ML20216H432
| ML20216H432 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Braidwood  |
| Issue date: | 12/31/1997 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20216H409 | List: |
| References | |
| PROC-971231-01, PROC-971231-1, NUDOCS 9803230018 | |
| Download: ML20216H432 (154) | |
Text
l BRAIDWOOD RIvision 1.8 i l October 1995 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING Table of Contents l SECTION M 10.1 AIR BO RNE RELE ASES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
- 1. System Description . . . . . . . . . . . . . . . . . . . . . . . . . . .... ..... .... 1
- 1. Waste Gas Holdup System . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 1 l
- 2. Ventilation Exhaust Treatment System . . . . . . . . . . . . . . . . . . ..... 1 1
- 2. Radiation Monitors . . . . . . . . . . . . . . . . ...... ................. 1
- 1. Auxiliary Building Vent Effluent Monitors . . ................ .... 1
- 2. Containment Purge Effluent Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . 2
- 3. Waste Gas Decay Tank Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
- 4. Gland Steam and Condenser Air Ejoctor Monitors . . . . . . . . . ....... 2
- 5. Radwaste Building Ventilation Mor'itor ....................... . 2
- 6. Component Cooling Water Monitor . . . . . . . . . . . . . . . . . . . . . . ..... 2
- 7. Miscellaneous Ventilation Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 1
- 3. Alarm and Trip Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
- 1. Setpoint . Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 ,
3 1. Auxiliary Building Vent Effluent Monitors . . . . . . . . . . . . . . . . . . 3 1
- 2. Containment Purge Effluent Monitors . . . . . . . . . . . . . . . . . . . . 3
- 3. Waste Gas Decay Tank Effluent Monitors . . . . . . . . . . . . . . . . 3
- 4. Component Cooling Water Monitors . . . . . . . . . . . . . . . . . . . . . 3
- 2. R e lease U m its . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
- 3. R e le as e M ixture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 4
- 4. Conv ersion Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 4
- 5. H VAC Flow R ates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 4 Allocation of Effluents from Common Release Points . . . . . . . . . . . . . . . . . 5 l 5. Dose Projections fur Batch Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 EPSPROJedembraid/1or18 10-il 9803230018 980313 PDR ADOCK 05000010 f
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l BRAIDWOOD Rivision 1.8 l October 1995 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING Table of Contents l SFCI1DN PAGE l 10.2 LIQ UI D R E LEAS ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
- 1. Syste m Description . . . . . . . . . . . . . . . . . . . . . . . .............. . 5
- 1. Release Tanks . . . . . . . . . . . . . . . . . . . ...... ..... . . ... 5 l 2. Radiation M onitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
- 1. Uguid Radwaste Effluent Monitors . . . . . . . . . . . . .. ... . ..... 6
- 2. Station Blowdown Monitor . . . . . . . . . . . . . .... .. ............ 6
- 3. Reactor Containment Fan Cooler (RCFC) and Essential Service Water l (ESSW) Outlet une Monitors . . . . . . . . . . . . . . . . . . . . . .... ..... 6 l 4. Turbine Building Fire and Oil Sump Monitor . . . . . . . . . . . . . . . . . . . . 6 l S. Condensate Polisher Sump Monitor . . . . . . . . . . . . . . . . . . . . . . . . 6
- 3. Alarm and Trip Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
- 1. Setpoint Calculation . . . . . . . . . . . . . ...................... . 6
- 1. Uquid Radwaste Effluent Monitor . . . . . . . . . .. .......... 6
- 2. Station Blowdown Monitor . . . . . . . . . . . . . . . . . . . . . . . ... 6
- 2. Discharge Flow Rates . . . . . . . . . . . . . . . . . . . . . . . . ............ 7
- 1. Release Tank Discharge Flow Rate . . . . . . . . . . . . . . . . . . . . . 7
- 3. Release Umits . . . . . . . . . . . . . ............ ............... 8 l 4. R e lease Mixture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 8 l 5. Conversion Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... ... .8 l 6. Uquid Dilution Flow Rates . . . . . . . . . . . . . . . . . . . . . . . . . . ......8
)
l 4. Allocation of Effluents from Common Release Points . . . . . . . . . . . . . ..... ...8
- 5. Projected Concentrations for Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .9 l 10.3 SOLIDIFICAT10N OF WASTE / PROCESS CONTROL PROGRAM . . . . . . . . . . . . . . . . 9 I
1 EPSPROJ4dem/ braid /10t1-4 10-lii
BRAIDWOOD Revision 1.8 October 1995 CHAPTER 10 >
LIST OF TABLES .
u 1
SECTION EAfaE l 10-1 Assumed Composition of the Braidwood Station Noble Gas Effluent 10-10 l 10-2 Assumed Composition of the Braidwod Station Uguid Effluent 10-11 l l
l EPSPROAdem4xmid/10rt-4 10-iv I
l BRAIDWOOD R: vision 1.8 l October 1995 CHAPTER 10 LIST OF FIGURES SECTION PAGE l 10-1 Simplified HVAC and Gaseous Effluent Flow Diagram 10-12 l 10-2 Simplified Uguid Radwaste Processing Diagram 10-14 l
l 10 3 Simplified Liquid Effbent Flow Diagram 10-15 f
1 l 10 4 Simplified Solid Radwaste Processing Diagram 10-16 l I
EPSPROhoden*mid/10ri-8 10-v
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l BRAIDWOOD R; vision 1.8 l October 1995 CHAPTER 10 -
RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES l 10.1.1 System Description A simplified HVAC end gaseous effluent flow diagram it provided in Figure 10-1. The principal release points for potentia 8y radioactive airbome affluents are the two auxiliary building vent stacks (designated Unit 1 Vent Stack and Unit 2 Vent Stack in Figure 10-1). In the classi6 cation scheme of Section 4.1.4, each is classified as a vent release point (see Table A 1 of Appendix A).
10.1.1.1 Waste Gas Holdup System The waste gas holdup system is designed and instaNed to reduce radioactive gaseous effluents by cohecting reactor coolant system off-gases from the reactor coolant system and providing for delay or holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The system is described in Section 11.3.2 of the Byron /Braadwood UFSAR.
10.1.1.2 Ventilation Exhaust Treatment System Ventilation, exhaust treatment systems are designed and instaRed to reduce gaseous radioiodine or radioactive materialin particulate form in gaseous effluents by passing ventilation or vent exhaust gases through HEPA filters (and charcoal adsorbers when required to mitigate potentialiodine releases) prior to release to the environment.
Such a system is not considered to have any effect on noble gas effluents. The ventiWtion exhaust treatment systems are shown in Figure 10-1.
Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components. '
10.1.2 Radiation Monitors 10.1.2.1 Auxiliary Building Vent Effluent Monitors Monitors 1RE-PR028 (Unit 1) and 2RE PR028 (Unit 2) continuously monitor the final effluent from the auxiliary building vent stacks.
Both vent stack monitors feature automatic isokinetic sampling, grab sampling, and tritium samplWg.
In normal operation aR three noble gas channels (low, mid-range, high) are on line and active. On a high alarm the low and mid-range noble gas channels are closed and only the high range noble gas channal rammins activa. Tha inctna anr1 partientata ,
channels, however, continue to operate under au conditions.
No automatic isolation or control fun::tions are performed by these monitors.
Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5 1.
EPSPROJedenWtweid/10ri-4 10-1
l BRAIDWOOD RCvision 1.8 l October 1995 10.1.2.2 Containment Purge Effluent Monitors Monitors 1RE-PR001 (Unit 1) and 2RE PR001 (Unit 2) continuously monitor the effluent from the Unit 1 and Unit 2 containments, respectively. When airbome radioactivity in the containment purge effluent stream exceeds a specified level, station personnel will foNow established procedures to terminate the release by manuaNy activating the containment purge valves. AdditionaNy, the auxiliary building vent effluent monitors provide an independent, redundant means of monitoring the containment purge effluent.
No automatic isolation or control functions are performed by these monitors.
Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5 1.
Area Radiation Monitors 1(2) RE-ARO11 and 1(2) RE-AR012 monitor the containment I atmosphere. On high alarm during a containment purge, these monitors will f automaticaNy 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.
l On high alarm, the monitors automaticahy irdtte closure of the valve OGWO14 thus terminating the release. J 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 Elector Monitors Monitors 1RE PR027 and 2RE PR027 continuously monitor the condenser air ejector gas from Units 1 and 2, respectively. On high alarm 1(2)RE-PR027 initiates startup of the offgas treatment system.
Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1.
10.1.2.5 Radwaste Building Ventilation Monitor Monitor ORE PR026 continuously monitors radioactivity in the radwaste building ventilation system. No control device is initiated by this channel.
Pertinent information on this monitor is provided in Byron /Braidwood UFSAR 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) l 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.
EPSPROAdem4waaidon 4 10-2
l BRAIDWOOD RIvision 1.8 l October 1995 Pertinent informahon on this monitor is provided in Byron /Braidwood UFSAR Table 11.5 1.
10.1.2.7 Miscellaneous Ventilation Monitors Monitor ORE PR003 continuously monitors radioactivity in the vcntilation 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 Segmints 10.1.3.i Setpoint Calculations 10.1.3.1.1 Auxiliary Buildng Vent Effluent Monitors The setpoints for the low range noble gas channel are conservatively established at 5% of the maximum permashio station release rate for the high alarm and 1/2% of the maximum release rate for the alert alarm.
The setpoirr.4 tor the high range noble gas channel are conservatively established at 50% of the maximum permissble station release rate for the high alarm and 25% of the max! mum release rate for the alert alarm.
10.1.3.1.2 Containment Pwge Effluent Monitors The setpoints are established at 1.50 times the analyzed containment noble gas activity durin0 purge, plus the back0round 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 waste gas tank activity during release. -
10.1.3.1.4 Corriponent Cooing 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 conversion tactor).
10.1.3.2 Release Umits 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 Equations 10-1 and 10-2 for the total allowed release rate of vont releases, .
Q,,.
EPSPROJedembroid/1 ort B 10-3
l BRAIDWOOD RIvision 1.8 l October 1995 (1.11)Q,, [ (V, 3) s 500 mrem /yr (10-1)
Q,, [ ( (f ) (gX/Q), exp(-1 R/3600u,)
- 3 1
+ 1.11V )) < 3000 mrem /yr 3
The summations are over noble gas radionuclides i.
f, Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides.
O,, Total Allowed Release Rate, Vent Release [pCl/sec)
The total allowed release rate of al noble gas radionuclides released as vent releases.
exp ( A,R/3600U,) is set equal to 1.0 for setpoint calculations.
The remaining parameters in Equation 10-1 have the same definitions as in Equation A-8 of Appendix A. The remaining parameters in Equation 10-2 have the same definition as in Equation A-9 of Appendix A.
Equation 10-1 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 mrom/yr) due to noble gases released in gaseous affluents (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 mrom/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 101, the value of Equation 10-2 (3.09 x 10' pCi/cac) 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 pr cedurally limited to 1 x 10
pCl/sec (less than 1/3 the maximum permissible station relaase rate).
Calibration methods and surveillance frequency for the moners 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.
