ML20063F896
| ML20063F896 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 01/31/1994 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| PROC-940131-02, NUDOCS 9402150220 | |
| Download: ML20063F896 (100) | |
Text
{{#Wiki_filter:r -] 8 i- .1 ERAIDWOOD Revision 1.0
- .*- -January 1994 .; -:y .
j 1
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[ BRAIDWOOD ANNEX INDEX ; I i PAGE RT:' VISION ; CHAPTER 10 10-i 1.0 10-11 1.0 10-iii .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 l ') - 5 1.O I 10-6 1.0 10-7 1.0 ' 10-8 1.0 ' 10-9 1.0 10-10 1.0 ! 10-11 1.0 t 10-12 1.0 10-13 1.0 10-14 1.0 10-15 1.0 10-16 1.0
-17 1.0 ,
10-18 1.0 10-19 1.0 l t l l I e i e V-L 0\ 1100.1.'8 10-i 9402150220 940131 PDR ADDCK 05000456 P PDR ..a
e 1 1 BRAIDWCOD Revision 1.0 l January 1994 - CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS ; 10.1 AIRBORNE RELEASES . . . . . . . 1 , l
- 1. System Description . . . . . . . 1 !
- 1. Waste Gas Holdup System '
. . . 1
- 2. Ventilation Exhaust Treatment System . . . 1
- 2. Radiation Monitors . . . . . . . . . 1
- l. Auxiliary Building Vent Effluent Monitors . 1
- 2. Containment Purce Effluent Monitors . . . . 2
- 3. Waste Gas Decay Tank Monitors . . . 2
- 4. Gland Steam and Condenser Air Ejector Monitors 2
- 5. Radwaste Building Ventilation Monitor . . 3
- 6. Component Cooling Water Monitor . . . 3
- 7. Miscellaneous Ventilation Monitors 3 i
- 3. Alarm and Trip Setpoints . . . . . . . . 3
- 1. Setpoint Calculations . . . . . . . 3 :
- 1. Auxiliary Building Vent Effluent Monitors 3 !
- 2. Containment Purge Effluent Monitors . . . 4
- 3. Waste Gas Decay Tank Ef tluent Monitors 4 f
- 4. Component Cooling Water Monitors . . . 4
- 2. Release Limits . . . . . . 4
- 3. Release Mixture . . . . . . 5 ,
- 4. Conversion Factors . . . . . . . . . . 5 '
- 5. HVAC Flow Rates . . . . . . . . . . . 5 4 Allocation of Effluents from Common Release Points 5 ,
l
- 5. Dose Projections for Batch Releases . . . . . 6 l
l l O 10-11
- s-L -
BF%IDWOOD - Revision 1.0
' January 1994 i
CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING i: i TABLE OF CONTENTS l 10.2 LIQUID RELEASES . . . . . . . . . . . . .. . . . . . . . . 6
- 1. System Description . . . . . . . . . . . . . . . . 6 j.
- 1. Release Tanks . . . . . . . . . . . . . . . 6
- 2. Radiation Monitors . . . . . . . . . . . . . 6
- 1. Liquid Radwaste Effluent Monitors . . . . . . . 6
- 2. Station Blowdown Monitor . . . . . . . . . . . . 6
- 3. Reactor Containment Fan Cooler (RCFC) and Essential Service Water (ESSW) Outlet Line Monitors . . . J7
- 3. Alarm ar.d Trip Setpoints . . . . . . . . . . . . . 7
- 1. Setpoint Calculation . . . . . . . . . . . 7
- 1. Liquid Radwaste Effluent Monitor . . . . . . 7
- 2. Station Blowdown Monitor . . . . . . . . . 7
- 2. Discharge Flow Rates . . . . . . . . . . . . . . 8
- 1. Release Tank Discharge Flow Rate . . . . . . 8
- 3. Release Limits . . . . . . . . . . . . . . . 8
- 4. Release Mixture . . . . . . . . . . . . . . . . 9
- 5. Conversion Factors . . . . . . . . . . . . 9
- 6. Liquid Dilution Flow Rates . . . . . . . . . . . 9-
) 4. Allocation of Effluen e from Common Release Points . . 9
- 5. Projected Concentrations for Releases . . . . . . . . . 9
-10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . . . . . . 11 O t 10-iii ai - - _ - - _ - _ _ - - - _
BRAIDWOOD Revision 1.O January 1994 - CHAPTER 10 , LIST OF TABLES 1RMPER PAGE 10-1 Assumed Composition of the Braidwood Station Noble Gas Effluent 10-12 10-2 Assumed Composition of the Braidwod l Station Liquid Effluent 10-13 l l ( O i i O 10-iv t _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ - _ - . _ _ _ _ _ _ _ __ _
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.h E BRAIDWOOD Revision 1.0 ) ~
January 1994 : si t I CHAPTER'10 LIST OF FIGURES l NUMPER M
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10-1 Simplified HVAC and Gaseous Effluent Flow Diagram 10-14 1 10-2 Sirplified Liquid Radwaste Processing Diagram 10-16
- 10-3 Simplified Liquid Effluent Flow Diagram 10-17 !
10-4 Simplified Solid Radwaste Processing Diagram 10-18 , f
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BRAIDWOOD Revision 1.0 January 1994 ' CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified HVAC and gaseous effluent flow diagram is provided in Figure 10-1. The principal release points for potentially radioactive airborne effluents are the two auxiliary building vent stacks (designated Unit 1 Vent Stack l and Unit 2 Vent Stack in Figure 10-1). In the classification scheme of Section 4.1.4, each is classified as a vent release point (see Table A-1 of Appendix A). i 10.1.1.1 Waste Gas Holdup System i The waste gas holdup system is designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system off-gases from the reactor coolant system and providing for delay or holdup to reduce the total radioactivity by radiodecay prior to release to the l' environment. The system is described in Section 11.3.2 of the Byron /Braidwood UFSAR. 10.1.1.2 Ventilation Exhaust Treatment System J ' . Ventilation exhaust treatment systems are designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in gaseous effluents by passing , ventilation or vent exhaust gases through HEPA filters (and j charcoal adsorbers when required to mitigate potential i iodine releases) 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 l 10.1.2.1 Auxiliary Building Vent Effluent Monitors l
- Monitors 1RE-FR028 (Unit 1) and 2RE-PR028 (Unit 2) j continuously monitor the final effluent from the auxiliary
- building vent stacks.
Both vent stack monitors feature automatic isokinetic sampling, grab sampling, and tritium sampling. i j 10-1 a
. -_ . .. - . .. ~ - , .- , . . s .. 5; I
BRAIDWOOD- Revision l'0, January 1994' In normal operation all three noble gas channels '( low , mid- l range, high) are on line and active. On a high alarm the. -i low and mid-range noble gas channels are closed and only the .:
'high range noble gas channel remains active. The. iodine and. ]
particulate channels, however, continue to operate under all- ; conditions. l
?
No automatic isolation or control functions are performed by these monitors. Pertinent information on these monitors is . provided in Byron /Braidwood UFSAR Table 11.5-1.
;{
. t 10.1.2.2 Containment Purge Effluent Monitors
- I Monitors 1RE-PR001 (Unit 1) and 2RE-PR001 - (Unit 2) !
continuously monitor the effluent from the Unit 1 and UnitL2 containments, respectively. When airborne radioactivity'in the containment. purge effluent stream exceeds a specified .; level, station personnel will follow established procedures i to terminate the release by manually activating the containment purge valves. Additionally, the auxiliary . building vent effluent monitors provide an independent; l redundant means of monitoring the containment purge i effluent. j No automatic isolation or control functions are performed by ; these monitors. Pertinent information on these monitors is provided in l Byron /Braidwood UFSAR Table.11.5-1. Area Radiation Monitors 1(2) RE-AR011 and 1(2) RE-ARO12 :) monitor the containment atmosphere. on.high alarm during a [ containment purge, these monitors will automatically. '! terminate the purge. ! 10.1.2.3 Waste Gas Decay Tank Monitors - Monitors ORE-PR002A/B continuously. monitor the noble gas > activity released from the gas decay tanks. , on high alarm, the monitors automatically initiate closure ; of the valve OGWO14 thus terminating the release. , Pertinent information on these monitors and associated control devices is provided in Byron /Braidwood UFSAR Table 11.5-1. 10.'1.2.4 Gland Steam and Condenser Air Ejector Monitors Monitors 1RE-PR027 and 2RE-PR027 continuously monitor the ; condenser air ejector gas from Units 1 and 2, respectively. 1 on high alarm 1(2)RE-PR027 initiates startup of the offgas j treatment system. , I 10-2 !
]
l BRAIDWOOD Revision 1.0 January 1994 ! Pertinent information on these monitors is provided in O Byron /Braidwood UFSAR Table 11.5-1. ' 10.1.2.5 Radwaste Building Ventilation Monitor Monitor ORE-PR026 continuously monitors radioactivity in the radwaste building ventilation system. No control device is initiated by this channel. ' Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-1. 10.1.2.6 Component Cooling Water Monitor Monitors ORE-PR009 (common), 1RE-PR009 (Unit 1), and 2RE-PR009 (Unit 2) continuously monitor the component cooling water heat exchanger outlets. On high alarm ORE-PR009 initiates closure of both component cooling water surge tank (CCWST) vents, 1RE-PR009 initiates closure of the Unit 1 CCWST vent, and 2RE-PR009 initiates closure of the Unit 2 CCWST vent. Pertinent information on this monitor is provided in Byron /Braidwood UFSAR 1able 11.5-1.
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10.1.2.7 Miscel- neous Ventilation Monitors Monitor ORE-PR003 continuously monitors radioactivity in the ventilation exhaust from the laboratory fume hoods. No control device is initiated by this channel. Pertinent information on this monitor and associated devices is provided in Byron /Braidwood UFSAR Table 11.5-1. 10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Auxiliary Building Vent Effluent Monitors The setpoints for the low range noble gas channel are conservatively established at 5% of the maximum permissible station release rate for the high alarm and 1/2% of the maximum release rate for the alert alarm. The setpoints for the high range noble gas channel are conservatively established at 50% of the maximum permissible rtatien release rate for the high alarm and 25% of the maximum release rate for the alert alarm. 1 4 ei . 10-3 j i k
~ , -.~ ... . . .. - b BRAIDWOOD Revision 1.0 January 1994- ;
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( 10.1.3.1.2 Containment ' Purge-Effluent Monitors The setpoints are-established at 1.50 times theLanalyzed j containment noble gas activity during purge, .plus the : background reading of the monitor prior to purge. 10.1.3.1.3 Waste Gas Decay. Tank Effluent Monitors The setpoints are established at 1.50 times the analyzed l waste gas tank activity during release. j
.i 10.1.3.1.4 Component Cooling Water Monitors The setpoint is based on the radionuclide mix in Table 10-1. -!
The total calculated detector response is divided by'2 to' : obtain-the final setpoint. (See section 10.2.3.5 for.the l conversion factor). -{ 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 limits are found by solving
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Equations 10-1 and 10-2 for the total allowed release rate of vent releases, Qw. ! i (1.11)D3 [{Tf,) s 500 mrem /yr (10-1) {
'l 0,, { { (f,) IE(X/0), exp (-A,R/3 600u,) (10-2)
+ 1.11 V,i ) < 3 000 mrem /yr -
{ The summations are over noble gas radionuclides i.. 13 Fractional Radionuclide Composition i The release rate of noble gas radionuclide i-divided by i the total release rate of all noble gas radionuclides. i Qe, Total Allowed Release Rate, (pCi/sec) Vent Release .; i The total allowed release rate of all noble gas radionuclides released as vent releases, exp (-1 R/3600Uy ) is set equal to 1.0 for 3 setpoint calculations. 10-4 i l
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i BRAIDWOOD Revision 1.0 January 1994 - The remaining parameters in Equation 10-1 have the same definitions as in Equation A-8 of Appendix A. The remaining G, parameters in Equation 10-2 have the same definition as in Equation A-9 of Appendix A. Equation 10-1 is based on Equation A-8 of Appendix A and the , RETS restriction on whole body dose rate (500 mrem /yr) due ! to noble gases released in gaseous effluents (see Section A.1.3.1 of Appendix A). Equation 10-2 is based on Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.1.3.2 of Appendix A). Since the solution to Equation 10-2 is more conservative than the solution to Equation 10-1, the value of Equation 10-2 (3. 09 x 10' pCi/ sec) is used as the limiting noble gas release rate. During evolutions involving releases from the containment or waste gas decay tanks, the release rate from-each release path is procedurally limited to 1 x 10' pCi/sec (less than 1/3 the maximum permissible station release rate). Calibration methods and surveillance frequency for the monitors will be conducted as specified in the RETS. 10.1.3.3 Release Mixture In the determination of alarm and trip setpoints, the radioactivity mixture in exhaust air is assumed to have the radionuclide composition of Table 10-1. 10.1.3.4 Conversion Factors The response curves used to determine the monitor count rates are based on the sensitivity to Xe-133 for conservatism. , 10.1.3.5 HVAC Flow Rates The plant vent stack flow rates are obtained from 1/2 PR2BJ. However, if the readout indicates "0" flow, the following minimum rated fan flow values are currently used: Unit 1 - 6.15 x 10' cc/sec Unit 2 - 4.55 x 106 cc/sec 10.1.4 Allocation of Effluents from Common Release points Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation systems and the gas decay tanks are comprised of contributions from both units. Consequently, allocation is made evenly between units.
\
10-5
.- - . . - _ . - .~ . .-- - . . - _ .
ll
.t BRAIDWOOD _ Revision'1.0 "O ' January 1994 l
- i
) 10.1'. 5_ Dose Projections-for Batch Releases l
J Dose. projections are not made prior-to release. Doses are: calculated'atter purging the containment or venting the ';
~ waste gas decay tanks. Per procedure, representative ..
samples are obtained and analyted, and the doses calculated on a monthly basis to verify compliance with 10CFR50. !
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10.2 LIQUID RELEASES 10.2.1 System Description A simplified liquid effluent flow diagram is provided in Figure ~10-3. A simplified liquid waste processing diagram is provided in Figure 10-2. 1 The liquid radwaste treatment. system is designed and .! installed to reduce radioactive liquid ef fluents by -! collecting the liquids, providing for retention or holdup, j and providing for. treatment by demineraliter or a ' concentrator for the purpose of reducing the total' .; radioactivity prior to release to the environment. The :! system is described in Section 11.2.2 of the Byron /Braidwood j Updated Final Safety Analysis Report. , l 10.2.1.1' Release Tanks i There are two radwaste release tanks (OWX01T - 33,100' gallon -l 1 capacity, and OWX26T - 33750 gallon-capacity) which receive liquid waste before discharge to the Kankakee' river. ; 4 10.2.2 Radiation Monitors ; 10.2.2.1 Liquid Radwaste Effluent Monitors Monitor ORE-PR001 is used to monitor.all releases from the release tanks. On high alarm, the monitor automatically, initiates closure of. valves OWX-353 and~OWX-896 to terminate
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the release. Pertinent information on the monitor and associated control ! devices is provided in Byron /Braidwood UFSAR Table 11.5-2.
.1 01. 2 . 2 . 2 Station Blowdown Monitor ,
-l Monitor ORE-PRO 10 continuously monitors the circulating water blowdown. No controlLdevice is initiated by this channel.
