ML20035A161

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Rev 0.K to ODCM, Chapter 10 & App F
ML20035A161
Person / Time
Site: LaSalle  
Issue date: 01/31/1993
From:
COMMONWEALTH EDISON CO.
To:
References
PROC-930131-02, NUDOCS 9303240200
Download: ML20035A161 (54)
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X244 NBC C/O DOC CTEL D5K, C. PATEL DIREC10R Of huC. ht.ACIOR REGULAT10!i i

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MAIL $1AII0h P1-137 WASHIF61Oh dC 20555

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

Please complete the following manual update.

REl1OYE IRSIBI i

LaSalle Station Annex LaSalle Station Annex Entire Chapter 10.

Entire Chapter 10

p. 10-1 to 10-111, Revision 0.K Jan. 1993 10-1 to 10-20
p. 10-1 to 10-v, 10-1 to 10-20 LaSalle Station Annex LaSalle Station Annex Entire Appendix F Entire Appendix F
p. F-1 to F-iv, Includes Rev. 0.K F-1 to F-24
p. F-1 to F-iv, F-1 to F-24 Please sign and date this control sheet and return to:

COMMONHEALTH EDISON COMPANY c/o Document Control - Emergency Preparedness 1400 Opus Pl.- 5th Floor i

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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LASALLE REVISION 0.K JANUARY 1993 LASALLE ANNEX INDEX PEE REVISION CHAPTER 10 10-1 0.K 10-11 0.K 10-111 0.K 10-1v 0.K l

10-v 0.K 10-1 0.K 10-2 0.K l

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 O.K O

10-11 0.K 10-12 0.K 10-13 0.K 10-14 0.K i

10-15 0.K 10-16 0.K 10-17 0.K 10-18 0.K 10-19 0.K 10-20 0.K l

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i 10-1 i

LASAllE REVISION 0 K JANUARY 1993 Os CHAPTER 10 RADIDACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS NUMBER PAGE 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 Station Vent Stack Effluent Monitor.............

2 10.1.2.2 Standby Gas Treatment System Effluent Monitor........

2 10.1.2.3 Reactor Building Ventilation Monitors............

3 10.1.2.4 Condenser Air Ejector Monitors 3

10.1.3 Alarm and Trip Setpoints 4

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

4 10.1.3.1.1 Reactor Building Vent Effluent Monitor 4

10.1.3.1.2 Condenser Air Ejector Monitors 4

10.1.3.1.3 Station Vent Stack Effluent Monitor.............

6 i

10.1.3.1.4 Standby Gas Treatment Stack Monitor..............

6 10.1.3.2 Release Limits 6

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

7 10.1.3.4 Conversion factors 7

10.1.3.5 HVAC Flow Rates........................ 8 10.1.4 Allocation of Effluents from Common Release Points 8

10.1.5 Dose Projections 8

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

8 10.2.1

System Description

8 10.2.1.1 Radwaste Discharge Tanks 9

10.2.2 Radiation Monitors 9

10.2.2.1 Liquid Radwaste Effluent Monitor 9

10.2.2.2 Service Water Effluent Monitors................

9 i

10.2.2.3 RHR Heat Exchanger Cooling Water Efflueni Monitors 9

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i 10-11 i

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LASALLE REVISION 0.K JANUARY 1993 CHAPTER 10 RADI0 ACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd)

NUMBER PAGE 10.2.3 Alarm and Trip Setpoints 9

10.2.3.1 Setpoint Calcul ations.....................

9 10.2.3.1.1 Liquid Radwaste Effluent Monitor 10 10.2.3.1.2 Service Water Effluent Monitors...............

10 i

10.2.3.1.3 RHR Heat Exchanger Cooling Water Monitors..........

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

12 10.2.3.5 Conversion Factors 12 10.2.3.6 Liquid Dilution Flow Rates 12 10.2.4 Allocation of Effluents from Common Release Points 13 10.2.5 Projected Concentrations for Releases............

13 i-10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM.......

