Text

Rev 1.8 to Odcm
	ML20095A907
Person / Time
Site:	Braidwood
Issue date:	10/31/1995
From:	; COMMONWEALTH EDISON CO.
To:	;
References
	PROC-951031-01, PROC-951031-1, NUDOCS 9512080066
	Download: ML20095A907 (140)
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Octobtr 31,1995 i

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Attached are the recent revisions to the Comed Offsite Dose Calculation Manual ODCM)

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BRAIDWOOD Revhion 1.8 October 1995

i CHAPTER 10 j

Q Braldwood Annex Index i

i EAGE REVISION 10-1 1.8

1 0 -11 1.8

10-lii 1.8 j 10-IV 1.8 1 10-v 1.8 10-1 1.8 10-2 1.8 l 10-3 1.8 I

10-4 1.8 l 10-5 1.8 i 10-6 1.8

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l Oct:ber 1995 CHAPTER 10 Q

b RADIOACTIVE EFFLUENT TREATMENT AND MONITORING Table of Contents l SECTION f.AfaE 10.1 AIRBOR NE RELE ASES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

1. Syste m D escriptio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

1. Waste Gas Holdup System . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 1

2. Ventilation Exhaust Tceatment System . . . . . . . . . . . . . ...... .. 1

2. Radiation M onitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

1. Auxiliary Bulkfing Vent Effluent Monitors . . . . . . . .............. . 1

2. Containment Purge Effluent Monitors . . . . . . . . . . . . . ............ 2

3. Waste Gas Decay Tank Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

4. Gland Steam and Condenser A'r Ejector Monitors . . . . . . . . . . . . . . . . . 2

5. Radwaste Building Ventilation Monitor ...... ................. 2

6. Component Cooling Water Monitor . . . . . . . . . . . . . . . . . . . . . . . . . .. 2

7. Miscellaneous Ventilation Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 ;

3. Alarm and Trip Setpoints . . . . . . . . . . . . . . . . . . . . . . . .. .......... 3

1. Setpoint . Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3

1. Auxiliary Building Vent Effluent Monitors . . . . . . . . . . . . . . . . . . 3 g

2. Containment Purge Effluent Monitors . . . . . . . . . .........3

3. Waste Gas Decay Tank Effluent Monitors . . . . . .......... 3

4. Component Cooling Water Monitors ....... . ... .. 3

2. Rekase Umns . . . . . . . . . . . . ................... . . . . 3

3. Release Mixture . . ..... . ........ . ............ 4 l 4. Conversion Factors . . . . . . . . . . . . . . . . . . ... . ........ .. 4

5. HVAC Flow Rates . . . . . . . . . . . .......... ......... ... 4 4 Allocation of Effluents from Common Release Points . . . .............. 5 l S. Dose Projections for Batch Releases . . . . . . . ................. .. 5 l

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l BRAIDWOOD R;vbion 1.8 l October 1995 r CHAPTER 10 d

i RADIOACTIVE EFFLIJENT TREATMENT AND MOidiTORING Table of Contents i

l SECTION g l l 10.2 LIQUI D RE LE ASES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

1. Syste m Descriptio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

1. Re kase Tan ks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 l 2. Radiation M onitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

1. Uquid Radwaste Effluent Monitors . . . . . . . . . . . . . . . . . . . ....... 6

2. Station Blowdown Monitor . . . . . . . . . . . . . . . . . . ... ........... 6

3. Reactor Containment Fan Cooler (RCFC) and Essential Service Water '

(ESSW) Outlet une Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 i 4. Turbine Building Fire and Oil Sump Monitor . . . . . . . . . . . . . . . . . . . . . 6

5. Condensate Polisher Sump Monitor . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 I 3. Alarm and Trip Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6

1. Setpoint Calculatio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6

1. Liquid Radwaste Effluent Monitor . . . . . . . . . . . . . . . . . . .... 6

2. Station Blowdown Monitor . . . . . . ......... ...... .... 6 1

i 2. Discharge Flow Rates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...... 7

1. Release Tank Discharge Flow Rate . . . . . . . . . . . . . . . . . . . . 7

3. Release Umits . . . . . . . . . . . . . . . . . . . . . ................... 8

4. Release Mixture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... 8

5. Conversion Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

) 6. Uguid Dilution Flow Rates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 l 4. Allocation of Effluents from Common Release Points ...................... 8 i

5. Projected Concentrations for Releases . . . . . . . . . ........... .... ... .. 9 ,

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l 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . . . . . . . . . . . . . . . . . 9 [

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OctSber 1995 CHAPTER 10 q LIST OF TABLES SECTION g l 10 1 Assumed Composition of the Braidwood Station Noble Gas Effluent 10-10 l 10 2 Assumed Composition of the Braidwod Station Liquid Effluent 10-11 i

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G CHAPTER 10 i LIST OF FIGURES l SECTION EAGE l 10 1 SimpWied HVAC and Gaseous Effluent Flow Diagram 10-12 4 I l 10-2 SimpWied Liquid Radwaste Processing Diagram 10 14 l 10-3 SimpWied Liquid Effluent Flow Diagram 10 15 l l 10-4 SimpWied Solid Radwaste Processing Diagram 10 16 4

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l October 1995 CHAPTER 10 Q

RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified HVAC and gaseous effluent flow diagram is provided in Figure 101. The principal release points for potentially radioactive airbome effluents are the two auxiliary building vent stacks (designated Unit 1 Vent Stack and Unit 2 Vent Stack in Figure 10-1). In the classification scheme of Section 4.1.4, each is classified as a vent release point (see Table A 1 of Appendix A).

10.1.1.1 Waste Gas Holdup System The waste gas holdup system is designed and instaBed to reduce radioactive gaseous effluents by collecting reactor coolant system off-gases from the reactor coolant system and providing for delay or hoidup to reduce the total radioactivity by radiodecay prior to release to the environment. The system is described in Section 11.3.2 of the Byron /Braidwood UFSAR.

10.1.1.2 Ventilation Exhaust Treatment System Ventilation, exhaust treatment systems are designed and installed to reduce gaseous radiciodine or radioactive materialin particulate form in gaseous affluents 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 ventilation exhaust treatment systems are shown in Figure 10-1.

Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.

10.1.2 Radiation Monitors l l

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 sampling. 1 In normal operation all three noble gas channels (low, mid-range, high) are on line 1 and active. On a high alarm the low and mid-range noble gas channels are closed and only the high range noble gas channal remains activa. The inriina anti partirmtata channels, however, continue to operate under all conditions.

No automatic isolation or control functions are performed by these monitors. g Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table T 11.5-1.

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. BRAIDWOOD Revision 1.8 l October 1995 ,

10.1.2.2 Containment Purge Eftluent Monitors

! Monitors 1RE PR001 (Unit 1) and 2RE PR001 (Unit 2) continuously monitor the ,

1 effluent from the Unit 1 and Unit 2 containments, respectively. When airborne -

, radioactivity in the containment purge effluent stream exceeds a specified level, station personnel will fobow established procedures to terminate the release by ,

i manuaNy activating the containment purge valves. AdditionaNy, the auxiliary building ;

vent effluent monitors provide an independent, redundant means of monitorin0 the j containment purge effluent. l

i i No automatic isolation or control functions are performed by these monitors. !

Pertinent information on thess monitors is provided in Byron /Braidwood UFSAR Table

, 11.5-1.

Area Radiation Monitors 1(2) RE AR011 and 1(2) RE-AR012 monitor the containment -

atmosphere. On high alarm during a containment purge, these monitors will 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 automaticaly initiate closure of the valve OGW014 thus terminating the release.

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Pertinent information on these monitors and associated control devices is provided in i Byron /Braidwood UFSAR Table 11.5-1.

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10.1.2.4 Gland Steam and Condenser Air Ejector Monitors i l

I Monitors 1RE PR027 and 2RE-PR027 continuously monitor the condenser air ejector j gas from Units 1 and 2, respectively. On high alarm 1(2)RE PR027 initiates startup of l j the offgas treatment system.

Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table l

, 11.5 1. -l i

! 10.1.2.5 Radwaste Building Ventilation Monitor 1 I

Monitor' ORE PR026 continuously monitors radioactivity in the radweste 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.

i 10.1.2.6 Component Coohng 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 j

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-4 PR009 initiates closure of the Unit 2 CCWST vent.

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Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5 1.

10.1.2.7 Miscellaneous Veritilation Monitors Monitor ORE PR003 continuously monitors radioactivity in the ventilation exhaust from the laboratory fume hoods. No control device is initiated by this channel.

Pertinent information on this monitor and associated devices is provided in Byron /Braidwood UFSAR Table 11.5-1.

10.1.3 Alarm and Trip Setpoints 10.1.3.i Setpoint Calculations 10.1.3.1.1 Auxiliary Building Vent Effluent Monitors The setpoints for the low range noble gas channel are conservatively established at 5% of the maximum permissible station release rate for the high alarm and 1/2% of the maximum release rate for the alert alarm.

The setpoints for the high range noble gas channel are conservatively established at 50% of the maximum permissite station release rate for the high alarm and 25% of the maxtraum release rate for the alert alarm.

10.1.3.i.2 Containment Purge Effluent Monitors The setpoints are established at 1.50 times the analyzed containment noble gas O

activity during purge, plus the background reading of the monitor prior to purge.

l 10.1.3.1.3 Waste Gas Decay Tank Effluent Monitors l

The setpoints are established at 1.50 times the analyzed waste gas tank activity during release.

10.1.3.1.4 Component Cooling Water Monitors The setpoint is based on the radionuclide mix in Table 10-1. The total calculated detector response is divided by 2 to obtain the final setpoint. (See section 10.2.3.5 for the conversion factor).

l 10.1.3.2 Release Umits Alarm and trip setpoints of gaseous effluent rr.c.,ers 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 vent releases, O,,.

O EPSPROJedembroidnor1-8 10-3

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! O-(1.11)Q,, [(KI,) s 500 mrem /yr (10 1) i Q,, [ { (f ) [K1X/Q), exp(-1 R/3600u,)*

3 3 002)

+ 1.11v,] ) < 3000 mrem /yr j i l

{ The summations are over noble gas radionuclides 1. i

!, f, Fractional Radionuchde Composition The release rate of noble gas radionuclide i divided by the total release rate i j of aR noble gas radionuclides.

J O, Total Allowed Release Rate, Vent Release [pCi/ soc] !

! The total showed release rate of au noble gas radionuclides released as vent j releases.

{ exp (-A,R/36000,) is set equal to 1.0 for setpoint calculations. -

t i The remaining parameters in Equation 10-1 have the same definitions as in Equation l - 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 !

l- effluents (see Section A.1.3.1 of Appendix A). Equation 10-2 is based on Equation A- i 3 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 l- 10-1, the value of Equation 10-2 (3.09 x 10' pCl/sec) is used as the limiting noble gas release rate. During evolutions involving releases from the containment or waste gas

] decay tanks, the release rate from each release path is proceduraNy limited to 1 x 10

] pCl/sec (less than 1/3 the maximum permissible station release rate).

2 CaNbration methods and surveillance frequency for the monitors will be conducted as

, specified in the RETS.

j 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 i sensitivity to Xe 133 for conservatism.

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BRAIDWOOD Revrion 1.8

October 1995 10.1.3.5 HVAC Flow Rates g The plant vent stack flow rates are obtained from 1/2 PR28J. However, if the readout indicates "0" flow, the following minimum rated fan flow values are currently used:

Unit 1 - 6.15 x 10' cc/sec Unit 2 - 4.55 x 10' cc/see 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building, misceHaneous ventilation systems and the gas decay tanks are comprised of contributions from both units. Consequently, allocation is made evenly between units.

10.1.5 Dose Projections for Batch Releases Dose projections are not made prior to release. Doses are calculated after purging the containment or venting the waste gas decay tanks. Per procedure, representative samples are obtained and analyzed, and the doses calculated on a monthly basis to verify compliance with 10CFR50.

10.2 LIQUID RELEASES 10.2.1 System Description A simplified liquid effluent flow diagram is provided in Figure 10-3. A simplified liquid waste processing diagram is provided in Figure 10 2. h The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by domineralizer 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 gaHon capacity, and I OWX26T - 33750 gaDon capacity) which receive liquid waste before discharge to the Kankakee river. '

10.2.2 Radiation Monitors f

10.2.2.1 Liquid Radwaste Effluent Monitors !

Monitor ORE-PR001 is used to monitor all releases from the release tanks. On high l alarm, the monitor automatically initiates closure of valves OWX-353 and OWX-896 to ,

terminate the release.

Pertinent information on the monitor and amant interi t'nntrni riavicac is provided in Byron /Braidwood UFSAR Table 11.5-2.

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BRAIDWOOD Revtion 1.8 October 1995 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 release. Pertinent information on this monitor l is provided in Byron /Braidwood UFSAR Table 11.5-2. 1 O l V 10.2.2.5 Condensate Polisher Sump Monitor l Monitor ORE-PR041 continuously monitors the condensate polisher sump discharge. .

On high alarm the monitor automatically initiates an interlock to trip the discharDe l pumps and terminate the release. Pertinent information on this monitor is provided in j Byron /Braidwood UFSAR Table 11.5-2. 1 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 j established to ensure that the limits of RETS and 10CFR20 are not exceeded in the l unrestricted area.

l 10.2.3.1.1 Liquid Radwaste Effluent Monitor '

During release the setpoint is established at 1.5 times the analyzed tank activity plus the background reading. .

l 10.2.3.1.2 Station Blowdown Monitor The monitor setpoint is found by solving equation 10-3.

0

(/ P s C* + (L.25 x C') x F' / (F" + T' )' (10-3)

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BRAIDWOOD Revan 1.8

October 1995 P Release Setpoint [pCi/mfj 1.25 Factor ;T Secount for minor fluctuations in count rah C" Concentration of activity in the circulating water blowdown [pCi/mf]

at the time of discharge. (" Background reading")

C7 Analyzed activity in the release tank [pCi/mf]

F" Circulating Water Blowdown Rate [gpm]

FL, Maximum Release Tank Discharge Flow Rate [gpm]

The flow rate from the radwaste discharDe 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.

The results of the anaYsis of the waste sample determine the discharge rate of each batch as follows:

FL, = 0. 5 (FL,/[ (CJ/10*DWC ) ) 3 (10-4)

The summation is over radionuclides 1.

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) 8 F, Circulating Water Blowdown Rate [gpm) cl Conrmntratinn nf Rartinnnelirie iin [pCl/mC the Release Tank The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank.

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DWC, Derived Water Concentration [pCi/mq !

j s of Radionuclide i !

The concentration of radionuclide i given in Appendix B. Table 2, Column 2 to 10CFR20.100120.2402.

]

1 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 i

10.2.3.2)

in addition to the limits identified within the RETS, an administrative action level for .

! tritium has been established for the Braidwood cooling pond. This limit, based on drinking water pathways, has been established as a control mechanism to ensure this . :

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pathway does not become a significant contributor to public dose. Because the public has access to the Braidwood cooling pond for fishing and/or boating an administrative -

l limit for discharges to the cooling pond is prudent to ensure dose to the public from this path remains wel below limits. ;

i l The controis for this pathway will be established by limiting the quantity (Curies) ;

discharged to the Braidwood cooling pond. Calculations were performed based on a

! tritium concentration of 20,000 pCl/ liter (40CFR190 public drinking water limit) and j 200 pCl/ liter which is a typical environmentallower limit of detection (LLD) for tritium.

i The administrative action level will be established at 4 Ci/ year which corresponds to ;

} an equilibrium cooling pond level of 200 pCl/ liter. !

. 10.2.3.4 Release Mixture

! l For monitors ORE PR001 and ORE-PRO 10 the release mixture used for the setpoint

! determination is the radionuclide mix identified in the grab sample isotopic analysis or

, the mix in Table 10-2.

[ For monitors 1RE PR001,1RE-PR002,2RE-PR001, and 2RE-PR002, the release

! mixture is the radionuclides which are listed in Table 10-2. Each nuclide in the mix is

! at a concentration which is 10% of the RETS value given in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402.

l l 10.2.3.5 Conversion Factors t

. The readouts for the liquid effluent monitors are in pCi/mt. The cpm to pCi/mi

{ conversion is based on the detector sensitivity to Os-137. !

10.2.3.6_ Liquid Dilution Flow Rates i Dilution flow rates are obtained from circulating water blowdown transmitter loop OFT-CWO32.

l l 10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid offluents released from either release tank (0WX01T or OWX26T) are comprised of contributions from both units. Under normal operating conditions, it i

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October 1995 is ditficult to apportion the radioactivity between the units. Consequently, allocation is g made evenly between units. T 10.2.5 Projected Concentrations for Releases After determining Fifrom Equation 10-4, RETS compliance is verified using Equations 10-5 and 10-6.

C,' = C,*[FL/(FL + F4)) (10-5)

(( C,'/10 OWC, } s 0.5 (10-6)

The summation is over radionuclides i.

C,' Concentration of Radionuclide iin the Unrestricted Area [pCi/mq The calculated concentration of radionuclide iin the unrestricted area as determined by Equation 10-5.

C[ Concentration of Radionuclide iin the Release Tank [pCi/m6 The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank.

DWC, Derived Water Concentration of Radionuclide i [pCi/mq O

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 DischarDe a Flow Rate [gpm)

FA 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.

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Assumed Composition of the Braidwood Station Noble Gas Effluent Percent of jagigga Total Annual Release Ar 41 00.89 Kr 65m 00.18 l Kr-85 24.90 l Kr 87 00.04 i

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 4

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l BRAIDWOOD Revhion 1.8

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CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table of Contents l CHAPTER IIILE PAGE 11 Radiological Environmental Monitoring Program 11 1 ,

LIST OF TABLES NUMBER ILILE g 11-1 Radiological Environmental Monitoring Program 11-2 LIST OF FIGURES NUMBER TITLE PAGE 11-1 Fixed Air Sampling Sites and Outer Ring TLD Locations 11 9 ,

11 2 inner Ring TLD Locations 11-10 11-3 Ingestion and Waterborne Exposure Pathway Sample Locations 11-11 O

EPSPROJedemtraid/11r1-8 11.[]

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l BRAIDWOOD RIvision 1.8

. l October 1995 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l Braidwood Station follows the Uniform Radiological Environmental monitoring Program which is I described in Chapter 9. This chapter identifies the site specific REMP for Braidwood Station.

l l Supplemental tables describing reporting levels and LLDs are included within Chapter 9 and figures l generally denoting Braidwood Station sample locations are contained herein.

O EPSPPOJedembroiddir14 11 1

i Braidwood Revision 1.8 i October 1995 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Samole Samole or Monitanna Location Collection Frecuency of Ana!vsis i

1. Airborne Continuous sampler F

operation with sarnple l Radiciodino Canisters:

l Radiciodine and a. Indicators-Near Field I collection weekly, or more 1-131 analysis weekly on

] Particulates frequently if required by near field and control l BD-06, Godley,0.5 mi WSW (0.8 km M) dust loading. samples'.

