ML20035A654

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Rev 0.K to ODCM, Chapter 10 & App F
ML20035A654
Person / Time
Site: Braidwood  
Issue date: 01/31/1993
From:
COMMONWEALTH EDISON CO.
To:
References
PROC-930131-03, NUDOCS 9303290122
Download: ML20035A654 (53)
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Text

,

1 l

February 24, 1993 l

i Attached are the recent revisions to the Offsite Dose Calculation Manual's (ODCM) Chapter 10 and Appendix F for Braidwood Station.

Please complete the following manual update:

REMOVE INSERT I

Braidwood Station Annex Braidwood Station Annex Entire Chapter 10.

Entire Chapter 10

p. 10-1 to 10-111, Revision 0.K Jan. 1993 10-1 to 10-18
p. 10-1 to 10-v, 10-1 to 10-19 Braidwood Station Annex Braidwood Station Annex Entire Appendix F Entire Appendix F
p. F-i to F-iv, Includes Rev. 0.K F-1 to F-22
p. F-1 to F-iv F-1 to F-22 i

Please sign and date this control sheet and return to:

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correct and you have updated your manual.

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PATE.L DIRECTOR Of NUC. REACT 06 REGULATION j

U.

S.

huC. REGULAluRY CCMMISSION MAIL STATION P1-137 Date WASH 1h610h DC 20555 k(

9303290122 930131 I

PDR ADOCK 05000456 l

P PDR I

"[

i 8

ZEMERPLN/347/18 l

BRAIDWOOD REVISION 0.K JANUARY 1993

'\\

BRAIDWOOD ANNEX INDEX PAGE REVISION CHAPTER 10 10-1 0.K 10-ii 0.K 10-iii 0.K 10-iv 0.K 10-v 0.K 10-1 0.K 10-2 0.K 10-3 0.K 10-4 0.K 10-5 0.K 10-6 0.K 10-7 0.K 10-8 0.K 10-9 0.K 10-10 0.K 10-11 0.K I

10-12 0.K 10-13 0.K 10-14 0.K 10-15 0.K 10-16 0.K 10-17 0.K 10-18 0.K 10-19 0.K I

V 10-1

BRAIDWOOD REVISION 0.K JANUARY 1993 CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS 10.1 AIRBORNE RELEASES......................

I 10.1.1

System Description

I 10.1.1.1 Waste Gas Holdup System...................

I 10.1.1.2 Ventilation Exhaust Treatment System I

10.1.2 Radiation Monitors I

10.1.2.1 Auxiliary Building Vent Effluent Monitors..........

I 10.1.2.2 Containment Purge Effluent Monitors.............

2 10.1.2.3 Waste Gas Decay Tank Monitors................

2 10.1.2.4 Gland Steam and Condenser Air Ejector Monitors 2

10.1.2.5 Radwaste Building Ventilation Monitor............

3 10.1.2.6 Component Cooling Water Monitor...............

3 10.1.2.7 Miscellaneous Ventilation Monitors 3

10.1.3 Alarm and Trip Setpoints 3

i 10.1.3.1 Setpoint Calcul ations.....................

3 10.1.3.1.1 Auxiliary Building Vent Effluent Monitors..........

3 10.1.3.1.2 Containment Purge Effluent Monitors..............

4 10.1.J.l.3 Waste Gas Decay Tank Effluent Monitors 4

10.1.3.1.4 Component Cooling Water Monitors 4

10.1.3.2 Release Limits 4

10.1.3.3 Release Mixture.......................

5 10.1.3.4 Conversion Factors 5

10.1.3.5 HVAC Flow Rates.......................

5 10.1.4 Allocation of Effluents from Common Release Points 5

10.1.5 Dose Projections for Batch Releases.............

6 10.2 LIQUID RELEASES.......................

6 10.2.1

System Description

6 10.2.1.1 Release Tanks..........

6 10.2.2 Radiation Monitors 6

10.2.2.1 Liquid Radwaste Effluent Monitors..............

6 10.2.2.2 Station Blowdown Monitor 6

i

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10-11

BRAIDWOOD REVISION 0.K JANUARY 1993 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS 10.2.2.3 Reactor Containment Fan Cooler (RCFC) and Essential Service Water (ESSW) Outlet Line Monitors.................

