ML20090B021
| ML20090B021 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/09/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| PROC-840709, NUDOCS 8407120234 | |
| Download: ML20090B021 (99) | |
Text
- - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
0 0FFSITE DOSE CALCULATION MANUAL FOR DUKE POWER NUCLEAR STATIONS l
I PFlil8iro!883%. r
TABLE OF CONTENTS SECTION Page 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 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 Radioiodines 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 Table 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 Table 3.1-9 Inhalation Dose Factors for Infant Table 3.1-10 External Dose Factors for Standing on Contaminated Ground Table 3.1-11 Stable Element Transfer Data Table 3.1-12 R. Values - Ground Pathway - All Ages Table ~3.1-13 Rt Values - Vegetable Pathway - Adult Table 3.1-14 Rt Values - Vegetable Pathway - Teenager
-Table 3.1-15 Rt Values - Vegetable Pathway - Child Table 3.1-16 Rt Values - Meat Pathway - Adult Table 3.1-1/ Rt Values - Meat Pathway - Teenager Table 3.1-18 Rt Values - Meat Pathway - Child Table 3.1-19 Rt Values - Cow Milk Pathway - Adult Table 3.'l-20 Rt Values - Cow Milk Pathway - Teenager Table 3.1-21 Rt Values - Cow Milk Pathway - Child Table 3.1-22 Rt Values - Cow Milk Pathway - Infant Table 3.1-23 Rt Values - Goat Milk Pathway - Adult Table 3.1-24 Rt Values - Goat Milk Pathway - Teenager Table 3.1-25 Rt Values - Goat Mill Pathway - Child Table 3.1-26 R[ Values-GoatMilkPathway-Infant Table 3.1-27 R. 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,1 Values - Inhalation Pathway - Infant li
INTRODUCTION The Offsite Dose Calculation Manual provides the methodology and parameters to te 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 effluents from the site to the unrestricted area will be limited to the 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 abcVe shall also be used to prepare the radioactive liquid and gaseous effluent reports required by the Technical Specifications. To assure compliance with 40CFR190 when twice the design objectives of 10CFR50, Appendix I are exceeded, 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 inplementing procedures.
iii
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 administrative 1y control releases to assure that the release rate calculations limit releases as stated in the Technical Specifications. Administrative controls could i
limit the number of releases occurring at one time and/or apportion the I releaserate between 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 ic limited ;
to the concentcations of 10CFR20, Appendix B, Table II, Column 2, the following release rate calculation shall be performed:
n C
f 5 F + (o I f )
i=1 MPC. f 1
where: i C = The concentration of radionuclide, 'i' , in undiluted liquid ef fluent, f
in pCi/ml.
MPCf = the concentration of radionuclide, 'i', from 10CFR20, Appendix B, Table ,
II, Column 2, in pCi/ml.
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. l u = recirculation factor at equilibrium; this factor accounts 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 GASE0US 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 $500 mrem /yr to the total body and $3000 mrem /yr to the skin for the noble gases and is limited a 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 reicase 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.
b 1-1 L
1.2.1 Noble Gases s
I K g'x [(X/Q)Q ] <500 mrem /yr, and 1
I (L g + 1.1 Mg ) [(X/Q)Q g] <3000 mrem /yr 1
where:
K. = The total body dose factor due to gamma emissions for each identified
- 3 noble gas radionuclide, in mrem /yr per pCi/m from Table 1.2-1.
L.
1
= The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3 from Table 1.2-1.
M. = The air dose factor due to gamma emissions for each identified noble
- 3 gas radionuclide, in mrad /yr per pCi/m from Table 1.2-1 (unit con-version constant of 1.1 mrem / mrad converts air dose to skin dose).
Pg = The dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem /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
= The release rate of radionuclides, 'i', in gaseous effluent from all Q *.
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 Qg =kCf+k2 t g = 4.72E+2 Cg f where:
Cg = the concentration of radionuclide, 'i', in undiluted gaseous effluent, in pCi/ml.
f = the undiluted effluent flow, in cfm.
kt = conversion factor, 2.83E+04 ml/ft3.
c k2 = conversion factor, 6.0E+01 sec/ min.
1.2.2 Radioiodines, Particulates, and Others s
IPg [W Qg ] < 1500 mrem /yr i
where the terms are as defined above.
1-2
TABLE 1.2-1 (1 of 1)
DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS
- Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K. L. M. N.
Radionuclide (ares /yr per pCi/m3) (arem/yr p$r pCi/m3 ) (mrad /yr per pCi/m3) (mrad /yr per pCi/m3 )
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 1.34E+03 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 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 3.06E+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,
TABLE 1.2-2 (1 of 1)
DOSE PARAMETERS FOR RADIOIODINES AND RADI0 ACTIVE PARTICULATE, GASEOUS EFFLUENTS
- P(I), DOSE PARAMETERS FOR RADIOIODINES AND RADIOACTIVE PARTICULATES IN GASEOUS EFFLUENTS Pathways Pathways Inhalation Milk and Ground Inhalation Milk and Ground (mrem /yr per (m2 . mrem /yr per (mrem /yr per (m2 . mrem /yr per Radionuclide pCi/m 3) pCi/sec) Radionuclide pCi/m i) pCi/sec) ,
H3 1.125 E+03 2.4E+03 RU 103 6.625 E+05 1.6E+08 Alpha Act 1.100 E+08 1.8E+10 RU 106 1.432 E+07 2.0E+08 CR 51 1.698 E+04 1.1E+07 AG 110M 5.476 E+06 1.5E+10 MN 54 1.576 E+06 1.1E+09 CD 115M 2.920 E+05 5.2E+07 FE 55 1.110 E+05 1.1E+08 SN 123 3.550 E+06 3.7E+09 FE 59 1.269 E+06 7.2E+08 SN 126 1.120 E+07 1.IE+10 CO 58 1.106 E+06 5.8E+08 SB 124 3.240 E+06 1.4E+09 CO 60 7.067 E406 4.6E+09 SB 125 2.320 E+06 9.1E+08 NI 63 8.214 E+05 3.0E+10 TE 127M 1.408 E+06 1.0E+09 ZN 65 8.399 E+04 1.8E+10 TE 129M 1.761 E+06 1.3E+09 RB 86 1.983 E+05 2.1E+10 CS 134 1.014 E+06 5.6E+10 SR 89 2.157 E+06 1.1E+10 CS 136 1.709 E+05 5.7E+09 SR 90 1.010 E+08 1.0E+11 CS 137 9.065 E+05 5.0E+10 Y 91 2.627 E+06 5.9E+06 BA 140 1.743 E+06 2.6E+08 ZR 95 2.231 E+06 3.5E+08 CE 141 5.439 E+05 3.2E+07 NB 95 4.142 E+05 3.8E+08 CE 144 1.195 E+07 1.6E+08 MO 99 1.354 E+05 3.2E+08 I 131 1.624 E+07 1.0E+12 I 133 3.848 E+06 9.6E+09
- If SR-90 analysis is performed, use P(I) given in I-131 for unidentified components. If SR-90 and I-131 l analyses are performed, use P(I) given in CS-137 for unidentified components. If SR-90, I-131, and CS-137 analyses are performed, use P(I) given in Zn-65 for unidentified components.
Revision 1 4/15/83
2.0 RADIATION MONITORING SETPOINTS i
Effluent radiation monitor alarm / trip setpoints shall be determined using the calculations presented in the following sections. The calculations define the i 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 following equation shall be used to calculate liquid radiation monitor setpoints:
y fg < MPC where:
MPC = the effluent concentration limit implementing 10CFR20 for the site, in pCi/ml.
i 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.
< f = the flow measured at the radiation monitor location in gpm.
1 F = the dilution water flow as measured prior to the release point in gpm.
(Note that if no dilution is provided, C < MPC. Also, note that when (F) is
+
large compared to (f), then F t f ~ F.)
2.2 GAS MONITORS
- . The following equation shall be used to calculate noble gas radiation monitor setpoints based on Xc-133
Kg(X/Q)Qg < S00 Dg = 4.72E+2 C f (See Section 1.2.1) where:
C = the gross activity in undiluted effluent, in pCi/ml.
f = the flow from the tank or building and varies for various release i
sources, in efm.
i l 2-1 i
L
K =
i from Table 1.2-1 for Xe-133, 2.94E+2 mrem /yr per pCi/m3 .
=
X/Q the highest calculated annual average dispersion parameter for any area at or beyond the unrestricted area boundary for long term releases.
2-2
3.0 DOSE CALCULATIONS 3.1 DOSE MODELS FOR MAXINUM EXPOSED INDIVIDUAL 3.1.1 Liquid Effluents of the possible exposure pathways in the aquatic 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 St ={[Aait Atg Cig F]
g 1 f=1 where:
D "I = the cumulative dose commitment to the total body or any organ, t, for an individual of age group, a, from the liquid effluent m
for the total time period I Atg, in mrem.
f=1 l Atg= the length of the fth time period over which C gg and Fg are averaged for all liquid releases, in hours.
Cgg= the average concentration of radionuclide, 'i', in undiluted liquid effluent during time period Atg from any liquid release, in pCi/ml.
Fg = the near field average dilution factor for Cgg during any liquid effluent release where:
I" F
1=F+f where:
o = 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 and varies for sites where water is recirculated. It is specified in the appropriate Appendix. <
f = liquid radwaste flow, in gpm.
F = dilution flow, in gpm.
A aI
= 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-fled principal gamma and beta emitter, mrem /hr per pCi/ml.
A =
ait 1.14E+05 (U,,/Dy + U,g BFg )DF,g7 3-1
where:
1.14E5 = 108 pCi/pCi x 103 ml/kg + 8760 hr/yr.
U,, = Water consumption by age group,1/yr.
infant 330 child 510 teen 510 adult 730 D" = Dilution factor from the near field area to the potable water intake.
U,g = fish consumption by age group, kg/yr.
infant --
child 6.9 teen 16 adult 21 BF.
- = Bioaccumulation factor for radionuclide, 'i', in fish, pCi/kg per pCi/1, from Table 3.1-1.
DF "* .I = Dose conversion factor for radionuclide, 'i', by age group in pre-selected organ, t, in mrem /pCi, from Tables 3.1-2, 3.1-3, 3.1-4, and 3.1-5, respectively.
Using the above information, A .t values for the adult have been calculated for each site. This informati$n is provided in the Table "X" 5.0-4 where "X" 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-8i=1 I Mi [(X/Q) Q1 ]
For beta radiation:
s Dp = 3.17 E-8 I Ng [(X/Q) Qg ]
i=1 where:
3.17E-08 = The inverse of the number of seconds in a year.
Hg = The air case factor due to gamma emissions for each identified nobic gas radionuclide, in mrad /yr per pCi/m 3 from Table 1.2-1.
3-2
N. = The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 from Table 1.2-1.
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, in pCi.
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 D = 3.17 E-8 Ig R N] g 1
where:
3.17E-08 = The inverse of the number of seconds in a year.
s Qg = The release of radioiodines, radioactive materials in particulate form 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.