BD-19, Nearsite NW,0.3 mi NW (0.5 km Q) i BD-20 Nearsite N,0.6 mi N (1.0 km A) Particulate Samoler-l ~ BD-21, Nearsite NE,0.5 mi NE (0.8 km C) ,

Gross beta analysis I b. Indicators-Far Field following weekly filter I

change' and gamma BD-02, Custer Park,5.0 mi E (8.0 km E) l isotopic analysis' quarterly l BD-04, Essex,4.8 mi SSE (7.7 km H) l on composite filters by l

l BD-05, Gardner,5.5 mi SW (8.8 km L) ' location on near field and l

l control samples.

c. Controls l BD-03, County Line Road, 6.2 mi ESE (10.0 km F) l l

OJ4dembraid/11rt-8 *

.. .l l

O O Braidwood O -

Revision 1.8

I October 1995 Table 11-1 (Cont'd) -

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Samole Samole or Monitorino Location CoRection Freauency of Analvain l 2. Direct Radiahon a. Indicators-Inner Ring Quarterly Gamma dose on each TLD quarterly BD-101-3, 0.5 mi N (0.8 km A)

B D-101-4, 0.5 mi N (0.8 km A)

BD-102-1, 1.2 mi NNE (1.9 km B)

BD-102-2, 1.1 mi NNE (1.8 km B)

BD-103-1, 1.0 mi NE (1.6 km C)

BD-103-2, 1.0 mi NE (1.6 km C) 1 BD-104-1, 0.7 mi ENE (1.1 km D)

BD-104-2, 0.7 mi ENE (1.1 km D) l BD-105-1, 2.2 mi E (2A km E) l BD-105-2, 2.2 mi E (2.4 km E) l BD-106-1, 2.5 mi ESE (2.7 km F) i BD-106-2, 2.5 mi ESE (2.7 km F) l BD-107-1, 3.2 mi SE (3.2 km G) l B D-107-2, 3.2 mi SE (3.2 km G) l BD-108-1, 3.2 mi SSE (3.2 km H) l BD-108-2, 3.2 mi SSE (3.2 km H) l BD-109-1, 3.8 mi S (4.0 km J) i BD-109-2, 3.8 mi S (4.0 km J) l BD-110-1, 2.8 mi SSW (2.9 km K) l . BD-110-2, 2.8 mi SSW (2.9 km K)

B D-111 a-1, 1.4 mi SW (2.2 km L) l BD-111a-2, 1.4 mi SW (2.2 km L)

BD-112-1, 0.7 mi WSW (1.1 km M)

BD-112-2, 0.7 mi WSW (1.1 km M)

BD-113a-1, 0.5 mi W (0.8 km N)

BD-113a-2, 0.5 mi W (0.8 km N) 80-114-1, 0.4 mi WNW (0.6 km P)

BD-114-2, 0.4 mi WNW (0.6 km P)

BD-115-1, 0.3 mi NW (0.5 km Q)

B D-115-2, 0.3 mi NW (0.5 k m Q)

BD-116-1, 0.4 mi NNW (0.6 km R)

BD-116-2, 0.5 mi NNW (0.8 km R)

EPSPROJAodem& raid /11,r1-8 11-3

l Braidwood Revtion 1.8 l

October 1995 l Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Samole Samole or Monitorino Location Collection Freauency of Analysis l 2. Direct Radiation b. Indicators-Outer Ring l (Cont'd) BD-201-1, 4.2 mi N (6.8 km A) l B D-201-2, 4.2 mi N (6.8 km A) l BD-202-1, 4.8 mi NNE (7.7 km B) l B D-202-2, 4.8 mi NNE (7.7 km B)

BD-203-1, 4.9 mi NE (7.9 km C)

BD-203-2, 4.9 mi NE (7.9 km C)

BD-204-1, 4.3 mi ENE (6.9 km D)

B D-204-2, 4.3 mi ENE (6.9 km D)

BD-205-1, 4.0 mi E (6.4 km E)

BD-205-2, 4.0 mi E (6.4 km E)

BD-206-1, 4.5 mi ESE (7.2 km F)

BD-206-2, 4.5 mi ESE (7.2 km F) l B D-207-1, 4.5 mi SE (6.6 km G) l BD-207-2. 4.5 mi SE (6.6 km G)

B D-208-1, 4.5 mi SSE (7.2 km H)

BD-208-2, 4.5 mi SSE (7.2 km H)

B D-209-1, 4.8 mi S (7.7 km J)

[ BD-209-2, 4.8 mi S (7.7 km J)

BD-210-1, 4.9 mi SSW (7.9 km K) g B D-210-2, 4.9 mi SSW (7.9 km K)

BD-211-1, 4.8 mi SW (7.7 km L)

B D-211-2, 4.8 mi SW (7.7 km L) l B D-212-3, 5.0 mi WSW (8.0 km M)

BD-212-4, 5.0 mi WSW (8.0 km M) l BD-213-3, 4.8 mi W (7.7 km N)

BD-213-4, 4.8 mi W (7.7 km N)

B D-214-1, 4.3 mi WNW (6.9 km P)

BD-214-2, 4.3 mi WNW (6.9 km P)

BD-215-1, 4.5 mi NW (7.2 km O)

BD-215-2, 4.5 mi NW (7.2 km 0) 1 B D-216-1, 4.0 mi NNW (7.1 km R) l BD-216-2, 4.0 mi NNW (7.1 km R) ,

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c s l Brokhrood Revtion.1.8

1 -

I October 1995 '

t Table 11-1 (Cont'd) i Radiological Environmental Rionitoring Program Exposure Pathway Sampling or - Type and Fi m and/or Samole Samnia or Monitorina i ac=*iari CoRaction Freauency of Analrsas i

l 2. Direct Radiation c. Other (Cont'd)

Indcators

1 One at each of the airborne location given in part 1.a I and 1.b.

l BD-305-1, Fossil Hunting Area,0.4 mi E (0.64 km E) l BD-305-2, Braidwood Pond Access,1.0 mi E (1.6 km E) l BD-309 Braidwood Pond Access,2.7 mi S (4.3 km J)

I d. Conkok I i l' One at each airborne controllocation given in part 1.c.

1 I

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i EPSPROJ4dembraid/11,rt-8 11 5

--. _._ _ . . . . _ _ _ - . . . - - - - , ._, _ . . . , , - ~ - - , . _ . . . . , - . -

l Braidwood Revision 1.8 l

October 1995 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or and/or Samole Type and Frequency Samole or Monitorino Location Collection Frecuency of Ana!vsis

3. Waterborne l a. Ground / Wen a. Indicators Quarterly Gamma isotopic' and l

tritium analysis quarterfy.

BD-13 Braidwood City Hall Wen, l 1.7 mi NNE (2.7 km B) 1 BD-3a. Gibson Wen,4.7 mi E (7.6 km E) l BD-35, Joly Weg,4.7 mi E (7.6 km E) l BD-36, Hutton Weg,4.7 mi E (7.6 km E) l BD-37, Nurczyk Wen,4.7 mi E (7.6 km E) l l b. Drinkino Water a. Indicator Weekly grab sample Gross beta and gamma l

i isotopic analysis

on BD-22, Wilmington,5.0 mi NE (8.0 km C) monthly composite; tritium a

analysis on quarterly composite.

l c. Surface Water a. Indicator

, Weekly grab sample l Gross beta and gamma l

isotopic analysis' on 1 BD-10, Kankakee River downstream of monthly composite; tritium l discharge,5.4 mi NE (8.0 km C) l and analysis on quarterly I

composite.

I d. Control a. Control Weekly grab sample Gross beta and gamma l

l Isotopic analysis' on BD-25, Kankakee River upstream l

monthly composite; tritium of discharge,9.6 mi E (15.4 km E) l and analysis on quarterly composite.

e j e. Sediments a. Indicators ; Semiannually Gamma isotopic analysis' l ' semiannually.

BD-10, Kankakee River downstream of l discharge,5.4 mi E (8.0 km C) -

EAOJbdem/ braid /11,rt-8 916 9 Y

__ _ . . _ _ . ~ _ . . _ . _

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l I

n o Craidwood Rev'rion 1.8 O -

October 1995 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program

Exposure Pathway Sampling or I Type and Frequency and/or Samole Samole or Monitorino Location CoBection Freauency l of Analysis l I l 4. Inoestion Biweekly: May through Gamma isotopic

and 1-131 l 1 October or monthly: analysis

biweekly May l a. Mjjk a. indicators I November through April through October, monthly l

November through April.

l BD-17, Halpin's Dairy,5.5 mi SSW (8.8 km K) l 1

b. Controls I

l BD-24, Goodwin Dairy,7.4 mi E (11.9 km E) l l b. Ejsh a. Indicator Two times annuaHy Gamma isotopic analysis' on edible portions l BD'-28 Kankakee River in discharge l area,5.4 mi E (8.7 km E)

I b. Control l BD-25, Kankakee River upstream of discharge l area,9.6 mi E (15.4 km E) l c. Food Products a. Indicators Three times annuaRy. Gamma isotopic analysis' i Two sample locations within 6.2 mi. on edible portions.

l l Sample locations for food products may vary based i on availability and therefore are not required to be l identified here but sher be taken. Samples have I been taken previously at the following locations. t l

l BD-14, Pinnick Farm,1.8 mi N (2.9 km A) l BD-15, Girot Farm,1.4 mi NNE (2.2 km B)

BD-16, Clark Farm,3.3 mi ENE (5.5 km D)

b. Controls Two samples within 9.3 to 13.6 mi.

EPSPROJedem/ braid /11.rt-8 11 7

l Braidwood R:visi n 1.8 l October 1995 * ,

Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program 1' Far field samples are analyzed when near field results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents released from the station, or at the discretion of the Health Physics Support Director.

l l Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 shall be performed on the individual samph7 8

l Gamma isotopic analysis means L n'?ntification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station.

l l-131 analysis means the analytical separation and counting procedure are specific for this radionuclide.

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RIvision 1.8 l October 1995 i

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CHAPTER 12.0 :

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1

! SPECIAL NOTE l

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The transfer of the Radiological Effluent Technical Specifications to the ODCM by Technical Specification, Amendment 35, dated April 13,1992, was approved by the Nuclear Regulatory Commission.

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CHAPTER 12 &

ANNEX INDEX PAGE REYlSION P.AfaE REYlSION l 12 - l 1.8 12 .40 1.8 l 12 il 1.8 12 - 41 1.8 l 12 lii 1.8 12 - 42 1.8 l 12 iv 1.8 12 - 43 1.8 l 12 1 1.8 12 - 44 1.8 l 12 2 1.8 12 - 45 1.8 1 12 3 1.8 12 - 46 1.8 l 12 - 4 1.8 12 - 47 1.8 l 12 5 1.8 12 - 48 1.8 l 12 - 6 1.8 12 - 49 1.8 l 12 - 7 1.8 12 - 50 1.8 l 12 - 8 1.8 12 - 51 1.8 l 12 - 9 1.8 12 - 52 1.8 l 12 10 1.8 l 12 11 1.8 l 12 12 1.8 l 12 - 13 1.8 l 12 14 1.8 l 12 - 15 1.8 l 12 - 16 1.8 l 12 - 17 1.8 l 12 - 18 1.8 l 12 -19 1.8 l 12 - 20 1.8 l 12 - 21 1.8 l 12 22 1.8 l 12 - 23 1.8 l 12 - 24 1.8 l 12 25 1.8 l 12 26 1.8 l 12 27 1.8 l 12 28 1.8 l 12 29 1.8 l 12 - 30 1.8 l 12 31 1.8 l 12 - 32 1.8 l 12 33 1.8 l 12 - 34 1.8 l 12 - 35 1.B .

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. l October 1995 CHAPTER 12 dr ,

RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE l 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12-1 l 12.1 DEFINITIONS 12-4

! l 12.2 INSTRUMENTATION 12-8 i

l 1. Radioactive Liquid Effluent Monitoring instrumentation 12-8 l 2. Radioactive Gaseous Effluent Monitoring Instrumentation 12 13 l 12.3 LIQUID EFFLUENTS 12-20 4

l 1. Concentration 12-20 '

l 2. Dose 12-27 1

l 3. Liquid Radwaste Treatment System 12-29 l 12.4 GASEOUS EFFLUENTS 12-31 l

, l 1. Dose Rate 12-31 1 2. Dose - Noble Gases 12-37

3. Dose - lodine-131 and 133, Tritium, I and Radioactive Materialin Particulate Form 12-39 I 4. Gaseous Radwaste Treatment System 12 41 l S. Total Dose 12-43

I 6. Dose Limits for Members of the Public 12-45 i 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-46 l 1. Monitoring Program 12-46

, l 2. Land Use Census 12-47 j l 3. Interlaboratory Comparison Program 12-48 1

1 12.6 REPORTING REQUIREMENTS 12-49 l 1. Annual Radiological Environmental Operating Report 12-49 l 2. Annual Radioactive Effluent Release Report 12-50 l 3. Offsite Dose Calculation Manual (ODCM) 12-51

4. Major Changes to Liquid and Gaseous Radwaste ,

! Treatment Systems 12-52 4

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CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

LIST OF TABLES PAGE l 12.0 1 Effluent Compliance Matrix 12-2 l 12.0 2 REMP Compliance Matrix 12-3 1 12.11 Frequency Notations 12-7 l 12.2-1 Radioactive Liquid Effluent Monitoring Instrumentation 12-9 l 12.2-2 Radioactive Liquid Effluent Monitoring instrumentation Surveillance Requirements 12-11 l 12.2 3 Radioactive Gaseous Effluent Monitoring Instrumentation 12 14 l 12.2-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 12-15 l 12.3-1 Radioactive Liquid Waste Sampling and Analysis Program 12-20 12.4-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-31 0 l 12.5 1 Radiological Environmental Monitoring Program 12-45 l 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-51 1 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-52 O

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12.0 RADIOLOGICAL EFFLtJENT TECHNICAL STANDARDS l Chapter 12 of the Braidwood Station ODCM is a compilation of the various regulatory requirements, ,

I surveillance and bases, commitments and/or components of the radiological effluent and '

l environmental monitoring programs for Braidwood Station. To assist in the understanding of the I relationship between affluent regulations, ODCM equations, RETS (Chapter 12 section) and related l Technical Specification requirements, Table 12.0-1 is a matrix which relates these various I components. The Radiological Environmental Monitoring Program fundamental requirements are l contained within this chapter and are explained programmatically in Chapter 9 with Braidwood I specific information in Chapter 11 and with a supplemental matrix in Table 12.0-2.

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l October 1995 .

I l Table 12.0-1 g

l l EFFLUENT COMPLIANCE MATRIX l

l Regulation Dose Component Limit ODCM RETS Technical l Equation Specification l 10 CFR 50 1. Gamma air dose and beta air dose A1 12.4.2 6.8.4.e.8 l Appendix I due to airborne radioactivity in effluent A-2 l plume.

l l a. Whole body and skin dose due to A-6 N/A N/A l airborne radioactivity in effluent A-7 l plume are reported only if certain I gamma and beta air dose criteria l are exceeded.

I l 2. CDE for all organs and all four age A 13 12.4.3 6.8.4.e.9 l groups due to iodines and particulates I in effluent plume. All pathways are l considered.

l l 3. CDE for all organs and all four age A-29 12.3.2 6.8.4.e.4 l groups due to radioactivity in liquid I effluents.

I 10 CFR 20 1. TEDE, totaling all deep dose A-38 12.4.6 6.8.4.e.3 l equivalent components (direct, ground I and plume shine) and committed I effective dose equivalents (all l pathways, both airborne and liquid-I borne). CDE evaluation is made for j adult only using FGR 11 data base.

I 40 CFR 190 1. Whole body dose (DDE) due to direct A-35 12.4.5 6.8.4.e.10 l (now by dose, ground and plume shine from all 1 reference, sources at a station.

I also part of l 10 CFR 20) 2. Organ dosee. (CDE) to an adult due to A-13 l all pathways.

l Technical 1. " Instantaneous" whole body (DDE), A-8 12.4.1 6.8.4.e.7 l Specifications skin (SDE), and organ (CDE) dose A-9 l rates to an adult due to radioactivity in A 28 1 airborne effluents. For the organ I dose, only inhalation is considered.

l l 2. " Instantaneous" concentration limits for A-32 12.3.1 6.8.4.e.2 1 hquid effluents.

l Technical 1. Radiological Effluent Release Report NA 12.6.2 6.9.1.7 i Specifications i

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i 1 BRAIDWOOD Revision 1.8 l October 1995 l Table 12.0-2

( l l REMP Compliance Matrix l

i Regulation Component RETS Technical l Specification l 10CFR50 Implement environmental monitoring program. 12.5.1 6.8.4.1 l Appendix 1 l Section IV.B.2 l Technical Land Use Census 12.5.2 6.8.4.f.2 l Specifications l Technical Interlaboratory Comparison Program 12.5.3 6.8.4.f.3 l Specifications l Technical Radiological Environmental Operating Report 12.6.1 6.9.1.6 l Specifications O

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l October 1995 e 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12.1 DEFINITIOh[S 12.1.1 AC112D shall be that which prescribes remedial measures required under designated conditions.

12.1.2 Analoo Channel Doeratinnal Test shall be the injection of a simulated signalinto the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm interlock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy.

12.1.3 Channel Calibration shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CAllBRATION shall encompass the entire channelincluding the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.-

12.1.4 Channel Check shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channelindication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

12.1.5 Dioital Channel Onerational Test shall consist of exercising the digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY of alarm and/or trip functions.

12.1.6 Dose Eauivalent 1131 shall be that connection of I 131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133,1134, and 1135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table ill of TID-14844,

" Calculation of Distance Factors for Power and Test Reactor Sites".

l 12.1.7 Frecuency - Table 12.1-1 provides the definitions of various frequencies for which I surveillance, sampling, etc. are performed unless defined otherwise. The 25%

l variance shall not be applied to Operability Action statements. The bases to l Technical Specification 4.0.2 provide clarifications to this requirement.

l 12.1.8 Member (s) of the Public means any individual except when that individualis I receiving an occupational dose.

l l 12.1.9 Occuantional Dose means the dose received by an individualin the course of l employment in which the individual's assigned duties involve exposure to radiation I and/or to radioactive material from licensed and unhcensed sources of radiation, -

l whether in the possession of the licensee or other person. Occupational dose does i not include dose from background radiation as a patient from medical practices, from I voluntary participation in medical research programs, or as a member of the public.

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l BRAIDWO2D Revision 1.8 I October 1995 p i 12.1.10 Operable / Operability a system, subsystem, train, component or device shall be Q OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical

{

power, cooling or seat water, lubrication or other auxiliary equipment that are required 1 for the system, subsystem, train, component, or device to perform its function (s) are l also capable of performing their related support function (s).

I 12.1.11 Ooerational Mode (i.e. Mode) shall correspond to any one inclusive combination of core reactivity condition, power level, and' average reactor coolant temperature specified in Table 1.2 of the Technical Specifications.

I 12.1.12 Process Control Prooram (PCP) shall contain the current formulas, sampling, ,

analyses, tests, and determinations to be made to ensure that processing and l packaging of solid radioactive wastes based on demonstrated processing of actual or l simulated wet solid wastes will be accomplished in such a way as to assure I compliance with 10 CFR Parts 20,61,71 and State regulations, burial ground requirements, and other requirements governing the disposal of radioactive wastes.

l 12.1.13 Puron/Puraina shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, conccntration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

l 12.1.14 Rated Thermal Power shall be a total core heat transfer rate to the reactor coolant of 3411 MWt.

O l 12.1.15 Site Boundarv shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

l 12.1.16 Solidification shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.

l 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.

l 12.1.18 Thermal Power shall be the total core heat transfer rate to the reactor coolant.

l 12.1.19 Unrestricted Area means an area, access to which is neither limited nor controlled by the licensee.

l 12.1.20 Ventilation Exhaust Treatment System shall be any system designed and installed to reduce gaseous radiciodine or radioactive m3terialin particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

I 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.

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I BRAIDWOOD R;visi:n 1.8 l- October 1995 .

I 12.1.22 Waste Gas Holdun System shall be any system designed and installed to reduce radioactivo gaseous effluents by collecting Reactor Coolant System off-gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

I 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 incorporated into the database.

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f I BRAIDWOOD Revision 1.8 I October 1993 i

TABLE 12.1 1 1 FREQUENCY NOTATION 9*

1 1

4 NOTATION FREQUENCY j -l S - Shiftly At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D - Daily l At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I W - Weekly At least once per 7 days.

l l M Monthly At least once per 31 days.

O - Quarterly I At least once per 92 days.

] l' SA - Semiannually At least once per 184 days.

j l A - Annually At least once per 366 days.

I R - Refueling cycle At least once per 18 months (550 davr;.

I S/U Startup Prior to each reactor startup.

I P - Prior Prior to each radioactive release.

N.A. Not applicable.

I* Each frequency requirement shall be performed within the specified time interval with the !

I maximum allowable extension not to exceed 25% of the frequency interval. The 25% variance l l shall not be applied to Operability Action statements. The bases to Technical Specification ,

l 4.0.2 provide clarifications to this requirement.

