ML031220663

Radioactive Effluent Release Report, Summation of All Releases Through Figure B-4

ML031220663
Person / Time
Site:	Braidwood
Issue date:	04/25/2003
From:	Vonsuskil J Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Bw/030039
Download: ML031220663 (234)

Text

Braidwood Nuclear Station 2002 Radioactive Effluent Release Report

RADIOACTIVE EFFLUENT RELEASE REPORT Supplemental Information January - December 2002 Facility. BRAIDWOOD NUCLEAR POWER STATION Licensee EXELON GENERATION COMPANY, LLC

1. Regulatory Limits a For Noble Gases Dose Rate

1) Less than 500 mrem/year to the whole body.

2) Less than 3000 mrem/year to the skin.

Dose Gamma Radiation

1) Less than or equal to 5 mrad/quarter.

2) Less than or equal to 10 mrad/year.

Beta Radiation

1) Less than or equal to 10 mrad/quarter.

2) Less than or equal to 20 mrad/year.

b ,c. For lodine-1 31, for lodine-1 33, and for all radionuclides in particulate form with half-lives greater than 8 days.

Dose Rate

1) Less than 1500 mrem/year.

Dose

1) Less than or equal to 7.5 mrem/quarter.

2) Less than or equal to 15 mrem/year.

d For Liquid

1) Less than or equal to 1.5 mrem to the whole body during any calendar quarter.

2) Less than or equal to 5 mrem to any organ during any calendar quarter.

3) Less than or equal to 3 mrem to the whole body during any calendar year.

4) Less than or equal to 10 mrem to any organ during any calendar year.

p \depts\zd84g\environsgroup\2002eff doc

2. Maximum Permissible Concentration a., b ,c., For fission and activation gases, iodines, and particulates with half-lives greater than 8 days, allowable release limits are calculated by solving equations 10.1 and 10.2 from the Offsite Dose Calculation Manual.

d. For liquid effluents, allowable release limits are calculated by solving equations 10.3 and 10.4 from the Offsite Dose Calculation Manual.

3. Average Energy This item is not applicable. Release rates are calculated using an isotopic mix rather than average energy.

4. Measurements and Approximations of Total Radioactivity a Fission and Activation Gases, lodines, and Particulates Containment batch releases are analyzed for noble gas and tritium before being discharged by gamma isotopic and scintillation, respectively. Gaseous decay tanks are analyzed for noble gas before being discharged by gamma isotopic. Released activity is normally calculated using volume of release, which is determined by change in tank or containment pressure.

The Auxiliary Building ventilation exhaust system is continually monitored for iodines and particulates. These samples are pulled every 7 days and analyzed by gamma isotopic. The particulate samples are also analyzed quarterly for gross alpha and Sr-89/90.

Noble gas and tritium grab samples are pulled and analyzed weekly by gamma isotopic and scintillation, respectively. The average flow at the release points are used to calculate the curies released.

b. Liquid Effluents The liquid release tanks are analyzed before discharge by gamma isotopic and for tritium. A representative portion of this sample is saved This is composited, every 31 days, with other discharges that occurred and is analyzed for tritium and gross alpha. The batch composites are composited quarterly and sent to a vendor for Sr-89/90 and Fe-55 analysis Circulating Water Blowdown, Condensate Polisher Sump and Waste Water Treatment are analyzed weekly by gamma isotopic and for tritium. These weekly samples are composited quarterly and sent to a vendor for Sr-89/90 and Fe-55 analysis. However, the June 2002 monthly composite sample of Circulating Water Blowdown did not include a weekly sample that had been inadvertently prematurely disposed. This also affected the quarterly composite for second quarter 2002. This issue is documented in the Braidwood Corrective Action Program as CR #114419 The tank volumes and activities are used to calculate the curies released for the liquid release tanks. The total volume of water released and the activity is used to calculate the diluted activity released at the discharge point from batch discharges.

c Less than the lower limit of detection (<LLD).

Samples are analyzed such that the Offsite Dose Calculation Manual (ODCM) LLD requirements are met. When a nuclide is not detected during the quarter then <LLD is reported.

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BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 GAS RELEASES UNIT 1 (Docket Number 50-456)

SUMMATION OF ALL RELEASES Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission and Activation Gas Releases

. Total ReleaseActivity l Ci l 7.59E-02 l 1.71E-01 l 8.03E-02 l 9.29E-02 l 4.20E-O1

12. Average Release Rate uCt/sec 9.76E-03 2.17E-02 1.01 E-02 1.17E-02 1.33E-02 B. Iodine Releases

11. Total 1-131 Activity l Ci <LLD I 8.82E-07 l <LLD 1.05E-06 1.93E-06

12. Average Release Rate uCi/sec <LLD 1.12E-07 <LLD 1.32E-07 6.13E-08 C. Particulate (> 8 day half-life) Releases

1. Gross Activity i LLD 1.03E-06 <LLD <LLD 1E

2. Average Release Rate uCi/sec <LLD 1.31 E-07 <LLD <LLD 3 27E-08

3. Gross Alpha Activity Ci <LLD <<LL LL<LLD <LLD D. Tritium Releases 1I.Total Release Activity l Ci l 4.71E-01 I 7.51E-01 I 7.61E-01 2.37E+00 l 4.35E+00O 12.Average Release Rate I uCVsec I 6.06E-02 I 9.55E-02 I 9.57E-02 I 2.98E-01 I 1.38E-01l E. Sum of Iodine, Particulate (> 8 day half-life),

and Tritium Releases.

1. Total Release Activity Cl 4.71E-01 I 7.51E-01 I 7.61E-01 I 2.37E+00 I 4.35E+00 Note LLD Values are included in Appendix A of this report Note % Limit Values are included in Appendix B of this report p:\depts\zd84g\environsgroup\2002eff.doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 GAS RELEASES UNIT 1 (Docket Number 50-456)

BATCH MODE I Units I 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total A. Particulate (> 8 day half-life) Releases Cr-51 Ci ****

Mn-54 Ci lt_

Co-57 Ci * * * *

• Co-58 Ci *****

Fe-59 Ci Co-60 Ci * * * *

• Zn-65 Ci * * * *

• Sr-89 Ci * * * *

• Sr-90 Ci * * * *

• Mo-99 Ci

• Sn-117m Ci * = =

Cs-1 34 Ci Cs-1 37 Ci ***

• Ba\La-140 Ci ****

Ce-1 41 Ci ****

Ce-144 Ci

• Value reported as Continuous Mode B. Tritium Releases l1. Total Release Activity Ci I 4.71E-01 7.51E-01 7.61E-01 2.37E+00 4.35E+00 C. Fission and Activation Gas Releases Ar-41 Ci 5.08E-02 5.92-02 4.70E-02 5.30E-02 2.1 OE-01 Kr-85 Ci <LLD <LLD <LLD <LLD <LLD Kr Ci <LLD 9.71 E-04 <LLD <LLD 9.71 E-04 Kr-87 Ci <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD Xe-131 m Ci <LLD <LLD <LLD <LLD <LLD Xe-133 Ci 2.51E-02 8.25E-02 3.30E-02 3.93E-02 1.80E-01 Xe-133m Ci <LLD <LLD <LLD <LLD <LLD Xe-1 35 Ci <LLD 2.88E-02 3.22E-04 6.23E-04 2.97E-02 Xe-1 35m Ci <LLD <LLD <LLD <LLD <LLD Xe-1 38 Ci <LLD <LLD <LLD <LLD <LLD D. Iodine Releases

• Value reported as Continuous Mode p.Xdepts'~zd84g\environsgroup\2002eff doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 GAS RELEASES UNIT 1 (Docket Number 50-456)

CONTINOUS MODE I Units I 1st Qtr I2nd Qtr I 3rd Qtr I4th Qtr I Total l A. Particulate ( > 8 day half-life) Releases Cr-51 Ci <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD Co-57 Ci <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD 1.03E-06 <LLD <LLD 1.03E-06 Fe-59 Ci <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD An-65 Ci <LLD <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD Sn-117m Ci <LLD <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD <LLD Cs-1 37 Ci <LLD <LLD <LLD <LLD <LLD Ba\La-140 Ci <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD B. Tritium Releases

1. Total Release Activity Ci <LLD <LLD <LLD <LLD <LLD C. Fission and Activation Gas Releases Ar-41 Ci <LLD <LLD <LLD <LLD <LLD Kr-85 Ci <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD Xe-131 m Ci <LLD <LLD <LLD <LLD <LLD Xe-1 33 Ci <LLD <LLD <LLD <LLD <LLD Xe-133m Ci <LLD <LLD <LLD <LLD <LLD Xe-1 35 Ci <LLD <LLD <LLD <LLD <LLD Xe-1 35m Ci <LLD <LLD <LLD <LLD <LLD Xe-1 38 Ci <LLD <LLD <LLD <LLD <LD D. Iodine Releases 1-131 Ci <LLD <LLD <LLD 1.05E-06 1.05E-06 1-132 Ci <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD 8.82E-07 <LLD <LLD 8.82E-07 1-134 Ci <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LID p \depts\zd84g\environsgroup\2002eff~doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 GAS RELEASES UNIT 2 (Docket Number 50-457)

SUMMATION OF ALL RELEASES I Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr ITotall A. Fission and Activation Gas Releases 11._To~t~al:Release Activity Il Ci I 3.85E-01 I 2.26E-01 I 4.76E-02 I 5.18E-02 I 7.10E-01 l

2. Average Release Rate I uCi/sec I 4.95E-02 I 2.87E-02 I 5.99E-03 I 6.52E-03 I 2.25E-02l B. Iodine Releases

11. Total 1-131 Activity l Ci l <LLD l 2.75E-06 <*LLD <LLD 2.75E-06 l2. Average Release Rate uCi/sec <LLD 3.50E-07 <LLD <LLD 8.72E-08 C. Particulate (> 8 day half-life) Releases

1. Gross Activity Cl <LLD 5.41E-06 <LLD <LLD 5.41 E-06

2. Average Release Rate uCi/sec <LLD 6 96E-07 <LLD I <LL 1.72E-07 3 Gross Alpha Activity Ci <LLD <LLD <LLD <LLD <LLD D. Tritium Releases

11. Total Release Activity l Ci l 9.14E-02 l 2.54E-02 l 3 92E-02 l 9.63E-02 2.52E-01 l

2. Average Release Rate uCi/sec 1.18E-02 3.23E-03 4.93E-03 1.21E-02 7.99E-03 E. Sum of Iodine, Particulate (> 8 day half-life),

and Tritium Releases.

1. Total Release Activity Ci 9.14E-02 2.54E-02 3.92E-02 9.63E-02 2.52E-01 Note LLD Values are included in Appendix A of this report.

Note: % Limit Values are included in Appendix B of this report.

p-Ndepts\zd84g\environsgroup\2002eff.doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 GAS RELEASES UNIT 2 (Docket Number 50-457)

BATCH MODE I Units I1st Qtr 2nd Qtr 3rd Qtr 4th Qtr lTotal A. Particulate (> 8 day half-life) Releases Cr-51 Ci * *

• Mn-54 Ci * * * *

• Co-57 Ci Co-58 Ci Fe-59 Ci ***

Co-60 Ci* **

Zn-65 Ci ****

Sr-89 Ci ***

Sr-90 Ci ****

Mo-99 Ci ***

Sn-117m Ci

• Cs-1 34 Ci Cs-137 Ci . **

Ba\La-140 Ci ****

Ce-141 Ci ***

Ce-144 Ci ****

• Value reported as Continuous Mode B. Tritium Releases l1. Total Release Activity Ci 9.14E-02 2.54E-02 3.92E-02 9.63E-02 2.52E-02 C. Fission and Activation Gas Releases Ar-41 Ci 1.73E-01 6.59E-02 3.20E-02 3.17E-02 3.03E-01 Kr-85 Ci <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD 9.71 E-04 <LLD <LLD 9.71 E-04 Kr-87 Ci <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD Xe-131 m Ci <LLD <LLD <LLD <LLD <LLD Xe-133 Ci 2.01 E-01 1.26E-01 1.55E-02 2.01 E-02 3.63E-01 Xe-I 33m Ci <LLD <LLD <LLD <LLD <LLD Xe-135 Ci 1.12E-02 3.28E-02 1.05E-04 <LLD 4.41 E-02 Xe-1 35m Ci <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD D. Iodine Releases 1-131 * **

1-132 * * *

• 1-133 *****

1-134* ****

11-1-35***

• Value reported as Continuous Mode p.\depts\zd84g\environsgroup\2002eff.doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 GAS RELEASES UNIT 2 (Docket Number 50-457)

CONTINUOUS USE I Units I 1st Qtr I 1

_2nd Qtr I 3rd Qtr I 4th Qtr I Total I A. Particulate ( > 8 day half-life) Releases Cr-51 Ci <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD Co-57 Ci <LLD 3.03E-06 <LLD <LLD 3.03E-06 Co-58 Ci <LLD 2.38E-06 <LLD <LLD 2.38E-06 Fe-59 Ci <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD Sn-117m Ci <LLD <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD <LLD Cs-1 37 Ci <LLD <LLD <LLD <LLD <LLD Ba\La-140 Ci <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD B. Tritium Releases l1. Total Release Activity Ci <LLD <LLD <LLD <LLD < LLD C. Fission and Activation Gas Releases Ar-41 Ci <LLD <LLD <LLD <LLD <LLD Kr-85 Ci <LLD <LLD LLD <LLD <LLD Kr-85m Ci <LD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD Xe-131 m Ci <LLD <LLD <LLD <LLD <LLD Xe-1 33 Ci <LLD <LLD <LLD <LLD <LLD Xe-1 33m Ci <LLD <LLD <LLD <LLD <LLD Xe-1 35 Ci <LLD <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD D. Iodine Releases 1-131 Ci <LLD 2.75E-06 <LLD <LLD 2.75E-06 1-132 Ci <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD <LLD 1-134 Ci <LLD <LLD <LLD <LLD d<LD 1-135 Ci <LLD <LLD <LLD <LLD <LLD p \depts\zd84g\environsgroup\2002eff doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 LIQUID RELEASES UNIT 1 (Docket Number 50-456)

SUMMATION OF ALL RELEASES I Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I Total A. Fission and Activation Products l1.TotalActivity Released l Ci l 1.37E-02 l 2.39E-02 l1.19E-02 l 3.81E-03 l 5.33E-02 I l2. Average Concentration Released uCVml 5.66E-09 8.12E-09 3.68E-09 1.16E-09 4.48E-09 B. Tritium

1. Total Activity Released Ci 2.31 E+02 2.25E+02 2.21 E+02 4.94E+02 1.17E+03

2. Average Concentration Released uCi/ml 9.54E-05 7.65E-05 6.84E-05 1.50E-04 9.85E-05

3. % of Limit (1E-3 uCiml)  % 9.54E+00 7.65E+00 6.84E+00 1.50E+01 9.85E+00 C. Dissolved Noble Gases

1. Total Activity Released Ci _1.87E-04 2.14E-03 8.91 E-05 1.23E-04 2.54E-03

2. Average Concentration Released uCiml 7.72E-11 7.27E-10 2.76E-11 3.74E-11 2.14E-1

3. % of Limit (2E-4 uCVml)  % 3.86E-05 3.64E-04 1.38E-05 1.87E-05 1.07E-04 D. Gross Alpha l1. Total Activity Released l Ci l <LLD l <LLD l <LLD I <LLD I <LLnDl

2. Average Concentration Released uC/mI <LLD <LLD <LLD <LLD <LLD E. Volume of Releases l1.VolumeofLiquid Waste to Discharge l liters l 1.29E+06 l 2.17E+06 1.81E+06 l 1.02E+06 l 6.29E+06 l

2. Volume of Dilution Water I liters I 2.42E+09l 2.94E+091 3.23E+091 3.29E+09l 1.19E+10 Note: LLD Values are included in Appendix A of this report.

Note: % Limit Values are included in Appendix B of this report p \depts\zd84g\environsgroup\2002eff doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 LIQUID RELEASES UNIT I (Docket Number 50-456)

BATCH MODE lNuclides From Batch Releases Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total l H-3 Ci 2.27E+02 2.25E+02 1.81 E+02 3.59E+02 9.91 E+02 Ar-41 Ci <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD 1.41 E-03 <LLD <LLD 1.41 E-03 Mn-54 Ci 2.25E-04 6.16E-04 1.42E-04 3.76E-05 1.02E-03 Fe-55 Ci <LLD <LLD <LLD <LLD <LLD Co-57 Ci 4.08E-05 6.66E-06 1.70E-06 6.25E-06 5.54E-05 Co-58 Ci 6.87E-03 6.21 E-03 4.34E-03 9.56E-04 1.84E-02 Fe-59 Ci <LLD 1.40E-04 <LLD <LLD 1.40E-04 Co-60 Ci 1.74E-03 5.74E-03 1.77E-03 9.17E-04 1.02E-02 Ni-65 Ci <LLD 8 60E-06 <LLD <LLD 8.60E-06 Zn-65 Ci <LLD <LLD <LLD <LLD <LLD Kr-85 Ci <LLD 1.06E-03 <LLD <LLD 1.06E-03 Kr-87 Cl <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD Nb-95 Ci 6.54E-05 2.13E-04 1.86E-06 <LLD 2.80E-04 Zr-95 Ci 3.45E-06 4.01 E-05 <LLD <LLD 4.35E-05 Nb-97 Ci <LLD 5.17E-05 5 60E-05 2.55E-05 1.33E-04 Zr-97 Ci <LLD <LLD 3.OOE-06 <LLD 3.OOE-06 Tc-99m Ci <LLD 5.20E-06 <LLD <LLD 5.20E-06 Mo-99 Ci <LLD <LLD <LLD <LLD <LLD Ag-11 Om Ci 1.60E-05 3.OOE-04 1.76E-05 1.15E-05 3.45E-04 Sn-117m Ci <LLD <LLD <LLD <LLD <LLD Sb-122 Ci <LLD <LLD <LLD <LLD <LLD Te-123m Ci 1.32E-04 2.23E-03 1.21 E-04 9.66E-05 2.57E-03 Sb-124 Cl <LLD 1.68E-03 2.12E-03 1.14E-04 3.91 E-03 Sb-1 25 Ci 2.05E-03 2.36E-03 3.27E-03 1.35E-03 9.02E-03 Te-125m Ci 2.56E-03 2.29E-03 <LLD <LLD 4.85E-03 Xe-131 m Cl 1.26E-04 <LLD <LLD <LLD 1.26E-04 1-131 Ci <LLD <LLD <LLD 3.08E-06 3.08E-06 1-132 Ci <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD 5.80E-04 <LLD <LLD 5.80E-04 Xe-1 33 Ci 6 18E-05 1.08E-03 7.76E-05 1.24E-04 1.34E-03 Xe-1 33m Ci <LLD <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD <LLD Xe-1 35 Ci <LLD 3 83E-06 <LLD <LLD 3.83E-06 1-135 Ci <LLD <LLD <LLD <LLD <LLD Cs-137 Ci 2.38E-05 <LLD <LLD 1.50E-05 3.88E-05 Cs-1 38 Ci <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD I<LLD 1.17E-05 <LLD 1.17E-05 p:\depts\zd84g\environsgroup\2002eff-doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 LIQUID RELEASES UNIT 1 (Docket Number 50-456)

BATCH MODE Nucldes From Batch Releases Units 1st Qtr 2nd Qtr I 3rd Qtr 4th Qtr Total Ba\La-140 Cl <LLD <LLD <LLD 2.89E-04 2.89E-04 Ce-141 Ci <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD 1-134 Ci <LLD 1.46E-05 5.15E-06 <LLD 1.98E-05 Cs-1 36 Ci <LLD 5.90E-06 <LLD <LLD 5.90E-06 Rb-88 Ci <LLD <LLD 4.11E-05 <LLD 4.11E-05 Br-82 Ci <LLD 5.80E-04 <LLD <LLD 5.80E-04 Na-24 Ci <LLD 4.17E-06 <LLD <LLD 4.17E-06 Tc-101 Ci <LLD 1.20E-05 <LLD <LLD 1.20E-05 p:\depts\zd84g\environsg roup\2002eff.doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 LIQUID RELEASES UNIT 1 (Docket Number 50-456)

CONTINUOUS MODE Nuclides From Continuous Releases lUnits 1st Qtr I 2nd Qtr I 3rd Qtr 4th Qtr Total H-3 Ci 4.49E+00 0.OOE+00 4.03E+01 1.36E+02 1.81E+02 Ar-41 Ci <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD <LLD Co-57 Ci <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD Ni-65 Ci <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD Kr-85 Cl <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD <LLD Nb-97 Ci <LLD <LLD <LLD <LLD <LLD Zr-97 Ci <LLD <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD Ag-1 Om Ci <LLD <LLD <LLD <LLD <LLD Sn-117m Ci <LLD <LLD <LLD <LLD <LLD Sb-122 Ci <LLD <LLD <LLD <LLD <LLD Te-1 23m Ci <LLD <LLD <LLD <LLD <LLD Sb-124 Ci <LLD <LLD <LLD <LLD <LLD Sb-125 Ci <LLD <LLD <LLD <LLD <LLD Te-1 25m Ci <LLD <LLD <LLD <LLD <LLD Xe-131 m Ci <LLD <LLD <LLD <LLD <LLD 1-131 Cl <LLD <LLD <LLD <LLD <LLD 1-132 Ci <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD <LLD Xe-1 33 Ci <LLD <LLD <LLD <LLD <LLD Xe-1 33m Ci <LLD <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD Cs-1 37 Ci <LLD <LLD <LLD <LLD <LLD Cs-1 38 Ci <LLD <LLD <LLD <LLD <LLD Xe-1 38 Cl <LLD <LLD <LLD <LLD <LLD Ba\La-140 Ci <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD p:\depts\zd84g\environsgroup\2002eff.doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 LIQUID RELEASES UNIT 2 (Docket Number 50-457)

SUMMATION OF ALL RELEASES I Units I 1st Qtr I 2nd Qtr I 3rd Qtr I 4th Qtr I TotalI A. Fission and Activation Products EI. Total Activity Released l Cl l 1.37E-02 l 2.39E-02 I 1.19E-02 l 3.81E-03 l 5.33E-021

2. Average Concentration Released uCi/mI 5.66E-09 8.12E-09 I 3.68E-09 I 1.16E-09 I 4.48E-09 B. Tritium

1. Total Activity Released Ci 2.31E+02 2.25E+02 2.21E+02 4.94E+02 1.17E+03

2. Average Concentration Released uCi/mI 9.54E-05 7.65E-05 6 84E-05 1.50E-04 9.85E-05

3. % of Limit (1E-3 uCi/ml)  % 9.54E+00 7.65E+00 6.84E+00 1.50E+01 9.85E+00 C. Dissolved Noble Gases

1. Total Activity Released Ci 1.87E-04 2.14E-03] 8.91E-05 1.23E-04 2.54E-03

2. Average Concentration Released uCi/ml 7.72E-11 7.27E-10 2.76E-11 3.74E-11 2.14E-10

3. % of Limit (2E-4 uCi/ml)  % 3.86E-05 3.64E-04 1.38E-05 1.87E-05 1.07E-04 D. Gross Alpha 1I.Total Activity Released l Ci l <LLD l <LLD l <LLD l <LLD <LLD

2. Average Concentration Released uCi/mI <LLD <LLD <LLD <LLD <LLD E. Volume of Releases

[1. Volume of Liquid Waste to Disch lE+06 2.17E+06 1.81E+06 1.E

2. Volume of Dilution Water I liters l 2 42E+09l 2.94E+09l 3.23E+09l 3.29E+09l 1.19E+10 Note: LLD Values are included in Appendix A of this report.

Note: % Limit Values are included in Appendix B of this report p \depts\zd84g\environsgroup\2002eff.doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 LIQUID RELEASES UNIT 2 (Docket Number 50-456)

BATCH MODE Nucldes From Batch Releases Units 1st Qtr 2nd Qtr I 3rd Qtr 4th Qtr Total H-3 Ci 2.27E+02 2.25E+02 1.81 E+02 3.59E+02 9.91 E+02 Ar-41 Cl <LLD <LLD <LLD <LLD .<LLD Cr-51 Cl <LLD 1.41 E-03 <LLD <LLD 1.41 E-03 Mn-54 Ci 2.25E-04 6.16E-04 1.42E-04 3.76E-05 1.02E-03 Fe-55 Ci <LLD <LLD <LLD <LLD <LLD Co-57 Ci 4.08E-05 6.66E-06 1.70E-06 6.25E-06 5.54E-05 Co-58 Ci 6.87E-03 6.21 E-03 4.34E-03 9.56E-04 1.84E-02 Fe-59 Ci <LLD 1.40E-04 <LLD <LLD 1.40E-04 Co-60 Ci 1.74E-03 5.74E-03 1.77E-03 9.17E-04 1.02E-02 Ni-65 Ci <LLD 8.60E-06 <LLD <LLD 8.60E-06 Zn-65 Ci <LLD <LLD <LLD <LLD <LLD Kr-85 Ci <LLD 1.06E-03 <LLD <LLD 1.06E-03 Kr-87 Ci <LLD <LLD <LLD <LLD <LLD Kr-88 Cl <LLD <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD Nb-95 Ci 6.54E-05 2.13E-04 1.86E-06 <LLD 2.80E-04 Zr-95 Ci 3.45E-06 4.01 E-05 <LLD <LLD 4.35E-05 Nb-97 Ci <LLD 5.17E-05 5.60E-05 2.55E-05 1.33E-04 Zr-97 Ci <LLD <LLD 3.OOE-06 <LLD 3.OOE-06 Tc-99m Cl <LLD 5.20E-06 <LLD <LLD 5.20E-06 Mo-99 Ci <LLD <LLD <LLD <LLD <LLD Ag-1 1Om Ci 1.60E-05 3.OOE-04 1.76E-05 1.15E-05 3.45E-04 Sn-117m Ci <LID <LLD <LLD <LLD <LLD Sb-122 Ci <LLD <LLD <LLD <LLD <LLD Te-123m Ci 1 32E-04 2.23E-03 1.21 E-04 9.66E-05 2.57E-03 Sb-124 Ci <LLD 1.68E-03 2.12E-03 1.14E-04 3.91 E-03 Sb-125 Ci 2.05E-03 2.36E-03 3.27E-03 1.35E-03 9.02E-03 Te-1 25m Ci 2.56E-03 2.29E-03 <LLD <LLD 4.85E-03 Xe- 31m Cl 1.26E-04 <LLD <LLD <LLD 1.26E-04 1-131 Ci <LLD <LLD <LLD 3.08E-06 3.08E-06 1-132 Ci <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD 5.80E-04 <LLD <LLD 5.80E-04 Xe-133 Ci 6.18E-05 1.08E-03 7.76E-05 1.24E-04 1.34E-03 Xe-I 33m Ci <LLD <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD <LLD Xe-1 35 Cl <LLD 3 83E-06 <LLD <LLD 3.83E-06 1-135 Ci <LLD <LLD <LLD <LLD <LLD Cs-137 Ci 2.38E-05 <LLD <LLD 1.50E-05 3.88E-05 Cs-1 38 Ci <LLD <LLD <LLD <LLD <LLD Xe-138 Cl <LLD <LLD 1.177E-05 <LLD 1.17E-05 p:\depts\zd84g\enviroflsgroup\2002eff .doc

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 LIQUID RELEASES UNIT 2 (Docket Number 50-456)

BATCH MODE lNuclides From Batch Releases Units 1st Qtr 2nd Qtr I 3rd Qtr 4th Qtr Total Ba\La-1 40 Cl <LLD <LLD <LLD 2.89E-04 2.89E-04 Ce-141 Ci <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD 1-134 Ci <LLD 1.46E-05 5.15E-06 <LLD 1.98E-05 Cs-1 36 Ci <LLD 5.90E-06 <LLD <LLD 5.90E-06 Rb-88 Ci <LLD <LLD 4.11 E-05 <LLD 4.11 E-05 Br-82 Ci <LLD 5.80E-04 <LLD <LLD 5.80E-04 Na-24 Ci <LLD 4.17E-06 <LLD <LLD 4.17E-06 Tc-101 Ci <LLD 1.20E-05 <LLD <LLD 1.20E-05 p:\depts\zd84g\environsgroup\2002eff.doc

BRAIDWODO NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2002 LIQUID RELEASES UNIT 2 (Docket Number 50-457)

CONTINUOUS MODE lNuclides From Continuous Releases Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total H-3 Ci 4.49E+00 0.OOE+00 4.03E+01 1.36E+02 1.81E+02 Ar-41 Ci <LLD <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD <LLD <LLD <LLD Co-57 Ci <LLD <LLD <LLD <LLD <LLD Co-58 Cl <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD Co-60 Cl <LLD <LLD <LLD <LLD <LLD Ni-65 Ci <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD Kr-85 Ci <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD Kr-88 Cl <LLD <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD <LLD Sr-90 Cl <LLD <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD <LLD Nb-97 Ci <LLD <LLD <LLD <LLD <LLD Zr-97 Ci <LLD <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD Ag-1 Om Ci <LLD <LLD <LLD <LLD <LLD Sn-1 17m Ci <LLD <LLD <LLD <LLD <LLD Sb-1 22 Ci <LLD <LLD <LLD <LLD <LLD Te-123m Ci <LLD <LLD <LLD <LLD <LLD Sb-1 24 Ci <LLD <LLD <LLD <LLD <LLD Sb-125 Ci <LLD <LLD <LLD <LLD <LLD Te-125m Ci <LLD <LLD <LLD <LLD <LLD Xe-131 m Ci <LLD <LLD <LLD <LLD <LLD 1-131 Ci <LLD <LLD <LLD <LLD <LLD 1-132 Ci <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD <LLD Xe-1 33 Ci <LLD <LLD <LLD <LLD <LLD Xe-133m Ci <LLD <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD <LLD Xe-1 35 Ci <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD Cs-1 37 Ci <LLD <LLD <LLD <LLD <LLD Cs-1 38 Ci <LLD <LLD <LLD <LLD <LLD Xe-1 38 Ci <LLD <LLD <LLD <LLD <LLD Ba\La-140 Ci <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD p:\depts\zd84g\environsgroup\2002eff doc

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 SOLID RADIOACTIVE WASTE UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. Types of Waste

a. Process Waste 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Yr total Total (m;) = 5.83E+00 5.83E+00 1.59+02 O.OOE+00 1.71 E+02 Total (Ci) = 4.09E+01 1 15E+01 1.21E+01 0.O0E+00 6.45E+01

% Error = 2.50E+01 2.50E+01 2.50E+01 2.50E+01

b. Dry Active Waste 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Yr total Total (ma) = 0.OQE+00 1.15E+02 7.65E+01 1.45E+02 3.37E+02 Total (Ci) = 0.OQE+00 4.75E-01 I1.45E-01 3 08E-02 6.51 E-01

% Error = 2.50E+01 2.50E+01 2.50E+01 2.50E+01

2. Estimate of major nuclide composition (by type of waste) a Process Waste 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Yr total Nuclide Ci Ci Ci Ci Ci  % Composition H-3 3 24E+01 4.56E+00 1.55E-02 0.OOE+00 3.70E+01 5.73E+01

• Cr-14 2.64E+00 2.19E+00 5.39E+00 0.OOE+00 1.02E+01 1.58E+01 Cr-51 3 OOE+00 2.56E+00 3 57E+00 0.OOE+00 9.13E+00 1.42E+01 Mn-54 1.77E+00 1.49E+00 2.75E+00 0.OOE+00 6.01 E+00 9.32E+00

• Fe-55 5 58E-01 1.61 E-01 5.19E-02 0.OOE+00 7.71 E-01 1.20E+00 Fe-59 1.16E-01 9.63E-02 2.40E-01 0.OOE+00 4 52E-01 7.01 E-01 Co-57 2.32E-01 5.56E-02 3.97E-03 0.OOE+00 2 92E-01 4 52E-01 Co-58 5 90E-02 1.65E-01 8.78E-03 0.OOE+00 1.02E-01 3.61 E-01 Co-60 2.61 E-02 2.17E-02 5.40E-02 0.OOE+00 1.02E-01 1.58E-01

• Ni-59 3.92E-02 5.44E-02 1.76E-04 0.OOE+00 9.38E-02 1.45E-01

• Ni-63 9.26E-03 5 29E-02 2.71 E-02 0.OOE+00 8.93E-02 1.38E-01

• Activities based on 10CFR61 scaling factors p.\depts\zd84g\environsgroup\2002eff.doc

b Dry Active Waste 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Yr total Nuclide Ci Ci Ci Ci Ci  % Composition H-3 0 OOE+00 1.53E-01 4 26E-02 1 07E-02 2.06E-01 3.17E+01

• Cr-14 0.0E+00 1.32E-01 3.67E-02 9.21 E-03 1.78E-01 2.73E+01 Cr-51 O.OOE+00 8.91 E-02 2.47E-02 6.25E-03 1.20E-01 1.84E+01 Mn-54 O.OOE+00 3.16E-02 2.19E-02 0.OOE+00 5.35E-02 8.21 E+00

• Fe-55 0.OOE+00 3.25E-02 9.OOE-03 2.09E-03 4.36E-02 6.69E+00 Co-57 0.OOE-00 6.71 E-03 1.85E-03 3.93E-04 8.95E-03 1.37E+00 Co-58 0.OOE+00 5.79E-03 1.61 E-03 4.08E-04 7.81 E-03 1.20E+00 Co-60 0.OOE+00 5.62E-03 1.56E-03 3.95E-04 7.58E-03 1.16E+00

• Ni-59 O.OOE+00 5.27E-03 1.46E-03 3.64E-04 7.09E-03 1.09E+00

• Ni-63 0.OOE+00 4 07E-03 1.13E-03 2.59E-04 5.46E-03 8.38E-01 Sr-89 O.OOE+00 4.02E-03 1.11E-03 2.81 E-04 5 41 E-03 8.31 E-01 Sr-90 0.OOE+00 1.74E-03 4.78E-04 9.67E-05 2.31 E-03 3.55E-01 Zr-95 0.OOE+00 1.30E-03 3.62E-04 9.18E-05 1.75E-03 2.69E-01 Nb-95 O.OOE+00 6.96E-04 1.93E-04 4.40E-05 9.33E-04 1.43E-01

• Tc-99 O.OOE+00 5.34E-04 1.48E-04 3.67E-05 7.19E-04 1.10E-01

• Activities based on IOCFR61 scaling factors Number of Shipments: 10 Mode of Transportation: Exclusive Use Destination: Envirocare, Clive, Utah (2)

GTS Duratek, Kingston, Tennessee (4)

GTS Duratek, Oak Ridge, Tennessee (4)

B. IRRADIATED FUEL SHIPMENTS No irradiated fuel shipments for January through December, 2002 p-\depts\zd84g\environsgroup\2002eff.doc

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 SOLID RADIOACTIVE WASTE UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

Shipment Number Waste Class Type of Container Solidification Agent RWS02-001 AU Type A Cask None RWS02-002 AU STC None RWS02-003 AU STC None RWS02-004 AU STC None RWS02-005 AS Cask STC None RWS02-006 AU STC None RWS02-007 AU STC None RWS02-008 AU STC None RWS02-009 AU STC None RWS02-01 0 AU STC None p:\depts\zd84g\envlronsgroup\2002eff.doc

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

1. The following items reflect changes to the Braidwood Station Process Control Program implementing procedure(s). BwRP 5600-13, 10CFR61 Waste Stream Sampling and Analysis, was changed to move the Radwaste (WX) Mixed Bed Demineralizers from the Primary Resin Waste Stream into the Radwaste Resin Waste Stream to reflect the way the demineralizers are currently being used for processing The Steam Generator Blowdown Demineralizers (SGBD) and Condensate Polisher Demineralizers (CP) were moved from the Secondary Resin Waste Stream into the Radwaste Resin Waste Stream, and the Secondary Resin Waste Stream was eliminated This eliminates the cost and effort required for sampling and analyzing one waste stream, while moving the SGBD and CP resin waste types into the more conservative and more highly concentrated Radwaste Resin Waste Stream

2. There were no changes to the installed liquid, gaseous, or solid radwaste treatment systems in 2002.

3. There were no liquid release tanks or gas decay tanks which exceeded the limits addressed in the ODCM-RETS

4. Pursuant to ODCM-RETS Section 12.6.2, the following is an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in ODCM-RETS.

There were no liquid or gaseous effluent monitoring instruments that exceeded their specified inoperability time in 2002

5. Error in Measurement -

The following is an estimate of the errors associated with effluent monitoring and analysis. The estimate is calculated using the square root of the sum of the squares methodology.

A. Gaseous Effluents Est Total Error %

1. Fission and Activation Gas Releases 7 59

2. Iodine Releases 33.2

3. Particulates (>8 day half life)

Releases 19.8

4. Tritium Releases 8.07 B. Liquid Effluents Est. Total Error %

1. Fission and Activation Products 2.64

2. Tritium 5.85 3 Dissolved Noble Gases 2.64 4 Gross Alpha 14.7 5 Volume of Liquid Waste to Discharge 2.0

6. Volume of Dilution Water 1.5 p.\depts\zd84g\environsg roup\2002eff doc

I

6. The complete ODCM manual with changes is attached. The following is a summary of the 2002 Revisions to the Exelon Nuclear Offsite Dose Calculation Manual (ODCM).

Generic Section Table of Contents Page or Section Change Description Cover Page Replaced ComEd logo with Exelon Nuclear logo.

Table of Contents Updated table of contents to reflect changes to generic section of ODCM.

Chapter 1 Page or Section Change Description page vii Added INTRODUCTION' to chapter heading 1.0 Last paragraph. Changed "ComEd" to "Exelon Nuclear" 1.1 Revised first sentence of first paragraph to read: "The manual is the ODCM for the following Exelon Nuclear power stations: Braidwood, Byron, Dresden, LaSalle, Quad Cities and Zion."

Second paragraph. Changed "ComEd" to "Exelon Nuclear" Revised second sentence in second paragraph to read: "Appendices A and B provide detailed information on specific aspects of the methodology."

Chapter 2 Page or Section Change Description 2.0 Editorial revision. Changed "CFR" to read " Code of Federal Regulations (CFR)"

2.1.4 Changed "whole body" to "total body" 2.1.5 Changed "whole body" to "total body" Changed "ComEd" to "Exelon Nuclear" Editorial revision. Changed "calculational" to 'calculation" in last sentence of last paragraph.

2.4 Changed "whole bodyV to "total body" Added '(or TEDE)" to first paragraph 25 Revised section to indicate that dose methodology is based upon maximum individual concept of Regulatory Guide 1.109 and NUREG 0133. Clarified location of dose receptor based upon NUREG 0133.

Table 2-1 Revised references to equation numbers.

Added footnote 4 to explanation of Total Effective Dose Equivalent.

Changed "whole body" to "total body" Changed "ComEd" to "Exelon Nuclear" in footnote 2.

p:Xdepts\zd84g\environsg roup\2002eff.doc

Chapter 2 (cont.)

Pace or Section Change Description Table 2-2 Clarified reference to Table F-8.

Deleted reference to direct dose from radioactivity deposited on the ground.

Added reference to dose due to radioiodines, tritium and particulates with half-lives greater than 8 days for inhalation, ingestion of vegetation, milk and meat, and ground plane exposure pathways.

Deleted reference to receiver at unrestricted area boundary location with highest D/Q.

Defined dose receptor in accordance with methodology of NUREG 0133.

Deleted reference to Total Effective Dose Equivalent replacing it with Total Dose.

Added. "Note it may also be necessary to address dose from on-site activity by members of the public."

Deleted footnote 1.

Table 2-3 Revised to reflect new equation and section numbers.

Changed "whole body" to "total body" Deleted reference to IOCFR20 requirement for instantaneous dose rate limits from airborne radioactivity and added reference to RETS.

Revised footnote 1 to include all groups for 10CFR20 and 40CFR190 compliance assessment.

Deleted reference to FGR 11 in footnote 1.

Added footnote 4 to explanation of Total Effective Dose Equivalent.

Figure 2-1 Changed receptor from "Adult" to "Child" for Non-Noble Gas Inhalation dose rate.

Changed "whole body" to "total body" Revised references to new section numbers.

Changed "Leafy Vegetables" to 'Vegetation" Deleted reference to "Produce" Revised footnote c to reflect changes in location of dose receptor.

Changed "ComEd" to "Exelon Nuclear" in footnote 2.

Chapter 3 Pace or Section Change Description 3.1 Deleted reference to Figure 3-1.

Changed 'Radiation from radioactivity airborne..." to read, 'External Radiation from radioactivity airborne..."

Changed "Radiation from radioactivity deposited..." to read, "External Radiation from radioactivity deposited..."

Deleted references to "transfer of radioactivity deposited on the soil" for vegetation and animal food products.

Delete last paragraph and added statement: "Dose for airborne releases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures "

3.2 Delete references to the following pathways: direct exposure, shoreline exposure, vegetation irrigation and animal food product irrigation.

Changed "CornEd" to "Exelon Nuclear" Figure 3-1 Revised Figure 3-1 to reflect NUREG 0133 pathways.

p:\depts\zd84g\environsgroup\2002eff.doc

Chapter 4 Page or Section Change Description 4.0 Changed "ComEd" to "Exelon Nuclear" 4.1.1 Deleted, "and Dose Commitment" from section title.

Deleted last sentence of first paragraph Changed first sentence of second paragraph to read: "Internal exposure occurs when the source of radioactivity is inside the body."

Editorial change, second paragraph. Changed "eating" to "consumption of."

Deleted definition of ingested activity.

Added paragraph to define dose as used by Regulatory Guide 1.109.

4 1.2 Editorial revision. Changed "...deposited the radioactivity on vegetation' to read 'deposited radioactivity on vegetation."

Changed notation for'"N16" to " 16N."

4.1.3 Changed "CornEd" to "Exelon Nuclear" Editorial revision. Changed "where-as" to "whereas".

Editorial revision. Deleted "(Ci)" in second paragraph.

4.1.4 Revised first paragraph to read. " The dose impact from airborne release of radioactivity, is determined by the height of the release of the effluent plume relative to the ground and by the location of the dose recipient."

Changed second paragraph from, "It has been found that the height an..." to read "The height an..."

Changed "ComEd" to "Exelon Nuclear".

4.1.5 Changed 5'X/Q" to "X/Q*I Added reference to "gamma-x/Q' Deleted reference to Gamma Air Dose Factor.

Deleted reference to Whole Body Dose Factor.

Changed first sentence of last paragraph to read, "The bases sections of the Standard Radiological Effluent Technical Specifications (guidance documents NUREGs 0472, 0473,1301 and 1302)..."

4.1.6 Changed NX/Q" to "X/Q Added reference to 'gamma-x/Q."

Added verbal definition of gamma-x/Q.

Changed "methodology" to "methodologies" in last paragraph.

4.1.7 Changed "X/Q" to "X/Q Changed "ComEd" to "Exelon Nuclear" 4.2.1 Added discussion of how gamma-x/Q impacts assessment of gamma air dose.

Revised definition of Finite Cloud Gamma Air Dose Factor to be consistent with that of Regulatory Guide 1.109 and the use of gamma-x/Q.

Revised definition of Semi-Infinite Cloud Gamma Air Dose Factor to be consistent the use of gamma-xIQ 4.2 1.1 Changed section title from "The Gamma Air Dose Factor" to "Finite Cloud Gamma Air Dose Factor" p \depts\zd84g\environsgroup\2002eff doc

Chapter 4 (cont.)

Pace or Section Chbnqe Description 4.2.1 2 Revised definition of Semi-Infinite Cloud Gamma Air Dose Factor to be consistent the use of gamma-X/Q.

4.2.2 Changed first sentence of first paragraph to read " The term 'beta air dose' refers to the component of dose absorbed by air resulting from the absorption of energy from emissions of beta particles..."

Revised definition of Beta Air Dose Factor to be consistent with that of Regulatory Guide 1.109.

4 2.3 Revised wording referring to "Whole Body" to read 'Total Body" to be consistent with that of Regulatory Guide 1.109 and NUREG 0133.

Deleted references to deep dose equivalent and DDE.

Revised references to equation numbers Revised definition of Whole Body Dose Factor (now Total Body Dose Factor) to be consistent with that of Regulatory Guide 1.109 and NUREG 0133 4 2.4 Deleted reference to shallow dose equivalent and SDE.

Revised references to equation numbers Revised definition of Skin Dose Factor to be consistent with that of Regulatory Guide 1.109 and NUREG 0133.

Changed "whole body" to "total body" 4.2.5 Deleted reference to deep dose equivalent Revised wording referring to "Whole Body" to read "Total Body."

Revised references to equation numbers.

Editorial revision. Deleted last two sentences of last paragraph.

4.2.6 Replaced wording of "Dose Commitment" with "Dose".

Deleted reference to C-14 Revised references to equation numbers.

Deleted reference to committed dose equivalent and CDE.

Revised definition of Inhalation Dose Factor to be consistent with that of Regulatory Guide 1.109 and NUREG 0133.

Changed receptor age group from "Adult" to "Child."

4.2.7 Replaced reference to "Leafy Vegetables" with "Vegetables."

Deleted reference to "Produce" Deleted reference to absorption by vegetation.

Changed "ComEd" to "Exelon Nuclear" Editorial revision. Replaced "Milk, and" with "Milk" Revised references to equation numbers.

Deleted reference to FGR 11.

Changed last sentence of section to read. "The equations used for radioactivity concentration on vegetation and in milk and meat are discussed in Appendix A "

43 Changed "ComEd" to "Exelon Nuclear" Deleted reference to dose rate.

Changed "bio-accumulation" to "bioaccumulation."

In first paragraph changed wording "principal pathways" to "pathways."

In first paragraph changed wording, "from both the drinking water" to "from the drinking water."

Revised references to equation numbers Revised wording to reflect change from Regulatory Guide 1.109 to NUREG 0133 dose calculation methodology.

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Chapter 4 (cont.)

Page or Section Change Description 4.4 Changed "whole body" to "total body" Changed "rad" to "radioactive" in last sentence of last paragraph.

4.4.1 Changed notation for "N16" to "'6 N."

Revised references to equation numbers.

4.4.2 Editorial revision- Changed "Low level" to "Low-level" in first sentence of first paragraph Changed "CornEd" to "Exelon Nuclear" Editorial revision: changed "In addition Rad Material may be stored on site:"

to read, "Rad Material may be stored on site."

Added reference to ISFSI facilities.

4.5 Revised to address details of how 10CFR20 compliance will be demonstrated.

Reference to TEDE was deleted.

4.6 Changed notation for "N16" to " 16N."

Table 4-1 Deleted reference to C-14.

Deleted footnote 1.

Revised to reflect changes in footnotes.

Table 4-2 Changed 'Whole Body" to "Total Body" Changed units for whole body (now total body) dose factor from "mrad/yr per pCi/m3" to "inrem/yr per pCi/m "

Changed Name and Symbol for ground plane to "Ground Plane Dose Conversion Factor" Deleted references to S., VI and G,.

Revised references to equation numbers Revised units for Gamma Air Dose Factors.

Deleted Inhalation Dose Commitment Factor reference to FGR 11.

Deleted Ingestion Dose Commitment Factor reference to FGR 11.

Deleted reference to FGR 11 from table Note 1.

Chapter 5 Page or Section Change Description 5.2 Changed "station's" to "stations' Changed "ComEd" to "Exelon Nuclear" Chapter 6 Page or Section Chanae Descrption 6.1 Changed third sentence of first paragraph to read, "These data are used..."

Deleted last paragraph.

63 Changed reference to "GSRPD" to "corporate" 64 Deleted p \depts\zd84g\environsgroup\2002eff doc

Chapter 7 Page or Section Change Description Reference 93 Deleted Reference 104 Added: " Federal Register, Vol. 56, No. 98, Tuesday, May 21, 1991, page 23374, column 3."

Reference 105 Added: " U.S. Nuclear Regulatory Commission, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, NUREG-1301, April 1991."

Reference 106 Added " U.S. Nuclear Regulatory Commission, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, NUREG-1302, April 1991."

Reference 107: Added. " U.S. Nuclear Regulatory Commission, LADTAP II - Technical Reference and Users Guide, NUREG-4013, April 1986."

Appendix A Page or Section Change Description Table of Contents Updated table of contents to reflect changes to Appendix A A.0 Revised "These factors, X/Q and D/Q are defined..." to read, "These atmospheric dispersion and deposition factors..."

Reworded to remove references to meteorologically based dose factors.

Deleted fifth paragraph and added the statement, "This section of the ODCM provides the methodological details for demonstrating compliance with the 10CFR20, 10CFR50 Appendix I and 40CFR190 radiological limits for liquid and gaseous effluents."

A 1.2.1 Revised section to reflect change to NUREG 0133 and gamma-X/Q methodology.

Clarified location of calculation for gamma air dose.

A 1.2 2 Revised section to reflect change to NUREG 0133 methodology.

Clarified location of calculation for beta air dose.

A.1.2.3 Revised section to reflect change to NUREG 0133 and gamma-X/Q methodology.

Changed "whole body" to "total body."

Clarified location of calculation for total body noble gas dose.

A.1.2.4 Revised section to reflect change to NUREG 0133 and gamma-X/Q methodology.

Clarified location of calculation for skin noble gas dose.

A.1.3.1 Revised section to reflect change to NUREG 0133 and gamma-X/Q methodology.

Deleted references to deep dose equivalent Changed "whole body" to "total body."

A.1.3.2 Revised section to reflect change to NUREG 0133 and gamma-X/Q methodology.

Deleted reference to "shallow dose equivalent rate" p:\depts\zd84g\environsgroup\2002eff.doc

Appendix A (cont.)

Page or Section Change Description A.1.4 Revised to reflect change to NUREG 0133 methodology.

Added paragraph to define dose as used by Regulatory Guide 1.109.

Clarified location of calculation for dose due to non-noble gas radionuclides.

A 1.4.1 Revised to reflect change to NUREG 0133 methodology.

Changed "whole body" to "total body" A.1.4.2 Revised to reflect change to NUREG 0133 methodology.

A.1.4.3 Revised to reflect change to NUREG 0133 methodology.

A.1.4.3.1 Revised to reflect change to NUREG 0133 methodology.

A 1.4.3.2 Revised to reflect change to NUREG 0133 methodology.

A.1.4.3.3 Revised to reflect change to NUREG 0133 methodology.

A.1.5 Revised to reflect change to NUREG 0133 methodology.

Changed age group typically considered as dose rate receptor from adult to child in accordance with guidance in NUREGs 0472, 0473, 1301 and 1302.

A.1.6 Deleted last paragraph of "Requirements" Revised equation numbers A2 Deleted references to dose commitment.

Deleted references to FGR 11.

Revised to reflect change to NUREG 0133 methodology.

A.2.1.1 Added section for potable water pathway dose factors.

A 2.1.2 Added section for fish ingestion pathway dose factors.

A2.2 Editorial revision: changed format of Equation A-21.

Editorial revision: changed "over index I (radionuclides)." to read "over radionuclides i "

Editorial revision: changed "mL" to "ml" Deleted wording "(if approved)" in definition of Tech Spec Multiplier.

Revised equation numbers.

A23 Editorial revision: changed "mL" to "ml" Revised Equation A-22 to reflect terminology of Equation 18.

Revised definition of dilution flow to be consistent with NUREG 0133.

A.2.5 Changed "whole body" to "total body."

Revised equation numbers Changed wording in last paragraph from, "Projected radionuclide releases are used in placed of measured releases, A, " to read, "Projected radionuclide release concentrations are used in placed of measured concentration, C,"

A3 Changed "ComEd" to "Exelon Nuclear' Changed notation for "N16" to "0 6N."

Added "(boiling water reactor)"

Chanced reference to "whole body" to "total body."

Deleted references to deep dose equivalent.

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Appendix A (cont.)

Page or Section Change Description A 3.1 Changed "ComEd" to "Exelon Nuclear" Changed notation for "N16" to "06N."

Changed notation for "16" to .. 160.Q Editorial revision: Reworded paragraph 4.

Editorial revision: changed format of Equation A-23.

Deleted references to deep dose equivalent.

A 3.2 Added bullet "Independent Spent Fuel Storage Installation (ISFSI) facilities" Deleted next-to-last paragraph.

Revised equation numbers Changed "ComEd" to "Exelon Nuclear" A4 Section reworded to reflect change to NUREG 0133 methodology.

Section reworded to reflect compliance with 10CFR20 to be based upon compliance with 40CFR190.

A 4.1 Changed title of section to "External Total Body Dose" Deleted references to deep dose equivalent.

Deleted item 3 following first paragraph and incorporated into item 2.

Changed references to "whole body" to "total body" A 4.2 Deleted CEDE Methodology A 4.3 Changed TEDE methodology to Total Dose A 5.1 Section reworded to reflect compliance with 10CFR20 to be based upon compliance with 40CFR1 90 A 5.1.1 Deleted 2nd paragraph.

A 5.1 2 Section reworded to reflect compliance with IOCFR20 to be based upon compliance with 40CFR190.

A 5.2 Changed 'whole body' to 'total body" Editorial revision: Changed "The calculation of compliance to 40CFR190 regulations is now required as part of demonstration of compliance to 10CFR290 regulations." to read, "Compliance with the 40CFR1 90 regulations is now required as part of demonstration of compliance with 10CFR20 regualtions per IOCFR20 1301(d)"

Revised equation numbers.

