ML20034H749

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Revised Odcm,Including Rev O.K. to Chapter 10 & App F
ML20034H749
Person / Time
Site: Quad Cities  
Issue date: 01/31/1993
From:
COMMONWEALTH EDISON CO.
To:
References
PROC-930131, NUDOCS 9303220016
Download: ML20034H749 (50)
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{{#Wiki_filter:. v X244 hRC C/0 00C CI AL 056, C. PAILL j DIREC1GR Of hUC. RE AC10ii REGULATION l' U. 5. huC. R E6dLA TO RY CCMMISS10h February 24, 1993 l M t. I L STATIGN P1-137 WASHIAGTON DC 20555 l Attached are the recent revisions to the Offsite Dose Calculation ] Manual's (ODCM) Chapter 10 and Appendix F for Quad Cities Station. Please complete the following manual update: REMOVE INSERT Quad Cities Station Annex Quad Cities Station Annex Entire Chapter 10. Entire Chapter 10

p. 10-1 to 10-111, Revision 0.K Jan. 1993 t

10-1 to 10-18

p. 10-1 to 10-v, 10-1 to 10-15 Quad Cities Station Annex Quad Cities Station Annex Entire Appendix F Entire Appendix F
p. F-1 to F-iv, Includes Rev. 0.K F-1 to F-?4
p. F-1.to F-iv, F-1 to F-24 s

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m. t } Please sign and date this control sheet and ret. urn'to: l 3 COMMONWEALTH EDISON COMPANY I c/o Document Control - Emergency Preparedness 1400 Opus Pl.- 5th Floor Downers Grove, IL 60515 (708)663-6547 .i Your signature indicates jou have verified that your control number is correct and you have updated your manual. Signature l I Date 190076 9303220016 930131 PDR ADOCK 05000254 h P PDR t ZEMERPLN/347/22 I 'i I

t QUAD CITIES REVISION 0.K JANUARY 1993 t t QUAD CITIES ANNEX INDEX \\ PAGE REVISION CHAPTER 10 10-i 0.K 10-ii 0.K 10-iii 0.K i 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,X 10-10 C.K i 10-11 0.K 10-12 0.K 10-13 0.K 10-14 0.K 10-15 0.K f 4 4se 5 4 P i l 10-i t

QUAD CITIES REVISVON 0.K JANUARY 1993 CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS 10.1 AIRBORNE RELEASES...................... I 10.1.1 System. Description I 10.1.1.1 Condenser Offgas Treatment System.............. I 10.1.1.2 Ventilation Exhaust Treatment System I 10.1.2 Radiation Monitors 2 10.1.2.1 Pl ant Chimney Moni tor.................... 2 10.1.2.2 Reactor Building Vent Stack Efflucat Monitor 2 10.1.2.3 Reactor Building Ventilation Monitors............ 2 10.1.2.4 Condenser Air Ejector Monitors 3 i 10.1.3 Alarm and Trip Setpoints 3 10.1.3.1 Setpoint Calculation 3 10.1.3.1.1 Reactor Building Vent Stack Monitors 3 10.1.3.1.2 Condenser Air Ejector Monitors 3 10.1.3.1.3 Plant Chimney Radiation Monitor............... 4 10.1.3.2 Release Limits 4 I 10.1.3.3 Release Mixture.........'.............. 5 10.1.3.4 Conversion Factors 5 10..l.3.5 HVAC. Flow Rates .s.,7 6 10.1.4 Allocation of Effluents from Common Release Points 6 10.1.5 Dose Projections 6 10.2 LIQUID RELEASES 6 10.2.1

System Description

6 10.2.1.1 River Discharge Tank 7 10.2.2 Radiation Monitors 7 10.2.2.1 Liquid Radwaste Effluent Monitor 7 10.2.2.2 Service Water Effluent Monitors................ 7 ~ 10.2.3 Alarm and Trip Setpoints 7 10.2.3.1 Setpoint Calculations.................... 7 10.2.3.1.1 Liquid Radwaste Effluent Monitor 7 10-ii i i 4

