ML19344B241
| ML19344B241 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/21/1980 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19268D006 | List: |
| References | |
| PROC-800821, NUDOCS 8008250875 | |
| Download: ML19344B241 (81) | |
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. a OAugust 19, 1980
Subject:
McGuire Nuclear Station Offsite Dose Calculation Manual Please find attached copy / copies No. [ of Revision 1 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. Revision 1 of this manual has been approved as indicated below. Approval Date: [ 12 h/) Approval Date:
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J . l' n i/ / -
/ .% ?'U Lionel Lewis 'M. D. McIntosh, Manager System Eealth Physicist McGuire Nuclear Station
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A a 0 0FFSITE DOSE CALCULATION MANUAL FOR DUKE POWER NUCLEAR STATIONS I t i i i f
-o. O MCGUIRE YUCLEAR STATION OFFSITE DOSE CALCULATION MANUAL-LIST OF EFFECTIVE PAGES Page Revision LOEP Page 1 of 4 Rev. 1 LOEP Page 2 of 4 Rev. 1 LOEP Page 3 of 4 Rev. 1 LOEP Page 4 of 4 Rev. I i Rev. 1 ii Original iii Rev. 1 1-1 Rev. 1 __
1-2 Originel Table 1.2-1 Rev. 1 Table 1.2-2 Rev. 1 2-1 Original 2-2 Original 3-1 Rev. 1 3-2 Original 3-3 Original 3-4 Original 3-5 Original 3-6 Original 3-7 Rev. 1 3-8 Rev. 1 3-9 Rev. 1 - Table 3.1-1 (1 of 1) Rev. 1 Table 3.1-2 (1 of 3) Rev. 1
- Page 1 of 4 Revision 1
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, o MCGUIRE NUCLEAR STATION OFFSITE DOSE CALCULATION MANUAL LIST OF EFFECTIVE PAGES (Cont'd)
Pm Revision Table 3.1-2 (2 of 3) Original Table 3.1-2 (3 of 3) Original Table 3.1-3 (1 of 3) Rev. 1 Table 3.1-3 (2 of 3) 0~riginal Table 3.1-3 (3 of 3) Original Table 3.1-4 (1 of 3) Rev. 1 Table 3.1-4 (2 of 3) Original Table 3.1_4 (3 of 3) Original _ Table 3.1-5 (1 of 3) Rev. 1 Table 3.1-5 (2 of 3) Original Table 3.1-5 (3 of 3) Original Table 3.1-6 (1 of 3) Rev. 1 Table 3.1-5 (2 of 3) Original Table 3.1-5 (3 of 3) Original Table 3.1-7 (1 of 3) Rev. 1 Table 3.1-7 (2 of 3) Original Table 3.1-7 (3 of 3) Original Table 3.1-8 (1 of 3) Rev. 1 Table 3.1-8 (2 of 3) Original Table.3.1-8 (3 of 3) Original Table 3.1-9 (1 of 3) Rev. 1 Table 3.1-9 (2 of 3) Original Table 3.1-9 (3 of 3) Original Page 2 of 4 Revision 1
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g- _ MCGUIRE NUCLEAR STATION OFFSITE DOSE CALCULATION MANUAL LIST OF EFFECTIVE PAGES (Cont'd) Page Revision Table 3.1-10 (1 of 2) Rev. 1 Table 3.1-10 (2 of 2) Original Table 3.1-11 (1 of 1) Rev. 1 Appendix B Table of Contents Rev. 1 B-1 Original Figure Bl.0-1 Original B-2 Original Figure Bl.0-2 Original - B-3 Original Table Bl.0-1 (1 of 2) Original Table Bl.0-1 (2 of 2) Original B-4 Rev. 1 B-5 _ Rev. 1 B-6 Rev. 1 B-7 Rev. 1 B-8 Rev. 1 B-9 Rev. 1 B-10 Rev. 1 B-11 Rev. 1 B-12 Rev. 1 B-13 Rev. 1 Table B4.0-1 Rev. 1 Table B4.0-2 Rev. 1 B-14 Rev. 1 Page 3 of 4 Revision 1
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MCGUIRE NUCLEAR STATION OFFSITE DOSE CALCULATION MANUAL LIST OF EFFECTIVE PAGES (Cont'd) , Pam Revision Table B5.0-1 Rev. 1 Table B5.0-2 Rev. 1 Table B5.0-3 Rev. 1 Figure B5.0-1 (1 of 2) Rev. 1 Figure B5.0-1 (2 of 2) Rev. 1 i i I Page 4 of 4 Aevision 1
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. e 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 Conver:. ion 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
.,,,endix A - Oconee Nuclear Station Site Specific Information Appendix B -
McGuire Nuclear Station Site Specific Information Appendix C - Catawba Nuclear Station (Later) Site Specific Information i l i i i Revision 1
( . 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 Adultr. 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 _ i ii t
INTRODUCTION The Offsite Dose Calculation Manual provides the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents to assure compliance with the dose limitations of the Technical Specifications. These dose limitations assure that:
- 1) the concentration of radioactive liquid effluents from the site to the unrestricted area will be limited to the concentration levels of 10CFR20, Appendix B, Table II;
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- 2) the exposures to any individual from radioactive liquid effluents will not result in doses greater than tae design objectives of 10CFR50, Appendix I;
- 3) the dose rate at any time at the site boundary from radioactive gaseous effluents will be limited to the annual dose limits of 10CFR20 for unrestricted areas; and
- 4) the exposure to any individual from radioactive gaseous effluents will not result in doses greater than the design objectives of 10CFR50, -
Appendix I. The methodology used to assure compliance with the dose limitations described above shall also be used to prepare the radioactive liquid and gaseous effluent 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 prc rides the methodology and parameters to be used in the calculation of rad:.oactive 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 Health Physicist 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 within 90 days of the date the change was made effective by inclu-sion in the Monthly Operating Report to comply with the Technical Specifica-tions. This Manual does not replace any station f2plementing procedures. iii Revision 1
1.0 RELEASE RATE CALCULATIONS The release rate calculations presented in the following sections are site release limits. Sites containing two or more units shall administratively control releases to assure that the release rate calculations limit releases as stated in the Technical Specifications. Administrative controls could limit the number of releases occurring at one time or apportion the release rate between the units. 1.1 LIQUID EFFLUE.VTS To comply with Technical Specifications and to assure that the concentration of radioactive liquid effluents from the site to the unrestricted area is limited to the concentrations of 10CFR20, Appendix B, Table II, Column 2, the following release rate calculation shall be performed: a fiF+(oI Ci ) i=1 MPC f where: C. = The concentration of radionuclide, 'i', in undiluted liquid effluent, in pCi/ml. MPC. = the concentration of radionuclide, 'i#, from 10CFR20, Appendix B, Table 1 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. o = 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 GASEOUS EFFLUENTS In order to comply with the Technical Specifications and to assure that the dose rate, at any time, in the unrestricted area due to radioactive materials released in gaseous effluents from the site is limited to 1500 mrem /yr to the total body and $3000 mrem /yr to the skin for the noble gases and is limited to $1500 mrem /yr to any organ for all radioiodine and for all radioactive materials in particulates form and radionuclides other than noble gases with half lives greater than 8 days, the following release rate calculations shall be performed. These calculations, when solved for ' f' , .e. flowrate, are the release rates for noble gases and for radiciodines, particulates and other radionuclides with half-lives greater the " days. The most conservative of release rates calculated shall control the release rate. 1-1 Revision 1
1.2.1 Noble Gases s IK x1 [(X/Q)Q ] g<500 mrem /yr, and 1 I (Lg + 1.1 Mg ) [(i7Q)Qg ] <3000 mrem /yr 1 where: K.
= The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m 3 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/m3 from Table 1.2-1.
M. = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m 3 from Table 1.2-1 (unit con-version constant of 1.1 mrem / mrad converts air dose to skin dose). P. 1
= The dose parameter for radionuclides other than noble gases for the 3
inhalation pathway,2in mrem /yr per pCi/m and for the food and ground plane pathways in m (mrem /yr) per pCi/sec from Table 1.2-2. The dose factors are based on the critical individual organ and most restric-tive age grcup (child or infant). s
= The release' rate of radionuclides, 'i', in gaseous effluent from all Q *.
release points at the site, in pCi/sec. (i7Q)= 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
- g. Qg =kCf+k2 t g = 4.72E+2C1 f where:
C. = the concentration of radionuclide, 'i', in undiluted gaseous effluent, in , "./ml. f = the undiluted effluent flow, in cfm. k = conversion factor, 2.83E4 ml/f t3 t k2 = conversion factor, 6El sec/ min. 1.2.2 Radioiodines, Particulates, and Others s
< 1500 mrem /yr IP1 1
[W Qg ] where the terms are as defined above. 1-2
TABLE 1.2-1 (1 of 1)
- DOSE FACTORS FOR NOHLE CASES AND DAUGitTERS*
Total Body Gannua Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K. L. M. N. Radionuclide (mrem /yr per DCi/m ) 3 (mrem /yr p$r pCi/m3 ) (mrad /yr per pCi/m 3) (mrad /yr per pCi/m 3) lKr-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 1 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.llE+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 g 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 a
~Erhe listed dose factors are for radionuclides that may be detected in gaseous effluents.
