Text

Rev 0.K to ODCM, Chapter 10 & App F
	ML20035A665
Person / Time
Site:	Dresden
Issue date:	01/31/1993
From:	; COMMONWEALTH EDISON CO.
To:	;
References
	PROC-930131-04, NUDOCS 9303290137
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i February 24, 1993 k-i i

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

Please complete the following manual update:

. REMOVE JRSIRI Dresden Station Annex Dresden Station Annex Entire Chapter 10.

Entire Chapter 10

p. 10-1 to 10-111, Revision 0.K, Jan. 1993 10-1 to 10-22

p. 10-1 to 10-v, 10-1 to 10-18 Dr?sden Station Annex Dresden Station Annex Entire Appendix F Entire Appendix F

p. F-i to F-iv, Includes Rev. 0.K F-1 to F-41

p. F-1 to F-iv, F-1 to F-41 Please sign and date this control sheet and return to:

COMMONWEALTH EDISON COMPANY c/o Document Control - Emergency Preparedness 1400 Opus Pl.- 5th Floor Downers Grove, IL 60515 (708)663-6547 Your signature indicates you have verified that your control number is correct and you have updated your manual.

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

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10-12 0.K 10-13 0.K 10-14 0.K 10-15 0.K 10-16 0.K r

10-17 0.K 10-18 0.K I

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

I 10.1.1

System Description

I 10.1.1.1 Condenser Offgas Treatment System..............

I 10.1.1.2 Ventilation Exhaust Treatment System I

10.1.2 Radiation Monitors 2

10.1.2.1 Unit 1 Chimney Monitor 2

10.1.2.2 Units 2/3 Chimney Monitor..................

2 10.1.2.3 Reactor Building Vent Stack Effluent Monitors........

3 10.1.2.4 Reactor Building Ventilation Monitors............

3 10.1.2.5 Condenser Air Ejector Monitors 3

10.1.2.6 Isolation Condenser Vent Monitor 3

10.1.3 Alarm and Trip Setpoints 4

10.1.3.1 Setpoint Calculations.................

4 10.1.3.1.1 Reactor Building Vent Monitors 4

10.1.3.1.2 Condenser Air Ejector Monitors 4

10.1.3.1.3 Units 2/3 Plant Chimney Radiation Monitor..........

4 10.1.3.2 Release Limits 4

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

5 10.1.3.4 Conversion Factors 6

10.1.3.5 HVAC Fl ow Rates.......................

7 10.1.4 Allocation of Effluents from Common Release Points 7

10.1.5 Dose Projections 7

10.2 LIQUID RELEASE 7

10.2.1

System Description

7 10.2.1.1 Unit 1 Storage Tanks 8

10.2.1.2.

Units 2/3 Waste Sample Tanks 8

10.2.1.3 Units 2/3 Floor Drain Sample Tanks 8

10.2.1.4 Units 2/3 Waste Surge Tank 8

10.2.2 Radiation Monitors 8

10.2.2.1 Liquid Radwaste Effluent Monitor 8

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DRESDEN REVISION 0.K JANUARY 1993 1

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CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATHENT AND MONITORING TABLE OF CONTENTS (Cont'd) 10.2.2.2 Units 2/3 Service Water Effluent Monitors..........

8 10.2.2.3 Chemical Cleaning Facility Service Water Effluent Monitor..

9 i

10.2.3 Alarm and Trip Setpoints 9

10.2.3.1 Setpoint Calculations....................

9 10.2.3.1.1 Liqvid Radwaste Effluent Monitor 9

10.2.3.1.2 Units 2/3 Service Water Effluent Monitor 10 10.2.3.1.3 Chemical Cleaning Facility Service Water Effluent Monitor..

10 10.2.3.2 Discharge Flow Rates 10 10.2.3.2.1 Release Tank Discharge Flow Rate 10 10.2.3.3 Relecse Limits 11 10.2.3.4 Release Mixture.......................

