ML032320216

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Radioactive Effluent Release Report
ML032320216
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 05/01/2003
From: Landahl S
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML032320216 (211)
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Text

Exel nm Exelon Generation Company, LLC www.exeloncorp.com Nuclear LaSalle County Station 2601 North 21" Road Marseilles, IL61341-9757 May 1, 2003 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-1 and NPF-18 NRC Docket Nos. 50-373 and 50-374

Subject:

2002 Radioactive Effluent Release Report Enclosed is the Exelon Generation Company, (EGC), LLC, LaSalle County Station 2002 Annual Radioactive Effluent Release Report. This report is submitted in accordance with Technical Specification 5.6.3, "Radioactive Effluent Release Report."

Should you have any questions concerning this letter, please contact Mr. Glen T. Kaegi, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, Susan Landahl Plant Manager LaSalle County Station Attachment cc: Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - LaSalle County Station

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

Supplemental Information Regulatory Limits

a. Gaseous Effluents I) The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site shall be limited to the following:

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 beta radiation.

2) The dose to an individual from radioiodines and radioactive materials in particulate form, and radionuclides, other than noble gases, with half-lives greater than eight days in gaseous effluents released, from each reactor unit, from the site shall be limited to the following:

3) 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.

b. Liquid Effluents
1) The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from eaci reactor unit, from the site shall be limited:

a) During any calendar quarter: 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: Less than or equal to 3 mRem to the total body and to less than or equal to 10 mRem to any organ.

c. Total Dose -
1) The dose or dose commitment to any member of the public, due to releases or radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mRem to the body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mRem) over 12 consecutive months.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

Supplemental Information (continued)

2. Allowable Concentrations -
a. Gaseous Effluents I) The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to the following:

a) For noble gases: Less than or equal to 500 mRem/year to the total body and less than or equal to 3000 mRem/year to the skin, and b) For all radioiodines and for all radioactive materials in particulate form, and radionuclides, other than noble gases, with half-lives greater than eight days: Less than or equal to 1500 mRem/year to any organ via the inhalation pathway.

b. Liquid Effluents
1) The concentration of radioactive material released from the site shall be limited to ten (10) times the concentrations specified in 10 CFR Part 20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to the following:

Nuclide DWC (uci/mi)

Kr-85m 2.00E-04 Kr-85 5.OOE-04 Kr-87 4.00E-05 Kr-88 9.OOE-05 Ar-4I 7.00E-05 Xe-131m 7.00E-04 Xe-133m 5.00E-04 Xe-133 6.00E-04 Xe-135m 2.00E-04 Xe-135 2.OOE-04

3. Average Energy Not applicable - average energy is no longer used to determine dose to the public.
4. Measurements and Approximations of Total Radioactivity
a. Gaseous Effluents I) Containment Vent and Purge System is sampled by grab sample which is analyzed for principal gamma emitters and H-3.
2) Main Vent Stack is sampled by grab sample, which is analyzed for principal gamma emitters and H-3.
3) Standby Gas Treatment System is sampled by grab sample, which is analyzed for principal gamma emitters.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

Supplemental Information (continued)

4) All release types as listed in 1 and 2 above, at the vent stack and as listed in 3 above, at the Standby Gas Treatment System whenever there is flow, are continuously sampled by charcoal cartridge and particulate filter paper, which are analyzed for iodines and principal gamma emitters. Particulate filter papers are composited and analyzed for gross alpha, Sr-89 and Sr-90. Noble gases, gross beta and gamma are continuously monitored by noble gas monitors for the vent stack and the standby gas treatment system.
b. Liquid Effluents
1) Batch waste release tanks are sampled each batch for principal gamma emitters, 1-131, dissolved and entrained noble gases, H-3, gross alpha, Sr-89, Sr-90 and Fe-55.
2) Continuous releases are sampled continuously in proportion to the rate of flow of the effluent stream and by grab sample. Samples are analyzed for principal gamma emitters, 1-131, dissolved and entrained noble gases, H-3, gross alpha, Sr-89, Sr-90 and Fe-55.
5. Batch Releases
a. Gaseous
1) Number of batch releases: None
2) Total time period for batch releases: N/A
3) Maximum time period for a batch release: N/A
4) Average time period for batch releases: N/A
5) Minimum time period for a batch release: N/A
b. Liquid
1) Number of batch releases: None
2) Total time period for batch releases: Min. N/A
3) Maximum time period for a batch release: Min. N/A
4) Average time period for batch releases: Min. N/A
5) Minimum time period for a batch release: Min. N/A
6) Average stream flow during periods of release of effluent into a flowing stream: gpm N/A

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

Supplemental Information (continued)

6. Abnormal Releases
a. Gaseous
1) Number of releases: None
2) Total activity released: N/A
b. Liquid I) Number of releases: None
2) Total activity released: N/A
7. Process Control Program There were no changes to the Process Control Program during this time period.
8. Effluent Monitoring Instrumentation timeclocks and sample anomalies.

There were no effluent monitoring instrumentation timeclocks exceeded durinti this time period.

During the reporting period, the Illinois Department of Nuclear Safety Effluent Monitoring Instrumentation was replaced. This activity involved the opening of a Station Vent Stack access hatch. which created a mixed mode release pathway. Dose calculations were performed for the pathway associated with this activity. The dose information for this pathway is included in the Annual Dose Report. Release activity information is included as the "Gaseous Effluent - Mixed Mode" summary under continuous releases.

During the reporting period, there was one case of loss of power and one case of inadequate flow to the Cooling Pond Blowdown Compositor. This compositor samples the Plant's ultimate outfall for liquid release. Composite samples are collected three times a week, with a weekly composite analyzed for gamma isotopic. There were no radioactive liquid releases conducted during the reporting period. Compensatory sampling was initiated for the low flow condition. For the case of loss of power, the compositor was shutdown for a period of two days without compensatory sampling. A review of historical isotopic and trending of future data ensured representative sampling for the composite samples that were obtained. A review of REMP data also ensured no resultant impact to offsite dose as measured in the environment. The loss of power was associated with a planned maintenance activity. The low flow condition was found to be due to a leak in the sample pump tubing. Both cases were identified and incorporated into the Corrective Actions Program.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

Supplemental Information (continued)

9. Offsite Dose Calculation Manual Revisions.

An entire copy of the ODCM LaSalle Annex is submitted in accordance with Technical Specification 5.5.1 (refer to Appendix A). Following are change summaries for Rev. 4 and Rev. 5.

Rev 4 changes

1. Section 10.1.3.1.2 is in error as it states the following: "The high trip setpoint is established at 1.5 times the nominal nitrogen-16 (N-16) background dose rate to help ensure that effluents are maintained ALARA."

It has been corrected to read as follows: "The high trip setpoint is established at 1.5 times the normal full power background rate, including nitrogen-] 6 (N-16) to help ensure that effluents are maintained ALARA."

2. Reference change in ODCM section 10.1.3.1.2 from TS 3.11.2.2 to 3.7.6.

Rev 5 changes

1. Figure 10-1 entitled "Simplified Gaseous Radwaste Gaseous Effluent Flow Diagram" has been revised to remove the Turbine Building Sandblast Room from the flow path.
2. Table 11-1 and Table 12.5-1 have been revised to require an 1-131 analysis for Food Products, which are sampled as part of the Radiological Environmental Monitoring Program.
3. Table 12.5-1 has been revised to require an 1-131 analysis on each composite when the dose calculated for the consumption of water is greater than I mrem per year.
4. The evaporators, which at one time were used to process waste, have been abandoned in place per EC #331686 and safety screening LO]-0427. ODCM Section 10.2.1, Figure 10-2, Figure 10-4, and Bases 12.3.3.C have been revised to remove the reference to the evaporators.
5. Table 11-1, Figure 11 -3, and Table 12.5-1 has been revised to add a fish monitoring location for the LaSalle Lake.

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

UNITS ONE AND TWO DOCKET NUMBERS 50-373 AND 50-374 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated I Units I Ist Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total Error %

A. Fission and Activation Gas Releases

1. Total Release Activity Ci 1.31E+03 5.96E+03 2.25E+03 3.77E+03 3.50E+01
2. AverageReleaseRate uCi/sec 18E+02 7.7E+02 2.83E+02 4.74E+02
2. percent of Technical Specification %s X I2 1 Limit _ _ _ _ _

B. Iodine Releases

1. Total 1-131 Activity Ci 2.95E-02 4A2E-02 7.92E-02 1.63E-01 3.50E+01
2. Average Release Rate
3. Percent of Technical Specification Limit uCi/sec 3.80E-03 j 5.63E-03
  • I 9.96E-03 2.05E-02 C. Particulate (> 8 day half-life) Releases
1. Gross Activity Ci 6.69E-04 2.78E-03 l 1.53E-02 9.36E-03 3.30E+0
2. Average Release Rate uCi/sec 8.60E-05 3.54E-04 1.92E-03 1.18E-03
3. Percent of Technical Specification  %* * *
  • Limit
13. Gross Alpha Activity Ci <1.0OE-II <1.00E-Il - 2.71E-05 -1.87E-05 D. Tritium Releases
1. Total Release Activity Ci 3.84E+O1 1.64E+01 2.55E+01 3.60E+01 2.1E+OI
2. Average Release Rate uCi/sec 4.93E+00 1.96E+00 3.21 E+00 4.41 E+O0
3. Percent of Technical Specification  % * * *
  • Limit I _ _ I I I I

"*" This information is contained in the Radiological Impact on Man section of the report.

"<" Indicates activity of sample is less than LLD given in uCi/ml

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

GASEOUS EFFLUENTS-ELEVATED RELEASE Unit I and Unit 2 Continuous Mode I Units I Ist Qtr I 2nd Qtr I 3'd Qtr I 4th Qtr l

1. Fission and Activation Gas Releases Ar-41 Ci 1.01E-03 3.40E+00 6.78E-04 2.38E-02 Kr-85 Ci <1.00-6 <1.00e-6 <1.OOe-6 <1.000-6 Kr-85m Ci 3.19E+02 6.54E+02 5.39E+02 5.90E+02 Kr-87 Ci 5.08E+01 1.15E+02 9.24E+01 8.65E+01 Kr-88 Ci 4.40E+02 9.94E+02 7.76E+02 7.33E+02 Xe-1 31 m Ci <1.00-6 <1.00.-6 <1.00.-6 <1.00e-6 Xe-133 Ci 4.96E+02 3.00E+03 6.72E+02 1.30E+03 Xe-133m Ci <1.00e-6 7.80E+01 3.49E-04 2.OOE-03 Xe-135 Ci 2.01E-03 1.01 E+03 2.35E+01 7.78E+02 Xe-135m Ci <1.00e-6 1.04E+02 2.68E+01 2.84E+02 Xe-138 Ci <1.00-6 <1.00e-6 1.19E+02 4.53E+01 TOTAL Ci 1.31 E+03 5.96E+03 2.25E+03 3.82E+03
2. Iodine Releases 1-131 Ci 2.95E-02 4.42E-02 7.92E-02 1.63E-01 1-132 Ci 7.77E-03 2.11 E-02 5.68E-02 1.28E-01 1-133 Ci 3.09E-02 4.83E-02 1.25E-01 2.94E-01 1-134 Ci <1.00-1I <1.00e-Il <1.OOe-11 <1.00e-11 1-135 Ci 1.97E-02 3.95E-02 9.94E-02 2.51 E-01 TOTAL IODINE Ci 8.79E-02 1.53E-01 3.60E-01 8.36E-01 ITOTAL 1-131,1-133,1-135 Ci 8.01 E-02 1.32E-01 3.04E-01 7.08E-01
3. Particulate ( > 8 day half-life) Releases Cr-5I Ci <1.00.-11 <1.00e-Il <1.00e-1 <1.00e-11 Mn-54 Ci 2.32E-05 1.54E-05 2.40E-05 1.69E-04 Co-57 Ci <1.009-11 <1.00e-Il <1.00e-Il <1.00e-1i Fe-55 Ci <1.00e-11 <1.000-11 <1.00e-I1 <1.00e-1l Co-58 Ci <1.OOe-11 <1.00-11 <1.00e-11 <1.00o-11 Fe-59 Ci <1.00e-1 1 <1.000-1 1 <1.00e-11 <1.00e-11 Co-60 Ci 4.46E-04 1.62E-04 1.74E-04 6.19E-04 Zn-65 Ci <1.00e-11 <1.00e-11 <1.00e-1 1 <1.00e-11 Sr-89 Ci 1.95E-04 7.57E-04 3.27E-03 3.13E-03 Sr-90 Ci 4.05E-07 1.37E-06 3.70E-06 <1.00e-1I Zr-95 Ci <1.00e-Il <1.00e-11 <1.00e-11 <1.00e-11 Mo-99 Ci <1.00e-1I <1.000-1 <1.00e-11 <1.00e-11 Ru-1 03 Ci <1.00e-11 <1.000-11 <1.00e-11 <1.00e-11 Sn-I 17m Ci <1.00e-11 <1.OOe-1 1 <1.00e-11 <1.00e1I Cs-134 Ci 4.62E-06 <1.00e-11 5.33E-04 1.20E-04 Cs-137 Ci <1.000-11 <1.00e-Il 4.24E-04 1.08E-04 Ba\La-140 Ci <1.00e-11 9.99E-04 5.72E-03 3.89E-03 Ce-141 Ci <1.OOe-11 8.49E-04 5.13E-03 1.32E-03 Ce-144 Ci <1.00-1I1 <1.00.-I1 <1.00e-11 <1.00e-II TOTAL PARTICULATES Ci 6.69E-04 2.78E-03 1.53E-02 9.36E-03
4. Tritium Releases
1. Total Release Activity Ci 3.84E+01 1.54E+01 2.55E+01 I 3.50E+01

"<" Indicates activity of sample is less than LLD given in uCi/ml

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

GASEOUS EFFLUENTS-MIXED MODE RELEASE Unit I and Unit 2 Continuous Mode Units l1Ist Qtr l 2nd Qtr 3d Qtr 4

1. Fission mnd Activation Gas Releases Ar4 Ci c1.OOe-6 <1.OOe-6 <1.OOe-6 <1.OOe-6 Kr-85 Ci <1.OOe-6 <1.OOe-6 <1.OOe-6 <1.OOe-6 Kr-85m Ci <1.00e-6 <1.00e-6 <1.00e-6 1.38E-01 Kr-87 Ci <1.OOe-6 <1.OOe-6 <1.OOe-6 2.37E-02 Kr-88 Ci <1.OOe-6 <1.00e46 <1.OOe-6 1.58E-01 Xe-131 m Ci <1.OOe-6 <1.OOe-6 <1.OOe-6 <1.OOe-6 Xc-133 Ci <1.OOe-6 <1.OOe-6 <1.OOe-6 1.50E-01 Xe-133m Ci <1.0e-6 <1.00e-6 'c1.0e-6 1.00e.6 Xe-135 Ci <1.00e-6 <1.OOe-6 <1.O0e-6 7.70E-05 Xe-135m Ci <1.00e4 <1.00e-6 <1.OOe-6 4.08E-02 Xe-138 Ci <1.00e-6 1.OOe-6 1.OOe-6 1.D.OOe-6 TOTAL Ci <1.OOe-6 <1.OOe-6 <1.O0e-6 5.1II E-O1
2. Iodine Releases 1-131 Ci <1.00e-12 <1.ODe-12 <1.OOe-12 2.36E-05 1-132 Ci <1.OOe-ttI 1.00e-11 1.OOe-1 _2.69E-05 1-133 Ci 1.OO0e-10 <1.O0e-1 <1.O0e-10 4.68E-05 1-134 Ci <1.0Oe-11 1.0Oe-11 <1.OOe-11 <1.OOe-11 1-135 Ci <1 .OOe-1 I <1.OOe-1 1 <1.OOe-1 I 5.07E-05 TOTAL IODINE Ci <1.00e-11 1.00e-11 1.00e-11 _1.48E-04 lTOTAL 1-131,1-133,1-135 Ci <1.00e-1t <1.00e-11 <1.00e-11 1.21E-04
3. Particulate (> 8 day half-life) Releases Cr-51 Ci <1.00e-1i <1.00e-11 <1.00e-11 <1.00e-11 Mn-54 Ci <1.OOe-1I <1.00e-11 <1.00e-11 2.93E-07 Co-57 Ci <1.00e-11 <1.00e-11 <1.00e-11 <1.00e-11 Fe-55 Ci <1.OOe-11 c1.0Oe-II <1.00e-I1 <1.00e-11 Co-58 Ci <1.OOe-11 <1.00e-11 c1.00e-11 <1.00e-II Fe-59 Ci <1.OOe-1t <1.Oe-11 <1.OOe-I1 <1.OOe-II Co-60 Ci <1.00e-II <1.00e-11 I.OOe-11 2.93E-07 Zn-65 Ci c1.0De-11 1.OOe-11 <1.00e-11 <1.00e-11 Sr-89 Ci <1.O0e-1I1 <1.OOe-11 <1.COe-I1 3.77E-06 Sr-90 Ci <1.OOe-1I I.00e-1I C1.00e-11 2.26E-08 Zr-95 Ci <1.OOe-II <1.OOe-I1 <1.OOe-11 <1.OOe-11 Mo-99 Ci <1.OOe-1I C1.00e-I <1.00e-1I <1.00e-11 Ru-103 Ci <1.OOe-1 <1.00e-11 <1.00e-11 c1.00e-11 Sn-I 17m Ci <1.OOe-11 <1.O0e-11 <1.OOe-11 <1.OOe-11 Cs-134 Ci <1.OOe-1I <1.OOe-11 <1.00e-11 <1.OOe-1i Cs-137 Ci <1.OOe-1t <1.Oe-11 I<1.OOe-11 <1.OOe-11 Ba\La-140 Ci <1.OOe-11 <1.OOe-11 <1.OOe-11 9.12E-09 Ce-141 Ci <1.OOe-11 <1.00e-11 c1.00e-1I 1.73E-07 Ce-144 Ci <1.00e-11 <1.00e-11 1.C0e-11 <1.DOe-11 TOTAL PARTICULATES Ci CI.O0e-11 <1.O0e-11 I.C0e-11 4.56E-06
4. Tritium Releases 1.Total Release Activity Ci <1.00e-6 <1.00e-6 <1.00e-6 1.28E-02

"<" Indicates activity of sample is less than LLD given in uCi/ml

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

LIQUID RELEASES UNIT I and UNIT 2 SUMMATION OF ALL LIQUID RELEASES Estimated I Units I I st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total Error %

A. Fission and Activation Products

1. Total Activity Released Ci <LLD <LLD L <LLD N/A
2. Average Concentration Released uCi/mi <LLD <LLD <LLD <LLD
3. Percent of Applicable Limit [

B. Tritium

1. Total Activity Released Ci j__<LLD <L LD <LLD
2. Average Concentration Released uCi/ml <LLD <LLD <LLD <LLD
3. Percent of Applicable Limit  %

C. Dissolved Noble Gases

1. Total Activity Released Ci <LLD <LLD <LLD <LLD l N/A
2. Average Concentration Released uCi/ml <LLD <LLD <LLD <LLD
3. Percent of Applicable Limit  %

D. Gross Alpha I. Total Activity Released (estimate) l Ci <LLD <LLD <LLD <LLD N/A

2. Average Concentration Released uCi/ml <LLD <LLD <LLD <LLD
3. Percent of Applicable Limit l** ]

lE. Volume of Liquid Waste to Discharge liters l0.OOE+00 O.OOE+0l 0.OOE+00 O.OOE+00 N/A IF. Volume of Dilution Water liters O.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 N/A

"*" This information is contained in the Radiological Impact on Man section of the report.

"<" Indicates activity of sample is less than LLD given in uCi/ml

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

LIQUID RELEASES UNIT I and UNIT 2 BATCH MODE lNuclides From Batch Releases I Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr H-3 Ci ___

Cr-5 I Ci Mn-54 Ci Fe-55 Ci Co-58 Ci == = =

Fe-59 Ci Co-60 Ci Zn-65 Ci Sr-89 Ci Sr-90 Ci _ _ _ _

Nb-95 Ci Zr-95 Ci Mo-99 Ci Tc-99m Ci

_Ag 1___m Ci Sb-122 ~~~~~~~Ci Sb-124 Ci 1-131 Ci Cs-134 Ci Cs- 137 Ci Ba\La-140 Ci Ce-141I Ci ________

Ce-144 Ci W-187 Ci TOTAL Ci None None None None Xe-131m Ci Xe-133 Ci Xe-133m Ci Xe-135 Ci Xe-135m Ci TOTAL Ci None None None None

"<" Indicates activity of sample is less than LLD given in uCi/ml

LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

LIQUID RELEASES UNIT I and UNIT 2 CONTINUOUS MODE lNuclides From Continuous Releases I Units Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Gross Alpha Ci <I1.OOE-07 <1.OOE-07 <1.OOE-07 <l.OOE-07 H-3 Ci <1.OOE-05 <1.OOE-05 <I .OOE-05 <I .OOE-05 Cr-51 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Mn-54 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Fe-55 Ci <1.OOE-06 <I.OOE-06 <I.OOE-06 <I.OOE-06 Co-58 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Fe-59 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Co-60 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Zn-65 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Sr-89 Ci <5.OOE-08 <5.OOE-08 <5.OOE-08 <5.OOE-08 Sr-90 Ci <5.OOE-08 <5.OOE-08 <5.OOE-08 <5.OOE-08 Nb-95 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Zr-95 Ci <5.OOE-07 <5.ooE-07 <5.OOE-07 <5.00E-07 Mo-99 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Tc-99m Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Ag- I11 Om Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Sb- 122 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Sb- 124 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 1-131 Ci <I.OOE-06 <I.OOE-06 <I.OOE-06 <I.OOE-06 Cs- 134 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Cs-137 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Ba\La- 140 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Ce- 141 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Ce- 144 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 W-187 Ci <5.OOE-07 <5.OOE-07 c5.00E-07 <500E-07 TOTAL Ci <LLD <LLD <LLD <LLD Xe-131m Ci <1.OOE-05 <.OOE-05 <1.OOE-05 <.OOE-05 Xe-133 Ci <l.OOE-05 <I.OOE-05 <.OOE-05 <OOE-05 Xe- 133m Ci <I.00E-05 <I.OOE-05 <l.OOE-05 <I.OOE-05 Xe- 135 Ci <1 .OOE-05 <1.OOE-05 <I .OOE-05 < .OOE-05 Xe- 135m Ci <I.OOE-05 <I.OOE-05 <I1.OOE-05 <I .OOE-05 TOTAL Ci <LLD <LLD <LLD <LLD I

"<" Indicates activity of sample is less than LLD given in uCi/ml

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FIRST QUARTER A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL I Spent resins, filter sludges, evaporator bottoms, etc.

a. Quantity shipped cu.m. 0.OOE+00
b. Total activity Ci 0.OOE+00
c. Major nuclides (estimate %) N/A
d. Shipment type N/A
e. Solidification agent None
2. Dry compressible waste, contaminated equipment, etc.
a. Quantity shipped cu.m. 4.40E+02
b. Total activity Ci 2.65E+01
c. Major nuclides (estimate %)

Mn-54 1.17E+0I Fe-55 1.37E+01 Co-60 4.52E+01 Ni-63 2.06E+01 Zn-65 7.13E+00

d. Shipment type LSA

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FIRST QUARTER

3. Other
a. Quantity shipped cu.m. O.OOE+00
b. Total activity Ci 0.00E+00
c. Major nuclides (estimate %) N/A
d. Shipment type N/A
4. Irradiated Components
a. Quantity shipped cu.m 0.00E+00
b. Total activity Ci 0.00E+00
c. Major nuclides (estimate %) N/A
d. Number of shipments 0
e. Mode of Transportation N/A
f. Destination N/A
5. Solid Waste Disposition Number of Shipments Transportation Mode Destination 7 Truck Duratek- Bear Creek, TN TOTAL THIS QUARTER 7 Estimated total error % for spent resins, filter sludges, evaporator bottoms, etc. (Jan-Dec) 2.50E+01 Estimated total error % for dry compressible waste, contaminated equipment, etc. (Jan-Dec) 2.50E+0I Estimated total error % for irradiated components (Jan-Dec) N/A B. IRRADIATED FUEL SHIPMENTS None

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND QUARTER A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL I. Spent resins, filter sludges, evaporator bottoms, etc.

a. Quantity shipped cu.m. 4.84E+00
b. Total activity Ci 6.79E+01
c. Major nuclides (estimate %/6)

Mn-54 5.52E+00 Fe-55 7.15E+01 Co-60 1.40E+0i Zn-65 3.45E+00

d. Shipment type LSA
e. Solidification agent None
2. Dry compressible waste, contaminated equipment, etc.
a. Quantity shipped cu.m. 3.26E+02
b. Total activity Ci 4.09E-0 I
c. Major nuclides (estimate %)

Mn-54 1.17E+01 Fe-55 1.37E+01 Co-60 4.52E+OI Ni-63 2.06E+0 I Zn-65 7.13E+00

d. Shipment type LSA

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND QUARTER

3. Other
a. Quantity shipped cu.m. 0.00E+00
b. Total activity Ci 0.00E+00
c. Major nuclides (estimate %) N/A
d. Shipment type N/A
4. Irradiated Components
a. Quantity shipped cu.m 0.00E+00
b. Total activity Ci O.OOE+00
c. Major nuclides (estimate %) N/A
d. Number of shipments N/A
e. Mode of Transportation N/A
f. Destination N 'A
5. Solid Waste Disposition Number of Shipments Transportation Mode Destination 6 Truck Duratek-Bear Creek, TN I Truck lnvirocare of Utah TOTAL THIS QUARTER 7 Estimated total error % for spent resins, filter sludges, evaporator bottoms. etc. (Jan-Dec) 2.50E+01 Estimated total error % for dry compressible waste, contaminated equipment. etc. (Jan-Dec) 2.50E+01 Estimated total error % for irradiated components (Jan-Dec) N/A B. IRRADIATED FUEL SHIPMENTS None

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS THIRD QUARTER A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. Spent resins, filter sludges, evaporator bottoms, etc.
a. Quantity shipped cu.m. 1.99E+01
b. Total activity Ci 1.02E+02
c. Major nuci ides (estimate %)

Mn-54 5.52E+00 Fe-55 7.15E+01 Co-60 1.40E+01 Zn-65 3.45E+00

d. Shipment type LSA
f. Solidification agent N/A
2. Dry compressible waste, contaminated equipment, etc.
a. Quantity shipped cu.m. 1.14E+02
b. Total activity Ci 2.22E+00
c. Major nuclides (estimate %)

Mn-54 1.17E+01 Fe-55 1.37E+01 Co-60 4.52E+0I Ni-63 2.06E+0I Zn-65 7.13 E+00

d. Shipment type LSA

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS THIRD QUARTER

3. Other
a. Quantity shipped cu.m. 0.OOE+00
b. Total activity Ci 0.OOE+00
c. Major nuclides (estimate %) N/A
d. Shipment type N/A
4. Irradiated Components
a. Number of shipments 0
b. Mode of Transportation N/A
c. Destination N/A
5. Solid Waste Disposition Number of Shipments Transportation Mode Destination 3 Truck Duratek-Bear Creek, TN 4 Truck Envirocare of Utah TOTAL THIS QUARTER 7 Estimated total error % for spent resins, filter sludges, evaporator bottoms, etc. (Jan-Dec) 2.50E+0I Estimated total error % for dry compressible waste, contaminated equipment, etc. (Jan-Dec) 2.50E+01 Estimated total error % for irradiated components (Jan-Dec) N/A B. IRRADIATED FUEL SHIPMENTS None

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOURTH QUARTER A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. Spent resins, filter sludges, evaporator bottoms, etc.
a. Quantity shipped cu.m. 4.08E+0 1
b. Total activity Ci 4.55E+00
c. Major nuclides (estimate %)

Mn-54 5.52E+00 Fe-55 7.15E+01 Co-60 1.40E+OI Zn-65 3.45E+00

d. Shipment type LSA
e. Solidification agent None
2. Dry compressible waste, contaminated equipment, etc.
a. Quantity shipped cu.m. I .09E02
b. Total activity Ci 2.12E-02
c. Major nuclides (estimate %)

Mn-54 1.17E+0I Fe-55 1.37E+01 Co-6 4.52E+O1 Ni-63 2.06E+0 I Zn-65 7.13E+00

d. Shipment type LSA

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOURTH QUARTER

3. Other (Oil for incineration)
a. Quantity shipped cu.m. 0.00E+00
b. Total activity Ci 0.OOE+00
c. Major nuclides (estimate %) N/A
d. Shipment type N/A
4. Irradiated Components
a. Number of shipments 0
b. Mode of Transportation N/A
c. Destination N/A
5. Solid Waste Disposition Number of Shipments Transportation Mode Destination 2 Truck Duratek-Bear Creek, TN 4 Truck Envirocare of Utah TOTAL THIS QUARTER 6 Estimated total error % for spent resins, filter sludges, evaporator bottoms, etc. (Jan-Dec) 2.50E+0 I Estimated total error % for dry compressible waste, contaminated equipment, etc. (Jan-Dec) 2.50E+01 Estimated total error % for other irradiated components (Jan-Dec) N/A B. IRRADIATED FUEL SHIPMENTS None

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

RADIOLOGICAL IMPACT ON MAN MAXIMUM DOSES RESULTING FROM RELEASES AND COMPLIANCE STATUS

08-06-2003 01:16pm From-Exelon LaSalle 81 535tl1262 T-701 P.002/013 F-057 LASALLE STATION UNIT ONE ACTUAL 2002 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/04/03 INFANT RECEPTOR 1ST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 2. 00E-02 4.99E-02 3 .78E-02 3. 91E-02 1.47E-01 (MRAD) (WSW ) (WSW ) (WSW ) (WSW ) (WSW )

BETA AIR 7.25E-04 2.77E-03 1.33E-03 1 92E-03 6.74E-03 (MRAD) (ESE ) (ESE ) (ESE ) (ESE ) (ESE )

TOT. BODY 1. 51E-02 3. 77E-02 2.86E-02 2.95E-02 1. 11E-01 (MREM) (WSW ) (WSW ) (WSW ) (WSW ) (WSW )

SKIN 1.59E-02 4. O1E-02 3.01E-02 3. 14E-02 1.18E-01 (MREM) (WSW ) (WSW ) (WSW ) (WSW ) (WSW )

ORGAN 3.89E-03 6. 19E-02 1. 94E-01 1.38E-01 3. 97E-01 (MREM) (ESE ) (ESE ) (ESE ) (ESE ) (ESE )

THYROID THYROID THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 10CFR 50 APP. I INFANT RECEPTOR

 % OF APP I. ------------

QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY OF OBJ JAN-MAR APR- JUN JUL-SEP OCT-DEC OBJ APP. I 3AMMA AIR (MRAD) 5.0 0.40 1.00 0.76 0.78 10.0 1.47 3ETA AIR (MRAD) 10.0 0.01 0 . 03 0 . 01 0.02 20.0 0 . 03 rOT. BODY (MREM) 2.5 0.61 1.51 1.14 1.18 5.0 2.22 SKIN (MREM) 7.5 0.21 0.53 0.40 0.42 15.0 0.78 DRGAN (MREM) 7.5 0.05 0.83 2.58 1. 84 15. 0 2. 65 THYROID THYROID THYROID THYROID THYROID RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

8153571262 T-101 P 003/013 F-057 08-06-2003 01:16pm From-Exelon LaSalle LASALLE STATION UNIT ONE ACTUAL 2002 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/04/03 CHILD RECEPTOR 1ST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 2.OOE-02 4.99E-02 3 . 78E-02 3.912-02 1.47E-01 (MRAD) (WSW ) (WSW ) (WSW ) (WSW ) (WSW )

BETA AIR 7.25E-04 2.77E-03 1.33E-03 1. 92E-03 6.74E-03 (MRAD) (ESE ) (ESE ) (ESE ) (ESE ) (ESE )

TOT. BODY 1.51E-02 3.77E-02 2.86E-02 2.95E-02 1.11E-01 (MREM) (WSW ) cWSW ) (WSW ) (WSW ) (WSW )

SKIN 1.59E-02 4.01E-02 3.01E-02 3 .14E-02 1. 18E-01 (MREM) (WSW ) (WSW ) (WSW ) (WSW ) (WSW )

ORGAN 3.25E-03 6.562-02 2.OOE-01 1.41E-01 4. 10E-01 (MREM) (NNE ) (ESE ) (ESE ) (ESE ) (ESE )

THYROID THYROID THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 10CFR 50 APP. I CHILD RECEPTOR

OF -APP I. -------

QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY OF OBJ JAN-MAR APR-JUN JUL - SEP OCT-DEC OBJ APP. I AAMMA AIR (MRAD) 5.0 0.40 1.00 0 . 76 0.78 10.0 1.47 BETA AIR (MRAD) 10.0 0.01 0 . 03 0.01 0 . 02 20.0 0.03 rOT. BODY (MREM) 2.5 0.61 1.51 1.14 1.18 5.0 2.22 SKIN (MREM) 7.5 0.21 0.53 0.40 0 . 42 15.0 0.78 DRGAN (MREM) 7.5 0.04 0.87 2. 67 1.87 15.0 2. 73 THYROID THYROID THYROID THYROID THYROID RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

08-06-2003 01:1 7Pm From-Exel on LaSallIe 8153571262 T-101 P.004/013 F-057 LASALLE STATION UNIT ONE ACTUAL 2002 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/04/03 TEENAGER RECEPTOR 1ST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 2 .OOE-02 4.99E-02 3.78E-02 3. 91E-02 1.47E-01 (MRAD) (WSW ) (WSW ) (WSW ) (WSW ) (WSW )

BETA AIR 7.2SE-04 2.77E-03 1.33E-03 1. 92E-03 6.74E-03 (MRAD) (ESE ) (ESE ) (ESE ) (ESE ) (ESE )

TOT. BODY 1.51E-02 3.77E-02 2.86E-02 2.95E-02 1. llE-01 (MREM) (WSW ) (WSW ) (WSW ) (WSW ) (WSW )

SKIN 1.592-02 4. 01E-02 3.01E-02 3. 14E-02 1.18E-01 (MREM) (WSW ) (WSW ) (WSW ) (WSW ) (WSW )

ORGAN 2.41E-03 4.OOE-02 1.22E-01 8. 54E-02 2.49E-01 (MREM) (NNE ) (NNE ) (NNE ) (NNE ) (NNE )

THYROID THYROID THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 10CFR 50 APP. I TEENAGER RECEPTOR

 % OF APP I. ---

QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I vAMMA AIR (MRAD) 5.0 0.40 1.00 0.76 0.78 10.0 1.47 BETA AIR (MRAD) 10. 0 0.01 0 . 03 0. 01 0.02 20.0 0.03 rOT. BODY (MREM) 2.5 0.61 1.51 1.14 1.18 5.0 2 .22 3KIN (MREM) 7.5 0.21 0. 53 0.40 0.42 15. 0 0.78

)RGAN (MREM) 7.5 0 . 03 0. 53 1.62 1.14 15.0 1.66 THYROID THYROID THYROID THYROID THYROID RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

08-06-2003 01:1l7pm From-Exelon LaSa le 81535TI262 T-T01 P.005/013 F-05T LASALLE STATION UNIT ONE ACTUAL 2002 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/04/03 ADULT RECEPTOR 1ST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 2. OOE-02 4 99E-02 3. 78E-02 3. 91E-02 1.47E-01 (MRAD) (WSW ) (WSW ) (WSW ) (WSW ) (WSW )

BETA AIR 7.25E-04 2.77E-03 1.33E-03 1. 92E-03 6.74E-03 (MRAD) (ESE ) (ESE ) (ESE ) (ESE ) (ESE )

TOT. BODY 1.51E-02 3.77E-02 2.86E-02 2 .95E-02 1.1lE-01 (MREM) (WSW ) (WSW ) (WSW ) (WSW ) (WSW )

SKIN 1. 59E-02 4. 0E-02 3 .01E-02 3 .14E-02 1. SE-01 (MREM) (WSW ) (WSW ) (WSW ) (WSW ) (WSW )

ORGAN 2.66E-03 4.13E-02 1.26E-01 8. 88E-02 2. 59E-01 (MREM) (NNE ) (NNE ) (NNE ) (NNE ) (NNE )

THYROID THYROID THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 10CFR 50 APP. I ADULT RECEPTOR

-- OF APP I -------

QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY  % OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I

,AMMA AIR (MRAD) 5.0 0.40 1.00 0.76 0 .78 10.0 1.47 BETA AIR (MRAD) 10.0 0.01 0. 03 0. 01 0. 02 20.0 0.03 TOT. BODY (MREM) 2.5 0. 61 1.51 1.14 1.18 5.0 2.22 SKIN (MREM) 7.5 0.21 0.53 0.40 0.42 15. 0 0.78 DRGAN (MREM) 7.5 0. 04 0.55 1.68 1.18 15.0 1.73 THYROID THYROID THYROID THYROID THYROID RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

DB-06-2003 1:llpm From-Exelon LaSalle 8153571262 T-701 P.006/013 F-057 LASALLE STATION UNIT ONE ACTUAL 2002 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/02/03 INFANT RECEPTOR 1ST 2ND 3 RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN- MAR APR-JUN JUL-SEP OCT-DEC TOTAL 0 . OOE+00 0 . OOE+00 0 . OOE+00 0 . OOE+00 0. OOE+00 BODY INTERNAL . OOE+00 0. OOE+00 0. OOE+00 O . OOE+00 0. OOE+00 ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 10 CR 50 APP. I

 % OF APP I. ------------

QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY  % OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I TOTAL BODY (MREM) 1.5 0 .00 0 . 00 0 .00 0 .00 3.0 0 . 00 CRIT. ORGAN(MREM) 5.0 0. 00 0 .00 0 . 00 0 .00 10. 0 0 . 00 RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

08-06-2003 01:17pm From-Exelon aSalle 1535T1262 T-T01 P.007/013 F-057 LASALLE STATION UNIT ONE 2002 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM

  • PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/02/03 INFANT RECEPTOR 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN - MAR APR-JUN JUL- SEP OCT-DEC TOTAL 0. OOE+00 C . OOE+00 0 . 00E+00 0 . OOE+00 o . OOE-00 BODY INTERNAL 0. OOE+00 0. 0E+00 0. 00E+00 0 . 0 E+00 0. OOE+00 ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT OF LIMIT TOTAL 4. 0 MREM 0. 000 BODY INTERNAL 4. 0 EM 0 . 000 ORGAN
  • THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.

RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 A. ... . . _ S , .

08-06-2003 01:l7pm From-Exelon LaSalle 3153571 Z62 T-701 P.008/013 F-057 LASALLE STATION UNIT ONE ACTUAL 2002 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/02/03 CHILD RECEPTOR 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUtAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 0. OOE+00 0. 00E+00 0. OE+00 0. 00E+00 0. OOE+00 BODY INTERNAL 0. 00E+00 0 . OOE+00 0. OOE+00 0. OOE+00 0 . OOE+00 ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 10 CR 50 APP. I

- OF APP I -------- __

QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY  % OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I TOTAL BODY (MREM) 1.5 0 .00 0.00 0 . 00 0 . 00 3. 0. 00 CRIT. ORGAN(MREM) 5.0 0 . 00 0 .00 0 . 00 0 .00 10. 0 0 . 00 RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

08-06-2003 01:17pm From-Exelon LaSalle 81 53571262 T-701 P 009/013 F-057 LASALLE STATION UNIT ONE 2002 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM

  • PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/02/03 CHILD RECEPTOR 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 0. OOE+00 0. 00E+00 0 . OOE+00 0. 00E+00 0 . OOE+00 BODY INTERNAL 0. OOE+00 0. 00E+00 0. OOE+00 0. 00E+00 0. OOE+00 ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT  % OF LIMIT TOTAL 4.0 MREM 0 .000 BODY INTERNAL 4.0 MREM 000 ORGAN
  • THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.

RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

08-06-2003 01 :17pm From-Exelon LaSal le 8153571262 T-70 I P.010/013 F-057 LASALLE STATION UNIT ONE ACTUAL 2002 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/02/03 TEENAGER RECEPTOR 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 0. OOE+00 0 . OOE+00 0. OOE+00 . OOE+00 0. OOE+00 BODY INTERNAL 0 . OOE+00 0 . OOE+00 0. OOE+00 0 . 00E+00 0. OOE+00 ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 10 CFR 50 APP. I

k OF APP I. ------------

QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY ' OF OBJ JAN-MAR APR-JUN JUL-SEP OCT -DEC OBJ APP. I TOTAL BODY (MREM) 1.5 0. 0 0 0 . 00 0 . 00 0 .00 3 .0 0. 0 0 CRIT. ORGAN(MREM) 5.0 0 . 00 0 .00 0 . 00 0 .00 10.0 0 .00 RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

08-06-2003 01 :17pm From-Exelon LaSal le 81 53571262 T-701 P.011/013 F-057 LASALLE STATION UNIT ONE 2002 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM

  • PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/02/03 TEENAGER RECEPTOR 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 0. 00E+00 0. OOE+00 0 . OOE+00 0. OOE+00 0 . OOE+00 BODY INTERNAL 0 . OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT k OF LIMIT TOTAL 4.0 MREM 0 .000 BODY INTERNAL 4.0 MREM 0 .000 ORGAN
  • THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CR 141.

RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

08-06-2003 01 :17pm From-Exelon LaSal Is 8153571262 T-101 P.012/013 F-057 LASALLE STATION UNIT ONE ACTUAL 2002 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/02/03 ADULT RECEPTOR lST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 0. OOE+00 0 .OOE+00 0. OOE+00 . OOE+00 0 .OOE+00 BODY INTERNAL 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 10 CFR 50 APP. I

OF APP I. ------------

QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY  % OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I TOTAL BODY (MREM) 1.5 0.00 0 .00 0 .00 0 . 00 3.0 0. 0 0 CRIT. ORGAN(MREM) 5.0 0. 0 0 0. 0 0 .0 0 0. 0 0 1 0. 0 0. 0 0 RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

08-06-2003 01:7pm From-Exelon LaSa le 8153571262 T-701 P 013/013 F-057 LASALLE STATION UNIT ONE 2002 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM

  • PERIOD OF RELEASE - 01/01/02 TO 12/31/02 CALCULATED 04/02/03 ADULT RECEPTOR 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 0 .OOE+00 . OOE+00 0. 00E+00 0. 00E+00 0 . OOE+00 BODY INTERNAL 0. OOE+00 0. OOE+00 0. OOE+00 0. 00E+00 . OOE+00 ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 2002 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT E OF LIMIT TOTAL 4.0 MREM 0 .000 BODY INTERNAL 4.0 MREM 0 .000 ORGAN
  • THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CR 141.

RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.2 January 1995 ODCM DATABASE VERSION 1.1 January 1995

LASALLE STATION UNIT ONE 10 CFR 20 COMPLIANCE ASSESSMENT PERIOD OF ASSESSMENT 01/01/02 TO 12/31/02 CALCULATED 04/04/03

1. 10 CFR 20.1301 (a)(1) Compliance Total Effective Dose Eqivalent, mrem/yr 4.41E-01 10 CFR 20.1301 (a)(1) limit mrem/yr 100.0

% of limit 0.44 Compliance Summary - 10CFR20 1st 2nd 3rd 4th of Qtr Qtr Qtr Qtr Limit TEDE 7.54E-02 1.16E-01 1.25E-01 1.25E-01 0.44 RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

LASALLE STATION UNIT ONE 10 CFR 20 COMPLIANCE ASSESSMENT PERIOD OF ASSESSMENT 01/01/02 TO 12/31/02 CALCULATED 04/04/03

2. 10 CFR 20.1301 (d)/40 CFR 190 Compliance Dose Limit  % of (mrem) (mrem) Limit Whole Body Plume 1.llE-01 (DDE) Skyshine 3. 09E-01 Ground 2. 05E-03 Total 4.22E-01 25.0 1.69 Organ Dose Thyroid 2.36E-01 75. 0 0.32 (CDE) Gonads 1.23E-02 25.0 0.05 Breast 1.22E-02 25.0 0.05 Lung 1.23E-02 25. 0 0.05 Marrow 1.23E-02 25.0 0.05 Bone 1.23E-02 25.0 0.05 Remainder 1.26E-02 25.0 0.05 CEDE 1.91E-02 TEDE 4.41E-01 100 .0 0.44 RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

LASALLE STATION UNIT TWO 10 CFR 20 COMPLIANCE ASSESSMENT PERIOD OF ASSESSMENT 01/01/02 TO 12/31/02 CALCULATED 04/04/03

1. 10 CFR 20.1301 (a)(1) Compliance Total Effective Dose Eqivalent, mrem/yr 3.14E-01 10 CFR 20.1301 (a) (1) limit mrem/yr 100.0

% of limit 0.31 Compliance Summary - 10CFR20 1st 2nd 3rd 4th of Qtr . Qtr Qtr Qtr Limit TEDE 8.53E-02 7.18E-02 8.39E-02 7.31E-02 0.31 RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

LASALLE STATION UNIT TWO 10 CFR 20 COMPLIANCE ASSESSMENT PERIOD OF ASSESSMENT 01/01/02 TO 12/31/02 CALCULATED 04/04/03

2. 10 CFR 20.1301 (d)/40 CFR 190 Compliance Dose Limit  % of (mrem) (mrem) Limit Whole Body Plume 0.OOE+00 (DDE) Skyshine 3.14E-01 Ground 0. OOE+00 Total 3.14E-01 25.0 1.26 Organ Dose Thyroid 0. OOE+00 75. 0 0. 00 (CDE) Gonads 0. OOE+00 25.0 0. 00 Breast 0. OOE+00 25.0 0.00 Lung 0. OOE+00 25.0 0 . 00 Marrow 0. OOE+00 25.0 0. 00 Bone 0. OOE+00 25.0 0. 00 Remainder 0. OOE+00 25.0 0.00 CEDE 0. OOE+00 TEDE 3. 14E-01 100.0 0.31 RESULTS BASED UPON: ODCM ANNEX REVISION 3.0 MAY 2001 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

METEOROLOGICAL DATA

MURRAY & TRETTEL, INC.

Wednesday, February 5, 2003 Mr. Mike Wolfe Rad Protection LaSalle Station Exelon Nuclear 2601 N. 215t Road Marseillies, IL 61341

Dear Mr. Wolfe:

Enclosed are copies of the LaSalle Station meteorological site quarterly joint-frequency wind rose tables for 2002. They are being sent pursuant to the Specification for Meteorological Data and Meteorological Monitoring Services & Maintenance (MET1), 3.3.2,3.3.3, METSPECS/18/15 and METSPECS/18/41, Table 2a, format of wind rose table.

At this time, we would like to request the 2002 effluent data for your nuclear plant The effluent data is required to process the 2002 annual report on the Meteorological Monitoring Program as per Specification No. MET1 3.3.4.

In order to expedite the annual report generation, please forward the 2002 effluent data from your plant to:

Tom Begley Murray & Trettel, Inc 414 W Frontage Road Northfield, IL 60093 If you have any questions, please contact Tom Begley @ (847) 446-7800 x 175.

Thank you for your assistance.

Sincerely, Tom Begley Environmental Meteorologist

/tb Enclosures 414 WEST FRONTAGE ROAD NORTHFIELD. IL 60093 PHONE: (847) 446-7800 FAX: (847) 446-8130 E-MAIL: MTQNXWFATHFRCOMMAND-rOM

Lalle M ear Stati a Jamary-Nrch, 2002 33 ft. ind Speed and Directin 200Ft-33ft Deta-T F)

NImber of Mserations 2159 Values are Perent Occurenc SRBD --- D DRE=

---------------------------- SnraBm a -SEs- -

OASS N Is E IN B E S8 Si S SSI SW IS 1 W IV I Tm 1U SuI S ISUML I

u 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Cl 0.00 LSu 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ISI 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 LSs .QO0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.00 0.00 0.00 0.00 0.00 0.00 iRs 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 S 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ki 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1 Su 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

- I 0.05 0.05 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.09 0.14 0.05 0.00 0.00 0.00 0.00 0.42 0.42 3 Ss 0.05 0.05 0.00 0.00 0.00 0.05 0.00 0.09 0.05 0.05 0.05 0.05 0.00 0.00 0.09 0.00 0.51 0.51 KS 0.00 0.00 0.05 0.00 0.00 0.09 0.05 0.05 0.00 0.05 0.00 0.09 0.09 0.00 0.00 0.00 0.46 0.46 Is 0.05 0.00 0.00 0.00 0.09 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.23 0.23 1.62 ID 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 R 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 4S 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.14 0.09 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.37 0.37

- 1 0.93 0.65 0.09 0.14 0.14 0.09 0.00 0.19 0.14 0.09 0.19 0.14 0.46 0.32 0.46 0.37 4.40 4.40 7SS 0.69 0.05 0.23 0.00 0.37 0.28 0.19 0.19 0.37 0.00 0.46 0.23 0.19 0.14 0.28 0.46 4.12 4.12 KS 0.09 0.00 0.00 0.19 0.05 0.00 0.23 0.05 0.14 0.32 0.23 0.37 0.14 0.65 0.42 0.19 3.06 3.06 i 0.05 0.00 0.00 0.00 0.00 0.19 0.14 0.05 0.14 0.28 0.19 0.19 0.14 0.56 0.28 0.09 2.27 2.27 14.27 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 - 0.05 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.09 0.00. 0.00 0.00 0.19 0.00 0.05 0.00 0.00 0.37 0.37 1.71 0.88 0.93 1.02 0.60 0.09 0.09 0.05 0.14 0.32 0.32 0.79 1.16 0.51 0.93 1.34 10.88 10.88 0.42 0.09 0.09 0.09 0.65 0.09 0.46 0.28 0.37 0.56 0.56 0.74 0.65 0.74 0.56 0.69 7.04 7.04 0.00 0.00 0.00 0.00 0.05 0.00 0.09 0.56 0.69 0.56 2.36 2.22 0.79 0.42 0.32 0.00 8.06 8.06 0.00 0.00 0.00 0.00 0.00 0.32 0.32 0.23 0.19 0.37 2.73 1.30 1.39 0.05 0.05 0.00 6.95 6.95 33.44 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00' 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.09 0.09 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.00 0.00 0.05 0.32 0.19 0.05 0.19 0.09 0.00 0.97 0.97 0.69 0.14 1.20 1.16 0.51 0.19 0.19 0.46 0.65 1.53 0.97 1.07 1.57 2.27 0.79 2.36 15.75 15.75 0.09 0.00 0.00 0.09 0.32 0.00 0.23 0.79 1.48 1.67 1.39 1.07 0.74 0.88 0.28 0.23 9.26 9.26 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.37 0.42 0.74 2.73 0.97 0.05 0.00 0.00 0.00 5.28 5.28

.00 0.00 0.00 0.00 0.00 0.00 0.23 0.09 0.09 0.23 0.79 0.42 0.05 0.00 0.00 0.00 1.90 1.90 33.30

LaSalle ulear Statimn Jamay-farch, 2002 33 ft. Wind Speed and Direction 200Ft-33Ft Delta-T (F)

ED --------------------------------- WID DIRKCION CLASSES --------------------------------- --------- STABILITY CASSES ----------

loSS X ID ME Es I aBS SE SSE S SW SI WS# I NWDl 1mm u M SJ S S ESTOM 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.14 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.09 0.09 0.14 0.00 0.00 0.42 0.42 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.14 0.14 0.05 0.09 0.00 0.00 0.56 0.56 0.23 0.00 0.97 0.32 0.09 0.09 0.00 0.19 0.79 0.60 0.56 0.14 1.1 1.30 0.97 0.60 7.97 7.97 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.83 0.56 0.56 0.14 0.69 1.25 0.05 0.05 4.21 4.21 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 0.23 0.28 0.05 0.00 0.05 0.00 0.00 0.69 0.69 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 13.99 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.19 0.19 0.00 0.00 0.14 0.00 0.00 0.00 0.05 0.09 0,09 0.00 0.05 0.05 0.65 0.05 0.19 0.19 1.53 1.53 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.46 0.23 0.09 0.00 0.46 0.32 0.05 0.00 1.62 1.62 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.33 MVT5.05 1.90 3.94 3.10 2.87 1.48 2.50 4.03 7.55 8.57 15.15 10.84 10.56 10.05 5.79 6.62 100.00 0.28 0.60 2.45 40.94 26.77 17.60 11.35 100.00 wind Direction by Stability I MINHEIISSE s SSWS SW ISW I S W w m -STABILm CLASSES-0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.28 Extremely Unstable 0.00 0.00 0.05 0.00 0.00 0.00 0..00 0.05 0.14 0.00 0.00 0.14 0.09 0.14 0.00 0.00 0.60 Moderately Unstable 0.00 0.00 0.05 0.05 0.00 0.00 0.14 0.23 0.28 0.09 0.51 0.51 0.14 0.32 0.09 0.05 2.45 Slightly Unstable 3.61 1.71 3.33 2.64 1.34 0.46 0.37 0.97 1.81 2.64 2.22 2.22 4.96 4.45 3.33 4.86 40.94 Neutral 1.25 0.19 0.32 0.23 1.34 0.42 0.88 1.39 3.57 3.06 3.10 2.22 2.73 3.33 1.30 1.44 26.77 Slightly Stable 0.09 0.00 0.05 0.19 0.09 0.09 0.37 1.02 1.34 1.90 5.60 3.71 1.07 1.16 0.74 0.19 17.60 uderately Stable 0.09 0.00 0.00 0.00 0.09 0.51 0.74 0.37 0.42 0.88 3.71 1.90 1.57 0.65 0,32 0.09 11.35 Extremely Stable Wind Directin by Wind Speed I NEREESESE SSS S SSW SW NV N TM -WNSE aSSRS-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 C LM 0.14 0.09 0.05 0.00 0.09 0.14 0.14 0.14 0.05 0.19 0.19 0.19 0.09 0.05 0.09 0.00 1.62 < 3.5 qlh 1.76 0.69 0.32 0.32 0.56 0.56 0.60 0.65 0.88 0.74 1.11 0.93 0.93 1.67 1.44 1.1 14.27 3.6 - 7.5 ph 2.13 0.97 1.20 1.11 1.30 0.51 0.97 1.20 1.39 1.81 5.97 5.23 3.98 1.76 1.85 2.04 33.44 7.6 - 12.5 ph 0.79 0.14 1.25 1.30 0.83 0.19 0.69 1.71 2.69 4.21 6.21 3.75 2.45 3.33 1.16 2.59 33.30 12.6 - 18.5 mph 0.23 0.00 0.37 0.37 0.09 0.09 0.00 0.23 1.95 1.39 1.53 0.69 1.95 2.83 1.02 0.65 13.99 18.6 - 24.5 mph 0.00 0.00 0.14 0.00 0.00 0.00 0.09 0.09 0.60 0.23 0.14 0.05 1.16 0.42 0.23 0.23 3.38 , 24.5 mph

IaSalle udear Statim Januarylrh 2002 375 ft. Kind Speed and Direio 375Ft-33Ft Delta-T II)

Ember of Observais: 2143 Talues are Percent Occurence

-- ---- SDBILM USS -------

ISE BE I IE S SSo S SSW SW SW E SN I U SU I Ss SMS irs I 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ka 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Su 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 I 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ss 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 is 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 IS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 v 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Ka 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Su 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,0 0.00 0.00 0.00 0.00 0.00 I 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.09 0.00 0.00 0.00 0.23 0.23

$ 0.00 0.05 0.00 0.14 0.05 0.05 0.00 0.05 0.00 0.05 0.00 0.05 0.00 0.00 0.05 0.14 0.61 0.61 NS 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 is 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.05

- 0.98 la 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Su 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1 0.14 0.19 0.05 0.05 0.05 0.09 0.05 0.23 0.09 0.19 0.14 0.09 0.23 0.09 0.37 0.37 2.43 2.43 1S 0.19 0.14 0.14 0.26 0.09 0.00 0.14 0.14 0.14 0.05 0.09 0.05 0.05 0.05 0.00 0.00 1.54 1.54 KS 0.00 0.05 0.09 0.00 0.05 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.05 0.05 0.00 0.05 0.47 0.47 iS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 0.00 0.00 0.05 0.05 0.00 0.09 0.05 0.23 0.23 4.67 la 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ItT 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Su 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1 0. 0.56 0.23 0.61 0.4 0.14 0.05 0.23 0.19 0.09 0.33 0.37 0.47 0.28 0.65 0.33 5.83 5.83 I$ 0.28 0.37 0.19 0.19 0.19 0.09 0.09 0.05 0.14 0.19 0.09 0.23 0.19 0.09 0.28 0.14 2.80 2.80 KS 0.00 0.00 0.05 0.05 0.00 0.00 0.14 0.14 0.05 0.00 0.19 0.00 0.00 0.14 0.14 0.09 0.98 0.98 IS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.10 0.05 0.05 0.00 0.14 0.14 9.75 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Q.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.14 1.91 0.70 1.17 0.61 0.33 0.09 0.19 0.23 0.05 0.23 0.28 0.79 1.31 0.65 0.98 0.93 10.45 10.45 0.33 0.23 0.09 0.14 0.19 0.09 0.OS 0.09 0.14 0.19 0.28 0.70 0.70 0.19 0.93 0.47 4.81 4.81 0.14 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.00 0.23 0.14 0.37 0.28 0.56 0.9 0.14 2.19 2.89 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.00 0.14 0.09 0.00 0.00 0.05 0.00 0.42 0.42 18.71

LaSalle Nuclear Station Januay-Marc, 2002 375 ft. Wind Speed and Direction 375Ft-33Ft Delta-T (F)

SPI ---------------------------------- ND DIRECION CASS ---------------------------------- --------- STABILITY fiHS ----------

CSS m NNEm ES3 S SSE S SSW SW W w NNW T so mg Su N SS MS 5S TL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.09 0.09 1.17 0.09 0.56 0.89 0.42 0.05 0.05 0.51 0.56 1.49 1.26 0.75 0.93 2.24 1.21 1.31 13.49 13.49 0.37 0.00 0.00 0.00 0.23 0.2B 0.00 0.33 0.05 0.61 0.56 0.93 0.42 0.75 0.47 0.23 5.23 5.23 0.05 0.00 0.00 0.00 0.00 0.00 0.05 0.28 0.05 0.14 0.33 0.79 1.12 0.98 0.28 0.09 4.15 4.15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.14 0.23 0.33 0.09 0.00 0.00 0.89 0.89 23.85 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TSU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.05 0.42 0.00 1.26 0.05 0.37 0.05 0.14 0.23 1.91 0.75 0.89 0.42 1.59 1.12 1.82 0.70 11.71 11.71 2Ss 0.05 0.00 0.00 0.09 0.28 0.05 0.00 0.37 2.71 3.13 3.03 1.31 2.38 2.85 0.65 0.19 17.08 17.08 4 5S 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.42 1.12 0.79 4.29 3.03 1.31 0.23 0.09 0.00 11.34 11.34 is 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.23 0.33 0.00 0.51 0.37 0.14 0.23 0.00 0.00 1.87 1.87 42.04 TOT 5.97 2.47 3.97 3.08 2.66 1.03 1.07 3.69 7.75 8.26 12.69 10.83 11.62 10.64 9.01 5.27 100.00 0.00 0.00 0.28 44.14 32.06 19.93 3.59 100.00 Wind Direction by Stability N II s ES Ss SSE S SSW S a1W 1I WNW H I TOL -SILTCl ASSE-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ktremely Unstable 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Moderately Unstable 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.28 Slightly Unstable 4.57 1.54 3.27 2.19 1.59 0.42 0.47 1.45 2.85 2.75 2.89 2.47 4.62 4.39 5.04 3.64 44.14 Neutral 1.21 0.79 0.42 0.84 1.03 0.56 0.28 1.03 3.17 4.20 4.06 3.27 3.73 3.92 2.38 1.17 32.06 Slightly Stable 0.19 0.14 0.14 0.05 0.05 0.05 0.28 0.89 1.21 1.31 4.95 4.20 2.75 1.96 1.40 0.37 19.93 Moderately Stable 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.33 0.51 0.00 0.79 0.75 0.51 0.37 0.19 0.09 3.59 Rtrmely Stable Wind Direction by Wind Speed I INH B RE ISSESS SSB S SSW SW UTL VW N MR - WINDSPBD MASSS-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CAL N 0.05 0.14 0.00 0.14 0.05 0.05 0.00 0.05 0.05 0.05 0.00 0.09 0.09 0.00 0.05 0.19 0.98 < 3.5 h 0.33 0.37 0.28 0.33 0.19 0.09 0.19 0.37 0.23 0.37 0.23 0.19 0.37 0.19 0.47 0.47 4.67 3.6 - 7.5 mph 1.17 0.93 0.47 0.84 0.61 0.23 0.28 0.42 0.42 0.28 0.61 0.61 0.65 0.56 1.12 0.56 9.75 7.6 - 12.5 mph 2.38 0.93 1.40 0.75 0.51 0.19 0.33 0.42 0.28 0.65 0.84 1.96 2.29 1.40 2.85 1.54 18.71 12.6 - 18.5 mph 1.59 0.09 0.56 0.89 0.65 0.33 0.09 1.17 0.70 2.24 2.29 2.80 2.80 4.06 1.96 1.63 23.85 18.6 - 24.5 ph 0.47 0.00 1.26 0.14 0.65 0.14 0.19 1.26 6.07 4.67 8.73 5.18 5.41 4.43 2.57 0.89 42.04 >24.5 mh

WaSalle Nuclear Station Jamary-kDe er, 2002 33 ft. ind Speed and Directi 200Ft-33Ft Delta-T F)

Number of Mservations 8457 Values are Pee Ocuece

......--.----. .-...... -..--..--..-.- NID DI={ amSSs -------- S.BILMMM --------

ISS IX E ED F ISE SESS! S SWSW I owEIE WTO IU USu I ..SS s SisAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 .0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.08 0.02 0.05 0.01 0.09 0.01 0.04 0.04 0.05 0.09 0.06 0.04 0.06 0.04 0.02 0.79 0.79 0.05 0.08 0.04 0.02 0.04 0.05 0.05 0.07 0.07 0.06 0.05 0.04 0.06 0.01 0.07 0.00 0.74 0.74 0.04 0.02 0.04 0.01 0.02 0.02 0.01 0.02 0.05 0.04 0.01 0.07 0.1 0.01 0.02 0.05 0.54 0.54 0.02 0.00 0.01 0.00 0.05 0.02 0.0s 0.02 0.00 0.01 0.05 0.06 0.09 0.05 0.05 0.05 0.53 0.53 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.02 0.02 0.01 0.06 0.02 0.01 0.00 0.04 0.01 0.04 0.02 0.02 0.04 0.05 0.01 0.01 0.01 0.01 0.37 0.37 0.05 0.07 0.07 0.08 0.12 0.06 0.os 0.14 0.15 0.1S 0.11 0.13 0.14 0.13 0.02 0.04 1.51 1.51 1.03 1.01 0.38 0.39 0.41 0.37 0.35 0.34 0.31 0.25 0.54 0.45 0.51 0.57 0.44 0.63 7.97 7.97 0.77 0.76 0.27 0.15 0.50 0.3 0.21 0.22 0.31 0.22 0.48 0.31 0.37 0.45 0.44 0.40 6.21 6.21 0.09 0.19 0.01 0.06 0.41 0.53 0.48 0.33 0.51 0.54 0.63 0.44 0.38 0.59 0.34 0.19 5.73 5.73 0.02 0.01 0.00 0.01 0.24 0.52 0.43 0.78 0.61 0.82 0.89 t.56 0.38 0.53 0.1 0.04 5.94 5.94 0.00 0.00 0.07 0.02 0.00 0.00 0.00 0.00 0.00 0.11 0.04 0.18 0.1 0.00 0.00 0.00 O.S2 0.52 0.04 0.04 0.09 0.20 0.04 0.01 0.01 0.05 0.04 0.19 0.17 0.14 0.14 0.05 0.04 0.00 1.23 1.23 0.07 0.06 0.14 0.12 0.13 0.08 0.12 0.12 0.11 0.15 0.31 0.33 0.13 0.15 0.07 0.11 2.20 2.20 1.32 0.96 1.25 0.76 0.78 0.27 0.20 0.19 0.53 0.69 1.03 0.99 1.12 1.02 0.99 1.61 13.72 13.72 0.41 0.1 0.40 0.57 1.01 0.21 0.33 0.21 0.69 0.79 0.98 0.63 0.70 0.64 0.51 .56 8.74 8.74 0.00 0.00 0.01 0.00 0.39 0.09 0.14 0.44 0.57 0.66 1.38 0.90 0.67 0.18 0.17 0.01 5.62 5.62 0.00 0.00 0.00 0.00 0.05 0.21 0.19 0.28 0.30 0.78 1.4 1.08 0.1 0.06 0.05 0.00 5.03 5.03 0.02 0.00 0.02 0.06 0.00 0.00 0.00 0.01 0.02 0.11 0.08 O.04 0.02 0.02 0.00 O.00 0.41 0.41 0.00 0.01 0.04 0.05 0.02 0.O0 0.01 0.04 0.04 0.15 0.14 0.12 0.09 0.14 0.00 0.04 0.89 0.89 0.04 0.00 0.05 0.06 0.06 0.01 0.05 0.09 0.07 0.09 0.24 0.18 0.19 0.21 0.09 0.13 1.56 1.56 0.46 0.11 1.31 0.19 0.77 0.25 0.08 0.32 0.51 0.78 0.74 0.69 0.91 1.42 0.69 1.51 U.43 11.43 0.05 0.00 0.09 0.22 0.50 0.07 0.1 0.28 0.91 1.02 1.05 0.58 0.56 0.41 0.17 0.07 6.09 6.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.15 0.26 0.50 0.99 0.32 0.12 0.00 0.00 0.00 2.34 2.34 0.00 0.00 0.00 0.00 0.00 0.00 0.06 0.02 0.02 0.1 0.22 0.14 0.01 0.00 0.00 0.0 0.59 0.59

LaSalle Muclear Station January-December, 2002 33 ft. ind Speed and Direction 200t-33ft Dlelta-T F)

PEE-----------------WND DINEMION CLASSES------------------ -----STAILITY CLASSES----

LASS N NR8 HE I ESE SE SSE SSSW S WSW I 11 WWImm EUMICSu N Ss Ms s TL EU 0.00O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.07 0.12 0.02 0.04 0.00 0.00 0.00 0.00 0.25 0.25 NV 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.12 0.02 0.05 0.02 0.06 0.02 0.00 0.34 0.34 SuT0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.07 0.08 0.07 0.09 0.02 0.11 0.01 0.00 0.47 0.47 I 0.11 0.00 0.33 0.25 0.24 0.26 0.05 0.06 0.27 0.37 0.22 0.09 0.53 0.57 0.43 0.27 4.04 4.04 Ss 0.00 0.00 0.00 0.01 0.01 0.05 0.02 0.02 0.33 0.43 0.34 0.08 0.34 0.56 0.05 0.01 2.26 2.26 Ms 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.06 0.07 0.09 0.01 0.00 0.01 0.00 0.00 0.25 0.25 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 la 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.07 0.00 0.00 0.00 0.00 0.00 0.00 0.07 0.07 mg

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 ISu 0.00 0.000.00 0.00 0.00 0.00 0.01 0.00 0.01 0.01 0.00 0.00 0.01 0.00 0.00 0.01 0.06 0.06 I 0.00 0.00 0.04 0.00 0.04 0.00 0.01 0.04 0.05 0.06 0.06 0.01 0.20 0.14 0.08 0.0 0.80 0.80

!Ss 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.14 0.06 0.02 0.02 0.20 0.20 0.02 0.00 0.70 0.70 IMs 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.01 0.01 Bs 0.00 0.00 0.00 0.00O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MTUI 4.69 3.56 4.72 4.00 5.83 3.57 3.05 4.36 7.19 9.68 12.56 8.86 8.81 8.37 4.92 5.83 100.00 1.28 2.84 5.81 38.76 24.74 14.50 12.08 100.00 Wind Direction by Stability N MM ENH EESESEEgSi so S S SWW SW I NW NNW2TL -STABILMl CASSES-0.02 0.00 0.09 0. 08 0.00 0.00 0.00 0.01 0.09 0.41 0.15 0.25 0.13 0.02 0.00 0.00 1.28 Etreonly Unstable 0.05 0.11 0.15 0.26 0.06 0.05 0.04 0.12 0.15s 0.48 0.37 0.35 0.27 0.26 0.07 0.05 2.84 Noderately Unstable 0.15 0.13 0.26 0.26 0.32 0.15s0.22 0.35 0.41 0.50 0.72 0.73 0.50 0.60 0.20 0.28 5.81 Slightly Unstable 3.02 2.15 3.33 2.33 2.25 1.24 0.71 0.98 1.70 2.19 2.70 2.29 3.31 3.77 2.66 4.13 38.76 Neutral 1.28 0.95 0.80 0.98 2.05 0.72 0.72 0.842.45 2.58 2.93 1.66 2.22 2.27 1.25 1.04 24.74 Slightly Stable 0.13 0.21 0.06 0.07 0.83 0.65 0.64 0.95 1.44 1.81 3.11 1.74 1.28 0.80 0.53 0.2S 14.50 Moderately Stable 0.05s 0.01 0.01 0.01 0.33 0.76 0.72 1.11 0.93 1.71 2.58 1.83 1.10 0.64 0.20 0.08 12.08 Extremely Stable Wind Direction by NWin Speed I M N E I RSSR SSE SW WSW W I VMINW TAm -IDD SPEED CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CAL 0.20 0.19 0.11 0.08 0.12 0.19 0.12 0.15 0.15 0.15 0.20 0.22 0.30 0.13 0.18 0.12 2.61 <3.5 qb 1.97 2.09 0.76 0.71 1.68 1.861.54 1.86 1.92 2.02 2.70 1.93 1.79 2.28 1.36 1.30 27.75 3.6 - 7.5 iop 1.84 1.16 1.97 1.67 2.39 0.89 0.99 1.29 2.22 3.37 5.32 4.25 3.49 2.09 1.822.28 37.05 7.6 - 12.5 mph 0.57 0.12 1.51 1.28 1.35 0.33 0.31 0.92 1.83 2.76 3.48 2.06 1.90 2.21 0.95 1.75 23.32 12.6 - 18.5 aph 0.11 0.00 0.33 0.26 0.26 0.31 0.07 0.08 0.85 1.18 0.78 0.37 0.92 1.30 0.51 0.28 7.61 18.6 - 24.5 mph 0.00 0.00 0.04 0.00 0.04 0.00 0.02 0.06f 0.21 0.20 0.08 0.04 0.41 0.35 0.11 0.09 1.66 > 24.5 npb

LiSalle Nuclear Station Jamary-December, 2002 375 ft. Wind Speed ad Dectim 375ft-33Ft Delta-T F) bneof Cbsenatios 8735 Vales are Perct Oirrence NM DREsCTI m -SS m-------- -- BI

STlhm SS ----------

ME I SE E ssWS SW Tsw I w NW

'T mm Eu u SU; I. SS ES S TL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 KU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 I N 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 S 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Is 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 0.02 0.00 0.03 0.05 0.01 0.00 0.01 0.02 0.01 0.01 0.06 0.02 0.05 0.01 0.01 0.35 0.35 0.02 0.03 0.02 0.06 0.03 0.02 0.01 0.02 0.02 0.02 0.00 0.01 0.03 0.00 0.02 0.03 0.38 0.38 0.01 0.06 0.00 0.00 0.01 0.00 0.02 0.00 0.03 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.15 0.15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.01 0.89 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.44 0.41 0.35 0.38 0.38 0.30 0.26 0.33 0.29 0.30 0.25 0.27 0.46 0.22 0.33 0.32 5.29 5.29

0. 0.09 0.21 0.14 0.09 0.07 0.14 0.08 0.15 0.08 0.16 0.09 0.10 0.08 0.08 0.09 1.81 1.81 0.05 0.08 0.06 0.07 0.06 0.07 0.02 0.01 0.05 0.14 0.07 0.15 0.08 0.1 0.01 0.01 1.03 1.03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.05 0.01 0.02 0.03 0.06 0.00 0.02 0.01 0.23 0.23 8.36 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.03 0.01 0.00 0.00 0.00 0.00 0.05 0.02 0.01 0.03 0.00 0.00 0.00 0.17 0.17 1.09 1.04 0.65 0.810.63 0.37 0.34 0.40 0.58 0.53 0.80 0.98 0.58 0.68 0.88 0.80 5.17 11.17 0.38 0.34 0.29 0.41 0.41 0.27 0.18 0.16 0.18 0.21 0.14 0.37 0.29 0.14 0.23 0.16 4.16 4.16 0.05 0.05 0.02 0.09 0.07 0.13 0.11 0.23 0.16 0.18 0.29 0.18 0.16 0.22 0.18 0.14 2.26 2.26 0.01 0.01 0.00 0.00 0.00 0.01 0.02 0.02 0.1 0.08 0.10 0.06 0.03 0.02 0.03 0.01 0.54 0.54 18.29 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.oq 0.01 0.01 0.00 0.00 0.00 0.02 0.02 0.00 0.00 0.08 0.05 0.00 0.00 0.00 0.01 0.00 0.01 0.01 0.14 0.06 0.01 0.01 0.00 0.38 0.3J 1.08 0.76 1.64 1.20 0.73 0.22 0.18 0 J4 0.38 1.66 1.06 1.01 1.25 1.03 1.17 0.96 13.67 13.67 0.52 0.47 0.48 0.78 0.46 0.27 0.15 0.16 0.27 0.30 0.47 0.55 0.49 0.47 0.60 0.42 6.66 6.16 0.14 0.02 0.02 0.08 0.07 0.16 0.18 0.26 0.18 0.31 0.35 0.35 0.26 0.57 0.45 0.19 3.62 3.62 0.00 0.00 0.00 0.00 0.00 0.01 0.14 0.29 0.09 0.11 0.15 0.16 0.06 0.02 0.05 0.07 1.14 1.14 25.69

LaSalle Nuclear Station Jamuary-Deceder, 2002 375 ft. Wind peed ad Direction 375Ft-33Ft Delta-T (F) 3D --------------------------------- ND DIRECLON CLASSES --------------------------------- --------- STABILITY ASSES ----------

1SS NNiE NHE I ISE SS3 51 S SSV sW H NN NW I NEW TOTAL H m SuN SS MS S TAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.03 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.05 0.07 0.06 0.02 0.00 0.00 0.00 0.00 0.24 0.24 0.74 0.5 1.03 0.87 0.56 0.17 0.10 0.29 0.50 0.93 0.98 0.63 0.81 1.31 1.05 0.87 li.00 11.00 0.27 0.05 0.17 0.15 0.50 0.29 0.16 0.24 0.31 0.50 0.81 0.49 0.37 0.62 0.57 0.29 5.79 5.79 0.01 0.00 0.00 0.00 0.11 0.23 0.23 0.16 0.21 0.34 0.66 0.52 0.64 0.50 0.23 0.10 3.95 3.95 0.03 0.00 0.00 0.00 0.00 0.06 0.09 0.13 0.13 0,25 0.23 0.21 0.17 0.07 0.00 0.01 1.37 1.37 22.37 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.02 0.00 0.00 0.00 0.00 0.00 0.03 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.14 0.02 0.01 0.00 0.00 0.01 0.00 0.19 0.19 0.18 0.00 0.50 0.19 0.42 0.31 0.10 0.11 0.77 0.85 0.58 0.26 0.71 0.65 0.95 0.40 7.01 7.01 0.03 0.00 0.00 0.02 0.16 0.14 0.10 0.19 1.17 2.31 1.97 0.73 1.20 1.11 0.32 0.07 9.54 9.54 0.00 0.00 0.00 0.00 0.02 0.08 0.17 0.38 0.65 0.96 1.84 1.09 0.79 0.21 0.02 0.00 6.22 6.22 0.00 0.00 0.00 0.00 0.00 0.01 0.07 0.11 0.38 0.07 0.23 0.41 0.05 0.08 0.00 0.00 1.41 1.41 24.40 MT 5.28 3.58 5.54 5.37 4.80 3.19 2.80 3.97 6.75 9.44 11.33 8.82 8.72 8.16 7.24 4.99 100.00 0.00 0.07 0.98 48.49 28.53 17.22 4.71 100.00 Wind Dimrection by Stability N I E B S S SSE S SSWSWa W NINWT -STABILITY CASSHS-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Extremely Unstable 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.02 0.01 0.01 0.00 0.00 0.00 0.07 kderately Unstable 0.03 0.00 0.09 0.08 0.02 0.00 0.00 0.01 0.06 0.26 0.11 0.18 0.09 0.01 0.02 0.00 0.98 Slightly Unstable 3.56 2.38 4.18 3.49 2.77 1.37 1.00 1.49 2.54 3.27 3.70 3.22 3.84 3.93 4.40 3.37 48.49 Neutral 1.39 0.98 1.17 1.56 1.66 1.06 0.74 0.86 2.11 3.42 3.55 2.24 2.48 2.42 1.82 1.06 28.53 Slightly Stable 0.25 0.21 0.10 0.24 0.34 0.66 0.74 1.04 1.28 1.95 3.22 2.29 1.93 1.61 0.89 0.45 17.22 Moderately Stable 0.05 0.01 0.00 0.00 0.00 0.09 0.32 0.S7 0.76 0.53 0.73 0.87 0.37 0.19 0.10 0.11 4.71 Etrewly Stable Wind Direction by Wind Speed N

I NIB B BI6 SSR SS3 S SSW SfR RR NW NNW TUAL -WIND SPEED MhSSRS-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CALX 0.07 O.1 0.02 0.09 0.09 0.03 0.03 0.03 0.08 0.05 0.01 0.07 0.06 0.05 0.03 0.06 0.89 < 3.5tph 0.64 0.58 0.62 0.58 0.53 0.44 0.42 0.45 0.53 0.53 0.50 0.55 0.70 0.41 0.45 0.44 8.36 3.6 - 7.5mh 1.52 1.44 0.97 1.35 1.12 0.78 0.66 0.81 1.04 1.04 1.35 1.60 1.10 1.05 1.33 1.11 18.29 7.6 - 12.5 Mh 1.73 1.25 2.22 2.11 1.26 0.66 0.65 1.06 0.93 1.40 2.05 2.22 2.13 2.11 2.27 1.65 25.69 12.6 - 18.5 q*

1.10 0.19 1.20 1.02 1.19 0.74 0.58 0.81 1.20 2.10 2.75 1.87 1.99 2.50 1.85 1.27 22.37 18.6 -24.5 b 0.22 0.00 0.50 0.22 0.61 0.54 0.45 0.80 2.98 4.34 4.67 2.51 2.75 2.05 1.31 0.47 24.40 >24.5 mph

LaSalle Wlear Statima Wril-Jme, 2002 33 ft. id Speed and Directim 200ft-33ft Delta-T (F)

Ier of Obsenatioms 2179 Values are Percet O wr

- M1 DM~0tf CUSSES ----- --------- STIBMY CUSSES ----------

I X INE I ISE SE S S S SW la I I! TML I KU Su Bs Ks SSI I 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 C.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.05 0.14 0.00 0.14 0.00 0.00 0.05 0.00 0.18 0.09 0.00 0.00 0.09 0.05 0.96 0.96 0.05 0.14 0.05 0.05 0.05 0.09 0.00 0.05 0.14 0.14 0.05 0.05 0.09 0.00 0.09 0.00 1.01 1.01 0.00 0.00 0.09 0.00 0.05 0.00 0.00 0.05 0.09 0.05 0.00 0.05 0.00 0.00 0.00 0.09 0.46 0.46 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 2.48 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.09 0.09 0.00 0.05 0.00 0.05 0.00 0.05 0.09 0.09 0.00 0.18 0.14 0.09 0.05 0.18 0.00 0.00 0.96 0.96 0.87 0.96 0.60 0.55 0.73 0.55 0.23 0.46 0.60 0.37 0.55 0.41 0.32 0.23 0.55 1.01 8.99 8.99 0.41 0.50 0.18 0.14 0.46 0.32 0.18 0.32 0.23 0.23 0.69 0.23 0.50 0.69 0.50 0.28 5.87 5.87 0.14 0.05 0.00 0.05 0.37 0.46 0.87 0.41 0.46 0.55 0.64 0.50 0.64 0.64 0.28 0.18 6.24 6.24 0.00 0.00 0.00 0.00 0.00 0.14 0.28 0.73 0.87 0.96 0.69 O.U 0.0 0.14 0.00 0.00 4.31 4.31 26.48 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.05 0.00 0.00 0.00 0.28 0.09 0.09 0.05 0.00 0.09 0.00 0.73 0.73 0.09 0.09 0.32 0.05 0.00 0.05 0.23 0.2 0.18 0.32 0.46 0.60 0.23 0.18 0.14 0.14 3.35 3.35-0.6O O.C4 1.19 0.64 0.83 0.41 0.32 0.28 1.33 0.87 1.10 0.92 1.06 1.56 1.38 2.02 15.14 15.14 0.05 0.05 0.23 0.64 1.28 0.50 0.41 0.23 0.92 0.05 0.87 0.64 0.96 0.32 0.50 0.32 7.99 7.99 0.00 0.00 0100 0.00 0.37 0.18 0.32 0.92 0.32 0.64 0.83 0.55 0.50 0.14 0.05 0.00 4.82 4.82 0.00 0.00 0.00 0.00 0.00 0.05 0.37 0.78 0.50 0.83 0.73 1.10 0.28 0.00 0.00 0.00 4.64 4.64 36.67 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.09 0.23 0.14 0.00 0.00 0.00 0.00 0.00 0.50 0.50.