A 6.1 Added wording, "(not verbatim)"

A62 Changed "radionuclides" to "radionuclide" in second sentence of first paragraph Revised equation numbers Table A-1 Deleted references to CDE.

Deleted references to TEDE.

Added wording to reflect compliance with 10CFR20 to be based upon compliance with 40CFR190.

Changed "whole body" to "total body."

Added the wording "'Instantaneous' noble gas total body and skin dose rates and radioiodine, tritium and particulate inhalation dose rates to a child due to radioactivity in airborne effluents" Deleted first sentence of footnote 1.

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Appendix A (cont.)

Page or Section Change Description Table A-2 Revised Table to include "Chemical Cleaning" and 'Vent (Mixed Mode)" for Dresden 1.

Table A-3 Changed "ComEd" to "Exelon Nuclear' Table A-4 Revised equation numbers.

Changed references to "whole body" to "total body" Changed wording, "Deep Dose Equivalent" to "Total Body Dose."

Changed wording, "Committed Dose Equivalent" to "Organ Dose."

Added table note 1c Deleted table note 2.

Appendix B Page or Section Change Description Table of Contents Updated table of contents to reflect changes to Appendix B.

B.0 Added reference to gamma-X/Q.

Deleted references to meteorologically dependent dose factors Changed wording in last paragraph from, "Most of these equations..." to "These equations..."

Revised section numbers.

B.2.1 Changed "X" to "X" B.2 2 Changed "X" to "X" B.3 Revised equation numbers.

Changed first sentence of first paragraph to read, ". .provides a simplified method of calculating..."

Changed "X" to 'X" B.3 1 Changed "X" to "X" B.3.2 Changed "X" to "X" B.3.3 Changed "X" to "X" B.3.4 Deleted last sentence of 1 st paragraph.

Changed "X"to "X" B.3.5 Added section to address to gamma-x/Q methodology.

B4 Revised equation numbers.

B 4.1 Revised equation numbers.

B 4.2 Revised equation numbers.

B.4.3 Revised equation numbers.

B.5 Revised equation numbers B.5.1 Revised equation numbers p:\depts\zd84g\environsgroup\2002eff doc

Appendix B (cont.)

Page or Section Change Description B.5.2 Deleted last two sentences of last paragraph.

B.6 Renamed 'Whole Body Dose Factors" to "Gamma Total Body Dose Conversion Factor" Changed wording from "whole body" to "total body" Revised definition of dose factor in this section to correspond to NUREG 0133 methodology.

B.6.1 Deleted Stack Release Methodology B.6.2 Deleted Ground Release Methodology B.6.3 Deleted Vent Release Methodology B.7 Editorial revision. Changed title from "BETA AIR AND SKIN DOSE FACTORS" to read, "BETA AIR AND BETA SKIN DOSE CONVERSION FACTORS" Revised definition of dose factors in this section to correspond to NUREG 0133 methodology.

B.8 Revised equation numbers.

B.9 Revised equation numbers.

Editorial revision Changed "(mrem) per (pCi inhaled)" to "mrem per pCi inhaled" Deleted last paragraph.

B.10 Revised equation numbers Changed ingestion dose commitment factor from "DFAija" to "DFLja" to be consistent with the notation of Appendix A.

B.14 Deleted reference to radiological decay constants.

B.15.1 Revised equation numbers.

Revised section to reflect change to NUREG 0133 methodology.

B.15.2 Revised equation numbers.

Revised section to reflect change to NUREG 0133 methodology.

B.15.3.1 Revised section to reflect change to NUREG 0133 methodology.

B.1 5.3.1.1 Revised section to reflect change to NUREG 0133 methodology.

Deleted references to radioactive decay in transit B.15.3.1.2 Revised section to reflect change to NUREG 0133 methodology.

Deleted references to radioactive decay in transit.

B.1 5.3.2 Revised equation numbers.

Changed ingestion dose commitment factor from "DFl1ja" to "DFLija" to be consistent with the notation of Appendix A Deleted last paragraph to remove references to FGR 11 and radioactive decay in transit B.1 5.3.3 Changed "A," to "C," to be consistent with notation of Appendix A.

B 15.3.4 Deleted reference to Decay Constants p \depts\zd 84g\environsgroup\2002eff.doc

Appendix B (cont.)

Page or Section Change Description B.1 5.3.5 Renumbered.

Revised equation numbers Changed "Uwa'" and "Ufra" to S'UaW" and "U.F" to be consistent with notation of Appendix A.

B.16 Revised equation numbers.

Revised Equation A-22 to match Appendix A.

Table B-0 Added table of Noble Gas Nuclide Fractions.

Figure B-5 Deleted generic plume diagram Figure B-6 Deleted generic plume diagram.

Appendix C Page or Section Change Description Table of Contents Updated table of contents to reflect changes to Appendix C.

C.1 Deleted reference to section C 3.

C.2 Added reference to NUREG 4013 for H-3 dose factors C.3 Deleted reference to 10 CFR 20 Dose Commitment factors Table C-1 Revised equation numbers Revised to reflect change to NUREG 0133 methodology.

Deleted Basis Key "B" Changed tb from 20 years to 30 years.

Revised footnote C to read: " The parameter tb is taken as the midpoint of plant operating life (based upon an assumed 60 year plant operating lifetime)."

Table C-2 Revised terms in Variable column to reflect notation of Appendix A.

Table C-3 Changed reference to "FE" to "Ft' to be consistent with notation of Appendix A.

Table C-7 Changed nuclide abbreviation notation from "XX" to "Xx" (e.g. "BE" changed to "Be")

Table C-8 Changed reference to "B," to "BF1" to be consistent with notation of Appendix A.

Table C-9 Revised to reflect change to NUREG 0133 methodology.

Table C-10 Deleted reference to FGR 11 in table note.

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Appendix 0 Page or Section Change Description General Document Changed revision number and data Table of Contents Updated table of contents to reflect changes to Appendix 0 of ODCM.

List of Tables Changed "ComEd" to Exelon" 0.1.1 Changed "whole body" to "total body" 0.3.1 Revised to reflect changes from Reg. Guide 1.109 to NUREG 0133 methodology.

0.3.2 Revised to reflect changes from Reg Guide 1.109 to NUREG 0133 methodology.

Changed wording in first sentence of third paragraph from: "The selection of liquid pathways evaluated was based on..." to read: "The liquid pathways were evaluated based on..."

0.33 Changed "whole body" to "total body" in fifth paragraph.

0.4.1 Revised definition of time factors to agree with that of NUREG 0133, Section 2.2.

04.2 Corrected Reg Guide 1.111 Section reference.

0.4.3 Corrected reference number.

0.6 Changed- "ComEd's" to "Exelon's" 0.7.1 Corrected Reg. Guide 1.109 Section reference.

Corrected Reg. Guide 1.111 Section reference.

0.7.3 Corrected Reg. Guide 1.111 Section reference in first and second paragraph.

0.7.4 Corrected Reg. Guide 1.109 Section reference.

Corrected Reg. Guide 1.111 Section reference.

Changed ""X/Q" to "X/Q" Changed "whole body" to "total body" 0.7.5 Changed "x to "X" 0.7.6 Changed "X/Q" to "x/Q" 0.7.6.1 Changed "(X/Q),1" to "(X/Q) "

0.7.6.2 Changed reference to Reg. Guide 1.01 Changed " (X/Q) g" to " (X/Q) g 0.7.6 3 Changed wording in first sentence from: "Equation B-29 of Appendix B is the formula for calculating..." to read. "Equation B-29 of Appendix B may be used for calculating..."

Changed" (X/Q),1" to " (X/Q)V" Corrected Reg. Guide 1.111 Section reference.

0 7.6 4 Changed "X/Q" to "X/Q" p \depts\zd84g\environsgroup\2002eff.doc

Appendix 0 (cont.)

Pace or Section Change Description 0.7.6.5 Added section for Gamma-x/Q 0.7.7 Revised references to equation numbers in Appendix B.

Corrected Reg. Guide 1.111 Section reference.

0.7.8.1 Revised first paragraph to reflect use of gamma-x/Q .

Changed reference from Regulatory Guide 1.109 to NUREG 0133 in first and second paragraphs.

Changed wording in second sentence of second paragraph from: "

contains a term representing each of the three release point..." to read.

"contains terms representing the appropriate release point..."

Corrected Reg. Guide 1.111 Section reference.

Added reference for M, dose factors.

0.7.8.2 Revised references to equation numbers in Appendix B.

Corrected Reg Guide 1.111 Section reference Changed wording in first sentence of first paragraph from: "Equation A-1 of Appendix A involves the use of dose factors..." to read "Calculation of gamma-X/Q involves the use of finite plume gamma air dose factors..."

Changed wording in first two sentences of third paragraph from: " As explained in Section B.5.2 of Appendix B, the gamma air dose factor for a ground level release is obtained by a slightly modified version of Equation B-36 of Appendix B. The approach corresponds to use of a finite plume model and differs from Regulatory Guide 1.109. In the regulatory guide, dose factors for a ground level release are based on a semi-infinite cloud model (see Equation 7 of Regulatory Position B 16.b)." to read "The finite plume gamma air dose factors for a ground level release are obtained by Equation B-40 of Appendix B using the ground level joint frequency distribution data and assuming an effective release height of zero. The use of a finite plume model differs from NUREG 0133 in that ground level releases are based on a semi-infinite cloud model (see Equation 7 of Regulatory Position C.2.b)."

Changed wording in second paragraph from- "The dose factor is obtained

..." to read: "The dose factors are obtained..."

0.7.8.3 Changed wording in second sentence of first paragraph from: "...the gamma air dose factors should be..." to read: "...the gamma-X/Q values should be..."

Revised table reference.

Changed wording in third sentence of first paragraph from: "...of Appendix F are unrestricted are boundary values" to read: ".. of Appendix F are for the unrestricted area boundary" Changed wording in last sentence of first paragraph from. "...gamma air dose factors..." to read: "...gamma air dose factors used to calculate gamma-x/Q ... "

Changed wording in first sentence of last paragraph from: "The dose factors in the each station's..." to read: "The gamma air dose factors used to calculate gamma-X/Q in each station's .."

Changed wording in last sentence of last paragraph from: "...it is judged that a gamma air dose factor value..." to read: "it is judged that a gamma-X/Q value..."

0.7.9 Changed reference from Regulatory Guide 1.109 to NUREG 0133 Corrected Reg. Guide 1.111 Section reference.

Changed dose factor "LI" to "N.".

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Appendix 0 (cont.)

Page or Section Change Description 0.7.10 Changed "Whole body" to "Total body" in first paragraph Revised references to equation numbers in Appendix A in first paragraph.

Corrected Reg Guide 1.111 Section reference in first paragraph.

Changed reference from Regulatory Guide 1.109 to NUREG 0133 in first paragraph.

Added sentence. "The dose factors Ki used in Equation A-3 of Appendix A are identical to the beta air dose factors DFBi specified in Table B-1 of Regulatory Guide 1.109." in first paragraph.

Deleted rest of section.

0.7.11 Revised references to equation numbers in Appendix A Changed reference from Regulatory Guide 1.109 to NUREG 0133 Corrected Reg Guide 1.111 Section reference.

Changed wording in last sentence of first paragraph from " The dose factors Li used in Equation A-7 of Appendix A are identical to the beta skin dose..."

to read " The dose factors LI and M, used in Equation A-4 of Appendix A are identical to the gamma and beta skin dose..."

Changed wording in first sentence of last paragraph from: "... calculated with the same dose factors as used in Equation..." to read: "...calculated with gamma-X/Q in the same manner as that of Equation..."

Changed wording in the second sentence of the last paragraph from:

"...contribution due to ground level releases" to read. "...contnbution to the skin due to gamma emissions..."

Deleted last sentence of last paragraph.

0.7.12 Changed "Whole body" to "Total body" Revised references to equation numbers in Appendix A 0.7.13 Revised references to equation numbers in Appendix A.

0.7.14 Revised references to equation numbers in Appendix A.

Changed reference from Regulatory Guide 1.109 to NUREG 0133.

0.7.15 Revised references to equation numbers in Appendix A Deleted second and third sentence of first paragraph and added: " The methodology is based upon Sections 5.3 1 and 5.3 1.2 of NUREG 0133" Changed wording in last sentence of last paragraph from: "...of R.G. 1.109."

to read: "...of Regulatory Guide 1.109 and Section 5.3.1.2 of NUREG 0133" 0.7.16 Revised references to equation numbers in Appendix A.

Changed wording in first paragraph from: "It is based on Equations 13 and C-3 of Regulatory Guide 1.109 except that the relative concentration factor,

-X/Q, depends on whether the release point is elevated, vent, or ground level This is done for conformance with Regulatory Position B 16.b of Regulatory Guide 1.111." to read: "This equation is explained in Section 4.2.6. It is based on Sections 5.3.1 and 5.3.1.1 of NUREG 0133."

Deleted last sentence of first paragraph.

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Appendix 0 (cont.)

Page or Section Change Description 0.7.17 Revised references to equation numbers in Appendix A.

Changed wording in third sentence of first paragraph from. " They are similar to Equations 14 and C-5 through C-13 of Regulatory Guide 1.109 except as follows:" to read. " They are based the methodology found in Sections 5.3.1.3 through 5.3.1.5 of NUREG 0133."

Deleted bulleted paragraphs.

Deleted second sentence of last paragraph Deleted last bulleted paragraph.

0.7.18 Revised references to equation numbers in Appendix A 0.8.1 Revised references to equation numbers in Appendix A Changed wording in second sentence of first paragraph from: "The total dose is the sum..." to read: "The dose is based upon the sum..."

Deleted second paragraph and the bulleted paragraphs that followed Added reference to dilution factors "Z" and "DW" Deleted last paragraph.

0.8 2 Revised references to equation numbers in Appendix A.

0.9.1 Revised references to equation numbers in Appendix A.

Table 0.8 Changed. "ComEd" to "Exelon" Table 0.9 Changed. "ComEd" to "Exelon" p \depts\zd84g\environsg roup\2002eff.doc

• Site Specific Annexes Chapter 10, Revision 5 Page or Section Change Description Cover Page Changed revision number and date.

10.1.3.2 Changed setpoint equations to reflect revised dose rate methodology of Appendix A. Updated references to equations in Appendix A.

Chapter 11, Revision 3 Page or Section Change Description Cover Page Changed revision number and date.

Chapter 12, Revision 6 Page or Section Change Description Cover Page Changed revision number and date. Deleted Paragraph referring to ITS 12.0 Revised wording in first sentence, replaced "compliance" with "compilation".

12.1.8 Deleted references to ITS 12.1.12 Deleted references to ITS Table 12.0-1 Revised equation numbers to reflect changes in Appendix A Changed references to "whole" body dose and dose rate to "total" body dose and dose rate.

Deleted references to ITS..

Replaced references to "CDE" with "Dose".

Replaced references to "deep" dose to "external" dose.

Changed reference age group for instantaneous organ dose rate from "adult" to "child".

Table 12 0-2 Deleted references to ITS Table 12.1-1 Deleted references to ITS Table 12.3-1 Deleted footnote "7" references to dissolved and entrained noble gases.

Revised footnote "7" principle gamma emitters list.

Revised footnote "7" to change Ce-144 LLD to 5E-06.

Bases 12.4 1.C Revised to reflect changes in 10 CFR Part 20.

Specified reference age group for organ dose rate to be "child".

Table 12.5-1 Changed "Commonwealth Edison" to "Exelon Nuclear" Table 12 5-3 Changed LLDs to reflect ROG standards 12.6.1 Deleted references to ITS 12.6 2 Deleted references to ITS p \depts\zd84g\environsg roup\2002eff.doc

Appendix F, Revision 5 Page or Section Chanae Description Cover Page Changed revision number and date.

List of Tables Revised to reflect changes to Appendix F.

List of Figures Revised to reflect changes to Appendix F.

Table F-1 Editorial revision: Replaced "ocurring" with "occurring".

Changed units for water and fish consumption to "Uyr' and "kg/yre, respectively.

Revised Table to reflect changes to methodology in Appendix A.

Table F-5 Changed X/Q to X/Q Table F-5a Changed X/Q to X/Q Table F-5b Added Table F-5b, Maximum Offsite Gamma Table F-6 Broken into new Tables F-6, "X/Q and D/Q at the Nearest Resident Locations within 5 Miles," F-6a, "X'Q and D/Q at the Nearest Cow Milk Locations within 5 Miles," and F-6b IX/Q and D/Q at the Nearest Cow Meat Locations within 5 Miles" Table F-7a Deleted, redundant to Table F-7 Table 8 Added site specific potable water dose factor table for adult age group.

Table 8a Added site specific potable water dose factor table for teen age group.

Table 8b Added site specific potable water dose factor table for child age group.

Table 8c Added site specific potable water dose factor table for infant age group.

Table 9 Added site specific fish ingestion dose factor table for adult age group.

Table 9a Added site specific fish ingestion dose factor table for teen age group Table 9b Added site specific fish ingestion dose factor table for child age group Table 10 Added ground plane dose factors.

Table 11 Added adult inhalation dose factors.

Table 11a Added teen inhalation dose factors.

Table 1lb Added child inhalation dose factors.

Table Ilc Added infant inhalation dose factors.

Table 12 Added adult vegetation dose factors.

Table 12a Added teen vegetation dose factors Table 12b Added child vegetation dose factors.

Table 13 Added adult grass-cow-milk dose factors Table 13a Added teen grass-cow-milk dose factors p:\d epts\zd84g\envi ron sg rou p\2002eff.doc

Appendix F, Revision 5 (cont.)

Page or Section Chance Description Table 13b Added child grass-cow-milk dose factors.

Table 13c Added infant grass-cow-milk dose factors Table 14 Added adult grass-goat-milk dose factors.

Table 14a Added teen grass-goat-milk dose factors.

Table 14b Added child grass-goat-milk dose factors.

Table 14c Added infant grass-goat-milk dose factors.

Table 15 Added adult grass-cow-meat dose factors Table 15a Added teen grass-cow-meat dose factors.

Table 15b Added child grass-cow-meat dose factors.

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BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 UNIT 1 AND 2 (Docket Numbers 50-456 and 50457)

APPENDIX A LLD Tables p:\depts\zd84g\environsg roup\2002eff doc

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

LLD VALUES FOR GASEOUS RELEASES Isotope LLD (Ci/ml)

Alpha 9 43E-22 H-3 5.70E-14 Ar-41 5.38E-14 Mn-54 5 77E-19 Co-57 9.87E-1 9 Co-58 1.95E-1 8 Fe-59 1.34E-1 8 Co-60 2.43E-1 8 Zn-65 4.08E-1 8 Kr-85 4.94E-12 Kr-85m 5.72E-14 Kr-87 5.78E-14 Kr-88 1.45E-13 Sr-89 1 86E-20 Sr-90 2.42E-21 Mo-99 1.01E-18 1-131 9.45E-1 9 1-133 1.03E-18 Xe-1 33 2.35E-14 Xe-1 33m 3 03E-13 Cs-134 1.51 E-18 1-135 8.83E-18 Xe-135 3.82E-14 Xe-1 35m 3.88E-12 Cs-1 37 2.07E-1 8 Xe-138 3.69E-1 I Ba-140 4.45E-1 8 La-140 1.34E-18 Ce-141 1.93E-18 Ce-144 9.04E-1 8 NOTE: LLD Value for total activity released is based on LLD values for individual isotopes used in the calculation.

p.\depts\zd84g\environsgroup\2002eff doc

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

LLD VALUES FOR LIQUID RELEASES Isotope LLD (Ci/ml)

Alpha 7.55E-14 H-3 8 46E-12 Ar-41 3.60E-14 Cr-51 5.53E-13 Mn-54 5.12E-14 Fe-55 9.94E-13 Co-57 5.43E-14 Co-58 6 85E-14 Fe-59 1.03E-13 Co-60 2.26E-14 Ni-65 4.07E-1 3 Zn-65 3.86E-14 Sr-89 4.58E-14 Sr-90 1.60E-14 Nb-95 5 28E-14 Zr-97 7.83E-14 Zr-95 1.01E-13 Nb-97 1.32E-13 Mo-99 3 13E-13 Tc-99m 3 18E-13 Ag-1 Om 6.58E-14 Sb-124 6.39E-14 Sb-1 25 1.23E-13 Te-125m 1.73E-11 1-131 9.88E-14 Xe-133 1.37E-13 Cs-134 5.81 E-14 Xe-1 35 4.98E-1 4 Cs-137 2.62E-14 Ba-140 2.10E-13 La-1 40 5.63E-13 Ce-141 9.93E-14 Ce-144 3 25E-13 Na-24 2 44E-14 1-134 5.77E-14 Tc-101 2 04E-12 Cs-1 36 5.78E-14 Rb-88 7.17E-12 Br-82 1.41 E-12 NOTE: LLD Value for Total Activity Released is based on LLD Values for individual isotopes used in the calculation.

p \depts\zd84g\environsgroup\2002eff.doc

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

APPENDIX B Supplemental Information p:\depts\zd84g\environsgroup\2002eff.doc

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 UNIT COMMON (Docket Numbers 50-456 and 50-457)

GASEOUS EFFLUENTS (WASTE GAS DECAY TANKS)

SUPPLEMENTAL RELEASE INFORMATION A. Batch Release 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total

1. Total Number of Batch Releases 0 5 0 0 5

2. Total Time Period for Batch Releases (minutes) N/A 370 N/A N/A 370

3. Maximum Time Period for a Batch Release (minutes) N/A 83 N/A N/A 83

4. Average Time Period for a Batch Release (minutes) N/A 74 N/A N/A 74.0

5. Minimum Time Period for a Batch Release (minutes) N/A 60 N/A N/A 60 B. Abnormal Releases

1. Number of Releases 0 0 0 0 0

2. Total Activity Released 0.00 0.00 0.00 0.00 0.00 p:\depts\zd84g\environsg roup\2002eff doc

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 UNIT 1 (Docket Number 50-456)

GASEOUS EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION A Batch Release 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total

1. Total Number of Batch 27 28 28 30 113 Releases

2. Total Time Period for Batch Releases (minutes) 1275 1120 1290 1190 4875

3. Maximum Time Period for a Batch Release (minutes) 142 83 910 530 910

4. Average Time Period for a Batch Release (minutes) 47.2 40 46.2 39.8 43.1

5. Minimum Time Period for a Batch Release (minutes) 9 10 22 24 9 B. Abnormal Releases

1. Number of Releases 0 0 0 0 0

2. Total Activity Released 0.00 0.00 0.00 0.00 0.00 p Xdepts\zd84g\environsgroup\2002eff.doc

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 UNIT 2 (Docket Number 50-457)

GASEOUS EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION A Batch Release 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total

1. Total Number of Batch 79 37 29 29 174 Releases

2. Total Time Period for Batch Releases (minutes) 3840 9080 1090 1120 15,130

3. Maximum Time Penod for a Batch Release (minutes) 370 2010 50 54 2010

4. Average Time Period for a Batch Release (minutes) 48.6 245 37.5 38.6 87.0

5. Minimum Time Period for a Batch Release (minutes) 17 25 17 25 17 B Abnormal Releases

1. Number of Releases 0 0 0 0 0

2. Total Activity Released 0.00 0.00 0.00 0.00 0.00 p.\depts\zd84g\environsgroup\2002eff doc

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2002 UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

BRAIDWOOD NUCLEAR POWER STATION LIQUID EFFLUENTS SUPFtLEMENTAL RELEASE INFORMATION A. Batch Release 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total

1. Total Number of Batch 41 23 144 30 50 Releases

2. Total Time Period for Batch 4,180 5,450 24,510 4,280 10,600 Releases (minutes)

3. Maximum Time Period for a 622 622 305 473 478 Batch Release (minutes)

4. Average Time Period for a 102 237 170 143 212 Batch Release

5. Minimum Time Period for a 50 44 52 44 50 Batch Release (minutes)

6. Average Stream Flow During Periods of Release of Effluent 1.82E+07 2.62E+06 1.74E+06 N/A 1.4 7E+07 into a Flowing Stream (liters/min)

B. Abnormal Releases

1. Number of Releases 0 0 0 0 0

2. Total Activity Released (Ci) I).00 0.00 0.00 0.00 0.00

3. Description p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... :1 All Gas Release Types Period Start Date....: 01/01/2002 00:00 Period End Date ...... :01/01/2003 00:00 Period Duration (min): 5.256E+05 Coefficient Type ..... :Historical Unit .................  : 1

=== RELEASE DATA Total Release Duration (minutes) .............. ........................

2.407E+04 Total Release Volume (cf) ..................... 3.077E+09 Average Release Flowrate (cfm) ................ 1.278E+05 Average Period Flowrate (cfm) .......... ............................... 5.854E+03

=== NUCLIDE DATA Average EC Nuclide uci uci/cc Ratio EC AR-41 2.10E+05 2.41E-09 2.41E-01 1.OOE-08 KR-85M 9.71E+02 1.11E-11 1. llE-04 1. OOE-07 XE-135 2.98E+04 3.42E-10 4.88E-03 7.OOE-08 XE-133 1.80E+05 2.06E-09 4.13E-03 5. OOE-07 F&AG 4.21E+05 4.83E-09 2.50E-01 I-131 1. 05E+00 1.21E-14 6.03E-05 2.O0E-10 I-133 8.82E-01 1.01E-14 1. 01E-05 1.OOE-09 Iodine 1. 93E+00 2.22E-14 7. 04E-05 H-3 4.35E+06 5.OOE-08 5.OOE-01 1. OOE-07 H-3 4.35E+06 5.OOE-08 5.OOE-01 CO-58 1. 03E+00 1.18E-14 1.18E-05 1. OOE-09 P>=8 1.03E+00 1.18E-14 1.18E-05 Total_____

Total 4.78E+06 5.48E-08 7.50E-01 Date/Time: 04/25/2003 11:16 brwmn Page - 1 p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... : 1 All Gas Release Types Period Start Date .... : 01/01/2002 00:00 Period End Date ...... : 01/01/2003 00:00 Period Duration (min): 5.256E+05 Coefficient Type.....: Historical Unit ................. : 1

=== MAXIMUM I&P DOSE FOR PEFJOD Limit Organ Age Dose Limit Limit Percent Type Type Group Organ (mrem) Period (mrem) of Limit Admin Any Organ INFANT THYROID 2.OOE-03 31-day 2.25E-01 8.89E-01 Quarter 5. 63E+00 3.56E-02 Annual 1. 13E+01 1.78E-02 T.Spec Any Organ INFANT THYROID 2.OOE-03 31-day 3.OOE-01 6.67E-01 Quarter 7.50E+00 2.67E-02 Annual 1.50E+01 1.33E-02 Receptor............. 5 Composite Crit. Receptor - IP Distance (meters) .... 0.0 Compass Point........ 0.0 Critical Pathway..... 3 Grs/Goat/Milk (GMILK)

Major Contributors... 0.0  % or greater to total Nuclide Percentac 1e H-3 3.61E+01 CO-58 1.02E-02 I-131 6.34E+01 I-133 4.92E-01 Date/Time: 04/25/200: 3 11:16 brwmn Page - 2 p.\depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... : 1 All Gas Release Types Period Start Date .... : 01/01/2002 00:00 Period End Date ...... : 01/01/2003 00:00 Period Duration (min): 5.256E+05 Coefficient Type ..... : Historical Unit ................. : 1

PERIOD ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem) =======================

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB AGPD 2.14E-07 2.14E-07 2.14E-07 2.14E-07 2.14E-07 2. 14E-07 0.OOE+00 2.14E-07 AINHL 1.25E-09 1.15E-04 1.16E-04 1. 15E-04 1. 15E-04 1. 15E-04 0.OOE+00 1. 15E-04 AVEG 4.51E-08 2.07E-04 2.28E-04 2.07E-04 2. 07E-04 2.07E-04 0.OOE+00 2. 07E-04 AGMILK 1.97E-07 1.43E-04 2.34E-04 1. 43E-04 1. 42E-04 1. 42E-04 0. OOE+00 1. 42E-04 ACMEAT 5.87E-09 2.97E-05 3.24E-05 2.97E-05 2. 97E-05 2.99E-05 0.OOE+00 2.97E-05 ACMILK 1.64E-07 7.OOE-05 1.46E-04 7. 01E-05 6.97E-05 6. 99E-05 0. OOE+00 6.99E-05 TGPD 2.14E-07 2.14E-07 2.14E-07 2. 14E-07 2. 14E-07 2. 14E-07 0. OOE+00 2. 14E-07 TINHL 1.77E-09 1.16E-04 1.17E-04 1. 16E-04 1.16E-04 1. 16E-04 0. OOE+00 1. 16E-04 TVEG 4.29E-08 2.36E-04 2.54E-04 2.36E-04 2. 36E-04 2. 37E-04 0.OOE+00 2.36E-04 TGMILK 3.57E-07 1.86E-04 3.30E-04 1.86E-04 1.85E-04 1.85E-04 0.OOE+00 1.85E-04 TCMEAT 4.88E-09 1.77E-05 1.97E-05 1.77E-05 1. 77E-05 1.78E-05 0. OOE+00 1.77E-05 TCMILK 2.97E-07 9.12E-05 2.12E-04 9.15E-05 9.0 8E-05 9.09E-05 0. OOE+00 9.1OE-05 CGPD 2.14E-07 2.14E-07 2.14E-07 2.14E-07 2. 14E-07 2.14E-07 0.OOE+00 2. 14E-07 CINHL 2.40E-09 1.03E-04 1.03E-04 1.03E-04 1. 03E-04 1.03E-04 0.OOE+00 1. 03E-04 CVEG 7.98E-08 3.67E-04 3.93E-04 3.67E-04 3.67E-04 3.67E-04 0.OOE+00 3.67E-04 CGMILK 8.65E-07 2.94E-04 5.80E-04 2. 95E-04 2. 93E-04 2. 93E-04 0. OOE+00 2. 94E-04 CCMEAT 9.05E-09 2.15E-05 2.45E-05 2.15E-05 2.14E-05 2.15E-05 0.OOE+00 2. 15E-05 CCMILK 7.21E-07 1.45E-04 3.83E-04 1 .45E-04 1.44E-04 1. 44E-04 0. OOE+00 1.44E-04 IGPD 2.14E-07 2.14E-07 2.14E-07 2. 14E-07 2. 14E-07 2. 14E-07 0. OOE+00 2.14E-07 IINHL 1.90E-09 5.90E-05 5.97E-05 5.90E-05 5. 90E-05 5. 90E-05 0. OOE+00 5. 90E-05 IGMILK 1.81E-06 4.47E-04 1.14E-03 4.48E-04 4.45E-04 4 . 45E-04 0.OOE+00 4 .46E-04 ICMILK 1.50E-06 2.20E-04 7.99E-04 2.20E-04 2. 18E-04 2. 18E-04 0.OOE+00 2.19E-04

___________________________________ TOTALS -------------------------------------

ADULT 6.27E-07 5.64E-04 7.56E-04 5.65E-04 5.64E-04 5.64E-04 0.OOE+00 5.64E-04 TEEN 9.17E-07 6.47E-04 9.32E-04 6.48E-04 6.46E-04 6.47E-04 0.OOE+00 6.47E-04 CHILD 1.89E-06 9.30E-04 1.48E-03 9.31E-04 9.28E-04 9.29E-04 0.OOE+00 9.29E-04 INFANT 3.53E-06 7.26E-04 2.OOE-03 7.27E-04 7.22E-04 7.23E-04 0.OOE+00 7.24E-04

=== AGE GROUP / PATHWAY DESCRIPTIONS Abbreviation Age Group Pathway

____________ ADULT____ ________________________________

AGPD ADULT Ground Plane Deposition (GPD)

AINHL ADULT Inhalation (INHL)

AVEG ADULT Vegetation (VEG)

AGMILK ADULT Grs/Goat/Milk (GMILK)

ACMEAT ADULT Grs/Cow/Meat (CMEAT)

ACMILK ADULT Grs/Cow/Milk (CMILK)

TGPD TEEN Ground Plane Deposition (GPD)

TINHL TEEN Inhalation (INHL)

Date/Time: 04/25/2003 11:16 brwmn Page - 3 p\depts\zd84g\environsgroup\2002eff .doc

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... : 1 All Gas Release Types Period Start Date....: 01/01/2002 00:00 Period End Date ...... : 01/01/2003 00:00 Period Duration (min): 5.256E+05 Coefficient Type.....: Historical Unit ................. : 1

=== AGE GROUP / PATHWAY DESCRIPTIONS Abbreviation Age Group Pathway

____________ TEEN_____ ________________________________

TVEG TEEN Vegetation (VEG)

TGMILK TEEN Grs/Goat/Milk (GMILK)

TCMEAT TEEN Grs/Cow/Meat (CMEAT)

TCMILK TEEN Grs/Cow/Milk (CMILK)

CGPD CHILD Ground Plane Deposition (GPD)

CINHL CHILD Inhalation (INHL)

CVEG CHILD Vegetation (VEG)

CGMILK CHILD Grs/Goat/Milk (GMILK)

CCMEAT CHILD Grs/Cow/Meat (CMEAT)

CCMILK CHILD Grs/Cow/Milk (CMILK)

IGPD INFANT Ground Plane Deposition (GPD)

IINHL INFANT Inhalation (INHL)

IGMILK INFANT Grs/Goat/Milk (GMILK)

ICMILK INFANT Grs/Cow/Milk (CMILK)

Date/Time: 04/25/2003 11:16 brwmn Page - 4 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... : 1 All Gas Release Types Period Start Date .... : 01/01/2002 00:00 Period End Date ...... : 01/01/2003 00:00 Period Duration (min): 5.256E+05 Coefficient Type ..... : Historical Unit ................. : 1

=== MAXIMUM NG DOSE FOR PERIOD Limit Dose Limit Limit Percent Type Dose Type (mrad) Period (mrad) of Limit Admin Gamma 4.69E-05 31-day 1.50E-01 3.12E-02 Quarter 3.75E+00 1.25E-03 Annual 7. 50E+00 6.25E-04 Admin Beta 3.51E-05 31-day 3.OOE-01 1.17E-02 Quarter 7. 50E+00 4.68E-04 Annual 1.50E+01 2.34E-04 Ga______a T. Spec Gamma 4.69E-05 31-day 2. OOE-01 2.34E-02 Quarter 5. OOE+00 9.37E-04 Annual 1.OOE+01 4.69E-04 Receptor ................ 4 Composite Crit. Receptor - NG Distance (meters) ....... 0.0 Compass Point ........... 0.0 Major Contributors ...... 0.0 % or greater to total Nuclide Percentage AR-41 9.41E+01 KR-85M 5.75E-02 XE-135 2.75E+00 XE-133 3.06E+00 T.Spec Beta 3.51E-05 31-day 4.OOE-01 8.77E-03 Quarter 1. OOE+01 3.51E-04 Annual 2. OOE+01 1.75E-04 Receptor ................ 4 Composite Crit. Receptor - NG Distance (meters) ....... 0.0 Compass Point ........... 0.0 Major Contributors ...... 0.0  % or greater to total Nuclide Percentage AR-41 7.23E+01 KR-85M 2.01E-01 XE-135 7.68E+00 XE-133 1.98E+01 Date/Time: 04/25/2003 11:16 brwmn LAST Page - 5 p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... : 1 All Gas Release Types Period Start Date....: 01/01/2002 00:00 Period End Date ...... : 01/01/2003 00:00 Period Duration (min): 5.256E+05 Coefficient Type.....: Historical Unit ................. : 2

=== RELEASE DATA Total Release Duration (minutes).............. 4.117E+04 Total Release Volume (cf)..................... 4.041E+09 Average Release Flowrate (cfm)................ 9.815E

+04 Average Period Flowrate (cfm).................. 7.688E+03

=== NUCLIDE DATA Average EC Nuclide uci uci/cc Ratio EC AR-41 3.02E+05 2.64E-09 2. 64E-01 1. OOE-08 KR-85M 9.71E+02 8.48E-12 8 .48E-05 1. 00E-07 XE-135 4 .41E+04 3.86E-10 5.51E-03 7. OOE-08 XE-133 3.62E+05 3.17E-09 6.33E-03 5. 00E-07 F&AG 7. 10E+05 6.20E-09 2.76E-01 I-131 2. 75E+00 2.40E-14 1.20E-04 2.00E-10 Iodine 2.75E+00 2.40E-14 1.20E-04 H-3 2. 52E+05 2.21E-09 2.21E-02 1. OOE-07 H-3 2. 52E+05 2.21E-09 2.21E-02 CO-57 3.03E+00 2.65E-14 2. 95E-05 9.00E-10 CO-58 2.38E+00 2.08E-14 2. 08E-05 1. 00E-09 5_______ 4.______ _________

P>=8 5. 41E+00 4.73E-14 5.02E-05 Total 9.62E+05 8.41E-09 2.98E-01 Date/Time: 04/21/2003 15:00 brwmn Page - 1 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... : 1 All Gas Release Types Period Start Date .... : 01/01/2002 00:00 Period End Date . ..: 01/01/2003 00:00 Period Duration (min): 5.256E+05 Coefficient Type ..... : Historical Unit ................. : 2

=== MAXIMUM I&P DOSE FOR PEEJIOD Limit Organ Age Dose Limit Limit Percent Type Type Group Organ (mrem) Period (mrem) of Limit Admin Any Organ INFANT THYROID 3.36E-03 31-day 2.25E-01 1.49E+00 Quarter 5.63E+00 5.97E-02 Annual 1.13E+01 2.99E-02 T.Spec Any Organ INFANT THYROID 3.36E-03 31-day 3. OOE-01 1.12E+00 Quarter 7.50E+00 4.48E-02 Annual 1. 50E+01 2.24E-02 Receptor............. 5 Composite Crit. Receptor - IP Distance (meters) .... 0.0 Compass Point........ 0.0 Critical Pathway..... 3 Grs/Goat/Milk (GMILK)

Major Contributors... 0.0  % or greater to total Nuclide Percentac 1e H-3 1.25E+00 CO-58 1.40E-02 I-131 9.87E+01 Date/Time: 04/21/200:3 15:00 brwmn Page - 2 p:\depts\zd84g\environsg roup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... : 1 All Gas Release Types Period Start Date .... : 01/01/2002 00:00 Period End Date ...... : 01/01/2003 00:00 Period Duration (min): 5.256E+05 Coefficient Type ..... : Historical Unit ................. : 2

PERIOD ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem) =======================

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB AGPD 4. 95E-07 4.95E-07 4.95E-07 4.95E-07 4. 95E-07 4. 95E-07 0. OOE+00 4. 95E-07 AINHL 2.55E-09 6.67E-06 7.88E-06 6.68E-06 6.75E-06 6.68E-06 0.OOE+00 6.67E-06 AVEG 1. 16E-07 1.22E-05 6.61E-05 1.23E-05 1.20E-05 1.28E-05 0.OOE+00 1.21E-05 AGMILK 5.08E-07 8.97E-06 2.47E-04 9.49E-06 8.24E-06 8. 45E-06 0. 00E+00 8. 66E-06 ACMEAT 1.54E-08 1.77E-06 8.92E-06 1.76E-06 1.72E-06 2. 18E-06 0. OOE+00 1.78E-06 ACMILK 4.24E-07 4.65E-06 2.03E-04 5.08E-06 4. 04E-06 4.32E-06 0.OOE+00 4. 40E-06 TGPD 4. 95E-07 4.95E-07 4.95E-07 4.95E-07 4. 95E-07 4. 95E-07 0.00E+00 4.95E-07 TINHL 3.58E-09 6.74E-06 8.21E-06 6.74E-06 6. 85E-06 6. 74E-06 0.OOE+00 6.73E-06 TVEG 1. 10E-07 1.39E-05 5.86E-05 1.40E-05 1. 37E-05 1. 45E-05 0.0OE+00 1.39E-05 TGMILK 9. 23E-07 1.20E-05 3.88E-04 1.29E-05 1. 07E-05 1. lOE-05 0.0OE+00 1. 14E-05 TCMEAT 1.28E-08 1.06E-06 6.24E-06 1.06E-06 1. 03E-06 1.27E-06 0.OOE+00 1.07E-06 TCMILK 7. 69E-07 6.34E-06 3.19E-04 7.11E-06 5.26E-06 5. 61E-06 0.OOE+00 5.86E-06 CGPD 4. 95E-07 4.95E-07 4.95E-07 4.95E-07 4.95E-07 4 .95E-07 0.OOE+00 4.95E-07 CINHL 4.86E-09 5.95E-06 7.59E-06 5.95E-06 6.04E-06 5.95E-06 0.OOE+00 5.95E-06 CVEG 2.05E-07 2.16E-05 8.93E-05 2.16E-05 2. 13E-05 2.17E-05 0. OOE+00 2.16E-05 CGMILK 2.24E-06 1.92E-05 7.61E-04 2.07E-05 1.70E-05 1. 72E-05 0.OOE+00 1. 83E-05 CCMEAT 2. 37E-08 1.29E-06 9.12E-06 1.28E-06 1.24E-06 1.36E-06 0.OOE+00 1.32E-06 CCMILK 1.86E-06 1.02E-05 6.29E-04 1.14E-05 8.33E-06 8.59E-06 0. OOE+00 9.4 4E-06 IGPD 4. 95E-07 4.95E-07 4.95E-07 4.95E-07 4. 95E-07 4. 95E-07 0. OOE+00 4. 95E-07 IINHL 3.84E-09 3.42E-06 4.92E-06 3.42E-06 3. 49E-06 3. 42E-06 0. OOE+00 3. 42E-06 IGMILK 4. 67E-06 3.13E-05 1.83E-03 3.22E-05 2.58E-05 2. 60E-05 0.OOE+00 2. 82E-05 ICMILK 3.89E-06 1.73E-05 1.52E-03 1.80E-05 1.26E-05 1.29E-05 0.OOE+00 1. 47E-05 TOTALS -------------------------------------

ADULT 1.56E-06 3.47E-05 5.33E-04 3.58E-05 3.32E-05 3.49E-05 0.OOE+00 3.42E-05 TEEN 2.31E-06 4.06E-05 7.80E-04 4.23E-05 3.80E-05 3.96E-05 0.OOE+00 3.95E-05, CHILD 4.83E-06 5.87E-05 1.50E-03 6.14E-05 5.44E-05 5.53E-05 0.OOE+00 5.71E-05 INFANT 9.06E-06 5.25E-05 3.36E-03 5.41E-05 4.24E-05 4.28E-05 0.OOE+00 4.69E-05

=== AGE GROUP / PATHWAY DESCRIPTIONS Abbreviation Age Group Pathway AGPD ADULT Ground Plane Deposition (GPD)

AINHL ADULT Inhalation (INHL)

AVEG ADULT Vegetation (VEG)

AGMILK ADULT Grs/Goat/Milk (GMILK)

ACMEAT ADULT Grs/Cow/Meat (CMEAT)

ACMILK ADULT Grs/Cow/Milk (CMILK)

TGPD TEEN Ground Plane Deposition (GPD)

TINHL TEEN Inhalation (INHL)

Date/Time: 04/21/2003 15:00 brwmn Page - 3 pNdepts'~zd84g~environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... : 1 All Gas Release Types Period Start Date....: 01/01/2002 00:00 Period End Date ...... : 01/01/2003 00:00 Period Duration (min): 5.256E+05 Coefficient Type ..... : Historical Unit ................. : 2

=== AGE GROUP / PATHWAY DESCRIPTIONS Abbreviation Age Group Pathway

____________ TEEN-----

TVEG TEEN Vegetation (VEG)

TGMILK TEEN Grs/Goat/Milk (GMILK)

TCMEAT TEEN Grs/Cow/Meat (CMEAT)

TCMILK TEEN Grs/Cow/Milk (CMILK)

CGPD CHILD Ground Plane Deposition (GPD)

CINHL CHILD Inhalation (INHL)

CVEG CHILD Vegetation (VEG)

CGMILK CHILD Grs/Goat/Milk (GMILK)

CCMEAT CHILD Grs/Cow/Meat (CMEAT)

CCMILK CHILD Grs/Cow/Milk (CMILK)

IGPD INFANT Ground Plane Deposition (GPD)

IINHL INFANT Inhalation (INHL)

IGMILK INFANT Grs/Goat/Milk (GMILK)

ICMILK INFANT Grs/Cow/Milk (CMILK)

Date/Time: 04/21/2003 15:00 brwmn Page - 4 p.\depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... : 1 All Gas Release Types Period Start Date....: 01/01/2002 00:00 Period End Date ...... : 01/01/2003 00:00 Period Duration (min): 5.256E+05 Coefficient Type ..... : Historical Unit ................. : 2

=== MAXIMUM NG DOSE FOR PERIOD Limit Dose Limit Limit Percent Type Dose Type (mrad) Period (mrad) of Limit Admin Gamma 6.83E-05 31-day 1. 50E-01 4.55E-02 Quarter 3.75E+00 1.82E-03 Annual 7.50E+00 9.11E-04 Admin Beta 5.46E-05 31-day 3. OOE-01 1.82E-02 Quarter 7.50E+00 7.28E-04 Annual 1.50E+01 3.64E-04 T.Spec Gamma 6.83E-05 31-day 2. OOE-01 3.42E-02 Quarter 5. OOE+00 1.37E-03 Annual 1. OOE+01 6.83E-04 Receptor ................  : 4 Composite Crit. Receptor - NG Distance (meters).......  : 0.0 Compass Point ...........  : 0.0 Major Contributors ......  : 0.0 % or greater to total Nuclide Percentage AR-41 9.29E+01 KR-85M 3.95E-02 XE-135 2.80E+00 XE-133 4.23E+00 T.Spec Beta 5.46E-05 31-day 4 . 0OE-01 1. 36E-02 Quarter 1. 00E+01 5. 46E-04 Annual 2.OOE+01 2.73E-04 Receptor ................ 4 Composite Crit. Receptor - NG Distance (meters) ....... 0.0 Compass Point ........... 0.0 Major Contributors ...... 0.0  % or greater to total Nuclide Percentage AR-41 6.69E+01 KR-85M 1.29E-01 XE-135 7.32E+00 XE-133 2.57E+01 Date/Time: 04/21/2003 15:00 brwmn LAST Page - 5 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(---- (PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05 Unit .................. : 1

== MULTIPLE RELEASE POINT MESSAGE

Undiluted and Diluted Flowrate(s) and Concentration(s) cannot be combined.