Pertinent information on this monitor is provided in g Byron /Braidwood UFSAR. Table 11.5-2. ; 1 l 9 1 i 10-6
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BRAIDWOOD Revision 1.0 January 1994 10.2.2.3 Reactor Containment Fan Cooler (RCFC) and Essential Service O' Water (ESSW) Outlet Line Monitors Monitors 1RE-PR02, 2RE-PR002, 1RE-PR003, and 2RE-PR003 continuously monitor the RCFC and ESSW outlet lines. No control device is initiated by these channels, Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-2. 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of RETS and 10CFR20 are not exceeded in the unrestricted area. 10.2.3.1.1 Liquid Radwaste Effluent Monitor During release the setpoint is established at 1.5 times the analyzed tank activity plus the background reading. 10.2.3.1.2 Station Blowdown Monitor The monitor setpoint is found by solving equation 10-3. P s C# + (1.25 x C) x (Fi, / (FN + Fi,)) (10-3) ' 1 P Release Setpoint [pCi/ml] 1.25 Factor to account for minor fluctuations in count rate. C" Concentration of activity in the [pci/nJ) circulating water blowdown at the time of discharge. (" Background reading") . C7 Analyzed activity in the release tank [pci/ml] F" Circulating Water Blowdown Rate [gpm] O 10-7
BRAIDWOOD Revision 1^.0 January 1994 e Ei, Maximum Release Tank Discharge Flow Rate [gpm) The flow rate from the radwaste discharge-tank. i 10.2.3.2 Discharge Flow Rates 10.2.3.2.1. Release Tank Discharge Flow Rate - Prior to each batch release, a grab sample is.obtained. j. The results of the analysis of the waste sample determine the discharge rate of each batch as follows: F/,, = 0. 5 (Ffn/{ (C[/10 *DWC;) ) (10-4) The summation.is over radionuclides 1. 0.5 Factor for conservatism 1 EL, Maximum Permitted Discharge Flow Rate [gpm] i The maximum permitted flow rate from the radwaste discharge tank based on radiological limits (not chemistry limits which may.be more restrictive) i Ffu Circulating Water Blowdown Rate- [gpm] I C[ Concentration of Radionuclide i in [pCi /mi ] ~ ! the Release Tank ! The concentration of radioactivity-in l the radwaste discharge tank based on 'l measurements of a sample drawn from the tank. DWC 3 Derived Water Concentration [pC1/ml]. of Radionuclide i The concentration of radionuclida i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402. 10 Multiplier I 10.2.3.3 Release Limits Release limits are determined from RETS. Discharge rates and setpoints are adjusted to ensure that 50% of applicable RETS are not exceeded. (See section 10.2.3.2) 1 10-8
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BRAIDWOOD Revision 1.0 " January 1994 10.2.3.4 Release Mixture For monitors ORE-PR001 and ORE-PRO 10 the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis or the mix in Table 10-2. For monitors 1RE-PR001, 1RE-PR002, 2RE-PR001, and 2RE-PR002,
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the release mixture is the radionuclides which are listed in Table 10-2. Each nuclide in the mix is at a concentration which is 10% of the RETS value given in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402. 10.2.3.5 Conversion Factors
- The readouts for the liquid effluent monitors are in pCi/nl.
The cpm to pCi/nd conversion is based on the detector sensitivity to Cs-137. 10.2.3.6 Liquid Dilution Flow Rates Dilution flow rates are obtained from circulating water blowdown transmitter loop OFT-CWO32. 10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from either release tank (OWX0lT or OWX26T) are comprised of contributions from ' both units. Under normal operating conditions, it is - difficult to apportion the radioactivity between the units. Consequently, allocation is made evenly between units. 10.2.5 Projected Concentrations for Releases After determining Fi,from Equation 10-4, RETS compliance is verified using Equations 10-5 and 10-6. Cf = C((Fi,/ (Fi, + Ffa ) ) (10-5)
}] { Cf /10 *DNC, ) s 0. 5 (10-6)
The summation is over radionuclides i. Cf Concentration of Radionuclide i [pC1/ml) in the Unrestricted Area The calculated concentration of radionuclide i in the unrestricted area as determined by Equation 10-5. O. 10-9
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BRAIDWOOD . Revision-1.0 January'1994 C[ Concentration of Radionuclide 1 [pCi/mi]- j. in the Release Tank The concentration of radioactivity'in the ! radwaste' discharge tank based on measurements 1 of a sample drawn from the tank. DWC 3 Derived Water Concentration [pCi/nJ) of Radionuclide i
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-l The concentration of radionuclide i given in Appendix- -{
B, Table 2, Column 2 to 10CFR20.1001-20.2402. ! l 10 Multiplier I F,l , Maximum Releaso Tank Discharge [gpm] Flow Rate Ffe. Circulating Water Blowdown Rate Igpm] 0.5 Factor for conservatism l 10-10 I ' ___.____1____:___.____"_
i 1 BRAIDWOOD Revision 1.O i January 1994- I 10.3 SOLIDIFICATIOt1 OF WASTE / PROCESS CorJTROL PROGRAM O I The process control program (PCP) contains the sampling, analysic, -l and formulation determination by which solidification of j radioactive wasten from liquid systems is ensured. l Figure 10-4 la a nirnplified diagrwn of solid radwaste processing system. l; l
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l 1 1 i l i O, 10-11
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- t BRAIDWOOD Revision'150 -4 l
January 1994 1.:! Table 10-1 h .j ; , Assumed Composition of the Braidwood Station.
- Noble Gas Effluent -
i i
! ; -i Percent ~of ,
Isotone Total Annual' Release Ar-41 00.89 .i Kr-85m 00.18 Kr-85 24,9
-i Kr-87 00,O'4 >
-i Kr-88 00.28 'i Xe-131m 01.4 -
Xe-133m -004 57 i Xe-133 71.1 l s Xe-135 00.53 j
- . Xe-138 00.04. I i
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BRAIDWOOD Revision 1.0 i January 1994 Table 10-2 9:. l Assumed Composition of the Braidwood Station Liquid Effluent i Isotope Concentration Isotope Concentration (uci/ml) (uci/ml) Ru-103 8.00E - 06 Mn-54 1.00E - 05 t Ag-110m 3.00E - 06 Fe-59 5.00E - 06 Te-127 2.00E - 05 Co-58 9.00E - 06 Te-129m 2.00E - 06 Co-60 3.00E - 06 Te-131m 4.00E - 06 Rb-86 2.00E - 06 Te-132 2.00E - 06 Zr-95 6.00E - 06 I-130 3.00E - 07 Nb-95 1.00E - 05 I-131 3.00E - 08 Mo-99 4.00E - 06 I-132 8.00E - 07 I-133 1.00E - 07 I-135 4.00E - 07 Cs-134 9.00E - 07 Cs-136 9.00E - 06 Cs-137 2.00E - 06 Ce-144 1.00E - 06 Np-239 1.00E - 05 O 10-13
i REVISION 1.0 r JANUARY 1994 rw lo av
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f ~ l" l~ E6sv. 200'00* z lw zlg above grade ; State of e State of (!hnois lilinois stack rnonttor ,,, ,,, stack rnonttor ' em- = i Containment Unit 1 H Masn purga (Typical) . E qh 0 b m s 3l1 vF 43#oo 1RE428028 iei iii O , H Minf purge , 2 REP R028 H C 3 g ____ ___ ___ LT* JL
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3.800 I Laundry Ff O I ORE PN15 OFFSITE DOSE CALCULATION MANUAL l BRAIDWOOD STATION l FIGURE 10-1 SIMPLIFIED HVAC AND GASEOUS s EFFLUENT FLOW DIAGRAM (SHEET 1 OF 2) I u2464.ooi. os43 i 10~14 I I
REVISION 1.0 - JANU ARY 1994 i i Une 1 condenser 2.500 (Dunng Unh 1 stanup) ho99 1n9 pump Gland steam 1.400 3 p N 1,432 O condenser b T I 6,000 (Note 3) g-Bl}D4------ H G C H N --------- Steam Jet g 32 i air ejector M "" " #" l l Turbine building
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I (Elevation 451 ft) Unit 2 2.500 (Dunng g condenser Unt 2 startup) hogging pump i , I I I g Stack 1 Stack 2 I I Gand steam m 1
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condenser v y ' F 0 2RE-PR027 Steam jet % 32 air eNK: tor # Solid radwaste ' > b ORE-PR026 3,100 Drumming station. . _ _ _ _RE-PRO 14 votame reducten p ____g_____ __ _ j iH CC H I ORE-PRD40 l i
'4 004-03 l
Legend Notes I l [ - Norma' or frequent flow path 1. Used intermittentty to vent containment during normal cperation.
---- Occasional flow path 2. Used only during postaccuent operation.
A Containment atmosphere radation monttor 3. Fmer unt operates only when high radation is detected in offgas C Charcoat filter 'YS** * *"'
- 4. All flow rates are design flow ratos in cubic feet per minute.
F Refuehng
- 5. Integrated Laak Rate Test (ILRT) pressure relief point G Nooie gas radation monitor (offline)
H HEPA ftltar M Three<:hannel radiation rnonttor for particulate, todine, and noth gas (offitne) N Normal operation P particuter.o rnonttor (offline) OFFSITE DOSE CALCULATION MANUAL a "r*o9an'="mua" BRAIDWOOD STATION S Normal ranga stock radiation monnor (particulate, tadine, and noble gas) w wee range stack nobie radation monito, FIGURE 10-1 l SIMPLIFIED HVAC AND GASEOUS EFFLUENT FLOW DIAGRAM (SHEET 2 OF 2) , M2464oD2a 0643 ( 10-15 l
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an ~~ UNIT 1 UN BLOWDOWN WO PRE-FILTERS MINEf UNIT 1 UNC1 STEAM ' L BLOWDOWN L CENERATOR CONDENSER BLOWDOWN UNIT 2 _ UN BLOWDOWN __ BLOWDOVA PRE-FITTERS ' DEMNEL 2 UMT2 GEN RA OR = R \ \ BLOWDOWN TURB. BLDG EQUIP. / / DRAIN FILTER \ \ TURB. BLOG. EQUIP. -e es / r DRAIN TANKS \ \ TURB. BLDG. FLOOR 1' TURB.i DRAIN FILTER jL FIRE & 0-TURB. E4DO.
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FLOOR - DRAIN TANKS G L ORE-T-CHEMICAL DRAIN FILTER CHEMICAL - DRAIN TANK " REGENERATON WASTE DRAIN FILTER : REGENERATON
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. . . January 1994- . . .y . ./ BRAIDWOOD ANNEX INDEX .( .;
PAGE REVISION CHAPTER 11
'11-1 1.0 11-i1 1.0 11-iii 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 11 ~7 1.0 11-8 1.0 -
11-9 1.0 11-10 1.0 11-11 1.0 11-12 1.0 11-13 1.0 11-14 1.0 11-15 1.0 11-16 1.0 l 11-17 1.O f ( F k l l l 11-i l
- j
(- 1 l .. , BRAIDWOOD Revision 1.0 l January 1994 CHAPTER 11 - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS 1R1MPER TITLE PM 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 11-1 l O 4 O 11-ii [
. ~ _ .-.-_... . -. . .____ .--_--- _..__- .
t BRAIDWOOD' Revision .1. 0 N
. January 1994 .
CHAPTER 11 LIST'OF TABLES .i
?
' NUMPER g p 11_1 Radiological Environmental Monitoring Program ' 11-2 i 11 Reporting Levels for Radioactivity Concentrations in Environmental Samples 11-11 f
11-3 Detection capabilities for Environmental i Sample Analysis . 11-12 i N i 4 l l l
=
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7 BRAIDWOOD Revision 1.0 January 1994 . CHAPTER 11 LIST OF FIGURES : m3MPEP m PAGE 11-1 Fixed Air Sampling Sites and Outer Ring TLD Locations 11-15 4 11-2 Inner Ring TLD Locations 11-16 11-3 Ingestion and Waterborne Exposure Pathway Sample Locations 11-17 4 3 4
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. .. . . . - _ . . - . ~ . . . - - . . ....-~.- . ~
d BRAIDWOOD Revision 1.O January 1994 CHAPTER 11
. . . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The parameters of the radiological environmental monitoring program for the environs around Braidwood Station are given in Table 11-1. The reporting levels for radioactivity concentrations in environmental samples are given in Tal,e 11-2. The lower limits of detection for this program are given in Table 11-3.
Figure 11-1 shows the fixed air sampling sites and TLD locations. l Figure 11-2 shows the locations of the inner ring TLDs. The TLDs are code numbered as iollows: XYY7-N X= 1 means inner rinr, X= 2 means outer ring, and i YYz-N is an identification code (YY and N are numbers; = is an optional letter). Figure 11-3 shows the ingestion and waterborne exposure pathway sample locations. A f 1 11-1
- t. , _ . . . . .- . . _ ,
~n.. .. . . . . ~ -. . . - . ~ , . . - . - . - - - - . , ~ . . - . . - ~ . . . ~ - . - . . . . . . . ,
BRAIDh'OOD Revisionl'O January 1994 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Samolo Samulina or f-f on i t or i na Locationn* Collection Freauency of Analvnis
- 1. Airborne a. Onnite and f fr+ar F i e l d Continuous campler ope r a t. i on Radiciodino Canintern with sample collection weekly Radiciodine and Indicatorn I-131 analysis weekly Pa r t i cu late:1 UD-01, Braidwood, 1.5 mi flE (2.4 km C) Pa r t_ i cu la t e Samnler:
BD-06, Godley, 0.5 mi WSW (0.8 km M) BD-19, t.earsite !!W , 0.3 mi !!W (0.5 km Q) a. Gross beta analysis BD-20, tiearsite !!, 0.6 mi !! (1.0 km A) following filter d BD-21 tiearsite !!E, 0.5 mi IlllE (0.8 km B) change
- b. Far Field' b. Gamtmi isotopic analysis on quar-Indicators terly composite (by location)
BD-02, Custer Park, 5.0 mi E (8.0 km E) ED-04, Essex, 4.8 mi SSE (7.7 km 11) Samulina Train: HD-05, Gardner, 5.5 mi SW (8.8 km L) Test and maintenance Controls weekly DD-03, County Line Road, 6.2 mi ESE (10.0 km F)
. . . _ _ . . _ . . _ . _ . . . . _ _ . _ _ _ _ . _ . _ . . . . . _ _ _ _ , . . . _.. .,_.. . . . .m . .-- . . _ .___ _ _ _ . _ . . - - . _
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;l Collection Frecuency '
i 'and/or Samnie Samulina or Monitori'nd Locationn* of Analvnis
'l
' 2. Direct Padiation a. Inner Rina' Quarterly Gamma dose quarterly-
- Indicatorn i I
DD-101-1, 0.6 mi II (1.0 km A) HD-101-2, 0.6 mi 11 (1.0 km A) i BD-101-3, 0.5 mi II (0.8 km A) -j
- BD-101-4, 0.5 mi II (0.8 km A)- i BD-102-1, 1.2 mi lIIIE -(1.9 km B)
DD-102-2, 1.1 mi title (1.8 km B) I BD-103-1, 1 . 0 m i'!!E- (1.6 km C) l BD-103-2, 1.0 ~ mi !!E (1.6 km C) .!