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10-111

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LASALLE REVISION 0.K JANUARY 1993 CHAPTER 10 LIST OF TABLES l

ML@B 11GE 10-1 Assumed Composition of the LaSalle Station 10-15 Noble Gas Effluent i

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LASALLE REVISION 0.K JANUARY 1993

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CHAPTER 10 LIST OF FIGURES bMMJEB PAGE 10-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram 10-16 10-2 Simplified Liquid Radwaste Processing Diagram 10-18 4

10-3 Simplified Liquid Effluent Flow Diagram 10-19 10-4 Simplified Solid Radwaste Processing Diagram 10-20 l

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LASALLE REVISION 0.K JANUARY 1993 b

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

System Description

A simplified gaseous radwaste and gaseous effluent flow diagram are provided in Figure 10-1.

The airborne release point for radioactive effluents is the ventilation stack which is classified as a stack in accordance with the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A.

In addition, the standby gas treatment system effluent is released through a separate stack inside the ventilation stack.

This release point has the same location and classification as the ventilation stack.

10.1.1.1 Condenser Offgas Treatment System

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The condenser offgas treatment system is designed and installed to reduce radioactive gaseous effluents by collecting non-s 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 11.3.2.1 of the LaSalle UFSAR.

10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in selected effluent streams by-. passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters prior to release to the environment.

Such a system is not considered to have any effect on noble gas ef fluents. The ventilation exhaust treatment systems are shown in Figure 10-1.

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

10-1

LASALLE REVISION 0.K JANUARY 1993 10.1.2 Radiation Monitors l

10.1.2.1 Station Vent Stack Effluent Monitor Monitor OPLD5J (Wide Range Noble Gas Monitor) continuously monitors the final effluent from the station vent stack.

l The monitor system has isokinetic sampling, gaseous grab sampling, iodine and particulate sampling, tritium sampling, and postaccident sampling capability.

In normal operation the low-range noble gas channel is on line and active. The mid-range channel replaces the low-range channel at a concentration of 0.1 pCi/cc and the high-range channel replaces the mid-range channel at a concentration of 100 pCi/cc.

The low-range and mid/high-range iodine and particulate samplers operate in a similar manner.

In normal operation the low-range samplers are on line. At a concentration of 0.05 pCi/cc the mid/high-range samplers are brought on line, and at a concentration of 10 pCi/cc the low-range sample pump is turned off.

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

Pertinent information on this monitor is provided in the LaSalle UFSAR Section 11.5.2.2.1.

10.1.2.2 Standby Gas Treatment System Effluent Monitor l

Monitor OPLD2J (Wide Range Noble Gas Monitor) continuously monitors the final effluent from the_ standby gas treatment system (SGTS) stack.

The SGTS stack monitor has isokinetic sampling, gaseous grab sampling, particulate and iodine sampling, and post accident sampling capability.

In normal operation the low range noble gas channel is on line and active. The mid-range channel replaces the' low-range channel at a concentration of 0.1 uCi/cc and the high-range channel replaces the mid-range chunel at a concentration of 100 pCi/cc.

10-2

LASALLE REVISION 0.K JANUARY 1993 n

V The low-range and mid/high-range iodine and particulate samples operate in a similar manner.

In normal operation, the low-range samples are on-line. At a concentration of 0.05 pCi/cc the mid/high-range samplers are brought on-line, and at a concentration of 10 pCi/cc the low-range sample pump is turned off.

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

Pertinent information on this monitor is provided in the LaSalle UFSAR Section 11.5.2.2.2.

10.1.2.3 Reactor Building Ventilation Monitors Monitors 1(2)D18-N009 continuously monitor the effluent from the Unit 1(2) reactor building. On high alarm, the monitors automatically initiate the following actions:

A.

Shutdown and isolation of the reactor building vent system B.

Startup of the standby gas treatment system C.

Isolation of primary containment purge and vent lines Pertinent information on these monitors is provided in LaSalle UFSAR Section 11.5.2.1.1.

10.1.2.4 Condenser Air Ejector Monitors Monitors 1(2)D18-N002/N012 (pre-treatment) and 1(2)D18-N903A/B (post-treatment) continuously monitor gross gamma activity downstream of the steam jet air ejector and prior to release to the main stack.

On "high-high-high" alarm monitor 1(2)D18-N903A/B automatically initiates closure of valve 1(2)N62-F057 thus terminating the release.

Pertinent information on these monitors is found in LaSalle UFSAR Sections 11.5.2.1.2 and 11.5.2.1.3.

10-3 il

LASALLE REVISION 0.K JANUARY 1993 V

10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Reactor Building Vent Effluent Monitor The setpoint for the reactor building vent effluent monitor is established at 10 mR/hr.