7 10.2.3 Alarm and Trip Setpoints 7

10.2.3.1 Setpoint Calculation 7

10.2.3.1.1 Liquid Radwaste Effluent Monitor 7

10.2.3.1.2 Station Blowdown Monitor 7

10.2.3.2 Discharge Flow Rates 8

10.2.3.2.1 Release Tank Discharge Flow Rate 8

10.2.3.3 Release Limits 8

10.2.3.4 Release Mixture.......................

9 l

l 10.2.3.5 Cetversion Factors 9

10.2.3.6 Liquid Dilution Flow Rates 9

10. 2..~

Allocation of Effluents from Common Release Points 9

10.2.5 Projected Concentrations for Releases............. 9 l

10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM.......

11 l

l C

10-111

BRAIDWOOD REVISION 0.K JANUARY 1993 i

)

'V CHAPTER 10 LIST OF TABLES NUMBEP PAGE 10-1 Assumed Composition of the Braidwood Station Noble Gas Effluent 10-12 10-2 Assumed Composition of the Braidwod Station Liquid Effluent 10-13 s

10-iv

BRAIDWOOD REVISION 0.K JANUARY 1993 O

CHAPTER 10 LIST OF FIGURES NUMBER PAGE 10-1 Simplified HVAC and Gaseous Effluent Flow Diagram 10-15 10-2 Simplified Liquid Radwaste Processing Diagram 10-17 10-3 Simplified Liquid Effluent Flow Diagram 10-18 10-4 Simplified Solid Radwaste Processing Diagram 10-19 4

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10-v

i BRAIDWOOD REVISION 0.K JANUARY 1993 su

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CHAPTER 10 1

RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1

System Description

A simplified HVAC and gaseous effluent flow diagram is provided 1

in Figure 10-1.

The principal release points for potentially radioactive airborne effluents are the two auxiliary building vent stacks (designated Unit 1 Vent Stack and Unit 2 Vent Stack l

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 installed to reduce radioactive gaseous effluents by collecting reactor coolant system off-gases from the reactor coolant system and providing for delay or holdup to reduce the total radioactivity by radiodecay prior to release to the 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 material in particulate form in gaseous effluents by passing ventilation i

or vent exhaust gases through HEPA filters (and charcoal adsorbers when required to mitigate potential iodine releases) prior to release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figure 10-1.

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

10.1.2 Radiation Monitors 10.1.2.1 Auxiliary Building Vent Effluent Monitors Monitors IRE-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.

10-1

BRAIDWOOD REVISION 0.K i

JANUARY 1993 In normal operation all three noble gas channels (low, mid-range, high) are on line and active. On a high alarm the low and mid-range noble gas channels are closed and only the high range noble gas channel remains active. The iodine and particulate channels, however, continue to operate under all conditions.

No automatic isolation or cor. trol functions are performed by these monitors.

Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1.

10.1.2.2 Containment Purge Effluent Monitors Monitors IRE-PR001 (Unit 1) and 2RE-PR001 (Unit 2) continuously monitor the 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 follow established procedures to terminate the release by manually activating the containment purge valves.

Additionally, the auxiliary building vent effluent monitors provide an independent, redundant means of monitoring the containment purge effluent.

No automatic isolation or control functions are performed by

(}

these monitors.

Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1.

Area Radiation Monitors 1(2) RE-AR0ll and 1(2) RE-AR012 monitor the containment atmosphere. On high alarm during a containment purge, these monitors will automatically terminate the purge.

10.1.2.3 Waste Gas Decay Tank Monitors Monitors ORE-PR002A/B continuously monitor the noble gas activity released from the gas decay tanks.

On high alarm, the monitors automatically initiate closure of the valve OGWD14 thus terminating the release.

Pertinent information on these monitors and associated control i

devices is provided in Byron /Braidwood UFSAR Table 11.5-1.

t 10.1.2.4 Gland Steam and Condenser Air Ejector Monitors Monitors IRE-PR027 and 2RE-PR027 continuously monitor the condenser air ejector gas from Units 1 and 2, respectively. On high alarm 1(2)RE-PR027 initiates startup of the offgas treatment system.

s x_

10-2

BRAIDWOOD REVISION 0.K JANUARY 1993 Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-1, 10.1.2.5 Radwaste Building Ventilation Monitor Monitor ORE-PR026 continuously monitors radioactivity in the radwaste building ventilation system. No control device is initiated by this channel.

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

10.1.2.6 Component Cooling Water Monitor Monitors ORE-PR009 (common), 1RE-PR009 (Unit 1), and 2RE-PR009 (Unit 2) continuously monitor the component cooling water heat exchanger outlets. On high alarm ORE-PR009 initiates closure of both component cooling water surge tank (CCWST) vents, IRE-PR009 initiates closure of the Unit 1 CCWST vent, and 2RE-PR009 initiates closure of the Unit 2 CCWST vent.

