ML20035A671

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Rev 0.K to ODCM, Chapter 10 & App F
ML20035A671
Person / Time
Site: Byron  
Issue date: 01/31/1993
From:
COMMONWEALTH EDISON CO.
To:
References
PROC-930131-05, NUDOCS 9303290144
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{{#Wiki_filter:l X244 Nisc C/D DOC CTRL USK, C. PATEL D IliE c 1Cf( Of NUC. RE AC10li RE GUL ATION U.S. h0C. REGULATORY CCMMISSION ItAIL STATION P1-137 February 24, 1993 bASHIh6 TON UC 20555 Attached are the recent revisions to the Offsite Dose Calculation Manual's (ODCM) Chapter 10 and Appendix F for Byron Station. Please complete the following manual update: l REMOVE INSERT Byron Station Annex Byron Station Annex Entire Chapter 10. Entire Chapter 10

p. 10-1 to 10-111, Revision 0.K, Jan. 1993 10-1 to 10-17
p. 10-1 to 10-v, 10-1 to 10-19 Byron Station Annex Byron Station Annex Entire Appendix F Entire Appendix F
p. F-1 to F-iv, Includes Rev. 0.K F-1 to F-24
p. F-i to F-iv, F-1 to F-24 Please sign and date this control sheet and return to:

COMMONWEALTH EDISON COMPANY c/o Document Control - Emergency Preparedness 1400 Opus Pl.- 5th Floor Downers Grove, IL 60515 (708)663-6547 Your signature indicates you have verified that your control number is correct and you have updated your manual. Signature 1 5 1 ff Date fdb 9303[9014k930131 ^ PDR ADOCK 05000454 P ppy gl ZEMERPLN/347/20

BYRON REVISION 0.K JANUARY 1993 '\\ ) BYRON ANNEX INDEX PAGE REVISION CHAPTER 10 10-1 0.K 10-ii 0.K 10-iii 0.K 10-iv 0.K 10-v 0.K 10-1 0.K 10-2 0.K 10-3 0.K 10-4 0.K 10-5 0.K 10-6 0.K 10-7 0.K 10-8 0.K 10-9 0.K 10-10 0.K s, / 10-11 0.K \\-/ 10-12 0.K 10-13 0.K 10-14 0.K 10-15 0.K 10-16 ).K 10-17 0.K 10-18 0.K 10-19 0.K I 1 e 1 .[ g (_ / 10-i e

BYRON -REVISION 0.K .j . JANUARY 1993

i O

CHAPTER 10 l RADIDACTIVE EFFLUENT TREATMENT AND MONITORING l l . TABLE OF CONTENTS l f NUMBER PAGE 10.1 AIRBORNE RELEASES...................... I j 4 10.1.1

System Description

I 10.1.1.1 Waste Gas Holdup System................... 1 10.1.1.2 Ventilation Exhaust Treatment System 1 l 10.1.2 Radiation Monitors l i 10.1.2.1 Auxiliary Building Vent Effluent Monitors.......... 1 10.1.2.2 Containment Purge Effluent Monitors............. -2 l 10.1.2.3 Waste Gas Decay Tank Monitors................ 2 10.1.2.4 Gland Steam and Condenser Air Ejector Monitors 2 i 10.1.2.5 Radwaste Building Ventilation Monitor............ 3 10.1.2.6 Component Cooling Water Monitor............... 3 10.1.2.7 Miscellaneous Ventilation Monitors 3 10.1.3 Alarm and Trip Setpoints 3 10.1.3.1 Setpoint Calcul ations.................... 3 i 10.1.3.1.1 Auxiliary Building Vent Effluent Monitors.......... 3 j 10.1.3.1.2 Containment Purge Effluent-Monitors............. 4 10.1.3.1.3 Waste Gas Decay Tank Effluent Monitors ............4 10.1.3.2 Release Limits -....................... 4 10.1.3.3 Release Mixture....................... 5 1 10.1.3.4-Conversion Factors 10.1.3.5 HVAC Dilution Flow Rates

5 l

5 1 e 10.1.4 Allocation of Effluents from Common Release Points 6L l 10.1.5 Dose Projections for Batch Releases............. 6 j .I 10.2 LIQUID RELEASES.............-.......... 6 i 10.2.1

System Description

6 10.2.1.1 Rel ease Tanks.................... -.... 6 10.2.1.2 Turbine Building Fire and Oil Sump 6 10.2.1.3 Condensate Polisher Sump ...................7 l i 10.2.2 Radiation Monitors '7 l 10.2.2.1 Liquid Radwaste Effluent Monitors.............. 7. 10.2.2.2 Station Blowdown Monitor 7 10-11

BYRON REVISION 0.K JANUARY 1993 CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING 9 TABLE OF CONTENTS (Cont'd) 10.2.2.3 Reactor Contair int Fan Cooler (RCFC) and Essential Service Wate- ~,SW) Outlet Line Monitors........... 7 10.2.2.4 Turbine Bui', ..y Fire and Oil Sump Monitor 8 10.2.2.5 Condensate Polisher Sump Monitor 8 10.2.3 Alarm and Trip Setpoints 8 10.2.3.1 Setpoint Calcul ations..................... 8 10.2.3.1.1 Liquid Radwaste Effluent Monitor 8 10.2.3.1.2 Station Blowdown Monitor 8 10.2.3.2 Discharge Flow Rates 9 10.2.3.2.1 Release Tank Discharge Flow Rate 9 10.2.3.3 Release Limits 10 10.2.3.4 Rel e ase Mi xture....................... 10 10.2.3.5 Conversion Factors 10 () 10.2.3.6 Liquid Dilution Flow Rates 10 10.2.4 Allocation of Effluents from Common Release Points 10 10.2.5 Projected Concentrations for Releases............ 10 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM....... 12 r' k 10-111 l

5 BYRON REVISION 0.K JANUARY 1993 .,sm. k/ CHAPTER 10 LIST OF TABLES NUMBER PAGE 10-1 Assumed Composition of the Byron 10-13 Station Noble Gas Effluent 10-2 Assumed Composition of the Byron Station Liquid Effluent 10-14 t F $(J 10-iv

BYRON REVISION 0.K JANUARY 1993 s 7 CHAPTER 10 LIST OF FIGURES NUMBER PAGE 10-1 Simplified HVAC and Gaseous Effluent Flow Diagram 10-15 I 10-2 Simplified Liquid Radwaste Processing Diagram .0-17 10-3 Liquid Release Flowpath 10-18 10-4 Simplified Solid Radwaste Processing Diagram 10-19 O o (s 10-v

BYRON REVISION 0.K JANUARY 1993 'J CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1