11 10.2.3.S Conversion Factors 11 10.2.3.6 Liquid Dilution Flow Rates 11 10.2.4 Allocation of Effluents from Common Release Points 12 10.2.5 Projected Doses for Releases 12 10.3 SOLIDIFICATION OF WASTE /PROCFSS CONTROL PROGRAM.......

13 10-iii l

4 DRESDEN REVISION 0.K JANUARY 1993 CHAPTER 10 LIST OF TABLES NUMBER PAGE 10-1 Data for Determination of Dilution Flow Rates 10-14 r

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DRESDEN REVISION 0.K JANUARY 1993 J~

CHAPTER 10 LIST OF FIGURES NUMBER PAGE 10-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-15 10-2 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-16 10-3 Simplified Liquid Radwaste Processing and Liquid Effluent Flow Diagram 10-17 10-4 Simplified Solid Radwaste Processing Diagram 10-18 s

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DRESDEN REVISION 0.K JANUARY 1993 g(

CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1

System Description

i A simplified gaseous radwaste and gaseous effluent flow diagram is provided for Dresden Unit 1 in Figure 10-1 and for Dresden Units 2 and 3 in Figure 10-2.

Dresden 1 is no longer operational, but monitoring of potentially radioactive releases from the plant chimney continues.

Each airborne release point is classified as stack, vent, or ground level in accordance with the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A.

The principal release points for potentially radioactive airborne effluents and their classifications are as follows:

For Dresden 1, the plant chimney (a stack release point).

For Dresden 2/3:

-- The ventilation chimney (a stack release point).

s,

-- The reactor building ventilation stack (a vent release point).

10.1.1.1 Condenser Offgas Treatment System The condenser offgas treatment system is designed and -installed to reduce radioactive gaseous effluents by collecting non-condensable off-gases from the condenser and providing for holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The daughter products are retained by charcoal and HEPA filters. The system is described in Section 9.2 of the Dresden UFSAR.

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 selected effluent streams by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters prior to release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figures 10-1 and 10-2.

s 10-1

DRESDEN REVISION 0.K JANUARY 1993

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

10.1.2 Radiation Monitors 10.1.2.1 Unit 1 Chimney Monitor Monitor 1-SPING-4A continuously monitors the final effluent from the Unit I chimney.

The monitor has isokinetic sampling, gaseous grab sampling, and particulate and iodine sampling capability. Tritium samples are obtained using a portable sampling system. A tap is available for obtaining a sample from the isokinetic probe.

In normal operation all three noble gas channels (low, mid-range, high) are on line and active.

No automatic isolation or control functions are performed by this monitor.

10.1.2.2 Units 2/3 Chimney Monitor Monitor 2/3-SPING-4C continuously monitors the final effluent from the Units 2/3 chimney.

The monitor has isokinetic sampling, gaseous grab sampling, particulate and iodine sampling, and postaccident sampling capability. Tritium samples are obtained using a portable sampling system. A tap is available for obtaining a sample from the isolinetic probe.

In normal operation the two lower noble gas channels (low and mid-range) are on line and active. The high range noble gas channel flow is bypassed and this channel is in standby. On a high alarm the low and mid-range noble gas channels are bypassed and only the high range noble gas channel remains active.

No automatic isolation or contral functions are performed by this monitor.

Pertinent information on this monitor is provided in the Dresden 2/3 UFSAR Section 7.6.2.4.

In addition to the primary monitor described above, there is a backup system consisting of two additional detectors and sample taps in series in the primary sample stream.

t 10-2 1

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l DRESDEN REVISION 0.K JANUARY 1993 O

10.1.2.3 Reactor Building Vent Stack Effluent Monitors Monitor 2/3 SPING-4A continuously monitors the final effluent from the reactor building vent stack.

The vent stack monitor has isokinetic sampling, gaseous sampling, and iodine and particulate sampling capability.

Tritium samples are obtained using a portable sampling system.

A tap is available for obtaining a sample from the isokinetic probe.

All channels are continuously on line and active.

No automatic isolation or control functions are performed by this monitor.