EPSPROJeocmbrednort-8 10-4
l BRAIDWOOD RIvision 1.8 l Oct:bar 1995 10.1.3.5 HVAC Flow Rates The plant vent stack flow rates are obtained from 1/2 PR28J. However, if the readout indicates *0" flow, the folowing minimum reted fan flow values are currently used:
Unit 1 - 6.15 x 10' cc/sec Unit 2 - 4.55 x 10' cc/sse 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building, misceuaneous ventilation systems and the gas decay tanks are comprised of contributions from both units. Consequently, abocation is made evenly between units.
10.1.5 Dose Projections for Batch Releases Dose projections are not made prior to rolsase. Doses are calculated after purging the containment or venting the waste gas decay tanks. Per procedure, representative samples are obtained and analyzed, and the doses calculated on a monthly basis to verify compliance with 10CFR50.
10.2 LIQUID RELEASES 10.2.1 System Description A simplified rquid effluent flow diagram is provided in Figure 10-3. A simpHfied liquid waste processing diagram is provided in Figure 10-2.
The liquid radwaste treatment system is designed and instaBed to reduce radioactive liquid effluents by colectag the liquids, providing for retention or holdup, and providing for treatment by domineraEzer 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 Updated Final Safety Analysis Report.
10.2.1.1 Release. Tanks There are two radwaste release tanks (0WX01T - 33,100 gallon capacity, and OWX26T - 33750 galon capacity) which receive liquid waste before discharge to the Kankakee river.
10.2.2 Radiation Monitors 10.2.2.1 Uquid Radweste Effluent Monitors Monitor ORE-PR001 is used to monitor au releases from the release tanks. On high l alarm, the monitor automaticaty initiates closure of valves 0WX 353 and 0WX 896 to .
terminate the release.
Pertinent information on the monitor anri maanniatart enntml @vica* i= providad in Byron /Braidwood UFSAR Table 11.5-2.
s EPSPROJ/odembroidnori-8 10-5
l BRAIDWOOD R: vision 1.8 l October 1995 4 10.2.2.2 Station Blowdown Monitor Monitor ORE PRO 10 continuously monitors the circulating water blowdown. No control device is initiated by this channel Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-2.
10.2.2.3 Reactor Containment Fan Cooler (RCFC) and Essential Service Water (ESSW) Outlet Line Monitors Monitors 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.
10.2.2.4 Turbine Building Fire and Oil Sump Monitor Monitor ORE-PR005 continuously monitors the fire and oil sump discharge. On high alarm the monitor automatically initiates an interlock to trip the discharge pumps, close valve 00D030, and terminate the raisose. Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-2.
10.2.2.5 Condensate Polisher Sump Monitor Monitor ORE PR041 continuously monitors the condensate polisher sump discharge.
On high alarm the monitor automatically initiates an interlock to trip the discharge pumps and terminate the release. Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-2.
10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of RETS and 10CFR20 are not exceeded in the unrestricted area.
10.2.3.1.1 Liquid Radwasta 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 F' , / (F" + F' , (10 3)
EPSPROJetiembreW1or1-8 10-6
l BRAIDWOOD Revhion 1.8 l October 1995 P Release Satpoint [pCi/mf] -
1.25 Factor to account for minor fluctuations I in count rate. !
C~ Concentration of activity in the circulating water blowdown [pCi/mf]
at the time of discharge. (" Background reading")
C' Analyzed activity in the release tank [pCl/mf]
F* Circulating Water Blowdown Rate [gpm)
FL, Maximum Reisase Tank Discharge Flow Rate [gpm)
The flow rate from the radwaste discharge tank.
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.
1 I
The results of the analysis of the waste sample determine the discharge rate of each batch as follows:
FL, = 0.5 (FL,/[ (C}/10*DWC ) ) 3 (10-4)
The summation is over radionuclides i.
0.5 Factor for conservatism FL, Maximum Permitted Discharge Flow Rate [gpm)
The maximum permitted flow rate from the radwaste discharge tank based on radiologicallimits (not chemistry limits which may be more restrictive)
FL, Circulating Water Blowdown Rate [gpm) .
c! Conrmntration of Rariinnuclirta i in [pCi/mf]
the Release Tank The concentration of radioactivity in the radwaste discharge tank based i on measurements of a sample drawn from the tank.
EPSPROJedcmbroid/10r18 10 7
BRAIDWOOD RIvisiin 1.8 October 1995 DWC, Derived Water Concentration [pCi/mf]
of Radionuclide i The concentration of radionucide i given in Appendix B. Table 2, Column 2 to 10CFR20.100120.2402.
10 Multiplier 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)
In addition to the limits identified within the RETS, an administrative action levol for tritium has been established for the Braxiwood cooling pond. This limit, based on drinking water pathways, has been estabished as a control mechanism to ensure this pathway does not become a significant contributor to public dose. Because the public has access to the Braidwood cootnD pond for fishing and/or boating an administrative limit for discharges to the cooing pond is prudent to ensure dose to the public from this path remains wel below limlis.
The controls for this pathway wil be established by limiting the quantity (Curies) discharged to the Braidwood cooling pond. Calculations were performed based on a tritium concentration of 20,000 pCi/Blor (40CFR190 public drinking water limit) and 200 pCi/ liter which is a typical environmental lower limit of detection (LLD) for tritium.
The administrative action level wiu be estabished at 4 Cl/ year which corresponds to an equilibrium cooling pond level of 200 pCilliter.
10.2.3.4 Release Mixture l For monitors ORE-PR001 and DRE PRO 10 the release mixture used for the setpoint dt 'ermination is the radionuclide mix identlSed in the grab sample isotopic analysis or th6 :.?ix in Table 10-2.
For monitors 1RE-PR001,1RE PR002,2RE-PR001, and 2RE PR002, the release mixture is the radionucildes 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 pCl/mt. The epm to pCl/mi conversion is based on the detector sensitivtty 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 (0WX01T or OWX26T) are comprised of contributions from both units. Under normal operating conditions, it EPsPROAdem4waid/10rt-4 10 3
l BRAIDWOOD R0 vision 1.8 l Octsber 1995 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 i' Equations 10-5 and 10-6.
C/ = C((F/,,,/(Fi + Fi)] (10-5)
(( C//10=0WC, } s 0.5 (10-6)
The summation is over radionuclides i.
C/ Concentration of Radionuclide iin the Unrestricted Area [pCl/mq The calculated concentration of radionuclide iin the unrestricted area as determined by Equation 10-5.
C[ Concentration of Radionuclide iin the Release Tank [pCl/mq The concon* ration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank.
DWC, Derived Water Concentration of Radionuclide 1 [pCl/mq of Radionuclide i The concentration of radionuclide i given in Appendix B. Table 2, Column 2 to 10CFR20.100120.2402.
10 Multiplier FL Maximum Release Tank Discharge a Flow Rate [gpm)
F1 Circulating Water Blowdown Rate [gpm) 0.5 Factor for conservatism 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation .;
determination by which solidification of radioactive wastes from liquid systems is ensured.
Figure 10-4 is a simplified diagram of solid radwaste processing system.
EPSPROJ4dem4 paid /10rt-8 10-9 I
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BRAIDWOOD Revision 1.8 October 1995 Table 10-1 Assumed Composition of the Braldwood Station Noble Gas Effluent Percent of isotone Total Annual Release Ar 41 00.89 Kr 85m 00.18 l Kr-85 24.90 l Kr-87 00.04 Kr-88 00.28
~
l Xe-131m 01.40 Xe-133m 00.57 l Xe-133 71.10 Xe-135 00.53 Xe-138 00.04 EPSPROAMreid/10ri-8 10-10
l BRAIDWOOD R0 vision 1.8 l October 1995
. Table 10 2 Assumed Composition of the Braidwood Station Liquid Effluent Isotope Concentration isotope Concentration (pCl/ml) (pCl/ml)-
Ru-103 8.00E - 06 Mn-54 1.00E - 05 A0110m 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 To-132 2.00E - 06 Zr-95 6.00E - 06 l130 3.00E - 07 Nb-95 1.00E - 05 l-131 3.00E - 08 Mo-99 4.00E - 06 l132 8.00E - 07 l133 1.00E - 07 l-135 4.00E - 07 Cs 134 9.00E 07 Cs-136 9.00E - 06 Cs 137 2.00E - 06 Co-144 1.00E - 06 Np-239 1.00E - 05 EPSPROJedom4 aW10r1-4 10-11
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CRAIDWOOD Revision 19 Juns 1996 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table of Contents CHAPTER IIILk PAGE 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 11-1 LIST OF TABLES NUMBER TITLE PAGE 11-1 Radiological Environmental Monitoring Program 11 .
l LIST OF FIGURES NUMBER TITLE E6GE 11-1 Fixed Air Sampling Sites and Outer Ring TLD Locations 11-10 11-2 inner Ring TLD Locations 11 ' '
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CRAIDWOOD Ravision 1.9 June 1993 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The radiological environmental monitoring program for the environs around Braidwood Station is given in Table 11-1, Figures 11-1 through 11-3 show sampling and monitonng locations.
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ERAIDWOOD Rsvision 2 Decimber 1996 CHAPTER 12.0 SPECIAL NOTE The transfer of the Radiological Emuent Technical Specifications to the ODCM by Technical Specification.
Amendment 35, dated Apnl 13,1992, was approved by the Nuclear Regulatory Commission.