- BD-104.1,-
0.7 mi EllE (1.1 km C) -j l~ BD-104-2,- 'O.7 mi EllE (1.1 km.D) i
- BD-105-1, '1.5.mi E (2.4 km E) .
l BD+105-2, 1.5 mi E (2.4 km E) ! BD-106-1, 1.7 mi ESE (2.7 km F) ! ! BD-106-2, 1.7 mi ESE '(2.7 km F) .-[ UD-107-1, 2.0 mi SE i l- (3.2 km C) ! BD-107-2, 2.0.mi SE (3.2'km G) ! BD-108-1, 2.0 mi SSE (3.2 km H) [ BD-108-2, BD-109-1, 2.0 mi SSE ( 3. 2 km II) -
- 2.,5 mi S (4.0 km J) i
, DD-109-2, 2.5 mi S~ (4.0 km J) ! 3 BD-110-1, 1.8 mi SSW , (2.9 km K) BD-110-2,. 1.8 mi SSW (2.9 km K). ll BD-111a-1, 1.4 mi SW (2.2 km L) I 'DD-111a-2, 1.4 mi SW' (2.2 km 1.) BD-111b-1,. 1.1 mi'SW (1.8 km~L) , BD-111b-2, 1.1.mi SW- (1.8.km L) BD-112-1, 0.7 mi WSW (111 km f4) - BD - 112 - 2, 0.7 mi WSW (1.1 km 14) l i f I [ 11-3 _ i 1 -
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BRAIDWOOD Revision 1. O January 1994 Table 11-1 (Continued) Radiological Environmental Monitoring Program Exposure Pathway Sampiina or Type and Frequency and/or Samole Sarroli na or Monitorina Locationn* Collection Freauency of Analvain
- 4. Inaention" (Cont'd)
- d. Food Products Indicatorn Grown nearent each of two ditferent offsite Monthly when available and Gamma isotopic and locations of hiahest predicted annual requited; reauired only if I-131 analynis.
Samples of average ground level D/O (see Table F-5), milk ramolina in not oerformed, three differ-ent kinds of broadleaf vegetation Controin From a locat ion 15 to 30 km from the station Monthly when available and Gamma isotopic and in direction of least prevalent wind required; reouired eniv if I-131 analysis. One sample direction. milk namelino not oerformed. each of broadleaf vegetation l similar to j that collected l for the above , requirement l l i 5. and Use Cennus I
- a. Milch Animals 1. Site boundary to 2 miles Annually during grating ceason Enumeration by a door-to-door or equivalent l
l counting technique. l i l- 11-8 O O O. .
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) r mt l l -
d o ac l l m e t Se a a - u i l u u . n n l n n w i o o n n . r t M C A A D n l w o O C a 9 ( t m n :- e 1 = 1 1
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BRAIDWOOD Revision 1. 0 - January 1994 Table 11-1 (Continued) Radiological Environmental Monitoring Program
-Exposure Pathway Samplitig or Type and Frequency and/or Samole Samnl i rra or tionitorina Locations' Collection Freauency of Analysis
- b. t!earest Resident In all 16 sectors up to 5 miles. Annually See Table D-16 ter definitions of sector codes used with kilometer distances.
* " Fixed Air Sampling Sites and Outer Ring TLD Locat: ions . "
See Figure 11-1, See Figure 11-2, " Inner Ring TLD I,ocations."
- Perform gamma inotopic analysis on each sample when gross beta activity is greater t han (>) 10 times the yearly mean of control samples.
See Figure 11-3, " Ingestion and Waterborne Exposure Pathway Sample Locations." Biweekly means every two weeks. e- - . V . e..
BRA 1 D' Revis1 JO' , 1 January '1994 Table 11-2 - I Reporting Levels for Radioactivity Concentrations in Enviroruuental Samples Water Airborne Particulate Fish Milk- Food Products
-Analysis (pCi/L) or Cases ' (pCi/m') (pCi/Kg, wet) (pCi/L) (pCi/Kg, wet)
H-3 2 0, G00* .j l' ~ i Mn-54 - 1,000 30,000 Fe-59 400 10,000 co 1,000: 30,000.. ; Co-60 300' 10,000 Zn-65 . 300' 20,000 3 Z r -tib- 9 5 400 t I1131 2' O9 3 100 Cs-134 30 10 1,000 60 1,000 .; Cs-137 50 .~20- 2,000 70 2,000 Ba-La-140 '200' 300
' *For; drinking water 'samplen.
This.is a.40 CFR.Part 141 value. If-ho drinking water pathway exists, a,.value of'30,000,pC1/L may-be used. 11-11 t
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BRAIDWOOD Revision 1. 0 January 1994 Table 11-3 Detection capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD)* Water Airborne Particulate Fish Milk Food Products Sediment Analysis (pCi/L) or Gases ( pC i /m' ) (pCi/kg, wet) (pCi/L) (pCi/ko, wet) (pCi/kg, dry) Gross Beta 4 0.01 H-3 2000* Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Z r - f il>- 9 5 15 1-131 1* 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba - La - 14 0 15 15 l l l l 11-12 i O O O. .
. BRAIDWOOD1 Revision'1.O- /- January 1994 9
1 Table 11-3 (continued) O Detection capabilities for Environmental Sample Analysis' ~ i General Notes: i i
- 1. This list does not mean that only these nuclides are to be .
considered. Other peaks that are identifiable, together with those
~
4 of the above nuclides, shall also be analyzed ~and reported in the Annual Radiological Environmental Operating Report.
- 2. Regyired det'ection capabilities for thermoluminescent dosimetersi ;]
used for environmental measurements are given in Regulatory Guide _, 4.13. r Footnotes: i
-The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that'will be,
, detected with 95% probability with only 5% probability lof f alselyf concluding that a blank observation represents a real. signal. '
For a particular measurement system (which may include
~
radiochemical separation) ' 4.66 l(s n) . u2> - ! E V 2.22 Y. exp (-lat) - LLD The a criori lower limit of detection (picoeuries per unit mass or volume). , s, The standard deviation of.tho background counting rate or of{ the counting rate of a blank sample.as. appropriate'(counts per minute). : E The counting efficiency (counts per disintegration). V The sample. size (units of mass or volume). I 2.22 The number of disintegrations per minute per picoeurie. Y The. fractional radiochemical yield, when applicable; A The radioactive decay const' ant for the particular. i radionuclide (sec").
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.2 1.1
BRAIDWOOD Revision 1.0 January 1994 Table 11-3 (Continued) g Detection capabilities for Environmental Sample Analysis a The elapsed time between sample collection or end of the sample collection period and time of counting (sec) Typical values of E, V, Y, and at should be used in the calculation. It should be recognized.that the LLD is defined as an a orderi (before the fact) limit representing the capability of a measurement system and not as an a nesteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. If no drinking water pathway exists, a value of 3000 pCi/L may be used. LLD for drinking water samples. If no drinking water pathway exists, an LLD of 60 pCi/L may be used. O 11-14 L-
? Revision 1.0 January 1994 f V) '
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- . y BRAIDWOOD ' Revision 1. 0 -~ l I
.. January 1994 .a.
e I CHAPTER 12.0
?
i i f SPECIAL NOTE The transf er of the Radiological Ef fluent Technical Specifications to the' =! ODOM by Technical Specification,. Amendment 35, dated April 13, 1992,.was- ~! approved by the Nuclear; Regulatory Commission. .
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[ BRAIDWOOD Revision 1. 0 Januatr 1994 BRAIDWOOD ANNEX INDEX PAGE REVISION CHAPTER 12 12 -i 1.0 12 - ii 1.0 12 - iii 1.0 12 - iv 1.0 12 -v 1.0 12 - 1 1.0 12 - 2 1.0 12 -3 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.C 12 - 31 1.0 12 - 32 1.0 12 - 33 1.0
- l 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 - 44 1.0 12 - 45 1.0 12-11 l
F .~ 7 1 I. . . - t i BRAIDWOOD 'Revisioni.0 I y- 7 Janua:qr 1994 ; ( i
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BRAIDWOOD ANNEX INDEX f PAGE REVISION CHAPTER 12 f 12 46 1.0 .j 12 - 47 1.0 ' 12 - 48 1.0
~i 12 - 49 1.0 ;
12 - 50 1.0 , 51 1.0 l 12 - 52 ' 1. 0 12'- 53 1.0 { 12-- 54 1.0 ., 12 - 55 1.0 ~' 12 - 56 1.0 l 12 - 57 1.0-12 - 58 1.0 12 - 59 1.0 ; 12 -'60 1.0 + s t 5 ' l. 1 i 4 I i li f i r i
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12-111 , I,
i BRAIDWOOD Revision 1. O January 1994 CHAPTER 12 i RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS) TABLE OF CONTENTS EMiZ 12.1 DEFINITIONS 12-1 12.2 INSTRUMENTATION 12-5
- 1. Radioactive Liquid Effluent Monitoring Instrumentation 12-5
- 2. Radioactive Gaseous Effluent Monitoring Instrumentation 12-10 12.3 LIQUID EFFLUENTS 12-17
- 1. Concentration 12-17
- 2. Dose 12-23
- 3. Liquid Radwaste Treatment System 12-25 12.4 GASEOUS EFFLUENTS 12-27
- 1. Dose Rate 12-27
- 2. Dose - Noble Gases 12-32
- 3. Dose - Iodine-131 and 133, Tritium, and Radioactive Material in Particulate Form 12-34 /
- 4. Gaseous Radwaste Treatment System 12-36
- 5. Total Dose 12-38 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-40
- 1. Monitoring Program 12-40
- 2. Land Use Census 12-53
- 3. Interlaboratory Comparison Program 12-55 12.6 REPORTING REQUIREMENTS 12-56 .
1
- 1. Annual Radiological Environmental Operating Report 12-56
- 2. Annual Radioactive Effluent Release Report 12-58 3, Offsite Dose Calculation Manual (ODCM) 12-59
- 4. Major Changes to Liquid and Gaseous Radwaste Treatment Systems 12-60 i
e i O 12-iv l
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_j.- _ i,. ; BRAIDWOOD Revision 1. O . January 1994 :
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CHAPTER 12
~{d. ,
RADIOACTIVE' EFFLUENT TECHNICAL STANDARDS {RETS) , LIST OF TABLES l PAGE f
'12.1-1 Frequency Notations 12-4 12.2-1 Radioactive. Liquid Effluent Monitoring i Instrumentation 12 T 12.2-2 Radioactive Liquid Effluent Monitoring . ,
Instrumentation Surveillance Requirements 12-8 12.2-3 Radioactive. Gaseous Effluent Monitoring Instrumentation 12 . 12.2-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 12-14 12.3--1 Radioactive Liquid Waste Sampling and Analysis Program' 19 f 12.4-1 Radioactive Gaseous Waste Sampling and Analysis- I Program 12 I12.5-1 Radiological Environmental Monitoring Program 12-43' -
.12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-49 12.5-3 Detection Capabilities for Environmental Sample
' Analysis 12-50~ r i
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*I BRAIDWOOD Revision 1. O January 1994 i
12.0 RADIOLOGICAL ENVIRONMENTAL TECHNICAL STANDARDS 12.1 DEFINITIONS 12.1.1 Action shall be that which prescribes remedial measures required under designated co' ?itions. 12.1.2 Analoc Channel Oneratiena, 're s t shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm interlock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy. 12.1.3 Channel Calibration shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. 12.1.4 Channel Chest shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications . and/or status derived from independent instrument channels measuring the same parameter. 12.1.5 Dicit al Channel Onerat ional Test shall consist of exercising the digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY of alarm and/or trip functions. 12.1.6 Dose Eauivalent T-131 shall be that connection 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 conversion f actors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites". 12.1.7 Member (s) of the Public means an individual in a controlled area or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives occupational dose. 5 k 9: l '. - 1 J
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.u BRAIDWOOD Ikevision 1. 0 I
. January 1994 a
, .} : ( - l 12.1.8 -onerable/onerability .a system,-subsystem, train,. component- *
^'
or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant . instrumentation, controls, , electrical power, cooling - or seal water, lubrication or , other auxiliary equipment that are -required for the system, subsystem, train, component, or ' device to perf orm its ! function (s) are also capable of performing' their related , support function (s). 12.1.9 onerational Mode (i.e. Mode) shall. correspond to any . one inclusive combination of core reactivity. condition, . power
' level, and average reactor coolant-temperature specified in- t Table 1.2 of the Technical Specifications. I 12.1.10 Process Control Procram (PCP) 'shall contain the -current < -l formulas, sampling, analyses, tests, and determinations--to
[ be made to ensure that processing ,and packaging "of L solid 7 radioactive wastes based on demonstrated . : processing ' of - , actual or simulated wet solid wastes will be accomplished- l in such a way as to assure compliance with 10'CFR Parts 20, 61, 71 and State regulations, burial ground ~ requirements, , and other requirements governing the disposal of' radioactive. .; wastes. l
~
t 12.1.11 Purce/Purcing shall be any controlled process of discharging l air .or gas from a confinement to maintain temperature, pressure, humidity, concentration or other -operating-condition, in such a manner that replacement air'or gas is- L required to purify the confinement. ; q 12.1.12 Rated Thermal Power shall be a total core heat transfer rate to the reactor coolant of 3411 MWt. 12.1.13 site Boundarv shall be that.line beycnd which the ~ 1and is I neither owned, nor leased, nor otherwise controlled'by the i licensee. . f P 12.1.14 solidi fication . shall be the conversion of wet l wastes into - a form that meets shipping and burial ground requirements. ' 12.1.15 Source check shall.be the qualitative assessment of channel' , response when the channel sensor is exposed to a source of-increased radioactivity. 12.1.16 Thermal Power shall be the total core' heat transfer-rate to. i the reactor coolant.
.I i
12.1.17 Unrestricted Area means an area, access to which is neither' ~ limited nor controlled by'the licensee.
-i i
3 y . 12-2
'f
BRAIDWOOD Revision 1. 0 l January 1994 12.1.18 Ventilation Exhaust Treatment system shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the ' gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. 12.1.19 ventina shall be any controlled process of discharging air or gas f rom a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. 12.1.20 Waste Gar Holdun System shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System of f-gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. 12.1.21 Definitions Peculiar to Estimating Dose to Members of the Public Using the ODCM Computer Program,
- a. ACTUAL - ACTUAL refers to using known release data to project the dose to members of the public for the previous time period. This data is stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.
- b. PROJECTED - PROJECTED refers to using known release data from the previous time period or. estimated release data to forecast a future dose to members of the public. This data is not incorporated-into the database.
4 12-3
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'BRAIDWOOD- . Revision 1. 0 l
. January 1994 . ?l
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- i TABLE 12.1-1 ,
i FREOUENCY NOTATIONS : i k Motation .Procuency
'S At least'once per 12 hours ;
3 D. At least once per 24-hours - W :At least once'per 7 days' ri i M At.least once per 31 days 'l Q At least.once per 92 days . SA At least once per 184 days -l R At least once per 18 months S/U Prior to each' reactor startup , F N.A. Not applicable ) P Completed prior to-each. release , ,, e I a i ,~ j l
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BRAIDWOOD Revision 1. 0 l
. January 1994 12.2 INSTF" MENTATION 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation enerabi!itv Recru i remont s 12.2.1.A The radioactive liquid effluent monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of 12.3.1.A are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
Annlicability: At all times Action
- 1. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.
- 2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2-1.
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Radioactive Effluent Release Report pursuant to Section 12.6 why this inoperability was not corrected within the time specified, surveillance Recruirenents 12.2.1.B Each radioactive liquid ef fluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and DIGITAL and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 12.2-2. Bases 12.2.1.C The radioactive liquid ef fluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm / Trip Setpointe for these instruments shall be calculated and adjusted in accordance with the methodology and parameters ! in the ODCM to ensure that the alarm / trip will occur prior j to exceeding the limits of RETS. The OPERABILITY and use , of this instrumentation is consistent with the requirements ; of General Design Criteria 60, 63, and 64 of Appendix A to 1 10 CFR Part 50. 1 O 12-5 l
.BRAIDWOOD- Revision 1. 0 - .;
- January 1994
# l
( TABLE 12.2-1 RADIOACTIVE LTOUID EFFLUENT MONITORING TNSTPUMENTATION l t ' MINIMUM CHANNELS IM9TRUMENT OPERABLE ACTION j
- 1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release !