10.1.2.4 Reactor Building Ventilation Monitors i

Monitors 2(3)-1735A/B continuously monitor the effluent from the Unit 2(3) reactor building ventilation.

On high alarm, the monitors automatically initiate closure of valves A02(3)A-5741, A02(3)B-5741, A02(3)A-5742, and A02(3)B-5742 thus isolating the Unit 2(3) reactor building ventilation, and initiate startup of the Unit 2/3 standby gas treatment system.

Pertinent information on these monitors is provided in Dresden UFSAR Section 7.6.2.5.

10.1.2.5 Condenser Air Ejector Monitors Monitors 2(3)-1733A/B and 2(3)-1738B continuously monitor gross gamma activity downstream of the Unit 2 and 3 steam jet air ejector and prior to release to the main chimney.

On high alarm monitors 2(3)-1733A/B automatically activate an interval timer which in turn initiates closure of air operated valve A02(3)-5406, thus terminating the release.

Pertinent information on these monitors is found in Dresden UFSAR Section 7.6.2.3.

10.1.2.6 Isolation Condenser Vent Monitor Monitors 2(3)-1736 A/B continuously monitor radioactivity in the effluent from the isolation condenser vent.

No control device is initiated by this monitor.

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DRESDEN REVISION 0.K

-JANUARY 1993

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Pertinent information'on this monitor is provided in Dresden UFSAR Section 7.6.2.10 10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Reactor Building Vent Monitors The alarm setpoint for the reactor building vent monitor is established at 4 mr/hr.

10.1.3.1.2 Condenser Air Ejector Monitors The high-high trip setpoint is established at s 100 pCi/Sec per MWt (e2.5E5 Ci/sec) and the high alarm is established at s 5"rCi/ set per MWt (*1.25E5pci/sec).

10.1.3.1.3 Units 2/3 Plant Chimney Radiation Monitor The setpoint is established at a count rate corresponding to 105,000 Ci/sec.

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10.1.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of 10 CFR 20 are not exceeded. The release limits are found by solving Equations 10-1 and 10-2 for the total allowed release rate, Q,v.

(1.11) { { f,[Q,,$, + Q,,V,]) < 500 mrem /yr (10-1)

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

+ (X/Q),Q,,exp-A,R/3600u,)]

(10-2)

+ (1.ll)(f )[Q,,S + Q,,V l) f i

i

< 3000 mrem /yr m) 10-4

DRESDEN REVISION 0.K JANUARY 1993 (V

The summations are over noble gas radionuclides i, f

Fractional Radionuclide Composition i

The release rate of noble gas radionuclide i divided by l

the total release rate of all noble gas radionuclides.

i Q,,

Total allowed Release Rate, Stack

[pCi/sec)

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

Q,,

Total Allowed Release Rate,

[pCi/sec]

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

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

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

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

Equation 10-2 is based on Equation A-9 of Appendix A and the 10 CFR 20 restriction on skin dose rate (3000 mrem /yr) due to noble gases released in gaseous effluents 1

(see Section A.I.3.2 of Appendix A).

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

10.1.3.3 Release Mixture In the determination of alarm and trip setpoints the radioactivity mixture in the exhaust air is assumed to have the following compositions.

Reactor building vent effluent monitors.

a The mixture used for the GE monitors is taken from a representative isotopic analysis of the vent stack noble gas released during the calendar quarter in which the 10-5

DRESDEN REVISION 0.K JANUARY 1993

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monitor is recalibrated. The " mixture" used for the SPING-4 is assumed to be a single pseudo-noble gas radionuclide.

Condenser air ejector monitor.

The mixture used for this monitor is taken from a representative isotopic analysis of noble gases collected at the recombiner outlet during the calendar quarter in which the monitor is recalibrated.

Units 2/3 plant chimney monitors.

The mixture used for the GE monitors is taken from the most recent isotopic analysis of noble gases collected from the chimney monitor during the calendar quarter in which the monitor is recalibrated. The " mixture" used for the SPING-4 is assumed to be a single pseudo-noble gas radionuclide.

