Text

Rev 34 to Catawba Nuclear Station Odcm
	ML20094H251
Person / Time
Site:	Oconee, Catawba
Issue date:	01/01/1992
From:	Mccollum W; DUKE POWER CO.
To:	;
Shared Package
ML15217A135	List: ML15217A134; ML16131A522; ML16131A524; ML20094H239; ML20094H251;
References
	PROC-920101-02, NUDOCS 9203090207
	Download: ML20094H251 (57)
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{{#Wiki_filter:_ - _- __ ___ _ _________ - _ ______ _ ___-___ - _ December 26, 1991

SUBJECT:

Offsite Dose Calculation Manual novision 34 i The General offico RadWaste Proconsing & Management Staff is transmitting to you this dato, Rovision 34 of the Offsito Doso Calculation Manual. As this rovision only affects Catawba i 11uclear Station, the approval of other station managers is not required. Picaso update your copy lio. _fL, and discard the affocted pages. Instructions: Please replace the entire contonts of Seculon "C" except rigure C5.0-1 (1 of 2) With the attached package. !JOTE: As this letter, with its attachments, contains "LOEP" information, please insert this in front of the December 24, 1991 letter. Approval Dato: n/2 8/t/ Approval Dato

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Etfoctive Dato: 1/1/92 Effective Dato: 1/1/92 ,_E 6)h h/' /k W / 'l / / G. L. Courthey / W. R. McCollum, Mamiger Radiation Protection Manager Catawba lluclear Station If you have any questions concerning Revision 34, please call Jim Stewart at (704) 373-5444. / rrte Y ? /, James M. Stewart, Jr. Scientist Radwaste Processing & Management JMS/prm 091 l l O 9203090207 920228 PDR ADOCK 05000269 p PDR _._._..__.~__.,.___.___.~.._._.____.,__._..__.._.___.._..-.m

F i I i ll P 1 L I i L i l I I I I i i i . i I l } l 1 i . l APPEND 1X C l CATAWBA NUCLEAR STATION 1 l SITE SPECIFIC INFORMATION j i l - t 1 i i 1 l i b l-1 4 h in h i 4.. 1 i :. i ) lI t i L9 4 s a.

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Pane Ci.0-CATAWB A NUCLEAR STATION RADWASTE SYSIQ13........ C-1 l C2.0 Ef,IIASE RATE CALCULATION, C-3 C3.0 RADIATION MONITOR SETPOINTS C-7 C4.0 DOSE CALCULATIONS C-11 C5. 0. RADIOLOGICAL ENVIRONMENTAI.,1!ONITORING C-18 i .o O O Rev. 34 1/1/92

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LIQUID RADVASTE P30CEF> SING The liquid radwaste system at Catawba Nuclear Station (CNS) is used to collect- "and treat f! aid chemical and radiochemical by-products of unit operation. The . system produces effluents which can be reused in the plant or discharged in small, dilute-quantities to the environment. The means of treatment vary with waste type and desired product in the various systems:

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Filtration - All waste sources are filtered during processing, In some cases, such as the Laundry and flot Shower Tank (LHST) Subsystem of the Liquid Vaste (VL) System, filtration may be the only treatment required. B) Adsorption - Adsorption of halides and organic chemicals by activated charcoal (Carbon Filtration) can be used as needed for the waste streams in the WL System, =C)- Ion Exchange - Ion exchange is used to remove radioactive cations (cobalt, manganese) and anions (iodone) from the waste streams. This process _can be used on all waste streams as needed. D) Gas Stripping - The fluids processed in the WL System does not contain entrained fission gases. Those fluids that are processed for recycle, however, do contain entrained fission gases, Removal of these gaseous radioactive fission products is accomplished in both the NB and WL Evaporators. These gases are stored in the Waste Gas Holdup System for decay _ prior to release, E Distillation and Concentration - Evaporation is used to process rO ) recyclable liquids for reuse in the primary systems. However, the (_,) evaporators can-be used to process non-recyclable fluids in an emergency situation. In this case, the distillate would be recycled to the primary -systems while the concentrates would be solidified and routed to an approved low-level waste disposal site, Figure.Cl.0-1 is a schematic representation of the liquid radwsste system at Catawba. C-1 Rev. 30 1/1/91

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f* _ Table C1.0-1 ABBREVIATIONS Systems: CM --Condensate System KC. Component _ Cooling NB - Boron Recycle RL - Low Pressure Service Water RN - Nuclear Service Water System WC - Conventional Waste Water Treatment WL - Liquid Waste Recycle WP - Turbine Building Sump WS - Nuclear Solid Waste Disposal Tanks: BA - Boric Acid Tank FDT - Floor Drain Tank -IJIST - Laundry and-llot Shower Tank MST - Mixing and Settling Tank ( NCDT - Reactor Coolant' Drain Tank RHT - Recycle Holdup Tank RMT - Recycle-Monitor Tank RMWST - Reactor Makeup Water Storage-Tank SGDT - Steam Generator Drain Tank VUCDT - Ventilation Unit Condensate Drain Tank WDT - Waste Drain-Tank WEFT - Wastel-Evaporator Feed Tank WMT - Waste Monitor Tank-Table C1.0-1 i Rev. A 7/18/84

.~ .= 4 --pl.- 2 GASEOUS RADVASTE SYSTEMS. DbegaseouswastedisposalsystemforCatawbaisdesignedwiththecapability. of-processing the fission product gases from contaminated reactor coolant fluids resulting from operation. The system shown schematically in Fig. C1.0-L2 is designed to allow for the retention and subsequent decay of the gaseous fission _ products generated from the reactor coolant system via the chemical and volume control system and/or the boron recycle system in order _ to limit the need for intentional discharge of high level radioactive gasen from the waste gas holdup tanks. Sources of low-level radioactive gaseous discharge to the environment include periodic purging operations of the containment, the auxiliary building ventilation system, the secondary system air ejector and -decayed WG Tanks. With respect to purging operations, the potential contamination is expected to arise from uncollectible reactor coolant leakage. With-respect to the air ejector, the potential source of contamination will be from leakags of the reactor coolant to the secondary system through defects _ in steam generator tubes. The gaseous waste disposal system includes two waste gas compressors, two catalytic hydrogen recombiners, six gas decay storage tanks for use during normal power generation, and two gas decay storage tanks for use during shutdown -and startup operations, and for pressure relief. Cl.2.1 Gas Collection System - The gas collection system combines the waste hydrogen and fission gases f rom the volume control tanks and that from the boron recycle-gas stripper evaporator produced during normal operation with the gas collected during the shutdown degasification (high percentage of nitrogen) and cycle it through the catalytic recombiners converting all the hydrogen to water. After the water 'is removed, the resulting gas stream is transferred from the recombiner into -the gas decay tanks.-where the accumulated activity may be contained. From the decay tanks the gas will flow back to the compressor suction to complete he circuit, b tl.2.2 Containment and; Auxiliary Building Ventilation Nonrecyclable reactor coolant leakage occurring either inside the containment or inside the auxiliary building will generate gaseous activity. Cases resultaing from leakage inside the containment will be contained until the containment air is released through the VQ or Vp system. The containment atmosphere will be discharged:through a charcoal adsorber and a particulate filter prior to release to the atmosphere. Gases-resulting from leakage inside the auxiliary building are released, with-out further decay, to the atmosphere via the auxiliary building ventilation system. The ventilation exhaust from-potentially contaminated areas in the auxiliary building is normally unfiltered. However, on a radiation monitor alarm, the exhaust is passed through charcoal adsorbers to reduce releases to the atmosphere. C1.2.3 Secondary Systems - through I. condensate flow and steam generator blowdown will go parallelof the 5 condensate polis Normally harmful ions from the water. Noncondensable gases will be taken from the secondary system by the condenser steam air ejector and are passed through a radiation monitor to the unit vent. Figure C1.0-2 is a schematic representation of the gaseous radwaste system at -Catawba. C-2 Rev. 34 Ul/92

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.0 RELEASE RATE CALCULATION A Deneric release rate.:alculations are presented in Section 1.0; these calcula- -tions will-be used to calculate release rates for Catawba Nuclear Station. C2.1 LIQUID RELEASE RATE CALCULATIONS There are two potential release points at Catawba. They are as follows: 1. Liquid Waste Effluent Discharge Line (WL) 2. Conventional Vaste Water Treatment System Effluent Line (WC) C2.1.1 Liould Waste Ef fluent Discharge Line (WM There are three low pressure service water pumps with a minimum flow rate of-16,500 gpm each and four. nuclear service water pumps with a minimum flow rate of 9,000 gpm each which provide the required dilution water needed for a release. The LPSV system flow rate monitor has a variable setpoint which terminates the release-by closing an isolation valve should the dilution flow . fall below the setpoint. Releases can either be made via EMF-49 which uses isolation valve IWL124, or EMF-57 which uses isolation valve IWLX28. The following is a typical equation which can be used to calculate a discharge flow, in gpra, f5FRL'I I I l 'i=1 MPC g where: f = the undiluted effluent flow, in gpm. F

8Ctual I w pressure service water flowrate. In gpm.

RL o = the recirculation factor at equilibrium (dimensionless), 1.027. Q 120 efs = 1.027 i g, y4 ,g4 4400 cfs g!! where: Q = average dilution flow (120 cfs) R Q = average fl w past Wylie Dam (4400 cfs) H C = the concentration of radionuclide, 1.-in-undiluted effluent as i determined by laboratory analyses, in pC1/ml. MPC = the concentration of radionuclide, i, from 10CFR20, Appendix-B, i Table II, Column 2. If radionuclide, i, is a dissolved noble gas, the MPC = 2.0E-04 pC1/ml. 1 X = f actor used to reduce the WL-flowrate ( f) to allow the WC system to release simultaneously. F::r example. 0.9 would' allow 10. of the stations releases to b+ WC. l l C-1 Revi 20 7/1/88

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,.dg.l.2 Conventional Waste Water Treatment System Ef fluent Line (VC) a conventional waste water treatment system effluent is potentially radio-active; that is, it is possible the effluent will contain measurable activity above background.

it.is assumed that no activity is present in the effluenc until indicated by periodic analysis of the composite sample collected on that line. The water sources listed below that are normally discharged via the conventional waste water treatment system and/or the Turbine Building Sump. - will be diverted -if they will cause the WC discharge. to exceed cdministrative ' limits designed-to ensure that station releaso limits will not be exceeded. l a. Section Deleted 1/1/92-Revision 34 b. Auxiliary Feedwater Sump Pumps and Floor Drain Sump Pump Line Normally the discharge line coming from these sumps will discharge into the Turbine Building sump, but if activity is detected above its monitor's setpoint, the discharge flow will automatically be routed te the floor drain tank,for processing and later be discharged through the liquid waste ef fluent line. Subsequent radioactive releases may be allowed to discharge into the TBS if administrative 1y controlled to assure that release limits are not exceeded, c. Steam Generator Blowdown Line Normally the discharge from the Steam Generator Blowdown will be pumped to the Turbine Building Sump, but if activity is detected above its monitor's setpoint, each blowdown flow control valve, the atmospheric vent, and the valve to the Turbine Building Sump will close, thus terminating"the discharge. Blowdown can only be continued by venting the steam to "D heater and pumping the liquid to the condensate system. Turbine Building Sump Discharge Line Normally the discharge from the Turbine Building sump will go into the .. act1/ity is detected conventional waste water treatment system, but above its monitor's setpoint, the sump pumps A, B, and C will stop and an alarm actuated. The Turbine Building sump discharge line can then either be routed to the steam generator drain tanks for processing, or allowed to continue-being discharged via the circuit with proper administrative controls implemented to assure-that release limits are not exceeded. Ov) .e C-4 Rev. 34 1/1/32

2 GASEOUS RELEASE RATE CALCULATIONS \\ ne unit vent is the release point for waste gas decay tanks, containment air releases,.the condenser air ejector.-and auxiliary building ventilation. The-condenser air ejector-effluent is normally considered nonradioactive;-that is, it is unlikely the effluent will contain measurable activity above background. It-is assumed.that no activity is present in the effluent until indicated by. radiation monitoring measurements and/or by analyses of periodic samples collected on that--line. Radiation. monitoring alarm / trip setpoints in con- -junction with administrative controls assure that release limits are not exceeded; see section C,3.0 on radiation monitoring setpoints. The Auxiliary Monitor "ank Building ( A!ffB) ventilation system and lab hoods are exhausted directly through 4 vent on the AMTB. The process areas of the AMTB ventilation pass-through particulate and charcoal filters, The effluent is normally considered nonradioactive;-however, the potential for release of radioactive effluents remains with certain job evolutions that may take place in the AMTB. The following calculations, when solved for flowrate,. are the release rates ' for ' noble gases and for radiciodines, particulates and other radionuclides with half-lives greater than 8 days; the most conservative of release rates calculated in C2.2.1 and C2,2.2 shall control the release rate for a single release point, 48% of the controlling release rate calculated is apportioned .co the unit _ vent--and 2".' is apportioned to the.AMTB vent (assuring simultaneous releases from both points do not exceed the controlling release rate for a single point). C2.2.1 Noble Gases [(I[6)h]g _ < 500 mrem /yr, and IK g I (Lg + 1.1 M ) [(T/6)h] < 3000 mrem /yr g g where the terms are defined below. ^ C2.2.2 Radiciodines. Particulatas. and Other Radionuclides With T 1/2 > 8 Days g (W h j < 1500 mrem /yr IP g t -where: -K =.The total-body dose factor due to gamma emissions for each identified ~ i 3 noble gas radionuclide, in mrem /yr per pC1/m from Table 1.2-1. L = The skin dose f actor due to beta emissions for each identified' noble i gas radionuclide, in mrem /yr per pC1/m' from Table 1.2-1. 'M = The air dose factor due to gamma emissions-for each identified noble 1 gas radionuclide, in mrad /yr per pCi/m' from Table 1.2-1-(unit conver-sion-constant of 1.1 mrem / mrad converts air dose to skin dose). P = The dose parameter for radionuclides other than noble gases for the i inhalation pathway,2 in mrem /yr per pC1/m' and for the food and ground plane pathways.In m.(mrem /yr) per pCi/sec-from Table 1.2-2. The dose - f actors are based on the critical individual organ and most restrictive age group (child or infaut). OVI = The release rate of radionuclides, i, in gaseous effluent from all release points at the site, in pC1/sec. C-5 Rev. 34 1/1/92

