SR 89 5.43E-05 NO DATA 1.56E-06 NO DATA NO DATA 3.02E-04 4.64E-05 SR 90 1.35E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9.56E-05 ZR 95 1.82E-05 5.73E-06 3.94E-06 NO DATA 8.42E-06 3.36E-04 1.86E-05 SB 124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 NO DATA 4.81E-04 4.98E-05 I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11E-07 I 133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1.29E-06 CS 134 6.28E-05 1.41E-04 6.86E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 CS 136 6.44E-06 2.42E-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.36E-06 7'~N CS 137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51E-05 1.06E-06
]
'T, BA 140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-09 2.86E-05 CE 141 3.55E-06 2.37E-06 2.71E-07 NO DATA 1.11E-06 7.67E-05 1.58E-05 CE 144 6.11E-04 2.53E-04 3.28E-05 NO DATA 1.51E-04 1.67E-03 1.08E-04
- Table taken from NUREG-0597 TABLE 3.
7 h
(1 of 1)
O
1 TABLE 3.1-8*
(1 of 1)
INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED) i NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H
3 NO DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 CR 51 NO DATA NO DATA 4.17E-08 2.31E-08 6.57E-09 4.59E-09 2.93E-07 MN 54 NO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19E-06 FE 55 1.28E-05 6.80E-06 2.10E-06 NO DATA NO DATA 3.00E-05 7.75E-07 FE 59 5.59E-06 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 CO 58 NO DATA 4.79E-07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 a
CO 60 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03
~.60E-05 2
ZN 65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 SR 89 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.52E-05 SR 90 2.73E-02 NO DATA 1.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 ZR 95 5.13E-05 1.13E-05 1.00E-05 NO DATA 1.16E-05 6.03E-04 1.65E-05 SB 124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 NO DATA 8.76E-04 4.43E-05 I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 NO DATA 7.68E-07 I 133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 NO DATA 1.48E-06 CS 134 1.76E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 CS 136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06
T CS 137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 h
BA 140 2.00E- 05 1.75E-08 1.17E-06 NO DATA 5.71E-09 4.71E-04 2.75E-05 CE 141 1.06E-05 5.28E-06 7.83E-07 NO DATA 2.31E-06 1.47E-04 1.53E-05 CE 144 1.83E-03 5.72E-04 9.77E-05 NO DATA 3.17E-04 3.23E-03 1.05E-04
- Table taken From NUREG-0597.
l l
TABLE 3.1-8 (1 of 1)
TABLE 3.1-9*
I (1 of 1)
INHALATION DOSE FACTORS FOR INFANT O
(MREM PER PCI IN10d.ED)
U NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LII H
3 NO DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 CR 51 NO DATA NO DATA 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 MN 54 NO DATA 1.81E-05 3.56E-06 NO DATA 3.56E-06 7.14E-04 5.04E-06 FE 55 1.41E-05 8.39E-06 2.38E-06 NO DATA NO DATA 6.21E-05 7.82E-07 FE 59 9.69E-06 1.68E-05 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05 CO 58 NO DATA 8.71E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 CO 60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 ZN 65 1.38E-05 4.47E-05 2.22E-05 NO DATA 2.32E-05 4.62E-04 3.67E-05 SR 89 2.84E-04 NO DATA 8.15E-06 NO DATA NO DATA 1.45E-03 4.57E-05 SR 90 2.92E-02 NO DATA 1.85E-03 NO DATA NO DATA 8.03E-03 9.36E-05 ZR 95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05 SB 124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 NO DATA 1.89E-03 4.22E-05 I 131 2.71E-05 3.1)E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 I 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 1.54E-06 CS 134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07
~
CS 136 3.45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 CS 137 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07 M
k
)
BA 140 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 CE 141 1.98E-05 1.19E-05 1.42E-06 NO DATA 3.75E-06 3.69E-04 1.54E-05 CE 144 2.2.8E-03 8.65E-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04
- Table taken from NUREG-0597.
TABLE 3.1-9
/]
(1 of 1)
V
TABLE 3.1-10*
(1 of 2)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND D) 2
(
(mrem /hr per pCi/m )
Element Total Body Skin H-3 0.0 0.0 Na-24 2.50E-08 2.90E-08 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Ma-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10.
Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13
,,nt Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08
- \\' *
Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10
- Taken from Regulatory Guide 1.109 (Rev. 1)
TABLE 3.1-10 (1 of 2)
TABLE 3.1-10 (cont'd)
(2 of 2)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 2
(mrem /hr per pCi/m )
Element Total Body Skin Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 i
La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 0,
Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 h
TABLE 3.1-10 (2 of 2)
O l
i
,-------m-
--r-
TABLE 3.1-11*
(1 of 1)
STABLE ELEMENT TRANSFER DATA F,(Cow)
Ff Element Milk (d/2)
Meat (d/kg)
H 1.0E-02**
1.2E-02 Na 4.0E-02 3.0E-02 Cr 2.2E-03 2.4E-03 Mn 2.5E-04 8.0E-04 Fe 1.2E-03**
4.0E-02 Co 1.0E-03 1.3E-02
- Ni 6.7E-03 5.3E-02 Cu 1.4E-02**
8.0E-03 Zn 3.9E-02 3.0E-02 Rb 3.0E-02 3.1E-02' Sr 8.0E-04**
6.0E-04 Y
1.0E-05 4.6E-03 Zr 5.0E-06 3.4E-02 Nb 2.5E-03 2.8E-01 Mo 7.5E-03 8.0E-03 Tc 2.5E-02 4.0E-01 Ru 1.0E-06 4.0E-01 Rh 1.0E-02 1.5E-03 Ag 5.0E-02 1.7E-02 Te 1.0E-00 7.7E-02 I
6.0E-03**
2.9E-03 Cs 1.2E-02**
4.0E-03 7
Ba 4.0E-04 3.2E-03 x,
La 5.0E-06 2.0E-04 Ce 1.0E-04 1.2E-03 Pr 5.0E-06 4.7E-03 Nd 5.0E-06 3.3E-03 W
5.0E-04 1.3E-03 Np 5.0E-06 2.0E-04
- Taken from Regulatory Guide 1.109 (Rev. 1)
- Nuclide Transfer parameters for Goat's milk I
Element Fm (d/1)
{
H 0.17 Fe 1.30E-09 i
Cu 0.013 Sr 0.014 I
0.06 Cs 0.30 TABLE 3.1-11 (1 of 1) i
-.--,--- - -- -.. - - - -,.. - - - - ~ - -,
- - - - ~ - -
- - - - - - - - - ~ - - - - - -
O TABLE 3.1-12 (1 of 1)
R VALUES - GROUND PATHWAY - ALL AGES g
NUCLIDE T. BODY SKIN H 3 NO DATA NO DATA CR 51 4.65E+06 5.49E+06 MN 54 1.38E+09 1.62E+09 FE 55 NO DATA NO DATA FE 59 2.72E+08 3.20E+08 CO 58 3.79E+08 4.44E+08 CO 60 2.15E+10 2.53E+10 ZN 65 7.44E+08 8.56E+08 SR 89 2.16E+04 2.50E+04 SR 90 NO DATA NO DATA ZR 95 2.51E+08 2.91+08 SB 124 5.98E+08 6.91E+08 I 131 8.59E+06 1.04E+07 I 133 1.22E+06 1.49E+06 CS 134 6.82E+09 7.96E+09 CS 136 1.50E+08 1.70E+08 CS 137 1.03E+10 1.20E+10 BA 140 2.05E+07 2.34E+07 CE 141 1.36E+07 1.54E+07 N
CE 144 6.92E+07 8.01E+07
'l 4
TABLE 3.1-12 (1 of 1)
.)
I i
O TABLE 3.1-13
-(1 of 1)
R VALUES - VEGETABLE PATHWAY - ADULT g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3 0.0 2.28E+03 2.28E+03 2.28E+03 2.23E+03 2.28E+03 2.28E+03 CR 51 0.0 0.0 4.58E+04 2.74E+04 1.01E+04 6.07E+04 1.15E+07 NN 54 0.0 3.07E+08 5.86E+07 0.0 9.14E+07 0.0 9.41E+08 FE 55 1.99E+08 1.38E+08 3.21E+07 0.0 0.0 7.68E+07 7.90E+07 FE 59 1.23E+08 2.90E+08 1.11E+08 0.0
'0.0 8.09E+07 9.66E+08 CO 58 0.0 2.99E+07 6.71E+07 0.0 0.0 0.0 6.07E+08 CO 60 0.0 1.66E+08 3.67E+08 0.0 0.0 0.0 3.12E+09 ZN 65
-4.00E+08 1.27E+09 5.76E+08 0.0 8.52E+08 0.0 8.02E+08 SR 89 9.75E+09 0.0 2.80E+08 0.0 0.0 0.0 1.56E+09 SR 90 6.70E+11 0.0 1.64E+11 0.0 0.0 0.0 1.94E+10 Ut 95 1.16E+06 3.73E+05 2.52E+05 0.0 5.85E+05 0.0 1.18E*09 SB 124 1.01E+08 1.91E+06 4.01E+07 2.45E+05 0.0 7.88E+07 2.87E+09 I 131 4.03E+07 5.76E+07 3.30E+07 1.89E+10 9.88E+07 0.0 1.52E+07 I 133 1.04E+06 1.80E+06 5.50E+05 2.65E+08 3.15E+06 0.0 1.62E+06 O
CS 134 4.54E+09 1.08E+10 8.83E+09 0.0 3.49Et09 1 16E+09 1.89E+08 CS 136 4.23E+07 1.67E+08 1.20E+08 0.0 9.30E+07 1.27E+07 1.90E+07 CS 137 6.63E+09 9.07E+09 5.94E+09 0.0 3.08E+09 1.02E+09 1.76E+08 BA 140 1.28E+08 1.61E+05 8.40E+06 0.0 5.47E+04 9.22E+04 2.64E+08 CE 141 1.94E+05 1.31E+05 1.49E+04 0.0 6.09E+04 0.0 5.02E+08 CE 144 3.15E+07 1.31E+07 1.69E+06 0.0 7.80E+06 0.0 1.06E+10 TABLE 3.1-13 (1 of 1)
i 1
TABLE 3.1-14 4
(1 of 1)'
R VALUES - VEGETABLE PATHWAY - TEENAGER g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 2.61E+03 2.61E+03 2.611 2.61E+03 2.61E+03 2.61E+03 CR 51 0.0 0.0 6 08E+04 3.38E+u*
1.33E+04 8.68E+04 1.02E+07 MN 54 0.0 4.46E+08 d.85E+07 0.0 1.33E+08 0.0 9.15E+08 FE 55 3.10E+08 2.20E+08 5.13E+07 0.0 0.0 1.39E+08 9.51E+07 FE 59 1.75E+08 4.09E+08 1.58E+08 0.0 0.0 1.29E+08 9.68E+08 CO 58 0.0 4.25E+07 9.79E+07 0.0 0.0 0.0 5.86E+08 CO 60 0.0 2.47E+08 5.57E+08 0.0 0.0 0.0 3.22E+09 ZN 65 5.35E+08 1.86E+09 8.66E+08 0.0 1.19E+09 0.0 7.86E+08 SR 89 1.48E+10 0.0 4.24E+08 0.0 0.0 0.0 1.76E+09
-SR 90 8.32E+11 0.0 2.05E+11 0.0 0.0 0.0 2.34E+10 i
ZR 95 1.70E+06 5.38E+05 3.70E+05 0.0 7.90E+05 0.0 1.24E+09 SB 124 1.51E+08 2.78E+06 5.88E+07 3.42E+05 0.0 1.32E+08 3.04E+09 I 131 3.83E+07 5.37E+07 2.88E+07 1.57E+10 9.24E+07 0.0 1.06E+07 I 133 9.63E+05 1.63E+06 4.98E+05 2.28E+08 2.87E+06 0.0 1.24E+06
[%
CS 134 6.90E+09 1.62E+10 7.54E+09 0.0 5.16E+09 1.97E+09 2.02E+08
(,,J.