QUAD CITIES REVISION 0.K JANUARY 1993 CHAPTER 10 RADI0 ACTIVE EFF'UENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd) NUMBER PAGE 10.2.3.1.2 Service Water Effluent Monitors............... 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 9 10.2.3.4 Rel e ase Mi xt u re....................... 10 10.2.3.5 Ccnversion 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............ 11 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM....... 11 l 4 I 1 10-iii

L QUAD CITIES REVISION 0.K JANUARY 1993 f LIST OF TABLES i - None - 7 i r I i i e 'h' l 9 4 i I 10-iv i i l I i

QUAD CITIES REVISION 0.K JANUARY 1993 CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING LIST OF FIGURES NUMBER PAGE 10-1 Simplified Gaseous Radwaste and Gaseous Effluent flow Diagram 10-12 10-2 Simplified Liquid Radwaste Processing l Diagram 10-13 10-3 Simplified Liquid Effluent flow Diagram 10-14 ^ 10-4 Simplified Solid Radwaste Processing Diagram 10-15 10-v

QUAD CITIES REVISION 0.K JANUARY 1993 CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1

System Description

A simplified gaseous radwaste and gaseous effluent flow diagram is provided in Figure 10-1. Each airborne release point is classified as stack, vent, or ground level in accordance with the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A. The principal release points for potentially radioactive airborne effluents and their classifications are as follows: The ventilation chimney (a stack release point). The reactor building ventilation stack (a vent release point). 10.1.1.1 Condenser Offgas Treatment System The condenser offgas treatment system is designed and installed to reduce radioactive gaseous effluents by collecting non-condensable off-gases from the condenser and providing for' holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The daughter products are retained by charcoal and HEPA filters. The system is described in Section 11.3.2.1.1 of the Quad Cities UFSAR. 10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in selected effluent streams 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 ef fluents. 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 i

QUAD CITIES REVISION 0.K JANUARY 1993 10.1.2 Radiation Monitors 10.1.2.1 Plant Chimney Monitor Monitors 1(2)-1730A/B continuously monitor the final effluent from the chimney. The monitor system has isokinetic sampling, gaseous grab sampling, iodine and particulate sampling, and tritium sampling capability. The chimney effluent is also monitored by a separate particulate, iodine, and noble gas (SPING-4) system and a Victoreen system. The SPING/Victoreen system has high range capabilities to deal with accident conditions including postaccident sampling capability. The Victoreen sampling system automatically begins taking samples after a high signal has been received on the SPING-4 low range noble gas monitor. Output from the SPING/Victoreen system is obtainable in the control room. No automatic isolation or control functions are performed by these monitors. Pertinent information on these monitors is provided in the Quad Cities UFSAR Section 11.5.2.3. 10.1.2.2 Reactor Building Vent Stack Effluent Monitor The combined reactor building ventilation is also monitored by a SPING-4. This monitor has high range capabilities to deal with accident conditions. The SPING-4 noble gas detectors have ranges that envelope the range for the reactor building vent effluent trip' point. The vent stack monitor has isokinetic sampling and iodine and particulate sampling capability. No automatic isolation or control functions are performed by this monitor. Pertinent information on this monitor is provided in the Quad Cities UFSAR Section 11.5.2.4. ~ 10.1.2.3 Reactor Building Ventilation Monitors Monitors 1(2)-1735A/B continuously monitor the effluent from the Unit 1(2) reactor building. On high alarm, the monitors automatically initiate closure of valves A01(2)A-5741, A01(2)B-5741, A01(2)A-5742, and A01(2)B-5742 thus isolating the Unit 1(2) reactor building, and initiate startup of the Unit 10-2 i