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

10.1.2.7 Miscellaneous Ventilation Monitors Monitor ORE-PR003 continuously monitors radioactivity in the i

ventilation exhaust from the laboratory fume hoods.

No control device is initiated by this channel.

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

10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Auxiliary Building Vent Effluent Monitors The setpoints for the low range noble gas channel are conservatively established at 5% of the maximum permissible station release rate for the high alarm and 1/2% of the maximum release rate for the alert alarm.

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

10-3 E--

BRAIDWOOD REVISION 0.K JANUARY 1993 O

V 10.1.3.1.2 Containment Purge Effluent Monitors The setpoints are established at 1.25 times the analyzed containment noble gas activity during purge.

10.1.3.1.3 Waste Gas Decay Tank Effluent Monitors The setpoints are established at 1.25 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 respone is divided by 2 to obtain the final setpoint.

(See section 10.2.3.5 for the conversion factor).

10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of 10 CFR 20 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, Q,,.

(1.11)Q,, { ((f,) s 500 mrem /yr (10-1)

Q,, { ((f,) [((X/Q), exp(-A,R/3600u,) *

+ 1.11V,]) < 3000 rem /yr The summations are over noble gas radionuclides i.

f; Fractional Radionuclide Composition The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides.

Q,,

Total Allowed Release Rate,

[pCi/sec]

Vent Release The total allowed release rate of all noble gas radionuclides released as vent releases.

j O-exp (-A,R/3600U,) is set equal to 1.0 for

\\._,,)

setpoint calculations.

10-4

BRAIDWOOD REVISION 0.K JANUARY 1993

(

)

v The remaining parameters in Equation 10-1 have the same definitions as in Equation A-8 of Appendix A.

The remaining parameters in Equation 10-2 have the same definition as in Equation A-9 of Appendix A.

Equation 10-1 is based on Equation A-8 of Appendix A and the 10 CFR 20 restriction on whole body dose rate (500 mrem /yr) due to noble gases released in gaseous effluents (see Section A.I.3.1 of Appendix A).

Equation 10-2 is based on Equation A-9 of Appendix A and the 10 CFR 20 restriction on skin dose rate (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.I.3.2 of Appendix A).

Since the solution to Equation 10-2 is more conservative than the solution to Equation 10-1, the value of Equation 10-2 (3.09 x 10' Ci/sec) is used as the limiting noble gas release rate.

During evolutions involving releases from the containment or waste gas decay tanks, the release rate from each release path is procedurally limited to 1 x 10' pCi/sec (less than 1/3 the maximum permissible station release rate).

Calibration methods and surveillance frequency for the monitors will be conducted as specified in the RETS.

p 10.1.3.3 Release Mixture d

In the determination of alarm and trip setpoints, the radioactivity mixture in exhaust air is assumed to have the radionuclide composition of Table 10-1.

10.1.3.4 Conversion Factors The response curves used to determine the monitor count rates are based on the sensitivity to Xe-133 for conservatism.

10.1.3.5 HVAC Flow Rates The plant vent stack flow rates are obtained from 1/2 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 8

Unit 2 -

4.55 x 10 cc/sec 10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the auxiliary building, miscellaneous ventilation systems and the gas decay tanks are. comprised of contributions from both units.

Consequently, allocation is made evenly between units.

10-5

BRAIDWOOD REVISION 0.K JANUARY 1993

[%

.i 10.1.5 Dose Projections for Batch Releases Dose +rojections 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.

The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralizer or a concentrator for the purpose of reducing the total radioactivity prior to release to the environment. The system is described in Section 11.2.2 of the Byron /Braidwood Updated Final Safety Analysis Report.

10.2.1.1 Release Tanks There are two radwaste release tanks (0WX01T - 33,100 gallon capacity, and OWX26T - 33750 gallon capacity) which receive liquid waste before discharge to the Kankakee river.

10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitors Monitor ORE-PR001 is used to monitor all releases from the release tanks. On high alarm, the monitor automatically initiates closure of valves OWX-353 and 0WX-896 to terminate the release.

Pertinent information on the monitor and associated control devices is provided in Byron /Braidwood UFSAR Table 11.5-2.