CS 136 4.33E+07 1.71E+08 1.15E+08 0.0 9.28E+07 1.46E+07 1.37E+07 i
CS 137-1.06E+10 1.41E+10 4.90E+09 0.0 4.78E+09 1.86E+09 2.00E+08 BA 140 1.38E+08 1.69E+05 8.88E+06 0.0 5.72E+04 1.14E+05 2.12E+08 CE 141 2.78E+05 1.86E+05 2.13E+04 0.0 8.75E+04 0.0 5.32E+08 CE 144 5.04E+07 2.09E+07 2.71E+06 0.0 1.25E+07 0.0 1.27E+10 0
TABLE 3.1-14 (1 of 1)
(}
TABLE 3.1-15
\\,,/
(1 of 1)
R VALUES - VEGETABLE PATINAY - CHILD g
t NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 4.04E+03 4.04E+03 4.04E+03 4.04E+03 4.04E+03 4.04E+03 CR 51 0.0 0.0 1.15E+05 6.40E+04 1.75E+04 1.17E+05 6.12E+06 MN 54 0.0 6.53E+08 1.74E+08 0.0 1.83E+08 0.0 5.48E+08 FE 55 7.62E+08 4.04E+08 1.25E+08 0.0 0.0 2.29E+08 7.49E+07 FE 59 3.88E+08 6.29E+08 3.13E+08 0.0 0.0 1.82E+08 6.54E+08 CO 58 0.0 6.27E+07 1.92E+08 0.0 0.0 0.0 3.66E+08 CO 60 0.0 3.76E+08 1.11E+09 0.0 0.0 0.0 2.08E+09 ZN 65 1.02E+09 2.73E+09 1.70E+09 0.0 1.72E+09 0.0 4.80E+08 3R 69 3.52E+10 0.0 1.00E+09 0.0 0.0 0.0 1.36E+09 SR 90 1.38E+12 0.0 3.49E+11 0.0 0.0 0.0 1.86E+10 ZR 95 3.82E+06 8.40E+05 7.48E+05 0.0 1.20E+06 0.0 8.77E+08 SB 124 3.44E+08 4.46E+06 1.20E+08 7.59E+05 0.0 1.91E+08 2.15E+09 I 131 7.13E+07 7.17E+07 4.08E+07 2.37E+10 1.18E+08 0.0 6.39E+06 I 133 1.76E+06 2.17E+06 8.22E+05 4.03E+08 3.62E+06 0.0 8.75E+05 rw CS 134 1.56E+10 2.56E+10 5.40E+09 0.0 7.93E+09 2.85E+09 1.38E+08
.(~")
CS 136 8.16E+07 2.24E+08 1.45E+08 0.0 1.19E+08 1.78E+07 7.88E+06 CS 137 2.49E+10 2.39E+10 3.52E+09 0.0 7.78E+09 2.80E+09 1.50E+08 BA 140 2.76E+08 2.42E+05 1.61E+07 0.0 7.87E+04 1.44E+05 1.40E+08 CE 141 6.45E+05 3.22E+05 4.78E+04 0.0 1.41E+05 0.0 4.02E+08 CE 144 1.22E+08 3.81E+07 6.48E+06 0.0 2.11E+07 0.0 9.93E+09 l
l fg TABLE 3.1-15 i
1 (1 of 1)
J
(g~"}
TABLE 3.1-16 (1 of 1)
R VALUES - MEAT PATHWAY - ADULT g
NUCLIDE BONE LIVL2 T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 3.27E+02 3.27E+02 3.27E+02 3.27E+02 3.27E+02 3.27E+02 i
CR 51 0.0 0.0 5.86E+03 3.50E+03 1.29E+03 7.77E+03 1.47E+06 MN 54 0.0 6.83E+06 1.30E+06 0.0 2.03E+06 0.0 2.09E+07 FE 55 2.13E+08 1.47E+08 3.43E+07 0.0 0.0 8.20E+07 8.44E+07 FE 59 2.12E+08 4.99E+0S 1.91E+08 0.0 0.0 1.39E+08 1.66E+09 C0 58 0.0 1.41E+07 3.17E+07 0.0 0.0 0.0 2.87E+08 C0 60 5.0 5.56E+07 1.23E+08 0.0 0.0 0.0 1.04E+09 ZN 65 3.01E+08 9.57E+08 4.32E+08 0.0 6.40E+08 0.0 6.03E+08 SR 89 2.39E+08 0.0 6.86E+06 0.0 0.0 0.0 3.83E+07 SR 90 9.67E+09 0.0 2.37E+09 0.0 0.0
-0.0 2.79E+08 ZR 95 1.47E+06 4.72E+05 3.20E+05 0.0 7.41E+05 0.0 1.50E+09 SB 124 1.55E+07 2.93E+05 6.15E+06 3.76E+04 0.0 1.21E+07 4.40E+08 I 131 4.92E+06 7.03E+06 4.03E+06 2.30E+09 1.21E+07 0.0 1.86E+06 I 133 1.69E-01 2.94E-01 8.97E-02 4.32E+01 5.14E-01
-0.0 2.65E-01 7'"}
CS 134 4.83E+08 1.15E+09 9.39E+08 0.0 3.72E+08 1.23E+08 2.01E+07
( c CS 136 1.06E+07 4.20E+07 3.03E+07 0.0 2.34E+07 3.21E+06 4.78E+06 CS 137 6.58E+08 9.00E+08 5.89E+08 0.0 3.05E+08 1.02E+08 1.74E+07 BA 140 2.56E+07 3.22E+04 1.68E+06 0.0 1.09E+04 1.84E+04 5.27E+07 CE 141 1.15E+04 7.79E+03 8.84E+02 0.0 3.62E+03 0.0 2.98E+07 CE 144 1.07E+06 4.49E+05 5.76E+04 0.0 2.66E+05 0.0 3.63E+08 l
l i
l
(
I'
/"'T TABLE 3.1-16
()
(1 of 1) l
TABLE 3.1-17 (1 of 1)
R VALUES - MEAT PATHWAY - TEENAGER f
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 1.95E+02 1.95E+02 1.95E+02 1.95E+02 1.95E+02 1.95E+02 CR 51 0.0 0.0 4.68E+03 2.60E+03 1.03E+03 6.69E+03 7.87E+05 MN 54 0.0 5.21E+06 1.03E+06 0.0 1.55E+06 0.0 1.07E+07 FE 55 1.73E+08 1.23E+08 2.86E+07 0.0 0.0 7.78E+07 5.31E+07 FE 59 1.70E+08 3.96E+08 1.53E+08 0.0 0.0 1.25E+08 9.36E+08 CO 58 0.0 1.09E+07 2.51E+07 0.0 0.0 0.0 1.50E+08 CO 60 0.0 4.31E+07 9.72E+07 0.0 0.0 0.0 5.62E+08 ZN 65 2.11E+08 7.34E+08 3.43E+08 0.0 4.70E+08 0.0 3.11E+08 SR 83 2.02E+08 0.0 5.78E+06 0.0 0.0 0.0 2.40E+07 SR 90 6.26E+09 0.0 1.55E+09 0.0 0.0 0.0 1.76E+08 ZR 95 1.18E+05 3.72E+05 2.56E+05 0.0 5.47E+05 0.0 8.58E+08 SB 124 1.27E^07 2.33E+05 4.94E+06 2.87E+04 0.0 1.11E+07 2.55E+08 I 131 4.00E+06 5.72E+06 3.07E+06 1.67E+09 9.85E+06 0.0 1.13E+06 I 133 1.42E-01 2.40E-01 7.32E-02 3.35E+01 4.21E-01 0.0 1.82E-01 CS 134 3.84E+08 9.04E+08 4.19E+08 0.0 2.87E+08 1.10E+08 1.12E+07
)
CS 136 8.30E+06 3.27E+07 2.19E+07 0.0 1.78E+07 2.80E+06 2.63E+06 CS 137 5.46E+08 7.27E+08 2.53Er08 0.0 2.47E+08 9.61E+07 1.03E+07 BA 140 2.12E+07 2.59E+04 1.36E+06 0.0 8.79E+03 1.74E+04 3.26E+07 CE 141 9.67E+03 6.46E+03 7.42E+02 0.0 3.04E+03 0.0 1.85E+07 CE 144 9.04E+05 3.74E+05 4.86E+04 0.0 2.24E+05 0.0 2.27E+08 TABLE 3.1-17 O
(1 of 1)
,m.
,v..n-,
-._,n.
c---
/
TABLE 3.1-18 i
(1 of 1)
R VALUES - MEAT PATHWAY - CHILD g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 2.36E+02 2.36E+02 2.36E+02 2.36E+02 2.36E+02 2.36E+02 CR 51 0.0 0.0 7.31E+03 4.06E+03 1.11E+03 7.40E+03 3.87E+05 MN 54 0.0 5.96E+06 1.59E+06 0.0 1.67E+06 0.0 5.00E+06 FE 55 3.32E+08 1.76E+08 5.45E+07 0.0 0.0 9.95E+07 3.26E+07 FE 59 3.01E+08 4.86E+08 2.42E+08 0.0 0.0 1.41E+08 5.06E+08 CO 58 0.0 1.27E+07 3.90E+07 0.0 0.0 0.0 7.43E+07 CO 60
.0.0 5.12E+07 1.51E+08 0.0 0.0 0.0 2.84E+08 ZN 65 3.17E+08 8.45E+08 5.26E+08 0.0 5.33E+08 0.0 1.48E+08 SR 89 3.82E+08 0.0 1.09E+07 0.0 0.0 0.0 1.48E+07 SR 90 8.08E+09 0.0 2.05E+09 0.0 0.0 0.0 1.09E+08 ZR 95 2.09E+06 4.60E+05 4.10E+05 0.0 6.59E+05 0.0 4.80E+08 SB 124 2.29E+07 2.97E+05 8.03E+06 5.06E+04 0.0 1.27E+07 1.43E+08 I 131 7.58E+06 7.62E+06 4.33E+06 2.52E+09 1.25E+07 0.0 6.78E+05 I 133 2.63E-01 3.25E-01 1.23E-01 6.04E+01 5.42E-01 0.0 1.31E-01 CS 134 6.77E+08 1.11E+09 2.34E+08 0.0 3.44E+08 1.24E+08 5.99E+06 CS 136 1.43E+07 3.94E+07 2.55E+07 0.0 2.10E+07 3.13E+06 1.38E+06 CS 137 1.01E+09 9.63E+08 1.42E+08 0.0 3.14E+08 1.13E+08 6.03E+06 BA 140 3.91E+07 3.42E+04 2.28E+06 0.0 1.11E+04 2.04E+04 1.98E+07 CE 141 1.82E+04 9.08E+03 1.35E+03 0.0 3.98E+03 0.0 1.13E+07 CE 144 1.70E+06 5.34E+05 9.10E+04 0.0 2.96E+05 0.0 1.39E+08 l
l l
l p
TABLE 3.1-18
(,/
(1 of 1) l
I~'h TABLE 3.1-19 b
(1 of 1)
R VALUES - COW MILK PATH'.!AY - ADULT g
NUCLICE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 7.69E+02 7.69E+02 7.69E+02 7.69E+02 7.69E+02 7.69E+02 CR 51 0.0 0.0 2.38E+04 1.42E+04 5.24E+03 3.15E+04 5.98E+06 MN 54 0.0 6.26E+06 1.19E+06 0.0
~.86E+06 0.0 1.92E+07 FE 55 1.82E+07 1.26E+07 2.94E+06 0.0 0.0 7.03E+06 7.22E+06 FE 59 2.37E+07 5.58E+07 2.14E+07 0.0 0.0 1.56E+07 1.86E+08 CO 58 0.0 3.66E+06 8.19E+06 0.0 0.0 0.0 7.41E+07 C0 60 0.0 1.21E+07 2.68E+07 0.0 0.0 0.0 2.28E+08 ZN 65 1.16E+09 3.69E+09 1.67E+09 0.0 2.47E+09 0.0 2.32E+09 SR 89 1.15E+09 0.0 3.30E+07 0.0 0.0 0.0 1.84E+08 SR 90 3.64E+10 0.0 8.93E+09 0.0 0.0 0.0 1.05E+09 ZR 95 7.38E+02 2.37E+02 1.60E+02 0.0 3.71E+02 0.0 7.50E+05 SB 124 2.02E+07 3.81E+05 7.99E+06 4.89E+04 0.0 1.57E+07 5.72E+08 I 131 1.36E+08 1.94E+08 1.11E+08 6.36E+10 3.32E+08 0.0 5.12E+07 I 133 1.80E+06 3.13E+06 9.55E+05 4.61E+08 5.47E+06 0.0 2.82E+06 CS 134 4.15E+09 9.88E+09 8.08E+09 0.0 3.20E+09 1.06E+09 1.73E+08 CS 136 2.33E+08 9.22E+08 6.63E+08 0.0 5.13E+08 7.03E+07 1.05E+08 CS 137 5.57E+09 7.62E+09 4.99E+09 0.0 2.59E+09 8.59E+08 1.47E+08 BA 140 2.39E+07 3.01E+04 1.57E+06 0.0 1.02E+04
~.72E+04 4.93E+07 1
CE 141 2.38E+04 1.61E+04 1.83E+03 0.0 7.49E+03 0.0 6.17E+07 CE 144 1.58E+06 6.61E+05 8.48E+04 0.0 3.92E+05 0.0 5.34E+08 TABLE 3.1-19 (1 of 1)
i
)
l l
TABLE 3.1-20 V
(1 of 1)
R VALUES - COW MILK PATHWAY - TEENAGER g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 1.00E+03 1.00E+03 1.00E+03 1.00E+03 1.00E+03 1.00E+03 CR 51 0.0 0.0 4.15E+04 2.31E+04 9.10E+03 5.93E+04 6.98E+06 MN 54 0.0 1.04E+07 2.07E+06 0.0 3.11E+06 0.0 2.14E+07 FE 55 3.23E+07 2.29E+07 5.34E+06 0.0 0.0 1.45E+07 9.92E+06 FE 59 4.14E+07 9.67E+07 3.73E+07 0.0 0.0 3.05E+07 2.29E+08 CO 58 0.0 6.15E+06 1.42E+07 0.0 0.0 0.0 8 45E+07 CO 60 0.0 2.06E+07 4.63E+07 0.0 0.0 0.0 2.68E+08' ZN 65 1.78E+09 6.18E+09 2.88E+09 0.0 3.96E+09 00 2.62E+09 SR 89 2.12E+09 0.0 6.07E+07 0.0 0.0 0.0 2.53E+08 SR 90 5.14E+10 0.0 1.27E+10