System Description

A simplified HVAC and gaseous effluent flow diagram is provided in Figure 10-1. The principal release points for potentially radioactive airborne effluents are the two auxiliary building vent stacks (designated Vent Stack I and Vent Stack 2 in Figure 10-1). In the classification scheme of Section 4.1.4, each is classified as a vent release point (see Table A-1 of Appendix A). 10.1.1.1 Waste Gas Holdup System The waste gas holdup system is designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system off-gases from the reactor coolant system and providing for delay or holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The system is described in Section 11.3.2 of the Byron /Braidwood UFSAR. 10.1.1.2 Ventilation Exhaust Treatment System t Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in gaseous effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters prior to release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figure 10-1. Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components. 10.1.2 Radiation Monitors 10.1.2.1 Auxiliary Building Vent Effluent Monitors Monitors IRE-PR028 (Unit 1) and 2RE-PR028 (Unit 2) continuously monitor the final effluent from the auxiliary building vent stacks. Both vent stack monitors feature automatic isokinetic sampling, grab sampling, iodine and particulate sampling and tritium sampling. In normal operation all three noble gas channels (low, 10-1 i

BYRON REVISION 0.K JANUARY 1993 O mid-range, high) are on line and active. On a high alarm the low and mid-range noble gas channels are closed and only the high range noble gas channel remains active. The iodine and particulate channels, however, continue to operate under all conditions. No automatic isolation or control functions are performed by these monitors. Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1. 10.1.2.2 Containment Purge Effluent Monitors Monitors IRE-PR001 (Unit 1) and 2RE-PR001 (Unit 2) continuously monitor the effluent from the Unit I and Unit 2 containments, respectively. When airborne radioactivity in the containment purge effluent stream exceeds a specified level station personnel will follow established procedures to terminate the release by manually activating the containment purge valves. Additionally, the auxiliary building vent effluent monitors provide an independent, redundant means of monitoring the containment purge effluent. No automatic isolation or control functions are performed by these monitors. I\\ Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1. Monitors 1(2)RE-AR0ll and 1(2)RE-AR012 monitor the containment atmosphere. On high alarm during a containment purge, these monitors will automatically terminate the purge. 10.1.2.3 Waste Gas Decay Tank Monitors Monitors ORE-PR002A/B continuously monitor the noble gas activity released from the gas decay tanks. On high alarm, the monitors automatically initiate closure of the valve OGW104 thus terminating the release. Pertinent information on these monitors and associated control devices is provided in Byron /Braidwood UFSAR Table 11.5-1. 10.1.2.4 Gland Steam and Condenser Air Ejector Monitors Monitors IRE-PR027 and 2RE-PR027 continuously monitor the condenser air ejector gas from Units 1 and 2, respectively. No control device is initiated by these channels. r~'s V 10-2

+ BYRON REVISION 0.K JANUARY 1993 o) (U The following actions are initiated by this monitor: a) Start 00G01C, Off-Gas Ejector HVAC System Exhaust Fan b) Close 100G035 and 200G035 c) Open 00G038, 100G037, and 200G037 Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1. 10.1.2.5 Radwaste Building Ventilation Monitor Monitor ORE-PR026 continuously monitors radioactivity in the radwaste building ventilation system. No control device is initiated by this channel. Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Tables 11.5-1. 10.1.2.6 Component Cooling Water Monitor Monitors ORE-PR009 (common), IRE-PR009 (Unit 1), and 2RE-PR009 (Unit 2) continuously monitor the component cooling water heat exchanger outlets. On high alarm ORE-PR009 initiates closure of both component cooling water surge tank (CCWST) vents, IRE-PR009 O initiates closure of the Unit 1 CCWST vent, and 2RE-PR009 initiates closure of the Unit 2 CCWST vent. Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-1. 10.1.2.7 Hiscellaneous Ventilation Monitors Monitor ORE-PR003 continuously monitors radioactivity in the ventilation exhaust from the laboratory fume hoods. No control device is initiated by this channel. Pertinent information on this monitor and associated devices is provided in Byron /Braidwood UFSAR Table 11.5-1. 10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Auxiliary Buildin; Vent Effluent Monitors The setpoints for the low range noble gas channel are conservatively established at 2.5% of the maximum permissible release rate for the high alarm and 1/4% of the maximum release rate for the alert alarm. OQ 10-3

BYRON. REVISION 0.K JANUARY 1993 The setpoints for the high range noble gas channel are conservatively established at 50% of the maximum permissible release rate for the high alarm and 5% of the maximum release rate for the alert alarm. 10.1.3.1.2 Containment Purge Effluent Monitors The setpoints are established at 1.25 times the containment noble gas activity during purge. However, per procedure, the total station release rate is limited to 1% of the maximum permissible release rate during this evolution. (See Section 10.1.3.2) 10.1.3.1.3 Waste Gas Decay Tank Effluent Monitors The setpoints are established at 1.25 times the analyzed waste gas tank activity during release. However per procedure, the total station release rate is limited to 1% of the maximum permissible release rate during this evolution. (See Section 10.1.3.2) 10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are x established to ensure that the release rate limits of 10 CFR 20 are not exceeded. The release limits are found by solving Equations 10-1 and 10-2 for the total allowed release rate of vent releases, Q,. (1.11)Q,, { ((f,) s 500 mrem /yr (10-1) Q,, { {(f,)[((X/Q), exp(-A,R/3600u,) i (10-2) + 1.11 V,]) < 3000 mrem /yr The summations are over noble gas radionuclides i. f Fractional Radionuclide Composition i The release rate of noble gas radionuclide i divided by the tota.1 release rate of all noble gas radienuclides. <xb 10-4