QUAD CITIES REVISION 0.K JANUARY 1993 1(2) standby gas treatment system, and isolates control room HVAC. In addition to the above monitors, there is continuous iodine and particulate sampling of the reactor building exhaust. Pertinent information on these monitors is provided in Quad Cities UFSAR Section 11.5.2.4. 10.1.2.4 Condenser Air Ejector Monitors Monitors 1(2)-1733A/B continuously monitor gross gamma activity downstream of the steam jet air ejector and prior to release to the main chimney. On high alarm the monitors automatically activate an interval timer which in turn initiates closure of air operated valve A01(2)-5406, thus terminatir.g the release. In addition, monitors 1(2)-1741 continuously monitor the final offgas effluent prior to entering the chimney, and monitors 1(2)-1738 continuously monitor gross gamma activity downstream of the steam jet air ejector. No control device is initiated by these monitors. Pertinent information on these monitors is found in Quad Cities UFSAR Sections 11.5.2.1 and 11.5.2.2. 10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Reactor Building Vent Stack Monitors The setpoint for the reactor building vent stack monitor is conservatively set at 2 mr/hr above background. The reactor building ventilation stack release rate, Q,, at 2 mr/hr is calculated to be 14,400 Ci/sec. Qu is then substituted into Equations 10-1 and 10-2 to determine 0,.. 10.1.3.1.2 Condenser Air Ejector Monitors ~ The high-high trip setpoint is established at s 100 pCi/Sec per MWt (e2.5E5 Ci/sec) and the high alarm is established at s 50 Ci/sec per MWt (el.25E5 Ci/sec). 10-3 i l l

QUAD CITIES REVISION 0.K JANUARY 1993 10.1.3.1.3 Plant Chimney Radiation Monitor The setpoints for the plant chimney radiation monitor are conservatively set at 34,200 pCi/sec and 68,400 pCi/sec (high and high-high alarms respectively). At this level the combined release from chimney and vent'is approximately 10% of the 10 CFR 20 limit. This is determined by solving Equations 10-1 and 10-2 below. 10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of 10 CFR 20 are not exceeded. The release limit Q,, is found by solving Equations 10-1 and 10-2. (1.11) E ( f,[Q,,S; + Q,,V ]) < 500 mrem /yr (10-1) i j [ (Ef l(X/Q), Q,, exp(-AR/3600u,) (10-2) fj j (X/Q),Q,,exp(-A,R/3600u,)] + + (1 ll)(f;)[Q,,S 4 Q,,V;l) i < 3000 mrem /yr The summations are over noble gas radionuclides,i. f, Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides. Q,, Total Allowed Release Rate, Stack [pCi/sec] Release The total Allowed release rate of all noble gas radionuclides released as stack releases. 0,, Total Allowed Release Rate, [pti/sec] Vent Release The total allowed release rate of all noble gas radionuclides released as vent releases. 10-4 l

i QUAD CITIES REVISION 0.K JANUARY 1993 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). The value of Equation 10-1 (2.3 x 10' pCi/sec) is used as the limiting noble gas 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 set points the radioactivity mixture in the exhaust air is assumed to be the same as the analysis of a representative sample of noble gases collected at the recombiner during the calendar quarter in which the monitor is recalibrated. 10.1.3.4 Conversion factors The conversion factors used to establish gaseous effluent monitor setpoints are obtained as follows. Reactor building vent effluent monitor. r The monitor setpoint is established at 2 mr/hr above background. For the purpose of setpont determination it is assumed that the background is 1 mr/hr. There is sufficient conservatism in the setpoint calculation to accommodate routine variations in the background. However, the isotopic analysis in Section 10.1.3.3 is used to confirm that the setpoint is conservative. Condenser air ejector monitor. The isotopic analysis in Section 10.1.3.3 and the flow and monitor reading at the time of the analysis are used to establish the conversion factor. 10-5

QUAD CITIES REVISION 0.K JANUARY 1993 Plant chimney monitor. Calibration of the plant chimney monitor consists of recirculating an amount of off-gas (see 10.1.3.3) through the noble gas monitors and a Marinelli beaker. After readings have stabilized, the Marinelli beaker is removed and gamma isotopic analysis performed. The efficiency is determined from a plot of average gamma energy of the off-gas sample and net monitor readings. 10.1.3.5 HVAC Flow Rates The HVAC exhaust flow rates may be obtained from the process computers, indication in the control room, or fan combinations. Setpoints were calculated using the following values: Chimney Air Flow 350,000 cfm Combined Reactor Vent * (1 fan) 48,000 cfm Combined Rcactor Vent * (2 fans)....... 96,000 cfm

  • per unit 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents rele,,ed from the main chimney are comprised of contribut ?ons from both units. Under normal operating conditions, it is difficult to allocate the radioactivity between units due to fuel performance, in-plant leakage, power history, and other variables.

