ML021340647
| ML021340647 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/30/2002 |
| From: | Schiavoni M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML021340647 (95) | |
Text
Exelons Exelon Generation Company, LLC www.exeloncorp.com N u. c ar LaSalle County Station 2601 North 21"Road Marseilles, IL 61341-9757 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-18 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
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 (tici/ml)
Kr-85m 2.OOE-04 Kr-85 5.OOE-04 Kr-87 4.OOE-05 Kr-88 9.00E-05 Ar-41 7.OOE-05 Xe-131m 7.OOE-04 Xe-133m 5.OOE-04 Xe-133 6.00E-04 Xe-135m 2.OOE-04 Xe-135 2.OOE-04
- 3.
Average Energy Not applicable - average energy is no longer used to determine dose to the public.
- 4.
Measurements and Approximations of Total Radioactivity
- a.
Gaseous Effluents
- 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 1 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 of effluent 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 instrumentationtimeclocks 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 r Units I
1st Qtr I 2nd Qtr I
3rd Qtr I
4th Qtr Estimated Total Error %
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 5.81 E-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
<I.OOE-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 6.1OE+00 6.47E+00
- 3. Percent of Technical Specification Limit
"*1"' 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 T
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 I
st Qtr I 2nd Qtr I
3rd Qtr I
4th Qtr
]
- 1. Fission and Activation Gas Releases Ar-41 Ci
<l.0OE-06
<I.OOE-06 2.04E-04
<l.OOE-06 Kr-85 Ci
<l.0OE-06 7.21E+02
<l.OOE-06
<l.0OE-06 Kr-85m Ci 9.72E+01 8.41E+01 7.45E+01 9.04E+01 Kr-87 Ci 3.10E+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 Ci
<l.OE-06
<I.00E-06
<I.O0E-06
<I.O0E-06 Xe-133 Ci 5.27E+01 6.71E+01 4.73E+02 5.39E+01 Xe-133m Ci
<l.OE-06
<l.OOE-06
<1.00E-06
<1.OE-06 Xe-135 Ci 7.33E+00 1.01E+01 1.51E+01 1.48E+00 Xe-135m Ci 9.07E+00
<i.OOE-06 7.70E-04
<i.00B-06 Ke-138 Ci
<l.OOE-06
<l.00E-06
<l.OOE-06
<l.00E-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
<I.00E-I l
<I.00E-11
<I.0BE-11
<1.00E-II 1-135 Ci 2.16E-03 6.06E-03 2.47E-02 1.45E-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-51 Ci
<1.00E-I l
<I.00E-l I
<1.00E-l I
<1.00E-l I Mn-54 Ci 2.06E-05 1.52E-04 1.42E-04 5.70E-05 Co-57 Ci
<I.00E-Il
<I.00E-11
<I.G0E-I1
<I.00E-lI Fe-55 Ci
<I.G0E-11
<I.00E-Il
<1.0BE-11
<I.0GBE-I Co-58 Ci
<I.00E-11
<I.00E-1i
<I.00E-I I
<I.00E-I l Fe-59 Ci
<1.0GE-11
<l.00E-i 1
<1.00E-Il
<1.00E-l I Co-60 Ci 2.79E-04 2.11 E-04 4.66E-04 2.78E-04 Zn-65 Ci
<1.00E-l I
<I.0OE-11
<1.00E-I l
<1.00E-i 1 Sr-89 Ci 2.42E-04 3.34E-04 1.22E-03 4.13E-04 Sr-90 Ci 1.54E-06
<I.0BE-lI
<1.00E-l1
<I.G0E-11 Zr-95 Ci
<1.00E-I
<1.0BE-I I
<I.0GE-11
<I.0GE-11 Mo-99 Ci
<I.00E-l1
<I.00E-Il
<1.00E-11
<I.G0E-I I Ru-103 Ci
<I.G0E-11
<I.00E-li
<1.0BE-11
<1.0GBE-I Sn-117m Ci
<1.00E-11
<1.0BE-11
<1.0GE-11
<1I.0BE-Il Cs-134 Ci
<I.0GE-11
<I.GOE-1
<1.00E-i l
<1.00E-i l Cs-137 Ci
<1.00E-i l
<I.G0E-11
<1.0BE-I I
<1.00E-l I Ba\\La-140 Ci
<I.00E-I I
<I.GOE-11 8.G0E-05
<I.0BE-11 Ce-141 Ci
<I.00E-il
<I.GGE-11 3.41E-04
<I.0BE-lI Ce-144 Ci
<l.00E-1I
<1.0BE-lI
<I.GOE-l11
<I.00E-I1 TOTAL PARTICULATES Ci 5.43E-04 6.97E-04 2.25E-03 7.48E-04
- 4. Tritium Releases "l. Total Release Activity Ci s5.02E+01 i9.17E+01 D4i85E+01 i5.14E+01
"<" 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 SUMMATION OF ALL LIQUID RELEASES I Units I l stQtr I 2ndQtr I Estimated 3rd Qtr 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/ml
<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
<LLD
- 3. Percent of Applicable Limit C. Dissolved Noble Gases
- 1. Total Activity Released Ci
<LLD
<LLD
<LLD
<LLD 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 E. 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 O.OOE+00 O.OOE+00 O.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 I and UNIT 2 BATCH MODE INuclides From Batch Releases I
Units I 1st Qtr 2nd Qtr I 3rd Qtr I 4th Qtr 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-110n 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-131mn Ci Xe-133 Ci Xe-133mn 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
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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
- e.
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.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 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.
- b.
C.
Total activity Ci Major nuclides (estimate %)
- d.
Shipment type
- e.
Solidification agent
- 2.
Dry compressible waste, contaminated equipment, etc.
- a.
Quantity shipped cu.m.
- b.
Total activity Ci
- c.
Major nuclides (estimate %)
- d.
Shipment type 5.63E+01 6.49E+01 4.57 76.97 1.73 15.59 LSA None 2.17E+02 3.93E-02 2.65 22.93 60.02 11.85 LSA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND 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.
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
- 1.
Spent resins, filter sludges, evaporator bottoms, etc.
- a.
Quantity shipped cu.m.
0.00E+00
- b.
Total activity Ci 0.OOE+00
- c.
Major nuclides (estimate %)
N/A
- d.
Shipment type N/A
- 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 O.OOE+00
- c.
Major nuclides (estimate %)
N/A
- d.
Shipment type N/A
- 4.
Irradiated Components
- a.
Number of shipments 0
- b.
Mode of Transportation N/A
- c.
Destination N/A
- 5.
Solid Waste Disposition Number of Shipments Transportation Mode Destination 2
Truck 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 I.
Spent resins, filter sludges, evaporator bottoms, etc.
- a.
Quantity shipped
- b.
C.
Total activity Major nuclides (estimate %)
cu.m.
- d.
Shipment type
- e.
Solidification agent
- 2.
Dry compressible waste, contaminated equipment, etc.
- a.
Quantity shipped cu.m.
- b.
Total activity Ci
- c.
Major nuclides (estimate %)
%/
0
- d.
Shipment type 1.89E+01 3.06E+02 3.90 73.60 6.64 14.95 LSA (5)
Type B (1)
None 1.09E+02 3.75E-02 3.13 23.11 59.25 11.64 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.OOE+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 1
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 TYPE GAMMA AIR (MRAD)
BETA AIR (MRAD)
TOT.
BODY (MREM)
SKIN (MREM)
ORGAN (MREM) 1ST QUARTER JAN - MAR 9.29E-03 (WSW) 2.88E-04 (ESE) 7.02E-03 (WSW) 7.39E-03 (WSW) 4.65E-03 (ESE) 2ND QUARTER APR-JUN 8.05E-03 (WSW) 6.18E-04 (ESE) 6.08E-03 (WSW) 6.59E-03 (WSW) 2.07E-02 (ESE) 3RD QUARTER JUL-SEP 4.74E-03 (WSW) 2.67E-04 (ESE) 3.58E-03 (WSW) 3.79E-03 (wSw) 3.48E-02 (ESE)
THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2001 4TH QUARTER OCT-DEC 6.99E-03 (WSW) 2.32E-04 (ESE) 5.28E-03 (WSW) 5.57E-03 (WSW) 1.55E-02 (ESE)
THYROID ANNUAL 2.91E-02 (wSW) 1.40E-03 (ESE) 2.20E-02 (WSW) 2.33E-02 (WSW)
- 7. 56E-02 (ESE)
THYROID COMPLIANCE STATUS -
10CFR 50 APP.
I INFANT RECEPTOR
% OF APP I.
GAMMA AIR (MRAD)
BETA AIR (MRAD)
TOT.
BODY (MREM)
SKIN (MREM)
ORGAN (MREM)
QTRLY OBJ 5.0 10.0 2.5 7.5 7.5 1ST QTR JAN-MAR 0.19 0.00 0.28 0.10 0.06 THYROID 2ND QTR APR-JUN 0.16 0.01 0.24 0.09 0.28 3RD QTR JUL-SEP 0.09 0.00 0.14 0.05 0.46 THYROID THYROID 4TH QTR OCT-DEC 0.14 0.00 0.21 0.07 0.21 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 YRLY OBJ 10.0 20.0 5.0 15.0 15.0
% OF APP.
I 0.29 0.01 0.44 0.16 0.50 THYROID
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 CHILD RECEPTOR TYPE GAMMA AIR (MRAD)
BETA AIR (MRAD)
TOT.
BODY (MREM)
SKIN (MREM)
ORGAN (MREM) 1ST QUARTER JAN - MAR 9.29E-03 (WSW) 2.88E-04 (ESE) 7.02E-03 (wSW) 7.39E-03 (WSW) 3.83E-03 (NNE) 2ND QUARTER APR-JUN 8.05E-03 (WSW) 6.18E-04 (ESE) 6.08E-03 (WSW) 6.59E-03 (WSW) 3.46E-02 (NNE) 3RD QUARTER JUL-SEP 4.74E-03 (WSW) 2.67E-04 (ESE) 3.58E-03 (WSW) 3.79E-03 (WSW) 5.40E-02 (NNE
)
THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2001 4TH QUARTER OCT-DEC 6.99E-03 (WSW) 2.32E-04 (ESE) 5.28E-03 (WSW) 5.57E-03 (WSW) 2.28E-02 (NNE)
THYROID ANNUAL
- 2. 91E-02 (WSW) 1.40E-03 (ESE) 2.20E-02 (WSW) 2.33E-02 (WSW)
- 1. 15E-01 (NNE)
THYROID COMPLIANCE STATUS -
10CFR 50 APP.
I CHILD RECEPTOR
% OF APP I.
GAMMA AIR (MRAD)
BETA AIR (MRAD)
TOT.
BODY (MREM)
SKIN (MREM)
ORGAN (MREM)
QTRLY OBJ 5.0 10.0 2.5 7.5 7.5 1ST QTR JAN-MAR 0.19 0.00 0.28 0.10 0.05 THYROID 2ND QTR APR-JUN 0.16 0.01 0.24 0.09 0.46 3RD QTR JUL-SEP 0.09 0.00 0.14 0.05 0.72 THYROID THYROID 4TH QTR OCT-DEC 0.14 0.00 0.21 0.07 0.30 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 YRLY OBJ 10.0 20.0 5.0 15.0 15.0
% OF APP.
I 0.29 0.01 0.44 0.16
- 0. 77 THYROID
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 TYPE GAMMA AIR (MRAD)
BETA AIR (MPAD)
TOT.
BODY (MREM)
SKIN (MREM)
ORGAN (MREM) 1ST QUARTER JAN-MAR 9.29E-03 (WSW) 2.88E-04 (ESE) 7.02E-03 (wSW) 7.39E-03 (WSW) 2.76E-03 (NNE) 2ND QUARTER APR-JUN 8.05E-03 (WSW) 6.18E-04 (ESE) 6.08E-03 (WSW) 6.59E-03 (WSW) 2.23E-02 (NNE) 3RD QUARTER JUL-SEP 4.74E-03 (WSW) 2.67E-04 (ESE) 3.58E-03 (WSW) 3.79E-03 (wSw) 3.41E-02 (NNE)
THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2001 4TH QUARTER OCT-DEC 6.99E-03 (WSW) 2.32E-04 (ESE) 5.28E-03 (WSW) 5.57E-03 (wSw) 1.46E-02 (NNE)
THYROID ANNUAL
- 2. 91E-02 (WSW) 1.40E-03 (ESE) 2.20E-02 (WSW) 2.33E-02 (WSW) 7.38E-02 (NNE)
THYROID COMPLIANCE STATUS 10CFR 50 APP.