10.1.3.1.2 Condenser Air Ejector Monitors Pre-Treatment Monitor The high-high trip setpoint is conservatively set at or below one-half the release limit obtained from the post-treatment monitor "high-high-high" trip setpoint.

P s; K x 0.5 x Q,, x E f, x e" (10-1)

P Off-gas Pretreatment high-high alarm setpoint K

Conversion constant

[(mr/hr) per (pci/sec)]

The value is determined using noble gas radionuclides identified in a representative sample, and the off-gas release rate and monitor response at the time the sample is taken.

0.5 Factor for conservatism i

Q, Release Rate

[pti/sec]

The release rate of all noble gas radionuclides released as stack releases based on post treatment monitor "high-high-high" trip setpoint. This is less than the solutions obtained from Equations 10-3 and 10-4.

f.

Predetermined fraction of total release attributed to nuclide i.

The fractions, f, are obtained from the mixture of i

radionuclides calculated to be present in the steam as it exits the vessel 10-4

LASALLE REVISION 0.K JANUARY 1993 e

Term to correct for 30 minute transit time.

The high trip setpoint is established at s 100 pCi/sec per MW-th (e 3.4E5 pCi/sec) per Technical Specification 3.11.2.2.

Post-Treatment Monitor The off gas isolation setpoint is conservatively set at or below one-half the release limit calculated using equations 10-3 and 10-4 below.

The off-gas isolation setpoint is converted into the I

monitor units of counts per second (cps) as follows:

P s 0.5 x Q,, x E/(472 x F)

(10-2)

P Off-gas Posttreatment

[ cps)

Monitor Isolation Setpoint The off-gas posttreatment monitor setpoint which initiates isolation of flow of off-gas to the station vent stack.

Q,,

Total Allowed Release Rate,

[pti/sec]

Stack Release The total allowed release rate of all noble gas radionuclides released as stack releases. This is the smaller of the solutions obtained from Equations 10-3 and 10-4.

I E

Efficiency of the Off-Gas

[ cps per j

Posttreatment Monitor (pci/cc)]

The response of the off-gas post-treatment monitor to a reference source.

472 Conversion Constant

[(cc/sec)/cfm]

Converts cubic feet per minute to cubic centimeters per second.

F Maximum Off-Gas Flow Rate

[cfm]

l 10-5

i LASALLE REVISION 0.K JANUARY 1993 O

10.1.3.1.3 Station Vent Stack Effluent Monitor The setpoint for the station vent stack effluent monitor is conservatively set at or below one-half the calculated release limit calculated using equations 10-3 and 10-4 below.

10.1.3.1.4 Standby Gas Treatment Stack Monitor The setpoint for the standby gas treatment system effluent monitor is conservatively set at or below one-half the release limit calculated using equations 10-3 and 10-4 below.

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 limit Q,,is found by solving Equations 10-3 and 10-4.

(1.11) Q,, { (f,S, ) < 500 mrem /yr (10-3)

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

  • s (10-4)

+ (1.ll)(f ) S;)

j

< 3000 mrem /yr The summations are over noble gas radionuclides i.

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

Q,,

Total Allowed Release Rate, Stack

[pci/sec]

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

exp (-A,R/3600 U,) is conservatively set equal to 1.0 for purposes of determining setpoints.

10-6

LASALLE REVISION 0.K JANUARY 1993 i

1 The remaining parameters in Equation 10-3 have the same definitions as in Equation A-8 of Appendix A.

The remaining parameters in Equation 10-4 have the same definition as in Equation A-9 of Appendix A.

Equation 10-3 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 10-4 is based on Equation A-9 of Appendix A and the 10 CFR 20 restriction on skin dose rate (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.I.3.2 of Appendix A).

Since the solution to Equation 10-3 is more conservative than the solution to Equation 10-4, the value of Equation 10-3, 1.22 x 10' pCi/sec, is used as the limiting noble gas release rate.

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 set points, the radioactivity mixture in the exhaust air is assumed to have the radionuclide composition in Table 10-1.

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

Station vent stack effluent monitor.

Calibrations compare the response of station detectors to that of a reference detector using NIST traceable sources (Cs-137 and Co-60).

Condenser air ejector monitor.

Pretreatment Monitor The value is determined using noble gas radionuclides identified in a representative sample, and the offgas release rate and monitor response at the time the sample is taken.