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12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitoring instrumentation Ooerability Recuirements 12.2.1.A The radioactive liquid effluent monitoring instrumentation channels shown in Table 12.21 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of 12.3.1.A are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM. -

Acolir nhility: At all times Actista

1. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.

2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Radioactive Effluent Release Report pursuant to Section 12.6 why this inoperability was not corrected within the time specified.

h Surveillance Raouirements 12.2.1.B Each radioactive liquid effluent mon'.oring inst'.umentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and DIGlYAL and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 12.2 2.

Bases 12.2.1.C The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior 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.

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I BRAIDWOOD Revtion 1.8 l October 1995

?

TABLE 12 2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION t

MINIMUM

CHANNELS INSTRUMENT OPERABLE ACTION !

t

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release i

a. Uguid Radwaste Effluent une (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

1) Unit 1 a) RCFC 1 A and 1C Outlet (1RE PR002) 1 32 b) RCFC 18 and 1D Outlet (1RE-PR003) 1 32

2) Unit 2 a) RCFC 2A and 2C Outlet (2RE-PR002) 1 32 b) RCFC 2B and 2D Outlet (2RE PR003) 1 32

b. Station Blowdown Line (ORE-PRO 10) 1 32

3. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent une (Loop-WXOO1) 1 33

b. Liquid Radwaste Effluent Low Flow Une (Loop-WX630) 1 33

c. Station Blowdown Une (Loop-CWO32) 1 33 ,

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- e i BRAIDWOOD Revbion 1.8

l October 1995 .

TABLE 12.2-1 (Continued) l RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ,

i ACTION STATEMENTS ACTION 31 - 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 14 days provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with Section 12.3 and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

l ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are l collected and analyzed for principal gamma emitters and 1-131 at a lower limit of detection as specified in Table 12.3-1.

ACTION 33 - With the number of channels OPERABLE less than required by the Minimum O

Channels OPERABLE requirement, effluent releases via this pathway may continue l for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated in , lace may be used l to 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 I for up to 30 days provided grab samples are analyzed for principal gamma emitters I 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT l-131, or

b. At least once pqr 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less tian or equal te 0.01 microcurie / gram DOSE EQUlVALENT l-131.

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Rev2 ion 1.8

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Octobert 1995 TABLE 12.2-2 RADIOACTIVE LIOUlD EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ;

DIGITAL ANALOG CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST TEST

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release i a. Liquid Radwaste Effluent Une (ORE-PR001) D P R(3) Q(1) N.A.

b. Fire and Oil Sump Discharge (ORE-PR005) D M R(3) O(1) N.A.

c. Condensate Polisher Sump Discharge (ORE-PR041) D M R(3) O(1)* N.A.

2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Essential Service Water

1) Unit 1 l a) RCFC 1 A and 1C Outlet (1RE-PR002) D M R(3) O(2) N.A.

I b) RCFC 18 and 1D Outlet (1RE-PR003) D M R(3) O(2) N.A.

2) Unit 2 l a) RCFC 2A and 2C Outlet (2RE-PR002) D M R(3) O(2) N.A.

I b) RCFC 2B and 2D Outlet (2RE-PR003) D M R(3) O(2) N.A.

I b. Station Blowdown Line (ORE-PRO 10) D M R(3) O(2) N.A.

3. Flow Rate Measurement Devices I a. Uquid Radwaste Effluent Line (Loop-WX001) D(4) N.A. R N.A. O

b. Liquid Radwaste Effluent Low Flow Line (Loop-WX630) D(4) N.A. R N.A. O

c. Station Blowdown Line (Loop-CWO32) D(4) N.A. R N.A. O EPSPROJ/odem& raid /12rt-8 12-11

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l October 1995 .

TABLE 12.2-2 (Continued) l RADIOACTIVE LfOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE l REQUIREMENTS TABLE NOTATIONS l

(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

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or

c. Detector check source test failure, or

d. Detector channel out-of-service, or

e. Monitor loss of sample flow. This is only applicable for ORE-PR001 and ORE-PR005.

Monitor ORE PR041 will not trip on loss of sample flow.

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm Setpoint, or

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or

c. Detector check source test failure, or

d. Detector channel out-of service, or

e. Monitor loss of sample flow.

(3) The initial CHANNEL 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. Th9se 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.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

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. l October 1995 1

12.2.2 Radioactive Gananus Effluent Monitorino Instrumentation 6

~

Onarability Rannirements "

12.2.2.A The radioactive gaseous effluent monitoring instrumentation channels shown in Tat,:e 12.2-3 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Section 12.4 are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

Apphcabihtv - As shown in Table 12.2-3 Actin.o

1. With a radioactive gaseous effluent munitoring instrumentation channel Alarm / Trip 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 i inoperable.

l

2. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2-3. Restore the inoperable instrumentation to -

1 OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report pursuant to Section 12.6 why this inoperability was not corrected within the time specified.

4 Surveillance Raouirements

12.2.2.B Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and DIGITAL and CHANNEL OPERATIONAL TEST at the frequencies shown in Table 12.2-4.

4 Bases 12.2.2.C The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents

, during actual or potential releases of gaseous effluents. The Alarm / Trip a

Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior 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. The sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent .

release requirements of Section 12.4 shall be such that concentrations as low l

as 1x10* uCi/cc are measurable.

O l EPSPROJ4dembroidn2rt-8 12-13

l BRAIDWOOD Revision 1.8 l

October 1995 TABLE 12.2-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Plant Vent Monitoring System - Unit 1

a. Noole Gas Activity Monitor Providing Alarm

1) High Range (1RE-PR028D) 1 39

2) Low Range (1RE-PR0288) 1 39

b. lodine Sampler (1RE-PR028C) 1 40

c. Particulate Sampler (1RE-PR028A) 1 40

d. Effluent System Flow Rate Measuring Device (LOOP-VA019) 1 36

e. Sampler Flow Rate Measuring Device (1FT-PR165) 1 36^

2. Plant Vent Monitoring System - Unit 2

a. Noble Gas Activity Monitor Providing Alarm

1) High Range (2RE-PR028D) 1 39

2) Low Range (2RE-PR0288) 1 39

b. lodine Sampler (2RE-PR028C) 1 40

c. Particulate Sampler (2RE-PR028A)

1 40

d. Effluent System Flow Rate Measuring Device (LOOP-VA020) 1 36

e. Sampler Flow Rate Measuring Device (2FT-PR165) 1 36 E OJtdem/ braid /12rt-8

6 A l

O O BRAIDWOOD Revision 1.8 O- -

l October 1995 1 ABLE 12.2-3 iContinued) t RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

3. Not Used.

4. Gas Decay Tank System

a. Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release (ORE-PR002A and 2B) 2 35

5. Containment Purge System

a. Noble Gas Activity Monitor-Providing Alarm (RE-PR001B) 1 37

b. lodine Sarrpler (RE-PR0010) 1 40

c. Particulate Sampler (RE-PR001 A) 1 40

6. Radioactivity Monitors Providing Alarm and Automatic Closure of Surge Tank Vent-Component Cooling Water Une (ORE-PR009 and RE-PR009) 2

41 a

EPSPROJedembroid/12rt-8

'12-15 hr-- -.r g g y -==m'. g de y . y --,y-y , w .iwe- -~ ~ e -,-- =9 m _- a------ -- - - - - - - - . _ _ . - - - - - - - - - - - . - - - - - - = - ' - - - - - - - - - - - - - - -

I BRAIDWOOD R: vision 1.8 l l October 1995 . l l

)

TABLE 12.2-3 (Continued) l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION I TABLE NOTATIONS

At all times.

ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently I verify the release rate calculations and discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement,immediately suspend PURGING of radioactive l effluents via this pathway. Releases may continue via this pathway for up to 7 days l provided real time monitoring of radioactive effluents released via this pathway is l l established.

ACTION 38 - Not used.

ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and l these samp;es are analyzed for principle gamma emmitters at a LLD as specified in l Table 12.4-1.

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 sampling equipment as required in Table 12.41.

l ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue l for up to 30 days provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , liquid grab samples are

)

collected and analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1.

l EPsPROJ/odem/ braid /12rt-8 12-16

. _ _ _ . . . . . _ . _ . _ _ . . __ _. _ . . . .. .. _ _ _ _ . . . _ . _ . . . _ . _ . . . . _ . _ _ . . _ _ _ . ___ . __m. ._ _ m _. ..

$ h' 1

O O CRAIDWOOD -

O Revision 1.8 l

October 1995 i

TABLE 12A4 I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CHECK CALIBRATION TEST IS REOulRsr)

1. Plant Vent Monitoring System - Unit 1 i

a. Noble Gas Activity Monitor-Providing l

Alarm ,

1

1) High Range (1RE-PR028D) D M R(3) O(2) l

2) Low Range (1RE-PR028B) D M R(3) O(2)

b. lodine Sampler (1RE-PR028C) D M R(3)

O(2) l

c. Particulate Sampler (1RE-PR028A) D M R(3)

O(2)

d. Ettluent System Flow Rate Measuring D N.A. R O.

Device (LOOP-VA019) i

e. Sampler Flow Rate Measuring Device D N.A. R O +

(1FT-PR165) i

2. Plant Vent Monitoring System - Unit 2 -

a. Noble Gas Activity Monitor-Providing !

Alarm

1) Higft ege (2RE-PR028D) D M R(3) O(2)

2) Low Range (2RE-PR0288) D M R(3) O(2)

b. lodine SampW (2RE-PR028C) D M R(3)

O(2)

EPSr*ROAdembroid/12rt-4 12 17

~.

_ _ _ _ _ _ __ _ . _ _ _ _ _ _ _ _ _ - . _ _ _ - _ _ _ _ _ ~ __ _ _ _ _ _ . . . . . _ . _-.-.. ._. ~__.. _ _ .. -.- -- ,-...__....-_ _.__. _ . . _

i CRAIDWOOD RevC0 ion 1.8 i October 1995 TABL E 12.2-4 (Continued) -

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

- DIGITAL CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CHECK CALIBRATION TEST IS REQUIRED

2. Plant Vent Monitoring System - Unit 2 (Continued)

c. Particulate Sampler (2RE-PR028C) D M R(3)

O(2)

d. Effluent System Flow Rate Measuring D N.A. R O

Device (LOOP-VA020)

e. Sampler Flow Rate Measuring Device D N.A. R O *

(2FT-PR165)

3. Not Used

4. Gas Decay Tank System

a. Noble Gas Activity Monitor P P R(3)

O(1)*

Providing Alarm and Automatic Termination of Release (ORE-PR002A and 28)

5. Containment Purge System

a. Noble Gas Activity Monitor-Providing Alarm (RE-PR0018) D P R(3)

O(2)

b. lodine Sampler (RE-PR001C) P P N.A.

R(3)

c. Particulate Sampier (RE-PR001 A) P P R(3) N.A. *

6. Radioactivity Monitors Providing Alarm and Automatic Closure of Surge Tank Vent-Component Cooling Water Line (ORE-PR009 and RE-PR009) D M R(3) O(1)

OJ/bdem/ braid /12rt-8 g

l BRAIDWOOD RIvision 1.8

. l October 1995 i TABLE 12.2-4 (Continued)

^

l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l SURVElLLANCE REQUIREMENTS TABLE NOTATIONS l* At all times.

(1) The DIGITAL CHANNEL OPERATIONAL TEST shal! 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

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or i

c. Detector check source test failure, or r

d. Detector channel out-of-service, or

e. Monitor loss of sample flow. Monitoring ORE PR002A and 2B will not trip on loss of sample flow. This is only app. cable 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 measured levels above the Alarm Setpoint, or ;

b. Circuit failure (monitor loss of communications - alarm only, detector loss of counts, or monitor loss of power), or l

c. Detector check source test failure, or l l

d. Detector channel out-of-service, or i

e. Monitor loss of sample flow. I (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. ..

4 O

y/

EPSPROJ4dembroid/12rt-a 12 19

l BRAIDWOOD Revision 1.8 l October 1995 ,,

12.3 LIQUID EFFLUENTS 12.3.1 Concentration Onerability ReauireMents 12.3.1.A The concentration of radioactive 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 concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.100120.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases; the concentration shall be limited to 2x10 microcurie /mi total activity.

Anolicability: At all times Afdl2D

1. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

Surveil!ance Raouirements 12.3.1.1.8 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 12.3-1.

12.3.1.2.B The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of 12.3.1.A.

Bases 12.3.1.C This section is provided to ensure that the concentration of radioactive materials released in liquid waste offluents to UNRESTRICTED AREAS will be less than 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section ll.A design objectives of Appendix 1, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.1301.

This section applies to the release of radioactive materials in liquid effluents from all units at the site.

O EPSPROJ/odem/ braid /12rt-8 12 20

+

I l BRAIDWOOD Revision 1.8 >

l October 1995 l

j A 12.3 LlOUlD EFFLUENTS (Continued) i L) a....

The required detection ceabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed )

discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for l Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Cham. 40. 586-93 (1968), and Hartwell, J.K., " Detection !

Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH SA-215 (June 1975).

s J

l

, )

i i l

a r

I !

!O I

h i

I I

lO EPSPROJ4dembroid/12rt 4 12-21 1

I BRAIDWOOD Revision 1.8

l October 1995 ,

TABLE 12.3-1, RADIOACTIVE LfDUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTIVITY LOWER LIMIT TYPE FREQUENCY FREQUENCY ANALYSIS OF DETECTION (LLD)") (pCl/ml)

1. Batch Release #

P P Principal Gamma 5x10 1 Tanks (2) Each Batch Each Batch Emitters (7) 4 1-131 1x10 4

P M Dissolved and 1x10 One Batch /M Entrained Gases I (Gamma Emitters)(7)

P M H-3 1x10*

I Each Batch Composite (3)

Gross Alpha 1x10 P O Sr-89, Sr-90 5x10*

l Each Batch Composite (3) 4 Fe-55 1x10 l 2. Continuous Continuous (5) W Principal Gamma 5x10 #

l Releases (4) Composite (5) Emitters (7) 4 1-131 1x10 M M Dissolved and 1x10 4

a. Circulating Grab Sample Entrained Gases I W ater Blow &;wo (Gamma Emitters)(7) l Continuous (5) M H3 1x10* l 1 Composite (5) l

b. Waste Water T " #

Gross Alpha 1x10 D ge b Circulating W ater Discharge I

Continuous (5) O Sr-89, Sr 90 5x10 4 ,,

I Composite (5) 4

c. Condensate Fe-55 1x10 Polisher Sump Discharge i

EPSPROJ4dem/ braid /12rt-8 12 22

l BRAIDWOOD R vision 1,8

- l Oct:ber 1995 p TABLE 12 3-1 (Continuari)

\

, RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i

LIQUID RELEASE SAMPLING MINIMUM TYPE OF ACTIVITY LOWER LIMIT

} TYPE FREQUENCY ANALYSIS ANALYSIS OF DETECTION FREQUENCY. (LLD)N(pCi/ml)

3. Continuous #

l W(6) W(6) Principal Gamma 5x10 3 i Release (4) Grab Sample Emitters (7)

Essential Service Water I131 1x10*

Reactor 4

l Containment H3 1 x 10

~

Fan Coobr l

M(6) Dissolved and 1x10 4 (RCFC) Outlet Line Entrained Gases I

(Gamma Emitters)(7)

4. Continuous None None Principal Gamma 5x 10" i Surge Tank Emitters (7)

Vent-

, Component 4 Dissolved and 1x10

(' Cooling Water Entrained Gases

) Line (8)

(Gamma Emitters)(7) 1-131 1x10 4 4

C 3

(

l I

i I

I 1

i O l EPsPROJ/odctrsraid/12rt 4 12-23

l BRAIDWOOD Revision 1.8 l Oct1ber 1995 i

TABLE 123-1 (Continued) l 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 materialin 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 l represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = **

E + V + 2.22 x 10' + Y + exp (-141)

Where:

LLD = the lower limit 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 efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

122 x 10' = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec "), and at = the elapsed time between the midpoint of sample collection and the time of counting (sec).

Typical values of E, V, Y, and at should be used in the calculation.

l Alternative LLD Methodoloov l

1 An alternative methodology for LLD determination follows and is similar to the above LLD l equation:

l l [ 2.71 + 4,65(B ] + Decay l LLD =

1 l E q b Y t (2.22E06) l I

O EPsPROJ4dembraid/12r1-8 12 24

1 l- BRAIDWOOD Revision 1.8

l October 1995

, TABLE 12 3-1 (Confirmad)

l. RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

' \

TABLE NOTATIONS '

i .i

. l Where:

l (

i l B = background sum (counts) !

'l !

l. E = counting efficiency. (counts detected / disintegrations) I j l 'q = sample quantity, (mass or volume) ;

j l '

} l b = abundance,(if applicable) l

I Y = fractional radiochemical yield or coNection efficiency, (if appEcable) l l l

I t = count time (minutes) ;

i l !

i 1 2.22E06 = number of disintegrations per minute per microcurie l

i l 2.71 + 4.65(B = k' + (2k (2 (B), and k = 1.645. f

} I l (k=value of the t stat'stic from the single-tailed i distribution at a significance level of

. l 0.95 and infiiite degrees of freedom. This means that the LLD result represents a i ! 95% detection probability with a 5% probability of falsely concluding that the nuclide l present when it is not or that the nuclide is not present when it is.)

{ l Decay = e"' [ ART /(1 e")) [AT, /1 e"*)), (if applicable) !

l A = radioactive decay constant, (units consistent with At, RT and T,) ;

I '

j l 41 = " delta t", or the elapsed time between cample coHection or the midpoint of sample l

! I collection and the time the count is started, depending on the type of sample, (units i j~ l consistent with A) !

i I i l RT = elapsed real time, or the duration of the sample count, (units consistent with A)

I i T,- sample deposition time, or the duration of analyte collection onto the sample media, !

l (Units consistent with A) l 1 l l

{ l The LLD may be determined using installed radioanalytical software, if available. In ;

! I addition to determining the correct number of channels over which to total the background .

I sum, utilizing the software's ability to perform decay corrections (i.e. during sample !

' -l collection, from sample collection to start of analysis and during counting), this altomate i l method will result in a more accurate determination of the LLD. ..

) l l It should be recognized that the LLD is defined as a before the fact limit representing the j capability of a measurement system and not as an after the fact limit for a particular measurement.

4-

~

(2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

4 EPSPROAdenhenidn2rt-4 12-25

l BRAIDWOOD Revision 1.8 "

l October 1995 .

TABLE 12.3-1 (Continued) l RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (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.

I (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.

1 (5) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously whenever the effluent stream is flowing. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

l (6) Not required unless the Essential Service Water RCFC Outlet Radiation Monitors RE-PR002 4

and RE-PR003 indicates measured levels greater than 1x10 pCi/m! above background at any time during the week.

l (7) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for dissolved and entrained gases and Mn 54, Fe-59, Co-58, Co-60, Zn-65, Mo 99, Cs-134, Cs-137, Ce-141, and Ce-144 for principal gamma emitters. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report !

pursuant to Section 12.6.2, in the format outlines in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

l (8) A continuous release is the discharge of dissolved and entrained gaseous waste from a nondiscrete liquid volume.

I i

O EPsPROJ/odembraid/12ri-8 12-26

l BRAIDWOOD R: vision 1.8 i October 1995 1

O 12.3.2 Dosa b Onerability Ranuirements !

12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F, Figure F 1) shall be limited:

1. During any calendar quarter to 16ss than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mroms to any orDan, 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.

Anolir nhilitv: At all times.

t MlD.D

1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. '

Surveitlance Renuirements 12.3.2.B Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Bases 12.3.2.C This section is provided to implement the requirements of Sections ll.A, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements implement the guides set forth in Section ll.A 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 1 to assure that the releases of radioactive materialin liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dose calculation methodology and parameters in the ODCM implement the a

requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix l be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid 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 n Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977.

EPsPSOJhdembraid/12r18 12 27

I J BRAIDWOOD Revtion 1.8 l l October 1995 ,

l 12.3.2 Dnlig (Continued)

Bases i l

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 ascribed to a I specific unit. An estimate should be made of the contributions from each unit based ;

on input conditions, e.g., flow rates and radioactivity concentrations, or, if not l practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releasec .pecifically attributed to each unit to obtain the total releases per unit.