I TEENAGER RECEPTOR
% OF APP I.
GAMMA AIR (MRAD)
BETA AIR (MRAD)
TOT.
BODY (MREM)
SKIN (MREM)
ORGAN (MREM)
QTRLY OBJ 5.0 10.0 2.5 7.5 7.5 1ST QTR JAN - MAR 0.19 0.00 0.28 0.10 0.04 THYROID 2ND QTR APR-JUN 0.16 0.01 0.24 0.09 0.30 3RD QTR JUL-SEP 0.09 0.00 0.14 0.05 0.45 THYROID THYROID 4TH QTR OCT-DEC 0.14 0.00 0.21 0.07 0.19 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 YRLY OBJ 10.0 20.0 5.0 15.0 15.0
% OF APP.
I 0.29 0.01 0.44 0.16 0.49 THYROID
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 ADULT RECEPTOR TYPE GAMMA AIR (MRAD)
BETA AIR (MRAD)
TOT.
BODY (MREM)
SKIN (MREM)
ORGAN (MREM) 1ST QUARTER JAN - MAR 9.29E-03 (WSW) 2.88E-04 (ESE) 7.02E-03 (WSW) 7.39E-03 (WSW)
- 3. 12E-03 (NNE) 2ND QUARTER APR-JUN 8.05E-03 (WSW) 6.18E-04 (ESE) 6.08E-03 (WSW) 6.59E-03 (WSW) 2.21E-02 (NNE) 3RD QUARTER JUL-SEP 4.74E-03 (WSW) 2.67E-04 (ESE) 3.58E-03 (WSW) 3.79E-03 (WSW) 3.36E-02 (NNE)
THYROID THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 2001 4TH QUARTER OCT-DEC 6.99E-03 (WSW) 2.32E-04 (ESE) 5.28E-03 (WSW) 5.57E-03 (WSW) 1.46E-02 (NNE)
THYROID ANNUAL
- 2. 91E-02 (WSW) 1.40E-03 (ESE)
- 2. 20E-02 (WSW) 2.33E-02 (WSW)
- 7. 33E-02 (NNE)
THYROID COMPLIANCE STATUS -
10CFR 50 APP.
I ADULT RECEPTOR
% OF APP I.
GAMMA AIR (MRAD)
BETA AIR (MRAD)
TOT.
BODY (MREM)
SKIN (MREM)
ORGAN (MREM)
QTRLY OBJ 5.0 10.0 2.5 7.5 7.5 1ST QTR JAN - MAR 0.19 0.00 0.28 0.10 0.04 THYROID 2ND QTR APR-JUN 0.16 0.01 0.24 0.09 0.29 THYROID 3RD QTR JUL-SEP 0.09 0.00 0.14 0.05 0.45 4TH QTR OCT-DEC 0.14 0.00 0.21 0.07 0.19 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 YRLY OBJ 10.0 20.0 5.0 15.0 15.0
% OF APP.
I 0.29 0.01 0.44 0.16 0.49 THYROID
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 DOSE TYPE TOTAL BODY INTERNAL ORGAN 1ST QUARTER JAN-MAR 0.00E+00 0.00E+00 2ND QUARTER APR-JUN 0.OOE+00 0.OOE+00 3RD QUARTER JUL-SEP 0.OOE+00 0.OOE+00 4TH QUARTER OCT-DEC 0.OOE+00 0.OOE+00 ANNUAL
- 0. OOE+00
- 0. OOE+00 THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS 10 CFR 50 APP.
I
% OF APP I.
QTRLY 1ST QTR OBJ JAN-MAR TOTAL BODY (MREM) 1.5 CRIT.
ORGAN(MREM) 5.0 0.00 0.00 RESULTS BASED UPON:
2ND QTR APR-JUN 0.00 0.00 3RD QTR JUL-SEP 0.00 0.00 4TH QTR OCT-DEC 0.00 0.00 YRLY
% OF OBJ APP.
I 3.0 10.0 0.00 0.00 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 INFANT RECEPTOR DOSE TYPE TOTAL BODY INTERNAL ORGAN 1ST QUARTER JAN-MAR 0.OOE+00 0.OOE+00 2ND QUARTER APR-JUN 0.OOE+00 0.OOE+00 3RD QUARTER JUL-SEP 0.OOE+00 0.OOE+00 4TH QUARTER OCT-DEC 0.OOE+00 0.OOE+00 ANNUAL
- 0. OOE+00
- 0. OOE+00 THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS -
40 CFR 141 ANNUAL LIMIT
% OF LIMIT TOTAL BODY INTERNAL ORGAN 4.0 MREM 4.0 MREM 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 TYPE 0.000 0.000
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 DOSE TYPE TOTAL BODY INTERNAL ORGAN 1ST QUARTER JAN-MAR 0.00E+00 0.00E+00 2ND QUARTER APR-JUN 0.OOE+00 0.OOE+00 3RD QUARTER JUL-SEP 0.OOE+00 0.OOE+00 4TH QUARTER OCT-DEC 0.OOE+00 0.OOE+00 ANNUAL
- 0. OOE+00
- 0. OOE+00 THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS 10 CFR 50 APP.
I 6% OF APP I.
QTRLY 1ST QTR 2ND QTR OBJ JAN-MAR APR-JUN 3RD QTR JUL-SEP 4TH QTR OCT-DEC YRLY
% OF OBJ APP.
I TOTAL BODY (MREM) 1.5 CRIT.
ORGAN(MREM) 5.0 RESULTS BASED UPON:
ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.0 10.0 0.00 0.00
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 CHILD RECEPTOR DOSE TYPE TOTAL BODY INTERNAL ORGAN 1ST QUARTER JAN-MAR 0.OOE+00 0.OOE+00 2ND QUARTER APR-JUN 0.OOE+00 0.OOE+00 3RD QUARTER JUL-SEP 0.OOE+00 0.OOE+00 4TH QUARTER OCT-DEC 0.OOE+00 0.OOE+00 ANNUAL 0.00E+00
- 0. OOE+00 THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS -
40 CFR 141 ANNUAL LIMIT
% OF LIMIT TOTAL BODY INTERNAL ORGAN 4.0 MREM 4.0 MREM 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 TYPE 0.000 0.000
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 DOSE TYPE TOTAL BODY INTERNAL ORGAN 1ST QUARTER JAN-MAR 0.00E+00 0.00E+00 2ND QUARTER APR-JUN 0.OOE+00 0.OOE+00 3RD QUARTER JUL-SEP 0.OOE+00 0.OOE+00 4TH QUARTER OCT-DEC 0.OOE+00 0.OOE+00 ANNUAL
- 0. OOE+00
- 0. OOE+00 THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS -
10 CFR 50 APP.
I
%% OF APP I.
QTRLY 1ST QTR 2ND QTR OBJ JAN-MAR APR-JUN 3RD QTR JUL-SEP 4TH QTR OCT-DEC YRLY
% OF OBJ APP.
I TOTAL BODY (MREM) 1.5 CRIT.
ORGAN(MREM) 5.0 RESULTS BASED UPON:
ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.0 10.0 0.00 0.00
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 DOSE TYPE TOTAL BODY INTERNAL ORGAN 1ST QUARTER JAN-MAR 0.OOE+00 0.OOE+00 2ND QUARTER APR-JUN 0.OOE+00
- 0. OOE+00 3RD QUARTER JUL-SEP 0.OOE+00 0.OOE+00 4TH QUARTER OCT-DEC 0.OOE+00 0.00E+00 ANNUAL
- 0. OOE+00
- 0. OOE+00 THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS -
40 CFR 141 ANNUAL LIMIT
% OF LIMIT TOTAL BODY INTERNAL ORGAN 4.0 MREM 4.0 MREM 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 TYPE 0.000 0.000
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 ADULT RECEPTOR DOSE TYPE TOTAL BODY INTERNAL ORGAN 1ST QUARTER JAN - MAR 0.OOE+00 0.OOE+00 2ND QUARTER APR-JUN 0.OOE+00 0.OOE+00 3RD QUARTER JUL-SEP 0.OOE+00 0.OOE+00 4TH QUARTER OCT-DEC 0.OOE+00 0.OOE+00 ANNUAL
- 0. OOE+00
- 0. OOE+00 THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS -
10 CFR 50 APP.
I
% OF APP I.
QTRLY 1ST QTR 2ND QTR OBJ JAN-MAR APR-JUN 3RD QTR JUL-SEP 4TH QTR OCT-DEC YRLY
% OF OBJ APP.
I TOTAL BODY (MREM) 1.5 CRIT.
ORGAN(MREM) 5.0 RESULTS BASED UPON:
ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.0 10.0 0.00 0.00
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 DOSE TYPE TOTAL BODY INTERNAL ORGAN 1ST QUARTER JAN-MAR o.OOE+00 0.OOE+00 2ND QUARTER APR-JUN 0.OOE+00 0.OOE+00 3RD QUARTER JUL-SEP 0.OOE+00 0.OOE+00 4TH QUARTER OCT-DEC 0.OOE+00 0.OOE+00 ANNUAL
- 0. OOE+00
- 0. OOE+00 THIS IS A REPORT FOR THE CALENDAR YEAR 2001 COMPLIANCE STATUS -
40 CFR 141 ANNUAL LIMIT
% OF LIMIT TOTAL BODY INTERNAL ORGAN 4.0 MREM 4.0 MREM 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 TYPE 0.000 0.000
LASALLE STATION UNIT ONE 10 CFR 20 COMPLIANCE ASSESSMENT PERIOD OF ASSESSMENT 01/01/01 TO 12/31/01 CALCULATED 04/16/02
- 1.
(1) Compliance Total Effective Dose Eqivalent, mrem/yr 3.97E-01 10 CFR 20.1301 (a)(1) limit mrem/yr 100.0
% of limit Compliance Summary -
10CFR20 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TEDE 9.41E-02 1.04E-01 1.02E-01 9.77E-02 RESULTS BASED UPON:
ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 0.40
% of Limit 0.40
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 (mrem)
Whole Body (DDE)
Organ Dose (CDE)
Plume 2.20E-02 Skyshine 3.48E-01 Ground 9.39E-04 Total 3.71E-01 Thyroid Gonads Breast Lung Marrow Bone Remainder CEDE TEDE 5.60E-02 2.49E-02 2.49E-02 2.49E-02 2.49E-02 2.49E-02 2.50E-02 2.59E-02 3.97E-01 25.0 75.0
- 25. 0 25.0 25.0 25.0 25.0 25.0 100.0 RESULTS BASED UPON:
ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 Limit (mrem)
% of Limit 1.49 0.07 0.10 0.10 0.10 0.10 0.10 0.10 0.40
LASALLE STATION UNIT TWO 10 CFR 20 COMPLIANCE ASSESSMENT PERIOD OF ASSESSMENT 01/01/01 TO 12/31/01 CALCULATED 04/16/02
- 1.
(1) Compliance Total Effective Dose Eqivalent, mrem/yr 3.41E-01 10 CFR 20.1301 (a)(1) limit mrem/yr 100.0
% of limit Compliance Summary -
10CFR20 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TEDE 8.73E-02 8.29E-02 8.15E-02 8.94E-02 RESULTS BASED UPON:
ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 0.34
% of Limit 0.34
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 (mrem)
Whole Body (DDE)
Organ Dose (CDE)
Plume 0.OOE+00 Skyshine 3.41E-01 Ground 0.OOE+00 Total 3.41E-01 Thyroid Gonads Breast Lung Marrow Bone Remainder CEDE TEDE 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00
- 0. OOE+00 3.41E-01 25.0 75.0 25.0 25.0 25.0 25.0 25.0 25.0 100.0 RESULTS BASED UPON:
ODCM ANNEX REVISION 1.7 SEPTEMBER 1995 ODCM SOFTWARE VERSION 1.1 January 1995 ODCM DATABASE VERSION 1.1 January 1995 Limit (mrem)
% of Limit 1.36 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.34
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. 21st 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 (MET1), 3.3.2,3.3.3, METSPECS/18/15 and METSPECS/18/41, Table 2a* format of wind rose table.