=== RELEASE DATA Total Release Duration (minutes) ..................................... 5.069E+05 Total Undiluted Volume Released (gallons) ............................ NA Average Undiluted Flowrate (gpm) ..................................... NA Total Dilution Volume (gallons) ...................................... NA Average Dilution Flowrate (gpm) ...................................... NA

=== NUCLIDE DATA Nuclide uCi CO-57 5.54E+01 BR-82 5.81E+02 NB-97 1.33E+02 SB-124 3.91E+03 SB-125 9.01E+03 TE-123M 2.57E+03 NA-24 4.16E+00 CR-51 1.40E+03 MN-54 1.02E+03 FE-59 1.40E+02 CO-58 1.84E+04 CO-60 1.02E+04 NI-65 8.61E+00 RB-88 4.10E+01 ZR-95 4.35E+01 ZR-97 3.OOE+00 NB-95 2.80E+02 TC-99M 5.21E+00 TC-101 1.20E+01 AG-llOM 3.45E+02 TE-125M 4.85E+03 I-131 3.08E+00 I-134 1.98E+01 CS-136 5.91E+00 CS-137 3.87E+01 BA-140 2.89E+02 Gamma 5.33E+04 Date/Time: 04/21/2003 15:04 brwmn Page - 1 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05

== NUCLIDE DATA

Nuclide uCi KR-85 1.06E+03 XE-131M 1.25E+02 XE-135 3.83E+00 XE-133 1.34E+03 XE-138 1.17E+01 D&EG 2.54E+03 H-3 1. 17E+09 Beta 1. 17E+09 Total____ ________

Total 1. 17E+09 Date/Time: 04/21/2003 15:04 brwmn Page - 2 p:\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS - BY UNIT) ------

Release ID ............ 1: All Liquid Release Types Period Start Date .....  : 01/01/2002 00:00 Period End Date .......  : 01/01/2003 00:00 Period Duration (mins): 5.256E+05 Unit ..................  : l Receptor ..............  : 0 Liquid Receptor

PERMIT ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem) =======================

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB 0.00E+OO APWtr 4. 87E-06 1. 74E-02 1.74E-02 1.74E-0 2 1. 74E-02 1.76E-02 0. OOE+00 1. 74E-02 AFWFSp 1. 15E-03 8. 64E-03 7.38E-03 9. 66E-0 3 7.31E-03 3.08E-02 0. OOE+00 8.28E-03 TPWtr 4. 82E-06 1. 23E-02 1.23E-02 1. 23E-0 2 1. 23E-02 1.24E-02 0.00E+00 1. 23E-02 TFWFSp 1.23E-03 7. 01E-03 5.70E-03 5. 91E-0 3 5. 66E-03 2.23E-02 0.OOE+00 6.38E-03 CPWtr 1. 42E-05 2.36E-02 2.36E-02 2.35E-0 2 2.35E-02 2.36E-02 0.OOE+00 2.36E-02 CFWFSp 1. 57E-03 5. 89E-03 4.80E-03 4. 90E-0 3 4. 69E-03 1.06E-02 0.OOE+00 5.28E-03 IPWtr 1. 82E-05 2. 31E-02 2.31E-02 2.31E-0 2 2.31E-02 2.32E-02 0.00E+00 2.32E-02 TOTALS _____________________________________

ADULT 1. 15E-03 2. 61E-02 2.48E-02 2. 71E-0 2 2.47E-02 4.83E-02 0.00E+00 2.57E-02 TEEN 1.24E-03 1. 93E-02 1.80E-02 1. 82E-0 2 1.79E-02 3.47E-02 0.00E+00 1.87E-02 CHILD 1.58E-03 2. 95E-02 2.83E-02 2.84E-0 2 2.82E-02 3.43E-02 0.00E+00 2.89E-02 INFANT 1. 82E-05 2. 31E-02 2.31E-02 2. 31E-0 2 2.31E-02 2.32E-02 0.00E+00 2.32E-02

=== AGE GROUP / PATHWAY DESCRIPTIONS Abbreviation Age Group Pathway APWtr ADULT Potable Water (PWtr)

AFWFSp ADULT Fresh Water Fish - Sport (FFSP)

TPWtr TEEN Potable Water (PWtr)

TFWFSp TEEN Fresh Water Fish - Sport (FFSP)

CPWtr CHILD Potable Water (PWtr)

CFWFSp CHILD Fresh Water Fish - Sport (FFSP)

IPWtr INFANT Potable Water (PWtr)

Date/Time: 04/21/2003 15: 04 brwmn Page - 3 p:\depts\zd84g\environsg roup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05 Unit .................. : 1 Receptor .............. : 0 Liquid Receptor

=== PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT H-3 0. OOE+00 2.4 6E-02 2.4 6E-02 2.4 6E-02 2. 46E-02 2.46E-02 0. OE+00 2.4 6E-02 NA-24 7. 15E-08 7. 15E-08 7. 15E-08 7. 15E-08 7. 15E-08 7.15E-08 0. OOE+00 7. 15E-08 CR-51 0.OOE+00 0.OOE+00 4 .47E-08 1. 65E-08 9.91E-08 1.88E-05 0. OOE+00 7. 47E-08 MN-54 0.OOE+00 1.85E-04 0. OOE+00 5.51E-05 0.OOE+00 5. 68E-04 0.OOE+00 3.54E-05 FE-59 6. 15E-06 1.45E-05 0.OOE+00 0.OOE+00 4.04E-06 4.82E-05 0. 00E+00 5.54E-06 CO-58 0. OOE+00 7.06E-05 0.OOE+00 0.OOE+00 0. OOE+00 1. 43E-03 0. OOE+00 1.58E-04 CO-60 0.OOE+00 1. 12E-04 0. OOE+00 0. OOE+00 0. OOE+00 2. liE-03 0. OOE+00 2.47E-04 NI-65 4.59E-08 5. 97E-09 0. OOE+00 0.OOE+00 0. OOE+00 1.51E-07 0. OOE+00 2.72E-09 RB-88 0.OOE+00 4. 92E-07 0.OOE+00 0. OE+00 0.OOE+00 6.80E-18 0. OOE+00 2. 61E-07 ZR-95 7.16E-10 2.29E-10 0. OOE+00 3.60E-10 0. OOE+00 7.27E-07 0.0OE+00 1. 55E-10 ZR-97 2.73E-12 S.50E-13 0.OOE+00 8. 31E-13 0.0OE+00 1.71E-07 0.0OE+00 2.52E-13 NB-95 5. 17E-06 2. 88E-06 0.0OE+00 2. 84E-06 0.OOE+00 1.75E-02 0. OOE+00 1. 55E-06 TC-99M 2. 19E-12 6.18E-12 0. OOE+00 9.39E-11 3.03E-12 3.66E-09 0. OOE+00 7. 88E-il TC-101 5. 18E-12 7. 47E-12 0. OOE+00 1.34E-10 3. 82E-12 2.24E-23 0. OOE+00 7. 33E-l1 AG-ilOM 2. 44E-08 2.26E-08 0. OOE+00 4.45E-08 0. OOE+00 9.23E-06 0. OOE+00 1.34E-08 TE-125M 5.17E-04 1.87E-04 1.55E-04 2. lOE-03 0. OOE+00 2.06E-03 0. OOE+00 6.92E-05 I-131 2. 18E-08 3.11E-08 1.02E-05 5.33E-08 0.OOE+00 8.21E-09 0. OOE+00 1.78E-08 I-134 3. 56E-09 9.67E-09 1. 68E-07 1.54E-08 0. OOE+00 8 .43E-12 0. OOE+00 3.4 6E-09 CS-136 7. 62E-06 3. 01E-05 0. OOE+00 1. 67E-05 2.29E-06 3.42E-06 0. OOE+00 2.17E-05 CS-137 6.11E-04 8.35E-04 0. OOE+00 2.84E-04 9. 43E-05 1. 62E-05 0. OOE+00 5.47E-04 BA-140 3.58E-06 4.50E-09 0.OOE+00 1.53E-09 2.58E-09 7. 38E-06 0. OOE+00 2.35E-07 TEEN H-3 0. OOE+00 1.78E-02 1.78E-02 1.78E-02 1.78E-02 1.78E-02 0.OOE+00 1.78E-02 NA-24 7.36E-08 7. 36E-08 7.36E-08 7. 36E-08 7.36E-08 7.36E-08 0.OOE+00 7.36E-08 CR-51 0.OOE+00 0.OOE+00 4.28E-08 1.69E-08 1.10E-07 1.29E-05 0.0OE+00 7.70E-08 MN-54 0. OOE+00 1. 82E-04 0. OOE+00 5. 43E-05 0. OOE+00 3.74E-04 0.OOE+00 3.61E-05 FE-59 6.33E-06 1.48E-05 0.OOE+00 0.OOE+00 4. 66E-06 3.4 9E-05 0.OOE+00 5.7OE-06 CO-58 0.OOE+00 7. OOE-05 0. OOE+00 0.OOE+00 0. OOE+00 9.64E-04 0. OOE+00 1. 61E-04 CO-60 0.OOE+00 1. 12E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.4 6E-03 0.OOE+00 2.52E-04 NI-65 4. 95E-08 6.33E-09 0.OOE+00 0.OOE+00 0.OOE+00 3. 43E-07 0. OOE+00 2. 88E-09 RB-88 0. OOE+00 5.28E-07 0.OOE+00 0.OOE+00 0.OOE+00 4.52E-14 0.OOE+00 2.81E-07 ZR-95 7. 14E-10 2.25E-10 0.OOE+00 3.31E-10 0.OOEE+00 5.20E-07 0.OOE+00 1.55E-10 ZR-97 2. 84E-12 5. 61E-13 0. OOE+00 8.51E-13 0. OOE+00 1. 52E-07 0. OOE+00 2.58E-13 NB-95 5.21E-06 2.89E-06 0.OOE+00 2.80E-06 0. OOE+00 1.24E-02 0. OOE+00 1.59E-06 TC-99M 2.22E-12 6.19E-12 0. OOE+00 9.22E-l1 3. 43E-12 4.06E-09 0. OOE+00 8.01E-ll TC-101 5.54E-12 7. 88E-12 0.OOE+00 1. 43E-10 4 .80E-12 1. 35E-18 0. OOE+00 7.74E-ll AG-llOM 2.29E-08 2.17E-08 0.OOE+00 4 .13E-08 0.0OE+00 6.09E-06 0.OOE+00 1.32E-08 TE-125M 5. 63E-04 2. 03E-04 1. 57E-04 0. OOE+00 0.0OE+00 1. 66E-03 0. OOE+00 7. 52E-05 Date/Time: 04/21/2003 15:04 brwmn Page - 4 p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05

=== PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB 0.______

I-131 2.31E-08 3. 23E-08 9.42E-06 5.56E-08 0. OOE+00 6.39E-09 0. OE+00 1. 73E-08 I-134 3.70E-09 9.80E-09 1. 63E-07 1.54E-08 0.OOE+00 1.29E-10 0.OOE+00 3.52E-09 CS-136 7. 66E-06 3.02E-05 0.OOE+00 1. 64E-05 2.59E-06 2.43E-06 0.OOE+00 2. 03E-05 CS-137 6.54E-04 8.70E-04 0.OOE+00 2. 96E-04 1.15E-04 1.24E-05 0. OOE+00 3.03E-04 BA-140 3.71E-06 4. 54E-09 0. OOE+00 1.54E-09 3. 05E-09 5.72E-06 0. 00E+00 2.39E-07 CHILD H-3 0.OOE+00 2.81E-02 2. 81E-02 2. 81E-02 2. 81E-02 2.81E-02 0.OOE+00 2. 81E-02 NA-24 8.21E-08 8.21E-08 8.21E-08 8. 21E-08 8.21E-08 8.21E-08 0.OOE+00 8.21E-08 CR-51 0.OOE+00 0. OOE+00 4.61E-08 1.26E-08 8.43E-08 4.41E-06 0. OOE+00 8. 31E-08 MN-54 0. OOE+00 1.43E-04 0.OOE+00 4.02E-05 0.OOE+00 1.20E-04 0. OOE+00 3. 82E-05 FE-59 7.87E-06 1.27E-05 0.OOE+00 0.OOE+00 3.69E-06 1.33E-05 0. OOE+00 6.34E-06 CO-58 0.0OE+00 5. 87E-05 0.OOE+00 0.OOE+00 0.OOE+00 3.42E-04 0.0OE+00 1. BOE-04 CO-60 0.OOE+00 9.54E-05 0. OOE+00 0. OOE+00 0.OOE+00 5.28E-04 0.OOE+00 2. 81E-04 NI-65 6.50E-08 6.12E-09 0.OOE+00 0. OOE+00 0. OOE+00 7.4 9E-07 0. OOE+00 3.57E-09 RB-88 0. OE+00 5. 08E-07 0.OOE+00 0.OOE+00 0.OOE+00 2.4 9E-08 0. OOE+00 3.53E-07 ZR-95 1.30E-09 2.85E-10 0. OOE+00 4. 08E-10 0.00E+00 2. 98E-07 0. OOE+00 2.54E-10 ZR-97 5. 40E-12 7.80E-13 0. OOE+00 1. 12E-12 0.OOE+00 1. 18E-07 0. OOE+00 4. 60E-13 NB-95 6.15E-06 2.39E-06 0.OOE+00 2.25E-06 0.OOE+00 4.43E-03 0.OOE+00 1.71E-06 TC-99M 3. 07E-12 6.02E-12 0.0OE+00 8.75E-il 3.06E-12 3. 42E-09 0. OOE+00 9. 98E-11 TC-101 8. 19E-12 8.58E-12 0. OOE+00 1. 46E-10 4. 54E-12 2.73E-11 0. OOE+00 1. 09E-10 AG-llOM 4.19E-08 2. 83E-08 0. OOE+00 5.27E-08 0.OOE+00 3. 36E-06 0. OOE+00 2.26E-08 TE-125M 7.27E-04 1. 97E-04 2. 04E-04 0.OOE+00 0.OOE+00 7. 01E-04 0.OOE+00 9.69E-05 I-131 3.38E-08 3. 40E-08 1. 12E-05 5.58E-08 0.OOE+00 3.02E-09 0.0OE+00 1.93E-08 I-134 5.28E-09 9.81E-09 2.26E-07 1. 50E-08 0. OOE+00 6.50E-09 0. OOE+00 4.51E-09 CS-136 9.05E-06 2.49E-05 0. OOE+00 1.33E-05 1.98E-06 8.74E-07 0. OOE+00 1. 61E-05 CS-137 8.24E-04 7.89E-04 0. OOE+00 2. 57E-04 9.25E-05 4. 94E-06 0. OOE+00 1.16E-04 BA-140 6.73E-06 5.89E-09 0. OOE+00 1. 92E-09 3.51E-09 3. 41E-06 0.OOE+00 3. 93E-07 INFANT H-3 0.OOE+00 2.31E-02 2.31E-02 2.31E-02 2.31E-02 2.31E-02 0. OOE+00 2. 31E-02 NA-24 4. 09E-09 4.09E-09 4.09E-09 4. 09E-09 4.09E-09 4.09E-09 0. OOE+00 4.09E-09 CR-51 0.OOE+00 0. OOE+00 1.26E-09 2.74E-10 2.44E-09 5. 61E-08 0.0OE+00 1. 92E-09 MN-54 0.OOE+00 1.97E-06 0.OOE+00 4. 37E-07 0.OOE+00 7.24E-07 0. OOE+00 4 .47E-07 FE-59 4. 20E-07 7.33E-07 0. OOE+00 0. OOE+00 2. 17E-07 3.50E-07 0. OOE+00 2.89E-07 CO-58 0.OOE+00 6. 42E-06 0.OOE+00 0. OE+00 0.OOE+00 1.60E-05 0.OOE+00 1. 60E-05 CO-60 0.OOE+00 1. 07E-05 0. OOE+00 0. OOE+00 0.OOE+00 2.54E-05 0. OOE+00 2. 52E-05 NI-65 3. 93E-09 4. 45E-10 0.OOE+00 0.OOE+00 0.OOE+00 3.39E-08 0. OOE+00 2.02E-10 RB-88 0.OOE+00 1. 99E-09 0.OOE+00 0. OOE+00 0.OOE+00 1. 93E-09 0.OOE+00 1. 09E-09 ZR-95 8.70E-10 2.12E-10 0. OOE+00 2.29E-10 0. OOE+00 1. 06E-07 0. OOE+00 1.50E-10 ZR-97 4.31E-12 7.40E-13 0. OOE+00 7.46E-13 0. OOE+00 4. 72E-08 0. OOE+00 3. 38E-13 Date/Time: 04/21/2003 15:04 brwmn Page - 5 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

-- (PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05

PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem) =======================

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB NB-95 1.14E-09 4.71E-10 0.OOE+00 3.38E-10 0. OOE+00 3. 97E-07 0.00E+00 2.72E-10 TC-99M 9.73E-13 2.01E-12 0.OOE+00 2.16E-11 1. 05E-12 5.83E-10 0.OOE+00 2.58E-11 TC-101 2.65E-12 3.34E-12 0.OOE+00 3. 97E-11 1. 82E-12 5.67E-10 0. OOE+00 3.30E-1l AG-llOM 3.34E-08 2.44E-08 0.00E+00 3.4 9E-08 0. OOE+00 1.26E-06 0.OOE+00 1. 61E-08 TE-125M 1.10E-05 3.67E-06 3.69E-06 0.OOE+00 0. OOE+00 5.23E-06 0.OOE+00 1.48E-06 I-131 1.07E-08 1.26E-08 4.16E-06 1.48E-08 0. OOE+00 4.52E-10 0. O0E+00 5.56E-09 I-134 1.67E-09 3.42E-09 7.97E-08 3.82E-09 0. OOE+00 3.53E-09 0.0OE+00 1.22E-09 CS-136 2.64E-08 7.76E-08 0.OOE+00 3.09E-08 6.32E-09 1.18E-09 0.0OE+00 2.89E-08 CS-137 1.96E-06 2.30E-06 0.00E+00 6.16E-07 2. 50E-07 7.18E-09 0.0OE+00 1.63E-07 BA-140 4.80E-06 4.80E-09 0.OOE+00 1.14E-09 2. 95E-09 1.18E-06 0. OOE+00 2.47E-07 Date/Time: 04/21/2003 15:04 brwmn Page - 6 p \depts\zd84g\environsgroup\2002eff.doc

lI RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS - BY UNIT) --

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05 Unit .................. : 1 Receptor .............. : 0 Liquid Receptor

=== MAXIMUM DOSE FOR PERIOD Limit Organ Age Dose Limit Limit Percent Type Type Group Organ (mrem) Period (mrem) of Limit Admin Any Organ ADULT GILLI 4.83E-02 31-day 1.50E-01 3.22E+01 Quarter 3.75E+00 1.29E+00 Annual 7.50E+00 6.45E-01 Admin Tot Body CHILD TBODY 2.89E-02 31-day 4.50E-02 6.42E+01 Quarter 1.13E+00 2.57E+00 Annual 2.25E+00 1.28E+00 T.Spec Any Organ ADULT GILLI 4.83E-02 31-day 2.OOE-01 2.42E+01 Quarter 5.OOE+00 9.67E-01 Annual 1.00E+01 4.83E-01 Critical Pathway ........ 1 Fresh Water Fish - Sport (FFSP Major Contributors ...... 0.0 % or greater to total Nuclide Percentage H-3 5.09E+01 NA-24 1.48E-04 CR-51 3.89E-02 MN-54 1.17E+00 FE-59 9.97E-02 CO-58 2.96E+00 CO-60 4.36E+00 NI-65 3.13E-04 RB-88 1.41E-14 ZR-95 1.50E-03 ZR-97 3.53E-04 NB-95 3.61E+01 TC-99M 7.57E-06 TC-101 4.64E-20 AG-llOM 1.91E-02 TE-125M 4.27E+00 I-131 1.70E-05 I-134 1.74E-08 CS-136 7.07E-03 CS-137 3.34E-02 BA-140 1.53E-02 Date/Time: 04/21/2003 15:04 brwmn Page - 7 p:\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS - BY UNIT) ------

(-

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05

=== MAXIMUM DOSE FOR PERIOD = = = = = = = = = = = = = = ==Dose Limit Organ Age Dose Limit Limit Percent Type Type Group Organ (mrem) Period (mrem) of Limit T.Spec Tot Body CHILD TBODY 2.89E-02 31-day 6.OOE-02 4.81E+01 Quarter 1. 50E+00 1. 92E+00 Annual 3. OOE+00 9.62E-01 Critical Pathway ........ 0 Potable Water (PWtr)

Major Contributors ...... 0.0 % or greater to total Nuclide Percentage H-3 9.74E+01 NA-24 2.84E-04 CR-51 2.88E-04 MN-54 1.32E-01 FE-59 2.20E-02 CO-58 6.22E-01 CO-60 9.74E-01 NI-65 1.24E-05 RB-88 1.22E-03 ZR-95 8.80E-07 ZR-97 1.59E-09 NB-95 5.92E-03 TC-99M 3.46E-07 TC-101 3.77E-07 AG-llOM 7.83E-05 TE-125M 3.36E-01 I-131 6.68E-05 I-134 1.56E-05 CS-136 5.58E-02 CS-137 4.03E-01 BA-140 1.36E-03 Date/Time: 04/21/2003 15:04 brwmn LAST Page - 8 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS - BY UNIT) ------

Release ID............ 1 All Liquid Release Types Period Start Date ..... 01/01/2002 00:00 Period End Date ....... 01/01/2003 00:00 Period Duration (mins): 5.256E+05 Unit .................. : 2

== MULTIPLE RELEASE POINT MESSAGE

Undiluted and Diluted Flowrate(s) and Concentration(s) cannot be combined.

=== RELEASE DATA Total Release Duration (minutes)..................................... 5.069E+05 Total Undiluted Volume Released (gallons) ............................ NA Average Undiluted Flowrate (gpm)..................................... NA Total Dilution Volume (gallons) ...................................... NA Average Dilution Flowrate (gpm) ...................................... NA

=== NUCLIDE DATA Nuclide uCi CO-57 5.54E+01 BR-82 5.81E+02 NB-97 1.33E+02 SB-124 3.91E+03 SB-125 9.01E+03 TE-123M 2.57E+03 NA-24 4.16E+00 CR-51 1.40E+03 MN-54 1.02E+03 FE-59 1.40E+02 CO-58 1.84E+04 CO-60 1.02E+04 NI-65 8.61E+00 RB-88 4.10E+01 ZR-95 4.35E+01 ZR-97 3.OOE+00 NB-95 2.80E+02 TC-99M 5.21E+00 TC-101 1.20E+01 AG-llOM 3.45E+02 TE-125M 4.85E+03 I-131 3.08E+00 I-134 1.98E+01 CS-136 5.91E+00 CS-137 3.87E+01 BA-140 2.89E+02 Gamma 5.33E+04 Date/Time: 04/21/2003 15:06 brwmn Page - 1 p.\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05

=== NUCLIDE DATA Nuclide uCi KR-85 1.06E+03 XE-131M 1.25E+02 XE-135 3.83E+00 XE-133 1.34E+03 XE-138 1.17E+01 D&EG 2.54E+03 H-3 1. 17E+09 Beta 1.17E+09 Total 1.17E+09 Date/Time: 04/21/2003 15:06 brwmn Page - 2 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

- (PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05 Unit ................... 2 Receptor .......  : 0 Liquid Receptor

=== PERMIT ORGAN DOSE BY AGE GROUP AND PATHWAY (mrem)

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB APWtr 4.87E-06 1.74E-02 1.74E-02 1.74E-02 1.74E-02 1. 76E-02 0.OOE+00 1.74E-02 AFWFSp 1. 15E-03 8. 64E-03 7. 38E-03 9.66E-03 7.31E-03 3. 08E-02 0. OOE+00 8.28E-03 TPWtr 4. 82E-06 1. 23E-02 1. 23E-02 1.23E-02 1.23E-02 1.24E-02 0.OOE+00 1.23E-02 TFWFSp 1. 23E-03 7.01E-03 5.70E-03 5.91E-03 5. 66E-03 2. 23E-02 0. OOE+00 6.38E-03 CPWtr 1.42E-05 2.36E-02 2.36E-02 2.35E-02 2. 35E-02 2.36E-02 0.0OE+00 2.36E-02 CFWFSp 1.57E-03 5.89E-03 4 .80E-03 4. 90E-03 4 .69E-03 1. 06E-02 0.0OE+00 5.28E-03 IPWtr 1. 82E-05 2.31E-02 2.31E-02 2.31E-02 2.31E-02 2. 32E-02 0.0OE+00 2.32E-02 TOTALS -------------------------------------

ADULT 1.15E-03 2. 61E-02 2. 48E-02 2.71E-02 2.47E-02 4.83E-02 0.OOE+00 2.57E-02 TEEN 1.24E-03 1. 93E-02 1. 80E-02 1.82E-02 1.79E-02 3.47E-02 0.OOE+00 1.87E-02 CHILD 1. 58E-03 2. 95E-02 2. 83E-02 2.84E-02 2.82E-02 3.43E-02 0.OOE+00 2.89E-02 INFANT 1.82E-05 2.31E-02 2. 31E-02 2.31E-02 2.31E-02 2.32E-02 0.OOE+00 2.32E-02

=== AGE GROUP / PATHWAY DESCRIPTIONS Abbreviation Age Group Pathway APWtr ADULT Potable Water (PWtr)

AFWFSp ADULT Fresh Water Fish - Sport (FFSP)

TPWtr TEEN Potable Water (PWtr)

TFWFSp TEEN Fresh Water Fish - Sport (FFSP)

CPWtr CHILD Potable Water (PWtr)

CFWFSp CHILD Fresh Water Fish - Sport (FFSP)

IPWtr INFANT Potable Water (PWtr)

Date/Time: 04/21/2003 15:06 brwmn Page - 3 p \depts\zd84g\environsg roup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05 Unit .................. : 2 Receptor .............. : 0 Liquid Receptor

=== PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT H-3 0. OOE+00 2.4 6E-02 2. 46E-02 2.4 6E-02 2.4 6E-02 2. 46E-02 0.OOE+00 2.4 6E-02 NA-24 7. 15E-08 7. 15E-08 7. 15E-08 7.15E-08 7. 15E-08 7. 15E-08 0.OOE+00 7.15E-08 CR-51 0.OOE+00 0.OOE+00 4 .47E-08 1.65E-08 9. 91E-08 1. 88E-05 0.OOE+00 7. 47E-08 MN-54 0.OOE+00 1. 85E-04 0. 00E+00 5.51E-05 0.OOE+00 5. 68E-04 0.OOE+00 3. 54E-05 FE-59 6.15E-06 1.45E-05 0.OOE+00 0.0 0E+00 4. 04E-06 4 .82E-05 0.OOE+00 5.54E-06 CO-58 0. OOE+00 7. 06E-05 0.OOE+00 0.0 0E+00 0. OOE+00 1.43E-03 0. OOE+00 1. 58E-04 CO-60 0.OOE+00 1. 12E-04 0.OOE+00 0.OOE+00 0.OOE+00 2.11E-03 O.OOE+00 2. 47E-04 NI-65 4.59E-08 5. 97E-09 0.OOE+00 0. OOE+00 0. OOE+00 1. 51E-07 0.OOE+00 2.72E-09 RB-88 0. OOE+00 4.92E-07 0. OOE+00 0. OOE+00 0. OOE+00 6.80E-18 0.OOE+00 2. 61E-07 ZR-95 7. 16E-10 2.29E-10 0.OOE+00 3.60E-10 0. OOE+00 7.27E-07 0. OOE+00 1.55E-10 ZR-97 2.73E-12 5.50E-13 0. OOE+00 8.31E-13 0. OOE+00 1.71E-07 0. OOE+00 2.52E-13 NB-95 5. 17E-06 2.88E-06 0. OOE+00 2.84E-06 0.OOE+00 1.75E-02 0.OOE+00 1.55E-06 TC-99M 2. 19E-12 6.18E-12 0. OOE+00 9.39E-l1 3.03E-12 3. 66E-09 0.OOE+00 7.88E-1l TC-101 5. 18E-12 7. 47E-12 0.OOE+00 1.34E-10 3.82E-12 2.24E-23 0. OOE+00 7.33E-l1 AG-11OM 2. 44E-08 2.26E-08 0.0OE+00 4.45E-08 0. OOE+00 9.23E-06 0. OOE+00 1.34E-08 TE-125M 5. 17E-04 1. 87E-04 1.55E-04 2. 1OE-03 0.OOE+00 2.06E-03 0. OOE+00 6.92E-05 I-131 2.18E-08 3. 11E-08 1. 02E-05 5.33E-08 0.OOE+00 8.21E-09 0.0OE+00 1.78E-08 I-134 3.56E-09 9.67E-09 1. 68E-07 1. 54E-08 0. OOE+00 8. 43E-12 0.OOE+00 3.4 6E-09 CS-136 7. 62E-06 3.01E-05 0. OE+00 1. 67E-05 2. 29E-06 3. 42E-06 0. OOE+00 2. 17E-05 CS-137 6.11E-04 8. 35E-04 0.OOE+00 2.84E-04 9.43E-05 1. 62E-05 0. OOE+00 5.47E-04 BA-140 3.58E-06 4.50E-09 0. OOE+00 1.53E-09 2.58E-09 7. 38E-06 0. OOE+00 2.35E-07 TEEN H-3 0. OOE+00 1.78E-02 1.78E-02 1.78E-02 1. 78E-02 1.78E-02 0. OOE+00 1.78E-02 NA-24 7.36E-08 7.36E-08 7.36E-08 7.36E-08 7.36E-08 7.36E-08 O.OOE+00 7. 36E-08 CR-51 0.OOE+00 0. OOE+00 4.28E-08 1. 69E-08 1. 1OE-07 1.29E-05 0. OOE+00 7.7OE-08 MN-54 0.OOE+00 1.82E-04 0. OE+00 5.43E-05 0.OOE+00 3.74E-04 0.0OE+00 3. 61E-05 FE-59 6.33E-06 1. 48E-05 0.0 0E+00 0. OOE+00 4. 66E-06 3. 49E-05 0.0OE+00 5. 70E-06 CO-58 0. OOE+00 7. OOE-05 0.OOE+00 0.OOE+00 0. 00E+00 9.64E-04 0. OOE+00 1. 61E-04 CO-60 0. OOE+00 1. 12E-04 0. OOE+00 0.0OE+00 0. OOE+00 1.46E-03 O.OOE+00 2. 52E-04 NI-65 4. 95E-08 6.33E-09 0. OOE+00 0.OOE+00 0. OOE+00 3. 43E-07 0. OOE+00 2.88E-09 RB-88 0.OOE+00 5.28E-07 0.OOE+00 0.OOE+00 0.0OE+00 4. 52E-14 0.OOE+00 2.81E-07 ZR-95 7. 14E-10 2.25E-10 O.OOE+00 3. 31E-10 0.OOE+00 5. 20E-07 0.OOE+00 1.55E-10 ZR-97 2. 84E-12 5.61E-13 0.0OE+00 8.51E-13 0.OOE+00 1. 52E-07 0.OOE+00 2.58E-13 NB-95 5.21E-06 2. 89E-06 0. OOE+00 2. 80E-06 0. OOE+00 1.24E-02 0. OOE+00 1. 59E-06 TC-99M 2.22E-12 6.19E-12 0.OOE+00 9.22E-11 3.43E-12 4.06E-09 0.OOE+00 8.01E-l1 TC-101 5.54E-12 7.88E-12 0. OOE+00 1. 43E-10 4.80E-12 1. 35E-18 0.OOE+00 7.74E-11 AG-11OM 2.29E-08 2. 17E-08 0.OOE+00 4. 13E-08 0.OOE+00 6.09E-06 0.0OE+00 1. 32E-08 TE-125M 5. 63E-04 2. 03E-04 1.57E-04 0.OOE+00 0. OOE+00 1. 66E-03 O.OOE+00 7. 52E-05 Date/Time: 04/21/2003 15:06 brwmn Page - 4 p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05

PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem) =======================

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB I-131 2.31E-08 3.23E-08 9.42E-06 5.56E-08 0.OOE+00 6.39E-09 0. OOE+00 1.73E-08 I-134 3.70E-09 9.80E-09 1.63E-07 1.54E-08 0.OOE+00 1.29E-10 0.OOE+00 3.52E-09 CS-136 7.66E-06 3.02E-05 0.OOE+00 1.64E-05 2.59E-06 2.43E-06 0.0OE+00 2.03E-05 CS-137 6.54E-04 8.70E-04 0.OOE+00 2. 96E-04 1. 15E-04 1.24E-05 0.0OE+00 3. 03E-04 BA-140 3.71E-06 4.54E-09 0.OOE+00 1.54E-09 3.05E-09 5.72E-06 0.0OE+00 2.39E-07 CHILD H-3 0.OOE+00 2. 81E-02 2.81E-02 2.81E-02 2.81E-02 2.81E-02 0. O0E+00 2.81E-02 NA-24 8.21E-08 8.21E-08 8.21E-08 8.21E-08 8. 21E-08 8. 21E-08 0.OOE+00 8.21E-08 CR-51 0.OOE+00 0. OE+00 4.61E-08 1.26E-08 8.43E-08 4.41E-06 0.OOE+00 8.31E-08 MN-54 0.OOE+00 1. 43E-04 0. OOE+00 4. 02E-05 0. OOE+00 1.20E-04 0. OOE+00 3.82E-05 FE-59 7. 87E-06 1.27E-05 0. OOE+00 0. OOE+00 3. 69E-06 1. 33E-05 0. OOE+00 6.34E-06 CO-58 0. OOE+00 5. 87E-05 0. OOE+00 0.OOE+00 0. OOE+00 3.42E-04 0. OOE+00 1.80E-04 CO-60 0. OOE+00 9. 54E-05 0.OOE+00 0. OOE+00 0. OOE+00 5.28E-04 0. OOE+00 2. 81E-04 NI-65 6.50E-08 6.12E-09 0.OOE+00 0.OOE+00 0. OOE+00 7.49E-07 0. OOE+00 3.57E-09 RB-88 0.00E+00 5. 08E-07 0.OOE+00 0. OOE+00 0. OOE+00 2.49E-08 0. OOE+00 3.53E-07 ZR-95 1.30E-09 2. 85E-10 0.OOE+00 4. 08E-10 0.OOE+00 2.98E-07 0. OOE+00 2.54E-10 ZR-97 5. 40E-12 7. 80E-13 0. OOE+00 1. 12E-12 0.OOE+00 1. 18E-07 0.OOE+00 4. 60E-13 NB-95 6. 15E-06 2. 39E-06 0.OOE+00 2.25E-06 0.OOE+00 4.43E-03 0. OOE+00 1.71E-06 TC-99M 3.07E-12 6.02E-12 0.OOE+00 8.75E-11 3.06E-12 3. 42E-09 0.OOE+00 9.98E-11 TC-101 8. 19E-12 8. 58E-12 0.OOE+00 1. 46E-10 4.54E-12 2. 73E-11 0.OOE+00 1. 09E-10 AG-llOM 4.19E-08 2.83E-08 0. OOE+00 5.27E-08 0.0OE+00 3. 36E-06 0. OOE+00 2.26E-08 TE-125M 7.27E-04 1. 97E-04 2. 04E-04 0.OOE+00 0.0OE+00 7. 01E-04 0.OOE+00 9. 69E-05 I-131 3.38E-08 3. 40E-08 1. 12E-05 5.58E-08 0.0OE+00 3. 02E-09 0. OOE+00 1. 93E-08 I-134 5.28E-09 9. 81E-09 2.26E-07 1.50E-08 0.0OE+00 6.50E-09 0. OOE+00 4. 51E-09 CS-136 9.05E-06 2.4 9E-05 0. OOE+00 1.33E-05 1. 98E-06 8.74E-07 0. OOE+00 1. 61E-05 CS-137 8.24E-04 7.89E-04 0.00E+00 2.57E-04 9.25E-05 4.94E-06 0.OOE+00 1. 16E-04 BA-140 6. 73E-06 5. 89E-09 0. 00E+00 1. 92E-09 3.51E-09 3. 41E-06 0. OOE+00 3. 93E-07 INFANT H-3 0.OOE+00 2.31E-02 2.31E-02 2. 31E-02 2.31E-02 2.31E-02 0. OOE+00 2. 31E-02 NA-24 4.09E-09 4 . 09E-09 4.09E-09 4. 09E-09 4.09E-09 4.09E-09 0. OOE+00 4.09E-09 CR-51 0.OOE+00 0.OOE+00 1.26E-09 2. 74E-10 2. 44E-09 5.61E-08 0. OOE+00 1. 92E-09 MN-54 0. 00E+00 1. 97E-06 0.OOE+00 4.37E-07 0. OOE+00 7.24E-07 0. OOE+00 4.47E-07 FE-59 4.20E-07 7. 33E-07 0.OOE+00 0.OOE+00 2. 17E-07 3.50E-07 0.OOE+00 2. 89E-07 CO-58 0.OOE+00 6.42E-06 0.OOE+00 0.OOE+00 0. OOE+00 1. 60E-05 0.OOE+00 1. 60E-05 CO-60 0.OOE+00 1. 07E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.54E-05 0. OE+00 2. 52E-05 NI-65 3. 93E-09 4 .45E-10 0. OOE+00 0.OOE+00 0. OOE+00 3.39E-08 0.OOE+00 2.02E-10 RB-88 0.OOE+00 1. 99E-09 0. OOE+00 0.OOE+00 0. OOE+00 1. 93E-09 0.OOE+00 1.09E-09 ZR-95 8.70E-10 2. 12E-10 0.OOE+00 2.29E-10 0.OOE+00 1.06E-07 0. OOE+00 1.50E-10 ZR-97 4.31E-12 7. 40E-13 0. OOE+00 7.46E-13 0.OOE+00 4.72E-08 0. OOE+00 3.38E-13 Date/Time: 04/21/2003 15:06 brwmn Page - 5 p.\depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05

PERMIT ORGAN DOSE BY AGE GROUP AND NUCLIDE (mrem) ======== ================

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB NB-95 1. 14E-09 4.71E-10 0.OOE+00 3.38E-10 0.OOE+00 3. 97E-07 0.OOE+00 2.72E-10 TC-99M 9.73E-13 2. 01E-12 0. OOE+00 2.16E-11 1. 05E-12 5. 83E-10 0.OOE+00 2.58E-11 TC-101 2.65E-12 3.34E-12 0. OE+00 3.97E-11 1. 82E-12 5.67E-10 0.OOE+00 3.30E-11 AG-llOM 3.34E-08 2.44E-08 0. OOE+00 3.4 9E-08 0.OOE+00 1.26E-06 0.OOE+00 1.61E-08 TE-125M 1.10E-05 3.67E-06 3. 69E-06 0.OOE+00 0.0OE+00 5.23E-06 0.OOE+00 1.48E-06 I-131 1. 07E-08 1.26E-08 4.16E-06 1.48E-08 0.OOE+00 4.52E-10 0.OOE+00 5.56E-09 I-134 1. 67E-09 3.42E-09 7. 97E-08 3.82E-09 0. 00E+00 3. 53E-09 0.00E+00 1.22E-09 CS-136 2.64E-08 7. 76E-08 0. OOE+00 3.09E-08 6.32E-09 1. 18E-09 0.OOE+00 2.89E-08 CS-137 1.96E-06 2.30E-06 0. OOE+00 6.16E-07 2.50E-07 7. 18E-09 0.OOE+00 1.63E-07 BA-140 4. 80E-06 4 .80E-09 0. OOE+00 1.14E-09 2. 95E-09 1.18E-06 0.OOE+00 2.47E-07 Date/Time: 04/21/2003 15:06 brwmn Page - 6 p:\depts\zd84g\environsg roup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

---

(PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05 Unit .................. : 2 Receptor .............. : 0 Liquid Receptor

=== MAXIMUM DOSE FOR PERIOD Limit Organ Ag e Dose Limit Limit Percent Type Type Gr oup Organ (mrem) Period (mrem) of Limit AnyOrgan ________ ________

Admin Any Organ AD ULT GILLI 4.83E-02 31-day 1.50E-01 3.22E+01 Quarter 3.75E+00 1.29E+00 Annual 7. 50E+00 6.45E-01 Admin Tot Body CH ILD TBODY 2.89E-02 31-day 4.50E-02 6.42E+01 Quarter 1.13E+00 2.57E+00 Annual 2.25E+00 1.28E+00 T.Spec Any Organ AD ULT GILLI 4.83E-02 31-day 2. OOE-01 2.42E+01 Quarter 5. OOE+00 9.67E-01 Annual 1.OOE+01 4.83E-01 Critical Pathway....... 1 Fresh Water Fish - Sport (FFSP Major Contributors..... 0.0 % or greater to total Nuclide Percentage H-3 5.09E+01 NA-24 1.48E-04 CR-51 3.89E-02 MN-54 1.17E+00 FE-59 9.97E-02 CO-58 2.96E+00 CO-60 4.36E+00 NI-65 3.13E-04 RB-88 1.41E-14 ZR-95 1.50E-03 ZR-97 3.53E-04 NB-95 3.61E+01 TC-99M 7.57E-06 TC-101 4.64E-20 AG-llOM i.91E-02 TE-125M 4.27E+00 I-131 1.70E-05 I-134 1.74E-08 CS-136 7.07E-03 CS-137 3.34E-02 BA-140 1.53E-02 Date/Time: 04/21/2003 15:06 brwmn Page - 7 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

- (PERIOD BASIS - BY UNIT) ------

Release ID ............ : 1 All Liquid Release Types Period Start Date ..... : 01/01/2002 00:00 Period End Date ....... : 01/01/2003 00:00 Period Duration (mins): 5.256E+05

MAXIMUM DOSE FOR PERIOD ==============================

Limit Organ Age Dose Limit Limit Percent Type Type Group Organ (mrem) Period (mrem) of Limit T.Spec Tot Body CHILD TBODY 2.89E-02 31-day 6.OOE-02 4.81E+01 Quarter 1.50E+00 1. 92E+00 Annual 3.OOE+00 9.62E-01 Critical Pathway ........ : 0 Potable Water (PWtr)

Major Contributors ...... : 0.0 % or greater to total Nuclide Percentage H-3 9.74E+01 NA-24 2.84E-04 CR-51 2.88E-04 MN-54 1.32E-01 FE-59 2.20E-02 CO-58 6.22E-01 CO-60 9.74E-01 NI-65 1.24E-05 RB-88 1.22E-03 ZR-95 8.80E-07 ZR-97 1.59E-09 NB-95 5.92E-03 TC-99M 3.46E-07 TC-101 3.77E-07 AG-llOM 7.83E-05 TE-125M 3.36E-01 I-131 6.68E-05 I-134 1.56E-05 CS-136 5.58E-02 CS-137 4.03E-01 BA-140 1.36E-03 Date/Time: 04/21/2003 15:06 brwmn LAST Page - 8 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT

- LIQUID DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) QUARTER 1 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 1.19E-03 9.07E-03 7.94E-03 1.02E-02 7.89E-03 1.92E-02 0.OOE+00 8.67E-03 TEEN 1.29E-03 6.97E-03 5.78E-03 5.99E-03 5.76E-03 1.38E-02 0.00E+00 6.25E-03 CHILD 1.64E-03 1.01E-02 9.10E-03 9.21E-03 9.OOE-03 1.19E-02 0.O0E+00 9.35E-03 INFANT 1.29E-05 7.32E-03 7.31E-03 7.31E-03 7.31E-03 7.33E-03 0.OOE+00 7.33E-03

=== SITE DOSE LIMIT ANALYSIS UARTER 1 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 1 - Admin. Any Organ ADULT GILLI 1. 92E-02 3.75E+C30 5.12E-01 Qtr 1 - Admin. Total Body CHILD TBODY 9.35E-03 1.13E+C )0 8.31E-01 Qtr 1 - T.Spc. Any Organ ADULT GILLI 1.92E-02 5.OOE+00 3.84E-01 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 4.06E+01 MN-54 1.20E+00 CO-58 5.13E+00 CO-60 3.46E+00 ZR-95 5.53E-04 NB-95 3.91E+01 AG-llOM 4.09E-03 TE-125M 1.05E+01 CS-137 9.50E-02 Qtr 1 - T.Spc. Total Body CHILD TBODY 9.35E-03 1.50E+00 6.23E-01 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.51E+01 MN-54 1.66E-01 CO-58 1.32E+00 CO-60 9.47E-01 ZR-95 3.96E-07 NB-95 7.86E-03 AG-llOM 2.05E-05 TE-125M 1.01E+00 CS-137 1.41E+00 Date/Time: 04/25/2003 12:03 brwmn Page - 1 p:\depts'izd849\environsg roup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) QUARTER 2 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 4.99E-04 8.44E-03 7.95E-03 9.80E-03 7.82E-03 3.89E-02 0.OOE+00 8.33E-03 TEEN 5.40E-04 6.29E-03 5.79E-03 5.74E-03 5.66E-03 2.77E-02 0.00E+00 6.18E-03 CHILD 6.95E-04 9.48E-03 9.11E-03 9.00E-03 8.93E-03 1.69E-02 0.OOE+00 9.52E-03 TNFANT 1.08E-05 - - 7.35E-03 7.33E-03 7.33E-03 7.33E-03 7.38E-03 0.00E+00 7.37E-03

=== SITE DOSE LIMIT ANALYSIS ============================= QUARTER 2 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 2 - Admin. Any Organ ADULT GILLI 3.89E-02 3.75E+00 1.04E+00 Qtr 2 - Admin. Total Body CHILD TBODY 9.52E-03 1. 13E+00 8.46E-01 Qtr 2 - T.Spc. Any Organ ADULT GILLI 3.89E-02 5.OOE+00 7.79E-01 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major-Contributors ( 0% or greater to total)

Nuclide Percentage H-3 2.01E+01 NA-24 3.50E-04 CR-51 9.19E-02 MN-54 1.68E+00 FE-59 2.36E-01 CO-58 2.37E+00 CO-60 5.82E+00 NI-65 7.41E-04 ZR-95 3.28E-03 NB-95 6.49E+01 TC-99M 1.79E-05 TC-101 1.10E-19 AG-llOM 3.93E-02 TE-125M 4.77E+00 I-134 3.05E-08 CS-136 1.67E-02 Qtr 2 - T.Spc. Total Body CHILD TBO DY 9.52E-03 1.50E+00 6.34E-01 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.37E+01 NA-24 1. 64E-03 Date/Time: 04/25/2003 12:03 brwmn Page - 2 p.\depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> vSSI 4OCFR190 URANIUM FUEL CYCLE DOSE REPORT Nuclide Percentage CR-51 1.66E-03 MN-54 4.62E-01 FE-59 1.27E-01 CO-58 1.22E+00 CO-60 3.18E+00 NI-65 7.15E-05 ZR-95 4.68E-06 NB-95 2.60E-02 TC-99M 2.OOE-06 TC-101 2.18E-06 AG-110M 3.93E-04 TE-125M 9.16E-01 I-134 6.67E-05 CS-136 3.22E-01 Date/Time: 04/25/2003 12:03 brwmn Page - 3 p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) QUARTER 3 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 5.55E-08 6.39E-03 6.29E-03 6.31E-03 6.29E-03 7.66E-03 0.OOE+00 6.42E-03 TEEN 5.58E-08 4.65E-03 4.55E-03 4.56E-03 4.55E-03 5.49E-03 0.OOE+00 4.68E-03 CHILD 6.74E-08 7.27E-03 7.19E-03 7.20E-03 7.19E-03 7.53E-03 0.OOE+00 7.34E-03 INFANT 3.26E-09 5.92E-03 5.91E-03 5.91E-03 5.91E-03 5.92E-03 0.00E+00 5.92E-03

SITE DOSE LIMIT ANALYSIS ==========================

QUARTER 3 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 3 - Admin. Any Organ ADULT GILLI 7.66E-()3 3.75E+0)0 2.04E-01 Qtr 3 - Admin. Total Body CHILD TBODY 7. 34E-()3 1.13E+0)0 6.53E-01 Qtr 3 - T.Spc. Any Organ ADULT GILLI 7.66E-03 5.OOE+00 1.53E-01 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 8.22E+01 MN-54 1.56E+00 CO-58 6.70E+00 CO-60 7.26E+00 RB-88 1.35E-13 ZR-97 3.38E-03 NB-95 2.30E+00 AG-llOM 9.29E-03 I-134 4.36E-08 Qtr 3 - T.Spc. Total Body CHILD TBODY 7.34E-03 1.50E+00 4.89E-01 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.80E+01 MN-54 1.10E-01 C0-58 8.78E-01 CO-60 1.01E+00 RB-88 7.30E-03 ZR-97 9.52E-09 NB-95 2.35E-04 AG-llOM 2.37E-05 I-134 2.44E-05 Date/Time: 04/25/2003 12:03 brwmn Page - 4 p:\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) QUARTER 4 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 3.64E-04 1.44E-02 1.39E-02 1.41E-02 1.40E-02 1.44E-02 0.0OE+00 1.43E-02 TEEN 3.89E-04 1.06E-02 1.01E-02 1.02E-02 1.01E-02 1.04E-02 0.0OE+00 1.03E-02 CHILD 4.94E-04 1.64E-02 1.59E-02 1.60E-02 1.59E-02 1.60E-02 0.OOE+00 1.60E-02 INFANT 8.44E-06 1.31E-02 1.31E-02 1.31E-02 1.30E-02 1.31E-02 0.OOE+00 1.31E-02

=== SITE DOSE LIMIT ANALYSIS ============================= QUARTER 4 =-

Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit

_____________________________ CHILD__

Qtr 4 - Admin. Any Organ CHILD LIVER 1. 64E-C)2 3.75E+00 4.37E-01 Qtr 4 - Admin. Total Body CHILD TBODY 1.60E-C)2 1.13E+00 1.42E+00 Qtr 4 - T.Spc. Any Organ CHILD LIVER 1.64E-02 5.OOE+00 3.27E-01 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.70E+01 MN-54 4.89E-02 CO-58 2.82E-02 CO-60 7.96E-02 AG-llOM 8.65E-06 I-131 3.14E-04 CS-137 2.83E+00 BA-140 5.45E-05 Qtr 4 - T.Spc. Total Body CHILD TBODY 1.60E-02 1.50E+00 1.07E+00 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.92E+01 MN-54 1.33E-02 CO-58 8.84E-02 CO-60 2.40E-01 AG-llOM 7.08E-06 I-131 1.83E-04 CS-137 4.27E-01 BA-140 3.71E-03 Date/Time: 04/25/2003 12:03 brwmn Page - 5 p:\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Ranqe - From: 1 To: 1 Liquid Receptor

PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) ANNUAL 2002 ======

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI , Skin TB ADULT 1.98E-03 3.95E-02 3.74E-02 4.13E-02 3.72E-02 7.79E-02 0.OOE+00 3.89E-02 TEEN 2.13E-03 2.94E-02 2.71E-02 2.74E-02 2.70E-02 5.59E-02 0.OOE+00 2.83E-02 CHILD 2.72E-03 4.47E-02 4.27E-02 4.29E-02 4.25E-02 5.30E-02 0.OOE+00 4.36E-02 INFANT 3.14E-05 3.49E-02 3.48E-02 3.48E-02 3.48E-02 3.49E-02 0.OOE+00 3.49E-02

=== SITE DOSE LIMIT ANALYSIS ==================== ========= ANNUAL 2002 Age Dose Limit Max % of Annual - Limit Group Organ (mrem) (mrem) Limit 2002 - Admin. Any Organ ADULT GILLI 7.79E-()2 7.50E+00 1.04E+00 2002 - Admin. Total Body CHILD TBODY 4.36E-()2 2.25E+00 1. 94E+00 2002 - T.Spc. Any Organ ADULT GILLI 7.79E-02 1.OOE+01 7.79E-01 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 4.76E+01 NA-24 1.58E-04 CR-51 4.15E-02 MN-54 1.25E+00 FE-59 1.06E-01 CO-58 3.16E+00 CO-60 4.65E+00 NI-65 3.34E-04 RB-88 1.50E-14 ZR-95 1.61E-03 ZR-97 3.77E-04 NB-95 3.86E+01 TC-99M 8.08E-06 TC-101 4.96E-20 AG-llOM 2.04E-02 TE-125M 4.56E+00 I-131 1.81E-05 I-134 1.86E-08 CS-136 7.55E-03 CS-137 3.57E-02 BA-140 1.63E-02 2002 - T.Spc. Total Body CHILD TBODY 4.36E-02 3.OOE+00 1.45E+00 Date/Time: 04/25/2003 12:03 brwmn Page - 6 p:\depts~zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.71E+01 NA-24 3.24E-04 CR-51 3.28E-04 MN-54 1.51E-01 FE-59 2.50E-02 CO-58 7.08E-01 CO-60 l.l1E+00 NI-65 1.41E-05 RB-88 1.39E-03 ZR-95 1.OOE-06 ZR-97 1.81E-09 NB-95 6.74E-03 TC-99M 3.93E-07 TC-101 4.29E-07 AG-110M 8.91E-05 TE-125M 3.82E-01 I-131 7.61E-05 I-134 1.78E-05 CS-136 6.35E-02 CS-137 4.59E-01 BA-140 1.55E-03 Date/Time: 04/25/2003 12:03 brwmn Page - 7 p.\depts\zd84g\environsg roup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1

I&P DOSE LIMIT ANALYSIS == ==========================

QUARTER 1 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit

______________________________ CHILD__ ________ ____E__

Qtr 1 - Admin. Any Organ CHILD LIVER 1.20E-()4 5.63E+CJO 2.13E-03 Qtr 1 - Admin. Total Body CHILD TBODY 1.20E-(04 5.25E+CJO 2.28E-03 Qtr 1 - T.Spc. Any Organ CHILD LIV ER 1.201 E-04 7.50E+00 1.60E-03 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compas s Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 1.00E+02 Qtr 1 - T.Spc. Total Body CHILD TBO DY 1.20JE-04 7.50E+00 1.60E-03 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compas s Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 1.OOE+02 Date/Time: 04/25/2003 12:03 brwmn Page - 8 p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1

=== NG DOSE LIMIT ANALYSIS == QUARTER 1 Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit Qt_1---__Ad________in____________Gamma___________

Qtr 1 - Admin. Gamma 4.92E-( )5 3.75E+C)0 1.31E-03 Qtr 1 - Admin. Beta 3.68E-( )5 7.50E+C)0 4.90E-04 Qtr 1 - T.Spc. Gamma 4.92E-05 5.00E+00 9.85E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point : NA Nuclide Percentage AR-41 9.54E+01 XE-135 9.87E-01 XE-133 3.66E+00 Qtr 1 - T.Spc. Beta 3.681E-05 1.OOE+01 3.68E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage AR-41 7.35E+01 XE-135 2.76E+00 XE-133 2.38E+01 Date/Time: 04/25/2003 12:03 brwmn Page - 9 p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1

I&P DOSE LIMIT ANALYSIS ===========================

UARTER 2 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 2 - Admin. Any Organ INFANT THYROID 3.4 6E-03 5.63E+C 10 6.14E-02 Qtr 2 - Admin. Total Body CHILD TBODY 1. 69E-04 5.25E+C 10 3.22E-03 Qtr 2 - T.Spc. Any Organ INFANT THYROID 3.46]7E-03 7.50E+00 4.61E-02 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Critical Pathway: Grs/Goat/Milk (GMILK)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 3.73E+00 CO-58 1.95E-02 I-131 9.60E+01 I-133 2.85E-01 Qtr 2 - T.Spc. Total Body CHILD TBO DY 1.691>E-04 7.50E+00 2.26E-03 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compas s Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.78E+01 CO-58 7.02E-01 I-131 1.48E+00 I-133 6.07E-03 Date/Time: 04/25/2003 12:03 brwmn Page - 10 p:\depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1

=== NG DOSE LIMIT ANALYSIS == QUARTER 2 Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit Qt_2---__A_________i_____________Ga___________a__

Qtr 2 - Admin. Gamma 3.07E-C)5 3.75E+C)0 8.17E-04 Qtr 2 - Admin. Beta 2.89E-C)5 7.50E+C)0 3.85E-04 Qtr 2 - T.Spc. Gamma 3.07E-05 5.OOE+00 6.13E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage AR-41 8.57E+01 KR-85M 1.76E-01 XE-135 8.71E+00 XE-133 5.41E+00 Qtr 2 - T.Spc. Beta 2.89E-05 1.OOE+01 2.89E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point : NA Nuclide Percentage AR-41 5.23E+01 KR-85M 4.88E-01 XE-135 1.93E+01 XE-133 2.79E+01 Date/Time: 04/25/2003 12:03 brwmn Page - 11 p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1

I&P DOSE LIMIT ANALYSIS ===========================

LUARTER 3 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit

____________________________ CHILD__ ________ 1____E__

Qtr 3 - Admin. Any Organ CHILD LIVER 1.7lE-04 5.63E+C '0 3.03E-03 Qtr 3 - Admin. Total Body CHILD TBODY 1.71E-04 5.25E+C )0 3.25E-03 Qtr 3 - T.Spc. Any Organ CHILD LIV ER 1.71] E-04 7.50E+00 2.28E-03 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compas s Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 1.00E+02 Qtr 3 - T.Spc. Total Body CHILD TBODY 1.71E-04 7.50E+00 2.28E-03 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 1.0OE+02 Date/Time: 04/25/2003 12:03 brwmn Page - 12 p:\depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1

=== NG DOSE LIMIT ANALYSIS = == QUARTER 3 Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit Qtr 3 - Admin. Gamma 1.70E-()5 3.75E+CW0 4.53E-04 Qtr 3 - Admin. Beta 1. 14E-()5 7.50E+C10 1.53E-04 Qtr 3 - T.Spc. Gamma 1.70E-05 5.OOE+00 3.40E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage AR-41 9.76E+01 XE-135 1.09E-01 XE-133 2.27E+00 Qtr 3 - T.Spc. Beta 1.14E-05 1.OOE+01 1.14E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point : NA Nuclide Percentage AR-41 8.33E+01 XE-135 3.37E-01 XE-133 1.64E+01 Date/Time: 04/25/2003 12:03 brwmn Page - 13 p \depts'zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1

I&P DOSE LIMIT ANALYSIS == ==========================

QUARTER 4 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 4 - Admin. Any Organ INFANT THYROID 1. 68E-C)3 5.63E+CW0 2.98E-02 Qtr 4 - Admin. Total Body CHILD TBODY 5.27E-()4 5.25E+C10 1.OOE-02 Qtr 4 - T.Spc. Any Organ INFANT THYROID 1.681E-03 7.50E+00 2.24E-02 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Critical Pathway: Grs/Goat/Milk (GMILK)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 2.44E+01 I-131 7.56E+01 Qtr 4 - T.Spc. Total Body CHILD TBO 'DY 5.27]E-04 7.50E+00 7.02E-03 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compas s Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.98E+01 I-131 1.82E-01 Date/Time: 04/25/2003 12:03 brwmn Page - 14 p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1

=== NG DOSE LIMIT ANALYSIS =QUARTER 4 Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit Qtr 4 - Admin. Gamma 1.83E-05 3.75E+CDO 4.88E-04 Qtr 4 - Admin. Beta 1.26E-05 7.50E+C3O 1.68E-04 Qtr 4 - T.Spc. Gamma 1.83E-05 5.OOE+00 3.66E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage AR-41 9.73E+01 XE-135 1.48E-01 XE-133 2.59E+00 Qtr 4 - T.Spc. Beta 1.261 >E-05 1.OOE+01 1.26E-04 Receptor: : 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage AR-41 8.13E+01 XE-135 4.48E-01 XE-133 1.83E+01 Date/Time: 04/25/2003 12:03 brwmn Page - 15 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 4OCFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1