BYRON REVISION 0.K JANUARY 1993 f3 \\- / Q, Total Allowed Release Rate, Vent Release [pti/sec) l The total allowed release rate of all noble gas radionuclides released as vent releases. The remaining parameters in Equation 10-1 have the-same definitions as in Equation A-8 of Appendix A. The remaining parameters in Equation 10-2 have the same definition as in Equation A-9 of Appendix A. Equation 10-1 is based on Equation A-8 of Appendix A and the 10 CFR 20 restriction on whole body dose rate (500 mrem /yr) due to noble gases released in gaseous effluents (see Section A.I.3.1 of Appendix A). Equation 10-2 is based on Equation A-9 of Appendix A and the 10 CFR 20 restriction on skin dose rate (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.I.3.2 of Appendix A). Since the solution to Equation 10-2 is more conservative than the 7 solution to Equation 10-1, the value of Equation 10-2 (1.02 x 10 Ci/sec) is used as the limiting noble gas release rate. During evolutions involving releases from the containment or waste gas decay tanks, the total station release rate is procedurally 5 (~'g limited to 1 x 10 pCi/sec (1% of the maximum permissible release () rate). Calibration methods and surveillance frequency for the monitors will be conducted as specified in the RETS. 10.1.3.3 Release Mixture In the determination of alarm and trip setpoints, the radioactivity mixture in exhaust air is assumed to have the radionuclide composition of Table 10-1. 10.1.3.4 Conversion Factors The response curves used to determine the monitor count rates are based on the sensitivity to Xe-133 for conservatism. 10.1.3.5 HVAC Dilution Flow Rates The plant vent stack flow rates are obtained from the RM-11 console in the control room. If the values cannot be obtained from RM-II, the following default values are used. Unit 1 - 1.02 x 10 cc/sec f 8 lT (,j 10-5 i i

s BYRON REVISION 0.K~ JANUARY 1993 Unit 2 - 1.00 x 10' cc/sec-10.1.4 . Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation systems and the gas decay tanks-are comprised of contributions from both units. Consequently, allocation is made' evenly between units. 10.1.5 Dose Projections for Batch Releases-The 10 CFR 20 dose limits have been converted into a station administrative release rate limit using the methodology in the ODCM. Compliance is verified prior-to each release. Doses are-calculated after purging the containment or venting the waste gas decay tanks. Per procedure, representative samples are obtained and analyzed, and the doses calculated on a monthly basis to verify compliance with 10CFR50. 10.2 LIQUID RELEASES 10.2.1

System Description

A simplified liquid release flowpath diagram is provided in Figure 10-3. A simplified liquid radwaste processing diagram.is provided : in Figure 10-2. ~ ~ The liquid radwaste treatment system is designed and installed to reduce' radioactive liquid effluents' by collecting the liquids, providing for retention or holdup, and providing for treatment by-demineralizer for the purpose of reducing-the total radioactivity - prior to release to the environment. The system is described in Section 11.2.2 of the Byron /Braidwood Updated Final-Safety Analysis Report. ~ 10.2.1.1 Release Tanks There are two radwaste release tanks- (0WX0lT and OWX26T 30,000-gallon capacity each) which receive liquid waste before discharge to the Rock river. 10.2.1.2 Turbine Building Fire and Oil Sump The turbine building fire and oil s_ ump receives water from. selected turbine building sumps, the tendon tunnel sumps, and the diesel fuel oil storage sumps, all of which are normally non-radioactive'but potentially contaminated. The effluent from this' sump is monitored, and if radioactive contamination exceeds a 10-6

BYRON REVISION 0.K JANUARY 1993 V' predetermined level pump operation is automatically terminated. The water may then be sent to the liquid radwaste treatment system. 10.2.1.3 Condensate Polisher Sump The condensate polisher sump receives waste water from the condensate polisher system which is normally non-radioactive but potentially contaminated. The effluent from this sump is monitored and if radioactive contamination exceeds a predeter-mined level sump discharge is terminated and major condensate polisher inputs to the sump are automatically isolated. The water may then be sent to the liquid radwaste treatment system. 10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitors Monitor ORE-PR001 is used to monitor all releases from the release tanks. On high alarm, the monitor automatically initiates closure of valves OWX-353 and OWX-869 to terminate the release. Pertinent information on the monitor and associated control devices is provided in Byron /Braidwood UFSAR Table 11.5-2. -O V 10.2.2.2 Station Blowdown Monitor Monitor ORE-PR010 continuously monitors the recirculating water blowdown. No control device is initiated by this channel. Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-2. 10.2.2.3 Reactor Containment Fan Cooler (RCFC) and Essential Service Water (ESSW) Outlet Line Monitors Monitors IRE-PR002, 2RE-PR002, 1RE-PR003, and 2RE-PR003 continuously monitor the RCFC and ESSW outlet lines. No control device is initiated by these channels. Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-2. 10-7

BYRON REVISION 0.K JANUARY 1993 10.2.2.4 Turbine Building Fire and Oil Sump Monitor Monitor ORE-PR005 continuously monitors the fire and oil sump discharge. On high alarm the monitor automatically initiates an interlock to trip the discharge pumps, close valve 00D030, and terminate the release. Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-2. 10.2.2.5 Condensate Polisher Sump Monitor Monitor ORE-PR041 continuously monitors the condensate polisher sump discharge. On high alarm the monitor automatically initiates an interlock to trip the discharge pumps and terminate the release. Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5.2 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the unrestricted area. 10.2.3.1.1 Liquid Radwaste Effluent Monitor ( During release the setpoint is established at 1.5 times the analyzed tank activity plus the background reading. However, per procedure, the maximum release rate is limited to a value that will result in less than 50% MPC at the discharge point. (See Section 10.2.3.2). 10.2.3.1.2 Station Blowdown Monitor The monitor setpoint is found by solving equation 10-3. P s C" + (1.25 x C ) x FL/(F" + F' ) (10-3) 7 P Release Setpoint [pCi/mt] 1.25 Factor to account for minor fluctuations in count rate C)N L. 10-8

l BYRON REVISION 0.K JANUARY 1993 C" Concentration of activity in the circulating [ Ci/mt] l water blowdown at the time of discharge l (" Background reading") Cr Analyzed activity in the release tank [pti/mt] excluding tritium F" Circulating Water Blowdown Rate [gpm] l F', Maximum Release Tank Discharge Flow Rate [gpm] The flow rate from the radwaste discharge tank. l l 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Release Tank Discharge Flow Rate l Prior to each baLn release, a grab sample is obtained. i The results of the analysis of the waste sample determine the discharge rate of each batch as follows: FL, = 0.5(Flg (C, /MPC;)) (10-4) The summation is over radionuclides i. FL, Maximum Permitted Discharge Flow Rate l l l The maximum permitted flow rate from the radwaste discharge tank based on radiologica' limits (not chemistry limits which may be more restrictive) [gpm] FI, Circulating Water Blowdown Rate [gpm] C, Concentration of Radionuclide i in [ Ci/mL) the Release Tank (

