Text

Radioactive Effluent Release Report
	ML061210376
Person / Time
Site:	Braidwood
Issue date:	04/28/2006
From:	Polson K; Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BW060049, FOIA/PA-2010-0209
	Download: ML061210376 (159)
	v • d • e

ExekIcn.

Exelon Generation Company, LLC www.exeloncorp.com Nuclear Braidwocd Station 35100 South Rt 53, Suite 84 Braceville, IL 60407-9619 April 28, 2006 BW063049 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457

Subject:

2005 Radioactive Effluent Release Report The attached document includes the Radioactive Effluent Release Report for Braidwood Station. This report is being submitted in accordance with 10 CFR 50.36a, "Technical specifications on effluents from nuclear power reactors," and Technical Specification 5.6.3, "Radioactive Effluent Release Report," and includes a summary of radiological liquid and gaseous effluents and solid waste released from the site from January 2005 through December 2005.

If you have any questions regarding this information, please contact Mr. Dale Ambler, Regulatory Assurance Manager, at (815) 417-2800.

Respectfully, Keith J. Polson Site Vice President Braidwood Station Attachment cc:

Regional Administrator - NRC Region ill NRC Senior Resident Inspector - Braidwood Station L/ 8

RADIOACTIVE EFFLUENT RELEASE REPORT Supplemental Information January - December 2005 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.

Iodine: (summed with particulate, see below)

c.

Particulates with half-lives > 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.

1 of 105

2.

Maximum Permissible Concentration

a.

Fission and Activation Gasses: 1 OCFR20 Appendix B Table 2

b.

Iodine: 1 OCFR20 Appendix B Table 2

c.

Particulates: 10CFR2O Appendix B Table 2

d.

Liquid Effluents: 10 X 10CFR2O Appendix B Table 2

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 trilium. A representative portion of this sample is saved. This is composited, every 31 days, wilh 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 monthly.

The monthly composites are then composited quarterly and sent to a vendor for Sr-89/90 and Fe-55 analysis.

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.

2 of 105

4.

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.

d.

Summary of Assessment of Offsite Doses from Inadvertent Releases of Water from Blowdown Line at Braidwood Station Calculations based on gaseous and liquid effluents, Kankakee River flow and meteorological data indicate that public dose due to radioactive material attributable to Braidwood Station during the period does not exceed regulatory or Offsite Dose Calculation Manual (OECM) limits.

The Total Effective Dose Equivalent (TEDE) due to licensed activities at Braidwood Station calculated for the maximally-exposed individual for the period has been calculated not to exceed 3.51 E-01 mrem. The annual limit of TEDE is 100 mrem.

In the spring of 2005, tritium was detected above background level concentration in the site's east side perimeter ditch. This prompted groundwater studies in the summer and fall of 2005 that indicated contamination of the groundwater. Past failures at three vacuum breaker valves in the blowdown line that returns water from the cooling lake to the Kankakee River in 1996, 1998, 2000 and 2003 were known to have released tritium (as well as other radionuclides in much lower concentrations) into the ground. The offsite dose to a member of the public was assessed based upon conservative assumptions. This assessment is provided as Attachment 2.

The assessment of radiation doses to the public due to routine effluent releases is pErformed in accordance with the ODCM. The results of these analyses for routine releases as well for the groundwater contamination confirm that the Station is operating well within the dose limits of 10CFR50, Appendix I, 1 OCFR20 and 40CFR190.

The dose receptor for the groundwater contamination pathway assessment represents a different location and exposure pathway than that assumed for the maximally exposed individual in the Offsite Dose Calculation Manual. Thus there is no increase in reported dose to the maximum individual for the years 1996 to 2005. The dose assessment demonstrated that at no time did the dose exceed that of the maximum individual dose reported for the 1996-2005 time period. Therefore the doses already reported for those years continue to represent the highest potential dose to a member of the public.

3 of 105

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 GAS RELEASES UNIT 1 (Docket Number 50-456)

SUMMATION OF ALL RELEASES Units l

st Qtr 2nd Qtr 3rd Qtr 4th Qtrl 1st EIt. Tota A. Fission and Activation Gas Releases

1. Total Release Activity Ci 1.99E+00 8.08E-01 9.60E+00 6.98E-01 7.59

2. Average Release Rate uCi/sec 2.56E-01 1.03E-01 1.21E+00 8.78E-02

3. Percent of ODCM Limit -gamma 1.38E-04 8.39E-05 3.67E-02 1.14E-04

4. Percent of ODCM Limit - beta 1.18E-03 4.11E-04 7.49E-03 2.72E-04 B. lodine Releases

1. Total 1-131 Activity Ci 1.37E-05 8.36E-05 1.38E-04 1.22E-05 33.20

2. Average Release Rate uCi/sec 1.76E-06 1.06E-05 1.74E-05 1.53E-06

3. Percent of ODCM Limit - gamma J

1.24E-01 5.02E-01 5.47E-01 1.50E-01 C. Particulate (> 8 day half-life) Releases

1. Gross Activity l

Ci

<LLD 1.01 E-05 l <LLD

<LLD l 19.80

2. Average Release Rate uCi/sec 0.OOE+00 1.28E-06 0.OOE+00 0.OOE+00

3. Percent of ODCM Limit N/A 5.02E-01 N/A N/A

4. Gross Alpha Activity Ci

<LLD

<LLD D. Tritium Releases Ii. Tota' Release Activity Ci

[3.90E+01 [ 1.65E+01 l4.53E+01 I 9.86E+00 l 8.07

2. Aver.age Release Rate uCi/sec I 5.02E+00 I 2.10E+00 I 5.70E+00 I 1.24E+00

3. Percent of ODCM Limit l

I 1.24E-01 1 5.02E-01 l 5.47E-01 l 1.50E-01 Note: L.LD Values are included in Appendix A of this report.

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BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 GAS RELEASES UNIT 1 (Docket Number 50-456)

CONTINUOUS MODE AND BATCH MODE Nuclides Released Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1

2 3

4 1

2 3

4

1. Fission Gases Ar-41 Ci

<LLD

<LLD 1.26E-03 cLLD

<LLD

<LLD Kr-85 Ci

<LLD

<LLD 1.22E+00 2.96E-01 3.92E-01

<LLD Kr-85m Ci

<LLD

<LLD 1.62E-03 Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD 5.26E+00

<LLD

<LLD Xe-131m Ci

<LLD

<LLD 2.62E-02

<LLD Xe-133 Ci

<LLD

<LLD 7.69E-01 5.11E-01 3.87E+00) 6.94E-01 Xe-133m Ci

<LLD

<LLD 9.34E-04 2.68E-02

<LLD Xe-1 35 Ci

<LLD

<LLD 2.69E-04

<LLD 2.35E-02 2.40E-03 Xe-135m Ci

<LLD

<LLD Xe-1 38 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD 5.26E+00

<LLD 1.99E+00 8.08E-01 4.34E+00 6.98E-01

2. lodines

=

1-131 Ci 1.76E-06 2.84E-05 2.69E-05 7.94E-06

<LLD

<LLD 1-132 Ci

<LLD

<LLD 9.35E-06

<LLD

<LLD 1-133 Ci 1.20E-05 5.52E-05 9.41 E-05 4.25E-06

<LLD

<LLD 1-134 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD 7.42E-06

<LLD

<LLD Total for Period Ci 1.38E-05 8.36E-05 1.38E-04 1.22E-05

<LLD

3. Particulates Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Br-82 Ci

<LLD

<LLD 1.01 E-07

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Mo-99 Ci

<LLD

<LLD Tc-99m Ci

<LLD

<LLD Sn-i1m Ci

<LLD

<LLD 5 of 105

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 GAS RELEASES UNIT 1 (Docket Number 50-456)

CONTINUOUS MODE AND BATCH MODE Nuclides Released Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter Cs-1341 2

3 4

1 2

3 4

Cs-1 34 Ci

<LLD

<LLD Cs-i 37 Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-i144 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD 1.01 E-07

<LLD

4. Tritium Ci 3.88E+O1 1.64E+01 4.50E+01 9.77E+00 2.02E-01 1.12E-01 2.62E-01 8.30E-02 6 of 105

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 GAS RELEASES UNIT 2 (Docket Number 50-457)