=== I&P DOSE LIMIT ANALYSIS ANNUAL 2002 Age Dose Limit Max % of Annual - Limit Group Organ (mrem) (mrem) Limit 2002 - Admin. Any Organ INFANT THYROID 5.36E-03 1.13E+01 4.76E-02 2002 - Admin. Total Body CHILD TBODY 9.86E-04 1.05E+01 9.4 OE-03 2002 - T.Spc. Any Organ INFANT THYROID 5.36E-03 1.50E+01 3.57E-02 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Critical Pathway: Grs/Goat/Milk (GMILK)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 1.43E+01 CO-58 1.26E-02 I-131 8.55E+01 I-133 1.84E-01 2002 - T.Spc. Total Body CHILD TBO DY 9.86]iE-04 1.50E+01 6.58E-03 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compas s Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.95E+01 CO-58 1.20E-01 I-131 3.51E-01 I-133 1.04E-03 Date/Time: 04/25/2003 12:03 brwmn Page - 16 p.\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1

=== NG DOSE LIMIT ANALYSIS == ANNUAL 2002 Dose Limit Max % of Annual - Limit (mrad) (mrad) Limit 2002-____A_________in____________Gamma___________

2002 - Admin. Gamma 1.15E-C)4 7.50E+00 1.54E-03 2002 - Admin. Beta 8.97E-C)5 1.50E+01 5.98E-04 2002 - T.Spc. Gamma 1.15E-04 1.OOE+01 1.15E-03 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage AR-41 9.34E+01 KR-85M 4.68E-02 XE-135 2.78E+00 XE-133 3.75E+00 2002 - T.Spc. Beta 8.97E-05 2.00E+01 4.48E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point : NA Nuclide Percentage AR-41 6.90E+01 KR-85M 1.57E-01 XE-135 7.46E+00 XE-133 2.34E+01 Date/Time: 04/25/2003 12:03 brwmn Page - 17 p:\depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Braidwood Unit 1, 2002 Report for: 2002 Unit Range - From: 1 To: 1

MAXIMUM DOSE ANALYSIS=  :===============

ANNUAL 2002 =========

Age Dose Dose Type Group Organ (mrem)

Any Organ ADULT GILLI 7.851E-02 Liquid Receptor: C Liquid Receptor Gaseous Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Liquid Dose: 7.79E-02  % of Total: 9.93E+01 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors 0% or greater to total)

Nuclide Percentage H-3 4.76E+01 NA-24 1.58E-04 CR-51 4.15E-02 MN-54 1.25E+00 FE-59 1.06E-01 CO-58 3.16E+00 CO-60 4.65E+00 NI-65 3.34E-04 RB-88 1.50E-14 ZR-95 1.61E-03 ZR-97 3.77E-04 NB-95 3.86E+01 TC-99M 8.08E-06 TC-101 4.96E-20 AG-llOM 2.04E-02 TE-125M 4.56E+00 I-131 1.81E-05 I-134 1.86E-08 CS-136 7.55E-03 CS-137 3.57E-02 BA-140 1.63E-02 Gaseous Dose: 5.99E-04  % of Total: 7.63E-01 Critical Pathway: Vegetation (VEG)

Major Contributors t 0% or greater to total)

Nuclide Percentage H-3 9.95E+01 CO-58 4.40E-01 I-131 9.84E-02 I-133 1.51E-03 Date/Time: 04/25/2003 12:03 brwmn Page - 18 p \depts'.zd84g\environsg roup\2002eff~doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT

= MAXIMUM DOSE ANALYSIS == =

ANNUAL 2002 =========

Age Dose Dose Type Group Organ (mrer n)

Total Body CHILD TBODY 4.461 -102 Liquid Receptor: 0 Liquid Receptor Gaseous Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Liquid Dose: 4.36E-02  % of Total: 9.79E+01 Critical Pathway: Potable Water (PWtr)

Major Contributors 0% or greater to total)

Nuclide Percentage H-3 9.71E+01 NA-24 3.24E-04 CR-51 3.28E-04 MN-54 1.51E-01 FE-59 2.50E-02 CO-58 7.08E-01 CO-60 1.llE+00 NI-65 1.41E-05 RB-88 1.39E-03 ZR-95 1.OOE-06 ZR-97 1.81E-09 NB-95 6.74E-03 TC-99M 3.93E-07 TC-101 4.29E-07 AG-llOM 8.91E-05 TE-125M 3.82E-01 I-131 7.61E-05 I-134 1.78E-05 CS-136 6.35E-02 CS-137 4.59E-01 BA-140 1.55E-03 Gaseous Dose: 9.86E-04  % of Total: 2.21E+00 Critical Pathway: Vegetation (VEG)

Major Contributors 0% or greater to total)

Nuclide Percentage H-3 9.95E+01 CO-58 1.20E-01 I-131 3.51E-01 I-133 1.04E-03 Date/Time: 04/25/2003 12:03 brwmn LAST Page - 19 p:\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit____2____2002__

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) QUARTER 1 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT l.19E-03 9.07E-03 7.94E-03 1.02E-02 7.89E-03 1.92E-02 0.OOE+00 8.67E-03 TEEN 1.29E-03 6.97E-03 5.78E-03 5.99E-03 5.76E-03 1.38E-02 0.00E+00 6.25E-03 CHILD 1.64E-03 1.01E-02 9.10E-03 9.21E-03 9.OOE-03 1.19E-02 0.00E+00 9.35E-03 INFANT 1.29E-05 7.32E-03 7.31E-03 7.31E-03 7.31E-03 7.33E-03 0.OOE+00 7.33E-03

SITE DOSE LIMIT ANALYSIS ==========================

QUARTER 1 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 1 - Admin. Any Organ ADULT GILLI 1.92E-02 3.75E+00 5.12E-01 Qtr 1 - Admin. Total Body CHILD TBODY 9.35E-03 1.13E+00 8.31E-01 Qtr 1 - T.Spc. Any Organ ADULT GILLI 1.92E-02 5.00E+00 3.84E-01 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 4.06E+01 MN-54 1.20E+00 CO-58 5. 13E+00 CO-60 3.46E+00 ZR-95 5.53E-04 NB-95 3.91E+01 AG-llOM 4. 09E-03 TE-125M 1. 05E+01 CS-137 9.50E-02 Qtr 1 - T.Spc. Total Body CHILD TBODY 9.35E-03 1.50E+00 6.23E-01 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.51E+01 MN-54 1. 66E-01 CO-58 1.32E+00 CO-60 9.47E-01 ZR-95 3. 96E-07 NB-95 7.86E-03 AG-llOM 2. 05E-05 TE-125M 1. 01E+00 CS-137 1.41E+00 Date/Time: 04/21/2003 14:53 brwmn Page - 1 p:\depts\zd 84g\environsg roup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) QUARTER 2 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 4.99E-04 8.44E-03 7.95E-03 9.80E-03 7.82E-03 3.89E-02 0.OOE+00 8.33E-03 TEEN 5.40E-04 6.29E-03 5.79E-03 5.74E-03 5.66E-03 2.77E-02 0.OOE+00 6.18E-03 CHILD 6.95E-04 9.48E-03 9.11E-03 9.00E-03 8.93E-03 1.69E-02 0.OOE+00 9.52E-03 INFANT 1.08E-05 7.35E-03 7.33E-03 7.33E-03 7.33E-03 7.38E-03 0.00E+00 7.37E-03

=== SITE DOSE LIMIT ANALYSIS ============================= QUARTER 2 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 2 - Admin. Any Organ ADULT GILLI 3.89E-()2 3.75E+C )0 1.04E+00 Qtr 2 - Admin. Total Body CHILD TBODY 9.52E-()3 1.13E+C)0 8.46E-01 Qtr 2 - T.Spc. Any Organ ADULT GILLI 3.89E-02 5.OOE+00 7.79E-01 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 2.01E+01 NA-24 3.50E-04 CR-51 9.19E-02 MN-54 1.68E+00 FE-59 2.36E-01 CO-58 2.37E+00 CO-60 5.82E+00 NI-65 7.41E-04 ZR-95 3.28E-03 NB-95 6.49E+01 TC-99M 1.79E-05 TC-101 1.10E-19 AG-llOM 3.93E-02 TE-125M 4.77E+00 I-134 3.05E-08 CS-136 1.67E-02 Qtr 2 - T.Spc. Total Body CHILD TBODY 9.52E-03 1.50E+00 6.34E-01 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.37E+01 NA-24 1.64E-03 Date/Time: 04/21/2003 14:53 brwmn Page - 2 p:\depts\zd84g\environsgroup\2002eff .doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Nuclide Percentage CR-51 1.66E-03 MN-54 4.62E-01 FE-59 1.27E-01 CO-58 1.22E+00 CO-60 3.18E+00 NI-65 7.15E-05 ZR-95 4.68E-06 NB-95 2.60E-02 TC-99M 2.OOE-06 TC-101 2.18E-06 AG-lOM 3.93E-04 TE-125M 9.16E-01 I-134 6.67E-05 CS-136 3.22E-01 Date/Time: 04/21/2003 14:53 brwmn Page - 3 p.\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit____2____2002__

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) QUARTER 3 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 5.55E-08 6.39E-03 6.29E-03 6.31E-03 6.29E-03 7.66E-03 0.OOE+00 6.42E-03 TEEN 5.58E-08 4.65E-03 4.55E-03 4.56E-03 4.55E-03 5.49E-03 0.OOE+00 4.68E-03 CHILD 6.74E-08 7.27E-03 7.19E-03 7.20E-03 7.19E-03 7.53E-03 0.OOE+00 7.34E-03 INFANT 3.26E-09 5.92E-03 5.91E-03 5.91E-03 5.91E-03 5.92E-03 0.OOE+00 5.92E-03

=== SITE DOSE LIMIT ANALYSIS ============================= LUARTER 3 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 3 - Admin. Any Organ ADULT GILLI 7. 66E-03 3.75E+C '0 2.04E-01 Qtr 3 - Admin. Total Body CHILD TBODY 7.34E-03 1.13E+C'0 6.53E-01 Qtr 3 - T.Spc. Any Organ ADULT GILLI 7.66E-03 5.OOE+00 1.53E-01 Critical Pathway: Potable Water (PWtr)

Major Contributors t 0% or greater to total)

Nuclide Percentage H-3 8.22E+01 MN-54 1.56E+00 CO-58 6.70E+00 CO-60 7.26E+00 RB-88 1.35E-13 ZR-97 3.38E-03 NB-95 2.30E+00 AG-llOM 9.29E-03 I-134 4.36E-08 Qtr 3 - T.Spc. Total Body CHILD TBODY 7.34E-03 1.50E+00 4.89E-01 Critical Pathway: Potable Water (PWtr)

Major Contributors t 0% or greater to total)

Nuclide Percentage H-3 9.80E+01 MN-54 1.10E-01 CO-58 8.78E-01 CO-60 1.01E+00 RB-88 7.30E-03 ZR-97 9.52E-09 NB-95 2.35E-04 AG-llOM 2.37E-05 I-134 2.44E-05 Date/Time: 04/21/2003 14:53 brwmn Page - 4 p:\depts\zd84g\environsg roup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit____2,___2002__

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2 Liquid Receptor

=== PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) QUARTER 4 Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 3.64E-04 1.44E-02 1.39E-02 1.41E-02 1.40E-02 1.44E-02 0.00E+00 1.43E-02 TEEN 3.89E-04 1.06E-02 1.01E-02 1.02E-02 1.01E-02 1.04E-02 0.00E+00 1.03E-02 CHILD 4.94E-04 1.64E-02 1.59E-02 1.60E-02 1.59E-02 1.60E-02 0.OOE+00 1.60E-02 INFANT 8.44E-06 1.31E-02 1.31E-02 1.31E-02 1.30E-02 1.31E-02 0.OOE+00 1.31E-02

=== SITE DOSE LIMIT ANALYSIS ============================= QUARTER 4 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit

_____________________________ CHILD__ ________

Qtr 4 - Admin. Any Organ CHILD LIVER 1. 64E-()2 3.75E+C10 4.37E-01 Qtr 4 - Admin. Total Body CHILD TBODY 1. 60E-C)2 1.13E+C 10 1.42E+00 Qtr 4 - T.Spc. Any Organ CHILD LIVER 1.64E-02 5.OOE+00 3.27E-01 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.70E+01 MN-54 4.89E-02 CO-58 2.82E-02 CO-60 7.96E-02 AG-llOM 8.65E-06 I-131 3.14E-04 CS-137 2.83E+00 BA-140 5.45E-05 Qtr 4 - T.Spc. Total Body CHILD TBODY 1.60E-02 1.50E+00 1.07E+00 Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.92E+01 MN-54 1.33E-02 CO-58 8.84E-02 CO-60 2.40E-01 AG-llOM 7.08E-06 I-131 1.83E-04 CS-137 4.27E-01 BA-140 3.71E-03 Date/Time: 04/21/2003 14:53 brwmn Page - 5 p:\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2 Liquid Receptor

PERIOD DOSE BY ORGAN AND AGE GROUP (mrem) ANNUAL 2002 ======

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB ADULT 1.98E-03 3.95E-02 3.74E-02 4.13E-02 3.72E-02 7.79E-02 0.OOE+00 3.89E-02 TEEN 2.13E-03 2.94E-02 2.71E-02 2.74E-02 2.70E-02 5.59E-02 0.OOE+00 2.83E-02 CHILD 2.72E-03 4.47E-02 4.27E-02 4.29E-02 4.25E-02 5.30E-02 0.OOE+00 4.36E-02 INFANT 3.14E-05 3.49E-02 3.48E-02 3.48E-02 3.48E-02 3.49E-02 0.OOE+00 3.49E-02

=== SITE DOSE LIMIT ANALYSIS ANNUAL 2002 Age Dose Limit Max % of Annual - Limit Group Organ (mrem) (mrem) Limit 2002 - Admin. Any Organ ADULT GILLI 7.79E-02 7.50E+00 1.04E+00 2002 - Admin. Total Body CHILD TBODY 4.36E-02 2.25E+00 1. 94E+00 2002 - T.Spc. Any Organ ADULT GILLI 7.79E-02 1.00E+01 7.79E-01 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 4.76E+01 NA-24 1.58E-04 CR-51 4.15E-02 MN-54 1.25E+00 FE-59 1.06E-01 CO-58 3.16E+00 CO-60 4.65E+00 NI-65 3.34E-04 RB-88 1.50E-14 ZR-95 1.61E-03 ZR-97 3.77E-04 NB-95 3.86E+01 TC-99M 8.08E-06 TC-101 4.96E-20 AG-llOM 2.04E-02 TE-125M 4.56E+00 I-131 1.81E-05 I-134 1.86E-08 CS-136 7.55E-03 CS-137 3.57E-02 BA-140 1.63E-02 2002 - T.Spc. Total Body CHILD TBODY 4.36E-02 3.OOE+00 1.45E+00 Date/Time: 04/21/2003 14:53 brwmn Page - 6 p-\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Critical Pathway: Potable Water (PWtr)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.71E+01 NA-24 3.24E-04 CR-51 3.28E-04 MN-54 1.51E-01 FE-59 2.50E-02 CO-58 7.08E-01 CO-60 l.1lE+00 NI-65 1.41E-05 RB-88 1.39E-03 ZR-95 1.OOE-06 ZR-97 1.81E-09 NB-95 6.74E-03 TC-99M 3.93E-07 TC-101 4.29E-07 AG-llOM 8.91E-05 TE-125M 3.82E-01 I-131 7.61E-05 I-134 1.78E-05 CS-136 6.35E-02 CS-137 4.59E-01 BA-140 1.55E-03 Date/Time: 04/21/2003 14:53 brwmn Page - 7 p \depts'zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 4OCFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit_____2,___2002__

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2

=== I&P DOSE LIMIT ANALYSIS ============================== UARTER 1 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 1 - Admin. Any Organ CHILD LIVER 1.20E-04 5. 63E+C )0 2.13E-03 Qtr 1 - Admin. Total Body CHILD TBODY 1.20E-04 5.25E+C)0 2.28E-03 Qtr 1 - T.Spc. Any Organ CHILD LIV ER 1.20)E-04 7.50E+00 1.60E-03 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compas s Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 1.OOE+02 Qtr 1 - T.Spc. Total Body CHILD TBO'DY 1.20]E-04 7.50E+00 1.60E-03 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compas s Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 1.00E+02 Date/Time: 04/21/2003 14:53 brwmn Page - 8 p.\depts\zd 84g\envi ronsg rou p\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2

=== NG DOSE LIMIT ANALYSIS =QUARTER 1 Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit Qtr 1 - Admin. Gamma 4.92E-05 3.75E+C30 1.31E-03 Qtr 1 - Admin. Beta 3.68E-05 7.50E+C)0 4.90E-04 Qtr 1 - T.Spc. Gamma 4.92E-05 5.00E+00 9.85E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage AR-41 9.54E+01 XE-135 9.87E-01 XE-133 3.66E+00 Qtr 1 - T.Spc. Beta 3.68E-05 1.OOE+01 3.68E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Pointt: NA Nuclide Percentage AR-41 7.35E+01 XE-135 2.76E+00 XE-133 2.38E+01 Date/Time: 04/21/2003 14:53 brwmn Page - 9 p:\depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit_____2____2__02_

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2

=== I&P DOSE LIMIT ANALYSIS QUARTER 2 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 2 - Admin. Any Organ INFANT THYROID 3.46E-03 5.63E+C'0 6.14E-02 Qtr 2 - Admin. Total Body CHILD TBODY 1.69E-04 5.25E+0)0 3.22E-03 Qtr 2 - T.Spc. Any Organ INFANT THYROID 3.46E-03 7.50E+00 4.61E-02 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Critical Pathway: Grs/Goat/Milk (GMILK)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 3.73E+00 CO-58 1.95E-02 I-131 9.60E+01 I-133 2.85E-01 Qtr 2 - T.Spc. Total Body CHILD TBO DY 1.691 E-04 7.50E+00 2.26E-03 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compas s Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.78E+01 CO-58 7.02E-01 I-131 1.48E+00 I-133 6.07E-03 Date/Time: 04/21/2003 14:53 brwmn Page - 10 p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit_____2____2002__

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2

=== NG DOSE LIMIT ANALYSIS =QUARTER 2 Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit Qtr 2 - Admin. Gamma 3.07E-05 3.75E+C)0 8.17E-04 Qtr 2 - Admin. Beta 2.89E-05 7.50E+C)0 3.85E-04 Qtr 2 - T.Spc. Gamma 3.07E-05 5.OOE+00 6.13E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage AR-41 8.57E+01 KR-85M 1.76E-01 XE-135 8.71E+00 XE-133 5.41E+00 Qtr 2 - T.Spc. Beta 2.89E-05 1.OOE+01 2.89E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point : NA Nuclide Percentage AR-41 5.23E+01 KR-85M 4.88E-01 XE-135 1.93E+01 XE-133 2.79E+01 Date/Time: 04/21/2003 14:53 brwmn Page - 11 p.\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit_____2,___2002__

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2

=== I&P DOSE LIMIT ANALYSIS Q JARTER 3 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 3 - Admin. An- r Organ CHILD LIVER 5.89E-03 5.63E+C 30 1.05E-01 Qtr 3 - Admin. Tot :al Body CHILD TBODY 5.89E-03 5.25E+C)0 1.12E-01 Qtr 3 - T.Spc. Any Organ CHILD LIV ER 5.89]E-03 7.50E+00 7.86E-02 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compas s Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 1.OOE+02 Qtr 3 - T.Spc. Total Body CHILD TBO'DY 5.891E-03 7.50E+00 7.86E-02 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compas s Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 1.OOE+02 Date/Time: 04/21/2003 14:53 brwmn Page - 12 p \depts\zd 84g\environsg roup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit_____2,___2002__

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2

=== NG DOSE LIMIT ANALYSIS ==QUARTER 3 Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit Qtr 3 - Admin. Gamma 1.70E-05 3.75E+C)0 4.53E-04 Qtr 3 - Admin. Beta 1.14E-05 7.50E+C)0 1.53E-04 Qtr 3 - T.Spc. Gamma 1.70E-05 5.OOE+00 3.40E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage AR-41 9.76E+01 XE-135 1.09E-01 XE-133 2.27E+00 Qtr 3 - T.Spc. Beta 1.14E-05 1.OOE+01 1.14E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Pointt NA Nuclide Percentage AR-41 8.33E+01 XE-135 3.37E-01 XE-133 1.64E+01 Date/Time: 04/21/2003 14:53 brwmn Page - 13 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit_____2,___2002__

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2

=== I&P DOSE LIMIT ANALYSIS QUARTER 4 Age Dose Limit Max % of Quartr - Limit Group Organ (mrem) (mrem) Limit Qtr 4 - Admin. Any Organ INFANT THYROID 1.68E-03 5.63E+00 2.98E-02 Qtr 4 - Admin. Total Body CHILD TBODY 5.27E-04 5.25E+00 1.00E-02 Qtr 4 - T.Spc. Any Organ INFANT THYROID 1.681E-03 7.50E+00 2.24E-02 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Critical Pathway: Grs/Goat/Milk (GMILK)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 2.44E+01 I-131 7.56E+01 Qtr 4 - T.Spc. Total Body CHILD TBODY 5.271E-04 7.50E+00 7.02E-03 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.98E+01 I-131 1.82E-01 Date/Time: 04/21/2003 14:53 brwmn Page - 14 p:\depts\zd84g\environsg roup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit_____2____2002__

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2

= NG DOSE LIMIT ANALYSIS =QUARTER 4

Dose Limit Max % of Quartr - Limit (mrad) (mrad) Limit Qtr 4 - Admin. Gamma 1.83E-05 3.75E+00 4. 88E-04 Qtr 4 - Admin. Beta 1.26E-05 7.50E+00 1.68E-04 Qtr 4 - T.Spc. Gamma 1.83E-05 5.OOE+00 3.66E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage AR-41 9.73E+01 XE-135 1.48E-01 XE-133 2.59E+00 Qtr 4 - T.Spc. Beta 1.26E-05 1.00E+01 1.26E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point : NA Nuclide Percentage AR-41 8.13E+01 XE-135 4.48E-01 XE-133 1.83E+01 Date/Time: 04/21/2003 14:53 brwmn Page - 15 p \depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit_____2,___2002__

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2

I&P DOSE LIMIT ANALYSIS ===========================

ANNUAL 2002 Age Dose Limit Max % of Annual - Limit Group Organ (mrem) (mrem) Limit 2002 - Admin. Any Organ INFANT THYROID 9.81E-()3 1.13E+01 8.72E-02 2002 - Admin. Total Body CHILD TBODY 6.71E-C)3 1.05E+01 6.39E-02 2002 - T.Spc. Any Organ INFANT THYROID 9.81] 7--03 1.50E+01 6.54E-02 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Critical Pathway: Grs/Goat/Milk (GMILK)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 5.32E+01 CO-58 6.87E-03 I-131 4.67E+01 I-133 1.OOE-01 2002 - T.Spc. Total Body CHILD TBODY 6.71E-03 1.50E+01 4.47E-02 Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point:: NA Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.99E+01 CO-58 1.77E-02 I-131 5.16E-02 I-133 1.53E-04 Date/Time: 04/21/2003 14:53 brwmn Page - 16 p.\depts\zd84g\environsgroup\2002eff doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

Unit_____2____2002__

Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2

=== NG DOSE LIMIT ANALYSIS =ANNUAL 2002 Dose Limit Max % of Annual - Limit (mrad) (mrad) Limit 2002 - Admin. Gamma 1.15E-04 7.50E+00 1.54E-03 2002 - Admin. Beta 8.97E-05 1.50E+01 5. 98E-04 2002 - T.Spc. Gamma 1.15E-04 1.OOE+01 1.15E-03 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Point: NA Nuclide Percentage AR-41 9.34E+01 KR-85M 4.68E-02 XE-135 2.78E+00 XE-133 3.75E+00 2002 - T.Spc. Beta 8.97E-05 2.OOE+01 4.48E-04 Receptor: 4 Composite Crit. Receptor - NG Distance: 0.00 (meters) Compass Pointt: NA Nuclide Percentage AR-41 6.90E+01 KR-85M 1.57E-01 XE-135 7.46E+00 XE-133 2.34E+01 Date/Time: 04/21/2003 14:53 brwmn Page - 17 p \depts\zd84g\environsgroup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Unit 2, 2002 Report for: 2002 Unit Range - From: 2 To: 2

MAXIMUM DOSE ANALYSIS ====- ANNUAL 2002 ======

Age Dose Dose Type Group Organ (mrem)

Any Organ ADULT GILLI 8.20E-02 Liquid Receptor: 0 Liquid Receptor Gaseous Receptor: 5 Composite Crit. Receptor - IP Distance: 0.00 (meters) Compass Point: NA Liquid Dose: 7.79E-02  % of Total: 9.50E+01 Critical Pathway: Fresh Water Fish - Sport (FFSP)

Major Contributors 0% or greater to total)

Nuclide Percentage H-3 4.76E+01 NA-24 1.58E-04 CR-51 4.15E-02 MN-54 1.25E+00 FE-59 1.06E-01 CO-58 3.16E+00 CO-60 4.65E+00 NI-65 3.34E-04 RB-88 1.50E-14 ZR-95 1.61E-03 ZR-97 3.77E-04 NB-95 3.86E+01 TC-99M 8.08E-06 TC-101 4.96E-20 AG-llOM 2.OOE-02 TE-125M 4.56E+00 I-131 1.81E-05 I-134 1.86E-08 CS-136 7.55E-03 CS-137 3.57E-02 BA-140 1.63E-02 Gaseous Dose: 4.07E-03  % of Total: 4.97E+00 Critical Pathway: Vegetation (VEG)

Major Contributors ( 0% or greater to total)

Nuclide Percentage H-3 9.99E+01 CO-58 6.48E-02 I-131 1.45E-02 I-133 2.22E-04 Date/Time: 04/21/2003 14:53 brwmn Page - 18 p:\depts\zd84g\environsg roup\2002eff.doc

RETDAS v3.6.3 <BRA> VSSI 40CFR190 URANIUM FUEL CYCLE DOSE REPORT

MAXIMUM DOSE ANALYSIS ==ANNUAL 2002 ======

Age Dose Dose Type Group Organ (mrem)

Total Body CHILD TBODY 5.04E-02 Liquid Receptor: C Liquid Receptor Gaseous Receptor: 5 Composite Crit. Receptor - IP Distance: 0.0C (meters) Compass Point: NA Liquid Dose: 4.36E-02  % of Total: 8.66E+01 Critical Pathway: Potable Water (PWtr)

Major Contributors 0% or greater to total)

Nuclide Percentage H-3 9.71E+01 NA-24 3.24E-04 CR-51 3.28E-04 MN-54 1.51E-01 FE-59 2.50E-02 CO-58 7.08E-01 CO-60 1.1lE+00 NI-65 1.41E-05 RB-88 1.39E-03 ZR-95 1.OOE-06 ZR-97 1.81E-09 NB-95 6.74E-03 TC-99M 3.93E-07 TC-101 4.29E-07 AG-llOM 8.73E-05 TE-125M 3.82E-01 I-131 7.61E-05 I-134 1.78E-05 CS-136 6.35E-02 CS-137 4.59E-01 BA-140 1.55E-03 Gaseous Dose: 6.71E-03  % of Total: 1.33E+01 Critical Pathway: Vegetation (VEG)

Major Contributors 0% or greater to total)

Nuclide Percentage H-3 9.99E+01 CO-58 1.77E-02 I-131 5.16E-02 I-133 1.53E-04 Date/Time: 04/21/2003 14:53 brwmn LAST Page - 19 p:\depts\zd84g\environsgroup\2002eff doc

TABLE 7 Braidwood Nuclear Station January-March. 2002 34 ft Wind Speed and Direction 203Ft-34Ft Delta-T (F)

Number of Observations - 2150 Values are Percent Occurrence SPEED --------------------------- :------ WIND DIRECTION CLASSES ----------------------------------

---

STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 MU 0.00 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 C SU 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0 00 0.00 0.00 A N 0.00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0 00 L SS 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 M MS 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 a 00 0 00 0.00 0 00 0 00 ES 0.00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0.00 EU 0 00 0 00 0 00 0 00 0 00 000 0.00 0 00 0.00 0 00 0.00 0 00 0.00 0.00 0 00 000 0 00 0 00 MU 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 05 0 00 0 00 0 00 0 00 005 0.05 1 SU 0.00 0.00 0.00 0 05 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0.05 0 00 0.00 0 00 0 09 0 09

- N 0 09 0 14 0 19 0.28 0 23 0 05 0 05 0 05 0 05 0 00 0 00 0 05 0.09 0 09 0 19 0 33 1 86 1 86 3 SS 0.19 0.05 0 23 0.42 014 028 0 00 0.05 0.05 0 05 0 05 0 19 0 23 0 42 0.56 0 33 3 21 3 21 MS 0 05 0 09 0 09 0 05 0 19 0 09 0 05 0 00 0 05 0.14 0 00 0 09 0.51 0 33 0 37 0 09 2 19 2 19 ES 0.00 0.00 0.00 0 09 0.09 0 05 0.00 0 00 0 00 0.05 0 05 0.00 0.00 0 28 0 23 0 05 0 88 0 88 8 28 F ,c00 0 00 0.00 0 00 0 05 0 00 0 00 0.00 0 00 0.00 0 00 0.00 0 05 0.28 0 09 0.05 0 51 0.51 0.00 0.00 0 00 0.05 0 00 0 05 0.00 0.05 0 05 0 14 0 09 0 19 0.09 0 14 0 14 0 98 0 98 4 SU 0.00 0 00 0 00 0.14 0 09 0 00 0 05 0 09 0 09 O 14 0 19 0 05 0 28 0 09 0.14 0.05 1.40 1 40

- N 0.56 0.98 0 98 1 95 0 88 0 14 0.23 0 19 0 09 0 05 0.47 0.65 0 74 0 51 0 37 1 12 9.91 9 91 7SS 033 0.09 0 28 0.42 0.47 0.23 0 60 0.28 0.70 0.23 1.26 7 28 1 26 1 21 0 65 0 93 11 21 11 21 MS 0 00 0 00 0 00 0 00 0 00 0 14 0 09 0 05 0.05 0 00 0 05 1 40 1.02 0.42 0 00 0 00 3 21 3.21 ES 0.00 0.00 0 00 0.00 0 00 0 00 0 05 0 00 0 00 0 00 0.00 0 23 0 19 0 00 0.00 0.00 0.47 0.47 27 67 EU 0 00 0 05 0.19 0.00 0 00 0 00 0 05 0 00 0 00 0 09 0 05 0 28 0.47 1 12 0 65 0 09 3 02 3 02 MU 0.00 0.00 0 00 0.05 0 00 0 05 0 00 0 05 0.14 0.05 0.00 0 33 0 37 0 47 0.00 0.19 1.67 1 67 8 SU 0.00 0 00 0.00 0.00 0.00 0.00 0 05 0.23 0 00 0 09 0 19 0.37 0 14 0 51 0 05 0 23 1.86 1.86

- N 0 70 0 79 1 63 0 37 0 14 0 09 0 19 1.81 1 67 0.70 2.09 1 81 1.67 2 33 1.12 2 51 19 63 19.63 I Ss 0 05 0.00 0.05 0 05 0.00 0 00 0 47 1.35 1 53 0 74 6 00 2.23 0.70 0.65 0.14 0 47 14 42 14 42 2MS 0 00 0 00 0 00 0 00 0.00 0 00 0.05 0 00 0 00 0 00 0.19 0 05 0.00 0.00 0.00 0 00 0 28 0.28 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 40.88 EU 0 00 0 00 0.00 0.00 0.00 0 00 0.09 0.14 0 51 0 37 0 37 0.28 0.65 0 51 0 00 0 14 3.07 3.07 1MU 0 00 0 00 0.00 0.00 0.00 0 00 0.00 0.09 0 14 0 47 0 51 0.09 0 19 0.23 0.05 0 05 1.81 1.81 3 SU 0.00 0 00 0 05 0 00 0 00 0 00 0 00 0 09 0.23 0.42 0 47 0 00 0 09 0 23 0 14 0 05 1 77 1 77

- N 0 37 0 19 1.12 0 00 0 00 0 00 0.00 0.42 1.63 1.35 1.72 0 14 1 16 1 26 0 28 0 56 10 19 10 19 1 SS 0.00 0 00 0.05 0 00 0.00 0.00 0.00 0 23 1.12 1.30 0 93 0.00 0 00 0 09 0 00 0.00 3 72 3 72 8MS 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0.00 0 00 0 00 0.00 0 00 0.00 0 00 ES 0 00 000 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 20.56 Murray & Trettel, Inc.

• 414 West Frontage Road

• Northfield, Illinois

• 60093 -f (847) 446-7800

TABLE 7 continued Braidwood Nuclear Station January-March. 2002 34 ft. Wind Speed and Direction 203Ft-34Ft Delta-T (F)

I ---------------------------------- WIND DIRECTION CLASSES ----------------------------------

cb N NNE NE ENE E --------- STABILITY CLASSES ----------

ESE SE SSE 5 SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU O 00 0 00 0.00 0.00 0 00 0 00 0 00 0 05 0 05 0 05 0.00 0.00 0 00 0.00 0 00 0 05 0 19 1MU 0 00 0 00 0O.19 0 00 0 00 0.00 0.00 0 00 0.00 0 05 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0.05 0.05 9 SU 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0.05 0 09 0 00 0.00 0 00 0.00 0 00 0 05 0 19

- N 0 00 0 00 O 00 0.00 0 19 0 00 0.00 0 00 0.00 0 23 0 42 0.23 0 00 0.33 O 14 0 00 0 14 1.49 1 49 2 SS O 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 19 0.19 4MS 000 0 00 000 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 ES 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 0.00 0.00 O 00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0.00 2.09 EU 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 GMU 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0.00 0 00 0 00 0.00 0.00 0.00 000 0 00 T SU 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.05 0 00 0.00 0 00 0 05 N 0 00 0 00 0.00 0 05 0 00 0 00 0 00 0 00 0 05 0 00 0 00 0 00 0 00 0 42 0 00 0.00 0 00 0 47 0 47 2 SS 0.00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 4IMS 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 ES 0.00 0.00 0.00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00.51 TOT 2 33 2 37 4.84 3 86 2 33 1 12 2.05 5 21 8.56 6 93 14 93 10.65 10 84 11.26 5 16 7 58 100.00 6 79 4.56 5 35 43 53 32 74 5 67 1.35 100.00 Wfs .rection by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -STABILITY CLASSES-0 00 0.05 0 19 0.00 0 05 0 00 0 14 0 19 0 56 0 51 0 42 0 56 1 16 1 91 0 74 0 33 6.79 Extremely Unstable 0.00 0 00 00o 0 05 0 05 0 05 0 05 0 14 0 37 0 56 0.65 0 56 0.74 0 79 0.19 0 37 4 56 Moderately Unstable 0.00 0 00 0.05 0 19 0 09 0 00 0 09 0.42 0 37 0 74 0.84 0 42 0.60 0.84 0 33 0.37 5.35 1 72 2 09 3 91 Slightly Unstable 2 60 1.26 0 28 0.47 2 51 3 67 2 51 4.51 2.65 4.42 4 33 1.95 4 65 43 53 Neutral 0 56 0 14 0 60 0.88 0 60 0 51 1 07 1.91 3 49 2 42 8 23 4.70 2 19 2.37 1 35 1 72 32.74 Slightly Stable 0 05 0 09 0 09 0.05 0.19 0 23 0.19 0 05 0.09 014 0 23 1.53 1.53 0.74 0 37 0 09 5.67 Moderately Stable 0.00 0.00 0.00 0 09 0 09 0.05 0 05 0.00 0.00 0 05 0 05 0.23 0 19 0.28 0 23 0.05 1 35 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -WIND SPEED CLASSES-0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0.00 0.00 0 00 O 00 0 00 0.00 0 00 CALM 0 33 0 28 0 51 0 88 0 65 0.47 0.09 0 09 0.14 0.23 0.09 0 37 0.88 1.12 1 35 0 79 8.28 < 3.5 mph 0 88 1 07 1 26 2.51 1 53 0 51 1 07 0 60 0.98 0 47 2.09 4.70 3.72 2.60 1.40 2.28 27 67 3.6 - 7.5 mph 0 74 0.84 1 86 0.47 0 14 0 14 0 79 3.44 3 35 1 67 8 51 5.07 3.35 5 07 1 95 3 49 40 88 0 37 0 19 7.6 - 12.5 mph 1.21 0 00 0 00 0 00 0 09 0 98 3 63 3.91 4.00 0 51 2.09 2.33 0.47 0.79 20 56 12.6 - 18 5 mph 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 05 0 47 0 65 0 23 0 00 0.33 0 14 0.00 0 23 2 09 18 6 - 24 5 mph 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 47 0.00 0.00 0 00 0 51 > 24.5 mph Murray & Trettel, Inc.

• 414 West Frontage Road

• Northjield, Illinois

• 60093 (847)

( 446-7800

TABLE 8 Braidwood Nuclear Station April-June. 2002 34 ft. Wind Speed and Direction 203Ft-34Ft Oelta-T (F)

Number of Observations - 2161 Values are Percent Occurrence SPEED ---------------------------------- WIND DIRECTION CLASSES ----------------------------------

CLASS N --------- STABILITY CLASSES ----------

NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU O 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0, MU 0 00 0.00 .00 0 00 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 O 00 0 00 C SU 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 O 00 0.00 0.00 0.00 O 00 0.00 A N 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0 00 0.00 L SS 0 00 0.00 0 00 0.00 0 00 0.00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0.00 0.00 0.00 0 00 0.00 0.00 MMS 0.00 0.00 0.00 0 00 0.00 0.00 0 00 0.00 0.00 0.00 0 00 0 00 0.00 0.00 0.00 0 00 0 00 ES 0.00 0.00 0 00 0 00 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 EU 0 00 0 05 O 05 0.05 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0.09 0.00 0 00 0 00 0 00 0.23 0 23 MU 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 0.00 0 09 1 SU 0 00 0.00 0 05 0 09 0.09 0 00 0 00 0.05 0.05 0.00 0 00 0 00 0.05 0 00 0 00 000 0.05 0.32 0.32

- N 0.00 0 28 0.28 0 56 0 28 0 14 0 19 0 09 0 05 0 05 0 09 0 05 0 09 0.28 0 28 0 05 2.73 2.73 3SS 014 0.09 0 46 0 69 0.88 0 65 0 37 0 28 0 05 0 05 0 14 0.09 0 46 0.88 0 32 0.05 5.60 MS 0 23 0 19 0 14 0 23 0 37 5 60 0 93 0 14 0.09 0 09 0 09 0.05 0.19 0 79 0.19 0 28 0 19 4.16 ES 0 09 0 00 0 09 0 05 0 00 0 28 4 16 0 05 0.09 0 00 0 14 0 14 0.09 0 37 0 14 019 0 00 1.71 1 71 14.85 El' 09 0.23 0 28 0.23 0 09 0.51 0 14 1 06 0 88 0.56 0 56 0 83 0.23 0 65 0 19 0 23 6 76 6 76 ts: 09 0 05 0.14 0.14 0.00 0 09 0.28 0 09 0.14 0 23 0.28 0 05 0 09 0 14 0 19 0.09 2.08 4 SU 0 19 0 14 0 14 0 19 2 08 0 00 0.14 0.28 0.28 0.05 0.14 0 05 0.09 0.05 0 23 0 14 0 14 2.22 2.22

- N 0 42 1.02 1 85 1 53 1.11 0.42 0 51 0 46 0 69 0 37 0.42 0 88 0.65 1.02 1.06 0.65 13.05 13.05 7 SS 0.37 0 05 0 28 0 37 0 56 1.06 1 39 1 85 2 08 0 51 1.20 1 67 1 62 0.79 0.51 0 32 14.62 MS 0 00 0.05 0 00 0.05 14.62 0 05 0 23 0 28 0 23 0 32 0 19 0 32 0.46 0 56 0 09 0 00 0 00 2.82 ES 0 00 0 00 0 00 0 00 0 05 0 00 0.00 2.82 0.00 0 00 0 05 0 05 0.09 0.05 0 00 0 00 0 00 0.28 0 28 41.83 EU 0.09 0 14 0 37 0 19 0 05 0.05 0 09 0 51 0 56 0.42 0.60 0 88 0.74 1.11 0 69 0.69 7.17 7.17 MU 0 00 0.14 0.28 0.05 0 00 0.05 0.09 0 23 0.09 0 05 0 09 0.28 0.09 0 23 0 28 0 09 2.04 8 SU 0.09 2 04 O 05 0.60 0 00 0 05 0 00 0 05 0 05 0.14 0 14 0.05 0.05 0.23 0.28 0.14 0 09 1 99

- N 0 97 0 83 1.90 1.99 0.46 0 28 0 42 0 56 0 69 0 56 0.56 1.53 0 74 0 42 0 74 1.11 0.88 12.63 12 63 1 SS 0.09 0 00 0 14 0.05 0.14 0 23 0 37 1.80 2 08 0 69 2 13 0 19 0.28 0 00 0 14 0 23 8 56 2MS 0 00 0.00 0.00 0 00 8 56 0 00 0.00 0.00 0.00 0 00 0.00 0.19 0.05 0 00 0 00 0 00 0.00 0.23 ES 0 00 0.00 0 00 0.00 0.00 0 00 0.00 0.23 0 00 0.00 0.00 0 00 O 00 0 00 0 00 0 00 0 00 0.00 0 00 32.62 EU 0 CO 0.00 0.05 0 00 0 00 0 00 0 00 0.00 0.56 0.79 0 37 0 14 0.32 0.23 0 14 0 00 2 59 2 59 1 MU 0.00 0.09 0 05 0.00 0 00 0.00 0.00 0.00 0 05 0.19 0 14 0.00 0 09 0 05 0 00 0 00 3 SU 0.00 0 65 0 65 0 00 0 05 0 00 0 00 0 00 0 00 0 00 0.09 0.14 0.00 0.05 0.05 0.14 0 00 0 00 0.51 0 51

- N 0 19 0 00 0 19 0.00 0 00 0.00 0 14 0.19 0.37 0 88 0 37 0.09 0 19 0 42 0 09 0.05 1 SS 0.00 3 15 3.15 0.00 0 00 0 00 0 00 0 00 0 00 0 09 0.46 1.34 0 46 0.05 0 05 0.00 0.05 0 00 2 50 9MS 0 00 0 00 0 00 0.00 2 50 0.00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0.00 0.00 0.00 a 00 ES 0.00 0 00 0 00 0 00 0.00 0 0 0.00 00 0 00 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0.00 0 00 0.00 9.39 Murray & Trettel, Inc.

• 414 West Frontage Road

• Northfield, Illinois

• 60093 eir (847) 446-7800

TABLE 8 continued Braidwood Nuclear Station April-June. 2002 34 ft. Wind Speed and Direction 203Ft-34Ft Delta-T (F)

S. -- - WIND DIRECTION CLASSES ---------------------------------- --------- STABILITY CLASSES ----------

CI\SS" N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0 28 0 00 0.00 0 23 0 05 0.00 0 00 0 56 0 56 1 MU 0.00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0.00 0.05 0 00 0 00 0.00 0 00 0 00 0.00 0 05 0 05 9 SU 0.00 0.00 0 00 0 00 0.00 0 00 0.00 0 00 0.00 0.05 0.00 0.00 0.00 0 00 0 00 0 00 0.05 0 05

- N 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 19 0 00 0 05 0 14 0.05 0.00 0.00 0 42 0 42 2 SS 0 00 0 00 0.00 0 00 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 19 0.19 4MS 0.00 0.00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 0.00 0.00 0.00 0.00 0 00 0 00 0 00 0 00 0.00 ES 0.00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0.00 1.25 EU 0.00 0.00 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 G MU 0.00 0.00 0.00 0 00 0.00 0.00 0 00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 T SU 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 N 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0.05 0.00 0.00 0.00 0.00 0 00 0 00 0.05 0.05 2 SS 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0.00 4 MS 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0.00 0 00 ES 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 0.00 0.00 0 00 0.00 0.00 0.00 0 00 0 00 0.00 0 co 0.05 TOT 3 05 3 38 7 36 4 91 3 89 5 18 4.95 8 14 9 35 8.33 9 21 7 17 7 77 7.6B 5 83 3.79 100 00 17.31 4.91 5.09 32.02 31.47 7.22 1.99 100 00 W4iI,_rection by Stability N NNE NE ENE E ESE SE SSE S 55W SW WSW W WNW NW NNWTOTAL -STABILITY CLASSES-0 19 0 42 0 74 0 46 0 14 0.56 0 23 1 57 1 99 2.04 1.53 1.94 1.53 2 04 1.02 0.93 17.31 Extremely Unstable 0 09 0 28 0.46 0.19 0.00 0.14 0 37 0 32 0 32 0 51 0 51 0 32 0 28 0 42 0 51 0.19 4 91 Moderately Unstable 0.28 0.19 0 83 0.28 0 05 0 14 O 37 0 37 0.28 0 46 0 09 0.23 0.32 0 65 0 28 0 28 5.09 Slightly Unstable 1.57 2.13 4.21 2.55 1.67 0.97 1.39 1.43 1 67 2 08 2 41 1 80 1 48 2.50 2.55 1 62 32.02 Neutral 0 60 0 14 0 88 1 11 1 57 1 94 2 13 4 03 4 67 2.78 3 93 1 99 2 41 1 67 1.02 0.60 31.47 Slightly Stable 0 23 0 23 0 14 0 28 0.42 1.16 0 42 0.32 0 42 0 28 0 56 0.69 1 34 0 28 0 28 0 19 7.22 Moderately Stable 0.09 0.00 0 09 0 05 0 05 0.28 0 05 0 09 0.00 0 19 0.19 0 19 0.42 0.14 0 19 0.00 1 99 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNWTOTAL -WIND SPEED CLASSES-0.00 0 00 0 00 0 00 0.00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0.00 0 00 0.00 0.00 0.00 CA L M 0 46 0 60 1.06 1 67 1 53 1 99 0 79 0 60 0 23 0.32 0 42 0 56 1 71 1.48 1.11 0.32 14 85 < 3 5 mph 1.16 1.53 2 68 2.50 1.85 2.45 2.87 3.98 4.16 2.04 2 87 4.07 3 24 2.92 2.08 1 43 41 83 3 6 - 7.5 mph 1.25 1 16 3 29 0 74 0 51 0 74 1 16 3 29 3 42 1.85 4.58 2 17 1.76 2.36 2 36 1.99 32.62 7.6 - 12.5 mph 0.19 0 09 0 32 0 00 0.00 0 00 0 14 0.28 1.53 3.33 1 34 0.32 0 69 0 83 0.28 0.05 9 39 12.6 - 18 5 mph 0.00 0.00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0.74 0 00 0 05 0 37 0 09 0.00 0 00 1 25 18 6 - 24 5 mph 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0.05 0.00 a 00 0 00 0.00 0.00 0 00 0.05 > 24 5 mph Murray & Trettel, Inc.

• 414 West FrontageRoad

• Northflield, Illnois

• 60093 ' (847) 446-7800

TABLE 9 Braidwood Nuclear Station July-September, 2002 34 ft. Wind Speed and Direction 203Ft-34Ft Delta-T (F)

Number of Observations - 2071 Values are Percent Occurrence SPEED ----------------------------- WIND DIRECTION CLASSES ----------------------------------

---

STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0O.00 MU 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 O 00 0.00 C SU 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0.00 A N 0 00 0.00 0.00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 0.00 L SS 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 M MS 0.00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 ES 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 0.00 0.00 0.00 EU 0.00 0 00 0.10 0 00 0 05 0.00 0 05 0 05 0 00 0.10 0 00 0 05 0 05 0.14 0.05 0 05 0 68 0 68 MU 0 00 0 00 0 05 0 00 0.14 0 05 0.00 0 05 0 00 0 00 0 05 0 00 0 10 0 14 0.00 000 0 58 0 58 I SU 0.05 0.00 0.00 0 24 0.05 0 05 0 14 0.05 0.00 0.00 0.00 0.00 0 00 0 05 0 05 0 00 0 68 0 68

- N 0 14 0 19 0 43 0 68 0.43 0 39 0.14 0.14 0.05 0.05 0 00 0 10 0.24 0.10 0 10 0 05 3 24 3 24 3 SS 0.14 0 58 1 35 2.03 0 82 0 58 0 24 0 19 0 14 0 00 0 19 0.19 0 68 0 48 0 58 0 14 8 35 8.35 MS 0 39 0.24 0 29 0 53 1.59 0.77 0 19 0 19 0.05 0 24 0.19 0.19 0 77 0 48 0.29 0 29 6 71 6 71 ES 0.19 0.05 0.14 0.14 1 21 1 11 0 10 0.00 0 05 0 10 0 05 0.00 0.72 0 72 0 29 0.19 5 07 5 07 25 30 E' 39 0 19 1 93 2.46 0.77 0.53 1 11 1.30 0 53 0 97 0 92 1.45 2 03 1 55 0 58 0 34 17.09 17.09 Mi. 05 0 14 0.39 0.39 0.48 0 19 0 34 0.43 0 19 0 05 0.00 0 00 0.58 0.19 0 10 0 29 3 81 3.81 4 SU 0.14 0.05 0 24 0 14 0 05 0.14 0 05 0.14 0 10 0 00 0.00 0 14 0.24 0.00 0 05 0 05 1.55 1.55

- N 0 53 1.06 1 50 1.50 0 34 0 29 0.63 0 97 0 48 0 53 0.82 0 77 0.77 0.29 0.48 0 43 11.40 11.40 7 SS 0.68 1 50 1.64 1 01 0.05 0 34 0.72 1 98 3 19 0 68 1 11 0.63 0.72 0 19 0 29 0.43 15 16 15.16 MS 0.10 0 10 0.05 0.05 0.10 0.39 0 39 0.10 0 00 0.05 0.05 0 43 0.34 0 00 0 00 0.00 2 12 2.12 ES 0 00 0.00 0 00 0 00 0 00 0.14 0.05 O 05 0.00 0 00 0.00 0 10 0 10 0 00 0.00 0 00 0.43 0.43 51.57 EU O 14 0 43 0.82 0.14 0.10 0 00 0 10 0 48 0 48 1 11 1 26 0 87 0 97 0 29 0 05 0 14 7.39 7 39 MU 0 05 0.05 0 10 0.05 0 00 0.00 0.00 0.10 0 10 0 14 0.24 0 14 0 05 0 00 0 00 0 00 1.01 1 01 8 SU 0.19 0.10 0.10 0.00 0.00 0.00 0 00 0 05 0.19 0.14 0.10 0.10 0.05 0.00 0.00 0 00 1.01 1.01

- N 0 29 0.68 0 24 0.05 0.00 0.00 0 05 0.10 1 30 1.06 2.66 0 58 0.00 0.05 0 00 0 10 7 15 7.15 1 SS 0.24 0 14 0 00 0.00 0.00 0 00 0 00 0 39 1.11 1 30 0.68 0 00 0.00 0 05 0.00 0 24 4.15 4 15 2MS 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 0.00 0.00 0.00 0.00 0 00 0 00 ES 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0.00 0.00 20 71 EU 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0.00 0 92 0 19 0 00 0 00 a00 0 00 0.00 1.11 1.11 I MU 0.00 0.00 0 00 0.00 0.00 0 00 0 00 0 00 0 00 0.14 0 14 0 00 0.00 0 00 0.00 0 00 0 29 0 29 3 SU 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 00 0.19 0.19

- N 0.05 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0.00 0 43 0 14 0.05 0 10 0 00 0 00 0 05 0 82 0 82 1 SS 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0 00 8MS 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 ES 0.00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 2 41 Murray & Trettel, Inc.