(

10-9 l l l

BYRON REVISION 0.K JANUARY 1993 C\\d The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank. MPC; Maximum Permissible [pti/mt] Concentration of Radionuclide i 10.2.3.3 Release Limits Release limits are determined from 10 CFR 20. Discharge rates and setpoints are adjusted to ensure that 50% of applicable maximum permissible concentrations (MPC) are not exceeded. 10.2.3.4 Release Mixture For monitors ORE-PR001 and ORE-PR010 the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis. For all other liquid effluent monitors the release mixture is the radionuclides which are listed in Table 10-2. Each nuclide in the mix is at a concentration which is 10% of the MPC value given in 10 CFR 20 Appendix 2, Table II, Column 2. 10.2.3.5 Conversion Factors The readouts for the liquid effluent monitors are in Ci/mt. The cpm to pCi/mi conversion is based on the detector sensitivity to Cs-137. 10.2.3.6 Liquid Dilution Flow Rates Dilution flow rates are obtained from the main control board in the control room. Liquid effluents are not released if this information is unavailable. 10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from either release tank (0WX0lT or OWX26T) are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation is made evenly between units. 10.2.5 Projected Concentrations for Releases After determining _ F' from Equation 10-4, 10 CFR 20 compliance is verified using Equations 10-5 and 10-6. ( 10-10

BYRON REVISION 0.K JANUARY 1993 ,-~ Cl = C,[F' f(F' +Fi,)] (10-5) }] { Cl/MPC, } s! (10-6) The summation is over radionuclides 1. Cl Concentration of Radionuclide i .[pti/ml] in the Unrestricted Area The calculated concentration of-radionuclide i in the unrestricted area as determined by Equation 10-5. MPC; Maximum Permissible Concentration [ Ci/ml] of radionuclide i F ',, Maximum Release Tank Discharge [gpm] Flow Rate Ff, Circulating Water Blowdown Rate [gpm] () i i ? t 10-1.1 .i

BYRON REVISION 0.K JANUARY 1993 k_ 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured. Figure 10-4 is a simplified diagram of solid radwaste processing. 10-12

4 I BYRON REVISION 0.K JANUARY 1993 r~'s k/ Table 10-1 Assumed Composition of the Byron Station Noble Gas Effluent i Percent of i Isotope Effluent Ar-41 00.89 Kr-85m 00.18 Kr-85 24.9 Kr-87 00.4 Kr-88 00.28 Xe-131m 01.4 Xe-133m 00.57 Xe-133 71.1 ) Xe-135 00.53 Xe-138 00.04 I. s I i 10-13 i

BYRON REVISION 0.K JANUARY 1993 O Table 10-2 Assumed Composition of the Byron Station Liquid Effluent t Isotope Concentration Isotope Concentration (pCi/ml) (pCi/ml) Ru-103 8.00E - 06 Mn-54 1.00E - 05 Ag ' 10m 3.00E - 06 Fe-59 5.00E - 06 Te-127 2.00E - 05 Co-58 9.00E - 06 Te-129m 2.00E - 06 Co-60 3.00E - 06 Te-131m 4.00E - 06 Rb-86 2.00E - 06 Te-132 2.00E - 06 Zr-95 6.00E - 06 I-130 3.00E - 07 Hb-95 1.00E - 05 I-131 3.00E - 08 Mo-99 4.00E - 06 I-132 8.00E - 07 I-133 1.00E - 07 O I-135 4.00E - 07 4 Cs-134 9.00E - 07 Cs-136 9.00E - 06 Cs-137 2.00E - 06 Ce-144 1.00E - 06 Np-239 1.00E - 05 i () 10-14 l 4 S

S + REVISION 0.K JANUARY 1993 h it U E V E [ 8- 0. Sl"E g -l-3- Ew. 200txt z I u. ziw above g ame saw s r saw s Bhnots Whnots stack morer stack monitor = = Containment Unit 1 H Main page fypiCRI) E No E f '3 M 1RE-vH028 2RE-PR028 H Mini pWDe H C N sue % 5; l g l 'l Fo asa ass 2GW ,N H C H Post 10CA purge ~ r _'.gomrL I 1RE-PR001 h ** ji h R i N 0 1RE-PR011 Containtrent g" Unit 2 F 43,900 E 1 Aux &ary buildinD Sm1 SM2 Fuel handling H l 135.990 21.000 r 1 E m u. -.i u u ORE-PRC24 I ( 125. C H At: cess areas H --{E, e = ORE-PRC22 Nonacmss areas CH Gas 20 (og ung ' escharge) cay CRE-PR002 135.980 i m

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p r buildinD tank vents HCH

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-l-01-04E " = ,_ _ _ _ _ _ _ _ __, ORE.rRC25 ,,,,,,,a,,,,,,s HCH g g Vo'ume reducDon 44 _Q j 5 i equipment vents __________.,1 H 9.230 13.030 S* W *MDMS l and laborarres 7 l ORE-PR003 l 3.800 taandy Ff O ~d i f ORE-PRO 15 'I OFFSITE DOSE CALCULATION MANUAL BYRON STATION [ FIGURE 10-1 -[_ - SIMPLIFIED HVAC AND GASEOUS l EFFLUENT FLOW DIAGRAM - (SHEET 1 OF 2) M2464.!D1 143 10-15 P

REVISION 0.K JANUARY 1993 ? Unit 1 condenser 2.500 (Dunng Unit 1 sta' tup) ~~~ hogging pump h 1 I N 1.432 Gland steam 1.400 g cond'fmer t_ 8 F 0 1RE-PR027l 4g Df g 3 N E,000(Note 3) g g glHCCH Steam Jet g 32 g a)r e,ecer ,8 ig Tutt>ne buhding I t. { Generalarea l (Elevaton 451 ft) Unit 2 2.500 (Dunng g condenser g2,slartup) l hogging pump __i g l l Stack 1 Stack 2 I I I I N 1,432 Gland steam 1.400 r ;g b concenser F 0 2RE-PR027 Steam jet 32 air e}ector m n 8.830 b Solid ra0 waste %7 j ORE-PR028 Drumming station. _ _ _ _ _RE-PR014_ _ _ _ _ _ _ _ _.100 3 -( I p _ ___ g____ _ __ y _ j s volwne reducnon l ORE-PR040 HCCH ' 4{}D4-OJ t Legend Notes y F Normal or treguent now path 1. Used intermittenity to vent consulnment durm0 normal operaton. .... Ckx:asional now path 2. Used only during postacesdom operstbn.- A Contahment atmosphere radiation monitor 3. Riier unit operates only when htDN redaton is detected in oMgas "I""* * # C Charcoal fiter 4. All Dow rates are design flow rates in cubic feet per minute. p g, G Not9e Das radenon monitor (offkne) and Leam Test M passe W W (an altemate release point tnat is seldom used). H HEPA Riter M Three-channel tediation monitor for partculate, bdine, and noble pas (omine) N Normal operaton P parneuiaw m-etor (omme) OFFSITE DOSE CALCULATION MANUAL' n Hrameen recombner BYRON STATION S Normat range stack radaten monitor (parsculate, todine, and noble pas) l FIGURE 10-1 w w* range stack nobie radianon mcretor SIMPLIFIED HVAC AND GASEOUS EFFLUENT FLOW DIAGRAM l (SHEET 2 OF 2) M2464.002 143 j 10-16

