ML022620606
| ML022620606 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/30/2002 |
| From: | Schiavoni M Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022620606 (208) | |
Text
Exelonf.
Exelon Generation Company, LLC LaSalle County Station wwwexeloncorp corn NucleaT 2601 North 21"Road MaTseilles, IL61341-9757 April 30, 2002 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 1 and NPF-1 8 NRC Docket Nos. 50-373 and 50-374
Subject:
2001 Radioactive Effluent Release Report Enclosed is the Exelon Generation Company, (EGC), LLC, LaSalle County Station 2001 Annual Radioactive Effluent Release Report. This report is submitted in accordance with Technical Specification 5.6.3, "Radioactive Effluent Release Report."
Program enhancements are in-place and on-going in an effort to minimize previously identified human errors associated with the Annual 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, Mark A. Schiavoni Plant Manager LaSalle County Station Attachment cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - LaSalle County Station (2
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
Summary of Changes to the Annual Effluent Report
- 1) The formatting of the supplemental information section has been revised to be more consistent with the recommendations of Regulatory Guide 1.21, while maintaining some site specific procedurally required information.
- 2) While there were no liquid radwaste discharges conducted, or occurrences of positive nuclide activity detected in the plant's ultimate outfall during 2001, the reporting of liquid effluents has been changed to reflect actual plant configuration. Since the plant has a common radwaste treatment facility and does not segregate inputs into radwaste by unit, and since there is a common release point from the plant's cooling pond to the Illinois River, it is appropriate for any liquid releases to be reported under Unit 1. This practice is consistent with that for reporting gaseous releases via the common vent stack. The past practice of applying half of the total liquid release activity to each unit and reporting releases under Unit 1 and Unit 2 will no longer be followed based on the reasons stated above and the fact that there is no value added from this practice.
- 3) In the Solid waste and Irradiated Fuel Shipments Section, "Container Type" has been changed to "Shipment Type" based on technical accuracy. While this information is not specified in Regulatory Guide 1.21, LaSalle Station's ODCM and local procedure for preparation of the Annual Effluent Report currently require it.
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
Supplemental Information
- 1. Regulatory Limits
- a. Gaseous Effluents
- 1) 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 each 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 (2001)
Supplemental Information (continued)
- 2. Allowable Concentrations
- a. Gaseous Effluents
- 1) 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 II, 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/ml)
Kr-85m 2.00E-04 Kr-85 5.00E-04 Kr-87 4.00E-05 Kr-88 9.00E-05 Ar-41 7.OOE-05 Xe-131m 7.00E-04 Xe-133m 5.OOE-04 Xe-133 6.00E-04 Xe-135m 2.00E-04 Xe-135 2.00E-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
- 1) 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 (2001)
Supplemental Information (continued)
- 4) All release types as listed in I and 2 above, at the vent stack and as listed in 3 above, at the Standby Gas Treatment System whenever there is a 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 ofeffluent into a flowing stream: gpm N/A
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
Supplemental Information (continued)
- 6. Abnormal Releases
- a. Gaseous
- 1) Number of releases: None
- 2) Total activity released: N/A
- b. Liquid
- 1) 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 Instrumentationtimeclocks and sample anomalies.
There were no effluent monitoring instrumentation timeclocks exceeded during this time period.
- 9. Offsite Dose Calculation Manual Revisions. The ODCM was revised in May 2001 in support of and as a result of the implementation of Improved Technical Specifications at LaSalle Station. Concurrent with the revision, the ODCM LaSalle Annex was relocated to the Technical Requirements Manual.
An entire copy of the ODCM LaSalle Annex, along with the ITS change summary, is submitted in accordance with Technical Specification 5.5.1 (refer to Appendix A).
/
LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
UNITS ONE AND TWO DOCKET NUMBERS 50-373 AND 50-374 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated I Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr Tot Erro A. Fission and Activation Gas Releases
- 1. Total Release Activity Ci 4.01 E+02 1.09E+03 6.74E+02 3.24E+02 35%
- 2. Average Release Rate uCi/sec 5.15E+01 1.38E+02 8.47E+01 4.08E+01
- 3. Percent of Technical Specification %* * *
- Limit B. Iodine Releases
- 1. Total 1-131 Activity Ci 5.81E-03 6.95E-03 1.25E-02 1.09E-02 35%
- 2. Average Release Rate uCi/sec 7.47E-04 8.84E-04 1.57E-03 1.37E-03
- 3. Percent of Technical Specification % * * *
- Limit C. Particulate (> 8 day half-life) Releases
- 1. Gross Activity Ci 5.43E-04 6.97E-04 2.25E-03 7.48E-04 33%
- 2. Average Release Rate uCi/sec 6.98E-05 8.87E-05 2.83E-04 9.41 E-05
- 3. Percent of Technical Specification % * * *
- Limit
- 3. Gross Alpha Activity Ci 5.08E-06 1.95E-06 1.19E-6 <1.00E-11 D. Tritium Releases
- 1. Total Release Activity Ci 5.02E+01 9.17E+01 4.85E+01 5.14E+01 21%
- 2. Average Release Rate uCi/sec 6.46E+00 1.17E+01 6.1 0E+00 6.47E+00
- 3. Percent of Technical Specification % * * *
- Limit
"*" 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 (2001)
GASEOUS EFFLUENTS-ELEVATED RELEASE Unit I and Unit 2 Continuous Mode I Units IlstQtr I 2ndQtr I 3rdQtr 1 4thQtr -
I. Fission and Activation Gas Releases Ar-41 CI <I.OOE-06 <I.OOE-06 2.04E-04 <1.00E-06 Kr-85 C1 <I.OOE-06 7.21E+02 <I.OOE-06 <I.OOE-06 Kr-85m Ci 9.72E+01 8.41E+01 7.45E+01 9.04E+01 Kr-87 Ci 3.I0E+01 2.92E+01 9.24E+00 2.62E+01 Kr-88 Ci 2.03E+02 1.75E+02 1.02E+02 1.52E+02 Xe-131m C1 <I.OOE-06 <I.OOE-06 <1.00E-06 <I.OOE-06 Xe-133 C1 5.27E+01 6.71E+01 4.73E+02 5.39E+01 Xe-133m Ci <I.OOE-06 <I.OOE-06 <I.OOE-06 <l.00E-06 Xe-135 Ci 7.33E+00 1.01E+01 1.51E+01 1.48E+O0 Xe-135m CQ 9.07E+00 <I.OOE-06 7.70E-04 <I.OOE-06 Xe-138 C1 <1.00E-06 <1.00E-06 <1.00E-06 <I.OOE-06 TOTAL Ci 4.01E+02 1.09E+03 6.74E+02 3.24E+02
- 2. Iodine Releases 1-131 Ci 5.81E-03 6.95E-03 1.25E-02 1.09E-02 1-132 Ci 1.98E-03 5.48E-03 1.41E-02 8.33E-03 1-133 Ci 1.08E-02 1.42E-02 2.55E-02 2.13E-02 1-134 Ci <1.00E-I1 <I.00E-11 <1.00E-1I <I.00E- 1 1-135 Ci 2.16E-03 6.06E-03 2.47E-02 1.45E3,-02 TOTAL IODINE Ci 2.08E-02 3.27E-02 7.68E-02 5.50E-02 TOTAL 1-131, 1-133, 1-135 Ci 1.88E-02 2.72E-02 6.27E-02 4.67E-02
- 3. Particulate (> 8 day half-life) Releases Cr-5! C1 <I.OOE- 1I <1.00E-I 1 <i.00E-I I <I.00E-I 1 Mn-54 C1 2.06E-05 1.52E-04 1.42E-04 5.70E-05 Co-57 Ci <1.00E-I1 <1.OOE-1I <.OOE-11 <1.OOE- 1 Fe-55 Ci <1.00E-11 <1.00E-I I <I.00E-I1I <1.OOE- I1 Co-58 C1 <I.00E-11 <1.OOE-11 <I.OOE- 1 <I.00E-I1 Fe-59 Ci <1.00E-11 <I.OOE-11 <I.OOE-II <I.00E-11 Co-60 C1 2.79E-04 2.11 E-04 4.66E-04 2.78E-04 Zn-65 Ci <I.00E-I1 <I.OOE- 11 <1.OOE- 11 <I.OOE-11 Sr-89 C1 2.42E-04 3.34E-04 1.22E-03 4.13E-04 Sr-90 C1 1.54E-06 <l.00E-1I <I.OOE- 1 <I.OOE-11 Zr-95 C1 <1.0OE-11 <1.00E-11 <I.00E- 1I <I.OOE-1I Mo-99 Ci <I.00E-1I <I.0OE-11 <I.OOE-I 1 <I.OOE-I I Ru-103 Ci <I.OOE- 11 <1.00E-11 <l.OOE-I 1 <I.OOE-I Sn-117m Ci <I.00E- 1 <I.00E-II <1.0013E- 1 <I.00E-I11 Cs-134 C1 <I.OOE-II <1.OO1-11 <1.00E-I1 <I.00E-11 Cs-137 C1 <1.OOE-I I <1.00E- 11 <l.OOE-11 <1.00E-1I Ba\La-140 C1 <I.OOE-I 1 <I.00E-I 1 8.00E-05 <I.00E-I 1 Ce-141 C1 <1.00E-11 <1.00E-1I 3.41E-04 <l.00E-I1 Ce-144 Ci <I.OOE-11 <I.OOE-II <I.OOE- 11 <I.OOE-11 TOTAL PARTICULATES Ci 5.43E-04 6.97E-04 2.25E-03 7.48E-04
- 4. Tritium Releases
- 1. Total Release Activity Ci 5.02E+O1 I 9.17E+01 4.85E+01 5.14E+01
"<" indicates activity of sample is less than LLD given in uCi/mI
LASALLE COUNTY NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
LIQUID RELEASES UNIT I and UNIT 2 SUMMATION OF ALL LIQUID RELEASES Estimated I Units I lstQtr I 2nd Qtr I 3rd Qtr I 4th Qtr Total Error %
A. Fission and Activation Products
- 1. Total Activity Released Ci <LLD <LLD <LLD <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 <LLD <LLD <LLD <LLD N/A
,2. Average Concentration Released uCi/ml <LLD <LLD <LLD <L-j
- 3. Percent of Applicable Limit %* * *
- C. Dissolved Noble Gases
- 1. Total Activity Released Ci <LLD <LLD <LLD <LLD I N/A
.2. Average Concentration Released uCi/ml <LLD <LLD <LLD <LLD
- 3. Percent of Applicable Limit %* * *
- D. Gross Alpha
- 1. Total Activity Released (estimate) Ci <LLD <LLD <LLD <LLD N/A
- 2. Average Concentration Released uCi/ml <LLD <LLD <LLD <LLD
- 3. Percent of Applicable Limit %* * *
- JE. Volume of Liquid Waste to Discharge liters 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 N/A IF. Volume of Dilution Water liters 0.00E+00 0.00E+00 0.OOE+00 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 (2001)
LIQUID RELEASES UNIT 1 and UNIT 2 BATCH MODE lNuclides From Batch Releases Units lstQtr 2ndQtr 3rdQtr 4thQtr H-3 Ci Cr-51 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 10m Ci Sb-122 Ci Sb-124 Ci 1-131 Ci Cs-134 Ci Cs-137 Ci Ba)La-140 Ci Ce-141 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 (200 1)
LIQUID RELEASES UNIT I and UNIT 2 CONTINUOUS MODE lNuclides From Continuous Releases Units 1st Qtr I2nd Qtr I3rd Qtr I4thQ~t~r Gross Alpha Ci <I.OO13-07 <1.OO13-07 <I.OOE-07 <1.OO13-07 H-3 Ci <1.OO13-05 <1.OOE-05 <1 .O13-05 <1.OOE3-05 Cr-51 Ci <5.0013-07 <5.OOE-07 <5.OOE-07 <5.0013-07 Mni-54 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.0013-07 Fe-55 Ci <1.OOE-06 <1.OOE-06 <1.OO13-06 <1.OOEf-06 Co-58 Ci <5.0013-07 <5.0013-07 <5.0013-07 <5.0013-07 Fe-59 Ci <5.0013-07 <5.0013-07 <5.0013-07 <5.OOE-07 Co-60 Ci <5.0013-07 <5.OOE-07 <5.0013-07 <5.0013-07 Zn-65 Ci <5.0013-07 <5.OOE-07 <5.0013-07 <5.OOE-07 Sr-89 Ci <5.0013-08 <5.OOE-08 <5.0013-08 <5.0013-08 Sr-90 Ci <5.0013-08 <5.OOE-O8 <5.0013-08 <5.OOE-08 Nb-95 Ci <5.OOE-07 <5.OOE-07 <5.0013-07 <5.OOE-07 Zr-95 Ci <5.0013-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Mo-99 Ci <5.OOE-07 <5.0013-07 <5.OOE-07 <5.OOE-07 Tc-99m Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.0013-07 Ag-I bin 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 C1 <5.OOE-07 <5.0013-07 <5.OOE-07 '<5.OOE-O7 1-131 Ci <1.OOE-06 <l.OOE-06 <l.OOE-06 <1.OO13-06 Cs-134 Ci <5.0013-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Cs- 137 Ci <5.OOE-07 <5.OOE-07 <5.OOE-07 <5.0013-07 Ba\La-140 Ci <5.0013-07 <5.OOE-07 <5.OOE-07 <5.OOE-07 Ce-I 41 Ci <5.0013-07 <5.0013-07 <5.OOE-07 <5.OOE-07 Ce-144 Ci <5.OOE-07 <5.OOE-07 <S.OOE-07 <5.0013-07 IW-187 Ci <5.OOE-O7 <5.0013-07 <5.OOE-07 <5.OOE-07 ITOTAL Ci <LLD I<LLD <LLD <LLD Xe-13 im Ci <1.OOE-05 <1.OOE-05 <1.OOE-05 <1.OOE-05 Xe-133 Ci <I.OO13-05 <1.OOE-O5 <1.OO13-05 <1.OOE3-05 Xe-133mn Ci <1.OOE3-05 <1.OOE3-05 <l.OOE-05 <1.OOE-05 Xe-135 Ci <1.OO13-05 <1.OOE3-05 <1.OO13-05 <1.OOE-05 Xe-135m Ci <1.OOE-05 <1.OOE-05 <1.OOE-05 <l.0O13-05 ITOTAL Ci <LLD <LLD <LLD <L
"<'indicates activity of sample is less than LLD given in uCi/mi
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FIRST QUARTER A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL
- 1. Spent resins, filter sludges, evaporator bottoms, etc.
- a. Quantity shipped cu.m. 4.66E+01
- b. Total activity Ci 1.81E+00
- c. Major nuclides (estimate %)
Mn-54 9.09 Fe-55 23.92 Cs-137 2.73 Co-60 59.74
- d. Shipment type LSA C. Solidification agent None
- 2. Dry compressible waste, contaminated equipment, etc.
- a. Quantity shipped cu.m. 7.25E+01
- b. Total activity Ci 1.22E-01
- c. Major nuclides (estimate %)
Fe-59 2.74 Mn-54 8.84 Fe-55 67.73 Co-60 17.33
- d. Shipment type LSA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FIRST QUARTER
- 3. Other
- a. Quantity shipped cu.m. 0.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 4 Truck CNSI, Barnwell, SC 2 Truck Duratek- Bear Creek, TN TOTAL THIS QUARTER 6 Estimated total error % for spent resins, filter sludges, evaporator bottoms, etc. (Jan-Dec) 25%
Estimated total error % for dry compressible waste, contaminated equipment, etc. (Jan-Dec) 25%
Estimated total error % for irradiated components (Jan-Dec) N/A B. IRRADIATED FUEL SHIPMENTS None
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND QUARTER A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL
- 1. Spent resins, filter sludges, evaporator bottoms, etc.
- a. Quantity shipped cu.m. 5.63E+01
- b. Total activity Ci 6.49E+01
- c. Major nuclides (estimate %)
Mn-54 % 4.57 Fe-55 % 76.97 Zn-65 % 1.73 Co-60 % 15.59
- d. Shipment type LSA
- e. Solidification agent None
- 2. Dry compressible waste, contaminated equipment, etc.
- a. Quantity shipped cu.m. 2.17E+02
- b. Total activity Ci 3.93E-02
- c. Major nuclides (estimate %)
Fe-59 % 2.65 Mn-54 % 22.93 Fe-55 % 60.02 Co-60 % 11.85
- d. Shipment type LSA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND QUARTER
- 3. Other
- a. Quantity shipped cu.m. 0.00E+00
- b. Total activity Ci O.OOE+00
- c. Major nuclides (estimate %) N/A
- d. Shipment type N/A
- 4. Irradiated Components
- a. Quantity shipped cu.m 0.OOE+00
- b. Total activity Ci 0.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 7 Truck CNSI, Barnwell, SC 3 Truck Duratek-Bear Creek, TN 2 Truck US Ecology Recycle Ctr TOTAL THIS QUARTER 12 Estimated total error % for spent resins, filter sludges, evaporator bottoms, etc. (Jan-Dec) 25%
Estimated total error % for dry compressible waste, contaminated equipment, etc. (Jan-Dec) 25%
Estimated total error % for irradiated components (Jan-Dec) N/A B. IRRADIATED FUEL SHIPMENTS None
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS THIRD QUARTER A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL I. Spent resins, filter sludges, evaporator bottoms, etc.
- a. Quantity shipped cu.m. 0.00E+00
- b. Total activity Ci O.OOE+00
- c. Major nuclides (estimate %) N/A
- d. Shipment type N/A
- f. Solidification agent N/A
- 2. Dry compressible waste, contaminated equipment, etc.
- a. Quantity shipped cu.m. 3.26E+02
- b. Total activity Ci 2.74E-01
- c. Major nuclides (estimate %)
Fe-59 % 2.70 Mn-54 % 23.07 Fe-55 % 60.15 Co-60 % 11.87
- d. Shipment type LSA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
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 Shinments Transportation Mode Destination 2 Truck ATG, Richland, WA 2 Truck Duratek-Bear Creek, TN 2 Truck US Ecology Recycle Ctr TOTAL THIS QUARTER 6 Estimated total error % for spent resins, filter sludges, evaporator bottoms, etc. (Jan-Dec) 25%
Estimated total error % for dry compressible waste, contaminated equipment, etc. (Jan-Dec) 25%
Estimated total error % for irradiated components (Jan-Dec) N/A B. IRRADIATED FUEL SHIPMENTS None
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
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. 1.89E+01
- b. Total activity Ci 3.06E+02 C. Major nuclides (estimate %)
Mn-54 3.90 Fe-55 % 73.60 Zn-65 6.64 Co-60 14.95
- d. Shipment type LSA (5)
Type B (1)
- e. Solidification agent None
- 2. Dry compressible waste, contaminated equipment, etc.
- a. Quantity shipped cu.m. 1.09E+02
- b. Total activity Ci 3.75E-02
- c. Major nuclides (estimate %)
Fe-59 3.13 Mn-54 23.11 Fe-55 59.25 Co-60 11.64
- d. Shipment type LSA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
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 0.00E+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 CNSI, Barnwell, SC 2 Truck Duratek-Bear Creek, TN I Truck (Type B) Studsvik, TN TOTAL THIS QUARTER 6 Estimated total error % for spent resins, filter sludges, evaporator bottoms, etc. (Jan-Dec) 25%
Estimated total error % for dry compressible waste, contaminated equipment, etc. (Jan-Dec) 25%
Estimated total error % for other irradiated components (Jan-Dec) N/A B. IRRADIATED FUEL SHIPMENTS None
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
RADIOLOGICAL IMPACT ON MAN MAXIMUM DOSES RESULTING FROM RELEASES AND COMPLIANCE STATUS
LASALLE STATION UNIT ONE ACTUAL 2001 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/02 INFANT RECEPTOR 1ST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN- MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 9.29E-03 8.05E-03 4.74E-03 6.99E-03 2.91E-02 (MRAD) (WSW) (WSW) (WSW) (WSW ) (WSW)
BETA AIR 2.88E-04 6.18E-04 2.67E-04 2.32E-04 1.40E-03 (MRAD) (ESE) (ESE) (ESE) (ESE ) (ESE)
TOT. BODY 7.02E-03 6.08E-03 3.58E-03 5.28E-03 2.20E-02 (MREM) (WSW) (WSW) (WSW) (WSW ) (WSW)
SKIN 7.39E-03 6.59E-03 3.79E-03 5.57E-03 2.33E-02 (MREM) (WSW) (WSW) (WSW) (WSW ) (WSW )
ORGAN 4.65E-03 2.07E-02 3.48E-02 1.55E-02 7.56E-02 (MREM) (ESE ) (ESE) (ESE) (ESE ) (ESE)
THYROID THYROID THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS - 10CFR 50 APP. I INFANT RECEPTOR
% OF APP I-QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY % OF OBJ JAN-MAR APR-JUN JULL-SEP OCT-DEC OBJ APP. I GAMMA AIR (MRAD) 5.0 0.19 0.16 0.09 0.14 10.0 0.29 BETA AIR (MRAD) 10.0 0.00 0.01 0.00 0.00 20.0 0.01 TOT. BODY (MREM) 2.5 0.28 0.24 0.14 0.21 5.0 0 .44 SKIN (MREM) 7.5 0.10 0.09 0.05 0.07 15.0 0 .16 ORGAN (MREM) 7.5 0.06 0.28 0.46 0.21 15.0 0.50 THYROID THYROID THYROID THYROID THYROID RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
LASALLE STATION UNIT ONE ACTUAL 2001 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/d2 CHILD RECEPTOR 1ST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT -DEC GAMMA AIR 9.29E-03 8.05E-03 4.74E-03 6.99E-03 2.91E-02 (MRAD) (WSW) (WSW ) (WSW) (wSw ) (WSW)
BETA AIR 2.88E-04 6.18E-04 2.67E-04 2.32E-04 1.40E-03 (MRAD) (ESE) (ESE) (ESE ) (ESE ) (ESE)
TOT. BODY 7.02E-03 6.08E-03 3.58E-03 5.28E-03 2.20E-02 (MREM) (WSW ) (WSw) (WSW) (wSW ) (WSW)
SKIN 7.39E-03 6.59E-03 3.79E-03 5.57E-03 2.33E-02 (MREM) (WSw ) (wSw) (WSW ) (WSW) (WSW)
ORGAN 3.83E-03 3.46E-02 5.40E-02 2.28E-02 1. 1SE-01 (MREM) (NNE) (NNE) (NNE) (NNE) (NNE)
THYROID THYROID THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2001 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 JULL-SEP OCT-DEC OBJ APP. I GAMMA AIR (MRAD) 5.0 0.19 0.16 0.09 0.14 10.0 0.29 BETA AIR (MRAD) 10.0 0.00 0.01 0.00 0.00 20.0 0.01 TOT. BODY (MREM) 2.5 0.28 0.24 0.14 0.21 5.0 0.44 SK-tN (MREM) 7.5 0.10 0.09 0.05 0.07 15.0 0.16 ORGAN (MREM) 7.5 0.05 0.46 0.72 0.30 15.0 0.77 THYROID THYROID THYROID THYROID THYROID RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
LASALLE STATION UNIT ONE ACTUAL 2001 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/02 TEENAGER RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JULL-SEP OCT-DEC GAMMA AIR 9.29E-03 8.05E-03 4.74E-03 6.99E-03 2.91E-02 (MRAD) (WSW) (WSW ) (WSW) (WSW) (WSW)
BETA AIR 2.88E-04 6.18E-04 2.67E-04 2.32E-04 1.40E-03 (MRAD) (ESE) (ESE ) (ESE) (ESE) (ESE)
TOT. BODY 7.02E-03 6.08E-03 3.58E-03 5.28E-03 2.20E-02 (MREM) (WSW) (WSW ) (WSW) (WSW) (WSW)
SKIN 7.39E-03 6.59E-03 3.79E-03 5.57E-03 2.33E-02 (MREM) (WSW) (WSW ) (WSW) (WSW) (WSW)
ORGAN 2.76E-03 2.23E-02 3.41E-02 1.46E-02 7.38E-02 (MREM) (NNE ) (NNE) (NNE) (NNE) (NNE)
THYROID THYROID THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2001 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 GAMMA AIR (MRAD) 5.0 0.19 0.16 0.09 0.14 10.0 0.29 BETA AIR (MRAD) 10.0 0.00 0.01 0.00 0.00 20.0 0.01 TOT. BODY (MREM) 2.5 0.28 0.24 0.14 0.21 5.0 0.44 SKIN (MREM) 7.5 0.10 0.09 0.05 0.07 15.0 0.16 ORGAN (MREM) 7.5 0.04 0.30 0.45 0.19 15.0 0.49 THYROID THYROID THYROID THYROID THYROID RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
LASALLE STATION UNIT ONE ACTUAL 2001 MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/o6 ADULT RECEPTOR 1ST 2ND 3RD 4TH rYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 9.29E-03 8.05E-03 4.74E-03 6.99E-03 2. 91E-02 (MRAD) (WSW) (WSW) (WSW) (WSW) (WSW)
BETA AIR 2.88E-04 6.18E-04 2.67E-04 2.32E-04 1.40E-03 (MRAD) (ESE) (ESE) (ESE) (ESE) (ESE)
TOT. BODY 7.02E-03 6.08E-03 3.58E-03 5.28E-03 2.20E-02 (MREM) (WSW) (WSW) (WSw) (WSW) (WSW)
SKIN 7.39E-03 6.59E-03 3.79E-03 5.57E-03 2.33E-02 (MREM) (WSW) (WSW) (WSW) (WSW) (WSW)
ORGAN 3.12E-03 2.21E-02 3.36E-02 1.46E-02 7.33E-02 (MREM) (NNE) (NNE ) (NNE) (NNE) (NNE)
THYROID THYROID THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS - 10CFR 50 APP. I ADULT RECEPTOR
- ------------ % OF APP I--------------.
QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRPJY % OF OBJ JAN -MAR APR-JUN JUL-SEP OCT-DEC OBJ APP. I GAMMA AIR (MRAD) 5.0 0.19 0.16 0.09 0.14 10.0 0.29 BETA AIR (MRAD) 10.0 0.00 0.01 0.00 0.00 20.0 0.01 TOT. BODY (MREM) 2.5 0.28 0.24 0.14 0.21 5.0 0.44 SKIN (MREM) 7.5 0.10 0.09 0.05 0.07 15.0 0.16 ORGAN (MREM) 7.5 0.04 0.29 0.45 0.19 15.0 0.49 THYROID THYROID THYROID THYROID THYROID RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
LASALLE STATION UNIT ONE ACTUAL 2001 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/02 INFANT RECEPTOR 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 0.O0E+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 4
THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS - 10 CFR 50 APP. I
OF APP I.
O%
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 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
LASALLE STATION UNIT ONE 2001 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM
- PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/d2 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 0.0OE+00 0.OOE+00 0.OOE+00 0. OOE+00 BODY INTERNAL 0.00E+00 0.OOE+00 0.OOE+00 o.OOE+00 0. OOE+00 ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT % 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 CFR 141.
RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
LASALLE STATION UNIT ONE ACTUAL 2001 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/02 CHILD RECEPTOR 1ST 2ND 3RD 4TH bOSE 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 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 2001 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 0.00 CRIT. ORGAN(MREM) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
LASALLE STATION UNIT ONE 2001 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM
- PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/0d2 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.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 2001 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT % 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 CFR 141.
RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
LASALLE STATION UNIT ONE ACTUAL 2001 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/02 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 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 2001 COMPLIANCE STATUS - 10 CFR 50 APP. I
%-OF APP I.
QTRLY IST 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 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
LASALLE STATION UNIT ONE 2001 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM
- PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/02 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 0.00E+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 2001 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT % 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 CFR 141.
RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
LASALLE STATION UNIT ONE ACTUAL 2001 MAXIMUM DOSES (MREM) RESULTING FROM AQUATIC EFFLUENTS PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/62 ADULT RECEPTOR 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL O.OOE+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 2001 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 0.00 CRIT. ORGAN(MREM) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
LASALLE STATION UNIT ONE 2001 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM
- PERIOD OF RELEASE - 01/01/01 TO 12/31/01 CALCULATED 04/16/02 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 0.OOE+00 0.OOE+00 0.00E+00 0. OOE+00 BODY INTERNAL 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0. OOE+O0 ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT % 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 CFR 141.
RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 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 01/01/01 TO 12/31/01 CALCULATED 04/16/02
- 1. 10 CFR 20.1301 (a) (1) Compliance Total Effective Dose Eqivalent, mrem/yr 3.97E-01 10 CFR 20.1301 (a) (1) limit mrem/yr 100.0
% of limit 0.40 Compliance Summary - 10CFR20 ist 2nd 3rd 4th % of Qtr Qtr Qtr Qtr Limit TEDE 9.41E-02 1.04E-01 1.02E-01 9.77E-02 0.40 RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 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 01/01/01 TO 12/31/01 CALCULATED 04/16/02
- 2. 10 CFR 20.1301 (d)/40 CFR 190 Compliance Dose Limit % of (mrem) (mrem) Limit Whole Body Plume 2.20E-02 (DDE) Skyshine 3.48E-01 Ground 9.39E-04 Total 3.71E-01 25.0 1.49 Organ Dose Thyroid 5. GOE-02 75.0 0.07 (CDE) Gonads 2.49E-02 25.0 0.10 Breast 2.49E-02 25.0 0.10 Lung 2.49E-02 25.0 0.10 Marrow 2.49E-02 25.0 0.10 Bone 2.49E-02 25.0 0.10 Remainder 2.50E-02 25. 0 0.10 CEDE 2.59E-02 TEDE 3.97E-01 100.0 0.40 RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 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 01/01/01 TO 12/31/01 CALCULATED 04/16/02
- 1. 10 CFR 20.1301 (a) (1) Compliance Total Effective Dose Eqivalent, mrem/yr 3.41E-01 10 CFR 20.1301 (a) (1) limit mrem/yr 100.0
% of limit 0.34 Compliance Summary - 10CFR20 1st 2nd 3rd 4th % of Qtr Qtr Qtr Qtr Limit TEDE 8.73E-02 8.29E-02 8.15E-02 8.94E-02 0.34 RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 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 01/01/01 TO 12/31/01 CALCULATED 04/16/02
- 2. 10 CFR 20.1301 (d)/40 CFR 190 Compliance Dose Limit % of (mrem) (mrem) Limit Whole Body Plume 0. OOE+00 (DDE) Skyshine 3.41E-01 Ground 0. OOE+00 Total 3.41E-01 25.0 1.36 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 3.41E-01 100.0 0.34 RESULTS BASED UPON: ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
METEOROLOGICAL DATA
MURRAY & TRETTEL, INC.
Tuesday, February 12, 2002 Mr. Mike Wolfe Rad Protection LaSalle Station Exelon Nuclear R. R. #1 - Box 220 2601 N. 21t Road Marseillies, IL 61341
Dear Mr. Wolfe:
Enclosed are copies of the LaSalle Station meteorological site quarterly joint-frequency 'wind rose tables for 2001. They are being sent pursuant to the Specification for Meteorological Data and Meteorological Monitoring Services & Maintenance (METi), 3.32,3.3.3, METSPECS/18/15 and METSPECS/18/41, Table 2a, format of wind rose table.
At this time, we would like to request the 2001 effluent data for your nuclear plant. The effluent data is required to process the 2001 annual report on the Meteorological Monitoring Program as per Specification No. METI 3.3.4.
In order to expedite the annual report generation, please forward the 2001 effluent data from your plant to:
Tom Begley Murray & Trettel, Inc 414 W.Frontage Road Northfield, IL 60093 If you have any questions, please contract Tom Begley @ (847) 446-7800 x 142.
Thank you for your assistance.
Sincerely, Tom Begley Environmental Meteorologist Enclosures 414 WEST FRONTAGE ROAD - NORTHFIELD, IL - 60093 PHONE: (847) 446-7800
- FAX: (847) 446-8130 E-MAIL: MZT0FWATHF.RCQOMANnCOAM - INTERNET: 4TTPJJ/WWW.WU,,ATH4RCOMMAND COM
LaSalle County Nuclear Station January-March. 2001 375 ft. Wind Speed and Direction 375Ft.33Ft Delta-T (F)
'I Number of Observations - 2153 Values are Percent Occurrence EED .................................. WIND DIRECTION CLASSES .................................. ......... STABILITY CLASSES ..........