. ~ . - -, ~ ~ -., -..- - - -.. - _ ~, ~. -. O' (5/Q) = 3.10E-05 sec/m. -The highest calculated annual average relative 8 _ concentration (dispersion parameter) for any. area at or beyond the' unrestricted area boundary. -llua location is the NNE sector '@ 0.5-miles. W = The highest calculated' annual average dispersion parameter for- -estimating'the dose to an individual at a location in the unrestricted area where the total inhalation,--food and ground plane pathway dose is - determined to be a maximum based on operational source term data, land use surveys, and NUREG-0133 guidance. W = 3.lE-05 sec/m', for-the inhalation pathway. The location is the NNE sector @ 0.5 miles. W =-1.lE-07 meter'#,-for the food and ground plane pathways. The A location -is : the NNE sector @ 0.5 miles. h=kCf6 g k 4.72E+2C f = t g where: C = the concentration of raddonuclide. 1, in undiluted gaseous effluent, i-in pCi/ml. f = the undiluted effluent flow, in cfm 3' k = conversion factor, 2.33E4 ml/ft i -ks = conversion factor, 6El sec/ min D. -Q-l l 1 I' C-6 Rev, 34 l 1/1/92

.0 RADIATION MONITOR SETPOINTS 'J\\- esing the generic calculations presented in Section 2.0, final effluent radiation monitoring'setpoints are calculated for monitoring as required by -the Technical Specifications. All radiation monitors for catawba are of f-line except EMF-50 (Waste Gas System) which is-in-line..These monitors: alarm on. low flow; the minimum flow-alarm-level for both the liquid _ monitors and the gas monitors is. based on the 1 manufacturer's recommendations except-EMF-50. These monitors measure the activity in the liquid or gas volume exposed to the detector, Liquid monitors indepencent of flow rate-if a minimum flow rate is assured. -Gaseous are monitors are dependent on pressure or vacuum. Particulate monitors are depenoent on flow rates. Radiation monitoring setpoints calculated in the following sections are expressed-in activity concentrations; in reality the monitor readout is in counts per minute. Station radiation monitor setpoint procedures which correlate concentration and counts per minute shall be based on_the following relationship: r C " 2.22 x 10e V where: c = the gross activity, in pC1/ml r = the count rate, in cpm 2.22 x 10 = the disintegration per minute per pC1 -e = the counting efficiency, cpm /dpm V = the volume of fluid exposed to the detector, in ml. ( for those occurrences when simultaneous releases of radioactive material must x -te made, monitor setpoints will be adjusted downward in accotdance with Station Procedures to insure that instantaneous concentrations will not be exceeded. C3.1 LIQUID RADInTION-MONITORS EMF 49 and EMF 57 l -C3.1.1 Weste Liouid Effluent Line 'As described in Section C2.1.1 on release rate calculations for the waste liquid effluent, the release is controlled by limiting the flow rate of effluent from the station. Although the release rate is flow rate controlled, -the radiation monitor _ setpoint shall be set to terminate the release if the

effluent activity should exceed that determined by laboratory analyses and used to calculate the release rate.

A typical radiation monitor setpoint may be calculated as follows: c 5 MPC F 2.48E-05 pC1/ml o where: c = the gross activity in undiluted effluent, in pC1/ml f = the flow from the tank may vary from 0-100 gpm but, for this calculation, is assumed to be-100 gpm. ' MPC = -1.0E-07 pCi/ml, the MPC for an unidentified mixture o = 1.027 (See Section C2.1.1) = the dilution flow may vary as described in section C2.1.1, but is conservatively estimated at 25,500 gpm, the minimum flow available. C-7 Rev. 20 7/1/88

~-. .. ~. prmally, discharges - from-the WL-system will be limited. to either EMF-49 or CaIF-57. Simultaneouscreleases may occur, however, if proper station ytocedures are followed to insure that-instantaneous concentration limits will not be exceeded. C3.1.2 Section Deleted 1/1/92 Revision 34 C3.1.3 Anvillarv Foodwater Sumn Pumos and Floor Drain Sumn Pumn - EMF 52 As described in Section C2.1.2 on release rat a calculations for the auxiliary feedwater sump pumps and floor drain sump pump offluents,-it is possible that the effluent will contain measurable activity above background, it is assumed that the effluent activity is less than the monitors setpoint until indicated' by a radiation alarm. Since the sumps are discharged automatically, the radiation monitor setpoint will initially.be set at 1.0E-06 Ci/ml (the monitor's minimum practical setpoint) plus background to assure that no activity is unknowingly discharged into the-Turbine Building sump. The set-point may be changed after initial detection to allow positive control of effluent releases using the guidance given in Section C3.1.5. C3.1.4 Steam Generator Blowdown Line - EMF 34 As described in Section C2.1.2 on Release Rate Calculations for the Steam Generator Blowdown, it is possible that the effluent will contain measurable activity ~above its monitors setpoint. It is assumed that no activity is-present in.the effluent until indicated by radiation monitoring. Since the the radiation Steam Generator Blowdown line is discharged automatically (, monitor setpoint will be initially set at 1.0E-06 pCi/ml the monitor's minimum practical setpoint) plus background to assure no activity is unknowingly discharged into the Turbine Building sump. The setpoint may be changed after detection to allow positive control of effluent releases using ]heguidancegiveninSectionC3.1.5. C-8 Rev. 34 1/1/92

3.1, 5 Turbine Buildine Sumo Discharce Line --EMP 31 L a described.in Section C2.1.2 on release rate calculations for the turbine building sumps, it is possible that the effluent will contain measurable-activity above its monitor setpoint. Since the sump contents are discharged

automatically, the radiation. monitor setpoint will be initially set at 1.0E-06 Ci/ml (the monitor's minimum practical setpoint) plus background to assure that no activity.is unknowingly discharged into the WC system.-

Should radioactive effluent releases need to be made from the TBS via the WC system a typical monitor setpoint may be calculated as follows: c 5 MPC x F 5 1.42E-06 pC1/ml where: c = the gross activity-in undiluted effluent, in pCi/ml f = the undiluted effluent flow in spm for this examole the flow is from the Turbine Building Sumps and is assumed to be 250,000 gallons / day or 175 gpm. MPC = 1.0E-07 pCi/ml, the MPC for an unidentified mixture o = 1.027 (See Section C2.1.1) F = the dilution flow,.-in gpm, available to dilute the undiluted effluent -discharge flow -( f); for this example it is assumed that 2550 gpm (10% of the stations RL minimum flow) will-be used to dilute the discharge of the WC system.. This flowrate will allow the WC system to discharge 10% of the stations MPC and dose limits. O o( ' C-9 Rev. 13 1/1/87

~ C3.2-GAS MONITORS Y-b he following equation shall.be used to calculate noble gas radiation monitor setpoints based-on Xe-133 (!Ilstorical data.shows that Xe-133 is the predominant isotope): K(X/Q) Q < 500 (see Section C2.2,1) _g Q== 4. 72E+02 C f (see Section C2.2.2) g g LC _< 116/f g where: C = the gross activity in undiluted ef fluent, in pC1/ml g f = the flow from the tank or building sources, in cfm K = from TableLI.2-1 for Xe-133, 2.94E+2 mrem /yr per pC1/m' X/Q = 3.1E-05, as defined in Section C.2.2.2 As stated in Section C2.2, the unit vent is the release point for the contain-ment purge ventilation system, the containment air release and addition system, the condenser air ejector, -and auxiliary building ventilation. The Auxiliary Monitor-Tank-Building (AMTB) vent is the release point for the AMTB ventilation. 98% of the single point controlling release rate is apportioned to the unit vent and 2% is' apportioned to the AKfB vent. For releases from the containment purge ventilation system, a typical radiation monitor setpoint may be calculated as follows: C 4.98(116/f) = 6.46E-4 g where: - f = 150,000 cfm (auxiliary building ventilation) + 26,000 cfm (containment purge) = 176,000 cfm For releases from the AMTB-ventilation a typical radiation monitor setpoint may.be calculated as follows:. Cg <.02(116/f) = 2.11E-4 where: f = 11,000 cfm (AMTB ventilation) For release from the containment air release and addition system, the waste gas decay tanks, the condenser air ejectors, and the auxiliary building ventilation, a' typical radiation monitor setpoint may be calculated as follows: Cg < 116/f = 7.73E-04 l where: f = 150,000 cfm (auxiliary building ventilation) O C-10 Rev. 34 1/1/92 l

.0 DOSE CALCULATIONS 4;l-FREQUENCY OF CALCULATIONS Dose contributions to the maximum individual shall be calculated at'least .every -31 days, quarterly, semiannually, and annually-(or as required by Tech-nical-Specifications)-using the methodology in the generic information

sections or the LADTAP and GASPAR computer programs.

Example input templates for Catawba LADTAP and GASPAR computer program calculations are provided in Figures C4.0-1 and C4.0-2. One of these methods shall also be used for any special reports. Station long-term historical and dose projection' calculations are periodically performed to determine the station's status with respect to meeting annual ALARA goals specified in the Catawba Nuclear Station Selected Licensing Commitment Manual. Such calculations are used to verify that adequate margin remains during a-report period to allow normal stations and radwaste system operation, including anticipated operational occurrences, for the remainder of the report period withouit exceeding applicable goals. Station dose projections can be performed using generic methodology,-LADTAp end/or GASPAR, or simplified dose calculation methods presented in Section C4.3. Dose calculations that are required for individual pre-release calculations, and/or abnormal releases shall not be calculated using simplified dose calculation methods. Station dose projections for these types and others that are known to vary from the station historical averages shall be calculated by using-the methodology in the generic information sections or the LADTAP and/or GASPAR computer codes. Fuel cycle dose calculations shall be' performed annually or as required by special reports. Dose contributions shall be calculated using the methodology p n the appropriate generic information sections or the LADTAP and GASPAR g omputer programs. C4.2 DOSE MODELS FOR MAXIMUM EXPOSED INDIVIDUAL C4.2.1 Licuid Effluents Generic methodology for calculating liquid pathway exposures to the maximum individual is presented in Section 3.1.1. Catawba site specific parameters to be used in the generic methodology are presented as follows: .= Tables C4.0-3 through C4.0-6 A,gg F, = (f x o) / (F + f) (0.027 default for projections)

Where:

Catawba average liquid radwaste flow, gpm (5,34E+04 default for F = projections --based on 120 cfs) Recirculation f actor at equilibrium, 1.027 o = Catawba average dilution flow for period of interst, gpm (1.97E+06 F = default for projections - based on 4400 cfs) An input template for Catawba LADTAP computer program calculations is provided in Figure C4.0-1. The input template includes default dilution parameters. Radionuclide release input (Ci/ period) and optional non-default dilution flow (CFS) parameters are necessary to perform LADTAP calculations to determine offsite dose impact from specific releases during the period that dilution flow is averaged over. l C-11 Rev. 34 1/1/92 L

. - - = C4.2.2 Gaseous Effluents .2.2.1 Noble Gases . Gamma Air and Bata Air Dose Generic methodology for calculating noble gas airboine pathway gamma air (Dy) and beta air (D ) doses is presented in Section 3.1.2.1. Catawba site-specific parame,ters to be used in the generJc methodology are presented as follows: 3 3.10E-5 sec/m. The highest calculated annual average relative .(X/Q) = concentration for any area at or beyond the unrestricted area boundary. The location is the NNE sector @ 0.5 miles. An input template for Catawba GASPAR computer program noble gas airborne pathway gamma air (Dy) and beta air (D.) dose calculations is provided in Figure C4.0-2, Location 1. The input template includes the maximum Catawba site specific annual average relative concentration parameters, edinnuclide release input (C1/ period) and optional non-default relative co.-~ ton parameters are necessary to perform GASPAR calculations to det._ wine offsite dose impact from specific releases. C4.2.2.2 Radiolodines, Particulates, and Other Radionuclides with T 1/ 2 ) 8 days Generic methodology for calculating airborne pathway maximum organ (D,,) exposures to the maximum individual is presented in Section 3.1.2.2. cxternal exposure from deposited ground contamination and inhalation exposure pathways are considered to exist at all locations offsite. Food pathways (i.e., vegetable, meat and milk) are analyzed only at locations where site surveys pve verified vegetable gardens, meat producing animals, or cow / goat milk .roducing animals exist, however. Therefore, the location of the maximum ndividual may vary depending on the mixture and levels of radionuclides released during a period of time. Additionally, the critical (or limiting) age group and organ will var location (i.e., combination of dose pathways contributing. dose) y based on theand mixture / level of radionuclide releases during the release period. Performing calculations separately for all potential maximum locations, age groups and organs assures that a maximum 1ccation is identified, and that a conservative estimate is obtained for maximum of fsite dose impact _lo any organ or age group __ Catawba site specific meteorological dispersion (X/Q) and deposition (D/Q) parameters and applicable terrestrial / food pathways for the potential maximum locations to be analyzed using generic methodology are presented in Table C4.0-7. An input template for Catawba GASPAR computer program airborne pathway maximum organ (D dose calculations is provided in Figure C4.0-3, Locations 1 - 5. RadionucIl)de release input (C1/ period) and optional not.-default meterological parameters and pathway applicability flags are necessary to perform GASPAR calculations to determine offsite dose impact from specific releases. \\ C-12 Rev. 34 1/1/v2 i l

I 3 "" ''"^ (~24.3.1 w Liould Effluents For dose estimates, a simplified calculation based on the assumptions presented in Section C4.'2.1 and operational source term data is presented below. Updated operational source term data shall be used to revise these calculations as necessary, m D 'B = 6.26E+05_E (F,)(T,) (CCs-134 + 0.59 CCs-137) b f=1-where: 6.26E+05 = 1.14E+05 (U,,/D, + U,f SF ) DF,g (1.08) 1 where: 8 1.14E+05 = 10pci/pCi x 10 ml/kg + 8760 hr/yr U,, a 730 f /yr, adult water consumption D = 37.7, dilution factor from the near field area to the nearest potable W water intake. U,g-= 21 kg/yr, adult fish consumption BF = 2.00E+03, bioaccumulation factor for Cesium (Table 3.1-1) g DF'it = 1.21E-04, adult, total body, ingestion dose factor for a Cs-134 (Table 3.1-2) 0.08=factorderivedfromtheassumptionthat93%ofdoseisfromCs-134 and Cs-137 or 100% + 93% = 1.08 And where: L1-- p r F+f where: f =. liquid radwaste-flow, in gpm o = recirculation factor at equilibrium, 1.027 (see Section C2.1.1) F = dilution flow, in gpm i l l i l l l C-13 Rev. 34 1/1/92

i I i Snd,where' A -T = The length of time, in hodrs, over whicii CCs-134. CCs-137. and F 8 0 are-averaged. 'CCs-134 = the~ average = concentration of Cs-134 in-undiluted offluent, in pC1/ml, during the-time period considernd. C _the average concentration'of Ca-137 in undiluted effluent, in Cs-137 _uci/ml-during the time period considered. 0.59. = The ratio of the adult total-body ingestion dose-factors for Cs-134 and Cs-137 or 7.14E-05 + 1.21E-04 = 0.59 - 9 o I l 9 C-14 Rev. 24 l-1/1/89 l 1.- . -..... -..,. - - -.,, - - -. - - ~.

s._. ~- m 7 4.-3.2 Gas echs ' E f fluent s -r). %eteorological data is provided in Tables _C4.0-1 and C4.0 2. C4.3.L 1 - Noble Gases For dose estimates, simplified dose calculations based on the assumptions in

C4.2.2. I and operational source term data are presented below.. Updated operational source term data shall bo 1 sed to revise these calculations'as necessary.