SUMMATION OF ALL RELEASES Units l

st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total I

I s I

I r II Error% I A. Fission and Activation Gas Releases

1. Total Activity Released Ci 1.38E+00 4.24E-01 2.67E+00 1.37E-02 7.59

2. Average Release Rate uCi/sec 1.77E-01 5.39E-02 3.36E-01 1.72E-03

3. Percant of ODCM Limit - gamma 4.21E-05 2.86E-05 3.77E-04 2.18E-06

4. Percent of ODCM Limit - beta 9.41 E-04 2.67E-04 1.18E-03 5.28E-06 B. Iodine Releases

1. Total 1-131 Activity Ci

<LLD 1.1 6E-05

<LLD

<LLD 33.20

2. Average Release Rate uCi/sec 0.OOE+00 1.48E-06 O.OOE+00 0.OOE+00

3. Percant of ODCM Limit N/A 1.87E-01 N/A N/A C. Particulate (> 8 day half-life) Releases

1. Gross Activity Ci

<LLD 7.04E-06

<LLD l <LLD 19.80

2. Average Release Rate uCi/sec 0.00E+00 8.95E-07 O.OOE+00 l 0.OOE+00

3. Percent of OCDM Limit NA 1.87E-01 N/A N/A

4. Gross Alpha Activity Ci

<LLD

<LLD D. Tritilum Releases l1. Total Release Activity

[

Ci l 6.22E+01 l1.75E+01 l4.12E+01 l1.67E+02 l 8.07

2. Average Release Rate uCi/sec 8.00E+Oo I 2.23E+00 I 5.18E+00 l 2.10E+O1

3. Percent of ODCM Limit

% J 1.77E-01 1.87E-01 j 1.17E-01 4.74E-01 Note: LLD Values are included in Appendix A of this report.

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BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 GAS RELEASES UNIT 2 (Docket Number 50-457)

CONTINUOUS MODE AND BATCH MODE Nuclides Released Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1

2 3

4 1

2 3

4

1. Fission Gases Ar-41 Ci

<LLD

<LLD 1.26E-03

<LLD

<LLD Kr-85 Ci

<LLD

<LLD 1.22E+00 2.96E-01 3.92E-01

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD 2.62E-02

<LLD Xe-133 Ci

<LLD

<LLD 1.60E-01 1.19E-01 2.20E+00 1.37E-02 Xe-1 33m Ci

<LLD

<LLD 9.34E-04 2.68E-02

<LLD Xe-1 35 Ci

<LLD

<LLD 2.01 E-03 8.31 E-03 2.01 E-02

<LLD Xe-1 35m Ci

<LLD

<LLD Xe-1 38 Ci

<LLD

<LLD Total for Period Ci

<LLD

<LLD 1.38E+00 4.24E-01 2.67E+00 1.37E-02

2. lodines 1-131 Ci

<LLD 9.18E-06

<LLD

<LLD 1-132 Ci

<LLD

<LLD 1-133 Ci

<LLD 2.37E-06

<LLD

<LLD 1-134 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Total for Period Ci

<LLD 1.16E-05

<LLD

3. Particulates Cr-51 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD 4.47E-06

<LLD

<LLD Fe-59 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Br-82 Ci

<LLD 2.57E-06

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Mo-99 Ci

<LLD

<LLD Sn-117m Ci

<LLD

<LD dLD

<LLD

<LLD Cs-1 34 Ci

<LLD

<LLD dLLD

<LLD

<LLD 8 of 105

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 GAS RELEASES UNIT 2 (Docket Number 50-457)

CONTINUOUS MODE AND BATCH MODE Nuclides IReleased Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1

2 3

4 1

2 3

4 Cs-137 Ci

<LLD

<LLD Ba-1 40 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Ce-1 41 Ci

<LLD

<LLD Ce-1 44 Ci

<LLD

<LLD Nd-147 Ci

<LLD

<LLD Total for Period Ci

<LLD 7.04E-06

<LLD

4. Tritium Ci 6.18E+01 1.69E+01 4.11E+01 1.67E+02 4.22E-01 6.89E-01 1.1OE-O, 1.70E-01 9 of 105

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 LIQUID RELEASES UNIT 1 (Docket Number 50-456)

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

1. Total Activity Released Ci 1.17E-02 8.52E-03 4.43E-03 2.56E-03 2.64

2. Average Concentration Released uCi/mI 2.17E-09 2.51E-09 1.76E-09 8.45E-10

3. Percent of limit

%m B. TritiuJm

1. Total Activity Released Ci 2.69E+02 I 2.10E+02 1.82E+02 2.20E+02 5.85

2. Average Concentration Released uCi/mI 5.OOE-05 6.1 9E-05 7.25E-05 7.26E-05

3. % of Limit (1 E-2 uCi/ml) 5.00E-01 6.19E-01 7.25E-01 7.26E-01 C. Dissolved Noble Gases

1. Total Activity Released Ci 8.29E-04 2.41 E-03 7.41 E-04 8.11 E-04 _ 2.64

2. Average Concentration Released uCi/mI 1.54E-10 7.1OE-10 2.95E-10 2.68E-10 _

3. % of Limit (2E-4 uCi/ml) 7.70E-05 3.55E-04 1.48E-04 1.34E-04 D. Gross Alpha

1. Total Activity Released l

Ci l <LLD

< LLD l <LLD l <LLD l

12.Average Concentration Released uCi/mI

<LLD

<LLD E. Volume of Releases

11. Volume of Liquid Waste to Discharge l liters I 1.55E+06 1.98E+06 T 1.67E+06 1 7.41 E+05

[2youme of Dilution Water I

liters 75.38E+09l 3.39E+09 72.51 E+09 I 3.03E+09 Note: LLD Values are included in Appendix A of this report.

This limit is equal to 10 times the concentration values in Appendix B, Table 2, Column 2 to 1 0CFR20.1001-20.2402.

10 of 105

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 LIQUID RELEASES UNIT 1 (Docket Numbers 50-456)

CONTINUOUS MODE & BATCH MODE Nuclides Released Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1

2 3

4 1

2 3

4 H-3 Ci 1.OOE+01 5.59E+01 5.16E+00 1.27E-01 2.59E+02 1.54E+02 1.77E+02 2.20E+02 Ar-41 Ci

<LLD

<LLD Cr-51 Ci

<LLD 5.92E-06

<LLD

<LLD 7.96E-04

<LLD

<LLD Mn-54 Ci

<LLD

<LLD 6.99E-05 1.21 E-04 2.53E-0,5

<LLD Fe-55 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD 1.77E-03 3.45E-03 2.40E-O'3 2.27E-03 Fe-59 Ci

<LLD

<LLD 7.37E-05

<LLD

<LLD Co-60 Ci

<LLD

<LLD 7.31 E-04 8.72E-04 5.72E-0-4 2.42E-04 Ni-65 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD 1.87E-04 7.40E-04, 8.1OE-04 Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD 3.75E-05 1.39E-04 3.33E-06;

<LLD Zr-95 Ci

<LLD

<LLD 2.01 E-06 4.94E-05

<LLD

<LLD Nb-97 Ci

<LLD

<LLD Zr-97 Ci

<LLD

<LLD Tc-99m Ci

<LLD

<LLD Mo-99 Ci

<LLD

<LLD Ag-11 Om Ci

<LLD

<LLD Sn-1i17m Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD 4.80E-06 2.71E-05

<LLD

<LLD Te-123m Ci

<LLD

<LLD 2.99E-05 6.84E-04 5.49E-OE, 3.12E-05 Sb-124 Ci

<LLD

<LLD 6.75E-06 4.31 E-05 1.21 E-OZ.