.0.0 0.0 0.0 1.44E+09 ZR 95 1.29E+03 4.07E+02 2.80E+02 0.0 5.98E+02 0.0 9.39E+05 SB 124 3.60E+07 6.62E+05 1.40E+07 8.16E+04 0.0 3.14E+07 7.25E+08 I -131 2.46E+08 3.44E+08 1.85E+08 1.01E+11 5.93E+08 0.0 6.81E+07 I-133 3.29E+06 5.58E+06 1.70E+06 7.79E+08 9.79E+06 0.0 4.22E+06 CS 134 7.21E+09 1.70E+10 7.87E+09 0.0 5.39E+09 2.06E+09 2.11E+08
%)
CS 136-3.97E+08 1.56E+09 1.05E+09 0.0 8.51E+08 1.34E+08 1.26E+08 CS 137 1.01E+10 1.34Et10 4.68E+09 0.0 4.57E+09 1.78E+09 1.91E+08 i
BA 140 4.32E+07 5.30E+04 2.78E+06 0.0 1.80E+04 3.56E+04 6.67E+07 I
CE 141 4.37E+04 2.92E+04 3.35E+03 0.0 1.37E+04 0.0 8.35E+07 CE 144 2.91E+06 1.20E+06 1.56E+05 0.0 7.19E+05 0.0 7.31E+08 l
TABLE 3.1-20 (1 of 1)
.s 4
's TABLE 3.1-21 s,)
(1 of 1)
R VALUES - COW MILK PATHWAY - CHILD g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 CR 51 0.0 0.0 8.47E+04 4.70E+04 1.28E+04 8.58E+04 4.49E+06 MN 54 0.0 1.56E+07 4.16E+06 0.0 4.38E+06 0.0 1.31E+07 FE 55 8.11E+07 4.30E+07 1.33E+07 0.0 0.0 2.43E+07 7.97E+06 FE 59 9.61E+07 1.55E+08 7.74E+07 0.0 0.0 4.51E4G7 1.62E+08 CO 58 0.0 9.40E+06 2.88E+07 0.0 0.0 0.0 5.48E+07 CO 60 0.0 3.19E+07 9.41E+07 0.0 0.0 0.0 1.77E+08 ZN 65 3.49E+09 9.31E+09 5.79E+09 0.0 5.87E+09 0.0 1.63E+09 SR 89 5.25E+09 0.0 1.50E+08 0.0 0.0 0.0 2.03E+08 SR 90 8.69E+10 0.0 2.20E+10 0.0 0.0 0.0 1.17E+09 ZR 95 3.00E+03 6.59E+02 5.86E+02 0.0 9.43E+02 0.0 6.87E+05 SB 124 8.51E+07 1.10E+0'6 2.98E+07 1.88E+05 0.0 4.72E+07 5.32E+08 I 131 5.97E+08 6.00E+08 3.41E+08 1.98E+11 9.85E+08 0.0 5.34E+07 I 133 8.00E+06 9.89E+06 3.74E+06 1.84E+09 1.65E+07 0.0 3.98E+06 CS 134 1.66E+10 2.73E+10 5.75E+09 0.0 8.45E+09 3.03E+09 1.47E+08 CS 136 8.97E+08 2.47E+09 1.60E+09 0.0 1.31E+09 1.96E+08 8.67E+07 y
CS 137 2.43E+10 2.33E+10 3.44E+09 0.0 7.59E+09 2.73E+09 1.46E+08 BA 140 1.04E+08 9.14E+04 6.09E+06 0.0 2.98E+04 5.45E+04 5.29E+07 CE 141 1.08E+05 5.37E+04 7.97E+03 0.0 2.35E+04 0.0 6.70E+07 CE 144 7.17E+C6 2.25E+06' 3.83E+05 0.0 1.24E+06 0.0 5.86E+08
(
TABLE 3.1-21 (1 of 1)
/)
TABLE 3.1-22
'Q (1 of 1)
R VALUES - COW MlLK PATHWAY - INFANT g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 2.40E+03 2.40E+03 2.40E+03 2.40E+03 2.40E+03 2.40E+03 CR 51 0.0 0.0 1.34E+05
- 8. 75E+04 1.91E+04 1.70E+05 3.91E+06 MN 54 0.0 2.90E+07 6.58E+06 0.0 6.43E+06 0.0 1.07E+07 FE 55 9.81E+07 6.34E+07 1.69E+07 0.0 0.0 3.10E+07 8.04E+06 FE 59 1.79E+08 3.13E+08 1.23E+08 0.0 0.0 9.26E+07 1.50E+08 C0 58 0.0 1.88E+07 4.69E+07 0.0 0.0 0.0 4.69E+0/
CO 60 0.0 6.52E+07 1.54E+08 0.0 0.0 0.0 1.55E+08 ZN 65 4.69E+09 1.61E+10 7.42E+09 0.0 7.80E+09 0.0 1.36E+10 SR 89 9.98E+09 0.0 2.86E+08 0.0 0.0 0.0 2.05E+08 SR 90 9.45E+10 0.0 2.41E+10 0.0 0.0 0.0 1.18E+09 ZR 95 5.30E+03 1.30E+03 9.20E+02 0.0 1.40E+03 0.0 6.46E+05 SB 124 1.64E+08 2.41E+06 5.08E+07 4.35E+05 0.0 1.03E+08 5.06E+08 I 131 1.25E+09 1.47E+09 6.45E+08 4.82E+11 1.71E+09 0.0 5.24E+07 I 133 1.69E+07 2.46E+07 7.20E+06 4.47E+09 2.89E+07 0.0 4.16E+06
- )
CS 134 2.68E+10 4.99E+10 5.04E+09 0.0 1.29E+10 5.27E+09 1.36E+08 CS 136 1.75E+09 5.15E+09 1.92E+09 0.0 2.05E+09 4.20E+08 7.83E+07 CS 137 3.88E+10 4.54E+10 3.22E+09 0.0 1.22E+10 4.94E+09 1.42E+08 BA 140 2.15E+08 2.15E+05 1.11E+07 0.0 5.10E+04 1.32E+05 5.27E+07 CE 141 2.13E+05 1.30E+05 1.53E+04 0.0 4.01E+04 0.0 6.73E+07 CE 144 1.03E+07 4.21E+06 5.76E+05 0.0 1.70E+06 0.0 5.89E+08 f'j TABLE 3.1-22
\\g (1 of 1)
\\
TABLE 3.1-23 (1 of 1)
R VALUES - GOAT MILK PATHWAY - ADULT g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 CR 51 0.0 0.0 2.85E+03 1.71E+03 6.28E+02 3.79E+03 7.17E+05 MN 54 0.0 7.51E+05 1.43E+05 0.0 2.24E+05 0.0 2.30E+06 FE 55 2.37E+06 1.64E+06 3.82E+05 0.0 0.0 9.13E+05 9.39E+05 FE 59 3.09E+06 7.25E+06 2.78E+06 0.0 0.0 2.03E+06 2.42E+07 CO 58 0.0 4.39E+05 9.83E+05 0.0 0.0 0.0 8.89E+06 C0 60 0.0 1.46E+06 3.21E+06 0.0 0.0 0.0 2.73E+07 ZN 65 1.39E+08 4.43Et08 2.00E+08 0.0 2.96E+08 0.0 2.79E+08 SR 89 2.42E+09 0.0 6.93E+07 0.0 0.0 0.0 3.87E+08 SR 90 7.64E+10 0.0 1.87E+10 0.0 0.0 0.0 2.21E+09 ZR 95 8.85E+01 2.84E+01 1.92E+01 0.0 4.46E+01 0.0 9.00E+04 SB 124 2.42E+06 4.57E+04 9.59E+05 5.87E+03 0.0 1.88E+06 6.87E+07 l
I 131 1.63E+08 2.33E+08 1.33E+08 7.63E+10 3.99E+08 0.0 6.14E+07 I 133 2.16E+06 3.76E+06 1.15E+06 5.53E+08 6.56E+06 0.0 3.38E+06 f'S CS 134 1.25E+10 2.96E+10 2.42E+10 0.0 9.59E+09 3.18E+09 5.19E+08 x,,)
CS 136 7.00E+08 2.76E+09 1.99E+09 0.0 1.54E+09 2.11E+08 3.14E+08 CS 137 1.67E+10 2.28E+10 1.50E+10 0.0 7.76E+09 2.58E+09 4.42E+08 BA 140 2.87E+06 3.61E+03 1.88E+05 0.0 1.23E+03 2.07E+03 5.92E+06 CE 141 2.86E+03 1.94E+03 2.20E+02 0.0 8.99E+02 0.0 7.40E+06 CE 144 1.90E+05 7.93E+04 1.02E+04 0.0 4.70E+04 0.0 6.41E+07 i
(O TABLE 3.1-23
,,)
(1 of 1)
O TABLE 3.1-24 (1 of 1)
R VALUES - GOAT MILK PATHWAY - TEENAGER f
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H
3 0.0 204E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 CR 51 0.0 0.0 4.98E+03 2.77E+03 1.09E+03 7.11E+03 8.37E+05 MN 54 0.0 1.25E+06 2.48E+05 0.0 3.73E+05 0.0 2.57E+06 TE 55 4.20E+06 2.98E+06 6.95E+05 0.0 0.0 1.89E+06 1.29E+06 FE 59 5.39E+06 1.26E+07 4.85E+06 0.0 0.0 3.96E+06 2.97E+07 CO 58 0.0 7.39E+05 1.70E+06 0.0 0.0 0.0 1.02E+07 CO 60 0.0 2.47E+06 5.56E+06 0.0 0.0 0.0 3.21E+07 ZN 65 2.14E+08 7.42E+08 3.46E+08 0.0 4.75E+08 0.0 3.14E+08 SR 89 4.45E+09 0.0 1.28E+08 0.0 0.0 0.0 5.30E+08 SR 90 1.08E+11 0.0 2.67E+10 0.0 0.0 0.0 3.03E+09 ZR 95 1.55E+02 4.d8E+01 3.36E+01 0.0 7.18E+01 0.0 1.13E+05 SB 124 4.31E+06 7.95E+04 1.68E+06 9.79E+03 0.0 3.77E+06 8.70E+07 I 131 2.95E+08 4.13E+08 2.22E+08 1.21E+11 7.12E+08 0.0 8.18E+07 I 133 3.95E+06 6.70E+06 2.04E+06 9.35E+08 1.17E+07 0.0 5.07E+06 k',)3 CS 134 2.16E+10 5.09E+10 2.36E+10 0.0 1.62E+10 6.17E+09 6.33E+08 CS 136 1.19E+09 4.69E+09 3.15E+09 0.0 2.55E+09 4.03E+08 3.78E+08 CS 137 3.03E+10 4.03E+10 1.40E+10 0.0 1.37E+10 5.33E+09 5.73E+08 BA 140 5.19E+06 6.35E+03 3.34E+05 0.0 2.15E+03 4.27E+03 8.00E+06 CE 141 5.25E+03 3.50E+03 4.02E+02 0.0 1.65E+03 0.0 1.00E+07 CE 144 3.49E+05 1.44E+05 1.88E+04 0.0 8.62E+04 0.0 8.77E+07
('~N)
TABLE 3.1-24 g,
(1 of 1)
[h TABLE 3.1-25
\\l (1 of 1)
R VALUES - GOAT MILK PATHWAY - CHILD g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LLWG GI-LLI H
3 0.0 3.23E+03 3.23E+03 3.23E+03 3.23E+03 3.23E+03 3.23E+03 CR 51 0.0 0.0 1.02E+04 5.64E+03 1.54E+03 1.03E+04 5.39E+05
.1N 54 0.0 1.87E+06 4.99E+05 0.0 5.25E+05 0.0 1.57E+06 FE 55 1.05E+07 5.59E+06 1.73E+06 0.0 0.0 3.16E+06 1.04E+06 FE 59 1.25E+07 2.02E+07 1.01E+07 0.0 0.0 5.86E+06 2.10E+07 CO 58 0.0 1.13E+06 3.45E+06 0.0 0.0 0.0 6.58E+06 CO 60 0.0 3.83E+06 1.13E+07 0.0 0.0 0.0 2.12E+07 ZN 65 4.19E+08 1.12E+09 6.95E+08 0.0 7.04E+08 0.0 1.96E+08 SR 89 1.10E+10 0.0 3.15E+08 0.0 0.0 0.0 4.27E+08 SR 90 1.82E+11 0.0 4.62E+10 0.0 0.0 0.0 2.46E+09 ZR 95 3.60E+02 7.91E+01 7.04E+01 0.0 1.13E+02 0.0 8.25E+04 SB 124 1.02E+07 1.32E+05 3.58Et06
- 2. 25E+04 0.0 5.67E+06 6.38E+07 I 131 7.16E+08 7.20E+08 4.09E+08 2.38E+11 1.18E+09 0.0 6.41E+07 j
I 133 9.59E+06 1.19E+07 4.49E+06 2.20E+09 1.98E+07 0.0 4.78E+06
('N CS 134 4.99E+10 8.18E+10 1.73E+10 0.0 2.54E+10 9.10E+09 4.41Et08 s_,)
CS 136 2.69E+09 7.40E+09 4.79E+09 0.0 3.94E+09 5.88E+08 2.60E+08
~
CS 137 7.30E+10 6.98E+10 1.03E+10 0.0 2.28E+10 8.19E+09 4.37E+08 BA 140 1.25E+07 1.10E+04 7.31E+05 0.0 3.57E+03 6.54E+03 6.34E+06 CE 141 1.29E+04 6.44E+03 9.57E+02 0.0 2.83E+03 0.0 8.04E+06 CE 144 8.60E+05 2.70E+05 4.59E+04 0.0 1.49E+05 0.0 7.03E+07 p
TABLE 3.1-25 (1 of 1) l
{
l
. _ _ _ _ ~ _ _ _ _ _
('
TABLE 3.1-26
(,
(1 of 1)
R VALUES - GOAT MILK PATHWAY - LVFANT g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H