w#+ UNIT ' UNIT 1 BLOWDOWN BLOWDOWN % DEMINERAL PRE. FILTERS UNfT 1 UNTT 1 SIEAM @+ BLOWDOWN ^ GENE hM R CONDENSER BLOWoovoi 6 UNIT 2 UNIT ( BLOWDOWN ELO6WN M DEMINERAI pre-MLTERS UNIT 2 STEAM r r A A N N GENERATOR BLOWDOWN TURD. BLDG. EQU!P. / / \\ \\ DRAIN FILTER TURB. BLDG. EQUIP. DRAIN TANKS 1r NQ TURB. BLDG. FLOOR FIRE & Old DRAIN FILTER TURB. BLDO. FLOOR DRAIN TANKS ORE-PI OHEMICAL DRAtN FILTER CHEMICAL m DRAIN TANK 1 e' REGENERATION q, WASTE DRAIN FILTER REGENERATION WASTE DRAIN TANKS AUK BIDG. EQUIP. DRA!N FILTER g} /_PERTURE eORu Aux B m G. EQUIP. m DRAIN TANKS DEM!NIEq utg) gm g diSO AV31ldl11e On - es i AUK BLDG. FLOOR AbRi1Ut C Cyd DRAIN FILTER AUX. BLDG. FLOOR RADWI DRAIN TANKS RADWASTE 1' M XED EVAPERATORS DEM!NEF

6 LAUNDRY DRAIN FILTER LAUNDRY LAUNDRY WASTE DRAIN TANK STORAGE TANKS

--usus cos m L

REVISION 0.K - J ANU ARY 1993~ RLOWDOWN N BED DtiMw.LP,N ITER ZERS AFTER FILTEh6 70 UNIT 1 -y CONDENSATE J, STORAGE TANIK l es es Js CLOWDOWN BLOWDOWN IID-BED DEMINERALIZER SONITOR TANKS @RS MTF R FfLTERS I' ~ ~ TO UNfT 2 e-- . CONDENSATE y f s .~~ l RELEASE TANK STORAGE TANK I I TO RADWASTE l - DISCHARGE I J$ (SEE FIG.10-3) 1__ N N VACUUM DEARATOR / - TO PRIMARY WATER ' STORAGE TANK r r / 3 UMP g ( g TO UNIT 2 J. / _ WASTE WATER TREATMENT " CIRCULATING WATER RETURN (SEE FIG.10-3) LEGEND ,g ,g M FLEXIBLE HOSE 14AIN PROCESS PATH SECONDARY PROCESS PA1H LLIZER

INTE@E @CASN USQ LlOUlO RADIATION MONITOR i r RADWASTE m

e s _ pg lONfTOR TANK RADWASTE DEMINERALIZER AFTER FILTER 1 ' RADWASTE OFFSITd DOSE CALCULATION MANUAL sD u3NrTOR TANK P'" BYRON STATION FIGURE 10-2 SIMPLIFIED LIQUID RADWASTE PROCESSING DIAGRAM 10 17 ~

REVISION 0.K 4 JANUARY 1993 1 RE.PR002 Unit 1 g RCFC A & C 7 { SX System v 1 RE.PR003 Unit 1 RCFC B & D 7 SX System 2 RE.PR002 Unit 2 RCFC A & C 7 SK System Eese ntiat Service Water Cooling 2RE.PR003 Tower. nn 2 1,000,000 gal m RCFC B & D Rewrvoir SX System k 3 r T l NDCT 1 1 NDCT 2 Compcstte Sampler M a ke up Ma keup Makeup Blowdown m Dynamic RememWNme JIowdown 96wdown 62,000,000 gotions k e o Ea!,i ' 8 81-OMR 41J i x R.,e.seTank 1 C a.en-ie W l ,g C Polisher CWXO1T ) CRE-PR001 h Ik (Flow Rate detonained I OR 05J by Station prior to E-each release) 2E g Turbine Building Fire /OR ) gg Sump Drairee Release Tank g3 OWX26T 2m j bE O <.0.nd Lktund radiation monkor NDCT a Wural&an Rock River cooling tower RCFC = Reactor. Cornalnment Fan conners OFFSITE DOSE CALCULATON MANUAL BYRON STATDN FGURE10-3 LIQUD RELEASE FLOWPATH i W1592.001 1-93 + 10-18

REVISION 0.K = -. ~ JANUARY 1993 i i I i l i i i y SOLIDIFIED PORTABLE DEMIN FOR i RADWASTE MIXED LOJtD RADWASTE '? DED DEMIN AND SPENT f LINER BLOWDOWN MIXED DED RESIN -p DEMIN RESIN TANK l MOSILE i RADWASTE SOUDIFICATION SYSTEM p-OFFSITE l DISPOSAL

i i

i l OFFSITE DOSE CALCULATION MANUAL BYRON STATION LEGEND FIGURE 10-4. @ FLEXSLE HOSE SIMPLIFIED SOLID RADWASTE ' PROCESSING DIAGRAM i ) WSB39.008 1-93 10-19 j 1 1 .I

BYRON REVISION O.K JANUARY 1993 BYRON ANNEX INDEX PAGE REVISION APPENDIX F F-i O.K F-ii O.A F-iii O.A F-iv O.A F-1 O l l F-2 O.K F-3 0.A F-4 0.K l F-5 O I F-6 O.K F-7 O.K F-8 O.K F-9 O.K F-10 0.K F-ll O.K F-12 O.K F-13 O.K F-14 O.K F-15 O.K F-16 O.K F-17 O.K F-18 O.K F-19 O.K

i-F-20 O.K F-21 0.K F-22 O.K F-23 0.K

[ F-24 O- + n I F-1 1 [

......-.m BTRO3 REVISION 0.A APRIL 1991 t APPENDIX F STATION-SPECIFIC DATA FOR BYRON UNITS 1 AND 2 I l TABLE OF CONTENTS i PAGE j F.1 INTRODUCTION F-1 F.2 REFERENCES ~ F-1 l '? t 1 il O t h 1 t i k s f ~ - a i h [ ) I 'l 6 h F-il I - ~.