0.00 0.05 0.14 0.05 0.05 0.00 0.05 0.05 0.00 0.32 0.32 0.32 0.23 0.37 0.00 0.05 1.97 1.97 0.00 0.00 0.18 0.09 0.05 0.00 0.14 0.28 0.18 0.09 0.18 0.18 0.28 0.46 0.05 0.23 2.39 2.39 0.55 0.28 2.39 0.83 0.73 0.64 0.09 0.60 0.83 0.60 0.55 0.64 0.46 1.10 0.83 1.47 12.57 12.57 0.00 0.00 0.14 0.28 0.73 0.14 0.00 0.23 0.96 1.28 1.10 0.41 0.09 0.14 0.23 0.00 5.74 5.74 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.37 0.8 0.23 0.00 0.05 0.00 0.00 0.00 1.70 1.70 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.00 0.00 0.00 0.00 0.00 0.14 0.14 25.01

LaSalle Nuclear Station April-June, 2002 33 ft. Wind Speed and Direction 200Ft-33Ft Delta-T F)

-PE--- D DIION CLUSSES- --------- S'TMTI CSSES ----------

mm No E E S SE S SSW SWS WWNW NW m IvmL EU SU N SS !! S s TL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.28 0.41 0.09 0.00 0.00 0.00 0.00 0.00 0.78 0.78 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.41 0.00 0.05 0.00 0.09 0.09 0.00 0.73 0.73 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.14 0.00 0.09 0.05 0.32 0.05 0.00 0.78 0.78 0.09 0.00 0.28 0.23 0.41 0.55 0.18 0.00 0.18 0.55 0.09 0.05 0.09 0.69 0.41 0.00 3.81 3.81 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.14 0.50 0.05 0.05 0.09 0.41 0.14 0.00 1.42 1.42 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.28 0.00 0.00 0.00 0.00 0.00 0.00 0.28 0.28 GMu 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0,00 0.00 0,00 0.00 0.05 0.05 IJ 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.23 0.00 0.00 0.05 0.50 0.05 0.00 0.96 0.96 2SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.14 0.23 0.05 0.00 0.50 0.50 4M 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Is 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TOT 2.94 2.89 5.87 3.81 6.33 4.31 3.76 5.97 8.99 11.47 9.87 7.71 6.29 8.40 5.55 5.83 100.00 1.56 3.58 7.53 42.45 22.53 13.22 9.13 100.00 Wind Direction by Stability N a 8 5SES3 aSS S S NWm W W mL -SMILrlf ClASSES-0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.37 0.92 0.23 0.00 0.00 0.00 0.00 0.00 1.56 Extremely Unstable 0.00 0.05 0.18 0.05 0.09 0.05 0.05 0.05 0.14 1.01 0.41 0.55 0.28 0.46 0.18 0.05 3.58 Moderately Unstable 0.09 0.14 0.50 0.18 0.05 0.09 0.46 0.64 0.50 0.78 0.78 0.96 0.60 1.15 0.23 0.37 7.53 Slightly Unstable 2.20 1.97 4.50 2.39 2.85 2.29 0.83 1.33 2.98 2.62 2.48 2.11 1.97 4.08 3.30 4.54 42.45 Neutral 0.50 0.69 0.60 1.10 2.57 1.06 0.60 0.83 2.39 2.20 2.75 1.47 1.88 1.79 1.51 0.60 22.53 Slightly Stable 0.14 0.05 0.09 0.05 0.78 0.64 1.19 1.56 1.24 2.11 1.70 1.10 1.19 0.78 0.32 0.28 13.22 Moderately Stable 0.00 0.00 0.00 0.00 0.00 0.18 0.64 1.56 1.38 1.84 1.51 1.51 0.37 0.14 0.00 0.00 9.13 ktremely Stable Wind Direction by Wind Speed N SSSusSa S WsW 9 NW WM -NDSEED CLUSSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CALM 0.14 0.23 0.18 0.18 0.09 0.23 0.00 0.14 0.28 0.18 0.23 0.18 0.09 0.00 0.18 0.14 2.48 < 3.5mph 1.42 1.56 0.78 0.78 1.56 1.51 1.65 2.02 2.16 2.29 2.71 1.74 1.61 1.8 1.33 1.47 26.48 3.6 - 7.5 mph 0.73 0.78 1.79 1.33 2.52 1.24 1.65 2.48 3.26 2.98 4.08 3.90 3.07 2.20 2.16 2.48 36.67 7.6 - 12.5 mph 0.55 0.32 2.85 1.28 1.56 0.78 0.28 1.33 2.43 3.44 2.62 1.56 1.10 2.07 1.10 1.74 25.01 12.6 - 18.5 tph 0.09 0.00 0.28 0.23 0.46 0.55 0.18 0.00 0.83 2.02 0.23 0.23 0.23 1.51 0.69 0.00 7.53 18.6 - 2.5 mph 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.05 0.55 0.00 0.09 0.18 0.73 0.09 0.00 1.84 > 4.5 mph

LaSlle udear Statimc 4pri-june, 2002 375 ft. ilid Speed and DirectiM 375Pt-33Ft Delta-T )

er of ftentimes 2178 Values a Perc= Occurrece

...... .............. ... ---------- ID DIR OU WSSS ---------------------------------- SDI ASC ----------

11 811 B }S EI E Si S SSW S I wI w WlML UR SUND SSS IS isTM 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 '0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.00 .. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.09 0.09 0.00 0.00 0.00 0.05 0.00 0.00 0.18 0.00 0.05 0.00 0.00 0.55 0.55 0.00 0.00 0.05 0.05 0.09 0.05 0.00 0.05 0.05 0.05 0.00 0.00 0.05 0.00 0.05 0.00 0.46 0.46 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0;00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.51 0.60 0.51 0.64 0.73 0.28 0.23 0.28 0.28 0.18 0.37 0.23 0.09 0.09 0.18 0.32 5.51 5.51 0.18 0.18 0.37 0.14 0.09 0.14 0.14 0.05 0.28 0.09 0.18 0.18 0.14 0.09 0.14 0.00 2.39 2.39 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.00 0.09 0.05 0.14 0.05 0.00 0.00 0.00 0.41 0.41 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.14 0.14 8.45 0.00 0.00 0.00 0.00 0.00 0.00 0.00- 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.64 0.96 0.64 0.32 0.23 0.09 0.55 O.6O 1.42 0.92 0.78 1.33 0.46 0.55 1.06 1.33 U.89 11.89 0.55 0.18 0.37 0.46 0.32 0.32 0.37 0.23 0.14 0.48 0.18 0.46 0.18 0.18 0.23 0.09 4.45 4.45 0.00 0.00 0.00 0.00 0.00 0.05 0.14 0.32 0.18 0.37 0.28 0.18 0.09 0.14 0.14 0.14 2.02 2.02 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.14 0.18 0.00 0.05 0.05 0.00 0.05 0.00 0.51 0.51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.32 1.88 1.19 0.60 0.32 0.28 0.73 0.69 0.92 1.15 1.15 1.10 1.97 2.07 1.33 15.93 15.93 0.28 0.28 0.05 0.23 0.41 0.28 0.23 0.41 0.37 0.28 0.73 0.64 0.51 0.60 0.28 Q.18 5.74 5.74 0.09 0.00 0.00 0.00 0.00 0.14 0.23 0.51 0.18 0.51 0.51 0.46 0.14 0.23 0.14 0.18 3.31 3.31 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.18 0.23 0.05 0.14 0.00 0.00 0.00 0.00 0.73 0.73

LaSalle Nuclear Station April-June, 2002 375 ft. ind Speed and Directio 375Ft-33Ft Delta-T (F)

D ---------------------------------- I DIDTION CLASSES ---------------------------------- --------- STABILITY CLASSES ----------

1SSI NSN I MM E S SESSE S SS SW WSWN N NW MTMM Su mu Su N SS MS ES TTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.23 0.09 0.00 0.00 0.00 0.00 0.00 0.55 0.55 0.83 0.37 1.79 1.10 0.55 0.46 0.28 0.32 0.92 0.83 0.69 0.92 0.,4 1.15 1.06 0.83 12.72 12.72 0.09 0.00 0.05 0.14 0.64 0.64 0.37 0.28 0.37 0.41 0.73 0.46 0.51 0.55 0.51 0.37 6.11 6.11 0.00 0.00 0.00 0.00 0.00 0.09 0.18 0.23 0.37 0.14 0.87 0.60 0.60 0.32 0.18 0.09 3.67 3.67 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.23 0.05 0.18 0.14 0.00 0.00 0.00 0.73 0.73 23.83 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.00 0.00 0.00 0.00 0.00 0.14 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.51 0.05 0.00 0.00 0.00 0.05 0.00 0.64 0.64 0.14 0.00 0.73 0.23 0.51 0.73 0.28 0.09 0.55 1.65 0.41 0.18 0.28 1.29 1.10 0.14 8.31 8.31 0.00 0.00 0.00 0.00 0.09 0.32 0.14 0.09 0.83 2.62 1.38 0.73 0.28 0.41 0.37 0.00 7.25 7.25 0.00 0.00 0.00 0.00 0.00 0.05 0.32 0.69 0.92 1.15 0.55 0.23 0.51 0.09 0.00 0.00 4.50 4.50 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.73 0.14 0.00 0.28 0.00 0.00 0.00 0.00 1.29 1.29 22.13 TOT 3.63 2.94 6.43 4.64 4.36 3.99 3.81 5.14 9.04 U.94 9.18 8.72 5.88 7.71 7.58 5.00 100.00 0.00 0.18 1.19 54.91 26.40 13.91 3.40 100.00 Wind Direction by Stability INNlliR 3NE51I SE SSR S SSW Sn IW NW NWTMM -STABILITY CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Rtremely Unstable 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.09 0.00 0.00 0.00 0.00 0.00 0.18 Moderately Unstable 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.73 0.14 0.00 0.00 0.00 0.05 0.00 1.19 Slightly Unstable 2.39 2.30 5.56 3.58 2.71 1.88 1.61 2.02 3.90 4.50 3.40 3.99 2.57 5.10 5.46 3.95 54.91 Neutral 1.10 0.64 0.57 1.01 1.65 1.74 1.24 1.10 2.02 3.63 3.21 2.48 1.65 1.84 1.56 0.64 26.40 Slightly Stable 0.09 0.00 0.00 0.05 0.00 0.32 0.87 1.79 1.65 2.25 2.25 1.61 1.38 0.78 0.46 0.41 13.91 Moderately Stable 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.23 1.19 0.78 0.09 0.64 0.28 0.00 0.05 0.00 3.40 Extremely Stable Wind Direction by Wind Speed NI ME ME IS3 S SS S SS7 SW WSW M NW NN L -WIND SPEED CS-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CA LM 0.05 0.05 0.05 0.14 0.18 0.05 0.00 0.05 0.09 0.05 0.00 0.18 0.05 0.05 0.05 0.00 1.01 ' 3.5Imh 0.69 0.78 0.87 0.83 0.83 0.41 0.37 0.41 0.55 0.37 0.60 0.55 0.37 0.18 0.32 0.32 8.45 3.6 - 7.5 ph 1.19 1.15 101 0.78 0.55 0.51 1.06 1.15 1.88 1.65 1.24 2.02 0.78 0.87 1.47 1.56 18.87 7.6 - 12.5 mph 0.60 0.60 1.93 1.42 1.01 0.73 0.78 1.74 1.42 1.93 2.43 2.39 1.74 2.80 2.48 1.70 25.71 12.6 -18.5 ph 0.96 0.37 1.84 1.24 1.19 1.19 0.83 0.83 2.02 1.84 2.43 2.16 1.88 2.02 1.74 1.29 23.83 18.6 - 24.5 mph 0.14 0.00 0.73 0.23 0.60 1.10 0.78 0.96 3.08 6.11 2.48 1.42 1.06 1.79 1.52 0.14 22.13 >24.5mph

LaSalle lucear Statim dy-Septer, 2002 33 ft. ianSpedand Dketi 200Ft-33Ft Delta-T (F) tbber of bservatims 1912 Value are Peret Ocmrrence

.. ...... ..... ...... ,... WM DMREt MS ........ ............... ............... ----- -- S= .LSS ----------

E IE BE SESSB S S SF E V SW Tm u Su I ss is mu 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 o.0o 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.21 0.05 0.05 0.05 0.05 0.16 0.00 0.16 0.10 .00 0.00 0.05 0.0S 0.05 0.00 0.05 1.05 1.05 0.05 0.16 0.05 0.05 0.05 0.05 0.10 0.10 0.05 0.00 0.10 0.00 0.00 0.00 0.00 0.00 0.78 0.78 0.05 0.10 0.00 0.00 0.05 0.00 0.00 0.00 0.10 0.05 0.05 O.0S 0.31 0.05 0.05 0.05 0.94 0.94 0.05 0.00 0.05 0.00 0.10 0.10 0.16 0.05 0.00 0.05 0.10 0.26 0.37 0.16 0.16 0.21 1.83 1.83 4.60 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.10 0.10 0.05 0.26 0.10 0.05 0.00 0.16 0.05 0.10 0.10 0.10 0.16 0.10 0.05 0.05 0.00 0.05 1.41 1.41 0.10 0.26 0.31 0.31 0.52 0.21 0.05 0.26 0.52 0.42 0.26 0.47 0.52 0.31 0.05 0.10 4.71 4.71 0.94 1.05 0.52 0.47 0.52 0.68 1.20 0.68 0.47 0.37 1.15 0.94 1.10 0.94 0.37 0.31 11.72 11.72 0.21 1.15 0.42 0.37 0.89 0.52 0.26 0.26 0.52 0.31 0.63 0.47 0.26 0.47 0.37 0.26 7.37 7.37 0.05 0.58 0.05 0.00 1.15 1.26 0.58 0.68 1.41 1.10 1.31 0.58 0.21 0.37 0.26 0.16 9.73 9.73 0.05 0.05 0.00 0.05 0.47 1.52 0.94 1.67 1.05 1.46 1.94 1.62 0.78 0.69 0.10 0.05 I2.66 12.66 47.70 0.00 0.00 0.21 0.10 0.00 0.00 0.00 0.00 0.00 0.37 0.16 0.78 0.47 0.00 0.00 0.00 2.09 2.09 0.00 0.16 0.31 0.89 0.10 0.00 0.05 0.10 0.10 0.42 0.47 0.52 0.58 0.21 0.05 0.00 3.97 3.97 0.00 0.05 0.16 0.47 0.58 0.05 0.26 0.10 0.26 0.21 0.47 0.47 0.21 0.31 0.00 0.05 3.66 3.66 0.84 0.58 1.31 0.68 0.94 0.31 0.31 0.42 0.68 1.20 1.36 0.99 0.78 0.47 0.21 0.31 1.40 1.40 0.52 0.16 1.15 1.41 1.26 0.05 0.21 0.21 0.78 1.73 1.62 0.68 0.26 0.26 0.16 0.47 10.93 10.93 0.00 0.00 0.05 0.00 1.10 0.05 0.05 0.16 0.99 0.59 0.26 0.26 0.00 0.00 0.00 0.00 3.92 3.92 0.00 0.00 0.00 0.00 0.10 0.16 0.00 0.10 0.31 0.21 0.47 0.05 0.05 0.00 0.00 0.00 1.46 1.46 37.45 0.10 0.00 0.05 0.21 0.00 0.00 0.00 0.00 0.00 0.16 0.21 0.16 0.10 0.10 0.00 0.00 1.10 1.10 0.00 0.00 0.00 0.16 0.05 0.00 0.00 0.00 0.10 0.26 0.26 0.00 0.10 0.05 0.00 0.05 1.05 1.05 0.00 0.00 0.00 0.05 0.21 0.00 0.00 0.00 0.10 0.26 0.26 0.16 0.10 0.10 O.0 0.00 1.26 1.26 0.21 0.00 0.78 0.68 0.42 0.00 0.00 0.00 0.26 0.68 0.78 0.37 0.10 0.21 0.00 0.21 4.71 4.71 0.10 0.00 0.16 0.47 0.21 0.00 0.00 0.00 0.10 0.21 0.52 0.10 0.00 0.00 0.00 0.05 1.94 1.94 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 10.04

LaSalle Nuclear Station July-Septemer, 2002 33 ft. wind Speed and Direction 200Ft-33Ft Delta-T (F)

PEID -------------------------------- WID) DIr 1OC ES --------- STADILI! CASSIS ----------

mISSN N isE S 3 SE SSE SSSI SI WSW1 N NW N ITAL 1U Mg SU N SS MS ES TL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.21 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TOT 3.56 4.60 5.75 6.49 8.79 5.28 4.24 5.07 8.11 10.72 12.66 9.10 6.43 5.02 1.78 2.41 100.00 3.35 6.49 9.62 28.92 21.03 14.64 15.95 100.00 Wind Direction by Stability N li ENBi! SI SSE S SS SW N W hN TAL -STABILf CLASSES-0.10 0.00 0.26 0.31 0.00 0.00 0.00 0.00 0.00 0.63 0.42 0.94 0.58 0.10 0.00 0.00 3.35 Extrly Unstable 0.05 0.42 0.42 1.10 0.16 0.16 0.10 0.21 0.31 0.84 0.89 0.63 0.73 0.31 0.05 0.10 6.49 lnderately Unstable 0.10 0.31 0.47 0.84 1.31 0.26 0.31 0.37 0.89 0.89 0.99 1.10 0.84 0.73 0.05 0.16 9.62 Slightly Unstable 2.20 1.67 2.67 1.8 1.94 1.15 1.52 1.26 1.52 2.25 3.35 2.35 2.04 1.67 0.58 0.89 28.92 Neutral 0.89 1.46 1.78 2.30 2.41 0.63 0.58 0.58 1.46 2.25 2.88 1.26 0.52 0.73 0.52 0.78 21.03 Slightly Stable 0.10 0.68 0.10 0.00 2.30 1.31 0.63 0.84 2.56 2.14 1.62 0.89 0.52 0.42 0.31 0.21 14.64 Moderately Stable 0.10 0.05 0.05 0.05 0.68 1.78 1.10 1.83 1.36 1.73 2.51 1.94 1.20 1.05 0.26 0.26 15.95 Extremely Stable Wind Direction by Wind Speed NI ME RE ISE SSSS SS SW WSW NW 1NNW TL -ID SP SSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CALM 0.37 0.31 0.16 0.10 0.26 0.31 0.26 0.31 0.26 0.10 0.26 0.37 0.73 0.26 0.21 0.31 4.60 < 3.5 mph 1.41 3.35 1.41 1.26 3.56 4.34 3.09 3.66 4.08 3.82 5.49 4.18 2.93 3.03 1.15 0.94 47.70 3.6 - 7.5 qph 1.36 0.94 3.19 3.56 4.08 0.63 0.89 1.10 3.14 5.13 4.81 3.77 2.35 1.26 0.42 0.84 37.45 7.6 - 12.5 ph 0.42 0.00 0.99 1.57 0.89 0.00 0.00 0.00 0.58 1.57 2.04 0.78 0.42 0.47 0.00 0.31 10.04 12.6 - 18.5 ph 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.10 0.05 0.00 0.00 0.00 0.00 0.00 0.21 18.6 - 24.5 mph 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 > 2.5 mph

LSalle uclear Station July-Septeuber, 2002 375 ft. ind Speed and Directin 375Ft-33kt Delta-T F)

Nmober of tservatims 2208 Values are Percent Occe

. .... ---------- W DI E............ CI DSSES

,.VIE W .. NW . . --------- SUBTh aASSES ----------

I m Is 7m I E aSE E S 8W SW w I w VW ,NM I N Su SS lS S 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 0.00 0.00 o.e0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.05 0.00 0.00 0.05 0.00 0.05 .0.00 0.00 0.00 0.05 0.00 0.00 0.27 0.27 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.18 0.18 0.05 0.14 0.00 0.00 0.05 0.00 0.09 0.00 0.14 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.50 0.50 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.50 0.59 0.72 0." 0.59 0.72 0.77 0.68 0.77 0.72 0.36 0.59 1.13 0.45 0.36 0.27 9.92 9.92 0.14 0.05 0.18 0.14 0.09 0.09 0.05 0.09 0.18 0.14 0.14 0.09 0.18 0.18 0.18 0.18 2.08 2.08 0.14 0.27 0.11 0.23 0.14 0.14 0.09 0.00 0.14 0.27 0.23 0.41 0.23 0.36 0.05 0.00 2.81 2.81 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.18 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.32 0.32 15.13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.14 0.05 0.00 0.00 0.00 0.00 0.18 0.09 0.05 0.14 0.00 0.00 0.00 0.68 0.68 0.91 1.49 0.91 1.72 1.36 0.82 0.63 0.63 0.72 0.68 1.31 1.77 1.04 1.22 0.12 0.45 16.49 16.49 0.41 0.18 0.14 0.77 0.72 0.45 0.23 0.23 0.41 0.32 0.18 0.50 0.27 0.00 0.23 0.09 5.12 5.12 0.18 0.14 0.05 0.32 0.27 0.32 0.09 0.27 0.32 0.14 0.45 0.41 0.32 0.54 0.23 0.05 4.08 4.08 0.05 0.05 0.00 0.00 0.00 0.00 0.05 0.09 0.14 0.05 0.09 0.05 0.09 0.00 0.05 0.00 0.68 0.68 27.04 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.09 0.09 0.00 0.00 0.18 0.18 0.00 0.00 0.00 0.00 0.00 0.00 .0.05 0.54 0.23 0.05 0.05 0.00 1.27 1.27 0.45 0.59 1.49 1.90 1.22 0.32 0.18 0.14 0.63 0.95 1.31 0.91 1.00 0.27 0.18 0.27 11.82 11.82 0.41 0.54 1.13 2.67 0.95 0.50 0.32 0.05 0.50 0.36 0.50 0.59 0.23 0.41 0.63 0.41 10.19 10.19 0.14 0.05 0.09 0.32 0.27 0.32 0.27 0.36 0.36 0.14 0.27 0.36 0.27 0.72 0.36 0.05 4.35 4.35 0.00 0.00 0.00 0.00 0.00 0.00 0.41 0.91 0.09 0.05 0.32 0.32 0.05 O.00 0.14 0.00 2.26 2.26 29.98

aSalle Nuclear Statim July-Septaeer, 2002 375 ft. ind Speed d Direction 375Ft-33Ft Delta-T (F)

PE ) ------------------------ KM1 DIRECT'ION CLASSM ------------------ --------- STABILIT CSSES ----------

IASS NE R S 5 8SS S SSW WSW W W WIL EU M Su 'I SS Ms iS T 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.14 0.00 0.00 0.00 0.00 0.00 0.32 0.32 0.36 0.00 1.00 0.82 0.23 0.05 0.05 0.09 0.50 1.22 1.27 0.41 0.18 0.32 0.05 0.09 6.61 6.61 0.18 0.14 0.45 0.41 0.82 0.14 0.09 0.14 0.45 0.54 1.00 0.41 0.14 0.09 0.14 0.18 5.30 5.30 0.00 0.00 0.00 0.00 0.45 0.59 0.32 0.09 0.32 0.63 0.91 0.32 0.27 0.23 0.00 0.18 4.30 4.30 0.14 0.00 0.00 0.00 0.00 0.18 0.14 0.41 0.27 0.45 0.32 0.05 0.09 0.00 0.00 0.05 2.08 2.08 18.61 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.05 0.00 0.00 0.09 0.05 0.00 0.00 0.00 0.23 0.36 0.36 0.09 0.00 0.00 0.00 0.14 1.36 1.36 0.05 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.18 1.31 1.18 0.14 0.00 0.00 0.00 0.00 2.94 2.94 0.00 0.00 0.00 0.00 0.09 0.05 0.23 0.23 0.41 1.13 0.82 0.36 0.00 0.00 0.00 0.00 3.31 3.31 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.09 0.27 0.05 0.09 0.05 0.00 0.00 0.00 0.00 0.59 0.59 8.29 1 4.21 .26 6.57 10.42 7.52 4.71 4.03 4.57 7.20 9.87 11.41 8.42 6.07 4.89 3.44 2.40 100.00 0.00 0.09 2.36 46.47 25.82 19.34 5.93 100.00 Wind Direction by Stability N i g B S8 SE SSE S SSW S W i WN NW1 TL -STABILITY CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Extremely Unstable 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.09 Moderately Ustable 0.09 0.00 0.23 0.32 0.09 0.00 0.00 0.00 0.00 0.27 0.32 0.59 0.36 0.05 0.05 0.00 2.36 Slightly Unstable 2.26 2.72 4.12 5.25 3.49 1.90 1.63 1.59 2.85 3.99 4.62 3.76 3.35 2.31 1.40 1.22 46.47 Neutral 1.18 0.91 1.95 3.99 2.67 1.18 0.72 0.50 1.72 2.67 2.99 1.72 0.91 0.68 1.18 0.86 25.82 Slightly Stable 0.50 0.59 0.27 0.86 1.27 1.40 1.09 0.95 1.68 2.36 2.67 1.86 1.09 1.86 0.63 0.27 19.34 Moderately Stable 0.18 0.05 0.00 0.00 0.00 0.23 0.59 1.54 0.95 0.59 0.82 0.45 0.32 0.00 0.18 0.05 5.93 Eztremely Stable Rind Direction by Wind Speed NNE I EB 8ESSB SSSS S W WNW W M TOTAL -WIND SPEE CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CALM 0.05 0.18 0.05 0.05 0.09 0.00 0.14 0.05 0.14 0.09 0.00 0.00 0.09 0.05 0.00 0.00 0.95 ( 3.5ph 0.77 0.91 1.04 1.04 0.82 0.95 0.91 0.82 1.27 1.13 0.72 1.09 1.63 1.00 0.59 0.45 15.13 3.6 - 7.5 mph 1.54 1.86 1.13 2.94 2.40 1.59 1.00 1.22 1.59 1.36 2.13 2.76 1.86 1.77 1.31 0.59 27.04 7.6 - 12.5 mph 1.00 1.18 2.90 5.07 2.45 1.13 1.18 1.45 1.59 1.49 2.45 2.76 1.81 1.45 1.36 0.72 29.98 12.6 - 18.5 mph 0.77 0.14 1.45 1.22 1.54 0.95 0.59 0.72 1.54 2.90 3.62 1.18 0.68 0.63 0.18 0.50 18.61 18.6 - 24.5 mph 0.09 0.00 0.00 0.09 0.23 0.09 0.23 0.32 1.09 2.90 2.49 0.63 0.00 0.00 0.00 0.14 8.29 >24.5mph

aale hlear Statim October-Dcter, 2002 33 ft. ind Speed and DirectiM 200Ft-33Ft DeltaT ()

1umber of bservatioms 2207 Values are Percent Occuneace

  • ---------- ID DIC a .SS.S ---------

smn mm ----------

I3M E1 I ESSSSSS S U IWN IIH Ew TL 11 U Su I - ss S SIsTaL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.14 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.09 0.05 0.05 0.09 0.18 0.05 0.00 0.77 0.77 0.05 0.00 0.05 0.00 0.05 0.00 0.09 0.05 0.05 0.05 0.00 0.05 0.14 0.05 0.09 0.00 0.68 0.6 0.09 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.00 0.05 0.05 0.36 0.36 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.05 0.00 0.05 0.00 0.18 0.18 1.99 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.05 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.00 0.00 0.00 0.05 0.05 0.05 0.05 0.41 0.41 1.36 1.36 0.32 0.41 0.27 0.18 0.09 0.09 0.05 0.18 0.36 0.36 0.23 0.82 0.36 0.77 7.20 7.20 1.68 1.36 0.27 0.14 0.32 0.27 0.23 0.14 0.14 0.36 0.18 0.32 0.50 0.50 0.59 0.59 7.57 7.57 0.09 0.18 0.00 0.00 0.18 0.50 0.27 0.23 0.14 0.27 0.41 0.32 0.50 0.68 0.41 0.23 4.40 4.40 0.00 0.00 0.00 0.00 0.50 0.36 0.41 0.77 0.45 0.63 0.86 0.14 0.54 0.59 0.05 0.00 5.30 5.30 24.92 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.09 0.14 0.00 0.00 0.00 0.00 0.00 0.50 0.50 0.18 0.09 0.05 0.00 0.00 0.23 0.00 0.00 0.00 0.09 0.32 0.09 0.09 0.09 0.14 0.23 1.59 1.59 2.08 1.68 1.59 0.68 0.77 0.27 0.09 0.05 0.00 0.41 1.36 1.27 1.45 1.45 1.36 2.58 17.08 17.08 0.68 0.14 0.23 0.23 0.86 0.18 0.23 0.14 0.68 0.95 0.95 0.45 0.86 1.18 0.77 0.72 9.24 9.24 0.00 0.00 0.00 0.00 0.14 0.14 0.09 0.09 0.32 0.50 1.95 0.50 1.31 0.14 0.27 0.05 5.48 5.48 0.00 0.00 0.00 0.00 0.09 0.32 0.05 0.00 0.18 1.63 1.63 1.72 0. 0.18 0.14 0.00 6.62 6.62 40.60 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 O.00 0.60 0.00 0.00 0.00 0.09 0.09 0.00 0.00 0.00 0.00 0.00 0.00, 0.00 0.09 0.00 0.05 0.00 0.09 0.05 0.14 0.00 0.05 0.45 0.45 3SU 0.14 0.00 0.00 0.05 0.00 0.05 0.00 0.09 0.00 0.00 0.18 0.18 0.32 0.09 0.23 0.27 1.59 1.59

-I 0.36 0.00 0.82 0.86 1.36 0.14 0.05 0.18 0.27 0.32 0.68 0.63 1.40 1.95 1.04 1.86 11.92 11.92 1Ss 0.00 0.00 0.09 0.09 0.68 0.14 0.18 0.09 1.00 0.82 1.13 0.68 1.31 0.59 0.14 0.00 6.93 6.93 0.00

'is 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,05 0.23 0.32 0.91 0.27 0.36 0.00 0.00 0.00 2.13 2.13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.14 0.00 0.00 0.00 0.00 0.27 0.27 23.38

LaSalle Nuclear Station October-Decter, 2002 33 ft. W Spee and Direction 200?t-33Ft Delta-T ()

3PM ----------------- WND DIRETON CLASSE------------------ SMhILMT CLASSES---- -

NoB RNgE B SA SE SSE S SS1SESW Ws WNw m HU muSu N S Ss mmA 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00o0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.00 0.00 0.00 0.00 0.14 0.14 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.18 0.14 0.14 0.00 0.00 0.00 0.00 0.50 0.50 0.09 0.00 0.05 0.41 0.41 0.36 0.00 0.05 0.09 0.27 0.18 0.18 0.86 0.23 0.27 0.45 3.90 3.90 0.00 0.00 0.00 0.00 0.00 0.18s 0.09 0.05 0.32 0.59 0.72 0.14 0.54 0.50 0.00 0.00 3.13 3.13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.09 0.00 0.00 0.00 0.00 0.00 0.23 0.23 0.00 -0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 7.88 Ea 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3 NU0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 r SD 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.00 0.18 0.00 0.09 0.00 0.09 0.14 0.63 0.63 2SS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.00 0.00 0.00 0.18 0.23 0.00 0.00 0.59 0.59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4EM 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.22 Mr 7.07 4.94 3.44 2.90 5.66 3.40 1.86 2.49 4.26 8.11 12.60 7.84 11.64 9.61 6.16 8.02 100.00 0.18 1.13 4.08 41.50 28.14 12.60 12.37 100.00 Mind Direction by Stability N iBBHE B ESSE S SW S WSW m NW TAL -STABILITY CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.18 Extrenely Unstable 0.14 0.00 0.00 0.00 a.00 0.00 0.00 0.18 0.05 0.14 0.23 0.14 0.05 0.14 0.05 0.05 1.13 Moerately Unstable 0.41 0.09 0.05 0.05 0.05 0.27 0.00 018 0. 05 0.27 0.63 0.1 0.45 0.23 0.41 0.54 4.08 Slightly Unstable 3.94 3.17 2.76 2.36 2.81 1.04 0.23 0.41 0.50o 1.27 2.81 2.49 4.12 4.62 3.17 5.80o 41.50 Neutral 2.40 1.50 0.63 0.45 1.90 0.77 0.82 0.54 2.27 2.76 2.99 1.63 3.53 3.04 1.59 1.31 28.14 Slightly Stable 0.18s 0.18 0.00 0. 05 0.32 0.63 0.36 0.36 0.77 1.3 3.35 1.18 2.22 0.82 0.72 0.32 12.60 Moderately Stable 0.00 0.00 0.00 0.00 0.59 0.68 0.45 0.7 0.63 2.40 2.58 1.99 1.27 0.77 0.23 0.00 12.37 Extremely Stable NW Direction by Wind Speed N N is m I S SSWSWS I WNgW1TAL -IND SPEN CLASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CAL 0.18 0.14 0.05 0.05 0.05 0.09 0.09 0.05 0.05 0.14 0.14 0.18 0.32 0.23 0.23 0.05 1.99 <3.5 Mph 3.22 2.90 0.59 0.54 1.27 1.31 1.00 1.31 0.82 1.45 1.81 1.13 1. 81 2.63 1.50 1.63 24.92 3.6 - 7.5mph 3.08 1.90 1.86 0.91 1.86 1.13 0.45 0.36 1.22 3.76 6.34 4.03 4.40 3.04 2.67 3.58 40.60 7.6 -12.5 mph 0.50 0.00 0.91 1.00 2.04 0.32 0.23 0.54 1.50 1.68 2.90 1.99 3.44 2.76 1.40 2.17 23.38 12.6 - 18.5 mph 0.09 0.00 0.05 0.41 0.45 0.54 0.09 0.09 0.50 1.09 1.22 0.50 1.40 0.72 0.27 0.45 7.88 18.6 -24.5 mph 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.18 0.00 0.18 0.00 0.27 0.23 0.09 0.14 1.22 >24.5 mph

LSalUe Iuclear Station OctceDc , 2002 375 ft. Vind Speed and Directio 375Ft-331t Delta-T (1) ltuber of Obsevations - 2206 Valies are Perct Ocmrmece SPeD --------------------------------- W DDIC O SES --------- ..--------------------- --------- SUBI mm ----------

WASS I INK B I ESE SS 8 SSW S W n IN ON TL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.o 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.0 0.05 0.00 0.00 0.09 0.05 0.05 0.36 0.36 0.09 0.09 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.27 0.27 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.06 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.63 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.d0 0.00 0.00 0.00 0.59 0.27 0.14 0.14 0.14 0.09 0.00 '0.14 0.00 0.09 0.14 0.18 0.36 0.23 0.41 0.32 3.22 3.22 0.14 0.00 0.14 0.00 0.09 0.05 0.23 0.05 0.00 0.05 0.23 0.05 0.05 0.00 0.00 0.18 1.22 1.22 0.05 0.00 0.00 0.00 0.05 0.14 0.00 0.00 0.05 0.05 0.00 0.05 0.00 0.05 0.00 0.00 0.41 0.41 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.09 0.00 0.00 0.00 0.00 0.23 0.23 5.08 0.O0 0.00 0.40 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.OD 0.00 0.00 0.00 0.00 0.00 0.O0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.90 1.13 0.82 0.59 0.50 0.41 0.14 0.14 0.00 0.41 0.77 0.45 0.36 0.63 1.00 1.09 10.34 10.34 0.27 0.63 0,45 0.23 0.41 0.23 0.05 0.14 0.05 0.14 0.09 0.27 0.50 0.27 0.18 0.32 4.22 4.22 0.00 0.05 0.00 0.00 0.00 0.14 0.09 0.18 0.09 0.23 0.23 0.14 0.23 0.05 0.23 0.27 1.90 1.90 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.14 0.09 0.32 0.14 0.00 0.05 0.00 0.05 O.8 0.12 17.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.O0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 1.72 1.41 1.99 1.09 0.77 0.14 0.09 0.27 0.14 0.54 1.50 1.18 1.59 1.22 1.45 1.31 16.41 16.41 1.04 0.82 0.63 0.05 0.27 0.23 0.00 0.09 0.09 0.36 0.36 0.27 0.54 0.68 0.54 0.63 6.62 0.18 0.05 0.00 0.00 0.00 0.18 0.14 0.14 0.18 0.36 0.50 0.23 0.36 0.77 0.41 0.41 3.90 3.90 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.09 0.00 0.18 0.09 0.09 0.18 0.09 0.00 0.27 1.13 1.13 28.15

Laaulle Nuclear Statim ctober-Decerber, 2002 375 ft. Wind Speed and Directio 375Ft-33Ft Delta-T (F)

PM ----------------------- NM DIRECYON CUSSE ------------------ --------- SILrIT CUSSS ----------

1ASS I N s Be I ESE SE SSE S W SWV W NW mm U uSU I SS Ss1KsAm EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1 0.63 0.14 0.77 0.68 1.04 0.1I 0.05 0.23 0.05 0.18 0.73 0.45 1.50 1.54 1.90 1.27 11.29 11.29

'SS 0.45 0.05 0.18 0.05 0.32 0.09 0.18 0.23 0.36 0.45 0.95 0.18 0.41 1.09 1.18 0.36 6.53 6.53 MS 0.00 0.00 0.00 0.00 0.00 0.23 0.36 0.05 0.09 0.45 0.54 0.36 0.59 0.50 0.45 0.05 3.67 1.67 iS 0.00 0.00 0.00 0.00 0.00 0.05 0.23 0.05 0.05 0.32 0.41 0.36 0.14 0.18 0.00 0.00 1.77 1.77 23.25 E 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

KU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ISU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1 0.14 0.00 0.05 0.41 0.77 0.45 0.00 0.14 0.41 0.63 0.68 0.36 1.00 0.23 0.91 0.63 6.80 6.80

!SS 0.05 0.00 0.00 0.00 0.18 0.18 0.27 0.32 1.00 2.22 2.31 0.77 2.18 1.22 0.27 0.09 11.06 11.06 INS 0.00 0.00 0.00 0.00 0.00 0.18 0.14 0.18 0.18 0.77 1.77 0.77 1.36 0.50 0.00 0.00 5.85 5.85 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.05 0.18 0.09 0.32 0.95 0.05 0.09 0.00 0.00 1.90 1.90 25.61 TOT 7.30 4.62 5.17 3.26 4.58 2.99 2.27 2.49 3.08 7.71 12.06 7.34 11.38 9.47 8.98 7.30 100.00 0.00 0.00 0.09 48.41 29.92 15.73 5.85 100.00 Wd Directio by Stability INN B BI E SE SS3S SS SN S R N NNW 7A -STABILr CASSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Extremely Ustable 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Moderately Unstable 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.09 Slightly nstable 5.03 2.95 3.76 2.90 3.26 1.27 0.27 0.91 0.59 1.86 3.85 2.63 4.81 3.94 5.71 4.67 48.41 Heutral 2.04 1.59 1.41 0.36 1.27 0.77 o.73 0.82 1.54 3.22 3.94 1.54 3.67 3.26 2.18 1.59 29.92 Slightly Stable 0.23 0.09 0.00 0.00 0.05 0.86 0.73 0.54 0.59 1.86 3.04 1.54 2.54 1.86 1.09 0.73 15.73 Moderately Stable 0.00 0.00 0.00 0.00 0.00 0.09 0.54 0.18 0.36 0.73 1.22 1.63 0.36 0.41 0.00 0.32 5.85 xtremely Stable Wind Direction by Wind Speed I NEI RR E RS SE SSSI S SRWW m WI NNW -WIND SPED CSSES-0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CAL 0.14 0.09 0.00 0.05 0.05 0.05 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.09 0.05 0.05 0.63 c 3.5 h 0.77 0.27 0.27 0.14 0.27 0.27 0.23 0.18 0.05 0.23 0.45 0.36 0.41 0.27 0.41 0.50 5.08 3.6 - 7.5 ph 2.18 1.81 1.27 0.82 0.91 0.77 0.32 0.45 0.27 0.86 1.41 1.00 1.09 1.00 1.41 1.72 17.27 7.6 - 12.5 iph 2.95 2.27 2.63 1.13 1.04 0.59 0.32 0.63 0.41 1.50 2.45 1.77 2.67 2.77 2.40 2.63 28.15 12.6- 18.5 ph 1.09 0.18 0.95 0.73 1.36 0.50 0.82 0.54 0.54 1.41 2.63 1.36 2.63 3.31 3.54 1.68 23.25 18.6 - 24.5 ph 0.18 0.00 0.05 0.41 0.95 0.82 0.59 0.68 1.77 3.72 5.08 2.86 4.58 2.04 1.18 0.73 25.61 >24.5 ah

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2002)

APPENDIX A OFFSITE DOSE CALCULATION MANUAL

APPENDIX L OFFSITE DOSE CALCULATION MANUAL (ODCM)

LASALLE ANNEX

LASALLE Revision 5 November 2002 LASALLE ANNEX INDEX CHAPTER 10 Revision 5 P:cupgdrapproved'Xdcm'Is10Or5doc 104

LASALLE Revision 5 November 2002 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENTAND MONITORING Table of Contents NUMBER PAGE 10.1 AIRBORNE RELEASES 1

1. System Description 1
1. Condenser Offgas Treatment System 1
2. Ventilation Exhaust Treatment System 2
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
5. Turbine Building Trackway 3
3. Alarm and Trip Setpoints 4
1. Setpoint Calculations 4
1. Reactor Building Vent Effluent Monitor 4
2. Condenser Air Ejector Monitors 4
3. Station Vent Stack Effluent Monitor 4
4. Standby Gas Treatment Stack Monitor 5
2. Release Limits 5
3. Release Mixture 6
4. Conversion Factors 6
5. HVAC Flow Rates 6
4. Allocation of Effluents from Common Release Points 6
5. Dose Projections 6 10.2 LIQUID RELEASES 6
1. System Description 6
1. Radwaste Discharge Tanks 7
2. Cooling Pond Blowdown 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 7 P:4pocupgapprovedodn=Us10r5.doc 10i4

LASALLE Revision 5 November 2002 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENTAND MONITORING Table of Contents (Cont'd)

NUMBER PAGE

3. Alarm and Trip Setpoints ................. 7
1. Setpoint Calculations ................................... .. 7
1. Liquid Radwaste Effluent Monitor ....................................... 7
2. Service Water Effluent Monitors ....................................... 8
3. RHR Heat Exchanger Cooling Water Monitors ...................................... 8
2. Discharge Flow Rates ....................................... 9
1. Release Tank Discharge Flow Rate ....................................... 9
3. Release Umits.................................................................................................... 10
4. Release Mixture ................. 10
5. Conversion Factors ................. 10
6. Liquid Dilution Flow Rates .. 10
4. Allocation of Effluents from Common Release Points . . ........................10
5. Projected Doses for Releases ....................................... 10 10.3 SOUDIFICATION OF WASTEIPROCESS CONTROL PROGRAM .. .. ......... 10 P:,rocupUsrvmdW s15.doc 10-i1

LASALLE Revision 5 November 2002 CHAPTER 10 LIST OF TABLES NUMBER PAGE 10-1 Assumed Composition of the LaSalle Station Noble Gas Effluent ........................ 10-11 LIST OF FIGURES NUMBER PAGE 10-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram ....................... 10-12 10-2 Simplified Liquid Radwaste Processing Diagram.....................................................10-14 10-3 Simplified Liquid Effluent Flow Diagram .................................................. 10-15 10-4 Simplified Solid Radwaste Processing Diagram.......................................................1-16 P~pmwpgbappvvtd"d=Ms1r5.doc 10iv

LASALLE Revision 5 November 2002 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENTAND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified gaseous radwaste and gaseous effluent flow diagram are provided in Figure 10-1.