3 0.0 4.90E+03 4.90E+03 4.90E+03 4.90E+03 4.90E+03 4.90E+03 CR 51 0.0 0.0 1.61E+04 1.05E+04 2.29E+03 2.04E+04 4.69E+05 MN 54 0.0 3.48E+06 7.89E+05 0.0 7.72E+05 0.0 1.28E+06 FE 55 1.27E+07 8.24E+06 2.20E+06 0.0 0.0 4.03E+06 1.05E+06 FE 59 2.33E+07 4.07E+07 1.60E+07 0.0 0.0 1.20E+07 1.95E+07 CO 58 0.0 2.26E+06 5.63E+06 0.0 0.0 0.0 5.62E+06 C0 60 0.0 7.82E+06 1.85E+07 0.0 0.0 0.0 1.86E+07 ZN 65 5.63E+08 1.93E+09 8.91E+08 0.0 9.36E+08 0.0 1.63E+09 SR 89 2.10E+10 0.0 6.01E+08 0.0 0.0 0.0 4.31E+08 SR 90 1.98E+11 0.0 5.05E+10 0.0 0.0 0.0 2.48E+09 ZR 95 6.39E+02 1.56E+02 1.10E+02 0.0 1.68E+02 0.0 7.75E+04 SB 124 1.97E+07 2.90E+05 6.10E+06 5.22E+04 0.0 1.23E+07 6.07E+07 I 131 1.49E+09 1.76E+09 7.74E+08 5.79E+11 2.06E+09 0.0 6.29E+07 I 133 2.03E+07 2.95E+07 8.64E+06 5.36E+09 3.47E+07 0.0 4.99E+06
'N CS 134 8.03E+10 1.50E+11 1.51E+10 0.0 3.86E+10 1.58E+10 4.07E+08
^")
CS 136 5.26E+09 1.55E+10 5.77E+09 0.0 6.16E+09 1.26E+09 2.35E+08 CS 137 1.16E+11 1.36E+11 9.66E+09 0.0 3.66E+10 1.48E+10 4.26F+08 BA 140 2.58E+07 2.58E+04 1.33E+06 0.0 6.12E+03 1.58E+04 6.33E+06 CE 141 2.56E+04 1.56E+04 1.84E+03 0.0 4.82E+03 0.0 8.07E+06 CE 144 1.23E+06 5.05E+05 6.91E+04 0.0 2.04E+05 0.0 7.07E+07
(~
IABLE 3.1-26
(
(1 of 1)
/'"D TABLE 3.1-27 k)
(1 of 1) s-R VALUES - INHALATION PATINAY - ADULT g
NUCLIDE BONE LIVER T.BCDY THYROID KIDNEY LUNG GI-LLI H
3 0.0 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 CR 51 0.0 0.0 9.99E+01 5.94E+01 2.28E+01 5.94E+04 3.32E+03 MN 54 0.0 3.95E+04 6.29E+03 0.0 9.83E+03 1.40E+06 7.72E+04 FE 55 2.45E+04 1.69E+04 3.94E+03 0.0 0.0 7.20E+04 6.02E+03 FE 59 1.17E+04 2.77E+04 1.05E+04 0.0 0.0 1.01E+06 1.88E+05 CO 58 0.0 1.58E+03 2.07E+03 0.0 0.0 9.27E+05 1.06E+05 CO 60 0.0 1.15E+04 1.48E+04 0.0 0.0 5.96E+06 2.84E+05 ZN 65 3.24E+04 1.03E+05 4.65E+04 0.0 6.89E+04 8.63E+05 5.34E+04 SR 89 3.04E+05 0.0 8.71E+03 0.0 0.0 1.40E+06 3.49E+05 SR 90 9.91E+07 0.0 6.09E+06 0.0 0.0 9.59E+06 7.21E+05 ZR 95 1.07E+05 3.44E+04 2.32E+04 0.0 5.41Ew04 1.77E+06 1.50E+05 SB 124 3.12E+04 5.88E+02 1.24E+04 7.54E+01 0.0 2.48E+06 4.06E+05 I 131 2.52E+04 3.57E+04 2.05E+04 1.19E+07 6.12E+04 0.0 6.27E+03 I 133 8.63E+03 1.48E+04 4.51E+03 2.15E+06 2.58E+04 0.0 8.87E+03 CS 134 3.72E+05 8.47E+05 7.27E+05 0.0 2.87E+05 9.75E+04 1.04E+04 k'm,)T CS 136 3.90E+04 1.46E+05 1.10E+05 0.0 8.55E+04 1.20E+04 1.17E+04
~
CS 137 4.78E+05 6.20E+05 4.27E+05 0.0 2.22E+05 7.51E+04 8.39E+03 BA 140 3.90E+04 4.90E+01 2.56E+03 0.0 1.67E+01 1.27E+06 2.18E+05 CE 141 1.99E+04 1.35E+04 1.53E+03 0.0 6.25E+03 3.61E+05 1.20E+05 CE 144 3.43E+06 1.43E+06 1.84E+0!
0.0 8.47E+05 7.76E+06 8.15E+05 O
TABLE 3.1-27 (1 of 1)
<N TABLE 3.1-28 (1 of 1)
R VALUES - INHALATION PATHWAY - TEENAGER g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H
3 0.0 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 CR 51 0.0 0.0 1.35E+02 7.49E+01 3.07E+01 2.09E+04 3.00E+03 MN 54 0.0 5.10E+04 8.39E+03 0.0 1.27E+04 1.98E+06 6.67E+04 FE 55 3.34E+04 2.38E+04 5.54E+03 0.0 0.0 1.24E+05 6.38E+02 FE 59 1.59E+04 3.69E+04 1.43E+04 0.0 0.0 1.53E+06 1.78E+05 CO 58 0.0 2.07E+03 2.77E+03 0.0 0.0 1.34E+06 9.51E+04 CO 60 0.0 1.51E+04 1.98E+04 0.0 0.0 8.71E+06 2.59E+05 ZN 65 3.85E+04 1.33E+05 6.23E+04 0.0 8.63E+04 1.24E+06 4.66E+04 SR 89 4.'4E+05 0.0 1.25E+04 0.0 0.0 2.41E+06 3.71E+05 SR 90 1.08E+08 0.0 6.67E+06 0.0 0.0 1.65E+07 7.64E+05 ZR 95 1.45E+05 4.58E+04 3.15E+04 0.0 6.73E+04 2.68E+06 1.49E+05 SB 124 4.30E+04 7.92E+02 1.68E+04 9.75E+01 0.0 3.84E+06 3.98E+05 I 131 3.54E+04 4.90E+04 2.64E+04 1.46E+07 8.39E+04 0.0 6.48E+03 I 133 1.21E+04 2.05E+04 6.21E+03 2.92E+06 3.59E+04 0.0 1.03E+04
('S CS 134 5.02E+05 1.13E+06 5.48E+05 0.0 3.75E+05 1.46E+05 9.75E+03
\\'"')
CS 136 5.14E+04 1.93E+05 1.37E+05 0.0 1.10E+05 1.77E+04 1.09E+04 CS 137 6.69E+05 8.47E+05 3.11E+05 0.0 3.04E+05 1.21E+05 8.47E+03 BA 140 5.46E+04 6.69E+01 3.51E+03 0.0 2.28E+01 2.03E+06 2.28E+05 CE 141 2.84E+04 1.89E+04 2.16E+03 0.0 8.87E+03 6.13E+05 1.26E+05 CE 144 4.88E+06 2.02E+06 2.62E+05 0.0 1.21E+06 1.33E+07 8.63E+05
, p TABLE 3.1-28 y
(1 of 1)
(N TABLE 3.1-29
\\
(1 of 1)
R VALUES - INHALATION PATINAY - CHILD g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H
3 0.0 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 CR 51 0.0 0.0 1.54E+02 8.53E+01 2.43E+01 1.70E+04 1.08E+03 MN 54 0.0 4.29E+04 9.50E+03 0.0 1.00E+04 1.57E+06 2.29E+04 FE 55 4.73E+04 2.51E+04 7.76E+03 0.0 0.0 1.11E+05 2.86E+03 FE 59 2.07E+04 3.34E+04 1.67E+04 0.0 0.0 1.27E+06 7.06E+04 CO 58 0.0 1.77E+03 3.16E+03 0.0 0.0 1.10E+06 3.43E+04 CO 60 0.0 1.31E+04 2.26E+04 0.0 0.0 7.06E+06 9.61E+04 ZN 65 4.25E+04 1.13E+05 7.02E+04 0.0 7.13E+04 9.94E+05 1.63E+04 SR 89 5.99E+05 0.0 1.72E+04 0.0 0.0 2.15E+06 1.67E+05 SR 90 1.01E+08 0.0 6.43E+06 0.0 0.0 1.47E+07 3.43E+05 ZR 95 1.90E+05 4.17E+04 3.69E+04 0.0 5.95E+04 2.23E+06 6.10E+04 SB 124 5.73E+04 7.39E+02 2.00E+04 1.26E+02 0.0 3.24E+06 1.64E+05 I 131 4.80E+04 4.80E+04 2.72E+04 1.62E+07 7.87E+04 0.0 2.84E+03 I 133 1.66E+04 2.03E+04 7.68E+03 3.84E+06 3.37E+04 0.0 5.47E+03 C's CS 134 6.50E+05 1.01E+06 2.24E+05 0.0 3.30E+05 1.21E+05 3.84E+03 CS 136 6,50E+04 1.71E+05 1.16E+05 0.0 9.53E+04 1.45E+04 4.17E+03 D
CS 137 9.05E+05 8.24E+05 1.28E+05 0.0 2.82E+05 1.04E+05 3.61E+03 BA 140 7.39E+04 6.47E+01 4.32E+03 0.0 2.11E+01 1.74E+06 1.02E+05 CE 141 3.92E+04 1.95E+04 2.89E+03 0.0 8.53E+03 5.43E+05 5.65E+04 CE 144 6.76E+06 2.11E+06 3.61E+05 0.0 1.17E+06 1.19E+07 3.88E+05
)
TABLE 3.1-29 (1 of 1)
i
{N TABLE 3.1-30 (1 of 1) 1 R VALUES - INHALATION PATHWAY - INFANT g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNO GI-LLI H
3 0.0 6.46E+02 6.46E+02 6.46E+02 6.46E+02 6.46E+02 6.46E+02 CR 51 0.0 0.6 8.93E+01 5.75E+01 1.32E+01 1.2bE+04 3.56E+02 MN 54 0.0 2.53E+04 4.98E+03 0.0 4.98E+03 9.98E+05 7.05E+03 FE 55 1.97E+04 1.17E+04 3.33E+03 0.0 0.0 8.68E+04 1.09E+03 FE 59 1.35E+04 2.35E+04 9.46E+03 0.0 0.0 1.01E+06 2.47E+04 CO 58 0.0 1.22E+03 1.82E+03 0.0 0.0 7.76E+05 1.11E+04 CO 60 0.0 8.01E+03 1.18E+04 0.G 0.0 4.50E+06 3.19E+04 ZN 65 1.93E+04 6.25E+04 3.10E+04 0.0 3.24E+04 6.46E+05 5.13E+04 SR 89 3.97E+05 0.0 1.14E+04 0.0 0.0 2.03E+06 6.39Et04 SR 90 4.08E+07 0.0 2.59E+06 0.0 0.0 1.12E+07 1.31E+05 ZR 95 1.15E+05 2.78E+04 2.03E+04 0.0 3.10E+04 1.75E+06 2.17E+04 SB 124 3.79E+04 5.55E+02 1.20E+04 1.00E+02 0.0 2.64E+06 5.90E+04 1 131 3.79E+04 4.43E+04 1.96E+04 1.48E+07 5.17E+04 0.0 1.06E+03 I 133 1.32E+04 1.92E+04 5.59E+03 3.55E+06 2.24E+04 0.0 2.15E+03
~
(~
CS 134 3.96E+05 7.02E+05 7.44E+04 0.0 1.90E+05 7.95E+04 1.33E+03
(
CS 136 4.82E+04 1.34E+05 5.28E+04 0.0 5.63E+04 1.17E+04 1.43E+03 CS 137 5.48E405 6.11E+05 4.54E+04 0.0 1.72E+05 7.12E+04 1.33E+03 BA 140 5.59E+04 5.59E+01 2.89E+03 0.0 1.34E+01 1.59E+06 3.83E+04 CE 141 2.77E+04 1.66E+04 1.99E+03 0.0 5.24E+03 5.16E+05 2.15E+04 i
CE 144 3.19E+06 1.21E+06 1.76E+05 0.0 5.37E+05 9.83E+06 1.48F+05 1
7 i
e TABLE 3.1-30 (1 of 1)
i--
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APPENDIX A OCONEE NUCLEAR STATION SITE SPECIFIC INFORMATION O
t I
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a w
a O
l TO BE ADDED LATER O
l
i L
l O
i i
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I i
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APPENDIX B l
MCGUIRE NUCLEAR STATION l
SITE SPECIFIC INFORMATION i
O
u.
2-4 a
_.2.2 m
.a.
m m_
m Bl.0 MCGUIRE NUCLEAR STATION RADWASTE SYSTEMS B-1 B2.0 RELEASE RATE CALCULATION B-4 B3.0 RADIATION MONITOR SETPOINTS B-8 B4.0 DOSE CALCUIATIONQ B-12 4
B5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING B-18 1
I O
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i
.. =. __ _ _ - _.
Bl.0 MCGUIRE NUCLEAR STATION RADWASTE SYSTEMS Bl.1 LIQUID RADWASTE PROCESSING i
The liquid radwaste system at McGuire Nuclear Station (MNS) is used to collect and treat fluid chemical and radiochemical by-products of unit operation. The i