• 414 West FrontageRoad

• Northfield, Illinois

• 60093 a (847) 446-7800

TABLE 9 continued Braidwood Nuclear Station July-September. 2002 34 ft Wind Speed and Direction 203Ft-34Ft Delta-T (F)

---

WIND DIRECTION CLASSES ----------------------------------

---

STABILITY CLASSES ----------

Cb' N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0.00 0.00 0.00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 I MU 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0.00 0.00 0 00 0.00 0 00 0 00 9 SU 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0 00

- N 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0.00 0.00 2 SS 0.00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0.00 4MS 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0.00 ES 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0.00 0 00 0.00 0 00 0.00 0 00 0.00 0 00 EU 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0 00 0.00 0 00 0 00 000 0 00 0 00 0 00 0 00 0 00 0 00 GMU 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 T SU 0.00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0.00 0.00 0.00 O 00 0 00 0 00 0 00 0 00 0 00 0 00 N 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0 00 2 SS 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0.00 0 00 4MS 0 00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0.00 0 00 ES 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0 00 TOT 3 77 5 50 9 37 9.42 6 18 4 97 4 30 6.76 8.02 8 16 8 84 5.79 8 50 4 73 2 90 2 80 100.00 26 27 5.70 3 43 22.60 27.67 8 84 5.50 100 00 WI K rection by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -STABILITY CLASSES-0.53 0 63 2 85 2.61 0.92 0 53 1 26 1 83 1 06 3 09 2 37 2.37 3.04 1 98 0 68 0 53 26.27 Extremely Unstable 0.10 0 19 0.53 0 43 0 63 0.24 0.34 0 58 0 29 0.34 0 43 0 14 0 72 0 34 0.10 0 29 5.70 Moderately Unstable 0 39 0.14 0 34 0 39 0.10 0.19 0.19 0.24 0 29 0 29 0.14 0.24 0 29 0 05 0 10 0 05 3 43 Slightly Unstable 1 01 1 93 2 17 2.22 0 77 0.68 0 82 1 21 1.83 2.08 3 62 1 50 1 11 0 43 0 58 0.63 22.60 Neutral 1.06 2.22 2.99 3 04 0.87 0 92 0 97 2 56 4 44 1.98 1 98 0 82 1 40 0.72 0.87 0 82 27.67 Slightly Stable 0.48 0.34 0 34 0 58 1 69 1.16 0 58 0.29 0.05 0 29 0.24 0 63 1 11 D.48 0.29 0 29 8 84 Moderately Stable 0 19 0 05 0 14 0.14 1.21 1 26 0 14 0 05 0.05 0 10 0 05 0 10 0 82 0.72 0 29 0 19 5.50 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -WIND SPEED CLASSES-0.00 0.00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 CAL M 0.92 1.06 2.37 3 62 4 30 2 95 0 87 0.68 0 29 0.48 0.48 0 53 2.56 2.12 1.35 0 72 25 30 < 3.5 mph 1 88 3.04 5.75 5 55 1.79 2.03 3 28 4.97 4.54 2.27 2 90 3.52 4 78 2.22 1.50 1 55 51.57 3.6 - 7 5 mph 0 92 1.40 1.26 0.24 0.10 0 00 0 14 1.11 3.19 3.77 4.93 1.69 1.06 0.39 0 05 0.48 20 71 7 6 - 12.5 mph O 05 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 1.64 0.53 0.05 0.10 0 00 0.00 0 05 2.41 12.6 - 18 5 mph 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 18 6 - 24 5 mph 0.00 0 00 0.00 0 00 0.00 0 00 0 00 0.00 0 00 0.00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 > 24.5 mph Murray & Trettel, Inc.

• 414 West FrontageRoad

• Northfield, Illinois

• 60093 8 (847) 446-7800

TABLE 10 Braidwood Nuclear Station October-December, 2002 34 ft Wind Speed and Direction 203Ft-34Ft Delta-T (F)

Number of Observations - 2170 Values are Percent Occurrence SPEED ---------------------------------- WIND DIRECTION CLASSES ----------------------------------

---

STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0 00 MU 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 0 00 0 00 C SU 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0.00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 A N 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 L SS 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 M MS 0.00 0.00 0.00 0 00 0 00 0 00 0 00 O 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 ES 0 00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0.00 EU 0 00 0 00 0 00 0 00 0.00 0 00 0.05 0 00 0.00 0 00 0 00 0.00 0 00 0 05 0 00 0.00 0 09 0.09 MU 000 0.00 0.00 0 00 0 00 0 00 0 09 0 00 0.00 0.00 0.00 0 05 0 05 0 00 0.09 0.05 0.32 0 32 I SU 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 05 0 05 0.18 0 18

- N 014 0.37 0 32 0 69 0 14 0.05 0 05 0 05 0 00 0 05 0.05 0 14 0.18 0 28 0 00 0 18 2.67 3SS 037 0.23 2 67 0.65 0.78 0.60 0 37 0 14 0 00 0.00 0 00 0.05 0.14 0.55 0 69 I 01 0.37 5 94 5 94 MS 000 0 09 0.00 0 14 0.37 0 41 0 14 0 05 0.18 0 05 0.09 0 37 0 97 0 46 0.41 0 23 3 96 ES 0 00 0.00 0 00 0 32 3 96 0 41 0 28 0.05 0 09 0.05 0.00 0 1B 0 05 0 14 0 32 0 l1 0 09 2 17 2.17 15.35 E' 09 0 00 0 05 0 05 0 18 0 14 0 00 0 09 0.05 0.05 0.00 0 14 0 28 0.23 0 65 0 32 2.30 2 30 ML- ,05 0.05 0.00 0.23 0 14 0 05 0.05 0 09 0.00 0 23 0.32 0 00 0 00 0.09 0 18 0 23 1.71 1 71 4 SU 0 09 0 09 0 14 0 41 0 09 0 09 0.00 0 00 0.00 0 05 0 00 0 18 0 09 0 05 0.18 0 09 1.57

- N 0 97 1 57 2.03 2.03 1.47 1 34 0 23 0 14 0 23 0.37 0 23 0 37 0.97 1.38 1 24 1 57 2.26 16 82 16 82 7 SS 0 60 0 65 1.01 0 65 0 37 0.37 0 65 0.69 1 34 0 32 1.20 1 94 2 30 1.11 1 15 1 11 15 44 MS 0 00 0.05 0 00 15.44 0 00 0.00 0 14 0.14 0 05 0 18 0 46 0 32 1 52 0 65 0 37 0.05 0 18 4 10 4 10 ES 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0.00 0 00 0 23 0 32 0 00 0 00 0 00 0 55 0.55 42.49 EU 0 18 0 05 0 00 0 00 0 05 0.00 0.05 0 32 0 18 0 46 0.32 0 00 0 32 0.28 0.41 0 32 2 95 2.95 mU 0.14 0 09 0.00 0 00 0 05 0 05 0.05 0.00 0.09 0 09 0 37 0.23 0 32 0 09 0.14 0 23 1.94 1 94 8 SU 0.09 0 09 0 05 0.00 0 05 0 00 0 05 0.05 0 00 0 32 0 37 0.32 0.14 0 18 0 18 0 18 2 07 2 07

- N 0 51 0.83 0 97 0 05 0 32 0 46 0 09 1 06 0.83 0.97 1.61 1.57 1 52 1 38 0 92 1.57 14.65 I SS 0.09 0 05 0.05 0 05 0 00 0 14 0 23 0.28 1 24 1.34 14.65 2 76 0 83 0 88 0.46 0.28 0 14 8 80 2MS 0.00 0 00 0.00 0 00 0 00 0.00 0.00 0.00 0 00 0.37 8 80 0 74 0 00 0.00 0.00 0.00 0 00 1.11 ES 0 00 0.00 0 00 0.00 0 00 0.00 0 00 0 00 0.00 0.00 1.11 0 05 0 00 0 00 0 00 0.00 0.00 0 05 0.05 31.57 EU 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0.05 0 05 0 14 0.09 0 00 0.05 0.05 0.41 0 41 1MU 0.05 0.00 0.00 0.00 0.00 0 00 0.00 0 00 0 00 0 09 0.09 0 09 0 05 0.00 0.09 0.00 0.46 0 46 3 SU 0 00 0.00 0.00 0 00 0.00 0 00 0.00 0.00 0 05 0.14 0.14 0.14 0.14 0.00 0.05 0 00 0 65 0 65

- N 0.14 0 05 0.00 0 00 0 00 0.00 0.05 0 18 0.37 0 83 0.55 0.60 1.43 0 37 0 18 0 37 5.12 1 SS 0 00 0 00 0.00 0.00 0.00 0 00 5 12 0 05 0.23 0 41 1 75 0 74 0 00 0 00 0.00 0 00 0 00 3.18 8MS 0 00 0 00 0.00 0 00 0.00 0 00 3 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 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 9.82 Murray & Trettel, Inc.

• 414 West Frontage Road

• Northfield, Illinois

• 60093 'm (847) 446-7800

TABLE 10 continued Braidwood Nuclear Station October-December. 2002 34 ft. Wind Speed and Direction 203Ft-34Ft Delta-T (F)

S ---------------------------------- WIND DIRECTION CLASSES ----------------------------------

CbS --------- STABILITY CLASSES ----------

N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 000 000 0.00 0.00 0.00 0 00 0 00 1MU 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0.00 0,00 0 00 0 00 0 00 0 00 9 SU 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0 0o 0.00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0 00

- N 0.00 0.00 0.00 0.00 0 00 0 0o 0.00 0 09 0 09 0 18 0 14 0.00 0.18 0 00 0 00 0.00 0 69 2 SS 0 00 0.00 0.00 0 00 0 69 0.00 0 00 0.00 0 00 0 05 0 00 0 00 0.00 0 00 0.00 0 00 0.00 005 0 05 4MS 0.00 0 00 0 00 0 0o 0 00 0 00 0 00 o 00 0 00 0 00 0.00 0.00 0 00 0 00 0.00 0.00 0 00 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 74 EU 0 00 0.00 0 00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 GMU 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 T SU O 00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 05 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0.05 0.05 N 0 00 0 00 0 00 0 00 0.00 0 00 0.00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0.00 0 00 0 00 2 SS 0 00 0.00 0.00 0 00 0.00 0.00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 000 0.00 0 00 0 00 0 00 0.00 4MS 0 00 0 00 0.00 0.00 0.00 0 00 0.00 0 00 0 00 0 00 0.00 0.00 000 0 00 0.00 0.00 0 00 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 0 0 05 TOT 3 50 4.70 5 25 4 88 4.10 2 81 2 03 3 55 5 53 8 02 10 51 9 63 11 98 7 65 7.83 8 02 100.00 5 76 4.42 4.52 39.95 33.41 9.17 2.76 100 00 Wi1. rection by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -STABILITY CLASSES-0 28 0 05 0.05 0 05 0 23 0.14 0 09 0.41 0 23 0.55 0.37 0.28 0.69 0 55 1.11 0 69 5.76 Extremely Unstable 0 23 0.14 0 00 0.23 0 18 0 09 0 18 0 09 0.09 0 41 0 78 0 37 0 41 0 18 0.51 0 51 4 42 Moderately Unstable 0.18 0.18 0.18 0.46 0 14 0 14 0.05 0 05 0.09 0 51 0 51 0 65 0 37 0 23 0.46 0.32 4 52 Slightly Unstable 1.75 3.27 3 32 2 21 1 80 0.74 0 32 1 61 1.66 2 26 2 72 3.27 4 70 3 27 2.67 4 38 39.95 Neutral 1 06 0 92 1 71 1.47 0 97 0 88 1.06 1 20 3 04 3.41 4 75 2 90 3.73 2.26 2 44 1 61 33 41 Slightly Stable 0.00 0 14 0 00 0.14 0 37 0 55 0.28 0 09 0 37 0.88 1.15 1.89 1.61 0 83 0 46 0.41 9.17 Moderately Stable 0 00 0.00 0 00 0 32 0 41 0.28 0 05 0.09 0.05 0.00 0 23 0 28 0 46 0.32 0.18 0 09 2.76 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNWTOTAL -WIND SPEED CLASSES-0.00 0 00 0.00 0.00 0 00 0.00 0 00 0.00 0 00 0.00 0.00 0 00 0 00 0.00 0 00 0 00 0.00 CA L M 0 51 0 69 0 97 1 98 1.52 1 15 0 51 0 18 0.23 0 09 0 37 0.74 1.89 1.80 1 75 0.97 15 35 < 3.5 mph 1 80 2 86 3.23 2.81 2.12 1 01 0.97 1 15 1.94 1.34 2 21 4.98 5 02 3 09 3 78 4.19 42.49 3 6- 7.5 mph 101 1.11 1.06 0.09 0.46 0 65 0 46 1 71 2.35 3.55 6 22 2 95 3.18 2.40 1 94 2 44 31.57 7.6 - 12.5 mph 0 18 0 05 0 00 0 00 0 00 0 00 0.09 0.41 0 83 2.86 1 57 0.97 1.71 0 37 0 37 0 41 9 82 12 6 - 18.5 mph 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 09 0 14 0 18 0 14 0.00 0 18 0 00 0.00 0 00 0 74 18 6 - 24 5 mph 0 00 0 00 0 00 0.00 0 00 0.00 0.00 0.00 0.05 0.00 0.00 0 00 0.00 0.00 0 00 0.00 0.05 > 24.5 mph Murray & Trettel, Inc.

• 414 West Frontage Road

• Northfield, Illinois

• 60093 r (847) 446-7800

TABLE 11 Braidwood Nuclear Station January-December, 2002 34 ft. Wind Speed and Direction 203Ft-34Ft Oelta-T (F)

Number of Observations - 8552 Values are Percent Occurrence SPEED ---------------------------------- WIND DIRECTION CLASSES ----------------------------------

---

STABILITY CLASSES ----------

CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL EU MU SU N SS MS ES TOTAL EU 0 04 1 0 00 0.0 0 00 0 0.00 O 0 0 000 0 00 00 0O 0.0 D0 0 00 00 '0 0 00 0 00 00 0 0.00P 000 0 00 MU 0.0(1 0 00 0 i1 0.0 0 0 00 0 0 G0 00 0 0 00 00 0 0 00 0.0 00 00 0.0 0 00 0 0 00 0 00 0 00 C SU 0 o0 0.00 0 0O0 00 0 0 00 0 01 0 0.00 0.00 00 0 00 0 0.00 00 0 0 00 O 00 0.00 0.00 0 00 0 00 A N O.O0O 0 00 0 0O O0 0] 0 0 00 0 010 0.0 0 0.00 00 0 00 0 0 00 00 0 00 0 0D000 0 0.00 000 0 00 L SS O OC 3 0 00 O04O0.0(0 0 00 O 04 0 00 0 0 00 0 0D000 0 0 00 0.0 0 0.00 0.04 0 00 0 0 00 0 00 0 00 MMS O OC 0 0.00 OOC 001 0.00 0 0O 2 000 0.00 0 0i 0 0 00 0 00 0.00 0 04 0 0.00 2 0 01 0 00 0 00 ES 0 00 0 00 0 OC 0O042 0 00 0 O0 )0 01 0 0 00 0.0( 2 0.0 0 0 00 00 0 0 00 0 04 2 0.0' a0 00 0.00 O 00 0 00 0 00 EU 0 0CI0 01 0.04 0 011 0 01 0.00 0 01 0.O14 2 0.00 0 0O40 01 0 0E 50.0:1 0 01 0 0; 0 25 0 25 MU 0 0cI0.00 0 0110 D0 O 0 04 0 01 0 O; 20.01 0.01I 0.042 0 01 O 0)20.04 0 04I 0 044 0 01 0 26 0 26 1SU 0 01 0.00 0 01I0 111 0.01 0.0220.0O S0.02 0.012 0 070 0.00 10 01 0 0:4 0 011 0.022 0 02 0.32 0 32

- N 0.09 0 25 0 30I0.55 0 27 0 15 0.111 0.08 0 04I 4 0.04 0 02 0.013 0 15 0 199 0.144 0.15 2 62 2 62 3 SS 0.21 0.23 0.67 0 977 0 61 0.47 0 199 0 13 0.ME 0.0)~20 11 0 1E 50 48 0 6220 6220 22 5 75 5 75 MS 0 16 0.15 0 13 023 0.62 0.55 0.1)33 0 08 0.09 I 0 08 0.211 0 76 0.36 0 3440.20 4 23 4.23

`ES 0 07 0 01 0 06 0 15i 0.42 0 42 0 DO 0 05 0.02 0 0? 0 11 0 O0 0.30 0.36 0.2220 08 2.43 2.43 15.86 E' 14 0 11 0.55 067 0 27 0 29 0.30 0 61 0 37 0 39 0 36 0.60 0.63 0 67 0 37 0.23 6 56 6.56 A 05 0 06 0 13 0 19 0.16 D 08 0 18 0 15 0.09 0 14 0.19 0 04 0 21 0.13 0.15 0 19 2 13 2.13 4SU 0 11 0.07 0 13 0 22 0 06 0 09 0 09 0.13 0.06 0 08 0 06 0 12 0 16 0 09 0 13 0.08 1.68 1 68

- N 0 62 1.27 1.59 1.61 0 92 0.27 0 37 0 46 0 41 0.29 0 51 0 82 0 89 0 77 0 88 1 12 12.82 12 82 7 SS 0.49 0.56 0 80 0 61 O 36 0 50 0.84 1 19 1 81 0 43 1.19 1.64 1 49 0.83 0 65 0 70 14 10 14.10 MS 0.02 0 05 0.01 0 02 0 04 0 22 0 22 0.11 0 14 0.18 0 19 0 96 064 0.22 001 0 05 3 08 3 08 ES 0.00 0 00 0.00 0 00 0 01 O 04 0 02 0 01 0.00 0 01 0 01 0 16 0 16 0 00 0 00 0 00 0 43 0 43 40 80 EU 0 11 0 16 0 34 0 08 0.05 0 01 0 07 0.33 I 0 30 0 51 0 55 0 50 0 62 10.70 0 46 0.32 5.11 5 11 MU 0.05 0 07 0 09 0 04 0 01 (0 04 0 04 0 09 I 0.11 0.08 0 18 0 25 021 40 20 0 11 0 13 1.67 1 67 8 SU 0.09 0 06 0 19 0.00 0 02 0.00 0 04 0.09 I0 08 0 18 0 18 0.21 0.14 C0.25 0 09 0.13 1 74 1 74

- N 0.62 0.78 1.19 0 23 0 19 10 25 0.22 0 92 1 09 0 82 1 96 1 18 091 11.13 0.80 1.27 13.58 13 58 1 SS 0.12 0.05 0 06 0.04 0 04 (0 09 0.27 0.96 L 50 1.02 2.91 t2.82 047 0 29 0 14 0 27 9.03 9.03 2MS 0 00 0 00 0.00 0.00 0 00 0 00 0.01 0.00 0 00 0.09 0 28 2 02 0 00 o400 0 00 0 00 0 41 0 41 ES 0 00 0 00 0 00 0 00 0 00 0.00 0.00 000 0 0.00 0 00 0.01 3 00 000 o0.00 0 00 0 00 0 01 0 01 31 55 EU 0 00 0 00 0.01 0 00 0.00 000 0 02 0.04 C1.27 0.53 025 04.14 027 04.19 0.05 0.05 1.80 1 80 1 MU 0 01 0.02 I 0 01 0 00 0 00 00.00 0 00 0 02 C4.05 0.22 0 22 C4.05 0 08 0.07 0 04 0 01 081 0 81 3 SU 0.00 0.00 0.02 0 00 0.00 CI00 0.00 0 02 C4.09 0.21 0 16 C1.05 0 07 0.09 0 05 0.01 0 78 0 78

- N 0.19 0.06 I0.33 0 00 0.00 00.00 0.05 0.20 00.60 0 88 070 00 22 0.72 0 .51 0 14 0.26 4 85 4 85 1 SS 0 00 O 00 42 01 0 00 0.00 0 00 0 01 0 14 0 50 1.11 0.54 0 01 0.01 0.02 0 01 0 00 2 37 2 37 8Ms 0.00 0 00 C0.00 0.00 0.00 0 .00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 0 00 ES 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 000 0 00 10 62 Murray & Trettel, Inc.

• 414 West Frontage Road

• Northfield, Illinois e 60093 (847)

( 446-7800

TABLE 11 continued Braidwood Nuclear Station January-December, 2002 34 ft Wind Speed and Direction 203Ft-34Ft Oelta-T (F)

---

WIND DIRECTION CLASSES ----------------------------------

---

STABILITY CLASSES ----------

N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL EU MU SU N SS MS ES TOTAL EU 0.00 0 00 0 00 0.00 0.00 0 00 0.00 0 01 0 01 0 08 0 00 0 00 0 06 0 01 0.00 0.01 0.19 0.19 1 MU 0 00 0.00 0 00 0 00 0 00 0.00 0.00 0 00 0.01 0 01 0.00 0.00 0 00 0 00 0 00 0.00 0 02 0.02 9 SU 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0.00 0 01 0.04 0 00 0.00 0 00 0 00 0 00 0 01 0 06 0 06

- N 0.00 0.00 0.00 0 00 0.00 0 00 0 00 0 02 0 08 0 20 0 09 0.01 0 16 0.05 0.00 0 04 0.65 0.65 2 SS 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0.04 0 07 0.00 0 00 0.00 0.00 0 00 0.00 0 11 0.11 4MS 0 00 0 00 0.00 0.00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 ES 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 a 00 1.03 EU 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0.00 0 00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 G MU 0 00 0.00 0.00 0 00 0 00 0 00 0 00 0 00 0.00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0.00 0 00 T SU 0 00 0.00 0 00 0 00 0.00 0 00 0.00 0 00 0.01 0 00 0 00 0 00 0 01 0 00 0 00 0 00 0.02 0.02 N 0.00 0.00 0 00 0.00 0 00 0 00 0 00 0 01 0.00 0.01 0 00 0 00 0 11 0 00 0.00 0 00 0 13 0 13 2 SS 0 00 0 00 0 00 0 00 0.00 0 00 0.00 0.00 0 00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 4MS 0 00 0 00 0.00 0.00 0.00 0 00 0 00 0 00 0.00 0 00 0.00 0.00 0 00 0.00 0 00 0 00 0.00 0.00 ES 0 00 0 00 0.00 0 00 0.00 0 00 0.00 0.00 0 00 0 00 0.00 0.00 0 00 0 00 0 00 0 00 0 00 0 00 0 15 TOT 3 16 3.98 6 68 5 73 4.10 3 51 3.32 5.91 7.86 7 86 10.89 8.34 9 79 7.86 5.46 5 58 100.00 13 90 4 89 4 6134 65 31.36 7.72 2.88 100 00 Wi> rection by Stability N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNWTOTAL -STABILITY CLASSES-0 25 0 28 0 94 0 76 0.33 0 30 0 42 0.99 0.96 1.53 1.16 1.27 1 59 1.61 0 69 0.62 13 90 Extremely Unstable 0 11 .0 15 0.25 0 22 0 21 0 13 0 23 0 28 0 27 0 46 0 60 0.35 0.54 0.43 0 33 0 34 4 89 Moderately Unstable 0 21 0.13 0.35 0 33 0 09 0.12 0 18 0.27 0 26 0 50 0.40 0 39 0 40 0.44 0 29 0 26 4.61 Slightly Unstable 1.52 2.36 3 41 2 40 1 38 0 67 0.75 1.70 2.21 2.23 3 31 2.32 2.95 2 65 1 95 2 84 34.65 Neutral 0 82 0.84 1 53 1 61 1.01 1 06 1 31 2 42 3 91 2 65 4.75 2 62 2 44 1 77 1 43 1 19 31.36 Slightly Stable 0 19 0 20 0.14 0 26 0 65 0 77 0.36 0.19 0 23 0 40 0.55 1 19 1 40 0.58 O 35 0.25 7 72 Moderately Stable 0.07 0.01 0 06 0.15 0 43 0.46 0 07 0 06 0 02 0 08 0 13 0 20 0.47 0 36 0 22 0 08 2.86 Extremely Stable Wind Direction by Wind Speed N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNWTOTAL -WIND SPEED CLASSES-0 00 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0 00 0.00 0 00 0 00 0.00 0.00 0.00 0.00 0.00 CA LM 0 55 0 65 1.22 2.02 1.98 1.63 0.56 0.39 0 22 0.28 0.34 0 55 1.75 1 63 1.39 0 70 15 86 < 3 5 mph 1.43 2.12 3 20 3 32 1.82 1 50 2.03 2 65 2.89 1.52 2.51 4.33 4.19 2.71 2 20 2 37 40 80 3 6 - 7.5 mph 0 98 1 12 1 87 0 39 0 30 0 39 0 64 2 40 3.08 2.70 6.07 2.98 2.35 2 57 1 59 2 12 31 55 7 6 - 12 5 mph 0 20 0.08 0.39 0 00 0 00 0.00 0 08 0.42 1.51 2.95 1.87 0.47 1.16 0.89 0.28 0.33 10 62 12 6 - 18 5 mph 0 00 0 00 0 00 0 00 0 00 0 00 0 00 0 04 0 15 0.40 0.09 0 01 0.22 0 06 0 00 0.06 1.03 18 6 - 24.5 mph 0.00 0 00 0 00 0.00 0 00 0 00 0 00 0 01 0 01 0 01 0.00 0 00 0.12 0 00 0 00 0 00 0 15 > 24.5 mph Murray & Trettel, Inc.

• 414 West Frontage Road

• Northfield, Illinois

• 60093 - (847) 446-7800

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2001 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

APPENDIX C Offsite Dose Calculation Manual p:\depts\zd84g\environsgroup\2002eff doc

ftM Nuclear Offsite-Dose Calculation Manual Docket Numbers:

Dresden 50-10, 50-237, 50-249 Quad Cities 50-254, 50-265 Zion 50-295, 50-304 LaSalle 50-373, 50-374 Byron 50-454, 50-455 Braidwood 50-456, 50-457

3 Revision Revision 3 January 2002 OFFSITE DOSE CAL CULA TION MANUAL TABLE OF CONTENTS Part 1: GENERIC SECTIONS TABLE OF CONTENTS PAGE Chapter 1 Introduction 1 Chapter 2 Regulations and Guidelines 2 Chapter 3 Pathways 12 Chapter 4 Introduction to Methodology 15 Chapter 5 Measurement 28 Chapter 6 Implementation of Offsite Dose Assessment Program 30 Chapter 7 References 31 Chapter 8 Intentionally Left Blank Chapter 9 Intentionally Left Blank Appendix A Compliance Methodology A-i Appendix B Models and Parameters for Airborne and Liquid Effluent Calculations B-i Appendix C Generic Data C-i Appendix D Intentionally Left Blank Appendix E Intentionally Left Blank Part2: SITE SPECIFIC SECTIONS Chapter 10 Radiological Effluent Treatment and Monitoring Chapter 11 Radiological Environmental Monitoring Program Chapter 12 Radiological Effluent Technical Standards Appendix F Station Specific Data Note: Previous Chapter 6 was deleted and previous Chapter 8 was renumbered as Chapter 6.

Previous Chapter 7 was deleted and replaced by the references section.

Previous Chapter 9 was deleted.

Previous Appendix B and C have been combined into Appendix B.

Previous Appendix D has been revised into Appendix C.

Previous Appendix E has been deleted and is Reference 101.

Generic Chapters ii 0212210646

3 Revision January 2002 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)

CHAPTER 1 INTRODUCTION PAGE

1.0 INTRODUCTION

1 1.1 STRUCTURE OF THIS MANUAL 1 CHAPTER 2 REGULATIONS AND GUIDELINES 2

2.0 INTRODUCTION

2 2.1 CODE OF FEDERAL REGULATIONS 2

1. 10CFR20, Standards for Protection Against Radiation 2

2. Design Criteria (Appendix A of 10CFR50) 2

3. ALARA Provisions (Appendix I of 10CFR50) 2

4. 40CFR190, Environmental Radiation Protection Standards for Nuclear Power Operations 3

5. 40CFR141, National Primary Drinking Water Regulations 3 2.2 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS/STANDARDS 3

1. Categories 4 2.3 OFFSITE DOSE CALCULATION MANUAL 4 2.4 OVERLAPPING REQUIREMENTS 5 2.5 DOSE RECEIVER METHODOLOGY 5 CHAPTER 3 EXPOSURE PATHWAYS 12

3.0 INTRODUCTION

12 3.1 AIRBORNE RELEASES 12 3.2 LIQUID RELEASES . 12 3.3 RADIATION FROM CONTAINED SOURCES 13 Generic Chapters iii 02122106-46

Revision 3 January 2002 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)

PAGE CHAPTER 4 METHODOLOGY 15

4.0 INTRODUCTION

15 4.1 IMPORTANT CONCEPTS AND PARAMETERS 15

1. Dose 15

2. Exposure Pathways 15

3. Categories of Radioactivity 16

4. Atmospheric Release Point Classifications 16

5. Historical Average Atmospheric Conditions 17

6. Relative Concentration Factor xIQand Gamma-X/Q 18

7. Relative Deposition Factor D/Q 18

8. Dose Factors 19 4.2 AIRBORNE RELEASES 19

1. Gamma Air Dose 19 X7 Finite Cloud Gamma Air Dose Factor 19

2. Semi-Infinite Cloud Gamma Air Dose Factor 20

2. Beta Air Dose 20

3. Total Body Dose and Dose Rate 20

4. Skin Dose and Dose Rate7 21

5. Ground Radiation 21

6. Inhalation 22

7. Ingestion 22 4.3 LIQUID RELEASES 23 4.4 CONTAINED SOURCES OF RADIOACTIVITY 23

1. BWR Skyshine 23

2. Onsite Radwaste Storage Facilities 24 4.5 TOTAL DOSE REQUIREMENTS 24

1. Total Effective Dose Equivalent Limits of 10CFR20 24

2. Total Dose for Uranium Fuel Cycle 24 CHAPTER 5 MEASUREMENT 28

5.0 INTRODUCTION

28 5.1 EFFLUENT AND PROCESS MONITORING 28 5.2 METEOROLOGICAL MONITORING 28 5.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 28

1. Interlaboratory Comparison Program 28 Genenc Chapters iv 0212210646

Revision 3 January 2002 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)

PAGE CHAPTER 6 IMPLEMENTATION OF OFFSITE DOSE ASSESSMENT 30 6.1 NUCLEAR POWER STATION 30 6.2 METEOROLOGICAL CONTRACTOR 30 6.3 REMP CONTRACTOR 30 CHAPTER 7 REFERENCES 31 Generic Chapters V 0212210646

Revision 3 January 2002 OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES FOR THE ODCM GENERIC SECTIONS SECTION TABLE NUMBER TITLE Chapter 2 2-1 Regulatory Dose Limit Matrix 2-2 Dose Assessment Receivers 2-3 Dose Component/Regulation Matrix Chapter 4 4-1 Radionuclide Types Considered For Airborne Effluent Exposure Pathways 4-2 Radiation Dose Factors Appendix A A-0 Average Annual Concentrations Assumed to Produce a Total Body or Organ Dose of 4 mrem/yr A-1 Compliance Matrix A-2 Release Point Classifications A-3 Nearest Downstream Community Water Systems A-4 40CFR1 90 Compliance Appendix B B-0 Noble Gas Nuclide Fraction B-1 Portion of an Example Joint Frequency Distribution Appendix C C-1 Miscellaneous Dose Assessment Factors Environmental Parameters C-2 Miscellaneous Dose Assessment Factors -

Consumption Rate Parameters C-3 Stable Element Transfer Data C-4 Atmospheric Stability Classes C-5 Vertical Dispersion Parameters C-6 Allowable Concentrations of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste C-7 Radiological Decay Constants (,) in hr' C-8 Bio-accumulation Factors B, to be Used in the Absence of Site-Specific Data C-9 Dose Factors for Noble Gases C-10 External Dose Factors for Standing on Contaminated Ground C-i 1 Sector Code Definitions Generic Chapters vi 021221 0646

Revision 3 January 2002 OFFSITE DOSE CALCULATION MANUAL LIST OF FIGURES FOR THE ODCM GENERIC SECTIONS SECTION FIGURE NUMBER TITLE Chapter 2 2-1 Simplified Flow Chart of Offsite Dose Calculations Chapter 3 3-1 Radiation Exposure Pathways to Humans Appendix B B-1 Instantaneous View of a Plume B-2 A Gaussian Curve B-3 Effect of Observation Period on Plume Shape B-4 A Gaussian Plume CHAPTER 1 INTRODUCTION

1.0 INTRODUCTION

The Offsite Dose Calculation Manual (ODCM) presents a discussion of the following:

• The basic concepts applied in calculating offsite doses from nuclear plant effluents.

• The regulations and requirements for the ODCM and related programs.

• The methodology and parameters for the offsite dose calculations used by the nuclear power stations to assess impact on the environment and compliance with regulations.

The methodology detailed in this manual is intended for the calculation of radiation doses during routine (i.e., non-accident) conditions. The calculations are normally performed using a computer program.

Manual calculations may be performed in lieu of the computer program.

The dose effects of airborne radioactivity releases predominately depend on meteorological conditions (wind speed, wind direction, and atmospheric stability). For airborne effluents, the dose calculations prescribed in this manual are based on historical average atmospheric conditions. This methodology is appropriate for estimating annual average dose effects and is stipulated in the Bases Section of the Radiological Effluent Technical Standards (RETS) of all Exelon Nuclear nuclear power stations.

1.1 STRUCTURE OF THIS MANUAL This manual is the ODCM for the following Exelon Nuclear power stations: Braidwood, Byron, Dresden, LaSalle, Quad Cities and Zion. It is divided into two parts. The material in the first part is generic (applicable to more than one station) and consists of Chapters 1 through 7 and Appendices A through C.

The material in the second part is station (or site) specific. Therefore, there are six separate sets of station-specific sections each containing three chapters (chapters 10, 11, 12) and an appendix (App. F).

The chapters of the generic section provide a brief introduction to and overview of Exelon Nuclear's offsite dose calculation methodology and parameters. Appendices A and B provide detailed information on specific aspects of the methodology. Appendix C contains tables of values of the generic parameters used in offsite dose equations.

Generic Chapters vii 0212210646

Revision 3 January 2002 The station-specific section provides specific requirements for the treatment and monitoring of radioactive effluents, for the contents of the Radiological Environmental Monitoring Program (REMP) and the Radiological Effluent Technical Standards (RETS). These three programs are detailed in ODCM Chapters 10, 11 and 12, respectively. Appendix F contains tables of values for the station-specific parameters used in the offsite dose equations. References are provided as required in each station-specific chapter and appendix.

An ODCM Bases and Reference Document (see Reference 101) provides description of the bases for the methodology and parameters discussed in the generic section of the ODCM. This is a stand-alone document and is not considered to be a part of the ODCM.

Generic Chapters 1 0212210646

Revision 3 January 2002 CHAPTER 2 REGULATIONS AND GUIDELINES

2.0 INTRODUCTION

This chapter of the ODCM serves to illustrate the regulations and requirements that define and are applicable to the ODCM. Any information provided in the ODCM concerning specific regulations are not a substitute for the regulations as found in the Code of Federal Regulations (CFR) or Technical Specifications.

2.1 CODE OF FEDERAL REGULATIONS Various sections of the Code of Federal Regulations (CFR) require nuclear power stations to be designed and operated in a manner that limits the radiation exposure to members of the public. These sections specify limits on offsite radiation doses and on effluent radioactivity concentrations and they also require releases of radioactivity to be nAs Low As Reasonably Achievable". These requirements are contained in 10CFR20, 10CFR50 and 40CFR190. In addition, 40CFR141 imposes limits on the concentration of radioactivity in drinking water provided by the operators of public water systems.

2.1.1 10CFR20, Standards for Protection Against Radiation This revision of the ODCM addresses the requirements of 10CFR20. The 10CFR20 dose limits are summarized in Table 2-1.

2.1.2 Design Criteria (Appendix A of 10CFR50)

Section 50.36 of 10CFR50 requires that an application for an operating license include proposed Technical Specifications. Final Technical Specifications for each station are developed through negotiation between the applicant and the NRC. The Technical Specifications are then issued as a part of the operating license, and the licensee is required to operate the facility in accordance with them.

Section 50.34 of 10CFR50 states that an application for a license must state the principal design criteria of the facility. Minimum requirements are contained in Appendix A of 10CFR50.

2.1.3 ALARA Provisions (Appendix I of 10CFR50)

Sections 50.34a and 50.36a of 10CFR50 require that the nuclear plant design and the station RETS have provisions to keep levels of radioactive materials in effluents to unrestricted areas 'As Low As Reasonably Achievable" (ALARA). Although 10CFR50 does not impose specific limits on releases, Appendix I of 10CFR50 does provide numerical design objectives and suggested limiting conditions for operation.

According to Section I of Appendix I of 10CFR50, design objectives and limiting conditions for operation, conforming to the guidelines of Appendix I 'shall be deemed a conclusive showing of compliance with the "As Low As Reasonably Achievable" requirements of 10CFR50.34a and 50.36a."

An applicant must use calculations to demonstrate conformance with the design objective dose limits of Appendix I. The calculations are to be based on models and data such that the actual radiation exposure of an individual is "unlikely to be substantially underestimated" (see 10CFR50 Appendix I, Section III.A.1).

The guidelines in Appendix I call for an investigation, corrective action and a report to the NRC whenever the calculated dose due to the radioactivity released in a calendar quarter exceeds one-half of an annual design objective. The guidelines also require a surveillance program to monitor releases, monitor the environment and identify changes in land use.

2.1.4 40CFR190, Environmental Radiation Protection Standards for Nuclear Power Operations Generic Chapters 2 0212210646

Revision 3 January 2002 Under an agreement between the NRC and the EPA, the NRC stipulated to its licensees in Generic Letter 79-041 that Compliance with Radiological Effluent Technical Specifications (RETS), NUREG-0472 (Rev.2) for PWR's or NUREG-0473 (Rev.2) for BWR's, implements the LWR provisions to meet 40CFR190". (See Reference 103 and 49.)

The regulations of 40CFR1 90 limit radiation doses received by members of the public as a result of operations that are part of the uranium fuel cycle. Operations must be conducted in such a manner as to provide reasonable assurance that the annual dose equivalent to any member of the public due to radiation and to planned discharges of radioactive materials does not exceed the following limits:

• 25 mrem to the total body

• 75 mrem to the thyroid

• 25 mrem to any other organ An important difference between the design objectives of 10CFR50 and the limits of 40CFR1 90 is that 10CFR50 addresses only doses due to radioactive effluents. 40CFR190 limits doses due to effluents and also to radiation sources maintained on site. See Section 2.4 for further discussion of the differences between the requirements of 10CFR50 Appendix I and 40CFR190.

2.1.5 40CFR141, National Primary Drinking Water Regulations The following radioactivity limits for community water systems were established in the July, 1976 Edition of 40CFR141:

• Combined Ra-226 and Ra-228: < 5 pCi/L.

• Gross alpha (particle activity including Ra-226 but excluding radon and uranium): < 15 pCVL.

• The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 mrem/yr.

The regulations specify procedures for determining the values of annual average radionuclide concentration which produce an annual dose equivalent of 4 mrem. Radiochemical analysis methods are also specified.

The responsibility for monitoring radioactivity in a community water system falls on the supplier of the water.

However, some of the Exelon Nuclear stations have requirements related to 40CFR141 in their specific RETS. For calculation methodology, see Section A.6 of Appendix A.

2.2 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS The Radiological Effluent Technical Standards (RETS) were formerly a subset of the Technical Specifications. They implement provisions of the Code of Federal Regulations aimed at limiting offsite radiation dose. The NRC published Standard Radiological Effluent Technical Specifications for PWRs (Reference 2) and for BWRs (Reference 3) as guidance to assist in the development of technical specifications. These documents have undergone frequent minor revisions to reflect changes in plant design and evolving regulatory concerns. The Radiological Effluent Technical Specifications have been removed from the Technical Specifications and placed in the ODCM as the Radiological Effluent Technical Standards (RETS) (see Reference 90). The RETS of each station are similar but not identical to the guidance of the Standard Radiological Effluent Technical Specifications.

2.2.1 Categories Generic Chapters 3 021 221 0646

Revision 3 January 2002 The major categories found in the RETS are the following:

• Definitions A glossary of terms (not limited to the ODCM).

• Instrumentation This section states the Operability Requirements (OR) for instrumentation performance as well as the associated Surveillance Requirements. The conservative alarm/trip setpoints ensure regulatory compliance for both liquid and gaseous effluents. Surveillance requirements are listed to ensure ORs are met through testing, calibration, inspection and calculation. Also included are the bases for interpreting the requirements. The Operability Requirement (OR) is the ODCM equivalent of a Limiting Condition for Operation (LCO) as defined in both the NRC published Standard Radiological Effluent Technical Specifications and the stations' Technical Specifications.

• Liquid Effluents This section addresses the limits, special reports and liquid waste treatment systems required to substantiate the dose due to liquid radioactivity concentrations to unrestricted areas.

Surveillance Requirements and Bases are included for liquid effluents.

• Gaseous Effluents This section addresses the limits, special reports and gaseous radwaste and ventilation exhaust treatment systems necessary for adequate documentation of the instantaneous offsite radiation Slse rates and doses to a member of the public. Surveillance Requirements and Bases are included for gaseous effluents.

• Radiological Environmental Monitoring Program This section details the Radiological Environmental Monitoring Program (REMP) involving sample collection and measurements to verify that the radiation levels released are minimal.

This section describes the annual land use census and participation in an interlaboratory comparison program. Surveillance Requirements and Bases are included for environmental monitoring.

• Reports and Records This section serves as an administrative guide to maintain an appropriate record tracking system.

The management of procedures, record retention, review/audit and reporting are discussed.

2.3 OFFSITE DOSE CALCULATION MANUAL The NRC in Generic Letter 89-01 defines the ODCM as follows (not verbatim) (see Reference 90):

The Offsite Dose Calculation Manual (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 AlarmTrrip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs and (2) descriptions of the Information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

Additional requirements for the content of the ODCM are contained throughout the text of the RETS.

2.4 OVERLAPPING REQUIREMENTS Generic Chapters 4 0212210646

Revision 3 January 2002 In 10CFR20, 10CFR50 and 40CFR1 90, there are overlapping requirements regarding offsite radiation dose and dose commitment to the total body. In 10CFR20.1301 the total effective dose equivalent (or TEDE) to a member of the public is limited to 100 mrem per calendar year. In addition, Appendix I to 10CFR50 establishes design objectives on annual total body dose or dose commitment of 3 mrem per reactor for liquid effluents and 5 mrem per reactor for gaseous effluents (see 10CFR50 Appendix I, Sections il.A and ll.B.2(a)). Finally, 40CFR1901imits annual total body dose or dose commitment to a member of the public to 25 mrem due to all uranium fuel cycle operations.

While these dose limits/design objectives appear to overlap, they are different and each is addressed separately by the RETS. Calculations are made and-reports are generated to demonstrate compliance to all regulations. Refer to Tables 2-1, 2-2 and 2-3 for additional information regarding instantaneous effluent limits, design objectives and regulatory compliance.

2.5 DOSE RECEIVER METHODOLOGY Table 2-2 lists the location of the dose recipient and occupancy factors, if applicable. Dose is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. The dose calculation methodology is consistent with the methodology of Regulatory Guide 1.109 (Reference 6) and NUREG 0133 (Reference 14). Dose is therefore calculated to a maximum individual. The maximum individual is characterized as maximum' with regard to food consumption, occupancy and other usage of the area in the vicinity of the plant site.

Such a maximum individual" represents reasonable deviation from the average for the population in general. In all physiological and metabolic respects the maximum individual is assumed to have those characteristics that represent averages for their corresponding age group. Thus, the dose calculated is very conservative compared to the average" (or typical) dose recipient who does not go out of the way to maximize radioactivity uptakes and exposure.

Finally Table 2-3 relates the dose component (or pathway) to specific ODCM equations and the appropriate regulation.

Generic Chapters 5 0212210646

Revision 3 January 2002 Table 2-1 Regulatory Dose Limit Matrix REGULATION DOSE TYPE DOSE LIMIT(s) ODCM EQUATION Airborne Releases: (quarterly) (annual) 10CFR50 App. 13 Gamma Dose to Air due to Noble Gas 5 mrad 10 mrad A-1 Radionuclides (per reactor unit)

Beta Dose to Air Due to Noble Gas 10 mrad 20 mrad A-2 Radionuclides (per reactor unit) l Organ Dose Due to Specified Non-Noble 7.5 mrem 15 mrem A-7 Gas Radionuclides (per reactor unit)

Total Body and Skin Total Body 2.5 mrem 5 mrem A-3 Dose (if air dose is exceeded)

Skin 7.5 mrem 15 mrem A-4 Technical Specifications Total Body Dose Rate Due to Noble Gas 500 mrem/yr A-5 Radionuclides (instantaneous limit, per site)

Skin Dose Rate Due to Noble Gas 3,000 mremfyr A-6 Radionuclides (instantaneous limit, per site)

Organ Dose Rate Due to Specified Non- 1,500 mremlyr A-1 6 Noble Gas Radionuclides (instantaneous limit, per site) I Liquid Releases: (quarterly) (annual) 10CFR50 App. 13 Whole (Total) Body Dose 1.5 mrem 3 mrem A-17 (per reactor unit) I Organ Dose (per reactor unit) 5 mrem 10 mrem A-i7 Technical Specifications The concentration of radioactivity in liquid Ten (10) times the effluents released to unrestricted areas concentration values A-21 listed in 10CFR20 Appendix B; Table 2, Column 2,Table C-6 of ODCM Appendix Cfor Noble Gases Total Doses :

10 CFR 20.1301 (a)(1) Total Effective Dose Equivalent 4 100 mrem/yr A-25 10CFR20.1301 (d) Total Body Dose 25 mremfyr A-25 and 40CFR190 Thyroid Dose 75 mrem/yr A-25 Other Organ Dose 25 mrem/yr A-25 Other Limits :

40CFR141 Total Body Dose Due to Drinking Water 4 mrem/yr A-17 From Public Water Systems I Organ Dose Due to Dnnking Water From 4 mremtyr A-17 Public Water Systems _

1 These doses are calculated considering all sources of radiation and radioactivity in effluents.

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Revision 3 -

January 2002 2 These limits are not directly applicable to nuclear power stations. They are applicable to the owners or operators of public water systems. However, the RETS of some of the Exelon Nuclear nuclear power stations require assessment of compliance with these limits. For additional information, see Section A.6 of Appendix A.

3 Note that 10CFR50 provides design objectives not limits.

4 Compliance with 10CFR20.1301 (a)(1) is demonstrated by compliance with 40CFR190. Note that it may be necessary to address dose from on-site activity by members of the public as well.

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Revision 3 January 2002 TABLE 2-2 DOSE ASSESSMENT RECEIVERS Location; Occupancy if Dose Component or Pathway Different than 100%

"Instantaneous' dose rates from airborne Unrestricted area boundary location that results in radioactivity the maximum dose rate lnstantaneous concentration limits in liquid Point where liquid effluents enter the unrestricted effluents area Annual average concentration limits for liquid Point where liquid effluents enter the unrestricted effluents area Direct dose from contained sources Receiver spends part of this time in the controlled area and the remainder at his residence or fishing nearby; occupancy factor is considered and is site-specific. See Appendix F. Table F-8 for occupancy factors for N-16 skyshine.

Direct dose from airborne plume Receiver is at the unrestricted area boundary location that results in the maximum dose.

Dose due to radioiodines, tritium and Receiver is at the location in the unrestricted area particulates with half-lives greater than 8 days where the combination of existing pathways and for inhalation, ingestion of vegetation, milk and receptor age groups indicates the highest potential meat, and ground plane exposure pathways. exposures.

Ingestion dose from drinking water The drinking water pathway is considered as an additive dose component in this assessment only if the public water supply serves the community immediately adjacent to the plant.

Ingestion dose from eating fish The receiver eats fish from the receiving body of water (lake or river)

Total Organ Doses Summation of ingestion/inhalation doses Total Dose Summation of above data (Note it may also be necessary to address dose from on-site activity by members of the public.)

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Revision 3 January 2002 TABLE 2-3 DOSE COMPONENT/REGULATION MATRIX Regulation in which dose component is utilized Dose Component or Reference equation; 10CFR50 Pathway Comments IOCFR20 40CFR190 App. I

'Instantaneous" dose rates from airborne A-5: Total Body radioactivity (RETS requirement only) A-6: Skin A-16: Organ

'Instantaneousm concentration limits in liquid A-21:

effluents Ten times the limits of Table 2, Col. 2,10CFR20, Appendix B to

§§20.1001 - 20.2402, Table C-6 of Appendix C for Noble Gases Annual average concentration limits for liquid 10CFR20, Appendix B to effluents §§20.1001 - 20.2402(2)

Direct dose from contained sources A-23 and Section A.3.2 X X Direct dose from airborne plume A-1: Gamma air dose X A-2: Beta air dose X A-3: Total body dose X X X A-4: Skin dose X Direct dose from radioactivity deposited on 4

he ground A-7 and A-8 X X X

.nhalation dose from airborne effluents A-7 and A-9 1 ) X X X Ingestion dose from vegetables A-7, Al0 and A-11 1)X X X Ingestion dose from milk A-7, A-12 and A-13 X X X Ingestion dose from meat A-7, A-14 and A-13 (1) X X X Ingestion dose from drinking water A-17, A-18 and A-19 1) x x X Ingestion dose from eating fish

__ __ _ __ _ _ _ _ _ _ _ _ _ A-17, A-18 and A-20 (') X X X Total Organ Doses A-25 X X Total Effective Dose Equivalent A-25X I Ingestion/inhalation dose assessment is evaluated for adult/teen/child and infant for 10CFR50 Appendix I compliance and for 10CFR20/40CFR1 90 compliance. Ingestion/inhalation dose factors are taken from Reg. Guide 1.109 (Reference 6).

2 Technical Specifications for most stations have been revised to allow 10 times the 10CFR20 value or specifically states the maximum instantaneous dose rate limit.

3 Optional for 10CFR20 compliance.

4 Compliance with the Total Effective Dose Equivalent limits of 10CFR20 is demonstrated by compliance with 40CFR190. It may also be necessary to address dose from on-site activity by members of the public.

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Revision 3 January 2002 Figure 2-1 Simplified Chart of Offsite Dose Calculations2 Cateaory Radionuclides Pathway Text Receptor Code and Limits Frequency of Section Calculation' Airborne Releases:

Noble Gases: Plume ,? A.1.3.1 Total Body RETS: As Required by 500 mrem4yr Instantaneous Noble Gases: Plume e and pb 1 A-1.3.2 Skin RETS: Station 3000 mremnyr Procedure Instantaneous Noble Gases: Plume - A.1.2.1 Air 10CFR50O 5 mrad/qtr, t0 mrad/yr Noble Gases: Plume pb A.1.2.2 Air4 10CFR503: Monthly 10 mrad/qtr, 20 mrad/yr Non-Noble Inhalatjonb A.1.5 Child RETS: As required by Gases: (Any Organ) t 500 mrem/yr Station i Instantaneous Procedure l Ground A.t.4.1 Total body IDepositione Non-Noble Inhalationc A.1.4.2 l Gases: Vegetationd A.1.4.3.1 Four Age groups t I Monthly and II (All Organs) j Annually l Milkd A .4  ! l 7.5 mrem/qtr, 15 mremlyr j Meat" A.1 A.3.3 Liquid Releases:

All Water A.2.2 RETS, 10 times 10CFR20 As Required by

, I Appendix B; Table 2; Col. 2, Station Table 0-6 of Appendix C for I Procedure Noble Gases Non-Noble Watero and j A.2.1 Total Body 300FR50:

Gases Fish' 1.5 mrem/qtr 3 mrem/yr Non-Noble Water' and A.2.1 4 Age Groups 10CFR503! Monthly Gases Fisht (All Organs) 5 mrem/qtr 10mrem/yr Non-Noble Watere A.6 Adul(Total 40CFR141: j When Required Gases Body and all 4 mrem/yr by RETS i l  ! Organs). I Total Body 40CFR190:

Uranium 25mrem/yr Fuel All All releases plus i A.4.2 Thyroid (Adult) 40CFR190: Annually direct radiation 75 mrem/yr Cycle: I from contained sources (

All Other Organs 40CFR1 90.

- (AduH) 25 mrem/yr _

TEDE: All Extemal + Intemal A.5 Total Body.+ 1 OCFR20: Annually

_ _ organs (Adult) 100 mremlyr  !

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Revision 3 January 2002 Figure 2-1 (Cont'd)

Notes for Figure 2-1:

1. Definition: Monthly means at least once per 31 days or once per month. See station RETS for exact requirements.

2. Additional Calculations: In addition to the calculations shown inthis figure, monthly projections of doses due to radioactive materials are required for gaseous and liquid effluents from Exelon Nuclear nuclear power stations. See Sections A.1.6 and A.2.5 of Appendix A.

Also, projections of drinking water doses are required at least once per 92 days for Dresden and Quad Cities. See Section A.7 of Appendix A.

3. 10 CFR 50 prescribes design objectives not limits.

4. If the air dose is exceeded, doses to the total body and skin are calculated. Total body objectives are 2.5 mrernqtr and 5.0 mrem/year, the skin dose objectives are 7.5 mremfqtr and 15 mrem/year.

a Evaluated at the unrestricted area boundary.

b Evaluated at the location of maximum offsite X'Q.

c Ground plane and inhalation pathways are considered to be present at all offsite locations.

d Evaluated at the location in the unrestricted area where the combination of existing pathways and receptor age groups Indicates the maximum potential exposures. If no real pathway exists then a hypothetical cow-milk producer is evaluated at 5 miles In the highest D/Q sector.

e Evaluated for the nearest downstream community water supply as specified inTable A-3 of Appendix A. The flow and dilution factors specified inTable F-i of Appendix F are used.

f Evaluated for fish caught inthe near-field region downstream of plant using the flow and dilution factors specified inTable F-1 of Appendix F.

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Revision 3 January 2002 CHAPTER 3 EXPOSURE PATHWAYS

3.0 INTRODUCTION

Figure 3-1 illustrates some of the potential radiation exposure pathways to humans due to routine operation of a nuclear power station. These exposure pathways may be grouped into three categories:

• Airborne Releases Exposures resulting from radioactive materials released with gaseous effluents to the atmosphere.

• Liquid Releases Exposures resulting from radioactive materials released with liquid discharges to bodies of water.

• Radiation from Contained Sources Exposures to radiation from contained radioactive sources.

When performing radiation dose calculations, only exposure pathways that significantly contribute (2 10%)

to the total dose of interest need to be evaluated. The radiation dose from air and water exposure pathways are routinely evaluated. (see Regulatory Guide 1.109, Reference 6.)

