ML19289D102
| ML19289D102 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/25/1979 |
| From: | Parker W DUKE POWER CO. |
| To: | Baer R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901290228 | |
| Download: ML19289D102 (60) | |
Text
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!' 7 DuxE PowEIz Coxe_o.y Powen Dett.otxo 40c SocTn Curacu Starrr. Ciunt.oTTE. N. C. 28242
.. .. .u o .. p a r n. s a. January 25, 1979 oc. p.es 2c.a T r c.-e~ c: 4.c 7:4 E ' t a na Cs 0C.s;* 3% 2 7 3-4 0 a 3 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Robert L. Baer, Chief Light Water Reactors, Project Branch No. 2 Re: McGuire Nuclear Station Units 1 and 2 Docket Nos. 50-369, 50-370
Dear Mr. Denton:
Please find attached ten copies of the Offsite Dose Calculation Manual (ODCM) for McGuire Nuclear Station. This document supplements the radiological effluent technical specifications which were submitted to the staff on December 18, 1978.
The attached version of the ODCM is the first draft and it is expected that some changes will be necessary prior to implementation. It is anticipated that a meeting between representatives of the NRC st-ff and , ,
Duke Power would be appropriate after the staff has reviewed both the proposed radiological effluent technical specifications and the ODCM.
Very truly yours, ,
cb!A$be.~ 0 & L "
Williac 0. Parker, Jr. ,h 7 GAC:scs Attachments (1C) 7901290S
' s 0FFSITE DOSE CALCULATION btNUAL FOR MCGUIPI NUCLEAR STATION DOCKET #50-369, 370
TAELE OF CONTEhTS PAGE INTRODUCTION 1 1.0 RELEASE RATE CALCULATIONS 1-1 1.1 LIQUID EFFLUENTS 1-1 1.1.1 WASTE LIQUID EFFLUENT LINE l-1 1.1.2 CONTAINMENT VEhTILATION INIT CONDENSATE EFFLUENT LINE l-2 1.1.3 CONVEhTIONAL WASTE WATER TREATMEhT SYSTEM EFFLUENT LINE l-2 1.2 GASEOUS EFFLUENTS 1-3 1.2.1 NOBLE GASES 1-3 1.2.2 RADI0 IODINES, PARTICULATES, AND OTHERS 1-3 2.0 DOSE CALCULAiIONS 2-1 2.1 LIQUID EFFLUENTS 2-1 2.1.1 QUARTERLY DOSE CALCULATIONS 2-3 2.1.2 31 DAY DOSE CALCULATIONS 2-3 2.2 GASEOUS EFFLUENTS 2-4 2.2.1 N0BLE GASES 2-4 2.2.2 RADI0 IODINES, PARTICULATES, AND OTHERS 2-4 2.2.3 QUARTERLY DOSE CALCULATIONS 2-10 2.2.4 31 DAY DOSE CALCULATIONS 2-10 2.3 FUEL CYCLE CALCULATIONS 2-12 3.0 RADIATION MONITORING SETPOINTS 3-1 3.1 LIQUID MONITORS 3-1 3.1.1 WASTE LIQUID EFFLUENT LINE 3-1 3.1.2 CONTAINMENT VESTILATION UNIT CONDENSATE EFFLUENT LINE 3-1 3.1.3 CONVEhTIONAL WASTE WATER TREATMENT SYSTEM DISCRARGE LINE 3-2 3.2 GAS MONITORS 3-3 3.2.1 WASTE GAS EFFLUENT LD.'E 3-3 3.2.2 CONTAINMENT PURGE 3-3 3.2.3 CONDENSER AIR EJECTOR 3-3 3.2.4 UNIT VENT 3-4
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;
- 2) the exposures to any individual from radioactive liquid effluents will not result in doses greater than the design objectives of 10CFR50, Appendix I;
- 3) the dose rate at any time at the site boundary from radioactive gaseous effluents vill 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 me 1odology 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 Maaual. The Manual also provides the methodology and parameters to be used in the calculation of radioactive liquid and gaseous effluent monitoring instrumen-tation elarm/ trip setpoints to assure compliance with the concentration and dose rate limitations of the Technical Specifications. Changes to the methodology and parameters used in this Manual shall be reviewed by a qualified reviewer (s) and approved by the Station Manager and Nuclear Safety Review Board prior to implementation. Changes to this Manual shall be submitted to the Nuclear Regulatory Commission within 90 days of the date the change was made ef fective by inclusion 'a che Monthly Operating Report to comply with Specifi-cation 6.15.2. This Manual does not replace any station implementing procedures. I
1.0 RELEASE RATE CALCULATIONS 1.1 LIQUID EFFLUENTS To comply with specification 3.11.1.1 and to assure that the concentration of radioactive liquid effluents from the site to the unrestricted area is limited to the concentrations of 10CFR20, Appendix B, Table II, Column 2, the following release rate calculation shall be performed: n f i F + (c I Ci ) i=1 MPC. 1 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 II, Column 2, in pCi/ml. f = the undiluted effluenc flow from the tank, in gpm. F = the dilution flow from the site discharge structure to unrestricted area receiving waters, in gpm. . c = recirculation factor at equilibrium. The aboie calculation is the release rate for a single release point. There are three potential release poirts at McGuire. Two of these release points, the waste liquid effluent line and the containment ventilation unit con-densate effluent line, discharge into the condenser cooling water flow; the third possib1c release point is through the conventional waste water treatment system. 1.1.1 Waste Liquid Effluent Line To simplify calculations for the waste liquid effluen* line, it is assumed that no activity above background is present in the cortsiti mt ventilation unit condensate effluent. This assumption shall be confirmed by radiation zonitoring measurements and by periodic analysis of the composite sample collected on that line. For the waste liquid effluent line, one of the following calculations shall be performed for discharge flow, in gpm, depending on the number of condenser cooling water punps in service: n n f t< 2.5E5+2.5(I Ci ) i 1.0 ES+(I _Ci_) i=1 MPC. i=1 MPC. 1 1 n n f2 16.4ES+2.5(I Ci ) i 2.6E5+(I Ci ) i=1 MPC. i=1 MPC. 1 1 1-1
e . n n f3 18.6E5+2.5(I Ci ' 5 3.4E5+(I _Ci) i=1 MPC. i=1 MPC. 1 1 n n f4 11.0E6+2.5(I Ci ) $ 4.0ES+(I Ci ) i=1 MPC. i=1 MPC. 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, Tabl. II, Column 2. If radionuclide, i, is a dissolved noble gas, the MPC., 1
= 2E-4pCi/ml.
F = the dilution flow available depending on the number of condenser cooling water pumps in service, in gpm: F1 = 2.5E5 gpm F2 = 6.4E5 gpm F3 = 8.6ES gpm F4 = 1.0E6 gpm c = the recirculation factor at equilibrium is 2.5. 1.1.2 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 meas-urable activity above background; it is assumed that no activity is present in tne effluent until indicated by radiation monitoring measurements and by periodic analysis of the composite sample collected on that line. If mea-surable activity is present in the effluent, administrative controls shall be implemented to assure that specification 3.11.1.1 is not exceeded. See section 3.1.2 on raciation monitoring alarm / trip setpoints. 1.1.3 Conventional Waste Water Treatment Systen Effluent Line The conventional waste water treatment system effluent is nornally considered nonradioactive; that ir, it is unlikely the effluent will contain measurable activity above backgraind. It is assumed that no activity is present in the effluent until indicated by radiation mcnitoring measurements and by periodic analyses of the composite sample collected on that line. Radiation monitoring alarm / trip setpoints assure that specification 3.11.1.1 is not exceeded; see section 3.1.3 on radiation monitoring alarm / trip setpoints. 1-2
1.2 GASEOUS EFFLUENTS In order to comply with the specification 3.11.2.1 to assure that the dose rate, at any time, in the unrestricted area due to radioactive materials re-leased in gaseous effluents from the site is limited to < 500 mrem /yr to the total body and < 3000 mrem /yr to the skin for the noble gases and is limited to < 1500 mrem /yr to any organ for all radioiodine and for all radioactive materials in particulate form and radionuclides other than noble gases with half lives greater than 8 days, the following release rate calculations shall be performed solving for f: 1.2.1 Release rate limit for noble gases: IK g [(i7Q)h]g < 500 mrem /yr, and 1 I (Lg + 1.1. Mg ) [(57U)h]g < 3000 mrem /yr 1 where the terms are defined below: 1.2.2 Release rate limit for all radioiodines and radioactive materials in particulate form and radionuclides other than noble gases: IPg [W Q f] < 1500 mrem /yr 1 where: K. 1
= The total body dose factor due to gamma emissions for each identified 3
noble gas radionuclide, in mrem /yr per pCi/m from Table 1.2-1. L. 1
= The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3 from Table 1.2-1.
M. 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 con-version constant of 1.1 mrem / mrad converts air dose to skin dose).