O e

EPsPROJ4demoraid/12rt-8 12-28

l BRAIDWOOD RIvtion 1.8 i October 1995 f 12.3.3 Iinmid Radwaste Treatment System b Onershility Rannirements 12.3.3.A . The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) would exceed 0.06 mrom to the whole body or 0.2 mrem to any organ in a 31. day period.

Acoliemhi!!tv: At all times.

1 Action 4

1

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 Specification 6.9.2, a Special Report that includes the following information:

a. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s) taken to prevent a recurrence. !

l Surveiflance Raouirements 12.3.3.1.B Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when the Liquid Radwaste Treatment System is not being fully utilized.

12.3.3.2.B The installed Liquid Radwaste Treatment System shall be considered

OPERABLE by meeting Sections 12.3.1.A and 12.3.2.A.

Bases 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of

)

l this system be used when specified provides assurance that the releases of

' radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This section implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix 1 to 10 CFR Part 50.

l

! l EPsPROJ/odem/ braid /12rt.s 12-29 i l

l

l l BRAIDWOOD Revision 1.8 , :

l October 1995 ,!

I I 12.3.3 Linuid Radwaste Treatment System (Continued)

Bases The specified limits governing the use of appropriate 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 effluents.

This section applies to the release of radioactive materials in liquid effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such

mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

O O

EPsPROJ/odem/ braid /12r18 12 30

i l BRAIDWOOD Revision 1.8 l e i October 1995 i 12.4 GASEOUS EFFLUENTS

%J 12.4.1 Dose Rate Onerability Renuirements 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 l

whole body and less than or equal to a dose rate of 3000 mrems/yr to the skin, and l

2. For lodine 131 and 133, for tritium, 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.

)

l Anchcability At all times.

l Acho.n i

1. With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s).

Surveillance Raouirements C\

\_./ 12.4.1.1.B The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

12.4.1.2.B The dose rate due to 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 p trameters in the !

ODCM by obtaining representative samples and performing analyses h accordance !

with the sampling and analysis program specified in Table 12.41.

Bases 1 12.4.1.C This section is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annualdose limits of 10CFR20. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, exceeding the limits specified in 10CFR20.1301.

\

I 1

O EPsPROJAodem/bredn2r1-4 j g.31 l

1

+ .

I BRAIDWOOD R; vision 1.8 i October 1995 .

l l

12.4 GASEOUS EFFLUENTS (Continued)

Bases l

For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to :

compensate for any increase in the atmospheric diffusion factor above that for the !

SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE-BOUNDARY to less than or equal to 500 mrems/ year to the whole body or to less than or equal to 3000 mrams/ year to the skin. These release rate limits also restrict, at all times the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to 1500 mroms/ year.

This section applies to the release of radioactive materials in gaseous effluents from all units at the site.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection Smits can be found in HASL Procedures Manual, HASL 300 (revised annually).. Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J.K., "Jetection Limits for Radioanalytical Counting Techniques," Atlantic RicMeld Hanford Company Report ARH-SA-215 (June 1975).

l t

l l

l O

EPSPROJ/odem/ braid /12ri--8 12-32 '

I BRAIDWOOD Revision 1.8 l October 1995 TABLE 12.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM LlOUID RELEASE SAMPLING MINIMUM TYPE OF ACTIVITY LOWER LIMIT TYPE FREQUENCY ANALYSIS ANALYSIS OF (e)

FREQUENCY DETECTION (LLD)"8 (pCl/cc) 1, Waste Gas P P Principal Gamma 1x10" Decay Tank Each Tank Each Tank Emitters (2)

Grab Sample

2. Containment P P Principal Gamma 1x10" Purge Each Purge Each Purge (3) Emitters (2)

(3) Grab #

Sample H-3 1x10 d

3. Auxiliary Bidg. M (4)(5) M Principal Gamma 1x10 Vent Stack Grab Sample Emitters (2)

(Unit 1 and 2) #

H3 1x10 Continuous W (7) 1-131 1 x 10

(6) Charcoal Sample 1133 1x10"'

Continuous W (7) Principal Gamma 1x 10'"

(6) Particulate Emitters (2)

Sample l Continuous O Gross Alpha 1x 10'"

(6) Composite Particulate Sample Continuous O Sr-89, Sr-90 1x 10'"

(6) Composite Particulate Sample Continuous Noble Gas Noble Gases, Gross 4 1x10

Monitor Beta or Gamma 1

O EPSPROhdem4 raid /12rt-4 12 33

l BRAIDWOOD Rev2 ion 1.8 l October 1995 ,

TABLE 12.41 (Continued) l RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (1) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive materialin 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:

60s, LLD =

E V 2.22 x 10'- Y exp (-AAt)

Where:

LLD e the lower limit 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 efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 x 10' = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec "), and At = the elasped time between the midpoint of sample collection and the time of counting (sec).

Typical values of E, V, Y, and at should be used in the calculation.

I Afternative LLD Methodoloav i

l An alternative methodology for LLD determination follows and is similar to the above LLD l equation:

I l [ 2.71 + 4.65(B ) Decay I LLD =

I I E q b Y t (2.22E06) 1 I

O EPsPROJedembraid/12rt-8 12 34

3 I BRAIDWOOD Revision 1.8 l October 1995 TABLE 12 41 (Continuarn l

Q] l RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS l Where; I

l B = background sum (counts) l E = counting efficiency. (counts detected / disintegrations) 1 -

l q = sample quantity, (mass or volume) l l b = abundance, (if applicable) l l Y = fractional radiochemical yield or collection efficiency, (if applicable) l l t = count time (minutes) l l 2.22E06 = number of disintegrations per minute per microcurie I 2.71 + 4.65(B = k" + (2k (2 (B), and k = 1.645.

l l (k=value of the t statistic from the single tailed t distribution at a significance level of I 0.95 and infinite degrees of freedom. This means that the LLD result represents a l 95% detection probability with a 5% probability of falsely concluding that the nuclide i present when it is not or that the nuclide is not present when it is.) l l Decay = e*" [ ART /(1-e")) [AT,11 e#')], (if applicable) l A = radioactive decay constant (unhits consistent with At, RT and T,)

I l

l At = " delta t", or the elapsed time between sample collection or the midpoint of sample I collection and the time the count is started, depending on the type of sample, (units I consistent with 1)

I l RT - elapsed real time, or the duration of the sample count, (units consisten with 1) l I T = sample deposition time, or the duration of analyte collection onto the sample media, l (units consistent with A)

. l l The LLD may be determined using installed radioanalytical software, if available. In s I addition to determining the correct number of channels over which to total the background i sum, utilizing the software's ability to perform decay corrections (i.e. during sample l collection, from sample collection to start of analysis and during counting), this alternate I 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 limit and not as an after the f act

, limit for a particular measurement.

. O EPSPROJbdcmkraidn2r1-8 12 35

l BRAIDWOOD R:vri:n 1.6

l Octob r 1995 .l TABLE 12.41 (Continued)

I l RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM g

TABLE NOTATIONS (2) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr 88, Xe-133, Xe 133m, Xe-135, and Xe-138 in noble gas releases and Mn-54 Fe 59, Co-58, Co-60, Zn-65, Mo 99,1131, Cs 134, Cs-137, Ce-141, and Ce-144 in particulate releases. This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with ihose 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 samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canalis flooded.

(5) Tritium grab samples shall be taken at least once per 7 days from the spent fuel pool area, whenever spent fuelis 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.

I (7' Samples shall be changed at least once per 7 days and analyses shall be completed within a l timeframe necessary to meet the applicable lower limits of detection but not to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at lesst 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL i POWER within a 1-hour period and analyses shall be completed in a timeframe necessary to l meet the appicable lower limits of detection but not to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLPs may be lilcreased by a factor of 10. This requirement does not apply it: (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 effluent activity has not increased more than a factor of 3.

O EPsPROJ/odembraid/12rt-8 12-36

l ..

. BRAIDWOOD R: vision 1.8

'l. October 1995 i

12.4.2 Dona - Noble Gases Onarahility Ranniraments 12.4.2.A The air dose due to noble gases released in gaseous effluents, from each unit, to !

I arsab at and beyond the SITE BOUNDARY (soo Braidwood Station ODCM Annex, Appendix F, Figure F 1) shall be limited to the following: I

1. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and l

less than or equal to 10 mrads for beta radiation, and r a

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. !

Anphcabthly. At all times. t ActioII*

l

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 Techni ,al 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.

j Survaillance Amaniramants 12.4.2.8 Cumulative dose contributions for the current calendar quarter and the current ,

calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Bases j

j 12.4.2.C This section is provided to implement the requirements of Sections 11.B, lil.A and IV.A '

s of Appendix 1,10 CFR Part 50. The Operability Requirements implement the gaides

' set forth in Section 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 l IV.A of Appendix ; to assure that the releases of radioactive materialin gaseous l l l effluents to areas at or beyond the SITE BOUNDARY will be kept "as low as is ,

reasonable achievable." The Surveillance Requirements implement the requirements i in Section Ill.A of Appendix l that conformance with the guides of Appendix l be '

shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. (

l

+ .

4 I 1

EPSPROJedembras#12rt s 12 37 i

i

I l BRAIDWOOD R:vhion 1.8 '

l October 1995 .

12.4.2 Dose Noble Gases (Continued)

Bases ;

The dose calculation methodology and parameters established in the ODCM for ;

calculating the doses due to the actual release rates of radioactive materials in !

gaseous effluents are consistent with the methodology provided in Regulatory Guide j 1.109," Calculation of Annual Doses to Man From Routine Releases of Reactor i Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I" Revision 1. October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors, Revision 1," July 1977. The ODCM equations provided I for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste

, producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

O EPsPROJ/odem/ brad /12rt-8 12-38

+

l BRAIDWOOD R!visi:n 1.8 l Oct:ber 1995 12.4.3 Dona . lodine I-131 and 133. Tritium. and Rartinnetive Materialin Particulate Form A)

L. . Onarahility Ranniraments 12.4.3.A The dose to a MEMBER OF THE PUBLIC from lodine 131 and 133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents l 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 72 mrems to any organ, and

'2. During any calendar year: Less than or equal to 15 mrems to any organ.

Anplicability At all times.

Actina

1. With the calculated dose from the release of lodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous affluents 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 actioris 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 12.4.3.B Cumulative dose contributions fur the current calendar quarter and the current calendar ye for lodine 131 and 133, tritium, and radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. -

Bases 9

12.4.3.C This section is provided to implement the requirements of Sections ll.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements are the guides set forth in Section ll.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the S3me time implement the guides set forth in Section IV.A of Appendix i to assure that the I releases of radioactive materialin gaseous effluents to areas at or beyond the SITE 1 i 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

{

l of Appendix l 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 through appropriate pathways is unlikely to be substantially underestimated.

EPSPROJedembroid/12r1-4 12-39

= .

l BRAIDWOOD Revision 1.8 l Oct;ber 1995 ,

i 12.4.3 Dasa (Continued)

Bases The ODCM calculatiorial methodology and parameters' for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1 July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for lodine 131 and 133, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide l pathways to man,in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animars graze with consumption of the milk and meat by man, and (4) deposition on the pround with subsequent exposure to man.

This section applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

O EPsPROJedem/ braw 12rt-a 12-40

i l

l. BRAIDWOOD Revision 1.8~ j l October 1995 5

12.4.4 Gannous Radwasta Treatment System i

{

i

) . Onarahility Ranniramania j

i t 12.4.4.A The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS 4 HOLDUP SYSTEM shaN be OPERABLE and appropriate portions of these systems :

1 shaN 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 j 1 SITE BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) j I meet or exceed Technical Specifications and/or Code of Federal Regulation limits.

l l l Apohcabilliv: At aH times. 1 Actian*

1. With radioactive gaseous waste being discharged without treatment and in f

l excess of limits, prepare and submit to the Commission within 30 days, rursuant to Technical Specification 6.9.2, a Special Report that includes the j following information

a.- Identification of any inoperable equipment or subsystems, and the i reason for the inoperability, a

L b. Action (s) taken to restore the inoperable equipment to OPERABLE !

status, and

- I

c. Summary description of action (s) taken to prevent a recurrence, j Surveillance Ranniraments I

, i 12.4.4.1.8 Doses due to gaseous releases from each unit to areas at and beyond the SITE ;

i i BOUNDARY shall be projected at least once per 31 days in accordance with the !

i methodology and parameters in the ODCM when Gaseous Radweste Treatment ;

j Systems are not being fully utilized.

J 12.4.4.2.B The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS j HOLDUP SYSTEM shall be considered OPERABLE by meeting Section 12.4.1 and i 12.4.2 or 12.4.3.

j r

Banac 1 12.4.4.C The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION l

{

EXHAUST TREATMENT SYSTEM ensures that the system will be available for use j

j. whenever gaseous effluents require treatment prior to release to the environment.

l The requirement that the appropriate portions of this system be used when specified ..

f' i provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This section implements j the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to i 10 CFR Part 50 and the design objective given in Section ll.D of Appendix 1 to 10 J

CFR Part 50. The specified limits goveming the use of appropriate portions of the l 4 - .

Gaseous Radwaste Treatment System were specified as a suitable fraction of the '

dose design objectives set forth in Section ll.B and ll.C of Appendix 1,10 CFR Part ,

50, for gaseous effluents.

I

~

EPSPROJ4dembeaki/12ri-s 12-41 n + -

n - w m- .--

I BRAIDWOOD Rivisi:n 1.8

i October 1995 ,

12.4.4 Gaseous Radwaste Treatment System (Continued)

Bases This section applies to the release of radioactive materials in gaseous effluents from each unit at the site, When shared Raowaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit.

An estimate should be made of the contributions from each unit based on input conditions, e.2. flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For dstermining conformance to Operability Requirements, these al!ocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

O l

0 EPSPROJ4dembradn2rt-8 12 42

3 l~ BRAIDWOOD Revision 1.8 - f 1 October 1995 i 4

\ 12.4.5 Total Dona Onarahility Ramdramenta i

. _12.4.5.A The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC l

, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be j limited to less than or equal to 25 mroms to the whole body or any organ, except the

-l thyroid, which shall be limited to less than or equal to 75 mroms. ,

Anolicabihty At at times. !

i

Action' t

j 1. With the calculated doses from the release of radioactive materials in liquid or j gaseous affluents exceeding twice the limits of Sections 12.3.2,12.4.2, or 12.4.3, j calculations should be made including direct radiation contributions from the units

and from outside storage tanks to determine whether the above limits of Section ,

4 12.4.5.A have been exceeded if such is the case, prepare and submit to the !

i Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special j Report that defines the corrective action to be taken to reduce subsequent l releases to prevent recurrence of exceeding the above limits and includes the

! schedule for achieving conformance with the above limits. This Special Report, I

as defined in 10 CFR 20.2203, shall include an analysis that estimates the '

j radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel >

cycle sources, including al effluent pathways and direct radiation, for the calendar

, year that includes the release (s) covered by this report. It shall also describe

levels of radiation and concentration of radioactive materialinvolved, and the i cause of the exposure levels or concentrations. If the estimated dose (s) exceeds i the above limits, and if the release condition resulting in violation of 40 CFR Part l 190 has not already been corrected, the Special Report shah include a request for l l a variance in accordance with the provisions of 40 CFR Part 190. Submittal of l l the report is considered a timely request, and a variance is granted until staff

action on the request is complete.

Surveillance Ranniraments I

i 12.4.5.1.A Cumulative dose contributions from liquid and gaseous effluents shau be determined in

! accordance with Sections 12.3.2,12.4.2, and 12.4.3, and in accordance with the l- methodology and parameters in the ODCM. .

)

12.4.5.2.B Cumulative dose contributions from direct radiation from the units and from radwaste

! storage tanks shall be determined in accordance with the methodology and parameters !

j in the ODCM. This requirement is applicable only under conditions set forth in ACTION 1 of Section 12.4.5.A.

i 4

)

O-EPSPROAdemApeWnart.a t2 43 I

l BRAIDWOOD R; vision 1.8 l October 1995 .

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 highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose tu a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBUC from other uranium fuel cycle sources is negligible, with the exception that doss contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 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 action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Sections 12.3.1 and 12.4.1. An individualis not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

O EPsPROJbdcmbrad/12rt-8 12-44 .

d i BRAIDWOOD Revision 1.8 1

. October 1995 l 12.4.6 Dosa Umits for Members of the Public

/G I

() i 12.4.6.A Onarability Ranniramants l

l The licensee shall conduct operations such that the TEDE to individual MEMBERS I OF THE PUBLIC does not exceed 100 mrom in a year. In addition, the dose in any l unrestricted area from external sources does not exceed 2 mrom in any one hour, s l The Effluents Program shallimplement monitoring, sampling, and analysis of l radioactive liquid and gaseous effluents in eccordance with 10CFR20.1302 and with I the methodology and parameters in the ODCM.

I l Anoliemhilitv: At all times.

l l Acuan' I

1 1. If the calculated dose from the release or exposure of radiation meets or 1 exceeds the 100 mrem / year limit for the MEMBER OF THE PUBLIC, prepare

I and submit a report to the Commission in accordance with 10CFR20.2203.

l l 2. If the dose in any unrestricted area from external sources of radiation meets I or exceeds the 2 mrom in any one hour limit for the MEMBER OF THE l PUBLIC, prepare and submit a report to the Commission in accordance with 1 10CFR20.2203.

I l Surveitlanca Raouirements i

I 12.4.6.B Calculate the TEDE to individual MEMBERS OF THE PUBLIC annually to j

I determine compliance with the 100 mrem / year limit in accordance with the ODCM.

.- l in addition, evaluate and/or determine if direct radiation exposures exceed 2 mrem I in any hour in unrestricted areas.

l l Bases I

i 12.4.6.C This section applies to direct exposure of radioactive materials as well as i radioactive materials released in gaseous and liquid effluents.10CFR20.1301 sets l

forth the 100 mrem / year dose limit to members of the public; 2 mrem in any one i hour limit in the unrestricted area; and reiterates that the licensee is also required to I meet the 40CFR190 standards.10CFR20.1302 provides options to determine

, I compliance to 10CFR20.1301. Compliance to the above operability requirement is

I based on 10CFR20,40CFR190 and Braidwood Station Technical Specifications.

J l

EPSPROJedembraid/12r14 12-45

l BRAIDWOOD Revision 1.8

l October 1995 ,

12.5 RAD.lOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitorino Prooram Ocarability Recuirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified I in Table 9.1 1 of Chapter 9 and Chapter 11.

golit nhilitv: At all times.

Action

1. With the Radiological Environmental Monitoring Program not being conducted I as specified in Table 9.1 1 of Chapter 9 and Chapter 11, see Chapter 9 for I required actions.

Surveillance Raouirements 12.5.1.B The radiological environmental monitoring program samples shall be collected I pursuant to Table 9.1 1 of Chapter 9 and Chapter 11. See Chapter 9 for detailed I surveillance requirements.

Bases 12.5.1.C The Radiological Environmental Monitoring Program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation.

I See Chapter 9 for detailed information. In addition, this requirement is stated in l Technical Specification 6.8.4.f.

O EPsPROJ4dembraid/12rt 8 12-46

l BRAIDWOOD R: vision 1.8 I October 1995 (3 12.5.2 Land Use Census V Onarability Ranuirements l 12.5.2.A. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE l i BOUNDARY are identified and that modifications to the monitoring program are made if l l required by the results of the census, j

Anoticability: At all times. +

1 a &

l 1. See Section 9.2 of Chapter 9 for more details. !

Surveillance Ranuirements I 12.5.2.B See Section 9.2 of Chapter 9 for more details.