ASS N NNE NE ENE E ESE SE SSE S SSW SW WsW W wIS ME "W TOTAL EU "j SU N SS HS ES TOTAL ELI 0.00 0.00 0.00 0.00I 0.00 0.00 0.0 0 0.00 0.00 0.00 0.00 0.00I 0.00 0.00 0.00 0.00 0.00 0.00 J 0.00 0.00 0.00 0.00 0.00 0.00 0.0 0 0.00 0.00 0.00 0.00 0.00I 0.00 0.00 0.00 0.00 0.00 0.00 SUP0.00 0.00 0.00 0.00 0.00 0.00 0.040 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NI 0.00 0.00 0.00 0.00 0.00 0.00 0.040 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 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 HS 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MU 0.00 0.00 0.00 0.00 0.00 0.00 0.00I 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 N 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 0.05 0.00 0.00 0.19 0.19 SS 0.05 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 0.05 0.19 0.19 MS 0.00 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 0.09 0.09 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0:00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.05 0.42 0.23 0.23 0.29 0.19 0.19 0.19 0.05 0.14 0.23 0.51 0.33 0.37 0.14 3.62 3.62 0.14 0.09 0.19 0.09 0.14 0.19 0.05 0.05 0.09 0.00 0.09 0.00 0.00 0.14 0.23 0.05 1.53 1.53 0.05 0.05 0.09 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.00 0.00 0.00 0.00 0.05 0.05 0.42 0.42 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 5.57 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 6SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00
- N 0.51 1.02 0.74 0.84 0.46 0.74 0.56 0.28 0.23 0.37 0.84 1.u1 0.98 0.93 1.44 0.70 n.75 1.75 1SS 0.05 0.14 0.51 0.33 0.09 0.39 0.14 0.23 0.14 0.42 0.65 0.23 0.23 0.60 0.33 0.46 4.74 4.74 2IM 0.09 0.09 0.14 0.00 0.00 0.09 0.00 0.00 0.00 0.09 0.23 0.09 0.09 0.00 0.00 0.09 1.02 1.02 ES 0.09 0.09 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 0.05 0.37 0.37 17.88 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 3SU 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 0.00 0.00 0.00 0.05 0.05
- N 2.42 0.74 0.70 0.42 0.28 0.70 0.23 0.19 0.51 0.74 0.88 1.02 1.35 2.14 2.09 1.81 16.21 16.21 1SS 0.42 0.23 0.37 0.74 0.19 0.33 0.23 0.42 0.33 0.33 0.51 0.33 0.84 1.21 1.44 0.60 8.50 8.50 8 S 0.28 0.05 0.09 0.00 0.00 0.09 0.09 0.05 0.14 0.23 0.37 0.19 0.19 0.42 0.14 0.14 2.46 2.46 ES 0.14 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.09 0.05 0.19 0.00 0.14 0.14 0.23 0.09 1.16 1.16 28.38
LaSalle County Nuclear Station Jamuary*March. 2001 375 it. Wind Speed and Direction 375Ft.33Ft Delta.T (F)
PEED .................................. WIND DIRECTION CLASSES .................................. ......... STABILITY CSSES ..........
LASS N NIE NE DEN E ESE SE SSE S 5SW SW W W WNW W NNW TOTAL EU HU SU N SS HS ES TOT 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
.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 0.00 0.00 0.00 0.00 0.00 ISU 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 0.00 0.09 0.00 0.14 0.14 N 0.93 0.19 0.14 0.33 0.19 0.42 0.28 0.14 0.33 0.56 0.33 0.88 1.63 1.81 3.58 1.44 13.14 13.14
!SS 0.19 0.00 0.06 0.14 0.00 0.33 0.23 0.19 0.74 0.56 0.42 0.42 1.25 0.93 1.30 0.42 7.15 7.15 1HS 0.09 0.00 0.05 0.00 0.05 0.05 0.37 0.05 0.23 0.19 0.23 0.42 0.56 0.56 0.28 0.33 3.44 3.44 ES 0.19 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.00 0.14 "0.09 0.09 0.05 0.09 0.19 0.37 1.35 1.35 25.2:
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
- N 0.05 0.28 1.07 0.19 0.14 0.00 0.28 0.00 0.28 0.51 0.33 0.46 1.58 1.30 2.74 0.28 9.48 9.48 2SS 0.05 0.00 0.00 0.05 0.14 0.84 0.51 0.09 0.42 1.21 0.84 0.23 1.02 1.63 0.51 0.09 7.62 7.62 4HS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.51 0.51 0.65 0.37 0.33 0.37 0.00 0.00 2.83 2.83 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.33 0.23 0.70 1.16 0.09 0.05 0.00 0.00 2.55 2.55 22.44 TOT 5.90 3.07 4.64 3.39 2.00 4.13 3.30 2.04 4.60 6.27 7.57 7.25 10.92 12.68 15.05 7.20 100.00 0.00 0.00 0.19 54.39 29.73 10.26 5.43 100.01 Wiald Direction by Stability N iKE NE ENE E ESE SE SSE S SSW SW WS WhW NW NNWTOTAL -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 0.00 0.00 0.00 0.00 0.00 0.00 Hoderately Unstable 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.19 Slightly Unstable 4.09 2.28 3.11 2.04 1.30 2.04 1.53 0.79 1.53 2.23 2.51 3.72 6.08 6.55 10.22 4.37 54.39 Neutral 0.88 0.51 1.16 1.35 0.S6 1.66 1.16 0.98 1.72 2.51 2.51 1.21 3.34 4.51 3.81 1.67 29.73 Slightly Stable 0.51 0.19 0.37 0.00 0.05 0.23 0.46 0.19 0.93 1.11 1.49 1.07 1.21 1.35 0.46 0.65 10.26 Moderately Stable 0.42 0.09 0.00 0.00 0.00 0.00 0.14 0.09 0.42 0.42 1.07 1.25 0.28 0.28 0.46 0.51 5.43 Extremely Stable Wind Direction by Wind Speed N WNE NE ENE E ESE SE SSE S SSW SW WIW W WW Wk NNWTOTAL -WIND 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 CALM 0.05 0.05 0.09 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.00 0.09 0.46 1.0. 3.5 mph 0.37 0.19 0.70 0.33 0.37 0.37 0.23 0.23 0.33 0.14 0.23 0.23 0.51 0.46 0.65 0.23 5.57 3.6. 7.5 mph 0.74 1.35 1.39 1.16 0.56 1.02 0.70 0.51 0.37 0.88 1.81 1.44 1.30 1.53 1.81 1.30 17.68 7.6-12.5 mph 3.25 1.02 1.16 1.16 0.51 1.11 0.65 0.65 1.07 1.35 1.95 1.53 2.51 3.90 3.90 2.65 28.38 12.6-18.5 mph 1.39 0.19 0.23 0.46 0.28 0.79 0.93 0.46 1.30 1.44 1.07 1.81 3.48 3.39 5.43 2.55 25.22 18.6-24.5 mph 0.09 0.28 1.07 0.23 0.28 0.94 0.79 0.19 1.53 2.46 2.51 2.23 3.02 3.34 3.25 0.37 22.48 :24.5 mph
LaSalle County Nuclear Station April-June. 2001 375 ft. WInd Speed and Direction 375Ft-33Ft Delta.T (F)
II Number of Observations - 2184 Values are Percent Occurrence D .................................. WIND DIRECTION CLASSES .................................. ......... STABILITY CLASSES ..........
kSS N NNE NE DIE E ESE SE SSE S SSW SW WSW W WN NW NIWTOTAL EU MU SU N SS HS ES TOTAL 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 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 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 HS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 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 N 0.05 0.05 0.00 0.18 0.05 0.00 0.05 0.05 0.09 0.05 0.00 0.00 0.00 0.00 0.05 0.00 0.60 0.60 SS 0.05 0.00 0.09 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.09 0.00 0.41 0.41 MS 0.05 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 0.05 0.00 0.14 0.14 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 0.05 0.05 0.05 1.19 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 HSU0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 N 2.01 1.05 0.64 0.09 0.00 0.05 0.46 0.23 0.46 0.60 0.27 0.23 0.18 0.41 0.32 0.46 6.46 6.46
'SS 0.14 0.00 0.05 0.05 0.09 0.00 0.00 0.05 0.05 0.14 0.18 0.37 0.09 0.18 0.23 0.05 1.65 1.65 HS 0.00 0.00 0.00 0.09 0.00 0.14 0.09 0.05 0.00 0.05 0.05 0.09 0.05 0.05 0.00 0.00 0.64 0.64 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 8.75 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 flu 0.00 K) 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00
. N 1.01 1.19 0.64 0.50 0.27 0.46 0.37 0.41 0.92 0.50 0.55 0.60 0.50 1.01 0.27 0.82 10.03 10.03 1SS 0.32 0.50 0.27 0.14 0.09 0.14 0.18 0.37 0.37 0.14 0.18 0.23 0.23 0.32 0.50 0.27 4.26 4.26 21S 0.18 0.05 0.00 0.00 0.00 0.09 8.18 0.37 0.27 0.69 0.32 0.05 0.18 0.09 0.09 0.18 2.75 2.75 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.09 0.09 0.09 0.05 0.46 0.46 17.49 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 1 M 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3SU 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.09 0.00 0.09 0.00 0.00 0.27 0.27
. N 0.27 0.37 1.37 2.47 0.60 0.46 0.60 0.73 0.73 0.64 0.64 0.60 0.69 1.37 0.50 0.18 12.23 12.23 1SS 0.41 0.23 0.18 0.64 0.73 0.27 0.18 0.18 0.27 0.32 0.46 0.37 0.37 0.60 0.46 0.37 6.04 6.04 1HS 0.05 0.09 0.00 0.00 0.05 0.14 0.37 0.46 0.82 0.78 0.37 0.23 0.14 0.14 0.23 0.00 3.85 3.85 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.23 0.00 0.00 0.14 0.05 0.00 0.18 0.78 0.78 23.17
LaSalle County Nuclear Station April-June. 2001 375 ft. Wind Speed and Direction 375Ft-33Ft Oelta-T (F)
ED .................................. WID DIRECTION CLASSES .................................. ......... STABILITY CLASSES ..........
.ASS N NIE NE ENE E ESE SE SSE S SSW SW WW W V I N NNWTOTAL EU mu SU N SS HS ES TOTAL 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 MU 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 SU 0.00 0.00 0.18 0.00 0.14 0.00 0.00 0.00 0.14 0.23 0.41 0.00 0.05 0.05 0.00 0.00 1.19 1.19 N 0.09 0.41 1.65 2.11 1.05 0.60 0.14 0.78 0.87 1.14 1.37 0.82 0.60 1.33 0.41 0.18 13.55 13.55 SS 0.09 0.09 0.41 0.41 0.41 0.60 0.27 0.32 0.46 0.55 0.64 0.18 0.32 0.64 0.46 0.09 5.95 5.95 HS 0.00 0.00 0.00 0.00 0.05 0.00 0.23 0.23 0.27 0.46 0.55" 0.50 0.09 0.27 0.05 0.00 2.70 2.70 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.05 0.09 0.23 0.23 0.00 0.09 0.00 0.87 0.87 24.33 EU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NJ 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.09 0.00 0.00 0.00 0.00 0.23 0.23 SU 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.96 0.05 0.00 0.00 0.00 0.00 1.19 1.29
- N 0.23 0.00 0.00 0.09 0.41 0.18 0.05 0.05 0.69 1.79 1.92 0.96 0.73 0.92 0.50 0.32 8.84 8.84
!SS 0.00 0.05 0.05 0.18 0.37 0.14 0.41 0.50 1.33 3.39 1.28 0.73 0.87 0.69 0.37 0.00 10.35 10.35 1HS 0.00 0.00 0.00 0.00 0.09 0.23 0.27 0.05 0.32 1.01 0.64 0.37 0.14 0.00 0.00 0.00 3.11 3.11 E:S 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.27 0.41 0.14 0.18 0.23 0.00 0.00 0.00 1.37 1.37 25.05 TOT 4.03 4.08 5.63 6.96 4.44 3.48 3.85 5.04 8.79 13.28 11.17 7.10 5.91 8.29 4.76 3.21 100.00 0.00 0.27 2.66 51.69 28.66 13.19 3.53 100.0(
Wind Direction by Stability N NNE NE EN E ESE SE SSE S SSW SW WSW W WW NW NNW TOTAL -STABILITY CIASSES 0.00 0.00 0.00 0.00 0.00 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 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.09 0.00 0.00 0.00 0.00 0.27 Moderately Unstable 0.09 0.00 0.23 0.00 0.14 0.00 0.00 0.00 0.14 0.37 1.37 0.14 0.05 0.14 0.00 0.00 2.66 Slightly Unstable 2.66 3.07 4.30 5.45 2.38 1.74 1.65 2.24 3.75 4.72 4.76 3.21 2.70 5.04 2.06 1.97 51.69 Neutral 1.01 0.87 1.05 1.42 1.74 1.14 1.05 1.42 2.47 4.53 2.75 2.01 1.88 2.43 2.11 0.78 28.66 Slightly Stable 0.27 0.14 0.00 0.09 0.18 0.60 1.14 1.14 1.74 2.98 1.92 1.24 0.60 0.55 0.41 0.18 13.19 Moderately Stable 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.69 0.69 0.23 0.41 0.69 0.14 0.18 0.27 3.53 Extremely Stable Wind Direction by Wind Speed N NNWE E BE E ESE SE SSE S SS. SW WWW " W W*0OTAL -WIND 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 CALM 0.14 0.05 0.09 0.28 0.09 0.00 0.05 0.05 0.14 0.05 0.00 0.14 0.00 0.00 0.18 0.05 1.19 1.0- 3.5 mph 1.14 1.05 0.69 0.23 0.09 0.18 0.55 0.32 0.50 0.78 0.50 0.69 0.32 0.64 0.55 0.50 8.75 3.6- 7.5 mph 1.51 1.74 0.92 0.64 0.37 0.69 0.73 1.14 1.69 1.33 1.05 0.87 1.01 1.51 0.96 1.33 17.49 7.6-12.5 mph 0.73 0.69 1.60 3.11 1.37 0.87 1.14 1.47 1.92 2.01 1.47 1.28 1.33 2.24 1.29 0.73 23.17 12.6-18.5 mph 0.18 0.50 2.29 2.52 1.65 1.19 0.64 1.33 1.92 2.43 3.07 1.74 1.28 2.29 1.01 0.27 24.31 18.6-24.5 mph 0.32 0.05 0.05 0.27 0.67 0.55 0.73 0.73 2.61 6.68 5.08 2.38 1.97 1.60 0.87 0.32 25.09 :24.5 mph
LaSalle County Nuclear Station July-Septembr. 2001 375 ft. Wind Speed and Direction 375Ft-33Ft Delta-T (F)
Nuber of Observations - 2208 Values are Percent Occurrence SPEED .................................. WIND DIRECTION CLASSES .................................. ......... STABILITY CLASSES ..........
CLASS N NNE NE ENE E ESE SE SSE S SSW SW* WSW W WNW II NW TOTAL EU K) SU N SS HS ES TOTAL 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 M)i0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CSU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 A 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 LSS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 HItS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.05 0.00 0.09 0.09 0.09 0.00 0.09 0.14 0.09 0.09 0.00 0.05 0.00 0.95 0.95 0.05 0.05 0.00 0.05 0.00 0.09 0.00 0.05 0.14 0.09 0.09 0.09 0.09 0.09 0.00 0.05 0.91 0.91 0.00 0.05 0.05 0.05 0.00 0.05 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.32 0.32 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2.17 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 HU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4SU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00
. N 0.32 0.63 0.91 0.27 0.36 0.27 0.41 0.63 0.91 1.27 0.72 1.13 0.45 0.36 0.32 0.54 9.51 9.51 7SS 0.27 0.14 0.09 0.36 0.09 0.14 0.18 0.05 0.36 0.32 0.36 0.27 0.18 0.23 0.14 0.00 3.17 3.17 MS 0.14 0.14 0.09 0.09 0.05 0.05 0.14 0.23 0.14 0.09 0.14 0.14 0.09 0.05 0.23 0.18 1.95 1.95 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.09 0.05 0.00 0.05 0.00 0.00 0.05 0.00 0.41 0.41 15.04 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 0.00 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 0.00 0.05 0.00 0.18 0.14 0.00 0.00 0.00 0.45 0.45 0.91 2.31 0.86 0.95 0.59 0.86 0.54 0.54 1.13 1.00 0.72 1.13 1.63 0.45 0.63 0.86 15.13 15.13 0.41 0.36 0.45 0.36 0.68 0.05 0.23 0.14 0.18 0.09 0.27 0.54 0.45 0.23 0.68 0.32 5.43 5.43 0.18 0.09 0.05 0.00 0.18 0.23 0.63 0.32 0.36 0.14 0.41 0.45 0.54 0.41 0.50 0.14 4.62 4.62 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.05 0.14 0.05 0.18 0.05 0.09 0.09 0.77 0.77 26.40 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 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.05 0.00 0.05 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.09 0.09 0.05 0.14 0.00 0.00 0.63 0.63 0.41 0.63 1.18 1.77 0.77 0.59 0.09 0.18 0.59 0.45 0.77 1.00 0.41 0.72 0.95 0.45 10.96 10.96 0.23 0.63 0.72 1.40 1.22 0.68 0.36 0.32 0.68 0.50 0.63 0.63 0.41 0.50 0.50 0.36 9.78 9.78 0.23 0.23 0.32 0.14 0.63 0.72 0.27 0.41 0.27 0.41 0.72 0.36 0.82 0.50 0.59 0.18 6.79 6.79 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.41 0.27 0.36 0.23 0.50 0.27 0.05 0.18 0.05 2.40 2.40 30.62
LaSalle County Nuclear Station July-Septe*br. 2001 375 ft. Wind Speed and Direction 375Ft-33Ft Delta.T (F)
SPEED .................................. WIND DIRECTION CLASSES .................................. ......... STABILITY CLASSES ..........
LAM N NINE NE ENE E ESE SE SSE S SSW SW WSW W " WNNW TOTAL EU FU SU N SS HS ES TOTAL 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 11U 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 9SU 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
- N 0.95 0.05 1.22 0.77 0.18 0.05 0.00 0.27 0.09 0.59 0.45 0.63 0.32 0.77 0.63 0.50 7.47 7.47 2SS 0.50 0.05 0.54 0.45 0.45 0.32 0.18 0.27 0.41 0.41 0.59 0.50 0.23 0.41 0.27 0.14 5.71 5.71 4HS 0.09 0.00 0.00 0.00 0.14 0.50 0.14 0.18 0.45 0.68 0.54 0.27 0.41 0.45 0.23 0.23 4.30 4.30 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.36 0.41 0.09 0.05 0.09 0.05 0.05 0.00 0.00 1.09 1.09 18.61 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 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 N
0.36 0.00 0.05 0.09 0.00 0.00 0.09 0.09 0.18 0.18 0.09 0.09 0.09 0.09 0.14 0.00 1.54 1.54 255 0.27 0.00 0.09 0.00 0.18 0.00 0.14 0.36 0.72 0.50 0.23 0.05 0.00 0.00 0.00 0.00 2.54 2.54 41H 0.00 0.00 0.00 0.00 0.09 0.09 0.09 0.09 0.18 0.36 0.05 0.05 0.41 0.09 0.09 0.00 1.59 1.59 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.32 0.77 0.09 0.00 0.00 0.00 0.05 0.00 1.40 1.40 7.16 TOT 5.39 5.66 6.70 6.79 5.62 4.76 3.62 5.43 7.93 8.79 7.52 8.38 7.38 5.62 6.34 4.08 100.00 0.00 0.05 1.22 45.56 27.54 19.57 6.07 100.00 Wind Direction by Stability N NE NE ENE E ESE SE SSE S SSW SW WSW W MW W NNWTOTAL -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 0.00 0.05 0.00 0.00 0.00 0.05 Moderately Unstable 0.00 0.14 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.32 0.09 0.27 0.18 0.14 0.00 0.00 1.22 Slightly Unstable 3.03 3.71 4.21 3.89 1.90 1.86 1.22 1.81 2.90 3.68 2.90 4.08 2.99 2.40 2.72 2.36 45.56 Neutral 1.72 1.22 1.90 2.63 2.63 1.27 1.09 1.18 2.49 1.90 2.17 2.08 1.36 1.45 1.59 0.86 27.54 Slightly Stable 0.63 0.50 0.50 0.27 1.09 1.63 1.27 1.22 1.45 1.68 1.86 1.27 2.31 1.49 1.68 0.72 19.57 Moderately Stable 0.00 0.09 0.00 0.00 0.00 0.00 0.05 "1.22 1.09 1.31 0.50 0.68 0.50 0.14 0.36 0.14 6.07 Extremely Stable Wind Direction by Wind Speed N WE NE EN E ESE SE SSE S SSW SW *W W WN NW NNWTOTAL -WIND 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 CALH 0.14 0.18 0.05 0.14 0.00 0.23 0.09 0.14 0.18. 0.18 0.23 0.18 0.23 0.09 0.09 0.05 2.17 1.0- 3.5 mph 0.72 0.91 1.09 0.72 0.50 0.45 0.72 1.09 1.49 1.72 1.22 1.59 0.72 0.63 0.72 0.72 15.04 3.6- 7.5 sph 1.49 2.90 1.36 1.31 1.45 1.13 1.40 1.09 1.68 1.31 1.54 2.36 2.94 1.13 1.90 1.40 26.40 7.6-12.5 mph 0.86 1.59 2.31 3.31 2.63 1.99 0.77 1.31 1.81 1.86 2.45 2.58 1.99 1.90 2.22 1.04 30.62 12.6.18.5 mph 1.54 0.09 1.77 1.22 0.77 0.96 0.32 1.09 1.36 1.81 1.63 1.49 1.00 1.68 1.13 0.86 18.61 18.6-24.5 mph 0.63 0.00 0.14 0.09 0.27 0.09 0.32 0.72 1.40 1.90 0.45 0.18 0.50 0.18 0.27 0.00 7.16 :24.5 mph
LaSalle County Nuclear Station October-December. 2001 375 ft. Wind Speed and Direction 375Ft-33Ft Delta-T (F)
Nmuber of Observations - 2207 Values are Percent Occurrence EEl .................................. WIND DIRECTION CLASSES .................................. ......... STABILITY CLASSES ..........
ASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WW W NNWTOTAL EU HU SU N SS HS ES TOTAL 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 HU 0.00 0.00 0.00 0.00 0.00 0.00 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 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 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 MS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 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 KJ 0.00 0.00 0.00 0.00 0.00 0.00 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 N 0.00 0.05 0.00 0.09 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.27 0.27 SS 0.05 0.00 0.05 0.05 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.23 0.23 MS 0.00 0.00 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 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 0.54 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 N 0.27 0.32 0.23 0.50 0.09 0.23 0.18 0.05 0.18 0.09 0.05 0.14 0.27 0.18 0.23 0.05 3.04 3.04 SS 0.05 .0.05 0.05 0.09 0.09 0.05 0.23 0.05 0.05 0.00 0.05 0.05 0.05 0.09 0.00 0.09 1.00 1.00 MS 0.00 0.00 0.09 0.09 0.05 0.05 0.09 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.50 0.50 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.05 0.00 0.00 0.00 0.00 0.14 0.14 4.67 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.00 0.50 0.36 0.32 0.23 0.00 0.05 0.45 0.36 0.41 0.68 0.82 0.77 0.50 0.41 0.41 7.25 7.25 0.18 0.23 0.18 0.14 0.18 0.14 0.05 0.23 0.45 0.09 0.27 0.23 0.18 0.18 0.18 0.36 3.26 3.26 0.09 0.05 0.00 0.00 0.05 0.00 0.09 0.32 0.23 0.05 0.05 0.09 0.09 0.09 0.14 0.00 1.31 1.31 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.23 0.27 0.09 0.05 0.14 0.18 0.14 0.00 1.13 1.13 12.96 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 LHU 0.00 0.00 0.00 0.00 0.00 0.00 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 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 1.00 0.68 0.23 0.41 0.27 0.32 0.23 0.63 0.59 0.68 0.82 1.22 1.54 1.09 0.63 0.77 11.10 11.10 LSS 0.45 0.18 0.32 0.18 0.45 0.32 0.14 0.14 0.68 0.45 0.54 0.23 0.32 0.68 0.54 0.41 6.03 6.03 3ItS 0.09 0.14 0.09 0.00 0.18 0.05 0.09 0.00 0.27 0.41 0.32 0.36 0.18 0.27 0.36 0.23 3.04 3.04 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.23 0.36 0.27 0.32 0.18 0.18 0.36 0.14 0.05 2.17 2.17 22.34
LaSalle Count Nuclear Station October-December. 2001 375 ft. Wind Speed and Direction 375Ft-33Ft Delta-T (F)
)EEM .................................. Iho DIRECTION CLASSES .................................. ......... STABILITY CLASSES ..........
LASS N NE NE ENE E ESE SE SSE S SSW SW WSW W " NW NNW TOTAL EU 1J SU N SS ES IS TOTAL 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 NU 0.00 0.00 0.00 0.00 0.00 0.00 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 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 N 0.14 0.00 0.68 0.36 0.00 .0.23 0.14 0.23 0.68 0.54 1.54 1.22 2.27 2.40 1.50 0.18 12.10 12.10 SS 0.18 0.00 0.27 0.27 0.27 0.23 0.50 0.14 0.45 0.63 0.50 0.54 0.77 1.72 0.63 0.36 7.48 7.48 HS 0.00 0.00 0.00 0.00 0.09 0.09 0.14 0.14 0.32 0.32 0.54 0.50 0.50 0.63 0.36 0.14 3.76 3.76 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.27 0.36 0.32 0.27 0.09 0.27 0.05 0.00 1.63 1.63 25.01 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 HU 0.00 0.00 0.00 0.00 0.00 0.00 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 0.05 0.00 0.05 0.09 0.00 0.00 0.00 0.00 0.18 0.18 SN 0.05 0.00 0.23 0.05 0.00 0.05 0.32 0.27 1.13 2.49 0.91 0.77 1.68 0.91 1.72 0.41 10.97 10.97
!SS 0.00 0.00 0.00 0.00 0.05 0.27 0.36 0.59 2.17 3.76 2.08 0.41 1.40 1.68 0.50 0.05 13.32 13.32 INS 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.45 0.14 1.09 1.54 1.63 0.41 0.18 0.05 0.00 5.62 5.62 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.27 0.45 0.54 1.68 1.09 0.23 0.00 0.14 0.00 4.40 4.40 34.48 TOT 3.53 2.17 2.76 2.54 1.99 2.08 2.76 4.30 9.15 12.55 12.32 9.97 11.06 11.46 7.70 3.62 100.00 0.00 0.00 0.23 44.72 31.31 14.27 9.47 100.00 Wind Direction by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW WM NNW TOTAL- -ITABILITY 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 0.00 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 0.00 0.05 0.05 0.05 0.09 0.00 0.00 0.00 0.00 0.23 Slightly Unstable 2.45 1.54 1.72 1.72 0.59 0.82 0.95 1.68 2.95 4.21 3.99 4.17 6.52 5.07 4.49 1.86 44.72 Neutral 0.91 0.45 0.86 0.72 1.04 1.00 1.27 1.18 3.81 4.94 3.44 1.50 2.72 4.35 1.86 1.27 31.31 Slightly Stable 0.18 0.18 0.18 0.09 0.36 0.27 0.45 0.91 1.00 1.86 2.45 2.58 1.18 1.22 0.91 0.45 14.27 Moderately Stable 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.54 1.36 1.50 2.40 1.63 0.63 0.82 0.45 0.05 9.47 Extremely Stable Wind Direction by Wind Speed N NE NE iE E ESE SE SSE S SSW SW WSW W WNW M W NNW TOTAL -WIND 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 CALM 0.05 0.05 0.05 0.14 0.00 0.00 0.05. 0.09 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.05 0.54 1.0. 3.5 mph 0.32 0.36 0.36 0.68 0.23 0.32 0.50 0.09 0.32 0.14 0.09 0.23 0.32 0.27 0.23 0.23 4.67 3.6. 7.5 mph 1.27 0.77 0.54 0.45 0.45 0.14 0.18 1.04 1.27 0.82 1.09 1.18 1.18 0.95 0.86 0.77 12.96 7.6-12.5 mph 1.54 1.00 0.63 0.59 0.91 0.68 0.54 1.00 1.90 1.81 1.99 1.99 2.22 2.40 1.68 1.45 22.34 22.68.5 h 0.32 0.00 0.95 0.63 0.36 0.54 0.77 0.50 1.72 1.90 2.90 2.54 3.62 5.03 2.54 0.68 25.01 18.6-24.5 mph 0.05 0.00 0.23 0.05 0.05 0.41 0.72 1.59 3.94 7.88 6.25 3.99 3.72 2.76 2.40 0.45 34.48 :-24.5 mnph
LaSalle County Nuclear Station January-Decemer. 2001 375 ft. Wind Speed and Direction 37SFt-33Ft Delta-T (F)
Nuber of Observations - 8752 Values are Percent Occurrence PEED .................................. WIND DIRECTION CLASSES .................................. ......... STABILITY CLASSES ..........
LASS N NNE NE ENE E ESE SE SSE S SS SW WS W MU NWM 1W TOTAL EU MU SU N . SS 11S ES TOTAL 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 HU 0.00 0.00 0.00 0.00 0.00 0.00 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 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
.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 IHS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 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 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 0.10
- N 0.03 0.05 0.01 0.09 0.01 0.02 0.05 0.05 0.02 0.03 0.03 0.02 0.03 0.01 0.02 0.01 0.50 0.50 3 SS 0.05 0.02 0.05 0.02 0.01 0:02 0.00 0.02 0.03 0.02 0.02 0.07 0.02 0.02 0.02 0.02 0.43 0.43 HS 0.01 0.01 0.01 0.01 0.00 0.01 0.00 0.00 0.02 0.00 0.00 0.00 0.02 0.01 0.02 0.01 0.15 0.15 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 0.01 0.01 0.01 1.10 ELU0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 0.00 "4SU0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00
. N 0.45 0.51 0.55 0.27 0.17 0.28 0.31 0.27 0.43 0.50 0.30 0.43 0.35 0.32 0.31 0.30 5.67 5.67 7SS 0.15 0.07 0.09 0.15 0.10 0.09 0.11 0.05 0.14 0.11 0.17 0.17 0.08 0.16 0.25 0.05 1.64 1.84 HS 0.05 0.05 0.07 0.07 0.02 0.06 0.06 0.07 0.06 0.06 0.05 0.06 0.03 0.02 0.07 0.08 0.88 0.88 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.03 0.02 0.00 0.02 0.00 0.00 0.01 0.00 0.14 0.14 8.52 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."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 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.05 0.03 0.00 0.00 0.00 0.11 0.11 N
0.86 1.26 0.65 0.65 0.39 0.51 0.38 0.42 0.66 0.57 0.70 0.91 0.97 0.72 0.69 0.70 11.04 11.04 155 0.24 0.31 0.35 0.24 0.26 0.23 0.15 0.24 0.29 0.18 0.34 0.31 0.27 0.33 0.42 0.35 4.42 4.42 2HS 0.14 0.07 0.05 0.00 0.06 0.10 0.23 0.25 0.22 0.24 0.25 0.17 0.23 0.15 0.28 0.10 2.43 2.43 ES 0.02 0.03 0.00 0.00 0.00 0.00 0.00 0.03 0.09 0.08 0.08 0.02 0.10 0.08 0.09 0.05 0.69 0.69 18.69 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 1I1K 0.00 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 0.01 0.01 3SU 0.00 0.01 0.03 0.00 0.01 0.00 0.00 0.00 0.00 0.05 0.02 0.05 0.01 0.06 0.00 0.00 0.24 0.24
. N 1.02 0.61 0.87 1.27 0.48 0.51 0.29 0.43 0.61 0.63 0.78 0.96 0.99 1.33 1.04 0.80 12.60 12.60 1SS 0.38 0.32. 0.40 0.74 0.65 0.40 0.23 0.26 0.49 0.40 0.54 0.39 0.48 0.74 0.73 0.43 7.59 7.59 8E 0.16 0.13 0.13 0.03 0.22 0.25 0.21 0.23 0.38 0.46 0.45 0.29 0.33 0.33 0.33 0.14 4.04 4.04 0.03 0.01 0.00 0.00 0.00 0.00 0.06 0.18 0.21 0.23 0.18 0.17 0.18 0.15 0.14 0.09 1.63 1.63 26.12
LaSalle County Nuclear Station January-December. 2001 375 ft. Wind Speed and Direction 375Ft-33Ft Delta-T (F)
EED .................................. WIND DIRECTION CLASSES .................................. .......... STABILITY CLASSES ..........
ASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W I4 NW NNWTOTAL EU MU SU N SS MS ES TOTAl ELU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 SU 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.03 0.08 0.10 0.00 0.01 0.01 0.02 0.00 0.35 0.35 N 0.53 0.16 0.93 0.89 0.35 0.32 0.14 0.35 0.49 0.71 0.93 0.89 1.20 1.58 1.52 0.57 11.55 11.55 SS 0.24 0.03 0.32 0.32 0.29 0.37 0.30 0.23 0.51 0.54 0.54 0.41 0.64 0.93 0.66 0.25 6.57 6.57 mS 0.05 0.00 0.01 0.00 0.08 0.16 0.22 0.15 0.32 0.41 0.47 0.42 0.39 0.48 0.23 0.17 3.55 3.55 Es 0.05 0.00 0.00 0.00 0.00 0.00 0.01 0.11 0.22 0.16 0.14 0.17 0.10 0.10 0.08 0.09 1.23 1.23 23.2:
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
.i 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 0.00 0.00 0.00 0.06 0.06 SU 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.05 0.25 0.03 0.00 0.00 0.00 0.00 0.37 0.37 N 0.17 0.07 0.33 0.10 0.14 0.06 0.18 0.10 0.57 1.25 0.81 0.57 1.02 0.80 1.27 0.25 7.69 7.69 SS 0.08 0.01 0.03 0.06 0.18 0.31 0.35 0.39 1.17 2.22 1.11 0.35 0.82 0.99 0.34 0.03 8.46 8.46 MIS 0.00 0.00 0.00 0.00 0.05 0.10 0.10 0.17 0.29 0.74 0.72 0.61 0.32 0.16 0.03 0.00 3.29 3.29 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.15 0.34 0.49 0.65 0.61 0.14 0.01 0.05 0.00 2.43 2.43 22.21 "7OT 4.71 3.75 4.94 4.92 3.52 3.61 3.38 4.22 7.63 10.24 9.65 8.18 8.81 9.49 8.43 4.51 100.00 0.00 0.08 1.07 49.05 29.31 14.35 6.14 100.01 Wind Direction by Stability N NE NE DCE E ESE SE SSE S SSW SW S W WW N" NNW TOTAL -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 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 0.02 0.01 0.00 0.00 0.00 0.08 Moderately Unstable 0.02 0.03 0.08 0.00 0.06 0.00 0.00 0.00 0.05 0.18 0.38 0.13 0.06 0.07 0.02 0.00 1.07 Slightly Unstable 3.05 2.65 3.34 3.28 1.54 1.61 1.34 1.63 2.79 3.69 3.54 3.79 4.57 4.75 4.84 2.63 49.05 Neutral 1.13 0.77 1.25 1.53 1.50 1.31 1.14 1.19 2.63 3.47 2.72 1.70 2.32 3.18 2.33- 1.14 29.31 Slightly Stable 0.40 0.25 0.26 0.11 0.42 0.69 0.83 0.87 1.28 1.91 1.93 1.54 1.33 1.15 0.87 0.50 14.35 Moderately Stable 0.10 0.05 0.00 0.00 0.00 0.00 0.07 0.53 D.89 0.98 1.05 0.99 0.53 0.34 0.37 0.24 6.14 Extremely Stable Wind Direction by Wind Speed N WE NE DCE E ESE SE SSE S SSW SW WS K WNW NW NNWTOTAL -WIND 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 CALM 0.09 0.08 0.07 0.13 0.02 0.06 0.05 0.07 0.08 0.06 0.06 0.09 0.08 0.05 0.07 0.06 1.10 1.0. 3.5 mh 0.64 0.63 0.71 0.49 0.30 0.33 0.50 0.43 0.66 0.70 0.51 0.69 0.47 0.50 0.54 0.42 8.52 3.6. 7.5 mph 1.26 1.69 1.05 0.89 0.71 0.74 0.75 0.95 1.26 1.09 1.37 1.46 1.61 1.28 1.38 1.20 18.69 7.6.12.5 mph 1.59 1.07 1.43 2.05 1.36 1.17 0.78 1.11 1.68 1.76 1.97 1.85 2.01 2.61 2.24 1.46 26.12 12.6-18.5 mph 0.86 0.19 1.31 1.21 0.77 0.85 0.66 0.85 1.58 1.90 2.17 1.90 2.34 3.10 2.51 1.09 23.27 18.6.24.5 mh 0.27 0.08 0.37 0.16 0.37 0.47 0.64 0.81 2.38 4.74 3.58 2.19 2.30 1.97 1.69 0.29 22.29 :-24.5 mph
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
APPENDIX A OFFSITE DOSE CALCULATION MANUAL
I Synopsis of ODCM Changes The proposed ODCM changes are being made as a result of the implementation of Improved Technical Specifications. Please find below a synopsis of those changes.
NOTE For an explanation of the specific changes to the ODCM, see attached document.
- 1. Many reference changes to reflect new ITS section numbers.
- 2. The definition of various terms is being changed to reflect ITS definitions.
- 3. The surveillance frequency of various instrumentation is being changed from 18 months to 24 months to reflect 24 month fuel.
- 4. The reporting date of the Annual Radiological Environmental Operating Report changes from May I to May 15.
- 5. Many clarifications to existing requirements.
- 6. Many editorial changes.
- 7. The most significant change to the ODCM involves a change in Chemistry sampling requirements after a change in power levels. Previously, sampling was required after a 15% power change. The proposed change requires sampling after a 20% change in power.
Changes to the ODCM to Support ITS Implementation Section: Chapter 12
Description:
Many administrative changes I editorial / reference changes.
Reason: Clarification / Reflect new ITS references.
Section: 12.0
Description:
Add note stating the following, "The requirements of TSR 3.0.b apply to Chapter 12."
Reason: To be consistent with surveillance requirements of the TRM as the ODCM is now an appendix to the TRM.
Section: Table 12.0-1, 12.0-2
Description:
Reference changes.
Reason: Reflect new ITS reference numbers / descriptions.
Section: 12.1.2
Description:
Definition of "Channel Calibration" is changing. The "Channel Calibration" is now required to encompass the required sensor and display. Also, the following sentence is being added: Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an in-place qualitative assessment of sensor behavior and normal calibration of the remainin' adiustable devices in the channel.
Reason: The definition is changing to include the definition from TSTF 205 to apply to the ODCM as well as the Improved Technical Specifications. See ITS page 1.1-1.
Section: 12.1.3
Description:
Definition of "Channel Check" is changing. It is now defined to be the following: A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation by epeFatien. This determination shall include, where possible, comparison of the channel indication and /-w status with to other indications aR44 or status derived from independent instrument channels measuring the same parameter.
Reason: Clarification. See ITS page 1.1-1.
Section: 12.1.4
==
Description:==
Definition of "Channel Functional Test" is changing. It is now defined to be the following: 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 aRd- or, interlock, display, and trip functions, and channel failure trips. The following is being deleted. Biddabl*o*Chaninl the injection of a simulated 6ignal inte tho seno: to 'rif,' OPERA.BILl,4i1nlu.d*in alam;n aI orF trp
Reason: To be consistent with ITS definition of Channel Functional Test (See, ITS page 1.1-2).
Section: 12.1.5
Description:
Add reference to definition of Dose Equivalent 1-131.
Reason: Clarification.
Section: 12.1.6
Description:
The definition of "Frequency" is changing. It is now defined to be the following: -Table 12.1-1 provides the definitions of various frequencies for which surveillances, sampling, etc. are performed unless defined otherwise. The-25%
'.larianc shall net be applied to Operabilit3 ' Action ntatomonts. Thme bases toe TIochni-l Specification 4.0.2 pro'.ide clarifications to this requirement. The provisions of Technical Specification 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).
Reason: To be consistent with ITS definition of Frequency.
Section: 12.1.9
==
Description:==
Add definition of "Mode." It is defined to the following: A MODE shall correspond to any one of the inclusive combination of mode switch position, average temperature, and reactor pressure vessel head closure bolt tensioning specified in Table 12.1-2 with fuel in the reactor vessel.
Reason: To be consistent with Table 1.1-1 of ITS.
Section: 12.1.11
==
Description:==
The definition of "Operable" is changing. It is now defined to be the following: A system, subsystem, tIai 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 ef seal water, lubrication, er-and other auxiliary equipment that are required for the system, subsystem, trainT division, component or device to perform its function(s) are also capable of performing their related support function(s).
Reason: To be consistent with ITS definition of Operable. (See ITS page 1.1-5).
Section: Table 12.1-1
==
Description:==
Revise frequency notation to define a refueling cycle to be 24 months.
Reason: The refueling cycle will be 24 months with the implementation of ITS.
Section: Table 12.1-1
==
Description:==
Add notation "Sesquiannually" to mean at lease once per 18 months.
Reason: New notation needed with the use of 24-month fuel.
Section: Table 12.1-1
- -. ' ='-!* * -- '. ,
Description:
Delete note which states the following: ah frequ nc. r,,uimnt . shall, be po~formed within the specfifed time inter:al with the maximun alfelow-bl extenbiOR not to exceed 25% of the frequency intor.al. The 25,0 v.airianco shall not bo applied to Operabilit,' .Artiofl statoments. The bases to T-8 4.0.2 provide clarifcationr, to this, requirement. Th~ese frequency noetations do not apply,to tho REMP (Soction; 12.5).
Reason: This information is redundant with that in ITS S.R. 3.0.2.
Section: Table 12.1-2
Description:
Add Table 12.1-2 entitled "MODES." The table is shown below:
MODE TITLE REACTOR MODE AVERAGE RX SWITCH POSITION COOLANT TEMP
( Degrees F) 1 Power Op eration Run N/A 2 Startup Refuel (a)or Startup I Hot N/A Standby 3 Hot Shutd own (a) Shutdown >200 4 Cold Shut down (a) Shutdown < or = 200 5 Refueling M) Shutdown or Refuel N/A (a) All reactor vessel head closure bolts fully tensioned.
(b) One or more reactor vessel head closure bolts less than fully tensioned.
Reason: Conform to Table 1.1-1 in ITS.
Section: Table 12.2.1-2
Description:
Change the frequency of radioactive liquid effluent monitoring instrumentation surveillance's from once every 18 months to 24 months.
Reason: The refueling cycle has been extended from 18 months to 24 months.
Section: Table 12.2.2-1
Description:
Under Action 113, the word "STARTUP" is replaced with the words "MODE 2."
Reason: MODE 2 is synonymous with the word STARTUP as described in ITS Table 1.1-1.
Section: Table 12.2.2-2
==
Description:==
Change the frequency of radioactive gaseous effluent monitoring instrumentation surveillance's from once every 18 months to 24 months.
Reason: The refueling cycle has been extended from 18 months to 24 months.
Section: Table 12.2.1-2
==
Description:==
Change the frequency of radioactive liquid effluent monitoring instrumentation surveillance's from once every 18 months to 24 months.
Reason: The refueling cycle has been extended from 18 months to 24 months.
, no sample is required before venting.
Section: Table 12.4.1-1.b, 12.4.1-1.d
Description:
The following sentence is being deleted ..........
"Analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of the RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. If there are several power transients that exceed 15%, the off gas sample may be delayed until after the last transient provided it is within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the first transient (See Technical Specification clarification 01/87 (p. 17) signed by the Station Manager 3123187.)"
it is being replaced by the following statement ...........
"Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20% 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."
Description:
The following sentence is being deleted ..........
"Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3."
It is being replaced by the following statement ...........
"Samples shall 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 once hour. This requirement does not apply if 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. 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."
Reason: This change was made due to the fact that CTS 3.4.8 was removed as an administrative change since it did not meet any of the 4 criteria of 10 CFR 50.36. The words in the ODCM were modified to be consistent with Dresden and Quad Cities Station.
Section : Table 12.4.1-1.c
==
Description:==
The following sentence is being moved from Table 12.4.1-1.h to Table 12.4.1-1.c. u When SBGT equipment is started and shutdown, ensure noble gas iodine and particulate samples are taken.
Reason: Clarification.
Section: Table 12.4.1-1.h
==
Description:==
A paragraph has been revised to read as follows: Ifthe drywell is purged in accordance with the T-,chnical Spei,,,fication; and O,,DCM definitions, both noble gas and tritium analyses must be completed before the purge begins. If the drywell is simply vented in accordance with the Technical eifictionand ODCM definitions, no sample is required before venting.
Reason: Clarification.
Section: 12.4.4.C, 12.4.5.C
==
Description:==
Reference change from Section 11.3 and 11.0 to II.B and II.C of Appendix I, 10 CFR Part 50 for gaseous effluents.
Reason: Reflect appropriate reference in the Code of Federal Regulations.
Section: 12.4.6.B.2
==
Description:==
The term "Operational Condition" is replaced with the word "Mode."
Reason: These two terms are synonymous with each other. (See ITS Table 1.1-1)
Section: 12.4.8.A
==
Description:==
The Operability requirements for Main Condenser - Gaseous Effluents has been changed to the following:
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 3.4 E5 microGepiescuries / second after decay of 30 minutes.
Applicability: Operational Coe^nd-itions MODE 1,2-ai4-4.
MODES 2 and 3 with any main steam line not isolated and steam jet air ejector (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 3.4 E5 microeepiescuries I 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 be nhat east STARTUP '.'.th the m.ain rtam inolation wahsoc cloed within tho Ret 6 hews*, 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 />.
Reason: To be consistent with ITS.
Section: 12.4.8.B.2 1
Description:
States that the determination of 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 spec 12.4.8.A at the following frequencies by performing an isotopic analysis of a representative sample of gases taken prior to the holdup line. The change involves the following wording regarding this statement: Not required to be performed until 31 days after any main steam line not isolated and SJAE not in operation.
Reason: To be consistent with ITS.
Section: Table 12.5-3
Description:
Remove reference to footnote (1).
Reason: Footnote I did notexist.
Section: 12.6.1
==
Description:==
The submittal date of the Annual Radiological Environmental Operating Report changes from May I to May 15.
Reason: Conforms with ITS 5.6.2.
Section: 12.6.1
==
Description:==
State that the material provided in the Annual Radiological Environmental Operation Report shall be consistent with the objectives outlined in the ODCM as well as 10 CFR 50.
Reason: Clarification.
Section: 12.6.1
==
Description:==
State that the submittal of the Annual Radiological Environmental Operation Report should combine sections common to all units at the station.
Reason: Clarification.
Section: 12.6.2.a
==
Description:==
State that the Radioactive Effluent Release Report shall be submitted in accordance with 10 CFR 50.36a prior to May I of each year.
Reason: Conforms with ITS 5.6.3.
Section: 12.6.2.a
==
Description:==
Delete the following statement: The period of the, it repor shll begin with the date of initial criticaky-.
Reason: LaSalle is an operational plant. This statement is no longer applicable.
Section: 12.6.2.a
==
Description:==
Add the following wording in regard to the Radioactive Effluent Release Report. The report shall include a summary of the quantities of radioactive liquid and gaseous effluent and solid waste released from the unit. The material provided shall be
consistent with the objectives outlined in the ODCM and the Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.
Reason: Clarification.
Section: 12.6.2.c
==
Description:==
Add the following wording in regard to the Radioactive Effluent Release Report. 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.
Reason*' Clarification.
Section: 12.6.2.c
==
Description:==
Delete the following statement: "however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
Reason: LaSalle does not have separate radwaste systems. This statement-is not applicable to LaSalle.
Section: 12.6.3.1 Des*c-ription: Remove statement concerning the need for the ODCM to be approved by the Commission prior to implementation.
Reason: This statement is longer applicable as the ODCM has already been approved for use.
Section: 12.6.3.1
==
Description:==
Add the following wording: The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and ,liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip set points, and in the conduct of the radiological environmental monitoring program.
Reason: Clarification.
Section: 12.6.3.2
==
Description:==
Add the following wording: The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the Infor*ation that should be included in the Annual Radiological Environmental Operating;,and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3.
Reason: Clarification.
Section: 12.6.3.2.a
==
Description:==
Replace the wording "Specification 6.5.8" with the wording "the Quality Assurance (QA) Manual."
Reason: Since existing Federal Code exists (10 CFR 50 App B), this no longer meets any of the criteria of 10 CFR 50.36. Therefore, the specific reference is a licensee document (ie, QA manual).
ii Section: 12.6.3.2.a.2.a
==
Description:==
Removed statement from procedure stating that the ODCM must be reviewed and accepted by the onsite review and investigative function, prior to implementation and to document this review.
Reason: This requirement is being relocated to the QA manual. The review activities performed are required by ANSI N18.7-1976. Thus, the provisions are not necessary to be included in the ITS to provide adequate protection of the public health and safety, given the existence of these redundant requirements. Changes to the QA manual are controlled by the provisions of 10 CFR 50.54.
LASALLE Revision 3 May 2001 LASALLE ANNEX INDEX CHAPTER 10 Revision 3 I
P:*procudapprmido UlslOr3.doc 10-i
LASALLE Revision 3 May 2001 CHAPTER 10 RADIOACTIVE EFFLUENTTREATMENT AND 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 Umits 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 7 1.. System Description 7
- 1. Radwaste Discharge Tanks 7
- 2. Cooling Pond Blowdown 7
- 2. Radiation Monitors 7
- 1. Uquid Radwaste Effluent Monitor 7
- 2. Service Water Effluent M6nitors 7
- 3. RHR Heat Exchanger Cooling Water Effluent Monitors 7 P.procupgdfapproveodcrnIss1 r3.doc 10-ii
LASALLE Revision 3 May 2001 CHAPTER 10 RADIOACTIVE EFFLUENTTREA TMENT AND MONITORING Table of Contents (Cont'd)
NUMBER PAGE
- 3. Alarm and Trip Setpoints .......................................................................................... 7
- 1. Setpoint Calculations .................................................................................... 7
- 1. Uquid Radwaste Effluent Monitor ...................................................... 8
- 2. Service Water Effluent Monitors ...................................................... 8
- 3. RHR Heat Exchanger Cooling Water Monitors ................................. 8
- 2. Discharge Flow Rates .................................................................................... 8
- 1. Release Tank Discharge Flow Rate ..................................................... 8
- 3. Release Umits ................................................................................................ 9
- 4. Release Mixture ............................................................................................. 9
- 5. Conversion Factors ...................................................................................... 9
- 6. Liquid Dilution Flow Rates ........................................................................... 10
- 4. Allocation of Effluents from Common Release Points ............................................... 10
- 5. Projected Doses for Releases .................................................................................. 10 10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM ..................................... 10 P.Npracupgd\approvedcodcmJlsIOr3.doc 10-iii
LASALLE Revision 3 May 2001 CHAPTER 10 LIST OF TABLES NUMBER PAGE 10-1 Assumed Composition of the LaSalle Station Noble Gas Effluent ..................... 10-11 LIST OFFIGURES NUMBER PAGE 10-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram .................... 10-12 10-2 Simplified Uquid Radwaste Processing Diagram .................................................. 10-14 10-3 Simplified Liquid Effluent Flow Diagram .............................................................. 10-15 10-4 Simplified Solid Radwaste Processing Diagram ................................................... 10-16 P:rcupgd~apprmedwdcmJsl r3.doc 10-iv
LASALLE Revision 3 May 2001 CHAPTER 10 RADIOACTIVE EFFLUENTTREA TMENT AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description A simplified gaseous radwaste and gaseous effluent flow diagram are provided in Figure 10-1.
The airborne release point for radioactive effluents is the ventilation stack which is classified as a stack in accordance with the definitions in Section 4.1.4 and the results in Table A-1 of Appendix A
In addition, the standby gas treatment system effluent is released through a separate stack inside the ventilation stack. This release point has the same location and classification as the ventilation stack.
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 in the Fall of 1998.
Sampling and analyses of each batch of oil is required to be performed in accordance with ODCM Table 12.4.1-1. 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, is a ground level release, and will be quantified and considered In dose calculations.
Airborne releases to the environment may result if 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.
P:\procupgd\approvedlodcm'ls1Or3.doc 10-1
LASALLE Revision 3 May 2001 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 ttCVcc png* and the high range channel replaces the mid-range channel at a concentration of 10 tICi/cc 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 giCVcc png the mid/high-range samplers are brought on line, and at a concentration of 0.1 i.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 Oi/cc png and the high range channel replaces the mid-range channel at a concentration of 10 RCVcc 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.
P.*omcupgdfprooep d cm\Ls1Or3 doc 10-2
LASALLE Revision 3 May 2001 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 pCVcc png the mid/high-range samplers are brought on-line, and at a concentration of 0.1 p.CVcc 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 11.5.2.2.2.
10.1.2.3 Reactor Building Ventilation Monitors Monitors 1 (2)D1 8-NO09 continuously monitor the effluent from the Unit 1(2) reactor building. On high alarm, the monitors automatically initiate the following actions:
A. Shutdown and isolation of the reactor building vent system B. Startup of the standby gas treatment system C. Isolation of primary containment purge and vent lines Pertinent information on these monitors is provided in LaSalle UFSAR Section 11.5.2.1.1.
10.1.2.4 Condenser Air Ejector Monitors Monitors I (2)D1 8-N002/N01 2 (pre-treatment) and 1 (2)D1 8-N903ANB (post-treatment) continuously monitor gross gamma activity downstream of the steam jet air ejector and prior to release to the main stack.
On "high-high-high" alarm monitor 1 (2)D18-N903N1B automatically initiates closure of valve 1 (2)N62-F057 thus terminating the release.
Pertinent information on these monitors is found in LaSalle UFSAR Sections 11.5.2.1.2 and 11.5.2.1.3.
10.1.2.5 Turbine Building Trackway In order to quantify any identified 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.
P:ProcupgdPprovedkdcm\ls1Or3.doc 10-3
LASALLE Revision 3 May 2001 10.1.3 Alarm and Trip Setpoints 10.1.3.1 Setpoint Calculations 10.1.3.1.1 Reactor Building Vent Effluent Monitor The setpoint for the reactor building vent effluent monitor is established at 10 mR/hr.
10.1.3.1.2 Condenser Air Ejector Monitors Pre-Treatment Monitor The high trip setpoint is established at 1.5 times the nominal nitrogen-1 6 (N-1 6) background dose rate to help ensure that effluents are maintained ALARA.
The high-high trip setpoint is established at < 100 p.CVsec per MW-th = 3.4E+05 L.CVsec per Technical Specification 3.11.2.2.
Post-Treatment Monitor The off-gas isolation setpoint Is conservatively set at or below one-half the release limit calculated using 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)
P5 Qsvs xEx[Rpng /Roo]+FoG P Off-gas Post-treatment Monitor Isolation Setpoint [cps]
The off-gas post-treatment monitor setpoint which initiates isolation of flow of off-gas to the station vent stack.
Qsvs Actual Station Vent Stack High Alarm Setpoint [gi/CVsec of png]
The actual high alarm setpoint of the Station Vent Stack wide range gas monitor In units of p*C/sec of png (pseudo noble gas). This is determined by using Equations 10 3 and 10-4 and then converting the result to units of p.Ci/sec of png.
E Efficiency of the Off-Gas Post Treatment Monitor [cps/(pCi/sec of off gas mix)]
Rp Response of the Station Vent Stack WRGM to Pseudo Noble Gas
[cpm per p.Ci/cc of pseudo noble gas]
RF6 Response of the Station Vent Stack WRGM to Off Gas [cpm per p.Ci/cc of off gas]
FOa Maximum Off-Gas Flow Rate [cclsec]
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 PAprocugftpprvedWdcm\1s10r3.doc 10-4
LASALLE Revision 3 May 2001 units of lgCVsec 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 ILCVsec of pseudo noble gas before being entered into the monitor data base.
10.1.3.1.4 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 p.C/sec 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 j.Ci/sec of pseudo noble gas before being entered into the monitor data base.
10.1.3.2 Release Limits 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 Q19 is found by solving Equations 10-3 and 10-4.
(103)
(1.11) Q. T{f 1 1) 500 mrem/yr Q 1, .Z{Lfif(X /Q), exp( -Ai RI3600 U,)t +(1.11)(fj)S 1 I < 3000 mrem lyr 4 The summations are over noble gas radionuclides i.
Fractional Radionuclide Composition:
The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides.
C6 Total Allowed Release Rate, Stack [t.CVsec of ODCM mix]
Release The total allowed release rate of all noble gas radionuclides released as stack releases in units of pCVsec of the mix specified in section 10.1.3.3.
t exp (-;4R/3600 U.) is conservatively set equal to 1.0 for purposes of determining setpoints.
The remaining parameters In Equation 1 0-3 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 mrem/yr) 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 mrem/yr) due to noble gases released in gaseous effluents (see Section A.1.3.2 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 in the RETS.
P:*procupgd~approvedvxdcm'ls1Or3.doc 10-5
LASALLE Revision 3 May 2001 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 Row Rates The main stack flow rate is obtained from either the process computer orflonitor 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 "Radioactivegaseous 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.
P.\procupgdcappromddcmnlslOr3.doc 10-6
LASALLE Revision 3 May 2001 10.2 LIQUID RELEASES 10.2.1 System Description A simplified liquid radwaste and liquid effluent flow diagram are provided In Figures 10-2 and 10-3.
The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by filter, demineralizer, or evaporator for the purpose of reducing the total radioactivity prior to release to the environment. The system is described in Section 11.2.2 of the LaSalle UFSAR.
10.2.1.1 Radwaste Discharge Tanks There are two discharge tanks (1(2)WFO5T, 25,000 gallons each) which receive water for discharge to the Illinois River via the cooling lake blowdown.
10.2.1.2 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.
10.2.2 Radiation Monitors 10.2.2.1 Liquid Radwaste Effluent Monitor Monitor OD1 8-K907 monitors all releases from the release tanks. On hi-hi alarm the monitor Wautomatically 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 11.5.2.3.3.
10.2.2.2 Service Water Effluent Monitors Monitors 1/(2)DI8-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 11.5.2.3.2.
10.2.2.3 RHR Heat Exchanger Cooling Water Effluent Monitors
................-Instrument channels 1/(2)D18-N906/8 continuously'rimioritorlhe RHR`e'afe water effluent. On high alarm the operating loop may be terminated manually and the redundant loop brought on line. No control device is initiated by these monitors.
Pertinent information on these monitors is provided in LaSalle UFSAR Section 11.5.2.3.4.
10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of RETS are not exceeded in the unrestricted area.
P.\procupgdWpprowed~dcm\ls1Or3.doc 10-7
LASALLE Revision 3 May 2001 10.2.3.1.1 Liquid Radwaste Effluent Monitor The monitor setpoint is found by solving equation 10-5 for the total isotopic activity.
P < K x [E CT / 1: (CT / 10xDWCi)] x [(F + Fr,,Frr. (10-5)
P Release Setpoint [cpm]
K [E (K.x CQx WY 7,CdT [cprnliCVml Ki Counting efficiency for radionuclide i [cpm/Y&cvmr W, Weighting Factor CIT Concentration of radionuclide i in the release tank. [_Cvmr]
F rrr Maximum Release Tank Discharge Flow Rate [gpm]
The maximum flow rate is 45 gpm.
DWC Derived Water Concentration [p.Ciml]
of radionuclide I The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402.
10 Multiplier associated with the limits specified in 12.3.1 .A.
Fd Dilution Row [gpm]
10.12.3.1.2 Service Water Effluent Monitors The monitor setpoint is established at two times the background count rate (not to exceed 10000 cpm).
10.22.3.1.3 RHR Heat Exchanger Cooling Water Monitors The monitor setpoint is established at two times the background count rate (not to exceed 10000 cpm).
P:*procupdoapprovedodcrnm\Is1 Or3.doc 10-B
LASALLE Revision 3 May 2001 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Release Tank Discharge Flow Rate Prior to each batch release, a grab sample is obtained.
The results of the analysis of the sample determine the discharge rate of each batch as follows:
Fr. = 0.1 x [F/. (C /1IxDW--] (10-6)
The summation is over radionuclides i.
0.1 Reduction factor for conservatism.
Fr. Maximum Permitted Discharge Flow Rate [gpm]
The maximum permitted flow rate from the radwaste discharge tank.
F1 Dilution Flow [gpm]
Ci Concentration of Radionuclide I In the Release Tank [RC/mL]
The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank.
DWC, Maximum Permissible Concentration of Radionuclide i [hCVmI]
The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402.
10 Multiplier associated with the limits specified in 12.3.1 .A.
MF Multiplication Factor Fr,. < 0.5; MF = 3 0.5 < Frmv < 5; MF=5 5 < Fr,,.; MF = 7.5 10.2.3.2.2 Recommended Release Tank Flow Rate.
F',m ---F" rna °XM F'.. .....
"0(0-7)
Frr recqmmended discharge flow rate (gpm)
Frr, maximum permitted discharge flow rate (gpm)
MF multiplication factor.
p:*procupgdjapprovet\odcm'Js1 Or3.doc 10-9
LASALLE Revision 3 May 2001 10.2.3.3 Release Limits Release limits are determined from RETS. Calculated maximum permissible discharge rates are divided by 10 for conservatism and to ensure that release concentrations are well below applicable derived water concentrations (DWC).
10.2.3.4 Release Mixture 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 WASTEIPROCESS 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.
P-\orpcuPgd*PproedM=ris1Or3.doc 10-10
LASALLE Revision 3 May 2001 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 1.7E-1 Kr-90 3.7E-1 Xe-131m 2.OE-5 Xe-133m 3.8E-4 Xe-133 1.1 E-2 Xe-135m 3.4E-2 Xe-135 2.9E-2 Xe-137 2.OE-1 Xe-138 1.2E-1 P.-procupgd~apprved odcm'ls lOr3.doc 10-11
Qr Scj ci,
)1 01 9.
I qd w
-J 8
0 IS
-ft 0.
I
INV IiI'iI II ii' ViI 111111111 t)-------------
LASALLE Revision 3 May 2001 OPSUE DOW~~CLUn ICAIL LASLL CU~ TAION FHWMI0.2 SDPUEDL P IiST PRCESSNG DAGRA P.Aprocupg&ýmprvedzodcrnUslM do, 10-14
LASALLE Revision 3 May 2001 OFFSITE DOW CALCtLA11OHMMIUAL-.
tmaaouaiu LA5SALLE COUNTY STATION..
FJRnM 10-3 In SUIMPURED UCUID EFFLUJENT FL~OW DLAGRAM P.\procupgdtopproveciAodcrn\1slOr3 dac 10-15
LASALLE Revision 3 May 2001 is i
-m OR:S31E DOWE CALCULAflON MANUAL ILASALLIE COUNTY STAWNO 1!" -"- SIAPLIFED SOLID RAWASTE PROESJ DIAGRAM p.\rCUpgd~apprvefdodcm*'JslOr3.doc 10-16
LASALLE Revision 3 May 2001 CHAPTER 11 LaSalle Annex Index Revision 3 p*.procupgftproved~odcm\1s1 Ir3.doc 11-i
LASALLE Revision 3 May 2001 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS CHAPTER ITEPAGE 11 Radiological Environmental Monitoring Program 11-1 LIST OF TABLES NUMBER TITLE 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:.procupgtdapprovyNefdcm\Js1 1r.doc 11-ii
LASALLE Revision 3 May 2001 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:-procupgdopproedkxacrns 1 I r3.doc 11-1
I LASALLE Revision 3 May 2001 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Location Collection Frequency of Analysis
- 1. Airborne Continuous sampler Radiolodine Canisters:
operation with particulate Radiolodine and a. Indicators-Near Field sample collection weekly, 1-131 analysis biweekly on Particulates or more frequently if near field and control L-01, Nearsite No. 1, 1.5 mi NNW (2.4 km R) required by dust loading, samples1 .
L-03, Onsite No. 3, 1.0 ml ENE (1.6 km D) and radiolodine canister L-05, Onsite No. 5, 0.3 ml ESE (0.5 km F) collection biweekly. Particulate Sampler:
L-06, Nearsite No. 6, 0.4 ml WSW (0.6 km M)
Gross beta analysis followlnp weekly filter change and gamma isotopic analysis3 quarterly on composite filters by location on near field and control samples.1
- b. Indicators-Far Field L-04, Rte 170, 3.2 ml E (5.1 km E)
L-07, Seneca, 5.2 ml NNE (8.4 km B)
L-08, Marseilles, 6.0 ml NNW (9.7 km R)
L-11, Ransom, 6.0 ml S (9.7 km J)
.4 LASALLE Revision 3 May 2001 Table 11-1 (Cont'd)
Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency 2nd/or Sampk SamDle or Monitoring Location Collection Frequency of Analvl
- 2. Urc aito a. Indicator-Inner Ring Quarterly Gamma dose on each TLD 1-101-1, 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) 1-102-2, 0.6 mi 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 (1.1 km E)
L-106-1, 1.4mi ESE (2.2 km F)
L-106-2, 1.4 ml ESE (2.2 km F)
L-107-1, 0.8 mi SE (1.3 km G)
L-107-2, 0.8 mi SE (1.3 km G)
L-108-1, 0.5 mi SSE (0.8 km H)
L-108-2, 0.5 ml SSE (0.8 km H)
L-109-1, 0.6 ml S (1.0 km J)
L-109-2, 0.6 ml S (1.0 km J)
L-110-1, 0.6 mi SSW (1.0 km K)
L-110-2, 0.6 ml SSW (1.0 km K)
L-111b-1, 0.8 ml SW (1.3 km L)
L-111b-2, 0.8 ml SW (1.3 km 1) 1-112-1, 0.9 mI WSW (1.4 km M)
L-112-2, 0.9 ml WSW (1.4 km M)
L-113a-1, 0.8 ml W (1.3 km N)
L-1 13a-2, 0.8 ml W (1.3 km N)
L-114-1, 0.9 mi WNW (1.4 km P)
L-114-2, 0.9 ml WNW (1.4 km P)
L-115-1, 0.7 mi NW (1.1 km Q)
L-115-2, 0.7 ml NW (1.1 km Q) 1-116-1, 0.6 ml NNW (1.0 km R)
L-116-2, 0.6 mi NNW (1.0 km R) p:\procupgd~approved\odcm1s1 I r3.doo -
11-3
ft LASALLE Revision 3 May 2001 Table 11-1 (Cont'd)
Radiolodical Environmental Monitorina Proaram Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitorina Location of-Analysis Collection Frequency
- 2. Direct Radiation b. Indicators-Outer Ring (Cont'd) L-01 -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 ml 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 mi 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 mi SE (6.9 km G)
L-206-2, 4.3 mi 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 mi SW (5.3 km L)
L-210-2, 3.3 mi SW (5.3 km L)
L-211-1, 4.5 mi WSW (7.2 km M)
L-211-2, 4.5 ml 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 Q)
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)
).\procupgdfapprovedkodcmVi9 1lr3.doo 11.4
41 LASALLE Revision 3 May 2001 L Table 11-1 (Cont'd)
Radioloalcal Environmrnntnl Mnnitntlnn Dmrnram Rdoola Enviromenta Mo........
ev~tprinl
- n. i Pr e*l-m Exposure Pathway Sampling or Type and Frequency and/or Sampln Sample or Monitoring Location Collection Frequency of Analysis
- 2. Direct Radiation C. Oiter (Cont'd)
Ihdicator, One at each of the airborne location given in part 1.a and 1.b.
d.Controls One at each airborne control location given In part 1.c.
t p.Vprocupgdfapproverodcm\ls 1 r3.doo 11-5
4 LASALLE Revision 3 May 2001 Table 11-1 (Contd)
Radiological Environmental Monitoring Program Exposure Pathway Exposure Pathway Sampling or Type and Frequency and/or Sam..e Sample or Monitoring Location Collection Frequency of-Analysis
- 3. Waterbome 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 0)
There Is no drinking water pathway within 6.2 ml (10 km) downstream of station.