- a. Liquid Radwaste Effluent Line (ORE-PR001) 1 31. . l 1
- b. Fire and Oil Sump (ORE-PR005) 1 34 fr
- c. Condensate Polisher Sump Discharge (ORE-PR041) 1 34 [
- 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release j
- a. Essential Service Water 1
- 1) Unit'1 .[
a) RCFC 1A and IC Outlet (1RE-PR002) 1 32 b) RCFC 1B and ID Outlet (1RE-PR003) 1 32 i (" 2) Unit 2 km .
's a) RCFC 2A and 2C Outlet (2RE-PR002) 1 32 !
b) RCFC 2B and 2D Outlet ( 2 RE-PR003 ) 1 32. ! 1
- b. Station Blowdown Line (ORE-PRO 10) 1 -32
- 3. Flow Rate Measurement Devices-i
- a. Liquid Radwaste Effluent Line (Loop-WXOO1) 1 33 ;
- b. Liquid Radwaste Effluent Low Flow Line ,
(Loop-WX630) 1 33
- c. Station Blowdown Line (Loop-CWO32) 1 33 r i
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BRAIDWOCD Revision 1. O January 1994 TABLE 12.2-1 (Continued) ACTION STATEMENTS ACTION 31 - With the number of channels OPERABLE less than required by t? e Minimum Channels OPERABLE requirement , effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Section 12.3 and
- b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactive ef fluents via this pathway. ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement , effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours, grab samples are collected and analyzed f or radioactivity at a lower limit of detection as specified in Table 12.3-1. ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, ef fluent releases via this pathway may continue f or up to 30 days provided the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves generated in place may be used to estimate flow. ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirenent, etfluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed f or radioactivity at a lower limit of detection as specified in Table 12.3-1:
- a. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 microcurle/ gram DOSE EQUIVALENT I-131, or
- b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.
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BRAIDWOOD Revision 1.0 January 1994 TABLE 12.2-2 (continued) h, TABLE MOTATIONS
#The specified 18 month interval may be extended to 32 months for cycle 1 only. ,
(1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolatien of this pathway and control room alarm annunciation occur if any of the following conditions exists:
- a. Instrument indicates measured levels above the Alarm / Trip Setpoint, or
- b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or
- c. Detector check source test failure, or
- d. Detector channel out-of-service, or
- e. Monitor loss of sample flow. This is only applicable for ORE-PR001 and ORE-PR005. Monitor ORE-PR041 will not trip on loss of sample flow.
(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- a. Instrument indicates measured levels above the Alarm Setpoint, or
- b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or
- c. Detector check source test failure, or
- d. Detector channel out-of-service, or
- e. Monitor loss of sample flow.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. 12-9
.~ . _ - . . _ _ ._ .
Lel 1
'BRAIDWOOD Revision 1. 0 ,
January.1994 c/ fl2.'2. 2 - Radioactive caseous Effluent Monitorina Inst rument at i on Onerability Peauirements i
'i 12.2.2.A The radioactive gaseous effluent' monitoring instrumentation channels shown in Table 12.2-3 shall be. OPERABLE with their l Alarm / Trip Setpoints set to ensure-that the limits'of- -i Section 12.4 are not exceeded. The Alarm / Trip Setpoints of +
these channels shall be determined and adjusted in , [ accordance with the methodology and parameters in the ODCM. ' Annlicabilitv: As shown in Table 12.2-3 ! Action:
- 1. With a. radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less- t conservative than required by the'above section, ,
immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.
-t
- 2. With less than the minimum number of radioactive ;
gaseous effluent monitoring instrumentation channels ; OPERABLE, take the ACTION shown in Table 12 2-3. ' Restore the inoperable instrumentation.to OPERABLE ! status within the time specified in the ACTION,-or explain'in the next Semiannual' Radioactive Effluent Release Report pursuant to Section 12.6 why.this inoperability was not corrected within the time 1 specified. Surveillance Recuirements , 12.2.2.B Each radioactive gaseous effluent monitoring instrumentation f channel shall be demonstrated OPERABLE by performance'of the ! CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and DIGITAL' - and CHANNEL OPERATIONAL TEST at the frequencies shown in1 l Table 12.2-4. ' Pares- . 12.2.2.C The radioactive gaseous effluent instrumentation-is provided g to monitor and control, as applicable, the releases of j radioactive materials in gaseous effluents during actual or : potential releases of gaseous effluents. The Alarm / Trip j' Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters t in the ODCM to ensure that the alarm / trip will occur prior l to exceeding the limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of
.l$
General Design Criteria 60, 63, and 64 of Appendix A to 10 f CFR Part 50. The sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent release requirements of Section 12.4 shall be such that concentrations as low as lx10 4 uCi/cc are measurable. 12-10 5
. ~ _
04 9 19 n oy ir sa 1 O iu vr i ea RJ _ O I T 99 0 0 6 6 99 0 0 6 6 I C 33 4 4 3 3 33 4 4 3 3 O A I T - A - T I - I E Y - dl T I U R L T I B S I I A * * * * * * * * * * *
- I C I
C L I I P I P R A O 3 T 1 D 2 1 f O O O 2 M 1 W 1 G 1 D T l L - I 2 E t E A R B L B
?-
T E U L F F f l l E AL l i CA B 1 O. - E R 11 1 1 1 1 11 1 1 1 1 S 1 f E U UP . O MO I E 1 S f I _ - A G M E V - I T 1 ) 2 ) C A A A t 8 t 8 C i 2 ) i 2 ) I D n ) 0 9 n ) 0 0 A U D) ) R 1 g U - D) ) R 2 g R r 8H C P 0 n r 8D C P 0 n _ o 28 8 - eA i - o 28 8 - eA i t 02 2 E tV r t 02 2 E tV r m i R0 0 R a- u m i R0 0 R a- u . e n PR R 1 HP s e n PR R 2 RP s - t e - P P ( O a t o P P ( O a s i t E - - wO e s M E - - wO e y RE E t oL M y RE E r oL M . S y 1R R e l ( ) S y 2R R e l( - t (1 1 l F e5 g t ( 2 2 l p F e5) - g i ( ( p e t6 i ( ( e t6 n sm e m mc a1 n vm e m mc a1 RR i i r ge r a ei RR i i t ge r a ei r t a ng e S t v P r t a ng e l S t v P o cl an l p se w- o cl an p e se w-t AA Ra e yD oT t AA Ra yD oT [i R m t S l 1 - i R m t S lF r n sg h a a g F1 n sg h a a g F2 T E o an gw S l t n ( o an gw S l t n ( M M Gi i o u ni r M Gi i o u ni r U d i L e c er ee d f I L e c er ee R t e'. l n i uu l c t n ei n i uu l c T n ls i t l s pi l v i t l s pi S e bo d r f a mv e bo d t f a mv f i V lor ) ) o a f e ae V or ) ) o a f e ae l I P 1 2 I P EM SD lf P 1 2 I P El f SD O t t n n a a . l . . . . l . . . . P a b c d e P a b c d e 1 2
g . . . .
^
BR dOD , sio 1Y0
- xJanuary.1994; ,
-l
- TABLE 12.2-3 (Continued) l l RADIOACTIVE CASEOUS EFFLUEllT moi!ITORIf1C If fSTRUMEllTATIOfl
! i . i
- i. MilllMUti CilAtitlELS' .i
) IllSTRUMEIIT OPERAHLE APPLICABILITY ACTIOf! , i, j p - 3. ' !!ot Used. };
- 4. Gas Decay Tank System
[ a. Iloble Gas.ketivity f4onitor- ' Providing-Alarm and Automatic j ' Termination of Release 4 (ORE-PR002A'and 28) .2
- 35 l
- 5. Containment Purge System >
i ! ' a. Iloble Gas Activity Monitor- R Providing. Alarm (RE-PR00111) ' 1-
- 37 l
4. [- b. Iodine Sampler
- " (RE-PR001C)~ 1
- 40 -t
, 4_ !- c. Particulate Sampler : f l (RE-PROO1A)- 1- 40 7 i
.v
! 6. Radioactivity Monitors Providing Alarm-l . and Automatic Closure of Surge' Tank Vent-Component Cooling Water Line' . (ORE-PR009 and RE-PR009)- 2 41
-: t
't n
- t
;i i
l~ 12-12 j :1
.N e '. i
- t. 6 i- '!
I 4 t-
-] .
me- e e-e.- -- w i re'sv .=,,- ..w- e-<%-- se -Tv*^m ab ,r- e e m er- e in.a ii awn.ww- s-+m.+b s+-'e e,. eeme wee.sur**es-m +*,-.c4mene s-m- m-W.wA+,*med-a-**se+swv+s x- e. -
?- e e- e -.mme ma we e r - am e-==== w e e- wee n = 4 we w- un~_.-__=2.-ses.-___ Aen -ad
BRAIDWOOD Revision 1. 0 January 1994 TABLE 12.2-3 (continued) TABLE NOTATIONS
- At all times.
ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this pathway. ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours. ACTION 37 - With the nunber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. ACTION 38 - Not used. ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours and these samples are analyzed for radioactivity within 24 hours. ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue f or up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 12.4-1. ACTION 41 - With the number of channels OPERABLE less than required by the Mininum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours, liquid grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1. O 12-13 r
' " [ , { j' i: l ! , 9
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l- - L ' BRAIDWOOD- Revision 1. 0 - Januaqr 1994 ' , m-g TABLE 12.2-4 (continued) j i TABLE NOTATIONS l t At all times.
*#The-specified 18 month. interval may be extended to 32 months for j cycle 1 only. >
.i (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also' demonstrate'that ,
automatic isolation of this pathway and control room alarm I annunciation occur if any of the following conditions exists:
- a. Instrument indicatesLmeasured levels above'the Alarm / Trip ij Setpoint, .;
or ; e !
- b. Circuit failure (monitor loss of communications - alarm l only, detector loss of counts, or monitor loss of power), or j i
- c. Detector check. source test failure, or ,.
i
- d. Detector channel out-of-service, or ;
- e. Monitor loss of sanple flow. Monitoring ORE-PR002A and 2B will not trip on loss of sample flow. This is only ,
applicable for functional unit 6, ORE "R009.and RE-009. 3
. .. .i (2) The DIGITAL CHANNEL OPERATIONAL. TEST shall also~ demonstrate that }
control room alarm annunciation occurs if any'of the following. ! conditions exists. , I
- a. Instrument indicates measured levels above the Alarm :
Setpoint, or 'I
- b. Circuit failure (monitor loss of communications - alanm only, detector loss of counts, .or monitor loss of power), or i
- c. Detectcr check source test failure, or ;
i
- d. Detecter channel out-of-service, or- j
- e. Monitor loss of sample flow. l (3) The initial CHANNEL CALIBRATION shall be performed using one or I more of the reference standards certified by the National'. !
Institute of Standards and Technology .(NIST) or using standards that have been obtained from suppliers that participate $n measurement assurance activities with NIST. These standards shall l permit calibrating the system over its intended range of energy j and measurement range. For' subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be. . used. -l 1 12-16 1
BRAIDNOOD Revision 1. 0 Januaqr 1994 12.3 LIOUID EFFLUENTS 12.3.1 concentration Operabil d tv Recuirement s 12.3.1.A The concentration of radioactive material released in liquid effluents to UNRESTRICTED A.REAS (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited to 10 times the concentration values in
- Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2x10" microcurie /ml total activity.
Arnlicability: At all times Action:
- 1. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.
Surveillance ReauiremRDtr 12.3.1.1.B Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 12.3-1. 12.3.1.2.B The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of 12.3.1.A. Bases 12.3.1.C This section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will i>e less than 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402. This limitation provides additional assarance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result'in exposures within: (1) the Section II.A design objectives of Apnendix T, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.1301. Ol 12-17 , 1 l
, . . . . . ..,s --, . - . . . . . _ . . - .g i 1
BPAIDWOOD Revision 1. 0 1 January 1994 '
.12.3 LIOUTD EFFLOENTS (Continued)
Barer l This section applies.to the release of radioactive .
' materials.in liquid effluents from all-units at the !
site. '!
. r
.The required detection capabilities'for-radioactive '! -
materials.in liquid waste. samples'are tabulated in ! terms of the" lower limits of detection-(LLDs).- { Detailed discussion of.the LLD, and other detection ; limits can be found in HASL Procedures Manual, HAsL-300 r (revised annually), Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - l Application to Radiochemistry,* Anal. Chem. 40,-586-93. :( (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques,."' Atlantic 4 Richfield Hanford Company Report ARH-SA-215 (June i
'1975). .
.i
.. t t
7 t e r
,0 1
f a 9
.i
')
12-18 l 1
-l l
i BRAIDWOOD Revision 1. 0 l January 1994 )
.l ,
TAPLE 12.3-1 , PADTOACTIVP LTOUID WA9TE SAMPLING AND ANALYSTS PROGPAM l LOWER LIMIT ' TYPE OF ACTIVITY OF DETECTIOf1 LIQUID RELEASE SAMPL1!1G MIIIIMUM AIJALYSIS ATJ ALYSIS (LLD)") ! TYPE FR EQUEllCY FREQUEt1CY (pCi/ml)
- 1. Batch Pelease P P Principal Gamma 5 x 10
Tankn(2) Each Batch Each Batch Emit ter s (3 ) 1-131 1 x10 -' P M Dissolved and 1x105 One Batch /M Entrained Gases (Gamma Emitters) P M H-3 1x10-5 Each Batch Componite (4) Grons Alpha 1 x 10-' , P Q Sr-89, Sr-90 5x10-' Each Batch Composite (4) Fe-55 1x10"
- 2. Continuous Continuouni W Principal Gamma 5 x10 -'
keleasen (5) Composite'" Emit ter s (3 ) 1-131 1 x 10-* M M Dinsolved and 1 x10-5
- a. Circulatina Grab Sample Entrained Gasec Water (Gamma Emitters)
Blowdown Continuoun(6) M H-3 1x10-5 Composite (6)
- b. Wante Water Treatment. Gross Alpha 1 x 10-'
D2scharge to Ci:culating Water Continuous (6) O Sr-89, Sr-90 5x10 Composite (6)
- c. Condennate Fe-55 1 x 10-'
Polisher Sump Dincharce 9 12-19 l
x, s BRAIDWOOD'. Revisi'on 120 January 1994
.e f TABLE 1?.3-1 (Continued) -
RADIOACTIVE LTOUID WASTE SAMPLING AND ANALYSIS PROCPAM
.. LOWER' LIMIT 0F-LIQUID.. RELEASE TYPE SAMPLI!JG MIllIMUM A1JALYSIS -TYPE OF ACTIVITY DETECTIOti FREQUEllCY FREQUEf1CY AIJALYSIS (LLD) "(pCi/ml)
- 3. Continuouc W (7 )' W (7 ) Ptincipal Gamma .5x10
Release (5) Grab Sample Emi tt e rs (3 ) Ennential
! Service Water I-131 ' 1x10
React or Containment. Dissolved and 1x10**
-Fan Cooler Entrained Gases (RCFC) Outlet (Gamma Emitters)
Line 11 - 3 1x105
- 4. Continuoun IJone? IJone Principal Gamma 5x10
Surge Tank Emitterc(8)- Vent-Component Dissolved and - 1x10-5 Cooling Water Entrained Gasea 1 Line (9) (Gamma
... k Emi t t er s ) ( 8 )
I-131 1x10-*
~
12-20 t
BRAIDWOOD Revision 1. 0 Januan/ 1994 IP.BLE 12.3-1 (centinued) f TABLE NOTATIONS (1) The LLD is defined, for purposes of these sections, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that'will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents u "real" signal. For a particular measurement system, which may include radiochemical separation: LLD = E - V + 2.22 x 10' + Y . exp (-AAt) Where: LLD = the lower limit of detection (microCuries per unit mass or volume), ss = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E= the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 2.22 x 10' = the number of disintegrations per minute per
- microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide ( sec ) , and At = the elasped time between the midpoint of sample collection and the time of counting (sec).