10.2.2.2 Station Blowdown Monitor Monitor ORE-PR010 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.

O 10-6

BRAIDWOOD REVISION 0.K JANUARY 1993 j#

-l 10.2.2.3 Reactor Containment Fan Cooler (RCFC) and Essential Service Water (ESSW) Outlet Line Monitors Monitors IRE-PR02, 2RE-PR002, 1RE-PR003, and 2RE-PR003 continuously monitor the RCFC and ESSW outlet lines.

No control device is initiated by these channels.

Pertinent information on these monitors is provided in Byron /Braidwood UFSAR Table 11.5-2.

10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of 10 CFR 20 are not exceeded in the unrestricted area.

10.2.3.1.1 Liquid Radwaste Effluent Monitor r

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

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

)

/ (F " + FL)

(10-3)

P s C " + (1.25 x C') x F'

C C

i P

Release Setpoint

[pti/mt]

1.25 Factor to account for minor fluctuations in count rate.

C'"'

Concentration of activity in the

[pCi/ml]

circulating water blowdown at the time of discharge.

(" Background reading")

Cr Analyzed activity in the release tank

[ Ci/mt]

F" Circulating Water Blowdown Rate

[gpm]

C

/m 10-7

Br.AIDWOOD REVISION 0.K JANUARY 1993 FL Maximum Release Tank Discharge Flow Rate

[gpm]

The flow rate from the radwaste discharge tank.

10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Release Tank Discharge Flow Rate Prior to each batch release, a grab sample is obtained.

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

FL = 0.5(F[/{ (C[/MPC,))

(10-4)

The summation is over radionuclides i.

0.5 Factor for conservatism i

FL Maximum Permitted Discharge Flow Rate

[gpm)

(

The maximum permitted flow rate from the radwaste discharge tank based on radiological limits (not chemistry limits which may be more restrictive)

Fi, Circulating Water Blowdown Rate

[gpm)

C[

Concentration of Radionuclide i in

[pti/mt]

the Release Tank The concentration of radioactivity in the radwaste discharge tank based on measurt,nents of a sample drawn from the tank.

MPC, Maximum Permissible

[ Ci/mt]

Concentration of Radionuclide i 10.2.3.3 Release Limits Release limits are determined from 10 CFR 20. Discharge rates and setpoints are adjusted to ensure that 50% of applicable maximum permissible concentrations (MPC) are not exceeded.

(See Section 10.2.3.2)

(q) 10-8

BRAIDWOOD REVISION 0.K JANUARY 1993 (m

10.2.3.4 Release Mixture For monitors ORE-PR001 and ORE-PRO 10 the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis or the mix in Table 10-2.

For monitors IRE-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 MPC value given in 10 CFR 20 Appendix B, Table II, Column 2.

10.2.3.5 Conversion Factors i

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

The cpm to pCi/mi conversion is based on the detector sensitivity to Cs-137.

10.2.3.6 Liquid Dilution Flow Rates Dilution flow rates are obtained from circulating water blowdown transmitter loop 0FT-CWO32.

p 10.2.4 Allocation of Effluents from Common Release Points

('

Radioactive liquid effluents released from either release tank (0WX01T or OWX26T) are comprised of contributions from both units. Under normal operating conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation is made evenly between units.

10.2.5 Projected Concentrations-for Releases After determining F' from Equation 10-4,10 CFR 20 compliance is verified using Equations 10-5 and 10-6.

f Cl = C((F' f(FL + F,)]

(10-5)

{ { Cl/MPC, ) s 0.5 (10-6)

The summation is over radionuclides 1.

Cl Concentration of Radionuclide i

[pCi/mt) in the Unrestricted Area The calculated concentration of pd radionuclide i in the unrestricted area as determined by Equation 10-5.

i 10-9 L

BRAIDWOOD REVISION 0.K JAN'JARY 1993 '

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C[

Concentration of Radionuclide i

[pCi/mt]

in the Release Tank The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank.

MPC; Maximum Permissible Concentration

[pci/mt]

of radionuclide i F',,

Maximum Release Tank Discharge

[gpm]

Flow Rate F,,

Circulating Water Blowdown Rate

[gpm]

0.5 Factor for conservatism ds i

e O

10-10

BRAIDWOOD REVISION 0.K JANUARY 1993 r) kJ 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.