At this time, we would like to request the 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. MET1 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
/tb Enclosures 414 WEST FRONTAGE ROAD
- NORTHFIELD, IL
- 60093 PHONE: (847) 446-7800
- FAX: (847) 446-8130 E-MAIL: MTitWFATH1ERCOMMAND.COM
- INTERNET: HTTP-//WWW.WRATHFRCOMMAND.COM
LaSalle County Nuclear Station 375 ft. Wind Speed and Direction January-March.
2001 375Ft-33Ft Delta-T (F)
Number of Observations -
2153 Values are Percent Occurrence SPEED..............................
WIND DIRECTION CLASSES........
CLASS N
NNE NE ENE E
SSW SW WSW EU NU CSU A N LSS MMS ES EU MU 1 SU
-N 3SS MS ES EU MU 4SU N
7SS MS ES EU NU 8SU N
1 SS 8MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.19 0.14 0.05 0.00 0.00 0.00 0.00 0.51 0.05 0.09 0.09 0.00 0.00 0.00 2.42 0.42 0.28 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.05 0.00 0.00 0.00 0.00 1.02 0.14 0.09 0.09 0.00 0.00 0.00 0.74 0.23 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 0.00 0.00 0.00 0.00 0.00 0.42 0.19 0.09 0.00 0.00 0.00 0.00 0.74 0.51 0.14 0.00 0.00 0.00 0.00 0.70 0.37 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.09 0.00 0.00 0.00 0.00 0.00 0.84 0.33 0.00 0.00 0.00 0.00 0.00 0.42 0.74 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.14 0.00 0.00 0.00 0.00 0.00 0.46 0.09 0.00 0.00 0.00 0.00 0.05 0.28 0.19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.19 0.00 0.00 0.00 0.00 0.00 0.74 0.19 0.09 0.00 0.00 0.00 0.00 0.70 0.33 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.05 0.00 0.00 0.00 0.00 0.00 0.56 0.14 0.00 0.00 0.00 0.00 0.00 0.23 0.23 0.09 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.05 0.00 0.00 0.00 0.00 0.00 0.28 0.23 0.00 0.00 0.00 0.00 0.00 0.19 0.42 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.09 0.05 0.00 0.00 0.00 0.00 0.23 0.14 0.00 0.00 0.00 0.00 0.00 0.51 0.33 0.14 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.09 0.00 0.00 0.00 0.00 0.37 0.42 0.09 0.00 0.00 0.00 0.00 0.74 0.33 0.23 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.09 0.00 0.00 0.00 0.00 0.00 0.84 0.65 0.23 0.09 0.00 0.00 0.00 0.88 0.51 0.37 0.19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.00 0.00 0.00 0.00 0.00 0.00 1.11 0.23 0.09 0.00 0.00 0.00 0.00 1.02 0.33 0.19 0.00 W
WNW NW NNW TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.00 0.51 0.00 0.00 0.00 0.00 0.00 0.00 0.98 0.23 0.09 0.00 0.00 0.00 0.00 1.35 0.84 0.19 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.33 0.14 0.00 0.00 0.00 0.00 0.00 0.93 0.60 0.00 0.00 0.00 0.00 0.00 2.14 1.21 0.42 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.37 0.23 0.05 0.00 0.00 0.00 0.00 1.44 0.33 0.00 0.05 0.00 0.00 0.00 2.09 1.44 0.14 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.14 0.05 0.05 0.00 0.00 0.00 0.00 0.70 0.46 0.09 0.05 0.00 0.00 0.00 1.81 0.60 0.14 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.19 0.09 0.00 0.00 0.00 0.00 0.00 3.62 1.53 0.42 0.00 0.00 0.00 0.00 0.00 11.75 4.74 1.02 0.37 0.00 0.00 0.00 0.05 16.21 8.50 2.46 1.16 STABILITY CLASSES..........
EU pJ SU N
SS MS ES TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.19 0.09 0.00 0.46 0.00 0.00 3.62 1.53 0.42 0.00 5.57 0.00 0.00 11.75 4.74 1.02 0.37 17.88 0.00 0.05 16.21 8.50 2.46 1.16 28.38
LaSalle County Nuclear Station 375 ft. Wind Speed and Direction January-March.
2001 375Ft-33Ft Delta-T (F)
SPEED WIND DIRECTION CLASSES..................................
STABILITY CLASSES..........
CLASS N
NNE NE ENE E
NNW TOTAL EU MU SU 0.00 0.00 0.00 0.14 0.05 0.05 0.00 0.00 0.00 0.00 1.07 0.00 0.00 0.00 0.00 0.00 0.00 0.33 0.14 0.00 0.00 0.00 0.00 0.00 0.19 0.05 0.00 0.00 0.00 0.00 0.05 0.19 0.00 0.05 0.00 0.00 0.00 0.00 0.14 0.14 0.00 0.00 0.00 0.00 0.00 0.42 0.33 0.05 0.00 0.00 0.00 0.00 0.00 0.84 0.00 0.00 0.00 0.00 0.00 0.28 0.23 0.37 0.05 0.00 0.00 0.00 0.28 0.51 0.00 0.00 0.00 0.00 0.00 0.14 0.19 0.05 0.09 0.00 0.00 0.00 0.00 0.09 0.09 0.00 0.00 0.00 0.00 0.33 0.74 0.23 0.00 0.00 0.00 0.00 0.28 0.42 0.51 0.33 0.00 0.00 0.00 0.56 0.56 0.19 0.14 0.00 0.00 0.00 0.51 1.21 0.51 0.23 0.00 0.00 0.00 0.33 0.42 0.23 0.09 0.00 0.00 0.00 0.33 0.84 0.65 0.70 0.00 0.00 0.00 0.88 0.42 0.42 0.09 0.00 0.00 0.00 0.46 0.23 0.37 1.16 0.00 0.00 0.00 1.63 1.25 0.56 0.05 0.00 0.00 0.00 1.58 1.02 0.33 0.09 0.00 0.00 0.00 1.81 0.93 0.56 0.09 0.00 0.00 0.00 1.30 1.63 0.37 0.05 0.00 0.00 0.09 3.58 1.30 0.28 0.19 0.00 0.00 0.00 2.74 0.51 0.00 0.00 0.00 0.00 0.00 1.44 0.42 0.33 0.37 0.00 0.00 0.00 0.28 0.09 0.00 0.00 0.00 0.00 0.00 0.14 13.14 7.15 3.44 1.35 0.00 0.00 0.00 0.00 9.48 7.62 2.83 2.55 N
SS MS ES TOTAL 0.00 0.14 13.14 7.15 3.44 1.35 25.22 0.00 0.00 EU 1MU 9 SU
> N 2S5 4NS ES 0.00 0.00 0.00 0.93 0.19 0.09 0.19 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.19 0.00 0.00 0.00 0.00 0.00 0.00 0.28 0.00 0.00 0.00 2.55 22.48 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 5.43 100.00 Wind Direction by Stability N
NNE NE ENE E
ESE SE SSE 0.00 0.00 0.00 4.09 0.88 0.51 0.42 0.00 0.00 0.00 2.28 0.51 0.19 0.09 0.00 0.00 0.00 3.11 1.16 0.37 0.00 0.00 0.00 0.00 2.04 1.35 0.00 0.00 0.00 0.00 0.09 1.30 0.56 0.05 0.00 0.00 0.00 0.00 2.04 1.86 0.23 0.00 0.00 0.00 0.00 1.53 1.16 0.46 0.14 0.00 0.00 0.00 0.79 0.98 0.19 0.09 S
SSW SW WSW W WNW NW 0.00 0.00 0.00 1.53 1.72 0.93 0.42 0.00 0.00 0.00 2.23 2.51 1.11 0.42 0.00 0.00 0.00 2.51 2.51 1.49 1.07 0.00 0.00 0.00 3.72 1.21 1.07 1.25 0.00 0.00 0.00 6.08 3.34 1.21 0.28 0.00 0.00 0.00 6.55 4.51 1.35 0.28 0.00 0.00 0.09 10.22 3.81 0.46 0.46 NNW TOTAL 0.00 0.00 0.00 4.37 1.67 0.65 0.51 0.00 0.00 0.19 54.39 29.73 10.26 5.43 Wind Direction by Wind Speed N
NNE NE ENE E
SSW SW WSW W WNW NW NNW TOTAL 0.00 0.05 0.33 1.16 1.16 0.46 0.23 0.00 0.00 0.37 0.56 0.51 0.28 0.28 0.00 0.00 0.37 1.02 1.11 0.79 0.00 0.00 0.23 0.70 0.65 0.93 0.00 0.00 0.23 0.51 0.65 0.46 0.00 0.00 0.33 0.37 1.07 1.30 0.00 0.00 0.14 0.88 1.35 1.44 0.00 0.00 0.23 1.81 1.95 1.07 0.00 0.00 0.23 1.44 1.53 1.81 0.00 0.09 0.51 1.30 2.51 3.48 0.00 0.05 0.46 1.53 3.90 3.39 0.00 0.00 0.65 1.81 3.90 5.43 0.00 0.09 0.23 1.30 2.65 2.55 0.00 0.46 5.57 17.88 28.38 25.22 0.84 0.79 0.19 1.53 2.46 2.51 2.23 3.02 3.34 3.25 0.37 22.48
-WIND SPEED CLASSES-CALM 1.0- 3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 mph mph mph mph mph
>24.5 mph 9.48 7.62 2.83
-STABILITY CLASSES Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable 0.00 0.05 0.37 0.74 3.25 1.39 0.09 0.00 0.05 0.19 1.35 1.02 0.19 0.28 0.00 0.09 0.70 1.39 1.16 0.23 1.07
LaSalle County Nuclear Station 375 ft. Wind Speed and Direction April-June.
2001 375Ft-33Ft Delta-T (F)
Number of Observations -
2184 Values are Percent Occurrence SPEED WIND DIRECTION CLASSES..................................
CLASS N
NNE NE ENE E
WNW NW NKNW TOTAL STABILITY CLASSES..........
