ML20094D927

Rev 1.7 to ODCM Chapters 10,11,12 & App F for LaSalle Station

ML20094D927
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Site:	LaSalle
Issue date:	09/30/1995
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October 31,1995 Attached are the recent revisions to the Comed Offsite Dose Calculation Manual (ODCM)

Chapters 10,11,12 and Appendix F for LaSalle Station. This revision was approved on October 18,1995. Please complete the following manual update:

Remove Insert LaSalle Station LaSalle Station Chapter 10 Chapter 10 Entire Contents Revision 1.7 Entire Contents LaSalle Station LaSalle Station Chapter 11 Chapter 11

• Entire Contents Revision 1.7 Entire Contents LaSalle Station LaSalle Station Chapter 12 Chapter 12 Entire Contents Revision 1.7 Entire Contents LaSalle Station LaSalle Station Appendix F Appendix F Entire Contents Revision 1.7 Entire Contents Please sign and date this control sheet. Return to:

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LASALLE Revision 1.7 8

.. September 1995 Q LASALLE ANNEXINDEX CHAPTER 10 EAfag REVISION 10-1 1.7 1 0 -11 1.7 10 lii 1.7 10-iv 1.7 10 v 1.7 10-1 1.7 10-2 1.7 10 3 1.7 .

10 4 1.7 10-5 1.7 10-6 1.7 10 7 1.7 10 8 1.7 10-9 1.7 10 10 1.7 10-11 1.7 O 10 12 10-13 1.7 1.7 10-14 1.7 10-15 1.7 10-16 1.7 4

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EPSPROJ4demAssane/10r17f 10-1

LASALLE R vtion 1.7 Srptemb;r 1995 CHAPTER 10 &

RADIOACTIVE EFFLUENT TREATMENT AND MONITORING Table of Contents l NUMBER PAGE 10.1 AIRBORNE RELEASES 1

1. System Description 1

1. Condenser Offgas Treatment System 1

2. Ventilation Exhaust Treatment System 2 1 2. Radiation Monitors 2

1. Station Vent Stack Effluent Monitor 2

2. Standby Gas Treatment System Effluent Monitor 2

3. Reactor Building Ventilation Monitors 3

4. Condenser Air Ejector Monitors 3 l S. Turbine Building 3

3. Alarm and Trip Setpoints 3

1. Setpoint Calculations 3

1. Reactor Building Vent Effluent Monitor 3

2. Condenser Air Ejector Monitors 3

3. Station Vent Stack Effluent Monitor 5

4. Standby Gas Treatment Stack Monitor 5

2. Release Limits 5

3. Release Mixture 6

4. Conversion Factors 6

5. HVAC Flow Rates 7

4. Allocation of Effluents from Common Release Points 7

5. Dose Projections 7 10.2 LIQUID RELEASES 7

1. System Description 7

1. Radwaste Discharge Tanks 7

2. Radiation Monitors 7

1. Liquid Radwaste Effluent Monitor 7

2. Service Water Effluent Monitors 7

3. RHR Heat Exchanger Cooling Water Effluent Monitors 8 l

9 EPsPROJedemAasale/1or1-7f 10-li

LASALLE R: vision 1.7 ,

September 1995

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1 CHAPTER 10 i l i

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RADIOACTIVE EFFLUENT TREATMENT AND MONITORING i

Table of Contents (Cont'd) j i

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$ NUMBER PAGE 4

+ 3. Alarm and Trip Setpoints . . . . ................. ............... .... 8 1

1. Setpoint Calculations . . . . . . . . . . . . . . . . . . . . . . . ........ .... 8 ,

! 1. Liquid Radwaste Effluent Monitor . . .... ........ ..... . 8  ;

1 2. Service Water Effluent Monitors . . . . . . . .......... . ..... 9  !

3. RHR Heat Exchanger Cooling Water Monitors . . ...... .... 9 l 1

2. Discharge Flow Rates . ........ . ...... ... .... .... . . 9

1. Release Tank Discharge Flow Rate . ...... .. ... . 9 I

3. Release Limits . . . . ........ ... .. .... ... . .. . . 10 ,

4. Release Mixture . . ...... .. . . .... . ....... . ... 10

5. Conversion Factors . ........ ..... .......... .. ...... 10 j 6. Liquid Dilution Flow Rates . . . . ...... . ............ . .... 10 4

4. Allocation of Effluents from Common Release Points . . . . . . .... .. .... 10

, l

, s/ 5. Projected Concentrations for Releases . ... . . . . . ...... .. 10 1

l 10.3 SOLIDIFICATION OF WASTE / PROCESS CONTROL PROGRAM . . . . . . . . . . . . . . . . . 10 4

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i EPSPROJ/odemAasale/10r17f 10-lii

LASALLE Rsvision 1.7 Septambar 1995 CHAPTER 10 Q

LIST OF TABLES NUMBER PAGE 10-1 Assumed Composition of the LaSalle Station Noble Gas Effluent .. . 10-11 O

O EPSPROJedemAcsale/10r17f 10-iv

1 Rsvision 1.7 i LASALLE 1

4 Szptembsr 1995 i -

CHAPTER 10 i

l LIST OF FIGURES 4

1 NUMBER PAGE

10 1- Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram . , . . 10-12 l 10-2 Simplified Liquid Radwaste Processing Diagram . . . . . . . . . . . . . . . . .. 10-14 i

! 10-3 Simplified Liquid Effluent Flow Diagram . . . . ................ . . . . . 10 15 1

! 10-4 Simplified Solid Radwaste Processing Diagram . . . . . . . . . . . . . . . . . . . . . . 10-16 i

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EPSPROJ/odemAasale/10r17f 10-v

LASALLE R; vision 1.7 Sept:mb:r 1995 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified gaseous radwaste and gaseous effluent flow diagram are provided in Figure 10-1. s The airborne release point for radioactive effluents is the ventilation stack which is classified as a stack in accordance with the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A.

In addition, the standby gas treatment system effluent is released through a separate stack inside the ventilation stack. This release point has the same location and classification as the ventilation stack.

l Exfiltration to the environment from the Turbine Building has been identified at times of l positive pressure in the Turbine Building. Continuous air sampling is in place in the l south Turbine Building trackway to monitor releases through this pathway. The l releases through the trackway door and other potential release paths contain l insignificant levels of contamination when compared to the Station Vent Stack which l has a 1,000,000 cfm typical stack flow compared to the Trackway flow rate of 40,000 l scfm and conservatively estimated as a total of 80,000 scfm to account for pathways l other than the trackway. In addition, typical releases from LaSalle Station have not l exceeded 0.02% of the 10CFR50 Appendix ! dose limits. This pathway is a ground l level release and should be considered in dose calculations. See Figure 10-1 for l further inf ormation.

l Waste oil processing via incineration is planned at LaSalle Station. Upon l implementation, evaluations will be made which focus on the radiological characteristics l of the oil. The identified radiological characteristics may warrant inclusion into the l radiological effluent report and inclusion in calculations to determine member of the l public dose.

10.1.1.1 Condenser Offgas Treatment System l

The condenser offgas treatment system is designed and installed to reduce radioactive I gaseous effluents by collecting non- condensable off-gases from the condenser and l providing for holdup to reduce the total radioactivity by radiodecay prior to release to the environment. The daughter products are retained by charcoal and HEPA filters. The system is described in Section 11.3.2.1 of the LaSalle UFSAR.

EPSPROJ/odemAasale/10rt.7f 10-1

LASALLE Revision 1.7 SzptembIr 1995 i

l 10.1.1.2 Ventilation Exhaust Treatment 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 j and/or HEPA filters prior to release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figure 10-1.

}

Engineered safety features atmospheric cleanup systems are not considered to be

~

j ventilation exhaust treatment system components.

10.1.2 Radiation Monitors 10.1.2.1 Station Vent Stack Effluent Monitor 4

Monitor OPLD5J (Wide Range Noble Gas Monitor) continuously monitors the final i effluent from the station vent stack,

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

, in normal operation the low range noble gas channelis on line and active. The i mid-range channel replaces the low range channel at a concentration of 0.1 pCl/cc

{ and the high range channel replaces the mid range channel at a concentration of 100 pCi/cc.

l l T

) The low-range and mid/high-range iodine and particulate samplers operate in a i

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

j No automatic isolation or control functions are performed by this monitor. Pertinent j 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 i Monitor OPLD2J (Wide Range Noble Gas Monitor) continuously monitors the final effluent from the standby gas treatment system (SGTS) stack.

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

j 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

, and the high range channel replaces the mid range channel at a concentration of 100 pCi/cc.

The low range and mid/high range iodine and particulate samples operate in a similar manner. In normal operation, the low range samples are on-hne. At a i concentration of 0.05 pCi/cc the mid/high-range samplers are brought on line, and at a concentration of 10 pCl/cc the low-range sample pump is turned off. j EPSPROJedemAssale/1or17f 10-2

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l LASALLE Rzvision 1.7 S:ptember 1995 l

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

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

10.1.2.3 Reactor Building Ventilation Monitors l

Monitors 1(2)D18-NOO9 continuously monitor the effluent from the Unit 1(2) reactor building. On high alarm, tha monitors automatically initiate the following actions l

A. Shutdown and isolation of the reactor building vent system B. Startup of the standby gas treatment system C. Isolation of primary containment purge and vent lines Pertinent information on these monitors is provided in LaSalle UFSAR Section 11.5.2.1.1.

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

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

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

l 10.1.2.5 Turbine Building Trackway l

l In order to quantify releases via the Turbine Building trackway, at times of positive l pressure in the Turbine Building, airborne sampling should be continuously collected l using an air sampler located within the trackway. The samples collected should be l counted on a weekly basis. Air sampling to identify noble gas, iodine and l particulate monitoring (either as a grab sample or continuous sampling) is designed l to ensure evaluation of releases emanating from the Turbine Building.

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

EPsPROJ/odemAasale/1or1-7f 10-3

1.ASALLE Revisi:n 1.7 l I

Szptimber 1995 10.1.3.1.2 Condenser Air Ejector Monitors Pre-Treatment Monitor The high-high trip setpoint is conservatively set at or below one-half the release limit obtained from the post-treatment monitor "high-high-high" trip setpoint. I P s K x 0. 5 x Q,, x E f, x eA ' (10-1)

P Off-gas Pretreatment high-high alarm setpoint K Conversion constant [(mr/hr) per (pCl/sec)] '

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

0.5 Factor for conservatism Q. Release Rate [pCl/sec]

l The release rate of all noble gas radionuclides released as stack releases 1 f

based on post treatment monitor "high-high-high" trip setpoint. This is less than the solutions obtained from Equations 10-3 and 10-4.

f, Predetermined fraction of total release attributed to nuclide i.

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

e A' Term to correct for 30 minute transit time.

The high trip setpoint is established at s 100 pCl/sec per MW-th = 3.4E5 pCl/sec per Technical Specification 3.11.2.2.

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

The off-gas isolation setpoint is converted into the monitor units of counts per second (eps) as follows:

P s 0.5 x Q, x E/(472 x F) (10-2)

P Off-gas Post-treatment Monitor Isolation Setpoint [ cps]

( The off-gas post-treatment monitor setpoint which initiates isolation EPSPROJ/odemAssalle/1ori-7f 10-4 l

LASALLE Revision 1.7 Srptember 1995 of flow of off-gas to the station vent stack.

O,, Total Allowed Release Rate, Stack Release [pCl/sec The total allowed release rate of all noble gas radionuclides released as stack releases. This is the smaller of the solutions obtained from Equations 10-3 and 10-4.

E Efficiency of the Off-Gas Posttreatment Monitor [ cps per (pCl/cc)]

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

472 Conversion Constant [(cc/sec)/cfm]

Converts cubic feet per minute to cubic centimeters per second.

F Maximum Off-Gas Flow Rate (cfm]

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

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

10.1.3.2 Release Limits 4 Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of RETS are not exceeded. The release limit Q,,is found by solving Equations 10-3 and 10-4.

(1.11) 0,, { { f 3- ) < 500 mrem /yr 3

(10-3)

O , [ (WI (X/0), exp(-A R/3600u,)

• t 1 g (10-4)

+ (1.11) ( fi ) S t)

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

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

O,, Total Allowed Release Rate, Stack [pCi/s Release EPSPROJ/odemAasale/10r17f 10-5

. LASALLE Rsvision 1.7 September 1995

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

exp ( AR/3600 U,) is conservatively set equal to 1.0 for purposes of ,

determining setpoints. J l

Th's remaining parameters in Equation 10-3 have the same definitions as in Equation A 8 of l Appendix A. The remaining parameters in Equation 10-4 have the same definition as in l Equation A 9'of Appendix A. I l

Equation 10-3 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 mrem /yr) due to noble gases released in gaseous effluents (see Section A.1.3.1 l of Appendix A). Equation 10-4 is based on Equation A-9 of Appendix A and the RETS restriction i on skin dose rate (3000 mrem /yr) due to noble gases released in gaseous effluents (see Section A.1.3.2 of Appendix A).

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

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

10.1.3.3 Release Mixture In the determination of alarm and trip set points, the radioactivity mixture in the exhaust air is assumed to have the radionuclide composition in Table 101.

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

Station vent stack effluent monitor. )

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

l Condenser air ejector monitor.

Pretreatment Monitor l

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

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

Standby gas treatment system monitor.

Calibrations corr. pare the response of station detectors to that of a reference detector usin, l O_ NIST traceable sources (Cs-137 and Co-60). I EPSPROhodemAssale/1 ort-7f 10-6

LASALLE Revision 1.7 September 1995

• i l

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

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

4 10.1.4 Allocation of Effluents from Common Release Points l l

Radioactive gaseous effluents released from the main chimney are comprised of contributions l from both units. Under normal operating conditions, it is difficult to allocate the radioactivity j between units due to fuel performance, in plant leakage, power history, and other variables. I Consequently, no allocation is normally made between the units. Instead, the entire release is treated as a single source. I 1

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

10.2 LIQUID RELEASES 10.2.1 System Description A simplified liquid radwaste and liquid effluent flow diagram are provided in Figures 10-2 and 10-3~

The liquid radwaste treatment system is designed and installed to reduce radioactive liquid G effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by filter, demineralizer, or evaporator for the purpose of reducing the total radioactivity prior to release to the environment. The system is described in Section 11.2.2 of the LaSalle UFSAR.

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

10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitor Monitor OD018 N907 monitors all releases from the release tanks. On high alarm the monitor automatically initiates closure of valves 0WLO67 and trips the radwaste discharge pump to terminate the release.

Pertinent information on the monitor and associated control devices is provided 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 water effluent. On high alarm service water discharge may be terminated manually. No control device is initiated by these monitors.

EPsPROJ/odemAasale/10rt.7f 10-7

LASALLE Rtvision 1.7

., September 1995 Pertinent information on these monitors is provided in LaSalle UFSAR 11.5.2.3.2.

10.2.2.3 RHR Heat Exchanger Cooling Water Effluent Monitors Instrument channels 1/(2)D18 N906/8 continuously monitor the RHR heat exchanger cooling water effluent. On high alarm the operating loop may be terminated manually and the redundant loop brought on line. 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 liquid effluent monitors at the principal release points are established to ensure that the limits of RETS are not exceeded in the unrestricted area.

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

PsKx C{/{ (CJ/10xDWC,)) x ((F8 + FL,) / FL,) (10-5)

P Release Setpoint [ cpm)

O (K, x C, x W,) /[CJ)

K, Counting efficiency for radionuclide i [ cpm /pCi/mt)

W, Weighting Factor

,C! Concentration of radionuclide iin the release tank. [pCi/mf] l l

i FL, Maximum Release Tank Discharge Flow Rate (gpm)

The maximum flow rate is 45 gpm.

DWC, Derived Water Concentration [pCl/mt) of radionuclide i The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402.

YY EPSPROJ/odemAasaBe/1 ort-7f 10-8 i

LASALLE Revision 1.7 S ptember 1995 10 Multiplier Fd Dilution Flow [gpm]

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

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

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 (Fd/{ (C, /10xDWC )) x MF 3 (10-6 The summation is over radionuclides i.

0.1 Reduction f actor for conservatism.

F',,, Maximum Permitted Discharge Flow Rate [gpm]

The maximum permitted flow rate from the radwaste discharge tank.

F' Dilution Flow [gpm]

C, Concentration of Radionuclide iin the Release Tank [pClimL]

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

DWC, Maximum Permissible Concentration of Radionuclide i [pCi/ml]

The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.10012402.

10 Multiplier MF Multiplication Factor EPSPROJMdemAasale/10r17f 10 9

LASALLE Ravision 1.7 Ssptemb3r 1995 ,

. 1

< l 1

O F' < 0.5; MF = 3 O

0.5 < F',r, 5 M F = 5 5 < F',,,, ; M F = 7.5 10.2.3.3 Release Limits Release limits are determined from RETS. Calculated maximum permissible discharge rates are divided by 10 for conservatism and to ensure that release concentrations are well below applicable derived water concentrations (DWC).

10.2.3.4 Release Mixture j For the liquid radwaste effluent monitor the release mixture used for the setpoint j determination is the radionuclide mix identified in the grab sample isotopic analysis plus four '

additional radionuclides. The additional radionuclides are H-3, Fe-59, Sr 89, and Sr 90. The quantities to be added are obtained from the most current analysis for these four radionuclides.

For all other liquid effluent monitors no release mixture is used because the setpoint is

' established at "two times background."

10.2.3.5 Conversion Factors

. The readout for the liquid radwaste effluent monitor is in CPM. The calibration constant is based on the detector sensitivity to Cs 137/Ba 137.

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

10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from the Unit 1 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 solidification of radioactive wastes from liquid systems is ensured.

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

EPsPROJ/odemAasale/1 ort 7f 10-10

4 LASALLE Rcvision 1.7 September 1995 TABLE 10-1 O

Assumed Composition of the LaSalle Station Noble Gas Effluent i

Percent of Isotooe Total Annual F.elease 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 Xe-131m 2.0E 5 Xe 133m 3.8E-4 l Xe-133 1.1 E 2 Xe-135m 3.4 E-2 Xe 135 2.9E-2 Xe 137 2.0E-1 Xe 138 1.2E 1 EPSPROJ4demAasale/1 ort 7f 10-11

i LASALLE Revision 1.7 i September 1995 i

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LASALLE Rsvision 1.7 RE 10184002 (LOG)

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OF 4.000 CFM. BOTH TRAINS START LA8 j6 tid j ON AUTOMATIC SGTS ACTUATON.

ONE TRAIN CAN T)EN BE STOPPED MANUALLY IF DESIRED

• COUNTING 910 CFM ROCM l

RADWASTE em m 88370 CN _

' I HIGH RAD tij g 1r 1.000 CFM " $

SAMPLDIG SYSTEM OFFSTTE DOSE CALCULATION MANUAL l LASALLE COUNTY STATION l FIGURE 10-1 EPSPROJ4demAasale/10r1-7f 10-13 SIMPLIFIED GASEOUS RADWASTE AND GASEOUS EFFLUENT FLOW DIAGRAM (SHEET 2 OF 2)

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1 LASALLE RiviSion 1.7 Srptemb2r 1995 1

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- J OFFSITE DOSE CALCULATION MANUAL LASALLE COUNTY STATION .

LEGEND AND NOTES FIGURE 10-3

@ U0010 RADlATION MONITOR

$ FLOWELIMENT SIMPLIFIED LIQUID EFFLUENT FLOW DIAGRAM

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f A l LASALLE Revision 1.7 l ,

September 1995 CHAPTER 11 4

' O LaSaIIe Annex Index \

Pace Revision i l 11-i 1.7 l 11-ii 1.7 l 11-lii 1.7 l 11-iv 1.7 l 11-1 1.7 1 1 11-2 1.7 l 11-3 1.7 l l 11-4 1.7 )

I 11-5 1.7 l l 11-6 1.7 i l 11-7 1.7

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EPSPROJMdemAasale/11r17f 11.j

1 LASALLE Revision 1.7 l September 1995 e

CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS I

l l CHAPTER ILTLE PAGE 11 Radiological Environmental Monitoring Program 11 1 LIST OF TABLES NUMBER ILTLE PAGE 11-1 Radiological Environmental Monitoring Program 11 2 i

j l

1 LIST OF FIGURES i

NUMBER TITLE PAGE 11-1 Fixed Air Sampling Sites and Outer Ring TLD Locations 11 9 11-2 inner Ring TLD Locations 11 10 l l

11-3 Ingestion and Waterborne Exposure Pathway '

Sample Locations 11-11 9

O EPSPROJedemiasale/11ri 71 11-ii l

I

_=_ . . . _ . _ . ._ _ _ _ _ _ . _ _ . _ . _ . _ _ _ . _ _ _ _ _ _ . _ . . . _ _ . _ _ _ _ . _ . _ _ _ _ . . _._ . _ _ . _

I LASALLE Revision 1.7 4

l . September 1995

}*

CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i

f l LaSalle Station follows the Uniform Radiological Environmental monitoring Program which is described 1 in Chapter 9. This chapter identifies the site specific REMP for LaSalle Station.

I i l Supplemental tables describing reporting levels and LLDs/MDCs are included within Chapter 9 and I figures generally denoting LaSalle Station sample locations are contained herein.

I

)

l

)

O l EPsPROJ/odemAasale/11rt 7f 11 1

1 LASALLE Revision 1.7 I Septsmber 1995

. Table 11-1 Radiological Environmental Monitoring Program l

Exposure Pathway Sampling or Type and Frequency and/or Samole Samole or Monitorino Location Collection Frecuency of Analvsis l

t t

1. Airborne Continuous sampler l Radiciodine Canistem operation with sample l l Radiciodine and , a. Indicators-Near Field collection weekly, or more 1-131 analysis weekly on l Particulates frequently if required by near field and control l L-01, Nearsite No.1, 0.5 mi NNW (0.8 km R) dust loading. sa mples'.

l L-03, Onsite No. 3. 0.2 mi ENE (0.3 km D) l L-05. Onsite No. 5, 0.3 mi ESE (0.5 km F) Particulate Samoler:

L-06 Nearsite No. 6,0.4 mi WSW (0.6 km M) e Gross beta analysis I following weekly filter l change' and gamma isotopic analysis' quarterly j on composite filters by I location on near field and I control samples.

I b. Indicators-Far Field L-07, Seneca. 5.2 mi NNE (8.4 km B)

' L-08, Marseilles,6.3 mi NNW (10.1 km R)

L-11, Ransom 6.0 mi S (9.7 km J) l L-12, Kernan,5.0 mi SSW (8.0 km K) l 1 I

c. Controls I I L-10, Streator,13.5 mi SW (21.7 km L)

EPsPROJ/odemMasafte/11r1-7f 11-2 O O O. ..

m. m..__._, . _ _ . _ _ _ _ _ _ _ _ _ _ . . _ . . _ . _ . . . _ _ . - _ - _ . _ _ . . _ . _ . . _ _ _ . _

[ . .

1 LLE Rsvisi l l Septsmber 1995. i Table 11-1 (Cont'd) i

.. Radiological Environmental Monitoring Program l

e Exposure Pathway l l Sampling or Type and Frequency '

l and/or Samole l Samole or Monitorinti Location ,1 Collection Freauency j of Analysis

!  !  ! ~

T t

[

i 2. Direct Radiation j a. Indicators-Inner Ring .Ouarterly [ Gamma dose quarterl i

L- 101 -1, 0.5 mi N (0.8 km A) ^ l l

l L-101'-2 0.5 mi N (0.8 km A) 3 l L-102-1, 0.6 mi NNE (1.0 km 8) e l

i l L-102-2, 0.6 mi NNE (1.0 km B) l L-103- 1, 0.7 mi NE (1.1 km C) l l  !

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

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

l L- 104-2, 0.8 mi ENE (1.3 km D)  !

