Text

Offsite Dose Calculation Manual Revisions to Chapters 10-12 & Appendix F for Lasalle Station
	ML20077Q560
Person / Time
Site:	LaSalle
Issue date:	12/30/1994
From:	; COMMONWEALTH EDISON CO.
To:	;
References
	PROC-941230, NUDOCS 9501190292
	Download: ML20077Q560 (154)
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D:camb:r 30,1994 1

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i l Attached ara the recent revisions to the Offsite Dose Calculation Manual's (ODCM)

Chapters 10,11,12 and Appendix F for LaSalle Station. Please complete the V following manual update:

I Remove Insert E LaSalle Statbn LaSalle Station Entire Chapter 10 Contents Entire Chapter 10 Rev.1.1 LaSalle Station LaSalle Station Entire Chapter 11 Contents Entire Chapter 11 Rev.1.1 LaSalle Station LaSalle Station Entire Chapter-12 Contents Entire Chapter 12 Rev.1.1 LaSalle Station LaSalle Station

('3 Entire Appendix F Contents Entire Appendix F V Rev.1.1 Please sign and return this control document to:

COMk'ONWEALTH EDISON c\o Document Control- Emergency Preparedness 1400 Opus Place - 5th floor Downers Grove, IL 60515 Your signature indicates you have verified that your control number is correct, and you ,

have updated your procedure.

4 X244 Nac c/0 00c cT RL osx, c. PATet )

Signature DIRECTOR Of H u C ., RcACTOR REGULATION U. 5. huC. REGULATORY COMMISSION MAIL STATION P1-137 Date gg3gggurou DC 20555 g

EPCEPIPMocctrt2/47

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PAGE REVISION CHAPTER 10 10-1 1.1 10-li 1.1 -

1 0 - 111 1.1 10-iv 1.1 10-v 1.1 10-1 1.1 10-2 1.1 10-3 1.1 10-4 1.1 10-5 1.1 10-6 1.1 10-7 1.1 10-8 1.1 10-9 1.1 10-10 1.1 10-11 1.1 10-12 1.1 10-13 1.1 O

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CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS NUMBER Eardi 10.1 AIRBORNE RELEASES . . ...............,............................... 1

1. System Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

1. Condenser Offgas Treatment System . . . . . . . . . . . . . . - . . . . . . . . . . . . . 1

2. Ventilation Exhaust Treatment System . . . . . . . . . . . . ... ......... 1

2. Radiation Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .......... 2

1. Station Vent Stack Emuent Monitor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

2. Standby Gas Treatment System Emuent Monitor . . . . . . . . . . . . . . . . . . . 2

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

4. Condenser Air Ejector Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3

3. Alarm and Trip setpoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

1. Setpoint Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

1. Reactor Building Vent Emuent Monitor . . . . . . . . . . . . . . . . . . . . . 4

2. Condenser Air Ejector Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . 4

3. Station Vent Stack Effluent Monitor . . . . . . . . . . . . . . . . . . . . . . . . 6

4. Standby Gas Treatment Stack Monitor . . . . . . . . . . . . . . . . . . . . . 6

2. Rele ase Umits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 -

3. Release Mirture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

4. Conversion Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

5. HVAC Flow R ates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

4. Allocation of Emuents from Common Release Points . . . . . . . . . . . . . . . . . . . . . . . 8

5. Dos e Projections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 10.2 U Q UI D RE LEAS E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

1. Syste m Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

1. Radwaste Discharge Tanks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9

2. Radiation Monitors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9

1. Uquid Radwaste Effluent Monitor . . . . . . . . . . . . . . . . . . . . . . . ....... 9

2. Service Water Effluent Monitors . . . . . . . ............. ...... 9

3. RHR Heat Exchanger Cooling Water Ef' V Monitors . . . . . . . . ...... 9 O

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RADIOACTIVE EFFLUENT TREATMENT AND MONITORING TABLE OF CONTENTS (Cont'd)

NUMBER P. AGE :

3. Alarm and Trip Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9

1. Sotpoint Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 ;

1. Liquid Radweste Emuent Monitor . . . . . . . . . . . . . . . . . . . . . . . . 10 ,

2. Service Water Emuent Monitors . . . . . . . . . . . . . . . . . . . . . . . . . 10

3. RHR Heat Exchanger Cooling Water Monitors . . . . . . . . . . . . . . . 11

2. Discharge Flow Rates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11

1. Release Tank Discharge Flow Rate . . . . . . . . . . . . . . . . . . . . . . 11

3. Release Lirnits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

4. Release Mixture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

5. Conversion Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

6. Liquid Dilution Flow Rates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

4. Allocation of Emuents from Comtnon Release Points . . . . . . . . . . . . . . . . . . . . . . 12 -

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5. Projected Concentrations for Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 l 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . . . . . . . . . . . . . . . . . 12 h

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CHAPTER 10 LIST OF TABLES NUMBER P.69.E 10-1 Assumed Composition d the LaSalle Station . . . . . . . . . . . . . . . . . . . . . 10-13 Noble Gas Emuent O

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-( UST OF FIGURES NUMBER P.Afri 10-1 SimpHed Gassous Radweste and Gaseous Effluent Flow Diagram . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10-14 10-2 SimpHed Uquid Radweste Processing Diagram . . . . . . . . . . . . . . . . . . . . . 10-16 10-3 SimpBiled Liquid Emuent Flow Diagram . . . . . . . . . . . . . . . . . . . . . . . . . . . 10-17 10-4 SimpBfied Solid Radweste Processing Diagram . . . . . . . . . . . . . . . . . . . . . . 10-18 l

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CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simpified gaseous radweste and gaseoos emuent flow diagram are provided in Figure 10-5 The airbome 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 stsck inside t'io ventilation stack. This release point has the same location and classification as the ventilation stack.

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 envbninent. 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 Trraatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive materialin 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 effluents. The ventilation exhaust treatment systerms are shown im Figure 10-1.

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

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.10.1.2 Radiation Monitors ;

i 10.1.2.1 Station Vent Stack Efiluent Monitor ,

i Monitor OPLD5J (Wkle Ra: Jo Noble Gas Monitor) continuously monitors the final l effluent from the station vent stack.

The monitor system has isokinetic samping, gaseous grab samping, lodine and j particulate sampung, tritium sampung, and postaccident sampling capabilty. j in normal operation the low-range noble gas channelis on line and active. The f mid-range channel replaces the low-range channel at a concentration of 0.1 pCl/cc l and the high-range channel replaces the mid-range channel at a concentration of 100 pCi/cc. .

1 The low-range and iint4 -range lodine and particulate samplers operate in a similar manner. In normal operation the low-range samplers are on Ine. At a concentration of 0.05 pCi/cc the rnid/high-range samplers are brought on Eno, and i at a concentration of 10 pCi/cc the low-range sample pump is tumed off.

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

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

i 10.1.2.2 Standby Gas Treatment System Effluent Monitor Monitor OPLD2J (Wide Range Noble Gas Monitor) continuously rnonitors the final .

effluent from the standby gas treatment system (SGTS) stack.

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

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

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O 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-Eno, and at a concentration of 10 pCi/cc the low-range sample pump is tumed off.

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

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

10.1.2.3 Reactor Building Ventilation Monitors J

Monitors ig)D18-NOO9 continuously monitor the effluent frem the Unit 1Q) reactor building. On high alarm, the monitors automatically initiate the tollowing 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 n'onitors is provided in LaSalle UFSAR Section 11.5.2.1.1. .

10.1.2.4 Condenser Air Ejector Monitors Monitors 1Q)D18-N002/N012 (pre-treatment) and 19)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 1Q)D18-N903A/B automatically initiates closure of valve ip)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.

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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 Pro-Treatment Monitor !

'~ The high-high trip setpoint is conservativeh set at or below one-half the release Imit obtained from the post-treatment monitor "high-high-high" trip i setpoint.

P s K x 0.5 x Q x E f, x e 4 (10-1) !

l P Off-gas Protreatment high-high alarm setpoint l K Conversion constant [(mr/hr) por (pCi/sec)]

The value is determined using noble gas ,

I radionucildes 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 Q. Release Rate [pCi/sec] j 1

The release rate of all noble gas I l

radionuclides released as stack releases based on post treatment monitor "high-high-high" i trip setpoint. This is less than the solutions I obtained from Equations 10-3 and 10-4. !

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f. Predetermined fraction of total release attributed to nuclide 1.

The fractions, f,, are obtained from the mixture of radionuclides calculated to be present in the steam as it exits the vessel.

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O e Term to correct for 30 minute transit time.

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

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

The off-gas isolation setpoint is converted into the 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 Post-treatment [ cps]

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

Q, Total Allowed Release Rt.te, [pCl/sec]

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

E Efficiency nf the Off-Gas [ cps per Posttreatment Monitor (pCi/cc))

l 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]

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10.1.3.1.3 . Station Vent Stack Effluent Monitor The setpoint for the station vent stack effluent rnonitor is conservatively se' et or below one-half the calculated release Ernit calculated using equations 10-3 and 10-4 below. ,

F 10.1.3.1.4 Standby Gas Treatment Stack Monitor The setpoint for the standby gas treattnent system effluent monitor is conservatively set at !

or below one-half the release Emit 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 Imits of RETS are not exceeded The release imit Q is found by solving !

Equations 10-3 and 10-4. ,

(1.11) 4, E {ff ) < 500erem/yr (10-3) j Qc, [((QCX/Q), exp(-4R/3600u,)*

+ (1.11)(f,) 5,)

< 3000erem/yr j The summations are over noble gas radionuclides 1.

f, Fractional Radionucide Composition The release rate of noble gas radionuclide i divided by the total release rate of ;

aN noble gas radionucEdes. l Q. Total ANowed Release Rate, Stack [pci/sec)

Release The total aHowed release rate of au noble gas radionuclides released as stack releases. ,

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

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

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 A4 of Appendix A and the RETS restriction on whole body dose rate (500 mrerr/yr) due to noble gases released in gaseous effluents (see Section A.1.3.1 of Appandix A). Equadion 10-4 is based on Equation A-9 of App on skin dose rate (3000f~mremfyr) due to noble Oases released in gaseous effluents (see l Section A.1.3.2 of Apperxdix A).

Since the solution to Equation 10-3 is more conservative than the solution to Equation 10 4, tne value of Equation 10-3,1.22 x 10 8pC1/sec, is used as the Emiting noble gas release rate.

Calbration 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 radionucide composition in Table 10-1.

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

Station vont stack effluent monitor.

CaEbrations 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 radionucEdes , identified in a representative sample,

- and the offgas release rate and monitor response at the time the sample is taken.

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Post-treatment Monitor L

The value is determined using noble gas radionuclides identified in a representative sample, and the ollges concentration and monitor response at the time the sample is taken.'

Standtg gas treatment system monitor.

Calbrations compare the response of stabon 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 e%er the process computer or Monitor RM-23.

The SGT3 flow rate is obtained from either the process computer or chart recorders in the main control room.

10.1.4 Anocabon of Effluents from Common Release Points Radioactive gaseous effluents released from the main chimney are comprised of contributions from both units. Under normal operahng conditions, it is difficult to allocate the radioactwity between units due to fuel performance, in-plant leakage, Power history, and other variables.

Consequently, no anocation is normany 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.

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i 10.2 LIQUID RELEASES )

10.2.1 System Description A simpified liquid redweste and liquid effluent flow diagram are provided in Figures 10-2 and 10-3.

The Equid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by coNecting the Equids, providing for retention or holdup, and providing for treatment by filter, dominersizer, or evaporator for the purpose of reducing the total radioactwity pdor to release to the environment. The system is described in Section 11.2.2 of the LaSalle UFSAR.

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10.2.1.1 Radweste Discharge Tanks There are two discharge tanks (1(2)WF05T,25,000 gallons each) which receive water for discharge to the llEnois River via the cooing lake blowdown.

10.2.2 Radiation Monitors 10.2.2.1 Liquid Radweste Emuent Monitor Monitor OD018-N907 monitors all releases from the release tanks. On high alarm the monitor automatically initiates closure of valves OWLO67 and trips the radwaste discharge pump to terminate the release.

Pertinent information on the monitor and associated control devices is prrvided in LaSalle -

UFSAR Section 11.5.2.3.3..

10.2.2.2 Service Water Effluent Monitors Monitors 1/(2)D18-N912 continuously monitor the service wr ter emuent. On high alarm service water discharge may be 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 Cooing Water Emuent Monitors Instrument channels 1/(2)D18-N906/8 continuously monitor the RHR heat exchanger cooing water emuent. On high alarm the operating loop may be terminated manually and the redundant loop brought on Ene. No control device is initiated by these 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 Equid emuent monitors at the principal release points are established to ensure that the Emits of RETS are not exceeded in the unrestricted area.

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10.2.3.1.1 Uquid Radweste Emuent Monitor The monitor setpoint is found by soMng equation 10-5 for the total isotopic activity.

P s K x Id/E(CI/10xDWC,)) x ((F + F' )/F' ) (10-5)

P Release Setpoint [ cpm]

K ((K, x C, x W,)/[CI) [ cpm /pCVm4 K, Counting efficiency for [ cpm /pCi/md radionucide i W, Weighting Factor -

CI Concentration of radionucEde iin [pC1/m6 the release tank.

F.' Maximum Release Tank Discharge Flow Rate [gpm]

The maximum flow rate is 45 gpm.

DWC, Derived Water Concentration [pCi/mq of radionuclide i The concentration of radionucEde i given in Appendix B, Table 2 Column 2 to 100FR20.1001-2402, 10 Multipier F8 Di;ution Flow [gpm]

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

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

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 (F8/E (C, /10xDWCM x MF (10 6)

The summation is over radionucides I.

0.1 Reduction factor for conservatism.

F'. Maximum Permitted Discharge Flow Rate [gpm]

The maximum permitted flow rate from the radwaste discharge tank.

F' Diletion Flow [g C, Concentration of RadionucEde 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.

DWC, Maximum Permissible Concentration [pCi/md of RadionucEde i The concentration of radionucHde i ghten in Appendix B, Table 2, Column 2 to l

10CFR20.1001-2402.

10 Multipier MF Multiplication Factor j F < 0.5; MF = 3 0.5 < F',,s 5; MF = 5 l

5 < F,,,, ; MF = 7.5 '

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-10.2.3.3 Release Umits Release Bmits are determined from RETS. Calculated maximum permissible discharge rates are divided by 10 for conservatism and to ensure that release concentrations are wen below appicable derived water concentrations (DWC).

10.2.3.4 Release Mixture For the Bquid radweste effluent monitor the release mixture used for the setpoint determinsbon is the radionuclide mix identHied in the grab sample isotopic analysis plus four odditional radionucBdes. The additional radenuclides 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 radionuc5 des.

For all other Equid 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 radweste effluent monitor is in CPM. The ceBbration constant is -

based on the detector sensitMty to Cs-137/Ba-137.

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

10.2.4 Allocation of Effluents from Common Release Points -

Radioactive Equid effluents released from the Unit i release tank are allocated to Unit 1, and effluents released from the Unit 2 tank are allocated to Unit 2. Other potential pathways (i.e.,

RHR) are allocated to their respective unit.

10.2.5 Projected Doses for Releases Doses are not calculated prior to release. Dose contributions from liquid effluents are determined in accordance with the RETS and station procedures.

10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation determination by which soldification of radioactive wastes from Equid systems is ensured.

Figure 10-4 is a simpified diagram of solid redweste processing.

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LASALLE Revision 1.1 July 1994 ,

O TABLE 10-1 Assumed Composition of the LaSalle Station Noble Gas Effluent 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 Kr-88 2.6E-2 Kr-89 1.7E-1 Kr-90 3.7E-1 l Xo-131m 2.0E-5 Xe-133m 3.8E-4 Xe-133 1.1E-2 Xe-135m 3.4E-2 Xe-135 2.9E-2 Xe-137 2.0E-1 Xe-138 1.2E-1 j l

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l LASALLE Rsvision 1.1 1 July 1994 LASALLE ANNEX INDEX EA91 REVISION CHAPTER 11

)

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11-i

l.ASAl.LE Revisi:n 1,1 July 1994 ,

CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS PAGE 11 Radiological Environmental Monitoring Program 11-1 0

l O'

11-il

l.ASALLE Rividon 1.1 July 1994 CHAPTER 11 v

UST OF TABLES NUMBER I]ILE PAGE 11-1 Radiological Environmental Monitoring Program 11-2 11-2 Reporting Levels for Radioactivity

Concentrations in Environmental Samples 11-10 11-3 Maximum Values for the Lower Umits of ,

Detection (LLD) 11-11 i

O O -

11-iii

LASALLE RIvisi:n 1.1 Juty 1994 ,

l CHAPTER 11 UST OF FIGURES NUMBER ))ILE PAGE 11-1 Fixed Air Samping Sites and Outer Ring TLD Locations 11 14 11-2 inner Ring TLD Locations 11-15

, 11-3 Ingestion and Waterbome Exposure Pathway l Samph Locatons 11-16 O

1 0

11-iv

LASALLE R:visi:n 1.1 July 1994 1

(" CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM b

The parameters for the radiological environinental monitoring program to be performed in the environs around La Salle County Station are given in Table 11-1.

Figure 11-1 shows the 14 fixed air samping sites and TLD locations; also shown are the outer ring (approximately 5 miles distant) TLD locations. Figure 11-2 shows the inner ring TLD locations. Figure 11-3 shows all other sampling locations.

The TLDs are coded as follows: l XYYz-N t

X = 1 means inner ring, X = 2 means outer ring, O YYz-N is an identificati6n code (YY and N are numbers; z is an optional letter)

The reporting levels for radioactivity concentrations in environmental samples are given in Table 11-2.

t Tlie lower Emits of detection for this program are given in Table 11-3.

i i

O '

11-1

l LASALLE Revision 1.1

! July 1994 l

Table 11-1 Radiological Envuonmental Moniloring Program Exposure Pathway Samping or Type and Frequency and/or Samole Samole or Monitorina Location" CoNection Frecuency of Analysis i 1. Airbome a. Onsite and Near Field' Continuous sampler Radiolodine Cani=ters:

operation with sample collection weekh Radioiodine and Indicators 1-131 anahsis Particulates following canister L-01, Nearsite No.1,0.5 mi NNW (0.8 km R) change and at least L-02, Nearsite No. 2,0.6 mi NNE (1.0 km B) once per 7 days L-03, Onsite No. 3,0.2 mi ENE (0.3 km D)

L-04, Nearsite No. 4,1.5 mi E (2.4 km E) Particulate Samoler-L-05, Onsite No. 5,0.3 mi ESE (0.5 km F)

L-06, Nearsite No. 6, 0.4 mi WSW (0.6 km M) Gross beta anahsis following filter change' Gamma isotopic analysis i l

on quarterly composite (by lobation) i Samolina Train:

Test and maintenance weekly l b. Far Field' Continuous sampler operation Radioiodine Canisters:

with particulate filter Indicators exchange weekly and 1-131 when analyses radioiodine canister exchange are made d L-07, Seneca. 5.2 mi NNE (8.4 km B) biweekly" e e e..

LASat.LE Revleion 1.1 July 1994 Table 11-1 (Contd)

Radiological Environmental Monitoring Program Exposure Pattmay Samp5ng or Type and Frequency end/or Sample Sample or Monitorina Location" Co5ection Frecuency of Analysis

1. Airbome L-08, Marseilles, 6.3 mi NNW (10.1 km R) Particulate Samotor-(Cont'd) L-11, Ransom,6.0 mi S (9.7 km J)

L-13. Route 6 at Gonnam Rd., Gross beta when 7.0 mi E (11.3 km E) analyses are made*'

Controls Sarno5na Train-L-09. Grand Ridge,10.4 mi W (16.7 km N) Test and maintenance L-10, Strentor,13.5 mi SW (21.7 km L) weekly L-12. Keman,5.0 mi SSW (8.0 km K)

L-14. Ottawa,12.0 mi NW (19.3 km Q)

2. Direct Radiation a. Inner Rina' At least ace per 31 days or Gamma dose at least at least once per 92 days. Once per 31 days or at Indmaton (Read-out frequencies are least once per 92 determined by type of days.

L-101-1, 0.5 mi N (0.8 km A) dosimeters selected.)

L-101-2, 0.5 mi N (0.8 km A)

! L-102-1, 0.6 mi NNE (1.0 km B)

, L-102-2, 0.6 mi NNE (1.0 km B)

L-103-1, 0.7 mi NE (1.1 '.m C)

L-103-2, 0.7 mi NE (1.1 km C)

L-104-1, 0.8 mi ENE (1.3 km D)

L-104-2, 0.8 miENE (1.3 km D)

L-105-1, 0.7 mi E (1.1 km E)

L-105-2, 0.7 mi E (1.1 km E)

L-106-1, 1.4 mi ESE (2.2 km F)

L-106-2, 1.4 mi ESE (2.2 km F)

L-107-1, 0.8 mi SE (1.3 km G)

L-107-2, 0.8 mi SE (1.3 km G)

L-108-1, 0.5 mi SSE (0.8 km H)

L-108-2, 0.5 mi SSE (0.8 km H)

L-109-1, 0.6 mi S (1.0 km J)

L-109-2, 0.6 mi S (1.0 km J) 11-3

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

LASALLE Revision 1.1 July 1994 Tatde 11-1 (Cont'd)

Radiological Envimnmental Monitorbg Program Exposure Pathway Samping or Type and Frequency and/or Samole Samole or Monitorino Location" Collection Freauency of Anahrsis

2. Direct Radiation L-110-1, 0.6 mi SSW (1.0 km K)

(Cont'd) L-110-2, 0.6 mi SSW (1.0 km K)

L-111b-1, 0.8 ml SW (1.3 km L)

L-111b-2, 0.8 mi SW (1.3 km L)

L-112-1, 0.9 rni WSW (1.4 km M)

L-112-2, 0.9 mi WSW (1.4 km M)

L-113a-1, 0.8 mi W (1.3 km N)

L-113a-2, 0.8 mi W L-114-1, 0.9 mi WNW (1.3 km N) l (1.4 km P)

L-114-2, 0.9 mi WNW (1.4 km P)

L-115-1, 0.7 mi NW (1.1 km Q)

L-115-2, 0.7 mi NW (1.1 km Q)

L-116-1, 0.6 mi NNW (1.0 km R)

L-116-2, 0.6 mi NNW (1.0 km R)

b. Outer Rina*

At least once per 31 days or Gamma dose at least at least once per 92 days. once per 31 days or at Indicators (Read-out frequencies are least once per 92 days.

determined ty type of L-201-3, 4.0 mi N (6.4 km A) dosimeters selected.)

L-201-4, 4.0 mi N (6.4 km A) i L-202-3, 3.6 mi NNE (5.8 km B) l L-202-4, 3.6 mi NNE (5.8 km B)

L-203-1, 4.0 mi NE (6.4 km C)

L-203-2, 4.0 mi NE (6.4 km C) l l

9 "'O -- -

O.

LAbed12 Revision 1.1 July 1994 Table 11-1 (Conrd)

Radiological Environmental Monlioring Program Exposure Pattmey Samping or Type and Frequency and/or Sample Samole or Monitorina Location" Collection Frecuency of Anahrsis

2. Direct Radiation L-204-1, 3.5 mi ENE (5.6 km D)

(Cont'd) L-204-2, 3.5 mi ENE (5.6 km D)

L-205-1, 3.5 mi ESE (5.6 km F)

L-205-2, 3.5 mi ESE (5.6 km F)

L-205-3, 5.1 mi E (8.2 km E)

L-205-4, 5.1 mi E (8.2 km E)

L-206-1, 4.3 mi ESE (6.9 km F)

L-206-2, 4.3 mi ESE (6.9 km F) l I

L-207-1, 4.5 mi SE p.2 km G)

L-207-2, 4.5 mi SE U.2 km G)

L-208-1, 4.5 mi S 9 2 km J)

L-208-2, 4.5 mi S 9.2 km J) '

L-209-1, 4.0 mi SSW (6.4 km K)

L-209-2, 4.0 mi SSW (6.4 km K)

L-210-1, 3.3 mi SW (5.3 km L)

L-210-2, 3.3 mi SW (5.3 km L)

L-212-1, 4.0 mi WSW (6.4 km M) -l '

L-212-2, 4.0 mi WSW (6.4 km M)

L-213-3, 4.9 mi W U.9 km H)

L-213-4, 4.9 mi W U.9 km N)

L-214-3, 5.1 mi WNW (8.2 km P)

L-214-4, 5.1 mi WNW (8.2 km P)

L-'215-3, 5.0 mi NW (8.0 km Q)

L-215-4, 5.0 mi NW (8.0 km Q)

L-216-3, 5.0 mi NNW (8.0 km R)

L-216-4, 5.0 mi NNW (8.0 km R) 11-5.

LASALLE Revision 1.1 July 1994 Table 11-1 (Contd)

Radiological Envkonmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Samole Sample or Monitorina Location" Co8echon Frecuency of Analysis

2. Direct Radiation c. Special Interest At least once per 31 days or Gamma dose at least (Cont'd) at least once per 92 days. once per 31 days or at Indicators (Read-out frequencies are least once per 92 days determined by type of on one set of TLDs Two TLDs at each of the airbome pathway dosimeters selected.) Gamma dose on second indicator locations specified in Part 1 of set if requested by this table. CECO.

Controls Two TLDs at each of the airbome pathway controllocations specified in Part 1 of this table.

3. Waterbome'

a. Surface L-21, Illinois River at Seneca, Weekly collection composited Gamma isotopic on 4.0 mi NE (6.4 km C) monthly monthly composite; L-24, LSCS Cooing Lake near recreation area, composite quarterly 0.3 mi ESE (0.5 km F) for tritium analysis,

b. Ground /Well L-27, LSCS Onsite Well at Station Quarterly Gamma isotopic and L-28, Marseilles Well,7.0 mi NW (11.3 km Q) tritium analysis L-29, Seneca Well, S.1 mi NNE (8.2 km B) quarterly of each L-30, Ransom Well, 6.0 mi S (9.7 km J) sample.

L-31. Ottawa Well,12.8 mi NW (20.6 km Q)

L-32, Illinois State Park 6.5 mi NW (10.5 km Q) e W e..

1 SALLE Revleion 1.1 July 1994 Table 11-1 (Contd)

Radiological Environmental Monitoring Program Exposure Pathway Samping or Type and Frequency and/or Samole Sample or Monitorina Location" CollectNm Frecuency of Analysis

3. Waterbome (Cont'd)

c. Shoreine L-34, Downstream of Cooing Lake discharge SemiannuaNy Gamma isotopic Sediments structure at station analysis semiennually of each sample.

4. Incestion'

a. Milk" L-16, Lowery Dairy,7.2 mi ESE (11.6 km F) Biweekly *: May to October Gamma isotopic and g L-19, Bettenhausen Dairy,7.0 mi S (11.3 km J) Monthly: November to April 1-131 analysis on each L-20, Gass Dairy, 5.0 mi NNW (8.0 km R) sample.

L-38, Richer Dairy Farm,7.6 mi SSW (12.2 km K)

L-39, Village View Acres,10.5 mi SW (16.9 km L) '

i

b. Fish L-24, LSCS Cooing Lake near recreation SemiannuaNy Gamma isotopic area,0.3 mi ESE (0.5 km F) analysis on edible L-35, Marseilles Pool of Ilinois River, portions of each 6.5 mi NW (10.5 km Q) sample.