- a. Indicator Weekly grab sample Gross beta and gamma L-40, Illinois River downstream, isotopic analysis on 5.2 mi NNW (8.4 km R) monthly composite; tritium analysis on quarterly composite.
Weekly grab sample Gross beta and gamma
- a. Contrl Isotopic analysis on monthly composite; tritium L-21, Illinois River at Seneca, analysis on quarterly 4.0 ml NE (6.4 km C) composite.
- a. Indicators Semiannually Gamma Isotopic analysis 3
- e. Sedlmentg semiannually.
L-40, Illinois River downstream, 5.2 ml NNW (8:'4 km R)
L-41, Illinois River downstream 4.6 ml NNW (7.4 kmn A) p:*procupgd~appoved odcmis1 I r3.doo 11-6
t LASALLE Revision 3 May 2001 Table 11-1 (Cont'd)
Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Location Collection Frequency of Analysis
- 4. Ingestion Biweekly: May through Gamma isotopic 3 and 1-131
- a. MilE a. Indicators October; monthly: analysis 4 biweekly May November through April through October, monthly At the time of this revision, there are no dairies November through April.
within 6.2 miles which consistently produce milk.
- b. Conirols L-42, Biros Dairy, 14.2 ml E (22.9 km E)
- b. Eiab a. Indicator Two times annually Gamma isotopic analysis L-35, Marseilles Pool of Illinois River, on edible portions of each 6.5 ml NW (10.5 km 0)
- c. Food Prducts a. Indicators Two samples from each of the four major quadrants within 6.2 miles of the station, if available. Annually Gamma isotopic analysis 3 each sample.
Sample locations for food products may vary based on availability and therefore are not required to be identified here but shall be taken.
- b. Controls Two samples within 9.3 to 18.0 miles of the station, If available.
p:.\procupgdAappraved~ocm\Isi 1r3.doo 11-7
LASALLE Table 11.1 (Cont'd) Revision 3 Radiological Environmental Monitop., b)... May 2001 a....b...c, E-,gram Its Farorigin field in samples airborne areeffluents analyzedreleased when near fromfield the results station arenr inconsistent 4L.. ...with previous
.# measurnno ,, ._ .. .....
dauighterdecay, analysis,,shallrbe performed sampleor if gross beta activltin air particulate . ,. ...~ ..~ ~...~~~~4 , ur aoactivi y Is confirm ed as having samples aonatheninditeiduan GAirore aotartcuat mpaIc naysmpl is m fllrsshall beaaye is greater than 10 o rs earadioactIvity 24 times hoursthe or more yearlyafter sampling to allow for radon andi thoron anth Ind enividu samays i n a d q a tfc to fga m mti g r d o u lsal mean of control samples, gamma isotopic gamttrmuabIsoto uepiecff t
Gamma Isotopic from the station. analysis means the Identification and quantificatin of gamma emitting radionuclides that" 1-31 analysis means t 1,-
S.......... U-',a.yucal separation and counting procedure are specific for this radionuclide. 0 P'PrupA~approVed~odcmVs M113.doo 11-8 r
LASALLE Revision 3 May 2001 ty206-1 SOA42 Gaind Ridge 21 -
.11OR-OS I
Sbuator La So" County _
7.
Sy
- Air Sam A~g La05tian
- lt Locaton OFTEr DOSE CAKAWO MIAL
- LaSalle Station LA SALLE COWY STAflOS a 2 a
- POMSILAMU14G UMAN OUTER 4OMLDLOCATCH P:'procupgd~appmvd~odcrnMsl1 r3.doc
LASALLE Revision 3 May 2001 U..& e ~ a
%a is N TLM Umation *OFFME DOSE CAULA ANUMMAL
[ A SALLE COUNTY STATIO RAE MaWC114X p-\procupgd'aPofed~xdcfT~sl I r3 doc 11-10
LASALLE Revision 3 May 2001 411 OFFMIT DOSE CALCIJIflON UMAUAL
' 'U ' LA SALLE COUNTY STATIO dFGRI- a 9 -.- .
J Fish 1=1 m AND WATERBORNE EXOSURE m Milk ArASAPEL=C
- SeAdWA SMPardCNO
- WSW.
.%prcupgWroeftýIsl1 rS.doc 11-11
LASALLE Revision 3 May 2001 LASALLE ANNEX INDEX CHAPTER 12 Revision 3 SPECIAL NOTE The transfer of the Radiological Effluent Technical Specifications (RETS) to the ODCM has been approved by the Nuclear Regulatory Commission in Amendments 85/69.
P:\prcp arofvedocm\S12r3 12-i
LASALLE Revision 3 May 2001 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 Liquid Effluent Monitoring Instrumentation 12-8
- 2. Radioactive Gaseous Effluent Monitoring Instrumentation ., 12-13 12.3 LIQUID EFFLUENTS 12-19
- 1. Concentration 12-19
- 2. Dose 12-25
- 3. Uquid Waste Treatment System 12-27 12.4 GASEOUS EFFLUENTS 12-29
- 1. Dose Rate 12-29
- 2. Dose - Noble Gases 12-36
- 3. Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form 12-37
- 4. Gaseous Radwaste Treatment System 12-39
- 5. Ventilation Exhaust Treatment System 12-40
- 6. Venting or Purging 12-41
- 7. Total Dose 12-42
- 8. Main Condenser 12-44
- 9. Dose Umits for Members of the Public 12-45 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-46
- 1. Monitoring Program 12-46
- 2. Land-Use Census- ..- II- - *-,- - 12-59
- 3. Interlaboratory Comparison Program 12-60 12.6 REPORTING REQUIREMENTS 12-61
- 2. Radioactive Effluent Release Report 12-62
- 3. Offsite Dose Calculation Manual (ODCM) 12-63
- 4. Major Changes to Radioactive Waste Treatment Systems 12-64 P.AprocugdapproveWdcmWs12r3 12-ii
LASALLE Revision 3 May 2001 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 Uquid 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 12-49 12.5-2 Reporting Levels for Radioactivity Concentrations In Environmental Samples 12-55 12.5-3 Detection Capabilities for Environmental Sample Analysis 12-56 P:.procupgd\approvedxodcm\s12r3 12-iii
LASALLE Revision 3 May 2001 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 requirerments, 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.
12-1
LASALLE Revision 3 May 2001 TABLE 12.0-1 EFFLUENT COMPLIANCE MATRIX Regulation Dose to be compared to limit ODCM RETS Technical Equation Specification 10CFRS0 Appendix I
- 1. gamma air dose and beta air dose due to airborne radioactivity in A-1 A-2 12.4.2 5.5.4.h i effluent plume.
1.a whole body and skin dose due to A-6 N/A N/A airborne radioactivity in effluent A-7 plume are reported only if certain gamma and beta air dose criteria are exceeded.
- 2. CDE for all organs and all four age A-13 12.4.3 5.5.4.i groups due to lodines and particulates In effluent plume. All pathways are considered.
- 3. CDE for all organs and all four age A-29 12.3.2 5.5.4.d groups due to radioactivity 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 airborne and liquid-borne). CDE evaluation Is made for adult only using FGR 11 database.
4DCFR190 1. Whole body dose (DDE) due to A-35 12.4.7 5.5.4.j (now by direct dose, ground and plume reference, also shine from all sources at a station.
part of 10CFR20) 2. Organ doses (CDE) to an adult due A-13 to all pathways.
Technical 1. "instantaneous whole body (DDE), A-8 12.4.1 5.5.4.g Specifications thyroid (CDE) and skin (SDE), dose A-9
°,
rates to an adult due to A-28 radioactivity in airborne effluents.
For the thyroid dose, only 5.5.4.b inhalation is considered.
- 2. "instantaneous" concentration limits A-32 12.3.1 for liquid effluents.
Technical 1. Radioactive Effluent Release NA 12.6.2 5.6.3 Specifications Report I 12-2
LASALLE Revision 3 May 2001 Table 12.0-2 REMP Compliance Matrix Regulation Component RETS Technical Specification 10CFR50 Appendix I Implement environmental monitoring program. 12.5.1 N/A I
Section IV.B.2 10CFR50 Land Use Census 12.5.2 N/A Appendix I Section IV.B.3 10CFR50 Interlaboratory Comparison Program 12.5.3 N/A Appendix I Section IV.B.2 10CFR50 Annual Radiological Environmental Operating 12.6.1 5.6.2 Appendix I Report Section IV B.2 and Technical Specifications 12-3
LASALLE Revision 3 May 2001 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.
12.1.4 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 1-131 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 III 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 RADWASTETREATMENT 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.
12-4
LASALLE Revision 3 May 2001 12.1.10 OCCUPATIONAL DOSE - means the dose received by an individual in the course of employment in which 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 J 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, and 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 line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
12.1.16 SOLIDIFICATION - SOUDIFICATION 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 iodines or particulates from the gaseous exhaust system prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).
Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
12-5
LASALLE Revision 3 May 2001 12.1.21 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.
12-6
LASALLE Revision 3 May 2001 TABLE 12.1-1 FREQUENCY NOTATION NOTATION FREQUENCY S - Shiftly 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.
0 - 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.
B - Refueling cycle At least once per 24 months.
S/U - Startup Prior to each reactor startup.
P - Prior Prior to each radioactive release.
N.A. Not applicable.
Table 12.1-2 (Page 1 of 1)
MODES MODE TITLE REACTOR MODE SWITCH AVERAGE REACTOR POSITION COOLANT TEMPERATURE (OF) 1 Power Operation RUN N/A 2- Startup - Refuel(") or Startup/Hot -.N/A Standby 3 Hot Shutdown(a) Shutdown > 200 4 Cold Shutdown(a) Shutdown < 200 5 Refueling(b) 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.
12-7
LASALLE Revision 3 May 2001 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation Operability 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 12.3.1.A are not exceeded. The alarm trip setpoints of these channels shall be determined in accordance with the ODCM Chapter 10.
Applicability: At all times, when flow ispresent 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 Requirements 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. I -.
12-8
LASALLE Revision 3 May 2001 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. Uquid 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) 1 101
- b. Service Water System Effluent Line (Unit 2) 1 101 C. RHR Service Water (Une A) Effluent Une (Unit 1) 1 101
- d. RHR Service Water (Une A) Effluent Line (Unit 2) I 101
- e. RHR Service Water (Line B) Effluent Line (Unit 1) 1 101
- f. RHR Service Water (Line B) Effluent Line (Unit 2) I 101
- 3. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line 1 102
- b. Cooling Pond Blowdown Pipe* 1 102
- Same as River Discharge Blowdown Pipe.
12-9
LASALLE Revision 3 "May2001 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 inoperability 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.
12-10
LASALLE Revision 3 May 2001 TABLE 12.2.1-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE FUNCTIONAL CHANNEL INSTRUMENT CHECK CHECK TEST CALIBRATION
- 1. GAMMA SCINTILLATION MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluents Line D P . Q(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) 1(3)
- b. Service Water System Effluent Line (Unit 2) D M Q(2) B(3)
- c. RHR Service Water (Line A) Effluent Line (Unit 1) D M 0(2) B(3)
- d. RHR Service Water (Line A) Effluent Line (Unit 2) D M 0(2) B(3)
- e. RHR Service Water (Line B) Effluent Line (Unit 1) D M Q(2) B(3)
- f. RHR Service Water (Line B) Effluent Line (Unit 2) D M 0(2) B(3)
- 3. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line D(4) N.A. P B
- b. Cooling Pond Blowdown Pipe D(4) N.A. a E 12-11
LASALLE Revision 3 May 2001 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE 12.2.1-2 (Continued)
TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control alarm annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alarm/trip setpoint.
- 2. Loss of power.
- 3. Instrument alarms on downscale failure.
- 4. Instrument controls not set in Operate or High Voltage mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Loss of power.
f' 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 initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days in which continuous, periodic, or batch releases are made.
12-12
LASALLE Revision 3 May 2001 12.2 INSTRUMENTATION 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Operability Reauirements 12.2.2.A The radioactive gaseous effluent monitoring instrumentation channels shown in Table 12.2.2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Section 12.4.1 .A are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the ODCM.
Applicability: As shown in Table 12.2.2-1.
Action:
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint 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 12.2.2.B 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 12.2.2-2.
Bases 12.2.2.0 The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated In accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of RETS.
12-13
LASALLE Revision 3 May 2001 TABLE 12.2.2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT 1 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, K601A, R601) and/or (1(2) D18-N903B, K901B, K601B, R601)
- 2. MAIN STACK MONITORING SYSTEM
- a. Noble Gas Activity Monitor (0D18-N514, R517, R518 Low Range 1 110 WRGM) or (0D18-N515, R517, R518 Mid Range WRGM)
- b. Iodine Sampler (Grab Sampler) 1 111
- c. Particulate Sampler (Grab Sampler) 1
- 111
- d. Effluent System Flow Rate Monitor (OFT-VRO19, 0FY-VR019 and I9A, OFR-VRO19, 0D18-K510, 0D1 8-R518) 1 112
- e. Sampler Flow Rate Monitor (Low:. ODI 8-N527, ODI 8-N528, OD1 8-R518; 1
- 112 MId/HI: OD18-N530, 0D18-N531, 00D18-R518)
- 3. CONDENSER AIR EJECTOR RADIOACTIVITY MONITOR (Prior to Input to Holdup System)
- a. Noble Gas Activity Monitor (1(2) D18-N002, K613, R604) I 113 (1(2) D18-N012, K600, R605)
- 4. SBGTS MONITORING SYSTEM
- a. Noble Gas Activity Monitor (0D18-N511, R515, R516 Low Range WRGM) 1## 110 or (ODI8-N512, R515, R516 Mid Range WRGM)
- b. Iodine Sampler (Grab Sampler) 1 ##111
- c. Particulate Sampler (Grab Sampler) 1 ##111
- d. Effluent System Flow Rate Monitor (1(2) FT-VG009, 1(2)FY-VG009, 1 ## 112 1(2)FR-VG009) I
- e. Sampler Flow Rate Monitor (Low: 0D18-N521, 0D18-N522, 0D18-R516; ## 112 MId/HI: 0D18-N524, 0D18-N525, 0D18-R516)
'Equipment Part Number (EPN) numbers or monitor types are provided Inparentheses "0.
12-14
LASALLE Revision 3 May 2001 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.
During operation of the SBGTS.
ACTION110- 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 I hour.
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 within 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 12.4.1-1. (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.'- "Th-e-dffgas'tr-atmehFdlelay system noble gas activity'effiuent 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 />. I NOTE: For Actions 110 through 112 above, effluent releases may continue beyond the 30 days as long 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.
12-15
LASALLE Revision 3 May 2001 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 Alarm and Automatic Termination of Release D D Q(1) B(3) **
- 2. MAIN STACK MONITORING SYSTEM
- a. Noble Gas Activity Monitor D M Q(4) B(3)
- b. Iodine Sampler W N.A. N.A. N.A.
- c. Particulate Sampler W N.A. N.A. N.A. *
- d. Effluent System Flow Rate Monitor D N.A. Q B *
- e. Sampler Flow Rate Monitor D N.A. 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 N.A. N.A. N.A. ##
- c. Particulate Sampler W N.A. N.A. N.A. ##
- d. Effluent System Flow Rate Monitor D N.A. Q B ##
- e. Sampler Flow Rate Monitor, D N.A. Q B ##
12-10
LASALLE Revision 3 May 2001 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE 12.2.2-2 (Continued)
TABLE NOTATION At all times.
During effluent releases via this pathway.
- During operation of the main condenser air ejector.
- 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 perfdrmed using one or more of 1i"rle ferkerie ..
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 shall be used.
12-17
LASALLE Revision 3 May 2001 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 12-18
LASALLE Revision 3 May 2001 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Operability Requirements 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 gases, the concentration shall be limited to the concentrations specified in Table 12.3.1-1.
Applicability: At all times.
Action:
With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the concentration to within the above limits.
Surveillance Requirements 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 12.3.1.A.
12.3.1..B.2 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 12.3.1-2. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the 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 12.3.1 .A 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 II.A design objectives of Appendix I, 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.
12-19
LASALLE Revision 3 May 2001 TABLE 12.3.1-1 ALLOWABLE CONCENTRATION (AC) OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE AC(gCi/mll*
Kr 85 m 2E-4 85 5E-4 87 4E-5 88 9E-5 Ar 41 7E-5 Xe 131 m 7E-4 133m 5E-4 133 6E-4 135 m 2E-4 135 2E-4
- Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion In water, and R = 0.01 rem/week, pw = 1.0 gm/cm 3, and P,,Pt = 1.0. ". .
12-20 I
LASALLE Revision 3 May 2001 TABLE 12.3.1-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID SAMPLING MINIMUM TYPE OF LOWER LIMIT OF RELEASE TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD)
FREQUENCY ANALYSIS (pOVml)a A. Batch Waste P P Principal 5x10 7 Release Each Batch Each Batch Gamma Tanks' Emitters!
I-131 1xl0e P M Dissolved and lx10" One BatcWM Entrained Gases (Gamma Emitters)
P M H-3 lx10" Each Batch Compositeb Gross Alpha lxlO 7 P Q Sr-89, Sr-90 5x10"8 Each Batch Compositeb Fe-55 lx10" B. Continuous Continuousc W Principal 5x1 0" Releases! Compositee Gamma Emitters' Cooling Pond Blowdown 1-131 1x10s M M Dissolved and lx10" Grab Sample Entrained Gases (Gamma Emitters)
"-Cohtinuousc M H-3 Compositec Gross Alpha lx1O 7 Continuousc Q Sr-89, Sr-90 5x107' Compositec Fe-55 lx10" 12-21
LASALLE Revision 3 May 2001 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 'real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66esb LLD= E.V. 2.22x10 6 . Y.exp (-M.t)
Where:
LLD is the *a priod' 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),
2.22x10e is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
I 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, &tIs 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) rathler than on an unverified theoretically predicted variance. Typical values of E, V. Y, and &tshall be used in the calculation.
Alternate LLD Methodology An alternate methodology for LLD 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*)
12-22
LASALLE Revision 3 May 2001 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 (if applicable)
Y= fractional radiochemical yield or collection efficiency (if applicable) t= count time (minutes) 2.22 x 106 = number of disintegrations per minute per microCurie 2.71 + 4.654B = V + (2k 42 41B), 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 = eWt [XRT/(1 -e-'T)][Td /(1 -e'Td)] if applicable S= radioactive decay constant (units consistent with At, RT and Td)
At = "delta tf, 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 X)
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 1)
Th6LLD 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 (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.
12-23
LASALLE R3evision 3 May 2001 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, all 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.
12-24
LASALLE Revision 3 May 2001 12.3 LIQUID EFFLUENTS 12.3.2 Dose Operability Requirements 12.3.2.A The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem 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 10CFR50, Appendix I, Section IV.A, 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 IIA, III.A and IV.A of Appendix I, 10 CFR Part 50. The ULmiting Condition for Operation implements to guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept 'as low as is reasonably achievable.' Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations In the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section III.A 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, 12-25
LASALLE Revision 3 May 2001 "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 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,"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.
12-26
LASALLE Revision 3 May 2001 12.3 LIQUID EFFLUENTS 12.3.3 Liquid Waste Treatment System Operability Requirements 12.3.3.A The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from each reactor unit, from the site, when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.
Applicability: 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 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 12.3.3.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.
12-27
LASALLE Revision 3 May 2001 Bases 12.3.3.C The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." 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 including the evaporator. During extended shutdown or low power operation, i.e.,
> 92 days, when steam is not available to the concentrators and 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. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth In Section IL.A of Appendix I, 10 CFR Part 50, for liquid effluents.
12-28
LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Operability Requirements 12.4.1 .A The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY, shall be limited to the following:
- a. For noble gases: Less than or equal to a dose rate of 500 mremlyr to the total body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and
- b. For iodine-1 31, for iodine-1 33, 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 mrems/yr to any organ via the inhalation pathway.
Applicability: 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 Requirements 12.4.1.B.1 The dose rate due to noble gases in gaseous effluents'shall be determined to be within the above limits in accordance with the 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.
12.4.1.8.2 The dose rate due to iodine-1 31, iodine-1 33, tritium, and all radionuclides in particulate form with half 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 12.4.1-1.
Bases 12.4.1.C This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of RETS for unrestricted areas. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents 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 10CFR20.1301. For individuals who may at times be within the site boundary, the occupancy of the individual 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 mrem/year to the total body or to less than or equal to a dose rate of 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background via the inhalation pathway to less than or equal to a dose rate of 1500 mrem/year.
This specification applies to the release of radioactive effluents in gaseous effluents from all reactors at the site. For units within shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.
12-29
LASALLE Revision 3 May 2001 TABLE 12.4.1-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT OF TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LLD)
FREQUENCY ANALYSIS (pCVmI)a A. Containment Vent P P Principal Gamma lxi0"4 and Purge Systemh Each Purge Grab Sample Each Purgeb Emittersg H-3 lxlO06 B. Main Vent Stack Mb Mb Principal Gamma lxi1" Grab Sample Emittersg Wb'e Wbe H-3 lxil0 Grab Sample C. Standby Gas Dc Dc Principal Gamma lxi0 Treatment System Grab Sample Emitters9 D. Main Vent Stack Continuous! Wd 1-131 lxI 012 And Standby Charcoal Gas Treatment Sample SystemC 1-133 lxl 0" Continuous! Wd Principal Gamma lx0-1"1 Particulate EmittersP Sample (1-131, Others)
Continuous! M Gross Alpha lxi0" Composite Particulate Sample Cqntinuousf . 0 O Sr-89,Sr-90 lx0"11 Composite Particulate
.Sample Continuous! Noble Gas Noble Gases lxlo0" Monitor Gross Beta or Gamma 12-30
LASALLE Revision 3 Mly 2001 TABLE 12.4.1-1 (Continued)
GASEOUS RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT OF TYPE FREQUENCY ANALYSIS ACTIVITY DETECTION (LUD)
FREQUENCY ANALYSIS (,Cu/mI)a P P Principle Gamma 5x1W0" E. Oil Burner Each Batch Each Batch Emitters Grab Sample Dissolved and lx10" Entrained Gases (Gamma Emitters) 1-131 1x10" P M H-3 1x10"1 Each Batch Composite Grab Sample Gross Alpha lxi0"e Q Sr-89, Sr-90 5x10" Composite Fe-55 lxil0 12-31
LASALLE Revision 3 May 2001 TABLE 12.4.1-1 (Continued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION
- a. The ILD 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 'real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 sb LLD= E.V. 2.22x10 6 . Y. exp (-XAt)
Where:
LLD is the 'a priori' lower limit of detection as defined above (as microcurie per unit mass or volume),
8b 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),
2.22x1 0 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
x 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 Methodology An alternate methodology for LLD 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 )
12-32
LASALLE Revision 3 May 2001 TABLE 12.4.1-1 (Continued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION Where:
B = background sum (counts)
E = counting efficiency q = sample quantity (mass or volume) b = abundance (if applicable)
Y= fractional radiochemical yield or collection efficiency (if applicable) t= count time (minutes) 2.22 x 10 = number of disintegrations per minute per microCurie 2.71 + 4.654B =V + (2k 42 41B), 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 [.RT/(1.-e'RT)][XTd /(1-e'Td)] if applicable X = radioactive decay constant (units consistent with At, RT and Td)
At = "delta r, 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 .)
"Td = sample deposition time, or the duration of analyte collection onto the sample media (units consistent with X)
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 altemate 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.
12-33
LASALLE Revision 3 May 2001 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 is run more than 10 minutes in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period then it must be run a minimum of 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> run is required to meet the sample requirements for iodine and particulates.) When SBGT equipment is started and shutdown, ensure noble gas iodine and particulate samples are taken.
- d. Samples shall 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 tritium 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 12.4.1.A, 12.4.2.A and 12.4.3.A.
- g. The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Os-1 34, Cs-137, Ce-141 and Ce-1 44 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, at the 95% confidence level, together with the above nuclides, shall also be identified and reported.
- h. The drywell tritium and noble gas sample results are valid for 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> from sample time If 1) the drywell radioactivity monitors have not Indicated an increase in airbome 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 is any reason to suspect that gaseous radioactivity levels have changed in the drywell that would compromise the calculated, or estimated, radionuclide concentrations at the time of the release, since th lIat rn)ple (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 oumed 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.
12-34
LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.2 Dose - Noble Gases Operability Reg uirements 12.4.2.A The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site shall be limited to the following:
- 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.
Applicability: 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 IOCFR50, Appendix I,Section IV.A, 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 limits. This report is due to the NRC within 30 days from the end of the quarter in which the release occurred.
Surveillance Requirements 12.4.2.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 12.4.2.C This specification is provided to implement the requirements of Sections 11.B, III.A and IV.A of Appendix 1,10 CFR Part 50. The Operability Requirements are the guides set forth in Section 11.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements In Section III.A 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 Regu!atoRy 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 I, "Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Ught-Water Cooled Reactors,"
Revision I, July 1977. The ODCM equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions.
12-35
LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.3 Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form Operability Requirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from iodine-131, 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.
Applicability: At all times.
Action:
- a. With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission, pursuant to 1 0CFR50, Appendix I,Section IV.A, a report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed correction actions to be taken to assure that subsequent releases will be in compliance with the above limits. This report is due to the NRC within 30 days from the end of the quarter in which the released occurred.
Surveillance Requirements 12.4.3.B Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
12-36
LASALLE
,Revision 3 lay 2001 Bases 12.4.3.C The specification is provided to implement the requirements of Sections I1.0, III.A and IV.A of Appendix I, 10 CFR Part 50. The Operability Requirements are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept 'as low as is reasonably achievable.! The ODCM calculational methods specified in the Surveillance Requirements Implement the requirements in Section ilI.A 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 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, "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. 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) individual 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) deposition on the ground with subsequent exposure of man.
12-37
LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.4 Gaseous Radwaste Treatment System Operability Requirements 12.4.4.A The GASEOUS RADWASTE (OFF-GAS) TREATMENT SYSTEM shall be in operation.
Applicability: 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 Requirements 12.4.4.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 was 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 suithbleifraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
12-38
LASALLE Revision 3
'nay 2001 12.4 GASEOUS EFFLUENTS 12.4.5 Ventilation Exhaust Treatment System Operability Requirements 12.4.5.A The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from each reactor unit, from the site, when averaged over 31 days, would exceed 0.3 mrem to any organ.
Applicability: 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 due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM.
12.4.5.B.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.
Bases 12.4.5.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 in Sections II.B and I1.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
12-39
LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.6 Venting or Purging Operability Requirements 12.4.6.A VENTING or PURGING of the containment drywell shall be through the Primary Containment Vent and Purge System or the Standby Gas Treatment System.
Applicability: 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 Requirements 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 12.4.6.C This specification provides reasonable assurance that releases from drywell purging operations will not exceed the annual dose limits of 10CFR20 for unrestricted areas.
12-40
LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.7 Total Dose Operability Requirements 12.4.7.A The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less or equal to 75 mrem) over 12 consecutive months.
Apolicabilitv: 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 12.3.2.A.a, 12.3.2.A.b, 12.4.2.A.a, 12.4.2.A.b, 12.4.3.A.a or 12.4.3.A.b, 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 12.4.7.A. 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 12.4.7.A, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified Information of 40 CFR 190.11. Submittal of the report Is considered a timely request, and a variance Is granted until staff action on the request Is complete. The variance only relates to the limits of 40 CFR 190, and does not apply In any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.
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 12.3.2.13, 12.4.2.B and 12.4.3.B, and in accordance with the ODCM.
12-41
LASALLE Revision 3 May 2001 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 if 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 he/she Is engaged in carrying out any operation which is part of the nuclear fuel cycle.
12-42
LASALLE Revision 3 May 2001 12.4 GASEOUS EFFLUENTS 12.4.8 Main Condenser Operability Requirements 12.4.8.A 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 3.4 x 105 microcuries/second after decay of 30 minutes.
Applicability: MODE 1. MODES 2 and 3 with any main steam line 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 3.4 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 12.4.8.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.
12.4.8.8.2 *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 12.4.8.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 12.4.8.C In accordance with surveillance requirements contained Athin"ODCM Chapter 12 item number 12.4.8.1.1 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 /> if the increase is not due to thermal power changes. If the cause Is known and not fuel related and less than I hour 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.]
12-43
LASALLE Revision 3 May 2001 12.4.9 Dose Limits for Members of the Public Operability Requirements 12.4.9.A The licensee shall conduct operations such thatthe 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 monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10CFR20.1302 and with the methodology and parameters in the ODCM.
Applicability: At all times.
Action:
- 1. If the calculated dose from the release or exposure of radiation meets or exceeds the 100 mrem/year limit for the MEMBER OF THE PUBLIC, prepare and submit a report to the Commission in accordance with 1 OCFR20.2203.
- 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 1 OCFR20.2203.
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 mrem In any hour in unrestricted areas.
BaseMs 12.4..9.C This section applies to direct exposure of radioactive materials as well as radioactive materials released In gaseous and liquid effluents. 10CFR20.1301 sets forth the 100 mremnyear 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 40CFR190 standards. 10CFR20.1302 provides options to determine compliance to 10CFR20.1301. Compliance to the above operability requirement Is based on IOCFR20, 40CFR190 and LaSalle Station Technical Specification 5.5.4.g. I 12-44
LASALLE Revision 3 May 2001 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitoring Program Operability Requirements 12.5.1 .A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1.
Applicability: 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 limit(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, 12.4.2, 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) > 1.0 reporting level (1) reporting level (2)
When radionuclides other than those In Table 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 12.3.2, 124.2, or 12.4.3. 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.
- The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
12-45
LASALLE Revision 3 May 2001 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 Requirements 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 in 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 (LDs). 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 b'efore thebfbatlimit representing the capability of a mbasurdrnfent system and "nt.
as an after the fact limit for a particular measurement.
Detailed discussion of the LLD, and other detection limits, can be found in HASL 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).
12-46
LASALLE Revision 3 May 2001 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.
12-47
t LASALLE Revision 3 May 2001 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"') COLLECTION FREQUENCY ANALYSIS
- 1. Airborne Samples from a total of eight locations: Continuous sampler Radiolodine Canister:
Radlolodine and operation with particulate 1-131 analysis biweekly Particulates a. Indicator- Near Field sample collection weekly (or on near field and control more frequently if required samples.(2)
Four samples from locations within 4 due to dust loading) and km (2.5 ml) in different sectors. radiolodine canister Particulate Sampler:
collection biweekly. Gross beta analysis following
- b. Indicator- Far Field weekly filter change(3) and gamma Isotopic analysis(4*
Three additional locations within 4 to quarterly on composite filters by 10 km (2.5 to 6.2 ml) Indifferent location on near field and sectors. control(2) samples.
- c. Control One sample from a control location within 10 to 30 km (6.2 to 18.6 mi).
12-48
I LASALLE Revision 3 May 2001 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
- 2. Direct Forty routine monitoring stations either with Quarterly Gamma dose on Radiationt5 ) a thermoluminescent dosimeter (TLD) or each TLD quarterly.
with one Instrument for measuring dose rate continuously, placed as follows:
- a. Indicator- Inner Ring (100 Series TLD)
One in each meteorological sector, in the general area of the SITE BOUNDARY (within 0.1 to 2.0 ml; 0.2 to 3.2 kin)
- b. Indicator- Outer Ring (200 Series TLD)
One Ineach meteorological sector, within 4.8 to 10 km (3 to 6.2 mi); and
- c. Other One at each Airborne location given in part 1.a. and 1.b.
The balance of the TLDs to be placed at special Interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access. (300 Series TLD) 12-49
I-LASALLE Revision 3 May 2001 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"t ) COLLECTION FREQUENCY ANALYSIS
- 2. Direct d. Control Quarterly Gamma dose on Radiation(s) (Cont'd) One at each Airborne control location each TLD quarterly.
given in part 1.c
- 3. Waterborne (4
- a. Ground/ Well a. Indicator Quarterly Gamma Isotopic(4) and tritium analysis Samples from two sources only If likely quarterly.
to be affected.(")
- b. Drinking(7) a. Indicator Weekly grab samples. Gross beta and gamma Isotopic One Sample from each community analyses(4) on monthly drinking water supply that could be composite; tritium affected by the station discharge within analysis on quarterly 10 km (6.2 mi) downstream of composite.
discharge.