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

Exfiltration to the environment from the Turbine Building has been identified at times of positive pressure In the Turbine Building. Within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of the turbine building being at positive pressure continuous air sampling shall be in place in the south Turbine Building trackway to monitor releases through this pathway. The releases through the trackway door and other potential release paths contain insignificant levels of contamination when compared to the Station Vent Stack which has a 1,000,000 cfm typical stack flow compared to the Trackway flow rate of 40,000 scfm and conservatively estimated as a total of 80,000 scfm to account for pathways other than the trackway. In addition, typical releases from LaSalle Station have not exceeded 0.02% of the 10CFR50 Appendix I dose limits. Any identified release via this pathway is a ground level release and should be considered in dose calculations. See Figure 10-1 for further information.

Waste oil burning to fuel a heat recovery system is planned to begin Inthe Fall of 1998. Sampling and analyses of each batch of oil Is required to be performed in accordance with ODCM Table 12A.1-1. The effluent will be verified to be within the instantaneous release limits prior to each batch (assuming 100% of the activity in the waste oil Is released in the gaseous effluent). The oil burning unit is located in an onsite building within the protected area. The effluent is released out the top of the building, s a ground level release, and will be quantified and considered in dose calculations.

Airborne releases to the environment may result a fire occurs in a contaminated material warehouse. In the event of a fire In a contaminated material warehouse this pathway would be considered a ground level release and should be quantified and considered In dose calculations.

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

VX===Wr0VeaWa=VS10M.GX 10-1

LASALLE Revision 5 November 2002 10.1.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radiolodine or radioactive material in particulate form in selected effluent streams by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters prior to release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figure 10-1.

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

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

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

In normal operation the low-range noble gas channel is on line and active. The mid-range channel replaces the low-range channel at a concentration of 0.01 gCi/cc png' and the high-range channel replaces the mid-range channel at a concentration of 10 ICVcc png.

The low-range and mid/high-range iodine and particulate samplers operate in a similar manner. In normal operation the low-range samplers are on line. At a concentration of 0.001 pCi/cc png the mid/high-range samplers are brought on line, and at a concentration of 0.1

+/-Ci/cc png the low-range sample pump is turned off.

No automatic isolation or control functions are performed by this monitor. Pertinent information on this monitor is provided in the LaSalle UFSAR Section 11.5.2.2.1.

10.1.2.2 Standby Gas Treatment System Effluent Monitor Monitor OPLD2J (Wide Range Noble Gas Monitor) continuously monitors the final effluent from the standby gas treatment system (SGTS) stack.

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

In normal operation the low range noble gas channel is on line and active. The mid-range channel replaces the low-range channel at a concentration of 0.01 ixCi/cc png and the high-range channel replaces the mid-range channel at a concentration of 10 g+/-C/cc png.

'To facilitate use of the wide range gas monitors on the Station Vent Stack and Standby Gas Treatment System Stack in post-accident dose assessment, the output of each is expressed in units of pseudo noble gas (png) activity. Pseudo noble gas is a fictitious radionuclide defined to have emission characteristics representative of a post-accident noble gas mix Upon decay, a pseudo noble gas nuclide emits one gamma ray with energy 0.8 MeV and one beta particle with endpoint energy 1.68 MeV and average energy 0.56 MeV.

pWogxj~dcapmbI=S1Or5.dOC 10-2

LASALLE Revision 5 November 2002 The low-range and mid/high-range Iodine and particulate samples operate in a similar manner. In normal operation, the low-range samples are on-line. At a concentration of 0.001

-LClcc png the mid/high-range samplers are brought on-line, and at a concentration of 0.1 gCicc png the low-range sample pump is turned off.

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

Pertinent information on this monitor Is provided In the LaSalle UFSAR Section 11.5.222.

10.1.2.3 Reactor Building Ventilation Monitors Monitors 1(2)DIS-NO9 continuously monitor the effluent from the Unit 1(2) reactor building.

On high alarm, the monitors automatically initiate the following actions:

A. Shutdown and Isolation of the reactor building vent system B. Startup of the standby gas treatment system C. Isolation of primary containment purge and vent lines Pertinent information on these monitors is provided in LaSalle UFSAR Section-11.52.1.1.

10.1.2A Condenser Air Ejector Monitors Monitors 1(2)DI-N002/N012 (pre-treatment) and 1(2)D18-N903AIB (post-treatment) continuously monitor gross gamma activiy downstream of the steam jet air ejector and prior to release to the main stack.

On -high-hlgh-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 11.52.12 and 11.5.2.1.3.

10.12.5 Turbine Building Trackway In order to quantify any kentified releases via the Turbine Building trackway, at times of positive pressure in the Turbine Building, airborne sampling should be continuously collected using an air sampler located within the trackway. The air sampler collecting shall begin within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of the turbine building being at positive pressure, and then continuously for as long as the turbine building remains at positive pressure. The samples collected should be counted on a weekly basis. Air sampling to Identify noble gas, iodine and particulate monitoring (either as a grab sample or continuous sampling) Is designed to ensure evaluation of releases emanating from the Turbine Building.

The curie content of any contaminated material warehouse Is maintained current by site administrative procedures. If a fire were to occur, the actual curie content of the warehouse would be used In determining the ground level release.

-Iroc~fmannmdadaidiUslk5Aoc 10-3

LASALLE Revision 5 November 2002 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 mRlhr.

10.1.3.1.2 Condenser Air Ejector Monitors Pre-Treatment Monitor The high trip setpoint is established at 1.5 times the normal full power background rate, including nitrogen-16 (N-16) to help ensure that effluents are maintained ALARA.

The high-high trip setpoint is established at c 100 Cisec per MW-thE 3AE+05 pCisec per Technical Specification 3.7.6.

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

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

(10-2)

P Qsvs xEX[RPC /ROG]+FOG P Off-gas Post-treatment Monitor Isolation Setpoint [cprS The off-gas post-treatment monitor setpoint which initiates isolation of flow of off-gas to the station vent stack.

Qs Actual Station Vent Stack High Alarm Setpoint [ILCUsec of png]

The actual high alarm setpoint of the Station Vent Stack wide range gas monitor in units of iCi/sec of png (pseudo noble gas). This is determined by using Equations 10-3 and 104 and then converting the result to units of giCisec of prg.

E Efficiency of the Off-Gas Post Treatment Monitor [cps/(uCi/sec of off gas mix)]

Rpm Response of the Station Vent Stack WRGM to Pseudo Noble Gas

[cpm per IxCi/cc of pseudo noble gas]

ROG Response of the Station Vent Stack WRGM to Off Gas [cpm per gCicc of off gas]

FOG Maximum Off-Gas Flow Rate [ccisec]

10.1.3.1.3 Station Vent Stack Effluent Monitor The high alarm setpoint for the station vent stack effluent monitor is conservatively set at or below one-half the calculated release limit calculated using the more conservative value obtained from equations 10-3 and 10-4 below. These equations yield the release limit In units of uCi/sec of the mix specified in Section 10.1.3.3. For consistency with the monitor readout,

__1 Xr5.do~~~~~LM cV-10-4

LASALLE Revision 5 November 2002 this calculated release limit is converted to units of ILCVsec of pseudo noble gas before being entered into the monitor data base.

10.1.3.1A Standby Gas Treatment Stack Monitor The high alarm setpoint for the standby gas treatment system effluent monitor Is conservatively set at or below one-half the release limit calculated using the more conservative value obtained from equations 10-3 and 10-4 below. These equations yield the release limit in units of ItClsec of the mix specified In Section 10.1.3.3. For consistency with the monitor readout, this calculated release limit Is converted to units of ILCI/sec of pseudo noble gas before being entered Into the monitor data base.

10.1.3.2 Release LUmits 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 QCIs found by solving Equations 10-3 and 10-4.

(1.11)Qts lX{fi S)i)< 500mremlyr (10 Qj {Lf1 (X IQ). 5 exp(-1 R/3600U)t +(1.11)(fi)S,) < 3000 mrem I yr '4 The summations are over noble gas radionuclides I.

Ai Fractional Radionuclide Composition:

The release rate of noble gas radionuclide divided by the total release rate of ! '

noble gas radionuclides.

at Total Allowed Release Rate, Stack (bCUsecof ODCM mix]

Release The total allowed release rate of all noble gas radionuclides released as stack releases in units of jiCVsec of the mix specified In section 10.1.3.3.

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

The remaining parameters in Equation 10-3 have the same definitions as In Equation A-8 of Appendix A. The remaining parameters In Equation 10-4 have the same-definition as In Equation A-9 of Appendix A.

Equation 10-3 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 mren*) due to noble gases released In gaseous effluents (see Section A.1.3.1 of Appendix A). Equation 10-4 Is based on Equation A-9 of Appendix A and the RETS restriction on skin dose rate (3000 mremn) due to noble gases released In gaseous effluents (see Section A.1.32 of Appendix A).

The more conservative solution from Equations 10-3 and 10-4 is used as the limiting noble gas release rate.

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

'%XDCUDdU1D~r~edO=Sir5.doc 105

LASALLE Revision 5 November 2002 10.1.3.3 Release Mixture In the determination of alarm and trip set points, the radioactivity mixture in the exhaust air is assumed to have the radionuclide composition in Table 10-1.

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

Station vent stack effluent monitor.

Calibrations compare the response of station detectors to that of a reference detector using NIST traceable sources. Conversion factors for the station detectors are obtained from the response to noble gas or solid sources.

Condenser air ejector monitor.

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

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

Standby gas treatment system monitor.

Calibrations compare the response of station detectors to that of a reference detector using NIST traceable sources. Conversion factors for the station detectors are obtained from the response to noble gas or solid sources.

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

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

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

Consequently, no allocation is normally made between the units. Instead, the entire release is treated as a single source.

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

10.2 LIQUID RELEASES 10.2.1 System Description

3pocupgdtpprovedtodcmUs1Or5.doc 10-6

LASALLE Revision 5 November 2002 A simplified liquid radwaste and liquid effluent flow diagram are provided In Figures 0-2 and 10-3.

The liquid radwaste treatment system Is designed and Installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by filter or demineralzer for the purpose of reducing the total radioactivity prior to release to the environment. The system is described In Section 11.22 of the LaSalle UFSAR.

102.1.1 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 cooling lake blowdown.

102.12 Cooling Pond Blowdown Cooling Pond Blowdown is the liquid discharge line to the Illinois River. The Cooling Pond Blowdown has a flow monitoring device as well as a compositor to meet the sampling requirements of ODCM Table 12.3.1-2.

1022 Radiation Monitors 1022.1 Liquid Radwaste Effluent Monitor Monitor ODI-K907 monitors all releases from the release tanks. On hi-hi alarm the monitor automatically Initiates closure of valves OWL067 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 11.52.3.3.

10.22.2 Service Water Effluent Mbnitors Monitors 1/(2)D18-K912 continuously monitor the service water effluent. On high alarm service water discharge may be terminated manually. No control device Is Initiated by these monitors.

Pertinent Information on these monitors is provided In LaSalle UFSAR 11.52.32.

1022.3 RHR Heat Exchanger Cooling Water Effluent Monitors Instrument channels 1/(2)D1-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 11.5.2.3A.

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 lims of RETS are not exceeded In the unrestricted area.

102.3.1.1 Liquid Radwaste Effluent Monitor The monitor setpoint Is found by solving equation 10-5 for the total Isotopic activity.

P < KX T jI (Aj/IxDWC)]x [(FdF..,YFr,

+ (10-6) ioproaiDnxXMDr0VadbodckIs1OT5.dO 10-7

LASALLE Revision 5 November 2002 P Release Setpoint [cpmJ K Z(K x x W)y/C T J [cpmnCvm

[cpmlmCimq Ki Counting efficiency for radionuclide i [cpmliCifmq W. Weighting Factor Ci Concentration of radionuclide i in the release tank. jpC~mlQ Fn Maximum Release Tank Discharge Flow Rate [9pm]

The maximum flow rate is 45 gpm.

DWC Derived Water Concentration ipCifmn of radionuclide i The concentration of radionuclide i given in Appendix B. Table 2, Column 2 to IOCFR20.1001-2402.

10 Multiplier associated with the limits specified in 12.3.1 A.

FP Dilution Fow [gpm]

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

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

%prcupgfppmedodcmUs1Or5.doc 108

LASALLE Revision 5 November 2002 102.32 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:

'.1 0 x F/I( IOxDW)] (104)

The summation Is over radionuclides 1.

0.1 Reduction factor for conservatism.

F!,= Maximum Permitted Discharge Flow Rate [gpm]

The maximum permitted flow rate from the radwaste discharge tank.

Fd Dilution Flow TgpmJ Ci Concentration of Radionuclide I In the Release Tank mLJ The concentration of radioactivity In the radwaste discharge tank based on measurements of a sample drawn from the tank.

DWCI Maximum Permissible Concentration of Radionuclide I 11CIml)

The concentration of radionuclide I given In Appendix B, Table 2, Column 2 to IOCFR20.1001-2402.

10 Multiplier associated with the limits specified In 12.3.1 A.

MF Multiplication Factor F,= < 0.5; MF 3 0.5<F,x1<5; MF-5 5 - Ft ,,X; MF 7.5 102.3.2.2 Recommended Release Tank Flow Rate.

F= F max X MF (10-7)

F'.c recommended discharge flow rate (gpm)

Fr,,. maximum permitted discharge flow rate (gpm)

MF multiplication factor.

jP=d~ftPPro 1OdC1rn'iS1Or5 oc 10-9

LASALLE Revision 5 November 2002 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).

10.2.3A Release Mixture For the liquid radwaste effluent monitor the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample isotopic analysis plus four additional radionuclides. The additional radionuclides are H-3. Fe-59, Sr-89, and Sr-90. The quantities to be added are obtained from the most current analysis for these four radionuclides.

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

10.2.3.5 Conversion Factors The readout for the liquid radwaste effluent monitor is in CPM. The calibration constant is based on the detector sensitivity to Cs-137/Ba-137 and an energy response curve.

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 Liquid releases from the Station will be allocated one half to Unit 1 and one half 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.

WomvgdsppwW~od=V310r5.doc 10-10

LASALLE Revision 5 November 2002 TABLE 10-1 Assumed Composition of the LaSalle Station Noble Gas Effluent Percent of Isotope Total Annual Release Kr-83m 4.5E-3 Kr-85m 8.OE-3 Kr-85 2.6E-5 Kr-87 2.6E-2 Kr-88 2.6E-2 Kr-89 I.7E-1 Kr-O 3.7E-1 Xe-131m 2.OE-5 Xe133m 3.8E4 Xe-133 1.IE-2 Xe-135m 3.4E-2.

Xe-135 2.9E-2 Xe-137 2.OE-1 Xe-138 1.2E-1 ip=cuW ppOdWnIs1 Or5.doc 10-11

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LASALLE Revision 5 November 2002 OFFITE DOSE CALCULAlOH MANUAL LASALLE COUNTY STATION IWMAmiWI -RURE104 I umI,%4 ~ . S1UFIRED SOam RADWAST PROCESSING DLAGRAM

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Uxocpgd8.apprwvedrdcanJs1 r5.doc 10-16

LASALLE Revision 5 November 2002 CHAPTER 11 LaSalle Annex Index Revision 5

p. oo 11r5.doc 11-i

LASALLE Revision 5 November 2002 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS CHAPTER TITLE PAGE 11 Radiological Environmental Monitoring Program 11-1 LIST OF TABLES NUMBER TnLE PAGE 11-1 Radiological Environmental Monitoring Program 11-2 LIST OF FIGURES NUMBER TITLE PAGE 11-1 Fixed Air Sampling Sites and Outer Ring TLD Locations 11-9 11-2 Inner Ring TLD Locations 11-10 11-3 Ingestion and Waterbome Exposure Pathway Sample Locations 11-11 p:Vfrocupgdappoved\odcmrs1 IrS.doc 1 1-ii

LASALL Revision 5 November 2002 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program for the environs around LaSalle Station Is given In Table 11-1.

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

p:Drocupgftpproved\x Jst Mr5.doc 11-1

LASAL.LE Revision 5 November 2002 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or SamDle SamDle or Monitorina Location Collection Freauencv of Analysis

1. Airbome Continuous sampler Radiolodine Canisters:

operation with particulate Radioiodine and a. ndicators-Near Field sample collection weekly, 1-131 analysis biweekly on Particulates or more frequently near field and control L-01, Nearsite No. 1, 1.5 mi NNW (2.4 km R) required by dust loading, samples'.

L-03, Onsite No. 3, 1.0 ml ENE (1.6 km D) and radioiodine canister L-05, Onsite No. 5, 0.3 ml ESE (0.5 km F) collection biweekly. Particulate SamDler:

L-06, Nearsite No. 6, 0.4 ml WSW (0.6 km M)

Gross beta analysis followinp weekly filter change and gamma isotopic analysis3 quarterly on composite filters by location on near field and control samples.'

b. Indicators-Far Field L-04, Rle 170, 3.2 ml E (5.1 km E)

L-07, Seneca, 5.2 mi NNE (8.4 km B)

L-08, Marseilles, 6.0 mi NNW (9.7 km R)

L-1 1, Ransom, 6.0 mi S (9.7 km J)

c. Controls L-10, Streator, 13.5 ml SW (21.7 km L) pAprocupgdfapproved~odcm\Jsi 1r5.doc

- 11-2

LALE Rev5 November 2002 Table 11-1 (Cont'd)

Radioloolcal Environimenal Monitorina Prouram Exposure Pathway Sampling or Type and Frequency and/or Samle Samole or Monitoring Location Collectlon Freouengv at Analvsis

2. Direct Radiation a. indkcatom-Inner Ring Quartaely Gamma dose on each TLD L-101-1, 0.5 ml N (0.8 km A) quarterly.

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

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

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

L-103-1, 0.7 ml NE (1.1 km C)

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

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

L-104-2, 0.8 ml ENE (1.3 km D)

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

L-105-2, 0.7 ml E .(1.1km E)

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

L-108-2, 1.4 mi ESE (2.2 km F)

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

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

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

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

L-109-1, 0.G ml S (1.0 km J)

L-109-2, 0.6 ml S (1.0km J)

L-110-1, 0.6 ml SSW (1.0 km K)

L-110-2, 0.6 ml SSW (1.0 km K)

L-111b-1, 0.8mlSW (1.3 km L)

L-1IIb-2, 0.8 ml SW (1.3 km L)

L-112-1, 0.9 mlWSW (1.4 km M) 1112-2, 0.9 ml WSW (1.4 km M)

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

L-1 13a-2, 0.8 ml W (1.3 km N)

L-114-1, 0.9 ml WNW (1.4 km P)

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

L-115-1, 0.7mlNW (1.1 km 0)

L-115-2. 0.7 ml NW (1.1 km )

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

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

PV.MxvKftppMVWMCMV8kmrs.Go 11-3 I

LAOLE Rev*lll 5 November 2002 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency antior Samole SamDle or Monitoring Location Collection Freauencv of Analysis

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

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

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

L-202-4, 3.6 ml NNE (5.8 km B)

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

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

L-204-1, 3.2 ml ENE (5.2 km D)

L-204-2, 3.2 ml ENE (5.2 km D)

L-205-1, 3.2 ml ESE (5.2 km F)

L-205-2, 3.2 ml ESE (5.2 km F)

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

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

L-206-1, 4.3 ml SE (6.9 km G)

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

L-207-1, 4.5 ml SSE (7.2 km H)

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

L-208-1, 4.5 ml S (7.2 km J)

L-208-2, 4.5 ml S (7.2 km J)

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

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

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

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

L-211-1, 4.5 mi WSW (7.2 km M)

L-211-2, 4.5 mi WSW (7.2 km M)

L-212-1, 4.0 ml WSW (6.4 km M)

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

L-213-3, 4.9 ml W (7.9 km N)

L-213-4, 4.9 ml W (7.9 km N)

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

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

L-215-3, 5.0 ml NW (8.0 km 0)

L-215-4, 5.0 ml NW (8.0 km 0)

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

L-216-4, 5.0 ml NNW (8.0 km R) p:\procupgd\approved\odcmJs 1 r.doc 11-4

LASe Revislon 5 November 2002 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program p:upgdpomMlftdVs1 lrS.doc 11-5

0 LAS9 E Revit5 November 2002 Table 11-1 (Cont'd)

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

3. Waterborne a.. Ground/Well
a. Indicators Quarterly Gamma Isotopic 3 and tritium analysis quarterly.

L-27, LSCS Onsite Well at Station L-28, Marseilles Well, 7.0 ml NW (11.3 km a)

b. Drinking Water There is no drinking water pathway within 6.2 ml (10 km) downstream of station.
c. Surface Water a. Indicator Weekly grab sample Gross beta and gamma L-40, Illinois River downstream, isotopic analysis on 5.2 ml NNW (8.4 km R) monthly composite; tritium analysis on quarterly composite.

Weekly grab sample Gross beta and gamma

d. Control a. Control isotopic analysis on monthly composite; tritium L-21, Illinois River at Seneca, analysis on quarterly 4.0 ml NE (6.4 km C) composite.

Semiannually Gamma isotopic analysis3

e. Sediments a. Indicators semiannually.

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

L-41, Illinois River downstream 4.6 mi NNW (7.4 km A) p:procupgdftpprovedodcmVY1 1r5.doc 11-6

LAS 9E Revisi November 2002 Table 11-1 (Cont'd)

Radiological Environmental Monitoring Prgram Exposure Pathway Samping or Type and Frequency and/or Samle Sample or Montorin Location Collection renuenc otAnaivsis

4. Ingestion
a. mk a. Indicators Biweekly May through Gamma isotopic8 and 1-131 October, monthly. analysis4 biweekly May November through April through October, monthly At the time of this revision, there are no dairies within 6.2 miles which consistently produce milk. November through April.
b. Controls L-42, Biros Dairy, 14.2 ml E (22.9 km E)
b. Fish a. Indicator Two times annually Gamma Isotopic analysis3 L-35, Marseilles Pool of Illinois River, on edible portions of each 6.5 m NW (10.5 km Q)

L-34, LaSalle Lake 2mlE (3.2 km E) I

b. Control L-36, Illinois River upstream of discharge, 4.3 ml NNE (6.9 km B)
c. Food Products a. Indicators Two samples from each of the four major quadrants Annually Gamma Isotopic analysis3 within 6.2 miles of the station, If available.

and 1-131 analysis each Sample locations for food products may vary based sample. I on availability and therefore are not required to be Identified here but shall be taken.

b. Controls Two samples within 9.3 to 18.6 miles of the station, ifavailable.

p~prVoup ppret s1 iir.do 11-7

LASALLE Revision 5 November 2002W Table 11-1 (Cont'd)

Radiological Environmental Monitoring Program 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 Radiation Protection Director.

2 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. If gross beta activity in air particulate samples Is greater than 10 times the yearly mean of control samples, gamma Isotopic analysis shall be performed on the individual samples.

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

4 1- 31 analysis means the analytical separation and counting procedure are specific for this radionuclide.

  • 1 .R

LASALLE Revision s November 2002 L4"5415 L4154' a L446 L.'2144 1A1343

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LASALLE Revision 5 November 2002 I as la to s xa i

  • TLD OnU+/-J BE~1 DOSE CALCULAN MAHUAL LA SALLEI COUNTI STATION FUMMID WCAN prpocupgd\approvtOdcxl1~ml 1 rS.doc 11-10

LASALLE Revision 5 November 2002 IT "W34 3S>

OFF3fE DOSE CALCULATION MANUAL

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P-%p=wVwVaM'\0ftM'lSllf5.d0c 11-11

LASALLE Revision 5 November 2002 LASALLE ANNEX INDEX CHAPTER 12 Revision 5 SPECIAL NOTE The transfer of the Radiological Effluent Technical Specifications (RETS) to the ODCM has been approved by the Nuclear Regulatory Commission in Amendments 85169.

~nwuonataoomvad~nd=1os12r5 12-i

LASALLE Revision 5 November 2002 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

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

1. Radioactive Lquid Effluent Monitoring Instrumentation 12-8
2. Radioactive Gaseous Effluent Monitoring Instrumentation 12-13 12.3 UQUID EFFLUENTS 12-19
1. Concentration 12-19
2. Dose 12-25
3. Liquid Waste Treatment System 12-27 12A GASEOUS EFFLUENTS 12-29
1. Dose Rate 12-29
2. Dose - Noble Gases 12-35
3. Dose - odine-131, odine-133, Tritium, and Radionuclides in Particulate Form 12-36
4. Gaseous Radwaste Treatment System 12-38
5. Ventilation Exhaust Treatment System 12-N39
6. Venting or Purging 12-40
7. Total Dose 12-41
8. Main Condenser 12-43 S. Dose Limits for Members of the Public 12-44 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-45
1. Monitoring Program 12-45
2. Land Use Census 12-58
3. Interlaboratory Comparison Program 12-59 12.6 REPORTING REQUIREMENTS 12-60
1. Annual Radiological Environmental Operating Report 12-60
2. Radioactive Effluent Release Report 12-61
3. Offste Dose Calculation Manual (ODCM) 12-62
4. Major Changes to Radioactive Waste Treatment Systems 12-63

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LASALLE Revision 5 November 2002 CHAPTER 12 RADIOACTIVE EFFLUENT TECHNICAL STANDARDS (RETS)

LIST OF TABLES PAGE 12.0-1 Effluent Compliance Matrix 12-2 12.0-2 REMP Compliance Matrix 12-3 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 (AC) of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste 12-20 12.3.1-2 Radioactive Liquid Waste Sampling and Analysis Program 12-21 12.4.1-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-30 12.5-1 Radiological Environmental Monitoring Program 12-48 12.5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 12-54 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-55 wn%wvi 7 12-iii

LASALLE Revision 5 November 2002 NOTE The requirements of TSR 3.0.b apply to Chapter 12.

12.0 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS Chapter 12 of the LaSalle Station ODCM Is a compilation of the various regulatory requirements, surveillances and bases, commitments and/or components of the radiological effluent and environmental monitoring programs for LaSalle Station. To assist In the understanding of the relationship between effluent regulations, ODCM equations, RETS (Chapter 12 section) and related Technical Specification requirements, Table 12.0-1 Is a matrix which relates these various components. The Radiological Environmental Monitoring Program fundamental requirements are contained within this chapter, with LaSalle specific information In Chapter 11 and a supplemental matrix In Table 12.0-2.

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LASALLE Revision 5 November 2002 TABLE 12.0-1 EFFLUENT COMPLIANCE MATRIX Regulation Dose to be compared to limit ODCM RETS Technical l Equation Specification IOCFR50 1. gamma air dose and beta air dose A-I 12.4.2 5.5.4.h Appendix I due to airborne radioactivity In A-2 effluent plume.

l.a whole body and skin dose due to A-6 N/A NIA airborne radioactivity in effluent 47 plume are reported only if certain gamma and beta air dose criteria are exceeded.

2. CDE for all organs and all four age A13 12.4.3 5.5A.I groups due to odines and particulates in effluent plume. All pathways are considered.
3. CDE for all organs and all four age A-29 12.3.2 5.5A.d groups due to radioactvity in liquid effluents.

IOCFR20 1. TEDE, totaling all deep dose A-38 12.4.9 5.5.4.c equivalent components (direct.

ground and plume shine) and committed effective dose equivalents (all pathways, both trbome and liquid-borne). CDE aluation s made for adult only g FGR 11 database.

40CFR190 1. Whole body dose (DDE) due to A-35 12A.7 5.5.4.j (now by direct dose, ground and plume reference, also shine from all sources at a station.

part of I0CFR20) 2. Organ doses (CDE) to an adult due A13 to all pathways.

Technical I. Instantaneous whole body (DDE), A-8 12A.1 5.5.4.g Specifications thyroid (CDE) and skin (SDE). dose 49 rates to an adult due to A28 radioactivity In airborne effluents.

For the thyroid dose, only 5.5A.b nhalation Is considered.

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

Technical 1. Radioactive Effluent Release Report NA 12.8.2 5.6.3 Specifications I Table 12.0-2 p.prtuftppvvedodcm s12r5 12-2

LASALLE Revision 5 November 2002 REMP Compliance Matrix Regulation Component RETS Technical

,_____________ __ .S ___________ pecification IOCFR50 Implement environmental monitoring program. 12.5.1 NIA Appendix I Section IV.B.2 10CFR5O Land Use Census 12.5.2 NIA Appendix I Section IV.B.3 10CFR5O Interlaboratory Comparison Program 12.5.3 NA Appendix I Section IV.B.2 10CFR5O Annual Radiological Environmental Operating 12.6.1 5.6.2 Appendix I Report Section IV B.2 and Technical Specifications DpVorCugaVzVaNO= Vs12Z5 1243

LASALLE Revision 5 November 2002 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 CALIBRATION shall encompass the entire channel, Including the required sensor, alarm, display, and trip..

functions, and shall Include the CHANNEL FUNCTIONAL TEST. Calibration of Instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices In the channel. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps so that the entire channel is calibrated.

12.1.3 CHANNEL CHECK - A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other Indications or status derived from independent Instrument channels measuring the same parameter.

12.1A CHANNEL FUNCTIONAL TEST - A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal Into the channel as close to the sensor as practical to verify OPERABILITY including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

12.1.5 DOSE EQUIVALENT 1-131 - DOSE EQUIVALENT -131 shall be that concentration of 1-131, (microcuries/gram), that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132. 1-133,1-134, and 1-135 actually present The thyroid dose conversion factors used for this calculation shall be those listed In Table IlIl of TID-14844, AEC 1962, Calculation of Distance Factors for Power and Test Reactor Sites;" Table E.7 of Regulatory Guide 1.109, Rev. 1. NRC, 1977; or ICRP 30, Supplement to Part 1. pages 192-212, Table titled, Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity.

12.1.6 FREQUENCY - Table 12.1-1 provides the definitions of various frequencies for which surveillances, sampling, etc. are performed unless defined otherwise. The provisions of Technical Specifications SR 3.0.2 and SR 3.0.3 are applicable to the frequencies except that they do not apply to the frequencies associated with the Radiological Environmental Monitoring Program (Section 12.5).

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

12.1.8 MEMBER(S) OF THE PUBLIC - means an individual except when that individual Is receiving an occupational dose.

12.1.9 MODE - A MODE shall correspond to any one of the inclusive combination of mode switch position, average reactor coolant temperature, and reactor pressure vessel head closure bolt tensioning specified In Table 12.1-2 with fuel in the reactor vessel.

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LASALLE Revision 5 November 2002 12.1.10 OCCUPATIONAL DOSE - means the dose received by an individual In the course of employment Inwhich the Individual's assigned duties Involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether In the possession of the licensee or other person. Occupational dose does not Include dose from background radiation as a patient from medical practices, from voluntary participation In medical research programs, or as a member of the public.

12.1.11 OPERABLE - OPERABILITY - A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when It is capable of performing its specified function(s),

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

12.1.12 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.

12.1.13 PURGE - PURGING - PURGE or PURGING 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 required to purify the confinement.

12.1.14 RATED THERMAL POWER (RTP) - RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3489 Mwt.

12.1.15 SITE BOUNDARY - The SITE BOUNDARY shall be that fine beyond which the land Is neither owned, nor leased, nor otherwise controlled by the licensee.

12.1.16 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 (free-standing).

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

12.1.18 THERMAL POWER - THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant 12.1.19 UNRESTRICTED AREA BOUNDARY - means an area, access to which is neither limited nor controlled by the licensee.

.12.1.20 VENTILATION EXHAUST TREATMENT SYSTEM - A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and Installed to reduce gaseous radiolodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing odines or particulates from the gaseous exhaust system prior to the release to the environment (such a system is rot 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.

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LASALLE Revision 5 November 2002 12.121 VENTING - VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, In such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

12.1.22 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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LASALLE Revision 5 November 2002 TABLE 12.1-1 FREQUENCY NOTATION NOTATION FREQUENCY S - Shftly At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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

W - Weekly At least once per 7 days.

M - Monthly At least once per 31 days.

o - Quarterly At least once per 92 days.

SA - Semiannually At least once per 184 days.

A - Annually At least once per 366 days.

E - Sesquiannually At least once per 18 months.

- Refueling cycle At least once per 24 months.

S/U - Startup Prior to each reactor startup.

P - Prior Prior to each radioactive release.

NA Not applicable.

Table 12.1-2 (Page 1 of 1)

MODES MODE TITLE REACTOR MODE SWITCH AVERAGE REACTOR POSITION COOLANT TEMPERATURE

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (,F )

I Power Operation RUN N/A 2 Startup Refuel(') or Startup/Hot N/A Standby

.3 Hot Shutdownl") Shutdown - >200 4 Cold Shutdown(a) Shutdown < 200 5 Refuelingm Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.

(b) One or more reactor vessel head closure bolts less than fully tensioned.

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LASALLE Revision 5 November 2002 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitorina Instrumentation ODerability Requirements 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 12.3.1A are not exceeded. The alarm trip setpoints of these channels shall be determined in accordance with the ODCM Chapter 10.

ADolicabilit. At all times, when flow Is present in the system.

Action:

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 Reguirements 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 CALIBRATION 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 during 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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LASALLE Revision 6 November 2002 TABLE 12.2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. GAMMA SCINTILLATION MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
a. Liquid Radwaste Effluent Line I 100
2. GAMMA SCINTILLATION MONITORS PROVIDING ALARM BUT NOT PROViDING AUTOMATIC TERMINATION OF RELEASE
a. Service Water System Effluent Line (Unit 1) I 101
b. Service Water System Effluent Une (UnIt 2) I 101
c. RHR Service Water (Line A) Effluent Line (Unit 1) I 101
d. RHR Service Water (Line A) Effluent Line (Unit 2) I 101
e. RHR Service Water (Line B) Effluent Une (Unit 1) I 101
f. RHR Service Water (Line 6) Effluent ine (Unit 2) I 101
3. FLOW RATE MEASUREMENT DEVICES
a. Liquid Radwaste Effluent Line I 102
b. Cooling Pond Blowdown Ppe* I 102
  • Same as River Discharge Blowdown Pipe.

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I LASALLE Revision 5 November 2002 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION .,

TABLE 12.2.1-1 (Continued)

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

a. At least two independent samples are analyzed In accordance with Section 12.3.1.B.1, 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 for principal gamma emitters and 1-131 at a lower limit of detection as specified In Table 12.3.1-2. If effluent releases continue via this pathway beyond 30 days, continue to collect and analyze samples, then explain in the next Radioactive Effluent Release Report why this noperability was not corrected within the time specified.

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 for Instrument 3a, or for known valve positions for Instrument 3b, may be used to estimate flow. Actual releases of radioactive effluent will not be initiated without an OPERABLE channel.

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ISALLE evIsion 5 November 2002 TABLE 12.2.1-2 RA DIOACTIV LIQUID EFFLUENT MONMJRING INUTRUMENTATIQN 6URVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE FUNCTIONAL CHANNEL INSTRUMENT CHECK HCK TEST CLIBRTIO

1. GAMMA SCINTILLATION MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
a. Liquid Radwaste Efuents LIne D P 0(1) B(3)
2. GAMMA SCINTILLATION MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
a. Service Water System Effluent LIne (UnIt 1) D M Q(2) B(3)
b. Servce Water System Effluent Line (Unit 2) D M 0(2) B(3)

C. RHR Servie Water (LIne A) Effluent ne (Unit 1) D M Q(2) B(3)

d. RHR Service Water (Line A) Efuent Lne (UnIt 2) D M Q(2) 6(3)
e. RHR Servce Water (Line B) Effluent Line (UnIt 1) D M 0(2) B(3)
f. RHR Service Water (LIne B) Effluent Une (Unit 2) D M Q(2) B(3)
3. FLOW RATE MEASUREMENT DEVICES
a. Liquid Radwaste Effluent Line D(4) N.A. P B
b. Coi Pond Bowdown Pipe D(4) NA a E p._12 15 .:

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LASALLE Revision 5 November 2002 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 it any of the following conditions exist

1. Instrument indicates measured levels above the alarm setpoint.
2. Loss of power.
3. Instrument alarms on downscale failure.
4. Instrument controls not set In Operate or High Voltage mode.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference radioactive standards certified by the National Institute of Standards and Technology (NIST)or using standards that have been obtained from suppliers that participate In measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, the Initial reference radioactive standards or radioactive sources that have been related to the nitial 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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LASALLE Revision 5 November 2002 12.2 INSTRUMENTATION 12.22 Radioactive Gaseous Effluent Monitoring Instrumentation Ooerabilitv Reauirements 12.2.2OA The radioactive gaseous effluent monitoring Instrumentation channels shown In Table 122.2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Section 12A..A are not exceeded. The alarmitrip setpoints of these channels shall be determined in accordance with the ODCM.

Awplicability. As shown in Table 12.2.2-1.

Action:

a. With a radioactive gaseous effluent monitoring Instrumentation channel alarmtrip setpolnt less conservative than required, Immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel Inoperable.
b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 12.2.2-1.

Surveillance Requirements 12.22.3 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown In Table 12.22-2.

Bases 12.2.2.C The radioactive gaseous effluent monitoring nstrumentation 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 nstruments shall be calculated In accordance with the procedures In the ODCM to ensure that the alarnip will occur prior to exceeding the limits of RETS.

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LASALLE Naws I Iw NWber2002 TABLE 12.2.2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTUMENT OPERABLE APPLICABILITY ACTION

1. MAIN CONDENSER OFFGAS TREATMENT SYSTEM EFFLUENT MONITORING SYSTEM
a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release 2 110 (1(2) D18-N903A, K901A, K6OIA, R601) and/or (1(2) D18-N903B, K901B, K801B. R601)
2. MAIN STACK MONITORING SYSTEM
a. Noble Gas Activity Monitor (D18-N514, R517, R518 Low Range 1
b. Iodine Sampler (Grab Sampler) I
  • 111
c. Particulate Sampler (Grab Sampler) I
  • 111
d. Effluent System Flow Rate Monitor (OFT-VRO19, 0FY-VR0I9 and 19A, OFR-VR0I9, OD18-K510, OD11-R518) 1
  • 112
e. Sampler Flow Rate Monitor (Low: 0D18-N527, 0D18-N528, 0D18-R518; t
3. CONDENSER AIR EJECTOR RADIOACTIVITY MONITOR (Prior to Input to Holdup System)
a. Nobb Gas Activity Monlitor (1(2) DIB-N002, K613, R604) I 113 (1(2) D18-N012, K600, R6805)
4. SBGTS MONITORING SYSTEM
a. Noble Gas Activity Monitor (0D18-N511. R515. R516 Low Range WRGM) I 110 or (OD18-N512, R515, R516 Mid Range WRGM)
b. Iodine Sampler (Grab Sampler) I 111
c. Particulate Sampler (Grab Sampler) I 111
d. Effluent System Flow Rate Monitor (1(2)FT-VG009, 1(2)FY-VG009, I 112 1(2)FR-VG009)
e. Sampler Flow Rate Monitor (Low: 0018-N521, 0D18-N522, 0D18-R516; I 112 Mid/Hi: 0D18-N524, 0D18-N525, OD18-R516)

'Equlpna PMt Numer (EPh) nm or montor type we provhin Wen_ ess:

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LASALLE Revision 5 November 2002 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE 12.2.2-1 (Continued)

TABLE NOTATION At all times.

During effluent releases via this pathway.

During operation of the main condenser air ejector.

    1. During operation of the SBGTS.

ACTION 110- a. For the Main Condenser Offgas Treatment System Effluent Monitoring System:

With only one channel OPERABLE, place the Inoperable channel In a tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

With no channel OPERABLE, 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 wlthn 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (See NOTE below.)

b. For the Low/Mid Range of the Main Stack Monitoring System or SBGTS Monitoring System:

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 /> at a lower limit of detection as specified in Table 12A.1-1. (See NOTE below.)

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. (See NOTE below.)

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 />. (See NOTE below.)

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 Mode 2 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: For Actions 110 through 112 above, effluent releases may continue beyond the 30 days as lor as the applicable sampling requirements are met. Explain in the next Radioactive Effluent Release Report why the Inoperability was not corrected within the time specified.

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A Revision November 2002 TABLE 12.2.2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS OPERATIONAL CHANNEL CONDITIONS FOR CHANNEL SOURCE FUNCTIONAL CHANNEL WHICH SURVEIL-INSTRUMENT CHECK CHECK TEST CALIBRATION LANCE REQUIRED

1. MAIN CONDENSER OFFGAS TREATMENT SYSTEM EFFLUENT MONITORING SYSTEM
a. Noble Gas Activity Monitor -

Providing Aiarm and Automatic Terminatlon of Release D D 0(1) B(3)

2. MAIN STACK MONITORING SYSTEM
a. Noble Gas Activity Monitor D M Q(4) B(3)
b. Iodine Sampler W NA NA NA
c. Particulate Sampler W NA NA. NA.
d. Effluent System Flow Rate Monitor D NA. Q B
e. Sampler Flow Rate Monitor D NA Q B
3. CONDENSER AIR EJECTOR RADIOACTIVITY MONITOR
a. Noble Gas Activity Monitor D M Q(2) B(3)
4. SBGTS MONITORING SYSTEM
a. Noble Gas Activity Monitor D M Q(4) B(3)
b. Iodine Sampler W NA. NA NA
c. Particulate Sampler W NA NA. NA
d. Effluent System Flow Rate Monitor. D NA a B
e. Sampler Flow Rate Monitor D NA a B DC zr:Ug 'Wrnsia2A 12-16

LASALLE Revision 5 November 2002 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE 122.2-2 (Continued)

TABLE NOTATION At a times.

During effluent releases via this pathway.

During operation of the main condenser air ejector.

    1. During operation of the SBGTS.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic Isolation capability of this pathway for the following conditions:

- 1. Upscale.