These calculations further assume that the annual average dispersion parameter-is used and that Xenon-133 contributes 45% of the gamma l' air = dose and'80% of the beta air dose. D-=3,47E-10[h]Xe-133(2.22) _y D = _ _1.03E-09 ;[Q]ye,3 33 (l. 25) 3 -where: 3.47E-10.= (3.17E-8)(353) (X/Q), derived from equation presented in Section 3.1.2.1. 1 1.03E-09 = ( 3.17E-08) (1050) IY7Q). _'darived from equation presented in Section 3.1.2.1. -X/Q =_3.1E-05 sec/m', as defined in Section C2.2.2 {Q]y,,333 = the total-Xenon-133 activity released in uCi 2.22 =' factor derived from the' assumption that 45% of the gamma air dose is contributed _by Xe-133. .25 = factur derived from the assumption _ that 80% of the bata air dose is contributed by Xe-133. C4.3.2.2 Radiciodines, Particulates, and Other Radionuclides with T 1/2 ) 8 days For dose estimates,. simplified dose calculations' based on the assumptions in C4.2.2.2--and operational source term data are presented below. Up.in t ed operational source term data shall. be used to revise these calculations as necessary. These-calculations-further assume that the annual average l dispersion / deposition parameters are used and that 78% of.the dose results from H-3 ingested by the maximally axposed individual via the vegetable garden pathway at the controlling-location. The simplified dose estimate for exposure to the thyroid of a child is: D = 1.28E-04 w (Q)H-3 (1.28) l where: .w = 2.5E-05 = X/Q for vegetable garden pathway, in sec/m' from Table C4.0-1 for the controlling location (S sector at 0 miles). (h);g,3 = the total Tritium activity released.in pC1. 1.28E-04'=(3.17E-08)(R{[X7Q])withtheappropriatesubstitutionsfor child thyroid vegetable pathway f actor, RY [X7Q) for H-3. 1 See Section 3.1.2.2. C-15 Rev_ 24 1/1/92 .. ~

1.28 = factor derived from the assumption that 78* of the total l'_'\\ inhalation, food and ground plane pathway dose to the maximally () exposed individual is contributed by H-3 via the vegetable garden pathway. C4.4 FUEL CYCLE CALCULATIONS As discussed in Section 3.3.5, more than one nuclear power station site may contribute to the doses to be considered in accordance with 40CFR190. The fuel cycle dose assessments for Catawba Nuclear Station must include liquid and gaseous dose contributions from McGuire Nuclear Station, which is located approximately thirty miles NNE of Catawba. For this dose assessment, the total body and maximum organ dose contributions to the maxjmum exposed individual from the combined Catawba and McGuire liquid and gaseous releases are estimated using the following calculations: Dy3(T) = DVB(I ) + DWB m lI ) +DVB(a ) + DWB m I8 ) c c D )" 5 c) + M0( m M0(S ) +DM0(E ) MO M0 c m whare: D,'B )= tal estimated fuel cycle who k body dose commitment resulting from the combined liquid and gaseous effluents of Catawba and McGuire during the calendar year of interest, in mrom. DM0(T) = Total estimated fuel cycle maximum organ dose commitment resulting from the combined liquid and gaseous effluents of Catawba and McGuire during the calendar year of interest, in

mrem, fuel cycle dose calculation worksheet is provided in Figure C.4.0-4.

.4.1 Licuid Effluents Liquid pathway dose estimates are calculated using generic methodology or the LADTAP computer program. The values for D (1 ) liquid pathway dose contributions are calculated based on the, methodology, values and assumptions presented in Section C4.2.1. The values for Dm(1 and Dm(1 ) liauld dose LADTAP t empL) t e s hown,i n F i gu r e A4. 0 - 1, l contributions are calculated using the and using the Catawba average dilution flow value for the period of interest 1 (4400 cfs default value), j C4.4.2 Gaseous Eff1 s ts Total Body The methodology for calculating noble gas airborne pathway whole body exposures to the maximum individual, D is derived from Section 3.1.2.1 generic methodology for gamma air and @ eta air dose calculations as foi ows: 3.17E-8 I K [(X/Q)Q ] mrem /yr D, = g i i=1 Gtneric methodology parameters Kg are described in Section 1.2.1. The Catawba site specific parameter X/Q ~/alue is 3.10E-5 sec/m3 as described in Section C4.2.2.1 for Catawba gamma air and beta air dose calculations, Dose contributions by McGuire via the airborne pathway to the Catawba fuel cycle l whole body dose are trivial and need not be calculated unless a significant (beyond Tech Spec) release takes place at McGuire during the period of j interst. 'D /j N. C-16 Rev. 34 1/1/92

'taximum Organ irborne pathway maximum organ dose estimates are calculated using generic methodology or the GASPAR computer program. The maximum organ dose is established by calculating doses to all organs for each potential maximum offsite location identified in Table C4.0-7. A conservative estimate (i.e., overestimate) of the fuel cycle maximum organ dose is obtained by 1) determining the locations with the highest exposure releases for each organ,

2) adding the highest exposure value for the airborne release to the same organ dose resulting f rom liquid releases, and 3) comparing i. lues obtained when the liquid and airborno pathway components are added for all organs and age groups to determine the maximum (or limiting) organ and age group.

Dose contributions by McGuire via the airborne pathway to the Catawba fuel cycle maximum organ dose are trivial and need not be calculated unless a significant ) (beyond Tech Spec) release takes placa at McGuire during the period of interest. i O O C-17 Rev. 34 1/1/"2 l 1

,,Vl f J ( D TAB .0-1 (1 of 2) CATAVBA NUCLEAR STATION lllSPERSION PARI. HETER (f75') FOR I.ONG TERM RELEASES ) 500 liR/Yh OR ) 125 HH/0TR (sec/m') Distance to the control location, (miles) bector 0.5 1.0 1.3 2.0 2.1 3.0 2.3 4 0 4.5 1.0 3 N 2.6E-5 c.5E-6 2.7E-6 1.5E-6 9.7E-7 6.9E-7 5.2E-7 4.1E-7 3.3E-7 2.8E-7 NNE 3.1E-5 8.1E-6 3.3E-6 1.8E-6 1.2E-6 8.2E-7 6.2E-7 4.9E-7 4.0E-7 3.3E-7 NE 3.OE-5 7.8E-6 3.2E-6 1.8E-6 1.1E-6 8.0E-7 6.07E-7 4.7E-7

3. 9 r.- 7 3.2E-7 ENE 1.5E-5 J.9E-6 1.6E-6 8.9E-7 5.7E-7 4.1E-7 3.1L-7 2.4E-7 2.0E-7 1.6E-7 E

1.4E-5 3.7E-6 1.5E-6 8.4E-7 5.4E 7 3.8E-7 2.9E-7 2.3E-7 1.9E-7 1 6E-7 ESE 9.0E-o 2.3E-6 9.5E-7 5.3E-7 3.4E-7 2.4E-7 1.8E-7 1.4E-7 1.2E-7 9.7E-5 SE 9.2E-6 2.4E-6 9.8E, 5.4E-7 3.5E-7 2.4E-7 1.8E-7 1.4E-7 1.2E-7 9.8E-8 SSE 1.1E-5 2.9E-6 1.2E-6 6.4E-7 4.1E-7 2.9E-7 2.2E-7 1.7E-7 1.4E-7 1.1E-7 S 2.5E-5 6.4E-6 2.6E-6 1.5E-6 9.3E-7 6.6E-7 5.0E-7 3.9E-7 3.2E-7 2.7E-7 SSW 1.7E-5 4 4E-6 1.8E-6 1.0E-6 6.4E-7 4.5E-7 3.4E-7 2.7E-7 2.2E-7 1.SE-7 SW 1.3E-5 3.4E-6 1.4E-6 7.4E-7 4.7E-7 3.3E-7 2.4E-7 1.9E-7 1.5E-7 1.3E-7 WSW 7.0E-6 1.8E-6 7.2E-7 3.9E-7 2.5E-7 1.7E-7 1.3E-7 1.0E-7 6.2E-8 6.8E-8 U 8.9E-6 2.3E-6 9.3E-7 5.0E-7 3.2E-7 2.2E-7 1.7E-7 1.3E-7 1.1E-7 8.7E-8 WNW 6.6E-6 1.7E-6 6.8E-7 3.7E-7 2.4E-7 1.7E-7 1.3E-7 9.8E-8 8.0E-8 6.6E-8 NW 1.0E-5 2.6E-6 1.1E-6 5.9E-7 3.8E-7 2.7E-7 2.0E-7 1.6E-7 1.3E-7 1.1E-7 NNW 1.3E-5 3.3E-6 1.4E-6 7.5E-7 4.8E-7 3.4E-7 2.6E-7 2.0E-7 1.6E-7 1.4E-7 Rev. 4 7/18/84

. - _ - _ _.. -... ~ i IbBLE C4.0-1 9 (2-ot.2) CATAVBA NUCLEAR STAT 103 1 nhe' values-presented in this table were generated by using the computer program-10QD0Q (NUREQ/CR-2919)'which implements NRC Regulatory Guide 1.111 (1977) and the allowing assumptions: 1. Data Collection Period 12/17/75 to 12/16/77. - i ~ 2. Ground Level Releases. l 3. Height of The Vent's Building = 47 meters. - l 4 Open Terrain. Recirculation Correction factors. i I I t i l' l-i l-l-O Rev. 13 1/1/87 .i_ -, -. ....-e. m- .m,w,,-.. ,- -, -, - - - -,. --13 -w., ,,, - me --v- + - -sy, r, y,

s. '

c4 0 m + ~ ~. >m i O O O O O O O O O O O O O O O O G% \\ m - m - a m - - - - m - - - - m xm C e e i e e e e t e e s e s i x W W W W W W W W W W W W W W W W O o e m n m O m M m 1 uo 6 N m n o. M e m C.4

- ea

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m. 4 R

4 6 6 e4 04 M N 04 4 -7 M e-*

- ee -r4 ZO O C C O O O O.

O C O O O O O O O. g m - m m e m e-m eo e em m n - e. e-O 4 I I e ( e 4 4 4 4 4 4 4 e e i W W W W W W W W W W inJ W W W W W N @ n M CO m st @ lo @ 4 4 m M @ N. O. -^ m m A M M N e4 M @ m A N 04 W N M g C .j O O O O O O O O O O O O O O - m m - - - - - - - - - - - - - N m a e i e e e a e 6 4 4 e i s i e 5 4 W W W W W W W W W W W W W W W W m n e n n m n m e in m o s e N c. 4 m ~ m m ** ~t 4 rs M 4 uO W 4 rs n ci n ~t C ,+ AW , ^ O O O O O O O O O O O w m m m em em m a m m m m m m m m m V W G O e a a e t t e e a e a e e a W p v W W W W W W W W W W W i.4 W W W W C. n M C W m ed N M @ Q @ r4 W O. 4 N. b H C m M ** @ @ st e @ eo em m 4 4 M -3 N D ~ s n O W O m n w W W N e h 4 W O O O O O O O O j h [%C,) W 64 0 m m m m ** - - m m m m ea <= - em m t O O m i e i e e a i e i e e i e e I'. N N

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n 04 N em em CQ - -

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m. m. m.

C.5 m. m. m. m. m. m m m m m m = m e i i i i i 7 4 W W LJ W W W W W W W W W W W W W [ sb m 4 4 m C N D n n D O en 4 > sn 4 N. M 4 mm M M N N M @ m m r3 04 ** N n A C C C C & m m m C C M m m m mm C,- e e a e e I e a e s 6 e e a s h W W W W W W W W W W W W W W W W @ N @ O co O M M cc @ e 5 @ C m 4 [

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W Q m h r. 4 to m 4 4 4 4 e co e co 4 co e a 4 e s i e I 6 e i e a e e e e W W W id W W W W W W W W W W W W O m ea @ sn O 4 ..... co. m. N 4 6 4 c.o m.* O M ** 4 M N M M N @ m N N - ca 4 l [ e.,. l / t ) U O e. N N N Eb N U ) ~5 S 4 Z W Z A L4 W 4 3 m 2 3 2 V. 2 4 '4 M W LJ 4 CD Lf; D ' 3 2 "S 4 2 A

IARLE C4.OS (2 or 2) CATAWBA NUCLEAR STATION The values presented in this table were generated by using the corsputer program XOOD0Q (NUREQ/CR-2919) which implements NRC Regulatory Guide 1.111 (1977) and the following assumptions: 1. Data Collection Period, 12/17/75 to 12/16/77, 2. Ground Level Releases. 3. Height of The Vent's Building = 47 meters. 4 Open Terrain Recirculation Correction Factors. f Rev. 11 3/31/86