L-105- 1, 0.7 mi E (1.1 km E) i L- 105-2, 0.7 mi E (1.1 km E) ,

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

• l 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 L-108-2, 0.5 mi SSE (0.8 km H) i

! L-109-1, 0.6 mi S (1.0 km J) e l L-109-2, 0.6 mi S (1.0 km J) ,

I L-110-1, 0.6 mi SSW '

l (1.0 km K)

! L- 1 10-2, 0.6 mi SSW (1.0 km K)  ;

! L-111b-1, 0.8 mi SW (1.3 km L) l l L-111b-2, 0.8 mi SW (1.3 km L) l ,

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

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

j L-113a-1, 0.8 mi W (1.3 km N) I l L-113a-2, 0.8 mi W (1.3 km N)  !

i

! L-114-1, 0.9 mi WNW (1.4 km P) I g L-114-2, 0.9 mi WNW (1.4 km P) l l }

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

L-115-2, 0.7 mi NW (1.1 km 0) e L-116-1, 0.6 mi NNW (1.0 km R) e e l L-116-2, 0.6 mi NNW (1.0 km R) l l t

EPSPROJ/odemMasaue/11r17f 11-3

i I LASALLE Revision 1.7 I

Septamber 1995'-

t Table 11-1 (Cont'd)

.- Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency l and/or Samole L Samole or Monitorino Location Collection Frecuency of Analysis l 4- - -+

l 1 2. Direct Radiation ' b. Indicators-Outer Ring (Cont'd) L-201-3, 4.0 mi N (6.4 km A)

L-201 -4, 4.0 mi N (6.4 km A)

L-202-3, 3.6 mi NNE (5.8 km B) .

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-204 1, 3.5 mi ENE (5.6 km D)

[ L-204-2. 3.5 mi ENE (5.6 km D) *

' L-205- 1, 3.2 mi ESE (5.2 km F) g L-205-2, 3.2 mi ESE (5.2 km F)

L-205-3, 5.1 mi E (8.2 km E) e L-205-4 5.1 mi E (8.2 km E) l L-206- 1, 4.3 mi SE (6.9 km G) l '

L-206-2, 4.3 mi SE (6.9 km G)

• l L-207-1, 4.5 mi SSE

( (7.2 km H) l L-207-2, 4.5 mi SSE (7.2 km H)

L-208- 1, 4.5 mi S (7.2 km J) i  ;

L-208-2, 4.5 mi S (7.2 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 L-21 1 - 1, 4.5 mi WSW (7.2 km M)*

l L-21 1 -2, 4.5 mi WSW (7.2 km M)*

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 (7.9 km N)

L-213-4, 4.9 mi W (7.9 km N) l L-214-3, 5.1 mi WNW (8.2 km P)

L-214-4, 5.1 mi WNW

• l (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 O)

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

L-216-4, 5.0 mi NNW (8.0 km R) l

• TLD placement scheduled during 4th quarter 1995 l OJbdcm!!asalle/11rt -7f

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i LASALLE R: vision 1.7 I Septemb:r 1995 Table 11-1 (Cont'd)

.- Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Samole Samole or Monitorino location Collection Freauency of Analysis l 3. Waterborne l a. GroundM/ ell I a. Indicators Quarterly Gamma isotopic

• and tritium analysis quarterly.

I L-27, LSCS Onsite Well at Station l L-28, Marseilles Well, 7.0 mi NW (11.3 km O)

I l b. Drinkino Water There is no drinking water pathway within 6.2 km Weekly grab sample Gross beta and gamma 1 downstream of station. isotopic analysis' on monthly composite; tritium 1 analysis on quarterly l c. Surface Water a. Indicator composite.

l L-40, Illinois River downstream, Weekly grab sample Gross beta and gamma 1 5.2 mi NNW (8.4 km R) isotopic analysis' on i monthly composite tritium l and analysis on quarterly l composite.

I l d. Control a. Control Weekly grab sample Gross beta and gamma l isotopic analysis' on l L-21, Illinois River at Seneca, monthly composite tritium l 4.0 mi NE (6.4 km C) and analysis on quarterly l composite.

l e. Sediments a. Indicators Semiannually Gamma isotopic analysis' semiannually.

I L-40, Illinois River downstream,5.2 mi NNW (8.4 km R)

OJ/odem/lasalle/11rt -7f

L .,1LE RevisioAd l

September 1995 i

Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Sampling or Type and Frequency Exposure Pathway of Analysis Collection Frecuency and/or Samole Samole or Monitorino Location Biweekly: May through Gamma isotopic' and 1-131 1 4. Incestion October or monthly: analysis' biweekly May I

a. Indicators November through April through October, monthly I a. Milk November through April.

l l

At the time of this revisian, there are no dairies I

within 6.2 miles which consistently produce milk.

I b. Controls l

l L-16, Lowery Dairy,7.2 mi ESE (11.6 km F) l L-41, Burton Farm, 7.5 mi N (12 km A) l

a. Indicator Two times annually Gamma isotopic analysis' l b. Eish on edible portions of each L-35, Marseilles Pool of lilinois River, .

6.5 mi NW (10.5 km O)

I b. Control L-36, Illinois River upstream of discharge,4.3 mi NNE (6.9 km B) l c. Food Products a. Indicators 1

Two sample locations within 6.2 mi. Three times annually. Gamma isotopic analysis l

l on edible portions.

I Sample locations for food products may vary based I on availability and therefore are not required to be l identified here but shall be taken.

l l b. Controls l

l Two samples within 9.3 to 18.6 mi.

EPsPROJ/odcrrtiasaHe/11r17f jj.7

. _ _ _ _ _ _ _ _ _ _ _ . _ _ . - _ _ _ . . _ _ _ . _ . - _ . _ _ . _ _ _ _ . _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - - _ _ _ _ ___s

f I LASALLE Rsvision 1.7 l Septemb:r 1995 Table 11-1 (Cont'd)

. Radiological Environmental Monitoring Program l Far field samples are analyzed when near field results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents released from the station, or at the discretion of the Emergency Preparedness Director.

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

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

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

OJ/odentiasalle/11rt-7f

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

a LASALLE Revision 1.7 September 1995 O .

S Ottawa e

' l a!

=& C

- I Marseilles South  %

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L-216 4 = ==

y, L-216N-2013 L 201-4 L-215-4 "

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La seite county county , , , _

> I.Eringston county Air Sampling Location a TLD Location a LaSalle Station CPPSITE DOSE CALCULATION MANUAL

, ism LA SALLE COUNTY STATION

, 4 e e se unemen MRE 11-1 a

O .

FDED AIR SAMPUNG StTES AND ourER FUNGTLD LOCATIONS "A

Il'9 EPSPROJedemAasale/11ri-7I

LASALLE Revision 1.7 ,

l September 1995 j

~

31851 EE k\ g '

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EPSPROJ/odemAasale/11r1-7f 11 10

. LASALLE Revision 1.7 September 1995 O l.80

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~

• Fish INGESTION AND WATERBORNE EXPOSURE E Milk PATHWAY SAMPLE LOCATIONS cau.s

• Sediment

• Vegetables G Water 11-11

i -

j -g g i LASALLE Revision 1.7 l September 1995 2 e s

i i

l CHAPTER 12 I

l l

l t }

J l

i I l I lj e

SPECIAL NOTE The transfer of the Radiological Effluent Technical Specifications (RETS) to the ODCM has been approved by the Nuclear Regulatory Commission in Amendments 85/69.

l l

t EPSPROJ/odemAasab/12r17f 12 1

4 1 LASALLE Revision 1.7 1 ,

September 1995 -

LASALLE ANNEX INDEX CHAPTER 12 PAGE REVISION PAGE REVISION  !

I 12 -i 1.7 - 12 43 1.7 l 12 - ii 1.7 12 - 44 1.7 l 12 - iii 1.7 12 45 1.7 l 12 iv 1.7 12 - 46 1.7 l 12 - 1 1.7 12 - 47 1.7 l 12 - 2 1.7 l 12 - 3 1.7 l 12 4 1.7 l 12 - 5 1.7 l 12 - 6 1.7 1 12 - 7 1.7 l 12 - 8 1.7 l 12 - 9 1.7 l 12 - 10 1.7 l 12 - 11 1.7 l 12 - 12 1.7 ,

l 12 - 13 1.7 l 12 - 14 1.7 l 12 - 15 1.7 l 12 - 16 1.7 l 12 17 1.7 l 12 - 18 1.7 1 12 - 19 1.7 l 12 - 20 1.7 l 12 - 21 1.7 1 12 - 22 1.7 l 12 23 1.7 l 12 24 1.7 l 12 - 25 1.7 l 12 - 26 1.7 l 12 - 27 1.7 1 12 - 28 . 1.7 l 12 - 29 1.7 l 12 30 1.7 l 12 - 31 1.7 1 12 - 32 1.7 l 12 33 1.7 l 12 34 1.7 l 12 35 1.7 l 12 - 36 1.7 l 12 - 37 1.7 l 12 - 38 1.7 1 12 - 39 1.7 l 12 40 1.7 l 12 - 41 1.7 l 12- 42 1.7 EPSPROJ/odernAasale/12r17f 12 ii

I LASALLE Rsvision 1.7 A

- l Srptember 1995 l

CHAPTER 12 l O RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

TABLE OF CONTENTS 1

PAGE 12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS 12 1 12.1 DEFINITIONS 12-4 l I

12.2 INSTRUMENTATION 12-8  !

)

1. Radioactive Liquid Effluent Monitoring instrumentation 12 8

2. Radioactive Gaseous Effluent Monitoring instrumentation 12-13 12.3 LIQUID EFFLUENTS 12-19

1. Concentration 12 19 -

1

2. Dose 12-24

3. Liquid Wasta Treatment System 12 26 12.4 GASEOUS EFFLUENTS 12-27

1. Dose Rate 12 27

( 2.

3.

Dose - Noble Gases 12-31 Dose lodine-131, lodine-133, Tritium, and Radionuclides in Particulate Form 12-32

4. Gaseous Radwaste Treatment System 12-34  ;

5. Ventilat.on Exhaust Treatment System 12-35

6. Venting or Purging 12-36

7. Total Dose 12-37 l 8. Main Condenser 12 39 l 9. Dose Limits for Members of the Public 12-40 l 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-41 1 1. Radiological Environmental Monitoring Program 12-41 1 2. Land Use Census 12-42 l 3. Interlaboratory Comparison Program 12-43 12.6 REPORTING REQUIREMENTS 12 44 l

1. Annual Radiological Environmental Operating Report 12-44 l 2. Radioactive Effluent Release Report 12-45 1

3. Offsite Dose Calculation Manual (ODCM) 12-46

4. Major Changes to Radioactive Waste Treatment Systems 12 47 l

l l

O ,

EPSPROJ/odemMasale/12rt-7f 12-lii

1 LASALLE Revision 1.7 g l ,

S:ptemb r 1995 -

CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

LIST OF TABLES PAGE l 12.0 1 Effluent Compliance Matrix 12-2 l

l 12.0-2 REMP Compliance Matrix 12-3 1 12.1-1 Frequency Notation 12 7 12.2.1-1 Radioactive Liquid Effluent Monitoring Instrumentation 12-9 12.2.1-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 12 11 12.2.2 1 Radioactive Gaseous Effluent Monitoring instrumentation 12-14.

12.2.2 2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 12-16 12.3.1-1 Allowable Concentration of Dissolved or Entrained Noble Gases Release from the Site to Unrestricted Areas in Liquid Waste 12-20 12.3.12 Radioactive Liquid Waste Sampling and Analysis Program 12-21 12.4.1 1 Radioactive Gaseous Waste Sampling and Analysis Program 12 28 l

l i

l l

EPsPROJ/odemAasale/12ri-7f 12.jy

g i LASALLE Revision 1.7 l ,

SrptBmb3r 1995 l 12.0 ftADIOLOGICAL EFFLUENT TECHNICAL STANDARDS G I k,,,/ l Chapter 12 of the LaSalle Station ODCM is a compilation of the various regulatory I requirements, surveillances and bases, commitments and/or components of the radiological i effluent and environmental monitoring programs for LaSalle Station. To assist in the i understanding of the relationship between effluent regulations, ODCM equations, RETS 1 (Chapter 12 section) and related Technical Specification requirements, Table 12.01 is a matrix l which relates these various components. The Radiological Environmental Monitoring Program l fundamental requirements are contained within this chapter ano are explained programmatically l in Chapter 9 with LaSalle specific information in Chapter 11 and with a supplemental matrix in l Table 12.0-2.

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• l TABLE 12.01 l l

1 EFFLUENT COMPLIANCE MATRIX

\ l l Regulation Dose to be compared to Emit ODCM RETS Technical l Equation Specification i 10CFR50 1. gamma air dose and beta air dose A-1 12.4.2 6.2.F.4.h l Appendix 1 due to airbome radioactivity in A-2 l emuent plume.

l l 1.a whole body and skin dose due to l l airbome radioactivity in emuent A-6 N/A N/A l plume are reported only if certain A-7 ,

I l gamma and beta air dose criteria l are exceeded.

l l 2. CDE for all organs and all four age l groups due to iodines and l particulates in effluent plume. All A-13 12.4.3 6.2.F.4.1 l pathways are considered.

l l 3. CDE for all organs and all four age i groups due to radioactivity in Equid i emuenb.

l A-29 12.3.2 6.2.F.4.d l 10CFR20 1. TEDE, totaing all deep dose A-38 12.4.9 6.2.F.4.c l equivalent components (direct, l ground and plume shine) and l committed effective dose i equivalents (all pathways, both I airborne and Equid-borne). CDE l evaluation is made for adult only l using FGR 11 data base.

l 40CFR190 1. Whole body dose (DDE) due to A-35 12.4.7 6.2.F.4.k l (now by direct dose, ground and plume l reference, also shine from all sources at a station.

l part of .

A-13 l 10CFR20) 2. Organ doses (CDE) to an adult due I to all pathways.

l Technical 1. " Instantaneous" whole body (DDE), A-8 12.4.1 6.2.F.4.g l Specifications thyroid (CDE) and skin (SDE), dose A-9 1 rates to an adult due to A-28 l radioactivity in airborne effluents.

l For the thyroid dose, only I inhalation is considered.

l l 2. ' Instantaneous" concentration Emits A-32 12.3.1 6.2.F.4.b l for Equid effluents.

l Technical 1. Radiological Emuent Release NA 12.6.2 6.6.A.4 l Specifications Report EPSPROJ/odem/lasalle/12ri-7f 12-2

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l REMP Compliance Matrix l

l Regulation Component RETS Technical l Specification l 10CFR50 Implement environmental monitoring program. 12.5.1 6.2.F.5 l Appendix I I Section IV.B.2 l Technical Land Use Census 12.5.2 6.2.F.5.b I Specifications l Technical interlaboratory Comparison Program 12.5.3 6.2.F.5.c l Specifications I

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Sept 3mber 1995 .

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 channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAllBRATION shall encompass the entire channelincluding the alarm and/or trip functions, and shallinclude the CHANNEL FUNCTIONAL TEST. The CHANNEL CAllBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channelis calibrated.

12 1.3 CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channelindication and/or status with other indications ar'dior status derived from independent instrument channels measuring the same parameter.

1E.1.4 CHANNEL FUNCTIONAL TEST - A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signalinto the channel as close to the sensor as practical to verify OPERABILITY including alarm and/or trip functions and channel failure inps,

b. Bistable channels - the injection of a simulated signalinto the sensor to verify OPERABILITY 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 channelis tested.

12.1.5 DOSE EOUIVALENT l-131 - DOSE EQUIVALENT l 131 shall be that concentration of I 131 microcuries/ gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1132.1-133,1134 and 1135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table Ill of TID 14844,

" Calculation of Distance Factors for Power and Test Reactor Sites." )

1 1 12.1.6 FREOUENCY - Table 12.1-1 provides the definitions of various frequencies for which i surveillances, sampling, etc. are performed unless defined otherwise. The 25% variance shall I not be applied to Operability Action statements. The bases to Technical Specification 4.0.2 l provide clarifications to this requirement.

I 12.1.7 GASEOUS RADWASTE TREATMENT SYSTEM - A GASEOUS RADWASTE TREATMENT l 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.

I 12.1.8 MEMBERf S) OF THE PUBLIC - means an individual except when that individualis receiving I and occupational dose. j l 12.1.9 OCCUPATIONAL DOSE - means the dose received by an individualin the course of I employment in which the individual's assigned duties involve exposure to radiation and/or to I radioactive material from licensed and unlicensed sources of radiation, whether in the I possession of the licensee or other person. Occupational dose does not include dose from I

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i background radiation as a patient from medical practices, from voluntary participation in i l

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• l 12.1.10 OPERABLE - OPERABILITY - A system, subsystem, train, component or device shall be

"""^"'" '"""' ' ' " ^ ' ' ' " ' * " ' " " ' ' ' ' ' ' ' ' ' ' ' ' ' ' ' * ' " " ' " ' ' ' ' ' ' ' ' " " ' ' ' " ' ' ' '

CD and when all necessary attendant instrumentation, controls, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

I 12.1.11 PROCESS CONTROL PROGRAM - The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes shall be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

l 12.1.12 PURGE - PURGING - PURGE or PURGING Snall 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 required to purity the confinement.

I 12.1.13 RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3323 MWT.

l 12.1.14 SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

I 12.1.15 SOLIDIFICATION SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides O- (free-standing).

I 12.1.16 SOURCE CHECK - A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

I 12.1.17 THERM AL POWER - THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

I 12.1.18 UNRESTRICTED AREA BOUNDARY - means an area, access to which is neither limited nor controlled by the licensee.

l 12.1.19 VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radiciodine 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 iodines 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) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

I 12.1.20 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.

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I 12.1.21 Definitions Peculiar 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 public for the previous time period. This data is stored in the database and used to demonstrate compliance with the reporting requirements of Chapter 12.6.

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 public. This data is not incorporated into the database.

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Septembar 1995 TABLE 12.1-1 l FREQUENCY NOTATION

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

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

l W Weekly At least once per 7 days.

l M Monthly At least once per 31 days.

l 0 - Quarterly At least once per 92 days.

l SA Semiannually At least once per 184 days.

l A - Annually . At least once per 366 days.

l R Refueling cycle At least once per 18 months (550 days).

l S/U - Startup Prior to each reactor startup.

I P - Prior Prior to each radioactive release.

N.A. Not applicable.

l l

l Each frequency requirement shall be performed within the specified time interval with the maximum i allowable extension not to exceed 25% of the frequency interval. The 25% variance shall not be I applied to Operability Action statements. The bases to Technical Specification 4.0.2 provide ,

I clarifications to this requirement. I O ..

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12.2 INSTRUMENTATION 1

12.2.1 Radioactive Liould Effluent Monitorino Instrumentation Ocerability Recuirements 12.2.1. A The radioactive liquid effluent monitoring instrumentation channels shown in Table 12.2.1 1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Section 12.3.1.A are not exceeded. The alarm inp setpoints of these channels shall be determined in accordance with the ODCM Chapter 10.

Aeolicabilitv: At all times.

Action .

l

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid 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 Effluent Release Report why this inoperability was not corrected within the time specified.

Surveillance Recuirements 12.2.1.B Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CAllBRATION operations at the frequencies shown in Table 12.2.1-2.

Bases 12.2.1.C The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents dunng actual or potential releases of liquid 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 limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to 10 CFR Part 50.

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l 0

Nj TABLE 12.2.1-1 l

RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION l

1 l

( MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

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

a. Liquid Radwaste Effluent Line 1 100 l 2. GAMMA SCINTILLATION MONITORS PROVIDING ALARM BUT I NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE l a. Service Water System Effluent Line (Unit 1) 1 101 l b. RHR Service Water (Line A) Effluent Line 1 101 l c. RHR Service Water (Line B) Effluent Line 1 101

d. Service Water System Effluent Line (Unit 2) 1 101

3. FLOW RATE MEASUREMENT DEVICES I

l a. Liquid Radwaste Effluent Line 1 102 1

'O '

1

b. River Discharge - Blowdown Pipe 1 102 I

I 1 l

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RADIOACTIVE LIOUlO EFFLUENT MONITORING INSTRUMENTATION 1

TABLE 12.2.1-1 (Continued)

TABLE NOTATION l l

l 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 initiating a release:

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

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 101 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed i at a limit of detection as specified in Table 12.3 2.

ACTION 102 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, actual radioactive releases in progress via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Pump curves f l 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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l x enSALLE w cvision 1.7 l Septsmber 1995 TABLE 12.2.1-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL

! CHANNEL SOURCE' FUNCTIONAL CHANNEL INSTRUMENT CHECK CHECK TEST CALIBRATION

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

a. Liquid Radwaste Effluents Line D P O(1) R(3)

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

a. Service Water System Effluent 8.ine (Unit 1) D M O(2) R(3)

b. RHR Service Water (Line A) Effluent Line D M O(2) R(3)

c. RHR Service Water (Line B) Effluent Line D M O(2) R(3)

d. Service Water System Effluent Line (Unit 2) D M O(2) R(3)

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line D(4) N.A. P R

b. River Discharge - Blowdown Pipe D(4) N.A. O R EPSPROJ/odemMasalle/12rt-7f 12-11

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RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE 12.2.1-2 (Continued)

TABLE NOTATION (1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the 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. O (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference radioactive standards certified by the NationalInstitute of Standards and Technology (NIST)or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CAllBRATION, the initial reference radioactive standards or radioactive sources that have been related to the initial calibration shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days in which continuous, periodic, or batch releases are made.

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J-l l 12.2 INSTRUM ENTATION 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation j Ooerability Reauirements 1

12.2.2. A The radioactive gaseous effluent monitoring instrumentation channels shown in Table 12.2.2-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Section 12.4.1.A are not exceeded. The alarm / trip setpoints of these channels shall be l

determined in accordance with the ODCM.  !

l Acolienhilitv: As shown in Table 12.2.2-1.

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required, immediately suspend the release of radioactive j gaseous effluents monitored by the affected channel or declare the channelinoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2.21.

Surveillance Reauirements J

{ 12.2.2.B Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated i OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in 4

O V

Table 12.2.2-2.

Bases l

i 12.2.2.C The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of RETS.

l l

b

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i LASALLE R , vision 1.7 I S pt3mber 1995 TABLE 12 23;.1 .

RADIOACTIVE GASEOUS EFFLUENT MCNITORING INSTRUMENTATION 1 MINIMUM '

CHANNELS l IN STRUM EN T' OPERABLE APPLICABILITY ACTION

1. MAIN CONDENSER OFFGAS TREATMENT SYSTEM

EFFLUENT MONITORING SYSTEM l a. Noble Gas Activity Monitor - Providing l

Alarm and Automatic Terminetion of Release 1 110 l (1(2) D18-N003A, K901 A, K601 A, R601) and/or l (1(2) D18-N903B, K9018. K601B, R601)

2. MAIN STACK MONITORING SYSTEM i a. Noble Gas Activity Monitor (OD18-N514 R517, R518 Low Range 1 110 l WRGM) or (OD18-N515 R517. R518 Mid Range WRGM)

I l b. Iodine Sampler (Grab Sampler) 1 111 l c. Particulate Sampler (Grab Sampler) 1 111 I d. Effluent System Flow Rate Monitor (OFT-VR019,0FY-VR019 and 19A, 1 OFR-VR019, OD18 K510) 1 112 l e. Sampler Flow Rate Monitor (Low: OD18-N527, OD18-N528, OD18-R518; 1 112 l Mid/Hi: OD18-N530, OD18-531, OD18-R518)

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

I a. Noble Gas Activity Monitor (1(2) D18-N002, K613, R604) 1 # 113 l (1(2) D18-N012 K600, R605)

4. SBGTS MONITORING SYSTEM l a. Noble Gas Activity Monitor (0D18-N511, R515 R516 Low Range WRGM) 1 ## 110 or (0D18-N512, R515, R516 Mid Range WRGM)

I b. lodine Sampler (Grab Sampler) 1 ## III l c. Particulate Sampler (Grab Sampler) 1 ## 111 I d. Effluent System Flow Rate Monitor (1(2)FT-VG009,1(2)FY-VG009, 1 ## 112 l 1(2)FR-VG009)

I e. Sampler Flow Rate Monitor (OD18-N520 WRGM; Low: OD18-N521, Mid/Hi: 1 ## 112 l OD18-N524)

Equpment Part Number (EPN) numbers or monitor types are provided in parentheses *( }".

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September 1995 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION O{ TABLE 12.2.2-1 (Continued)

TABLE NOTATION At all times.

During main condenser offgas treatment system operation.

1. During operation of the main condenser air ejector.

1. 1. During operation of the SBGTS.

1 ACTION 110 - For the Main Condenser Offgas Treatment System Effluent Monitoring System and low /mid I range of WRGMs:

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for noble gas gamma emitters within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l l

ACTION 111 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment as required in Table 12.4.1-1.