W = (X/Q) for the inhalation pathway, in sec/m3.
W = (D/Q) for the food and ground plane pathways, in meters 2, R'.
- = The dose factor for each identified radionuclide, 'i', in m2 (mrem /yr) per a
pCi/sec or mrem /yr per pCi/m , for each pathway. (Tables 3.1-12 -+ 3.1-30) where:
Inhalation Pathway Factor, RIg [X/Q) 3 Rf[X/Q)=K'(BR),(DFA),(mrem g /yrperpCi/m) where:
K' 8
= a constant of unit conversion, 10 pCi/pCi.
(BR), = the breathing rate of the receptor of age group (a), in m3 /yr.
The givenbreathing rates Guid in Regulatory (BR)$ 1.109.for the various age groups are tabulated below, as 3-3
Age Greup (a) Breathing Rate (m 3/yr)
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 mrem /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 (DFAg ) for the various age groups are given in Tables 3.1-6, 3.1-7, 3.1-8, and 3.1-9 (taken from Regulatory Guide 1.109 (Rev.1)).
Ground Plane Pathway Factor, R [D/Q)
~
R [D/Q] = K'K"(SF)DFG g [(1-e i )/A ] (m2 .
mrem /yr per pCi/sec) where:
K' = a constant of unit conversion, 106 pCi/pCi.
K" = a constant of unit conversion, 8760 hr/ year.
Ag = the decay constant for the ith radionuclide, sec1 t = the exposure time, 4.73 x 108 sec (15 years).
DFG.
= the ground plane dose conversion factor for the ith radionuclide (mrem /hr per pCi/m2 ),
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-flilk Pathway Factor, R [D/Q]
)~ {ff f )e l'h (1-f"" -A't Rf[D/Q)=K'E f[Q(Ui W
,"E F,(r)(DFL),{
g (8p
+
s
,e s l l (m2 . mrem /yr per pCi/sec) (
where:
K' = a constant of unit conversion, 106 pCi/pC1.
Qp = the cow's consumption rate, in kg/ day (wet weight), (Regulatory Guide 1.109 (Rev. 1)). (?! ilk cow = 50, Beef Cattle = 50, Goats :- 6).
3-4
l U,p = the receptor's milk consumption rate for age (a), in liters /yr.
U ap (liters /yr) - Infant 330
- Child 330
- Teen 400
- Adult 310 (Regulatory Guide 1.109 (Rev. 1))
Y P
= the agricultural 2
productivity by unit area of pasture feed grass, in kg/m , 0.7.
Y 8 = the 2agricultural productivity by unit area of stored feed, in 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 radiof odine and r = 0.2 for particulates (Regulatory Guide 1.109).
(DFLt )" = 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. i l
Ag = the decay constant for the ith radionuclide, in sec' .
A
" = the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 107 sec 7 (corresponding to a 14 day half-life).
t g =thetransgorttimefrompasturetocow,tomilk,toreceptor,insec, 1.73 x 10 (2 days),
t h = the transport time from pasture, to harvest, to cow, to milk, to re-ceptor, in sec, 7.78 x 10 (90 6 days),
f p = fraction of the year that the cow is on pasture (dimensionless), 1.0.
f 8
= fraction of the cow feed that is pasture grass while the cow is on 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 on the airborne concentration rather than the deposition. Therefore, the R is based on [X/Ql:
3 RflX/Q] = K'K'"F,Qp U,p(DFL g ), [0.75(0.5/II)) (mrem /yr per pC1/m )
where:
K'" = a constant of unit conversion, 103 gm/kg.
Il = absolute humidity of the atmosphere, 8 gm/m3 , (Regulatory Guide 1.109) 3-5
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:
QF (U- ff ih -A.t if '
R" [D/Q] = K, g ap) Ff (r)(DFL g ),
Ps (P * + (1-f yf )e e i i w; S a a . . i 2
(m . mrem /yr per pCi/sec) where:
-Fg = the stable element transfer coefficients, in days /kg, Table 3.1.11.
U,p = the receptor's meat consumption rate for age (a), in kg/yr.
U 0 ap (kg/yr) -- Infant Child 41
- Teen 65
- Adult 110 Taken from Regulatory Guide 1.109 (Rev. 1),
tg = the transport time from pasture to receptor, in sec, 1.73 x 105 (2 days),
t h
=thetransporttimefromcropfi$ldtoreceptor,insec,7.78xlo,(99 r days).
The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R is based on [X/Q]:
3 R"[X/Q) = K'K'"F gp Q U,p(DFL g ), [0.75(0.5/H)] (mrem /yr per pCi/m )
where all terms are defined above.
Vegetation Pathway Factor, R [D/Q]
The integrated concentration 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 e time period between harvest and consumption, therefore: '
e -
r R [D/Q] = K' ,y(3[3)() (DFLg ), Ufeg +Ufe g h
. v i w -
u .
(m2 . mrem /yr per pCi/sec) where:
K' = a constant of unit conversion,10 ' 0pCi/pCi.
3-6 Hevision 1 4/15/83
U = the consumption rate of fresh leafy vegetation by the receptor in age group (a), in kg/yr.
U = (kg/hr) - Infant 0
- Child 26 '
- Teen 42
- Adult 64 U ,S = the consumption rate of stored vegetation by the receptor in age group (a), in kg/yr. l
- Child 520 ;
- Teen 630
- Adult 520 f
g = locally, (1.0).the fraction of the annual intake of fresh leafy vegetation grown, f g= the fraction of the annual intake of stored vegetation grown locally, (0.76).
t g = the average time between harvest of leafy vegetation and its consumption, in seconds, 8.6 x 104 (1 day).
th = the average time between harvest of stored vegetation and its consumption, in seconds, 5.18 x 108 (60 days).
Yy = the vegetation area density, 2.0 kg/m2 ,
and all other factors are previously defined.
The concentration of tritium in vegetation is base on the airborne concentra-tion rather than the deposition. Therefore, the R is based on [X/Q]:
r 8
~
Rf[X/Q]=K'K'" Ufg + U f '(DFLg ), [0.75(0.5/H)] (mrem /yr per pCi/m3 ).
6 !
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 <
1 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 individual in the critical population using only data for the critical pathway 3-7 Revision 1 4/15/83
and critical radionuclide(s). Critical populations, critical pathways, and critical radionuclides 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 millirems 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, but excludes mining operations, operations at waste disposal sites, 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 W A SH-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 miles of any Duke Nucicar Station is negligible.
3.3.2 Conversion No uranium hexafluoride production occurs within fif ty miles of any Duke Nuclear Station. The increment of dose from UFs production to any individual -
within fif ty miles of any Duke Nuclear Station is negligible.
3.3.3 Enrichment No uranium enrichment operations occur within fif ty miles of any Duke Nuclear Station. The increment of dose from enrichment operations to any individual within fif ty miles of any Duke Nuclear Station is negligible.
3-8
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 operations occur within fifty miles of any Duke Nuclear Station. The increment of dose from reprocessing operations to any individual within fifty miles of any Duke Nuclear Station is negligible.
To summarize, only dose increments from nuclear power production operations (Section 3.3.5) need be considered in esiculations to demonstrate compliance with the requirements of 40CFR190.
1 d
3-9
TABLE 3.1-1*
(1 of 1)
BI0 ACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA (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 1.0E 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 3.0E 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 l
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)
TABLE 3.1-2*
(1 of 3)
INGESTION DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED)
NUCLIDE B0NE LIVER T.B0DY 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 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 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 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 3 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 CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 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 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-03 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 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
- Table taken from Regulatory Guide 1.109 (Rev. 1)
TABLE 3.1-2 (1 of 3)
TABLE 3.1-2 (2 of 3)
INGESTION DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED)
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 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 PU 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-06 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 8.68E-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 1E 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 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-06 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 c
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)
_ _ . _ _ _ . . . - _ - _ . . _ _ _ _ _ . _ . = . _ _ _ _ _ _ . . _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ .
4
{
t TABLE 3.1-2 (3 of 3) ,
INGESTION DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED) i 3
NUCLIDE BONE LIVER i
T. BODY THYROID KIDNEY LUNG GI-LLI i t
i 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 l PR 144 3.01E-11 1.2SE-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 4.25E-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 l
[
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t (3 of 3) i f
t
, t
TABLE 3.1-3*
(1 of 3)
INGESTION DOSE FACTORS FOR TEENAGER (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T.B0DY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.06E-07 1.06E-07 1.06E-07 NA 24 1.06E-07 1.06E-07 1.06E-07 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 MN 54 7.89E-10 5.14E-09 6.03E-07 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 FW 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 6.2SE-07 NO DATA 1.70E-06 NO DATA 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 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 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 NO 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-08 NO DATA 3.69E-10 NO DATA NO DATA NO DATA 1.13E-04 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 DATA 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) <
TABLE 3.1-3 (1 of 3)
TABLE 3.1-3 (2 of 3)
INGESTION DOSE FACTORS FOR TEENAGER (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T. BODY 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-08 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 la 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 3.92E-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.b7E-06 3.43E-06 1.f';-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 129M 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 TE 131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 NO DATA 2.29E-09 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 DATA 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 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 434 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 i
' 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 1.24E-06 c
I TABLE 3.1-3 l (2 of 3) l
__n_ _ _ ,m-#,.._ha _, a l a _
l TABLE 3.1-3 (3 of 3)
INGESTION DOSE FACTORS FOR TEENAGER (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T. BODY TIIYROID 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 NO 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 1
(
-1 l
I l
l TABLE 3.1-3 (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 5.80E-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-09 9.02E-09 4.72E-07 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 FE 55 1.15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.45E-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 C0 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 t-NI 65 2.22E-06 2.09E-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 i CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 NO DATA 1.15E-05 ,
ZN 65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 i 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 NO DATA 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-07 NO DATA NO DATA NO DATA 9.32E-09 I
RB 89 NO DATA 1.17E-07 1.04E-07 NO DATA NO DATA NO DATA 1.02E-09 ,
SR 89 1.32E-03 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 1
,t
- Taken from Regulatory Guide 1.109 (Rev. 1).
?
1 TABLE 3.1-4 (1 of 3)
I
- + e ,, - - ----- ,,,m--y e- , , -- - ,r - - ~ - - , , - -
TABLE 3.1-4 (2 of 3)
INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED)
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 8.23E-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 1E 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 .N0 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 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 1
TABLE 3.1-4 (2 of 3) t
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 1.24E-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 l
Y L
TABLE 3.1-4 (3 of 3) l I
(
i TABLE 3.1-5*
(1 of 3)
INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T.B0DY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 3.08E-07 3.08E-07 3.08E-07 NA 24 3.08E-07 3.08E-07 3.08E-07 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 I
CR 51 NO DATA NO DATA 1.41E-08 9.20E-09 MN 54 2.01E-09 1.79E-08 4.11E-07 l NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 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 FE 59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 C0 58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 CO 60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 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-08 NO DATA 6.98E-08 NO DATA 1.37E-05 BR 83 NO DATA NO DATA 3.63E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24
, 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 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 NO DATA NO DATA 5.16E-05 SR 90 1.85E-02 NO DATA 4.71E-03 NO DATA NO DATA NO DATA 2.31E-04 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 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
- Taken from Regulatory Guide 1.109 (Rev. 1)
TABLE 3.1-5 (1 of 3)
TABLE 3.1-5 (2 of 3)
INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T. BODY THYROID 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-08 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-03 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 i 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 1.4SE-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 TE 131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 NO DATA 7.11E-06 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-06 6.49E-04 8.07E-06 NO DATA 2.62E-06 CS 134 3.77E-04 's.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 (2 of 3) 1 . .