v 10-11

BRAIDWOOD REVISION 0.K JANUARY 1993

\\

Table 10-1 Assumed Composition of the Braidwood Station Noble Gas Effluent Percent of Isotope Total Annual Release Ar-41 00.89 Kr-85m 00.18 Kr-85 24.9 Kr-87 00.04 Kr-88 00.28 Xe-131m 01.4 Xe-133m 00.57 Xe-133 71.1 Xe-135 00.53 Xe-138 00.04 4

n l

l 10-12

BRAIDWOOD REVISION 0.K JANUARY 1993 i

s' Table 10-2 Assumed Composition of the Braidwood Station Liquid Effluent Isotope Concentration Isotope Concentration (pCi/ml)

(pCi/m')

Ru-103 8.00E - 06 Mn-54 1.00E - 05 Ag-110m 3.00E - 06 Fe-59 5.00E - 06 Te-127 2.00E - 05 C0-58 9.00E - 06 Te-129m 2.00E - 06 Co-60 3.00E - 06 Te-131m 4.00E - 06 Rb-86 2.00E - 06 Te-132 2.00E - 06 Zr-95 6.00E - 06 I-130 3.00E - 07 Nb-95 1.00E - 05 I-131 3.00E - 08 Mo-99 4.00E - 06 I-132 8.00E - 07 I-133 1.00E - 07

()

I-135 4.00E - 07 Cs-134 9.00E - 07 Cs-136 9.00E - 06 Cs-137 2.00E - 06 Ce-144 1.00E - 06 Np-239 1.00E - 05 O

10-13

1 BRAIDWOOD REVISION 0.K JANUARY 1993 O

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THIS PAGE IS INTENTIONALLY LEFT BLANK L

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.. REVISION 0.K :

JANUARY 1993

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BRAIDWOOD STATION -

FIGURE 10-1 SIMPLIFIED HVAC AND GASEOUS EFFLUENT FLOW DIAGRAM.

(SHEET 1 OF 2) umaa m.

10-15

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REVISION 0.K JANUARY 1993 unn i corxlenser 2,500 (Dunng Unit i staqup)

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'4&D4-O' u.gend Nm.s

- Normal or frequent tow path 1.

Used intemmency to vent containment durmg norma! operaton.

Occasbnal flow path 2.

Used only during postaccident operation.

A Contamment atmosphere redut'. son monttor 3.

Fitter unt operaies only when high radiatbn is ostected in o'rgas

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C Cham fmer 4.

Alt fkm rates are desij;in flow raios in cubic feet per minute.

F Retualing 5.

Integrated Leak Rate Test (ILRT) pressure reiset point G

Noble pas raduttlon monitor (omhe)

(an attomate reisese point that is sekbm used).

H HEPA fitter W

Three.chartnel radiaton rrentor for pailculate, lodine, ard not:4e pas (omine)

N Normal operston P

particulate monitor (omano)

OFFSITE DOSE CALCULATION MANUAL a

Hyd=8enre==mbaar BRAIDWOOD STATION S

Normal ra%s stack radiaton fronkor (particulate. ladine. and notMe gas)

FIGURE 10-1 w

wenge staan nobi. redumon monnor n

v SIMPLIFIED HVA.C AND GASEOUS EFFLUENT FLOW DIAGRAM (SHEET 2 OF 2)

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i GENERIC BRAIDWOOD ANNEX INDEX PAGE REVISION APPENDIX F i'

F-i O.K F-ii O.A F-iii O.A F-iv O.A 7

F-1 0

F-2 O.K F-3 O.K F-4 0.A F-5 O.K F-6 0.K F-7 O.K F-8 O.K F-9 O.K F-10 O.K F-ll O.K F-12 O.K F-13 0.K F-14 O.K F-15 O.K

.Og F-16 O.K k,/

F-17 O.K s

F-18 O.K F-19 0.K F-20 O.K F-21 0.K F-22 O.K F-23 O

t f

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I, REVISIog o,;

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1 f

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APPENDIX F STATION-SPECIFIC DATA FOR BRAIDWOOD I

UNITS 1 AND 2 TABLE OF CONTENTS PAGE j

F.1 INTRODUCTION F-1 I

F.2 REFERENCES F-1 i

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l I

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ION 0.A BRAIDWOOD

APRIL 1991 l

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-APPENDIX F LIST OF TABLES

'i i

i NUMBER TITLE PAGE F-1 Aquatic Environmental Dose Parameters F-2 F Station Characteristics F-3

+

F-3 Critical Ranc'es F-4 F-4 Average Wind Speeds F-5 i

F X/Q and D/Q Maxima At or Beyond the i

Unrestricted Area Boundary F-6 i

F-6 D/Q at the Nearest Milk Cow and Meat

't Animal Locations Within 5 Miles F-7 j

F-7 Site Boundary Finite Plume Gamma Dose Factors for Selected Nuclides F-8 l

t

-l O

t i

f t

i i

r I

I i

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F-iii l

1 BRAIDWOOD REVISION 0.A APRIL 1991 APPENDIX F LIST OF FIGURES NUMBER TITLE PAGE F-1 Unrestricted Area Boundary F-23 r

i 1

O e

F-iv 1

l

BRAIDWOOD REVISION O MARCH 1989

(~s APPENDIX F

\\

STATION-SPECIFIC DATA FOR BRAIDWOOD UNITS 1 AND 2 F.1 INTRODUCTION i

This appendir contains data relevant to the Braidwood site.