Typical values of E, V, Y, and At should be used in the calculation. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. (2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling. O 12-21
BRAIDWOOD Revision l'.0- 'i January 1994 : y ][~' : . TABLE 12.3-1 (continued) 3 (( J q _ TABLE MOTATIONS (3) -The principal gamma emitters for.which the LLD specification j applies include.the following radionuclides: .Mn-54, Fe-59, Co-58,- Co-60, Zn-65, Mo-99, Cs-134, Cs-137, .Ce-141, and Ce-144. This
~
j list does not'mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of ! the above nuclides,'shall also be analyzed and reported'in the -- Radioactive Effluent Release Report pursuant to Section 12.6'2 in . ]R; ' the format-outlined in Regulatory Guide 1.21, Appendix B, Revision-1, June 1974.
'i (4) A composite sample is one in which the quantity of. liquid sampled j is proportional to the quantity-of liquid waste. discharged and in .!
which the. method of sampling employed results in'a specimen that is representative of the. liquids released. (5) A continuous release is the discharge of liquid wastes of a j nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release. ; (6) To be representative of the quantities and concentrations of , radioactive materials in liquid effluents, samples shall be q collected continuously whenever the effluent stream is flowing. , Prior to analyses, all samples taken for the: composite shall be
- ('
\
thoroughly mixed in order for the composite sample to be representative of the effluent release.
~
(7) Not required unless the Essential Service Water RCFC outlet Radiation Monitors RE-PR002 and RE-PR003 indicates measured levels greater than 1x10 4 pC1/ml above background at any time'during the week. ,
.t (8) The principal gamma emitters for which'the LLD specification' ;
applies include'the following radionuclides: .Kr-87, Kr-88, Xe-133,- Xe-133m, Xe-135, and Xe-138 for dissolved and entrained gases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137,' ce-141, and Ce-144 for principal gamma emitters. This list does not mean l that only these nuclides are to be considered. Other gamma. peaks that are identifiable, together with those of the above nuclides, .l' shall also be analyted and reported in the Radioactive Effluent , Release Report pursuant to Section 12.6.2, in the forru' outlines' l in Regulatory Guide 1.21, Appendix B, Revision 1, June 174. l
-(9) A continuous release is the discharge of dissolved and entrained gaseous waste from a nondiscrete liquid volume. l I
J l i I
'12-22 I
ERAIDWOOD Revision 1. 0 January 1994 12.3.2 Dose Orerability Reauirements 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F. Figure F-1) shall be limited:
- 1. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and
- 2. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.
Annlicability At all times. Action:
- 1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above litait s .
i Su rve i l lance Reauirements 22.3.2.B Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. Pares 12.3.2.C Thic section is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Operability Requirements implement the guides set forth in Section II.A of Appendix I. The ACTION 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 to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dose calculation methodology and parameters 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 a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially - underestimated. 12-23
. ., ., m m , ... _ _. __ _ . . - - - .- ,_
- 4
-l BRAIDWOOD Revision 1. 0 j January 1994' ,{
f(/, J 12.3.2 IEwa .JContinued)- : Bases l The' equations specified in the oDcM1 tor calculating the..
- doses due to the actual release rates of radioactive 1 materials in liquid effluents are consistent with the- ,l methodology provided in Regulatory Guide 1.109, " Calculation 1 ;
of Annual Doses to Man From Routine Releases of Reactor- ? Effluents For the Purpose of. Evaluating Compliance with 101 'l CFR Part 50, Appendix I" Revision 1, October 1977 Land Regulatory Guide'1.113', " Estimating Aquatic Dispersion'of ] Effluents from Accidental and Routine ReactorcReleases'for '; the Purpose of. Implementing Appendix I,": April 1977. i This section applies to the release'of radioactive materials' l in liquid effluents from each reactor at the site. When shared Radwaste Treatment Systems are used by more:than one ]; unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the-effluent releases :! cannot accurately be ascribed to a specific unit. An- ; estimate should be made of the contributions from each unit' -l based on input conditions, e.g., flow rates and_ . j radioactivity concentrations, or,-if not. practicable,=the' ll treated effluent' releases may.be allocated equally to each ;
~
of the radioactive waste producing units' sharing'the Radwaste Treatment-System. For determining conformance to ;
/"" operability Requirements, these allocationsffrom shared '!
Radwaste Treatment Systems are to be.added to the releases ~! specifically attributed to each unit to obtain the total y releases per unit. ; l 1 i f
'I, 6
.E r
i I 6 I i F 12-24 ;
BRAIDWOOD Revision 1. 0 January 1994 12.3.3 Licuid Radwast e Trentment system h Orerability Penuiroments 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) would exceed 0. 06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period. Arnlicab21ity: At all times. Actien-
- 1. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Technical Specifi cation 6.9.2, a special Report that includes the following information:
- a. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
- b. Action (s) taken to restore the inoperable equipment ,
to OPERABLE status, and
- c. Summary description of action (s) taken to prevent a recurrence.
Survei1 lance Recuirements 12.3.3.1.B Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when the Liquid Radwaste Treatment System is not being fully utilized. 12.3.3.2.B The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Sections 12 3.1.A and 12.3.2.A. Bases 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This section implements the requiremen,3 of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. 12-25
~ . . . . .- .-. .
t e
'i
. - . - t , l BRAIDWOODz Revision 1.0' I
' January 1994-12.3.3 Licuid Radwaste Treatment system (Continued)-
-l
' Bases The.specified limits governing the use of appropriate !
portions of the Liquid Radwaste Treatment System.were' I specified as a suitable fraction of the dose. design [ objectives' set'forth in Section II.A of Appendix I, 10_CFR i Part 50, for liquid effluents. l This section applies to the release of radioactive. materials- i in liquid effluents from each unit at the site. bC2en shared- ' i Radwaste Treatment Systems are used by more than one unit on [ a site, the wastes'from all units are mixed for shared. l treatment; by such mixing,.the effluent releases cannot accurately be ascribed to a specific unit. An estimate- ' should be made of the contributions from each unit based'on-input conditions, e.g., flow rates and radioactivity _ ! concentrations, or, if not practicable, the treated effluent , releases may be allocated equally to each of the radioactive .! waste producing units sharing the Radwaste Treatment' System. i For determining conformance to Operability Requirements, 'j - these allocations from shared Radwaste Treatment' Systems are ; to be added to the releases specifically attributed to each ,5 unit to obtain the total releases per unit. j a
+
t i i i 1 1 1
}
i e t 6 b 4 P 12-26 1
BRAIDWOOD Revision 1. 0 January 1994 12.4 GASEOUS EFFLUEMTS ' 12.4.1 Dose Rate Onerability Fem i r oment s 12.4.1.A The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limit ed to the following:
- 1. For noble gases: less than or equal to a dose rate of 500 nxems/yr to the whole body and less tnan or equal to a dose rate of 3000 mrems/yr to the skin, and l
- 2. For Iodine 131 and 133, for tritium, and for all radienuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate ;
of 1500 mrems/yr to any organ. Arnlicability: At all times. Action:
- 1. With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s).
Surveillance Recru i rement s 12.4.1.1.B The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM. 12.4.1.2.B The dose rate due to Iodine 131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be i within the above limits in accordance with the methodology I and parameters in the ODCM by obtaining representative 1 samples and performing analyses in accordance .71th the sampling and analysis program specified in Table 12.4-1. Barer 12.4.1.C This section is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR2O to UNRESTRICTED AREAS. These limits provide reasonable assurance that radioactive material discharged in l gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, exceeding the limits specified in 10CFR20.1301. i 4 O 12-27
BRAIDWOOD Revision'l.0'- Januaqr 1994 12.4 CASEOUS EFFLUENTS Pases For MEMBERS OF THE PUBLIC who-may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC-will.usually be sufficiently low to' compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate. occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding ganna and beta dose rates-above background'to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than'or equal ~ to 500 mrems/ year to the whole body or to- less than or equal to 3000 neems/ year to the skin. These release ~ rate limits also restrict, at all times-the corresponding thyroid dose rate'above background.vla the inhalation pathway to less than or equal to 1500 mrems/ year. This section applies to the release of radioactive materials in gaseous effluents from all units at the site. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in.HASL. Procedures Manual, MASL-300 (revised annually),. Currie, L.A., " Limits for Qualitative Detection and-Quantitative Determination - Application to Radiochemistry." Anal. Ch5m. 12,.586-93 (1968), and Hartwell, J.K., " Detection Limits for. Radioanalytical Counting Techniques," Atlantic Richfield Hanf ord Conpany Report ARH-SA-215 (June 1975). 12-28
BRAIIfdOOD Pevision 1.0 January 1994 TAI 3LE 12.4-1 PADIOACTIVE G71SEOUS WASTE SIJ4PL1!!G Af fD AfiALYSIS PROCPAM LOWER LIMIT OF GASEOUS RELEASE TYPE S Af4PL IllG MIIIIffUM AllALYSIS TYPE OF (e) DETECTIOfi FREQUEllCY FREQUEriCY ACTIVITY AtlALYSIS ( LLD) "' (hcl /cc)
- 1. Waste Gas Decay P P Tank Each Tank Each Tank Principal Gamma Emitters (2) 1 x 10 -*
Grab Sample
- 2. Containment Purge P P Ptincipal Gamma Emitters (2) 1 x 10
Each Purge (3 ) Each Purye(3) Grab Sample 11 - 3 1x10"
- 3. Auxiliary Bldg. M (4 ) (5) M Principal Gamma Emitters (2) 1 x10 -
- Vent Stack Grab Sample (Unit 1 and 2) l{- 3 1x10' Continuous (6) W (7 ) I-131 1x10-i2 Charcoal Sample I-133 1 x10 ~"
Continuous (6) W (7 ) Principal Gamma Emitters (2) 1 x 10-" Particulate Sample Cont itiuous ( 6 ) M(7) Gross Alpha 1 x 10 '" Composite Particulate Sample Continuous (6) O Sr-89, Sr-90 1 x10 ^ " Composite Patticulate Sample Continuous tioble Gas Monitor floble Gases, Gross Beta or 1x10* Gamma 12-29
i t, 4
.BRAIDWOOD. Revision 1. 0 January 1994 IABLE 12.4-1 (continued) :i TABLE NOTATIONS ,
L (1) The LLD is defined, for purposes of these specifications,-as the. smallest concentration of radioactive. material in a sample that
'f ,
will yield a net count, above system background, that.willJbe . "i detected.with 95% probability with only 5% probahility of falsely :j concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: ;! 4' LLD = "b ! E .V. 2.22 x 10' . Y
- exp (-AAt)- l i
Where: 1 LLD = the lower limit of detection (microCuries per unit mass or volume), .l st = the standard deviation of the background counting rate or of , the counting rate of a blank sample as appropriate (counts per. j minute), j E = the counting efficiency (counts per disintegration), I 9 V= the sample size (units of mass or volume),
- 2. 22 x 10" = the number of disintegrations per. minute'per microcurie, Y = the fractional radiochemical yield, when applicable, .;
A = the radioactive decay constant for the particular radionuclide ( sec ^* ) , and I At = the elasped time between the midpoint of sample collection , and the time of counting (sec). !
.. i Typical values of E, V, Y, and At should be used in the calculation.
It should be recognized that the LLD is defined as a before.the ; fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. (2) The principal gamma emitters for which the LLD specification ' applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases.and', J Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases, :This list ( does not mean that only these nucliden are to be considered. i 12-30 l
BRAIDWOOD Revision 1. 0 January 1994 TABLE 12.4-1 (continued) TAPtE NOTATIONS Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Section 12.6.2, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. (3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of BATED THERMAL POWER within a 1-hour period. (4) Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. (5) Tritfum grab samples shall be taken at least once per.7 days from the spent fuel pool area, whenever spent fuel is in the spent fuel pool. (6) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Sections 12.4.1.A, 12.4.2.A and 12.4.3.A. (7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler. -Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by ; factor of 10. This requirement does not apply if: (1) analysis'shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a f actor of 3, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. , I i i 12-31 ] l
bb , 1 j BRAIDWOOD .Revisionl.0 I Januaq/1994
, E ;
y
-s =:
12.4.2 Dose'- Noble Gasds ,3 Onerability Recuirements L 12 . 4 . 2 .~ A ' The air dose due to noble gases released in gaseous _ effluents, from each unit, to areas at and'beyond.the SITE' t BOUNDARY / UNRESTRICTED AREA BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F-1)'shall be limited to the A following: ,j t
- 1. During any calendar quarter: Less than or equal tol5 l mrads for gamma radiation and less than'or eqpal to 10 ,
mrads for beta radiation, and l r
- 2. During any calendar year: Less than or equal to 10. , ;
mrads for gamma radiation and less than-or equal'to 20. 3 mrads for beta radiation. I e Annlicability: At all_ times, f Action: l .With the calculated air dose from radioactive noble- -- ' gases-in gaseous effluents exceeding any of'thefabove' q limits, prepare and submit to the ccmmission within 30 i days, pursuant to Technical Specification 6.9.2,'a ?? Special Report that. identifies the cause(s) for. I exceeding the limit (s) and defines.the corrective-actions that have been taken to' reduce the releases and-
- the proposed corrective actions to be taken to assure !
that subsequent releases.will be'in compliance with the' above limits. , Surveillance Renuirements 12.4.2.B Cumulative dose contributions for.the current calendar ! quarter and the current calendar year for noble-gases shall: , be determined in accordance with the~ methodology and parameters in the ODCM at least~once per 31 days. , Bases
.12.4.2.C This section is provided to inplement the requirements of Sections II.h, III.A'and IV.A of Appendix I, 10 CFR Part 50. '
The Operability Requirements inplement the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and'at the same time inglement the guides set forth in Section IV.A of , Appendix I to: assure-that the releases of radioactive material in gaseous effluents:to UNRESTRICTED AREAS will be . kept "as low as is reasonable achievable." The Surveillance Requirements implement the requirements in Section III.A of ;
. Appendix I that conformance with the guides of Appendix I be i shown by calculational procedures based on models and data such that the actual' exposure of a MEMBER OF'THE PUBLIC . .I through appropriate pathways is unlikely to be substantially underestimated. -
12-32
BRAIDWOOD Revision 1. 0 January 1994 12.4.2 Done - Noble cases (Continued) Pases The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive materials-in gaseous effluents are 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 1.111,
- Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, Revision 1," July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY / UNRESTRICTED AREA BOUNDARi are based upon the historical average atmospheric conditions.