TABLE 3.1-5 (3 of 3)
INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T.B0DY THYROID KIDNEY LUNG GI-LLI BA 140 1.71E-04 1.71E-07 8.81E NO DATA 4.06E-08 1.05E-07 4.20E-05 BA 141 4.2SE-07 2.91E-10 1.34E-08 NO DATA 1.75E-10 1.77E-10 5.19E-06 L BA 142 1.84E-07 1.53E-10 9.06E-09 NO DATA 8.81E-11 9.26E-11 7.59E-07 l 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 I PR 143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E-05 l PR 144 2.74F-10 1.06E-10 1.38E-11 NO DATA 3.84E-11 NO DATA 4.93E-06 [
ND 147 3.53E-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 [
i i
+
t J
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 1.5SE-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 1.80E-06 4.15E-07 HN 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 1.85E-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 s CS 134 4.66E-05 1.06E-04 9.10E-05 NO DATA 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-f5 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 TABLE 3.1-6 (1 of 1)
TABLE 3.1-7*
(1 of 1)
INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALED)
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 DATA 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 CO 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 LZR 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 ENO 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 CS 137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51E-05 1.06E-06 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 3.1-7 (1 of 1)
TABLE 3.1-8*
(1 of 1)
INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED)
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 C0 58 NO DATA 4.79E-07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05 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 CS 137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 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.
c TABLE 3.1-8 (1 of 1) t
TABLE 3.1-9*
(1 of 1)
INHALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED)
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 3.17E-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 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 2.28E-03 8.65E-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04
- Table taken from NUREG-0597.
L l
TABLE 3.1-9 (1 of 1)
I
TABLE 3.1-10*
(1 of 2)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GRGUND (mrem /hr per pCi/m2 )
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 Mn-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 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) m
TABLE 3.1-10 (cont'd)
(2 of 2)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /hr per pCi/m2 )
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 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 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 l
l l
I ,
l l
TABLE 3.1-10 (2 of 2)
TABLE 3.1-11*
(1 of 1)
STABLE ELEMENT TRANSFER DATA F,(Cow) F f
' 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 Ba 4.0E-04 3.2E-03 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 Eor Goat's milk Element Fm (d/1)
H 0.17 Fe 1.30E-09 Cu 0.013 c Sr 0.014 I 0.06 Cs 0.30 TABLE 3.1-11 (1 of 1)
TABLE 3.1-12 (1 of 1)
RgVALUES - GROUND PATHWAY - ALL AGES 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 C0 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 CE 144 6.92E+07 8.01E+07 TABLE 3.1-12 (1 of 1)
. - _ .- _ . = ._ _
i r
1 TABLE 3.1-13 (1 of 1) I RgVALUES - VEGETABLE PATHWAY - ADULT NUCLIDE BONE LIVER T.B0DY THYROID KIDNEY LUNG GI-LLI !
I H 3 0.0 2.28E+03 2.28E+03 2.28E+03 2.28E+03 2.28E+03 2.28E+03 CR 51 l 0.0 0.0 4.58E+04 2.74E+04 1.01E+04 6.07E+04 1.15E+07 MN 54 0.0 3.07E+08 5.86E+07 0.0 9.14E+07 0.0 9.41E+08 i FE'55 1.99E+08 1.38E+08 3.21E+07 0.0 FE 59 0.0 7.68E+07 7.90E+07 !
1.23E+08 2.90E+06 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 l ZN 65 4.00E+08 1.27E+09 5.76E+08 0.0 8.52E+08 0.0 8.02E+08 !
r 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 ZR 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 ,
CS 134 4.54E+09 1.08E+10 8.83E+09 0.0 3.49E+09 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 .
i 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 5
L i
l h-TABLE 3.1-13 (1 of 1) 4 i
+
e , ,, ,- , - - - - . . . -. , , _ , _ . - - - . - - . - - _ _ - - - . , _ - - . . - - - , _ _ _ , . - - - - , - - - _ - , - , - - , - - - - . - . - , .
TABLE 3.1-14 (1 of 1)
RgVALUES - VEGETABLE PATHWAY - TEENAGER NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 2.61E+03 2.61E+03 2.61E+03 2.61E+03 2.61E+03 2.61E+03 CR 51 0.0 0.0 6.08E+04 3.38E+04 1.33E+04 8.68E+04 1.02E+07 MN 54 0.0 4.46E+08 8.85E+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 C0 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 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 CS 136' 4.33E+07 1.71E+08 1.15E+08 0.0 9.28E+07 1.46E+07 1.37E+07 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 C
TABLE 3.1-14 (1 of 1)
TABLE 3.1-15 (1 of 1)
RgVALUES - VEGETABLE PATHWAY - CHILD 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 SR 89 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 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 TABLE 3.1-15 (1 of 1)
TABLE 3.1-16 (1 of 1)
RgVALUES - MEAT PATHWAY - ADULT NUCLIDE BONE LIVER 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 CR 51 0.0 0.0 5.86E+03 3.50E+03 1.29E+03 7.77E+03 1.47E+05 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+08 1.91E+08 0.0 0.0 1.39E+08 1.66E+09 CO 58 0.0 1.41E+07 3.17E+07 0.0 0.0 0.0 2.87E+08 CO 60 0.0 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 3.75E+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 CS 134 4.83E+08 1.15E+09 9.39E+08 0.0 3.72E+08 1.23E+08 2.01E+07
.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 TABLE 3.1-16 (1 of 1)
TABLE 3.1-17 (1 of 1)
RgVALUES - MEAT PATHWAY - TEENAGER NUCLIDE BONE LIVER T. BODY TIIYROID KIDNEY LUNG GI-LLI II 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 38 0.0 1.09E+07 2.51E+07 0.0 0.0 0.0 1.50E+08 LO 60 0.0 4.31E+07 9.72E+07 0.0 0.0 0.0 5.62E+08 ZN 65 2.11E+08 7.34Et08 3.43E+08 0.0 4.70E+08 0.0 3.11E+08 SR 89 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+06 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 4.09E+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 9.04Et08 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 2.53E+08 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 (1 of 1)
t i
TABLE 3.1-18 I (1 of 1)
RgVALUES - MEAT PATHWAY - CHILD :
t NUCLIDE BONE LIVER T. BODY THYROID '
KIDNEY LUNG GI-LLI H 3 0.0 2.36E+02 2.36E+02 2.36E+02 !
CR 51 2.36E+02 2.36E+02 2.36E+02 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 FE 55 1.67E+06 0.0 5.00E+06 !
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 L CO 60 0.0 5.12E+07 1.51E+08 0.0 0.0 0.0 2.84E+08 e 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 .
4 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 CS 136 3.44E+08 1.24E+08 5.99E+06 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 :
4 BA 140 3.91E+07 3.42E+04 2.28E+06 0.0 1.11E+04 2.04E+04 1.98E+07 l 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
TABLE 3.1-18 (1 of 1) >
r
.- . _ . . - _ _ _ _ - . - . . _ . . . , _ . , .,,,,,_m____.__ ,,m. , _ . ...m.-, . - , ym.m,,y,, _ , - - - , , , , , . - , . . _ , - . _
TABLE 3.1-19 (1 of 1)
RgVALUES - COW MILK PATIIWAY - ADULT NUCLIDE BONE LIVER T. BODY TilYROID 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 1.86E+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 CO 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 1.72E+04 4.93E+07 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)
d k
i TABLE 3.1-20 '
(1 of 1)
RfVALUES - COW MILK PATHWAY - TEENAGER NUCLIDE B0NE 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 2.14EF07 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 l
, C0 58 0.0 6.15E+06 1.42E+07 0.0 0.0 0.0 8.48E+07 ,
CO 60 0.0 2.06E+07 4.63E+07 0.0 0.0 0.0 2.68E+08 r ZN 65 1.78E+09 6.18E+09 2.88E+09 0.0 3.96E+09 '
0.0 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 r
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 i
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 1 CS 137 1.01E+10 1.34E+10 4.68E+09 0.0 4.57E+09 1.78E+09 1.91E+08 BA 140 4.32E+07 5.30E+04 2.78E+06 0.0 1.80E+04 3.56E+04 6.67E+07 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 i
t 1 l t
' i TABLE 3.1-20
! (1 of 1) ;
t
?
TABLE 3.1-21 (1 of 1)
R; VALUES - COW MILK PAT 11WAY - CHILD 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 S1 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 4.51E+07 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 RZR 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+06 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 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+06 2.25E+06 3.83E+05 0.0 1.24E+06 0.0 5.86E+08 i-i TABLE 3.1-21 (1 of 1)
TABLE 3.1-22 (1 of 1)
RgVALUES - COW MILK PATHWAY - INFANT NUCLIDE BONE LIVER T.B0DY 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 3.20E+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+07 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 5.32E+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 TABLE 3.1-22 (1 of 1)
TABLE 3.1-23 (1 of 1)
RfVALUES - GOAT MILK PATHWAY - ADULT NUCLIDE BONE LIVER T.B0DY 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 C0 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 4.43E+08 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 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 CS 134 1.25E+10 2.96E+10 2.42E+10 0.0 9.59E+09 3.18E+09 5.19E+08 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 TABLE 3.1-23 (1 of 1)
J i
I TABLE 3.1-24 '
(1 of 1) '
RgVALUES - GOAT MILK PATHWAY - TEENAGER l
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.0 204E+03 2.04E+03 i
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 FE 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 4.88E+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 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 4
(
4 TABLE 3.1-24 (1 of 1) l..
TABLE 3.1-25 (1 of 1) .
RgVALUES - GOAf MILK PATHWAY - CHILD NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 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 NN 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
.C0 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 o0. 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 T.04E+01 0.0 1.13E+02 0.0 8.25E+04 SB 124- 1.02E+07 1.32E+05 3.58E+06 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 I. 133 9.59E+06 1.19E+07 '4.49E+06 2.20E+09 1.98E+07- 0.0 4.78E+06 CS1134- 4.99E+10 8.18E+10 1.73E+10 0.0 2.54E+10 9.10E+09 4.41E+08 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 10 . 0 2.28E+10 8.19E+09 4.37E+0S 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 TABLE 3.1-25 (1 of 1)
( TABLE 3.1-26 (1 of 1)
RfVALUES - GOAT MILK PATHWAY - INFANT 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 CO 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 2.4SE+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 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 4.26E+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 TABLE 3.1-26 (I of 1) c
TABLE 3.1-27 (1 of 1)
RgVALUES - INHALATION PATHWAY - ADULT NUCLIDE BONE LIVER T. BODY 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 5.41E+04 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 6.63E+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 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+05 0.0 8.47E+05 7.76E+06 8.15E+05 TABLE 3.1-27 (1 of 1)
TABLE 3.1-28 (1 of 1)
RgVALUES - INHALATION PATHWAY - TEENAGER NUCLIDE BONE LIVER T.B0DY 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+03 FE 59 1.59E+04 3.69E+04 1.43E+04 0.0 0.0 1.53E+06 1.78E+05 C0 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 4.34E+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 6.48Et03 I 133 1.21E+04 2.05E+04 6.21E+03 2.92E+06 3.59E+04 0.0 1.03F+04 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 c
TABLE 3.1-28 (1 of 1)
r i
TABLE 3.1-29 (1 of 1) !
