ML20063F923
| ML20063F923 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/31/1994 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| PROC-940131-06, NUDOCS 9402150243 | |
| Download: ML20063F923 (100) | |
Text
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. . January 1994 QUAD CITIES ANNEX INDEX M REVISION CHAPTER 10 10-1 1.0 10-11 1.0 10-111 1.0 10-iv 1.0 10-v~ 1.0 10-1 1.0 10-2 1.0 10-3 1.0 10-4 1.0 10-5 1.0 10-6 1.0 10-7 1.0 10-8 1.0 10-9 1.0 10-10 1.0 10-11 1.0 10-12 1.0 10-13 1.0 10-14 1.0 O
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I QUAD CITIES Revision 1.0 January 1994 e t CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS , NUMPER PAGE 10.1 AIRBORNE RELEASES . . . . . . . . . . . . . . . . . . . . . 1
- 1. System Description . . . . . . . . . . . . . . . . . 1
- 1. Condenser Offgas Treatment System . . . . . . . . 1
- 2. Ventilation Exhaust Treatment System . . . . . . . 1
- 2. Radiation Monitors . . . . . . . . . . . . . . . . . . 1
- 1. Plant Chimney Monitor . . . . . . . . . . . . . . 1
- 2. Reactor Building Vent Stack Effluent Monitor . . . 2
- 3. Reactor Building Ventilatiun Monitors . . . . . 2
- 4. Condenser Air Ejector Monitors . . . . . . . . . . 2
- 3. Alarm and Trip Setpoints . . . . . . . . . . . . . . 3
- 1. Setpoint Calculation . . . . . . . . . . . . . 3
- 1. Reactor Building Vent Stack Monitors . . . . 3
- 2. Condenser Air Ejector Monitors . . . . . . . 3
- 3. Plant Chimney Radiation Monitor . . . . . . 4
- 2. Release Limits . . . . . . . . . . . . . . 4
- 3. Release Mixture . . . . . . . . . . . . . . . 4
- 4. Conversion Factors . . . . . . . . . . . . . . 5
{ }
- 5. HVAC Flow Rates . . . . . . . . . . . . . . . 5
- 4. Allocation of Effluents from Common Release Points . . 5
- 5. Dose Projections . . . . . . . . . . . . . . . . 6
/
O 10-11
f. i HQ'UAD CITIES Revision 1.0
. January 1994 ; ' l l
l CHAPTER 10 I RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd) ; i MUMPER, PAGE 10.2 LIQUID RELEASES . . . . . . . . . . . . . . . . . . . . . . . 6
- 1. System Description . . . . . . . . . . . . . . . . . . 6.
- 1. River Discharge Tank . . . . . . . . . . . . . . . 6 i
- 2. Radiation Monitors . . . . . . . . . . . , . . . . . . 6
- 1. Liquid Radwaste Effluent Monitor.. . . . . . . . . 6
- 2. Service Water Effluent Monitors' . . . . . . . . . 6 r
- 3. Alarm'and Trip Setpoints . . . . . . . . . . . . . . . 6
- 1. Setpoint Calculations . . . . . . . . . . . . . . 6
- 1. Liquid Radwaste Effluent. Monitor . . . . . . 7
- 2. Service Water Effluent Monitors . . . . . . 7 L I
- 2. Discharge Flow Rates . . . . . . . . . . . . . . 8'
- 1. Release Tank Discharge Flow Rate . . . . . . 8 ,
- 3. Release Limits . . . . . . . . . . . . . . . . . . 9 !
- 4. Release Mixture . . . . . . . . . . . . . . . . 9
- 5. . Conversion Factors . . . . . . . . . . . . . . . . 9
- 6. . Liquid Dilution Flow Rates . . . . . . . . . . . 9-
- 4. Allocation of Effluents from Common Release Points . . 9
-i
- 5. Projected Concentrations for Releases . . . . . . . . 10 !
10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM , . . . . . . 10 f I 1 10-111 1
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QUAD CITIES Revision 1.0 January 1994 . LIST OF TABLES
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2 4 e I O d 10-iv
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i QUAD CITIES Revision 1.0 'l
. January 1994 -I f\ CHAPTER 10 ) . t] . RADIOACTIVE EFFLUENT TREATMENT AND MONITORING -
LIST OF' FIGURES NUMBER, 2 AGE , 10-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-11 -i 10-2 Simplified Liquid Radwaste Processing { Diagram 10-12 , 10-3 Simplified Liquid Effluent Flow Diagram 10-13 , t 10-4 Sinplified Solid Radwaste Processing Diagram 10-14 i
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QUAD CITIES Revision 1.0 January 1994 . CHAPTER 10 RADIOACTIVE 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 radioiodine or radioactive material in particulate form in selected effluent streams by passing ventilation or vent exhaust gases through charccal 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 Plant Chimney Monitor Monitors 1(2)-1730A/B continuously monitor the final effluent from the chimney. l The monitor system has isokinetic sampling, gaseous grab sampling, iodine and particulate sampling, and tritium , sampling capability. . < i 10-1 i
QUAD CITIES Revision 1.0~ January 1994
.'f I 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, t 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 i reactor building vent effluent trip point. The vent stack monitor has isokinetic sampling and iodine and particulate sampling capability. Ti 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 j the Unit 1(2) reactor building. On high 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 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. j J' Pertinent information on these monitors is provided in Quad Cities UFSAR Section 11.5.2.4. 10.1.2.4 Condenser A'ir Ejector Monitors-1 Monitors 1(2)-1733A/B continuously monitor gross gamma ~ activity downstream of the steam jet air ejector and prior i to release to the main chimney. 4 fl 10-2
QUAD CITIES Revision 1.0 January 1994 . On high high alarm the monitors automatically activate an ' interval timer which in turn initiates closure of air operated valve A01(2)-5406, thus terminating 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. j 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 pC1/sec. O,,is then. substituted into Equations 10-1 and 10-2 to determine Q ,. t 10.1.3.1.2 Condenser Air Ejector Monitors The high-high trip setpoint is established at s 100 pCi/Sec per MWt ( 42. 5E5pCi / uec ) and the high alarm in established at s Souci/sec per MWt (41.25E5pCi/nec). 10.1.3.1.3 Plant Chimney Radiation Monitor The setpoints for the plant chimney radiation monitor are l conservatively set at 10,000 pCi/sec and 20,000 pCi/sec (high and high-high alarms respectively). At this level the combined release from chimney and vent is approximately 10% of the RETS 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 RETS are not exceeded. The release limit Q,,is found by solving Equations 10-1 and 10-2. O 10-3
QUAD CITIESJ Revision 1.0-
- January 1994 I
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- (J~~\. (1.11) { { f,[Q ,E + Q ,WJ} < 500 mrem /yr (10-1) t t
{ {Q[(X/Q), Q , exp(-A,R/3600u,) t l(10-2) 1
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< 3000 mrem /yr j The summations are over noble gas radionuclides 1.
ft Fractional Radionv.clide Composition The release rate of noble gas radionuclide.1 divided by the total release rate of all noble gas radionuclides. Qu Total Allowed Release Rate, Stack (pCi/sec) l Release
]
Tne total Allowed release rate of all noble gas radionuclides released as stack releases. ; Qw Total Allowed Release Rate, [pci/sec]. ; Vent Release ! 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 el Appendix A and the-RETS restriction on whole body dose rate (500 mrem /yr)'due-to' noble gases released in gaseous effluents (see Section l A.1.3.1 of Appendix A). Equation 10-2 is based on Equation A-9 of Appendix A and the RETS restriction on .ekin dose rate l (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.1.3.2 of Appendix A). The value of . Equation 10 (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. 10-4
QUAD CITIES Revision 1.0 January 1994 10.1.3.4 Conversion Factors 9' The conversion factors used to establish gaseous effluent monitor setpoints are obtained as follows.
- Reactor building vent effluent monitor.
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. 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 garna isotopic analysis performed. The efficiency is determined g 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 Reactor Vent * (2 f ans) . . . 96,000 cfm per unit 10.1.4 Allocatien of Effluents from Common Release Points t Radioactive gaseous effluents released from the main ; chimney are comprised of contributions 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 effluents is estimated on a monthly basis. 10-5
QUAD CITIES Revision'1.0~ :
,. January 1994
("' 10.1.5 Dose Projections ( Because the gaseous releases are continuous, the' doses are routinely calculated in accordance with the RETS. 10.2 LIQUID RELEASES 10.2.1 System Description - 4 l Simplified liquid radwaste and liquid effluent flow ! diagrams are provided in Figures 10-2 and 10-3 l l The liquid radwaste treatment system is designed and l 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 1 release to the environment. The system is described 2n ; Section 11.2 of the Quad Cities UFSAR. } 10.2.1.1 River Discharge Tank j
.t There is one river discharge tank (65,000 gallons' f capacity) which receives water for discharge to the Mississippi River. This is the only release path in use. ]
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i 10.2.2 Radiation Monitors . 10.2.2.1 Liquid Radwaste Effluent Monitor Monitor 1/2-1799-01 is used to monitor all releases from I the river discharge tank. On high alarm the release is { terminated manually. j i 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(21-1799-01 continuously monitor the service water effluent. No control device is initiated by these monitors. ; j Pertinent information on these monitors is provided in , Quad Cities UFSAR 11.5.3. ; 10.2.3- Alarm and Trip Setpoints l I 10.2.3.1 Setpoint Calculations l Alarm and trip setpoints.of liquid effluent monitors at j the principal release points are established to ensure 1 that the limits of 10 CFR 20 are not exceeded in the ] unrestricted area. 1 10-6 1
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QUAD CITIES Revision 1.0 January 1994 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 Liquid Radwaste Effluent Monitor The monitor setpoint is found by solving equation 10-3 for the total isotopic activity. P s (K) x C[/[C[/DNC) x ((0.5 FAc + Fi,) /Fi ) + B (10-3) P Release Setpoint [ cpm) C[ Concentration of radionuclide i in [pCi/ml] the release tank. Fi, Maximum Release Tank Discharge Flow Rate [gpm) The flow rate from the radwaste discharge tank. K Calibration constant (cpm /pCi/nJ) DNC, Derived Water Concentration of [pCi/nd] O j radionuclide i ' From Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402. Fic Average dilution flow of initial dilution [gpm) stream B Background Count Rate [ cpm) 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, /DWC,) x ((FAc + Fi,) /FL,)+B (10-4) 9 10-7
l 1 1 QUAD CITIES Revision 1.0 , . January 1994 i r C3 = concentration of radionuclide i in service water If there is no detectable activity then . 1 EC /EC /DWC3 is assumed to be 1 x 10-* pCi/ml . 3 3 [ Fi, = Maximum discharge rate of service water [gpm] for one unit. 't All other terms are as defined in equation 10-3. 10.2.3.2 Discharge Flow Rates , i 10.2.3.2.1 Release Tank Discharge Flow Rate i 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: l Fi, = 0.1 (0.5 P /{ (C, /DNC )) d 3 (10-5) - The summation is over radionuclides 1. i 0.1 Reduction factor for conservatism.
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FL, Maximum Permitted Discharge Flow Rate [gpm] ; The maximum permitted flow rate from the radwaste discharge tank. i F3 Dilution Flow [gpm] ' k C 3 Concentration of Radionuclide i in- [pCi/ml] the Release Tank- l The concentration of radioactivity in , the radwaste discharge tank based on measurements of a sample drawn from the , tank. l
-g DWC = Derived Water Concentration of {pC1/mi]
i f radionuclide i j From Appendix B, Table 2, Column 2 'l te 10CFR20.1001-20.2402. j I
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QUAD CITIES Revision 1.0 January 1994 - 10.2.3.3 Release Limits - Release limits are detenmined from 10 CFR 20. Calculated maximum permissible discharge rates are divided by 10 and dilution flows are divided by 2 to ensure that releases are well below applicable derived water concentrations (DWC). (The factor of 2 used in the dilution flows accounts for discharging the RDT tank to the south diffuser pipe). 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 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.
10.2.3.5 Conversion Factors The readout for the liquid radwaste effluent monitor is in CPM. 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. Fd = (N" x F" + N'" x F" - F2CE ) (10-6) Fd = 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 F 'C' = 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. 10-9
QUAD CITIES Revision 1.0-
. January 1994 a :
E10.2.5 Projected Concentrations for Releases If total DWC is greater than 25, the predected dose due to liquid effluent releases is calculated. Otherwise, the 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 i 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.
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8 O O O
QUAD CITIES- Revision 1. 0 i 4 - Janua q/1994 ! y ) QUAD CITIES ANNEX INDEX ,
\
PAGE EgVISION ! CHAPTER 11
.11-1 1.0 11-11 1.0 !
11-111 1.0 11-iv 1.0 ' ! 11-1 1.0 . 11-2 1.0 ' 11-3 1.0 ;
'11-4 1.0 11-5 1.0 11-6 1.0 l 11-7 1.0 ,
11-8 1.0 11-9 1.0 11-10 1.0 ! 11-11 1.0 1 11-12 1.0 I 11-13 1.0 'l 11-14 1.0 11-15 1.0 ) i I i 11-1 . l
e-QUAD CITIES Revision 1. 0
- January 1994 ,#
CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
~
TABLE OF CONTENTS ELGE 11 RADIOLOGICAL EINIRONMENTAL MONITORING PROGRAM 11-1 O O 11-11 f
. . _ . . . . _ . _ . . . _ . . . - - , . < . = . _. _ . __ . . _ .
./
. i ai; QUAD CITIES Revision 1. 0 -
f.- January 1994 l 1 CHAPTER 11 .l LIST OF TABLES t NUMBER TITLE PAGE 'I 11-1 Radiological Environmental .i Monitsrirn Program 11-2 11-2 Repo ;s for Radioactivity ' Conc. e in Environmental i Sant 11-9 _. 11-3 Prt ir Limits of Detection (LLD) for a i:nvironmental Radiological ! Monitorin -rogram 11-10 , h I i I r 1 t i 4 > r
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QUAD CITIES Revision 1. 0 January 1994 CHAPTER 11 LIST OF FIGURES NUMBER TITLE PAGE 11-1 Fixed Air Sampling Sites and outer Ring;TLD Locations 11 13 11-2 Inner Ring TLD Locations 11_14 11-3 Milk, Fish, Water, and Sediment Sample Locationa 11-15 9 I i l l l l l l O 11-iv
1 a l QUAD CITIES Revision 1. O
, January 1994 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PRCGRAM' .
I l The parameters of the radiological environmental monitoring program to be performed in the environs around Quad Cities Stat' ion are_ presented in Table 11-1. { Figure 11-1 shows the l'6 fixed air sampling sites and TLD locations; also shown are the outer ring (approximately 5 miles distant) TLD locations. Figure 11-2 chows the inner ring TLD locations. The TLDs are code numbered as follows: XYY-N , i i i
- g. X= 1 means inner ring,
[ X=2 means outer ring, and ; YY-N is an identification code. j Figure 11-3 shows the milk,-fish, water, and sediment sanple locations. The reporting levels for radioactivity concentrations in environmental samples are given in Table 11-2. The practical lower limits of detection for this program are given in Table 11-3. i O 1. 11-1 ' i
QUAD CITIES Revision 1. 0 January 1994 Table 11-1 Radiological Environmental Monitoring Program l l Exposure Pathway Sampling or Type and Frequency and/or Sa~r l e Sa~nlina er Monitorina Locations
- Cellection Frecuency of Analysis
- 1. Airborne a. Onsite and Near Field" Continuous sampler Particulate .samnle r :
cperation with particu-Q-01 Onsite No. 1 0.5 mi N (0.8 km A) late filter collection Gross beta analysis Q-02 Onsite No. 2 0.5 mi ENE (0.8 km D) weekly and radiciodine following filter Q-03 Onsite No. 3 0.6 mi S (1.0 km J) canister collection change d Q-04 Nitrin 1.5 mi NE (2.4 km C) biweekly" Q-05 Saddle Club Dairy Farm 1.8 mi S . . . _ (2.9 km J) Q-06 Fairbanks 1.8 mi UNW (2.9 km R) Radiciodine Canister: I-131 analysis biweekly SaTrlina Train: Test and maintenance weekly
- b. Far Field' Continuous sampler Particulate Samnler:
operation with particu-Q-07 Clinton 9.0 mi NE (14.5 km C) late filter exchange Gross beta when d Q-08 Sikkema Farm 7.0 mi ENE (11.3 km D) weekly and radioiodine analyses are made'* Q-09 Erie 13.0 mi ESE (20.9 km F) canister exchange biweekly
- 11-2
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QUAD CITIES Revision 1. 0 January 19 94 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program - Exposure Pathway sampling or Pfpe and Frequency and/or Sa ne Srrline er Mcnitorinc Lccatiens' Collection Frecuenc/ cf Tinalysis
- 2. Direct Radiatien Q-106-1, 0.7 mi ESE 1.1 km F fcent'd) Q-106-2, 0.7 mi ESE 1.1 km F Q-107-1, 0.7 mi SE 1.1 km G Q-107-2, 0.7 mi SE 1.2 km G Q-107-3, 0.8 mi SE 1.3 km G ^
Q-108-1, 0.9 mi SSE 1.4 km H . . _ Q-108-2, 0.9 mi SSE 1.4 km H Q-109-1, 0.9 mi S 1.4 km J Q-109-2, 0.9 mi S 1.4 km J Q-111-1, 2.6 mi SW 4.2 km L Q-111-2, 2.6 mi SW 4.2 km L Q-112-1, 2.4 mi WSW -3.9 km M Q-112-2, 2.4 mi WSW 3.9 km M Q-113-1, 2.5 mi W 4.0 km N Q-113-2, 2.5 mi W 4.0 km N Q-114-1, 2.6 mi win 1 4.2 km P Q-114-2, 2.6 mi WNW 4.2 km P Q-115-1, 2. 3 mi !."d 3.7 km Q Q-115-2, 2.3 mi 161 3.7 km Q Q-116-1, 2.2 mi laiW 3.5 km R Q-116-2, 2.2 mi IHiW 3.5 km R
- c. Outer Rina b Quarterly Gamma dose quarterly Q-201-1, 4.0 mi N 6.4 km A Q-201-2, 4.0 mi N 6.4 km A Q-202-1, 4.4 mi laiE 7.1 km B Q-202-2, 4.4 mi UNE 7.1 km B Q-203-1, 5.5 mi NF 8.8 km C Q-203-2, 5.5 mi UE 8.8 km C 11-4 O O O. --
T p -
. + ..
< CAD CITIES. Revis fba'l ; 0 January 1994}
Table 11-1 (Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Samole Samolino or Monitorina Locations
- cellection Frecuency of Analysis
- 2. Direct Radiation Q-204-1, 4.5 mi ENE 7.2 km D fcent'd) Q-204-2, 4.5 mi ENE 7.2 km D Q-205-1, 4.5 mi E 7.2 km E Q-205-2, 4.5 mi E 7.2 km E Q-205-4, 4.5 mi E 7.2 km E .[
Q-206-1, 4.8 mi ESE. 7.7 km F ' Q-206-2, 4.8 mi ESE 7.7 km F _ Q-207-1, 4.8 mi SE 7.7 km G Q-207-2, 4.8 mi SE 7.7 km H - Q-207-4, 4.8 mi SE 7.7 km G Q-208-1, 4.4 mi SSE 7.1 km H l Q-208-2, 4.4'mi SSE 7.1 km H Q-209-1, 4.8 mi 5 7.7 km J Q-209-2, 4.8 mi S 7.7 km K Q-209-4, 4.8 mi S 7.7 km J Q-210-1, 4.4 mi SSW 7.1 km K Q-210-2, 4 4 mi SSW 7.1 km L .. Q-210-4, 4.4 mi SSW. 7.1 km K Q-211-1, 5.0 mi SW 8.0 km L Q-211-2, 5.0 mi SW 8.0 km L Q-212-1, 4.8 mi WSW 7.7 km M Q-212-2, 4.8 mi WSW 7.7. km M Q-213-1, 4.7 mi W 7.6 km N Q-213-2, 4.7 mi W 7.6 km N Q-214-1, 4.8 mi NW 7.7 km P Q-214-2, 4. 8 mi IM 7.7 km P
~Q-215-1, 4.8 mi'NW 7.7 km Q Q-215-2, 4.8 mi NW 7.7 km Q Q-216-1, 4.~5'mi'NNW 7.2 km R Q-216-2, 4.5 mi NNW. 7.2 km R
.11-5.
__ . . _ _ . . . _ . _ - . . _ . _ . - - _ . . _ - . . _ . . . . - . _ . _ _ . . . - . _ . . _ _ _ . . . . _ . . - _ _ ~ . . . . _ . . _ . .. . . . ~ . . - m _ . _ . _
'I i
QUAD CITIES Revision 1. 0 January 1994 4 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program 'l
-j l Exposure Pathway Sampling or Type and Frequency and/or 5*amele Samolina er Monitorina Locations' Collection Frea'lency of Analysis
- 3. Waterborne 36
- a. Public Water Q-19 East Moline Mater Works, 16.0 mi SSW Weekly collection Gamma isotopic (25.8 km K) composited monthly analysis monthly Q-20 Davenport Water Works, 18.0 mi SSW (29.0 km L) ,
- b. Coolina dater Q-21 Intake Canal, 0.1 mi W (0.2 km 11) Weekly Gross beta analysis Q-22 Discharge Canal, 0.1 mi SW (0.2 km L) weekly
- c. Shoreline Q-27 Albany, Upstream on IIississippi River, Annually Gamma isotopic Sediments > 5.5 mi NE (8.8 km C) analysis annually Q-28 Cordova, Downstream on Mississippi River, 3.3 mi SSW (5.3 km K)
- 4. Incestion"
- a. Ifilk' Q-18 !!usal Dairy, 6.0 mi WSW (8.9 km M) Weekly May to October I-131 analysis on l Q-26 Bill Stanley Dairy, 3.0 mi EME Monthly: November to April each sample *
(4.8 km F) Q-31 Gerald Peterson Dairy, 5.0 mi ESE (8.0 km F)
- b. Fishi Q-24 Pool *14 of Miss. River Semiannually Gamma isotopic on edible portions of each sample.
- 5. Land Use Census
- a. Milch Animals 1. Site boundary to 2 miles Annually during grazing Enumeration by a season door-to-door or equivalent counting technique.
11-6 9 - 9 . . . 9.
~
s . .
.s -.. .
t D CITIES Revisi6e ;O' January 1994 Table 11-1 (Cont'd) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency. and/or Samele Samelind or Monitorina Locations
- Collection Fremiency of Analysis '
- 5. Land Use census 2. 2 to 5 miles Annually during grazing season Enumeration by us'ing -
fcent'd) referenced information from county agricultural. agencies or other reliable. ,
.... sources.
- 3. At dairies listed in. Item 4.a. Annually during grazing season Inquire as to' feeding practices:
- a. Pasture only.
- b. Feed and chop only.
- c. Pasture and feed; If both,~.ask
. farmer.to estimate
. fraction of food from pasture:
<25%,.25-50%,
75%, or.>75%. 11-7 e _ ______-_____.__2..__m._ _ _ _ _ _ _ - ee m-_. >w -, we V- >- a em.fsee- r .smnavVP-e fe ( ,--' y----*e'e-'tb
- s' O.e g W wW'4 f..t!----4mva .masri.v- w -. :w, ,
QUAD CITIES Revis ion 1. 0 January 1994 Table 11-1 (Cont'd) Radiological Environmental Monttoring Program Exposure Pathway Sampling or Type and Frequency __and/or Samn L , Samnlina or Monitorin'3 Locations
- collect ion Fremiency of Analysis
- b. Hearest Resident In all 16 sectors up to 5 miles. Annually See Table D-16 of Appendix D for definitions of sector codes used with kilometer distances.
3 See Figure 11-1. , Biweekly means every two weeks. A gamma isotopic analysis shall be performed wherever the gross beta concentration in a sample exceeds by five times (5x) the average concentration of the preceding calendar quarter for the sample location. Far field samples are analyzed when near field results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents released from the station or at the discretion of the Emergency Preparedness Director. ' See Figure 11-2.
- Upstream shoreline sediment monitoring location is not required, serves as control only.
h ggg pg g7g yg_3, Milk samples are required from two monitoring locations only. Three dairies are listed to ensure the minimum criteria. 5 The fish monitoring location is not identified exactly on the map, the point, Q-24, represents the area of the station discharge, Pool #14. e 11-8 e _ --- O. .
d l QUAD CITIES. Revision 1. 0 ) 4 January 1994 ; -:t I TABLE 11-2 REPORTING LEVELS FOR RADIOACTTVITY ') CONCE51TPATION9 TN EINTRONMENTAL 9 AMPLE 9 Reporting Levels ,
) -
) i t
Analysis Water Airborne Particulate Fish Milk Food-Products (pci/1) or G,ases (pC1/m') (pCi/Kg, wet). (pCi/1) (pci/Kg,1 wet), 2 H-3 2 x 10* (a)
.\
Mn-54 1 x 10' .3 x 10* ; Fe-59 4 x 10 2 1 x 10'
.i F
Co-58 1 x 10' 3 x 10* Co-60 3 x 10 1 x 10' i Zn-65 3 x 10 2 2 x 10' Zr-Nb-95 4 x 102 m I-131 2 0.9 3 l1 x-10 8 Cs-134 30 10 l'x 10 $ 60 1 x 10 2 1 Cs-137 50 20 1 x 10' 3 70 2 x 10 8 i 2 Ba-La-140 2 x 10'N 3 x 10 2
],
1 a) For drinking water samples, This is 40 CFR Part 141 value.