5. Land Use Census

a. Milch Animals 1. In all 16 sectors from the site boundary Annually between June 1 and Enumerabon by a door-to 2 miles October 1 to-door or equivalent counting technique.

11-7

LASALLE Revision 1.1 July 1994 Table 11-1 (Contd)

Radiological Environmental Moniknhg Program Exposure Pathway Samping or Type and Frequency and/or Sample Samole or Monitorina Location

CoRection Freauency of Anafysis

5. Land Use Census 2. In all 16 sectors from 2 to 5 mihm Annually between June 1 and Enumeration by using (Cont'd) October 1 referenced information from county agricutural agencies or other relable sources.

3. At dairies Fated in item 4.a. Annually between June 1 and inquire as to feeding October 1 oractices:

a. Pasture only.

b. Feed and Chop only.

c. Pasture and feed; if both, ask farmer to estimate fracGon of food

<25%, 25-50%,

50-75%, or >75%.

e 6 e..

e amas 18 V

Revleion 1.1 July 1994 Table 11-1 (Contd)

Radiological Environmental Monbodng Program Exposure Pattmey Samp5ng or Type and Frequency and/or Sample Sample or Monitorina Location

Cotection Freauency of Analysis

5. Land Use Census (Contd)

A Nearest in all 16 sectors up to 5 miles. Annua 5y between June 1 and Resident October 1

See Table D-16 for definitions of actor codes used with kilometer distances

See Figure 11-1, " Fixed Air Sampling Sites and Outer Ring TLD Locahons

Perform gamme isotopic anshsis on each sample when Dross beta actmty is greater than (>) 10 times the yearly mean of control samples. -

Far field samples are analyzed when near field results are inconsistent with previous nessurements and radioactivity is confirmed as having its origin in airbome effluents released from the stabon, or at the discrebon of the Emergency Preperedness Director.

*Biweekh means every two weeks.

'See Figure 11-2, " Inner Ring TLD Locations

i

! 'See Figure 11-3, " ingestion and Waterbome Exposure Pathway Locations *

' Milk samples are required from three monitoring locahons only. Five dawles are Ested to ensure at least three dairies era sampled i

l 11-9 l

l .

IASAl.LE Revision 1.1 July 1994 Table 11-2 Report'ng Levels For RadioactMty Concentrations l

In Environmental Samples l

Airbome Particulate Water or Gases Fish Milk Analysis (Ci/L) (DCi/mh foci /ka. wet) foci /L)

H-3 20,000*

Mn-54 1,000 30,000 F(>59 400 10,000 Co-58 1,000 30,000 CD60 300 10,000 Zn45 300 20,000 ,

Zr-Nb-95 400 1-131 2 0.9 3 Co-134 30 10 1,000 60 Cs-137 50 20 2,000 70 Ba-La-140 200 300 "For drinking water samples. This is 40 CFR Part 141 value.

h - - - - - - - -- -

h.

O O O' LASALLE Revision 1.1 July 1994 Table 11-3 Maximum Values for the Lower Lknks of Detecelon (LLD)

(.

/ u,ime Particulate Water or Gases Fish Milk Sedimord b;.fysis (DCi/L) foCl/m') (DCi/ka. wet) foci /L) foci /ka. dtv)

Gross Beta 5 0.01 1,000 NA 2,000 H-3 200 NA NA NA NA Mn-54

NA b *

Fo-59

NA b *

Co-58,60

NA b *

Zn-65

NA' b *

Zr-95

NA b *

Nb-95

NA b * * '

l-131 NA 0.1 200 0.5

Ca-134 10 0.01 100 10

Cs-137 10 0.01 100 10

Ba-140

NA b *

Lo-140

NA b *

11-11

r LASALLE Revision 1.1 July 1994 ,

Table 11-3 (Cont'd)

Maximum Values for the Lower Umits of Detection (LLD)

General Notes:

1. The LLD is the smallest concentration of radioactive materialin a sample that wi!! be detected with 95% probabilty with 5% probabiEty of falsely concludirag that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 s, LLD =

E V 2.22 Y exp (-14t)

LLD The a gdgd lower Emit of detection as defined above (as picocuries per unit mass or volume),

s. The standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E The counting officiency (as counts per transformation),

V The sample size (in units of mass or volume).

2.22 The number of transforrnations per minute per picoeurie, Y The fractional radiochemics! yield (when applicable),

A The radioactive decay constant for the particular radionuclide, and l

At The elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluents).

l The value of s, used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionucEde determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionucEdes normally present in the samples (e.g.,

potassium-40 in milk samples). Typical values of E, V, Y. and at ,hai: br, used in the calculations.

O 1

i 11-12

. .. ._. - 2. -

l LASALLE Revisi:n 1.1 )

., July 1994 ;

Table 11-3 (Conrd)

Maximum Values for the Lower Umits of Detection (LLD)

2. Other peaks which are measurable and identi6able, together with the radionuclides in this table, shall be identi6ed and reported.

i Footnotes:

Gamma leotopic analysis provides LLD of approximately 20 pCi/L per nucide.

Gamma isotopic analysis provides LLD of approximately 20 pCi/kg per nucEde.

O l

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11-13

s LASALLE Revisi:n 1.1 July 1994

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LASALLE R:visi:n 1.1 July 1994 !

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MN R::visi:rn 1.1 July 1994 N~

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SPECIAL NOTE The transfer of the Radiological Emuent Technical SpeciAcations (RETS) to the ODCM has been approved by the Nuclear Regulatory Commission in Amendrnents 8549.

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LASALLE Revision 1.1 July 1994 ,

LASALLE ANNEX INDEX EAgg REVISION P.AQE REVISION CHAPTER 12 12 -i 1.1 12 - 46 1.1 l 12 - R 1.1 12 - 47 1.1 12 - lii 1.1 12 - 48 1.1 12 -iv 1.1 12 - 49 1.1 12 - 1 1.1 12 - 50 1.1 12 - 2 1.1 -

12 - 51 1.1 12 - 3 1.1 12 - 52 1.1 12 - 4 1.1 12 - 53 1.1 12 - 5 1.1 12 - 54 1.1 12 - 6 1.1 12 - 55 1.1 12 - 7 1.1 12 - 8 1.1 12 - 9 1.1 12 - 10 1.1 12 - 11 1.1 12 - 12 1.1 12 - 13 1.1 12 -14 1.1 12 - 10 1.1 12 - 16 1.1 12 - 17 1.1 12 -18 1.1 12 - 19 1.1 12 - 20 1.1 12 - 21 1.1 12 - 22 1.1 12 23 1.1 12 - 24 1.1 12 - 25 1.1 12 - 26 1.1 12 - 27 1.1 12 - 28 1.1 12 - 29 1.1 12 - 30 1.1 12 - 31 1.1 12 - 32 1.1 12 - 33 1.1 12 - 34 1.1 12 - 35 1.1 12 - 36 1.1 12 - 37 1.1 12 - 38 1.1 12 - 39 1.1 12 - 40 1.1 12 - 41 1.1 12 - 42 1.1 12 - 43 1.1 12 - 44 1.1 12 - 45 1.1 1 2 - 11

LASALLE Revision 1.1

. July 1994 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS ,

(RETS) !

TAsts OF CONTENTS 12.0 COMPUANCE MATRIX 12-1 '

12.1 DEFINITIONS 12-2 12.2 INSTRUMENTATION 124

1. Radioactive Uquid Emuent Monitoring Instrumentation 12 4

2. Radioactive Gaseous Emuent Monitoring instrumentation 12-11 12.3 UQUID EFFLUENTS 12-18

1. Concentration 12-18

2. Dose 12-23

3. Uquid Weste Treatment System 12-24 ;

12.4 GASEOUS EFFLUENTS 12-27

1. Dose Rate 12-27

2. Dose - Noble Gases 12-31

3. Dose - lodine-131, lodine-133, Tritium, and Radionuclides in Particulate Form 12-32

4. Gaseous Radweste Treatment System 12-33

5. Ventilation Exhaust Treatment System 12-34

6. Venting or Purging 12-35

7. Total Dose 12-36 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-40

1. Radiological Environmental Monitoring Program 12-40

2. Land Use Census 12-47

3. Interlaboratory Comparison Program 12-49 12.8 REPOR11NG REQUIREMENTS 12-51'

1. Annual Radiological Environmental Operating Report 12-51

2. Radioactive Emuent Release Report 12-52

3. Offsite Dose Caculation Manual (ODCM) 12-54

4. Major Changes to Radioactive Weste Treatment 12-55 Systems O

12-lii

LASALLE Revisisn 1.1 July 1994 ,

CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

UST OF TABLES 12.0-1 Compiance Matrix 12-1 l

12.1-1 Surveillance Frequency Notation 12-5 12.2.1-1 Radioactive Uquid Emuent Monitoring instrumentation 12-7 12.2.1-2 Radioactive Liquid Effluent Monitoring instrumentation Surveillance Requirements 12-9 12.2.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation 12-12 12.2.2-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 12-14 12.3.1-1 Allowable Concentration of Dissolved or Entrained Noble Gases Release from the Site 12-19 to Unrestricted Areas in Uquid Waste 12.3.1-2 Radioactive Uquid Waste Samping and Analysis Program 12-20 12.4.1-1 Radioactive Gaseous Waste Samping and Analysis Program 12-28 12.5.1-1 Radiological Environmental Monitoring Program 12-42 12.5.1-2 Reporting Levels for Radioactivity Concentrations in Environmental SampEng 12-45 12.5.1-3 Maximum Values for the Lower Umits of Detection (LLD) 12-46 O

12-iv

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LAsALLE Revision 1.1 July 1994 Table 12.0-1 COMPUANCE MATRIX Regulation Dose to be compared to Emit ODCM RETS l

Technical Equation Specification 10 CFR 50 1. gamma air dose and beta air dose due to airbome radioactivity in effluent A-1 12.4.2 62.F.4.h Appendix I plume. A-2 1.a whole body and skin dose due to airbome radioactivity in effluent plume are A-6 N/A N/A reported only if certain gamma and beta air dose criteria are exceeded. A-7

2. CDE for aR organs and a!! four age groups due to lodines and particulates A-13 12.4.3 6.2.F.4.1 in effluent plume. All pathways are considered. 3

]

3. CDE for aR organs and all four age groups due to radioactMty in Equid A-29 12.3 2 6.2.F.4.d effluents.

l 10 CFR 20 1. TEDE, totalng aR deep dose equivalent components (direct, ground and A-38 6.2.F.4.c plume shine) and committed effective dose equivalents (aR pathways, both airbome and liquid-bome). CDE evaluation is made for adult only using FGR 11 data base.

40 CFR 190 1. Whole body dose (DDE) due to direct dose, ground and plume shine from A-35 12.4.7 (now by reference, 6.2.F.4.]

aR sources at a station.

also part of 10 CFR 20) 2. Organ doses (CDE) to an adult due to all pathways. A-13 Technical 1. " Instantaneous" whole body (DDE), thyroid (CDE) and skin (SDE), dose A-8 12.4.1 62.F.4.g Specifications and rates to an adult due to radioactnnty in airbome effluents. For the thyroid A-9 Generic Letter dose, only inhalation is considered. A-28 93-xx

2. " Instantaneous" concentration Emits for Equid effluents. A-32 12.31 6.2.F.4.b 12-1

LASALLE Revision 1.1 July 1994 ,

12.1 DEFINITIONS 12.1.1 ACTION - ACTION shall be that part of a requirement which prescribes remedial measures required under designated conditions.

12.1.2 CHANNEL CALIBRATION - A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channei output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAUBRATION shall encomwss the entire channelincluding tha alarm and/or trip functions, and shallinclude the CHANNEL FUNCTIONAL TEST. The CHANNEL CAUBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is caEbrated.

12.1.3 CHANNEL CHECK - A CHANNEL CHECK shan be the quaDtative assessment of channel behavior during operation by observation. This determination shallinclude, where possible, comparison of the channelindication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

12.1.4 CHANNEL FUNCTIONAL TEGI- A CHANNEL FUNCTIONAL TEST shau be:

s. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practical to verify OPERABluTY including alarm and/or trip functions and channel failure trips.

b. Bistable channels - the injection of a simulated signalinto the sensor to verify OPERABluTY including alarm and/or trip functions.

The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is tested.

12.1.5 DOSE EQUIVALENT l-131 - DOSE EQUIVALENT l-131 shan be that concentration of I-131, rnicrocuries/ gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133,1-134 and 1-135 actuaHy present.

The thyroid dose conversion factors used for this calculation shall be those Ested in Table til of TID-14844," Calculation of Distance Factors for Power and Test Reactor Sites."

12.1.6 GASEOUS RADWASTE TREATMENT SYSTEM - A GASEOUS RADWASTE TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing total radioactivity prior to release to the environment.

O 12-2

4 LASALLE Revision 1.1 July 1994 O 12.1.7 MEMBER (S) OF THE PUBLIC - means an Individualin a controlled area or unrestricted area. However, en individualis not a member of the public during any period in which the individual receives occupational dose.

12.1.8 OPERABLE - OPERABILITY - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its speci6ed function (s), and when su necessary attendant instrumentation, controls, cooing or seal water, lubrication or other auxilary equipment that are reqeired for the system, ,

subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s). ;

12.1.9 PROCESS CONTROL PRQQB6ld - The PROCESS CONTROL PROGRAM (PCP) shaN contain the current formulas, samping, analyses, test, and determinations to be 1 made to ensure that processing and pacicaging of solid radioactive wastes based on !

demonstrated processing of actual or simulated wet solid wastes shall be accomplished )

in such a way as to assure compiance with 10 CFR Parts 20,61, and 71, State regulations, budal ground raquirements, and other requirements goveming the disposal I' of sold radioactive waste.

12.1.10 PURGE - PURGING - PURGE or PURGING shaN be the controlled process of ;

discharging air or gas from a con 8nement to maintain temperature, pressure, humidity, concentrabon or other operating condition, in uuch a manner that replacement air or gas is required to purify the con 8nement. ,

12.1.11 RATED THERMAL POWER - RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3323 MWT.

O 12.1.12 SITE BOUNDARY - The SITE BOUNDARY shall be that Ene beyond which the land is 1

i neither owned, nor leased, nor otherwise controlled by the Econsee. l 12.1.13 SOLIDIFICATION - SOLIDIFICATION shal be the conversion of radioactive wastes i from Equid systorm to a homogeneous (uniformly distributed), monoEthic, immobilized l solid with de6 nite volume and shape, bounded by a steble surface of distinct outine on all sides (free-standing).

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LASALLE Revision 1.1 July 1994 ,

12.1.14 SOURCE CHECK - A SOURCE CHECK shall be the quaEtative assessment of channel response when the channel sensor is exposed to a radioactive source.

12.1.15 THERMAL POWER - THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

12.1.16 UNRESTRICTED AREA BOUNDARY - means an ares, access to which is neither Emited nor controlled by the Econsee.

12.1.17 VENTILATION EXHAUST TREATMENT SYSTEM - A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radiolodine or radioactive materialin particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust system prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atomspheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

12.1.18 VENTING - VENTING shall be the 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.

12.1.19 Def.nitions PecuEar to Estimating Dose to Members of the Public Using the ODCM Computer Program.

a. ACTUAL - ACTUAL refers to using known release data to project the dose to members of the pubEc for the previous time period. This data is stored in the database and used to demonstrate compiance with the reporting requirements of Chapter 12.6.

b. PROJECTED - PROJECTED refers to using known release data from the previous time period or estimated release data to forecast a future dose to members of the pubic. This data is not incorporated into the database.

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12-4

LASALLE Revision 1.1 July 1994 O TABLE 12.1-1 SURVElLLANCE FREQUENCY NOTATION NOTATION FREQUENCY S At least oncd per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

A At least once per 366 days.

R At 8 east once per 18 months (550 days). ;

S/U Prior to each reactor startup. i P Prior to each radioactive release.

I N.A. Not applicable. i 1

, O 12-5

l.ASALLE Revision 1.1 July 1994 12.2 INSTRUMENTATION RADIOACTNE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS 12 2.1.A The redioactive Equid effluent monitoring instrumentation channels shown in Table 12.2.1-1 shall be OPERABl.E with their alarm / trip setpoints set to ensure that the Emits of Section 12.3.1.A are not exceeded. The alarm trip setpoints of ,

these channels shall be determined in accordance with the ODCM Chapter 10.

APPLICABILITY: At all times.

ACTION

a. With a radioactive Equid emuent monitoring instrumentation channel alarm / trip cetpoint less conservative than required, immediately suspend the release of radioactive Equid effluents monitored by the affected channel or declare the channelinoperable.

b. With less than the rninimum number of radioactive Equid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2.1-1.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or, explain in the next Radioactive Emuent Release Report why this inoperabiEty was not corrected within the time specified.

SURVEILLANCE REQUIREMENTS 12.2.1.B Each radioactive Equid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 12.2.12.

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O O O' LAoALLE Revision 1.1 July 1994 TABLE 122.1-1 RADIOACTIVE UQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. GAMMA SCINTILLATION MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

s. Uquid Radweste Effluent Une 1 100

2. GAMMA SCINTILLATION MONITORS PROV' DING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Service Water System Effluent une (Unit 1) 1 101

b. RHR Service Water (Une A) Effluent Une 1 101

c. RHR Service Water (Line B) Effluent une 1 101

d. Semce Water System Effluent Une (Unit 2) 1 101

3. FLOW RATE MEASUREMENT DEVICES

a. Uquid Radweste Effluent une 1 102

b. River Descharge - Blowdown Pipe 1 102 12-7

LASALLE Revision 1.1 July 1994 4

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE 12.2.1-1 (Continued)

TABLE NOTATION ACTION 100 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided that prior to initia ,

ting a release:

a. At least two independent samples are analyzed in accordance with Section 12.3.1.B.3, and

b. At least two technically quaified members of the Facitty Staff independently verify the release rate calculations and discharge Ene !

vaMng; 1 Otherwise, suspend release of radioactive effluents via this pathway. I ACTION 101 - With the number of channels OPERABLE less than required by the Minimum Channels OPFRABLE requirement, effluent releases via this pathway may l continue for Lp to 30 days provided that, at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab i samples are collected and analyzed at a imit of detection as specified in Table j 12.3-2.

l ACTION 102 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, actual radioactive releases in progress via O. l this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Pump curves for Instrument 3a, or for known valve positions for Instrument 3b, may be used to estimate flow. Actual releases of radioactive effluent will not be initiated without an OPERABLE channel.

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1.ASALLE Revleion 1.1 July 1994 TABLE 12.2.1-2 RADIOACTIVE UQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE FUNCTIONAL CHANNEL INSTRUMENT CHECK CHECK TEST CAUBRATION

1. GAMMA SCINTILLATION MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

o. Uquid Redweste Effluents Une D P Q(1) R(3)

2. GAMMA SCINTILIATION MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

o. Service Water System Effluent Line (Unit 1) D M Q(2) R(3)

b. RHR Seevice Water (Une A) Effluent une D M Q(2) R(3)

c. RHR Service Water (Une B) Effluent une D M Q(2) R(3)

d. Service Water System Effluent une (Unit 2) D M Q(2) , R(3)

3. FLOW RATE MEASUREMENT DEVICES

e. Liquid Redweste Effluent une D(4) N.A. P R

b. River Discharge - Blowh Pipe D(4) N.A. Q R l

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LASALLE Revision 1.1 July 1994 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE 12.2.1-2 (Continued)

TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also ocmonstrate that automatic isolation of this pathway and control alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above il$e alarm / trip setpoint.

2. Loss of power.

3. Instrument alarms on downscale failure.

4 Instrument controls not set in Operate or High Voltage mode.

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

1. Instrument indicates measured levels above the alarm setpoint.

2. Loss of power.

3. Instrument alarms on downscale failure.

4. Instrument controls not set in Operate or High Voltage mode.

(3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference radioactive standards certified by the NationalInstitue 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 caEbrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, the initial reference radioactive standards or radioactive sources that have been related to the initial caEbration shall be used.

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

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

O 12-10

LASALLE Revision 1.1 July 1994 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERABluTY REQUIREMENTS 12.2.2.A The radioactwo gaseous effluent monitoring instrumentation channels shown in Table - l 12.2.2-1 shaN be OPERABLE with their alormMp setpoints set to ensure that the Emits of Section 12.4.1.A are not exceeded. The alarmMp setpoints of these channels shail ,

be determined in accordance with the ODCM. {

APPUCABluTY: As shown in Table 12.2.2-1.

ACTION

a. With a radioactive gaseous effluent monitoring instrumentation channel alarmMp setpoint less conservative than required, immediately suspend the release of radioactive ,

gaseous effluents monitored by the affected channel or declare the channelinoperable. {

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentabon channels OPERABLE, take the ACTION shown in Table 12.2.2-1. l SURVEILLANCE REQUIREMENTS 12.2.2.8 E;ach radioactive gaseous effluent monitoring instrumentation chen: eel shah be comonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE i CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CAUBRATION operations at l the frequencies shown in Table 12.2.2-2. l t

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LASALLE Revision 1.1 July 1994 TABLE 12.2.2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRLNENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTIQN

1. MAIN CONDENSER OFFGAS TREATMENT SYSTEM EFFLUENT MONITORING SYSTEM

a. Noblo Gas Activity Monitor- Providing Alarm and Automatic Termination of Release 1 110

2. MAIN STACK MONITORING SYSTEM

a. Noble Gas Activity Monitor 1 1M

b. lodine Sampler 1 111

c. Particulate Sampler 1 111

d. Effluent System Flow Rate Monitor 1 112

e. Sampler Flow Rate Monitor 1 112

3. CONDENSER AIR EJECTOR RADIOACTIVITY MONITOR (Prior to Input to Holdup System)

a. Noble Gas Activity Monitor 1 # 113

4. SBGTS MONITORING SYSTEM

a. Noble Gas Activity Monitor 1 M 110

b. Iodine Sampler 1 M 111

c. Particulate S>mpler 1 M 111

d. Effluent System Flow Rate Monitor 1 M 112

e. Sampler Flow Rate Monitor 1 M 112

LASALLE Revision 1.1 July 1994 ;

. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION <

g -

h TABLE 12 2 2-1 (Continued) ;

TABLE NOTATION At aN times. !

During main condenser offges treatment system operation. '

During operation of the main condenser air ejector.

8# During operation of the SBGTS. i ACTION 110 - With the number of channels OPERABLE less than required by the Minimum Channels !

OPERABLE requirement, emuent releases via this pathway may continue for up to 30 .

days provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are l analyzed for noble gas gamma emitters within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Ensure midrange channel -

indicator for noble gas activity indicated flow is occurring. l ACTION 111 - With the number of channels OPERABLE less than required by the Minimum Channels - l OPERABLE requirement, emuent releases via this pathway may continue for up to 30 i days provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the channel has been declared inoperable,' l samples are continuously collected with auxilary sampung equipment as required in !

Table 12.4.1-1. ;

ACTION 112 - _ With the number of channels OPERABLE less than required by the Minimum Channels !

O OPERABLE requirement, emuent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 113 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the output from the charcoal adsorber vessels may be released to the environment for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided:

a. The offgas treatment system is not bypassed, and j

b. The offges treatment delay system noble gas activity emuent dwnstream monitor is OPERABLE; Otherwis . be in at least STARTUP with the main steam isolation valves closed within ;

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

t NOTE: Clarification: Even though only 1 channelis required by Tech Specs, in order to prmide automatic termination of release (i.e. to auto close 1(2)N62 F057),1 out of 3 twice irgic is required (i.e. 2 channels). One channel uses the 1(2)A Post Treatment PRM H1', Dwe. scale, inop Trips while the other channel uses the 1(2)B Post Treatment PRM Hi', Downscale, inop Trips. Therefore, if one of the Post Treatment PRM's is inop, then that inop PRM must be placed in the Trip Condition (i.e, taken out of operate), otherwise the Associated Action Statement must be followed (i.e. Sample 1/8 hrs. for up to 30 days).

(See Technical Specification clarification 02/88 signed by Station Manager 3/31/88.)

O 12-13

LASALLE Revision 1.1 July 1994 TABLE 12.2.2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS OPERATIONAL CHANNEL CONDITIONS FOR CHANNEL SOURCE FUNCTIONAL CHANNEL WHICH SURVEIL-INSTRUMENT CHECK CHECK TEST CALIBRATION LANCE REQUIRED

1. MAIN CONDENSER OFFGAS TREATMENT SYSTEM EFFLUENT MONITORING SYSTEM

a. Noble Gas Actmty Monitor-Providing Alarm and Automatic Termination of Release D D Q(1) R(3)

2. MAIN STACK MONITORING SYSTEM

a. Noble Gas Activity Monitor D M Q(4) R(3)

b. todine Sampler W NA NA N.A. *

c. Particulate Sampler W N.A. N.A. , NA '

d. Effluent System Flow Rate Monitor D NA Q R *

e. Sampler Flow Rate Monitor D NA Q R

3. CONDENSER AIR EJECTOR RADIOACTIVITY MONITOR

a. Noble Gas Activity Monitor D M Q(2) R(3) #

4. SBGTS MONITORING SYSTEM

a. Noble Gas Activity Monitor D M Q(4) R(3) M

b. Iodine Sampler W N.A. N.A. NA N

c. Particulate Sampler W N.A. NA N.A. N

d. Effluent System Flow Rate Monitor D NA Q R M

e. Sampler Flow Rate Monitor D N.A. Q R M e E -

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LASALLE Revision 1.1 ,

July 1994 [

RADIOACTIVE GASEOUS EFFLUENT MONITORING lNSTRUMENTATION SURVEILLANCE l [

i REQUIREMENTS I t !

TABLE 12.2.2-2 (Continued) l i

TABLE NOTATION .

i At at times. i

During operation of the main condenser air ejector, t

$8 During operation of the SBGTS. l (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolabon capabitty of :

this pathway, and that control room alarm annunciation occurs if any of the following conditions !

arists: (each channel win be tested independently so as not to initiate automatic isolabon dudng operation),

1. Instrument indicates measured levels above the alarmarip setpoint. !

2. Loss of power. l

3. Instrument alarms on downscale failure. ;

4. Instrument controls not set in Operate or High Voltage mode. (Automatic isolation shaN be demonstrated during the CHANNEL CAUBRATION). l (2) The CHANNEL FUNCTIONAL TEST for the log scale monitor shall also demonstrate that ,

control room alarm annunciation occurs if any of the following conditions exists. j

1. Instrument indicates measured levels above the alarm setpoint. 5 i

2. Loss of power. j

3. Instrument alarms on downscale failure. t

4. Instrument controls not set in Operator or High Voltage mode (3) The initial CHANNEL CAUBRATION shall be performed using one or more of the reference j radioactive standards certified by the National Institute of Standards and Technology (NIST) or

, using standards that have been obtained from suppliers that participate in measurement ' l l assurance activities with NIST. These standards shall permit caibrating the system over its i

intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, ;

the initial reference radioactive standards or radioactive sources that have been related to the initial caibration shall be used.