RgVALUES - INHALATION PATHWAY - CHILD f
- NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI ,
i t H 3 0.0 1.12E+03 1.12E+03 1.12E+03 CR 51 1.12Et03 1.12E+03 1.12E+03 !
0.0 0.0 1.54E+02 8.53E+01 2.43E+01 1.70E+04 1.08E+03 l 0.0 MN 54 4.29E+04 9.50E+03 0.0 1.00E+04 1.57E+06 2.29E+04 l 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 7.0cE+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+0L 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 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-CS 137 9.C5E+05 8.24E+05 1.28E+05 0.0 2.82E+05 1.04E+05 3.61E+03 i 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 L
i f
4 e
r TABLE 3.1-29 (1 of 1)
I
, , ,, , - , - , , - , , . . , , . - - . . - , . . , . _ . . - - , , , ~ . ...,.,,.,,-._-,,,,.,.-,.,,.-.,n-,,n-- .,n.n _.,,.n, , , - . . , , , - , - .
TABLE 3.1-30 (1 of 1)
RfVALUES - INHALATION PATHWAY - INFANT NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG 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 0.0 8.93E+01 5.75E+01 1.32E+01 1.28E+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 0.0 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 6.39E+04 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 I 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 5.48E+05 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 CE 144 3.19E+06 1.21E+06 1.76E+05 0.0 5.37E+05 9.83E+06 1.48E+05 C
TABLE 3.1-30 (1 of 1)
APPEhTIX C CATAWBA NUCLEAR STATION SITE SPECIFIC INFORMATION t
f APPENDIX C - TABLE OF CONTENTS Page C1.0 CATAWBA NUCLEAR STATION RADWASTE SYSTEMS . . . . . . . . C-1 C2.0 RELEASE RATE CALCULATIOP . . . . . . . . . . . . . . . . C-4 C3.0 RADIATION MONITOR SETPOINTS . . . . . . . . . . . . . . C-8 C4.0 DOSE CALCULATIONS . . . . . . . . . . . . . . . . . . . C-11 C5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING . . . . . . . . . C-17 l
I
C1.0 CATAWBA NUCLEAR STATION RADWASTE SYSTEMS C1.1 LIQUID RADRASTE PROCESSING The liquid radwaste system at Catawba Nuclear Station (CNS) is used to collect and treat fluid chemical and radiochemical by products of unit operation. The system produces efflucents 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 - All 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) is used primarily in treating waste in the Laundry and Hot Shower Tank (LHST) Subsystem of the WL System. FDT waste may also be treated by this method.
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, manganese) and anions (chloride, fluoride) from evaporator distillates in order to purify the distillates for reuse as makeup water. Distillate from the 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 letdown.
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 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 war.te 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 concentrated to 4% so that it may be reused for makeup to the reactor coolant system.
Figure C1.0-1 is a schematic representation of the liquid radwaste system at Catawba.
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Table C1.0-1 ABBREVIATIONS Systems:
i CM - Condensate System KC - Component Cooling NB - Boron Recycle RL - Low Pressure Service Water
- RN - Nuclear Service Water System WC - Conventional Waste Water Treatment WL - Liquid Waste Recycle ,
WP - Turbine Building Sump WS - Nuclear Solid Waste Disposal r Tanks: r BA - Boric Acid Tank FDT - Floor Drain Tank LHST.- Laundry and Hot Shower Tank i MST - Mixing and Settling Tank NCDT - Reactor Coolant Drain Tank I RHT - Recycle Holdup Tank RMT - Recycle Monitor Tank RMWST - Reactor Makeup Water Storage Tank -
SGDT - Steam Generator Drain Tank VUCDT - Ventilation Unit Condensate Drain Tank WDT - Waste Drain Tank WEFT - Waste Evaporator Feed Tank WMT - Waste Monitor Tank TABLE C1.0-1
C1.2 GASE0US RADWASTE SYSTEMS The gaseous waste disposal system for Catawba is designed with the capability of processing the fission product gases from contaminated reactor coolant fluids resulting from operation. The system shown schematically in Fig. C1.0-2 is designed to allow for the retention, through the plant lifetime, of all the gaseous fission products to be discharged from the reactor coolant system to the chemical and volume control system or the boron recycle system, to limit the need for intentional discharge of radioactive gases from the waste gas holdup tanks. Thus, the only unavoidable sources of low-level radioactive 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 uncollectable reactor 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.
C1.2.1 Gas Collection System The gas collection system combines the waste hydrogen and fission gases from the volume control tanks and that from the boron recycle gas stripper evaporator produced during normal operation with the gas collected during the shutdown degasification (high percentage of nitrogen) and will cycle it through the catalytic recombiners to convert all the hydrogen to water. After the water vapor is removed, the resulting gas stream will be transferred from the recom-biner into the gas decay tanks, where the accumulated activity may be contained in six approximately equal parts. From the decay tanks the gas will flow back to the compressor suction to complete the loop circuit.
C1.2.2 Containment and Auxiliary Building Ventilation Nonrecyclable reactor coolant leakage occurring either inside the containment or inside the auxiliary building will generate gaseous activity. Gases result-ing from leakage inside the containment will be contained until the containment air is released through the VQ or VP system. The containment atmosphere will be discharged through a charcoal adsorber and a particulate filter prior to release to the atmosphere.
Gases resulting from leakage inside the auxiliary building are released, with-out further decay, to the atmosphere via the auxiliary building ventilation system. The ventilation exhaust from potentially contaminated areas in the <
auxiliary building is normally unfiltered. However, on a radiation monitor alarm, the exhaust is passed through charcoal adsorbers to reduce releases to the atmosphere.
C1.2.3 Secondary Systems Normally, condensate flow and steam generator blowdown will go parallel through 4 of the 5 condensate polishing demineralizers to remove activity and harmful ions from the water. Noncondensable gases will be taken from the C-2
secondary system by the condenser steam air ejector and are passed through a radiation monitor to the unit vent.
Figure C1.0-2 is a schematic representation of the gaseous radwaste system at Catawba.
C C-3
j( ROOF VENTS 600,200 cfD OUTSIDE AIR
,. 3
~~
r- -
-- .. ABOVE
- .T g CUT DE g
GROUND PRIMARY g
4 1
, .. ~
l i UNIT I
{ COND EN SE R ST E A M T f 60 cfm E M F-35 GENERATOR '"
L-_ CONDENSER E M F-36 4
_ _TURBINE
_ _ _ BLDG.
_ _ _Y_ _ J STE AM JET AIR E M F-3 7
( EMF-34 + TO "D" F EE DWATE R
"* HEATERS BLOWDOWN E MF-33 l RECYCLE TANK' LETDOWN FLOW SECONDARY SYSTEM (2 UNITS)
F ROM RE ACTOR COOLANT SYSTEM _
m - (2) HYDROGEN M 3 RECOMBINERS WASTE G AS g g g g 4 I
[b COM PR ESSO RS VOLUME CONTROL TANK
// \\
/Q%
2 [b g &
/# g\
/Q5 H 2 (2 UNITS)
SHUTDOWN
[I3l+ g I
OX YG EN WATE Rl TO VOLUME l
UNIT 1 W W STO RAG E CONTROL l TANKS l TANK I VOLUME CONTROL TANK E 1J I
+___ ________ _____J REACTOR REACTOR
- BORON RECYCLE GAS GAS TANKS SHIMBLEED STOR AGE 600 FT.3 EVAPORATOR TANKS 100 psig v v v v v v G AS STRIPPE R * * * * * * &
WASTE G AS SYSTEM l EMF-50 l CONTAINMENT 200efm '
m m NORM ALLY CLOSED CONTAINMENT g g P A C M CONTAINMENT AIR & "
UPPER VOLUME 18,000 cfm ADDITION SYSTEM (VO) p LOWER VOLUME jg( A C U PURGE INLET $ PURGE OUTLET (VP)
C A P g pg 10,000 EMF 39 cfm E M F-40 CONTAINMENT VENTILATION SYSTEMS (2)
INTERNATL. RECIRCU TR AINS (2) 8,000 cfm E ACH l EMF-42 l e 35.700 erm ha m "I
p =
FUE L H ANDLING ] PER UNIT AREA l EMF-41 l CO AM NAT CN 5 O efm h O U TSID E AREA " dPlAlC D
OTHER ARE AS M AU X ILI A R Y PER UNIT BUILDING SUPPLY FANS AUXILI ARY BUILDING SYSTEM (SH AREDI , p A HIG H-E F F ICI E NC Y PARTICULATE FILTER C CH ARCOAL ABSORBER FUEL HANDLING AREA IS NORMALLY UNFILTERED. UPON A RADIATION ALARM BY EMF 42, THE EXHAUSTWILL BE DIVERTED TO THE FILTERED MODE.
POTENTIALLY CONTAIMINATED AREAS OF THE AUXILIARY BUILDING ARE NORMALLY UNFILTERED RADIATION ALARM BY EMF 41, THE EXH AUST WILL BE DIVERTED TO THE FILTERED MODE.
FIGURE C1.0-2 CATAWBA NUCLEAR STATION G ASEOUS R ADWASTE SYSTEM
C2.0 RELEASE RATE CALCULATION Generic release rate calculations are presented in Section 1.0; these calcula-tions will be used to calculate release rates for Catawba Nuclear Station.
Catawba Nuclear Station will operate as a single unit until the second unit is completed and licensed. As a single unit, releases shall be administratively controlled to assure that release rate calculations limit releases as stated in the Technical Specifications.
C2.1 LIQUID RELEASE RATE CALCULATIONS There are two potential release points at Catawba. They are as follows:
- 1. Liquid Waste Effluent Discharge Line
- 2. Conventional Waste Water Treatment System Effluent Line C2.1.1 Liquid Waste Effluent Discharge Line There are three low pressure service water pumps with a minimum flow rate of 16,500 gpm each and four nuclear service water pumps with a minimum flow rate of 9,000 gpm each which provide the required dilution water needed for a release. The LPSW system flow rate monitor has a variable setpoint which term-inates the release by closing the isolation valve, 1 WL124 should the dilution flow fall below the setpoint. The following equation shall be used to calculate a discharge flow, in gpm.
C f<Fpg + o I i i=1 MPC.
1 whe re,:
f = the undiluted effluent flow, in gpm.