ACTION 112 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided:

a. The offgas treatment system is not bypassed, and

b. The offgas treatment delay system noble gas activity effluent downstream monitor is OPERABLE; Otherwise, be in at least STARTUP with the main steam isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

NOTE: Clarification: Even though only 1 channelis required by Tech Specs, in order to provide automatic termination of release (i.e. to auto close 1(2)N62-F057),1 out of 3 twice logic is required (i.e. 2 channels). One channel uses the 1(2)A Post Treatment PRM Hi',

Downscale, 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.)

l lO l

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I LASALLE R: vision 1.7 l Srptember 1995 TABLE 12.2.2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVElLLANCE REQUIREMENTS OPERATIONAL CHANNEL CONDITIONS FOR CHANNEL SOURCE FUNCTIONAL CHANNEL WHICH SURVEIL-INSTRUMENT CHECK CHECK TEST C Alf BR ATION LANCE REQUIRED

1. MAIN CONDENSER OFFGAS TREATMENT SYSTEM EFFLUENT MONITORING SYSTEM

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release D D O(1) R(3)

2. MAIN STACK MONITORING SYSTEM i a. Noble Gas Activity Monitor D M O(4) R(3)

b. lodine Sampler W N.A. N.A. N.A. *

c. Particulate Sampler W N.A. N.A. N.A. *

d. Effluent System Flow Rate Monitor D N.A. O R

e. Sampler Flow Rate Monitor D N.A. O R

3. CONDENSER AIR EJECTOR RADIOACTIVITY MONITOR

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

4. SBGTS MONITORING SYSTEM

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

b. lodine Sampler W N.A. N.A. N.A. ##

c. Particulate Sampler W N.A. N.A. N.A. ##

d. Effluent System Flow Rate Monitor D N.A. O R ##

e. Sampler Flow Rate Monitor D N.A. O R ##

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1 1 l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE l 9

O- REQUIREMENTS TABLE 12.2.2-2 (Continued) j l

TABLE NOTATION 1

At all times.  !

1. During operation of the main condenser air ejector.

1. 1. During operation of the SBGTS. I (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation capability of I this pathway for the fol. lowing conditions:

1 1 1. Upscale. I i

l 2. Inoperative. l l

l 3. Downscale. I I

(2) The CHANNEL FUNCTIONAL TEST for the log scale monitor shall also demonstrate that I control room alarm annunciation occurs for the following conditions:

,O- l 1. Upscale.

l 2. Inoperative.

i 3. Downscale.

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

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RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE 12.2.2 2 (Continued)

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

1

1. Instrument indicates measured levels above the alarm setpoint.

I 2. Loss of Counts l

I 1

9 l

l

= 0 EPSPROJedemAasale/12ri 7f 12-18

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September 1995 12.3 LIQUID EFFLUENTS f

l 12.3.1 Concentration Onerability Raouirements 12.3.1. A The concentration of radioactive material released from the site shall be limited to ten (10) times the concentration value in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402 for radinnuclides other than dissolved or entrained noble gases. For dissolved or entrained noDie gases, the concentration shall be limited to the concentrations specified in Table 12.3.1 1.

1 Anolicability: At all times.

Aralan With the concentration of radioactive material released from the site exceeding the l above limits, immediately restore the concentration to within the above limits.

Surveillance Raouirements 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by samphng and analysis in accordance with Table 12.3.12. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits 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 k 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 limits of Section 12.3.1.A.

12.3.1.B.3 The radioactivity concentration of liquids discharged from continuous 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 hmits of Section 12.3.1.A.

I 12.3.1.B.4 Identify outside temporary liquid holdup tanks within the site and restrict the I quantity of radioactive material contained in specified tanks to provide assurance l that in the event of an uncontrolled release of the tanks contents, the resulting I concentrations would be less than the limits of Section 12.3.1.A. Refer to LaSalle I Technical Specification 3/4.11.1.

l Bases 12.3.1.C This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than ten (10) times the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR20.10012402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposure within (1) the Section ll.A design objectives of Appendix 1,10 CFR 50, to an I individual, and (2) the limits of 10 CFR 20.1301 to the population. In addition, this l limit is associated with 40 CFR 141 which states concentration limits at the nearest I downstream potable water supply.

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Septsmber 1995 -

l .

TABLE 12.3.1-1 ALLOWABLE CONCENTRATION (AC) OF  !

l DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE l

NUCLIDE AC(uCi/mt)*

Kr 85 m 2E-4 85 SE-4 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 2E-4 Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion in water, and R - 0.01 rem / week, p, - 1.0 gm/cm', and PJP, - 1.0.

EPSPR.OJedem4asale/12r17f 12 20

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1 1

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

LIQUID SAMPLING MINIMUM TYPE OF LOWER LIMIT OF l RELEASE TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD) l FREQUENCY ANALYSIS (pCi/ml)' ,

A. Batch Waste P P Principal Gamma 5x10 Release Each Batch Each Batch ' Emitters' l-131 .1x10*

P M Dissolved and 1x10 4 l i

One Batch /M Entrained Gases (Gamma Emitters)

P M H3 1x10 4 Each Batch Composite * ,,

l P O St-89, Sr-90 5x10* )

Each Batch Composite

• Fe-55 1x10 4

2. Continuous Continuous

• Composite

• Principal Gamma 5x10 Releases' Emitters' l-131 1x10*

4 M M Dissolved and 1x10 Grab Sample Entrained Gases (Gamma Emitters) )

4 Continuous' M H3 1x10 Composite

• Gross Alpha 1x10"

' Continuous

• O Sr 89, Sr 90 5x10*  ;

Composite' l Fe-55 1x10*

l I

l O .

EPSPROJ/odemAasate/12r1-7f 12 21

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S:ptemb:r 1995 ,

l 1

RADIOACTIVE LfOUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE 12.31-2 (Continued)

I 7 ABLE NOTATION l

a. The LLD is the smallest concentration of radioactive materialin a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal l l

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

4.66 s.

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

Where:

LLD is the "a priori" tower limit 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 t'io counting efficiency (as counts per transformation),

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

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

A is the radioactive decay constant for the particular radionuclide 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 shall be based on the actual observed vanance 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. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of samp's employed results in a specimen which is representative of the liquids released.

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.I Septemb2r 1995 A RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM V

TABLE 12 31-2 (Continued)

TABLE NOTATION

c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, 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 l order for the composite sample to be representative of the effluent release,

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

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

J

f. The principal gamma emitters for which the LLD specification applies exclusively are the i following radionuclides: Mn 54, Fe-59, Co 58, Co-60, Zn 65, Mo-99, Cs 134, Cs-137, Ce-141, )

and Ce 144. This list does not mean that only these nuclides are to be detected and reported.

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

l D

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September 1995 -

I 12.3 LIQUID EFFLUENTS I 12.3.2 Dose Ooerability Recuirements 12.3.2. A The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site shall be limited:

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

b. During any calendar year to less than to equal to 3 mrem 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 liquid effluents exceeding any of the above limits, 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 identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and dunng the subsequent three calendar quarters, '

so that the cumulative dose or dose commitment to an individual from these releases is within 3 mrem to the total body and 10 mrem to any organ.

This Special Report shall also include the radiologicalimpact on finished drinking water supplies at the nearest downstream drinking water source.

Surveillance Reouirements 12.3.2.B Dose Calculations Cumulative dose contnbutions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days, when liquid discharges are performed.

Bases 12.3.2.C T.his requirement is provided to implement the requirements of Sections ll.A, Ill.A and IV.A of Appendix 1.10 CFR Part 50. The Limiting Condition for Operation implements to guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies i which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide ,

concentrations in the finished drinking water that are in excess of the l requirements of 40 CFR 141. The dose calculations in the ODCM implement the ,

requirements in Section Ill.A of Appendix ! that conformance with the guides of ,

Appendix l be shown by calculational procedures based on models and data, '

such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM EPSPROJedemAasalle/12r17f 12-24

I LASALLE Rsvision 1.7.

'I Septembsr 1995 a

for calculating the doses due to the actual release rates of radioactive materials in O

liquid effluents are consistant with the methodology provided in Regulatory Guide 1.109," Calculation of Annual Doses to Man from Routine Releases of Reactor  ;

Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," Ap'il 1977.

This requirement applies to the release of radioactive materials in liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared are proportioned among the units sharing that  ;

system. l 1

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1 O

i I

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EPSPROJedemAasate/12r1-7f 12-25 .

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I LASALLE Revision 1.7 i

September 1995 -

l 12.3 LIQUID EFFLUENTS l 12.3.3 Liquid Waste Treatment System Ooerability Recuirements 12.3.3. A The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid 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 mrem to any organ.

Aeolicabilitv: At all times.

Action

a. With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits,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 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.

Surveillance Recuirements 12.3.3.B.1 Doses due to liquid releases shall be projected at least once per 31 days or when 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 opera;ing the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

Bases 12.3.3.C The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." 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 ll.0 of Appendix 1 to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10 CFR Part 50, for liquid effluents.

EPSPROJ/odemAasalle/12r17f 12-26

-l LASALLE Revision 1.7

-l Septembsr 1995 12.4 GASEOUS EFFLUENTS

( l 12.4.1 Dose Rate Ooerability Reauirements 12.4.1.A The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY, shall be limited to the following:

a. For noble gases: Less than or equal to a dose rate of 500 mrem /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 e" radionuclides in particulate form with half lives greater than 8 days' ' ess than or equal to a dose rate of 1500 mrems/yr to any organ via the inh w : ,4thway.

Anolicabilitv: At all times.

Action With the dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s).

Surveillance Raouirements 12.4.1.B.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM.

O V 12.4.1.B.2 The dose rate due to iodine 131, iodine-133, tritium, and all radionuclides in l

particulate form with half lives greater than eight days, in accordance with the methodology and parameters of the ODCM by obtaining representative samples l and performing analyses in accordance with sampling and analysis program specified in Table 12.4.1 1.

Bases 12.4.1.C This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of RETS for unrestricted areas. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents I will not result in the exposure of an individualin an unrestricted area, either within or outsioe the site boundary exceeding the limits specosd in 10CFR20.1301. For individuals who may at times be within the site boundary, 'he occupancy of the individual will be sufficiently low to compensate for any incraase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to a dose rate of 500 mrem / year to the total body or to less than or equal to a dose rate of 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to a dose rate of 1500 mrem / year.

This specification applies to the release of radioactive effluents in gaseous effluents from all reactors at the site. For units within shared radwaste treatment g -,

systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

EPSPROJ/odemAasaue/12r1-7f 12-27

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Stptember 1995 -

TABLE 12.4.1-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 1

1 GASEOUS RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT OF l TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD)

FREQUENCY ANALYSIS (pCi/ml)'

A. Containment P P Principal Gamma 1x10*

Vent and Purge Each Purge' Each Purge' Emitters' System' Grab Sample H3 '1x10 4 B. Main Vent Stack M M' Principal Gamma 1x10" Grab Sample Emitters' H3 1x10*

1 x 10-7 d

C. Standby Gas D' W' Principal Gamma 1x10 Treatment Grab Sample Emitters' System Continuous' W' l-131 1 x 10

Charcoal D. All Release Sample 1131 1 x 10

Types as listed in ,

A and B above, Continuou?' W' Poncipal Gamma 1 x 10'" I at the Vent Particulate Emitters' Stack, and as Sample (1 131, Others) l listed in C above, I Continuous' M Gross Alpha 1 x10-" l at the SBGTS '

Compos,i e henever there Sample Continuous' O Sr 89.Sr 90 1 x 10'"

Composite Particulate Sample Continuous' Noble Gas Noble Gases 1x10' Monitor Gross Beta & (Xe 133 equivalent)

Gamma EPSPROJ6demAasale/12r17f 12 28

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] LASALLE Revision 1.7

.l September 1995 i -

- J TABLE 12.4.1-1 (Continued) 5 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 1

! TABLE NOTATION <

i l l a. The LLD is the smallest concentration of radioactive materialin a sample that will be detected 4 with 95% probability with 5% probability of falsely concluding that a blank observation ,

represents a "real" signal. l For a particular measurement system (which may include radiochemical separation):

j 4.66 s, i

] LLD = E . V . 2.22x10' . Y . exp (-Aat) j Where:

! LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or

! volume),

) 4 i 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),

4 4 *

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 radiochemical yield (when applicable),

1 is the radioactive decay constant for the particular 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 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. Typical values of E, V, Y, and At shall be used in the calculation,

b. Analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.

If there are several power transients that exceed 15% , the off gas sample may be delayed until after the last transient provided it is within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the first transient (See Technical l Specification clarification 01/87 (p.17) 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period then it must be run a minimum of 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> run is required to meet the sample requirements for iodine and particulates.)

EPsPROJ6dem4asale/12r17f 12-29

I LASALLE Revision 1.7 l' .

September 1995 TABLE 12.4.1-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION

d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding 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 fuelis in the spent fuel pool.

f. The ratio of the sample flow rate to the sampled stream flow rate shall be k1own for the time period covered by each dose or dose rate calculation made in accordance wnu Sections 12.4.1.A 12.4.2.A and 12.4.3.A.

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

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

h. The drywell tritium and noble gas sample results are valid for 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> from sample time if 1) the drywell radioactivity monitors have not indicated an increase in airborne or gaseous radioactivity, and 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 Gny reason to suspect that gaseous radioactivity levels have changed in the drywell since the last sample (30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />), 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 Durced in accordance with Technical Specification definitions, both noble gas and tntium 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)

O EPsPROJ/odemAasale/12ri-71 12-30

l l LASALLE Revision 1.7 I- September 1995 l ,

- l 12.4 GASEOUS EFFLUENTS i ('

! I 12.4.2 Dose Noble Gases J

Ooerability Raouirements

. 12.4.2.A The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site shall be limited to the following:

1 l a. During any calendar quarter: Less than or equal to 5 mrad for gamma

! radiation and less than or equal to 10 mrad for beta radiation, and

. b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for fxta radiation.

Anolit nhilitv

At all times.

A.cito.a l

a. With the calculated air dose from radioactive . mole gases in gaseous effluents exceeding any of the above limits, 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 identifies the cause(s) for I

exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to  ;

assure that subsequent releases will be in compliance with the above l limits.

Surveillance Reauirements I O 12.4.2.8 Dose Calculations Cumulative dose contributions for the current calendar l

quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

Bases 12.4.2.C This specification is provided to implement the requirements of Sections 11.B, Ill.A and IV.A of Appendix I,10 CFR Part 50. The Operability Requirements are the guides set forth in Section ll.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releases of radioactive materialin gaseous effluents will be kept as low as is reasonably l achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix l be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropnate pathways is unlikely to be substantially underestimated. The dose calculations estab!!shed in the ODCM l for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Dosos to Man from Routine Releases of Reactor Effluents for the Purpose of Eva?uating Compliance with 10 CFR Part 50. Appendix 1," Revision 1. October 1977 end 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.

Dr EPsPROJedcm4asale/12rt.7f 12-31 l

l LASALLE Revision 1.7 I

September 1995 -

l I

l 12.4 GASEOUS EFFLUENTS I 12.4.3 Dose - lodine-131, lodine 133, Tritium, e Radionuclides in Particulate Form l

Ooerability Reauirements  ;

12.4.3.A The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous eff!uents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited 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 or equal to 15 mrems to any organ.

Aeolicability: At all times.

Action

a. With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu 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 limits.

Surveillance Recuirements 12.4.3.B Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Bases 12.4.3.C The specification is provided to implement the requirements of Sections ll.C, l Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements l are the guides set forth in Section ll.C of Appendix 1. The ACTION statements I 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 will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely 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 methodology provided in Regulatory Guide 1.109," Calculation of Annual Doses EPsPROJ/odem4asale/12r17f 12-32

-l LASALLE Revision 1.7

-l Septembsr 1995 s

to Man from Routine Releases of Reactor Effluents for the Purpose of O Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1 October b 1977 and Regulatory Guide 1.111," Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions, The release rate specifications for radiciodines, radioactive materials in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1)individualinhalation of airborne radionuclides l2).

deposition of radionuclides 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, v

a a

e e

EPSPROJ/odemAasale/12rt 7f 12-33

I LASALLE Revision 1.7 l September 1995 -

l 12.4 GASEOUS EFFLUENTS l 12.4.4 Gaseous Radwaste Treatment System Ooerability Recuirements 12.4.4. A The GASEOUS RADWASTE (OFF-GAS) TREATMENT SYSTEM shal! be in operation.

Acolicability: Whenever the main condenser rir ejectoi system is ln operation.

AC.110D

a. With the GASEOUS RADWASTE (OFF-GAS) TREATMENT SYSTEM inoperable for more than 7 days, 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 inoperabihty.

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 Recuirements 12.4.4.8 The GASEOUS RADWASTE TREATMENT SYSTEM shall be verified to be in operation at least once per 7 days.

Bases 12.4.4.C The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable" This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section ll,0 of Appendix I to 10 CFR Part

50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.3 and 11.0 of Appendix 1,10 CFR Part 50, for gaseous effluents.

.- O EPsPROJedemAasaBe/12ri.7f 12-34

[ LASALLE R: vision 1.7 I S:ptember 1995 l 12.4 GASEOUS EFFLUENTS O

l 12.4.5 Ventilation Exhaust Treatment System Ooerability Reauirements 12.4.5.A The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and be used to reduce radioactive materials in gaseous waste prior to their discharge 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. I i Aeolicability: At all times.

Action With the VENTILATION EXHAUST TREATMENT SYSTEM inoperab!e for more

, than 31 days, and with gaseous waste being discharged without treatment and i

! in excess of the above limits,in lieu of any other report required by LaSalle l

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

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

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

status, and j 3. Summary description of action (s) taken to prevent a recurrence.

1 Surveillance Reauirements i

l 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.

t i 12.4.5.B.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated l OPERABLE by operating the VENTILATION EXHAUST TREATMENT SYSTEM l 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.

Bases i

12.4.5.C The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and l j the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system I will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of l these systems be used, when specified, provides reasonable assurance that the i releases of radioactive materials in gaseous effluents will be kept "as low as is i

reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 1

50, and the design objectives given in Section 11,0 of Appendix l to 10 CFR Part

50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.3 and 11.0 of Appendix 1,10 CFR Part 50, for gaseous effluents.

EPSPROJ/odemAssaBe/12r17f 12 35

l LASALLE Revision 1.7 l- ,

Septemb:r 1995 -

l 12.4 GASEOUS EFFLUENTS l 12.4.6 Venting or Purging i Ooerability Reauirements 12.4.6. A VENTING or PURGING of the containment drywell shall be through the Primary Containment Vent and Purge System or the Standby Gas Treatment System.

Anoticability: Whenever the drywell is vented or purged.

Action

a. With the requirements of the above specification not satisfied, suspend all VENTING and PURGING of the drywell.

1 Surveillance Recuirements 12.4.6.B.1 The containment drywell shall be determined to be aligned for VENTING or ,

PURGING through the Primary Containment Vent and Purge System or the j Standby Gas Treatment System within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to start of and at least <

once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING of the drywell.

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. Both Standby Gas Treatment System trains are OPERABLE, and

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

Bases 12.4.6.C This specification provides reasonable assurance that releases from drywell purging operations will not exceed the annual dose limits of 10CFR20 for unrestricted areas. I I

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EPsPROJ/odemAasale/12rt-7f 12-36

l LASALLE Revision 1.7

-l ,

Septemb2r 1995 4

l 12.4 GASEOUS EFFLUENTS i 12.4.7 Total Dose Ooerability Raouirements j 12.4.7.A The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less or equal to 75 mrem) over 12 consecutive months.

Anolicabilitv: At all times.

8C110D l

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits 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 lieu of any other report required by LaSalle Technical Specification 6.6.A, prepare and submit, pursuant to LaSalle Technical Specification 6.6.C, a Special Report 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 limits of 1 Section 12.4.7.A. This Special Report shallinclude an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle h}

V sources (including all effluents pathways and direct radiation) for a 12 consecutive month penod that includes the release (s) covered by this report. If the estimated dose (s) exceeds the limits 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 shall include a request for a variance in accordance with the I provisions of 40 CFR 190 and including the specified information of 40 CFR 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 limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification. j 1

Surveillance Recuirements l 12.4.7 B Dose Calculations - Cumulative dose contnbutions from liquid and gaseous effluents shall be determined in accordance with Sections 12.3.2.B 12.4.2.8 and 12.4.3.B. and in accordance with the ODCM.

Bases 12.4.7.C This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report ,

whenever the calculated doses f rom plant radioactive effluents exceed twice the I design objective doses of Appendix 1. For sites containing up to 4 reactors,it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting O '

requirement level. The Special Repor1 will describe a course of action which should result in the limitation of dose to a member of the public for 12 EPSPROJ/odemAasaBe/12rt.7f 12 37

I LASALLE Retrision 1.7 I September 1995 -

consecutive months to within the 40 CFR 190 limits. For the purpose of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 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 violation 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 fulfills the requirements of 40 CFR 190 until NRC staff action is completed. An individualis not considered a member of the public during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.

O l

. O EPSPROJ/odemAasale/12r17f 12-38

. 1

-l LASALLE Revision 1.7

-l September 1995 12.4 GASEOUS EFFLUENTS l 12.4.8 Main Condenser l

l Ooerability Reauirements I

l 12.4.8.A The release rate of the sum of the activities from the noble gases measured I prior to the holdup line shall be limited to less than or equal to 3.4 x 10' l microcuries/second.  ;

I l Anolicability Operational Conditions 1,2 and 3.

I I Achcn-1 l With the release rate of the sum of the activities from the noble gases prior to I the holdup line exceeding 3.4 x 10' microcuries/second, restore the release rate I to within its limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least STARTUP with the main )

I steam isolation valves closed within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. I I l l Surveillance Reauirements I

l 12.4.8.B.1 The radioactivity rate of noble gases prior to the holdup line shall be I continuously monitored in accordance with the ODCM and Table 12.2.2-2.

l l 12.4.8.B.2 The release rate of the sum of the activities from noble gases prior to the I holdup line shall be determined to be within the limits of specification 12.4.8.A I at the following frequencies by performing an isotopic analysis of a

( l representative sample of gases taken prior to the holdup line.

I l a. At least once per 31 days.

l l b. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following an increase, as indicated by the off gas pre.

I treatment Noble Gas Activity Monitor, of greater than 50%, after I factoring out increases due to changes in THERMAL POWER level, in I the nominal steady state fission gas release from the primary coolant.

I Bases l 12.4.8.C in accordance with surveillance requirements contained within ODCM Chapter 1 < 12 item number 12.4.8.B.1 and 2, this specification provides reasonable l assurance that the releases from the main condenser will not exceed the I requirements of the LaSalle Technical Specifications 3/4.11.2.2. In addition, a

! sample is required within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if the increase is not due to thermal power I changes. If the cause is known and not fuel related and less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in I duration, then no sample is required. [This is based on interpretation letter from l W. R. Huntington to Operating Engineers, Shift Engineers and F.R. Lawless, I dated May 24,1984.)

O EPsPROJ/odemAasale/12r17f 12 39

a i i

I LASALLE Revision 1.7 i I ,

Septemb2r 1995 .

Dose Limits for Members of the Public I I 12.4.9 Ooerability Reauirements l

l 12.4.9. A The licensee shall conduct operations such that the TEDE to individual 1 MEMBERS OF THE PUBLIC does not exceed 100 mrem in a year. In addition, I the dose in any unrestricted area from external sources does not exceed 2 mrem I in any one hour. The Effluents Program shallimplement monitoring, sampling, I and analysis of radioactive liquid and gaseous effluents in accordance with 1 10CFR20.1302 and with the methodology and parameters in the ODCM.

l l Annlicability: At all times.

l l Action l

l 1. If the calculated dose from the release or exposure of radiation meets or I exceeds the 100 mrem / year limit for the MEMBER OF THE PUBLIC, prepare l and submit a report to the Commission in accordance with 10CFR20.2203.

l l 2. If the dose in any unrestricted area from external sources of radiation meets I or excesos the 2 mrem in any one hour limit for the MEMBER OF THE I PUBLIC, prepare and submit a report to the Commission in accordance with l 10CFR20.2203.

l l Surveillance Reauirements l

l 12.4.9.B Calculate the TEDE to individual MEMBERS OF THE PUBLIC annually to I determine compliance with the 100 mrem / year limit in accordance with the l ODCM. In addition, evaluate and/or determine if direct radiation exposures i exceed 2 mrem in any hour in unrestricted areas.

l l Bases I

i 12.4.9.C This section applies to direct exposure of radioactive materials as well as I radioactive materials released in gaseous and liquid effluents.10CFR20.1301 I sets forth the 100 mrem / year dose limit to members of the public; 2 mrert in any I one hour limit in the unrestricted area; and reiterates that the licensee is also l required to meet the 40CFR190 standards.10CFR20.1302 provides options to I determine compliance to 10CFR20.1301. Compliance to the above operability l requirement is based on 10CFR20,40CFR190 and LaSalle Station Technical I . Specifications.