O TABLE C4.0-3 (1 of 2) LIQUID EFFLUENT DOSE - ADULT PARAMETERS CATAWBA NUCLEAR STATION Am MREM /HR PER UCl/ML NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00 E + 00 4.64 E-01 4.64 E -01 4.64 E -01 4.64 E- 01 4.64 E- 01 4.64 E -01 NA 24 4.11 E + 02 4.11 E + 02 4.11 E + 02 4.11 E + 02 4.11 E + 02 4.11 E v 02 4.11 E + 02 CR - 51 0.00E + 00 0.00E + 00 1.28 E + 00 7.65 E-01 2.82E - 01 1.70E + 00 3.22E + 02 MN54 0.00E + 00 4.39 E + 03 8.37 E + 02 0.00E + 00 1.31 E + 03 0.00E + 00 1.34 E + 04 MN 56 0.00E + 00 1.10 E + 02 1.96E + 01 0.00E + 00 1.40E + 02 0.00E + 00 3.52E + 03 FE 55 6.65E +02 - 4.59E +02 1.07 E + 02 0.00E + 00 0.00E + 00 2.56 E + 02 2.63 E + 02 FE 59 1.05 E + 03 2.47 E + 03 9.45E +02 0.00E + 00 0.00E + 00 6.89 E + 02 8.22E + 03 CO 58 0.00E + 00 9.09 E + 01 2.04 E + 02 0.00E + 00 0.00E + 00 0.00 E + 00 1.84 E + 03 - CO 60 0.00E + 00 2.61 E + 02 5.76E + 02 0.00E + 00 0.00E + 00 0.00E + 00 4.90 E + 03 NI 63M 3.14 E + 04 2.18 E + 03 1.05E + 03 0.00E + 00 0.00E + 00 0.00E + 00 4.54 E + 02 NI 65 1.28E + 02 1.66 E + 01 7.56E + 00 0.00E + 00 0.00E + 00 0.00E t00 4.21 E + 02 CU 64 0.00E + 00 1.02E + 01 4.77E + 00 0.00E + 00 2.56 E + 01 0.00 E + 00 8.66 E + 02 OZN 65 2.32E + 04 7.38 E + 04 3.33E t 04 0.00 E + 00 4.93 E + 04 0.00E + 00 4.65E + 04 BR 83 - 0.00E + 00 0.00E + 00 4.05E + 01 0.00E + 00 0.00 E + 00 0.00E + 00 5.83E + 01 BR 85 0.00E +00 0.00E + 00 2.16 E + 00 0.00 E + 00 0.00 E + 00 0.00E + 00 0.00E + 00 R8 86 0.00 E + 00 1.01 E + 05 4.71 E + 04 0.00 E + 00 0.00 E + 00 0.00 E + 00 1.99E +04 RB 88 0.00 E + 00 2.90 E + 02 1.54 E + 02 0.00E + 00 0.0CE + 00 0.00E + 00 4.00E-09 RB 89 - 0.00 E + 00 1.92E + 02 1.35 E + 02 0.00E + 00 0.00E + 00 0.00 E + 00

1. ' 2E - 11_

~ SR 89 2.28 E + 04 0.00E + 00 6.55 E + 02 0.00E + 00 0.00E + 00 0.00E t 00 3.66 E + 03 SR 90 2.84 E + 05 0.00E + 00 7.63E +04 0.00F + 00 0.00 E + 00 0.00E +00 - 1.62E + 04 SR 91 4.20 E + 02 0.00 E + 00 1.70E + 01 0.ON + 00 0.00 E + 00 0.00E + 00 2.00E + 03 SR 92 1.59E 02 0.00E + 00 6.89 E + 00 0.00 E + 00 0.00E + 00 0.00E + 00 3.16 E + 03 Y 90' 5.98 E -01 0.00E + 00 1.60E-02 0.00 E + 00 0.00E + 00 0.00 E + 00 6.34 E + 03 Y 91 M 5.65E-03 0.00 E + 00 2.19 E -04 0.00 E + 00 0.00 E + 00 0.00E + 00 1.66 E -02 Y 91 ' 8.'76 E + 00 0.00E + 00 2.34 E -01 0.00E +00 0.00E + 00 0.00E + 00 4.82E + 03 -Y 92 5.25E-02 0.00E + 00 1.53E-03 0.00E + 00 0.00E + 00 0.00E + 00 9.19E + 02 Y 93 1.6AE -01 0.00E + 00 4.60E-03 0.00 E + 00 0.00 E + 00 0.00E + 00 5.28E + 03 ZR 95 3.09 E-01 9.91 E -02 6.71 E -02 0.00E + 00 1.56E -01 0.00E + 00 3.14 E + 02 ZR 97 1.71 E-02 3.45E-03 1.58E-( ) 0.00 E + 00 5.21 E-03 0.00 E + 00 1.07E + 03 NB 95 4.47E + 02 2.49E + 02 1.34 E + 02 0.00E + 00 2.46 E + 02 0.00E + 00 1.51 E + 06 MO 99 0.00E + 00 1.13 E + 02 2.15 E + 01 0.00 E + 00 2.56 E + 02 0.00 E + 00 2.62E + 02 TC 99M 9.43E - 03 2.66 E - 02 3.39E -01 0.00 E + 00 4.05 E - 01 1.31 E -02 1.58 E + 01 TC 101 9.70E-03 1.40E-02 1.37E -01 0.00E + 00 2.52E - 01 7.14 E - 03 4.20E - 14 O Rev.34 1 92

TACLE C4.0 (2 of 2) LIQUID EFFLUENT DOSE - ADULT PARAMETERS CATAWBA NUCLEAR STATION Am MREM /HR PER UCl/ML NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI RU 103 4.85E + 00 0.00E + 00 2.09E + 00 0.00 E + 00 1.85E + 01 0.00 E + 00 5.66E + 02 RU 105 4.04 E -01 0.00E + 00 1.59E -01 0.00E + 00 5.22E + 00 0.00E + 00 2.47 E + 02 PU 106 7 21 E + 01 0.00E + 00 9.12E + 00 0.00 E + 00 1.39E + 02 0.00E + 00 4.66E + 03 AG 110M 1.24 E + 00 1.15 E + 00 6.83E-01 0.00E + 00 2.26 E + 00 0.00E + 00 4.70E + 02 TE 125 2.57 E + 03 9.32E +02 3.45E + 02 7.74E t 02 1.05E + 04 0.00E + 00 1.03E + 04 . TE 127M 6.50 E + 03 2.32E + 03 7 92E+02 1.66 E + 03 2.64E + 04 0.00E + 00 2.18 E + 04 .TE 127 1.06E4 02 3.79 E + 01 2.20 E + 01 7.82E + 01 4.30E + 02 0.00 E + 00 8.33E + 03 TE 129M 1.10E + 04 4.12E + 03 1.75E +03 3.79 E + 03 4.61 E + 04 0.00E + 00 5.56 E + 04 TE 129 3.01 E + 01 1.13E + 01 7.34 E + 00 2.31 E + 01 1.27E + 02 0.00E + 00 - 2.27E +01 TE 131M 1.66E + 03 8.12E + 02 6.77 E + 02 1.29 E + 03 8.23E t03 0.00E + 00 8.06 E + 04 TE 131 1.89E + 01 7.90E + 00 5.97 E + 00 1.55 E + 01 8.28 E + 01 0.00E + 00 2.68 E + 00 TE 132 2.42E + 03 1.56 E + 03 1.47 E + 03 1.73 E + 03 1.51 E + 04 0.00E+ 00 7.30Ee04~ 130 2.89E + 01 8.51 E + 01 3.36E + 01 7.22E + 03 1.33 E + 02 0,00E + 00 7.33 E+ 01 ~ v)i 131 1.59 E + 02 2.27E + 02 1.30E + 02 7.44 E + 04 3.89E + 02 0.00 E + 00 5.39 E + 01 1 132 7.75 E + 00 2.07 E + 01 7.25E + 00 7.25 E + 02 3.30E + 01 0.00E + 0G 3.89 E + 00 1 133 5.42E + 01 9.43E + 01 2.87 E + 01 1.39 E + 04 1.65 E + 02 0.00E + 00 8.48 E + 01 1 135 1.69 E + 01 4.43 E + 01 1.63 E + 01 2.92E + 03 7.10E + 01 0.00E + 00 5.00 E + 01 CS 134 2.98 E + 05 7.09 E + 05 5.80E + 05 0.00E + 00 2.WE + 05 7.62E + 04 1.24 E +04 CS 136 3.12E + 04 1.23 E + 05 8.86E + 04 0.00 E + 00 6.85E + 04 9.39 E + 03 1,40 E + 04 CS 137 3.82E + 05 5.22E + 05 1.42E + 05 0.00 E + 00 1.77 E + 05 5.89 E + 04 1.01 E + 04 CS 138 2.64 E + 02 5.22E + 02 2.59 E + 02 0.00 E + 00 3.84 E + 02 3.79E + 01 2.23E -03 BA 139 1.15 E + 00 8.18 E -04 3.36E-02 0.00 E + 00 7.65E-04 4.64 E - 04 2.04 E + 00 BA 140M 2.40 E + 02 3.02E -01 1.58 E + 01 0.00E + 00 1 '.03 E - 01 1.73 E -01 4.95E +02 B A 141 5.58 E -01 4.22E -04 1.88E-02 0.00 E + 00 3.92E-04 2.39E -04 2.63E - 10 BA 142 2.52E -01 2.59E-04 1.59E-02 0.00E + 00 2.19E-04 1.47E-04 3.55 E - 19 LA 140 1.55 E-01 7.83E-02 2.07E -02 0.00 E + 00 0.00 E + 00 0.00 E + 00 5.75E + 03 LA 142 7.95 E -03 3.62E-03 9.01 E - 04 0.00E + 00 0.00E + 00 0.00E + 00 2.64 E + 01_ CE 141 4.36E-02 2.95 E -02 3.35E-03 0.00 E + 00 1.37E-02 0.00E + 00 1.13 E + 02 CE 143 7.69 E -03 5.69 E + 00 6.29 E -04 0.00 E + 00 2.50E -03 0.00E + 00 2.13 E + 02 CE 144 2.27E + 00 9.51 E - 01 1.22E-01 0.00E + 00 - 5.64E-01 0.00E + 00 7.69E + 02 PR 143 5.71 E -01 2.29 E -01 2.83 E -02 0.00E + 00 1.32E - 01 0.00E + 00 2.50 E + 03 PR 144 1.87E-03 7.76 E -04 9.50E-05 0.00 E + 00 4 38E-04 0.00 E + 00 2.69 E-10 ND 147 3.91 E-01 4.52E-01 2.70 E -02 0.00E + 00 2.64 E-01 0.00E + 00 2.17 E + 03 W 187 2.96 E + 02 2.48 E + 02 8.65E + 01 0.00E + 00 0.00E + 00 0.00 E + 00 8.11 E + 04 NP 239 3.12E - 02 3.07E -03 1.69E-03 0.00E + 00 9.57E-03 0.00 E + 00 6.29E + 02 l l Rev.34 l 1 92

O TABLE C4.0-4 ) (1 of 2) i LIQUID EFFLUENT DOBE - TEEN PARAMETERS CATAWBA NUCLEAR STATION Arn MREM /HR PER UCl/ML NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI h 3 0.00E + 00 3.42E -01 3.42 E - 01 3.42E - 01 3.42E - 01 3.42E -01 3.42E -01 NA 24 4.23E v 02 4.23E + 02 4.23 E + 02 4.23 E + 02 4.23 E + 02 4.23 E + 02 4.23E + 02 CR 51 0_.00 E + 00 0.00E + 00 L32E + 00 7.33E-01_ _2.89E-01 1.88 E + 00 2.22E + 02, MN$4 0.00E + 00 4.31 E + 03 8.55 E + 02 0.00 E + 00 1.29E + 03 0.00E + 00 8.85 E + 03 MNE6 0.00E + 00 1.16 E + 02 2.05 E + 01 0.00E + 00 1.46E + 02 0.00E + 00 7.00E + 03 FE 55 6.95 E + 02 4.93 E + 02 1.15 E + 02 0.00E + 00 0.00E + 00 3.13 E + 02 2.13E + 02 p5 59 1.08E + 03 2.52E + 03 9.7FE + 02 0.00h + 00 0$05 + 00 7.95N + 02 5.96E + 03 CO 58 0.00E + 00 9.02E + 01 2.08 E + 02 0.00E + 00 0.00E + 00 0.00E + 00 1.24 E + 03 CO 60 0.00 E + 00 2.61 E + 02 5.87 E + 02 0.00 E + 00 0.00E + 00 0.00E + 00 3.40E + 03 NI 63M 3.26 E + 04 2.30 E + 03 1.10E + 03 0.00 E + 00 0.00 E + 00 0.00 E + 00 3.66 E + 02 NI 65 1.38 E + 02 1.76 E + 01 8.02E + 00 0.00E + 00 0.00E + 00' O.00E + 00 9.55E + 02 CU 64 0.00E + 00 1.07 E + 01 5.02E + 00 0.00E + 00 2.70E + 01 0.00E + 00 8.28 E + O2 OZN65 2.10E + 04 7.30E + 04 3.41 E + 04 0.00E t 00 4,67E + 04 0.00 E + 00 3.09E + 04 0R 83 0.00E ' 00 0.00E + 00 4.41 E + 01 0.00E + 00 0.00E + 00 0.00 E + 00 0.00 E + 00 BR 85 0.00E + 00 0.00 E + 00 2.34 E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 ' B 86 0.00E + 00 1.09 E + 05 5.11 E + 04 0.00E + 00 0.00E + 0if"0.00E + 00 1.61 E + 04 R RB 88 0.00 E + 00 3.11 E + 02 1.66E + 02 0.00E + 00 0.00E + 00 0.00E + 00 2.66E-05 R_B 89 0.00E + 00_ 2.01 E + 02 1.42E + O2 0.00E + 00_ _0.00E + 00 0.00E +00 3.08E-07 SR 89 2.48 E + 04 0.00E + 00 7.09 E + 02 0.00E + 00 0.00E + 00 0.00E + 00 2.95 E + 03 SR 90 2.52E + 05 0.007 600 6.76 E + 04 0.00 E + 00 0.00E + 00 0.00E + 00 1.31 E + 04 SR 91 4.54E +02 0.000 + 00 1.81 E + 01 0.00E + 00 0.00 E + 00 0.00E + 00 2.06E + 03 5P 92 1.72E + 02 0.00E + 00 7.32E + 00 0.00E + 00 0.00E + 00 0.00E + 00 4.37ET0f Y 30 6.46 E - 01 0.00E + 00 1.74 E - 02 0.00E + 00 0.00E + 00 0.00E + 00 5.33E + 03 Y 91 M 6.09 E -03 0.00E + 00 2.33 E - 04 0.00E + 00 0.00 E + 00 0.00E + 00 2.87 E - 01__ Y 91 9.48E + 00 0.00E + 00 2.54 E -01 0.00E + 00 0.00 E + 00 0.00E + 00 3.89E +03 i Y 92 5.71 E - 02 0.00E + 00 1.65E-03 0.00E + 00 0.00 E + 00 0.00E + 00 1.57E + 03 Y 93 1.01 E - 01 0.00E + 03 4.95 E - 03 0.00E + 00 0.00E + 00 0.00E + 00 5.522 + 03 ZR 95 3.13 E - 01 9.88 E - 02 6.80E - 02 0.00E + 00 1.45 E - 01 0.00$ + 00 2.20 E + 02 ZR 97 1.80E - 02 3.57 E -03 1.64 E - 03 0.00E + 00 5.41 E - 03 0.00E + 00 9.66 E + 02 NB 95 4.50E + 02 2.50E + 02 1.37 E + 02 0.00E + 00 2.42E + 02 0.00E + 00 1.07E + 06 IAC 99 0.00E t 00 1.20E + 02 2.28 E + 01 0.00E + 00 2.74 E + 02 0.00E + 00 2,14 E + 02 TC 99M 9.61 E - 03 2.68E-02 3.47 E -01 0.00E + 00 3.99 E - 01 1.49 E - 02 1.76 E + 01 TC 101 1.04 E - 02 1.48E-02 1.46 E -01 0.00E + 00 2.68 E -01 9.03 E _- 03 2.53 E - 09 Rev.34 1 92