- c. Surface Water(7) Ifno community water supply (Drinking Weekly grab samples. Gross beta and Water) exists within 10 km downstream gamma Isotopic of discharge then surface water analyses(4) on monthly sampling shall be performed. composite; tritium analysis on quarterly A.Indicator composite.
One sample downstream 12-50
t LASALLE Revision 3 May 2001 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
- d. Control Sample(7 a; Control Weekly grab samples. Gross beta and gamma Isotopic One surface sample upstream analyses(4 ) on monthly discharge. composite; tritium analysis on quarterly composite.
- e. Sediment a. Indicator Semiannually. Gamma Isotopic analysis (4)
At least one sample from downstreamU) semiannually.
area within 10 km (6.2 mi).
- 4. Ingestion a. Indicator Biweekly (9)when animals are Gamma Isotopic(4) on pasture (May through and
- a. Milk(8) Samples from milking animals from a October), monthly at other 1-131(l°) analysis on maximum of three locations within 10 times (November through each sample.
km (6.2 ml) distance. Apnl).
- b. Control One sample from milking animals at a control location within 10 to 30 km (6.2 to 18.6 mi).
12-51
It.
LASALLE Revision 3 May 2001 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 Representative samples of portions "commercially and recreationally IImportant species Indischarge area.
- b. Control Representative samples of commercially and recreationally Important species In control locations upstream of discharge.
- a. Indicator Annually Gamma isotopic(4)
- c. Food Products analysis on each Two representative samples from the sample.
principal food pathways grown In each of four major quadrants within 10 km (6.2 ml), if available:
At least one root vegetable sample(i')
At least one broad leaf vegetable (or vegetation)(")
- b. Control Two representative samples similar to Indicator samples grown within 15 to 30 km (9.3 to 18.6 mi), Ifavailable.
LaSalle Revision 3 May 2001 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 location 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 is confirmed 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 is greater 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 Identification 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 in place 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., If a 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 in areas where the hydraulic gradient or recharge properties are suitable for contamination.
(7) The "downstream' sample shall be taken in an area beyond but near the mixing zone.
The Oupstream 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.
(8) If milking animals are iot found in the designated indicator locations, or If the owners decline to participate in the 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 volume/weight of sample large enough to fill contractor specified container.
12-53
LaSalle Revision 3 May 2001 TABLE 12.5-2 IN ENVIRONMENTAL SAMPLES RADIOACTIVITY CONCENTRATIONS REPORTING LEVELS FOR REPORTING LEVELS MILK FOOD PRODUCTS FISH WATER AIRBORNE PARTICULATE ANLYI OR GASES (pCim 3 ) (pC0/kg, wet) (PC/i/) (pCI/kg, wet)
ANALYSIS (pCVI)
H-3 20,000) 30,000 10,000 Mn-54 1,000 Fe-59 400 30,000 10,000 Co-58 1,000 20,000 Co-60 300 300 Zn-65 3
Zr-Nb-95 400 1,000 1-131 2(2) 0.9 1,000 70 2,000 10 Cs-13 4 30 300 50 20 Cs-137 Ba-La-1 40 200 of 30,000 value. If no drinking water pathway exists, a value This is 40 CFR Part 141 (1) For drinking water samples.
pCi/I may be used. exists, a value of 20 pCVI may be used.
(2) If no drinking water pathway 12-54
t LaSalle Revision 3 May 2001 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)(2 )(3)
WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT (pCI/I) OR GASES (pCi/m3) (pCI/kg, wet) (pCI/I) (pCI/kg, wet) (pCi/kg, dry)
ANALYSIS Gross Beta 4 0.01 1000 H-3 2,000(7)
Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131(6) 1/15(4) 0.07 100 0.515(5) 60 0.01 100 15 60 150 Cs-134 15 0.01 100 18 80 180 Cs-137 18 Ba-La-140 15 15 12-55
LaSalle Revision 3 May 2001 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 in the 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 Limit of Detection (LID) is defined, 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 observation represents a "real* signal.
For a particular measurement system, which may include radiochemical separation, the LiD is defined as follows:
4.66 Sb + S/tb LLD=
(E) (V) (2.22) (Y) (exp (- MLt))
4.66 Sb LLD (E) (V) (2.22) (Y) (exp (-Mt))
Where: 4.66 Sb >> S/tb LLD = the "a priod' 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),
= 4Itotal 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 picoCurie, Y = the fractional radiochemical yield, when applicable,
= the radioactive decay constant for the particular radionuclide (sec-1),
12-56
LaSalle Revision 3 May 2001 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 time 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 limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, 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 Report.
(4) If no drinking water pathway exists, the value of 15 pCi/I may be used.
(5) A value of 0.5 pCi/I shall be used when the animals are on pasture (May through October) and a value of 5 pCLI/ 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 pCVI.
12-57
LaSalle Revision 3 May 2001 12.5.2 Land Use Census Operability Requirements 12.5.2.A. 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: At 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 sectors 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.B.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.
12-58
N LaSalle Revision 3 May 2001 12.5.3 Interlaboratory Comparison Program Operability Requirements 12.5.3.A 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 in the Annual Radiological Environmental Operating Report.
Surveillance Requirements 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.
12-59
LaSalle Revision 3 May 2001 12.6 REPORTING REQUIREMENTS 12.6.1 Annual Radiological Environmental Operating 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 IOCFR5O, Appendix I, Sections IV.B.2, IV.B.3, and IV.c. It should include, as found appropriate, a comparison of preoperational studies with operational controls or with previous environmental 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 the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall 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 discussion 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 12.5.2; and the results of licensee participation in an Interlaboratory Comparison Program and the corrective actions being taken if the specified 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.
- A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.
12-60
LaSalle Revision 3 May 2001 12.6.1 Annual Radiological Environmental Operating Report (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 in the ODOM and in compliance with 10CFR2O and 40 CFR 190, "Environmental Radiation Protection Standards for Nuclear Power Operation.*
12.6.2 Radioactive Effluent Release Report4
- 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 I OCFR5O.36a prior to May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluent and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the PROCESS CONTROL PROGRAM and In conformance with 10CFR5O.36a and 10CFR50, Appendix I, 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,u 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 offsite during the report period:
- 1. Container volume,
- 2. Total curie quantity (specify whether determined by measurement or estimate),
- 3. Principal radionuclides (specify whether determined by measurement or estimate),
- 4. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
- 5. Type of container (e.g., LSA, Type A, Type 8, 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.)
'4pigle 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.
12-61
LaSalle Revision 3 May 2001 12.6 REPORTING REQUIREMENTS 12.6.3 Offsite Dose Calculation Manual (ODCM)*
12.6.3.1 The ODCM shall contain the methodology and parameters used in the 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 12.6.32 The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3.
12.6.3.3 Ucensee-initiated changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance (QA) Manual. This documentation shall contain:
- 1. Sufficient Information to support the change(s) together with the appropriate analyses or evaluations justifying 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 markings in the margin of the affected pages, clearly Indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
- The OFFSITE DOSE CALCULATION MANUAL (ODCM) is common'tb LaSalle Urit-1.
and LaSalle Unit 2.
12-62
LaSalle Revision 3 May 2001 12.6 REPORTING REQUIREMENTS 12.6.4 Major Changes to Radioactive Waste Treatment Systems 12.6.4.1 License initiated major changes to the radioactive waste treatment systems (liquid and gaseous):
- a. Shall be reported to the Commission in the 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 individual 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 b:cbrrie effective upon review- arn dacceptance by the Orilfe"Reviev ard Investigative Function.
12-63
LaSalle Revision 3 May 2001 APPENDLI F STATION-SPECIFIC DATA FOR LASALLE UNITS I AND 2 Table of Contents PAME F.1 INTRODUCTION F-1 F.2 REFERENCES F-i F-i
LaSalle Revision 3 May 2001 APPENDIX F LIST OF TABLES WUJMAE TIPLE F-1 Aquatic Environment Dose Parameters F-2 F-2 Station Characteristics F-3 F-3 Critical Ranges F-4
.F-4 Average Wind Speeds F-5 F-5 X10 and D/0 Maxima At or Beyond the Unrestricted Area Boundary F-6 F-5a X1Q and D/0 Maxima At or Beyond the Restricted Area Boundary F-7 F-5 D/0 at the Nearest Mil Cow and Meat Animal Locations Within 5 Miles F-8 F-7 Maximum Oftsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Selected Nuclides F-*
F-7a Maximum Offslte Fbinte Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Selected Nucikes F-24 F-8 Parameters for Calculation of N-1a Siryshine Radiation from LaSale F-39 Supplemental Tables A Elevated Level Joint Frequency Distribution "TableSummary - 375 Foot Elevation Data F-40
-Summary Table of Percent by Direction and Class
-Summary Table of Percent by Direction and Speed
-Summary Table of Percent by Speed and Class B Mid Elevation Joint Frequency Disrbution Table Summary - 200 Foot Elevation Data F-42
-Summary Table of Percent by Direction and Class
-Summary Table ot Percent by Direction and Speed
-Surenary Table of Percent by Speed and Class C Ground Level Joint Frequency Distribution Table Summary - 33 Foot Elevation Data F-44
-Summary Table ol Percent by Direction and Class
-Summary Table of Percent by Direction and Speed
-Summary Table of Percent by Speed and Cas F-i
LaSalle Revision 3 May 2001 APPENDIX F LIST OF FIGURES NUMBER TnL F-1 Unrestrictd Area Boundary F-46 F-2 Restrcted Ares Boundary F-47 F-ill
LaSalle Revision 3 May 2001 APPENDIX F STATION-SPECIFIC DATA FOR LASALLE "UNITSI AND 2 I.1 INTRODUCTION "lusappendix contains data relevant to the LaSale she. Included is a figure showing Mte unrestricted area boundary, restricted area boundary, and values of paramet used In oMitsle dose assessment.
F.2 REFERENCES
- 1. Sargent & Lundy, Analysis and Technology Division, LaSale Caculatllon No. ATD-0164, ReviSions 0, 1, 2 and 3.
- 2. Sargent & Lundy, Nuclear Safeguards and Ucensing Division. LaSale Calculation No. ATD 0138, N-16 Skyshine Ground Level Doses from LaSale Turbine System & Piping, Revision 0.
- 3. Verification of Environmental Pararneter used for Cormmonwealth Edison Counpsny's Offsie Dose Calculallons, ONUS CoWporatlon. 1988.
F-1
LaSalle Revision 3 May 2001 Table 1.I Aquatic Environment Dose Parameter General Inf~rnsmtlon",
The station iquid discharge flows into the Illinois River then into the Mississippi River.
Recreation Includes one or more of the folowing: boating. watorasdtng. swimming. and sport fishing.
Two downstream dams are on t*e lI*os River, Marolles-and Starved Rock. This Information is based on Section 2.4.1.1 and Figures 2A.-2 and 2.40 of the LaSille Environmental Report.
Wautr And Fish Ingaostln ParamuLarL V1M". IVW 1.0 F. CIS 1.B5E4 F', rs 1.31E4 e'. Wi 24.0 I', IN? 97.0 qwý Limits on RadipnsCl*ft in tLhnMretesd OtidowrTanks Outside Temporary Tank " 10 C&
- This is based on information In LaSale Ervironrentai Repor. Figure 3.3-1 and Section 2.14.21.
The parametes are defind in Sections A.2.1 of Appendix A.
ft'(hr) ,24 hr (al stations) for the fish Ingestion pathway t" (hr) 97 hr (distancato nearst public potable watr Intake, Peoria, is 97 miles; flow Mate of I mph i assumed.)
- See Section A.2.4 61 Appendix A.,
'Tritium and dissolved or entrained nobl, gases are exchided from this ilit.
F-2
LaSalle Revision 3 May 2001 Table F1-2 Station Charamtsistics STATION: LaSale LOCATION: 6 miles south of Marseilles, Illinois - LaSale County "CHARACTERISTICS OF ELEVATED RELEASE POINT
- 1) Release Height m -.. LUm" 2) Diameter
- 2) Exit Speed -,....4.,J$Ms 4) Heat ContentI. ,_ Cals" CHARACTERISTICS OF VENT STACK RELEASE POINT: Not Applicable (NA)
- 1) Release Height , n 2) Diamter - __.fit
- 3) Exit Speed -- -is" CHARACTERISTICS OF GROUND LEVEL RELEASE 1)felaaseH*, =0-o m
- 2) Buldng Factor (D) - m' METEOROLOGICAL DATA A 400l Tower isLctd75_ SE ni elevated relases point Tower Data Used inCaculations Release Point -Wind Speed and Direction DeMirenhal Temperature Elevated 375 It 375-33 ft Vent (NA) (NA)
Ground 33 ft 200-33 It "Used in calculating the meteorological and dose factors in Tables F-5, F-6, and F-7. See Sections B.3 through B.6 of Apppaen B.
F-3
LaSalle
, Revision 3 May 2001 "TabteF-3 crical Ranges Unrestricted Restricted Nearest Nearest Dairy Farm Area Area Reakidee Within 5 Miles" Boundarya Boundary Ifni IfrA 6300 None 1036 1036 N 2800 None NNE 1378 1378 1609 3400 None.
NE 2408 5300 None "44S0 1079 ENE 1996 5200 None
- E None 845 2300 ESE 1465 None N96 969 2700
- SE 598 2900 None "SSE .38 I-2400 None 829 120 S 835 1100 None SSW 835 1600 None SW 628 2400 None WSW 533 524 1300 None W "524 643 1400 None 643 2900 None 762 752 NW 390 2700 7400 NNW 890 I 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.
F-4
LaSalle Revision 3 May 2001 Table Fd4 Averegs, Wind Speeds Dowvnwind Avernna Wind Snood 1m/safer Flavt~d yac+/- ~ mn+/-adLove N 9.7 7.7 4.9 10.1 .LO 5.1 NNE NE 92 7.4 4.9 ENE 9.0 7.2 4.8 E 9.5 7.8 5.2 ESE 9.7 BA 5.9 SE 8.1 7.4 5.9 "SSE ?A 6.7 5.0 S 6.7 5.9 4.3 SSW 5.6 3.7 2.9 SW 5.5 4.1 3.1 WSW 6.9 5.4 3.9 W 7.6 6.5 4.5 WNW 7.5 6.3 4.3 NW 7.5 6.2 3.9 NNW 6.3 6.7 4.3 "OBasad an LaSlle site meteorological dat. January 1978 through Decenber 1987. Calculated Reference I of Section F.2, using formulas in Section 6.1.3 of Appendix B.
F-5
CLa 0 0
- a. .. .
gA a~ Rai Ago CL a Fr 0ZIP* H 0-14411
.~IM~*baa.Uaaa4 P444 IO
c LaSalle Revision 3 May 2001 Table F-5a XIQ and D0Q Maxima at or Beyond the Restricted Area Boundary Downmlnd Elevated(Stack) Rteiste Nixed Node(Vent) Release Ground Level Relelse Direction Radius X/4 Radius Di0 Radius 1O DIG Radius 1/01 1q (letere) (secfm**3) (meters) (1/0m*2) (meters) (secjm**3) (0/012) (meters) (seclm/*3) (1/m*'2)
N 5633. 6.123]-09 1036. 7.20JE-10 6000. 6.289E-09 8.311E-10 1036. 1.524E-06 1.019E-08 NNE 1378. 7.043E-09 1378. 9.831E-10 3633. 7.102E-09 9.659E-10 1378. 9.737E-07 7.095E-09 NE ":4400. 5.535E-09 1609. 6.556E-to 1609. 6.052E-09 7.933E-10 1609. 7.003E-OT 4.747E-09 ENE :5200. 5.086E-09 1079. 6.3761-10 1079. 6.579E-09 9.861E-10 1079. 1.125E-06 ?.755E-09 E 5200. 5.863E-09 1500. 6.659E-I0 1053. 7.712E-09 1;160E-09 1055. 1.275E-06 8.779E-09 ESE ,3200. 8.000E-09 1300. 8.896E-10 1055. 9.981E-09 1.546E-09 1055. 1.192E-06 1.021E-08 ISE 5633. ?. 116E .09 1500. 7.3051-10 969. 1.087E-08 1.709E-09 969. 1.1371-06 1.123E-08 15200. 6.717E-09 698. 7.210E-10 698. 1.444E-08 2.403E-09 698. 1.492E-06 1.428E-08 S 5633. 5.910E-09 1500. 6.136E-10 820. 8.453E-09 1.312E-09 820. 1.130E-06 1.055E-08 Slit 6000. 5.269E.09 835. 5.793E-10 835. 7.322E-09 9.9991-10 835. 7.940E-07 5.359E-09 SU 6000. 6.7671-09 628. 8.543E-10 628. 2.224E-08 2.154E-09 628. 1.8641-06 1.407f-08
"- U 6000. 6.0658-09 533. 6.5271-I0 540. 2.103E-08 2.079E-09 533. 2.101E-06 1.970E-08 6437. 5.354E-09 1500. 4.811E-10 540. 1.344E-08 1.6299-09 524. 2.830E-06 2.453E-08 kv 7242. 3.9161-09 1500. 3.173E-10 643. 5.963E-09 9.071E-10 643. 2.429E-06 1.S05E-08 NNW 7242. 3.766E-09 1500. 3.118E-10 5633. 4.1271-09 6.660E-10 762. 1.984E-06 1.051E-08 6437. 4.240E-09 1300. 3.806E-10 "637. 4.095E-09 5.574E-10 890. 1.605E-06 8.840E-09 LASALLE SITE NETEOIOLOGICAL DATA 1/78 - 12/87 EP8PROJ1cf1mA, Nib/j.71 F-7
4 LAMiE Revision May 20013 Table F-6 within 5 miles DIO at the Nearest Milk Cow and Meat Animal Locations . b.
- 21 Nearest Elevated Heat Animal Mixed O/Q(1/m**21 Grbund Downwind Na arest Milk Cow DIQ(I/m*
Mixed Ground Radius Radius Elevated Release Release Direction Release (meters) Release (meters) Release Release 2.915E-10 6400. 1.387E-10 1.436E-10 4.320E-10 4.352E-10 1.760E-0Q N 8000. 9.711E-11 3.273E-10 3100. 4.257E-10 1.151E-10 1.006E-10 1.1789-10 1.538E-10 1.649E-10 5.403E-10 NNE 8000. 2. 851E-10 5600.
8.939E-11 9.468E-11 1.725E-10 5.519E-10 HE 8000. 2.381E-10 5000. 1.739E-10 8.559E-11 8.420E-11 1.056E-10 9.772E-11 2.587E-10 ENE 8000. 2.587E-10 8000.
8000. 1.056E-10 9.772E-11 1. 450E-10 1.356E-10 3.010E-10 E 3.010E-10 8000.
9000. I . 450E-10 1.356E-10 1.354E-10 1.437E-10 3.160E-10 ESE 1.242E-10 I .322E-10 2.891E-10 7600. 2.360E-10 SE 8000. 7600. 1.279E-10 1.389E-10 1.174E-10 1.278E-10 2.152E-10 9.895E-11 2.065E-10 SSE 8000. 2.065E-10 8000. 9.947E-11 8000. 9.947E-11 9.895E-11 8.647E-11 9.097E-11 1.077E-10 S 1.077E-10 8000.
8000. 8.647E-11 9.097E-11 1.096E-10 1.210E-10 1.793E-10 SSW I .096E-10 1.210E-10 1.793E-10 8000. 1.940E-10 8000. 8000. 1.017E-10 1.083E-10 SW 1.017E-10 1.083E-10
- 1. 940E-10 2.362E-10 S.896E-10 WSW 8000. 2. 354E-1 0 4800. 1. 08E-10 8000. 9.494E-11 1. 094E-10 1.117E-10 1.331E-10 4.312E-10 W
5.824E-11 6.886E-11 1. 994E-1 0 5200. 9.022E-11 2.730E-10 WNW 8000. 1. 828-10 6400. 7.773E-11 5.436E-11 6.319E-ll 7.002E-11 6.954E-11 2.163E-10 N1W 8000. 2.269E-10 7600.
7400. 7.317E-11 7.264E-11 NNW
- 12/87 Lasalle Site Heteorological Data 1/78 formulas in Section 8.4 of Appendix B.
Note: Based on Reference 2 of Section F.2 and the IInJi... .. et.n.If .7f 'F-8
I May 2001 Table F-7 Maximum Offalte Finite Plume Gamma Dose Factors Based on I cm Depth at the Unrestricted Area Boundary for Kr-83m Oawulnd Unirestricted Ilevated(Stack) itele@$e Nixed Noda(Vent) Release Growun Level Release Dlreetlen Area Boemd Iedlus s SIAN tedlus v VUAR Radgus a - GUAR (Peters) (meters) (wredlyr)(uClIsec) (meters) (wjredfyr)/(uCllsec) (meters) (.redlyr)f(uCl/sec)
N 1036. 1016. 4.78Y7-07 3.609E-07 1036. 5.281E-07 3.982E-07 1036. 1.78SE-04 1.346E-04 NNE 1378. 1378. 8.7511-0? 6.5991-0? 1378. 6.90S1-0? 5.2061-07 1378. 1.139E-04 8.586E-05 2408. 2408. 6.4718-0T 4.879E-07 2408. 6.697E-0? 5.049E-07 2408. 4.355E-05 3.284E-05 ENE 4450. 4450. 5,700E-07 4.298E-07 4450. 5.653E-07 4.262E-07 4450. 1.466E-05 1.105E-05 E 1996. 1996. 4.687E-0? 3.534E-07 1996. 7.559E-O? 5.700*-0? 1996. 5.491E-05 4.140E-05 ESE 1465. 1465. 5.252E-0? 3.960E-07 1465. 1.002E-06 7.559E-07 1465. 8,270E-05.6.236E-05 SE 969. 969. 3.545E-07 2.673E-07 969. 1.267[-06 9.554E-07 969. 1.3331-04 1.005E-04 SSE 838. 838. 3.051E-0? 2.301E-O? 838. 1.512E-06 1.140E-06 838. 1.323E-04 9.978E-05 S 829. 829. 2.840E-0? 2.1411-0? 829. 1.040E-06 ?.842E-0? 829. 1.3301-04 1.003E-04 SSW 815.
SSu 835. 3.185E-07 2.401E-0? 835. 1.071E-06 8.076E-07 835. 9.326E-05 7.0321-05 SSU 628. 628. 3.1711-07 2.395E-07 628. 2.826E-06 2.131E-06 "628. 2.305E-04 1.738E-04 533. 533. 2.617E.O7 1.97?3-O? 533. 2.674E-06 2.0171-06 533. 2.5688-04 1.936E-04
'Ut 524. 524. 2.32]1E-O 1.?54E-Or 524. 1.6581-06 1.250E-06 524. 3.352E-04 2.527E-04
. HIW 643. 643. 1.1140-0? 1.2921-0? 643. 7.235E-0? 5.455E-07 643. 2.7281-04 2.057E-04 Nil 762. 762. 1.744E-0? 1.315E-07 762. 4.3915-07 3.311E-07 762. 2.219E-04 1.673E-04 Rum4K 890. 890. 2.3971-0? 1.807E-07 890. 3.334E-0? 2.514E-07 890. 1.823E-04 1.374E-04 LASALLE SITE hlOMOLOGICAL DATA 1/78 - 12/87 Nola: Based on Reference 1 of Section F.2 and the formulas In Seclbons 6.5 and 6.6 of Appendix B.
EPSPROJMadem~evsk/h.7f F-9
t Revision 3 Table F-7 (Continued) May 2001 Maximum Oflllte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-05m Dowwlnd Unretricted llevated(Stack) Releseo Nixed Node(Vent) Release around Level latease Direction Area Round Redlus I SIAN Radius V VSAN Raedus a lIAR (meters) (meters) (mrad/yr)/(uCLi/sec) (meters) (mradlyr)I(uCl/sec) (meters) Cmrad/yr)l(uCI/sec)
N 1036. 1036. 5.747E-05 5.560E-05 1036. 6.602E-05 6.388E-05 1036. 9.660E-04 9.252E-04 NNE 1378. 1378. 5.0631-05 4.8961-05 1378. 5.514E-05 5.3340-05 1378. 6.7761-04 6.496E-04 NE 2408. 2408. 2.5921-05 2.506f-05 2408. 2.727E-05 2.6361-05 2408. 2.969E-04 2.849E-04 lEN "4450. 4450. 1.3519-05 1.3041-05 E 4450. 1.332E-05 1.286E-05 4450. 1.156E-04 1.111E-04 1996. 1996. 2.7051-05 2.616E-05 1996. 2.8631-05 2.767E-O5 1996. 3.557E-04 3.412E-04 SE 1465. 1465. 4.351E-05 4.209E-05 1465. 4.6241-05 4.4701-05 1465. 5.2018-04 4.989E-04 SSE 969. 969. 5.596E-05 5.415E-05 969. 6.6101-05 6.391E-05 969. 7.793E-04 7.4709-04 S 838. 838. 5.5181-05 5.339E-05 838. 6.630E-05 6.410E-05 838. 7.683E-04 7.364E-04 829. 829. 4.712E-05 4.560E-05 829. 5.330E-05 5.154E-05 829. 7.986E-04 T.657E-04 SI' 835. 835. 4.4221-05 4.279E-05 835. 5.3511-05 5.174E-05 835. 5.684E-04 5.450E-04 USU 628. 628. 7.281E-05 7.046E-05 628. 9.9525-05 9.6181-05 628. 1.285E-03 1.231E-03 533. 533. 7.7511-05 7.507E-05 533. 9.714E-05 9.388E-05 533. 1.389E-03 1.331E-03 V 524. 524. 7.601E-05 7.356E-05 524. 9.705E-05 9.385E-05 524. 1.6879-03 1.614E-03 HI 643. 643. 5.286E-05 5.116E-05 643. 6.615E-05 6.399E-05 643. 1.327E-03 1.270E-03 MlD 762. 762. 4.668E-05 4.518E-05 762. 5.688E-05 5.503E-05 762. 1.0940-03 1.047E-03 890. 890. 4.683E-05 4.532E-05 890. 5.142E-05 4.976E-05 890. 9.2821-04 8.885E-04 LAIALH BITE NETEOSOLOGICAL DATA 1/78 - 12/17 EPSPROModn*m6ahll.T7 F.10
L &.t:
Revision 3 May 2001 Table F-? (Continued)
Maximum 01s1te Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85 Dowulnd Unrestricted Elevuted(Iteek) Release Nlxed Node(Vent) Release Growmd Level Eelease Direction Area loewd ladius I IRAN Imdlfus V "lAN Radfus a RIAf (meters) (Meters) (mrmdlyr).(uCIlbec) (meters) (raedlyr)l(uCIlsec) (10ters) (nrsd/yr)/(uCllsec)
N '1036. 1036. 8.54T7-07 8.265E-0? 1036. 9.889E-07 9.563E-07 1036. 1.056E-05 1.021E-05 NNE 1378. 1378. 7.3091-07 7.068E-0? 1378. 8.O77M-O0 7.811E-OT 1378. 1.4741-06 7.221E-06 HE '2408. 2408. 3.651E-0? 3.510E-0? 2408. 3.909E-07 3.780E-07 2408. 3.363E-06 3.252E-06 ENE 4450. 4450. 1.885E-07 1.823E-O0 4450. 1.8561-0? 1.7951-0? 4450. 1.377E-06 1.332E-06 E ,1996. 1996. 3.912E-0? 3.782E-07 1996. 4.096E-0? 3.9611-07 1996. 4.001E-06 3.876E-06 ESE 1465. 1465. 6.3591-07 6.149E-0? 1465. 6.632E-0? 6.413E-O0 146S. 5.783E-06 5.593E-06 SE 969. 969. 8.386E-07 8.1108-0? 969. 9.583E-07 9.26?E-O0 969. 8.555E-06 8.273E-06 SSE 838.
S 838. 8.350E-07 8.075E-O? 838. 9.612E-0? 9.294E-07 838. 8.432E-06 8.1541-06 829. 829. 7.2621-0? 7.023E-07 829. 8.0671.0? 7.801E-OT 829. 8.741E-06 8.453E-06 SSu 8035. 835. 6.8571E-O 6.630E-0? 835. 8.4021-0? 8.124E-O? 835. 6.2701-06 6.063E-06 SU 628. 628. 1.142E-06 1.104E.06 628. 1.494E-06 1.444E-06 628. 1.4011-0 1.355E-05 NSU 533. 533. 1.2111-06 1.1711-06 533. 1.433E-06 1.386E-06 533. 1.5101-05 1.460E-05 524. 524. 1.1?2E-06 1.1341-06 524. 1.443E-06 1.395E-06 524. 1.8204-05 1.763E-05 IU 643. 643. 8.185E-07 7.91SE-a? 643. 1.0001-06 9.670E-07 643. 1.436E-05 1.389E-05 762. 762. 7.192f-o0 6.934e-O0 762. 8.694E-07 8.401E-OT 762. 1.188E-05 1.148E-05
"- NNV 890. 890. 7.128E-0? 6.8931-0? 890. 7.849E-0? 7.590E-OT 890. 1.0111E-05 9.7?7E-06 LASALLE SlIE NIUE OLOGICAL DATA 1178 - 12/87 19PSqPR(']LIA #&mA..L6A,a _Vr
I Revision 3 May 2001 Table F-7 (Continued)
Maximum Olfsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-87 Oowwlnd IJrestricted fleveted(Steck) Ratel.. Nixed Node(Vent) elet.os iround Levl Rtelese.
Direction Area Round Redlus I 3lAI Radis V VIA* Radius a - CIAR (meters) (meters) (rale/yr)/(uCI/sec) (meters) (mradlyr)O/uCllsec) (meters) (mradlyr)I(uCl/sec)
N 1036. 1036. 3.226E-04 3.135E-04 1036. 3.7588-04 3.652E-04 1036. 2.879E-03 2.795E-03 NNE 1378. 1378. 2.672E-04 2.5971-04 1378. 3.005E-04 2.9201-04 1378. 2.019E-03 1.960E-03 RE 2408. 2408. 1.28]E-04 1.246E-04 2408. 1.359E-04 1.320E-04 2408. 8.6051-04 8.355E-04 ENE 4450. 4450. 5.904E-05 S.7387-05 4450. 5.8591-05 5.692E-05 4450. 3.133E-04 3.0421-04 E 1996. 1996. 1.412E-04 1.372E-04 1996. 1.458E-04 1.4171-04 1996. 1.030E-03 9.998E-04 ESE 1465. 1465. 2.351E-04 2.2841-04 1465. 2.426E-04 2.3571-04 1465. 1.545E-03 1.500E-03 SE 969. 969. 3.211E-04 3.120E-04 969. 3.612E-04 3.5101-04 969. 2.355E-03 2.287E-03 SSE 838. 838. 3.254E-04 3.162E-04 838. 3.655E-04 3.552E-04 838. 2.329E-03 2.262E-03 S 829. 829. 2.8508-04 2.770E-04 829. 3.081E-04 2.994E-04 829. 2.431E-03 2.361E-03 SSu 835. 835. 2.7421-04 2.665E-04 835. 3.4008-04 3.305E-04 035. 1.706E-03 1.657E-03 sw 628. 628. 4.6141-04 4.484E-04 628. 5.936E-04 5.769E-04 628. 3.903E-03 3.790E-03 usW 533. 533. 4.8801-04 4.743E-04 533. 5.683E-04 5.523E-04 533. 4.251E-03 4.128E-03 W 524. 524. 4.675E-04 4.543]-04 524. 5.7081-04 5.547E-04 524. 5.136E-03 4.986E-03 imU 643. 643. 3.224E-04 3.1331-04 643. 3.9141-04 3.804E-04 643. 4.001E-03 3.884E-03 N! 762. 762. 2.823E.04 2.1431-04 762. 3.397E-04 3.3011-04 762. 3.2761-03 3.1801-03
-e, NNU 890. 890. 2.747E-04 2.669E-04 890. 3.0311-04 2.945E-04 890. 2.763E-03 2.683E-03 LASALLf SIrE NETEOIOLOGICAL DATA 1/78 - 12/187 EPSPROJocmvtak/if.mf 1.419
L,. .. ,LLE . .
Revision 3 May 2001 Table F-7 (Continued)
Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-88 Donuwind Unrestricted *leveted(Stack) Release Nixed Noda(Vent) Release erwa" Level 1e6t;89 Direction Area Bouerd Radius I SIAN Radius V WAR Radius a GBAR (meters) (meters) (mradlyr)(uCIlsec) (meters) (mradlyr)/(uClIsec) (meters) (mredlyr)I(uCilsec)
N 1036. 1036. 8.602E-04 8.374E-04 1036. 1.003E-03 9.769E-04 1036. 6.983E-03 6.787E-03 NINE 1378. 1378. 7.111E-04 6.922E-04 1378. 7.989E-04 7.777E-04 1378. 4.9403-03 4.798E-03 ME 2408. 2.182E-03 2.120E-03 2408. 2408. 3.435E-04 3.344E-04 2408. 3.694E-04 3.596E-04
[EN 4450. 4450. 1.6483-04 1.604E-04 4450, 1.646E-04 1.602E-04 4450. 8.502E-04 8.263E-04 E 1996. 1996. 3.781E-04 3.680E-04 1996. 3.9283-04 3.824E-04 1996. 2.599E-03 2.525E-03 ESE 1465. 1465. 6.235E-04 6.070E-04 1465. 6.445E-04 6.273E-04 1465. 3.816E-03 3.707E-03 SE 969.