g Wahunnextraun12r2f.coc 12-i l
ERAIDWOOD R; vision 2 December 1996 CHAPTER 12 ANNEXINDEX 1
Revision 2 i
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I g waboern\annextrad12r2f doc 12-ii
BRAIDWOOD Rsvision 2 DecImb r 1996 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)
TABLE OF CONTENTS PAGE 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12-1 12.1 DEFINITIONS 12-4 12.2 INSTRUMENTATION 12-8
- 1. Radioactwe Liquid Emuent Monrtonng instrumentabon 12-8
- 2. Radioactwe Gaseous Emuent Monhi g Instrumentation 12-13 12.3 LIQUID EFFLUENTS 12-20
- 1. Concentrabon 12-20
- 2. Dose 12-27
- 3. Liquid Radwaste Treatment System 12-29 12.4 GASEOUS EFFLUENTS 12-31
- 1. Dose Rate 12-31
- 2. Dose - Noble Gases 12-37
- 3. Dose -lodine-131 and 133. Tntium, and Radioactwo Matenalin Parbculate Form 12-39
- 4. Gaseous Radwaste Treatment System 12 41
- 5. Total Dose 12-43
- 6. Dose Limits for Members of the Public 12-45 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12 46
- 1. Monitonng Program 12-46
- 2. Land Use Cens'es 12 59
- 3. Intertaboratory Companson Program 12-60 12.6 REPORTING REQUIREMENTS 12-61
- 2. Annual Radioactwo Effluent Release Report 1243
- 3. Offsite Dosa Calculabon Manual (ODCM) 12-64
- 4. Major Changes to Liquid and Gaseous Radweste Treatment Systems 12-65 g Wabdomunnextrad12r2f doc 12-iii I
BRAIDWOOD R1 vision 2 December 1996 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)
LIST OF TABLES PAGF, 12.0-1 Effluent Compliance Matrix 12-2 12.0-2 REMP Compliance Matrix 12-3 12.1 1 Frequency Notations 12 7 12.2-1 Radioactive Liquid Emuent Moritoring Instrumentation 12-9 12.2-2 Radioactive Liqued Effluent Monitoring instrumentation Surveillance Requirements 12-11 12.2-3 Radioactive Gaseous Effluent Monitoring instrumentation 12-14 12.2-4 Radioactive Gaseous Effluent Monitoring instrumentation Surveillance Requirements 12-17 12.3-1 Radioactive Liqued Waste Sampling and Analysis Pmgram 12-22 12.4 1 Radicadive Gaseous Weste Sampling and Analyses Program 12 33 12.5-1 Radioiog6 cal Environmental Monitoring Prograrn 12-49 12.5 2 Reporting Levels for Radsoectivity Concentrations in Environmental Samples 12 55 s
12.5-3 Detection Capatnisties for Environmental Sample Analysis 12-56 gDWsomennererauM2r2r.coc 12-IV
BRAIDWOOD Rsvision 2 Dec;mber 1996 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS l
l Chapter 12 of the Braidwood Staten ODCM is a compliance of the vanous regulatory requirements. i surveillance and bases, commitments and/or components of the radiological effluent and environmental monitonng programs for Braidwood Station. To assist in the understanding of the relationship between effluent regulatons ODCM equations, RETS (Chapter 12 secten) and related Techncal Specificaton requirements. Table 12.0-1 is a matnx which relates these vanous components. The Radiologeal Environmentas Monitonng Program fundamental requirements are contained within this chapter with Braidwood specific infonnaton in Chapter 11 and with a supplemental matnx in Table 12.0-2.
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g WamdcrMannextrastM2r2f doc 12-1
BRAIDWOOD Revision 2 Deczmber 1996 Table 12.0-1 EFFLUENT COMPLIANCE MATRIX Regulation Dose Component Limit ODCM RETS Technical Equation Specification 10 CFR 50 1. Gamme air dose and beta air dose due A-1 12.4.2 6.8.4.e 8 Appendix 1 to airbome radioactwity in emuent A-2 plume.
- a. Whole body and skin dose due to A-6 N/A N/A airbome radioactmty in effluent A-7 plume are reported only if certain gamma and beta air dose entens ars = m
- 2. CDE for allorgans and all four age A-13 12.4.3 6.8.4 e.9 l
groups due to iodines and particulates in effluent plume. All pathways are considered
- 3. CDE for as organs and all four age A-29 12.3.2 6.8.4.e.4 groups due to radioactwity in liquid emuents.
10 CFR 20 1. TEDE, totehng all deep does equivalent A-38 12.4.6 6.8.4.e.3 components (direct, ground and plume shine) and committed effectwo does equivalents (all pathways, both arbome and hquuMome). CDE evalumbon is made for adult only using FGR 11 data bene.
40 CFR 190 1. Whole body done (DDE) due to direct A-35 12.4.5 6.8.4.e.10 (now by dose, ground and plume shine from all i reference, sources at a staton also part of 10 CFR 20) 2. Organ doses (CDE) to an adult due to all A-13 pathways.
Techmcal 3, . instantaneous" whole body (DDE), skin A-8 12.4.1 6.8.4.e.7 Specifications (SDE), and organ (CDE) dose rates to A-9 an adult due to radioactivity in airbome A-28 effluents. For the organ dose, only inhalabon is considered
,. 2. " Instantaneous" concentraton limits for A-32 12.3.1 6.8.4.e.2 liquid emuents Technical 6.9.1.7
- 1. Radiological Emuent Release Report NA 12.6.2 Specifications g Wawdamannextrad12r2f. doc 12-2
CRAIDWOOD Ravis.on 2 Decsmber 1996 Table 12.0-2 REMP COMPLIANCE MATRIX Regulation Dose Component Limit RETS Technical Specification 10 CFR 50 Implement environmental monitonng 12.5.1 6.8.4.f Appendix i program.
Section IV.B.2 Technical Land Use Census 12.5.2 6.8.4.f.2 Specifications Technical Intertauoratory Companson Program Specifications 12.5.3 6.8 4.f.3 Technical Radiological Environmental Operating Report 12.6.1 6.9.1.6 Specifications i
1 i
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g *swocrn\annextrad\12r2f doc 12 3
CRAIDWOOD Revision 2 December 1996 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12.1 DEFINITIONS 12.1.1 AglifLr! shall be that whidi presenbes remedial measures required under designated conditions.
12.1.2 Analoa Channel Ooeranional Test shall be the injection of a simulated signal into the channel as dose to the ransor as practicable to venfy OPERABILITY of alarm, interlock and/or trip funcuons. The ANALOG CHANNEL OPERATIONAL TEST shall indude adjustments, as necessary, of the alarm inledock and/or Trip Setpoints such that the Setpoints are wElin the requwed range and accuracy, 12.1.3 Channel Calibration shut he the adjustment, as necessary, of the channel such that it responds within the requesd range and accuracy to known values of input. The CHANNEL CALIBRATION shaN encompass the entire channel induding the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overiapping, or total channel steps such that the entire channel is calibrated.
12.1.4 Channel Check shall be the qualitative assessment of channel behavior during operation by observation. This determination shallinclude, where possible, comparison of the channel indication and/or status with other indications and/or status derived fmm independent instrument channels measuring the same parameter.
12.1.5 Dialtal Channel Ocoratonal Test shaN consist of exordsing the digital computer hardware using data base mamputation and injecting simulated process data to venfy OPERABILITY of alana and/or trip functions.
12.1.6 Dose EaulvalentJ-131shed be that connedion of I-131 (mimoCurialgram) wtiich alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, '
l-132,1-133,1-134, and M35 adually present. The thyroid does conversion factors used for this calculation shall be those listed in Table lit of TID-14844, " Calculation of Distance Fadors for Power and Test Reedor Sites".
12.1.7 Freauency - Table 12.1-1 provides the definitions of vanous frequencies for which surveillance's, sampling, etc. are performed unless defined otherwise The 25%
vanance shall not be applied to Operab6lity Action Statements The bases to Technical Specification 4.0.2 provide danfications to this requirement.
12.1.8 Member (s) of the Putac means any individual except when that Individual is receiving an occupeOM dose.
12.1.9 Occucational Does mesesthe done received by an individual in the course of employment in which die individuars assigned duties involve exposure to radiation and/or radioactive malertal fmm licensed and unlicensed sources of radiation, whether in the m of the licensee or other person Occupational dose does not indude dose fmm back0round radiation, as a patient fmm medical practices, from voluntary p W nc6i in mWical research programs, or as a member of the public.
l g:*seecrnemorerenm2r2r. doc 12-4
CRAIDWOOD Revision 2 December 1996 12.0 RAD;OLOGICAL EFFLUENT TECHNICAL STANDARDS (Cont) 12.1.10 Operable /Ooerability 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, electncal power, cooling or seal water, lubncehon or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
12.1.11 Operational Mode (i.e. Mode) shall correspond to any one inciusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2 of the Technical Specifications.
12.1.12 Process Control Proaram (PCP) shall contain the curTent formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Paits 20,61,71 and State regulations, burial ground requirements, and other requirements goveming the disposal of radioactive wastes.
12.1.13 Purne/Pumina shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, hurnidity, concentration or other operating condition, in sucn a manner that replacement air or gas is required to punfy the confinement.
12.1.14 Rated Thermal Power shall be a total core heat transfer rate to the reactor coolant of 3411 MWt.
12.1.15 Site Boundary shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
12.1.16 Solidification shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements 12.1.17 Source Check shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
12.1.18 Dermal Power shall be the total core heat transfer rate to the reactor coolant.
12.1.19 Unrestricted Area means an area, access to which is neither limited nor controlled by the licensee.
12.1.20 Ventilation Exhaust Treatment Syntam shall be any system designed and installed to reduce gaaeous radiciodine or radioactive matertal in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodenes 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 Atmosphenc Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
g *scocmwmemruurd2r2f.coc 12-5
CRAIDWOOD Ravision 2 December 1996 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (Cont.)
12.1.21 Venting shall be any controlled process of discharging 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 not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
12.1.22 Waste Gas Holduo System shall be any system 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 hoidup for the purpose of reducing the total radioactivity pnor to release to the environment.
12.1.23 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 irninixisted into the database.
gwoocrnannereract2r2r one 124
BRAIDWOOD RQvision 2 Dgegmber 1996 TABLE 12.1-1 FREQUENCY NOTATIONS
- i l
NOTATION FREQUENCY S - Shiftly At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D - Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W- Weekly At least once per 7 days.
M - Monthly Atleast once per 31 days.
Q - Quarterly Atleast once per 92 days.
SA - Semiannually At least once per 184 days.
A - Annually At least once per 366 days.
R - Refueling cycle At least once per 18 months (550 days).
S/U - Startup Prior to each reactor startup.
P - Prior Prior to each radioactive release.
N.A. Not applicable.
Each frequency requirement shall be performed within the specified time interval with the maximum allowable extension not to exceed 25% of the frequency interval. The 25% variance shall not be applied to Operability Action Statements. The bases to Technical Specification 4.0.2 provide clanfications to this requirement. These frequency notations do not apply to the Radiological Environmental Monitoring Program (REMP) as desenbed in Section 12.5.
g:*abdcmiar.nextreed\12r2f doc 12-7 .
3
BRAIDWOOD Rsvision 2 Dec:;mber 1996 12.2 INSTRUMENTATION 12.2.1 Rsidioachve Liquid Effluent Monitonng instrurnentation Ooer=hitihr Raouirements 12.2.1.A The radcactive liquid effluent monitonng int *Jumentation 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 /Tnp Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
Anchcatuhly Atalltimes achon
- 1. With a radcochve liquid effluent monitonng instrumentation channel Alarm / Trip Setpoint less conservative than requwed by the above specificabon, immediately suspend the releme6 of radioactive liquid effluents menitored by the affected channel, or declare the channel inoperable.