This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a cite, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit. O 12-33
BRAIDWOOD . Revision 1. 0 ! Januaqr 1994 j
-12.4.3 Dose - Todine I-131 and 133. Tritium. and Radioaceive Material in (
Particulate Form - Onerability Recuiremonts 'I
.i 12.4.3.A The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, ,
tritium, a- all radionuclides in particulate form with half-lives t greater than a days in gaseous effluents released, from each-unit, i to areas at and beyond the SITE BOUNDARY / UNRESTRICTED AREA BOUNDARY . I! (see Braidwood Station ODCM Annex, Appendix F,-Figure F-1) shall be limited to the following:
'[
l
- 1. During any calendar quarter: Less than or equal to.7.5 mrems to any organ, and l
- 2. During any calendar year: Less than or equal to 15 mrems'to ,
any organ. Annlicability: At all times. ; Action:
- 1. With the calculated dose from the release of Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents l exceeding any of the above limits, prepare and submit to the f Commission within 30 days, pursuant to Technical . ,
Specification 6.9.2, a special Report that identifies the ! cause(s) for exceeding the limit (s) and defines the-( corrective actions that have been taken to reduce the ! releases and the proposed corrective actions to be taken to l assure.that subsequent releases will be in compliance with i the above limits. ', surveillance Recuiremont s 12.4.3.B Cumulative dose contributions for the current calh ar quarter and . the current calendar year for Iodine-131 and 133, taitium, and- ! radionuclides in particulate form with half-lives greater than 8 [ days shc11 be determined in accordance with the methodology and ; parameters in the ODCM at least once per 31 days. l Basec 12.4.3.C This section is provided to implement the requirements of Sections ! II.C, III.A and IV.A of Appendix I, 10 CFR Part.50' . The , Operability Requirements are the guides set ~torth'in Section II.C of Appendix I. The ACTION statements. provide the required ' opersting flexibility and at the same time implement the guides set 4 forth in Section'IV.A of Appendix I to assure that the releases of- ! radioactive material in gaseous effluents to UNRESTRICTED AREAS -!
- will be kept "as. low as.is reasonable achievable." The ODCM -i calculational methods specified in the Surveillance Requirements ;
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 a MEMBER OF.THE PUBLIC through appropriate pathways is '2nlikely
- to be substantially underestimated. ,
i 12-34
.]
i i
,, g , - ,, - - - - - -
BRAIDWOOD . Revision 1. 0 January 1994 12.4.3 DP2 e (Continued) Pares The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology i provided in Regulatory Guide 1.109, "Celculation 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 Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-cooled Reactors,* Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. 6 The release rate specitications for Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY / UNRESTRICTED AREA BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat , producing animal's graze with consumption of the milk and ' meat by man, and (4) deposition on the ground with , subsequent exposure to man. This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit. L O 12-35
BRAIDWOOD Revision 1'0' u Januan( 1994 i 4 12.4.4 caseous Radwaste Treatment 9ystem Onorability Peauirements 12.4.4.A The VENTILATION EXHAUST TREATHENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of
.these systems shall be used te, reduce releases of ,
radioactivity-when-the projected doses in 31 days due to ' gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY / UNRESTRICTED AREA BOUNDARY (see l Braidwood Station ODCM Annex, Appendix F, Figure F-1) would > exceed: ,
- 1. 0.2 mrad to air f rom gamma radiation, or t
- 2. 0.4 mrad to air from beta radiation, or ;
- 3. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
Arnlicability: At all times. i Action: f
- 1. With radioactive gaseous waste being discharged without- !
treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant -( to Technical Specification 6.9.2, a Special' Report-that j
-includes the following information .
- a. Identification of any inoperable equipment or I subsystems, and the reason for the inoperability, j i
- b. Action (s) taken to restore the inoperable ct equipment to OPERABLE status,-and
- c. Summary description of action (s) taken to prevent- {
a recurrence, l Surveillance Recudrements
;lt y
12.4.4.1.B-Doses due to gaseous releases from each unit to areas ~at'and Li
'beyond the SITE BOUNDARY / UNRESTRICTED ^ AREA BOUNDARY shall be .i projected at least once per 31 days in accordance with the Li methodology and parameters in the ODCM when Gaseous.Radwaste Treatment Systems are not-being; fully' utilized.
.l 12-.4.'4.2.B The installed VENTILATION EXHAUST TREATMENT SYSTEM-and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Section 12.4.1 and 12.4.2 or 12,4.3.
.l
' Eases f
112.414.C The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and-the
~
VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system. 'l;
will be available for use whenever gaseous effluents require' treatment prior to release to the environment.
12-36
-l i
e p = ~ - , um e- .w. , c
BRAIDWOOD Revision 1. 0 January 1994 12.4.4 careous Radwaren Treatment rvst em (Continued) f Baser The requirement that the appropriate portions of this system j be used when specified provides reasonable assurance that i the releases of radioactive materials in gaseous effluents I will be kept "as low as is reasonably achievable". This -l section implements the requirements of 10 CFR 50.36a, l General Design Criterion 60 of Appendix A to 10 CFR Part 50 l and the design objective given in Section II.D of Appendix I. l to 10 CFR Part 50. The specified limits governing the use j of appropriate portions of the Gaseous Radwaste Treatment i System were specified as a cuitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. l-This section applies to the release of radioactive materials in gaseous eff] .ents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for f shared treatment; by such mixing, the effluent releases l cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit. l l l l O 12-37
=t f
BRAIDWOOD Revision 1. 0 - January 1994 : i l 12.4.5 Total Dose Onorability Requirements f
. . -i 12 . 4 '. 5 . A The annual (calendar year) dose or dose commitment to any l MEMBER OF THE'PUBLIC due to releases of radioactivity and.to radiation f rom uranium fuel cycle sources shall 1x3 limited to i less than or equal to 25 mrems to the whole body or any organ,. .;
except the thyroid, which nhall be limited to less than or ! equal to 75 mrems. j f~ Annlicability: At all times. I Action: l
- 1. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice -
the limits of Sections 12.3.2, 12.4.2, or 12.4.3, i calculations should be made including direct radiation contributions from the units and from outside storage tanks.to determine whether the above limits of Section l 12.4.5.A have been exceeded. If such is the. case,- i prepare ~and submit to the Commission within 30 days, t pursuant to. Technical Specification 6.9.2,.a.Special' , Report that defines the corrective action to be taken~to, -; reduce subsequent releases to prevent recurrence-of 1 exceeding the above limits and~ includes the schedule for : achieving conformance with the above limits. This : Special Report, as defined in 10 CFR 20.2203, shall ! include anLanalysis that estimates the radiation exposure ! (dose)' to a MEMBER-OF THE PUBLIC from uranium fuel cycle sources, including all effluent' pathways and direct- t radiation, f or the calendar year that includes the. l release (s) covered by this report. It shall also- ) describe levels of radiation and concentration of- 'j radioactive material involved, and the cause of the - exposure levels or concentrations. 'If_the estimated-dose (s) exceeds the above limits, and if the release' i condition resulting in violation.of 40 CFR Part.190 has. l not already been corrected, the Special Report;shall' ! include a request for a variance in accordance with the ! provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance-is granted i until staff action on the request'is complete. surveillance Renuirements
- 12. 4. 5.1. A Cumulative dose contributions f rom liquid and, gaseous ef fluents j shall be. determined in accordance with Sections 12.3.2, 12.4.2,
.and 12.4.3, and in accordance with the methodology and. I parameters in the ODCM. !
- i 12.4.5.2.B Cumulative dose contributions from direct radiation from the-units and from radwaste storage tanks shall be' determined in accordance with the methodology and parameters in the ODCM.
J This requirement is applicable only under conditions se~t forth
.t in ACTION 1 of Section 12.4.5.A. !
12-38 i a - - r -
BRAIDWOOD Revision 1.0 January 1994 12.4.5 Total nose (Continued) Pasas 12.4.5.C This section is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The section requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a . variance (provided the release conditions resulting in violation of 40 CPR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 l until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Sections 12.3.1 and 12.4.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is p'rt of the nuclear fuel cycle. I i i I O 12-39
BRAIDWOOD Revision 1. 0 f
- Januaqr 1994 j
,i
'12.5 RADIOLOGIOAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitorino Procram Onerability Remuirements 12.5.1.A The Radiological-Environmental Monitoring Program shall be ,
conducted as-specified in. Table 12 5-1. ; Arnlicability: At all times. I Action: ,
- 1. With the Radiological Environmental Monitoring Program j not being conducted as specified in. Table 12.5-1, ;
prepare and submit to the Commission, in the Annual- i Radiological Environmental Operating. Report required byg l Technical Specification 6.9.1.6, a description of the' .! reasons-for not conducting the program as required and ; the plans for preventing a recurrence. -
- 2. With the level of radioactivity as the result of plant ;
effluents;in an environmental sampling medium at a ! specified location' exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, -l prepare and submit to the Commission within 30 days, i pursuant to Technical Specification 6.9.2, a Special .i Report that. identifies the cause(s) for exceeding the .[
- Os limit (s)-and defines the corrective actions to be taken J
to reduce radioactive effluents so that the potential ! annual dose
- to a MEMBER OF THE PUBLIC is less than the .;
calendar year limits of section 12.3.2, 12 . 4 l. 2 , or 12.4.3. When more than one of the radionuclides in j Table 12.5.2 are detected in the sampling medium, .this ! report-shall be submitted if: ,
~
concentration-(1) , concentration (2), ...21.0 reporting level.(1) reporting level (2) j l When radionuclides other than those in Table 12.5-2 are. detected and are the result of plant ef f luent s', this report shall be submitte'd if the potential annual' dose
- to A MEMBER OF THE PUBLIC from al1~ radionuclides is equal to.or. greater than the calendar year limits of I Section 12.3,2, 12.4.2, or 12.4.3. This report is.not l required if the measured level of radioactivity was not ;
the result of plant effluents; however, in such an i event, the condition shall.be reported and. described in ~ l the Annual Radiological = Environmental Operating Report ; required by Section 12.6.1. t i L
*The methodology and parameters used to estimate the potential j annual dose to a MEMBER.0F THE PUBLIC:shall be indicated in this '
report. 12-40 "I
= . .. . . - . . - . . .
BRAIDWOOD Revision 1. 0 , Januatr 1994 12.5 RADIOLOGICAL ENVIROWRNTAL MONITORING PROGRAM (Continued)
- 3. With the milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table-12.5-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted f rom the monitoring program. Submit controlled version of the CDCM within 180 days including a revised figure (s) _,
and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location (s) for obtaining samples. surveillance Reauiremener 12.5.1.B The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5-1 from the l specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 12.5-1 and the detection capabilities required by Table 12.5-3. Pares 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Part 50 and 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 the modeling of the environmental exposure pathways. Guidance for this monitoring program is , provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience. The required detection capabilities for environmental sample , analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. O 12-41
- .. _ ..... . . - . . ~ . . . - . . . - . . .-. - - ..- . . . . .~, . ~ . - . ...-. ,. .
1 i
- BRAIDWOOD Revision 1. O j
' January 1994 e
12.5 PADIOLOGIcAL rtw1RONMC'NTAL MONTTORING ' PROGRLM (Continued) Detailed discussion of the LLD, and other detection. limits, .; can be found in NASL Procedures Manual, HASL-300 (revised ; annually), Currie,-LA., " Limits for Qualitative Detection i
- ' -and Quantitative Determination - Application =to'
,. Radiochemistry 4 Ig a l . Chem. 40. . 586~93 (1968), and , l Hartwell, J.K., Detection Limits-for Radioanalytical' ! Counting Techniques," Atlantic Richfield Hanford Ccmpany .I Report ARM-S'A-215 (June 1975). _; 4
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BRAIDWOOD Revision 1.O January 1994 TABLE 12.5-1 RADIOLOGICAL E*IVIROI!MEllTAL MOMITORING PROOPldi NUMBER OF REPRESEMTATIVE EXPOSURE PATW'AY SAMPLES AND SAMPLIIIG AMD TYPE AND FRECUENCY AND/OR SAMPLE SAMPLE LOCAT IOU S ' ' ' COLLECTION FREOUENCY OF ANALYSIS
- 1. Direct Radiation" Forty routine monitoring stations Quarterly. Gamma dose quarterly.
either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows: An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector in the 6- to 8- km range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations. 12-43
u-4 s - BRAIDWO'- L Ision'l'0:- . JanuaryJ1994i TABLE 12.5-1 (Continued)~ 4 RADIOLOGICAL EINIROMMENTAL MONITORIMG PROGRAM NUMBER- OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND . SAMPLING AND TYPE AND FREQUENCY-AMD/OR SAMPLE SAMPLE LOCATIONS
- COLLECTION FREOUEt!CY OF ANALYSIS
._2. Airborne
~ Radiciodine and Samples from five. locations: ~ Continuous' sampler Radioicdino Canister: Particulates , operation with sample I-131 analysis weekly. Three samples from close to the collection weekly, or three SITE BOUNDARY locations, more frequently if in different sectors, of the: ' required by dust Particulate Sammler: - highest calculated annual average loading. Gross-beta radioactivity ground level D/Q; analysis following filter change;* .and One sample from the vicinity of gamma isotopic analysis
- a community having the highest of composite (by location).
calculated, annual average ground- quarterly, level-D/Q: ' and One sample from a control location,
'as'for example 10 to 30 km distant -
and in the least prevalent wind direction.
- 3. Waterborne Surface *
~
'a. One sample upstream. Composite sample over Gamma isotopic analysis"'
One sample-downstream. 1-month period'by monthly. Ccmposite for' weekly grab samples. ' tritium analysis quarterly. _
- b. Ground Samples'from one or two-' sources . Quarterly. Gamma isotopic
- and only,if'li.kely to be,affected - 'U . tritium analysis quarterly.
12-44=
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1 BRAIDWOOD Revision 1.0 January 1994 TABLE 12.5-1 (Continued) RADIOLOGICAL EUVIROMMEMTAL MONITORING PROGPAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AMD/OR SAMPLE SAMPLE LOCATIONS'" COLLECTICII FREOUENCY OF ANALYSIS 3 '. Waterborne (Continued)
- c. Drinking One sample of each community Composite sample over I-131 analysis on each drinking water supply within 2-week period"" when composite when the dose 10 miles downstream of the I-131 analysis is calculated for the discharge. performed, monthly consumption of the water composite otherwise. is greater than 1 mrem per One sample from a control year.(8) Composite for gross locatien. beta and gamma isotopic analyses (4) monthly.
Composite for tritium analysis quarterly.
- d. Sediment One sample from downstream area Semiannually. Gamma isotopic analysis"'
from shorellne with existing or potential semiannually. recreational value.
- 4. Ingestion
- a. Milk Samples from milking animals Semimonthly when Gamma isotopic"' and I-131 in three locations within animals are on analysis semimonthly when 5 km distance having the highest pasture, monthly at animals are on pasture; dose potential. If there are other times. monthly at other times.
none, then, one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per yr"". One sample from milking animals at a control location, 15 to 30 km distant and in the least prevalent wind direction. 12-45 O O O .
BRAIDvlO ' - .dw[sion;1.O'
~ . January ; 19 94.
TABLE 12.5-1 (Continued) EADIOLOGICAL ENVIRONMEtITAL MONITORIIIG PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS"' COLLECTIOri FREOUENCY OF ANALYSIS
- 4. Ingestion' .(continued).
- b. Fish and Representative samples'of Three times per year Gamma isotopic analysis"'
Invertebrates commercially and recreationally (spring, summer and on edible portions. important species in vicinity fall). of plant discharge area. Representative samples of commercially and recreationally important species in areas not influenced by plant discharge.
- c. Food Products' Representative samples of the .
At. the time of Gamma isotopic analysis i" principal classes of food products harvest "' . on edible portion. from any area within 10 miles of the plant that.is irrigated by water in which liquid plant wastes have-been discharged. Samples of three different kinds Monthly when Gamma isotopic"' and I-131 of broad leaf vegetation grown. available, analysis. nearest each cf two different offsite locations of highest predicted annual average ground-level D/Q if milk ~ sampling.is not performed. One sample of each of'the similar Monthly when Gamma isotopic"' and I-131 l- . broad leaf vegetation grown 15 to- 'available. analysis. 30 Am-distant in the least prevalent wind direction if milk sampling is not performed. 12-46' i i l 1 ___ m. .i...-_-,..,_-..__,-A._ .