EPSPROJ/odemAasale/12r17f 12-40

1 l LASALLE Revision 1.7 i

. l September 1995 i 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM eO l 12.5.1 Radiological Environmental Monitoring Program Ooerability Reauirements

/

12.5.1. A The radiological environmental monitoring program shall be conducted as I specified in Table 9.1 1 of Chapter 9.

Acoliemhilitv: At all times Actio.n

a. With the radiological environmental monitoring program not being conducted l as specified in Table 9.1-1 of Chapter 9 and Chapter 11, see Chapter 9 for l required actions.

Surveillance Reauirements 12.5.1.B The radiological environmental monitoring program samples shall be collected I pursuant to Table 9.1-1 of Chapter 9 and Chapter 11, see Chapter 9 for detailed l surveillance requirements.

Bases 12.5.1.C The radiological environmental monitoring program required by this specification

( }

provides measurements of radiation and of radioactive materials in those N/ exposure pathways and for those radionuclides which lead to the highest potential I radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. See Chapter 9 for further information, in addition, this requirement is stated in Technica: Specification 6.2.F.5.

1 EPsPROJ/odemAasale/12r17f 12 41 l

1

l LASALLE Revision 1.7 i l .

September 1995

• I 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l 12.5.2 Land Use Census ooerability Reauirements l 12.5.2. A A land use census shall be conducted to ensure changes in the use of areas at I and beyond the SITE BOUNDARY are identified and that modifications to the l l monitoring program are made if required by the results of this census. l Acolicabilitv: At all times Action I a. See Section of 9.2 of Chapter 9 for required actions.

Surveillance Reauirements ,

1 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 will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local I agriculture authorities. See Section of 9.2 cf Chapter 9 for required surveillances.

l Bases l 12.5.2.C See Section of 9.2 of Chapter 9 for required surveillances and Technical i

! Specification Section 6.2.F.5.b for more bases details.

l l

l l

l i

EPsPROJedemAasalle/12r17f 12-42

I LASALLE Revision 1.7

• I ,

September 1995 I

O l 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM V

l 12.5.3 Interlaboratory Comparison Program Ooerability Reauirements a

j l 12.5.3.A Participation in an interlaboratory Comparison Program to ensure that 1 independent checks on the precision and accuracy of the measurements of I radioactive materials in environmental sample matrices are performed as part of I the quality assurance program for environmental monitoring.

Acolicabilitv: At alt times Ac.tton

1. 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 2. See Section 9.2 of Chapter 9 for required actions.

Surveillance Reauirements I 12.5.3.B 1. See Section 9.2 of Chapter 9 for surveillance requirements.

Bases V l 12.5.3.C See Section 9.2 of Chapter 9 for more information. In addition, this requirement I is stated in Technical Specification Section 6.2.F.c.

4 O ,

EPSPROJ/odemAasaW12r17f 12-43

I LASALLE Revision 1.7 September 1995 a l

12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radiological Environmental Operating Report' l

Ooerability Recuirements 12.6.1. 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 I year.

Anolicability: At all times Action l 1. See Section 9.2 of Chapter 9 for required actions.

l l Surveillance Recuirements I

l 12.6.1.8 1. See Section 9.2 of Chapter 9 for surveillance requirements.

l l Bases I

i 12.6.3.C See Section 9.2 of Chapter 9 for more information. In addition, this requirement I is stated in Technical Specification Section 6.6.A.3.

l .

I l

O1 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.

EPSPROJ/odemAasale/12r17f 12-44

1 1

-l LASALLE Revision 1.7 j f

• l September 1995 l 1

12.6 REPORTING REQUIREMENTS Ci l 12.6.2 Radioactive Effluent Release Recort'

a. Routine radioactive effluent release reports covering the operation of the unit during the  ;

previous calendar year of operation shall be submitted according to the Technical Specifications. The period of the first report shall begin with the date of initial criticality,

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

c. The radioactive effluent release report shallinclude the following information for each type of solid waste shipped offsite during the report period:

1. Container volume,

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

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

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

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

6. Solidification agent (e.g., cement, urea formaldehyde).

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

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

l 'A single submittal may be made for a multiple unit station. The submittal should combine those I 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 to annualis approved by the NRC in the LaSalle Technical Specifications.

t U '.

1 l

I EPsPROJedemAasa8el12t17f 12-45

e l LASALLE R:: vision 1.7 1 ,

September 1995

• 12.6 REPORTING REQUIREMENTS 12.6.J Offsite Dose Calculation Manual (ODCMP 12.6.3.1 The 'ODCM shall be approved by the Commission prior to implementation.

12.6.3.2 Licensee-initiated changes to the ODCM:

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

1. Sufficient information to support the change 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 I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

a. Shall become effective after review and acceptance by the Onsite Review and investigative Function and the approval of the Plant Manager on the date specified by the Onsite Review and investigative Function,

b. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or 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 markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month / year) the change was implemented.

'The OFFSITE DOSE CALCULATION MANUAL (ODCM) is common to LaSalle Unit 1 and LaSalle Unit 2.

I EPsPROJ/odemAasale/12r17f 12 46

o l LASALLE Revision 1.7

.l September 1995 12.6 REPORTING REQUIREMENTS

/G V 12.6.4 Maior Chances to Radioactive Waste Treatment Systems 12.6.4.1 License 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:

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

2. Sufficient detailed information to totally support the reason for the change without benefit or additional or supplemental infonnation;

3. A detailed description of tha equipment, components and processes j involved and the interfaces with other plant systems;

4. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents waste that differ from those previously predicted in the license application and amendments thereto;

5. An evaluation of the change which shows the expected maximum l exposures to individualin the unrestricted area and to the general l population that differ from those previously estimated in the license l V application and amendments thereto;

6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period to when the changes are to be made;

7. An estimate of the exposure to plant operating personnel as a result of the change; and

8. Documentation of the fact that the change was reviewed and found acceptable by the Onsite Review and Investigative Function.

b; Shall become effective upon review and acceptance by the Onsite Review and investigative Function.

A k .

EPsPROJedemAasale/12ri-7f 12 47

4--1 =-ba b. 5M--A,mA LA,,A.-4-*MA w k =& An mMMA0 6KA asm' mm Am -o m m-aw==Km~--==-~~ m------

i 9

e O

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LASALLE Revision 1.7 b' September 1995 f APPENDIX F

~

. LASALLE ANNEXINDEX P. AGE REVISION P. AGE REVISION F-1 1.7 F-43 1.7 F-li 1.7 F-44 1.7 F-lii 1.7 F 45 1.7 i F-iv 1.7 F 46 1.7 l F-1 1.7 F-47 1.7 F-2 1.7 F-3 1.7 F-4 1.7 -

F-5 1.7 F-6 1.7 F-7 1.7 F-8 1.7 F9 1.7 F 10 1.7 F 11 1.7 F-12 1.7 .

F 13 1.7 g F-14 1.7

) F-15 F-16 1.7 1.7 l

F 17 1.7 F-18 1.7 l F-19 1.7 l F-20 1.7 F-21 1.7 F 22 1.7 F 23 1.7 F-24 1.7 F-25 1.7 F-26 1.7 F-27 1.7 e

F-28 1.7 F-29 1.7 F-30 1.7 F-31 1.7 F-32 1.7 F-33 1.7 F-34 1.7 F-35 1.7 F-36 1.7 F-37 1.7 F-38 1.7 F-39 1.7 O '

F-40 F-41 F-42 1.7 1.7 1.7 EPSPROJedemaasale/fri-7f F-i

LASALLE Rsvision 1.7 Septembsr 1995 'r APPENDIX F STATION-SPECIFIC DATA FOR LASALLE

- UNITS 1 AND 2 Table of Contents EAGE F.1 INTRODUCTION F1 F.2 REFERENCES F-1~

O f

EPSPROJhdemAasale/tri 7f F li

LASALLE Revision 1.7 o

Septemb2r 1995 APPENDIX F

}

/ LIST OF TABLES NUMBER .T.LT.LE PAGE F-1 Aquatic Environment Dose Parameters F2 F-2 Station Characteristics F-3 F-3 Critical Ranges F-4 F-4 Average Wind Speeds F5 F5 X/O and D/O Maxima At or Beyond the Unrestricted Area Boundary F-6 l F-Sa X/O and D/O Maxima At or Beyond the Restricted Area Boundary F-7 F-6 D/O at the Nearest Milk Cow and Meat Animal Locations Within 5 Miles F-8 F-7 Maximum Offsite Finite Plume Gamma Dose Factors Cased on 1 cm Depth at the Unrestricted Area Boundary for Selected Nemides F9 F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Selected Nuclides F 24 F8 Parameters for Calculation of N-16 Skyshine Radiation from LaSalle F-39 Supplemental Tables A Elevated Level Joint Frequency Distribution Table Summary - 375 Foot Elevation Data F-40 l 1

-Summary Table of Percent by Direction and Class 1

-Summary Table of Percent by Direction and Speed l

-Summary Table of Percent by Speed and Class l

B Mid Elevation Joint Frequency Distribution )

1 Table Summary - 200 Foot Elevation Data F-42

-Summary Table of Percent by Direction and Class l

-Summary Table of Percent by Direction 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 l

-Summary Table of Percent by Speed and Class U ,

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~l LASALLE Revision 1.7 l September 1995 el APPENDIX F LIST OF FIGURES NUMBER ILT.LE PAGE F1 Unrestricted Area Boundary F-46 F2 Restricted Area Boundary F 47 O

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LASALLE R: vision 1.7 Sept 2mber 1995 Q -

APPENDIX F STATION-SPECIFIC DATA FOR LASALLE 1 UNITS 1 AND 2 '

F.1 INTRODUCTION This appendix contains data relevant to the LaSalle site. Included is a figure showing the unrestricted area boundary, restricted area boundary, and values of parameters used in offsite dose assessment.

l F.2 REFERENCES

1. Sargent & Lundy, Analysis and Technology Division, LaSalle Calculation No. ATD-0164, Revisions 0,1,2 and 3.

2. Sargent & Lundy, Nuclear Safeguards and Licensing Division, LaSalle Calculation No. ATD-0139,"N 16 Skyshine Ground Level Doses from LaSalle Turbine System & Piping, Revision 0.

3. Verification of Environmental Parameter used for Commonwealth Edison Company's Offsite Dose Calculations, "NUS Corporation,1988.

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EPsPROJedemAasale/fr17f F1

LASALLE Revision 1.7 Septemb:r 1995 Table F-1 Aquatic Environment Dose Parameters -

General Information*

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

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

Two downstream dams are on the Illinois 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 Incestion Parameters Parameter *' y,gthig 1/M",1/M' 1.0 F", cfs 1.85E4 F', cfs 1.31 E4 t', hr* 24.0 1", hr' 97.0 Limits on Radioactivity in Unoratected Outdoor Tanks' Outside Temporary Tank s 10 Ci' (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'(hr) = 24 hr (all stations) for the fish ingestion pathway

• t* (hr) = 97 hr (distance to nearest public potable water intake, Peoria, is 97 miles; flow rate of 1 mph is assumed.) l

• See Section A.2.4 oi Appendix A.

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

EPsPROJ/odemAasale/tri.7f F-2

LASALLE R vision 1.7 September 1995 Table F-2

. Station Characteristics STATION: LaSalle LOC /, TION: 6 miles south of Marseilles, Illinois - LaSalle County CHARACTERISTICS OF ELEVATED RELEASE POINT

1) Release Height = 112.8 m' 2) Diameter .. igim

2) Exit Speed = _11Z Jns 4) Heat Content = Q _KCals'

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

1) Release Height = m. 2) Diameter = m

3) Exit Speed - m s

CHARACTERISTICS OF GROUND LEVEL RELEASE

1) Release Height = 0 m ,

2) Building Factor (D)- 58 4 m' l

O- METEOROLOGICAL DATA A (Q,0 ft Tower is Located 300 m SSW of elevated release point Tower Data Used in Calculations Release Point Wind Speed and Direction Differential Temperature Elevated 375 ft 375-33 ft Vent (NA) (NA)

Ground 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 EPSPROJ/odemAasate/trl-7f F-3

LASALLE R vision 1.7 September 1995 Table F-3

- Critical Ranges Unrestricted Restricted Area Area Nearest Nearest Dairy Farm Boundary

• 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 833 5200 None ESE 1465 845 2300 None SE 969 965 2700 None SSE 858 698 2900 None S 829 820 2400 None SSW 835 835 1100 None SVV 628 628 1600 None WSW 533 533 2400 None W 524 524 1300 None WNW 643 643 1400 None N\v 762 762 2900 None NNW 890 890 2700 7400 l

Used in calculating the rn9teorological dose factors in Tables F-5 and F 7. See Sections B.3 through B.6 of Appendix B.

1994 annual survey by Teledyne isotopes Midwest Laboratories. The distances are rounded to the nearest l conservative 100 meters.

• 1994 annual milch' animal census, by Teledyne isotopes Midwest Laboratories. Used in calculating the D/O values in Table F-6. The distances are rounded to the nearest con 8000 meters is used when there are no dairies within 5 miles.

O EPsPROJ,bdemAasale/tr17f F-4

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LASALLE Rsvision 1.7 I Septemb2r 1995 I

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Table F-4

!l Average Wind Speeds I Downwind Avernae Wind Soeed (m/sec)*

Direction Elevated ,Wylt' Ground Level 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 E 9.5 7.8 5.2 ESE 9.7 8.4 5.9 SE 8.1 7.4 5.9

'SSE 7.4 6.7 5.0 S 6.7 5.9 4.3 SSW 5.6 3.7 2.9 SW 5.5 4.1 3.1 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 s

i

• Based on LaSalle site meteorological data, January 1978 through December 1987. Calculated in Reference 1 of Section F.2, using formulas in Section B.1.3 of Appendix B.

t l

i EPSPROJ/odemAasale/fr17f F-5

LASALLE R vision 1.7 S pt3mber 1995 Table F-5 X/O and D/Q Maxima at or Beyond the Unrestric'ad Area Boundary Downwind Elevated (Stack) Release Nimed Mode (Vent) Reteese Gromd Level Reteese Direction Radius X/Q Radius 0/0 Radius X/0 0/0 Radius X/Q 0/Q (metefs) (sec/m**3) (meters) (1/m**2) (meters) (sec/m**3) (1/m"2) (meters) (sec/ar**3) (1/m**2)

N 5633. 6.123E-09 1036. 7.203E-10 6000. 6.289E-09 8.311E-10 1036. 1.524E-06 1.019E-08 NNE 1378. 7.045E-09 1378. 9.831E-10 5633. 7.102E-09 9.659E-10 1378. 9.737E-07 7.095E-09 NE 4400. 5.535E-09 2408. 4.245E-10 2408. 5.600E-09 4.836E-10 2408. 3.907E-07 2.377E-09 ENE 5200. 5.086E-09 4450. 2.021E-10 4450. 4.909E-09 2.024E-10 4450. 1.496E-07 6.784E-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 5.880E-09 SE 5633. 7.116E-09 1500. 7.505E-10 %9. 1.087E-08 1.709E-09 M9. 1.137E-06 1.123E-08 SSE 5200. 6.717E-09 1500. 7.176E-10 838. 1.313E-06 2.124E-09 838. 1.124E-06 1.064E-08 5 5633. 5.910E-09 1500. 6.136E-10 829. 8.402E-09 1.303E-09 829. 1.112E-06 1.039E-08 SSW 6000. 5.269E-09 835. 5.793E-10 835. 7.322E-09 9.999E-10 835. 7.940E-07 5.359E-09 SW 6000. 6.767E-09 628. 8.545E-10 628. 2.224E-08 2.154E-09 628. 1.864E-06 1.407E-08 WSW 6000. 6.065E-09 533. 6.527E-10 540. 2.105E-08 2.079E-09 533. 2.101E-06 1.970E-08 W 6437. 5.354E-09 1500. 4.811E-10 540. 1.344E-08 1.629E-09 524. 2.830E-06 2.453E-08 WNW 7242. 3.916E-09 1500. 3.175E-10 643. 5.963E-09 9.071E-10 643. 2.429E-06 1.508E-08 NW T242. 3.766E-09 1500. 3.118E-10 5633. 4.127E-09 6.660E-10 762. 1.984E-06 1.055E-08 NNW 6437. 4.240E-09 1500. 3.806E-10 6437. 4.095E-09 5.574E-10 890. 1.605E-06 8.840E-09 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 Note: Based on Reference 2 of Section F.2 and the formulas in Sections B.3 and B.4 of Appendix B.

Used for beta air, 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.

f EPSPROJ/odcrrulasalle/fr1-7f F-6 O O O.

) ) R vis d .7

_,/ L vlE Septsmber 1995 Table F-Sa X/O and D/O Maxima at or Beyond the Restricted Area Boundary Mixed Mode (Vent) Reteese Groemd Levet Reteese  !

Downsind Elevated (Stock) Reteese Radius X/G D/G Radius D/0 Radius X/0 D/0 Direction Redfus X/Q (meters) (sec/m**3) (meters) (1/#*2) (meters) (sec/aF*3) (1/sF*2) (metws) (sec/#*3) (1/m**2) 1036. 7.203E-10 6000. 6.289E-09 8.311E-10 1036. 1.524E-06 1.019E-08 N 5633. 6.123E-09 9.737E-07 7.095E-09 1378. 9.831E-10 5633. 7.102E 09 9.659E-10 1378. ,

NNE 1378. 7.045E-09 7.003E-07 4.747E-09 1609. 6.556E-10 1609. 6.052E-09 7.953E-10 1609.

NE 4400. 5.535E-09 1.120E-06 7.788E-09 1079. 6.376E-10 1079. 6.579E-09 9.861E-10 1079.

ENE 5200. 5.086E-09 1055. 1.278E 06 8.779E-09 5200. 5.865E-09 1500. 6.659E-10 1055. 7.712E-09 1.160E-09 E 1055. 1.192E-06 1.021E-06 5200. 8.000E-09 1500. 8.896E-10 1055. 9.981E-09 1.546E-09 ESE 969. 1.137E-06 1.123E-08 5633. 7.116E-09 1500. 7.505E-10 969. 1.087E-08 1.709E-09 SE 1.492E-06 1.428E-06 698. 7.210E-10 698. 1.444E-06 2.403E-09 698.

SSE 5200. 6.717E-09 1.130E-06 1.058E-08 1500. 6.136E-10 820. 8.455E-09 1.312E-09 820.

S 5633. 5.910E-09 835. 5.793E-10 835. 7.322E-09 9.999E-10 835. 7.940E-07 5.359E-09 SSW 6000. 5.269E-09 628. 1.864E-06 1.407E-06 6000. 6.767E-09 628. 8.545E-10 628. 2.224E-08 2.154E-09 SW 533. 2.101E-06 1.970E-08 6000. 6.065E-09 533. 6.527E-10 540. 2.105E-08 2.079E-09 WSW 524. 2.830E-06 2.453E-08 i w 6437. 5.354E-09 1500. 4.811E-10 540. 1.344E-08 1.629E-09 l' 1500. 3.175E-10 643. 5.963E-09 9.071E-10 643. 2.429E-06 1.500E-08 WNW 7242. 3.916E-09 1500. 3.118E-10 5633. 4.127E-09 6.660E-10 762. 1.984E-06 1.055E-08 NW 7242. 3.766E-09 j l

1500. 3.806E-10 6437. 4.095E-09 5.574E-10 890. 1.605E-06 8.840E-09 NNW 6437. 4.240E-09 l

LASALLE SITE METEORotoGICAL DATA 1/78 - 12/87 L

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EPSPROJ/odem/lasalle/1rt-7f F-7 6

LASALLE R: vision 1.7 Sept:rnber 1995 Table F-6 D/Q at the Nearest Milk Cow and Meat Animal Locations within 5 miles

[* unw i n.t. N* a s . s t Milk ivw D/vt1/m**2} Hearegt Meat Animal D/Q(1/m**2) tii a =<-t i . .n H + 11 u s Elevated Mixed Ground Radius Elevated Mixed Groumi (merets) Release Release Release (meters) Release Release Release

^

N 8000. 4.711E-11 1.006E-10 2.915E-10 6400. 1.387E-10 1.436E-10 4.352E-10 NME 8000. 1.151E-10 1.178E-10 3.273E-10 3100. 4.257E-10 4.320E-10 1.760E-09 HE 8000. 8.839E-11 9.468E-11 2.851E-10 5600. 1.538E-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 R000. 1.056E-10 9.772E-11 2.587E-10 8000. 1. 056E-10 9.772E-11 2.587 E-10 ESE 8000. 1. 4 50 E- 10 1. 3 56 E- 10 3.010E-10 8000. 1.450E-10 1.356E-10 3.010E-10 SE 8000. 1. 2 4 2 E-10 1.322E-10 2. 8 81 E- 10 7600. 1.354E-10 1.437E-10 3.160E-10 SSE 8000. 1.174E-10 1.278E-10 2.152E-10 7600. 1.279E-10 1.389E-10 2.360E-10 S 8000. 9.447E-11 9.895E-11 2.065E-10 0000. 9.947E-11 9.895E-11 2.065E-10 Ssw 8000, 8.647E-11 9.097E-11 1.077E-10 8000. 0.647E-11 9.097E-11 1.077E-10 SW 8000. 1.096E-10 1.210E-10 1.793E-10 0000. 1.096E-10 1.210E-10 1.793E-10 wsw 8000. 1.017E-10 1.083E-10 1.940E-10 8000. 1.017E-10 1.083E-10 1.940E-10 ,

W 8000. 8.444E-11 1.094E-10 2.354E-10 4000. 1. 80 0E-10 2. 362E-10 5. 866E-10 wrm 8000. 5.824E-11 6.886E-11 1.994E-10 5200. 1.117 E- 10 1. 3 31 E-10 4. 312 E-10 PM 8000. 5.436E-11 6. 310E- 11 1.828E-10 6400. 7.773E-11 9.022E-11 2.730E-10 nrm 7409. 7.317E-11 7.264E-11 2.269E-10 7600. 7. 002 E-11 6. 95 4 E-11 2.16 3 E-10 LaSalle site Meteorological Data 1/78 - 12/07 e

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

ROJ/Odem/lasane/ht-7f F-8

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. . l s LA lLE Revid.7  !