]l b) Total for parent and daughter.
l 1 1 11-9
.i QUAD CITIES Revision 1.0:
January 1994 2 < i TABLE 11-3 PPACTICAL LOWER LIMITS OF DETECTION (LLD) FOR STANDARD PTVIRONMENTAL RADIOLOGICAL MONITORING PROOPAM Sample Media Analysis LLD^" Units l (4.66 E_1, > Airborne " Particulate" Gross Beta + 0.01 pCi/m 3 Gamma Isotopic 0.01 pci/m' Airborne I-131 Iodine 131 0.10 pCi/m' ; Milk /Public water I-131 5 pCi/1 Cs-134 10 pCi/1 Cs-137 10 A pC1/1 Tritium 200 pCi/1 Gross Beta + 5 pCi/1 Gamma Isotopic 20 ' pCi/1/nuclide Sediment Gross Beta + 2 pCi/g dry , Gamma Isotopic 0.2 pCi/g Fish Tissue I-131 Thyroid 0.1 pCi/g wet Cs-134, 137 0.1 pCi/g Gross Beta + 1.0 pCi/g Gamma Isotopic 0.2 pCi/g 0.5 pC1/1 on milk samples collected during the pasture season. + Referenced to Cs-137 i A 5.0 pCi/1 on milk samples l l O! ; 11-10 , l
. t QUAD CITIES Revision 1.0- si
, January 1994 .,
v I~ Table 11-3'(cont'd) ks ! PRACTICAL LOWER LIMITS OF DETECTION (LLD). ; FOR STANDARD ENVIRONMENTAL RADIOLOGICAL MONITORING PROGPJLH -[ General Notes: '
- 1. Other radionuclides which are measurable and identifiable by gamma ray spectrometry, together with the nuclides indicated in Table 11-3, shall also be identified and reported when an actual analysis ,
is performed on a sample. Nuclides which are below the LLD for the ! analyses shall not be reported as being present at the LLD level for that'nuclide. }
- 2. The LLD is the smallest concentration of radioactive' material in a '
sample that will be detected with 95% probability with only 5% ; probability of falsely concluding that a blank observation represents a real signal. For a particular measurement system j (wnich may include radiochemical separation). t i 4.66 . (S r) l LLD = l - (A) . (E) . (V) . ( 2.22) . (Y) . (exp (-AAt)) . (t) LLD The a nriori lower limit of detection'for a blank sample or background analysis as defined above-(as pC1-per unit mass 3 or volume). l t Se The square root of the background count or of a blank samp3e- ! count; it is the estimated standard error of a background ? count or a blank sample count as appropriate (in units of counts). j E The counting efficiency (as counts per disintegration). .i A The number of gamma rays emitted per distintegration for 5 gamma ray radionuclide analysis (A = 1.0 for gross alpha and l- i tritium measurements). - V The sample size (in units of mass or volume). .I 2.22 The number of disintegrations per minute per picoeurie. Y The fractional radiochemical yield when applicable ! (otherwise Y = 1.0). l I i
'f i
i l 11-11 ? i t
QUAD CITIES Revision 1. 0 January 1994 4 f Table 11-3 (Cont'd) l PRACTICAL LOWER LIMITS OF DETECTION (LLD) FOR STANDARD ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM A The radioactive decay constant for the particular radionuclide (in units of reciprocal minutes).
?
At The elapsed Itime between the midpoint of sample collection and the start time of counting (At = 0.0 for environmental samples and for gross alpha measurements). t The duration of the count (in units of minutes). The value of S,, used in the calculation of the LLD for a detection system shall be based on an actual observed background count or a blank sample count (as appropriate) rather than on an unverified theoretically predicted value. Typical values of E, V, Y, t, and At shall be used in the calculation. , For gamma ray radionuclide analyses the background counts are determined from the total counts in the channels which are within plus or minus one FNHM (Full Width at Half Maximum) of the gamma {'! ray photopeak energy normally used for the quantitative analysis for that radionuclide. Typical values of the FNHM shall be used in , the calculation. The LLD for all measurements is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a nosteriori (after the fact) limit for a particular measurement. l l 0- l l i 11-12 l I
4 QUAD CITIES Revision 1.o - January 1994. l
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! us so vs so _
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o 8 1o is to t$ 30 km - 0FFSITE DOSE CALCULATION MANUAL ' i OUADCTIES STATON i FOURE111 FIXED AIR SMAPUNG StTES AND OUTER RINGTLD LOCATIONS UOsn P O t 11-13 ! i
9 QUAD CITIES Revision 2.0 January 1994 - g f j'j /) ! )ffsy~ lJ- ,sA nowy"'"*** ns.s l n.. , [ // ..k/)Iff/
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FIGURE 11-2 NNER RN3 TLD LOCATIONS
,.;s, ,,,
N TLD Location O 11-14
1 Revision 1.0 1 QUAD CITIES January 1994
]
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) O IOW A 13s Goose Lake uS II y g,gg,ggh pp, v n...' in sa x Clinton >
q t ! i us si < '0 ** ' 3 < us st Fulto,n iu r, i Clinton / ..
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DeWitt ),4 j t
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, / ru 's r :
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, s.80
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0FFSITE DOSE CALCULATION MANUAL ; QUAD-CITIES STATION FIGURE 113 MILK, RSH, WATER, AND SEDIMENT SAMPLE LOCATONS {j i.s5_m . 11-15 l
.i e- l s
QUAD CITIES Revision 1.0 January 1994
.o l
l l This page reserved for GENERIC QUAD CITIES ANNEX INDEX l CHAPTER 12.0
) i 4
All pages in Chapter 12.0 are designated REVISION 1.0 SPECIAL NOTE Until removal of the Radiological Effluent Technical Specifications has been approved by the Nuclear Regulatory Commission, the requirements of the Technical Specifications shall take precedence over this chapter, should any differences occur.
.I l
1
'l 1
l l l l l 12-i
m l 1 QUAL CITIES Revision 1.0 ' January 1994 *2 PAGE REVISION PAGE REVISIGg hj 12 - i 1.0 12 - 46 1.0 12 - ii 1.0 12 - 47 1.0 12 - iii 1.0 12 - 47 1.0 12 - iv 1.0 12 - 49 1.0 12 - 1 1.0 4 12 - 50 1.0 12 - 2 1.0 ' 12 - 51 1.0 12 - 3 1.0 12 - 52 1.0 12 - 4 1.0 12 - 5 1.0 12 - 6 1.0 12 - 7 1.0 12 - 8 1.0 12 - 9 1.0 12 - 10 1.0 12 - 11 1.0 12 - 12 1.0 12 - 13 1.0 12 - 14 1.0 12 - 15 1.0 12 - 16 1.0 12 - 17 1.0 12 - 18 1.0 12 - 19 1.0 12 - 20 1.0 12 - 21 1.0 12 - 22 1.0 12 - 23 1.0 12 - 24 1.0 12 - 25 1.0 12 - 26 1.0 12 - 27 1.0 12 - 28 1.0 12 - 29 1.0 12 - 30 1.0 12 - 31 1.0 12 - 32 1.0 12 - 33 1.0 12 - 34 1.0 12 - 35 1.0 ' 12 - 36 1.0 12 - 37 1.0 12 - 38 1.0 12 - 39 1.0 12 - 40 1.0 12 - 41 1.0 12 - 42 1.0 12 - 43 1.0 12 - $4 1.0 12 - 45 1.0 l O 12-ii
r QUAD CITIES Revision 1.0 ;
, January 1994 '
,~
I CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) ' TABLE OF CONTENTS 12.1 DEFINITIONS 12 , e i 12.2 INSTRUMENTAhION 12-6
- 1. Radioactive Liquid Effluent Instrumentation Operability 12-6 -!
- 2. Radioactive Gaseous Effluent Instrumentation Operability 12-8 t
12.3 LIQUID EFFLUENTS 12-16 ,
- 1. Concentration 12-16
- 2. Dose 12-16
- 3. Liquid Radioactive Waste Treatment System 12-19
- 4. Liquid Radioactive Waste Treatment 12-19 i S. Systems Operability and Plant Operations 12-20 12.4 GASEOUS EFFLUENTS 12-26
- 1. Dose Rate 12-26
- 2. Noble Gas Dose 12-27
- 3. Iodine-131, Iodine-133 and Particulates Dose 12-29
- 4. Off-Gas Treatment 12-31 S. Systems Operability and Plant Operations 12-32 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-37 l
- 1. Radiological Environmental Monitoring i Program 12-37
- 2. Land Use Census 12-39
- 3. Nearest Residents & Milk Animal Census 12-39
- 4. Interlaboratory Comparison Program 12-40 .
- 5. Systems Operability and Plant Operations 12-40 Radiological Envirorraental
- 6. Monitoring Program Bases 12-46 .,
12.6 RECoRDKEEPING AND REPORTING 12-47
- 1. Station Operating Records .
12-47 -
- 1. Radioactive Effluent Release Report 12-47
- 2. Annual Meteorological and Environmental Radioactivity Monitoring Report 12 I
- 3. Changes to the ODCM ~1 2-49 j
- 4. Major Changes to Radioactive Waste {
Treatment Systems (Liquid and GaseousE2-50 j l, l l I 12-iii l l
QUAD CITIES Revision 1.0 January 1994 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) LIST OF TABLES
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NUMBER TITLEPAGE 12.2-1 Radioactive' Liquid Effluent Monitoring Instrumentation 12-9 12.2-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 12-10 12.2-3 Radioactive Gaseous Effluent Monitoring Instrumentation 12-11 12.2-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 12-13 12.3-1 Allowable Concentration of Dissolved or Entrained Noble Gases Release from the Site to Unrestricted Areas in Liquid Waste 12-21 12.3-2* 12.3-3 Radioactive Liquid Waste Sampling and Analysis Program 12-22 12.4-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-33 12.5-1 Radiological Environmental Monitoring Program 12-41 12.5-2 Reporting Levels for Radioactivity Concentrations In Environmental Samples 12-42 12.5-3 Practical Lower Limits of Detection (LLD) 12-43 i
- At present, there is no Table 12.3-2 in this chapter. i l
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- .- j QUAD CITIES ' Revision 1.0 January 1994' t
12.1- Definitions 12.1.1 Channel Calibration - A Channel Calibration shall be the adjustment, as necessary, of-the. Channel' output f such.that it responds with the necessary range and { accuracy to known. values of the parameter-which the ! Channel monitors. The Channel Calibration shall 1 encomphss the entire Channel including the sensor _and L alarm and/or trip functions, .and shall include the j Channel Functional. Test. The Channel Calibration may ] be perfomed by any series of sequential, overlapping ! or total Channel steps such that the entire. Channel is !
-calibrated. !
't 12.1.2 Channel check'- A Channel Check shall be the l qualitative assessment of Channel behavior during- ~
operation by observation. This determination shall > include, where possible, comparison of the Channel j irdication and/or status with other indications and/or i status derived from independent instrument Channels I measuring the same parameter. - 12.1.3 Channel Function Test - A Channel Functional Test f shall be: l
- a. Analog Channels - the injection of a simulated signal into the Channel as close to the sensor as-
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practicable to verify Operability' including alarm ! and/or trip functions and Channel failure trips. j b.
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Bistable Channels - the injection of a simulated- ri signal into the sensor to verify Operability 'i including alarm and/or trip functions. ! The Channel Functional Test may be performed by any ' series of sequential, overlapping or totalLChannel steps such that the entire Channel is tested. 12.1.4 Dose Eauivalent I-131 1 Dose' Equivalent I-1311is that concentration of I-131-(microcurie / gram) _ which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, . I-133, I-134,. ., and I-135 actually present. The thyroid dose l conversion factors used for this calculation shall be' those listed in Table III of TID-14844, " Calculation '! of Distance Factors For Power and Test Reactor Sites.' ij i 12.1.5 Hot Standbv - Hot standby means operation'with the l reactor critical, system pressure less than 1060 psig, Li the main steam isolation valves closed, and thermal power not exceeding 15%; j 12.1.6 Immediate-.Immediat'e means that the required action: j will be initiated as soon as practicable considering i the safe operation of the unit and the importance of- ;; the required action. I t 12-1 ). I e w. y yyn- w c
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QUAD CITIES Revision 1.0 January 1994 12.1.7 Member (s) of the Public - Members of the Public means an individual in a controlled or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose. 12.1.3 Modes Switch Interlock - A reactor mode switch selects the proper interlocking for the operating or shutdown condition of the plant. Following are the reactor mode switch positions and interlocks provided:
- 1. Shutdown - In this position, a reactor scram is initiated, power to the control rod drives is removed, and the reactor protection trip systems have been deenergized for 10 seconds prior to permissive for manual reset.
- 2. Refuel - In this position, interlocks are established so that one control rod only may be withdrawn when flux amplifiers are set at the prcper sensitivity level and the refueling crane is not over the reactor. Also the trips from the turbine control valves, turbine stop valves, main steam isolation valves, and condenser vacuum are bypassed. If the refueling crane is over the reactor, all rods must be fully inserted and none can be withdrawn.
- 3. Startun/ Hot Standby - In this position, the reactor protection scram trips, initiated by condenser low vacuum and main steamline isolation valve closure, are bypassed, the low pressure main steamline isolation valve closure trip is bypassed, and the reactor protection system is energized, with IRM and APRM neutron monitoring system trips and control rod withdrawal interlocks in service.
- 4. Pun - In this position, the reactor system pressure is at or above 825 psig and the reactor protection system is energized with the APRM protection and RBM interlocks in service (excluding the 15% high flux scram).
12.1.9 Offsite Dose Calculation Manual (ODCM) - The Offsite Dose Calculation Manual shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The CDCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Sections 12-5 and (2) descriptions of the information that should be included in the Radioactive Effluent Release Reports and in the Annual ; Radiological Environmental Operating Reports required by Sections 12.6.2.1 and 12.6.2 ' 12-2 i
1 QUAD CITIES Revision-l'.O l January 1994 - ! 1 1
'I 12.1.10 Onerable - onerability - A system, subsystem, train, i component, or device shall be Operable or have .i Operability when it is_ capable of performing-its ;
specified function (s). Implicit in this definition l shall be the assumption that is necessary attendant :i instrumentation, controls, normal andcenergency l electrical power sources,' cooling or seal water, ! a lubricition or other auxiliary equipment.that are ; required for the system, subsystem,= train, component.. ^! or device to perform its function (s)=are also capable l of performing.their related support function (s). 'j 12.1.11 Oneratina'- Operating means that a system, subsystem, - train, . component or device is performing its intended .! functions in its required manner.
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'l 12.1.12 . Oneratina Cvcle - Operating Cycle is the interval between the end of one Refueling Outage for a' j particular unit and the end of the.next subsequent Refueling Outage for the same unit.
12.1.13 Process control Proaram (PCP) - The Process Control 1 Program shall contain the current formulas, sampling, I analyses,. test, and determinations to be made'to - ensure that processing and packaging of solid -: radioactive wastes based on demonstrated processing of-actual or simulated wet solid wastes will-be i accomplished in such a way as to assure compliance it with 10CFR Parts 20,-61, and 71, State regulations, burial ground requirements, and other. requirements. : governing the-disposal of solid radioactive waste. j 12.1.14 frotective' Instrumentation Definitions - Protective instrumentation definitions are as follows , r
- a. Channel - A Channel'is'an' arrangement of a sensor i and associated components used to evaluate. plant variables and produce' discrete outputs used in.
logic. A' Channel. terminates and? loses'its- q identity where individual Channel' outputs are-combined in a logic. 4
- b. Trin System A Trip System means'an' arrangement of instrument Channel trip signals and auxiliary. 1 equipment-required to initiate action to-- ;!
accompl.t.sh a protective trip function, Al Trip > System may' require:one'or more instrument. Channel- j trip signals-related to one or more plant , t parameters in' order to initiate _ Trip-System' j action. Initiation of Protective Action may , require the tripping of_a' single Trip System or ;! the coincident tripping ~of two Trip Systems, i
- c. Protective Action - An action initiated by the. , ;
protection system when a limit is' reached. ~ A :l Protective Action can be at the Channel or system j level. > 1 12-3 -! u
QUAD CITIES Revision 1.0
, January 1994 O
- d. Protective Function - A' system protective action which results form the Protective Action of the Channels monitoring a particular plant condition.
12.1.15 Rated Thermal Power - Rated Thermal Power means a steady;- state power level of 2511 thermal megawatts. 12.1.16 Reactor Power Oneration - Reactor Power Operation is any operation with the mode switch in the Startup/ Hot Standby or Run position with the reactor critical and above 1% Rated Thermal Power. 12,1.17 Reactor Vessel Pressure - Reactor Vessel Pressures listed in the Technical Specifications, unless otherwise indicated, are those measured by the reactor vessel steam space detector. 12.1.28 Refuelina Outace - Refueling Outage is the period of time between the shutdown of the unit prior to a refueling and startup of the plant subsequent to that refueling. For the purpose of designating frequency of testing and surveillance, a Refueling Outage shall mean a regularly scheduled Refueling Outage; however, where such outages occur within 8 months of the completion of the previous Refueling Outage, the required surveillance testing need not be performed until the next regularly scheduled outage. , 13.1.19 Source Check - Source Check is the qualitative assessment of instrument response when the sensor is exposed to a radioactive source. 12.1.20 Definitions Related to Estimatina Dose to the Public Usina the Anoendix I Comouter Procram:
- a. Actual - Refers to using known release data to project the dose to the public for the previous month. This data is stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.
- b. Proiected - Refers to using known release data r from the previous month or estimated release data to forecast a future dose to the public. This data is URI incorporated into the database.
1 l 1 l 12-4
l 9 QUAD CITIES -Revision 1.0 ' January 1994: N i This page is intentionally left blank. l
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QUAD CITIES Revision 1.0 Janumy 1994 12.2 INSTRUMENTATION 12.2.1.B Radioactive Licuid h Effluent Instrumentation 12.2.1.A Radioactive Licuid Surveillance Effluent Instrumentation Onerability Arnlicability: Applies to the periodic An;1icability: Applies to measurements of radioactiv'e radioactive effluents from effluents. the plant. Each radioactive liquid effluent monitoring instrument shown in The effluent monitoring Table 12.2-2 shall be inc-:rumentation shown in Table demonstrated operable by 12 . 1 shall be operable with performance of the given source al.3rm setpoints set to ensure check, instrument check, tha* the limits of Section 12.3 calibration, and functional test are not exceeded. The alarm operations at the frequencies se t aoints shall be determined in shown in Table 12.2-2. accordance with Section 10.2.
- 1. With a radioactive liquid effluent monitoring instrument alarm / trip setpoint less conservative than required, without delay suspend the release of radioactive liquid effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative.
- 2. With one or more radioactive liquid effluent monitoring instruments inoperable, take the action shown in Table 12.2-1. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
O 12-6
QUAD CITIES Revision 1.0 January 1994 .l 2.2.1.A Radioactive Liould 12.2.1.B I Radioactive Liould Effluent Instrumentation Effluent Instrumentation Ooerability Surveillance 3 In the event a limiting condition for operation and , associated action i : requirements cannot bel satisfied because of circumstances in excess of j those addressed in the specifications, provide a 30-day written report to the j NRC and no changes are required in the operational condition of the plant, and r this does not prevent the - plant from entry into an operational mode. l l A i i
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1 12-7
QUAD CITIES Revision 1.0 January 1994 12.2 2.A Radioactive Gareous 12.2.2.B Radioactive Gaseous Effluent Instrumentation Effluent Instrumentation Onerability Surveillance The effluent monitoring Each radioactive gaseous instrumentation shown in Table radiation monitoring instrument 12.2-3 shall be operable with in Table 12.2-4 shall be alarm / trip setpoints set to demonstrated operable by ensure that the limits of Section performance of the given source 12.4 are not exceeded. The check, instrument check, alerm/ trip setpoints shall be calibration, and functional test det armined in accordance with the operations at the frequency Section 10.1. shown in Table 12.2-4.
- 1. With a radioactive gaseous effluent monitoring instrument alarm / trip set point less conservative than required, without delay suspend the release of radioactive gaseous effluents monitored by the affected instrument, or declare the instrument inoperable, or change the setpoint so it is acceptably conservative.
- 2. With one or more radioactive gaseous effluent monitoring instruments inoperable, take the action shown in Table 12.2-3. Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next Semi-Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
This is in lieu of an LER.
- 3. In the event a limiting condition for operation and associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specifications, provide a 30-day written report to the '
NRC and no changes are required in the operational condition of the plant, and this does not prevent the - plant from entry into an operational mode. 12-8
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-, 'f QUAD CITIES Revision l'.0L i
,. January 1994 ;
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. TABLE 12.2-1
. RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION j1
! i Minimum No. 3 l of Operable Total No. "
Channels of Channels Parameter ActionUI ~; l 1 1 Service Water A Effluent Gross l Activity Monitor j 1 l' Liquid Radwaste C I Effluent Flow :
, Rate Monitor ;
.q 1 1 . Liquid Radwaste B .;
Effluent Gross Activity Monitor - 1
~i Notes "
i Action A: With less than the minimum number of. operable channels, releases via this pathway may continue, provided that at : least once per 12 hours grab samples are collected and analyzed for beta.or gamma activity.at an LLD of.less'than . or equal to 10-' uCi/ml. ! LAction B: With less than the minimum number of operable channels, ti effluent releases via this' pathway-may continue,'provided :i that prior to initiating a release,~at least 2 independent' samples are analyzed in accordance with Section 12.3.A.1, I and at least.2 members of the facility: staff independently- i verify the release calculation and discharge valving. Otherwise, suspend release of radioactive effluents via
-this pathway. '
. 'i Action-C: With less than the minimum number of operable channels, O releases.via this pathway may continue,:provided the. flow:. . .: ;
. rate is estimated at least once per 4 hours during actual'-.
releases. Pump curves may be utilized:to estimate flow. j d lf o i I 12-9 'I l
. . . - , ,. _ _ _ . _ _ .. . ,, ~_ - _2
QUAD CITIES Revision 1.0 January 1994 O TABLE 12.2-2 ! RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRE'ENTS Instrument Functional Source ' Instrument Check (1) Calibrat ion (1) ( 3 ) Test (1) (2) Check (1) Liquid Radwaste Effluent D R Q (7) (6) Gross Activity Monitor Service Water Effluent D R Q (7) R Gross Activity Monitor Liquid Radwaste Effluent (4) R NA NA , Flow Rate Monitor Notes (1) D = once per 24 hours M = once per 31 days Q = once per 92 days R = once per 18 months S = once per 6 months (2) The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable,
- a. Instrument indicates levels above the alarm setpoints.
- b. Circuit failure,
- c. Instrument indicates a downscale failure.
- d. Instrument controls not set in OPERATE mode.
(3) Calibration shall include performance of a functional test. (4) Instrument Check to verify flow'during periods of release. (5) Calibration shall include performance of a source check. (6) Source check shall consist of observing instrument response during a discharge. (7) Functional test may be performed by using trip check and test circuitry associated with the monitor chassis. J O^ 12-10
QUAD CITIES Revision 1.'O i January.1994 ; Im
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i TABLE 12.2-3 ; RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUME1JTATION l i Minimum No. ! [ of Operable Total 11o. 1 Channels") of Channels Parameter -Action 123 d 1 2 SJAE Radiation Monitors' D j 1 2 Main Chimney Noble A i Gas Activity Monitor _l 1 1 Main Chimney Iodine C -) Sampler ? 1 1 Main Chimney C ! Particulate Sampler
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1 1 Reactor Bldg. Vent B .! Sampler , Flow Rate Monitor' l 1 Reactor Bldg. Vent 1 C t Iodine Sampler 1 1 Reactor Bldg. Vent C Particulate Sampler ! 1 1 Main Chimney Sampler B Flow Rate Monitor 1 1 Main Chimney Flow- B Rate Monitor- l
'i 1 2 Reactor-l Bldg. Vent E 'i Noble Gas Monitor 1 1 Main Chimney F ,
High Range' Noble , Gas' Monitor 16tes ! (1) For SJAE monitors, applicable.during SJAE operation.
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For other instrumentation, applicable at.all times, j (2) Action A: With the number of operable channels less than the a minimum requirement, effluent releases via this- 3 pathway may continue,:provided grab samples are taken at least once'per 8 hour shift:and these samples are analyzed within 24. hours. J 12-11 1 l l
QUAD CITIES Revision 1.0 January 1994 O TABLE 12.2-3 (Con't) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l Action B: With the humber of operable channels less than the minimum required, effluent releases via this pathway may continue provided that the flow rate is estimated at least once per 4 hours. Action C: With less'than the minimum channels operable, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment, as required in Table 12.4-1. Action D: With less than the minimum channels operable, gases from the main condenser off gas system may be released to the environment for up to 72 hours provided at least one chimney monitor is operable; otherwise, be in hot stand-by in 12 hours. Action E: With less than the minimum channels operable, immediately suspend release of radioactive effluents via this pathway. Action F: With less than the minimum channels operable, initiate & the preplanned alternate method of monitoring the appropriate parameter (s) within 72 hours, and: W l (1) either restore the inoperable channel (s) to operable status within 7 days of the event, or (2) prepare and submit a Special Report to the Commission within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status. 12-12
1 QUAD CITIES Revision 1.0 <! January 1994 !
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TABLE 12.2-4 { RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE i REQUIREMENTS ';
-t
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Instrument Calibra- Functional Source ! Instrument Mode (2) Check (1) tion (1) (4 ) Test (1) (3 ) Check (1) .i Main Chimney Noble Gas B D R Q M : Activity Monitor + Main Chimney Sampler B D R O'" .NA I
'llow Rate Monitor i Reactor Bldg. Vent Sampler B D R QN .NA Flow Rate Monitor
{ Main Chimney Flow Rate B D R Q NA i Monitor
-l Reactor Bldg Vent- B -D R Q Q l Activity Monitor !