system produces effluents which can be reused in the plant or discharged in small, dilute quantities to the environment. The means of treatment vary with waste type and desired product in the various systems:
A)
Filtration - Waste sources are filtered during processing. In some cases, such as the Floor Drain Tank (FDT) Subsystem of the Liquid Waste (WL)
System, filtration may be the only treatment required.
B)
Adsorption - Adsorption of halides and organic chemicals by activated charcoal (Carbon Filter) may be used in treating waste in the Laundry and Hot Shower Tank (LHST). The carbon filter is designed to remove organ-ophosphetes and free chlorine. Activated charcoal need not be used when these chemicals are not present (e.g., phosphate detergents are not used at the station).
Ion exchange resin or other media may be ased in the carbon filter vessel as desired.
C)
Ion Exchange - Ion exchange is used to remove radioactive cations from solution, as in the case of either LHST or FDT waste in the WL System after removal of organics by carbon filtration (adsorption).
Ion exchange is also used in removing both cations,(cobalt, mangarese) and i
anions (chloride, fluoride) from evaporator distillates in order to
/ )
purify the distillates for reuse as makeup water. Distillate from the k- /
Waste Evaporator in the WL System and the Boron Recycle Evaporator in the Boron Recycle System (NB) can be treated by this method, as well as FDT, LHST waste, and reactor bleed.
D)
Gas Stripping - Removal of gaseous radioactive fission products is accomplished in both the WL Evaporator and the NB Evaporator.
E)
Distillation - Production of pure water from the waste by boiling it away from the contaminated solution which originally contained it is accomplished by both evaporators. Proper control of the process will i
l yield water which can be reused for makeup. Polishing of this product can be achieved by ion exchange as pointed out above.
F)
Concentration - In both the WL and NB Evaporators, dissolved chemicals are concentrated in the lower shell as water is boiled away.
In the case of the WL Evaporator, the volume of water containing waste chemicals and radioactive cations is reduced so that the waste may be more easily and cheaply solidified and shipped for burial.
In the NB Evaporator, the dilute boron is normally concentrated to 4% so that it may be reused for makeup to the reactor coolant system.
l-Figure Bl.0-1 is a schematic representation of the liquid radwaste system at McGuire.
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N TABLE Bl.0-1 (1 of 2)
ABBREVIATIONS Systems:
KC - Component Cooling NB - Boron Recycle NC - Reactor Coolant ND - Residual Heat Removal NI - Safety Injection NR - Boron Thermal Regeneration NV - Chemical Volume and Control WC - Conventional Waste Water Treatment WG - Waste Cas WL - Liquid Waste Recycle WM - Liquid Waste Monitor and Disposal WS - Nuclear Solid Waste Disposal i
Terms:
I BOL - Beginning of Core Life BTRS - Boron Thermal Regeneration System CCW - Condenser Cooling Water CDT - Chemical Drain Tank ECST - Evaporator Concentrates Storage Tank EOL - End of Core Life FDT - Floor Drain Tank FWST - Fueling Water Storage Tank (formerly Refueling Water Storage Tank)
LHST - Laundry and Hot Shower Tank MST - Mixing and Settling Tank NCDT - Reactor Coolant Drain Tank RBT - Resin Batching Tank RHT - Recycle Holdup Tank i
RMT - Recycle Monitor Tank l
l RMWST - Reactor Makeup Water Storage Tank TABLE Bl.0-1 (1 of 2)
-+
y 97---
-4
l
'f TABLE Bl.0-1 (2 of 2)
ABBREVIATIONS i
i d
l j
SRST - Spent Resin Storage Tank
]
VUCDT - Ventilation Unit Condensate Drain Tank l
WDT - Waste Drain Tank WEFT - Waste Evaporator Feed Tank WMT - Waste Monitor Tank i
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TABLE Bl.0-1 l
(2 of 2)
- l
l 1
Bl.2 GASEOUS RADWASTE SYSTEMS The gaseous waste disposal system for McGuire is designed with the capability of processing the fission product gases from contaminated reactor coolant fluids resulting from operation. The design base for the system shown schema-tically in Fig. Bl.0-2 is the retention, through the plant Lifetime, of all L
the gaseous fission products to be discharged from the reactor coolant system to the chemical and volure control system and other plant systems to eliminate the need for intentional discharge of radioactive gases from the waste gas holdup tanks. Actual system operation is aimed at maximizing storage time for decay prior to infrequent releases. Unavoidable ources of low-level radio-active gaseous discharge to the environment will be from periodic purging operations of the containment, from the auxiliary building ventilation system, and through the secondary system air ejector. With respect to the former, the potential contamination is expected to arise from non-recyclable reactor i
coolant leakage. With respect to the air ejector, the potential source of contamination will be from leakage of the reactor coolant to the secondary system through defects in steam generator tubes. The gaseous waste disposal system includes two waste gas compressors, two catalytic hydrogen recombiners, six gas decay storage tanks for use during normal power generation, and two gas decay storage tanks for use during shutdown and startup operations.
Bl.2.1 Gas Collection System l
The gas collection system combines the waste hydrogen and fission gases from the volume control tanks, the boron recycle and liquid waste gas stripper evaporators, and other sources produced during normal operation or the gas I
collected during the shutdown degasification (high percentage of nitrogen) and cycles it through the catalytic recombiners to convert the hydrogen to water.
After the water vapor is removed, the resulting gas stream is transferred from the recombiner into the gas decay tanks, where the accumulated activity may be contained in six approximately equal parts. From the decay tanks, the gas flows back to the compressor suction to complete the loop circuit.
Bl.2.2 Containment and Auxiliary Building Ventilation Nonrecyclable reactor coolant leakage occurring either inside the containment
~
or inside the auxiliary building will generate gaseous activity. Gasc" result-ing from leakage inside the containment will be contained until the containment i
is purged. The containment atmosphere will be circulated through a charcoal adsorber and a particulate filter prior to release to the atmosphere.
i Gases resulting from leakage inside the a.txiliary building are released, with-i out further decay, to the atmosphere via the auxiliary building ventilation
(
system. The ventilation exhaust-from potentially conteminated areas in the auxiliary building is passed through charcoal adsorbers to reduce releases to the atmosphere.
j Bl.2.3 Secondary Systems When activity is in the secondary system, steam generator blowdown will be recycled through demineralizers to remove activity and the liquids will be removed by the ejector condenser prior to discharge to the unit vent.
B-2
_ = _ _ _ _ _
i I
i l
i r
I Gland leak-off steam, which represents a minor source of activity, is routed to the gland condenser. The non-condensable gases are passed through a vent stack to the roof; the condensables are condensed and drained to the condensate storage tank.
I Figure Bl.0-2 is a schematic representation of the gaseous radwaste system at McGuire.
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ROOP VENTS
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689.000 cfm s.