9ases l 12.5.2.C See Section 9.2 of Chapter 9 for required surveillances and Technical Specification 6.8.4.f.2 for l more bases details. I I

i 1

4 i

i EPSPROhdembraid/12rt.8 12 47 4

l BRAIDWO3D R: vision 1.8 l October 1995 ,

12.5.3 Interlaboratory Comnarison Prooram Onerability Raouirements i 12.5.3.A Participation in an Interlaboratory Comparison Program to ensure that independent checks on I the precision and accuracy of the measurement of radioactive materials in the environmental i sample matrices are performed as part of the quality assurance program for environmental l monitoring.

Anolicabilitv: At all times.

ACli2F i 1. See Section 9.2 of Chapter 9 for required actions.

Surveillance Raouirements l 12.5.3.B See Section 9.2 of Chapter 9 for surveillance requirements.

Bases l 12.5.3.C See Section 9.2 of Chapter 9 for more information. In addition, this requirement is stated in l Technical Specification 6.8.4.f.3 O

O EPSPROJedembraid/12rt 8 1248

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I BRAIDWOOD R: vision 1.8 l October 1995 i

12.6 REPORTING REQUIREMENTS .

i 12.6.1 Annual Rartiolonical Environmental Onaratino Rannrt*

i I l Onarabi!ity Raouirements 1

j l 12.6.1.A Routine Annual Radiological Environmental Operating Report covering the operation of the i Units during the previous calendar year shall be submitted prior to May 1 of each year.

l Anolicabihty At all times.

l I Actina 1

l 1. See Section 9.4 of Chapter 9 for information.

> l

_ l Surveillance Raouirements I l I 12.6.1.B See Section 9.2 of Chapter 9 for more information.

l Bases l

l 12.6.1.C See Section 9.2 of Chapter 9 for more information and Technical Specification 6.9.1.6.

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O EPSPROJedembraid/12r1-s 12-49

I BRAIDWOOD Revision 1.8 l Oct:ber 1995 ,

I 12.6 REPORTING REQUIREMENTS (Continued) l 12.6.2 Annual Radioactive Effluent Release Recort**

1 Routine Annual Radioactive Effluent Release Reports covering the operation of the unit J l during the previous calendar year operation shall be submitted prior to May 1 of the j 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 Materials in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants," Revision 1 June 1974, with data summarized on a quarterly basis following the format of Appendix 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 agent or absorbent (e.g, cement, urea formaldehyde).

The Annual Radioactive Effluent Release Reports shallinclude a list and description of

,I unplanned releases from the site to areas beyond the site boundary of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Annual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PCP, as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.6.3.

h The Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6, respectively.

- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

O EPSPROJ,tdembraid/12rt-a 12 50

l BRAIDWOOD Revision 1.8

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, October 1995 12.6 REPORTING REQUIREMENTS (Continued) 12.6.3 Offsite Dose Calculation Manual (ODCM) 12.6.3.1 The ODCM shall be approved by the Commission prior to implementation.

12.6.3.2 Licensee-initiated changes to the ODCM:

I a. Shall be documented and records of reviews performed shall be retained as I required by Specification 6.10.2. This documentation shall contain:

1. Sufficient information to support the change together with the appropiate analyses or evaluations justifying the changes (s); and

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20,160,40 CFR Part 190,10 CFR 50.36a, and Appendix i to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the Onsite Review and Investigative Function and the approval of the Plant Manager on the date specified by the Onsite Review and Investigative Function.

i 4 c. Shall be submitted to the Commission in the form of a complete legible copy l l . of the entire ODCM as part of or concurrent with the Annual Radioactive ;

i Effluent Release Report for the period of the report in which any change to l O) \ the ODCM was made effective. Each change shall be identified by markings 1

in the margin of the affected pages, clearly indicating the area of the page I that was changed, and shall indicate the date (e.g., month / year) the change i was implemented.

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EPsPROJ4dembraid/12r1-4 12 51

l BRAIDWOOD R: vision 1.8 l October 1995 . I 12.6 REPORTING REQUIREMENTS (Continued) 12.6.4 Maior Chanaes to Iinuid and Gaseous Radwasto 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 period 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 materials in liquid and gaseous affluents and/or quantity of solid waste that differ from those previously predicted in the License application 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 period prior to when the i changes are to be made, i

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.

EPSPROJedem/braldd2rt-8 12 52 I

, 6 l BRAIDWOOD Rivision 1.8

[. I October 1995 l

APPENDIX F l STATION-SPECIFIC DATA FOR BRAIDWOOD

UNITS 1 AND 2 f

TABLE OF CONTENTS

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F.1 INTRODUCTION

F-1 .

l F.2 REFERENCES F1 i

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4 l BRAIDWOOD RIvision 1.8

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APPENDIX F O

BRAIDWOOD ANNEXINDEX EAGE REYlSION RAGE REVISION l Fl 1.8 F-43 1.8 l F-li 1.8 F-44 1.8 l F lii 1.8 ' 45

/- 1.8 l F-iv 1.8 F-46 1.8 l F1 1.8 l F2 1.8 i F3 1.8 l F-4 1.8 l F5 1.8 l F6 1.8 l F7 1.8 l F8 1.8 I F9 1.8 i F 10 1.8 l F 11 1.8 l F-12 1.8 l F 13 1.8 l F-14 1.8 1 F 15 1.8 l F 16 1.8 1 F-17 1.8 1 F 18 1.8 l F 19 1.8 I F-20 1.8 i F-21 1.8 l F 22 1.8 l F-23 1.8 i F-24 1.8 l F-25 1.8 l F-26 1.8 l F-27 1.8 !

l F 28 1.8 l F-29 1.8

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l F 30 1.8 i F 31 1.8 l F 32 1.8 I F-33 1.8 l F-34 1.8 I F-35 1.8 l F 36 1.8 i F 37 1.8 i F 38 1.8 i F-39 1.8 i F-40 1.8 l F-41 1.8 g

l F-42 1.8 W

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BRAIDWOOD Revision 1.8

, 1 October 1995 APPENDIX F

-) LIST OF TABLES NUMBER . TIT.LE faraE F-1 Aquatic Environmental Dose Parameters F2 F2 Station Characteristics F3 1

F-3 Critical Ranges F4 F-4 AveraDe Wind Speeds F-5 F5 X/O and D/O Maxima At or Beyond the Unrestricted Area Boundary F-6 F Sa X/O and D/O Maxima At or Beyond the Restricted Area Boundary F7 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 Based on 1 cm Depth at the Restricted Area Boundary for Selected Nuclides F 24 Supplemental Tables O A Mixed Mode Joint Frequency Distribution Table Summaries

- 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 l

B Ground LevelJoint Frequency Distribution Table Summaries F-43 e

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

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l BRAIDWOOD R2vuion 1.8

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l October 1995 .

APPENDlX F LIST OF FIGURES gl NUMBER ILT.LE EAGE F1 Unrestricted Area Boundary F-45 F2 Restricted Area Boundary F-46 ;

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l BRAIDWOOD R; vision 1.8 -

. 1 October 1995 g APPENDIX F Q STATION-SPECIFIC DATA FOR BRAIDWOOD UNITS 1 AND 2 F.1 INTRODUCTION

(

This appendix contains data relevant to the Braidwood site. Included is a figure showing the ,

unrestricted area boundary and values of parameters used in offsite dose assessment.

FJ REFERENCES

1. SarDent & Lundy, Nuclecr Analysis and Technology Division Braidwood Calculation No.

I ATD-0149, Revisions 0,1,2 and 3,3/30/95 for Braidwood.

l 2. " Assessment of the impact of Uguid Radioactive Effluents from Braidwood Station on Proposed Public Water intakes at Wilmington, Illinois", J.C. Golden NSEP, January 1990.

3. " Verification of Environmental Parameters Used for Commonwealth Edison Company's Offsite Dose Calculations," NUS Corporation,1988.

4. " Verification of Environmental Parameters Used for Commonwealth Edison Company's Offsite Dose Calculations," NUTECH Engineers Group,1992.

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l BRAIDWOOD Revision 1.8 '

l October 1995 .

Table F-1 Aquatic Environment Dose Parameters General Information There is no irrigation ocurring on the Kankakee River downstream of the station.

Recreation includes one or more of the following: boating, waterskiing, swimming, and sport fishing.

I 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 inoestion Parameters Parameter

ygg g U", water usage, Uhr 0.042 U', fish consumption, kg/hr 2.4E-3 1/M",1/M' O.25, 1.0 F",cfs F', cis 1.85E4 5.63E3 h

t', hr" 24.0 1", hr* 3.0 Limits on Radioactivity in Unorotegd Outdoor Tanks' Outride Temporary Tank s 10 Ci' (per Technical Specification 3.11.1.4)

'The parameters are defined in Section A.2.1 of Appendix A.

t' (hr) = 24 hr (all stations) for the fish ingestion pathway

t* (hr) = 3 hr (distance nearest potable water intake, to Wilmington, is 4 river miles downstream; a flow rate of 1.4 mph is assumed) s.

See Section A.2.4 of Appendix A.

Tritium and dissolved or entrained noble gases are excluded from this limit.

O EPsPROJ4dem43raidMrt-8 F2

I l BRAIDWOOD R vision 1.8 l l October 1995

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Table F-2 Station Characteristics STATION: Braidwood LOCATION: Bracoville, 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 = .1LD _ms"*

CHARACTERISTICS OF GROUND LEVEL RELEASE

1) Release Height - O m

2) Building Factor (D)= 60.6 m' METEOROLOGICAL DATA A.220 it Tower is Located.5Z3,.m3E,.of vent stack release point Tower Data Used in Calculations

' Wind Speed Differential F,elease Point and Direction Temperature Elevated (NA) (NA)

Vent 203h 199-30 ft Ground 34 ft 199-30 ft 1

'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.

EPSPROJedembroidM-4 p.3

l BRAIDWOOD R vision 1.8 , ,

l October 1995 .)

Table F-3 l

Critical Ranges i

1 Unrestricted Area Restricted koa Nearest Dairy Farm Boundary

BorAdary . Nearest Resident

within 5 Miles

Direction (m) (m) (m) (m) l N 610 305 800 None 1 NNE 914 265 500 None i NE 702 299 1000 None l ENE 701 361 1300 None I E 1036 355 1300 None 1 ESE 2713 425 3500 None i SE 3414 448 4300 None i SSE 3444 540 5300 None l S 4633 530 6800 None l SSVV 975 540 2400 None i SW 632 632 800 None l WSW 555 555 700 None l W 518 500 600 None l WNW 503 434 600 None

! NW 495 428 600 None i NNW 510 442 600 None ;

1 l

1 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.

l* 1994 annual survey by Teledyne isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters. ,

l*

1994 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 me O

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t l BRAIDWOOD RIvision 1.8

. I October 1995 Table F 4 O

Average Wind Speeds Average Wind Speed (m/sec)*

Downwind Direction Elevated" Mirad Mode Ground Laval*

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 6.6 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 NNW 6.8 5.4 3.9 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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l BRAIDWOOD Revision 1.8 I

October 1995 Table F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary Dowwind Mixed Mode (Vent) Release tround Level Release Direction Radius x/G Radius D/0 Redlus x/0 D/0 (meters) (sec/ e*3) (meters) (1/ar**2) (meters) (sec/m**3) (1/ar**2)

~

N 610. 1.161E-06 610. 1.643E-08 610. 4.646E-06 3.355E-06 NNE 914. 5.076E-07 914. 7.023E-09 914. 1.783E-06 1.382E-06 NE 792. 2.990E-07 792. 4.274E-09 792. 1.738E-06 1.092E-08 ENE 701. 4.281E-07 701. 4.903E-09 701. 2.174E-06 1.310E-08 E 1036. 3.104E-07 1036. 3.780E-09 1036. 1.505E-06 8.551E-09 ESE 2713. 1.065E-07 2713. 1.164E-09 2713. 3.990E-07 1.949E-09 SE 3414. 7.575E-08 3414. 7.225E-10 3414. 2.757E-07 1.088E-09 ssE 3444. 6.028E-08 3444. 6.345E-10 3444. 2.165E-07 1.015E-09 s 4633. 4.068E-08 4633. 2.644E-10 4633. 1.749E-07 4.520E-10 ssu 975. 1.925E-07 975. 2.843E-09 975. 1.333E-06 6.781E-09 su 632. 5.153E-07 632. 5.408E-09 632. 3.485E-06 1.494E-08 Wsw 555. 7.821E-07 555. 4.558E-09 555. 5.471E-06 1.853E-08 W 518. 8.901E-07 518. 5.064E-09 518, 5.902E-06 1.830E-08 WWW 503. 1.0TTE-06 503. 6.100E-09 503. 6.472E-06 1.913E-08 NW 495. 1.081E-06 495. 8.650E-09 495. 5.501E-06 2.537E-06 NNW 510. 1.098E 06 510. 1.185E-08 510, 5.421E-06 3.023E-08 BRAIDWOOD SITE METEOR 0t0GICAl. DATA 1/78 - 12/87 Note:

Based on Reference 1 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B.

X/O is used for beta Gin, and inhalation dose pathways. See Sections A.1.2, A.1.3, and A.1.4.2 of Apprendix A.

D/O is used for produce and leafy vegetable pathways. Section A.1.4 of Appendix A.

The ground level release data are provided for reference purposes only. Routine dose calculations are performed using mixed mode data.

Radius is the approximate distance from the mldpoint between gaseous effluent release points to the location of highest X/O or D/O at or beyond the unrestricted area boundary (UAB).

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BRAIDWOOD Revision 1.8 l

October 1995 Table F-Se XIQ and D/Q Maxima at or Beyond the Restricted Area Boundary Downwind Mined Mode (Went) Retenee tround Level Reteese Direction Radius N/G Redius 9/G Redlue X/O D/G ,

(meters) (sec/m**3) (meters) (1/mf"2) (meters) (sec/uP*3) (1/aF*2) a 305 3.766E-06 305. 4.266E-08 305. ,

NNE 265 3.841E-06 265. 1.551E-05 9.627E-08 3.855E-06 265. 1.445E-05 9.318E-08 NE 299 1.412E-06 299. 1.473E-08 299.

ENE 361 1.265E-06 361. 8.827E-06 4.892E-08 1.138E 08 361.

E 355 1.669E-06 355. 6.706E-06 3.652E-08 1.590E-08 355.

ESE 425. 1.264E-06 425. 8.978E-06 4.611E-08 1.678E-08 425.

SE 448. 1.056E-06 448. 7.012E-06 4.132E-08 1.266E-08 448.

SSE 540. 5.596E-07 540. 6.269E-06 3.177E-08 s 8.639E-09 540. 3.673E-06 2.258E-08 530. 6.166E-07 530. 5.425E-09 ssW 540 530. 4.576E-06 1.745E-08 4.441E-07 540. 6.000E-09 540 SW 632. 5.153E-07 632. 3.423E-06 1.748E-08 5.400E-09 632.

Wsw 555. T.821E-07 555. 3.485E-06 1.494E-08 W 4.558E-09 555. 5.471E-06 1.853E 08 500. 9.431E-07 500. 5.289E-09 WNW 434. 500. 6.265E-06 1.932E-08 1.384E-06 434. 7.394E-09 434.

NW 428. 1.381E 06 428. 8.361E-06 2.399E-08 1.050E-08 428.

NNW 442. 1.388E-06 442. 7.070E*06 3.170E-08 1.444E-08 442. 6.878E-06 3.766E-08 ORAIDWOOD SITE METEOR 0 LOGICAL DATA 1/78 - 12/87 .

Note:

Based on Reference 1 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B.

The ground level release data are provided for reference purposes only. Routine dose calculations are performed using the restricted area boundary (RAB). Radius is the approximate distance from the midpoint between Gas EPSPROJ4demereid/tt-8 F-7

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October 1995 l

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Table F-7 Maximum Offsite FinMe Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Ex.t y for Kr-83m '

l l

' Dourwiruf unrestricted Mised Mode (Vent) Reteese Greisul Level Reteese Direction Aree kwui Redius V VSAR Redlue G ESAR (meters) (meters) tered/yr)/(uct/sec) (meters) (ared/yr)/(ucI/sec)

N 610. 610. 1.455E-04 1.097E- M 610.

WWE 914. 914 5.333E-04 4.021E-M 6.375E-05 4.007E-05 91%. 2.125E-04 1.602E 04 NE 792. 792. 3.020E-05 2.006E-05 792. ,

ENE 701. 2.007E-04 1.513E 04 701. 5.294E-05 3.992E-05 - 701.

E 1036. 1936.

2.575E-041.941E 04 3.703E-05 2.792E-05 1936. 1.710E-04 1.295E-04 ESE 2713, 2713. 1.129E-05 0.514E-06 2T13. 3.792E-05 2.059E 05 SE 3414. 3414. 7.009E-06 5.345E-06 3414.

SSE 3444. 2.141E-05 1.614E-05 i 3444. 6.M7E-06 4.559E-06 3444.

S 4633. 1.790E-05 1.356E-05 4633. 3.224E-06 2.431E-06 4633. ,

SSW 975. 9.260E-06 6.900E-06 975. 2.363E-05 1.702E-05 975.

sw 632. 1.444E-04 1.000E-04 632. 5.950E 05 4.4T2E-05 632. 3.694E- M 2.706E-04 Wsw 555. 555. 0.469E-05 6.300E-05

, 555. 5.942E-04 4.400E-04 W 510. 510, 9.909E-05 7.471E-05 510.

Wuu 503. 6.292E-04 4.744E 04 503. 1.205E 04 9.002E-05 503.

NW 495. 495. 6.653E-04 5.016E-04 1.242E-04 9.366E-05 495. 6.066E-04 4.574E-04 NWW 510. 510. 1.322E-04 9.969E-05 510. 6.144E-04 4.633E 04

ORAIDWOOD SITE NETEOROLOGICAL DATA 1/70 - 12/07 Note:

Based on Reference 1 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B.

Routine dose calculations are performed using mixed mode (vent) release data.

i e

EPSPROJedemereid&1-0 p.g I

!. BRAIDWOOD I Revision 1.8 October 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85m Downwind Ur estricted Mined Mode (Vent) Reteese Ground Level Welease Direction Aree Botmd Radius V VBAR Radius G GOAR (meters) (meters) (ared/yr)/(utt/see) (neters) tared /yr)/(uct/sec) m 610. 610. 9.989E*04 9.590E 04 610. 2.731E-03 2.614E-03 NME 914. 914. 4.979E-04 4.785E 04 NE 792. 914. 1.222E-03 1.171E 03 792. 3.618E-04 3.481E 04 792.

EME 701. 701, 1.1T3E-03 1.124E-03 E

4.452E-04 4.280E-04 701. 1.363E-03 1.305E-03 1036. 1036. 3.452E-04 3.320E-04 ESE 2713. 1936. 1.023E-03 9.809E-04 2T13. 1.220E-04 1.174E-04 2713.

SE 3414 3414. 3.051E 04 2.930E-04 8.179E-05 T.874E-05 3414. 1.970E-04 1.893E-04 SSE 3444, 3444.

5 6.958E-05 6.700E-05 3444. 1.634E-04 1.570E-04 4633. 4633. 4.000E-05 3.851E 05 sSW 975. 4633. 1.051E 04 1.010E-04

, 975. 2.413E-04 2.323E 04 975.

SW 632. 632. 9.063E-04 8.688E-04 5.199E-04 4.999E-04 632.

Wsw 555. 555. 1.989E-03 1.905E-03 W 6.T07E-04 6.444E-04 555 318. 518. 3.061E-03 2.929E-03 WWW 6.900E-04 6.632E-04 518. 3.081E 03 2.947E 03 503. 503. 7.511E-04 7.204E 04 NW 495. 503. 3.126E-03 2.988E 03 495. 8.396E-04 8.059E-04 NNW 510. 495. 2.915E 03 2.788E 03 510. 9.023E-04 8.662E-04 510 3.091E-03 2.958E-03 BRAIDWOOD SITE METEOROLOGICAL OATA 1/78 - 12/87 E OJ/odemkraid/fri-8

- . - . _ . - - . . . - . . - - _ . .~ . . . . - . .. . - . - . . - . - . . . . - - _ -- -_

O

~

l0 l

BRAIDWOOD-Revision 1.8 October 1995 Tob!s F-7 (Continued)

Maximum Offsite Finite Plume Gamme Dose Factors Based on 1 cm Depth at the Unrestricted Aree E_._ 'i y for Kr-85 Ocurwirul Unrestricted Mixed Mode (Vent) Reteese Grossid Levet Reteese Direction Area Sotsid Redfue V VDAR Redius e esAR (metere) (enters) (arodryr)/(uct/see) (metere) tared /yr)/(tCI/see)

N 610, 610 1.125E-05 1.000E-05 410. 2.986E 05 2.800E 05 NNE 914. 914 5.661E-06 5.474E-06 NE 792. 914. 1.344E-05 1.300E-05 792. 4.192E*06 4.053E-06 792.