P. 1
= The dose parameter for radionuclides other than noble gn es for the inhalation pathway, in mrem /yr per pCi/m3 and for the food and ground plane pathways in m2 (mrem /yr) per pCi/sec from Table 1.2-2. The dose factors are based on the critical individual organ and most restric-tive age group (child or infant).
Q.1 = The release rate of radionuclides, i, in gaseous effluent from all release points at the site, in pCi/sec. (57Q)=2.6E-6sec/m. 3 The highest calculated annual average relative concen-tration for any area at or beyond the unrestricted area boundary. 1-3
e r W = The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location: W = 7.6E-8 sec/m3 , for the inhalation pathway. The location is the unrestricted area in the SW sector. W = 2.0E-8 meter 2, for the food and ground plane pathways. The location is the unrettricted area boundary in the E sector (nearest residence, cow, and vegetable garden) Q.1 =kC.F+K2 i 1 = 4.72E-2C.f1 where: C. = the concentration of radionuclide, i, in undiluted gaseous effluent, 1 in pCi/ml. f = the undiluted effluent flow, in cfm ki = conversion factor, 2.83E4 ml/ft a k2 = conversion factor, 6El sec/ min The above calculations, when solved for flowrate, are the release rates for noble gases and for radioiodines, particulates and other racionuclides with half-lives greater than 8 days; the most conservative of release rates calculated in 1.2.1 and 1.2.2 shall control the release rate for a single release point. The unit vent is the release point for waste gas decay tanks, containment building purges, the condenser air ejector, and auxiliary building ventilation. The condenser air ejector effluent is normally considered nonradioactive; that is, it is unlikely the effluent will contain measureable 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 samples collected on that line. Radiation monitot ing alarm / trip setpoints in conjunction with administrative controls assure that specification 3.11.2.1 is not exceeded; see section 3.2 on radiation monitoring setpoints. 1-4
TABLE 1.2-1 . DOSE FACTORS FOR POPLE CASES AND DAUGIITERS* Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K. L. fl . N. Radionuclide (mrem /yr per pCi/m3) (mrem /yr per yCiAn3) (mrad /yr per pCi/m 3) (mrad /yr per pCi/m3) Kr-83m 7.56E-022* --- 1.93E+01 2.66E+02 K r-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.6]E+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.C '+ 04 1.73E404 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 Xc-133m 2.51Et02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E403 4.13E+03 9.21E+03 4.75E+03 AR-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03
~5ihe listed dose factors are for radionuclides that may be detected in gaseous effluents. **7.56E-02 = 7.56 x 102
~
TABLE 1.2-2 DOSE PARAtETERS FOR RADIGIODINES AND RADI0 ACTIVE PARTICULATE, GASEQUS EFFLUENTS
- P. P. P. P.
I 1 1 1 Radio- Inhalation Pathway Food & Ground Pathways Radio- Innalation Pathway Food & Ground Pathways nuclide (mrem /yr per_pCi/m3) (m2 - mrem /yr per_pCi/sec) nuclide (mrem /yr per pCi/m 3) (m2 mrem /yr per pCi/sec) 11 - 3 6.5E+02 2.4E+03 Cd-115m 7.0E+04 5.2E+07 Sn-123 2.9E+05 3.7E+09 Mn-54 2.5E+04 1.1E409 Sn-126 1.2E+06 1.1E+10 Fe-59 2.4E+04 7.2E+09 Sb-124 5.9E+04 1.4E+09 Co-58 1.1E+04 5.8E+08 SB-125 1.5E+04 9.1E+09 Co-60 3.2E+04 4.6E+09 Te-127m 3.8E+04 1.3E+09 Zn-65 6.3E+04 1.8E+10 Te-129m 3.2E+04 1.3E+09 Rb-86 1.9E+05 2.1E+10 Cs-134 7.0E+05 5.0E+10 Sr-89 4.0E+05 1.1E+10 Cs-136 1.3E+05 5.7E+09 Sr-90 4.1E+07 1.0Eill Cs-137 6.lE+05 5.0E+10 Y-91 7.0E+04 5.9E+06 Ba-140 5.6E404 2.6E+08 Zr-95 2.2E+04 3.5EiO8 Cc-141 2.2E+04 3.2E+07 Nb-95 1.3E+04 3.8E+08 Ce-144 1.5E+05 1.6E+08 Ru-103 1.6E+04 1.6E+08 I-131 1.5E+07 1.0E+12 Ru-106 1.6E+05 3.0E+08 I-133 3.6E+06 9.6E+09 Ag-110m 3.3E+04 1.5E+10 Unidentified ** 4.1E+07 1.0E+11 YThe listed dose parameters are for radionuclides that may be detected in gaseous affluents. k
2.0 DOSE CALCULATIONS 2.1 LIQUID EFFLUENTS Cumulative dose contributions resulting from liquid radioactive effluent releases shall be calculated for the maximum exposed individual; the maximum exposed individual is an adult who drinks water from a downstream water supply and who consumes fish caught in the discharge area. Dose calculationsl shall be based on: m D1 = I [Ai I Atg Cff fF] 1 f f=1 where: Di = the cumulative dose commitment to the total bodt or ang organ, i, from the liquid effluent for the total time period I atp, in mrem. 2=1 At g= the 1er.gth of the f th time period over which C and Fg are ff averaged for all liquid teleases, in hours C gg= the average concentration of radionuclide, i, in undiluted liquid effluent during time period Atg from any liquid release, in pCi/ml. F = the near field average dilution factor for Cig during any liquid f effluent release where: F g=Fxk f where: f = ligtid radwaste flow, in gpm F = dilution flow, in gpm k = 1 for once through cooling A gg = the site related ingestion dose commitment factor to the total body or any organ, t, for each identified principal gamma and beta emitter, mrem /hr per pCi/ml: ICalculated in accordance with Rerilatory Guide 1.109 (Lev.1) 2-1
A.2 1 = 1.14E5 (730/Dw + 21BF.)Df.I where: D" = Dilution factor from the near field area to the potable water intake for adult water consumption, 0.22 BF.= Bioaccamulation factor for radionuclide, i, in fish, pCi/kg, 1 per pCi/1, from Table 2.1-1. DF.= Dose couversion factor for radionuclide, i, for adults in 1 pre-selected organ, t, in mrem /pCi, from Table 2.1-2. 730= Adult, water comsumption, in kg/yr 21 = Adult, fish consumption, in kg/yr 2-2
2.1.1 QUARTERLY DOSE CALCULATIONS , To comply with specification 6.9.1.8, monthly and quarterly cumulative dose contributions resulting from liquid radoactive effluent releases shall be calculated quarterly using the calculations listed in Section 2.1. 2.1.2 31 DAY DOSE CALCULATIONS To comply with specifications 3.11.1.2 and 3.11.1.3, cumulative dose contri-butions shall be determined every 31 days. Based on the dose calculations performed, using source terms presented in the FSAR, to evaluate Appendix I to 10 CFR50 compliance; the calculations to determine 31 days dose contribu-tions may be simplified from those presented in Section 2.1. Based on these calculations, it is assumed that the minimum 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. The simplified calculation to determine the whole body dose of an adult is: m D WB = 6.8SE5 I Fg atg (Cst 34 + 0.59 Cst 37) f=) where: Cs334 - the average concentration of Cs-134 in undiluted liquid effluent during time period Atg, in pCi/ml Cst 37 - the average concentration of Cs-137 in undiluted liquid effluent during time period Aty, in pCi/ml Fg , atf, D - defined in section 2.1 BF - 2E3 pCi/kg per pCi/1 from Table 2.1-1 Cs DF334 - 1.21 E-4 mrem /pCi from Table 2.1-2 DFi a7 - 7.13 E-5 mrem /pCi from Table 2.1-2 2-3
TABLE 2.1-1* BI0 ACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA (pCi/kg per pCi/ liter) FRESHWATER ELEMENT IISH INVERTEBRATE H 9.0E-01 9.0E-01 C 4.6E-03 9.1E-03 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 G2 TE 4.0E 02 6.1E 03 I 1.5E 01 5.0E 00 CS 2.0E 03 1.0E 03 BA 4.0E 00 2.0E 02 LA 2.5E 01 1.0E 03 CE 1.0E 00 1.0E 03 PR 2.5E 01 1.0E 03 hT 2.5E 01 1.0E 03 W 1.2E 03 1.0E 01 NP 1.0E 01 4.0E 02
? Table taken from Regulatory Guide 1.109 (Rev.1)
TABLE 2.1-2 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 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-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 C0 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 C0 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI $3 1.30E-04 9.01E-06 4.56E-06 NO DATA NO DATA NG DATA 1.88E-06 NI 55 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU t'4 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 RS 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-1) 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 (1 of 3)
TABLE 2.1-2 (Cont'd) INGESTION DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED) NUCL.TDE BONE LIVER T.B0DY 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 . 6 3~. ^. 8 NO DATA 2.79E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-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 1.05E-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 CaTA 8.01E-08 7.91E-09 4.65E-13 BA 139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA 140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA 141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA 142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA 140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 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 (2 of 3)
TABLE 2.1-2* INGESTION DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T.B0DY 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 DAT'. 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 5.04E-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 *Taken from Regulatory Guide 1.109 (3 of 3)
2.2 GASEOUS EFFLUENTS 2.2.1 NOBLE GASES To comply with Specification 3.11.2.2 to assure that the air dose in unres-tricted areas during any calendar quarter, due to noble gases released in gaseous effluents from the site, is limited to 5 5 mrad for gamma radiation and 510 mrad for beta radiation; and during any calendar year, to 110 mrad for gamma radiation and 5 20 mrad for beta radiation, the following air dose calculations shall be performed: For gamma radiation: s s DY = 3.17 E-8 I M.1 ((X/Q) Q. 1 + (X/9) 9.} 1 i=1 For beta radiation: s s D = 3.17 E-8 1 Ni [(X/Q) Qi + (X/q) qi} 1=1 where: 3.17 x 10 8 = The inverse of the number of seconds in a year. 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.