3.1 AIRBORNE RELEASES For airborne releases of radioactivity, the NRC considers the following pathways of radiation exposure of persons:

• External radiation from radioactivity airborne in the effluent plume.

• External radiation from radioactivity deposited by the plume on the ground.

• Ingestion of radioactivity on, or in, edible vegetation (from direct plume deposition).

• Ingestion of radioactivity that entered an animal food product (milk or meat) because the animal ingested contaminated feed, with the contamination due to direct deposition on foliage.

• Inhalation of radioactivity in the plume.

Dose for airborne releases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures.

3.2 LIQUID RELEASES For liquid releases of radioactivity (Figure 3-1), the NRC considers the following pathways of radiation exposure of persons:

• Ingestion of aquatic food (e.g., fish or inverterbrate) obtained from the body of water to which radioactive station effluents are discharged.

• Ingestion (drinking) of potable water contaminated by radioactive liquid effluents discharged from the station.

For the aquatic food pathway, only fish is considered since it is the only significant locally produced aquatic food consumed by humans.

The stations omit the pathways involving irrigation and animal consumption of contaminated water because these pathways were determined to be insignificant. The stations also omit the pathway of Generic Chapters 12 0212210646

Revision 3 January 2002 radiation exposure from shoreline sediment because this pathway was also found to be insignificant (see ODCM Bases and Reference Document, Section 0.3.2).

The stations have also verified that the dose contribution to people participating in water recreational activities (swimming and boating) is negligible. (See ODCM Bases and Reference Document, Reference 101, Tables 0-3 and 0-4) This pathway was not addressed explicitly in Regulatory Guide 1.109. Thus, the stations also omit dose assessments for the water recreational activities pathway.

Periodically the Illinois Army Corps of Engineers dredges silt and debris from the river beds near Exelon Nuclear nuclear stations. As a part of the land use census, Exelon Nuclear will determine if the Corps performed dredging within one mile of the discharge point. If so, Exelon Nuclear will obtain spoils samples, through it's REMP vendor, for analysis. The impact to the offsite dose will be evaluated on a case by case basis and added to the station annex of the ODCM when applicable.

In addition, to assure that doses due to radioactivity in liquid effluents will be ALARA, concentrations will be limited to ten times (1Ox) the values given in 10CFR20 Appendix B, Table 2; Column 2. Specific limitations for concentrations of entrained noble gases are contained in the stations' Radiological Effluent Technical Standards (RETS).

3.3 RADIATION FROM CONTAINED SOURCES Radioactivity contained within tanks, pipes or other systems and contained radioactive material or waste stored on site can produce radiation at offsite locations. Annual offsite radiation doses near the stations due to such sources were judged to be negligible in comparison with applicable limits except for doses due to BWR turbine skyshine and potential doses due to radioactive waste storage facilities (excludes radioactive material storage). See ODCM Bases and Reference Document, Reference 101. Changes or modifications to the power station that may impact the offsite dose through increases to the direct radiation levels need to be evaluated on a case by case basis and added to Chapter 12 of the station annex to the ODCM when applicable (e.g.; the Old Steam Generator Storage Facilities).

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Revision 3 January 2002 Figure 3-1 Radiation Exposure Pathways to Humans Generic Chapters 14 021Z210646

Revision 3 January 2002 CHAPTER 4 METHODOLOGY

4.0 INTRODUCTION

This chapter provides an introduction to the methodology used by Exelon Nuclear to calculate offsite radiation doses resulting from the operation of nuclear power stations. Additional explanation and details of the methodology are provided in Appendices A and B. Appendix A discusses each dose limit in the RETS and provides the associated assessment equations. Appendix B describes methods used to determine values of parameters included in the equations.

4.1 IMPORTANT CONCEPTS AND PARAMETERS 4.1.1 Dose The dose calculation equations contained in the ODCM are based on two types of exposure to radiation; external and internal exposure. The first type of exposure is that resulting from radioactive sources external to the body (including radiation emanating from an effluent plume, radiation emanating from radioactivity deposited on the ground and radiation emanating from contained sources (also referred to as direct radiation)). Exposure to radiation external to the body only occurs while the source of the radioactivity is present.

Internal exposure occurs when the source of radioactivity is inside the body. Radiation can enter the body by breathing air containing the radioactivity, or by consumption of food or drinking water containing radioactivity. Once radioactivity enters the body and becomes internal radiation, a person will continue to receive radiation dose until the radioactivity has decayed or is eliminated by biological processes. The dose from this type of exposure is also termed dose commitment, meaning that the person will continue to receive dose even-though the plume containing the radioactivity has passed by the individual, or even-though the individual is no longer drinking water containing radioactivity.

The regulations addressed by the ODCM may require assessment of either type of exposure to radiation or of both types in summation.

The term dose is used instead of the term dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). When applied to the evaluation of internal deposition of radioactivity, the term "dose," as used in the ODCM, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is evaluated over a period of 50 years.

4.1.2 Exposure Pathways All of the exposure pathways are discussed in Chapter 3. This section presents the exposure pathways addressed by Exelon Nuclear nuclear stations in the ODCM and associated software.

For releases of radioactivity in airborne effluents the primary pathways are the following:

• Direct radiation from an effluent plume.

• Direct radiation from radioactivity deposited on the ground by a plume.

• Inhalation of radioactivity in a plume.

• Ingestion of radioactivity that entered the food chain from a plume that deposited radioactivity on vegetation.

For releases of radioactivity in liquid effluents, the exposure pathways considered are human consumption of water and fish.

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Revision 3 January 2002 When determining total doses, as required by 10CFR20 and 40CFR1 90, the BWR stations also consider direct radiation due to skyshine from nitrogen-1 6 ('6N) in turbines and associated piping. All nuclear power stations will consider exposure to radiation emanating from onsite radwaste storage facilities when they are put into operation.

4.1.3 Categories of Radioactivity Radionuclide content of effluent releases from nuclear power stations can be categorized according to the characteristics of the radionuclides. In evaluating doses associated with a particular pathway, only those categories of radionuclides that significantly contribute to the dose need to be included in the dose calculations (See Section 3.0). The categories of radionuclides considered by the Exelon Nuclear nuclear power stations for each of the airborne pathways are summarized in Table 4-1. Selection of the significant airborne pathways was based on the following:

• The requirements in the RETS (see discussion in Appendix A)

• Applicable regulatory guidance (References 6 and 14), and

• A study of the potential radiological implications of nuclear facilities in the upper Mississippi River basin (Reference 20).

Calculations were used to determine which radionuclides were significant for a particular pathway. For example, in the case of direct radiation from a plume of airborne radioactivity, it was found that radiation from noble gases is significant and radiation from radioactive iodine was not. The dose rate per unit of airborne radioactivity concentration is about the same for noble gases and radioactive iodine since they emit comparable types and energies of radiation. However, the quantity of noble gas radioactivity released in routine nuclear plant operation typically exceeds the quantity of radioactive iodine by a factor of about 10,000.

As another example, consider the inhalation pathway. Here, the calculations showed that the dose commitment due to radioactive iodine was significant but the dose commitment due to radioactive noble gases was not significant and can be excluded from the compliance calculations for the inhalation pathway. This is true despite the fact that a much larger quantity of noble gas radioactivity is released.

The reason for this is that the solubility of noble gas in body tissue is very low, whereas the inhaled radioactive iodine does concentrate in specific body organs such as the thyroid (see the discussion on Pages 228 and 231 to 234 of Reference 38).

4.1.4 Atmospheric Release Point Classifications The dose impact from airborne release of radioactivity is determined by the height of the release of the effluent plume relative to the ground and by the location of the dose recipient.

The height an effluent plume maintains as it travels above the ground is related to the elevation of the release point and to the height of structures immediately adjacent as follows:

• If the elevation of the release point is sufficiently above the height of any adjacent structures, the plume will remain elevated for considerable distances.

• If the elevation of the release point is at or below the heights of adjacent structures, the plume is likely to be caught in the turbulence of the wakes created by wind passing over the buildings. The plume elevation would then drop to ground level.

• If the elevation of the release point is not significantly above the heights of adjacent structures, then the plume may be elevated or at ground level.

For the calculations of this manual, each established release point has been designated as belonging to one of three release point classifications:

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• Stack (or Elevated) Release Points (denoted by the letter S or subscript s)

These are release points approximately twice the height of adjacent solid structures.

Releases are treated as elevated releases unaffected by the presence of the adjacent structures.

• Ground Level Release Points (denoted by the letter G or subscript g)

These are release points at ground level or lower than adjacent solid structures. Releases are considered drawn into the downwind wake of these structures and are treated as ground level releases.

• Vent (or Mixed Mode) Release Points (denoted by the letter V or subscript v)

These are release points as high or higher than adjacent solid structures but lower than twice the structure's heights. These releases are treated as a mixture of elevated and ground level releases. The proportion of the release attributed to either elevated or ground level in a vent release is determined by the ratio of stack exit velocity to the wind speed (see Section B.1.2.4 of Appendix B).

The definitions of these classifications are based on Regulatory Guide 1.111 (Reference 7). A list of the classifications of specific airborne release points for each of the Exelon Nuclear nuclear power stations is contained in Table A-2 in Appendix A.

4.1.5 Historical Average Atmospheric Conditions The dispersion characteristics of airborne effluents from a nuclear power station are dependent on weather conditions. Meteorological factors that directly affect the concentration of airborne radioactivity in a plume include the following:

• Wind Direction The concentration of radioactivity is highest in the direction toward which the wind is blowing.

• Wind Speed Greater wind speeds produce more dispersion and consequently lower concentrations of radioactivity.

• Atmospheric Turbulence The greater the atmospheric turbulence, the more a plume spreads both vertically and horizontally. For calculations in this manual, the degree of turbulence is classified by use of seven atmospheric stability classes, designated A (extremely unstable) through G (extremely stable). The seven classes and some of their characteristics are listed in Table C-4 of Appendix C.

Meteorological conditions strongly impact the values of various parameters applied in the dose calculations of this manual. These include:

• The Relative Concentration Factors X/O and gamma-x/Q (Section 4.1.6)

• The Relative Deposition Factor D/Q (Section 4.1.7)

The bases sections of the Standard Radiological Effluent Technical Specifications (guidance documents NUREGs 0472, 0473, 1301 and 1302) and the RETS specify that dose calculations be based on "historical average atmospheric conditions'. Therefore, this manual provides values for the above Generic Chapters 17 0212210646

Revision 3 January 2002 parameters that are based on station-specific historical average meteorological conditions. These values were obtained by averaging hourly values of the parameters over a long-term, several-year period of record. The averaging period was based on calendar years in order to avoid any bias from weather conditions associated with any one season. The period of record is identified in each of the tables providing the values (see Appendix F).

4.1.6 Relative Concentration Factors X/O and Gamma- IQ A person immersed in a plume of airborne radioactivity is exposed to radiation from the plume and may also inhale some of the radioactivity from the plume. The concentration of radioactivity in air near the exposed person must be calculated to adequately evaluate doses resulting from any inhalation. The relative concentration factor X/Q (referred to as chi over Qu) is used to simplify these calculations. X/Q is the concentration of radioactivity in air, at a specified location, divided by the radioactivity release rate.

X/Q has the following units:

Units of XIQ = (gLCi/m 3) / (ptCsec) = sec/m 3 Station-specific values of X/Q are provided for each nuclear power station in Table F-5 of Appendix F.

These values are based on historical average atmospheric conditions (see Section 4.1.5).

For each of the release point classifications (eg. stack, vent and ground level) and for the 16 compass-direction sectors (N, NNE, etc.), Table F-5 provides the maximum value of X/Q for locations at or beyond the unrestricted area boundary.

The value of XLO for each sector reflects the fraction of time that the wind blew into that sector and the distribution of wind speeds and atmospheric stability classes during that time. Note that the value would be zero if the wind never blew into the sector.

The gamma-X/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. It is used in place of the semi-infinite plume model that tends to underestimate gamma air dose for elevated plumes. Use of the gamma-X/Q also corrects for the tendency of the semi-infinite plume model to overestimate gamma air dose for mixed mode and ground level releases.

The methodologies for determining X/Q and gamma-X/Q are discussed in detail in Section B.3 of Appendix B.

4.1.7 Relative Deposition Factor D/Q As a plume travels away from its release point, portions of the plume may touch the ground and deposit radioactivity on the ground and/or on vegetation. Occurrences of such deposition are important to model since any radioactivity deposited on the ground or on vegetation may directly expose people and/or may be absorbed into food products which can ultimately be ingested by people. The relative deposition factor is used to simplify the dose calculations for these pathways.

The relative deposition factor D/Q is the rate of deposition of radioactivity on the ground divided by the radioactivity release rate. Its value was determined for specific conditions. In this manual it has the following units:

Units of DIQ = [(pCi/sec)/m 2 ] / (pCilsec) = 1uM2 The values of D/Q are affected by the same parameters that affect the values of X/Q: release characteristics, meteorological conditions and location (see Section 4.1.6). Station-specific values of D/Q are provided for each Exelon Nuclear nuclear power station in Appendix F Tables F-5 and F-6. These values are based on historical average atmospheric conditions (see Section 4.1.5).

For each release point classification and for each of the 16 compass-direction sectors (N, NNE, etc.),

Table F-5 provides the maximum value of D/Q for locations at or beyond the unrestricted area boundary.

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Revision 3 January 2002 In Table F-6, values of D/Q are given for the locations of the nearest milk and meat producers within 5 miles of the nuclear power station. The methodology for determining DIQ is discussed in Section B.4 of Appendix B.

4.1.8 Dose Factors Various dose factors are used in this manual to simplify the calculation of radiation doses. These factors are listed in Table 4-2. Definitions of these factors are given in the remainder of this chapter. Methods of determining their values are addressed in Appendix B.

4.2 AIRBORNE RELEASES 4.2.1 Gamma Air Dose The term 'gamma air dose' refers to the component of dose absorbed by air resulting from the absorption of energy from photons emitted during nuclear and atomic transformations, including gamma rays, x-rays, annihilation radiation, and Bremsstrahlung radiation (see footnote on page 1.109-19 of Regulatory Guide 1.109).

The noble gas dose factors of Reg. Guide 1.109, Table B-1 are based upon assumption of immersion in a semi-infinite cloud. For ground level and mixed mode releases this tends to over estimate the gamma air dose arising from a plume that is actually finite in nature.

For elevated releases, the Reg. Guide 1.109 noble gas dose factors will underestimate exposure as they consider only immersion and not that portion of exposure arising from sky shine. At distances close in to -

the point of elevated release, the ground level concentration as predicted by X/Q will be essentially zero. In such a case, the sky shine component of the exposure becomes significant and must be considered.

The gamma-X/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. The methodology of Reg. Guide 1.109, Section C.2 and Appendix B provide the methodology for calculating finite cloud gamma air dose factors from which the gamma-X/Q values can be derived. Section B.5 addresses the calculation of these dose factors.

Three gamma-X/Q values are defined: (X/Q)5 7, (XIQ)V,, and (Q/Q)97 for stack, vent and ground level releases, respectively. Section B.3.5 addresses the calculation of the gamma-X/Q values.

4.2.1.1 Finite Cloud Gamma Air Dose Factor The finite cloud gamma air dose factor is determined by calculating the gamma dose rate to air (at a specific location and corresponding to a given release rate) and dividing that dose rate by the corresponding release rate:

Finite Cloud Gamma Air Dose Factor = [(mradlyr)I(gCilsec)]

The methodology for this calculation is discussed in Section B.5 of Appendix B. The calculation is complex because the dose rate at any given point is affected by the radioactivity concentration and distance. Calculation of the finite cloud gamma air dose factor takes into consideration release characteristics, meteorological conditions and location (see Section 4.1.6). Additionally, the value is affected by radiological parameters: the distribution of energies and intensities for gamma emissions from each specific radionuclide and the photon attenuation characteristics of air.

In the ODCM, station-specific values of gamma dose factors are provided for each station in Appendix F, Table F-7. These values are based on historical average atmospheric conditions (see Section 4.1.5). For the release point classification and for each of the 16 compass-direction sectors, Table F-7 provides the maximum value of the gamma air dose factor for noble gas radionuclides at the unrestricted area Generic Chapters 19 0212210646

Revision 3 January 2002 boundary. The value includes a correction for radioactive decay during transport of the radionuclide from the release point to the dose calculation location.

4.2.1.2 Semi-infinite Cloud Gamma Air Dose Factor The semi-infinite cloud gamma dose factor is the gamma air dose rate divided by the concentration of radioactivity in air at the dose calculation location. Values of these gamma dose factors are radionuclide specific and are provided in Appendix C, Table C-9.

The semi-infinite cloud gamma dose factor is used in conjunction with gamma-X/Q to calculate noble gas gamma air dose and dose rate for elevated and finite noble gas plumes. The gamma-X/Q is defined such that for a given finite cloud the semi-infinite cloud methodology will yield the same gamma air dose as the finite cloud methodology.

4.2.2 Beta Air Dose The term 'beta air dose' refers to the component of dose absorbed by air resulting from the absorption of energy from emissions of beta particles, mono-energetic electrons and positrons during nuclear and atomic transformations (see the footnote on Page 1.109-20 of Regulatory Guide 1.109).

The Beta Air Dose Factor The beta air dose factor is the beta air dose rate divided by the concentration of radioactivity in air at the dose calculation location. Values of the beta air dose factor are radionuclide specific and are provided in Appendix C Table C-9.

4.2.3 Total Body Dose and Dose Rate Total Body Dose Equation A-3 of Appendix A is used to calculate dose to the total body from noble gas radionuclides released in gaseous effluents. The total body dose equation is similar to that used to calculate gamma air dose (Equation A-1 of Appendix A).

Total Body Dose Rate Equation A-5 of Appendix A is used to calculate dose rate to the total body. The assumptions used for this equation are the same as those used in the calculation of total body dose (Equation A-3 of Appendix A) except that any shielding benefit (dose attenuation) provided by residential structures is not applied.

Since the calculation is for the maximum instantaneous dose rate, the dose recipient may be out of doors when exposed and would not be shielded from the exposure by any structural material.

The Total Body Dose Factor The total body dose factor is the total body dose rate divided by the radioactive release rate. Values for the total body dose factor are site specific and are provided in Table C-9 of Appendix C.

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Revision 3 January 2002 4.2.4 Skin Dose and Dose Rate Skin Dose Equation A-4 of Appendix A is used to calculate dose to skin from noble gas radionuclides released in gaseous effluents. The skin dose is the summation of dose to the skin from beta and gamma radiation.

The equation for beta dose to skin is similar to that used to calculate beta dose to air (Equation A-2 of Appendix A) except that beta skin dose factors are used instead of beta air dose factors. The beta skin dose factor differs from the beta air dose factor by accounting for the attenuation of beta radiation by the dead layer of skin. The dead layer of skin is not susceptible to radiation damage and therefore is not of concern. The beta dose to the skin from non-noble gases is insignificant and is not calculated for the reason described in Section 4.1.3. When calculating the beta contribution to skin dose, no reduction is included in the calculations due to shielding provided by occupancy of residential structures.

The equation for gamma dose to skin is similar to that used to calculate gamma dose to air except for the following:

• Equation A-4 of Appendix A includes a units conversion factor 1.11 rem/rad to convert from units of gamma air dose (rad) to units of tissue dose equivalent (rem).

• Equation A-4 of Appendix A includes a dimensionless factor of 0.7 to account for the shielding due to occupancy of residential structures.

Equation A-4 of Appendix A uses gamma air dose factors not gamma total body dose factors. When calculating gamma dose to skin, no reduction is applied for the attenuation of radiation due to passage through body tissue (dead layer of skin).

Skin Dose Rate Equation A-6 of Appendix A is used to calculate dose rate to skin. The assumptions are the same as those used in the calculation of skin dose (Equation A-4 of Appendix A) except that no credit is taken for shielding of gamma radiation by residential structures. The dose recipient may be outdoors when exposed and the maximum instantaneous dose rate is of concern.

The Skin Dose Factor Values of the beta air dose factors and skin dose factors are nuclide specific and are provided in Table C-9 of Appendix C for 15 noble gas radionuclides.

4.2.5 Ground Radiation Equations A-7 and A-8 of Appendix A are used to calculate the total body dose due to non-noble gas radionuclides released in gaseous effluents and deposited on the ground.

Comment Note that if there is no release of radionuclide i during a given time period, then the deposition rate is zero, the ground plane concentration is zero and the resulting dose due to ground deposition is zero. If there is a release of radionuclide i, the ground concentration is computed as if that release had been occurring at a constant rate for the ground deposition time period.

The Ground Plane Dose Conversion Factor The ground plane dose conversion factor is the dose rate to the total body per unit of radioactivity concentration on the ground. Values of the ground plane dose conversion factor that are calculated by Genenc Chapters 21 0212210646

Revision 3 January 2002 assuming constant concentration over an infinite plane are provided for various radionuclides in Table C-10 of Appendix C.

4.2.6 Inhalation Dose Radioactivity from airborne releases of radioactive iodine, particulate and tritium can enter the body through inhalation. Equations A-7 and A-9 of Appendix A are used to calculate dose commitment to the total body or organs due to inhalation of non-noble gas radionuclides released in gaseous effluents.

The Inhalation Dose Factor Values for the inhalation dose commitment factor are nuclide specific and are taken from Reg. Guide 1.109 (Reference 6) Tables E-7, 8, 9 and 10. These tables include data for four age groups (adult, teenager, child and infant) and seven body organs.

Dose Rate The inhalation dose rate is the rate at which dose is accrued by an individual breathing contaminated air.

Equation A-16 of Appendix A is used to calculate dose commitment rate to an organ due to inhalation of non-noble gas radionuclides. The assumptions are the same as used in the calculation of inhalation dose.

The dose rate is determined for the child age group in accordance with the guidance found in NUREGs 0472, 0473,1301 and 1302 (References 2, 3, 105 and 106).

4.2.7 Ingestion Airborne releases of radioactive iodine, particulate and tritium can enter the food chain through deposition on vegetation. The radioactivity can be Ingested by humans who consume the vegetation or who consume products (e.g., milk or meat) of animals who have fed on the contaminated vegetation. Each Exelon Nuclear nuclear power station considers the following ingestion pathways:

• Vegetables

• Milk

• Meat.

Equations A-7 and A-1 0 through A-1 5 of Appendix A are used to calculate the dose due to ingestion of food containing non-noble gas radionuclides released in gaseous effluents. Dose is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures.

Values of the ingestion dose commitment factor are the same for each Exelon Nuclear nuclear power station. The components of this factor are not impacted by station-specific parameters. The station-specific aspects of the calculation of ingestion dose only concern the quantity of radioactivity ingested. Values of the ingestion dose commitment factors are taken from Reg. Guide 1.109 Tables E-1 1, 12, 13 and 14. These tables include data for four age groups and seven organs.

The equations used for radioactivity concentration on vegetation and in milk, and meat are discussed in Appendix A.

Generic Chapters 22 0212210646

Revision 3 January 2002 4.3 LIQUID RELEASES The evaluation of dose due to releases of radioactivity in liquid effluents is required to confirm compliance with the provisions of RETS related to 10CFR50 Appendix I. ODCM Section 3.2 and Figure 3-1 list some of the pathways by which radioactivity in liquid effluents can impact man. The pathways used by Exelon Nuclear to calculate dose from liquid effluents are ingestion by drinking water and by eating fish from the body of water receiving station liquid discharges. The nuclear power stations obtain the dose commitment due to radioactivity in liquid effluent releases by summing the dose commitments from the drinking water and fish pathways depending upon their presence. -

Equations A-17 through A-20 of Appendix A are used to calculate dose for the member of the public due to consumption of drinking water and fish.

The radioactivity concentration in water is obtained by dividing the quantity of radioactivity released by the volume of water in which the release is diluted. The result can be modified by a factor to represent any additional dilution that might occur.

The radioactivity concentration in fish is the product of the radioactivity concentration in water and a bioaccumulation factor. The dilution factors for fish may be different from those for water. (The fish may be caught at a location different from where drinking water is drawn.)

The bioaccumulation factor accounts for the fact that the quantity of radioactivity in fish can build up with time to a higher value relative to the concentration of the radioactivity in the water they consume. The bioaccumulation factor is the equilibrium ratio of the concentration of radionuclide i in fish to its concentration in water. The same values are used for the bioaccumulation factor at each station. These values are provided in Appendix C, Table C-8.

4.4 CONTAINED SOURCES OF RADIOACTIVITY In addition to the total body, skin and single organ dose assessments previously described, an additional assessment is required. The additional assessment addresses radiation dose due to radioactivity contained within the nuclear power station and its structures.

There are presently two types of contained sources of radioactivity which are of concern in offsite radiological dose assessments. The first is that due to gamma rays resulting from nitrogen-16 carry- over to the turbine in BWR steam (skyshine). The second is that due to gamma rays associated with radioactive material contained in onsite radwaste and radioactive material storage facilities.

4.4.1 BWR Skyshine The most significant dose component to members of the public produced by "contained sources is nitrogen-1 6 ("6N) within the turbine building of BWRs. Although primary side shielding is around the turbine and its piping, 16N gamma rays scattered by air molecules in the overhead air space above the turbine and piping cause a measurable 'skyshine radiation dose in the local power plant environs.

Equation A-23 of Appendix A is used to evaluate skyshine dose. A complicating factor in the calculation is the practice at some stations of adding hydrogen to reactor coolant to improve coolant chemistry. The addition of hydrogen can increase the dose rate due to skyshine up to a factor of 10 times expected levels depending on injection rates and power levels (Reference 39). Increasing the hydrogen injection rate will increase the dose rates even further. (See Reference 102) The skyshine dose determined by Equation A-23 of Appendix A depends on the following factors:

• The distance of the dose recipient location from the turbine.

• The number of hours per year that the location is occupied by a dose recipient.

• The total energy [MWe-hr] generated by the nuclear power station with hydrogen addition.

• The total energy [MWe-hr] generated by the nuclear power station without hydrogen addition.

Generic Chapters 23 02122510646

Revision 3 January 2002 4.4.2 Onsite Radwaste and Rad Material Storage Facilities Low-level radioactive waste may be stored at any Exelon Nuclear nuclear power station in the following

-types of storage facilities:

• Process Waste Storage Facilities

• Interim Radwaste Storage Facility (IRSF) structure

• Concrete vaults containing 48 radwaste liners (Also referred to as "48-pack";)

• DAW Storage Facilities

• Dry Active Waste (DAW) facilities (may include Butler buildings/warehouses)

• Replaced Steam Generator Storage Facilities Rad Material may be stored in facilities on site

• Rad Material Storage Facilities

• Contaminated tools and equipment in seavans and/or warehouses Spent Fuel may be stored in facilities on site:

• ISFSI Facilities

• Independent spent fuel storage installation facilities Administrative controls are implemented by each station to ensure compliance to applicable regulations.

The impact to the offsite dose will be evaluated on a case by case basis and added to the station annex of the ODCM when applicable. In addition, a 10CFR50.59 analysis may be required for radwaste storage facilities.

4.5 TOTAL DOSE REQUIREMENTS 4.5.1 Total Effective Dose Equivalent Limits; 10CFR20 and 40CFR190 10CFR20 requires compliance to dose limits expressed as "Total Effective Dose Equivalent" (TEDE).

Although annual dose limits in 10CFR20 are now expressed in terms of TEDEs, 40CFR190 limits remain stated as organ dose. The NRC continues to require 10CFR50 Appendix I and 40CFR1 90 doses to be reported in terms of organ dose and not TEDE. Due to the fact that organ dose limits set forth in 40CFR1 90 are substantially lower than those of 10CFR20 (25 mrem/yrvs 100 mrem/yr), the NRC has stated that demonstration of compliance with the dose limits in 40CFR190 will be deemed as demonstration of compliance with the dose limits of 10CFR20 for most facilities (Reference 104). In addition to compliance with 40CFR1 90, it may be necessary for a nuclear power plant to address dose from on-site activity by members of the public.

4.5.2 Total Dose For Uranium Fuel Cycle The nuclear power stations are required to determine the total dose to a member of the public due to all uranium fuel cycle sources in order to assess compliance with 40CFR1 90 as part of demonstrating compliance with 10CFR20.

The total dose for the uranium fuel cycle is the sum of doses due to radioactivity in airborne and liquid effluents and the doses due to direct radiation from contained sources at the nuclear power station. When evaluation of total dose is required for a station, the following contributions are summed:

. Doses due to airborne and liquid effluents from the station.

Genenc Chapters 24 0212210646

Revision 3 -

January 2002

• Doses due to liquid effluents from nuclear power stations upstream.

• Doses due to nitrogen-16 (16 N) skyshine, if the station is a boiling water reactor.

• Doses due to any onsite radioactive waste storage facilities; if applicable.

Section A.5.2 of Appendix A discusses the details of evaluations.

GIeneric Chapters 25 0212210646

Revision 3 January 2002 Table 4-1 Radionuclide TVpes Considered For Airborne Effluent Exposure Pathways External Radiation Internal Radiation Category Plume Ground Inhalation Ingestion Noble Gases x Tritium (H-3) x x Iodine' x x x Particulate' x x x a The nuclear power stations are not required to consider all iodine radionuclides. Only particulates with half-life greater than 8 days need be considered. For details, see Generic Letter 89-01 and the RETS.

Genenc Chapters 26 0212210646

Revision 3 January 2002 Table 4-2 Radiation Dose Factors Name and Symbol Units Definition Table Gamma Air Dose mrad/yr Gamma air dose rate per RG 1.109 Factor per unit of radioactivity Table B-1, Ml gCVm 3 concentration for Column 4 radionuclide i.

Total Body Dose mrem/yr Total body dose rate per Factor RG 1.109 per unit of radioactivity Table B-1, K1 piCVm3 concentration for Column 5 radionuclide i.

Beta Air Dose mrad/yr Beta air dose rate per RG 1.109 Factor N. per unit of radioactivity Table B-1,

,rCVm 3 concentration for Column 2 radionuclide i.

Beta Skin Dose mrem/yr Beta skin dose rate per RG 1.109 Factor L4 per unit of radioactivity Table B-1, ziCVm3 concentration for Column 3 radionuclide i.

Ground Plane Dose mremfhr Dose rate per unit Conversion Factor RG 1.109 per 2 of ground radioactivity Table E-6, DFG, pCVm concentration for Column 2 radionuclide i.

Inhalation Dose mrem Dose to organ j of age RG 1.109 Commitment Factor per group a per unit of Tables; DFAja pCi radioactivity inhaled E-7, E-8, for radionuclide i. E-9, E-1 0 (see Note 1)

Ingestion Dose mrem Dose to organ j of age RG 1.109 Commitment Factor per group a per unit of Tables; DFIja pCi radioactivity ingested E-11, E-12, for radionuclide i. E-13, E-14 (see Note 1)

Note 1: Dose assessments for 10CFR20 and 40CFR 190 compliance are made for an adult only.

Dose assessments for 10CFR50 Appendix I are made using dose factors of Regulatory Guide 1.109 (Reference age groups. 6) for all Generic Chapters 27 0212210646

Revision 3 January 2002 CHAPTER 5 MEASUREMENT

5.0 INTRODUCTION

Each nuclear station has three measurement programs associated with offsite dose assessment:

• Measurement of releases of radioactivity from the station.

• Measurement of meteorology at the station site.

• Measurement of levels of radiation and radioactivity in the environs surrounding the station.

5.1 EFFLUENT AND PROCESS MONITORING Radioactivity in liquid and gaseous effluents is measured in order to provide data for calculating radiation doses and radioactivity concentrations in the environment of each nuclear power effluent radioactivity is required by 10CFR20.1302 and 10CFR50. The RETS of station. Measurement of each nuclear power station provide detailed requirements for instrumentation, sampling and analysis.

Guides are 1.21 (Reference 4) and 4.15 (Reference 13). Chapter 10 of the ODCMRelevant Regulatory descriptions of effluent monitoring instruments at each nuclear power station. The includes brief RETS of each nuclear power station require submission to the NRC of reports of effluent radioactivity releases environmental measurements. and 5.2 METEOROLOGICAL MONITORING Meteorological parameters are measured in the vicinity of each nuclear power data for calculating radiation doses due to airborne effluent radioactivity. Somestation in order to provide nuclear Technical Specifications state applicable requirements (typically under the subheading, power stations' Instrumentation," in the instrumentation section). Regulatory guidance is given in 'Meteorological Regulatory Guide 1.23 (Reference 5). Wind speed, wind direction and the temperature gradient are measured at two or more elevations on a meteorological tower at each Exelon Nuclear station. using instruments chosen to provide meteorological data representative of the elevations of the airborne The elevations are station. The Annual Radiological Environmental Operating Report includes a summary releases from the data collected over the reporting year. These data are used to calculate optional of meteorological dose and radioactivity concentration. isopleths of radiation 5.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

Each nuclear power station has a REMP that provides representative measurements radioactive material in the environment. The program provides verification that of radiation and measurable radiological impacts from the power station on the environment are within expectations derived from effluent measurements and calculations. The REMP is required by 10CFR50 (see Appendix and IV.B.3). General requirements of the program are prescribed in each station's I, Sections IV.B.2 precise details (such as specific monitoring locations) are specified in ODCM Chapter RETS and more 11.

5.3.1 Interlaboratory Comparison Program The laboratory which performs the REMP analyses is required by the RETS to participate in an interlaboratory comparison program. The purpose is to provide an independent check on the laboratorys analytical procedures and to alert it to potential problems (e.g. accuracy). In order measurements of radioactivity in environmental media, an independent agency to assess the laboratories with samples of environmental media containing unspecified amounts supplies participating of radioactivity. The Genenc Chapters 28 0212210646

Revision 3 January 2002 laboratories measure the radioactivity concentrations and report the results to the agency. At a later time, the agency informs the participating laboratories of the actual concentrations and associated uncertainties.

Any significant discrepancies are investigated by the participating laboratories. A similar process is used to assess measurements of environmental radiation by passive thermoluminescent dosimeters.

Generic Chapters 29 0212210646

Revision 3 January 2002 CHAPTER 6 IMPLEMENTATION OF OFFSITE DOSE ASSESSMENT PROGRAM 6.1 NUCLEAR POWER STATION The nuclear power station staff is responsible for effluent monitoring. The staff determines effluent radioactivity concentration and flow rate. These data are used to determine the radioactivity release information required for the Radioactive Effluent Release Report and to perform monthly calculations and projections of offsite radiation dose.

The nuclear power station staff is also responsible for control of effluent radioactivity. Procedures are implemented for determining, calculating and implementing setpoints. Uquid and gaseous radwaste treatment systems and ventilation exhaust treatment systems are utilized when appropriate. The nuclear power station staff implements the Process Control Program (PCP) for solid radwaste and measures tank radioactivity and BWR off-gas radioactivity.

The nuclear power station staff maintains instrumentation associated with these activities and demonstrates operability of the instrumentation in accordance with the surveillance requirements of the RETS. In the event that any RETS requirements are violated, the nuclear power station staff is responsible for taking one of the actions allowed by the RETS and issuing any required reports to the NRC.

The nuclear power station staff assembles and distributes the Radioactive Effluent Release Report.

6.2 METEOROLOGICAL CONTRACTOR The meteorological contractor operates and maintains the meteorological tower instrumentation at each nuclear power station. The contractor collects and analyzes the data and issues periodic reports. The contractor prepares the meteorological data summary required for the Annual Radiological Environmental Operating Report (AREOR) and also computes and plots isopleths included in the AREOR.

6.3 REMP CONTRACTOR The radiological environmental contractor collects environmental samples and performs radiological analyses as specified in the nuclear power station's REMP (see ODCM Chapters 11 and 12). The contractor issues reports of results to appropriate points of contact and each nuclear station. The contractor participates in an interlaboratory comparison program and reports results in the Annual Radiological Environmental Operating Report. The contractor performs the annual land use census and assembles the Annual Radiological Environmental Operating Report.

Generic Chapters 30 0212210646

Revision 3 January 2002 CHAPTER 7 REFERENCES

1. Deleted

2. U.S. Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, NUREG-0472, Rev. 3, Draft, January 1983 (frequently revised).

3. U.S. Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for Boiling Water Reactors, NUREG-0473, Rev. 3, Draft, September 1982 (frequently revised).

4. U.S. Nuclear Regulatory Commission, Measuring. Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Regulatory Guide 1.21. Revision 1, June 1974.

5. U.S. Nuclear Regulatory Commission, Onsite Meteorological Programs, Regulatory Guide 1.23, Safety Guide 23, February 17,1972.

6. U.S. Nuclear Regulatory Commission, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix 1,Regulatory Guide 1.109, Rev. 1, October 1977.

7. U.S. Nuclear Regulatory Commission, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Regulatory Guide 1.111, Rev. 1, July 1977.

8. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors, Regulatory Guide 1.112, Rev. 0-R, April 1976; reissued May 1977.

9. U.S. Nuclear Regulatory Commission, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, Regulatory Guide.

1.113, Rev. 1, April 1977.

10. U.S. Nuclear Regulatory Commission, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants, Regulatory Guide 4.1, Rev. 1, April 1975.

11. U.S. Nuclear Regulatory Commission, Preparation of Environmental Reports for Nuclear Power Stations, Regulatory Guide 4.2, Rev. 2, July 1976.

12. U.S. Nuclear Regulatory Commission, Environmental Technical Specifications for Nuclear Power Plants, Regulatory Guide 4.8, Rev. 1, December 1975. (See also the related Radiological Assessment Branch Technical Position, Rev. 1, November 1979.)

13. U.S. Nuclear Regulatory Commission, Quality Assurance for Radiological Monitorinq Programs (Normal Operations)--Effluent Streams and the Environment, Regulatory Guide 4.15, Rev. 1, February 1979.

14. U.S. Nuclear Regulatory Commission, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, edited by J. S. Boegli et al. NUREG-0133, October 1978.

Generic Chapters 31 021221 0646

Revision 3 January 2002

15. U.S. Nuclear Regulatory Commission, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, J. F. Sagendorf et al.

NUREG/CR-2919, PNL-4380, September 1982.

16. U.S. Nuclear Regulatory Commission, Radiological Assessment, edited by J. E. Till and H. R.

Meyer, NUREG/CR-3332, ORNL-5968, September 1983.

17. U.S. Nuclear Regulatory Commission, Standard Review Plan, NUREG-0800, July 1981.

18. U.S. Atomic Energy Commission, Meteorology and Atomic Energy 1968, edited by D. H. Slade, TID-21940, July 1968.

19. U.S. Atomic Energy Commission, Plume Rise, G. A. Briggs, TID-25075, 1969.

20. U.S. Atomic Energy Commission, The Potential Radiological Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000, WASH 1209, January 1973.

21. U.S. Atomic Energy Commission, HASL Procedures Manual, Health and Safety Laboratory, HASL-300 (revised annually).

22. U.S. Department of Energy, Models and Parameters for Environmental Radiological Assessments, edited by C. W. Miller, DOE/TIC-1 1468,1984.

23. U.S. Department of Energy, Atmospheric Science and Power Production, edited by D. Randerson, DOErMTC-27601,1984.

24. U.S. Environmental Protection Agency, Workbook of Atmospheric Dispersion Estimates, D. B.

Turner, Office of Air Programs Publication No. AP-26, 1970.

25. U.S. Environmental Protection Agency, 40CFR1 90 Environmental Radiation Protection Requirements for Normal Operations of Activities in the Uranium Fuel Cycle, Final Environmental Statement, EPA 520/4-76-016, November 1, 1976.

26. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle, EPA-520/9-73-003-C, November 1973.

27. American Society of Mechanical Engineers, Recommended Guide for the Prediction of the Dispersion of Airborne Effluents, 1973.

28. Eisenbud, M., Environmental Radioactivity, 3rd Edition, (Academic Press, Orlando, FL, 1987).

29. Glasstone, S., and Jordan, W. H., Nuclear Power and Its Environmental Effects (American Nuclear Society, LaGrange Park, IL, 1980).

30. International Atomic Energy Agency, Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine Releases, Safety Series, No. 57, 1982.

31. National Council on Radiation Protection and Measurements, Radiological Assessment:

Predicting the Transport, Bioaccumulation, and Uptake by Man of Radionuclides Released to the Environment, NCRP Report No. 76, March 15,1984.

32. American National Standards Institute, Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities, ANSI N13.1 -1969, February 19, 1969.

Genenc Chapters 32 0212210646

Revision 3 January 2002

33. Institute of Electrical and Electronics Engineers, Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N13.10-1974, September 19, 1974.

34. American National Standards Institute, Testing and Procedural Specifications for Thermoluminescence Dosimetry (Environmental Applications), ANSI N545-1975, August 20, 1975.

35. American Nuclear Insurers, Effluent Monitoring, ANI/MAELU Engineering Inspection Criteria for Nuclear Liability Insurance, Section 5.1, Rev.-2, October 24,1986.

36. American Nuclear Insurers, Environmental Monitoring, ANI/MAELU Engineering Inspection Criteria for Nuclear Liability Insurance, Section 5.2, Rev. 1, March 23, 1987.

37. American Nuclear Insurers, Environmental Monitoring Programs, ANI/MAELU Information Bulletin 86-1, June 9,1986.

38. Cember, H., Introduction to Health Physics, 2nd Edition (Pergamon Press, Elmsford, NY 1983).

39. Electric Power Research Institute, Guidelines for Permanent BWR Hydrogen Water Chemistry Installations-1987 Revision, EPRI NP-5283-SR-A, Special Report, September 1987.

40. Commonwealth Edison Company, Information Relevant to Keeping Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable. LaSalle County Station, Units 1 and 2, June 4, 1976.

41. U.S. Nuclear Regulatory Commission, Branch Technical Position, Radiological Assessment Branch, Revision 1, November 1979. (This is a branch position on Regulatory Guide 4.8.)

42. Deleted

43. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code),

NUREG-0017, April 1976.

44. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWR-GALE Code), NUREG-0016, April 1976.

45. Sargent & Lundy, N-16 SkVshine from BWR Turbine Systems and Piping, NSLD Calculation No.

D2-2-85, Rev. 0, 211/85.

46. Sargent & Lundy Calculation ATD-01 38, Rev. 0, N-16 Skyshine Ground Level Dose from Dresden Turbine Systems and Piping. July 14,1992.

47. Sargent & Lundy Calculation ATD-0139, Rev. 0, N-16 Skyshine Ground Level Dose from LaSalle Turbine Systems and Piping. July 28, 1992.

48. Sargent & Lundy Calculation ATD-0140, Rev. 0, N-16 Skvshine Ground Level Dose from Quad Cities Turbine Systems and Piping. July 28,1992.

49. U.S. Nuclear Regulatory Commission, Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), NUREG-0543, February 1980.

Generic Chapters 33 0212210646

Revision 3 January 2002

50. International Commission on Radiological Protection, Report of Committee Two on Permissible Dose for Internal Radiation, Recommendations of the International Commission on Radiological Protection, ICRP Publication 2, 1959.

51. U.S. Nuclear Regulatory Commission, Ape-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, Battelle Pacific Northwest Laboratories, NUREG-0172,1977.

52. W. C. Ng, Transfer Coefficients for Prediction of the Dose to Man via the Foraue-Cow-Milk Pathway from Radionuclides Released to the Biosphere, UCRL-51939.

53. E. C. Eimutis and M. G. Konicek, Derivations of Continuous Functions for the Lateral and Vertical Atmospheric Dispersion Coefficients, Atmospheric Environment 6, 859 (1972).

54. D. C. Kocher, Editor, Nuclear Decay Data for Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities, ORNUNUREG/TM-1 02, August 1977.

55. R. L. Heath, Gamma-Ray Spectrum Catalog, Aerojet Nuclear Co., ANCR-1000-2, third or subsequent edition.

56. S. E. Thompson, Concentration Factors of Chemical Elements in Edible Aquatic Organisms, UCRL-50564, Rev. 1, 1972.

57. U.S. Nuclear Regulatory Commission, Instruction Concerning Risks from OccuDational Radiation Exposure, Regulatory Guide 8.29, July 1981.

58. Dresden Nuclear Power Station, Radioactive Waste and Environmental Monitoring, Annual Report 1987, March 1988.

59. Reserved reference number

60. Sargent & Lundy Calculation ATD-01 73, Rev. 0, 9/21/92, Annual Dose to Members of the Public Due to the LaSalle IRSF.

61. Sargent & Lundy Calculation ATD-01 74, Rev. 0, 9/21/92, Annual Dose to Members of the Public Due to the Zion IRSF.

62. Sargent & Lundy Calculation ATD-0175, Rev. 0, 9/21/92, Annual Dose to Members of the Public Due to the Quad Cities IRSF.

63. Sargent & Lundy Calculation ATD-01 76, Rev. 0, 9/21/92, Annual Dose to Members of the Public Due to the Dresden IRSF.

64. Reserved reference number

65. Sargent & Lundy Calculation ATD-01 80, Rev. 0, 9/25/92, Dose Information Around Braidwood DAW Sea/Land Van Storage Area.

66. Sargent & Lundy Calculation ATD-0181, Rev. 0, 9/25/92, Dose Information Around Byron DAW Sea/Land Van Storage Area.

67. Sargent & Lundy Calculation ATD-01 82, Rev. 0, 9/25/92, Dose Information Around Dresden DAW Sea/Land Van Storage Area.

68. Sargent & Lundy Calculation ATD-01 83, Rev. 0, 9/25/92, Dose Information Around LaSalle DAW Sea/Land Van Storage Area.

Generic Chapters 34 0212210646

Revision 3 January 2002

69. Catalytic, Inc., Determination of Roof and Wall Shielding for Onsite and Offsite Radiation Protection from Skyshine, Calculation Index Number 70161-19, August 22, 1984 (applies to Dresden).

70. D. C. Kocher, Radioactivity Decay Data Tables, DOE/TIC-1 1026, 1981.

71. J. C. Courtney, A Handbook of Radiation Shielding Data, ANS/SD-76/14, July 1976.

72. Commonwealth Edison Company, Information Relevant to Keeping Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable. Zion Station, Units 1 and 2, June 4,1976.

73. Commonwealth Edison Company, Information Relevant to Keeping Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable, Dresden Station, Units 2 and 3, June 4, 1976.

74. Commonwealth Edison Company, Information Relevant to Keeping Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable, Quad Cities Station, Units 1 and 2, June 4, 1976.

75. Sargent & Lundy, METWRSUM, S&L Program Number 09.5.187-1.0.

76. Sargent & Lundy, Comments on CECo ODCM and List of S&L Calculations, Internal Office Memorandum, P. N. Derezotes to G. R. Davidson, November 23, 1988.

77. Sargent & Lundy, AZAP. A Computer Program to Calculate Annual Average Offsite Doses from Routine Releases of Radionuclides in Gaseous Effluents and Postaccident X/Q Values, S&L Program Number 09.8.054-1.7.

78. National Oceanic and Atmospheric Administration, A Program for Evaluating Atmospheric Dispersion from a Nuclear Power Station, J. F. Sagendorf, NOAA Technical Memorandum ERL ARL-42, Air Resources Laboratory, Idaho Falls, Idaho, May 1974.

79. G. P. Lahti, R. S. Hubner, and J. C. Golden, Assessment of Gamma-Rav ExDosures Due to Finite Plumes, Health Physics 41, 319 (1981).

80. National Council of Radiation Protection and Measurements, Ionizing Radiation Exposure of the Population of the United States. NCRP Report No. 93, September 1, 1987.

81. Reserved reference number

82. W. R. Van Pelt (Environmental Analysts, Inc.), Letter to J. Golden (CornEd) dated January 3, 1972.

83. Electric Power Research Institute, Radiological Effects of Hydrogen Water Chemistry, EPRI NP-4011, May 1985.

84. U.S. Nuclear Regulatory Commission, Draft Generic Environmental Impact Statement on Uranium Milling, NUREG-051 1, April 1979.

85. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cvcle. Part I -

Fuel Supply, EPA-520/9-73-003-B, October 1973.

86. U.S. Nuclear Regulatory Commission, Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors, NUREG-0002, August 1976.

Generic Chapters 35 0212210646

Revision 3 January 2002

87. U.S. Nuclear Regulatory Commission, Demographic Statistics Pertaining to Nuclear Power Reactor Sites, NUREG-0348, Draft, December 1977.

88. Nuclear News 31, Number 10, Page 69 (August 1988).

89. General Electric Company, Irradiated Fuel Storage at Morris Operation, Operating Experience Report, January 1972 through December 1982, K. J. Eger, NEDO-20969B.

90. U.S. Nuclear Regulatory Commission, Generic Letter 89-01, 'Guidance For The Implementation of Programmatic Controls For RETS In The Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program', January 1989.

91. 'Assessment of the Impact of LiWuid Radioactive Effluents from Braidwood Station on Proposed Public Water Intakes at Wilmington, Illinois', J.C. Golden, NSEP, January 1990

92. NRC Safety Evaluation Report (SER)Adaho Notional Engineering Laboratory Technical Evaluation Report (TER) of the Commonwealth Edison Offsite Dose Calculation Manual (ODCM), Revision O.A, December 2,1991.

93. Deleted

94. Deleted.

95. U.S. Nuclear Regulatory Commission, Standards for Protection Against Radiation (10CFR20).

96. U.S. Nuclear Regulatory Commission, Licensing of Production and Utilization Facilities (10CFR50).

97. Federal Register, Vol. 57, No. 169, Monday, August 31, 1992, page 39358.

98. Miller, Charles W., Models and Parameters for Environmental Radiological Assessments, U.S.

Dept. of Energy, DE8102754, 1984, pages 32, 33,48, and 49.

99. Kocher, D. C., 'Dose-Rate Conversion Factors For Extemal Exposure To Photons and Electrons',

Health Physics Vol. 45, No. 3 (September), pp. 665-686,1983.

100. U.S. Department of Health, Education and Welfare Public Health Service, Radiological Health Handbook, January 1970.

101. ODCM Bases and Reference Document, rev.0, November, 1998.

102. G. Moran, D. Goff, Quad Cities Nuclear Power Station: 1993 Hydrogen Water Chemistry Stress Corrosion Monitoring Test - Unit 2, 9/17-23/93.

103. U.S. Nuclear Regulatory Commission, Generic Letter 79-041, September 17,1979.

104. Federal Register, Vol. 56, No. 98, Tuesday, May 21, 1991, page 23374, column 3.

105. U.S. Nuclear Regulatory Commission, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, NUREG-1301, April 1991.

106. U.S. Nuclear Regulatory Commission, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, NUREG-1 302, April 1991.

Genenc Chapters 36 0212210646

Revision 3 January 2002 107. U.S. Nuclear Regulatory Commission, LADTAP II - Technical Reference and Users Guide, NUREG-4013, April 1986.

Generic Chapters 37 0212210646

APPENDIX A Revision 3 January 2002 APPENDIX A COMPLIANCE METHODOLOGY TABLE OF CONTENTS PAGE A.0 INTRODUCTION A-1 A.1 AIRBORNE RELEASES A-1

1. Release Point Classifications A-1

2. Dose Due to Noble Gas Radionuclides A-1

1. Gamma Air Dose A-1

2. Beta Air Dose A-3

3. Total Body Dose A-4

4. Skin Dose .

A-4

3. Dose Rate Due to Noble Gas Radionuclides A-5

1. Total Body Dose Rate A-5

2. Skin Dose Rate A-6

4. Dose Due to Non-Noble Gas Radionuclides A-7

1. Ground Deposition A-8

2. Inhalation A-9

3. Food Ingestion Pathway Dose Factors A-10

1. Vegetation A-10

2. Milk A-12

3. Meat A-13

5. Dose Rate Due to Non-Noble Gas Radionuclides A-14

6. Operability and Use of Gaseous Effluent Treatment Systems A-15 A.2 LIQUID RELEASES A-16

1. Dose A-16 I. Potable Water Pathway A-17

2. Fish Ingestion Pathway A-18

2. Liquid Effluent Concentrations Requirement A-18

3. Tank Discharges A-1 9

4. Tank Overflow A-20

5. Operability and Use of the Liquid Radwaste Treatment System A-20

6. Drinking Water A-20

7. Non-routine Liquid Release Pathways A-21 A.3 DOSE DUE TO CONTAINED SOURCES A-21

1. BWR Skyshine A-21

2. Dose from Onsite Radwaste Storage Facilities A-23 A.4 TOTAL DOSE LIMITS (I OCFR20 and 40CFR1 90) A-23 I. Total External Total Body Dose A-23

2. Total Dose A-24 Appendix A A-i 0212210640

Revision 3 January 2002 APPENDIX A TABLE OF CONTENTS (Cont'd)

PAGE A.5 COMPLIANCE TO TOTAL DOSE LIMITS A-25

1. Total Dose Limit- IOCFR20 Compliance A-25

1. Dose to a Member of the Public in the Unrestriced Area A-25

2. Dose to a Member of the Public in the Restricted Area A-25

2. Total Dose Due to the Uranium Fuel Cycle (40CFRI90) A-25

3. Summary of Compliance Methodology A-26 A.6 DOSE DUE TO DRINKING WATER (40CFRI41) A-26

1. 40CFRI41 Restrictions on Manmade Radionuclides A-26

2. Application A-27 LIST OF TABLES NUMBER TITLE PAGE A-0 Average Annual Concentrations Assumed to Produce A-27 a Total Body or Organ Dose of 4 mrem/yr.