- 2. With less than the minimum number of radioactive liquid eifluent monitonng instrumentaucr: de% OPEP.3LE, take the ACTION shown in Table 12.2-1, Restore the inoperable instrumentation to j OPERABLE status within the time specified in the ACTION, or explain in the next Radioachve Effluent Release Report pursuant to Sechon 12.6 why this inoperatnilty was not corrected within the time specified Sure = ,ce P=ad-w .1 12.2.1.8 Each radioactive liquid effluent monitonng instrumentabon channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and DIGITAL and ANALOG CHANNEL OPERATIONAL TEST at the frequences shown in Table 12.2-2.
nm 12.2.1.C The radcochve liquid effluent instrumentabon is provided to monitor and control, as apphcable, the reiseses of radioechve metenals in liquid effluents during actual or potential relooses of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm /inp will occur prior 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 10 CFR Part 50.
d g:Wawscmwmertwad12r2f*c 12-8
ERAIDWOOD Revision 2 Dec2mb:r 1996 TABLE 12 2-1 BADIOACTIVE LlOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release
- a. Liquid Radwaste Emuent Line (ORE-PR001) 1 31
- b. Fire and Oil Sump (ORE-PR005) 1 34
- c. Condensate Polisher Sump Discharge (ORE-PR041) 1 34
- 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release
- a. Essential Service Water
- b. Station Blowdown Line (ORE-PR010) 1 32
- 3. Flow Rate Measurement Devices
- a. Liquid Radweste Emuent Line (Loop-WXOO1) 1 33
- b. Liquid Radweste Emuent Low Flow Line (Loop-WX630) 1 33
- c. Station Blowdown Line (Loop-CWO32) 1 33 g W.aioacm\ennextrad\12r2f doc 12-9
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CRAIDWOOD RIvision 2 Dec1mber 1996 (
l TABLE 12.2-1 (Continued)
RADI ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ACTION STATEMENTS l
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ACTION 31 - VAth theI. umber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that pnor 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 faci lity staff independently venfy the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents 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 tnat, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for principal gamma emitters and 1-131 at a lower limit of detection as specified in Tablo 12.3-1.
ACTION 33 - 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during ,
actual releases. Pump performance curves generated in place may be used to l estimate flow.
ACTION 34 - 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 analyzed for pnncipal gamma emitters and 1-131 at a lower limit of detection as specified in Table 12.3-1:
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specifle activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT l-131, or
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT l-131.
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BRAIDWOOD Rivision 2 Oec:mber 1996 '
TABLE 12 2-2 (Continued)
RADIOACl VE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE .
REQUIREMENTS TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation 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 l
- 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 tnp on loss of sample flow.
(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciabon occurs if any of the following conditions exists;
- a. Instrument indicates measured levels above the Alarm Setpoint, or
- b. Circuit failure (monitor loss of communicabons - alarm only, detector loss of counts, or monitorloss of power), or
- c. Detector check source test failure, or
- d. Detector channel out-of-service, or
- e. Monitorloss of sample flow.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the Nabonal Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that parbeipate 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 CAllBRATION, sources that have been related to the initial calibrabon shall be used.
(4) CHANNEL CHECK shall consist of venfying indicabon of flow during penods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
g woocmwnnextraunt2r2f. doc 12-12
~-
I BRAIDWOOD Raytsion 2 D;,c:mber 1996 k 12.2.2 Radianchve n== anus Emuent Monitonna Instrumard=+mn Ooerabilitv Reauirements
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12.2.2.A The radioactive gaseous effluent monitoring instrumentation channels shown in Table 12.2 3 shall be OPERABLE with their Alarm /Tnp Setpoints set to ensure that the limits of Section 12 4 are not exceeded. The Alarm /Tnp Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
Aeolienh ! !!*v: As shown in Table 12.2-3 6GhQQ
- 1. With a radioactive gaseous emuent monitoring instrumentation channel Alarm /Tnp Setpoint less 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.
- 2. With less than the minimum number of radioactive gaseous effluent monitonng 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 Radmec2ve Emuent Release Report pursuant to Sechon 12.6 why this inoperability was not corrected within the time specified.
Survaillance Raanirements 12.2.2.B Each radioactive gaseous effluent monitonng instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and DIGITAL and CHANNEL OPERATIONAL TEST at the frequences shown in Table 12.2-4.
Raame 12.2.2.C The radioactive gaseous affluent instrumentation is provgied to monitor and control, as applicable, the releases of radioactive matenals in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm /tnp will occur pnor to exceeding the limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Cntena 60, 63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitor used to show complance with the gaseous effluent release requirements of Seebon 12.4 shall be such that concentrations as low as 1x10*
uCi/cc are measurable.
giaWocrn'annewersed\12r2f doc 12-13
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BRAloWOOD Rsvision 2 December 1996 IABLE 12.2-3 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATIONS
- At all times.
ACTION 35 - Wrth 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 pnor 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 venfy 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 contiaue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. Releases may continue via this pathway for up to 7 days provided real time monitonng of radioachve affluents released via this pathway is estabbshed ACTION 38 - Not used.
- ACTION 39 - Wlth 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for principle gamma emitters at an LLD as specified in Table 12.41.
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 for up to 30 days provided samples are continuously collected with auxiliary samphng equipment as required in Table 12.4-1.
ACTION 41 - With tho number of channels OPERABLE less than required by the Minimum Channois OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, liquid grab samples are collected and analyzed for radioactivity at a lower limit of detachon as specified in Table 12.3-1.
g1kabckrn\enneutreard2r2f. doc 12-16
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BRAIDWOOD Rsvision 2 I Dscsmber 1996 i TABLE 12 2-4 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVElli ANCE REQUIREMEMIS TABLE NOTATIONS At all times.
(1) The OlGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation 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, 1
- 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-sennce, or
- e. Monitor loss of sample flow. Monitonng ORE-PR002A and 2B will not tnp on loss of sample flow. This is only applicable for functional unit 6, ORE-PR009 and RE-009.
(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 rnessured levels above the Alarm Setpoint, or
- b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitorloss of power), or
- c. Detector check source test failure, or
- d. Detector channel out-of-service, or
- e. Monitorloss of sample flow.
(3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the Nationalinstitute 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 CAllBRATION, sources that have been related to the initial calibration shall be used.
g%swdemunnextraad\12r2. doc 12-19
CRAIDWOOD Rsvision 2 Dec:mber 1996 12.3 LIQUID EFFLUENTS l
12.3.1 Concentrabon Onorabihtv Raouirements 12.3.1.A The concentrabon of radioachve material released in liquid effluents to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex Appendix F.
Figure F.1) shall be limited to 10 times the concentrabon 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" microCunelmi total activrty.
Anchcabikty' At au times 8CllDQ
- 1. With the concentrabon of radioachve matenal released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentrabon to within the above limits.
Sure-'mca Raanica.a -A 12.3.1.1.B Radioachve liquid wastes shed be sampled ansi analyzed according to the samphng and analysis program of Table 12.3-1.
12.3.1.2.B The results of the radioactr/ity analysis shed be w.W in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of reisese are mamtamed within the limits of 12.3.1.A.
Ramme 12.3.1.C This sechon is provided to ensure that the concentrabon of radioactive matenals released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the concentrabon values in Appendix B. Table 2. Column 2 to 10 CFR 20.1001 20.2402. This lirrwtabon provides addibonal assurance that the levels of radioactive materals in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Sechon ll.A doesgn My=Cr of Appendix 1.10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.1301.
This sechon applies to the release of radioachve matensis in liquid effluents from all units at the site.
9 g:*abdcmurmertrad12r2. doc 12-20
CRAIDWCOD Revision 2 Osczmtnr 1996 12.3 LIQUID EFFLUENTS (Continued)
Bases The required detection capabilities for radioactive matenals in liquid waste samples are tabulated in terms of the lower hmits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Cume LA.," Limits for Quahtative Detection and Quantitative Determination - Application to Radiochemistry," Anal _ Chem 40. 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
12-21
BRAIDWOOD Rsvision 2 December 1996 l
TABLE 12.3-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM , )
LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTMTY LOWER LIMIT OF TYPE FREQUENCY FREQUENCY ANALYSIS DETECTION (LLD)'"
(pCumi)
- 1. Batch Release P P Pnncapal Gamma 5x10
Tanks;" Each Batch Each Batch Emnters*
l-131 4 1x10 P M 4 Dissolved and Entramed 1x10 One PatcNM Gases (Gamma Emators) m P M H-3 4 1x10 Each Batch Composee0)
Gross Alpha 1x10
P Q Sr49, Sr-90 4 5x10 Each Batch Composde
Fe-55 1x10*
- 2. Continuous W Principal Gamma 5x10'#
Releases '*
% <s)
Compoone(*
l-131 1x10'
- a. Circulating Water M M 4 Oneolved and Entramed 1x10 Blowdown Grab Sample Genes (Gamma Emitters)*
- b. Weste Water 4 T
Contmuous!* C te(*
Circulating Water Discharge Gross Alpfs 4 x10
Discharge Fe-55 1x10*
6 gvamunnextraed\12r2. doc 12-22
)
i
[RAIDWOOD Revision 2 Dec:mt:cr 1996 TABLE 12 3-1 (Continued)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTIVITY LOWER LIMIT TYPE FREQUENCY FREQUENCY ANALYSIS OF DETECTION (LLD)'"(pCi/ml)
- 3. Continuous W W Pnncipal Gamma 5x10
Release
- Grab Sample Emittersm Essential Service Water Reactor Containment Fan Cooler (RCFC) Outlet Line I-131 4 1x10 H-3 4 1x10 M* Dissolved and 1x10 4
Entrained Gases (Gamma Emitters)*
- 4. Continuous None #
None Principal Gamma 5x10 Surge Tank Emitters
- Vent-Component Cooling Water Line
- 4 Dissolved and 1x10 Entrained Gases (Gamma Emitters)m 4
I-131 1x10 i
1 I
g Wabdanunnextrad\12r2. doc 12-23
BRAIDWOOD Rsvision 2 Deczmber 1996 TABLE 12 31 (Continued)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM .
TABLE NOTATIONS (1) The LLD is defined, for purposes of these sections, as the smallest concentration of radioactive matenal 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 separatons:
LLD = 4.66s, E V 2.22'x 10' Y exp (-AAt)
Where:
LLD = the lower limrt of detection (microCuries per unit mass or volume),
s, = 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 emenency (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 fracbonal radiochemical yield, when applicable, A = the radoectrve decay constant for the particular radionuclide (sec ), and at = the elapsed time between the midpoint of sample collechon and the time of counting (sec).
Typical values of E, V, Y, and at should be p ed in the calculation.
Altemahve LLD Methodology An altematve methodology for LLD determinabon follows and is similar to the above LLD equation:
(2.71 + 4.65VB) Decay LLD = ,
E q b Y t(2.22E06) gvabocmunnextraun12r2. doc 12-24
BRAIDWOOD Revision 2 D:cesmber 1996 TABLE 12 3-1 (Continued)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS Where:
B = background sum (counts)
E = counting efficiency, (counts detected / disintegration's) q = sample quantity, (mass or volume) b = abundance,(if applicable)
Y = fracbonal radiochemical yield or collection emenency, (if appleable) t = count time (minutes) 2.22E06 = number of disintegration's per minute per microcurie 2.71 + 4.65VB = k2+ (2k V 2 V B), and k = 1.645.
(k=value of the t statistic from the single-tailed t distnbution at a significance level of 0.95 and infinite degrees of freedom. This means that the LLD result represents a 95% detection probability with a 5% probability of falsely concluding that the nuclide present when it is not or that the nuclide is not present when it is.)
Decay = e"[ ART /(1-e#))[AT,/1#,)],(if applicable)
A = radioactive decay constant,(units consistent with At, RT and T.)
At = " delta t*, or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample, (units consistent with A)
RT= elapsed real time, or the duration of the sample count, (units consistent with A)
T. = sample deposition time , or the duration of analyte collection onto the sample media, (units consistent with 1)
The LLD may be determined using installed radioanalytical software, if available. In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. dunng sample collection, from sample collection to start of analysis and during counting), this altemate method will result in a more accurate determination of the LLD.