10.1.3.4 Conversion Factors The conversion factors used to establish gaseous effluent monitor setpoints are obtained as follows.

Reactor building vent effluent monitor.

For the GE monitors, the isotopic analysis in Section 10.1.3.3 and the monitor reading (in mR/hr) at the time of the analysis are used to establish the conversion factor in mR/hr per pCi/cc.

For the SPING-4 the conversion factor is based on the 0.8 MeV gamma of the pseudo-noble gas radionuclide.

Condenser air ejector monitor.

The isotopic analysis in Section 10.1.3.3 and the flow and monitor reading (in mR/hr) at the time of the analysis are used to establish the conversion factor in mR/hr per Ci/cc.

Units 2/3 plant chimney monitors i

for the GE monitors, the isotopic analysis in Section 10.1.3.3 and flow and monitor reading (in CPS) at the time of the analysis are used to establish the conversion factor in CPS per Ci/cc. For the SPING-4 the conversion factor is based on the 0.8 MeV gamma of the pseudo-noble gas radionuclide.

i 10-6

DRESDEN REVISION 0.K JANUARY 1993

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10.1.3.5 HVAC Flow Rates The HVAC exhaust flow rates are obtained from either the Units 2/3 process computers or the SPING-4 control station.

If the actual flows are not available, the default values are:

Units 2/3 Chimney Air Flow....

1.00E10 cc/ min Units 2/3 Combined Reactor Vent.

6.23E9 cc/ min Unit 1 Chimney Air Flow.....

1.76E9 cc/ min 10.1.4 Allocation of Effluents from Common Release Points Radioactive gases, particulates, and iodir.es released from the Unit I chimney originate from Unit 1 only. However, radioactive gaseous effluents released from Units 2/3 are comprised of contributions from both units. Estimates of noble gas contributions from Units 2 and 3 are allocated considering appropriate operating conditions and measured SJAE off-gas activities. Allocation of radioiodine and radioactive particulate releases to Units 2 or 3 specifically is not as practical and is influenced greatly by in-plant leakage. Under normal operating conditions, allocation is made using reactor coolant iodine activities.

During unit shutdowns or periods of known major in-plant leakage, the apportionment is adjusted O

accordingly.

The allocation of effluents is estimated on a monthly basis.

10.1.5 Dose Projections Because the gaseous releases are continuous, the doses are routinely calculated in accordance with the RETS.

10.2 LIQUID RELEASES 10.2.1

System Description

A simplified liquid radwaste and liquid effluent flow diagram is provided in Figure 10-3.

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 evaporator, demineralizer and filter for the purpose of reducing the total radioactivity prior to reuse or release to the environment. The system is described in Section 9.3 of the Dresden Updated Final Safety Analysis Report.

10-7

DRESDEN REVISION 0.K JANUARY 1993 i

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j 10,2.1.1 Unit 1 Storage Tanks Liquid radioactive effluents are not released from Unit 1 Storage tanks directly to the environment but are made through the Units 2/3 radwaste system.

10.2.1.2 Units 2/3 Waste Sample Tanks There are three waste sample tanks (33,000 gallons each) which

' i' receive water from the liquid waste treatment system. These tanks are transferred to the waste surge tank for discharge to the Illinois river via the discharge canal.

10.2.1.3 Units 2/3 Floor Drain Sample Tanks There are two floor drain sample tanks (22,000 gallons each) which receive liquid waste from the floor drain treatment i

system. These tanks are transferred to the waste surge tank for discharge to the Illinois river via the discharge canal.

10.2.1.4 Units 2/3 Waste Surge Tank

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The waste surge tank receives processed water from the waste O

sample tanks and floor drain sample tanks. This tank

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discharges to the Illinois river via the discharge canal.

10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitor Monitor 2/3-1721 is used to monitor all releases from the waste j

surge tank. On high alarm, a grab sample of the effluent is automatically taken from the discharge side of the sample chamber after a 0 to 60 second delay determined by a locally mounted timer. The release is terminated manually by initiating closure of the low flow (A0 2001-170) or high flow (AO-2001-195) discharge line valves.