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LASALLE Revision 1.1 July 1994 l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE )

REQUIREMENTS TABLE 12.2.2-2 (Continued)

O TABLE NOTATION (4) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: j

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1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Instrument controls not set in the Operate mode.

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LASALLE Revision 1.1 i July 1994 l l

INSTRUMENTATION LIQUID AND GASEOUS INSTRUMENTATION BASES i i

l 12.2.1.C RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive Equid effluent monitoring instrumentation is provided to rnonitor and control, as appicable, the releases of radioactive rnatorials in liquid effluents during actual or potential releases of Equid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the Ernits of RETS. The OPERABILITY and use of ;

this instrumentation is consistent with the requirements of General Design Criteria 60,63, l and 64 of Appendix A to 10 CFR Part 50.-

12.2.2.C RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and ;

control, as appicable, the releases of radioactive materials in gaseous effluents during i actual or potential releases of gaseous effluents. The alarm / trip setpoints for these ,

instruments shall be calculated in accordance with the procedures in the ODCM to I ensure that the alarm / trip will occur prior to exceeding the limits of RETS. ;

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LASALLE Revision 1.1 July 1994 12.3 LIQUID EFFLUENTS CONCENTRATION OPERABILITY REQUIREMENTS 12.3.1.A The concentration of radioactive material released from the site shall be Emited to ten (10) times the concentration value in Appendix B, Table 2, Column 2 to l 10CFR20.1001-20.2402 for radionucEdes other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be Emited to the concentrations specified in Table 12.3.1-1.

APPLICABILITY: At all times.

ACTION With the concentration of radioactive material released from the site exceeding the above Emits, immediately restore the concentration to within the above Emits.

SURVEILLANCE REQUIREMENTS 12.3.1.B.1 The radioactivity content of each batch of radioactive Equid waste shall be determined prior to release by sampEng and analysis in accordance with Table 12.3.1-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentratior' at the point ,

of release is maintained within the Emits of Section 12.3.1.A.

12.3.1.B.2 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 12.3.1-2. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the Emits of Section 12.3.1.A.

12.3.1.B.3 The radioactivity concentration of Enuids discharged from enntinuous release points shall be determined by collection and analysis of samples in accordance with Table 12.3.1-2. The results of the analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release are maintained within the Emits of Section 12.3.1.A.

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LASALLE RIvisi n 1.1 July 1994 I'

TABLE 12.3.1-1 ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE t

NUCLIDE AC(uCl/mD*

Kr 85 m 2E-4 85 SE4 87 4E-5 88 9E-5 Ar 41 7E-5 ,

Xe 131 m 7E-4 133 m SE-4 133 6E-4 135 m 2E-4 135 2E4

Computed from Equation 20 of ICRP Pub 5 cation 2 (1959), adjusted for infinite cloud submersion in water, and R = 0.01 rem / week, p., = 1.0 gm/cm', and P,/P, = 1.0. J l

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LASALLE Revision 1.1 l July 1994 !

TABLE 12.3.1-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM l

LIQUID RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT OF TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD) !

FREQUENCY ANALYSIS (pCl/ml)*

l l A. Batch Waste P P Principal Gamma 5x10 '

Release Each Batch Each Batch Emitters' Tanks' d l-131 1x10 1

P M Dissolved and 1x10 4 )

One Batch /M Entrained Gases j (Gamma Emitters) 1 P M H-3 1x10*

Each Batch Composite

Gross Alpha 1x10 # ]

P Q Sr-89, Sr-90 5x10 )

Each Batch Composite

4 Fe-55 1x10

2. Continuous Continuous' Composite' Principal Gamma 5x10 #

Releases

Emitters' l-131 1x10*

M M Dissolved and 1x10 4 Grab Sample Entrained Gases (Gamma Emitters) 4 Continuous' M H-3 1x10 Composite' 4

Gross Alpha 1x10 Continuous

Q Sr-89, St-90 5x10*

Composite

Fe-55 1x10' O

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l LASALLE ~ Revision 1.1 July 1994 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE 12.3.1-2 (Continued)

TABLE NOTATION

a. The LLD is the smallest concentration of radioactive matedalin a sample that win be detected with 95% probabitty with 5% probabilty of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.06 s.

LLD = E . V . 2.22x10' . Y . exp (-Aat)

Where:

LLD is the "a pdor!" lower Emit of detection as defined above (as microcurie per unit mass or volume),

s, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

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

2.22x10'is the number of transformations per minute per microcurie, Y is the fractional radiochernical yield (when appBcable),

A is the radioactive decay constant for the particular radionucide and for composite samples, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples). For batch samples taken and analyzed prior to release, at is taken to be zero.

The value of s, used in the calculation of the LLD for a detection system shaR be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E. V, Y, and at shan be used in the calculation,

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of Equid waste discharged and in which the method of sample employed results in a specimen which is representative of the liquids released.

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LASALLE Revision 1.1 July 1994 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE 12.3.1-2 (Continued)

TABLE NOTATION

c. To be representative of the quantities and concentrations of radioactive materials in Equid ofnuents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representativa of the effluent release.

d. A batch release is the discharge of Equid waste of a discrete volume. Prior to sampEng for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampEng.

e. A continuous release is the discharge of Equid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.

f. The principal gamma emitters for which the LLD specification appEes exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60,2n45, Mo-99, Cs-134, Cs-137, Co-141, and Co-144. This Est does not mean that only these nucEdes are to be detected and reported.

Other peaks which are measurable and identifiable, at the 95% confidence level, together with the above nucEdes, shall also be identified and reported.

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LASALLE Revision 1.1 July 1994

,q LIQUID EFFLUENTS DOSE OPERABILITY REQUIREMENTS 12.3.2.A The dose or dose commitment to an individual from radioactive materials in liquid emuents released, from each reactor unit, from the site shau be limited:

l a. During any calendar quarter to less than or equal to 1.5 mrom to the total body and to less than or equal to 5 mrom to any organ, and

b. During any calendar year to less than to equal to 3 mrom to the total body and to less than or equal to 10 mrom to any organ.

APPLICABILITY: At all times.

ACTION

a. With the calculated dose from the release of radioactive materials in Equid effluents exceeding any of the above Emits,in Eeu of any other report required by LaSalle Technical Specification 6.6.A, prepare and submit to the Commission within 30 days, pursuant to LaSalle Technical Specification 6.6.C a Special Report which identifies the !

cause(s) for exceeding the Emit (s) and defines the corrective actions to be taken to l reduce the releases of radioactive materials in liquid effluents during the remainder of O the current calender quarter and during the subsequent three calender quarters, so that h the cumulative dose or dose comrnitment to an individual from these releases is within 3 mrom to the total body and 10 mrom to any organ. This Special Report shall also include the radiologicalimpact on finished drinking water suppies at the nearest downstream drinking water source.

SURVEILLANCE REQUIREMENTS 12.3.2.B Dose Calculations- Cumulative dose contributions from Equid emuents shall be determined in accordance with the ODCM at least once per 31 days, when Equid discharges are performed.

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LASALLE Revision 1.1 July 1994 LIQUID EFFLUENTS 1 LIQUID WASTE TREATMENT SYSTEM OPERABILITY REQUIREMENTS 12.3.3.A The Equid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in Equid wastes prior to their discharge when the projected doses due to the Equid effluent from each reactor unit, from the site, when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 rnrem to any organ.

APPLICABILITY- At all times.

ACTION

a. With the Equid radwaste treatment system inoperable for : ore than 31 days or with radioactive Equid waste being discharged without treatment and in excess of the above Emits, in lieu of any other report required by LaSalle Technical Specification 6.6.A.

prepare and submit to the Commission within 30 days pursuant to LaSalle Technical Specification 6.6.C, a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperabiEty,

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

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

SURVEILLANCE REQUIREMENTS l

12.3.3.B.1 Doses due to Equid releases shall be projected at least once per 31 days or when I releases are to be performed, in accordance with the methods in the ODCM.

12.3.3.B.2 The liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid radwaste system has been utiEzed to process radioactive Equid effluents during the previous 92 days.

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LASALLE Revision 1.1 i July 1994 l LIQUID EFFLUENTS O LIQUID EFFLUENTS BASES i

I 12.3.1.C CONCENTRATION This requirement is provided to ensure that the concentration of radioactive materials ,

toisased in Equid waste affluents from the Jsite wlR be less than ten (10) times the concentration levels specified in Apperdx B, Table 2, Column 2 to 10CFR20.1001-2402. This Emitation provides additional assurance that the levels of radioactive ;

materials in bodies of water outside the site win result in exposure within (1) the Section ;

ll.A design objectwas of Appendix 1,10 CFR 50, to an individual, and (2) the Emits of 10 CFR 20.1301 to the population.

12.3.2.C QQ.EE This requirement is provided to implement the requirements of Sections ll.A, Ill.A and l IV.A of Appendix 1,10 CFR Part 50. The 1.imiting Condition for Operation implements l' to guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibilty and at the same time implement the guides set forth in >

Section IV.A of Appendix I to assure that the releases of radioactive materialin Equid emuents wiH be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there j is reasonable assurance that the operation of the faci 8ty wlR not result in radionuclide i concentrations in the Anished drinking water that are in excess of the requirements of r O 40 CFR 141. The dose calculations in the ODCM implement the requirements in Sechon Ill.A of Apperdx 1 that conformance with the guides of Appendix i be shown by _

~

l calculational procedures based on models and data, such that the actual exposure of l an individual through appropriate pathways is unNkely to be substantiaHy underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid emuents are consistant with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Emuents for the Purpose of Evaluating Compiance with 10 CFR Part 50, Appendix 1," Revision 1 October 1977 and Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Emuents from Accidental and Routine Reactor L Releases for the Purpose of implementing Appendix 1," April 1977.

This requirement applies to the release of radioactive materials in Equid ofnuents from l each reactor at the site. For units with shared redweste treatment systems, the liquid ,

emuents from the shared are proportioned among the units sharing that system. '

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LASALLE Revision 1.1 July 1994 LIQUID EFFLUENTS LIQUID EFFLUENTS BASES 12.3.3.C LIQUID WASTE TREATMENT SYSTEM The OPERABILITY of the Equid radweste treatment system ensures that this system will be available for use whenever Equid 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 Equid effluents will be kept "as low as is reasonably achievable." During extended shutdown or low power operation, i.e., > 92 days, when steam is not available to the concentrators, Surveillance Requirement 12.3.3.B.2 may be extended to 180 days. This specification implements the requirements of 10 CFR Part 50.36a. General Design Criterion 50 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix 1 to 10 CFR Part 50. The specified Emits goveming the use of appropriate portions of the Equid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section ll.A of Appendix I,10 CFR Part 50, for Equid effluents.

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LASALLE Revision 1.1 July 1994 12.4 GASEOUS EFFLUENTS )

O DOSE RATE l

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OPERABluTY REQUIREMENTS l

12.4.1.A The dose rate due to radioactive materials released in geseous effluents from the site to areas at and beyond the SITE BOUNDARY, shall be Emited to the following: ,

s. For noble gases: Less than or equal to a dose rate of 500 mrom/yr to the total body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and

b. For iodine-131, for iodine-133, for tritium, and for all radionucides in particulate form with half Eves greater than 8 days: Less than or equal to a dose rate of 1500 mroms/yr to any organ via the inhalation pathway.

APPLICABILITY- At all times.

ACTION With the dose rate (s) exceeding the above Emits, immediately decrease the release rate to within the above Emit (s).

SURVEILLANCE REQUIREMENTS 12.4.1.B.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above Emits in accordancs with the methods and procedures of the ODCM.

12.4.1.B.2 The dose rai) due to iodine-131, iodine-133, tritium, and all radionucides in particulate form with half Eves greater than eight days, in accordance with the methodology and parameters of the ODCM by obtaining representative samples and performing analyses in accordance with samping and analysis program specified in Table 12.4.1-1.

O 12-27

LASALLE Revision 1.1 July 1994 TABLE 12.4.1-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS RELEASE TYPE SAMPLING MINIMUM TYPE OF LOWER LIMIT FREQUENCY ANALYSIS ACTIVITY OF FREQUENCY ANALYSIS DETECTION (LLD) (pCl/ml)*

l d

A. Contalment Vent P P Principal Gamma 1x10 and Purge System" Each Purge

Each Purge

Emitters' Grab Sample ,

B. Main Vent Stack M*' M* Principal Gamma 1x10*

Grab Sample Emitters' H-3 1x10' 1x104 C. Standby Gas D* W Principal Gamma Treatment System Grab Sample Emitters' 1 x10-*

Continuous' # l-131 1x1042 D. All Release Types as Charcoal listed in A and B Sample l above, at the Vent 1-131 1x10"'

Stack, and as listed 1x10-"

in C above, at the Continuous' # Principal Gamma l SBGTS whenever there Particulate Emitters' !

is flow. Sample (1-131, Others) l l

Continuous' M Gross Alpha 1x10-"

Composite Particulate Sample ,

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Composite j Particulate Sample 4

Continuous' Noble Gas Noble Gases 1x10 Monitor Gross Beta & (Xe-133 Gamma equivalent) 1 12-28

LASALLE Revision 1.1 July 1994 TABLE 12.4.1-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION l.

I l s. The LLD is the smallest concentration of radioactive material in a sample that win be detected l with 95% probabitty with 5% probebitty of falsely concludmp that a blank observation

{ represents a "real" signal.

For a particular measurement system (which mayinclude radiochemical separation):

l

( 4.66 s.

LLD = E . V . 2.22x10' . Y . exp (4.at)

Where:

LLD is the "a priori" lower Emit of detection as defined above (as microcurie por unit mass or volume),

l s, is the standard deviation of the back0round counting rate or of the counting rate of a l blank sample as appropriate (as counts per minute), j E is the counting efilciency (as counts per transformabon),

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

2.22x10'is the number of transformations per rninute per microcurie, Y is the fractional radiochornical yield (when appicable),

A is the radioactive decay constant for the pesticular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

The value of s, used in the calcul9 tion of the LLD for a detection system shaR be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E. V, Y, and at shall be used in the calculation.

b. Analyses shaN also be performed following shutdown, startup, or a THERMAL POWER chan0e exceeding 15% of the RATED THERMAL POWER within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period if there are several power transients that exceed 15% , the off gas sarnple may be delayed until after the last transient providied it is within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the first transient (See Technical Specification clarification 01/87 signed by Station Manager 3/23/87.)

c. Whenever there is flow through the SBGTS. (if SBGT is run more than 10 minutes in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period then it must be run a minimum of 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . The 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months run is required to meet the sample requirements for iodine and particulates.)

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i e i LASALLE Revision 1.1 l Juy 1994 , )

TABLE 12.4.1-1 (Continued) j RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION l

d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 l hours after changing or after removal from sampler. Samping shau also be performed at least nnce per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days folwwing each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and anayses completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the j corresponding LLD's 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 primary coolant has not increased more than a factor of 3; (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

e. Tritium grab samples shall be taken at least once per 7 days from the plant vent to determine tritium releases in the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool.

f. The ratio of the sample flow rate to the sampled stream flow rate shou be known for the time I 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. l 4

g. The principal gamma emitters for which the LLD specification applies include the following l radionucEdes: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Co-141 and Co-144 for particulate 4 emissions. This list does not mean that only these nucEdes are to be detected and reported. -

)

Other peaks which are measurable and identifiable, at the 95% confidence level, together with l the above nuclides, shall also be identified and reported. )

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h. The drywell tritium and noble gas sample results are vaEd for 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months from sample time if 1) i the drywell radioactivity monitors have not indicated an increase in airbome or gaseous radioactivity, RDd 2) the drywell equipment and floor drain sump pumps run times have not indicated an increase in leakage in the drywell since the sample was taken.

If there is any reason to suspect that gaseous radioactivity levels have changed in the drywell since the last sample (30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ), a new sample and analyses should be requested prior to starting a drywell purge to meet the intent of providing current analyses to reflect actual activity released to the environment.

If the drywellis numed in accordance with Technical Specification definitions, both noble gas and tritium analyses must be completed before the purge begins. If the drywellis simply vented in accordance with Technical Specification definitions, no sample is required before venting.

When SBGT equipment is started and shut down, ensure noble gas iodine and particulate samples are taken. (This is from Technical Specification Clarification 01/87 p.34 signed 3-23-87 by Station Manager)

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LASALLE Revision 1.1 :

July 1994 !

l GAhEOUS EFFLUENTS -

A '

DOSE - NOBLE GASES ,

OPERABluTY REQUIREMENTS t 12.4.2.A The air dose due to noble gases released in gaseous effluents, from each reactor unit, !

from the site shaN be Smited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation i and less than or equal to 10 mrad for beta radiation, and

b. During any calender year: Less than or equal to 10 mrad for gamma radiation i and less than or equal to 20 mrad for beta radiation. ,

APPUCABILITY: At aN times.

ACTION' I

a. With the calculated air dose from radioactive noble gases in gaseous affluents exceeding any of the above imits,in Eeu of any other report required by LaSalle Technical SpeciScotion 6.6.A, propero and submit to the Commission within 30 days, j pursuant to LaSalle Technical Specification 6.6.C, a Special Report which identines the l cause(s) for exceeding the Emit (s) and defines the corrective actions to be taken to :

reduce the releases, and the proposed corrective actions to be taken to assure that i subsequent releases will be in compEence with the above Emits. j l

SURVEILLANCE REQUIREMENTS 12.4.2.8 Dose Calculations - Cumulative dose contributions for the current calendar quarter and current calender year shall be determined in accordance with the ODCM at least once ;

per 31 days.

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LASALLE Revision 1.1 July 1994 GASEOUS EFFLUENTS DOSE -IODINE-131. IODINE-133. TRITIUM. AND RADIONUCLIDES IN PARTICULATE FORM OPERABILITY REQUIREMENTS 12.4.3.A The dose to a MEMBER OF THE PUBLIC from iodine-131, lodine-133, tritium, and au radionucEdes in particulate form with half-Eves greater than 8 days in gaseous effluents released, from each reactor unit, to areas 1st and beyond the SITE BOUNDARY shall be imited to the following:

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

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

APPLICABILITY: At all times.

ACTION *

a. With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionucides in particulate form with half Eyes greater than 8 days, in gaseous effluents exceeding any of the above imits, in Eeu of any other report required by Technical Specification 6.6.A, prepare and submit to the Commission within 30 days, pursuant to LaSalle Technical Specification 6.6.C. a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed correction actions to be taken to assure that subsequent releases will be in compliance with the above Emits.

SURVEILLANCE REQUIREMENTS 12.4.3.B Cumulative dose contributions for the current calendar quarter and current calendar year for lodine-131, lodine-133, tritium, and radionucEdes in particulate form with half Eves greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

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l LASALLE Revisi:n 1.1

, July 1994 ,

1 GASEOUS EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM OPERABluTY REQUIREMENTS 12.4.4.A The GASEOUS RADWASTE (OFF-GAS) TREATMENT S (STEM shall be in opersbon.

622UCABluTY: Whenever the main condenser air'ojector system is in operation.

ACTION-

a. With the GASEOUS RADWASTE (OFF-GAS) TREATMENT SYSTEM inoperable for ,

rnore than 7 days, in Eeu of any other report required by LaSalle Technical Specification 6.6.A, prepare and submit to the Corrmssion within 30 days, pursuant to LaSaNo Technical Specification 6.6.C, a Special Report which includes the following information.

1. Identification of the inoperable equipment or subsystems and the reason for inoperabitty.

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

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

1 SURVElLLANCE REQUIREMENTS 12.4.4.B The GASEOUS RADWASTE TREATMENT SYSTEM shall be verified to be in operation at least once per 7 days.

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LASALLE Revision 1.1 l July 1994 !

1 GASEOUS EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM OPERABILITY REQUIREMENTS 12.4.5.A The appropriato portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and be used to reduce radioactive materials in gaseous waste prior to their ditcharge when the projected doses due to gaseous effluent releases from each reactor unit, from the site, when averaged over 31 days, would exceed 0.3 mrem to any organ.

APPLICABILITY: At all times.

ACTION With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days, and w!th gaseous waste being discharged without treatment and in excess of the above Emits,in Eeu of any other report required by LaSalle Technical Specification 6.6.A, prepare and submit to the Commission within 30 days, pursuant to LaSalle Technical Specification 6.6.C, a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

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

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

I SURVEILLANCE REQUIREMENTS 12.4.5.B.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM.

12.4.5.B.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appropriate

, system has been utilized to process radioactive gaseous effluents during the previous 92 days.

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LASALLE . Revision 1.1 July 1994 GASEOUS EFFLUENTS VENTING OR PURGING OPERABILITY REQUIREMENTS 12.4.6.A VENTING or PURGING of the containment dryweg shall be through the Pdmary ,

Containment Vent and Purge System or the Standby Gas Treatment System.

APPLICABILITY: Whenever the drywell is vented or purged.

ACTION-

e. With the requirements of the above speci6 cation not satisAed, suspend all VENTING and PURGING of the drywell.

SURVEILLANCE REQUIREMENTS 12.4.6.B.1 The containment drywell shall be determined to be sligned for VENTING or PURGING ,

through the Pdmary Containment Vent and Purge System or the Standby Gas Treatment System within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months pdor to start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months dudng VENTING or PURGING of the dryweH.

12.4.6.B.2 Prior to use of the Purge System through the Standby Gas Treatment System in OPERATIONAL CONDITION 1,2 or 3 assure that:

a. Beth Standby Gas Treatment System trains are OPERABLE, and

b. Only one of the Standby Gas Treatment System trains is used for PURGING.

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LASALLE Revision 1.1 July 1994 ,

GASEOUS EFFLUENTS TOTAL DOSE OPERABILITY REQUIREMENTS 12.4.7.A The dose or dose commitment to any member of the p@lic, due to releases of radioactivity and radiation, from uranium fuel cycle sources shah be Emited to less than or equal to 25 mrem to the total body or ahy organ (except the thyroid, which shau be Emited to less or equal to 75 mrem) over 12 consecutive months.

APPLICABILITY: At au times.

ACTION With the calculated doses from the release of radioactive materials in Equid or gaseous affluents exceeding twice the Emits of Sections 12.3.2.A.a,12.3.2.A.b,12.4.2.A.a.

12.4.2.A.b,12.4.3.A.a or 12.4.3.A.b, in Eeu of any other report required by LaSalle Technical Specification 6.6.A, prepare and submit, pursuant to LaSalle Technical Specification 6.6.0, a Special Repo 1 to the Director, Nuclear Reactor Regulation, U.S.

Nuclear Regulatory Commission, Washington, D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the Emits of Section 12.4.7.A. This Special Report shau include an analysis which estimates the radiation exposure (dose) to a member of the pubEc from uranium fuel cycle sources (including all effluents pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dose (s) exceeds the Emits of Section 12.4.7.A, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shallinclude a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of K 190.11.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the Emits of 40 CFR 190, and does not apply in any way to the requirements for dose Emitation of 10 CFR Part 20, as addressed in other sections of this technical specification.

SURVElLLANCE REQUIREMENTS 12.4.7.B Dose Calculations - Cumulative dose contributions from Equid and gaseous effluents shall be deterrnined in accordance with Sections 12.3.2.B,12.4.2.B and 12.4.3.B, and in accordance with the ODCM.

O 12-36

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LASALLE Rension 1.1 ,

July 1994 i

GASEOUS EFFLUENTS GASEOUS EFFLUENTS BASES OPERABluTY REQUIREMENTS l

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12.4.1.C DOSE RATE This specif6 cation is provided to ensure that the dose at any time at the site boundary from gaseous effluents from a8 units on the site wiR be within the annual dose Emits of RETS for unrestricted areas. These Emits provide reasonable assurance that !

radioactive material discharged in gaseous effluents win not result in the exposure of an i individual in an unrestricted area, either within or outsde the site boundary exceeding the Emits specified in 10CFR20.1301. For individuals who may at times be within the ,

site boundary, the occupancy of the individual will be sufRciently low to compensets for ;

any increase in the atmosphenc diffusion factor above that for the site boundary. The specified release rate imits restrict, at aR times, the corresponding gamme and beta dcse rates above background to an individual at or beyond the site boundary to less than or equal to a dose rate of 500 mrom/ year to the total body or to less than or equal to a dose rate of 3000 mrom/ year to the sidn. These release rate Emits also restrict, at all times, the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to a dose rate of 1500 mrom/ year.

t Tnis specification apples to the release of radioachve effluents in gaseous effluents {

from all reactors at the site. For units within shared redweste treatment systems, the :

( gaseous effluents from the shared system are proportioned among the units sharing i that system. l 12.4.2.C DOSE - NOBLE GASES This specification is provided to implement the requirements of Sections 11.B, Ill.A and .

IV.A of Appendix 1,10 CFR Part 50. The Operabigty Requirements are the guides set forth in Section li.B of Appendix 1. The ACTION statements provde the required ;

operating flexibiity and at the same time implement the guides set forth in Sechon IV.A !

of Appendix 1 to assure that the releases of radioactive materialin gaseous effluents wlN i be kept "as low as is reasonat9y achievable." The Surveigence Requirements l implement the requirements in Section lil.A of Appendix I that conformance with the guides of Appendix l be shown by calculational procedures based on models and data l such that the ectual exposure of an individual through appropriate pathways is unikely i to be substantially underestimated. The dose calculations established in the ODCM for ;

calculating the doses due to the actual release rates of radioachve noble gases in gaseous ofnuents are consistent with the methodology provided in Regulatory Guide !

1.109, l 1

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LASALLE Revision 1.1 July 1994 ,

GASEOUS EFFLUENTS GASEOUS EFFLUENTS BASES OPERABILITY REQUIREMENTS l l

i DOSE RATE (Continued) l

" Calculation of Annual Doses to Man frord Routine Releases of Reactor Effluents for the Purpose of Evaluating CompEance with 10 CFR Part 50, Appendix 1, " 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 I, July 1977. The ODCM equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions.

12.4.3.C DOSE - IODINE-131. IODINE-133. TRITIUM. AND RADIONUCLIDES IN PARTICtJLATE FORM The specification is provided to implement the requirements of Sections ll.C lil.A and IV.A cf Appendix 1,10 CFR Part 50. The Operability Requirements are the guides set forth in Section ll.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix i to assure that the releases of radioactive materials in gaseous effluents w!!! be kept "as low as 's reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section lil.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures bssed on models and data, such that the actual exposure of an individual through appropriate pathways is unEkely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the mr* xiology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man frorc, Routine Releases of Reactor Effluents for the Purpose of Evaluating Comphance with 10 CFR Part 50, Appendix 1, " Revision 1, October 1977 and Regulatory Guide 1.111," Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Ught-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for radiolodines, radioactive materials in particulate form and radionucEdes other than noble gases are dependent on the existing radionucEde pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1)individualinhalation of airbome radionucEdes,2) deposition of radionucEdes onto green leafy vegetation with subsequent consumption by man,3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and

4) deposition on the ground with subsequent exposure of man.