N. 1
= The air dose factor due to beta emissions for each identified noble 3
gas radionuclide, in mrad /yr per pCi/m from Table 1.2-1. (X7Q) = 2.8 E-6 sec/m 3 . The highest calculated annual average relative con-centration for any area at or beyond the unrestricted area boundary for long term releasei (greater than 500 hrs / year). (X7q) = 1.9 E-5 sec/m 3 - The relative concentration for any area at or beyond the unrestricted area boundary for short term releases (equal to or less than 500 hrs /yr). s
= The release of noble gas radionuclides, i, in gaseous effluents, for Q *.
long term releases (greater than 500 hrs /yr), in pCi. s
- q. = The release of noble gas radionuclides, i, in gaseous effluents, for 1
short term releases (equal to or less than 500 hrs /yr), in pCi. 2.2.2 RADI0 IODINES, PARTICULATES, AND OTHERS To comply with Specification 3.11.2.3 to assure that the air dose to an indi-vidual from all radioiodines, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas, is limited to 5 7.5 mrem to any organ during any calendar quarter and to 515 mrem to any organ during any calendar year, the following calculation shall be performed: s s D = 3.17 E-8 I R.1 [WQ. 1 t wqi] 2-4
where: 3.17 x 10'8 = The inverse of the number c f seconds in a year. Q. = The release of radioiodines, radioactive materials in particulate form 1 and radionuclides other than noble gases in gaseous effluents, i, for long term releases (greater than 500 hrs /yr), in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate. s q*. = The release of radioiodines, radioactive materials in particulate form and radionuclides other than gases in gaseous effluents, i, for short tera releases (equal to or less than 500 hrs /yr), in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate. W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location for long term releases (greater than 500 hrs /yr): 3 W = (X/Q) for the inhalation pathway, in sec/m from Table 2.2-1. W = (D/Q) for the food anu ground plane pathways, in meters 2 from Table 2.2-2. w = The dispersion parameter for estimating the dose to an individual at the controlling location for short term releases (equal to or less tban 500 hrs /yr): w = (X/q) for the inhalation pathway, in sec/m3 from Table 2 2-3. w = (D3 ) for the food and ground plane pathway, in meters 2 from Table 2.2-4. R. = The dose factor for each identified radionuclide, i, in m 2(mrem /yr) per
- 3 pCi/sec or mrem /yr per pCi/m R.=Rf[X/Q)+Rh(D/Q)+Rh[D/Q,X/Q)+R9[D/Q,X/Q}+RY[D/Q,X/Q]
1 1 1 1 1 1 where: InhalationPathwayFactor,Rf(X/Q} Rf (X/Q] = K'(BR), (DFAg), (mrem /yr per pCi/m3) where: K' = 1 constaat c,f unit conversion, 10G pci/p gi, (BR), = the breathing rate of the receptor of age group (a), in m 3/yr. 2-5
The breathing rates (BR) for the various age groups are tabulated below, as given in Regulatory Guid$ 1.109. Age Group (a) Breathing Rate (m 3/yr) Infant 1400 Child 3700 Teen 8000 Adult 8000 (l>FA.)" 1 = t.he maximum organ inhalation dose factor the receptor of age group (a) for the ith radionuclide, in mrem /pCi. The total body is con-sidered as an organ in the selection of (DFA.) . See Tables 2.2-5, 2.2-6, 2.2-7 and 2.2-8. Inhalation dose factors (DFA.) for the various age groups are given in Tables 2.2-5, 2.2-6, 2.2-7, an8 2.2-8 (taken from Regulatory Guide 1.109 (Rev.1)). Ground Plane Pathway Factor, R [D/Q] Rf[D/Q]=K'K"(SF)DFG[(1-e- g i)/Ay(m 2 mrem /yr per pCi/sec) where: K' = a constant of unit conversion,106 pCi/pCi. K" = a constant of unit conversion, 8760 hr/ year.
= 1 A the decay constant for the ith radionuclide, sec f
t = the exposure time, 4.73 x 10 8sec (15 years). DFG.1
= the ground plane dose conversion factor for the ith radionuclide (mrem /hr per pCi/m2 ).
SF = the shielding factor (dimensionless), 0.7 (Regulatory Guide 1.109 (Rev. 1)). Ground plane dose conversion factors, DFG, are found in Table 2.2-9. Grass-Cow-MilkPathwayFactor,Rf[D/Q] Q (U# ) ff * (1-fPf Je'^i h_ -A.t 1 f Rf[D/Q]=K'E , F,(r)(DFLf ), + e 2 mrem /yr per pCi/sec) (m
- 2-6
where: K' = a constant of unit conversion, 106 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 (Regulatory Guide 1.109 (Rev. 1))
Y = the agricultural productivity by unit area of nasture feed grass, P in kg/m 2 , o,7, Y, = the agricultural productivity by unit area of stored feed, in kg/m 2 , 2.0.
= the stable element transfer coefficients, in ays/ liter, Table 2.2-13.
F, r = f raction of deposited activity retained on cow's feed grass, r = 1 for radioiodine and r = 0.2 for particulates (Reg 21 story Guide 1.109) . (LFL.) 1
= the maximum organ ingestion dose factor for the ith radionuclide for the receptor in age group (a), in mrem /pCi. See Tables 2.1-2, 2.2-10, 2.2-11, and 2.2-12.
A = ti.e decay constant for the ith radionuclide, in sec1 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 = the transport time from pasture to cow, to milk, to receptor, in sec, g 1.73 x 10 5 (2 days) t = the transport time from pasture, to harvest, to cow, to milk, to re-ceptor, in sec, 7.78 x 106 (90 days). f = fraction of the year that .he cow is on pasture (dimensionless), 1.0. p f = fraction of the cow feed that is pasture grass while the cow is on s pasture (dimensionless), 1.0. E. = an adjustment fraction which accounts for the fraction of radionu-clides in elemental form which contribute dose for this pathway, E = 0.5 for radioiodine, E = 1.0 for all others. The concentration of tritium in milk is based n the airborne concentration rather than the deposition. Therefore, the R. C1is based on h/Q}: 2-7
3 Rf[X/Q]=K'K'"F,QU,p(DFL),[0.75(0.5/H)](mrer./yrperpCi/m) p 1 where: K'" = a constant of unit conversion, 103 gm/kg. H = absolute humidity of the atmosphere, in gm/m3, 8 (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. Grass-Cow-MeatPathwayFactor,Rf[D/Q] The integrated concentration in meat follows in a similar manner to the develop-ment for the milk pathway, threfore: Q (U ff (1-fPsf )ei h -A.t R [D/Q] = K' [,ap) F (r)(DFL f g ), (8 + e 1 f I w p s (m2 . mrem /yr per pCi/sec) where: F = the stable element transfer coefficients, in days /kg, Table 2.2-13. f U = the receptor's meat consumption rate for age (a), in kg/yr. U 0 ap(kg/yr) - Infant
- Child 41
- Teen 65
- Adult 110 Taken from Regulatory Guide 1.109 (Rev. 1).