F RL = actual low pressure senice water flowrate, in gpm, from the sum of the flowrate monitors located in the Control Room.
o = the recirculation factor at equilibrim (dimensionless),1.027.
0 cfs = 1.027 o=1+9R -
9
= 1 + 4400 cfs H
where:
Q = aver ge dilution flow (120 cfs) '
R QH aver 8e fl W Past Wylie Dam (4400 cfs)
C f = the concentration of radionuclide, i, in undiluted effluent as determined 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 MPC g
= 2.0E-04 pCi/ml.
C-4
i C2.1.2 Conventional Waste Water Treatment System Effluent Line i
The conventional 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 analyses of the composite sample collected on that line. The water sources listed below that are normally discharged via the conventional waste water treatment system and/or the Turbine Building Sump will be diverted if they become radioactive.
- a. Containment Ventilation Unit Condensate Effluent Line Normally the containment ventilation unit condensate effluent line would discharge into the Turbine Building sump, but if radiation is detected l above background, the discharge will be terminated and an alarm actuated. '
The containment ventilation unit condensate tank will then be i
recirculated, sampled and then discharged through the liquid waste l effluent line and monitored or processed thru the WL system.
l
- b. Auxiliary Feedwater Sump Pumps and Floor Drain Sump Pump Line
. f Normally the discharge line coming from these sumps will discharge into the Turbine Building sump, but if radiation is detected above background, the discharge flow will automatically be routed to the floor drain tank for processing and later be discharged through the liquid waste effluent i
line.
- c. Turbine Building Sump Discharge Line f Normally the discharge from the Turbine Building sump will go into the l conventional waste water treatment system, but if radiation is detected above background, the sump pumps A, B, and C will stop and an alarm >
actuated. The Turbine Building sump discharge line can either be routed '
to the floor drain tank for processing or routed directly to the liquid waste effluent discharge line.
- d. Steam Generator Blowdown Line Normally the discharge from the Steam Generator Blowdown will be pumped to the Turbine Building Sump, but if radiation is detected above background, each blowdown flow control valve, the atmospheric vent, and the valve to the Turbine Building Sump will close, thus terminating the discharge.
Blowdown can only be continued by venting the steam to "D" heater and pumping the liquid to the condensate system. '
C2.2 GASEOUS RELEASE RATE CALCULATIONS The unit vent is the release point for waste gas decay tanks, containment air releases, the condenser air ejector, and auxiliary building ventilation. The condenser air ejector 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 neasurements and/or by analyses of periodic samples C-5
collected on that line. Radiation monitoring alarm / trip setpoints in con-junction with administrative controls assure that release limits are not exceeded; see section C.3.0 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 C2.2.1 and C2.2.2 shall control the release rate for a single release point.
C2.2.1 Noble Gases IK g [(UQ)D] g
< 500 mrem /yr, and i
I (Lg + 1.1 Mg ) [(XTQ)Qg ] < 3000 mrem /yr i
where the terms are defined below.
C2.2.2 Radioiodines, Particulates, and Other Radionuclides With T 1/2 > 8 Days s
IPg [W Qg ] < 1500 mrem /yr i
where:
Kg = The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3 from Table 1.2-1.
L I
= The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3from Table 1.2-1.
Hg = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m 3from Table 1.2-1 (unit conver-sion constant of 1.1 mrem / mrad converts air dose to skin dose).
P g = 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 plane pathways in m2 .(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).
Dg = The release rate of radionuclides, i, in gaseous effluent from all release points at the site, in pCi/sec, c (X/Q) = 3.10E-05 sec/m 3 . The highest calculated annual average relative concen-tration for any area at or beyond the unrestricted area boundary. The location is the NNE sector @ 0.5 miles.
W = The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location:
W = 3.1E-05 sec/m3 , for the inhalation pathway. The location is the unrestricted area in the NNE sector 0 0.5 miles.
C-6
W = 1.1E-07 meter 2, for the food and ground plane pathways. The location is the unrestricted area boundary in the NE/NNE sector
@ 0.5 miles (nearest residence, and vegetable garden).
Q g=kCf+k2 ig = 4.72E+2Cg f where:
C f = the concentration of radionuclide, i, in undiluted gaseous effluent, in pCi/ml.
f = the undiluted effluent flow, in efm kg = conversion factor, 2.83E4 ml/ft3 k2 = conversion factor, 6El sec/ min d
C-7
C3.0 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 Catawba are off-line except EPIF-50 (Waste Gas System) which is in-line. These monitors alarm on low flow; the minimum flow alarm level for both the liquid monitors and the gas monitors is based on the manufacturer's recommendations. These monitors measure the activity in the liquid or gas volume exposed to the detector and are independent of flow rate if a 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 is estab-lished by a str. tion procedure using the following relationship:
c = 2.22 x 10 6e V where:
c = the gross activity, in pCi/ml r = the count rate, in cpm 2.22 x 106= the disintegration per minute per pCi e = the counting efficiency, cpm /dpm V = the volume of fluid exposed to the detector, in ml.
For those occurrences when simultaneous releases of radioactive material must be made, monitor setpoints will be adjusted downward in accordance with Station Procedures to insure that instantaneous concentrations will not be exceeded.
C3.1 LIQUID RADIATION MONITORS C3.1.1 Waste Liquid Effluent Line As described in Section C2.1.1 on release rate calculations for the waste liquid effluent, 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 analyses and used to calculate the release rate. A typical radiation monitor setpoint may be calculated as follows:
MPC x F c5 9 $ 2.48E-05 pCi/ml ~
where:
c = the gross activity in undiluted effluent, in pC1/ml f = the flow from the tank may vary from 0-100 gpm but, for this calculation, is assumed to be 100 gpm.
C-8
MPC = 1.0E-07 pCi/ml, the MPC for an unidentified mixture o = 1.027 (See Section C2.1.1)
F = the dilution flow may vary as described in section C2.1.1, but is conservatively estimated at 25,500 gpm, the minimum flow available.
C3.1.2 Containment Ventilation Unit Condensate Effluent Line - EMF 44 As described in Section C2.1.2 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.
Since the tank contents are discharged automatically, the radiation monitor setpoint will be set at 1.0E-06 pCi/ml (the monitor's lowest level of detection) plus background to assure that release limits are not exceeded.
C3.1.3 Auxiliary Feedwater Sump Pumps and Floor Drain Sump Pump - EMF 52 As described in Section C2.1.2 on release rate calculations for the auxiliary feedwater sump pumps and floor drain sump pump effluents, 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. Since the sumps are discharged automatically, the radiation monitor setpoint will be set at 1.0E-06 pCi/ml (the monitor's lowest level of detection) plus background to assure that release limits are not exceeded.
C3.1.4 Turbine Building Sump Discharge Line - EMF 31 As described in Section C2.1.2 on release rate calculations for the turbine building sumps, 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. Since the sump contents are discharged automatically, the radiation monitor setpoint will be set at 1.0E-06 pCi/ml (the monitor's lowest level of detection) plus background to assure that release limits are not exceeded.
C3.1.5 Steam Generator Blowdown Line - EMF 34 As described in Section C2.1.2 on Release Rate Calculations for the Steam Generator Blowdown, 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. Since the Steam Generator Blowdown line is discharged automatically, the radiati'on monitor setpoint will be set at 1.0E-06 pCi/ml (the monitor's lowest level of detection) plus background to assure that release limits are not exceeded.
C-9
C3.2 GAS MONITORS The following equation shall be used to calculate noble gas radiation monitor setpoints based on Xe-133 (Historical data shows that Xe-133 is most predominant isotope):
K(X/Q)Qg < 500 (see Section C2.2.1)
Dg = 4.72E+02 Cg f (see Section C2.2.2)
Cg < 1.16/f where:
C = the gross activity in undiluted effluent, in pCi/ml f
f = the flow from the tank or building sources, in efm K = from Table 1.2-1 for Xe-133, 2.94E+2 mrem /yr per pCi/m 3 X/Q = 3.1E-05, as defined in Section C.2.2.2 As stated in Section C2.2, 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.
For releases from the containment purge ventilation system, a typical radiation monitor setpoint may be calculated as follows:
Cf < 1.16/f = 6.5E-06 where:
f = 151,000 cfm (auxiliary building ventilation) + 28,000 cfm (containment purge) = 179,000 cfm For release from the containment air release and addition system, the waste gas decay tanks, the condenser air ejectors, and the auxiliary building ventilation, a typical radiation monitor setpoint may be calculated as follows:
Cg < 1.16/f = 7.7E-06 where:
f = 151,000 cfm (auxiliary building ventilation) -
c C-10
C4.0 DOSE CALCULATIONS C4.1 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 used for any special reports. Dose projections shall be performed using siniplified 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.
C4.2 DOSE MODELS FOR MAXIMUM EXPOSED INDIVIDUAL C4.2.1 Liquid Effluents For dose cor.oributions 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-137 have not been detected (i.e., plants without any fuel failure) dose calculations will be based upon 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 13% of that individual's total body dose.
- 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.
C4.2.2 Gaseous Effluents C4.2.2.1 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.
C4.2.2.2 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 nearest goat or cow in each meteorological sector.
C-11
C4.3 SIMPLIFIED DOSE ESTIMATE C4.3.1 Liquid Effluents For dose estimates, two simplified calculations using the assumptions presented i.n Section C4.2.1 and source terms presented in the FSAR are presented. Once operational source term data is available, this information shall be used to reiise these calculations, if necessary.
Case 1 - No Cs-134 or Cs-137 present in effluent.
m D
WB = 1.57E+03 I (Fg)(T )g (CCo-60 + 0.35 CCo-58) f=1 where:
1.57E+03 = 1.14E+05 (Uaw/Dw +U af BF.) 1 DFat.t (7.69) where:
0 1.14E+05 = 10 pci/pCi x 103 ml/kg + 8760 hr/yr U, = 730 kg/yr, adult water consumption D = 37.7, dilution factor from the near field area to the nearest potable water intake.
where:
Dy = o (See Section C2.1.1)
QR 9H U,g = 21 kg/yr, adult fish consumption BF7 = 5.0E+01, bioaccumulation factor for Cobalt (Table 3.1-1)
DF,g7 = 1.67E-06, adult, total body, ingestion dose factor for Co-60 (Table 3.1-2) 7.69 = factor derived from assumption that 13% of dose is from Co-58 and Co-60 or 100% + 13% = 7.69 And where:
F2 =
F+f where:
f = liquid radwaste flow, in gpm a = recirculation factor at equilibrium, 1.027 (see Section C2.1.1)
F = dilution flow, in gpm C-12
And where:
Tg = The length of time, in hours, over which CCo-38' Co-60, nd Fg are averaged.
C = the average concentration of Co-58 in undiluted effluent, in Co-58 Ci/ml, during the time period considered.
C Co-60 = the average concentration of Co-60 in undiluted effluent, in pCi/ml, during the time period considered.
0.35 = The ratio of the adult total body ingestion dose factors for Co-58 and Co-60 or 1.67E-06 4.72E Table 3.1-2.