O TABLE C4.0-4 (1 of 2) LIQUl0 EFFLUENT DOSE - TEEN PARAMETERS CATAWBA NUCLEAR STATION Am MREM /HR PER UCl/ML NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI RU 103 5.00 E + 00 0.00 E + 00 2.16 E + 00 0.00E + 00 1.78 E + 01 0.00E + 00 4.22E + 02 RU 105 4.32E-01 0.00E + 00 1.68E-01 0.00E + 00 5.45E+00 0.00E + 00 3.49 E + 02 R U __10,6 7.77 E + 01_0.00E + 00 9.79E + 00 0.00E + 00 1.50E + 02 0.00E + 00 3.73E + 03 AG 110M 1.18 E + 00 1.12E + 00 6.82E-05 0.00E + 00 2.14 E + 00 0.00E + 00 3.15 E + 02 TE 125 2,00 E + 03 1.01 E + 03 3.74E + 02 7.82E + 02 0.00E + 00 0.00E + 00 8.26 E + 03 TE 127M 7.07 E + 03 2.51 E + 03 8.41 E + 02 1.68 E + 03 2.87E + 04 0.00E + 00 1.76E + 04 'E 127 1.16'E + 02 4.09 E + 01 2.49E + 01 7.97E + 01 4.68 E + 02 036G C0 8.92E + 03 T TE 123M 1.19 E + 04 4.42E + 03 1.89 E + 03 3.85 E + 03 4.99E + 04 0.00E + 00 4.47E + 04 TE 129 3.28 E + 01 1.22E + 01 7.97 E + 00 2.34 E + 01 1.37E + 02 0.00 E + 00 1.79 E + 02 TE 131M 1.78 E + 03 8.55 E + 02 7.14 E + 02 1.29E + 03 8.92E+03 0.00E + 00 6.87 E + 04 TE 131 2.04 E + 01 8.41 E + 00 6.38 E + 00 1.57 E + 01 8.92 E + 01 0.00E + 00 1.67 E + 00 TE 132 2.55 E + 03 1.62E + 03 1.52E + 03 1.70E + 03 1.55E + 04 0.00E + 00 5.12 E + 04 l 130 2.90 E + 01 8.63 E + 01 3.44 E + 01 7.03 F. + 03 1.33E + 02 0.00E + 00 6.63E + 01 1 131 1.69E + 02 2.37E + 02 1.27 E + 02 6.92E + 04 4.08 E + 0? 0.00E + 00 4.69E + 01 1 132 8.08 E + 00 2.11 E + 01 7.SB E + 00 7.12E + 02 3.33 E + 01 0.00E + 00 9.20E 4 00_ l 133 5.82E + 01 9.87 E + 01 3.01 E t 01 1.38ETDI 1.73E + 02 0.00E + 00 7,47 E + 01 1 135 1.7'7 E + 01 4.54 E + 01 1.68 E + 01 2.92 E + 03 7.18 E + 01 0.00E + 00 5.04 E + 01 CS 134 3.0S E + 05 7.19 E + 05 3.34 E + 05 0.00E + 00 2.28E + 05 8.72E + 04 8.94 E + 03 CS 136 3.13 E + 04 1.23 E + 05 8.20E +04 0.00 E + 00 6.72E + 04 1.06E +04 9.93 E + 03 CS 137 4.09 E + 05 5,44 E + 05 1.89E + 05 0.00E + 00 1.85 E + 05 7.19E + 04 7.74 E + 03 CS 138 2.83 E + 02 5.44E A02 2.72E + 02 0.00E + 00 4.01 E + 02 4.67 E + 01 2.47 E -01 BA 139 1.23 E + 00 0.68 E - 04 3.60E-02 0.00E + 00 8.19 E - 04 5.99 E -04 1.10E + 01 BA 140M 2.52E + 02 3.09E -01 1.63 E + 01 0.00E + 00 1.05 E - 01 2.08 E - 01 3.89E + 02 9 A 141 5.96 E -01 4.45 E - 04 1.99E-02 0.00 E + 00 4.13 E -04 3.05 E - 04 1 27_E - 06 BA 142 2.66 E -01 2.66 E -04 1.63E -02 0.00E + 00 2.25 E - 04 1.77 E - 04 0.15 E - 13 LA 140 1.64 E - 01 0.07 E -02 2.15E-02 0.00E + 00 0.00 E + 00 0.00E + 00 4.63 E + 03 LA 142 8.45 E -03 3.75E-03 9.34 E - 04 0.00E + 00 0.00E 4 00 0.00E + 00 1.14 E + 02 DE 141 4.53 E - 02 3.03 E -02 3.48 E - 03 0.00E + 00 1I42E-02 0.00E 4 0 0.66 E + 01 ~~ CE 143 8.01 E - 03 5.83E + 00 6.51 E -0 4 0.00 E + 00 2.61 E - 03 0.00 E + 00 1.75E + 02 CE 144 2.37E + 00 9.82E -01 1.27 E- 01 0.00E + 00 _ S.86E-01 0.00 E + 00 5.96 E + 02 PR 143 6.18 E - 01 2.47 E - 01 3.08 E - 02 0.00E + 00 1.43 E - 01 0.00E + 00 2.03 E t 03 7 PR 144 2.03 E - 03 8.30E-04 1.03 E -04 0.00 E + 00 4.77E-04 0.00E + 00 2.24 E - 06 ND 147 4.43 E - 01 4.81 E -01 2.88 E - 02 0.00E + 00 2.83 E - 01 0.00E + 00 1.74 E + 03 ] W 187 3.20E + 02 2.61 E + 02 9.13 E + 01 0.00E + 00 0.00E + 00 0.00E + 00 7.05 E + 04 NP 239 3.49E-02 3.29E-03 1.83 E - 03 0.00E + 00 1.03 E -02 0.00E + 00 5.29 E + 02 O Rev.34 1 92

f O t TABLE C4.0-5 (1 of 2) LIQUID EFFLUENT DOSE - CHILD PARAMETERS CATAWBA NUCLEAR STATION Am MREM /HR PER UCl/ML NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG Gl-LLI __ H 3 0.00 E + 00 4.65 E - 01 4.65E -01 4.65 E - 01 4.65 E -01 4.65 E - 01 4.65 E -01 NA 24 4.65 E + 02 4.65E + 02 4.65E + 02 4.65E + 02 4.65E + 02 4.65 E + 02 4.65 E + 02 CR 51 0.00 E + 00 0.00E + 00 1.41 E + 00 7.85 E -01 2.15 E-01 1.43 E + 00 7.50E + 01 MN54 0.00 E + 00 3.38 E + 03 9.01 E + 02 0.00 E + 00 9.49 E + 02 0.00E + 00 2.84 E + 03 MN 56 0.00E + 00 1.06E + O2 2.38 E + 01 0.00E + 00 1.28E + 02 0.00 E + 00 1.53 E + 04 FE 55 9.23E + 02 4.89 E + 02 1.52E + 02 0.00 E,+ 00 0.00E + 00. 2.77 E + 02 9.07 E + 0_1_ FE 59 1.32E + 03 2.14 E + 03 1.07E + 03 0.00 E + 00 0.00E + 00 6.21 E + 02 2.23E + 03 CO 58 0.00 E + 00 7.36 E + 01 2.25 E + 02 0.00 E + 00 0.00 E + 00 0.00E + 00 4.30E + 02 CO 60 0.00E + 00 2.16 E + 02 6.38E+02 0.00 E + 00 0.00E + 00 0.00E + 00 1.20E + 03 NI 63M 4.32E + 04 2.31 E + 03 1.47E + 03 0.00 E + 00 0.00E + 00 0.00E + 00 1.56E + 02 NI 65 1.78 E + 02 1.68 E + 01 9.79 E + 00 0.00E + 00 0.00E + 00 0.00E + 00 2.05E + 03 CU 64 0.00 E + 00 1.00 E + 01 6.06E + 00 0.00E + 00 2.42E + 01 0.00E + 00 4.71 E + 02 CCN65 2.10 E + 04 5.75E + 04 3.57 E + 04 0.00 E + 00 3.62E + 04 0.00 E + 00 1.01 E + 04 BR 83 0.00E + 00 0.00E + 00 5.68 E + 01 0.00 E + 00 0.00 E + 00 0.00 E + 00 0.00E + 00 BR 85 0.00E + 00 0.00E + 00 3.03 E + 00 0.00 E + 00 0.00E + 00 0.00 E + 00 0.00E + 00 RB 86 0.00E + 00 1.06 E + 05 6.49 E + 04 0.00E + 00 0.00E + 00 0.00 E + 00 6.79 E + 03 RB 88 0.00E + 00 2.99 E + 02 2.08 E + 02 0.00 E + 00 0.00 E + 00 0.00E + 00 1.47 E + 01 R3 89 0.00E + 00 1.84 E + O2 1.64 E + 02 0.00E + 00 0.00E + 00 0.00E + 00 1.61 E + 00 SR 89 3.32E + 04 0.00E + 00 9.49E + 02 0.00 E + 00 0.00E + 00 0.00E + 00 1.29E + 03 SR 90 2.85 E + 05 0.00E + CO 7.63 E + 04 0.00E + 00 0.00E + 00 0,00E + 00 5.77E + 03 SR 91 6.04 E + 02 0.00E + 00 2.28 E + 01 0.00E + 00 0.00E + 00 0.00E + 00 1.33E + 03 SR 92 2.27 E + 02 0.00E + 00 9.12E + 00 0.00E + 00 0.00E + 00 0.00 E + 00 4.31 E + 03 Y 90 0.73 E-01 0.00 E + 00 2.34 E - 02 0.00 E + 00 0.00E & OO 0.00E + 00 2.49 E + 03 Y 91M 8.12E- 03 0.00 E + 00 2.95 E - 04 0.00E + 00 0.00E + 00 0.00E + 00 1.59 E + 01 Y 91 1.28 E + 01 0.00E + 00 3.42E -01 0.00E + 00 0,00'i + 00 0.00E + 00 1.70E + 03 Y 92 7.65E-02 0.00E + 00 2.19E-03 0.00 E + 00 0.00E + 00 0.00E + C0 2.21 E + 03 Y 93 2.42E - 01 0.00E + 00 6.65 E -03 0.00E + 00 0.00E + 00 0.00E + 00 3.61 E + 0 ?, ZR 95 4.85 E -01 1.07 E -01 9.49E-02 0.00 E + 00 1.53 E - 01 0.00 E + 00 1.11 E + 02 ZR 97 2.92E-02 4.22E -03 2.49 E-03 0.00E + 00 6.06E-03 0.00E + 00 6.40E + 02 NB 95 5.31 E + 02 2.07 E + 02 1.48E + 02 0.00 E + 00 1.94 E + 02 0.00_E + 00 3.82E + 05_ MO 99 0.00E + 00 1.26E + 02 3.11 E + 01 0.00 E + 00 2.68 E + 02 0.00 E + 00 1.04 E + 02 TC 99M 1.24 E - 02 2.42E - 02 4.01 E - 01 0.00E + 00 3.52 E - 01 1.23 E - 02 1.38 E + 01 TC 101 1.43 E -02 150E-02 1.90 E - 01 0.00E + 00 2.56 E - 01 7.92E-03 4.76E-02. O Rev.34 1 92 L t l