'It should be recognized that the LLD is defined as a before the fact limrt representing the capability of a measurement system and not as an after the fact limit for a particular measurement.
g WaWxk:m\annextrad\12r2. doc 12-25
BRAIDWOOD Rsvision 2 Deesmb r 1996 TABLE 12 3-1 (Continued 1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (2) A batch release is the discharge of liquid wastes of a discrete volume. Pnor to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
(3) A composite sample is one in which the quantity of liquid sampled 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.
(4) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release j (5) To be representative of the quantities and concentrabons of radioactwo materials in liquid effluents, samples shall be collected continuously whenever the effluent stream is flowing. Prior to analyses, all samples taken for the composste shall be thoroughly mixed in order for the composite sample to be representatwo of the effluent release (6) Not required unless the Essential Service Water RCFC Outlet Radiation Monitors RE-PR002 and RE-PR003 indicates measured levels greater than 1x10* pCi/mi above background at any time during the week.
(7) The principal gamma emitters for which the LLD specificanon applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for dissolved and entrained for pnncipal gamma ernstters, This list does not mean that only these nuclides are to be considered Other gamma peaks that are identflable, together with those of ^*w above ;
nuclides, shall also be analyzed and reported in the Radioactrve Ef!Iuent Release Report 1 June 1974.
(8) A continuous release is the discharge of dissolved and entrained gaseous waste form a nondiscrete liquid volume.
1 0
g1kaudcrmannextreed\12r2. doc 12-26
BRAIDWOOD Revison 2 DIctmber 1996 12.3.2 QQAR Ooerability Reauirements i
12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive matenals in liquid emuents released, from each unit, to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited:
- 1. Dunng any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mroms 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.
Aophcabdsty At all times.
AGilDQ
- 1. With the calculated dose from the release of radioactive matenals in liquid ,
effluents exceeding any of the above limits, prepare and submit to the l Commission within 30 days, pursuant to Technical Specificaton 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 I corrective actions to be taken to assure that subsequent releases will be in 1 compliance with the above limits.
Surveillance Reauirements 12.3.2.B Cumulative dose contnbutions from liquid emuents 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.
I Bases 12.3.2.C This secton is provided to implement the requirements of Sections ll.A, til.A and IV A of Appenda 1,10 CFR Part 50. The Operatzhty Requirements implement the guides set forth in Soction ll.A of Appendix 1. The ACTION statements provide the required operating Sexibility and at the same time implement the guides set forth in Secten IV.A of Appendi/ i to assure that the releases of radioactive material in liquid emuents to UNRESTRIOTED AREAS will be kept"as low as is reasonably achievable." The dose calculation a ethodology and parameters in the ODCM implement the requirements in Secton Ill.A of Appendix ! that conLin.nce with tne guides of Appendix I be shown by calculebonal procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropnate pathways is unlikely to be substantially undereshmeted The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive matenals in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109,"Calculaton of Annual Doses to Man From Routine Releases of Reactor Emuents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Emuents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977.
g Waedem\ennextreed\12r2. doc 12-27
BRAIDWOOD Rovision 2 Dec2mber 1996 12.3.2 QQan(Continued)
Bases ?
This section applies to the release of radioactive materials 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 affluent releases cannot accurately be asenbed to a specific unit. An estimate should be made of the contnbutions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not pracbcable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units shanng the Radweste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attnbuted to each unit to obtain the total releases per unit.
g *abocrMarmertrad12r2. doc 12-28 i
)
1 1
BRAIDWOOD Rsvision 2 Dactmber 1996 12.3.3 Liauid Radwaste Treatment System Ooerability Reauirements 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE and appropnate 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 mrom to any organ in a 31 day penod.
Anolicability Atalltimes.
8C11QD
- 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 Spec.acWoci 6.9.2, a Special Report that includes the following informabon
- 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. Acbon(s) taken to restore the inegrable equipment to OPERABLE status, and
- c. Summary desenption of acbon(s) taken to prevent a recurrence.
Surveillance Reauirements 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 Seebons 12.3.1.A and 12.3.2.A.
Bases 12.3.3.C The OPERABILITY of the Liquid Radweste Treatment System ensures that this system,will be available for use whenever liquid effluents require treatment pnor to release to the environment. The requirement that the appropnate portions of this system be used when speerflod provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This sechon implements the requirements of 10 CFR 50.36a, General Design Cnterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Seebon 11.0 of Appendix i to 10 CFR Part 50.
g%abdcrnunnextreed\12r2. doc 12-29 l
1 BRAlOWOOD Rsvision 2 Dscirnber 1996 12.3.3 Liauid Radwante Treatment Svatem (Continued)
Aname The specified limits goveming the use of appropnate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set '
forth in Section ll.A of Appendix 1,10 CFR Part 50, for liquid efRuents. '
This section applies to the release of radioactive matenals in liquid effluents from each unit at the site, When shared Radweste Treatment Systems are used by more than one j unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be asenbod to a specific unit. An estimate should be made of the contnbutions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not pracbcable, the treated efRuent releases may be allocated equally to each of the radioactive waste producing units shanng the Radwaste Treatment System. For determming conferir i.cs to Operability Requirements, these allocabons from shared Radweste Treatment Systems are to be added to the releases specifically attnbuted to each unit to obtain the total releases per unit.
g:Wawdanunnezered12r2. doc 12-30 l
l
1 BRAIDWOUD Rsvision 2 DecImber 1996 i
12.4 GASE"'JS EFFLUENTS 12.4.1 Dese Rate Ooerability Reauirements 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 limited to the following:
- 1. For noble gases: less than or equal to a dose rate of 500 mrems/yr to the whole body and less than or equal to a dose rate of 3000 mrems/yr to the skin, and
- 2. For lodine 131 and 133, for tntium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
Acolicability- 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).
Surveiffance Raouirements 12.4.1.1.8 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 lodine 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 within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.41. 4 Bases .
12.4.1.C This section is prov.1ed to rim
- tt at the dose at any time at and beyond the SITE BOUNDARY from gaMus effluents from all units on the site will be within the annual dose limits of 10CFR20. 3ese limits provide reasonable assurance that radioactive material discharged in gaseoes effluents will not result in the exposure of a MEMBER OF THE PUBLIC exceeding the limits specified in 10CFR20.1301.
l g tabdcm\annertrad12r2. doc f
l 12-31 '
1 I
J
BRAIDWOOD Rcvision 2 D::cimber 1996 12.4 GASEOUS EFFLUENTS (Continued) 1 Bases j 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 atmosphenc 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 gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE i BOUNDARY to less than or equal to 500 mrems/ year to the whole body or to less than or equal to 3000 mroms/ year to the skin. These release rate limits also restnct, at all times the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to 1500 mrems/ year.
This sechon applies to the release of radioachve matensis in geseous effluents from all units at the site.
The required detecten capabilities for radioachve matenals in liquid waste samples are tabulated in terms of the lower limits of detecton (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., " Limits for Qualitative Detecten and Quanbtative Determnation - Applicecon to Radiochemistry," Anal Chem. 40. 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radionnalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
I g%staan\enneinbreed\12r2. doc 12-32
1 BRAIDWOOD Ravision 2 Dec:mber 1996 TABLE 12.41 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM TYPE OF ACTIVITY LOWER LIMIT OF TYPE FREQUENCY ANALYSIS ANALYSIS (e) DETECTION FREQUENCY (LLD)'" (pCi/cc)
- 1. Waste Gas P P Pnncipal Gamma 1x10" Decay Tank Each Tank Each Tank Emitters
- 2. Containment P P Principal Gamma 1x10" Purge Each Purge (') Each Purge
- Emitters (2)
Grab Sample H-3 1x10
- 3. Auxiliary Bldg. M ' 8) M Principal Gamma 1x10" Vent Stack Grab Sample Emitters (2)
(Unrt 1 and 2)
H-3 1x10 Continuous (*) Wm I-131 1x10"*
Charcoal Sample I133 1x10"'
Continuous (') WM Principal Gamma 1 x10'"
Particulate Emitters (')
Sample Continuous (*) Q Gross Alpha 1 x10'"
Composite Particulate Sample Continuous (*) Q Sr-89, Sr-90 1x10'"
Composite Particulate Sample 4
Continuous Noble Gas Noble Gases, Gross 1x10 Monitor Beta or Gamma i
g Wabdcrmannextrad12r2. doc 12-33 l
1
CRAIDWOOD Ravision 2 Dec:mber 1996 TABLE 12.4-1 (Continued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM I TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive matenal in a sample that will yield a not 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:
LLD = ___ 4.68S.
E
- V 2.22 x 10'
- Y exp (-Aat)
Where:
LLD = the lower limit of detection (mcroCuries per unit mass or volume), I 1
s = the standard deviation of the background counting rate or of the counting rate of a l blank sample as appropriate (counts per minute), j
\
E = the counting effloency (counts per disintegration),
V = the sample size (units of mass or volume),
2.22 x 10' = the number of disintegrations per minute per microcurie, I Y = the fracbonal radiochemical yield, when applicable.
A= the radcactive decay constant for the parbcular radionuclide (sec ), and At = the elapsed time between the midpoint of sample collechon and the time of counting (sec).
Typical values of E, V, Y, and At should be used in the calculation.
Altamate I i r) P ^_ _'_-1=v An altemate methodology for LLD determination follows and is similar to the above LLD equation:
(2.71 + 4.65VB)* Decay LLD =
E q b Y t (2.22E06) g taWdcmunnerbrad12r2. doc 12-34
BRAIDWOOD Rsvision 2 D:cimber 1996
, TABLE 12.4-1 (Continued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS Where:
B = background sum (counts)
E = counting efficiency (counts detected / disintegrations) q = sample quantity, (mass or volume) b = abundance,(if applicable)
Y = fracbonal radiochemical yield or collecbon efficiency, (if applicable) t = count time (minutes) 2.22E06 = number of disintegrations per minute per microcurie (2.71 + 4.65VB) = kr + (2k 4 2 V B), and k = 1.645.
(k=value of the t statistic from the single-tailed t distnbution at a significance level of 0.95% and infinite degrees of freedom. This means that the LLD result represents a 95% detecton probability with a 5% probability of falsely concluding that the nuclide present when it is not or that the nuclide is not present when it is.)
Decay = e* [1-e"))(AT /1-e#d)], (if applicable)
A = radioactive decay constant, (units consistent with At, RT and T )
At =
- delta t*, or the elapsed time between sample collection or the midpoint of sample collecbon and the time the count is started, depending on the type of sample, (units consistent with 1)
RT = elapsed rest time, or the duration of the sample count, (units consistent with A)
T. = sample deposabon time, or the duration of analyte collection onto the sample media, (unit consistent with A)
The LLD may be determined using installed radioanalytical software, if available. In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. during
' sample collection, from sample collection to start of analysis and during counting), this attemate method will result in a more accrue determination of the LLD.
