ML20153C035

Revs to ODCM for Plant,Including Rev 2 to Chapters 10 & 11, Rev 4 to Chapter 12 and Rev 3 to App F

ML20153C035
Person / Time
Site:	Braidwood
Issue date:	08/31/1998
From:	COMMONWEALTH EDISON CO.
To:
References
PROC-980831, NUDOCS 9809230316
Download: ML20153C035 (100)

Text

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i X244 ALL

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Document Control Desk k

Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Ma;l Station PI-137 Washington DC 20555 i

September 14,1998 Attachkd are revisions to the Offsite Dose Calculation Manual, Braidwood Annex.

Please update your manual as follows:

Remove:

Braidwood, Chapter 10, Revision 1.9 Braidwood, Chapter 11, Revision 1.9 Braidwood, Chapter 12, Revision 3 Braidwood, Appendix F, Revision 2 l

Insert:

Braidwood, Chapter 10, Revision 2 l

Braidwood, Chapter.11, Revision 2 Braidwood, Chapter 12, Revision 4 Braidwood, Appendix F, Revision 3 Please sign below indicating your manual has been updated and that your controlled copy number is correct.

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Name Date Return to:

l h)O i

Comed Pracedures Clerk l

Procedures Clerk OR 4th Floor

- 1400 Opus Place,4th Floor ETW lli Downers Grove, IL 60515 T

9809230316 980831 PDR ADOCK 05000456 P

PDR i

I

i l

i Braidwood Station g

Chapter 10 Change Summary ODCM Revision 2, August 1998 Page Change Description

~

10-1 Updated revision number.

10-5 Removed volume of release tanks. The volume of the tanks is given in the UFSAR 11.5.2.3.1 (30,000 gallons).

10-13, Update figures to electronic format.

10-14, l

10-15, 10-16, 10-17 i

e i

i 10 I

BRAIDWOOD Revision 2 August 1998 O

CHAPTER 10 BRAIDWOOD ANNEXINDEX Revision 2 l

i O

10-1 I

BRAIDWOOD Ravision 2 August 1998 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS SECTION PAGE 10.1 AIRBORNE RELEASES..

1 1.

System Description.

1 1.

Waste Gas Holdup System.

1 2.

Ventilation Exhaust Treatment System....

.1 2.

Radiation Monitors.

.1

1. Auxiliary Building Vent Effluent Monitors..

1 2.

Containment Purge Effluent Monitors..

2 3.

Waste Gas Decay Tank Monitors.

2 4.

Gland Steam and Condenser Air 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 2.

Containment Purge Effluent Monitors..

..3 3.

Waste Gas Decay Tank Effluent Monitors....

3 2.

Release Limits................

3 3.

Release Mixture..

5 4.

Conversion Factors...

5 5.

HVAC Flow Rates...

5 4

Allocation of Effluents from Common Release Points...

5 5.

Dose Projections for Batch Releases..

5 i

1 0

10-li

_m_

BRAIDWOOD Revision 2 August 1998 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS l

SECTION PAGE l

10.2 LlQUID RELEASES...

............5 1.

System Description..............

5 1.

Release Tanks..........

...........................5 2.

Radiation Monitors..............................

.......6 1.

Liquid Radwaste Effluent Monitors..

....l

.. 6 2.

Station Blowdown Monitor..

.....6 3.

Reactor Containment Fan Cooler (RCFC) and Essential Service Water (ESSW) Outiet Line Monitors.

6 4.

Turbine Building Fire and Oil Sump Monitor..

....6 5.

Condensate Polisher Sump Monitor.................

6 3.

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

7 1.

Setpoint Calculation.....

... 7 1.

Station Blowdown Monitor.....................

.......7 2.

Liquid Radwaste Effluent Monitor.............................. 7 1.

Release Tank Discharge Flow Rate.............

...........7 2.

Release Limits...

...........8 3.

Release Mixture................

.............8

\\

4.

Liquid Dilution Flow Rates...........

.9 5.

Projected Concentrations for Releases....................... 9 3.

Other Liquid Effluent Monitors........................

....9 4.

Conversion Factors....

... 10

4. Allocation of Effluents from Common Release Points........................

.10 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM..

......... 10 1 0 -111

BRAIDWOOD Revision 2 August 1990 I

i CHAPTER 10 LIST OF TABLES NUMBER PAGE 10-1 Assumed Composition of the Braidwood Station Noble Gas Effluent 10-11 10-2 Assumed Composition of the Braidwood Station Liquid Effluent 10-12 O

O 10-iv 1

l 1

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

.. - ~._. - _.

BRAIDWOOD Revision 2 August 1998 1

CHAPTER 10 LIST OF FIGURES NUMBER PAGE 10-1 Simplified HVAC and Gaseous Effluent Flow Diagram 10-13' 10 2 Simplified Liquid Radwaste Processing Diagram 10-15 10-3 Simplified Liquid Effluent Flow Diagram 10-16 10-4 Simplified Solid Radwaste Process Diagram 10-17 O

6 O

10-v

BRAIDWOOD Rsvision 2 August 1998 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1

System Description

A simplified HVAC and gaseous effluent flow diagram is provided in Figure 10-1. The principal release points for potentially radioactive airbome effluents are the two auxiliary building vent stacks (designated Unit i 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 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 Chapter 11 of the Byron /Braidwood UFSAR.

i 10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in gaseous effluents by passing ventilation or vent exhaust gases through HEPA filters (and charcoal adsorbers when required to mitigate potential iodine releases) prior to release to the environment.

l Such a system is not considered to have any effect on noble gas effluents. The l

ventilation exhaust treatment systems are shown in Figure 10-1.

l l

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

l 10.1.2 Radiation Monitors 10.1.2.1 Auxiliary Building Vent Effluent Monitors 1

Monitors 1RE PR028 (Unit 1) and 2RE-PR028 (Unit 2) continuously monitor the final effluent from the auxiliary building vent stacks.

l 80th vent stack monitors feature automatic isokinetic sampling, grab sampling, and i

tr.:ium sampling.

No automatic isolation or control functions are performed by these monitors. Pertinent I

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

l 10-1

BRAIDWOOD Revision 2 August 1998

(

10.1.2.2 Containment Purge Effluent Monitors Monitors 1RE PR001 (Unit 1) and 2RE-PR001 (Unit 2) continuously monitor the effluent from the Unit 1 and Unit 2 containments, respectively. When airbome radioactivity in the containment purge effluent stream exceeds a specified level, station personnel will 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-ARO11 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 OGWO14 thus r.

terminating the release.

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

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

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

Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5-1, 10.1.2.6 Component Cooling Water Monitor Monitor 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 O

(CCWST) vents,1RE-PR009 initiates closure of the Unit 1 CCWST vent, and Q

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

10-2

BRAIDWOOD Remaori2 August 1998 10.1.2.7 Miscellaneous Ventilation Monitors Monitor ORE-PR003 continuously monitors radioactivity in the ventilation exhaust from the laboratory fume hoods. No control device is initiated by this channel.

Pertinent information on this monitor and associated devices is provided in Byron /Braidwood UFSAR Table 11.5-1, 10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Auxiliary Building Vent Effluent Monitors The High Alarm setpoint for the High Range Noble Gas Channel (1/2PR028D) is established at the maxirnum release rate for the station as calculated in 10.1.3.2 The Alert Alarm setpoint for the High Range Gas Channelis established at a fraction of the maximum release rate for the station.

The High Alarm setpoint for the Low Range Noble Gas Channel (1/2PR0288) is established at less than or equal to 50% of the maximum release rate for the station as calculated in 10.1.3.2. The Alert Alarm setpoint for the Low Range Gas Channelis established at a fraction of the High Alarm setpoint for the Low Range Noble Gas Channel.

10.1.3.1.2 Containment Purge Effluent Monitors The setpoints are established at 1.50 times the analyzed containment noble gas activity during purge, plus the background reading of the monitor prior to purge.

10.1.3.1.3 Waste Gas Decay Tank Effluent Monitors The setpoints are established at 1.50 times the analyzed waste gas tank activity during release.

10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of RETS are not exceeded. The release limits are found by solving Equations 101 and 10-2 for the total allowed release rate of vent releases, Qu.

(1.11) Qu Z {Vif,} < 500 mrem /yr (10-1)

Qu Z {(fi) [Li (X/Q), exp (-L R/3600 uy)*

(10-2)

+ 1.11Vi]} < 3000 mrem /yr O

.10-3

~ _

BRAIDWOOD Rtvision 2 August 1998 The summations are over noble gas radionuclides i.

1.11 Conversion Constant (mrem / mrad) f, Fractional Radionuclide Composition l

The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides.

3 L.

Beta Skin Dose Factor (mrem /yr)/( Cl/m )

l Beta skin dose rate per unit of radioactivity concentration for radionuclide 1.

2 Attenuation of beta radiation during passage through 7 mg/cm of dead skin is accounted for.

l Qu Total Allowed Release Rate, Vent Release

[ Ci/sec]

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

exp (-A R/3600u,) is set equal to 1.0 for setpoint calculations, i

V, Gamma Whole Body Dose Factor (mrad /yr)/( Ci/sec) l Gamma whole body dose rate at a specified location per unit of radioactivity release rate for radionuclide i released from a vent..The attenuation of gamma radiation due to passage through 1 cm of body tissue of 1 g/cm density is taken into account in calculating this quantity.

3 (X/Q), Relative Concentration Factor (sec/m )

l Radioactivity concentration at a specified location per unit of radioactivity release rate for a vent release.

Equation 10-1 is based on Equation A-8 of Appendix A and the RETS restriction on l

whole body dose rate (500 mrem /yr) due to noble gases released in gaseous effluents l-(see Section A.1.3.1 of Appendix A). Equation 10-2 is based on Equation A-9 of I

Appendix A and the RETS restriction on skin' dose rate (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.1.3.2 of Appendix A).

Since the solution to Equation 10-2 is more conservative than the solution to Equation.

5 10-1, the value of Equation 10-2 (7.02 x 10 Ci/sec) is used as the limiting noble gas release rate. During evolutions involving releases from the containment or waste gas 5

decay tanks, the release rate from each release path is procedurally limited to 1 x 10 Ci/sec.

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

O 10-4

BRAIDWOOD Rzvision 2 August 1998 10.1.3.3 Release Mixture in the determination of alarm and trip setpoints, the radioactivity mixtur'e 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:

8 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.

10.1.5 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.

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 Chapter 11 of the Byron /Braidwood UFSAR.

10 2.1.1 Release Tanks There are two radwaste release tanks (0WX01T and OWX26T) which receive liquid I

waste before discharge to the Kankakee river.

O l

10-5 i

BRAIDWOOD Ravision 2 August 1998 10.2.2 Radiation Monitors V

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

)

i 10.2.2.3 Reactor Containment Fan Cooler (RCFC) and Essential Service Water (ESSW) Outlet Line Monitors Monitors 1RE PR002,2RE-PR002,1RE-PR003, and 2RE-PR003 continuously monitor l

the RCFC and ESSW outlet lines.

No control device is initiated by these channels.

tO l

Pertinent information on these monitors is pmvided 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 is provid'ed in Byron /Braidwood UFSAR Table 11.5-2.

10.2.2.5 Condensate Polisher Sump Monitor Monitor ORE-PR041 continuously monitors the condensate polisher sump discharge.

On high alarm the monitor automatically initiates an interlock to trip the discharge pumps and terminate the release.

Pertinent information on this monitor is provided in Byron /Braidwood UFSAR Table 11.5 2.

i l

/* s t.

I 10-6

r BRAIDWOOD RG; vision 2 August 1998 j

J 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Ca;culations l

Alarm and trip setpoints of liquid effluent monitors at the principal release points are i

established to ensure that the limits of RETS and 10CFR20 are not exceeded in the

)

unrestricted area.

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

P 5 C * + (1.25 x C') x [(F'mo / (Few + F'ma)]

(10-3)

P Release Setpoint

[pCi/ml]

1.25 Factor to account for minor fluctuations in count rate.

C'"

Concentration of activity in the circulating water blowdown

[pCi/ml]

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

C' Analyzed activity in the release tank

[pCl/ml]

F Circulating Water Blowdown Rate

[gpm]

O F'm.

Maximum Release Tank Discharge Flow Rate

[gpm]

The flow rate from the radwaste discharge tank based on the more restrictive of the maximum chemistry permitted flow rate or the Maximum Radiological Permitted Discharge Flow Rate.

10.2.3.1.2 Liquid Radwaste Effluent Monitor During release the setpoint is established at 1,5 times the analyzed tank activity plus the background reading.

10.2.3.1.2.1 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 dischai9e rate of each batch as follows:

F'r.s = 0.5(F",a /E(C',/10

• DWC,))

(10-4)

The summation is over radionuclides i.

0.5 Factor for conservatism O

10-7

BRAIDWOOD Revision 2 August 1998

/N F'r.a Maximum Radiological 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 Slowdown Rate

[gpm]

l C[-

Concentration of Radionuclide iin

[pCi/ml]

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

DWC, Derived Water Concentration

[ C1/ml]

of Raaionuclide i The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402.

10 Multiplier 10.2.3.1.2.2 Release Limits Release limits are determined from RETS. Discharge rates and setpoints are adjusted to ensure that 50% of applicable RETS are not exceeded. (See Section 10.2.3.1.2.1.)

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

! Q 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

(

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

The controls for this pathway will be established by limiting the quantity (Curies) discharged to the Braidwood cooling pond. The administrative action level will be established at 4 Ci/ year. During times when tritium discharged to the cooling pond is in excess of the 4 Ci/ year administrative action level, cooling pond tritium samples should be collected and analyzed (tritium LLD as defined in ODCM Chapter 12, Table i

l.

12.3-1) in order to assess actual tritium cooling pond tritium concentrations. Effluent l

pathways to the cooling pond are analyzed for tritium in accordance with ODCM Chapter 12, Table 12.3-1, The administrative action level was chosen based on an equilibrium concentration of 200 pCi/l in the cooling pond water (1% of the public drinking water limit as specified in 40CFR141.) Information regarding calculation and assumptions can be found in Braidwood Health Physics Technical Document 98-001,1 Cooling pond tritium issues".

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

!O l

10-8 l

BRAIDWOOD RQvision 2 August 1998 10.2.3.1.2.4 Liquid Dilution Flow Rates Dilution flow rates are obtained from circulating water blowdown transmitter loop OFT-CWO32.

10.2.3.1.2.5 Projected Concentrations for Releases After determining F'm,1from Equation 10-4, RETS compliance is verified using Equations 10-5 and 10-6.

FL)]2 (10-5)

Cf = CI[F' a / (F' a

~

m E{ Cf /10

• DWC, J s 0.5 3 (10-6)

The summation is over radionuclides i.

C,"4 Concentration of Radionuclide iin the Unlestricted Area

[ Cl/ml]

The calculated concentration of radionuclide i in the unrestricted area as determined by Equation 10-5.

C[5 Concentration of Radionuclide iin the Release Tank

[ Ci/ml]

The concentration of radioactivity in the radwaste discharge tank based on measur,ements of a sample drawn from the tank.

DWC, Derived Water Concentration of Radionuclide i

[ Cl/ml]

of Radionuclide i The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402.

10 Multiplier F'mo6 Maximum Release Tank Discharge a Flow Rate (gpm]

FL 7 Circulating Water Blowdown Rate

[gpm]

0.5 Factor for conservatism 10.2.3.1.3 Other Liquid Effluent Moilitors For all other liquid effluent monitors, including ORE-PR001 and ORE-PRO 10 when not batch releasing, setpoints are determined such that the concentration limits do not exceed 10 times the DWC value given in Appendix B, Table 2, Column 2 to 10CFR20.1001 - 20.2402 in the unrestricted area. Release mixtures are based on a representative ;sotopic mixture of the waste stream or inputs to the waste stream, or defaulted to the mix listed in Table 10-2.

O 10-9

BRAIDWOOD Rsvision 2 August 1998 10.2.3.1.4 Conversion Factors The readouts for the liquid effluent monitors are in C1/ml. The epm to Ci/mi conversion is determined for each monitor.

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.

10.3 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.

OV I

%)

10-10

BRAIDWOOD Revision 2 August 1998 Table 10-1 Assumed Composition of the Braidwood Station Noble Gas Effluent Isotope Percent of Total Annual Releases Ar-41 00.89 Kr-85m 00.18 Kr-85 24.90 Kr 87 00.04 Kr-88 00.28 O

Xe-131m 01.40 Xe-133m 00.57 Xe-133 71.10

(

Xe-135 00.53 Xe-138 00.04 O

1 10-11

BRAIDWOOD Revision 2 August 1998 1

(~h l 'w)

Table 10-2 Assumed Composition of the Braidwood Station Liquid Effluent Isotope Concentration Isotope Concentration

( Ci/ml)

( Cl/ml)

Mn-54 1.00E - 05 l-132 8.00E - 07 l

Co-58 9.00E - 06 l-133 1.00E - 07 Fe-59 5.00E - 06 Cs-134 9.00E - 07 Co-60 3.00E - 06 l-135 4.00E - 07 l

Rb-86 2.00E - 06 Cs-136 9.00E - 06 Nb-95 1.00E - 05 Cs-137 2.00E - 06 Zr 95 6.00E - 06 Ce-144 1.00E - 06 Mo-99 4.00E - 06 Np-239 1.00E - 05 Ru-103 8.00E - 06 Ag-110m 3.00E - 06

/~N t

Te 127 2.00E - 05 l %J Te-129m 2.00E - 06 l-130 3.00E - 07 l131 3.00E - 08 Te-131m 4.00E - 06 Te-132 2.00E - 06 l

G 10-12

BRAIDWOOD Mcvision 3 August 1998 i

4* * ',

El.v.200'00" na Zim.

EL State.f State of Ilknels lilla.as staat monit.r l i

stack m.na.r 7

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& v $3200 1

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~ n a.......a.

"I Gas 4ih8I Desg 7-138J88 ORErno02 y

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=y s.____________

building tant vents HCH Q

vuores buses tank vents CH I

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9 OREPR016 OFFSITE DOSE CALCULATION AW4UAL BRAIDWOOD STATION l

FIGURE 101 l

l SIMPLIFIED HVAC AND GASEOUS I

EFFLUENT FLOW DIAGRNA (SHEET 1 OF 2) l l

I 10-13 l

~.-

BRAIDWOOD Revision 2 August 1998 O

Unit 1 b-2.soo t,ourms unn i stap) conden.,

- +

-4 he..m. -,

s 8

I 8

Glandsteam d (4o0 Q

N 1.432 eendenne 1RE#R0270 E O 1p g g.g.______;_.!;_m.n_,

seeam jet

% 32 l

HCCH

"*I'***'

Turbine building g gg, ung

.j(oeneral area 8

I Elevasen dst ft) unm2 2.500 (Dunne unu 2 i he..enser

,$d 1 cond I'**

2

.-p I

il I

p L

N 1432 Gland steam i :

im r"M"1 eendenser y

F 0 2RE#R02 Steamjet

% 32 air ejeeter r

r"1 8.830 y

~

Solid redwaste LJ ORE #R026 Drummme etenen.. _Re_. pro _14___ _3_.1_00_

Veluule reduction g ___ _r.__g__3 l

ORE #Rodo I HC H

~

LEGEND NOTES

- Nwmai er frequent now path t Used Intermutenth te vent sentainment during normal operaden.

• • ** Oecessenai new path

2. Used enly duttng poetaccident operation.

A C_

atmoehpere radiation meneter C Chareeni Alter

3. Fiber unit operatea only when high radiasen le detected in engas F Refue46ng syseem emuent.

O Noble gas radiation monster (emme)

4. All flew rates are design flew rate in sub&c feet per minute.

M HEPA flMer

6. Intergrated Leak Rate Test (ILRT) pressure relief point M Three thannel radianen menhor for p articulate.

(an amernate rolesee point that is sendem used).

icene and nobie su tema.)

N Normal operasen P Parecuaate menner (enune3 OFFSITE DOSE CALCULATION MANUAL R Hydrogen resembiner.

BRAIDWOOD STATION S Normal range stuk radialien monter (parmulate.

FIGURE 101 ledins. and no66e gas) w widevane stub nebae su radianen menn" SIMPLFED HVAC AND GASEOUS EFFLUENT FLOW DIAGRAM (SHEET 2 OF 2) v 10-14

BRAIDWOOD R:v s on 2 i i August 1998 L.naT t UtaT g N

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• RE FLTERS GENERATOR N

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tTrstaar Tws 9

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1 BRAIDWOOD Revision 2 August 1998 1

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BRAIDWOOD Wevision F - ~~

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Chapter 11 Change Summary j

ODCM Revision 2, August 1998 Page Change Description 11 1 Updated reyision number.

11-5 Corrected sector location from "N" to "SSW".

Il-6 Removed special interest TLD locations. These locations are not REMP related and are for station information use only. Add address to BD-34,35,36,37 to ensure samples are taken from the correct location. Corrected estimated distance ofBD-22 from station.

Il-7 Add address to BD-17,18 to ensure samples are taken from the correct location.

Il-8 Added wording "if available" in case food products are not available.

I l-10, Update figures to electronic format.

Il-11, Il-12 l.

i l

l 6

O

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

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

i l

BRAIDWOOD Revision 2 August 1998 CHAPTER 11 BRAIDWOOD ANNEX INDEX l

1 Revision 2 l

l i

l 1-l I

F i

I I

l t

l 1.

l l

l l

i

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1 1

11-i

August tM9-J CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table of Contents CHAPTER TITLE PAGE 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 11-1 LIST OF TABLES NUMBER TITLEj PAGE 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 11-10 11-2 inner Ring TLD Locations 11 11 11-3 Ingestion and Waterbome Exposure Pathway Sample Locations 11-12 0

11 -ii

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

BRAIDWOOD Revision 2 August 1998 O

CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The radiological environmental monitoring program for the environs around Braidwood Station is given in Table 11-1.

l I

j' Figures 11-1 through 11-3 show sampling and monitoring locations.

l 1-I i

h t

h l

f-4 11-1

BRAIDWOOD Revision 2 l

August 1998 l

Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway j

Sampling or l

Type and Frequency l

and/or Sample Sample or Monitoring Locations Collection Frequency of Analysis i

l

1. Airbome f

, Continuous sampler g Radiciodine Canisters:

I

• operation with particulate l

Radioactive and

a. Indicators-Near Field sample collection weekly, or 1-131 analysis biweekly on Particulates g more frequently if required near field and control l

BD-06, Godley,0.5 mi WSW (0.8 km M) l by dust loading, and samples'.