<LLD Sb-1 25 Ci

<LLD

<LLD 2.56E-04 4.97E-04 1.25E-03' 1.82E-05 Te-1 25m Ci

<LLD

<LLD 7.81 E-03 1.71 E-03

<LLD

<LLD Xe-1 31 m Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD I-132 Ci

<LLD

<LLD 3.30E-06

<LLD

<LLD Te-132 Ci

<LLD

<LLD Ba-1 33 Ci

<LLD

<LLD 3.68E-06

<LLD

<LLD 1-133 Ci

<LLD

<LLD Xe-i33 Ci

<LLD

<LLD 8.29E-04 1.92E-03

<LLD

<LLD 11 of 105

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 LIQUID RELEASES UNIT 1 (Docket Numbers 50-456)

CONTINUOUS MODE & BATCH MODE Nuclides lReleased Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1

2 3

4 1

2 3

4 Xe-133m Ci

<LLD

<LLD 1.22E-05

<LLD

<LLD Cs-1 34 Ci

<LLD

<LLD 2.41 E-05

<LLD

<LLD Xe-1 35 Ci

<LLD

<LLD 2.91 E-04

<LLD

<LLD 1-134 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-1 37 Ci

<LLD

<LLD 3.57E-04 2.71 E-05

<LLD

<LLD Cs-1 38 Ci

<LLD

<LLD Xe-1 38 Ci

<LLD

<LLD Ba-1 39 Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD La-1 40 Ci

<LLD

<LLD Ce-1 41 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Np-239 Ci

<LLD

<LLD Total for pLriod Ci 1.OOE+01 5.59E+01 5.16E+00 1.27E-01 2.59E+02 1.54E+02 1.77E+02 2.20E+02 12 of 105

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 LIQUID RELEASES UNIT 2 (Docket Number 50-457)

SUMMATION OF ALL RELEASES Units 1st Qtr l 2nd Qtr 3rd Qtr 4th Qtr

.Total A. Fission and Activation Products 1 Total Activity Released Ci 1.1 7E-02 8.52E-03 4.43E-03 l 2.56E-03 2.64

2. Average Concentration Released uCi/ml 2.17E-09 2.51E-09 1.76E-09 8.45E-10

3. Percgnt of Limit

]

B. Tritium

1. Tota' Activity Released I

Ci 2.69E+02 I 2.10E+02 11.82E+02 2.20E+02 _ 5.85

2. Average Concentration Released uCi/ml 5.00E-05 6.19E-05 7.25E-05 7.26E-05

3. % of Limit (1 E-3 uCi/mI) 5.00E-01 6.19E-01 7.25E-01 7.26E-01 _

C. Dissolved Noble Gases

1. Total Activity Released Ci 8.29E-04 2.41 E-03 7.41 E-04 8.11 E-04 l 2.64

2. Average Concentration Released uCimlI 1.54E-10 7.1OE-10 [ 2.95E-10 2.68E-10

3. % of Limit (2E-4 uCi/ml) 7.70E-05 3.55E-04 1.48E-04 1.34E-04 _

D. Gro ss Alpha

11. Total Activity Released l

Ci l <LLD

<LLD l

L LD 14.70 age Concentration Released uCi/mI

<LLD

<LLD E. VolIme of Releases

1. Volumne of Liquid Waste to Discharge l liters l 1.55E+06 l 1.98E+06 l 1.67E+06 1 7.41 E+05 l 2.Voujne of Dilution Water liters 5.38E+09 I 3.39E+09 1 2.51 E+09 3.03E+09 Note: I-LD Values are included in Appendix A of this report.

This limit is equal to 10 times the concentration values in Appendix B, Table 2, Column 2 to 1 OCFR20.1001-2402.

13 of 105

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 LIQUID RELEASES UNIT 2 (Docket Numbers 50-457)

CONTINUOUS MODE & BATCH MODE Nuclides FReleased Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1

2 3

4 1

2 3

4 H-3 Ci 1.OOE+01 5.59E+01 5.16E+00 1.27E-01 2.59E+02 1.54E+02 1.77E+02 2.20E+02 Ar-41 Ci

<LLD

<LLD cLLD

<LLD

<LLD Cr-51 Ci

<LLD 5.92E-06

<LLD

<LLD 7.96E-04

<LLD

<LLD Mn-54 Ci

<LLD

<LLD 6.99E-05 1.21 E-04 2.53E-05

<LLD Fe-55 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD dLLD

<LLD

<LLD Co-58 Ci

<LLD

<LLD 1.77E-03 3.45E-03 2.40E-03 2.27E-03 Fe-59 Ci

<LLD

<LLD 7.37E-05

<LLD

<LLD Co-60 Ci

<LLD

<LLD 7.31 E-04 8.72E-04 5.72E-04 2.42E-04 Ni-65 Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD 1.87E-04 7.40E-04 8.1 OE-04 Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD 3.75E-05 1.39E-04 3.33E-06

<LLD Zr-95 Ci

<LLD

<LLD 2.01 E-06 4.94E-05

<LLD

<LLD Nb-97 Ci

<LLD

<LLD Zr-97 Ci

<LLD

<LLD Tc-99m Ci

<LLD

<LLD Mo-99 Ci

<LLD

<LLD Ag-11Om Ci

<LLD

<LLD Sn-11 7m Ci

<LLD

<LLD Sb-1 22 Ci

<LLD

<LLD 4.80E-06 2.71 E-05

<LLD

<LLD Te-1 23m Ci

<LLD

<LLD 2.99E-05 6.84E-04 5.49E-05 3.12E-05 Sb-124 Ci

<LLD

<LLD 6.75E-06 4.31 E-05 1.21 E-04

<LLD Sb-125 Ci

<LLD

<LLD 2.56E-04 4.97E-04 1.25E-02.

1.82E-05 Te-125m Ci

<LLD

<LLD 7.81 E-03 1.71 E-03

<LLD

<LLD Xe-1 31 m Ci

<LLD

<LLD 1-131 Ci

<LLD

<LLD 1-132 Ci

<LLD

<LLD dLLD 3.30E-06

<LLD

<LLD Te-132 Ci

<LLD

<LLD Ba-1 33 Ci

<LLD

<LLD 3.68E-06

<LLD

<LLD 1-133 Ci

<LLD

<LLD LLD

<LLD

<LLD Xe-1 33 Ci

<LLD

<LLD 8.29E-04 1.92E-03

<LLD

<LLD 14 of 105

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2005 LIQUID RELEASES UNIT 2 (Docket Numbers 50-457)

CONTINUOUS MODE & BATCH MODE Nuclides iReleased Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1

2 3

4 1

2 3

4 Xe-1 33m Ci

<LLD

<LLD 1.22E-05

<LLD

<LLD Cs-134 Ci

<LLD

<LLD 2.41 E-05

<LLD

<LLD Xe-1 35 Ci

<LLD

<LLD 2.91 E-04

<LLD

<LLD 1-134 Ci

<LLD

<LLD 1-135 Ci

<LLD

<LLD Cs-1 36 Ci

<LLD

<LLD Cs-1 37 Ci

<LLD

<LLD 3.57E-04 2.71 E-05

<LLD

<LLD Cs-1 38 Ci

<LLD

<LLD Xe-1 38 Ci

<LLD

<LLD Ba-1 39 Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD La-1 40 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-1 44 Ci

<LLD

<LLD Np-239 Ci

<LLD

<LLD Total for pe riod Ci 1.OOE+01 5.59E+01 5.16E+00 1.27E-1 2.59E+02 1.54E+02 1.77E+0' 2.20E+02 15 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2004 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 Proces;, Waste 1 st Qtr 2nd Qtr 3rd Qtr 4th Qtr Yr total Total (m3) =

8.58E+01 9.99E+02 9.28E+00 1.02E+01 2.05E+02 Total (Ci) =

1.54E+01 1.84E+01 1.46E+02 4.58E+02 6.38E+02

% Error =

2.50E+01 2.50E+01 2.50E+01 2.50E+01 2.50E+01 Dry Active Waste 1 st Qtr 2nd Qtr 3rd Qtr 4th Qtr Yr total Total (m3) =

Total (Ci) =

% Error =

7.64E+01 2.91 E-02 2.50E+01 2.64E+02 5.57E-01 2.50E+01 0.00E+00 0.OOE+00 2.50E+01 3.82E+01 1.29E-02 2.50E+01 3.40E+02 6.15E-01 2.50E+01

2.

Estimate of major nuclide composition (by type of waste)

Process; Waste 1 st Qtr 2nd Qtr 3rd Qtr 4th Qtr Yr total Nuclide Ci Ci Ci Ci Ci

% Composition Cs-137 5.74E-01 1.22E-01 3.43E+01 1.17E+02 1.52E+02 2.37E+0-1

Fe-55 3.68E+00 2.18E+00 2.60E+01 8.24E+01 1.14E+02 1.792+01 Cs-134 2.50E-01 1.02E-01 2.12E+01 7.25E+01 9.41 E+01 1.47E+0-1 Co-60 2.70E+00 1.04E+00 2.31 E+01 6.23E+01 8.91 E+01 1.40E+01 Zn-65 2.18E-03 9.85E-03 1.80E+01 6.33E+01 8.13E+01 1.27E+01

Ni-59 7.26E-02 1.62E-02 1.29E+01 4.52E+01 5.82E+01 9.11 E+0O)

Co-58 4.83E-01 1.26E+01 6.60E+00 2.44E+00 2.21 E+01 3.47E+00 Mn-54 1.04E-01 5.42E-01 3.17E+00 9.95E+00 1.38E+01 2.16E+00

Ni-63 6.90E+00 1.59E+00 4.81 E-01 7.24E-01 9.69E+00 1.52E+00

C-14 1.87E-01 4.14E-02 4.68E-01 1.51E+00 2.20E+00 3.45E-01 H-3 4.35E-01 6.44E-03 3.33E-03 8.702-01 1.31 E+00 2.06E-01

Activities based on 10CFR61 scaling factors 16 of 105

2.