1 SJAE A D R R
-Q
{l-Main. Chimney Iodine and B D'M NA' NA NA- ! Particulate Sampler : Reactor Bldg. Vent Iodine B -Dm NA NA- NA and Particulate Sampler l
. Main Chimney High Range- DN "- 0 "
B 'l Noble Gas Monitor , Notes t
-(l) D=- once per 24' hours M= once per 31 days Q= once per-92 days i R= once per 18 months j i
(2) A= during SJAE operation ' B= at all times (3) The Instrument Functional Test shall also demonstrate that control' room = alarm annunciation occurs,.if any of the following conditions exist, where applicable:
- a. Instrument indicates levels above the alarm setpoint
- b. Circuit failure
- c. Instrument indicates a downscale failure
- d. ' Instrument controls not set in OPERATE mode.
12-13 1
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QUAD CITIES Revision 1.0 l January 1994 TABLE 12.2-4 (cont'd) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ! (4) Calibration shall unclude performance of a functional test. (5) Instrument check to verify operability of the instrument; that the ' instrument is in place and functioning properly. (6) Functional test shall be performed on local switches providing' low flow alarm. O i O 12-14 ,
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= -
QUAD CITIES Revision 1.0
' January 1994 :
n 12.2.C LIOUID AND GASEOUS EFFLUENTS INSTRUMENTATION PASES-
- 1. The radioactive liquid and gaseous effluent instrumentation is provided to monitor the release of radioactive materials in liquid and gaseous effluents during releases. The alarm setpoints for the instruments are provided to ensure that the alarms will occur prior to exceeding the limits of RETS and.10 -!
CFR 20. , y t 1 (
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12-15 - l
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E QUAD CITIES Revision 1.0
, January 1994 12.3.A Liauid Effluents Limits 12.3.B Liouid Effluents add Renortina Surveillance
- 1. The concentration of radioactive material released 1. The concentration of form the site to unrestricted radioactive material in areas (at or beyond the site unrestricted areas shall be boundary, see Quad Cities determined to be within the Station ODCM renex, Appendix prescribed limits by F, Figure F-1) t all be obtaining the representative limited to the c u entrations samples in accordance with specified in 10 CFR Part 20, the sampling and analysis Appendix B, Table 11, Column program specified in Table l 2 with the Table 12.3-1 12.3-3. The sample analysis I values representing the MPC's results will be used with for noble gases. the calculational methods in the ODCM to determine that With the concentration of the concentrations are radioactive material released within the limits of from the site to unrestricted Specification 12.3.A.l.
areas exceeding the above limits, without delay decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits.
- 2. a. The dose contributions
- 2. The dose or dose commitment from measured quantities above background to a member of radioactive material of the public from shall be determined by radioactive materials in calculation at least once liquid effluents released to per 31 days and a !
unrestricted areas (at or cumulative summation of beyond the site boundary) these total body and from the site shall be organ doses shall be limited to the following: maintained for each calendar quarter.
- a. During any calendar quarter:
(1) Less than or equal to 3 mrem to the whole body. (2) Less than or equal to 10 mrem to any organ. O 12-16
1 i 7 l QUAD-CITIES Revision 1.0 .. January.1994 -q
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2.1.A Licuid Effluents Limits 12.3.B Liauid Effluents ! and Recortino Surveillance l 3 b. .During any' calendar year: .
- b. Doses computed at the ,
(1) -Less than or equal nearest community water to 6 mrem t? the system will. consider only ; whole body. the drinking water- ; pathway and shall be ; i (2) Less than or equal projected using the to 20 mrem to any methods prescribed in the- ;i organ. ODCM at least once per 92 days, i 1
- c. With the calculated dose from the release of 1
-radioactive materials in :
liquid effluents 1 exceeding any of the t above limits,-prepare and - submit to the Commission H; within-30 days a Special j Report which identifies the cause(s) for y exceeding the limit (s) and defines the . , corrective actions taken , and the proposed actions : to be taken-to ensure that future releases are in compliance with 12.3.A.2.a & b. This is in lieu of a Licensee " Event' Report. -
- d. With the calculated dose 'i from the release of radioactive materials in
-liquid effluents- t exceeding the limits of Specification 12.3.A.2.a.
or 12.3.A.2.b., prepare : and submit a Special : Report to the Commission t within 30 days and limit , the subsequent releases , such'that_the dose or , dose commitment to a member of the public from , 1 1 i 12-17 i i i l
QUAD CITIES Revision 1.0 January 1994 12.3.A Licuid Effluents Limits 12.3.B Licuid Effluents and Recortina Surveillance all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the totalibody or any organ (except-thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months'. This Special Report shall include an analysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise ' obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard. The radiation exposure analysis contained in the Special Report shall use methods prescribed in the ODCM. This report is in lieu of a Licensee Event Report. 3 e. With the projected annual whole body or any internal organ dose computed at the nearest downstream community water system is equal to or exceeds 2 mrem from all radioactive materials released in liquid effluents from the - Station, prepare and submit a Special Report within 30 days to the operator of the community water syster., t O 12-18
b QUAD CITIES Revision 1.0 January 1994 q
-1 Q2.3. A
. Licuid Effluents Limits. 12.3.B Licuid Effluents !
and Renortina Surveillance ' '
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The report is prepared to _i assist the operator'in- ; meeting the requirements I of 40 CFR 141: EPA ' Primary Drinking Water Standards. A copy of this report will be sent to the IRC. This is in [ lieu of a Licensee Event *
. Report.
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- 3. 'At all' times during 3. Liquid Waste Treatment .!
processing prior to discharge 1 to the environs, process and a. Doses due to liquid control equipment provided to releases to unrestricted .; reduce the amount or areas (at or beyond the concentration of radioactive site boundary) shall be ~i materials shall be operated projected at least once ~' when the projected doce due per 31 days in accordance i to liquid effluent releases with ODCM. .i to unrestricted areas (see Figure 12.5-1), when averaged ; over 31. days, exceeds 0.13 -! mrem to the total body or ' O.42 mrem to any organ.
- 4. If liquid waste has to be or I is being discharged without '
treatment as required above, prepare and submit to the a Commission within 30 days, a /i report which includes the .! following information: j
- a. Identification of the !
defective equipment. I
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- b. Cause of the defective i equipment. l
- c. Action (s) taken to :!
restore the equipment to .I an operating status. j
- d. ' Length of time the above !
requirements were not !i satisfied. J-1[ [ .f q
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E 12-19 :
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L QUAD CITIES Revision 1.0 January 1994 12..A Licuid Effluents Limits and Recortina
- 5. In the event a limited and/or associated action requirements identified '
in Sections 12.3.A and 12.3.B cannot be f satisfied because of circumstances in excess of those addressed in this Section, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode, j t p i l l 1 i l i 1 1 12-20 ; I
l QUAD CITIES Revision 1.0- j
, January 1994' ;
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TABLE 12.3-1
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.iT ALLOWABLE' CONCENTRATION OF DISSOLVED i.
OR ENTRAINED NOBLE GASES RELEASED FROM THE- .l-' i i SITE TO UNRESTRICTED AREAS IN LIOUID WASTE .I o . f '\ i HUCLIDE . ACfuCi/mli* -I
.t
-i Kr-85m 2x10 !
t Kr-85 5x10-' f
)
Kr-87 4x10-5'
~
Kr-88 9x10-5 i i j.; Ar-41 7x10-5 : q Xe-131m 7x10-8 H l- Xe-133m 5x10" ! Xe-133 6x10-4 Xe-135m 2x10-4 ! < . .i j 2. Xe-135 2x10-8 -! i
-t 1
't { I' _ i e
.l
- j. Computed from Equation 20 of ICRP Publication 2 (1959),- ,
adjusted.for infinite cloud submersion in water, and R ,
= 0.01 rem / week, density = 1.0 g/cc abd Pw/Pt = 1 0. '
i i I_
.l s
q 4 :- e : i.' .l , 12-21 'l
- 3 1 ,
s
.e--m-e,*.-...-
QUAD CITIES Revision 1.0 January 1994 TABLE 12.3-3 PADICACTIVE LIOUID WASTE SM4PLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLItJG MITJIMUM Af!ALYSIS TYPE OF LOWER LIMIT OF TYPE FREQUEf1CY FREQUE!JCY ACTIVITY DETECTIO!3 ATIALYSIS (LLD) (uci/ml) A. Ptior to Each Prlor to Each Principal Gamma 5x10" Batch Batch Emitterc* I-131 1x10* liat ' h Wanter Prior t o Each M Gross Alpha Ix10" Rel '.sc > Tanke Batch Composite' H-3 1 x10_, Prior to Each Q Fe-55 1 x 10 Batch Componite* Sr-89, St-90 5x10 Prior to One M Discolved & 1 x10-5 Batch /M Entrained Gacec' (Gamma Emitterc) D. M" (Grab Sample) Mc I-131 1 x 10 Ple t. Continuoun Principle Gamma 5x10" pe!einen Dnitt er n' Dincolved and 1x10-5 Ent rained Ganen' (Gamma Dni tter s ) H-3 1x10-5 Gross Alpha 1x10" O (Grab Sample) O' SI-89, Sr-90 5x10-* Fe-55 1 x10 I 1 l l O: 12-22 i l l
, ,-- . - , . . . . - .~ . .- . - - . 4
-QUAD CITIES Revision 1.0 !
January 1994- j
._ y i
TABLE 12-3-3 (Continued) i RADIOACTIVE LIQUID WASTE SAMPLING l AND ANALYSIS PROGRAM .)
} TABLE NOTATION -
~!
- a. The LLL is defined in Notation A of Table'll-3. j
- b. A composite sample is one in which the quantity of liquid samples (
is proportional tc the quantity of liquid waste discharged and in ! which the method of sampling employed results in a specimen which is representative of the liquids released. f t
- c. If the alarm setpoint of the service water effluent monitor as :f determined in the ODCM is exceeded, the frequency of analysis -;
shall be increased to daily until the condition.no longer exists. -
.t
- d. A batch release is the discharge of liquid wastes of a' discrete' volume. Prior to' sampling for analyses, each batch shall be i isolated then thoroughly mixed to assure' representative sampling. l A continuous release is the discharge of liquid. wastes of a 3
-nondiscrete volume; e'g., from a volume or system that has an input flow during the release. !
- e. The principal gamma emitters for which the LLD specification . f applies exclusively are the following radionuclidesi Mn-54,- Fe-59, !
Co-60, Zn-65, Co-58, Mo-99, Cs-134, Csl37, Ce-141, and Ce-144. other peaks which are measurable and identifiable by-gamma ray . spectrometry together with the above nuclides, shall be also identified and reported when the actual' analysis'is performed on a 1 sample. Nuclides which are below the LLD for the analyses _shall . not be reported as being present at - the LLD. level for.that j nuclide. ,;
- f. The dissolved and entrained gases (gamma emitters) for which the. 1 LLD specification applies exclusively are the following .
radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, .Xe-135, and Xe-138. '! Other dissolved and entrained gases ~(gamma emitters):which-are ; measurable and. identifiable by gamma-ray spectrometry, together ! with the above nuclides, shall also be identified and reported" when an actual analysis is performed on a sample. Nuclides which are below the LLD for the' analyses.shall not be-reported as being; j present at the LLD level for that nuclide. ! q
.]
1 12-23 ! _ - , _ .. . _ , a i
QUAD CITIES Revision 1.0 January 1994 ( O 12.3.C LIOUID EFFLUENTS BASE 9
- 1. Concentration This specification is provided to ensure that the concentratiori of radioactive materials released in liquid waste effluen'ts from the site to unrestricted areas will be less than the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402. The concentration limit for noble gases was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2.
- 2. Dose This specification is provided to implement the requirements of Sections II.A. III.A and IV.A of Appendix I, 10 CFR Part
- 50. The Limiting Condition for Operation implements.the guides set forth in Section II.A of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I*, April 1977. NUREG-0113 provides methods for dose calculations consistent with Reg Guide 1.109 and 1.113.
el 12-24
- - - . - . . , . . - . . . - . . ~ . _ ~ . . . . . . ~ . . . .. . . - . . - .. . . - . - . - . - - . .- -
}
[ -QUAD CITIES' . Revision l'.0 l January 1994 . e-
.I i
12.3.C LTOUID EFFLUENT 9 BASE 9 (CONT.) l
- 3. Liquid' Waste' Treatment .
The operability of the liquid radwaste treatment system
-ensures that khis system will be available for use whenever liquid effludhts require treatment prior to release to the !
environment. The requirement that the. appropriate portions'- '! of this systern be used when specified provides assurance that - ~i the releases of radioactive materials in liquid effluents i will be kept "as low as is reasonably achievable". This i specification implements the requirements of 10 CFR Part ! 50.36a, General Design Criterion 60 of Appendix A-to 10 CFR l Part 50 and design objective Section 11.D of Appendix I to.10 j CFR Part 50. '{
.i t
^}
.t i
- t t
O 1 ., .. t 1 i
..4 q
.i l
1 i i i
'L I
f 12 # j i
.1 . :.- -= . . - - . -. - ..-.- . . . . - . - - - . . . ..=.- .
I
.l QUAD CITIES Revision 1.0 January 1994 12.4 Garcour Effluents 12.4.A. Gareoun Effluente Limitr 12.4.B carecur Effluents and Penortina Su n'eil1 an ce
- 1. The dose rate in unrestricted 1. The dose rates due to areas (at or beyond the site radioactive materials '
boundary, see Quad Cities released in gaseous Station ODCM Annex, Appendix effluents from the site F, Figure F-1) due to shall be determined to be radioactive materials within the prescribed limits released in gaseous offluents by obtaining representative from the site cha!1 Le samples in accordance with limited to the fc110 wing: the sampling and analysis program specified in Table
- a. For Noble Gases: 12.4-1. The dose rates are calculated using methods (1) Less than 500 prescribed in the off-Site -
mrem / year to the Dose calculation Manual whole body. (ODCM). (2) Less than 3000 mrem / year to the skin.
- b. For iodine-131, for iodine 133, and for all radionuclides in particulate form with half-lives greater than 8 days less than 1500 mrem / year.
f O, 12-26
~~ .
l 1 .
. . . . t QUAD CITIES. Revision 1.0~ ;
4 January 1994 - j
~ ,
1 F 2.4.A. Caseous Effluents' Limits 12.4.B caseous Effluents ! j and Renortina Surveillance -l 1 i e
- c. If the dose rates exceed the above limits,.without
- j. delay-decrease the a c release rates to bring l
the dose rates within the j !, limits, and to provide j i prorrpt notification to l l the Commission (12.6.2.1) 4 l- 2. The air dose in unrestricted 2. The air dose due to releases [ areas (at or beyond the site of radioactive noble gases :l boundary) due to Noble Gases in gaseous effluents shall i l released in gaseous effluents be determined to be.within j from the unit shall be the prescribed limits by
- limited to the following.: obtaining representative l
! samples in accordance with
- j. .
the sampling and analysis
- a. For gamma radiation: program specified in i sections A and B of Table 't i i 4
(1) Less than or equal 12.4-1. The allocation of ; ) .. to 5 nead during effluents between units a any calendar having shared effluent > l quarter. control systems and the air. l
- j. doses are determined using -l j (2) Less than or equal methods prescribed.in the- '
! to 10 mrad during ODCM at least once every 31 j' any calendar year. days. [
- b. For Beta radiation: i
, .l
]
~
(1) Less than or equal , .to 10 mrad during ! j any calendar { j quarter. ;; ' t i f 8' (2) Less than or equal ; . to 20 mrad during ') y any calendar year { i k d o ; a L >' V j- ! c ! 1 L< s-4 - 12-27 l' s-J _ _ . . - ._ ~ , , _ . . . . _ . . _ _ _ _ - _ - _ , . ~ , , . . . . . , _ . . , , . . . _ . . , , .-,,,,__,..m. . , . . . _ . , , , _ . , , . . . ., ,,.
QUAD CITIES FMwision 1.0 ,\ January 1994 12.4.A. caseous Effluents Limits 12.4.B caseous Effluents O and Penortina Surveillance 2 c. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to ensure that future releases are in compliance with 12.4.A.2.a & b. This is in lieu of a Licensee Event Report.
- d. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding the limits of Specificaticn 12.4.A.2.a. or 12.4.A.2.b., prepare and su bmit a special Report to the Commission within 30 days and limit the subsequent ~eleases such that the doses or dose committment to a member of the public from all uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposure to all members of the public from all uranium fuel cycle sources (including 1 all effluent pathways and l c'i rect l 12-28 l i
. . - ~ = . -. .. ~ , . -. - .. .
i
.. l QUAD CITIES Revision 1.0 1
' January 1994
=
I 2.4.A. Gaseous Effluents' Limits 12.4.B Gaseous Effluents and Renortina Surveillance radiation) are less than l the 40 CFR Part 90 Standard. Otherwise, obtain a variance from l the Commission to permit i releases which exceed the j 40 CFR Part 190 Stdndard. The radiation exposure t analysis contained 'in the i Special Report shall use the methods prescribed in jl the ODCM. This report is ; in lieu of a Licensee ! Event Report. , i
- 3. The dose to a member of the 3. The dose to a member of the public in unrestricted areas. public due to releases of !
(at or beyond the site iodine-131, iodine-133,
- boundary) from iodine-131, tritium, and all i iodine-133,. tritium, and all radionuclides in-particulate radionuclides in particulate form with half-lives greater form with half-lives greater than 8 days shall be than 8 days in gaseous determined to be within the r effluents released from the prescribed limits by j unit shall be limited to the obtaining representative j fellowing: samples in accordance with the sampling and analysis' j;
program specified in Table ! 12.4-1. _l For-radionuclides.not~- , determined in each batch or
- weekly composite, the dose
of radioative materials ! shall be operated. i
- b. The above specification '
shall not apply for the , off-Gas Charcoal Adsorber Beds below 30 percent of r rated thermal power. + 1 fi
.i
QUAD CITIES Revision 1.0 January 1994 12.4.A. Garecur Effluents Limits and Reoortina S. The release rate of the 5. The radioactivity rate of sum of the activities noble gases at (near) the from the noble gases outlet of the main condenser measured at the main air ejector shall be condenser air ejector continuously monitored in e shall be limited to less accordance with than or equal to 100 Specification 12.2.2.A. The microcuries/see per MWt release rate of the sum of * (after 30 minutes decay) the activities from nolble at all times. With the gases from the main release rate of the sum condenser air ejector shall of the activities from be determined to be within noble gases at the main the limits of Specification condenser air ejector 12.4.A.5 at the following exceeding 100 frequencies by performing.an microcuries/sec per icit isotope analysis of a (after 30 minutes decay), representative sample of , restore, the release rate gases taken at the ' to within its limits recombiner outlet, or at the within 72 hours, or be in rir ejector outlet if the at least HOT STANDBY recombiner is bypassed. within the next 12 hours.
- a. At least once per 31 days.
- b. Within 4 hours following an increase, as indicated by i
the main condenser air ejector noble gas activity monitor, of greater than 50%, after factoring out increases due to changes in thermal power 1evel and off-gas flow, in the nominal steady-state fission gas release from the primary coolant.
- 6. In the event a limit and/or associated action reqairement identified in Sections 12.4.A and 12.4.B cannot be satisfied because of circumstances in excess of those addressed in this Section, no changes are required in the operational condition of the plant, and this does not prevent the plant from entry into an operational mode. ,
12-32
QUAD CITIES Revision 1.0 ' January 1994. (
\ 4 TABLE 12.4-1 !
+
PADIOACTIVE CASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM i
> l I
MITJIMUM LOWER LIMIT OF 'i G ASEOUS RELEASE SAMPhl!JG AIJALYSIS TYPE OF DETECTIO!J TYPE FREQUETJCY FREQUEtJCY ACTIVITY ANALYSIS (LLD) ' (i1Ci/ml)
- A. (1ain Chimney M M' Principal Gamma 1x10'*
- aeactor H1dg. Grab Sample Emitters' ent Stack
- M Tritium 1 x 10^' '
B. 11 Heleace Continuous (d) W" -I-131 1x10-22 ,
' / pen as List ed Charcoal !
n A Above Sample 3-133 1x10* Continuous (d) W' - Principal Gamma Particulate Emitters *~ 1x10-22 Sample (I-131, otherc). [ Continuous (d) 0 'SR-89 1 x10-" - lI Composite ~i Particulate SR-90
. Sample 1x10-31 Continuoun (d) M Gross Alpha 1x10-'2 -[
Composite 1 Particulate 7 I Sample- f C. Main Chimney Continuoun (d) IJoble Gas floble Gasen 1 x10-* Monitor f 1
~ i D. heactor B3dg. Continuous (d) 13oble Gas Noble Gaces mix 10- 8 l[
Vent Stack Monitor- [ T f 1 4 t I 12-33 t b
QUAD CITIES Revision 1.0 January 1994 O TA14LE 12. 4 -1 (Continued) TAPII t10 TAT 10!!
- a. The lower limit of detection (LLD) is defined in table notation A. of Table 12.5-3. a
- b. Sampling and analyc'en shall alco be performed following chutdown, atartup, or a thermal power change exceeding 20 percent of rated thermal power in I hour unleon (1) analynis shows that the DOSE EQUIVALEtTI' I-131 ,
concentration in the primary coolant has not increased more than a tactor of 5, and ( 2') the noble gas activity monitor shows that effluent activity has not increaced by more than a factor of 3. c S.imples shall be changed at least once pet 7 days and t he analysec completed within 48 hourt aftet removal from the sampler. Sampling chall also be performed within 24 hours following each chutdown, startup, or thermal power level change exceedina 20% of rated thermal power in one hour. This requirement does not apply if (1) analynia nhows that the DOSE EQUIVALE!IT I-131 concentration in the primary coolant han not increased more than a factor of 5, and (2) the noble gas activity monitor chows that effluent activity has not increased by more than a factor of 3. When samples collec ted f or 24 hours are analyzed, the correcponding LLD*c may be increased by a factor of 10.
- d. The ratio of cample flow rate to the campled stream flow rate chall be known.
e The principal gamma emitterc for which the LLD specification applies exclusively are the followin- 1 di .lidea: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 tor caseous emissions, and Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Co-234, Cc-137, Ce141, and Ce-144 for particulate emissions. Other peako which are measurable and identifiable by gamma ray spectrometry, together with the above nucliden, chall be also identified and reported when an actual analysis is performed on a sample. IJuclides which are below the LLD for the analysen shall not be repcrted an being present at the LLD level for that nuclide. O 12-34 l
* , I
- --\
-QUAD CITIES Revision 1.0
' January 1994
'l 12.4.C. CASEOUS EFFLUENTS BAMPS -!
')
- 1. Gasoous Effluents Dose l l
This specification is provided to ensure that the dose at the unrentricted area boundary from gaseous-etfluents from the units-on the ! site will be within the annual dose limits of 10CFR20. These limits ! provide reasonable assurance that radioactive material discharged in [ , gaseous effludpts will not result in the exposure of an individual-in i an unrestricte'd area to annual average concentrations exceeding the j limits specified in Appendix B, Table 2 of 10CFR20. The specified .. i release rate l'imits restrict, at all times, the corresponding gamma and. -i beta dose rates above background to an individual at or beyond the. ~1 unrestricted area boundary to less than or equal to 500 miem/ year to , the total body or to not less than or equal to 3000 mrem / year to the= ! skin. These release rate limits also restrict, at all' times, the a corresponding thyroid dose rate above background via the inhalation. ! pathway to not less than or equal to 1500 miem/ year. For purposes of ! calculating doses resulting from airborne releases the main chimney is . considered to be an elevated release poir' 'nd the reactor vent stack l is considered to be a mixed mode release ;. !
- 2. Done, Hoble Cases-i This specification in provided to implement the r equirements of ;
Sections'II.B. III.A and IV.A of Appendix I, 10 CFR Part 50. The. ~! himiting Condition-for Operation implements the guides set forth in ! Section II.B of Appendix I. The statements provide the required ; operating flexibility and at the same time implement the' guides set. ! forth in Section IV.A of Appendix I_to assure that the releases:of. radioactive naterial in gaseous effluents will bekept "as low as is. ;; reasonably achievable." The Surveillance Requirements implement the ! requirements in Section III.A of Appendix I that conformance with.the: f guides of Appendix I is to be shown by calculational procedures' based- , on models and data such that the actual exposure of an. individual -l through the appropriate pathways is unlikely to be substantially .; underestimated. The dose calculations established in the ODCM for. , calculating-the doses due to the actual release rates- of radioactive . i noble gases in gaseous effluents will be consistent with the ' methodology pr ovided in Regulatory Guide 1.109,. " Calculation of Annual ' Doses to Man from Routine Releases of Reactor Effluents-for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating- i Atmospheric Transport and Dispersion of Gaseous Effluents'in Routine , Releases from bight-Water Cooled Reactors", Revision.1, July 1977 .The. , ODCM equations provide for determining the air doses at the .; untestricted boundary based upon the historical average atmospheric' conditions. HUREG-0133 provides methods for done calculations - consistent with Regulatory Guides 1.109 and 1.111. < i
.L
.I 12-35 !