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 based on its airborne concentration rather than the deposition. Therefore, the R'yg is based on [x/Q): 3 R [X/Q) = K'K'"FfF Q U (DFLg ), [0.75(0.5/H)] (mrem /yr per pCi/m ) where all terms are defined above. 2-8
VegetationPathwayFactor,RY[D/Q] 1 _ 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 RI,[D/Q)=K' (# L 1 8 ih (DFL.)a Ufe +Ufe 1 Yy (A.+
1 Aw) 1 aL ag (m2 . mrem /yr per pCi/sec) where: K' = a constant of unit conversion, 106 pCi/pCi. U = the consumption rate of fresh leafy vegetation by the receptor in age group (a), in kg/yr. U = (kg/hr) - Infant 0
- Child 26
- Teen 42
- Adult 64 S
U = the consumption rate of stored vegetation by the receptor in age group
^
(a), in kg/yr. U = (kg/yr) - Infant 0
- Child 520
- Teen 630
- Adult 520 f = the fraction of the annual intake of fresh leafy vegetation grown locally.
f = the fraction of the annual intake of stored vegetation grown Ic. ally. 8 t g = the average time between 4 harvest of leafy vegetation and its consumption, in seconds, 8.6 x 10 (1 day) t = the average time between harvest of stored vegetation and its consumption, h in seconds, 5.18 x 106 (60 days). Yy = the vegetation areal density, in kg/m 2, 2.0. and all other factors are previously defined. Theconcentrationoftritiuminvegetationisbasegontheairborneconcentra-tion rather than the deposition. Therefore, the R fis based on [X/Q): RS[X/Q)=K'K'" UfaL+Ufa g (DFL.)a [0.75(0.5/H)] (mrem /yr per pCi/m3 ). 1 i All terms defined previously. 2-9
2.2.3 QUARTERLY DOSE CALCULATIONS To comply with Specification 6.9.1.8, quarterly cumulative dose contributions resulting from gaseous effluent releases shall be calculated using the calcu-lations listed in section 2.2.1 and 2.2.2. Meteorological conditions concur-rent with the releases of effluents shall be used to calculate the long and short term dispersion factors referenced in sections 2.2.1 and 2.2.2 for these calculations. Doses from radiciodine, radioactive materials in particulate form and radio-nuclides other than noble gases with half-lives gre. or than eight days shall be calculated using the appropriate calculations of section 2.2.2 based on the results of the most current land use census. 2.2.4 31 DAY COSE CALCULATIONS To comply w...h Specifications 3.11.2.2, 3.11.2.3 and 3.11.2.4, cumulative dose contributions shall be determined every 31 days. The calculations to determine 31 day dose contributions may be simplified from those presented in sections 2.2.1 and 2.2.2 based on the dose calculations performed using sc urce terms presented in the FSAR to evaluate compliance with Appendix I to 10CFR50. Based on these calculations, the maximum exposed individual is an infant who consumes milk from a goat (s) grazed in the vicinity of the station and that 95% of the dose is from iodine-131. The simplified calculation to determine the thyroid dose of an infant is: D = 1.75 E5w (Q + q)I-131 where: w = (57q) for food and ground plane pathway, in m 2 from Table 2.2-4 for location of nearest real cow or goat.
= the release of iodine-131 in gaseous effluents, in pCi.
(Q + q)I-131 1.75E5 =(3051{3.17E-8)RC1 [D7Q) with the appropriate substitutions in R [D/Q) for iodine-131. See section 2.2.2. The beta and gamma air doses can be approximated using the xenon-133 activity since it contributes about 45% of the dose; the simplified calculations to determine the beta and gamma air doses are: s s D = 6.96E-11 [Q + q]Xe-133 s s Dp = 2.07E-10 [Q + q]Xe-133 where: X/Q = 2.8E-6 sec/m 3 2-10
6.96E-11 = constant determined from factors prcviously presented 2.07E-10 = constant determined from factors previously presented s s [Q + q]Xe-133 = the total xenon-133 activity released in pCi 2-11
s TAllLE 2.2-1 DISPERSION l'ARAtlETER (Q) FOR LONG TERT! RELEASES > 500 llR/YR OR > 125 IIR/QTR Distance to the control location, in nales Sector 0 0-0.5* 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 1.2E-6 5.2E-7 2.7E-7 1.7E-7 1.2E-7 9.0E-8 7.0E-8 6.1E-8 4.8E-8 NNE 2.3E-6 1.0E-6 5.7E-7 3.6E-7 2.4E-7 2.0E-7 1.4E-7 1.2E-7 9.6E-8 NE 2.3E-6 1.0E-6 5.5E-7 2.9E-7 2.3E-7 1.7E-7 1.2E-7 1.1E-7 9.2E-8 ENE 1.6E-6 6.7E-7 3.6E-7 2.2E-7 1.5E-7 1.0E-7 8.9E-8 8.0S-8 6.6E-8 E 1.1E-6 3.8E-7 2.1E-7 1.4E-7 9.0E-8 7.8E-8 6.1E-8 5.3E-8 4.0E-8 ESE 9.6E-7 3.8E-7 1.8E-7 1.2E-7 8.4E-8 5.5E-8 4.3E-8 4.1E-8 3.4E-8 SE 1.0E-6 4.1E-7 1.7E-7 1.1E-7 8.1E-8 5.7E-8 4.6E-8 4.1E-8 3.3E-8 SSE 1.1E-6 4.4E-7 1.9E-7 1.2E-7 8.3E-8 6.0E-8 5.4E-8 4.8E-8 3.7E-8 S 1.2E-6 5.2E-7 2.7E-7 1.7E-7 1.3E-7 9.0E-8 6.5E-8 6.5E-8 5.2E-8 SSW 2.3E-6 9.0E-7 4.2E-7 2.6E-7 1.8E-7 1.2E-7 9.4E-8 8.3E-8 6.6E-8 SW 2.6E-6 9.3E-7 4.2E-7 2.4E-7 1.7E-7 1.1E-7 9.5E-8 8.6E-8 7.0E-8 WSW 1.6E-6 5.8E-7 2.7E-7 1.5E-7 9.8E-8 6.6E-8 5.5E-8 4.8E-8 3.7E-8 W 1.0E-6 3.8E-7 2.0E-7 1.2E-7 8.6E-8 6.2E-8 5.0E-8 4.3E-8 3.3E-8 WNW 6.8E-7 2.6E-7 1.6E-7 1.0E-7 6.9E-8 5.1E-8 4.2E-8 3.7E-8 3.0E-8 NW 6.4E-7 2.9E-7 1.6E-7 1.1E-7 7.4E-8 5.3E-8 4.7E-8 4.2E-8 3.4E-8 NNW 8.0E-7 3.8E-7 2.1E-7 1.3E-7 8.4E-8 7.2E-8 5.9E-8 5.4E-8 4.4E-8 h Inside EAR
TAllLE 2.2-2 DISPERSION PARAtlETER (li[Q) FOR LONG TERtl RELEASES > 500 lili/YR OR > 125 IIR/QTR Distance to the control location, in miie-Sector 0 0-0._5* 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 2.2E-8 5.8E-9 2.3E-9 1.1E-9 6.5E-10 4.0E-10 2.9E-10 2.4E-10 1.8E-10 NNE 4.8E-8 1.3E-8 5.0E-9 2.4E-9 1.5E-9 9.0E-10 6.4E-10 5.4E-10 4.0E-10 NE 5.2E-8 1.6E-8 5.7E-9 2.6E-9 1.7E-9 1.0E-9 7.0E-10 5.9E-10 4.4E-10 ENE 2.2E-8 6.1E-9 2.3E-9 1.1E-9 6.8E-10 4.2E-10 3.0E-10 2.5E-10 1.9E-10 E 1.6E-8 4.9E-9 2.0E-9 9.0E-10 5.6E-10 3.4E-10 2.4E-10 2.0E-10 1.5E-10 ESE 1.9E-8 4.6E-9 1.8E-9 8.5E-10 5.1E-10 3.1E-10 2.3E-10 1.9E-10 1.4E-10 SE 3.2E-8 8.1E-0 3.2E-9 1.4E-9 8.02-10 5.5E-10 3.8E-10 3.2E-10 2.4E-10 SSE 2.8E-8 7.0E-9 2.7E-9 1.2E-9 7.5E-10 4.6E-10 1 2E-10 2.8E-10 2.1E-10 S 3.9E-8 9.9E-9 3.8E-9 1.7E-9 1.1E-9 6.6E-10 ,.7E-10 4.0E-10 3.0E-10 SSW 5.6E-8 1.4E-8 5.5E-9 2.4E-9 1.5E-9 9.4E-10 6.6E-10 5.6E-10 4.3E-10 SW 7.6E-8 1.8E-8 6.9E-9 3.1E-9 2.0E-9 1.2E-9 8.3E-10 7.1E-10 5.3E-10 WSW 3.1E-8 1.3E-9 2.9E-9 1.3E-9 8.0E-10 4.8E-10 3.5E-10 3.0E-10 2.2E-10 W 2.4E-8 5.8E-9 2.3E-9 1.0E-9 6.3E-10 3.9E-10 2.8E-10 2.4E-10 1.8E-10 WNW 1.3E-8 3.2E-9 1.2E-9 5.6E-10 3.5E-10 2.1E-10 1.6E-10 1.3E-10 9.6E-11 NW 1.6E-8 4.1E-9 1.6E-9 7.3E-10 4.5E-10 2.7E-10 2.0E-10 1.7E-10 1.2E-10 NNW 1.8E-8 4.6E-9 1.8E-9 8.3E-10 5.1E-10 3.1E-10 2.3E-10 1.9E-10 1.4E-10 h Inside EAB
TABLE 2.2-3 DISPERSION PARAMETER (X/9)p FOR SIIORT TERM RELEASES > 500 llR/YR OR >_ 150 llR/QTR Distance to the control location, in miles Sector _0 0-0.5* 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 8.2E-6 3.7E-6 2.0E-6 1.3E-6 9.4E-6 7.2E-7 6.0E-7 5.lE-7 4.4E-7 NNE t.6E-5 7.lE-6 4.2E-6 2.7E-6 1.9E-6 1.6E-6 1.2E-6 1.0E-6 S.7E-7 NE 1.6E-5 7.lE-6 4. 0E-6 2.2E-6 1.8E-6 1.4E-6 1.0E-6 9.lE-7 8.4E-7 ENE 1.lE-5 4.8E-6 2.6R-6 1.7E-6 1.2E-6 8.0E-7 7.7E-7 6.6E-7 6.0E-7 E 7.5E-6 2.7E-6 1.5E-6 1.lE-6 7.lE-7 6.2E-7 5.3E-7 4.4E-7 3.6E-7 ESE 6.5E-6 2.7E-6 1.3E-6 9.0E-i 6.6E-7 4.4E-7 3.7E-7 3.4E-7 3.lE-7 SE 6.8E-6 2.9E-6 1.2E-6 8.3E-7 6.4E-7 4.6E-7 4.0E-7 3.4E-7 3.0E-7 SSE 7.5E-6 3.lE-6 1.4E-6 9.0E-7 6.6E-7 4.8E-7 4.6E-7 4.0E-7 3.4E-7 S 8.2E-6 3.7E-6 2.0E-6 1.3E-6 1.0E-6 7.2E-7 5.6E-7 5.4E-7 4.7E-7 SSW l.6E-5 6.4E-6 3.lE-6 2.0E-6 1.4E-6 9.6E-7 8.lE-7 6.9E-7 6.0E-7 SW 1.9E-5 6.6E-6 3.lE-6 1.8E-6 1.3E-6 8.8E-7 8. '_ E-7 7.lE-7 6.4E-7 WSW l . lE-5 . 4.lE-6 2.0E-6 1.lE-6 7.7E-7 5.3E-7 4.7E-7 4.0E-7 3.4E-7 W 6.8E-6 2.7E-6 1.5E-6 9.0E-7 6.8E-7 5.0E-7 4.3E-7 3.6E-7 3.0E-7 WNW 4.6E-6 1.9E-6 1.2E-6 7.5E-7 5.5E-7 4.lE-7 3.6E-7 3.lE-7 2.7E-7 NW 4.4E-6 2.lE-6 1.2E-6 8.3E-7 5.9E-7 4.2E-7 4.0E-7 3.5E-7 3.lE-7 NNW 5.4E-6 2.7E-6 1.5E-6 9.8E-7 6.6E-7 5.8E-7 5.lE-7 4.5E-7 4.0E-7