?

BD-19, Nearsite NW,0.3 mi NW (0.5 km Q)

I radioiodine canister BD-20, Nearsite N,0.6 mi N (1.0 km A) l collection biweekly.

Particulate Sampier-BD-21, Nearsite NE,0.5 mi NE (0.8 km C) l g

l g Gross beta analysis following z

b. Indicators-Far Field 6 weekly filter change and l

gamma isotopic analysis l

BD-02, Custer Park,5.0 mi E (8.0 km E) e quarterly on composite filters BD-04, Essex,4.8 mi SSE (7.7 km H)

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

! contrul samples'.

I c. Controls i

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

l l

l 11-2

(

J G

w./

BRAIDWOOD Rsvision 2 August 1998 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Locations Collection Frequency of Analysis

2. Direct Radiation i a. Indicators-Inner Ring

! Quarterty i Gamma dose on each TLD l

' quarterly.

BD-101-3,0.5 mi N (0.8 km A) l BD-101-4,0.5 mi N (0.8 km A) l BD-102-1,1.1 mi NNE (1.8 km B) l BD-102-2,1.1 mi NNE (1.8 km B)

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

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

BD-105-1,2.2 mi E (3.5 km E) l BD-105-2,2.2 mi E (3.5 km E) l l

BD-106-1,2.5 mi ESE (4.0 km F) l l

BD-106-2,2.5 mi ESE (4.0 an F) l l

BD-107-1,3.2 mi SE (5.1 km G)

I i

BD-107-2,3.2 mi SE (5.1 km G) l BD-108-1,3.2 mi SSE (5.1 km H)

BD-108-2,3.2 mi SSE (5.1 km H)

I BD-109-1,3.8 mi S (6.1 km J) l BD-109-2,3.8 mi S (6.1 km J)

BD-110-1,2.8 mi SSW (4.5 km K) i BD-110-2,2.8 mi SSW (4.5 km K) l l

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

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

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

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

CD413a-1,0.5 mi W (0.8 km N) l BD-113a-2,0.5 mi W (0.8 km N) t I

b 11-3

BRAIDWOOD R: vision 2 August 1998 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway j

i Sampling or l

Type and Frequency and/or Sample Sample or Monitoring Locations Collection Frequ3ncy of Analysis

2. Direct Radiation

a. Indicators-Inner Ring (Cont'd)

(Cont'd) l BD-114-1, O

• 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)

BD-115-2,0.3 mi NW (0.5 km Q)

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

BD-116-2,0.5 mi NNW (0.8 km R) l b. Indicatgg-Outer Ring i

BD-201-1,4.2 mi N (6.8 km A)

BD-201-2,4.2 mi N (6.8 km A)

BD-202-1,4.8 mi NNE (7.7 km B) l BD-202-2,4.8 mi NNE (7.7 km B) l' 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)

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

BD-205-1,4.0 mi E (6.4 km E) i BD-205-2,4.0 mi E (6.4 km E) l BD-206-1,4.5 mi ESE (7.2 km F)

J BD-206-2,4.5 mi ESE (7.2 km F)

BD-207-1,4.5 mi SE (7.2 km G)

BD-207-2,4.5 mi SE (7.2 km G)

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

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

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

BD-209-2,4.8 mi S (7.7 km J) 1-4

o eWOOD o

BRA R: vision 2 August 1998 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Locations Collection Frequency of Analysis

2. Direct Radiation

b. Indicators-Outer Ring (Cont'd)

BD-210-1,5.3 mi SSW (8.5 km K) l BD-210-2, 5.3 mi SSW (8.5 km K) l BD-211-1,4.8 mi SW (7.7 km L) l l'

BD-211-2,4.8 mi SW (7.7 km L)

BD-212-3, 5.0 mi WSW (8.0 km M) l BD-212-4,5.0 mi WSW (8.0 km M) l l

BD-213-3,4.8 mi W (7.7 km N) l l

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

l BD-214-1,4.3 mi WNW (6.9 km P) l l

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

BD-215-1,4.5 mi NW (7.2 km Q) l BD-215-2,4.5 mi NW (7.2 km Q) j BD-216-1,4.0 mi NNW (6.4 km R) l BD-216-2,4.0 mi NNW (6.4 km R) l i

!c.Other l

Indicators i

I l One at each of the airbome location given in part 1,a l

! and 1.b.

l l

11-5

BRAIDWOOD R vision 2 August 1998 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway l

l Sampling or l

Type and Frequency and/or Sample l

Sample or Monitoring Locations Collection Frequency g

of Analysis s

I

2. Direct Radiation e c. Controls 1

(Cont'd) l One at each airbome controllocation given in part 1 i'

1.c.

I

3. Waterbome l

l l

a. Ground /Well l a. Indicators Quarte:1y Gamma isotopic and tritium l

analysis quarterly.

I BD-13 Braidwood City Hall Well, l

1.7 mi NNE (2.7 km B) g BD-34, Gibson Well,4.7 mi E (7.6 km E) l

[22032 Rt.113]

l BD-35, Joly Well,4.7 mi E (7.6 km E)

[22028 Rt.113]

BD-36, Hutton Well,4.7 mi E (7.6 km E) g

[22040 Rt.113]

BD-37, Nurczyk Well,4.7 mi E (7.6 km E

[22100 Davy Lane]

g 5

b. Drinkino Water

a. Indicator Weekly composite samples Gross beta and gamma I

isotopic analysis on monthly BD-22, Wilmington 6.0 mi NE (9.7 km C) composite; tritium analysis l

on quarterly composite.

c. Surface Water

! a. Indicator Weekly grab samples Gross beta and gamma I

, isotopic analysis on monthly i

l BD-10 Kankakee River downstream of l composite; tritium analysis discharge,5.4 mi NE (8.7 km C) l on quarterly composite.

-6

,m t

)

.\\

B OD R, vision August 1998 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway l

Sampling or l

Type and Frequency and/or Sample l

Sample or Monitoring Locations Collection Frequency l

of Analysis.

I I

i j

j

3. Waterbome (Cont'd) l l

l 1

d. Control l a. Control Weekiv grab samples Gross beta and gamma l

isotopic ananalysis' on i

BD-25. Kankakee River upstream of monthly composite; tritium i

l discharge,9.6 mi E (15.4 km E) g analysis on quarterly l

l compostte.

I I

e. Sediments

' a. Indicators l Semiannually l Gamma isotopic analysis' l

l semiannually.

I BD-10, Kankakee River downstream of discharge, 5.4 mi E (8.7 km C)

4. Inaestion g

3

a. Milk

a. Indicators 1 Biweekly-May through Gamma isotopic and 1-131 l October; monthly:

analysis' on each sample.

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

[8625 South Halpin Rd]

l l

I 1

b. Controls l

l l

l l

BD-18, Biros Farm,8.7 mi W (14.0 km N) l l

[1168 Reed Road}

e i

l n. Indicator Two times annually Gamma isotopic analysis' on

~

b. Fish edible portions s

l BD-28, Kankakee River in discharge g

l area,5.4 mi E (8.7 km E)

{

j b c a trol i

I l

BD-25 Kankakee River upstream of g

I g

discharge area,9.6 mi E (15.4 km E) 11-7

Revision 2 BRAIDWOOD August 1998 1

Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Sampling or Type and Frequency Exposure Pathway l

Sample or Monitoring Locations Collection Frequency of Analysis and/or Sample g

4. Inaestion (Cont'd) l t

Gamma isotopic analysis' on 8

Annually

c. Food Products

a. Indicators each sample.

Two samples from each of the four major i

l quandrants within 6.2 miles of the station, if l

available.

Sample locations for food products may vary l

I based on availability and therefore are not required to be identined here but shall be taken.

[

o l

! b. Controls I

Two samples within 9.3 to 18.6 miles of the l

Station,if available.

l 11-8

Revision b- -

August 1998

' Far field samples are analyzed when near field results are inconsistent with previous measurements and the radioactivity is confirmed as having its origin in airbome effluents released from the station, or at the discretion of the Radiation Protection Director.

2

- Airbome particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If ross beta adivity in air particulate samples is greater.han 10 times the yearty mean of control samples, gamma isotopic D

analysis shall be performed on the individual samples.

Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station.

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

5 Grab sample (s) shall be taken at the time of collection if the compositor is not in service.

1 11-9

j 155 I

l a

E 53 "n "

h n

216-2 m 201-288 d

216-1 e e2011 ts NN 1

l 214 2m Braldwood 204 Im 11 204 2 214-18 E 129 Kankakee River

• 0 m 213 4 2

e 213 3 gg 421 m205-1

/

6 Braldwood Station g ig3

/

s206.1 E

m212 4 m206-2 1

m 212-3 Braceville l

0 County Line Rd 15 1 53 em NM 3

[. Gardner kk 4

l I

s' 1 "='

• n SE

$5 South gg g&

Wikningon gg

$R N

3 k OFFSITE DOSE CALCULATIONMANUAL BRAIDWOOD STATION 0

1 2

3 4

5 Miles FIGURE 11-1 FDGD AIR SAMPLING SITES a TLD Locanons AND OUTER RING TLD LOCATIONS g Air Samphag Locanons O

11-10

BRAIDWOOD Revision 2 August 1998 O

L 129 i

L 53

\\

L 113 102-1 me

.m mh A103-2

E E104-1 5

l-55

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h$

, B104-2 m

105-i n f

105-28

1. j g,,

, Braidwood Station

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2 106-1 L.129 106-2 q^

Cooper Rd.

e s

n.

s107-1 bb 110-2m 110-1 s mg N

j l

U N500W W

0FFSITE DOSE CALCULATION MANUAL 0

1 Miles BRAIDWOOD STATION e TLD Location FIGURE 11-2 INNER RING TLD LOCATIONS 11 11

BRAIDWOOD Revision 2 August 1998 9

155 22 m hLS3

/

Kankakee River 13 X 10,

(3,7 miles Eut)

Braldwood 13 8 E II3 37 36 34 m

3 28 25

/

Braidwood Station a g13 a:

Uraceville 55 County Line Rd 155 E 53

/

Gardner 1 Essex n

Fuce Rd LJ South wumington X 17 N

k OFFSIE DOSE CALCULATION MANUAL BRAIDWOOD STATION O

1 2

3 4

5 FIGURE 11-3 Ie iiI I

I I

"I Eles INGESTION AND WATERDORNE EXPOSURE PATHWAYSAMPLEl.OCATIONS a W ater S Sed:rnent e Fish X Mdk el l

11-12

i I

D Braidwood Station

\\

Chapter 12 Change Summary ODCM Revision 4, August 1998 2

Page Change Description 12Ti Added wording indicating how Improved Technical Specification is annotated and when the references become effective.

12-il Updated revision number.

12-iii, Updated page numbers to reflect changes in text.

12-iv 12-1 Added Improved Technical Specification reference.

12-2 Added Improved Technical Specification and/or Technical Review Manual 1

12-3 reference. Corrected formatting of Code of Federal Regulations references.

i 12-4, Added definition for Continuous Sampling, this will allow for filter changes of 4

12-5, RETS monitors without having to do alternate monitoring. Added Improved 1

12-6 Technical Specification reference. Update definition numbers.

j

{

12-7 Added Improved Technical Specification reference.

~

12-8 Corrected formatting of Ccde of Federal Regulations references.

12-10 Reworded for clarification when releases are to be suspended. Added notation to clarify that an explanation in the next Radioactive Effluent Report is required when the monitor is not operational within the time specified in the ODCM.

Capitalized "OR" for better clarification.

12-12 Capitalized "OR" for better clarification.

2 12-13 Corrected formatting of Code of Federal Regulations references.

12-16 Reworded for cir.rification when releases are to be suspended. Added notation to clarify that an explanation in the next Radioactive Effluent Report is required when the monitor is not operational within the time specified in the ODCM.

12-18 Added additional tabi notation to the Gas Decay Tank System to reference monitor loss of sample ilow description.

.12-19 Capitalized "OR" for better clarification. Removed reference to functional unit 6 for the RE-PR009 radiation monitor. Added channel check information.

O W

12-20 Corrected formatting of Code of Federal Regulations references. Corrected numbering of surveillance requirements.

12-24, Changed formatting of exponent in the LLD equation.

l 12-25 12 26 Added additional information for the requirements or other gamma peaks that are l

identifiable. Corrected typographical error.

12-27 Corrected formatting of Code of Federal Regulations references. Changed reference to Technical Specification 6.9.2 to 10CFR50 Appendix I, Section IV. A.

12-29 Changed reference to Technical Specification 6.9.2 to 10CFR50 Appendix I, Section IV. A. Corrected formatting of Code of Federal Regulations references.

Corrected numbering of surveillance requirements.

12-30 Corrected formatting of Code of Federal Regulations references.

12-31 Corrected numbering of surveillance requirements.

12-34 Changed formatting of exponent in ths LLD equation.

12-35 Changed formatting of exponent in the LLD equation. Corrected typographical error.

12-37 Corrected formatting of Code of Federal Regulations references. Changed reference to Technical Specification 6.9.2 to 10CFR50 Appendix I, Section IV. A.

12-38 Corrected formatting of Code of Federal Regulations references.

12-39 Corrected formatting of Code of Federal Regulations references. Changed reference to Technical Specification 6.9.2 to 10CFR50 Appendix I, Section IV. A.

12-40 Corrected formatting of Code of Federal Regulations references.

12-41 Changed reference to Technical Specification 6.9.2 to 10CFR50 Appendix I, Section IV.A. Corrected numbering of surveillance requirements.

12-42 Corrected form. tin, of Code of Federal Regulations references.

12-43 Corrected numbering of surveillance requirements. Removed reference to Technical Specification 6.9.2. This is a 10CFR20 special report. Added information rermuing storage of the Unit i Old Steam Generators.

12-44 Added information regarding storage of the Unit 1 Old Steam Generators.

g' 12-45 Corrected formatting of Code of Federal Regulations references.

i

)

12-46 Removed reference to Technical Specification this is governed by 10CFR20 and 40CFR190. Add limit of 2 mrem in 12.4.6.A.2.

12-47 Changed reference to Technical Specification 6.9.2 to 10CFR50 Appendix I, Section IV. A.

12-48 Corrected formatting of Code of Federal Regulations references.

12-60 Corrected formatting of Code of Federal Regulations references.

12-61 Corrected formatting of Code of Federal Regulations references.

12-62 Added Improved Technical Specification reference.

12-63 Corrected formatting of Code of Federal Regulations references.

12-64 Added Improved Technical Specification reference.

12-65 Added reference to UFSAR Chapter 17 12-66 Corrected punctuation.

i l

!O i

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. - ~

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

BRAIDWOOD Revision 4 l

l August 1998 li.

CHAPTER 12.0 l

SPECIAL NOTE The' transfer of the Radiological Effluent Technical Specifications to the ODCM by Technical l

Specification, Amendment 35, dated April 13, 1992, was approved by the Nuclear Regulatory Commission.

improved Technical Specifications (l.T.S.) sections are annotated following the CTS section and are only l

l applicable after implementation of I T.S.

l l-i O

l f'

l' l

!O 12-1

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

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

.~.-

BRAIDWOOD Revi' an 4 AL. gust 1998 CHAPTER 12 ANNEXINDEX Revision 4 i

l O.

O 1 2 -11

.__~

BRAIDWOOD Rsvision 4 August 1998

[h)

CHAPTER 12 L

RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS PAGE 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12-1 12.1 DEFINITIONS 12-4 12.2 INSTRUMENTATION 12-8

1. Radioactive Liquid Effluent Monitoring instrumentation 12-8

2. Radioactive Gaseous Effluent Monitoring instrumentation 12-13 12.3 LIQUID EFFLUENTS 12-20

1. Concentration 12-20

2. Dose 12-27

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

./

t

1. Dose Rate 12-31

\\

2. Dose - Noble Gases 12-37

3. Dose - lodine-131 and 133, Tritium, and Radioactive Materialin Particulate Form 12-39

4. Gaseous Radwaste Treatment System 12-41

5. Total Dose 12-43

6. Dose Limits for Members of the Public 12-46 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12 47

1. Monitoring Program 12-47

2. Land Use Census 12-60

3. Interlaboratory Comparison Program 12-61 12.6 REPORTING REQUIREMENTS 12-62

1. Annual Radiological Environmental Operating Report 12-62

2. Annual Radioactive Effluent Release Report 12-64

3. Offsite Dose Calculation Manual (ODCM) 12-65

4. Major Changes to Liquid and Gaseous Radwaste Treatment Systems -

12-66 G/

1 2 -111

August 1998 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

UST OF TABLES PAGE 12.0-1 Effluent Compliance Matrix 12-2 12.0-2 REMP Compliance Matrix 12-3 12.1-1 Frequency Notations 12-7 12.2-1 Radioactive Liquid Effluent Monitoring instrumentation 12-9 12.2-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 12-11 12.2-3 Radioactive Gaseous Effluent Monitoring Instrumentation 12-14 112-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 12-17 12.3-1 Radioactive Liquid Waste Sampling and Analysis Program 12-22 12.4-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-33 12.5-1 Radiological Environmental Monitoring Program 12-50 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-56 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-57 l

l O

12-lv

_~

~. _ -

- _....,.. _ ~

BRAIDWOOD Rsvision 4 August 1998 i

12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS p

d Chapter 12 of the Braidwood Station ODCM is a compliance of the various regulatory l

l requirements, surveillance and bases, commitments and/or components of the radiological effluent and environmental monitoring programs for Braidwood Station. To assist in the l

understanding of the relationsnip between effluent regulations, ODCM equations, RETS (Chapter 12 section) and related Technical Specification (i.T.S.) requirements, Table 12.01 is a matix l

which relates these various components. The Radiological Environmental Monitoring Program fundamental requirements are contained within this chapter with Draidwood specific information in Chapter 11 and with a cupplemental matrix in Table 12.0-2.

l l

1 l

l l

1 12-1 i

BRAIDWOOD Revision 4 August 1998 Table 12.0-1 EFFLUENT COMPLIANCE MATRIX Regulation Dose Component Limit ODCM RETS Technical Equation Specification (ITS) l 10CFR50 1.

Gamma air dose and beta air dose due A-1 12.4.2 6.8.4.e.8 l

Appendix l to airbome radioactivity in effluent A-2 (5.5.4.h) plume.

a.

Wnole body and skin dose due to A-6 N/A N/A airbome radioactivity in efflJent A-7 plume are reported only if certain gamma and beta air dose criteria are exceeded.

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 in (5.5.4.i) effluent plume. All pathways are considered.

3.

CDE for ali organs and all four age A-29 12.3.2 6.8.4.e.4 groups due to radioactivity in liquid (5.5.4.d) l effluents.

10CFR20 1.

TEDE, totaling all deep dose equivalent A-38 12.4.6 6.8.4.e.3 components (direct, ground and plume (5.5.4.c) shine) and committed effective dose equivalents (all pathways, both abbome and liquid-bome). CDE evaluation is made for adult only using FGR 11 data base.

40CFR190 1,

Whole body dose (DDE) due to direct A-35 12.4.5 6.8.4.e.10 (now by dose, ground and plume shine from all (5.5.4.j) reference, sources at a station.

also part of 10CFR20) 2.

Organ doses (CDE) to an adult due to A-13 all pathways.

Technical 1.

" Instantaneous" whole body (DDE), skin A-8 12.4.1 6.8.4.e.7 Specifications (SDE), and organ (CDE) dose rates to A-9 (5.5.4.g)

(i.T.S.)

an adult due to radioactivity in airborne A-28 effluents. For the organ dose, only inhalation is considered.

2.

" Instantaneous" concentration limits for A-32 12.3.1 6.8.4.e.2 liquid effluents.

(5.5.4.b) l NA 12.6.2

1. Radiological Effluent Release Report Spec cations (i.T.S.)

O 12-2

~ -.,.

1 BRAIDWOOD Rsvision 4 August 1998 Table 12.0-2 O

REMP COMPLIANCE MATRIX Regulation Dose Component Limit RETS Technical Specification (ITS) 10CFR50 implement environmental monitoring 12.5.1 6.8.4.f Appendix 1 program-(TRM 5.2.C.1)

Section IV.B.2 1

Technical Land Use Census 12.5.2 6.8.4.f.2 Specification (TRM 5.2.C.2) 1 (1.T.S.)

Technical Interlaboratory Comparison Program 12.5.3 6.8.4.f.3 Specifications (TRM 5.2.C.3)

(l.T.S.)

Technical Radiological Environmental Operating 12.6.1 3

6.9.1.6 Specifications Report (5.6.2)

(1.T.S.)

O v

I i

l l

l

\\

12-3

BRAIDWW vemum August 1998 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12.1 DEFINIT".S Action shall be that which prescribes remedial measures required under designated 12.1.1 conditions.

Analoo Channel Operational Test shall be the injection of a simulated signal into the 12.1.2 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 channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of j

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 shallinclude, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

12.1.5 Continuous Samplino is uninterrupted sampling with the exception of sampling interruptions of short duration's, for routine activities (e.g. filter replacement) 12.1.6 Dioital Channel Operational Test shall consi.st of exercising the digital computer hardware using data base manipulation and injecting simulated process data to verify OPERABILITY of alarm and/or trip functions.

12.1.7 Qose Eouivalent I 131 shall be that concentration of I-131 (microcurie / gram) which l

alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133,1-134, and f-135 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".

12.1.8 Frecuency - Table 12.1-1 provides the definitions of various frequencies for which l

surveillance's, sampling, etc. are performed unless defined otherwise. The 25%

variance shall not be applied to Operability Action Statements. The bases to Technical Specification 4.0.2 (l.T.S. SR 3.0.2) sprovide clarifications to this l

requirement.