~;
I QUAD CITIES Revision 1.0 January 1994 i 12.4.C CA9FOUD FFFIMEt1TD HA9F9 (COf Q , 3. Done, Radiciodiner, Radioactive Material in Particulate Form and 4 Radionucliden other thar, noble Gases This specification is ptovided to implement the requiremento of a Cections II.C, III.A and IV.A ot' Appendix I, 10 CPR Part 50. The 1 Limiting Cond i',t i on s for Operation are the guiden set forth in ! Dection II .C of Appendix I. The statementa provide the required operating flexibility and at the same time implement the guiden set - t or th in Sect it>n IV.A of Appendix I to anaute that the teleases of
~
radioactive matetials in aaseous ef fluent a will be kept "as low as j it tranonable achievable." The ODCM calculational methods npecified in t he curveillance requiremento irnpl ernento the r equ i r ement o in Cection III.A of Appendix I that contornance with 'l ' the guiden of Appendix I be shown by calculational ptoceduren based on modeln and data cuch that the actual exposure of an individual l thr ough appr opriat e pathwayn ia unlikely to be substantially undereotimated. The ODCM calculational methodo anproved by NRC for i calculating the dones due t o the actual release r tes of the subject materials are required to be connistent with the methodology provided in Regulatory Guide 1.109, " Calculation of , Annual Doser, to Man f rom Routine Releaner of Reactor Effluentn for 'I the Purpone of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Eclimating Atmocpheric Transport and Dispernion of Caneous i Eftluenta in Routine Releaces from Light-Water-Cooled Reactors,a i Revision 1 July 1977. These equations alno provide for i det ermining the actual dones based upon the histcrical average ' atmocpheric conditions. The teleane rate specificationn for , radiciodines, radioactive material in particulate form and ..; radionucliden other than noble gasec are dependent on the exinting radionuclide pat hways t o man, in the unrestricted area. The , pathwayo which were examined in the development of these npeci f icat.iono wer e: 1) individual inhalation of airborne radionucliden, 2) deposition of radionuclides onto green leafy veget ation with cubsequent consumption by man and 3) deponition ont o gr acuy ar ean where milk animala graze with consumption of the J milk by man. , 4 b j ! ) 0 12-36 1
~- c-. - , . _ . . == ;_. - .- ...--- . . - .
if y.. a QUAD CITIES Revision 1.0 ,
, January 1994
- l f
IO 2 . 5' EfNIPONMENTAL'MOMITORIfiq 12.5.A' Environmontal Monitorina 12.5.H. Fnvironmental Monitorinc , Procram Survei11anco l
- 1. The environmental 1. The radiological environmental I monitoring program given in monitoring samples shall be .
Table 12.5--l nhall lie collected pursuant to Table ! conducted except as 12.5-1 fror the locations '! cpecified below. npecified in the ODCM, and j chall be analyzed pursuant to the requirements of Table ; 12.5-3. +
- 2. 'With the radiological 2. The results of analyses -{
environmental monitoring performed on radiological : program not being conducted envi rorunental monitoring . as specified in Table samples shall be summarized in 12.5-1, prepare and submit. the Annual Radiological < to the Commission, in the Environmental Operating Report. i Annual Radiological ! Operating Report,'a i descr iptiot, of the. reasons ; for not conducting the program as required and the l plana for preventing a I recurrence. Deviations are . permitted from the required sampling schedule'if' specimena are unobtainable due to hazardous - conditions, seasonal l unavailability., contractor ' C ominnion which is corrected - as noon as diccovered, i malfunction of nampling equipment, or if a person + who participaten in the program goen out of business. If the equipment malfunctions, corr ect ive actions chall be completed , as soon as practical. If a .i person supplying samples goes out of business, a ' replacernent will be found I as coon as poncible. All deviationn from the campling ochedule shall be dencIibed in the annual 'j teport. ' 4 A i
-I .
12.5.A Environmental Monitorina . Procram '- I
- 3. With the level of radioactivity in an environmental sampling medium at one or more of the 12-37
QUAD CITIES Revision 1.0 January 1994
*1 1
locationn npecified in the ODcM exceeding the limito 01. Table 12.5-2 when averaged over any calendar quarter, pr epare and n u t>mi t to the Comminsion within 30 daya f1om the end of the affected calendar quarter, a Special Report which includes an evaluation of any releand, I condit ionn, envi r onmental-factort or other aspects which cauced the limit: ot Table 12.5-2 to be exceed"d. Thin report in not required if the ineanu t ed level of radioactivity wan not the tenult of plant et t luent.s; however, in such an event the conditiori chall be reported and deceribed in.the Antiual Radiologica] Environmental Operating Report. s 4 12 . r. H. Environm"ntal Monitorirm
! Sirs 'i1]anco
- 3. The land une cennua chall be conducted at leant once per t welve months but ween t he dater of June 1 and October I by a doot-to-door survey, aetial curvey, toad survey, or by conr.ul t i ng local agriculture aut hot it ien I
i O 12-38
QUAD CITIES Revision 1.0 January 1994 i
. -l
\
N. I A Environmentnl Monitorina 12.5.B. Environmentnl Monitorina -l i Pr ocr am norveillance
- 4. With milk camplen unavailable 4. The results of the' land use -
irom one or more of the sample census shall be included in the l locations required by Table Annual Radiological l 12.5-1,-identify locations for Envit orunental Operating Report. ll
- _ obtaining replacement sarijples j and add them to the ladiological ;
environmental monitoring program i within 30 days. The l oca't l onu ; itom which-namplen were j i unavailable may then be deleted ' f rom the monit.oring pr ogram. In lieu of a Licennee. Event Heport, identify the cause of the- . '
.inavailability of samples and -l identify the new location (s) for !
obtaining replacement samples in .i the Annual Radiological l
, Envirotunental Operating r epor t l and also include in the report a !
revined figure (s) and table for l the ODCM reflecting the new l
^ 1ocation (n) . .!
5 .. A census of nearent residences of animalc producing milk for
'j human consumption.shall be 5. The tenults of the analyses ;
[ conducted annually (during the grhzing:ceacon for animalc) to performed as part. of.the required crosscheck program' -! l det er mine their location and chall be included in the' Annual 7 number with-tecpect to.the cite. Radiological Environmental i The neatent residence in each of Operating Report. The analyses-the 16 rnet eorological sector s chall be done in accordance nhall alco be determined within with Section 5.3.1 and Chapter a distance of five miles. The 11. cennus chall be conducted under -) the following conditionn i
- a. Within a 2-mile radius from I
, the plant site, enumeration j U of aninula and nearest l residences by a 'l door-to-door or equivalent ~
- counting technique.
{ 4 I- 12.5./- Envi ronmont al Monitorina 12.5.h. Environmontal Moni t orina ) ftparam nurvei11ance ~j i l- Within a 5-mile radiuc, i p . enumeration of animals by uning l- teferenced iniormatio'n from l county agricultural agento ot other reliable cources.
- J
( i) '. I th a land.une cennua identifying -l l I, cation (s) of animalc which 'l t 12-39 r 9 _ _ ~ - __ _ - J
)
QUAD CITIES Revision 1.0 January 1994 yield (c)an ODCM calculated dose or
-iane commitment greater t.han the ralues cutrently beina calculated n Specification 12.4.A.3, the new location (s) chall l>e added to the radiological environmental monitoring program with 30 days, if poucible. ,
The campling location, havihig the lowest calculated doce or done
,ammitment (via the same exposure , .at hway ) may be deleted from this lionitat ing pr ogt,un a f t"t October 31 the year in which thin land une cnnun war conducted.
- 7. mediological analysen shall be p+rformed on campleo repr esentative
, thone in Table 12.5-1, supplied
- 1. a part of the Interlaboratory
' mparicon I'roa r ion which han been
. proved by the IJRC .
- 8. 4 i t.h analyses not. being per-
.ogmed an 2equiIed, report the
( TrIective actions tWKen to pt.+ vent
. IecurIence to the CommiOpion in l *be Annual Radir as lical l 1snvi t onment'a1 ( per uting Pepot t . )
I
- 9. In the event a 1imit and/or accociated actionn requirements identified in Sections 12.5.A and l 12.5.B cannot be natisified because of ci r cumnt.ancen in execs of those
.3drecned in these Sectionn, no changen ar e required in the operational condition of the plant, und f hit doec not pievent the plant
'com entry int.o an opetational mode.
O 12-40
O.
. QUAD? CITIES ' Revision'1.0.-
January 1994: TABLE'12.5-1 RAD 101,0GICAL EfNIPOMMFiff'AL MnflT'I'OPIf1G " PROGRAM - 1
. Exposure Pathway Minimum Numbe of Samplec Sampling and Col- Type and Frequency anr1/n r namnlo an<1 gamnie Lodationn* 3ection Frenooney of Analvnin-
- 1. . AIRBORNE
- a. Particulaten 16 locations Continuous opera-' Gross beta and tion of sampler gamma Isotopic as !
for a week specified in ODCM.
- 'b. Radiciodine 16 locationn Continuous opera- 1-131 au speci-tion of sampler '
fied in ODCM. for two weeks !
- 2. DIPECT RADIATION Forty Locationc Quarterly '
(Minimum.of two TLDs per packet) 11
. 3. - WATERBORNE ;
- a. 'Public Water 2 bocations Monthly composite Gamma: Isotopic. 1f of weekly collec- analysis of each -?
ted samples composite sample'~ '
.. i
- b. . Sediment 1 downstream location Annually Gamma Isotopic ;
in receiving body of analynic.of each _'i water nample. "l
- c. Plant Cooling Intake, Discharge Weekly composite Grosa Beta analy-:
Water cis.of each sample .' !
- 4. If1GI.GTION .l
- a. Milk 2 Locations At least once I-131 analysis of weekly when ani- each sample- i animals are on 'l pasture; at least !
once per month at ' other times. .I r i
- b. Fish 1 location in receiv- Semi-annually Czunma Icotopic
~
ing body of water analysis on , edible portions .; i
- Sample locations are denctibed in the ODCM ;[
I 1 1 12-41 1
QUAD CITIES Revision 1.0 January 1994 TABLE 12.5-2 O j I REPORTIf10 I,FV FT.9 FOR RADIOACTIVITY COf frFf fTR ATinfl9 If f FfJVIROf P4Ff fTAI, 9 AM PI .FM I Reporting Levelc 3
]
i i Arm lyn , Water Ai r bo rn'e Particulate Fish ' Milk Food Producto or Gast4s ( pCi /m') (pCi/Kg, wet) (PCi/1) (PCi/Kg, wet) l 11 - 3 2x 10*(a) Mn-54 1 x 10' 3 x 10' Fe-59 4 x 10 2 1 x 10' 8 Co-58 1 x 10 3 x 10' Co-60 3 x 10 2 1 x 10' Zn-65 3 x 10 2 2 x 10' Z r - tJb - 9 '. 4 x 10 2 I-131 2 0.9 3 1 x 10 2 I Co-234 30 10 1 x 10' 60 1 x 10' l Co-137 50 20 1 x 10' 70 2 x 10 2 Ba -- 1,a - 14 0 2x 10 2 3 x 10 2 .s) for drinking wat er campleo. This is 40 CFR Part 141 value. O 12-42
s 4 { Revision 1 0 , QUAD CITIES . January 1994 ' TABLE 12.5-3 , PRACTICAL I,0WFR I,IMIT9 OF DRTErTION (Lf ,D) , FOR STANDARD EfMIROflMFilTAb RADIOLOGICAL MOTIITORITIC PROGRAM
? .; I 3
Sarnple Media Analysis LLDa.s . Units , t o . 66 02 . L t
' Airborne " Particulate" Gross Beta + 0.01 pCi/m3 i Gamma Icotopic 0.01' pCi/m' ,;
Airt rne I-131 Iodine 131 0.10 pCi/m' i t Milk /Public Water I-131 5 pCi/l Cs-134 10 pCi/l Cs-137 10 A pCi/1. i Tritium 200 pCi/1 ! Gross Beta + 5 . pCi/1 ; Gamma Isotopic 20 pCi/1/nuclide -j Sediment Gross Beta + 2 pCi/g' dry- -! Gamma Isotopic 0.2. .pCi/g dry ; ish Tissue I-131 Thyroid 0.1 pCi/g wet-Cs-134, 137 0.1 .pCi/g-wet- 3 Gross Beta + 1.0 pCi/g wet .: Gamma Isotopic 0.2- .pCi/g wet ! O.S pCi/l on milk samples collected during the pasture season, ,
-+ Referenced to Cs-137 ) t
.t .
A 5.0 pCi/l on milk samples
-1 I
=f 1
)
~
i 12-43 ! k3 5 I
- .. ~ , ,
4 QUAD CITIES Revision 1.0 January 1994 4 O TABLE 12.5-3 (Continued) PRACTICAL LOWER LIMITS OF DETECTION (LLD) FOR STANDARD ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM { TABLE NOTATION A. The LLD is the smallest concentration of radioactive material in the sample that will be detected with 95 percent probability with only 5% probability of falsely concluding that a blank observation represents a "real" sequal. For a particular measurement system (which may include radiochemical separation) 4.66.s r LLD = ------------------------------------------ A E V 2.22 Y exp (-A A t) t Where: ' LLD is the "a prioria lower limit of detection for a blank sample or background analysis as defined above (as pCi per unit mass or volume). so is the square root of the background count or of a blank cample count; is the estimated standard error of a background count or a blank sample count as appropriate (in units of counts). E is the counting efficiency (as counts per disintegrat.on). A is the number of gamma rays emitted per disintegration for gamma ray radionuclide analysis (A=1.0 for gross alpha and tritium measurements). V is the sample size (in units of mass or volume). 2.22 is the number of disintegrations per minute per picocurie. Y is the fractional radio-chemical yield when applicable (otherwise Y = 1.0) A is the radioactive decay constant for the particular radionuclide (in units of reciprocal minutes). At is the elapsed time between the midpoint of sample collection and the start time of counting. (At = 0.0 for environmental samples and for gross alpha measurements) ! I t is the duration of the count (in units of minutes). 1 12-44
. i
-~. .. .
' QUAD CITIES ~ Revision l.0 -
January 1994'- l i{
-( :
TABLE 12.5-3 (Continued)
-PRACTICAL LOWER LIMITS OF DETECTION.(LLD) .
FOR STANDARD EINIRONMENTAL RADIOLOGICAL MONITORING PROGRAM .
} TABLE NOTATION-
} .I The value-of.asu " used in the calculation-~of the LLD for a detection system shall be based on an-actual observed background:
count or a blank sample count (as appropriate) rather than on an unverified theoretically predicted value... Typical values (of "E",.
"V", "Y", "t", and!"At" shall be used in the calculation.
For gamma ray radionuclide analyses the background counts are .l- , determined from the total-counts in the channels which are within ' plus or minus one FWHM'(Full Width at Half Maximum)-of the gamma ray photopeak energy normally used for the quantitative analysis 3 ' for that radionuclide. Typical values.of the FWHM shall be'used in the calculation. The LLD for all measurements is defined as ans"A' priori":(before , the fact) limit. representing the capability of a' measurement system and not as an "a posteriori" (after the fact) limit for a. particular sample measurement. B. Other radionuclides which are measureable.and' identifiable by '
. gamma-ray spectrometry, together with the nuclides-indicated in-.
Table.12.-5-2, shall also be identified and' reported-when an actual ' l ..
-analysis is performed'on a sample. .Nuclides which are below the' LLD for the analyses.shall not.be-reported as being present at the. ,
LLD level for that nuclide.
=;
b a p 12-45 ! t l
QUAD CITIES Revision 1.0 January 1994 O 12.5.C RADIOLOGICAL ENVIPONMENT14.L MONITORING PROGRAM
- 1. Monitoring Program i
The radiologic 41 monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Program changes may be initiated based on operational experience. The detection capabilities required by Table 12.5-3 are state-of-the-art for routine environmental measurements in - industrial laboratories. The specified lower limits of detection for I-131 in water, milk and other food products correspond to approximately one-quarter of the Appendix I to 10 CFR Part 50 design objective dose-equivalent of 15 mrem / year for atmospheric releases and 10 mrem / year for liquid releases to the most sensitive organ and individual. They are based on the assumptions given in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", October 1977, except the change for an infant consuming 330 liter / year of drinking water instead of 510 liters / year.
- 2. Land Use Census This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.
- 3. Interlaboratory Comparison Program The requirement for participation in the interlaboratory comparison crosscheck program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
O 12-46
QUAD CITIES Revision 1.0L :
, January 1994
i a 12.6 RECORD KEEPING AND REPORTING i 12.6.1 Plant Operating Records l A. Records ahd/or logs relative to the following. items'shall. ) be kept in a manner convenient for review and shall be ; retained for at least 5 years:
- 1. Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance ,
requirements (see Section 6.4 of the Technical- . Specifications) are being met (all equipment failing 1 to meet surveillance requirements and the corrective action taken shall be recorded);
- 2. Records of radioactive shipments; !
B. Records and/or logs relative to the following items._shall be recorded in a manner convenient for review and shall i be retained for the life of the plant: j
- 1. Records of offsite environmental monitoring surveys;
- 2. Records of radioactivity in liquid and_ gaseous wastes released to the environment; .
- 4. Records of reviews performed-for changes made.to the r
.Offsite Dose Calculation Manual. [
12.6.2 Reports
- 1. Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted prior to April 1 of each - d year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents .
and solid waste released from the unit. The material ' provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with Ji 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
- 2. Annual Radiological Environmental Operating Report An annual report containing the data taken in the r standard radiological monitoring program (Table _12.5-1) ;
shall be submitted prior to May 1 of each year. The content of the report shall include: r 12-47 ; i
QUAD CITIES Revision 1.0
, January 1994
- a. Results of all environmental measurements summariced in the format of the Regulatory Guide 4.8 Table 1 (December 1975). (Individual sample results will be retained at the Station). In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explain 1ng the reasons for missing results. Summaries, interpretations, and analysis of trends of the results are to be provided.
- b. An assessment of the monitoring results and radiation dose via the principal pathways of exposure resulting from plant emissions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (ODCM).
- c. Results of the census to determine the locations of nearest residences and of nearby animals producing milk for human consumption (Table 12.5-1).
- d. The reason for the emission if the nearest dairy to the station is not in the monitoring program (Table 12.5-1).
- e. An annual summary of meteorological conditions concurrent with the releases of gaseous effluents in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.
- f. The results of the Interlaboratory Comparison Program described in Section 12.5.C.3.
- g. The results of the 40 CFR 190 uranium fuel cycle dose analysis for each calendar year.
- h. A summary of the monitoring program, including maps showing sampling locations and tables giving distance and direction of sampling locations from the Station.
- 3. If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting level given in Table 12.5-2 and if the radioactivity is attributable to plant operation, a written report shall be submitted to the Administrator of the NRC Regional Office, with a copy to the Director, Office of Nuclear Reactor Regulation, within 30 days from the end of the quarter.
O 12-48
A
. QUAD CITIESL FWvision 1.0 ;
January 1994
.x. 1
- a. When more than one of the radionuclides in' Table 12.5-2 !
are detected in the medium,Jthe reporting level shal'1 -i have been exceeded if , !
' l c_
1 2 1 :
. ! R.L. i ,
?
where Ci is the average quarterly concentration of the-i" radionuclide in the medium and RL is the reporting level of radionuclidefi.
- b. If radionuclides other than those in Table 12.5-2 are ,
detected and are due to plant effluents, a reporting ,, level is exceeded if the potential annual dose to an ! individual is equal to or greater than the design ; objective doses of 10 CFR 50, Appendix 1.
- c. This report shall include an evaluation offany release :l conditions, environmental factors, or other aspects !
necessary to explain the. anomalous effect.. . 12.6.2.3 OFFSITE DOSE CALCULATION MANUAL (ODCM) j 12.5.2.3.A. The OFFSITE DOSE CALCULATION MANUAL (ODCM) ~ shall contain the-methodology and parameters used in the- -i calculation.of offsite doses resulting.from. t radioactive gaseous and liquid effluents, in the
' - calculation of gaseous and liquid. effluent' j monitoring Alarm / Trip Setpoints, and in the conduct' !
of the Radiological Environmental Monitoring 7 Program. 'The ODCM shall also contain (1) the ~; Radioactive Effluent Controls and Radiological Environmental Monitoring Programs described in i section 12.5 and (2) descriptions of'.the.information- :{ that should be included in the Semi-annual , Radioactive Effluent Release Reports and in the j Annual Radiological Environmental Operating Reports ~ required by sections 12.6.2.1 and 12.6.2.2. ; 1 The ODCM shall be subject-to review and approval.by > the Commission prior to implementation. ! 12.6.2.3.B. Changes-to the ODCM l
^
- 1. Shall be documented and records of reviews performed i shall be retained as required by Specification i 6.5.B.14. This documentation shall.contain: .i
- a. Sufficient information to support the change !
together with the appropriate analyses or i evaluations justifying the change (s) and [ i i 12-49 ! I i c _ _ _ _ a
QUAD CITIES Revision 1.0 January 1994 - 4
- b. .A determination that the change will maintain the level of radioactive effluent control 1 required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
)
~
- 2. Shall become effective after review and acceptance by the Onsite Review and Investigative Function a i the approval of the Plant Manager on the date specified by the Onsite Review and Investigative Function.
- 3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of tne affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
12.6.2.4 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (LIQUID AND GASEOUS) A. Licensee initiated major changes to the radioactive waste systems may be made provided:
- 1. The change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by the -!
onsite review function. The discussion of each change shall contain:
- a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; 4
1
- b. Sufficient detailed information to support the reason 1 for the change; I
- c. A detailed description of the equipment, components, and process involved and the interfaces with other plant systems;
- d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and (or quantity of solid waste that differ from those previously predicted in the license I application and amendments); l I
O 12-50
. ~ . . - . . .- - .. ,~ - . ~. . -,.. ....-. --.. --- .. .. . - -~~ . .
n
. QUAD CITIES Revision 1.0
-January 1994
~l 9 ' e. A comparison of the predicted releases of radioactive'
~
1 I materials in-liquid and gaseous effluents and in solid. waste to the actual releases for the period in which .; l the changes were made; -1
- f. An estiinate of the exposure to plant operating l personn'le as a result of the change; and. ~
- g. Documentation of the fact that the' change was reviewed.
and found acceptable by the onsite review function. i i
- 2. The change shall become effective upon review and acceptance ~j i --
by onsite review function. ; 1 I i h
'I l
i c 8
)
.g l
0 ,
\
q I I f t
'l i
l l F. 12-51 j N--8+- -'-- r -___----_-er%rwe+me,,- --w.-,-ser.-ww. -mse-e- .,,%e- s a, nm ey .r9._.g _ _ , ,g,, _, y 7m ,_ ,g. y.. _i9_ . _ , ,y y
M 4 O P 1 7 O i i l l
- . s
. . . . 1 y QUAD CITIES Revision 1.0 January 1994 6
QUAD CITIES ANNEX INDEX PAGE REVISION PAGE REVISION APPENDIX F , F-1 1.0 . F-43 ~1.0 F-li 1.0 !* F-44 1.0 F-iii 1.0 F-45 1.0 F-iv 1.0' F-46 1.0 F-1 1.0 -F-47 1.0 F-2 1.0 F-48 1.0 F-3 1.0 F-49 1.0 F-4 1.O _{ F-5 1.0 F 1.0 , F-7. 1.0 F-8 1.0 -I F-9 ' 1.0 F-10 1.0 F-11 1.0 ^ F-12 1.0 F-13 1.0 > F-14 1.0 , F-15 1.0 F-16 1.0 F-17 1.0 F-18 1.0
'. F-19 1.0 1
'F-20 1.0 l F-21 1.0 F-22 1.0 .
.F-23 1.0
- F-24 1.0 F-25 1.0 F-26 1.0 l F-27 1.0 F-28 1.0 F-29 1.0 F-30 1.O I F-31 1.0 '
1 F-32 1.0 l F-33 1.O ! F-34 1.0 ' F-35 1.O i F-36 1.O ; F-37 1.0-F-38 1.0 ' F-39 1.0 F-40 1.0 F-41 1.0 F-42 1.0 i I l
'I '
F-1
-I. . t QUAD CITIES Revision 1.0 j January 1994 APPENDIX F STATION-SPECIFIC DATA FOR QUAD CITIES UNITS 1 and 2 TABLE OF CONTENTS 3 PAGE F.1 INTRODUCTION F-1 F.2 REFERENCES F-1 0-lI k 1 j l l F-il
. ~,. - -. . . . . . . -
.e
.' QUAD CITIES RevAsion 1.0 January 1994 j APPENDIX F l LIST OF TABLES :;
L NUMPER TITLE PAGE F-1 Aquatic Environment Dose Parameters F-2 -! y F-2 Station Characteristics F-3 l 1 !
~
F-3 Critical Ranges F-4 { F-4 Average Wind Speeds F-5 ! F-5 X/O and D/Q Maxima at or Beyond the-Unrestricted Area' Boundary F-6 l F-Sa X/Q and D/Q Maxima At or Beyond the Restricted Area Boundary {
-F-7 F-6 D/Q at the Nearest Milk Cow and Meat Aninal r Locations Within 5 Miles F-8 F-7 Maximum Offsite Finite Plume Gamma Dose Factors ;
Based on 1 cm Depth at the Unrestricted Area , Boundary for Selected Nuclides F-9
~!