Estimate of major nuclide composition (by type of waste) (continued)

Dry Active Waste Nuclide Co-58 H-3

Fe-55

Ni-63 Co-60 Nb-95 Mn-54 Zr-95 Cs-1 34 Cs-1 37 Zn-65

Ni-59 1 st Qtr Ci 1.58E-02 O.OOE+00 1.1 5E-02 8.64E-03 5.60E-03 8.37E-04 1.06E-03 5.87E-04 3.44E-04 2.62E-04 1.17E-04 8.81 E-05 2nd Qtr Ci 1.73E-01 1.40E-01 9.44E-02 6.90E-02 4.53E-02 1.18E-02 9.15E-03 6.66E-03 2.84E-03 2.10E-03 1.03E-03 7.04E-04 3rd Qtr Ci O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO 4th Qtr Ci 3.62E-03 6.39E-03 9.09E-04 4.43E-04 3.37E-04 8.79E-06 1.01 E-04 O.OOE+00 3.31 E-04 7.26E-04 O.OOE+00 5.29E-06 Yr total Ci 1.93E-01 1.47E-01 1.07E-01 7.81 E-02 5.12E-02 1.27E-02 1.03E-02 7.25E-03 3.51 E-03 3.08E-03 1.15E-03 7.97E-04

% Composition 3.13E+01 2.38E+01 1.74E+01 1.27E+01 8.32E+OC 2.06E+OC 1.68E+OO 1.18E+OO 5.71 E-01 5.01 E-01 1.87E-01 1.30E-01

Activities based on 1 OCFR61 scaling factors Number of Shipments: 16 Mode of Transportation: Exclusive Use Destination:

Alaron, Wampum, PA (6)

Barnwell Waste Management Facility, Barnwell, South Carolina (5)

Envirocare, Clive, Utah (4)

GTS Duratek, Kingston, Tennessee (2)

GTS Duratek, Oak Ridge, Tennessee (1)

B.

IRRADIATED FUEL SHIPMENTS No irradiated fuel shipments for January through December, 2005 17 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 SOLID RADIOACTIVE WASTE UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

Shipment Number RWS05-001 RWS05-002 RWS05-003 RWS05-004 RWS05-005 RWS05-006 RWS05-007 RWS05-008 RWS05-009 RWS05-010 RWS05-011 RWS05-012 RWS05-013 RWS05-014 RWS05-015 RWS05-016 RWS05-017 RWS05-018 Waste Class AU AU C

AU AU AU AU AU AU AU AU AU AU B

AU B

B C

TvDe of Container General Design General Design Cast STC Cask STC General Design General Design Cast STC General Design General Design General Design Cask STC General Design Cask STC Cask Type B General Design Cask Type B Cask Type A Cask Type B Solidification Agent None None None None None None None None None None None None None None None None None None 18 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

1.

There were no changes to the Braidwood Station Process Control Program in 2005.

2.

There were no changes to the installed liquid, gaseous, or solid radwaste treatment systems in 2005.

There were no changes to the vendor supplied, non-plant equipment used to process liquid radwaste.

3.

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

4.

There were no unplanned released of gaseous or liquid effluents in 2005.

5.

There were no liquid or gaseous effluent monitoring instruments that exceeded their specified inoperability time in 2005.

6.

There were no changes to the Offsite Dose Calculation Manual (ODCM) during 2005.

7.

NUREG-0543, Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190) states in section IV, "As long as a nuclear plant site operates at a level below the Appendix I reporting requirements, no extra analysis is required to demonstrate compliance with the 40 CFR Part 190." The organ and whole body doses reported on pages.28 through 47 are determined using 10 CFR 50 Appendix I methodology. The doses are below the limits of Appendix I.

19of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

APPENDIX A LLD Tables 20 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

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

Alpha 7.i1 E-19 H-3 7.60E-14 Ar-41 7.63E-1 3 Mn-54 1.89E-18 Co-57 1.02E-18 Co-58 5.67E-1 9 Fe-59 3.64E-1 8 Co-60 8.94E-1 9 Zn-65 4.80E-1 8 Br-82 7.44E-1 9 Kr-85 5.83E-1 1 Kr-85m 7.03E-1 3 Kr-87 7.59E-13 Kr-88 3.18E-12 Sr-89 1.41 E-20 Sr-90 2.71 E-21 Mo-99 9.37E-1 9 1-131 8.96E-1 9 1-132 2.38E-17 1-133 1.17E-18 Xe-131 m 1.82E-1 1 Xe-133 1.27E-1 2 Xe-1 33m 4.87E-12 Cs-1 34 2.25E-18 1-135 2.88E-1 8 Xe-135 5.17E-13 Xe-1 35m 1.48E-1 1 Cs-137 2.18E-18 Xe-138 4.65E-1 1 Ba-1 39 1.04E-1 5 Ba-1 40 4.45E-1 8 La-1 40 3.64E-1 8 Ce-141 1.78E-18 Ce-1 44 7.93E-18 NOTE:

LLD Value for total activity released is based on LLD values for individual isotopes used in the calculation.

21 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

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

Alpha 4.90E-14 H-3 8.80E-12 Ar-41 3.73E-14 Cr-51 4.46E-1 3 Mn-54 1.56E-14 Fe-55 6.99E-1 3 Co-57 4.64E-1 4 Co-58 4.39E-1 4 Fe-59 3.94E-14 Co-60 9.40E-14 Zn-65 4.04E-14 Sr-89 4.OOE-1 4 Sr-90 9.23E-1 5 Nb-95 1.64E-14 Zr-95 1.22E-1 3 Nb-97 1.51 E-13 Mo-99 2.94E-1 3 Tc-99m 3.00E-1 3 Ag-1 Om 7.89E-14 Sb-124 5.43E-1 4 Sb-125 1.87E-1 3 Te-1 25m 1.62E-1 1 1-131 1.36E-1 3 Xe-133 1.41 E-13 Cs-134 5.02E-14 Cs-1 37 6.50E-14 Ba-1 39 3.57E-1 3 Ba-140 1.50E-13 La-1 40 5.89E-1 3 Ce-141 9.35E-14 Ce-144 3.48E-1 3 Kr-85 9.29E-1 2 Nb-95 1.64E-14 Sb-122 4.32E-13 Te-1 23m 4.92E-14 Te-1 32 2.28E-13 1-132 5.93E-1 4 1-133 2.37E-1 1 Cs-1 36 9.72E-1 4 Xe-1 33m 3.81 E-13 Xe-131 m 1.72E-12 Np-239 1.64E-12 Ba-133 6.31 E-14 Xe-1 35 2.43E-1 3 NOTE: LLD Value for Total Activity Released is based on LLD Values for individual isotopes used in the calculation.

22 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

APPENDIX B Supplemental Information 23 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 UNIT COMMON GASEOUS EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION A. Batch Release

1. Total Number of Batch R aleases

2. Total Time Period for Batch R Bleases (minutes)

3. Maximum Time Period for a Batch Release (minutes)

4. Average Time Period for a Batch Release (minutes)

5. Minimum Time Period for a Batch Release (minutes) 1 st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total 8

3,984 1,810 498 69 2

216 124 108 92 8

829 303 104 2

0 0

N/A N/A N/A 18 5,029 N/A N/A N/A B. A'Dnormal Releases

1. Number of Releases 0

0 0.00 0

0.000 0

0.00 0

2. Total Activity Released 0.00 0.0 3 24 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 UNIT 1 (Docket Number 50-456)

GASEOUS EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION A. Batch Release

1. Total Number of Batch Releases

2. Total Time Period for Batch Releases (minutes)

3. Maximum Time Period for a Batch Release (minutes)

4. Average Time Period for a Batch Release (minutes)

5. Minimum Time Period for a Batch Release (minutes) 1 st Qtr 2nd Qtr 3rd Qtr 4th Qtr 28 1,286 130 46 21 28 1,113 51 40 7

35 4,439 1,340 127 16 33 2,941 800 89 21 Total 124 9,779 N/A, N/A.