2. Inoperative.
3. Downscale.

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

1. Upscale.
2. Inoperative.
3. Downscale.

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

DProCda0D tso0oan'IS1z1M 12-17

LASALLE Revision 5 November 2002 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE 12.2.2-2 (Continued)

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

1. Instrument Indicates measured levels above the alarm setpoint.
2. Loss of Counts p:procupgdappmvedkx)Vs12rS 12-18

LASALLE Revision 5 November 2002 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Operability Reauirements 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 radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble aases, the concentration shall be limited to the concentrations specified In Table 12.3.1-1.

Applicablitvy At all times.

Action:

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

Surveillance Reauirements 12.3.1 .B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 12.3.1-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release Is maintained within the limits of Section 12.3.1A.

12.3.1.B.2 Post-release analyses of samples composited from batch releases shall be performed In accordance with Table 12.3.1-2. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the 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 limits of Section 12.3.1 A 12.3.1.B.4 Identify outside temporary liquid holdup tanks within the site and restrict the quantity of radioactive material contained in specified tanks to provide assurance that in the event of an uncontrolled release of the tanks contents, the resulting concentrations would be less than the limits of Section 12.3.A1A Refer to LaSalle Technical Specification 5.5.9.b.

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 IOCFR20.1001-2402. 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 IIA design objectives of Appendix , 10 CFR 50, to an Individual, and (2) the limits of 10 CFR 20.1301 to the population. In addition, this limit Is associated with 40 CFR 141 which states concentration limits at the nearest downstream potable water supply.

piV=ocpgdtppvmd~odanis125 12-19

LASALLE Revision 5 November 2002 TABLE 12.3.1-1 ALLOWABLE CONCENTRATION (AC} OF DISSOLVED OR ENTRAINED NOBLE GASEC RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE AC(pCmll?

Kr 85 m 2E-4 85 SE-4 87 4E-5 88 9E-5 Ar 41 7E-5 Xe 131 m 7E-4 133m 5E-4 133 6E-4 135m 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, pw = 1.0 gm/cm 3 , and PP, = 1.0.

n=nDvsnrfaDnnr bel12r5 12-20

LASALLE Revision 5 November 2002 TABLE 12.3.1-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID SAMPLING MINIMUM TYPE OF LOWER UMIT OF RELEASE TYPE FREQUENCY ANALYSIS ACTiViTY DETECTION (LLD)

FREQUENCY ANALYSIS (PIClmi' A. Batch Waste P P Principal Gamma 5x10 Release Each Batch Each Batch Emittersi Tanksd 1-131 1x10 4, P M Dissolved and 1x104 One Batch/M Entrained Gases (Gamma Emitters)

P M H-3 1x10 Each Batch Composite Gross Alpha 1xtO7 P a~ Sr-89, Sr-90 5x10 Each Batch Compositeb Fe-55 1x104 B. Continuous Continuousc W Principal Gamma 5x10 Releases! Compositec Emitters Cooling Pond Blowdown 1-131 1x104 M M Dissolved and 1x104 Grab Sample Entrained Gases (Gamma

._____ _ Emitters)

Continuous" M H-3 1xi Composte'

.___________ Gross Alpha 1xlO 7 ContinuousC Q Sr89, Sr-90 5x1o4 Compositec F-55 xi10,6 DnhaDcLmDarovedla=m'S1ZgM 12-21

LASALLE Revision 5 November 2002 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE 12.3.1-2 (Continued)

TABLE NOTATION

a. The LLD Is the smallest concentration of radioactive material In a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a rear signal.

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

4.66 sb LLD E . V . 2.22x10 . Y . exp (-Xt)

Where:

LLD Is the a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

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

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

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

2.22x106 is the number of transformations per minute per microcune, 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 sb 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.

Atemate LLD Methodoloay An alternate methodology for LD determination follows and Is similar to the above LLD equation:

(2.71 + 4.654B). Decay LLD =

E q b Y t (2.22 x 10) p:N==VWupgdVapOVefd=rnJ3lZI 12-22

LASALLE Revision 5 November 2002 TABLE 12.3.1-2 (Continued}

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATIONS Where:

B = background sum (counts)

E = counting efficiency q = sample quantity (mass or volume) b = abundance (f applicable)

Y= fractional radiochemical yield or collection efficiency (if applicable) t= count time (minutes) 2.22 x 10 = number of disintegrations per minute per microCurle 2.71 + 4.65.1B = 1c2 + (2k 2 -4B), and k = 1.645 (k-value of the t statistic from the single-tailed t distribution at a significance level of 0.95 and infinite degrees of freedom. This means that the LLD result represents a 95% detection probablity with a 5% probability of falsely concluding that the nuclide Is present when It Is not or that the nuclide Is not present when It Is.)

Decay= eAt XRT/(1-eT)D.T. /(1-Td)] If applicable A = radioactive decay constant (units consistent with At, RT and Td)

At = delta to, or the elapsed time between sample collection or the midpoint of sample collection and the time the count is started, depending on the type of sample (units consistent wih A)

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

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

The LLD may alternately be determined using Installed radioanalytical software, If available. In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (i.e.

during sample collection, from sample collection to start of analysis, and during counting),

this alternate method will result In a more accurate determination of the LLD.

It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement ppgtpo WW1 Vs12r5 12-23

LASALLE Revision 5 November 2002 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE 12.3.1-2 (Continued)

TABLE NOTATION

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 sample employed results in a specimen which is representative of the liquids released.
c. To be representative of the quantities and concentrations of radioactive materials In liquid effluents, samples shall be collected in proportion to the rate of flow of the effluent stream. Prior to analyses, a samples taken for the composite shall be thoroughly mixed In 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 analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
e. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an Input flow during the continuous release.
f. The principal gamma emitters for which the LLD specification applies exclusively are the 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.

p:'procugdanWpprvedxdUs¶5 12-24

LASALLE Revision 5 November 2002 12.3 LIQUID EFFLUENTS

.12.32 Dose Ooerabilitv Requirements 12.3.2A 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 or equal to 3 mrern to the total body and to less than or equal to 10 mrem 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, prepare and submit to the Commission, pursuant to 10CFR5O, Appendix I, Section VA, a 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 during 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. The Report shall also include the radiological impact on finished drinking water supplies at the nearest downstream drinking water source. The Report Is due to the NRC within 30 days from the end of the quarter in which the release occurred.

Surveillance Requirements 12.3.2.B Dose Calculations- Cumulative dose contributions 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 This requirement is provided to implement the requirements of Sections 11A, IA and IVA of Appendix , 10 CFR Part 50. The Umiting Condition for Operation implements to guides set forth In Section IA of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IVA of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept as low as Is reasonably achievable.0 Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there Is reasonable assurance that the operation of the facility will not result In radionucide concentrations In the finished drinking water that are In excess of the requirements of 40 CFR 141. The dose calculations In the ODCM Implement the requirements In Section IlA of Appendix I that conformance with the guides of Appendix I 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 for calculating the doses due to the actual release rates of radioactive materials In liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the nciodnloovd2dmiS1t 12-26

LASALLE Revision 5 November 2002 Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix ,' 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 ," April 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.

_ .~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

nfnrmainroad=352 12-26

LASALLE Revision 5 November 2002 12.3 LIQUID EFFLUENTS 12.3.3 Liquid Waste Treatment System ODerability Reauirements 12.3.3A The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in iquid 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 02 mrem to any organ.

AoolicabliW. 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, prepare and submit to the Commission within 30 days a Special Report which includes the following information:
1. Identification of the noperable 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 Reguirements 12.3.3.B.1 Doses due to liquid releases shall be projected at least once per 31 days 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 operating the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

piproaupgd~pprove dcm=s12r5 12-27

I I LASALLE Revision 5 November 2002 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 achievabte." A system bypass allows connection to portable waste treatment equipment. This enables the efficient processing of liquid radwaste through the use of state-of-the-art radwaste processing technology. The portable radwaste treatment system may be used in lieu of various- portions of the liquid radwaste treatment system when a portable waste treatment is not used, Surveillance Requirement 12.3.3.B.2 may be extended to 180 days. This specification implements the requirements of 10 CFR Part 50.36a. General Design Criterion 50 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix I to 10 CFR Part 50. Th3 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 Ml.A of Appendix I. 10 CFR Part 50, for liquid effluents.

p:rocupg doved=Msl2i5 12-28

LASALLE Revision 5 November 2002 12A GASEOUS EFFLUENTS 12A.1 Dose Rate Operabfity Reguirements 12A..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 mremtyr to the total body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and
b. For odine-131, for odine-133, for tritium, and for all radionuclides In particulate form with half lives greater than 8 days: Less than or equal to a dose rate of 1500 mremstyr to any organ via the inhalation pathway.

ADplicablty. 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 Reoulrements 12A.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 methodology and parameters of the ODCM by obtaining representative samples and performing analyses In accordance with the sampling and analysis program specified In Table 12.4.1-1.

12A.1.6.2 The dose rate due to odine-131, iodine-133, tritium, and all radionuclides in particulate form with haf lives greater than eight days, In accordance with the methodology and parameters of the ODCM by obtaining representative samples and performing analyses In accordance with the sampling and analysis program specified In Table 12A.1-1.

Bases 12A.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 will not result In the exposure of an individual In an unrestricted area, either within or outside the site boundary exceeding the limits specified in IOCFR20.1301. For individuals who may at times be within the site boundary, the occupancy of the ndividual will be sufficiently low to compensate for any Increase 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 mremiyear to the total body or to less than or equal to a dose rate of 3000 mremnyear to the skin. These release rate mits 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 mremlyear.

This specification applies to the release of radioactive effluents in gaseous effluents from all reactors at the site. For units within shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

nap~vvedW12 S12r5 12-29

LASALLE Revision 5 November 2002 TABLE 12..11 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT OF TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD)

FREQUENCY ANALYSIS (PC mIr)

A. Containment Vent P P Principal Gamma 1x104 and Purge Each Purge Each Purge Emitters' System. Grab Sample H-3 1x10 4 B. Main Vent Stack he Mb Principal Gamma 1x104 Grab Sample Emitters' Wks"0 7H-3 1x104 Grab Sample C. StandbyGas D D' Principal Gamma 1xi10 Treatment System Grab Sample Emitters' D. Main Vent Stack Continuous' Wd 1-131 lxl1'2 And Standby Charcoal Gas Treatment Sample Systemc .,

1-133 1xi0101 Continuous' W Principal Gamma 1xl1 Particulate Emitters' (I-Sample 131, Others)

Continuous' M Gross Alpha 1xl1O" Composite Particulate Sample Continuous' a Sr-89,Sr-90 1xl 1 Composite Particulate Sample Continuous' Noble Gas Noble Gases 1x104 Monitor Gross Beta or Gamma p:oupgWdPVeadoc1b2r5 12-30

LASALLE Revision 5 November 2002 TABLE 12.4.1-1 (Continued)

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

FREQUENCY ANALYSIS (PC0mIf P P Principle Gamma 5x1e E. Oil Burner Each Batch Each Batch Emitters Grab Sample Dissolved and 1xi -

Entrained Gases (Gamma Emitters) 1-131 1x10 4 P M H-31x10 4 Each Batch Composite Grab Sample Gross Alpha 1x1O Q Sr-89. Sr-90 5x10 4 Composite Fe-55 1x104 pppoufpusod12rS 12-31

LASALLE Revision 5 November 2002 TABLE 12A.1-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION

a. The LLD Is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank obseNation represents a real signal.

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

4.66 sb LLD E. V. 2.22x10. Y. exp (-t)

Where:

LLD is the a priori lower limit of detection as defined above (as microcurse per unit mass or volume),

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

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

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

2.22x10 6 s the number of transformations per minute per microcurle, Y Is the fractional radiochemical yield (when applicable).

A 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 sb 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.

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

(2.71 + 4.650). Decay LLD =

Eq b Yt (2.22 x 100) n~nean naumanuwejrV19rs 12-32

LASALLE Revision 6 November 2002 TABLE 12A.1-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION Where:

B background sum (counts) i = counting efficiency q sample quantity (mass or volume) b abundance (f applicable)

Ye fractional radiochemical yield or collection efficiency (If applicable) t= count time (minutes) 222 x 106 = number of disintegrations per minute per microCurie 2.71 + 4.654B = k2 + (2k -42IB), and k = 1.645 (k=value of the t statistic from the single-tailed t distribution at a signIficance level of 0.95 and infinite degrees of freedom. This means that the LLD result represents a 95%

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

Decay e' DRT/(1-e'¶D',T /( 1-eTd)] If applicable

= radioactive decay constant (units consistent with at, RT and Td)

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

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

T = sample deposition time, or the duration of analyte collection onto the sample media (units consistent with 2)

The LLD may alternately be determined using Installed radioanaytical software, If available. In addition to determining the correct number of channels over which to total the background sum, utilizing the software's ability to perform decay corrections (ie. during sample collection, from sample collection to start of analysis, and during counting), this alternate method will result In a more accurate determination of the LLD.

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

b. Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20 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 /> unless (1) analysis shows that the dose equivalent 1-131 concentration In the primary coolant has not Increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

PlrOnxw pproveauxocnlsim 12-33

LASALLE Revision 5 November 2002 TABLE 12.4.1-1 (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION

c. Whenever there is flow through the SBGTS. (If SBGT s 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.) When SBGT equipment is started and shutdown, ensure noble gas iodine and particulate samples are taken.
d. Samples shaH be changed at least once per 7 days and the analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after removal from the sampler. Sampling shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal power in one hour. This requirement does not apply if 1) analysis shows that the dose equivalent 1-131 concentration in the primary coolant has not increased by more than a factor of 5, and 2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.

e. Tritium grab samples shall be taken at least once per 7 days from the plant vent to determine tritium releases in the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool. If there is no spent fuel in the fuel pool, sampling and analysis of tritfum grab samples shall be performed at least monthly.
f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Sections 12A.1 A, 12.42.A and 12.4.3-A
9. 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 C-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 dentified 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, and 3) conditions are such that activity can be calculated for the radionuclide concentration at the time of the release.

If there s any reason to suspect that gaseous radioactivity levels have changed in the drywel that would compromise the calculated, or estimated, radionuclide concentrations at the time of the release, 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 a known steady state leakage condition exists in the drywell it is possible to calculate a safe and accurate release package. Final release quantification will be based on calculated radionuclide concentrations at the time of the actual release.

If the drywell is pumed In accordance with the ODCM definition, both noble gas and tritium analyses must be completed before the purge begins. If the drywell is simply vented in accordance with the ODCM definition, no sample Is required before venting.

p-.Vmag~appvd~d=V12r5 12-34

LASALLE Revision 5 November 2002 12.4 GASEOUS EFFLUENTS 12A2 Dose - Noble Gases Operability Recwuirements 12A42A The air dose due to noble gases released In gaseous effluents, from each reactor unit, from the site shall be limited to the following:

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 beta radiation.

ADDlicabilit. At all times.

Action:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission, pursuant to 10CFR50, Appendix 1,Section IVA, a report which Identifies the cause(s) for 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 mits. This report Is due to the NRC within 30 days from the end of the quarter In which the release occurred.

Surveillance Riequirements 12A.2.B Dose Calculations - Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined In accordance with the ODCM at least once per 31 days.

Bases 12A.2.C This specification is provided to implement the requirements of Sections II.B. IIlA and IVA of Appendix 1,10 CFR Part 50. The Operability Requirements are the guides set forth in Section 11.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth In Section IVA of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept as low as Is reasonably achievable.

The Surveillance Requirements Implement the requirements In Section lIlA of Appendix I that conformance with the guides of Appendix I 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 dose calculations established in the ODCM 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 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 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents In Routine Releases from Light-Water Cooled Reactors,@ Revision 1,July 1977. The ODCM equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions.

p.Apocpgmproedd l2r5 12-35

LASALLE Revision 5 November 2002 12.4 GASEOUS EFFLUENTS 12.4.3 Dose - odine-131, odine-133, Tritium, and Radionucldes in Particulate Form 0 erabifli Reguirements 12.4.3A The dose to a MEMBER OF THE PUBLIC from lodine-131, IodIne-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days In gaseous effluents 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.

Appicabill: At all times.

Action:

a. With the calculated dose from the release of Iodine-1 31, odine-133, tritium, and radionuclides In particulate form with half lives greater than 8 days, In gaseous effluents exceeding any of the above limits, prepare and submit to the Commission, pursuant to 10CFR50, Appendix I, Section IV.A, a report that Identifies te cause(s) for exceeding the lmilt 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. This report is due to the NRC within 30 days from the end of the quarter In which the released occurred.

Surveillance Reguirements 12.4.3.B Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-1 31, iodine-1 33, tritlum, 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.

_\wois1v2avvd%0dcV31Wr5 12-36

LASALLE Revision 5 November 2002 Bases 12A.3.C The specification is provided to implement the requirements of Sections II.C, IIIA and VA of Appendix , 10 CFR Part 50. The Operability Requirements are the guides set forth n Section I.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time Implement the guides set forth in Section IVA 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 IllA of Appendix I that conformance with the guides of Appendix I 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 1.1 09, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Lght-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 radioiodines, 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) ndividual inhalation of airborne radionuclides, 2) 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)deposltion-on-the-ground with subsequent exposure of man.

D:iroCUood%2Dor0VedkX1=VS12r5 12-37

LASALLE Revision 5 November 2002 12.4 GASEOUS EFFLUENTS 12.4.4 Gaseous Radwaste Treatment System Onerability Reauirements 12AA.A The GASEOUS RADWASTE (OFF-GAS) TREATMENT SYSTEM shal be in operation.

Aoolicabilita. Whenever the main condenser air ejector system Is in operation.

Action:

a. With the GASEOUS RADWASTE (OFF-GAS) TREATMENT SYSTEM inoperable for more than 7 days, prepare and submit to the Commission within 30 days, 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 Reouirements 12A.4.B 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 11,0 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 ll.B and Il.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

p:.cupgdapprvedWdas12r5 12-38

LASALLE Revision 5 November 2002 12.4 GASEOUS EFFLUENTS 12A.5 Ventilation Exhaust Treatment System Operabilitv Requirements 12A.5A 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.

Avolicabili. At all times.

Action:

With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days, and with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, 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 Requirements 12.4.5.B.1 Doses dd to gaseous releases from the site shall be projected at least once per 31 days In accordance with the ODCM.

12.4.5.B.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

Bases 12A.5.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 11,0 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 n Sections II.B and IC of Appendix I, 10 CFR Part 50, for gaseous effluents.

pogpprovewdkbp s2r 12-39

LASALLE Revision 5 November 2002 12A GASEOUS EFFLUENTS 12A.6 Venting or Purging Operability Requirements 12.4.6A VENTING or PURGING of the containment drywell shall be through the Primary Containment Vent and Purge System or the Standby Gas Treatment System.

Applicabili. 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.

Surveillance Reguirements 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 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 MODE 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 12A.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.

Pa\_0_ M s1r200r0Vedr9X=V31Z5 12-40

LASALLE Revision 5 November 2002 12A GASEOUS EFFLUENTS 12A.7 Total Dose Operabilitv Requirements 12.4.7A 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.

Applicabil: At all times.

Action:

With the calculated doses from the release of radioactive materials In liquid or gaseous effluents exceeding twice the limits of Sections 12.3.2Aa, 12.3.2Ab, 12A.2Aa, 12.42Ab, 12.4.3Aa or 12A.3Ab, prepare and submit 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 Section 12A.7A. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluents pathways and direct radiation) for a 12 consecutive month period that includes the release(s) covered by this report. If the estimated dose(s) exceeds the limits of Section 12.4.7A. 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

-- n accordance with theprovisionsof40-CFR-90fandincuding the-specfied 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.

Surveillance Requirements 12.4.7.B Dose Calculations - Cumulative dose contributions from direct radiation and liquid and gaseous effluents shall be determined in accordance with Sections 12.32.B, 12A.2.6 and 12A.3.B, and In accordance with the ODCM.

0wcodaoovd~odrnhs12r5 12-41

LASALLE Revision 5 November 2002 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 from plant radioactive effluents exceed twice the design objective doses of Appendix I. 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 i the Individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 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 individual Is not considered a member of the public during any period in which helshe is engaged in carrying out any operation which is part of the nuclear fuel cycle.

plAup 2r5 ustappvmdbdcMVS 12-42

LASALLE Revision 5 November 2002 12.4 GASEOUS EFFLUENTS 12A.8 Main Condenser Operability Reauirements 12.4.8A The release rate of the sum of the activities from the noble gases measured prior to the holdup line shall be limited to less than or equal to 3A x microcuries/second after decay of 30 minutes.

Anoicabllitv. MODE 1. MODES 2 and 3 with any main steam fine not Isolated and steam jet air ejectors (SJAE) not in operation.

Action:

With the release rate of the sum of the activities from the noble gases prior to the holdup line exceeding 3A x 10 5 microcuries/second after decay of 30 minutes, restore the release rate 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 either Isolate all main steam lines or Isolate the SJAEs In the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or be In MODE 3 In the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 In the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Surveillance Requirements 12A.B.B.1 The radioactivity rate of noble gases prior to the holdup line shall be continuously monitored In accordance with the ODCM and Table 12.2.2-2.

12.4.8.6.2 *The release rate of the sum of the activities from noble gases prior to the holdup line shall be determined to be within the limits of specification 12A.8.A at the following frequencies by performing an isotopic analysis of a representative

-sample-of gases taken prior to the holdup line.

a. At least once per 31 days.
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-treatment Noble Gas Activity Monitor, of greater than 50%, after factoring out Increases due to changes in THERMAL POWER level, In the nominal steady state fission gas release from the primary coolant

'Not required to be performed until 31 days after any main steam line not isolated and SJAE not In operation.

Bases 12A.8.C In accordance with surveillance requirements contained within ODCM Chapter 12 Item number 12.4.8.B.1 and 2, this specification provides reasonable assurance that the releases from the main condenser will not exceed the requirements of the LaSalle Technical Specifications 3.7.6. 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 /> I the Increase Is not due to thermal power 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 duration, then no sample Is required. [This Is based on Interpretation letter from W. R. Huntington to Operating Engineers. Shift Engineers and F.R. Lawless, dated May 24, 1984.1 pasrocuVomipprovedvdw1Ms1Z5S 12-43

LASALLE Revision 5 November 2002 12A.9 Dose Limits for Members of the Public Operability Requirements 12.4.9A The licensee shaM conduct operations such that the TEDE to Individual MEMBERS OF THE PUBLIC does not exceed 100 mrem In a year. In addition, the dose In any unrestricted area from external sources does not exceed 2 mrem In any one hour.

The Effluents Program shall Implement monitorirg, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10CFR20.1302 and wfth the methodology and parameters In the ODCM.

ApRllcabilitv. At all times.

Action:

1. If the calculated dose from the release or exposure of radiation meets or exceeds the 100 mremlyear limit for the MEMBER OF THE PUBLIC. prepare and submit a report to the Commission in accordance with I0CFR2O2203.
2. If the dose In any unrestricted area from external sources of radiation meets or exceeds the 2 mrem In any one hour limit for the MEMBER OF THE PUBLIC, prepare and submit a report to the Commission In accordance with IOCFR2O.2203.

Surveillance Requirements 12.4.9.B Calculate the TEDE to individual MEMBERS OF THE PUBLIC annually to determine compliance with the 100 mrem/year limit in accordance with the ODCM.

In addition, evaluate and/or determine if direct radiation exposures exceed 2 mrern in any hour in unrestricted areas.

Bases 12.4.9.C This section applies to direct exposure of radioactive materials as well as radioactive materials released in gaseous and liquid effluents. IOCFR20.1301 sets forth the 100 mremlyear dose limit to members of the public; 2 mrem In any one hour limit in the unrestricted area; and reiterates that the licensee is also required to meet the 40CFRI90 standards. 10CFR20.1302 provides options to determine compliance to IOCFR20.1301. Compliance to the above operability requirement is based on IOCFR20, 40CFR190 and LaSalle Station Technical Specification 5.5.4.g.

pXrocpgdtPprved'cdcniV1a5 12-44

LASALLE Revision 5 November 2002 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitorino Proaram Operabilitv Reguirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.

Anglicabilit. At all times.

Action:

1. With the Radiological Environmental Monitoring Program not being conducted as specified In Table 12.5-1, prepare and submit to the Commission, In the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

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

2. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, a Special Report that Identifies the cause(s) for exceeding the imit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose- to a MEMBER OF THE PUBLIC Is less than the calendar year limits of Section 12.3.2, 12.42, or 12.4.3.

When more than one of the radionuclides in Table 12.5.2 are detected In the sampling medium, this report shall be submitted if:

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

When radionuclides other than those inTable 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose' to A MEMBER OF THE PUBLIC from all radionuclides Is equal to or greater than the calendar year limits of Section 12.32, 12A.2, or 12A.3. This report is not required If the measured level of radioactivity was not the result of plant effluents; however, In such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Section 12.6.1.

'me methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated In this report.

P: vMXCUy9G%8DVveMX~asr1M 12-45

I LASALLE Revision 5 November 2002 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

3. If the sample type or sampling location(s) as required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the pathway of interest and/or specific sampling locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Prepare and submit controlled version of the ODCM within 180 days including a revised figure(s) and table reflecting the new location(s) with supporting information Identifying the cause of the unavailability of samples and Justifying the selection of new location(s) for obtaining samples.

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

Bases 12.5.1 .C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials n those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

Guidance for this monitoring program Is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

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

Detailed discussion of the LD, and other detection limits, can be found InHASL Procedures Manual, HASL-300 (revised annually), Currie, LA., Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry,' Anal. Chem. 40.586-93 (1968), and Hartwell, J.K, Detection Limits for Radloanalytical Counting Techniques,' Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

WDU=0DDanrdatdU2M 12-46

LASALLE Revision 5 November 2002 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued)

Interpretations 12.5.1.D Table 12.5-1 requires one sample of each community drinking water supply downstream of the plant within 10 kilometers. Drinking water supply Is defined as water taken from rivers, lakes, or reservoirs (not well water) which is used for drinking.

p:nWoCmODCKMrOVbdOCO SIZf5 12-47

IA E 0 Revision 5 November 2002 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY OF AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS(1) COLLECTION FREQUENCY ANALYSIS

1. Airborne Radiolodine Samples from a total of eight locations: Continuous sampler Radlolodine Canister. 1-131 and Particulates operation with particulate analysis biweekly on near field and
a. Indicator- Near Field sample collection weekly (or control samples.)

more frequently If required Four samples from locations within 4 due to dust loading) and Particulate Sampler: Gross beta km (2.5 ml) Indifferent sectors. radoodine canister collection analysis following weekly filter biweekly. change3 ) and gamma Isotopic

b. Indicator- Far Field analysis(4)quarterly on composite filters by location on near field and Three additional locations within 4 io conrolW samples.

10 km (2.5 to 6.2 ml) In different sectors.

c. Control One sample from a control location within 10 to 30 km (6.2 to 18.6 ml);

p wID~vguwvvrve m1Zro

' 12-48

LASte .

RevisIon 5 November 2002 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY OF ANDIOR SAMPLE SAMPLES AND SAMPLE LOCATIONSs) COLLECTION FREQUENCY ANALYSIS

2. Direct Radlatlons) Forty routine monitoring stations either with Quarterly Gamma dose on each TLD a thermolumrinescent dosimeter (TLD) or quarterly.

with one Instrument for measuring dose rate continuously, placed as follows:

a. Indicator- Inner Ring (100 SerIes TLD)

One Ineach meteorological sector, In the general area of the SITE BOUNDARY (within 0.1 to 2.0 ml; 0.2 to 3.2 km)

b. Indicator- Outer Ring (200 Series TLD)

One Ineach meteorological sector, within 4.8 to 10 km (3 to 6.2 ml); and

c. Other One at each Airborne location given in part .a. and 1.b.

The balance of the TLDs to be placed at special nterest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwesith Edison employees have routine access. (300 Series TLD) ri:i~z

- 1249

LADE Revision 5 November 2002 TABLE 12.5-1 (Continued)

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

2. Direct RadiationrM d. Control Quarterly Gamma dose on each TLD (Conrd) One at each Airbome control location quarterly.

given In part I.c

3. Waterborne
a. Ground/ Well a. Indicator Quarterly Gamma sotopic") and tritium analysis quarterly.

Samples from two sources only if likely to be affected.t 1

b. DrInkinge a. Indicator Weekly grab samples. Gross beta and gamma isotopic analyses4) on monthly composite; One Sample from each community tritium analysis on quarterly Drinking water supply that could be Composite. 1-131 analysis on Affected by the station discharge within each composite when the dose 10 km (6.2 ml) downstream of calculated for the consumption of discharge. water is greater than I mrem per year.
c. Surface WaterM It no community water supply (Drinking Weekly grab samples. Gross beta and gamma isotopic Water) exists within 10 km downstream analyses")on monthly composite; of discharge then surface water tritium analysis on quarterly sampling shall be performed. composite.
a. Indicator One sample downstream p:1cuPgaAPWoedWMM81zr5 50

LASIF Revision 5 November 2002 TABLE 12.5-1 (Continued)

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

d. Control Samplely a. Control Weekly grab samples. Gross beta and gamma Isotopic analyses) on monthly composIte; One surface sample upstream tritium analysis on quarterly discharge. composite.
e. Sediment a. Ind Semiannually. Gamma Isotopic analysis 14 semiannually.

At least one sample from dowstreamtX1 area within 10 km (.2 MI).

4. Ingestion a. Indicator Beekly 9'when animals are Gamma lsotoplc 4)and 1-131(')

on pasture (May through analysis on each sample.

a. Mlkt) Samples from milking animals from a October), monthly at other maximum of three locations wIthIn 10 times (November through km (6.2 ml) distance. April).
b. Control One sample from milking animals at a control location within 10 to 30 km (6.2 to 18.6 ml).

p 12rh5 51

LASt 0 Revision 5 November 2002 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY OF AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS(1 ) COLLECTION FREQUENCY ANALYSIS

b. Fish a. Indicator Two times annually. Gamma Isotopic analysis(4) on edible portions Representative samples of commercially and recreatlonally Important species Indischarge area.

Representative samples from the LaSalle Lake. I

b. Control Representative samples of commercially and recreatIonally Important species Incontrol locations upstream of discharge.

Annually Gamma sotopict4) and 1-131

c. Food Products a. Indicator Analysis on each Two representative samples from the Sample.

principal food pathways grown Ineach of four major quadrants within 10 km (6.2 ml), If available:

At least one root vegetable sample"l At least one broad leaf vegetable (or vegetation)i

b. Control Two representative samples similar to Indicator samples grown within 16 to 30 km (9.3 to 18.6 mi), I available.

_~gw 12t7f

' 12-52

LaSalle Revision 5 November 2002 TABLE 12.5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent shall be provided for each and every sample locaton in Table 12.5-1, except for vegetation. For vegetation, due to location variability year to year, the parameters of distance and direction shall be provided In the Annual Environmental Operating Report.

(2) Far field samples are analyzed when the respective near field sample results are Inconsistent with previous measurements and radioactivity Isconfirmed as having Its origin In airborne effluents from the station, or at the discretion of the Radiation Support Director.

(3) 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. If gross beta activity In air particulate samples Isgreater than 10 times the yearly mean of control samples, gamma Isotopic analysis shall be performed on the Individual samples.

(4) Gamma Isotopic analysis means the dentification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station.

(5) One or more Instruments, such as a pressurized Ion chamber, for measuring and recording dose rate continuously may be used Inplace of, or In addition to, integrating dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation. The 40 locations Is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., Ifa station Is adjacent to a lake, some sectors may be over water thereby reducing the number of dosimeters which could be placed at the Indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

(6) Groundwater samples shall be taken when this source Is tapped for drinking or Irrigation purposes Inareas where the hydraulic gradient or recharge properties are suitable for contamination.

(7) The downstreaW sample shall be taken in an area beyond but near the mixing zone. The upstream sample" shall be taken at a distance beyond significant Influence of the discharge. Upstream samples in an estuary must be taken far enough upstream to be beyond the station Influence.

(6) Ifmilking animals are not found In the designated Indicator locations, or If the owners decline to participate Inthe REMP, all milk sampling may be discontinued.

(9) Biweekly refers to every two weeks.

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

(11) One sample shall consist of a volumevelght of sample large enough to fill contractor specified container.

p-.Vra~gdppv~d(S=V18125 12-53

LaSali Revision 5 November 2002 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCI/) OR GASES (pCUm3) (pCikg, wet) (pCI/I ) (pC/kg, wet)

H-3 20,0001')

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-BO 300 10,000 Zn-85 300 20,000 Zr-Nb-95 400 1-131 2(2) 0.9 3 100 Cs-134 30 10 1,000 60 '1,000 Cs-137 20 2,000 70 2,000 Ba-La-140 200 300 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCI/I may be used.

(2) If no drinking water pathway exists, a value of 20 pCI/I may be used.

p:\arogd~apved~d c 12P5 1Z-54

LasDe 0 RevIsion 5 November 2002 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLDf)M WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCIl) OR GASES (pCIfm 3) (pCIkg, wet) (pCI/) (pCUkg. wet) (pCI/kg, dry)

Gross Beta 4 0.01 1000 H-3 2,000M Mn-54 15 130 Fe"59 30 280 Co-58,60 15 130 Zn-O5 30 280 Zr-Nb-95 15 1-1310" 1/15(4) 0.07 100 0.s55) 60 Cs-134 15 0.01 100 15 60 150 Cs-137 18 0.01 100 18 80 180 Be-1 40 15 15 wVM12ftl 55

LaSalle Revision 5 November 2002 TABLE 12.5-3 (Continued)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) The nuclides on this list are not the only nuclides intended to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported Inthe Annual Radiological Environmental Operating Report.

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

(3) The Lower LUmit of Detection (LLD) sdefined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observatirn represents a realr signal.

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

4.66 Sb 3tb LLD =

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

4.66 Sb LLD -

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

Where: 4.66 Sb >> 3/tb LLD the Oa priori" Minimum Detectable Concentration (picoCuries per unit mass or volume),

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

= 4total counts tb E = the counting efficiency(counts per disintegration),

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

2.22 = the number of disintegrations per minute per picoCurle, Y = the fractional radlochemical yield, when applicable, A, = the radioactive decay constant for the particular radionuclide (sec-t),

x:~rocuPgdwPProved~odaim~s12r5 12-56

LaSalle Revision 5 November 2002 TABLE 12.5-3 (Continued)

DETECTION CAPABILITI ES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS tb counting time of the background or blank (minutes), and at = the elapsed tine between sample collection, or end of the sample collection period, and the time of counting (sec).

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

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

Analyses shall be performed In such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described In the Annual Radiological Environmental Operating ReporL If no drinking water pathway exists, the value of 15 pCi/I may be used.

(5) A value of 0.5 pCi/1 shall be used when the animals are on pasture (May through October) and a value of 5 pCi/I shall be used at all other times (November through April).

(6) This LLD applies only when the analytical separation and counting procedure are specific for this radionuclide.

(7) This LLD Is the minimum allowable, however, vendors performing environmental sample analyses off-site will be required to meet an LLD of 200 pCiJ4.

wlra,1;n ~ r S 12-57

LaSalle Revision 5 0__ November 2002 12.5.2 Land Use Census ODerabifty Recuirements 12.5.2A A Land Use Census shall be conducted and shall Identify within a distance of 10 km (6.2 miles) the location In each of the 16 meteorological sectors of the nearest milk animal, the nearest residence", and an enumeration of livestock. For dose calculation, a garden will be assumed at the nearest residence.

Applicability. Al all times.

Action:

1. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained In accordance with Section 12.5.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given In Chapter 11. The sampling location(s), excluding the control location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit In the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM Including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change In sampling locations.
  • This requirement may be reduced according to geographical limitations; e.g. at a lake site where some sector's will be over water.

"The nearest industrial facility shall also be documented if closer than the nearest residence.

Surveillance Requirements 12.5.2.B The Land Use Census shall be conducted during the growing season, between June 1 and October 1, at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included In the Annual Radiological Environmental Operating Report Bases 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. This census satisfies the requirements of Section IV.1.3 of Appendix I to 10 CFR Part 50. An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence In each sector for dose calculations.

0pMopg~prvvawcsi=

12-58

LaSalle Revision 5 November 2002 12.5.3 Interiaboratory Comparison Program Operablitv Requlrements 12.5.3A Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that correspond to samples required by Table 12.5-1.

Applicability At all times.

Action:-

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

Survellance Reauirements 12.5.3.B A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be Included In the Annual Radiological Environmental Operating Report.

Bases 12.5.3.C The requirement for participation In an Interlaboratory Comparison Program Is provided to ensure that Independent checks on the precision and accuracy of the measurements of radioactive material In environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

r:P1nrctmonoffwrovedod1Is12r5 12-59

LaSalle Revision 5 November 2002 12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radiological Environmental Ooerating Report' Routine Annual Radiological Environmental Operating Report covering the operation of the Units during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring program for the report period. The material provided shall be consistent with the objectives outlined In the Offsite Dose Calculation Manual, and In 10CFR50, Appendix I, Sections IV.B2, IV.B.3, and IV.c. It should Include, as found appropriate, a comparison of preoperational studies with operational controls or with previous envionmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment The Annual Radiological Environmental Operating Report shall Include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified In the tables and figures in Chapter 11 of the ODCM, as well as summarized and tabulated results of these analyses and measurements In the format of the table In the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some Individual results are not available for inclusion with tile report the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shag be submitted as soon as possible In a supplementary report The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, and discussio6 of all deviations from the sampling schedule of Table 12.5-1; a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents; discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; results of the Land Use Census required by Section 12.52; and the results of licensee participation In an Intertaboratory Comparison Program and the corrective actions being taken if the specfied program is not being performed as required by Section 12.5.3.

The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report the licensee has the option of -

retaining the summary of required meteorological data on site In a file that shall be provided to the NRC upon request

  • Asingle submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

n n1rrv trw~vdlvsodavnmU51 7m 12-60

LaSalle Revision 5 November 2002 12.6.1 Annual Radiolooical Environmental Operating Reort (Continued)

The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This report shall also Include an assessment of radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year.

The assessment of radiation doses shall be performed in accordance with the methodology and parameters Inthe ODCM and in compliance with IOCFR20 and 40 CFR 190,

  • Environmental Radiation Protection Standards for Nuclear Power Operation.

12.6.2 Radioactive Effluent Release Reoort'

a. The radioactive effluent release reports covering the operation of the unit during the previous calendar year of operation shall be submitted In accordance with I0CFR50.36a prior to May I of each year. The report shall include a summary of the quantifies of radioactive liquid and gaseous effluent and solid waste released from the unit. The material provided shall be consistent with the objectives outlined Inthe ODCM and the PROCESS CONTROL PROGRAM and Inconformance with 10CFR50.36a and 10CFR50, Appendix 1,Section IV.B.1.
b. The radioactive effluent release reports shall Include 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 shall Include the following information for each type of solid waste shipped offslte 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 shall Include 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 shall Include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

The radioactive effluent release reports shall Include a description of licensee initiated major changes to the radioactive waste treatment systems (liquid, gaseous and solid), as described In Section 12.6.3.)

4A 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.

P:AProcupgd"fPPrMV6d=dcflVSiZ*

12-61

LaSalle Revision 5 November 2002 i2.8 REPORTING REQUIREMENTS 12.6.3 Offsite Dose Calculation Manual (ODCM1' 12.6.3.1The ODCM shall contain the methodology and parameters used Inthe calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and 12.6.3.2 The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be Included Inthe Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3.

12.8.3.3 Licensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance (A) Manual. This documentation shall contain:
1. Sufficient information to support the change(s) together with the appropriate analyses or evaluationsjustfying the change(s); and
2. A determination that the change(s) maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190, 10 CFR 50.36a, and 10 CFR Part 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
a. Shall become effective after approval of the Plant Manager.
b. Shall be submitted to the NRC 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. Each change shall be identified by marldngs In the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (Le., month and year) the change was Implemented.

The OFFSITE DOSE CALCULATION MANUAL (ODCM) iscommon to LaSalle Unit 1 and LaSalle Unit 2.

p.Apoup ws1vedW 812Z5 12-62

LaSalle Revision 5 November 2002 12.6 REPORTING REQUIREMENTS 12.6A Malor Chances to Radioactive Waste Treatment Svstems 12.6A.1 License initiated major changes to the radioactive waste treatment systems (liquid ard gaseous):

a. Shall be reported to the Commission in the Radioactive Effluent Release 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 Information;
3. A detailed description of the equipment, components and processes 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 exposures to idividual In the unrestricted area and to the general population that differ from those previously estimated In the license application and amendments thereto;
6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, 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.

p="tpvdd=a5 12-63

LaSalle Revision 5 November 2002 APPENDIX F

- STATION-SPECLIFiC DATA FOR LASALLE UNITS 1 AND 2 Table of Contents F.1 RODUCTION F-I F2 REFERENCES P-I' p?.propgd aproved.dcm~I12r5 F-i

LaSalle Revision 6 November 2002 APPEDIX F LIST OFTABLES F- I Aquatic Environent Oe Parameters P4E FP- E tation Charncustics F-3 P4 X tjcan.Ranga Fg P.4 Average Wind Spe.d F-5 F-S X1O and DO Maxia At or Beyond te Unrcled Area Soundary F6 F46a XO and DJQ Maxima At or Beyond be Rutricted Area Boundary F-?