EU MU SU N
SS MS ES TOTAL EU NU CSU A N LSS NNS ES EU NU 1SU N
3SS HS ES EU MU 4 SU N
1SS 2MS ES EU 1HU 3JSU
-N 1SS 8MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.05 0.00 0.00 0.00 0.00 1.01 0.14 0.00 0.00 0.00 0.00 0.00 1.01 0.32 0.18 0.00 0.00 0.00 0.00 0.27 0.41 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 0.00 0.00 0.00 0.00 0.00 0.00 1.05 0.00 0.00 0.00 0.00 0.00 0.00 1.19 0.50 0.05 0.00 0.00 0.00 0.00 0.37 0.23 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.64 0.05 0.00 0.00 0.00 0.00 0.00 0.64 0.27 0.00 0.00 0.00 0.00 0.05 1.37 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.09 0.00 0.00 0.00 0.00 0.50 0.14 0.00 0.00 0.00 0.00 0.00 2.47 0.64 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.27 0.09 0.00 0.00 0.00 0.00 0.00 0.60 0.73 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.14 0.00 0.00 0.00 0.00 0.46 0.14 0.09 0.00 0.00 0.00 0.00 0.46 0.27 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.46 0.00 0.09 0.00 0.00 0.00 0.00 0.37 0.18 0.18 0.00 0.00 0.00 0.00 0.60 0.18 0.37 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.05 0.05 0.00 0.00 0.00 0.00 0.41 0.37 0.37 0.00 0.00 0.00 0.00 0.73 0.18 0.46 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.05 0.00 0.00 0.00 0.00 0.46 0.05 0.00 0.00 0.00 0.00 0.00 0.92 0.37 0.27 0.14 0.00 0.00 0.00 0.73 0.27 0.82 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.60 0.14 0.05 0.00 0.00 0.00 0.00 0.50 0.14 0.69 0.00 0.00 0.00 0.05 0.64 0.32 0.78 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.27 0.18 0.05 0.00 0.00 0.00 0.00 0.55 0.18 0.32 0.00 0.00 0.00 0.00 0.64 0.46 0.37 0.00 0.00 0.09 0.09 0.23 0.00 0.00 0.14 0.05 0.00 0.18 0.78 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.23 0.37 0.09 0.00 0.00 0.00 0.00 0.60 0.23 0.05 0.00 0.00 0.00 0.09 0.60 0.37 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.09 0.05 0.00 0.00 0.00 0.00 0.50 0.23 0.18 0.09 0.00 0.00 0.00 0.69 0.37 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.41 0.18 0.05 0.00 0.00 0.00 0.00 1.01 0.32 0.09 0.09 0.00 0.00 0.09 1.37 0.60 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.05 0.00 0.00 0.00 0.00 0.32 0.23 0.00 0.00 0.00 0.00 0.00 0.27 0.50 0.09 0.09 0.00 0.00 0.00 0.50 0.46 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.46 0.05 0.00 0.00 0.00 0.00 0.00 0.82 0.27 0.18 0.05 0.00 0.00 0.00 0.18 0.37 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.60 0.41 0.14 0.05 0.00 0.00 0.00 0.00 6.46 1.65 0.64 0.00 0.00 0.00 0.00 0.00 10.03 4.26 2.75 0.46 0.00 0.00 0.00 0.27 12.23 6.04 3.85 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.60 0.41 0.14 0.05 1.19 0.00 0.00 6.46 1.65 0.64 0.00 8.75 0.00 0.00 10.03 4.26 2.75 0.46 17.49 0.00 0.27 12.23 6.04 3.85 0.78 23.17
LaSalle County Nuclear Station 375 ft. Wind Speed and Direction April-June.
2001 375Ft-33Ft Delta-T (F)
SPEED WIND DIRECTION CLASSES..................................
CLASS N
NNE NE ENE E
0.00 0.05 0.18 1.65 0.41 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 2.11 0.41 0.00 0.00 0.00 0.00 0.00 0.09 0.18 0.00 0.00 0.00 0.00 0.14 1.05 0.41 0.05 0.00 0.00 0.00 0.00 0.41 0.37 0.09 0.00 ESE SE SSE 0.00 0.00 0.00 0.60 0.60 0.00 0.00 0.00 0.00 0.00 0.18 0.14 0.23 0.00 0.00 0.00 0.00 0.14 0.27 0.23 0.00 0.00 0.00 0.00 0.05 0.41 0.27 0.00 0.00 0.00 0.00 0.78 0.32 0.23 0.00 0.00 0.00 0.00 0.05 0.50 0.05 0.14 S
SSW SW WSW W WNW NW NNW TOTAL 0.00 0.00 0.14 0.87 0.46 0.27 0.18 0.00 0.00 0.00 0.69 1.33 0.32 0.27 0.00 0.00 0.23 1.14 0.55 0.46 0.05 0.00 0.00 0.09 1.79 3.39 1.01 0.41 0.00 0.00 0.41 1.37 0.64 0.55 0.09 0.00 0.14 0.96 1.92 1.28 0.64 0.14 0.00 0.00 0.00 0.82 0.18 0.50 0.23 0.00 0.09 0.05 0.96 0.73 0.37 0.18 0.00 0.00 0.05 0.60 0.32 0.09 0.23 0.00 0.00 0.00 0.73 0.87 0.14 0.23 0.00 0.00 0.05 1.33 0.64 0.27 0.00 0.00 0.00 0.00 0.92 0.69 0.00 0.00 0.00 0.00 0.00 0.41 0.46 0.05 0.09 0.00 0.00 0.00 0.50 0.37 0.00 0.00 0.00 0.00 0.00 0.18 0.09 0.00 0.00 0.00 0.00 0.00 0.32 0.00 0.00 0.00 0.00 0.00 0.05 1.19 13.55 5.95 2.70 0.87 0.00 0.00 0.23 1.19 8.84 10.35 3.11 1.37
......... STABILITY CLASSES..........
EU MU SU N
SS MS ES TOTAL 0.05 1.19 13.55 5.95 2.70 0.87 24.31 0.23 1.19 EU 1HU 9SU N
> N 2 SS 4HS ES 0.00 0.00 0.00 0.09 0.09 0.00 0.00 0.00 0.00 0.09 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.41 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 25.09 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 3.53 100.00 Wind Direction by Stability N
NNE NE ENE E
SSW SW WSW W WMN 0.00 0.00 0.09 2.66 1.01 0.27 0.00 0.00 0.00 0.00 3.07 0.87 0.14 0.00 0.00 0.05 0.23 4.30 1.05 0.00 0.00 0.00 0.00 0.00 5.45 1.42 0.09 0.00 0.00 0.00 0.14 2.38 1.74 0.18 0.00 0.00 0.00 0.00 1.74 1.14 0.60 0.00 0.00 0.00 0.00 1.65 1.05 1.14 0.00 0.00 0.00 0.00 2.24 1.42 1.14 0.23 0.00 0.00 0.14 3.75 2.47 1.74 0.69 0.00 0.00 0.37 4.72 4.53 2.98 0.69 0.00 0.14 1.37 4.76 2.75 1.92 0.23 0.00 0.09 0.14 3.21 2.01 1.24 0.41 0.00 0.00 0.05 2.70 1.88 0.60 0.69 0.00 0.00 0.14 5.04 2.43 0.55 0.14 NW NNW TOTAL 0.00 0.00 0.00 2.06 2.11 0.41 0.18 0.00 0.00 0.00 0.27 0.00 2.66 1.97 51.69 0.78 28.66 0.18 13.19 0.27 3.53
-STABILITY CLASSES Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N
NNE NE ENE E
NW NW NNW TOTAL 0.00 0.14 1.14 1.51 0.73 0.18 0.00 0.05 1.05 1.74 0.69 0.50 0.00 0.09 0.69 0.92 1.60 2.29 0.00 0.18 0.23 0.64 3.11 2.52 0.00 0.09 0.09 0.37 1.37 1.65 0.00 0.00 0.18 0.69 0.87 1.19 0.00 0.05 0.55 0.73 1.14 0.64 0.00 0.05 0.32 1.14 1.47 1.33 0.00 0.14 0.50 1.69 1.92 1.92 0.32 0.05 0.05 0.27 0.87 0.55 0.73 0.73 2.61 0.00 0.05 0.78 1.33 2.01 2.43 6.68 0.00 0.00 0.50 1.05 1.47 3.07 5.08 0.00 0.14 0.69 0.87 1.28 1.74 2.38 0.00 0.00 0.32 1.01 1.33 1.28 1.97 0.00 0.00 0.64 1.51 2.24 2.29 1.60 0.00 0.18 0.55 0.96 1.19 1.01 0.87 0.00 0.05 0.50 1.33 0.73 0.27 0.32 0.00 1.19 8.75 17.49 23.17 24.31 25.09
-WlND SPEED CLASSES CALM 1.0- 3.5 mph 3.6-7.5 mph 7.6-12.5 mph 12.6-18.5 mph 18.6-24.5 mph
>24.5 mph 8.84 10.35 3.11 1.37
LaSalle County Nuclear Station 375 ft. Wind Speed and Direction July-September, 2001 375Ft-33Ft Delta-T (F)
Number of Observations -
2208 Values are Percent Occurrence SPEED WIND DIRECTION CLASSES..................................
CLASS N
NNE NE ENE E
EU MU C SU A N L SS MNS ES EU MU SU N
.N 1SS 2MS ES EU 3 SU
.N 1 SS 8OM ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.00 0.00 0.00 0.00 0.00 0.32 0.27 0.14 0.00 0.00 0.00 0.00 0.91 0.41 0.18 0.00 0.00 0.00 0.00 0.41 0.23 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.05 0.00 0.00 0.00 0.00 0.63 0.14 0.14 0.00 0.00 0.00 0.09 2.31 0.36 0.09 0.05 0.00 0.00 0.05 0.63 0.63 0.23 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 0.00 0.00 0.00 0.00 0.91 0.09 0.09 0.00 0.00 0.00 0.00 0.86 0.45 0.05 0.00
-0.00 0.00 0.09 1.18 0.72 0.32 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.05 0.00 0.00 0.00 0.00 0.27 0.36 0.09 0.00 0.00 0.00 0.00 0.95 0.36 0.00 0.00 0.00 0.00 0.00 1.77 1.40 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.36 0.09 0.05 0.00 0.00 0.00 0.00 0.59 0.68 0.18 0.00 0.00 0.00 0.00 0.77 1.22 0.63 0.00 ESE SE SSE S
SSW SW WSW W WNW NW NNW TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.05 0.00 0.00 0.00 0.00 0.27 0.14 0.05 0.00 0.00 0.00 0.00 0.86 0.05 0.23 0.00 0.00 0.00 0.00 0.59 0.68 0.72 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 0.41 0.18 0.14 0.00 0.00 0.00 0.00 0.54 0.23 0.63 0.00 0.00 0.00 0.00 0.09 0.36 0.27 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.00 0.00 0.00 0.00 0.00 0.63 0.05 0.23 0.18 0.00 0.00 0.00 0.54 0.14 0.32 0.09 0.00 0.00 0.00 0.18 0.32 0.41 0.41 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.05 0.00 0.00 0.00 0.00 0.91 0.36 0.14 0.09 0.00 0.00 0.00 1.13 0.18 0.36 0.00 0.00 0.00 0.00 0.59 0.68 0.27 0.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.00 0.00 0.00 0.00 0.00 1.27 0.32 0.09 0.05 0.00 0.00 0.05 1.00 0.09 0.14 0.05 0.00 0.00 0.14 0.45 0.50 0.41 0.36 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 0.00 0.72 0.36 0.14 0.00 0.00 0.00 0.00 0.72 0.27 0.41 0.14 0.00 0.00 0.09 0.77 0.63 0.72 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.05 0.00 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 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.95 0.91 0.32 0.00 STABILITY CLASSES..........
EU MU SU N
SS MS ES TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.95 0.91 0.32 0.00 2.17 0.00 0.00 0.00 1.13 0.27 0.14 0.05 0.00 0.00 0.18 1.13 0.54 0.45 0.05 0.00 0.00 0.09 1.00 0.63 0.36 0.50 0.00 0.00 0.00 0.45 0.18 0.09 0.00 0.00 0.00 0.14 1.63 0.45 0.54 0.18 0.00 0.00 0.00 0.36 0.23 0.05 0.00 0.00 0.00 0.00 0.45 0.23 0.41 0.05 0.00 0.00 0.00 0.32 0.14 0.23 0.05 0.00 0.00 0.00 0.63 0.68 0.50 0.09 0.00 0.00 0.00 0.54 0.00 0.18 0.00 0.00 0.00 0.00 0.86 0.32 0.14 0.09 0.00 0.00 0.00 9.51 3.17 1.95 0.41 0.00 0.00 0.00 9.51 3.17 1.95 0.41 15.04 0.00 0.00 0.00 0.45 15.13 5.43 4.62 0.77 0.00 0.45 15.13 5.43 4.62 0.77 26.40 0.00 0.05 0.05 0.41 0.41 0.82 0.27 0.00 0.00 0.14 0.72 0.50 0.50 0.05 0.00 0.00 0.00 0.95 0.50 0.59 0.18 0.00 0.00 0.00 0.45 0.36 0.18 0.05 0.00 0.00 0.05 0.63 10.96 9.78 6.79 2.40 0.05 0.63 10.95 9.78 6.79 2.40 30.62
LaSalle County Nuclear Station 375 ft. Wind Speed and Direction July-September, 2001 375Ft-33Ft Delta-T (F)
SPEED WIND DIRECTION CLASSES..................................