Pertinent information on the monitor and associated control devices is provided in Dresden UFSAR Section 7.6.2.9.

i 10.2.2.2 Units 2/3 Service Water Effluent Monitors Monitors 2(3)-1724 continuously monitor the service water f

ef fluent. On high alarm a grab sample is automatically taken.

i Pertinent information on these monitors is provided in Dresden UFSAR Table Section 9.6.2.8.

10-8

DRESDEN REVISION 0.K JANUARY 1993 O

10.2.2.3 Chemical Cleaning facility Service Water Effluent Monitor Monitor WASMC-06641-0700 continuously monitors service water effluent from the chemical cleaning facility. On high alarm the release is terminated by manually initiating closure of isolation valve AOS-06699-7904.

No control device is initiated by this monitor.

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

t 10.2.3.1.1 Liquid Radwaste Effluent Monitor The monitor setpoint is found by solving equation 10-3 for the total isotopic activity.

P s K x ({ C[/{ C[/MPC,) x ((40,000 + F',)/F',)

(10-3)

P Release Setpoint

[ cpm)

C[

Concentration of radionuclide i in

[pCi/mt] -

the re?2ase tank F',

Maximum Release Tank Discharge Flow Rate

[gpm]

The flow rate from the radwaste discharge tank.

The maximum pump discharge rate of 250 gpm is used for calculating the setpoint.

K Calibration constant

[ cpm /pCi/ml]

MPC, Maximum Permissible Concentration

[pC1/mt]

10-9 l

~

DRESDEN REVISION 0.K

[

JANUARY 1993 (M

L) 40,000 Dilution Flow

[gpm]

Releases are not permitted if the calculated dilution flow is less than 40,000 gpm. Once it has been determined that the dilution flow is 2 40,000 gpm, this value (40,000 gpm) is used even if the actual dilution flow is much greater.

10.2.3.1.2 Units 2/3 Service Water Effluent Monitor The monitor setpoint is established at two times the background radiation value.

10.2.3.1.3 Chemical Cleaning Facility Service Water Effluent Monitor The monitor setpoint is established at two times the background radiation value.

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

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

FL = 0.1(40,000/E (C, /MPC;))

(10-4)

The summation is over radionuclides i.

0.1 Reduction factor for conservatism.

FL Maximum Permitted Discharge Flow Rate

[gpm]

i The maximum permitted flow rate from the I

radwaste discharge tank. Releases are not permitted if the calculated discharge rate, F',, is less than 250 gpm.

[gpm]

i i

I 10-10

DRESDEN REVISION 0.K.

JANUARY 1993 i

40,000 Dilution Flow

[gpm]

r C,

Concentration of Radionuclide i in

[ Ci/mL) the Release Tank The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank.

MPC, Maximum Permissible

[pCi/ml]

Concentration of Radionuclide i 10.2.3.3 Release Limits Release limits are determined from 10 CFR 20.

Calculated maximum permissible discharge' rates are divided by 10 to ensure that applicable maximum permissible concentrations (MPC) are not exceeded.

10.2.3.4 Release Mixture

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For the liquid radwaste effluent monitor, the release mixture

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used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis.

For all other liquid effluent mon tors no release mixture is used because the setpoint is established at "two times background."

10.2.3.5 Conversion Factors The readout for the liquid radwaste effluent monitor is in CPM.

The calibration constant is based on the detector sensitivity to Co-60.

The readouts for the Units 2/3 service water effluent monitors are in pCi/mt. The calibration constants are based on the detector sensitivity to C0-60.

10.2.3.6 Liquid Dilution Flow Rates The dilution flow is determined using the information in Table 10-1.

However, by procedure the maximum dilution flow used for determining liquid radwaste release rates and setpoints is 40,000 gpm. Thus, even if the dilution flow exceeds 40,000 10-11

DRESDEN REVISION 0.K l

JANUARY 1993 i

i gpm, for conservatism, the calculations are based on 40,000 gpm.