**7.56E-02 = 7.56 x 10 2, I
TAltl.E 1.2-2 (1 of 1)-
- DOSE PARAME1ERS FOR RAD 1010 DINES AND RADIDACTIVE
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PARflCUI.ATib GA5E0tlS EFFill5ffT5* P(l), DOSE PARAMETERS FOR RADIO 10 DINES AND RADIOACTIVE PARTICUI.ATES IN GASEOUS EFFLUENTS Pathways Pathways Inhalation Hilk and Ground Inhalation Hilk and Ground (mrem /yr per m2 . mrem /yr per (arem/yr per (m2 . seres /yr per RadionucIide __pci/m3 ) _pcijsec) Radionuctide pCi/m3) _ pci/se() 11 3 *
- 6.5E+02 2.4E+03 RU 103 1.6E+04 1.6Et08 RU 106 1.6E+05 3.0Et08 P 32 2.0Et06 1.6E*ll AG 110H 3.3E*04 1.5E*lo CR 51 3.6Et02 1.lEt07 CD ll5H 7.0E+04 5.2E*07 HN S4 2.5E*04 1.lE+09 SN 123 2.9Et05 3.7E*09 FE 55 2.0E+04 1.lE+08 SN 126 1.2E+06 1.lEt10 FE 59 2.4Et04 7.2E+08 SB 124 5.9E*04 1.4E+09 CO 58 1.lEt04 5.8E+08 SB 125 1.5E+04 9.lE+08 CO 60 3.2Et04 4.6Et09 TE 127H 3.8E+04 1.0E+09 NI 63 3.4E+05 3.0E+10 TE 129H 3.2E+04 1.3Et09 ZN 65 6.3E+04 1.8E+10 CS 134 7.0E+05 5.6E+10 Ril 86 1.9E+05 2.IE+10 CS 136 1.3Et05 5.7Et09 SR 90 4.lE*07 1.0E+11 BA 140 5.6E+04 2.6E*08 Y 91 7.0Et04 5.9E+06 CE 141 2.2E+04 3.2Et07 2R 95 2.2E+04 3.5E+08 CE 144 1.5E+05 1.6E+08 Nil 95 1.3Et04 3.8E*08 I 131 1.5E+07 1.0E+12 H0 99 2.6E+02 3.2E+08 I 133 3.6E+06 9.6E+09
{g *1f SR-90 analysis is performed, use P(I) given in 1-131 for unidentified components. I f SR-90 and I-131 analyses are performed, use P(I) given in CS-137 for unidentified components. If SR-90, 1-131, and CS-137 g analyses .sre perf ormed, use P(I) given in ZN-65 f or unidentified components, u 3 - ** Fo r t r i t i um , the units of dose parameters are mrem /yr per pCi/m f or all pathways, and they must be multiplied ley X/Q in Specification 3.11.2.1.11. I
2.0 RADIATION MONITORING SETPOINTS Effluent radiation monitor alarm / trip setpoints shall be determined using the calculations presented in the following sections. The calculations define the relationships between the measured effluent activity, the maximum allowable effluent activity, the effluent flowrate, and the dilution available in the restricted area (as defined for effluent releases in the Technical Specifica-tions) which must be controlled to assure that the instantaneous release rate is not exceeded. The setpoints shall be determined for those monitors listed in the appropriate tables of the Technical Specifications. 2.1 LIQUID MONITORS The following equation shall be used to calculate liquid radiation monitor setpoints: y g S MPC where: - MPC = the effluent concentration limit implementing 10CFR20 for the site, in pCi/ml. C = the radioactivity concentration in pCi/ml, in the effluent line prior to dilution and subsequent release, which may be the setpoint and, if so, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10CFR20 in the unrestricted area. f = the flow measured at the radiation monitor location in gpm. F = the dilution water flow as measured prior to the release point in gpm. (Note that if no dilution is provided, C 5 HPC. Also, note that when (F) is large compared to (f), then F + f 3 F.) 2.2 GAS MONITORS The following equation shall be used to calculate noble gas radiation monitor setpoints based on Xe-133: s Kg (X/Q)Qg < 500 Qg = 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 ar building and varies for various release sources, in efm. 2-1
. . _ . . _ . - . . -. .. . . . . . ~ _
_ . - ~ . . .- . . . . _ - . . Y Kg = fros Table 1.2-1 for Xe-133, 2.94E-2 ares /yr per pCi/m . 3 (5) = the highest calculated annual average dispersion parameter for any area at or beyond the unrestricted area boundary for long term releases. i i t i l i 4
=>
k t s I 4 h l i 2-2
f 3.0 DOSE CALCULATIONS 3.1 DOSE MODELS FOR MAXIMUM 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 11guid effluents released to unrestricted areas shall be calculated for the maxi-mum exposed individual in each age group using: m St *hIAait 1 O'A C gg F] I f=1 g where: gg = the cumulative dose commitment to the total body or any organ, I, for an individual of age group, a, from the liquid efflueut a -- for the total time period I at g, in mrem. f=1 at g= the length of the Ath 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 l F2=Fxf where: , a = recirculation factor at equilibrium; this factor accounts for the frac-
- tion of discharged water reused by the station. This factor is one for stations on rivers or lakes where discharged water cannot be reused, and varies for sites where water is recirculated and is specified in the appropriate Appendix.
f = liquid radwaste flow, in gpm. l F = dilution flow, in gpm. l A.I
"* = the site related ingestion dose commitment factor for an individual of age group, a, to the total body or any organ, 'T', for each identi-fled principal gamma and beta emitter, mrem /hr per pCi/ml.
A,g7 = 1.14E5 (U,y/D y +U aF BF;)DF,g7 3-1 Revision 1 , a
F o where: 1.14E5 = 10 8 pci/pci x 103ml/kg + 8760 hr/yr. U,y = Water consumption by age group, 2/yr. infant 330 child 510 teen 510 adult 730 Dy = Dilution factor froo the near field area to the potable water intake. UaF = 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**.* = 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. 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: I 3.1.2.1 Noble Gases For gamma radiation: s D = 3.17 E-8 I M. i=1 * [(X7Q) Q } l Y i l l For beta radiation: s Dp = 3.17 E-81:,1 I Ng [(X7Q) Qi l where: l 3.17 x 10 8 = The inverse of the number of seconds in a year. M. = The air dose factor due to gamma emissions for each identified noble
- gas radionuclide, in mead /yr per pCi/m3 from Table 1.2-1. ,
t ! 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.
(X7Q) = The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary. 3-2
s Qi = 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: D = 3.17 E-8 I Rg [WQg ] t where: . 3.17 x 10 8 = The inverse of the number of seconds in a year. s Q.1
= 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/m 3. W = (DTQ) for the food and ground plane pathways, in meters 2, R. = The dose factor for each identified radionuclide, 'i', in m2 (arem/yr) per 1 pCi/sec or mrem /yr per pCi/m3. R g=Rf[X/Q]+R [D/Q]+Rf[D/Q,X/Q)+R [D/Q,X/Q] + R [D/Q,X/Q] where: Inhalation Pathway Factor, RIg [X/Q] 3 Rf [X/Q] = K'(BR), (DFAg), (mrem /yr per pCi/m ) where: K' = a constant of ur.it conversion, 108 pCi/pci. 3 (BR), = the breathing rate of the receptor of age group (a), in m /yr. The breathing rates (BR) for the various age groups are tabulated below, as given in Regulatory Guide 1.109. i Age Group (a) Breathing Rate (m3/yr) Infant 1400 l Child 3700 l Teen 8000 Adult 8000 3-3 l
I . (DFA g ), = 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 (DFAg ),. See Tables 3.1-6, 3.1-7, 3.1-8, and 3.1-9. Inhalation dose factors (DFA.) for the various age groups are given in Tables 3.1-6, 3.1-7, 3.1-8, an$ 3.1-9 (taken from Regulatory Guide 1.109 (Rev.1)). Ground Plane Pathway Factor, RG [D/Q] 1 R [D/Q] = K'K"(SF)DFG [(1-e i )/A g] (m2 . mrem /yr per pCi/sec) where: K' = a constant of unit conversion, 108 pCi/pCi. K" = a constant of unit conversien, 8760 hr/ year. A f
= the decay constant for the ith radionuclide, sec~1 t = the exposure time, 4.73 x 10s sec (15 years). -
1 DFG g = the ground plane dose conversion factor for the ith radionuclide (mres/hr per pCi/m 2), SF = the shielding factor (dimensionless), 0.7 (Regulatory Guide 1.109 (Rev. 1)). Ground plane dose conversion factors, DFG, are found in Table 3.1-10. Grass-Cow-MilkPathwayFactor,Rf[D/Q] Q (U*) ff P* i'h -A't' Rf[D/Q]=K'E[i,[w F,(r)(DFLg ), (p * + (1-f f )e s . e (m2 . mrem /yr per pCi/sec) where: K' = a constant of unit conversion, 108 pCi/pci. Qp = the cow's consumption rate, in kg/ day (wet weight), 50 (Regulatory Guide 1.109 (Rev. 1)). U = the receptor's milk consumption rate for age (a), in liters /yr. U ap (liters /yr) - Infant 330
- Child 330 -
- Teen 400
- Adult 310 (Reguistory Guide 1.109 (Rev. 1))
3-4
l Y = the agricultural productivity by unit area of pasture feed grass, P in kg/m 2 , o,7, Y = the agricultural productivity by unit area of stored feed, in 8 kg/m 2, 2.0. F, = the stable element transfer coefficients, in days / liter, Table 3.1-11. t = fraction of deposited activity retained on cow's feed grass, r = 1 for radiciodine and r = 0.2 for particulates (Regulatory Guide 1.109). (DFLg ), = 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. A g
= the decay constant for the ith radionuclide, in sec~1 A = the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10 7 sec"1 (corresponding to a 14 day half-life).
t g = the transport time from pasture to cow, to milk, to receptor, in sec, 1.73 x 108 (2 days). - t = the transport time from pasture, to harvest, to cow, to milk, to re-h ceptor, in sec, 7.78 x 10s (90 days). f = fraction of the year that the cow is on pasture (dimensionless), 1.0. f, = 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 radiciodine, E = 1.0 for all others. The concentration of tritium in milk is based n the airborne concentration C rather than the deposition. Therefore, the Rg is based on [X/Ql: 3 R [X/Q] = K'K'"F,Q FU (DFLg ), [0.75(0.5/H)] (mrem /yr per pCi/m ) where: K'" = a constant of unit conversion, 103 gm/kg. H = absolute humidity of the atmosphere, 8 gm/m3 , (Regulatory Guide 1.109) 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. 3-5
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: ff (1-f#8f )e ih Qp (U*) #* -A.t' R [D/Q) = K' g i,[w Ff (r)(DFL ), 7 p
+
s . e (m2 . ares /yr per pCi/sec) where: Fg = the stable element transfer coefficients, in days /kg, Table 3.1-11. U = the receptor's meat consumption rate for age (a), in kg/yr. U 0 ap(kg/yr) - Infant 41
- Child
- Teen 65
- Adult 110 Taken from Regulatory Guide 1.109 (Rev. 1). _.
t g = the transport time from pasture to receptor, in sec. t = the transport time from crop field to receptor, in sec. h The concentration of tritium in meat is base on its airborne concentration rather than the deposition. Therefore, the R' is based on [X/Q]: Q U (DFLg), [0.75(0.5/H)] (mrem /yr per pCi/m3) R'[X/Q] = K'K'"F gp where all terms are defined above. Vegetation Pathway Factor, RVg[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 time period between harvest and consumption, therefore:
-A.t -A.t
(# [fe *
- RY[D/Q)=K' (DFL.)a aL
+ Ufe ag 1 YpA1+ A ) 1
_ J - (m2 mrem /yr per pCi/sec) where: K' = a constant of unit conversion, 108 pCi/pci. b U = the consumption rate of fresh leafy vegetation by the receptor in age group (a), in kg/yr. 3-6
Ub = (kg/hr) - Infant 0
- Child 26
- Teen 42
- Adult 64 S
U, = the consumption rate of stored vegetation by the receptor in age group (a), in kg/yr. US*
= (kg/yr) - Infant 0
- Child 520
- Teen 630
- Adult 520 fg = the fraction of the annual intake of fresh leafy vegetation grown locally, f = the fraction of the annual intake of stored vegetation grown locally.
g t g = the average time between 4 harvest of leafy vegetation and its consumption, in seconds, 8.6 x 10 (1 day). t h = 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/m 2, and all other factors are previously defined. Theconcentrationoftritiuminvegetationisbasepontheairborneconcentra-tion rather than the deposition. Therefore, the R gis based on [X/Q]: 3 R [X/Q] = K'K'" Ufg+Uf g (DFL1 ), [0.75(0.5/H)] (mrem /yr per pCi/m3 ). 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 and reactor makeup water storage tanks. , Dose calculations using this method performed for Duke Nuclear Stations indicate direct radiation doses are much less than 0.01 mrem /yr. and, therefore, makes a negligible contribution to individual dose. Direct radiation doses will not be calculated routinely. 3.2 SIMPLIFIED DOSE PROJECTIONS To estimate the cumulative dose contributions to the maximum exposed individ-ual for 31 day dose projection calculations, the calculations presented in l 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 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. 3-7 Revision 1
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 calcultted to assure that doses are limited to 25 millirems to the total body or an). organ with the exception of the thyroid whien is limited to 75 millirems. Is.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 10CFR5. Table S-3 and WASH-1248, the radiological impact of the following operations has been assessed for Duke Nuclear Stations: 3.3.1 Milling No milling operations occur within fifty miles of any Duke Nuclear Station. The increment of dose from milling operations to any individual within fifty miles of any Duke Nuclear 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 fifty miles of any Duke Nuclear Station is negligible. 3.3.3 Enrichment No uranium enrichment operations occur within fifty. miles of any Duke Nuclear Station. The increment of dose from enrichment operations to any individual within fifty miles of any Duke Nuclear Station is negligible. 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. 3-8 Revision 1
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.:.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 calculations to demonstrate compliance with the requirements of 40CFR190.