12-38

r LASALLE Revision 1.1

, July 1994 RADIOACTIVE EFFLUENTS BASES 12.4.4.C and 12.4.5.C GASEOUS RADWASTE TREATMENT SYSTEM AND VENTILATION EXHAUST TREATMENT SYSTEM The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system win be s available for use whenever gaseous effluents require treatment prior to telease to the !

environment. The requirement that the appropriate portions of these systems be used, !

when rpeciAed, provides reasonable assurance that the releases of radioactive l materials in gaseous effluents win be kept *as low as is reasonaby achievable". This I speciAcation implements the requirements of 10 CFR Part 50.36a, General Design l Criterion 60 of Appendix A to 10 CFR Part 50, and the design objechvos given in l Section ll,0 of Appendix i to 10 CFR Part 50. The speci#ed Imits govemin0 the use of I appropriate portions of the systems were specified as a suitable fracten of the dose i desi0n objectives set forth in Sections 11.3 and 11.0 of Appendix 1,10 CFR Part 50, for !

Daseous ofnuents.

12.4.6.C VENTING OR PURGING This specification provides reasonable assurance that releases from dryweN purging ;

operations win not exceed the annual dose Emits of 10CFR20 for unrestricted areas. ;

12.4.7.C TOTAL DOSE This speciAcetion is provided to meet the dose Imitations of 40 CFR 190. The specification requires tne preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objectwo doses of Appendix 1. For sites containing up to 4 reactors, it is highly unEkely that the resultant dose to a member of the public wiX exceed the dose Emits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report wiX describe a course of action which should result in the Emitabon of dose to a member of the pubic for 12 consecutive months to within the 40 CFR 190 Emits. For the purpose of the Special Report, it may be assumed that the dose commitment to the member of the pubic from other uranium fuel evcle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle faciEties at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violabon of 40 CFR 190 have not already been corrected),in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulAus the requirements of 40 CFR 190 until NRC staff action is completed. An individus11s not considered a member of the pubic during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.

O 12-39

LASALL5 Revision 1.1 July 1994 ,

12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM OPERABILITY REQUIREMENTS 12.5.1.A The radiological environmental monitoring program shall be conducted as specified in Table 12.5.1-1.

APPLICABILITY: At all times ACTION

a. With the radiological environmental monitoring program not being conducted as specified in Table 12.5.1-1, in Eeu of any other report required by LaSalle Technical Specification 6.6.A, prepare and st@ nit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence,

b. With the level of radioactivity in an environmental samping medium exceeding the reporting levels in Table 12.5.1-2 when averaged over any calendar quarter, in Eeu of any other report required by LaSalle Technical Specification 6.6.C, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Special Report pursuant to LaSalle Technical Specification 6.9.1-13. When more than one of the radionucEdes in Table 12.5.1-2 are detected in the samping medium, this report shall be submitted if: -

concentration (1) + concentration (2) + ...t 1.0 Emit level (1) Emit level (2)

When rsdionucides other than those in Table 12.5.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individualis equal to or greater than the calendar year Emits of Sections 12.3.2.A.12.4.2.A and 12.4.3.A.

This report is not required if the measured level of radioactivity was not the result o1 plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 12.5.1 1, in Eeu of any other report required by LaSalle Technical Specification 6.6.A. prepare and submit to the Commission within 30 days, pursuant to LaSalle Technical Specification 6.6.C, a Special Report which 9

12-40

LASALLE Revision 1.1

, July 1994 i

, 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAjd '

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM OPERABILITY REQUIREMENTS (Cont'd) identifies the cause of the unavailabilty of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from those required by Table 12.5.1-1, provided thb locations from which the replacement samples were obtained are added to the radiological environmental monitoring program as replacement locations.

SURVEILLANCE REQUIREMENTS 12.5.1.8 The radiological environmental monitoring program samples shau be couected pursuant to Table 12.5.1 1 from the locations given in the table and figure in the ODCM and shall be analyzed pursuant to the requirement of Tables 12.5.1-1 and 12.5.1-3.

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LASALLE Revision 1.1 July 1994 TABLE 12.5.1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pathway and Samping and Type and Frequency and/or Sample Sample Locations

Collection Frecuency of Anahrsis

1. AIRBORNE Radiolodine and 5 Locations Continuous operation of Radioiodine canister.

Particulates sampler with sample col- Analyze at least once lection as required by per 7 days for I-131.

dust loading but at least once per 7 days. Particulate sampler.

Analyze for gross beta radioactivity > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change. Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the yearly mean of control samples Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.

2. DIRECT 38 Locations At least once per 31 days, Gamma dose. At least once.per 31 days RADIATION 2 2 dosimeters or 21 or at least once per 92 days. or Gamma dose. At least once per 92 days.

Instrument for continuously (Readout frequencies are measuring and recording determined by type of dose rate at each location. dosimeters selected.)

Sample locations are described in ODCM Chapter 11.

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LASALLE Revision 1.1 July 1994 '

TABLE 12.5.1-1 (Conhnued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Sarnples Exposure Pathway and Sarnping and Type and Frequency and/or Samole Samoso tocations* CoRechon Frequency of Analysis

3. WATERBORNE

a. Surface 2 Locabons Composite sample collected Gamma isotopic analysis of each wiWe -

over aperiod of s 31 days. sample at least once per 92 days.

b. Ground 5 locahons At least once per 92 days. Gamma isotopic and tritium analyses of each sample.

c. Sediment i locabon At least once per 184 days. Gamma isotopic analysis of each sample from ShoreEne 12-43

LASALLE Rewsion 1.1 July 1994 TABLE 12.5.1 1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pattnvey and Samping and Type and Frequency and/or Samole Samole Locations

Collecbon Frecuency of Analysis

4. INGESTION

a. Milk 3 Locations At least once per 15 days Gamma isotopic and 1-131 analysis of each when animals are on pasture. sample at least once per 31 days at other times.

b. Fish 2 locations One sample in season, or at Gamma isotopic analysis on edible portions.

least once per 184 days if l not seasonal e - - - .

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O LASALLE Revision 1.1 July 1994 TABLE 12.5.1-2 BEPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Water Airborne Particulate Fish Milk Food Products Analysis (pCill) or Gases (pCi/m') (pCi/Kg, wet) (pCi/I) (pCi/Kg, wet)

H-3 2x10*"

Mn-54 1x10' 3x10' 2

Fe-59 4x10 1x10' Co-58 1x10' 3x10' Co-60 3x102 1x10' Zn-65 3x102 2x10' Zr-Nb-95 4x102 1-131 2 0.9 3 1x102 Cs-134 30 10 1x10' 60 ,1x10' Cs-137 50 20 2x10' 70 2x10' Ba-La-140 2x102 3x102

For drinking water samples This is 40 CFR Part 141 Value.

1 12-45

LASALLE Revision 1.1 July 1994 TABLE 12.5.1-3 MAXIMUM VALUES FOR LOWER LIMITS OF DETECTION (LLD) ,

Water Airborne Particulate Fish Milk Food Products Sediment Analysis (PCIA) or Gases (pCim') (pCi/Kg, wet) (pCi/i) (pCl/Kg, wet) (pCi/kg, dry) gross beta +5 1 x0-2 1000 NA NA 2000 H-3 200 NA NA NA NA Mn-54 NA Fe-59 NA Co-58, 60 NA Zn45 NA Zr-95 NA Nb-95 NA l-131 NA 10x10 2 200 0.5 30 Cs-134 10 1x10 100 10 " ' "

1x10 2 Cs-137 10 100 10 Ba-140 NA La-140 NA Gamma isotopic analysis provides LLO of - 20 pCill per nucide.

~

Gamma isotopic analysis provides LLD of - 20 pCill per nucide.

12-46

i LASALLE Revision 1.1 July 1994 TABLE 12.5.1-2 (Continued)

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES TABLE NOTATION

a. The LLD is the smallest concentration of radioactive materialin a sample that win be detected ,

with 95% probabilty with 5% probabiaty of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 s.

LLD = E . V . 2.22. Y . exp (-Aat)

Where: ,

LLD is the "a pdori" lower 8mit of detection as defined above (as microcurie per unit mass or volume),

s, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per transformation),

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

2.22 is the number of transformations per minute per picrocurie, Y is the fractional radiochemical yield (when appicable),

A is the radioactive decay constant for the particular radionuclide and at is the elapsed time between sample collection (or end of the sample collection period and time of counting (for environment samples, not plant effluents).

The value of s used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionucEde determined by gamma ray spectrometry, the back0round shall include the typical contibutions of other radionuclides normally present in the samples (e.g.

potassium.40 in milk samples). Typical values of E, V, Y, and at shall be used in the calculation.

b. LLD for drinking water.

c. Other peaks which are measurable and identifiable, together with the radionuclides in Table 12.5.1-3, shall be identified and reported.

12-47 ,

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LASALLE Revision 1.1 4 July 1994 RADIOLOGICAL ENVIPONMENTAL MONITORING PROGRAM !

1 LAND USE CENSUS OPERABILITY REQUIREMENTS 12.5.2.A A land use census shall be conducted and shallidentify the location of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within e distance of five miles. (For elevated releases ;

as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use !

census shall also identify the locations of all milk animals in esch of the 16 !

meteorological sectors within a distance of three miles).

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APPLICABILITY: At all times j ACTION

a. With a land use census identifying a location (s) which yleids a calculated dose or dose commitment greater than the values currently being calculated in Section 12.4.3.B, in Eeu of any other report required by LaSalle Technical Specification 6.6.A, prepare and submit to the Commission within 30 days, pursuant to LaSalle Technical Specificadon 6.6.C., a Special Report which identifies the new locations.

b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance ,

with Section 12.5.1.A. In Eeu of any other report required by LaSalie Technical Specification 6.6.A, prepare and submit to the Commission within 30 days, pursuant to LaSalle Technical Specification 6.6.C., a Special Report which identifies the nsw location. The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control location, having the lowest calculated dose or dose commitment (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.

SURVEILI.ANCE REQUIREMENTS 12.5.2.B The land use census shall be conducted at least once per 12 months between the dates of (June 1 and October 1) using that information which wi!! provide l the best results, such as by a door-to-door survey, serial survey, or by ;

consulting local agriculture authorities. '

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LASALLE Revision 1.1 July 1994 O, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM INTERLABORATORY COMPARISON PROGRAM OPERABluTY REQUIREMENTS

12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission. .

APPLICABILITY: At all times l I

ACTION With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. )

I SURVEILLANCE REQUIREMENTS l

l 12.5.3.B A summary of the results obtained as part of the above required interlaboratory Comparison Program and in accordance with the ODCM (or participants in the EPA crosscheck program shall provide the EPA program O code designation of the unit) shall be included in the Annual Radiological Environmental Operating Report.

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12-49

LASALLE Revision 1.1 j July 1994 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM BASES 12.5.1.C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station !

operation. This monitoring program thereby supplements the radiological )

effluent monitoring program by verifying that the measurable concentrations of I radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeEng of the environmental e: posure pathways. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation, as defined in the ODCM.

The detection capabiities required by Table 12.5.1-3 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as a *a posteriori" (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. Occasionally background fluctuations, unavoidabty small sample sizes, the presence of interfering nuc5 des, or other uncontrollable circumstance may render these LLDs unachievable. In such cases, the ,

contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

12.5.2.C LAND USE CENSUS This specification is provided to ensure that changes in the use of unrestricted areas are ident! fed and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door survey, serial survey or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix l to 10 CFR Part 50.

12.5.3.C INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materialin environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

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12-50

LASALLE Revision 1.1

,.- July 1994 ;

12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radioloolcal Environmental Operatino Reoort*

a. Routine environmental radiological operating report covering the operation of the units during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year :

following initial criticalty.

{

b. The annual radiological environmental operating report shan include summaries, interpretations, and an analysis of trends of the results of the radiological environmental survelRance activities for the report period, including i a comparison with preoperational studies, as appropriate, operational controls, as appropriate, and previous environmental survelRance reports and an assessment of the observed impacts of the plant operation on the ,

environment. The reports shen also include the results of land use censuses '

required by Section 12.5.2.

The annual radiological environmental operating report shah include summartzed and tabulated results in the format of Regulatory Guide 4.8, ;

December 1975, of au radiological environmental samples taken during the :

report period. In the event ti;st some results are not available for inclusion l with the report, the report shaR be submitted noting and explaining the l reasons for the missing results. The missing data shaN 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; a map of au samping locations j keyed to a table giving distances and directions from the midpoint between i the reactors; and the results of Econsee participation in the Interleboratory Comparison Program, required by Section 12.5.3. >

The report shallinclude an annual summary of hourly meteorological dets !

collected over the previous year. This annual summary may be either in the j form of an hour-by-hour lising of wind speed, wind direction, and atmospheric ,

stabilty, and precipitation (if measured) on magnetic tape, or in the form of 1 joint frequency distributions of wind speed wind direction and atmosph

, , er ic stabilty. This same report shan include an assessment of the radiation dose due to the radioactive liquid and gaseous effluents released from the unit or ,

station during the previous calendar year. The assessment of radiation doses J shall be performed in accordance with the ODCM.

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

12-51 y --,y y-

I LASALLE Revision 1.1 July 1994 Annual Radioloalcal Environmental Operatina Report (Continued)

The report shall also include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for j the previous 12 consecutive months to show conformance with 40 CFR 190, i Environmental Radiation Protection Standards for Nuclear Power Operation. The ,

assesament of radiation doses shall be performed in accordance with the ODCM. i l

12.6.2 Radioactive Effluent Release Reoort8 .

a. Routine radioactive effluent release reports covering the operation o'the unit !

during the previous calendar year of operation shall t,o submitted according to l the Technical Specifications. The period of the first report shall begin with the l cate of initial criticality.

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b. The radioactive effluent release reports shallinclude a summary of the quantities of radioactive Equid and gaseous effluents and soEd waste released from the unit as outlined in Regulatory Guide 1.21, Nessuring, Evaluating and Reporting Radioactivity in SoEd Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear l Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

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. Semiannual Radioactive Effluent Release Reports are required until the frequency change i to annualis approved by the NRC in the LaSalle Technical Specifications. '

O 12-52 ,

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LASALLE Revision 1.1 July 1994 REPORTING REQUIREMENTS Radioactive Effluent Releas6 Report (Continued) i 1

The radioactive effluent release report shallinclude the following information for each type of !

soud waste shipped offsite during the report period: l

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

i

e. Type of container (e.g., LSA, Type A. Type B, Large Quantity), and

f. Soudification agent (e.g., cement, uros formaldehyde). )

i The radioactive effluent release reports shallinclude unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and Equid effluents on a quarterly basis.

The radioactive effluent release reports shallinclude any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

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LASALLE Revision 1.1 July 1994 4

REPORTING REQUIREMENTS 12.6.3 Offsite Dose Calculation Manual (ODCMP l 12.6.3.1 The ODCM shall be approved by the Commission prior to implementation.

12.6.3.2 Ucensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.5.B. This documentation shall contain:

l 1. Sufficient information to support the chan0e together with the appropriate analyses or evaluations justifying the changes (s); and

2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,106,40 CFR Part 190, 10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliabilty of effluent, dose, or setpoint calculations.

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

c. Shall be submitted to the Commission in the form of a

! complete, legible copy of the entire ODCM as a part of or ,

l concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by marldngs in the margin of the affected pages, clearly i indicating the area of the page that was changed, and shall l Indicate the date (e.0., month / year) the change was l Implemented.

12.6.4 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS 12.6.4.1 Ucense initiated major changes to the radioactive waste treatment systems (liquid and gaseous):

a. Shall be reported to the Commission in the Monthly Operating Report for the period in which the evaluation was reviewed by the Onsite Review and Investigative Function. The discussion of each change shall contain:

I

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; i

l

The OFFSITE DOSE CALCULATION MANUAL (ODCM)is common to LaSalle Unit 1 I and LaSalle Unit 2. i 12-54 1

LASALLE Revision 1.1 Juh 1994 REPORTING REQUIREMENTS l O 1 1

12.6.4 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT l SYSTEMS fCont'd)

2. Suflicient detailed information to totaly support the reason for the change without benefit or additional or supplernental information;

3. A detailed description of the equipment, components and processes !

invoked and the interfac: 9 with other plant systems; ,

4. An evaluation of the chan0e which shows the predicted releases of radioactive materials in liquid and gaseous effluents waste that differ from those previousy predicted in the Econse appication and -

amendments thereto;

5. An evaluation of the chan0e which shows the expected maximum ,

exposures to individualin the unrestricted area and to the general population that differ frcm those previoush estimated in the Econse i appication and amendments thereto i

6. A comparison of the predicted releases of radioactive materials, in ,

Equid and gaseous effluents, to the actual releases for the period to when the chan0es are to be made; t

7. An estimate of the exposure to plant operating personnel as a result '

of the change; and ,

8. Documentation of the fact that the chan0e was reviewou and found acceptable ty the Onsite Review and Investigative Function.

i

b. Shall become effective upon review and acceptance by the Onsite Review -

and Investigative Function.

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12-55

L.ASALLE Revision 1.1 July 1994 LASAllE ANNEX INDEX R&g,E REVISION E&gg REVISION APPENDIX F F4 1.1 F-43 1.1 F-il 1.1 F-44 1.1 F411 1.1 F-45 1.1 F-iv 1.1

F-46 1.1 F-1 1.1 F-47 1.1 F-2 1.1 F-3 1.1 F-4 1.1 F-5 1.1 F4 1.1 F-7 1.1 F-8 1.1 F-8 1.1 F-10 1.1 F-11 1.1 F-12 1.1 F-13 1.1 F-14 1.1 F-15 1.1 F-16 1.1 O F-17 F-18 1.1 1.1 F-19 1.1 l

F-20 1.1 F-21 1.1 F-22 1.1 4

F-23 1.1 F-24 1.1 FIS 1.1 F-26 1.1 F-27 1.1

~

F-28 1.1 F-29 1.1 1

F-30 1.1 F-31 1.1 F-32 1.1 F-33 1.1 F-34 1.1 F-35 1.1 F-36 1.1 F-37 1.1 F-38 1.1 F-39 1.1 F 40 1.1 F-41 1.1 F-42 1.1 F4

LASALLE Revision 1.1 July 1994 ,

APPENDlX F STAT 10N4PECIFIC DATA FOR I.ASALLE l UNITS 1 AND 2 TABLE OF CONTENTS

. P_8E .

F.1 INTRODUCTION p.y F.2 REFERENCES p.3 9

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Oj F4 -

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LASALLE R: vision 1.1

, July 1994 APPENDIX F UST OF TABLES NUMBER IIILE E6GE F-1 Aquabc Environment Dose Parameters F-2 l F-2 Station Characteristics F-?

F-3 Cettical Ranoes F.4 F-4

Average Wind Speeds F-5 F-5 X/Q and DlQ Maxima At or Beyond the Unrestricted Area Boundary F4 F-Se X/Q and D/Q Maxima At or Beyond the l

Restricted Area Boundary F-7 '

F4 D/Q st the Nearest Mitt Cow and Most Animal ,

Locations Within 5 Miles F4 l F-7 Maximum ONsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area i Boundary for Selected Nucildes F-9 F-7a Maximum ONsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area '

Boundary for Selected NucBdes F-24 F4 Parameters for Calculation of N-16 Skyshine Radiation from LaSale F-39 Supplemental Tables '

A Elevated Level Joint Frequency Distribution Table Summary - 375 Foot Elevation Data F-40

-Summary Table of Percent by Drection and Class

-Summary Table of Percent by Direction and Speed

. -Summary Table of Percent by Speed and Class B Mid Elevation Joint Frequency Distribution Table Summary - 200 Foot Elevation Data F-42 i

-Summary Table of Percent by Drechon and Class :

-Summary Table of Percent by Dirochon and Speed

-Summary Table of Percent by Speed and Class ;

C Ground Level Joint Frequency Distribution Table Summary - 33 Foot Elevation Data F-44

-Summary Table of Percent by Direction and Class

-Summary Table of Percent by Direction and Speed O. -Summary Table of Percent by Speed and Class F lii i

LASALLE Revision 1.1 July 1994 ,

APPENDEX F UST OF FIGURES NUMBER m PAGE F-1 Unrestdcted Are:e Boundary 74 F-2 Restdcted Area Boundary - F-47 O

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F-iv

LASALLE Revision 1.1

- July 1994 O APPENDIX F STATION-SPECIFIC DATA FOR LASAU.E UNITS 1 AND 2 F.1 INTRODUCTION This appendir contains data relevant to the LaSalle alte. Included is a figure showing the unrestricted area boundry and values of parameters used in offsite dose assessment.

F.2 REFERENCES

1. Sargent & Lundy, Analysis end Technology DMelon, LaSalle Calculation No. ATD-0164, I Revisions 0,1 and 2.

2. Sargent & Lundy, Nuclear Safe 0uards and Ucensin0 Division, LaSalle Calculation No. ATD-0139, H-16 Skyshine Ground Level Doses from LaSaue Turbine System & Piping, Revision 0.

3. Vert # cation of Environmental Parameter used for Commonwealth Edison Company's Offsite Dose Calculations, HUS Corporation,1988.

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F-1

LASALLE Revision 1.1 July 1994 ,

Table F-1 '

Aquatic Environment Dose Parameters GeneralInformation*

The station liquid discharge flows into the filinois River then into the Mississippi River.

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

Two downstream dams are on the llEnois River, Marseilles and Starved Rock. This information is based on Section 2.4.1.1 and Figures 2.4-2 and 2.4-6 of the LaSalle Environmental Report.

Water and Fish inoestion Parameters Pereir,eter* y.gjyg IN*,1/M' 1.0 F", cfs 1.85E4 F', cfs 1.31E4 t', hr' 24.0 t", hr' 97.0 Umits on RadioactMtv in Unorotected Outdoor Tanks' Outside Temporary Tank $ 10 Cf (per Technical Specification 3.11.)

This is based on information in LaSalle Environmental Report, Figure 3.3-1 and Section 2.1.4.2.1.

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

' t'(br) = 24 hr (all stations) for the fish ingestion pathway 8

t"(hr) = 97 hr (distance to nearest pubic potable water intake, Peoria, is 97 rniles; flow rate of 1 mph is assumed.3

See Section A.2.4 of Appendix A.

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

. O F-2

LASALLE Revision 1.1 July 1994 Tabin F-2 Station Charactedstics STATION: LaSaue LOCATION: 6 miles south of Marseilles,15nois - LaSalle County CHARACTERISTICS OF ELEVATED RELEASE POINT

l

1) Release Height = 112.8 m' -

2) Diometer = 5Atm

2) Exit Speed = 16Z.Jns4* 4) Heat Content = 0 KCais4*

CHARACTERISTICS OF VENT STACK RELEASE POINT: Not Appicable (NA)

1) Reloose Height = m 2) Diameter = m

3) Exit Speed msd

~

=

CHARACTERISTICS OF GROUND LEVEL RELEASE

1) Rakaos Height = 0 m

2) Building Factor (D) = 58.4 m' METEOROLOGICAL DATA A _(Q(LJt Toweris Located 300 m SSW of elevated release point l

Tower Data Used in Calculations Wind Speed and Differenhal Release Point DirW Temper =he Elevated 375 A 375-33 ft Vent (NA) (NA)

Gmund 33 ft 200-33 ft

'Used in calculating the meteorological and dose factors in Tables F-5, F 6, and F-7. See Sections B.3 through B.6 of Appendix B.

O.

F-3 i

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

LASALLE Revision 1.1 l July 1994 ,

Table F-3 Critical Ranges l I

1 l

Unrestricted Area Restricted Nearest Nearest Dairy Farm Boundary

Area Boundary Resident

Within 5 Miles' Direction (m) (m) ,

(m) (m)

N 1036 1036 6300 None NNE 1378 1378 2800 None NE 2408 1609 3400 None '

ENE 4450 1079 5300 None E 1996 1055 5200 None ESE 1465 1055 2300 None SE 969 969 2700 None SSE 838 698 2900 None S 829 820 2400 None SSW 835 835 1100 None SW 628 628 1600 None WSW 533 533 2400 None W 524 524 1300 None WNW 643 643 1400 Nona NW 762 762 2900 None NNW 890 890 2700 None Used in calculating the meteorological dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of Appendix B.

1993 annual survey by Telodyne isotopes lAidwest Laboratories. The distances are roundet b the nearest conservative 100 meters. l 1993 annual rnlich animal cer. sus, by Telodyne isotopes Midwest bboratories. Used in calculating the D/Q l values in Table F 6. The distances are rounded to the nearest conservative 100 meters. A default value of I l 8000 meters is used when there are no dairies within 5 miles.

O F-4 i l

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1

l LASALLE Revision 1.1 July 1994 Table F 4 Average Wind Speeds Downwind Avernae Wind Speed (m/sec)* ,

Direction Elevated ygg* Ground Level I N 9.7 -

7.7 4.9 NNE 10.1 8.0 5.1

)

NE 9.2 7.4 4.9

)

ENE 9.0 7.2 4.8 l l

E 9.5 7.8 5.2 ESE 9.7 8.4 5.9 SE 8.1 7.4 5.9 I SSE 7.4 6.7 5.0 l

S 6.7 5.9 4.3 .

SSW 5.6 3.7 2.9 SW 5.5 4.1 3.1 l

WSW 6.9 5.4 3.9 l W 7.6 6.5 4.5 WNW 7.5 6.3 4.3 NW 7.5 6.2 3.9 NNW 8.3 6.7 4.3

" Based on LaSalle site meteorolo9i cal data, January 1978 throu9h December 1987. Calculated in Reference 1 of Section F.2, using formulas in Section B.1.3 of Appendix 8.

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F-5

. LASALLE Revision 1.1 July 1994 Table F-5 X/Q and DlQ Maximo at or Beyond the Unrestricted Anna Boundary Doeewind Elevated (stock) Relesee Mlmed Nede(Vent) Release Groted Level Release Ofrectlen Redfue

~

X/e Redlue 0/0 Redlue N/9 D/e Redlus x/e 8/t (eeters) (sec/uF*3) toeters) (1/uP*2) (meterc) (sec/uP*3) (1/sF*2) (surters) (sec/uF*3) (1/uP*2) a 5433, 6.123E-09 1036. 7.20M-10 6000. 6.289E-09 8.311E-10 1036. 1.524E-06 1.019E 08 nee 1378. 7.045E-09 1378. 9.831E-10 5633. 7.102E-09 9.659E-10 1378. 9.737E-07 7.095E-09 WE 4400. 5.535E-09 2408. 4.245E-10 2408. 5.600E-09 4.836E 10 2408. 3.907E-07 2.37FE 09 ENE 5200. 5.086E-09 4450. 2.021E-10 4450. 4.909E-09 2.024E 10 4450. 1.496E-07 6.7%E-10 E 5200. 5.865E 09 1996. 5.415E-10 1996. 6.198E-09 6.396E-10 1996. 4.870E-07 2.980E-09 ESE 5200. 8.000E-09 1500. 8.896E-10 1465. 8.290E 09 1.229E 09 1465. 7.223E 07 3.880E-09 SE 5633. 7.116E 09 1500. 7.505E-10 969. 1.087E-08 1.709E 09 969. 1.137E-06 1.12M 08 stE 5200. 6.717E-09 1500. 7.176E-10 838. 1.31M-08 2.124E-09 838. 1.124E-06 1.064E-08 s 5633. 5.910E-09 1500. 6.136E-10 829. 8.402E-09 1.30M-09 829. 1.112E-06 1.039E-08 sw 6000. 5.269E-09 835. 5.793E-10 835. 7.322E-09 9.999E-10 835. 7.940E-07 5.359E-09 m 6000. 6.767E-09 628. 8.545E-10 628. 2.224E-08 2.154E-09 628. 1.864E-06 1.407E-06 Wsv 6000. 6.065E-09 533. 6.527E-10 540, 2.105E-08 2.079E-09 533. 2.101E 06 1.970E-08 v 6437. 5.354E-09 1500. 4.811E-10 540. 1.344E-08 1.629E-09 524. 2.830E-06 2.45M-08 WWW 7242. 3.916E 09 s500. 3.175E-10 643. 5.963E-09 9.071E-10 443. 2.429E-06 1.500E-08 W 7242. 3.766E-09 1500. 3.118E-10 5633. 4.127E 09 6.660E-10 762. 1.984E 06 1.055E-08 muu 6437. 4.240E-09 1500. 3.806E-10 6437. 4.095E-09 5.574E 10 890. 1.605E-1l68.840E09 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 Note: Based on Reference 2 of Section F.2 and the formules in Sections B.3 and B.4 of Appendix B.