F-7a Maximum offsite Finite Plume Gamma Dose Factors l Based on 1 cm Depth at the Restricted Area' i Boundary ior Selected Nuclides- F-24 1 F-8 Parameters for Calculation of N-16 [ Skyshine Radiation'from Quad Citier F-39' l t Supplemental Tables { l A Elevated Level Joint Frequency Distribution ; Table Summary - 296 Foot Elevation Data F-40 0
-Summary Table of Percent by Direction and-Class.
-Summary Tablegot Percent by Direction and Speed
-Summary Table of Percent by speed and Class B Mixed Mode Joint Frequency Distribution _ . !
' Table Summary - 196 Foot Elevation' Data -F-42 *
-Summary Table.of Percent by Direction and Class
-Summary Table of Percent by Direction and Speed
-summary Table of Percent by speed and Class C Ground Level Joint Frequency' Distribution .
ij Table Summary - 33 Foot Elevation Data. F-46 f
. j
-Summary Table of Percent by Direction'and Class .
~
-Summary Table of Percent by Direction and Speed !
-Summary Table'of' Percent by Speed and Class '!
l
\
4 F-iii 1
.i
e QUAD CITIES Revision 1.0 , January 1994 APPENDIX F LIST of FIGURES 170MPER g pAGE F-1 Unrestricted hrea Boundary F-48 F-2 Restricted Area Boundary F-49 I l O O F-iv
. , .- - . _ - - - u - .. . -. .
. t QUAD CITIES Revision 1.0
, January 1994 APPENDIX F STATION-SPECIFIC DATA FOR QUAD CITIES - <
UNITS 1 and 2 F.1 INTRODUCTION i i This appendix contains I data relevant to the Quad Cities site. Included i are a . diagram of the unrestricted area boundary and tables of values.of [ parameters used in offsite doce assessment. -2 t
.l F.2 REFERENCES I
- 1. Sargent & Lundy, Analysis and Technology Division, Quad Cities. .;
Calculation No. ATD-0148, Revision 1. , I
- 2. Sargent & Lundy, Nuclear Safeguards and Licensing Division, Quad cities Calculation No. QC-03-88, Revision 0. .-
j
- 3. Quad Cities Public Water Supply' letter from B.S. Ferguson.(NSEP) .f to G. Wassenhove U.S. Army Corps of Engineers, February 16, 1989.
i 4
- Verification of Environmental Parameters - used f or Commonwealth i Edison Company's Offsite Dose Calculations *, NUTECH Engineering l Group, 1992. !
- 5. " Verification of Environmental Parameters. used for Commonwealth i Edison Company's Of f site Dose Calculations", NUS Corporation,1988.
r
.+
- i I
;l
~
f f 4 d
.f i
. l l ' ?
~I I
j i l
~i F-1 !
l i
,_ _ - - . . . , - - , . ~ _ _
QUAD CITIES Revision 1.0 January 1994 Table F-1 Aquatic Environment Dose Parameters Goneral Inf om-w ien* Existence of irrigation not mentioned in Quad Cities Final Saf ety Analysis Report (FSAR), UFSAR, or Plant Design Analysis. Fecreation includes one! or more of the f ollowing: boating, water skiiing, swimming and sport f i shfing . The station liquid disenarge flows into the Mississippi River. Mississippi River Lock and Dam IJumber 14 is located between the station discharge and the E. Moline intake (see Figure 12 of the Quad Cities Unit 1 Plant Design Analysis, Volume II, and Figure 2.4.1 of the Quad Cities safety Analysis Report.) Water and Fich Inacct ion Paramet err Parameter" Value 1/ M* , 1/M' l.0 F', ets 5.75E4 F', cfs 5.75E4 t', hr- 24.0 t', hr' 8.0 Limits on Radioactivity in Unnrotected Outdoor Tanks Not Applicable (See Section A.2.4 of Appendix A)
- Quad Cities Updated Final Safety Analysis Report (USFAR) ,
updated through Amendment 5 (9-3-87) Section 1.5.2 and
- Cuad Cities Plant Design Analysis, Section 4.4 The parameters are defined in Section A.2.1 of Appendix A.
t' (hr) = 24 hr (all stations) f or the fish ingestion pathway t' .r ) = 8 hr (Distance to the nearest public potable water
,F. :e, E. Moline, is 16 miles; flow rate of 2 mph is assumed)
I 1 0' F-2 l
.. . - . ... . - - - . ... . ~. . _ ._- -
= ;
.- i QUAD CITIES Revision-1.0 January 1994 Table F-2
-{"' Station characteristics s
Station: Quad Cities Nucle'ar Power Station ! Location: Cordova, Illinois f Characteristics of Elevhted Release Point ' r
- 1) Release Height = 9'.49 4 m' 2) Diameter = 3.35 -m
- 3) Exit Speed = 16.0 m s'1' 4) Heat Content = _ER_kCal s'2" !
i t
?
Characteristics of Vent lack Release Point ! q
- 1) Release Height = 48.5 m* 2) Diameter = 2.74 m ,
- 2) Exit Speed = 14.8 ms -2*
Characteristics of Ground Level Release ! 1 )' Releas. Height = 0m 2). Building Factor (D) = 43_4 m'
?
l Meterological Data i r A 296- ft Tower is Located 1623 m 49" of Elevated. Release Point ;
-Tower Data Used in Calculations ;
Wind Speed and Differential l Release Point -Direction Tomnerature i Elevated 296 ft 296-331 ft Vent 196 ft 196-33 ft i Ground 33 ft 196-33 ft l
'Used in calculating the meteorological and dose factors'in f Tables F-5, F-6, and F7. See Sections B.3 through B.6 of ;
Appendix B. l f I v i F-3 i
QUAD CITIES Revision 1.0 January 1994 , Table F-3 Critical Ranges Unrestricted
- Area Restricted Nearest Nearest Dairy Farm Boundary
- Area Boundary Resident' Within 5 Miles" Direction Im) rm) fm) (m)
N 864 300 800 None NNE 1029 300 1200 None NE 1212 325 2000 None ENE 1307 1210 2000 None E 1170 1170 3600 None ESE 1170 1125 4000 4800 SE 1189 475 4000 None SSE 1422 475 1600 None S 1198 325 1200 None SSW 2140 325 4800 None SW 1372 250 4800 None WSW 823 200 3600 None W 713 200 3600 None WNW 713 200 3600 None NW 823 200 3600 None IUM 1481 200 2800 None Nearest land in unrestricted area. Used in calculating the O meteorological dose factors in Tatf s F-5 and F-7. See Sections B.3 through B.6 of Appendix B. 1992 annual survey by Teledyne Isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters. c 1992 annual milch animal census, by Teledyne Isotopes Midwest , Laboratories. Used in calculating the D/Q values in Table F-6. The distances are rounded to the nearest conservative 100 meters. A default value of 8000 meters is used when there are no dairies within 5 miles. a i F-4
QUAD CITIES Rev'ision 1.0- l January 1994 ; s Table F-4 Average Wind Speeds , Downwind Averace Wind heed (m/ rec)* i Direction Elevated Mixed Mode Ground Level N 6.9 3 5.0 2.6 NNE 6.2 4.6 2.8 NE 5. 3 , 3.7 2.4 ENE 6.0 4.4 2.8 5 i E 6.9 5.0 3. 2 I ESE~ 7.1 5.2 3.7 - SE 6.5 4.9 3.6 f SSE 5.7 4.5 3.5 t t i S 5.6 4.4 3.4 SSW 5.6 4.4 3.3 t SW 5.8 4.6 3.0 ; WSW 6.0 4.7 3.4 W -l 6.1 4.8 3.1 ; WNW 6.0 4.5 2.6 l NW 5.9 4.4 2.4 -l NNW 6.5 4.7 2.5
.i
" Based on Quad Cities site meteorological data January 1978 through December 1987 data for ground level and mixed mode release analysis and-1982-1987 data for elevated releases. Calculated in Reference l'of ..
Section F.2 using formulas in Section B.1.3 of Appendix B. "
?
l l 9 F-5
QUltD CITIES Revision 1.0 January 1994 Table F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary Downwind Elevated (Stack) Release Mixed Mode (vent) Release Ground Level Release Direction Radtus X/O Radius D/O Radius X/O D/O Radius ?/O D/O (meters) (sec/m**3) (meters) (1/m**2) (meters) (sec/m**3) (1/m**2) (meters) (sec/m**3) (1/m**2) N 4430. 1.344E-08 864. 9.642E-10 864. 3.427E-07 2.869E-09 864. 3.817E-06 1.105E-08 NNE . 40: 3. 1.703E-08 1020 1.407E-09 1029, 2.219E-07 3.049E-09 1029. 2.597E-06 1.052E-08 NE 4829. 1.287E-08 12- 7.Ot9E-tO 1212. 1.321E-07 1.299E-09 1212. -2.249E-06 6.701E-09 ENE 440). 1.091E-08 13b7. 6.723E-10 1367. 1.213E-07 1.319E-09 1367. 1.446E-06 4.806E-09 E 36CO. 1.513C-08 1170. 1.139E-09 1170. 2.215E-07 2.811E-09 1170. 2.212E-06 9.318E-09 ESE 36 >O 1 2 .12 6 E - 08 1170. 1.536E-09 1170. 2.332E-07 3.437E-09 1170. 2.094E-06 1.047E-08 SE 40:3. 1.758E-08 1189. 1.082E-09 1189. 1.439E-07 2.384E-09 1189. 1.255E-06 6.450E-09 SSE 2003. 1.259E-08 1422. 6.915E-10 1422, 8.279E-08 1.167E-09 1422. 6.885E-07 3.222E-09 5 4400. 1.OOSE-08 '1500. 4.437E-10 1198. 6.887E-08 9.516E-10 1198. 8.371E-07 3.350E-09 SSW 4400. 8.62tE-09 2140. 3.110E-10 2140. 5.104E-08 4.693E-10 2140. 4.296E-07 1.380E-09 SW 4400. 1.102E-08 1500. 4.856E-10 1372. 1.OO6E-07 1.116E-09 1372. 1.224E-06 3.856E-09 WSW 4400 1.123E-08 1500. 4.674E-10 823. 2.158E-07 2.298E-09 823. 2.96BE-OG 1.093E-08 W 4828. 1.139E-OB 1500. 4.704E-to 713. 3.445E-07 2.737E-09 713. 5.271E-OG 1.522E-08 WNW 4828. 9.486E-09 1500. 4.025E-10 713. 5.025E-07 2.816E-09 713. '.554E-06 1.788E-08 NW 4828, 9.752E-09 823. 5.475E-to 823. 2.981E-07 2.OO9E-09 823. 4.739E-06 1.144E-08 NNW 4400. 1.045E-08 1481. 6.126E-10 1481. 1.712E-07 1.202E-09 1481. 1.928E-06 4.543E-09 Quad Cities Site Meteorological Data 1/78 - 12/87 tiote: Based on Reference 2 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B. X/O is used for beta air, beta skin, and inhalation dose pathways. See Sections A.1.2, A.1.3, and A.1.4.2 of Appendix A. D/O is used for produce and leafy vegetable pathways. See section A.1.4 of Appendix A. Radius is the approximate distance from midpoint between gaseous effluent release points to location of highest X/Q or D/O at or beyond the unrestricted area boundary (UAB). F-6
~
QUAD /rIESL Revi s iOrt--/. O January 1994 Table F-Sa
.X/Q and D/Q Maxima at or Beyond the Restricted Area Boundary Elevated (Stack) Release Mixed Mode (vent) Release Gr rr'd ! ( w: .< 1 Release Downwind A/d D/O Direction Radius x/O Radius D/O Radius X/O . D/O Radius (meters) (sec/m**3) (meters) (1/m**2) (meters) (sec/m**3) (1/m**2) (meters) (sec/m**3) (1/m**2) -
2.220E %5 5.676E-08 . N 4400. 1.344E-08 420. 1.244E-09 300. -1.824E-06 9.651E.09 300. 2.173E-08 420. 2.103E-09 300. 1.278E-06 1.163E-08 300. 1.864E-05 7.192E-08 NNE 480. NE 4828, 1.287E-08 420. 1.OO6E-09 325. 7.600E-07 5.329E-09 325, 1.805E-05 5.345E-08 4400. -1.091E'08 1210. 6.945E-10 1210. 1.346E-07 1.516E-09 1210. 1.741E-06 5.907E-09 *
- ENE 3600. 1.513E-08 1170. 1.139E-09 1170. 2.215E-07 2.811E-09 1170. 2.212E-06 9.318E-09 E
36DO. 2.126E-09 1125. 1.557E-09 1125. 2.417E-07 3.600E-09 1125. 2.223E-06 1.118E-08 ESE SE 4023. 1.758E-OB 475. 1.434E-09 475. 4.201E-07 6.339E-09 475. 5.067E-OE 2.813E-08 1.259E 08 475. 9.120E-10 475. 2.659E-07 3.632E*O9 475. 3.727E-06 1.901E-08 SSE 4023. 5 4400. 1.OOSE-08 1500. 4.437E-10 325. 3.596E-07 3.512E-09 325. 6.585E-06 2.620E-08 8 m21E-09 420. 4.OO4E-10 325. 4.288E-07 3.838E-09 325. 8.119E-06 2.902E-08 SSW 4400. 4400. 1.102E-08 1500. 4.85GE-10 250. 1.028E-06 6.593E-09 250. 1.950E-05 5.556E-08
- SW WSW 4400. 1.123E-08 1500. 4.674E-10 200. 2.040E-06 1.182E-08 200. 3.239E-05 9.263E-08 W 4828, .1.139E-08 1500. 4.704E-10 200. 2 886E-06 1.260E-08 200. 4.733E-05 1.025E-07 WNW 4828. 9.486E-09 420. 4.079E-10 200. 4.445E-06 1.331E-08 200. 6.984E-05 1.203E-07 NW 4828.' 9.752E-09 420. 6.595E-10 200. 3.175E-06 1.065E-08 200. 5.467E-05 9.706E-08 NNW 4400. 1.045E-08 420. 1.027E-09 200. 3.784E-06 1.367E-08 200. 5.47GE-05 1.023E-07 i
Quad Cities Site Meteorological Data 1/78 12/87 7 1 F-7 1 b__.___m-_.u__Lamm___. __._A________m_ . - ' mwn- ..-v. c . Lwr -ym-e- y-. .y,.g .i.ee w t- .,a f4 . .**PW W=g'*1'- '=rr'-MeiT- ?- P'*M.. *4r.9 '
'--@T+W=*.'@ Tm *E *'
u e rP $ gF- p,1'h ew-ms.'
CUAD CITIES Revision 1.0 Januarv ? " ' Table F-6 D/O at the Nearest Hilk Cow and Meat Animal Locations within 5 miles Dowwind Nearest Milk Cow D/Q(1/eP*2) Wearest Meat Animet D/Q(1/m"2) Direction Radius Elevated Mixed Radius Elevated Mixed (meters) Release Release (meters) Release Release N 5000. 1.019E-10 1.079E-10 6400. 1.455E-10 1.572E-10 l NNE 8000. 1.354E-10 1.475E-10 5600, 2.357E-10 2.662E-10 NE 8000. 9.339E 119.377E-11 4800. 2.004E-10 2.134E-10 . .-- ENE 8000. 9.066E 11 9.792E-11 4800. 1.946E-10 2.262E-10 E 8000. 1.364E-10 1.620E-10 4800. 2.934E-10 3.775E 10 ESE 4800. 4.243E-10 4.692E-10 2800. 7.722E-10 1.080E-09 SE 8000. 1.542E-10 1.454E-10 7600. 1.680E-10 1.587E-10 SSE 8000. 1.026E*10 9.303E-11 4400. 2.451E-10 2.454E-10 5 8000. 7.650E-11 6.524E 11 '2400. 3.247E-10 4.141E-10 ssu 8000. 6.616E-11 6.303E-11 8000. 6.616E-11 6.303E-11 su 8000. 8.419E-11 8.742E-11 2800. 3.124E-10 4.479E-10 WsW 8000. 8.454E-11 1.002E-10 5600. 1.467E-10 1.814E-10 W 8000. 8.206E 11 9.545E 11 3600. 2.429E 10 3.461E-10 WWW 8000. 6.761E-11 8.718E-11 5600. 1.173E-10 1.585E-10 NW 8000. 7.046E-11 7.767E-11 6400. 1.007E-10 1.1312-10 NNW 8000. 7.938E 11 9.082E 11 3600. 2.444E 10 3.316E-10 ouAD CITIES SliE METEOROLOGICAL DATA 1/78 - 12/87 i Note: Based on Reference 2 of Section F.2 and the formulas in Section B.4 l 'f Appendix'B. F-8 9 0 -- __
- 0. -
n p - - 1 QUAD 'IES Revisior$%'. 0 January: 1994 Table F-7 Maximum Offsite Finite Plume. Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-83m i Downwind unrestricted Elevated (Stack ) Release Mixed Mode (vent) Release Ground 1evel Release Direction Area Bound Radtus S SBAR Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) , N 864. 864. 1.193E-06 8.998E-07 864. 4'.094E-05 3.087E-05 864. - '378iEE-04 2.929E-04 NNE 1029. 1029. 1.785E-06 1.346E-06 1029. 2.796E-OS 2.108E-05 1029. 2.651E-04 1.999E-04 NE 1212. 1212. 9.747E-07 7.349E-07 1212. 1.639E-05 1.236E-05 1212. 2.162E-04 1.630E-04 ENE 1367. 1367. 9.035E-07 6.812E-07 1367. 1.409E-05 1.063E-05 1367. 1.373E-04 1.036E-04 E 11,70. 1170. 1.378E-06 1.039E-06 1170. 2.602E-05 t.962E-05 1170. 2.220E-04 1.674E-04 E5E 1170. 1170. 1.775E-06 1.338E-06 1170. 2.752E-05 2.075E-05 1170. 2.113E-04 1.593E-04 SE 1189. 1189. 1.286E-06 9.695E-07 1189. 1.748E-05 1.318E-05 1189. 1.24SE-04 9.407E-05 SSE 1422. 1422. 9.303E-07 7.014E-07 1422, 9.663E-06 7.286E-06 1422. 6.648E-05 5.012E-05 5 1198. 1198. 4.932E-07 3.719E-07 1198. 8.591E-06 6.478E-06 1198. 8.157E-05 6 150E-05 SSW !140. 2140. 6.664E-07 5.025E-07 2140 5.469E-06 4.124E-06 2140. 3.670E-05 2.767E-05 SW 1372. 1372. 6.134E-07 4.625E-07 1372.. 1.175E-05 8.862E-06 1372. 1.164E-04 8.775E-05 WSW 823. 823. 4.376E-07 3.3OOE-07 823. 2.665E-05 2.010E-05 823. 3.016E-04 2.274E-04 W 713. 713. 4.936E-07 3.722E-07 713. 4.059E-05 3.060E-05 713. 5.263E-04 3.968E-04 WNW 713, 713. 4.839E-07 3.648E-07 713. 5.484E-05 4.135E-05 713. 7.361E-04 5.550E-04 NW '823. 823. 8.023E-07 6.049E-07 823. 3.493E-05 2.634E-05 823. 4.707E-04 3.549E-04 NNW 1481. 1481. 9.575E-07 7.22OE-07 1481. 1.950E-05 1.470E-05 1481. 1.814E-04 1.368E-04 Quad Cities Site Meteorological Data 1/78 - 12/87 t Note: Based on' References 1 and 2 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B. F-9
. _ _ . . _ , . _.,._.__:.. - . . . -- _ .. - . ,. - . . - . . . . . . . _ _ _ _ _ = _ _ _ _ _ . _ _ _ _ _ _
QUAD CITIES Revision 1.0 Janumy 1994 Table F-7 (Continued) Maximum Of fsite Finite Plume Ganur.a Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85m Downwind unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uCi/sec) , N 864. 864 1.266E-04 1.225E-04 864. 4.908E-04 4.728E-04 864.' 7'.689E-03 2 OOOE-03 NNE 1029. 1029. 1.322E-04 1.278E-04 1029. 4.358E-04 4.204E-04 1029, 1.591E-03 1.525E-03 NE 1212. 4212. 8.448E-05 8.172E-05 1212. 2.793E-04 2.694E-04 1212. 1.3R9E-03 1.326E-03 ENE 1367. 1367. 5.783E-05 5.593E-05 1367. 2.056E-04 1.983E-04 1367. 9.a49E-04 8.872E-04 E 1170. 1170. 8.118E-05 7.850E-05 1170. 3.308E-04 3.187E-04 1170. 1.393E-03 1.336E-03 ESE 1170. 1170. 1.067E-04 1.032E-04 1170, 3.662E-04 3.530E-04 1170. 1.337E-03 1.282E-03 SE 1189. 1189. 9.118E-05 8.82OE-05 1189. 2.618E-04 2.525E-04 1189. 8.091E-04 7.760E-04 SSE 1422. 1422. 5.797E-05 5.606E-05 1422. 1.518E-04 1.464E-04 1422. 4.523E-04 4.340E-04 5 1198. 1198. 5.611E-05 5.428E-05 1198. 1.469E-04 1.417E-04 1198. 5.192E-04 4.978E-04 , SSW 2140. 2140. 3.024E-05 2.924E-05 2140. 7.862E-05 7.579E-05 2140. 2.775E-04 2.663E-04 i SW 1372. 1372. 5.402E-05 5.226E-05 1372. 1.697E-04 1.63SE-04 1372. 7.514E-04 7.204E-04 l WSW 823, 823. 8.767E-05 E.484E-05 823. 3.499E-04 3.372E-04 823. 1.633E-03 1.564E-03 W 713. 713. 1.112E-04 1.076E-t4 713, 4.644E-04 4.473E-04 713. 2.573E-03 2.461E-03 l l WNW '713. 713. 1.OOOE-04 9.678E-05 713, 5.046E-04 4.854E-04 713. 3.454E-03 3.302E-03 l NW 823. 823. 9.794E-05 9.476E-05 823. 3.993E-04 3.846E-04 823. 2.406E-03 2.302E-03 NNW 1481. 1481. 6.223E-05 6.018E-05 1481. 2.449E-04 2.360E-04 1481 1.147E-03 1.099E-03 Quad Cities Site Meteorological Data 1/78 - 12/87 o 4 e- _
I QUAD IES 'RevisiOrt . 0 January.1994s Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area' Boundary. for Kr-85 ' s
't' Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent). Release Ground Level Release ^
Direction Area Bound Radius S SBAR Radius .V VBAR Radius G GBAR -
- (meters) (meters) (mrad /yr)/(uCt/sec) ( rneters ) (farad /yr)/(uCt/sec) ( enet ers ) (mrad /Vf')/(uC t /sec )