Included is a figure showing the unrestricted area youndary and values of parameters used in offsite dose assessment.

F.2 REFERENCES 1.

Sargent & Lundy, Nuclear Safeguards and Licensing Division Braidwood Calculation No. BR-ER-02, Revs. O and 2.

O I

O F-1

BRAIDWOOD REVISION O.K JANUARY 1993 O

Table F-1 Aquatic Environment Dose Parameters a

Parameter Value W

f 1/M 1/M 0.25,

1. 0 -

W F, cfs 5.63E3 f

F, cfs 5.63E3 i

f b

t, hr 24

.)

W c

t, hr 3

j i

Limits on Radioactivity in Unprotected Outdoor Tanksd primary Water Storage Tank 1 2000 Cie Outside Temporary Tank i

10 Cie (per Technical Specification 3.11.1.4) a The parameters are defined in Section A.2.1 of Appendix A.

b f (hr) = 24 hr (all stations) for the fish ingestion pathway t

ctW (hr) = 3 hr (distance co Wilmington is 4 river miles; flow rate of 1.4 mph assumed) d See Section A.2.4 of Appendix A.

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

i i

l t

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F-2

,+

BRAIDWOOD REVISION O.K JANUARY 1993 i

~j Table F-2 i

/

Station Characteristics STATION:

Braidwood l

LOCATION:

Braceville, Illinois j

CHAR 7CTERISTICS OF ELEVATED RELEASE POINT: Not Applicable (NA) f

1) Release Height =

m

2) Diameter =

m

=

ms

4) Heat Content =

KCal s-1

-1

3) Exit Speed l

CHARACTERISTICS OF VENT STACK RELEASE POINT a

1) Release Height = 60.66 m
2) Effnctive Diameter = 2.80 m
3) Exit Speed

= 11.00 ms-1 CHARACTERISTICS OF GROUND LEVEL RELEASE

1) Release Height = 0 m

a

2) Building Factor (D)

= 60.6 m

O METEOROLOGICAL DATA A

320 ft Tower is Located 573m NE of vent stack release point i

Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Temperature i

i Elevated (NA)

(NA)

Vent 203 199-30 ft I

Ground 34 199-30 ft i

aUsed in calculating the meteorological and dose factors in

[

Tables F-5, F-6, F-7.

See Sections B.3 through B.6 of Appendix B.

g l

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F-3 t

s

BRAIDWOOD REVISION 0.A APRIL 1991 rs Table F-3 Critical Ranges i

Site Nearest Nearest Dairy Farm Boundarya ResidentD Within 5 Milesc Direction (m)

(m)

(m)

N 610 800 None NNE 914 1100 None i

NE 792 1900 None ENE 701 1800 None E

1036 1100 3540 ESE 2713 3500 None SE 3414 4500 None SSE 3444 5100 None S

4633 6300 None SSW 975 1400 None SW 625 1100 None WSW 533 600 None r

W 518 500 None WNW 503 600 None NW 495 500 7723 NNW 510 600 None b

aEnvironmental Report, Table 2.1-1.

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.

bl988 annual survey, Teledyne Isotopes Midwest Laboratories.

cMilch animal census, Teledyne Isotopes Midwest Laboratories, 1985.

Used in calculating the D/Q values in Table F-6.

F-4 l

I

BRAIDWOOD REVISION 0.K JANUARY 1993 Table F-4 p

Average Wind Speeds Downwind Averace Wind Speed (m/secia Direction Elevated Mixed Mode Ground Level N

7.6 6.0 4.7 NNE 7.5 5.8 4.4 NE 6.1 5.3 3.9 ENE 6.2 5.2 3.7 E

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 EBased on Byron site meteorological data, January 1978 through December 1987.

Calculated in Reference 1 of Section F.2, using formulas in Section B.l.3 of Appendix B.

f bThe 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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