*l BRAIDWOOD Revision 1.0 January 1994 TAPLE 12.5-1 (Oontinued)
TABLE NOTATIONS i (1) Specific parameters of distance and direction sector trom the l centerline of one unit, and additional description where pertinent, shall be provided for each and every sample location in Table 12.5-1 in a table and figure (s) in the ODCM. Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Section 12.6.1. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and allocations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Submit controlled revisions of the ODCM within 180 days including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location (s) for obtaining samples. (2) One or more instruments, such as a pressurited ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The 40 ' locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., at an ocean site, some sectors will be'over water so that the number of dosimeters may be reduced accordingly. The f requency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mnan of control samples, gamma isotopic analysis shall be performed on the individual samples. O 12-47
.~ _. . . _ .
t , !BRAIDWOOD , Revision 1. 0 = January 1994
?
v
.1 TABLE 12.5-1 fcontinued) ,
.. ~
TAPLP NOTATIDNS (4) Gamma isotopic analysis means the identification and l quantification of gamma-emitting radionuclides that may be
~. 3 attributable to the effluents from the facility. '
t . (5) The
- upstream sample" shall be taken at a distance beyond ~ j significant: influence of the discharge. The " downstream *. sample l shall be taken in an area beyond but near the. mixing zone. !
(6) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program. composite sample aliquots shall be collected at time intervals-that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample. (7) ' Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. (. 8 ) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM. (9) If harvest occurs more than once a year, sampling shall be
~
performed during each discrete harvest. EIf harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products. M 12-48
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V DWOOD'. dsion 1.'02 January '199 4. TABLE 12.5-3 r, DETECTIOM CAPABILITIES FCR ENVIRONMENTAL SAMPLE ANALYSIS'" .,. LOWER LIMIT OF DETECTION (LLD)'2"U WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT-ANALYSIS (pCi/L) OR GASES (pC1/m') (pC1/kg, wet) (pCi/L) (pci/kg, wet) (pCi/kg,: dry)- Gross Beta 4 0.01 H-3 2000*- FM-54 15 130 Fe-59 30- 260
?
Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 : I-131 l'C 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 '18 0.06 150- 18- 80' 180 [ Ba-La-140 15 15
*If no drinking water' pathway exists,.a value of 3000 pCi/L may be used.
I-
.12-50 6
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i4 BRAIDWOOD Revision 1. 0 January 1994 l 1 TABtE 17.5-3 (Continued) TABtF NOT$TIONS I { (1) This list does not mean that only these nuclides are to be ! censidered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported f in the Annual Radiological Environmental Operating Report pursuant to Section 12.6.1. (2) Required detection capabilities for thenmoluminescent dosimeters used for environment Measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. (3) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, 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, which may include radiochemical separation: 4.66s n LLD = E V - 2.22 x 10' - Y . exp (-AAt) Where: LLD = the "a priori" lower limit of detection (picocuries per unit mass or volume), sn = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E= the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 2.22 = the number of disintegrations per minute per picocurie, Y= the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec ~'), and At = the elasped time between sample collection, or end of j the sample collection period, and the time of counting (sec). 1 Typical values of E, V, Y, and At should be used in the calculation. I j It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. 12-51 L . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
i' -BRAIDWOOD- Revision 1. 0
. January 1994 '
9 v TABLE 12.5-3-(continuedi-TABLE NOTATIONS Analysen-shall be performed in such a manner that the stated LLDs .; will be achieved under routine conditions.. Occasionally, background fluctuations, unavoidable small sample sizes,'the presence.of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Section 12.6.1. (4) LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may.be used. 12-52
BRAIDWOOD Revision 1. 0 January 1994 12.5.2 tand Use censur Onerability Recuiremente 12.5.2.A. A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, and the nearest residence. For dose calculation, a garden will be assumed at the nearest residence. Annlicability: At all times. Action:
- 1. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Section 12.4.3, identify the new location (s) in the next Annual Radiological Environmental Operating Report, pursuant to Section 12.6.1.
- 2. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location (s), excluding the control location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to Section 12.6.1, submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change in' sampling locations.
Surveillance Reauirements 12.5.2.B The Land Use Census shall be conducted during the growing season i at least once per 12 months using that inf onmation that will provide the bent results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 12.6.1. Bares 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY / UNRESTRICTED AREA !! BOUNDARY are identified and that modifications to the Radiological 4 Environmental Monitoring Program given in the ODCM are made if required by the results of this census. The best information from . the door-to-door survey, from aerial survey, or from consulting I with local agricultural authorities shall be used. ; i 12-53
~'
'E
?
,,4 BRAIDWOOD ~ Revision 1,0 : }
January 1994 .; T ' , . 12.5 2- Land tire census -(Continued) !
- Ba's e r
, This census satisfies the requirements of Section IV,B.3 of l Appendix I to 10 CFR Part 50. An. annual garden census will j
, not be required since the licensee will assume that there is I a garden at the, nearest residence in each sector for dose-calculations. '; f i e j-i 1 ) i i t
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i BRAIDWOOD Revision 1. 0 January 1994 12.5.3 Int erl aborat orv connariren Procram f ODerability Recuirements __ 12.5.3.A Analyses shall be performed on radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 12.5-1 Arnlicabilitv. At all times. Action:
- 1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursaant to Section 12.6.1.
Surveillance Recuiremente 12.5.3.B The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 12.6.1. Parer 12.5.3.C The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. i
- i O
12-55
Sw BRAIDWOOD. / Revision 1.0' ! January 1994 !
.)
l 12. 6' REPORTTNG RrOUIREMENTS
-l 12,6.1 Annual Radic1'ocical Environmental oneratino Renort* ;
Routine Annual Radiological Environmental Operating Report . covering the operation of the Units during the previous ! alendar year shall be submitted prior to May 1 of each ! year. The initial report shall be submitted prior to May 1- ! of the year following initial criticality. '} The Annual Radiological Environmental Operating Report shall. ; include summaries, interpretations, and an analysis of. ; trends of the results of the radiological environmental' ! surveillance activities for.the report period, including a 'l comparison ~with preoperational studies, with operational l controls as. appropriate, and with previous environmental j surveillance reports, and an assessment of the observed ! impacts of the plant. operation on the environment. The l reports shall also include the results of the Land Use j Census required by Section 12.5.2. j i The Annual Radiological Environmental Operating Report shall- l 6 include the-results of all radiological environmental :l' samples and of all environmental' radiation measurements [ taken during the period pursuant to the locations specified ; in the tables and figures in the ODCM, as well as. summarized- l and tabulated results of these analyses and measurements in ; the f ornat of the table in the Radiological Assessment , Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for ( inclusion with the report, the report shall be' submitted .; noting and explaining the reasons for the missing results. j The missing data shall be submitted as soon as possible in a i supplementary report. ~! 4 The reports shall also include the following: a summary. i description of the Radiological Environmental Monitoring ; Program; at least two legible maps ** covering all sampling -j locations keyed to a table giving. distances and directions } from the midpoint between the reactors; the results of . ] licensee participation in the Interlaboratory Comparison j Program and the corrective actions being taken if the- i specified program is not being. performed as. required by j section 12.5.3; reasons for not conducting'the Radiological j Environmental Monitoring Program as required by Section l 12.5.1, and discussion of all deviations from the sampling i schedule of Table 12.5-1; discussion of environmental sample ! measurements that exceed the reporting levels of Table ; 12.5-2 but are not the result of plant effluents, pursuant i to Section 12.5-1; and discussion'of all analyses;in which .i the LLD required by Table 12 5-3'was not ~ achievable.
*A single submittal may be made for a m;ultiple unit' station.
f **One map may cover locations near the SITE BOUNDARY / UNRESTRICTED
^
AREA BOUNDARY; a second nay include the more distant locations. y l 12-56 . n i
4 BRAIDWOOD Revision 1. 0 January 1994 4 12.6 EEPORTIMG PEOlHRFMENTF (Continued) 12.6.1 Ennual R adi ol oq,1gp1 Environmental eneratina Renort (continued) The Annual Radiological Envirormental Operating Report shall also include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY / UNRESTRICTED AREA BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM. The Annual Radiological Environmental Operating Report to be submitted prior to May 1 of each year shall also include an j assessment of radiation doses to the most likely exposed MEMBER ' OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent 1 pathways and direct radiation, for the previces calendar year ! to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous ef fluents are given in Regulatory quide 1.109, Rev. 1, October 1977.
- In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this sunmary of required meteorological data on site in a file that shall be provided to the NRC upon request.
O ( 12-57 { I L - - - - _ - _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
. _ ,. . . ~
3 BRAIDWOOD- Revision 1.0= January 1994
- f (x = 12.6 REPORTING REOUTREMENTS (Continued) 'i
^4-I >
12.6.2 Annuali'Radioastive Effluent Pelease Rerort** Routine Annual Radioactive Effluent Release Reports covering.the f operation of the unit during the previous calendar year operation :l 2 shall be submitted prior to April 1 og the following" year. .'The' ? period of the first report shall begin with the date of initial- ' criticality. 7 The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined-in ' Regulatory Guide 1.21, " Measuring Evaluating,'and Reporting Radioactivity in Solid Wastes and Releases of Radioactive
- Materials in Liquid'and Gaseous Effluents from Light-Water-cooled, Nuclear Power Plants," Revision 1., June 1974, with data summarited on a quarterly basis following the format of Appendix ;
B thereof. l For solid wastes, the format for Table 3 in Appendix B shall.be - supplemented with three additional categories: class: of solid wastes (as defined by 10 CFR Part 61), type of container-(e g.,. . LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION agent or absorbent (e.g, cement, urea formaldehyde). The Annual Radioactive Effluent Release-Reports-shall include a-list and description of unplanned releases from the site to
.l.
.(
\
UNRESTRICTED AREAS of radioactive materials in gaseous and' liquid' effluents-made during the reporting period. The Annual Radioactive' Effluent Release Reports shall include anyo l~ changes made during the reporting period to the PCP, as well as , any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.6.3'. i The-Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the t inoperability of liquid or' gaseous effluent monitoring. l instrumentation was not corrected within the time specified in ;
.Section 12.2.1 or 12.2.2, respeccively; and description of the i events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6, respectively. >
A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common "l to all units at the station; however, for units with separateL radwaste systems, the submittal shall specify the releases of radioactive material from each unit. Semiannual Radioactive Effluent Release Reports are required- t until the frequency change to annual is approved by the NRC , in the.Braidwood~ Tech Spees. -l 2 Semiannual Radioactive Effluent Release reporting is required i within 60 days after January 1 and July 1 of each year. ; (_,I'. , l 12-58
i BRAIDWOOD Revision 1. 0 January 1994 12.6 FEPORTING PEOUIREMENTS (Continued) l 12.6.3 Offsite Dose calculaticn Manual toDCM) 12.6.3.1 The ODCM shall be approved by the Commission prior to implementation. 12.6.3.2 Licensee-initiated changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be Specification 6.10.2. This documentation shall contain:
- 1. Sufficient information to support the change together 1 with the appropiate analyses or evaluations justifying the changes (s); and
- 2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20,
. 160, 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.
- b. Shall become effective after review and acceptance by the Onsite Review and Investigative Function and the approval of the Plant Manager on the date specified by the Onsite Review and Investigative Function.
- c. Shall be submitted to the Commission in the form of a -
complete legible copy of the entire ODCM as part of or concurrent with the Annuali 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 the 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. O 12-59
, -. .s, . -
1 l m BRAIDWOOD Revision 1.0. January 1994 - l
- p. 12.6 REPORTING REOUIREMEMTS (Continued)'
'T
"- Ma-ior Chances to LitTuid and Gaseous Radwnste Treatment Systems *
'12.6.4 Licensee-initiated major changes to the Radvaste Treatment Systems (liquid and gaseous):
- a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in'which the evaluation was reviewed by the Onsite Review-and
~
Investigative Function. The discussion of each-change 1 shall contain:
.a
- 1) A summary of the evaluation that led to the '
determination that the. change could be made in
-accordance with 10 CFR 50.59;
- 2) sufficient detailed information to-totally support the.. ,
reason for the change without benefit of additional and: supplemental information;
- 3) A detailed. description of the equipment, components, and processes involved and the' interfaces with other plant systems.
- 4) 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 1 application _and amendments thereto;
- 5) An evaluation of the change,.which shows the expected maximum exposures to a MEMBER OF THE pUBLIC in the UNRESTRICTED AREA and to the general population that ,
i differ from those previously estimated in the License application and amendments thereto;
- 6) A comparison'of the predicted releases of radioactive materials, in liquid and gaseous' effluents and in solid waste, to the actual releases for the period prior.to when the changes are to be made; 7)' An estimate of the exposure to plant' operating-
. personnel as a result of the change; and
- 8) Documentation of the fact that the change was reviewed. 3 and found acceptable by the Onsite Review and '
Investigative Function.
- b. Shall become effective upon review and acceptance by the ,
Onsite Review and Investigative Function. Licensees may choose to submit tlua information called ~for in this section'as part of the annual FSAR update. ; 1 12-60 1
[.;
't.
ERAIDWOOD ~ Revision 1.0-January 1994
..4..
.f BRAIDWOOD ANNEX INDEX
'l PAGE REVISION PAGE REVISION APPENDIX F F-i 1.0 F-43 1.0 F-ii 1.0 F-44 1.0 F-111 1.0 F-45 1.0 F-iv 1.0 F-46 1.0 F-1 1.O F-2 -1.0' F-3 1.0 F-4 1.0 F-5 1.0 F-6 1.0 F-7 1.0 F-8 1.0 F-9 1.0 F-10 1.0-
.F-11 1.O 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-15 1.O
\
.F-20 1.O F-21 1.0 F-22 1.O F-23 1.0 F-24 1.0 F-25 1.0 F-26 1.0 F-27 1.0 F-28 1.0 F-29 1.0 F-30 1 :. 0 F-31 1.0 1 F-32 1.0 F-33 1.0 F-34 1.0 F-35 1.0 F-36 1.0 F-37 1.0 F-38 1.0 F-39 -1.0 F-40 1.0 F-41 1.0 F-42 1.0 F-1
l l
'I EhAIDWOOD Revision 1.0 )
January 1994 j APPENDIX F l STATION-SPECIFIC DATA FOR BRAIDWOOD l UNITS 1 AND 2 1 i TABLE OF CONTENTS PAGE ! F.1 INTRODUCTION F-1 F.2 REFERENCES F-1 i e b i j O\ F-ii j
e
-BRAIDWOOD Revision 1.0 January 1994 l' - -
APPENDIX F LIST OF TABLES MUMPPR TITLE 214E F-1 Aquatic Environmental Dose Parameters F-2 F-2 Station Characteristics F-3 F-3 Critical Ranges F-4 F-4 Average Wind Speeds F-5 F-5 X/Q and D/Q Maxima At or Beyond the Unrestricted Area Boundary F-6 F-Sa X/Q and D/O Maxima At or Beyond the Restricted Area Boundary F-7 F-6 D/O at the Nearest Milk Cow and Meat Animal 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 Based on 1 cm Depth at the Restricted Area Boundary for Selected Nuclides F-24 Supplemental Tables A Mixed Mode Joint Frequency Distribution Table Summaries - 203 and 34 Foot Elevation Data F-39
-Sunenary Table of Percent by Direction and Class
-Summary Table of Percent by Direction and Speed
-Summary Table of Percent by Speed and Class B Ground Level Joint Frequency Distribution Table Summaries F-43
-Summary Table of Percent by Direction and Class
-Summary Table of Percent by Direction and Speed
-Summary Table of Percent by Speed and Class F-lii e
L ' BRAIDWOOD Revision 1.0 l Jaanary 1994 i
.i APPENDIX F LIST OF FIGURES i
l 1RTMPER I.22J,3 FAGE i F-1 Unrestricted Area Boundary F-45 F-2 Restricted Area Boundary F-46 - t l i t O 4 V W L C i O' F-iv ,
l: I ~ *. . p BRAIDWOOD Revision 1 O January 1994 L .