It should be recognized that the LLD is defined as a before the fact limit and not as an after the fact limit for a particular measurement.
gvadocmwnnextred12r2. doc 12-35 j 1
]
CRAIDWOOD Rsvision 2 DecImber 1996 TABLE 12.4-1 (Continued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (2) The pnncipal 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 Mn-54, Fe-59, Co-58, Co40,2n-65, Mo-99,1-131, Cs-134, Cs-137, Ce-141, and Ce-144 in oarticulate releases. This list does not mean that only these nuclides are to be considered.
Other gamma peales 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 RATED THERMAL POWER within a 1-hour period.
(4) Tritium grab sampies shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
(5) Tritium 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 a timeframe necessary to meet the applicable lower limits of detection, but not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 a timeframe necessary to meet the applicable lower limits of detection, but not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that efRuent activity has not increased more than a factor of 3, g%abdcrmannextraun12r2. doc 12-36
BRAIDWOOD Revision 2 DIcmber 1996 12.4.2 Dose - Noble an===
i Ooerability Reauirements 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 BOUNDARY (see Braidwood Station ODCM Annex. Appendix F, Figure F-1) shall be limited to the following:
- 1. Dunng any calendar quarter Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
- 2. During any calendar year Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
Acolicabilitv: At all times.
Action
- 1. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, 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 limits.
Surveillance Reauirements ,
12.4.2.B Cumulative dose contnbubons for the current calendar quarter and the current calendar ,
year for noble gases shall be determined in accordance wrth the methodology and !
parameters in the ODCM at least once per 31 days.
Bases 12.4.2.C This soebon is provided to implement the requirements of Secbons 11.B, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements implement the guides set forth in Sechon ll.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releases of radioachve materialin gaseous effluents to area at or beyond the SITE BOUNDARY will be kept "as low as is reasonable achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix i be shown by calcu ;tional 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 i
I g%abdt:m\annextraad\12r2. doc 12-37
BRAIDWOOD R3 vision 2 Dectmb:r 1996 12.4.2 Dose - Noble Gases (Continued)
Bases i The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive matenals 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 Atmosphenc Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, Revision 1," Juh 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the histoncal average atmosphenc conditions.
This secbon applies to the release of radioactive matenais in gaseous effluents from each unit at the site. When shared Radweste 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 ascnbod to a specific unit. An estimate should be made of the contnbutions from each unit based on input conditions, e.g., Sow rates and radioactivity concentrabons, or, if not pracbcable, the treated effluent releases may be allocated equally to each of the radioachve waste producing units shanng the Radweste Treatment System. For determming conformance to Operability Requirements, these allocations from shared Radweste Treatment Systems are to be added to the releases Wisily attributed to each unit to obtain the total releases per unit.
gDabdcmumextrad12r2. doc 12-38
GRAIDWOOD Revision 2 Drcsmber 1996 12.4.3 Dose - Iodine 1-131 and 133. Tntium_ and RMia=Mive M-" ial in Particulate Form Ooerahih*v Rannirements 12.4 3.A The dose to a MEMBER OF THE PUBLIC from lodine-131 and 133, tntium, and all radionuclides in particulate form with half-leves greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the following:
- 1. During any calendar quarter Less than or equal to 7.5 mrems to any organ. and
- 2. Dunng any calendar year Less than or equal to 15 mrems to any organ.
Aoplicability At all times.
Achon
- 1. With the calculated dose from the release of lodine-131 and 133, tntium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days.
pursuant to Technical Specificebon 6.9.2, a Special Report that identifies the cause(s) for exceeding the limet(s) and defines the correcbve actions that have been taken to reduce the releases and the proposed corrective acbons to be taken to assure that subsequent releases will be in compliance with the above limits.
Survaillanca Raanirements 12.4.3.B Cumulative dose contributions for the current calendar quarter and the current calendar year for lodine-131 and 133, tntium, and radionuclides in parbculate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once por 31 days.
Bases 12.4.3.C This sechon is provided to implement the requirements of Sechons ll.C Ill.A and IV.A of Appendix I,10 CFR Part 50. The Operability Requwoments are the guides set forth in Section ll.C of ]
Appendix 1. The ACTION statements provide the required operating flexibility and at the same time imniement the guides set forth in Sechon IV.A of Appendix l to assure that the releases of radioactive matenalin gaseous effluents to areas at or beyond the SITE BOUNDARY will be kept "as low as is reasonable achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix i that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC th'ough appropnate pathways is unlikely to be substantially underestimated.
12-39
BRAIDWOOD Reveion 2 December 1996 1 1
12.4.3 Dose (Continued) l Raama The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject matenals are consistent with the methodology I provided in Regulatory Guide 1.10g, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix l* Revision 1 October 1977 and Regulatory Guide 1,111," Methods for Estimating Atmosphenc 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 atmosphenc conditions. The release rate spK Teis for lodine-131 and 133, tntium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the armes at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) irtiividual inhalabon of airbome radionuclides, (2) deposition of radionuclides onto groef leafy vegetation with subsequent consumphon by man, (3) deposebon onto grassy areas where milk animals and most producing animars graze with consumphon of the milk and most by man, and (4) depossbon on the ground with subsequent exposure to man.
This secbon apphes to the release of radioecbve motonais in gaseous effluents from each unit at the site. When shared Radweste 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 contnbutions from each unit based on input conditions, ;
e.g., flow rates and radiosebvity concentrabonJ, or, if not prar*enhia, the treated effluent releases may be meineman,e equally to each of the radioachve waste producing :
units shanng the Radwnte Treatment System. For detstmining conformance to Operability Requirements, these allocations from shared Radweste Treatment Systems are to be added to the releases specifically attnbuted to sech unit to obtain the total releases per unit.
g:*awdaniantentrad12r2. doc 12-40
BRAIDWOOD Revision 2 D:cimbIr 1996 12.4 4 Gaseous Radwaste Treatment System Ooerabilitv Recuirements 12.4 4.A The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropnate portions of these systems shall be used to 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 (see Braidwood Station ODCM Annex, Appendix F Figure F-1) would exceed:
- 1. 0.2 mrad to air from gamma radiation, or l
- 2. 0.4 mrad to air from beta radiation, or
- 3. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
Aeolicabilitv: At all times.
Action
- 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 includes the following informabon:
- a. 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 e: tion (s) taken to prevent a recurrence.
Surveillance Reauirements 12.4.4.1.B Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days an accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.
12.4.4.2.B The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Section 12.41 and i 12.4.2 or 12.4.3. I Aname 12.4.4 C The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment pnor to release to the environment.
gtabdcm\annextrad\12r2 doc 12-41 l
BRAIDWOOD Rsvision 2 Drcember 1996
'12.4 4 Anamous Radwaste Treatment Svstem (Continued)
Bases The requirement that the appropriate portions of this system be used when specified provides reasonable assurance that the releases of radcactive matenals in gaseous emuents will be kept "as low as is reasonably achievable". This section implements the requirements of 10 CFR 50.36a, General Design Critenon 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix i to 10 CFR Part 50. The specified limits goveming the use of appropriate portens of the Gaseous Radwaste Treatment System were specified as a 2% fracton of the dose design l
objectives set forth in Secten ll.B and ll.C of Appendix i,10 CFR Part 50, for gaseous emuents.
This secten applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radweste Treatment Systems are used by more than one unft on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be asenbod to a specific unit. An estimate should be made of the contnbutions from each unit based on input conditions.
e.g., flow rates and radioactivity concentratons, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units shanng the Radweste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radweste Treatment Systems are to be added to the releases specifically attnbuted to each unit to obtain the total releases per untt.
t h
12-42
CRAIDWOOD Rcvision 2 0:c;mbIr 1996 12.4.5 Total Dogg Ooerability Reauirements 12.4.5.A The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, wh:ch shall be limited to less than or equal to 75 mrems.
AcDhcabstv: At all times. !
)
- 1. With the calculated doses from the release of radioactive matenals in liquid or '
gaseous effluents exceeding twice the limits of Sections 12.3.2,12.4.2, or 12.4 3, calculations should be made including direct radiation contnbutions from the units i and from outside storage tanks to determine whether the above limits of Section 12.4.5.A have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the correchve action to be taken to reduce subsequent releases to prevent recurrence of 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 an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also desenbe levels of radiation and concentration of radioactive materialinvolved, and the cause of the exposure levels or concentrations. If the eshmeted dose (s) exceeds the above limits, and if the release condition resulting in violabon of 40 CFR Part 190 has not already been corrected, the Special Report shallinclude 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 venance is granted until staff action on the request is complete.
Surveillance Reauirements 12.4.5.1.A Cumulative dose contnbutions from liquid and gaseous effluents shall be determined in accordance with Seebons 12.3.2,12.4.2, and 12.4.3, and in accordance with the methodology and parameters in the ODCM.
12.4.5.2.8 Cumulative dose contnbutions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in ACTION 1 of Sechon 12.4.5.A. ]
t g Waiodcrn\ annex \ brad 12r2. doc 12-43 I
BRAIDWOOD Revision 2 D:c mber 1996 j l
12.4.5 Total Dose (Continued)
Bases 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 h:ghly 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 1, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will desenbe a course of action that should result in the limitabon 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 commstment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the excephon that dose contnbutions 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 CFR 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 until NRC staff schon 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 Secbons 12.3.1 and 12.4.1. An individual is not consadored a MEMBER OF THE PUBLIC during any penod in which he/she is engaged in canying out any operation that is part of the nuclear fuelcycle.
g-*swocrmarmerered12r2. doc 12-44
ERAIDWOOD Revision 2 December 1996 12.4.6 Dose Limits for Members of the Pohlir-Ooerability Reouirements 12.4.6.A The licensee shall conduct operations such that the TEDE to individual MEMBERS OF THE PUBLIC does not exceed 100 mrem in a year. In addition, the dose in any unrestncted area from external sources does not exceed 2 mrem in any one hour. The Effluents Program shallimplement monitonng, sampling and analysis of radioactive liquid and gaseous effluents in accordance with 10CFR20.1302 and with the methodology and parameters in the ODCM.
Acolicabilitv: At all times.
Action
- 1. If the calculated dose from the release or exposure of radiation meets or exceeds the 100 mrom/ year limit for the MEMBER OF THE PUBLIC, prepare and submit a report the Commission in accordance with 10CFR20.2203.
- 2. If the dose in any unrestncted area from extemal sources of radiation meets or exceeds the in any one hour limit for the MEMBER OF THE PUBLIC.
prepare and submit a report to the Commission in accordance with 10CFR20.2203.