CLASS N
NNE NE ENE E
ESE SE 0.00 0.00 0.00 1.22 0.54 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.00 0.00 0.00 0.00 0.00 0.77 0.45 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.45 0.14 0.00 0.00 0.00 0.00 0.00 0.18 0.09 0.00 0.00 0.00 0.00 0.05 0.32 0.50 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.18 0.14 0.00 0.00 0.00 0.00 0.09 0.14 0.09 0.00 SSE S
0.00 0.00 0.00 0.27 0.27 0.18 0.36 0.00 0.00 0.00 0.09 0.36 0.09 0.18 0.00 0.00 0.00 0.09 0.41 0.45 0.41 0.00 0.00 0.00 0.18 0.72 0.18 0.32 SSW SW WSW W WNW NW NNW TOTAL 0.00 0.00 0.05 0.59 0.41 0.68 0.09 0.00 0.00 0.09 0.18 0.50 0.36 0.77 0.00 0.00 0.00 0.45 0.59 0.54 0.05 0.00 0.00 0.00 0.09 0.23 0.05 0.09 0.00 0.00 0.00 0.63 0.50 0.27 0.09 0.00 0.00 0.00 0.09 0.05 0.05 0.00 0.00 0.00 0.00 0.32 0.23 0.41 0.05 0.00 0.00 0.00 0.09 0.00 0.41 0.00 0.00 0.00 0.00 0.77 0.41 0.45 0.05 0.00 0.00 0.00 0.09 0.00 0.09 0.00 0.00 0.00 0.00 0.63 0.27 0.23 0.00 0.00 0.00 0.00 0.14 0.00 0.09 0.05 0.00 0.00 0.00 0.50 0.14 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 7.47 5.71 4.30 1.09 0.00 0.00 0.00 0.09 1.54 2.54 1.59 1.40 STABILITY CLASSES..........
EU MU SU N
SS MS ES TOTAL 0.00 0.05 7.47 5.71 4.30 1.09 18.61 0.00 EU 1IU 9 SU
- N 2SS 4HS ES EU SU
> N 2 SS ES 0.00 0.00 0.00 0.95 0.50 0.09 0.00 0.00 0.00 0.00 0.36 0.27 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.59 1.40 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
NNE NE ENE E
0.00 0.00 0.00 3.03 1.72 0.63 0.00 0.00 0.00 0.14 3.71 1.22 0.50 0.09 0.00 0.00 0.09 4.21 1.90 0.50 0.00 0.00 0.00 0.00 3.89 2.63 0.27 0.00 0.00 0.00 0.00 1.90 2.63 1.09 0.00 0.00 0.00 0.00 1.86 1.27 1.63 0.00 0.00 0.00 0.00 1.22 1.09 1.27 0.05 0.00 0.00 0.00 1.81 1.18 1.22 1.22 0.00 0.00 0.00 2.90 2.49 1.45 1.09 SSW 0.00 0.00 0.32 3.58 1.90 1.68 1.31 SW WSW W WNW IN NNW TOTAL 0.00 0.00 0.09 2.90 2.17 1.86 0.50 0.00 0.00 0.27 4.08 2.08 1.27 0.68 0.00 0.05 0.18 2.99 1.36 2.31 0.50 0.00 0.00 0.14 2.40 1.45 1.49 0.14 0.00 0.00 0.00 2.72 1.59 1.68 0.36 0.00 0.00 0.00 2.36 0.86 0.72 0.14 0.00 0.05 1.22 45.56 27.54 19.57 6.07 Wind Direction by Wind Speed N
NNE NE ENE E
WIN NW NNM TOTAL 0.00 0.14 0.72 1.49 0.86 1.54 0.63 0.00 0.18 0.91 2.90 1.59 0.09 0.00 0.00 0.05 1.09 1.36 2.31 1.77 0.14 0.00 0.14 0.72 1.31 3.31 1.22 0.09 0.00 0.00 0.50 1.45 2.63 0.77 0.27 0.00 0.23 0.45 1.13 1.99 0.86 0.09 0.00 0.09 0.72 1.40 0.77 0.32 0.32 0.00 0.14 1.09 1.09 1.31 1.09 0.72 0.00 0.18.
1.49 1.68 1.81 1.36 1.40 0.00 0.18 1.72 1.31 1.86 1.81 1.90 0.00 0.23 1.22 1.54 2.45 1.63 0.45 0.00 0.18 1.59 2.36 2.58 1.49 0.18 0.00 0.23 0.72 2.94 1.99 1.00 0.50 0.00 0.09 0.63 1.13 1.90 1.68 0.18 0.00 0.09 0.72 1.90 2.22 1.13 0.27 0.00 0.05 0.72 1.40 1.04 0.86 0.00 0.00 2.17 15.04 26.40 30.62 18.61 7.16
-WIND SPEED CLASSES CALM 1.0- 3.5 mph 3.6-7.5 mph 7.6-12.5 mph 12.6-18.5 mph 18.6-24.5 mph
- 24.5 mph 0.09 1.54 2.54
-STABILITY CLASSES Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable
LaSalle County Nuclear Station 375 ft. Wind Speed and Direction October-December, 2001 375Ft-33Ft Delta-T (F)
Number of Observations -
2207 Values are Percent Occurrence SPEED W IND DIRECTION CLASSES..................................
CLASS N
NNE NE ENE E
SSW SW WSW W WNW NW NNW TOTAL EU M1U CSU A N LSS NNS ES EU NU SU N
.N 7SS MS ES EU MU 8SU N
1SS 2MS ES EU 1U 3SU
-N ISS 8MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.27 0.05 0.00 0.00 0.00 0.00 0.00 1.00 0.18 0.09 0.00 0.00 0.00 0.00 1.00 0.45 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.32
.0.05 0.00 0.00 0.00 0.00 0.00 0.50 0.23 0.05 0.00 0.00 0.00 0.00 0.68 0.18 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.23 0.05 0.09 0.00 0.00 0.00 0.00 0.36 0.18 0.00 0.00 0.00 0.00 0.00 0.23 0.32 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.00 0.00 0.00 0.00 0.00 0.50 0.09 0.09 0.00 0.00 0.00 0.00 0.32 0.14 0.00 0.00 0.00 0.00 0.00 0.41 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.05 0.00 0.00 0.00 0.00 0.23 0.18 0.05 0.00 0.00 0.00 0.00 0.27 0.45 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.32 0.32 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 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.23 0.09 0.00 0.00 0.00 0.00 0.05 0.05 0.09 0.00 0.00 0.00 0.00 0.23 0.14 0.09 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.45 0.23 0.32 0.05 0.00 0.00 0.00 0.63 0.14 0.00 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.05 0.05 0.05 0.00 0.00 0.00 0.36 0.45 0.23 0.23 0.00 0.00 0.00 0.59 0.68 0.27 0.36 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.05 0.00 0.00 0.00 0.41 0.09 0.05 0.27 0.00 0.00 0.00 0.68 0.45 0.41 0.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.68 0.27 0.05 0.09 0.00 0.00 0.00 0.82 0.54 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 0.05 0.00 0.00 0.00 0.00 0.00 0.14 0.05 0.00 0.05 0.00 0.00 0.00 0.82 0.23 0.09 0.05 0.00 0.00 0.00 1.22 0.23 0.36 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.27 0.05 0.00 0.00 0.00 0.00 0.00 0.77 0.18 0.09 0.14 0.00 0.00 0.00 1.54 0.32 0.18 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.18 0.09 0.00 0.00 0.00 0.00 0.00 0.50 0.18 0.09 0.18 0.00 0.00 0.00 1.09 0.68 0.27 0.36 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.41 0.18 0.14 0.14 0.00 0.00 0.00 0.63 0.54 0.36 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.09 0.00 0.00 0.00 0.00 0.41 0.36 0.00 0.00 0.00 0.00 0.00 0.77 0.41 0.23 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 0.27 0.23 0.05 0.00 0.00 0.00 0.00 0.00 3.04 1.00 0.50 0.14 0.00 0.00 0.00 0.00 7.25 3.26 1.31 1.13 STABILITY CLASSES..........
EU MU SU N
SS MS ES TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.27 0.23 0.05 0.00 0.54 0.00 0.00 3.04 1.00 0.50 0.14 4.67 0.00 0.00 7.25 3.26 1.31 1.13 12.96 0.00 0.00 0.00 0.00 11.10 6.03 3.04 2.17 0.00 0.00 11.10 6.03 3.04 2.17 22.34
LaSalle County Nuclear Station 375 ft. Wind Speed and Direction WIND DIRECTION CLASSES October-December, 2001 375Ft.33Ft Delta-T (F)
STABILITY CLASSES ----------
CLASS N
NNE NE ENE E
WNW NW NNW TOTAL EU MU SU N
SS MS ES TOTAL 0.00 0.00 0.00 2.40 1.72 0.63 0.27 0.00 0.00 0.00 0.91 1.68 0.18 0.00 0.00 0.00 0.00 1.50 0.63 0.36 0.05 0.00 0.00 0.00 1.72 0.50 0.05 0.14 0.00 0.00 0.00 0.18 0.36 0.14 0.00 0.00 0.00 0.00 0.41 0.05 0.00 0.00 0.00 0.00 0.00 0.05 12.10 7.48 3.76 1.63 0.00 0.00 0.00 0.18 10.97 13.32 5.62 4.40 0.00 0.05 12.10 7.48 3.76 1.63 25.01 0.00 0.18 EU 1jIU 9 SU H
2S5 4MS ES EU MU SU
> N 2SS 4MS ES 0.00 0.00 0.00 0.14 0.18 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 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
WNW NW NNW TOTAL 0.00 0.00 0.00 5.07 4.35 1.22 0.82 0.00 0.00 0.00 4.49 1.86 0.91 0.45 0.00 0.00 0.00 1.86 1.27 0.45 0.05 0.00 0.00 0.23 44.72 31.31 14.27 9.47
-STABILITY CLASSES Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N
SSW SW WSW W WNW NW NNW TOTAL 0.00 0.05 0.32 1.27 1.54 0.32 0.05 0.00 0.05 0.36 0.77 1.00 0.00 0.00 0.00 0.05 0.36 0.54 0.63 0.95 0.23 0.00 0.14 0.68 0.45 0.59 0.63 0.05 0.00 0.00 0.23 0.45 0.91 0.36 0.05 0.00 0.00 0.32 0.14 0.68 0.54 0.41 0.00 0.05 0.50 0.18 0.54 0.77 0.72 0.00 0.09 0.09 1.04 1.00 0.50 1.59 0.00 0.00 0.32 1.27 1.90 1.72 3.94 0.00 0.00 0.14 0.82 1.81 1.90 7.88 0.00 0.00 0.09 1.09 1.99 2.90 6.25 0.00 0.05 0.23 1.18 1.99 2.54 3.99 0.00 0.00 0.32 1.18 2.22 3.62 3.72 0.00 0.05 0.27 0.95 2.40 5.03 2.76 0.00 0.00 0.23 0.86 1.68 2.54 2.40 0.00 0.05 0.23 0.77 1.45 0.68 0.45 0.00 0.54 4.67 12.96 22.34 25.01 34.48
-WIND SPEED CLASSES CALM 1.0- 3.5 mph 3.6-7.5 mph 7.6-12.5 mph 12.6-18.5 mph 18.6.24.5 mph
>24.5 mph SPEED 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.68 0.27 0.00 0.00 0.00 0.00 0.00 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.36 0.27 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.27 0.09 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00
.0.23 0.23 0.09 0.00 0.00 0.00 0.00 0.05 0.27 0.09 0.00 0.00 0.00 0.00 0.14 0.50 0.14 0.00 0.00 0.00 0.00 0.32 0.36 0.05 0.00 0.00 0.00 0.00 0.23 0.14 0.14 0.00 0.00 0.00 0.00 0.27 0.59 0.45 0.27 0.00 0.00 0.00 0.68 0.45 0.32 0.27 0.00 0.00 0.05 1.13 2.17 0.14 0.45 0.00 0.00 0.05 0.54 0.63 0.32 0.36 0.00 0.00 0.00 2.49 3.76 1.09 0.54 0.00 0.00 0.00 1.54 0.50 0.54 0.32 0.00 0.00 0.05 0.91 2.08 1.54 1.68 0.00 0.00 0.00 1.22 0.54 0.50 0.27 0.00 0.00 0.09 0.77 0.41 1.63 1.09 0.00 0.00 0.00 2.27 0.77 0.50 0.09 0.00 0.00 0.00 1.68 1.40 0.41 0.23 10.97 13.32 5.62 4.40 0.00 0.00 0.00 2.45 0.91 0.18 0.00 0.00 0.00 0.00 1.54 0.45 0.18 0.00 0.00 0.00 0.00 1.72 0.86 0.18 0.00 0.00 0.00 0.00 1.72 0.72 0.09 0.00 0.00 0.00 0.00 0.59 1.04 0.36 0.00 0.00 0.00 0.00 0.82 1.00 0.27 0.00 0.00 0.00 0.00 0.95 1.27 0.45 0.09 0.00 0.00 0.00 1.68 1.18 0.91 0.54 0.00 0.00 0.05 2.95 3.81 1.00 1.36 0.00 0.00 0.05 4.21 4.94 1.86 1.50 0.00 0.00 0.05 3.99 3.44 2.45 2.40 0.00 0.00 0.09 4.17 1.50 2.58 1.63 0.00 0.00 0.00 6.52 2.72 1.18 0.63
LaSalle County Nuclear Station 375 ft. Wind Speed and Direction January-December, 2001 375Ft-33Ft Delta-T (F)
Number of Observations -
8752 Values are Percent Occurrence SPEED WIND DIRECTION CLASSES..................................
CLASS N
NNE NE ENE E
WNWW NiNW TOTAL
......... STABILITY CLASSES..........
