ML20066C363

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Offsite Dose Calculation Manual for Tx Utils Generating Co, Comanche Peak Nuclear Station
ML20066C363
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 10/31/1982
From:
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20066C357 List:
References
PROC-821031, NUDOCS 8211090475
Download: ML20066C363 (80)


Text

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!O                                                                                                                                                                                                    !

s 1 1 L I i 1 L , OFFSITE DOSE CALCULATION MANUAL  ! FOR L i i TEXAS UTILITIES GENERATING COMPANY COMANCHE PEAK NUCLEAR STATION t O OCTOBER 1982 1 l L i i .t l I l l i l

'O I

0211090475 821028 , PDR ADOCK 05000445 - A PDR i

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TABLE OF CONTENTS O List of Tables 111 List of Figures iv References v Introduction vi 1.0 Liquid Effluents 1-1 1.1 Liquid Radwaste Monitor Setpoint 1-1 1.2 Turbine Building Sump Effluent Monitor 1-5 1.3 Dose Calculations for Liquid Effluents 1-8 1.4 Service Water Effluent 1-12 2.0 Gaseous Effluents 2-1 2.1 Gaseous Effluent Monitor Setpoints 2-1 2.1.1 Plant Vent Stack Noble Gas Monitors 2-1 XRE 5570A and XRE5570B 2.1.2 Plant Vent Stack Iodine Monitors 2-4 2.2 Gaseous Effluent Dose Calculations 2-6 2.2.1 Unrestricted Area Boundary Dose Rates 2-6 2.2.1.a Dose Rates Due to Noble Gases 2-6 2.2.1.b Dose Rates Due to Radioiodine, 2-6 i Tritium, and Particulates 2.2.2 Unrestricted Area Air Dose and Dose to Individuals 2-7 2.2.2.a Air Dose in Unrestricted Areas 2-7 2.2.2.b Dose to An Individual 2-8 2.2.2.c Dose Calculations to Support Other 2-9 Technical Specification 2.3 Meteorological Model 2-25 2.4 Definition of Gaseous Effluent Parameters 2-31 i

I TABLE OF CONTENTS O

  • 3.0 Radiological Environmental Monitoring 3-1 APPENDIX A. Pathway Dose Factor (Pg ) Determination A-1 B. Inhalation Pathway Factor (R g) Determination B-1

, C. Ground Plane Pathway Factor (Rg ) Determinatien C-1 l D. Grass, Cow-Milk Pathway Factor (Rg ) Determination D-1 E. Vegetation Pathway Factor (Rg) Determination E-1 F. Computer Program (ODCM-1) F-1 l I O 1 1 < l 4

. O                                                                   ii

List of Tables

 - Table No.                   Title                  g 1.1      Site Related Ingestion Dose              1-10 Commitment Factor (A )

4 2.1 Dose Factors for Exposure to a Semi- 2-5 Infinite Cloud of Noble Gases 2.2 Pathway Dose Factors for Section 2-10 2.2.1.b (P g) (For Dose Calculations Required by TS 3.11.2.1) 2.3 Pathway Dose Factors for Section 2-19 2.2.2.b (R g) (For Dose Calculations Required by TS 3.11.2.3) Infant 2.4 Pathway Dose Factors for Section 2-16 2.2.2.b (R g) (For Dose Calculations Required by TS 3.11.2.3) Child 2.5 Pathway Dose Factors for Section 2-18 2.2.2.b (R g) (For Dose Calculations Required by TS 3.11.2.3) Teenager 2.6 Pathway Dose Factors for Section 2-20 l 2.2.2.b (R f) (For Dose Calculations Required by TS 3.11.2.3) Adult i 2.7 Atmospheric Dispersion Parameters for 2-23 l Technical Specifications 4.11.2.4.1 2.8 Controlling Receptore. Locations, and 2-24 Pathways (For Dose Calculations Required by TS 3.11.2.3, 3.11.2.4 and 6.9.1.13'j 3.1 Environmental Sampling Locations 3-2 111

List of Figures On U Figure Title Pjijge 1.1 Liquid Effluent Discharge Pathways 1-13 1.2 Example Calibration Curve for Liquid 1-14 Effluent Monitors 1.3 Circulating Water Pump Curves 1-15 1.4 Simplified Liquid Waste Processing System 1-16 2.1 Simplified Gaseous Waste Processing System 2-22 2.2 Plume Depletion Effect for Ground Level 2-27 Releases 2.3 Vertical Standard Deviation of Material 2-28 in Plume 2.4 Relative Deposition for Ground-Level 2-29 Releases 2.5 Open Terrain Recirculation Factor 2-30 3.1 Environmental Sampling Locations 3-6 l l l l O iv i i r I

                                         .                        .                                                  = -

l REFERENCES

1. Boegli, T. S., R. R. Bellamy W. L. Britz, and R. L. Waterfield,
                       " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133 (October 1978).
2. Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, U. S. NRC Regulatory Guide 1.109 (March 1976) .
3. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, U. S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977).
4. " Environmental Report," Texas Utilities Generating Company, Comanche Peak Steam Electric Station.
5. " Final Safety Analysis Report." Texas Utilities Generating Company, Comanche Peak Steam Electric Station.
6. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors,

?. O U. S. NRC Regulatory Guide 1.111 (March 1976).

7. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Release from Light - Water - Cooled Reactors, U. S. NRC Regulatory Guide 1.111, Rev. 1 (July 1977).

O V d 4 i

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INTRODUCTION O The OFFSITE DOSE CALCULATION Manual is a supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS. As such the ODCM describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. The ODCM contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program. Minimum OPERABLE configurations of the liquid and gaseous radwaste treatment systems are shown in Figures 1.4 and 2.1. The ODCM will be maintained at the plant for use as a reference guide and training document of accepted methodologies and calculations. Changes in O the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas. Computer sof tware to perform the described calculations l will be maintained current with this ODCM. I l l l l l l [ O vi l

SECTION 1.0 LIQUID EFFLUENTS The Comanche Peak Steam Electric Station, Units 1 and 2, is located on the U~' Squaw Creek Reservoir which is a point of supply and discharge for the plant circulating water. Liquid releases are made via the Circulating Water Discharge Canal. Discharge pathways for the liquid radwaste sources are shown in the diagram of Figure 1.1. Although no significant releases of radioactivity are expected from the General Service Water System, this effluent pathway is monitored as a precautionary measure. 1.1 GENERAL METHODOLOGY FOR DETERMINING LIQUID EFFLUENT MONITOR SETPOINTS Normal liquid releases from the radwaste system will originate from the laundry holdup tanks and waste monitor tanks and terminate in Squaw Creek Reservoir. To ensure such discharges do not exceed the limits of 10CFR20, Appendix B, Table II, Column 2 at the release point to the unrestricted area, an in-line radiation detector monitors O

 \s /          discharges to the circulating water discharge canal.

X-RV-5253 is the isolation valve controlled by detector X-RE-5253. The isolation valve shuts automatically if the detector alarms or is placed out of service. The methodology for determining the setpoint for detector X-RE-5253 is as follows: 1.1.1 Determine the isotopic concentration of the waste tank to be re- ! leased. IC g = IC + ( C, + C, + Cg + Cp ,) i g l ICf= batch radioactive concentration (uCi/ml) i l IC = concentration of each measured gamma emitter (pci/ml) 8 C, = concentration of alpha emitters as measured in the monthly composite sample. (Sample analyzed for ! 1-1 I

  <                               gross alpha only)  (pCi/ml)

C, = concentration of Sr-89 and Sr-90 as measured in the quarterly composite sample (pCi/ml) C = concentration of H-3 as measured in the monthly composite sample (pC1/ml) Cp ,= concentration of Fe-55 as measured in the quarterly composite sample (pC1/ml) 1.1.2 Determine the Maximum Effluent Flow Rate (f) The effluent discharge rate is determined from the number of pumps running and their capacity. The radwaste system is-comprised of the following pumps: Laundry Holdup and Monitor Tank Pump - 100 gpm Waste Monitor Tank Pump #1 - 100 gpm i Waste Monitor Tank Pump #2 - 100 gpm Normally, only one waste tank will be pumped at a time. If, however, more than one tank is to be pumped, the tanks will be sampled and the maximum isotopic concentrations will be used to determine ECg . As a worst case condition, the effluent flow rate 1 (f) will be determined as total pumping capacity of the Laundry Holdup and Waste Monitor Pumps (300 gpa). To ensure that under no circumstances the effluent flow rate is under estimated, a safety factor of 1.5 will be applied (300 x 1.5) to yield f = 450 gpm. This maximum effluent flow rate of 450 gpm will be used in the calculation of dilution factor for all liquid radwaste system batch discharges. i 1.1.3 Dilution of Liquid Effluents Due to Circulating Water Flow (F) Since liquid effluent from the radwaste treatment system is mixed.with circulating water prior to being returned to Squaw 1-2

Crssk Recsrvoir, the catpoint for datsctor X-RE-5253 is a function of the circulating water flow rate. The total circulating water flow rate per plant is 1.1 million gpm. This is determined from the Ingersoll-Rand pump curves (Fig. 1.3) which indicate a flow rate per pump of 275,000 gpm. At least two operating pumps are required for a discharge to take place. Isolation valve, X-RV-5253, will shut automatically if less than two circulating pumps are in operation. F(diluting flow) = (275,000 gpm/ pump) x (# of pumps) x SF x AF Where: SF = Safety Factor of (.9). This compensates for flow fluctuations from tr.e rate predicted by the circulating water pump curses (Fig. 1.3). AF = Allocation Factor of (.5). This compensates for simultaneous turbine building sump discharges with batch radwaste discharges to the environment. Turbine building sumps would only be contaminated upon a significant primary to secondary leak. 1.1.4 Determine the Actual Dilution Factor (ADF) ADF is the ratio of the effluent flow rate plus the circulating water flow rate divided by the effluent flow rate. ADF = (f + F)/f Where: f = 450 gpm F = (275,000 gpm/ pump) x (# of pumps) x SF (.9) x AF (.5) 1.1.5 Determine the Required Dilution Factor (RDF) The required dilution factor ensures that the isotopic concentrations expressed in 10CFR20, Appendix B, Table II, Column 2 are not exceeded during a discharge. RDF = (E (C /MPC 1 )) x SF , i ,

                   = (E (C g/MPCg ) + (C,/MPC,+ C,/MPC, + C /MPC t +CFe/MPCFe)) x SF Where: MPCf = Maximum Permissible Concentrations of Radionuclide i SF = Safety Factor of 2 1-3

NOTE: If RDF is less than 1, the tank effluent meets discharge limits without dilution. Detector, X-RE-5253, would O then be set in accordance with Eq. 1 below with RFD set equal to 1. 1.1.6 Determining the Counts / Minute (Upper Setpoint Limit) for Detector X-RE-5253 Eq. 1 c = (ADF/RDF) x I Cg Where c = The gamma concentration corrected for dilution in microcuries/ml. From this concentration level, the detector setpoint in counts / minute is determined from the detector calibration curve (Figure 1.2

         .                     Example Only).

As a further consideration, the reservoir into which the diluted rad-waste flows may build up a concentration of radioactive isotopes. It is therefore necessary to account for recirculation of previously discharged radionuclides. This is accomplished as follows: Eq. 2 F' = F (1 - I (C'/MPCf)) F' = Adjusted Circulating Water Flow Rate C[=RadionuclideConcentrationoftheReservoir l MPCf = Maximum Permissible Concentration of Radionuclide i F = (275,000 gpm/ pump) x (# of pumps) x SF x AF NOTE: If C is less LLD then F' = F and no adjusted flow rate f need be considered in the calculation of ADF. LLD is the ! smallest concentration of radioactive material in a sample l that will be detected with a 95% probability. A V l-4 1

1 1.2 Turbin7 Building Su p Efflumnt Lina Monitor The Purpose of the detector for the turbine building sumps is to O menicer discharSes se as te Prevent centaminatien in excess ef the 10CFR20 limits from reaching Squaw Creek Reservoir. Because the only sources to the sump effluent are from the secondary steam system, activity is expected in the turbine building sump effluent only if a significant primary-to-secondary leak is present. If a primary-to-secondary leak does exist, the activity in the sump effluent system would be comprised of only those radionuclides found in the secondary system, but with reduced activity due to decay and dilution. Until activity is measured in the secondary system, it will not be possible to measure all the radionuclides on which the detector should be set. Therefore, the detector will be set administratively as follows: C = MPC (Co ) x Actual Dilution Factor (ADF) O C in microcuries/ml is then used to determine the count per minute setpoint from the detector curves.' i l The Actual Dilution Factor is determined in the following manner: 1.2.1 Determine Maximum Effluent Flow Rate (f) A maximum sump effluent flow rate is determined by summing the 1 . combined outputs of the pumps for the turbine building sumps.