~
1 l i l 3-9 Revision 1
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 e Na 1.0E-02 2.0E 02 P 1.0E 05 2.0E 04 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 l Ba 4.0E 00 2.0E 02 j La 2.5E 01 1.0E 03 Ce 1.0E 00 1.0E 03 Pr 2.5E 01 1.0E 03 i Nd 2.5E 01 1.0E 03 W 1.2E 03 1.0E 01 Np 1.0E 01 4.0E 02 l
- Table taken from Regulatory Guide 1.109 (Rev.1)
TABLE 3.1-1 (1 of 1) Revision 1 L
TABLE 3.1-2 (1 of 3) INGESTION DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 , NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 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 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 3.1-2 (1 of 3) Revision 1
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 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 S.I.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-04 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 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 2.9/3-09 NO DATA 2.42E-05 CE 143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR 144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-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 TABLE 3.1-2 (2 of 3)
TABLE 3.1-2 (3 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 RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG 110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE 125M 2.68E-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 i l t i TABLE 3.1-2 (3 of 3) L
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 1.06E-07 1.06E-07 1.06E-07 1.06E-07 H 3 NO DATA 1.06E-07 1.06E-07 NA 24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P 32 2.76E-04 1.71E-05 1.07E-05 NO DATA NO DATA NO DATA 2.32E-05 CR 51 NO DATA NO DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN 54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 MN 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 NO DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 CO 58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 CO 60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 NI 63 1.77E-04 1.25E-05 6.00E-06 NO DATA NO DATA NO DATA 1.99E-06 NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-07 CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 -- ZN 65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ZN 69 1.47E-08 2.80E-08 1.96E-09 NO DATA 1.83E-08 NO DATA 5.16E-08 BR 83 NO DATA NO DATA 5.74E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 7.21E-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 4.93F-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 S.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) l l TABLE 3.1-3 l (1 of 3)
Revision 1
TABLE 3.1-3 (cont'd) (2 of 3) INGESTION DOSE FACTORS FOR TEENAGER (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T.B0DY THYROID KIDNEY LUNG GI-LLI Y 93 3.83E-09 NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 ZR 95 4.12E-08 1.30E-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 TC101 3.60E-10 5.12E-10 5.03E-09 NO DATA 9.26E-09 3.12E-10 8.75E-18 RU103 2.55E-07 NO DATA 1.09E-07 NO DATA 8.99E-07 NO DATA 2.13E-05 RU105 2.18E-08 NO DATA 8.46E-09 NO DATA 2.75E-07 NO DATA 1.76E-05 RU106 3.92E-06 NO DATA 4.94E-07 NO DATA 7.56E-06 NO DATA 1.88E-04 AG110M 2.05E-07 1.94E-07 1.18E-07 NO DATA 3.70E-07 NO DATA 5.45E-05 TE125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 NO DATA NO DATA 1.13E-05 TE127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05 -- TE127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 NO DATA 1.22E-05 TE129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 NO DATA 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 NO DATA 2.45E-07 TE131M 2.44E-06 1.17E-06 9.76E-07 1.76F-06 1.22E-05 NO DATA 9.39E-05 TE131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 NO DATA 2.29E-09 TE132 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-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 NO DATA 3.18E-07 I 133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 NO DATA 2.58E-06 i 1.14 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 CS134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 CS136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1.84E-05 2.90E-06 2.72E-06 CS137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 CS138 7.76E-08 1.49E-07 7.45E-08 NO DATA 1.10E-07 1.28E-08 6.76E-11 BA139 1.39E-07 9.78E-11 4.05E-09 NO DATA 9.22E-11 6.74E-11 1.24E-06 TABLE 3.1-3 (2 of 3)
TABLE 3.1-3 (cont'd) (3 of 3) INGESTION DOSE FACTORS FOR TEENAGER (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI BA140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 BA141 6.71E-08 5.01E-11 2.24E-08 NO DATA 4.65E-11 3.43E-11 1.43E-13 BA142 2.99E-08 2.99E-11 1.84E-09 NO DATA 2.53E-11 1.99E-11 9.18E-20 LA140 3.48E-09 1.71E-09 4.55E-10 NO DATA NO DATA NO DATA 9.82E-05 LA142 1.79E-10 7.95E-11 1.98E-11 NO DATA NO DATA NO DATA 2.42E-06 CElal 1.33E-08 8.88E-09 1.02E-09 NO DATA 4.18E-09 NO DATA 2.54E-05 CE143 2.35E-09 1.71E-06 1.91E-10 NO DATA 7.67E-10 NO DATA 5.14E-05 CD144 6.96E-07 2. 88E-07 3.74E-08 NO DATA 1.72E-07 NO DATA 1.75E-04 PR143 1.31E-03 5.23E-09 6.52E-10 NO DATA 3.04E-09 NO DATA 4.31E-05 PR144 4.30E-11 1.76E-11 2.18E-12 NO DATA 1.01E-11 NO DATA 4.74E-14 ND147 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 NP239 1.76E-09 1.66E-10 9.22E-11 NO DATA 5.21E-10 NO DATA 2.67E-05 - 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 i NA 24 5.80E-06 5.80E-06 5.80E 5.80E-06 5.80E-06 5.80E-06 5.80E-06 I P 32 8.2SE-04 3.86E-05 3.18E-05 NO DATA NO DATA NO DATA 2.28E-05 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 '6 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-]6 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 CP 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 NI 65 2.22E-06 2.09E-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 NO DATA 1.15E-05 - ZN 65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ZN 69 4.38E-08 6.33E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA 1.71E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.98E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 9.12E-09 NO DATA NO DATA 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 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
*Taken from Regulatory Guide 1.109 (Rev. 1). ,
TABLE 3.1-4 (1 of 3) Revision 1
TABLE 3.1-4 (cont'd) (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 TC101 1.07E-09 1.12E-09 1.42E-08 NO DATA 1.91E-08 5.92E-10 3.56E-09 RU103 7.31E-07 NO DATA 2.81E-07 NO DATA 1.84E-06 NO DATA 1.89E-05 RU105 6.45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.21E-05 RU106 1.17E-05 NO DATA 1.46E-06 NO DATA 1.58E-05 NO DATA 1.82E-04 AG110M 5.39E-07 3.84E-07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.10E-05 TE127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 NO DATA 2.34E-05 - TE127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 NO DATA 1.84E-05 TE129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 NO DATA 8.34E-06 TE131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 NO DATA 1.01E-04 TE131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 i TE132 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 CS134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 CS136 2.35E-05 6.46E-05 4.18E-05 NO DATA 3.44E-05 5.13E-06 2.27E-06 CS137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.01E-07 NO DATA 2.23E-07 2.40E-08 1.46E-07 BA139 4.14E-07 2.21E-10 1.20E-08 NO DATA 1.93E-10 1.30E-10 2.39E-05 l l
- TABLE 3.1-4 l
(2 of 3)
TABLE 3.1-4 (3 of 3) INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI BA140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 BA141 2.00E-07 1.12E-10 6.51E-09 NO DATA 9.69E-11 6.58E-10 1.14E-07 BA142 8.74E-08 6.29E-11 4.88E-09 NO DATA 5.09E-11 3.70E-11 1.14E-09 LA140 1.01E-08 3.53E-09 1.19E-09 NO DATA NO DATA NO DATA 9.84E-05 LA142 5.24E-10 1.67E-10 5.23E-11 NO DATA NO DATA NO DATA 3.31E-05 CE141 3.97E-08 1.98E-08 2.94E-09 NO DATA 8.68E-09 NO DATA 2.47E-05 CE143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1.59E-09 NO DATA 5.55E-05 CE144 2.08E-06 6.52E-07 1.11E-07 NO DATA 3.61E-07 NO DATA 1.70E-04 PR143 3.93E-08 1.18E-08 1.95E-09 NO DATA 6.39E-09 NO DATA 4.24E-05 PR144 1.29E-10 3.99E-11 6.49E-12 NO DATA 2.11E-11 NO DATA 8.59E-08 ND147 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 NP239 5.25E-09 3.77E-10 2.65E-10 NO DATA 1.09E-09 NO DATA 2.79E-05 - i TABLE 3.1-4 (3 of 3)
TABLE 3.1-5* (1 of 3) INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 -, NA 24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P 32 1.70E-03 1.00E-04 6.59E-05 NO DATA NO DATA NO DATA 2.30E-05 CR 51 NO DATA NO DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MN 54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 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 DAIA 1.59E-05 2.57E-05 CO 58 NO DATA 3.60E-06 8.93E-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 S0 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 BF 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 S.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04
*1aken from Regulatory Guide 1.109 (Rev. 1)
TABLE 3.1-5 (1 of 3) Revision 1
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-08 NO DATA 1.46E-05 MO 99 NO DATA 3.40E-05 6.63E-06 NO DATA 5.08E-05 NO DATA 1.12E-05 TC 99M 1.92E-09 3.96E-09 5.10E-08 NO DATA 4.26E-08 2.07E-09 1.15E-06 TC101 2.27E-09 2.86E-00 2.83E-08 NO DATA 3.40E-08 1.56E-09 4.86E-07 RU103 1.48E-06 NO DATA 4.95E-07 NO DATA 3.08E-06 NO DATA 1.80E-05 RU105 1.36E-07 NO DATA 4.58E-08 NO DATA 1.00E-06 NO DATA 5.41E-05 RU106 2.41E-05 NO DATA 3.01E-06 NO DATA 2.85E-05 NO DATA 1.83E-04 AG110M 9.96E-07 7.27E-07 4.81E-07 NO DATA 1.04E-06 NO DATA 3.77E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 NO DATA NO DATA 1.11E-05 5.85E-05 1.94E-05 7.08E-06 TE127M 1.69E-05 1.44E-04 NO DATA 2.36E-05 - TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 NO DATA 2.27E-05 TE131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04 TE131 1.7eE-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 NO DATA 7.11E-06 TE132 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 CS134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 CS136 4.59E-05 1.35E-04 5.04E-05 NO DATA 5.38E-05 1.10E-05 2.05E-06 CS137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 CS138 4.81E-07 7.82E-07 3.79E-07 NO DATA 3.90E-07 6.09E-08 1.25E-06 < BA139 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)