12.1.9 Member (s) of the Public means any individual except when that individual is receiving l

an occupational dose.

12.1.10 Occupational Dose means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include i

dose received from background radiation, from any medical administration the I

individual has received, from exposure to individuals administered radioactive material and released in accordance with 10CFR35.75, from voluntary participation in medical research programs. or as a member of the public.

1 1

0 1

12-4 l

l

(

BRAIDWOOD Revision 4 August 1998 12.0 RAD!OLOGICAL EFFLUENT TECHNICAL STANDARDS (Conti f.s

( )

l u

j 12.1.11 Operable / Operability a system, subsystem, train, component or device shall be l

OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical l.

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

12.1.12 Ooerational Mode (i.e. Mode) shall correspond to any one inclusive combination of l

core reactivity condition, power level, and averaoe reactor coolant temperature specified in Table 1.2 of the Technical Specifications (i.T.S. Table 1.1-1).

l 12.1.13 Process Control Prooram (PCP) shall contain the current formulas, sampling, l

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

12.1.14 Puroe/Puroino shall be any controlled process of discharging air or gas from a l

confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the cor.finement.

12.1.15 Rated Thermal Power shall be a total core heat transfer rate to the reactor coolant of l

3411 M W1.

O)

(

12.1.16 Site Boundary shall be that line beyond which the land is neither owned, nor leased, l

nor otherwise controlled by the licensee.

12.1.17 Sohdification shall be the conversion of wet wastes into a form that meets shipping and l

burial ground requirements.

12.1.18 Source Check shall be the qualitative assessment of channel response when the l

channel sensor is exposed to a source of increased radioactivity.

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

l 12.1.20 Unrestricted Area means an area, access to which is neither limited nor controlled by l

the licensee.

12.1.21 Ventilatlen Exhaust Treatment System shall be any system designed and installed to j

reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA tilters 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 n

12-5

BRAIDWOOD Revision 4 August 1998 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS (Cont.)

r 1

12.1.22 Ventina shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

12.1.23 Waste Gas Holduo System shall be any system designed and installed to reduce l

radioactive 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 releas3 to the environment.

12.1.24 Definitions Peculiar to Estimating Dose to Members of the Public using the ODCM l

Computer Program.

i ACTUAL-ACTUAL refers to using known release data to project the dose to a.

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 refer.s 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 in::orporated into the database.

l O

O 12-6

BRAIDWCOD Revision 4 August 1998 i

()

TABLE 12.1-1 FREQUENCY NOTATIONS

• NOTATION FREQUENCY S - Shiftly At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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

J W - Weekly At least once per 7 days.

M - Monthly At least once per 31 days.

Q - Quarterly At least once per 92 days.

SA - Semiannually At least once per 184 days.

A-Annually At least once per 366 days.

R - Refueling cycle At least once per 18 rnonths (550 days).

S/U - Startup Prior to each reactor startup.

P - Prior Prior to each radioactive release.

N.A.

Not applicable.

Each frequency requirement shall be performed within the specified time interval with the maxirnum allowable extension not to exceed 25% of the frequency interval. The 25% vziance shall not be applied to Operability Action Statements. The bases to Technical Specification 4.0.2 (1.T.S. SR 3.0.2) provide clarifications to this requirement. These frequency notations do not apply l

l to the Radiological Environmental Monitoring P ogram (REMP) as described in Section 12.5.

5 O

12-7

BRAIDWOOD Revision 4 August i998 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation Qperability Reouirements 12.2.1. A The radioactive liquid effluent monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of 12.3.1.A are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

Acolicability: At all times Action 1.

With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above f

specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.

2.

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

Surveillance Reouirements i

12.2.1.B Each radioactive liquid effluent monitoring instrumentation channel shall be l

demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE l

CHECK, CHANNEL CALIBRATION and DIGITAL and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 12.2-2.

Bases 12.2.1.C The radioactive liquid 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 Aiann/ 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 cf General Design Criteria 60,63, and 64 of Appendix A to 10CFR50.

l l

12-8

CRAIDWOOD Revision 4 August 1998 TABLE 12.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1

1.

Radioactivity Monitors Providing Alarm and Automatic Termination of Release a.

Liquid Radwaste Effluent Line (ORE-PR001) 1 31 b.

Fire and Oil Sump (ORE-PR005) 1 34 c.

Condensate Polisher Sump Discharge (ORE-PR041) 1 34 2.

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

Essential Service Water 1)

Unit 1 a)

RCFC 1 A and 1C Outlet (1RE-PR002) 1 32 b)

RCFC 18 and 1D Outlet (1RE-PR003) 1 32 Q(~3 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 Line (Loop-WX001) 1 33 b.

Liquid Radwaste Effluent Low Flow Line (Loop-WX630) 1 33 c.

Station Blowdown Line (Loop-CWO32) 1 33 O'

(v 12 9

BRAIDWOOD Revision 4 August 1998 TABLE 12.2-1 (Continglj RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ACTION STATEMENTS With the number of channels OPERABLE less than required by the Minimum l

• ACTION 31 -

Channels OPERABLE requirement. effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:

At least two independent samples are analyzed in accordance with Section a.

12.3 and At least two technically qualified members of the facility staff b.

independently verify the release rate calculations and discharge line valving.

l If a and b can not be met, suspend releases of radioactive effluents via this pathway.

l With the number of channels OPERABLE less than required by the Minimum

• ACTION 32 -

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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for principal gamma emitters and 1-131 at a lower limit of detection as specified in Table 12.3-1.

With the number of channels OPERABLE less than required by the Minimum l

• ACTION 33 -

Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance curves generated in place may be used to estimate fiow.

With the number of channels OPERABLE less than required by the Minimum l

• ACTION 34 -

Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for principal gamma emitters and 1-131 at a lower limit of detection as specified in Table 12.3-1:

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary a.

coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT l-131, l

OR b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT l-131.

• If effluent releases continue via this pathway beyond the time specified, continue to perform actions and explain in the next Radioactive Effluent Report why the time specified was exceeded.

9 12-10

CRAI

'D Rzvision 4 August 1998 TABLE 12.2-2

. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL ANALOG CHANNEL CHANNEL CHANNEL SOURCE CHANNEL' OPERATIONAL OPERATIONAL INSTRUMENT CHECK CHECK CAllBRATION TEST TEST 1.

Radioactivity Monitors Providing Alarm and AutomaticTermination of Release a.

Liquid Radwaste Effluent Line (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)

Q(1)*

N.A.

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)

D M

R(3)

Q(2)

N.A.

b)

RCFC 18 and 1D Outlet (1RE-PR003)

D M

R(3)

Q(2)

N.A.

2) Unit."-

a)

RCFC 2A and 2C Outlet (2RE-PR002)

D M.

R(3)

Q(2)

N.A.

b)

RCFC 2B and 2D Outlet (2RE-PR003)

D M

R(3)

Q(2)

N.A.

b.

Station Blowdown Line (ORE-PR0")

D M

R(3)

Q(2)

N.A.

3.

Flow Rate Measurement Dev' ices a.

Liquid Radwaste Effluent t

,t.oop-WX001)

D(4)

N.A.

R N.A.

Q 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.

Q 12-11 L

.____.______o

M@anruaa TABLE 12.2-2 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS (1)

The OlGITAL CHANNEL OPERATIONAL TEST shall also deracnstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

Instrument indicates measured levels above the Alarm / Trip Setpoint, OR l

a.

b.

Circuit failure (monitor ioss 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 Monitor loss of sample flow. This is only apolicable for ORE-PR001 and ORE PR005.

e.

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

l (2)

The OlGITAL CHANNEL OPERATIONAL T EST shall also demonstrate that control room alarm annunciation occurs if any of the following canditions exists:

a.

Instrument indicates measured levels above the Alarm Setpoint, OR l

b.

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

Detector check source test failure, OR d.

Detector channel out-of-service, OR l

e.

Monitor loss of semple flow.

(3)

The initial CHANNEL CAllBRATiON shall be performed using one or more of the reference l

standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the inillat 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, l

periodic, or batch releases are made.

l i

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O 12-12 l

BRAIDWOOD Revision 4 August 1990 12.2.2 Radioactive Gaseous Effluent Monitorina instrumentation Operability Reauirements 12.2.2.A The radioactive gaseous effluent monitoring instrumentation channels shown in Table 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.

Apolicability: As shown in Table 12.2-3 6.di9.0 1.

With a radioactive gaseous effluent monitoring 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 inoperable.

2.

With less than the minimum number of radioactive gaseous effluent '

monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2 3. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Annual Radioactive Effluent Release Report pursuant to Section 12.6 why this inopenbility was not corrected within the time specified.

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

Bases 12.2.2.C The radioactive gaseous eff!uent 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 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 10CFR50. The sensitivity of any noble l

gas activity monitor used to show compliance with the gaseous effluent release requirements of Section 12.4 shall be such that concentrations as low as 1x10 4 uCl/cc are measurable.

L 12 13 i.

l l

CRAIDWOOD R: vision 4 l

August 1b98 l

TABLE 12.2-3 I

l RADIO /,CTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l

MINIMUM CHANNELS l

INSTRUMENT OPERABLE APPLICABILITY ACTION l

1.

Plant Vent Monitoring System - Unit 1 a.

Noble Gas Activity Monitor Providing Alarm 1)

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

Low Range (1RE-PR028B) 1 39 b.

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

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

Elfluent 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 12-14

l-O 9,,,

O' ERAl Revision 4 August 1998 j

('

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

MINIMUM CHANNELS I

INSTRUMENT OPERABLE

. APPLICABILITY ACTION 3.

Not Used.

4.

Gas Decay Tank System i

. a.

Noble Gas Activity Monitor-Providing Alarm and AAomatic Termination of Release (ORE-PR002A and 28) 2 35 5.

Containment Purge System a.

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

lodine Sampler.

4 (RE-PR001C) 1 40 c.

Particulate Sampler (RE-PR001 A)'

1 40 6.

Radioactivity Monitors Providing Alarm

[

and Automatic Closure of Surge Tank Vent-Component Cooling Wate-Line (ORE-PR009 and RE-PR009) 2 41 i

l I

12-15 i

R; vision 4 CRAIDWOOD August 1998 TABLE 12.2-3 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATIONS

• At all times.

l

• • ACTION 35 -

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

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

b.

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

If a and b can not be met, suspend releases of radioactive effluents via this pathway.

l

• • ACTION 36 -

With the number of channels OPERABLE less than required by the Minimum l

Channels OPERABLE requirement, effluent releases via this pathway may continue er up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• • ACTION 2 :

With the number of channels OPERABLE less than required by the Minimum l

Channels OPERABLE requirement,immediately suspend PURGING of radioactive effluents via this pathway. Releases may continue via this pathway for up to 7 days provided real time monitoring of radioactive effluents released via this pathway is established.

• • ACTION 38 -

Not used.

• • ACTION 39 -

With the number of channels OPERABLE less than required by the Minimum j

Channels OPER ABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for principle gamma emitters at an LLD as specified in Table 12.41.

• • ACTION 40 -

With it.e number of channels OPERABLE less than required by the Minimum l

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 coritinue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, liquid grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table 12.3-1.

• • If effluent releases continue via this pathway beyond the time specified, continue to perform actions and explain in the next Radioactive Effluent Report why the time specified was exceeded.

O 12-16

o aOD o

BRAI R: vision 4 August 1998 TABLE 12.2-4 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 1.

Plant Vent Monitoring System - Unit 1 a.

Noble Gas Activity Monitor-Providing Alarm 1)

High Range (1RE-PR028D)

D M

R(3)

Q(2) 2)

Low Range (1RE-PR028B)

D M

R(3)

Q(2) b.

lodine Sampler (1RE-PR028C)

D M

R(3)

Q(2) c.

Particulate Sampler (1RE-PR028A)

D M

R(3)

Q(2) d.

Effluent System Flow Rate Measuring D

N.A.

R Q

Device (LOOP-VA019) e.

Sampler Flow Rate Measuring Device D

N.A.

R Q

(1FT-PR165) 2.

Plant Vent Monitoring System - Unit 2 a.

Noble Gas Activity Monitor-Providing Alarm 1)

High Range (2RE-PR028D)

D M

R(3)

Q(2) 2)

Low Range (2RE-PR028B)

D M

R(3)

Q(2) b.

todine Sampler (2RE-PR028C)

D M

R(3)

Q(2) 12-17 9

BRAIDWOOD R: vision 4 August 1998 TABLE 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 CAllBRATION TEST IS REQUIRED

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

Particulate Sampler (2RE-PR028C)

D M

R(3)

Q(2) d.

Effluent System Flow Rate Measuring D

N.A.

R Q

Device (LOOP-VA020) e.

Sampler Flow Rate Measuring Device D

N.A.

R Q

(2FT-PR165)

3. Not Used

4. Gas Decay Tank System a.

Nobie Gas Activity Monitor P

P R(3)

Q(1)"

Providing Alarm and Automatic Termination of Release (0RE-PR002A and 2B)

5. Containment Purge System a.

Noble Gas Activity Monitor-Providing Alarm (RE-PR001B)

D P

R(3)

Q(2) b.

lodine Sampler (RE-PR001C)

P P

R(3)

N.A.

c.

Particulate Sampler (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)

Q(1)

O Ge e

.. _ =, _ -. - -. - - - - -. -. -.... _ _ -.. - - -. - - -. -. -,

BRAIDWOOD Rsvision 4 August 1998 s

TABLE 12.2-4 (Continued)

RADIOACTIVE GASEOUS EFi-LUENT MONITORING INSTRUMENTATION l

SURVEILLANCE REQUIREMENTS TABLE NOTATIONS At all times.

(1)

The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurif any of the following conditions exists:

a.

Instrument indicates measured levels above the Alarm / Trip Setpoint, OR l

b.

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

c.

Detector check source test failure, OR l

d.

Detector channel out-of-service, OR ll e.

Monitor loss of sample flow. Monitoring ORE-PR002A and 2B will not trip on loss of 1

sample flow.

(2)

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

.Q g

a.

Instrument indicates measured levels above the Alarm Setpoint, OR j

. b.

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

c.

Detector check source test failure, OR l,

d.

Detector channel out-of-service, OR l

e.

Monitorloss of sample flow.

(3)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

.(4)

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

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

C i

12-19

_. ~. _ _

August 1@@@

12.3 LlOUlD EFFLUENTS 12.3.1 Concentration Ooerability Reauirements The concentration of radioactive material released in liquid effluents to 12.3.1.A UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited to 10 times the concentration values in Appendix B, l

Table 2, Column 2 to 10CFR20.1001-20.2402, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2x10" microcurie /mi total activity.

Applicability: At all times Action With the concentration of radioactive material released in liquid effluents 1.

to UNRESTRICTED AREAS exceeding the above limits,immediately restore the concentration to within the above limits.

Surveillance Reauirements l

Radioactive liquid wastes shall be sampled and analyzed according to the 12.3.1.B.1 sampling and analysis program of Table 12.3-1.

f l

The results of the radioactivity analysis shall be used in accordance with the 12.3.1.B.2 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 This section is provided to ensure that the concentration of reicactive materials 12.3.1.C released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the concentration values in Appendix B. Table 2, Column 2 to 10CFR20.1001-20.2402. 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 1,10CFR50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10CFR20.1301.

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

12-20

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

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

l BRAIDWOOD Ravision 4 August 1998 12.3 LIQUID EFFLUENTS (Continued)

Bases The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (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., " Detection l

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

l t

l l

1iL i

l

'! v i

12-21

August 1998 TABLE 12.2-1 RADIOACTIVE LIQU!D WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM ANALYSIS TYPE OF ACTIVITY LOWER LIMIT OF LIQUID RELEASE SAMPLING TYPE FREQUENCY FREQUENCY ANALYSIS DETECTION (LLD)'"

(pCl/mi) 1.

Batch Release P

P Principal Gamma 5x10

Tanks *'

Each Batch Each Batch Emitters

l-131 1 x10

4 P

M Dissolved and Entrained 1x10 One Batch /M Gases (Gamma Emmers)

(7) 4 P

M H-3 1x10 Each Batch Composite (

Gross Alpha 4 x10-#

4 P

Q Sr-89. Sr-90 5x10 Each Batch Composite )

4 Fe-55 1x10 W

Principal Gamma 5x10

2.

Continuous Releases

Continuous #'

Composite '

d l-131 1x1(i' 4

a.

Circulating Water M

M Dissolved and Entrained 1x10 Gases (Gamma Emrtters)*

Blowdown Grab Sample 4

b.

Waste Water M

H-3 1x10 d

Continuous *'

Composite '

0 r b Circulating Water Discharge Gross Alpha 1 x10

4 c.

Condensate Continuous *'

Q Sr-89, Sr-90 5x10 d

Polisher Sump Composite '

Discharge Fe.'3 1 x10

O 12-22

BRAIDWOOD Rsvision 4 August 1998 TABLE 12.3-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID SAMPLING MINIMUM TYPE OF ACTIVITY LOWER LIMIT RELEASE TYPE FREQUENCY ANALYSIS ANALYSIS OF DETECTION FREQUENCY (LLD)'"(pCi/ml)

3. Continuous W*

W Principal Gamma 5x10'7 W

Release

• Grab Sample EmittersA Essential Service Water Reactor Containment Fan Cooler (RCFC) Outlet Line 4

1-131 1x10 H-3 1x10'5 iMW Dissolvr,d and 1x10'5 Entrahied Gases (Gamma Emitters)W g

4. Continuous None None Principal Gamma 5x10~7 i

Surge Tank Emitters

• Vent-Component Cooling Water Line

• Dissolved and 1x10'5 Entrained Gases (Gamma Emitters)*

4 l-131 1x10 i

l'V) 12-23

LdiML%dsL%D August 1998 TABLE 12.34 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (1)

The LLD is defined, for purposes of these sections. as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD =

4.66s3 E V 2.22 X10 Y exp (-AAt) l 5

Where:

LLD = the lower limit of detection (microCuries per unit mass or volume),

so = 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),

8 2.22 X10 = 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.

Attemative LLD Methodoloav An attemative methodology for LLD determination follows and is similar to the above LLD equation:

(2.71 + 4.65VB) Decay LLD =

Eq b Y t (2.22 X10 )

l 8

12-24

-,~.

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

l l

i BRAIDWOOD Rsvision 4 August 1998 TABLE 12.3-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM l

TABLE NOTATIONS Where:

t B = background sum (counts)

E = counting efficiency, (counts detected / disintegration's).

I l

q = sample quantity, (mass or volume) b = abundance, (if applicable)

Y = fractional radiochemical yield or collection efficiency, (if applicable) l t = count time (minutes) 8 2.22X10 = number of disintegration's per minute per microcurie l

I 2

2.71 + 4.65VB = k + (2k V 2 V B), and k = 1.645.

(k=value of the t statistic from the single-tailed t distribution at a significance level l

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

Decay = e*^' [ ART /(1-e'*")] [ATo/(1-e'*")], (if applicable)

A = radioactive decay constant, (un!te consistent with At, RT and Ta)

At = " delta t', or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample, (units consistent with A)

RT= elapsed real time, or the duration of the sample count, (units consistent with 1)

To = sample deposition time, or the duration of analyte collection onto the sample media, (units consistent with A)

' The LLD may be determined using installed radioanalytical software,if available, in addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e. during sample collection, from sample collection to start of analysis and during counting), this l

altemate method will result in a more accurate determination of the LLD.

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

O 12-25

Revision 4

{

BRAIDWOOD August $998 l

l TABLE 12.31 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTAT'ONS A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for (2) analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

l (3)

A composite sample is one in which the quant 2y of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(4)

A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a l

volume of a system that has an input flow during the continuous release.

(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.

(6)

Not required unless the Essential Service Water RCFC Outlet Radiation Monitors RE-PR002 and 4

RE-PR003 indicates measured levels greater than 1x10 Cl/ml above background at any time during the week.

(7)

The principal gamma emitters for which the LLD 3pecification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for dissolved and entrained for principal gamma emi".ers. 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 outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(8)

A continuous release is the discharge of dissolved and entrained gaseous waste from a l

nondiscrete liquid volume.

l O

12-26

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

BRAIDWOOD Revision 4 August 1998 12.3.2 Quig O

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

1.

During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and 2.

During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

Anal!Mbility: At all times.

Action 1.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the l

Commission within 30 days, pursuant to 10CFR50 Appendix 1,Section IV.A. a l

l.

Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

Surveillance Reauirements 12.3.2.8 Cumulative dose contnoutions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology l

and parameters in the ODCM at least once per 31 days.

l l

Bases l

12.3.2.C This section is provided to implement the requirements of Sections ll.A, Ill.A and IV.A l

of Appendix 1,10CFR50. The Operability Requirements implement the guides set l

l forth in Section li.A of Appendix 1. The ACTION statemerits provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The i

dose calculation methodology and parameters in the ODCM implement the l

requirements in Section Ill.A of Appendix 1 that conformance with the guides of l

Appendix i be shown by calculational procedures based on models and data, such that l.

the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is I

unlikely to be substantially underestimated.

The equaticas specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in 1: quid 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 10CFR50, Appendix I" Revision 1, October 1977 and Regulatory l

l Guide 1.113," Estimating Aquatic Dispersion of Effluents from Accidental and Routine l

Reactor Releases for the Purpose of Implementing Appendix 1," April 1977.

i O

12-27

BRAIDWOOD Revision 4 August 1998 12.3.2 Dose (Continued)

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 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, a.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 u.iits sharing the Radwaste Treatment System. For determining conformance to Operability Requirements, these allocations from shared Radwaste Treatment Sy items are to be added to the releases specifically attributed to each unit to obtain the total releases per unit.

1 0'

O 12-28

~ ~. - - - -

BRAIDWOOD Revision 4 August 1998 12.3.3 Ljayjg Radwaste Treatment System Operability Reauirements 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Braidwood Station ODCM Annex, Appendix F, Figure F 1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

Apolicability: At all times.