N/A B. Abnormal Releases

1. Number of Releases 0

0 0.00 0

0.000 0

0.00 0

0.0(

2. Total Activity Released 0.00 25 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 UNIT 2 (Docket Number 50-457)

GASEOUS EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION A. Batch Release 1.. Total Number of Batch Releases

2. Total Time Period for Batch Releases (minutes) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total 36 2,337 31 14,793 27 1,084 31 125 1,848 20,062

3. Maximum Time Period for a Batch Release (minutes) 254 6,690 99 535 N/A

4. Average Time Period for a Batch Release (minutes)

5. Minimum Time Period for a Batch Release (minutes) 65 23 477 15 40 15 60 N/A 9

N/A p

B. Abnormal Releases

1. Number of Releases

2. Total Activity Released 0

0.00 0

0 0.00 0.00 26 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

BRAIDWOOD NUCLEAR POWER STATION SUl A.

Batch Release

1.

Total Number of Batch Releases

2.

Total Time Period for Batch Releases (minutes)

3.

Maximum Time Period for a Batch Release (minutes)

4.

Average Time Period for a Batch Release

5.

M nimum Time Period for a Batch Release (minutes)

6.

Average Stream Flow During Periods of Release of Effluent int:o a Flowing Stream (Ii :ers/min)

B.

Abnormal Releases

1.

Number of Releases

2.

Total Activity Released (Ci)

LIQUID EFFLUENTS 3PLEMENTAL RELEASE INFORMATION 1 st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total 17 134 35 6,178 393 177 65 45 7,541 399 168 32 37 3,259 3,571 20,549 218 431 N/A N/A 88 210 51 80 N/A 1.88E+07 4.95E+06 1.61E+06 2.93E+06 N/A 0

0.00 0

0.00 27 of 105

RETDA'; v3.6.3

<BRA>

V',SI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID........... : 1 All Gas Release Types Period Start Date.... : 01/01/2005 00:00 Period End Date......

01/01/2006 00:00 Period Duration (min): 5.256E+05 Coefficient Type.....

Historical Unit.................

1 RELEASE DATA =-

Total Release Duration (minutes)...................................... 3.368E+05 Total Release Volume (cf)......................................

5.080E+10 Averagre Release Flowrate (cfm)......................................

1.508E+05 Average Period Flowrate (cfm)......................................

9.61;5E+04

=== NICLIDE DATA==-

Nuclide AR-41 KR-85M KR-85 XE-133M KR-88 XE-131M XE-13'i XE-13:

F&AG I-131 I-132 I-133 I-135 Iodine BR-82 Other H-3 H-3 Total uci 1.26E+03

1. 62E+03 1.91E+06 2.77E+04 5.26E+06 2.62E+04

2. 62E+04

5. 84E+06 1.31E+07 6.50E+01 9.35E+00

1. 66E+02 7.42E+00 2.47E+02 1.01E-01

1. 01E-01 1.11E+08 l.11E+08 Average uci

/cc 8.75E-13 1.12E-12 1.33E-09 1.93E-11 3.66E-09 1.82E-11 1.82E-11 4.06E-09 9.10E-09 ECrcent Ratio 8.75E-05 1.12E-05 1.90E-03 3.21E-05 4.06E-01 9.09E-06 2.60E-04 8.12E-03 4.17E-01 EC 1.OOE-08 1.OOE-07

7. OOE-07 6.OOE-07 9.OOE-09 2.OOE-06 7.OOE-08

5. OOE-07 2.OOE-10

2. OOE-08 1.00E-09 6.OOE-09 5.OOE-09 1.00E-07 4.52E-14 6.50E-15 1.15E-13 5.16E-15 1.72E-13 7.02E-17 7.02E-17 7.69E-08 7.69E-08 2.26E-04 3.25E-07 1.15E-04 8.59E-07 3.42E-04 1.40E-08

1. 40E-08

7. 69E-01 7.69E-01 1.24E+08 8.60E-08 1.19E+00 Date/"?ime: 04/21/2006 15:31 retdasID: Retdas Page -

1 28 of 105

RETDAS v3.6.3

<BRA>

VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID........... : 1 All Gas Period Start Date.... : 01/01/2005 Period End Date...... : 01/01/2006 Period Duration (min): 5.256E+05 Coeff-.cient Type.....

Historical Unit.................. : 1 Release Types 00:00 00:00 Date/Time: 04/21/2006 15:31 retdasID: Retdas Page -

2 29 of 105

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.... : 01/01/2005 00:00 Perioc End Date...... : 01/01/2006 00:00 Perioc. Duration (min): 5.256E+05 Coefficient Type.....

Historical Unit.................

1 Receptor............. : 5 Composite Crit. Receptor -

IP Distar.ce (meters)....

0.0 Compass Point........

0.0

=== PERIOD DOSE BY AGEGROUP,

PATHWAY, ORGAN (mrem)-

Age/Pe.th Bone Liver Thyroid Kidney Lung GI-Lli Skin TB AGPD AINHL AVEG AGMILE:

ACMEAT ACMILP:

TGPD TINHL TVEG TGMILP:

TCMEAT TCMILE:

CGPD CINHL CVEG CGMILE CCMEAT CCMILE IGPD IINHL IGMILE:

ICMILE 8.1OE-07 1.14E-07

2. 91E-06 1.24E-05

3. 63E-07

1. 04E-05 8.10E-07 1.60E-07 2.77E-06 2.26E-05 3.02E-07

1. 88E-05

8. IOE-07 2.18E-07 5.14E-06 5.47E-05 5.60E-07 4.56E-05 8.1OE-07 1.73E-07 1.14E-04 9.52E-05 8.10E-07 2.93E-03 5.25E-03 3.63E-03 7.55E-04 1.79E-03 8.1OE-07 2.95E-03 6.01E-03 4.74E-03 4.50E-04 2.33E-03 8.1OE-07 2.61E-03 9.33E-03 7.51E-03 5.45E-04 3.70E-03 8.10E-07 1.50E-03 1.14E-02 5.66E-03 8.10E-07 2.97E-03 6.58E-03 9.36E-03 9.25E-04 6.56E-03

8. 1OE-07 3.OOE-03 7.11E-03 1.38E-02 5.73E-04 9.88E-03 8.1OE-07 2.67E-03 1.10E-02

2. 55E-02 7.31E-04 1.87E-02 8.1OE-07 1.56E-03 5.51E-02 4.20E-02 8.10E-07 2.93E-03 5.26E-03 3.65E-03 7.55E-04 1.80E-03 8.10E-07 2.95E-03 6.OIE-03 4.76E-03 4.50E-04 2.35E-03 8.10E-07 2.61E-03 9.33E-03 7.54E-03 5.46E-04 3.73E-03 8.1OE-07 1.50E-03 1.15E-02

5. 67E-03 8.1OE-07 2.93E-03 5.25E-03

3. 62E-03 7.55E-04 1.77E-03 8.1OE-07 2.95E-03 6.01E-03 4.70E-03 4.50E-04 2.31E-03 8.1OE-07 2.61E-03 9.33E-03 7.45E-03 5.45E-04 3.65E-03 8.10E-07 1.50E-03 1.13E-02 5.54E-03 8.1OE-07 2.93E-03 5.25E-03 3.62E-03

7. 55E-04 1.78E-03 8.1OE-07 2.95E-03 6.01E-03 4.71E-03 4.50E-04 2.31E-03 8.1OE-07 2.61E-03 9.33E-03 7.46E-03 5.45E-04 3.66E-03 8.10E-07 1.50E-03 1.13E-02

5. 55E-03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00

0. OOE+00 0.OOE+00 0.OOE+00

0. OOE+00

8. 1OE-07

2. 93E-03 5.25E-03

3. 63E-03

7..5SE-04 1.78E-03

8.

.OE-07 2.95E-03

6.