, i N 864-. 864. 1.753E-06 1.695E-06' 864. 5.814E-06 5.622E-06 864. 2.347E-05 2.269E-05 NNE 1029. 1029. 1.834E-06 f.773E-06 1029. 5.237E-06 5.064E-06 1029. 1.792E-05 1.733E-05 NE 1212. 1212. 1.185E-06.1.146E-06 1212. 3.399E-06 3.287E-06 1212. 1.595E-05 1.542E-05 ENE 1367. 1367. 8 083E-07 7.817E-07 1367. 2.473E-06 2.391E-06 1367. 1.072E-05 1.037E-05 E 1170. 1170. 1.116E-06 1.079E-06 1170. 3.908E-06 3.779E-06 1170. 1.578E-05 1.525E-05 ESE " 1170. 1170. 1.46tE-06 1.413E-06 1170. 4.335E-06 4.192E-06 1170. 1.510E-05 1.460E-OS ,
SE. 1189. 1189. 1.259E*06 1.217E-06 1189. 3.118E-06 3.015E-06 1'39. 9.186E-06 8.883E-06 SSE' 1422. .1422. 8.057E-07 7.791E-07 1422. 1.829E-06 1.769E-06 1422. 5.211E-06 5.039E-06 5 1198. 1198. 7.916E-07 7.655E-07 1198. 1.774E-06 1.716E-06 1198. 5.956E-04 5.760E-06 SSW 2140. 2140. 4.230E-07 4.090E-07 2140. 9.632E-07 9.314E-07 2140. 3.375E-06 3.264E-06 SW 1372. 1372. 7.572E-07 7.322E-07 1372. 2.039E-06 1.97tE-06 1372. 8.743E-06 8.454E-06 l WSW 823. 823, 1.239E-06 1.198E-06 823. 4.157E-06 4.020E-06 823. 1.828E-05 1.768E-05 W -713. 713-. 1.570E-06 1.519E-06 713. 5.481E-06 5.3OOE-06 713. 2.847E-05 2.753E-05 WNW 713. 713. 1. 414 E -06 1.367E-06 713. 5.906E-06 5.711E-06 713. 3.816E-05 3.690E-05 NW 823. 823. 1.372E-06 1.327E-06 823. 4.734E-06 4.578E-06 823. 2.700E-OS 2.610E-05 , NNW 1481. 1481. 8.575E-07 8.292E-07 1481. 2.93fE-06 2.834E-06 1481. 1.350E-05 1.305E-05 Quad Cities Site Meteorological Data'1/78.- 12/87 F-11
-6mi_mu +9+-- J___'- m1-a er -* Item 4+h1Ex+-W stra-e me y m -1me.-.+,4 %'- 4mrg i*1re- iu.e%ts4-..'--w*4 -"'7= .Iw- 6 .mw .T- --
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QUAD CITIES Revision 1.0 Janu ry 1994 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius 5 SBAR Radius V VBAR Radius G G8AR (meters) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uC1/sec) N 864. 864. 6.162E-04 5.987E-04 864. f.698E-03 1.649E-03 864. 5.808E-03 5.639E-03 NNE 1029; 1029. 6.389E-04 6.207E-04 1029. 1.557E-03 1.512E-03 1029. 4.508E-03 4.377E-03 NE 1212. 1212. 4.118E-04 4.OO1E-04 1212. 9.907E-04 9.622E-04 1212. 3.742E-03 3.633E-03 ENE 1367. 1367. 2.753E-04 2.675E-04 1367. 7.128E-04 6.923E-04 1367. 2.504E-03 2.432E-03 E 1170. 1170. 3.853E-04 3.743E-04 1170. 1.146E-03 1.l13E-03 1170. 3.929E-03 3.815E-03 ESE 1S70. 1170. 5.023E-04 4.880E-04 1170. 1.270E-03 1.234E-03 1170. 3.806E-03 3.695E-03 SE 1189. 1189. 4.324E-04 4.201E-04 1189. 9.253E-04 8.936E-04 1189. 2.291E-03 2.225E-03 SSE 1422. 1422. 2.723E-04 2.646E-04 1422. 5.290E-04 5.'37E-04 1422. 1.256E-03 1.220E-03 S 1198. 1198. 2.704E-04 2.628E-04 1198. 5.202E-04 5.052E-04 1198. 1.424E-03 1.383E-03 SSW 2140.- 2140. 1.354E-04 1.315E-04 2140, 2.615E-04 2 540E-04 2140. 7.068E-04 6.863E-04 SW 1372. 1372. 2.581E-04 2.507E-04 1372. 5.872E-04 5.702E-04 1372. 2.OO1E-03 1.943E-03 WSW 823, 823. 4.379E-04 4.255E-04 823. 1.238E-03 1.202E-03 823. 4.588E-03 4.454E-03 W 713. 713. 5.602E-04 5.443E-04 713. 1.632E-03 1.585E-03 713. 7.313E-03 7.101E-03 WNW 713. 713. 5.039E-04 4.896E-04 713. 1.129E-03 1.679E-03 713. 9.810E-03 9.52bE-03 NW 823. 823. 4.859E-04 4.721E-04 823. 1.388E-03 1.348E-03 823. 6.654E-03 6.461E-03 NNW 1481. 1481. 2.903E-04 2.820E-04 1481. 8.192E-Of 7.955E-04 1481. 2.955E-03 2.869E-03 Quad C1ttes Site Meteorological Data 1/78 - 12/87 P-12 O O O . g ,-e-
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QUAD CITIES Revision 1.0 J ruary 1904 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-89 Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) N 864. 864. 7.300E-04 7.172E-04 864. 1'.425E-03 1.385E-03 864. 2.0 -03 1.976E-03 NNE 1029. 1029. 6.261E-04 6.085E-04 1029. 1.149E-03 1.116E-03 1029. 1.603E-03 1.557E-03 NE 1212. 1212. 3.167E-04 3.078E-04 1212. 5.081E-04 4.936E-04 1212. 7.823E-04 7.598E-04 ENE 1367. 1367. 2.047E-04 1.989E-04 1367. 3.701E-04 3.595E-04 1367. 5.059E-04 4.914E-04 E 1170. 1170. 3.698E-04 3.594E-04 1170. 8.126E-04 7.894E-04 1170. 1.310E-03 1.273E-03 ESE 1170. 1170. 5.046E-04 4.904E-04 1170. 9.740E-04 9.462E-04 1170. 1.566E-03 1.522E-03 SE 1189. 1189. 4.116E-04 4.OOOE-04 1189. 6.659E-04 6.469E-04 1189. 9.264E-04 8.998E-04 SSE 1422. 1422. 2.OO3E-04 1.946E-04 1422. 2.810E-04 2.730E-04 1422. 3.822E-04 3.712E-04 5 1198. 1198. 2.189E-04 2.127E-04 1198. 3.175E-04 3.084E-04 1198. 4.622E-04 4.490E-04 SSW 2140. 2140. 5.751E-05 5.588E-05 2140. 7.519E-05 7.304E-05 2140. 8.761E-05 8.510E-05 SW 1372. 1372. 1.914E-04 1.860E-04 1372. 3.241E-04 3.149E-04 1372. 4.441E-04 4.313E-04 WSW 823. 823. 4.790E-04 4.655E-04 823. 1.113E-03 1.081E-03 823. 2.203E-03 2.140E-03 W 713. 713. 6.760E-04 6.569E-04 713. 1.569E-03 1.524E-03 713. 3.460E-03 3.361E-03 WNW 713. 713. 6.075E-04 5.904E-04 713. 1.513E-03 1.470E-03 713. 4.161E-03 4.041E-03 NW 823. 823. 5.447E-04 5.293E-04 823. 1.114E-03 1.082E-03 823. 2.198E-03 2.135E-03 NNW 1481. 1481. 2.270E-04 2.206E-04 1481. 3.806E-04 3.697E-04 1481. 3.958E-04 3.844E-04 Quad C1ttes Site Meteorological Data 1/78 - 12/87 F-14
L ~ . . ; .. - QUAD ~1 IES Revisicr'i 0: January 1994. Table F-7 (Continued)
- Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted' Area Boundary-for Kr-90 Downwind Unrestricted ' Elevated (Stack) Release Mixed' Mode (Vent) Release Ground Level Release Direction Area' Bound Radius S 58AR Radius V VBAR . , G. GBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) (meters) Radius ,,(mrad /yr)/(OC1/sec)
~
N ., 864. 864. 1.025E-04 9.947E-05 864. 1'. OO 1 E -04 9.715E-05 864. 3.226E-05 3.128E-05 NNE- 1029. 1029. 4.953E-05 4.807E-OS 1029. 4.309E-05 4.181E-OS 1029. 1.549E-OS 1.502E-05 NE 1212. 1212. 1.210E-05 1.174E-05 1212. 7.167E-06 6.953E-06 1212. 2.958E-06 2.869E-06 ENE 1367. 1367. 8.572E-OG 8.320E-06 1367. 7.121E-06 6.908E-06 1367. 3.357E-06 3.255E*06 . E 1170. 1170. '2.876E-05 2.792E-05 1170. 3.061E-05 2.970E-05 1170. 1.687E-05 1.636E-05 ESE- it70. 1170. 4.141E-05 4.019E-05 1170. 3.846E-05 3.731E-OS 1170. 2.748E-05 2.665E-05 SE 1189. 1189. 2.685E-05 2.606E-05 1189. 2.120E-05 2.056E-05 1189. 1.306E-05 1.267E SSE 1422 1422. 5.661E-06 5.494E-06 1422. 4.092E-06 3.970E-06 .1422. 2.460E-06 2.385E-06 S 1198. 1198. 9.811E-06 9.523E-06 1198. 7.891E-06 7.656E-06 1198. 6.776E-06 6.571E-06 SSW 2140. 2140. 5.194E-07 5.040E-07 2140. 2.996E-07 2.907E-07 2140. 1.827E-07 1.772E-07 SW 1372. 1372. 6.788E-06 6.588E 1372. 6.147E-06 5.963E-06' 1372. 3.347E-06 3.246E-06 WSW. '823. 823. 5.697E-05 5.530E-05 823. 8.167E-05 7.923E-05 823. 8.406E-05 8.151E-05' W 713, 713. 't.054E-04 1.023E-04 713. 1.550E-04 1.504E-04 713. 1.486E-04 1.441E-04 WNW 713. 713. 9.367E-05 9.092E-05 713. 1.286E-04 1.247E-04 713. 1.211E-04 1.174E-04 NW 823. 823. 6.316E-05 6.131E-05 -823. 6.467E-05 6.275E-05 823. 3.606E-05 3.497E-OS NNW 1481 1481. 8.234E-06 7.992E-06 1481. 6.106E-06 5.924E-06 1481. 1.127E-06 1.093E-06 Ouad C1ttes Site Meteorological Oata 1/78 - 12/87 F , e r n_...r, _ . _ . . _ . r._ ei- e y, -- - c-. ..-.n :_-. y e= w .e..k. -~a m .-. .. _ _ _ _ _ - . . _ _ _ _ . _ _ _ . _ _ _ . _ .
QUAD CITIES Revision 1.0 January 1c94 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-131m Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uCt/sec) (meters) (mrad /yr)/(uCl/sec) N 864 864. 3.647E-06 3.327E-06 864. 4'.407E-05 3.544E-05 864. ~3.8'3'4I-04 2.9850-04 NNE 1029. 1029 4.237E-06 3.798E-OG 1029. 3.179E-05 2.595E-05 1029. 2.633E-04 2.057E-04 NE 1212. 1212. 2.587E-06 2.338E-06 1212. 1.947E-05 1.596E-05 1212. 2.279E-04 1.782E-04 ENE 1367. 1367. 1.965E-06 1.747E-06 1367. 1.6u2E-05 1.302E-05 1367. 1.466E-04 1.149E-04 E 1170. 1170. 2.839E-06 2.511E-06 1170. 2.808E-05 2.266E-05 1170. 2.237E-04 1.750E-04 ESE t t70. 1170. 3.680E-06 3.262E-06 1170. 2.997E-05 2.426E-05 1170. 2.118E-04 1.657E-04 SE 1189. 1189. 2.967E-06 2.654E-06 1189. 1.963E-05 1.599E-05 1189. 1.267E-04 9.918E-05 SSE 1422, 1422. 1.993E-06 1.769E-06 1422. 1.114E-05 9.095E-06 1422. 6.993E-05 5.482E-05 5 1198. 1198. 1.599E-06 1.463E-06 1198. 1.013E-05 8.309E-06 1198. 8.492E-05 6.642E-05 SSW 2140. 2140. 1.206E-06 1.050E-06 2140. 6.337E-06 5.144E-06 2140. 4.359E-05 3.422E-05 SW 1372. 1372. 1.650E-06 1.493E-06 1372. 1.332E-05 1.082E-05 1372. 1.252E-04 9.792E-05 WSW 823. 823. 2.220E-06 2.075E-06 823. 2.888E-05 2.335E-05 823. 2.959E-04 2.304E-04 W 713. 713. 2.761E-06 2.589E-06 713. 4.243E-05 3.407E-05 713. 4.991E-04 3.877E-04 WNW 713. 713. 2.521E-OG 2.357E-06 713. 5.524E-05 4.391E-05 713. 6.941E-04 5.386E-04 NW 823. 823. 2.732E-06 2.507E-06 823. 3.710E-05 2.977E-05 823. 4.622E-04 3.593E-04 NNW 1481. 1481. 2.099E-06 1.868E-06 1481, 2.184E-OS 1.759E-05 1481. 1.999E-04 1.561E-04 Quad Cities Site Meteorological Data 1/78 - 12/87 F-16 O O O .
QUAD. < IES- Revisiotx~4.0 January ~1994 T Table F-7 (Continued) .
' Maximum Offsite Finite' Plume Gamma Dose Factors Based.on 1 cm Depth at the Unrestricted Area Boundary' '
for Xe-133m t Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Reisase
'S~ 58AR Radius V VBAR Radius ,G _ G8AR Direction Area Bound Radius ,
(meters) (meters) (mrad /yr)/(uC1/sec) (me ters ) ' ( mrad / yr )/ (uC 1/sec) (meters) (mrad /yr)/(uC1/sec) N 864. 864. 1.894E-05 1.812E-05 864. I'.039E-04 9.3OSE-05 864. 6.441E-04 5.482E-04 NNE 1029. 1029. 2.025E-05 1 928E-05 1029. 8.483E-05'7.710E-05 1029. 4.614E-04 3.957E-04 NE 1212. 1212. 1.285E-05 1.226E-05 1212. 5.369E-05 4.897E-OS 1212. 4.033E-04 3.465E-04
-ENE 1367. 1367. 9.011E-06 8.562E-06 1367. 4.123E-05 3.733E-05 1367. 2 642E-04 2.277E-04
. E 1170. 1170. 1.267E-05 1.202E-05 1170. 6.835E-05 6.147E-05 1170. 3.977E-04 3.419E-04 - ESE 1170. 1170. 1.660E-05 1.576E-05 1170. 7.460E-05 6.727E-05 1170. 3.783E-04 3.255E , SE 1189. 1189. 1. 4 02 E -05 1.334E-05 1189. 5.149E-05 4.671E-05'. 1189. 2.278E-04 1.962E-04 SSE 1422. 1422. 9.051E-06 8.594E-06 1422. 2.975E-05 2.704E-05 1422. 1.270E-04 1.096E-04 , S 1198. 1198. 8.431E-06 8.074E-06 1198. 2.808E-OS 2.563E-05 1198. 1.505E-04 1.293E-04 SSW 2140. 2140. 4.938E-06-4.65BE-06 2140. 1.613E-05 1.459E-05 '2140. 8.011E-05 6.932E-05 SW 1372. 1372. 8,224E-06 7.852E-06 1372. 3.413E-05 3.088E-05 1372. 2.212E-04't.900E-04 WSW 823. -823. 1.283E-05 1.234E-05 823. 7.137E-05 6.430E-05 823. 4.990E-04 4.250E-04 W' 713. 713. 1.619E-05 1.558E-05 713. 9.876E-05 8.833E-05 713. 8.170E-04 6.918E-04 WNW 713, 713. 't.461E-05 1.405E-05 713. 1.166E-04 1.029E-04 713. 1.121E-03 9.4ESE-04 NW 823. 823. 1.457E-05 1.396E-05 823. 8.573E-05 7.661E-05 823. 7.625E-04 6.468E-04 NNW 1481. 1481. 9.664E-06 9.184E-06 1481. 5.202E-05 4.667E-05 1481. 3.480E-04 2.982E-04 Ouad C1ttes Site Meteorological Data 1/78 - 12/87 f F-17
. ._ . . ~ . _ , . . . _ _ _ - . . . . - _ _. . _ _ _
QUAD CITIES Revision 1.0 Jan'lary 1991 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133 Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius 5 58AR Radius V VBAR Radius G G8AR * (meters) (meters) (mrad /vr)/(uC1/sec) (meters) (mrad /yr)/(uCi/sec) (meters) (mrad /yc)/(uC1/sec) N 864. 864 1.741E-05 1.678E-05 864. f.161E-04 1.068E-04 864. 7.126E-04 6.308E-04 NNE 1029. 1029, 1.886E-05 1.810E-05 1029. 9.493E-05 8.825E-05 1029. 5.171E-04 4.609E-04 NE 1212. 1212. 1.186E-05 1.140E-05 1212. 5.974E-05 5.567E-05 1212. 4.541E-04 4.054E ENE 1367. 1367. 8.561E-06 8.203E-06 1367. 4.602E-05 4.266E-05 1367. 2.989E-04 2.675E-04 E 1170. 1170. 1.214E-05 1.162E-05 1170. 7.658E-05 7.065E-05 1170. 4.478E-04 4.OOOE-04
- ESE 1170. 1170. 1.606E-05 1.538E-05 1170. 8.356E-05 7.724E-05 1170. 4.264E-04 3.81tE-04 SE 1189. 1189. 1 340E-05 1.286E-05 1189. 5.757E-05 5.344E-OS 1189. 2.572E-04 2.301E-04 SSE 1422. 1422. 8.767E-06 8.399E-06 1422. 3.309E-05 3.076E-05 1422. 1.438E-04 1.289E-04 5 1198. 1198. 7.778E-06 7.503E-06 1198. 3.131E-05 2.919E-05 1198. 1.695E-04 1.513E-04 SSW 2140. 2140. 4.975E-06 4.743E-06 2140. 1.790E-05 1.657E-05 2140. 9.115E-OS 8.184E-05 SW 1372. 1372. 7.778E-06 7.484E-06 1372. 3.803E-05 3.523E-05 1372. 2.491E-04 2.224E-04 WSW 823. 823. 1.135E-05 1.099E-05 823. 7.956E-05 7.348E-05 823, 5.527E-04 4.896E-04 W 713. 713. 1.419E-05 1.375E-05 713. 1.096E-04 1.OOGE-04 713. 8.936E-04 7.872E-04 WNW 713. 713. 1.281E-05 1.241E-05 713. 1.283E-04 1.166E-04 713. 1.218E-03 1.070E-03 NW 823. 823. 1.308E-05 1.262E-05 823. 9.513E-05 8.731E-05 823. 8.374E-04 7.389E-04 NNW 1481. 1481. 9.317E-06 8.932E-06 1481. 5.833E-05 5.372E-OS 1481. 3.907E-04 3.480E-04 Ouad Cities Site Meteorological Data 1/78 - 12/87 F-18
_ m i
. ~.
QUAD t-fTIES Revisio)t .O January 1994 Table F-7 (Continued) , Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary ^ for Xe-135m Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius S 58AR Radius V VBAR Radius G GBAR ~, (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) ( me t e r,s ) (mrat1/ yr )/ (uO 1/ sec ) ' N 864. 864. 2.899E-04 2.803E-04 864 8.530E-04 8.236E-04 864. 2.453E-03'2.363E-03 NNE 1029. 1029. 2.877E-04 2-781E-04
. 1029. 7.645E-04 7.384E-04 1029. 1.941E-03 1.870E-03 NE 1212 1212. 1.756E-04 1.697E-04 1212. 4.447E-04 4.296E-04 1212. 1.382E-03 1.332E-03 ENE 1367. 1367. 1.163E-04 1.125E-04 1367. 3.217E-04 3.107E-04 1367. 9.117E-04 8.789E-04 E 1170. 1170. 1.741E-04 1.683E-04 1170. 5.632E-04 5.438E-04 1170. 1.662E-03 1.602E-03 ESE 1170. 1170. 2.308E-04 2.231E-04 1170. 6.317E-04 6.100E-04 1170. 1.681E-03 1.620E-03 SE 1189. 1189. 1.959E-04 1.894E-04 1189. 4.53GE-04 4.381E-04 1189. 1.OO3E-03 9.670E-04 SSE 1422. 1422. 1.166E-04 1.127E-04 1422. 2.398E-04 2.316E-04 1422. 5.084E-04 4.901E-04 5 1198. 1198. 1.163E-04 1.-124E-04 1198. 2.423E-04 2.340E-04 1198. 5.714E-04 5.507E-04 SSW 2140. 2140. 5.156E-05 4.984E-05 2140. 1.028E-04 9.925E 2140. 2.160E-04 2.082E-04 SW 1372. 1372. 1.099E-04 1.063E*04 1372. 2.682E-04 2.590E-04 1372.- 7.263E-04 7.OOOE-04 WSW 823, 823, 1.979E-04 1.914E-04 823. 6.335E-04 6.118E-04 823. 2.055E-03 1.979E-03 W 713. 713. 2.585E-04 2.499E-04 713. 8.524E-04 8.229E-04 713. 3.381E-03 3.255E-03 WNW 713. 713. 2.323E-04 2.246E-04 713. 8.874E-04 8.564E-04 713. 4.500E-03 4.332E-03 NW 823. 823. 2.227E-04 2.153E-04 823. 6.913E-04 6.674E-04 823. 2.772E-03 2.670E-03 NNW 1481. 1481. 1.264E-04 1.222E-04 1481. 3.575E-04 3.452E-04 1481 9.461E-04 9.117E-04 Quad Cities Site Meteorological Data 1/78 - 12/87 F-19 P w.,.-.-w..--z-- --a. *,==,se=.i. - ere . n w w, ,. * =,w *-n,e- ,w or e- -,er *-w- -
w *ee -m.. . . - . m-a, --e -ew6-. .+~~-.a, e -v'- , . - - - - e - . - - ~ - - - -
QUAD CITIES Revision 1.0 7enuary 1994 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Doundary for Xe-135 Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direct ion Area Bound Radius 5 SBAR Radius V VBAR Radius G' GBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) (meters) ( mracj/yr )/(uC 1/ sec ) N 864. 864. 1.787E-04 1.729E-04 864. 6.779E-04 6.555E-04 BG4. 2.851E-03 2.753E-03 NNE 1029. 1029. 1.867E-04 1.807E-04 1029. 6.045E-04 5.847E-04 1029, 2.178E-03 2.103E-03 NE 1212. 1212. 1.196E-04 1.158E-04 1212, 3.894E-04 3.766E-04 1212. 1.917E-03 1.851E-03 ENE 1367. 1367. 8.192E-05 7.928E-05 1367. 2.860E-04 2.766E-04 1367, 1.285E-03 1.242E-03 E 1170. 1170. 1.145E-04 1.108E-04 1170. 4.571E-04 4.420E-04 1170. 1.913E-03 1.848E-03 ESE I t70. 1170. 1.504E-04 1.456E-04 1170. 5.067E-04 4.900E-04 1170. 1.833E-03 1.771E-03 SE 1189. 1189. 1.287E-04 1.246E-04 1189. 3.627E-04 3.508E-04 1189. 1.113E-03 1.075E-03
$5E 1422. 1422. 8.2O4E-05 7.939E-05 1422, 2.113E-04 2.044E-04 1422. 6.264E-04 6.OS2E-04 5 1198. 1198. 7.961E-OS 7.705E-05 1198. 2.044E-04 1.977E-04 1198. 7.175E-04 6.931E-04 55W 2140. 2140. 4.304E-05 4.165E-05 2140. 1.103E-04 1.067E-04 2140. 3.945E-04 3.812E-04 SW 1372. 1372. 7.655E-05 7.409E-05 1372. 2.359E-04 2.282E-04 1372. 1.046E-03 1.010E-03 WSW 823. 823. 1.242E-04 1.202E-04 823. 4.833E-04 4.674E-04 823. 2.225E-03 2.149E-03 W 713, 713. 1.573E-04 1.522E-04 713. 6.395E-04 6.183E-04 713. 3.478E-03 3.358E-03 WNW 713. 713. 1.415E-04 1.370E-04 713. 6.923E-04 6.693E-04 713. 4.660E-03 4.498E-03 NW B23. 823. 1.384E-04 1.340E-04 823. 5.510E-04 5.328E-04 823. 3.277E-03 3.164E-03 NNW 1481, 1481, 8.796E-05 8.512E-05 1481. 3.406E-04 3.293E-04 1481. 1.605E-03 1.550E-03 Quad C1ttes Site Meteorological Data 1/78 - 12/87 l
l l F-20 9 - 9 9 - - _ _
-QUAD u IIES Revisio .0 January 1994 Table F-7 (Continued)
Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-137 Downwind Unrestricted Elevated (Stack) Release tit xed Mode (Vent ) Release Ground Level Release Direction Area Bound Radius 5 5BAR Radius V VBAR Radius G G8AR
,( meters) (meters) (mrad /yr)/(uCl/sec) (moters) (mrad /yrb(uCt/sec) (meters) (mrad /yr)/(uC1/sec)
N 864. 864 9.587E-05 9.280E-05 864, 2'.169E-0 2.100E-04 864. 3'.650E-04 3.532E-04' NNE 1029. 1029. 8.396E-05 8.127E-05 1029. 1.789E-04 1.731E-04 1029. 2.883E-04 2.789E-04 NE 1212. 1212. 4.406E-05 4.265E-05 1212. 8.327E-05 8.059E-05 1212. 1.506E-04 1.457E-04 ENE' 1367. 1367. 2.876E-05 2.784E-05 1367. 6.062E-05 5.866E-05 1367. 9.706E-05 9.394E-05 E 1170, 1870. 5.Ot4E-05 4.854E-05 1170. 1.28CE-04 1.239E-04 1170. 2.375E-04 2.298E-04 ESE 1170. 1170. 6.82tE-05 6.603E-05 1170. 1.517E-04 1.468E-04 1170. 2.747E-04 2.65BE-04 SE 1189. 1189. 5.604E-05 5.425E-05 1189. 1.044E-04 1.010E-04 1189. 1.63tE-04 1.576E-04 55E 1422. 1422. 2.842E-05 2.75tE-05 1422. 4.591E-05 4.443E-05 1422. 6.975E-05 6.749E-05
$ 1198. 1198. 3.027E-OS 2.930E-05 1198. 5.064E-05 4.901E-05 1198. 8.267E-05 7.999E-05 SSW 2140. 2140, 8.925E-06 8.639E 2140. 1.344E-05 1.301E-05 2140. 1.753E-05 1.696E-05 SW 1372. 1372. 2.697E-05 2.61tE-05 1372. 5.26tE-05.5.091E-05 '1372. 8.334E-05 8.064E-05
~ WSW 823. 823. 6.236E-05 6.037E-05 823. 1.682E-04 1.628E-04 823. 3.760E-04 3.638E-04 W- 713. 713. 8.655E-05's.378E-05 713. 2.349E-04 2.274E-04 713. 5.968E-04 5.775E-04 WNW 713. 713. 7.777E-05 7.529E-05 713. 2.298E-04 2.224E-04 713. 7.354E-04-7.115E-04 NW 823. 823. 7.090E-05.6.863E-05 823. 1.705E-04 1.650E-04 823. 3.973E-04 3.845E-04 ; NNW 1481. 1481. 3.192E-05 3.090E-05 1481. 6.298E-05 6.095E-05 1481. --7.935E-05 7.678E-05 Ouad Cities Site Meteorological Data 1/78 - 12/87 9 F __ _ . _ _ _ 2. - _ ., .; _ _. . , _ ._ . _ .. . . . - - . . . - ..a-.. _. . .- - .- -. . .. -.- _ . ~ . - . _ _ - . ~ . . _ _ _ _ _ _ _ _
QUAD CITIES Revision 1.0 January 1994 Table F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-138 Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Relecae Direction Area Bound Radtus 5 SBAR Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) (meters) ( mrad /y[-)](uC t /sec ) N 864. 864. 7.602E-04 7.388E-04 864. I' . 909 E -03 1.854E-03 864. 5.OO7E-03 4.860E-03 NNE 1029. ~1029, 7.527E-04 7.315E-04 1029. 1.728E-03 1.679E-03 1029. 3.991E-03 3.874E-03 NE 1212. 1212. 4.600E-04 4.471E-04 1212. 1.OOSE-03 9.759E-04 1212. 2.814E-03 2.731E-03 Et4E 1367. 3367. 3.014E-04 2.929E-04 1367. 7.202E-04 S.995E-04 1367. 1.859E-03 1.804E-03 E 1170. 1170. 4.505E-04 4.378E-04 1170. 1.258E-03 1.222E-03 1170. 3.418E-03 3.318E-03 ESE if70, 1170. 5.943E-04 5.775E-04 1170. 1.414E-03 1.373E-03 1170. 3.473E-03 3.371E-03 SE 1189. 1189. 5.05*4E-04 4.916E-04 1189. 1.022E-03 9.929E-04 1189-. 2.076E-03 2.015E-03 SSE 1422. 1422. 2.995E-04 2.910E-04 1422. 5.384E-04 5.229E-04 1422. 1.049E-03 1.018E-03 5 1198. 1198. 3.027E-04 2.941E-04 1198. 5.469E-04 5.312E-04 1198. 1.174E-03 1.139E-03 l , SSW 2140. 2140, 1.297E-04 1.260E-04 2140. 2.269E-04 2.204E-04 2140. 4.390E-04 4.262E-04 l SW 1372. 1372. 2.843E-04 2.763E-04 1372.. 6.OO5E-04 5.832E-04 1372. 1.480E-03 1.436E-03 WSW 823. 823. 5.252E-04 5.104E-04 823. 1.428E-03 1.387E-03 823. 4.220E-03 4.095E-03 l l W 713, 713. G.885E-04 6.691E-04 713. 1.914E-03 t.859E-03 713. 6.917E-03 6.712E-03 WNW 713. 713. 6.188E-04 6.014E-04 713, 1.974E-03 1.917E-03 713. 9.182E-03 8.910E-03 i l NW 823. 823. 5.894E 04 5.728E-04 823. 1.550E-03 1.505E-03 823. 5.640E-03 5.474E-03 NNW 1481. 1481. 3.244E-04 3.152E-04 1481. 7.909E-04 7.681E-04 1481. 1.903E-03 1.847E-03 Quad Cities Site Meteorclogical Data 1/78 - 12/87 l I F'a
N - = QUAD %1 TIES Revision .0 Januat'f 1994 s Table F-7.(Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Ar-41 r l Downwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release 01rection' Area Bound Radius S SBAR Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad],r)/(uC1/sec) - _, N 864 864. 9.169E-04 8.875E-04 864 2.639E-03 2.555E-03 864. 9.453E-03 9.150E-03 NNE 1029. 1029. 9.534E-04 9.229E-04 '1029. 2.410E-03 2.333E-03 1029. 7.295E-03 7.061E-03 NE 1212 1212. 6.143E-04 5.947E-04 1212. 1.545E-03 1.496E-03 1212. 6.170E-03 5.973E-03 '- 1367. 1367. 4.130E-04 3.998E-04 1367. 1.116E-03 1.080E-03 1367. 4.131E-03 3.999E-03 ENE E 1170, 1170. 5.748E-04 5.564E-04 1170. 1.782E-03 1.725E-03 1170. 6.371E-03 6.167E-03 ESE 1170. 1170. 7.494E-04 7.254E-04 1170. 1.976E-03 1.913E-03 1170. 6.148E-03 5.951E-03 SE 1189. 1189. 6.447E-04 6.241E-04 1189. 1.435E-03 1.389E-03 1189. 3.710E-03 3.591E-03 SSE 1422. 1422. 4.090E-04 3.959E-04 1422. 8.282E-04 8.017E-04 1422. 2.052E-03 1.986E-03
$ 1198. 1198. 4.040E-04 3.910E-04 1198. 8.103E-04 7.843E-04 1198. 2.334E-03 2.259E-03 ,
SSW 2140. 2140. 2.070E-04 2.OO4E-04 2140. 4.157E-04 4.024E-04 2140. 1.195E-03 1.157E-03 SW 1372. 1372. 3.864E-04 3.740E-04 1372. 9.192E-04 8.898E-04 1372. 3.318E-03 3.212E-03 WSW 823. 823. 6.504E-04 6.296E-04 823. 1.917E-03 1.856E-03 823. 7.433E-03 7.196E-03 W 713. 713. 8.303E-04 8.037E-04 713. 2.525E-03 2.445E-03 713. 1.179E-02 1.141E-02
- WNW 713. 713. 7.474E-04 7.235E*04 713. 2.689E-03 2.603E-03 713, 1.583E-02 1.532E-02 NW 823. 823. 7.219E-04 6.988E-04 823. 2.157E-03 2.088E-03 823. 1.085E-02 1.050E-02 NPN 1481'. 1481. 4.362E-04 4.222E-04. 1481. 1.291E-03 1.249E-03 1481. 4.963E-03 4.805E-03 Ouad C1ttes Site Meteorological Oata 1/78 - 12/87 f
F-23
, _. _ _ . . ___ a ....x_ - . . u___..-._ - . . . _ . _ . . _ _ ~ . - . . .. .-. . _:--_,__._~_._.. . _ ~ - . . . . _ - ,
QUAD CITIES Revision 1.0 January 1094 Table F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-83m Downwind Controlled Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius 5 SBAR Radtus V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/tuC1/sec) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) N 300. 300. 7.953E-07 5.996E-07 300. I'. 7 95 E -04 1.353E 300.- l'.M BE-03 1.461E-03 NNE 300. 300. 1.313E-06 9.897E*07 300. 1.448E-04 1.092E-04 300. 1.809E-03 1.3G4E-03 NE 325.. 325. 7.351E-07 5.543E-07 325. 8.809E-05 6.642E-05 325. 1.740E-03 1.312E-03 ENE 1210. 1210. 9.OO9E-07 6.793E-07 1210. 1.602E-05 1.208E-05 1210. 1.688E-04 1.273E-04 E 1170. 1170, 1.378E-06 1.039E-06 1170. 2.602E-05 1.962E-05 1170. 2.22OE-04 1.674E-04 ESE 1125. 1125. 1.778E-06 1.340E-06 1125. 2.874E-05 2.167E-05 1125. 2.255E-04 1.700E-04 SE 475. 475. 1.799E-06 1.357E-06 475. 5.328E-OS 4.017E-05 475. 5.475E-04 4 128E-04 SSE 475. 475. 9.937E-07 7.492E-07 475. 3.379E-05 2.547E-05 475. 3.931E-04 2.964E-04 5 325. 325. 3.591E-07 2.707E-07 325. 4.296E-05 3.239E-05 325. 6.418E-04 4.839E-04 55W 325. 325, 3.038E-07 2.291E-07 325. 4.855E-05 3.661E-05 325. 7.603E-04 5.733E-04 SW 250. 250. 3.014E-07 2.273E-07 250. 1.026E-04 7.733E-05 250. 1.652E-03 1.245E-03 WSW 200. 200. 3.517E-07 2.652E-07 200. 1.842E-04 1.389E-04 200. 2.503E-03 1.887E-03 W 200. 200. 4.135E-07 3.118E-07 200. 2.314E-04 1.745E-04 200. 3.341E-03 2.519E-03 WNW 200. 200. 3.679E-07 2.774E-07 200. 3.157E-04 2.381E-04 200. 4.573E-03 3.448E-03 NW 200, 200. 4.282E-07 3.229E-07 200. 2.468E-04 1.861E-04 200. 3.784E-03 2.853E-03 NNW 200. 200. 5.028E-07 3.791E-07 200. 3.OO9E-04 2.269E-04 200. 3.901E-03 2.941E-03 Quad Cities Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B. F-24
^
( QUAD M)IES Revisic.b .0 January 1994l Table F-7a (Continued)
-Maximum Offsite Finite' Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted. Area Boundary for Kr-85m Downwind Controlled Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius -S SBAR Radius V VBAR Rad!us G GBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec)
N 300. 300. 3.440E-04 3.330E-04 300. I'.565E-03 1.505E-O3 '300. 7.885 -03 7.526E-03 NNE 300. 300. 4.237E-04 4.100E-04 300. 1.663E-03 1.602E-03 300. 7.799E-03 7.450E-03 NE 325. 325. 2.890E-04 2.797E-04 325. 1.104E-03 1.064E-03 325. 7.549E-03.7.211E-03 ENE. 1210. 1210. 6.453E-05 6.242E-05 1210. 2.333E-04 2.249E-04 1210. 1.091E-03 1.046E-03 ., E 1170. 1170. 8.118E-05 7.850E-05 1170. 3.308E-04 3.187E-04 1170. 1.393E-03 1.336E-03 ESE 1 f25. 1125. 1.106E-04 1.070E-04 1125. 3.817E-04 3.679E-04 1125. 1.409E-03 1.351E-03 SE 475. 475. 2.157E-04 2.087E-04 475. 6.976E-04 6.724E-04 475. 2.702E-03 2.5G5E-03 SSE 475. 475. 1.584E-04 1.532E-04 475. 4.768E-04 4,597E-04 475. 1.918E-03 1.835E-03 5 325. 325. 1.887E-04 1.826E-04 325. 5.731E-04 5.524E-04 325. 2.792E-03 2.667E-03 SSW 325. 325. 1.661E-04 1.608E-04 325. 5.652E-04 5.445E-04 325. 3.247E-03 3.101E-03 SW 250. 250. 2.612E-04 2.529E-04 250. 1.020E-03 9.822E-04 250. 6.563E-03 6.262E-03 WSW 200. 200. 3.394E-04 3.285E-04 200. 1.593E-03 1.532E-03 200. 9.455E-03 9.OtSE-03 W 200. 200. 3.795E-04 3.673E-04 200. 1.823E-03 1.752E-03 200. 1.215E-02 1.15BE-02 WNW 200. 200. '3.412E-04 3.303E-04 200. 2.037E-03 1.955E-03 200. 1.618E-02 1.541E-02 NW 200. 200. 3.796E-04 3.674E-04 200. 1.863E-03 1.790E-03 200. 1.375E-02 1.310E-02 NNW 200. 200. 4.103E-04 3.972E-04 200. 2.187E-03 2.100E-03 200. 1.432E-02 1.365E-02 Ouad C1ttes Site Meteorological Data 1/78 - 12/87 T p 25 -
. . _ _ - _ _ _ _ _ _ _ _ _ _ -__ . . ._. - . _ . . . - . _ - _ . . . . . . _ _ ~ . _ _. - -, . . . . . ._._ .. .._
QUAD CITIES Revision 1.0 January 1994 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-85 Downwind Controlled Elevated (5 tack) Release Mimed Mode (Vent) - -wase Ground Level Welease - 5 58AR Radius V iB AR Radius G GBAR D irec t ion Area Bound Radius (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/ 1/sec) (meters) ( rfirad/FF)/ ( uC i / sec ) > N 300. 300, 4.841E-06 4.682E-06 300. 1.82OE-05 1.760E-OS 300. B.527E-05 8.246E-05 300. 300. 6.016E-06 5.817E-06 300. 1.965E-05 1.900E-05 300. 8.415E-05 8.137E-05 NNE 325. 325. 4.147E-06 4.010E-06 325. 1.322E-05 1.278E-05 325. 8.181E-05 7.911E-05 NE ENE 1210. 1210. 9.034E-07 8.736E-07 1210. 2.80tE-06 2.708E-06 1210. 1.252E-05 1.210E-05 E 1170. 1170. 1.116E-06 1.079E-06 1170. 3.908E-06 3.779E-06 1170. 1.578E-05 1.525E-05 1125. 1125 1.515E-06 1.465E-OG 1125. 4.518E-06 4.368E-06 1t25. 1.587E-05 1.535E-05 ESE 475. 475. 3.013E-06 2.914E-06 475. 8.268E-06 7.995E-06 475. 2.946E-05 2.848E-05 SE 475. 475. 2.238E-06 2.164E-06 475. 5.695E-06 5.507E-06 475. 2.092E-05 2.023E-05 SSE 5 325. 325. 2.703E-06 2.614E-06 325. 6.845E-OG 6.619E-06 325. 3.022E-05 2.923E-05 325. 325. 2.389E-06 2.310E-06 325. 6.715E-06 6.493E-06 325. 3.516E-05 3.400E-05 SSW SW 250. 250. 3.748E-06 3.624E-06 250. 1.202E-05 1.163E-05 250. 7.075E-05 6.841E-05 WSW 200. 200. 4.863E-06 4.703E-06 200. 1.861E-05 1.800E-05 200. 1.015E-04 9.820E-05 W 200. 200. 5.424E-06 5.245E-06 200. 2.118E-05 2.048E-05 200. 1.304E-04 1.261E-04 200. 4.877E-06 4.716E-06 200. 2.340E-05 2.263E-05 200. 1.737E-04 1.680E-04 WNW 200. NW 200. 200. 5.415E-06 5.237E-06 200. 2.162E-05 2.090E-05 200. 1.479E-04 1.430E-04 NNW 200. 200. 5.816E-06 5.624E-06 200. 2.526E-05 2.443E-05 200. 1.540E-04 1.490E-04 Ouad C1ttes Site Meteorological Data 1/78 - 12/87 F-26
- 9. - .
9 .
- 9. .
'%/ QUAD d IES RevisiO!m .0.-
January 1994 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-87 Dosnwend Controlled Elevated (Stack) Release Mtwed Mode (vent) Re! ease Ground Level Release Direction Area Bound Radius 5 5BAR Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uC1/sec) N 300. 300. 1.764E-03 1.713E-03 300. 5.505E-03 5.347E-03 300. 2.333E-02 2.265E-02 f4NE 300. 300. 2.207E-03 2.144E-03 300. 6.066E-03 5.891E-03 300. 2.334E-02 2.266E-02 NE 325. 325. t.538E-03 1.495E-03 325. 4.104E-03 3.985E-03 325. 2.228E-02 2.163E ENE 1210. 1210. 3.112E-04 3.024E-04 1210. 8.155E-04 7.920E-04 1210. 2.990E-03 2.903E-03 E 1170. 1170. 3.853E-04 3.743E-04 1170. 1.146E-03 1.113E-03 1170. 3.929E-03 3.815E-03 ESE ff25. 1925. 5.225E-04 5.076E-04 1125. 1.327E-03 1.289E-03 1125. 4.02tE-03 3.904E-03 SE 475. 475. 1.087E-03 1.056E-03 475. 2.539E-03 2.466E-03 475. 8-OOOE-03 7.768E-03 SSE 475. 475. 8.111E-04 7.880E-04 475. 1.747E-03 1.697E-03 475. 5.666E-03 5.501E-03 5 325. 325. 9.932E-04'9.650E-04. 325. -2.122E-03 2.060E-03 325. 8.26BE-03 8.027E-03 SSW 325, 325. 8.813E-04 8.563E-04 325. 2.067E-03 2.OO8E-03 325. 9.605E -03 9.326E -03 SW 250. 250. 1.392E-03 1.352E-03 250. 3 712E-03 3.605E 03 250. 1.953E-02 1.897E-02 WSW 200. 200. 1.802E-03 1.751E-03 200. 5.733E-03 5.567E-03 200. 2.837E-02 2.754E W 200. 200. 2.01CE-03 1.953E-03 200. 6.487E-03 6.3OOE-03 200. 3.652E-02 3.546E-02 WNW 200. 200. 1.805E-03 1.754E-03 200. 7.089E-03 6.885E-03 200. 4.869E-02 4.728E-02 NW -200. 200. '2.OO4E-03 1.947E-03 200. 6.600E-03 6.409E-03 200. 4.117E-02 3.997E-02 NNW 200. 200. 2.139E*O3 2.078E-03 '200. 7.684E-03 7.463E'03 200. 4.284E-02 4.159E Quad Cities Site Meteorological Data 1/78 - 12/87 l l
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QUAD CITIES Revision 1.0 January 1994 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-90 Oownwind Controlled Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius 5 SBAR Radius V VBAR Radius G GBAR . (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yn)/(uC1/sec) N 300. 300. 1.558E-03 1.512E-03 300. 2.684E-03 2.604E-03 300. 3.025E-03 2.933E-03 NNE 300. 300. 1.673E-03 1.624E-03 300. 3.OOOE-03 2.911E-03 300. 4.213E-03 4.084E-03 NE 325, 325. 8.837E-04 8.578E-04 325. 1.302E-03 1.263E-03 325. 2.182E-03 2.115E-03 ENE 1210. 1210. 1.434E-05 1.392E-05 1210. 1.294E-05 1.255E-05 1210. G.697E-06 G.494E-06 E 1170. 1170. 2.876E-05 2.792E-05 1170. 3.OG1E-OS 2.970E-05 1170. 1.687E-05 1.636E-OS ESE 1125. 1125. 4.806E-05 4.665E-05 1925. 4.598E-05 4.460E-05 1125, 3.402E-05 3.299E-05 SE 475. 475. 5.097E-04 4.947E-04 475. 7.089E-04 6.878E-04 475. 8.952E-04 8.679E-04 SSE 475. 475. 3.075E-04 2.985E-04 475. 3.993E-04 3.874E-04 475. 5.764E-04 5.588E-04 5 325, 325. 6.028E-04 5.852E-04 325. 8.849E-04 8.585E-04 325. 1.565E-03 1.517E-03 SSW 325. 325. 5.150E-04 4.999E-04 325. 8.626E-04 8.368E-04 325. 1.683E-03 1.631E-03 SW 250. 250. 1.184E-03 1.150E-03 250. 2.311E-03 2.242E-03 250, 4.598E-03 4.457E-03 W5W 200. 200. 1.907E-03 1.852E-03 200. 4.742E-03 4.GOOE-03 200. 1.108E-02 1.074E-02 W 200. 200. 2.179E-03 2.115E-03 200. 5.116E-03 4.963E-03 200. 1.147E-02 1.112E-02 WNW 200. 200. 1.957E-03 1.899E-03 200. 4.847E-03 4.702E-03 200. 1.265E-02 1.226E-02 NW 200. 200. 2.194E-03 2.130E-03 200. 4.603E-03 4.465E-03 200. 9.815E-03 9.513E-03 NNW 200. 200. 2.522E-03 2.448E-03 200. 5.495E-03 5.331E-03 200. 1.032E-02 1.OO1E-02 Ouad C1ttes Site Meteorological Data 1/78 - 12/87 F-10 9 . 9 . .
- 9. .
QUAD IES Revision O January 1994 , Table F-7a-(Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on.1 cm Depth at the Restricted Area Boundary for Xe-131m k Downwind Controlled Elevated (Stack) Release Mixet) Mode (Vent) Release Ground Level Release Direction Area Bound Radius 5 SBAR Radius V VBAR Radius G GBAR .
-(meters) (meters) (mrad /yr)/(uCl/sec) (meters) (mrad /yr)/(uCl/sec) (meters) (mradlyc)/(uC1/sec)
N 300. - 300. 7.919E-06 7.533E-06 300. t'.746E-04 1.386E-04 300. 1.725E-03 1.335E-03 NNE 300. 300. 1.OO2E-05 9.476E-06 300. 1.482E-04 1.192E-04 300. 1.605E-03 1.244E-03 NE 325. 325. 6.711E-06 6.373E-06 325. 9.259E-05 7.474E-05 325. 1.564E-03 1.212E-03 ENE 1210. 1210. 2.101E-06 1.88tE-06 1210. 1.811E-05 1.471E-05 1210. 1.761E-04 1.378E-04 E 1170. 1170. 2.839E-06 2.SttE-06 1170. 2.808E-05 2.266E-05 1170. 2.237E-04'1.750E-04 ESE 1125. 1125. 3.764E-06 3.342E-06 1125. 3.124E-05 2.528E-05 1125. 2.248E-04 1.758E-04 SE 475. 475. 5.987E-06 5.494E-06 475. 5.658E-05 4.578E-05 475. 5.013E-04 3.898E-04 SSE 475. 475. 4.145E-06 3.846E-06 475. 3.671E-05 2.982E-05 475. 3.604E-04 2.801E-04 5 325. 325. 4.292E-06 4.095E-06 325. 4.579E-05 3.709E-05 325. 5.754E-04 4.460E-04 55W 325, 325. 3.771E-06 3.599E-06 325. 5.OO3E-05 4.024E-05 325. 6.8ttE-04 5.276E-04 SW 250. 250. 5.781E-06 5.546E-06 250. 1.017E-04 8.122E-05 250. 1.457E-03 1.127E-03 WSW 200. 200. 7.477E-06 7.179E-06 200. 1.771E-04 1.406E-04 1 200. 2.181E-03 1.685E-03 W 200. 200. 8.374E-06 8.037E-06 200. 2.188E-04 1.73OE-04 200. 2.896E-03 2.235E-03 WNW 200. 200. 7.527E-06 7.225E-06 200. 2.898E-04 2.274E-04 200. 3.952E-03 3.049E-03 NW 200. 200. 8.386E-06 8.046E-06 200. 2.324E-04 1.834E-04 200. 3.293E-03 2.542E-03 NNW 200. 200. 9.093E-06 8.719E-06 200. 2.814E-04 2.218E-04 200. 3.400E-03 2.625E-03' Ouad Cities Site Meteorological Data 1/78 - 12/87 F' .