Case 2 - Cs-134 and/or Cs-137 present in effluent.
m Dg
= 6.38E+05 I (Fg)(T )g (CCs-134 + 0.59 CCs-137) f=1 where:
+U BF.) DF al.T (1.10) 6.38E+05 = 1.14E+05 (Uaw/D w af 1 where:
1.14E+05 = 10 8 pCi/pCi x 103 ml/kg + 8760 hr/yr U,y = 730 kg/yr, adult water consumption D = 37.7, dilution factor from the near field area to the nearest potable water intake.
where:
Dy = a (see Section C2.1.1)
OR H U,g = 21 kg/yr, adult fish consumption BF g = 2.00E+03, bioaccumulation factor for Cesium (Table 3.1-1)
- t^21E-04, adult, total body, ingestion dose factor for Cs-134 (Table 3.1-2) ait 1.10 = factor derived from the assumption that 90% of dose is from Cs-134 and Cs-137 or 100% + 90% = 1.10 And where:
F2=F+f C-13
l r
i where:
?
f = liquid radwaste flow, in gpm t a = recirculation factor at equilibrium, 1.027 (see Section C2.1.1) ,
l F = dilution flow, in gpm And where: ;
Tg = The length of time, in hours, over which CCs-134, CCs-137, and Fg j are averaged, i j CCs-134 = the average concentration of Cs-134 in undiluted effluent, in ,
pCi/ml, during the time period considered. 3 h
j C
Cs-137 = the average concentration of Cs-137 in undiluted effluent, in pCi/ml, L during the time period considered.
i i 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 C4.3.2 Gaseous Effluents ,
Meteorological data is provided in Tables C4.0-1 and C4.0-2.
.C4.3.2.1 Noble Gases $
For dose estimates, simplified dose estimates using the assumptions in C4.2.2.1 I 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, I if necessary. These calculations further assume that the annual average dispersion parameter is used and that Xenon-133 contributes 45% of the dose, j D
=3.47E-10[D]Xe-133(2.22)
'D p=1.03E-09[D]Xe-133(*
where:
3.47E-10 = (3.17E-8)(353) (X/Q), derived from equation presented in Section 3.1.2.1.
1.03E-09 = (3.17E-08) (1050) (X/Q), derived from equation presented in c Section 3.1.2.1.
X/Q = 3.1E-05 sec/m3 , as defined in Section C2.2.2
[Dj 133 = the total Xenon-133 activity released in pCi Xe 2.22 = factor derived from the conservative assumption (based on historical data) that 45% of the dose is contributed by Xe-133.
C4.3.2.2 Radioiodines, Particulates, and Other Radionuclides with
.. T 1/2 > 8 days For dose estimates, simplified dose estimates using the assumptions in C4.2.2.2 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 dispersion / 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:
D=1.84E+04w(D)I-131(1.05) where:
\
w = 7.3E-10 = D/Q for food and ground plane pathway, in m2 from Table C4.0-2 for location of nearest real goat (NW sector at 2.5 miles).
(Q)I-131 = the total Iodine-131 activity released in pCi.
1.84E+04 = (3.17E-08)(RC g
[D/Q)) with the appropriate substitut ons for goat's milk in the grass-cow-milk pathway factor, R{. [D/Q] for Iodine-131. See Section 3.1.2.2.
- 1.05 = factor derived from the conservative assumption (based on historical data) that 95% of the dose is contributed by I-131.
C4.3 FUEL CYCLE CALCULATIONS As discussed in Section 3.3.5, more than one nuclear power station site may contribute to the doses to be considered in making fuel cycle dose assessments in accordance with 40CFR190. The fuel cycle dose assessments for Catawba Nuclear Station must include dose contributions from McGuire Nuclear Station, which is located upstream approximately thirty miles NNE of Catawba. For this dose assessment, the maximum exposed individual is conservatively assumed to live 5 miles NNE of Catawba and 5 miles SSW of McGuire; this individual eats fish caught in the discharge area at Catawba.
The dose contributions resulting from gaseous effluents are calculated using the methodology ir Section 3.1.2:
Df (g) < 0.47 Dg(g) + 0.55 D C(8)
Where:
Dg (g) = dose contribution from McGuire calculated using X/Q = 1.5E-07 sec/m 3 and D/Q = 3.8E-10 sec/m3 . The location is 5 miles SSW of McGuire.
0.47 = fraction of time the wind direction is out of NNE.
C-15
Dc (g) = dose contribution from Catawba calculated using 5/Q = 3.3E-07 sec/m 3 and D/Q = 3.5E-10 sec/m3 . The location is 5 miles NNE of Catawba.
0.55 = Fraction of time the wind direction is out of SSW.
Using the methodology above and the assumption that each station releases their maximum Technical Specification dose limit, the gaseous effluent contribution to the fuel cycle calculation is but a small fraction (< 1/100) of the allowable dose. Therefore, fuel cycle calculations will not normally be performed unless either station exceeds their gaseous effluent Technical Specifications by a factor of 10.
The dose contribution resulting from liquid effluents is calculated using the methodology in Section 3.1.1:
Df (f) < 0.607 Dg (f) + DC I')
Where:
- 607 = 4400670 cfs (average cfs (average flowflow past past Lake Cowans Wylie Ford Dam)Dam) dilution D,(f) = Dose contribution from McGuire via liquid effluents D (f) = Dose contribution from Catawba via liquid effluents Using the methodology above and the assumption that each station releases its maximum Technical Specification dose limit, the liquid effluent contribution to the fuel cycle calculation would be 48% of the allowoble dose. Therefore, fuel cycle calculations will not normally be preformed unless either station exceeds its liquid effluent Technical Specifications by a factor of 2.
In summary, Technical Specification 3.11.4 will be the deciding criteria for Catawba fuel cycle calculations since it is either equal to (liquid) or is more restrictive than (gaseous) the cases outlined above.
r w
C-16
l TABLE C4.0-1 (1 of 2)
CATAWBA NUCLEAR STATION DISPERSION PARAMETER (X/Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR (sec/m3 )
Distance to the control location, (miles)
Sector 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 N 2.6E-5 6.5E-6 2.7E-6 1.5E-6 9.7E-7 6.9E-7 5.2E-7 4.1E-7 3.3E-7 2.8E-7 NNE 3.1E-5 8.1E-6 3.3E-6 1.8E-6 1.2E-6 8.2E-7 6.2E-7 4.9E-7 4.0E-7 3.3E-7 NE 3.0E-5 7.8E-6 3.2E-6 1.8E-6 1.1E-6 8.0E-7 6.0E-7 4.7E-7 3.9E-7 3.2E-7 ENE 1.5E-5 3.9E-6 1.6E-6 8.9E-7 5.7E-7 4.1E-7 3.1E-7 2.4E-7 2.0E-7 1.6E-7 E 1.4E-5 3.7E-6 1.5E-6 8.4E-7 5.4E-7 3.8E-7 2.9E-7 2.3E-7 i.9E-7 1.6E-7 ESE 9.0E-6 2.3E-6 9.5E-7 5.3E-7 3.4E-7 2.4E-7 1.8E-7 1.4E-7 1.2E-7 9.7E-8 SE 9.2E-6 2.4E-6 9.8E-7 5.4E-7 3.5E-7 2.4E-7 1.8E-7 1.4E-7 1.2E-7 9.8E-8 SSE 1.1E-5 2.9E-6 1.2E-6 6.4E-7 4.1E-7 2.9E-7 2.2E-7 1.7E-7 1.4E-7 1.1E-7 S 2.5E-5 6.4E-6 2.6E-6 1.5E-6 9.3E-7 6.6E-7 5.0E-7 3.9E-7 3.2E-7 2.7E-7 SSW 1.7E-5 4.4E-6 1.8E-6 1.0E-6 6.4E-7 4.5E-7 3.4E-7 2.7E-7 2.2E-7 1.8E-7 SW 1.3E-5 3.4E-6 1.4E-6 7.4E-7 4.7E-7 3.3E-7 2.4E-7 1.9E-7 1.5E-7 1.3E-7 WSW 7.0E-6 1.8E-6 7.2E-7 3.9E-7 2.5E-7 1.7E-7 1.3E-7 1.0E-7 8.2E-8 6.8E-8 W 8.9E-6 2.3E-6 9.3E-7 S.0E-7 3.2E-7 2.2E-7 1.7E-7 1.3E-7 1.1E-7 8.7E-8 WNW 6.6E-6 1.7E-6 6.8E-7 3.7E-7 2.4E-7 1.7E-7 1.3E-7 9.8E-8 8.0E-8 6.6E-8 NW 1.0E-5 2.6E-6 1.1E-6 5.9E-7 3.8E-7 2.7E-7 2.0E-7 1.6E-7 1.3E-7 1.1E-7 NNW 1.3E-5 3.3E-6 1.4E-6 7.5E-7 4.8E-7 3.4E-7 2.6E-7 2.0E-7 1.6E-7 1.4E-7
r
- TABLE C4.0-1 (2 of 2)
CATAWBA NUCLEAR STATION The values presented in this table were generated by using the computer program XOQD0Q (NUREQ/CR-2919) which implements NRC Regulatory Guide 1.111 (1977) and the following assumptions:
-1. Data Collection Period, 12/17/75 to 12/16/77.
- 2. Ground Level Releases.
- 3. Height of The Vent's Building = 47 meters.
- 4. Open Terrain Recirculation Connection Factors.