F. DIO at te Nearest Mtc Cow and Met Animal Loiatons Wth 6Slb F8 F.? Maximum Oftte Fint Plume Gamma Doe Factor. Based on 1 cm Depth at the Unstriced Area Boundary for Selected Nucde F-6 F-la Maximum Otfl Fie Plume Gamma Dose Factos Based on 1 cm Depth at te Restricted Area Boundary for Selected-Nudos F-24 Parameters tor Cabiution, of N-16 Skyshine Radiation trom LaSalle 43 Supplemental Tables A Elevated Leva Joint Frequency Disatiuton Table Summary- 375 Foot Elevation Darn F-40

-Summary Table of Percent Oy Direction and Clas

-Summary Table of Percent by Direction and Speed

-Summary Tabl at Percent by Sped and Clat 6 Mid Elevationloint44squency Distrution Table Summary - 200 Foot Elevation Data F-42

-Summary Ta al Percent by Direction and Clat

-Summary Table of Percent by Direction aid Speed

-Summary Tabb of Percent by Speed ard Class C Ground Laval Joint Frequency Distybution Tabe Summary - 33 Foot Elevation Data F-44

-Summary Table o Percent by Direction and Class

-Summary Table a1 Percent by Direction and Speed

-Summary Table of Percent by Speed and Class ppoCugdaprovedkodm1I2r5 F-Ii

IS 0 S So~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~P X z rE~~~~~~~~~~~~~~~~

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~E ;u I

LaSalle Revision 6 November 2002 APPENDK F

- STATION-SPECIFIC DATA FOR LASALLE UNITS 1 AND 2 F.1 INTRODUCTION hs apendLx onlaln data rant to to LaSle afe. Incled b a someashowing estrict area boundary, sticted area oundary. and val s of parmet used in ofth dose asessment.

F2 REFERENCE I. Sargent & Un. Analisis and Technology Dsion. LaSale Calculation No. ATD-0164.

Revlsbn O.1, nd .

2 Sargent a Lundy. Nuclear Sabguards and UcenshV Dhision. LaSale Calculation No. ATD-0139. N-16 Skrshln Ground Level Doses rorn LaSale Tufbin System &Pling, Rviion C.

a Verification of Environmental Parameter used tor Commonwealth Edson Companys Ofske Dose Caculstions, ONUS Corporaton. 198.

p~gopedopaiNdls1W5 F-i

LaSalle Revision 5 November 2002 Toble I'1

- AquoUt Envlrnmeri Do" Priwetm Gleneral tnfrrmaltla The station Iquld dcharg Ibwa hto the Ilinois Rher then into ths Mississippi River.

Recrealin nckjde3 one wMiore of the o01nW boating. watshilng. swimming, and spo lssng.

Two downream dams are on i linois Rmr, Mansilles and Starved Rock. This Information s based on Section 24.1.1 and Figures 24-2 nd 2.4-60 ot e LaSale Environmental Repons.

Water nd Fish Ingostn PrMem Fe. adt 1.0 F1. dh 1.91E4

e. he 24.0
f. he 70 ilmit n RlalnRl In [tar~etad fludnarTankn' Outsklo Tempory Tank £ 10 C Ths is based on intormaion In LaSale Environmental Report, Fgure 3.3-1 and Section 2.1.2.1.

' The parameters are deim.ed i Sections A2.1 of Appendi A.

()h' *24 hr (al stations) for the fsh Ingestion pathway

  • 1 (hr) 97 r (distanc to nearest public potable water Intake, Peoria, is 97 miles; flow rats of I Mph is assumed.)
  • See Section A.2.4 o Apndl A Tritium and dissolved or entrained nble gases a exckded from this limt.

PN-OWPqd~aPPrvedzodm112r5 F-2

LaSalle Revision 5 November 2002 Table F4 Station Characterisics STATION: LaSal LOCATION: 6 mlhc south ot Marseilles. lOhN LaSaie Courty CHARACTERISTICS OF ELEVATED RELEASE POINT 1)Release Height -.J2. 2) Damater LMn R Exi ISped.

  • _J . 4) eat Contn m LJCOWle CHARACTERISTICS OF VENT STACK RELEASE POINT: Not Appicable (NA) 1)Rebs Height a ._n 2) Diameter _m
3) E Speed *u fl CHARACTERISTICS OF GROUND LEVEL RELEASE
1) Reus Height . M
2) eulkig Factor (D) a _JAA__je METEOROLOGICAL DATA A -AjWJI Tower k Locatd.25 S..- of elevated eles point Tower Data Used In Catubiti,-

Release Point J Wmd Speed and Direcion ODiferentlal Tenperstue Elevated 3751 375-3311t Vent (NA) (A Ground 33 11 200-331 Used hIcalcuating the meteorologlcal and CM actors hITables F4. F4, and F-7. S Sections 3 "fough9.6 of Appendix S D:EpDCUoaODor0oVeodcrm'sl1Z5 F-3

LaSalle Revision 5 November 2002 Table F-3 cdmoe Re Unrstcted Restfkted Area Nearest Nearest Da" Farm Bouidwry Rsif WithIn 5 Mil Boimday fmi 4mL

. GM 1038 None N 1036

  • None t39 2800 NNE 3400 None.

NE. 2405 1609I

' 1079 5300 -None EY'E 4450 190 833 5200 None E Non 145 B45 2300 ESE None 969 '961 2700

  • SE 2900 Noe

'3m 69 62o 2400 Non S None 65 635 1100 1600 None SSW a None WSW 533 533 2400 524 1300

  • None.

WSW 524 None 643 643 1400 762 2900 None W 762 7400 NNW 8950 50 2700 .1 a Used in calculating the meteorological dose factors in Tables F-5 and F-7. See Sections B.3 through B.6 of Appendix B.

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

1994 annual milk animal census, by Teledyne Isotopes Midwest Laboratories. Used In Calculating the D/Q values in table F.6. The distances are rounded to the nearest conservative 100 meters. A default value of 8000 meters is used when there are no dairies within 5 miles.

p:vprocupgd'npprvdadVs12r5 F4

LaSalle Revision 5 November 2002 Tabb F4 Aveage Wind Speds DDWnVWd Averrns W9d eld iMt~e maa yae Dmund+/-SxI N g*7 7.7

  • 4.9 NNE 10.1 ." 5.1 NE SI TA 4.9 ENE G. 7* 4.8 E

6.5 7.4 5.

ESE 5.9 SE 6.1 7A 5.9

-SSE 7A.- 6? 5.0, 6 6.7 GA 4.

SSW 5.6 3.7 2.6

.SW 5.5 4.1 83 WSW 69 -A SA W T 45 WNW 7.5 4.3

---. -. -3.9 NNW 6J 6. 4' 9ased on LaSale ste meteorological data. January 1978 OUGh Dcoeber 1987. Catulutod Rethrnce 1 1 Section F2 usg formulas hi SecSon 6.1.3 of Appendix B.

p AappkvedCrVS125 F-6

i Z F R~~~~ l'I'I'iI'Ei' 4t

$ .... § itiem e... EI0..

&~~~~~

X I [ 1rIti; I a ~~~~a

LASS Table F-Ba Revisfon 5 November 2002 X/Q and DOIQ Maxims at or Beyond th Restricted Area Bounday dw~f ' 11 0 lNned HadefVmnt) Relese arotu LaS Rate"*.

Direction 3Rdtus P.du X1 Dn0 (mters) (see/m"3) Nmetws) 011m"2) (eters £uec/a^3) ( 1/mP2} (meters) etc/f0*3) 0/C1ju2

'J.

  • 0$33. 6.123E-09 1036. 7.2031-10 600. 6.289E-09 8.311E-10 1036. 1.524E-06 1.019E-08 NVE I18. 7.0451-09 37. 9.831E-10 5943. 7.102E-09 9.659E1tO 1378. 9.I77-07 7.0ss-09 WE 4400. 5.5351-09 1609. 6.5561t10 1609. 6.052E-09 7.953S-10 1609. 7.003-or 4.74T7E09 IE 5200. 5.0861-09 1079. 6.376E-10 1079. 6.57S9-09 9.861E-10 1079. 1.128E-06 7.788E-09 C 5200. 5.865E-09 1500. 6.659E110 1055. 7.712E-09 1.160E-0 1055. 1.2781-06 5.7m-09 Et 5200. 8.00E-09 1500. 8.896E-10 105. 9.9811-09 1.5461-09 10s5. 1.1921-06 1.021e-08 SE 5833. 7.116-09 1500. 7.505E-10 969. 1.08E-08 1.701-09 969. 1.1371-06 1.1231-08 SE 5200. 6.J1TE-09 698. 7.2101-10 698. 1.444E-08 2.4031-09 698. 1.4921-06 1.4281-08 S 5633. 5.9101-09 1500. 6.136E-10 820. 8.455e-09 1.3121-09 820. 1.130E-06 1.05SE-08 SW 6000. 5.2692-09 835. S.ME-10 835. 7.22e-09 9.9m10 835. 7.9401-07 5.359E-09 SW 6000. 6.76TE-09 628. 8.545- 10 628. 2.2241-05 2.1541-09 628. 1.864E-06 1.407e-08 USU 6000. 6.0651.09 533. 6.5-10 540. 2.1051-08 2.079E-09 533. 2.101E-06 1.97CE-08 V 6437. 5.354E-09 1500. 4.811E-10 540. 1.3441-08 1.629E-09 524. 2.830E-06 2.453E-08 IW 7242. 3.916E-09 1500. 3.1751-10 643. 5.963-09 9.071E-10 643. 2.4291-06 1.508E-08 Nlu 7242. 3.766E-09 1500. 3.1181-10 5633. 4.127E-09 6.6801-10 762. 1.98E-06 1.055E-05 NW 6437. 4.2401-09 1500. 3.806E10 6437. 4.09SE-09 5.574E-10 890. 1.6051-06 8.8401-09 LASALLE ITE TEIOOLCIAL DATA 178 - 12ff EPSPROJbdm&u1J.Vg F-7

L6Wf 0

Table F4 Revision 5 November 2002 D/O at the Noaest Milk Cow and Meat Animal Locations within 5 miles thownlwn4 Has-wwt alk Cow 1/Qj1/m921 Nearest Meat A111al tl/91/00*21 Directio Radiuu Ilevated mixed Ground Radlus elevat-d Mixed Ogound Imeterul 146.I.. Halease Holeesu Imttusra Release "u1sua" 14.1...

N 9000. 9.711E-11 1.0061-10 2.915C-10 b400. 1.3971-10 1.4369-10 4.1521-10 9000. I . ISIC-10 1.179-10 3.2733-10 3100. 4.2571-10 4.3201-10 1.7b0-09 a 000. .919C 11 9.46 911 2.9511-10 5(.00. I.1 630 1.649 10 5.4011-10 E

9000. II.S592-11 0.4201-11 2.3819-10 5000. 1.5399-10 1.725s-10 5.5199-10 9000. I . 05k6-O0 9.772C-11 2. 979-1 0 9000. 1.0561-10 9.7721-l1 2.5971-10 E9E 9000. I .4501-10 I .IS6E-10 3. 010E-10 9000. 1.450E-10 1.156C-10 3.010C-10 SE 9000. 1.242E-10 .322E-10 2.9919-10 7600. 1.1541-10 1.4371-10 3.1601-10 SSW 9oo. 1.1749-10 1.2791-10 2.152C 10 700 . I.2799-10 1.199C-10 2.16013-10 S 9000. 9.4'J7E 11 9.09SE-11 2.ObSE-10 0000. 0q IIJE-11 9.095C-11 2.0';E-10 SW 9oo. U.t41E l1 9.0971-11 1.0771-10 9000. 9.647c-11 9.097E-11 1.077E-10 SW 9oo. 1.096E-10 1.2103-10 1.7931-10 9000. 1.096e-10 1.210C-10 1.791C-I0 9OO. 1.0171-30 1.0931-10 1.9401-10 9000. 1.017C-10 1.0193-10 1.9401-10 W 900. 0.4949-11 1.0941-10 2. 354-10 4900. 1 .091-10 2.1829-lo S . 966.-10 WS Noun. b.VSbl-11 1 .9'41-1o S100. 1.1173-10 1.1311-10 4. 311-3 0 1414 "o0"1. '.414E l U.3196-ll 1.291-10 b400. 7.7711-11 9.0J29-11 2.7Iue-lo HH141 7400. 7.)179-11 7 .2k41-11 2.2b9g-10 7600. 7.002K-11 6.9641-11 2.3011-10 I,.::1, e1II 1 :e ti"WtobrsuI.. gltcI 1bS 1 79 - 1@

I Nola: Based on Relerenco 2 of Secton F.2 and the formulas In Secton 8.4 ol Appendix 8.

EP8PRAJO0d=&sa&/1-71 I F-e

0 Revision 5 Table F.? November 2002 Maximum Ofisife Finite Plume Gamma Cose Factors Based on 1 cm Depth at the Unrestrfcted Arn Boundary for Kr-83m I

Daeiwd Uwutrictd 1rendtk I Iota"t . N1ud M&(Vmt leinwa ,rowdLwMnt em Diectlon A oun Pdus I SIAN RIedfu V "Al Indius tw ) (Meter) (ed/Wr)MIt/se) (etes) (WAlyr)t/(UI/c) c-t" U 1036. 1036. 4.7879-0o 3.60E9-0? 1036. 5.2111-0T 3.982E-0? 1036. .M53-04 1.3461-04 1371. 1371. 8.132-0? 6.599-0?r 1378. 6. 0 1-0? 5.2061-or 1373. 1.1393-04 8.5863-03 2408. 2408. 6.4711- ?r 1.89 -0? 2403. 6.693-0? 5.049E-0o 2408. 4.3351-03 3.284-05

'S 4450. 4450. 5.70E1-07 4.29 1-0 4450. 5.633E-0? 4.262E-0? 4450. 1.466E105 1.1051-05 E 1996. 1996. 4.6871-0 3.53Eo-0r 1996. 7.559EO? 5.7001-0? 1996. 5.4911-05 4.1401-05 ESE 1465. 1465. 5.252E-07 .9609-0? 1465. 1.002E-06 7.559-?OT 1465. 8.2701-05 6.1361-05 SE 969. 9M9. 3.SSE1-0 2.6731-07 959. 1.267E-06 9.5541-07 969. 1.333E-04 1.005E104 838. 3.0511-07 2.3011-07 838. 1.512E-06 1.140E-06 838. 1.323E-04 9.M -

829. 829. 2.840-OT 2.1411-O0 829. 1.040E-06 7.8421-0? 829. 1.330E-04 1.003E-04 833. 835. 3.185Eo-0 2.4011.0? 833. 1.0711-06 8.0763-0? 835. 9.3261-05 7.0321-03 SV 628. 628. 3.t7E-0? 2.39E-0 628. 2.8261-06 2.11E-06 628. 2.305E-04 1.7381-04 SU 533. 533. 2.61tE-0? 1.9733-0? 533. 2.674E-06 2.017E-06 53. 2.568E-04 1.9361-04 524. 524. 2.32TE-O 1.7541-0? 524. 1.68-06 1.2501E06 524. 3.32E-04 2.527E-04 643. 43. 1.714E-0? 1.2921-0? 64. 7.235E-0? 5.455E-07 3. 2.728E-04 2.0571-04 i NV 762. 762. 1.7441-or 1.3151-O0 4.3913-0? 3.3113-0? 2.219E-04 1.6733-04 i M~~~~~~~l

80. 890. 2.971-0? 1.8071-07 762.

890. 3.3341-0? 2.5141-07 762.

90. 1.8231-04 1.3741-04 LASALLE III INTIUULOGICAL DATA 1/78 - 12/1 i

Nole: Based on Reference 1ot Sectilon F.2 and the formulas InSecilons 6.5 and B. o Appendix B.

I EPPRoJMdm b1 -Fn F

sAQ .

Revisio Table F-7 Contliaod) November2002 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unieststed Area Boundry tar Kr-85m 4

DamEiaad Unrestricted Elevatedtltack) Retese iaed boB(Vu*) otel"se' Seemed LenteReeas.

Direction Ame ownd adius 5 SW5 adius V van Radlue S 03*31 Cmt.'s) (meters) (ad/VrjjtClissc) (mteutrs) ( rd/yuCi/cw) (tuters)Cured/yrMUCIi/sal 1036. 1036. 5.d47-05 .560-05 1036. 6.6021-05 6.3588-05 1036. 9.6-_04 9.2521-04 MI 1378. 1378. 5.061-05 4.8961-05 1378. 5.5141-05 5.3341-05 1378. 6.1761-04 6.496-04 2408. 2408. 2.5921-OS 2.50461-05 2408. 2.7271-05 2.6361-05 2408. 2.9691-04 2.8491-04 4450. 4450. 1.35l-05 1.3041-05 4450. 1.3321-05 1.2861-05 4450. 1.1561-04 1.1111-04 E 19W6. 1996. 2.7051-05 2.6161-OS 1996. 2.E65E-OS 2.1671-05 1996. 3.5571-04 3.4121-04 1465. 1465. 4.3511-05 4.2091.05 1465. 4.6241-05 4.470E-05 1465. 5.2011-04 4.9f91-04 969. 969. 5.5961-05 5.4151-05 969. 6.610E-0 6.3911-05 969. .ME7-04 7.4706-04 Su 338. 5.51AE-05 5.3391-OS 83. 6.6301-05 6.4101-05 838. 7.6 3-04 7.3 E-04 029. 29. 4.712E-05 4.560E-OS 029. 5.3301-05 5.154E-OS 829. 7.98E-04 7.6571-04 8t5. 835. 4.4221-05 4.2791-05 835. 5.3511-05 5.1741-05 US5. 5.6841-04 5.4501-04 USu 628. 628. 7.201E-05 7.0461-05 628. 9.9521-05 9.6181-05 628. 1.5E-03 1.2311-03 533. 533. 7.7511-05 7.507-OS 533. 9.714E-05 9.381-05 533. 1.391-0 1.3311-03 U 524. 524. 7.6011-05 7.3561.05 S24. 9.105E1-S 9.35-OS 524. 1.6871-03 1.614-03 M 64. 64. 5.2061-05 S.16l-OS "4. 6.6151-0S 6.39M-Os 643. 1.3211-03 1.2t01-03 762. 762. 4.6681-05 4.511-OS 762. 5.6ue-0os S.503-05 762. 1.0941-03 1.047E-0 890. 090. 4.6A1-05 4.5321-0S 390. 5.1421-05 4.9761-05 890. 9.2A21-04 8.8851-04 ASAU Ut1 EtlUMICAL DATA tll - 12 EP8PR0J/udcmsaslbl-7f 1 F-10

LASA 9 Revislon 5 November 2002 Table F.7 (Continued)

Ustmum Offstle Finite Plum Gamma Dos Factors Based on 1 cm Depth at the lnresticted Am Boundary or Itr-85 Downhrd no tcted EIIted(Steck) 1e0ms 13used Pod(*efltatmee1 StunS LowSl i*'.,

Directfen Am ld Redus I It" Rtais V VIAR Emd lus 0 S*tA I (m(&r) cuet) cadrOt/CiluOe) cuter.) (wr)1(ueised) jig iU U 10l&. 1036. 8.5471-0t 8.2651-0? 1016. 9.e89-r0? 9.5631-r 1036. 1.0561-05 1.0211-05

. -t. 1378. 7.309-O? 7.0681-07 1378. 8.071-07 7.811t-07 137 . 7.4741-06 t.2271-06 240b. 2408. 3.6511-0? 3.531-07 2408. 3.909-07 3.7801-07 2408. 3.3631-06 3.252E-06 ENE 4450. 4450. l.885E-O? 1.823E1-0 4450. 1.856t-07 1.7ME-07 4450. .3m7-06 1.3321-06 ElR 131 tM. 1996. 3.912-0? 3.782Eo-0 1996. 4.096107 3.9611-Or 1996.

6.6321-07 6.4131-07. 145.

4.008E-06 3.8?t6f06 1465. 1465. 6.359E1-? 6.1491-07 1465. 5.7831-06 5.5931-06 I 969. 969. 8.386E-0? 8.1101-0? 969. 9.5831-07 9.267E-07 969. 8.5551-06 8.273E-06 51 818. 838. 8.3501-07 .Ot5E-07 8386' 9.612t0T 9.2941-07 838. 8.4321-06 8.1541-06 829. 829. 7.2621-07 7.0231-07 829. 8.0671-T T.O1E-07 829. 8.7411-06 8.4531E06 835.* 835. 6.8571-07 6.6301-07 83. 8.4021-07 8.1241-07 5S. 6.2701-06 6.063E-06 SW 628. 628. 1.1421-06 1.1041-06 628k 1.4941-06 1.4441-06 628. 1.4011-05 1.3551-05 WSI 533. 533. 1.2U1-06 1.171E-06 533 ; 1.4331-06 1.386E-06 533. 1.5101-05 1.460E-05 524. 524. 1.1721-06 1.1341-06 524.

643.6 1.4431-06 1.395E-06 524. 1.824-0S 1.763E-05 NV 843. 643. 6.1851-07 7.9151-0? 1.0001-06 9.670E-07 643. 1.436E-05 1.389E-05 762. 762. 7.192E-O 6.9541-Ot 762. 8.6941-07 8.4071-O0 762. 1.1881-03 1.148E-05 NW. 890. 890. 7.1289-07 6.893t-07 89. 7.849E-07 7.591-0or 890. 1.0111-05 9.?718-06 MAIW SIT1 MeMtOMCLOaIM DATA W8

  • 12/87 I

71 II I

I I

I I

EP8PROJmauab~-7f F F-11

LnGIII &

Revision 5 Tabe F (Coniued) November2002 Maximum Offllst Finite Plum. Gamma Dose Fators Basd on I cm Depth at the Unrestricted Ara Boundary or Kr-87 d

paamid Unretricted leviedStesk) sle... Mixed HodeVmntl me"" ground Lovel R110...

Directln Aom Round Radius S UAD 1.41w V VA" Raius a tC i (mters) (moters) (mrodVr)lUCIlsc) (mters) (reyr)I(uctl" (meters caradlyr)iCuSlCeak) 1036. 1036. 3.2261-04 3.1351-04 1036. 3.1581-04 3.6521-04 1036. 2.8U9E-03 2.795E03 Ue 1371. 1370. 2.6721-04 2.5971-04 1378. 3.00SE-04 2.9201-04 1378. 2.0191-03 1.9601-03 2408. 240. 1.28SE304 1.246E- 2408. 1.359E-04 1.3201-04 2408. 5.60ts-04 8.3551-04 44SO. 4450. 5.904E-0S 3.737-OS 4450. S.tS9E-OS S.692E-OS 4450. 5.133-04 3.042F-04 ES 1996. 1996. 1.4125-04 1.3721-0 1996. 1.4581-04 1.4171-04 1996. 1.030-03 9.9981-04 1465. 1465. 2.351£-04 2.2t4E-04 146S. 2.426E-04 2.3S7E-04 1465. 1.S41-03 1.5E-03 969. 969. 3.211E-04 3.1205-04 969. 3.6121-04 3.5101-04 969. 2.3551-03 2.2871-03 SI 38. 838. 3.2541-04 3.162E-04 3. 3.655E-04 3.5521-04 2.3291-03 2.2621-03 SSW 829. 829. 2.805-04 2.701-04 029. 3.0811-04 2.9941-04 829. 2.4311-03 2.3611-03 Ssu 835. 535. 2.742-04 2.66SE-04 835. 3.4001-04 3.3051-04 1.7061-03 1.651E-03 628. 628. 4.614E-04 4.484104 628. 5.9361-04 5.7691-04 628. 3.9031-03 3.7901-03 U 533. 533. 4.880E-04 4.7431-04 533. 5.6831-04 5.5231-04 533. 4.2511-03 4.1281-03 524. 524. 4.675SE-0 4.543504 524. 5.7081-04 5.5471-04 524. 5.1346-03 4.9861-03 VA 643. 643. 3.224E-04 3.1335-04 643. 3.9141-04 3.8041-04 643. 4.0011-03 3.84E-03 762. 762. 2.8SE- 2.74U- 762. 3.971-04 3.3011-04 762. 3.2761-03 3.1801-03 590. 590. 2.7475-04 2.6691-04 890. 3.031 04 2.9451-04 890. 2.7631-03 2.6831-03 LASULLI S£lil NEIIOSOWICAt BATA 1/78 - 12/87 ElOSPROJIdafthsalshil-7i FF1 12

LASS Revision 5 November 2002 Table F-7 (Continued)

Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Urestricted Area Boundary for KrDO d

  • osuwird IJwutrfeted 1eted(SIt) R.1ms NIued Nod.(Ventl 3.1emm @romm eWM feSoo.

OfireetIon Am Dowd *sdhus I flARt Eadtns V "IAt ledlus a OPA (meter.) (meters) (radlyr)ItucI/uef) (mleters) (mradlyr)/(uCIIsec) (mester.) (udlyr)Isec)

U 1036. 1036. 8.6021-04 8.3741-04 1036. 1.003E-03 9.7691-04 1036. 6."98-03 6.787343 WE! 1378. 1378. 7.1111-04 6.922E-04 1378. 7.99E-04 7.7773-04 1378. 4.940E-03 4.7983-03 RE 2408. 2408. 3.4353-04 3.344E-04 2408. 3.694E-04 3.596E-04 2408. 2.1821-03 2.120E-03 ENE 4450. 4450. 1.6483-04 1.6041-04 4450. 1.6461-04 1.6021-04 4450. 8.502E-04 8.263E-04 E 1996. 1996. 3.781E04 3.6801-04 1996. 3.928E-04 3.824E-04 1996. 2.5M-03 2.525E-03 ESE 1465. 146S. 6.235E-04 6.0701-04 1465. 6.445E-04 6.2731-04 1465. 3.816E-03 3.7E7-03 SE 969. 969. 8.5371-04 8.3111-04 969. 9.5713-04 9.3171-04 969. 5.712E-03 5.549E-03 5!! 838. 838. 8.6711-04 8.442E-04 838. 9.702E-04 9.4451-04 838. 5.64SE-03 5.483E-03 S 829. 829. 7.696E-04 7.492t-04 829. 8.417E-04 8.194E-04 829. 5.62E1-03 5.695E-03

$Su 835. 835. 7.42?E-04 7.2311-04 835. 9.3751-04 9.127E-04 as5. 4.167E-03 4.048E-03 Su 628. 628. 1.246E-03 1.2131-03 628. 1.6011-03 1.5591-03 628. 9.396E-03 9.1261-03 us" 333. 533. 1.3141-03 1.2791-03 533. 1.525E-03 1.48S1-03 533. 1.0173-02 9.8821-03 V 524. 524. 1.249E-03 1.216E-03 524. 1.5201-03 1.480E-03 524. 1.2251-02 1.190E-02

64. 643. 8.669E-04 8.440-04 643. 1.045E-03 1.011-03 643. 9.5951-03 9.31E-03 KNW 762. 762. 7.538E-04 7.379.-04 762. 9.125E-04 8.884E-04 762. 7.895E-03 7.666E-03 890. 890. 7.3691-04 7.1741-04 890. 8.161E-04 7.945E-04 890. 6.693E-03 6.500E-03 LAIALLE SITE HETECRLOOICAL DATA 1/78 - 12/87 EP3PR10JAbdemi~mub1il-7I -1 F-13
  • - ~~~~~~~~~~~~~~~~~~~~

5 RevIionl Table F 7 (ContInued) iaxImunn Ollalte Finite Plume Gamma Dos Factors Based on 1 cm Dep at the Unrestricted Ate Boundary for Kr-89 OnwlI Uroetrlcted tevato dtstack$ kuei. KIX ModsLVenS) lea"e BrwE Levl 1lt" Direction Am BwW Radius I SWA Radius V VI" adius a IA Cuterl) (oters) ar~ dy r)/ i/s ec) (meters) (radlyr)(uCI/soc) (meters) (red/yr)<auI/sad)

M 036. 1016. 3.9048-04 3.7941-04 M136. 4.258-04 4.1396-04 036. 2.0511-03 1.9921:03 U 1378. 138. 2.8201-04 2.7418-04 1370. 2.9881-04 2.904-04 1378. 1.1511-03 1.118E-03 E 2408. 2408. 8.3L61-05 B.0721-OS 2408. 7.4031-05 7.195-05 2408. 2.0601-04 2.001E-0 4450. 4450. 1.5701-05 1.261-05 4450. 1.1531-05 1.1211-05 4450. 1.701E-05 1.653E-05 ES 1996. 1996. 1.0521-04 1.0231-04 1996. 9.2991-05 9.051E-05 1996. 3.031E-04 2.9441E-04 1465. 1465. 2.3651-04 2.2991.04 1465. 2.2401-04 2.1711-04 146S. 7.7621-04 7.5401-04 SSE 969. 969. 3.8918-04 .78UE-04 969. *.1U1-04 4.001-04 969. 1.846U03 1.7931-03 Su 838. 838. 4.1081-04 3.993-04 838. 4.36S-04 4.2431-04 838. 1.U 1E-03 1.781-03 829. 829. 3.4081-04 3.3121-04 029. 3.2531-04 3.1621-04 829. 2.0341-03 1.976E-03 IN SU uS 835. 835. 2.9211-04 2.8391-04 835. 2.7791-04 2.7021-04 835. 1.021E-03 9.9161-04 NNW 628. 628. 5.8301-04 s.67-04 628. 6.6001-04 6.415-04 628. 3.274E-03 3.1801-03 Sal 533. 533. 6.9131-04 6.7n20-04 533. 7.525E-04 7.3141-04 533. 4.592E-03 4.4601-03 Il 524. 524. 6.961E-04 6.7661-04 524. 8.2591-04 8.021-04 524. 5.96TE-03 5.7961-03 643. "S. 4.2ME5-04 4.1741-04 643. S.147M-04 S.31-04 643. 3.7461-03 3.63U8-03 762. 162. 3.5001-04 3.4021-04 762. 4.0351-04 3.9226-04 762. 2.5611-03 2.481-03 890. 890. 3.301E-04 3.2011-04 890. 3.4158-04 3.3191-04 890. 1.9661-03 1.9091-03 LAS1I S1ElENEIOSIOLICAL DATA 1/78 12181 EP8PROJ~odcmsA b&1-7F F 14

LA Revision S November2002 Table F.7 (Continued)

MaxImum Ofite Fnte Plume Gamma Dose Factors Bused on 1 cm Depth at the Unrestcted Area Bo'ndary for Kr-90 DOwtufl toou-tricted letwd(Sttk) teme Nixed NodCYant) Iblmue Crowd 1lo Ite.

Olrtfon AMes d Rtedful I MI Nedtts V "Alt Radius a CIA*

(tor) (eters) (wmdlrmugtl/sec) eter) curedlyr)1(uClisee) wtmrs) (rwtr)/ia C9tIt 1 N 1036. 1036. 6.M7-05 6.586E-05 1036. 5.199-05 5.047V05 1036. 3.2031-05 7542-05 1378. 1378. S319£E-05 3.102.-05 1378. 2.1611-05 2.09tE-05 1378. 2.2651-OS 2.1961-0S E 2401. 2408. 2.160E-06 2.09TE-06 2408. 9.1361-07 8.86SE107 2408. 5.8701-0? 5;6932-Ot F11E 4450. 4450. 1.1091;OT 1.0761-07 4450. 3.90E1-08 3.7921-08 4450. 1.8141-08 1;759-o8 I 1996. 1996. 4.131E-06 4.575E-06 1996. 2.562E-06 2.486E606 1996. 2.86SE-06 2.?77E-06 ESE 1465. 1465. 2.1341-05 2.072E05 1465. 1.5511-05 1.506E05 146S. 2.501-E05 2.4271-05 969. 969. 5.843E-05 5.673E-05 969. 5.3241-05 5.168E-05 969. 1.3651-04 1.324E-01 se 838. 838. 6.8631-05 6.6631-05 B38. 6.1741-05 5.9931-05 . 1.227E-04 1.190E-04 31 829. 829. 1.05SE-04 1.023E-04 t29. 5t057E-05 4.9091-05 829. 3.745E-05 3.635E-05 Su ISV 835. 835. 3.0621-05 2.921-os 835. 1.274E-05 1.237E-05 835. 1.835-05 1.T77-05 628. 628. 9.7541-OS 9.4701-05 628. 6.538t-05 6.3471-05 628. 1.4101-04 1.368t-04 VW 533. 533. 1.892E-04 1.8361t04 533. 1.525E-04 1.480-04 533. 4.8611-04 4.7131-04 524. 524. 2.1651-01 2.1011-04 524. 2.1851-04 2.121E-04 524. 8.4271-04 8.1701-04 WNW 643. 643. 1.018-04 9.883E-05 643. 1.00SE-04 9.787E-05 643. . 3.1411-04 3.04SE-04 Nu 762. 762. 6.6341-05 6.440E-05 762. 5.8151-05 5.6451-05 762. 1.308E-04 1.26TE-04 Nu 890. 890. 5.725E-05 5.558E-05 890. 4.336E-05 4.209 -05 890. 8.819E-05 8.5511-05 MAWSALL SITU PER LOMOICI DATA 1171 - 12187 EPSFROJt&dMIbunkII1-7F F-16

S LASA S Revislon 5 November 2002 Table F-7 (Continued)

Maximum Offslt. Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary or Xe.131m 4

Dowmind Unrstricted lehvatedStak) *olel" NIzsd NodsVwAt lele&&s grwuW Level Release Diretion Area boand adlus S SAA8 sodiu V van 3sdlu a Go" imeters) (ters) m^rsdyr)/1(CI/ssc) (mtors) urwd/yr)/uCIIsecI meters) (arodl/yr uClise4 N 1036. 1036. 1.6061-06 1.4731-06 1036. 1.827E-06 1.6791-06 1036. 1.6451-04 1.28SE-04 mu' 1378. 1378. 1.n77-06 1.s5 -06 1378. 1.7261-06 1.5531-06 1378. 1.072E-04 8.35411-5 NE 2408. 2408. 1.0861-06 9.3161-07 2408. 1.1361-06 9.126E-07 2408. 4.3471-OS 3.412E-05 EVE 4450. 4450. 1.9311E-07 6.617E-07 4450. 7.8581E-07 6.5501-01 4450. 1.623E-05 1.2791-05 I 1996. 996. 9.5721-07 I.4574-07 1996. 1.230E-06 1.058E-06 1996. 5.42aE-05 4.253E-05 ISE 1465. 1465. 1.3471-06 1.2151-06 1465. 1.7891-06 1.5601-06 1465. 7.9351-05 6.215E-05 SE 969. 969. 1.4721-06 1.3651-06 969. 2.4061-06 2.115E-06 969. 1.240E-04 9.696E-05 SSE 038. 838. 1.415-06 1.310E-06 838. 2.591-06 2.260E-06 838. 1.2211-04 9.597E-05 S 829. 829. 1.8591-06 1.14E-06 829. 1.966£-06 1.7271-06 829. 1.2321-04 9.639E-05 SSW 835. 835. 1.1961-06 1.1031-06 835. 2.003£-06 1.7551-06 535. 8.79JE-05 6.8SE-05 Su 628. 628. I.802E-06 1.6911-06 628. 4.34s5-06 3.281-06 628. 2.109E-04 I.U66-04 usu 533. 533. 1.859E-06 1.755E-06 533. 4.1611-06 3.5771-06 533. 2.324E-04 1.8131-04 W 524. 524. 1.8S0£-06 1.703E-06 524. 3.359E-06 2.972E-06 524. 3.0001-04 2.3351E-04 WNW 64. 643. 1.2631E-06 1.194E-06 643. 1.978E-06 1.7911-06 643. 2.4461-04 1.902E-04 mu 762. 762. 1.13SE-06 1.069E-06 762. 1.5611-06 1.43E-06 762. 2.003E-0 1.3601-04 NNW 890. 890. 1.191E-06 1.112E-06 890. 1.363E-06 1.2631E-06 890. 1.664E-04 1.295E-04 MAALLS S11l NIIE0SQOGICAL DAJA 1178 - 12/87 EPSPRA Odcm fbsa" 11-l71 -I F-10

1O.M.&F*

Reviston 5 Table F7 (Continued) November 2002 Maximum Offe,1. Finie Phm. Gamma Dose Factors Basod on cm Depth at the Unfrutricled Aa Bounday for Xe-133m aI DowWn Untsstrftetd twvmted(Stuck) Release Wniwd PaMYM mnt) ee &rmwI Laet etsse Direction AMe 0019d 1.41S 3 "3Al Rod4iw V "l Remus a aml (meter") (ters) IswoftYrfuttII3.) (motors) (adyr)/(ut1/2eO) (Ofters) (rudhWyrlIl/soc) f U 1036. 1036. 8.5571-06 .199E-06 1036. 9.8141-06 9.40tE-06 1036. 2.822E-04 2.410E-04 E 137. 1378. 7.91tE-06 7.509E-06 1578. 8.400E-06 8.0091-06 1378. 1.9011-04 1.6 M -04 WE 2408. 2408. 4.2461-06 3.9M1-.06 2408. 4.482-06 4.217E-06 2408. 8.032E-05 6.95CE-05' Elm 4450. 4450. 2.4c85-06 2.298t.06 4450. 2.4501-06 2.262E-06 4450. 3.108-05 2.7O61-05 E m. 1996. 4.24TE-06 4.0281-06 1996. 4.7211-06 4.433E-06 1996. 9.835E-0S 8.482E-05 ESE 1465. 1465. 6.614E-06 6.309E-06 1465. 7.393E-06 6.9781-06 1465. 1.432E-04 1.234E-04 St 969. 969. 8.229E-06 7.9031-06 969. 1.039E-0S 9.834E-06 969. 2.1891-04 1.879E-04 sit 838. 838. 8.070-06 7.758E-06 838. 1.060 -05 9.981E-06 838. 2.163E-04 1.856R-04 S 829. 829. 6.932E-06 6.660E-06 829. 8.449E106 7.9SE-06 829. 2.2011-04 1.8931-04 331 835. 6.5411-06 6.2761-06 835. 8.500E-06 8.036E-06 835. 1.5741-04 1.3541-04 SW 628. 628. 1.0591-05 1.020E-05 628. 1.637E-05 1.535E-05 628. 3.66t8-04 3.1401-04 Mg 533. 533.. 1.121E-0S 1.0811-05 533. 1.588E-05 1.490E-0 533. 4.005E-04 3.423E-04 U 524. 524. 1.0961-05 1.056-05 524. 1.504E-05 1.427E-03 524. 5.0391-04 4.2811-04 mmn 643. 643. 7.6481-06 7.3741.06 643. 9.9561-06 9.510E-06 643. 4.055E-O4 3.441-04 NVl 762. 762. 6.7141-06 6.526f-O0 762. 8.43SE-06 8.08BE-06 762. 3.3341-04 2.831E-04

'N 890. 890. 6.8551-06 6.594E-06 _. 7.S881-06 7.286E-06 890. 2.794-04 2.37m -04 LASALIE SITE MEOLOGIMA DATA I - 1218T EP8PROM~dcu~ubnal t -I F-17

Revision 5 Table F-I (Continued) November 2002 Uaxlmum Olisite Finite Plume Gamma Dos Factors Based on I cm Depth at the Unrestr~cted Ara Bounday or Xe-133 DoemInd Uestricted teIlvat&9S}sc) isle1s. Nixed dCent) Ile.441 G1aow Level 515...

b=ruotlen Ar Sd Sdius S 5 RadIus V VSA radius a GU&

("tes) (eters) (wmyr)I(uCIsec) thiters) (wd/yr)/(uCl/"c) (Seter (OVyrWIC 1Ise 11 1056. 1036. 7.010E-06 6.57YE-06 136. 7.9331-06 7.649-06 1036. 3.136-04 2.78-04 S 1378. 1316. 6.939E-06 6.629f-06 1376. 7.1491-06 6.J606-06 1378. 2.13U-04 1.9031O4 Ml 2408. 2406. 3.9691-06 3.7671-06 2408. 4.1061-06 3.59M-06 240. 9.0941-05 6.164-05 9UI 4450. 450. 2.4421-06 2.2M-06 4450. 2.354106 2.229E-06 450. 3.S40-05 3.1931-05 E 1996. 1996. 3.8411-06 3.671-06 1996. 4.3101-06 4.0U-06 1996. 1.1091-04 9.929£-05 ISE 1465. 1465. 5.7621-06 5.5341-06 1465. 6.5996-06 6.2713-06 1465. 1.6123-04 1.4438-04

  1. 969. 969. 6.U-06 6.4161-06 969. 8.9131-06 O.S81-06 969. 2.4501-04 2.18sE-04 SS£ 38. 538. 6.1641-" 6.1531-06 036. 9.21E-06 0.769-06 838. 2.41s-04 2.16-04 S 829. 529. 5.3331-06 5.1521-06 629. 6.9621-06 6.6271-06 629. 2.4761-04 2.212E-04 OSIJ 635. 635. 4.9691-06 4.1931-06 63S. 6.S981-06 6.26E-06 635. 1.7701-04 1.S21-04 Wu 628. 620. 7.79 1-06 7.5491-6 626. 1.3621-OS 1.2851-05 628. 4.0901-04 3.601-04 WSW S33. 533. 8.24E-06 7.9921-06 533. 1.3261-05 1.2521-05 533. 4.4471-04 3.951-04 U 524. 5z4. 6.1661-06 7.9191-06 S24. 1.220-05 1.1E-05 524. 5.5511-04 4.911E-04 WNW 6"3. 643. S.1S9-06 5.5411-06 6S. T.J5106 7.5741-06 63. 4.441-04 3.922E-04 mm 762. 762. S.1IE-06 4.9581-06 762. 6.531-06 6.3031-06 762. 3.6611-04 3.2331-04 Wm 890. 690. 5.340E-06 5.165E-06 890. 5.911E-06 S.7081-06 890. 3.080-04 2.ME-04 LASALL 51i NE6190N ICAL DATA 1176 - 12167 EPSPAOM&cuibAUul-71 -I F-18

L ASS O Revision 5 November2002 Table F-7 (Continued)

Maximum Olsffte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundty for Xe-135m Oowrd twaetteted fl1.e ted(Stok)

Wase NIIsd ROdWntl) Nelms Oetad Sevel hle m.