Sept 3mber 1995 l

l Table F-7 l

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-83m l

l i

Mixed Mode (Vent) Release Ground Level Release Doe.rM onrestricted Elevated (Stack) Release S S8AR Radius V VSAR Radius G GSAR f'.rection Area Bound Radius (meters) (meters) (arad/yr)/(ucl/sec) (meters) (arad/yr)/(uci/sec) (meters) (arad/yr)/(uct/sec)

N 1036. 1036. 4.787E-07 3.609E-07 1036. 5.281E-07 3.982E-07 1036. 1.785E-04 1.346E-04 l 1378. 1378. 8.751E-07 6.599E-07 1378. 6.905E-07 5.2ME-uT 1378. 1.139E-04 8.586E-05 t

NNE NE 2408. 2408. 6.471E-07 4.879E-07 2408. 6.697E-07 5.049E-07 2408. 4.355E-05 3.284E-05 i t

4450. 4450. 5.700E-07 4.298E-07 4450. 5.653E-07 4.262E-07 4450. 1.466E-05 1.105E-05 ENE E 1996. 1996. 4.687E-07 3.534E-07 1996. 7.559E-07 's.700E-07 1996. 5.491E-05 4.140E-05 ESE 1465. 1465. 5.252E-07 3.960E-07 1465. 1.002E-06 7.559E-07 1465. 8.270E-05 6.236E-05 SE 969. %9. 3.545E-07 2.673E-07 M9. 1.267E-06 9.554E-07 969. 1.333E-04 1.005E-04 SSE 838 838. 3.051E-07 2.301E-07 838. 1.512E-06 1.140E-06 838. 1.323E-04 9.978E-05 S 829. 829, 2.840E-07 2.141E-07 829. 1.040E-06 7.842E-07 829. 1.330E-04 1.003E-04 SSW 835. 835. 3.185E-07 2.401E-07 835. 1.071E-06 8.076E-07 835. 9.326E-05 7.032E-05 i SW 628. 628. 3.177E-07 2.395E-07 628. 2.826E-06 2.131E-06 628. 2.305E-04 1.738E-04

• WSW 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 WNW 643. 643. 1.714E-07 1.292E-07 643. 7.235E-07 5.455E-07 643. 2.728E-04 2.057E-04 i NW 762. 762. 1.744E-07 1.315E-07 762. 4.391E-07 3.311E-07 762. 2.219E-04 1.673E-04 WNW 890. 890. 2.397E-07 1.807E-07 890. 3.334E-07 2.514E-07 890. 1.823E-04 1.374E-04 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 i

Note: Based on Reference 1 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B.

l EPSPROJ/odem/lasalle/trl-7f F-9 l

t

LASALLE R vision 1.7 September 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85m Dowwind Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius S SBAR Radius V VBAR Radius G GSAR (meters) (meters) (arad/yr)/(uct/sec) (meters) (arad/yr)/(uCI/sec) (meters) (arad/yr)/(uct/sec)

N 1036. 1036. 5.747E-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.%9E-04 2.849E-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. 2.705E-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 4.989E-04 SE 969. M9. 5.596E-05 5.415E-05 M9. 6.610E-05 6.391E-05 969. 7.793E-04 7.470E-04 SSE 838. 838. 5.518E-05 5.339E-05 838. 6.630E-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 835. 835. 4.422E-05 4.279E-05 835. 5.351E-05 5.174E-05 835. 5.684E-04 5.450E-04 -

SW 628. 628. 7.281E-05 7.046E-05 628. 9.952E-05 9.618E-05 628. 1.285E-03 1.231E-03 WSW 533. 533. 7.757E-05 7.507E-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-03 WNW 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 METEOROLOGICAL DATA 1/78 - 12/87 WROJ/odemAssate/trl-7f 40 e..:

L LE (Tl.7 R svisi September 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85 Dounuind Unrestricted Elevated (Stock) Reteese Mixed Mode (Vent) Reteese Groimd Level Reteese Oirection Area sound Redius S SSAR Radius V VSAR Redius G GSAR (meters) (meters) (ared/yr)/(uCl/sec) (meters) (ared/yr)/(uCl/sec) (meters) (ared/yr)/(ucl/sec) -

W 1036. 1036. 8.547E-07 8.265E-07 1036. 9.889E-07 9.563E-07 1036. 1.056E-05 1.021E-05

! INIE 1378. 1378. 7.309E-07 7.068E-07 1378. 8.077E-07 7.811E-07 1378. 7.474E-06 7.227E-06 NE 2408. 2408. 3.651E-07 3.530E-07 2408. 3.909E-07 3.780E-07 2408. 3.363E-06 3.252E-06 ENE 4450. 4450. 1.885E-07 1.823E-07 4450. 1.856E-07 1.795E-07 4450. 1.377E-06 1.332E-06 E 1996. 1996. 3.912E-07 3.782E-07 1996. .4.096E-07 3.%1E-07 1996. 4.000E-06 3.876E-06 ESE 1465. 1465. 6.359E-07 6.149E-07 1465. 6.632E-07 6.413E-07 1465. 5.783E-06 5.593E-06 SE M9. 969. 8.386E-07 8.110E-07 969. 9.583E-07 9.267E-07 969. 8.555E-06 8.273E-06 SSE 838. 838. 8.350E-07 8.075E-07 838. 9.612E-07 9.294E-07 838. 8.432E-06 8.154E-06 5 829. 829. 7.262E-07 7.023E-07 829. 8.067E-07 7.801E-07 829. 8.741E-06 8.453E-06 SSW 835. 835. 6.857E-07 6.630E-07 835. 8.402E-07 8.124E-07 835. 6.270E-06 6.063E-06 -

SW 628. 628. 1.142E-06 1.104E-06 628. 1.494E-06 1.444E-06 628. 1.401E-05 1.355E-05 WSW 533. 533. 1.211E-06 1.171E-06 533. 1.433E-06 1.386E-06 533. 1.510E-05 1.460E-05 W 524. 524. 1.172E-06 1.134E-06 524. 1.443E-06 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. 7.128E-07 6.893E-07 890. 7.849E-07 7.590E-07 890. 1.011E-05 9.778E-06

- LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 i

EPSPROJhdem,1asate/fr17f p.jj

LASALLE R: vision 1.7 Sept 3mber 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-87 Downwind unrestricted Elevated (Stock) Reteese Mixed Mode (Vent) Reteese Cromd Levet Reteese Direction Area Bound Radius S S8AR Radius V V8AR Radius G G8AR (meters) (meters) (ared/yr)/(ucl/sec) (meters) (arad/yr)/(uct/sec) (meters) (arad/yr)/(uti/sec)

N 1036. 1036. 3.226E-04 3.135E-04 1036. 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. 2.0?9E-03 1.960E-03 NE 2408. 2408. 1.283E-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-04 E 1996. 1996. 1.412E-04 1.372E-04 1996. 1.458E-04 1.417E-04 1996. 1.030E-03 9.998E-04 ESE 1465. 1465. 2.351E-04 2.284E-04 1465. 2.426E-04 2.357E-04 1465. 1.545E-03 1.500E-03 SE M9. 969. 3.211E-04 3.120E-04 M9. 3.612E-04 3.510E-04 969. 2.355E-03 2.287E-03 SSE 838. 838. 3.254E-04 3.162E-04 838. 3.655E-04 3.552E-04 838. 2.329E-03 2.262E-03 S 829. 829. 2.850E-04 2.770E-04 829. 3.081E-04 2.994E-04 829. 2.431E-03 2.361E-03 SSW 835. 835. 2.742E-04 2.665E-04 835. 3.400E-04 3.305E-04 835. 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-C3 WSW 533. 533. 4.880E-04 4.743E-04 533. 5.683E-04 5.523E-04 533. 4.251E-03 4.128E-03 W 524. 524. 4.675E-04 4.543E-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 2.743E-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 METEOROLOGICAL DATA 1/78 - 12/87

(

EP PROJ/odemAasalle/fr17f F-12

x [

L LE Rsvis .7 Septamber 1995 -

i i

- Table F-7 (Continued) t Maximum Difsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-88 i

t Doeswind unrest'rfcted Elevated (Stock) Reteese Mixed Mode (Vent) Reteese trotsed Level Reteese ,

Radius V WBAR Radius G GSAR I Direction Area Sound Radius s SSAR (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uct/sec)

N 1036. 1036. 8.602E-04 8.374E-04 1036. 1.003E-03 9.769E-04 1036. 6.9BBE-03 6.787E-03 [

mNE 1378. 1378. 7.111E-04 6.922E-04 1378. 7.989E-04 7.777E-04 1378. 4.940E-03 4.798E-03 3.435E-04 3.344E-04 2408. 3.694E-04 3.596E-04 2408. 2.182E-03 2.120E-03 I NE 2408. 2408.

4450. 4450. 1.648E-04 1.604E-04 4450. 1.646E-04 1.602E-04 4450. 8.502E-04 8.263E-04 [

ENE E 1996. 1996. 3.781E-04 3.680E-04 1996. 3.928E-04 3.824E-04 1996. 2.599E-03 2.525E-03 l 1465. 3.816E-03 3.707E-03  ;

ESE 1465. 1465. 6.235E-04 6.070E-04 1465. 6.445E-04 6.273E-04 SE 969. %9. 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-04 8.442E-04 838. 9.702E-04 9.445E-04 838. 5.645E-03 5.483E-03 l s 829. 829. 7.696E-04 7.492E-04 829. 8.417E-04 8.194E-04 829. 5.862E-03 5.695E-03 ssu 835. 835. 7.427E-04 7.231E-04 835. 9.375E-04 9.127E-04 835. 4.167E-03 4.048E-03 l su 628. 628. 1.246E-03 1.213E-03 628. 1.601E-03 1.559E-03 628. 9.396E-03 9.126E-03  !

533, 533. 1.314E-03 1.279E-03 533. 1.525E-03 1.485E-03 533. 1.017E-02 9.882E-03 I

^WSW l 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-03 890. 7.369E-04 7.174E-04 890. 8.161E-04 7.945E-04 890. 6.693E-03 6.500E-03 I NNW 890.

LASALLE SITE METEOR 0 LOGICAL DATA 1/78 - 12/87 l i

?

i l

i 5

I i

i I

i l

I i

i EPSPROJ/odemansene/fr1-7f F-13  ;

i

LASALLE R: vision 1.7 l

Septsmber 1995 l

l Table F-7 (Continued)

M*.ximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-89 l

l Dowmird Unrestricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Levet Release l Radius G GBAR Direction Area Sound Radius S SBAR Radius V VSAR (meters) (meters) (arad/yr)/(uci/sec) (meters) (arad/yr)/(ucl/sec) (meters) (mrad /yr)/(uci/sec)

N 1036. 1036. 3.904E-04 3.794E-04 1036. 4.258E-04 4.139E-04 1036. 2.051E-03 1.992E-03 NNE 1378. 1378. 2.820E-04 2.741E-04 1378. 2.988E-04 2.904E-04 1378. 1.151E-03 1.118E-03 NE 2408. 2408. 8.306E-05 8.072E-05 2408. 7.403E-05 7.195E-05 2408. 2.060E-04 2.001E-04 ENE 4450. 4450. 1.570E-05 1.526E-05 4450. 1.153E-05 1.121E-05 4450. 1.701E-05 1.653E-05 E 1996. 1996. 1.052E-04 1.023E-04 1996. 9.299E-05 9.037E-05 1996. 3.031E-04 2.944E-04 ESE 1465. 1465. 2.365E-04 2.299E-04 1465. 2.240E-04 2.177E-04 1465. 7.762E-04 7.540E-04 SE 969. 969. 3.891E-04 3.782E-04 M9. 4.188E-04 4.070E-04 M9. 1.846E-03 1.793E-03 SSE 838. 838. 4.108E-04 3.993E-04 838. 4.365E-04 4.243E-04 838. 1.831E-03 1.778E-03 S 829. 829. 3.408E-04 3.312E-04 829. 3.253E-04 3.162E-04 829. 2.034E-03 1.976E-03 SSW 835. 835. 2.921E-04 2.839E-04 835. 2.779E-04 2.702E-04 835. 1.021E-03 9.916E-04 .

SW 628. 628. 5.830E-04 5.667E-04 628. 6.600E-04 6.415E-04 628, 3.274E-03 3.180E-03 WSW 533. 533. 6.913E-04 6.720E-04 533. 7.525E-04 7.314E-04 533. 4.592E-03 4.460E-03 W 524. 524. 6.%1E-04 6.766E-04 524. 8.259E-04 8.028E-04 524. 5.%7E-03 5.796E-03 WNW 643. 643. 4.295E-04 4.174E-04 643. 5.147E-04 5.003E-04 643. 3.746E-03 3.638E-03 NW 762. 762. 3.500E-04 3.402E-04 762. 4.035E-04 3.922E-04 762. 2.561E-03 2.488E-03 NNW 890. 890. 3.301E-04 3.208E-04 890. 3.415E-04 3.319E-04 890. 1.966E-03 1.909E-03 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 ROJtdemAasalle/frt-7f

1. F b_14 O. .

Lh wE R svis v .7 i Sept 3mber 1995 Table F-7 (Continued) j

'i Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-90  ;

i Mized Mode (Vent) Reteese Ground Level Reteese Doesmind Unrestrt'cted Elevated (Stock) Reteese Radius G GSAR Olrection Area 8ound Radius 5 SSAR Radius V VBAR I

(meters) (meters) tared /yr)/(ucl/sec) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uct/sec) .

1036. 8.203E-05 7.954E-05  !

N 1036. 1036. 6.785E-05 6.586E-05 1036. 5.199E-05 5.047E-05 1378. 3.195E-05 3.102E-05 1378. 2.161E-05 2.090E-05 1378. 2.265E-05 2.196E-05 NME 1378.

• 2408. 2.160E-06 2.097E-06 2408. 9.136E-07 8.868E-07 2408. 5.870E-07 5.693E-07 NE 2408. 1 4450. 1.109E-07 1.076E-07 4450. 3.907E-08 3.792E-08 4450. 1.814E-08 1.759E-08 ENE 4450.

1996. 4.713E-06 4.575E-06 1996. 2.562E-06 2.486E-06 1996. 2.865E-06 2.779E-06 i E 1996.

1465. 2.134E-05 2.072E-05 1465. 1.551E-05 1.506E-05 1465. 2.503E-05 2.427E-05 [

ESE 1465.

5.843E-05 5.673E-05 969. 5.324E-05 5.168E-05 969. 1.365E-04 1.324E-04  !

SE M9. %9.

838. 1.227E-04 1.190E-04 l SSE 838. 838. 6.863E-05 6.663E-05 838. 6.174E-05 5.993E-05 829. 3.745E-05 3.635E-05 829. 1.055E-04 1.023E-04 [

S 829. 829. 5.057E-05 4.909E-05  :

835. 3.062E-05 2.972E-05 835. 1.274E-05 1.237E-05 835. 1.835E-05 1.779E-05 SSW 835. l 628. 628. 9.754E-05 9.470E-05 628. 6.538E-05 6.347E-05 628. 1.410E-04 1.368E-04 SW 533. 1.892E-04 1.836E-04 533. 1.525E-04 1.480E-04 533. 4.861E-04 4.713E-04 i WSW 533. 8.427E-04 8.170E-04 l 524. 524. 2.165E 04 2.101E-04 524. 2.185E-04 2.121E-04 524.

W 643. 643. 1.018E-04 9.883E-05 643. 1.000E-04 9.787E-05 643. 3.141E-04 3.045E-04 l WNW 762. 762. 6.634E-05 6.440E-05 762. 5.815E-05 5.645E 05 762. 1.306E-04 1.267E-04 f NW l 890. 890. 5.725E-05 5.558E-05 890. 4.336E-05 4.209E-05 890. 8.819E-05 8.551E-05 NNW r

LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 t

i i

EPSPROJ/odem/lasage/fr17f F-15

LASALLE Resision 1.7 September 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-131m Mixed Mode (Vent) Release Grotmd Level Release Oourwind Unrestricted Elevated (Stack) Release Radius G G8AR Direction Area bound Radius S 58AR Radius V VBAR (meters) (meters) (arad/yr)/(uci/sec) (meters) (arad/yr)/(uci/sec) (meters) (arad/yr)/(uCf/sec) 1036. 1036. 1.606E-06 1.473E-06 1036. 1.827E-06 1.679E-06 1036. 1.645E-04 1.283E-04 N

1378. 1378. 1.778E-06 1.572E-06 1378. 1.726E-06 1.553E-06 1378. 1.072E-04 8.384E-05 NNE 2408. 2408. 1.086E-06 9.376E-07 2408. 1.136E-06 9.826E-07 2408. 4.347E-05 3.412E-05 NE 4450. 4450. 7.931E-07 6.617E-07 4450. 7.858E-07 6.550E-07 4450. 1.623E-05 1.279E-05 ENE 1996. 1996. 9.572E-07 8.457E-07 1996. 1.230E-06 1.058E-06 1996. 5.428E-05 4.253E-05 E

1465. 1465. 1.347E-06 1.215E-06 1465. 1.789E-06 1.560E-06 1465. 7.935E-05 6.215E-05 ESE 969. 969. 1.472E-06 1.365E-06 M9. 2.406E-06 2.115E-06 M9. 1.240E-04 9.696E-05 SC 838. 838. 1.415E-06 1.318E-06 838. 2.598E-06 2.260E-06 838. 1.228E-04 9.597E-05 SSE 829. 829. 1.231E-06 1.144E-06 829. 1.966E-06 1.727E-06 829. 1.232E-04 9.639E-05 s

835. 835. 1.196E-06 1.103E-06 835. 2.003E-06 1.755E-06 835. 8.798E-05 6.885E-05 ssu SW 628. 628. 1.802E-06 1.691E-06 628. 4.345E-06 3.728E-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-04 .

W 524. 524. 1.800E-06 1.703E-06 524. 3.359E-06 2.972E-06 524, 3.000E-04 2.335E-04 WNW 643. 643. 1.263E-06 1.194E-06 643. 1.976E-06 1.791E-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-04 890. 890. 1.191E-06 1.112E-06 890. 1.363E-06 1.263E-06 890. 1.664E-04 1.295E-04 NNW LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 WOJ/odemAasaFa/frt-7f # e..

'h RavisV.7 O i LvlE Stptsmber 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133m i

Mixed Mode (Vent) Reteese Gronsid Level Reteese Downuind unrestri.cted Elevated (Stack) Reteese Radius G -GSAR ofrection Area Sound Radius S SSAR Radius V VSAR (meters) (meters) (ared/yr)/(ucl/sec) (meters) (arad/yr)/(ucl/sec) (meters) (arad/yr)/(uct/sec)

N 1036. 1036. 8.557E-06 8.199E-06 1036. 9.814E-06 9.407E-06 1036. 2.822E-04 2.410E-04 1378. 1378. 7.917E-06 7.509E-06 1378. 8.400E-06 8.009E-06 1378. 1.901E-04 1.633E-04 NME NE 2408. 2408. 4.246E-06 3.993E-06 2408. 4.482E-06 4.217E-06 2408. 8.032E-05 6.950E-05 4450. 4450. 2.488E-06 2.298E-06 4450. 2.450E 06 2.262E-06 4450. 3.100E-05 2.706E-05 ENE 1996. 1996. 4.247E-06 4.028E-06 1996. 4.721E-06 4.433E-06 1996. 9.835E-05 8.482E-05 E

1465. 1465. 6.614E-06 6.309E-06 1465. 7.393E-06 6.978E-06 1465. 1.432E-04 1.234E-04 ESE SE %9. 969. 8.229E-06 7.903E-06 M9. 1.039E-05 9.834E-06 969. 2.189E-04 1.879E-04 SSE 838. 838. 8.070E-06 7.758E-06 838. 1.060E-05 9.990E-06 838. 2.163E-04 1.856E-)4 S 829. 829. 6.932E-06 6.660E-06 829. 8.449E-06 7.995E-06 829. 2.201E-04 1.893E-14 SSW 835. 835. 6.541E-06 6.276E-06 835. 8.500E-06 8.036E-06 835. 1.574E-04 1.354E-i4 SW 628. 628. 1.059E-05 1.020E-05 628. 1.637E-05 1.535E-05 628. 3.668E-04 3.140E-G**

• WSW 533. 533. 1.121E-05 1.081E-05 533. 1.588E-05 1.490E-05 533. 4.005E-04 3.423E-04 W 524. 524. 1.096E-05 1.056E-05 524. 1.504E-05 1.427E-05 524. 5.039E-04 4.287E-04 www 643. 643. 7.648E-06 7.374E-06 643. 9.956E-06 9.510E-06 643. 4.055E-04 3.441E-04 NW 762. 762. 6.774E-06 6.526E-06 762. 8.435E-06 8.088E*06 762. 3.334E 04 2.831E-04 muu 890. 890. 6.855E-06 6.594E-06 890. 7.588E-06 7.286E-06 890. 2.794E 04 2.377E-04 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 i

l l

EPSPROJ/odern/lasage/frt-7f p.j7 l

LASALLE R;; vision 1.7 Septamber 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133 Mixed Mode (Vent) Release Ground Levet Release Dourwind Unrestricted Elevated (Stack) Reteese

$8AR Radius V VBAR Radius G GBAR Direction Area Bomd Radius S (meters) (meters) (arad/yr)/(uCl/sec) (meters) (arad/yr)/(uC1/sec) (seters) (ared/yr)/(uti/sec)

N 1036. 1036. 7.010E-06 6.757E-06 1036. 7.933E-06 7.649E-06 1036. 3.136E-04 2.785E-04 1378. 1378. 6.939E-06 6.629E-06 1378. 7.149E-06 6.860E-06 1378. 2.132E-04 1.903E-04 NME 2408. 2408. 3.%9E-06 3.767E-06 2408. 4.106E-06 3.897E-06 2408. 9.094E-05 8.164E-05 NE 4450. 4450. 2.442E-06 2.286E-06 4450. 2.384E-06 2.229E-06 4450. 3.540E-05 3.193E-05 ENE 1996. 1996. 3.841E-06 3.671E-06 1996. 4.310E-06 4.083E-06 1996. 1.109E-04 9.929E-05 E

1465. 1465. 5.762E-06 5.534E-06 1465. 6.599E-06 6.277E-06 1465. 1.612E-04 1.443E-04 ESE 969. 969. 6.641E-06 6.416E-C6 M9. 8.978E-06 8.558E-06 969. 2.450E-04 2.185E-04 SE 838. 838. 6.364E-06 6.153E-06 838. 9.231E-06 8.769E-06 838. 2.418E-04 2.156E-04 SSE S 829. 829. 5.333E-06 5.152E-06 829. 6.%2E-06 6.627E-06 829. 2.476E-04 2.212E-04 835. 4.%9E-06 4.793E-06 835. 6.598E-06 6.266E-06 835. 1.770E-04 1.582E-04 SSW 835.

628. 628. 7.798E-06 7.549E-06 628. 1.362E-05 1.285E-05 628. 4.090E-04 3.640E-04 SW 533. 533. 8.245E-06 7.992E-06 533. 1.326E-05 1.252E-05 533. 4.447E-04 3.951E-04 WSW W 524. 524. 8.166E-06 7.919E-06 524. 1.220E-05 1.164E-05 524. 5.551E-04 4.911E-04 643. 643. 5.715E-06 5.541E-06 643. 7.885E-06 7.574E-06 643. 4.444E-04 3.922E-04 WNW NW 762. 762. 5.117E-06 4.958E-06 762. 6.538E-06 6.303E-06 762. 3.661E-04 3.233E-04 890. 890. 5.340E-06 5.165E-06 890. 5.911E-06 5.708E-06 890. 3.080E-04 2.725E-04 NNW LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 i

EOROJ/odemMasalle/frt-7f bg O. .

-~- .

C L Q LE T fl Reviv.7 i

Sept 3mber 1995 i

I Table F-7 (Continued)

\

l Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-135m Mixed Mode (Vent) Release Groemd Level Release Doeswind unrestricted Elevated (Steck) Release V Radius G GBAR l

Olrection Aree' Sound Radius S $8A4 Redlue VBAR '

(meters) (meters) (ared/yr)/(uti/sec) (meters) (ared/yr)/(uCl/sec) (meters) (ared/yr)/(uCl/sec) 1036. 1.531E-03 1.475E-03 i N 1036. 1036. 1.396E-04 1.349E-04 1036. 1.598E-04 1.545E-04 1378. 1.151E-04 1.113E-04 1378. 1.274E-04 1.232E-04 1378. 1.019E-03 9.821E-04 NME 1378.

5.077E-05 4.907E-05 2408. 5.129E-05 4.958E-05 2408. 3.516E-04 3.390E-04 ,

NE 2408. 2408.

4450. 1.919E-05 1.854E-05 4450. 1.778E-05 1.718E-05 4450. 8.758E-05 8.445E-05 ENE 4450. 4.329E-04 4.172E-04 1996. 5.672E-05 5.483E-05 1996. 5.675E-05 5.486E-05 1996.

E 1996.

1465. 1.005E-04 9.716E-05 1465. 1.024E-04 9.902E-05 1465. 7.369E-04 7.103E-04 ESE 1465.

%9. 969. 1.575E-04 1.522E-04 969. 1.262E-03 1.216E-03 SE M9. 1.389E-04 1.343E-04 1.254E-03 1.209E-03 838. 838. 1.402E-04 1.356E-04 838. 1.591E-04 1.538E-04 838.

SSE 829. 1.183E-04 1.144E-04 829. 1.235E-04 1.194E-04 829. 1.341E-03 1.292E-03 S 829.

835. 1.104E-04 1.068E-04 835. 1.260E-04 1.218E-04 835. 8.762E-04 8.444E-04 SSW 835.

628. 1.904E-04 1.841E-04 628. 2.444E-04 2.363E-04 628. 2.173E-03 2.094E-03 su 628.

533. 2.063E-04 1.995E-04 533. 2.427E-04 2.345E-04 533. 2.479E-03 2.388E-03 WSW 533. 3.050E-03 2.937E-03 524. 524. 2.033E-04 1.966E-04 524. 2.511E-04 2.427E-04 524.