- Inside EAB
TAllLE 2.2-4
~
DISPERSION PARA!!ETER (Dh)p FOR Si!0RT TERM RELEASES $ 500 llR/YR OR $ 150 lIR/QTR Distance to the control location, in miles Sector 0 0-0.5* 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 1.5E-7 4.1E-8 1.7E-8 8.3E-9 5.1E-9 3.2E-9 2.5E-9 2.0E-9 1.6E-9 NNE 3.3E-7 9.2E-8 3.7E-8 1.8E-8 1.2E-8 7.1E-9 5.5E-9 4.5E-9 3.6E-9 NE 3.5E-7 1.1E-7 4.2E-8 2.0E-8 1.3E-8 7.9E-9 6.0E-9 4.9E-9 4.0E-9 ENE 1.4E-7 4.3E-8 1.7E 8.3E-9 5.4E-9 3.3E-9 2.6E-9 2.1E09 1.7E-9 E 1.lE-7 3.5E-8 1.5E-8 6.8E-9 4.4E-9 2.7E-9 2.1E-9 1.7E-9 1.4E-9 ESE 1.3E-7 3.3E-8 1.3E-8 6.4E-9 4.0E-9 2.5E-9 2.0E-9 1.6E-9 1.3E-9 SE 2.2E-7 5.8E-8 2.3E-8 1.1E-8 7.0E-9 4.3E-9 3.3E-9 2.7E-9 . 2E-9 SSE 1.9E-7 5.0E-8 2.0E-8 9. 0E-9 5.9E-9 3.6E-9 2.8E-9 2.3E-9 1.9E-9 S 2.7E-7 7.0E-8 2.8E-8 1.3E-8 8.7E-9 5.2E-9 4.0E-9 3.3E-9 2.7E-9 SSW 3.8E-7 9.9E-8 4.0E-8 1.8E-8 1.2E-8 7.4E-9 5.7E-9 4.7E-9 3.9E-9 SW 5.2E-7 1.3E-8 5.0E-8 2.3E-8 ?.6E-8 9.5E-9 7.1E-9 5.9E-9 4.8E-9 WSW 2.1E ' 5.2E-8 2.1E-8 9.8E-9 6.3E-9 3.8E-9 3.0E-9 2.5E-9 2.0E-9 W 1.6E-7 4.1E-8 1.7E-8 7.5E-9 5.0E-9 3.1E-9 2.4E-9 2.0E-9 1.6E-9 WNW 8.8E-8 2.3E-8 8.8E-9 4.2E-9 2.8E-9 1.7E-9 1.4E-9 1.1E-9 8.7E-10 NW 1.1E-7 2.9E-8 1.2E-8 2.5E-9 3.6E-9 2.1E-9 1.7E-9 1.4E-9 1.1E-9 NNW 1.2E-7 3.3E-8 1.3E-8 6.2E-9 4.0E-9 2.5E-9 2.0E-9 1.6E-9 1.3E-9
- Inside EAB
TAB LE 2. 2. 5
- PAGE 1 0F 3 INHALATION DOSE FACTORS FOR ADULTS (MREM PER PCI INHALED)
NUCLIE1 B0NE LIVER T. BODY THYROID KIDNEY LUNG GI-LL' H 3 NO DATA 1.58E-07 1. 58E-0 7 1.58E-07 1.58E-07 1.58E-07 1. 58E-0 7 C 14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4. 26E-0 7 NA 24 1.28E-06 1. 28E-0 6 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 68 7.44E-09 2.85E-09 1. 80E-06 4.15E-0 7 MN 54 NO DATA 4.95E-0 6 7.87E-0/ NO DATA 1.23E-06 1.75E-04 9.67E-06 MN 56 NO DATA 1.55E-10 2.29E-ll NO DATA 1.63E-10 1.18E-06 2. 53E-06 FE 55 3. 07E-0 6 2.12E-06 4.93E-07 NO DATA NO DATA 9.01E-06 7. 54E-0 7 FE 59 1. 47E-06 3. 47E-06 1. 3 2E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 58 NO DATA 1.98E-07 2.59E-0 7 NO DATA NO DATA 1.16E-04 1.33E-05 CO 60 NO DATA 1. 44E-0 6 1.85E-06 NO DATA NO DATA 7.46E-04 3.56E-05 NI 63 5.40E-05 3.93E-06 1. 81E-0 6 NO DATA NO DATA 2.23E-05 1. 67E-0 6 NI 65 1.92E-10 2.62E-11 1.14E-ll NO DATA NO DATA 7.00E-07 1. 54E-0 6 CU 64 NO DATA 1.83E-10 7.69E-il NO DATA 5.78E-10 8.48E-07 6.12E-06 ZN 65 4. 05 E-0 6 1.29E-05 5. 82E-06 NO DATA 8. 62E-0 6 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-0 8 2.12E-03 NO DATA NO DATA NO DATA 1.16E-21 SR 89 3.80E-05 NO DATA 1. 09 E-06 NO DATA NO DATA 1.75E-04 4. 3 7E-05 SR 90 1.24E-02 NO DATA 7.62E-04 NO DATA NO DATA 1.20E-03 9.02E-05 SR 91 7. 74N-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-ll NO DATA NO DATA 2. 06E-06 5. 38E-0 6 Y 90 2.61E-07 NO DATA 7.01E-09 NO DATA NO DATA 2.12E-05 6.32E-05 Y 91M 3.26E-ll 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-ll NO DATA NO DATA 1. 96E-06 9.19E-06
*Taken from Regulatory Guide 1.109 (Rev. 1)
(1 of 3)
TABLE 2.2-5 PAGE 2 of 3 INHALATION DOSE FACTORS FOR ADULTS (MREM PER PCI LNHALED) 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-08 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 7.52E-15 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-ll NO DATA 1.27E-10 1.3"E-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 127M 1.58E-06 7. 21E-0 7 1.96E-07 4.11E-07 5. 72E-0 6 1.20E-04 1.87E-05 TE 127 1.75E-10 8.03E-ll 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE 129M 1.22E-06 5. 84E-0 7 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-ll 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 3.25E-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-0 7 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 17 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 1.4 4.70E-07 1.12E-0 7 (2 of 3)
TABLE 2.2.5 PAGE 3 of 3 INHALATION DOSE FACIORS FOR ADULTS (MREM PER PCI INHALED) NUCLIDE BONE LIVER T.B0DY THYROID KIDNEY LUNG GI-LLI BA 140 4. 88E-0 6 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 1.70"-05 5.73E-05 LA 142 8.54E-11 3.88E-Il 9.652-12 NO DATA NO DATA 7.91E-07 2.64E-07 CE 141 2. 49E-0 6 1. 69E-0 6 1.91E-07 NO DATA 7. 83 E-0 7 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-06 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 147 6. 59E-0 7 7. 62E-0 7 4. 56E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05 W 187 1. 06E-09 S.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 (3 of 3)
TABLE 2.2-6 PAGE 1 0F 3 INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALED) NUCLIDE B0NE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.59E-07 1.59E-0 7 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C 14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6. 09E-0 7 6. 09 E-0 7 6.09E-07 NA 24 1.72E-06 1.72E-06 1. 72E-06 1.72E-06 1.72E-06 1. 72E-06 1. 72 E-0 6 P 32 2.36E-04 1.37E- 8. 95 E-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-ll NO DATA 2.24E-10 1. 90E-06 7.18E-0 6 FE 55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-0 7 FE 59 1.9 9 E-06 4. 62E-0 6 1.79E-06 NO DATA NO DATA 1. 91E-04 2.23E-05 C0 58 NO DATA 2. 59E-0 7 3. 47E-0 7 NO DATA NO DATA 1.68E-04 1.19E-05 CO 60 NO DATA 1. 89E-06 2. 48E-06 NO DATA NO DATA 1.09E-03 3.24E-05 NI 63 7.25E-05 5. 43E-06 2. 47E-06 NO DATA NO DATA 3.84E-05 1. 7 7E-0 6 NI 65 2.73E-10 3.66E-11 1.59E-Il NO DATA NO DATA 1.17E-06 4. 59 E-0 6 CU 64 NO DATA 2.54E-10 1.06E-10 NO DATA 8.01E-10 1.39E-06 7. 68E-0 6 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 91 1.10E-0 8 NO DATA 4.39E-10 NO DATA NO DATA 7. 59E-0 6 3. 24 E-05 SR 92 1.19E-09 NO DATA 5.08E-ll NO DATA NO DATA 3.43E-06 1.49E-05 Y 90 3. 73E-0 7 NO DATA 1.00E-08 NO DATA NO DATA 3.66E-05 6.99E-05 Y 11M 4.63E-ll NO DATA 1.77E-12 NO DATA NO DATA 4. 00E-0 7 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-ll NO DATA NO DATA 3.35E-06 2.06E-05
*Taken from Regulatory Guide 1.109 (Rev. 1)
(1 of 3)
TABLE 2.2-6 PAGE 2 0F 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-0 8 3.40E-09 1.57E-09 NO DAT? 5.15E-09 1.62E-05 7.88E-05 NB 95 2.32E-06 1.29E-06 7.08E-07 NO DATu 1. 25E-0 6 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-0 7 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-0 7 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-0 7 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-0 6 1.02E-06 2.73E-07 5. 48E-0 7 8.17E-06 2.07E-04 1.99E-05 TE 127 2.51E-10 1.14E-10 5.52E-ll 1.77E-10 9.10E-10 1.40E-06 1.01E-05 TE 129M 1. 74E-0 6 8. 23E-0 7 2.81E-07 5. 72E-0 7 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-0 7 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-0 7 5.6:E-05 5. 79E-05 I 130 7. 80E-0 7 2. 24E-06 8.96E-07 1.86E-04 3.44E-06 NO LATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.03E-05 NO DATA 8.11E-07 I 132 1. 99E-0 7 5.47E-0 7 1.97E-07 1.89E-05 8.65E-07 NO DATA 1. 59E-0 7 I 133 1. 52E-0 6 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1. 29E-0 6 I 134 1.11E-07 2. 90E-0 7 1. 05E-0 7 4. 94 E-06 4. 58E-0 7 NO DATA 2. 5 5E-09 I 135 4.62E-07 1.18E-06 4. 36E-0 7 7.76E-05 1. 86E-0 6 NO DATA 8. 69E-0 7 CS 134 6.28E-05 1.41E-04 6. 86E-05 NO DATA 4.69E-0 1.83E-05 1. 22E-0 6 CS 136 6. 44E-0 6 2.42E-05 1.71E-05 NO DATA 1.38E-s5 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-0 7 5. 58E-08 NO DATA 8.285-08 9.84E-09 3.38E-11 BA 139 1.67E-10 1.18E-13 4.87E-12 NO DATA 1.11E-13 8.08E-07 8. 06E-0 7 (2 of 3)