Sur "mca R=an4rMs 12.4.6.8 Calculate the TEDE to individual MEMBERS OF THE PUBLIC annually to determine compliance with the 100 mrom/ year limit in accordance with the ODCM. In addition, evaluate and/or determine if direct radiation exposures exceed 2 mrem in any hour in unrestncted areas Raama 12.4.6.C This sechon applies to direct exposure of radioactive materials as well as radioactive materials released in gaseous and liquid effluents. 10CFR20.1301 sets forth the 100 mrem / year dose limit to members of the public; 2 mrom in any one hour limit in the unrestncted area; and reiterates that the licensee is also required to meet the 40CFR190 standards. 10CFR20.1302 pnmies opbons to determine compliance to 10CFR20.1301. Compliance to the above operability requirement is based on 10CFR20,40CFR190 and Braidwood Station Technical Speancatsns.
gtabacm'.annextrad12r2. doc l
12-45
CRAIDWOOD Revision 2 Oscsmb3r 1996 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitonna Proaram Ooer=hiti+v Raanirements I
- 12. 5.1.A The Radiological Environmental Monitonng Program shall be conducted as specified in Table 12.5-1.
Aopicabihty At all times.
i AGil00
- 1. With the Radeologmal Environmental Monitonng Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiologmal Envoonmental Operabng Report required by Section 12.6.1, a description of the reasons for not conduchng the program as required and the plans for prevenhng a recurrence Deviabons are permitted from the required sampling schedule if specimens are unobtamable due to hazardous conditions, seasonal unavailability, malfunction of samphng equipment, if a person / business who pasimipates in this program goes out of busmess or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective schons shall be completed as soon as pracbcal if a person / business supplying samples goes out of busmess, a replacement supplier shall be found as soon as possible All deviabons from the sampimg schedule will be desenbod in the Annual Radiological Envoonmental Operabng Report.
- 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, prepare and submit to the Commission wikin 30 days, pursuant to Technical F S - LM 6.g.2, a Special Report that idenlass the cause(s) for exceedmg the limit (s) and defines the corrective achons to be taken to reduce radioecbve effluents so that the potential annual dose
- to a MEMBER OF THE PUBLIC is less than the esiendar year limits of Sechon 12.3.2,12.4.2, or 12.4.3. When more than one of the radionuclides in Table 12.5.2 are detected in the sampimg medium, this report shall be submitted if-conmntrabon (1) . amcentrabon (21 + . 21.0 reportmg level (1) re: 3rting level (2)
When radionudidos other than those in Table 12.5-2 are detected and are the result of plant efiluents, this report shall be submstted if the potential annual dose
- to A MEMBER "lF THE PUBLIC from all radionuchdes is equal to or greater than the calendar yesi limits of Sechon 12.3.2,12.4.2, or 12.4.3. This report is not required if the measured level of radioachvity was not the result of plant effluents; however, in such an event, the condition shall be reported and desenbod in the Annual Radiologmal Environmental Operating Report required by Sechon 12.6.1.
'The methodology and paramotors used to eshmate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
l gwennumn12r2.aoc l
1 12 46 i l
m BRAIDWOOD Rsvision 2 Oectmber 19%
12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Conbnued)
- 3. If the sample type or sampling location (s) as required by Table 12.5-1 become(s) permanently unavailable, identify suitable attemative sampling media for the pathway of interest and/or specific sampling locations for obtaining replacement samples and add them to the Radiological Environmental Monitonng Program as soon as practicable. The specific locabons from which samples were unavailable may then be deleted from the monitonng program.
Prepare and submit a controlled version 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 and justifying the selection of new location (s) for obtaining samples.
Surveillance Reauirements 12.5.1.B The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5-1 from the 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.
Bases 12.5.1.C The Radiological Environmental Monitonng Program required by this section provides ;
representative measurements of radiation and of radioactive matenals 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 operabon. This monitoring program implementsSection IV.B.2 of Appendix ! to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by venfying 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 monitonng program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitonng. The initially specified monitoring program will be effective for at least the first 3 years of mmmercial operation. Following this penod, program changes may be initiated based on operabonal experience.
The required detection capab6bes for environmental sample analyses are tabulated in terms of the lower limits of detecbon (LLDs). The LLDs required by Table 12.5-3 are considered optimum for soubne environrnental measurements in industnal 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 J for a particular measurement j l
Detailed discussion of the LLD, and other detection limrts, can be found in HASL I Procedures Manual, HASL-300 (revised annually), Currie, LA., " Limits for Qualitative Detection and Quantitative Determination . Application to Radiochemistry," Anal.
)
Chem. 40. 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical ,
Counbng Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
g \kaiodern\annextrad12r2 doc 12-47 l
l
[RAIDWOOD Rsvision 2 Dec mber 1996 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)
Intersi.:_: bas '
12.5.1.0 Table 12.5-1 requires "one sample of each community dnnking water supply downstream of the plant within 10 kilometers." Drinking water supply is defined as water taken from nyers, lakes, or reservoirs (not well water) which is used for drinking.
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t.hML'Au %* 6 M6Vis100 2 ~ l Dscsmear 1996 TABLE 12.5-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional desenption where pertinent, shall be provided for each and every sample location in Table 12.5-1 of the ODCM Station Annexes. 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.
l (2) Far field samples are analyzed when the respective near Sold sample results are inconsistent with previous measurements and radioactivity is confirmed as having its ongin in airbome effluents from the shtion, or at the discretion of the Radiation Protection l
Director.
(3) Airbome parDeulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 mean of control samples, gamma isotopic analysis shat be performed on the individual samples.
(4) Gamma isotopic analysis means the identification and quantification of gamma emitting i radionuclides that may be attributable to the effluents from the station.
(5) One or more instruments, such as a pressurtzed ion chamber, for rneasuring and recording dose rate continuously may be used in place of, or in addition to, integrating i dosimeters Film badges shall not be used as dosimeters for measuring direct radiation.
The 40 locations is not an choolute number. The pumber of direct radiation monitonng l
stations may be reduced according to geographidal limitations; e.g., if a station is adjacent to a lake, some sectors may be over water thereby reducing the number of dosimeters which could be placed at the ir:dicated distances The frequency of analysis or readout for TLD systems will depend upon the charactenstics of the specif6c system used and should be enlarted to obtain opbmum dose informabon with minimal fading.
(6) Groundwater samples shall be taken when this source is tapped for drinking or irngation purposes in areas where the hydraulic gradient or recharge properties are suitable for contaminabon.
(7) The " downstream" sample shall be taken in an area beyond but near the mixing zone. l The "upstroom sample" shall be taken at a distance beyond significant influence of the I discharge. Upstream samples in an estuary must be taken far enough upstream to be beyond the stabon influence (8) If milking animals are not found in the designated indicator locations, or if the owners l decline to participate in the REMP, all milk sampling may be discontinued.
(9) BMeeldy refers to every two weeks.
(10) . l.131 analysis means the analytical separabon and counting procedure are specific for this radionuclide.
(11) One sample shall consist of a volume /weeght of sample large enough to fill contractor specified container g%abacrmannextrad\12,2f doc g
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ORAIDWOOD Rsvision 2 Deczmber 1996 TABLE 12.5-3 (Continued)
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) The nuclides on this list are not the only nuclides intended to be concidered. Other peaks that are identifiable.
together with those of the above nuchdes, shall also be analyzed and reported in the Annual Radiological Environmental Operatng Report.
(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.
(3) The 1.ower Limit of Detection (LLD)is defined, for purposes of these specifications, as the smallest concen. ration of radioactive matenalin 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, the LLD is defined as follows:
4.66 S. + 3/t.
LLD =
(E)(V) (2.22)(Y)(exp (-ut))
4.66 S. l LLD -
(E) (V)(2.22)(Y)(exp (-ut)) i Where: 4.66 S n 3/t.
LLD = the "a prion" Minimum Detectable Concentration (picoCuries per unit mass or volume),
- s. = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts per minute),
, JTotal Counts
!s E = the counting efficiency (counts per disintegrabon),
V = the sample size (units of mass or volume),
2.22 = the number of disintegrations per minute per picoCune, Y = th'sfractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec"),
g Yxaedem\ennextrad\12r2f doc 12-57
BRAIDWOOD Revision 2 Deczmber 1996 TABLE 12.5-3 (Continued)
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS ,
t, = counting time of the background or blank (minutes), and At = the elapsed time between sample collection, or end of the sample collection penod, 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.
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 contnbuting factors shall be identified and desenbod in the Annual Radiological Environmental Operating Report.
(4)lf no drinking water pathway exists, the value of 15 pCill may be used.
(5) A value of 0.5 pCill shall be used when the animais are on pasture (May through October) and a value of 5 pCill shall be used at all other times (November through Apn!).
(6) This LLD applies only when the analytical separabon and counting procedure are specific for this radionuclide.
1 g%swdcrn\ennextraun12r2f doc 12-58
BRAIDWOOD Rsvision 2
\
Dic:mber 1996 12.5.2 Land Use Censul Ooerability Recuirements 1
12.5.2.A. A Land Use Census shall be conducted and shall identify within a distance of 10 km (6 2 miles) the location in each of the 16 meteorological sectors
- of the nearest milk animal, the nearest residence **, and an enumeration of livestock. For dose calculation, a garden will be assumed at the nearest residence. (
Aeolicability: At all times.
Action
- 1. 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 Monitonng Program given in Chapter 11. The sampling location (s), excluding the controllocation, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitonng program after October 31 of the year in which this Land Use Census was l conducted. 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 supportir,g the change in sampling locations.
- This requirement may be reduced according to geographical limitations; e.g. at a lake site where some sector's will be over water.
"The nearest industrial facility shall also be documented if closer than the nearest residence.
Surveillance Recuirements 12.5.2.8 The Land Use Census shall be conducted during the growing season, between June 1 and October 1, at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, senal survey, or by consulting local agriculture authonties. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.
Bases i
12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE I BOUNDARY are identified and that modifications to the Radiological Environmental Monitonng '
Program given in the ODCM are made if required by the results of this census. l, This census satisfies the requirements of Section IV.B.3 of Appendix i to 10 CFR Part 50. An annual garden census will not be required since the licensee will assume that there is a garden at j the nearest residence in each sector for dose calculations. :
I l
1 gta\odern\annexibraid\12r2f doc 12-59 i
a
CRAIDWOOD Rsvision 2 Decimber 1996 12.5.3 Interimboratorv Comnarison Proaram Ooerability Requirements 12.5 3.A Analyses shall be performed on radioactive matenals supplied as part of an intertaboratory Comparison Program that correspond to samples required by Table 12.5-1.
Anolicability 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.
Surveillance Raanicaments 12.5.3.B A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operabng Report.
Ramme
)
12.5.3.C The requirement for p d Ai in an interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioachve matenalin 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 Sechon IV.B.2 of Appendix 1 to 10 CFR Part 50.
l l
g%sedcmwmextrad12r2f. doc 12-60 i
BRAIDWOOD Rsvision 2 Dec;mber 1996 12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radioloaical Environmental Ooeratino Reoort*
Routine Annual Radiological Environmental Operating Report covenng the operation of the Unit (s) dunng the previous calendar year shall be submitted prior to May 1 of each year.
The Annual Radiological Environmental Operating Report shall include summanes, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a companson with preoperational studies, with operational controls as appropnate, and with previous environmental l surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken dunng the penod pursuant to the locations specified in the tables and figures in Chapter 11 of the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format 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. The missing data shall be submitted as soon as possible in a supplementary report.