                                      #1              300 gpm Sump No. 2
                                      #2              300 gpm
                                      #1               50 gpm Sump No. 2 l                                      #2               50 gpm Total pumping capacity = 700 gpm x SF (1.5) = 1050 gpm SF = Safety Factor of 1.5 1-5
            . __                             __       .- . _ _ _               _                .~   ._ _

l.2.2 Determine Minimum Circulating Water Flow (F) 1 As a worst case, the administrative monitor setpoint will be based upon two operating circulating water pumps out of four. Due to pump cavitation and pump flow vortexing, two pumps is the minimum conceivable circulating water pump lineup.

  • l F = 2 pumps x-(275,000 gpm/ pump) x SF (.9) x AF (.$) = 247,500 gym (SF = Safety Factor of .9), (AF = Allocation Factor of .5) 1.2.3 Determine the Actual Dilution Factor (ADF)

ADF = f + F f

                                 = 1050 + 247,500 = 236.7 1050                                                              i The administrative setpoint therefore becomes:

c = 236.7 (MPC Co ) (Setpoint Upper Limit) If the administrative alarm point is exceeded while discharging to the lake, the discharge will be halted or directed to the i evaporation ponds as desired. After a significant primary-to-secondary leak'has been confirmed and the isotopic concentration of the secondary has been determined, the monitor alarm point will be redetermined in the following manner: 1.2.4 Determine the Isotopic Concentration of the Secondary Effluent Eg C1 .= E C + (C, + C, + Ct + Cp ,) E C = radioactive concentration of the secondary (y C /mi) g I C = concentration of each measured gamma emitter in the effluent i C, = measured concentration of alpha emitters in the effluent A 1-6 vm w- - - - - - . , , + - , - , - , , - , - , , - . e

C, = mascurtd concsntration of SrS9 and SR90 in th2 effluent O C g = measured concentration of H-3 in the effluent Cp , = measured concentration of Fe55 in the effluent 1.2.5 Determine the Required Dilution Factor (RDF) RDF={(C/MPC)xSF g MPC = Maximum Permissible Concentration of Radionuclide i SF = Safety Factor of 2 C g = effluent isotopic concentrations 1.2.6 Determine the Actual Dilution Factor (ADF) ADF = f + F f f = 1050 gpm F = (275,000 gpm/ pump) x (# of pumps) x SF x AF Note: See Eq. 2 if C ' is greater than LLD 1 O Cg ' = radionuclide concentration of the lake water 1.2.7 Utilizing the information provided above, the turbine building sump detector will be set as follows: c = (ADF/RDF)x E C 8 8 , t c in microcuries/ml is then referenced to the detector curves to determine the proper count per minute setpoint. If at any time, the administrative or post accident alarm setting is exceeded, effluent flow will be terminated or directed to the evaporation ponds until such time as the effluent meets State and Federal limits for discharge to Squaw Creek Reservoir. l

O i

1-7

1.3 Dose Calculation for Liquid Effluents The dose contribution from the release of liquid effluents will be O calculated once per 31 days and a cumulative summation of the total body and organ doses will be maintained for each calendar quarter. The dose contribution for all b. tch releases for the quarter will be calculated using the following equation: D =E[A gT It k ik k i k=1 Where: D = the cumulative dose commitment to the total body or any organ from all liquid effluent releases in a 31 day period. t k= the time duration of the batch release in hours. C = the isotopic concentration (microcuries/al) of ik radionuclide (1) found in the pre-release sample. Concentrations are determined primarily from a gamma O isotopic analysis of the' liquid effluent sample. For , Sr89, Sr90, H3, and Fe55, the last measured value i will be used in the dose calculation. F = near field average dilution factor during a liquid k effluent release. Defined as the ratio of the average undiluted liquid waste flow during release to l the average circulating water flow. For conservatism, the maximum effluent flow rate will be used in the calculation.

                                       = Maximum Effluent Flow Rate Circulating Water Flow Rate Max. Eff. Flow Rate = 450 for the Waste Processing System or 1050 for the Turbine Building Sump discharge.

1-8

        .-         _         -=             .                                              - -

A g7 = the site related ingestion dose comitment factor to I the total body or any organ for each identified principle gansna and beta emitter, mrem /hr per microcurie /ml. Ag7 = ko (U ,/ D,+ UpBF f) DFg Where: ko = unit conversion factor, 1.14x10 5 Uy = adult water consumption, 730 liters / year Up = adult fish consumption, 21 liters / year BFg = Bio accumulation factor, Table A-1, Ref. 3 DF = Dose Conversion Factor, Table II, Ref. 2 Dy = near field dilution factor, (1) for CPSES Calculated values for Ag for nuclides with a half life greater than eight days are given in Table 1.1. NOTE: It may be necessary to consider the recirculation of

   /

previously discharged radionuclides should they be detected in the water of Squaw Creek Reservoir. If C' i (lake) is greater than LLD, then D g must be calculated and added to the 31 day Dg (effluent) amount. D x t x C' h (lake) = A f Where: t = 744 hours (31 days) C' = isotopic concentration for radionuclides i in the lake. 1-9 O

TABLE 1.1 SITE 7 ELATED INGESTION DOSE COMMI7t4ENT FAC OR. 4ir (]~) (mrem /HR PEP.uC /ML) 4 TOM SONE _IVER T-BODY THYROID KIDNEY LONG GI-LLI H3 0.00E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 3.96E+00 '

 ;       RC : 4          3.!5E+04          6.30E+03             6.30E+03    6.30E+03      S.30E+03               6.30E+03   6.30E+03 4

P32 4.62E+07 2.87E+06 1.79E+06 0.00E+00 0.00E+00 0.00E+00 5.20E+06 CR51 0.00E+00 0.00E+00 f.49Ee00 8.94E-Of 3.29E-01 f.98E*00 3.76E+02 MN54 0.00E+00 4.76E+03 9.08E+02 0.00E+00 1.42E+03 0.00E+00 1.46E+04 FESS 8.87E+02 6.I3E+02 f.43E+02 0.00E+00 0.00E+00 3.42E+02 3.52E+02 FES9 1.40E+03 3.29E+03 1.26E+03 0.00E+00 0.00E+00 9.19E+02 1.10E+04 4 C058 0.00E+00 1.51E+02 3.39E+02 0.00E+00 0.00E+00 0.00E+00 3.06E+03. C060 0.00E+00 4.34E+02 9.58E+02 0.00E+00 0.00E+00 0.00E+00 8.16E+03 NI63 4.i9E+04 2.9tE+03 1.4tE+03 0.00E+00 0.00E+00 0.00E+00 6.07E+02'r 2.36E+04 7.50E+04 3.39E+04 0.00E+00 -5.02E+04 0.00E+00 4.73E+04 ({J-ZN65 RB86 0.00E+00 1.03E+05 4.79E+04 0.00E+00 0.00E+00 0.00E+00 2.03E+04 SR89 4.78E+04 0.00E+00 1.37E+03 0.00E+00 0.00E+00 0.00E+00- 7.66E+03 , SR90- t,t8E+06 0.00E+00 2.88E+05 0.00E+00 0.00E+00 0.00E+00 3.40E+04-Y91M 1.30E-02 0.00E+00 5.04E-04 0.00E+00 0.00E+00 0.00E+00 3'.82E-02 Y91 2.02E+01 0.00E+00 5.39E-01 0.00E+00 0.00E+00 0.00E+00 f.11E+04 ZR95 2.77E+00 8.88E-01 6.01E-01 0.00E+00 1.39E+00 0.00E+00 2.82E+03 1895 4.47E+02 2.49E+02 1.34E+02 0.00E+00 2.46E+02 0.00E+00 f.51E+06 h 4.07E-02 TC99M 2.94E-02 8.32E-02 1.06E+00 0.00E+00 1.26E+00 4.92E+01 RUiG3 1.98E+01 0.00E+00 8.54E+00 0.00E+00 7.57E+0 0.00E+00 2.31E+03 i RU106 2.95E+02 0.00E+00 3.73E+01 0.00E+00 5.69E+02 0.00E+00 1.91E+04 i

AGi10M l.33E+01 f.23E+01 7.32E+00 0.00E+00 2.42E+01 0.00E+00 5.03E+03 TE125M 2.79E+03 1.01E+03 3.74E+bz 8.39E+02 1.13E+04 0.00E+00 1.11E+04 i

4 _ _ _ _ _ _ _. .__ . . . _ _ _ _ _1 _-10_ _ _ _ . . _ -_ . . . _ . . ., .-

TABLE 1.l(Cont)

 <-                 SI7E RELATED INGESTION DOSE COMMITMENT FACTOR. air

(_)3 (MREM /hr per uC1/ml) cTOM BGNE LIVER T-BODY THYROID KIDNEY LONG Gt-LL1 TE127M 7.05E+03 2.52E+03 8.59E+02 ' 80E+03

                                                    .      2.86E+04   0.00E+00  2.35E-Oc TE 27  f.i4E+02    4.11E+01  2.48E+01     8.48E-01  4.66E+02  0.00E+00   9.03E+03 TE129M 1.20E+04    4.47E+03  1.89E+03     c.11E+03  5.00E-04  0.00E+00   6.03E+04 TEf29 3.27E+0!     i.23E+0i  7.96E+00     2.51E+0!   1.37E-02 0.00E+00  2.47E+0:

I131 4.96E+02 7.09E+02 4.06E+02 2.32E+05 1.22E+03 0.00E+00 1.87E+02 CS134 3.03E+05 7.2fE+05 5.39E+05 0.00E+00 2.33E+05 7.75E+04 1.26E+04 CS136 3.17E+04 1.25E+05 9.01E+04 0.00E+00 6.97E+04 9.55E+03 1.42E+04 CS137 3.88E+05 5.31E+05 3.48E+05 0.00E+00 1.80E+05 5.99E+04 1.03E+04 BA140 1.88E+03 2.37E+00 1.23E+02 0.00E+00 8.05E-01 1.35E+00 3.88E+03 CE144 4.!8E+0i f.75E+01 2.24E+00 0.00E+00 1.04E+01 0.00E+00 1.41E+04 1.32E+00 (]) PR143 5.28E-01 6.52E-02 0.00E+00 3.05E-01 0.00E+00 5.77E+03 ND147 9.00E-01 1.04E+00 6.22E-02 0.00E+00 6.08E-01 0.00E+00 4.99E+03 W187 3.04E+02 2.55E+02 8.90E+01 0.00E+00 0.00E+00 0.00E+00 8.34E+04 NP239  :.28E-0! i.25E-02 6.9fE-03 0.00E+00 3.91E-02 0.00E+00 2.57E+03 l l ($) i SL-XL

1.4 SERVICE WATER EFFLUENT RADIATION MONITOR RF 4270 Concentration of radioactivity in this effluent line normally is expected to be insignificant. Therefore, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur. If this effluent stream should become contaminated with radioactivity, radionuclide concentrations must be determined and a radiation monitor setpoint determined as follows: C=(ICg )

  • DF (Setpoint upper limit)

Where IC = the concentration of each measured gamma emitter observed g in the effluent (uci/ml) DF = (Cg/MPC ) For this release pathway no additional dilution is available. Therefore, o releases are permissible if DF is greater than 1. O l-12

O O O

                                                                 ,.                                                                    ,    " lilGURE 1.1 LIQUID EFFLUENT DISCHARGE PATHWAYS C

450 CPM g q, . _ (7242 GAL) g Yancat U y M ( G EAi w name

       =

40CFM EA W l Q300 GAL) 23 . 7 =-" _,pwe b I acut sawnaian a (f35 GAL EA) 40GPM EA g ' Q300 GAL) _ , , _

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qM ,, 3

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                                                                                                                              %                                                                          y                       ,

I- I l\ l 4  ; I I ( 7 GAL) t.ases esoUs tsar a **8 Lean os.