Action 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 10CFR50 Appendix 1,Section IV.A, a Special Report that includes the l

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.

Surveillance Reouirements 12.3.3.B.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be l

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.B.2 The installed Liquid Radwaste Treatment System shall be considered l

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

Bases 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This section implements the requirements of 10CFR50.36a, General Design Criterion 60 of Appendix A to 10CFR50 and the design obje ;tive given in Section 11.0 of Appendix I to 10CFR50.

O 12-29

)

BRAIDWOOD Revision 4 August 1998 12.3.3 Liould 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 dase design objectives set l

forih in Section ll.A of Appendix 1,10CFR50, 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 she, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releaces 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 i

l l

l O

i l

I 12-30 l

_ __.. _.m.

BRAIDWOOD Revision 4 August 1998 12.4 GASEOUS EFFLUENTS O

l O

12.4.1 Dose Rate Ooerability Reouirements j

12.4.1.A The dose late due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (sse Braidwood Station ODCM Annex, Appendix F, Figure F 1) shall be limited to the following:

4 1.

For noble gases: less than or equai to a dose rate of 500 mrems/yr to the j

whole body and less than or equal to a dose rate of 3000 mrems/yr to the skin, and 2.

For lodine 131 and 133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr j

to any organ.

Anolicability: At all times.

A.ction-1 i

1.

With the dose rate (s) exceeding the above limits, immediately restore the

)

release rate to within the above limit (s).

)

i Surveillance Reouirements p

12.4.1.B.1 The dose rate due to noble gases in gaseous effluents shall be determined to be l

within the above limits in accordance with the methodology and parameters in the ODCM.

i 12.4.1.B.2 The dose rate due to lodine 131 and 133, tritium, and all radionuclides in particulate l

form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the

.ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.41.

Hasas 12.4.1.C This section is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR20. These limits provide reasonabl3 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.

t 12 31

3-August 1998 l

12.4 GASEOUS EFFLUENTS (Continu:d)

Bases 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 restnct, 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 mrems/ 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 mrems/ year.

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

The required detection capabilities f or 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 Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40,586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

O O

12-32

-. =

BRAIDWOOD Revision 4 l

August 1998 TABLE 12,41 BADIOACTIVE GASEOUS WASTE SAMPLING AND ANAL.YSIS PROGRAM GASEOUS SAMPLING MINIMUM TYPE OF ACTIVITY LOWER LIMIT l

RELEASE TYPE FREQUENCY ANALYSIS ANALYSIS OF DETECTION l

FREQUENCY (LLD)") (pCl/cc) l l

1.

Waste Gas P

P Principal Gamma 1x10" t2 Decay Tank Each Tank Each Tank Emitters )

Grab Sample l

t d

2.

Containment P

P Principal Gamma 1x10 Puge Each Purge (')

Each Purge (3)

Emitters m Grab Sample H-3 1x10

3.

Auxiliary Bldg.

M WS M

Principal Gamma 1x10" l

Vent Stack Grab Sample Emitters (2) l (Unit 1 and 2)

H-3 1x10'7 Continuous (*

W W 1-131 1x10a2 Charcoal Sample-l-133 1x10"0 Continuous (S WA Principal Gamma 1 x10'"

Particulate Emitters

• Sample Continuous (0 Q

Gross Alpha 1 x10'"

Composite Particulate Sample I

Continuous (*

Q Sr-89, Sr-90 1x10'"

Composite Particulate Sample 4

Continuous N.A.

Noble Gases, Gross 1x10 Beta or Gamma Monitor

' /%

12-33

CRAIDWOOD kvision 6 August 1998 TABLE 12.4-1 (Continued)

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 material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD =

4.66S.,

l E V 2.22 X10 Y exp (lat)

Where:

LLD = the lower limit of detection (microCuries per unit mass or volume),

s = the standard deviatinn of the background counting rate or of the counting rate of a o

blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

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

l 2.22X10 = the number of disintegrations per minute per microcurie, l

8 Y = the fractional radiochemical yield, when applicable, A= the radioactive decay constant for the particular radionuciide (sec ), and l

At = the elapsed time between the midpoint of samole collection and the time of counting (sec).

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

Attemate LLD Methodolooy l

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

(2.71 + 4.65YB) Decay LLD =

8 E q b Y t (2.22 X10 )

l l

O 12 34

l CRAIDWOOD Revision 4 August 1998 TABLE 12.4-1 (Cc.itinued) l g

RADIOACTIVE GASEOl'S WASTE SAMPLING AND ANALYSIS PROGRAM I

TABLE NOTATIONS Wh9re:

B = background sum (counts)

E = counting efficiency, (counts detected / disintegrations) l q = sample quantity, (mass or volume) b = abundance, (if applicable)

Y = fractional radiochemical yield or collection efficiency, (if applicable) t = count time (minutes) 8 2.22 X10 = number of disintegrations per minute per microcurie l

2 (2.71 + 4.65VB) = k + (2k V 2 V B), and k = 1.645.

(k=value of the t statistic from the single-tailed t distribution at a significance level of 0.95 and infinite degrees of freedom. This means that the LLD result represents l

a 95% detection probability with a 5% probability of falsely concluding that the nuclide present when it is not or that the nuclide is not present when it is.)

Decay = e*^' (ART /(1-e#)) [ATo /(1-e*'8)], (if applicable)

A = radioactive decay constant, (units consistent with At, RT and To)

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

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

To = sample deposition time, or the duration of analyte collection onto the sample media, (unit consistent with A)

The LLD may be determined using installeJ radioanalytical software, if available in addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform deccy corrections (i.e. during sample collection, from sample collection to start of analysis and during counting), this attemate method will result in a more accurate determination of the LLD.

It should be recognized that the 1,LD is defined as a before the fact limit and not as an after the fact limit for a particular measurement.

i v

i 12-35

BRAIDWOOD Rsvision 4 August 1998 TABLE 12.4-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS (2)

The pr'ncipal 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-99,1-131, 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 those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report pursuant to Section 12.6.2, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3)

Sampling and analysis shall also be perfomled following sinutdown, startup, or a THERMAL.

POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.

j (4)

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.

(5)

Tritium grab samples shall be taken at least once per 7 days from the soent 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.

O (7)

Samples shall be changed at least once per 7 days and analyses shall be completed within a 1

timeframe necessary to meet the applicable lower limits of detection, but not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each l

I shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period and analyses shall be completed within a tim 6 frame necessary to meet the applicable lower limits of detection, but not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

O 12-36

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l BRAIDWOOD Revision 4 August 1998 12.4.2 pose - Noble Gases k

Ooerability Reouirements l

12.4.2.A The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE 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 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and 2.

During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

i Aoolicability:

At all times.

A_!gon' 1,

With the calculated air dose from radioactive noble gases in gaseous effluents j

exceeding any of the above limits, prepare and submit to the Commission within 30 l

days, pursuant to 10CFR50 Appendix 1,Section IV.A, a Special Report that identifies I

i the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

Surveillance Reouirements

(

12.4.2.B Cumulative dose contributions for the current calendar quarter and the current

'g]

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

Bases 12.4.2.C This section is provided to implement the requirements of Sections ll.B, Ill.A and IV.A of Appendix 1,10CFR50. The Operability Requirements implement the guides set l

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 IV.A of Appendix l to assure that the releases of radioactive material in gaseous effluents to area at or beyond the SITE BOUNDARY will be kept "as low as is reasonable achievable," The Surveillance Requirements implement the requirements in Section Ill.A of Appendix l that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

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12-37

BRAIDWOOD KGRamTt)

August 1998 12.4.2 Dose - Noble Ga es (Continu:d) s 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 1.109," Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10CFR50, Appendix I" l

Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, Revision 1," July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY 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.

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1 BRAIDWOOD Revision 4 August 1998 12.4.3 Dose - lodine I-131 and 133. Tritium. and Radioactive Material in Farticulate Form Operability Reauirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from todine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see l

Braidwood Station ODCM Annex, Appendix F, Figure F-1) shall be limited to the l

following:

1.

During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and l

2.

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

l ADolicabilltv At all times.

M19.0:

1.

With the calculated dose from the release of lodine-131 and 133, tritium, and j

radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10CFR50 Appendix 1,Section IV.A, a l

1 Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

Surveillance Reauirements 12.4.3.B Cumulative dose contributions for the current calendar quarter and the current calendar year 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 12.4.3.C This section is provided to implement the requirements of Sections ll.C, Ill.A and IV.A of Appendix 1,10CFR50. The Operability Requirements are the guides set forth in l

Section ll.C 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 I to assure that the releases of radioactive material in gaseous effluents to areas at or beyond the SITE BOUNDARY will be kept "as low as is reasonable achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section lit.A of Appendix 1 that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substant! ally underestimated.

O 12 39

CRAIDWOOD Rr, vision 4 August 1998 12.4.3 Dose (Continued)

Bases The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology l

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 i

10CFR50, Appendix I" Revision 1, October 1977 and Regulatory Guide 1.111, l

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents l

In Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.

These equations also provide for determining the actual doses based upon the l

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 pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the l

development of these calculations were: (1)individualinhalation of airbome radionuclides, (2) deposition of radionuclides onto green leafy vegetation with j

subsequent consumption by man, (3) deposition onto grassy areas where milk animals j

and meat producing animal's graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure to man.

7 l

l This section applies to the release of radioactive materials in gaseous effluents from l

each unit at the site. When shared Radwaste Treatment Systems are used by more l

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 i

estimate should be made of the contnbutions 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.

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BRAIDWOOD Revision 4 August 1998 12.4.4 Gaseous Radwaste Treatment System d

Operability Reauirements 1

12.4.4.A The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Braidwood Station ODCM Annex, Appendix F, Figure F-1) would i

exceed:

1.

0.2 mrad to air from gamma radiation, or l

2.

0.4 mrad to air from beta radiation, or 3.

0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

1 Acolicability: At all times.

Action:

1.

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to 10CFR50 Appendix 1,Section IV.A, a Special Report that l

Includes the following information:

f a.

Identification of any inoperable equipment or subsystems, and the

/~

reason for the inoperability,.

b.

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

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

Surveillance Reauirements 12.4.4.B.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE l

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

methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.

12.4.4.B.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS l

HOLDUP SYSTEM shall be considered OPERABLE by meeting Section 12.4.1 or 12.4.2 and 12.4.3.

Bases l

12.4.4.C The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION i

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

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

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l 12-41

s BRAIDWOOD Revision 4 August 1998 12.4.4 Gaseous Radwaste Trestment System (Continued) fases The requirement that the appropriate portions of this system be used when specified provides ressonable assurance that tha releases of radioactive materials in gaseous effluents will be kept "as low as is reasonabiy achievable" This section implements the requirements of 10CFR50.36a, General Design Criterion 60 of Appendix A to 10CFR50 and the design objective given in Section ll.D of Appendix I to 10CFR50.

The specified limits goveming the use of a,,oropriate portions of the Gaseous Radwaste Treatment System were specified as a 2% fraction of the dose design l

objectives set forth in Section ll.B and ll.C of Appendix 1,10CFR50, for gaseous effluents.

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 release per unit.

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l BRAIDWOOD Rsvision 4 August 1998 12.4.5 Total Dose I b l V Ooerability Reauirements 12.4.5.A The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

Apolicability: At all times.

Action:

1.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Sections 12.3.2,12.4.2, or l

12.4.3, calculations should be made including direct radiation contributions j

from the units and from outside storage tanks to determine whether the above limits of Section 12.4.5.A have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, a Special Report that defines l

the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10CFR20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar 1

year that includes the release (s) covered by this report. It shall also desenbe levels of radiation and concentration of radioactive materialinvolved, and the l O cause of the exposure levels or concentrations. If the estimated dose (s) l exceeds the above limits, and if the release condition resulting in violation of 40CFR190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFR190.

Submittal of the report is considered a timely request, and a variance is j

granted until staff action on the request is complete.

Surveillance Reauirements 12.4.5.B.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined l

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

12.4.5.B.2 Cumulative dose contributions from direct radiation from the units and from radweste l

l storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in ACTION 1 of Section 12.4.5.A.

12.4.5.B.3 Initial estimates of expected dose rates at the Old Steam Generator Storage Facility l

(OSGSF) are provided through calculations. After the old steam generators are placed in the facility and the equipment opening is sealed, a radiation survey of the walls and roof will be performed. The measured dose rates will be used for comparison to the calculated dose rates and to confirm or adjust the initial estimates for use in 10CFR20,10CFR50 Appendix 1, and 40CFR190 compliance j

determinations.

d 12-43 1

1-Levuem August 1998 12.4.5 Total Dose (Continued)

Surveillance Reauirements Environmental TLDs are located near the OSGSF. The TLDs are prccessed quarterly to determine the dose at the locations for use in comphance determinations.

Quarterly monitoring of the sump for indications of liquid is performed and, if liquid is present and seepage appears to have occurred, a sample will be taken and analyzed.

Bases 12.4.5.C.1 This section is provided to meet the dose limitations of 40CFR190 that have been incorporated into 10CFR20 by 46FR18525. 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 40CFR190 if the individual reactors remain within twice the dose design objectives of l

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 to a MEMBER OF THE PUBLIC to within the 40CFR190 limits. For the purposes of the Special Report, it may be assumed that l

the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40CFR190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40CFR190 have not already been corrected),in accordance with the provisions of 40CFR190.11 and 10CFR20.2203, is considered to be a timely request and fulfills the requirements of 40CFR190 until NRC staff action is completed. The variance only relates to the limits of 40CFR190, and does not apply in any way to the other requirements for dose limitation of 10CFR20, as addressed in Sections 12.3.1 and 12.4.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

12.4.5.C.2 The OSGSF was constructed to provide long-term storage of the four old steam generators removed from Braidwood Station Unit 1 during the Steam Generator Replacement Outage. The facility is designed to ensure that the dose rates at the wall and roof meet the limits of 10CFR20 (UFSAR Zone 1-A for the walls and Zone 1-B for the roof). The facility is also designed to ensure that the dose rates at the site boundary and to the nearest resident meet the limits of 10CFR20 and 40CFR190.

The OSGSF design includes 2'-6" thick concrete walls and 1'-6" inch thick concrete roof. Personnel access is through a labyrinth-style vestibule with a locked exterior door and a lockable sliding door for access beyond the vestibule to the interior of the facility. A water collection sump is provided with access from the vestibule for sampling water if liquid is present. The opening used for placement of the steam generators inside the facility will be sealed with concrete panels. The panels have a tongue and groove design to preclude radiation " shine" after installation.

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12-44 1

1

BRAIDWOOD Revision 4 August 1998 12.4% Total Dose (Continued)

Bases The potential for radiological release from the OSGSF is also minimized by sealing openings in the steam generators caused by removed piping with welded structural cover plates or seal plugs. Trunnions installed during removal of the old steam generators from the containment and existing opening covers remain attached to the steam generators to ensure the penetrations are leaktight. Extemal exposed surfaces cf the steam generators are coated to seal and fix surface contamination to the steam generators.

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12-45

1 BRAIDWOOD Revision 4 August 1998 12.4.6 Dose Limits for Members of the Public Operability Reouirements 12.4.6. A The licensea shall conduct operations such that the TEDE to individual MEMBERS OF THE PUBLIC does not exceed 100 inrem in a year. In addition, the dose in any unrestrictec area from extemal sources does not exceed 2 mrem in any one hour. The Effluents Program shallimplement monitoring, sampling and analysis of radioactive liquid and gaseous effluents in accordance with 10CFR20.1302 and with the methodology and parameters in the ODCM.

6policabilitv: At all times.

Action:

1.

If the calculated dose from the release or exposure of radiation meets or exceeds the 100 rirem/ year limit for the MEMBER OF THE PUBLIC, prepare and submit a report the Commission in accordance with 10CFR20.2203.

2.

If the cose in any unrestricted area from extemal sources of radia!!on meets or exceeds the 2 mrem in any one hour limit for the MEMBER OF THE PUBLIC, l

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

Surveillance Reauirements 12.4.6.B Calculate the TEDE to individual MEMBERS OF THE PUBLIC annually to determine compliance with the 100 rrwem/ year limit in accordance with the ODCM. In addition, evaluate and/or determine if direct radiation exposures exceed 2 mrem in any hour in unrestricted areas.

Bases 12.4.6.C This section applies to direct exposure of radioactive materials as well as radioactive materials released in gaseous and liquid effluents.10CFR20.1301 sets forth the 100 mrem / year dose limit to members of the public; 2 mrem in any one hour limit in the unrestricted area; and reiterates that the licensee is a!so required to meet the 40CFR190 standards.10CFR20.1302 provides options to determine compliance to l

10CFR20.1301. Compliance to the above operability requirement is based on 10CFR20 and 40CFR190.

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12-46

BRAIDWOOD Revision 4 August 1998 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i

12.5.1 Monitorino Prooram Operability Reouirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.

l Aoolicability: At all times.

1 Action 1.

With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Section 12.6.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of sampling equipment, if a person / business who participates in this program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person / business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule will be described in the Annual Radiological Environmental Operating Report.

2.

With the level of radioactivity as the result of plant effluents in an environmental r

sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to 10CFR50 Appendix 1,Section IV.A, a l

Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

• to a MEMBER OF THE PUBLIC is less than the calendar yearlimits of Section 12.3.2,12.4.2, or 12.4.3. When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2) +.. >1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 12.5 2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose

• to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2,12.4.2, or 12.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Section 12.6.1.

I

• The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

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ggewom August 1998 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continu:d) 3.

If the sample type or sampling location (s) as required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the pathway of interest and/or specific sampling locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the monitoring program, Prepare and submit a controlled version of the ODCM within 180 days including a revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and Justifying the selection of new location (s) for obtaining samples.

Surveillance Reauirements 12.5.1.B The radiological environmental monitoring program samples shall be collected pursuant to Table 12.5-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 12.5-1 and the detection capabilities required by Table 12.5-3.

Bases 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclide? that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10CFR50 and thereby supplements the radiological effluent monitoring program by l

verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective i

for at least the first 3 years of commercial operetion. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be fotnd in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal.

Chem. 40. 586-93 (1968), and Hartwell, J.K.," Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).s O

12-48

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BRAIDWOOD Revision 4 August 1998 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

Interpretations 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply i

downstream of the plant within 10 kilometers." Drinking water suppiy is defined as water taken from rivers, lakes, or reservoirs (not well water) which is used for drinking.

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R: vision 4 BRAIDWOOD August 1998 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION

'IYPE AND AND SAMPLE LOCATIONS")

FREQUENCY FREQUENCY OF ANDI OR SAMPLE ANALYSIS

1. Airbome Samples from a total of eight locations:

Continuous sampler operation Radiciodine Canister.

with particulate sample I-131 analysis biweekly Radiciodine and Particulates

a. Indicator-Near Field collection weekly (or more on near field samples frequently if required due to dust and control.A Four samples from locations within 4 km (2.5 mi) loading), and radioiodine canister collection biweekly.

Particulate Samoler.

in different sectors.

Gross beta analysis

b. Indicator-Far Field following weekly filter change"and gamma isotopic analysis"'

Three additional locations within 4 to 10 km (2.5 quarterly on composite to 6.2 mi) in different sectors.

filters by location on near field samples and

c. Control c itrol.A One sampl3 from a controllocation within 10 to 30 km (6.2 to 18.6 mi).

12-50 9

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BRAI Revision 4 August 1998 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATNE SAMFLES SAMPLING AND COLLECTION TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONSW FREQUENCY FREQUENCY OF ANALYSIS

2. Direct Forty routine monitoring stations either with a Quarterfy Gamma dose on each Radiation" thermoluminescent dosimeter (TLD) or with one TLD quarterly.

Instrument for measuring dose rate continuously, j'

placed as follows:

a. Indicator-Inner Ring (100 Series TLD)

One in each meteorological sector, in the general area of the SITE BOUNDARY (0.1 to 3.8 miles);

i

b. Indicator-Outer Ring (200 Series TLD)

One in each meteorological sector, within 6.1 to 10 km (3.8 to 6.2 mi); and

c. Other One at each Airbome location given in part 1.a.

and 1.b.

The balance of the TLDs to be placed at special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access.

(300 Series TLD) l i

12-51

- _- ~

BRAIDWOOD R; vision 4 August 1998 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONS"3 FREQUENCY FREQUENCY OF ANALYSIS

2. Direct

d. Control Quarterly Gamma dose on each Rad]ation* (Cont'd)

TLD quarterly.

One at each Airbome controllocation given in part 1.c

3. Waterbome

a. Indicator Quarterly Gamma isotopic") and

a. Ground / Well tritium analysis quarterly.

Samples from two sources only if likely to be affected.*

b. Drinking *

a. Indicator Weekly grab samples.

Gross beta and g"amma isotopic analyses )on One Sample from each community drinking monthly composite; water supply that could be affected by the tritium analysis on quarterly composite.

station discharge within 10 km (6.2 mi) downstream of discharge.

c. Surface if no community water supply (Drinking Water)

Weekly grab samples.

Gross beta and g"amma Water

• exists within 10 km downstream of discharge isotopic analyses ) on then surface water sarnpling shall be performed.

monthly composite; tritium analysis on

a. Indicator quarterly composite.

One sample downstream

d. Contrv

a. Control Weekly grab samples.

Gross beta and g"amma Sarr ale

• isotopic analyses ) on One surface sample upstream of discharge.

monthly composite; tritium analysis on quarterly composite.

G

't 4

BRAI D

Rsvision 4 August 1998 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONS")

FREQUENCY FREQUENCY OF ANALYSIS

e. Sediment

a. Indicator Semiannually.

Gamma isotopic analysis") semiannually.

At least one sample from downstream (7) area within 10 km (6.2 mi).

4. Ingestion

a. Indicator Biweekly (* when animals are Gamma isotopic") and 03 on pasture (May through l-131 analysis on each

a. Milk'8)

Samples from milking animals from a October), monthly at other times sample.

maximum of three locations within 10 km (6.2 (Novemberthrough April).

mi) distance.

b. Control One sample from milking animals at a control location within 10 to 30 km (6.2 to 18.6 mi).

b. Fish

a. Indicator Two times annually.