O TABLE C4.0-5 (2 of 2) LIQUID EFFLUENT DOSE - CHILD PARAMETERS CATAWBA NUCLEAR STATION A,n MREM /HR PER UCl/ML NUCLtDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI RU 103~~~ 6.91 E + 00 0.00E + 00 2.66'E + 00 0.00E + 00 1.74 E + 01 0.00 E + 00 1.79 E + 02 RU 105 0.10 E - 01 0.00E + 00 2.21 E- 01 0.00E + 00 5.36 E + 00 0.00 E + 00 3.90 E + 02 RU 106 1.11 E + 02 0.00E + 00 1.38 E + 01 0.00 E + 00 1.49 E + 02 0.00E + 00 1.72E + 03 AG 1101 83E + 00 1.24 E + 00 9.87 E - 01 0.00E + 00 2.30E + 00 0.00E + 00 1.47E + 02 TE 125 J.60E + 03 9.77 E + 02 4.81 E + 02 1.01 E + 03 0.00 E + 00 0.00E + 00 3.48E + 03 TE 127M 9.14 E + 03 2.46 E + 03 1.0BE + 03 2.19E + 03 2.61 E + 04 0.00E + 00 7.40 E + 03 TE 127 1.49E + 02 4.02E + 01 3.19E + 01 1.03E + 02 4.24 E + 02 0.00E + 00 5.82E + 03 TE 129M 1.54 E + 04 4.30E +03 2.39 E + 03 4.96 E + 03 4.52E + 04 0.00 E + 00 1.88 E + 04 TE 129 4.24 E + 01 1.18 E + 01 1.01 E + 01 3.02E + 01 1.24 E + 02 0.00E + 00 2.64 E + 03 TE 131M 2.28 E + 03 7.87E + 02 8.38E + 02 1.62EIO3 7.62E + 03 0.00 E + 00 3.19 E + 04 TE 131 2.62E + 01 0.00E + 00 7.81 E + 00 2.01 E + 01 7.94 E + 01 0.00E + 00 1.38 E + 02 TE 132 3.19 E + 03 1.41 E + 03 1.71 E + 03 2.06E + 03 1.31 E + 04 0.00 E + 00 1.42E + 04 O1 130 3.91 E + 01 7.90E + 01 4.07 E + 01 8.70E + 03 1.18 E + 02 0.00E + 00 3.69 E + 01 1 131 2.30 E + 02 2.32E + 02 1.32E + 02 7.66 E + 04 3.80E + 02 0.00 E + 00 2.06 E + 01 1 132 1.07 E + 01 1.97 E + 01 9.05E + 00 9.13 E + 02 3.01 E + 01 0.00E + 00 2.32E + 01 1 133 7.92E + 01 9.80E + 01 3.71 s f0T 1.82E + 04 1.63E 4 02 0.00 E + 00 3.95 E + 01 1 135 2.34 E + 01 4.22E + 01 1.90E + 01 3.73E + 03 6.46 E + 01 0.00 E + 00 3.21 E + 01 CS 134 3.68E + 05 6.05 E + 05 1.28E + 05 0.00E + 00 1.87E + 05 6.72E + 04 3.26E + 03 CS 136 3.70E + 04 1.02E + 05 6.58E + 04 0.00E + 0'O 5.42E + 04 8.0SE + 03 3.57E + 03 CS 137 5.15 E + 05 4.93E + 05 7.28 E + 04 0.00E + 00 1.61 E + 05 5.78 E + 04 3.09 E + 03 CS 138 3.59E + 02 4.99E + 02 3.17 E + 02 0.00 E + 00 3.51 E + 02 3.78E + 01 2.30E + 02-BA 139 1.96 E + 00 1.05E-03 5.68E- 02 0.00E + 00 9.13 E - 04 6.15 E -04 1.13 E + 02 BA 140M 3.93E + 02 3.44 E - 01 2.29 E + 91 0.00E + 00 1.12E -01 2.05 E-01 1.99E + 02 BA 141 9.46 E - 01 5.30E - 04 3.08 E - 02 0.00E + 00 4.58E-04 3.11 E - 03 5.39E-01 BA 142 4.13 E - 01 2.98 E - 04 2.31 E - 02 0.00E + 00 2.41 E -04 1.75 E - 04 5.39 E -03 LA 140 2.15 E - 01 7.50E-02 2.53 E - 02 0.00E + 00 0.00E + 00 0.00E + 00 2.09 E + 03 LA 142 1.11 E - 02 3.55 E - 03 1.1_1 E - 03 0.00E + 00 0.00E + 00 0.00E + 00 7.03E + O2 CE 141 9 41E-02 4.69 E - 02 6.97 E - 03 0.00 E + 00 2.06 E -02 0.00 E + 00 5.86E + 01 CE 143 1.66E-02 8.99E + 00 1.30E-03 0.00 E + 00 3.77 E- 03 0.00E + 00 1.32E + 02 CE 144 4.93E + 00 1.55E + 00 2.63 E -01 0.00E + 00 8.56 E -01 0.00E + 00 4.03 E + 02 PR 143 8.35 E - 01 2.51 E -01 4.14 E - 02 0.00E 4 00 1.36 E - 01 0.00E + 00 9.01 E + 02 PR 144 2.74 E- 03 8.48 E -04 1.38 E - 04 0.00E + 00 4.48E-04 0.00E + 00 1.63 E + 00 ND 147 5.93 E - 01 ' 4.80 E -01 3.72E-02 0.00E + 00 2.63 E -01 0.00E + 00 7.61 E + 02 - W 187 4.06E + 02 2.40E + 02 1.08E + 02 0.00E + 00 0.00 E + 00 0.00E + 00 3.38E + 04 NP 239 4.96 E - 02 3.56E-03 2.50 E - 03 0.00E + 00 1.03 E- 02 0.00E + 00 2.64 E + 02 Rev.34 1 92

O 1 l TABLE C4.0-6 l (1 of 2) l L10UID EFFLUENT DOSE - INFANT PARAMETEMS I CATAWBA NUCLEAR STATION l Am MREM /HR PER UCl/ML NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-Lt.l__ H 3 0.00 E + 00 3.10 E -01 3.10 E -01 3.16 E - 01 3.10 E - 01 3.16 E -01 3.16 E-01 NA 24 1.04 E + 01 1.04 E + 01 1.04E + 01 1.04 E + 01 1.04 E + 01 1.04 E + 01 1.04 E + 01 CR 51 ,, 0.00E + 00 0.00 E + 00 1.45 E - 02 9.43 E -03 2.06E-03 1.83 E - 02 4.21 E - 01_ MN 54 0.00 E + 00 2.04 E + 01 4.62E + 00 0.00E + 00 4.52E d OO 0.00 E + 00 7.49E + 00 MN 56 0.00 E + 00 8.39 E -01 1.45 E -01 0.00E + 00 7.21 E -01 0.00 E + 00 7.62E + 01 F_E 55 1.42E + 01 9.21 E + 00 2.46E + 00 0.00 E + 00 0.00E + 00 4.50E + 00 1.17F + 00_ FE 59 3.16 E + 01 5.51 E + 01 2.17 E + 01 0.00 E + 00 0.00E + 00 1.63E + 01 2.63 E + 01 CO 58 0.00E + 00 3.69 E + 00 9.21 E + 00 0.00 E + 00 0.00 E + 00 0.00E + 00 9.19 E + 00 CO 60 0.00E + 00 1.11 E + 01 2.61 E + 01 0.00E + 00 0.00E +00 ' O 00E +00 2.63 E + 01_ NI 63M 6.50E + 02 4.02E + 01 2.26 E + 01 0.00E + 00 0.00 E + 00 0.00 E + 00 2.00E + 00 NI 65 4.82E + 00 5.45 E - 01 2.48 E -01 0.00E + 00 0.00E + 00 0.00 E + 00 4.15 E + 01 O CU 64 0.00 E + 00 6.24 E -01 2.89 E - 01 0.00E + 00 1.06E + 00 0.00 E + 00 1.28 E + 01_ ZN 65 1.89 E + 01 6,47 E + 01 2.98 E + 01 0.00E + 00 3.14 E + 01 0.00E + 00 5.46 E + 01 BR 83 0.00E + 00 0.00E + 00 3.72E -01 0.00E + 00 0.00E + 00 0.00 E + 00 0.00E + 00 BR 85 0.00 E + 00 0.00E + 00 1.99E-02 0.00E + 00 0.00 E + 00 0.00E + 00 0.00E + 00 : RB 86 0.00 E + 00 1.74 E + 02 8.61 E + 01 0.00E +00 0.00E + 00 0.00E + 00 4.46E + 00 RB 88 0.00 E + 00 5.10 E-01 2.80E -01 0.00 E + 00 0.00E + 00 0.00E +00 4.97E - 01 RB 89 0.00E + 00 2.93 E -01 2.02E -01 0.00E + 00 0.00 E + 00 0.00E + 00 9.9B E -02 SR 89 2.57 E + 03 0.00E + 00 7.38 E + 01 0.00E + 00 0.00 E + 00 0.00E + 00 5.29E + 01 SR 30 1.28 E + 04 0.00E + 00 3.45 E + 03 0.00E + 00 0.00E + 00 0.00E + 00 2.37E + 02 SR 91 5.13 E + 01 0.00E + 00 1.86 E + 00 0.00E + 00 0.00E +00 - 0.00E + 00 6.07 E + 01 ~ SR 92 1.97 E + 01 0.00E + 00 7.31 E - 01 0.00E + 00 0.00 E + 00 0.00E +60 2.12E + 02 Y -90 8.91 E -02 0.00E + 00 2.39E- 03 0.00 E + 00 0.00E + 00 0.00E + 00 1.23 E + 02 Y 91M 8.30 E -04 0.00E + 00 2.83 E - 05 0.00 E + 00 0.00 E + 00 0.00E + 00 2.77E + 00 Y 91 1.16 E + 00 0.00 E + 00 3.09E-02 0.00E + 00 0.00E+00 0.00 E + 00 8.30E + 01 Y 92 7.84 E - 03 0.00 E + 00 2.20E -04 0.00 E + 00 0.00 E + 00 0.00E + 00 1.50E + 02 Y~ 93 2.49 E - 02 0.00E + 00 6.79E - 04 0.00 E + 00 0.00 E + 00 0.00E + 00 1.97 E + 02 'ZR 95 2.11 E -01 5.15 E - 02 3.65 E - 02 0.00E + 00 5.55E-02 0.00 E + 00 2.56E + 01 ZR 97 1.52E-02 2.60E -03 1.19 E -03 0.00E + 00 2.62E-03 0.00 E + 00 1.66E + 02 N_B 95 4.31 E - 02 1.77 E - 02 1.03 E - 02 0.00E + 00 1.27 E -02 0.00E + 00 1.50E + 01 MO 99 0.00E + 00 3.49 E + 01 6.80 E + 00 0.00E + 00 5.21 E + 01 0.00 E + 00 1.15 E + 01 TC 99M 1.97E-03 4.06E-03 5.23E-02 0.00 E + 00 4.37E-02 2.12E - 03 1.18 E + 00 - TC 101 2.33E-03 2.93 E-03 2.90E -02 0.00E + 00 3.49E-02 1.60E - 03 4.98 E -01 O Rev.34 1 92

O TABLE C4.0-6 (2 of 2) j LIQUID EFFLUENT DOSE - INFANT PARAMETERD j CATAWBA NUCLEAR STATION Arn MREM /HR PER UCl/ML NUCLIDE BONE _ LIV 6 R _. T. BODY THYROID KlDNE_Y_ LUNG GI-L Ll___ RU 103 1.52E + 00 0.00 E + 00 5.07 E - 01 0.00E + 00 3.16E + 00 0.00E + 00 1.85 E + 01 RU 105 1.39 E - 01 0.00E + 00 4.69E-02 0.00 E + 00 1.03E + 00 0.00E + 00 5.55 E + 01 RU 100 2.47 E + 01 0.00E + 00 3.09E + 00 0.00E + 00 2.92E + 01 0.00E + 00 1.88E + 02 AG 110M 1.02E + 00 7.45 E - 01 4.93 E -01 0.00 E + 00 1.07 E + 00 0.00E + 00 3.86E + 01 TE 12S 2.39 E + 01 7.99E + 00 3.23 E + 00 8.04 E + 00 0.00E + 00 0.00E + 00 1.14 E + 01 TE __127M 6.00 E + 01 1.99 E + 01 L26E + 00 1.73 E + 01 1.40 E + 02 0.00 E + 00 2.42E + 01_ TE 127 1.03 E + 00 3.43 E -01 2.20 E -01 8.34 E -01 2.50 E + 00 0.00 E + 00 2.15 E + 01 - TE 129M 1.03 E + 02 3.52E + 01 1.58 E + 01 3.94 E + 01 2.56 E + 02 0.00E + 00 6.12E +01 TE 129 2.91 E -01 1.00 E - 01 6.80E-02 2.44 E - 01 7.25 E -01 0.00E + 00 2.33 E + 01 TE 131M 1.56E + 01 0.27 E + 00 5.18 E + 00 1.27 E + 01 4.32E + 01 0.00E + 00 1.06 E + 02 TE 131 1.80 E -01 6.66 E -02 5.06E-02 1.61 E-01 4.61 E -01 0.00E + 00 7.29 E + 00 TE 132 2.13 E + 01 1.06 E + 01 9.85 E + 00 1.56 E + 01 8.60E + 01 0.00E + 00 3.91 E + 01 1 130 6.15 E + 00 1.35 E + 01 5.43E + 00 1.52E + 03 1.49E + 01 0.00E + 00 2.90E + 00 1 131 3.68 E + 01 4.34 E + 01 1.91 E + 01 1.42E + 04 5.06 E + 01 0.00 E + 00 1.55 E + 00 1-132 1.70E + 00 3.45 E + 00 1.23E + 00 1.62E + 02 3.85 E + 00 0.00 E + 00 2.80E + 00 1 133 1.28 E + 01 1.87 E + 01 5.46 E +00 3.39 E + 03 2.19E + 01 0.00E + 00 3.16 E + 00 1 135 3.73E + 00 7.42E + 00 2.71 E + 00 6.65E + 02 8.27 E + 00 0.00E + 00 2.69 E + 00 CS 134 3.86E + 02 7.21 E + 02 7.28E + 01 0.00E + 00 1.86 E + 02 7.61 E + 01 1.96E + 00 CS 136 4.71 E + 01 1.38E + 02 5.17 E + 01 0.00E + 00 5.51 E + 01 1.13 E + 01 2.10E + 00 CS 137 5.35E + 02 6.26 E + 02 4.44 E + 01 0.00 E + 00 1.c4E + 02 6.81 E + 01 1.96E + 00 CS 138 4.93 E - 01 8.0./E - 01 3.89E-01 0.00 E + 00 4.00 E -01 6.24 E -02 1.28 E + 00 BA 139 9.03 E-01 5.99E-04 2.61 E -02 0.00E + 00 3 60E 3.63E-04 5.72E + 01 BA 140M 1.75 E + 02 1.75 E - 01 9.03 E + 00 0.00E + 00 4.16 E - 02 1.08 E - 01 4.31 E + 01 B A 141 4.36E-01 2.98E-04 1.37 E -02 0.00E + 00 1.79 E -04 1.81 E -04 5.32E + 00__ BA142 1.89 E 1.57 E - 04 9.29 E -03 0.00E + 00 9.03 E -05 9.49E - 05 7.78 E -Oi LA 140 2.16 E- 02 8.53E-03 2.19E 0.00E +00 0.00E + 00 0.00E + 00 1.00E + 02 LA 142 1.13 E - 03 4.14 E -04 9.91 E - 05 0 00E +00 0.00E + 60 0.00E + 00 7.03 E + 01 CE 141 8.07 E-02 4.92E-02 5.79 E-03 0.00 E + 00 1.52E -02 0.00E + 00 2.54 E + 01 CE 143 1.52E-02 1.01 E + 01 1.15 E - 03 0.00E + 00 2.93 E -03 0.00E + 00 5.87 E + 01 CE 144 3.05 E + 00 1.25 E + 00 1.71 E-01 0.00 E + 00 5.0SE -01 0.00E + 00 1.75E + 02 PR 143 8.33 E - 02 3.12E - 02 4.13 E - 03 0.00E + 00 1.16 E - 02 0.00E + 00 4.40E + 01 PR 144 2.61 E - 04 1.09 E - 04 1.41 E-05 0.00E + 00 3.94 E -05 0.00E + 00 5.05 E + 00 ND 147 5.67 E - 02 5.82E-02 3.57E-03 0.00 E + 00 2.24 E- 02 0.00E + 00 3.69 E + 01 W 187 9.26 E - 01 6.44 E-01 2.22E - 01 0.00E + 00 0.00E + 00 0.00E + 00 3.78 E + 01 NP 239 1.14 E - 02 1.02E-03 5.75 E -04 0.00E + 00 2.03 E - 03 0.00E + 00 2.94 E + 01 O Rev.34 1 92

a TaF# fo' NC4.0 7 Meteorological Parameter and Applicable Pathways tantial Worst-case Offsite Locations V Vorst-Case locations * (5/D) (D/Q) Applicable Food Pathwayn** (1)-Inhalation, Ground ~ . Site Boundary, NNE 3.lE-L 1.1E 7 -(2) Garden, 0.9 mi,-S 2.5E 3 7.2E-8 Veg (3)_ Meat Animal. 2.3 mi, NNV 7.5E-7 1.8E-9 Meat (S) Milk Animal. *** (4 X.XE-X X.XE-X ) Combination 5.0 mi, NNE 3.3E-7 5.8E-10 Veg, Meat, Goat Milk i

~

Based on August 1991 Land Use Census Data (See Table C4.0-8) i The food pathways to be included for exposure contribution to the maximum individual at this location. Inhalation and 1 ground exposure pathways also considered at all locations.