  • g gpg g sese m as 300 GPM (1120 GAL) h I*

(135 GAL EA)

                                                                                                                                                       , M PL.f a, I

i p b us a g GPM a= u ra- r-

i FHMIE 1.2 EXAMPLE CAUBRATION CURVE O FOR LIQUID EFFLUENT MONITOR 10-31 , 1-  ; f

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                                                                                                                                                                                                  +

s FIGURE 1.4 Reactor Codont Drain Tonk , Ll0UID WASTE PROCESSING SYSTEM Pressurirer Relief Tonk R; fueling Canal Drains , > gm

                                                                                                                           @-Radiation Monitor R C. Loop Drains                                     I    Recycle
                                                    ,                                                                      @-Stroiner SI. Accurnfotor Drains                                    Holdup Tonk                                                  -
                                                                                                                           @- Riter                              Reactor g                                                                              Main Flow fbth              Make @
                                                                                                                                                         --> %ter
                                                      ;                                                                      ----- Alternate Flow Poth           Storoge l

Tonk I CHANNEL A. I Waste - OUf*

  • Evaporator p

Drain Header y Tonk We Sample Room Sinks ___ _ ___ M hdizer g# onk Tank l i

                                                                                  -----__--___________________-t__..____--

i E CHANNEL B ' Floor Drain Condensate

  • Evoporator Storage Floor Drains Floor g Tonk La Rs o er k e i----------i Monitor l l jg Tonk l l L_____________________.__________________,l l l

I CHANNEL C Loun&y e lDischooge Loundry f Loundry, Handwash T l Ho Shower Reverse l*'"* Y l ed Het Shower Drains Tonk ~@-~b A Osmosis ,$" - - ~ ~ - - - - - - fbckage Tonk t______________________]

SECTION 2.0 GASEOUS EFFLUENTS-O 2.1 GASEOUS EFFLUENT MONITOR SETPOINTS The gaseous monitor setpoint values determined in the following sections will be regarded as upper bounds for the actual setpoint adjustments. That is, setpoint adjustments are not required to be made if the existing setpoint level corresponds to a lower count rate than the calculated value. Setpoints may'be established at values lower than the calculated values if desired. If a calculated setpoint is less than the monitor reading associated with the particular release pathway, no release may be made. Under such circumstances, contributing source terms may be reduced and the setpoint recalculated. At CPSES, all gaseous effluents are released to the atmosphere through the two Plant Vent Stacks (Figure 2.1). Setpoint methodology for the noble gas monitors O associated with the plant vent is addressed in the following section. 2.1.1 PLANT VENT STACK NOBLE GAS MONITORS XRE5570A and XRE5570B For implementation of Technical Specification 3.3.3.11, the alarm setpoint level i for these noble gas monitors will be calculated as follows: C 3 = Honitor reading of the noble gas monitor at the alarm setpoint con-centration. (SF) x R xDTB * ^

               = the lesser of              or l

(SF) x Rs xD ss x AF

 ]

L 2-1

SF = Safsty FIctor (.5); a cannorvativa factor cpplisd to ecch noble gas moni-tor to compensate for statistical fluctuations and errors of measurement. AF = Allocation Factor (.5); a factor allowing for releases from both plant stacks simultaneously. R t

     = m nitor reader per mrem /yr to the total body
     = C + (X/5) IKgQg K

1

     = total body dose factor due to gamma emissions from noble gas radio-nuclide 1 (mrem / year per microcurie /m ) from Table 2.1.

R, = monitor reading per mrem /yr to the skin

     = C + (X/Q) E (Lg + 1.1 M1 ) Qt L

1

     = skin dose factor due to beta emissions from noble gas radionuclide 1 (mrem /yr per microcurie /m ) from Table 2.1.

1.1 = mrem skin dose per mrad air dose Mg = air dose factor due to gamma emissions from noble gas radionuclide 1 (mrad /yr per microcurie /m ) from Table 2.1) Qg = the release rate of noble gas radionuclide i from the Plant Vent Stack (microcurie /sec).

     = the product of Zgy and Fy , where Xgy is the concentration of noble gas radionuclide 1 (microcurie /ml) as measure at the vent and F y

is the flowrate at the vent (ml/sec). C = monitor reading of a noble gas monitor corresponding to the grab sample radionuclide concentrations taken in accordance with RETS Table 4.11-2. The count rate corresponding to the measured concen-tration is determined from the monitor calibration curve supplied by the instrument manufacturer or based on historical data for a parti-cular monitor. O 2-2

X/Q = the highest annual average relative concentration at the site boundary. , (If desired, the annual average relative concentration at the site boundary for the particular release point may be used). 3

                = 3.3 x 10     sec/m    in the NNW sector.

D TB = d se rate limit to the total body of an individual in an unrestricted area.

               = 500 mrem / year (Technical Specification 3.11.2.la).

D,, = Dose rate limit to the skin of the body of an individual in an unrestricted area.

              = 3000 mrem / year (Technical Specification 3.11.2.1.a).

With the addition of a batch release (waste gas decay tank or containment purge) into the effluent stream, the Q1 term will be calculated in a similar manner as previously shown. The flow rate at the vent monitor is given by F =F +F i v c B where F e = the flow rate contribution of the plant ventilation system (ml/sec). F B = the flow rate contribution associated with the release rate of the batch source (ml/sec). This value will be very small as compared to the value of F . The resulting concentration due to the combined sources that would be detected by the Plant Vent Stack Monitor is given by:

                                                 +

ic c 1B B, iv " F +F B O v 2-3

whers: Xg = the concentration of noble gas radionuclide 1 (microcurie /ml) in the continuous release stream as sampled in accordance with RETS Table 4.11-2. X iB = the concentration of noble gas radionuclide 1 (microcurie /ml) in the continuous release stream as sampled in accordance with RETS Table 4.11-2. The count rate corresponding to this combined concentration (Xgy) at the vent monitor is determined by the monitor calibration curve as previously described. The release rate at the vent for noble gas radionuclide 1 (microcurie /sec) is given by 0 1 =F y Xgv

                                 "        +

ic c iB B l 2.1.2 PLANT VENT STACK IODINE MONITORS l l In general it is not practical to establish a setpoint for the Plant Vent Stack Radioiodine !!onitors to ensure compliance with Technical Specification 3.11.2.lb.

Therefore, dose rate calculations should be performed in accordance with Section 2.2.1 and compared with the Technical Specification dose rate limit of 1500 mrem /

year for compliance. An Allocation Factor and Safety Factor should also be utilized for this determination. 1 O l 2-4

TABLE 2-1 O DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUO OF NOBLE CASES,

  • Nuclide Y' -80dy'** (K) 0-Skin ***(L) Y-Air **(M) @-Air **(N)

Kr-85m 1.17E+03**** 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.llE+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-13$m 3.12E+03 7.llE+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

  • Values taken from Reference 3, Table B-1
     " mrad-m3 pCi-yr
    *** mrem-m3 pCi-yr
   *"* 1.17E+03 = 1.17 x 103 2-5

2.2 CASEOUS EFFLUENT DOSE CALCULATIONF

       -2.2.1  Unrestricted Area Boundary Dose Rates 2.2.1.a  Dose Rates Due to Noble Gases For implementation of Technical Specifications 3.11.2.1.a, the dose rate at the unrestricted area boundary due to noble gases shall be calculated as follows:

D = average total body dose rate in the current t year (mrem /yr)

                            = (X/Q)     {K         Q D, = average skin dose rate in the current year (mrem /yr)
                            = (X/Q)   [ (L g      + 1.1 M)  (Q )

2.2.1.b Dose Rates Due to Radiciodines, Tritium and Particulates Organ doses due to radioiodines, tritium, and all radioactive materials in particulate form with half-lives greater than eight days, will be calculated to implement O the requirements of. Technical Specification 3.ll.2.1.b as follows: D = average organ dose rate in the current year 9 (mrem /yr)

                            = (X/4     [P         Q1 where:   P = dose parameter factor for radionuclide i; (mrem /yr per microcurie /m ), for inhalation.

(Table 2.2) Q = the release rate of radionuclide i for (radioiodine, tritium, and particulates) as determined from the concentrations measured in the analysis of the appropriate sample required by Technical Specification 3.11.2.1.b. 2-6

2.2.2 Unrestricted Arca (Air Dose / Dose to Individual) 2.2.2.a Air Dose in Unrestricted Areas For implementation of Technical Specification 3.11.2.2 and 3.11.2.4, the air dose in unrestricted areas shall be determined as follows: D y= air dose due to ganma emissions from noble gas radionuclide 1 (mrad)

                      = 3.17 x 10 -8      M (X/Q) Q where: 3.17 x 10 -8   = the fraction of a year represented by one second M gis defined in section 2.1.1 X/Q = the relative concentration for the location occupied by the maximum exposed individual
                                            -0        3
                                 = 3.3 x 10     sec/m in the NNW Sector Qg    = the cumulative release of noble gas radionuclide i (microcuries) for the type of release under consideration Dg    = air dose due to beta emissions from noble gas radionuclide 1 (mrad)
                                 = 3.17 x 10 -8 I

N (X/Q) Q 1 where: N = the air dose factor due to beta emissions from ! noble gas radionuclide 1 (mrad /yr per ( microcurie /m ) Table 2.1 l l 2-7

a m - 2.2.2.b Dose to an Individual O

  \w /               Dose to an individual from radiciodine, tritium, and radioactive materials in particulate form will be calculated to impleuent Technical Specification 3.11.2.3. and 3.11.2.4 as follows:

D = do'se to an individual from radioiodine, tritium, and radionuclides in particulate form (mrem)

                            = 3.17 x 10
                                         -8 R   W' Q where:  W'     = relative dispersion parameter
                            = for inhalation of all tritium pathways
                            = 2.8 x 10 ' M-2 in the WNW Sector R      = dose factor for radionuclide 1 (Table 2.3 - 2.6)

Q} = cumulative release of radionuclide i as required by Technical Specification 3.11.2.3 in

    }

(microcuries) 4 i I i () 1 2-8 l t

O 2.2.2.c DOSE CALCULATIONS TO SUPPORT OTHER TECHNICAL SPECIFICATIONS For the purpose of implementing Technical Specification 6.9.1.13 dose calculations will be performed using the above equations with the substitution of average i meteorological parameters for the period of the report, and the appropriate pathway receptor dose factors (Rg ) . Values for Rg may be found in Tables 2.3 through 2.6. For the purpose of implementing Technical Specification 6.9.1.9, dose calcula-tions may be performed using the above equations with the substitution of the dispersion parameters (X/Q, D/Q) which are concurrent with actual releases, and the appropriate pathway receptor dose factors. For the purpose of implementing Technical Specification 3.12.2, dose calcula-tions may be performed using the above equations substituting the appropriate pathway receptor dose factors and the appropriate dispersion parameters for the location (s) of interest. Annual average dispersion parameters (or grazing period average for D/Q may be used for these calculations). I l O 2-9

TABLE 2.2

 /~'                   PATHWAY DOSE FACTORS FOR SECTION 2.2.1.b (P

(_) I )* (For Dose Calculation Required by TS 3.11.2.1) Page 1 of 4 AGE GROUP ( CHILO )

ISOTOPE  : INHALATION  :
H_3  : 1.125E+03  :
C-14  : 3.589E+04  :
NA-24  : 1.610E+04  :
P-32  : 2.605E+06  :
CR-51  : 1.698E+04  :
MN-54  : 1.576E+06  :
MN-56  : 1.232E+05  :
FE-55  : 1.110E+05  :
FE-59  : 1.269E+06  :
C0-58  : 1.106E46  :
C0-60  : 7.067E+06  :
NI-63  : 8.214E+05  :
NI-65  : 8.399E+04  :
CU-64  : 3.670E+04  : -
ZN-65  : 9.953E+05  :
ZN-69  : 1.018E+04  :
BR-83  : 4.736E+02  :
BR-84  : 5.476E+02  :
     + Values based on Reference 1,           Section 5.2.1 assumptions unless otherwise indicated in Reference 5 1 - mrem /yr per pC1/m 3 2-10

TABLE 2.2 (Continued) PATHWAY OOSE FACTORS FOR SECTION 2.2.1.b (Pg ) Page 2 of 4 AGE GROUP ( CHILO )

ISOTOPE : INHALATION :
8R-85  : 2.531E401  :
RB-86  : 1.983E+05  :
R8-88  : 5.624E+02  :
R8-89  : 3.452E+02  :
SR-89  : 2.157E+06  :

i

SR-90  : 1.010E+08  :
SR_91  : 1.739E+05  :
SR-92  : 2.424E+05  :
Y-90  : 2.679E+05  :
Y-91M  : 2.812E+03  :
Y-91  : 2.627E+06  :
Y_92  : 2.390E+05  :
Y-93  : 3.885E+05  :

l

ZR-95  : 2.231E+06  :
ZR-97  : 3.511E+05  :
2 -95  : 6.142E+05  :
MO-99  : 1.354E+05 .:
TC-99M  : 4.810E+03  :
TC-101  : 5.846E+02  :
RU-103  : 6.623E+05  :
RU-105  : 9.953E+04  :