Dfretlen AM lOWd *NW I SSAI t pe311w V WIN df*s i . ,CIA (lster) (meters) (mrWYr)uCI/21m) (ters) (rediyr)l(s"ci'c) (wters) drftr CI/s )

N 1036. 1036. 1.396M-04 1.3491!-04 1036. 1.5981-04 1.5451-04 1036. 1.5311-03 1.475-03 M ,1378. 1378. 1.191E-04 1.11315-04 1378. 1.2741-04 1.2321-04 m78.. 1.0191-03 9.321E-04 IE 1oa8. 2408. 5.077E-05 4.0715-05 2406. 5.129-05 4.91-05 2408. 3.3161-04 3.390t-04 ME .4450. 4450. 1.919E-05 .8341!-Os 4450. 1.77M -05 1.71E-05 4450.: 8.7581-05 8.4451-05 E 1996. 1996. 5.672E-05 5.4831I-OS 1996. 5.675e-0s 5.4862-05 1996. 4.3m-04 4.1M-04

'ESE :1465. 1465. 1.005-04 9.7161I-05 1465. 1.0241-04 9."0-05 1465.. 7.3691-04 7.103E-04 SE 969. 969. 1.389E04 1.3431E-04 969. 1.57S£-04 1.5221-04 969. 1.262E-03 1.216E-03 SSE 838. 838. 1.402E-04 1.3561E-04 838. 1.591t-04 1.5381-04 838. 1.254E-03 1.21-03 S 829. t29. 1.tS3E-04 1.1441E-04 829. 1.23SE-04 1.194E-04 29. 1.341E-03 1.2921-03 5SU 835. 835. 1.1041-04 1.0681E-04 835. 1.260E-04 1.2181-04 835. 8.162E-04 8.4441-04 SU 628. 628. 1.9041-01 1.8411 E-04 628. 2.444E-04 2.3631-04 628. 2.173E-03 2.0941-03 U&V 533. 533. 2.063E-04 1.99515-04 533. 2.427E-04 2.3451-01 533. 2.479-03 2.381E-03 U 524. 524. 2.0331-04 1.9UI85-04 524. 2.5111-04 2.4n104 524. 3.0301-03 2.9371-03 WV 643. 643. 1.3631-04 1.3181s-04 643. 1.6871-04 1.631E-04 643. 2.286E-03 2.2011-03 INS 762. 762. 1.187E-04 1.141 E-01 762. 1.423E-04 1.3761-04 762. 1.806-03 1.7391-03

90. 890. 1.1611-04 1.122E-04 890. 1.2591-04 1.21TE-04 890. 1.482-03 1.4271-03 LASAIUS 1 n OOIICAL DATA 1M - 12h fP8PROJhdcm ukblk1-7l F-19

LASSE Revision 5 November 2002 Tbe F-7 (Continued) tMaxlnum Ollale Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary lor Xe-135 Ai Daumind IUratrited glevatmdUtec) Bet.a.. "pmmdfbdd(V.ant We.I.a Cireation Area ow4~ Bedius 3I I Beudims V YUVW.

tutors) (mters) (~c/yr)/(uC/mA) (intero) (nradjyr)/(utIJ/eC) (atere) 1uradvywr)(as) 1036. 1036. 8.165A-US 7.9026-05 1036. 9.3876-05 9.051-OS 1036. 1.302-03 1.257E 03 Nu 1318.

ww 1378. 1378. 7.171S-05 6.9401-05 7.8211-05 7.569-05 1378. 9.1781-06.86104 tug 2408. 2408. S.69-05 3.5501.S 2408. 3.876E-OS 3.7511-OS 2408. 4.0751-04 3.9371-04 4450. 4450. 1.928-0S 1.8a6-05 4450. 1.599E-05 1.8371-05 4450. 1.6251-04 1.5701-04 1996. 1996. 3.8381-OS 3.7141-05 1996. 4.0561-05 3.92SE-OS 1996. 4.869E-0 4.IM-04 1465. 1465. 6.1711-05 5.972E-05 1465. 6.539E-05 6.3281-05 1465. 7.0731-04 6.8331-04 SE 969. 969. 7.95310- 7.6976-OS 969. 9.3461-05 9.0441-05 969. 1.0S29-03 1.0171-03 SS 838. 838. 1.8451-0s 1.5931-O05 838. 9.367-05 9.06410S 838. 1.037E-03 1.0021-03 S 329. 829. 6.7191.05 6.5031-OS 829. 7.5871-05 .3421-05 829. 1.07U-03 1.041E-03 Su 835. 835. 6.3061-05 6.IO31OS 835. Y.636-05 M.391-OS 835. 7.699E-04 7.4381-04 USI 628. 428. 1.0391-4 L.OWE-0 628. 1.4099-04 1.3631- 62O. 1.7291-03 1.6701-03 533. S33. 1.1061-04 1.0719-04 533. 1.372E-04 1.32AE1- 533. 1.841-03 1.801E-03 524. 524. 1.082-04 1.0451-04 524. 1.374E-04 1.3295-04 524. 2.256E-03 2.179E-03 U

64S. 643. 7.538E-05 1.2961-OS S3. 9.395E-05 9.092-05 3. 1.775E-03 1.713E-03 NuD 762. 762. 6.654E-05 6.44U0-05 762. 8.0981-05 7.831-05 762. 1.466-031.415-03 kmMI 890. 890. 6.671£-OS 6.4S61.05 890. 7.327-05 7.0921-05 890. 1.247E-03 1.2041-03 LASALLE SITE NIEUL CAL DATA 178 - 12/87 EP8PRO Jbdmnibah/bI-7l F2 F-20

0 LASS -

Revision 5 Table F.7 (Continued) November2002 Maximum Offsits Finite Phne Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Am Bounday for Xe.137 DOMnild tbregtrfted twted(Itsnc*1 Iehuen MIwed Mhdu~mnt) hIst. Ord levat etMw Olrwctlcn Am leund RadIus I SIAS Radius V "IAl Radus 6a 3*31 aters) Cottern) (ursdlyr)1INCI/seel (asters) (adhTr)I(uCllstc) 1036. 1036. 4.78E0-05 4.6271-05 1036. S.242E-05 5.074E-05 1036. 3.4091-04 3.298E-04 N! 1378. 3.5 M1-05 3.471E1-0 1378. 3.6141-05 3.692-05 1378. 1.9731-04 1.9111-04 E 2408. 2403. 1.1531-05 1.1163-05 2408. 1.052E-05 1.0181-05 2408. 3.91-O 3.81E-05 4450. 4450. 2.5121-06 2.4321-06 4450. 1.9331-06 1.8t11-06 4450. 3.9491-06 3.821E-06 E sM. 1996. 1.420E-OS 1.3741-05 1998. 1.2851-05 1.2441-05 1996. 5.599105 5.4181-05 egg 1465. 1465. 3.0331-05 2.9361-05 1465. 2.9181-05 2.8251-05 1465. 1.3271-04 1.2841-04 969. 969. 4.743E-05 4.5911-05 9A9. 5.1881-05 5.0231-05 969. 2.991-04 2.8921-04 31 838. 838. 4.9261-05 4.769E-05 833. 5.357E-05 5.1861-05 838. 2.9701-04 2.8741-04 S, 829. . 4.07M-5 3.942-05 829. 3.9751-05 3.849E-05 829. 3.2951-04 3.1911-04 835. 835. 3.5211-05 3.40S1.05 8s5. 3.4241-05 3.3151E-5 1.7481-04 1.691-04 628. 628. 6.7m9E-05 6.3632-05 628. .9381-05 7.6tSE-05 628. 5.3331-04 5.161e-04 533. 533. 7.919E-05 7.6671-05 533. 8.829E-05 .548E-05 533. 7.1641-04 6.9321-04 524. 524.  ?.9M-05 7.762-05 524. 9.6081-05 9.3021.05 524. 9.223E-04 8.924E-04 I 643. 643. 5.0231-05 4.8631-05 643. 6.o0 -os 5.8096105 643. 6.00-04 5.8E-04 1g 762. 762. 4.1601-05 4.0 M1-05 762. 4.8411-0O 4.88TE-05 762. 4.228-04 4.09104 890. a0. 3.95E1-05 3.0881-05 890. 4.152E-OS 4.020E-05 890. 3.2791-04 3.1721-04 8

LASALLE 3311 PITIOKLOGICAL DATA IM7 - 1213 EP8PROJtdcm*ksa&uIH71 F-21

  • LRO* S Revislon 5 November2002 Table F-7 (Continued)

Maximum Ollst Finite Plum. Gamma Dose Factors Basd on 1 cm Depth l the Unrestricted Area Boupdary for X-138 siwmind Unretricted lewsted4Stec Reaine Nixed Nod.vent) Salem ground LevI blls.

Dirtion Ate" Round Radius S SIAR Radiu V Vs" Iadis .6 -a"

£mters) (ters) Crwdlyrsj(UCIIlPW (moters) Wadlyr)/lucilso) c(aters) (gredyr31(uIcsec)

(A 1036. 1036. 3.921-04 3.816-04 1036. 4.5231-04 4.3961-04 1036. 3.1781-0U3.3.4103 mu 1378. 1378. S.1601-4 3.0711.04 1378. 3.5361-04 3.4373-04 I37. 2.11711-03G2L051-03 ME 2408. 2408. 1.356E-04 1.3181-04 2403. 1.3791-04 1.3401-04 2408. 7.2441-02'.032U-04 EME 4450. 4450. 4.939E-OS 4.1991-0S 4450. 4.572E-05 4.4431-05 4450. 1.7691-04x71a-04 E 1996. 1996. 1.5401-04 1.497E-04 1996. 1.'351-04 1.4921-04 1996. 8.9211-048.6591-04 ESE 1465. 1465. 2.7661-04 2.609E-04 1465. 2.50E-04 2.725E-0 1465. 1.5321-031.4871-03 SI 969. 969. 3.9381-04 3.82804 969. 4.4081-04 4.2851-04 969. 2.6411-03 2.5641-03 SSE 838. 838. 4.0371-04 3.924E-04 838. 4.4E-04 4.3581-04 38. 2.6281-03 2.551E-03 S 529. 529. 34S7E-04 3.3601-04 829. 3.50E-04 3.4601-04 829. 2.09-03 2.7271-03 Ml 535. 835. 3.271E-04 3.1561-04 535. 3.532f-04 3.72(1-04 835. 1.U2E-03 1.741-03 Su. 628. 628. 5.698E-04 5.5381-04 628. 7.29-0 7.7-04 628. 4.546-03 4.4126-03 "SI. 533. 533. 6.144E-04 5.9731-04 533. 7.121£-04 6.9211-0 5. 5.206-03 5.0531-03 U S24. 524. 5.916E-04 5.809E-04 524. 7.381-04 7.11SE-04 524. 6.383-03 6.195E-03 LW 643. 643. 3.9861-04 3.87SE-04 643. 4.8876-04 4.7501-04 643. 4.7571-03 4.616E-03 mIu 762. 762. 3.457E-04 3.3601-04 762. 4.1311-04 4.0161-04 762. 3.7461-03 3.61SE-03 mu 890. 890. 3.3301-04 3.2361-04 890. 3.626-04 3.525E-04 890. 3.0691-03 2.978-03 LASALL I S NIT111OGICAL DATA 117 - 12157

.A EPSPRO/Odciaft8*41-71 F2 F-22

Revislon 5 November 2002 Table F-7 (Continued)

Maximum Offlt Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unetricted Ars Boundaty for Ar-41 40 owwlrd Ibmtricted fIwmted(Stft*1 Mo Pf *ad Rad.(Vut) lt.. frowid ."t #*left*

Otr seean Ar" wd ladfus I A 1sdltu V "IAt Padiua a 6313t Cwter) (tmute) (sredfyr)UtuIjn 9Inter,~o) (dr)(UClIiec) COMMe) C~dlr)jCUtlluec)

N 1036. 1036. 4.746E-04 4.5941 *04 1036. 5.5281-04 5.35l1-04 1036. 4.557E-03 4A11!-0)

11. 1378. 1378. 3."4f-04 3.82 44 1378. 4.4391-04 4.297E04 1378. 3.203E03 3.101E-03 ItC 2408. 240g. 1.92SE-04 1.863!404 2408. 2.0451-04 1.90-04 2408. 1.38E-03 1.343E-03 ENE 4450. 4450. 9.1411-05 8.848! -05 4450. 9.0511E-05 .m71-0 4450. 5.219E-04 5.032E-04 E 1m. 1m. 2.1101.04 2.043! -01 1996. 2.180E-04 2.1101-04 1996. 1.658E-03 1.6031-03 ESE 1465. 1465. 3.4801-04 3.368t -04 1465. 3.5931-04 3.41-04 1465. 2.459E-03 2.3511-03 SE 969. 969. 4.711-04 4.560! .04 969. 5.3201-04 5.1491-04 969. 3.71SE-03 3.5971-03 S 838. 838. 4.7611E04 4.608E -04 838. 5.3781-04 .205E-04 838. 3.6718-03 3.5541-03 S 829. 829. 4.168E-04 4.033! .04 829. 4.5318-04 4.3881.04 829. 3.823E-03 3.701E-03 S 835. 835. 3.994-04 3.866! .04, 835. 835. 2.7001-03 2.614E-03 SW 628. 628. 6.7111.04 6.495! .04 628. 8.591E-04 .315E-04 621. 6.139E-03 5.931!-03 USU 533. 5"3. 7.0891-04 6.862t -04 53. 0.22m .04 7.96e-04 533. 6.667E03 6.4"33-03 V 524. 524. 6.802E.04 6.5841 -.04 524. 4.930-04 O.2911-01 4.11-04 8.0251-04 524. 8.0STE-03 7.71WE-03 UWV 643. 643. 4.7081-04 4.5581 143. 5.7161-04 5.5331.0Z 643. 6.30CE-03 6.0991-03 NW 762. 762. 4.1231-04 3.991! .04 762. 4.9701-04 4.8111-04 762. 5.173E-03 5.00BE-03 MU 90. 89. 4.0251.04 3.8961l.04 890. 4.4471-04 4.3051-04 89. 4.374E-03 4,234E-03 LASAUi 8It111TEOMIOICAI. DATA W - 12187 EP8ROjAhdcm1&62b/S.7f F-23

Revslon November 2002 Table F-7a Maximum Ofisht Fnie Plum. Gauna Dose Factors Based on 1 cm Depth at the Restricted Ares Boundary for Kr43m

.1 Dowlid Restricted fIevated(Stack) Rel*"e mixed Rodef Ven) Release Croisd evel 3.1w.se Direction Area od gedus s SUA Radius V VWi Radius a lAR (aters) (mters) (edlyr)/(uCllsec) (motors) (mredlyrVIC/soc) astens) CWa4/ywn1/('lec)

N 1036. 1036. 4.7875-07 3.6 ON-07 1036. 5.2811.07 3.9521-07 106. 1.7851-04 1.3468-O kmI 1378. O.1515-O 6.5991-O IQ.

1378. 1378. 6.90SE-10 5.206£-07 1378. 1.1391-04 .50E-05 NI 1609. 1609. 6.8731-07 5.L2-0 1609. 7.291-o0 5.497-07 1609. 8.106 -05 6.112E-os Ila 1079. 1079. 4.1601-0 3.1371-C 1079. 8.0101-0? 6.0591-07 1079. 1.322-04 9.967E 0; a 1055. 1055. 3.4761EO 2.621-0t loss. 9.1811-01 6.923E-07 loss. 1.43U-04 1.11-04 518 5OS5. t05S. 4.3115.07 3.296E-07 1055. 1.1751-06 8.5561-07 1055. 1.3941-04 1.0511-04 1 969. 969. 3.54SE-0 2.6751-0? 969. 1.267t-06 9.5541-O0 969. 1.3331-04 1.80SE-04 Su1 698. 698. 2.41SE-07 1.21E-07 698. 1.646E-06 1.2411-06 694. 1.7713-04 1.337E-04 S 820. 820. 2.8031-07 2.1141-07 820. 1.047E-06 M.8951-07 820. 1.354E-04 1.01E-0 M~ 835. 835. 3.185E-07 2.401E-07 835. 1.071E-06 8.076 -07 835. 9.3261-05 7.032E-05 USu 628. 620. 3.1771-07 2.3951-07 628. 2.826-06 2.131E-06 620. 2.3051-04 1.738-04 533. 533. 2.6175-07 1.971-07 533. 2.614E-06 2.011t-06 533. 2.5681-04 1.9361-04 524. 524. 2.3271-07 1.7S41-07 524. 1.65aE-06 1.250-06 524. 3.3521-04 2.527-N4 MU 643. 643. 1.7145-07 1.292E-O0 7.2355-07 5.4551-07 "3. 2.7285-04 2.0575-04 762. 762. 1.1441-07 1.3S1-O0 762. 4.3911-O 3.3111-01 762. 2.2191-04 1.67E-04 "M 90. 890. 2.3975-07 1.80Y5-07 890. 3.3341-O7 2.5141-07 890. 1.8f1-04 1.374E-04 LASALLA 8118 WEl L 0OGICAL DATA 1/8 - 12J/

The restricted area boundary (RAB) was redellned In sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result GI this change of range, the dose factors were re-evaluated using the lowIng equation. Here, FR Is the resulling dose factor at the new range (I.e. 833). F, Is the value provided in the above ODCM tables (i.e.S. SBAR, V. VBAR, 6, GBAR). R Is the former RAS dCstance I.e. 1055). and R is the RAB distance I.e. 833).

g P<-16@4R.6 This analysis Indicates that the change Inrange would Increase th dose factor error by aprxImately 40%. Shce Othdillerence Iswoll within the expected error of th current factors, no further adjustment Inthe above factors Is considered necessary.

Based on Reference o Section F.2 and the formulas I Sections 6.8 and 8.6 of Appendix B.

EpspAOJ~ dcmbwsab" I-7f .F2

_F24

-0 Revision 5 November2002 Table F7a (Conthiued)

Maximm Offelte Finite Plum. Gamma Dose Factors Based on I cm Depth at the Restricted Area Boundty for Kr4Sm d

powtrd Restrlced Elhvetedttck) 1t,10... Nied Poalments flate.. orosii liv t eave Otretton Ar" Sao RadIus I SlAN Radtta V VIA* adius a CIAN (uteri) (ter) faredtyrl/Cutl/ubo) ("teri) (W9&Vy)/(ttUio/)

y 1036. 1036. 5.3.T4fe 5.601-05 1036. 6.6021-05 6.388t-05 1036. 9.660E-04 9.232.-04 K! m. 1378. 5.0631.05 4.89610 1378. 5.5141-05 5.3341-05 1375. 6.7761-04 6.4961-04 N2 1609. 1609. 3.6321-05 3.S12Xr0g 1609.

st" 3.84tE-0 3.720E-05 1609. 5.003E104 4.7m-04 ENE 1079. 1079. 4.3151-05 4.1?41i0 1079.. 4.569t-05 4.4191-o5 1079. 7.3453-04 7.0371-04 I toss. 4.5721os 4.4241: 1055. 5.0531-05 4.886E-05 1055. 8.1341-04 7.792E-04 ESE 1055. 1055. 5.7301-05 3.5441-05 1055. 6.2981-05 6.09M -05 1055. 8.0201-04 7.60YE-04 St 969. 969, S.596E-05 5.41SE-05 6.6101-05 6.3911-05 969. 7.7931-04 7.4701-04 SS1 69. 69. 6.4711-05 6.2631-05 698. 7.05E-05 7.64SE-05 698. 9.813E-04 9.404E-04 S 820. 820. 4.7561-05 4.603E-10 820. 5.386f-05 3.2081-05 820. 6.1031-04 7.769E-04

$SW 835. 835. 4.422E-03 4.27M -05 833. 5.3511-05 5.174E-05 IRIS. 5.6841-04 5.4501-04 Sut 628. 628. 7.281t-03 7.0461-0 628. 9.952E-05 9.618E-05 628. 1.2858-03 1.2311-03 WV 533. 533. 7.73r71os 7.07E-05 533. 9.7146-05 9.3881-05 533. 1.389E-03 1.3318-03 II 524. 524. 7.6011-05 7.356E-05 324. 9.705-05 9.385E-05 524. 1.687E-03 1.614E-03 WV 643. 643. 5.286-OS S.116-OS 643. 6.615-0os 6.39m o5 643. 1.3271-03 1.2M-03 RV 762. 762. 4.6681-05 4.51tE-05 762. 3.688E-05 S.503-0 762. 1.0941-03 1.0478-03 "N 890. 890. 4.63E-05 4.51 M105 tOS. 5.1421-05 4.9768-05 890. 9.2821-04 .8E-04 USRUS Sill MITIUMOIC*L DAtA IM7 12/8?

The restricted area boumdary (RAB) was redefined Insectors E and ESE to 033 and 848 from 1055 and 1055 meters, respective. 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. 933). F, Is the value proIded In the above ODCM tables 0.e. S. SOAR, V. VBAR, 0, GBAR). R s the former RAB distance i.e. 1055) and R Is the RAB distance (I.e. 833).

F 1.F 1J!!jIp1 .6 R

This analysts Indicates that the change Inrange would Increase th dose factor err by approximately 40%. Ohc t dfenc Is well within the expWed ror of th cuent factors, no luher adpstment Inthe ibove factors Isconsdered necessary.

E PSPR dawnihteabil-711.2 F-25

0 RevIslon 5 November 2002 TablO F-7a (Continued)

Maximum Oll1lte FIAIte Plum Gamma Dos Factore Based an cm Depth t the Restricted Ate Boundary o KwS Dan.ind Raltricted Eievatd(StWsl Balsm Mixed ".Vn) Release Groul d Level got Dlreatluin a SWd Radius S aUm 1.d41w V v5an (mtera) (iter) (.,s/rvyr)1(/( l/ I.). . tutoers) (Wadlyr)/IaC116) I SIAN/(uClu 1 1036. 1036. 5.5471-07 8.2651 ;&0Z 1036.' 9.8891-Or 9.563-or 1036. 1.0561-05 1.021E-05 KU 1378. 1378. 7.3091-07 7.0681 1378., LO677-O 7.8111-0? 1378. 7.4746-06 7.2211-06 UE 1609. 169. S.225E-07 S.0529 1609. 5.6151-07 5.43E-01 1609. 5.5S91-06 5.3751-06 E111 1079. 1079. 6.4631-07 6.2491 -A? 1079. 6.7070-or 6.481-O 1079. 8.0571-06 7.7911-06 E OSS. 1055. 6.8191-0? 6.5941:.Or 1055. 7.3851-07 7.1421-0? oss. 8.9231-06 6.62U-06 E5 1055. 1OSS. 8.484E-07 8.2041 lOS5. 9.1081-07 .8108E-07 1055. 1.801-06 8.517E-06 SE 969. 969. 0.386E-0? 8.11011-0? 969. 9.5831-07 9.267E-07 969. 3.5553-06 8.273£-06 SSE 698. 690. 9.8691-07 9.5431:.or 698. 1.1531-06 1.1151-06 691. 1.0721-05 1.0361-05 S 20. 820. 7.3331-07 7.0911 820. G.1S41-07 7.851-o 820. 8.86-06 6.5746-06 SSW 835. 835. 6.8576-0? 6.6301 835. 8.402-0? 8.124E-01 835. 6.270E-06 6.061-06

. gm 628. 628. 1.142E-06 1.104 1-06 628. 1.4941-06 1.4441-06 628. 1.401E-05 1.355E-05 Usu 533. 533. 1.2111-06 1.1711I1-06 533. 1.4331-06 I.36E-06 533. 1.510E-05 1.4601-05 u 524. 524. .I23-0 1.1341r-07 524. 1.4431-06 1.395C-06 524. 1.8241-05 1.7631-05 wm M/. 643. .L18SE-077.9151I..C7 64. 1.001-06 9.67010? 643. I.U6E-0 t.3a9-05 Ku 762. 762. 7.l921-0?'6.95411-07 762. 8.6941-0? 8.4071-o0 762. i.imE-OS 1.1U-OS muW 90. 890. 7.1231-07 6.8931 890. 7.rOf91-0 7.5901-or 890. 1.o011-oS 9.7781-06 LASALLE S1E MECO ICAL OATA 117 - 12/7 The restricted area boundary (RAB) was rdefined Insectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectivey. As a resu of tis change of range, the dose factors were re-evaluated using the ollowing quatlon. Here, Fa Is the resulting dose factor at the now range (.e. 833). f Is the value provided Inthe above 00CM tables (L.e. S. SBAR, V, VBAR, G,GBAR). R. Is the former RAB dislance (I.e. 1055) and R Is the RAO distance (Lea. 033).

FeF.4R!tp .

This analysis Indcates that the chang Intan would Incr the dose factor error by aroxkaatey 40%. Since this difference Iswea within the expected error of the currant factors, no frh aoJusjment in the bve fators Is considered necessary.

E.P&P5OJ~doaftikosti-71 -2 F-28

Revision 5 Novenber2002 Table fP7. (Continued)

Paxlmum Off1f1e Finks Plume Ganma Dos Factors Based on 1cm Depth a the Retited Arm Botndary for KW Dwugutyd Restricted 11mrsted(Stack) hileas Riod Roaertot) eease Crouwd ei Reieas Otrection Ath f3urd ladits 3 StAR 1.d41w V WAR Radius a 03*A, (meters) (meters) (malr )IWttltuec (meaters) (radty)l(9tille) (mr) (fr rfttllec N 1036. 1036. 3.2261-04 3.13SE-04 1036. 3.758E-04 3.6521-04 1036. .O8 -03 2.M -03 1378. 1378. 2.6m2-04 2.59m7-04 1378. 3.005E-04 2.920E-04 Im. 2.019E-03 t.9601-P ENE 1609. 1609. 1.901t-04 1.8P31-04 1609. 2.0381-04 1.981-04 1609. 1.4801-03 1.437E-03 EN 1079. 1079. 2.4301-04 2.36t1-04 t079. 2.5341-04 2.462E-04 1079. 2.19ZE-03 2.129E-03 ES 1055. toss. 2.6011-04 2.528E-04 loss. 2.7851-04 2.7M6E-04 1055. 2.4231-03 2.331E-03 105S. 3.211E-04 3.1251-04 toss. 3.412E-04 3.315E-04 toss. 2.40?E-03 2.3371-03 969. 969. 3.211E-04 3.1201-04 969. 3.612E-04 3.St1E-04 9t9. 2.3351-03 2.287E-03 698. 698. 3.8851-04 3.776E-04 695. 4.423E-04 .2982-04 698. 2.9851-03 2.898E-03 S 820. 820. 2.8811-04 2.8t 0-04 820. 3.11TE-04 3.029E-04 820. 2.467E-03 2.3961-03 835. 83. 2.7421-04 2.665E-04 835. 3.400E-04 3.305E-04 835. 1.7061-03 1.657E-03 "5V 628. 628. 4.6141-04 4.4841-04 628. 5.936E-04 5.769E-04 628. 3.901-03 3.M0-03

'V 533. 533. 4.880E-04 4.7431.04 533. 5.6831E04 5.523E-04 533. 4.251E-03 4.128E-03 Wu. 324. 524. 4.6751-04 4.5431-04 524. 3.708E-04 5.547E-04 324. 5.136E-03 4.981E-03 643. 643. 3.2241-04 3.133E-04 £43. 3.914E-04 3.8041-04 643. 4.001E-03 3.884E-03 No 762. 762. 2.823E-04 2.7431-04 762. 3.397-04 3.301E-04 rM. 3.261-03 3.t180-03 890. 890. 2.74tr-04 2.669-04 890. 3.031E-04 2.9451-04 890. 2.USE-03 2.483S-03 lAWUL SITE NE.0OL GICAL DATA 1/78 1218T The restricted area boundary (RAB) was redefined Insectors E and ESE to 833 and 848 from 1055 and 1055 meters. respectively. As a resull ol th1 change of range, the dose factors were re-evaluated using the bloowing equation. Here, Fn Is the resulng dose factor at the new range (I.e. 833). F s the value provided In the above ODCM tables (I.O. S. SBAR, V, VBAR, G. GBAR). R Is the former RAB distance (I.e. 1055) and R Is the RAB distance (e.833).

This analysis Indicates that the change In range would Increase the dose factor error by approximately 40%. Sin this difference Is wel within the xpected error of the currn factors, no further arlstment Inthe above factors Isconsidered necessary.

OMMPO1~dmhggbf&.79 F-27

0 Revision 5 November 2002 Table F-7a (Continued) axlmum 011fte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary lor Kr-B amaind estricted glevtdst -) Rleles Nixed Nodo(Vnt) eese Oruaxi Level Release Direction Area Boud mediun S 53* Radius V VBIl Radian a ClAR ttors) (ster.) (d/yr)/(atll9c (asters) (mra4/VrI)/w/e) (aters) Cored/yr)/(sl/soc)

N 1036. 1036. 5.602 -04 6.374104 1036. I.0031-03 9.769E-04 1036. *6.9M8-03 6.787E43 WEI 1378. 1378. 7.1111-04 6.9325.04 1376. 7.989E-04 .7m7704 1378. 4.94E-03 4.7981-03 WE 1609. 1609. 5.067 04 4.9R2-04 1609. S.485E-04 5.3401-04 1609. I 3.656-0 3.5525-03 6111 1079. 1079. 6.521-04 6.3551-04 1079. 6.769E-04 6.5891-84 1079. 5.3371-03 5.1103 I I05S. 1055. 6.9151-04 6.732-04 loss. 7.419E-04 7.2223-04 loss. *5.9071-03 5.737E-03 511 tOSS. 10S5. 8.5141-04 6.2881-04 1055. 9.030E-04 8.7901-04 105s. 5.851-03 5.689-03 SE 969. 969. 8.531E-04 8.3111-04 969. 9.511-E04 9.3171-04 969. 5.7121-03 5.5491-03 Su1 698. 698. 1.034E-03 1.0071-03 698. 1.1721-03 1.1411-03 698. '7.1931-03 6.9861-03 S 520. 820. 7.ME7-04 7.571104 820. 6.S13E-0 8.28E7-04 820. - S.9471-03 5.7nE-03 Ms 35. 835. 7.427E-04 7.231E04 635. 9.375E-04 9.1271-04 035. 4.167E-03 4.04SE-03 Su 628. 628. 1.246E-03 1.213E-03 628. 1.6011-03 1.5591-03 628. 9.3961-03 9.1261-03 USM 533. 533. 1.3141-03 1.2791-03 533. 1.52S1-03 1.48SE-01 533. 1.017E-02 92-03 U 524. 524. 1.249E-03 1.216-03 S24. 1.52G£-03 1.4801-00 524. 1.2251-02 1.1901-02 I'U "4. 63. 8.669E-04 8.4401.04 643. 1.045E-03 1.017E-03 64. 9.5951-03 9.317-03 IM 762. 762. 7.5801-04 7.371%-04 762. 9.12SE-04 8.AM1-0 762. 7.8951-03 7.666E-03 MN 890. 890. T.369E-04 7.1741-04 890. 8.1611-04 7.9451-04 690. 6.6931-03 6.5001-03 LASULE ITE NUh1G0LOICAL DATA 176 - IU8 The restricted area boundary (RAB) was redefined In sectors E and ESE to 8 and 848 from 1055 and 1055 meters. respectIvely. As a rsult of this change of range, the dose actors were re-evaluated using the following equallon. Here. FR Is the rsulting cose factor at the now range (I.e. 833). FR, Is the value provided Inthe above 00CM tables (.e. S. SBAR. V, VBAR, G.GBAR). R, Is the ormer RAO distance (I.e. 1055) and R Is the RAD distance (I.e. 833).

This anawlyb Indicates that change In range would ncrease m dose fr error by abxkmatoly 40%. Since to dmerence Is WeN Within the expect eror of the current fact, no further adjustment In te above factors Is considered necessary.

EPS13R10bdCui46881"Ib-79 -

F-28

LASft Revision 5 November 2002 Table F-7a (Continued)

Maximum Offille Finite Plume Gamma Dose Factors Based on 1 cmh Depth at the Restrted Area Boundary for Kr488 0orId Rtricted Iteveted(Stec ) 1.1.... Wined Pods(Vent) 14 mmee GIOa Ud LewI Rele .'.

Dtret en Ars ourd Nedf us I "At3 Nadlue V "At Nodlus a 03A3 (mters) (meter.) (sd/Vr)I(e~fjsec) (ms (mrad/yrIC~ttl/a) (tes) (fwdVyr)/(Itt/a¶4)

2. 0511_0_

_ . _9_1_03

-'I 1036. 1036. *3.9041-04 3.794l04 1036. 4.258E-04 4.1391WO4 1036. 2.0S1E-03 1.992E-03 ImE 1378. 1378. 2.8201-04 2.741E-04 I3s. 2.988E-04 2.904-04 1378. 1.151E-03 1.1181-03 WE 1609. 1609. 1.75CE-04 1.7011-04 1609. 1.654E-04 1.607E-04 1609. 6.564E-04 6.37SE-04 EVE 1079. 1079. 2.7031-04 2.6281-04 1079. 2.6191-04 2.5451-04 1079. 1.450E-03 1.409E-03 E 1055. 1055. 3.041E-04 2.956E-04 1OS5. 2.9721-04 2.8881-04 l0Ss. 1.569E-03 1.5241-03 ESE tOS5. tOss. 3.931E 04 3.821E-04 tOS5. 3.909E-04 3.8001-04 tO55. 1.6821-03 1.633E-03 5I 969. 969. 3.8911-04 3.7821-04 969. 4.1881-04 4.0701-04 969. 1.8461-03 1.7931-03 SSE 698. 698. S.333E04 5.1841-04 698. 5.971-04 5.631-04 698. 2.n2E-03 2.643E-03 S 820. 820. 3.4641-04 3.3671-04 820. 3.312E-04 3.2191-04 820. 2.0831-03 2.023E-03 SUW 835. 835. 2.9211-04 2.839E-04 835. 2.779-04 2.7021-04 835. 1.021E-03 9.9161-04 su 628. 628. 5.8301-04 5.86ft-04 628. 6.600E-04 6.4151-04 628. 3.274103 3.180E-03 UsW 533. 533. 6.913E-04 6.7201-04 533. 7.525E04 7.3141-04 533. 4.592E-03 4.460E-03 u .524. 524. 6.9611-04 6.7661-04 524. 5.259E04 8.028t-04 524. 5.96TE-03 5.796E-03 Mu 643. 643. 4.295E-04 4.174-04 643. 5.147E-04 5.0031-04 643. 3.7461-03 3.6381-03 Ill 752. 762. 3.5001-04 3.402E-04 762. 4.035SE-04 3.922E-04 762. 2.561E-03 2.48SE-03

. Ma 890. 890. 3.30tE-04 3.20M-04 890. 3.415E-04 3.319E-04 890. 1.96M -03 1.9091-03 LASALLE 3111 NETOMOLICAL DATA 18 127 The restricted area boundary (RAO) was redeflned In sectors E and ESE to 833 and 848 from 1055 and 1055 moters, respectely. As a result of this change of range. the dose factors were re-evaluated using the loftowMg equation. Here. F. Is the resuffing dose factor el the new range (I.e. 833). F Is the value providad In the above 00CM tables (.e. S. SOAR, V. VOAR, G,GOAR). R. Is the former RAO distance (.e. 1055) and R Is the RAG distance (I.e. 833).

FF416x1 .5 This analysis Indicates that he change In range would ncrease Mhdose factor error by approximatel 40%. SInce this difference Is wet within the expected error of the curent factors, no further adjtment In the above factors Is considered necessary.

EP8PlOJAtdewnbahI-7I -

F-28

I 0 Revision 5

  • November 2002 Table F-7a (Continued)

Maximum Oflslte FinIt Plume Gamma Dose Factors Based on can Depth al the Restricted Are Boundary for Kr-SO

.4 DowIid Sostrieted leske1d(stscki et"es tMed veds(Vent) hi....e OraaiW Level &*I"&*

Sireotimn Area Roun Iadlus 3 586 Radis V V9A1 Radius a GMI (saster.) (ater.) (radytr)/(CtIsec) (aters) (mrad/yr)/(uC/sea) (aister.) (d/yr)/(C1sG)

M 1036. 1036. 6.7iSE-oS 6.58m-OS 036. 5.199E-O5 5.0471-05 1036. 8.2031-O 7.9S410s UKI 1370. 1378. 3.1951-05 3.1021-05 Isla. 2.1611-05 2.0UE1-OS 1378. 2. 26S-05 2.1961-0 ME 1609. 1609. 1.2.01-05 1.2031-OS 1609. 6.99-0 6.7451-06 1609. 7.3576-06 T.134E-06 111 1079. 1079. 3.71IM-05 3.61CE0OS 1079. 2.SIOE 0S 2.4641-OS 1079. 4.5771-05 4.43BIgGS 6 loss. loss. 4.582E-OS 4.44U8-OS 1055. 3.2571-05 3.1621-OS 105S. 6.8119-0S 6.6101-05 ESE 1055. 1055. 6.3151-05 6.130E-05 lOSS. 5.0711-OS 4.9221-OS toss. 1.081U-04 1.046E-04 SE 969. 969. 5.843E-OS 5.6731-05 969. 5.324E-OS 5.1680OS 969. 1.3651-04 1.324.-04 551 698. 698. 1.170E-04 1.136E-04 698. 1.1031-04 1.070E-04 698. 2.5781-04 2.500E-04 S 820. 820. 5.233E-05 5.0811-05 820. 3.188E-05 3.771E-05 20. l.OSE-04 1.075E-04 S~U '35. 835. 3.062E-OS 2.972E-05 835. 1.274E-05 1.2371-05 $35. 1.8351-05 1.7791-05 Su 628. 628. 9.7541-05 9.4701-OS 628. 6.5381-05 6.3471-05 628. 1.4101-04 1.368E-04 Usu 533. 533. 1.892E-04 .8U6E-04 533. 1.525E-04 1.401-04 533. 4.611-04 4.13E-04 VI 524. S24. 2.165E-04 2.1016-04 524. 2.1051-04 2.121E-04 524. 8.421E-04 8.1701-04 WNWU 643. 643. 1.0181-04 9.831-OS 613. 1.08-04 9.787-OS 64. 3.1411-04 3.0451-04 mm 762. 762. 6.6341-05 6.4401-OS 762. 5.1SE-OS 5.6451-OS 762. 1.3061-04 1.267E-04 NN5W a90. 890. S.72SE-OS 5S.SS8-OS 890. 4.3361-05 4.209E-05 890. 8.8196-05 8.551E-OS LASALLE SITE NITEIOLOICAL DATA 1/78 - 1287 The rstdcled area boundary (RAS) was redefinad In sectors E and ESE to 833 and 548 from 1055 and 1055 moters, espectvel. As a result at this change of range, the dose factors were reevaluated using the oflowing equation. Here, F. Is the resulting dose factor at the new range (i.e. 33). f Is the value provided In the above 00CM tables (i.e. S. SBAR, V. VBAR, G, GBAR). R, Is the ormer RAB distance (.e. 1055) and R Is the RAS distance (I.e. 833).

F;wP4-jxpRw@.5 R

This anaysi Indicates that the change In range would Increase tho dose factor error by a aroxknaty 40%. SInce ths differenc Is wll within the expected error of the current factors. no lumrer adjustment In the above factors Isconsidered necessary.

EP8PR OS'dca&4a& uifr-7f -3 P-30

S LASAO RevIsonW 5 November2002 Table F7a (Continued)

Maximum Offafte Finite Plume Ganma Dose Factors Based on 1 cm Deplh at the Restricted Am Boundary for Xe131m 4

pomwtnd botricted Elmst(teck) os"* Plited ftft(Veft) Riolm. Onoteu mi ftlow WI us olpttln Jm lan) (meteno) 3 n1* Ited~w V "l NedIts a CIN (ad/yr)/IjiIm) (ustor) Cwv41yWfl(UCl12#C) I N 1036. 1036. 1.606E-06 1.4731-06 I 1036. 1.827E-06 1.679E-06 1036. 1.645E-04 1.2831-04 NOR 17. 1371. .7E7806 1.512-06 1378. 1.7268-06 1.55SE1-0 1378. 1.02-04 8.3848-05 WE 1609. 1609. 1.3278-86 1.16it-06 ! 1609. 1.4098-06 1.239E-06 1609.  ?.747E-05 6.0648-03 EVE 1079. 1079. 1.2541-06 1.148-066 1079. 1.612n-06 1.1238-06 1079. .225E-04 9.5631-as I 1055. l055. 1.2491-06 1.150E-06 105S. 1.8061-06 1.592E-06 1oss. 1.376-04 1.073E-04 Est 1055. 1.566E-06 1.442t-06 10SS. 2.270E-06 1.99E-66 1s5. 1.298t-04 1.0141-04 St 69. 969. 1.4m-06 1.36SE-06 969. 2.406E-06 2.115E-06 969. 1.2401.04 9.696-05 35 69b. 1.5661-06 1.46t8-06 698. 2.969-06 2.597E-06 698. 1.624E104 1.267E-04 S 820.

- t. 820. 1.238E-06 1.15E1-06 820. 1.9831-06 1.742E-06 820. 1.2531-04 9.821-05 5:" *65. 835. 1.1968-06 1.103-E06 835. 2.0031-06 1.755E-06 835. 8.79BE-05 6.88se-05 MI 628. 628. 1.802E-06 1.691E-06 628. 4.3451-06 i.ni-06 628. 2.109E-04 1.646E-04 Ms 533. 533. 1.859E-06 1.755E-06 533. 4.161-E06 3.5771-06 533. 2.3248-04 1.813E-04 U 524. 524. 1.8001-06 1.7031-06 524. 3.359E-06 2.972E-06 524. 3.0C00-04 2.333E-04 WiNW 643. 643. 1.2638-06 1.1941.06 643. 1.9761-06 1.791E-06 643. 2.446E-04 1.902E-04 Nu 762. 762. 1.135f-06 1.069E-06 762. 1.5618-06 1.4378-06 762. 2.005E-04 1.560E-04 Min 890. 8M0. 1.191E-06 1.1121-06 890. 1.363106 1.2631-06 890. 1.664E-04 1.2ME-04 WLLSAS 5Itt MlC0101ICAL DTA 1175- 12187 The restricted area boundary (RAB) was redefined Insectors E and ESE to133 and 949 from 1055 and 1055 meters, respecilvely. As a result t this change of range, the dose factors were re-evaluated usn the foffowlng equation. Here. Fn Isthe resulting dose factor at the new range (.e. 833). F Is the value provided Inthe above ODCM tables (I.e. S.SOAR. V. VBAR., , GBAR). R. Isthe onarer RAO distance (.e. 1055) and R Is the RAO distance (I.e. 833).