TABLE 2.2-6 PAGE 3 0F 3 INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALED) NUCLIDE B0NE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI E A 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 hs DATA 1.23E-14 4.llE-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-Il 1.32E-ll NO DATA NO DATA 1.27E-06 1.50E-06 CE 141 3. 5 5E-0 6 2.37E-0 6 2.71E-07 NO DATA 1.llE-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.llE-06 1.65E-05 (3 of 3)
TABLE 2.2-7* PAGE 1 0F 3 INHALATION DOSE FACTORS FOR CHILD (MEEM PER PCI INHALED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C 14 9. 70E-06 1. 82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-OL 1. 82E-06 NA 24 4. 35E-06 4. 35E-0 6 4. 35E-0 6 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-0 6 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-0 6 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 CO 58 NO DATA 4. 79E-0 7 8.55E-07 NO DATA NO U..fA 2.99E-04 9.29E-06 C0 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-ll NO DATA NO DATA 2. 21E-0 6 2.27E-05 CU 64 NO DATA 5.39E-10 2.90E-10 NO DATA 1.63E-09 2. 59E-06 9.92E-06 ZN 65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4. 41E-0 6 ZN 69 1.81E-ll 2.61E-ll 2.41E-12 NO DATA 1.58E-11 3.84E-07 2. 75E-0 6 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-0 7 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 RB 89 NO DATA 9.33E-08 7.83E-08 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-0 3 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 6.55"-05 Y 90 1.11E-0 6 NO DATA 2. 9 9E-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. 64L-0 7 Y 91 2.47E-04 NO DATA 6. 59E-0 6 NO DATA NO DATA 7.10E-04 4.97 E-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)
(1 of 3)
TABLE 2.2-7 PAGE 2 0F 3 INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI LNHALED) NUCLIDE B0NE LIVER T. BODY 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 S.07E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07 I 133 4.48E-06 5.49c-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 CS134 1.76E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 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 (2 of 3)
TABLE 2.2-7 PAGE 3 0F 3 INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED) NUCLIDE BONE LIVER T. BODY THYROID 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 PR143 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 (3 of 3)
TABLE 2.2-8* PAGE 1 0F 3 INHALATION DOGE FACTORS FOR INFANT (MREM PER PCI IhTALED) NUCLIDE BONE LIVER T.B0DY 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 C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 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 C0 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 C0 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 "s 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 DATA NO DATA 1.45E-03 4.57E-05 SR 90 2.92E-02 NO DATA 1.85E-03 NO DATA NO DATA 8.03E-03 9.36E-05 SR 91 6.83E-08 NO DATA 2.47E-09 NO 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 Y 90 2.35E-06 NO DATA 6.30E-08 NO DATA NO DATA 1.92E-04 7.43E-05 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
*Taken from Regulatory Guide 1.109 (Rev. 1)
(1 of 3)
TABLE 2.2-8 PAGE 2 0F 3 IN11ALATION DOSE FACTORS FOR INFANT (MREM PER PCI INinI.ED) NUCLIDE B0NE LIVER T. BODY 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-15 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 99:1 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 (2 of 3)
TABLE 2.2-8 PAGE 3 0F 3 INHALATION DOSE FACTORS FOR IhTAh"I (MREM PER PCI INHALED) 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 10 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 4.2SE-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 (3 of 3)
TABLE 2.2-9* PAGE 1 0F 2 EXTERNAL DOSE FACT 3RS FOR STANDING ON CONTAMINATED GROUND (mrem /hr per pCi/m2 ) Element Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 NA-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1. 3 0E-L'. Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 S r-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10
*Taken from Regulatory Guide 1.109 (Rev. 1)
(1 of 2)
TABLE 2.2-9* PAGE 2 0F 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
- Taken from Regulatory Guide 1.109 (Rev. 1)
(2 of 2)
TABLE 2.2-10* PAGE 1 0F 3 INGESTION DOSE FACTORS FOR TEENAGER (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C 14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 NA 24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.3CE-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 6.25E-07 NO DATA NO DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 CO 58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 C0 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 1.9fE-09 NO DATA 1.83E-08 NO DATA 5.16E-08 BR 83 NO DATA NO DATA 5.74E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 3.05E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.98E-05 1.40E-05 NO DATA NO DATA NO DATA 4.41E-06 RB 88 NO DATA 8.52E-08 4.54E-08 NO DATA NO DATA NO DATA 7.30E-15 RB 89 NO DATA 5.50E-08 3.89E-08 NO DATA NO DATA NO DATA 8.43E-17 SR 89 4.40E-04 NO DATA 1.26E-05 NO DATA NO DATA NO DATA 5.24E-05 SR 90 8.30E-03 NO DATA 2.05E-03 NO DATA NO DATA NO DATA 2.33E-04 SR 91 8.07E-06 NO DATA 3.21E-07 NO DATA NO DATA NO DATA 3.66E-05 SR 92 3.05E-06 NO DATA 1.30E-07 NO DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E-08 NO DATA 3.69E-10 NO DATA NO DATA NO DATA 1.13E-04 Y 91M 1.29E-10 NO DATA 4.93E-12 NO DATA NO DATA NO DATA 6.09E-09 Y 91 2.01E-07 NO DATA 5.39E-09 NO DATA NO DATA NO DATA 8.24E-05 Y 92 1.21E-09 NO DATA 3.50E-11 NO DATA NO DATA NO DATA 3.32E-05
*Taken from Regulatory Guide 1.109 (Rev. 1)
(1 of 3)
TABLE 2.2-10 CONT'D PAGE 2 0F 3 INGESTION DOSE FACTORS FOR TEENAGER (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI Y 93 3.83E-09 NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 ZR 95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ZR 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.11E-10 NO DATA 1.27E-04 NB 95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 MO 99 NO DATA 6.03E-06 1.15E-06 NO DATA 1.38E-05 NO DATA 1.08E-05 TC 99M 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.38E-08 5.14E-10 6.062-07 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-09 NO DATA 4.94E-07 NO DATA 7.56E-06 NO DATA 1.88E-04 AG110M 2.05E ';7 1.94E-07 1.18E-07 NO DATA 3.70E-07 NO DATA 5.45E-05 TE125M 3.832-06 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 1.76E-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 134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 NO DATA 5.10E-09 I 135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 NO DATA 1.74E-06 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-35 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 (2 of 3)
TABLE 2.2-10 CONT'D PAGE 3 0F 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 1.9SE-11 NO DATA NO DATA NO DATA 2.42E-06 CE141 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 2.8EE-07 3.74E-08 NO DATA 1.72E-07 NO DATA 1.75E-04 PR143 1.31E-08 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 FD147 9.3EE-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 (3 of 3)