- - No milk animal is currently located withlu S.O miles of Catawba Nuclear Station I

() 5 c Table C4.0-7 (1 of 1) Rov, 24 [- 1/1/92 l

i' TABII C4.0-8 PATIMAY APPLICABil.ITY FOR AIL LOCATIONS BASED ON SITE SURVEY i CATAVBA NUCLEAR STATION (1 of 1) Distance to the control location in miles 4 SEC1DR 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 X X V V V V V V V VMc NNE X X X X X X X X -X VMG NE I X X X X X X X X VMG ENE X V V V V V V V V VMG E X V V V V V V VM VM VMG i ESE X V V V V V V V V VMG j SE X X V V V V V V V VMG SSE X X X V V V V V V VMG 1 S X V V V V V V V VM VMG SSV X V V V V V VM VM VM VMG SW X V V V V VM VM VM VM VMG WSW X V V V V V VM VM VM VMG I V X X X X X M M M M VMG WNV X X V VM VM VM VM VM VM VMG NW X X X VM VM VM VM VM VM VMG j NNW X X X V VM VM VM VM VM VMG i l PATINAYS: X - None V - VEGETASil M - MEAT C - COAT MIII C - COW MIII l No pathways exist within the Site Boundary (Exclusion Area Boundary) No milk pathway is identified within'5 miles of the plant. 11:ere f ore, it is assumed that the Goat (conservative vs Cow) Milk pathway exists at every 5.0 mile sector. Also, since there is no site survey data outside of 5 miles from the plact, it is conservative to assume that a Vegetable and Meat pathway exists at every 5 mile location. Rev. 3I. 1/1/92

7 t'~' FIDutt C4.01 ( CATAWEA LADf AP INMIT f tMPLAf t FOR 410010 RAD 10WUCL10E RELii.$10Fi$lf t Oost CALCULAfl0k$ e e e e e e + e.. + e......, + e............. T DP C F D A T A "'* * ** * * * * * * * * " ' " " " 3C0tts ++ t + 2 + 3 + 6 5 + 6 + ?- 000001 LA0f AP INPUT FDs CATAvsA ODCM METHOD

OFFAULT DILVil0N 000002 0

1.Lt+02 1.0 1 000003 1.0 000004 LIQUID ttLEA$t SOURCC f tRMS Cutill Ptt alLEASE FillCD 000005 N3 0.tht+00 00D006 EA24 0.00f+00 000007 tt31 0,00t.00 000008 mul4 0.00t+00 000009 Mul6 0.00t+00 000010 (155 0.00t+00 000011 ftSO 0.00t+09 000012 C058 0.00t+00 000013 C060 0.00t+00 000014 4163 0.00t*00 C00015 ul65 0.00t+00 000016 CU64 0.00E*00 0000l? 2h65 0.00t+00 000018 CN69 0.00t+00-000019 BRE3 0.00t+00 000020 stb 5 0.00E+00 000021 R646 0.00t+00 000022 R866 0.00t+00 000023 2889 0.00t+00 000024 st99 0.00t+00 000025 5t90 0.00t+00 000026 $t91 0.00t+00 000027 5t92 0.00t+00 000028 Y 90 0.00t+00 ( 000029 Y 91 M 0.00t+00 000030 Y 91 0.00t+00 000031 Y 92 0.00E+00 000032 Y 93 0.00t+00 000033 2t95 0.00E+00 000034 ZR97 0.00E*00 000035 WB95 0.00t+00 000036 Mo99 0.00t+00 000037 iC99 M 0.00E+00 000038 TC101 0.00t+00 000039 RU103 0.0Ct+00 000040 RU105 0.00t+00 000041 20106 0.00t+00 000042 AG110M 0.00t+00 000043 ft125M 0.00t+00 000044 f t127M 0.00t+00 000045 ft127 0.00t+00 000046 ft129M 0.00E+00 000047 ft129 0.00t+00 000048 ft131M 0.00t+00 000049 ft131-0.00t+00 000050 ft132 0.00t+00 000051 1 130 0.00t+00 000052 I 131 0.00t+00 000053 1 132 0.00t+00 000054 1 133 0.00t+00 000055 1 135 0.00t+00 000056 C5134 0.00t+00 000057 C5136 0.00t+00 000058 Cs137-0.00t+00 000059 C$138 0.00t*00 000060 -BA139 0.00t+00 0-000061 BA140 0.00E+00 000062 BA141 0.00t+00 000063 BA142 0.00t+00 ROV. 34 1-l-92

3 flGuat C4.0 1 (Cont'd) i CATAWBA LADIAP lhPUT TEMPLAff FtJt LIQUID RAD 40WUCLIDE ttLEA$t 0FF$ lit Dost CAL (11LAll0NS . C OI. $ >...... *

1... * * * *
2.... * * *
3.... +... 6........ 5..... *
6.... * * *. 7..

000066 LA160 0.00E.00 000065 LA162 0.00E+00 000066 Ct161 0.00t.00 000067 Ct163 0.00t+00 000068 Ct166 0.00E+00 000069 PR163 0.00E.00 000070 PR166 0.00t+00 000071 N0147 0.00E+00 0000T2 V 187 0.00t.00 0000T3 hP239 0.00t+00 000074 000075 000076 0.3 0.976 0.976 37.7 0.0 0.0 000077 000078 000079 .................................. gottom op para...... 4.................... T i l Rev. 34 1-1-92

1 [ flG.Rt C6.0 2 CAT AWEA f.ASPAR IWPUT f tMPLATE FOR WOSLE CAS RA010WUCLlDE ttLEME Wutli.CA$t LOCAf!ON e eee n e e nennee ne eeeeeenenene 10P OF D AT A ""**"""""""""""" scot s e.... o.. i n o e n.. p o n o n u } n.. n o 6.. n e " "l * * " + ' *

6 * ' * * * * " T" 000001 CASPAt thPUT FOR CAT AWSA ODCN mitMCO + MAR kOSLt CAS DC$t ( ALCVLA110NS 000002 0 0.0 0.0 0.0 0.0 000003 11 000004 1.0 1.0 1.0 0.76 1.0 000005 hostt GAS toutt! TERM CUtits Pit atttAtt Pttico 000006 1.0 000007 AR41 0.00t+00 000008 KR&3 N 0.00t+00 000009 tt85 0.00t+00 000010 tat 5 m 0.00t+00 000011 Et87 0.00t+00 000012 t 88 0.00t+00 000013 tt90 0.00t+00 000016 at131M 0.00t+00 000015
1133 0.00t+00 000016 st133M 0.00t+00 00001T at135 0.00t+00 000018 at135M 0.00t+00 000019 att37 0.00te00 000020 11138 0.00t+00 000C21 OM022 -eeeee...LOCATIDu 1 Nwt 0.50 3.12 05 3.1t*05 3.1E*05 1.1t*07

................ n e e e e e. *

B0 f f 0M OF D A T A " *""*"""++""""""

O Rev. 34 1-1-92

t timmt C4.0 3

,.ATANEA t.ASPAR INPUT ftMPLAtt FOR PitiltilLAlt,10Dikt AND OfNil NUCLlot$ WOR $I'CA$f LOCAfl0NS eene. nennenenenune.nnn. scp op pgts nennuneenannennnee.

.COLS ""+ "" 1 " " n * " 2 " a n "" 3 * " n ""4 "

n * "
l"
n " " 6"
n"" T" 000001 CASPAR lhPUT FOR CATAW$A 00CM MtfMOD + PAaf, I, AND OtN:2
iNhAL&fl0N l

000002 0 0.0 0.0 0.0 0.0 000003 11 000004 1.0 1.0 ' 1. 0 0.76 i.0 000005 PAtt. I A40 CittR WUCLlot$ $0L*CE

CUNILS *tt itLEAbt PIR10D 000006
0 000007 N3 0.00t+00 000008 cts 1 0.00E+00 000009= Mul6 0.00t+00 -

000010 ft15 0.00t+00 + 000011' ftS9 0.00t +00 000012 t058 0.00t+00 000013 C060 0.0M+00 - 000016 ZN65 0.00t+00 000015 $409 0.00D 00 000016 st90 0.00E+00 00001F. 2a95 0.00t+00' 000018 WJ99 0.00t+00 1 000019- ' if f 0.00t+00 000020 1.133 0.00t+00 000021 Cli34 0.00D 00 l 000022 C3136 0.00t+00 000023 C$137 -0.00f+00L i -000024 BA140 - 0.00t+00 000025-tt141 0.00t+00 000026 Ct166 0.00D 00 f .000027 000028' LOCAfl0W 1 NME 0.50 3.1t 05 3.It 05 3.it 05 1.1t 07 000029 - i 000030 000031 .. n unen.....n...n.n.. 30f f 0M Of D A T A +"""+"""""""""" FOR OTMtt 10CAfl0N$ 9tPt ACE F0ttNING INPUT L1Nt$t LOCATION 2

WORST VEGETABLE CAmptu 000001 GA$PAa INPUT FOR CATAWsA GDCN MIN 00
PART, I, AND OThtR
CARDEN 000002 0 1.0 1.0 0.0 0.0 000028 ' LOCAfl0W 2 5

0.90 2.$t*05 2.lt*05 2.5t 05 7.2t*08 ~! ~ LOCAtl0N 3

WOR $f MEAT ANIMAL

'1000001 GASPAR lhPUT FOR CATAWSA ODCM METHOD

PAtt, I, AND OTHit
MEAT 000002 0-1.0 1.0 0.0 0.0 000028 LOCATION 3 NNW 2.30 7.5t*0T 7.!E*07 7.lt 07 1.8t 09 t

i LOCATION 4

WOR $T httK ANIMAL (ENytLOPED BY LOCATIou 5)

LOCATION 5'* WOR $T COM8thAfl0N L -000001 GASPAR lkPUT FOR CAT AWSA CDCM MtTM00 P ART. I, AND OThtR -* COM81NAfION H 000002--0 1.0 1.0 0.0 1.0 ~ LOCAi!0N 5 NME 5.00 3.3t 07 3.3t 07 3.3t 01 5.8E 10 000028 Rev. 34 1-1-91

,c_.

.__.__._.._..._____..,__.___._______-.._.._.~.__2.-_-_._

I I I Meteorological Farameter and Applicable Pathways Tab)^~C4.0 7 ie \\~ / ntial Worst-cane Of fnite Locations fog Usrst-Case Locations

r (X/Q)

(574) Applicabl Tood Pathways ** (1) inhalation, Ground Site Boundary, NNE 3.1E-5 1.1E 7 (2) Garden, 0.9 mi, S 2.5E-5 7.2E-8 Veg (3) Most Animal, 2.3 mi, NNW 7.5E-7 1.8E-9 Hent (4) Milk Animal, *** X.XE-X X.XE X (5) Combination. 5.0 mi, NNE 3.3E-7 5.8E-10 Veg, Meat, Goat Hilk Based <>n August 1991 Land Use Census Data (See Table C4.0 8) The food pathways to be included for...posure contribution to the maximum individual at this location. Inhalation and ground exposure pathways also considered at all locations.

- - No milk animal is currently located within 5.0 miles of Catawba Nuclear Station L

Table C4.0-7 (1 of 1) i !~ l-l Rev. 34 1/1/92 _,,-,.-.--n, ,-n--n., ..,,,-.r,.,--.,.------,,,.,v-,---,,, ,,m,,,-,,..,,. ,-_s ,,,egr g., -~.n.. - ~ ~ -

Plgure C4.0 4 (Cont'd) fuel Cycin Done Calculation Worksheet f '> r Organ Doses Adult Age Group l 1 Location 1 Worst Case Inhalation / Ground Lccatton

Bone Livor T.Pody T&.froid Kidnny Lung GI-LLI

$a.of llc I D{j;g ) D., r ) D,,,( T ) Location 2 - Worst-Case Vegetable Garden Location

Bone Liver T. Body Thyroid Kidney Lung GI-LLI D,,,' },)

D,,, i,,, ) D,,, ge)) O.ok Iw e D,,(T) Location 3 - Worst-Cann Meat Animal Location

Bone Liver T. Body Thytold Kidney Lung GI-LLI D,,, 1,)

D,,, 1,,,) E::: hi D,,,( T ) Location 4 - Wor s t-Case flilk Anf rral Location

Bone Liver T.Dody Thyroid Kidney Lung G I - l.L1 D,.of I )D,,, g,))

Us c 1 II.,,.. T.. ) y D,,,( T ) Figure C4.0-4 (2 of 10) Rev. 24 1/1/92

Figure C4.0 4 (Cont'd) + fuel Cycle Dose C.ilculat ion Wor ksheet int Organ Doses Location 5 - Worst Case Comtiination 1.2. N !.ocation(s)

1

!!cnn Liver T. Body Thyroid Kidney Lung GI LLI D.o I) a c D,,,1,) D,o %)) e D,o 4 e U.o(T) a Location 5, - Vot s t Case Cor..binat ion 1. 2.., N 1,ocat ion ( s ) Bone Liver T,Ilody Thyroid Kidney Lung G I LI,I D,,,( 1, ) D,,,,1 )b ) aso:h) Unse b l D,,,( T ) Location 5 Vorst-Case Combination 1.2...N 1,ocation(s)

y Bone Liver T. Body Thyroid Kidney Lung GI LLI d

I) a o D,.oD,,, g,) 1 U,,o 4 a. D,,(T) Adult Organ Maximumn** Maximum Total llone Liver T. Ilod y Thyroid Kidney Lung GI LLI D.,,(T Figure C4.0 4 (3 of 10) Rev. 34 1/1/92

~-- _ _ _. 4 6 igure c4.0 4 (Cont'd) + ruel cycle Dose Calculation Worksheet for . Organ Doses 7 Toen Age Group Location 1 - Worst Caso inhalstion/tircund 1,ocation