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OUTSID E OUTSIDE AIR
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AIR R8WE i
A i
PRIMARY l
1 COOLANT l
CONDENSER I
g STEAM 1
)
itTRFIN3 IUMING "Y" GENERATOR V
~
_ _.3 00NDENSE R L
STEAM JET AIR g
TO CONDENSER WITH EJE CTO RS J ADI ATION MONITOR 142 PT 8 APPLES ggoyg GROUNO UNIT S LOWOOWN RECYCLE M k RADI V
TANK
~
MON LETOOWN PLOW SECONDARY SYSTEM (2 UNITS)
P ROM REACTOR COOLANT SYSTEM """
g
-(2) HYOROGEN j
g' RECOfASINERS f
ti Wun GAS i i
.--g, COMP RESSO RS I IOxvGEN W ATE R g
2 2
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// nN
/t gg CONTROL l CONTROL TANK /Q\\
/Q\\
ST G TANKS l
UNIT 1 W
W W PLANT j
jCONTROL TANK T_
1J VENT l
v0LuME STA,CX,j 4___
TO TO UNIT 2 REACTOR REACTOR 4
4 4
4 4
4 O#I BORON RECYCLE ST R GE SHIMOLEED TAN KS 600 PT3 EVAPORATOR 110 m g g g g y g GAS STRIPPER
]
WASTE GAS SYSTEM
\\
J
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CONTAINMENT CONTAINM E N T NORMALLY CLOSEO UPPER VOLUME 18,000 cfm 5
l g LOWER VOLUME L
P A C W
=
M" PURGE OUTLET PURGE INLET s.400cfm
^
INTERNATIONAL. RECIRUI.ATING TR AINS (2) 8,000 cfm E ACH E U E ' ",*
4 E PER 4
POTENTI A L 54.000 cfm CONTAMIN ATION a,PlAlC PER UNIT OUTSIDE AREA AlR 34.000 cfm
=
u 9
OTHER ARE AS PER UNIT AU XILI A R Y BUILDING SUPPLY PANS AUXSLI ARY SulLOING SYSTEM (SH ARED)
LEGENO:
(
P PR E PILTE R A HIGH-EPPICIENCY PARTICULATE PILTE R C CHARCOAL AOSOR8ER x\\
J l
FIGURE B1.0-2 l
McGUIRE NUCLEAR STATION GASEOUS RADWASTE SYSTEM DATE COMPILED 1/20/82
B2.0 RELEASE RATE CALCULATION Generic release rate calculations are presented in Section 1.0; these calculations will be used to calculate release rates for McGuire Nuclear Station.
B2.1 LIQUID RELEASE RATE CALCULATIONS There are three potential release points at McGuire. Two of these release points, the waste liquid effluent line and the containment ventilation unit condensate effluent line, discharge into the condenser cooling water flow; the third possible release point is through the conventional waste water treatment system.
B2.1.1 Waste Liquid Effluent Line To simplify calculations for the waste liquid effluent line, it is assumed that no activity above background is present in the containment ventilation unit condensate effluent. This assumption shall be confirmed by radiation monitoring measurements and by periodic analysis of the composite sample collected on that line. For the waste liquid effluent line, one of the follow-ing calculations shall be performed for discharge flow, in gpm, depending on the number of condenser cooling water pumps in service:
n C
i f < F + (o I
)
p i=1 MPC g where:
f = the undiluted effluent flow, in gpm.
F = the dilution flow available depending on the number of condenser cooling water pumps in service, in gpm.
where:
l F1 = 2.50E+05 gpm F2 = 5.00E+05 gym F3 = 7.50E+05 gpm F = 1.00E+06 gpm 4
a = The recirculation factor at equilibrim (dimensionless), 2.4 o=1+
=1+
= 2.4 QH where:
Q = average dilution flow (3720 Cfs)
J R
Q = average fl w past Cowans Ford Dam (2670 Cfs)
H
(
B-4
C
=
g the concentration of radionuclide, "i", in undiluted effluent as deter. mined by laboratory analyses, in pCi/ml.
MPC = the concentration of radionuclide, "i", from 10CFR20, Appendix B, Table II, Column 2.
If radionuclide, "i", is a dissolved noble gas, the MPCg = 2.00E-04 pCi/ml.
B2.1.2 Containment Ventilation Unit Condensate Effluent Line As described in the preceding section, it is possible but unlikely that the containment ventilation unit condensate effluent line will contain measurable activity above background; it is assumed that no activity is present in the effluent until indicated by radiation monitoring measurements and by periodic analysis of the composite sample collected on that line.
If measurable activity is present in the effluent, administrative controls shall be imple-mented to assure that release limits are not exceeded; see section on radia-tion monitoring alarm / trip setpoints.
B2.1.3 Conventional Waste Water Treatment System Effluent Line The conventiocal waste water treatment system effluent is normally considered nonradioactive; that is, it is unlikely the effluent will contain measurable activity above background.
It is assumed that no activity is present in the effluent until indicated by radiation monitoring measurements and by periodic analyJes of the composite sample collected on that line. Radiation monitoring p) alarm / trip serpoints assure that release limits are not exceeded; see section
\\
on radiation monitoring - alarm / trip setpoints.
i B2.2 GASEOUS RELEASE RATE CALCULATIONS The unit vent is the release point for waste gas decay tanks, containment building purges, the condenser air ejector, and auxiliary building ventilation.
The condenser air ejector effluent is normally cocsidered nonradioactive; that is, it is unlikely the effluent will contain measurable activity above back-ground. It if assumed that no activity is present in the effluent until indicated by radiation monitoring measurements and by analyses of periodic samples collected on that line. Radiatica monitoring alarm / trip setpoints in conjunction with administrative controls assure that release limits are not exceeded; see section B3.0 on radiation monitoring setpoints.
The following calculations, when solved for flowrate, are the release rates for noble gases and for radioiodines, particulates and other radionuclides with half-lives greater than 8 days; the most conservative of release rates calculated in B2.2.1 and B2.2.2 shall control the release rate for a single release point.
i
(
B2.2.1 Noble Gases IK
[(X/Q)Q ]
< 500 mrem /yr, and g
g 1
i B-5
l
\\
s
\\,
I (Lg + 1.1 M ) [(X/Q)Q ] < 3000 mrem /yr g
g 1
where the terms are defined below.
B2.2.2 Radioiodines, Particulates, and Others s
IPg [W Q ] < 1500 mrem /yr g
1 where:
K
= The total body dose factor due to gamma emissions for each identified i
noble gas radionuclide, in mrem /yr per pCi/m3 from Table 1.2-1.
L
= The skin dose factor due to beta emissions for each identified noble 3
gas radionuclide, in mrem /yr par pCi/m from Table 1.2-1.
M.
= The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 from Table 1.2-1 (unit conver-sion constant of 1.1 mrem / mrad converts air dose to skin dose).
P.
= The dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem /yr per pCi/m3 and for the food and ground 2
(a plane pathways in m.(mrem /yr) per pCi/sec from Table 1.2-2.
The dose
(,,)
factors are based on the critical individual organ and most restrictive age group (child or infant).
s Q *.
= The release rate of radionuclides, i, in gaseous effluent from all release points at the site, in pCi/sec.
2 x/Q
= 6.7E-5 sec/m. The highest calculated annual average relative concen-tration for any area at or beyond the unrestricted area boundary.
W
= The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location:
3 W = 6.7E-5 sec/m, for the inhalation pathway. The location is the unrestricted area in the NE sector.
W = 1.5E-7 meter 2, for the food and grourc plane pathways. The location is the unrestricted area boundary in the E sector (nearest residence, and vegetable garden).
s Q.
= kCf+k2 = 4.72E+2C.f i 1 1
1 where:
C.
= the concentration of radionuclide, i, in undiluted gaseous effluent, in pCi/ml.
O B-6
l f
= the undil,ted effluent flow, in efm k
=
t conversion factor, 2.83E4 ml/ft3 k
=
2 conversion factor, 6El sec/ min 1
B-7 1
l
(
B3.0 RADIATION MONITOR SETPOINTS
(
Using the generic calculations presented in Section 2.0, radiation monitoring setpoints are calculated for monitoring as required by the Technical Specifications.
All radiation monitors for McGuire are off-line. These monitors alarm on low flow; the minimus flow alarm level for the liquid monitors is 2 gallons per minute and for the gas monitors is 6 standard cubic feet per minute. These monitors measure the activity in the liquid or gas volume exposed to the detector and are independent of flow rate if 2 minimum flow rate is assured.
Radiation monitoring setpoints calculated in the following sections are expressed in activity concentrations; in reality the monitor readout is in counts per minute. The relationship between concentration and counts per minute shall be established by a station procedure using the following relationship:
c=
r 2.22 x 106eV where:
c = the gross activity, in pCi/ml r = the count rate, in epm 2.22 x 10s = the disintegration per minute per pCi e = the counting efficiency, cpm /dpm V = the volume of fluid exposed to the detector, in ml.
m (s )
B3.1 LIQUID RADIATION MONITORS s
B3.1.1 Waste Liquid Effluent Line As described in Section B2.1.1 on release rate calculations for the waste liquid ef fl uent, the release is controlled by limiting the flow rate of effluent from the station. Although the release rate is flow rate controlled, the radiation monitor setpoint shall be set to terminate the release if the effluent activity should exceed that determined by laboratory analysis and that used to calculate the release rate. When releases are not being made, a radiation monitor set-point shall be calculated to assure that release limits are not exceeded. A typical setpoint is calculated as follows:
c<
= 1.04E-4 pCi/ml f
l where:
c = the gross activity in undiluted effluent, in pCi/ml f = the flow from the tank may vary from 0-100 gpm but, for this calculation, is assumed to be 100 gpm (the actual flow is set by flow selection on the manually loaded throttle valve, a Kerotest globe valve)
B-8
P MPC = 1.0E-07 pCi/ml, the MPC for an unidentified mixture o = 2.4 (See Section B2.1.1)
F = the dilution flow is based on having only one condenser cooling water in service or 2.5E+5 gra. Should the number of pumps in service increase, the setpoint may be recalculated.
B3.1.2 Containment Ventilation Unit Condensate Effluent Line As described in Section B2.1.2 on release rate calculations for the containment ventilation unit condensate effluent, it is possible but unlikely that the effluent will contain measurable activity above background.
It is assumed that no activity is present in the effluent until indicated by radiation monitoring and by routine analyses of the composite sacple collected on that line. Since the tank contents are discharged automatically, a maximum tank concentration, which also is the radiation monitor setpoint, is calev. lated to assure that release limits are not exceeded. A typical monitor setpoint and maximum tank concentration is calculated as follows:
MPC x F
- I of
= 1.04E-4 pCi/ml where:
I
= the gross activi y in undiluted effluent, in pCi/ml e
f
= the flow from the tank may vary from 0-100 gpm but, for this calculation, is assumed to be 100 gpa MPC = 1.0E-07 pCi/ml, the MPC for an unidentified mixture j
o
= 2.4 (See Section B2.1.1) s F
= the dilution flow is based on having only one condenser cooling pump in service or 2.5E+5 gpm.
Should the number of pumps in service increase, the setpoint may be recalculated.
The above calculation will determine the maximum setpoint for this release point; releases and/or setpoints may be administratively controlled to assure that release limits are not exceeded since more than one release source may be released to the condenser cooling water.
.B3.1.3 Conventional Waste Water Treatment System Discharge Line As described in Section B2.1.3 on release rate calculations for the conventional waste water treatment system effluent, the effluent is noreally considered l
non-radioactive; that is, it is unlikely the effluent will contain measurable activity above background.
It is assumed that no activity is present in the effluent until indicated by radiation monitoring and by routine analysis of B-9
the composite sample collected on that line. Since the system discharges auto-matically, the ma imum system concentration, which also is the radiation moni-tor setpoint, is calculated so that release limits are not exceeded. A typical monitor setpoint and maximum effluent concentration is calculated as follows:
MPC x F CI of
= 5.4E-7 pCi/ml where:
= the gross activity in undiluted effluent, in pCi/ml c
f
= the flow rate of undiluted effluent which may vary from 0-6700 gpm, but is assumed to be 6700 gpm MPC = 1.0E-07 LCi/m1, the MPC for an unidentified mixture F
= the flow may vary from 80 to 50,000 cfs, but is conservatively estimated at 80 cfs (3.6E+4 gpm), the minimum flow available
= 1 [The Conventional Waste Water System discharge line is located down-o stream of Cowan's Ford Dam and, therefore, has no reconcentration (recirculation) factor associated with it.]
OL) pJ B-10
B3.2 GAS MONITORS v
The following equation shall be used to calculate noble gas radiation monitor setpoints based on Xe-133:
K(5)k<500 (See section B2.2.1) s Qg = 4.72E+2 C f (See Section B2.2.2) g Cg < 5.37E+01/f where:
C
= the gross activity in undiluted effluent, in pCi/ml g
f
= the flow from the tank or building and varies for various release sources, in cfm K
= from Table 1.2-1 for Xe-133, 2.94E+2 mrem /yr per pCi/m3
~
X7Q 3
= 6.7E-5 sec/m, as defined in Section B2.2.2.
As stated in Section B2.2, the unit vent is the release point for the contain-ment purge ventilation system, the containment air release and addition system, the condenser air ejector, and auxiliary building ventilation. Since all of these releases are through the unit vent, the radiation monitor on the unit vent may be used to assure that station release limits cre not exceeded.