W  ;

643. 643. 1.363E-04 1.318E-04 643. 1.687E-04 1.631E-04 643. 2.286E-03 2.201E-03 WNW -

l 762. 762. 1.187E-04 1.148E-04 762. 1.423E-04 1.376E-04 762. 1.806E-03 1.739E-03 NW 890. 890. 1.161E-04 1.122E-04 890. 1.259E-04 1.217E-04 890. 1.482E-03 1.427E-03 NuW LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 EPSPROJ/odemAssete/tri-7f p.j g

LASALLE R: vision 1.7 September 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-135 Mixed Mode (Vent) Release Groured Levet Release Downwind Unrestricted Elevated (Stack) Release Radius G GBAR

$8AR Radius V VSAR Direction Area Sound Radius S (meters) (meters) (arad/yr)/(uCI/sec) (meters) (arad/yr)/(uCf/sec) (meters) (arad/yr)/(utt/sec) 1036. 1036. 8.165E-05 7.902E-05 1036. 9.387E-05 9.085E-05 1036. 1.302E-03 1.257E-03 N

1378. 1378. 7.171E-05 6.940E-05 1378. 7.821E-05 7.569E-05 1378. 9.178E-04 8.866E-04 NNE 2408. 2408. 3.669E-05 3.550E-05 2408. 3.876E-05 3.751E-05 2408. 4.075E-04 3.937E-04 NE 4450. 4450. 1.928E-05 1.866E-05 4450. 1.899E-05 1.837E-05 4450. 1.625E-04 1.570E-04 ENE 1996. 1996. 3.838E-05 3.714E-05 1996. 4.056E-05 3.925E-05 1996. 4.869E-04 4.704E-04 E

1465. 1465. 6.171E-05 5.972E-05 1465. 6.539E-05 6.328E-05 1465. 7.073E-04 6.833E-04 ESE SE 969. 969. 7.953E-05 7.697E-05 969. 9.346E-05 9.044E-05 %9. 1.052E 03 1.017E-03 838. 838. 7.845E-05 7.593E-05 838. 9.367E-05 9.064E-05 838. 1.037E-03 1.002E-03 SSE 829. 829. 6.719E-05 6.503E-05 829. 7.587E-05 7.342E-05 829. 1.078E-03 1.041E-03 S

835. 835. 6.306E-05 6.103E-05 835. 7.636E-05 7.389E-C5 835. 7.699E-04 7.438E-04 .

SSW 1.729E-03 1.67DE-03 i

628. 628. 1.039E-04 1.006E-04 628. 1.409E-04 1.363E-04 628.

SW 533. 533. 1.106E-04 1.071E-04 533. 1.372E-04 1.328E-04 533. 1.864E-03 1.801E-03 WSW I

524. 524. 1.082E-04 1.048E-04 524. 1.374E-04 1.329E-04 524. 2.256E-03 2.179E-03

W 643. 643. 7.538E-05 7.296E-05 643. 9.395E-05 9.092E-05 643. 1.775E-03 1.713E-03 l WNW 762. 762. 6.654E-05 6.440E-05 762. 8.098E-05 7.838E-05 762. 1.466E-03 1.415E-03 NW l 890. 6.671E-05 6.456E-05 890. 7.327E-05 7.092E-05 890. 1.247E-03 1.204E-03 NNW 890.

I LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 I

l l

WROJA>demMasalle/fr1-7f 40 9 .

-. _ ~ - ~ ~ ~ ~ - ___ ___________

b b

L U LE R:vi;h .7 Sept 3mber 1995 d

Table F-7 (Continued) t Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-137 Downuind unrestcleted Elevated (Stock) Reteese Mixed Mode (Vent) Reteese Groted Levet Releese Direction Area Bound Radius S SSAR Radius V VSAR Radius G GBAR (meters) (meters) (arad/yr)/(ucl/sec) (meters) (ared/yr)/(uct/sec) (meters) (mrad /yr)/(uct/sec)

N 1036. 1036. 4.780E-05 4.627E-05 1036. 5.242E-05 5.074E-05 1036. 3.409E-04 3.298E-04 i NME 1378. 1378. 3.585E-05 3.471E-05 1378. 3.814E-05 3.692E-05 1378. 1.975E-04 1.911E-04 WE 2408. 2408. 1.153E-05 1.116E-05 2408. 1.052E-05 1.018E-05 2408. 3.979E-05 3.850E-05 ENE 4450. 4450. 2.512E-06 2.432E-06 4450. 1.933E-06 1.871E-06 4450. 3.949E-06 3.821E-06 E 1996. 1996. 1.420E-05 1.374E-05 1996. 1.285E-05 1.244E-05 1996. 5.599E-05 5.418E-05 1465. 1465. 3.033E-05 2.936E-05 1465. 2.918E-05 2.825E-05 1465. 1.327E-04 1.284E-04 ESE SE %9. M9. 4.743E-05 4.591E-05 M9. 5.188E-05 5.023E-05 969. 2.989E-04 2.892E-04 ssE 838. 838. 4.926E-05 4.769E-05 838. 5.357E-05 5.186E-05 838. 2.970E-04 2.874E-04 .

S 829. 829. 4.072E-05 3.942E-05 829. 3.975E-05 3.849E-05 829. 3.290E-04 3.191E-04 ssu 835. 835. 3.521E-05 3.408E-05 835. 3.424E-05 3.315E-05 835. 1.748E-04 1.691E-04 SW 628. 628. 6.779E-05 6.563E-05 628. 7.938E-05 7.685E-05 628. 5.333E-04 5.161E-04 Wsu 533. 533. 7.919E-05 7.667E-05 533. 8.829E-05 8.548E-05 533. 7.164E-04 6.932E-04 W 524. 524. 7.990E-05 7.736E-05 524. 9.600E-05 9.302E-05 524. 9.223E-04 8.924E-04 WNW 643. 643. 5.023E-05 4.863E-05 643. 6.090E-05 5.896E-05 643. 6.002E-04 5.808E-04 W 762. 762. 4.160E-05 4.028E-05 762. 4.841E-05 4.687E-05 762. 4.228E-04 4.090E-04 NW 890. 890. 3.985E-05 3.858E-05 890. 4.152E-05 4.020E-05 890. 3.279E-04 3.172E-04 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 l

l EPSPROJ/odem,1asaNe/frt-7f F-21 l *

\

LASALLE Rsvision 1.7 September 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-138 Downwind unrest.ricted Elevated (Stock) Reteese Mixed Mode (Vent) Release Ground Level Reteese ofrection Area bound Radius S $8AR Radius V VBAR Radius G G8AR (meters) (meters) (ared/yr)/(uCl/sec) (meters) (ared/yr)/(uCl/sec) (meters) (ared/yr)/(uCl/sec)

N 1036. 1036. 3.926E-04 3.816E-04 1036. 4.523E-04 4.396E-04 1036. 3.178E-03 3.084E-03 NME 1378. 1378. 3.160E-04 3.071E-04 1378. 3.536E-04 3.437E-04 1378. 2.117E-03 2.055E-03 NE 2408. 2408. 1.356E-04 1.318E-04 2408. 1.379E-04 1.340E-04 2408. 7.244E-04 7.032E-04 ENE 4450. 4450. 4.939E-05 4.799E-05 4450. 4.572E-05 4.443E-05 4450. 1.769E-04 1.718E-04 E 1996. 1996. 1.540E-04 1.497E-04 1996. 1.535E-04 1.492E-04 1996. 8.921E-04 8.659E-04 ESE 1465. 1465. 2.766E-04 2.689E-04 1465. 2.804E-04 2.725E-04 1465. 1.532E-03 1.487E-03 SE 969. %9. 3.938E-04 3.828E-04 M9. 4.408E-04 4.285E-04 M9. 2.641E-03 2.564E-03 SSE 838. 838. 4.037E-04 3.924E-04 838. 4.484E-04 4.358E-04 838. 2.628E-03 2.551E-03 5 829. 829. 3.457E-04 3.360E-04 829. 3.560E-04 3.460E-04 829. 2.809E-03 2.727E-03 SSW 835. 835. 3.277E-04 3.186E-04 835. 3.832E-04 3.724E-04 835. 1.828E-03 1.774E-03 SW 628. 628. 5.698E-04 5.538E-04 628. 7.209E-04 7.007E-04 628. 4.546E-03 4.412E-03

• Wsw 533. 533. 6.144E-04 5.973E-04 533. 7.121E-Gi 6.921E-04 533. 5.206E-03 5.053E-03 W 524. 524. 5.976E-04 5.809E-04 524. 7.318E-04 7.113E-04 524. 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 3.635E-03 NNW 890. 890. 3.330E-04 3.236E-04 890. 3.626E-04 3.52SE-04 890. 3.069E-03 2.978E-03 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 l

I WROJedcmMasans/ht-7f 4 92 e,

n n

~

c LA _,iLE R ,vis u .7 September 1995 Table F-7 (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Ar-41 1

Doermeind Unrestricted Elevated (Stock) Release Mixed Node (Vent) Reteese Groemd Levet Release Direction Area Sound Radius S SSAR Radius V VSAR Radius G GSAR (seters) (meters) (arad/yr)/(uci/sec) (meters) (ared/yr)/(uct/sec) (meters) (erad/yr)/(uct/sec)

N 1036. 1036. 4.746E-04 4.594E-04 1036. 5.528E-04 5.351E-04 1036. 4.557E-03 4.411E-03 NNE 1378. 1378. 3.954E-04 3.828E-04 1378. 4.439E-04 4.297E-04 1378. 3.203E-03 3.101E-03 NE 2408. 2408. 1.925E-04 1.863E-04 2408. 2.045E-04 1.900E-04 2408. 1.387E-03 1.343E-03

• ENE 4450. 4450. 9.141E-05 8.848E-05 4450. 9.061E-05 8.772E-05 4450. 5.219E-04 5.052E-04 E 1996. 1996. 2.110E-04 2.043E-04 1996. 2.180E-04 ?.110E-04 1996. 1.658E-03 1.605E-03 ESE 1465. 1465. 3.480E-04 3.368E-04 1465. 3.593E-04 3.478E-04 1465. 2.459E-03 2.381E-03 SE 969. M9. 4.711E-04 4.560E-04 M9. 5.320E-04 5.149E-04 M9. 3.715E-03 3.597E-03 SSE 838. 838. 4.761E-04 4.608E-04 838. 5.378E-04 5.206E-04 838. 3.671E-03 3.554E-03 i S 829. 829. 4.168E-04 4.035E-04 829. 4.533E-04 4.388E-04 829. 3.823E-03 3.701E-03 i SSW 835. 835. 3.994E-04 3.866E-04 835. 4.930E-04 4.772E-04 835. 2.700E 03 2.614E-03 .

SW 628. 628. 6.711E-04 6.496E-04 628. 8.591E-04 8.316E-04 628. 6.139E-03 5.943E-03 ,

WSW 533. 533. 7.089E-04 6.862E-04 533. 8.229E-04 7.966E-04 533. 6.667E-03 6.453E-03  !

W 524. 524. 6.802E-04 6.584E-04 524. 8.291E-04 8.026E-04 524. 8.057E-03 7.799E-03 643. 643. 4.708E-04 4.558E-04 643. 5.716E-04 5.533E-04 643. 6.300E-03 6.099E-03 WNW NW 762. 762. 4.123E-04 3.991E-04 762. 4.970E-04 4.811E-04 762. 5.1734-03 5.000E-03 j NNW 890. 890. 4.02SE-04 3.896E-04 890. 4.447E-04 4.305E-04 890. 4.374E-03 4.234E-03 i

i

- LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 i

l EPSPROJ/odem/lasane/fri-7f F.23 i

LASALLE R vision 1.7 Sept 5mber 1995 Table F-7a Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-83m Downwind Restricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bomd Radius S 58AR Radius V VBAR Radius G GBAR (sieters) (meters) (arad/yr)/(ucl/sec) (meters) (arad/yr)/(uti/sec) (meters) (arad/yr)/(uti/sec)

N 1036. 1036. 4.787E-07 3.609E-07 1036. 5.281E-07 3.982E-07 1036. 1.785E-04 1.346E-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 5.497E-07 1609. 8.106E-05 6.112E-05 ENE 1079. 1079. 4.160E-07 3.137E-07 1079. 8.010E-07 6.039E-07 1079. 1.322E-04 9.967E-05 E 1055. 1055. 3.476E-07 2.621E-07 1055. 9.181E-07 6.923E-07 1055. 1.483E-04 1.118E-04 ESE 1055. 1055. 4.371E-07 3.296E-07 1055. 1.175E-06 8.856E-07 1055. 1.394E-04 1.051E-04 SE 969. %9. 3.545E-07 2.673E-07 969. 1.267E-06 9.554E-07 969. 1.333E-04 1.005E-04 SSE 698. 698. 2.415E-07 1.821E-07 698. 1.646E-06 1.241E-06 698. 1.773E-04 1.337E-04 s 820. 820. 2.803E-07 2.114E-07 820. 1.047E-06 7.895E-07 820. 1.354E-04 1.021E-04 SSW 835. 835. 3.185E-07 2.401E-07 835. 1.071E-06 8.076E-07 835. 9.326E-05 7.032E-05 SW 628. 628. 3.177E-07 2.395E-07 628. 2.826E-06 2.131E-06 628. 2.305E-04 1.738E-04 WSW 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 WNW 643. 643. 1.714E-07 1.292E-07 643. 7.235E-07 5.455E-07 643. 2.728E-04 2.057E-04 NW 762. 762. 1.744E-07 1.315E-07 762. 4.391E-07 3.311E-07 762. 2.219E-04 1.673E-04 NNW 890. 890. 2.397E-07 1.807E-07 890. 3.334E-07 2.514E-07 890. 1.823E-04 1.374E-04 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, Fn is the resulting dose factor at the new range (!.e. 833). Fn, is the va!ue provided in the above ODCM tables (i.e. S, SBAR, V, VBAR, G, GBAR). R is the former RAB distance (i.e.1055), and R is the RAB distanco (i.e. 833).

F,=F ]exp1.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

Not3: Based on Reference 1 of Section F.2 and the formulas in Sections B.5 and B.6 of Appendix B.

EPsPROJAodem/lasalle/fri-7f e .

4F-4 e.. _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _

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

L E Rsvis .7 Septamber 1995 Table F-7a (Continued) ,

I Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-85m Downwind Restricted Elevated (Stock) Reteese Mised Mode (Vent) Reteese Ground Level Roteese  ;

i Olrection Area Boted Radius S SSAR Radius V V8AR Radius G G8AR (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(ucl/sec) (meters) (ared/yr)/(LCl/sec) ,

N 1036. 1036. 5.747E-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 1609. 1609. 3.632E-05 3.512E-05 1609, 3.847E-05 3.720E-05 1609. 5.003E-04 4.790E-04 ENE 1079. 1079. 4.315E-05 4.174E-05 1079. 4.569E-05 4.419E-05 1079. 7.345E-04 7.037E-04 I E 1055. 1055. 4.572E-05 4.424E-05 1055. 5.053E-05 4.886E-05 1055. 8.134E-04 7.792E-04 ESE 1055. 1055. 5.730E-05 5.544E-05 1055. 6.298E-05 6.090E-05 1055. 8.020E-04 7.687E-04 SE M9. M9. 5.596E-05 5.415E-05 969. 6.610E-05 6.391E-05 969. 7.793E-04 7.470E-04 SSE 698. 698. 6.471E-05 6.263E-05 698. 7.905E-05 7.643E-05 698. 9.815E-04 9.404E-04 5 820. 820. 4.756E-05 4.603E-05 820. 5.386E-05 5.200E-05 820. 8.103E-04 7.769E-04 ssW 835. 835. 4.422E-05 4.279E-05 835. 5.351E-05 5.174E-05 835. 5.684E-04 5.450E-04 ,

SW 628. 628. 7.281E-05 7.046E-05 628. 9.952E-05 9.618E-05 628, 1.285E-03 1.231E-03 WSW 533. 533. 7.757E-05 7.507E-05 533. 9.714E-05 9.388E-05 533. 1.389E-03 1.331E-03 i W 524. 524. 7.601E-05 7.356E-05 524. 9.70$E-05 9.385E-05 524. 1.687E-03 1.614E-03 l WNW 643. 643. 5.286E-05 5.116E-05 643. 6.615E-05 6.399E-05 643. 1.327E-03 1.270E-03 i 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 l LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 i

- The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of rar:ge. the dose factors were re-evaluated using the following equation. Here, Fn is the resulting dose factor at the new range (i.e. 833). Fn , is the value provided in the above ODCM tables (i.e. S, SBAR, V. VBAR, G. GBAR). R, is the former RAB distance (i.e.1055) and R is the RAB distance (i.e. 833).

F,=F ]exp1.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors no further adjustment in the above factors is considered necessary.

EPSPROJAodemMasate/Irt-7f F-25

LASALLE R vision 1.7 Septsmber 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-85 Mixed Mode (Vent) Release Grotrid Level Release Downwind Restricted Elevated (Stack) Release V VBAR Radius G G8AR Direction Area Bound Radius s 58AR Radius (meterst) (meters) (mrad /yr)/(uCl/sec) (meters) (arad/yr)/(uCI/sec) (meters) (arad/yr)/(uCI/sec) 1036. 8.547E-07 8.265E-07 1036. 9.889E-07 9.563E-07 1036. 1.056E-05 1.021E-05 N 1036. 7.474E-06 7.227E-06 1378. 7.309E-07 7.068E-07 1378. 8.077E-07 7.811E-07 1378.

NME 1378. 5.559E-06 5.375E-06 1609. 5.225E-07 5.052E-07 1609. 5.615E-07 5.430E-07 1609.

NE 1609.

1079. 6.463E-07 6.249E-07 1079. 6.707E-07 6.486E-07 1079. 8.057E-06 7.791E-06 ENE 1079. 8.923E-06 8.628E-06 1055. 4.819E-07 6.594E-07 1055. 7.385E-07 7.142E-07 1055.

E 1055.

1055. 8.484E-07 8.204E-07 1055. 9.108E-07 8.808E-07 1055. 8.808E-06 8.517E-06 ESE 1055.

sE 969. 969. 8.386E-07 8.110E 07 969. 9.583E-07 9.267E-07 %9. 8.555E-06 8.273E-06 698. 9.869E-07 9.543E-07 698. 1.153E-06 1.115E-06 698. 1.072E-05 1.036E-05 ssE 698.

820. 7.333E-07 7.091E-07 820. 8.154E-07 7.885E-07 820. 8.866E-06 8.574E-06 s 820.

835. 6.857E-07 6.630E-07 835. 8.402E-07 8.124E-07 835. 6.270E-06 6.063E-06 ssu 835.

628. 1.142E-06 1.104E-06 628. 1.494E-06 1.444E-06 628. 1.401E-05 1.355E-05 sw 628.

533. 1.211E-06 1.171E-06 533. 1.433E-06 1.386E-06 533. 1.510E-05 1.460E-05 Wsv 533.

524. 1.172E-06 1.134E-06 524. 1.443E-06 1.395E-06 524. 1.824E-05 1.763E-05 -

W 524.

643. 8.185E-07 7.915E-07 643. 1.000E-06 9.670E-07 643. 1.436E-05 1.389E-05 WWW 643.

762. 7.192E-07 6.954E-07 762. 8.694E-07 8.407E-07 762. 1.188E-05 1.148E-05 NW 762.

890. 890. 7.128E-07 6.893E-07 890. 7.849E-07 7.590E-07 890. 1.011E-05 9.778E-06 NNw LAsALLE stTE METEOROLOGICAL DATA 1/78 - 12/87

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, Fn is the resulting dose factor at the new range (i.e. 833). Fn , is the value provided in the above ODCM tables (i.e. S, SBAR, V, VBAR, G GBAR). R, is the former RAB distance (i.e.1055) and R is the RAB distance (i.e. 833).

F,=F jexp1.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

1 E4P ROJtdemMasalle/fr1-7f 3 9

LA LE Rt.vis .7 September 1995 Table F-7a (Continue ()

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-87 Mixed Mode (Vent) Reteese Grossid Level Reteese Dowwind Restricted Elevated (Stock) Reteese V8AR Redfus G GSAR Direction Area Oound Radius S 58AR Radius V (seters) (meters) (arad/yr)/(uCl/sec) (meters) (ared/yr)/(uCl/sec) (meters) (arad/yr)/(uti/sec) 1036. 1036. 3.226E-04 3.135E-04 1036. 3.758E-04 3.652E-04 1036. 2.879E-03 2.795E-03 N

1378. 1378. 2.672E-04 2.597E-04 1378. 3.005E-04 2.920E-04 1378. 2.019E-03 1.960E-03 NNE 1609. 1609. 1.908E-04 1.853E-04 1609. 2.038E-04 1.981E-04 1609. 1.480E-03 1.437E-03 NE 1079. 1079. 2.430E-04 2.361E-04 1079. 2.534E-04 2.462E-04 1079. 2.192E-03 2.129E-03 ENE 1055. 1055. 2.601E-04 2.528E-04 1055. 2.785E-04 2.706E-04 1055. 2.423E-03 2.353E-03 E

1055. 1055. 3.217E-04 3.125E-04 1055. 3.412E-04 3.315E-04 1055. 2.407E-03 2.337E-03 ESE 969. 969. 3.211E-04 3.120E-04 M9. 3.612E-04 3.510E-04 969. 2.355E-03 2.287E-03 SE 698. 698. 3.885E-04 3.776E-04 698. 4.423E-04 4.298E-04 698. 2.985E-03 2.898E-03 SSE 820. 820. 2.881E-04 2.800E-04 820. 3.117E-04 3.029E-04 820. 2.467E-03 2.396E-03 5

835. 835. 2.742E-04 2.665E-04 835. 3.400E-04 3.305E-04 835. 1.706E-03 1.657E-03 SSW 628. 628. 4.614E-04 4.484E-04 628. 5.936E-04 5.769E-04 628. 3.903E-03 3.790E-03 SW 533. 533. 4.880E-04 4.743E-04 533. 5.683E-04 5.523E-04 533. 4.251E-03 4.128E-03 WSW 524. 524. 4.675E-04 4.543E-04 524. 5.708E-04 5.547E-04 524. 5.136E-03 4.986E-03 W

643. 643. 3.224E-04 3.133E-04 643. 3.914E-04 3.804E-04 643. 4.001E-03 3.884E-03 WWW 762. 762. 2.823E-04 2.743E-04 762. 3.397E-04 3.301E-04 762. 3.276E-03 3.180E-03 NW 890. 890. 2.747E-04 2.669E-04 890. 3.031E-04 2.945E-04 890. 2.763E-03 2.683E-03 NNW LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here. nF is the resulting dose factor at the new range (i.e. 833). Fn , is the value provided in the above ODCM tables (i.e. S. SBAR, V, VBAR. G. GBAR). R,is the former RAB distance (i.e.1055) and R is the RAB distance (i.e. 833).

F,=F jexp1.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

EPSPROJ/odemMasane/frt-7f F-27

LASALLE Rt.; vision 1.7 S ptamber 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-88 Downwind Restricted Elevated (Stack) Reteese Mixed Mode (Vent) Reteese Growed Level Release s S8AR Radius- V VBAR Radius G GBAR Direction Area Bound Radius (meters) (meters) (mrad /yr)/(uci/sec) (meters) (arad/yr)/(uCl/sec) (meters) (ared/yr)/(ucl/sec)

N 1036. 1036. 8.602E-04 8.374E-04 1036. 1.003E-03 9.769E-04 1036. 6.988E-03 6.787E-03 NNE 1378. 1378. 7.111E-04 6.922E-04 1378. 7.989E-04 7.777E-04 1378. 4.940E-03 4.798E-03 NE 1609. 1609. 5.067E-04 4.932E-04 1609. 5.485E-04 5.340E-04 1609. 3.656E-03 3.552E-03 1079. 1079. 6.528E-04 6.355E-04 1079. 6.769E-04 6.589E-04 1079. 5.337E-03 5.184E-03 ENE 1055. 1055. 6.915E-04 6.732E-04 1055. 7.419E-04 7.222E-04 1055. 5.907E-03 5.737E-03 E

1055. 1055. 8.514E-04 8.288E-04 1055. 9.030E-04 8.790E-04 1055. 5.857E-03 5.689E 03 ESE SE 969. 969. 8.537E-04 8.311E-04 M9. 9.571E-04 9.317E-04 M9. 5.712E-03 5.549E-03 698. 698. 1.034E-03 1.007E-03 698. 1.172E-03 1.141E-03 698. 7.193E-03 6.986E-03 SSE 820. 820. 7.777E-04 7.571E-04 820. 8.513E-04 8.287E-04 820. 5.947E-03 5.777E-03 s

835. 835. 7.427E-04 7.231E-04 835. 9.375E-04 9.127E-04 835. 4.167E-03 4.048E-03 ssW SW 628. 625. 1.246E-03 1.213E-03 628. 1.601E-03 1.559E-03 628. 9.396E-03 9.126E-03 533. 533. 1.314E-03 1.279E-03 533. 1.52SE-03 1.485E-03 533. 1.017E-02 9.882E-03 WSW -

524. 524. 1.249E-03 1.216E-03 524. 1.520E-03 1.480E-03 524. 1.225E-02 1.190E-02 W

643. 643. 8.669E-04 8.440E-04 643. 1.045E-03 1.01 7 03 643. 9.595E-03 9.317E-03 WNW 762. 762. 7.580E-04 7.379E-04 762. 9.125E-04 8.876E-04 762. 7.895E-03 7.666E-03 NW 890. 890. 7.369E-04 7.174E-04 890. 8.161E-04 7.945E-04 890. 6.693E-03 6.500E-03 NNW LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 l

The changerestricted of range, thearea dose f boundary (RAB) was actors were re-evaluated usingredefined in sectors the following equation. Here,EF nand ESE to 833 and 848 from 1055 and 1055 l

the va!ue provided it: the above ODCM tables (i.e. S, SBAR, V, VBAR, G, GBAR). R, is the former RAB distance (i.e.1055) and R is the RAB distance

! (i.e. 833).