1 _ mrem /yr per uCl/m3 2-11 . i L

TABLE 2.2 (Continued) PATHWAY DOSE FACTORS FOR SECTION 2.2.1.b (Pg ) Page 3 of 4 AGE GROUP ( CHILD )

ISOTOPE : INHALATION  :

i

RU-106  : 1.432E+87  :
AG-110M : 5.476E+06  :
TE_125M : 4.773E+05  :
TE_127M : 1.480E+06  :
TE-127
5.624E+84  :
TE-129M : 1.761E+06  :
TE-129  : 2.549E+04  :
TE-131M : 3.078E+05  :
TE-131  : 2.054E+03  :
TE-132  : 3.774E+05  : .
I-138  : 1.046E+06  :
I-131  : 1.624E+07  :-
I-132  : 1.935E+05  :
I-133  : 3.848E+86  :
I-134  : 5.069E+04  :
I-135  : 7.918E+05  :
CS-134  : 1.014E+06  :
CS-136  : 1.709E+05  :
CS-137  : 9.065E+05  :
                 ~
CS-138  : 8.399E+02  :
BA-139  : 5.772E+04  :

1 1 - mrem /yr per pC1/m3 2-12

TABLE 2.2 (Continued) PATHWAY DOSE FACTORS FOR SECTION 2.2.1.b (Pf ) Page 4 of 4 AGE GROUP ( CHILD )

ISOTOPE : INHALATION  :
BA-148  : 1.743E+06  :
BA-141  : 2.919E+03  :
BA-142  : 1.643E+03  :
LA-140  : 2.257E+05  :
LA-142  : 7.585E+04  :
CE-141  : 5.439E45  :
CE 143  : 1.273E+05  :
CE-144  : 1.195E+07  :
PR-143  : 4.329E+05  :

i :PR_144  : 1.565E+03  :. l :tO-147  : 3.282E+05  : l :W-187  : 9.102E+04  :

NP-239  : 6.401E+04  :

1 - mrem /yr per pC1/m 3 1 l l l 1 l i l 2-13

TABLE 2.3 () P47" war DCSE 74C'CR (R) INF4NT 4'OM INHAL G /.C COW /.MILF COWiMEAT l VE6 s /M IC< H3 6.468E+02 0.000E*00 2.392E+03 0.000E*00 'O.000E+00 4.860E-03 Ci4 2.646E-04 0.000E-00

  • 579E+09 0.000E-00 0.000E+00 i.579E+09 P32 2.030E+06 0.000E+00 8.053E+10 0.000E*00 0.000E*00 9.663E+10 CR5: 1.284E+04 5.St7E+06 2.439E+06 0.000E*00 0.000E+00 2.927E-05 MN54 9.996E+05 1.629E+09 2.522E+07 0.000E+00 0.000E+00 3.027E+0E TE55 S.694E+0a 0.000E+00 8.975E+07 0.000E-00 0.000E+00  : . 67E+06 FE59 1.015E+06 3.238Ev08 2.137E+08 0.000E+00 0.000E+00 2.778E*06 C058 7.77'0E+05 4.4.90E+08 3.475E+07 0.000E+00 '0.000E+00 4.i?0E+06 C060 4.508E+06 2.528E+10 1.404E+08 0.000E*00 0.000E+00 1.685E+07 NI63 3.388E+05 2.357E+'0

(]) 0.000E+00 0.000E+00 0.000E+00 2.828E+09 ZN65 6.538E+05 8.574E+08 1.210E+10 0.000E+00 0.000E+00 1.452E+09 1886 1.'304E+05  !.029E+07 f.l28E+t0 0.000E+00 0.000E+00 i.353E+09 SR89 2.030E+06 2.523E+04 6.945E*09 0.000E*00 0.000E+00 1.459E+10 SR90 4.088E+07 0.000E+00 8.;95E+10 0.000E+00 0.000E+00 i.72iE+11 Y91 2.450E+06 1.217E+06 2.950E+06 0.000E+00- 0.000E+00 3.540E+05 ZR95 1.750E+06 2.915E+08 4.713E+05 0.000E-00 0.000E+00 5.656E+04

NB95 4.788E+05 1.614E+08 1.094E+08 0.000E+00 0.000E+00 1.313E-07 TC99M 2.030E+03 2.10!E+05 8.037E+03 0.000E+00 0.000E+00 9.644E+02 RU103 5.516E+05 1.226E+08 5.682E+04 0.000E+00 0.000E+00 6.819E-03 .

rut 06 i.:56E+07 5.063Et08 9.359E+05 0.000E-00 0.000E+00 1.i23E-05 ! AG110M 3.668E+06 4.062E+09 9.306E+09 0.000E+00 0.000E+00 1.ti7E+09 TE:25M 4.466E+05 2.133E+06 9.408E+07 0.000E+00 0.000E+00  !.00SE-07 () TE127M 1.312E+06 1.083E+03 6.206E+08 0.000E+00 0.000E+00 7.447E-07 2-14, _ ____ _ . _ _

l l TABLE 2.3 (cont) (]) SAThWAY DOSE FACTOR (R) INFANT 4 TOM INHAL G/P COW / MILK COW / MEAT VEG GT/ MILK TE129M 1.680E+06 2.348E+b7 7.396E+08 0.000E+00 0.000E-00 8.876E+07 Ii3:  :.484E+07 2.095E+07 5.278E+11 0.000E*00 0.000E+00 6.334E+'t CS134 7.028E+05 7.972E+09 4.495E+10 0.000E+00 0.000E+00 1.349E+11 CS136  !.345E+05 1.690E+08 2.892E+09 0.000E+00 0.000E+00 3.677E+09 CS137 6.118E+05 1.203E+10 4.060E+10 0.000E+00 0.000E+00 1.218E+11 SAr40  :.596E+06 2.35iE+07 r.2l0E+08 0.000E+00 0.000E+00 1.452E+07 CE141 5.166E+05 1.539E+07 7.181E+06 0.000E+00 0.000E+00 8.617E+05 CE!44 9.842E+06 8.046E+07 8.547E+07 0.000E+00 0.000E+00 1.026E+07 PR143 4.326E+05 0.000E+00 3.935E+05 0.000E+00 0.000E+00 4.722E+04 NDl47 3.220E+05 f.015E+07 2.887E+05 0.000Et00 0.000E+00 3.464E+04 NP239 5.950E+04 ' 978E+06

                              .          4.708E+04    0.000E+00     0.000E+00  5.649E+03 c

l O 2-u - - . -- -

TABLE 2.4 ('T

   %)

247hWAY DOSE CACTCR (R) CHILD 470M INHAL G/P CGW/MILX COW /!iEAT VEG G7/ MILK H3 i.125E+03 0.000E+00 1.570E*03 2.341E-02 4.008E*03 3.203E+03 Cia 3.589E+04 0.000E-00 8.064E+08 2.588E+08 S.894E+08 9.064E+08 P32 2.605E+06 0.000E+00 3.908E+10 3.730E+09 3.375E+09 4.690E*10 CR5: i.702E+04 5.5!7E+06 2.80tF+06 2.42iE+05 6.232E*06 3.36?E+05 MN54  :.576E+06 1.629E+0S 1.349E+07 5.155E+06 6.651E+08 1.G19E+06

                 .E55    :.!!0E+05           0.000E+00         7.426E+07              3.037E+08     8.012E+08         9.653E+05 FE59    1.269E+06           3.238E+08         1.104E+08              3.466E+08     6.766E+08          1.436E+06 C058    :.*10E+06           4.490E+08         4.063E+07              5.512E+07     3.786E+08         4.875E+06 C060   7.067E+06            2.528E+10         1.601E+08              2.569E+08     2.095E+09          1.921E+07 NI63  8.214E+05            0.000E+00          2.000E+10              !.965E+10     3.949E+10         2.400E+09
  . ('           ZN65  9.953E+05            8.574E+08          6.998E+09              6.355E+08    2.164E+09          8.398E+06 RB86    1.983E+05            f.029E+07         4.445E+09              2.92SE+08   -4.53SE+08          5.334E+08 SR89   2.157E+06            2.523E+04          3.653E+09              2.361E+08    }. 611 E+ 10       7.670E+09.

SR90 ' 010E+08

                          .                 0.000E+00          7.530E+10              7.008E+09     i.243E+f2         !.58:E*lt Y91    2.627E+06            1.217E+06         2.921E+06               1.351E+06    2.501E+09          3.505E+05 ZR95   2.23fE+06            2.915E-08         5.015E+05               3.504E'08    9.025E+08          6.018E+04 NB95   6.142E+05            1.614E+08          1.214E+08              1.184E+09    2.969E+08          1.457E+07 7C99M  a.810E+03            2.101E+05         7.!98E+03             2.816E-18      5.185E+03          9.637E+02 i

l RU103 6.623E+05 1.226E+08 5.966E+04 2.168E+09 4.031E-08 7.160E+03 l Ur06 f.432E+07 5.063E+08 9.308E+05 4.471E+10 1.iSOE+;0 f.!!7E+05 AG110M 5.476E+06 4.062E+09 1.069E+10 4.298E+08 2.587E+09 1.283E+09 TEt25M 4.773E+05 2.133E+06 4.132E+07 3.188E+08 3.512E+08 4.958E+06 TE127M 1.480E+06 1.083E+05 3.551E+08 3.030E+09 3.769E'09 I () 4.262E+07 4 2-16

TMILE 2.4 (cont)

ATbWAY DOSE FACTOR (R)

CHILD ATOM INHAL G/P CCW/ MILK CGW/ MEA 7 VEG G7/ MIL.< TE129M- 1.761E+06 2.348E+07 4.231E+08 2.807E+09 2.521E+09 5.077E+07 I!31  !.624Ev07 2.095E+07 2.l?2E+1! 2.771E+09 4.770E+10 2.606E-1? CSi3c 1.014E+06 7.972E+09 2.456E+10 1.000E+09 2.631E+10 7.367E+10-CSi36  !.709E+05 f.690E+08 f.384E+09 2.193E+07 2.2!6E+08 4.152E+09 CS137 9.065E+05 1.203E+10 2.173E+10 8.989E+08 2.392E+10 6.519E+10 BA!40 1.743E+06 2.351E+07 5.380E+07 2.205E+07 2.777E+08 7.056E+06 CE14' 5.439E-05 1.539E+07 7.152E+06 7.258E+06 4.078E+08 8.582E+05 CE144 1.195E-07 8.046E+07 8.497E+07 1.2!2Ev08 f.039E+10 1.020Ev07 PR143 4.329E+05 0.000E+00 3.889E+05 1.810E+07 1.574E+08 4.667E+04 NDt47 3.282E+05 1.015E+07 2.871E+05 7.614E+06 9.287E+07 3.445E+04 () NP239 6.401E+04 1.978E+06 4.577E+04 1.12SE+03 1.358E+07 5.492E+03 l O 2-17

TABLE 2.5

                                       ?ATHWAY DOSE CAC70R        fR)

O TEENAGER ATOM INHAL G/P COA' / MIL.< COW / MEAT VEG G7/ MILK H3 ' 272E+03 0.000E+00 9.938E+02  :.938E-02 2.588E+03 2.027E-03 C!4 2.600E+04 0.000E+00 3.312E+08 f.390E+08 3.726E+08 3.3r2E+08 P32 1.888E+06 0.000E+00 1.585E+10 1.978E+0'9 1.611E+09 1.902E+10-CR51 2.096E+04 5.5:7E+06 a.352E+06 4.919E+05 1.040E+07 5.222E+05 MN54 1.984E+06 1.629E+09 1.850E+07 9.243E+06 9.324E+08 2.220E+06