1OE-03 4.72E-03

4. EOE-04 2.-2E-03

8. IOE-07

2. 61E-03 9.33E-03 7.4:8E-03 5.45E-04 3.68E-03

8. JOE-07

1. 'iOE-03

1. 14E-02

5. 59E-03

=== PERIOD DOSE BY AGEGROUP, ORGAN (mrem) =-

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT TEEN CHILD INFANT 2.70E-05 4.54E-05

1. 07E-04 2.11E-04 1.44E-02

1. 65E-02 2.37E-02 1.86E-02

2. 64E-02 3.44E-02 5.86E-02 9.87E-02 1.44E-02

1. 65E-02 2.38E-02 1.86E-02 1.43E-02 1.64E-02 2.36E-02 1.84E-02 1.43E-02 1.64E-02 2.36E-02 1.84E-02

0. OOE+00

0. OOE+00 O. OOE+00

1. 413E-02

1. 6SE-02 2.36E-02

1. 85E-02 Date/P'ime: 04/21/2006 15:31 retdasID: Retdas Page -

3 30 of 105

RETDAS v3.6.3

<BRA>

VESS GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID........... : 1 All Gas Release Types Period. Start Date.... : 01/01/2005 00:00 Period End Date......

01/01/2006 00:00 Period Duration (min): 5.256E+05 Coefficient Type.....

Historical Unit................. : 1 Receptor............. : 5 Composite Crit. Receptor -

IP Distar.ce (meters).... : 0.0 Compass Point

0.0

=== MAXIMUM PERIOD DOSE TO LIMIT 6 Dose Age Dose Period Group Organ (mrem) t-__

End__ -NF--T THYROID Strt->End INFANT THYROID 9.87E-02 Qrtr-,-End INFANT THYROID 9.87E-02 Year-,-End INFANT THYROID 9.87E-02 kny Organ)-

Limit Admin Admin

% T.Spec T.S;pec %

Period Limit of Limit Limit of Limit 31-day 2.25E-01 4.39E+01 3.OOE-01 3.29E+01 Quarter 5.63E+00 1.75E+00 7.50E+00 1.,2E+00 Annual 1.13E+01 8.77E-01 1.50E+01 6.58E-01 Critical Pathway........ : 3 Grs/Goat/Milk (GMILK)

Major Contributors...... : 0.0

% or greater to total Nuclide Percentage H-3 I-131 I-132 1-133 1-135 1.85E+01 7.95E+01 6.52E-05

1. 87E+00 3.76E-04

=== MAXIMUM PERIOD DOSE TO LIMIT (Tot Body))

Dose Age Dose Limit Admin Period Group Organ (mrem)

Period Limit Strt-:-End CHILD TBODY 2.36E-02 31-day 1.50E-01 Qrtr-:>End CHILD TBODY 2.36E-02 Quarter 5.25E+00 Year-:-End CHILD TBODY 2.36E-02 Annual 1.05E+01 Admin %

of Limit 1.58E+01 4.50E-01 2.25E-01 T.Spec Limit

2. OE-01 7.50E+00

1. 50E+01 T.Spec %

of Limit 1.:8E+01 3.:L5E-01

1. 58E-01 Critical Pathway........ : 2 Vegetation (VEG)

Major Contributors...... : 0.0

% or greater to total Nuclide Percentage H-3 9.98E+01 I-131 2.50E-01 I-132 2.84E-05 I-133 8.16E-03 I-135 4.86E-05 Date/Time: 04/21/2006 15:31 retdasID: Retdas Page -

4 31 of 105

RETDAS v3.6.3

<BRA>

V':SI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID...........

1 All Gas Release Types Period Start Date.

01/01/2005 00:00 Period End Date......

01/01/2006 00:00 Period Duration (min): 5.256E+05 Coefficient Type.....

Historical Unit.................

1 Receptor.............

4 Composite Crit. Receptor -

NG Distance (meters)....

0.0 Compass Point........

0.0

=== MALXIMUM PERIOD NG DOSE TO LIMIT Dose Dose Period Dose Type (mrad)

Strt-:-End Gamma 1.85E-03 Qrtr-: End Gamma 1.85E-03 Year-:-End Gamma 1.85E-03 Major Contributors......

0.0

% or Nuclide Percentage AR-41 1.43E-02 KR-8511 2.42E-03 KR-85 4.OOE-02 XE-133M 1.10E-02 KR-88 9.74E+01 XE-13: M 4.97E-03 XE-13'i 6.13E-02 XE-13'1 2.51E+00

=== MaXIMUM PERIOD NG DOSE TO LIMIT Dose Dose Period Dose Type (mrad) tr

-E-d-Beta E-0___

Strtr->End Beta 9.35E-04 Qrtr-:-End Beta 9.35E-04 Year-:-End Beta 9.35E-04 Major Contributors......

0.0

% or Nuclide Percentage AR-41 1.63E-02 KR-8511 1.25E-02 KR-85 1.47E+01 XE-133M 1.62E-01 KR-88 6.06E+01 XE-13:!M 1.14E-01 XE-135 2.54E-01 XE-133 2.41E+01 (Gamma)

Limit Period 31-day Quarter Annual greater (Beta))

Limit Period 31-day Quarter Annual greater Admin Admin T. Spec T. Spec %

Limit of Limit Limit of Limit 1.50E-01 1.24E+00 2.OOE-01 9.27E-01 3.75E+00 4.94E-02 5.OOE+00 3.'71E-02 7.50E+00 2.47E-02 1.00E+01 1.85E-02 to total Admin Admin

% T.Spec T.Spec %

Limit of Limit Limit of Limit 3.OOE-01 3.12E-01 4.OOE-01 2.34E-01 7.50E+00 1.25E-02 1.OOE+01 9.35E-03 1.50E+01 6.23E-03 2.OOE+01 4.68E-03 to total Date/Time: 04/21/2006 15:31 retdasID: Retdas LAST Page -

5 32 of 105

RETDAS v3.6.3

<BRA>

V',1SI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID........... :

Period Start Date....:

Period End Date...... :

Period Duration (min):

Coefffcient Type.....

Unit.................

1 All Gas Release Types 01/01/2005 00:00 01/01/2006 00:00 5.256E+05 Historical 2

=== RELEASE DATA =-

Total Release Duration (minutes)...................................... 2.293E+05 Total Release Volume (cf)......................................

2.947E+10 Average Release Flowrate (cfm)......................................

1.285E+05 Average Period Flowrate (cfm)......................................

5.607E+04

=== NUCLIDE DATA =-

Nuclide AR-41 KR-85 XE-133M XE-13:M XE-135 XE-133 F&AG I-131 I-133 Iodine BR-82 Other H-3 H-3 CO-58 P>=8 Total uci 1.26E+03 l.91E+06 2.77E+04 2.62E+04

3. 04E+04 2.50E+06 4.49E+06

9. 18E+00 2.37E+00 1.16E+01 2.57E+00

2. 57E+00 2.88E+08 2.88E+08 4.47E+00 4.47E+00 Average uCi/cc 1.51E-12 2.29E-09 3.32E-11 3.13E-11 3.64E-11 2.99E-09 5.38E-09 1.10E-14 2.84E-15 1.38E-14 3.08E-15 3.08E-15 3.45E-07 3.45E-07 5.36E-15 5.36E-15 ECrcent Ratio 1.51E-04 3.27E-03 5.54E-05 1.57E-05 5.20E-04 5.98E-03 9.99E-03 5.50E-05 2.84E-06 5.79E-05 6.15E-07 6.15E-07 3.45E+00 3.45E+00 5.36E-06 5.36E-06 EC 1.OOE-08

7. OOE-07 6.OOE-07 2.OOE-06 7.OOE-08 5.0OE-07

2. OOE-10 1.OOE-09 5.OOE-09 1.OOE-07

1. OOE-09 2.92E+08 3.50E-07 3.46E+00 Date/Time: 04/21/2006 15:33 retdasID: Retdas Page -

1 33 of 105

RETDAS v3.6.3

<BRA>

V:,SI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID........... :

Period Start Date....:

Period End Date......

Period Duration (min):

Coeff.cient Type.....

Unit...................

1 All Gas 01/01/2005 01/01/2006 5.256E+05 Historical 2

Release Types 00:00 00:00 Date/Time: 04/21/2006 15:33 retdasID: Retdas Page -

2 34 of 105

RETDAS v3.6.3

<BRA>

V'SI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID...........

1 All Gas Release Types Period Start Date.

01/01/2005 00:00 Period End Date......

01/01/2006 00:00 Period Duration (min): 5.256E+05 Coefficient Type.....

Historical Unit.................

2 Receptor

.. : 5 Composite Crit. Receptor -

IP Distance (meters)....