BYRON REVISION 0.A APRIL 1991 APPENDIX F LIST OF TABLES NUMBER TITLE PAGE F-1 Aquatic Environmental Dose Parameters F-2 F-2 Station Characteristics F-4 F-3 Critical Ranges F-5 F-4 Average Wind Speeds F-6 F-5 X/Q and D/Q Maxima At or Beyond the Unrestricted Area Boundary F-7 F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 F-7 Site Boundary Finite Plume Gamma Dose Factors for Selected Nuclides F-9 ( 5 O F-iii

BYRON REVISION 0.A APRIL 1991 7-APPENDIX F () LIST OF FIGURES NUMBER TITLE PAGE F-1 Restricted Area Boundary F-24 O O F-iv

BYRON REVISION O MARCH 1989 i APPENDIX F STATION-SPECIFIC DATA POR BYRON UNITS 1 AND 2 F.1 INTRODUCTION j i This appendix contains data relevant to the Byron site, j Included is a figure showing the unrestricted area boundary and values of parameters used in offsite dose assessment. r t F.2 REFERENCES I i 1. U.S. Atomic Energy Commission, HERMES -- A Dicital Comeuter Code for Estimatino Recional Radiolacical Effects from the Nuclear Power Industry, Hanford Engineering Development [ Laboratory, HEDL-TME-71-168, UC-80, December 1971. l l 2. Sargent & Lundy, Nuclear Safeguards and Licensing Division Byron Calculation No. BY-ER-02, Revs. O and 1. I i 'i r t [ F-1 i 4

BYRON REVISION O.K JANUARY 1993 ^ \\ Table F-1 (V Aquatic Environment Dose Parameters i Parameter Value BasisD ( a f W f 1/M, 1/M 1 C W F, cfs 5.2E4 D i f F, cfs 4.7E3 E f t, hr 24 F t", hr 115 G Limits on Radioactivity in Unprotected Outdoor Tanksc j d Primary Water Storage Tank i 2000 Ci Outside Temporary Tank i 10 Cid (per Technical Specification 3.11.1.4) a The parameters are defined in Section A.2.1 of Appendix A. i b Basis codes: A: Reference 1 in Section F.2. B: Table E-5 of Reference 6. C: Conservative assumption (implies no additional-dilution). D: The receiving body of water is taken as the Mississippi River, whose confluence is approximatley W 115 miles downstream of the plant. F is taken as the sum of the following average flow rates: Rock River at Como, Illinois 5.0E3 cfs per Byron (45 miles downstream of Station Environmental 1 plant). Report, Section 2.4.1.2 F-2 i

REVISION 0.A APRIL 1991 Table F-1 (Cont'd) Notes (Cont'd): Mississippi River near 4.7E4 cfs per Quad-Dewitt, Iowa (approximately Cities Station Units 35 miles upstream of con-1 and 2 Safety fluence with Rock River) Analysis Report, Section 2.4 E. The near-field receiving body of water is the Rock River. Ff is taken as the average flow of the Rock River at the site, 4.7E3 cfs per Byron Station Environmental Report, Section 2.4.1.2. F. Assumption. G. There are no potable water intakes on the Rock River downstream of the plant (per Byron Station Environ-mental Report, Section 2.1.3.2.1). For 10 CFR 50 compliance evaluation purposes, tW is taken as 115 hr, the estimated time of flow to the Mississippi River. The confluence of the Rock River with the Mississippi River is approximately 115 miles downstream of the ( plant (per Byron Station Environmental Report, Section 2.1.3.2.1). The flow rate is estimated as 1 mph based on the data in Table 2.2-5 of the Byron Station Environmental Report. cSee Section A.2.4 of Appendix A. dTritium and dissolved or entrained noble gases are excluded from this limit. i i l O q l F-3 ~

BYRON ' REVISION O.K JANUARY 1993 (~ Table F-2 Station Characteristics STATION: Byron LOCATION: 3.7 miles SSW of Byron, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT: Not Applicable (NA).

1) Release Height =

m

2) Diameter =

m -1 = ms

4) Heat Content =

KCal s-1

3) Exit Speed CHARACTERISTICS OF VENT STACK RELEASE POINT a
1) Release Height = 60.66 m
2) Effective Diameter = 2.80 m
3) Exit Speed

= 13.00 ms-1

  • The station has two adjacent rectangular vent stack release points of the same height and cross section.

Their centers are 15.01 m apart. CHARACTERISTICS OF GROUND LEVEL RELEASE O' I

1) Release Height = 0 m

l a

2) Building Factor (D)

= 60.6 m METEOROLOGICAL DATA A 250 ft Tower is Located 1036m SW of vent stack release point Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Temperature Elevated (NA) (NA) Vent 250 250-30 ft Ground 30 250-30 ft aUsed in calculating the meteorological and dose factors in Tables F-5, F-6, F-7. See Sections B.3 through B.6 of Appendir B. O-F-4 j i

I NYRO3 -REVISIONf0 f MARCH 1989 Table F-3 I 4-Critical Ranges. Restricted Area Nearest Nearest Dairy Farm Boundarya ResidentD Within 5 Milesc l Direction (m) (m) (m) j N 1875 3100 None -l NNE 1829 2400' None .I NE 1585 1400 3400 ENE 1234 2100 None 9 a E 1227 1900 None ESE 991 2600 5100 l SE 1006 1800 5300 ? SSE 800 1900 None-l S 945' -1100 3200 l SSW 975' 1000 None i SW 1067 1400 None WSW 1212 2700 None j i W 1189 3200 '3100 i WNW 1227 1300 5300 8 NW 1128 1900 5100 NNW 1044 2100 None a l i aApproximate distance from midpoint between gaseous affluent r release points.- (See FSAR Table 2.1-la and ER Table 2.1-1.). l Used in calculating the meteorological and dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of-l Appendix B. i bApproximate distance from center of plant per 1988 annual-survey by Teledyne Isotopes Midwest-Laboratories. i cApproximate distance from center of plant per 1983 annual survey by Telodyne Isotopes Midwest Laboratories. Used in l calculating the D/Q values in Table F-6.- l l t O i F-5 i

BYRON REVISION 0 K JANUARY 1993 Table F-4 Average Wind Speeds Downwind Averace Wind Speed (m/secia Direction Elevated Mixed Mode Ground Level N 7.9 6.3 4.2 NNE 7.6 6.3 4.5 NE 6.8 5.8 4.1 ENE 6.6 5.6 4.0 E 6.9 5.9 4.5 ESE 6.9 5.9 4.5 SE 6.5 5.7 4.0 SSE 6.2 5.4 3.7 S 6.3 5.4 4.0 SSW 6.0 5.3 3.9 SW 6.1 5.4 4.2 WSW 6.4 5.6 4.1 W 6.8 5.5 3.4 WNW 7.1 5.7 3.7 NW 7.1 5.7 3.8 NNW 7.7 6.0 4.1 t abased on Byron site meteorological data, January 1978 through December 1987. Calculated in Reference 2 of Section F.2 using formulas in Section B.1.3 of Appendix B. bThe elevated and ground level values are provided for reference purposes only. Routine dose calculations are performed using the mixed mode values. l (]) F-6