Gamma isotopic analysis"3 on edible Representative samples of commerdally and portions recreationally important species in discharge area.

~

b. Control Representative samples of commercially an't recreationally important species in control

!ocations upstream of discharge.

L 12-53

BRAIDWOOD R: vision 4 August 1998 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPliESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND ANDI OR SAMPLE AND SAMPLE LOCATIONS"I FREQUENCY FREQUENCY OF ANALYSIS

c. Food Products

a. Indicator Annually Gamma isotopic"I analysis on each sample.

Two representative samples from the principal fr.od pathways grown in each of four major quadrants within 10 km (6.2 mi):

At least one root vegetable sample""

At least one broad leaf vegetable (or vegetation)"U

b. Control Two representative samples similar to indicator samples grown wl thin 15 to 30 km (9.3 to 18.6 mi).

G

'1D e

BRAIDWOOD Revision 4 August 1998 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1)

Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 12.5-1 of the ODCM Station Annexes. Refer to NUREG-0133,

" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, i

November 1979.

(2)

Far field samples are analyzed when the respective near field sample results are inconsistent with previous measurements and radioactivity is confirrned as having its origin in airbome effluents from the station, or at the discretion of the Radiation Protection Director.

(3)

Airbome particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(4)

Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station.

l (5)

One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation. The 40 locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to gec;;aphical limitations; e.g., If a station is adjacent to a lake, lO some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to l

obtain optimum dose information with minimal fading.

(6)

Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

l (7)

The " downstream" sample shall be taken in an area beyond but near the mixir.g zone. The i

" upstream sample" shall be taken at a distance beyond significant influence of the discharge. Upstream samples in an estuary must be taken far enough upstream to be beyond the station influence.

(8)

If milking animals are not found in the designated indicator locations, or if the owners decline to participate in the REMP, all milk sampling may be discontinued.

(9)

Biweekly refers to every two weeks.

t l

(10) 1-131 analysis means the analytical separation and counting procedure are specific for this l

radionuclide.

1 (11)

One sample shall consist of a volume / weight of sample large enough to fill contractor specified container.

O V

12 55

Revision 4 BRAIDWOOD Augut 1998 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CCNCENTRATIONS IN ENVIRONMENTAL SAr.PLES REPORTING LEVELS WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/I)

OR GASES (pCi/m )

(pCi/kg, wet)

(pCi/l)

(pCi/kg, wet)

W H-3 20,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co40 300 10,000 Zn-65 300 20,000 l

Zr-Nb95 400 1-131 0.9 3

100

A Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCill may be used.

1 (2) If no drinking water pathway exists, a value of 20 pCi/l may be used.

12-56

~

BRAI D

Revision 4 August 1998 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS"3 i

LOWER LIMIT OF DETECTION (LLD)*')

WATER AIRBORNE PARTICULATE -

FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCill)

OR GASES (pCi/m')

(pCi/kg, wet)

(pCi/I)

(pCi/kg, wet)

(pCi/kg, dry)

Gross Beta 4

0.01 1000 M

H-3 2000 i

Mn-54 15 1?0

?

Fe-59 30 200 Co-58,60 15

'30 Zn-65 30 260 Zr-Nb-95 15 83 03 l-131 1/15"3 0.07 100 0.5/5 60 Cs-134 15 0.01 100 15 60 150 Cs-137 18 0.01 100 18 80 190 t

Ba-La-140 15 15 t

h 12-57 t

i

BRAIDWOOD Rsvision 4 August 1998 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1)

The nuclides on this list are not tne only nuclides intended to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

(2)

Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3)

The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the s.nat. st concentration of radioactive materialin a sample that will yield a net count, above system L.ickg ound, that will be detected with 95% probability with only 5% probability of falsely co.1cluding that a blank Observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows:

4.66 So + 3/to LLD =

(E) (V) (2.22) (Y) (exp (-AAt))

4.66 So LLD ~

(E) (V) (2,22) (Y) (exp (-AAt))

Where: 4.66 So >> 3/to i

l LLD = the "a priori" Minimum Detectable Concentration (picoCuries per unit mass or volume),

1

= the standard deviation of the background counting rate or of the counting rate of a blank sample, as l

so appropriate (counts per minute),

l JTotalCounts is l

E

= the counting efficiency (counts per disintegration),

V

= the sample size (units f mass or volume),

l 2.22 = the number of disintegrations per minute per picocurie, Y

= the fractional radiochemiuil yield, when applicab'e, o

A

= the radioactive decay constant for the particular radionuclide (sec ),

l O

12-58

i BRAIDWOOD Revision A l

Augu;t 1998 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS to

= counting time of the background u blank (minutes), and At = the elapsed time between sample collection, or end cf the sample collection period, and the time of counting (sec).

Typical values of E, V, Y, and At should be used in the calculation, it should be recognized that the LLD is defined as a before the fact limit representir g the capability of a measurement system and not as an after the fact limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.

Oceslanally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmenta! Operating Report.

(4) If no drinking water pathway exists, the value of 15 pCl/l may be used.

(5) A value of 0.5 pCi/l shall be used when the animals are on pasture (May through October) and a value of 5 pCl/l shall be used at al.' other times (November through April).

(6) This LLD applies only when the analytical separation and counting procedure are specific for this radionuclide (7) This LLD is the minimum allowable, however, vendors perfonning environmental sample analyses off.

site will be required to meet an LLD of 200 pCl/l.

i t) l l

12-59

Revision 4 BRAIDWOOD August 1998 12.5.2 Land Use Census Ooerability Reaufrements 12.5.2.A.

A Land Use Census shall be conducted and shallidentify within a distance of 10 km (6.2 miles) the location in each cf the 16 meteorological sectors

• O f the nearest milk animal, the nearest residence", and an enumeration of livestock. For dose calculation, a gcrden will be assumed at the nearest residence.

Acolicability: At all times.

Action:

1. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location (s) within 30 days to the Radiological Environr.1 ental Monitoring Program given in Chapter 11. The sampling location (s), excluding the control location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change in sampling locations.

• This requirement may be reduced according to geographical limitations; e.g. at a lake site where some sector's will be over water.

"The nearest industrial facility shall also be documented if closer Surveillance Reauirements 12.5.2.8 The Land Use Census shall be conducted during the growing season, between June 1 and October 1, at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating sReport.

1 i

Bases 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the l

SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 of Appendix 1 to 10CFR50. An l

annual garden census will '10t be required since tu licensee ws assume that there is a garden at the nearest residence in each sector for dose calculations.

l l

l l

O l

l 12-60 l

l

ERAIDWOOD Revision 4 August 1998 12.5.3 Interlaboratory Comoarison Procram q

Operability Reauirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Prc cam that correspond to samples required by Table u

1 12.5-1.

Applicability: At all times.

Action 1.With analyses not being performed as requ; red above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

Surveillance Reauirements 12.5.3.B A summary of the results obtained as part of the above required interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.

Sases 12.5.3.C The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurernents of radioactive materialin environmental samples matrices are performed as part of the (Q

quality assurance program for environmental monitoring in order to demonstrate that the

/

results are valid for the purposes of Section IV.B.2 of Appendix l to 10CFR50.

l l

l l-t

(

J e

1 12 61

Revision 4 BRAIDWOOD August 1998 12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radioloaical Environmental Operatina Report

• Routine Annual Radiological Environmental Operating Report covering the operation of the Unit (s) during the previous calendar year shall be submitted prior to May 1 (1.T.S. May 15) of each year.

The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The Annual Radiological Environmental Operating Report shallinclude the results of all I

radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in Chapter 11 of the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual l

results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as recuired by Section 12.5.1, a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents, discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; result of the Land Use Census required by Section 12.5.2: and the results of the licensee participation in an Interlaboratory Comperison Program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3.

• A single' submittal may be made for a multiple unit station.

O 12-62

.m..

BRAIDWOOD Rsvision 4 August 1998 12.6 REPORTING REQUIREMFNTS (Cont'd) 12.6.1 Annual Radioloolcal Environmental Operatino Report (Cont'd) l l

The Annual Radiological Environmental Operating Report shall also include an annual i

summary of hourly meteorological data collected over the applicable year. This annual summary may De either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric j

stabiliiy. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This report sha!!

l also include an assessment of the radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other near-by uranium fuel cycle sources i

including doses from primary effluent pathways and direct radiation, for the previous l

calendar year. The assessment of radiation doses shall be performed in accordance with I

the methodology and parameters in the ODCM, and in compliance with 10CFR20 and 40CFR190, " Environmental Radiation Protection Standards for Nuclear Power l

Operation."

G L

i I!O 12-63

)

12.6 REPORTING REQUIREMENTS (Continurd) 12.6.2 Annual Radioactive Ef0uent Release Recor1**

Routine Annual Radioactive Effluent Release Reports covering the operation of the unit I

during the previous calendar year operation shall be submitted prior to May 1 of the following year.

i The Annual Radioactive Effluent Release Repcits shallinclude a summary of the quantities j

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 f

on a quarterly basis fellowing 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 10CFR61), type of container l

(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 oplanned releases from the site to areas beyond the site boundary of radioactive materials L.

1seous and liquid effluents made during the reporting period.

The Annual Radioactive Effluent Release Reports shallinclude any changes made during l

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.

The Annual Radioactive Effluent Release Reports shall also inc.cie the following: an explanation as to why the inoperabil:ty 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 holdr 1ks or gas storage 1 ' 6 (l.T.S. 5.5.12),

tanks exceeding the limits of Technical Specification 3.11.1.4 or.

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 12-64

BRAIDWOOD Rtvision 4 August 1998 f

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

12.6.3.2 Licensee-initiated changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2 (UFSAR Chapter 17). This documentation shall l

contain:

1.

Sufficient information to support the change together uith the appropriate I

analyses or evaluations justifying the changes (s); and l

2.

A determination that the change will maintain the level of radioactive effluent control required by 10CFR20,40CFR190.10CFR50.36a, and l

Appendix l to 10CFR50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

I 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 Onsita Review and Investigative Function.

l c.

Shall be submitted to the Commission in the form of a comp!ete legible copy of l

the entire ODCM or updated pages if the Commission retains a controlled copy. If l

an entire copy of me ODCM is submitted, it shall be submitted as part of or l ""3 concurrent with the Annual Radioactive Effluent Release Report for the period of Q

the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shallindicate the date (e.g., month / year) the change was implemented.

i i

I t

I 4

V 12-F5

BRAIDWOOD Revision 4 August 1998 12.6

, REPORTING REQUIREMENTS (Continued) 12.6.4 Maior Chanaes to Liauid and Gaseous Radwaste Treatment Systems

• Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):

Shall be reported to the Commission in the Annual Radioactive Effluent Release Report a.

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 10CFR50.59;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplementalinformation;

3) A dotalled description of the equipment, components, and processes involved and the interfaces with other plant systems; l

1

4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License 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 changes are to be made;

7) An estimate of the exposure to plant operating personnel as a result of the change; and

8) Documentation of the fact that the change was reviewed and found accepteble by the Onsite Reviev and Investigative Function.

b.

Shall become effective upon review and acceptance by the Onsite Review and trivestigative Function.

• Licensees may choose to submit the information called for in this section as part of the annual FSAR update.

O 12-66

i l

Braidwood Station

(

Appendix F Change Summary ODCM Revision 3, August 1998 Page Change Description F-i Updated revision number.

}

F-2 Added Improved Technical Specification for Limits on Radioactivity in Unprotected Outdoor Tanks.

F-5 Added " vent" to Note b to ensure consistency of mixed mode release definition.

Updated notation of exponent """ to "^"

F-6, Added " vent" to Note to ensure consistency of mixed mode release defmition.

F-7 Updated notation of exponent "* *" to "^"

F-8 Added " vent" to table header to ensure consistency of mixed mode release definition. Updated notation of exponent """ to "^"

F-24 Added " vent" to Note b to ensure consistency of mixed mode release defmition.

F-45, Update 'igures to electronic format.

\\g F-46

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

BRAIDWOOD Revision 3 August 1998 APPENDIX F j

BRAIDWOOD ANNEX INDEX REVISION 3 l

i i

i F-i

APPENDIX F STATION-SPECIFIC DATA FOR BRAIDWOOD UNITS 1 AND 2 TABLE OF CONTENTS PAGE F-1 F.1 INTRODUCTION F-1 F.2 REFERENCES 9

g; F.u

~

c-

BRAIDWOOD Revision 3 August 1998 APPENDIX F O

LIST OF TABLES V

l NUMBER TITLE PAGE I

F1 Aquatic Environmental Dose Parameters F-2 l

F-2 Station Characteristics F-3 i

F-3 Critical Ranges F-4 F-4 Average Wind Speeds F-5 F-5 X/Q and D/Q Maxima At or Beyond the Unrestricted Area Boundary F-6 F-Sa X/Q and D/Q Maxima At or Beyond the Restricted Area Boundary F-7 F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 F-7 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Selected Nuclides F-9 F 7a Maximum Offsite Finite Plume Gamma Dose Factors (T_

Based on 1 cm Depth at the Restricted Area 1

()

Boundary for Selected Nuclides F-24 Supplemental Tables A

Mixed Mode Joil equency D:stribution Table Summaries 13 and 34 Foot Elevation Data F 39

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed i-

-Summary Table of Percent by Speed and Class l

B Ground Level Joint Frequency Distribution Table Summaries '

F-43

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed l-

-Summary Table of Percent by Speed and Ciass l

n a

./

F-iii 4

[g-AB@ WOOD m%i*G August 1998 APPENDIX F LIST OF FIGURES PAGE NUMBER TITLE F-1 Unrestricted Area Boundary F 45 F 46 F-2 Restricted Area Boundary O

e

e. ~

I BRAIDWOOD Revision 3 August 1998 APPENDIX F

(

STATION-SPECIFIC DATA FOR BRAIDWOOD

(

UNITS 1 AND 2 F.1 INTRODUCTION This appendix contains data relevant to the Braidwood site. Included is a figure showing the unrestricted area boundary and values of parameters used in offsite dose assessment.

F.2 REFERENCES 1.

Sergent & Lundy, Nuclear Analysis and Technology Division Braidwood Calculation No.

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

2.

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

3.

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

4.

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

A F-1

BRAIDWOOD Revision 3 August 1998 Table F-1 Aquatic Environmental Case Parameters O

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.

Downstream dams are within 50 miles of the station. One is located on the Kankakee. The other is the Illinois River at Dresden Island, Marseilles and Starved Rock. The Kankakee River flows into the lilinois 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.

j l

Water and Fish Incestion Parameters j

Parameter' Value U*, water usage, Uhr 0.042 U', fish consumption, kg/hr 2.4 E-3 j

1/M*,1/M' O.25,1.0 1

F*, cfs 3950 F',cfs 3950 t', hr 24.0 b

t*, hr*

3.0 d

l Limits on Radioactivity in Unorotected Outdoor Tanks l

l Outside Temporary Tank 5 10 Ci' per Technical Specification 3.11.1.4 (l.T.S. 5.5.12) l l

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

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

• t* (br) = 3 hr (distance nearest potable water intake, to Wilmington, is 4 river miles downstream; a flow rate of 1.4 mph is assumed) d See Section A.2.4 of Appendix A.

• Tritium and dissolved or entrained nod!e gases are excluded from this limit.

O F-2

BRAIDWOOD Revision 3 August 1998 Table F-2

/N Station Characteristics U

STATION:

Braidwood LOCATION:

Braceville, Illinois CHARACTERISTICS ' ' ELEVATED RELEASE POINT: Not Applicable (NA) 1)

Release Height =

m 2)

Diameter =

m d

ms" 4)

Heat Content Kcal s 3)

Exit Speed

=

CHARACTERISTICS OF VENT STACK RELEASE POINT 1)

Release Height = 60.66 m' 2)

Diameter = 2.80 m 4

3)

Exit Speed

= 11.0 ms '

CHARACTERISTICS OF GROUND LEVEL RELEASE 1)

Release Height = 0 m

)

2)

Building Factor (D) =

60.6 m'

l METEOROLOGICAL DATA A 320 ft Tower is Located 573 m NE of vent stack release point Tower Data Used in Calcuiations Wind Speed Differential Release Point and Direction Temperature Elevated (NA)

(N.\\1 Vent 203 ft 199 '50 ft Ground 34 ft 199-30 ft I

Used in calculating the meteoro!ogical and dose factors in Tables F-5, F-6, and F-7. See Sections B.3 through B.6 of Appendix B.

O) b F-3

Tabl3 F-3 Critical Ranges O

Unrestricted Area Restricted Area Nearest Dairy Farm Boundary' Boundary Nearest Resident" within 5 Miles

• Direction (m)

(m)

(m)

(m)

N 610 305 800 None NNE 914 265 2800 None NE 792 299 1100 None ENE 701 361 1200 None E

1036 355 1200 None ESE 2713 425 3500 None SE 3414 448 4300 None SSE 3444 540 5300 None S

4633 530 6700 None SSW 975 540 2000 None SVV 632 632 600 None WSW 555 555 800 None VV 518 500 600 None WNW 503 434 600 None NW 495 428 600 None NNW 510 442 600 None 9

See Updated Final Safety Analysis Report Table 2.1-1a and Environmental Report. Used in calculating the meteorological and dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of Appendix B.

1996 annual survey by Teledyne isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters.

1996 annual milch animal census, by Teledyne isotopes Midwest Laboratories. Used in calculating the D/Q values in Table F-6. The distances are rounded to the nearest conservative 100 meters.

s F-4

BRAIDtNDOD Revision 3 August 1998 Table F-4 Average Wind Speeds d

- Average Wind Speed (m/sec)*

D n

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 i

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 (vent) values.

l

~

F5

Revision 3 BRAIDWOOD I

August 1998 Table F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary Ground Level Release Downwind Mixed Mode (Vent) Release Direction Radius X/Q Radius D/Q Radius X/Q D/Q (meters)

(sec/m^3)

(meters)

(1/m^2)

(meters)

(sec/m^3)

(1/m^2) l N

610.

1.161E-06 610.

1.643E-08 610.

4.646E-06 3.355E-08 NNE 914.

5.076E-07 914.

7.023E-09 914.

1.783E-06 1.382E-08 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 I

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 SSW 975.

1.925E-07 975.

2.843E-09 975.

1.333E-06 6.781E-09 SW 632.

5.153E-07 632.

5.408E-09 632.

3.485E-06 1.494E-08 WSW 555.

7.821E-07 555.

4.55BE-09 555.

5.471E-06 1.853E-08 W

518.

8.901E-07 518.

5.064E-09 518.

5.902E-06 1.830E-08 WNW 503.

1.077E-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-08 NNW 510.

1.098E-06 510.

1.185E-08 510.

5.421E-06 3.023E-08 Braidwood Site Meteorological Data 1/78 - 12/87 Based on Reference 1 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B.

Note:

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

D/Q 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 l

(vent) data.

Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of highest X/Q o beyond the unrestricted area boundary (UAB).

O 6

O

(

(

}

Revision W) l

%/

BRAI OD August 1998 Table F-Sa X/Q and D/Q Maxima at or Beyond the Restricted Area Boundary Downwind Mixed Mode (Vent) Release Ground Level Release Direction Radius X/Q Radius D/Q Radius X/Q D/O (meters)

(sec/m^3)

(meters)

(1/m^2)

(meters)

(sec/m^3)

(1/m^2) l.

N 305.

3.766E-06 305.

4.266E-08 305.

1.551E-05 9.627E-08 NNE 265.

3.841E-06 265.

3.855E-08 265.

1.445E-05 9.318E-08 NE 299.

1.412E-06 299.

1.473E-08 299.

8.827E-06 4.892E-08 ENE 361.

1.265E-06 361.

1.138E-08 361.

6.706E-06 3.652E-08 E

355.

1.669E-06 355.

1.590E-08 355.

8.978E-06 4.611E-08 ESE 425.

1.264E-06 425.

1.678E-08 425.

7.012E-06 4.132E-08 SE 448.

1.056E-06 448.

1.266E-08 448 6.269E-06 3.177E-08 SSE 540.

5.596E-07 540.

8.639E-09 540.

3.673E-06 2.258E-08 S

530.

6.166E-07 530.

5.425E-09 530.

4.576E-06 1.745E-08 SSW 540.

4.441E-07 540.

6.000E-09 540.

3.423E-06 1.748E-08 SW 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

500.

9.431 E-07 500.

5.289E-09 500.

6.265E-06 1.932E-08 WNW 434.

1.384E-06 434.

7.394E-09 434.

8.361E-06 2.399E-08 NW 428.

1.381 E-06 428.

1.050E-08 428.

7.070E-06 3.170E-08 NNW 442.

1.388E-06 442.

1.444E-08 442.

6.878E-06 3.766E-08 Braidwood Site Meteorological 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 mixed mode (vent) data.

l Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of highest X/Q or D/O at or beyond the restricted area boundary (RAB).

F-7

Revision 3 BRAIDWOOD August 1998 l

Table F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations within 5 miles Nearest Meat Animal D/O (1/m^2)

Downwind Nearest Milk Cow D/O (1/m^2)

Direction Radius Mixed Ground Release Radius Mixed Ground (meters)

Release (meters)

Release Release (vent)

(vent)

N 8000 2.694E-10 4.083E-10 4100 8.404E-10 1.347E- 09 NNE 8000 2.158E-10 3.221E-10 8000 2.158E-10 3.221E-10 NE 8000 1.333E-10 2.015E-10 1400 1.999E-09 4.252E-09 ENE 8000 1.305E-10 1.987E-10 5300 2.604E-10 4.153E-10 E

8000 1.614E-10 2.447E-10 3700 5.792E-10 9.701E-10 ESE 8000 1.962E-10 2.874E-10 3700 7.121E'a 1.134E- 09 SE 8000 1.779E-10 2.395E-10 4300 4.998 5 10 7.250E-10 SSE 8000 1.591E-10 2.270E-10 6600 2.210E-10 3.226E-10 S

8000 1.074E-10 1.704E-10 8000 1.074E-10 1.704E-10 SSW 8000 1.172E-10 1.757E-19 8000 1.172E-10 1.757E-10 SW 8000 1.417E-10 1.921E-10 7200 1.695E-10 2.326E-10 WSW 8000 1.143E-10 1.943E-10 6100 1.800E-10 3.169E-10 W

8000 9.700E-11 1.724E-10 2500 6.142e-10 1.350E-09 WNW 8000 9.286E-11 1.723E-10 8000 9.286E-11 1.723E-10 NW 8000 1.255E-10 2.228E-10 8000

. 255E-10 2.228E-10

)

NNW 8000 1.639E-10 2.781E-10 8000 1.639E-10 2.781E-10 Braidwood Site Meteorological Data 1/78 - 12/87 l

9 9

O

(

BRAI D

Rsvision 3s-August 1998 Table F-7 l

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-83m Downwind '

Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mrad /yr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 610.