ENE 701, 701. 1.311E-05 1.268E-05 E 1036 5.150E-06 4.900E-06 701. 1.486E 05 1A371-05 1936. 4.044E 06 3.911E-06 1036.

ESE 2713. 2713. 1.145E-05 1.107E-05 1 SE 3414 1.448E 06 1.420E-06 2713. 3.702E-06 3.579E-06 3414. 1.025E-06 9.911E-07 3414.

ssE 3444, 3444. 2.620E 06 2.534E 06 S 4633. 8.593E-07 8.310E-07 3444. 2.101E-06 2.032E-06 4333. 5.432E-07 5.253E-07 4433. '

ssu 975. 975. 1.699E-06 1.643E-06 SW 2.853E 06 2.759E-06 975. 1.042E 05 1.000E-05 632. 632. 6.09EE-06 5.897E-06 Wsw 555. 632. 2.227E 05 2.154E-05 555. 7.850E-06 7.599E-06 555.

W 518. 518, 3.400E 05 3.288E-05 WNW 7.924E-06 7.663E 06 518.~ 3.388E-05 3.276E-05 503. 503. 8.499E-06 8.219E-06 NW 495. 503. 3.430E-05 3.317E-05 495. 9.567E-06 9.251E-06 495.

NNW 510, 510. 3.174E-05 3.069E-05 i 1.025E-05 9.909E 06 510. 3.393E 05 3.201E-05 i

DRAIDWOOD SITE NETEOROLOGICAL DATA 1/78 - 12/87 '

t i

EFSPROJ4demeroid/fr1-3 F-11

_ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ . ~ . . . . . - _ _

l BRAIDWOGD Revision 1.8 l

October 1995 Table F-7 (Continued) l Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr47 Doienstruf Unrestricted Mixed Mode (Vent) Release Grownf Level Release Direction Aree Bound Redlus V VBAR Redius G GOAR (meters) (meters) (ared/yr)/(ucl/sec) (seters) (ared/yr)/(ucl/see)

N 610. 610. 3.313E-03 3.217E-03 610. 8.088E-03 7.853E-03 NNE 914. 914. 1.650E-03 1.602E-03 914.

792. 3.649E-03 3.543E-03 NE 792. 1.249E-03 1.213E-03 792. 3.373E-03 3.275E-03 ENE 701. 701. 1.516E-03 1.472E-03 701.

E 1036. 4.077E-03 3.958E-03 1036. 1.150E-03 1.117E-03 1036. 2.954E-03 2.868E-03 ESE 2713. 2713. 3.948E 04 3.834E 04 2713.

( SE 3414 3414. 2.559E 04 2.486E-04 3414.

8.084E-04 T.849E 04 SSE 3444, 4.691E-04 4.555E-04 3444. 2.231E-04 2.16TE-04 3444. 4.090E-04 3.979E-04 5 4633. 4633. 1.162E 04 1.129E-04 4633.

ssu 2.055E-04 1.996E-04 975. 975. 8.253E-04 8.015E-04 975.

SW 632. 2.4TTE 03 2.405E-03 632. 1.758E-03 1.707E-03 632. 5.625E-03 5.462E-03 Wsw 555. 555, 2.229E-03 2.165E-03 555.

W 518. 8.703E-03 8.450E-03 518. 2.276E-03 2.210E-03 518. 8.931E 03 8.671E-03 WNW 503. 503. 2.431E-03 2.360E-03 503. 9.052E-03 8.789E-03 NW 495. (95. 2.792E-03 2.711E-03 495. 8.646E-03 8.395E-03 NNW 510. 510. 2.982F-03 2.896E-03 510. 9.023E-03 8.76tE-03 SRAIDWUOD SITE METEOROLOGICAL DATA 1/78 - 12/87 e

Ey_.-. ;

e. . .

_ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ . . . . . _ . . _ _..____a

lO O

[RAIDWOOD O -

i l Revision 1.8 October 1995 i

Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for K '

Dourwiruf Unrestricted Mixed peodetvent) Release Direction Area Sotmd Redfus V Grenad Level Reteese WONt Redlus G GBAR (meters) (meters) (ared/yr)/(ucl/see) (meters) (ared/yr)/(uct/sec)

N 610. 610 7.997E-03 7.772E-03 610 sere 914, 914. 4.019E-03 3.906E-03 1.968E-02 1.911E-02 NE 792. 914. 8.899E-03 8.644E-03 792. 3.059E-03 2.974E-03 i i

ENE 701, 792. 8.441E-03 8.199E-03 701. 3.725E-05 3.621E-03 701.

E 1036. 1036. 1036, 9.870E-03 9.586E-03 2.878E-03 2.790E-03 ESE 2713. 2713, 1.022E-03 9.941E-M 7.396E-03 7.182E-03 SE 3414. 3414, 2713. 2.215E-03 2.152E-03 sSE 3444. 6.859E-04 6.670E 04 3414 1.396E-03 1.357E-03 3444. 5.929E-04 5.766E-04 5 4633. 3444. 1.185E-03 1.151E 03 4633. 3.301E-04 3.210E-04 4633.

ssu 9 75. 975. 6.907E-04 6.792E*04 i 2.066E-03 2.009E 03 975.

SW 632. 632. 4.309E-03 4.267E-03 6.466E-03 6.281E 03 Wsw 555. 632. 1.422E-02 1.381E-02 555. 5.589E 03 5.433E-03 W 513. 518, 555. 2.182E-02 2.119E 02 WNW 5.607E 03 5.449E-03 518.

503. 503. 5.947E-03 5.779E-03 2.205E-02 2.141E-02 (

NW 495. 503. 2.232E-02 2.167E 02 495. 6.814E-03 6.622E-03 495.

NNW 510. 510. 2.097E 02 2.036E-02 -

7.265E-05 7.060E-03 510. 2.215E 02 2.151E 02 SRA19 WOOD SITE METEOROLOGICAL DATA 1/78 - 12/07 i

l EPSPROJ/odem/breld/fr1-s F-13

l

_ _ _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .__ _ .__ -- - - - . . _ . . .._.t

l BRAIDWOOD' Revision 1.8 l ~

October 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-89 Doenwind unrestricted Mixed Mode (Vent) Reteese Ground Level Release Direction Aree Benmd Redlue V VSAR Redfue G GSAR (meters) (seters) (ared/yr)/(uCI/sec) (metere) (ared/yr)/(tCf/sec)

N 610. 610. 4.323E-03 4.199E-03 410.

NNE 914. 7.655E 03 7.435E-03 914. 1.692E-03 1.643E-03 914. 2.645E-03 2.569E-03 NE 792. 792. 1.305E-03 1.268E-03 792.

ENE 701. 2.219E-03 2.155E-03 701. 1.57?E 031.532E-03 701.

E 1036. 1036 3.016E-03 2.929E-03 9.092E 04 8.833E-04 1036. 1.387E-03 1.34?E-03 ESE 2713. 2713. 1.140E-04 1.108E 04 2713.

SE 3414 3414 9.720E-05 9.442E-05 4.392E-05 4.266E-05 3414, 2.983E-05 2.89FE-05 SSE 3444. 3444, 3.822E-05 3.712E-05 3444, 3 4633. 3.079E 05 2.990E 05 4633. 9.027E-06 8.769E-06 4433. 6.190E-06 6.021E-06 i

SSW 975. 975. 6.764E-04 4.571E-04 975.

SW 632. 1.066E 03 1.036E-03

! 632. 1.750E-03 1.700E-03 632. 3.181E 03 3.089E-03 W5W 555. 555. 2.009E-03 1.951E-03 W

555. 4.608E-03 4.475E-03 518. 518. 2.170E-03 2.100E-03 518.

WNW 503. 4.949E-03 4.007E-03 503. 2.410E-03 2.341E-03 503.

W 495. 5.589E-03 5.420E-03 495. 3.227E 03 3.134E-03 495.

l NNW 510. 7.228E-03 7.020E 03 510. 3.714E-03 3.600E-03 510. 7.735E-03 7.512E-03 BRAIDWOOD SITE METEOROLOGICAL DATA 1/78 - 12/87 E OJbdem4reid/tt-8

. . _ . . - ._ . _ . . . _ . . .__.__-...___.....____.-...__..._.--..__.m

. s

.]

O O -

i BRAIDWOOD i Revision 1.8 i October 1995 l Table F-7 (Continued) l Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Areet E .-fly for Kr-90

(

sowwind Unrestricted Mined Mode (Vent) Reteese Browul Level Reteese Ofrection Aree Bound Redius V VBAR 8edius G SsAR (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uct/sec)

N 610. 610. 8.576E-04 8.31FE-04 610 NNE 914, 914. 9.142E-04 8.863E-M 1.453E 04 1.409E-04 914 1.212E-M 1.175E-M NE 792. 792. 1.302E-M 1.263E-04 792. 1.132E-M 1.098E-06 ENE 701. 701. 1.874E-04 1.817E-M E 1036. 701. 1.634E-04 1.504E-M 1936 5.480E-05 5.316E-05 ESE 1934. 3.996E-05 3.875E-05 2713. 2713.

SE 3414. 2.691E-07 2.610E-07 2713. 1.795E-071.741E 07 3414 1.662E-06 1.612E-08 3414.

ssE 3444, 3444. 6.748E-09 6.544E-09 '

5 4633.

2.647E-08 2.568E-08 3444. 2.0334-08 1.972E-08 4633. 5.354E-10 5.193E-10 4633, tsu 975. 975. 4.411E-05 4.278E-05 3.704E-10 3.592E-10 SW 632. 975. 3.803E-05 3.688E-05 s 632. 2.254E-04 2.186E-04 632.

Wsu 555, 555. 1.900E-04 1.920E-04 W 2.200E 04 2.212E-04 555. 1.855E-04 1.799E-M 518. 518. 2.822E-04 2.730E-04 518.

WNW 503. 503. 1.673E-04 1.622E-04 NW 3.4*4E-04 3.341E-04 503. 2.412E-04 2.339E-M :

495. 495. 5.611E-04 5.442E-04 495.

NNW $10 510. 5.535E-04 5.366E M 8.014E-04 7.772E 04 510. * .221E-04 8.940E-M BRAl0WD00 SITE METEOROLO8ICAL DATA 1/78 - 12/87 I

l EPSPROJibdem/brald/trl 8 F-15

< .u_ . - . . . - - . ..m - w -- ,

i BRAIDWOOD l l Revision 1.8 l October 1995 t

i Table F-7 (Continued)

Maximum Offsite Finite Plunie Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-131m

Dounuled unrestrfeted Mixed Mode (Vent) peteese Ground Leve( Re(eese i

Direction Aree toimd Redius V VSAR Redlus G ESAR (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uCI/sec)

N 610 610.

! 1.355E-04 1.065E 04 610. 4.922E-M 3.831E 04 NME 914 914. 6.125E-05 4.839E 05 i 914. 1.988E-04 1.553E 04 NE 792. 792. 3.806E-05 3.031E-05 792.

ENE 701. 701.

1.946E-04 1.520E-04 l 5.153E-05 4.083E-05 701. 2.358E-04 1.838E-04 E 1036. 1036. 3.805E-05 3.024E-05 1036.

l EsE 2713. 2713.

1.677E-04 1.310E-04

, 1.232E 05 9.849E-06 2713. 4.412E-05 3.474E-05

' SE 3414 3414. 8.612E 06 6.883E-06 3414.

SSE 3444 3444.

3.046E-05 2.401E-05

! 6.862E-06 5.499E-06 3444. 2.387E-05 1.883E-05 5 4633 4633. 4.603E-06 3.676E-06 4633. 1.914E-05 1.510E-05 l ssW 975. 975. 2.441E-05 1.949E-05 975. 1.504E-04 1.176E-04 SW 632. 632.

l 6.073E-05 4.813E-05 632. 3.620E-04 2.819E-04 Wsw 555. 555. 8.569E-05 6.762E-05 555.

l' W 518 518. 5.701E 04 4.435E-04 9.576E 05 7.527E-05 518. 5.874E-04 4.565E-04 WNW 503. 503. 1.132E 04 8.870E-05 503.

MW 495. 495. 6.171E-04 4.790E-04 1.167E-04 9.171E-05 495. 5.515E-04 4.285E-04 NuW 510. 510. 1.244E-04 9.777E-05 510. 5.690E-04 4.432E-04 I SRAIOWOOO SITE METEOROLOGICAL DATA 1/78 - 12/87 l

E OJ.bdern. braid /frf-8

3 I ..

i BRAIDWOOD Revision 1.8

' October 1995 l Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area E:; _.y for Xe-133m l

Dounwind Unrestricted Mixed Mode (Vent) Release troised Levet Reteese Olrection Aree Bound Radius V VSAR Radius G OSAR (meters) (seters) (ared/yr)/(ucl/sec) (meters) tured/yr)/(utf/sec)

N 610. 610. 2.561E-M 2.223E-04 610.

j NNE 914. 914. 8.256E 04 7.023E-04 1.21dE-M 1.063E-04 914. 3.481E-M 2.984E-M NE 792. 792. 8.185E-05 7.244E-05 792.

ENE 701. 701.

3.399E-04 2.912E-M 1.055E-04 9.274E-05 701. 4.017E-04 3.426E-M i

E 1036. 1036. 8.032E 05 7.091E-05 1934.

Est 2713. 2713. 2.M3E-04 2.524E-M 2.749E 05 2.446E-05 2713. 8.394E-05 7.303E-05 sE 3414. 3414. 1.900E-051.497E 05 3414.

ssE 3444. 3444. 5.806E-05 5.060E-05 1.562E 05 1.3ME-05 3444. 4.609E 05 4.022E-05 s 4633. 4633. 1.005E 05 8.929E-06 4633. 3.632E-05 3.171E-05 ,

ssu 975. 975. 5.390E-05 4.7BOE-05 su 975. 2.651E-04 2.276E-M 632. 632. 1.243E-M 1.092E-04 432.

usu 555. 555. 6.091E-04 5.188E-04 1.679E M 1.446E-04 555. 9.48eE-04 8.060E-M W 518. 518. 1.799E-04 1.560E-04 518. 9.658E- M 8.185E- M WNW 503. 503. 2.046E 04 1.763E-04 503.

NW 495. 495. 1.001E-03 8.459E-M 2.185E-04 1.894E-04 495. 9.067E 04 7.683E-04 NNW 510, 510. 2.337E-M 2.027E-04 510. 9.487E-04 8.059E-04 BRAIDWOOO SITE METEOROLOSICAL DATA 1/78 - 12/87 ,

l EPSPROJ/odem/ braid /frt.8 F-17 i

i l

l BRAIDWOOD l

Revision 1.8 -

October 1995 Trble F-7 (Cont 8nued)

Maximum Offsite Finile Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Aree Boundary for Xe-133 l

l l

Downwind Unrestricted Mixed Mode (Vent) Reteese troe d Level Release Direction Area sound Redlue V VBAR Radius G GBAR (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/rr)/(uti/sec)

N 610. 610. 2.824E-04 2.536E-04 610. 9.100E-04 8.050E-04 NNE 914. 914. 1.355E-04 1.224E*04 914, NE 792. 792. 3.891E-04 3.466E-04 9.079E-05 8.273E-05 792. 3.804E-04 3.389E-04 ENE 701. 701. 1.161E-04 1.052E-04 701. 4.450E-04 3.946E-04 E 1036. 1036. 8.914E-05 8.108E-05 1036, EsE 2713. 2713. 3.295E-04 2.937E-04 3.072E-05 2.812E-05 2713. 9.583E-05 8.640E-05

! sE 3414. 3414. 2.135E-05 1.953E-05 ssE 3444, 3414. 6.660E-05 6.011E 05 i

3444. 1.740E-05 1.596E-05 3444.

! s 4633. 4633. 5.27CE-05 4.767E-05 1.130E-05 1.033E-05 4633. 4.215E-05 3.809E-05 ssu 975. 975.

sw 5.975E-05 5.460E-05 975. 2.97BE 04 2.657E-04 632. 632. 1.367E-04 1.238E-04 632. 6.726E-04 5.954E-04 Wsw 555. 555. 1.830E 04 1.649E-04 w 518.

555. 1.044E-03 9.224E-04

! 518. 1.965E-04 1.762E-04 518.

l WNW 503. 503. 1.056E-03 9.311E-04 2.231E-04 1.990E-04 503. 1.088E-03 9.570E-04 l NW 495. 495. 2.383F-04 2.135E 04 495. 9.911E-04 8.736E-04 NNW $10. 510. 2.563E-04 2.299E-04 510. 1.044E-03 9.221E-04 l BRAIDWOOD SITE METEOROLOGICAL DATA 1/78 - 12/87 EP OJ6dem,brald/Irt-s

'O 1

~ O

CRAIDWOOD I Revision 1.8 October 1995 Table F-7 (Continued) _

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-13&n f

Downsind unrestricted Mised Mode (Vent) Reteese Ground Levet Reteese Direction Aree townf Redius V WAR Redltas G GSAR (meters) (meters) (ared/yr)/(uCf/sec) (meters) (ared/yr)/tuCl/sec).

N 610. 610. 1.924E-03 1.856E-03 410.

914. 4.40 M-03 4.240E-03 NME 914. 9.071E-04 8.750E 914.

NE 792. 792.

1.913E-03 1.84M-03 6.745E-04 6.509E-04 792. 1.620E-03 1.568E-03 ENE 701. 701. 8.149E-04 7.862E-04 701.

E 1036. 1036.

2.191E-03 2.110E-03 5.710E-04 5.510E-04 1036. 1.368E 03 1.319E-03 ESE 2713. 2713. 1.557E-04 1.50M 04 2T13.

3414. 2.479E-04 2.391E 04 SE 3414. 8.843E-05 8.536E-05 3414.

SSE 3444. 1.16M-04 1.122E-04 3444. 7.741E-05 7.472E-05 3444.

5 4633. 1.062E 04 1.025E-04 4633. 3.277E-05 3.16M-05 46 3 .

SSW 975. 4.020E-05 3.879E-05 975. 4.100E-04 3.957E 04 975. 1.011E 03 9.747E-04 SW 632. 632. 8.898E-04 8.587E-04 632.

WSW 555. 2.532E-03 2.439E-03 555. 1.092E-03 1.054E-03 555.

W 518. 3.989E-05 3.842E-03 518. 1.187E-03 1.145E-03 518.

WNW 503. 4.362E-03 4.200E 03 503. 1.304E-03 1.258E-03 503.

NW 495. 495. 4.495E-03 4.327E-03 1.546E-03 1.490E-03 495. 4.695E-03 4.521E-03 NNW 510, 510. 1.673E-03 1./13E-03 510. 4.688E 03 4.514E-03 3RAIDWo0D SITE METE 000LO8tCAL DATA 1/78 - 12/87 EPSPROJ4dembraidifrt-8 p gg I

1 i BRAIDWOOD.