Used for beta sir, beta skin, and inhalation dose pathways. See sections A.1.2, A.1.3 and A.1.4.2 of Appendix A.

Used for produce and leafy vegetable pathways. See A.1.4 of Appendix A.

, LASKLLE -

Revisio'61.1 i July 1994 Tatde F-Se XIQ and DfQ Maxima at or Beyond tie ResticSed Ame Soundary Deemwind Eteweted(Stecit) Reteese Rfmed Itode(Vent) Selease Oreista Level Release Olrectlen Redfus X/t Redfus Oft Redfus N/4 9/G Redfue X/S Oft (seters) (sec/uP*3) (seters) (1/uP*2) (seters) (sec/tP*3) (1/tP*2) (meters) (sec/se*3) (1/mP*2)

N 5633. 6.123E-09 1036. 7.203E-10 6000. 6.209E 09 0.311E-10 1836.

uuE 1370. 1.524E-06 1.019E-SE 7.045E-09 1378 9.031E-10 5633. 7.102E-09 9.659E-10 1378.

NE 4400. 5.535E-09 9.737E-07 7.095E-09 i 1609. 6.554E-10 1609. 6.052E-09 7.953E-10 1609 7.00M-07 4.74M-09 ENE 5200. 5.006E-09 1979. 6.376E-10 1079. 4.579E-09 9.061E-10 1979.

3 E 5200. 5.065E-09 1.120E-06 7.700E-09 i 1500. 6.659E-10 1955. 7.713-09 1.160E-09 1055. 1.270E-06 0.TFTE-09 '

! 5200.

' ESE 0.000E-09 1990 0.096E-10 1955. 9.901E-09 1.54GE-09 1955.

SE 5633. 7.11GE-09 1.192E-06 1.021E-08 1500. 7.505E-10 969. 1.007E-00 1.709E-09 969. 1.13M-06 1.12M 08 i ssE 5200. 6.71FE-09 690. 7.210E-10 490, 1.444E-OS 2.403E-09 698 5633. 1.492E-06 1.420E-00 S 5.910E 09

1500. 6.13GE-10 020. 0.455E-09 1.313-09 020. 1.130E-06 1.050E 08 ssW 6000. 5.269E-09 035. 5.793E-10 855. 7.322E 09 9.999E-10 035.

sw 6000. 4.767E-09 7.940E-07 5.359E-09 620. 0.545E 10 628. 2.224E-08 2.154E-09 620. 1.064E 06 1.40FE-08 Wew 6000. 6.065E 09 533. 4.527E-10 540. 2.185E-80 2.079E-09 533.

W M37. 5.354E-09 2.101E-06 1.970E-08 1500. 4.811E-10 540. 1.344E-00 1.629E-09 524 WNW 7242. 3.914E-09 2.030E-06 2.453E-08 1500. 3.175E-10 M3. 5.963E 09 9.071E-10 M3 2.429E-06 1.500E-08 NW 7242. 3.766E-09 1500 3.110E-10 5633. 4.127E 09 6.660E-10 762.

NEW M37. 4.240E-09 1.904E 06 1.055E OS !

1500 3.00$E-10 M37. 4.095E 09 5.574E 10 050 1.605E-06 0.040E 09 LASALLE SITE BETOOROLOBBCAL DATA 1/75 - 12/ST i

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F-7

. LASALLE Revision 1.1 July 1994 Table F 4 DfQ at the Nearest MR Cow and Meet Anhist Locations wthin 5 m5es Dowwind peerest Milk Ceu D/e(1/m**2) Neerset Meet Anteel D/e(1/m"2)

Directlen Redlue Eleveted Mfmed scound Redfue Elevated Mimed Grewal (meters) Reteese Reteese Reteeee (seters) Roteeee Estseee Reteese N 8000. 9.711E 11 1.006E-10 2.915E-10 6400 1.387E-10 1.A36E-10 4.352E-10 NNE 8000. 1.151E-10 1.178E-10 3.273E-10 3100. 4.257E 10 4.320E-10 1.760E-09 l

NE 8000, 8.839E-11 9.468E 11 2.851E-10. 5600. 1.530E-10 1.649E 10 5.403E-10 ENE 8000, 8.559E-11 8.420E-11 2.381E-10 5000. 1.739E-10 1.725E-10 5.519E-10 E 8000. 1.056E-10 9.772E-11 2.587E-10 8000. 1.056E-10 9.772E-112.587E-10 Est 8000. 1.450E-10 1.356E-10 3.010E-10 8000. 1.450E 10 1.356E-10 3.010E-10 SE 8000. 1.242E-10 1.322E-10 2.881E-10 7600. 1.354E 10 1.437E-10 3.160E-10 ssE 8000. 1.174E-101.278E 10 2.152E-19 7600. 1.279E-10 1.389E-10 2.360E-10 s 8000. 9.947E-11 9.895E-11 2.065E-10 8000. 9.947E-11 9.895E-11 2.065E-10 Ssv 8000, 8.647E-11 9.097E-11 1.077E-10 8000. 8.647E-11 9.097E-11 1.077E-10 sw 80w. 1.096E-10 1.210E-10 1.793E-10 8000. 1.096E-10 1.210E 10 1.793E-10 WsW 8000. 1.017E-10 1.083E 10 1.940E-10 2600. 4.092E-18 5.082E-10 1.417E-09 W 8000. 8.494E-11 1.094E-10 2.354E-10 4000. 1.80EE-10 2.362E-10 5.866E-10 WNW 8000. 5.824E-11 6.886E-11 1.994E-10 8000. 5.824E-11 4.886E-11 1.994E-10 s NW 8000. 5.436E-11 6.319E 11 1.828E-10 8000. 5.4360-11 6.319E-11 1.820E-10

.INW 7400. 7.317E-11 7.264E-11 2.269E-10 0000. 4.420E-11 4.387E-11 1.972E-10 LASALLE SITE SETEOROLOGICAL DATA 1/78 - 12/87 l

l l

Note: Based on Reference 2 of Section F.2 and the formules in Section B.4 of Appendix B.

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, LASMLLE RevisicIdl.1 July 1994 Tame F-7 Maxtnum Offste Finite Plume Gamme Dose Factors Based on 1 cm Depth at Wie Unrestricted Asea Boundary for Mr-43m Deeewind Unrestrfeted Elevated (Steet) Release Illmed Nede(Tent) Reteese Grownf Level Releone 01reetten Aree sewul medlue s sean mediue y staa medfue a emaa (enters) (eetere) tured/yr)/(utt/see) (meters) (ared/yr)/(uct/see) (meters) (ered/yr)/(uct/see)

N 1036. 1036. 4.787E-07 3.409E-07 1934. 5.281E-07 3.98N-0T 1036. 1.785E-04 1.344E-M NME 1370. 1378. 8.751E 07 6.599E-07 1378. 6.905E-07 5.206E-07 NE 2408, 1378. 1.139E-04 8.586E-05 2408. 6.471E-07 4.879E-07 2448. 4.497E-07 5.M9E-07 2408.

ENE 4450. 4450. 4.355E-05 3.284E-05 5.700E-07 4.29E-07 4450. 5.453E 07 4.262E 0T 4450. 1.444E 05 1.195E-05 E 1996. 1996. 4.487E-07 3.534E-07 1996. T.559E-07 5.700E-07 E5E 1996. 5.491E-05 4.140E-05 1465. 1465. 5.252E-07 3.960E-07 1445. 1.002E 06 T.559E-07 l 1465. 5.270E-05 6.236E-05 sE 969. 969. 3.545E-07 2.473E-07 969. 1.267E-06 9.554E-0T ssE 969. 1.333E 041.005E-M 838. 838. 3.05*E-0T 2.301E 07 838. 1.512E-06 1.140E-06 s 838. 1.323E-04 9.978E-05 829. 829. 2. MOE-07 2.141E 07 829. 1.MOE-06 T.M2E 07 829, seu 835, 835 1.330E-M 1.003E M 3.185E-07 2.401E-07 835. 1.071E-06 8.076E-07 835. 9.326E 05 T.032E-05 sW 628. 628. 3.1TFE-07 2.395E-07 628. 2.826E 06 2.131E 06 l

628. 2.305E-04 1.738E-04 :

WsW 533. 533. 2.617E-07 1.973E-07 533, 2.674E 06 2.017E 06 533, W 524. 524 2.327E-07 1.754E-07 2.56eE-04 1.936E-04 '

524. 1.458E-06 1.250E 06 524. 3.352E 04 2.527E-04 lan# M3. M3. 1.714E-07 1.292E-07 M3. 7.235E-07 5.455E 07 M3.

NW 762. 762. 1.744E 07 1.315E-07 2.724 OL 2.057E-04 762. 4.391E-07 3.311E-07 762. 2.219E-04 1.673E 04 NNW 890. 890. 2.397E 071.007E-07 890. 3.334E-07 2.514E*0T 890. 1.823E-041.374E 04 LASALLE SITE IETEOROLeetcAL DATA 1/78 - 12/ST l

l Note: Based on Reference 1 of Section F.2 and the formules in Sections B.S and B.6 of Appendix B.

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I F-9

_ _ _ . _ _ _ _ __. _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ . _ _ _ _ _ _ . _ _ - _ _ _ _ __ ___.. - __ - _ _ _ _ _ - _ _ _ _+-'_~-+4- -

_a'_ -

+ + _ _ _ _---e<- = _ - - - - -

. LASALLE Revision 1.1 July 1994 Taldo F-7 (Continued)

Maximum Offshe Firdle Phane Gamma Dose Factors Based on 1 cm Depth at the Urwestricted Area Boundary for Kr-85m .

Desemelnd unrestrfeted Elevated (Steet) Reteeee Mimed Mode (Vent) Reteeee Ground Level Reteeee Directlen Aree Sound Redlus 5 58AR Redfus V VSAR Redfus G OSAR (noters) (meters) (ared/yr)/(uCf/sec) (aeters) (ared/yr)/(uCl/sec) (seters) (ared/yr)/(uCf/sec)

N 1036. 1036. 5.74?E-05 5.560E-05 1036, 6.602E-05 6.388E*05 1036, 9.660E-04 9.252E 04 NME 1378. 1378. 5.063E-05 4.896E-05 1378. 5.514E-05 5.334E-05 1378. 6.776E-04 6.496E-04 NE 2408. 2408. 2.592E 05 2.506E 05 2408. 2.727E 05 2.636E-05 2408, 2.969E-04 2.M9E-04 ENE 4450. 4450. 1.351E-05 1.304E 05 4450. 1.332E-05 1.286E-05 4450. 1.156E-04 1.111E-04 E 1996, 1996. 2.7tLE 05 2.616E-05 1996. 2.863E 05 2.767E-05 1996. 3.557E-04 3.412E-04 ESE 1465. 1465. 4.351E-05 4.209E-05 1465. 4.624E 05 4.470E-05 1465. 5.201E-04 4.999f-04 SE 969. 969. 5.596E 05 5.415E 05 969, 6.610E 05 6.391E-05 969. 7.71r3E-M 7.470E-04 SSE 838. 838. 5.518E-05 5.339E-05 838. 6.430E-05 6.410E-05 838. 7.683E-04 7.364E-04 s 829. 829. 4.712E-05 4.560E-05 829. 5.330E-05 5.154E-05 829. 7.986E-04 7.657E-04 ssw R35. 835. 4.422E-05 4.279E-05 835. 5.351E-05 5.174E-05 835. 5.684E-04 5.450E-04 su 628. 628. 7.281E 05 7.046E-05 628, 9.952E 05 9.618E 05 628. 1.285E-03 1.231E-03 UsW 533. 533. 7.757E-05 7.50?E-05 533. 9.714E-05 9.388E-05 533, 1.389E-03 ,1.331E 03 W 524. 524. 7.601E-05 7.356E-05 524. 9.705E-05 9.385E 05 524. 1.687E-03 1.614E unu 643. 643. 5.286E-05 5.116E-05 643, 6.615E-05 6.399E-05 643. 1.327E-03 1.270E-03 NW 762. 762. 4.668E-05 4.518E 05 762. 5.688E-05 5.503E-05 762. 1.094E 03 1.047E-03 NNW 890. 890 4.683E-05 4.532E 05 890. 5.142E-05 4.976E 05 890. 9.282E-04 8.885E 04 LASALLE SITE SETEOROLOGICAL DATA 1/78 - 12/87

s . .

. LASALLE R; vision 1.1 July 1994 Table F-7 (Condnued)

Maximum OWaho Fbee Plume Gamm8 Dose Factors Based on 1 cm Depsi at Wie Unrestricted Area Boundary for Mr.45 ,

f s

Sommeind unrestrfeted Eteveted(steek) Reteese Nined Nede(vent) Reteese OreuulLevel Reteese Directlen Aree Bound Redfue S sear Radius V VSAR Redlue 8 ESAR (astere) (eetere) (ered/yr)/(ucl/see) (metere) (ered/yr)/(ucl/sec) (aetere) (ared/yr)/(ucl/sec)

N 15. 15. E.547E-07 8.285E-07 15. 9.859E-07 9.563E-07 1M. 1.054E 05 1.021E-05 ENE 1378. 1378. T.309E-07 7.068E-07 1378. 8.0TFE-07 T.811E-07 1378. T.474E-06 T.227E-06 NE 2408. 2408, 3.651E-07 3.530E 07 2408. 3.999E-07 3.788E 07 2408. 3.363E-06 3.252E-06 ENE 4450. 4450. 1.085E-07 1.823E-07 4450. 1.854E-07 1.795E-07 4450. 1.377E-061.332E 06 E 1996. 1996. 3.912E-07 3.782E-07 1996. 4.090E-07 3.961E 0T 1996. 4.000E-06 3.876E-06 EsE 1465. 1465. 4.359E-07 6.14M 07 1465. 6.632E-07 6.413E-07 1465. 5.783E 06 5.593E-06 sE 969. 969. 8.388E-07 8.110E-07 969. 9.583E-07 9.267E-07 969. 8.555E-06 8.273E-06 stE 838. 838. 8.350E-07 8.075E-07 838. 9.612E-07 9.294E-07 838. 8.432E-06 8.154E-06 ;

s 829. 829. 7.262E-07 7.023E-07 829. 8.067E-0T T.001E-07 829. 8.741E-06 8.453E-06 seu 835. 835. 4.857E-07 6.630E-07 835. 8.482E-0T 3.124E 07 835. 4.279E 06 6.063E-06 su 628. 628. 1.142E-06 1.104E-06 428. 1.4ME-06 1.444E-06 628. 1.401E-05 1.355E-05 WeW 533. 533. 1.211E-06 1.1TTE-06 533. 1.433E-06 1.388E 06 533. 1.510E 05 f.460E-05 t W 524. 524. 1.172E-06 1.134E-06 524. 1.443E-06 1.395E-06 524. 1.824E-05 1.763E-05 WuW 643. 443. 8.185E-07 7.915E-07 643. 1.000E 06 9.67EE-0T 643. 1.436E-05 1.389E-05 i NW 762. 762. 7.192E-07 6.954E-07 762. 8.694E 07 8.407E-07 762. 1.188E-05 1.148E-05 uuW 890. 890. T.128E-07 6.093E-07 890. 7.849E 07 7.590E-07 890. 1.011E-05 9.778E-06 t

LASALLE SITE E TEUROLeticAL DATA 1/78 - 12/8T F-11

_ _ _ _ _ _ _ __ _.__ - - _ . _ _ _ _ _ _ - - - _ _ _ _ m __ -_ _ m ---__v 'w -_ _ _ _ _ - _ _ _m-__a__ '_F' '-- ' _i _.__m --*-% -_ _ _

. LASALLE R; vision 1.1 July 1994 Table F-7 (Contbued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at tw Unrestricted Area Boundary for Kr-87 Dounulful Unrestrleted Elevated (Stock) Reteese Mixed Mode (Vent) Release Sre e d Levet Reteese ,

Ofrectlen Aree Somd Redlue S 38AR Redlue V VSAR Redlus G G8AR (meters) (seters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uct/sec) (meters) (erfd/yr)/(uct/sec)

N 1036. 106. 3.226E-04 3.135E-04 1936. 3.758E-04 3.652E-04 1036. 2.879E-03 2.795E-03 NNE 1378. 1378. 2.672E-04 2.597E-04 1378. 3.005E-04 2.920E-04 1378. 2.019E-03 1.960E-03 NE 2408. 2408, 1.28M-04 1.246E-04 2408. 1.359E 04 1.320E-04 2408. 8.605E-04 8.355E-04 ENE 4450. 4450. 5.904E-05 5.737E-05 4450. 5.859E 05 5.692E 05 4450. 3.133E-04 3.042E-M E 1996. 1996. 1.412E 04 1.372E-04 1996. 1.458E-04 1.417E-M 1996. 1.030E-03 9.998E-04 ESE 1465. 1465. 2.351E-04 2.284E-M 1465. 2.4268 04 2.357E-04 1465. 1.545E-03 1.500E-03 SE 969. 969. 3.211E-04 3.120E-04 969. 3.612E-04 3.510E-04 969. 2.355E-03 2.287E-03 SSE 838. 838. 3.254E 04 3.162E-M 838. 3.455E-04 3.552E-04 838. 2.329E-03 2.262E-03 3 829. 829. 2.850E-04 2.770E-04 829. 3.081E-M 2.994E-04 829, 2.431E-03 2.361E-03 SSW 835. 835. 2.742E-04 2.665E-04 835. 3.400E-M 3.305E-04 535. 1.706E-03 1.657E-03 SW 628. 628, 4.614E-04 4.484E-04 628. 5.936E-04 5.769E-04 628. 3.903E-03 3.790E-03 Wsv 533. 533. 4.880E 04 4.74M -04 533, 5.683E-04 5.523E-04 533. 4.251E-Of 4.128E-83 W 524. 524. 4.675E-04 4.54M -04 524. 5.708E-04 5.547E-04 524. 5.136E-03 4.986E-03 WWW 643. 643. 3.224E-04 3.133E-04 643. 3.914E-04 3.804E 04 643. 4.001E-03 3.884E-03 NW 762. 762. 2.823E-04 2.74M-04 762. 3.397E 04 3.301E 04 762. 3.276E 03 3.180E-03 NNW 890. 890. 2.747E 04 2.669E-04 890. 3.031E-04 2.945E 04 890. 2.763E-03 2.683E-03 LASALLE SITE IETEGROLOSICAL SATA 1/78 - 12/87

_ t

. LASALLE Revision 1.1 July 1994 Taldo F-7 (Condnued)

Maxbnum Offshe Finne Plume Gamme Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Mr-SS Dowulnd unrestricted Eievetedtstect) 8elease Nined modetvent) 8eteeee Breed Level Retenee Directlen Aree Sound Redfue S SOAR Redfue V VSAR Redfue 8 00AR (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uct/sec) (meters) tared /yr)/(uct/sec)

N 1936, 1036. 8.602E-04 8.374E-04 1036. 1.003E-03 9.769E-M 1936. 6.989E-03 6.787E-03 NME 1378. 1378. 7.111E 04 6.922E-04 1378. 7.989E-04 7.777E M 1379. 4.940E-03 4.790E-03 NE 2408. 2408. 3.435E-M 3.344E-04 2408. 3.694E-04 3.596E-M 2408. 2.182E 03 2.120E 03 EWE 4450. 4450. 1.648E-04 1.604E- M 4450. 1.646E-04 1.682E-04 4450. 8.502E-04 8.263E-04 E 1996. 1996. 3.781E-04 3.600E-04 1996. 3.920E-04 3.824E 04 1996. 2.599E-03 2.525E-03 ESE 1465. 145. 6.235E 04 4.070E-04 1465. 6.445E-M 6.273E-04 1465. 3.816E-03 3.707E-03 SE 969. 969. 8.537E-04 8.311E-04 969. 9.571E-04 9.317E-04 969. 5.712E-03 5.549E-03 SSE 838. 838. 8.671E-0'. 8.442E-04 838. 9.702E-04 9.445E-04 838. 5.645E-03 5.483E-03 5 829. 829. 7.696E-04 7.492E-04 829. 8.417E-04 8.194E-04 829, 5.862E-03 5.695E-03 tsW 835. 835. 7.427E 04 7.231E-04 835. 9.375E-04 9.127E-04 835. 4.167E-03 4.048E-03 su 628. 628. 1.246E 03 1.213E-03 628, 1.601E-03 1.559E-03 628. 9.396E-03 9.126E-03 WsW 533. 533. 1.314E 93 1.279E-03 533. 1.525E 03 1.485E-03 533. 1.017E-02 9.882E-03 W 524, 524. 1.249E 03 1.216E-03 524. 1.520E-03 1.480E*03 524. 1.225E-02 1.190E-02 WNW 643. 643. 8.669E-04 8.440E-04 643. 1.045E 03 1.017E 03 643. 9.595E-03 9.317E-03 NW 762. 762. 7.580E 04 7.379E-04 762. 9.125E-04 8.884E-04 762. 7.895E-03 7.666E-03 NNW 890. 890. 7.369F 04 7.174E-04 890. 8.141E-04 7.945E-04 890. 6.693E-03 6.500E-03 LASALLE SITE NETEOROLOGICAL DATA 1/78 - 12/8T i

t i

F-13 i

(

. LASALLE Revision 1.1 July 1994 TaWe F-7 (Condnue4 Maximum OWake Fhdhe Plume Gamme Dose Factors Based on 1 cm Depts at the Unmetricted Ame Boundsey for Mr 89 Denewind Unrestrfeted Elevetedtstock) Roteeee Rfmed Ned KVent) Release Brewed Levet Reteeee Direction Aree Bound Redfus 3 SOM Redfus V VSAR Redfus 8 GBAR (setere) (seters) (ared/yr)/(stf/sec) (metere) (ared/yr)/(tCf/sec) (seters) (cred/yr)/(uct/see)

N 1936. 1M. 3.904E-M 3.794E-M 10 3 . 4.258E-M 4.139E-M 1936. 2.051E-03 1.992E-93 NME 1375. 1378. 2.820E-M 2.741E M 1373. 2.900E-M 2.904E M 1375.

NE 2405. 2408.

1.151E-03 1.118E-83 8.306E-05 8.972E 05 2400. 7.483E-05 7.195E-05 2408. 2.060E M 2.001E-M ENE 4450. 4450. 1.57DE-05 1.526E-05 4450 1.15M 05 1.121E 05 4450, E 1996.

1.701E-05 1.653E-05 1996. 1.052E-M 1.823E-M 1996. 9.299E-05 9.037E-05 1996.

ESE 1465.

3.031E M 2.944E-M 1465. 2.365E-M 2.299E-M 1465. 2.240E-M 2.1TFE M 1465.

SE 969. 998 7.762E-04 7.540E-M 3.891E-M 3.732E-M 969. 4.18E-M 4.079E-M 969. 1.846E-03 1.793E-03 ssE 838. M. 4.100E-M 3.993E-M ESS. 4.365E-M 4.243E-M M.

5 829, 829. 1.831E-03 1.773E-03 t

3.400E-M 3.312E-M B29. 3.25M -M 3.1 M -M 829. 2.034E-03 1.976E-03 SSW 835. 835, 2.921E-04 2.839E-M 835. 2.779E- M 2.792E-M 835. 1.921E-03 9.916E-M su M. 628. 5.830E-M 5.667E M M. 6.600E-M .4.415E-M M. 3.274E-03 3.100E-03 W5W 533. 533, 6.91M-M 6.720E-M 533. 7.525E-M 7.314E M 533.

W 524. 524. 4.592E-05 4.460E-03 6.M1E-M 6.756E-M 524. 8.259E 06 S.02EE-M 524. 5.M7E-03 5.796E-03 WNW M3. M3. 4.295E-M 4.174E M M3. 5.147E-M 5.083E-M M3. 3.746E-03 3.638E-03 NW 762. 762. 3.500E-M 3.402E-M 762. 4.03M M 3.922E M 762.

NNW 890. 890. 2.561E+03 2.480E-03 3.301E- M 3.200E M 890. 3.41M M 3.319E-M 890. 1.966E-03 1.909E-03 LASALLE SITE IETsenatestCAL MTA 1/78 - 12/8T I

~

)

~ . .

' LA ulLE Revision 1.1 July 1994 Table F-7 (Condnue4 Maximum Offste Finho Plume Gamme Dose Factors Based on 1 cm DepWi at the Unmetricted Ame Boundefy for Mr-80 L

Desewind unrestrfeted Elevated (5tect) Reteese Rfned Nede(Vent) Release troimd Level Release Directlen Aree Beimd Redfue 5 SRAR Radius V VBAR Redfue S EBAR (meters) (meters) (aredryr)/(utf/sec) (meters) (ared/yr)/(utf/sec) (meters) (eradryr)/(uct/sec)

R 1936. 1036. 6.785E 05 6.588E-05 1936. 5.199E-05 5.M 7E 05 1936.

1378. S.203E-05 7.954E 05 NME 1370. 3.19M-05 3.107E-05 1378. 2.141E-05 2.090E-05 1378.

2408. 2400. 2.265E-05 2.196E-05 l NE 2.160E-06 2.E /E-06 MSS. 9.136E-07 8.88M-0T 2400. 5.870E-0T 5.695E 07 ENE 4450. 4450. 1.109E 071.078E-07 4450. 3.907E-00 3.792E-08 4450.

1996. 1.814E-OS 1.759E-08 E 1996. 4.713E-06 4.575E-06 1996. 2.562E-M 2.488E-06 1996.

Est 1465. 2.865E-06 2.779E-06 1465. 2.134E 05 2.072E 05 1465. 1.551E-05 1.50N-05 1465.

i SE 969. 969. 2.503E-05 2.427E-05 5.M3E 05 5.673E-05 969. 5.324E-05 5.16EE-05 969. 1.365E-04 1.324E-04 ssE M. E5S. 6.M3E 05 6.663E-05 858. 4.174E-05 5.993E-05 830.

5 829. 1.227E-04 1.190E-04 829. 5.057E 05 4.909E-05 829. 3.745E-05 3.635E-05 829.