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LASALLE REVISION 0.K JANUARY 1993 Posttreatment Monitor The value is determined using noble gas radionuclides identified in a representative sample, and the offgas concentration and monitor response at the time the sample is taken.

Standby gas treatment system monitor.

Calibrations compare the response of station detectors to that of a reference detector using NIST traceable sources (Cs-137 and Co-60).

10.1.3.5 HVAC Flow Rates The main stack flow rate is obtained from either the process computer or Monitor RM-23.

The SGTS flow rate is obtained from either the process computer or chart recorders in the main control room.

10.1.4 Allocation of Effluents from Common Release Points

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Radioactive gaseous effluents released from the main chimney

(

are comprised of contributions from both units. Under normal operating conditions, it is difficult to allocate the radioactivity between units due to fuel performance, in-plant leakage, power history, and other variables.

Consequently, no allocation is normally made between the units.

Instead, the entire release is treated as a single source.

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 are provided in Figures 10-2 and 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 filter, demineralizer, or evaporator for the purpose of reducing the total radioactivity prior to release to 10-8

LASALLE REVISION 0.K JANUARY 1993 i

i V

the environment. The system is described in Section 11.2.2 of the LaSalle UFSAR.

10.2.1.1 Radwaste Discharge Tanks l

There are two discharge tanks (l(2)WF05T, 25,000 gallons each) l which receive water for discharge to the Illinois River via l

the cooling lake blowdown.

10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitor i

Monitor OD018-N907 monitors all releases from the release l

tanks. On high alarm the monitor automatically initiates l

closure of valves OWLO67 and trips the radwaste discharge pump to terminate the release.

l Pertinent information on the monitor and associated control l

devices is provided in LaSalle UFSAR Section 11.5.2.3.3.

l 10.2.2.2 Service Water Effluent Monitors l

Monitors 1/(2)D18-N912 continuously monitor the service water I

effluent. On high alarm service water discharge may be

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terminated manually.

No control device is initiated by these monitors.

Pertinent information on these monitors is provided in LaSalle UFSAR 11.5.2.3.2.

10.2.2.3 RHR Heat Exchanger Cooling Water Effluent Monitors Instrument channels 1/(2)D18-N906/8 continuously monitor the RHR heat exchanger cooling water effluent. On high alarm the i

operating loop may be terminated manually and the redundant l

loop brought on line.

No control device is initiated by these I

monitors.

Pertinent information on these monitors is provided in LaSalle UFSAR Section 11.5.2.3.4.

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 i

limits of 10 CFR 20 are not exceeded in the unrestricted area.

10-9 1

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LASALLE REVISION 0.K JANUARY 1993 k

10.2.3.1.1 Liquid Radwaste Effluent Monitor The monitor setpoint is found by solving equation 10-5 for the total isotopic activity.

P :s; K x ({ C[/{ (C[/MPC,)) x ((F#+ F',)/Fd (10-5)

P Release Setpoint

[ cpm]

({ (K, x C, x W,)/{ C,#)

[ cpm / Ci/mt)

K K,

Counting efficiency for

[ cpm /pCi/mt) radionuclide i W,

Weighting Factor C[

Concentration of radionuclide i in

[pCi/ml]

the release tank.

i F',

Maximum Release Tank Discharge Flow Rate

[gpm]

The maximum flow rate is 45 gpm.

MPC, Maximum Permissible Concentration

[pci/ml]

F Dilution Flow

[gpm]

10.2.3.1.2 Service Water Effluent Monitors

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The monitor setpoint is established at two times the background count rate (not to exceed 10000 cpm).

10.2.3.1.3 RHR Heat Exchanger Cooling Water Monitors The monitor setpoint is established at two times the background count rate (not to exceed 10000 cpm).

1 10-10 l

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LASALLE REVISION 0.K JANUARY 1993 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:

F', - 0.1 x (F /E (C, /MPC;)) x MF (10-6)

The summation is over radionuclides i.

0.1 Reduction factor for conservatism.

F' Maximum Permitted Discharge Flow Rate

[gpm)

The maximum permitted flow rate from the radwaste discharge tank.

d F

Oilution Flow

[gpm]

C, Concentration of Radior":lh'a i in

[pCi/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 Concentration

[pCi/mt]

of Radionuclide i MF Multiplication Factor F;,,,<0.5;MF-3 0.5 < F' S 5; MF 5

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5 < F;,,,; MF - 7.5 10.2.3.3 Release Limits Release limits are determined from 10 CFR 20.