10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from the release tanks are comprised of contributions from all three units. Under l

normal operating conditions, it is difficult to apportion the t

radioactivity between the units.

Consequently, allocation is l

normally made evenly between units 2 and 3.

10.2.5 Projected Doses for Releases Doses due to liquid effluents are calculated in accordance with the RETS.

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i DRESDEN REVISION 0.K JANUARY 1993 l

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.

F.gure 10-4 is a simplified diagram of solid radwaste processing.

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10-13

DRESDEN REVISION 0.K JANUARY 1993 OG TABLE 10-1 Data for Determination of Dilution Flow Rates Closed Cycle Dilution Flow Determination

'date 4451 out of water, Gate 4452 full closed) 6" 50,000 15" 100,000 21" 150,000 30" 200,000 36" 250,000 40" 300,000 0.0.W 350,000 Open Cycle Dilution Flow Determination (Gate 4450 full open, Gates 4451 and 4452 full closed) 6" 168,000 12" 335,000 O~

19" 404,000*

26" 580,000*

35" 740,000*

0.0.W 900,000*

These dilution flows have 100,000 gpm subtracted from them for conservatism.

Lake Bypassed Dilution Flow (Gates 4450 and 4452 full open, Gate 4451 Full Closed)

De-Icing Valves De-Icing Valves Circ. Water Closed Open Pump Running Flow in gpm Flow in gpm 2

380,000 300,000 3

480,000 380,000 4

760,000 600,000 5

860,000 780,000 6

960,000 890,000 10-14

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DRESDEN REVISION O.K JANUARY 1993 DRESDEN ANNEK INDEK j

PAGE REVISION APPENDIX F F-i O.K F-ii O.A F-iii O.A F-iv O.A F-1 O.A F-2 O.K F-3 O.K F-4 0.A F-5 O.K i

F-6 O.K F-7 O.K F-8 O.K F-9 O.K I

F-10 O.K F-ll O.K F-12 O.K F-13 O.K l

F-14 O.K F-15 O.K l

/~ '

F-16 O.x F-17 O.K F-18 O.K F-19 O.K F-20 O.K F-21 O.K F-22 O.K F-23 O.K F-24 O.K F-25 O.K F-26 O.K F-27 O.K F-28 O.K F-29 O.K F-30 0.K F-31 0.K F-32 0.K F-33 0.K F-34 0.K F-35 O.K F-36 O.K F-37 O.K F-38 0.K F-39 0.K F-40 0.A F-41 O

F-i

i DRESDEN REVISION 0.A l

APRIL 1991 j

APPEEDIX F STATION-SPECIFIC DATA FOR DRESDEN UKITS 1, 2, AND 3

{

TABLE OF CONTENTS PAGE i

F.1 INTRODUCTION F-1' I

F.2 REFERENCES F-1 l

l I

i F

h

s 4

i P

i i

i r

i l

i t

6 F-ii

DRESDEN REVISION O.A APRIL 1991 APPENDIX F f~

(y)

LIST OF TABLES NUMBER TITLE PAGE F-1 Aquatic Environmental Dose Parameters F-2 1

F-2 Station Characteristics F-3 F-3 Critical Ranges F-4 F-4 Average Wind Speeds F-5 F-5 X/Q and D/Q Maxima at or Beyond the f

Unrestricted Area Boundary F-6 F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 i

F-7 Site Boundary Finite Plume Grama Dose Factors for Selected Nuclides F-lO t

F-8 Parameters for Calculation of N-16 Skyshine Radiation from Dresden 2/3 F-40 F-iii

f DRESDN REVISICM 0.A t

APRIL 1991~

APPEEDIX F

. LIST OF FIGURES t

i 1.

i I

NUMBER ME E

d F-1 Unrestricted Area Boundary F-41

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s

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ll 6

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DRESDEN REVISION 0.A APRIL 1991 APPENDIX F

]

V STATION-SPECIFIC DATA FOR DRESDEN UNITS 1, 2, AND 3 F.1 INTRODUCTION This appendir contains data relevant to the Dresden site.