          #E55          1.240E+05  0.000E+00   2.959E-07      1.582E*08   3.259E+08   3.846E+05 FE59         1.528E+06   3.238E+08   1.560E+08      6.405E+08   1.000E+09   2.028E+06 C058          f.344E+06  4.490E+08   6.285E+07      1.115E+08   6.057E+08   7.542E+06 C060         8.800E+06   2.528E+10   2.424E+08      5.087E+08   3.237E+09   2.909E+07
          'iI63        5.800E+0S   0.000E+00   7.975E+09      !.025E+!0   1.606E+10   9.570E+08
  -( )    ZN65         1.240E+06   8.574E+08   4.648E+09      5.520E+08   1.471E+09  5.578E+08 RB86          !.304E+05   1.029E+07   2.396E+09     2.063E+08   2.747E+08   2.876E+08 SR89         2.416E+06   2.523E+04    1.476E+09      1.406E+08   1.521E+10  3.099E+09 SR90          !.080E+08  0.000E+00    4.456E+10     5.425E+09   7.507E+11   9.358E+10-Y91          2.936E+06   1.217E+06   3.637E+06      2.200E+08   3.233E+09   4.365E+05 ZR95         2.688E+06   2.915E+08   6.856E+05      6.265E+08    1'.278E+09 8.227E+04 NB95         7.512E+05   1.614E+08    1.771E+08     2.260E+09   4.581E+08   2.125E+07 7C99M        6.128E+03   2.101E+05   5.150E+03      2.636E-18   4.344E+03   6.180E-02 l         RU103        7.832E+05   1.226E+08   8.150E+04      3.874E+09   5.788E+08- 9.780E+03 RU106        f.608E+07   5.063E+08   1.!65E+06      7.322E+10   :.c84E-10   1.399E+05 AG110M       6.752E+06   4.062E+09   1.631E+10      8.576E+08   4.039E+09   1.957E+09 TE!25M       5.360E+05   2.133E+06   4.964E+07      5.010E+08   4.383E+08   5.957E+06 TE127M       1.656E+06   1.083E+05   2.048E+08      2.285E+09   2.236E+09   2.457E+07

() 2-18

TMILE 2.5 (cont) PATHWAY DOSE ACTOR (R) O TEENAGER ATOM INHAL G/P COW / MIL.< CUW/ MEAT VEG GT/ MILK TE129M 1.976E+06 2.348E+07 2.446E+08 2.123E-09 1.544E*09 2.935E+07 Il3! I'464E+07

               .        2.095E+07                  1.100E+11    :.835E+09     3.: 49E+!0  f.320E+1' CS134  1.128E+06    7.972E+09                  1.527E+10   8.134E+08      1.670E+10  4.581E+10 CS136  f.936E+05    1.690E+08                 8.778E+08       .319E*07     f.688E+08 2.633E+09 CSi37  8.480E+05    1.203E+10                 1.200E+10    6.493E*08      1.348E+10  3.600E-10 BA140  2.032E+06    2.35fE+07                 3.756E-07       .843E+07    2.137E+08  4.508E+06 CE141  6.136E+05    1.539E+07                 8.914E+06    1.183E+07      5.399E+08  1.070E+06 CE144  f.336E+07    8.046E+07                 1.060E+08    1.979E+08      1.326E+10  1.272E+07 PR143  4.832E+05    0.000E+00                4.792E+05     2.917E+07      2.308E+08  5.751E+04 NDl47  3.720E+05    !.015E+07                3.577E+05     !.241E+07      f.436E+08  4.293E+04

() NP239 1.320E+05 1.978E+06 5.309E+0c 1.706E+03 2.100E+07 6.371E+03 f l t i l I 2-19

TABLE 2-6 24THWAY DOSE ACTOR (R) O ADULT ATON INHAL G/P COW / MIL < COW / NEAT VEG GT/ MILK H3 1.264E+03 0.000E+00 7.629E+02 3.248E-02 2.260E+03 . 556E+03 Cl4 f.816E+04 0.000E+00 f.778E+08  !.630E+08 2.276E+0S 1.778E+08 P32 1.320E+06 0.000E+00 8.588E+09 2.341E+09 1.406E+09 1.031E+10 CR51 f.440E+04 5.5i7E+06 3.729E+06 9.205E+05 1.17 E+07 4.475E-05 MN54 1.400E+06 1.629E+09 1.659E+07 1.810E+07 9.589E+08 1.990E+06 ESS 7.208E+04 0.00CE+00 1.668E+07 f.948E-08 2.096E+08 2.!69E+05 FE59 1.016E+06 3.238E+08 1.269E+08 1.137E+09 9.969E+08 1.649E+06 C058 9.280E+05 4.490E+00 5.489E+07 2.!27E+08 6.274E+08 6.586E+06 C060 5.968E+06 2.528E+10 2.063E+08 9.456E+08 3.139E+09 2.476E+07 NI63 4.320E+05 0.000E+00 4.540E+09 1.274E+10 1.040E+f0 5.448E+08 () ZN65 8.640E+05 8.574E+08 2.774E+09 7.193E+08 1.009E+09 3.329E+08 RS86  !.352E+05 1.029E*07  !.315E+09 2.472E+08 2.201E+08 1.578E+08 SR8S 1.400E+06 2.523E+04 8.006E+08 1.666E+08 1.001E+10 1.681E+09 SR90 9.920E+07 0.000E+00 3.154E+10 8.384E+09 6.046E+11 6.624E+10 Y91 1.704E+06 1.217E+06 2.655E+06 3.506E+08 2.831E+09 3.1S6E+05 IR95 f.768E+06 2.915E+08 5.473E+05 1.092E+09 f.216E+09 6.567E+04 NB95 5.048E+05 1.614E+08 1.478E+08 4.119E+09 4.826E+08 '..774E+07 TC99N 4.!60E+03 2.!0iE+05 2.7:lE+03 3.030E-18 5.1i7E+03 3.253E+02 RU103 5.048E+05 1.226E+08 6.406E+04 6.649E+09 5.649E+08 7.687E+03 Rut 06 9.360E+06 5.063E+08 8.552E+05 i.173E+!! 1.248E+10 1.026E+05 4G110M 4.632E+06 4.062E+09 1.401E+10 1.608E+09 3.987E+09 1.681E+09 7Ei25M 3.!36E+05 2.133E+06 3.711E'07 8.179E+08 3.934E+08 4.453E+06 TE127M 9.600E+05 1.083E+05 1.113E+08 2.713E+09 1.418E+09 1.336E+07 O 2-20

TMBIZ 2.6 (cont)

                             "AThWAY DOSE .CACTOR (R)

[]} ADULT ATOM INHAL G/P. COW / MILK CON / MEA 7 VEG GT/ MILK TE129M 1.160E+06 2.348E+07 1.609E+08 3.049E+09 1.288E+09 . 931E+07 Ii31  !.!92E+07 2.095E+07 6.956E*IO 2.534E-09 3.795E+10 8.347E+l0 CS134 8.480E+05 7.972E+09 8.891E+09 1.034E+09 1.110E-10 2.667E+10 CSi36  !.464E+05 1.690E+08 5.172E+08 2.341E+07  !.660E+08  !.552E+09 CS137 6.208E+05 1.203E+10 6.804E+09 8.039E+08 8.696E+09 2.041E+10 BAf40  !.272E+06 2.35tE+07 2.778E+07 2.976E+07 2.652E+08 3.334E+06 CE141 3.616E+05 1.539E+07 6.582E+06 1.908E+07 5.094E+08 7.899E+05 CE!44 7.776E+06 8.046E+07 7.747E+07 3.157E+08 1.112E*IO 9.297E+06 ' PR143 2.808E+05 0.000E+00 3.473E+05 4.615E+07 2.747E+08 4.167E+04 ND147 2.208E+05 1.015E+07 2.629E+05 1.991E+07 f.865E+08 3.!55E+0'4 ' NP239 1.192E+05 1.978E+06 3.698E+04 2.596E+03 2.876E+07 ~4.438E+03 l f l l i l C) i l l k-- 2-21

O O O FIGURE 2.1 GASEO

                               ,______US   _____ WASTE _P_ROCESSIN_G_S_YS_T__EM
                                                                                                                                 ,_________,1
              .trd                                                               Shut Down       Shut Down                  Volume                    I home ,                                                                          Start-Up        Start-Up                   Control                   l Tank            Tank                       Tank Reactor Codant           hie                                                                                                                         l Drain Tanks I a 2
  • Gas > Catdylic Recombi.ner i 4
                                                                                            - -- p 4_                                                 l Compresser            Fbckage               l 9                        T - - -Q-- -             T - - -Q        j Evaporators                  g                                       i          % ste        hie          % ste                                      l
                                                                                                                      % ste         %ste     %ste     g Process Samplers             l Demy         Demy         Decay      Decay         Decay    Decay l                                                  Tank         Tank                                                    l Tank       Tank          Tank     Tank
                              !                                                      I i

I I I l 1 l L _ _ _ _. _ _ _ _ _ _ 4 _ _ _ _ __ _ _ __ _I_ _ _ _ L _._ _ _ _t _ _____ _I _ ___ _ _ L_ _ _ _ J l l p______________________________J l w I I General Atomic b l l Radiation Monitors I l I Main Flow Fhth I L l ---- Alternate Flow Fbth g I y } TRAIN A Auxiliary Building Fuel Handling Building kf E g$ > h Filter HEPA kh g ilter HEPA  % m 4 Nk> Safeguards Unit 1 - m $ Q U 3 6 Containment Purge Unit I > TRAIN B Safeguards Unit 2 h Cmtoinment Purge Unit 2 > {

                                                                -*
  • k, HEPA HEPA --->

MI

Table 2.7 i

                                                            ' ATMOSPHERIC DISPERSION PARAMETERS
  • FOR TECHNICAL SPECIFICATION 4.11.2.4.1 Sector Miles X/Q D/Q N- 4.2 2.7E-07 1.2E-09 NNE 3.9 1.9E-07 7.5E-10 NE 3.4 1.7E-07 5.0E-10 ENE 2.6 2.1E-07 5.5E-10 E 3.4 1.6E-07 2.9E-10 i
                                                                                                                              ~

I ESE 3.8 1.4E-07 2.7E-10 SE 2.8 3.7E-07 1.2E-09 SSE 2.9 2.8E-07 1.3E-09 S 4.2 1.2E-07 4.6E-10 SSW 4.4 9.0E-08 2.6E-10 SW 1.5 6.4E-07 '2.5E-09 WSW 1.7 5.2E-07 1.6E-09 l' W 1.6 7.8E-07 -2.5E-09 WNW 1.9 8.2E-07 2.8E-09 NW 5.0 2.4E-07 5.6E-10 l NNW 4.9 2.6E-07 8.0E-10 l. l co 1 t 2-23 I

        .._.._.._ ,~.._. _ ..   . . _ , . _ _ . . _ . . _.            - _ _ _ , _ . , . . . _ . _ , , _ _ , _ _ _ , , . . . ,                ,. . ____..         , _ _ . _ _
                                                  . TABLE 2.8 CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS (For Dose Calculations required by Technical Specifications 3.11.2.3, 3.11.2.4 and 6.9.1.13)

DISTANCE SECTOR (MILES) PATHWAY AGE GROUP N 4.2 Goat / Milk Infant NNE 3.9 Cow / Milk Infant NE 3.4 Cow / Milk Infant ENE 2.6 Vegetation Child E 3.4 Goat / Milk Infant ESE 3.8 Cow / Milk Infant SE 2.8 Vegetation Child

  • SSE 2.9 Cow / Milk Infant S 4.2 Goat / Milk Infant

{} SSW 4.4 Cow / Milk Infant SW 1.5 Cow / Milk Infant WSW 1.7 Vegetation Child W 1.6 Cow / Milk Infant WNW 1.9 Cow / Milk Infant NW* 5.0 Cow / Milk Infant NNW 4.9 Goat / Milk Infant

           *No pathway currently exists in this sector.                  Cow / Milk pathway to infant l              is assumed at distance of 5 miles.

l l t O ) 2-24

2.3 METEOROLOGICAL MODEL Atmospheric dispersion for releases are calculated using a straight line flow - Gaussian model. X/Q = average atmospheric dispersion (sec/m ) for a given wind direction (sector) and distance.

            = 2.032 6 k j ,k ( Nr u         )

jk tj 2.03 = (2/v )l/2 divided by the width in radians of a 22.5 sector (0.3927 radians). n = number of hours meteorological conditions are observed to be in a given wind direction, windspeed class k, and atmospheric stability class j which establishes a joint. frequency distribution of grouped meteorological data. NOTE: If periodic data (hourly) are used instead of the joint frequency data, all variable subscripts are dropped, the n is set equal to 1 and the hourly averaged meteorological variables are entered into the model. N = total hours of valid meteorological data throughout the period of effluent release. r = distance from the release point to location of interest (meters) u k = wind speed (midpoint of windspeed class k) measured at the 10 meter l level (m/sec) during atmospheric stability class j l I l 2-25 1 __ .

J. E)

                    = building wake corrected vertical standard deviation of the plume con-centration.