EU HU SU N
. SS MS ES TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 EU NU 1SU N
35S MS ES EU MU 4SU
.N 7SS MS ES EU NU 8 SU
-N 1SS 2HS ES EU 1iU 3SU N
1SS 8MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.m00 0.50 0.43 0.15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 EU MU C SU A N LSS N MS 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 0.03 0.02 0.00 0.00 0.00 0.00 0.00 0.50 0.11 0.06 0.02 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 0.00 0.30 0.17 0.05 0.00 0.00 0.00 0.00 0.70 0.34 0.25 0.08 0.00 0.00 0.00 0.01 0.05 0.01 0.00 0.00 0.00 0.00 0.55 0.09 0.07 0.00 0.00 0.00 0.00 0.65 0.35 0.05 0.00 0.00 0.00 0.03 0.87 0.40 0.13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.02 0.01 0.00 0.00 0.00 0.00 0.32 0.16 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.02 0.02 0.00 0.00 0.00 0.00 0.31 0.15 0.07 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.02 0.01 0.01 0.00 0.00 0.00 0.30 0.05 0.08 0.00 0.00 0.00 0.00 0.70 0.35 0.10 0.05 0.00 0.00 0.00 0.80 0.43 0.14 0.09.
1.63 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.50 0.43 0.15 0.01 0.00 0.00 0.00 0.00 5.67 1.84 0.88 0.14 0.00 0.00 0.00 0.11 11.04 4.42 2.43 0.69 1.10 0.00 0.00 5.67 0.00. 0.00 0.00 0.00 0.00 0.00 0.02 0.03 0.07 0.02 0.00 0.02 0.00 0.00 1.84 0.00 0.00 0.01 0.01 0.24 12.60 7.59 4.04 1.63 0.88 0.00 0.00 0.00 0.03 0.05 0.01 0.00 0.00 0.00 0.00 0.45 0.15 0.05 0.00 0.00 0.00 0.00 0.86 0.24 0.14 0.02 0.00 0.00 0.00 1.02 0.38 0.16 0.03 0.14 0.00 0.00 0.00 0.05 0.02 0.01 0.00 0.00 0.00 0.00 0.51 0.07 0.05 0.00 0.00 0.00 0.02 1.26 0.31 0.07 0.03 0.00 0.00 0.01 0.61 0.32 0.13 0.01 8.52 0.00 0.00 0.00 0.09 0.02 0.01 0.00 0.00 0.00 0.00 0.27 0.15 0.07 0.00 0.00 0.00 0.00 0.65 0.24 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.17 0.10 0.02 0.00 0.00 0.00 0.00 0.39 0.26 0.06 0.00 0.00 0.00 0.00 1.27 0.74 0.03 0.00 0.11 0.00 0.00 0.00 0.02 0:02 0.01 0.00 0.00 0.00 0.00 0.18 0.09 0.06 0.00 0.00 0.00 0.00 0.51 0.13 0.10 0.00 0.00 0.00 0.01 0.48 0.65 0.22 0.00 11.04 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.31 0.27 0.11 0.05 0.08 0.07 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.38 0.42 0.15 0.24 0.23 0.25 0.00 0.03 0.00 0.00 0.00 0.51 0.40 0.25 0.00 0.00 0.00 0.00 0.02 0.03 0.02 0.00 0.00 0.00 0.00 0.43 0.14 0.06 0.03 0.00 0.00 0.00 0.66 0.29 0.22 0.09 4.42 0.69 0.00 0.00 0.00 0.61 0.49 0.38 0.21 2.43 0.00 0.00 0.01 0.57 0.18 0.24 0.08 0.00 0.00 0.05 0.63 0.40 0.46 0.23 0.01 0.00 0.00 0.02 0.78 0.54 0.45 0.18 7.59 0.00 0.00 0.00 0.72 0.33 0.15 0.08 0.00 0.00 0.06 1.33 0.74 0.33 0.15 4.04 0.00 0.00 0.00 0.69 0.42 0.18 0.09 0.00 0.00 0.00 1.04 0.73 0.33 0.14 0.24 12.60 0.00 0.00 0.00 0.43 0.17 0.06 0.02 0.00 0.00 0.05 0.91 0.31 0.17 0.02 0.00 0.00 0.05 0.96 0.39 0.29 0.17 0.00 0.00 0.00 0.35 0.08 0.03 0.00 0.00 0.00 0.03 0.97 0.27 0.23 0.10 0.00 0.01 0.01 0.99 0.48 0.33 0.18 0.00 0.00 0.00 0.29 0.23 0.21 0.06 0.00 0.00 0.00 0.43 0.26 0.23 0.18 18.69 26.12
LaSalle County Nuclear Station 375 ft. Wind Speed and Direction January-December, 2001 375Ft-33Ft Delta-T (F)
SPEED WIND DIRECTION CLASSES..................................
CLASS N
NNE NE ENE E
SSW SW WSW W WNW NW NNW TOTAL 0.00 0.00 0.00 0.16 0.03 0.00 0.00 0.00 0.00 0.00 0.07 0.01 0.00 0.00 0.00 0.01 0.05 0.93 0.32 0.01 0.00 0.00 0.00 0.00 0.33 0.03 0.00 0.00 0.00 0.00 0.00 0.89 0.32 0.00 0.00 0.00 0.00 0.00 0.10 0.06 0.00 0.00 0.00 0.00 0.05 0.35 0.29 0.08 0.00 0.00 0.00 0.00 0.14 0.18 0.05 0.00 0.00 0.00 0.00 0.32 0.37 0.16 0.00 0.00 0.00 0.00 0.06 0.31 0.10 0.00 0.00 0.00 0.00 0.14 0.30 0.22 0.01 0.00 0.00 0.00 0.18 0.35 0.10 0.00 0.00 0.00 0.00 0.35 0.23 0.15 0.11 0.00 0.00 0.00 0.10 0.39 0.17 0.15 0.00 0.00 0.03 0.49 0.51 0.32 0.22 0.00 0.00 0.01 0.57 1.17 0.29 0.34 0.00 0.00 0.08 0.71 0.54 0.41 0.16 0.00 0.00 0.05 1.25 2.22 0.74 0.49 0.00 0.00 0.10 0.93 0.54 0.47 0.14 0.00 0.03 0.25 0.81 1.11 0.72 0.65 0.00 0.00 0.00 0.89 0.41 0.42 0.17 0.00 0.02 0.03 0.57 0.35 0.61 0.61 0.00 0.00 0.01 1.20 0.64 0.39 0.10 0.00 0.00 0.00 1.02 0.82 0.32 0.14 0.00 0.00 0.01 1.58 0.93 0.48 0.10 0.00 0.00 0.00 0.80 0.99 0.16 0.01 0.00 0.00 0.02 1.52 0.66 0.23 0.08 0.00 0.00 0.00 1.27 0.34 0.03 0.05 0.00 0.00 0.00 0.57 0.25 0.17 0.09 0.00 0.00 0.00 0.25 0.03 0.00 0.00 0.00 0.00 0.01 0.35 11.55 6.57 3.55 1.23 0.00 0.00 0.06 0.37 7.69 8.46 3.29 2.43
......... STABILITY CLASSES..........
EU MU SU N
SS MS ES TOTAL 0.01 0.35 11.55 6.57 3.55 1.23 23.27 0.06 0.37 EU 1I4U 9 SU
> N 2SS 4MS ES 0.00 0.00 0.00 0.53 0.24 0.05 0.05 0.00 0.00 0.02 0.17 0.08 0.00 0.00 2.43 22.29 TOT 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 6.14 100.00 Wind Direction by Stability N
NNE NE ENE E
SSW SW WSW 0.00 0.00 0.02 3.05 1.13 0.40 0.10 0.00 0.00 0.03 2.65 0.77 0.25 0.05 0.00 0.01 0.08 3.34 1.25 0.26 0.00 0.00 0.00 0.00 3.28 1.53 0.11 0.00 0.00 0.00 0.06 1.54 1.50 0.42 0.00 0.00 0.00 0.00 1.61 1.31 0.69 0.00 0.00 0.00 0.00 1.34 1.14 0.83 0.07 0.00 0.00 0.00 1.63 1.19 0.87 0.53 0.00 0.00 0.05 2.79 2.63 1.28 0.89 0.00 0.00 0.18 3.69 3.47 1.91 0.98 0.00 0.03 0.38 3.54 2.72 1.93 1.05 0.00 0.02 0.13 3.79 1.70 1.54 0.99 W
WNW W
mNW TOTAL 0.00 0.01 0.06 4.57 2.32 1.33 0.53 0.00 0.00 0.07 4.75 3.18 1.15 0.34 0.00 0.00 0.02 4.84 2.33" 0.87 0.37 0.00 0.00 0.00 2.63 1.14 0.50 0.24 0.00 0.08 1.07 49.05 29.31 14.35 6.14
-STABILITY CLASSES Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N
NNE NE ENE E
SSW SW WSW W WNW NW NN TOTAL 0.00 0.09 0.64 1.26 1.59 0.86 0.00 0.08 0.63 1.69 1.07 0.19 0.00 0.07 0.71 1.05 1.43 1.31 0.00 0.13 0.49 0.89 2.05 1.21 0.00 0.02 0.30 0.71 1.36 0.77 0.00 0.06 0.33 0.74 1.17 0.85 0.00 0.05 0.50 0.75 0.78 0.66 0.00 0.07 0.43 0.95 1.11 0.85 0.00 0.08 0.66 1.26 1.68 1.58 0.00 0.06 0.70 1.09 1.76 1.90 0.00 0.06 0.51 1.37 1.97 2.17 0.00 0.09 0.69 1.46 1.85 1.90 0.00 0.08 0.47 1.61 2.01 2.34 0.00 0.05 0.50 1.28 2.61 3.10 0.00 0.07 0.54 1.38 2.24 2.51 0.00 0.06 0.42 1.20 1.46 1.09 0.00 1.10 8.52 18.69 26.12 23.27 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
-WIND SPEED CLASSES CALM 1.0- 3.5 mh 3.6-7.5 mph 7.6-12.5 mph 12.6-18.5 mph 18.6-24.5 mqph
>24.5 mph 7.69 8.46 3.29
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (2001)
APPENDIX A OFFSITE DOSE CALCULATION MANUAL
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 1 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 / 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 remaining 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 epeFatain. This determination shall include, where possible, comparison of the channel indication and /-GF status with to other indications aA4 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 and4 or, interlock, display, and trip functions, and channel failure trips. The following is being deleted. Biddable hanneos the injectioG Of a fuiRGfieRs.
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%
' -.'rac hall not be applied to Operability Action statements. The bases, to Technical Specification 4.0.2 provide clarificatien* to thi require.ment. 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, trai, 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 eG seal water, lubrication, Gr-and other auxiliary equipment that are required for the system, subsystem, #ain 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: Eac h-.