Revision 1.8 October 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for X i

l Dowwind tkwestricted Mixed Mode (Vent) Reteese l Olrection Aree Bound 8edius V Ground Level Release V8AR Radius G G8AR (meters) (meters) (arad/yr)/(uct/sec) (meters) (arad/yr)/(uct/sec)

N 610. 610. 1.353E-03 1.30?E-03 6'10. 3.674E-03 3.548E-03 NNE 914. 914. 6.781E-04 6.554E-04 914. 1.652E-03 1.596E-03 NE 792. 792. 4.952E-04 4.788E-04 792. 1.599E-03 1.545E-03 ENE 701. 701. 6.084E-04 5.890E-04 E 701. 1.833E-03 1.770E-03 1036. 1036. t ,753E-04 4.595E-04 EsE 1036. 1.395E 03 1.348E-03 2713. 2713. 1.700E-04 1.644E-04

. sE 2713. 4.326E-04 4.181E-04 3414. 3414. 1.160E-04 1.121E-04 ssE 3414. 2.914E-M 2.816E-04 3444. 3444. 9.782E-05 9.459E-05 s 3444. 2.37?E-04 2.297E-04 4633. 4633. 5.868E-05 5.674E-05 ssu 4633. 1.690E-04 1.641E-04 975. 975. 3.328E-04 3.217E-04 SW 975. 1.253E-03 1.211E-03 632. 632. 7.144E-04 6.906E-04 632.

Wsw 555. 555. 2.700E-03 2.615E-03 W 9.205E-04 8.896E-04 555. 4.150E-03 4.00?E 03 518. 518. 9.400E-04 9.091E-04 WNW 518. 4.151E-03 4.008E-03 503. 503. 1.018E-03 9.833E-04 i

WW 503. 4.203E-03 4.058E-03 495. 495. 1.139E-03 1.101E-03 NNW 495. 3.908E-03 3.773E-03 510. 510 1.225E-03 1.183E 03 510. 4.166E-03 4.022E-03 BRAIOWOOD SITE NETECROLOGICAL DATA 1/78 - 12/87 E OJhdembraid/Irt.8

i O ~

BRAIDWOOD

l. -

Revision 1.8 October 1995 Table F-7 (Continued) i Maximum Offs!te Finite Plume Gemme Dose Factors Based on 1 cm Depth at the Unrestricted Aree tr_. ty for X ._

l t

i esimwirul Unrestricted nined Mode (Vent) Reteese eroemd Level Reteese ,

Direction Aree Boted Radius V VBAR Radius S ORAR {

(meters) (meters) tared /yr)/ocl/sec) (meters) (ared/yr)/(uct/sec) &

N 610 610. 6.360E-04 4.154E-M 610. 1.202E-03 1.164E-03 NME 914 914. 2.57BE 04 2.494E-M !

914. 4.345E-M 4.205E-M NE 772. 792. 1.950E-04 1.88?E-M 792.

EME 701. 701. 3.640E-M 3.522E-M 2.355E-04 2.279E-M 701. 4.977E-04 4.016E-M t E 1036. 1936. 1.407E-M 1.361E-M 1036.

ESE 2713. 2713. 2.400E-M 2.322E-M 2.042E-05 1.976E-05 2T13. 1.931E-05 1.060E-05 SE 3414, 3414.

SSE 3444 8.468E-06 8.195E-06 3414. 6.393E-06 6.186E-06 i

3444. 7.3ME-06 7.146E-06 3444.

S 4633. 4633. 6.474E-06 6.26M-06 1.951E-06 1.000E-06 4433. 1.457E-06 1.410E-06 t SSW 9 75. 975. 1.030E 04 1.004E- M su 975. 1.812E-04 1.753E-M 632. 632. 2.57?E-04 2.49M-04 632.

Wsw 555. 555. 5.246E 04 5.076E-M -

2.977E-04 2.881E-M 555. 7.T71E-04 7.519E-04 W 518. 518. 3.247E-04 3.143E-M WNW 518. 8.444E-04 8.170E i 503. 503. 3.635E-04 3.517E 04 503.

NW. 495. 495. 9.371E 04 9.06?E-M 4.769E-04 4.615E-04 495. 1.167E-03 1.129E-03 NNW 510. 510. 5.441E 04 5.265E-04 510. ;

1.222E 03 1.182E 03 I

BRAIDWDOB SITE 8ETEOROLosICAL DATA 1/78 - 12/97 i

1 e

EPSPROJ4demereki/tt-4 F-21

i I BRAIDWOOD Revision 1.8 October 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Besed on 1 cm Depth at the Unrestricted Area Boundary for l

Doerwind Unrestrfeted Mixed Mode (Vent) Roteese Grouruf Level Reteese Direction Aree Octed Radius V VSAR Radius 8 GSAR (meters) (meters) (ared/yr)/(LCl/see) (meters) (ared/yr)/(uct/sec)

N 610. 610. 4.201E-03 4.079E-03 610.

l 914. 9.169E-03 8.898E-03 l NME 914. 1.982E-03 1.925E-03 914. 3.986E 03 3.869E-03 NE 792. 792. 1.5042-03 1.460E-03 792.

ENE 701. 3.379E-03 3.200E-03 701. 1.805E-03 1.753E-03 701.

1036. 4.549E-03 4.415E-03 E 1036. 1.262E-03 1.225E-03 1036, ESE 2713. 2.830E-03 2.747E-03 2T13. 3.395E-04 3.297E-04 2713.

SE 3414. 5.079E 04 4.931E-04 3414. 1.926E-04 1.871E-04 3414.

sSE 3444.

2.381E-04 2.312E-04 3444. 1.685E-04 1.636E-04 3444, 2.185E-04 2.121E-04 s 4633. 4633. 7.045E-05 6.842E-05 4633. 8.174E 05 7.937E-05 ssu 975. 975. 9.144E-04 8.800E-04 975. 2.091E-03 2.030E-03 su 632. 632. 1.991E-03 1.934E-03 632.

Wsw 555. 5.226E 03 5.072E-03 555. 2.429E-03 2.359E-03 555.

W 518. 518.

8.199E 03 7.957E-03 2.609E-03 2.534E-03 518. 8.973E-03 8.708E 03 WNW 503. 503. 2.834E-03 2.751E-03 503.

NW 495. 495. 9.247E-03 8.973E-03 3.387E-03 3.288E-03 495. 9.733E-03 9.445E-03 NNW 510. 510. 3.657E-03 3.551E-03 510. 9.712E-03 9.425E-03 ORAIDWOOD SITE METEOR 0LOGlcAL DATA 1/78 - 12/87 l

E J,bdem/ braid /frt-8

. 6 I

O BRAIDWOOD -

v' h

I Revision 1.8 October 1995 Table F-7 (Continued) 4 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Ar-41 i

Dourwind unrestricted Mined Mode (Vent) Release Gretsui Level Reteese Direction Aree Beimd Redlus V VBAR Redlus G . 00AR (meters) (met'ers) (aradryr)/(uct/sec) (meters) (ared/yr)/(uCf/sec)

N 610 610. 5.141E-03 4.977E-03 610 1.283E-02 1.242E-02 NNE 914. 914. 2.560E-03 2.405E-03 914. 5.7BOE-03 5.595E-03 NE 792. 792. 1.935E-03 1.573E-03 792. 5.421E-03 5.248E-03 ENE 701. 701. 2.357E-03 2.28 E-03 701.

1036 6.445E-05 6.239E-03 E 1036. 1.003E-03 1.746E-03 1936. 4.745E-03 4.593E-03 ESE 2713. 2713. 6.281E-M 6.000E-M 2713. 1.352E-03 1.309E-03 SE 3414. 3414. 4.120E- M 3.996E-04 3414. 8.140E-04 7.800E-04 SSE 3444. 3444. 3.500E-M 3.466E-04 3444. 7.007E-04 6.783E-04 s 4633. 4633. 1.924E-04 1.062E-M 4433. 3.770E-04 3.650E-04 SSW 975 975. 1.209E-03 1.247E 03 975. 4.067E-05 3.937E-03 SW 632. 632. 2.740E-03 2.660E-03 632. 9.104E-03 8.813E 03 usu 555. 555. 3.504E-03 3.392E-03 555.

W 518. 1.404E-02 1.359E-02 518. 3.562E-03 3.448E-03 510. 1.430E-02 1.384E-02 WNW 503. 503. 3.806E-03 3.605E-03 503. 1.449E 02 1.403E-02 NW 495. 495. 4.350E-03 4.211E-03 495.

NNW 510.

1.371E-02 1.327E-02 510. 4.647E-03 4.490E-03 510. 1.439E-02 1.393E-02 BRAIDWOOD SITE NETEOROLOGICAL DATA 1/78 - 12/87 EPSPROJ4dem%rsid/tt-8 F-23 i

.- - _ _ - . . - .. .-. - . . ~ . - - - -.

l

.g BRAIDWOOD Revision 1.8 i October 1995 l

Table F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Aree Boundary for Kr-83m l

l Downwind Restricted Mixed Mode (Vent) Reteese trotruf Level Reteese Direction Aree Sound Radius V VSAR Radius G ESAR (meters) (meters) (ared/yr)/(utt/sec) (meters) (ared/yr)/(uCI/sec)

N 305. 305. 3.994E-04 3.012E-04 NME 265. 305. 1.521E-03 1.147E-03 265. 3.083E-04 2.928E-04 265.

l NE 299. 299. 1.406E-03 1.060E-03 1.555E 04 1.173E-04 299

! ENE 361. 361. 1.372E-04 1.034E-04 9.211E-04 6.945E-04 I E 355. 361. 7.062E-04 5.325E-04 355. 1.785E-04 1.346E-04 355.

! ESE 425. 425. 9.139E-04 6.891E-04 1.505E-04 1.135E-04 425.- 7.634E-04 5.756E 04 l SE 448. 448. 1.196E-04 9.017E-05 I SSE 540. 448. 6.583E-04 4.964E-04 540. 6.996E-05 5.275E-05 540.

! s 530. 530. 4.053E-04 3.056E-04 l ssW 6.499E-05 4.900E-05 530. 4.639E-04 3.490E-04 540. 540. 5.532E-05 4.171E-05 sw 540 3.829E-04 2.887E-04

! 632. 632. 5.930E-05 4.472E-05 Wsw 555. 432. 3.694E-04 2.786E-04 I 555. 8.469E-05 6.386E-05 555.

W 50@. 500. 5.942E-04 4.480E-04 WNW 1.045E-04 7.876E-05 500. 6.646E 04 5.011E-04 434. 434. 1.497E-04 1.129E 04 NW 428. 434. 8.320E-04 6.273E-04 428. 1.537E-04 1.159E-04 428.

NNW 442. 442. 1.633E-04 1.231E-04 7.562E-04 5.702E-04 442. 7.667E-04 5.781E-04 BRAIDWOOD SITE METEORfADGICAL DATA 1/78 - 12/87 l

f i

1 Note:

Based on Reference 1 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B.

Routine dose calculations are performed using mixed mode release data.

EP OJAodembraid/fri-8

O

~

l I CRAIDWOOD Revision 1.8 October 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gemme Dose Factors Based on 1 cm Depth atl_., _.

the Restricted Area C; for Kr-85m Oceewind Restricted Mimed Mode (Vent) Release Gronaut Level Release Direction Aree Bound Redius V VSAR Radius a GBAR (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uct/sec) ,

M 305. ;

305. 2.263E-03 2.169E-03

~

NME 265. 305. 6.552E-03 6.259E-03 265. 2.144E-03 2.056E-03 NE 299. 299. 265. 5.920E 03 5.662E-03 EWE 361. 1.094E-03 1.050E-03 299.

361. 9.475E-M 9.09?E-M 4.111E-05 3.92EE-03 '

E 355. 355. 361. 3.165E-03 3.025E-03 ESE 425.

1.197E-03 1.149E-03 355.

425. 4.072E-03 3.091E SE 448. 1.073E-031.031E 03 425.

448. 9.074E-04 8.718E 04 3.504E 03 3.42?E-03 SSE 540. 448. 3.167E 03 3.029E 03 540. 4.060E-04 5.836E-M 540 S 530. 2.006E 03 1.997E-03

' 530. 5.227E-04 5.023E- M 530.

, SW 540, 540. 2.351E-03 2.249E-03 SW 4.797E 04 4.613E-04 540.

i 632. 632. 5.199E-04 4.999E 04 1.999E-03 1.913E-03 Wsw 555. 632. 1.909E-03 1.905E-03 :

555. 6.707E-04 6.444E-04 555.

W 500. 500. 3.061E 03 2.929E 03 unW 7.204E-04 6.915E-04 500. 3.224E-05 3.083E 03 434. 434. 8.947E-04 8.578E-04 w 428. 428.

434. 3.764E-03 3.597E-03 NuW 9.954E 04 9.552E-04 428.

442. 442, 3.505E-05 3.351E-03 1.060E-03 1.025E-03 442. 3.712E-03 3.551E-03 I BRAIDucop SITE METEOROLOGICAL DATA 1/78 - 12/87 l

l l

i 4

j EPSPROAdembroid41-0 F-25 m___. _.___u_ __m m___m ._ _ ___.._.._m__..____.--___ ____._..___m_-.._____..__.mm__---__- _ _ _ - + ___ . _ _ _ _ _ _ 4-9_ _ -__-_____.___ _ -- _ . - - - -- _+ +-

i l

i

' l- BRAIDWOOD . Revision 1.8 l October 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-85

' Oeunwind Restricted Mixed mode (vent) Reteese Gro m d Level Reteese Direction Aree Sound Radius V VSAR Redlue G $84R (meters) (seters) tered/yr)/ttCl/sec) (meters) (ared/yr)/tucl/sec) u 305. 305. 2.521E-05 2.43?E-05 305. 7.053E-05 6.820E-05 NNE 265. 265. 2.389E-05 2.310E-05 265.

299. 6.351E-05 6.141E-05 NE 299. 1.248E-05 1.207E-05 299. 4.443E-05 4.296E-05 EWE 361. 361. 1.083E-05 1.047E-05 361.

355. 3.404E-05 3.292E-05 E 355. 1.366E-05 1.320E-05 355.

Est 425. 4.396E-05 4.251E-05 425. 1.220E-05 1.180E-05 425.

SE 448. 448. 3.889E-05 3.760E-05 1.042E-05 1.000E-05 448. 3.470E-05 3.355E-05

$5E 540. 540. 7.029E-06 6.79?E-06 540.

5 530. 530. 2.290E-05 2.215E-05 6.111E-06 5.909E-06 530. 2.632E-05 2.545E-05

' ssu 540. 540. 5.594E-06 5.409E-06 540. 2.217E-05 2.144E-05 SW 632, 632. 6.090E-06 5.897E-06 632. 2.227E 05 2.154E-05 WSW $55. 555. 7.858E-06 7.599E-06 555.

W 500. 500. 3.400E-05 3.288E-05 8.255E-06 7.983E-06 500. 3.541E-05 3.424E-05 WNW 434. 434. 1.009E-05 9.757E-06 434.

MW 428. 428. 4.111E-05 3.976E-95 1.131E-05 1.093E-05 428. 3.802E-05 3.677E-05 WWW 442. 442. 1.209E-05 1.169E 05 442. 4.056E-05 3.922E-05 BRAIDWOOD SITE METEOROLOGICAL D4TA 1/78 - 12/87 i

2 o

.i t

E J4dem% raid /Irt-8

~ _ . _ . _ _

O lob BRAIDWOOD i Revision 1.8 October 1995 Table F-7a (Contktuod)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Aree Ox. My for K -

i Downuirus Restricted Mixed Mode (vent) Re* ese tro md Levet Reteese Direction Aree So m d Radius V AAR Redius 0 00AR-(meters) (amters) (mrad /yr)/(iKf/sec) (meters) (ared/yr)/(uct/sec)

M 305. 305.

265, T.400E-03 7.264E-03 305.

NNE 265. 1.9T2E 02 1.915E-02 t 7.100E-03 4.095E-03 265.

NE 299 299. 3.700E-03 3.671E 03 1.002E-02 1.749E-02 ENE 361 299. 1.225E-02 1.109E-02

. 361. 3.246E-03 3.152E-03 341.

i E 355, 355. 9.572E-03 9.294E-03 4.060E-03 3.943E 03 355.

ESE 425. 425. 1.220E-02 1.185E-02 3.644E-05 3.539E-03 425.

SE 440 440. 3.001E-03 2.992E-03 1.060E-02 1.037E 02 SSE 540 440. 9.262E 03 0.992E 03 540. 2.111E-03 2.050E-03 540.

s 530 530. 6.149E 03 5.971E 03 1.762E-03 1.711E-03 530.

sSW 540 540. 6.549E-03 6.359E 03 sw 1.664E-03 1.616E 03 540.

632. 632. 1.750E-03 1.707E-03 5.727E-03 5.561E-03 i Wsw 555, 555, 632. 5.625E 03 5.442E-03 W 2.229E-03 2.165E-03 555.

500. 500. 2.375E-03 2.30aE-03 0.703E-03 0.450E-03 i WWW 500 9.363E 03 9.090E-03 434 434, 2.90M-03 2.010E-03 NW 420. 434. 1.090E-02 1.06dE-02 420. 3.315E 03 3.219E-03 420 NNW 442. 442, 1.044E-02 1.014E-02 3.533E 03 3.431E-03 442, 1.090E-02 1.050E-02 -

ORA 10 WOOD SITE METEOROLOGICAL DATA 1/70 - 12/07 EPSPRO#adembraid41-0 F-27 e

I I BRAIDWOOD Revision 1.8 October 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Bounda Downwind testricted Mixed Mode (Vent) Reteese Sreuul Levet Release Direction Aree Sound Redlue V VSAR Redlue (meters) G G8AR

r. meters) (ared/yr)/(ucl/sec) (meters) (ared/yr)/(uCI/sec)

N 305 305. 1.790E-02 1.739E-02 305 4.712E-02 4.574E-02 NNE 265. 265 1.698E-02 1.650E-02 265 4.272E-02 4.146E-02 NE 299. 299. 9.121E-03 8.865E-03 299 EWE 361. 361 2.947E-02 2.861E-02 7.868E-03 7.64?E 03 361 2.281E-02 2.214E-02 E 355 355. 9.873E-03 9.595E-03 355 2.928E-02 2.842E-02 ESE 425. 425. 8.818E-03 8.571E-03 425 SE 448 448. 2.578E-02 2.503E-02 7.516E-03 7.306E-03 448, SSE 540 540 2.27tE-02 2.205E-02 5 5.155E-03 5.012E-03 540 1.505E-02 1.462E-02 530. 530, 4.382E-03 4.260E-03 530 SSW 540. 540. 1.666E-02 1.618E-02 SW 4.092E 03 3.978E-03 540 1.429E-02 1.388E-02 632. 632. 4.389E 03 4.267E-03 632 WSW 555. 555. 1.422E-02 1.381E-02 W 5.589E-03 5.433E 03 555 2.182E-02 2.119E 02 500. 500. 5.844E 03 5.680E-03 WNW 500 2.300E-02 2.241E-02 434. 434. 7.074E 03 6.873E-03 434 NW 428. 428. 2.690E-02 2.6122-02 unu 8.064E-03 7.837E 03 428, 2.520E-02 2.447EcS2 442. 442. 8.580E-03 8.338E-03 442. 2.660E 02 2.583E-02 8RAl0 WOOD SITE PETEOR0 LOGICAL DATA 1/78 - 12/87 t

I EP OJMdem&reid/Ir1-8

. _ _ . _ _ _ _ _ . - . ----- - -- - - - - - - - - - - - - ~ - '

m o U l

i ERAIDWOOD Revision 1.8 October 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 ent Depth at the Restricted Aree 2;;z1_i for Kr-89 Downstrui Restricted Mined Mode (vent) Reteese Ortaruf Level Reteeee Direction Aree Gewuf Radius V VSAR Redius 0 004R (meters) (meters) (arad/yr)/(uct/sec) (meters) (arad/yr)/(uct/sec)

N 305. 305.

WWE 1.243E-02 1.200E-02 305 2.61M 02 2.530E-02 265. 265. 1.213E-02 1.170E-02 265 NE 299. 299. 2.655E-02 2.579E 02 6.070E-03 5.096E-03 299 1.430E-02 1.397E-02 ENE 361. 361. 4.630E-03 4.50GE-03 E 355. 341. 1.132E-02 1.099E-02 355. 5.715E-03 5.551E-05 355 EsE 425. 425. 1.360E-02 1.321E-02 5.133E 03 4.90GE-03 425. 1.004E-02 1.053E-02 SE 448. 440. 4.043E-03 3.927E-05 440 SSE 540. 540. 0.014E 03 7.704E-03 t 2.636E-03 2.561E-03 540 5.13?E-03 4.990E-03

. 530. 530. 1.936E-03 1.000E-03 530 ssW 540. 340. 4.055E-03 3.930E-03 su 1.970E 03 1.914E-03 540. 4.039E-03 3.922E-03 632. 632. 1.750E 03 1.700E-05 usW 555. 632. 3.181E-03 3.009E-03 555. 2.009E 03 1.951E 03 555 w 500. 4.600E-03 4.475E-03 - t' 500. 2.313E 03 2.24?E 03 500.