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QUAD CITIES Revisivn 1.0 January 1994 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133m i l Downwind Controlled Elevated 15 tack) R+1ehse Mixed Mode (Vent) Release Ground Level Release l Direction Area Oound Radius 5 SBAR Radius V VBAR Radius . G, ,. GBAR I (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) N 300. 300. 4.925E-05 4.753E-05 300. 3.633E-04 3.201E-04 300. 2.684E-03 2.250E-03 NNE 300. 300. 6.093E-05 5.876E-05 300. 3.485E-04 3.121E-04 300. 2.551E-03 2.148E-03 NE 325. 325. 4.145E-05 4.OOOE-05 325. 2.257E-04 2.030E-04 125. 2.483E-03 2.090E-03 ENE 1210. 1210. 9.950E-06 9.471E-06 1210. 4.664E-05 4.222E-05 1210. 3.1394-04 2.699E-04 E 1170. 1170. 1.267E-05 1.202E-05 1170. 6.835E-05 6.147E-05 1170. 3.97.' -J4 3.419E-04 ESE 1125. 1125. 1.715E-05 1.628E-05 1125. 7.772E-05 7.OO8E-05 1125. 4 . MvE -04 3.439E-04 SE 475. 475. 3.195E-05 3.061E-05 475. 1.407E-04 1.268E-04 475. 8.309E-04 7.051E-04 SSE 475. 475. 2.322E-05 2.230E-05 475. 9.430E-05 8.534E-05 475. 5.945E-04 5.041E-04 5 325. 325. 2.7 DOE-05 2.607E-05 325, 1.149E-04 1.037E-04 325. 9.151E-04 7.704E-04 SSW 325. 325. 2.377E-05 2.296E-05 325. 1.182E-04 1.059E-04 325. 1.076E-03 9.049E-04 SW 250. 250. 3.717E-05 3.593E-05 250. 2.246E-04 1.995E-04 250. 2.254E-03 1.887E-03 WSW 200. 200. 4.824E-05 4.664E-05 200. 3.688E-04 3.249E-04 200. 3.326E-03 2.776E-03 W 200. 200 5.395E-OS 5.215E-05 200. 4.38tE-04 3.837E-04 200. 4.J66E-03 3.636E-03 WNW 200. 200. 4.851E-05 4.689E-05 200. 5.352E-04 4.628E-04 200. 5.911E-03 4.914E-03 NW 200. 200. 5.396E-OS 5.216E-05 200. 4.567E-04 3.989E-01 200 4. 960E -03 4 .129E -03 NNW 200. 200. 5.835E-OS 5.639E-05 <O0. 5.447E-04 4.747E-04 200. 5.137E-03 4.279E-03 Quad Cities Site Meteorciogical Data 1/78 - 12/87 F-12 O O O. .
p .- . QUAD strIES Revisio 0 January 1994 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133 Downwind Controlled E levated(Stack ) Release Mixed Mode (vent) Release Ground Level Release Direction Area Bound Redius S 58AR Radius V VBAR Radius G GBAR ~ (meters) (meters) (mrad /yr)/(uCt/sec) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yt)/(uC1/sec) N 300. 300. 4.270E-OS 4.147E-05 300. d.950E-04 3.582E-04 300. .2.859E-03 2.493E*O3 NNE 300. 300. 5.247E-05 5.09tE-05 300. 3.809E-04 3.498E-04 300. 2.746E-03 2.404E-03 e NE 325. 325. 3.494E-05 3.393E-05 325. 2.450E-04 2.257E-04 325. 2.674E-03 2.34tE ENE 1210. 1210. 9.307E-06'8.93tE-06 1210. 5.206E-05 4.825E-05 1210. 3.540E-04 3.163E-04 . E 1170. 1170. 1.214E-05 1.162E-05 1170. 7.658E-05 7.065E-05 1170. 4.478E-04 4.OOOE-04 ESE t v25. 1125. 1.650E-05 1.581E-05 1125. 8.707E-OS 8.048E-05. 1125. 4.504E-04 4.023E-04 SE 475. 475. 2.856E-05 2.755E-05 475. 1.562E-04 1.443E-04 475. 9.121E-04 8.051E-04 SSE 475. 475. 2.032E-05 1.965E-05 475. 1.042E-04 9.655E-05 475. 6.513E-04 5.745E f S 325, 325. 2.272E-05 2.207E-05 325. -1.256E-04 1.160E-04 325. 9.860E-04 8.636E-04 55W 325. 325. 1.988E-05 1.932E-05 325. 1.288E-04 1.183E-04 325. 1.156E-03 1.OttE-03 SW 250. 250. '3.098E-05 3.Ot3E-05 250. 2.427E-04 2.214E-04 250. 2.393E-03 2.083E-03 WSW 200. 200. 4.018E-05 3.909E-05 200. 3.963E-04 3.59tE-04 200. 3.501E-03 3.038E-03 U 200 200. 4.515E-05 4.392E-05 200. 4.689E-04 4.229E-04 200. 4.563E-03 3.949E-03 WNW 200. 200. 4.058E-05 3.948E-05 200.- 5.668E-04 5.057E-04 200. 6.143E-03 5.305E-03 NW 200. 200. 4.529E-05 4.405E-05 200. 4.874E-04 4 385E-04
. 200. 5.179E-03 4.481E-03 NNW 200. 200. 4.951E-05 4.815E-05 200. 5.823E-04 5.230E-04 200. 5.375E-03 4.654E-03 Ouad Cities Site Meteorological Oata 1/78 - 12/87 i
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QUAD IES Revisio O January.1994 , Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary-for Xe-135 a k Downwind 'Controtted Elevated (Stack) Release Mixed Mode (vent) Release Ground Level Release Direction Area Bound Radius 5 SBAR Radius -V VBAR Radius . .G. GBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yrl/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) i N 300. 300. 4.855E-04 4.700E-04 300. d.135E-03 2.064E-03 300. 1.048E-02 1.011E-02 NNE 300. 300. 5.984E-04 5.792E-04 300, 2.283E-03 2.207E-03 300. 1.038E-02 1.OO2E-02 NE 325. 325. 4.086E-04 3.955E-04 325. 1.519E-03 1.469E-03 325. 1.OO7E-02 9.718E-03 ENE 1210. 1210. 9.137E-05 8.842E-05 1210. 3.240E-04 3.134E-04 1210. 1.508E-03 1.457E-03 E 1170. 1170. 1.14 5 E -04 1.108E-04 1170. 4.571E-04 4.420E-04 1170. -1.913E-03 1.848E-03 ESE tt25, 1125. 1.559E-04: 1.509E-04 1125. 5.278E-04 5.104E-04 1125. 1.93OE-03.1.864E-03 SE 475. 475. 3.041E-04 2.944E-04 475. 9.601E-04 9.285E-04 475. 3.628E-03 3.503E-03 SSE 475. 475. 2.237E-04 2.165E-04 475. 6.578E-04 6.362E-04 475. 2.575E*03 2.486E-03 S 325. 325, 2.669E-04 2.584E-04 325. 7.892E-04 7.632E-04 325. 3.722E-03 3.593E-03 SSW 325. 325. 2 351E-04 2.276E-04 325. 7.768E-04 7. Site-04 325. 4.326E-03 4.175E-03 SW 250. 250. 3.694E-04 3.575E-04 250. 1.396E-03 1.350E-03 250. 8.701E-03 8.396E-03 WSW 200, 200. 4.798E-04 4.644E-04 200. 2.172E-03 2.099E-03 200. .t.249E-02 1.205E-02 i W 200. 200. 5.363E-04 5.191E-04 200. 2.479E-03 2.396E-03 200. -1.601E-02 1.544E-02 WNW 200. 200. 4.823E-04 4.668E-04 200. 2.754E-03 2.661E-03 200. 2.128E-02 2.053E-02 NW 200. 200. 5.363E-04 5.19tE-04 200. 2.53tE-03 2.446E-03 200. 1.813E-02 1.749E-02 NNW 200. 200. 5.794E-04 5.608E-04 200. 2.967E-03 2.867E-03 200. 1.889E-02 1.823E-02 Quad Cities Site Meteorological Data 1/78 - 12/87 -j b o F-3 5 .. __ _ _ _ _ _ _ _ _ __ _ .__.~ .. , . _ . . . _ _ __ _ .. _ .. .... . . _ _ _ . _ , . . - - . _ _ _ . . ._ _ . . _ . _ . _ . . _ _ _ . _ . _ __ .. _ _ _ _ _ . _ _ . ~
QUAD CITIES Revision 1.0 January 1994 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-137 Downwind Controlled ElevatedtStack) Release Mixed Mode (Vent) Release Ground Level Release SBAR Radius V VBAR Radius G GBAR Direction Area Bocnd Radius S (meters; (meters) (mrad /yr)/(uct/sec) (meters) (mrad /yr)/(uct/sec) (meters) (mrad /yrl/tuct/sec) 300. 300. 3.700E-04 3.581E-04 300. 1.124E-03 1.088E-03 300. 3.439E-03 3.327E-03 N NNE 300. 300. 4.473E-04 4.33OE-04 300. 1.283E-03 1.241E-03 300. 3.916E-03 3.789E-03 325. 325. 2.955E-04 2.861E-04 325. 7.857E-04 7.604E-04 325. 3.145E-03 3.043E-03 NE 1210. 1210. 3.536E-05 3.423E-05 1210. 7.773E-05 7.523E-05 1210. 1.371E-04 1.327E-04 ENE E 1170. 1970. 5.014E-05 4.854E-OS 1170. 1.280E-04 1.239E-04 1170. 2.375E-04 2.299E-04 1125. 1125. 7.243E-05 7.011E-05 1125. 1.63tE-04 1.578E-04 1125. 3.022E-04 2.924E-04 ESE 475. 475. 2.037E-04 1.972E-04 475. 4.822E-04 4.667E-04 475. 1.172E-03 1.134E-03 SE 475. 475. 1.449E-04 1.403E-04 475. 3.122E-04 3.022E-04 475. 8.078E-04 7.816E-04 SSE 1.292E-03 1.250E-03 325. 1.899E-04 1.839E-04 325. 4.252E-04 4.stSE-04 325. 5 325. 55W 325. 325. 1.663E-04 1.610E-04 325. 4.115E-04 3.982E-04 325. 1.475E-03 1.427E-03 SW 250. 250. 2.847E-04 2.756E-04 250. 8.031E-04 7.792E-04 250. 3.244E-03 3.138E-03 WSW 200. 200. 3.814E-04 3.692E-04 200. 1.321E-03 1.279E-03 200. 5.309E-03 5.137E-03 W 200. 200. 4.285E-04 4.148E-04 200. 1.485E-03 1.437E-03 200. 6.737E-03 6.518E-03 200. 200. 3.849E-04 3.726E-04 200. 1.571E-03 1.520E-03 200. 8.876E-03 8.587E-03 WNW 200. 4.310E-04 4.172E-04 200. 1.463E-03 1.415E-03 200. 7.069E-03 6.839E-03 NW 200. 200. 200. 4.686E-04 4.536E-04 200. 1.711E-03 1.656E-03 200. 7.311E-03 7.073E-03 NNW Ouad Cities Site Meteorological Data 1/78 - 12/87 F 16
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C.UAD CITIES Revision 1.0 January 1994 Table F-7a (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Ar-41 Downwtrd Controlled Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Directton Area Bound Radius 5 SBAR Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) (meters) 1 mradlyrd /( uC 1/ sec ) N 300. 300. 2.602E-03 2.519E-03 300. 8.480E-03 8.209E-03 300. 3.703E-02 3.585E-02 NNE 300. 300. 3.254E-03 3.150E-03 300. 9.298E-03 9.OOOE-03 300. 3.685E-02 3.567E-02 NE 325. 325. 2.263E-03 2.190E-03 325. 6.288E-03 6.087E-03 325. 3.538E-02 3.424E-02 ENE 1210. 1210. 4.650E-04 4.501E-04 1210. 1.272E-03 1.231E-03 1210. 4.905E-03 4.748E-03 E 1170. 1170. 5.748E-04 5.564E-04 1170. 1.782E-03 1.725E-03 1170. 6.371E-03 6.167E-03 ESE 1125. 1125. 7.790E-04 7.541E-04 1125. 2.062E-03 1.996E-03 1125. 6.487E-03 6.280E-03 SE 475. 475. 1.609E-03 1.557E-03 475. 3.895E-03 3.770E-03 475. 1.269E-02 1.228E-02 SSE 475. 475. 1.199E-03 1.161E-03 475. 2.684E-03 2.598E-03 475. 8.994E-03 8.706E-03 5 325. 325. 1.464E-03 1.417E-03 325. 3.250E-03 3.146E-03 325. 1.311E-02 1.269E-02 SSW 325. 325. 1.298E-03 1.257E-03 325. 3.173E-03 3.072E-03 325. 1.524E-02 1.475E-02 SW 250. 250. 2.046E-03 1.981E-03 250. 5.695E-03 5.513E-03 250. 3.093E-02 2.994E-02 WSW 200. 200. 2.652E-03 2.567E-03 200. 8.799E-03 8.518E-03 200. 4.4BOE-02 4.337E-02 W 200. 200. 2.955E-03 2.860E-03 200. 9. 972E -03 9. (>52 E -03 200. 5.769E-02 5.584E-02 WNW 200. 200. 2.656E-03 2.571E-03 200 1.094E-02 1.059E-02 200. 7.694E-02 7.448E-02 NW 200. 200. 2.947E-03 2.853E-03 200. 1.016E-02 9.831E-03 200. 6.515E-02 6.306E-02 NNW 200. 200. 3.150E-03 3.049E-03 200. 1.183E-02 1.145E-02 200. 6.780E-02 6.563E-02 Quad C1ttes Site Meteorological Data 1/78 - 12/87 F-38 9 . . . 9 9. .
i 8 QUAD CITIES Revision 1.0 January 1994 '. O tj Table F-8 - Parameters for Calculations of N-16 Skyshine Radiation l From Quad Cities Location Activity Occupancy Occupancy Shielding Distance Number . Hours Factor Factor R. k Orif O F, SF, (m) 1 Living at home 8160 0.93 0.7 800 6 (nearest resident) 2 Fishing 50 0.005 1.0 140' 3 Fishing 50 0.005 1.0 170* f 4 Fishing 100 0.01 1.0 200" t 5 Fishing 400 0.05 1.0 400*
-== ,
K = 3.80E-05 mrem /(MWe-br) D U These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of ' the public using Equation A-34 in Appendix A. If desired, more realistic parameters could be used in place of these to refine the estimate. For example, one could determine whether the nearest resident really fishes the specified number of hours at the specified locatior. The amount of time in a year that a maximally exposed fisherman would spend fishing near the site is estimated as 12 hours per week for 8 months per year. This yields an estimate of: [12 hours / week) [(8 months /yr)/(12 months /yr)) x [52 weeks /yr] = 416 hours /yr The remaining time is assumed to be spent at the nearest residence. Distance to nearest residence (See Table F-3). Es'imated from a drawing of the site.
* ~
The OF,is the quotient of the number of hours a location is occupied and the number of hours in a year. Thus OH/8760 hours = OF, rounced to the 0.01 digit. i t O ! F-39
F QUAD CITIES Revision 1.0. January 1994: SupplementalTable A Elevated Level Joint Frequency Distribution Table Summary 296 FOOT Elevation Data Summary Table of Percent by Direction and Class ENE ESE SE SSE S SSW SW WSW W WNW NW NNW Total Class N NNE NE E A .076 .064 .045 .031 .086 .064 .164 .192 .236 .574 .211 .229 .457 .571 .360 .179 3.541
.060 .050 .064 .129 .189 .249 .385 .183 .199 .273 .324 .218 .158 2.690 8 .060 .075 .073
.185 .155 .151 .151 .168 .343 .391 .529 .312 .281 478 .658 .440 .309 4.832 C .147 .136 2.669 2.152 2.062 2.103 2.755 3.314 2.630 2.527 3.654 5.503 4.501 3.027 47.006 D 2.472 2.105 2.729 2.803 E 1.175 1.004 1.363 1.533 1.992 1.651 1.775 2.131 3.111 3.193 2.229 1.520 1.773 1.916 1.871, 1.219 29.457
.324 .324 .601 .815 .936 .979 1.128 1.010 .593 .365 .352 469 .397 .353 9.200 F .287 .267
.060 .083 .117 .168 .400 .517 .574 482 .294 .136 .111 .097 .076 .045 3.273 G .042 .069 4.989 5.666 5.066 5.634 6.454 8.445 9.487 6.453 5.258 7.097 9.538 7.864 5.291 100.000 Total 4.260 3.720 4.778 Summary Table of Perce..t by Directton and Speed SE SSE S SSW SW WSW W WNW NW NNV Totat Speed N NNE NF ENE E ESE
.013 .007 .005 .002 .004 .005 .000 .006 .001 .000 .003 .005 .082 45 .008 .009 .010 .005 1.05 .021 .025 .025 .035 .029 .023 .029 .026- .022 .032 .038 .038 041 .038 .031 .031 .485 182 .196 .192 .2 18 .199 .220 .190 .208 .325 .397 .299 .221 .239 .193 .188 3.650 2.05 .182 3.05 .428 .366 451 407 .441 .406 .453 .384 .434 .787 .752 .473 .478 .500 .481 .393 7.632
.552 .561 .627 .643 .624 .596 .598 .608 .643 1.136 .897 .589 .563 .636 .680 .681 10.634 4.05 .801 13.043 5.05 .684 .649 .752 .722 .803 .664 .756 .759 .831 1.264 1.130 .674 .692 .885 .977
.602 .725 .749 .939 712 .913 .967 1.229 1.448 1.130 .812 .948 1.248 1. 199 1.029 15.361 6.05 .712 8.05 1.143 .796 1.190 1.247 1.481 1.515 1.714 2.013 2.538 2.516 1.459 1.341 2.022 2.883 2.324 1.494 27.676
.363 .314 .548 .611 .653 .671 .793 .979 1.544 1.250 464 .588 1.254 1.004 1.347 .514 13.697 10.05 13.05 149 .173 .218 .324 .375 .245 .141 .440 .866 .596 .144 .321 .653 1.078 .568 .136 6.428 18.00 .016 .042 .035 .054 .086 .028 .013 .084 .123 .125 .042 .116 .212 .218 .062 019 1.276 99.00 .001 001 .000 .000 .001 .000 .000 .001 .003 .004 .000 .003 .012 .009 .000 .000 .037 4.989 5.666 5.066 5.634 6.454 8.445 9.487 6.453 5.258 7.097 9.538 7.864 5.291 100.000 Total 4.260 3.720 4.778 NOTE: Wind directions in tables are presented in " wind from" and not " wind to" direction.
F-40
y ..; QUAb-mTIES Revision 1.0 January 1994 SupplementalTable A-Continued Elevated Level Joint Frequency Distrb1 tion Table Summary 296 FOOT Elevation Data Summary 7able of Percent by Speed and Class .
"~
Class A B C D E F G Speed 45 .000 .006 .003 .016 .031 .019 .007 1.05 .003 .006 .006 .158 .170 .089 .053 2.05 .066 .045 .119 1.692 1.012 .478 .237 3.05 .176 .185 .308 3.840 1.925 .777 422 4.05 .289 .299 .522 5.012 2.924 1.105 484 5.05 .369 .362 .716 5.799 3.931 1.367 498 6.05 .571 .400 .736 6.691 4.835 1.596 .532 8.05 .998 .718 1.272 12.230 8.759- 2.859 .841 10.05 .588 .391 .661 7.034 4.032 .804 .186 13.05 .391 .214 .385 3.767 1.557 .100 .013 18.00 .085 .056 .101 .753 .274 .007 .000 99.00 .006 .009 .004 .012 .006 .000 .000 1 F-41 _ _ - . - _ _. .. _ . ~ . _ _ _ _ - . . .- ., . _ _ _ __
r OUAD CITIES Revision 1.0 January 1994 SupplernentalTable B Mixed Mode Joint Frequency Distribution Table Summaries Summary Table of Percent by Direction and Class 196 Foot Elevation Data Class N NNE NE ENE E ESE SE SSE 5 SSW SW W5W W WNW NW NNW Total A .158 .151 .168 .127 .107 .161 .192 .324 .365 .741 .187 .212 416 .453 .539 .252 4.552 B .049 .044 .070 .046 .043 .007 .073 .068 .100 .212 .080 .060 .117 .177 t.156 .078' 1.459 C .130 .135 .172 .194 .185 .164 .170 .211 .283 .494 .269 .242 .395 .421 .350 .247 4.063 0 1.397 1.290 1.866 2.073 1.889 1.508 1.388 1.441 1.735 2.308 1.967 1.899 2.881 3.767 2.712 1.908 32.028 E 1.025 .905 1.323 1.778 2.029 1.551 1.643 1.947' 2.558 3.048 2.280 1.841 2.437 2.656 *2.102 1.157 30.281 F .342 .319 .433 .501 .726 .863 .776 .936 1.291 1.051 .506 .337 415 ;475 " '.374 .311 9.655 G .125 .127 .167 .203 .380 .598 .843 .980 .955 .767 .306 .174 .203 .148 .102 .118 6.196 Total 3.225 2.970 4.200 4.922 5.359 4.932 5.086 5.907 7.287 8.620 5.596 4.765 6.865 8.097 6.334 4.071 88.234 Summary Table of Percent by Directton and Speed Speed N NNE NE ENE E ESE SE SSE 5 SSW SW W5W W WNW NW NNW Total 45 .006 .015 .006 .006 .006 .006 .008 .010 .012 .008 .018 .009 .002 .015 .000 .006 131 1.05 .046 .035 .064 .050 .048 .062 .058 .079 .060 .075 .097 .064 .054 .064 .052 .050 .959 2.05 .305 .265 .255 .356 .348 .342 .367 .391 .385 .621 .719 .499 .445 .383 .362 .331 6.372 3.05 .520 .477 .702 .680 787 .767 .699 .711 .744 1.289 1.295 .769 .790 .792 .810 .607 12.440 4.05 .761 .665 769 .981 .975 .886 1.081 1.172 1.228 1.725 1.389 1.000 1.217 1.191 1.132 .809 16.983 5.05 .607 .611 .848 .963 1.069 1.014 1.116 1. 138 1.376 1.673 .991 .912 1.308 1.603 1.240 .796 17.265 6.05 426 .372 .645 .684 .801 .760 .850 .899 1.266 1.303 .563 .631 1.099 1.435 1.024 .656 13.415 8.05 .412 .399 .650 .832 .821 .782 .721 .953 1.406 1.337 .453 .603 1.272 1.745 1.208 .643 14.237 10.05 .113 .086 .226 .302 .389 .249 .147 .417 .661 .520 .056 .220 .509 .702 412 156 5.165 13.05 .028 .045 .034 .068 .til .064 .036 .133 .144 .068 .014 .053 .160 .163 .094 .016 1.232 18.00 .009 .000 .002 .001 .003 .000 .000 .004 .004 4001 .001 .005 .008 .004 .000 .001 .034 99.00 .000 .000 .000 .000 .000 .000- .000 .000 .000 .000- .000 .000 .000 .000 .000 .000 .000 Total 3.225 2.970 4.200 4.922 5.359 4.932 5.086 5.907 7.287 8.620 5.596 4.765 6.865 8.097 6.334 4.071- 88.234 NOTE: Wind directions in tables are presented in " wind from" and not " wind tO" direction. In Order 10 determine the final mixed mode values,88.234% of the elevated value (presented in the 296 FT Mixed Mode table) and 11.766% Of the ground level value (presented in the 33 FT Mixed Mode table) are used to calculate the final values. F-42 O O O. .
k: h
. . QUAb u(TIES V Revision 1.0" A'uary 1994-Supplemental Table B - Continued Mixed Mode Joint Frequency Distribution Table Summaries 196 FOOT Elevation Data Summary Table of Percent by Speed and Class Class 'A B 'C D E F G '
Speed , ,_ 45 .000 .000 .000 .023 .056 .0 14 .039 1.05 .002 .002 .008 .249 .307 .166 .224 2.05 .089' .050 .184 2.680 1.748 .785 .837 3.05 . 358 .180 .684 4.451 3.666 1.724 1.378 4.05 . 794 .331 .869 5.305 .5.832 2.387- 1.466 5.05 - .885 .309 .724 5.544 6.119 2.367 1.317 6.05 . 850- .190 .640 4.731 4.847 1.458 .699 8.05 1.026 .281 .610 5.969 5.482 .655 . 216 10.05 .459 .102 .267 2.423 1.798 .096 . 020 13.05 .089 .014 .077 .636 411 .004 . 000 18.00 .001. .000 .000 .018 015 .000 .000
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QUAD CITIES Revision 1.0 - January 1994 Supplemental Table C Ground Level Joint Frequency Distribution Table Summary Sumary 7abte of Percent by Direct ton and Class Class N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total A .180 .185 .133 .155 .133 .224 .243 .352 .363 .856 .294 .247 .556 .539 .516 .303 5.280 B .058 .058 .071 .048 .044 .095 .093 .079 .087 .222 .122 .083 .164 .180 .168 .085 1.658 C .151 .189 .195 .201 .187 .195 .211 .220 .267 .527 .350 .313 .454 .527 .342 .253 4.582 D 1.614 1.666 1.966 2.403 2.014 1.814 1.586 1.537 1.562 2.410 2.476 2.451 3.540 4.726 2.898 2.124 36.786 E .946 1.011 1.561 2.128 2.275 2.129 1.985 2.335 2.585 3.085 2.739 2.277 3.197 3.168.-1.953 1.169 34.543 F .255 .383 .631 .574 .863 1.222 1.085 1.175 1.016 .718 491 403 .619 .564 .296- .227 10.523 G .088 .151 .205 .279 .886 1.841 .863 .691 .457 .212 .246 .126 .265 .175 .082 .O68 6.628 Total 3.291 3.644 4.763 5.788 6.402 7.519 6.065 6.389 6.337 8.030 6.712 5.900 8.795 9.879 6.255 4.229 100.000 Summary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total
.45 .047 .055 .086 .089 .083 .095 .132 .146 .115 .070 .123 .083 .073 .068 .054 .039 1.358 1.05 .214 .257 .417 .419 .723 .991 .860 .898 .730 .593 .782 .583 .504 .394 .214 .172 8.753 2.05 .612 .713 1.138 1.109 f.629 2.537 1.901 1.965 1.826 1.789 2.096 1.700 1.967 1.611 .987 .663 24.241 3.05 .713 .825 1.061 1.281 f.341 1.609 f.443 1.476 1.601 2.434 2.038 1.534 2.336 2.005 1.285 .935 23.916 4.05 .624 .701 .875 1.103 .983 .881 .925 .985 1.051 1.814 1.041 .974 1.629 1.905 1.395 .974 17.860 5.05 489 473 .576 .719 .607 .595 .429 .481 .576 .881 .452 .493 1.008 1.617 1.034 .751 11.259 6.05 .265 .323 .317 .471 .454 446 .257 .278 .305 .299 .124 .296 .632 1.188 .717 .437 6.808 8.05 .263 .205 .238 .504 .481 .296 .102 .153 .124 .133 .037 .133 .413 .910 '.504 .228 4.723 10.05 .056 .085 056 .091 .073 .064 .012 .008 .010 .015 .019 .091 .114 .170 .066 .027 .956 13.05 .008 .008 .000 .002 .029 .006 .004 .000 .000 .000 .000 .O14 .035 .012 .000 .004 .120 18.00 .000 .000 .000 .000 .000 .000 .000 .000 OOO .000 .000 .000 .006 .000 000 .000 .006 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 Total 3.291 3.644 4.763 5.788 6.402 7.519 6.065 6.389 6.337 8.030 6.712 5.900 8.795 9.879 6.255 4.229 100.000 NOTE: Wind directions in tables are presented in " wind from" and not " wind tO" direction.
F-46 O O O. .
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(' ~ ~ v QU Al.>mtflES V Revision t.0 January 1994 Supplemental Table C - Cont'lued a Ground Level Joint Frequency Distrbution Table Summary 33 Foot Elevation Data Sumary Table of Percent by Speed and Class
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Class A B C D E F G Speed
.45 .000 .000 .002 .056 .299 .375 .626 i I
1.05 .041 .012 .054 .902 2.390 2.569 2.786 2.05 439 .158 .553 5.844 9.138 5.363 2.747 3.05 1.285 .481 1.321 8.821 9.831 1.773 . 4H 4.05 1.544 .462 1.109 8.235 6.180 .307 .b-5.05 1.012 .255 .765 '5.683 3.435 .097 .0 2 6.05 .618 .182 .388 3.856 1.721 .017 .025 8.05 .313 .089 .328 2.755 1.215 .017 .006 10.05 .027 .017 .058 .556 .294 .004 .000 13.05 .002 .002 .004- .077 .035 .000 .000 18.00 .000- .000 .000 .000 .006 .000 .000 99.00 .000 .000 .000 .000 .000 .000 .000 F-47 C- - - _- - . .. . .
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