Ssv 335, 835, 1.055E 041.023E M 3.062E-05 2.972E-05 835. 1.274E 051.237E-05 835. 1.E55E-05 1.779E-05 su 628. 628. 9.754E-05 9.470E-05 628. 4.538E-05 6.347E-05 625. 1.410E-04 1.368E-04 WsW 533. 533. 1.092E 04 1.E36E M 533. 1.525E-M 1.480E M 533.

W SM. 4.861E-04 4.713E-04 524. 2.165E-04 2.101E-M SM. 2.185E-04 2.121E M SM.

M3. 8.427E-Of S.170E 04 wuW M3. 1.018E-04 9.853E 05 M3. 1.000E M 9.757E-05 M3. 3.141E-04 3.045E M uw 762. 762. 6.634E-05 6.448E 05 762. 5.815E 05 5.M5E 05 762. 1.306E M 1.267E 04 uuW 890. 890. 5.725E-05 5.558E 05 890. 4.336E 05 4.209E 05 890. 8.819E-05 8.551E 05 LASALLE SITE IEMOROL0stcAL MT41/78 - 12/87

. F-15

, LASALLE RQvision 1.1 July 1994 Tatdo F-7 (Condnued)

Maximum Offsite Finite Phane Gamme Dose Factors Based on 1 cm Depth at 1ho Umestricted Ama Boundary for Xe-131m Downwind Unrestricted Eleveted(Stock) Retesee Nfmed Nede(Vent) Reteese 8 row d Level Reteeee ofrectlen Aree See d Redfue 3 SBAR Redfue V VSAR Redfus G GBAR (meters) (meters) (ared/yr)/(uCI/sec) (meters) (ared/yr)/(Wl/sec) (meters) (ared/yr)/(uCI/sec)

N 1036. 1036. 1.606E-06 1.473E-06 1036. 1.827E 06 1.679E 06 1036. 1.645E-04 1.283E-M WNE 1378. 1378. 1.778E-06 1.572E-06 1378. 1.726E 06 1.553E-06 1378. 1.072E-04 8.384E-05 NE 2408. 2408, 1.086E-06 9.376E-07 2408. 1.136E-06 9.826E-07 2408. 4.347E-05 3.412E-05 ENE 4450. 4450. 7.931E-07 6.617E 07 4450. 7.858E 07 6.550E-07 4450, 1.623E-05 1.279E-05 E 1996. 1996. 9.572E-07 8.457E-07 1996. 1.230E-06 1.058E-06 1996. 5.428E-05 4.253E-05 ESE 1465. 1465. 1.347E-06 1.215E-06 1465. 1.789E-06 1.546E-06 1465. 7.935E-05 6.215E 05 SE 969. 969. 1.472E-06 1.365E-06 969. 2.406E-06 2.115E-06 969. 1.240E-M 9.696E 05 SSE 836. 838. 1.415E-06 1.318E-06 838. 2.590E-06 2.260E-06 838. 1.228E-04 9.597E-05 3 829. 829. 1.231E-061.144E M 829. 1.966E-06 1.727E-06 829. 1.232E-04 9.639E-05 SSW 835. 835. 1.196E-06 1.103E 06 835, 2.003E 06 1.755E-06 835. 8.798E-05 6.885E-05 SW 628. 628. 1.802E-06 1.691E-06 628. 4.345E-06 3.720E-06 628. 2.109E-04 1.646E 04 WSW 533. 533. 1.859E-06 1.755E-06 533. 4.161E 06 3.577E-06 533. 2.324E-04 1.813E-06 W 524, 524. 1.800E-06 1.703E-06 524. 3.359E-06 2.972E-06 524 3.000E-04 2.335E M WNW 643. 643. 1.263E-06 1.194E-06 643. 1.976E 061.791E-06 643. 2.446E-04 1.902E-04 NW 762. 762. 1.135E-06 1.069E 06 762. 1.561E-06 1.437E-06 762. 2.005E-04 1.560E 04 NNW 890. 890. 1.191E-06 1.112E-06 890. 1.363E-06 1.263E 06 890. 1.664E-04 1.295E-04 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 e 5 e..

. LAdALLE Revision 1.1 July 1994 Table F-7 (Conehemed) ,

Maxknum ONelle Finite Plume Gamme Does Factors Besed on 1 cm Depth at #se Umesthend Asee L " ci for Xe-133m

Doeswfrul unrestrfeted Eleveted(StocR) Roteese Nined Nede(Vent) Reteeee Grourul Level Releone Direction Aree Sound Radius B ERAR Redfus V VOAR Redfus S eBAR (seters) (seters) (ared/yr)/(utt/sec) (meters) (ared/yr)/(ucl/sec) (meters) tured/yr)/(uct/sec) u 1936. 1036. 8.557E-06 8.199E-06 1856. 9.814i2 06 9.407E-06 1936. 2.822E-M 2.410E-M NME 1378. 1375. 7.917E 06 7.509E-06 1378. 8.400E-06 8.000E- M 1375. 1.901E-M 1.633E-M NE MOS. 2408. 4.244E-06 3.993E- M 2400. 4.482E- M 4.217E- M 2408. 8.032E-05 4.950E-05 ENE 4450. 4450. 2.480E-M 2.290E-06 4450. 2.450E 06 2.262E-06 4450, 3.100E-05 2.708E-05 E 19%. 1996. 4.M7E-06 4.020E-06 1996. 4.721E-06 4.433E-06 1996. 9.835E-05 8.482E-05 E9E 1465. 1465. 4.614E-06 6.309E-06 1465. 7.393E-06 4.970E-M 1465. 1.432E-M 1.234E-M SE 969. 969. S.229E-06 7.903E M 909. 1.039E-05 9.834E-96 969. 2.189E-M 1.979E-M set 838. 830. 8.070E- M T.750E-06 850. 1.060E-05 9.99W 06 SSR. 2.163E- M 1.A5dE- M S 829. 829. 6.932E-M 6.440E-06 829. 8.449E-06 7.995E- M 329. 2.201E-M 1.093E-M ssW 835. 835. 6.541E-06 6.27M -06 835. 8.500E-06 8.03dE-06 835. 1.574E-M 1.354E M SW 628. 628. 1.0593 05 1.020E 05 625. 1.437E-05 1.535E 05 628. 3.660E-M 3.140E M WsW 533. 533. 1.121E-05 1.081E-05 533. 1.580E-05 1.490E 05 533. 4.005E-M*3.423E-M V 5M. 5M. 1.09dE-05 1.054E-05 5M. 1.506E-05 1.42M-05 5M. 5.039E-M 4.28M-M WWW 643. 443. 7.648E-06 7.374E 06 643. 9.95dE-06 9.510E-06 643. 4.055E-M 3.441E-M up 762. 762. 6.774E-06 6.52dE 06 762. 8.435E-06 8.000E-06 762. 3.334E M 2.831E M uuW 890. 890. 6.055E 06 6.594E 06 890. 7.500E 06 7.28dE-06 890. 2.7ME-M 2.377E-M LAsALLE stTE NETEOROLogitAL SATA 1/75 - 12/87 f

, F-17

. LASALLE Revision 1.1 July 1994 Tatdo F-7 (Continued)

Maximum Offshe Finte Plume Gamme Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundery for Xe-133 Deunmind Imrostricted Elevated (stock) Release Mixed Nede(Vent) Reloose Oreisid Level Release DIroctlen Aree Sound Rodlus s star Redius V VSAR Redlue G 8BAR (meters) (seters) (ared/yr)/(LCl/sec) (meters) (ared/yr)/(uCl/sec) (meters) (ared/yr)/(uCl/sec)

N 1036. 1036. 7.010E-06 6.757E-06 1036. 7.933E 06 7.649E 06 1036. 3.136E-04 2.7BSE-04 NNE 1378. 1378. 6.939E-06 6.629E-06 1378. 7.149E-06 6.960E-06 1378. 2.132E-04 1.90M 04 NE 2408. 2408. 3.969E-06 3.767E 06 2408. 4.106E-06 3.897E-06 2408. 9.094E-05 8.164E-05 ENE 4450. 4450, 2.442E-06 2.206E 06 4450. 2.384E-06 2.229E 06 4450. 3.540E-05 3.193E-05 E 1996. 1996. 3.841E-06 3.671E-06 1996. 4.310E-06 4.08M-06 1996, 1.109E-04 9.929E 05 EsE 1465. 1465. 5.762E-06 5.534E-06 1465. 6.599E-06 6.277E-36 1465. 1.612E-04 1.44M-M SE 969. 969. 6.641E-06 6.416E-06 969. 8.978E-06 8.558E-06 969. 2.450E-M 2.185E-04 ssE 838. 338. 6.364E-06 6.153E 06 838. 9.231E 06 8.769E-06 838. 2.418E-04 2.156E-04 s 829. 829. 5.333E-06 5.152E 06 829. 4.962E-06 6.627E-06 829. 2.476E-04 2.212E-04 ssW 835. 835. 4.969E-06 4.793E 06 835. 6.590E-06 6.266E-06 835. 1.770E-M 1.582E-04 sW 628. 628. 7.790E-06 7.549E 06 628. 1.362E-05 1.285E-05 628. 4.090E-94 3.640E-06 Wsw 533. 533. 8.245E-06 7.992E-06 533. 1.326E-05 1.252E 05 533. 4.447E-0% 3.951E-06 W 524. 524. 8.166E 06 7.919E-06 524. 1.220E-05 1.164E-05 524. 5.551E-04 4.911E 06 WNW 643. 643. 5.715E-06 5.541E-06 643. 7.885E-06 7.574E 06 643. 4.444E-04 3.922E-04 NW 762. 762. 5.117E-06 4.958E 06 -762. 6.530E 06 6.30M -06 762. 3.661E-04 3.23M-04 uMW 890. 890. 5.340E-06 5.16M 06 890. 5.911E-06 5.700E-06 890. 3.000E-04 2.725E-04 LAsALLE stTE NETEOROLO8tCAL DATA 1/78 - 12/87 e 5 _ _ _ - - .__ _ _ _ _ -_ -

e..

LASl)LLE Revision 1.1 O'

July 1994 i

Table F-7 (Condnue4 Maximum Offde Finho Phane Gamme Dose Factors Based on 1 cm Depet at Wie Usuestricted Ame Boundsey for Xe-135m Dewuled Unrestricted Elevated (Stock) Roteese Nined Nede(vent) Reteese GreeufLevel Reteese Directlen Aree Bound Redfus S STAR Redfue V VSAA Redfus G MAR (meters) (arters) (ared/yr)/(uCl/sec) (meters) (ersultyr)/(uti/sec) (meters) (ared/yr)/(tCI/sec)

N 1036. 1036. 1.396E-M 1.349E-M 1936. 1.598E- M 1.54 M- M 1934. 1.531E-03 1.475E 03 i NME 1378. 1378. 1.151E-M 1.113E M 1378. 1.274E-M 1.232E-M 1378. 1.019E-03 9.821E-M -

NE 2408. 2408. 5.0TM-05 4.90M-05 2408. 5.129E-05 4.95EE-05 N08. 3.514E-M 3.390E-M !

ENE 4450. 4450. 1.919E-05 1.854E-05 4450. 1.778E-05 1.718E-05 4450. 8.758E-05 8.44M-05 E 1996, 1996. 5.672E-05 5.483E-05 1996. 5.675E-05 5.488E-05 1996. 4.329E M 4.172E-M ESE 1465. 1465. 1.005E- M 9.716E 05 1465. 1.0ME-M 9.902E-05 1465. 7.369E-M 7.103E M SE 969. 969. 1.309E-M 1.343E-M 969. 1.57M-M 1.522E-M 969. 1.262E-03 1.214E-03 SSE 838. 838. 1.402E-M 1.35dE M 838. 1.591E-M 1.53EE M 838. 1.254E-03 1.209E 03 3 829. 829. 1.183E-M 1.144E-M 829. 1.235E M 1.194E-M 829. 1.341E-03 1.292E-03 SSW 835. 835. 1.104E-M 1.088E-M 835. 1.260E M 1.218E-M 835. 8.762E M 8.444E- M SW 628. 628. 1.906E- M 1. M 1E- M 628. 2.444E-M 2.363E-M 628, 2.173E 03 2.096E-03 USW 533. 533. 2.063E-M 1.995E-M 533. 2.42M-M 2.345E-M 533, 2.479E-03 2.38SE-83 W SM. 524. 2.033E-M 1.966E-M 5M. 2.511E-M 2.427E M SM. 3.050E-05 2.937E-03 WNW M3. M3. 1.363E-M 1.318E-M M3. 1.68M-M 1.631E-M M3. 2.286E 03 2.201E 03 NW 762. 752. 1.18M-M 1.148E-04 ,752. 1.423E-04 1.376E-M 762. 1.006E 05 1.739E-83 NNW 890. 890. 1.141E-M 1.122E M 890. 1.259E-M 1.21M-M 890. 1.482E 03 1.42M 03 ,

t LASALLE SITE IETOMOLO8tCAL DATA 1/78 - 12/87 F-19

, LASALLE ROvision 1.1 July 1994 Table F-7 (Continued)

Maximum Offsite Fhdte Plume Gamme Dose Factors Based on 1 cm Depts at the Unrestricted Area Boundefy for Xe-135 BoesmindImrestrfeted Eleveted(Steek) Reteeee Mized Nede(Vent) Rolesee Growid Level Release afractlen Aree Bound Redius s star Redlue V VBAR Redlue G ORAR (aeters) (meters) (ared/yr)/(utt/sec) (seters) (ared/yr)/(uCl/sec) (aeters) (ared/yr)/(uCl/sec)

E 1036. 1936. 8.165E-05 7.902E-05 1036. 9.387E 05 9.085E 05 1036. 1.302E-03 1.25 M 03 NNE 1378. 1378. 7.171E-05 6.948E 05 1378. 7.821E-05 7.569E-05 1378. 9.17st-M 8.866E-M NE 2408. 2408. 3.669E-05 3.550E-05 2408. 3.876E-05 3.751E-05 2408. 4.075E-04 3.937E-06 ENE 4450. 4450. 1.920E 05 1.866E-05 4450. 1.899E-05 1.857E 05 4450. 1.625E 04 1.570E-04 E 1996, 1996. 3.038E 05 3.714E-05 1996. 4.056E-05 3.925E-05 1996. 4.869E-04 4.704E-04 ESE 145. 145. 6.171E-05 5.972E 05 145. 4.539E-05 6.320E-05 145. 7.073E-04 6.833E M sf 969. 969. 7.953E-05 7.697E-05 969. 9.346E-05 9.M4E 05 969. 1.052E-03 1.017E-03 ssE 838. 838. 7.3 0E-05 7.59M 05 838. 9.367E-05 9.064E 05 838. 1.037E-03 1.002E 03 s 829. 829. 6.719E-05 6.503E-05 829. 7.5871-05 7.342E 05 829. 1.078E-03 1.041E-03 seu 835. 835. 4.306E-05 6.103E-05 835. 7.636E 05 7.389E 05 855 7.699E-04 7.438E-M SW 628. 628. 1.039E-041.006E M 628. 1.409E-06 1.363E-M 628. 1.729E-03 1.670E 05 usW 533. 533. 1.106E 041.071E-M 533. 1.372E 041.328E-M 533 1.864E-0) 1.801E-03 W 524. 524. 1.082E-04 1.048E-04 524. 1.374E 04 1.329E-04 524. 2.256E-03 2.179E-03 l 643.

Wuw 643. 7.538E-05 7.296E-05 643. 9.395E 05 9.092E-05 643. 1.775E-03 1.713E-03 uW 762. 762. 6.654E 05 6.440E 05 762. 8.090E 05 7.830E-05 762. 1.466E-03 1.415E-03 l NuW 890. 890. 6.671E-05 6.456E-05 890. 7.327E-05 7.092E-05 890. 1.247E-03 1.206E-03 LA8ALLE sift IETEOROLoticAL 8ATA 1/78 - 12/87 l

l l

l i

l l

l h _ - - _ _ _ -

h -

. LAbhLLE Revisi(?d'1.1 July 1994 Table F-7 (Congnmed)

Maxtnum OWelle Finite Phame Gamme Dose Facters Based on 1 cm Depeh at See Unresedcted Asea Boundary for Xe-137 possimind Unrestricted Elevated (Steet) Release mined mode (Vent) Reteese traneul Levet telease Strectlen Aree Sened Redlue S 384R Redfue V VBAR Redfue 8 BAR l (meters) (meters) (ared/yr)/(uti/see) (meters) (ared/yr)/(ucl/see) (meters) (ared/yr)/(uct/sec) l l

u 1936. 1836. 4.750E-05 4.427E-05 1936. 5.242E-05 5.074E-05 1936. 3.400E-M 3.290E-M t uuE 1375. 1375. 3.585E-05 3.471E-95 1375. 3.814E 05 3.60EE-95 1375. 1.975E- M 1.911E M t

NE 2408, 2488. 1.153E 95 1.116E-85 2400. 1.95M-95 1.018E-85 2408. 3.979E-05 3.850E-05 Eut 4450. 4450. 2.512E-06 2.432E 06 4450. 1.953E-06 1.8 TIE-06 4450. 3.M9E-06 3.821E-06 l E 1996. 1996. 1.420E-05 1.374E-95 1996. 1.205E 95 1.244E 95 1996. 5.599E-05 5.418E 85 ESE 1465. 1465. 3.833E-05 2.936E-95 1465. 2.910E-85 2.825E 05 1465. 1.327E-M 1.204E-M i sE 909. 969. 4.743E-95 4.591E-85 969. 5.180E 05 5.923E-95 909. 2.99pE- M 2.092E M SSE E38. 838. 4.92AE-05 4.780E-95 838. 5.357E-05 5.14dE-95 838. 2.979E-M 2.874E M s 829. 329. 4.072E 05 3.942E-95 829. 3.975E-05 3.MM-05 829. 3.29EE M 3.191E-M ssW S35. 835. 3.521E-95 3.480E 95 535. 3.424E-95 3.315E-85 535. 1.748E-M 1.691E-M i sW M. M. 6.779E-85 6.543E 95 M. 7.938E-95 7.605E-95 M. 5.333E-M 5.141E M '

Wsu 533. 533. 7.919E-95 7.667E 95 533. S.829E-05 S.548E-95 533. 7.144E-M W 5M. 5M. 7.990E-05 7.730E 05 SM. 9.60EE-05 9.303E 85 SM. 9.223E M,4.932E-M 8.924E-M i Wuu M3. M3. 5.023E 05 4.863E-05 M3. 6.990E-05 5.89dE 05 M3. 6.002E M 5.000E M

NW 762. 762. 4.160E-85 4.02M-95 762. 4.M1E-05 4.687E 85 762. 4.220E-M 4.090E-M uuW 890. 990. 3.985E-05 3.55GE-95 Spe. 4.152E 05 4.820E-95 898. 3.279E-M 3.1T2E-M i

t LASALLE SITE IETEOROLeSICAL DAT41/75 - 12/87 i

i i

. F-21

. LASALLE Revision 1.1 July 1994 Tatde F-7 (Continued)

Maximum Offslie Finile Plume Gamme Dose Factors Based on 1 cm Depet at the Unrestricted Ases Boundary for Xe-138 Dewerind Imrostricted Elevated (stock) Release Mized Rode (Vent) Release Scound Level Rolesee Directlen Aree Sourul Redlue S 38AR Redfus V VBAR Radius 8 30AR (metere) (metere) (ared/yr)/(uti/sec) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uct/sec)

N 1036, 1036. 3.926E M 3.816E-M 1036. 4.523E-04 4.396E-M 1036. 3.178E-03 3.004E-05 NNE 1378. 1378. 3.160E 04 3.071E-M 1378. 3.536E 04 3.437E-04 1378. 2.117E-03 2.055E 03 NE 2408. 2408. 1.356E-04 1.318E-M 2408. 1.379E M 1.340E-M 2408. 7.244E-M 7.032E-M EWE 4450. 4450. 4.939E-05 4.799E-05 4450. 4.572E-05 4.443E-05 4450. 1.769E-M 1.718E-04 E 1996. 1996. 1.540E-04 1.497E-M 1996. 1.535E-04 1.492E-04 1996. 8.921E-04 8.659E-06 ESE 1465. 1465. 2.766E-04 2.689E-04 1465. 2.004E-04 2.725E-04 1465. 1.532E-03 1.487E-03 SE 969. 969. 3.938E-04 3.820E-04 969. 4.400E-04 4.285E 04 969. 2.641E-03 2.564E-03 SSE 838. 838. 4.037E-04 3.924E-04 838. 4.484E-04 4.358E- M 838. 2.620E-03 2.551E-03

$ 829. 829. 3.457E-04 3.340E-04 829. 3.540E-04 3.440E-04 829. 2.809E-03 2.727E 03 SsW 335. 835. 3.277E-04 3.186E 04 835. 3.832E-04 3.724E- M 835. 1.828E 03 1.774E-03 SW 628. 428. 5.698E 04 5.530E-04 628. 7.209E-04 7.007E-04 628. 4.546E-03 4.412E-03 WsW 533. 533. 4.144E-04 5.973E-M 533. 7.121E-04 6.921E- M 533. 5.206E-0) 5.053E-03 U 524. 524. 5.976E 04 5.809E-04 524. 7.318E-04 7.113E-M 524. 6.383E-03 6.195E-03 WNW 643. 643. 3.986E 04 3.875E-04 643. 4.887E 04 4.750E-04 643. 4.757E-03 4.616E 03 NW 762. 762. 3.457E-04 3.360E 04 762. 4.131E-04 4.016E-04 762. 3.746E-03 3.435E 03 NNW 890. 890. 3.330E-04 3.236E 04 890. 3.626E-04 3.525E-04 890. 3.069E-03 2.978E 03 LASALLE SITE IETECNCLO8icAL DATA 1/78 - 12/87

m ( - -

. LAbaLLE Revision 1.1 July 1994 Table F-7 (Conlinued)

Maximum Offslie Fbdle Plume Gamme Dose Factors Based on 1 cm Depeh at Wie Umesenceed Asee Boundary for Ar-41

. t DoeswIruf Unrestrfeted Etoveted(steek) Reteese Nined Mode (vent) Retenee crewuf Lowet Reteese Directlen Area Sewuf Redfue S SGAR Redfue V VBAR Redfue 8 GAAR (metere) (metere) tared /yr)/(uct/sec) (metere) (erad/yr)/(utt/see) (metere) (ared/yr)/(uct/see)

N 1936. 15. 4.746E-M 4.5ME-M 1936. 5.52EE-M 5.351E-M 1936. 4.55M-03 4.411E-03 NME 1378. 1373. 3.954E-M 3.82SE-M 1375. 4.439E- M 4.297E-M 1378. 3.203E-03 3.101E-03 NE 2408. 2488. 1.925E-M 1.863E M 2408. 2.MM-M 1.900E-M 2408. 1.38M 031.34M-03 ENE 4450. 4450. 9.141E-05 8.M 8E-05 4450. 9. M 1E-05 8.772E-05 4450. 5.219E- M 5.052E-M E 1996. 1996. 2.110E M 2.MM M 1996. 2.180E-M 2.110E-M 1996. 1.658E 03 1.605E-03 Est 1465. 1465. 3.480E-M 3.368E-M 1465. 3.593E- M 3.478E-M 1465. 2.459E-03 2.381E-83 SE 969. 969. 4.711E M 4.560E M 989. 5.320E-04 5.149E-M 969. 3.71M 03 3.59M-03 ssE 838. 338. 4. M1E-M 4.60N-M 838. 5.375E-M 5.200E-M E38, 3.671E-03 3.554E-03 s 829. 329. 4.140E-M 4.035E-M 829. 4.53M M 4.300E-M 829. 3.823E 03 3.701E-83 ssW 835. 335. 3.994E-M 3.066E M S35. 4.930E M 4.772E M E35. 2.700E-03 2.614E-03 SW 628. 628. 6.711E-M 4.496E-M 628. 8.591E- M 8.316E M 628. 6.139E-03 5.M3E-83 Wuu 533. 533. 7.009E-M 4.862E-M 533, 8.229E- M 7.966E 04 533. 6.M7E-05 4.45M-03 W 524. 524. 6.002E-M 6.5ME M 524. 8.291E- M 8.026E- M 524. 8.057E-03 7.799E 03 WWW M3. M3. 4.700E M 4.558E M M3. 5 716E M 5.53M-M M3. 6.300E-03 6.099E-03 NW M2. 762. 4.12M-M 3.9F1E M 762. 4.970E-M 4.811E-M 762. 5.173E-03 5.000E-05 NNW 890. 890. 4.025E-M 3.896E M 890. 4.447E M 4.305E M 890. 4.374E-03 4.234E-83 LARALLE SITE IETEEROLO8ttAI MTA 1/75 - 12/87

.F-23

- LASALLE Revision 1.1

. July 1994 Tatdo F-7s

. Maximum Offste Finto Plume Gamma Dose Fac5ers Based on 1 cm Depth at the RestdcGod Area Boundary for Kr43m Doeewirul Restricted Elevated (Stock) Reteeee Nined Nede(Vent) Release trouruf Level Reteeee Directlen Aree Sound Redlue S SBAR Redlus V VBAR Redlue 8 sear (meters) (meters) tared /yr)/(uct/sec) (meters) (ared/yr)/(ucl/sec) (meters) (ared/yr)/(uct/sec) a 1936. 1936. 4.787E-07 3.609E-07 1936. 5.281E-07 3.982E-07 1036. 1.785E-M 1.344E-04 NME 1378. 1378. 8.751E-07 6.599E-07 1378. 6.905E 07 5.206E-07 1378. 1.139E-04 8.586E-05 NE 1609. 1609. 6.873E-07 5.182E-07 1609. 7.291E-07 5.49M 07 1609. 8.106E-05 6.112E-05 ENE 1079. 1979. 4.160E-07 3.137E-07 1079. 8.010E-07 6.039E-07 1979. 1.322E-04 9.967E-05 E 1055. 1055. 3.476E-07 2.621E 07 1055. 9.181E 07 4.9tM 07 1055. 1.483E-041.118E M ESE 1055. 1955. 4.371E-07 3.296E-07 1955. 1.175E-06 8.85M-07 1055. 1.394E-04 1.051E-04 st 969. 969. 3.545E-07 2.673E 07 969. 1.267E-06 9.554E 07 969. 1.33M-04 1.005E-04 SSE 698. 698. 2.415E-07 1.821E-07 698. 1.644E-06 1.241E-06 496. 1.TT3E-04 1.337E-M S 820. 820. 2.803E-07 2.114E-07 820. 1.047E-06 7.895E-07 820. 1.354E 041.021E-M SW 835. 835. 3.185E-07 2.401E-07 835. 1.071E-06 8.076E-07 835. 9.326E-05 7.032E-05 W 628. 628. 3.1TFE-07 2.395E-07 628. 2.826E-06 2.131E-06 428. 2.305E-04 1.730E-M UsW 533. 533. 2.617E-07 1.973E-07 533. 2.674E-06 2.017E 06 533. 2.568E-04 1.936E 04 W 524. 524. 2.327E-07 1.754E-07 524 1.658E-06 1.250E-06 524. 3.352E-04 2.527E 04 WW 643. 643. 1.714E-07 1.292E 07 643. 7.235E-07 5.455E-07 643. 2.720E-04 2.057E-06 W 762. 762. 1.744E-07 1.315E-07 762. 4.391E 07 3.311E-07 762. 2.219E-04 1.673E-04 uuW 890. 890. 2.397E-07 1.007E-07 890. 3.334E-07 2.514E 07 890. 1.82M-041.374E 04 LASALLE SITE NETEOROLDEICAL 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 Appendht B.