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[T BY REVISIOT SK V JANUARY C d3 Table F-7 (Cont'd) Site Boundary Finito Plume Gamma Dose Factors for Kr-85m l Downwind unrestrteted Mixed Modetvent) Release Grnund level Release Directton Area Bound Madtus V VBAR Radtus G GBAR (meters) (meters) (mrad /yr)/tuct/sec) (meters) Imrad/yr)/tutt/sec) N 1875. 1875. 2.177E-04 1.818E-04 1875. 6.403E-04 5.29BE-04 NNE 1829. 1829. 2.076E-04 1.73aE-04 1829. 5.544E-04 4.589E-04 NE 1585. 1585. 2.022E-04 1.694E-04 1585. 5.773E-04 4.778E 04 ENE 1234. 1234. 1.984E-04 1.664E-04 1234 6.395E-04 5.285E 04 E 1227. 1227. 2.331E-04 1.954E-04 1227 7.968E-04 6.580E-04 ESE 991. 991. 3.260E-04 2.728E-04 991. 1.136E - 03 9. 363E -04 SE 1006. 1006. 3.7IOE-04 3.102E-04 1006. 1.584E-03 1.305E-03 SSE 800. 800. 4.393E-04 3.660E-04 800. 2.273E-03 1.865E-03 S 945. 945. 2.813E 04 2.353E-04 945. l.240E-03 1.02tE-03 SSW 975. 975. 2.079E-04 1.743E-04 975. B.63tE-04 7.119E-04 SW 1067. 1067. 1.68BE-04 1.416E-04 1067. 6.286E-04 5.19tt 04 WSW 1212. 1212. 1.751E-04 1.468E-04 1212. 5.594E-04 4.627E-04 W 1189. 1189. 2.092E-04 1.74BE-04 1189. 6.723E-04 5.553E-04 WNW 1227. 1227. 1.4G4E-04 1.224E-04 1227. 4.690E-04 3.872E-04 NW 1128. 1128. 1.926E-04 1.607E-04 1128. 6.Ot7E-04 4.96tE-04 NNW 1044. 1044 3.126E-04 2.603E-04 1044. 9.676E-04 7.974E-04 Byron Site Meteorological Data 1/78 - 12/87 F-10

O, - BYR C REVISIO O,K ^ JANUARY C.;3 Table F-7 (Cont'd) Site Boundary Finite Plume Ganroa Dose Factors for Kr-85 Downwind Unrestrteted Mimed Mode (Vent) Release Ground Eevet Release Directton Area Dound Radius V VBAR Radius G GBAR (meters) (meters) I rnrad/v r l/ t uc t /sec ) (meters) (mrad /ycl/tutt/sec) N 1875. 1875. 2.535E-06 2.140E-06 1875. 7.3tBE-06 6.177E-06 NNE 1829.

1829, 2.469E-06 2.084E-06
1829, 6.382E-06 5.386E-06 NE 1585.

1585. 2.415E+O6 2.03BE-06 1585. 6.622E-06 5 589E-06 ENE 1234. 1234 2.367E-06 1.990E-OG

1234, 7.225E-06 6.098E-06 E

1227.

1227, 2.787E-06 2.352E-06 1227.
9. lote-06 7.68tE-06 ESE 991.

991. 3.828E-06 3.231E-06 991. 1.270E-05 1.072E-05 SE 1006. 1006. 4.364E-06 3.683E-06 1006. 1.803E-OS 1.57tE 05 SSE 800. 800. 5.153E-06 4.349E-06 800. 2.577E-05 2.t75E-05 S 945. 945. 3.32tE-06 2.803E-06 945. 1.404E 05 1.185E-05 SSW 975. 975. 2.493E-06 2.104E-OG 975. 9.869E-06 8 329E-06 SW

1067, 1067.

2.018E-06 f.703E-06 1067. 7.232E-06 6.104E-06 WSW 1212. 1212. 2.070E-06 1.747E-06 1212. 6.309E-06 5.324E-06 W 1989. 1189. 2.436E-06 2.056E-06 1189. 7.472E-06.6.306E-06 WNW 1227.. 1227. 1.708E-06 1.442E-06 1227. 5.191E-06 4.38tE-06 NW 1128. 1128. 2.238E-06-1.889E-06 1128. 6.678E -06 5.63 7E 06 NNW 1044 1044. 3.579E-06 3.021E-06

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n' /,T BYE REVISIO .K V V) JANUARY 93 Table F-7 (Cont'd) Site Boundary Finito Plumo Gamma Dose Factors for Kr-89 Oownwind Unrestricted Mined Mode (Vent) Release Ground Level Release Directton Area Bound Radius V VBAR Radius G GBAR tmeters) (meters) (mrad /yr)/(uct/sec) (meters) (mrad /yrl/tutt/sec) N 1875. 1875. 3.874E-04 3.353E-04 1875. 5.119E-04

4. 42R E -04 NNE 1829.

1829. 3.917E-04 3.390E-04 1829. 4.514E-04 3.904E-04 NE 1585. 1585. 4.092E-04 3.542E-04 1585. 4.994E 04

4. 320E -04 ENE 1234.

1234. 4.909E-04 4.250E-04 1234 7.066E-04 6.11tE-04 E 1227. 1227. 5.876E-04 5.087E-04 1227. 8,980E-04 7,7670-04 ESE 991. 991. 1.OOtE-03 8.669E-04 991. 1.662E-03 1.437E-O3 SE 1006. 1006. 1.052E-03 9.1IOE-04 1006. 1.834E-03 1.586E-03 SSE 800. 800. 1.274E-03 1.103E-03 800. 2.736E-03 2.366E-O3 S 945. 945. 8.388E-04 7.261E-04 945. 1.633E-03 f.413E 03 SSW 975. 975. 6.103E-04 5.283E-04 975. 1.138E 03 9.838E-04 SW 1067. 1067. 4.877E-04 4.222E-04 1067. 8.395E-04 7.2btE-04 WSW 1212. 1212. 4.748E-04 4.ttOE-04 1212. 7.570E-04 6.547E-04 W 1989. 1989. 5.142E-04 4.45tE-04 1189. 8.490E-04 7.342E-04 WNW 1227 1227. 3.590E-04 3.100E-04 1227. 5.905E-04 5.tO7E-04 NW 1128. 1128. 5.20SE-04 4.505E-04 1128. 8.806E-04 7.615E-04 NNW 1044. 1044. 9.408E-04 8.142E*04 1044. 1.738E-03 1.503E-03 Byron Site Meteorological Data 1/78 - 12/87 F-14

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BYr, REVISIO' K '.