l' I
Y l'
L
TABLE C4.0-2 (1 of 2)
CATAWBA NUCLEAR STATION DIPERSION PARAMETER (D/Q) FOR LONG TERM RELEASES > 500 RH'/YR OR > 125 HR/QTR (meter "2)
Distance to the control location, (miles)
Sector 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 N 6.4E-8 1.6E-8 5.6E-9 2.8E-9 1.6E-9 ,
1.1E-9 7.5E-10 5.6E-10 4.3E-10 3.4E-10 NNE 1.1E-7 2.7E-8 9.6E-9 4.7E-9 2.SE-9 1.8E-9 1.3E-9 9.5E-10 7.4E-10 5.8E-10 NE 1.1E-7 2.6E-8 9.3E-9 4.6E-9 2.7E-9 1.8E-9 1.3E-9 9.3E-10 7.2E-10 5.7E-10 ENE 4.1E-8 1.0E-8 3.6E-9 1.8E-9 1.IE-9 6.9E-10 4.9E-10 3.6E-10 , 2.8E-10 2.2E-10 E 3.6E-8 8.3E-9 3.2E-9 1.6E-9 9.3E-10 6.1E-10 4.3E-10 3.2E-10 2.4E-10 1.9E-10 ESE 2.5E-8 6.0E-9 2.2E-9 1.1E-9 6.3E-10 4.2E-10 2.9E-10 2.2E-10 1.7E-10 1.3E-10 SE 3.0E-8 7.3E-9 2.6E-9 1.3E-9 7.7E-10 5.0E-10 3.5E-10 2.6E-10 2.0E-10 1.6E-10 SSE 3.8E-8 9.3E-9 3.3E-9 1.7E-9 9.7E-10 6.4E-10 4.5E-10 3.3E-10 2.6E-10 2.0E-10 S 7.2E-8 1.8E-8 6.3E-9 3.1E-9 1.8E-9 1.2E-9 8.5E-10 6.3E-10 4.8E-10 3.8E-10 SSW 6.6E-8 1.6E-8 5.8E-9 2.9E-9 1.7E-9 1.1E-9 7.8E-10 5.8E-10 4.4E-10 3.5E-10 SW 5.7E-8 1.4E-8 5.0E-9 2.5E-9 1.5E-9 9.6E-10 6.7E-10 5.0E-10 3.9E-10 3.1E-10 WSW 2.4E-8 5.7E-9 2.1E-9 1.0E-9 6.0E-10 4.0E-10 2.8E-10 2.1E-10 1.6E-10 1.3E-10 W 2.8E-8 6.7E-9 2.4E-9 1.2E-9 7.0E-10 4.6E-10 3.2E-10 2.4E-10 1.9E-10 1.5E-10 WNW 1.9E-8 4.6E-9 1.7E-9 8.2E-10 4.8E-10 3.2E-10 2.2E-10 1.6E-10 1.3E-10 1.0E-10 NW 2.9E-8 7.0E-9 2.5E-9 1.3E-9 7.3E-10 4.8E-10 3.4E-10 2.5E-10 1.9E-10 1.5E-10 NNW 4.1E-8 9.9E-9 3.6E-9 1.8E-9 1.0E-9 6.8E-10 4.8E-10 3.6E-10 2.7E-10 2.2E-10
TABLE C4.0-2 (2 of 2)
CATAWBA NUCLEAR STATION The valves presented in this table were generated by using the computer program X0QD0Q (NUREQ/CR-2919) which implements NRC Regulatory Guide 1.111 (1977) and the following assumptions:
- 1. Data Collection Period, 12/17/75 to 12/16/77.
- 2. Ground Level Releases.
- 3. Ileight of The Vent's Building = 47 meters.
- 4. Open Terrain Recirculation Connection Factors.
t
TABLE C4.0-3 *
(1 of 3)
CATAWBA NUCLEAR STATION ADULT A,g DOSE PARAMETERS (mrem /hr per pCi/ml)
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LTI H 3 0.0 4.58E-01 4.58E-01 4.58E-01 4.58E-01 4.58E-01 4.58E-01 NA 24 4.11E+02 -4.11E+02 4.11E+02 4.11E+02 4.11E+02 4.11E+02 4.11E+02 CR 51 0.0 0.0 1.28E+00 7.65E-01 2.82E-01 1.70E+00 3.22E+02 MN 54 0.0 4.39E+03 8.37E+02 0.0 1.31E+03 0.0 1.34E+04 MN 56 0.0 1.10E+02 1.96E+01 0.0 1.40E+02 0.0 3.52E+03 FE 55 6.64E+02 4.59E+02 1.07E+02 0.0 0.0 2.56E+02 2.63E+02 FE 59- 1.05E+03 2.46E+03 9.45E+02 0.0 0.0 6.89E+02 8.21E+03 C0 58- 0.0 9.08E+01 2.04E+02 0.0 0.0 0.0 1.84E+03 C0 60 0.0 2.61E+02 5.75E+02 0.0 0.0 0.0 4.90E+03 NI 63 3.14E+04 2.18E+03 1.05E+03 0.0 0.0 0.0 4.54E+02 NI 65 1.28E+02 1.66E+01 7.56E+00 0.0 0.0 0.0 4.20E+02 CU 64 0.0 1.02E+01 4.77E+00 0.0 2.56E+01 0.0 8.66E+02 ZN 65' 2.32E+04 7.38E+04 3.33E+04 0.0 4.93E+04 0.0 4.65E+04
.i' ZN 69 4.93E+01 9.44E+01 6.56E+00 0.0 6.13E+01 0.0 1.42E+01
, 'BR 83 0.0 0.0 4.05E+01 0.0 0.0 0.0 5.83E+01 BR 84 0.0 0.0 5.25E+01 0.0 0.0 0.0 4.12E-04 BR 85 0.0 0.0 2.16E+00 0.0 0.0 0.0 0.0 RB 86 0.0 1.01E+05 4.71E+04 0.0 0.0 0.0 1.99E+04 RB 88 0.0 2.90E+02 1.54E+02 0.0 0.0 0.0 4.00E-09 RB 89 0.0 1.92E+02 1.35E+02 0.0 0.0 0.0 1.12E-11
'SR 89 2.28E+04 0.0 6.54E+02 0.0 0.0 0.0 3.66E+03 SR 90 2.84E+05 0.0 7.62E+04 0.0 0.0 0.0 1.62E+04 SR 91 4.20E+02 0.0 1.70E+01 0.0 0.0 0.0 2.00E+03 SR 92 1.59E+02 0.0 6.88E+00 0.0 0.0 0.0 3.15E+03 Y. 90 5.97E-01 0.0 1.60E-02 0.0 0.0 0.0 6.33E+03 Y 91M 5.64E-03 0.0 2.18E-04 0.0 0.0 0.0 1.66E-02 Y 91 8.75E+00 0.0 2.34E-01 0.0 0.0 0.0 4.82E+03 Y 92 5.24E-02 0.0 1.53E-03 0.0 0.0 0.0 9.18E+02
- Methodology for table provided by: M. E. Wrangler, RAB:NRR:NRC on 3/17/83 9
C TABLE C4.0-3 (1 of 3)
TABLE C4.0-3 (2 of 3)
CATAWBA NUCLEAR STATION ADULT A g DOSE PARAMETERS (mrom/hr per pCi/ml)
NUCLIDE BONE LIVER T. BODY TIIYROID KIDNEY LUNG GI-LII Y 93 1.66E-01 0.0 4.59E-03 0.0 0.0 0.0 5.27E+03 ZR 95 3.07E-01 9.85E-02 6.67E-02 0.0 1.55E-01 0.0 3.12E+02 ZR 97 1.70E-02 3.43E-03 1.57E-03 0.0 5.18E-03 0.0 1.06E+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 1.13E+02 2.14E+01 0.0 2.55E+02 0.0 2.61E+02 TC 99M 9.41E-03 2.66E-02 3.39E-01 0.0 4.04E-01 1.30E-02 1.57E401 TC 101 9.6AE-03 1.40E-02 1.37E-01 0.0 2.51E-01 7.13E-03 4.19E-14 RU 103 4 84E+00 0.0 2.08E+00 0.0 1.85E+01 0.0 5.65E+02 RU 105 4.03E-01 0.0 1.59E-01 0.0 5.20E+00 0.0 2.46E+02 RU 106 7.19E+01 0.0 9.10E+00 0.0 1.39E+02 0.0 4.65E+03 AG 110M 1.23E+00 1.14E+00 6.78E-01 0.0 2.24E+00 0.0 4.66E+02 TE 125M 2.57E+03 9.32E+02 3.45E+02 7.74E+02 1.05E+04 0.0 1.03E+04 TE 127M 6.50E+03 2.32E+03 7.92E+02 1.66E+03 2.64E+04 0.0 2.18E+04 TE 127 1.06E+02 3.79E+01 2.28E+01 7.82E+01 4.30E+02 0.0 8.33E+03 TE 129M 1.10E+04 4.12E+03 1.75E+03 3.79E+03 4.61E+04 0.0 5.56E+04 TE 129 3.01E+01 1.13E+01 7.34E+00 2.31E+01 1.27E+02 0.0 2.27E+01 TE 131M 1.66E+03 8.12E+02 6.77E+02 1.29E+03 8.23E+03 0.0 8.06E+04 -
TE 131 1.89E+01 7.90E+00 5.97E+00 1.55E+01 8.28E+01 0.0 2.68E+00 TE 132 2.42E+03 1.56E+03 1.47E+03 1.73E+03 1.51E+04 0.0 7.40E+04 I 130 2.88E+01 8.50E+01 3.35E+01 7.20E+03 1.33E+02 0.0 7.32E+01 I 131 1.59E+02 2.27E+02 1.30E+02 7.43E+04 3.89E+02 0.0 5.98E+01 I 132 7.74E+00 2.07E+01 7.24E+00 7.24E+02 3.30E+01 0.0 3.89E+00 I 133 5.41E+01 9.41E+01 2.87E+01 1.38E+04 1.64E+02 0.0 8.46E+01 I 134 4.04E+00 1.10E+01 3.93E+00 1.90E+02 1.75E+01 0.0 9.57E-03 I 135 1.69E+01 4.42E+01 1.63E+01 2.92E+03 7.09E+01 0.0 4.99E+01 CS 134 2.98E+05 7.09E+05 5.80E+05 0.0 2.29E+05 7.62E+04 1.24E+04 CS 136 3.12E+04 1.23E+05 8.86E+04 0.0 6.85E+04 9.39E+03 1.40E+04 CS 137 3.82E+05 5.22E+05 3.42E+05 0.0 1.77E+05 5.89E+04 1.01E+04 CS 138 2.64E+02 5.22E+02 2.59E+02 0.0 3.84E+02 3.79E+01 2.23E-03 BA 139 1.14E+00 8.14E-04 3.35E-02 0.0 7.61E-04 4.62E-04 2.03E+00
- TABLE C4.0-3 (2 of 3)
l TABLE C4.0-3 (3 of 3)
CATAWBA NUCLEAR STATION ADULT A g DOSE PARAMETERS t
(mrem /hr per pCi/ml) i NUCLIDE B0NE LIVER T. BODY THYROID KIDNEY LUNG GI-LII f
BA 140 2.39E+02 3.00E-01 1.57E+01 0.0 1.02E-01 1.72E-01 4.93E+02 i BA 141 5.55E-01 4.19E-04 1.87E-02 0.0 3.90E-04 2.38E-04 2.62E-10 y BA 142 2.51E-01' 2.58E-04 1.58E-02 0.0 2.18E-04 1.46E-04 3.54E-19 LA 140 _1.55E-01 7.82E-02 2.07E 0.0 0.0 0.0 5.74E+03 ;
LA 142 7.94E-03 3.61E-03 9.00E-04 '.0 0.0 0.0 2.64E+01 !
CE 141 4.31E-02 2.91E-02 3.30E-03 0.0 1.35E-02 0.0 1.11E+02 +
CE 143 7.59E-03 5.61E+00 6.21E-04 0.0 2.47E-03 0.0 2.10E+02 -
CE 144 2.25E+00 9.39E-01 1.21E-01 0.0 5.57E-01 0.0 7.59E+02 :
PR 143 5.71E-01 2.29E-01 2.83E-02 0.0 1.32E-01 0.0 2.50E+03
- PR 144 1.87E-03 7.76E-04 9.49E-05 0.0 4.38E-04 0.0 2.69E-10 ND 147 3.90E-01 4.51E-01 2.70E-02 0.0 2.64E.01 0.0 2.17E+03 ,
W 187 2.96E+02 2.48E+02 8.65E+01 0.0 0.0 0.0 8.11E+04 NP 239 3.11E-02 3.06E-03 1.69E-03 0.0 9.54E-03 0.0 6.28E+02 I
t f
_t i
l t
TABLE C4.0-3 i
(3 of 3) ;
l i
_ . _ . . ._ . . _ . _..-_..._.._..___-_._-_________.J
r C5.0 Radiological Environmental Monitoring The Radiological Environmental Monitoring Program shall be conducted in accordance with Technical Specification, Section 3/4.12.