969. 969. 8.537E-04 8.311E-04 969. 9.571E-04 9.317E-04 5.712E-03 5.549E-03 SSE 838. 838. 8.671E-04 8.442E-04 838. 9.702E-04 9.445E-04 838. 5.645E-03 5.483E-03 S 829. 5.862E-03 5.695E-03 SSW 829. 829. 7.69AE-04 7.492E-04 829. 8.417E-04 8.194E-04 835. 835. 7.427E-04 7.231E-04 835. 9.375E-04 9.127E-04 835. 4.167E-03 4.04BE-03 Sw 628. 9.3969-03 9.126E-03 628. 628. 1.2461-03 1.213E-03 628. 1.601E-03 1.559E-03 SU 533. 533. 1.314E-03 1.279E-03 533. 1.525E-03 1.4853-03 533. 1.017E-02 9.882E-03 524. 524. 1.249E-03 1.216E-03 524. 1.520E-03 1.480E-03 524. 1.225E-02 1.190E-02
- - tmu 643. 643. 8.669E-04 8.440E-04 643. 1.045E-03 1.017E-03 643. 9.595E-03 9.317E-03 762. 762. 7.580E-04 7.379E-04 762. 9.125E-04 8.884E-04 762. 7.895E-03 7.666E-03 NKU 6.500E-03 890. 890. 7.369E-04 7.1741-04 890. 8.161E-04 7.945E-04 890. 6.693E-03 LASALLE SIlT NEIEOROLOGICAL DATA 1178 - 12/87 EP8PROJidcm**seah/k1l-If F-13
LA,.,,,L I, Revision 3 May 2001 Table F-7 (Continued)
Maximum Olste Finite Plume Gamma Dose Factors Based on I cm Depth at the Unrestricted Area Boundary for Kr-89 Dowunlnd Unrestricted fleveted(Stack) Release Nixed NodeKVent) Release Ground Level Reluase Directlon Area sound Radius I $IAN Iadius V VIAR RIdius 0 GEAR (meters) (meters) (mradlyr)/(uCi/sec) (meters) (mradlyr)I(uCls9ec) (meters) (mrvdlyr)/(uCl/sec)
N 1036. 1036. 3.904E-04 3.794E-04 1036. 4.Z58E-04 4.139E-04 1036. 2.051E-03 1.992E-03 NlNE 1378. 1378. 2.820E-04 2.741E-04 1378. 2.988E-04 2.904E-04 1378. 1.151E-03 1.118E-03 RE 2408. 2408. 8.306E-05 8.072E-05 2408. 7.403E-05 7.1951-05 2408. 2.060E-04 2.001E-04 ENE E 4450. 4450. 1.570E;05 1.526E-05 4450. 1.153E-05 1.121E-05 4450. 1.701E-05 1.653E-05 1996. 1996. 1.052E-04 1.023E-04 1996. 9.299E-05 9.031E-05 1996. 3.031E-04 2.944E-04 ESE 1465. 1465. 2.3651-04 2.299E-04 1465. 2.2408-04 2.1771-04 1465. 7.762E-04 7.540E-04 SE 969. 969. 3.8911-04 3.7829-04 969. 4.188E-04 4.070E-04 969. 1.846E-03 1.793E-03 SSE 838. 838. 4.108E-04 3.993E-04 838. 4.365E-04 4.243E-04 838. 1.831E-03 1.7708-03 S 829. 829. 3.408E-04 3.312E-04 829. 3.253E-04 3.162E:04 829. 2.034E-03 1.976E-03 SSW 835. 835. 2.921E-04 2.839E-04 835. 2.7791-04 2.702E-04 835. 1.021E-03 9.916E-04 SU 628. 628. 5.830E-04 5.6671-04 628. 6.600E-04 6.4151-04 628. 3.2741-03 3.180E-03 WSW 533. 4.592E-03 4.460E-03 533. 533. 6.9131E-04 6.720E-04 533. 7.5258-04 7.314E-04 U 524. 524. 524. 8.259E-04 8.0281-04 524. 5.9671-03 5.796E-03 6.961E-04 6.766E-04 643. 643. 4.295E-04 4.1740-04 643. 5.1471-04 5.003E-04 643. 3.746E-03 3.638E-03 NQU 762. 762. 3.500E-04 3.4021-04 762. 4.035E-04 3.9221-04 762. 2.5611-03 2.488E-03 890. 890. 3.301E-04 3.208E-04 890. 3.415E-04 3.319E-04 890. 1.966E-03 1.909E-03 LASALLE Sill IIMEEOROLOGICAL DATA 1/78 - 12/87 EPSPROJhd uhgk/l-.7T F.1A
L .LE Revision 3 May 2001 Table F-7 (Continued)
Maximum Oflalte Finite Plume Gamma Dose Factors Based an I cm Depth at the Unrestricted Area Boundary for Kr-gO Du1nulnd Unlretricted Ilevated(Stack) Release Nixed Node(Vent) Reelee Ground Level Notes's ODrectlon Area Bound Radius S 313i Redlus V VIAl Redfui a GRAR (meters) (meters) (srsdfyr)j(uClI/ec) (meters) (w-adlyr)I(uCiluec) (meters) (Crod/yr)/(dll/tec)
N 1036. 1036. 6.785E-05 6.5861-O5 1036. 5.199-05 5.047E-05 1036. 8.203E-05 7.954E-05 1378, 1378. 3.19S1-0S 3.1021-05 1378. 2.1611-05 2.0981-05 1378. 2.2651-05 2.1961-05 2408. 2408. 2.1601-06 2.0971-06 2408. 9.1361-0? 8.8681-07 2408. 5.8708-07 5.693E-07 HE ERE 4450. 4450. 1.109E-07 1.076E-07 4450. 3.907E-08 3.792E-08 4450. 1.8140-08 1.759E-08 1996. 1996. 4.1131-06 4.5751-06 1996. 2.562E-06 2.486E-06 1996. 2.865E-06 2.779E-06 ESE 1465. 1465. 2.1341-05 2.072E-05 1465. 1.5511-05 1.506E-05 1465. 2.503E-05 2.427E-05 SE 969. 969. 5.843E*05 5.673E-05 969. 5.324E-05 5.168E-05 969. 1.365E-04 1.324E-04 SSE 838. 838. 6.863E-OS 6.663E-05 838. 6.174E-05 5.993E-O5 838. 1.2271-04 1.190E-04 S 829. 829. 5.057E-05 4.9098-05 829. 3.7453-03 3.635E-05 829. 1.0551-04 1.023E-04 SSu 835. 835. 3.062E-05 2.9721-05 835. 1.274E-05 1.2371-05 835. 1.835E-05 1.779E-05 USU 628. 628. 9.7541.03 9.470E-05 628. 6.5381-05 6.3471-05 628. 1.4101-04 1.368E-04 US'.*
Iv 533. 533. 1.892E-04 1.835E-04 533. 4.8611-04 4.713E-04 U 533. 1.525E-04 1.480E-04 524. 524. 2.165E-04 2.101E-04 524. 2.185E-04 2.121E-04 524. 8.4271-04 8.170E-04 MI' 643. 643. 1.018E-04 9.88]E-05 643. 1.008E-04.9.8?ETI05 643. 3.141E-04 3.045E-04 go, I 762. 762. 6.6341-05 6.4401-0S 762. 5.8151-05 5.645E;05 762. 1.3061-04 1.2671-04 10 NW' 890. 890. 5.7251-05 5.5581-05 890. 4.336E-05 4.209E-05 890. 8.819E-05 8.551E-05 LAIALLI SITE NITI01OLNICAL DATA 1/78 - 12/87 EPSPROJA~dom~bsh/*1.7I F-15
L'_.LE Revision 3 May 2001 Table F-7 (Continued)
Maximum Offsite Finite Plum. Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-131m Dowlnd nr*etrleted Ilevoted(etock) etessOe Nied Node(Vent) Relies grournd Level elease Direction Arms loewd lodlus I UAN ladiues v V"At Radius a -GEA (mters) (moters) (aredlyr)I(,dilstc) (motors) (mradlyr)I(ucMI/ec) (maters) (mrad/yr)/(uCIj3c)
N 1036. 1036. 1.6068-06 1.473E-06 1036. 1.8271-06 1.679E-06 1036. 1.645E-04 1.283E-04 NNE 1378. 1378. 1.778E-06 1.5721-06 1378. 1.7261-06 1.553E-06 3178. 1.072E-04 8.384E-05 HE 2408. 2408. 1.0861-06 9.3762-07 2408. 1.136E-06 9.826E-07 2408. 4.3471-05 3.412E-05 ENE 4450. 4450. 7.931E-07 6.6171-07 4450. 7.8588-07 6.550E-07 4450. 1.623E-05 1.219E-05 E 1996. 1996. 9.5721-O? 8.457E-07 1996. 1.210E-06 1.053E-06 1996. 5.4231-05 4.253E-05 ESE 1465. 1465. 1.347E-06 1.215E-06 1465. 1.789E-06 1.560E-06 1465. ?.935E-05 6.2151-05 SSE 969. 969. 1.472E-06 1.3658-06 969. 2.406E-06 2.115E-06 969. 1.240E-04 9.696E-05 SE 838. 838. 1.415E-06 1.313E-06 838. 2.5981-06 2.260E-06 838. 1.223E-04 9.5978-05 SSW 829. 829. 1.231E-06 1.1441-O0 829. 1.966E-06 1.727E-06 829. 1.232E-04 9.639E-05 SW 835. 835. 1.1961-06 1.103E-06 835. 2.003E-06 1.7551-06 835. 8.798E-05 6.8858-05 USU 628. 628. 1.802E-06 1.691E-06 628. 4.3451-06 3.123E-06 628. 2.109E-04 1.646E-04 533. 533. 1.059E-06 1.7551-06 533. 4.161E-06 3.577M-06 533. 2.324E-04 1.813E-04
- Nu 524. 524. 1.800E-06 1.703E-06 524. 3.359E-06 2.972E-06 524. 3.000-04 2.335E-04 643. 643. 1.2631-06 1.194E-06 643. 1.976E-06 1.791E-06 643. 2.4462-04 1.902E-04 NNU 762. 762. 1.1351-06 1.069E-06 762. 1.561E-06 1.4371-06 762. 2.005E-04 1.5601-04 890. 890. 1.191E-06 1.1128-06 890. 1.3631-06 1.263E-06 890. 1.664E-04 1.2951-04 LAIALLI 111 MEITEOIOLOGICAL DATA 1/li - 12/0?.
EPSPROJbdcmsakb/.yTI F-10
Revision 3 May 200o Table F-7 (Continued)
Maximum Ofatile Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133m Dowfl- Irheitricted Ilevated(Stack) Rltease Nixed Node(Vent) aginae DirectIon Area lound Radlus S SIAR drownd Level 1...,.
Radius V VsAm Radius a SIAN (meters) (meters) (mradlyr)(uCilenc) (meters) (mradlyr)O(uCIlsec) (meters) (iamdlyr)l(uCIIstc)
N 1036. 1036. 8.557E-06 8.199E-06 1036. 9.814E-06 9.407E-06 1378. 1036. 2.822E-04 2.410E-04 HE 1378. 7.9173-06 7.5091-06 1378. 8.400E-06 8.0091-06 1378.
2408. 2408. 4.2461-06 3.993.-06 1.9011-04 1.633E-04 2408. 4.4821-06 4.2171-06 2408. 8.032E-05 6.9501-05 ENE 4450. 4450. 2.488E-06 2.298E-06 4450. 2.450E-06 2.262E-06 4450.
1996. 1996. 3.1031-05 2.706E-05 4.2478-06 4.025E-06 1996. 4.721E-06 4.433E-06 1996. 9.835E-05 8.482E-05 ESE 1465. 1465. 6.6141-06 6.3091-06 1465.
SSE 7.393E-06 6.978E-06 1465. 1.432E-04 1.234E-04 SSE 1969. 969. 8.229E-06 7.903E-06 969. 1.039E-05 9.834E-06 969.
838. 838. 2.189E-04 1.879E-04 8.070E-06 7.758E-06 838. 1.060E-05 9.9981-06 838. 2.163E-04 1.856E-04 S 829. 829. 6.932E-06 6.660E-06 829. 8.449E-06 7.995E-06 829.
835. 835. 2.2011-04 1.893E-04 6.541E-06 6.2761-06 835. 8.500E-06 8.036E-06 835. 1.5741-04 SUt 628. 628. 1.059E-05 1.0201-05 1.354E-04 628. 1.637E-05 1.535E-05 628. 3.668E-04 3.140E-04 533. 533. 1.121E-05 1.0811.05 533. 1.58BE-05 1.490E-05 524. 524. 533. 4.005E-04 3.423E-04 1.0961-05 1.0563-05 524. 1.504E-05 1.427E-05 524. 5.039E-04 4.287E-04 NU 643. 643. 7.6481-06 7.3741-06 643.
762. 9.9561-06 9.510E-06 643. 4.0551-04 3.441E-04 762. 6.7741-06 6.526E-06 762. 8.4353-06 8.088E-06 ONI 890. 890. 762. 3.3341-04 2.031E-04 4m 6.8553-06 6.5941-06 890. 7.588E-06 7.28SE-06 890. 2.794E-04 2.30TE-04 LASALLE SITE METIOROLOGICAL DATA 1/7T - 12/87 EPSPROJMdamtmak/1. 7i C.47
Sf( ALE Revision 3 May 2001 Table F-7 (Continued)
Maximum 01slte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-133 Pmmafnd Unrestricted ftevated(Steck) Release Nixed Node(Vfnt) Release Oround Level Release DirectIon Area Bound Redius I MN Rudlus V "IAN Radius a GIAN (maters) (voters) (mrad/yr)/(uClluec) (meters) (Cradlyr)1luC0leec) (meters) (wredlyr)I(utt/eec)
N 1036. 1036. 7.010E-06 6.7371-06 1016. 7.933E-06 7.649E-06 1036. 3.136E-04 2.7L5E-0%
NNE 1378. 1378. 6.9391-06 6.629E-06 1378. 7.149t-06 6.860E-06 1378. 2;132E-04 1.9031-04 ENE 2408. 2408. 3.969E-06 3.7671-06 2408. 4.106E-06 3.8971-06 2408. 9.094E-05 8.164EI05 E 4450. 4450. 2.442E-06 2.28S1-06 4450. 2.384E-06 2.229E-06 4450. 3.540E-03 3.193E-05 1996. 1996. 3.941E-06 3.671E-06 1996. 4.310E-06 4.083E-06 1996. 1.109E-04 9.929E-05 ESE 1465. 1465. 5.762E.06 5.53R4-06 1465. 6.599E-06 6.2771-06 1465. 1.612E-04 1.443E-04 SE 969. 969. 6.641E-06 6.416E-06 969. 8.978E-06 8.558E-06 969. 2.450E-04 2.185E-04 SSE 838. 838. 6.364E-06 6.153E-06 838. 9.231E-06 8.769E-06 838. 2.418E-04 2.156E-04 S 829. 829. 5.333E-06 S.152E-06 829. 6.962E-06 6.627E-06 829. 2.476E-04 2.212E-04 SIU 835. 835. 4.969E-06 4.193E-06 835. 6.5981-06 6.266E-06 835. 1.770E-04 1.582E-04
- 628. 628. 7.7981.06 7.349E-06 628. 1.362E-05 1.285E-05 628. 4.090E-04 3.640E-04 WSW ,533. 533. 8.2451-06 U 7.992E-06 533. 1.326E-05 1.252E-05 533. 4.447E-04 3.951E-04 524. 524. 8.1d6E-06 7.919E-06 524. 1.220E-05 1.164E-05 524. 5.551E-04 4.911E-04 643. 643. 5.715E-06 5.541E-06 643. 7.8851-06 7.574E-06 643. 4.444E-04 3.922E-04 NiW INU 762. 762. 5.11rE-06 4.9381-06 762. 6.538E-06 6.303E-06 762. 3.661E-04 3.233E-04 890. 890. 5.340E-06 5.t651-06 890. 5.911E-06 5.708E-06 890. 3.080E-04 2.725E-04 S
LAtALLI 1111 NETEOROLOGICAL DATA 1173 - 12/87 EPSPROJ/*dcmsahb/kj.7l F-1i
L. LE Revision 3 May 2001 Table F-7 (Continued)
Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-135m oninild Unrhestrlcted flevated(Stack) Rleese Mixed aoda(Vent) Release around Level Release 9ireetlon Area Bound Radlus 9 lVAN Radius V VIAR Rdlius a CIAR (meters) (meters) (mradlyr)/(uClIsec) (meters) (mradtyr)/(uCllsec) (meters) (wradlyr)l(uCl/sec)
U 1036. 1036. 1.396E-04 1.349E-04 1036. 1.5981-04 1.545E-04 1036. 1.531E-03 1.475E-03 NHE 1378. 1378. 1.151E-04 1.113E-04 1378. 1.274E-04 1.232E-04 1378. 1.0191-03 9.821E-04 RHE 2408. 2408. 5.077-E05 4.907E-05 2408. 5.129E-05 4.9588-05 2408. 3.516E-04 3.390E-04 4450. 4450. 1.919E-05 1.854&-05 4450. 1.778E-05 1.715E-05 4450. 8.758E-05 8.445E-05 E 1996. 1996. 5.672t-05 5.483E-05 1996. 5.675E-05 5.4868-05 1996. 4.329E-04 4.172E-04 ESE SE 1465. 1465. 1.0051-04 9.716E-05 1465. 1.024E-04 9.902E-05 1465. 7.369E-04 7.103E-04 SSE 969. 969. 1.389E-04 1.343E-04 969. 1.575E-04 1.522E-04 969. 1.262E-03 1.216E-03 838. 838. 1.402E-04 1.356E-04 838. 1.591E-04 1.538E-04 838. 1.254E-03 1.209E-03 SO 829. 829. 1.183E-04 1.144E-04 829. 1.235E-04 1.194E-04 829. 1.341E-03 1.292E-03 SSu 835. 835. 1.1041-04 1.068E-04 835. 1.260E-04 1.2181-04 835. 8.762E-04 8.444E-04 S11 628. 628. 1.9041-04 1.8411-04 628. 2.440-04 2.363E-04 628.. 2.173E-03 2.094E-03 S533. 533. 2.0631-04 I.95t-04 533. 2.4271-04 2.345E-04 533. 2.4791-03 2.388E-03 U 524. 524. 2.0331-04 1.9619-04 524. 2.511E-04 2.4279-04 524. 3.050E-03 2.9371-03 643. 643. 1.3631-04 1.318E-04 643. 1.6871-04 1.6311-04 643. 2.286E-03 2.2011-03 Nwu 762. 762. 1.1871-04 1.1481-04 762. 1.4231-04 1.376E-04 762. 1.8061-03 1.739E-03 NW'. 890. 890. 1.1611-04 1.122E-04 890. 1.259E-04 1.2171-04 890. 1,482E-03 1.427E-03 LASALLE SITE METEOROLOGICAL DATA 1/71 - 1218T EPSPROJIodemnfsauds/ki-71 F.-1
I-.
Revision May 20013 Table F-7 (Continued)
Maximum Olfflle Finite Plume Gamma Dose Factors Based on I cm Depth at the Unrestricted Area Boundary for Xe-135 DoWurind Urwestricted Eleveted(Itmck) Coteus. NlXed udat(Vent) eltesee Direction Area Bound Radius Grounid Level Ceiea..
I niAt Radius V VIA*w Radius a GOAR (mrters) (meters) (mrad/yr)/(uCl/sec) (moters) (wrad/yr)/(uCI/sec) (meters) (mrad/yr)I(uCI/sec)
N 1036. 1036. 8.165E-05 7.902E-05 1036. 9.387.-05 9.0856.05 1036. 1.302E-03 1.257E-03 III NE 1378. 1378. 7.1715-os 6.9405-05 1378. 7.8215-05 7.569E-05 1378. 9.178E-04 0.866E-04 2408. 2408. 3.669E-05 3.550E-05 2408. 3.8765-0S 3.751E-05 2408.
ENE 4.075E-04 3.937E-04 E
4450. 4450. 1.928E-OS 1.8668-0S 4450. 1.899E-05 1.831E-05 4450. 1.625E-04 1.570E-04 1996. 1996. 3.8355-05 3.714E-05 1996. 4.056E-05 3.92SE-0S ESE 1465.
1996. 4.869E-04 4.704E-04 1465. 6.171E-05 5.912E-05 1465. 6.539E-05 6.328E-05 1465. 7.073E-04 6.833]-04 SE 969. 969. 7.9539-05 7.697E-05 969. 9.346E-05 9.044E-05 SSE 969. 1.052E-03 1.0178-03 838. 838. 7.8455-05 7.5935-05 838. 9.367E-05 9.064E-05 S 829. 829. 838. 1.037E-03 1.0025-03 6.719E-05 6.5035-aS 829. 7.5871-05 7.342E-05 829. 1.078E-03 1.041E-03 SSW 835. 835. 6.306E-05 6.103E-05 835. 7.6355-05 7.389E-05 Sv 628. 628.
835. 7.699E-04 7.438E-04 1.039E-04 1.006E-04 628. 1.4099-04 1.363E-04 628. 1.729E-03 1.670E-03 uSU 533. 533. 1.1065-04 1.071E-04 533. 1.372E-04 1.328E-04 533. 1.864E-03 1.801E-03 V 524. 524. 1.082E-04 1.0480-04 524. 1.3745-04 1.329E-04 524. 2.256E-03 2.179E-03 643. 643. 7.538E-05 7.2965-05 643. 9.395E-05 9.092E-05 643.
UNIm Hma 762. 762. 1.77E-03 1.713E-03 6.6545-OS 6.440E-OS 762. 8.0985-0 ?.8385-0s 762. 1.466E-03 1.415E-03 890. 890. 6.671E-05 6.456f-03 890. 7.3271-05 7.092E-05 890. 1.247E-03 1.204E-03 LASALLE IITI NETEIOaLOGICAL DATA 1/78 - 12/87 EPSPROJbdcmjiuunj 1 .lf F-20
I LA,....LLE Revision 3 Table F-7 (Continued) May 2001 Maximum Of9lte Finite Plume Gamma Dose Factbrs Based on 1 cm Depth at the Unrestricted Area Boundary for Xe-137 DmhinId lettrtcted Elevated(Stock) Release Nixed Node(Vent) Eele.se Grouncd Level Release Dtrection Area Round Radlus I SIIA Radilus V VIAR RadIus 0 -IAR (meters) (meters) (mr@d/yr)/(uCllsec) (meters) (mrodlyr)I~uClIsee) (meters) (mred/yr)/(uCll/ec)
V 1036. 1036. 4.7801-05 4.6279-05 1036. 5.242E-05 5.074E-05 1036. 3.409E-04 3.298E-04 MillE 1378.
NE 1378. 3.585E-05 3.4711-05 1378. 3.814E-05 3.692E-05 1378. 1.973E-04 1.911E-04 RHE 2408. 2408. 1.1531-05 1.116E-05 2408. 1.052E-05 1.018E-05 2408. 3.979E-05 3.850E-05 ENE 4450. 4450. 2.512E.06 2.432E-06 4450. 1.933E-06 1.8711E-06 4450. 3.949E-06 3.821E-06 E 1996. 1996. 1.420E-05 1.3741-05 1996. 1.285E-05 1.244E-05 1996. 5.599E-05 5.4188-05 ESE 1465. 1465. 3.033E-05 2.936E-05 1465. 2.918E-05 2.825E-05 1465. 1.327E-04 1.284E-04 SE 969. 969. 4.743E-05 4.591E-05 969. 5.1881-05 5.023E-OS 969. 2.989E-04 2.892E-04 SSE 838. 838. 4.926E-05 4.769E-05 838. 5.3571-OS 5.186E-05 838. 2.970E-04 2.874E-04 S 829. 829. 4.072E-05 3.942E-05 329. 3.9758-03 3.849E-05 829. 3.298E-04 3.191E-04 sSu 835. 835. 3.521E-05 3.408E-05 835. 3.424E-05 3.315E-05 835. 1.748E-04 1.691E-04 "isv USU, 628. 628. 6.779E-05 6.563E-05 628. 7.9381-05 7.685E-05 628. 5.333E-04 5.161E-04 I. 533. 533. 7.919E-05 7.667E-05 533. 8.829E-05 8.548E-05 533. 7.164E-04 6.932E-04 524. 524. 7.9901-OS 7.736E-05 524. 9.608E-05 9.302E-05 524. 9.223E-04 0.924E-04 WNW 643. 643. 5.023E-05 4.8631-OS 643. 6.090E-05 5.896E-05 643. 6.002E-04 5.808E-04 762. 762. 4.160E-05 4.028E-05 762. 4.841E-05 4.687E-05 762. 4.228E-04 4.09aE-04 NRU 890. 890. 3.985E-05 3.858E-05 890. 4.1521-OS 4.0201-05 890. 3.2791-04 3.172E-04 LASALLE lSITE MIEEOOLOGICAL DATA 1173 - !Z187 EPSPROJfbdcm/Ihsss/&I.71 F-21
Revision 3 May 2001 Table F-7 (Continued)
Maximum Ofuslle Finite Plume Gamma Dose Factors Based on I cm Depth at the Unrestricted Area Boundary for Xe-138 Oowind tUnestricted Elevated(Steck) Reteoao Niued Node(Vent) etmlage Grmoud Level Rteue Direction Area lound Radius I SlAR Radius V "AR Radius 0 -GiAR (metors) (meters) (mradlyr)(ICI/uec) (meters) (sradlyr)l(uCt/uee) (meters) (mredlyr)ICuCI/eec)
N 1036. 1036. 3.926E-04 3.816E-04 1036. 4.523E-04 4.396E-04 1036. 3.178E-03 3.084E-03 NaNE 1378. 1378.
ME 3.160E-04 3.01E-04 1378. 3.536E-04 3.4371-04 1378. 2.1171-03 2.055E-03 2408. 2408. 1.356E-04 1.318E-04 2408. 1.379E-04 1.340E-04 2408. 7.244E-04 7.032E-04 ENE 4450. 4450. 4.939E-05 4.7991-05 4450. 4.572E-05 4.443E-05 4450. 1.769E-04 1.718E-04 E 1996. 1996. 1.540E-04 1.497E-04 1996. 1.535E-04 1.492E-04 1996. 8.921E-04 8.659E-04 ESE 1465. 1465. 2.766E-04 2.689E-04 1465. 2.804E-04 2.7251-04 1465. 1.532E-03 1.4871r-03 SE 969. 969. 3.938E-04 3.828E-04 969. 4.4081-04 4.2851-04 969. 2.641E-03 2.564E-03 SSE 838. 838. 4.037E-04 3.9241-04 838. 4.484E-04 4.3581-04 838. 2.628E-03 2.551E-03 S 829. 829. 3.4571-04 3.360E-04 829. 3.560E-04 3.460E-04 829. 2.809E-03 Z.721E-03 SSW 035. 835. 3.2771-04 3.186E-04 835. 3.832E-04 3.724E-04 835. 1.828E-03 1.774E-03 su 628. 628. 5.698E-04 5.538E-04 628. 7.209E-04 7.607V'04 628. 4.5461-03 4.412E-03 usW 533. 533. 6.144E-04 5.973E-04 533. 7.121E-04 6.921t-04 533.
9 5.206E-03 5.053E-03 524. 524. 5.976E-04 5.809E-04 524. 7.318E-04 7.113E-04 524. 6.383t-03 6.195E-03 UMU 643. 643. 3.986E-04 3.875E-04 643. 4.88TE-04 4.7501-04 643. 4.7371-03 4.616E-03 HU 762. 762. 3.457E-04 3.360E-04 762. 4.131E-04 4.016E-04 762. 3.635E-03 "mum 3.746E-03 C
890. 890. 3.330E-04 3.236E-04 890. 3.626EI04 3.525E-04 890. 3.069E-03 2.978E-03 LASALLE SITE HEIEROOLOGICAL DATA I/1 - 12/817 EPOPROJIodem4cIwbui1.7l F-22
'I LaSalle Revision 3 May 2001 Table F-7 (Continued)
Maximum Ofallt Finite Plume Gamma Dose Factors Based on I cm Depth at the Unrestricted Area Boundary for Ar-41 DowOrnd Unritricted Elevated(stack) Release Nixed NodalVent) Release Ground Level Release Direction Ares B1ound Radius 3 55At Radius V VYAR Radius a GIA3 (meters) (meters) (mred/yr)/(uCl/sec) (meters) (mrad/yr)(uCII/sec) (meters) (wadlyr)/(uCl/sac)
N 1036. 1036. 4.746E-04 4.594E-04 1036. 5.528E-04 5.3511-04 1036. 4.557E-03 4.411E-03 1378. 1378. 3.9540-04 3.828E-04 1378. 4.4391-04 4.29?.-04 1378. 3.203E-03 3.1011-03 NNE 2408. 2408. 1.925E-04 1.863E-04 2408. 2.0451-04 1.980E-04 2408. 1.3071-03 1.343E-03 RE 4450. 4450. 9.141E-05 8.8431-05 4450. 9.0611-05 8.772E-05 4450. 5.219E-04 5.052E-04 ENE E 1996. 1996. 2.110E-04 2.043E-04 1996. 2.160E-04 2.110E-04 1996. 1.658E-03 1.605E-03 ESE 1465. 1465. 3.480E-04 3.368E-04 1465. 3.593E-04 3.418E-04 1465. 2.459E-03 2.3811-03 SE 969. 969. 4.711E-04 4.5601-04 969. 5.320E-04 5.149E-04 969. 3.715E-03 3.597E-03 SSE 838. 838. 4.761E-04 4.6031-04 838. 5.378E-04 5.2061-04 838. 3.671E-03 3.5540-03 829. 829. 4.168E-04 4.035E-04 829. 4.533E-04 4.3838-04 829. 3.823E-03 3.701E-03 Sw 835. 835. 3.994E-04 3.866E-04 835. 4.9301-04 4.772E-04 835. 2.7001-03 2.614E-03 sSU 628. 628. 6.711E-04 6.496E-04 628. 8.591E-04 8.316E-01, 628. 6.1391-03 5.943E-03 533. 533. 7.089E-04 6.862E-04 533. 8.229E-04 7.966E-04 533. 6.6671-03 6.453E-03 524. 524. 6.8029-04 6.5841-04 524. 8.291E-04 8.0261-04 524. 8.057E-03 ?.799E-03 U 643. 643. 4.706E-04 4.5583-04 643. 5.7161-04 5.533E-04 643. 6.300E-03 6.099E-03 UNU 762. 762. 4.1238-04 3.9911-04 762. 4.970E-04 4.8111E-04 762. 5.173E-03 5.003E-03 NNW 890. 890. 4.025E-04 3.8961-04 890. 4.447E-04 4.3051-04 890. 4.3741-03 4.234E-03 LASALLE SIT METEOROLOGICAL DAIA 1178 - 1218?"
EPSPROJomdcmpiasaehi.7f F-23
4-LaSalle Revision 3 May 2001 Table F.7a Maximum Offsite Finite Plume Gamma Dose Factors Based on I cm Depth 'a the Ristricted Area Boundary for Kr-03m DonuirId Estricted Elevatedclttck) Retlese Nixed Node(Vent) Release around Level Release Direction Ares ouind Radius S SiAR Radius V VIAN Radius a GIAN (meters) (meters) (mradlyr)!(uCl/sec) (meters) (oradlyr)l(uclsee©) (meters) (mrad/yr)/(uCll/ec)
N 1036. 1036. 4.787E-07 3.609E-07 1036. 5.281E-07 3.982E-0? 1036. 1.785E-04 1.346E-04 NNE 1378. 1378. 8.751E-0? 6.599M-0? 1378. 6.905E-0? 5.206E-0? 1378. 1.1391-04 8.586E-03 N! 1609. 1609. 6.8131-0? 5.1821-0? 1609. 7.2918-O? 5.497E-0? 1609. 8.106E-05 6.112E-05 ENE 1079. 1079. 4.160E-07 3.137E-07 1079. 8.0101E-07 6.039E-0? 1079. 1.322E-04 9.9671-05 E 1055. tOSS. 3.476E-07 2.621E-07 loss. 9.181E-0? 6.923E10? 1055. 1.4831-04 1.1181-04 ESE loss. 1055. 4.371E-0? 3.296E-07, 1055. 1.1758-06 8.8568-0? 1055. 1.394E-04 1.051E-04 SE 969. 969. 3.54SE-OT 2.673E-0? 969. 1.267E-06 9.554E-07 969. 1.333E-04 1.00S8-04 SSE 698. 698. 2.4158-07 1.821E-0? 698. 1.646E-06 1.241E-06 698. 1.773E-04 1.3378-04 S 820. 820. 2.8031-07 2.1141-07 820. 1.047E-06 1.8958-07 820. 1.3541-04 1.0211-04 SSW 835. 835. 3.1851-0T 2.401E-07 835. 1.071E-06 8.076E-07 835. 9.326E-05 7.032E-05 S11 628. 628. 3.177E-07 2.395E-0? 628. 2.826E-06 2.131E-06 628. 2.305E-04 1.738E-04 USU 533. 533. 2.6171-0? 1.9731-07 533. 2.674E-06 2.017E-06 533. 2.568E-04 1.936E-04 V 524. 524. 2.3271.07 1.7541-07 524. 1.658E-06 1.2S08-06 524. 3.352E-04 2.527E-04 M 643. 643. 1.7141-0? 1.292-*07 643. 1.233e-07 5.455E-07 643. 2.728E-04 2.057E-04 NV 762. 762. 1.7441-07 1.3151-0? 762. 4.391E-07 3.311E-0? 762. 2.219E-04 1.673E-04 Nml 890. 890. 2.3971-07 1.807E-07 890. 3.334E-07 2.5140-07 890. 1.8231-04 1.374E-04 LASALLE 8111 ETiOtROLOGICAL DATA 1/78 - 12/87 The restricted area boundary (RAB) was redefined in sectors E and ESE to 033 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose lactors were re-evaluated using the following equation. Here, F, is the resulting dose factor at the new range (I.e. 833). FR, Is the value provided In the above ODCM tables (i.e. S. SBAR, V, VBAR, G, GOAR). R, is- the form6r RAB distance (i.e. 1055), and R Is the RAB distance (i.e. 833).