TABLE 3.1-5 , (3 of 3) INGESTION DOSE FACTORS FOR INFANT (MREM PEP. PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI BA140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 BA141 4.25E-07 2.91E-10 1.34E-08 NO DATA 1.75E-10 1.77E-10 5.19E-06 BA142 1.84E-07 1.53E-10 9.06E-09 NO DATA 8.81E-11 9.26E-11 7.59E-07 LA140 2.11E-08 8.32E-09 2.14E-09 NO DATA NO DATA NO DATA 9.77E-05 LA142 1.10E-09 4.04E-10 9.67E-11 NO DATA NO DATA NO DATA 6.86E-05 CE141 7.87E-08 4.80E-OS 5.65E-09 NO DATA 1.48E-08 NO DATA 2.48E-05 CE143 1.48E-08 9.82E-06 1.12E-09 NO DATA 2.86E-09 NO DATA 5.73E-05 CE144 2.98E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.71E-04 PR143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E-05 PR144 2.74E-10 1.06E-10 1.38E-11 NO DATA 3.84E-11 NO DATA 4.93E-06 ND147 5.53E-08 5.68E-08 3.48E-09 NO DATA 2.19E-08 NO DATA 3.60E-05 W 187 9.03E-07 6.28E-07 2.17E-07 NO DATA NO DATA NO DATA 3.69E-05 NP239 1.11E-08 9.93E-10 5.61E-10 NO DATA 1.98E-09 NO DATA 2.87E-05 _. I i .l TABLE 3.1-5 (3 of 3)
TABLE 3.1-6* (1 of 3) INHALATION DOSE FACTORS FOR ADULTS (MREM PER PCI INHALED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58f-07 1.58E-07 _ NA 24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.26E-06 1.28E-06 P 32 1.65E-04 9.64E-06 6.26E-06 NO DATA NO DATA NO DATA 1.08E-05 CR 51 NO DATA NO DATA 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN 54 NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.75E-04 9.67E-06 MN 56 NO DATA 1.55E-10 2.29F.-11 NO DATA 1.63E-10 1.18E-06 2.53E-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 CO 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.S6E-05 NI 63 5.40E-05 3.93E-06 1.81E-06 NO DATA NO DATA 2.23E-05 1.67E-06 NI 65 1.92E-10 2.62E-11 1.14E-11 NO DATA NO DATA 7.00E-07 1.54E-06 _ CU 64 NO DATA 1.83E-10 7.69E-11 NO DATA 5.78E-10 8.48E-07 6.12E-06 ZN 65 4.05E-06 1.29E-05 5.82E-06 NO DATA 8.62E-06 1.08E-04 6.68E-06 ZN 69 4.23E-12 8.14E-12 5.65E-13 NO DATA 5.27E-12 1.15E-07 2.04E-09 BR 83 NO DATA NO DATA 3.01E-08 NO DATA NO DATA NO DATA 2.90E-08 BR 84 NO DATA NO DATA 3.91E-08 NO DATA NO DATA NO DATA 2.05E-13 BR 85 NO DATA NO DATA 1.60E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.69E-05 7.37E-06 NO DATA NO DATA NO DATA 2.08E-06 RB 88 NO DATA 4.84E-08 2.41E-08 NO DATA NO DATA NO DATA 4.18E-19 RB 89 NO DATA 3.20E-08 2.12E-03 NO DATA NO DATA NO DATA 1.16E-21 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 SR 91 7.74E-09 NO DATA 3.13E-10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43E-10 NO DATA 3.64E-11 NO DATA NO DATA 2.06E-06 5.38E-06 Y 90 2.61E-07 NO DATA 7.01E-09 NO DATA NO DATA 2.12E-05 6.32E-05 Y 91M 3.26E-11 NO DATA 1.27E-12 NO DATA NO DATA 2.40E-07 1.66E-10 Y 91 5.78E-05 NO DATA 1.55E-06 NO DATA NO DATA 2.13E-04 4.81E-05 Y 92 1.29E-09 NO DATA 3.77E-11 NO DATA NO DATA 1.96E-06 9.19E-06
*Taken f rom Regulatory Guide 1.109 (Rev. 1)
TABLE 3.1-6 (1 of 3) Revision 1
TABLE 3.1-6 (2 of 3) INHALATION DOSE FACTORS FOR ADULTS (MREM PER PCI INHALED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI Y 93 1.18E-08 NO DATA 3.26E-10 NO DATA NO DATA 6.06E-06 5.27E-05 ZR 95 1.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.21E-04 1.88E-05 ZR 97 1.21E-08 2.45E-09 1.13E-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 NB 95 1.76E-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 MO 99 NO DATA 1.51E-Od 2.87E-09 NO DATA 3.64E-08 1.14E-05 3.10E-05 TC 99M 1.29E-13 3.64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07 TC 101 5.22E-15 7.a2Ee15 7.38E-14 NO DATA 1.35E-13 4.99E-08 1.36E-21 RU 103 1.91E-07 NO DATA 8.23E-08 NO DATA 7.29E-07 6.31E-05 1.38E-05 RU 105 9.88E-11 NO DATA 3.89E-11 NO DATA 1.27E-10 1.37E-06 6.02E-06 RU 106 8.64E-06 NO DATA 1.09E-06 NO DATA 1.67E-05 1.17E-03 1.14E-04 aG 110M 1.35E-06 1.25E-06 7.43E-07 NO DATA 2.46E-06 5.79E-04 3.78E-05 TE 125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06
~
TE '../M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 T', 127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06
' E 129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE 129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 TE 131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE 131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 TE 132 3.2SE-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I 130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 NO DATA 9.61E-07 I 131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07 I 132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 NO DATA 5.08E-08 I 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 1.11E-06 I 134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 NO DATA 1.26E-10 I 135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 NO DATA 6.56E-07 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-04 1.50E-06 1.46E-06 CS 137 5.98E-05 7.76E-05 5.35E-05 NO DATA 2.78E-05 9.40E-06 1.05E-06 CS 138 4.14E-08 7.76E-08 4.05E-08 NO DATA 6.00E-08 6.07E-09 2.33E-13 BA 139 1.17E-10 8.32E-14 3.42E-12 NO DATA 7.78E-14 4.70E-07 1.12E-07 TABLE 3.1-6 (2 of 3)
TABLE 3.1-6 (3 of 3) INHALATION DOSE FACTORS FOR ADL7.TS (MREM PER PCI INHALED) NUCLIDE BONE LIVER T.B0DY THYROID KIDNEY LUNG GI-LLI BA 140 4.88E-06 6.13E-09 3.21E-07 NO DATA 2.09E-09 1.59E-04 2.73E-05 BA 141 1.25E-11 9.14E-15 4.20E-13 NO DATA 8.75E-15 2.42E-07 1.45E-17 BA 142 3.29E-12 3.38E-15 2.07E-13 NO DATA 2.86E-15 1.49E-07 1.96E-26 LA 140 4.30E-08 2.17E-08 5.73E-09 NO DATA NO DATA 1.70E-05 5.73E-05 LA 142 8.54E-11 3.88E-11 9.65E-12 NO DATA NO DATA 7.91E-07 2.64E-07 CE 141 2.49E-06 1.69E-06 1.91E-07 NO DATA 7.83E-07 4.52E-05 1.50E-05 CE 143 2.33E-08 1.72E-08 1.91E-09 NO DATA 7.60E-09 9.97E-06 2.83E-05 CE 144 4.29E-04 1.79E-04 2.30E-05 NO DATA 1.06E-04 9.72E-04 1.02E-04 PR 143 1.17E 4.69E-07 5.80E-08 NO DATA 2.70E-07 3.51E-05 2.50E-05 PR 144 3.76E-12 1.56E-12 1.91E-13 NO DATA 8.81E-13 1.27E-07 2.69E-18 ND 141 6.59E-07 7.62E-07 4.56E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05 W 187 1.06E-09 8.85E-10 3.10E-10 NO DATA NO DATA 3.63E-06 1.94E-05 NP 239 2.87E-08 2.82E-09 1.55E-09 NO DATA 8.75E-09 4.70E-06 1.49E-05 l l 4 i TABLE 3.1-6 (3 of 3)
TABLE 3.1-7* (1 of 3) 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 . NA 24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P 32 2.36E-04 1.37E-05 8.95E-06 NO DATA NO DATA NO DATA 1.16E-05 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 MN 56 NO DATA 2.12E-10 3.15E-11 NO DATA 2.24E-10 1 90E-06 7.18E-06 FE 55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-07 FE 59 1.99E-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 C0 58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 C0 60 NO DATA 1.89E-06 2.48E-06 NO DATA NO DATA 1.09E-03 3.24E-05 NI 63 7.25E-05 5.43E-06 2.47E-06 NO DATA NO DATA 3.84E-05 1.77E-06 NI 65 2.73E-10 3.66E-11 1.59E-11 NO DATA NO DATA 1.17E-06 4.59E-06 - CU 64 NO DATA 2.54E-10 1.06E-10 NO DATA 8.01E-10 1.39E-06 7.68E-06 ZN 65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06 ZN 69 6.04E-12 1.15E-11 8.07E-13 NO DATA 7.53E-12 1.98E-07 3.56E-08 BR 83 NO DATA NO DATA 4.30E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 5.41E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 2.29E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.38E-05 1.05E-05 NO DATA NO DATA NO DATA 2.21E-06 RB 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 RB 89 NO DATA 4.40E-08 2.91E-08 NO DATA NO DATA NO DATA 4.22E-17 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 SR 31 1.10E-08 NO DATA 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05 SR 92 1.19E-09 NO DATA 5.08E-11 NO DATA NO DATA 3.43E-06 1.49E-05 Y 90 3.73E-07 NO DATA 1.00E-08 NO DATA NO DATA 3.66E-05 6.99E-05 Y 91M 4.63E-11 NO DATA 1.77E-12 NO DATA NO DATA 4.00E-07 3.77E-09 Y 91 8.26E-05 NO DATA 2.21E-06 NO DATA NO DATA 3.67E-04 5.11E-05 Y 92 1.84E-09 NO DATA 5.36E-11 NO DATA NO DATA 3.35E-06 2.06E-05
*Taken from Regulatory Guide 1.109 (Rev. 1)
TABLE 3.1-7 (1 of 3) Revision 1
TABLE 3.1-7 (2 of 3) INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI Y 93 1.69E-08 NO DATA 4.65E-10 NO DATA NO DATA 1.04E-05 7.24E-05 ZR 95 1.82E-05 5.73E-06 3.94E-06 NO DATA 8.43E-06 3.36E-04 1.86E-05 ZR 97 1.72E-08 3.40E-09 1.57E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05 NP 95 2.32E-06 1.29E-06 7.08E-07 NO DATA 1.25E-06 9.39E-05 1.21E-05 MO 99 NO DATA 2.11E-08 4.03E-09 NO DATA 5.14E-08 1.92E-05 3.36E-05 TC 99M 1.73E-13 4.83E-13 6.24E-12 NO DATA 7.20E-12 1.44E-07 7.66E-07 TC 101 7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 RU 103 2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-07 1.36E-05 RU 105 1.40E-10 NO DATA 5.42E-11 NO DATA 1.76E-10 2.27E-06 1.13E-05 RU 106 1.23E-05 NO DATA 1.55E-06 NO DATA 2.38E-05 2.01E-03 1.20E04 AG 110M 1.73E-06 1.64E-06 9.99E-07 NO DATA 3.13E-06 8.44E-04 3.41E-05 _ TE 125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 NO DATA 6.70E-05 9.38E-06 TE 127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE 127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 TE 129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE 129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TE 131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE 131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE 132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I 130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 NO DATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11E-07 I 132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA 1.59E-07 I 133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1.29E-06 I 134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09 I 135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 NO DATA 8.69E-07 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 CS 138 5.82E-08 1.07E-07 5.58E-08 NO DATA 8.28E-08 9.84E-09 3.38E-11 i BA 139 1.67E-10 1.18E-13 4.87E-12 NO DATA 1.11E-13 8.08E-07 d.06E-07 l l l i IABLE 3.1-7 (2 of 3)
i
. \
i TABLE 3.1-7 (3 of 3) INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI BA 140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 2.86E-05 BA 141 1.78E-11 1.32E-14 5.93E-13 NO DATA 1.23E-14 4.11E-07 9.33E-14 BA 142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99E-20 LA 140 5.99E-08 2.95E-08 7.82E-09 NO DATA NO DATA 2.68E-05 6.09E-05 LA 142 1.20E-10 5.31E-11 1.32E-11 NO DATA NO DATA 1.27E-06 1.50E-06 CE 141 3.55E-06 2.37E-06 2.71E-07 NO DATA 1.11E-06 7.67E-05 1.58E-05 CE 143 3.32E-08 2.42E-08 2.70E-09 NO DATA 1.08E-08 1.63E-05 3.19E-05 CE 144 6.11E-04 2.53E-04 3.28E-05 NO DATA 1.51E-04 1.67E-03 1.08E-04 PR 143 1.67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 PR 144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14 ND 147 9.83E-07 1.07E-06 6.41E-08 NO DATA 6.28E-07 4.65E-05 2.28E-05 ~ W 187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21E-05 NP 239 4.23E-08 3.99E-09 2.21E-09 NO DATA 1.25E-08 8.11E-06 1.65E-05 TABLE 3.1-7 (3 of 3)