Calculated maximum permissible discharge rates are divided by 10 for

)

10-11 j

LASALLE REVISION 0.K JANilARY 1993 l

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conservatism and to ensure that release concentrations are well below applicable maximum permissible concentrations (MPC).

10.2.3.4 Release Mixture for the liquid radwaste effluent monitor the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis plus four additional radionuclides. The additional radionuclides are H-3, Fe-59, Sr-89, and Sr-90. The quantities to be added are obtained from the most current analysis for these four radionuclides.

For all other liquid effluent monitors 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 Cs-137/Ba-137.

10.2.3.6 Liquid Dilution Flow Rates A conservative maximum blowdown flowrate of 20,000 gpm is used for all radwaste discharge calculations unless actual blowdown flow is determined to be less.

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10-12 1

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LASALLE REVISION 0.K JANUARY 1993 10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from the Unit I release tank are allocated to Unit 1, and effluents released from the i

Unit 2 tank are allocated to Unit 2.

Other potential pathways (i.e., RHR) are allocated to their respective unit.

t 10.2.5 Projected Doses for Releases Doses are not calculated prior to release. Dose contributions i

from liquid effluents are determined in accordance with the RETS and station procedures.

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10-13 i

4

l LASALLE REVISION 0.K JANUARY 1993 J

O 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.

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1 LASALLE REVISION 0.K JANUARY 1993 1

TABLE 10-1 Assumed Composition of the LaSalle Station Noble Gas Effluent l

Percent of Isotope Total Annual Release Kr-83m 4.5E-3 Kr-85m 8.0E-3 Kr-85 2.6E-5 Kr-87 2.6E-2 i

Kr-88 2.6E-2 Kr-89 1.7E-1 Kr-90 3.7E-1 Xe-131m 2.0E-5 s

Xe-133m 3.8E-4 Xe-133 1.lE-2 O

Xe-135m 3.4E-2 Xe-135 2.9E-2 Xe-137 2.0E-1 Xe-138 1.2E-1 i

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F-ii O.A F-iii O.A F-iv O.A g

F1 O

F-2 O.K F-3 O.K F-4 O

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

/" '

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t

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9 LA SALLE

' REVISION.O.A j

APRIL 1991

.?

APPENDIX F j

i STATION-SPECIFIC DATA POR LA SALLE UNITS 1 AND 2 i

i TABLE OF CONTENTS

}.

PAGE t

F.1 INTRODUCTION F-1 i

.t F.2 REFERENCES F-1 i

1 I

f t

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4 1

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F-11 h

LA SALLE REVISION 0.A i

APRIL 1991 4

(g)

APPENDIX F LIST OF TABLES i

NUMBER TITLE PAGE F-1 Aquatic Environment Dose Parameters F-2

[

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 Unrestricted Area Boundary

'F-6 F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-7 F-7 Site Boundary Finite Plume Gamma Dose Factors for Selected Nuclides F-8 F-8 Parameters for Calculation of N-16 Sky-shine Radiation from La Salle F-23 i

i F-111 1

LA SALLE REVISION 0.A-APRIL 1991 l

.I' APPElenIX F LIST OF FIGURES NUMBER TITLE PAGE

-1 F-1 Unrestricted Area Boundary F-24 l

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MARCH 1989

{#'}

APPENDIX F STATION-SPECIFIC DATA FOR LA SALLE UNITS 1 AND 2 F.1 INTRODUCTION This appendix contains data relevant to the La Salle site.

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

F.2 REFERENCES 1.

Sargent & Lundy, Nuclear Safeguards and Licensing Division-,

La Salle Calculation No. 3-PR-02, Rev.

O.

2.

Sargent & Lundy, Nuclear Safeguards and Licensing Division, La Salle Calculation No. 0-SN-22, Rev.

O.

F-1

LASALLE REVISION O.K JANUARY 1993 c.