F,,F'j-! lexpl.5 This analysis Indicates that the change In range would Increase the dose factor error by approximately 40%. Since this difference Is well within the expected error of the current factors, no further adjustment in the above factors Is considered necessary.
ote: Based on Reference 1 of Secliod F.2 and the formulas in Sections 6.5 and 0.6 of Appendix 6.
EPSPROJobdnciesalb/ir-7l F-24
I LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Offslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-85m Dowwlnd e1ttricted Ileveted(Stack) Release Nixed Code(Vent) Release Ground Level Release Direction Ares sound Radius I IVAN Radius V VIA* eadlus a C3IR (11aters) (meters) (mradlyr)l(ulilsec) (meters) (mradlyr)l(uCl/sec) (meters) (mrdlyr)l(uCllmec)
N 1036. 1036. 5.74tE-05 S.560f,-OS 1378. 1036. 6.602E-05 6.388E-05 1036. 9.66EO-04 9.252E-04 NlNE 1378. 5.0631.O5 4.8961-05 1378. 5.5141-05 5.334E-05 1609. "3.6321-05 3.512E-05 1378. 6.T761-04 6.496E-04 RlE 1609. 1609. 3.847E-05 3.720E-05 1609. 5.003E-14 4.798E-04 ENE 1079. 1079. 4.114E-05 1055. 4.315E-05 1079. 4.569E-05 4.419E-05 1079. 7.345E-04 7.037E-04 E 1055. 4.5 721-05 4.424E-05 1055. 5.053E-05 4.886E-05
- 1055. 1055. 8.134E-04 ?.792E-04 ESE 1055. 5.730E-05 5.5441-05 1055. 6.298E-OS 6.090E-05 loss. 8.020E-04 7.687E-04 SE 969. 969. 5.596E-05 5.415E-05 969. 6.610E-05 6.391E-05 969. 7.793E-04 7.470E-04 SSE S698. 698. 6.471E-05 6.2631E-OS 698. 7.905E-05 7.643E-05 698. 9.815E-04 9.404E-04 S 820. 820. 4.756E-05 4.603E-05 820. 5.386E-OS 5.208F-05 820. 8.103E-04 7.769E-04 SSW S835. 835. 4.422E-05 4.279E-05 835. 5.351E-05 5.174E-05 835. 5.684E-04 5.450E-04 SU 628. 628. 7.281E-05 7.046E-05 628. 9.952E-OS 9.618E-05 628.
USt 1.285E-03 1.231E-03 533. 533. 7.757E-05 ?.507E-05 533. 9.714E-05 9.388E-05 533. 1.389E-03 1.331E-03 U 524. 524. 7.6011-05 7.3569-o5 524. 9.705E-05 9.385E-05 524. 1.6871-03 1.614E-03 lUR 643. 643. 5.286E-05 5.116E-05 643. 6.6151-05 6.399E-OS 643. 1.3271-03 1.270E-03 N9W 762. 762. 4.668E-05 4.518E-05 762. 5.688E-05 5.503E-05 762. 1.0941-03 1.047E-03 890. 890. 4.683E-05 4.532E-05 890. 5.142E-05 4.976E-05 890. 9.282E-04 8.885E-04 LASALLE 1i1M MTE010EL0OI0AL DATA 1178 - i218?
The restricted area boundary (RAB) was redefined In sectors E and ESE to 833 and 848 from 1055 and 1055 meters, change of range, the dose factors were re-evaluated using the foglowing equation. Here, F. is the resulting dose respectively. As a result of this factor at the new range (i.e. B33). Fn, is the value provided In the above ODCM tables (i.e. S, SOAR, V. VOAR, G, GBAR). R, is the foimer ROAB dislance (I.e. 533). (i.e. f055) and FH Is the FHAB distance FjtwI 78j Rjepll.5 This analysis indicates that the change in range would Increase the dose factor error by approximately 40%. Since this difference is wee within the expected error of the current factors, no further adiuslmant in the above factors Is considered necessary.
EPSPROJ/odcm4hMe8leff.7l F-25
i LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum OQlstle Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-8S Vowmwind Restricted Elevated(Stack) Release Nixed Node(Vent) Belease ground Level Release Dlrectln Area sound Redius S SIAN Radius V VIAl Radius a CUAR (meters) (meters) (mrsdly"rl/(urIlec) (meters) (nredlyr)/(uCtlsec) (meters) (m'id/yr)/(uClllc)
N 1036. 1036. 8.547E-07 8.265E-07 1036. 9.889E-07 9.563E-07 -1016. 1.056E-05 1.021E-05 1378. 1378. 7.3092-oT 7.068E-OT 1378. 8.077l-0? 7.811E-0? 13178. 7.4741-06 7,2211-06 MSE ENE 1509. 1609. 5.225E-0? 5.052E:0? 1509. 5.615E-0? 5.430E-0? 1609. 5.559E-06 5.37SE-06 E 1079. 1079. 6.463E-0? 6.249E-07 1079. 6.707E-07 6.486E-0? 1079. 8.0571-06 7.791E-06 lass. 1055. 6.819E-0? 6.5941-0? 1055. 7.385E-07 7.142E-07 1055. 8.923E-06 8.628E-06 ESE 1055. 1055. 8.484E-0? 8.204E-0?
SE 1055. 9.108E-0t 8.808E-0? 1055. 8.800E-06 8.517E-06 SSE 969. 969. 8.386E-0? 8.110E-0? 969. 9.583E-07 9.267E-0? 969. 8.555E-06 8.2731-06 698. 698. 9.869E-0? 9.543E-0? 698. 1.153E-06 1.115E-06 698. 1.072E-05 1.036E-05 820. 520. 7.333E-0? 7.091E-07 820. 8.154E-07 7.885E-07 820. 8.866E-06 8.5740-06 SSW SU ' 835. 835. 6.857E-0? 6.630E-O? 835. 8.402E-0? 8.124E-0? 835. 6.270E-06 6.063E-06 USt 628. 628. 1.142E-06 1.1041-06 628. 1.494E-06 1.444E-06 628. 1.401E-05 1.355E-05 533. 533. 1.211E-06 1.1711-06 533. 1.433E-06 1.386E-06 533. 1.510E-05 1.460E-05 1 524. 524. 1.112E-06 1.1349-06 524. 1.4431-06 1.393E-06 524. 1.8241-05 1.763E-03 643. 643. 8.1851-07 7.9151.07 643. 1.000E-06 9.6701-07 643. 1.436E-05 1.389E-05 lime NNU 762. 762. 7.1921-0? 6.954E-07 762. 8.694E-07 8.407E-0? 762. 1.1881-05 1.148E-05 SW 890. 890. 7.1281-0? 6.893E-0? 890. 7.849E-07 7.590E-07 890. 1.011E-05 9.771E-06 LASALLE BITE NETEOIOLOOICAL DATA 1178 - 12/a7 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the folowing equation. Here, F, is the resulting dose factor at the new range (i.e. 833). F,, is the value provided in the above 0DCM tables (i.e. S. SOAR, V, VDAR, (, GOAR). R, Is the former RAB distance (i.e. 1055) and R Is the RAO distance (I.e. 033).
FeFJ- lxp1.5 R
This analysis Indicates that the change in range would increase the dose factor error by approximately 40%. Since this difference Is wait within the expected error of the current factors, no further adjustment Inthe above factors Is considered necessary.
EPSPROJ/dcm4auel/it.TI F-20
I-LaSalle La~alleMay 20013 Revision Table F-7a (Continued)
Maximum Offalte Finite Plume Gamma Dose Factors Based on I cm Depth at the Restricted Area Boundary for Kr-07 Dowwlnd Restricted flevated(Stack) Release Nixed Node(Vent) Release around Level Releas Direction Area Cloid Radius I SCAR Radius V VWAR Radius a -h8AR (meters) (meters) M(radlyr)I(uClslec) (eaters) (w'adlyr)/(0Ci/sec) (meters) (mrad/yr)I(uCl/sec)
N 1036. 1036. 3.226E-04 3.135E-04 1036. 3.758E-04 3.652E-04 1036. 2.879E-03 2.79SE-03 NiNE 1378. 1378. 2.672E-04 2.597E-04 1378. 3.003E-04 2.920E-04 1378. 2.019E-03 1.960E-03 RE 1609. 1609. 1.9081-04 1.853E-04 1609. 2.038E-04 1.981E-04 1609. 1.480E-03 1.437E-03 ENE 1079. 1079. 2.430E-04 2.361E-04 1079. 2.534E-04 2.4621-04 1079. 2.192E-03 2.129E-03 E 1055. 1055. 2.601E-04 2.526E-04 1055. 2.785E-04 2.706E-04 1055. 2.423E-03 2.353E-03 ESE 1055. loss. 3.217E-04 3.125E-04 1055. 3.412E-04 3.3155-04 1055. 2.407E-03 2.337E-03 SE 969. 969. 3.211E-04 3.120E-04 969. 3.612E-04 3.510E-04 969. 2.355E-03 2.287E-03 SSE 698. 698. 3.8851-04 3.776E-04 698. 4.423E-04 4.2981-04 698. Z.985E-03 2.896E-03 S 820. 820. 2.881E-04 2.800E-04 620. 3.117E-04 3.029E-04 820. 2.467E-03 2.396E-03 SSu 835. 835. 2.742E-04 L.65E-04 835. 3.400E-04 3.3051-04 835. 1.706E-03 1.657E-03 SW 628. 628. 4.614E-04 4.484E-04 628. 5.936E-04 5.769E-04 628. 3.903E-03 3.790E-03 Us"t 533. 533. 4.880E-04 4.743E-04 533. 5.683E-04 5.523E-04 533. 4.251E-03 4.12SE-03 V 524. S524.. 4.6751-04 4.543E-04 524. 5.7085-04 5.5475-04 524. 5.136E-03 4.986E-03 iWN 643. 643. 3.224E-04 3.133E-04 643. 3.9149-04 3.804[-04 643. 4.001E-03 3.884E-03 IW 762. 762. 2.823E-04 2.743E-04 762. SNN 3.397E-04 3.301E-04 762. 3.276E-03 3.180E-03
- 1mum 890. 890. 2.7471-04 2.669E-04 890. 3.0311-04 2.945E-04 890. 2.763E-03 2.683E-03 LAALLI StiTlE NETIOROLODICAL DATA 1118 - 12/87 The restricted area boundary (RAB) was redefined In sectors E and ESE to 833 and 848 from 1055 and 1055 motors, respectively. As a result of this change of range, the-dose factors were re-evalualed using the following equation. Here, F. is the resulting dose factor at the new range (i.e. 833). F., is the value provided In the above 0DCM tables (i.e. S, SBAR, V, VBAR, (, GBAR). R. Is the former RAB distance (i.e. 1055) and R Is the RAS distance (I.e. 833).
F,-,uFJ .Joxp1.5 This analysis Indicates that the change In range would Increase the dose factor error by approximately 40%. Since this difference Is well within the expected error of the current factors, no further adjustment Inthe above factors Is considered necessary.
EPSPROJ/AdcmIsasbhr1.7f F-27
I LaSalle Revision 3 May 2001 Table F-7a (Continued)
Maximum Offelte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-88 Donmind Restricted glevated(Stack) Release Nixed Node(Vent) Reteese Ground Level elea.se Direction Area lound Radilus S 1SIAN Radius V VIAi Radlus 0 PeAR
,(meters) (meters) (.,rdlyr)U(CIl/ste) (meters) (mradIyr)/(uClHe©c) (meters) (mrodlyrO)(uCllsec)
N 1036. 1036. 8.602E-04 8.374E-04 1036. 1.003E-03 9.769E-04 1036. 6.988E-03 6.787E-03 NNE 1378. 1378. 7.1118-04 8.9221-04 1378. 7.989E-04 T7.T77-04 1378. 4.940E-03 4.798E-03 1609. 1609. 5.0673-04 4.932E-04 1609. 5.485E-04 5.3401-04 1609. 3.656E-03 3.552E-03 REY
[RE 1079. 1079. 6.528E-04 6.355E-04 1079. 6.769E-04 6.589E-04 1079. 5.337E-03 5.184E-03 E 1ass. lass. 6.915E-04 6.732E-04 os55. 7.419E-04 7.222E-04 lass. 5.9071-03 5.737E-03 ESE lass. 1055. 8.514E-04 8.288E-04 loss. 9.030E-04 8.79G1-04 1055. 5.8571-03 5.689E-03 SE 969. 969. 8.537E-04 8.311E-04 969. 9.571E-04 9.3171-04 969. 5.712E-03 5.549E-03 SSE 698. 1.172E-03 1.141E8.03 698. ?.193E-03 6.986E-03 IJt 698. 698. 1.034E-03 1.007E-03 S 820. 820. ?.7771-04 ?.571E-04 820. 8.513E-04 8.28?E-04 820. 5.9471-03 5.777E-03 SSU/ 835. 835. 7.427E-04 7.2311-04 835. 9.375E-04 9.1271[04 835. 4.1671-03 4.048E-03 USU 625. 628. 1.2461-03 1.213E-03 628. 1.601E-03 1.559E-03 628. 9.396E-03 9.126E-03 533. 533. 1.3149-03 1.279E-03 533. 1.5251-03 1.4858-03 533. 1.0171-02 9.882E-03 UH 524. 524. 1.249E-03 1.216E-03 524. 1.520E-03 1.480E-03 524. 1.22SE-02 1.1901-02 643. 643. 8.669E-04 8.440E-04 643. 1.045E-03 1.0171-03 643. 9.595E-03 9.317E-03 NU 762. 762. 762. 9.125E-04 8.884E-04 7.8951-03 7.666E-03 ESE 7.580E-04 7.3791-04 762.
890. 890. 7.369E-04 7.1748-b4 890. 8.1611-04 7.945E-04 890. 6.693E-03 6.500E-03 w
LAIALLE Sil METEOROLOGICAL DATA 1/78 - 12/87 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, F. Is the resulting dose factor at the new range (Le. 833). F., Is the value provided in the above 00CM tables (i.e. S. SBAR. V. VBAR, G. GUAR). R. is the former RAB dislance (i.e. 1055) and R is the RAB distance (i.e. 833).
FPANFeXP1 .5 This analysis Indicates that the change in range would Increase he dose factor arror by approximately 40%. Since this difference Is well within the expected error of the current faciors, no further adjustment In the above factors Is considered necessary.
EPSPROJ/odcm/hulk/kl.Tf" F.28
i LaSalle Revision 3 May 2001 Table F-7a (Continued)
Maximum Ofslte Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-69 Dmwlnd NuutrIcted I1t4Vetad(Iteck) plotlug Nixed Nod.(Vent) Relese Ground Level Release Direction Area Iound Radius I SAt Radius V VIAR Radius a 'CIAR (mEters) (meters) (mrad/Vr)1(ucfIlec) (meters) (oradlyr)l(uClluec) (meters) (mrad/yr) lUCI/sec)
N 1036. 1036. 3.904E-04 3.794E-04 1036. 4.258E-04 4.139E-04 1036. 2.051E-03 1.992E-03 NNE RE 1378. 1378. 2.820E-04 2.7411-04 1378. 2.985E-04 2.904E-04 1378. 1.1511-03 1.1181-03 ENE 1609. 1609. 1.750E-04 1.701E-04 1609. 1.654E-04 1.607E-04 1609. 6.564E-04 6.375E-04 1079. 1079. 2.703E-04 2.628E-04 1079. 2.619E-04 2.545E-04 1079. 1.450E-03 1.409E-03 E 1055. loss. 3.041E-04 2.956E-04 loss. 2.972E-04 2.888E-04 1055. 1.569E-03 1.524E-03 ESE 1055. o055. 3.93 1-04 3.821E-04 1055. 3.909E-04 3.f800E-04 1055. 1.682E-03 1.633E-03 SE 969. 969. 3.891E-04 3.782E-04 969. 4.1885-04 4.070E-04 969. 1.846E-03 1.793E-03 SSE 698. 698. 5.333E-04 5.184&-04 698. 5.797E-04 5.634E-04 698. 4.722E-03 2.643E-03 S 820. 820. 3.464E-04 3.36TE-04 820. 3.312E-04 3.219E-04 820. 2.083E-03 2.023E-03 SSW 835. 835. 2.921E-04 2.839E-04 835. 2.779E-04 2.702E-04 835.
SU 628. 1.021E-03 9.916E-04 628. 5.830E-04 5.667E-04 628. 6.600E-04 6.415E-04 628. 3.2741-03 3.180E-03 US" 533. 533. 6.913E-04 6.720E-04 533. 7.525E-04. 7.314C-6%
U 524.
533. 4.592E-03 4.4609-03 524. 6.961E-04 6.766E-04 524. 8.2591-04 8.028E-04 524. 5.9679-03 5.796E-03 UNW 643. 643. 4,295E-04 4.174E-04 643. 5.147E-04 5.003E-04 643. 3.746E-03 3.638E-03 762. 762. *3.500E-04 3.402E-04 762. 4,035E-04 3.922E-04 762. 2.561E-03 2.488E-03 NNW 890. 890. 3.3018-04 3.2081-04 890. 3.415E-04 3.319E-04 890. 1.966E-03 1.909E-03 LAIALLE SITE ETEOiROLOGICAL DATA 1/78 - 12/17 The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation.
Here, F. Is the resulting dose factor at the new range (i.e. 833). F, 13 the value provided in the above ODCM tables (i.e. S.SEAR, V.VYAR, G, GOAR).
(i.e. 633).'
R, Is the former RAG distance (i.e. 10551 and R Is the RAG distance R
'-F huFJ-:2jexp1.5 This analysis Indicates that the change In range would Increase the dose factor error by approximately 40%. Since this difference is wel within the expected error of the current factors, no further adjustment Inthe above factors Is considered necessary.
EPSPROJibdcmngfaa/kl -7l F-29
f f. '* .
LaSalle Revision 3 Table F-la (Continued) May 2001 Maximum alfalfa Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Kr-90 9o01wtnd Restricted lleoated(Stack) Releaee Nixed NodelVent) Release Ground Level Raises*
Direction Area Iound Radius S IAi Radius V V"Al Radius I CIAR (meters) (meters) (wad/yr)/(,ul/bec) (meters) (mra/yr)/(uCf/sec) (meters) (mrsdlyr)I(uCJlsec)
N 1036. 1036. 6.785E-05 6.586E-05 1036. 5.199E-05 5.0479-05 1036. 8.2031E-05 7.954E-05 NNE 1378. 1378. 3.1951-05 3.102E-05 1378. 2.161E-05 2.098E-05 1378. 2.2651-05 2.196E-05 ME 1609. 1609. 1.240E-05 1.203E-05 1609. 6.949E-06 6.745E-06 1609. 7.357E-06 7.134E-06 ERE 1079. 1079. 3.718E-05 3.610E-05 E 1079. 2.535E-05 2.464E-05 1079. 4,577E-05 4.438E-05 1055. 1055. 4.582E-05 4.441E-05 1055. 3.257E-05 3.162E-05 1055. 6.817E-05 6.610E-05 ESE 1055. 1055. 6.315E!0S 6.130E-05 1055. 5.0711-05 4.922E-05 1055. 1.078E-04 1.046E-04 SE 969. 969. 5.8431-05 5.673E-05 969. 5.324E-05 5.168E-05 969. 1.365E-04 1.324E-04 698. 698. 1.170E-04 1.136E-04 698. 1.103E-06 1.070E-04 698. 2.578E-04 2.500E-04 S 820. 820. 5.233E-05 5.081E-05 820. 3.881E-0 3.775E-0S 820. 1.108E-04 1.075E-04 ssu USS 835. 835. 3.062E-05 2.972E-05 835. 1.274E-05 1.237E-05 835. 1.835E-05 1.779E-05 628. 628. 9.754E-05 9.470E-05 628. 6.538E-05 6.347E-05 628. 1.410E-04 1.368E-04 usu 533. 533. 1.892E-04 1.836E-04 533. 1.525E-04 1.480E-04 533L 4.861E-04 4.713E-04 NaN 524. 524. 2.165E-04 2.101E-04 524. 2.185E-04 2.121E-04 524. 8.4271-04 1.170E-04 643. 643. 1.018E-04 9.8039-0S 643. 1.008E-04 9.7871-05 643. 3.141E-04 3.045E-04 NI'J 762. 762. 6.634E-05 6.440t-05 762. 5.115E-OS 5.64SE-OS 762. 1.3061-04 1.267E-04 890. B90. 5.7251-05 5.S5BE-05 890. 4.3361-05 4.209E105 890. 6.819E-05 8.351E-05 LAIALI8 811itS NEToiOLOC41rAL DATA 1/78 - 12/I7 The restricted area boundary (RAB) was redefined Insectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the folowing equation. Here, F. Is the resulting dose factor at the new range (i.e. 833). Fp, is the value provided Inthe above'ODCM tables (i.e. S. SOAR, V, VOAR, 0, GOAR). R, Is the former RAD distance (i.e. 1055) and R Is the RAO distance (I.e. 833).
Fu-F(l Re ilexpl .5 This analysis Indicates that the change Inrange woukd Increase the dose factor error by approximately 40%. Since this difference Is weU within the expected error of the curreht factors, no further adjusfment In the above factors Is considered necessary.
EPSPROJodcmsaelh/kI,71 F-30
I-
."I LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Offsle Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-131m bowmlnd Restricted Elevated(Stack) Release Mixed Node(Vent) Release ground Level Release Direction Ares lound Radius I 1IAR Radius V VIIAR Radius GIRAm (meters) (meters) (mradlyr)I(uClosec) (meters) (mradlyr)/(uCI/see) (meters) (mrsd/yr)l(uCtisec)
N HU 1036. 1036. 1.606E-06 1.473E-06 1036. 1.827E-06 1.679E-06 1036. 1.6 5E-04 1.203E-04 NNE '1378. 1378. 1.778E-06 1.5721-06 1378. 1.726E-06 1.553E-06 1378. 1.072E-04 8.384E-05 RE 11609. 1609. 1.327E-06 1.1678-06 1609. 1.409E-06 1.239E-06 1509. 7.747E-05 6.064E-05
[ER S1079. 1079. 1.143E-06 1079. 1.612E-06 1.423E-06 1079. 1.225E-04 9.563E-05 1.254E-06 E 1055. 1055. 1.249E.06 1.150E-06" 1055. 1.806E-06 1.592E-06 1055. 1.376E-04 1.073E-04 ESE 1055. 1055. 1.566E-06 1.442E-06 1055. 2.27CE-06 1.9981-06 1055. 1.298E-04 1.0140-04 SE 969. 969. 1.472E-06 1.3651-06 969. 2.406E-06 2.115F-06 969. 1.240E-04 9.696E-05 SSE 698. 698. 1.566E-06 1.476E-06 698. 2.969E-06 2.597E-06 698. 1.624E-04 1.267E-04 S 820. 820. 1.238E-06 1.1511-06 820. 1.983E-06 1.742E-06 820. 1.253E-04 9.802E-05 SSW 835. 835. 1.196E-06 1.103E-06 835. 2.003E-06 1.755E-06 835. 8.798E-05 6.885E-05 SU 628. 628. 1.802E-06 1.691E-06 628. 4.345E-06 3.728E-06 628. 2.109E-04 1.646E-04 USU 533. 533. 1.859E-06 1.755E-06 533. 4.161E-06 3.5771-06 533. 2.324E-04 1.813E-04 524. 524. 1.800E-06 1.703E-06 524. 3.359E-06 2.972E-06 524. 3.000E-04 2.335E-04 UII 643. 643. 1.263E-06 1.194E-06 643. 1.976E-06 1.791E-06 643. 2.446E-04 1.902E-04 NU NNU 762. 762. 1.135E-06 1.069E-06 762. 1.561E-06 1.437E-06 762. 2.005E-04 1.560E-04 890. 890. 1.191E-06 1.112E-06 890. 1.363E-06 1.263E-06 890. 1.664E-04 1.295E-04 w
LASALIU SiTU MITEOROLOGICAL DATA 11/T - 12/87,
- The restricted area boundary (RAS) was redefined In sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, F. Is the resulting dose factor at the now range (i.e. 833). F., Is Ihe value provided in the above 00CM tables (i.e. S. SBAR, V, VOAR, G, GOAR). R, Is the former RAO distance (i.e. 1055) and f Is the RAB distance (I.e. 833).
FX0a--!!Iexpl .6 R
This analysis Indicates that the change in range would Increase the dose factor error by approximately 40%. Since this difference Is wel within the expected error of the current factors, no further adjustment In the above factors Is considered necessary.
EPSPROJiodcm4&sakli -TI F-31
I-LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Offsile Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-133m DOwmulnd Restricted Eleveted(Stick) Release Nixed Iode(Vent) Release ground Level Release Direction Area loud Radlus I SlAR Radfis V "IAt Radius a CHIC (meters) teeters) (rradlyr)/(uCt/sec) (Peters) (mradlyr)l(uCtlsec) (meters) (arad/yr)I(uCllsec)
N 1036. 1036. 8.55TE-06 8.199E-06 1036. 9.814E-06 9.407E-06 1036. 2.822E-04 2.410E-04 ME I378. 1378. 7.917E-06 7.5091-as 1378. 8.4001-06 8.0091-06 1378. 1.901E-04 1.633E-04 ENE 1609. 1609. 5.729E-06 5.423E-06 1609. 6.0931E-06 5.768W;06 1609. 1.389E-04 1.191E-04 E 1079. 1079. 6.486E-06 6.20SE-06 1079. 7.1411E-06 6. 771-06 1079. 2.121E-04 1.815E-04 loss. 1055. 6.770E-06 6.492E-06 1o55. 7.917E-06 7.501E-06 loss. 2.368E-04 2.024E-04 ISe 1055. loss. 8.-481E-06 8.132E-06 1055. 9.879E-06 9.355E-06 1055. 2.276E-04 1.951E-04 SE '969. 969. 8.229E-06 7.903E-06 969. 1.039E-05 9.834E-06 969. 2.189E-04 1.879E-04 sS '698. 698. 9.363E-06 9.021E-06 698. 1.250E-05 1.181E-05 698. 2.815E-04 2.409E-04 820. 820. 6.991E-06 6.7181E-06 820. 8.532E-06 8.075E-06 820. 2.236E-04 1.923E-04 SW ssu '835. 835. 6.541E-06 6.276E-06 835. 8.500E-06 8.036E-06 835. 1.574E-04 1.3541E-04 Usti 628. 628. 1.059E-05 1.020E-05 628. 1.637E-05 1.535E-05 628. 3.668E-04 3.140E-04 U 533. 533. 1.121E-05 1.081E-05 533. 1.588E-03 1.490E-05 533. 4.005E-04 3.423E-04 524. 524. 1.096E-05 1.0561-OS 524. 1.504E-05 1.427E-05 524. 5.039E-04 4.287E-04 1110 643. 643. ?.648E-06 7.3741-06 643. 9.956E-06 9.510E-06 643. 4.055E-04 3.441E-04 RIN 762. 762. 6.7740-06 6.526E-06 762. 8.4351-06 8.088E-06 762. 3.334E-04 2.831E-04 890. 890. 6.855E-06 6.594E-06 890. 7.588E-06 7.286E-06 890. 2.794E-04 2.377E-04 LASALLE SITE NETIEOiLOGICAL DATA 1178 - 12/87
,, The restricted area boundary (RAB) was redefined In sectors E and ESE to 033 and 848 from 1055 and 1055 motors, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, F. is the resulting dose factor et the new range (I.e.
833). FR, is the value provided in the above ODCM tables (i.e. S. SOAR, V, VBAR, (, GOAR). R, is the former RAB distance (i.e. 1055) and R Is the RAB (I.e. 833). distance This analysis Indicates that the 6ange Inrange would Increase the dose factor error by aproximately 40%. Since this dillerence Is wel within the expected error of the current factors, no further adjustment In the above factors Is considered necessary.
EPSPROJ/adcnfteshftokif-71 F432
t Revision 3 LaSalle I May 2001 Table F-7a (Continued)
Maximum Olfflle Finite Plume Gamma Dose Factors Based an I cm Depth at the Restricted Area Boundary for Xe-133 Powulnd Restricted llavatitd(Steck) Release Nixed Node(Vent) Release Ground Level Release Direction Area found Radius (.rldlyu)I(tt Radius V I V8AR Radius a CIAN (meters) (meters) llec) (meters) (mrad/yr)/(uclI/ec) (meters) (mradlyr)I(uCtI/ec)
N 1036. 1036. 7.010E-06 6.757E-06 1036. 7.933E-06 7.649E-06 1036. 3.136E-04 2.785E-04 MNE 1378. 1378. 6.9391-06 6.629E-06 1378. 7.1491-06 6.860E-06 1378. 2.132E-04 1.903E-04 NE 1609. 1609. 5.088E-06 4.853E-06 1609. 5.323E-06 5.076E-06 1609. 1.562E-04 1.397E-04 ENE 1079. 1079. 5.306E-06 5.106E-06 1079. 6.045E-06 5.769E-06 1079. 2.362E-04 2.101E-04 E 1055. lOSS. 5.535E-06 5.340E-06 loss. 6.764E-06 6.452E-06 1055. 2.632E-04 2.338E-04 ESE 1055. 1055. 7.016E-06 6.769E-06 1055. 8.566E-06 8.169E-06 1055. 2.543E-04 2.266E-04 SE 969. 969. 6.641E-06 6.416E-06 969. 8.978E-06 8.5581-06 969. 2.450E-04 2.185E-04 SSE 698. 698. 7.217E-06 6.994E-06 698. 1.073E-05 1.021E-05 698. 3.132E-04 2.785E-04 s a 820. 820. 5.369E-06 5.188E-06 820. 1.024E-06 6.687E-06 820. 2.515E-04 2.246E-04 SSu 835. 835. 4.969f-06 4.793E-06 835. 6.598E-06 6.266E-06 835. 1.770E-04 1.582E-04 Sue 628. 628. 7.798E-06 7.549E-06 628. 1.362E-05 1.285E-05 628. 4.090E-04 3.640E-04 usU 533. 533. 8.245E-06 7.992E-06 533. 1.326E-05 1.252E-05 533. 4.447E-04 3.951E-04 u 524. 524. 8.166E-06 7.919E-06 524. 1.220E-05 1.164E-05 524.0 5.551E-04 4.911E-04 IMu 643. 643. 5.715E-06 5.541E-06 643. 7.8851-06 7.574E-06 643. 4.444E-04 3.922E-04 ku 762. 762. 5.117E-06 4.958E-06 762. 6.5381-06 6.3039-06 762. 3.6611-04 3.233E-04 NNW 890. 890. 5.340E-06 5.165E-06 890. 5.911E-06 5.708E-06 890. 3.080E-04 2.725E-04 LASALLI SIT! NETEOROL0OICAL DATA 1/78 - 12/87 The restricted area boundary (RAB) was redefined In sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here, F. Is the resulting dose factor at the now range (i.e. 833). Fn, is the value provided In the above'ODCM tables (I a. S, SOAR. V. VBAR. 0. GOAR). R, Is the former RAS dislance (i.e. 1055) and R Is the RAO distance (I.e. 83:3).
This analysis Incicates that the change In range would Increase the dose factor error by approximately 40%. Since Ihis difference Is wefl within the expected error of the current factors, no further adjustment In the above factors Is considered necessary.