Consequently, allocation is normally made evenly between the units. During extended unit shutdowns or~ periods of known differences, the apportionment is adjusted accordingly. The allocation of ef fluents is estimated on a monthly basis. 10.1.5 Dose Projections Because the gaseous releases are continuous, the doses are routinely calculated in accordance with the RETS. 10.2 L:IQUID RELEASES 10.2.1

System Description

Simplified liquid radwaste and liquid effluent flow diagrams are provided in Figures 10-2 and 10-3. 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 10-6

1 QUAD CITIES REVISION 0.K ) JANUARY 1993 total radioactivity prior to release to the environment. The system is described in Section 11.2 of the Quad Cities UFSAR. 10.2.1.1 River Discharge Tank There is one river discharge tank (65,000 gallons capacity) which receives water for discharge to the Mississippi River. This is the only release path in use. 10.2.2 Radiation Monitors 1 10.2.2.1 Liquid Radwaste Effluent Monitor Monitor 1/2-1799-01 is used to monitor all releases from the river discharge tank. On high alarm the release is terminated manually. Pertinent information on the monitor and associated control devices is provided in Quad Cities UFSAR Sections 11.5.2 and 11.5.3. 10.2.2.2 Service Water Effluent Monitors Monitors 1(2)-1779-01 continuously monitor the service water effluent. No control device fs initiated by these monitors. Pertinent information on these monitors.is.provided in Quad Cities UFSAR 11.5.3. P 10.2.3 Alarm and Trip Setpoints 1 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. Currently these setpoints are based on the most conservative releases during the previous 18 months. If it is determined that this is no longer conservative, the setpoints are reevaluated. ~ 10.2.3.1.1 Lielid Radwaste Effluent Monitor The monitor setpoint is found by solving equation 10-3 for the total isotopic activity. P s (K) x ({ C[/{ C[/MPC,) x ((0.5 FL + F' )/fL) + B (10-3) 10-7

QUAD CITIES REVISION 0.K JANUARY 1993 P Release Setpoint [ cpm] C[ Concentration of radionuclide i in [pCi/mt] the release tank. F',, Maximum Release Tank Discharge Flow Rate [gpm] i The flow rate from the radwaste discharge tank. K Calibration constant [ cpm / Ci/mt]

MPC, Maximum Permissible Concentration of

[pCi/mt] radionuclide i F j,,, Average dilution flow of initial dilution stream [gpm] B Background Count Rate [cpni] 10.2.3.1.2 Service Water Effluent Monitors The monitor setpoint is found by solving equation 10-4. P s (K) x ({ C, /{ C, /MPC;) x ((Fjy, + FL)/F',)+B (10-4) C concentration of radionuclide i in service water 3 If there is no detectable activity then EC/EC/MPC, is assumed to be 2 x 10 pCi/mt. F',, Maximum discharge rate of service water for one [gpm] unit. All other terms are as defined in equation 10-3. 10-8

QUAD CITIES REVISION 0.K JANUARY 1993 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Release Tank Discharge Flow Rate Prior to each batch release, a grab sample is obtained. The results of the analysis of the sample determine the discharge rate of each batch as follows: FL = 0.1 (0.5 F /{ (C, /MPC,)) (10-5) The summation is over radionuclides i. 0.1 Reduction factor for conservatism. FL Maximum Permitted Discharge Flow Rate [gpm] The maximum permitted flow rate from the radwaste discharge tank. F Dilution Flow [gpm] C, Concentration of Radionuclide i in [pCi/ml] the Release Tank The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank. MPC Maximum Permissible [pCi/mt] 3 Concentration of Radionuclide i 10.2.3.3 Release Limits Release limits are determined from 10 CFR 20. balculated maximum permissible discharge rates are divided by 10 and dilution flows are divided by 2 to ensure that releases are well below applicable maximum permissible concentrations (MPC). (The factor of 2 used in the dilution flows accounts for discharging the RDT tank to the south diffuser pipe). 10-9