1 i

Bone Livor T. Body Thyroid Kidney !.un g Gl

LLI D,,,

,) j U,, .) ... e j - D,,,( T ) I,oc tion 2 + Vorst+ Case Vegetable Garden Location

f Done Liver T. Body

-Thyroid Kidney Lung GI LL1 i D., $ l ) e D,,, 1,) D,8) D,, r,,) D,,,( T) ocation 3 - Worst Caso fleat Animal Location

N)-

Bone Liver T. Body Thyroid Kidney Lung 01 L1,1 ha.o o n..o g.og.e o e,o D,,,( T ) t,ocation 4:- Worst Case rtilk Animal Location

3 Bone Liver T. Body Thyroid Kidney 1,un n GI LLI l

h**'"*") D '* ge i ~ n.o *y o .e D,,,( T ) Figurn C4.0-4 (4 of 10)- i Rev. 34 i 1/1/90 v..a........ ~, _. _

-- ~---- - = - - - - - N k f Figure Cl. 0 4 (Cont'd) Fuel Cycle Dosn Calculation Worksheet for Organ Doses Location 5 - Worst Case Combination 1,2. N Locat ion ( s )

3 Bone Liver T.Dody Thyroid Kidney Lung GI-LLI fej eso

{ e U,o = i D,o Enh ^ s ,,\\ l,) D.o(T) e Locat ion $r - Vorst-Case Combination 1.2.. N Location (n)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI D,,!),))

D 1, U,s,.,): j An i I D,,o, ' f.' D,,,( T ) Location $n Worst Case Cembination 1,2. N Locat ion ( s ) (n Bone Liver T. Body Thyroid Kidney Lung GI-LLI U.o I D,,, 1,c) a D,,, g, D,,, r,,, D,,,( T ) Teen Organ Maxitoums** Haximum Total Pono Liver T Body Thyroid Kidney Lung GI-LLI D,,o(T,,,) l l Figure C4.0-4 (5 of 10) 0 'x key. )k 1/1/92 1 ) ev-v e r --er g e,-

--,w*-

w-- - + - ,,y.,,.,y-w w-w--v,

...--. ~. . ~. C][lguro C4.0 4 (Cont'd) Fuel Cvele Dose Calculation Worksheet for Organ Doses Child Age Group j Location 1 - Vorst-Caso Inhalation / Ground Location

i I

Bone Liver T,Dody Thyroid Kidney Lung GI-LLI ] U.I e e D 1, y,e,., 8e I ... c. D,,tT) Location 2 Worst Case Vegetable Garden Location

i i

Bone Liver T,13ody Thyroid - Kidney Lung GI-LLI D,,,j,)) e D,,o .) D,, ,)- l e.o D,,(T) i ,ocat on 3 - Worst Case Heat Animal Location

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Bone Liver-T. Body Thyroid Kidney -Lung GI LLI g...j.e e he.. .o 8, ... a.) 0,,,(T) Location 4 - Vorst-Case Milk Animal Location

Bone Liver T. Body Thyroid-Kidney-Lung.

GI-LLI 1 D,,(( 1,,) ) D,,,l ' 8:::d D.o(T) e Figure C4,0-4 (6 of 10) ). Rev. 34 1/1/92. w-,-- 3e ,-yo,,n,,,-.w ,,,w-:-- ,m ,2m., -,-w-, ...%,...w,-- -,--,~+.me- ~w-r-=

l figure C4.0 4 ( Cont ' :! ) Funi Cyclo !)ose Calculation Worksheet for Organ lioses Location ~3 - Worst Caso Combination 1.2.. N Locat tont s ) Bone Liver T. Body Thyroid Kidney Lung GI-LLI j { 1 te0 C .) e D,,, o g) U.,, %) y eo D., ( T) Location G Worst-Case Combination 1,2. .N i.ocation(s)

g Bone Liver T. Body Thyroid Kidney Lung GI-LLI

( fc)) $..f, S..C $ neo i ?. D.,,(T) 1 ( 1 Location S - Worst-Case Combination 1.2...N Location (s)

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Bone Livar T.Dody Thyroid Kidney Lung GI-LLI ("T / D,,,1,) 1 D,,,,g,) D,e,o 4 D,,,( T ) i Child Organ Maximums ** t Maximum Total Bone Liver T 3ody Thyroid Kidney Lung GI-LLI D,,,( T,,,,, ) Figure C4.0-4 (7 of 10) 32 Rev. 34 1/1/92

rigure C4.0 4 (Cont'd) Fuel Cycle Dose Calculation Worksheet for j Organ Doses infant Age Group Location 1 Vorst Case Inhalation / Ground Location

f Bone Liver T. Body Thyroid Kidney Lung 01-LLI D.o c) o he.o a

-D,. ..) . D.,,( T ) i Location 2 - Worst-Case Vegetable Gardon Location

I Dene Liver T, Body Thyroid Kidney Lung GI-LLI D,,.,(

D ) ) teO neo D,,,( T ) pcation 3 - Worst-Caso Meat Animal Location

Bone Liver T. Body Thyroid Kidney Lung 01-LLI D,,

,) D,, C D so,) D,,,( T ) Location-'4.- Worst-Case Milk Animal Location

Bone Liver T Body Thyroid Kidney Lung GI -1.LI Ua 1) m D

I) 8..o::: tl D,,,(T ) - t Figure C4.0-4 (8 of 10) I n-Rev. 34 1/1/92 . -,.. -.. _. ~ _.. .... -.-.a. .~... .. ~. ~.

-. ~. _ _ -. ~ _ _ -. g y figure C4.0-4 (Cont'd) - Fuel Cyc]n pose Calculation Workshoot for Organ Dones ( )p q Location 3 Worst-Case Combinatin.1 1.2. . N !.ocat ion ( s ) 3 Bone Liver T. Body Thyreid Midney Lung GI LLI D,,,(f 1,.) D,,, 1,) U,o' Ee! l s U.o Em) l s D,,(T) li i l Location 5, Vorst Case Combinat ion 1.2. . N Locat ion ( s )

Bone L i vt. -

T. Body Thyroid Kidney Lung 01-LLI he.ohlcf. ..o; m esOl C# e.o - D.,,( T ) i Location $y Worst-Case Combination 1.2. . N Locat ion ( s )

9 Bone Liver T.Dody Thyroid Kidney Lung GI-LLI D*'

) ~ D m) o D,,o g, seO k D,,,( T ) i Inf ant Organ Maximums ** Maximum Total Bone Liver T.Dody Thyroid Kidney Lung GI LLI U.o(T,,,) figure C4.0-4 (9 of 10) U Rev. 34 ic1/92

[ n Tigure C4.0 4 Dose Calculation Worksheet for fuel Cycle Q.J}. (Cont il) l'ood l'athway Organ Dosos All Age Groupa Maximum organ Doon Organ = xxxxxxxxxx Ago Group n xxxxxxxxxx Done = x.xE-xx mrem /yr Notes: I Fuel cycle dose for nach age group, a, and organ, o, at analyzed limiting feod pathway locations. D.,,(. T ) = D,,( 1,,,) + D,,,(g,,,) Limiting dose estimates for each organ for age group, a, (maximums of donc values calculated for Locations 1 through 5.) Limiting dose estimato for any organ or age group (maximum of dore values calculated for any age group) (:.v/ Figuro C4.0 4 (10 of 10) Rev. 24 1/1/92 l 1

C3.0 Radiological Environmental 'lonitoring he Radiological Environmental Monitoring Program shall be conducted in accordance with Technical Specification, Section 3/4.12. T1:e monitoring program locations and analysen are given in Tables C5.0-1 through C5.0 3 and Figure C3.0-1. The laboratory performing the radiological environmental analyses shall parti-cipate in an interlaboratory conparison program which has been approved by the h*RC. This progrcm is the Environmental Protection Agency's (EPA n) Environmental Radioactivity Laboratory Intercomparison Studies (crosscheck) Program, our participation code is CP. The land use consus that was used to identify the controlling receptor locations was conducted during August, 1991. The 1991 Lt...d 'Ise Census identified no locations where Radiological Environmental Monitoring Program samples are required to be collected but are unavailable for collection. v g \\f'u' t:.18 Rev. 34 l 1/1/92 l I

l 1ll Illll 1l. I lI l 1 l iI I l g ) ) ) i i ) )))) )) )E E)E SUS)W)?WEEENSS)T'.W i)W i 2N) SES) FEEESSSSSUWk?NEESSWW MMMMMMMMMMiMMMMMMMMM N IC502E26I766I2I50I3E O s_'#'y I 4444l. 444444444E77E09 T ((((((((((((((((((1( P ( I ~d 5 S 20 E 9 D ./ v1 N e/ O T TTT RI SSSSSSSSSSSSSSS SSS IT UUUUUUUUUUUUUUE EEE A IIIIIIIIIIIIIIR RRv C DDDDDDDDDDDDDDE EEI O AAAAAAAAAAAAAAT TT' i L RRRRRRRRRRRRRRN NNh I III G IIEIEIIIIEIEIE N IILILIIIILILILLLLLLL I IIIIIIIIIIIIIIAOAAAO L MMMMMMMMMMMMMMIRIIIR CTCCCT S P N M 55555555555555ESEEEN O A - - - - - - - - - - - - - - PCPPPO I S 44444444444444 SCSSSC TACO L GN I L P M A S !!AR 2345675901234557895 01 ) G 33333333444444/44? 1 O 222222222222222222'_5 S N 2 RP O

0. )I IT 5

G A CfN C oI O E R L LIO B(T D A I L T N T O ( M L AC I d G e O d t L e e O t l I e e D D l A e ) K D)) )) E ) ) ))) ) E) EV) S E) W NE)SSVWM)S)) ) EEE A SE)S) NNS NNEESSW!E NEESSWVW)NNES BW M A M M M M M M M M M 0. 7 6 6 7 S 5 6 E 4 2 6 6 MMMMMMMMMMMM T N 656453793 A O 0 C I 00000000310000O0004400 T (((((((((((((((((((((( P I RCS T E S SS D E UU YYYYYYYYR YYYYYYYYIIYY N RRRRRRRRE RRRRRRRRDDRR O AAAAAAAAT AAAAAAAAAAAA DDDDDDDDN DDDDDDDDRRDD I T NNNNNNNNI NNNNNNNN NN A i UUUUUUU UUUUUUUUEEUU l C oOOOOO0OLLOOOOOOOOLLOO O BBBBBS2BAOBBBBBBBBIIBB L 1R MM EEEETET ' TTEEElEEE EE T T T T T T I"E, L N T T T T l T T T 5 5 T T GN IIIIIIIIPOIIIIIIII - II SSSSSSSSSCSSSSSSSS44SS I L /_ P M d A S 01234 00000Y,6727230567690156 001 222222223355 1 222222 4222222222222222

(' TAEU ').0-3 (' \\ _ (l\\s/1) CATA'iBA RADIOLOGICAL MONITORING FROGRAM ANALYSES ANALYSIS i SAMPLE MEDILM ANALYSIS SCIIEDULE ' GAMMA ISOTDPIC THITIIM LIV IIVEL I-131 GROSS EETA ILD i y i l 1. Radioiodine and Weekly X Particulates X X 1 .i I I 2. Direct Radiation Quarterly X 3. Surface Water Eiweekly X Monthly Composite X j Quarterly Composite X i i l

e.. Drinking Water Biweekly X

Monthly Composite X X Quarterly Composite X-i' 5. Shoreline Sediment Semiannually X 6. Milk Semimonthly X X i j 7. Fish Semiannually X a j 5. Broadleaf Vegetation Monthly X \\ f 9. Groundwater Quarterly X X X l'- 10. Food Products Monthly X (a) during harvest season T t hev. 13 4-l 1/1/87 l i i d i

TABIE C5.0-2 (- 1) f CATAWBA RADIOLOGICAL MONITO

PROGRAM SAMPI.ING IDCATIONS j

(OTHER CAMPLING IDCATIONS) = 4 CODE: .v* 6-o 1 ~ SM - Sesimonthly o, = *, g, yo j au e = w l W - Veekly = j BW - Bjweekly Q - Quarterly eg 4 g ' sE o *g e eI wa a e a i M - Monthly SA - Semiannually

h 4 *-

-o a c au ~ e ne

s.

x

.c we 2 -s ..o s. .o e.s

s. -o s.

s. -

e c -e - S agelie s _pesa tign_Dustlesign__ __ _ __ _ __ _ __ __ _ _ ___ ___ _ ___ _ _ _ _ _ _ _ _ ____ ___ __s:a3__.a. ~ a _y____e__.!_.__x ___e___ a r____v___ a___ _200 Site Boundary (0.6m NNE) V M j _201 Site'Boundarv (0.5m NE) W M j- _203 Site Boundarv (0.4m ESE1 Deleted M 1, 205 Site Boundarv (0.3m SW) W 203 Discharre Canal f0.5m S) BW SA SA _209 Dairy f7.0m SSW) SM _210 tbenezer Access (2.4m SE) SA _211 Wylie Dam (4.0a ESE) BW _212 Tera Cav'f3.3m El V i _2]3 Fort Mill _Yster Suoniv (7.5m ESE) BW _214 Rock Hill Water Sucolv (7.3m SSE) BW I _215 River Pointe - Hwy 49 f4.1m NNE1 Control BE SA _2}6 Ifwv 49 Bridre f4.0m NNE) Control SA _217 Rock Hill Substation (10.0a SSEi Control W M _218 Belmont Vater Suco1r (13.5m N) Control BW f _219 Dairy f6.Om SW) SM f- _220 Dalrv (B.Om VSW) Deleted SM i- -^ SM { _221 Dairv (13.0m NW) Control _226 Site Boundary f0.5m Si M I 252 Residence (0.7m SW) O j-M( a) : I _253 Irrirated Gard - fDownstream within 5 mile radiusi k _254 Residence (0.8m N) O I (a) during harvest. season hev. 25 l 1/1/90

A u --4m.L_ a _..A_..++--4..i<.4. me-..ee..a h-A w..a da a n.5 -J-4 -mm-Je km A 3 -.--^8* e;;; n C), een E. z-liR !$ E v v 5 iE E Q 2 h h 5 0 5 L >K A% j$ x 1 e I d i-Or I } Gsi.9 [ r"3 f/1 a. s b ii f .N' l n% : # 3 ' Ar' mgas 'd i d co YP l' ucv.,y\\) s') \\,{!, g jp .l 7 1 f , li gvQ i ~ j .. j .c r.- id +d 19 t r - if' N N ') ~ i i ; - ( : L,,, _s e 1] - M, i \\ !e { .,I= 3 g f" k I b.. '~ b.N _D x i. ~ s; E - -~ ...}}

ML20094H251

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