EPSPf0J/bdcamsalklri.71 F-33
LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Ofisite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-135m DoaulInd It.trlctld 1esvtaed(Stack) ieitsts Nixed Node(Vent) Releas. Ground Ltvl Release Direction Arts sound Radius I SUAt ladlus V VIAR Radius a GEAR (meters) (meters) (mradlyr)lfuCI/sec) (meters) (mradlyr)l/uCl/50c) (meters) (wuad/yr)l(uC/Jsec) 1036. 1036. 1.396E-04 1.349E-04 1036. 1.598E-04 1.5452-04 1036. 1.531E-03 1.475E-03 NM NNE 1378. 1378. 1.1512-04 1.1132-04 1378. 1.274E-04 1.232E-04 1378. 1.019E-03 9.821E-04 ENE 1609. 1609. 8.046E-05 t.119E-05 1609. 8.260E-05 7.9852-03 1609. 7.033E-04 6.778E-01 E 1079. 1079. 1.024E-04 9.898E-05 1079. 1.064E-04 1.028E-04 1079. 1.147E-03 1.105E-03 loss. 1055. 1.121E-04 1.084E-04 1055. 1.183E-04 1.144E-04 1055. 1.253E-03 1.207E-03 ESE 1055. o055. 1.4L18-04 1.3652-04 1055. 1.490E-04 1.441E-04 1055. 1.256E-03 1.211E-03 St 969. 969. 1.389E-04 1.343E-04 969. 1.575E-04 1.522E-04 969. 1.262E-03 1.216E-03 SSE 698. 698. 1.692E-04 1.636E-04 698. 1.955E-04 1.890E-04 698. 1.667E-03 1.606E-03 s 820. 820. 1. 196E-04 1.1572-04 820. 1.251E-04 1.209E-04 820. 1.363E-03 1.3142-03 SSW 835. 835. 1.1040-04 1.068E.04 835. 1.260E-04 1.218E-04 835. 8.762E-04 8.444E-04 SOI 628. 628. 1.904E-04 1.841E-04 628. 2.444E-04 2.363E-04 628. 2.173E-03 2.094E-03 533. 533. 2.063]-04 1.995E-04 533. 2.427E-04 2.345E-04 533. 2.479E-03 2.388E-03 WN 524. 524. 2.033E-04 1.966E-04 524. 2.511E-04 2.4272-04 524. 3.050E-03 2.9378-03 643. 643. 1.363E-04 1.31SE-04 643. 1.6818-04 1.631E-04 643. 2.206E-03 2.201E-03 762. 762. 1.1878-04 1.148E-04 762. 1.423E-04 1.376E-04 762. 1.806E-03 1.739E-03 RNU 890. 890. 1.161E-04 1.122E-04 890. 1.259E-04 1.2173-04 890. 1.482E-03 1.427E-03 ZW LASALLE ITE HEtEORTOLOGICAL DATA 1/78 - 12/87 The restricted area boundary (RAB) was redefined In sectors E and ESE to 033 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evaluated using the following equation. Here. F. is the resulting dose factor at the new range (i.e. 833). Fn, Is the value provided In the above 00CM tables (i.e. S. SBAR, V, VBAR, G, GBAR). R. Is the former RAB distance (i.e. 1055) and R Is the RAO distance (i.e. 833). .
F1 .nF~j-Ijoxpl.5 R
This analysis Indicates that the change In range would increase the dose factor error by approximately 40%. Since this difference is well within the expected error of the current factors, no further adjustment In the above factors Is considered necessary.
EPSPROJ/odcm4uah/ki.-71 F-34
I I LaSalle Revision 3 May 2001 Table F.7a (Continued)
Maximum Ofttite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Botundary for Xe-135 Dowwulnd aeutricted Elevated(Steck) Releae Mixed Node(Vmnt) tes,. Ground Level Release DIrection Arto sound ladius 3 SlAN 1sdlu V "AR Radius
- GeAR (meters) (meters) (mradlyr)/(uCl/stc) (meters) (mradfyr)l(uCIlsec) (meters) (nrad/yr)/(uCI/sec)
U '1036. 1036. 8.16SE-05 7.9028-05 1036. 9.337E-05 9.08SE-05 1036. 1.302E-03 1.257E-03 NNE NE 1378. 1378. 7.171E-03 6.9409-03 1378. 7.821E-05 ?.5691-05 1378. 9.1711-04 8.866E-04 1609. 1609. 5.140E-05 4.974E-0S 1609. 5.463E-05 5.286E-05'" '1609. 6.801E-04 6.570E-04 ENlE 1079. 1079. 6.139E-05 5.942E-05 1079. 6.476E-05 6.267E-05 1079. 9.912E-04 9.573E-04 E
1055. 1055. 6.493E-05 6.284E-0S 1055. 7.155e-05 6.924E-05 1055. 1.097E-03 1.060E-03 ESE "1055. 1055. 8.130E-05 7.869E-05 1055. 8.9058-05 8.617E-05 1055. 1.083E-03 1.046E-03 SE 969. 969. 7.9531-05 7.6971-0S 969. 9.346E-0S 9.044E-05 969. 1.052E-03 1.017E-03 SSE 698. 698. 9.205E-05 8.910E-05 698. 1.117E-04 1.081.-04 698. 1.321E-03 1.276E-03 SW 820. 820. 6.782E-05 6.564E-05 820. ?.666E-05 7.419E-05 820. 1.093E-03 1.056E-03 SU 835. 835. 6.306E-05 6.103E-05 835. 7.636E-05 7.389E-05 835. 7.699E-04 7.4381-04 ts~u 628. 628. 1.039E-04 1.006E-04 628. 1.409E-04 1.363E-04 628. 1.729E-03 1.670E-03 Su 533. 533. 1.106E-04 1.O71E-04 533. 1.372E-04 1.3288-04 533. 1.864E-03 1.801E-03 524. 524. 1.052E-04 1.0481-04 524. 1.374E-04 1.329E-04 524. 2.256E-03 2.1791-03 UNU 643. 643. 7.538E-05 7.296E-0S 643. 9.39SE-OS 9.092E-05 643. 1.775E-03 1.713E-03 762. 762. 6.654E-05 6.440E-05 762. 8.098E-0S 7.838E-05 762. 1.466E-03 1.415E-03 Nil 890. 890. 6.671E-05 6.456E-05 890. 7.32TE-03 ?.092E-05 890. 1.247E-03 1.204E-03 X I LASAILEI SITE METEOROLOGICAL DATA 1178 - 12/87
- The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors wire re-evaluated using the following equation. Here, F. Is the resulting dose factor at Ihe new range (i.e. 833). FRI Is the value provided In the above ODCM tables (i.e. S, SBAR, V, VBAR, G, GOAR). R, Is the former RAAB distance (i.e. 1055) and R Is the RAB distance (i.e. 833).
R This analysis Indicates that the change Inrange would Increase the dose factor error by approximately 40%. Since this difference Is welt within the expected error of the current factors, no further adjustment In the above factors Is considered necessary.
EPSPROJ/odcml¶ssk/kl.Ti F-35
t-Revision 3 LaSalle May 2001 Table F-7a (Continued)
Maximum Ofsllo Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Restricted Area Boundary for Xe-137 Do rlnd Restricted lteveted(Stack) Release Nixed Node(Vent) Release Ground Level Release Direction Area Botud Radius S HIAN adiums V VIAR RAdihs S GEAR (meters) (meters) (mrad/yr)/(uCllsvc) (meters) (mrwd/yr)/(uCl/sec) (meters) (.radlyr)I(uCIsec3 N 1036. 1036. 4.780E-05 4.627E-05 1036. 5.242E-05 5.074E-05 1036. 3.409E-04 3.298E-04 OHE .1378. 1378. 3.5858-05 3.4711-05 1378. 3.814E-05 3.692E-05 1378. 1.975E-04 1.911E-04 ME :1609. 1609. 2.282E-05 2.209E-05 1609. 2.185E-05 2.115E-05 1609. 1.1661-04 1.128E-04 ENE 1079. 1079. 3.342E-0S 3.236E-05 1079. 3.282E-05 3.177E-03 1079. 2.4371-04 2.358E-04 E 'loss. 1055. 3.7411-OS 3.622E-05 loss. 3.716E-05 3.597E-05 1055. 2.6251-04 2.540E-04 ESE 1055. 1055. 4.827E-05 4.673E-05 1055. 4.8718-05 4.715E-05 1055. 2.765E-04 2.6761-04 SE 969. 969. 4.7431-05 4.591E-05 969. 5.188E-05 5.023]-05 969. 2.989E-04 2.892E-04 SSE 698. 698. 6.273E-05 6.07nE-05 698. 6.983E-05 6.7608-05 698. 4.329E-04 4.189E-04 S 820. 820. 4.1331-OS 4.002E-05 820. 4.042E.05 3.913E-05 820. 3.373E-04 3.264E-04 SSUJ 835. 835. 3.5211-05 3.408E-05 835. 3.424E-05 3.315.-05 835. 1.745E-04 1.691E-04 SW 628. 628. 6.779E-05 6.563E-05 628. 7.938E-05 7.6851-05 628. 5.333E-04 5.161E-04 Usti 533. 533. 7.9191-Os 7.6671-05 533. 8.829E-05 8.548E-05 533. 7.164E-04 6.932E-04 U 524. 524. 7.990E-0S ?.736E-05 524. 9.6081-05 9.302E-05 524. 9.223E-04 8.924E-04
'NJWg 643. 643. 5.023E-05 4.8631-OS 643. 6.0902-05 5.8961-05 643. 6.002E-04 5.808E-04 Nu 762. 762. 4.1601-os 4.0261-05 762. 4.841f-05 4.687E-05 762. 4.228E-04 4.090E-04 "NNU 890. 890. 3.985E-05 3.858E-05 890. 4.152E-05 4.020E-O5 890. 3.2791-04 3.172E-04 LASALLI SITE METOROLOGICAL DATA 1/18 - 12/87
- The restricted area boundary (RAB) was redefined in sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evalualed using the following equation. Here, F. Is the resulting dose factor at the new range (i.e. 833). Fn, is the value provided in the above ODCM tables (i.e. S. SOAR. V. VBAR, G, GBAR). R. Is the former RAB distance (i.e. 1055) and R Is the RAB dislance (I.e. 833).
R This analysis Indicates that the change In range would Increase the dose factor error by approximately 40%. Since this difference Is well within the expected error of the current factors, no further adjustment In the above factors Is considered necessary.
EPSPROJIodcm~stkhIfr.7l r ,,,
LaSalle Revision 3 Table F-7a (Continued) May 2001 Maximum Otlllte Finite Plume Gamma Dose Factors Based on 1 cm Depth lithe Renlriced Area Boundary for Xe-138 Doalnold Restricted flevuted(Stack) Release Nixed Noda(Vent) Ruleuse Ground Level Release Directon Akre lound Radius I liAN Nudli V "UAt Radlus a CIA%
(meters) (meters) (mredlyr)j(uCljsec) (metera) (mrPd/yr)/(uclfsec) (meters) (mrad/yr)I(uCl/sc) iN 1036. 1036. 3.926E-04 3.816E-04 1036. 4.523E-04 4.396E-04 1036. 3.178E-03 3.0848-03 NNE 1378. 1378. 3.160f-04 3.011E-04 1378. 3.5351-04 3.437E-04 1378. 2.111TE-03 2.05SE-03 ME 1609. 1609. 2.198E-04 2.136E-04 1609. 2.272E-04 2.2081-04. 1609. 1.457E-03 1.414E-03 ENE 1079. 1079. 2.887E-04 2.805E-04 M0O9. 2.996E-04 2.912E-04 1079. 2.383E-03 2.313E-03 E 1055. 1055. 3.1671-04 3.079E-04 1055. 3.323E-04 3.230E-04 tOSS. 2.6001-03 2.5248-03 ISE 1055. lOSS. 3.961E-04 3.850E-04 1055. 4.149E-04 4.032E-04 1055. 2.613E-03 2.51,E-03 SE 969. 969. 3.938E-04 3.828E-04 969. 4.408E-04 4.285E-04 969. 2.641E-03 2.564E-03 SSE 698. 698. 4.911E-04 4.773E-04 698. S.SO4E-04 5.384E-04 698. 3.494E-03 3.391E-01 S 820. 820. 3.498E-04 3.400E-04 820. 3.606E-04 3.505E-04 820. 2.857E*03 2.1731-03 sSW 835. 835. 3.2771-04 3.1866-04 835. 3.832E-04 3.7241-04 83S. 1.828E-03 1.774E-03 S3 628. 628. 5.698E-04 S.535E-04 628. 7.209E-04 7.0071-04 628. 4.546E-03 4.412E-03 USC 533. 533. 6.144E-04 5.973E-04 533. 7.121E-04 6.9211-04 533. 5.206E-03 5.053E-03 W 524. 524. 5.976E-04 5.809E-04 524. 7.31S8-04 7.113E-04 524. 6.331E-03 6.1951-03 M 643. 643. 3.986E-04 3.873E-04 643. .85871-04 4.1S01E04 643. 4.7571-03 4.616E-03 NC 762. 762. 3.457E-04 3.360E-04 762. 4.131E-04 4.016E-04 762. 3.746E-03 3.6351-03 NIU 890. 890. 3.330E-04 3.236E-04 890. 3.626E-04 3.525E-04 890. 3.069E-03 2.978E-03 LASALLE 311 NIETEGOLOGIcAL DATA 1/78 - 12/87 The restricted area boundary (RAS) was redefined Insectors E and ESE to 833 and 040 from 1055 and 1055 meters, respectively. As a result of change of range, the dose factors were re-evaluated using the foflowing equation. Here, FR Is the resulting dose factor at the new range this (i.e. 833). Fn' Is the value provided In the above ODCM tables (i.e. S, SBAR, V,VOEAR. G. GBAR). R, Is the former RAB distance (i.e. 1055) and R Is the RAB distance (i.e.,833).
FROFj itsoxpl.5 This analysis indicates that the change in range would Increase the dose factor error by approximately 40%. Since this difference Is wel within the expected error of the current factors, no further adjustment Inthe above factors Is considered necessary.
EPSPROJ/odcm4saliesb !.
F-37
I LaSalle Revision 3 May 2001 Table F-7a (Continued)
Maximum Ofislte Finite Plume Gamma Dose Factors Based on I cm Depth at the Restricted Area Boundary for Ar-41 DownInd Reutricted flovated(Stack) Retleae lixed Nodo(Vent) Release Cround Level Release Direction Ares Round Radius I SHAN iedlus V VIA* Radius a CtAi
"(foters) (meters) (mradlyr)I(uC11sec) (meters) (mrsdlyr)l(uClIsec) (meters) (fred/yr)/(uCl/lec)
NIE MII 1036. 1036. 4.746E-04 4.594E-04 1036. 5.528E-04 5.351E-04 1036. 4.557E-03 4.411E-03 NNE 1378. 1378. 3.954E-04 3.828E-04 1378. 4.439E-04 4.2971-04 1378. 3.203E-03 3.101i-03 1609. 1609. 2.825E-04 2.734E-04 1609. 3.029E-04 2.932E-04 1609. 2.358E-03 2.28]E-01 ENE E 1079. 1079. 3.582E-04 3.4681-04 1079. 3.729E-04 3.610E-04 1079. 3.472E-03 3.361E-03 loss.
1055.
1055. 3.81BE-04 3.696E-04 1055. 4.100E-04 3.969E-04 I055. 3.841E-03 3.718E-03 ESE loss. 4.725E-04 4.574E-04 loss. 5.025E-04 4.864E-04 1055. 3.807E-03 3.685E-03 SE 969. 969. 4.711E-04 4.560E-04 969. 5.320E-04 5.149E-04 969. 3.715E-03 3.397E-03 SSE 698. 698. 5.612E-04 5.490E.04 698. 6.491E-04 6.2801-04 698. 4.695E-03 4.545E-03 S 820. 820. 4.212E-04 4.077E-04 820. 4.585E-04 4.438E-04 820. 3.879E-03 3.755E-03 SSU 835. 835. 3.994E-04 3.866E-04 835. 4.930E-04 4.772E-04 835. 2.700E-03 2.614E-03 SU 628., 628. 6.711E-04 6.496E-04 628. 8.591E-04 8.316E-04 628. 6.139E-03 5.943E-03 USW 533. 533. 7.089E-04 6.862E-04 533. 8.229E-04 7.966E-04 533. 6.667E-03 6.453E-03 U 524. 524. 6.802E-04 6.584E-04 524. 8.291E-04 8.026E-04 524. 8.037E-03 7.799E-03 643. 643. 4.708E-04 4.556E-04 643. 5.716E-04 5.533E-04 643. 6.300E-03 6.099E-03 NV 762. 762. 4.123E-04 3.991E-04 762. 4.970E-04 4.811E-04 762. 5.173E-03 5.008E-03 NNI 890. 890. 4.025E-04 3.896E-04 890. 4.447E-04 4.305E-04 890. 4.374E-03 4.234E-03 LASALLE SITE MIIEI0OLOCICAL DATA 1178 - 1217S The restricted area boundary (RAB) was redefined In sectors E and ESE to 833 and 848 from 1055 and 1055 meters, respectively. As a result of this change of range, the dose factors were re-evalualed using the following equation. Here, FA Isthe resuling dose factor at the new range (I.e. 833). FRO Is the value provided In the above ODCM tables (i.e. S, SBAR, V, VBAR, 0, GBAR). R, is the former RAO distance (I.e. 1055) and R Is the RAS distance (I.e. 833).
,"" F~F,JF-Joxp' .5 R
This analysis Indicates that the change In range would Increase the dose factor error by approximately 40%. Since this difference Is well within the expected error of the current factors, no further adjustment In the above factors Is considered necessary.
EPSPROJ/odcm4hs@ /kI-.7I F-38
LASALLE Revision 3 May 2001 Table F-8 Parameters for Calculations of N-16 Skyshine Radiation From LaSalle
'I K = 2.28E-05 mremr(MWe-nri These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of the public using Equation A-34 in Appendix A. If desired, more realistic parameters could be used In place of these to refine the estimate. For examole. 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 :cr 8 months per year. This yields an estimate of:
[12 hours/week] [(8 monthstyr),C12 monthslyr)] x (52 weeks/yr] 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 De spent at the nearest residence.
b Distance to nearest residence (See Table F-3). ..
c The OF,, is the quotient of the numtier of hours a location is occupied and the number of hours in a year.
Thus OH./B760 hours = OF, rounoed to the 0.01 digit.
In determining the maximally exposed individual the following possibilities were considered: the nearest resident, fishermen, and persons
- ~It at the National Guard facility north of the site. The annual exposure time andj 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/odcnwasaI*r1-71 F-39
I Revision 3 Supplemental Table A May 2001 Elevated Level Joint Frequency Distribution Table Summiary 375 Foot Elevation Data Summary Table of Percent..by Direction and Clase a ES St SSE S SSV sV VIW V WNW "W NNW Total claoe N me HE. NEN
.060 .056 .169 .087 .051 .056 .064 .063 .024 .943 A .024 .032 .061 .051 .062 .040 .030 .183 2.842
.047 .055 .070 .233 . .463 .330 .189 .145 .192 .153 8 .149 .175 .227 .149 .080 .420 .329 .332 4.808 A2SS .138 .069 .104 .130 .375 .579 .464 .361 .344 C .300 .262 .351 2.460 3.248 4.533 3.922 3.611 46.551 2.634 3.232 C 192 2.180 1.948 1.161 2.053 2.810 '2.875 2.270 a 3.100 1.531 1.575 2.005 1.670 1.196 27.061
.913 1.162 1.421 1.823 1.495 1.480 1.753 2.867 2.317 2.124 E 1.018 1.561 1.041 1.012 1.099 .894 A.53 .13.430 F .320 .182 .248 .280 .409 .107 .905 .995 1.459 1.735 .103 4.358
.081 .217 .507 .874 .658 .660 .460 .309 .242 .217 a .055 .039 .022 .012 .041 5.567 8.474 9.457 7.487 6.093 6.688 8.615 7.240 6.073 100.000 Total 4.965 4.237 5.359 5.366 5.394 4.385 4.601 Sumary Table of Percent by Dlrection and Speed SE Se S 2SV SIV WS V WNV NW HM Total Speed N "HE HNE IN i Els
.013 .008 .013 .010 .000 .013 .000 .000 .001 .000 .137
.45 .015 .017 A015 .010 .006 .010 .402
.021 .023 .022 .027 .027 .017 .017 .028 .021 .024 .034 .027 1.05 .016 .033 .030. .027 .115 .136 .160 2.721
.260 .276 .215 .141 .149 .159 .171 .185 .166 .. 155,- 135 .141 2.05 .162 .317 .272 .302 .321 .317 .302 .311 5.590 2.05 .381 .479 .551. .417 .389 .201 .311 .210 .323
.494 .428 .431 .404 .453 .455 .429 .400 .381 .482 .487, .455 7.791 4.05 .508 .647 .755 .547 .542 .533 8.213
.598 .792 .519 .451 .403 .420 .505 .477 .489 .492 .472 .493 .640 8.05 .499 .556 .598 .603 .656 9.150 6.05 .577 .599 .861 .596 .506 .419 .479 .483 .556 .584 .823 .487 1:207 .912 .269. 1.062 1,415 1.500 1.371 1.164 1.207 1.622 1.669 1.623 20.037 3.05 1.297 .a15 1.353 1.289 1.557 1.210 17.186
.421 .487 .345 .e99 .151 .738 .247 1.385 1.552 1.325 1.098 1.240 1.671 10.05 .912 1.432 1.662 1.428 .300 13.396 12.05 .482 .2Q .163. .894 .835 .892 ,749 1.1?7 2.107 2.440 1.122 1.338
.231 .326 .240 .263 .459 1.478 1:615 1.043 .581 .746 1.137 .404 .222 9.163 13.00 .120 .055 .026 .019 .016 .706
.000 .011 .011 .011 .013 .035 .012 .109 .031 .086 .137 .14?
03.00 .002 .000 11116 5.394 4.268 4.601 8.597 1.414 0.457 7.481 .0923 3.633 1.105 7.248 6.073 100.000 Total 4.960 4.337 1.29 NOTE: Wind directions In tables are presented In"wind from" and not wlnd to* drection.
EP8PROJAbdOM/kelIrl7I F*4 F.40
.1 Revision 3 May 2001 Supplemental Table A -Continued Elevated Level Joint Frequency Distribution Table Summary 375 Foot Elevation Data Stumary Teble of Peroent by Speed 9nd Class Claos A a C D £ F Speed
.45 .000 .000 .000 .052 .053 .023 .004 1.05 .001 .004 .004 .176 .153 .060 .008 2.05 .011 .041 .109 1.540 .656 .307 .050 3.05 .046 .159 .390 3.269 1.193 .541 .096 4.05 .102 .249 .499 4.364 1.629 .768 .166 6.05 .lo2 .335 .547 4.159 1.945 .916 .210 5.05 .10 .341 .665 4.563 2.320 .866 .268 I.05 .225 .701 1.116 10.101 5.190 2.400 .785 10.05 .141 .4290 ,lUm 7.441 4"024 2.501 .671 13.08 .134 .404 ,.Sol 6.011 5.670 3.20o 19.296 16.00 .068 .163 :3.2563.424 4.128 1.511 .610
-03.00 .001 .017 .036 .306 .133 .043 .035 EPSPROJ/odcmmah1*.714l F.41
Supple nutal Table B Revision 3 Mid Elevation Joint Frequency Distribution Table Summaries May 2001 Sumeary Table of Percent by Direction and Class 200Foot ElevatonData SE SSE S SSW SW WSW W NWN NNV Total Class N NNE NE ENE I ESE
.231 .357 .441 .370 .453 ,.653 .579 .678 7.030 A .361 .246 .303 .700 .533 .256 .142 .119 .532 5.062
.110 .104 .201 .283 .337" .292 .350 .490 .530 F .313 .249 .377 .343 .'90 .175 .506 .673 .710 .785 7.634
.390 .299 .3231 .232 .310 .490 .479 .470 C .531 .420 .566 .434 ,.539 2.140 3.09g 2.041 2.408 37.410 2.517 2.248 3.669 1.715 1.617 1.775 2.781 3.045 2.096 D 2.274 2.315 2.910 1.697 1.176 1.226 1.712 1.429 1.015 33.034
.717 .734 1.088 V105 1.4856 1.323 1.243 1.436 3.678 .446 11.419 E .,03 1.2310 1.363 1.183 .66 .854 1.017 .046 F .233 .155 .177 4205 .433 .809 .802 .716 .562 .150 0.411
.255 .635 .896 1.244 1.239 .907 .689 .740 r .065 .060 .021 .013 .059 9.721 7.219 5.698 6.283 8.297 7.490 6.094 100.000 4.1832 5.547 . 8.133 5.857 4.841 4.930 5.413 S.722 Total 4.575 Summary Table of Percent by DIrectlon and Speed SSE S SSV Sw WSW W VNV NW NNW Total Speed N NNE NE ENE E ESE* SE
.009 .005 .000 .008 .000 .000 .000 .000 .000 .113
.45 .043 .003 .000 .020 .035 .003 .005
.034 .037 .021 .026 .038 .031 .026 .034 .046 .612 1.05 .046 .072 .063 .042 .033 .025 .040 3.915
.197 .202 .201 .232 .193 .201 .189 .163 .151 .153 .103 2.05 .219 .575 .500 .333 .233 .374 .366 .374 7.946 1.132 1.140 .601 .497 .390 .399 .353 .366 :344 .330 .353 .413 3.05 .442 .466 .461 .553 .630 .616 10.319 4.05 .536 .970 1.378 .720 .61? .520 .545 .532 .699 .583 .557
.635 .556 .521 .610 .579 .560 .590 .se6 .737, .720 10.863 6.05 .681 .564 1.041 .800 .639 .553
'.940 .016 11.069
.383 .570 .802 .777 .726 .703 .681 .143 .487 .696 .687 .685 .. I5 6.05 .729 1.903 1.59 23.700 1.004 1.561 1.351 1.333 1.428 2.234 2.473 1.925 1.484 1.604 1.933 3.05 1.0oe .339 .516 1.100 1.566 1.31S .910 1e.693
.472 .106 .153 .476 .801 .691 .600 1.015 2.123 2.439 1:707 1.106 10.05 1.414 1.096 .560 10.723
.202 .016 .029 .234 .502 .340 .296 . 16 1.342 1.779 1.012 .426 .190 13.05 .3132 .203 3.006
.001 .034 .177 .067 .076 .113 .310 .333 .134 .159 .300 .663 13.00 .111 .001 .074 .074 .013 .004 .247
.000 .000 .004 .001 .000 .000 .005 .010 .009 .014 .030 09.00 .001 5.138 8.351 4.141 4.920 5.413 8.722 .731 7.2319 5.891 6.203 8.297 7.490 6.094 300.000 Total 4.575 4.132 5.547 NOTE: Wind directions In tables are presented In "wind tram" and not "wind to" drection.
EPSPROJ'odemitulukl-f71 F-42
Supplmental Table B - Continued Revision SuppleentalMay 2001 Mid Elevation Joint Frequency Distribution Table Summaries 200 Foot Elevation Data Sumery. Tebl1 of Percent by Speed end Class Close A 3 C 1 IF a Speed
.45 .000 .000 .001 .046 .037 .021 .009 1.05 .013 .004 .023 .219 .175 .116 .063 2.05 .113 .130 .291 1.946 .132 .437 .207 3.05 .dO0 .453 .809 3.633 1.631 .642 .378 4.05 .776 .581 .970 4.134 2.320 .930 .591 5.05 .621 .511 .966 3.015 2.455 1.150 .690 6.05 .835 .533 .921 4.309 2.742 1.461 1.017 1.05 1.542 1.208 1.671 1.019 5.377 3.351 2.616 10.05 1.030 .780 .310 5.211 4.'164 2.310 2.160 13.05 .874 .658 .754 4.165 2.854 .938 .607 11.00 .331 .207 t231 1.621 * .830 .041 .020 43.00 .020 .013 WOil d162 .020 .005 .()O EPSPROJAtdcosa/kil-71 F-43
Supplemental Table C Revision 3 May 2001 Ground Level Joint Frequency Distribution Table Summary 33 Foot Elevation Data Suq.mary Table of Percent by Direction and Claim S *SV SW WSV V bim NV NNW Total Class N NINE HE IN[ f ESE U1 S51
.212 .407 .475 .447 .533 :Gd5 .844 .904 7.962 A .411 .318 .Go .e37 .594 .308 .133 .135 .501 4.238
.177 .103 .071 .112 .239 .263 .222 .293 .405 .505 d .314 .150 .273 .310 .276
.424 .343 .390 .507 .639 .501 .626
.330 .328 .262 .210 .189 .172 .285 * .385 C .380 .133 1.540 2.195 2.073 2.178 1.925 2.243 3.240 3.269 2.509 37.051 D 3.149 1.449 2.171 i.504 2.63? 1.735 1.677 1.480 1.557 1.945 1.692 .917 24.941 1.021 1.756 1.434 1.303 1.561 2.656 '2.705 1.068 11.409 E L.131 .661 1.161 1;376 1.039 1.048 .6l7 .609 .378
.0o7 .177 .160 .646 .840 .750 .811 1.259 1.200 .093 8.627 F .186 1.103 1.050 .998 .966 .925 .490 .214
.008 .017 .025 .127 .615 .013 1.023 0 .019 3.329 7.690 6.422 6.979 6.118 7.771 5.803 100.000 4:836 5.236 6.349 5.379 4.932 5.319 7.862 Total 5.570 2.906 Summary Table of Percent by Direction and Speed Sl SE S SSV SW WSW W VNW NW NNW Total Speed N NNE HE FNE" I ES I
.000 .002 .005 .002 .002 .004 .002 .000 .002 .002 .029
.46 .000 .004 .000 .002 .002 .000
.066 .066 1.035
.040 .073 .046 .056 .056 .052 .073 .081 .075 .079 .061 .102 .093 1.05 .052 .457 .466 .613 .628 .497 .498 6.731 2.05 .378 .609 .813. .517 .424 .601 . .686 .582 .532 .441 1.191 1.270 1.278 1.222 1.149 1.150 1.112 1.031 1.095 1.079 .931 1.043 18.933 3.05 1.114 1.153 1.002 1.286 1.023 1.000 .19g 19.313 1.326 .621 1.122 1.230 1.420 1.116 1.058 1.079 1.131 1.119 1.648 1.550 1.274 4.05 1.129 1.029 1.104 1.014 .777 15.605 6.05 1.129 .241 .6171 1.106 1.189 .694 .642 .738 1.276 1.509 1.305
.551 .509 .636 1.047 1.434 1.113 .008 .894 .914 .966 .813 12.163 6.05 .667 .091 .297 .697 .673 14.119
.817 .761 .480 .642 1.262 1.636 1.291 .827 1.072 1.418 1.644 1.014 8.05 .628 .102 .106 1.422 .942 .933 .497 6.0o4
.042 .303 .221 .172 .239 .561 .633 .332 .3Ag .460 10.05 .145 .002 .006
.834 .563 .220 2.797
.000 .000 .002 .067 .093 .066 .094 .20 .2536 .11 .121 .264 13.05 .114 .212 .154 .029 .i71
.000 .000. .002 .000 .004 .002 .012 .016 .012 .031 .046 .145 18.00 .003
.01 .012 .002 .000 .042
.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .002 .013 09300 5.379 4.932 8.319 7.132 8.829 37.630 .4ý2 6.979 .I.1 7.771 5.003 100.000 Total 5.570 2.906 4.833 ' 11235 6.349 NOTE: Wind directions Intables are presented In 'wlnd from" and not'wind to" direction.
EPSPROJ1odem4ak/kt-71 F-44
t.
Supplemental Table C - Continued Revision May 20013 Ground Level Joint Frequency Distribution Table Summary 33 Fool Elevation Data Suemmry Table of Percent by Speed end Class U C D E F a Close A Speed
.45 .000 .000 .004 .002 .006 .010 .006
.008 .012 .1,7 .355 .299 .195 1.05 .021 1.692
.326 .202 .212 2.282 2.334 1.764 2.09 2.608 3.05 .998 .578 .798 5.133 5.350 3.267
.882 6.435 4.793 3.064 2.725 4.05 1.247 .686 1.037
.646 .852 6.115 3.080 1.773 8.05 1.203 3.049 .017 .251 6.05 1.201 .570 .804 5.412 1.206 6.605 3.334 .463 .060 3.05 1.629 .000 .002
.422 .518 2.356 1.334 .031 10.05 .775 .002 13.05 .428 .212 4245 1.463 .438 .004 "052 .382 .063 .004 .000 11.00 .112 .02 .000 93.00 .023 .012 .000 .006 .004 .004 EPSPROJ/odcmIahulIar.klI F-45
Revision 3 May 2001 Point oF,-srrm DOSE CALCULATION MANUAL LASALLE COUNTY STATION FIGURE F-I UNRFSTRncTED AREA BOUNDARY L
2Dp 0 1 20.00 , 40,00 .6000 a*an " =
I Mile scale in F'eet UNWRESTRICTE AREA BOUNDARY I
Gaseousz EffluemI Release Pomi Meteoroioo= Towe
=PSPR0Jmacnfu~gaa~uti 79 .4 F-46
.kUvj(3Nrl(3G Z -.ý Minoij I
mml 2201 NOINIS liNnOO 37-WS 0
-NnNVW WlivinTK 3SOG 311 SL40 jau:o cur '=20-91p.
(oa=ss ;a sadh uj Actu voie stul wumejaco uat4M) BOJV 8fmJGIS 8lsRmzirU A=vj 8ft=S SMZMMti LUU81UI woz Am UOISIAG-a