QUAD CITIES REVISION 0.K JANUARY 1993 10.2.3.4 Release Mixture For the liquid radwaste effluent monitor the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis plus four i additional radionuclides. The additional radionuclides are H-3, Fe-55, Sr-89, and Sr-90. The quantities to be added are determined using scaling factors derived from station release data for the previous six months. t 10.2.3.5 Conversion factors The readout for the liquid radwaste effluent monitor is in CPM. I The calibration constant is based on the detector sensitivity to Cs-137. 10.2.3.6 Liquid Dilution Flow Rates The dilution flow is determined using Equation 10-6 below. F' (N'" x F** + N'* x F'" - Fl E) (10-6) = F' Dilution flow [gpm] N** Number of circulating water pumps on. F** 157000 gpm Flow with one circulating water pump on. N'" Number of service water pumps on F*

  • 13800 gpm Flow with one service water pump on
  1. CE F

Deicing flow 10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluent released from the release tank is comprised of contributions from both units. Allocation of waste is achieved by comparing the pump timer totals for each unit's floor drain and equipment drain pumps to the amount of waste sent to the river discharge tank from the floor drain and waste collector storage tanks. Liquid effluents from laundry and chemical waste are allocated evenly between units. During extended unit shutdown or periods of significant plant input differences, the apportionment is adjusted accordingly. The allocation of the effluents is made on a monthly basis. i 10-10 ( l

t QUAD CITIES REVISION 0.K JANUARY 1993 10.2.5 Projected Concentrations for Releases If total MPC is greater than 25, the projected dose due to liquid effluent releases is calculated. Otherwise, the i releases from the previous month are used to estimate the projected dose for the coming month using the methodology in Section A.2 of Appendix A. (See Section A.2.1 of Appendix A). 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. t i figure 10-4 is a simplified diagram of solid radwaste ( processing. 4 5 i i j i l i i j j i i ? i l 10-11 e 1 4

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~ QUAD CITIES REVISION O.K JANUARY 1993 j i QUAD CITIES ANNEX INDEX PAGE REVISION APPENDIX F l-F-i O.K F-ii O.A F-iii O.A F-iv O.A F-1 O l l F-2 0.K F-3 O F-4 0.A F-5 O.K F-6 O.K F-7 O.K 1 F-8 O.K F-9 O.K F-10 O.K F-ll O.K F-12 O.K F-13 O.K F-14 0.K F-15 O.K F-16 O.K F-17 ' O.K F-18 O.K F-19 ' O~.'K F-20 O.K F-21 O.K' F-22 O.K F-23 0.A F-24 O t f ) F-i 'l

REVISION o.A QUAD CITIES APRIL 1991 i APPENDIX F STATION-SPECIFIC DATA FOR QUAD-CITIES 1 UNITS 1 and 2-l TABLE OF CONTENTS PAGE F.1 INTRODUCTION F-1 I F.2 REFERENCES F-1 l 1 t f I I i 1 l 1 i F-ii j I

REVISION 0,A l QUAD CITIES APRIL 1991 i APPENDIX F LIST OF TABLES f NUMBER TITLE PAGE f F-1 Aquatic Environment Dose Parameters F-2 f F-2 Station Characteristics F-3 F-3 Critical Ranges F-4 i F-4 Average Wind Speeds F-5 i F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary F-6 F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-7 i F-7 Site Boundary Finite Plume Gamma Dose Factors for Selected Nuclides F-8 F-8 Parameters for Calculation of N-16 i Skyshine Radiation from Quad-Cities F-23 P I h I I r F-iii i