2 ( o) 2 + b /2 n)l/2

                    = the lesser of         or

( f7 o ) where: j = vertical standard deviation of the plume concentration (meters) at distance r for releases (Fig. 2.3)

                    = terrain recirculation factor (Fig. 2.5) 6        = plume depletion factor (radiciodines and particulates) at distance r for the applicable stability class.          Normally a factor of 1 is assumed when undepleted X/Q values are to be used in dose calculations. (Fig. 2.2)

T = 3.1416

b = vertical height of reactor containment structure (79.4 meters).

AT. = vertical temperature gradient ( C/100M). t Relative deposition per unit area is calculated.

                                                                  ~

D/Q = relative deposition per unit area (m ), for a given wind direction and at a given distance, r

                    = 2.55K D

( r g [ D = relative deposition rate for a ground-level release determined from 8 Figure 2.4.

                                                    -1 I           2.55     = (radians per 22.5 Sector) l O

2-26

FIGURE 2,2 c Plume Depletion Effect for Ground-LevelReleases a

                                              . (All Atmospheric S" ability Classes)                                                                                                                                                                                                                                                       a i                                                                                                                                                          O
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_._....a r o. I- - 3 o

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b. -'t. -i-- _ -?' r - x[M.rlh _= -- 1:=.-W.*/c ----l- '. _ . . ? ;,~'i- _j :: .:i: -M --a :y nY-N -- r . ___ .1-p-- fl.p-yQ
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                                ..-b.-                                     ..
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_ .= n : - - - ^ - - - - - - - - - _=_ m - - - --;-- $. t_;.. . . .

                              =---===.==-__-p-----/

r _;- : r t .- g r e M-*.g._ ._E:=: yg. y  :- ___ - --- g._._ .

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                       .= 5e. = -r=- q m= 3 =esgu.=- . :m_-                                                                                               ;        . _.-;=w==m-mews ame                                                                                         __
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W:=.b=-_g.--/.__. c _ . . . . . - . W y

t. .
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                                                                                                                                                                                                                                                                                                 - * -- ~-k= =j .i
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i t . _ . _ i O r- N o cn m e m M 9

                        &                         6                           6                    6                         6                   6                    6                          6                   6                     0 3Wfrid NI ONINIVW38 NOLLOVHd o

2-27

FIGURE 2.3 g;

 \

Vertical Standard Deviation of N'aterial in a Plume (Letters denote Pasquill Stability Class) 1000 . _ _ _ . . . . . . . .-...._._., , .._ ..._e ._-...__..__.__.f..m. .. ., __.....y. ._._..._.,...__,_g- f r_ f ,_m __ p. .. _ .4

                   ...____..._p..                                     ._.t._.,..,                         ,      , .,_ _ f_

f _ , .g- __ _ s.. . ;.,_,,

               ... _ . _ , _. _ :. _. . . ; . [ . . l . .) ._ ; i ; t_f                                                                           l          ,f                                                                       j' ; ; _ p._ ; 9_;_;
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c. . y : ,. v =l==_a = =,t _t-3/-
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l b O.1 1.0 10 10( PLUME TRAVEL DISTANCE (KILOMETERS) a I 2-28

FIGURE 2.4 Relative Deposition for Ground-Level Releases O (All Atmospheric Stability Classes)

                                               -===                                     _-       - - . .                  --                                 ..-,_                        -

_.m .__ _ - 10-4 N 'L

                                                                                                                        '                                              -  -                        i X
                                                                            ---                          m                                                                                  _ -

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              =
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_ _ _ .___ -_. __. _ _ _ .... , _ _ _ - - _1.- _ l l f3 V 10 ~ o.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) 2-29

O O O 10 i i _ _  : O v (D 4 3 d N a a N' - . B ta N 5' ., I \ I 5 y 2 o 1.0

                                 ' ~
                                     ~                         (D  E a                                                               O   m o F g-  p 8                                                             O   m g                                              _     __

C_ g _ __ . g o 3 m O O 0.1 0.1 1.0 10 100 DISTANCE (K.lLOMETERS)

2.4 DEFINITIONS OF GASEOUS EFFLUENTS PARAMETERS S1ction of Term Definition Initial Use () B = administrative allocation factor for gaseous 2.1.1 effluent pathways

      'b             = maximum height of the adjacent building.                                                  2.3.1 C             = monitor reading of a gaseous effluent monitor corre-                                      2.1.1 sponding to associated sample radionuclide concentrations.

D = average organ duse rate in the current year (mrem /yr) 2.2.1.b D = de a to an individual from radioiodines and radio- 2.2.2.b P nuclides in particulate form with half-lives greater than eight days (mrem). D, = calculated skin dose rate (mrem /yr) 2.2.1.a

                     = limiting dose rate to the skin                                                            2.1.1 D,,
                     = 3000 mrem /yr
     D             = calculated total body dose rate (mrem /yr)                                                2.2.1.a D             = limiting dose rate to the body                                                            2.1.1 TB
                     = 500 mrem /yr D             = air dose due to beta emissions from noble gas                                             2.2.2.a i

i D = air dose due to gamma emissions from noble gas 2.2.2.a i i D/Q = the sector averaged annual average relative deposition i for any distance in a given sector. i L i i V('h l 2-31 i l _ _ _ , , - _ _ _ - - - . . - - _ . . _ _ _ , _ - , . - . . _ _ , _ -

2.4 DEFINITIONS OF GASEOUS EFFLUENTS PARAMETERS (CONTINUED) Ssetion of Term Definition Initial Use D/Q' = annual average relative deposition at the location 2.2.2.b of the maximum exposed individual.

                           ~9           -2
              = 2.8 x 10              m      in the WNW sector 6          " P l ume depletion factor at distance r for the appro-                      2.3.1

, priate stability class (radioiodines and particulates). Kg = total body dose factor due to gamma emissions from 2.1.1 isotope 1 (mres/ year per microcurie /m ) Lg - skin dose factor due to beta emissions from isotope 2.1.1 1 (mrem /yr per microcurie /m ) Mg = air dose factor due to gansna emissions from isotope 2.1.1 1 (mrad /yr per microcurie /m ) N = air dose factor due to beta emissions from noble gas 2.2.2.a radionuclide 1 (mrad /yr per microcurie /m ) n k

              = number of hours meteorological conditions are                              2.3.1 observed to be in a given wind direction, wind-speed class k, and atmospheric stability class j.

N = total hours of valid meteorological data. 2.3.1 P g = dose parameter for radionuclide i, (mrem /yr per 2.2.1.b microcurie /m ) 2-32

_ _ - . . = . 2.4 DEFINITIONS OF GASEOUS EFFLUENTS PARAMETERS (CONTINUED) l Siction of Term Definition Initial Use Qg = rate of release of noble gas radionuclide i 2.1.1 (microcurie /sec) Q' g = rate of release of isotope i for radioiodine, 2.1.3 tritium, and radionuclides in particulate form. (microcurie /sec) i = cumulative release of noble gas radionuclide i over 2.2.2.a the period of interest (microcurie). Q' g = cumulative release of radionuclide i of iodine or 2.2.2.b material in particuJate form over the period of interest (microcurie). R = dose factor for radionuclide 1, (mrem /yr per microcurie /m ) 2.2.2.b-l 2 ! or (m -mrem /yr per microcurie /sec) O = monitor reading per mrem /yr to the skin. 2.1.1

R, R = monitor reading per mrem /yr to the total body. 2.1.1 r = distance from the point of release to the location 2.3.1 of interest for dispersion calculations (meters).

C 3

                   = monitor reading of the noble gas monitor at the alarm                2.1.1 setpoint for the release pathway under consideration.

r

                  = vertical standard deviation of the plume concentration with           2.3.1
          )

building wake correction.

     .O 2-33

2.4 DEFINITIONS OF GASEOUS EFFLUENTS PARAMETERS (CONTINUED) Section of Term Definition Initial Use

                            = vertical standard deviation of the plume concentration      2.3.1 a)

(in meters), at distance r_ for ground level releases under the stability category j indicated by AT AT = vertical temperature gradient (OC/100m). 2.3.1 K = terrain recirculation factor. 2.3.1 u = wind speed (midpoint of windspeed class k) at ground 2.3.1 level (m/sec) during atmospheric stability class J. 2.3.1 W' = relative dispersion for unrestricted areas at the 2.2.2.b controlling receptor. X/Q = the sector-averaged annual average relative concen- 2.3.1 tration at any distance r in a given sector. (sec/m ) 2.3.1 O X/Q = the highest annual average relative concentration in 2.1.1 any sector, at the site boundary. (sec/m )

                            =  3.3 x 10 -6 sec/m in the NNW sector X/Q'                   = relative concentration for the location occupied by         2.2.2.b the maximum exposed individual
                            = 8.2 x 10- sec/m in the WNW sector O

V 2-34

SECTION 3.O RADIOLOGICAL ENVIRONMENTAL MONITORING Sampling locations as required in Technical Specification 3/4.12.1 are described in Table 3.1 and shown on the map in Figure 3.1. NOTE: For the purpose of implementing Technical Specification 3.12.2, sampling locations will be modified as required to reflect the findings of the Land Use Census. O 1 9 < O 3-1

_. . - _ _ . .. _.._.m_ .- . - - - . __ . . _ _ . __ - _ _ _- Table 3.'1 1 Environmental Sampling Locations lO 4 Sampling Location Sample Point .(Sect.or - Miles) Type *

  ,                                              1                                                               E-0.5                                                           A 2                                                               N-2.2                                                          'A

]

 ;                                               3                                                              W-2.0                                                            A                                 i 4                                                                NNW-4.6                                                         A 5                                                               E-3.5                                                           A 6                                                                SE-3.85                                                         A 7                                                               SSE-4.5                                                         A 8                                                               N-9.4                                                            A 9                                                                SW-12.3                                                         A 10 N-1.2                                                            R' i

11 N-4.4 R 1

12 N-6.5 R-

[

13 N-9.4 R i

14 NNE-1.1 R 15 NNE-5.65 R 16 .NE-1.7 R l 17 NE-4.8 R 18 ENE-2.5 R 19 ENE-5.0 R 20 E-0.5 R 1. l l l O j 3-2

Tchle-3.1 (Continued) Environmental Sampling Locations O Sampling Location Sample Point (Sector - Miles) Type

  • 21 E-1.9 R 22 E-3.5 R 23 E-4.2 R 24 ESE-1.4 R-j 25 ESE-4.7 R 26 SE-1.3 R 27 SE-3.85 R 28 SE-4.6 R 29 SSE-1,3 R 30 SSE-4.4 R 31 SSE-4.5 R i 32 S-1.5 R
        '33                      S-4.2                                       R 34                      SSW-1.0                                     R l

l 35 SSW-4.4 R 36 SW-0.9 R 37 SW-4.8 R 38 SW-12.3 R 39 WSW-1.0 R 40 WSW-5.35 R l' I l t 3-3

                                            ' Tcblo 3.1                       (Contir.u:d)

Environmental Sampling Locations O Sampling Location Sample Point (Sector - Miles) Type

  • 41 WSW-7.0 R 42 W-1.0 R 43 W-2.0 -R 44 W-5.5 R 45 WNW-1.0 R 46 WNW-5.0 R 47 WNW-6.7 'R 48 NW-1.0 R 49 NW-5.7 R 50 NW-9.9 -R 51 NNW-1.35 R 52 NNW-4.6 R 53 ESE-0.5 SW 54 ESE-2.2 SW 55 N-9.9 SW 56 E-0.5 GW 57 SSE-4.5 GW 58 NNE-1.0 SS 59 N-9.9 SS 60 ** M l

i O

- 3-4 4

4

   --,e      - . , . - , .-.,----e     e, - --n...,,,-,r      - - - . . . , , , - - -

r.,,,- -:--,- - -- - -v - ,,,-gr--c, , , - . . - , ,, .-

0 Tchle 3.1 (Ccntinu:d) Environmental Sampling Locations O Sampling Location Sample Point (Sector - Miles) , Type

  • i 61 ** M 62 ** M 63 SW-13.5 g 64 ENE-2.0 F 65 NNE-8.0 F 4

66 E-4.2 y 67 SW-13.5 y 68 W-1.8 y I 69 SE-1.3 V 70 SSE-1.3 V 71 SW-13.5 V

  • Types: A - Air Sample, R - Direct Radiation, SW -- Surface Water, GW - Ground Water, SS - Shoreline Sediment, M - Milk, F - Fish; V - Vegetation.
       **As determined from yearly milk animal census.
O 3-5

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! $ cess *I , \ p- , _ Sources Comossee from Temas reignway Geot. l Figure 3.1 (cont.) -a.a.r wi.n .,u.o..os7si-Comanche Peak S.E.S. m== m- s-- x Radioloyced Environmemmi Monitoring Pmer" 3-7 Sample Locations Greater than 10 Miles from the Site

APPENDIX A Calculation of P (Inhalation) Pg = k' (BR) DFA f where P = the dose parameter for radionuclides other than noble gases for the f inhalation pathway, in mrem /yr per microcurie /m . The dose factors

are based on the critical individual organ for the child age group, 6

k' = conversion factor, 10 pCi/ microcurie BR = 3700 m /yr, breathing rate' for child, Ref. 3 DFA g = the maximum organ inhalation dose factor for the child age group Resolution of the units yields: P (Inhalation) = 3.7 x 10 DFA The latest NRC guidance has deleted the requirement to determine P (ground plane) and P (food). In addition, the critical age group has been changed from infant to child. 4 I I O A-1

                                                                                    .r - - - , - - - -   a r -

APPENDIX B InhalationPathwayFactor,Rf(X/Q) O Rf(X/Q) = k' (BR) (DFAg ) (mrem /yr per microcurie /m ) where 0 k' = cottversion factor,10 pC1/ microcurie BR = breathing rate,- 1400, 3700, 8000, 8000 m /yr for infant, child, teenager, and adult respectively DFA g = the maximum organ inhalation dose factor for the receptor of given age group for the ith radionuclide, in mrem /pci. The total body is considered as an organ in the selection of (DFA ). g O b l B-1 I i i.