TABLE 3.1-8* l (1 of 3) 1 INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED) NUCLIDE BONE LIVER T.B0DY 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 _ NA 24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-05 4.35E-06 P 32 7.04E-04 3.09E-05 2.67E-05 NO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA NO DATA 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 MN 54 NO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19E-06 MN 56 NO DATA 4.48E-10 8.43E-11 NO DATA 4.52E-10 3.55E-06 3.33E-05 FE 55 1.28E-05 6.80E-06 2.10E-06 NO DATA NO DATA 3.00E-05 7.75E-07 FE 59 5.59E-06 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 CO 58 NO DATA 4.79E-07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05 NI 63 2.22E-04 1.25E-05 7.56E-06 NO DATA NO DATA 7.43E-05 1.71E-06 _ NI 65 8.08E-10 7.99E-11 4.44E-11 NO DATA NO DATA 2.21E-06 2.27E-05 CU 64 NO DATA 5.39E-10 2.90E-10 NO DATA 1.605-09 2.59E-06 9.92E-06 IN 65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 ZN 69 1.81E-11 2.61E-11 2.41E-12 NO DATA 1.58E-11 3.84E-07 2.75E-06 BR 83 NO DATA NO DATA 1.28E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.48E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 5.36E-05 3.09E-05 NO DATA NO DATA NO DATA 2.16E-06 RB 88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 RB 89 NO DATA 9.33E-08 7.83E-03 NO DATA NO DATA NO DATA 5.11E-10 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 SR 91 3.28E-08 NO DATA 1.24E 09 NO DATA NO DATA 1.44E-05 4.70E-05 SR 92 3.54E-09 NO DATA 1.42E-10 NO DATA NO DATA 6.49E-06 6.55E-05 Y 90 1.11E-06 NO DATA 2.99E-08 NO DATA NO DATA 7.07E-05 7.24E-05 Y 91M 1.37E-10 NO DATA 4.98E-12 NO DATA NO DATA 7.60E-07 4.64E-07 Y 91 2.47E-04 NO DATA 6.59E-06 NO DATA NO DATA 7.10E-04 4.97E-05 Y 92 5.50E-09 NO DATA 1.57E-10 NO DATA NO DATA 6.46E-06 6.46E-05
*Taken From Regulatory Guide 1.109 (Rev. 1)
TABLE 3.1-8 (1 of 3) Revision 1
TABLE 3.1-8 (2 of 3) INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED) NUCLIDE BONE LIVER T.B0DY THYROID KIDNEY LUNG GI-LLI Y 93 5.04E-08 NO DATA 1.38E-09 NO DATA NO DATA 2.01E-05 1.05E-04 ZR 95 5.13E-05 1.13E-05 1.00E-05 NO DATA 1.61E-05 6.03E-04 1.65E-05 ZR 97 5.07E-08 7.34E-09 4.32E-09 NO DATA 1.05E-08 3.06E-05 9.49E-05 NB 95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 1.00E-05 MO 99 NO DATA 4.66E-08 1.15E-08 NO DATA 1.06E-07 3.66E-05 3.42E-05 TC 99M 4.81E-13 9.41E-13 1.56E-11 NO DATA 1.37E-11 2.57E-07 1.30E-06 TC101 2.19E-14 2.30E-14 2.91E-13 NO DATA 3.92E-13 1.58E-07 4.41E-09 RU103 7.55E-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-05 RU105 4.13E-10 NO DATA 1.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 RU106 3.68E-05 NO DATA 4.57E-06 NO DATA 4.97E-05 3.87E-03 1.16E-04 AG110M 4.56E-06 3.08E-06 2.47E-06 NO DATA 5.74E-06 1.48E-03 2.71E-05 TE125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 _ TE127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 TE127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 TE129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 TE129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 TE131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 TE132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I 130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 NO DATA 1.38E-06 I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 NO DATA 7.68E-07 I 132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07 I 133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 NO DATA 1.48E-06 I 134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 I 135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 NO DATA 1.20E-06 l CS134 1.76E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 l CS136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 CS137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 CS138 1.71E-07 2.27E-07 1.50E-07 NO DATA 1.68E-07 1.84E-08 7.29E-08 BA139 4.98E-10 2.66E-13 1.45E-11 NO DATA 2.33E-13 1.56E-06 1.56E-05 TABLE 3.1-3 (2 of 3)
TABLE 3.1-8 (3 of 3) INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED) NUCLIDE BONE LIVER T. BODY fHYROID KIDNEY LUNG GI-LII BA140 2.00E-05 1.75E-08 1.17E-06 NO DATA 5.71E-09 4.71E-04 2.75E-05 BA141 5.29E-11 2.95E-14 1.72E-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 BA142 1.35E-11 9.73E-15 7.54E-13 NO DATA 7.87E-15 4.44E-07 7.41E-10 LA140 1.74E-07 6.08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05 LA142 3.50E-10 1.11E-10 3.49E-11 NO DATA NO DATA 2.35E-06 2.05E-05 CE141 1.06E-05 5.28E-06 7.83E-07 NO DATA 2.31E-06 1.47E-04 1.53E-05 CE143 9.89E-08 5.37E-08 7.77E-09 NO DATA 2.26E-08 3.12E-05 3.44E-05 CE144 1.83E-03 5.72E-04 9.77E-05 NO DATA 3.17E-04 3.23E-03 1.05E-04 PRi43 4.99E-06 1.50E-06 2.47E-07 NO DATA 8.11E-07 1.17E-04 2.63E-05 PR144 1.61E-11 4.99E-12 8.10E-13 NO DATA 2.64E-12 4.23E-07 5.32E-08 ND147 2.92E-06 2.36E-06 1.84E-07 NO DATA 1.30E-06 8.87E-05 2.22E-05 W 187 4.42E-09 2.61E-09 1.17E-09 NO DATA NO DATA 1.11E-05 2.46E-05 _ NP239 1.26E-07 9.04E-09 6.35E-09 NO DATA -2.63E-08 1.57E-05 1.73E-05 l l l TABLE 3.1-8 (3'of 3)
TABLE 3.1-9* (1 of 3) INHALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED) NUCLIDE B0NE LIVER T. BODY THYROID KIDNEY LUNG GI-LII H 3 NO DATA 4.62E-07 4.62E-07 3.62E-07 4.62E-07 4.62E-07 4.62E-07 _ NA 24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P 32 1.45E-03 8.03E-05 5.53E-05 NO DATA NO DATA NO DATA 1.15E-05 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 MN 56 NO DATA 1.10E-09 1.58E-10 NO DATA 7.86E-10 8.95E-06 5.12E-05 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 NI 63 2.42E-04 1.46E-05 8.29E-06 NO DATA NO DATA 1.49E-04 1.73E-06
~
NI 65 1.71E-09 2.03E-10 8.79E-11 NO DATA NO DATA 5.80E-06 3.58E-05 CO 64 NO DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 ZN 65 1.38E-05 4.47E-05 2.22E-05 NO DATA 2.32E-05 4.62E-04 3.67E-05 ZN 69 3.85E-11 6.91E-11 5.13E-12 NO DATA 2.87E-11 1.05E-06 9.44E-06 BR 83 NO DATA NO DATA 2.72E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 2.86E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 1.46E-08 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 RB 88 NO DATA 3.98E-07 2.05E-07 NO DATA NO DATA NO DATA 2.42E-07 RB 89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 . SR 89 2.84E-04 NO DATA 8.15E-06 NO DA7 A NO DATA 1.45E-03 4.57E-05 l SR 90 2.92E-02 NO DATA 1.85E-03 NO D/TA NO DATA 8.03E-03 9.36E-05 l SR 91 6.83E-08 NO DATA 2.47E-09 60 DATA NO DATA 3.76E-05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E-10 NO DATA NO DATA 1.70E-05 1.00E-04 l Y 90 2.35E-06 NO DATA 6.30E-08 NO DATA NO DATA 1.92E-04 7.43E-05 l l Y 91M 2.91E-10 NO DATA 9.90E-12 NO DATA NO DATA 1.99E-06 1.68E-06 Y 91 4.20E-04 NO DATA 1.12E-05 NO DATA NO DATA 1.75E-03 5.02E-05 Y 92 1.17E-08 NO DATA 3.29E-10 NO DATA NO DATA 1.75E-05 9.04E-05 l l l
*Taken from Regulatory Guide 1.109 (Rev. 1)
TABLE 3.1-9 (1 of 3) i Revision 1 i t
. s TABLE 3.1-9 (2 of 3) INHALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED) NUCLIDE BONE LIVER T.B0DY THYROID KIDNEY LUNG GI-LII Y 93 1.07E-07 NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-04 ZR 95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05 ZR 97 1.07E-07 1.83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1.00E-04 NB 95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 MO 99 NO DATA 1.18E-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3.48E-05 TC 99M 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06 TC101 4.65E-14 5.88E-14 5.80E-13 NO DATA 6.99E-13 4.17E-07 6.03E-07 RU103 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05 RU105 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E-10 1.12E-05 3.46E-05 RU106 6.20E-05 NO DATA 7.77E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04 AG110M 7.13E-06 5.16E-06 3.57E-06 NO DATA 7.80E-06 2.62E-03 2.36E-05 TE125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06 _ TE127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 TE131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 I 131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 I 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1.36E-06 I 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 1.54E-06 I 134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21E-07 I 135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 NO DATA 1.31E-06 CS134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 CS136 3.45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 CS137 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07 CS138 3.61E-07 5.58E-07 2.84E-07 NO DATA 2.93E-07 4.67E-08 6.26E-07 BA139 1.06E-09 7.03E-13 3.07E-11 NO DATA 4.23E-13 4.25E-06 3.64E-05 TABLE 3.1-9 (2 of 3)
. l TABLE 3.1-9 (3 of 3)
INHALATION DOSE FACTORS FOR IhTANT (MREM PER PCI INIIALED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LII BA140 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 BA141 1.12E-10 7.70E-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 BA142 2.84E-11 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.11E-06 4.95E-07 LA140 3.61E-07 1.43E-07 3.68E-08 NO DATA NO DATA 1.20E-04 6.06E-05 LA142 7.36E-10 2.69E-10 6.46E-11 NO DATA NO DATA 5.87E-06 4.25E-05 CE141 1.98E-05 1.19E-05 1.42E-06 NO DATA 3.75E-06 3.69E-04 1.54E-05 CE143 2.98E-07 1.38E-07 1.58E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 CE144 2.28E-03 8.65E-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04 PR143 1.00E-05 3.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.66E-05 PR144 3.42E-11 1.32E-11 1.72E-12 NO DATA 4.80E-12 1.15E-06 3.06E-06 ND147 5.67E-06 5.81E-06 3.57E-07 NO DATA 2.25E-06 2.30E-04 2.23E-05 W 187 9.26E-09 6.44E-09 2.23E-09 NO DATA NO DATA 2.83E-05 2.54E-05 NP239 2.65E-07 2.37E-08 1.34E-08 NO DATA 4.73E-08 4.25E-05 1.78E-05 l l l 1 l i l l TABLE 3.1-9 (3 of 3)
TABLE 3.1-10* (1 of 2) EXTERNAL DOSE FACTOR 5. FOR STANDING ON CONTAMINATED GROUND (arem/hr per pCi/m2) Element Total Body Skin H-3 0.0 0.0 -{ NA-24 2.50E-08 2.90E-08 i P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 i Mn-54 5.80E-09 6.80E-09 i 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 Be-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 l 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 Z.-97 5.50E-09 6.40E-09 Nb->5 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 l Ag-110M 1.80E-08 2.10E-08 l Te-125M 3.50E-11 4.80E-11 i 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 l
*Taken from Regulatory Guide 1.109 (Rev. 1)
TABLE 3.1-10 (1 of 2) j Revision 1 L
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 Table 3.1-10 (2 of 2)
TABLE 3.1-11* (1 of 1) STABLE ELEMENT TRANSFER DATA F,(Cow) Fg Element Milk (d/2) Meat (d/kg) H 1.0E-02 1.2E-02 _ Na 4.0E-02 3.0E-02 P 2.5E-02 4.6E-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 2.8E-01 Nb 2.5E-03 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 f rom Regulatory Guide 1.109 (Rev. 1)
F, for goat is 6.0E-2. TABLE 3.1-11 (1 of 1) Revision 1
j 3 l APPENTIX B - MCGUIRE NUCLEAR STATION SITE SPECIFIC INFORMATION
a .,ame,