-APPElmIX F STATION-SPECIFIC DATA FOR BRAIDWOOD UNITS 1 AND 2 F.1 INTRODUCTION This appendix contains data relevant to the Braidwood site. Included is a figure showing the unrestricted area boundary and values of parameters used in offsite dose assessment.
F.2 REFERENCES
- 1. Sargent & Lundy, Nuclear Analysis and Technology Division Braidwood Calculation No. ATD-0149, Revision 0 for Braddwood.
- 2. " Assessment of the Impact of Liquid Radioactive Effluents ;
from Braidwood Station on Proposed Public Water Intakes at Wilmington, Illinois *, J.C. Golden NSEP, January 1990.
- 3. " Verification of Environmental Parameters Used for Commonwealth Edison Company's Offsite Dose Calculations,"
NUS Corporation, 1988.
- 4. " Verification of Environmental Parameters Used for Commonwealth Edison Company *s Offsite Dose Calculations.*
NUTECH Engineers Group, 1992. 1 J i F-1 _____*w__
BRAIDWOOD Revision 1.0 January 1994 Table F-1 Aquatic Environment Dose Parameters General Information There is no irrigation occurring on the Kankakee River downstream of
- the station.
Recreation includes one or more of the following: boating, waterskiing, swimming, and sport fishing. Downstream dams are within 50 miles of the state. One is located on the Kankakee. The other is the Illinois River at Dresden Island, Marseilles, and Starved Rock. The Kankakee River flows into the Illinois River about 12 river miles downstream of the station. This is based on information in Figure 2.1-13 of the Braidwood Environmental Report and in Section 2.4.1.1 and Figure 2.4-2 of the LaSalle Environmental Report. Water and Fich Incestion Parameters Paramet er* Value U*, water usage, L/hr 0.042 U' , fish consumption, kg/hr 2.4E-3 t 1/ M* , 1/M' O.25, 1.0 F" , cfs 1.85E4 F,f cfs 5.63E3 t', hr" 24.0 t*, hr" 3.0 Limits on Radioactivity in Unnrotected Outdoor Tanks d outside Temporary Tank 4 10 Ci* (per Technical Specification 3.11.1.4)
- The parameters are defined in Section A.2.1 of Appendix A.
' t' (hr) = 24 hr (all stations) for the fish ingestion pathway t* (hr) = 3 hr (distance nearest potable water intake, to Wilmington, is 4 river miles downstream; a flow rate i of 1.4 mph is assumed) ; 4 See Section A.2.4 of Appendix A. I
- I Tritium and dissolved or entrained noble gases are excluded j from this limit.
l O F-2 l l
?
]
BRAIDWOOD Revision 1.0 { January 1994 j Table F-2 .l i
.. Station Characteristics l N, '!
l STATION: Braidwood ! ll LOCATION: Braceville, Illinois
'{
CHARACTERISTICS OF ELEVATED RELEASE POINT: Not Applicable (NA)
- 1) Release Height = _3n 2) Diameter = m
- 3) Exit Speed = ms" 4) Heat Content Kcal s"' l I
i CHARACTERISTICS OF VENT STACK RELEASE POINT i i
- 1) Release Height = 60.66 m' 2) Diameter'= 2.80 m '!
I
- 3) Exit Speed r 11.0' ms"* f l
i CHARACTERISTICS'OF GROUND LEVEL RELEASE .i
'l
- 1) Release Height = 0 m j
- 2) Building Factor (D) = 60.6 m' :f r
METEOROLOGICAL DATA
-[
-i A 3?O ft Tower.is Located 573 m NE of vent stack release point
,i i
Tower Data Used in Calculations _; I 4 Wind Speed and Differential ( Release Point Direction Temperature i
+
Elevated fMA) (MA) Vent 203 ft 199-30 ft .j Ground 34 ft 199-30 ft
*Used in calculating the meteorological and dose factors in f Tables F-5, F-6, and F-7. See Sections B.3 through B.6 of 1 Appendix B. .{
'I c
t F-3 , i I
BRAIDWOOD Revision 1.0-January.1994 Table F-3 Critical Ranges Unrestricted Area Restricted Nearest Nearest Dairy Farm Bounda ry* Area Boundary Resident' Within 5 Miles
- Direction rmi im) (m) _
(m) N 610 610 800 None NNE 914 914 1400 None NE 792 792 1000 None ENE 701 701 1300 None E 1036 1036 1300 3540 ESE 2713 1841 3500 None SE 3414 3414 4300 None SSE 3444 3444 5300 None S 4633 4633 6800 None SSW 975 975 2400 None SW 625 625 800 None WSW 533 533 700 None W 518 518 600 None WNW 503 503 600 None NW 495 495 600 7700 NNW 510 510 600 None
- See Updated Final Safety Analysis Report Table 2.1-la and Environmental Report. Used in calculating the meteorological and dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of Appendix B.
19 92 annual survey by Teledyne Isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters.
- 1985 annual milch animal census, by Teledyne Isotopes Midwest i Laboratories. Used in calculating the D/Q values in Table F-6. The I distances are rounded to the nearest conservative 100 meters.
I Oi F-4 I l
BRAIDWOOD-- Revision 1.0 January 1994 Table F-4
'k/ Average Wind Speeds Average Wind Speed (m/sec)* ;
Downwind l ; Direction El eva t ed- Mixed Mode Ground Levelt' I ; r N 7.6 6.0 4.7 i NNE 7.5 5.8 4.4' ! NE 6.1 5.3 3.9 ; ENE 6.' 5.2 ~ 3.7 i E 6.6 5.4 4.0 ESE 6.8 5.6 4.3 ! SE 6.2 5.3 3.9 i SSE 5.8 5.2 4.1 S 5.5 4.9 3.6 ! SSW 5.5 5.0 3.7 , SW 5.3 4.8 3.3 L WSW 4.7 4.2 2 -. 4 W 5.4 4.4 2.2 l WNW' 6.0 4.6 2.4 r NW 6.0 4.8 3.1 NNW 6.8 5.4 3.9 l i h
" Based on Braidwood site meteorological data, January 1978-through December 1987 Calculated in Reference 1 of Section
_F.2, using formulas in Section B.l.3 of Appendix B.
"The elevated and ground level values are provided for reference purposes only. Routine dose calculations are performed using the mixed mode values.
i O F-5
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Table.F-7 (Continued) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary ' '
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BRAIDWOOD Revision 1.0'- January 1994 Table F-7a MQximum offsite Finite Plume Gamma Dose. Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-83m Downwind Controlled Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mead /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) N 610. 610. 1.455E-04 1.097E-04 610. 5.333E-04 4.021E-04 NNE 914. 914. 6.375E-05 4.807E-05 914. 2.125E-04 1.602E-04 NE 792. 792. 3.828E-05 2.886E-05 792. 2 OO7E-04 1.513E-04 ENE 701. 701. 5.294E-05 3.992E-05 701. 2.575E-04 1.941E-04 E 1036. 1036. 3.703E-05 ,2.792E-05 1036. 1.718E-04 1.295E-04 ESE 1941. 1841, 1.84BE-05 1.394E-05 1841. 7.237E-05 5.457E-05 SE 3414. 3414. 7.089E-06 5.345E-06 3414. 2.141E-05 1.614E-05 SSE 3444. 3444. 6.047E-06 4.559E-06 3444. 1.798E-05 1.356E-05 5 4633. 4633. 3.224E-06 2.431E-06 4633. 9.268E-OG,6.988E-OG SSW 975. 975. 2.363E-05 1.782E-05 975. 1.444E-04 1.088E-04 SW 625. 625. 6.030E-05 4.546E-05 625. 3.762E-04 2.836E-04 WSW 533. 533. 9.OOOE-05 6.786E-05 533. 6.336E-04 4.777E-04 W 518. 518. 9.909E-05 7.471E-05 518. 6.292E-04 4.744E WNW 503. 503. 1.20SE-04 9.082E-05 503. 6.653E-04 5.016E-04 NW 495. 495. 1.242E-04 9.366E-05 495. 6.066E-04 4.574E-04 Nhd 510. 510. 1.322E-04 9.969E-05 510. 6.144E-04 4.633E-04 Braidwood Site Meteorological Oata 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. Routine dose _ calculations are performed using mixed mode release data. 9 94 9. .
r- B "' WOOD
' RevisiorN O : ~ .x
- ( January ()4 Table F-7a (Continued)
Maximum Offnite Finite Plume Gamma Dose Factors Based on 1 cm Depth at.the Restricted Area Boundary for Kr-85m Downwind Controlled Mixed Mode (Vent) Release Ground Level Release Ofrection Area Bound Radius V VBAR Radius G _ GBAR (meters) (meters)-(mrad /yr)/(uCt/sec) ( me t er s ) (mrad /yr)/(uC1/sec) N 610. 610. 9.989E-04 9 590E-04 610. 2.731E-03 2.614E-03 NNE 914, 914 4.979E-04 4.785E-04 914. l.222E-03 1.171E-03 NE 792. 792. 3.618E-04 3.48tE-04 792. 1.173E-03 1.124E-03 ENE 701. 701. 4.452E-04 4.280E-04 701. 1.363E-03 1.3OSE-03 E 1036. 1036. 3.452E-04 3.320E-04 1036. 1.023E-03 9.809E-04 ESE 1841. 1841. 1. 921E-04 't . 8 49E -04 1841. 5.190E-04 4,981E-04 SE 3414. 3414. 8.179E-05 7.874E-05 3414. 1.970E-04 1.893E-04 SSE 3444 3444 6.958E-05 6.700E-05 3444. 1.634E-04 1.570E-04 5 4633. 4633, 4.OOOE-05 3.851E-05 4633. 1.05tE-04 1.010E-04 SSW 975. 975. 2.413E-04 2.323E-04 975. 9.063E-04'8.688E-04 SW 625. 625. 5.268E-04 5.065E-04 625. 2.Ot9E-03 1.933E-03 WSW 533. '533. 7.031E-04 6.755E-04 533. 3.226E-03 3.087E-03 W 518. 518. 6.908E-04 6.632E-04 518. 3.08tE-03 2.947E-03 WFJW 503. 503. 7.511E-04 7.204E-04 503. 3.126E-03 2.988E-03 NW 495. 495. 8.396E-04 8.059E-04 495. 2.915E-03 2.788E-03 NNW 510. 510. 9.023E-04 8.662E-04 510. 3.091E-03 2.958E-03 - Braldwood Site Meteorological Data 1/78 - 12/87 F-25 _ . - _ . _ _ , ._ __ - . . ~ .. . __ _. . _ . _ __ ____ _ ______-- ___._ _ _ ____ _ __ _ -_
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I g . . January C )4'- Table F-7a (Continued) Maximum Offsite Finite Plume Gamma-Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-131m Downwind Controlled Mixed Mode (vent) Release Ground Level Release Directton Area Bound Stadius V VBAR l'adius G GBAR (meters) (meters) (mrad /yr)/(uC1/sec) (meters) (mrad /yr)/(uC1/sec) N 610. 610. 1.355E-04 1.065E-04 610. 4.922E-04 3.831E-04 NNE 914 914. 6.125E-05 4.839E-05 914. 1.988E-04 1.553E-04 NE 792. 792. 3.806E-05 3.031E-05 792. 1.946E-04 1.52OE-04 FNE 701. 701. 5.153E-05 4.083E 701. 2.358E-04 1.838E-04 E 1036. 1036. - 3.80$E-05 3.024E-05 1036. 1.677E-04 1.3 TOE-04 ESE 1841. 1841. 1.944E-05 1.553E-05 1841, 7.757E-05 6.091E-05
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January V 4 . Table F-7a (Continued) Maximum Offsite Finite. Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135 Downwind Controlted Mixed Mode (Verit ) Release Groutid Level Release Direction Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(Oct/sec) (meters) (mred/yr)/(uCl/sec) N 610. 610. 1.353E-03 1.307E-03 610. 3.674E-03 3.548E-03 NNE 914. 9 14. 6.781E-04 6.554E-04 914 1.652E-03 1.596E-03 NE 792. 792. 4.952E-04 4.788E-04 792. 1.599E-03 1.545E-03 ENE 701. 701. 6.084E-04 5.880E-04 -701. 1.833E-03 1.770E-03 E 1036. 1036. 4.753E-04 4.595E-04 1036. 1.395E-03 1.348E-03 ESE -1841, 1841. -2.657E-04 2.569E-04 1841. 7.227E-04 6.983E-04 SE 3414 3414. 1.160E-04 1.12tE-04 3414 2.914E-04 2.816E-04 SSE 3444. 3444. 9.782E-05 9.459E-05 3444. 2.377E-04 2.297E-04 S' 4633. 4633. 5.868E-05 5.674E-05 4633. 1.698E-04 1.64tE-04 SSW 975. 975. 3.328E-04 3.217E-04 975. 1.253E-03 1.211E-03 SW 625. 625. 7.237E-04'6.995E-04 625. 2.748E-03 2.653E-03 WSW 533. 533. 9.642E-04 9.318E-04 533. 4.369E-03 4.218E-03
'W 518. 518. 9.408E-04 9.091E-04 518. 4.151E-03 4.OO8E-03 WNW 503. 503. 1.OtBE-03 9.833E-04 503. 4.203E-03 4.058E-03 NW 495. 495. 1.139E-03 1.101E-03 495. 3.908E-03-3.773E-03 NNW 510. 510. t.225E-03 1.183E-03 510. 4.166E-03 4.022E-03 Braldwood Site Meteorologicat Data 1/78 -
12/87 s F-35
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BRAIDWOOD ~ 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 Contro11ed Mixed Mode (Vent) Release Ground level Release Directton Area Bound Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uCt/sec) (meters) (mrad /yr)/(uCf/sec) N 610. 610. 6.360E-04 6.154E-04 610. 1.202E-03 1.164E-03 NNE 914. 914 2.578E-04'2.494E-04 914. 4.345E-04 4.205E-04 NE 792. 792. 1.950E-04 1.887E-04 792. 3.640E-04 3.522E-04 ENE 701. 701. 2.355E-04 2.279E-04 701. 4.977E-04 4.816E-04 E 1036. 1035. 1.407E-04 1.361E-04 1036. 2.400E-04 2.322E 04 ESE 1844. 1841. 5.208E-05 5.040E-05 1841. 6.192E-05 5.992E-JS SE 3414. 3414 8.468E-06 8.195E-06 3414. 6.393E-06 6.186E-06 SSE 3444 3444. 7.384E-06 7.146E-06 3444. 6.474E-06 6.265E-06 5 4633. 4633. 1.951E-OG 1.888E-06 4633. 1.457E-06 1.4 TOE-OG SSW 975. 975. 1.038E-04 1.OO4E-04 975. 1.812E-04 1.753E-04 SW 625. 625. 2.625E-04 2.541E-04 625. 5.373E-04 5.199E-04 WSW 533. 533. 3.189E-04 3.087E-04 533. 8.494E-04 8.219E-04 W 518. 518. 3.247E-04 3.143E-04 518. 8.444E-04 8.170E-04 WNW 503. 503. 3.635E-04 3.517E-04 503. 9.37tE-04 9.067E-04 NW 495. 495. 4.769E-04 4.615E-04 495. 1.167E-03 1.129E-03 NNW 510. 510, 5.441E-04 5.265E-04 510. 1.222E-03 1.182E-03 Braidwood Site Meteorological Data 1/78 - 12/87 i l ! G . Ge e..
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