I F,=F jexp1.5

{'

This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the l expected error of the current factors, no further adjustment in the above factors is considered necessary.

3ROJ/odem/lasalle/frt-71 5 9 .

_. ._ _ _ _ -._ -_._._m . _ _ . _ _ _ . _ . . _ . . _ . _ . . . . _ _ _ _ _ . _ _ _ . ._.

L LE R:vi .7 Septamber 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-89 Downwind Restricted Elevated (steck) Reteese Mixed Mode (Vent) Releese Ground Level Reteese Direction Areq.Botsid Radius 5 SSAR Radius V VSAR Radius G GBAR (meters) (meters) (ared/yr)/(ucl/sec) (meters) (ared/yr)/(ucl/sec) (meters) (ared/yr)/(uCi/sec) l N 1036. 1036. 3.90&E-04 3.794E-04 1036. 4.258E-04 4.139E-04 1036. 2.051E-03 1.992E-03 NME 1378. 1378. 2.820E-04 2.741E-04 1378. 2.988E-04 2.904E-04 1378. 1.151E-03 1.118E-03 NE 1609. 1609. 1.750E-04 1.701E-04 1609. 1.654E-04 1.607E-04 1609. 6.564E-04 6.375E-04 ENE 1079. 1079. 2.703E-04 2.628E-04 1079. 2.619E-04 2.545E-04 1079. 1.450E-03 1.409E-03 E 1055. 1055. 3.041E-04 2.956E-04 1055. 2.972E-04 2.888E-04 1055. 1.569E-03 1.524E-03 ESE 1055. 1055. 3.931E-04 3.821E-04 1055. 3.909E-04 3.800E-04 1055. 1.682E-03 1.633E-03 SE M9. 969. 3.891E-04 3.782E-04 M9. 4.188E-04 4.070E-04 969. 1.846E-03 1.793E-03 SSE 698. 698. 5.333E-04 5.184E-04 698. 5.797E-04 5.634E-04 698. 2.722E-03 2.643E-03 s 820. 820. 3.464E-04 3.367E-04 820. 3.312E-04 3.219E-04 820. 2.083E-03 2.023E-03 ssu 835. 835. 2.921E-04 2.839E-04 835. 2.779E-04 2.702E-04 835. 1.021E-03 9.916E-04 su 628. 628. 5.830E-04 5.667E-04 628. 6.600E-04 6.415E-04 628. 3.274E-03 3.180E-03 Wsw 533. 533. 6.913E-04 6.720E-04 533. 7.525E-04 7.314E-04 533. 4.592E-03 4.460E-03 .

W 524. 524. 6.%1E-04 6.766E-04 524. 8.259E-04 8.028E-04 524. 5.%7E-03 5.796E-03 WNW 643. 643. 4.295E-04 4.174E-04 643. 5.147E-04 5.003E-04 643. 3.746E-03 3.638E-03 NW 762. 762. 3.500E-04 3.402E-04 762. 4.035E-04 3.922E-04 762. 2.561E-03 2.488E-03 NNW 890. 890. 3.301E-04 3.208E-04 890. 3.415E-04 3.319E-04 890. 1.966E-03 1.909E-03 LASALLE SITE NETEOROLOGlcAL DATA 1/78 - 12/87

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this ,

change of range. the dose factors were re-evaluated using the following equation. Here.nF is the resulting dose factor at the new range (i.e. 833). Fn, is the value provided in the above ODCM tables (i.e. S, SBAR, V, VBAR, G, GBAR). R. is the former RAB distance (i.e.1055) and R is the RAB distance (i.e. 833).

F,=F,[ ]exp1.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

EPSPROJhdemMasalle/fr1-7f F-29 m__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _

LASALLE R: vision 1.7 Sept *,mber 1995

'- Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-90 Downwind Restricted Elevated (stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Bound Radius s sBAR Radius V V8AR Radius G G84R (meters) (meters) (arad/yr)/(uCl/sec) (meters) (mrad /yr)/(uCI/sec) (meters) (arad/yr)/(uCl/sec)

N 1036. 1036. 6.785E-05 6.586E-05 1036. 5.199E-05 5.047E-05 1036. 8.203E-05 7.954E-05 NNE 1378. 1378. 3.195E-05 3.102E-05 1378. 2.161E-05 2.098E-05 1378. 2.265E-05 2.196E-05 NE 1609. 1609. 1.240E-05 1.203E-05 1609. 6.949E-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. 4.577E-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 1.046E-04 sE 969. M9. 5.843E-05 5.673E-05 M9. 5.324E-05 5.168E-05 M9. 1.365E-04 1.324E-04 ssE 698. 698. 1.170E-04 1.136E-04 698. 1.103E-04 1.070E-04 698. 2.578E-04 2.500E-04 s 820. 820. 5.233E-05 5.081E-05 820. 3.888E-05 3.775E-05 820. 1.108E-04 1.075E-04 ssW 835. 835. 3.062E-05 2.972E-05 835. 1.274E-05 1.237E-05 835. 1.835E-05 1.779E-05 su 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 1.836E-04 533. 1.52SE-04 1.480E-04 533. 4.861E-04 4.713E-04 W 524. 524. 2.165E-04 2.101E-04 524. 2.185E-04 2.121E-04 524. 8.427E-04 8.170E-04 WNW 643. 643. 1.018E-04 9.883E-05 643. 1.008E-04 9.787E-05 643. 3.141E-04 3.045E-04 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. 5.72SE-05 5.558E-05 890. 4.336E-05 4.209E-05 890. 8.819E-05 8.551E-05 LAsALLE stTE METEOROLOGICAL DATA 1/78 - 12/87

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, Fn is the resulting dose factor at the new range (i.e. 833). Fn , is the value provided in the above ODCM tables (i.e. S, SBAR, V, VBAR, G, GBAR). R,is the former RAB distance (i.e.1055) and R is the RAB distance (i.e. 833).

F,=Fa,[ ]exp1.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors. no further adjustment in the above factors is considered necessary.

8 ROJhdenviasans/trl-7f E4P 9 5 4

% (3 (

. L L iLE RtvifV.7 Septsmber 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-131m Dounwind Restricted Elevated (stack) Release Mixed Mode (Vent) Reteese Gromd Level Reteese Oirection Area 59md Radius s S8AR Radius V VBAR Radius G GBAR (meters) (meters) (arad/yr)/(uct/sec) (meters) (arad/yr)/(uct/sec) (meters) (ared/yr)/(uct/sec)

N 1036. 1036. 1.606E-06 1.473E-06 1036. 1.827E-06 1.679E-06 1036. 1.645E-04 1.283E-04 NME 1378. 1378. 1.778E-06 1.572E-06 1378. 1.726E-06 1.553E-06 1378. 1.072E-04 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 ENE 1079. 1079. 1.254E-06 1.143E-06 1079. 1.612E-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-04 1.073E-04 ESE 1055. 1055. 1.566E-06 1.442E-06 1055. 2.270E-06 1.990E-06 1055. 1.290E-04 1.014E-04 SE %9. %9. 1.472E-06 1.365E-06 M9. 2.406E-06 2.115E-06 M9. 1.240E-04 9.696E-05 ssE 698. 698. 1.566E-06 1.476E-06 698. 2.M9E-06 2.597E-06 698. 1.624E-04 1.267E-04 s 820. 820. 1.238E-06 1.151E-06 820. 1.983E-06 1.742E-06 820. 1.253E-04 9.802E-05 ssW 835. 835. 1.196E-06 1.103E-06 835. 2.003E-06 1.755E-06 835. 8.790E-05 6.885E-05 sv 628. 628. 1.802E-06 1.691E-06 628. 4.345E-06 3.728E-06 678. 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-04 W 524. 524. 1.800E-06 1.703E-06 524. 3.359E-06 2.972E-06 524. 3.000E-04 2.335E-04 WNW 643. 643. 1.263E-06 1.194E-06 643. 1.976E-06 1.791E-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

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, Fn is the resulting dose 6, tor at the new range (i.e. 833). Fn, is the value provided in the above ODCM tables (i.e. S, SBAR, V, VBAR. G, GBAR). R,is the former RAB d, stance (i.e.1055) and R is the RAB distance (i.e. 833).

F,=Fn,[ jexp1.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expacted error of the current factors, no further adjustment in the above factors is considered necessary.

EPSPROJ>bdcm/lasate/fri-7f p.31

- - - _ _ _ _ . _ _ _ _ . _ _ _ . . . - _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - _ _ _ _ - _ - - _ - __ _ _ - _ _ - - - a

LASALLE R: vision 1.7 September 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133m Dowwind Restricted Elevated (Stack) Release Mixed Mode (Vent) Release Gromd Levet Release Of rection Area Bomd Radius S 58AR Radius V VBAR Radius G GSAR (meters) (meters) (mrad /yr)/(uCl/sec) (meters) (arad/yr)/(uCl/sec) (meters) (arad/yr)/(uCl/sec)

N 1036. 1036. 8.557E-06 8.199E-06 1036. 9.814E-06 9.407E-06 1036. 2.822E-04 2.410E-04 NNE 1378. 1378. 7.917E-06 7.509E-06 1378. 8.400E-06 8.009E-06 1378. 1.901E-04 1.633E-04 NE 1609. 1609. 5.729E-06 5.423E-06 1609. 6.093E-06 5.768E-06 1609 1.389E-04 1.195E-04 ENE 1079. 1079. 6.486E-06 6.205E-06 1079. 7.141E-06 6.771E-06 1079. 2.121E-04 1.815E-04 E 1055. 1055. 6.770E-06 6.492E-06 1055. 7.917E-06 7.501E-06 1055. 2.368E-04 2.024E-04 ESE 1055. 1055. 8.481E-06 8.132E-06 1055. 9.879E-06 9.355E-06 1055, 2.276E-04 1.951E-04 SE 969. 969. 8.229E-06 7.903E-06 969. 1.039E-05 9.834E-06 %9. 2.189E-04 1.879E-04 SSE 698. 698. 9.363E-06 9.021E-06 698. 1.250E-05 1.181E-05 698. 2.815E-04 2.409E-04 S 820. 820. 6.991E-06 6.718E-06 820. 8.532E-06 8.075E-06 820. 2.236E-04 1.923E-04 SSW 835. 835. 6.541E-06 6.276E-06 835. 8.500E-06 8.036E-06 835. 1.574E-04 1.354E-04 SW 628. 628. 1.059E-05 1.020E-05 628. 1.637E-05 1.535E-05 628. 3.668E-04 3.140E-04 USW 533. 533, 1.121E-05 1.081E-05 533. 1.588E-05 1.490E-05 533. 4.005E-04 3.423E-04 ,

W 524. 524. 1.096E-05 1.056E-05 524. 1.504E-05 1.427E-05 524. 5.039E-04 4.287E-04 WNW 643. 643. 7.648E-06 7.374E-06 643. 9.956E-06 9.510E-06 643. 4.055E-04 3.441E-04 NW 762. 762. 6.774E-06 6.526E-06 762. 8.435E-06 8.088E-06 762. 3.334E-04 2.831E-04 NNW 890. 890. 6.855E-06 6.594E-06 890. 7.588E-06 7.286E-06 890. 2.794E-04 2.377E-04 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, nF is the resulting dose factor at the new range (i.e. 833). Fn, is the value provided in the above ODCM tables (i.e. S. SBAR, V, VBAR, G. GBAR). R is the former RAB distance (i.e.1055) and R is the RAB distance (i.e. 833).

F,-F,,[ ]exp1.5 This analysis indicates that th9 change in range would increase the dose factor error by approxima191y 40%. Since this difference is well within the l expected error of the current factors, no further adjustment in the above factors is considered necessary.

8E ROJ6denviasalle/fr1-7f 82 e,.

_ _ _ _ _ _ _._ _ .. ._. . _ _ _ _ . . _ _ _ __ _ .- __ _ . _ . = . . . . _- _ _ . _ _ _ ._ _ _ _

O

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Rr.viswI.-(

Septsmber 1995 Table F-7a (Continued) l Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133 Mixed Mode (Vent) Reteese Gromd Level Reteese Downwind Restricted Elevated (stock) Release Radius G GSAR Direction Area Sound Radius s sSAR Radius V VSAR (meters) (meters) (arad/yr)/(uCl/sec) (meters) (erad/yr)/(uCl/sec) (meters) (arad/yr)/(uCl/sec)

N 1036. 1036. 7.010E-06 6.757E-06 1036. 7.933E-06 7.649E-06 1036. 3.136E-04 2.785E-04 1378. 1378. 6.939E-06 6.629E-06 1378. 7.149E-06 6.860E-06 1378. 2.132E-04 1.903E-04 WWE NE 1609. 1609. 5.088E-06 4.853E-06 1609. 5.323E-06 5.076E-06 1609. 1.562E-04 1.397E-04 1079. 1079. 5.306E-06 5.106E-06 1079. 6.045E-06 5.769E-06 1079. 2.362E-04 2.101E-04 ENE E 1055. 1055. 5.535E-06 5.340E-06 1055. 6.764E-06 6.452E-06 1055. 2.632E-04 2.338E-04 1055. 1055. 7.016E 06 6.769E-06 1055. 8.566E-06 8.169E-06 1055. 2.543E-04 2.266E-04 ESE SE M9. %9. 6.641E-06 S.416E-06 M9. 8.978E-06 8.558E-06 969. 2.450E-04 2.185E-04 SSE 698. 698. 7.217E 06 6.994E-06 698. 1.073E-05 1.021E-05 698. 3.132E-04 2.785E-04 s 820. 820. 5.369E 06 5.188E-06 820. 7.024E-06 6.687E-06 820. 2.515E-04 2.246E-04 ssW 835. 835. 4.M9E-06 4.793E-06 835. 6.598E-06 6.266E-06 835. 1.770E-04 1.582E-04 su 628. 628. 7.798E-06 7.549E-06 628. 1.362E-05 1.285E-05 628. 4.090E-04 3.640E-04 WsW 533. 533. 8.245E 06 7.992E-06 533. 1.326E-05 1.252E-05 533. 4.447E-04 3.951E-04 W 524. 524. 8.166E-06 7.919E-06 524. 1.220E-05 1.164E-05 524. 5.551E-04 4.911E-04 WNW 643. 643. 5.715E 06 5.541E-06 643. T.885E-06 7.574E-06 643. 4.444E-04 3.922E-04 NW 762. 762. 5.117E-06 4.958E-06 762. 6.538E-06 6.303E-06 762. 3.661E-04 3.233E-04 NNW 890. 890. 5.340E 06 5.165E-06 890. 5.911E-06 5.708E-06 890. 3.000E-04 2.725E-04 LAsALLE SITE METEOROLOGICAL DATA 1/78 - 12/87

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here,nF is the resulting dose factor at the new range (i.e. 833). Fn, is the value provided in the above ODCM tab!es (i.e. S, SBAR, V, VBAR. G, GBAR). R is the former RAB distance (i.e.1055) and R is the RAB distance (i.e. 833).

F,mF jexp1.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

EPSPROJhderrAnsalle/frt-7f F-33

l LASALLE R; vision 1.7 S:pt3mber 1995 l

• Table F-7a (Continued)

I Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135m i

Mixed Mode (vent) Release Gromd Level Release Downwind Restricted Elevated (Stack) Reteese Radius G GSAR Direction Area Bound Radius S $8AR Radius V VRAR l

(meters) (meters) (arad/yr)/(uCl/sec) (meters) (arad/yr)/(uCl/sec) (meters) (mrad /yr)/(uti/sec) 1036. 1036. 1.396E-04 1.349E-04 1036. 1.598E-04 1.545E-04 1036. 1.531E-03 1.475E-03 N

1378. 1.151E-04 1.113E-04 1378. 1.274E-04 1.232E-04 1378. 1.019E-03 9.821E-04 NME 1378.

1609. 1609. 8.046E-05 7.779E-05 1609. 8.260E-05 7.985E-05 1609. 7.033E-04 6.778E-04 NE 1079. 1079. 1.024E-04 9.898E-05 1079. 1.064E-04 1.028E-04 1079. 1.147E-03 1.105E-03 ENE 1055. 1055. 1.121E-04 1.084E-04 1055. 1.183E-04 1.144E-04 1055. 1.253E-03 1.207E-03 E

1055. 1055. 1.411E-04 1.365E-04 1055. 1.490E-04 1.441E-04 1055. 1.256E-03 1.211E-03 ESE 969. 969. 1.389E-04 1.343E-04 969. 1.575E-04 1.522E-04 M9. 1.262E-03 1.216E-03 SE 698. 698. 1.692E-04 1.636E-04 698. 1.955E-04 1.890E-04 698. 1.667E-03 1.606E-03 SSE 820. 820. 1.196E-04 1.157E-04 820. 1.251E-04 1.209E-04 820. 1.363E-03 1.314E-03 s 8.762E-04 8.444E-04 835. 835. 1.104E-04 1.068E-04 835. 1.260E-04 1.218E-04 835.

ssu 2.173E-03 2.094E-03 628. 628. 1.904E-04 1.841E-04 628. 2.444E-04 2.363E-04 625.

su 533. 533. 2.063E-04 1.995E-04 533. 2.427E-04 2.345E-04 533. 2.479E-03 2.388E-03 WSW 524. 524. 2.033E-04 1.966E-04 524. 2.511E-04 2.427E-04 524. 3.050E-03 2.937E-03 W

643. 643. 1.363E-04 1.318E-04 643. 1.687E-04 1.631E-04 643. 2.286E-03 2.201E-03 WNW 762. 762. 1.187E-04 1.148E-04 762. 1.423E-04 1.376E-04 762. 1.806E-03 1.739E-03 NW 890. 890. 1.161E-04 1.122E-04 890. 1.259E-04 1.217E-04 890. 1.482E-03 1.427E-03 NNW LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, F, is the resulting dose factor at the new range (i.e. 833). Fn, is the value provided in the above ODCM tables (i.e. S SBAR, V VBAR, G, G8AR). R. is the former RAB distance (i.e.1055) and R is the RAB distance (i.e. 833).

F,=F jexp1.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

E#ROJedemMasans/fr17f 41 4 9 .

.m_- _ . . _ . . . _ - _ _ _ _ _ - . . - - _ - -.

. - _ . _ _ . - _ .__- m_ - . _ . . . _ _ . __ __.m___._.-_m---m.__-m..+- _ .._ -

() ()

s LA M E R:viskd7 September 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135 Downuind Restricted Elevated (Stock) Reteese Nined Mode (Vent) Reteese Groned Level Release Direction Area Sound Radius S 58AR Radius V V8AR Radius G G8AR 1 (meter"s) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uCI/sec)

N 1036. 1036. 8.165E-05 7.902E-03 1036. 9.387E-05 9.085E-05 1036. 1.302E-03 1.257E-03 [

NNE 1378. 1378. 7.171E-05 6.940E-05 1378. 7.821E-05 7.569E-05 1378. 9.178E-04 8.866E-04 i NE 1609. 1609. 5.140E-05 4.974E-05 1609. 5.463E-05 5.286E-05 1609. 6.801E-04 6.570E-04  !

ENE 1079. 1079. 6.139E-05 5.942E-05 1079. 6.476E-05 6.267E-05 1079. 9.912E-04 9.573E-04 .

E 1055. 1055. 6.493E-05 6.284E-05 1055. 7.155E-05 6.924E-05 1055. 1.097E-03 1.060E-03  ?

ESE 1055. 1055. 8.130E-05 7.869E-05 1055. 8.905E-05 8.617E-05 1055. 1.083E-03 1.046E-03 l SE M9. M9. 7.953E-05 7.697E-05 969. 9.346E-05 9.044E-05 969. 1.052E-03 1.017E-03  ;

SSE 698. 698. 9.205E-05 8.910E-05 698. 1.117E-04 1.081E-04 698. 1.321E-03 1.276E-03 i 5 820. 820. 6.782E-05 6.564E-05 820. 7.666E-05 7.419E-05 820. 1.093E-03 1.056E-03 SSW 835. 835. 6.306E-05 6.103E-05 835. 7.636E-05 7.389E-05 835. 7.699E-04 7.438E-04 i SW 628. 628. 1.039E-04 1.006E-04 628. 1.409E-04 1.363E-04 628. 1.729E-03 1.670E-03  !

Wsu 533. 533. 1.106E-04 1.071E-04 533. 1.372E-04 1.328E-04 533. 1.864E-03 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 }

WWW 643. 643. 7.538E-05 7.296E-05 643. 9.395E-05 9.092E-05 643. 1.775E-03 1.713E-03 i NW 762. 762. 6.654E-05 6.440E-05 762. 8.098E-05 7.838E-05 762. 1.466E-03 1.415E-03 i NNW 890. 890. 6.671E-05 6.456E-05 890. 7.327E-05 7.092E-05 890. 1.247E-03 1.204E-03 ,

1 LAsALLE SITE METEOROLOGICAL DATA 1/78 - 12/87 l

• = The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this ,

change of range, the dose factors were re-evaluated using the following equation. Here, nF is the resulting dose factor at the new range (i.e. 833). Fn, is the value provided in the above ODCM tables (i.e. S, SBAR, V VBAR, G, GBAR). R, is the former RAB distance (i.e.1055) and R is the RAB distance (i.e. 833).

F,=F.,[ ]exp1.5 i

This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the  !

expected error of the current factors no further adjustment in the above factors is considered necessary. j EPSPROJ/odem!!asene/fr1-7f F-35 l t

L

LASALLE R vision 1.7 September 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-137 Downwind Restricted Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Area Sound Radius S $8AR Radius V VBAR Radius G GBAR (meters) (meters) (mrad /yr)/(uCl/sec) (meters) (msrad/yr)/(uct/sec) (meters) (arad/yr)/(uCl/sec)

N 1036. 1036. 4.780E-05 4.627E-05 1036. 5.242E-05 5.074E-05 1036. 3.409E-04 3.298E-04 NME 1378. 1378. 3.585E-05 3.471E-05 1378. 3.814E-05 3.692E-05 1378. 1.975E-04 1.911E-04 NE 1609. 1609. 2.282E-05 2.209E-05 1609. 2.185E-05 2.115E-05 1609. 1.166E-04 1.128E-04 ENE- 1079. 1079. 3.342E-05 3.236E-05 1079. 3.282E-05 3.177E-05 1079. 2.437E-04 2.358E-04 E 1055. 1055. 3.741E-05 3.622E-05 1055. 3.716E-05 3.597E-05 1055. 2.625E-04 2.540E-04 ESE 1055. 1055. 4.827E-05 4.673E-05 1055. 4.871E-05 4.715E-05 1055. 2.I'65E-04 2.676E-04 SE 969. 969. 4.743E-05 4.591E-05 969. 5.188E-05 5.023E-05 M9. 2.199E-04 2.892E-04 SSE 698. 698. 6.273E-05 6.073E-05 698. 6.983E-05 6.760E-05 698. 4.329E-04 4.189E-04 S 820. 820. 4.133E-05 4.002E-05 820. 4.042E-05 3.913E-05 820. .1.373E-04 3.264E-04 SSW 835. 835. 3.521E-05 3.408E-05 835. 3.424E-05 3.315E-05 835. 1.748E-04 1.691E-04 SW 628. 628. 6.779E-05 6.563E-05 628. 7.938E-05 7.685E-05 628. 5.333E-04 5.161E-04 WSW 533. 533. 7.919E-05 7.667E-05 533. 8.829E-05 8.548E-05 533. 7.164E-04 6.932E-04 W 524. 524, 7.990E-05 7.736E-05 524. 9.608E-(6 9.302E-05 524. 9.223E-04 8.924E-04 WNW 643. 643. 5.023E-05 4.863E-05 643. 6.090E-05 5.896E-05 643. 6.002E-04 5.808E-04 NW 762. 762. 4.160E-05 4.028E-05 762. 4.841E-05 4.687E-05 762. 4.228E-04 4.090E-04 NNW 890. 890. 3.985E-05 3.858E-05 890. 4.152E-05 4.020E-05 890. 3.279E-04 3.172E-04 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here. nF is the resulting dose factor at the new range (i.e. 833). Fa , is the value provided in the above ODCM tables (i.e. S. SBAR. V, VBAR, G, GBAR). R, is the former RAB distance (i.e.1055) and R is the RAB distance (i.e. 833).