0.0 Compass Point........

0.0

=== PERIOD DOSE BY AGEGROUP,

PATHWAY, ORGAN (mrem)-

Age/Path Bone Liver Thyroid AGPD AINHL AVEG AGMILE:

ACMEAT ACMILE:

TGPD TINHL TVEG TGMILK TCMEA1' TCMILE:

CGPD C INHL CVEG CGMILE CCMEAT CCMILE:

IGPD IINHL IGMILK ICMILE:

9.70E-07 9.27E-09 3.89E-07 1.70E-06 5.13E-08 1.42E-06 9.70E-07 1.30E-08 3.70E-07 3.09E-06 4.27E-08 2.58E-06 9.70E-07 1.77E-08 6.88E-07 7.50E-06 7.91E-08 6.25E-06 9.70E-07 1.40E-08

1. 57E-05 1.31E-05 9.70E-07 7.61E-03 1.37E-02 9.40E-03 1.96E-03 4.61E-03 9.70E-07 7.68E-03 1.56E-02 1.22E-02 1.17E-03 6.00E-03 9.70E-07 6.78E-03 2.43E-02 1.94E-02 1.42E-03 9.51E-03 9.70E-07 3.90E-03 2.94E-02 1.44E-02 9.70E-07 7.61E-03 1.38E-02 1.02E-02 1.99E-03 5.27E-03 9.70E-07 7.68E-03 1.58E-02 1.35E-02 l.19E-03 7.05E-03 9.70E-07 6.78E-03 2.45E-02 2.19E-02 1.44E-03 1.16E-02 9.70E-07 3.90E-03 3.55E-02 1.95E-02 Kidney 9.70E-07 7.61E-03 1.37E-02 9.41E-03 1.96E-03 4.61E-03 9.70E-07 7.68E-03 1.56E-02 1.22E-02 1.17E-03 6.00E-03 9.70E-07 6.78E-03 2.43E-02 1.94E-02 1.42E-03 9.51E-03 9.70E-07 3.90E-03 2.94E-02 1.44E-02 Lung GI-Lli Skin 9.70E-07 7.61E-03 1.37E-02 9.40E-03 1.96E-03

4. 61E-03 9.70E-07 7.68E-03 1.56E-02 1.22E-02 1.17E-03 6.00E-03 9.70E-07 6.78E-03 2.43E-02 1.94E-02 1.42E-03 9.50E-03 9.70E-07 3.90E-03 2.94E-02 1.44E-02 9.70E-07 7.61E-03 1.37E-02 9.40E-03 1.96E-03 4.61E-03 9.70E-07 7.68E-03

1. 56E-02 1.22E-02 1.17E-03 6.00E-03 9.70E-07 6.78E-03 2.43E-02

1. 94E-02 1.42E-03 9.50E-03 9.70E-07 3.90E-03 2.94E-02 1.44E-02 TB

0. OOE+00

0. OOE+00 0.00OE+00

0. OOE+00 0.00OE+00 0.00E+00 0.00OE+00 0.00OE+00

0. OOE+00 0.00OE+00 0.00OE+00

0. OOE+00 0.00OE+00 0.00OE+00 0.00OE+00 0.00OE+00 0.00OE+00 0.00OE+00 0.00OE+00

0. OOE+00 9.'OE-07 7.61E-03

1. 3-7E-02 9.40E-03 1.96E-03

4. 61E-03 9.70E-07

7. 68E-03

1. '6E-02

1. 22E-02

1. -.7E-03

6. (OE-03 9.70E-07 6.78E-03 2.43E-02

1. 94E-02 1.42E-03 9.51E-03 9.70E-07

3. 90E-03 2.94E-02

1. 44E-02

=== PERIOD DOSE BY AGEGROUP, ORGAN (mrem)

=-

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT TEEN CHILD INFANT 4.55E-06 7.07E-06

1. 55E-05 2.97E-05 3.72E-02 4.27E-02 6.13E-02 4.78E-02 3.89E-02 4.52E-02 6.62E-02 5.88E-02 3.72E-02 4.27E-02 6.14E-02 4.78E-02 3.72E-02 4.27E-02 6.13E-02 4.77E-02 3.72E-02 4.27E-02 6.13E-02 4.77E-02

0. 00E+00

0. OOE+00 0.00E+00 0.00E+00 3.72E-02 4.27E-02 6.:.3E-02

4. 77E-02 Date/"?ime: 04/21/2006 15:33 retdasID: Retdas Page -

3 35 of 105

RETDAS v3.6.3

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VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID...........

Period Start Date....:

Period End Date......

Period Duration (min):

Coefficient Type.....

Unit.................

Receptor............

Distance (meters)....:

Compass Point........

1 All Gas Release Types 01/01/2005 00:00 01/01/2006 00:00 5.256E+05 Historical 2

5 Composite Crit. Receptor -

IP 0.0 0.0

=== MAXIMUM PERIOD DOSE TO LIMIT (Any Organ)-

Dose Age Dose Limit Admin Admin

% T.Spec T.Spec %

Period Group Organ (mrem)

Period Limit of Limit Limit of Limit Strt->End CHILD THYROID 6.62E-02 31-day 2.25E-01 2.94E+01 3.OOE-01 2.2'1E+01 Qrtr-: End CHILD THYROID 6.62E-02 Quarter 5.63E+00 1.18E+00 7.50E+00 8.82E-01 Year-,-End CHILD THYROID 6.62E-02 Annual 1.13E+01 5.88E-01 1.50E+01 4.41E-01 Critical Pathway........

2 Vegetation (VEG)

Major Contributors......

0.0

% or greater to total Nuclide Percentage H-3 9.27E+01 CO-58 1.34E-03 I-131 7.29E+00 I-133 1.83E-02

=== MAXIMUM PERIOD DOSE TO LIMIT (Tot Body))

Dose Age Period Group Organ Dose (mrem) 6.______

6.13E-02 6.13E-02 6.13E- 02 Limit Period 31-day Quarter Annual Admin Limit 1.50E-01 5.25E+00 1.05E+01 Admin of Limit 4.09E+01

1. 17E+00 5.84E-01 T. Spec Limit

2. OOE-01

7. 50E+00 1.50E+01 T.Spec %

of Limit

3. 07E+01 8.:.8E-01

4. (09E-01 Strt->-End Qrtr->-End Year-,-End CHILD CHILD CHILD TBODY TBODY TBODY Critical Pathway........

Major Contributors......

Nuclide Percentage H-3 9.99E+01 CO-58 2.54E-03 I-131 1.36E-02 I-133 4.50E-05 2

Vegetation (VEG) 0.0

% or greater to total Date/Time: 04/21/2006 15:33 retdasID: Retdas Page -

4 36 of 105

RETDAS v3.6.3

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GASEOUS RELEASE AND DOSE

SUMMARY

REPORT -

BY UNIT (Composite Critical Receptor -

Limited Analysis)

Release ID........... :

Period Start Date....:

Period End Date......

Period Duration (min):

Coefficient Type.....

Unit................. :

Receptor............. :

Distance (meters)....:

Compass Point........ :

1 All Gas Release Types 01/01/2005 00:00 01/01/2006 00:00 5.256E+05 Historical 2

4 Composite Crit. Receptor -

NG 0.0 0.0

=== MAXIMUM PERIOD NG DOSE TO LIMIT Dose Dose Period.

Dose Type (mrad) t-E____

d_ Ga----ma Strt->End Gamma 2.25E-05 Qrtr->End Gamma 2.25E-05 Year->End Gamma 2.25E-05 Major Contributors......

0.0

% or Nuclidle Percentage AR-41 1.17E+00 KR-85 3.29E+00 XE-13-M 9.10E-01 XE-131M 4.09E-01 XE-13E 5.85E+00 XE-132 8.84E+01 (Gamma)

Limit Period 31-day Quarter Annual greater (Beta))

Limit Period 31-day Quarter Annual greater Admin Admin

% T.Spec T.Spec %

Limit of Limit Limit of Limit 1.50E-01 1.50E-02 2.OOE-01 1.12E-02 3.75E+00 6.OOE-04 5.OOE+00 4.50E-04 7.50E+00 3.OOE-04 1.OOE+01 2.25E-04 to total Admin Admin % T.Spec T.Spec %

Limit of Limit Limit of Limit 3.OOE-01 7.96E-02 4.OOE-01 5.97E-02 7.50E+00 3.19E-03 1.00E+01 2.39E-03 1.50E+01 1.59E-03 2.OOE+01 l.l9E-03 to total

=== MAXIMUM PERIOD NG DOSE TO LIMIT Dose Dose Period Dose Type (mrad) t-_ En Beta Strt-End Beta 2.39E-04 Qrtr-,-End Beta 2.39E-04 Year-,End Beta 2.39E-04 Major Contributors......