O,

. LASALLE Revision 1.1 July 1994 Tatdo F-7a (Condnued) blaximum OWsite Finto Plume Gamme Dose Factors Bened on 1 cm Depts at Wie Restricted Aves Boundsey for Ki45m J

Dewerind teatricted Eleveted(Steelt) Reteeee R1aed Rede(Vent) Release Gre e d Level Retesee Directlen Aree Dewei Redlue S sear Redlue V VBAR Redfue a essa (noters) (eeters) (ared/yr)/( d t/sec) (meters) taredryr)/(uct/see) (asters) (ared/yr)/tutt/sec)

N 1936. 1936. 5.74M-85 5.568E-95 1836. 6.602E-95 6.30E-05 mut 1375.

1836. 9.660E-M 9.25M-M 1375. 5.063E-05 4.598E-05 1373. 5.514E 05 5.334E 85 1375. 6.776:-M 6.49dE M WE 1609. 1609, 3.632E-95 3.512E-95 1609. 3.MM 95 3.720E-85 1609 5.003E-M 4. NEE 04 ENE 10M. 10M. 4.315E-05 4.174E-95 10M. 4.569E-95 4.419E-05 10M. 77.e45E-M 7.03M-M E 1955. 1955. 4.572E 05 4.424E-05 1955. 5.05M-85 4.aBGE-95 1955 Est 8.134E M 7.792E-M 1955. 1955. 5.730E 85 5.544E 05 1955. 6.290E-95 6. WISE-05 1055.

SE 969. 989 S.820E-M 7.4SM M 1.390E-95 5.415E-95 999. 6.610E 05 6.391E-05 999. 7.793E M 7.479E-M stE 698. 498. 6.471E-95 6.263E-05 688. 7.905E 85 7.M3E 85 698.

R20.

9.515E-M 9.404E M S 828. 4.756E-05 4.683E-05 820. 5.3ast-95 5.2em-85 829. 8.103E-M 7.799E-M Saw S35. 835. 4.422E-95 4.279E-85 835. 5.351E 05 5.174E-05 535 5.604E-M 5.450E-M SW 628. 625. 7.231E-85 T.846E-85 628. 9.952E-95 9.61M-85 628. 1.285E-OI 1.231E-55 Wsu 533. 533. 7.75M-95 7.50M-95 533. 9.714E-85 9.3EEE 05 535. 1.309E-53 1.331E-85 W SM. 524. 7.601E-95 7.356E-85 524. 9.795E 95 9.3ESE-05 SM. 1.687E 03 1.614E 05 WuW M3. M3. 5.200E 85 5.116E 05 M3. 6.615E 05 6.399E 05 M3. 1.327E-03 S.278E-85 Inf 762. 762. 4.66dE-85 4.518E-95 762. 5.60EE-95 5.503E-05 762. 1.094E 05 1.047E-03 NuW 890. SFO. 4.6E3E-95 4.532E-05 890. 5.142E-05 4.fME-95 Spe. 9.2BIE-04 8.835E 04 LASALLE SITE IET95BOLOBicAL DATA 1/78 - 12/87 l

t

- F-25

. LASALLE Revision 1.1 July 1994 Tatdo F-7a (Condnued)

Maximum Offste Finite Plume Gamme Dose Factots Based on 1 cm Depth at the Resticted Ama Boundely for Kr45 Downsind Reettleted Elevated (Stock) Reteese Nimed Rede(Vent) Reteese Brewul Level Reteese Olrectlen Aree Setsid Redlue S SSAR Redlue V VSAR Redius 8 COAR (meters) (meters) (ared/yr)/(ucl/sec) (meters) (ered/yr)/(uCf/sec) (meters) (ared/yr)/(uct/sec)

N 1036. 1036. 8.547E 07 8.265E-07 1036. 9.889E-07 9.563E-07 1036. 1.056E-05 1.021E-05 NNE 1378. 1378. 7.309E-07 7.068E 07 1378. 8.077E-07 7.811E-07 1378. 7.474E-06 7.227E-06 NE 1609. 1609. 5.225E 07 5.052E-07 1609. 5.615E-07 5.430E 07 1609. 5.559E-06 5.375E-06 l

ENE 1079. 1079. 6.463E-07 6.249E 07 1079. 6.707E-07 6.486E-07. 1979. 8.057E-06 7.791E-06 E 1055. 1055. 6.819E-07 6.594E 07 1055. 7.385E-07 7.142E-07 *055. 8.92X-06 8.628E 06 ESE 1055. 1055. 8.484E-07 8.204E-07 1055. 9.108E-07 8.800E-07 1055. 8.800E-06 8.517E-06 SE 969. 969. 8.386E 07 8.110E-07 969. 9.58)E-07 9.267E-07 969. 8.555E-06 8.273E 06 i

sst 698. 698. 9.869E-07 9.54M-07 698. 1.15M-06 1.115E 06 698. 1.072E-05 1.036E-05 I

S 820. 820. 7.33M 07 7.091E 07 820. 8.154E-07 7.885E-07 820. 8.866E-06 8.574E 06 SSW 835. 835. 6.857E-07 6.630E 07 835. 8.402E-07 8.124E-07 835. 6.270E-06 6.063E-06 SU 628. 628. 1.142E 06 1.104E-06 628. 1.494E-06 1.444E-06 628. 1.401E-05 1.355E-05 Wsu 533. 533. 1.211E 06 1.171E-06 533. 1.43M 06 1.386E-06 533. 1.510E-05 1,460E-05 u 524. 524. 1.172E-06 1.134E-06 524. 1.44M -G6 1.395E-06 524. 1.824E-05 1.763E-05 WNW 643. 643.' 8.185E-07 7.915E-07 643. 1.000E-06 9.670E-07 643. 1.436E-05 1.389E-05 NW 762. 762. 7.192E-07 6.954E-07 762. 8.694E 07 8.407E-07 762. 1.188E-05 1.148E-05 NNW 890. 890. 7.120E-07 6.893E 07 890. 7.849E 07 7.590E-07 890. 1.011E 05 9.778E-06 LASALLE SITE ETEOROLO4tCAL DATA 1/78 - 12/87 i

(

. LAbALLE O.

Revision 1.1 '

. July 1994 Tatdo F-7a (Condnued)

Maximum Offste Finte Phone Gamme Dose Factors Based on 1 cm Depts at See Resedcted Aree Boundary for Kr47 I

pauratind meetricted Eteveted(Steet) Releone Rised leado(Vent) Reteese tro m d Levet Reteese Streetlen Aree Beed Redfue S 3BAR Redfue V VBAE Redlue 5 MAR (meters) (setere) (ared/yr)/(ist/see) (metore) (aredryr)/(act/see) (aetors) tared /yr)/( dI/sec)

N 1936. 1934. 3.22GE-M 3.13M-M 1034. 3.750E-M 3.452E-M 1934. 2.879E-83 2.MM 03 uuE 1378. 1378. 2.672E- M 2.597E- M 1375. 3.005E-M 2.9E9E-M 1375. 2.919E-03 1.980E-83 NE 1609. 1609. 1.900E-M 1.5M M 1889. 2.830E-M 1.981E-M 1409. 1.480E 83 1.43FE-53 EnE 1979. 10M. 2.430E M 2.361E-M 10M. 2.534E-M 2.462E-M 19M. 2.192E 03 2.129E-03 E 1955. 1955. 2.401E-M 2.52EE-M 1955. 2.705E-M 2.798E-M 1955. 2.423E-03 2.35M-03 E9E 1955. 1955. 3.217E M 3.125E-M 1955. 3.41M-M 3.315E-M 1955. 2.487E E! 2.337E-93 SE 969. 969. 3.211E- M 3.120E-M 969. 3.412E-M 3.510E-M 969. 2.355E-03 2.2SM-93 SSE 698. 698. 3.305E-M 3.776E-M 498. 4.423E M 4.290E-M 490. 2.905E-83 2.050E-03 5 820. 320. 2.881E-M 2.800E-M S20. 3.11M-M 3.829E-M 320. 2.46M-93 2.396E 83 SSW S35. E55. 2.742E-M 2.ae5E-M E55. 3.400E-M 3.305E-M 835. 1.706E-03 1.657E-93 su m. M. 4.614E-M 4.484E M M. 5.93M-M 5.799E M M. 3.903E-83 3.MOE-93 Wsu 533. 533. 4.BBOE-M 4.MM M $33. 5.483E-M 5.523E-M 533. 4.251E-03 4.12EE 93 W 524. SM. 4.67M-M 4.54M M 524. 5.700E-M 5.547E-M 524. 5.134E-83 4.9edE-93 Wuw M3. M3. 3.224E-M 3.133E-M M3. 3.914E-M 3.804E-M H3. 4.001E-03 3.OB4E 03 Inf 762. 762. 2.823E-M 2.MM-M M2. 3.39M M 3.301E-M 762. 3.27EE-05 3.180E-03 NuW 990. 390. 2.747E-M 2.669E M 890. 3.031E-M 2.MM-M 890. 2.763E-03 2.455E-03 LASALLE SITE IETEUROLOGICAL MTA 1/75 < 12/87 l

l l

l

- F-27

LASALLE Revision 1.1 July 1994 Taide F-7a (Continued)

Maximum Offsite Finite Plume Gamme Dose Factors Based on 1 cm Depth at the Reserkted Area Boundery for Kr.48 i

l l Doeewiruf Reetrfeted Elevated (Stock) Retesse Mixed Nede(Vent) Reteeee $ro m d Level Rotence Directlen Aree Som d Redlue S SOAR Redlus V VSAR Redius G SOAR (seters) (meters) (ared/yr)/(uCI/sec) (meters) (aradryr)/(uCl/sec) (meters) (ared/yr)/(tCf/sec) u 1036. 1036. 8.602E M 8.374E M 1936. 1.003E-03 9.769E- M 1036. 6.988E-03 6.787E-03 WWE 1378. 1378. 7.111E-04 6.922E-M 1378. 7.989E M 7.7TM- M 1378. 4.940E-03 4.798E-03 NE 1609. 1609. 5.C67E-M 4.932E-M 1609 5.485E-04 5.340E-04 1609. 3.656E-03 3.552E-03 ENE 1079. 1079. 6.520E-04 6.355E-04 1079 6.769E 04 6.589E-04 1079. 5.337E-03 5.184E-03 E 1055. 1055. 6.915E-04 6.732E-04 1955, 7.419E- M 7.222E-04 1955. 5.907E-03 5.73 M-03 Est 1055. 1055. 8.514E 04 8.288E-04 1055. 9.630E-04 8.790E-04 1055. 5.857E 03 5.689E-03 st 969. 969. 8.537E-04 8.311E-04 969 9.571E-04 9.317E-04 969. 5.712E-03 5.549E 03 SSE 698. 698. 1.854E-03 1.007E-83 698. 1.172E 83 1.141E-03 698. 7.19M-03 6.986E-03 s 820. 820. 7.77M-04 7.571E-84 820 8.51M 04 8.287E-04 820. 5.947E-03 5.777E 03 SW 835. 835. 7.427E 04 7.231E-04 835. 9.375E-04 9.127E-04 835. 4.167E 03 4.048E-03 su 628. 628. 1.246E 03 1.21M 03 628. 1.601E-03 1.559E-G3 628. 9.396E-03 9.126E-03 Wsv 533. 533. 1.314E 03 1.279E-03 533. 1.525E-03 1.485E-03 533. 1.017E-02 9.882E-03 W 524. 524 1.249E-03 1.216E-03 524 1.520E 03 1.480E-03 524. 1.225E 02 1.190E-02 WNW 643. 643. 8.669E-04 8.440E-04 643. 1.045E-03 1.017E-03 643. 9.595E-03 9.317E 03 uw 762. 762. 7.580E-04 7.379E-04 762. 9.125E-04 8.884E 04 762. 7.895E-03 7.666E-03 NNW 890. 890. 7.369E-04 7.174E 04 890 8.161E-04 7.945E-04 890. 6.69M-03 6.500E-03 LASALLE SITE NETECAoLOGICAL DATA 1/78 - 12/87 l

s . .

' LAbnLLE Revision 1.1 July 1994 Tatdo F-7a (Conlinued)

Mantnum Offste Finto Plume Gamma Dose Factors Based on 1 can DepIh at #se Restricted Aeos Boundary for Mr-49 I

powwiral Restricted Elevated (steek) Retenee Nined Mode (vent) Reteese Grownf Levet Reteeee Blrectlen Ares Bewuf Rodius s SSAR Redfue V VBAR Redfue B OSAR (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(df/see) (meters) (ared/yr)/(df/sec) !

u 1936. 1936. 3.904E-M 3.794E-M 1036. 4.258E-M 4.139E M 1936. 2.051E-03 1.992E 03 uuE 1375. 1375. 2.820E-M 2.741E-M 1375. 2.988E-M 2.904E M 1378. 1.151E-03 1.118E-83 NE 1409. 1409. 1.750E-M 1.701E-M 1409 1.454E-M 1.407E-M 1609. 6.544E M 6.375E-M Est 1079. 1079. 2.703E M 2.628E-M 1979. 2.619E-M 2.545E-M 1979 1.450E-03 1.409E-03 E 1955. 1955. 3.M1E-M 2.954E-M 1955. 2.972E-M 2.888E-M 1355. 1.549E-03 1.524E-03 Ett 1055. 1955. 3.931E-M 3.821E M 1955. 3.909E-M 3.000E-M 1953. 1.682E-03 1.633E-83 SE 969. 969. 3.891E-M 3.782E-M 969. 4.188E- M 4.070E-M 969. 1.044E-03 1.793E-03 ssE 498. 498. 5.333E-M 5.184E-M 498. 5.797E-M 5.634E-M 498. 2.722E-03 2.MM-03 s 820, 820. 3.444E M 3.367E-M 320. 3.312E-M 3.219E-M 320. 2.083E 03 2.023E 83 seu 835. 835. 2.921E-M 2.839E-M 835, 2.779E-M 2.702E-M 835. 1.021E-03 9.914E-M su 628. 628. 5.830E M 5.M7E-M 628. 4.400E-M 6.415E M 628. 3.274E-113 3.100E 03 ueW 533. 533. 6.91M M 6.720E-M $33. 7.525E-M 7.314E-M 533. 4.592E-03 4.440E-03 W 524. 5M. 6.961E-M 6.764E-M 524. 8.259E-M 8.028E-M 524. 5.967E-03 5.796E-03 Wuu M3. M3. 4.295E M 4.174E M 643. 5.147E-M 5.003E M M3. 3.744E-03 3.630E-03 NW 762. 762. 3.500E M 3.482E-M 762. 4.035E-M 3.922E M 762. 2.541E-03 2.48EE 83 uuv 890. 390. 3.301E-M 3.20EE M 890. 3.415E-M 3.319E-M 990. 1.964E-03 1.909E-03 LASALLE SITE NETEOROLOSICAL DATA 1/75 - 12/ST 9

.F-29

. LASALLE Revision 1.1 July 1994 Tatdo F-7a (Condnued)

Maxinum Offste Finite Pkane Gamme Dose Factors Based on 1 cm Depth at the Restricted Atwa 0-M_ci for Kr-90 Dowwird Restricted Elevated (Stock) Reteese Mixed Nede(Vent) Reteeee Ground Levet Release 3 38AR todlue V V8AR Redlue 8 E8AR Directism Aree Sourd Redlue (reters) (meters) (ared/yr)/(uct/sec) (meters) (ered/yr)/(uct/sec) (meters) (ared/yr)/(ucl/sec) u 1036. 1036. 6.785E-05 6.586E-05 1936. 5.199E 05 5.M 7E-05 1836. 8.20M-05 7.954E-05 NNE 1378. 1378. 3.195E-05 3.102E-05 1378. 2.161E-05 2.098E 05 1378. 2.265E-uS 2.196E-05 NE 1609, 1609. 1.240E-05 1.203E-05 1609. 6.M9E-06 6.745E 06 1609. 7.357E-06 7.134E-06 ENE 1079. 1079. 3.718E-05 3.610E 05 1079. 2.538E-05 2.464E-05 1079. 4.57FE-05 4.438E-05 E 1055. 1055. 4.582E-05 4.448E 05 1055. 3.257E-05 3.162E-05 1055. 6.817E-05 6.610E-05 ESE 1055. 1055. 6.315E-05 6.130E-05 1055. 5.071E-05 4.922E-05 1055. 1.078E-04 1.M 6E-04 sE M9. 969. 5.84X-05 5.673E-05 969. 5.324E 05 5.168E 05 969. 1.365E-04 1.324E-04 SSE 698. 698. 1.170E-04 1.136E-M 698. 1.10M-M 1.070E 04 698. 2.578E-04 2.500E-04

$ 820, 820, 5.233E-05 5.081E-05 820. 3.888E-05 3.775E 05 820. 1.108E-04 1.075E-04 835. 3.062E-05 2.972E-05 835. 1.274E-05 1.237E-05 835, 1.835E 05 1.779E-05 SSW 835.

SW 628. 628. 9.754E-05 9.470E-05 628. 6.538E-05 6.347E-05 628. 1.410E 04 1.368E-04 WSW 533. 533. 1.892E-04 1.856E-04 533. 1.525E-04 1.480E 04 533. 4.861E-04 4.71M-06 W 324. 524. 2.165E-04 2.101E-04 524. 2.185E-04 2.121E-04 524. 8.427E-04'8.170E-04 WWW 643. 643. 1.018E-04 9.883E 05 643. 1.000E-04 9.787E-05 643, 3.141E-04 3.045E-04 i NW 762. 762. 6.634E-05 6.440E-05 762. 5.815E-05 5.645E-05 762. 1.306E 04 1.267E-04 NNW 890. 890. 5.725E-05 5.558E-05 890. 4.336E-05 4.209E-05 890. 8.819E-05 8.551E-05 LASALLE SITE M TEOROLO8tCAL DATA 1/78 - 12/87 I

i t

l l

t t

m 9

\

LAbALLE wJ Revision 1.1 July 1994 4 Table F-7a (Continued)

Maximum OffsAs Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundsey for Xe-131m I

l Doeswiruf Restrfeted Eleveted(Stock) Reteese Nlmed Nede(Vent) Roteese scownf Level Reteeee Direction Aree Sound Redlue S 90AR Redfue V VSAR Redfue 8 OSAR I (meters) (metero) (ered/yr)/(utf/sec) (meters) (ared/yr)/(ucl/see) (eeters) (ered/yr)/(uct/sec)

N 1036. 1036. 1.606E-06 1.473E-06 1036. 1.827E-06 1.679E-06 1036. 1.645E 04 1.28X-04 NNE 1378. 1378. 1.718E-06 1.572E-06 1378. 1.726E-06 1.55 M-06 1378. 1.072E M 8.384E-05 NE 1609, 1609, 1.327E-06 1.167E-06 1609. 1.409E-06 1.239E 06 1609. 7.747E-05 6.064E-05 EWE 1079. 1079. 1.254E-06 1.14M-06 1079. 1.61M-06 1.423E-06 1079. 1.225E-04 9.563E-05 E 1055. 1055. 1.249E 06 1.150E-06 1055. 1.806E-06 1.592E-06 1055, 1.376E-041.073E 06 ESE 1055. 1955. 1.566E-06 1.442E-06 1055. 2.270E-06 1.990E-06 1955. 1.298E-04 1.014E-04 SE 969. 969. 1.472E-C6 1.365E-06 969. 2.406E-06 2.115E-06 969. 1.240E-04 9.696E-05 SSE 698. 698. 1.566E-06 1.476E-06 698. 2.969E-06 2.597E-06 698. 1.624E-M 1.267E-04 S 820. 820. 1.238E-06 1.151E-06 820. 1.903E-06 1.742E 06 820. 1.253E-04 9.802E 05 SSW 835. 835. 1.196E-06 1.103E-06 835. 2.00M-06 1.755E-06 835. 8.790E-05 6.885E-05 SW 628. 628. 1.802E-06 1.691E-06 628. 4.345E-06 3.72EE-06 428. 2.109E-04 1.646E-04 W5W 533. 533. 1.859E-06 1.755E-06 533. 4.161E-06 3.577E-06 533. 2.324E-04 1.813E-06 W 524. 524. 1.800E-06 1.70M 06 524. 3.359E-06 2.972E-06 524. 3.000E-04 2.335E 04 WNW 643. 643. 1.263E-06 1.1ME-06 643. 1.976E-06 1.791E-06 443. 2.446E-04 1.902E-04 NW 762. 762. 1.135E-06 1.M9E-96 762. 1.561E-06 1.437E-06 762. 2.005E-04 1.560E-04 NNW 890. 890. 1.191E-On 1.112E M 890. 1.36M 06 1.263E 06 890. 1.664E-04 1.295E-04 LASALLE SITE NETEOROLORICAL DATA 1/78 - 12/87 I

-F-31

. LASALLE R; vision 1.1 July 1994 l

l Tatdo F-Ta (Continued) i I

t Maximum Offshe Finne Plume Gemma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133m Doomwind Restricted Elevated (Stock) Release Nimed Mode (Vent) Rolesee 8 cowed Levet Retenee Directlen Acee Sound Redlus S SBAR Redlus V VBAR Radius 8 GBAR (w ters) (aeters) (ared/yr)/(ucl/sec) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uct/sec) u 1036. 1036, 8.557E-06 8.199E-06 1036. 9.814E-06 9.407E-06 1036. 2.822E-04 2.4100 04 NME 1375. 1378. 7.917E 06 7.509E-06 1378. 8.400E-06 8.009E-06 1378.

1609. 1.901E 04 1.633E 04 WE ?609. L T29E-06 5.423E-06 1609. 6.093E-06 5.768E-06 1609. 1.389E 04 1.195E 04 EME 1079. 10.M. 6.486E-06 6.205E-06 1079. 7.141E 06 6.771E-06 1079.

1053 2.121E-04 1.815E-04 E 1055. 6.770E-06 6.492E-06 1055. 7.917E-06 7.501E-06 1055.

1055 2.368E 04 2.024E-04 ESE 1055. 4.481E-06 8.132E-06 1955. 9.879E-06 9.355E-06 1055.

969. 2.276E-04 1.951E-04 SE 969. 8.229E-06 7.903E 06 969. 1.039E 05 9.834E-06 969.

698 2.189E-M 1.879E-04 SSE 698. 9.363 06 9.021E-06 698. 1.250E-05 1.181E-05 698.

5 820 2."115E 04 2.409E-04 820. 6.991E-36 6.718E 06 820. 8.532E-06 8.075E-06 820.

E35.

2.236E 04 1.923E-04 SSW 835. 6.541E-06 6.276E 06 835. 8.500E-06 8.036E-06 835.

Su 628 1.574E-04 1.354E-04 628. 1.059E 05 1.020E-05 628. 1.637E 05 1.335E 05 628.

l 533. 3.668E-04 3.140E-04 95W 533. 1.121E-05 1.081E-05 533. 1.588E-05 1.490E-05 533.

W 524 524. 4.005E-04 f.423E-04 i

1.096E-05 1.056E 05 524. 1.504E-05 1.427E-05 524. 5.039E 04 4.287E-04 unu 643 643. 7.648E-06 7.374E-06 643. 9.956E-06 9.510E 06 l

643. 4.055E-04 3.441E-04 NW 762. 762. 6.774E-06 6.526E 06 762. 8.435E-06 8.088E-06 762.

uuv 890 3.334E 04 2.831E-04 890. 6.855E-06 6.594E 06 890. 7.588E-06 7.286E 06 890. 2.794E-04 2.37FE-04 l

LASALLE SITE BETEOROLOSICAL SATA 1/78 - 12/87 l

e ~5 9. --

N m . .

, LAbALLE Revision 1.1 July 1994 -

Tame F-7a (Condnued)

Maxtnum Offste Finite Plume Gamma Dose Factors Based on 1 cm DepIh at the Restricted Asea Boundary forXe-133 ,

r i

Dourwind aestricted Eteweted(Steet) Reteese Mined Nede(Vent) Roteese Oromd Levet telease DIrectien Aree De m d Redlue S SEAR Redlue V VSAR Redfue G OSAR (metere) (metere) (ared/yr)/(igf/see) (metere) (ared/yr)/(utf/sec) (metere) (ared/yr)/(uct/sec) ,

N 1036. 1036. 7.010E-06 6.75 M -06 1036. 7.953E-06 7.M 9E-06 1936, 3.134E-M 2.785E-M NME 1375. 1375. 6.939E-06 6.629E-06 1375. 7.149E-06 6.860E 06 1378. 2.13M-M 1.903E-M NE 1609. 1609. 5.000E-N 4.53E-06 1609. 5.323E-06 5.8NE-M 1809. 1.562E M 1.397E-M ENE 1079. 1979. 5.306E-06 5.196E-06 1979. 6.MM-06 5.769E-06 1979. 2.362E-M 2.101E-M E 1055. 1055. 5.535E-M 5.348E-06 1055. 6.764E-06 6.45M-06 1955, 2.632E-04 2.330E-M ESE 1055. 1055. 7.018E-06 6.789E-06 1955. 8.546E-06 8.149E-06 1955, 2.543E-04 2.266E-M SE 969. 969. 6.M1E-06 6.418E-06 969. 8.97W 06 8.55GE-06 969. 2.450E-M 2.185E-04 SsE 698. 698. 7.21 M-06 6.994E-06 698. 1.073E 05 1.021E-05 698. 3.132E-04 2.785E-M S 820. 820. 5.369E-06 5.18EE-06 B20, 7.024E-06 6.487E 06 820. 2.515E-04 2.24M-M !

$5W 835. 835. 4.969E-06 4.793E-06 855. 6.590E-06 6.264E-06 835. 1.7F0E-04 1.582E-M su 628. 628. 7.79W-06 7.549E-06 628. 1.362E 05 1.285E-05 628. 4.090E-04 3.440E-04 !