Included are a diagram of the unrestricted area boundary and tables of values of parameters used in offsite dose assessment.

F.2 REFERENCES 1.

Sargent & Lundy, Nuclear Safeguards and Licensing Division Calculation, " Appendix I Technical Specification Tables,"

Revision 2, July 10, 1979.

2.

Sargent & Lundy, Nuclear Safeguards and Licensing Division, Dresden Calculation No. DR-01-86, Rev. O.

1 s-)

i F-1

l DRESDEN REVISION O.K JANUARY 1993 j

^

Table F-1 Aquatic Environment Dose Parameters Parametera Value W

1/M l

f 1/M 1

W F, cfs 1.37E4 f

F, cfs 1 08E4 f

b t, hr 24 t", hrc 106 Limits on Radioactivity in Unprotected Outdoor Tanks Refer to Section 3.8.D of the Technical Specifications of Units 1, 2,

and 3 for specific limits.

,-)

w i

a The parameters are defined. in Section_A.2.1 of Appendix A.

b f

t (br) = 24 hr (all stations) for the fish ingestion pathway ctW (hr) = 106 (distance to Peoria is 106 miles; flow rate of 1 mph assumed) l e

t

(

,e F-2 t

}

-DRESDEN REVISION O.K JANUARY 1993 f

Table F-2 Station Characteristics STATION:

Dresden Nuclear Power Station I

LOCATION:

Morris, Illinois CHARACTERISTICS OF ELEVATED RELEASE POINT a

U1

91. 44m U1 1.4 m

a

1) Release Height = U2/3 94.49m

2) Diameter = U2/3 3.35m U1 17.9 ms-1

3) Exit Speed

= U2/3 16.6 cms-1

4) Heat Content e J E'. C a l s - 1 "

CHARACTERISTICS OF VENT STACK RELEASE POINT a

1) Release Height = 48.77 m

2) Effective Diameter = 2.74 m

12.0

-1

3) Exit Speed

=_

ms CHARACTERISTICG OF GROUND LEVEL RELEASE

1) Release Height = 0 m

a

(

2) Building Factor (D)

= __ 42 8_m j

i METEOROLOGICAL DATA A

400 ft Tower is Located' 800m HHH of elevated release point Tower Data Used in Calculations Wind Speed and Differential Release Point Direction Temperature Elevated 300 ft 300-35 ft Vent 150 ft 150-35 ft Ground 35 ft 150-35 ft t

aUsed in calculating the meteorological and dose factors in

[

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

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

i t

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F-3 k

DRUDH REVISION'O.A' APRIL.1091 Table F-3 Critical Ranges j

i Practical Site Nearest Nearest Dairy Farm Boundarya Residenth Within 5 Milesc Direction (m)

(m)

(m) l N

768 1600-

-None NNE 1207 1300 None NE 1100 1100-

.None l

ENE 1244 966 None i

E-1000 3400 None ESE 988

-2100 None' SE 1000 1400 13ne i

SSE

-792 1300 None S

841 1100

~ kone SSW 853 5000 None.

SW 1024 6100 None WSW 1170 3200 None

-W 1756 4800 None WNW 1215 5500 None NW 756 1600 None i

NNW 671 1600 None

.i O

a aNearest land in. unrestricted area.

bl990 annual survey, Teledyne Isotopes Midwest Laboratories.

Used in establishing the characteristics of the individual saximally exposed to N-16 skyshine (see Section A.3.2 of i

Appendix A and Table F-8).

l-c1988 annual survey, Teledyne Isotopes Midwest Laboratories..

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

i i

i 1

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F-4 I

i

DRESDEN REVISION 0.K JANUARY 1993 Table F-4

/"

Average Wind Speeds k.