The reports shali also include the following: a summary desenption of the Radiological Environmental Monitoring Program; legible maps covenng all sampling locations keyed to a table giving distances and directions from 'he midpoint between the two units; reasons for not conducting the Radiological Environrr. ental Monitonng Program as required by Section 12.5.1, a Table of Missed Samples and a Table of Sample Anomalies for all ,
deviations from the sampling schedule of Tabh 11,1-1; discussion of environmental 4 sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents, discussion of all analysss in which the LLD required by Table 12.5-3 was not achievable; result of the Land Use Census required by Section 12.5.2; and the results of the licensee participation in an Interlaboratory Cortpanson Program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3.
- A single submittal may be made for a multiple unit station.
g%odem\annextradi12r2f doc 12-61 l
BRAIDWOOD Rsvision 2 December 1996 12.6 REPORTING REQUIREMENTS (Cont'd) 12.6.1 Annual Radioloaical Environmental Ooeratina Reoort (Cont'd)
The Annual Radiological Environmental Operating Report shall also include an annual summary of hourty meteorological data collected over the applicable year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmosphenc stability, and precipitation (if measured), or in the form of joint frequency distnbutions of wina speed, wind direction, and atmosphenc stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
The Annual Radiological Environmental Operating Report shall also 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 report shall also include an assessment of the radiation doses to the most likely exposed MEMBER OF THE PUBUC from reactor releases and other near-by uranium fuel cycle sources including doses from primary effluent pathways and direct radiation, for the previous i I
calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM, and in compliance with 10CFR20 and 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power i Operation."
)
l l
l g'*sbacmWnnextrad12r2f doc 1242 x
BRAIDWOOD Revision 2 December 1996 12.6 REPORTING REQUIREMENTS (Continued) 12.6.2 Annual Radioactive Effluent Relamaa Reoort" Routine Annual Radioactive Effluent Release Reports covenng the operation of the unit dunng the previous calendar year operation shall be submitted pnor to May 1 of the following year, The Annual Radioactive Effluent Release Reports shallinclude 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 Matenals in Liquid and Gaseous Emuents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summanzed on a quarterly basis following the format of Apoendix B thereof.
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 ager t or absorbent (e g., cement, urea formaldehyde).
The Annual Radioactive Emuent Release Reports shall include a list and description of i
unplanned releases from the site to areas beyond the site boundary of radioactive matenals in gaseous and liquid effluents made during the reporting penod The Annual Radioachve Effluent Release Reports shall include any changes made during the reporting penod to the PCP, as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Sechon 12.6.3.
The Annual Radioactive Effluent Release Reports shall also include the following: an i explanation as to why the inoperability of liquid or gaseous emuent monitonng instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and desenption of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specifk;ation 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 secbons that are common to all units at the station; however, for units with separate radwaste systems, the submrttal shall specify the releases of radioactive matenal from each unit.
g%sbdaMannextrad12r2f doc 12-63
BRAIDWOOD Rsvision 2 Dec mber 1996 12.6 REPORTING REQUIREMENTS (Continued) 12.6.3 Offsite Dose C*nbtion Manual (ODCM) i 12.6 3.1 The ODCM shall be approved by the Commission prior to initial implementation.
12.6.3.2 Licensee-initiated changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2. This documentation shall contain:
- 1. Sufficient information to support the change together with the appropnate analyses or evaluatN>ns 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 1 to 10 CFR Part 50 and not adversaly impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acesptance by the Onsite Review and Investigative Funcbon aM the approval of the Plant Manager on the date specified by the Onsite Review and Investigabve Funcbon
- c. Shall be submitted to the Commission in the form of a complete legible copy of the entire ODCM or updated pages if the Comtr tssion retains a controlled copy.
If an entire copy of the ODCM is sulmtted, it shall be submitted as part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identitled 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.
g:*a\ocermannextraad\12r2f doc 12-64
BRAIDWOOD Rsvision 2 Dec;mber 1996 12.6 REPORTING REQUIREMENTS (Continued) 12.6.4 Maior Chanaes to Liouid and Gaseous Radwaste Treatment Systems
- Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):
- a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the penod in which the evaluation was reviewed by the Onsite Review and Investigative Function. The discussion of each change shall contain:
- 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 supplementalinformation;
- 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 matenals in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License app lication and amendments thereto;
- 5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC and to the general population that 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 penod pnor 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 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 the information called for in this section as part of the annual FSAR update.
g uwoernunnexersidu2r2r doc 12-65
BRAIDWOOD Revision 2 December 1996 APPENDIX F BRAIDWOOD ANNEXINDEX REVISION 2 k'Wimtwfr2. doc p
Revision 2 BRAIDWOOD Drc:mber 1996 APPENDlX F STATION-SPECIFIC DATA FOR BRAIDWOOD UNITS 1 AND 2 TABLE OF CONTENTS PAGE F.1 INTRODUCTION F-1 F.2 REFERENCES F-1 l
k:Wemtwfr2. doc p,
BRAIDWOOD Revision 2 December 1996 APPENDIX F LIST OF TABLES NUMBER TITLE PAGE F-1 Aquatic Environmental Dose Parameters F-2 F-2 Station Charactenstics F-3 F-3 Critical Ranges F-4 F-4 Average Wind Speeds F-5 F-5 X/O and D/O Maxima At or Beyond the Unrestncted Area Boundary F-6 F Sa X/Q and DIO Maxima At or Beyond the Restncted Area Boundary F-7 F-6 D/O at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 F7 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 i Based on 1 cm Depth at the Restncted Area Boundary for Selected Nuclides F-24 Supplemental Tables A Mixed Mode Joint Frequency Distnbution Table Summanes - 203 and 34 Foot Elevation Data F 39
-Summary 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 Distnbution 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 .
l k:Wimtwtr2. doc F-iii
BRAIDWOOD Revision 2 Deesmber 1996 APPENDlX F i LIST OF FIGURES NUMBER TITLE PAGE F-1 Unrestncted Area Boundary F 45 F-2 Restncted Area Bouncary F-46 1
i k:Wimewfr2. doc F-iv
j l BRAIDWOOD Revision 2 l
December 1996
! APPENDIX F
! STATION-SPECIFIC DATA FOR BRAIDWOOD UNITS 1 AND 2 l
F.1 INTRODUCTION l
This appenaix contains data relevant to the Braidwood site. Included is a figure showing the unrestncted l
area bouncary and values of parameters used in offsite dose assessment.
l F.2 REFERENCES
- 1. Sargent & Lundy, Nuclear Analysis and Technology Division Braidwood Calculation No.
ATD-0149. Revisions 0,1,2, and 3,3/30/95 for Braidwood.
l l
- 2. " Assessment of the impact of Liquid Radioactive Effluents from Braidwood Station on Proposed l
Public Water intakes at Wilmington, Illinois", J.C. Golden NSEP, January 1990.
l l 3. "Venfication of Environmental Parameters Used for Commonwealth Edison Company's Offsite i Dose Calculations," NUS Corporation,1988.
l
- 4. "Venfication of Environmental Parameters Used for Commonwealth Edison Company's Offsite Dose Calculations," NUTECH Engineers Group,1992.
I l
l l
l k:Wimtwtr2. doc
BRAIDWOOD RevisiIn 2 December 1996 Table F-1 ,
Aquatic Environment Dose Parameters (
General information There is no irrigation ocumng 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 station. One is located on the Kankakee. The other is the lilinois 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 Fish Incestion Parameters Parameter
- Mahlt U*, water usage, Uhr 0.042 U', fish consumption, kg/hr 2.4E-3 1/M",1/M' O.25,1.0 I
F",cfs 3950 F', cfs 3950 ,
(, hr* 24.0 t", hr* 3.0 Limits on Radioactivity in Unsie=N Outdoor Tanks' Outside Temporary Tank 5, 10 Ci' (per Technical Specification 3.11.1.4)
- The parameters are defined in Section A.2.1 of Appendix A.
- f (hr) = 24 hr (all stations) for the fish ingestion pathway
- t* (br) = 3 hr (distance nearest potable water intake, to Wilmington, is 4 river miles downstream; a flow rate of 1.4 mph is assumed) l 8
See Section A.2.4 of Appendix A.
- Tritium and dissolved or entrained noble gases are excluded from this limit.
k:*wmbwfr2. doc F-2
BRAIDWOOD Revision 2 December 1996 Tabis F-2 Station Charactenstics STATION: Braidwood LOCATION: Braceville, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT: Not Applicable (NA)
- 1) Release Height = m 2) Diameter = m
- 3) Exit Speed = ms" 4) Heat Content Kcal s" CHARACTERISTICS OF VENT STACK RELEASE POINT
- 1) Release Height = 60.66 m' 2) Diameter = 2.80 m
- 3) Exit Speed = 11.0 ms"*
CHARACTERISTICS OF GROUND LEVEL RELEASE
- 1) Release Height = 0 m
- 2) Building Factor (D)= 60.6 m' METEOROLOGICAL DATA A_32D_ft Tower is Located JiZ3_mEE.of vent stack release point Tower Data Used in Calculations Wind Speed Differential Release Point and Direction Temperature Elevated (NA) (NA)
Vent 203 ft 199-30 ft Ground 34 ft 199-30 ft I Used in calculating the meteorological and dose factors in Tables F-5, F-6, and F-7. See Sections B.3 through B.6 of Appendix B.
k:Wwntwfr2. doc
BRAIDWOOD Revision 2 December 1996 Table F-3 Critical Ranges Unrestricted Area Restncted Area Nearest Dairy Farm Boundary' Boundary Nearest Resident" within 5 Miles' Direction (m) (m) Im) Im)
N 610 305 800 None NNE 914 265 2800 None NE 792 299 1100 None ENE 701 361 1200 None E 1036 355 1200 None ESE 2713 425 3500 None SE 3414 448 4300 None SSE 3444 540 5300 None S 4633 530 6700 None SSW 975 540 2000 None SW 632 632 600 None WSW 555 555 800 None W 518 500 600 None WNW 503 434 600 None NW 495 428 600 None NNW 510 442 600 None See Updated Final Safety Analysis Report Table 2.1-1a 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.
- 1996 annual survey by Teledyne isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters.
- 1996 annual milch animal census, by Teledyne isotopes Midwest Laboratories. Used in calculating the D/O values in Table F-6. The distances are rounded to the nearest conservative 100 meters.
k:Wimewtr2. doc
BRAIDWOOD Revision 2 Decimber 1996 Table F-4 Average Wind Speeds Average Wind Speed (m/sec)*
Downwind Direction Elevated
- Mixed Mode Ground Level" N 7.6 6.0 4.7 NNE 7.5 5.8 4.4 NE 6.1 5.3 3.9 ENE 6.2 5.2 3.7 E G.c 5.4 4.0 ESE 6.8 5.6 4.3 SE 6.2 5.3 3.9 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 WSW 4.7 4.2 2.4 W 5.4 4.4 2.2 WNW 6.0 4.6 2.4 NW 6.0 4.8 3.1 1 NNW 6.8 5.4 3.9 i
i
- Based on Braidwood site meteorological data, January 1978 through December 1987. Calculated in Reference 1 of Section F.2, using formulas in Section B.1.3 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.
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