610.

1.455E-04 1.097E-04 610.

5.333E-04 4.021 E-04 i

NNE 914.

914.

6.375E-05 4.807E-05 914.

2.125E-04 1.602E-04 NE 792.

792.

3.828E-05 2.886E-05 792.

2.007E-04 1.513E-04 ENE 701.

701.

5.294E-05 3.992E-05

701, 2.575E-04 1.941E-04 E

1036.

1036.

3.703E-05 2.792E-05 1036.

1.718E-04 1.295E-04 ESE 2713.

2713.

1.129E 05 8.514E-06 2713.

3.792E-05 2.859E-05 SE 3414.

3414.

7.089E-06 5.345E-06 3414.

2.141E-05 1.614E-05 SSE 3444.

3444.

6.047E-06 4.559E-06 3444.

1.798E:05 1.355E-05 S

4633.

4633.

3.224E-06 2.431E-06 4633.

9.268E-0$

6.988E-06 SSW 975.

975.

2.363E-05 1.732E-05 975.

1.444E-04 1.088E-04 SW 632.

632.

5.930E-05 4.472E-05 632.

3.694E-04 2.786E-04 WSW 555.

555.

8.469E-05 6.386E-05 555.

5.942E-04 4.480E-04 t

W 518.

518.

9.909E-05 7.471E-05 518.

6.292E-04 4.744E-04 WNW 503.

503.

1.205E-04 9.082E-05 503.

6.653E-04 5.016E-04 i

NW 495.

495 1.242E-04 9.366E-05 495.

6.066E-04 4.574E-04 NNW 510.

510.

i322E-04 9.969E-05 510.

6.144E-04 4.633E-04 Braidwood Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B.

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

w F-9

BRAIDWOOD R: vision 3 August 1998 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 Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 610.

610.

9.989E-04 9.590E-04 610.

2.731E-03 2.16eE-03 NNE 914.

914.

4.979E-04 4.785E-04 914.

1.222E-03 1.171E-03 NE 792.

792.

3.618E-04 3.481E-04 792.

1.173E-03 1.124E-03 i

ENE 701.

701.

4.452E-04 4.280E-04 701.

1.363E-03 1.305E-03 E

1036.

1036.

3.452E-04 3.320E-04 1036.

1.023E-03 9.809E-03 ESE 2713.

2713.

1.220E-04 1.174E-04 2713.

3.051E-04 2.930E-04 SE 3414.

3414.

8.179E-05 7.874E-05 3414.

1.970E-04 1.893E-04 l

SSE 3444.

3444.

6.958E-05 6.700E-05 3444.

1.634E-04 1.570E-04 S

4633.

4633.

4.000E-05 3.851E-05 4633.

1.051 E-04 1.010E-04 SSW 975.

975.

2.413E-04 2.323E-04 975.

9.063E-04 8.688E-04 SW 632.

632.

5.199E-04 4.999E-04 632.

1.982E-03 1.90SE-03 WSW 555.

555.

6.707E-04 6.444E-04 555.

3.061E-03 2.929E-03 l

W 518.

518.

6.908E-04 6.632E-04 518.

3.081E-03 2.947E-03 WNW 503.

503.

7.511 E-04 7.204E-04 503.

3.126E-03 2.988E-03 NW 495.

495.

8.396E-04 8.059E-04 495.

2.915E-03 2.788E-03 NNW 510.

510.

9.023E-04 8.662E-04 510.

3.091E-03 2.958E-03 Braidwood Site Meteorological Data 1/78 - 12/87

-10

.,g BRAI D

Revision b s"

August 1998 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85 Downwind Unrestricted Mixed Mode fVent) Release Ground Level Release Direction Area Dound Radius V

VBAR Radius G

GBAR (meters)

(meters)

. (mradlyr)/(uCi/sec)

(meters)

(mrad /yr)/(.:Ci/sec)

N 610.

610.

1.125E-05 1.088E-05 610.

2.986E-05 2.888E-05 NNE 914.

914.

5.661E-06 5.474E-06 914.

1.344E-05 1.300E-05 NE 792.

792.

4.192E-06 4.053E-06 792.

1.311E-05 1.268E-05 ENE 701.

701.

5.150E-06 4.980E-06 701.

1.486E-05 1.437E-05 E

1036.

1036.

4.044E-06 3.911E-06 1036.

1.145E-05 1.107E-05 ESE 2713.

2713.

1.468E-06 1.420E-06 2713.

3.702E-06 3.579E-06 SE 3414.

3414.

1.025E-06 9.911 E-07 3414.

2.620E-06 2.534E-06 SSE 3444.

3444.

8.593E-07 8.310E-07 3444.

2.101E-06 2.032E-06 i

S 4633.

4633.

5.432E-07 5.253E-07 4633.

1.699E-06 1.643E-06 SSW 975.

975.

2.853E-06 2.759E-06 975.

1.042E-05 1.008E-05 SW 632.

632.

6.098E-06 5.897E-06 632.

2.227E-05 2.154E-05 l

WSW 555.

555.

7.858E-06 7.599E-06 555.

3.400E-05 3.288E-05 W

518.

518.

7.924E-06 7.663E-06 518.

3.388E-05 3.276E-05 WNW 503.

503.

8.499E-06 8.219E-06 503.

3.430E-05 3.317E-05 NW 495.

495.

9.567E-06 9.251E-06 495.

3.174E-05 3.069E-05 NNW 510.

510.

1.025E-05 9.909E-06 510.

3.393E-05 3.281E-05 r

Braidwood Site Meteorological Data 1/78 - 12/87 i

i I

t F-11 l

CRAIDWOOD R: vision 3 August 1998 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-87 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 610.

610.

3.313E-03 3.217E-03 610.

8.088E-03 7.853E-03 l

NNE 914.

914.

1.650E-03 1.602E-03 914.

3.649E-03 3.543E-03 NE 792.

792.

1.249E-03 1.213E-03 792.

3.373E-03 3.275E-03 l

ENE 701.

701.

1.516E-03 1.472E-03 701.

4.077E-03 3.958E-03 E

1036.

1036.

1.150E-04 1.117E-03 1036.

2.954E-03 2.868E-03 ESE 2713.

2713.

3.94-8E-04 3.834E-04 2713.

8.084E-04 7.849E-04 SE 3414.

3414.

2.559E-04 2.486E-04 3414.

4.691E-04 4.555E-04 l

SSE 3444.

3444.

2.231E-04 2.167E-04 3444.

4.098E-04 3.979E-04 S

4633.

4633.

1.162E-04 1.129E-04 4633.

2.055E-04 1.996E-04 SSW 975.

975.

8.253E-04 8.015E-04 975.

2.477E-03 2.405E-03 SW 632.

632.

1.758E-03 1.707E-03 632.

5.625E-03 5.462E-03 WSW 555.

555.

2.229E-03 2.165E-03 555.

8.703E-03 8.450E-03 W

518.

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.

495.

2.792E-03 2.711E-03 495.

8.646E-03 8.395E-03 NNW 510.

510.

2.982E-03 2.896E-03 510.

9.023E-03 8.761E-03 Braidwood Site Meteorological Data 1/78 - 12/87 F-12

O A

O Rsvision 3' August 1998

. Table F-7 (Continued) i Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-88 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters) -

(mradlyr)/(uCi/sec)

(meters) -

(mradlyr)/(uCi/sec) l N

610.

610.

7.997E-03 7.772E-03 610.

1.968E 1.911E-02 NNE 914.

-914.

' 4.019E-03 3.906E-03 914.

8.899E-03 8.644E NE 792.

792.

3.059E-03 2.974E-03 792.

. 8.441E-03

. 8.199E-03 I

ENE 701.

701.

3.725E-03 3.621E-03 701.

9.870E-03 9.586E-03 10 S.

1036.

2.878E-03 2.798E-03 1036.

7.394E-03 7.182E-03 E

ESE 2713.

2713.

1.022E-03 9.941 E-04 '

2713.

2.215E-03 2.152E-03 SE 3414.

3414.

6.859E-04 6.670E-04 3414.

1.396E-03 1.357E-03 SSE 3444.

3444.

5.929E-04 5.766E-04 3444.

1.185E-03 1.151 E-03 S

4633.

4633.

3.301E-04 3.210E-04.

4633.

6.987E-04 6.792E-04 SSW 975.

975.

2.066E-03 2.009E-03 975.

6.466E-03 6.281E-03 SW 632.

632.

4.389E-03 4.267E-03 632.

1.422E-02 1.381E-02 WSW 555.

555.

5.589E-03 5.433E-03 555.

2.182E-02 2.119E-02 W

518.

518.

5.607E-03 5.449E-03 518.

2.205E-02 2.141E-02 WNW 503.

503.

5.947E-03 5.779E-03 503.

2.232E-02 2.167E-02 NW 495.

495.

6.814E-03 6.622E-03 495.

2.097E-02 2.036E-02 NNW 510.

510.

7.265E-03 7.060E-03 510.

2.215E-02 2.151E-02 Braidwood Site Meteorological Data 1/78 - 12/87 t

F-13

GRAIDWOOD Revision 3 August 1998 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-89 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mrad /yr)/(uCi/sec)

N 610.

610.

4.323E-03 4.199E-03 610.

7.655E-03 7.435E-03 NNE 914.

914.

1.692E-03 1.643E-03 914.

2.645E-03 2.569E-03 NE 792.

792.

1.305E-03 1.268E-03 792.

2.219E-03 2.155E-03 ENE 701.

701.

1.577E-03 1.532E-03 701.

3.016E-03 2.929E-03 E

1036.

1036.

9.092E-04 8.833E-04 1036.

1.387E-03 1.347E-03 ESE 2713.

2713.

1.140E-04 1.108E-04 2713.

9.720E-05 9.442E-05 SE 3414.

3414.

4.392E-05 4.266E-05 3414.

2.983E-05 2.897E-05 SSE 3444.

3444.

3.822E-05 3.712E-05 3444.

3.079E-05 2.990E-05 S

4633.

4633.

9.027E-06 8.769E-06 4633.

6.198E-06 6.021E-06 SSW 975.

975.

6.764E-04 6.571E-04 975.

1.066E-03 1.036E-03 SW 632..

632.

1.750E-03 1.700E-03 632.

3.181 E-03 3.089E-03 WSW 555.

555.

2.009E-03 1.951E-03 555.

4.608E-03 4.475E-03 W

518.

518.

2.170E-03 2.108E-03 518.

4.949E-03 4.807E-03 WNW 503.

503.

2.410E-03 2.341E-03 503.

5.589E-03 5.428E-03 NW 495.

495.

3.227E-03 3.134E-03 495.

7.228E-03 7.020E-03 NNW 510.

510.

3.714E-03 3.608E-03 510.

7.735E-03 7.512E-03 Braidwood Site Meteorological Data 1/78 - 12/87 9

O" O

o' g_

9-BRAI Rsvision $'

l August 1998 Table F-7 (Continued)

'i Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-90 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR-

[

(meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mrad /yr)/(uCi/sec) l N

-610.

610.

8.576E-04 8.317E-04 610.

9.142E-04 8.863E-04 NNE 914.

914.

1.453E-04 1.409E-04 914.

1.212E-04 1.175E-04 NE 792.

792.

1.302E-04 1.263E-04 792.-

1.132E-04 1.098E-04 ENE 701.

701.

1.874E-04 1.817E-04 701.

1.634E-04 1.584E-04 E

1036.

1036.

5.480E-05 5.316E-05 1036.

3.996E-05 3.875E-05 t

ESE 2713.

2713.

2.691E-07 2.610E-07 2713.-

1795E-07 1.741E-07 l

SE 3414.

3414.

1.662E-08 1.612E-08 3414.

6.748E-09 6.546E-09 SSE 3444.

3444.

2.647E-08 2.568E-08 3444.

2.033E-08 1.972E-08 S

4633.

4633.

5.354E-10 5.193E-10 4633.

3.704E-10 3.592E-10 l

SSW 975.

975.

4.411E-05 4.278E-05 975.

3.803E-05 3.688E-05 SW 632.

632.

2.254E-04 2.186E-04 632.

1.980E-04 1.920E-04 WSW 555.

555.

2.280E-04 2.212E-04 555.

1.855E-04 1.799E-04 i

W 518.-

518.

2.822E-04 2.738E-04 518.

1.673E-04 1.622E-04 WNW 503.

503.

3.444E-04 3.341E-04 503.

2.412E-04 2.339E-04 NW 495.

495.

5.611E-04 5.442E-04 495.

5.535E-04.

5.366E-04 i

NNW 510.

510.

8.014E-04 7.772E-04 510.

9.221E-04 8.940E-04 i

f Braidwood Site Meteorological Data 1/78 - 12/87 t

t I

F-15

[

BRAIDWOOD Revision 3 August 1998 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-131m Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(Uci/sec)

N 610.

610.

1.355E-04 1.065E-04 610.

4.922E-04 3.831E-04 NNE 914.

914.

6.125E-05 4.839E-05 914.

1.988E-04 1.553E-04 NE 792.

792.

3.806E-05 3.031E-05 792.

1.946E-04 1.520E-04 ENE 701.

701.

5.153E-05 4.083E-05 701.

2.358E-04 1.838E-04 E

1036.

1036.

3.805E-05 3.024E-05 1036.

1.677E-04 1.310E-04 ESE 2713.

2713.

1.232E-05 9.849E-06 2713.

4.412E-05 3.474E-05 SE 3414.

3414.

8.612E-06 6.883E-06 3414.

3.046E-05 2.401 E-05 SSE 3444.

3444.

6.862E-06 5.499E-06 3444.

2.387E-05 1.883E-05 S

4633.

4633.

4.603E-06 3.676E-16 4633.

1.914E-05 1.510E-05 SSW 975.

975.

2.441E-05 1.949E-05 975.

1.504E-04 1.176E-04 SW 632.

632.

6.073E-05 4.813E-05 632.

3.620E-04 2.819E-04 WSW 555.

555.

8.569E-05 6.762E-05 555.

5.701E-04 4.435E-04 W

518, 518.

9.576E-05 7.527E-05 518.

5.874E-04 4.565E-04 WNW 503.

503.

1.132E-04 8.870E-05 503.

6.171E-04 4.790E-04 NW 495.

495.

1.167E-04 9.171E-05 495.

5.515E-04 4.285E-04 NNW 510.

510.

1.244E-04 9.777E-05 510.

5.698E-04 4.432E-04 Braidwood Site Meteorological Data 1/78 - 12/87 O

Os O

.h BRAlb R: vision 3 August 1998 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133m Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction ' Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 610.

610.

2.561E-04 2.223E-04 610.

8.256E-04 7.023E-04 NNE 914.

914.

1.216E-04 1.063E-04 914.

3.481E-04 2.984E-04 NE 792.

792.

8.185E-05 7244E-05 792.

3.399E-04 2.912E-04 ENE 701.

701.

1.055E-04 9.274E-05 701.

4.017E-04 3.426E-04 E

1036.

1036 8.032E-05 7.091E-05 1036.

2.943E-04 2.524E-04 ESE 2713.

2713.

2.749E-05 2.446E-05 2713.

8.394E-05 7.303E-05 SE 3414.

3414.

1.908E-05 1.697E-05 3414.

5.806E-05 5.060E-05 SSE 3444.

3444.

1.562E-05 1.394E-05 3444.

4.609E-05 4.022E-05 S

4633.

4633.

1.005E-05 8.929E-06 4633.

3.632E-05 3.171E-05 SSW 975.

975.

5.390E-05 4.788E-05 975.

2.651E-04 2.276E-04 SW 632.

632.

1.243E-04 1.092E-04 632.

6.091E-04 5.186E-04 WSW 555.

555.

1.679E-04 1.466E-04 555.

9.488E-04 8.060E-04 W

518.

518.

1.799E-04 1.560E-04 518.

9.658E-04 8.185E-04 WNW 503.

503.

2.046E-04 1.763E-04 503.

1.001E-03 8.459E-04 NW 495.

495.

2.185E-04 1.894E-04 495.

9.067E-04 7.683E-04 l

NNW 510.

510.

2.337E-04 2.027E-04 510.

9.487E-04 8.059E-04 Braidwood Site Meteorological Data 1/78 - 12/87 l

l l

1 l

F-17 i

ERAIDWOOD R* vision 3 August 1998 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/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.

3.891E-04 3.466E-04 NE 792.

792.

9.079E-05 8.273E-05 792.

3.804E-04 3.389E-04 i

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.

3.2956-04 2.937E-04 l

ESE 2713.

2713.

3.072E-05 2.812E-05 2713.

9.583E-05 8.640E-05 l

SE 3414.

3414.

2.135E-05 1.953E-05 3414.

6.660E-05 6.011E-05 SSE 3444.

3444.

1.740E-05 1.596E-05 3444.

5.275E-05 4.767E-05 S

4633.

4633.

1.130E-05 1.033E-05 4633.

4.215E-05 3.809E-05 SSW 975.

975.

5.975E-05 5.460E-05 975.

2.978E-04 2.657E-04 SW 632.

632.

1.367E-04 1.238E-04 632.

6.726E-04 5.954E-04 WSW 555.

555.

1.830E-04 1.649E-04 555.

1.044E-03 9.224E-04 W

518.

518.

1.965E-04 1.762E-04 518.

1.056E-03 9.311 E-04 WNW 503.

503.

2.231E-04 1.990E-04 503.

1.088E-03 9.570E-04 NW 495.

495.

2.383E-04 2.135E-04 495.

9.911E-04 8.736E-04 j

l NNW 510.

510.

2.563E-04 2.299E-04 510.

1.044E-03 9.221E-04 l

Braidwood Site Meteorological Data 1/78 - 12/87

-18

BRAI D

Rsvision 3 August 1998 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-135m Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mrad /yr)/(uCl/sec)

(meters)

(mradlyr)/(uCi/sec)

N 610.

610.

1.924E-03 1.856E-03 610.

4.403E-03 4.240E-03 NNE 914.

914.

9.071E-04 8.750E-04 914.

1.913E-03 1.843E-03 NE 792.

792.

6.745E-04 6.509E-04 792.

1.628E-03 1.568E-03 ENE 701.

701.

8.149E-04 7.862E-04 701.

2.191E-03 2.110E-03 E

1036.

1036.

5.710E-04 5.510E-04 1036.

1.368E-03 1.319E-03 ESE 2713.

2713.

1.557E-04 1.503E 04 2713.

2.479E-04 2.391 E-04 SE 3414.

3414.

8.843E-05 8.536E-05 3414.

1.163E-04 1.122E-04 SSE 3444.

3444.

7.741 E-05 7.472E-05 3444.

1.062E-04 1.025E-04 S

4633.

4633.

3.277E-05 3.163E-05 4633.

4.020E-05 3.879E-05 SSW 975.

975.

4.100E-04 3.957E-04 975.

1.011E-03 9.747E-04 SW 632.

632.

8.898E-04 8.587E-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

518.

518.

1.187E-03 1.145E-03 518.

4.362E-03 4.200E-03 WNW 503.

503.

1.304E-03 1.258E-03 503.

4.495E-03 4.327E-C3 NW 495.

495.

1.546E-03 1.490E-03 495.

4.695E-03 4.521 E-03 NNW 510.

510.

1.673E-03 1.613E-03 510.

4.688E-03 4.514E-03 Braidwood Site Meteorological Data 1/78 -12/87 b

F-19

+..

.-m m

o m-

BRAIDWOOD R vision 3 August 1998 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-135 Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 610.

610.

1.353E-03 1.307E-03 610.

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 5.880E-04 701.

1.833E-03 1.770E-03 E

1036.

1036.

4.753E-04 4.595E-04 1036.

1.395E-03 1.348E-03 ESE 2713.

2713.

1.700E-04 1.644E-04 2713.

4.326E-04 4.181E-04 SE 3414.

3414.

1.160E-04 1.121E-04 3414.

2.914E-04 2.816E-04 SSE 3444.

3444.

9.782E-05 9.459E-05 3444.

2.377E-04 2.297E-04 S

4633.

4633.

5.868E-05 5.674E-05 4633.

1.698E-04 1.641E-04 SSW 975.

975.

3.328E-04 3.217E-04 975.

1.253E-03 1.211E-03 SW 632.

632.

7.144E-04 6.906E-04 632.

2.708E-03 2.615E-03 WSW 555.

555.

9.205E-04 8.896E-04 555.

4.150E-03 4.007E-03 W

518.

518.

9.408E-04 9.091E-04 518.

4.151E-03 4.008E-03 WNW 503.

503.

1.018E-03 9.833E-04 503.

4.203E-03 4.058E-03 NW 495.

495.

1.139E-03 1.101E-03 495.

3.908E-03 3.773E-03 NNW 510.

510.

1.225E-03 1.183E-03 510.

4.166E-03 4.022E-03 Braidwood Site Meteorological Data 1/70 - 12/87 O

O O

8 Rt. vision 3

~

August 1998.

Table F-7 (Continued) -

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-137 -

Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release -

Direction Area Bound Radius.

V

.VBAR Radius G.

GBAR j

(meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

I l

N 610.

610.

6.360E-04 6.154E-04 610.