WWW 434. 434, 5.30$E-03 5.230E-03 3.129E-03 3.040E-03 434 "

WW 420. 420, T.749E 03 7.526E-04 NNW 4.110E 03 3.993E-03 420.- 9.703E-03 9.424E-03 442. 442. 4.6 TIE-G3 4.537E-03 442. 1.017E-02 9.070E-03 SRAIDWOCO SITE NETEOROLOGICAL DATA 1/70 - 12/0T '

!' i l

v EPSPROJbdembroid/tr1-0 F-29

- ~ . - -r. - , . , . ,. , .e, , - .-, .- ,e . . , _ . , , . .y--,. .,-.

l CRAIDWOOD l 1 Revision 1.8 -

October 1995 l

l l

Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-90 Dounwiral Restricted Mixed Nede(Vertt) Release Browul Level Reteese Direction Aree townf Redlue V VSAR Redius G SBAR (meters) (meters) (ered/yr)/(ucl/sec) (meters) (ared/yr)/(LCf/sec) s 305. 305. 5.688E-03 5.515E+03 305.

NNE 265. 265. 8.218E-03 7.966E-03 6.051E-03 5.868E*03 265.

NE 299. 299. 9.375E-03 9.087E-03 2.447E-03 2.374E-03 299. 3.836E-03 3.719E-03 ENE 361. 361. 1.410E-03 1.367E 03 361. 1.941E-03 1.882E-03 E 355. 355. 1.896E-03 1.839E-03 355,

! ESE 425. 425. 2.575E-03 2.496E-03 1.516E-03 1.470E-03 425.

SE 448. 448. 1.818E-03 1.762E-03 1.032E 03 1.001E-03 448.

SSE 540. 540. 5.186E-04 5.030E-04 1.147E-03 1.112E-03 s 540. 6.013E-04 5.830E-04 530. 530. 3.564E-04 3.457E-04 530. 4.307E-04 4.176E-04 SSW 540. 540. 3.743E-04 3.630E-04 540 su 632. 432. 4.345E-04 4.213E-04 2.254E-04 2.186E-M 632. 1.980E-04 1.920E 04 WsW 555. 555. 2.280E-04 2.212E-04 i

W 555. 1.855E 04 1.799E 04 500.

500. 3.175E-04 3.080E-04 500.

WNW 434, 434 1.971E-04 1.911E 04 5.483E-04 5.319E-04 434 w 428 428. 8.796E 04 8.532E-04 428.

4.559E 04 4.420E 04 >

NW 442. 442. 9.766E-04 9.468E 04 1.222E-03 1.185E-03 442. 1.523E-031.477E 03 sRAIDWoop SITE METEOROLOGICAL DATA 1/78 - 12/87 g F EP OJ/odemhraki/frt-8 -

_ ~ _ _ .._ -

___.m__ _ _ - _ _ _ _ _ .

r l

(~ -

\

BRAIDWOOD O -

i Revision 1.8

-+

October 1995 Table F-7a (Continued)

84aximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted i Area 0-sit for Xe-131m pounwind Reetricted Mixed Mode (Vent) Release Direction Aree Boted Radius V Grened Level Reteese VB4R Redium 8 SSAR (metere) (meters) Cared /yr)/tuti/sec) (meters) (ared/yr)/(uct/sec)

N 305. 305. 3.585E-04 2.001E 04 305.

NME 265. 265. 1.342E 03 1.040E-03 3.471E-M 2.710E-M 265.

NE 299 299. 1.442E-04 1.135E-04 1.225E-03 9.489E 04 ENE 361 299. 8.221E-04 6.37?E 361. 1.274E-M 1.002E-04 361.

E 355, 355. 6.227E-M 4.832E-04 1.664E 04 1.307E-04 355, ESE 425. 425. 1.40$E-04 1.100E-04 8.136E-04 4.311E-04 SE 448 425. 6.08?E-04 5.349E-04 448. 1.152E-04 9.000E-05 448.

SSE 540. 540. 6.093E-04 4.733E-04 5 6.790E 05 5.395E-05 540.

530. 530. 3.7T2E-04 2.936E-04 ssu 6.550E+05 5.172E-05 530.

540 540. 4.533E-04 3.523E-04 sw 5.419E-05 4.299E-05 540.

632. 632. 6.073E-05 4.813E-05 3.656E-04 2.846E-04 Wst 555. 632. 3.620E-04 2.819E 04 555. 5.569E-05 6.762E-05 555.

W 500. 500. 5.701E-04 4.435E-04 434, 1.006E-04 7.904E 05 500.

WNW 434. 1.391E-04 1.000E-M 6.184E-04 4.805E 04 NW 428. 434. 7.616E-04 5.90?E-04 428. 1.429E 04 1.121E 428, '

NNW 442. 442. 1.521E-04 1.194E-04 6.807E 04 5.285E-04' .

442. 7.027E 04 5.461E-04 BRAIDWOOD SITE METEOROLOGICAL DATA 1/78 - 12/87 i

EPSPROJ4dembreld41-0 F-31 o

I CRAIDWOOD I - Revision 1.8 October 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Bo;Eip for Xe-133m Downwind Restricted Mixed Mode (Vent) Reteese tround Level Reteese Olrection Aree Beimd Redius V VBAR Redius G GSAR (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(ucl/see)

N 305. 305. 6.300E-04 5.411E-M 305, NNE 265. 265. 2.135E 03 1.798E 03 6.053E-04 5.184E-04 265.

NE 299. 299. 2.759E-04 2.399E-04 1.940E*03 1.632E-03 ENE 361. 299. 1.321E-03 1.115E-03 361. 2.417E-04 2.099E 04 361.

E 355. 355. 3.110E 04 2.695E 04 1.005E-03 8.488E-04 ESE 425. 355. 1.307E-03 1.103E-03 425. 2.701E-04 2.350E-04 425.

l SE 448. 448. 2.251E 04 1.964E-04 1.125E-03 9.516E-04 SSE 540. 448. 9.971E-04 8.442E-04 540. 1.413E-04 1.245E-04 540.

5 530. 530, 1.293E-04 1.131E-04 6.325E-04 5.379E-04 SSW 540. 530. 7.46tE-04 6.326E-04 540. 1.123E-04 9.889E 05 540.

SW 632, 632. 6.124E-04 5.209E-04 1.243E-04 1.092E-04 632.

WSW 555. 555. 6.091E-04 5.186E 04 1.679E-04 1.466E-04 555.

W 500. 500. 1.883E 04 1.632E-04 9.488E-04 8.060E-04 WNW 434. 500. 1.014E 03 8.589E-04 434. 2.477E 04 2.129E-04 434.

NW 428. 428. 2.634E-04 2.277E-04 1.222E-03 1.031E-03 NNW 442. 442, 428. 1.107E-03 9.360E 04 -

2.813E-04 2.434E-04 442.

l 1.157E-03 9.803E-04 '

SRA10 WOOD SITE METEOROLOGICAL DAT41/78 - 12/87 6

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4 E OJedembraM/tr1-8

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l BRAIDWOOD Revision 1.8 October 1995 Table F-7a (Conthwed) i Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area E-;-ea-Ly for Xe-13 l

Downsind Restrleted Nimed Mode (Vent) Reteese Ground Level Reteese Direction Aree Bowed Redius V VBAR Radius G EBAR (meters) (seters) (ared/yr)/(ucl/sec) (meters) (ared/yr)/(uCI/sec)

N 305 305 NME 265 6.810E-M 6.050E-M 305 2.299E-03 2.013E-03 265 6.509E-M 5.774E-M NE 299. 265 2.084E-03 1.823E-03 299. 2.904E-M 2.679E-M 299 ENE 361. 361. 2.612E-M 2.343E 04 1.431E-03 1.256E-03 E 355. 341. 1.090E-03 9.571E-M 355. 3.363E-04 3.011E-M 355.

l ESE 425. 425. 1.414E-03 1.241E-03 2.954E M 2.656E-04 425, SE 448. 448, 2.460E-M 2.216E-M 1.226E-03 1.079E 03 i ssE 540. 540 448. 1.000E-03 9.581E-M s 530, 1.555E-M 1.411E-M 540 6.963E-04 6.158E M t

530. 1.400E-M 1.270E-M 530 ssu 540. 540 8.174E*M 7.209E 04 su 1.231E-M 1.117E-M 540 632. 632. 1.367E-04 1.230E-04 6.754E-M 5.974E-M W5W $55. 632. 6.726E-M 3.954E- M 555 1.850E-M 1.649E-M '

W 500. 555. 1.044E-03 9.224E-M 500. 2.055E-M 1.M2E-M 500.

tant 434. 434 1.100E-03 9.759E- M W 2.689E-M 2.394E-M 434. !

428. 428 2.860E-M 2.557E-M 1.323E-03 1.160E-03 NNW 442, 420. 1.2ME-03 1.059E-03 442. 3.0 TIE-M 2.749E-M 442. '

1.266E-03 1.116E-03 i

BRAIDWOOD SITE METEOROLOGICAL DATA 1/F8

12/87 [

i t

6 t

1 EPSPROJ4dembroid/frt-8 F-33

- _ _ _ . . _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _____ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . ~ _ . __- .

I CitAIDWOOD Revision 1.8 I

October 1995 Table F.7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135m Downwind Restricted Mined Mode (Vent) Release Greisid Level Reteeee Direction Aree Botsid Radius V VSAR Radius G GSAR (meters) (meters) (mrad /yr)/(utf/sec) (meters) (ared/yr)/(W I/sec)

N 305. 305. 4.59M-03 4.429E-03 305.

DNE 265, 265. 1.180E 02 1.135E-02 4.387E-03 4.227E-03 265. 1.125E-02 1.082E-02 NE 299. 299. 2.254E-03 2.174E-03 299.

ENE 361. 361. 7.028E-03 6.764E-03 1.883E-03 1.816E-03 361. 5.738E-03 5.523E-03 E 355. 355. 2.326E-03 2.242E-03 355.

ESE 425. 425. 7.076E-03 6.811E-03 2.121E-03 2.046E-03 425. 6.001E-03 5.778E-03 SE 448. 448. 1.723E-03 1.662E*03 448.

SSE 540. 540. 4.819E-03 4.640E-03 1.13E-03 1.137E-03 540. 3.220E-03 3.101E-03 s 530. 530. 9.052E-04 8.734E-04 ssu 530. 2.852E-03 2.747E-03 540. 540, 9.038E-04 8.720E-04 540.

SW 632. 632. 2.739E-03 2.638E-03 8.898E-04 8.58?E-04 632. 2.532E-03 2.439E-03 Wsw 555. 555. 1.092E-03 1.054E-03 555. 3.989E-03 3.842E-03 W 500. 500. 1.246E-03 1.202E-03 500. 4.61?E 03 4.446E-03 WNW 434. 434. 1.593E-03 1.536E-03 434.

W 428. 428. 5.652E 03 5.441E-03 1.869E-03 1.802E-03 428. 5.820E-03 5.603E-03 NW 442. 442. 2.013E-03 1.940E-03 442. 5.812E-03 5.596E-03 E2AIDWOOD SITE METEOROLOGICAL DATA 1/78 - 12/87 h

I EP OJ4dem/ braid /frt 8

1 O O CRAIDWOOD-O -

I Flevision 1.8 October 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area 35E= t i for Xe-135 Downwind Restricted Mixed Mode (Vent) Release Growed Levet Reteese Direction Aree Bound Redius V VSAR Redius G GSAR (meters) (meters) (ared/yr)/(uCI/sec) (meters) (ered/yr)/(uci/sec)

N 305. 3tc. 3.039E-03 2.936E-03 305. 8.709E-03 3.406E-03 NME 265. 265. 2.800E-03 2.781E-03 265.

299. 7.856E-03 7.583E-03 NE 299. 1.481E-03 1.431E-03 299.

ENE 361. 361. 5.482E-03 5.292E-03 ,

1.204E-03 1.241E-03 361. 4.211E-03 4.065E-03 E 355. 355. 1.621E-03 1.56?E-03 355.

EsE 425. 425. 5.425E-03 5.237E-03 1.455E-03 1.406E-03 425. 4.7ME-03 4.629E-03 SE 448. 448. 1.235E-03 1.1ME-03 448.

ssE 540. 540. 4.257E-03 4.110E-03 8.205E-04 8.000E- M 540. 2.811E-03 2.714E-03 S 530. 530. 7.163E-04 6.923E-04 530.

4 ssu 540. 3.19?E-03 3.00?E-03 540. 6.561E-04 6.342E-04 540. 2.709E-03 2.615E-03 sw 632. 632. 7.144E-04 6.906E-04 632.

Wsw 555. 2.700E-03 2.615E-03 555. 9.205E-04 8.896E-J4 555.

u 500. 4.150E 03 4.007E-03 500. 9.804E-04 9.473E-04 500.

WNW 434. 434.

4.340E-03 4.190E-03 1.210E-03 1.168E-03 434. 5.044E-03 4.869E-03 NW 428. 428. 1.348E-03 1.302E-03 428.

NNW 442. 442. 4.686E-03 4.524E-03 1.446E-03 1.397E-03 442. 4.987E-03 4.815E-03 BRAlcuo0D SITE METEOROLOGICAL DAT.11/78 - 12/87 EPSPROJ4dembraM/ti-8 F-35

_ _ _ _ , ,__ _ _ _ . _ _ _ _ _ _ - - - - - - " ^ - --

i CRAIDWOOD l Revision 1.8 October 1995 Table F-7a (Contn' sued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-137 Downsind Restricted Mlaed Mode (Vent) Reteese tromd Levet telease Direction Area Bomd Redius V VBAR Redlus G GBAR (meters) (meters) (ared/yr)/(ucl/sec) (meters) (arad/yr)/(uCI/sec)

N 305. 305. 1.764E-03 1.707E .*2 305. 3.915E-03 3.788E-03 NNE 265. 265. 1.712E-03 1.657E-03 265. 3.949E-03 3.821E 03 NE 299. 299. 8.519E-04 8.244E 04 299. 2.178E-03 2.108E-03 ENE 361. 361. 6.624E-04 6.410E-04 361. 1.748E-03 1.692E-03 E 355. 355. 8.157E-04 7.8931-04 355. 2.100E-03 2.032E-03 ESE 425. 425. 7.381E-04 7.142E-04 425. 1.690E-03 1.636E-03 SE 448. 448. 5.802E-04 5.615E-04 448. 1.259E-03 1.219E-03 sSE 540. 540. 3.822E-04 3.699E-04 540. 8.154E-04 7.890E-04 s 530. 530. 2.803E-04 2.713E-04 530.

540, 6.471E-64 e.1415-04 ssu 540. 2.864E-04 2.772E-04 540. 6.459E 04 6.250E-M sw 632. 632. 2.577E-04 2.493E-04 632. 5.246E-04 5.076E-04 WSW 555, 555. 2.97?E-04 2.881E-04 555. 7.771E-04 7.519E-04 W 500. 500. 3.4535-04 3.341E-04 500. 9.141E-04 8.844E-04 WNW 434. 434. 4.671E-04 4.520E-04 434. 1.275E-03 1.234E-03 NW 428. 428. 6.017E-04 5.823E-04 428, 1.543E-03 1.493E-03 NNW 442. 442. 6.784E-04 6.565E-04 442. 1.588E-03 1.537E4.3 BRAIDW0to SITE METEOROLOGICAL DATA 1/78 - 12/87 e

EP OJ/odembraid/Ir1-8

O c O -

I .

I BRAIDWOOD Revision 1.8 October 1995 Table F-7e (Continued)

Membnum Offsite Finite Plume Gemme Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-138 l

l

\

j Dowulrui testricted Mined Mode (vent) Reteeee grownf Levet Reteeee

Direction Aree Gewuf Radius V VOAR Redius S SOAR i

i (meters) (eeters) (aredlyr)/tutI/sec) (meters) (ared/yr)/(uct/sec) u 3e5. 305.

aut 1.001E-02 9.714E-03 305. 2.457E-02 2.304E-02 265. 265. 9.553E-03 9.273E-03 265.

NE 299. 299. 2.347E-02 2.270E-02 5.016E 03 4.070E-03 299. 1.459E-02 1.416E-02 EWE 361. 361. 4.169E-03 4.040E-03 361.

E 355. 355, 1.195E-02 1.140E-02 5.137F 03 4.900E-03 355. 1.471E-02 1.427E-02 Est 425. 425, 4.679E 03 4.543E-03 425. 1.247E 02 1.210E-02 l

SE 440. 448. 3.027E 03 3.716E-03 440.

BSE 540. 540. 9.902E-03 9.687E-03 l

' 2 630E-03 2.554E-03 540. 6.694E 03 6.497E-03 s 530. 530. 2.013E 03 1.964E-03 530. 5.057E-03 5.684E-03 ssu 540. 540. 2.049E 03 1.962E-03 540. 5.661E 03 5.495E-03 i sW 632. 632. 1.99W-03 1.934E-03 432.

WsW 555. 555. 5.226E 03 5.072E-03 2.429 i-03 2.359E-03 555. 9.199E 03 7.957E-03 W 500. 500.

l 2.T391-03 2.659E-03 500. 9.502E-03 9.221E-03 l falW 434. 434.

' 3.459E-03 3.358E-03 434. 1.164E-02 1.130E-02

~

nu 420. 420.

uMW 4.093E 03 3.974E-05 428. 1.207E-02 1.172E-02 442. 442. 4.399E-03 4.271E-03 442. 1.204E 02 1.169E*02 l ORAIDWOOD SITE METEOROLottcAL DATA 1/70 - 12/07 i

I c

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EPSPROAdemerald/t1-0 F-37 1 ,

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BRAIDWOOD-I Revision 1.8 October 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based ors 1 cm Depth at the Restricted Area Doundary for Ar-41 Detawind aestricted Mixed Mode (Vent) Reteese Direction Aree townf Radius V treemd Levet Reteese VSAR Redius G star (meters) toeters) tared /yr)/(uct/sec) (meters) (ared/yr)/(uct/sec)

N 305 305. 1.160E 02 1.122E 02 305 3.106E 02 3.006E-02 NNE 265. 265 1.101E 02 1.065E-02 265 NE 299 299. 2.826E-02 2.736E-02 5.833E-03 5.646E-03 299 1.936E-02 1.874E-02 ENE 361. 361. 5.023E 03 4.863E-03 361 E 355. 355. 1.505E-02 1.456E-02 ESE 6.295E-03 6.094E 03 355. 1.925E-02 1.864E-02 425 425. 5.640E-03 5.459E-03 425. 1.689E 02 1.635E-02 SE 448. 448. 4.783E 03 4.630E-03 448.

ssE 540 540 1.477E-02 1.430E-02 s

3.262E 03 3.157E-03 540. 9.781E-03 9.46EE-03 530 530. 2.756E-03 2.667E-03 ssu 530. 1.066E-02 1.032E-02 540. 540. 2.580E 03 2.497E-03 540.

su 632. 632. 9.211E-03 8.917E-33 Wsu 2.748E 03 2.660E-03 632. 9.104E-03 8.813E-03 555. 555. 3.504E-03 3.392E 03 555.

W 500 500 1.404E-02 1.359E-02 3.715E-03 3.596E-03 500. 1.498E-02 1.450E-02 WNW 434 434 4.539E-03 4.393E-03 434, NW 428 428. 1.753E-02 1.697E 02 NW 5.159E-03 4.994E-03 428. 1.652E-02 1.599E-02 442 442. 5.499E-03 5.323E-03 442. 1.734E-02 1.679E-02 DRAIDWOOD SITE METEOROLOGICAL DATA 1/78 - 12/87 i

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