TABLE 2.2-11* PAGE 1 0F 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 C 14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P 32 8.25E-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-06 NO DATA 3.00E-06 NO DATA 8.98E-06 MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 NO DATA 4.84E-05 FE 55 1.15E-05 6.10E- 36 1.89E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 C0 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 IT E-24 BR 84 NO DATA NO DATA 1.98E-07 NO DATA N' DATA NO DATA LT E-24 BR 85 NO DATA NO CATA 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 ':0 DATA NO DATA 1.0zE-09 SR 89 1.32E-03 NO DATA 3.77E-05 NO DATA NO DATA KO DATA 5.11E-05 SR 90 1.70E-02 NO DATA 4.37E-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 S.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.
(1 of 3)
TABLE 2.2-11 CONT'D PAGE 2 0F 3 INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG CI-LLI Y 93 1.14E-08 NO EATA 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 2.62E-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 1.5SE-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 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-03 MO 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-Oo 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 (2 of ?)
TABLE 2.2-11 CONT'D PAGE 3 0F 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.P5E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 BA141 2.00E-07 1.12E-10 6.51E-09 NO D3 rA 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 DAT A 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 NC 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 (3 of 3)
TABLE 2.2-12* PAGE 1 0F 3 INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T.B0DY TiiYROID 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 C 14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 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.~0E-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 DATA 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 C0 60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 NI 63 6.34E-04 3.92E-05 2.20E-05 NO DATA NO DATA NO DATA 1.95E-06 NI 65 4.70E-06 5.32E-07 2.42E-07 NO DATA NO DATA NO DATA 4.05E-05 CU 64 NO DATA 6.09E-07 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-05 ZN 65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ZN 69 9.33E-08 1.68E-07 1.25E-08 NO DATA 6.98E-08 NO DATA 1.37E-05 BR 83 No PATA NO DATA 3.63E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 1.94E-08 NO DATA NO DATA NO DATA LT E-24 RB S6 NO DATA 1.70E-04 8.40E-05 NO DATA NO DATA NO DATA 4.35E-06 RB 88 NO DATA 4.98E-07 2.73E-07 NO DATA NO DATA NO DATA 4.85E-07 RB 89 NO DATA 2.86E-07 1.97E-07 NO DATA NO DATA NO DATA 9.74E-08 SR 89 2.51E-03 NO DATA 7.20E-05 NO DATA NO DATA NO DATA 5.16E-05 SR 90 1.85E-02 NO DATA 4.71E-03 NO DATA NO DATA NO DATA 2.31E-04 SR 91 5.00E-05 No DATA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 SR 92 1.92E-05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 NO DATA 2.33E-09 NO DATA NO DATA NO DATA 1.20E-04 Y 91M 8.10E-10 NO DATA 2.76E-11 NO DATA NO DATA NO DATA 2.70E-06 Y 91 1.13E-06 NO DATA 3.01E-08 NO DATA NO DATA NO DATA 8.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04
*Taken from Regulatory Guide 1.109 (Rev. 1)
(1 of 3)
TABLE 2.2-12 CONT'D PAGE 2 0F 3 INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED) NUCLIDE BONE LIVER T. BODY THYROID NIDNEY LUNG GI-LLI Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA 1.92E-04 ZR 95 2.0(2-07 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-09 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 TE127M 5.85E-05 1.94E-05 7.08E-06 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-03 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 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 NO DATA 7.11E-06 TE132 2.00E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 f.0 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 1.2SE-06 BA139 8.81E-07 5.84E-10 2.55E-08 NO DATA 3.51E-10 3.54E-10 5.58E-05 (2 of 3)
TABLE 2.2-12 CONT'D PAGE 3 0F 3 INGESTION DOSE FACTORS FOR INFANT (MREM PER 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 DAIA 6.86E-05 CE141 7.87E-08 4.80E-08 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 (3 of 3)
s . TABI.E 2.2-13* STABLE ELEMENT TRANSFER DATA B gy F,(Cow) F f Element Veg/ Soil Milk (d/2) Meat (d/kg) H 4.8E 00 1.0E-02 1.2E-02 C 5.5E 00 1.2E-02 3.1E-02 Na 5.2E-02 4.0E-02 3.0E-02 P 1.1E 00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.0E-02 Co 9.4E-03 1.0E-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1.2E-01 1.4E-02 8.0E-03 Zn 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02 3.1E-02 Sr 1.7E-02 8.0E-04 6.0E-04 Y 2.6E-03 1.0E-05 4.6E-03 Zr 1.7E-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E 1 Mo 1.2E-01 7.5E-03 8.0E-03 Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E 01 1.0E-n2 1.5E-03 Ag 1.5E-01 3.0E-02 1.7E-02 Te 1.3E 00 1.0E-03 7.7E-02 I 2.0E-02 6.0E-03* 2.9E-03 Cs 1.0E-02 1.2E-02 4.0E-03 Ba 5.0E-03 4.0E-04 3.2E-03 La 2.5E-03 5.0E-06 2.CE-04 Ce 2.5E-03 1.0E-04 1.2E-03 Pr 2.5E-03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E-06 3.3E-03 W 1.8E-02 5.0E-04 1.3E-03 Np 2.52-03 5.0E-06 2.0E-04
*Taken from Regulatory Guide 1.109 (Rev. 1) +F for goat is 6.0E-2.
2.3 FUEL CYCLE CALCULATIONS To comply with Specification 3.11.2.5 when the calculac.ed doses associated with the effluent releases exceed twice the limits of any one of the specifications 3.11.1.2, 3.11.2.2 or 3.11.2.3, dose or dose commitment calculations to a real individual from all uranium fuel cycle sources shall be performed to assure that there doses are limited to 5 25 mrem to the total body or any organ ex-cept the thyroid, which is limited to 1 75 mrem, over twelve consecutive months. The " Uranium fuel cycle" is defined in 40 CFR Part 190.02(b) as:
" Uranium fuel cycle means the operations of milling or uranium ore, chemical couversion of uranium, isotopic enrichment of uranium, fab-rication of uranium fuel, generation of electricity by a light-watet -
cooled nuclear power plant using uranium fuel, and reprocersing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclerr energy, but excludes mining operations, operations at waste (is-posal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by product materials from the cycle." Based on this definition of the fuel cycle, McGuire Nuclear 3tation is the only facility to be considered in the evaluation of ccepliance with Specification 3.11.2.5. Dose contributions from radioactive liquid and gaseous effluents shall be calculated in accordance with sections 2.1.1 and 2.2.3 of this manual. The dose from direct radiation, skyshine and radiation from the station storage facilities, at the Exclusion Area Boundary is estimated at 1.6E-2 mrem /yr2 ; this dose rate is conservatively estimated assuming no attenuation by of f-site structures or terrain and assuming the dose results frcm radioactive material stored outside the station buildings in the refueling water storage tanks and the reactor makeup storage tanks. Summation of doses from direct radiation and from radioactive ef fluents determines the dose to the maximum exposed individual; doses calculated in this manner are extremely conservative for the real indivi-dual since it is highly unlikely that the real individual is maximumly exposed to all of the limiting pathways. s
! h ' Direct radiation estimates taken from ER section 5.3.4.