JANUARY'b 93' Table F-7 (Cont'd) Site Doundary Finite Plume Gamma Dose Factors for Xc-131m i Downwind unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area 80und Radius V VBAR Radius G G8AR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) N 1875. 1875. 2.385E-05 8.592E-06 1875. 9.757E-05 3.206E-05 NNE 1829. 1829. 2.062E-05 7.706E-06 1829. 8.424E-05 2.775E-OS NE 1585. 1585. 1.931E-05 7.318E-06 1585. 8.807E-OS 2.896E-05 ENE 1234. 1234 1.814E-05 6.971E-06 1234. 1.OO3E-04 3.262E-05 E 1227. 1227. 2.206E-05 8.382E-06 1227. 1.290E-04 4.175E-05 E?f 991. 991. 3.255E-05 1.208E-05 991. 1.885E-04 6.032E-05 SE 1006. 1006. 3.838E-05 1.408E-05 1006. 2.74tE-04 8.722E 05 SSE BOO. 800. 5.287E-05 1.849E-05 000. 4.308E*04 15341t-04 5 945. 945. 2.861E-05 1.056E-05 945. 2.140E-04 6.805E-05 SSW 975. 975. 1.939E-05 7.399E-06 975. 1.451E-04 4.653E-05 SW 1067. 1067. 1.511E-05 5.849E-06

1067, 1.030E-04 3.330E 05 WSW 1212.

1212. 1.568E-05 6.055E-06 1212. 8.542E-05 2.796E*05 W 1189.

1189, 2.220E*05 8.064E*O6 1189.

1.056E-04 3.420E-05 WNW 1227. 1227. 1.534E-05 5.595E-06 1227. 7.423E*05 2 397E-05 NW

1128, 1128.

2.119E-05 7.601E-06 1128. 9.904E-05 3.171E-05 NNW 1044 1044 3.749E-05 1.307E-05

1044, 1.610E-04 5.138E-05 Byron Site Meteorological Data 1/78 - 12/87 F-16

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.s BYR:,- R E V I S I O :,,i K.. ] JANUARY b d5 Table F-7 (Cont'd) Site Boundary Finito Plume Ganuna Dose Factors for Xe-135m Downwind unrestricted Mined Mode (vent) Release Ground Level Release Direction Area Bound Radtus v VBAR Radius G GnaR (meters) Imeters) (mred/yr)/(uct/sec) (meters) Imrad/yr)/(uct/seci N 1875. 1875. 3.355E-04 2.813E-04 1875. 7.574E-04 6.327E-04 NNE 1829. 1829. 3.191E-04 2.677E-04 1829. 6.353E-04 5.309E-04 NE 1585. 1$85. 3.171E-04 2.662E-04 1585. 6.645E-04 5.553E-04 ENE 1234. 1234 3.275E-04 2.750E-04 1234 7.919E-04 6.613E-04 E 1227 1227. 3.794E-04 3.185E-04 1227. 9.382E-04 7.834E-04 ESE 991. 991. 5.722E-04 4.802E-04 991. 1.502E-03 1.254E-03 SE 1006. 1006. 6.2BOE-04 5.269E-04 1006. 1.826E-03 1.523E-03 SSE 800. 800. 7.139E-04 5.985E-04 800. 2.546E-03 2.121E-03 5 945. 945. 4.850E-04 4.070E-04 945. 1.505E-03 1.256E-03 55W 975. 975. 3.539E-04 2.971E-04 975. 1.019E-03 8.502E-04 SW

1067, 1067.

2.924E-04 2.455E-04 1067. 7.378E-04 6.162E-04 WSW 1212. 1212. 3.058E-04 2.567E-04 1712. 7.396E-04 6.177E-04 W 1189. 1189. 3.530E-04 2.960E-04 1189. 9.316E-04 7.776E-04 WNW 1227. 1227. 2.475E-04 2.075E-04 1227 6.545E-04 5,462E-04 NW

1128, 1128.

3.325E-04 2.787E-04 1128. 8.492E-04 7.084E-04 NNW 1044 1044 5.542E-04 4.641E-04 1044. 1.425E-03 1.189E-03 Byron Site Meteorological Data 1/78 - 12/87 l l t l F-19 i l ,......... - - - _ -. ~.... ~...~. . -., ~.. - c,. ~..- ~ --

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REVISIO D) JANUARY \\.d3 BYRI I Table F-7 (Cont'd) Site Boundary Finite Plume Gamma Dose Factors for Xe-137 Downwind Unrestricted Mixed Mode (Vent) Release Ground Levet Release Direction Area Bound Radius V VB4R Radtus G GBAR (meters) (meters) (mrad /yr)/(uCt/sec) (meters) (mrad /yr)/(uCl/sec) N 1875. 1875. 6.403E-05 5.429E-05 1875. 9.597E-OS 8.133E-05 NNE 1829. 1829. 6.358E-05 5.391E-05 1829. 8.275E-05 7.013E-05 NE 1585. 1585. 6.560E-05 5.562E-05 1585. 9.063E-05 7.68tE-05 ENE 1234 1234 7.607E-05 6.45tE-05 1234 1.243E-04 1.054E-04 E 1227. 1227 9.065E-05 7.687E-05 1227. 1.555E-04 1.317E-04 ESE 991. 991. 1.509E-04 1.280E 04 901 2.80SE-04 2.377E-04 SE 1006. 1006. 1.596E-04 1.353E-04 1006. 3.144E-04 2.664E 04 SSE 800.

800, t.905E-04 1.615E-04 800.

4.627E-04 3.92tE-04 S 945. 945. 1.267E-04 1.074E-04 945. 2.775E-04 2.351E-04 SSW 975. 975. 9.229E-05 7.827E-05 975. 1.933E-04 1.638E-04 SW 1067. 1067. 7.424E-05 6.296E-05 1067. 1.4tBE-04 1.20tE-04 WSW 1212. 1212. 7.355E-05 6.237E-05 1212. 1.309E-04 1.109E-04 W 1189. 1189. 8.087E-05 6.857E-05 1189. 1.518E-04 1.286E-04 WNW 1227. 1227. 5.651E-05 4.792E*05 1227. 1.056E-04 8.945E-05 NW 1128. 1128. 8.102E-05 6.870E-05

1128, 1.535E-04 1.30tE-04 NNW 1044 1044 1.454E-04 1.232E-04 1044.

2.944E-04 2.495E-04 Byron Site Meteorotogicat Data 1/78 - 12/87 i F-21

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