- f c
- ;equ;mont.-hal be pe~forMed within the specified time interwal with th maximnum allowlable extension not to eXceed 25% of the fr.que...
int..al. The 25% variance shall not be applied to Operabili ci statement. The hbIase to T
.0pr'de clarification tto this requiemen.These frequency notatios do not apply to the REMP (Section 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 SWITCH POSITION AVERAGE RX COOLANT TEMP
( Degrees F)
Power Operation Run N/A Startup Refuel (a) or Startup / Hot N/A Standby Hot Shutdown (a)
Shutdown
>200 Cold Shutdown (a)
Shutdown
< or = 200 Refueling (b)
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.
1 2
3 4
5
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 3/23/87.)"
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. "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: If the drywell is purged in accordance with the Tec,-hni,-al pe, ation
.nd ODCM 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 pecification a.nd. 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: 12.4.6.1B.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 microepiescuries / second after decay of 30 minutes.
Applicability: Operational CoRditions MODE 1,2 ai*d*3.
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 microGGptescuries / 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-ii;at least START-UP With the main steam ioato valu.es closed within; theQ netw 6
-he ',': 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
==
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 1 did not exist.
Section: 12.6.1
==
Description:==
The submittal date of the Annual Radiological Environmental Operating Report changes from May 1 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 1 of each year.
Reason: Conforms with ITS 5.6.3.
Section: 12.6.2.a
==
Description:==
Delete the following statement: The pe-Fid of tho first repo.rt shall begin wAith the date of initial criticality.
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
==
Description:==
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 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.
Reason: Clarification.
Section: 12.6.3.2.a
==
Description:==
Replace the wording "Specification 6.5.B" 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).
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 LASALLE ANNEX INDEX CHAPTER 10 Revision 3 P:\\procupgd\\approved\\odcmxislOr3.doc 10-i Revision 3 May 2001
LASALLE Revision 3 May 2001 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT 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 Limits 5
- 3.
Release Mixture 6
- 4.
Conversion Factors 6
- 5.
HVAC Flow Rates 6
- 4.
Allocation of Effluents from Common Release Points 6
- 5.
Dose Projections 6
10.2 LIQUID RELEASES 7
- 1.
System Description
7
- 1.
Radwaste Discharge Tanks 7
- 2.
Cooling Pond Blowdown 7
- 2.
Radiation Monitors 7
- 1.
Liquid Radwaste Effluent Monitor 7
- 2.
Service Water Effluent Monitors 7
- 3.
RHR Heat Exchanger Cooling Water Effluent Monitors 7
P:\\procupgd\\approved\\odcm\\IsI 0r3.doG 10-ii
LASALLE Revision 3 May 2001 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT AND MONITORING Table of Contents (Cont'd)
NUMBER PAGE
- 3.
Alarm and Trip Setpoints...........................................................................................
7
- 1.
Setpoint Calculations....................................................................................
7
- 1.
Liquid 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.
- 4.
- 5.
6.
Release Limits...............................................................................................
9 Release Mixture............................................................................................
9 Conversion Factors...........................................................................................
9 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 PAprocupgd\\approved\\odcm\\lsl 0r3.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 OF FIGURES NUMBER PAGE 10-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram.................... 10-12 10-2 Simplified Liquid Radwaste Processing Diagram..................................................
10-14 10-3 Simplified Liquid Effluent Flow Diagram..............................................................
10-15 10-4 Simplified Solid Radwaste Processing Diagram...................................................
10-16 P:\\procupgd\\approved\\odcm\\Isl 0r3.doc 1 0-iv
LASALLE Revision 3 May 2001 CHAPTER 10 RADIOACTIVE EFFLUENT TREA 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\\approved\\odcm\\lslOr3.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 radioiodine 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 jtCVcc png* and the high range channel replaces the mid-range channel at a concentration of 10 RUCi/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 ttCi/cc png the mid/high-range samplers are brought on line, and at a concentration of 0.1 g.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 11.5.2.2.1.
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 lxCi/cc png and the high range channel replaces the mid-range channel at a concentration of 10 IACi/cc png.
- To facilitate use of the wide range gas monitors on the Station Vent Stack and Standby Gas Treatment System Stack in post-accident dose assessment, the output of each is expressed in units of pseudo noble gas (png) activity. Pseudo noble gas is a fictitious radionuclide defined to have emission characteristics representative of a post-accident noble gas mix. Upon decay, a pseudo noble gas nuclide emits one gamma ray with energy 0.8 MeV and one beta particle with endpoint energy 1.68 MeV and average energy 0.56 MeV.
P:\\procupgd\\approved\\odcm\\ls 10r3.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 jxCi/cc png the mid/high-range samplers are brought on-line, and at a concentration of 0.1 p.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 11.5.2.2.2.
10.1.2.3 Reactor Building Ventilation Monitors Monitors 1 (2)D1 8-NOO9 continuously monitor the effluent from the Unit 1(2) reactor building. On high alarm, the monitors automatically initiate the following actions:
A.
Shutdown and isolation of the reactor building vent system B.
Startup of the standby gas treatment system C.
Isolation of primary containment purge and vent lines Pertinent information on these monitors is provided in LaSalle UFSAR Section 11.5.2.1.1.
10.1.2.4 Condenser Air Ejector Monitors Monitors 1(2)D18-N002/N012 (pre-treatment) and 1 (2)D18-N903A/B (post-treatment) continuously monitor gross gamma activity downstream of the steam jet air ejector and prior to release to the main stack.
On "high-high-high" alarm monitor 1 (2)D18-N903NB 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:\\procupgd\\approved\\odcm\\lslor3.doc 10-3
LASALLE Revision 3 May 2001 10.1.3 10.1.3.1 10.1.3.1.1 10.1.3.1.2 10.1.3.1.3 P\\procupgd\\approved\\odcm\\s1 10r3.doc 10-4 Alarm and Trip Setpoints Setpoint Calculations Reactor Building Vent Effluent Monitor The setpoint for the reactor building vent effluent monitor is established at 10 mR/hr.
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 pCi/sec per MW-th _ 3.4E+05 giCi/sec per Technical Specification 3.11.2.2.
Post-Treatment Monitor The off-gas isolation setpoint is conservatively set at or below one-half the release limit calculated using 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 /Roc]+Fo.
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
[gCi/sec of png]
The actual high alarm setpoint of the Station Vent Stack wide range gas monitor in units of ptCi/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 giCi/sec of png.
E Efficiency of the Off-Gas Post Treatment Monitor
[cps/(jCVsec of off gas mix)]
Rpng Response of the Station Vent Stack WRGM to Pseudo Noble Gas
[cpm per p.CVcc of pseudo noble gas]
RoG Response of the Station Vent Stack WRGM to Off Gas
[cpm per gtCi/cc of off gas]
FoG Maximum Off-Gas Flow Rate
[cc/sec]
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
LASALLE Revision 3 May 2001 units of jCi/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.tCi/sec 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 gCVsec 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 gCVsec 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 Qt. is found by solving Equations 10-3 and 10-4.
(1.11) Qts X{fISi }< 500 mrem/yr t1o-3)
Q, XI{ Lif(X /Q), exp( -A i R / 3600 U, )t + (1.11)(fi) Si ) < 3000 mrem lyr 0'1)
The summations are over noble gas radionuclides i.
fi Fractional Radionuclide Composition:
The release rate of noble gas radionuclide i divided by the total release rate of all noble gas radionuclides.
Qts Total Allowed Release Rate, Stack
[p.CVsec of ODCM mix]
Release The total allowed release rate of all noble gas radionuclides released as stack releases in units of RCi/sec of the mix specified in section 10.1.3.3.
t exp (-XiR/3600 U.) is conservatively set equal to 1.0 for purposes of determining setpoints.
The remaining parameters in Equation 10-3 have the same definitions as in Equation A-8 of Appendix A. The remaining parameters in Equation 10-4 have the same definition as in Equation A-9 of Appendix A.
Equation 10-3 is based on Equation A-8 of Appendix A and the RETS restriction on whole body dose rate (500 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\\approved\\odcm\\lslOr3.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 Flow Rates The main stack flow rate is obtained from either the process computer or Monitor RM-23.
The SGTS flow rate is obtained from either the process computer or chart recorders in the main control room.
10.1.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the main chimney are comprised of contributions from both units. Under normal operating conditions, it is difficult to allocate the radioactivity between units due to fuel performance, in-plant leakage, power history, and other variables.
Consequently, no allocation is normally made between the units. Instead, the entire release is treated as a single source.
10.1.5 Dose Projections Because the gaseous releases are continuous, the doses are routinely calculated in accordance with the RETS.
P:\\procupgdcapproved\\odcmls1 0r3.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 OD18-K907 monitors all releases from the release tanks. On hi-hi alarm the monitor automatically initiates closure of valves OWL067 and trips the radwaste discharge pump to terminate the release.
Pertinent information on the monitor and associated control devices is provided in LaSalle UFSAR Section 11.5.2.3.3.
10.2.2.2 Service Water Effluent Monitors Monitors 1/(2)D18-K912 continuously monitor the service water effluent. On high alarm service water discharge may be terminated manually. No control device is initiated by these monitors.
Pertinent information on these monitors is provided in LaSalle UFSAR 11.5.2.3.2.
10.2.2.3 RHR Heat Exchanger Cooling Water Effluent Monitors Instrument channels 1/(2)D18-N906/8 continuously monitor the RHR heat exchanger coooling 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:\\procupgd\\approved\\odcm1sl 10r3.doc 10-7
LASALLE Revision 3 May 2001 Liquid Radwaste Effluent Monitor The monitor setpoint is found by solving equation 10-5 for the total isotopic activity.
P _< Kx[C
/
(C7 /10xDWCi)] x [(Fd + Fmax)/Frmax]
P Release Setpoint K
[E (Ki x Q x Wi)/I CTi]
Ki Counting efficiency for radionuclide i (10-5)
[cpm]
[cpm/ClCVml]
[cpmnpCVml]
Wi ci Weighting Factor Concentration of radionuclide i in the release tank.
Fj=
Maximum Release Tank Discharge Flow Rate
[c The maximum flow rate is 45 gpm.
DWC Derived Water Concentration 1C of radionuclide i The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 1 OCFR20.1001-2402.
10 Multiplier associated with the limits specified in 12.3.1.A.
Fd Dilution Flow Service Water Effluent Monitors The monitor setpoint is established at two times the background count rate (not to exceed 10000 cpm).
RHR Heat Exchanger Cooling Water Monitors The monitor setpoint is established at two times the background count rate (not to exceed 10000 cpm).
P:\\procupgd\\approved\\odcm\\Is 10r3.doc 10-8 10.2.3.1.1
[!.CVml]
pm]
Vml]
10.2.3.1.2 10.2.3.1.3
[gpm]
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 [Fd/II (Q/1OxDWq)]
(10-6)
The summation is over radionuclides i.
0.1 Reduction factor for conservatism.
Frmx Maximum Permitted Discharge Flow Rate
[gpm]
The maximum permitted flow rate from the radwaste discharge tank.
Fd Dilution Flow
[gpm]
Ci Concentration of Radionuclide i in the Release Tank
[gCVmL]
The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank.
DWOi Maximum Permissible Concentration of Radionuclide i
[RCi/ml]
The concentration of radionuclide i given in Appendix B, Table 2, Column 2 to 1 OCFR20.1001-2402.
10 Multiplier associated with the limits specified in 12.3.1.A.
MF Multiplication Factor Frmx < 0.5; MF = 3 0.5 < Frmax < 5; MF = 5 5 < Frmax; MF = 7.5 10.2.3.2.2 Recommended Release Tank Flow Rate.
Frrec =Fr iax X MF.....
(10-7)
F rr.
recommended discharge flow rate (gpm)
Frmax maximum permitted discharge flow rate (gpm)
MF multiplication factor.
P\\procupgd\\approved\\odcm\\IsI 0r3.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 WASTE/PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured.
Figure 10-4 is a simplified diagram of solid radwaste processing.