REVISION 0.A QUAD CITIES APRIL 1991 APPENDIX F LIST of FIGURES NUMBER TITLE PAGE F-1 Unrestricted Area Boundary F-24 4 I F-iv i

QUAD CITIES REVISION O PARCH 1989 APPENDIX F STATION-SFECIFIC DATA FOR QUAD-CITIES UNITS 1 and 2 F.1 INTRODUCTION This appendix contains data relevant to the Quad-Cities site. Included are a diagram of the unrestricted area boundary and tables of values of parameters used in offsite dose assessment. F.2 REFERENCES 1. Sargent & Lundy, Nuclear Safeguards and Licensing Division, Quad-Cities Calculation No. QC-01-86, Rev. O. 2. Sargent & Lundy, Nuclear Safeguards and Licensing Division, Quad-Cities Calculation No. QC-3-88, Rev. O. i ~ ) i i r F-1

QUAD CITIES REVISION O.K JANUARY 1993 i Table F-1 Aquatic Environment Dose Parameters a Parameter Value l 1 W 1/M l f 1/M 1 W F, cfs 4.7E4 Ff, cfs 4.7E3 tf, hrb g t", hrc 8 Limits on Radioactivity in Unprotected Outdoor Tankse Not Applicable (see Section A.2.4 of Appendix A) i s a The parameters are defined in Section A.2.1 of Appendix A. b tf (hr) = 24 hr (all stations) for the fish ingestion pathway c t" (hr) = 8 hr (Distance to E. Moline is 16 miles; flow rate of 2 mph assumed) i 1 F-2 4

QUAD CITIES REVISION O MARCH A989 Table F-2 Station Characteristics Station: Quad-Cities Nuclear Power Station Location: Cordova, Illinois Characteristics of Elevated Release Point j 1) Release Height = 94.49 ma 2) Diameter 3.35 m = 20.05 m s-la 4) Heat Content = Q_kCal s-la l 3) Exit Speed = l Characteristics of Vent Stack Release Point 1) Release Height = 48.77 ma 2) Diameter 2.74 m = 8.38 m s-la 3) Exit Speed = i Characteristics of Ground Level Release 1) Release Height = 0 m ~ I 2) Building Factor (D) a 44.72 m = Meterological Data A 296 ft Tower is Located 1623 m SSE of Elevated Release Point Tower Data Used in Calculations Release Point Wind Speed Differential and Direction Temperature Elevated 296 ft 296-33 ft Vent 196 ft 196-33 ft Ground 33 ft 196-33 ft aUsed in calculating the meteorological and dose factors in Tables F-5, F-6, and F7. See Sections B.3 through B.6 of Appendiz B. F-3

QUIS CITIES { REVISION 0.A APRIL 1991 t [ Table F-3 Critical Ranges Practical Site Nearest Nearest Dairy Farm Boundary Residentb Hithin 5 MilesC a I Direction (m) (in) (m) N 864 966 None NNE 1029 1600 None NE 1212 2100 None ENE 1367 4500 None E 1170 3700 None ESE 1170 3200 None SE 1189 1600 None SSE 1422 1800 None S 1198 1300 None SSH 2140 4800 None SH 1372 4500 None WSW 823 3200 Nane 'A 713 4000 None NdH 713 4000 None NH 823 3200 None i NNH 1481 3200 None ~ + { " Nearest land in unrestricted area. t bl990 annual survey, Teledyne Isotopes Midwest Laboratories. Used in establishing the characteristics of the individual l maximally exposed to N-16 skyshine (see Section A.3.2 of Appendix A and Table F-8). c1988 annual. survey, Teledyne Isotopes Widwest Laboratories. _ _ Used in calculating the 0/0 values in Tables F-6. i ) F-4