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APPENDIX B - TABLE OF CONTENTS , P_ajte Bl.0 MCGUIRE NUCLEAR STATION RADWASTE SYSTEMS B-1 B2.0 RELEASE RATE CALCULATION B-4 B3.0 RADIATION MONITOR SETPOINTS B-8 lB4.0 DOSE CALCULATIONS B-11 f lB5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING B-14 l P i i I i i Revision 1 l
1 l l Bl.0 MCGUIRE NUCLEAR STATION RADWASTE SYSTEMS Bl.1 LIQUID RADWASTE PROCESSING The liquid radwaste system at McGuire Nuclear Station (MNS) is used to collect and treat fluid chemical and radiochemical by products of unit operation. The system produces effluents which can be reused in the plant or discharged in small, dilute quantities to the environment. The means of treatment vary with waste type and desired product in the various systems: A) Filtration - 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) Adsception - 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 af ter 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 reactor bleed. D) Gas Stripping - Removal of gaseous radioactive fission products is accomplished in both the WL Evaporator and the NB Evaporator. E) Distillation - Production of pure water from the waste by boiling it away from the contaminated solution which originally contained it is accomplished by both evaporators. Proper control of the process will yield water which can be reused for makeup. Polishing of this product can be achieved by ion exchange as pointed out above. F) Concentration - In both the WL and NB Evaporators, dissolved chemicals are concentrated in the lower shell as water is boiled away. In the case of the WL Evaporator, the volume of water containing waste chemicals and radioactive cations is reduced so that the waste may be more easily and cheaply solidified and shipped for burial. In the NB Evaporator, the dilute boron is concentrated to 4* so that it may be reused for makeup to the reactor coolant system. Figure Bl.0-1 is a schematic representation of the liquid radwaste system at McGuire. i B-1
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Bl.2 GASEOUS RADWASTE SYSTEMS The gaseous waste disposal system for McGuire is designed with the capability of processing the fission-prcduct gases from contaminated reactor coolant fluids resulting from operation. The system shown schematically in Fig. Bl.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 elimi-nate 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. Bl.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. Bl.2.2 Containment and Auxiliary Building Ventilation Nonrecyclable reactor coolant leakage occurring either inside the containment or inside the auxiliary building will generate gaseous activity. Gases result-ing from leakage inside the containment will be contained until the containment is purged. The containment atmosphere will be circulated through a charcoal adsorber and a particulate filter prior to release to the atmosphere. I Gases resulting from leakage inside the 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 passed through charcoal adsorbers to reduce releases to the atmosphere. Bl.2.3 Secondary Systems l i ! When activity is in the secondary system, steam generator blowdown will be ! recycled through demineralizers to remove activity and the liquids will be removed by the ejector condenser prior to discharge to the unit vent. l B-2
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INTERNAftONAL REClRCULATING TRAtr.S (2, CONTAINMENT VENTILATTON SYSTEMS (2) 3.000 sem EACM , agga i Ups POTENTI A L g4,coe ,,. p_ CO86TAMINATION P A C OUTSsos AIR AREA PER UNIT OTHER AREAS / AuxlLI AR Y PER uMIT M LEGENO SULLDING P PRE 7tLTER AN5 AUXtWARY TUILDING SYSTEM (SHAREDI
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1 r-Gland leak-off steam, which represents a minor source of activity, is routed to the gland condenser. ' The non-condensable gases are passed through a vent stack to the roof; the condensables are condensed and drained to the condensate storage tank. l . . i T i f 3 { B-3
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r TABLE Bl.0-1 (1 of 2) ABBREVIATIONS Systems: KC - Component Cooling NB - Boron Recycle NC - Reactor Coolant ND - Residual Heat Removal NI - Safety Injection NR - Boron Thermal Regeneration NV - Chemical Volume and Control WC - Conventional Waste Water Treatment WG - Waste Gas WL - Liquid Waste Recycle _ WM - Liquid Waste Monitor and Disposal WS - Nuclear Solid Waste Disposal Terms: BOL - Beginning of Core Life BTRS - Boron Thermal Regeneration System CCW - Condenser Cooling Water CDT - Chemical Drain Tank ECST - Evaporator Concentrates Storage Tank E0L - End of Core Life FDT - Floor Drain Tank FWST - Fueling Water Storage Tank (formerly Refueling Water Storage Tank) LHST - Laundry and Hot Shower Tank MST - Mixing and Settling Tank NCDT - Reactor Coolant Drain Tank RET - Resin Batching Tank RHT - Recycle Holdup Tank RMT - Recycle Monitor Tank RMWST - Reactor Makeup Water Storage Tank TABLE Bl.0-1 (1 of 2)
r TABLE Bl.0-1' (2 of 2) , ABBREVIATIONS SRST - Spent Resin Storage Tank VUCDT - Ventilation Unit Condensate Drain Tank WDT - Waste Drain Tank WEIT - Wast.e Evaporator Feed Tank WMT - Waste Monitor Tank i I . l TABLE Bl.0-1 (2 of.2) i f l
r B2.0 RELEASE RATE CALCULATION Generic release rate calculations are presented in Section 1.0; these calculations will be used to calculate release rates for McGuire Nuclear Station. B2.1 LIQUID RELEASE RATE CALCULATIONS There are three potential release points at McGuire. Two of these release points, the waste liquid effluent line and the containment ventilation unit condensate effluent line, discharge into the condenser cooling water flow; the third possible release point is through the conventional waste water treatment system. B2.1.1 Waste Liquid Effluent Line To simplify calculations for the waste liquid effluent line, it is assumed that no activity above background is present in the containment ventilation unit condensate effluent. This assumption shall be confirmed by radiation monitoring measurements and by periodic analysis of the composite sample collected on that line. For the waste liquid effluent line, one of the follow-ing calculations shall be performed for discharge flow, in gpm, depending on the number of condenser cooling water pumps in service: -- n n l ft i 2.5ES+2.5(I Ci ) = 1.0E5+(I Ci ) i=1 MPC. i=1 MPC. 1 1 a n l f2 5 5.0ES+2.5(I Ci ) = 2.0E5+(I Ci ) i=1 MPC. i=1 MPC. 1 1 a n l fa $ 7.5ES+2.5(I Ci ) = 3.0E5+(I Ci ) i=1 MPC. i=1 MPC. 1 1 l n a f 45 1.0E6+2.5(I Ci ) = 4.0E5+(I _Ci ) l l i=1 MPC. i=1 MPC. I 1 1 where: C. = 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., *
= 2E-4pCi/ml.
1 F = the dilution flow available dependi.1g on the number of condenser l cooling water pumps in service, in gpm: l l l B-4 Revision 1
Ft = 2.5E5 gpm F2 = 5.0E5 gpm F3 = 7.5E5 gpm F4 = 1.0E6 gpm a = the recirculation factor at equilibrium is 2.4. a=1+ = 1 + 376 = 2.4 a = 2.4 (assuming C'ff is the concentration after initial dilution with the annual average plant condenser cooling water flow of 3720 cfs) where: QII = average flow past Cowans Ford Dam (2670 cfs) QR = average liquid radwaste release rate (3720 cfs)
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B2.1.2 Containment Ventilation Unit Condensate Effluent Line As described in the preceding section, it is possible but unlikely that the - containment ventilation unit condensate effluent line will contain measurable activity above background; it is assumed that no activity is present in the effluent until indicated by radiation monitoring measurements and by periodic analysis of the composite sample collected on that line. If measurable activity is present in the effluent, administrative controls shall be imple-mented to assure that release limits are not exceeded. See section on radia-tion monitoring alarm / trip setpoints. B2.1.3 Conventional Waste Water Treatment System Effluent Line The 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. Radiation monitoring alarm / trip setpoints assure that release limits are not exceeded; see section on radiation monitoring alarm / trip setpoints. l B2.2 GASEOUS RELEASE RATE CALCULATIONS l The unit vent is the release point for waste gas decay tanks, containment building purces, the condenser air ejector, and auxiliary building ventilation. The condenser air ejector effluent is normally considered nonradioactive; that i is, it is unlikely the effluent will contain measurable activity above back-ground. It is assumed that no activity is present in the effluent until ( indicated by radiation monitoring measurements and by analyses of periodic I samples collected on that line. Radiation monitoring alarm / trip setpoints in conjunction with administrative controls assure that release limits are not exceeded; see section on radiation monitoring setpoints. B-5 Revision 1
r The following calculations, when solved for flowrate, are the release rates for noble gases and for radioiodines, particulates and other radionuclides with half-lives greater than 8 days; the most conservative of release rates calculated in B2.2.1 and B2.2.2 shall control the release rate for a single release point. B2.2.1 Noble Gases {Kg [(i7Q)Q] g < 500 mrem /yr, and 1 {(Lt + 1.1 Mg) [(X/Q)Qt ] < 3000 mrem /yr 1 where the terms are defined below. B2.2.2 Radioiodines, Particulates, and Others s {Pg [W Qg] < 1500 mrem /yr 1 where: K. 1
= The total body doese factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m 3 from Table 1.2-1.
L.
= 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. 1
= The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 from Table 1.2-1 (unit conver-sion constant of 1.1 mrem / mrad converts air dose to skin dose).
P.
= The dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem /yr per pCi/m3 and for the food and ground plane pathways in m2 .(mrem /yr) per pCi/see from Table 1.2-2. The dose factors are based on the critical individual organ and most restrictive age group (child or infant).
~
= The release rate of radionuclides, i, in gaseous effluent from all Q *.
release points at the site, in pCi/sec. (X/Q) = 9.5E-6 sec/m3 . The highest calculated annual average relative concen-tration for any area at or beyond the unrestricted area boundary. W = The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location: W = 3.2E-6 sec/m3 , for the inhalation pathway. The location is the unrestricted area in the NE sector. { B-6 Revision 1
. O W = 1.1E-8 meter 2, for the food and ground ~ plane pathways. The l location is the unrestricted area boundary in the E sector (nearest r residence, and vegetable garden). 1 s
Qg =kCf+k ig 2 = 4.72E+2Cg f where: C. = the concentration of radionuclide, i, in undiluted gaseous effluent, in pCi/ml.