A-1 Compliance Matrix A-28 A-2 Release Point Classifications A-29

- A-3 Nearest Downstream Community Water Systems A-30 A-4 40CFR190 Compliance A-31 Appendix A A-ii 0212210640

Revision 3 January 2002 APPENDIX A COMPLIANCE METHODOLOGY A.0 INTRODUCTION This appendix reviews the offsite radiological limits applicable to the nuclear power stations and presents in detail the equations and procedures used to assess compliance with these limits. An introduction to the calculational approach used here is given in Chapter 4. The approach incorporates simplifications such as the following:

• Use of pre-calculated atmospheric transport parameters based on historical average atmospheric conditions (see Section 4.1.5). These atmospheric dispersion and deposition factors are defined in Chapter 4.

The equations and parameters of this appendix are for use in calculating offsite radiation doses during routine operating conditions. They are not for use in calculating doses due to non-routine releases (e.g.,

accident releases).

This section of the ODCM provides the methodological details for demonstrating compliance with the 10CFR20, 10CFR50 Appendix I and 40CFR1 90 radiological limits for liquid and gaseous effluents.

An overview of the required compliance is given in Tables 2-1, 2-2, and 2-3. In Table 2-1, the dose components are itemized and referenced, and an indication of their regulatory application is noted. A more detailed compliance matrix is given in Table 2-3. Additionally, the locations of dose receivers for each dose component are given in Table 2-2.

The following sections detail the required radiological dose calculations.

A1 AIRBORNE RELEASES A.1.1 Release Point Classifications The pattern of dispersion of airborne releases is dependent on the height of the release point relative to adjacent structures. For the equations of this appendix, each release point is classified as one of the following three height-dependent types, which are defined in Section 4.1.4:

• Stack (or Elevated) Release Point (denoted by the letter S or subscript s)

• Ground Level Release Point (denoted by the letter G or subscript g)

• Vent (or Mixed Mode) Release Point (denoted by the letter V or subscript v)

The release point classifications of routine release points at the nuclear power stations are stated in Table A-2.

A.1.2 Dose Due to Noble Gas Radionuclides A.1.2.1 Gamma Air Dose Requirement RETS limit the gamma air dose due to noble gas effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:

. Less than or equal to 5 mrad per calendar quarter.

Appendix A A-1 0212210640

Revision 3 January 2002

• Less than or equal to 10 mrad per calendar year.

Equation The gamma air dose due to noble gases released in gaseous effluents is calculated by the following expression:

D, = (3.1 7E -8)ZMI (X/Q)-'Al. + (X/Q)v A, + (X/Q)s/Aig (A-1)

The summation is over noble gas radionuclides i.

DY Gamma Air Dose [mradl Dose to air due to gamma radiation from noble gas radionuclides released in gaseous effluents.

3.17E-8 Conversion Constant (seconds to years) [yr/sec]

ml Gamma Air Dose Conversion Factor [(mrad/yr)/(ACilm 3 )]

Gamma air dose rate factor per unit of radioactivity release rate for radionuclide i. From Table B-1 of Reg Guide 1.190.

(X/Q)., (xIQ)%, (x/Q)g Gamma-X/Q Factor [sec/m3 Radioactivity concentration based on finite cloud methodology at a specific location per unit of radioactivity release rate from a stack, vent or ground level release, respectively. See Section B.3.5 and Table F-5b of appendix F.

A., A-,, Agg Cumulative Radionuclide Release [jiCO Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively.

Application RETS require determination of cumulative and projected gamma air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days (see Sections 12.4 of each station's RETS or Technical Specifications).

Gamma air dose is calculated for the sector with the highest offsite (X/Q)Y and is compared with the RETS limits on gamma air dose.

For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10.

A.1.2.2 Beta Air Dose Appendix A A-2 0212210640

Revision 3 January 2002 Requirement RETS limit the beta air dose due to noble gases in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:

• Less than or equal to 10 mrad per calendar quarter.

• Less than or equal to 20 mrad per calendar year.

Equation The beta air dose due to noble gases released in gaseous effluents is calculated by the following expression:

Dp = (3.17E - 8)Z {Ni[(X/Q).A,3 + (X/QIA, + (X/Q)gAigJ J (A-2)

The summation is over noble gas radionuclides i.

Dp Beta Dose [mrad]

Dose to air due to beta radiation from noble gas radionuclides released in gaseous effluents.

3.17E-8 Conversion Constant (seconds to years) [yr/sec]

N, Beta Air Dose Conversion Factor [(mrad/yr)I(;.Cilm 3 )]

Beta air dose rate per unit of radioactivity concentration for radionuclide i. Take from Table C-9 of Appendix C.

(XIQ)S Relative Concentration Factor [sec/rn3 ]

(XIQ)V (XIQ)9 Radioactivity concentration based on semi-infinite cloud methodology at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F.

A, A,,, Ag9 Cumulative Radionuclide Release [y4CI Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively.

Application RETS require determination of cumulative and projected beta air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days (see Section 12.4 of each station's RETS or Technical Specification).

Beta air dose is calculated for the sector with the highest offsite (X/Q) and is compared with the RETS limit on beta air dose.

For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10.

A.1.2.3 Total Body Dose Appendix A A-3 0212210640

Revision 3 January 2002 Requirement The total body dose, to any receiver is due, in part, to gamma radiation emitted from radioactivity airborne effluents. This component is added to others to demonstrate compliance to the requirements in 40CFR190 and IOCFR2O. of Equation The total body dose component due to gamma radiation from noble gases released in gaseous effluents is calculated by the following expression:

DTB =(3.17E-8)YK {(X/Q)' 1 A1. +(X/Q) Ai +(x/Q) Ai (A-3)

The summation is over noble gas radionuclides i.

DTB Total Body Dose [mrem]

Dose to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents.

3.1 7E-8 Conversion Constant (seconds to years) [yr/sec]

K, Gamma Total Body Dose Conversion Factor [(mrem/yr)/(uCim3)]

Gamma total body dose factor due to gamma emissions for noble gas radionuclide i released from a stack, vent or ground level release point, respectively. Taken from Table C-9 of Appendix C.

A,, A,,, A, Cumulative Radionuclide Release [ACE Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively.

Application The total body dose is also calculated for the 40CFRI 90 and 10CFR20 compliance assessments.

some cases, the total body dose may be required in 10CFR5O Appendix I assessments In (See Table 2-1).

A.1.2.4 Skin Dose Requirement There is no regulatory requirement to evaluate skin dose. However, this component is evaluated reference as there is skin dose design objective contained in 10CFR50 Appendix I. Note that for in the unlikely event that if beta air dose guideline is exceeded, then the skin dose will require evaluation.

Equation The part of skin dose due to noble gases released in gaseous effluents is calculated by the following expression:

DSK = (3.17E - 8) E {L, [ (x/Q) Al. + (X/Q),,As + (X/Q) 9 Ag]

+ (1.1 1)MI [ (X/Q)5 Al + (x/Q)" Ah + (X/Q)" A 9 ] (A-4)

Appendix A A-4 0212210640

Revision 3 January 2002 The summation is over noble gas radionuclides i.

DSK Skin Dose [mrem]

Dose to the skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents.

Li Beta Skin Dose Conversion Factor [(mremlyr)/(glCilm 3 )]

Beta skin dose rate per unit of radioactivity concentration for radionuclide i. Taken from Table C-9 of Appendix C.

1.11 Conversion Constant (rads in air to rem in tissue) [mrem/mrad]

All other terms have been previously defined.

Application The skin dose is calculated for reference only.

A.1.3 Dose Rate Due to Noble Gas Radionuclides A.1.3.1 Total Body Dose Rate Requirement RETS limit the total body dose rate due to noble gases in gaseous effluents released from a site at and beyond the site boundary to less than or equal to 500 mrem/yr at all times. (see Section to areas each station's RETS and Technical Specifications) 12.4 of Equation The total body dose rate due to noble gases released in gaseous effluents is calculated by the following expression:

DTB = K 1{C/Q)y Q1 + (X/Q)y Qw + (x/Q)y Q9 } (A-5)

The summation is over noble gas radionuclides i.

1TB Total Body Dose Rate [mrem/yr]

Dose rate to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents.

Q,15Q , Qig Release Rate [piCi/sec]

Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively.

All other terms have been previously defined.

Application Appendix A A-5 0212210640

Revision 3 January 2002 RETS require the dose rate due to noble gases in gaseous effluents be determined limit in accordance with methodology specified in the ODCM (see Section 12.4 of to be within the above each station's RETS and Technical Specifications).

To comply with this specification, each station uses an effluent radiation monitor setpoint an offsite total body dose rate at or below the limit (see Chapter 10). In addition, each corresponding to station assesses compliance by calculating offsite total body dose rate on the basis of periodic samples accordance with station procedures. obtained in A.1.3.2 Skin Dose Rate Requirement RETS limit the skin dose rate due to noble gases in gaseous effluents released from beyond the site boundary to less than or equal to a dose rate of 3000 mrem/yr at all a site to areas at and times. (See Section 12.4 of each station's RETS and/or Technical Specifications)

Equation The skin dose rate due to noble gases released in gaseous effluents is calculated expression:

by the following DSK = { Li [ (X/Q) 5 Q + (X/Q)t Qw + (X/Q)g Qig]

(A-6)

+ .11)Ml [ (X/Q)s Q1s + (c/Q)Q,, Q + (/Q) Q ]}

The summation is over noble gas radionuclides i.

DSK Skin Dose Rate [mrem/yrA Dose rate to skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents.

Qs, Q(vy Qig Release Rate [iCil/sec]

Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively.

All other terms been previously defined.

Application RETS require the dose rate due to noble gases in gaseous effluents to be determined to above limit in accordance with methodology specified in the ODCM. (See Section 12.4 be within the RETS and Technical Specifications.) of each station's To comply with this specification, each station uses an effluent radiation monitor setpoint an offsite skin dose rate at or below the limit (see Chapter 10). In addition, each station corresponding to compliance by calculating offsite skin dose rate on the basis of samples obtained periodicallyassesses accordance with station procedures. in A.1.4 Dose Due to Non-Noble Gas Radionuclides Requirement A0' AppendixA A-6 0212210640

Revision 3 January 2002 RETS provide the following limits, based on 10CFR50 Appendix I, on the dose to a member of the public from specified non-noble gas radionuclides in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary

• Less than or equal to 7.5 mrem to any organ during any calendar quarter.

• Less than or equal to 15 mrem to any organ during any calendar year.

The individual dose components are also required as part of the 40CFRI90 assessments and combined as part of the 10CFR20 assessment (See Section A.4). The dose due to radionuclides deposited on the ground is considered to be a component of the deep dose equivalent for 10CFR20 compliance and an organ (and total body) dose component for I OCFR50 Appendix I and 40CFR190 compliance.

In accordance with the definition of dose in Regulatory Guide 1.109, the term "dose" in this document when applied to individuals, is used instead of the more precise term 'dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). When applied to the evaluation of internal deposition of radioactivity, the term "dose" as used here, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is evaluated over a period of 50 years. Assessments for 10CFR50 Appendix I compliance are made for 4 age groups (adultlteenager/child/infant) using Regulatory Guide 1.109 (Reference 6) dose conversion factors.

Equation The dose is calculated for releases in the time period under consideration.

Specifically, the dose is calculated as follows:

DUNNG = (3.17E - 8)Z Z[W.R,PjAj + W,,RaipjA, + WuR,,PjA,,] (A-7) pi The summation is over pathways p and non-noble gas radionuclides i.

DNNG Dose Due to Non-Noble Gas Radionuclides [mrem]

Dose due to non-noble gases (radioiodines, tritium and particulates) to age group a, and to organ j.

3.17E-8 Conversion Constant (seconds to years) [yr/sec]

WsI Wv, Wg Relative Concentration Factor Radioactive concentration at a specific location per unit of radioactivity release rate or concentration for stack, vent or ground level release, respectively.

W., W,, or W. = (x/Q)s, (XIQ)v or (X/Q)g for immersion, inhalation and all tritium pathways.

W,, W,, or W9 = (D/Q)s, (D/Q), or (D/Q)g for ground plain and all ingestion pathways.

(x/Q)5 , (xIQ)v, (X/Q)g Relative Concentration Factor [sec/m3 ]

Appendix A A-7 0212210640

Revision 3 January 2002 Radioactivity concentration based on semi-infinite cloud model at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F.

(D/Q)., (D/Q)h, (D/Q)g Relative Deposition Factor [urM2]

Radioactivity concentration at a specified location per unit of radioactivity release concentration for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-6 of Appendix F.

Raipi Site-Specific Dose Factor [(m2 mrem/yr)I(pCi/sec)]

or [(mrem/yr)/(PCi/m 3 )]

Site-specific dose factor for age group a, nuclide i, pathway p and organ

j. Pathway included are ground plane exposure, inhalation, vegetation ingestion, milk ingestion and meat ingestion. Values of Raip, are provided in Appendix F.

Aiso Aiv Ag Cumulative Radionuclide Release [1Ci]

Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively.

Application RETS require cumulative and projected dose contributions for the current calendar quarter and the current calendar year for the specified non-noble gas radionuclides in airborne effluents to be determined at least once per 31 days (see Section 12.4 of each station's RETS and Technical Specifications).

To comply with this specification, each nuclear power station obtains and analyzes samples in accordance with the radioactive gaseous waste or gaseous effluent sampling and analysis program in its RETS. In accordance with NUREG 0133 (Reference 14), dose due to non-noble gases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure. The inhalation and ground plane exposure pathways are considered to exist at all locations. The food ingestion pathways at a specific location are considered based on their existence as determined by land use census. The values used for (X/Q) and (D/Q) correspond to the applicable pathway location.

For a release attributable to a processing or effluent system shared by more than one reactor, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system.

The allocation procedure is specified in ODCM Chapter 10.

The dose evaluated is also included as part of the 10CFR20 and 40CFRI90 assessment (See Section A.4).

A.1.4.1 Ground Deposition The site-specific dose factor for ground deposition of radioactivity is considered to be a total body dose component and is calculated by the following expression:

Ra(GP)J[D/Q] = K'Kw(o.7)DFG, [ ] (A-8)

Appendix A A-8 0212210640

Revision 3 January 2002 R ai(Gp)j [D/Q] Ground Plane Deposition Dose Factor [(M2 mrem/yr)/(pCi/sec)]

Site-specific ground plane dose factor for age group a, nuclide i and organ j. The ground plane dose is calculated using (D/Q).

K' Conversion Constant (I E6 pCi per pCi) [pCi/pCq K" Conversion Constant (8760 hr/yr) [hr/yr]

0.7 Shielding Factor; a factor which accounts for dimensionless shielding due to occupancy of structures.

DFG1 Ground Plane Dose Conversion Factor [(mrem/hr)/(pCim 2 )]

Dose rate to the total body per unit of surface radioactivity concentration due to standing on ground uniformly contaminated with radionuclide i. Taken from Table C-10 of Appendix C.

Note that ground plane dose factors are only given for the total body and no age group. Doses to other organs are assumed to be equal to the total body dose. All age groups are assumed to receive the same dose.

X1 Radiological Decay Constant [hr 1 ]

Radiological decay constant for radionuclide i. See Table C-7 of Appendix C.

tb Time Period of Ground Deposition [hr]

Time period during which the radioactivity on the ground is assumed to have been deposited. See Table C-1 of Appendix C.

Application The ground plane exposure pathway is considered to exist at all locations.

A.1.4.2 Inhalation The site-specific dose factor for inhalation is calculated by the following expression:

Ran(jnhal)jl /Q] = K'BRaDFAaQ (A-9)

Ral(Inhal)j [X/Q] Inhalation Pathway Dose Factor [(mnremlyr)I(PCVM 3)]

Site-specific inhalation dose factor for age group a, nuclide i and organ j.

The inhalation dose is calculated using (X/Q).

K' Conversion Constant (1E6 pCi per fiCi) [pCi/pCi r]

BRa Individual Air Inhalation Rate [m 3 lyrI The air intake rate for individuals in age group a. See Table C-2 of Appendix C.

DFAajj Inhalation Dose Conversion Factor [mrem/DCi 1 I-J Appendix A A-9 0212210640

Revision 3 January 2002 Dose commitment to an individual in age group a to organ j per unit of activity of radionuclide i inhaled. Taken from Tables E-7 through E-10 of Regulatory Guide 1.109. The value for H-3 is taken from NUREG 4013 (Reference 107).

Application The inhalation exposure pathway is considered to exist at all locations.

A.1.4.3 Food Ingestion Pathway Dose Factors Application Food ingestion pathway doses are calculated at locations indicated by the land use census survey. If no real pathway exists within 5 miles of the station, the cow-milk pathway is assumed to be located at 5 miles. Food pathway calculations are not made for sectors in which the offsite regions near the station are over bodies of water.

A.1.4.3.1 Vegetation Ingestion Pathway Dose Factor The dose factor for consumption of vegetables is calculated by the following expression:

R (V)j [D/Q] = K' (A+.r) 1 (DFLa. ) [Ua-fLe-LitL + Usfge-Xit1 (A-10)

Rai(veg)j [D/Q] Vegetation Ingestion Pathway Dose Factor [(m2 mrem/yr)/(.iCi/sec)]

Site-specific vegetation ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the vegetation dose is calculated using (D/Q).

K' Conversion Constant (1E6 pCi per piCi) [pCi/pCi]

r Vegetation Retention Factor dimensionless YV Agricultural Productivity Yield [kg! m2]

Radiological Decay Constant [11sec]

Radiological decay constant for radionuclide i. See Table C-7 of Appendix C.

Weathering Decay Constant [1/sec]

Removal constant for physical loss of activity by weathering. See Table C-1 of Appendix C.

DFL31j Ingestion Dose Conversion Factor [mrem/pCil Ingestion dose conversion factor for age group a, nuclide i and organ j.

Converts pCi ingested to mrem. Taken from Tables E-1 I though E-14 of Regulatory Guide 1.109. The value for H-3 is taken from NUREG 4013 (Reference 107).

UaL Consumption Rate for Fresh Leafy Vegetation [kglyr]

Appendix A A-10 0212210640

Revision 3 January 2002 Consumption rate for fresh leafy vegetation for age group a.

Uas Consumption Rate for Stored Vegetation [kg/yr]

Consumption rate for stored vegetation for age group a.

fL Local Leafy Vegetation Fraction dimensionless Fraction of the annual intake of fresh leafy vegetation which is grown locally.

fi Local Stored Vegetation Fraction dimensionless Fraction of the annual intake of stored vegetation which is grown locally.

tL Environmental Transport Time - Fresh Vegetation [sec]

Average time between harvest of leafy vegetation and its consumption.

th Environmental Transport Time - Stored Vegetation [sec]

Average time between harvest of stored vegetation and its consumption.

The tritium dose from the vegetation pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium vegetation pathway is:

Ra(H3Xveg)J[i/Q]=K'Kt - (UtfL + Usf 9 )DFLa(H 3)j [0.75(0.5/H)] (A-11)

Ra(3XVegqJ bC/Q] Tritium Vegetation Ingestion Pathway Dose Factor [(mrem/yr)/(pCi/m 3 )

Site-specific tritium vegetation ingestion dose factor for age group a and organ j. The tritium vegetation dose is calculated using X/Q.

K" Conversion Constant (1E3 gm per Kg) [gm/KEI]

H Absolute Atmospheric Humidity [gmwm3 0.75 Water Fraction dimensionless The fraction of total vegetation that is water.

0.5 Specific Activity Ratio dimensionlessa3 A.1.4.3.2 Milk Ingestion Pathway Dose Factor The dose factor for consumption of milk is calculated by the following expressions: .

Appendix A A-11 0212210640

Revision 3 January 2002 Ral(M.1k)j[D/Q] = K' Fm(r)(DFL.,j)[ + Y. ]e tf (A-1 2)

Rai(MIk)j[D/Q] Milk Ingestion Pathway Dose Factor [(M2 mremlyr)(pCi/sec)]

Site-specific milk ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the milk dose factor is calculated using (D/Q).

K' Conversion Constant (1E6 pCi per jiCi) [pCi/pCi]

QF Feed Consumption [Kg/da]

Amount of feed consumed by milk animal each day. See Table C-1 of Appendix C.

Uam Milk Consumption Rate [l/yr]

Milk consumption rate for age group a.

F. Stable Element Transfer Coefficient for Milk [dalI]

Fraction of animal's daily intake of a particular chemical element which appears in each liter of milk (pCi/l in milk per pCi/da ingested by animal).

See Table C-3 of Appendix C.

fp Pasture Time Fraction dimensionless Fraction of year that animal is on pasture.

f. Pasture Grass Fraction dimensionless Fraction of animal feed that is pasture grass while animal is on pasture.

Yp Agricultural Productivity Yield - Pasture Grass [kg/mi2 ]

The agricultural productivity by unit area of pasture feed grass.

Ys Agricultural Productivity Yield - Stored Feed [kg/m2t The agricultural productivity by unit area of stored feed.

th Environmental Transport Time - Stored Feed [sec]

Average time between harvest to consumption of stored feed by milk animal.

tf Environmental Transport Time - Pasture to Consumption [sec]

Average time from pasture, to milk animal, to milk, to consumption.

All other terms have been previously defined.

Appendix A A-12 0212210640

Revision 3 January 2002 The tritium dose from the milk pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium milk pathway is:

Ra(H-3XM.Ik)jk/Q]= K'K"-F. QFUamDFLa(H -)3j[0.75(0.5/H)] (A-1 3)

Ra(H-3XMIk)j [x/Q] Tritium Milk Ingestion Pathway Dose Factor [(mrem/yr)/(,pCi/M3 )]

Site-specific tritium milk ingestion dose factor for age group a and organ

j. The tritium milk dose is calculated using X/Q.

K"' Conversion Constant (I E3 gm per Kg) [gm/Kg]

H Absolute Atmospheric Humidity [gm/m 3 ]

0.75 Water Fraction dimensionless The fraction of total vegetation that is water.

0.5 Specific Activity Ratio dimensionless All other terms have been previously defined.

A.1.4.3.3 Meat The dose factor for consumption of meat is calculated by the following expression:

RaI(Meat)J [D/Q] = K' QF(Uf ) Ff (r)(DFLaj) [ yS+ (I - )e ] e-7t (A-14)

Ral(Meat)j [D/Q] Meat Ingestion Pathway Dose Factor [(m2 mrem/yr)/(jaCi/sec)]

Site-specific meat ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the meat dose factor is calculated using (D/Q).

Uaf Meat Consumption Rate [l/yr]

Meat consumption rate for age group a.

Stable Element Transfer Coefficient for Meat [da/Kg]

Fraction of animal's daily intake of a particular chemical element which appears in each liter of meat (pCi/Kg in meat per pC/da ingested by animal). See Table C-3 of Appendix C.

th Environmental Transport Time - Stored Feed [sec]

Average time between harvest to consumption of stored feed by meat animal.

tf Environmental Transport Time - Pasture to Consumption [sec]

Appendix A A-13 0212210640

Revision 3 January 2002 Average time from pasture, to meat animal, to meat, to consumption.

All other terms have been previously defined.

The tritium dose from the meat pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium meat pathway is:

Ra(H-3XMeat)jk[/Q]= K'K- F. QFUafDFLa(H 3)j[0.75(0.5/H)] (A-15)

Ra(H-3XMeat)J [C/Q] Tritium Meat Ingestion Pathway Dose Factor [(mremlyr)I(pCiM 3 )j Site-specific tritium meat ingestion dose factor for age group a and organ

j. The tritium meat dose is calculated using X/Q.

K"' Conversion Constant (1E3 gm per Kg) [gm/Kg]

H Absolute Atmospheric Humidity [gm/mr3 0.75 Water Fraction dimensionless The fraction of total vegetation that is water.

0.5 Specific Activity Ratio dimensionless All other terms have been previously defined.

A.1.5 Dose Rate Due to Non-Noble Gas Radionuclides Requirement RETS limit the dose rate to any organ, due to radioactive materials in gaseous effluents released from a site to areas at and beyond the site boundary, to less than or equal to a dose rate of 1500 mrem/yr (see Section 12.4 of each station's RETS and Technical Specifications).

Typically the child is considered to be the limiting receptor in calculating dose rate to organs due to inhalation of non-noble gas radionuclides in gaseous effluents.

Equation The dose rate to any child organ due to inhalation is calculated by the following expression:

. NNG D(Chd)1(1nha1)J = E R(chd) Q1. + (X/Q)1 Qtv + (X/Q)g Qjg J (x/Q)N (A-1 6)

The summation is over non-noble gas radionuclides i.

. NNG D(chIld)1(Inhal)j Inhalation Dose Rate [mrem/yr]

Dose rate to the child age group from radionuclide i, via the inhalation pathway to organ j due to non-noble gas radionuclides.

R(Chi~d)i(Inhalj Inhalation Dose Factor [(mrem/yr)/(pCim 3)]

Appendix A A-14 0212210640

Revision 3 January 2002 Inhalation dose factor for child age group for radionuclide i, and organ j.

This dose factor is defined by Equation A-9.

QiS9 Q1v? Qag Radionuclide Release Rate [pCi/sec]

Measured release rate of radionuclide i from a stack, vent, or ground level release point, respectively.

All other terms have been previously defined.

Application RETS require the dose rate due to non-noble gas radioactive materials in airborne effluents be determined to be within the above limit in accordance with a sampling and analysis program specified in the RETS (see Section 12.4 of each station's RETS and Technical Specifications).

To comply with this specification, each station obtains and analyzes samples in accordance with the sampling and analysis program in its RETS. The child organ dose rate due to inhalation is calculated in each sector at the location of the highest offsite X/Q. The result for the sector with the highest organ inhalation dose rate is compared to the limit.

A.1.6 Operability and Use of Gaseous Effluent Treatment Systems Requirement 10CFR50 Appendix I and the station RETS require that the ventilation exhaust treatment system and the waste gas holdup system be used when projected offsite doses in 31 days, due to gaseous effluent releases, from each reactor unit, exceed any of the following limits:

• 0.2 mrad to air from gamma radiation.

• 0.4 mrad to air from beta radiation.

• 0.3 mrem to any organ of a member of the public.

The nuclear power stations are required to project doses due to gaseous releases from the site at least once per 31 days.

Equation Offsite doses due to projected releases of radioactive materials in gaseous effluents are calculated using Equations A-1, A-2 and A-7. Projected cumulative radionuclide releases are used in place of measured cumulative releases A,, A4, and Ag.

Application For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in Chapter 10 of this manual.

A.2 LIQUID RELEASES Appendix A A-15 0212210640

3 Revision Revision 3 January 2002 A.2.1 Dose Requirement The design objectives of 10CFR50, Appendix I and RETS provide the following limits on the dose to a member of the public from radioactive materials in liquid effluents released from each reactor unit to restricted area boundaries:

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

• During any calendar year, less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ.

The organ doses due to radioactivity in liquid effluents are also used as part of the 40C FRI 90 compliance and are included in the combination of doses to determine the total dose used to demonstrate 10CFR20 compliance. (See Section A.4)

Dose assessments for 10CFR50 Appendix I compliance are made for four age groups (adult/teenager/child/infant) using NUREG 0133 (Reference 14) methodology and Regulatory Guide 1.109 (Reference 6) dose conversion factors.

Equation The dose from radioactive materials in liquid effluents considers the contributions for consumption of fish and potable water. All of these pathways are considered in the dose assessment unless demonstrated not to be present. While the adult is normally considered the maximum individual, the methodology provides for dose to be calculated for all four age groups. The dose to each organ (and to the total body) is calculated by the following expression:

= F At YAaipjCi a]Uq (A-I 7)

PI The summation is over exposure pathways p and radionuclides i.

DaLq Organ and Total Body Dose Due to Liquid Effluents [mrem]

Dose to organ j (including total body) of age group a due to radioactivity in liquid effluents.

F Near Field Average Dilution Factor dimensionless Dilution in the near field averaged over the period of interest.

Defined as:

F Waste Flow (A-18)

Dilution Flow xZ Waste Flow Liquid Radioactive Waste Flow [gpm]

The average flow during disposal from the discharge structure release point into the receiving water body.

Dilution Flow Dilution Water Flow During Period of Interest [gpm]

Z Discharge Structure Mixing Factor dimensionless Appendix A A-16 0212210640

Revision 3 January 2002 Site-specific factor to account for the mixing effect of the discharge structure. The factor addresses the dilution which occurs in the near field between the discharge structure and the body of water containing the fish in the liquid ingestion pathway. From Table F-1, Appendix F.

At Duration of Release [hrs]

C, Average Radionuclide Concentration [ICimlI]

Average concentration of radionuclide i, in the undiluted liquid effluent during time period At.

Aaipj Site-Specific Liquid Dose Factor [(mrem/hr)/(pCliml)]

Site-specific dose factor for age group a, nuclide i, liquid pathway p and organ j. The pathways included are potable water and fish ingestion.

Aaipj is defined for these pathways in the following sections. Values for Aaipj are provided in Appendix F.

A 2.1.1 Potable Water Pathway The site-specific potable water pathway dose factor is calculated by the following expression:

Aal(Pw)j ko{U}DFLal; (A-1 9)

Where:

Aaixpmj Site-Specific Dose Factor for Potable Water [(mrem/hr)/(jiC/ml)]

Pathway Site-specific potable water ingestion dose factor for age group a, nuclide i and organ j.

k. Conversion Constant (1.14E05) [(yr-pCi-ml)/(hr-pCi-I)]

Units constant to convert years to hours, pCi to pCi and liters to ml.

UaW Potable Water Consumption Rate [/yr]

Potable water consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109.

Dw Potable Water Dilution Factor dimensionless Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake. From Table F-1, Appendix F.

DFLaj Ingestion Dose Conversion Factor [mrem/pCi]

Ingestion dose conversion factor for age group a, nuclide i and organ j.

Converts pCi ingested to mrem. Taken from Tables E-1 1 though E-14 of Regulatory Guide 1.109. The value for H-3 is taken from NUREG 4013 (Reference 107).

Appendix A A-17 0212210640

Revision 3 January 2002 A.2.1.2 Fish Ingestion Pathway The site-specific fish ingestion pathway dose factor is calculated by the following expression:

Aal(F[Sh)j = koUFBFiDFLaiJ (A-20)

Where:

AaI(FIsh)j Site-Specific Dose Factor for Potable Water [(mrem/hr)/(pCi/ml)]

Pathway Site-specific fish ingestion dose factor for age group a, nuclide i and organ j.

UaF Fish Consumption Rate [kglyr]

Fish consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109.

BF1 Bioaccumulation Factor [(pCilkg)/(pCi/l)]

Bioaccumulation factor for nuclide i in fresh water fish. Taken from Table C-8 of Appendix C.

All other terms have been previously defined.

Application RETS require determination of cumulative and projected dose contributions from liquid effluents for the current calendar quarter and the current calendar year at least once per 31 days. (see Section 12.3 of each station's RETS and/or Technical Specifications).

For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10.

A.2.2 Liquid Effluent Concentrations Requirement Requirement One method of demonstrating compliance to the requirements of 10CFR20.1301 is to demonstrate that the annual average concentrations of radioactive material released in gaseous and liquid effluents do not exceed the values specified in 10CFR20 Appendix B, Table 2, Column 2. (See 10CFR 20.1302(b)(2).)

However, as noted in Section A.5.1, this mode of I OCFR20.1301 compliance has not been elected.

As a means of assuring that annual concentration limits will not be exceeded, and as a matter of policy assuring that doses by the liquid pathway will be ALARA; RETS provides the following restriction:

"The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402."

This also meets the requirement of Station Technical Specifications and RETS.

Equation Appendix A A-18 0212210640

Revision 3 January 2002 According to the footnotes to I OCFR20 Appendix B, Table 2, Column 2, if a radionuclide mix of known composition is released, the concentrations must be such that (T ECCI )1 (A-21) where the summation is over radionuclide i.

C1 Radioactivity Concentration in [jCi/mi Liquid Effluents to the Unrestricted Area Concentration of radionuclide i in liquid released to the unrestricted area.

ECLd Effluent Concentration Limit in Liquid [gCi/ml]

Effluents Released to the Unrestricted Area The allowable annual average concentration of radionuclide i in liquid effluents released to the unrestricted area. This concentration is specified in 10CFR20 Appendix B, Table 2; Column 2. Concentrations for noble gases are different and are specified in the stations' Technical Specifications/RETS.

10 Multiplier to meet the requirements of Technical Specifications.

If either the identity or concentration of any radionuclide in the mixture is not known, special rules apply.

These are given in the footnotes in 10CFR20 Appendix B, Table 2, Column 2.

Application The RETS and Technical Specifications require a specified sampling and analysis program to assure that liquid radioactivity concentrations at the point of release are maintained within the required limits.

To comply with this provision, each nuclear power station obtains and analyzes samples in accordance with the radioactive liquid waste (or effluent) sampling and analysis program in its RETS. Radioactivity concentrations in tank effluents are determined in accordance with Equation A-22 in the next section.

Comparison with the Effluent Concentration Limit is made using Equation A-21.

A.2.3 Tank Discharges When radioactivity is released to the unrestricted area with liquid discharge from a tank (e.g., a radwaste discharge tank), the concentration of a radionuclide in the effluent is calculated as follows:

I= Ct Waste Flow (-2 1 Dilution Flow (A-22)

C1 Concentration in Liquid effluent to the unrestricted area. [ACi/ml]

Concentration of radionuclide i in liquid released to the unrestricted area.

Cit Concentration in the Discharge Tank [ACi/mlJ Measured concentration of radionuclide i in the discharge tank.

All other terms have been previously defined.

Appendix A A-1 9 0212210640

Revision 3 January 2002 A.2.4 Tank Overflow Requirement To limit the consequences of tank overflow, the RETS/Technical Specifications may limit the quantity of radioactivity that may be stored in unprotected outdoor tanks. Unprotected tanks are tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. The specific objective is to provide assurance that in the event of an uncontrolled release of a tank's contents, the resulting radioactivity concentrations beyond the unrestricted area boundary, at the nearest potable water supply and at the nearest surface water supply, will be less than the limits of 10CFR20 Appendix B, Table 2; Column 2.

The Technical Specifications and RETS may contain a somewhat similar provision. For most nuclear power stations, specific numerical limits are specified on the number of curies allowed in affected tanks.

Application Table F-I of Appendix F provides information on the limits applicable to affected stations. The limits are as stated for some stations in the station Technical Specifications.

A.2.5 Operability and Use of the Liquid Radwaste Treatment System Requirement The design objectives of I OCFR50, Appendix I and RETS/Technical Specifications require that the liquid radwaste treatment system be operable and that appropriate portions be used to reduce releases of radioactivity when projected doses due to the liquid effluent from each reactor unit to restricted area boundaries exceed either of the following (see Section 12.3 of each station's RETS or Technical Specifications);

• 0.06 mrem to the total body in a 31 day period.

• 0.2 mrem to any organ in a 31 day period.

Equation Offsite doses due to projected releases of radioactive materials in liquid effluents are calculated using Equation A-17. Projected radionuclide release concentrations are used in place of measured concentrations, C1.

A.2.6 Drinking Water Five nuclear power stations (Braidwood, Dresden, LaSalle, Quad Cities, and Zion) have requirements for calculation of drinking water dose that are related to 40CFRI41, the Environmental Protection Agency National Primary Drinking Water Regulations. These are discussed in Section A.6.

Appendix A A-20 0212210640

Revision 3 January 2002 A.2.7 Non-routine Liquid Release Pathways Cases in which normally non-radioactive liquid streams (such as the Service Water) are found to contain radioactive material are non-routine will be treated on a case specific basis if and when this occurs. Since each station has sufficient capacity to delay a liquid release for reasonable periods of time, it is expected that planned releases will not take place under these circumstances. Therefore, the liquid release setpoint calculations need not and do not contain provisions for treating multiple simultaneous release pathways.

A.3 DOSE DUE TO CONTAINED SOURCES There are presently two types of contained sources of radioactivity which are of concern in Exelon Nuclear offsite radiological dose assessments. The first source is that due to gamma rays from nitrogen-16 (16N) carried over to the turbine in BWR (boiling water reactor) steam. The second source is that due to gamma rays associated with radioactive material resident in onsite radwaste storage facilities. Gamma radiation from these sources contributes to the total body dose.

A.3.1 BWR Skyshine The contained onsite radioactivity source which results in the most significant offsite radiation levels at Exelon Nuclear nuclear power stations is skyshine resulting from 16N decay inside turbines and steam piping at boiling water reactor (BWRs).

The 16N that produces the skyshine effect is formulated through neutron activation of the oxygen atoms (oxygen-1 6, or 160) in reactor coolant as the coolant passes through the operating reactor core. The 16N travels with the steam produced in the reactor to the steam driven turbine. While the 16N is in transport, it radioactively decays with a half-life of about 7 seconds and produces 6 to 7 MeV gamma rays. Typically, offsite dose points are shielded from a direct view of components containing ' 6N, but there can be skyshine radiation at offsite locations due to scattering of gamma rays off the mass of air above the steamlines and turbine.

The offsite dose rate due to skyshine has been found to have the following dependencies:

• The dose rate decreases as distance from the station increases.

• The dose rate increases non-linearly as the power production level increases.

• The dose rate increases when hydrogen is added to the reactor coolant, an action taken to improve reactor coolant chemistry characteristics (see Reference 39).

To calculate offsite dose due to skyshine in a given time period, a BWR must track the following parameters:

• The total gross energy Eh produced with hydrogen being added.

• The total gross energy E0 produced without hydrogen being added.

The turbines at BWR sites are sufficiently close to each other that energy generated by the two units at each site may be summed.

An initial estimate of BWR skyshine dose is calculated per the following equation:

D y= (K)(E 0 +MhEh)E{OFk SFk e 7 Rk } (A-23) k The summation is over all locations k occupied by a hypothetical maximally exposed member of the public characterized by the parameters specified in Table F-8 of Appendix F of the Dresden, LaSalle, and Quad Cities ODCMs. The parameters in Equation A-23 are defined as follows:

Appendix A A-21 0212210640

Revision 3 January 2002 DSk Dose Due to N-16 Skyshine [mrem]

External direct gamma dose due to BWR N-1 6 skyshine for the time period of interest.

K Empirical Constant [mrem/(MWe-hr)]

A constant determined by fitting data measured at each station.

E. Electrical Energy Generated Without Hydrogen Addition [MWe-hr]

Total gross electrical energy generated without hydrogen addition in the time period of interest.

Eh Electrical Energy Generated with Hydrogen Addition [MWe-hr]

Total gross electrical energy generated with hydrogen addition in the period of interest.

Mh Multiplication Factor for Hydrogen Addition dimensionless Factor applied to offsite dose rate when skyshine is present. Hydrogen addition increases main steam line radiation levels typically up to a factor of approximately 5 (see Page 8-1 of Reference 39). Mh is station specific and is given in Table F-8, Appendix F of Dresden, LaSalle and Quad Cities ODCMs.

OFk Occupancy Factor dimensionless The fraction of time that the dose recipient spends at location k during the period of interest. See Table F-8, Appendix F of Dresden, LaSalle and Quad Cities ODCMs.

SFk Shielding Factor dimensionless A dimensionless factor that accounts for shielding due to occupancy of structures.

SFk = 0.7 if there is a structure at location k; SFk = 1.0 otherwise. See Table F-8, Appendix F of Dresden, LaSalle and Quad Cities ODCMs.

0.007 Empirical Constant [m 1 ]

A constant determined by fitting data measured at the Dresden station (see Reference 45).

Rk Distance [ml Distance from the turbine to location k. See Table F-8, Appendix F of Dresden, LaSalle and Quad Cities ODCMs.

A3.2 Dose from Onsite Radwaste Storage Facilities Appendix A A-22 0212210640

Revision 3 January 2002 Low-level radioactive waste may be stored at any, or all Exelon Nuclear nuclear power stations in the following types of storage facilities:

• Interim Radwaste Storage Facility (IRSF)

• Concrete vaults containing 48 radwaste liners (48-Pack)

• Dry Active Waste (DAW) facilities

• Butler buildings/warehouses

• Steam generator storage facilities

• Independent Spent Fuel Storage Installation (ISFSI) facilities The "48-Pack" is a shielded concrete vault which is designed to hold three tiers of radwaste liners in a four by four array. The outer shell of the "48-Pack" is a three-foot thick concrete wall and a two and one-half foot thick concrete cover slab. The vault is placed on a poured concrete slab. The liners may have an average surface dose rate of fifteen (15) rem per hour (or up to 380 rem/hr if a 50.59 evaluation has been completed).

The DAW facility will contain low-level radioactive waste that would result in dose rates less than the 10CFR20 requirements.

The dose rates resulting from these radwaste and spent fuel storage facilities will be monitored frequently as they are being utilized, and if necessary, a dose calculation model similar to that of Equation A-23 will be developed and placed in the ODCM.

A.4 Total Dose Limits (IOCFR20 and 40CFR190)

The regulatory requirements of 10CFR20 and 40CFR190 each limit total dose to individual members of the public without regard to specific pathways. The only significant exposure pathways for light water reactors included in 10CFR20 and 40CFRI90 not addressed by 10CFR50 Appendix I are the direct radiation pathway and exposure from on-site activity by members of the public. Sections A.1 and A.2 considered organ doses from the gaseous and liquid effluent streams for purposes of compliance with 10CFR50 Appendix I. Section A.3 addresses the direct radiation component that must be considered for 10CFR20 and 40CFR190 compliance. The following sections will describe the methodology of assessing direct radiation dose and then the manner in which the various doses are combined to obtain the appropriate "total" for regulatory compliance purposes.

Although annual dose limits in 10CFR20 are now expressed in terms of Total Effective Dose Equivalent (TEDE) 40CFR1 90 limits are still stated as organ dose. The NRC continues to require 10CFR50 Appendix I and 40CFRI 90 doses to be reported in terms of organ dose. Due to the fact that organ dose limits set forth in 40CFR190 are substantially lower than those of 10CFR20 (25 mrem/yr vs 100 mremfyr), the NRC has stated that demonstration of compliance with the dose limits in 40CFR1 90 will be deemed as demonstration of compliance with the dose limits of I OCFR20 for most facilities (Reference 104). In addition to compliance with 40CFR1 90 it may be necessary for a nuclear power plant to address dose from on-site activity by members of the public.

A.4.1 External Total Body Dose The external total body dose is comprised of the following parts:

1) Total body dose due to noble gas radionuclides in gaseous effluents (Section A.1.2),

2) Dose due to N-16 skyshine and other contained sources (Sections A.3.1 and A.3.2) and

3) Total body dose due to radioactivity deposited on the ground (Section A.1.4.1).

The external total body dose due to radioactivity deposited on the ground is accounted for in the determination of the non-noble gas dose (See Equations A-7 and A-8) and is not considered here.

The total external total body dose, DF, is given by:

Appendix A A-23 0212210640

Revision 3 January 2002 DEx=DTB + DSky + DOsF (A-24)

Drx Total External Total Body Dose [mrem]

Total external total body dose due to irradiation by external sources at the location of interest.

DTB Noble Gas Total Body Dose [mrem]

External total body dose due to gamma radiation from noble gas radionuclides released in gaseous effluents at the location of interest.

See Equation A-3.

DSk N-1 6 Skyshine Total Body Dose [mrem]

External total body dose due to N-16 skyshine for the period and location of interest. See Equation A-23.

DOSF Dose From On-Site Storage Facilities [mrem]

External total body dose due to gamma radiation from on-site storage facilities at the location of interest. See Section A.3.2.

A.4.2 Total Dose The total dose, DT°", in the unrestricted area to a member of the public due to plant operations is given by:

DTot = DEx + D Uqa)

+ DNNG al (A-25) where:

DTot Total Dose To Member of Public [mrem]

Total off-site dose to a member of public due to plant operations.

DEx Total External Total Body Dose [mrem]

Total body dose due to external exposure to noble gases, N-1 6 skyshine and on-site storage facilities.

DLiq Liquid Effluent Dose [mrem]

Dose due to liquid effluents to age group a and organ j. The age group and organ with the highest dose from liquid effluents is used.

DNJNG Non-Noble Gaseous Effluent Dose [mrem]

Dose due to non-noble gaseous effluents to age group a and organ j.

The age group and organ with the highest dose from non-noble gas effluents is used.

A.5 COMPLIANCE TO TOTAL DOSE LIMITS Appendix A A-24 0212210640

Revision 3 January 2002 A.5.1 Total Effective Dose Equivalent Limit - IOCFR2O Compliance Requirement Each station's RETS limits the Total Effective Dose Equivalent (TEDE) to an annual limit of required by 10CFR20.1301 (a)(1). Demonstration of compliance with the limits of 40CFR1 100 mrem, as 90 (per Section 4.5.2) will be considered to demonstrate compliance with the 100 mrem/year limit.

A.5.1.1 Dose to a Member of the Public in the Unrestricted Area The NRC has stated that demonstration of compliance with the limits of 40CFR1 90 or with the objectives of Appendix I to 10CFR50 will be deemed to demonstrate compliance with the limits design of 10CFR20.1301(a)(1). Power reactors that comply with Appendix I may also have to demonstrate are within the 25 mrem limit of 40CFR190 (See Reference 104). that they A.5.1.2. Dose to a Member of the Public in the Restricted Area In August of 1995, a revision to I OCFR20 was implemented that changed the definition of a member of the public. As a result, for each nuclear station, estimated doses were calculated for a member public who enters the site boundary, but is not authorized for unescorted access to the protected of the the site and does not enter any radiologically posted areas on the site. Realistic assumptions area of were made for occupancy times and locations visited while within the site boundary.

These evaluations indicate that the doses estimated for these members of the public are well within the 10CFR20 limits. These dose evaluations will be performed annually and if necessary, a model developed and included in the ODCM. will be Application Evaluation of the 40CFRI 90 dose is used to demonstrate compliance to 10CFR20 and satisfy station RETS and Technical Specifications (see Chapter 12).

A-5.2 Total Dose due to the Uranium Fuel Cycle (40CFRI90)

Requirement RETS and 40CFR190 limit the annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources to the following:

• Less than or equal to 25 mrem to the total body.

• Less than or equal to 25 mrem to any organ except the thyroid.

• Less than or equal to 75 mrem to the thyroid.

Total Dose Components This requirement includes the total dose from operations at the nuclear power station. This includes doses due to radioactive effluents (airbome and liquid) and dose due to direct radiation from non-effluent sources (e.g., sources contained in systems on site). Italso includes dose due to plants under consideration, neighboring plants and dose due to other facilities in the uranium fuel cycle.

The operations comprising the uranium fuel cycle are specified in 40CFR190.02(b). The following are included to the extent that they directly support the production of electrical power for public use utilizing nuclear energy:

• Milling of uranium ore.

• Chemical conversion of uranium.

• Isotopic enrichment of uranium.

• Fabrication of uranium fuel.

Appendix A A-25 0212210640

Revision 3 January 2002

• Generation of electricity by a light-watered-cooled nuclear power plant using uranium fuel.

• Reprocessing of spent uranium fuel.

Excluded are:

• Mining operations.

• Operations at waste disposal sites.

• Transportation of any radioactive material in support of these operations.

• The re-use of recovered non-uranium special nuclear and by-product materials from the cycle.

When Compliance Assessment is Required Compliance with the 40CFRI90 regulations is now required as part of demonstration of compliance to IOCFR20 regulations per 10CFR20.1301 (d).

Equation The dose due to the uranium fuel cycle is determined by equation A-25.

A5.3 Summary of Compliance Methodology The required compliance is given in Tables 2-1, 2-2 and 2-3. In Table 2-1, the dose components are itemized and referenced, and an indication of their regulatory application is noted. A more detailed compliance matrix is given in Table 2-3. The locations of dose receivers for each dose component are given in Table 2-2.

Further, Table 2-2 states the location of the receiver and occupancy factors, if applicable. In general, the receiver spends time in locations that result in maximum direct dose exposure and inhales and ingests radioactivity from sites that yield maximum pathway doses. Thus, the dose calculated is a very conservative one compared to the "average" receiver who does not go out of his way to maximize radioactivity uptakes. Finally, the connection between regulations, the ODCM equations and the station RETS and Technical Specifications is given in Table 12-0.

A.6 DOSE DUE TO DRINKING WATER (40CFRI41)

The National Primary Drinking Water Regulations, 40CFR1 41, contain the requirements of the Environmental Protection Agency applicable to public water systems. Included are limits on radioactivity concentration. Although these regulations are directed at the owners and operators of public water systems, several stations have requirements in their Technical Specifications related to 40CFR141.

A6.1 40CFRI41 Restrictions on Manmade Radionuclides Section 141.16 states the following (not verbatim):

(a) The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 millirem/year.

(b) Except for the radionuclides listed in Table A-0, the concentration of man-made radionuclides causing 4 mrem total body or organ dose equivalents shall be calculated on the basis of drinking 2 liter of water per day. (Using the 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> data listed in "Maximum Permissible Body Burdens and Maximum Permissible Concentration of Radionuclides in Air or Water for Occupational Exposure, "NBSHandbook 69 as amended August 1963, U.S. Department of Commerce.). If two or more radionuclides are present, the sum of their annual dose equivalents to the total body or any organ shall not exceed 4 millirem/year.

Appendix A A-26 0212210640

Revision 3 January 2002 TABLE A-0 AVERAGE ANNUAL CONCENTRATIONS ASSUMED TO PRODUCE A TOTAL BODY OR ORGAN DOSE OF 4 MREM/YR Radionuclide Critical Organ pCi I liter Tritium Total body 20,000 Strontium-90 Bone marrow 8 A-6.2 Application The projection or calculation of dose due to the drinking water pathway is made using Equations A-17 and A-19. Projections are made using projected radionuclide releases in place of measured releases A.

Doses calculated using Equations A-1 7 and A-1 9 may differ from doses determined by the methodology prescribed in 40CFR141.16.

When required, a nuclear power station prepares a special report on radiological impact at the nearest community water system. This system is taken as the one listed in Table A-3 of this appendix. The report should include the following:

• The doses calculated by Equations A-17 and A-19.

• A statement identifying the dose calculation methodology (e.g., a reference to this manual).

• A statement that the doses calculated bythe ODCM methodology are not necessarily the same as doses calculated by the methodology prescribed in 40CFR1 41.16.

• The data used to calculate the doses. This information includes the amounts of radioactivity released and the flow rate and dilution values used (see Table F-1). This information is provided to assist the operator of the community water system in performing its own dose assessment.

Appendix A A-27 0212210640

Revision 3 January 2002 Table A-1 COMPLIANCE MATRIX Regulation Dose to be compared to limit IOCFR50

• Gamma air dose and beta air dose due to airborne radioactivity in effluent Appendix I plume.

l Total body and skin dose due to airborne radioactivity in effluent plume are reported only if certain gamma and beta air dose criteria are exceeded.

l Dose for all organs and all four age groups due to iodine and particulate in effluent plume. Existing pathways are considered.

l Dose for all organs and all four age groups due to radioactivity in liquid effluents.

IOCFR20

• Adherence determined by compliance with dose limits of 40CFR1 90.

40CFR190

• Total body dose due to direct radiation, ground and plume exposure from (now, by reference, all sources at a station.

also part of 10CFR20

. Organ doses to an adult due to all pathways.

RETSIODCM * "Instantaneous" noble gas total body and skin dose rates and radioiodine, tritium and particulate inhalation dose rates to a child due to radioactivity in airborne effluents.

• "Instantaneous" concentration limits for liquid effluents.

Appendix A A-28 021221 0640

Revision 3 January 2002 Table A-2 Release Point Classifications Release Release Point Station Point Classificationa Braidwood 1 & 2 Vent Stacks Vent (Mixed Mode)

Byron 1 & 2 Vent Stacks Vent (Mixed Mode)

Dresden 1 Plant Chimney Stack (Elevated)

Chemical Cleaning Vent (Mixed Mode)

Dresden 2 & 3 Chimney Stack (Elevated)

Reactor Building Vent (Mixed Mode)

Ventilation Exhaust Stack LaSalle I & 2 Main Station Stack (Elevated)

Vent Stack .

Standby Gas Stack (Elevated)

Treatment Stackb Quad Cities 1 & 2 Chimney Stack (Elevated)

Reactor Building Vent (Mixed Mode)

Ventilation Exhaust Stack Zion 1 &2 Vent Stacks Ground Level aThe definitions of release point classifications (stack, vent and ground level) are given in Section 4.1.4.

bThe LaSalle standby gas treatment stack is located inside the main station vent stack.

Appendix A A-29 0212210640

Revision 3 January 2002 Table A-3 Nearest Downstream Community Water Systems Characteristics of Nearest Affected Downstream Community Water SupplV Exelon Nuclear Other Exelon Facilities Location Nuclear Stations Upstream of and Upstream of Station Station Distancea Water Supplv Braidwood None Wilmington, None 5 river miles Byron None None within NAb 115 river miles Dresden Braidwood Peoria, Braidwood 106 river -LaSalle miles LaSalle Braidwood Peoria, Braidwood Dresden 97 river Dresden miles Quad Cities None E. Moline, None 16 river miles Zion None Lake County None Intake, 1.4 miles aODCM Bases and Reference Document (Reference 101) Table 0-2 and 0-6 provide the bases of the location and distance data.

bNA = not applicable. For purposes of the calculations in the ODCM, there are no community water supplies affected by liquid effluents from Byron Station. This is based on the absence of community water supplies between the Byron Station liquid discharge to the Rock River and the confluence of the Rock and Mississippi Rivers, 115 miles downstream.