REVISION 0.K JANUARY 1993 Table F-4 Average Wind Speeds Downwind Averace Wind Speed (m/secia Direction Elevated Mixed Mode Ground Level l N 6.9 5.0 2.6 l NNE 6.2 4.6 2.8 NE-5.3 3.7 2.4 i ENE 6.0 4.4 2.8 E 6.9 5.0 3.2 ESE 7.1 5.2 3.7 SE 6.5 4.9 3.6 SSE 5.7 4.5 3.5 i S 5.6 4.4 3.4 SSW 5.6 4.4 3.3 i SW 5.8 4.6 3.0 WSW 6.0 4.7 3.4 W 6.1 4.8 3.1 WNW =6.0, 4.5 2.6 IN 5.9 4.4 2.4 NNW 6.5' 4.7 2.5 t l abased on Quad-Cities site meteorological data (1980-1987 data i' for elevated release analysis, 1982-1987 data for ground level and mixed mode release analyses). Calet$1ated in Reference 1 of Section F.2 using formulas in Section B.I.3 of Appendix B. F-5

.. =-. QUAD CITIES REVISION 0.K JANUARY 1993 Table F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary l l Downwind E leva ted( S t ack ) Release Mtwett Mode (Vent) Release Ground Levet Release i Direction Radius A/O Radius O/O Radius X/O O/O Radius M/O D/O (meters) (sec/m**3) (meters) (1/m**2) (meters) (sec/m**3) 11/m**2) (meters). (sec/m**3) (1/m**2) N 4400. 1.344E-08 864. 9.642E-10 864 3.427E-07 2.869E-09 864. 3.817t-06 1.tOSE-08 NNE 4023. t.703E-08 1029. 1.407E-09 1029. 2.219E-07 3.049E-09 1029. 2.597E-06 1.052E-08 NE 4828. 1.287E-08 1212. 7.Of9E tO 1212. 1.32tE-07 1.299E-09 1212. 2.249E-06 6. 70 f t -09 ENE 4400. 1.09tE-08 1367. 6.723E-tO 1367. 1.213E-07 1.319E-09 1367. 1.446E-06 4 806E-09 E 3600. 1.513E-08 1970. 1.139E-09 1970. 2.215E-07 2.8ttE-09 1170. 2.212E-06 9.318t-09 ESE 3600. 2.126E-08

1970, t.536E-09 1970.

2.332E-07 3.437E-09 1970. 2.094E-06 1.047E-08 SE 4023. 1.758E-08 1189-1.OB2E O9 1189. 1.439E-07 2.384E-09 1189. 1.255E-06 6.450E-09 k SSE

4023, 1.259E-08 1422.

6.915E-10 1422. 8.279E-08 1.167E-09 1422. 6.885E-07 3.222E-09 S 4400. 1.OOSE-08 1500. 4.437E;10 1198. 6.887E-08 9.516E-10 1998. 8.371E-07 3.350E-09 SSW 4400. B.621E-09 2140. 3.110(-10 2140. 5.104E-08 4.693E-10 2140. 4.296E 07 1.3BOE 09 SW

4400, t.102E-08 1500.

4.856E,10 1372. 1.OO6E-07 1.116E-09 1372. 1.224E-06 3.856E 09 WSW

4400, t.123E-08 1500.

4.674t'-10 823. 2.158E-07 2.298E*O9 823. 2.968E-06 1.093E-08 W 4828. 1.139E-08 1500. 4.704E-10 713. 3.445E-07 2.737E-09 713. 5.27tE-06 1.522f 08 WNW 4828. 9.486E-09 1500. 4.025E,10 713. 5.02SE-07 2.816E-09 713. 7.554E-06 1.788E-08 NW 4828. 9.752E-09 823. 5.475E lO 823. 2.981E-07 2.OO9E-09 823. 4.739E-06 1.144E-08 NNW 4400. 1.045E-08 1481. 6.126E 710 1481. 1.712E-07 I. 2O? *. - 09 1481 t.928E 06 4.543E-09 Oued Cttles Site' Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B. aUsed for beta air, beta skin, and inhalation dose pathways. See Sections A.I.2, A.l.3, and A.l.4.2 of Appendix A. bUsed for produce and leafy vegetable pathways. See Section A.l.4 of Appendix A. F-6