; f = the undiluted effluent flow, in cfm kt =-conversion factor, 2.83E4 al/ft3 k2 = conversion factor, 6El sec/ min i
I I l l 1 l i-i I e B-7 Revision 1
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F B3.0 RADIATION MONITOR SETPOINTS Using the generic calculations presented in Section 2.0, radiation monitoring setpoints are calculated for monitoring as required by the Technical Specifications. All radiation monitors for McGuire are off-line. These monitors alarm on low flow; the minimum flow alarm level for the liquid moniters is 2 gallons per minute and for the gas monitors is 6 standard cubic feet per minute. These monitors measure the activity in the liquid or gas volume exposed to the detector and are independent of flow rate if 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 station procedure using the following relationship: c= r 2.22 x 106e V where: c = the gross activity, in mci /ml r = the count rate, in cpm - 2.22 x 106 = the disintegration per minute per mci e = the counting efficiency, cpm /dpm V = the volume of fluid exposed to the detector, in ml. B3.1 LIQUID RADIATION MONITORS B3.1.1 Waste Liquid Effluent Line As described in Section B2.1.1 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 that used to calculate the release rate. When releases are not being made, a radiation monitor set-point shall be calculated to assure that release limits are not exceeded. This setpoint is: cF" f F 1.04E-4 mci /ml where: c = the gross activity in undiluted effluent, in mci /ml f = the flow from the tank may vary from 0-100 gpm but, for this calculation, ' is assumed to be 100 gpm (the actual flow is set by flow selection on the manually loaded throttle valve, a Kerotest globe valve) C=MPC = IE-7 mci /ml, the MPC for an unidentified mixture s = 2.4 (See Section B2.1.1) B-8 Revision 1
r F = the dilution flow may vary as described in B2.1.1, but is conservatively estimated at 2.5E+5 gpm, the minimum flow available, minimum flow is aesured by valve interlock terminating effluent discharge. B3.1.2 Containment Ventilation Unit Condensate Effluent Line As described in Section B2.1.2 on release rate calculations for the containment ventilation unit condensate effluent, it is possible but unlikely that the effluent will contain measurable activity above background. It is assumed that no activity is present in the effluent until indicated by radiation monitoring and by routine analyses of the composite sample collected on that line. Since the tank contents are discharged automatically, a maximum tank concentration, whieb also is the radiation monitor setpoint, is calculated to assure that release limits are not exceeded. The monitor setpoint and maximum tank concen-tration is: c $ " g} $ 1.04E-4 pCi/ml where: c = the gross activity in undiluted effluent, in pCi/ml f = the flow from the tank may vary from 0-100 gpm but, for this calculation, is assumed to be 100 gpm C=MPC = IE-7 pCi/ml, the MPC for an unidentified mixture o = 2.4 (See Section B2.1.1) F = the dilution flow may vary as described in n2.1.1, but is con-servatively estimated at 2.5E+5 gpm, the minimum flow available The above calculation determines the maximum setpoint for this release point; releases and/or setpoints may be administrative 1y controlled to assure that release limits are not exceeded since more than one release source may be released to the condenser cooling water. B3.1.3 Conventional Waste Water Treatment System Discharge Line As described in Section B2.1.3 on release rate calculations for the conventional waste water treatment system effluent, the effluent is normally considered I non-radioactive; that is, it is unlikely the effluent will contain measurable ( activity above background. It is assumed that no activity is present in the effluent until indicated by radiation monitoring and by routine analysis of the composite sample collected on that line. Since the system discharges auto-matically, the maximum system concentration, which also is the radiation moni-tor setpoint, is calculated to assure compliance with 3.11.1.1. The monitor setpoint and maximum effluent concentration is: c1" g 5 5.4E-7 pCi/ml where: j c = the gross activity in undiluted effluent, in pCi/ml B-9 Revision 1
f = the flow rate of undiluted effluent which may vary from 0-6700 gpm, but is assumed to be 6700 gpm C=MPC = IE-7 pCi/ml, the MPC for an unidentified mixture F = the flow may vary from 80 to 50,000 cfs, but is conservatively estimated at 80 cfs (3.6E+4 gpm), the minimum flow available o = 1 [The Conventional Waste Water System discharge line is located down-stream of Cowan's Ford Dam and, therefore, has no reconcentration (recirculation) factor associated with it.] B3.2 GAS MOFITORS The following equation shall be used to calculate noble 3as radiation monitor setpoints based on Xe-133: K(X/Q)Q. 1
< 500 Q = 4.72E+2 Cg f (See Section B2.2.1)
C1 < 3.79E+2 _. where: Cg = the gross activity in undiluted effluent, in pCi/ml f = the flow from the tank or building and varies for various release sources, in Cfm
= from Table 1.2-1 for Xe-133, 2.94E+2 mrem /yr per pCi/m 3 K
(X/Q) = 9.5E-6 sec/m3 , the highest calculated annual average relative concen-tration for any area at or beyond the unrestricted area boundary for long term releases. As stated in Section B2.2, the unit vent is the release point for waste gas decay tanks, containment building purges, the condenser air ejector, and auxi-liary building ventilation. Since all of these releases are through the unit vent, the radiation monitor on the unit vent may be used to assure that station release limits are not exceeded. Depending on the stack flow, the radiation monitor setpoint may be: C. < 3.79E+2/ f = 4.62E-3 pCi/ml 1 l l where: ! f = 54,000 cfm (auxiliary building) + 28,000 cfm (containment purge) = 82,000 cfm l I or may be: C < 3.79E+2/f = 7.02E-3 pCi/ml where: l f = 54,000 cfm (auxiliary building ventilation) B-10 Revision 1
i B4.0 DOSE CALCULATIONS B4.1 FREQUENCY OF CALCULATIONS Dose contributions to the maximum exposed individual shall be calculated every 31 days, quarterly, semiannually, and annually (as required by Technical Spec-ifications) using the methodology in tha generic information sections. This methodology shall also be used for any special reports. Dose projections shall be performed usiag simplified estimates. Fuel cycle dose calculations shall be performed annually or as required by special reports. Dose contributions shall be calculated using the methodology in the appropriate generic information sections. B4.2 DOSE MODELS FOR MAXIMUM EXPOSED INDIVIDUAL B4.2.1 Liquid Effluents For liquid radioactive effluent release, it is assumed that the maximum exposed individual is an adult who consumes fish caught in the discharge area and drinks water from the nearest " downstream" water supply. B4.2.2 Gaseous Effluents B4.2.2.1 Noble Gases For dose contributions from exposure to beta and gamma radiation from noble gases, it is assumed that the maximum exposed individual is an adult on the site boundary in each meteorological sectors. B4.2.2.2 Radioiodines, Particulates, and Other Nuclides 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. B4.3 SIMPLIFIED DOSE ESTIMATE B4.3.1 Liquid Effluents For dose projections simplified calculations using the assumptions presented in Section B4.2.2 and source terms presented in the FSAR are presented below. Once operational source term data is available, this information shall be used to revise these calculations, if necessary. Dose calculations used to evaluate Appendix I to 10 CFR50 compliance indicate that the maximum exposed individual is an adult who consumes fish caught in the discharge area and that 90% of the dose is from cesium-134 and cesium-137. m D WB = 6.64E5 I (F g)(T )g(CCs-134 + 0.59 CCs-137) l=1 B-11 Revision 1
f where: - U ' 6.64E5 = (1.10)(1.14E5) + 21 BF g DF g and all terms are as previously D
.w .
defined except the following: CCs-134 = the average concentration of Cs-134 in undiluted effluent, in pCi/ml, during the time period considered. C the average c ncentrati n f Cs-137 in undiluted effluent, in pCi/ml, Cs-137 = during the time period considered. Dy = dilution factor from the near field area to the potable water intake, 0.42. B4.3.2 Gaseous Effluents Meteorological data is provided in Tables B4.0-1 and B4.0-2. B4.3.2.1 Noble Gases For dose calculations for time periods less than a quarter, simplified dose estimates using the assumptions in B4.2.2.1 and source terms in the FSAR are presented below. Once operational source term data is available, this infor- _ mation shall be used to revise these calculations, if necessary. These cal-culations further assume that the annual average dispersion parameter is used and that xenon-133 contributes 45% of the dose. s D = 2.36E-10 [Q]Xe-133 s D p = 7.03E-10 [Q}Xe-133 where: X74 = 9.5E-6 sec/m 3 2.36E-10 = constant determined from factors previously presented 7.03E- 10 = constant determined from factors previously presented s [Q]Xe-133
*'* ' I **" "'I #" " Y #* **** "E B4.3.2.2 Radioiodines, Particulates, and Other Nuclides For dose calculations for time periods less than a quarter, simplified dose estimates using the assumptions in B4.2.2.2 and source terms in the FSAR are presented below. Once operational source term data is available, this infor-mation shall be used to revise these calculations, if necessary. These cal-
, culations 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: s D = 1.75E5 w (Q)I-131 B-12 i Revision 1
where: w = D/Q for food and ground plane pathway, in m 2 from Tabic B4.0-2 for location of nearest real cow or goat. s (Q)I-131 = the release of iodine-131 in gaseous effluents, in pCi. 1.75E+5 = ( .05(3.17E-3) R [D/Q] with the appropriate substitutions in R [D/Q] for iodine-131. See Section B3.1.2. B4.3 FUEL CYCLE CALCULATIONS
. These calculations shall be performed using models presented in Section 3.3.