F,=F ]exp1.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors. no further adjustment in the above factors is considered necessary.

OJAodemMasmus/frt-71 E6P 6F- e..

fi b IJ vtE Rsvis:g.7 Q Sept 3mber 1995 Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-138 Mixed Mode (Vent) Reteese Ground Level Reteese Doeswirul Restricted Elevated (steck) Reteese Radius G GSAR s star Radium V VSAR Direction Area Botmd Radius (meters) (meters) (ared/yr)/(uct/sec) (meters) (ared/yr)/(uCI/sec) (meters) (ared/yr)/(ucl/sec) 1036. 1036. 3.926E-04 3.816E-04 1036. 4.523E-04 4.396E-04 1036. 3.178E-03 3.084E-03 N

NME 1378. 1378. 3.160E-04 3.071E-04 1378. 3.536E-04 3.437E-04 1378. 2.11TI-03 2.055E-03 NE 1609. 1609. 2.190E-04 2.136E-04 1609. 2.272E-04 2.200E-04 1609. 1.457E-03 1.414E-03 ENE 1079. 1079. 2.887E-04 2.806E-04 1079. 2.996E-04 2.912E-04 1079. 2.383E-03 2.313E-03 E 1055. 1055. 3.167E-04 3.079E-04 1055. 3.323E-04 3.230E-04 1055. 2.600E-03 2.524E-03 ESE 1055. 1055. 3.961E-04 3.850E-04 1055. 4.149E-04 4.032E-04 1055. 2.618E-03 2.541E-03 SE M9. 969. 3.938E-04 3.828E-04 M9. 4.400E-04 4.285E-04 969. 2.641E-03 2.564E-03 SSE 698. 698. 4.911E-04 4.773E-04 698. 5.540E-04 5.384E-04 698. 3.494E-03 3.391E-03 5 820. 820. 3.498E-04 3.400E-04 820. 3.606E-04 3.505E-04 820. 2.857E-03 2.773E-03 ssW 835. 835. 3.277E-04 3.186E-04 835. 3.832E-04 3.724E-04 835. 1.828E-03 1.774E-03 SW 628. 628. 5.690E 04 5.538E-04 628. 7.209E-04 7.007E-04 628. 4.546E-03 4.412E-03 WsW 533. 533. 6.144E-04 5.973E-04 533. 7.121E-04 6.921E-04 533. 5.206E-03 5.053E-03 W 524. 524. 5.976E-04 5.809E-04 524. 7.318E-04 7.113E-04 524. 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 3.635E-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 METEOROLOGICAL DATA 1/78 - 12/87

= The restilcted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here,nF is the resulting dose f8ctor at the new range (i.e. 833). Fn. is the value provided in the above ODCM tables (i.e. S SBAR, V, VBAR, G, GBAR). R,is the former RAB distance (i.e.1055) and R is the RAB distance (i.e. 833).

F,=F jexp1.5 -

This analysis indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

EPsPROJ/odern/lasahe/fr17f p.37 C

l LASALLE Rt. vision 1.7 September 1995 l

l Table F-7a (Continued)

Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Ar-41 Downsind Restricted Elevated (Stack) Release Mixed Mode (vent) Release Grotmd Level Release Direction Area Bound Radius S $8AR Radius V VBAR Radius G GBAR (meters) (meters) (erad/yr)/(ucl/sec) (meters) (arad/yr)/(uCl/sec) (meters) (arad/yr)/(uCl/sec)

N 1036. 1036. 4.746E-04 4.594E-04 1036. 5.528E-04 5.351E-04 1036. 4.557E-03 4.411E-03 NNE 1378. 1378. 3.954E-04 3.828E-04 1378. 4.439E-04 4.297E-04 1378. 3.203E-03 3.101E-03 NE 1609. 1609. 2.825E-04 2.734E-04 1609. 3.029E-04 2.932E-04 1609. 2.358E-03 2.283E-03 ENE 1079. 1079. 3.582E-04 3.468E-04 1079. 3.729E-04 3.610E-04 1079. 3.472E-03 3.361E-03 E 1055. 1055. 3.818E-04 3.696E-04 1055. 4.100E-04 3.969E-04 1055. 3.841E-03 3.718E-03 ESE 1055. 1055. 4.72SE-04 4.574E-04 1055. 5.025E-04 4.864E-04 1055. 3.807E-03 3.685E-03 SE 969. 969. 4.711E-04 4.560E-04 M9. 5.320E-04 5.149E-04 %9. 3.715E-03 3.597E-03 SSE 698. 698. 5.672E-04 5.490E-04 698. 6.491E-04 6.284E-04 698. 4.695E-03 4.545E-03 5 820. 820. 4.212E-04 4.077E-04 820. 4.585E-04 4.438E-04 820. 3.879E-03 3.755E-03 sSW 835. 835. 3.994E-04 3.866E-04 835. 4.930E-04 4.772E-04 835. 2.700E-03 2.614E-03 SW 628. 628. 6.711E-04 6.496E-04 628. 8.591E-04 8.316E-04 628. 6.139E-03 5.943E-03 Wsw 533. 533. 7.089E-04 6.862E-04 533. 8.229E-04 7.966E-04 533. 6.667E-03 6.453E-03 W 524. 524. 6.802E-04 6.584E-04 524. 5.291E-04 8.026E-04 524. 8.057E-03 7.799E-03 '

WNW 643. 643. 4.708E-04 4.558E-04 643. 5.716E-04 5.533E-04 643. 6.300E-03 6.099E-03 NW 762. 762. 4.123E-04 3.991E-04 762. 4.970E 04 4.811E-04 762. 5.173E-03 5.008E-03 NNW 890. 890. 4.025E-04 3.896E-04 890. 4.447E-04 4.305E-04 890. 4.374E-03 4.234E-03 LASALLE SITE METEOROLOGICAL DATA 1/78 - 12/87

= The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose f actors were re-evaluated using the following equation. Here, Fn is the resulting dose factor at the ne6 rarge (i.e. 833). Fn, is the value provided in the above ODCM tables (i.e. S SBAR, V, VBAR, G, GBAR). R is the former RAB distance (i.e.1055) ar d R is the RAB distance (i.e. 833).

F,=F jexp1.5 This analysis indicates that the change in range would increase the dose factor error by approximately 40% Since this difference is well within the expected error of the current factors, no further adjustment in the above factors is considered necessary.

E#ROJ/odemAasalla/fr1-7f 8E e..

LASALLE Revision 1.7 Septemb:r 1995

<w (g Table F-8 Parameters for Calculations of N-16 Skyshine Radiation From LaSalle Location Activity Occupancy Occupancy Shielding Distance Number Hours Factor

• Factor R, k O H,* OF, SF, (m) 1 Living at home 8360 0.95 0.7 1100*

(nearest resident) 2 Fishing 400 0.05 1.0 2100 3 Living at the 2500 0.7 2400 National Guard Facility M, = 5 K = 2.28E-05 mrem /(MWe-br)

These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of the public using Equation A 34 in Appendix A. If desired, more realistic parameters could be used in place of  ;

these to refine the estimate. For example, one could determine whether the nearest resident really fishes the specified number of hours at the specified location, a The amount of time in a year that a maximally exposed fisherman would spend fishing near the site is estimated as 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per week for 8 months per year. This yields an estimate of:

1

[12 hours / week) [(8 months /yr)/(12 months /yr)) x [52 weeks /yr) = 416 hours0.00481 days <br />0.116 hours <br />6.878307e-4 weeks <br />1.58288e-4 months <br /> /yr )

I The remaining time is assumed to be spent at the nearest residence.

l

. 1 b Distance to nearest residence (See Table F-3).

c The OF,is the quotient of the number of hours a location is occupied and the number of hours in a year.

Thus OH,/8760 hours - OF, rounded to the 0.01 digit, in determining the maximally exposed individual, the following possibilities were considered: the nearest resident, fishermen, and persons at the National Guard facility north of the site. The annual exposure time and location of a maximally exposed fisherman were estimated on the basis of discussion with a member of the station staff. The nearest resident was found to have the greatest exposure to skyshine. For details, see Reference 2 of Section F.2.

/"*%

!EPsPROJ/odemAasale/irt 7f F-39

Revision 1.7 Stptember 1995

- Supplemental Table A Elevated Level Joint Frequency Distribution Table Summary 375 Foot Elevation Data Summary Table of Percent..uy Ofrection and class ,

N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total Class A .024 .032 .067 .057 .062 .040 .030 .060 .056 .189 .087 .05t .056 *064

. .083 .024 .943 8 .349 .375 .227 .149 .080 .047 .056 .070 .233 '

.463 .330 .189 .145 .192 .153 .183 2.843 C .300 .262 .351 .255 .138 .069 .104 .130 .375 .579 .454 .361 .344 .420 .329 .332 4.806 3.192 2.780 1.945 1.767 2.053 2.810 2.875 2.270 2.460 3.248 4.533 3.922 3.681 46.551 D 3.100 2.634 3.282 1.531 1.575 2.065 1.670 1.196 27.061 E 1.018 .913 1.162 9.431 1.823 1.495 1.460 1.752 2.867 2.978 2.124

.382 .248 .260 .469 .707 .905 .995 1.459 1.735' t.561 1.041 1.012 1.099 .894 .553 .13.438 F .320 .217 .103 G .055 .039 g O22 .012 .041 .081 .278 .507 .674 .658 .660 .460 .309 .242 4.358 100.000 Total 4.965 4.237 5.359 5.356 5.394 4.385 4.601 5.567 8.474 9.457 7.487 6.093 8.688 8.615 7.248 6.073 Summary Table of Percent by Directton and Speed HE ENE ESE SE $$E S SSW SW WSW W WNW NW f4W Total Speed N PedE E

.013 .008 .018 .010 .000 .013 .000 .000 .001 .000 .137

.45 018 .017 .015 .010 .006 .010

.034 1.05 .018 .033 .030 .027 .021 .023 .032 .027 .027 .017 .017 .028 .021 .024 .027 .402

.255 .347 .149 .159 .171 .185 .168 .155 .135 .f47 .115 .t36 .160 2.721 2.05 .362 .260 .276 3.05 .381 .479 .551 .477 .369 .287 .311 .278 .323 .317 .272 .302 .321 .317 .302 .311 5.599

.508 .647 .785 .547 .494 .428 .437 .404 .453 .455 428 .400 .387 .482 .487 .455 7.798 >

4.05 542 5.05 .489 .598 .792 .515 .451 .403 .420 .505 .477 .489 .492 .472 .493 .540 .533 8.213

.599 .861 .596 .506 .419 .479 483 .556 .584 .523 .'487 .556 .598 .668 .656 9.150 8.05 .577 1.622 1.623 '

8.05 1.297 .918 1.353 1.289 1:207 .972 .969 1.062 1.415 1.500 1.371 1.164 1.207 1.669 20.637

.487 .845 .998 .751 .736 .947 1.385 1.552 1.325 1.088 1.240 1.671 1.557 1.270 17.188 10.05 .912 .421 18.286 13.05 .482 .210 .183 .594 .858 .692 .749 1.187 2.107 2.440 1.822 1.338 1.432 1.962 f.428 .800

.120 .055 .026 .231 .326 .240 .283 .459 1.476 1.815 1.043 .581 .746 1.137 .404 .222 9.163 18.00 .708

.011 .01t .013 .035 .072 .109 .038 .085 .137 .147 .019 .015 99.00 .002 .000 .000, .011 Total 4.ses 4.237 s.ast s.sse s.as4 4.38s 4.e01 s.se7 8.474 s.4s7 7.487 s.Oes 8.888 8.Sts 7.248 e.073 tOO.OOO NOTE: Wind directions in tables are presented in " wind from" and not " wind to" direction.

ROJ/odemAasaae/tr17f E6P 4-40 e..

Rzvision b .

Sept 3mber 1995 Supplemental Table A -Continued t

Elevated Level Joint Frequency Distribution Table Summary j 375 Foot Elevation Data Summary Table of Percent by Speed apnd Ctese  !

F G i Class A B C D '

E i

Speed

.45 .000 .000 .000 .052 .058 .023 .004 1.05 .001 .004 .004 .176 .153 .060 .005 2.05 .017 .041 .109 1.540 .656 .307 .050 3.05 .046 .159 .290 3.269 1.193 .547 .096 4.05 .102 .249 .499 4.364 1.629 .788 .166 5.05 .102 .335 .547 4.159 1.945 .916 .210 6.05 .106 .341 .565 4.563 2.320 .986 .288 -

S.05 .225 .701 1.1to 10.191 5.190 2.460 .755 10.05 .141 .429 ,.785 7.441. 4'.924 2.591 .878 13.05 .134 .404 . 598 6.977 5.670 3.208 1*.296 18.00 .068 .163 '.256 3.424 3.126 1.511 .815

• 99.00 .001 .017 .036 .396 .198 .043 .018 5

i EPSPROJ/odem/lasa!Ie/fr1-7f p.4j ,

I i

Revision 1.7 Septemb r 1995

.. Supplemental Table B Mid Elevation Joint Frequency Distribution Table Summaries Sumunary Table or Percent by Direction and Class Claes N NNE HE ENE E ESE SE SSE S SSW SW WSW W WNW ,

NW NNW Total A .381 .248 .801 .790 .531 .256 .142 .119 .231 .357 .441 .370 .453 *. 653 .579 .678 7.030' 8 .313 .249 .377 .343 .290 .175 .110 .104 .207 .288 .327 .292 .350 .496 .530 .612 5.062 C .531 .420 .566 .434 .390 .299 .321 .282 .370 .498 .479 .470 .506 .573 .710 .785 7.634 D 2.274 2.315 2.517 2.248 2.669 9.715 1.677 1.775 2.781 3.045 2.096 1.839 2.140 3.069 2.848 2.408 37.410 ,

E .777 .734 1.088 1.105 1.486 1.323 1.243 1.436 2.678 2.910 1.697 1.176 1.226 f.712 1.429 1.015 23.034 '

F .233 .t55 .177 .205 433 .809 .802 .801 1.210 1.383 1.183 .862 .854 t.017 .848 .446 18.419 i

.776 G .065 .060 .021 .093 .059 .265 .635 .896 f.244 1.239 .997 .689 .740 .562 .150 8.411 Total 4.575 4.182 5.547. 5.138 5.857 4.841 4.930 5.413 8.722 9.721 7.219 5.898 S.268 8.297 7.498 6.094 100.000 Susseary Table of Percent by Direction and Speed .

Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total

.45 .043 .003 .000 .020 .015 .003 .005 .009 .005 .000 .008 .000 .000- .000 .000 .000 .113 f.05 .046 .072 .063 .042 .033 .025 .040 .034 .037 .021 .026 .038 .031 .026 .034 .046 .612 2.05 .219 .57S .500 .323 .233 .197 .202 .201 .232 .193 .20f .189 .183 .t51 .153 .163 3.915 3.05 .442 1.132 1.140 .691 .497 .350 .399 .363 .366 .344 .339 .353 .413 .374 .366 .374 7.946 4.05 .536 .970 1.375 .729 .617 .328 .545 .532 .599 .583 .557 .486 .481 .553 .630 .618 10.319 8.05 .681 .584 f.041 .800 .639 .553 .635 .558 .621 .610 .579 .560 .590 .686 .737 .720 10.593 6.05 .729 .383 .670 .802 .777 .728 .708 .681 .843 .887 .696 .687 .695 .815

• 910

. .916 11.959 8.05 1.088 .339 .576 1.004 1.557 1.351 1.333 1.426 2.234 2.473 1.925 1.484 1.604 1.933 1.903 1.559 23.790 10.05 .472 .306 .153 .475 .801 .691 .690 1.015 2.122 2.439 f.707 1.106 f.106 1.586 1.315 .910 16.693 13.05 .202 .016 .029 .214 .509 .348 .296 .476 1.342 1.778 1.012 .626 .790 t.414 1.096 .580 10.728 18.00 .111 .001 .001 .034 .177 .067 .076 .113 .310 .383 .154 .159 .300 .683 .312 .203 3.086 99.00 .007 .000 .000 .004 .001 .000 .000 .005 .010 .009 .014 .030 .074 .074 .013 .004 .247 Total 4.575 4.182 s.s47 s.138 5.8s7 4.84 4.930 s.4 3 8.722 9.721 7.219 5.s98 s.2s8 8.297 7.498 6.094 100.000 NOTE: Wind directions in tables are presented in " wind from" and not " wind to" direction.

l l

EPSPROJ/odemAasalle/tri-71 F-42 O 6 O O. .

Revision Sept 3mber 1995

. Supplemental Table B - Continued Mid Elevation Joint Frequency Distribution Table Summaries r

200 Foot Elevation Data suomacy, Table of Percent by speed and class t

Class- A B C D E F -G Speed - .

.45 .000 .000 .001 .046 .037 .021 .000 1.05 .013 .004 .022 .219 .175 .118 .083 2.05 .172 .130 .291 f.946 .732 .437 .207 s 3.05 .600 .453 .309 3.533 1.531 .642 .378 4.C5 .776 .588 .970 4.134 2.329 .930 .591 5.05 .828 .588 .966 3.915 2.455 1.150 .690 8.05 .835 .533 .921 4.389 2.742 1.461 1.079 '

3.05 1.542 1.208 1.871 8.019 5.377 3.357 2.618 10.05 1.030 .780 .979 5.271 4.'154 2.319 2.160 13.05 .374 .558 .754 4.ISS 2.854 .935 .597 18.00 .331 .207 1231 1.821 .630 .048 .020 99.00 .029 .012 1018 182 .02C .005 .001 4

i f

EPSPROJ4demMasalle/frt-7f F-43

Rt. vision 1.7 S::pt3mber 1995 Supplemental Table C Ground Level Joint Frequency Distribution Table Summary 33 Foot Elevation Data Summary Table of Percent by Otraction and Class N NNE NE' ENE E ESE SE SSE S SSW - SW WSW W WNW NW NNW Total Class A .411 .318 .688 .887 .594 .308 .133 .135 .212 .407 .478 .447 .532

• 6tI5

. .844 .904 7.962 8 .314 .150 .278 .310 .276 .l77 .108 .071 .172 .239 .268 .222 .293 405 .505 .501 4.288 C .380 .233 .330 .328 .262 .270 .189 .172 .285 , .385 .424 .343 .380 .507 .638 .501 5.626 2.687 1.735 1.577 1.540 2.195 2.673 2.178 1.925 2.243 3.240 3.269 2.509 37.051 0 3.149 1.449 2.178 2.504 E 1.131 .661 1.168 1.021 1.758 1.434 1.303 1.561 2.556 '2.795 1.968 t.480 1.557 1.945 1.692 .917 24.947

.160 .646 .840 .750 .817 1.259 1.200 1.376 1.039 1.048 .867 .609 .378 11.499 F .f66 .087 .177

.025 .127 .615 .873 1.023 1.183 1.050 .998 .966 .925 .490 .214 .093 8.827 0 .019 .008 .017 Total 5.570 2.906 4'836 5.235 6.349 5.379 4.932 5.319 7.862 8.829 7.690 6.422 6.979 8.118 7.771 5.803 100.000 I

i Summary Table of Percent by Direction and Speed ENE- ESE SE SSE 5 SSW Stf WSW W WNW NW NNW Total Speed N NNE NE E

.002 .002 .002 .004 .002 .000 .002 .002 .029

.45 .000 .004 .000 .002 .002 .000 .000 .006

.046 .056 .056 .052 .073 .081 .075 .079 .067 .102 .093 .066 .066 1.085 1.05 .052 .048 .073 8.731 2.05 .378 .609 .813, .517 .424 .601 .686 .582 .532 .441 .457 .466 .613 .626 .497 .488 1.268 1.191 1.270 1.276 1.222 1.149 1.156 1.112 1.031 1.035 1.079 .931 1.043 18.932 3.05 1.124 1.183 f.802 19.813 4.05 1.326 .621 1.122 1.230 1.420 1.116 1.058 1.079 1.731 1.719 1.648 1.550 1.274 1.023 1.000 .896 1.106 1.189 .694 .642 .738 1.276 1.509 1.305 1.129 1.029 1.104 1.014 .777 15.505 5.05 1.129 .247 .617

.894 .914 .813 12.163 S.05 .667 .091 .297 .597 .879 .551 .509 .586 1.047 1.434 1.112 .808 .966

.102 .506 .422 .817 .767 .480' .642 1.282 1.636 f.291 .827 1.072 1.478 1.644 1.014 14.189 8.05 .628 6.036 10.05 .145 .002 .006 .042 .303 .227 .172 .289 .561 .588 .532 .358 .400 .942 .933 .457 13.05 .114 .000 .000 .002 .057 .093 .056 .094 .202 .256 .119 .121 .254 ,634 .563 .220 2.797

.002 .000 .004 .002 .012 .015 .012 .031 .046. .145 .212 .154 .029 .478 18.00 .008 .000 .000,

.019 .012 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .002 .013 .002 .000 .048 Total 5.570 2.90s 4.83e'8.235 e.349 5.379 4.932 5.3t9 7.8s2 a.829 7.e90 s.422 s.979 8.118 7.77 5.803 tOO.OOO NOTE: Wind directions in tables are presented in " wind from" and not " wind to" direction.

E5ROJ4demMasalle/fri-7f b.44 O. ~ . , -

__._m _ _ . . _ . _ . - _ . . . _ _ . _ _ . - . . _ . . . _ . . . _ _ _ _ . _ . . . . _ _ _ _ _ . _ _ _ _ _ . _ _ . . . _ _ . . _ . _ . . _ . _

. . r i

Rsvision i Septamber 199'5 i

f

• Supplemental Table C - Continued l

Grourid Level Joint Frequency Distribution Table Summary 33 Foot Elevation Data s

Summary Table of Percent by Speed and Clase Class A a C D E F G Speed

.45 .000 .000 .004 .002 .008 .010 .000 1.05 .021 .008 .012 .197 .355 .299 .195 2.05 .326 .202 .272 2.282 2.334 1.764 1.552 '

3.05 .998 .578 .798 5.133 5.350 3.267 2.008 4.05 1.247 .606 .862 6.435 4.793 3.064 2.725 5.05 1.203 .646 .852 6.115 3.880 1.773 1.037 6.05 1.201 .570 .804 5.472 3.049 .817 .251 S.05 1.629 .900 1.208 6.605 3.334 .463 .050 10.05 .775 .422 .518 2.955 1.334 .031 .002 13.05 .428 .212 e245 1.469 .~4 38 .004 .002 15.00 .I12 .052 4052 .382 .089 .004 .000 99.00 .023 .012 .000 .006 .004 .004 .000 EPSPROJ/bdem/lasapelfrt-7f F-45

Revision 1.7 i linsic' River --

September 1995 O

Effluent Discharge Point 7

i OFFSITE DOSE CALCULATION MANUAL LASALLE COUNTY STATION

1 FIGURE F-1 UNRESTRICTED AREA BOUNDARY a

\ * % & tlEs k 8 L e*lT \

1 Mile Scale in Feet N UNRESTRICTED AREA BOUNDARY (Property Line)

" ~

\

. l Waste Stabilization  ;

Pond I 1

= / l

, I e l 1 Exclusion LaSalle' Lake i Area " (

Meteorological Tower ('

)J i

t Gaseous Effluent Release Point -l, ,

, I I m_____;

EPSPROJ/oderMasale/Irt 7f F-46 l

2 i

. . Revision 1.7

'[

V,(/ f[A / ,, Stptember 1995 j

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A Interim Radwaste Storage Facility e

- Restricted Area Boundary

-5 Radwaste Storage Area (When Operational, this

}-} ~

area may include 48-packs, DAW, and other types e storage) 0FFSITE DOSE CALCULA110N MANUAL ieee . teme 2eee ren LA SALLE COUNTY STATION O M- FIGURE F-2

. onnewit sente RESTRICTED AREA BOUNDARY EPSPROJedemAasale/tri-7f p.47