For release from the containment purge ventilation system, a typical radiation monitor setpoint may be calculated as follows:
C. < 5.37E+01/f = 6.55E-04 pCi/ml I
where:
f = 54,000 cfm (auxiliary building ventilation) + 28,000 cfm (containment purge)
= 82,000 cfm For release from the continament air release and addition system, the waste gas decay tanks, the condenser air ejectors, and the auxiliary building ventilation system, a typical radiation monitor setpoint may be calculated as follows:
Cg < 5.37E+01/f = 9.94E-04 pCi/ml where:
f = 54,000 cfm (auxiliary building ventilation) m B-11
O B4,0 DOSE CALCULATIONS V
B4.1 FREQUENCY OF CALCULATIONS Dose contributions to the maximum exposed individual shall be calculated every 31 days, quarterly, semiannually, and annually. (as required by Technical Spec-ifications) using the methodology in the generic information sections. This methodology shall also be dsed for any special reports. Dose projections shall be performed using simplified estimates. Fuel cycle dose calculations shall be performed annually or as required by special reports. Dose contributions may be calculated using the methodology in the appropriate generic information sections.
B4.2 DOSE MODELS FOR MAXIMUM EXPOSED INDIVIDUAL B4.2.1 Liquid Effluents For dose contributions from liquid radioactive releases, one of the two following cases will apply:
1.
If the radionuclides Co-58 and/or Co-60 have been detected and Cs-134 and/or Cs-134 have not been detected (i.e., plants without any fuel failure) dose calculations indicate that the' maximum exposed individual would be a child who consumed fish caught in the discharge canal and who drank water from the nearest " downstream" potable water intake. The dose from these two radionuclides has been cal-culated to be 27% of that individual's total body dose.
v 2.
If the radionuclides Cs-134 and/or Cs-137 have been detected, dose calculations indicate that the maximum exposed individual would be an adult who consumed fish caught in the discharge canal and who drank water from the nearest " downstream" potable water intake. The dose from these two radionuclides has been calculated to be 90% of that individual's total body dose.
B4.2.2 Gaseous Effluents B4.2.2.1 Noble Gases For dose contributions from exposure to beta and gamma radiation from noble gases, it is assumed that the maximum exposed individual is an adult on the site boundary in each meteorological sectors.
B4.2.2.2 Radioiodines, Particulates, and Other Radionuclides T 1/2 ) 8 days For dose contributions from radioiodines, particulates and other radionuclides; it is assumed that the maximum exposed individual is an infant who breathes
' the air and consumes milk from the cearest goat or cow in each meteorological sector.
B-12
B4.3 SIMPLIFIED DOSE ESTIMATE B4.3.1 Liquid Effluents For dose estimates, two simplified calculations using the assumptions presented in Section B4.2.1 and source terms presented in the FSAR are presented. Once operational source term dats is available, this information shall be used to revise these calculations, if necessary.
Case 1 - No Cs-134 or Cs-137 present in effluent, a
D.g = 5.73E+03 I (F )(T ) (CCo-60 + 0.35 CCo-58) g g
A=1 where:
5.73E+03 = 1.14E+05 (U,,/D, + U,g BF ) DFan (3.70) g where:
1.14E+05 = 10s Ci/pci x 10 ml/kg + 8760 hr/yr 3
p U,, = 510 kg/yr, child water consumption D, = 1, dilution factor from the near field area to the nearest potable water intake, Huntersville Water Intake U,g = 6.9 kg/yr, child fish consumption BFg = 5.0E+01, bioaccumulation factor for Cobalt (Table 3.1-1)
DFg = 1.56E-05, child, total body, ingestion dose factor for Co-60 (Table 3.1-4) 3.70 = factor derived from assumption that 27% of dose is from Co-58 and Co-60 or 100% + 27% = 3.70 And where:
F1= F+f where:
f = liquid radwaste flow, in gpm a = recirculation factor at equilibrium, 2.4 F = dilution flow, in gpm And where:
T = The length of time, in hours, over which CCo-58, CCo-60, and Fg g
are averaged.
C
= the average concentration of Co-58 in undiluted effluent, in Co-58 pCi/ml, during the time pariod considered.
B-13 l
C
= the average concentration of Co-60 in undiluted effluent, in pCi/ml, Co-60 during the time period considered.
0.35
= The ratio of the child total body ingestion dose factors for Co-58 and Co-60 or 5.51E-06 + 1.56E Table 3.1-4.
Case 2 - Cs-134 and/or Cs-137 present in effluent.
m DWB = 6.48Etus I (F )(T ) (CCs-134 + 0.59 CCs-137 g
A 1=1 where:
6.48E+05 = 1.14E+05 (U,,/D,+ U,f BF ) DF,1 (1.10) g where:
1.14E+05 = 10s Ci/pci x 10 ml/kg + 5760 hr/yr 3
p U,, = 730 kg/yr, adult water consumption D,= 1, dilution factce from the near field area to the nearest potable water intake, Hunterville Water Intake U,f = 21 kg/yr, adult fish consumption f
i' (,
BFg = 2.00E+03, bioaccumulation factor for Cesium (Table 3.1-1)
DFg = 1.21E-04, adult, total body, ingestion dose factor for Cs-134 (Table 3.1-2) 1.10 = factor derived from the assumption that 90% of uose is from Cs-134 and Cs-137 or 100% + 90% = 1.10 And where:
FA=F+f where:
,i f = liquid radwaste flow, in gpm o = recirculation factor at equilibrium, 2.4 F = dilution flow, in gpm And where:
Tg = The length of time, in hours, over which CCs-134' Cs-137' ""
1 are averaged.
' O Cs-134 = the average concentration of Cs-134 in undiluted effluent, in C
pCi/ml, during the time period considered.
B-14
%f CCs-137 = during the time period considered.the average concentration of Cs-137 in u N
0.59 = The ratio of the adult total body ingestion dose factors for Cs-134 and Cs-137 or 7.14E-05 + 1.21E-04 = 0.59 B4.3.2 Gaseous Effluents Meteorological data is provided in Tables B4.0-1 and B4.0-2.
B4.3.2.1 Noble Gases For dese estimates, simplified dose estimates using the assumptions in B4.2.2.1 and source terms in the FSAR are presented below. Once operational source term data is available, this information shall be used to revise these calculations, if necessary. These calculations further assume that the annual average dispersion parameter is used and that Xenon-133 contributes 45% of the dose.
s D = 7.50E-10 [Q]Xe-133 2.22) p = 2.23E-09 [Q]Xe-133 (2.22)
D where:
X3 3
= 6.7E-05 sec/m, as defined in Section B2.2.2 7.50E-10 =(3.17E-8)(353)(5),derivedfromequationpresentedin j
v Section 3.1.2.1.
2.23E-09 = (3.17E-08) (1050) (X/Q), derived from equation presented in Section 3.1.2.1.
s
[Q]Xe-133 = the total Xenon-133 activity released in pCi 2.22 = factor derived from the assumption that 45% of the dose is contributed by Xe-133.
B4.3.2.2 Radioiodines, Particulates, and Other Radionuclides with T 1/2 ) 8 days For dose estimates, simplified dose estimates using the assumptions in B4.2.2.2 and source terms in the FSAR are presented below. Once operational source term data is available, this information shall be used to revise these calculations, if necessary. These calculations further assume that the annual average dispctsion/ deposition parameter is used and that 95% of the dose is from Iodine-131 concentrated in goat's milk. The simplified dose estimate to the thyroid of an infant is:
s D = 2.00E+04 w (Q)I-131 ( '
}
where:
w = 1.5E-07 = D/Q for food and ground plane pathway, in m2 The location is
(,
the unrestricted area boundary in the E sector (nearest
\\
residence, and vegetable garden).
B-15 4
l (Q)I-131 the total Iodine-131 activity released in pCi.
=
(3.17E-08)(R [@])withtheappropriatesubstitutgonsjor 2.00E+04 =
goat's milk in the grass-cow-milk-pathway factor, Rg [D/Q) for Iodine-131. See Section 3.1.2.2.
1.05 = factor derived from the assumption that 95% of the dose is contributed by I-131.
B4.3 FUEL CYCLE CALCULATIONS These calculations shall be performed using models presented in Section 3.3.
O O
l B-16 m
,-.,.---y,
,.,n,,,_
,.,.p.ww.
g
-,._m
.,s
-.y.m.
,,7.,
3 e
y-.
ny,.p-__-
-.,.-.-i-yy3,,,,9-y
i f
TABLE B4.0-1 (1 of 1)
MCGUIRE KUCLEAR STATION l
DISPERSION PARAMETER (X/Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR I
Distance to the control location, in miles Sector 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 S
4 WSW W
These values have been replaced by the maximum i
WNW values given in the McGuire SER, March 1978, l
NW Table 3 Appendix D.
j NNW j
N NNE i
NE 3
l ENE E
I l
i s
m O
O O
4 TABLE B4.0-2 (1 of 1)
MCGUIRE NUCLEAR STATION DEPOSITION PARAMETER (D/Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR i
e Distance to the contral location, in miles i
Sector 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.3 5.0 S
These values have been replaced by the maximum WNW values given in the McGuire SER, March 1978, NW Table 3 Appendix D.
NNW N
NME NE ENE E
8 1
l l
O B5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING U
The radiological environmental monitoring program shall be conducted in accot-dance with Technical Specification 3/4.12. The monitoring program locations and analyses are given in Tables B5.0-1 through B5.0-3 and Figure B5.0-1 Site specific characteristics make groundwater sampling, special low level I-131 analyses on drinking water, aad food product sampling unnecessary. Groundwater recharge is from Lake Norman and local precipitation the groundwater gradient is toward the effluent discharge area; therefore, contamination of groundwater from liquid effluents is highly improbable. Special low level I-131 analyses in drinking water fill not be performed routinely since the expected I-131 dose from this pathway is less than 1 mrem / year. Food products will not be sampled since lake water irrigation of crops is not practiced in the vicinity. Addi-tionally, two site boundary TLD locations in the NW and NNW sectors do not exist since the required locations are over water.
The laboratory perfor: sing the radiological environmental analyses shall parti-cipata in an interlaboratory comparison program which has been approved by the NRC. This program is the Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck) Program, our participation code is CP.
O a
O B-17
O O
O 4
1 TABE B5.0-1 (1 of 1)
MCGUIRE RADIOLOGICAL MONITOPMG PROGRAM SAMPLING LOCATIONS I
(TLD LOCATIONS)
SAMPLING LOCATION DE5t.RAFTION
- SAMPLING LOCATION DESCRIPTION
- 143 SITE BOUNDARY (0.5 MILES NW) 163 4-5 MILE RADIUS (5.0 MILES SE) 144 SITE BOUNDARY (0.6 HILES NNE) 164 4-5 MIE RADIUS (4.5 MILES SSE) 145 SITE BOUNDARY (0.5 MILES NE) 165 4-5 MILE RADIUS (5.0 MILES S) 146 SITE BOUNDARY (0.5 MILES ENE) 166 4-5 MILE RADIUS (5.2 MILES SSW) 147 SITE BOUNDARY (0.5 MILES E) 167 4-5 MILE RADIUS (4.9 MIES SW) 148 SITE BOUNDARY (0.5 MILES ESE) 168 4-5 MILE RADIUS (4.7 MIES WSW) 149 SITE BOUNDARY (0.7 HILES SE) 169 4-5 MI M RADIUS (4.4 MILES W) 150 SITE BOUNDARY (0.5 MILES SSE) 170 4-5 MILE RADIUS (4.4 HILES WNW) l 151 SITE BOUNDARY (0.5 MILES S) 171 4-5 MILE RADIUS (4.5 MILES NW) 152 SITE BOUNDARY (0.5 MILES SSW) 172 4-5 MILE RADIUS (5.2 MILES NNW) 153 SITE BOUNDARY (0.5 MILES SW) 173 SPECIAL INTEREST (8.5 MIES NNW) 154 SITE BOUNDARY (0.7 MILES WSW) 174 SPECIAL INTEREST (8.7 MILES WNW) 155 SITE BOUNDARY (0.7 HILES W) 175 SPECIAL INTEREST (12.7 MILES WNW) 156 SITE BOUNDARY (0.5 MILES WNW) 176 SPECIAL INTEREST (11.0 MILES SW) 157 4-5 MILE RADIUS (4.8 MILES N) li, SPECIAL INTEREST (8.6 MILES S) 158 4-5 MI E RADIUS (4.4 MILES WNE) 178 SPECIAL INTEREST (9.2 MIES SE) 159 4-5 MILE RADIUS (5.0 MILES NE) 179 SPECIAL INTEREST (10.4 MIES ESE) 160 4-5 MILE RADIUS (4.9 MILES ENE) 180 SPECIAL INTEREST (11.5 MIES NNE) 161 4-5 MILE RADIUS (4.7 MILES E) 181 SPECIAL INTEREST (6.7 MILES NE) 162 4-5 MILE RADIUS (4.6 MILES ESE) 182 SPECIAL INTEREST (6.0 MILES NE) 183 CONTROL (5.5 MILES S)
- All TLD samples are collected quarterly I
p A-
\\wl
'q,.)