3, 2-12
3.0 RADIATION MONITORING SETPOINTS Radiation monitor alarm / trip setpoints shall be calt 41ated for the monitors listed in Tables 3.3-11 and 3.3-12 of the Technical Specifications to assure that the tequirements of Specifications 3.11.1.1 and 3.11.2.1 are not ex-ceeded at any or all release points to the unrestricted area. 3.1 LIQUID MONITORS The following equation shall be used to calculate liquid raJiation monitor setpoints: cf
< C F+f where:
C = the effluent concentation limit implementing 10 CFR 20 fer 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 set point and, if so, represents a value which, if exceeded, would result in concentrations ex-ceeding the limits of 10 CFR 20 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 $ C. Also, note that when (F) is large compared to (f), then F + f a F.) 3.1.1 WASTE LIQUID EFFLUENT LINE As described in section 1.1.1 on release rate calculations for the waste li-quid effluent, the release is controlled by limiting the flow rate of effluent from the station. Although the release rate is flow rate controlled, the radi-ation 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. 3.1.2 CONTAINMENT VENTILATION LNIT CONDENSATE EFFLUENT 1.INE As described in section 1.1.2 on release rate calculations for the contain-ment 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 moni-toring and by routine analyses of the composite sample collected on that line. Since the tank contents are discharged automatically, a maximum tank concen-tration, which also is the radiation monitor setpoint, is calculated to assure compliance with 3.11.1.1. The monitor setpoint and maximum tank concentration is: c$ k
$ 1.25E-4 pCi/ml 3-1
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 calcula-tion, is assumed to be 100 gpm C=MPC = 1.E-7 pCi/ml, the MPC for an unidentified mixture k =2 F = the dilution flow may vary as described in 1.1.1, but is conservatively 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 administratively controlled to assure that the limits of Specification 3.11.1.1 are not exceeded since more than one release source may be released to the condenser cooling water. 3.1.3 CONVENTIONAL WASTE WATER TREATMENT SYSTEM DISCHARGE LINE As described in section 1.1.3 on release rate calculations for the conventional waste water treatmeat system effluent, the effluent is normally considered non-radioactive; that is, it is unlikely the effluent will contain measurable activi'.y 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: c $" k 1 3.6E-5 pCi/ml where: c = the gross activity in undi'ated effluent, in pCi/ml f = the flow rate of undiluted effluent which may vary from 0-600 gpm, but is assumed to be 600 gpm
.=tTC = IE-7 pCi/ml, the MPC for an unidentified mixture k =1 F = the flow may vary from 80 to 50,000 cfs, but is conservatively esti-mated at 80 cfs (3.6E-4 gpm), the minimum flow available 3-2
. s 3.2 GAS MONITORS The following equation shall be used to calculate noble gas radiation monitor setpoints based on Xe-133: K(X/Q)Q.1
< 500 Q = 4.72E-2 C f (see section 1.2.1)
C < 1.29E+3/f where: C = 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 K = from Table 1.2-1 for Xe-133, 2.94E-2 mrem /yr per pCi/m 3 (X/Q) = 2.8E-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. 3.2.1 WASTE GAS EFFLUENT LINE As described in section 1.2.1 on release rate calculations for gaseous effluents, the release is controlled by limiting the flow rate of effluent from the sta-tion. 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. 3.2.2 CONTAINMENT PURGE As described in section 1.2.1 on release rate calculations for gaseous efflu-ents, the release is controlled by limiting the flow rate of effluent from the station. Although the release rate is flow rate controlled, the radiation rconitor setpoint shall be set to terminate the relee ' if the effluent activi-ty should exceed that determined by laboratory analyr 3 and that used to calcu-late the release rate. 3.2.3 CONDENSER AIR EJECTOR The exhaust from the condenser air ejector is normally considered non-radio-active; that is, it is possible but unlikely that the effluent will contain measurable activity above background. It is assumed that no activity is pre-sent in the effluent until indicated by radiation monitoring and confirmed by analysis of grab samples from the line. Since the exhaust is continuous, a maximum concentration of gases in the exhaust, which also is the radiation monitor setpoint, is calculated to assure compliance with 3.11.2.1 The moni-tor setpoint is: C < 1.29E+3/f < 6.45E-1 pCi/ml 3-3
m s where: f = 20 cfm 3.2.4 UNIT VENT Releases as described in 3.2.1, 3.2.2, and 3.2.3 are released through the unit vent, su 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 < 1.29E+3/f < 1.6E-2 pCi/ml where: f = 54,000 cfm (auxiliary building) + 28,000 cfm (containment purge) = 82,000 cfm or may be: C < 1.29E+3/f < 2.4E-1 pCi/ml where: F = 54,000 cfm (auxiliary building ventilation) 3-4
6 Duxc POWER CO>IPANY Powra Betwixo 422 Socru Cucacu STurzT. CiuntoTTr. N. C. 28242 w n u = o. ,* a n ca. s a. January 25, 1979 SCF PACS 63fMT TCLC#=ONC: A# te 704 S eCams PeoswC%O% 373-408) Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Robert L. Baer, Chief Light Water Reactors, Project Branch l'o. 2 Re: McGuire Nuclear Station Units 1 and 2 Docket Nos. 50-369, 50-370
Dear Mr. Denton:
Please find attached ten copies of the Offsite Dose Calculation Manual (0DCM) for McGuire Nuclear Station. This document supplements the radiological effluent technical specifications which were submitted to the staff on December 18, 1978. The attached version of the ODCM is the first draft and it is expected that some changes will be necessary prior to implementation. It is anticipated that a meeting between representatives of the NRC staff and Duke Power would be appropriate after the staff has reviewed both the proposed radiological effluent technical specifications and the ODCM. Very truly y, s,
/ f / l h ';'A.sn G8 &fA's #'
William O. Parker, Jr. ,h ~ GAC:s.cs Attachments (10)
OFFSITE DOSE CALCULATION MANUAL FOR MCGUIRE NUCLEAR STATION DOCKET #50-369, 370
TABLE OF CONTENIS PAGE INTRODUCTION 1 1.0 RELEASE RATE CALCULATIONS 1-1 1.1 LIQUID EFFLUENTS 1-1 1.1.1 WASTE LIQUID EFFLUENT LINE l-1 1.1.2 CONTAINMENT VESTILATION UNIT CONDENSATE EFFLUENT LINE l-2 1.1.3 CONVESTIONAL WASTE WATER TREATMENT SYSTEM EFFLUENT LINE 1-2 1.2 GASEOUS EFFLJENTS 1-3 1.2.1 NOBLE CASES 1-3 1.2.2 RADI0 IODINES, PARTICULATES, AND OTHERS 1-3 2.0 DOSE CALCULATIONS 2-1 2.1 LIQUID EFFLUENTS 2-1 2.1.1 QUARTERLY DOSE CALCULATIONS 2-3 2.1.2 31 DAY DOSE CALCULATIONS 2-3 2.2 GASEOUS EFFLUENTS 2-4 2.2.1 NOBLE GASES 2-4 2.2.2 RADI0 IODINES, PARTICULATES, AND OTHERS 2-4 2.2.3 QUARTERLY DOSE CALCULATIONS 2-10 2.2.4 31 DAY 90SE CALCULATIONS 2-10 2.3 FUEL M LE CALCULATIONS 2-12 3.0 RADIAT'.ON MONITORING SETPOINTS 3-1 3.1 LIQUIE 10NITORS 3-1 3.1.1 WASTE LIQUID EFFLUENT LINE 3-1 3.1.2 CONTAINMENT VEhTILATION UNIT CONDENSATE EFFLUEhT LINE 3-1 3.1.3 CONVENTIONAL WASTE WATER TREATMEhT SYSTEM DISCHARGE LIhT 3-2 3.2 GAS MONITORS 3-3 3.2.1 WASTE GAS EFFLUENT LINE 3-3 3.2.2 CONTAINMENT PURGE 3-3 3.2.3 CONDENSER AIR FJECTOR 3-3 3.2.4 UNIT VENI 3-4
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