1.202E-03 1.164E-03 5

NNE 914.

914.

-- 2.578E-04 2.494E-04 914.

4.345E 4.205E-04 NE 792.

792.

1.950E - 1.887E-04 792.

3.640E-04 3.522E-04 ENE 701.

701.

2.355E-04 2.279E-04 701.

4.977E-04 4.816E-04 E

1036.

1036.

1.407E-04 ' 1.361E-04 1036.

2.400E-04 2.322E-04 1

ESE 2713.

2713.

2.042E-05 1.976E-05

2713, 1.931E-05 1.868E-05

-SE 3414.

3414.

8.468E-06 8.195E-06 3414.

6.393E-06 6.186E-06 SSE 3444.

3444.

7.384E-06 7.146E-06 3444.

6.474E-06 6.265E-06 S

4633.

4633.

1.951E-06 1.888E-06 4633.

1.457E-06 1.410E-06 SSW 975.

975.

1.038E-04 1.004E-04 975.

1.812E-04 1.753E-04 SW 632.

632.

' 2.577E-04 2.493E-04 632.

5.246E-04 5.076E-04 I

WSW 555.

555.

2.977E-04 2.881E-04 555.

7.771E-04 7.519E-04 W

518.

518.

3.247E-04 3.143E-04 518.

8.444E-04 8.170E-04 WNW 503.

503.

3.635E-04 3.517E-04 503.

9.371E-04 9.067E-04 NW 495.

495.

- 4.769E-04 4.615E 495.

1.167E-03 1.129E-03 NNW 510.

510.

5.441E-04 5.265E-04 510.

1.222E-03 1.182E-03 1

f

- Braidwood Site Meteorological Data 1/78 - 12/87 1

i t

l i

F-21

ERAIDWOOD Revision 3 August 1998 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary fcr Xe-138

(

Downwind Unrestricted Mixed Mode (Vent) Release Ground Level Release l

Direction Area Bound Radius V

VBAR Radius G

GBAR i

(meters)

(meters)

(mrad /yr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec) i N

610.

610.

4.201E-03 4.079E-03 610.

9.169E-03 8.898E-03 NNE 914.

914.

1.982E-03 1.925E-03 914.

3.986E-03 3.869E-03 NE 792.

792.

1.504E-03 1.460E-03 792.

3.379E-03 3.280E-03 ENE 701.

701.

1.805E-03 1.753E-03 701.

4.549E-03 4.415E-03 E

1036.

1036.

1.262E-03 1.225E-03 1036.

2.830E-03 2.747E-03 ESE 2713.

2713.

3.395E-04 3.297E-04 2713.

5.079E-04 4.931 E-04 SE 3414.

3414.

1.926E-04 1.871E-04 3414.

2.381 E-04 2.312E-04 SSE 3444.

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 SSW 975.

975.

9.144E-04 8.880E-04 975.

2.091E-03 2.030E-03 SW 632.

632.

1.991E-03 1.934E-03 632.

5.266E-03 5.072E-03 WSW 555.

555.

2.429E-03 2.359E-03 555.

8.199E-03 7.957E-03 W

518.

518.

2.609E-03 2.534E-03 518.

8.973E-03 8.708E-03 WNW 503.

503.

2.834E-03 2.751 E-03 503.

9.247E-03 8.973E-03 NW 495.

495.

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 l

Braidwood Site Meteorological Data 1/78 - 12/87 O

O O

.,~

(_)

\\J BRAI D

R: vision &

August 1998 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Ar-41 Downwind Unrestricted iviixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mrad /yr)/(uCi/sec)

N 610.

610.

5.141 E-03 4.977E-03 610.

1.283E-02 1.242E-02 NNE 914.

914.

2.568E-03 2.485E-03 914.

5.780E-03 5.595E-03 NE 792.

792.

1.935E-03 1.873E-03 792.

5.421 E-03 5.248E-03 ENE 701.

701.

2.357E-03 2.282E-03 701.

6.445E-03 6.239E-03 E

1036.

1036.

1.803E-03 1.746E-03 1036.

4.745E-03 4.593E-03 ESE 2713.

2713.

6.281E-04 6.080E-04 2713.

1.352E-03 1.309E-03 SE 3414.

3414.

4.128E-04 3.996E-04 3414.

8.140E-04 7.880E-04 SSE 3444.

3444.

3.580E-04 3.466E-04 3444.

7.007E-04 6.783E-04 S

4633.

4633.

1.924E-04 1.862E-04 4633.

3.770E-04 3.650E-04 SSW 975.

975.

1.289E-03 1.247E-03 975.

4.067E-03 3.937E-03 SW 632.

632.

1.991E-03 1.934E-03 632.

9.104E-03 8.813E-03 WSW 555.

555.

2.429E-03 2.359E-03 555.

1.404E-02 1.359E-02 W

518.

518.

3.562E-03 3.448E-03 518.

1.430E-02 1.384E-02 WNW 503.

503.

3.806E-03 3.685E-03 503.

1.449E-02 1.403E-02 NW 495.

495.

4.350E-03 4.211E-03 495.

1.371E-02 1.327E-02 NNW 510.

510.

4.647E-03 4.498E-03 510.

1.439E-02 1.393E-02 Braidwood Site Meteorological Data 1/78 - 12/87 F-23 m.

-m.

BRAIDWOOD R: vision 3 August 1998 Table F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-83m Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 305.

305.

3.994E-04 3.012E-04 305.

1.521E-03 1.147E-03 NNE 265.

265.

3.883E-04 2.928E-04 265.

1.406E-03 1.060E-03 NE 299.

299.

1.555E-04 1.173E-04 299.

9.211E-04 6.945E-04 ENE 361.

361.

1.372E-04 1.034E-04 361.

7.062E-04 5.325E-04 E

355.

355.

1.785E-04 1.346E-04 355.

9.139E-04 6.891E-04 ESE 425.

425.

1.505E-04 1.135E-04 425.

7.634E-04 5.756E-04 SE 448.

448.

1.196E-04 9.017E-05 448.

6.583E-04 4.964E-04 SSE 540.

540.

6.996E-05 5.275E-05 540.

4.053E-04 3.056E-04 S

530.

530.

6.499E-05 4.900E-05 530.

4.639E-04 3.498E-04 SSW 540.

540.

5.532E-05 4.171E-05 540.

3.829E-04 2.887E-04 SW 632.

632.

5.930E-05 4.472E-0 632.

3.694E-04 2.786E-04 WSW 555.

555.

8.469E-05 6.386E-05 555.

5.942E-04 4.480E-04 W

500.

500.

1.045E-04 7.876E-05 500.

6.646E-04 5.011E-04 WNW 434.

434.

1.497E-04 1.129E-04 434.

8.320E-04 6.273E-04 NW 428.

428.

1.537E-04 1.159E-04 428.

7.562E-04 5.702E-04 NNW 442.

442.

1.633E-04 1.231E-04 442.

7.667E-04 5.781E-04 Braidwood Site Meteorological Data 1/78 - 12/87 Note: Based on Reference 1 of Section F.2 and the formulas in Sections B 5 and B.6 of Appendix B.

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

l O

O 9

CR R: vision <

August 1998 Table F-7e (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-85m Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mrad /yr)/(uCi/sec)

(meters)

(mrad /yr)/(uCi/sec)

N 305.

305.

2.263E-03 2.169E-03 305.

6.552E 6.259E-03 NNE 265.

265.

2.146E-03 2.056E-03 265.

5.928E-03 5.662E-03 t

NE 299.

299.

1.094E-03. 1.050E-03 299.

4.111E-03 3.928E-03 ENE 361.

361.

9.475E-04 9.097E-04 361.

3.165E-03 3.025E-03 E

355.

355.

1.197E-03 1.149E-03 355.

4.072E-03 3.891E-03 ESE 425.

425.

1.073E-03 1.031E-03 425.

3.584E-03 3.427E-03 i

SE 448.

448.

9.074E-04 8.718E-04 448.

3.167E-03 3.029E-03 SSE 540.

540.

6.068E-04 5.836E-04 540.

2.086E-03 1.997E-03 S

530.

530.

5.227E-04 5.023E-04 530.

2.351E-03 2.249E-03 SSW 540.

540.

4.797E-04 4.613E-04 540.

1.999E-03 1.913E-03 SW 632.

632.

5.199E-04 4.999E-04 632.

1.989E-03 1.905E-03 WSW 555.

555.

6.707E-04 6.444E-04 555.

3.061E-03 2.929E-03 W

500.

500.

7.204E-04 6.915E-04 500.

3.224E-03 3.083E-03 i

WNW 434.

434.

8.947E 8.578E-04 434.

3.764E-03 3.597E-03 NW 428.

428.

9.954E-04 9.552E-04 428.

3.505E-03 3.351E-03 NNW 442.

442.

1.068E 1.025E-03 442.

3.712E-03 3.551E-03 l

Braidwood Site Meteorological Data 1/78-12/87 t

i P

I I

F-25 u.1 m

BRAIDWOOD Rsvision 3 August 1998 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-85 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

- N 305.

305.

2.521 E-05 2.437E-05 305.

7.053E-05 6.820E-05 NNE 265.

265.

2.389E-05 2.310E-05 265.

6.351E-05 6.141E-05 NE 299.

299.

1.248E-05 1.207E-05 299.

4.443E-05 4.296E-05 ENE 361.

361.

1.083E-05 1.047E-05 361.

3.404E-05 3.292E-05 E

355.

355.

1.366E-05 1.320E-05 355.

4.396E-05 4.251E-05 ESE 425.

425.

1.220E-05 1.180E-05 425.

3.889E-05 3.760E-05 SE 448.

448.

1.042E-05 1.008E-05 448.

3.470E-05 3.355E-05 SSE 540.

540.

7.029E-06 6.797E-06 540.

2.290E-05 2.215E-05 S

530.

530.

6.111E-06 5.909E-06 530.

2.632E-05 2.545E-05 SSW 540.

540.

5.594E-06 5.409E-06 540.

2.217E-05 2.144E-05 i

SW 632.

632.

6.098E-06 5.897E-06 632.

2.227E-05 2.154E-05 WSW 555.

555.

7.85BE-06 7.599E-06 555.

3.400E-05 3.288E-05 W

500.

500.

8.255E-06 7.983E-06 500.

3.541 E-05 3.424E-05 l

WNW 434.

434.

1.009E-05 9.757E-06 434.

4.111E-05 3.976E-05 NW 428.

428.

1.131E-05 1.093E-05 428.

3.802E-05 3.677E-05 NNW 442.

442.

1.209E-05 1.169E-05 442.

4.056E-05 3.922E-05 l

i Braidwood Site Meteorological Data 1/78 - 12/87 l

l t

i l

9 Os 9

- - - ~ _ _ __ - -

B Revision August 1998 -

Table F-7a (Continued):

. Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-87 Downwind Restricted _

Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

-(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 305.

305.

7.480E-03 7.264E-03 305.

1.972E-02 1.9 e 5E-02

, NNE 265.

265.

7.100E-03 6.895E-03 265.

1.802E-02 1.749E-02

.NE 299.

299.

3.780E-03 3.671E-03 299.

1.225E-02 1.189E-02 ENE 361.

361.

3.246E-03 3.152E-03 361.

9.572E-03 9.294E-03 E-355.

355.

4.060E-03 3.943E-03 355.

1.220E-02 1.185E-02 ESE 425.

425.

3.644E-03 3.539E-03 425.

1.068E-02 1.037E-02 SE 448.

448.

3.081 E 2.992E-03 448.

9.262E-03 8.992E-03 SSE 540.

540.

2.111 E-03 2.050E-03 540.

6.149E-03 5.971E-03 S

530.

530.

1.762E-03 1.711E-03 530.

6.549E-03 6.359E-03 SSW 540.

540.

1.664E-03 1.616E-03 540.

5.727E-03

' 5.561E-03 SW 632.

632.

1.758E-03 1.707E-03 632.

5.625E-03 5.462E-03 WSW 555.

555.

2.229E-03 2.165E-03 555.

8.703E-03 8.450E-03.

W 500.

500.

2.375E-03 2.306E-03 500.

9.363E-03 9.090E-03 WNW 434.

434.

2.903E-03 2.818E-03 434.

1.098E-02 1.066E-02 NW 428.

428.

3.315E-03 3.219E-03 428.

1.044E-02 1.014E-02 NNW 442.

442.

3.533E-03 3.431E-03 442.

1.090E-02 1.058E-02 Braidwood Site Meteorological Data 1/78 - 12/87 F-27

"JRAIDWOOD R: vision 3 August 1998 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-88 Downwind Restricted Mixed Mode (Vent) Release Ground Levt ' Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 305.

305.

1.790E-02 1.739E-02 305.

4.712E-02 4.574E-02 NNE 265.

265.

1.6.98E-02 1.650E-02 265.

4.272E-02 4.146E-02 NE 299.

299.

9.121E-03 8.865E-03 299.

2.947E-02 2.861E-02 ENE 361.

361.

7.868E-03 7.647E-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.

2.578E-02 2.503E-02 SE 448.

448.

7.516E-03 7.306E-03 448.

2.271E-02 2.205E-02 SSE 540.

540.

5.155E-03 5.012E-03 540.

1.505E-02 1.462E-02 S

530.

530.

4.382E-03 4.260E-03 530.

1.666E-02 1.618E-02 SSW 540.

540.

4.092E-03 3.978E-03 540.

1.429E-02 1.388E-02 SW 632.

632.

4.389E-03 4.267E-03 632.

1.422E-02 1.381E-02 WSW 555.

555.

5.589E-03 5.433E-03 555.

2.182E-02 2.119E-02 W

500.

500.

5.844E-03 5.680E-03 500.

2.308E-02 2.241E-02 WNW 434.

434.

7.074E-03 6.873E-03 434.

2.690E-02 2.612E-02 NW 428.

428, 8.064E-03 7.837E-03 428.

2.520E-02 2.447E-02 NNW 442.

442 8.580E-03 8.33BE-03 442.

2.660E-02 2.583E-02 Braidwood Site Meteorological Data 1/78 - 12/87 i

6 s

BRAIg,,

R vision 3o-August 1998 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-89 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 305.

305.

1.243E-02 1.208E-02 305.

2.613E-02 2.538E-02 NNE 265.

265.

1.213E-02 1.178E-02 265.

2.655E 2.579E-02 NE 299.

299.

6.070E-03 5.896E-03 299.

1.43BE-02 1.397E-32 ENE 361.

361.

4.638E-03 4.506E-03 361.

1.132E-02 1.099E-02 E

355.

355.

5.715E-03 5.551E-03 335.

1.360E-02 1.321E-02 EGE 425.

425.

5.133E-03 4.986E-03 425.

1.084E-02 1.053E-02 SE 448.

448.

4.043E-03 3.927E-03 448.

8.014E-03 7.784E-03 SSE 540.

540.

2.636E-03 2.561 E-03 540.

5.137E-03 4.990E-03 S

530.

530.

1.936E-03 1.880E-03 530.

4.055E-03 3.938E-03 SSW 540.

540.

1.970E-03 1.914E-03 540.

4.039E-03 3.922E-03 SW 632.

632.

1.750E-03 1.700E-03 632.

3.181E-03 3.089E-03 WS~

555.

555.

2.009E-03 1.951E-03 555.

4.608E-03 4.475E-03 W

500.

500.

2.313E-03 2.247E-03 500.

5.385E-03 5.230E-03 WNW 434.

434.

3.129E 3.040E-03 434.

7.749E-03 7.526E-03 NW 428.

428.

4.110E-03 3.993E-03 428.

9.703E-03 9.424E-03 NNW 442.

442.

4.671E-03 4.537E-03 442.

1.017E-02 9.878E-03 Braidwood Site Meteorological Data 1/78 - 12/87 I

F-29

Revision 3 BRAIDWOOD August 1998 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 Ground Level Release Downwind Restricted Mixed Mode (Vent) Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mrad /yr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 305.

305.

5.688E-03 5.515E-03 305.

8.218E-03 7.966E-03 NNE 265.

265.

6.051E-03 5.86BE-03 265.

9.375E-03 9.087E-03 299.

2.447E-03 2.374E-03 299.

3.836E-03 3.719E-03 NE 299.

y ENE 361.

361.

1.410E-03 1.367E-03 361.

1.941E-03 1.882E-03 E

355.

355.

1.896E-03 1.833E-03 355.

2.575E-03 2.496E-03 ESE 425.

425.

1.516E-03 1.470E-03 425.

1.818E-03 1.762E-03 SE 448.

448.

1.u32E-03 1.001E-03 448.

1.147E-03 1.112E-03 SSE 540.

540.

5.186E-04 5.030E-04 540.

6.013E-04 5.830E-04 S

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.

4.345E-04 4.213E-04 SW 632.

632.

2.254E-04 2.186E-04 632.

1.980E-04 1.920E-04 WSW 555.

555.

2.280E-04 2.212E-04 555.

1.855E-04 1.799E-04 W

500.

500.

3.175E-04 3.080E-04 500.

1.971E-04 1.911E-04 WNW 434.

434.

5.483E-04 5.319E-04 434.

4.559E-04 4.420E-04 NW 428.

428.

8.796E-04 8.532E-04 428.

9.766E-04 9.468E-04 l

NNW 442.

442.

1.222E-03 1.185E-03 442.

1.523E-03 1.477E-03 l

\\

Braidwood Site Meteorological Data 1/78 - 12/87 O

9" O

Revision August 1998 Table F-7a (Continued)

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

Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

.VBAR Radius G

GBAR

{

(meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(r rad /yr)/(uCi/sec)

N 305.

305.

3.585E-04 2.801E-04 305.

1.342E-03 1.040E-03 NNE 265.

265.

3.471E-04 2.710E-04 265.

1.225E-03 9.489E-04 l

NE 299.

299.

1.442E-04 1.135E-04 299.

8.221E-04 6.377E-04 ENE 361.

361.

1.274E-04 1.002E-04 361.

6.227E-04 4.832E-04 E

355.

355.

1.664E-04 1.307E-04 355.

8.136E-04 6.311E-04 i

ESE 425.

425.

1.40GE-04 1.108E-04 425.

6.887E-04 5.349E-04 SE 448.

448.

1.152E-04 9.088E-05 448.

6.093E-04 4.733E-34 i

SSE 540.

540.

6.798E-05 5.395E-05 540.

3.772E-04 2.936E-04

[

S 5?O.

530.

6.550E-05 5.172E-05 530.

4.533E-04 3.523E-04 i

SSW 540.

540.

5.419E-05 4.299E-05 540.

3.656E-04 2.846E-04 SW 632.

632.

6.073E-05 4.813E-05 632.

3.620E-04 2.819E-04 WSW 555.

555.

8.569E-05 6.762E-05 555.

5.701E-04 4.435E-04 l

W 500.

500.

1.006E-04 7.904E-05 500.

6.184E-04 4.805E-C4 WNW 434.

434.

1.391E-04 1.088E-04 434.

7.616E-04 5.9072-04

)

NW 428.

428.

1.429E-04 1.121E-04 428.

6.807E-04 5.285E-04 NNW 442.

442.

1.521E-04 1.194E-04 442.

7.027E-04 5.461E-04 l

I Braikood Site Meteorological Data 1/78-12/87 l

h

?

i

[

i F-31

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

Revision 3 BRAIDWOOD August 1998 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133m Ground Level Release Downwind Restricted Mixed Mode (Vent) Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 305.

305.

6.308E-04 5.411E-04 305.

2.135E-03 1.798E-03 NNE 265.

265.

6.053E-04 5.184E-04 265.

1.940E-03 1.632E-03 NE 299.

299.

2.759E-04 2.399E-04 299.

1.321E-03 1.115E-03 ENE 361.

361.

2.417E-04 2.099E-04 361.

1.005E-03 8.488E-01 E

355.

355.

3.110E-04 2.695E-04 355.

1.307E-03 1.103E-03 ESE 425.

425.

2.701E-04 2.350E-04 425.

1.125E-03 9.516E-04 SE 448.

448.

2.251E-04 1.964E-04 448.

9.971E-04 8.442E-04 SSE 540.

540.

1.413E-04 1.245E-04 540.

6.32SE-04 5.379E-04 S

530.

530.

1.293E-04 1.131E-04 530.

7.461E-04 6.326E-04 SSW 540.

540.

1.123E-04 9.889E-05 540.

6.124E-04 5.209E-04 SW 632.

632.

1.243E-04 1.092E-04 632.

6.091E-04 5.186E-04 WSW 555.

555.

1.679E-04 1.466E-04 555.

9.488E-04 8.060E-04 W

500.

500.

1.883E-04 1.632E-04 500.

1.014E-03 8.589E-04 WNW 434.

434.

2.477E-04 2.129E-04 434.

1.222E-03 1.031E-03 NW 428.

428.

2.634E-04 2.277E-04 428.

1.107E-03 9.360E-04 NNW 442.

442.

2.813E-04 2.434E-04 442.

1.157E-03 9.803E-04 l

l Braidwood Site Meteorological Data 1/78 - 12/87 F-32

B R: vision 3-August 1998_

Table F-7a (Continued) '

' Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133

?

Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meteis).

(mrad /yr)/(uCi/sec)

N 305.

305.

6.810E-04 6.050E-04 305.

2.299E-03 2.013E-03 NNE 265.

265.

6.509E-04 5.774E-04 265.

2.084E-03 1.823E !

NE 299.

299.

2.984E-04 2.679E-04 299.

1.431E-03 1.256E-03 l

ENE 361.

361.

2.612E-04 2.343E-04 361.

1.090E-03 9.571E-04 i

E 355.

355.

3.363E-04 3.011E-04 355.

1.414E-03 1.241E-03 ESE 425.

425.

2.954E-04 2.656E-04 425.

1.226E-03 1.079E-03 SE 448.

448.

2.460E-04 2.216E-04 448 1.088E-03 9.581E-04

(

SSE 540.

540.

1.5E5E-04 1.411E-04 540.

6.963E-04 6.158E-04 i

S 530.

530.

1.408E-04 1.270E-04 530.

8.174E-04 7.209E-04

.[

SSW 540.