-[]

Table F-1 V

Aquatic Environment Dose Parameters a

Parameter Value W

1/M l

f 1/M 1

F",

cfs 1.37E4 Ff, cfs 1.37E4 f

b t, hr 24 t", hrc 97 d

Limits on Radioactivity in Unprotected Outdoor Tanks i

Outside Temporary Tank i

10 Cid l

C i

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

b tf (hr) = 24 hr (all stations) for the fish ingestion pathway c t" (hr) = 97 hr (distance to Peoria is'97 miles; flow rate of 1 mph assumed) d See Section A.2.4 of Appendix A.

e Tritium and dissolved or entrained noble gases a're excluded from this limit.

]\\

F-2

LASALLE REVISION O.K JANUARY 1993 i

Table F-2

_,k/

Station Characteristics STATION:

LaSalle LOCATION:

6 miles south of Marseilles, Illinois - LaSalle County CHARACTERISTICS OF ELEVATED RELEASE POINT a

1) Release Height = 112.8 m
2) Diameter =

5.64 m

3) Exit Speed

= 14.7 ms-1

4) Heat Content =

0 KCal s-1 CHARACTERISTICS OF VENT STACK RELEASE POINT: Not Applicable (NA)

1) Release Height =

m

2) Diameter =

m

-1

3) Exit Speed

=

ms CHARACTERISTICS OF GROUND LEVEL RELEASE

1) Release Height = 0 m

r a

(

2) Building Factor (D)

= 56.4 m

METEOROLOGICAL DATA A

400 ft Tower is Located 300m SEE of elevated release point Tower Data Used in Calculations Wind Speed and Differential Eelease Point Direction Temperature Elevated 375 ft 375-33 ft Vent (NA)

(NA)

Ground 33 ft 200-33 ft 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.

j

-I F-3

LA SALLE REVISION O MARCH 1989 Table F-3

^

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

(m)

(m)

N 1022 3500 None NNE 1330 2300 None NE 2408 2900 None ENE 4450 5500 None E

1996 5000 None ESE 838 2600 None SE 884 2400 None SSE 838 1800 None S

829 3500 None SSW 829 3200 None SW 610 1100 None WSW 509 2100 None W

509 1400 None WNW 625 1600 None

~'

('v)

NW 732 4200 None NNW 848 1900 None aUsed in calculating the meteorological and dose factors in Tables F-5 and F-7.

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

bl988 annual survey, Teledyne Isotopes Midwest Laboratories.

Used in establishing the characteristics of the individual maximally exposed to N-16 skyshine (see Section A.3.2 of Appendix A and Table F-8).

c1988 annual survey, Teledyne Isotopes Midwest Laboratories.

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

F-4 l

w a.

LASALLE REVISION 0.K JANUARY 1993 Table F-4

~

Average Wind Speeds Downwind Wind Speed (m/secia Direction Elevated Release N

9.7 NNE 10.1 NE 9.2 ENE 9.0 E

9.5 ESE 9.7 SE 8.1 SSE 7.4 S

6.7 r

SSW 5.6 SW 5.5 WSW 6.9 s

W 7.6 (r~s)

WNW 7.5 NW 7.5 NNW 8.3 t

abased on LaSalle site meteorological data, 1978 - 1987.

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

[

'A F-5

REVISIO: p.K

)

LAST;O '

JANUARY \\ E3' Table F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary Downwind Elevated (Steck) Retesse Direction Radius X/O Radius D/0 (meters) (sec/m. 3) (meters)

(1/m++2)

N 5633.

6.123E-09 1022.

7.233E-tO NNE 1330.

7.059E-09 1330.

1.OO1E-09 NE 4400.

5.535E-09 2408.

4.245E-to ENE 5200.

5.086E-09

4450, 2.02tE-10 E

5200.

5.865E-09 1996.

5.41SE-10 ESE 5200.

8.OOOE-09 1500.

8.896E-to SE 5633.

7.I16E-09 1500.

7.505E-10 SSE 5200.

6.717E-09 1500.

7.176E-tO 5

5633.

5.910E-09 1500.

6.13GE-10 55W 6000.

5.269E-09 829.

5.804E-10 SW 6000.

6.767E-09

610, 8.619E-10 WSW 6000.

6.065E-09 509.

6.576E-lO W

6437.

5.354E-09 1500.

4.8ttE-to WNW 7242.

3.916E-09 1500.

3.175E-10 NW 7242.

3.766E-09 1500.

3.118E-10 NNW 6437.

4.240E-09 1500.

3.806E-to LaSalle site Meteoret steat Date 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.

aUsed for bet.a air, beta skin, and inhalation dose pathways.