APPENDIX C Ground Plane Pathway Factor, R (D/Q)

   ~

R (D/Q) = k' k" (SF) DFG ((1-e - ) /A ) where k' = conversion factor, 10 pC*/ microcurie k" = conversion factor, 8760 hr/yr

                                                                                                              ~

l A = radionuclide decay constant, sec t = the decay time, assuming that decay is the only operating removal 0 mechanism, 4.73 x 10 sec. DFG = the ground plane dose conversion factor for the ith radionuclide (mrem /hr per pCi/m ).

                                                                                                                                                +

SF = .7, shielding factor, from Table EIS Reg. Guide 1.109 O i I O C-1

APPENDIX D Grass-Cow-Milk Pathway Fcetor, R" (D/Q) R" (D/Q) = k' (Q p xUg) / (A +A ) x Fai x r x DFL x ((fp x fs)/ Yp + ((1-fp x fs) e I *h) Ys)) e- f where 6 k' = conversion factor, 10 pCi/ microcurie Qp = cow consumption rate, 50 kg/ day, R.G.l.109 U AP

          " receptor's milk consumption rate; 330,330,400,310 for infant, child, teenager, and adult resp. R.G. 1.109 Yp      = agricultural productivity by unit area of pasture feed grass,
             .7 kg/m , NUREG 133 Ys      = agricultural productivity by unit area of stored feed, 2.0 kg/m , NUREG 133 Fm      = stable element transfer coefficient, Table El R.G. 1.109 r       = fraction of deposited activ'.ty retained on cow's feed grass, .2 for particulates, 1.0 for radiciodine.

DFL = the maxf2num organ ingestion dose factor for the ith radionuclide for each respective age group tables E-11 to E-14 R. G. 1.109

          =   decay constant l      f l
          = decay constant for weathering, 5.73 x 10-                -1 see     , NUREG 133 5

t g = 1.73 x 10 sec, the transport time from pasture to cow, to milk to receptor, in seconds 6 t = 7.78 x 10 sec, the transport time from pasture, to harvest, to cow h l to milk, to receptor l l fp = 1.0, the fraction of the year that the cow is on pasture. Land Census l l Report 1982

D-1

? . ._.- .__ - .,

APPENDIX D (CONTINUED) fs = .5, the fracticn of the cow feed that is stored feed while the O cow is on pasture. Land Census 1982 The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore R"g (X/Q) becomes: R" (X/Q) = k'k FM Qp U p DFL (.75 (.5/H)) f where 3 k = 10 grams /kg H = 8 grams /m , absolute humidity of the atmosphere

   .75           = fraction of total feed grass mass that is water
   .5            = ratio of the specific activity of the feed grass water to the atmospheric water. -NUREG 133 I

i l l O D-2

APPENDIX E Vegetation Pathway Factor, R{ (D/Q) E R (D/Q) = k' x r/ (Yv (A g +A y)) x DFLg x U f e~i E 1. + U fge - 1h where k' = 106pci/ microcurie U = the consumption rate of fresh leafy vegetation, 0,26,42,64 for infant, child, teen, er adult respectively

                  = the consumption rate of stored vegetation, 0,520,630,520 for Uf infant, child, teen, or adult respectively f        = the fraction of the annual intake of fresh leafy vegetation grown locally, 1.0 NUREG 133 fg       = the fraction of the stored vegetation grown locally
                          .76 NUREG 133

,_O t t

                  - ca                    ti e det      *r             t er 1 17           E t cie    a it ce                     Pei .

8.6 x 10' seconds Table E-15 R.G. 1.109 t = the average time between harvest of stored vegetation and its h consumption, 5.18 x 10 6seconds Table E-15 R.G.1.109 Yv = 2.0 kg/m Table E-15 R.G.1.109 The concentration of tritium in vegetation is based on the airborne concen-tration rather than the deposition. Therefore,R{isbasedon(X/Q)

                  = k'k         UA f L+Uffg       (DFLi )          (.75 (.5/H))

R{ k = 103grams /kg H = 8 grams /m

         .75      = the fraction of total feed grass mass that is water
         .5       = the ratio of the specific activity of the feed grass water to the atmospheric water l

E-1 i - , . - -. _ _ . _ . . _. , _ _ _ _ . _ _ , __. _ . _ _ . . _ . . . . _ _ . .

Appendix F (-.s '~

   \

278  ! 'HIS PRCGRAM C0!*PUTES (R). PATHWAY DOSE FACTORS FOR ADULTS. TEENAGERS. C HILDREN. AND INFAfiTS > 379  ! TG USE THE PROGRAM, PRESS RUN AND THEN RESPOND TO THE QUESTIONS ASXED.  ? 480  ! 18 2  ! DEFINITION OF TERMS 483 ' 490 ' DFA-MAX ORGAN INHALATION DOSE FACTOR. TABLE E-6 THROUGH E-10 R.G. !. 109  ; 500  ! i 5!0  ! DFG-GROUND PLANE DOSE CONVERSION FACTOR. TABLE E-6 R.G. I.109 520  ! 530 ' DFL-MAX ORGAN INGESTION DOSE FACTOR. TABLE E-!! THROUGH E-14. R.G. 1.109 340 550  ! FM= STABLE ELEMENT TRANSFER COEFFICIENT MILK. TABLE Et R.G. 1.109 l 55;  ! 560  ! FF-STABLE ELEMENT TRANSFER' COEFFICIENT MEAT. TABLE El R.G. 1.109 57C  ! 580  ! <-CGNSTANT. 1.0E6, NUREG 133 590  ! E00  ! BR-BREATHING RATE. 1400, 3700. 8000 8000 FOR INFfNT. sHILD. TEEN. ADULT RESP. 610  ! 620  ! 4k-CONSTANT. 8760. NUREG 133 630  ! 540  ! SF-SHIELDING FACTOR. .7. TABLE EIS R.G. 1.109 650  !

  ' 560        ! LANDA-NUCLIDE DECAY CONSTANT s     570       ?

680  ! T-DECAY TIME, ASSUMING THAT DECAY IS THE ONLY REMOVAL MECHANISM, 4.73ES. NUREG 133 690  ! 700  ! 0F-COW'S CONSUMPTION RATE, 50. TABLE E3. R.G. 1.109 710  ! 720  ! R-FRACTION OF DEPOSITED ACTIVITY RETAINED ON COW'S FEED GRASS. 1.0 FOR I ODINE, .2 FOR 721  ! PARTICULATE. 740  ! 750  ! UAPi-RECEPT 0R'S MILK CONSUMPTION RATE. 330, 330. 400. 3f0 FOR INFANT. CHI LD, TEENAGER AND 760  ! ADULT RESPECTFULLY. 770  ! 780  ? Yp-AGRICULTURAL PRODUCTIVITY. .7. NUREG 133 790 t 900  ! Ys-AGRICULTURAL PRODUCTIVITY (STORED FEED). 2.0. NUREG 133. 910  ? 320  ! Tf-TRANSPORT TIME FROM PASTURE TO RECEPTOR. 1.73ES, NUREG 133. , 830  ! S40  ! Th-TRANSPORT TIME FROM PASTURE TO HARVEST TO RECEPTOR. 7.78E6.~NUREG 133

     $50      !

960  ! FP-FRACTION OF YEAR COW IS ON PASTURE. 1.0. LAND CENSUS. NOTE. THIS FAC TOR CAN POTENTIALLY 370  ! CHANGE ANNUALLY. 871

~T980 (V URE,      .5.

7S-FRACTION OF THE COW FEED THAT IS STORED FEED WHILE THE COW IS ON PAST: LAND CENSUS 390  ! FS CAN POTENTIALLY CHANGE ANNUALLY. TO UP-DATE THIS VALUE, SIMPLY CHANGE THE FS ASSIGNMENT G31  ! INSTRUCTION IN THE FIRST PART OF THE PROGRAM. ' 900  ! KKK-CONSTANT 1.0E3. NUREG 133 F-1 l

Appendix F-1 s 'O  ! (_) 20  ! H-1UNIDITY. 8. NUREG 133 c 30 - / 40 a 5.73E-7. NUREG 133 50  ! LAMDAW-DECAY CONSTANT FOR REMOVAL OF 60

                 ! UAP2-RECEPT 0R'S MEAT CONSUMPTION. O. a f . 65. !:0 ER. AND ADUL-                                                           FOR INFANi.v.11LD. EENA 70        ? RESPECTFULLY. NUREG 133 7;       !                                                                                              fj 80                                                                                                       <
                ! UAL-CONSUNPTION RATE OF FRESH LEAFY VEGETABLES 0, 26. 42, 64. FOR INFANT i CHILD. TEENAGER.

90  ?

                ! AND ADULT RESPECTFULLY. NUREG f33                                                            %

91  ! 000  ! UAS-CONSUMPTION RATE CF STORED VEGE7 ABLES 0, 520, 630. 520. NUREG 133 ft 010  ! FOR INFANT. CHILD. TEENAGER. AND ADULT. Ott  ! RESPECTIVELY 3 020 i

               ! FL-CRACTION FRESH VEGETABLES GROWN LOCALLY                                                  j 030     !

040 i

               ! FG-FRACTION STORED VEGETABLES GROWN LOCALLY                                                L, 050      !

060 ! TL-AVG. TIME BETWEEN HARVEST OF VEGETABLES AND CONSUMPTION, 8.6 E4 SEC.  ! NUREG 133 070  ! 080 SE6 SEC.! THH-AVERAGE NUREG 133 TIME BETWEEN HARVEST OF STORED VEGETABLES AND CONSUM 090 ! 100  ! (~)

's 110    K-1.0E+6 ! UNITS CONVERSION FACTOR 120 Kk-8760                                                                                         ,
                               ! UNITS CONVERSION FACTOR                                                  !