P:\\procupgd\\approved\\odcm\\lslOr3.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 1.1E-2 Xe-135m 3.4E-2 Xe-135 2.9E-2 Xe-1 37 2.OE-1 Xe-138 1.2E-1 P:\\procupgd\\approved\\odcm\\lslOr3.doG 10-11
P:\\procupgd\\approved\\odcm\\lsl 0r3.doc LASALLE Revision 3 May 2001 OFFSITE DOSE CALCULATION MANUAL LASAL.E COUNfY STATION FIGURE 10-1 SIMPLFIED GASEOUS RAOWASTE AND GASEOUS EFFLUENT FLOW DIAGRAM (SHEET I OF 2) 10-12
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OFFSITE DOSE CALCMAION MANUAL LASALLE COUNTY STATION.
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p:\\procupgd\\approved\\odcm\\Is 1 r3.doc 11-i LASALLE CHAPTER 11 LaSalle Annex Index Revision 3 Revision 3 May 2001
LASALLE Revision 3 May 2001 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE OF CONTENTS ER TITLE PAGE Radiological Environmental Monitoring Program 11-1 LIST OF TABLES ER TITLE PAGE Radiological Environmental Monitoring Program 11-2 LIST OF FIGURES NUMBER 11-1 11-2 11-3 TITLE Fixed Air Sampling Sites and Outer Ring TLD Locations Inner Ring TLD Locations Ingestion and Waterborne Exposure Pathway Sample Locations PAGE 11-9 11-10 11-11 p:\\procupgd\\approved\\odcm\\Isi 1 r3.doc 11-ii CHAPT 11 NUMBE 11-1
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:\\procupgd\\approved\\odcm\\ls1 1 r3.doc 11-1
LASALLE Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway and/or Sample Sample or Monitorinq Location
- 1. Airborne Radioiodine and Particulates
- a.
Indicators-Near Field L-01, Nearsite No. 1, 1.5 mi NNW L-03, Onsite No. 3, 1.0 mi ENE L-05, Onsite No. 5, 0.3 mi ESE L-06, Nearsite No. 6, 0.4 mi WSW (2.4 km R)
(1.6 km D)
(0.5 km F)
(0.6 km M)
Sampling or Collection Frequency Continuous sampler operation with particulate sample collection weekly, or more frequently if required by dust loading, and radioiodine canister collection biweekly.
Type and Frequency of Analysis Radioiodine Canisters:
1-131 analysis biweekly on near field and control samples'.
Particulate Sampler:
Gross beta analysis followin~g weekly filter change and gamma isotopic analysis 3 quarterly on composite filters by location on near field and control samples.'
- b.
Indicators-Far Field L-04, Rte 170, 3.2 mi E L-07, Seneca, 5.2 mi NNE L-08, Marseilles, 6.0 mi NNW L-11, Ransom, 6.0 mi S
- c.
Controls L-10, Streator, 13.5 mi SW (5.1 km E)
(8.4 km B)
(9.7 km R)
(9.7 km J)
(21.7 km L) p:\\procupgd\\approved\\odcm\\Is 1 r3.doc 11-2 Revision 3 May 2001
LASALLE Table 11-1 (Cont'd)
Radiological Environmental Monitoring Program Exposure Pathway and/or Sample
- 2.
Direct Radiation Sample or Monitoring Location
- a. Indicators-Inner Ring L-101-1, 0.5 mi N L-101-2, 0.5 mi N L-102-1, 0.6 mi NNE L-102-2, 0.6 mi NNE L-1 03-1, 0.7 mi NE L-103-2, 0.7 mi NE L-104-1, 0.8 mi ENE L-104-2, 0.8 mi ENE L-105-1, 0.7 mi E L-105-2, 0.7 mi E L-106-1, 1.4 mi ESE L-106-2, 1.4 mi ESE L-107-1, 0.8 mi SE L-107-2, 0.8 mi SE L-108-1, 0.5 mi SSE L-108-2, 0.5 mi SSE L-109-1, 0.6 mi S L-109-2, 0.6 mi S L-110-1, 0.6 mi SSW L-110-2, 0.6 mi SSW L-111b-1, 0.8 mi SW L-11 b-2, 0.8 mi SW L-112-1, 0.9 miWSW L-112-2, 0.9 mi WSW L-113a-1, 0.8 mi W L-113a-2, 0.8 mi W L-114-1, 0.9 miWNW L-114-2, 0.9 mi WNW L-115-1, 0.7 mi NW L-115-2, 0.7 mi NW L-116-1, 0.6 mi NNW L-116-2, 0.6 mi NNW Sampling or Collection Frequency (0.8 km A)
(0.8 km A)
(1.0 km B)
(1.0 km B)
(1.1 km i)
(1.1 km C)
(1.3 km D)
(1.3 km D)
(1.1 km E)
(1.1 km E)
(2.2 km F)
(2.2 km F)
(1.3 km G)
(1.3 km G)
(0.8 km H)
(0.8 km H)
(1.0 km J)
(1.0 km J)
(1.0 km.K)
(1.0 km K)
(1.3 km L)
(1.3 km L)
(1.4 km M)
(1.4 km M)
(1.3 km N)
(1.3 km N)
(1.4 km P)
(1.4 km P)
(1.1 km Q)
(1.1 km Q)
(1.0 km R)
(1.0 km R)
Quarterly Type and Frequency of Analysis Gamma dose on each TLD quarterly.
p:\\procupgd\\approved\\odcm\\Is 1 r3.doc 11-3 Revision 3 May 2001
LASALLE Table 11-1 (Cont'd)
Radiological Environmental Monitoring Program Exposure Pathway and/or Sample
- 2. Direct Radiation (Cont'd)
Sample or Monitoring Location
- b. Indicators-Outer Ring L-201-3, 4.0 mi N L-201-4, 4.0 mi N L-202-3, 3.6 mi NNE L-202-4, 3.6 mi NNE L-203-1, 4.0 mi NE L-203-2, 4.0 mi NE L-204-1, 3.2 mi ENE L-204-2, 3.2 mi ENE L-205-1, 3.2 mi ESE L-205-2, 3.2 mi ESE L-205-3, 5.1 mi E L-205-4, 5.1 mi E L-206-1, 4.3 mi SE L-206-2, 4.3 mi SE L-207-1, 4.5 mi SSE L-207-2, 4.5 mi SSE L-208-1, 4.5 mi S L-208-2, 4.5 mi S L-209-1, 4.0 mi SSW L-209-2, 4.0 mi SSW L-210-1, 3.3 mi SW L-210-2, 3.3 mi SW L-211-1, 4.5 mi WSW L-211-2, 4.5 mi WSW L-212-1, 4.0 miWSW L-212-2, 4.0 mi WSW L-213-3, 4.9 mi W L-213-4, 4.9 mi W L-214-3, 5.1 mi WNW L-214-4, 5.1 mi WNW L-215-3, 5.0 mi NW L-215-4, 5.0 mi NW L-216-3, 5.0 mi NNW L-216-4, 5.0 mi NNW Sampling or Collection Frequency Type and Frequency of Analysis (6.4 km A)
(6.4 km A)
(5.8 km B)
(5.8 km B)
(6.4 km C)
(6.4 km C)
(5.2 km D)
(5.2 km D)
(5.2 km F)
(5.2 km F)
(8.2 km E)
(8.2 km E)
(6.9 km G)
(6.9 km G)
(7.2 km H)
(7.2 km H)
(7.2 km J)
(7.2 km J)
(6.4 km K)
(6.4 km K)
(5.3 km L)
(5.3 km L)
(7.2 km M)
(7.2 km M)
(6.4 km M)
(6.4 km M)
(7.9 km N)
(7.9 km N)
(8.2 km P)
(8.2 km P)
(8.0 km Q)
(8.0 km Q)
(8.0 km R)
(8.0 km R)
).: piupyuiapprovei~odomms I rI.Qoc 11-4 Revision 3 May 2001 4,\\
LASALLE Table 11-1 (Cont'd)
Radiological Environmental Monitorina Proaram Exposure Pathway and/or Sample
- 2. Direct Radiation (Cont'd)
Sample or Monitoring Location
- c. Other Indicators 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.
Sampling or Collection Frequency Type and Frequency of Analysis p:\\procupgd\\approved\\odcm\\Isj 1 r3.doc 11-5 Revision 3 May 2001
LASALLE Revision 3 Table 11-1 (Cont'd)
May 2001 Radiological Environmental Monitoring Program Exposure Pathway and/or Sample
- 3. Waterborne a.. Ground/Well
- b. Drinking Water
- c.
Surface Water
- d.
Control
- e. Sediments Sample or Monitoring Location
- a. Indicators Sampling or Collection Frequency Quarterly L-27, LSCS Onsite Well at Station L-28, Marseilles Well, 7.0 mi NW (11.3 km Q)
There is no drinking water pathway within 6.2 mi (10 kin) downstream of station.
Weekly grab sample (8.4 km R)
Weekly grab sample Semiannually
- a. Indicators Type and Frequency of Analysis Gamma isotopic3 and tritium analysis quarterly.
Gross beta and gamma isotopic analysis on monthly composite; tritium analysis on quarterly composite.
Gross beta and gamma isotopic analysis on monthly composite; tritium analysis on quarterly composite.
Gamma isotopic analysis 3 semiannually.
L-40, Illinois River downstream, 5.2 mi NNW (8.4 km R)
L-41, Illinois River downstream 4.6 mi NNW (7.4 km A) p:\\p rocupgd\\approved\\odcm\\Is 1I r3.doo 11-6
LASALLE Revision 3 Table 11-1 (Cont'd)
May 2001 Radiological Environmental Monitoring Program Exposure Pathway and/or Sample Sample or Monitoring Location Sampling or Collection Frequency Type and Frequency of Analysis
- 4.
Ingestion
- a. Indicators At the time of this revision, there are no dairies within 6.2 miles which consistently produce milk.
- b. Controls L-42, Biros Dairy, 14.2 mi E (22.9 km E)
Biweekly: May through October; monthly:
November through April Two times annually Gamma isotopic 3 and 1-131 analysis 4 biweekly May through October, monthly November through April.
Gamma isotopic analysis 3 on edible portions of each
- a. Indicators Two samples from each of the four major quadrants within 6.2 miles of the station, if available.
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 18.6 miles of the station, if available.
Annually Gamma isotopic analysis 3 each sample.
p:\\procupgd\\approved\\odcmxls 11 rdoc 11-7
- a.
Wilk
- b.
Fish
- c.
Fo.od Products (6.9 km B)
LASALLE Revision 3 Table 11-1 (Cont'd)
May 2001 Radiological Environmental Monitoring Program Far field samples are analyzed when near field results are inconsistent with previous measurements and radioactivity is confirmed as having its origin in airborne effluents released from the station, or at the discretion of the Radiation Protection Director.
2 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
3 Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station.
4 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide.
p:\\procupgdfapproved&odcm\\js1 I r3.doC 11-8
LASALLE Revision 3 May 2001 L-212.4m 21134 60
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LASALLE Revision 3 May 2001 Muemifes U.S.,
411
- "ff FSE CALCULATION MANUAL
________L__SALLE COUNTY STATION r
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Fish Sediment water INGESTION AND WATERBORNE EXPOSURE PATHWAY SAMPLE LOCATtONS
LASALLE LASALLE ANNEX INDEX CHAPTER 12 Revision 3 P:\\procupgd\\approvedcodcm\\s12r3 12-i Revision 3 May 2001 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.
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.
Liquid 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 Limits for Members of the Public 12-45 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12-46
- 1.
Monitoring Program 12-46
- 2.
Land Use Census
.12-59
- 3.
Interlaboratory Comparison Program 12-60 12.6 REPORTING REQUIREMENTS 12-61
- 1.
Annual Radiological Environmental Operating Report 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:\\procupgd\\approvecdodcm\\s1 2r3 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 Liquid Waste 12-20 12.3.1-2 Radioactive Liquid Waste Sampling and Analysis Program 12-21 12.4.1-1 Radioactive Gaseous Waste Sampling and Analysis Program 12-30 12.5-1 Radiological Environmental Monitoring Program 12-49 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\\approved\\odcm\\s12r3 12-iii