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QUAD CITIES REVISION 0.K JANUARY 1993 Table F-7 (Cont'd) Site Boundary Finite Plume Garmna Dose Factors for Kr-85m I Downwind Unrestrteted Elevated (Stack) Release Newed Mode (Vent) Release Ground Eevet Retense Olrect tori Area Bound Radius 58&R Radius V V84R Radius G GRAR (meters) (meters) (mrad /yr)/(uct/sec) (meters) (mrad /yr)/(uCt/sec) (meters) (mead /yr)/(uct/ sect N 864 864 1.266E-04 1.077E-04 864. 4.908E-04 4.116E-04 864 2.089E-03 1.716E-03 NNE 1029. 1029. 1.322E-04 1.123E-04 1029. 4.35BE-04 3.670E-04 1029. 1.591E-03 1.312E-03 NE 1212. 1212. 8.448E-05 7.tB3E-05

1212, 2.793E-04 2.353E 04 1212.

1.383E-03 1.142E-03 ENE 1367. 1367 5.783E-05 4.913E-OS

1367, 2.056E-04 1.730E-04 1367.

9.249E-04 7.64RE-04 E 1170. 1970. 8.118E-05 6.895E-05 1970. 3.308E-04 2.777E-04 1170. 1.393E-03 1.15tE-03 ESE 1170. 1970. 1.067E-04 9.066E-05 1170. 3.662E-04 3.077E-04 1170. 1.337E-03 9.10SE-03 SE 1989. 1889. 9.118E-05 7.749E-05 1189. 2.618E-04 2.203E-04 1189. B 09tE-04 6.688E 04 SSE 1422. 1422. 5.797E-05 4.924E-05 1422. 1.5tBE-04 1.278E-04 1422. 4.523E-04 3.743E 04 5 1198 1198. 5.61tE 05 4.773E-05 1198. 1.469E-04 1.230E-04 1198. 5.192E 04 4.287E~O4 SSW 2140. 2140. 3.024E-OS 2.566E-05 2140. 7.862E-05 6.6 TOE-05 2140. 2.775E-04 2.299E 04 SW

1372, 1372.

5.402E 05 4.593E-05 1372. 1.697E-04 1.427E-04 1372. 7.594E-04 6.204E-04 WSW 823. 823. 8.767E-05 7.463E-05 823. 3.499E-04 2.939E-04 823. 1.633E-03 1.342E-03 W 713. 713. 1 112E-04 9.462E-05 713. 4.644E-04 3.893E-04

713, 2.573E-03 2.tO7E-03 WNW 713.

713. 1.OOOE-04 8,513E-05 713. 5.046E-04 4.213E-04 713. 3.454E-03 2.824E-03 NW

823, 823.

9.794E-05 8.332E-05 823. 3.993E-04 3.346E-04

823, 2.406E-03 9.972E-03 NNW 1481.

1481 6.223E-05 5.287E-05 1481. 2.449E-04 2.055E-04

1481, 1.t47E-03 9.460E-04 Quad Cttles 5 te Meteorological Osta 1/78 - 12/87 1

F-9

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) QUAD-CETIES REVISION 0.A APRIL 1991 Table F-8 Parameters for Calculation of N-16 Skyshine Radiation From Quad-Cities l Location Occupagcy Shielding Distance Nucher Hours Factor Rk k Activity OHk SFk (m) 1 Living 8160 0.7 966b j at home (nearest l resident) i 2 Fishing 50 1.0 140 3 Fishing 50 1.0 170 4 Fishing 100 1.0 200 5 Fishing 400 1.0 400 i Note: These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of the public using Equation A-35 of Appendix A. If desired, more realistic parameters could be used in place of these te refine the estimate. For example, one could determine whether the nearest resident really fishes at the specified locations. abased on Reference 2 in Section F.2. The amount of time in a year that a maximally exposed fisherman would spend at various locations near the ',tation was estimated on the basis of discussion with a 'aember of the station staff. bDistance to nearest residence (see Table F-3). I j i J F-23 1

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