This analysis Indicates that the change in range woukJ Increase th dose factor error by aproimately 40 Sce this df1serence Is wel within the expected er of th current factor, no f"er dsMent Inthe above factors ISconsIled necessaty.

EPSM/aJdemibeehAI1.7 3 F-31

LA8AS Revision 5

. November 2002 Table F-7a (Continued)

Maximum Ollsile Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for X-133m II DeaaaInd estricted ElvatedStack) lt"$a Nixed NadsIV~nt) Ralesa. round eel .1.".

Direction Area ound adlus SI SA Ra4dius v WmR dius a GM (ctars) ("stern) (ur.4Y1r)I(uCI/6 ) Cstes) (alr)/CeCi/koc) (aters) (arsdw )uCIsac M 1036. 1036. 6.5576-06 .199E-06 1036. 9.8146-06 9.407E-06 1036. 2.8221-04 2.4108-04 311 1373. 1378. 7.917E-06 7.S09E-06 1378. 8.4001-06 8.0091-06 1378. 1.9011-04 1.6=-4O MI 1609. 1609. S.7n39a06 S.4236-06 1609. 6.0931-06 5.768-06 1609. 1.3891-04 1.1951 ENE 1079. 1079. 6.4861-06 6.2051-06 1079. 7.141E-06 6.711-06 1079. 2.1211-04 1.8151-04 1 1OSS. 105S. 6.7701-06 6.4921-06 1055. 7.9111-06 1.5OE-06 loss. 2.3688-04 2.024U-04 ESE 1055. 1055. 6.4816-06 .1321-06 1OSS. 9.8191-06 9.35SE-06 1055. 2.276E-04 1.f511-04 SE 969. 969. 0.2291-06 7.9031-06 969. 1.091-0S 9.1341-06 969. 2.109E-04 1.8791-04 SSE 698. 698. 9.3631-06 9.021E-06 698. 1.2501-05 1.1811-0OS 698. 2.81SE-04 2.4091-04 s 820. 820. 6.991E-06 6.718E-06 820. 6.532E-06 8.075E-06 820. 2.2361-04 1.923E-04 SSU 835. 835. 6.541E-06 6.276E-06 83. O.51O-06 8.0361-06 835. 1.5741-04 1.3541-04 SU 628. 628. 1.0591-05 1.0201-05 628. 1.6371-05 1.S35E-0S 628. 3.665-04 3.1401-04 USJ 533. 533. 1.121E-OS 1.811aiOS 533. t1.5M-OS 1.49GE-aS 533. 4.0051-04 3.423E-04

_524. S24. 1.096-0S 1.6os- S24. 1.5041-0s 1.427E-05 524. 5.0391-04 4.2616-04 W11U 6U3. 643. 1.6481-06 .3141-06 643. 9.956E-06 9.5101-06 64. 4.OSE-04 3.4411-04 mU 762. 762. 6.7748-06 6.5261-06 762. .351-06 8.048E-06 762. 3.33Q4-04 2.8311-04 Mli 890. 890. 6.8551-06 6.5941-06 890. 7.5881-06 7.2861-06 590. 2.7941-04 2.3713-04 LASULL SITE WIItoLGICAL DAT 117 - 12/87 The restricted area boundary (RAB) was redaiined In sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of his change of range, the dose factors were re-evaluated using the ollowing equation. Hete. FR Is the esuling dose factor ai the new range (I.e. 833). F Is the value provided In the above ODCM tables (i.e. S. SBAR, V, VBAR, , GBAR). R. Is the forar RAB distance (I.e. 1055) and R Is the RAB distance

(.e. 833).

FaasOFaIZIOX0.5 This analysis Indicates Ihatthe change In range would Inrease t dose factor error by aproxinately 40iL Since this dfference Is weE within the expected er of th current factors, no further adjustment In the above lactors Is considered necessasy.

E136PRO~bilcmhasisib-71 -a

-F-32

Revlslon 4 November R02 Table F.7a (Continued)

Maximum Offnlts Finite Phime Gamma Dose Factors Based on I cm Depth at the Restricted Arn Boundary for Xo133 Level Sc~~~m.

Orued DowMCI Retricted elevetedt(stec) ftev* Mixd ROdet"sot) Role"* Cro eve1 em, Otrection Am ourd adtus

  • SA ho V VIA*

(ter) (aed/yr)j(Ifs.!) ustes) (wsdyr)t(W111s I cue" (wav ltuti:1ne

  • 1036. 1036. T.01E-06 6.t"th' 06 1036. 7.9331-06 7.649!; Red6. 3.136I04 2 ME-WE 1378. .1378. 6."9E-06 6.6i*06O 1m. 7.1491-06 6.860E; 096 1m. 2.132-04 1.9031-04 WE 1609. 1609. 5.088E-06 4.853E-06 1609. 5.323E-06 3.076E. '06 1609. 1.62E-04 1.3M-04 ENE 1079. 1079. 5.306E-06 S.108E-06 1079. 6.04SE-06 S.769E' 1079. 2.362-04 2.10l-04 E toss. toss. 5.535E-06 3.340E06 toSS. 6.7684-06 6.452E! 6 105S. 2.632M-04 2.3381-04 ESE 1055. 1055. 7.0161-06 6.7691-06 1053. 8.56-06 8.169E .06 105. 2.5431-04 2.266E-04 SI 969. 969. 6.6411-06 6.416E-06 969. 8.9781.06 8.58E 969. 2.450t-04 2.1851-04 se 698. 698. 7.217E-06 6.994E.06 698. 1.07SE-0 1.0211' .as 698. 3.132E-04 2.71-04 S 820. 820. 5.369E-06 5.18SE-06 820. 7.0241-06 6.687! '06 820. 2.5151-04 2.246E-04 SSU 835. 835. 4.9691-06 4.793E-06 835. 6.5981-06 6.266! .06 835. 1.77004 1.5822-04 Su 628. 628. 7.798E-06 7.5491-06 628. 1.362E-03 1.28tE .05 628. C.0 -04 3.640O-04 VI 533. 533. 8.2451-06 t.992E-06 533. 1.326E-OS 1.252E' .05 33. 4.4471-04 3.9511-04 U 524. 524. 8.1661-06 7.919E-06 524. 1.220E-05 1.1641E.05 524. 5.5511-04 4.9112-04 WIN 643. 643. 5.715t-06 S.541E-06 643. 7.8me-Os t.974t..06 643. 4.4441-04 3.922E-04 M 762. 762. 5.1171-06 4.9582-06 762. 6.5381-06 6.303!'.06 762. 3.6611-04 3.2332-04 M 890. 890. 5.340t-06 .165t-06 890. 5.911-06 5.?081 .06 890. 3.080E-04 2.MR-04 LASAIIE nITE ETIcOL00ICAIDATA 1178 - 12/8T The restricted area boundafy (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectIvely. As a result o tis change of range, the dose factors were re-evaluated using the toing eqatlon. Here. Fn Is the resulng dose factor at the new ane .e. 833). F Is the value provided In the above ODCM tables (.e. S. SOAR, V, VOAR, 0. GBAR). R Is me former RAO distance .e. 055) and h is e RAB distance

(.e. 833).

F,'F,-Jsxpl .5 R

This anaIs indcates that he change n range would Increase the dose factor error by approximately 40%. Sc s difference Is wel Within the expected aror of The current actors, no fuuther adlustment In above factors Is consklered necesary.

EP$PR0Jbdcm&hsski171 -3 F-33

0 0 Revision I November2002 Table F-7a (Coatlnued)

Uaxnumn Olisite Finite Phune Gama Do Factors Basd on 1 cm Depth at the Restricted Are Boundary for X-135M J1 huiund estricted Elvted4Stack) les Nixed Nodot Vent) Beteas. Crund Level Ms" DirecaAMn Aea Rdadius I S 1 Radius V Vs"1 3.81 a an ters) (moters) Carady)/(UCI"c) Casters) (WUray/(aiI1sa.) (t") (awd/rUCI/sec 1 IO. 1036. 1.396E104 491-" 1036. 1.591-04 1.55-04 1036. 1.531E-03 9.82S-IM ES 1378. 1378. 1.151104 .115-04 1378. 1.271 -04 1.2321-04 1378.

NI 1609. 16409. 8.0461-05 .7191-OS 1609. 8.2601-05 1.9851.05 109. 7.0335-0 6.77E-04 SI 1079. 1079. 1.0241:04 9.8981.05 1079. 1079. 1.147E-03 1.15-03 E IOSS. 10SS. 1.121i 04 1.09ie04 1055. 1.6UE-04 1.018104 1055. 1.2531-03 1.2071-03 1S 1055. 1055. 1.4111-06 I.3458'04 1055. 1.4901-04 1.421E-04 loss. 1.256E-03 1.211-03 St 969. 969. 1.3691-04 1.34 -04 969. 1.5751-04 1.522t 04 969. 1.2621-03 1.2161-03 SSE 698. 698. 1.692-04 1.6361-04 698. 2.1831-04 I.I441-0 1.9SSE-04 1.6901-04 696. 1.667-03 1.606-03 S 820. 820. 1.196-04 1.1571-04 820. 1.251E-04 1.2091-04 20. 1.3631-03 1.3141-03 61W 635. 835. 1.1041-04 1.06U1-04 835. 1.2601-04 1.2181-04 35. 8.762E-04 6.4441-04 Ci 628. 628. 1.9041-04 1.8411-04 628. 2.44£ 04 2.3631-04 628. 2.1731-03 2.094E-03 Ms1 533. 533. 2.0636-04 I.951*- 533. 2.4271-04 2.3451-04 533. 2.4791-03 2.388-03 U 524. 524. 2.033E-04 1.9661-04 524. 2.511E-04 2.4271-04 524. 3.050E-03 2.9371-03 WNW 643. 643. 1.363-04 1.3181- 4. 1.6871-04 1.6311-04 64. 2.2861-03 2.2011-03 No 762. 762. 1.1871-04 1.14U-04 762. 1.4231-04 1.3761-04 762. 1806103 1.391-03 IWU 890. 890. 1.1611-04 1.1221-04 890. 1.2591-04 1.2171-04 890. 1.4821-03 1.4271-03 LASALE ITE IEh1ROL0GICL DATA - WAY The restricted area boundary (RAO) was rdened In sectors E and ESE to 833 and 48 fron 1055 and 1055 moers, respectively. As a rsult of this change of range, the dose factors were r-evaluated using m lowing equation. Here, FR Is Oh resulting dose actor at the new range (.e. 3). F Is the value provIded Inthe above ODCM tables (i.e. S, SBAR, V. VBAR GBAR). , R, Is e former RAB distance (e. 1055) and R Is the RAS distance (L~e. 833).

FFg,4jep °l.6 This analysis Indicates ta te change In range would Increase the dose factor ror by aWroximatey 40%. Since ts dfference Is wag within the expected er o Ihe current factors, no lurther adjstment In the above factors Is considered necessary.

EPOPRObdmsss/I7I -

F-34

0 Revsluon9 November 2002 Table F-7 (Contfnued)

Maximum Offelle Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Arn Boundry for X*135 0osnIr Rtrfeted Elovoted(Stnc&) Nolm. PRiRod Ro(Vsntl Mte"e Crmed lowI 1elm.

  • Irectlei Am~ lourW Rad1us 3 "IAl NedIts V "At R

(voters) (voters) (mradtyv)j(u~l~vec) (mters) (adr)I(uClf/ec)

U 1036. 1036. 0.165E- 7.9022-0 2036. 9.3879-05 9.0851-05 1036. N1.302E-03 1.23TE-03 N 1378. 1378. 7.17t1-05 6.9402-03 1378. 7.8211-03 7.5691-03 1378. -N9.1 0 6.681-04 W1 1609. 1609. S.1401.03 4.97U05 1809. 5.463E-03 5.2866-05 1609. -A.8019-04 6.570-04 EVE 1079. 1079. 6.1391-05 5.942E-03 1079. 6.475- 6.2671-05 1079. 9.912E-04 9.573E-04 6 1035. tos5. 6.4936-05 6.234E03 loss. 7.133S-05 6.92041-0 1OSS. 1.097E-03 1.060E-03 ESE 1055. tOS5. 8.130E-05 7.869E-05 1055.

1053. 8.901E-03 8.61T7-03 1055. .1.083E-03 1.046E-03 SE 969. 969. 7.933E-05 7.697t-05 969. 9.346E-05 9.0441E-0 969. 1.032E-03 1.0171-03

$S1 698. 698. 9.205-os 8.910E-OS 698. 1.117E-04 1.081E-04 6". :1.321E-03 1.2M6E-03 S.' 620. 820. 6.782ES-0 6.564E-03 820. t.6UE-0S 7.4191-03 820. I.0931-03 1.056E-03 59W 833. 833. 6.306E-03 6.1031-05 7.6366-03 7.389E-03 835. 7.6M-04 t.4396-04 Su 628. 621. 1.039E-04 1.0062-04 628. 1.4091-04 .3631-0 628. 1.7M-03 1.67E-03 113 533. 533. I.*108-04 1.071E104 533. 1.3721-04 1.328E-04 533. .1.8541-03 1.801E-03 U 524. 524. 1.0821-04 1.048.04 524. 1.374E-04 1.329E-4 324. 2.236E-03 2.1291-03 iUU 643. 543. 7.53S-03 7.296t-03 643. 9.395E-05 9.092E- 643. 1I.M -03 1.713-E03 NV 762. 6.654E-05 6.440E-03 762. 8.099-03 7.83E-QS 762. 1.4661-03 1.415E-03 "NW M9. 890. 6.61E-05 6.456E-03 Mv. 7.3271-05 7.09M1-03 890. 1.2471-03 1.2042-03 LASAIE ITE PETORLOICAL DATA 1/T - 1218 i 0

I The restricted area boundary (RAB) was redefined In sectors E ard ESE to 833 and 8B from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the fowing equation. Herk. FR Is the resulting ose factor at the now range P.e. 833). F Is Me value provided In the above 00CM tables .e. S. SBAR, V. VBAR. G. GBAR). R Is he ormer RAN distance .e. 1055) ard R Is the RAB distance (I.e. 833).

Fh-Jex1.6 This anatys Indcates that the change In range would Increase te dose factor rror by approximately 40%. B1nce thIS difference Is wel wIhIn the expected error of te current factors, no further adpstment In the above factors I consideed necessay.

SPISPRO1~dembsolleffi-71 -3 F-35

0 Revision 5 November 2002 Table fNa Continued)

Maxuwm Olislie Finlte Pluao Gamma Dose Factor. Based on I cm Depth t lh Restrted Are Boundary tor Xe-137 cosauutd estricted Klevatedtacmk) Release Nixed NodetVant) Release Grundv i Release Direction Area sound Radius S SAAR mdi.s V vIan Rmdius A GEAR (meters) (ette) (rd.Vr/(LCi/sQC) ("etars) (md/YeMU(Cl/sec (seters) (wadlyr)u/(I~sm)

M mu' 1036.

1378.

1036.

1378.

4.78U-05 3.585E1-5 4.27jE-05 3.4711-OS 1036.

1375.

5.2421-05 5.0741-05 3.8141-OS 3.692E-05 1036.

1378.

3.4091-04 3.29A1-04 1.9751-04 1.9111-04 t

MI 1609. 1609. 2.20EGS 2.2091-05 1609. 2.1851-OS 2.11SE-05 1609. 1.1661-04 1.1281-04 LIII 1079. 1079. 3.342E-OS 3.236E-OS 1079. 3.282E-OS 3.1778-05 1079. 2.4371-04 2.35CE 04.

a loss. loss. 3.E41-0S 3.6221-05 1D55. 3.7161-OS 3.9M-OS 2.6251-04 2.S4U-04 Egg 1055. 1055. 4.211-05 4.6731-05 1055. 4.8711-OS 4.7151-05 1055. 2.76SE-04 2.6761-04 SI 969. 969. 4.741-OS 4.5911-05 969. S.181-OS 5.023L-OS 969. 2.9591-04 2.892E-04 SSE I 698. 695. 6.2731-0S 6.0731-05 698. 6.9831-OS 6.7601-OS 698. 4.3291-04 4.1898-04 S 820. 820. 4.133E-OS 4.002E-05 520. 4.0421-OS 3.9131-05 520. 3.373-04 3.2641-

'SSW 835. 3S5. 3.521E-05 3.40-05 5s5. 3.4241-05 3.3151-OS U5. 1.74U-04 1.691E-04 Vw 620. 628. 6.7791-05 6.S631-05 628. 7.9381-05 7.608E-05 628. 5.3331-04 5.1E-04 Uu' 533. 533. 7.9191-0S 7.667-O0S 533. 0.829E105 8.5481-05 533. 7.16.104 6.932E-04 U S24. 524. 7.990E-0S I.7U-O05 524. 9.6081-05 9.3021-OS 524. 9.223-04 6.924E-04 ilNUl 643. 643. 5.0231-05 4.8631-05 643. 6.090E-05 5.596E-05 643. 6.002E-04 5O.50E-04 kW' 762. 762. 4.160U05 4.0281-05 762. 4.41SE-05 4.6871-05 762. 4.281-04 6.0901-04 mum 890. 890. 3.9851-OS 3.055E-0S 890. 4.A521-OS 4.020E-05 690. 3.279-04 3.7nE-04 LASAULE SITE E1IIORLOGICAL DATA 117i- 12J87 The restrIcted area boundary (RAS) was redelined In sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectivelY. As 8 result of tIs change of range, the dose factors wore re-evaluated using the following equation. Here. FR Is the resulting dose factor at the new rango (.e. 833). F Is the value provided In the above 00CM tables (I.e. S. SBAR, V, VBAR, 0, GBAR). R. Is the forner RAS distance (I.e. 1055) and R Is the RAS distance (I.e. 833).

FP8 1JP--°Ixp1 .5 This analysis dicates tha the change In range would Incease the dose factor aorby appWxnaWly 40%. Since Ws difference Is wag witin the expected error of the current factors, no further adustiment Inthe above factors Is cosiered necessary.

ftuw'lwaoaisamasiuu -1J F-38

0 _ Revison 5 November 2002 Table F.7m (Continued)

Maxitum Off1te Finite Pume Gomma Dose Factors Bosed on 1 cm Depth St the Restricted Area Bounday for Xe-138 cwaitl Restricted Elvted(tek) *o1le. Ruxed RaweVut) 10les.. armwd Level 1#"

DirectIon Ame Otrd Radlus I "PR Ruddtus V V"Aft Nedus a WR (meter) (t) (wedlyr~t(UC1te") ("ltern) (rWlVyr)/(Wt1M1c N 1036. 1036. 3.926E-04 3.6161-04 1036. 4.5231-04 4.396-04 1036. 3.17M803 3.0U-a WE 1376. 1378. 3.160E-04 3.0OM-04 1378. 3.536E-04 3.4371-04 1373. 2.t17-03 2.0SSE-OS 1609. 1609. 2.19t-04 2.136E-04 1609. 2.2m-04 2.2081-04 1609. 1.45TE-03 .4141-03 El 1079. 1079. 2.88tE-04 2.8061-04 1079. 2.9961-04 2.9121-04 10J9.. 2.38-03 2.3131-03 toss. 10SS. 3.1601-04 3.079E-04 toss. 3.2-04 3.231E-04 toss.

1055.

2.600-03 2.5241-0 loss. 1055. 3.961E-04 3.850E-04 lOSS. 4.149E-04 4.032E-04 2.618E-S 2.541E-03 SE 969. 969. 3.938t-04 3.828E-04 969. 4.401E-04 4.ME-04 969. 2.6411-03 2.5641-03 Mi 69. 6". 4.911E-04 4.7M73-04 698. 5.540E-04 5.3841-04 698. 3.4941-03 3.3911-03 S 820. 820. 3.4981-04 3.4001-04 820. 3.6061-04 3.50ME-04 820. 2.7STE-03 2.7E-03

$Su 835. 835. 3.2771-04 3.1861-04 835. 3.832E-04 3.724E-04 835. 1.8281-03 1."41-03 Su. 628. 628. 5.6981-04 5.5381-04 628. 7.20M1-04 7.0071-04 628. 4.5461-03 4.412E-03 imi 533. 533. 6.1441-04 5.9731-04 533. 7.121E-04 6.921E-04 533. 5.206E-03 5.0331-03 M 524. 524. 5.976E-04 5.809-04 524. 7.31-04 7.1131.04 524. 6.383E-03 6.191-03 UM 643. 643. 3.986E-04 3.8731-04 643. 4.3TE-0 4.7301-04 643. 4.1571-03 4.616E-03 Nu 762. 762. 3.457E-04 3.3601-04 762. 4.1311-04 4.0166-04 762. 3.744E-03 3.63E-03

-v 890. 890. 3.3301-04 3.2361-04 890. 3.626E-04 3.5251-04 a". 3.069E-03 2.97-03 LASALLE *It3 MEIOMOCICAI DATA 117 - 1218T The restricted area boundary (RAO) was redefined Insectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectlvely. As a result ot this change of range, the dose factors were re-evaluated using the following equation. Here, FR Isthe resulting dose factor at the nfw range (I.e. 833). f Is the value provIded In the above 00CM tables (I.e. S. SBAR, V, VOAR. 0. GOAR). R. IsMe former RAO distance (.e. 1055) and R Is tMe RAS distance

(.e. 833).

This analysis Indicates that the chanoe Inrange would Increase the dose lactor eror by approxinately 40%. Since ft dMfference 1s Wel within the expcted error of he cunt factors, no further adustmen1 In th above factors Is considered necsty.

EPOPFOMMdonnk/ki1-711-3 F-37

Revision 5 November 2002 Table F-Ye (Continued)

Maximum Oflse Finite Plume Gamma Doze Factors Sed on I cm Depth at the Reaticted Are Boundary tot Ar-41 4

DOmWuInd 5.slrIcked aIevokodistak) Notoes HMe NOde(Ven) Role"* Growau Level 4e14e Siretica Area 6rw mwt1w 6 3843 5.1wlu V VSA KWdIaG a GlM Wasr) Casters) WoadvrYCUC1a8) ("ars) CWW/djA/(CI/sSG) War) Cured/yr)/u&t(Iee)

V 1036. 1036. 4.7466-04 4.5941-04 IOU. 5.5256-04 5.3511-04 1036. 4.5571-03 4.41103 muN 1378. 1378. 3.9549-0 3.821-04 1378. 4.4391-04 4.2971*04 1378. 3.2031-03 3.1011-03 IW 1609. 1609. 2.825E-04 2.734J-04 1609. 3.0291-04 2.9321-04 1609. 2.351-03 2.28-03 au' 1079. 1079. 3.SU5E-04 3.4685-04 1079. 3.7291-04 3.6101-04 1079. 3.4721-03 3.3611'03 I 1055. 3.8185-04 3.6961-04 105S. 4.100E-04 3.9691-04 toss. 3.8411E03 3.7181-03 toss. 'OS,. 4.725E-04 4749-04 loss. S.02SE-4 4.64-04 969.

3.6075-03 S.61 1 0 969. 969. 4.711U-04 4.560E-04 969. 5.3201-04 5.1491-04 3.715E-03 3.5971-03 St 698. 698. 5.6721-04 5.4901-04 698. 6.4915-04 6.2641-04 698. 4.6951-03 4.5451-03 820. 820. 4.2121-04 4.m7-04 820. 4.5851-04 4.431-04 820. 3.8791-03 3.7551-03 SW 835. 835. 3.994104 3.6 35. 4.9301-04 4.M-04 835. 2.7001-03 2.6141-03 628. 626. 6.7111-04 6.496U-04 628. 8.5911-04 1.31-04 628. 6.1396-03 5.9431-03 533. 533. 7.089E-04 6."66-04 533. 6.229E-04 .966-04 533. 6.6671-03 6.453U-03 U

524. 524. 6.802E04 6.5841-04 524. 5.2911-04 8.0 -04 52f.. 6.057603 7.7991-03

64. 3. 4.708104 4.555104 643. 5.7161-04 S.533-04 63S. 6.3006-03 6.0991-03 NW' 762. 762. 4.123104 3.9911-04 762. 4.910E-04 4.8111-" 762. 5.17-03 5.008£-03

.Wp 590. 590. 4.0251-04 3.891-04 890. 4.473-04 4.3051-04 690. 4.314-03 4.2341-03 LASU £III MKI1b 0 ICAL DATA un

  • l/87 The resiricted area boundary (RAB) was iodeUned In sectors E and ESE to 833 and 848 from 1055 and 1055 metars. resplvely. As a reult of tUs change of fange. the dose factors were re-evaluated using the ollowing equalon. Here, FR Is the resulting dose lactor at the new range (.0. 833). F Is the value provided In the above ODCM tables (I.e. S. SOAR, V. VBAR, (. GBAR). , Is the former RAS distance 1.e. 1055) and R Is the RAS distance (i.e. 833).

Thi anasls Indicates that the change Inrange woukW Ictase O dose (actor error by a~oxkaately 40* Since ts difference Iswel within the expected eror ge current factors, no Iuwher adzstznent Inthe above factors Is consied necessy.

F-38

LASALLE Revision S November2002 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 OW OF, SF, (M) 1 Uving at home 8360 0.95 0.7 1100' (nearest resident) 2 Fishing 400 0.05 1.0 2100 3 Uving at the 2500 0.7 2400 National Guard

.___ Fa.ilit . __ _ __ .

K a 2.28E-05 mrem(MWe-hr)

These parameters are used to obtain an initial estimate of skyshine dose to the maximaly exposed member of the pubic using Equation A-34 In Appendix A. It 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 ot 112 hour0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br />s/week) [(8 monthslyr)/(12 monthstyr)] x 52 weekstyrJ a 416 hour0.00481 days <br />0.116 hours <br />6.878307e-4 weeks <br />1.58288e-4 months <br />s/yr The remaining time is assumed to be spent at the nearest residence.

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 OH8760 hours

  • OF, rounded to the 0.01 digit.

In determining the maximaly 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~bdcmAa1asI1.7f -

F-9

  • Revon 5 Supplemental Table A Nober Elevated Level JoInI Frequency Disisibution Table Summary 375 Fool Elevatin Data Summary Tabl o Percent by Direct Ion en Class Class N mE NI INS a SES6 Ss U5 S SSW s WSW V NW m Total A .024 .032 .0067 .057 .082 .040 .030 .060 .056 .169 .087 .051 .056 '.064 j.063 .024 .943
  • .149 .175 .227 .149 .080 .047 .056 .070 .233 . .463 .330 .159 .145 .192 1.153 .183 2.643 C .300 .262 .351 .265 .138 .069 .104 .130 .315 .579 .464 .361 .344 .420 .329 .332 4.005 0 3.100 2.634 3.252 3.192 2.710 1.945 1.167 2.053 2.110 2.315 2.210 2.460 2.248 4.533 3.922 3.681 46.601 E 1.013 .913 1.162 1.431 1.623 1.495 0.480 1.752 2.67 2.915 2.124 I.531 1.575 2.085 1.170 1.196 27.061 F .320 .182 .248 .260 .469 .707 .105 . 95 1.459 1.735' 1.561 1.041 1.012 1.099 .094 .553 *13.436 o .055 .030 ,022 .012 .040 .00 .27 .507 .674 .658 .660 .460 .309 .242 .211 .103 4.358 Total 4.965 4.237 5.359 5.3 56 6.394 4.235 4.601 5.567 8.414 9.467 7.407 6.093 6.658 3.615 7.245 6.073 100.000 Summary Table of Percent by Direction ed Sped Spee N mgE NE IlS U ass s s 5 55W SW WSW V WNW NW NW Total

.45 .016 .017 .015 .010 .006 .010 .013 .008 .016 .010 .000 .013 .000 .000 .001' .000

  • 137 3.05 .011 .033 .030 .027 .021 .023 .032 .027 .027 .017 .017 .028 .021 .024 .034 .027 .402 a.05 .162 .260 .276 .215 .141 .149 .159 .171 .165 .185 .155 .135 .147 .115 .130 . 160 3.0S 2.731

.381 .479 .551 .417 .360 .207 .311 .215 .323 .317 .272 .302 .321 .317 ,302 .311 5.595 4.05 .50 .647 .785 .647 .494 .428 .431 .404 .453 .465 .42 .400 .381 .482 .407 .455 7.73 6.05 .489 .598 .792 .515 .451 .403 .420 .505 .477 .469 .402 .472 .493 .540 ,.643 .533 6.213 6.05 .577 .59 .681 .595 .506 .419 .479 .483 .556 .584 .523 .487 .556 .5958 .668 .656 6.05 1.29? 9.150

.910 1.353 1.289 1.207 .012 .960 1.062 1.415 1.500 1.311 1.104 1.20? 1.622 1.669 1.623 20.632 10.05 .912 .421 .487 .845 .998 .751 .736 .947 1.385 1.552 1.325 1.088 1.240 1.671 0.557 0.210 13.05 17.15

.462 .210 .183.. .594 .55 .692 .749 1.101 2.107 2.440 1.122 1.338 1.432 1.962 1.428 .600 1a.545 16.00 .120 .065 .026 .231 .326 .240 .283 .459 1.476 1.615 1.043 .501 .746 1.137 .404 .222 9.153 45.00 .002 .000 .000 .011 .011 .011 .013 .035 .012 .109 .038 .05 .131 .147 .010 .015 -.T0 Total 4.985 4.237 5.3806 5. 3 5.394 4.38o 4.601 16.07 0.414 3451 7.47 6.003 6.65 6.015 7.248 6.073 100.00 NOTE: Wld dU blons Intabs areo prntd In wind nor ad not wnd loedrcon.

EP86PA l-cmhsak7lF71 F-40

Revsl November2002 Supplemental Table A -Continued Elevated Level Joint Frequency Olstribution Table Summary 375 Fool Elevation Data Suary TbleoftPus ont b potf.ldcl t Clogs A C 0

  • 3 V 0 Speed

.45 .000 .000 .00O .012 .056 .023 .004 1.05 .001 .004 .004 . 76 .183 .080 .00 2.08 .ol .01 . too 1.640 .06 .307 .080 3.05 .046 .16 .290 3.269 1.193 .141 .096 4.05 .102 .249 .429 4.264 1.629 .788 .166 6.05 .1102 .336 .647 4.159 1.145 .916 .210 6.01 .306 .341 .865 4.663 2.320 .98 .263 6.05 .225 .701 1.16 10.191 5.190 2.480 .715 60.08 .141 .429 .71 7.441. 4:924 2.891 .671 13.01 .134 .404 !.693 6.9?? 5.670 3.208 t.218 13.00 .0s .103 '.26 5.424 4.126 1.611 .613 39.00 .001 .017 .033 .29 .191 .041 .013 EP8PROtJhdmftsbatk n F-41

. . . __e Supplemantal Table a November2002 Mid Elevation Joint Frequency DisIibullon Table Sumimasles Suary Table of Percent b Direction wid Clas Clan N mg NE on U 15 S£ SSE 6 SSW SM WSW V *". NW 'total A .381 .246 .801 .70 .531 .256 .142 .119 .230 .357 .440 .370 .453 '.653 ;579 .671 7.030 P .313 .249 .377 .343 .290 .175 . 10 .104 .201 .288 .321 .292 .350 .490 .520 .662 5.063 C .531 .420 .566 .434 .30 .209 .320 .282 .370 .496 .479 .470 .506 .073 .710 .165 7.634 0 2.274 2.315 2.517 2.48 2.609 1.115 1.677 1.75 2.781 3.045 2.096 1.639 2.140 5.040 '2.641 2.408 37.410 E .777 .734 1.066 1.105 1.486 1.323 1.243 1.436 2.678 2.910 1.697 1.176 1.220 1.712 1.420 1.015 23.034 a.233 .155 .177 .205 .433 .609 .802 .601 1.210 1.383 6.163 .662 .654 1.017 1.848 .446 11.410 Ii .065 .060 .021 .013 .059 .265 .635 .896 1.244 1.23 .997 .689 .740 .716 .562 .1650 6.41 Total 4.575 4.162 5.547 .. 136 5.657 4.641 4.930 6.413 .722 9.721 7.219 5.66 6.268 *.297 1.49 6.094 100.000 umary Table of Percent by Direction and ped N NNE Ng 1E4 1 SE SE 5 S SSW SW WSW V WNW NW NNW Total

.45 .043 .003 .000 .020 .015 .003 .OOS .oo .005 .000 .008 .000 .000 .000 .000 .000 .I1a 6.05 .046 .072 .063 .042 .033 .025 .040 .034 .037 .021 .026 .038 .031 .026 .034 .046 .662 2.05 .219 .5)5 .500 .323 .233 .697 .202 .201 .232 .193 .201 . 9 .183 .151 .153 .163 3.916 3.05 .442 1.132 1.140 .690 .497 .350 .399 .363 .36 .344 .339 .353 .413 .374 .386 .374 1.946 4.05 .538 .970 1.370 .729 .617 .526 .545 .532 .599 .563 .557 .466 .481 .563 .630 .616 10.319 5.05 .661 .564 0.041 .600 .639 .553 .635 .555 .621 .610 .579 .560 .500 .686 .737w .720 10.503 6*.05 .729 .383 .570 .802 .771 .726 .103 .661 .643 .967 .696 .661 .69 .615 *.940 .916 11.959 6.05 1.086 .330 .576 1.004 6.667 1.351 1.333 1.426 2.234 2.473 1.925 1.484 1.604 1.933 1.903 1.569 237.10 10.05 .472 .108 .153 .475 .601 .691 .690 1.015 2.122 2.430 1.707 1.106 to

.100 .56 1.315 .910 16.693 13.05 .202 .016 .029 .2314 .509 .346 .290 1 1.342 1.115 1.012 .626 .790 1.414 6t096 .580 10.726 16.00 .111 .001 .001 .034 .177 .067 .076 .163 .310 .362 .154 .150 .300 .663 .312 .203 2.086 99.00 .007 .000 .000 .004 .001 .000 .000 .005 .010 .009 .014 .030 .074 .074 .013 .004 .247 Total 4.50 4.12 5.4 5.130 5.57 4.341 4.980 S.0l3 a.1aa s.16 7.269 a. .6 6.207 7.468 6.094 100.00 NOTE: Wind dictns In ables are presented In'wind lonr and not wVnd to dlrecton.

EP8PAO~c,aami1.1F F-42

0 RevisiR November 2002 Supplemental Table a - Continued Mid Elevation Joint Frequency Dlstrbutn Table Summanes 200 Fool Elevation Data I

Summry. Table of Pecet by Sped WM e s Class- A a -. D p a SpOeed .

.45 .000 .000 .001 .046 .03? .021 .003 3.05 .013 .004 .022 .2tO .175 .116 .063 9.05 .112 .130 .291 1.946 .132 .437 .207 2.05 .600 .463 .609 2.633 3.621 .642 .376 4.06 .776 .686 .970 4.134 2.320 .930 .591 6.05 .629 .883 .966 3.016 2.455 1.150 .690 6.05 .835 .532 .921 4.369 2.742 1.483 1.079 8.06 1.542 3.208 1.671 3.019 6.277 3.35 2.616 10.05 1.030 .780 .97 6.211 4;64 2.319 .180 12.05 .874 .658 .754 4.155 2.854 .935 .697 13.00 .331 .20? i231 1.121" .830 .046 .020 99.00 .029 .012 ,01  ; 163 .020 .005 .001 EPSPRW "dem. tbI"-71 F43

Revs November2002 Supplemental Table C Ground Level Joint Fequncy Dlstilbution Tab Summuy 33 Foot Elevallon Data u.ary Table o Perent by Dlreclon and close cl..s i m Ns' 1.1 s us Is sut s Wsv SW WSw V WIN NW NW Total 4 .411 .318 .688 .887 .594 .30 .133 .135 .213 .407 .471 .447 .532 :Gds 1.844 .94o 7.9

  • .314 .150 .278 .310 .276 .177 .108 .071 .172 .239 .268 .222 .293 .405 .50S .501 4.288 C .380 .233 .330 .328 .262 .210 .189 .172 .285 ; .385 .424 .343 .380 .507 ..638 .50f 5.626 o 3.149 1.449 2.178 2.504 2.687 1.735 1.571 1.540 2.198 2.672 2.178 1.965 2.243 3.240 3.269 2.509 31.051 E 1.131 .601 1.16 1.021 1.758 1.434 1.303 1.51 2.656 2.795 1.068 1.480 1.557 1.946 1.692 .917 24.941 F .160 .031 .171 .160 .646 .640 .760 .817 1.250 1.280 6.316 I.039 1.048 .667 .609 .316 16.460 o .ol .008 .011 .025 .217 .615 .673 5.023 1.163 l.050 .998 .9 w6 .925 .490 .214 .003 6.6a Total 5.570 2.906 4:636 5.235 6.349 6.379 4.932 5.319 7.662 6.629 7.690 6.422 6.979 6.618 7.773 5.603 100.000 Summary Table of Paivent by Dirlt ion n Spee Spad N NN NgE ENE a £5. ESE US S 55W SW WS W WNW NW NW Total

.45 .000 .004 .000 .002 .002 .000 .000 .OC1 .oo. ' .00 .02 .004 .002 .000 .002 .002 .029 1.05 .052 .048 .073 .046 .058 .056 .052 .073 .081 .075 .079 .087 .102 .093 .086 .066 6.085 2.05 .371 .609 .113 .517 .424 .601 .688 .582 .532 .441 .45 .468 .613 .626 *497 .468 6.761 3.05 1.124 1.183 1.802 1.288 1.191 1.270 1.276 1.222 1.149 1.180 1.112 1.031 1.095 1.079 .931 1.043 18.632 4.05 1.328 .621 1.122 1.230 1.420 1.116 1.058 1.079 1.131 1.119 1.648 1.550 1.274 1.023 1.000 .896 19.J13 5.05 1.120 .241 .61

  • 6.106 6.189 .6094 .642 .73 0.276 1.509 1.305 1.129 1.029 1.104 1.014 .777 15.605 6.05 .667 .091 .297 .597 .679 .551 .509 .06 1.047 1.434 1.112 .308 .694 .914 .966 .613 12.163 6.05 .628 .102 .100 .422 .817 .761 .480 .642 1.262 .636 1.291 .027 1.072 3.478 1.644 1.014 34.345 10.05 .145 .002 .006 .042 .303 .227 .172 .289 .581 .58 .532 .35 .460 .942 .933 .467 6.038 13.05 .114 .000 .000 .002 .067 .093 .056 .094 .202 .256 .119 .121 .254 .634 .563 .220 2.77 16.00 .008 .000 .000.. .002 .000 .004 .002 .012 .016 .012 .031 .040 .145 .202 .154 .029 .971 09.00 .000 .000 .000 .000 .000 .000 .000 .0D0 .000 .o0 .003 .013 .06 .062 .04Q .000 .046 Total 5.570 2.906 4.S'3 S6&23 6.346 5.379 4.33 5.316 7.142 6.a2 1.630 0.422 6.31 .115 7.771 S. 100.000 NOTE: Wind dckwhks in ta are prsnw in wid ifoa and rgo w &cl on.

EP8PR0JbdcmAa1s/b71 F44

RevisIon 5 November2002 Suppmental Table C - Continued Ground Level Joint Frequency Distribution Table Summary 33 Foot Elevation Data Sumey Table f Pven by Speed end ClS Clean.. A S C 0 1 '

Speed

.45 .000 .000 .004 .002 .00 .060 .006

.05 .02 .0n .012 .11? .355 .219 .195 2.05 .326 .202 .212 2.282 2.334 1.764 1.652 3.05 .998 .578 .729 1.133 6.380 3.261 2.608 4.05 1.247 .696 .82 6.435 4.793 3.064 2.725 6.05 1.203 .646 .352 6.115 3.680 1.773 1.037 6.05 1.201 .570 .604 6.472 3.049 .81 .256 6.05 1.620 .900 1.203 6.605 2.334 .463 .060 10.05 .775 .422 .518 2.955 1.334 .031 .002 13.05 .428 .212 .245 1.489 * .436 .004 .002 16.00 .112 .052 4052 .282 .089 .004 M0 09.00 .023 .012 .000 .008 .004 .004 .000 EP8PR0jbdmq1bW11tr7IF F-45

- l l~~~~

Revision 5 November 2002 Point

_ =

OFFsrrE DOSs CALCULATION MANUAL LASALLE COUNTY AnON FIGURE.F-1 I

UNRESTRICTED AREA BOUNDARY 2oo . 2=0 O, 4n0 . .6000

.cc ~ ua 1 Muel Scale in Feet UNRESTRICTU AREA BOUNDARY (Property Lne)

Wast Stabilization Pond Laba.e Lake Sbus E=sa I Ml iteoozqca1 ToWr o _ _ _ _ _ i e ,.

".0000, I

Revision 5 November 2002

  • Irenm Raowasie Storage Facutzy esM=a Area Bournaas Raowasze Storage Area (When OoeratuonaL MIS area may rIcaxu48-pacm DAW. an: other types et storage) OFFSITE DOSE CALCULAT ION AL IaEc S to 2e2 F-a LA SALLE COUNTY STATION I

w GRAPHIC S" FIGURE F-2

- - --.---- . .5 PS? FESTRl CTWD - AREA- eOUNDARY--

Mowwmd

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