Downwind Averace Wind Speed (m/secia Directiqn Elevated Mixed Mode Ground Level i

N 7.3 5.5 4.3 NNE 7.4 5.3 4.1 NE 6.9 5.0 3.7 ENE 6.4 4.9 4.0 E

7.1 5.3 4.1 ESE 7.2 5.3 4.1 SE 6.4 5.1 3.7 t

SSE 6.4 4.8 3.4 S

5.9 4.4 3.1 SSW 5.9 4.5 3.0 SW 5.7 4.4 3.0 WSW 5.1 4.0 2.8 i

W 5.5 4.4 3.2 WNW 5.9 4.4 3.0

[

NW 5.7 4.4 3.4 NNW 6.3 4.9 3.8 b

l abased on Dresden 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.

bThe elevated and ground level values are provided for reference purposes only.

Routine dose calculations are performed using the mixed mode values.

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Table F-7 (Cont'd) l Sito Boundary Finito Plume Gansna Dose Factors for Kr-85m 1

Dresden 2 & 3 l'

Ocwnwind Unrestrteted Elevated (Stack) Retesse Mixed Mode (vent) Release Otrection Area Oound Radius 5

SBAR Radtus V

VBAR (meters) (meters) (mrad /yrl/(uct/sec) (meters) (mrad /yr)/(uCt/sec)

N 768.

768.

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1207.

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3.303E-04 2.76BE+04 NE 1100.

1100.

9.06tE-05 7.704E-05 1100.

3.296E-04 2.763E'04 ENE 1244 1244 7.359E-05 6.254E-05 1244 2.088E-04 1.753E-04 E

1000.

l.064E-04 9.049E-05 1000.

4.299E-04 3.601E-04 ESE 988.

988.

9.782E-05 8.314E-05 988.

3.568E 04 2.989E-04 SE 1000.

1000.

9.428E-05 8.01tE-05 1000.

3.260E-04 2.733E-04 SSE 792.

792.

1.046E*04 8.892E-05 792.

3.889E-04 3.259E-04 5

841.

8.695E-OS 7.391E-05 841.

3.045E-04 2.558E-04 55W 853.

853.

8.163E-05 6.939E-05

853, 2 929E-04 2.459E-04 SW 1024 1024 7.425E-05 6.313E-05 1024 2.735E-04 2.3OOE 04 WSW 1170.

1970.

7.278E-05 8.188E-05 1970.

2.394E-04 2.016E-04 W

1756.

4.764E-05 4.046E-05 1756.

1.134E-04 1.456E-04 WNW 1219.

1219, 5.561E-05 4.727E-05 1219.

2.513E-04 2.107E-04 NW 756.

756.

9.757E-05 8.30tE-05

756, 3.808E-04 3.196E-04 NNW 671 671.

1.240E-04 f.055E-04 671.

5.578E-04 4.67tE-04 Dresden Site Meteorological Oata t/78 - 12/87 F-26

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DRESDEN REVISION O.A APRIL 1991 Table F-8 l

,- 3

(_)

Parameters for Calculation of N-16 Skyshine Radiation From Dresden 2/3 Location Occupancy Shielding Distance Number Hours Factor Rk 8

k Activity OHk SFk (m) 1 Living 8344 0.7 966b at home (nearest resident) 2 Fishing 416 1.0 610C Note:

These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of the public using Equation A-35 in Appendix A.

If desired, more realistic parameters could be used in place of

(

these to refine the estimate.

For example, one could determine whether the nearest resident really fishes the specified number of hours at the specified location.

aThe amount of time in a year that a maximally exposed fisher-man would spend fishing near the site is estimated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per week for 8 months per year.

This yields an estimate of l

[12 hours / week) [(8 months /yr)/(12 months /yr)]

x [52 weeks /yr] = 416 hours0.00481 days 0.116 hours 6.878307e-4 weeks 1.58288e-4 months /yr The remaining time is assumed to be spent at the nearest residence.

bDistance to nearest residence (see Table F-3).

cEstimated from a drawing of the site.

i O

F-40

DRESDEN REVISION O

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MARCH 1989

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DRESDEN STATION LNETS 1,2, & 3

- i PRIURE F-1 L5GESTMICTED AREA SOLNDARY 4

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ML20035A665

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