WsW 533. 533. 8.MSE-06 7.992E-06 533. 1.326E-05 1.25 N-05 533. 4.44M-04 3.951E-M N SM. SM. 8.166E-06 7.919E-06 SM. 1.220E-05 1.144E 05 SM. 5.551E-04 4.911E-M i i

Wuw M3. M3. 5.715E-06 5.541E-06 M3. 7.ag5E-06 7.574E-06 M3. 4.444E 04 3.92 N-04 NW 762. 762. 5.11 M -06 4.958E-06 762. 6.53EE-06 6.303E-06 762. 3.661E-04 3.233E-M MuW 890. 890. 5.340E 06 5.145E-06 890. 5.911E 06 5.700E-06 890 3.000E-04 2.725E-04 LASALLE SITE M YEEROLOGICAL DATA 1/78 - 12/07 r

1 1

4 F-33 i

. LASALLE

~

Revision 1.1 July 1994 Table F-7s (Continued)

Meutnum OWshe Finite Plane Gamme Dose Factors Besed on 1 an Depth at the Residcted Ame Boundary for Xe-135m l

Deurerind Reetricted Eleveted(Stock) Reteese Mixed Rede(Vent) Reteeee Ground Level Release DIroctlen Aree Seted Redfue S sSAR Redlue V VBAR Redfue 8 agan (astere) (metere) (ered/yr)/tutt/sec) (meters) (ared/yr)/(ist/see) (metere) (ared/yr)/(W I/sec)

N 1036. 1036. 1.396E-04 1.349E-M 1936. 1.590E 04 1.545E-M 1036. 1.531E 03 1.475E-03 NME 1378. 1378. 1.151E-04 1.11M-04 1375. 1.274E-M 1.232E M 1378. 1.019E 03 9.821E-M NE 109. 1609. 8.046E-05 7.779E-05 1609. 8.260E-05 7.905E-05 1609. 7.03M M 6.778E M ENE IL79. 1979, 1.024E-04 9.990E-05 1079. 1.064E-M 1.02EE M 1079. 1.14M-031.105E 03 E 1055. 1055, 1.121E-04 1.0ME-M 1955. 1.183E M 1.144E M 1055. 1.25M-03 1.207E-03 ESE 1995, 1055. 1.41s?-M 1.365E-M 1055. 1.490E- M 1.441E- M 1055. 1.256E 03 1.211E-03 SE 969. 969. 1.309E M 1.34M M 969. 1.575E-M 1.522E-M 969. 1.262E-03 1.21M 03 sst 698. 698. 1.692E4 4 1.636E-M 698. 1.955E-D41.890E M 690. 1.66M-031.606E 03 s 820. 820. 1.196E 01 1.157E-M 820. 1.251E-04 1.209E-M 820. 1.363E 03 1.314E-03 seu 835, 835. 1.1ME-Di 1.068E-M 835. 1.260E-M 1.218E 04 835. 8.762E-04 8.4$4C-M su 628. 628. 1.904E 'A 1.M1E-M 628. 2.444E M 2.363E M 628. 2.17M 03 2.094E 03 Wsu 533. 533, 2.06M-04 1.99fE-M 533. 2.42M-M 2.345E M 533. 2.679E-04 2.380E 03 W 524 524. 2.03M-04 1.966E-M 524. 2.511E M 2.427E M 524. 3.050E-03 2.93M-03 Wuw 643. 643. 1.36M-04 1.318E-04 643. 1.687E-M 1.631E M 643. 2.286E-03 2.201E-03 NW 762. 762. 1.187E-04 1.14SE-M 762. 1.423E-M 1.376E-M 762. 1.806E-03 1.739E-03 Nuu 990. 890. 1.161E 041.122E-M 890. 1.259E M 1.217E-M 890. 1.482E 03 1.427E 03 LASALLE 917E NETECAOLOGICAL DATA 1/75 - 12/97 l

1

. LAbaLLE Revision 1.1 July 1994 Tatdo F-7a (Conlinued)

Maximum Offshe Fbdie Plume Gamma Dose Factors Based on 1 cm Depth at the Resedcted Asea Boundsey for Xe-135 i

Dourarind Reettleted Elevated (Steet) Reteese Nimed Nede(Vent) Release Srewuf Level Reteese Directlen Aree Bewuf Redlue 5 se4R Redlue V VSAR Redlue G ESAR (aetere) (aeters) (ared/yr)/(uct/sec) (aeters) taredryr)/(uct/sec) (motors) (ared/yr)/(uct/sec)

N 1036. 1936. 3.165E-05 7.903-05 1854. 9.387E-05 9.085E 05 1936.

i 1578.

1.302E 03 1.257E 03 NNE 1378. 7.171E-05 6.940E 05 1378. 7.821E-05 7.549E-05 1378.

ut 1609.

9.178E-M 8.864E M 1409. 5.140E-05 4.974E-05 1609. 5.463E 05 5.206E-05 1409.

1079.

6.001E-04 4.570E-M ENE 1979. 4.139E-05 5.942E-05 1979. 6.476E-05 6.267E-05 10M.

1055, 9.912E-04 9.573E-M E 1955. 6.493E-05 6.204E-05 1055. T.155E-05 6.9ME 05 1855.

1055. 1.097E 03 1.060E-03 ESE 1955. 8.130E-05 7.869E-05 1955. 8.905E 05 8.617E 05 1055.

969. 1.083E-03 1.04dE-03 st 969. T.953E-05 7.69?E-05 969. 9.344E-05 9.044E-05 969.

ssE 698. 1.052E-03 1.01?E-03 69E. 9.205E-05 8.f10E-05 698. 1.117E-04 1.081E-04 698.

3 820. 1.321E-031.276E 03 820. 4.782E-05 6.564E 05 820. 7.eddE-05 7.419E-05 820.

ssu 835. 835, 1.093E 03 1.05aE-03 6.306E-05 4.193E-05 835. 7.63dE-05 7.309E-05 855. 7.699E-04 7.438E-04 su M. M. 1.039E M 1.00$E M m. 1.409E-M 1.363E- M W. 1.729E-03 1.670E-03 usu 533. 533. 1.106E M 1.071E- M 533. 1.372E-M 1.32EE-M 533. 1.864E-dB 1.881E-03 W 5M. SM. 1.08M-M 1.048E-04 5M. 1.374E- M 1.329E-04 5M.

Wuv 643. 443. 2.25dE-03 2.179E-03 7.530E-05 7.296E-05 643, 9.395E-05 9.092E-05 643.

NW 762. 762. 1.775E 03 1.713E-03 6.654E-05 6.440E 05 761. 8.0ME-05 7.83EE 05 762. 1.466E-03 1.415E-03

. NuW 890. 890. 6.671E 05 6.456E-05 890. 7.327E-05 7.092E 05 890. 1.247E-03 1.204E 03 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87

- F-35

. LASALLE Revision 1.1 - ,

July 1994 U

Table F-Ta (Condmso4 Mastman OWehe Fkdbo Plume Gamme Does Factors Based on 1 crn Depet at See Restricted Asen Boundary for Xe-137 pourselnd aestricted Eleveted(steck) Reteese Rised Rede(Vent) Reteeee treasuf Level Roteese Streetten Aree Sound Redfus S SBAR Redfus V VSAR Redfus S esAR (meters) (meters) (ared/yr)/(uct/see) (astere) (ared/yr)/(uct/ses) (meters) (ared/yr)/(ucl/see) u 1834. 1934. 4.7 Bet-05 4.42M 85 1934. 5.24M-05 5.0ME 05 1834.

3.409E-M 3.2ME-M ENE 1378. 1375. 3.585E-05 3.471E 05 1375. 3.814E-05 3.492E-05 1378. 1.975E- M 1.911E M NE 1409. 1489. 2.252E-05 2.209E-05 1409. 2.185E-05 2.115E-05 1489. 1.144E-M 1.120E M i ENE 1979. 1979. 3.342E-05 3.234E-05 1079. 3.282E-85 3.177E-05 1079. 2.43M-M 2.35GE-M i

E 1055. 1955. 3.741E-05 3.422E-05 1955. 3.714E-05 3.59M-85 1955. 2.425E-M 2.54GE-M ESE 1955. 1055. 4.82M-05 4.473E-05 1955. 4.871E-85 4.715E-85 1855. 2.785E-M 2.4 FEE-M i

SE 969. 969. 4.M3E-85 4.591E-05 969. 5.18M-85 5.823E-05 969. 2.999E-M 2.892E-M i

i ssE 498. 698. 4.273E-05 4.073E-85 498. 4.983E-05 4.750E-85 690. 4.329E-M 4.ter-M s 320. 820. 4.133E-05 4.002E-05 820. 4.M2E-85 3.913E-05 820. 3.373E M 3.364E-M Seu E55. 835. 3.521E-05 3.40eE-85 535. 3.434E-85 3.315E-95 535. 1.74aE M 1.691E M su 428. 428. 4.T79E 05 4.343E-05 428. 7.950E-05 7.485E-85 428. 5.333E-M 5.14tt-M i i' upW 533. 533. 7.919E-05 7.d47E-05 533. 8.829E-85 8.54M -85 533. 7.144E M 4.932E-M W SM. SM. 7.990E-05 7.734E 85 5M. 9.40 M -05 9.302E-95 5M. 9.223E-M 8.924E M taaf M3. M3. 5.023E-05 4.863E-05 M3. 4.090E-95 5.89dE-85 M3. 4.002E M 5.80eE-M ini 762. 752. 4.140E-05 4.02EE-05 752. 4.M1E-05 4.4SFE-05 752. 4.22EE-M 4.090E-M i

uuW 890. 390. 3.985E-05 3.858E 95 890. 4.152E-05 4.02GE 95 990. 3.279E M 3.172E-M LASALLE SITE M TEOROLOGIcAL DATA 1/75 - 12/87 i

e _ - -_ -- - .-

TS e .

. LA LLE Revision 1.1

_ July 1994 Table F-7a (CoM Maximum OWohn Finho Ptsmo Gamme Dose Factors Based on 1 cm Depet at Wie Resehend Asse Boemdery forXe-134 Deureeind toetrleted Elevated (Steet) Rolesee Nimed liede(Vent) Roteese tround Levet beteese Directlen Aree Deed Redfue S SGAR Redfus V VBAR Redlue 8 MAR (meters) (soters) (ared/yr)/(ucl/sec) (meters) (eradryr)/(utt/sec) (noters) (ared/yr)/(uti/sec) a 1936. 1m. 3.92dE-M 3.814E-M IM. 4.523E-M 4.390E M 1936. 3 '73E 03 3.804E-03 EME 1375. 1378. 3.160E-M 3.071E-M 1375. 3.53dE-M 3.43M M 1378. 2.11M-03 2.055E 83 NE 1609. 1609, 2.19W-M 2.134E-M 1409. 2.272E M 2.200E-M 1609. 1.45M-03 1.414E 03 Eut 10M. 10M. 2.8BM M 2.800E-M 1079. 2.99dE- M 2.912E- M 1079. 2.383E-03 2.313E-93 E 1055. 1955. 3.16M-M 3.079E M 1955, 3.323E M 3.230E M 1955, 2.600E-03 2.524E 03 l ESE 1055, 1955. 3.M1E-04 3.850E-M 1055. 4.149E-M 4.832E M 1955. 2.618E-03 2.541E-93 sE 969. 969. 3.930E-M 3.82EE-M 969. 4.400E M 4.235E-M 969. 2.641E-03 2.564E-03 SSE 690. 498. 4.911E M 4.773E M 698. 5.540E-M 5.304E-M 698. 3.494E-03 3.391E-83 S 820. 820. 3.490E-M 3.400E M 820. 3.406E-M 3.505E-M 820. 2.85M 03 2.773E-03 sw E35. 835. 3.277E-M 3.188E 04 835. 3.832E-M 3.724E-M 835. 1.82EE-03 1.774E-03 su 628, 428. 5J90E-M 5.53eE-M 620. 7.209E-M T.00M-M 628. 4.544E-05 4.412E-03 Wow 533. 533. 6.144E-M 5.973E-M 533. 7.121E-M 6.921E M 533. 5.20dE ,03 5.053E-03 v 524. SM. 5.97eE-M 5.009E-M 524. 7.318E-M 7.113E-M SM. 4.383E-05 6.195E-83 inne M3. M3. 3.908E-M 3.875E-M M3, 4.8B7E M 4.750E 04 M3. 4.757E-03 4.614E-83 Int 762. 762. 3.45M M 3.360E-M 762. 4.131E-M 4.01M-M 762. 3.746E-03 3.635E-03 l luni 890. 890. 3.330E-M 3.236E-04 890, 3.42dE M 3.525E- M . 390. 3.069E 03 2.97EE 93 LASALLE BITE HETEUROLostCAL MTA 1/73 - 12/0T l

F-37

. LASALLE Revision 1.1 July 1994 Table F-7a (Conunned Maximum OWebe Finto Plume Gamme Does Factors Based on 1 cm Depen at sie Resekted Arom Boundary for Ar-41 Deeensind Beatricted Eleveted(Stact) Reteese Nf ned Rede(Vent) Rolesse Gressul Level Roteese Strectlen Aree Beimd Redfue S star Redlue V VSAR Radium 8 GBAR (aeters) (seters) (aredryr)/(uct/sec) (meters) (aradryr)/(uct/sec) (asters) (aradryr)/(uct/sec) u 15. 1M. 4.744E-M 4.5ME M 1934. 5.52AE-M 5.351E-M 15. 4.557E 03 4.411E-03 uut 1378. 1378. 3.954E-M 3.82M -M 1378. 4.4NE M 4.29M-M 1375. 3.203E-05 3.101E 03 ut 1409. 1609. 2.82M-M 2.734E-M 1489. 3.ONE M 2.93M M 1409. 2.350E-03 2.2GE-03 ENE 1979. 1979. 3.582E-M 3.46EE-M 1979. 3.729E-M 3.410E-M 10M. 3.472E 03 3.361E-03 E 1055. 1955. 3.810E-M 3.49dE M 1955. 4.100E-M 3.9ept-M 1955. 3.M1E-03 3.710E-03 ESE 1955. 1955. 4.725E M 4.5 FEE-M 1955. 5.025E M 4.0645-M 1955. 3.007E-05 3.485E 03 SE 969. 969. 4.711E M 4.560E-M 969. 5.320E-M 5.149E-M 969. 3.71M-05 3.59M-03 Set 690. GOS. 5.472E-M 5.490E-M 698. 4.491E-M 6.2ME-M 898. 4.405E-03 4.545E 03 S 820. 820. 4.21M-M 4.87M M 820. 4.5E5E M 4.430E-M 820. 3.879E-05 3.755E-03 SsW E35. 335. 3.994E-M 3.86dE-M E55. 4.930E-M 4.772E-M E55. 2.700E-03 2.414E 03 su 428. 625. 6.711E-M 6.49dE M 628. 8.591E-M 8.314E-M 628. 4.139E 03 5.MM-03 Wsu 533. 533. 7.009E-M 4.862E-M 533. 8.229E-M 7.96dE-M 533. 4.46M 03 6.45M 03 W 5M. SM. 4.8BIE-M 6.584E M 5M. 8.291E- M 8.02dE M SM. 8.057E-R3 7.799E-03 wuu 443. 443. 4.700E-M 4.55M-M e43. 5.714E-M 5.533E-M 643. 6.300E-05 6.099E-03 Inf 762. 762. 4.123E-M 3.991E M 762. 4.9NE M 4.811E-M 762. 5.1TM-03 5.000E-03 NEW 090. 390. 4.025E- M 3.896E M 890. 4.44M-M 4.305E-M 890. 4.374E 03 4.234E-03 LASALLE SITE BETEOROLOGICAL DATA 1/78 - 12/87 6 5 9. .

. _ _ _ _ _ _ _ _ _ _ . - . =_ . _. _ _ _ _ _. __. _

LASALLE Revision 1.1 l l

July 1994 l l l Table F-8 Parameters for Calculations of N-16 Skyshine Radiation From LaSaBe

}

I i

Lacadon ActMiy Occupancy

Occupancy Shieldng Distance l Number Hours Factor' Factor R, i k OH,' OF. SF. (m) l 1 LMng at home 8360 0.95 0.7 1100" (nearest resident) 2 Fishing 400 0.05 1.0 2100 l

3 LMng at the 2500 0.7 2400 National Guard Faclety l i

u. = 5 l ;

K = 2.28E45 mromf(MWe-br) . -

These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of l the puhuc using Equation A-34 in Appendix A. If desired, more ree8shc parameters could be used in place of ,

these to refine the estimate. For example, one could determine whether the nearest resident resNy Ashes the !

speclSed number of hours at the spedAed location.

a The amount of time in a year that a maximally exposed Asherman would spend Ashing 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 por year. This yioids 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. ,

t b Distance to need residence (See Table F-3).

i c The OF is the quotient of the number of hours a location is occupied and the number of hours in a year. i Thus OH/8760 hours = OF. rounded to the 0.01 digit. l 1

in determining the maximsby exposed indMdual, the following possibitties were considered: the nearest I resident, Ashermen, and persons at the National Guard faciBty north of the site. The annual exposure time and !

location of a maximally exposed Asherman were estimated on the basis of discussion with a member of the i station staff. The nearest resident was found to have the greatest exposure to skyshine. For detalis, see ,

Reference 2 of Seebon F.2. !

l l

I F-39 l

l j

. LASALLE Revision 1.1 July 1994 SupplementalTable A Elevated Level Joint Frequency Distritmlion Table Summary 375 Foot Elevallon Date j Susumery Tetste of Percent.try Direction and Class cises N Deet NE ENE E ESE SE SSE 5 $$W S4f WSW W WNW NW 9efW fote1 4

i A .024 .032 .087 .057 .002 .040 .030 .OSO .OSS .199 .007 .051 .055 *. 084 .003 .024 .943 I 8 .149 .175 .227 .149 .000 .047 .056 .070 .233 *

.463 .330 .109 .14B .192 .153 .183 2.843 C .300 .242 .351 .255 .138 .089 .104 .130 .375 .579 .454 .381 .344 .420 .329 .332 4.805 0 3.100 2.434 3.282 3.192 2.780 1.945 9.787 2.053 2.010 *2.875 2.270 2.400 3.24f4 4.933 3.922 3.681 48.551 E 1.018 .913 1.192 1.439 1.923 1.499 1.400 1.752 2.897 2.979 2.124 1.531 1.575 2.005 1.670 1.Its 27.OSI F .320 .102 .248 .290 .489 .707 .909 .998 1.459 1.735' 1.561 1.041 1.012 1.099 .894 .553 .13.438 G .055 .039 g O22 .012 .041 .003 .278 .507 .874 .SSS .SSO .400 .309 .242 .217 .103 4.258 Totet 4.985 4.237 5.356 5.398 5.394 4.385 4.001 S.587 8.474 9.457 7.487 S.003 S . Seit S. stb 7.248 S.073 100.000 Susumery feele of Percent try Of rection and Speed ,

Speed N NME ME ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW fotel i

j .45 .018 .017 .015 .010 .006 .090 .013 .000 .018 .090 .000 .013 .000 .000 .001 .000 .137 1.05 . Ole .033 .030 .027 .021 .023 .032 .027 .027 .017 .017 .028 .028 .024 .034 .027 .402 2.05 .182 .290 .279 .215 .147 .149 .199 .171 .ISS .ISS .195 .135 .147 .115 .138 . ISO 2.721 3.05 .381 .479 .591 .477 .369 .287 .311 .278 .323 .317 .272 .302 .321 .317 .302 .311 5.599 4.05 .508 .547 .785 .547 .494 .428 .437 .404 .483 .4SS .428 .400 .387 .482 .487 .455 7.794 S.05 .489 .598 .792 .515 .451 .403 .420 .509 .477 .489 .492 .472 493 .540 542 .533 S.213 0.05 .577 .599 . Set .598 .508 .419 .479 .483 .SSS .584 .523 .'487 .556 .598 .SSS .SSS 9.150 8.05 1.297 .918 1.353- 1.209 1:207 .972 .989 1.082 1.415 1.900 1.371 1.164 1.207 1.822 1.669 1.623 20.837 10.05 .912 .421 .487 .345 .998 .751 .738 .947 1.385 1.552 1.325 1.088 1.240 1.879 1.557 1.270 17.188 13.05 .482 .210 .183 . .594 .SSS .992 .749 1.187 2.107 2.440 1.822 f.338 1.432 1.962 f.428 .800 V8.236 18.00 .120 .055 .028' .231 .328 .240 .283 .459 1.478 1. stb t.043 .581 .746 1.137 .404 .222 9.163 99.00 .002 .000 .000, ,.011 .011 .011 .013 .005 .072 .408 .038 .005 .437 .147 .019 .015 .708 Totet 4.90s 4.z37 5.3st 5.300 5.s94 4.385 4.001 5.sS7 8.474 9.4sv v.487 S.003 e.SSS 8. stb 7.248 S.073 100.000 NOTE: Wind directions in tablet are presented in ' Wind from* and not " wind to" diredion O - . .

9 . . ._ .-

0.

. s

. J SALLE Hevision 1.1 July 1994 SupplementalTable A-Congnued r

Elevated Level Joint Frequency Distribution Table Summary 375 Foot Elevation Data Susumery 7 stile of Percent try Speed gnal Close Class A B C D

E F G Speed

.45 .000 .000 .000 .082 .088 .023 .004 1.05 .001 .004 .004 .178 .153 .000 .005

2.05 .017 .041 .109 1.540 'SSG

. .307 .050 3.05 .046 .159 .290 3.269 1.193 .547 .096 4.08 .102 .249 .499 4.384 1.629 .788 .ISS 5.05 .102 .335 .547 4.159 1.945 .918 .210 6.05 .tOS .341 .565 4.563 2.320 .986 .268 8.05 .225 .701 1.I18 10.191 5.190 2.400 .755 10.05 .141 .429 ,.785 7.441. 4.924 2.591 .870 13.05 .134 .404 .598 S.977 5.670 3.208 1*.296 ,

10.00 .088 .183 '.256 3.424 3.126 1.51I .815 99.00 .001 .017 .036 .396 .198 .043 .015

. F-41

, LASALLE Revlolon 1.1 July 1994 ,

Supplemental Table 8 l

Mid Elevation Joint Frequency DIStribullon Table Summerles l Summary Table of Percent any Strection entf Ctese Class N NME NE ENE E ESE SE SSE j- 5 SSW SW tf5W W ISAf. ,

, Det NNW fotet t

A .381 .248 .301 .790 .531 .258 .142 .119 .231 .357 .441 .370 .453 '. 883 .579 .878 7.030 l B .313 .249 .377 .343 .290 .175 .110 .t04 .307 .288 .327 .292 .350 .496 .530 .612 5.002 C .531 .420 .584 .434 .390 .299 .321 .282 .370 .498 .479 .470 .508 .573 .710 .785 7.834 D 2.274 2.315 2.517 2.248 2.689 1.795 1.977 1.775 2.781 3.045 3.098 1.039 2.140 3.069 2.84f 2.408 37.410 E .777 .734 1.008 1.105 1.486 1.323 1.243 1.43G 2.878 2.910 1.897 f.178 t.229 f.712 1.429 _f.015 23.034 F .233 .tSS .177 .205 433 .009 .002 .001 1.210 1.303 1.183 .392 .854 1.017 .848 446 18.4t9 0 .005 .000 .021 .013 .059 .245 .935 .896 1.244 1.23is .997 . Set .740 .776 .582 .150 E.4tf Totet 4.875 4.182 5.547.5.138 5.057 4.841 4.930 5.413 S.723 9.721 7.299 5.998 S.298 S.297 7.498 0.094 100.000

(

l l

Summary Table of Percent try Direction ents Speed .

Speed N 900E NE ENE E ESE SE SSE S SSW SW WSW W 3 WNW NW NNW foteI 45 .043 .003 .000 .020 .015 .003 .005 .009 .005 .000 .000 .000 .000 .000 .000 .000 .t13 1.05 .048 .072 .083 .042 .033 .025 .040 .034 .037 .021 .026 .038 .031 .026 .034 .046 .612 2.05 .219 .575 .500 .323 .233 .197 .202 .201 .232 .193 .201 .189 .193 .tSt .153 .163 3.915 3.05 .442 1.132 1.140 .991 .497 .350 .399 .383 .364 .344 .339 .353 .413 .374 .386 .374 7.949 4.05 .536 .970 1.375 .729 .617 .528 .545 .532 .599 .583 .557 .466 .491 .553 .830 .818 10.319 5.05 .SSt .584 1.04: .300 .839 .553 .635 .558 .421 .610 .579 .500 .590 .SSG .737 .720 10.593 S.05 .729 .383 .570 .302 .777 .728 .708 .481 .843 .887 .996 .SS7 .895 .815 *940

. .918 11.959 0.05 1.088 .339 .578 1.004 1.597 1.351 1.333 1.428 2.334 2.473 1.925 1.484 f.804 1.933 1.903 f.559 23.790 10.05 .472 .108 .153 .475 .009 .991 .990 1.015 2.122 2.439 1.707 t.IOS 't 106 f.596 1.3IS .910 16.893 13.05 .202 .019 .029 .214 .508 .348 .296 .478 1.342 1.778 1.012 .626 .790 1.414 1.096 .5GO 10.728 18.00 .111 .001 .009 .034 .177 .067 .079 .IIS .310 .383 .954 .159 .300 .683 .312 .203 3.086 l

99.00 .007 .000 .000 .004 .001 .000 .000 .005 .OtO .000 .014 .030 .074 .o74 .0:3 .004 .247 i

Totet 4.575 4.182 5.547 5.t38 5.857 4.84

. 4.930 5.!s t3 S.723 9.72 7. stb 5.898 S.200 8.297 7.499 S.094 100.000 NOTE: Wind directions in tables are presented in Nind from" and not Nind to" direction 0 . _ - _. . __- -- _ - -

0 __- --

0. -

.. +

, SALLE evleion 1.1 July 1994 SupplementalTable B - Continued Mid Elevation Joint Frequency Distribullon Table Summedes 200 Foot Elevellon Data

?_ -y ,7able of Percent by speed end close

! Cleep - A 8 C D E F S speed .

.45 .000 .000 .001 .048 .037 .021 .009 1.05 .013 .004 .022 .219 .175 . tit .083 2.05 .172 .130 .291 9.948 .732 .437 .307 3.05 .000 .453 .309 3.533 1.531 .442 .379 4.05 .775 .SSS .970 4.134 2.320 .930 .591

. 5.05 .328 .588 .964 3.915 2.455 1.190 .590 S.05 .835 .533 .921 4.309 2.742 1.461 1.079 8.05 1.542 1.208 1.471 S.019 S.377 3.357 2.618 10.05 1.030 .700 .979 5.271 4.'1E4 2.319 2.190 13.05 .374 .558 .754 4.ISS 2.854 .335 .597

18.00 .331 .307 1231 1.821 ,830 .048 .020 99.00 .029 .012 1018 .142 .020 .005 .00t l

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, IASALLE Hevision 1.1 July 1994 Supplemental Tobie c - consnued Ground Level Joint Frequency Distribullon Table Summary 33 Foot Elevation Data Summary Table of Percent by Speed and Class Close . A B C D E F e Speed *

.45 .000 .000 .004 .002 .005 .010 .008 1.05 .021 .000 .012 .197 .388 .299 .195 2.05 .326 .202 .272 2.282 2.334 9.764 1.982 3.05 .998 .578 .798 5.133 5.390 3.267 2.800 4.05 1.247 .SSS .Se2 S.435 4.793 3.004 2.725 5.05 "1.203 .848 .852 8.115 3.880 1.773 1.037 S.05 1.201 .570 .004 5.472 3.049 .817 .251 S.05 9.829 300 1.200 S.605 3.334 .463 .000 10.05 .778 .422 .Ble 2.995 1 334 .031 .002 13.05 .428 .212 4248 1.469 .'438 .004 .002 s

, 18.00 .112 .052 4052 .382 .089 .004 .000 99.00 .023 .012 .000 .006 .004 .004 .000 1

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