540.

1.231E 1.117E-04 540.

6.754E-04 5.974E-04 t

SW 632.

632.

1.367E-04 1.238E-04 632.

6.726E-04 5.954E-04 i

WSW 555.

555.

1.830E-04 1.649E-04 555.

1.044E-03 9.224E-04 W-500.

500.

2.055E-04 1.842E-04 500.

1.108E-03 9.759E-04 t

WNW 434.

434.

2.689E-04 2.394E-04 434.

1.323E-03 1.160E-03 NW 428.

428.

2.860E-04. 2.557E-04 428.

1.204E-03 1.059E-03 NNW 442.

442.

3.071 E-04 2.749E-04 442.

1.266E 1.116E-03 Braidwood Site Meteorological Data 1/78 - 12/87

[

t F-33 i

m

BRAIDWOOD R: vision 3 August 1998 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 Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Padius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mr..dlyr)/(uCi/sec)

N 305.

305.

4.596E-03 4.429E-03 305.

1.180E-02 1.135E-02 NNE 265.

265.

4.387E-03 4.227E-03 265.

1.125E-02 1.082E-02 NE 299.

299.

2.254E-03 2.174E-03 299.

7.028E-03 6.764E-03 ENE 361.

301.

1.883E-03 1.816E-03 361.

5.738E-03 5.523E-03 E

355.

d.5.

2.326E-03 2.242E-03 355.

7.076E-03 6.311E-03 i

ESE 425.

425 2.121E-03 2.046E-03 425.

6.001E-03 5.778E-03 SE 448.

448.

1.723E-03 1.662E-03 448.

4.819E-03 4.640E-03 SSE 540.

540.

1.178E-03 1.137E-03 540.

3.220E-03 3.101E-03 S

530.

530.

9.052E-04 8.734E-04 530.

2.852E-03 2.747E-03 SSW 540.

540.

9.038E-04 8.720E-04 540.

2.739E-03 2.638E-03 SW 632.

632.

8.898E-04 8.587E-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.

4.617E-03 4.446E-03 WNW 434.

434.

1.593E-03 1.536E-03 434.

5.652E-03 5.441E-03 NW 428.

428.

1.869E-03 1.802E-03 428.

5.820E-03 5.603E-03 NNW 442.

442.

2.013E-03 1.940E-03 442.

5.812E-03 5.596E-03 Braidwood Site Meteorological Data 1/78 - 12/87

-34

m p

BRAI D

Rsvision August 1998 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 305.

305.

3.039E-03 2.936E-03 305.

8.709E-03 8.406E-03 NNE 265.

265.

2.880E-03 2.781E-03 265.

7.856E-03 7.583E-03 NE 299.

299.

1.481E-03 1.431E-03 299.

5.482E-03 5.292E-03 ENE 361.

361.

1.284E-03 1.241E-03 361.

4.211E-03 4.065E-03 E

355.

355.

1.621E-03 1.567E-03 355.

5.425E-03 5.237E-03 ESE 425.

425.

1.455E-03 1.406E-03 425.

4.794E-03 4.629E-03 SE 448.

448.

1.235E-03 1.194E-03 448.

4.257E-03 4.110E-03 SSE 540.

540.

8.285E-04 8.008E-04 540.

2.811E-03 2.714E-03 S

530.

530.

7.163E-04 6.923E-04 530.

3.197E-03 3.087E-03 SSW 540.

540.

6.561 E-04 6.342E-04 540.

2.709E-03 2.615E-03 SW 632.

632.

7.144E-04 6.906E-04 632.

2.708E-03 2.615E-03 WSW 555.

555.

9.205E-04 8.896E-04 555.

4.150E-03 4.007E-03 W

500.

500.

9.804E-04 9.473E-04 500.

4.340E-03 4.190E-03 WNW 434.

434.

1.210E-03 1.168E-03 434.

5.044E-03 4.869E-03 NW 428.

428.

1.348E-03 1.302E-03 428.

4.686E-03 4.524E-03 NNW 442.

442.

1.446E-03 1.397E-03 442.

4.987E-03 4.815E-03 Braidwood Site Meteorological Data 1/78 - 12/87 e

l' F-35

BRAIDWOOD Revision 3 August 1998 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-137 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/sec)

N 305.

305.

1.764E-03 1.707E-03 305.

3.915E-03 3.788E-03 NNE 265.

265.

1.712E-03 1.657E-03 265.

3.949E-03 3.821E-03 l

l 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 l

E 355.

355.

8.157E-04 7.893E-04 355.

2.100E-03 2.032E-03 l

ESE 425.

425.

7.381 E-04 7.142E-04 425.

1.690E-03 1.636E-03 l

SE 448.

448.

5.802E-04 5.615E-04 448.

1.259E-03 1.219E-03 l

SSE 540.

540.

3.822E-04 3.699E-04 540.

8.154E-04 7.890E-04 l

S 530.

530.

2.803E-04 2.713E-04 530.

6.471E-04 6.261E-04 l

SSW 540.

540.

2.864E-04 2.772E-04 540.

6.459E-04 6.250E-04 SW 632.

632.

2.577E-04 2.493E-04 632.

5.246E-04 5.076E-04 WSW 555.

555.

2.977E-04 2.881E-04 555.

7.771E-04 7.519E-04 W

500.

500.

3.453E-04 3.341E-04 500.

9.141 E-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.PME-04 428.

1.543E-03 1.493E-03 NNW 442.

442.

6.784E-04 6.# LO4 442.

1.588E-03 1.537E-03 Braidwood Site Meteorological Data 1/78 - 12/87 O

O O

_.s.]

O BR R: vision 3 August 1998 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-138 Downwind Restricted Mixed Mode (Vent) Release Gruund Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (metes,'

(meters)

(mradlyr)/(uCi'sec)

(meters)

(mradlyr)/(uCi/sec)

N M/

305.

1.001E-02 9.714E-03 305.

2.457E-02 2.384E-02 NNE SM 265.

9.553E-03 9.273E-03 265.

2.347E-02 2.278E-02 NE 29's.

299.

5.016E-03 4.870E-03 299.

1.459E-02 1.416E-02 ENE 361.

361.

4.169E-03 4.048E-03 361.

1.195E-02 1.160E-02 E

355.

355.

5.137E-03 4.988E-03 355.

1.471E-02 1.427E-02 ESE 425.

425.

4.679E-03 4.543E-03 425.

1.247E-02 1.210E-02 SE 448.

448.

3.827E-03 3.716E-03 448.

9.982E-03 9.687E-03 SSE 540.

540.

2.630E-03 2.554E-03 540.

6.694E-03 6.497E-03 S

530.

530.

2.023E-03 1.964E-03 530.

5.857E-03 5.684E-03 SSW 540.

540.

2.021E-03 1.962E-03 540.

5.661E-03 5.495E-03 r

SW 632.

632.

1.991E-03 1.934E-03 632.

5.226E-03 5.072E-03 l

WSW 555.

555.

2.429E-03

?.359E-03 555.

8.199E-03 7.957E-03 W

500.

500.

2.739E-03

<.659E-03 500.

9.502E-03 9.221E-03 WNW 434.

434.

3.459E-03 3.358E-03 434.

1.164E-02 1.130E-02 NW 428.

428.

4.093E-03 3.974E-03 428.

1.207E-02 1.17?E-02 NNW 442.

442.

4.3N-03 4.271E-03 442.

1.204E-02 1.169E-02 Braidwood Site Meteorological Data 1/78 - 12/87 1

F-37

ERAIDWOOD R: vision 3 August 1998 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Ar-41 Downwind Restricted Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius V

VBAR Radius G

GBAR (meters)

(meters)

(mradlyr)/(uCi/sec)

(meters)

(mradlyr)/(uCi/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.

2.826E-02 2.736E-02 NE 299.

299.

5.833E-03 5.646E-03 299.

1.936E-02 1.874E-02 ENE 361.

361.

5.023E-03 4.863E-03 361.

1.505E-02 1.456E-02 E

355.

355.

6.295E-03 6.094E-03 355.

1.925E-02 1.864E-02 ESE 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.

1.477E-02 1.430E-02 SSE 540.

540.

3.262E-03 3.157E-03 540.

9.781E-03 9.468E-03 S

530.

530.

2.756E-03 2.667E-03 SSO.

1.066E-02 1.032E-03 SSW 540.

540.

2.580E-03 2.497E-03 540.

9.211E-03 8.917E-03 SW 632.

632.

2.748E-03 2.660E-03 632.

9.104E-03 8.813E-03 WSW 555.

555.

3.504E-03 3.392E-03 555.

1.404E-02 1.359E-02 W

500.

500.

3.715E-03 3.596E-03 500.

1.498E-02 1.450E-02 WNW 434.

434.

4.539E-03 4.393E-03 434.

1.753E-02 1.697E-02 NW 428.

428.

5.159E-03 4.994E-03 428.

1.652E-02 1.599E-02 NNW 442.

442.

5.499E-03 5.323E-03 442.

1.734E-02 1.679E-02 Braidwood Site Meteorological Data 1/78 - 12/87 F-38

Revision $

- BRAI August 1998 i

Supplemental Table A Mixed Mode Joint Frequency Distribution Table Summaries 203 Foot Elevation Data Summary Table of Percent by Direction and Class Class N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TotM i

A 290

.321

.441

.315

.303 256

.292 266

.474

.369

.202

.197

.191

.2 74

.463

.421 5 076 B

.197 241

.284 208 205

.167

.198

.220

.352

.288

.190

.192

.206

.225

.327

.335 3 833 L

C

.321

.302

.421

.293

.201

.203

.277 312

.437

.404

.322

.342

.373

.399

.457

.409 5 474 D

1.523 1.590 2.149 1.974 1.372 1.014 1324 1529 2 031 1.900 1.899 1.846 2,109 2.248 2.191 2 014 28 713 E

.679

.612

.764

.976

.986

.870 1,136 1.439 2.079 1 501 1 065

.921

.993 1.133

.922

.790 16 866 F

.344

.278

.260 298

.387

.496 530

.438 559

.526

.386

.397

.589

.688

.556

.417 7.148 G

.166

.095

.098

.078

.156

.174 2 70 213

.186

.199

.258

.210

.253

.266

.184

.159 2 966 I

TotM 3 520 3 439 4 418 4.143 3 611 3.180 4 025 4.418 6.118 5.187 4.322 4.104 4.714 5.231 5 100 4 545 70 076 i

Summary Table of Percent by Direction and Speed Speed N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW TotM i

.45

.008

.016

.027

.025

.001

.000

.017

.017

.001

.001

.002

.016

.037

.026

.001 026

.222 1.05

.044

.032

.042

.045

.026

.025

.036

.031

.032

.023

.033

.025

.037

.035

.040 026 332 2.05

.224

_266

.281

.260

.239 213

.243 225

.237

_220

.208

.208

.262

_244

.244

.243 3 819 3.05

.405

.426 540

.610

.459

.334

.467

.438

.596

.383

.393

.384

.447

.437

.507 487 7.313 4 05

.669

.622

.756

.973

.670

.453

.614

.663

.695

.543

.596

.663

.678

.702

.749

.782 10 829 5 05

.624 319

.875

.926

.681

.482

.669

.639

.769 677

.711

.681

.738

.782

.889 808 11 470 6 05

.670

.607

.761

.675

.674

.587

.s.57

.729

.944

.825

.833

.766

.788

.975

.909

.876 12.279 8 05

.732

.789

.956 5 34

.726

.919 1.073 1.227 2.070 1.858 1268 1.131 1.378 1598 1.381 1 041 18 680 l

10 05

.137

.154

.174

.094

.127

.158

.235

.423

.72 7

.621

.265

.216

.331

.404

.359

.245 4 667 r

13 05

.007

.008

.005

.002

.008

.010

.014

.026

.047

.037

.012

.012

.017

.028

.020

.012

.265 18 00

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000 000

.000 I

99 00

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000

.000 000

.000 TotM 3 520 3.439 4 418 4.143 3 611 3 180 4 025 4 418 6.118 5.187 4 322 4 104 4.714 5231 5.100 4 545 70 076 NOTE:

Wind directions in tables are presented in " Wind from" and not " Wind to" direction.

In order to determine the final mixed mode values,70.076% of the elevated value (presented in the 250 FT Mixed Mode table) and 29.924% of the ground level value (presented in the 30 FT Mixed Mode table) are used to calculate the final values.

F-39

Revision 3 BRAIDWOOD August 1998 Supplemental Table A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 203 Foot Elevation Data i

Summary Table of Percent by Speed and Class i

Class A

B C

D E

F G

Speed i

t

.45

.006

.005

.006

.075

.052

.048

.030

[

1.05

.014

.025

.027

.200

.108

.071

.086 2.05

.175

.197

.378 1.756

.659

.372

.283 3 05

.500

.593 836 3.100 1.206 683

.393 l

4 05

.803

.697 1 005 4 441 2.225 1.083

.575 1

5 05

.880

.674

.921 4 456 2.845 1.230

.464 6 05 885

.588 806 4.760 3.357 1.417

.466 8 05 1.469

.854 1.160 7.631 5 000 1.976

.591 to 05

.325

.190

.320 2.165 1.332

.259

.076 13 05

.018

.011

.015

.129

.081

.009

.002 7

18 00

.000

.000

.000

.000

.000

.000

.000 99 00

.000

.000

.000

.000

.000

.000 000 l

I i

b l

I t

l l

l h

1 i

F-40

A Rsvision 3 August 1998 Supplemental Table A - Continued -

Mixed Mode Joint Frequency Distribution Table Summaries 34 Foot Elevation Data l

Summary Table of Percent by Direction and Class

[

2 Cines N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Total i

l A

.068

.071

.077

.054

.100

.075

.110

.135

.278 215

.062

.050

.127

.270 257

.176 2.125 i

B

.054

.044

.050

.031 A35

.049

.081

.083

.172

.123

.058

.045

.121

.178

.150

.098 1357 C

.067

.056

.008

.059

.044

.049

.001

.124

.212

.133

.121

.082

.212

.276

.219

.164 2 005 D

.453

.551

.613

.453

.420

.423

.641

.926 1.487 1.230

.697

.717 1.084 1.496 1.044 889 13 125

[

E

.304

.387

.249

.180

.230

.368

.580 1.093 1.991 1.311

.435

.346

.299

.343 227

.317 8 659 F

.044

.063

.050

.069

.086

.160

.161

.137

.330

.306

.077

.133

.144

.130

.074

.050 2 014 i

G

.022

.006

.013

.025

.035

.059

.061 037

,102

.079

.024

.058

.039

.038

.026

.017

.641 l

[

Total 1.012 1.177 1.159

.860

.950 1.181 1.705 2.535 4 580 3.397 1.475 1.430 2.027 2.729 1 997 1209 29 924 l

r i

i Summary Table of Percent by Direction and Speed i

i Speed N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Total i

E

.43

.014

.002

.014

.018

.010

.009

.004

.008

.001

.001

.000

.000

.005

.000 A08

.000

.096 l

1.05

.014

.016

.027

.048

.085

.061

.030

.025

.013

.010 Ato

.016

.019

.018

.018

.017

.408 j

2.05

.051

.052

.093

.181

.246

.259

.165

.099

.072

.055

.051

.087

.119

.138

.103

.077 1.849

[

3 05

.121

.145

.172

.202

.189 251

.309 248

.269

.222

.166

.260

.234

.213

.174

.151 3 325 l

4.05

.158

.155

.187

.158

.173

.215

.319

.364

.490

.509

.246

.222

.241

.243

.237

.220 4 139

[

5 05

.130

.134

.156

.123

.152

.191

.296

.385

.600

.521

.236

.146

.233

.287 2 70

.214 4 075 i

6.05

.141

.152

.186

.089

.098

.123

.310

.435

.718

.639

.216

.167

.244

.38"

.340

.247 4 499 f

8 05

.250

.325 268

.038 A17

.066

.236

.667 1.496 1.032

.420 321

.544

.922

.648

.498 7 748

(

10.05

.111

.168

.050

.001

.000

.001

.032

.214

.679

.302

.102

.117

.269

.371

.183

.199 2.799 13 05

.023

.029

.006

.000

.000

.000

.005

.076

.214

.102

.024

.082

.107

.131

.015

.076

.891 18.00

.000

.000

.000

.000

.000

.000

.000

.014

.027

.002

.004

.012

.011

.017

.000

.010

.096 99 00

.000

.000

.000

.000

.000

.000

.000

.000 000

.000

.000

.000

.000

.000

.000

.000 000 Total 1 012 1 177 1.159

.860

.950 1.181 1.705 2.535 4.580 3.397 1.475 1.430 2.027 2 729 1 997 1.709 29 924 r

l NOTE:

Wind directions in tables are presented in " Wind from" and not " Wind to" direction.

I r

(

F-41

ERAIDWOOD R: vision 3 August 1998 Supplemental Table A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 34 Foot Elevation Data Summary Table of Percent by Speed and Class Class A

B C

D E

F G

Speed

.45

.000

.000

.000

.006

.015

.031 S44 1.05

.001

.001

.003

.049

.126

.151

.076 2.05

.017

.020

.029

.335

.690

.531

.226 3 05

.127

.103

.157 1.118 1.175

.491

.155 4 05

.277

.192

.291 1.686 1 211 "l83

.098 5 05

.332

.209

.274 1.870 1.179

.176

.035 6 05

.381

.219

.358 2.236 1.223

.076

.005 8 05

.735

.445

.632 3.993 1.844

.098

.001 10 05

.214

.126

.211 1.358 837

.053

.000 13 05

.038

.040

.044

.424

.320

.024

.000 18 00

.001

.002

.004

.049

.040

.000 000 99 00 000

.000

.000

.000

.000

.000

.000 l

l 9

9 42 e

t BRAI Rsvision A August 1998

' Supplemental Table B i

Ground Level Joint Frequency Distribution Table Summaries j

f Summary Table of Percent by Direction and Class 1

Class '

N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Toad i

?

A 3 79 A15 A70

.394

.420 291 A17 A18

.728

. 637

.246

.229

.358

.572

.648 609 7.230

[

B 280

.288 336

.241

~.229

.206

.285

.332

.530 Att

.256

.206

.340 A07

.441 A31 5203 r

C 345 3 73

.501 358

.246

.226

.388 A71

.865

.521 A62 380

.598

.588

.624

.619 7.504

[

D 2.098 2216

' 2.532 2AB3 1.766 1.392 2 034 2.892 3 611 3.198 2.674 2.392 3.065 3.678 3.063 2 925 41.P20 E

.968 1.029

.914 1221 1.210 1.387 1.849 2.754 4.116 2.772 1298 1.258 1.197 1A11 1.052 1.068 25.502

)

F

.339 347 3 02

.382

.552

.788

.729

.805

.949

.850

.366

.630

.795

.765

.441

.313 9 153 L

G

.147

.074

.128

.163

.228

.358 330

.229 A04

.300

.133 268

.248

.233

.191

.157 3 588 Total 4.595 4 740 5.183 5242 4 650 4 647 6.012 7.502 11.013 8.687 5A35 5.359 6.600 7.753 6 460 6 122 100 000 i

i

?'

Summary Table of Percent by Direction and Speed t

i Speed N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Totd l

2

.45

.194

.111

.128

.160

.078

.087

.042

.123

.063 213

.078

.004

.037

.051

.101

.054 1 328 1.05

.219

.263

.364

.579

.686

.517 311

.267

.218

.181

.174

,196 257

.264

.275

.269 5 038 r

2.05

.630

.645

.996 1.658 1.833 1 698 1367

.962

.771

.631

.561

.842 1D76 1.159

.952

.780 16 571 i

3.05

.949 1.045 1.179 1J82 1.085 1 218 1.744 1.581 1.820 1 A35 1.12s 1.533 1.442 1.369 1.174 1.070 21.156 4.05

.915

.902 1,015

.839

.577 624 1.228 1.593 2.123 2.039 1.256 1.084 1.167 1.180 1.189 1.215 18 947 5 05

.650 641

.667 A16 260

.292

.641 1.126 1.881 1.520

.937

.609

.884 1.104

.995

.959 13.582 l

6 05 A95 462 A32

.159

.113

.143

.395

.758 1 A35 1236

.598

.445

.644

.936

.770

.751 9 771 f

8 05 A08 A72

.346

.046

.018

.067

.247

.785 1.782 1226

.573 A36

.706 1.160

.806

.738 9 815 10 05

.113 170

.050

.001

.000

.001

.032

.214

.679 302

.102

.116

.269

.372

.183

.201 2 805

?

{

13 05 023

.029

.006

.000

.000

.000

.005

.076

.214

.102

.024

.082

.107

.131

.015

.076

.889 18.00

.000

.000

.000

.000

.000

.000

.000

.014

.027

.002

.004

.012

.011

.017

.000

.010

.096 3

99.00

.000

.000

.000

.000

.000

.000 000

.000

.000

.000

.000

.000

.000

.000

.000

.000 000

[

Total 4.595 4 740 5 183 5242 4 650 4 647 6 012 7.502 11.013 8 687 5.435 5,359 6 600 7.753 6.460 6 122 100 000 j

i NOTE:

Wind directions in tables are presented in " Wind from" and not " wind to" direction.

r F-43 l

t f

BRAIDWOOD Revision 3 August 1998 Supplemental Table B -Continued Grcund Level Joint Frequency Distribution Table Summaries Summary Table of Percent by Speed and Cla<,s Class A

B C

D E

F G

Speed

.45

.027

.018

.021

.197

.339

.388

.338 1.05

.102

.093

.145 1.038 1.463 1.379

.818 2.05

.426

.498

.796 4.865 5 159 3:380 1.446 3 05 1.147 1.009 1.493 8.268 6.225 2.342

.672 l

4 05 1.618 1.158 1.699 8 574 4.596 1.059

.244 1

5.05 1.446

.969 1.213 6 908 2.689

.304

.055 6 05 1 155

.661 1.007 5.053 1.763

.118

.014 8 05 1.054

.629

.870 5 034 2.068

.107

.002 10.05

.215

.126

.212 1.360

.839

.053

.000 l

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