See Sections A.1.2, A.l.3, and A.1.4.2 of Appendix A.

bUsed for produce and leafy vegetable pathways.- See Section A.l.4 of Appendix A.

F-6

(mV)

LAST REVISI

.K n'

V JANUARY 93 Table F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles Downwind Nearest Milk CCw D/Q(1/m**2) Nearest West Animet D/Q(1/m**2)

Otraction Redivs Elevated ondtus Etevnted (meters) Retense (meters) Retesse N

5047.

9.617E-11

2253, 4.691E-10 NNE
8047, 1.140E-10 2275.

5.988E-10 NE 8047.

B 754E-11

3219, 3.113E-10 ENE 8047.

B.476E-11 4506.

1.989E-10 E

8047.

1.046E-10 5150.

2.057E-10 ESE 8047.

1.436E-10 4345.

S.499E-10 SE 8047.

1.230E-10 4345.

2.996E-10 SSE 8047.

1.163E-10 5472.

2.105E-10 5

8047.

9.850E-11 2575.

4.054E-10 55w 8047.

8.563E-11 2897 3.202E-10 SW B047.

1.085E-10 1287.

7.208E-to W5W 8047.

1.OO7E-10 1448.

6.164E-10 W

B047.

8.411E-11 1770.

4.400E-10 WN 8047.

5.767E-11 1609.

3.077E-10 W

O.

1.474E-11 1609.

3.OO4E-10 NNW O.

2.OOBE-11 1287 3.650E-10 Lasette Site Meteorologicat Data 1/78 - 12/87 Note: Based on Reference 1 of Section F.2 and the formulas in Section B.4 of Appendix B.

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JANUAR'lx J93 Table F-7 (Cont'd)

Site Boundary Finito Plume Gamma Dose Factors for Kr-89 Downwind Unrestricted Elevated (Stack) Release D i rec t iori Area Bound Redtus 5

58AR (meters) (meters) (mred/yr)/(uCl/sec)

N 1022.

1022.

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1330.

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2408.

8.306E-05 7.20SE-05 ENE 4450.

4450.

1.570E-05 1.36tE-05 E

1996.

1996.

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838.

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884 4.455E-04 3.866E-04 SSE 838.

838.

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829.

829.

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829.

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610.

6.085E-04 5.284E-04 WSW 509.

509.

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$09.

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7.236E-04 6.282E-04 WNW 625.

625.

4.471E-04 3.882E-04 NW 732.

732.

3.715E-04 3.225E-04 NNW 848.

848, 3.548E-04 3. OBOE-04 Lesslie Site Meteorological Data 1/78 - 12/87 t

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JANUAR$_j93 Table F-7 (Cont'd)

Site Boundary Finite Plume Ganuna Dose Factors for Xe-135 Downwind Unrestricted Eleva ted(5teck ) Re tense Ofrection Arem Bound Radius 5

SBAR (meters) (meters) (mred/yr)/(uCt/sec)

N 9022.

1022.

8.262E-05 7.032E'-05 NNE 1330.

1330.

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2408.

3.669E-05 3.12tE-05 ENE 4450.

4450.

1.928E-05 1.639E-05 E

1996.

1996.

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838.

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838.

7.845E-05 6.677E-05 5

829.

829.

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829.

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610.

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509.

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SO9.

509.

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G25, 625.

7.742E-05 6.590E-05 NW 732.

732.

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848, 6.973E-OS 5.935E*05 LnSs11e Site Meteorological Date 1/78 - 12/87 F-19

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Table F-8 Parameters for Calculation of N-16 Skyshine Radiation From La Salle Location Occupancy Shielding Distance Number Hours Factor R t.

k Activity OHk SFk (m7 1

Living at 8360 0.7 1100a home 2

Fishing 400 1.0 2100 3

Living at 2500 0.7 2400 t

the National Guard Facility O

Notes:

1.

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

If desired, more realistic parameters could be used in place of these to refine the estimate.

2.

In determining the maximally exposed individual, the following possibilities were considered:

the nearest resident, fishermen, and persons at the National Guard facility north of the site.

The exposure time and location 1

of a maximally exposed fisherman were estimated on the basis of discussion with a member of the station staff.

The nearest-resident was found to have_the greatest exposure to skyshine.

For details, see Reference 2 of Section F.2.

a Distance to nearest residence (see Table F-3).

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