i 4 T 4 B-13 Revision 1
TA8Lt. B4.0-1 (1 of 1) MCGUIRE NUCLEAR STATION DISPERSION PARAMETER (X7Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR l Distance to the control location, in miles Sector 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 S ' 6 E-6
. 8.5 E-7 4.7 E-7 3.1 E-7 2.2 E-7 1.7 E-7 1.4 E-7 1.2 E-7 9.8 E-8 3.5 E-8 SSW 2.6 E-6 8.8 E-7 4.8 E-7 3.1 E-7 2.3 E-7 1.7 E-7 1.4 E-7 1.1 E-7 9.7 E-8 8.3 E-8 SW 3.6 E-6 1.2 E-6 6.2 E-7 4.0 E-7 2.8 E-7 2.2 E-7 1.7 E-7 1.4 E-7 1.2 E-7 1.0 E-7 WSW 2.4 E-6 7.6 E-7 4.0 E-7 2.5 E-7 1.8 E-7 1.4 E-7 1.1 E-7 8.8 E-8 7.4 E-8 6.3 E-8 W 2.2 E-6 7.1 E-7 3.8 E-7 2.5 E-7 1.8 E-7 1.4 E-7 1.1 E-7 9.0 E-8 7.6 E-8 6.5 E-8 WNW 2.0 E-6 6.8 E-7 3.8 E-7 2.5 E-7 1.8 E-7 1.4 E-7 1.1 E-7 9.4 E-8 8.0 E-8 6.9 E-8 NW 3.2 E-6 1.1 E-6 6.2 E-7 4.2 E-7 3.1 E-7 2.4 E-7 1.9 E-7 1.6 E-7 1.4 E-7 1.2 E-7 NNW 3.5 E-6 1.2 E-6 6.9 E-7 4.7 E-7 3.5 E-7 2.7 E-7 2.2 E-7 1.9 E-7 1.6 E-7 1.4 E-7 N 7.6 E-6 2.5 E-6 1.5 E-6 1.0 E-6 7.5 E-7 5.9 E-7 4.8 E-7 4.0 E-7 3.5 E-7 3.0 E-7 NNE 8.6 E-6 2.8 E-6 1.6 E-6 1.1 E-6 8.4 E-7 6.6 E-7 5.4 E-7 4.5 E-7 3.9 E-7 3.4 E-T NE 9.5 E-6 3.2 E-6 1.8 E-6 1.2 E-6 9.1 E-7 7.2 E-7 5.8 E-7 4.9 E-7 4.2 E-7 3.6 E-7 ENE 4.4 E-6 1.5 E-6 8.3 E-7 5.6 E-7 4.1 E-7 3.2 E-7 2.6 E-7 2.2 E-7 1.9 E-7 1.6 E-7 E 3.1 E-6 1.0 E-6 5.8 E-7 3.9 E-7 2.8 E-7 2.2 E-7 1.8 E-7 1.5 E-7 1.3 E-7 1.1 E-7 l
ESE 1.9 E-6 6.4 E-7 3.6 E-7 2.4 E-7 1.7 E-7 1.3 E-7 1.1 E-7 9.0 E-8 7.7 E-8 6.7 E-8 m SE 2.2 E-6 7.2 E-7 4.0 E-7 2.7 E-7 2.0 E-7 1.5 E-7 1.2 E-7 1.0 E-7 8.7 E-8 7.6 E-8 k SSE 1.5 E-6 5.0 E-7 2.8 E-7 1.8 E-7 1.3 E-7 1.0 E-7 8.2 E-8 6.8 E-8 5.8 E-8 5.0 E-8 n
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b-TABLE B4.0-2 (1 of 1) HCGUIRE NUCLEAR STATION DEPOSITION PARAMETER (ii/Q) FOR LONG TERN RELEASES > 500 tiR/YR OR > 125 IIR/QTR Distance to the control location, in miles Sector 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 S 1.1 E-8 3.5 E-9 1.8 E-9 1.1 E-9 7.2 E-10 5.2 E-10 4.0 E-10 3.1 E-10 2.5 E-10 2.1 E-10 SSW l.3 E-8 4.1 E-9 2.1 E-9 1.3 E-9 8.5 E-10 6.1 E-10 4.7 E-10 3.7 E-10 3.0 E-10 2.5 E-10 SW 2.2 E-8 6.9 E-9 3.4 E-9 2.1 E-9 1.4 E-9 1.0 E-9 7.7 E-10 6.1 E-10 4.9 E-10 4.1 E-10 WSW l.5 E-8 4.7 E-9 2.4 E-9 1.4 E-9 9.7 E-10 7.0 E-10 5.3 E-10 4.2 E-10 3.4 E-10 2.8 E-10 W l.1 E-8 3.4 E-9 1.7 E-9 1.0 E-9 7.0 E-10 5.0 E-10 3.8 E-10 3.0 E-10 2.4 E-10 2.0 E-10 . WNW 7.3 E-9 2.3 E-9 1.2 E-9 7.0 E-10 4.7 E-10 3.4 E-10 2.6 E-10 2.0 E-10 1.7 E-10 1.4 E-10 NW 7.5 E-9 2.4 E-9 1.2 E-9 7.1 E-10 4.8 E-10 3.5 E-10 2.7 E-10 2.1 E-10 1.7 E-10 1.4 E-10 NNW 6.0 E-9 1.9 E-9 9.4 E-10 5.7 E-10 3.8 E-10 2.8 E-10 2.1 E-10 1. 7 E- 10 1.4 E-10 1.1 E-10 N 1.4 E-8 4.4 E-9 2.2 E-9 1.3 E-9 9.0 E-10 6.5 E-10 4.9 E-10 3.9 E-10 3.2 E-10 2.6 E-10 NNE 1.8 E-8 5.7 E-9 2.8 E-9 1.7 E-9 1.2 E-9 8.4 E-10 6.4 E-10 5.0 E-10 4.1 E-10 3.4 E-10 NE 2.4 E-8 7.6 E-9 3.8 E-9 2.3 E-9 1.6 E-9 1.1 E-9 8.5 E-10 5.7 E-10 5.4 E-10 4.5 E-10 ENE 1.2 E-8 3.8 E-9 1.9 E-9 1.2 E-9 7.8 E-10 5.7 E-10 4.3 E-10 3.4 E-10 2.7 E-10 2.3 E-10 E 1.1 E-8 3.4 E-9 1.7 E-9 1.0 E-9 6.9 E-10 5.0 E-10 3 ' E-10 3.0 E-10 2.4 E-10 2.0 E-10 ESE 8.3 E-9 2.6 E-9 1.3 E-9 7.9 E-10 5.4 E-10 3.9 E-10 2.9 '-10 2.3 E-10 1.9 E-10 1.6 E-10 mw SE 8.3 E-9 2.6 E-9 1.3 E-9 7.9 E-10 5.4 E-10 3.9 E-10 2.9 E- 10 2.3 E-10 1.9 E-10 1.6 E-10
- om E1 na SSE 7.9 E-9 2.5 E-9 1.2 E-9 7.5 E-10 5.1 E-10 3.7 E-10 2.8 E-10 2.2 E-10 1.8 E-10 1.5 E-10 m
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. 4 B5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING The radiological environmental monitoring program shall be conducted in accor-dance with Technical Specification 3/4.12. The monitoring program locations and analyses are given in Tables B5.0-1 through B5.0-3 and Figure 35.0-1 Site specific characteristics make groundwater sampling, special low level I-131 analyses on drinking water, and food product sampling unnecessary. Groundwater l recharge is from Lake Norman and local precipitation the groundwater gradient is toward the effluent discharge area; therefore, contamination of groundwater l 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 lake water irrigation of crops is not practiced in the vicinity. Addi-tionally, two site boundary TLD locations in the NW and NNW sectors do not exist since the required locations are over water.
The laboratory performing the radiological environmental analyses shall parti-cipate in an interlaboratory comparison program which has been approved by the NRC. l l B-14 Revision 1
I w 2 7 TABLE B5.0-1 (1 of I) 1 McGUIRE RADIOlhGICAL MONITORING PROGRAM SAMPLING IDCATIONS a2 3. (TLD IDCATIONS) ". O at e" SAMPLING IDCATION DESCRIPTION
- SAMPLING IDCATION DESCRIPTION
- i 143 SITE BOUEDlRY (0.5 MILES N) 163 4-5 MILE RADIUS (5.0 MILES SE) 144 SITE BOUNDARY (0.7 hlLES NNE) 164 4-5 MILE RADIUS (4.5 MILES SSE) 145 SITE BOUNDARY (0.5 MILES NE) , 165 4-5 MILE RADIUS (5.0 MILES S) 146 SITE BOUNDARY (0.5 MILES ENE) 166 4-5 MILE RADIUS (5.2 MILES SSW)
-* SITE BOUNDARY (0.5 MILES E) 167 4-5 MILE RADIUS (4.9 HILES SW) k ;; 147 148 SITE BOUNDARY (0.5 MILES ESE) 168 4-5 MILE RADIUS (4.7 MILES WSW) g ,149 SITE BOUNDARY (0.6 MILES SE) 169 4-5 MILE RADIUS 4.4 MILES W) ,o 150 SITE BOUNDARY (0.5 MILES SSE) 170 4-5 MILE RADIUS (4.4 MILES WWW) a -* 15 l SITE BOUNDARY (0.5 MILES S) 171 4-5 MILE ktDIUS (4.5 MILES WW)
SITE BOUNDARY (0.5 MILES SSW) 172 4-5 MILE RADIUS (5.2 MILES NNW) h152153 SITE BOUNDARY (0.5 MILES SW) 173 SPECIAL INTEREST (8.5 MILES N) 154 SITE BOUNDARY (0.7 MILES WSW) 174 SPECIAL INTEREST (12.5 MILES NE) 155 SITE BJUNDAkY (0.7 MILES W) 175 SPECI AL INTEREST (7.5 MILES NE) 156 S11E BOUNDARY (0.5 MILES WNW) 176 SPECIAL INTEREST (6.2 MILES ENE) 157 4-5 Mile RADIUS (4.8 MILES N) 177 T.PECIAL INTEREST (10.8 MILES ESE) 158 4-5 MILE RADIUS (4.4 MILES NNE) 178 SPECIAL INTEkEST (5.9 MILES S) 159 4-5 MILE RADIUS (5.0 MILES NE) 179 SPECIAL INTEREST (10.3 MILES SW) 160 4-5 MILE RADIUS (4.9 MILES ENE) 180 CONTROL (12.2 MILES SSE) 161 4-5 MILE RADIUS (4.7 HILES E) 181 CONTROL (8.9 MILES S) 162 4-5 MILE RADIUS (4.6 MILES ESE) 182 CONTROL (8.7 MILES WSW)
- All TID samples are collected quarterly
e 5 TABLE B5.0-2 h (I of I) , w as MCGUIRE RADIO!hGICAL MONITOklNG PROGRAM SAMPLING lhCATIONS (OTHER SAMPLING LOCATIONS) aS
=2 CODE:
"hjU W - Weekly Q - Quarterly 0 a SM - Semimonthly SA - Semiannual g W g g
? $
N - Monthly SH :s o g { g~ d 4 E "9 M . a e B. s a. m =
. a.
.......=--
- ..........Stu3eting,tegI1gy,tgSgitI!gN_____ , _ _ _____=== ___ _,,,,,__, _ __,,,____,,_,,,,,___,,,
120 Site Boundary (0.7 miles NNE) W 121 Site Boundary (0.5 m!!es NE) V W M 125 Site Boundary (0.5 miles SW) 128 Discharge Canal Bridge (0.4 miles ENE) M Eo Discharge Canal Entrance to Lake Norman (0.6 miles ENE) SA SA 129 g M SA h 130 Hwy. 73 Bridge Downstream (0.6 miles SW) 131 Ituntersville Municipal Water Supply (3.0 miles ENE) M 132 Claarlotte Municipal Water Supply (11.2 miles SSE) M 133 Cornelius (6.2 miles NE) W East Lincoln Junior High School (8.7 miles WNW) Control W M 134 135 Plant Marshall Intake Canal (12.0 miles N) Control M 136 Mooresville Huuicipal Water Supply (12.5 miles NME) Control M Control SA SA 137 Pinnacle Access Area (12.0 miles N) Aut, bard Dairy (1.8 miles ESE) - Cows SM 138 SM 139 RC Howell Hesidence (1.8 miles SSE) - Coats 140 Kidd Dairy (2.8 miles SSE) - Cows SM 141 Keever Dairy (1.3 miles NW) - Cows Control SM 142 Davidson Municipal Water Supply (7.5 miles NE) M
- 18) Duke Power Substation - Lincoluton City Limits -
H (18 miles WNW) I
e O TABLE 5.0-3 w (I of 1) a HCGUIRE RADIOLOGICAL MONITORING PROGRAM ANALYSES ANALYSES j SAMPLE MEDitM ANALYSIS SCHEDULE GAP 9tA ISOTOPIC TRITitM IDW LEVEL I-131 GROSS BETA Ty j 1. Air Radiciodine and Particulates Weekly X Quarterly X
- 2. Direct Radiatiou
- 3. Surface Water Monthly X n
Quarterly Composite I kO Ng 4. Drinking Water Monthly X I d, Quarterly Composite X Q" e4
- 5. Shoreline Sediment Semiannually X l
Semimonthly X X . 6. Milk
- 7. Fish Semiannually X
- 8. Broadleaf Vegetation Monthly X e
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