TABLE B5.0-2 (1 of 1)
MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (OTHER. SAMPLING LOCATIONS) e 0
U E
CODE:
aa$$
M Y
u W - Weekly Q - Quarterly Yy E
3 I
Y 3
SM - Semimonthly SA - Semiannually 0o N
M - Monthly Ot E
en eu a
w 42 W
0 e
um t
4 8
1 d
8
+a a
u
.c
+
u f
f
_______________ SAMPLING _[gCAT!gN_gESCBIP{IQN_________,________________,___________________ ____ __________*_ _ _ _ _$_ _ _ f _
120 Site Boundary (0.7 miles NNE)
W 121 Site Boundary (0.5 miles NE)
W 125 Site Boundary (0.5 miles SW)
W H
128 Discharge Canal Bridge (0.4 mile ENE)
M 129 Discharge Canal Entrance to Lake Norman (0.6 mile ENE)
SA SA 130 Hwy. 73 Bridge Downstream (0.6 miles SW)
M
- M SA 131 Huntersville Muncipial Water Supply (3.0 miles ENE) 132 Charlotte Municipal Water Supnly (11.2 miles SSE)
M 133 Cornelius (6.2 miles NE)
W 134 East Lincoln Junior High School (8.7 miles WNW)
Control W M
135 Plant Marshall Intake Canal (12.0 miles N)
Control M
136 Mooresville Municipal Water Supply (12.5 miles NNE) Control M
137 Pinnacle Access Area (12.0 miles N)
Control SA SA 138 Hubbard Dairy (1.8 miles ESE) - Cows SM 139 RC Howell Residence (1.8 miles SSE) - Goats SH 140 Kidd Dairy (2.8 miles SSE) - Cows SM 141 Keever Dairy (7.3 miles NW) - Cows Control SM 142 Davidson Municipal Water Supply (7.5 miles NE)
M 184 Duke Power Substation - Lincolaton City Limits - (18 miles WNW) To be deleted 4/1/83 M
158 4-5 Mile Radius (5.0 miles NE) To be added 1/1/83 M
159 4-5 Mile Radius (4.4 miles NNE) To be added 1/1/83 M
O O
O.
TABLE B5.0-3 (1 of 1)
MCGUIRE RADIOLOGICAL MNilTORING PROGRAM ANALYSES ANALYSES SAMPLE MEDIUM ANALYSIS SCHEDULE GAMMA ISOTOPIC TRITIUM LOW LEVEL I-131 GROSS BETA TLD 1.
Air Radioiodine and Particulates Weekly X
2.
Direct Radiation Quarterly X
3.
Surface Water Monthly X
Quarterly Composite X
4.
Drinking Water Monthly-X X
Quarterly Composite X
5.
Shoreline Sediment Semiannually X
6.
Milk semimonthly X
X 7.
Fish Semiannually X
8.
Broadleaf Vegetation Monthly X
N TABLE B5.0-4*
.V (1 of 3)
MCGUIRE NUCLEAR STATION ADULT A,g DOSE PARAMETERS
,NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LII H
3 0.0 8.96E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00
- 8. 'i6E+00 NA 24 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 5.48E+02 CR 51 0.0 0.0 1.49E+00 8.94E-01 3.29E-01 1.98E+00 3.76E+02 MN 54 0.0 4.76E+03 9.08E+02 0.0 1.42E+03 0.0 1.46E+04 MN 56 0.0 1.20E+02 2.12E+01 0.0
- 1. 52E+02 0.0 3.82E+03 FE 55 8.87E+02 6.13E+02 1.43E+02 0.0 0.0 3.42E+02 3.52E+02 FE 59 1.40E+03 3.29E+03 1.26E+03 0.0 0.0 9.19E+02 1.10E+04 C0 58 0.0 1.15E+02 3.39E+02 0.0 0.0 0.0 3.06E+03 CO 60 0.0 4.34E+02 9.58E+02 0.0 0.0 0.0 8.16E+03 NI 63 4.19E+04 2.91E+03 1.41E+03 0.0 0.0 0.0 6.07E+02 NI 65 1.70E+02 2.21E+01 1.01E+01 0.0 0.0 0.0 5.61E+02 to 64 0.0 1.69E+01 7.93E+00 0.0 4.26E+01 0.0 1.44E+03 ZN 65 2.36E+04 7.50E+04 3.39E+04 0.0 5.02E+04 0.0 4.73E+04 ZN 69 5.02E+01 9.60E+01 6.67E+00 0.0 6.24E+01 0.0 1.44E+01 ER 83 0.0 0.0 4.38E+01 0.0 0.0 0.0 6.30E+01 N
BR 84 0.0 0.0 5.67E+01 0.0 0.0 0.0 4.45E-04 m
BR 85 0.0 0.0 2.33E+00 0.0 0.0 0.0 0.0 RB 86 0.0 1.03E+05 4.79E+04 0.0 0.0 0.0 2.03E+04 RB 88 0.0 2.95E+02 1.56E+02 0.0 0.0 0.0 4.07E-09 RB 89 0.0 1.95+02 1.37E+02 0.0 0.0 0.0 1.13E-11 SR 89 4.78E+04 0.0 1.37E+03 0.0 0.0 0.0 7.66E+03 SR 90 5.95E+05 0.0 1.60E+05 0.0 0.0 0.0 3.40E+04 SR 91 8.79E+02 0.0 3.55E+01 0.0 0.0 0.0 4.19E+03 SR 92 3.33E+02 0.0 1.44E+01 0.0 0.0 0.0 6.60E+03 Y 90 1.38E+00 0.0 3.69E-02 0.0 0.0 0.0 1.46E+04 Y 91M 1.30E-02 0.0 5.04E-04 0.0 0.0 0.0 3.82E-02 Y 91 2.02E+01 0.0 5.39E-01 0.0 0.0 0.0
'.11E+04 Y 92 1.21E-01 0.0 3.53E-03 0.0 0.0 0.0 2.12E+03
- Table provided by:
M. E. Wangler, RAB:NRR:NRC on 2/24/83.
TABLE B5.0-4 (1 of 3)
,n.
TABLE B5.0-4 (2 of 3)
MCGUIRE NUCLEA2. STATION ADULT A DOSE PARAMETERS g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LII Y 93 3.83E-01 0.0 1.06E-02 0.0 0.0 0.0 1.22E+04 ZR 95 2.77E+00 8.88E-01 6.01E-01 0.0 1.39E+00 0.0 2.82E+03 ZR 97 1.53E-01 3.09E-02 1.41E-02 0.0 4.67E-02 0.0 9.57E+03 NB 95 4.47E+02 2.49E+02 1.34E+02 0.0 2.46E+02 0.0 1.51E+06 MO 99 0.0 4.62E+02 8.79E+01 0.0 1.05E+03 0.0 1.07E+03 TC 99M 2.94E-02 8.32E-02 1.06E+00 0.0 1.26E+00 4.07E-02 4.92E+01 TC 101 3.03E-02 4.36E-02 4.28E-01 0.0 7.85E-01 2.23E-02 1.31E-13 RU 193 1:98E+01 0.0 8.54E+00 0.0 7.57E+01 0.0 2.31E+03 RU 105 1.65E+00 0.0 6.52E-01 0.0 2.13E+01 0.0 1.01E+03 RU 106 2.95E+02 0.0 3.73E+01 0.0 5.69Et02 0.0 1.91E+0~ '
AG 110M 1.42E+01 1.31E+01 7.80E+00 0.0 2.58E+01 0.0 5.36E+03 TE 125M 2.79E+03 1.01E+03 3.74E+02 8.39E+02 1.13E+04 0.0 1.11E+04 TE 127d 7.05E+03 2.52E+03 8.59E+02 1.80E+03 2.86E+04 0.0 2.36E+04 TE 127 1.14E+02 4.11E+01 2.48E+01 8.48E+01 4.66E+02 0.0 9.03E+03 TE 129M 1.20E+04 4.47E+03 1.89E+03 4.11E+03 5.00E+04 0.0 5.03E+04
_s
( )
TE 129 3.27E+01 1.23E+01 7.96E+00 2.51E+01 1.37E+02 0.0 2.47E+01
_~
TE 131M 1.80E+03 8.81E+02 7.34E+02 1.39E+03 8.92E+03 0.0 8.74E+04 TE 131 2.05E+01 8.57E+00 6.47E+00 1.69E+01 8.98E+01 0.0 2.90E+00 TE 132 2.62E+03 1.70E+03 1.59E+03 1.87E+03 1.63E+04 0.0 8.02E+04 I 130 9.01E+01 2.66E+02 1.05E+02 2.25E+04 4.15E+02 0.0 -
2.29E+02 I 131 4.96E+02 7.09E+02 4.06E+02 2.32E+05 1.22E+03 0.0 1.87E+02 I 132 2.42E+01 6.47E+01 2.26E+01 2.26E+03 1.03E+02 0.0 1.22E+01 I 133 1.69E+02 2.94E+02 8.97E+01 4.32E+04 5.13E+02 0.0 2.64E+02 I' 134 1.26E+01 3.43E+01 1.23E+01 5.94E+02 5.46E+00 0.0 2.99E-02 I 135 5.28E+01 1.38E+02 5.10E+01 9.11E+03 2.22E+02 0.0 1.56E+02 CS 134 3.03E+05 7.21E+05 5.89E+05 0.0 2.33E+05 7.75E+09 1.26E+04 CS 136 3.17E+04 1.25E+05 9.01E+04 0.0 6.97E+04 9.55E+03 1.42E+04 CS 137 3.88E+05 5.31E+05 3.48E+05 0.0 1.80E+05 5.99E+04 1.03E+04 CS 138 2.69E+02 5.31E+02 2.63E+02 0.0 3.90E+02 3.85E+01 2.27E-03 BA 139 9.00E+00 6.41E-03 2.64E-01 0.0 5.99E-03 3.64E-03 1.60E+01 TABLE B5.0-4
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TABLE B5.0-4 (3 of 3)
MCGUIRE NUCLEAR STATION ADULT A DOSE PARAMETERS g
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LII BA 140 1.88E+03 2.37E+00 1.23E+02 0.0 8.05E-01 1.35E+00 3.88E+03 BA 141 4.37E+00 3.30E-03 1.48E-01 0.0 3.07E-03 1.87E-03 2.06E-09 BA 142 1.98E+00 2.03E-03 1.24E-01 0.0 1.72E-03 1.51E-03 2.78E-18 LA 140 3.58E-01 1.80E-01 4.76E-02 0.0 0.0 0.0 1.32E+04 LA 142 1.03E-02 8.33E-03 2.07E-03 0.0 0.0 0.0 6.08E+01 CE 141 8.01E-01 5.42E-01 6.15E-02 0.0 2.5 2E-01 0.0 2.07E+03 CE 143 1.41E-01 1.04E+02 1.16E-02 0.0 4.60E-02 0.0 3.90E+03 CE 144 4.18E+01 1.75E+01 2.24E+00 0.0 1.04E+01 0.0 1.41E+04 PR 143 1.32E+00 5.28E-01 6.52E-02 0.0 3.05E-01 0.0 5.77E+03 PR 144 4.31E-03 1.79E-03 2.19E-04 0.0 1.01E-03 0.0 6.19E-10 ND 147 9.00E-01 1.04E+00 6.22E-02 0.0 6.08E-01 0.0 4.99E+03 W 187 3.04E+02 2.55E+02 8.90E+01 0.0 0.0 0.0 8.34E+04 NP 239 1.28E-01 1.25E-02 6.91E-03 0.0 3.91E 0.0 2.57E+03
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LgRLOTTE WATER WORKS
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' O APPENDIX C.
CATAWBA NUCLEAR STATION SITE SPECIFIC INFORMATION O
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