The monitoring program locations and analyses are given in Tables C5.0-1 through C5.0-3 and Figure C5.0-1.
Site specific characteristics make groundwater sampling, special low-level I-131 analyses on drinking water, and food product sampling unnecessary. Ground-water recharge is from precipitation and 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 will 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 lakewater irrigation is not practiced in the vicinity.
The laboratory performing the radiological environmental analyses shall parti-cipate 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 Intercomparsion Studies (crosscheck)
Program, our participation code is CP.
The dates of the land-use census that was used to identify the controlling receptor locations was 10/26/82 - 10/28/82. These dates will not be changed
. unless a subsequent census changes a controlling receptor's location.
D-L C-17
TABLE C5.0-1 (1 of 1)
CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD LOCATIONS)
SAMPLING LOCATION DESCRIPTION SAMPLING LOCATION DESCRIPTION i
200 SITE BOUNDARY (0.7M NNE) 232 4-5 MILE RADIUS (4.1M NE) .
201 SITE BOUNDARY (0.5M NE) 233 4-5 MILE RADIUS (4.0M ENE) 202 SITE BOUNDARY (0.6M ENE) 234 4.5 MILE RADIUS (4.5tf E) 203 SITE BOUNDARY (0.5M SE) 235 4.5 MILE RADIUS (4.0M ESE) 204 SITE BOUNDARY (0.5M SSW) 236 4-5 MILE RADIUS (4.2N SE)
]
205 SITE BOUNDARY- (0.6M SW) 237 4-5 MILE RADIUS (4.8t1 SSE) l 206 SITE BOUNDARY (0.7M WNW) 238 4-5 MILE RADIUS (4.2M S) 207 SITE BOUNDARY (0.8M NNW) 239 4-5 MILE RADIUS (4.6M SSW) 212 SPECIAL INTEREST (2.7M ESE) 240 4-5 MILE RADIUS (4.1M SW) 217 CONTROL (10.0M SSE) 241 4-5 MILE RADIUS (4.7M WSW) 222 SITE BOUNDARY (0.7M N) 242 4-5 MILE RADIUS (4.6M W) 223 SITE BOUNDARY (0.5M E) 243 4-5 MILE RADIUS (4.6M WNW) 224 SITE BOUNDARY (0.7M ESE) 244 4-5 MILE RADIUS (4.IM NW) 225 SITE BOUNDARY (0.5M SSE) 245 4-5 MILE RADIUS (4.2M NNW)
SITE BOUNDARY (0.5M S) 246 SPECIAL INTEREST (8.1M ENE) 226 227 SITE BOUNDARY (0.5M WSW) 247 CONTROL (7.5M ESE) 228 SITE BOUNDARY (0.6M W) 248 SPECIAL INTEREST (8.2M SSE) 229 SITE BOUNDARY (0.9M NW) 249 SPECIAL INTEREST (8.1M S) 4-5 MILE RADIUS (4.4M N) 250 SPECIAL INTEREST (10.3M WSW) 230 251 CCNTROL (9.SM WNW) 231 4-5 MILE RADIUS (4.2M NNE) m
TABLE C5.0-2 (1 of 1)
CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS 5
-(OTHER SAMPLING LOCATIONS) y CODE:
58 u e a a W - Weekly Q - Quarterly 3N O N SM - Semimonthly SA - Semiannual o3 $ e w M - Monthly aO e $ d E EU N 5 Y Y us t S 8 4 4 8 4e a e 5 d
~ a
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ S_ A_ M_ PL_ _I N_ G_ _ L_ O_ CA_T_ _I O_ N_ _ D_E_ S_ C_ R_ _I P_T_ I O_ N_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
200 Site Boundary (0.7m NNE) W Site Boundary (0.5m NE) W M 201 205 Site Boundary (0.6m SW) W Discharge Canal (0.5m S) M SA SA 208 Dairy (7.0m SSW) Stf 209 SA 210 Ebenezer Access (2.4m SE) 211 Wylie Dam (4.0m ESE) M 212 Tega Cay (2.7m ESE) W 213 Fort Mill Water Supply (7.5m ESE) M Rock liill Water Supply (7.3n SSE) M 214 Camp Steere-IIwy 49 (4.1m NNE) Control SA 215 M SA 216 IIwy 49 Bridge (4.0m NNE) Control W fl 217 Rock 11111 Jubstation (10.0m SSE) Control Belmont Water Supply (13.5m N) Control M
i
~
TABLE C5.0-3 (1 of 1)
CATAWBA RADIOLOGICAL MONITORING 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 Uater 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
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(1 OF 2)
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FIGURE C5.01 g' pA
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- (2 OF 2)
Th* "'""' Pg CATAWBA NtCLEAR STATION
DUKE POWER GOMPANY P.O. Box 33180 C11AHI.OTTE, N.C. 28242 ILE 15. TUCKER reterinose
,,J"",,",",*""",_ July 9, 1984 (*) "*"
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
~
Attention: jMs.E.G".9Aden' sam; Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
Please find attached for your review and approval five (5) copies of the Offsite Dose Calculation Manual for the Catawba Nuclear Station. This manual incorporates changes resulting from your staff's review.
Very truly yours, db M -
Hal B. Tucker RWO/rbs Attachment cc: (w/ attachment)
Mr. James P. O'Reilly, Regional Administrator V. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector Catawba Nuclear Station (w/o attachment)
Mr. Robert Guild, Esq. .
Attorney-at-Law P. 0. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 21351 Devine Street lQ i g Columbia, South Carolina 29205 i Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207
r December 22, 1983.
Offsite Dose Calculation Manual Distribution
SUBJECT:
Offsite Dose Calculation Manual Special Instructions for Issue - ONS File: GS-778.00 The General Office Radwaste Engineering staff is transmitting to you this date 7 copy / copies, number (s) 154-40 of the subject manual for issue by December 28, 1983.
This manual is limited in distribution to facilitate future revisions. Copies of this manual should be controlled in accordance with the requirements of Section 2.1 of the Administrative Policy Manual for Nuclear Stations.
All copies of this manual issued for use at nuclear stations will be issued to the station manager for reissue to the fo13owing individuals or locations:
Copy Number Individual /I.ocation 34 C. T. Yongue 35 J. A. Long 36 C. L. Harlin 37 D. P. Rochester 38 #1 Control Room 39 #2 Control Room 40 Master File If you have any questions regarding this distribution, please call Jim Stewart at Ext. 5444.
M. L. Birch System dwaste Enginae W$$ W- '
By: James M. Stewart, Jr.
- Associate Health Physicist WC - 2389 JMS/dkt .
d h
e
,/
December 22, 1983
SUBJECT:
Offsite Dose Calculation Manual - Revision 3 The General Office Radwaste Engineering staff is transmitting to you this date, Revision 3 of the Orfsite Dose Calculation Manual. As this revision only af-fects Oconee Nuclear Station, the approval of the manager of McGuire Nuclear Station is not necessary. Please update your copy No. , and discard affected pages.
REMOVE THESE PAGES INSERT THESE PAGES Remove all pages currently located Insert this package behind the tab behind the tab labeled "Oconee", labeled "Oconee", and in front of and in front of the tab labeled the tab labeled "McGuire".
"McGuire".
NOTE: As this letter contains "LOEP" information, please insert this letter in front of the September 30, 1983 letter.
Approval Date: /8!/2!d3 Approval Date: /2 f.f Effective Date: 01/01/84 Effective Date: 01/01/84~
-=1 r pr m Mary L. Birch J. E Smith, Manager System Redwaste Engineer Oconce Nuclear Station If you have any questions concerning Revision 3, please call Jim Stewart at (704) 373-5444.
O
&hS W*
James M. Stewart, Jr.
Associate Health Physicist MLB/JES /JMS/dkt Enclosures
September 30, 1983
SUBJECT:
Offsite Dose Calculation Manual - Revision 2 The General Office Radwaste Engineering staff is transmitting to you this date, Revision 2 of the Offsite Dose Calculation Manual. Please update your copy No.
, and discard affected pages.
REMOVE THESE PAGES INSERT THESE PAGES Page B-6 Page B-6 Revision 2 Page B-11 Page B-11 Revision 2 Page B-15 Page B-15 Revision 2 Table B4.0-1 Table B4.0-1 Revision 2 Table B4.0-2 Table B4.0-2 Revision 2 NOTE: As this letter contains "L0EP" information, please insert this letter in front of the April 15, 1983 letter.
Approval _ Date: 9/J//f_J Approval Date: 7f A'93
/ / ) !
Effective Date: 10/07/83 Effective Date: 10/07/83 0.AA M. L. Bir<fch h? '
M. D. McIntosh, Manager System Radwaste Engineer McGuire Nuclear Station If you have any questions concerning Revision 2, please call Jim Stewart at (704) 373-5444.
o , w /// S A 9 /
James M. Stewart, Jr.
Associate Health Physicist
'WC-2389 JMS/dkt i
i.
April 15, 1983 Subjec*: McGuire Nuclear Station Offsite Dose Calculation Manual The General Office Radwaste Engineering staff is transmitting to you this date, Revision 1, of the Offsite Dose Calculation Manual. Please update your copy No. and discard affected pages.
Remove These Pages Insert These Pages Table 1.2-2 Table 1.2-2 Rev. 1 Page 3-6 Page 3-6 Rev. 1 Page 3-7 Page 3-7 Rev. 1 Table B4.0-2 Table B4.0-2 Rev. 1 Table B5.0-4 (1 of 3) Table B4.0-3 (1 of 3)Rev. 1 Table B5.0-4 (2 of 3) Table B4.0-3 (2 of 3)Rev. 1 Table B5.0-4 (3 of 3) Table B4.0-3 (3 of 3)Rev. 1 Note: As this letter contains "LOEP" information, please insert this letter in front of the February 28, 1983 letter.
Approval Date: f// T3 Approval Date: Iff3
//
Effective Date: 4/15/83 Effective Date: 4/15/83 d
M.L c M.D. McIntosh, Manager System Radwaste Engineer McGuire Nuclear Station If you have any questions concerning Revision 1, please call Jim Stewart at 704/373-5444.
W ?N S .
James M. Stewart, Jr.
Associate Health Physicist WC-2389 JMS/fke
February 28, 1983 f
I
Subject:
McGuire Nuclear Station Offsite Dose Calculation Manual Please find attached copy / copies No. of the subject manual. As this revision constitutes a complete reprint of the manual, please discard all present manuals. Subsequent revisions will be issued as required and only affected pages will be changed.
Approval Date: 2/4f/85 Approval Date: I 89
</ /
%Y M. L. Birch W "
M. D. McIntosh, Manager System Radwaste Engineer McGuire Nuclear Station 1
J
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