130 SF .7  ! SHIELDING FACTOR 140 { l50 T-4.73E+8 ! DECAY TIME FOR DECAY AS ONLY REMOVAL MECHANISM. Of 50 ? COW CONSUMPTION RATE

      !60    R=.2
                         ! FRACTION OF PRODUCTIVITY DEPOSITED ACTIVITY RETAINED ON THE COW'S FEED GRASS. p f'

170 Yp .7 ! AGRICULTURAL ISO i 190 Ys-2.0 ! AGRICULTURAL PRODUCTIVITY FOR STORED FEED. i Tf-1.73E+5 ! TRANSPORT TIME FROM PASTURE TO RECEPTOR. 200 Yv-2 ! 201 Tf f =1. 73E+6 210 Th=7.78E+6 220 Fp .67  ! TRANSPORT TIME FROM PASTURE 70 HARVEST TO RECEPTOR. 230 Fs-i.0  ! FRACTION OF THE YEAR COW IS ON PASTURE. RE.  ! FRACTION OF THE COW'S FEED THAT IS STORED FEED WHILE COW ON PAST 240 <k<-!.0E+3  ! UNITS CONVERSION FACTOR. 250 H-8  ! ABSOLUTE HUMIDITY-DEFAULT VALUE 4 260 Lancaw-5.73E-7 ! DECAY CONSTANT FOR WEATHERING. y V 270 F1-1 ! FRACTION OF FRESH VEG. GROWN LOCALLY [ 280 Fg .76  ! FRACTION OF STORED VEG. GROWN LOCALLY. 290 TI-8.6E+4 ! AVG. TIME BETWEEN HARVEST OF VEG. AND CONSUMPTION. f 300 301 Thh=5.18E+6 ! AVG. TIME BETWEEN HARVEST OF STORED VEG. AND CONSUMPTION

             ! BY ENTERING JF PATHWAY       DOSE             THE AGE GROUP OF CONCERN. THE COMPUTOR WILL GENERA              i 302    ? FACTORS (R).                                                                             1 310                                                                                               #

312 INPUT "PLEASE INDICATE INFANT. CHILD. TEENAGER. OR ADULT". Ages 4 (~T \_) 314 375 INPUT "PLEASE INDICATE PATHWAY DOSE FACTOP R OR P".As IF As<>"P" THEN 1394 lq 316 PRINT USING DRIN7 "" "28X.26A //.":" PATHWAY DOSE FACTOR (P)": Ages '

                                                                                                       ~

3f7 IMAGE GX.7A.5X.22A./ " 318 PRINT USING 1317:"NUCLIDE" " INHALATION DOSE FACTOR" F-2

Appendix F-2 * () 319 32? IMAGE 6X.6A.9X.D.3DE READ Atoms.Df al .Dra2.Df a3.Df a4.Df11.Df12.Dfl3.Df14.Dfg.Fn.Ff.Lamoa b 5 322 P'-K-1400-Dfaa 323 PRINT USING 1319:A oms.P1 324 PRINT " 326 IF Atoms <>"TEf25M" THEN 1321 327 IF Atoms ="NP239" THEN 1391 328 PRINT USING "s.s" 329 PRINT USING" "28X.26A././.":" PATHWAY DOSE FACTOR (P)": Ages 330 PRINT " 33; IMAGE SX.74.5X.22A./ 332 PRINT USING 1331:"NUCLIDE"." INHALATION DOSE FACTOR" 333 GOTC 1321 352 IF Atoms ="NP239" THEN !39 ! CHECK FOR END OF DATA. 353 READ Atoms.Df a1.Df a2.Df a3.Df a4,Df11.Df12.Df13.Df14.Df s.Fm.Ff.Lanca ! THIS TATEMENT READS THE 354 ! DATA ASSOCIATED WITH THE DATHWAY DOSE FACTOR (R) CALCULATIONS. 355 IF Ages <>" INFANT" THEN 1364 ! ASSIGNS AGE GROUP SPECIFIC DATA. 356 Dfa-Ofa4 357 Df!-Df14 358 Br-1400 359 Uap1-330 360 Vap2-0 361 Val-0 362 Uas-0 363 GOTO 1333 364 IF Ages <>" CHILD" THEN 1373 ! ASSIGNS AGE GROUP SPECIFIC DATA. (s) 365 366 Dfa-Dia3 Df1-Df13 367 Br=3700 368 Uapt-330 369 Uap2-41 370 dal-26 371 Uas-520 372 GOTO ?333 i 373 IF Ages <>" TEENAGER" THEN 1382 ! ASSIGNS AGE GROUP SPECIFIC DATA. 374 Dia-Dia2 375 Dft-Dfi2 376 Br=8000 377 Uapi-400 378 Uap2-65 379 dal-42 380 Uas=630 38t GOTO '333 382 IF Ages <>" ADULT" THEN l390 ! ASSIGNS AGE GROUP SPECIFIC DATA. 383 Dia-Dial 38 4 Dfl-Dill 185 Br-8000 l 386 Uapi-310 l 387 Uap2-110 388 Val-63 389 Uas=520 390 GOTO !333 i ' 391 GOTO 2370 1 392  ! THE FOLLOWING CODE PRINTS THE PAGE TITLE AND THE COLUMN HEADS. (- S

    /

393  ! 394 PRINT USING "28X.26A /./.":" PATHWAY DOSE FACTOR (R) ": Ages 395 IMAGE 6X.4A.4X.5A.6X.3A.8X.8A.3X.8A 6X.3A 6X.7A./ 396 PRINT USING 1395 :" ATOM" "INHAL"."G/P"." COW / MILK"." COW / MEAT"."VEG"."GT/ MILK F-3

Appendix F-3 (~'; 'v' 397FOR ES  ! THIS THATREAD NUCLIDESTATEMENT READS TWE NUCLIDE OF CONCERN PLUS THE DF4 A 393 3 AND  ! NOTE DFA4 AREDFAt THEIS THE DFA VALUE FOR AN ADULT. DFA2 IS THE VALUE COR A TE 399 ? VALUES FOR CHILDREN AND INFANTS RESPECTIVELY. 400 40i READ Atoms.Df a1.Dia2.Df a3.Df a4.Dfl1.Dr!2,Df!3.Df14. Dig Fm,Fi,Lamoa IF Ages <>" INFANT" THEN 1480 402 Dfa-Dfa4 ! ASSIGN INFANT RELATED VALUE5 410 Dfl-Df14 420 Br-1400 330 Uapt-330 440 Uac2-0 350 Val-0 460 Uas=0 46f IF As "P" THEN 1329 470 GOTO 1740 480 IF Ages <>" CHILD" THEN f570 490 Dfa-Dfa3 ! ASSIGN CHILD RELATED VALUES 500 Df1-Df13 510 Br-3700 520 Uapt-330 530 Vap2-41 540 Ual-26 550 Uas-520 551 IF As="P" THEN 1329 560 GOTO 1740 570 IF Ages <>" TEENAGER" THEN 1660 / 'i 580 Dfa-Dfa2 ! ASSIGN TEENAGER RELATED VALUES ~ (/ 590 Df!=Df!2 500 Br-8000 5!0 Uapi-400 520 Uap2-65 530 Ual-42 540 bas =630 54! IF As="P" THEN 1329 550 GOTO 1740 360 IF Ages <>" ADULT" THEN 1740 570 Dfa-Dial ! ASSIGN ADULT RELATED VALUES 580 Dfl-Dfl 590 Br=8000 700 Vapt-310 710 Uap2-110 720 Val-64 730 Uas-520 737 IF As="P" THEN 1329 740 750 IF Atoms IF Atoms "II31" THEN

                          ="I132"    R-?

THEN !SEE NUREG 133 P.34 FOR EXPLANATION. R-1 76 0 I. Atoms ="I130" THEN R-f 770 IF Atoms ="I133" THEN R-1 78 0 IF Atoms ="It34" THEN R-1

    '90     IF Atoms "I135" THEN R-1 79i
            ! THE FOLLOWING 1.0E-300      IS USED      CODE CALCULATES FOUR EXPONENTIAL VALUES. A DEFAULT VALUE
    '92 ! TO AVOID THE ERROR "REAL UNDERFLOW".

i"; '93 IF Lamda*Tff<700 THEN 1796 U '94 Exoo7-1.0E-300

    '95    GOTO 1800
    '96    Expo 7-EXP(-Landa*Tff) 10 0   IF Lamda-Th<700 THEN 1830 11 0   Expol-1.0E-300 F4

AppendLc Fw f) 820 GOTO '840 830 Expo!-EXP(-Lamca*Th) 840 IF Landa*Tf<700 THEN 1870  ;! 850 Expo 2-r.0E-300 860 GOTO 1880 870 Expo 2-EXP(-Lamaa*Tf) '! 880 IF LamcaaT1<700 THEN 1910 l

         $90    Expo 3-i.0E-300                                                                       >

900  ! GOTO 1920 ' 9r0 Expo 3-EXP(-Lamda-TI) , 920 IF Lamda-Thh<700 THEN 1950 {f 030 Expou-1.0E-300 940 GOTO 1960 950 Expo 4-EXP(-Lamda*Thh) 951

                 ! EXPOA IS A FACTOR UTILIZED IN THE CALCULATION OF THE COW / MIL.K AND COW /ME iT DOSE PATHWAYS.

960 Expoa-((Fp*Fs)/Yo+((!-Fp*Fs)*Expol)/Ys)* Expo 2 ' 961  ! EXPOB IS USED IN THE CALCULATION OF VEGETABLE DOSE PATHWAY. 970 Expoo-Ual*Fl* Expo 3+Uas*Fg* Expo 4 971 Expec=((Fp*Fs)/Yo+((1-Fp*Fs)*Expol)/Ys)* Expo 7 960 IF Atoms <>"H3" THEN 2030 ' 990 R3-K*Kk k -Fm*0f *Uap l *Df l*( f . 75* . 5 /H ) ) ! H3 COW / MILK PATHWAY

      '000     Ra-K*Kkk-Ff*0f*Uao2*Dfl*((.75*.5/H)) !H3 COW / NEAT PATHWAY OTO RS-K*Kkk*(Ual*Fl+Fg*Uas)*Dfl*((.75*.5/H)) !H3 VEGETABLE PATHWAY 020 R6-K*Kkka.17*Uap1*6*Df1*((.75*.5/H))                     !H3 GT/ MILK PATHWAY 030 RI-K*Br*Dfa ! INHALATION DOSE FACTOR 040    IF Landa*T<700 THEN 2070

(~) (/ 050 Expo 5-1.0E-300 ! DEFAULT VALUE TO AVOID "REAL UNDERFLOW" 060 GOTO 2080 070 Expo 5-EXP(-Landa*T) 080 R2=K-Kk*Sf*Dfg*((1-Expos)/Landa) ! GROUND PLANE DOSE FACTOR 090 IF Atoms ="H3" THEN 2340 !H3 VALUES WERE CALCULATED ABOVE 100 R3-K*( Of *Uap l ) / (Lamda+Lamdaw)*Fm*R*Df l*Expoa! COW / MILK P ATHWAY 110 R4-K*(Of aUap2)/(Lamda+Lamdaw)*Ff *R*Df1*Expoc! COW / MEAT PATHWAY iff !

       !20    R5=K*R/(Yva(Lamda+Lamdau))*0f1*Expoo 121 130     !THE FOLLOWING CODE ITEMS ASSIGN FM VALUES FOR THE GOAT / MILK CALCULATION IF    Atoms ="H3" THEN Fm .17                                                    ^

140 IF Atoms ="C14" THEN Fm .1 ISO IF Atoms "P32" THEN Fm .25 160 IF Atoms ="FE55" THEN Fm=1.3E-4 170 IF Atoms ="FE59" THEN Fm=t.3E-4 180 IF Atoms ="CU64" THEN Fm .013 190 IF Atoms ="SR89" THEN Fm .014 200 IF Atoms "SR90" THEN Fm=.014 210 IF Atoms "Ii30" THEN Fm .06 220 IF Atoms "I131" THEN Fm .06

     -230    IF Atoms "If32" THEN Fm .06 240    IF Atoms "I133" THEN Fm=.06 250    IF Atoms ="It34" THEN Fm=.06
260 IF Atoms "I135" THEN Fm .06 l 270 IF Atoms ="CS134" THEN Fm .3 280 IF Atoms "CS136" THEN Fm=.3 290 IF Atoms "CS137" THEN Fm .3

('s I 300 IF Atoms ="CS138" THEN Fm .3 () _ 310 Of=6 3ff  ! R6 CALCULATES THE GOAT / MILK PATHWAY. 320 R6-Ka( Of aUap1 k/(Lamda+Lamdaw)*Fm*R-Df1-Expoa l 330 Of-50 331 R .2 ! REASSIGN FOR NON-IODINE F-5

Appendbc F-5 () 340 350 IMAGE 6X.6A.2X.D 3DE.2X.D.3DE.2X.D.3DE.2X.3.3DE.3X.D.30E.2X.D.3DE./ 35: PRINT USING 2340:Atons.R1.R2.R3.R4.R5.R6 355 IF Aton3<>"TE127M" THEN 236f PRINT USING "4.r" 356 P9 INT USING "2SX.26A./ /.":" PATHWAY DOSE FACTOR (R)". Ages 357

  ,356 IMAGE EX.4A.4X.54.6X.3A 8X.8A.3X.8A.6X.3A.6X.7A./
         ?RINT USING 2357:" ATOM"."IMHAL" "G/P"." COW / MILK"."CGW/ MEAT" "VEG 361 IF.Atons<>"NP239" THEN !400 370    END F.

1 i I I O O F-6}}