Appendix A A-30 0212210640

Revision 3 January 2002 Table A-4 40CFRI90 Compliance 40CFR190 Dose Annual Limit ODCM Dose and Equation Number (mrem)

Total Body 25 Total Body Dose; A-25 evaluated for total body Thyroid 75 Thyroid Dose; A-25 evaluated for thyroid Other Organs 25 Organ Dose; A-25 evaluated for all organs except thyroid Notes:

1. The evaluation is made considering the following sources:

a. Radioactivity in contained sources within the station;

b. Radioactivity in station gaseous and liquid effluents;

c. Dose contributions from neighboring stations and other facilities in the nuclear fuel cycle.

Appendix A A-31 0212210640

APPENDIX B Revision 3 January 2002 APPENDIX B MODELS AND PARAMETERS FOR AIRBORNE and LIQUID EFFLUENT CALCULATIONS TABLE OF CONTENTS SECTION 1: PAGE Models and Parameters for AIRBORNE Effluent Calculations B.0 INTRODUCTION B-1 B.1 METEOROLOGICAL DATA AND PARAMETERS B-1

1. Data B-2

2. Joint Frequency Distribution B-2

1. Downwind Direction Versus Upwind Direction B-2

2. Stack JFD B-3

3. Ground Level JFD B-3

4. Vent JFDs B-3

3. Average Wind Speed B4

1. Stack Release B-5

2. Ground Level Release B-5

3. Vent Release B-5 8.2 GAUSSIAN PLUME MODELS B-6

1. Mathematical Representation B-6

2. Sector-Averaged Concentration B-7 B.3 RELATIVE CONCENTRATION FACTOR X/Q B-7

1. Stack Release B-8

1. Effective Release Height B-9

1. Plume Rise B-1 0

2. Terrain Effects B-11

2. Ground Level Release B-i 1

3. Vent Release B-1 2

4. Removal Mechanisms B-1 2

5. Gamma-X/Q B-1 3 B.4 RELATIVE DEPOSITION FACTOR DIQ B-1 4

1. Stack Release B-1 5

2. Ground Level Release B-1 6

3. Vent Release B-1 6 8.5 GAMMA AIR DOSE FACTORS (SI, VI, GI) B-17

1. Stack Release B-17

2. Ground Level Release B-19

3. Vent Release B-19 Appendix B Bali 0212210641

Revision 3 January 2002 APPENDIX B Table of Contents (Cont'd)

B.6 GAMMA TOTAL BODY DOSE CONVERSION FACTORS (K,) PAGE B-20 B.7 BETA AIR AND SKIN DOSE FACTORS (N,, L,) B-20 B.8 GROUND PLANE DOSE CONVERSION FACTOR DFGi B-20 B.9 INHALATION DOSE COMMITMENT FACTOR DFAija B-20 B.10 INGESTION DOSE COMMITMENT FACTOR DFIija B-20 B.11 MEASURED RELEASE PARAMETERS B-21 B.12 RADIOLOGICAL DECAY CONSTANTS B-21 B.13 PRODUCTION/EXPOSURE PARAMETERS B-21 SECTION 2: Models and Parameters for LIQUID Effluent Calculations:

B.14 INTRODUCTION B-22 B.15 DOSE B-22

1. Drinking Water B-22

2. Aquatic Foods (Fish) B-22

3. Parameters B-23

1. Flow and Dilution B-23

1. River Model - B-23

2. Lake Michigan Model B-23

2. Dose Factors B-23

3. Measured Releases B-23

4. Consumption B-24 B.16 CONCENTRATION IN TANK DISCHARGES B-24 Appendix B A B-ii 0212210641

Revision 3 January 2002 APPENDIX B LIST OF TABLES NUMBER TITLE PAGE B-0 Noble Gas Nuclide Fraction B-25 B-1 Portion of an Example Joint Frequency Distribution B-26 LIST OF FIGURES NUMBER TITLE PAGE B-1 Instantaneous View of a Plume B-27 B-2 A Gaussian Curve B-28 B-3 Effect of Observation Period on Plume Shape B-29 B-4 A Gaussian Plume B-30 Appendix B B-iii 0212210641

Revision 3 January 2002 SECTION 1:

MODELS AND PARAMETERS FOR AIRBORNE EFFLUENT CALCULATIONS B.0 INTRODUCTION The equations used for calculation of doses due to radioactive airborne effluents are given in Section A.1 of Appendix A. The equations involve the following types of parameters:

• Meteorological Parameters These include XI0, gamma-7IQ, DIQ and wind speed. Their values are based on historical average atmospheric conditions at a site for a selected multi-year historical Section 4.1.5). period (see

• Dose Factors These parameters are used to provide a simple way to calculate doses and dose rates due to gamma and beta radiation. These parameters are independent of meteorological conditions and therefore generic (i.e., not station-specific).

• Measured Release Parameters These are measured values of radioactivity releases and release rates.

• Radiological Decay Constants These are used to account for the radioactive decay between the release the environment and the exposure of persons to it. of radioactivity to

• Production/Exposure Parameters These are parameters characterizing agricultural production (e.g., length of growing season, transport times) and human exposure patterns (e.g., exposure period, breathing rate, food consumption rates). These parameters affect the quantities of radioactivity may be exposed. to which persons This appendix discusses the methodology used to determine values addresses how the historical meteorology of a site is characterized of these parameters. Section B.1 by use of a function called the joint frequency distribution. Section B.1 and Sections B.3 through B.5 present frequency distribution to obtain values for site-specific meteorological equations that use the joint parameters. These equations involve a mathematical model of a plume known as the Gaussian plume in Section B.2. Various generic dose factors are discussed in Sections model. This model is developed B.6 through B.10. The other parameters are discussed in the remaining sections.

B.1 METEOROLOGICAL DATA AND PARAMETERS Predicting where airborne effluent will travel requires information on the following:

• Wind speed

• Wind direction

• Atmospheric turbulence The greater the atmospheric turbulence, the more an effluent plume will tend to broaden and the more dilute the concentration will be. Atmospheric turbulence is affected by the general condition of the atmosphere (e.g., the vertical temperature distribution) and by local features into the wind stream). A commonly used classification scheme for the (e.g., objects that protrude degree of atmospheric turbulence associated with the general condition of the atmosphere involves seven stability classes:

A Extremely Unstable B Moderately Unstable C Slightly Unstable D Neutral Appendix B B-1 0212210641

Revision 3 January 2002 E Slightly Stable F Moderately Stable G Extremely Stable This classification scheme is based on Reference 5, Table 1. Each class is associated with a particular range of wind direction fluctuations and of vertical temperature gradients in the atmosphere. These are specified in Table C-4 of Appendix C.

B.1.1 Data Historical atmospheric conditions at each nuclear power station were recorded by an instrumented meteorological tower that measured wind speed, wind direction, and temperature at various heights.

Hourly average values of wind speed, wind direction, and stability class were determined. The difference in temperature between two heights was used to assign an atmospheric stability class based on the correlation between temperature gradient and stability class in Table C-4 of Appendix C.

In obtaining the data, quality assurance checks and corrections were made. Also, corrections were applied to compensate for the limitations of wind sensors at low speeds. A calm was said to exist if the wind speed was less than that of the threshold of either the anemometer (wind speed meter) or the wind direction vane. For calm conditions, a wind speed equal to one-half of the higher threshold was assigned.

For each stability class, the wind directions during calm conditions were assumed to be distributed in proportion to the observed wind direction distribution of the lowest non-calm wind speed class.

B.1.2 Joint Frequency Distribution The data for a particular historical period are summarized by developing a joint frequency distribution (JFD). Each such distribution specifies the fraction of time during the historical period that the following jointly occur:

• Wind speed within a particular range (wind speed class).

• Downwind direction in one of the 16 sectors corresponding to the 16 principal compass directions (N, NNE, etc.).

• Atmospheric conditions corresponding to one of the seven atmospheric stability classes discussed in Section B.1. Table B-1 of this appendix displays a portion of an example JFD.

Different JFDs are associated with the different release classifications defined in Section 4.1.4. One JFD is defined for stack releases, and another JFD is defined for ground level releases. Two JFDs are associated with vent (mixed mode) releases, one for the portion of the time the release is treated as elevated and the other for the portion of the time the release is treated as ground level.

B.1.2.1 Downwind Direction Versus Upwind Direction Unless otherwise noted, any reference to wind direction in this document represents downwind direction, i.e., the direction in which the wind is blowing toward. This is because the parameters developed in this document are used to calculate radioactivity concentration and radiation dose downwind of a release point. In contrast, it is conventional for meteorologists to provide JFDs based on upwind direction, the direction from which the wind is blowing. For example, the JFDs presented in the annual operating reports of the nuclear power stations are obtained from a meteorological contractor and the directions specified in the reports are upwind directions. Users of JFDs should always be careful to ascertain whether the directions specified are upwind or downwind.

Appendix B B-2 0212210641

Revision 3 January 2002 B.1.2.2 Stack JFD For a stack release, the JFD is defined as follows:

5sf(n,O,c) Joint Frequency Distribution, Stack Release The fraction of hours during a period of observation that all of the following hold:

• The average wind speed is within wind speed class n.

• The downwind direction is within the sector denoted by 0.

• The atmospheric stability class is c.

This function is defined for application to a stack release point (see Section 4.1.4). Its value is based on hourly average wind data obtained at a height representative of the release point height.

The stack JFD is normalized to 1:

I fs(nOc) = 1 (B-1)

The summation is over all wind speed classes n, all compass direction sectors 0, and all stability classes C.

B.1.2.3 Ground Level JFD For a ground level release, the JFD f,(n, 0,c) is defined in the same way as for a stack release except that the wind data are obtained at a height representative of a ground level release point. This height is taken as about 10 meters.

The ground level JFD is normalized to 1:

I f,(n,O,c) = 1 (B-2)

The summation is over all wind speed classes n, all compass direction sectors, and all stability classes c.

B.1.2.4 Vent JFDs In accordance with the approach recommended in Regulatory Guide 1.111 (Reference 7), the plume from a vent release is treated as elevated part of the time and as ground level the rest of the time. Two JFDs are determined:

• fv,elev(n,O,c) characterizes the plume during the part of the time that it is considered elevated;

• fvgnd(n,O,c) characterizes the plume during the part of the time that it is considered ground level.

Their definitions are as follows:

fvelev(n,O,c) Joint Frequency Distribution, Elevated Portion of a Vent Release Appendix B B-3 0212210641

Revision 3 January 2002 The fraction of hours during a period of observation that the plume is considered elevated and that all of the following hold:

• The average wind speed is within wind speed class n.

• The downwind direction is within the sector denoted by 0.

• The atmospheric stability class is c.

fvgnd(nO,c) Joint Frequency Distribution, Ground Level Portion of a Vent Release The fraction of hours during a period of observation that the plume is considered ground level and that all of the following hold:

• The average wind speed is within wind speed class n.

• The downwind direction is within the sector denoted by e.

• The atmospheric stability class is c.

The value of fvelev(n 0,c) is based on hourly average wind data at a height representative of the vent release point. Where the measurement height differed considerably from the release height, wind speed data for the release height was obtained by extrapolation. The value of fvsgnd(n, Oc) is based on hourly average wind data obtained at a height representative of a ground level release point. This is taken as about 10 meters.

The sum of these two JFDs is normalized to 1:

Xf fvelev(n, Bc) + fvgnd(n, 0,c) I = 1 (B-3)

The summation is over all wind speed classes n, all compass direction sectors C.

0, and all stability classes The prescription of Regulatory Guide 1.111 is used in determining the fraction of considered elevated and the fraction of time that it is considered ground level. time that the plume is from the ratio of stack exit velocity WO to hourly average wind speed u at the The fractions are obtained height of the vent release point as follows:

-If Wo/u > 5, then the plume is considered elevated for the hour.

• If Wo/u < 1, then the plume is considered ground level for the hour.

• if 1 < WOIu < 5, the plume is considered to be a ground level release for a fraction Gt of the hour and an elevated release for a fraction (1 - Gt) of the hour where Gt is defined as follows:

Gt = 2.58 - 1.58(Wo/u) for 1.0 < Wo/U 5 1.5 (B4)

Gt = 0.30 - 0.06(WO/u) for 1.5 < Wo/u 5 5.0 (B-5)

B.1.3 Average Wind Speed Using the joint frequency distribution, average wind speeds are obtained for each station. Values are obtained for each downwind direction (N, NNE, etc.) and for various release point vent, and ground level). classifications (stack, Appendix B B-4 0212210641

Revision 3 January 2002 B.1.3.1 Stack Release For a stack release, the following formula is used:

u5 (O)= X{ fs(n, G,c)un 1}£{ fs(n, O,c) }

(B-6) where the summations are over wind speed classes n and stability classes c.

Us(0) Average Wind Speed, Stack Release fm/sec]

The average wind speed in downwind direction e for a stack release.

Un Wind Speed for Class n [m/sec]

A wind speed representative of wind speed class n. For each wind speed class except the highest, un is the average of the upper and lower limits of the wind speed range for the class. For the highest wind speed class, un is the lower limit of the wind speed range for the class.

The parameter f. is defined in Section B.1.2.2.

B.1.3.2 Ground Level Release For a ground level release, the following formula is used:

u g (O) = I{ fg(n, O,c)un }/I{ fg(n, O,c) I (B-7) where the summations are over wind speed classes n and stability classes c.

u g (O) Average Wind Speed, Ground Level Release [m/sec]

The average wind speed in downwind direction 8 for a ground level release.

The parameter fg is defined in Section B.1.2.3.

B.1.3.3 Vent Release For a vent release, the following formula is used:

Uv(O) = I [fv,elev(n, Oc) + fvgnd(n, O,c)]un )

(B-8)

/ i{ fvelev(nOC) + fvgnd(nOc) where the summations are over wind speed classes n and stability classes c.

uv(O) Average Wind Speed, Vent [m/sec]

Release The average wind speed in downwind direction 8 for a vent release.

The parameters fvelev and fvgnd are defined in Section B.1.2.4.

Appendix B B-5 0212210641

Revision 3 January 2002 B.2 GAUSSIAN PLUME MODELS As a plume of airborne effluents moves away from an elevated release point, the plume both and meanders. It has been found that the time-averaged distribution of material in an effluentbroadens plume can be well represented mathematically by a Gaussian function.

B.2.1 Mathematical Representation In a widely used form of the Gaussian plume model, the distribution of radioactivity in a plume is represented mathematically by the equation below:

X(xyz) = [Q/(2n cy ozu)]exP(-y 2/2<3 2 y) x {exp[-(z-he) 2/2cF 2 z] + eXP['(Z+he) 2/2c0 2Z1} (B-9)

X(X,Y,Z) Radioactivity Concentration [PCLm 3 The concentration of radioactivity at point (x,y,z). The x, y, and z axis are defined as follows:

x Downwind Distance [m]

Distance from the stack along an axis parallel to the wind direction.

y Crosswind Distance [m]

Distance from the plume centerline along an axis parallel to the crosswind direction.

z Vertical Distance [m]

Distance from the ground (grade level at the stack) along an axis parallel to the vertical direction.

Q Release Rate [piCVsec]

Release rate of radioactivity.

sy, CFz Horizontal and Vertical Dispersion Coefficients [ml Standard deviations of the Gaussian distributions describing the plume cross-sections in the y and z directions, respectively. The values of ay and az depend on several parameters:

• Downwind distance x.

Because a plume broadens and meanders as it travels away from its release point, the values of ay and cz increase as x increases.

• Atmospheric stability class.

The plume is broadest for extremely unstable atmospheric conditions (Class A) and narrowest for extremely stable conditions (Class G).

• Time period of averaging plume concentration.

Appendix B B-6 0212210641

Revision 3 January 2002 The values of cy and oz increase as the averaging period increases.

u Average Wind Speed [m/sec]

The average wind speed. The average speed of travel of the plume in the x direction.

he Effective Release Height [i]

The effective height of effluent release above grade elevation.

This may be greater than the actual release height (see Section B.3.1.1.1).

The two exponential functions of z in the curly brackets of Equation 8-9 represent the emitted and reflected components of the plume. The reflected component (represented by the exponential with (z +

he) in its argument) arises from the assumption that all material in a portion of the plume that touches' ground is reflected upward. This assumption isconservative if one is calculating airborne radioactivity concentration.

B.2.2 Sector-Averaged Concentration Sometimes, it is desired to determine the average concentration of radioactivity in a sector due to release at a constant rate over an extended period of time (e.g., a year). For such a case, it is reasonable to assume that the wind blows with equal likelihood toward all directions within the sector. From Equation B-9, the following equation for ground level radioactivity concentration can be derived:

Xsector = [2.032 f Q/1(z u x)]exp(-h2 e/2cr 2 z) (B-10)

Xsector Sector-Averaged Ground Level [pCim 3]

Concentration The time-averaged concentration of airborne radioactivity in a sector at ground level at a distance x from the release point.

2.032 A dimensionless constant.

f Sector Fraction The fraction of time that the wind blows into the sector.

Q Release rate of radioactivity. [pC sec]

The other parameter definitions are the same as for Equation B-9.

B.3 RELATIVE CONCENTRATION FACTOR X/O The relative concentration factor X/0 (called 'chi over 0") provides a simplified method of calculating the radioactivity concentration at a given point in an effluent plume when the release rate is known:

X = Q (X/Q) (B-11)

X Concentration of Radioactivity [pCi/rm3]

Concentration of radioactivity at point (x,y,z) in the atmosphere.

Appendix B B3-7 0212210641

Revision 3 January 2002 a Release Rate [plCVsec]

Release rate of radioactivity.

XiQ Relative Concentration Factor [sec/m 3 ]

Relative concentration factor for point (x,y,z). The airborne radioactivity concentration at (xy,z) per unit release rate.

Expressions for X/Q based on Gaussian plume models can be obtained from the equations for concentration X in Section B.2 simply by dividing both sides of each equation by the release rate Q. For example, from Equation B-1 0, we obtain the following expression for the sector-averaged X/Q:

(XWecto/Q) = [2.032 I(crz u x)]exp(-h2 eI2a 2 z) (B-12)

The values of XIQ used in ODCM calculations are both sector-averaged and time-averaged. The time averaging is based on the historical average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is accomplished by use of the joint frequency distribution discussed in Section B.1.2. The formulas used to obtain the time- and sector-averaged X/Q are based on Equation B-12, but vary depending on whether the release is a stack, ground level, or vent release. The three cases are discussed below.

B.3.1 Stack Release For a stack release, the relative concentration factor is designated (x/Q)s. Its value is obtained by the following formula:

(x/Q)s = (2.032/R) £{ fs(n,O,c) x [exp (-h2 e2cr2 z)]I(un cz) I (B-13)

The summation is over wind speed classes n and atmospheric stability classes c.

(xIQ)s Relative Concentration Factor, [sec/m 3 ]

Stack Release The time- and sector-averaged relative concentration factor due to a stack release for a point at ground level at distance R in downwind direction 0.

2.032 Constant A dimensionless constant.

R Downwind Distance [m]

The downwind distance from the release point to the point of interest.

f,(n,6,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2.

he Effective Release Height [m]

Appendix B B-8 0212210641

Revision 3 January 2002 The effective height of an effluent release above grade elevation. For a stack release, he is obtained by correcting the actual height of the release point for plume rise, terrain effects, and downwash as described in Section B.3.1.1, below.

CZ Standard Vertical Dispersion Coefficient [m]

A coefficient characterizing vertical plume spread in the Gaussian model for stability class c at distance R (see Table C-5 of Appendix C).

Un Wind Speed [m/sec]

A wind speed representative of wind speed class n. For each wind speed except the highest, un is the average of the upper and lower limits of the class wind speed range for the class. For the highest wind speed class, un is the lower limit of the wind speed range for the class.

This expression is recommended by the NRC in Regulatory Guide 1.111 (Reference model designated there as the constant mean wind direction model." In this 7) and is based on a mean wind speed, the mean wind direction, and the atmospheric stability class model it is assumed that the point also apply at all points within the region in which airborne concentration determined at the release is being evaluated.

B.3.1.1 Effective Release Height For a stack release, the effective height of an effluent plume is the height of the release point corrected for plume rise and terrain effects:

If (hs + hpr - ht) < 100 meters, then he = hs + hpr- ht (B-14)

If (hs + hpr - ht) > 100 meters, then;

-he = 100 meters (B-15) he Effective Release Height [m]

The effective height of an effluent release above grade elevation.

hs Actual Release Height [m]

The actual height of the release above grade elevation.

hpr Plume Rise [ml The rise of the plume due to its momentum and buoyancy.

(See Section B.3.1.1.1.)

ht Terrain Correction Parameter [m]

A parameter to account for the effect of terrain elevation on the effective height of a plume. Taken as zero (see Section B.3.1.1.2).

Aappendix B B-9 0212210641

Revision 3 January 2002 B.3.1.1.1 Plume Rise Because nuclear power stations generally have plumes that are not significantly warmer than temperature, plume rise due to buoyancy is neglected. The formulas used to calculate plume room rise due to momentum are given below.

Stability Classes A, B, C, and D For these stability classes (corresponding to unstable and neutral conditions), hpr is taken as the lesser of two quantities:

hpr = Minimum of [(hpr)i, (hpr)21 (B-16)

(hpr)I = (1.44)(Wo/u) 2 13 (R/d)l/3(d) - hd (B-17)

(hpr2 = (3)(Wolu)(d) (1-18)

WO Stack Exit Velocity [m/sec]

The effluent stream velocity at the discharge point.

u Wind Speed [m/sec]

R Downwind Distance [ml The downwind distance from the release point to the point of interest.

d Internal Stack Diameter [ml The internal diameter of the stack from which the effluent is released.

hd Downwash Correction [m]

A parameter to account for downwash at low exit velocities.

The parameter hd is calculated by the following equations:

hd = (3)(1.5 - WO/u)(d) if Wo<1.5u (B-19) hd = 0 if WO>1.5u (B-20)

Note that (hpr)i can increase without limit as R increases; thus, the effect of (hpr)2 is to limit calculated plume rise at large distances from the nuclear power station.

Stability Classes E, F, and G For these stability classes (corresponding to stable conditions), hpr is taken as the minimum of four quantities:

hpr = Minimum of [(hpr)i, (hpr)2, (hpr)3, (hpr)4] (B-21)

(hpr)3 = (4)(F/S) 114 (B-22)

(hpr)4 = (1.5)(F/u) 1/ 3 (S)i 1 l6 (B-23)

Appendix B B-10 0212210641

Revision 3 January 2002 F Momentum Flux Parameter [m4 /sec 2 ]

A parameter defined as:

F = W0 2 (d/2)2 (B-24)

S Stability Parameter [1/sec2 ]

A parameter defined as follows:

Stability Class S E 8.70E-4 F 1.75E-3 G 2.45E-3 The quantities (hpr)l and (hpr)2 are as defined by Equations B-1 7 and B-18.

B.3.1.1.2 Terrain Effects Due to general flatness of the terrain in the vicinity of the stations, the terrain correction parameter ht was taken as zero in all calculations of meteorological dispersion and dose parameters for this Manual.

B.3.2 Ground Level Release For a ground level release, the relative concentration factor is designated (XIQ)g. Its value is obtained by the following formula:

(xIQ)g = (2.032IR) If fg(ncC)/(unSz) I (B-25)

The summation is over wind speed classes n and atmospheric stability classes c.

(X/Q)g Relative Concentration Factor, Ground Level Release [sec/m 3 ]

The time- and sector-averaged relative concentration factor due to a ground level release for a point at ground level at distance R in downwind direction 8.

fg(n,O,c) Joint Frequency Distribution, Ground Level Release This function is defined in Section B.1.2.3.

Sz Wake-Corrected Vertical Dispersion Coefficient [m]

The vertical dispersion coefficient corrected for building wake effects. The correction is made as described below.

The remaining parameters are defined in Section B.3.1.

Wake-Corrected Vertical Dispersion Coefficient Appendix B B-l1 0212210641

Revision 3 January 2002 The wake-corrected vertical dispersion coefficient Sz in Equation B-25 is taken as the lesser of two quantities:

Sz = Minimum of [(Sz)i, (Sz)2 ] (B-26)

(SZ)1 = [a2z + D2/(2n)]"2 (B-27)

(SZ)2 (crz)(3" 2 ) (B-28)

SZ Wake-Corrected Vertical Dispersion Coefficient [m]

The vertical dispersion coefficient corrected for building wake effects.

Uz Standard Vertical Dispersion Coefficient [ml The coefficient characterizing vertical plume spread in the Gaussian model for stability class c at distance R (see Table C-5 of Appendix C).

D Maximum Height of Neighboring Structure [m]

The maximum height of any neighboring structure causing building wake effects (see Table F-2 of Appendix F).

B.3.3 Vent Release For a vent release, the relative concentration factor is designated (X/Q)v. Its value is obtained by the following formula:

(XIQ)v = (2.032/R) 1{ fvelev(nOc) (B-29) x [exp(-h 2e/202z)]/(un 9z)

+ fvgnd(noOsc)I(unSz) }

The summation is over wind speed classes n and atmospheric stability classes c.

(X/Q)v Relative Concentration [sec/m 3 ]

Factor, Vent Release The time and sector averaged relative concentration factor due to a vent release for a point at ground level at distance R in downwind direction 0.

The parameters fvelev(nOc) and fvgnd(nfoc) are defined in Section B.1.2.4. The parameter Sz is defined in Section B.3.2. The remaining parameters are defined in Section B.3.1.

B.3.4 Removal Mechanisms In Regulatory Guide 1.1 11, the NRC allows various removal mechanisms to be considered in evaluating the radiological impact of airborne effluents. These include radioactive decay, dry deposition, wet deposition, and deposition over water. For simplicity, these removal mechanisms cited by the NRC are not accounted for in the evaluation or use of X/O in this manual. This represents a conservative approximation as ignoring removal mechanisms increases the value of X/Q.

Appendix B B-12 0212210641

Revision 3 January 2002 B.3.5 Gamma-X/Q The noble gas dose factors of Reg. Guide 1.109, Table B-1 are based upon semi-infinite cloud. For ground level and mixed mode releases this tends assumption of immersion in a to overestimate the gamma air dose arising from a plume that is actually finite in nature.

For elevated releases, the Reg. Guide 1.109 noble gas dose factors will underestimate consider only immersion and not that portion of exposure arising from sky exposure as they shine. At distances close in to the point of elevated release, the ground level concentration as predicted by X/O In such a case, the sky shine component of the exposure becomes significant will be essentially zero.

and must be considered.

The gamma-XIQ provides a simplified method of calculating gamma air dose and/or elevated plume. The methodology of Reg. Guide 1.109, Section C.2 and dose rates for a finite and Appendix B provides the methodology for calculating finite cloud gamma air dose factors from which the gamma-X/Q values can be derived. Section B.5 addresses the calculation of these dose factors.

The gamma-X/Q is defined such that for a given finite cloud the semi-infinite cloud methodology will yield the same gamma air dose as the finite cloud methodology.

Three gamma-X/Q values are defined: (X/Q)S', (X/Q)V" and (XIQ)9g for stack, vent and ground level releases, respectively. These gamma-X/Q values are calculated as follows:

For stack releases:

X/Q).Y = ,; (B-30)

The summation is over all noble gas radionuclides i.

(/Q). Gamma-i/Q for Stack Releases [sec/m3]

fi Noble Gas Nuclide Fraction dimensionless Fraction of total noble gas release that is due to radionuclide i. Values for f1 are listed in Table B-0.

Si Stack Release Gamma Air Dose Factor [(mrad/yr)/(ltCi/sec)]

Gamma air dose factor for radionuclide i for stack releases as defined in Section B.5.1. Taken from Appendix F, Table 7.

ml Semi-Infinite Cloud Dose Factor [(mrad/yr)/(glCVm 3 )]

Dose factor for immersion exposure to a semi-infinite cloud of noble gas.

Taken from Reg. Guide 1.109, Table B-1, Col 4. (Note that the units in Reg. Guide 1.109 must be multiplied by 1E6 to convert pCi to gCi.)

For vent releases:

Ef V,

= I

-X/Q)r (B-31)

Appendix B B-13 0212210641

Revision 3 January 2002 The summation is over all noble gas radionuclides i.

WaQ)Y Gamma-VQ for Vent Releases [sec/m3]

VI Vent Release Gamma Air Dose Factor [(mrad/yr)/(.tCisec)]

Gamma air dose factor for radionuclide I for stack releases as defined in Section B.5.3. Taken from Appendix F, Table 7.

All other terms have been previously defined.

For ground level releases:

Xf 1 Gs (B-32)

The summation is over all noble gas radionuclides i.

WQ)Y Gamma-lQ for Ground Releases [sec/m3]

Gi Ground Level Release Gamma Air Dose Factor [(mrad/yr)/(glCisec)]

Gamma air dose factor for radionuclide i for ground level releases as defined in Section B.5.2. Taken from Appendix F, Table 7.

All other terms have been previously defined.

The Noble Gas Nuclide Fraction, f, is determined from historical release data and defined as:

f= Al (B-33)

EA, The summation is over all noble gas radionuclides i.

A, Cumulative Radionuclide Release units of activity Cumulative release of noble gas radionuclide i over a period of time.

B.4 RELATIVE DEPOSITION FACTOR DIQ The quantity DIQ (called OD over Q") is defined to provide the following simple way of calculating of deposition of radioactivity at a given point on the ground when the release rate is known. the rate d = a (DIQ) (B-34) d Deposition Rate [(pCim 2 )/sec]

Rate of deposition of radioactivity at a specified point on the ground.

0 Release Rate of radioactivity. [pCi/sec]

Appendix B B-14 0212210641

Revision 3 January 2002 DIQ Relative Deposition Factor [1/m 2 ]

Relative deposition factor for a specified point on the ground. The deposition rate per unit release rate.

The values of D/I used in this manual are time-averaged. The time averaging is based on the historical average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is accomplished by use of the joint frequency distribution described in Section B.1.2. The formulas used to obtain D/I vary depending on whether the release is a stack, ground level, or vent release. The three cases are discussed below.

B.4.1 Stack Release For a stack release, the relative deposition factor is designated (DIQ)s. Its value is obtained by the following formula:

(D/Q)s = [1/(2inRI16)] I{f 5 (n,O,c) Dr(c,R,he) I (B-35)

The summation is over wind speed classes n and stability classes c.

(D/I)s Relative Deposition Factor, Stack Release [l/m2 ]

The time-averaged relative deposition factor due to a stack release for a point at distance R in the direction 0.

2id16 Sector Width [radians]

The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section B.2.2). Taken as 1/16 of a circle.

R Downwind Distance [ml The downwind distance from the release point to the point of interest.

f5 (n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2.

Dr(CRhe) Relative Deposition Rate, Stack Release [m-1 ]

The deposition rate per unit downwind distance [,pCV(sec-m)] divided by the source strength [pCiisec] due to a stack release for stability class c, downwind distance R, and effective release height he.

The value is based on Figures 7 to 9 of Regulatory Guide 1.1 11, which apply, respectively, to release heights of 30, 60, and 100 m. Linear interpolation is used to obtain values at intermediate release heights. If the effective release height is greater than 100 meters, then the data for 100 meters are used.

he Effective Release Height [ml Appendix B B-15 0212210641

Revision 3 January 2002 The effective height of the release above grade elevation.

See Section B.3.1.1.

B.4.2 Ground Level Release For ground level release, the relative deposition factor is designated (D/Q),. Its value is obtained by the following formula:

(D/Q)g = [1/(2nR/1 6)] D,(R) X{ f 9(n,e,c) }

(B-36)

The summation is over wind speed classes n and stability classes c.

(D/Q)g Relative Deposition Factor, [1/m 2 J Ground Level Release The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction 0.

fg (n,O,c) Joint Frequency Distribution, Ground Level Release This function is defined in Section B.1.2.3.

Dr(R) Relative Deposition Rate, Ground Level The deposition rate per unit downwind distance [pCi/(sec-m)] divided by the source strength [pCVsec] due to a ground level release for downwind distance R. The value is taken from Figure 6 of Regulatory Guide 1.111 and is the same for all atmospheric stability classes.

The remaining parameters are defined in Section B.4.1.

B.4.3 Vent Release For a vent release, the relative deposition factor is designated (DIQ)v. Its value is obtained by the following formula:

(D/Q)v = [1I(2nRI1 6)] x [M{ fvelev(noc) Dr(CRhe) } + Dr(R) 1{ fvgnd(n,0,c) }]

(B-37)

The summation is over wind speed classes n and stability classes c.

(D/Q)v Relative Deposition Factor, Vent Release [1/m 2 ]

The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction 0.

The parameters fvelev(nGc) and fvsgnd(noc) are defined in Section B.1.2.4. The remaining parameters are defined in Sections B.4.1 and B.4.2.

Appendix B B-16 0212210641

Revision 3 January 2002 B.5 GAMMA AIR DOSE FACTORS (Si, Vi, GI)

The gamma air dose factors provide a simple way of calculating doses and dose rates to air due to gamma radiation. For example, using a dose factor DFI, gamma air dose rate may be calculated as follows:

D = :Di (B-38)

Di =Z{QiDFi (B-39)

The summations are over i radionuclides.

D Gamma Air Dose Rate [mrad/yr]

The gamma air dose rate due to all radionuclides released.

Gamma Air Dose Rate Due to Radionuclide i [mrad/yr]

Q. Release Rate of Radionuclide i [IpClsec]

DFI Gamma Air Dose Factor for [(mrad/yr)/ (pCi/sec)]

Radionuclide i A factor used to calculate gamma air dose or dose rate due to release of radionuclide i. Gamma air dose rate at a particular location per unit release rate.

Three gamma air dose factors are defined: Si, Vi, and GI. They are used for stack, vent, and ground level releases, respectively. These three release point classifications are defined in Section 4.1.4. The calculation of the three dose factors is discussed below.

B.5.1 Stack Release For a stack release, the gamma air dose factor SI is obtained by a model similar to that of Equation 6 of Regulatory Guide 1.109 (Reference 6). A sector-averaged Gaussian plume is assumed and the dose factor is evaluated on the basis of historical average atmospheric conditions. The value of S. depends on distance R from the release point and on downwind sector 0.

The following equation is used:

S. = [260I(27cR/1 6)] x X{f.(n,d,c)[exp(-4.R/3600un)] xEk IJS(Ek)AKI I(heUnCazEk)Yun (B-40)

The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k.

S. Gamma Air Dose Factor, Stack Release [(mrad/yr)l (pOCLsec)]

The gamma air dose factor at ground level for a stack release for radionuclide i, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period.

Appendix B B-17 0212210641

Revision 3 January 2002 260 Conversion factor [(mrad-radians-m 3 -disintegrations)/(sec-MeV-Ci)]

Reconciles units of Equation B-36.

27t 6 Sector Width [radians]

The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section B.2.2). Taken as 1/16 of a circle.

f,(n,O,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2.

Radiological Decay Constant [hrl]

Radiological Decay Constant for radionuclide i (see Table C-7 of Appendix C).

3600 Conversion Factor [sec/hr]

The number of seconds per hour. Used to convert wind speed in meters/sec to meters/hr.

Ek Photon Group Energy [MeV/photon]

An energy representative of photon energy group k. The photons emitted by each radionuclide are grouped into energy groups in order to facilitate analysis. All photons with energy in energy group k are assumed to have energy Ek-lJa(Ek) Air Energy Absorption Coefficient fm-1 ]

The linear energy absorption coefficient for air for photon energy group k. The fraction of energy absorbed in air per unit of distance traveled for a beam of photons of energy Ek. Distance is measured In units of linear thickness (meters).

AM Effective Photon Yield [photons/disintegration]

The effective number of photons emitted with energy in energy group k per decay of nuclide I. On the basis of Section B.1 of Regulatory Guide 1.109 (Reference 6), the parameter AkM is calculated as follows:

AkM = [Y{Am Em IJa(Em))]/[Ek pa(Ek)] (B41)

The summation in the numerator is over the index m.

Am True Photon Yield [photons per disintegration]

The actual number of photons emitted with energy Em per decay of nuclide i.

Appendix B B-18 0212210641

Revision 3 I January 2002 Em Photon Energy

[MeV/photon]

The energy of the mr] photon within photon energy group k.

lJa(Em) Air Energy Absorption Coefficient [rm-]

The linear energy absorption coefficient for air for photon energy Em.

I(. I Function A dimensionless parameter obtained by numerical evaluation of integrals that arise in the plume gamma dose problem. The value of I depends on the arguments (...) listed in Equation B-40. A specific definition for I is given by Equation F-13 of Regulatory Guide 1.109.

The integrals involved in calculating I arise from conceptually dividing up the radioactive plume into small elements of radioactivity and adding up the doses produced at the point of interest by all of the small elements.

The distribution of radioactivity in the plume is represented by a sector-averaged Gaussian plume model like that discussed in Section B.2.2.

The parameters R, he, un, and qz are defined in Section B.3.1.

B.5.2 Ground Level Release The gamma air dose factor Gi for a ground level release is defined as follows:

Gi Gamma Air Dose Factor, Ground Level Release [(mrad/yr)/(VCifsec)]

The gamma air dose factor at ground level for a ground level release for radionuclide i, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period.

The value of G, is obtained by the same equation as used for a stack release, Equation B.5.1, with the following modifications: B-36 of Section

• The joint frequency distribution for a ground level release (f. of Section B.1.2.3) is used in place of the one for a stack release (fe).

• In evaluating the I function, the effective release height h. is taken as zero.

This corresponds to use of a finite plume model.

B.5.3 Vent Release For a vent release, the gamma air dose factor is calculated as follows:

VI = [260I(2nR/1 6)] X {fv,eev(lnOc)[exp(-.iR/36OOun)] x AkiEkPa(Ek) l(heUnCjcazEk)/un (B-42)

+ fv,gnd(nOc)[exp(-AR/36OOUn)] X AkdEkp,(Ek) l(OUnCGzEk)/Ur}

The summation is over wind speed classes n, atmospheric stability classes c, and photon k.

group indices Appendix B B-19 0212210641

Revision 3 January 2002 VI Gamma Air Dose Factor, Vent Release [(mrad/yr)/(pCi/sec)]

The gamma air dose factor at ground level for a vent release for radionuclide i, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period.

The parameters fveiev(n,Oc) and fv,gnd(nf0,c) are defined in Section 8.1.2.4. The parameter cyz is defined in Section 8.3.2. The remaining parameters are discussed in Section B.5.1.

B.6 Gamma Total Body Dose Conversion Factor (K,)

The gamma total body dose conversion factors (K3) are used to calculate doses and dose rates due to gamma irradiation of the whole body. The gamma total body dose conversion factors are taken from Reg.

Guide 1.109, Table B1-, Column 5. The gamma total body dose conversion factors in Table B-1 of Reg.

Guide 1.109 are based upon the semi-infinite cloud model.

B.7 BETA AIR AND BETA SKIN DOSE CONVERSION FACTORS (NI,Li)

The beta air (Ni) and beta skin (Li) dose conversion factors are used to calculate doses and dose rates due to noble gas beta exposure. The beta air dose conversion factors are taken from Reg, Guide 1.109, Table B-1, Column 2. The beta skin dose conversion factors are taken from Column 5 of that same table.

The values are based on a semi-infinite cloud model.

B.8 GROUND PLANE DOSE CONVERSION FACTOR DFG, The ground plane dose conversion factor DFG, is used to calculate dose due to standing on ground contaminated with radionuclide i (see Equation A-8 of Appendix A). The units of DFG, are (mrem/hr) per 2

(pCi/M ).

Values are provided (see Table C-10 of Appendix C) for dose to the whole body. The values are taken from Regulatory Guide 1.109 and are based on a model that assumes a uniformly contaminated ground plane.

B.9 INHALATION DOSE COMMITMENT FACTOR DFAJS The inhalation dose commitment factor DFAj,, is used to calculate dose and dose rate to organ j of an individual of age group a due to inhalation of radionuclide i (see Equations A-7 and A-9 of Appendix A).

Values of DFAija for 10CFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFAIja are mrem per pCi inhaled. Values are provided for seven organs, with the whole body considered as an organ (see Tables E-7, E-8, E-9 and E-10 in Reg. Guide 1.109).

B.10 INGESTION DOSE COMMITMENT FACTOR DFLija The ingestion dose commitment factor DFL,,a is used to calculate dose to organ j of an individual of age group a due to ingestion of radionuclide i (see Equations A-7 and Al0 through A20 of Appendix A).

Values of DFLija for 10CFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFLija are mrem per pCi ingested. In Tables E-11, E-12, E-13 and E-14 of Reg. Guide 1.109, values are provided for seven organs, with the whole body considered as an organ.

Appendix B B-20 0212210641

Revision 3 January 2002 B.11 MEASURED RELEASE PARAMETERS Input parameters required for calculations of dose or dose rate due to airborne effluents include measured values of radioactivity release (Ak-, A,,, and A-,) or release rate (01,, Q,,,and Q,9) (see Section A.1 of Appendix A). These are obtained per the nuclear power station procedures.

B.12 RADIOLOGICAL DECAY CONSTANTS Values used for these are obtained from the literature and are specified in Table C-7 of Appendix C.

B.13 PRODUCTION/EXPOSURE PARAMETERS These parameters characterize various aspects of agricultural production and human exposure. Values used for generic (site-independent) parameters are specified in Appendix C.

Values of site-specific parameters are given in Appendix F. Many of the values are based on Reg. Guide 1.109, while others are based on site-specific considerations.

Appendix B B-21 0212210641

Revision 3 January 2002 SECTION 2:

MODELS AND PARAMETERS FOR LIQUID EFFLUENT CALCULATIONS B.14 INTRODUCTION Equations for radiation dose and radioactivity concentration due to liquid effluents are given in Section A.2 of Appendix A. The equations involve the following types of parameters:

• Flow and Dilution Parameters.

• Dose Factors.

• Measured Release Parameters.

• Transport/Consumption Parameters.

This section discusses the methodology used to determine these parameters. Section B.15 addresses dose calculations and Section B.1 6 addresses concentration calculations for tank discharges. For dose calculations, flow and dilution parameters are discussed for two different models; the River Model, which is used for all nuclear power stations except Zion, and the Lake Michigan Model, which is used for Zion.

B.1 5 DOSE B.15.1 Drinking Water The radiation dose due to consumption of drinking water containing released radioactivity is calculated by Equations A-17, A-18 and A-19 of Appendix A:

DLq = F At AajpjCi (A-17) p I F= Waste Flow Dilution FlowxZ ai(PW)I = k{. U .}D (A-19)

The summation is over index i (radionuclides) and p (pathways). The parameters are defined in Section A.2.1 of Appendix A.

This methodology addresses the following considerations:

• The duration of the release, At.

• The concentration of the activity released, C,.

• The dilution that takes place in the environment is represented by the parameters F and Z.

• Receptor consumption rate, UaW.

• Dilution which occurs from the near field discharge area to potable water intake as represented by Dw.

• The dose commitment per unit of ingested radioactivity is DFLa,.

B.15.2 Aquatic Foods (Fish)

Near the nuclear power stations, the only aquatic food of significance for human consumption is fish. The liquid dose due to consumption of fish containing released radioactivity is calculated by Equations A-17, A-1 8 and A-20 of Appendix A.

Appendix B B-22 0212210641

Revision 3 January 2002 Aai(Fih)j = koUFBFiDFL.rj (A-20)

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

This is similar to the methodolgy used for calculating the dose due to drinking water except for the addition of the bioaccumulation factor, BF1 . This factor is the equilibrium ratio of the concentration of radionuclide i in fish (pCi/kg) to its concentration in water (pCVL). It accounts for the fact that radioactivity ingested by fish can accumulate in their bodies to a higher concentration than in the waters in which the fish live.

B.15.3 Parameters B.15.3.1 Flow and Dilution The values of dilution can differ for potable water and fish. The dilution for potable water will depends on where water is drawn, while that for fish will depends on where the fish are caught. Models used to determine these parameters are discussed below. The values used for each station are summarized in Table F-1 of Appendix F.

B.15.3.1.1 River Model For the purpose of calculating the drinking water dose from liquid effluents discharged into a river, it is assumed that total dilution of the discharge in the river flow occurs prior to consumption. The measure of dilution for the potable water pathway is described by the parameter Dw. A value of DW = 1 represents no dilution.

For the fish consumption pathway, the dilution in the near-field is described by the parameter Z. This is an estimate of the dilution of released radioactivity in the water consumed by fish caught near the station downstream of its discharge. No additional dilution is assumed to occur.

B.15.3.1.2 Lake Michigan Model Only (Zion) discharges liquid effluents into Lake Michigan. For this nuclear power station, it is assumed that the dilution in the near-field (Z) is dictated by the initial entrainment dilution is a factor of 10. The potable water pathway dilution factor of 6 (DW) is derived from the plume dilution (a factor of 3 over approximately 1 mile) and the current direction frequency (annual average factor of 2).

B.15.3.2 Dose Factors Equations A-17 through A-20 of Appendix A determine dose due to ingested radioactivity using the same ingestion dose factor DFLija as used in the evaluation of airborne radioactivity which is ingested with foods. The units of DFLIja are:

(mrem) per (pCi ingested)

For 10CFR50 Appendix I compliance, the data of Tables E-1, E-12, E-13 and E-14 of Reg. Guide 1.109, are used for four age groups and for seven organs, with the whole body considered as an organ.

B.1 5.3.3 Measured Releases Calculations of dose due to liquid effluents require measured values of radioactivity concentration release (Ca) for input. These release values are obtained per the nuclear power station procedures.

Appendix B B3-23 0212210641

Revision 3 January 2002 B.1 5.3.4 Consumption Equations A-1 9 and A-20 of Appendix A involve consumption rates for water and fish (UW and Ua,). The values used are specified for each nuclear power station in Table F-1 of Appendix F.

B.16 CONCENTRATION IN TANK DISCHARGES The concentration of radioactivity in a release to the unrestricted area due to a tank discharge is calculated by Equation A-22 of Appendix A:

Waste Flow C I Dilution Flow (A-22)

The parameters are defined in Section A.2.3 of Appendix A.

The radioactivity concentration released from the tank (Ct1 at flow rate Fr) is diluted by mixing with the initial dilution stream (with flow rate Fd) to yield a lower concentration (C,) in the combined streams.

Appendix B B-24 0212210641

Revision 3 January 2002 Table B-O Noble Gas Nuclide Fractions Nuclide Braidwood' Byron' Dresdenz LaSalle QuadCitiese Zion' Ar-41 8.90E-01 8.90E-01 1.46E-02 O.OOE+0O 1.85E-02 O.OOE+00 Kr-83m O.OOE+00 O.OOE+O0 O.OOE+OO 4.50E-03 O.OOE+00 O.OOE+00 Kr-85 2.49E+01 2.49E+01 3.50E-05 2.60E-05 3.11 E-02 1.OOE+00 Kr-85m 1.80E-01 1.80E-01 3.68E-02 8.OOE-03 2.39E-02 O.OOE+00 Kr-87 4.OOE-02 4.OOE-02 3.71 E-02 2.60E-02 3.25E-02 O.OOE+00 Kr-88 2.80E-01 2.80E-01 4.47E-02 2.60E-02 3.1OE-02 O.OOE+00 Kr-89 O.OOE+OO O.OOE+00 O.OOE+00 1.70E-01 O.OOE+00 O.OOE+00 Kr-90 O.OOE+00 O.OOE+0O 0.OOE+OO 3.70E-01 O.OOE+00 O.OOE+00 Xe-131 m 1.40E+00 1.40E+0O O.OOE+00 2.OOE-05 1.15E-03 O.OOE+OO Xe-133 7.11E+01 7.11 E+01 4.88E-02 1.1OE-02 6.34E-02 O.OOE+00 Xe-133m 5.70E-01 5.70E-01 3.17E-04 3.80E-04 5.OOE-05 O.OOE+00 Xe-135 5.30E-01 5.30E-01 2.71 E-01 2.90E-02 4.95E-02 O.OOE+00 Xe-135m O.OOE+00 O.OOE+00 1.1OE-01 3.40E-02 1.77E-01 O.OOE+O0 Xe-1 37 O.OOE+00 O.OOE+OO O.OOE+00 2.OOE-01 O.OOE+00 O.OOE+OO Xe-1 38 4.00E-02 4.00E-02 4.37E-01 1.20E-01 5.72E-01 O.OOE+00 Notes:

(1) From Table 10-1.

(2) From 1998 and 1999 Dresden Station Radiological Environmental Operating Reports.

(3) From 1998 and 1999 Quad Cities Station Radiological Environmental Operating Reports.

Appendix B B-25 0212210641

Revision 3 January 2002 Table B-1 Portion of an Example Joint Frequency Distribution Suao-ry Table of Percent by Direction and Claus c)ais N NNE NE ENE E ESE SE SSE S A .289 .317 .301 .244 .249 .190 .198 .197 .335 B .190 .187 .178 .158- .125 .065 .079 .130 _193 C .269 .226 .252 .218 .190 .115 .152 .189 .302 D 3.298 2.327 2.338 2.684 1.992 1.334 1.365 2.172 3.0t2 E 1.466 1.198 .988 1.33t 1.661 1.226 1.472 2.553 3.628 F .504 .318 .185 .276 .699 .648 .803 1.293 1.732 o .202 .091 .061 .099 .253 .250 .355 .400 .624 Total 6.217 4.663 4.304 S.011 5.169 3.830 4.424 6.933 9.526 Sumary Table ot Percent by Direction and Speed Speed N NE NE ENE E ESE SE SSE S

.45 .098 .099 .078 .030 .009 .000 .014 .032 .046 1.05 .308 .154 .125 .137 .121 .093 .090 .090 .127 2.05 .939 .602 .458 .594 .843 .606 .1598 .605 1.008 3.05 1.164 1.030 .779 .981 1.468 1.075 1.093 1.478 1.982 4.05 1.179 1.024 .878 .995 1.243 .831 1.027 1.727 2.110 5.05 .839 .631 .658 .798 .724 .474 .652 1.254 1.636 6.05 .612 .467 .496 .5e9 .417 .313 .418 .803 8.05 1.153

.755 .437 .612 .695 .310 .313 .405 .735 1.319 10.05 .253 .157 .183 .165 .032 .093 .103 .180 13.05 .274

.053 .061 .034 .027 .001 .031 .025 .028 .072 18.00 .016 .001 .004 .000 .000 .001 .001 .002 .000 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 Iota) 6.217 4.663 4.304 Z.011 5.169 3.830 4.424 6.932 9.326 Sum-ary 1able of Percent by Speed and Class Clang A 8 C 0 E F a Speed

.45 .004 .001 .000 .09S .257 .27S .346 1.05 .018 .012 .027 .508 1.035 1.080 .780 2.05 .206 .171 1246 3.256 5.028 3.228 1.419 3.05 .744 .428 616 6.258 7.173 3.272 .985 A.05 .992 .581 .781 8.165 6.404 1.902 .460 5.05 .909 .506 .808 7.302 4.357 .607 .07 7 6.05 .712 .389 .613 6.167 2.938 .164 .013 8.05 819 .500 .755 7.616 2.734 .081 .011 10.05 .230 .150 .196 2.e60 .667 .009 .000 13.05 .075 .032 .055 .755 .161 .001 .000 18.00 C004 .OOO .018 .117 .012 .000 .000 99.00 .000 .000 .00t .001 .000 .000 .000 Appendix B B-26 0212210641

Revision 3 January 2002 Figure B-1 Instantaneous View of Plume y

Wind O I

This figure represents a snapshot of a projection of a plume on the horizontal plane. As it moves downwind, the plume meanders about the average wind direction and broadens (adapted from Reference 18).

Appendix B B-27 0212210641

Revision 3 January 2002 Figure B-2 A Gaussian Curve 1.0 0.I s I 0 2 (.,-a) 0.8 z.7 0.S y I aI '.5 0.4 a.:

0.2 a.1 0.0

.3 -2 -1 0 1 2 3 X -a (Adapted from Reference 24 of Chapter 9, Page 61.)

Appendix B B-28 0212210641

Revision 3 January 2002 Figure B-3 Effect of Observation Period on Plume Shape sof FL-S00 I ALLATMU COwCtICtRATtOM This sketch represents the approximate outlines of a smoke plume observed instataneously and averaged over periods of 10 minutes and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The diagram on the right shows the corresponding cross plume distribution pattems. The plume width increases as the period of observation increases (from Reference 18).

Appendix B B-29 0212210641

Revision 3 January 2002 Figure B-4 A Gaussian Plume Z

rv X (X.-Y,Z)

(z.-Y.O)

This sketch illsutrates a plume characterized by Equation B-9. The plume is moving downwind in the x direction. Both the horizontal dispersion parameter sz increases as x increases. The reflected component has been omitted in this illustration (adapted from Reference 24).

Appeal xB B-30 0212210641