0.0

% or Nuclicle Percentage AR-41 6.36E-02 KR-85 5.73E+01 XE-13-M 6.32E-01 XE-133M 4.47E-0l XE-135 1.15E+00 XE-13^

4.04E+01 Date/T1ime: 04/21/2006 15:33 retdasID: Retdas LAST Page -

5 37 of 105

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.....

01/01/2005 00:00 Period End Date.......

01/01/2006 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).....................................

1.45'E+06 Total Undiluted Volume Released (gallons)............................

NA Averacre Undiluted Flowrate (gpm).....................................

NA Total Dilution Volume (gallons)......................................

NA Average Dilution Flowrate (gpm)......................................

NA

=== NUCLIDE DATA Nuclide uCi NB-97 2.30E+00 SB-122 3.19E+01 SB-124 1.70E+02 SB-125 2.02E+03 BA-132-3.68E+00 TE-122-M 7.99E+02 CR-51 8.03E+02 MN-54 2.15E+02 FE-59 7.39E+01 CO-58 9.89E+03 CO-60 2.42E+03 ZR-95 5.14E+01 NB-95 1.79E+02 TE-12'iM 9.52E+03 I-132 3.30E+00 CS-134 6.08E+02 CS-13, 3.83E+02 Gamma 2.72E+04 KR-85 1.74E+03 XE-13_;M 1.22E+01 XE-13'i 2.90E+02 XE-13-;

2.75E+03 D&EG 4.79E+03 H-3 8.81E+08 Date/"lime: 04/21/2006 15:24 retdasID: Retdas Page -

1 38 of 105

RETDAS v3.6.3

<BRA>

VS;SI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS -

BY UNIT) ------

Release ID............ : 1 All Liquid Release Types Period Start Date.....

01/01/2005 00:00 Period. End Date....... : 01/01/2006 00:00 Period. Duration (mins): 5.256E+05

=== NECLIDE DATA =-

Nuclid.e uCi 8.81E+08 Beta Total 8.81E+08 Date/lime: 04/21/2006 15:24 retdasID: Retdas Page -

2 39 of 105

RETDAS' v3.6.3

<BRA>

V',SI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS -

BY UNIT) ------

Release ID............ :

Period Start Date..... :

Period End Date....... :

Period Duration (mins):

1 All Liquid Release Types 01/01/2005 00:00 01/01/2006 00:00 5.256E+05 Unit.......

1 Recept:or.......

0 Liquid Receptor

=== PERIOD DOSE BY AGEGROUP,

PATHWAY, ORGAN (mrem)-

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB APWtr AFWFSp TPWtr TFWFSp CPWtr CFWFSp IPWtr 1.53E-05 1.10E-02 1.48E-05 1.15E-02 4.28E-05 1.42E-02 4.79E-05

1. 95E-02 2.81E-02 1.37E-02 2.67E-02 2.63E-02 2.28E-02 2.59E-02 1.94E-02 8.29E-03 1.37E-02 6.42E-03 2.63E-02 5.43E-03 2.58E-02 1.95E-02 1.76E-02 1.37E-02 1.27E-02 2.63E-02 1.06E-02 2.58E-02 1.94E-02 1.02E-02 1.37E-02 8.71E-03 2.63E-02 7.10E-03 2.58E-02 1.95E-02 2.34E-02 1.37E-02 1.73E-02 2.63E-02 9.21E-03 2.58E-02 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.95E-02 2.34E-02 1.:37E-02 1.50E-02 2.f63E-02

8. 68E-03 2.58E-02

=== PERIOD DOSE BY AGEGROUP, ORGAN (mrem)-

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 1.10E-02 4.75E-02 2.77E-02 3.71E-02 2.97E-02 4.29E-02 0.OOE+00 4.28E-02 TEEN 1.15E-02 4.04E-02 2.01E-02 2.64E-02 2.24E-02 3.10E-02 0.OOE+00 2.:37E-02 CHILD 1.42E-02 4.92E-02 3.17E-02 3.69E-02 3.34E-02 3.55E-02 0.OOE+00 3.50E-02 INFAN"7 4.79E-05 2.59E-02 2.58E-02 2.58E-02 2.58E-02 2.58E-02 0.OOE+00 2.58E-02 Date/Time: 04/21/2006 15:24 retdasID: Retdas Page -

3 40 of 105

RETDAS v3.6.3

<BRA>

V',SI LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS -

BY UNIT) ------

Release ID............

1 All Liquid Release Types Period Start Date.....

01/01/2005 00:00 Period End Date.......

01/01/2006 00:00 Period Duration (mins): 5.256E+05 Unit

1 Recept:or..............

0 Liquid Receptor

=== MAQXIMUM PERIOD DOSE TO LIMIT Dose Period Strt-;-End Qrtr-:-End Year- -End Age Group CHILD-CHILD CHILD CHILD Organ LIVER--

LIVER LIVER LIVER Dose (mrem) 4.92E-0 4.92E-0 4.92E-0 (Any Organ)-

Limit Admin Admin

% T.Spec T.S'pec %

Period Limit of Limit Limit of Limit 2

31-day 1.50E-01 3.28E+01 2.OOE-01 2.46E+01 2

Quarter 3.75E+00 1.31E+00 5.OOE+00 9.83E-01 2

Annual 7.50E+00 6.56E-01 1.00E+01 4.92E-01 Critical Pathway........

Maj or Contributors......

Nuclide Percentage H-3 6.39E+01 CR-51 0.OOE+00 MN-54 4.66E-02 FE-59 1.03E-02 CO-58 4.84E-02 CO-60 3.48E-02 ZR-95 5.19E-07 NB-95 2.36E-03 TE-12'M 5.94E-01 I-132 4.74E-06 CS-134 2.34E+01 CS-137 1.20OE+01 0

Potable Water (PWtr) 0.0

% or greater to total

=== MALXIMUM PERIOD DOSE Dose Age Period Group Organ Strt---End ADULT TBODY Qrtr-,-End ADULT TBODY Year->-End ADULT TBODY TO LIMIT Dose (mrem) 4.28E- 0 4.28E-0 4.28E-0 (Tot Body)

Limit Period 2

31-day 2

Quarter 2

Annual Admin Admin

% T.Spec T.Spec %

Limit of Limit Limit of Limit 4.50E-02 9.51E+01 6.OOE-02 7.: 3E+01 1.13E+00 3.81E+00 1.50E+00 2.85E+00 2.25E+00 1.90E+00 3.OOE+00 1.4'3E+00 Critical Pathway........

1 Fresh Water Fish -

Sport (FFSP)

Major Contributors......

0.0

% or greater to total Nuclicle Percentage H-3 6.42E+01 CR-51 2.36E-02 MN-54 1.32E-02 FE-59 5.14E-03 CO-58 1.50E-01 CO-60 1.04E-01 Date/Time: 04/21/2006 15:24 retdasID: Retdas Page -

4 41 of 105

RETDAS v3.6.3

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VISSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS -

BY UNIT) ------

Release ID............ : 1 All Liquid Release Types Period Start Date.....

01/01/2005 00:00 Period End Date....... : 01/01/2006 00:00 Period Duration (mins): 5.256E+05 Major Contributors...... : 0.0

% or greater to total Nuclide Percentage ZR-95 NB-95 TE-125M I-132 CS-13 4 CS-13' 3.25E-07 1.75E-03 2.41E-01 1.88E-06

2. 57E+01

9. 55E+00 Date/Time: 04/21/2006 15:24 retdasID: Retdas LAST Page -

5 42 of 105

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.....

01/01/2005 00:00 Period End Date....... : 01/01/2006 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)..................................... 1.457E+06 Total Undiluted Volume Released (gallons)............................ NA Average Undiluted Flowrate (gpm)..................................... NA Total Dilution Volume (gallons)...................................... NA Averace Dilution Flowrate (gpm)...................................... NA

=== NUCLIDE DATA Nuclic.e uCi NB-97 2.30E+00 SB-122 3.19E+01 SB-124 1.70E+02 SB-125 2.02E+03 BA-133 3.68E+00 TE-123M 7.99E+02 CR-51 8.03E+02 MN-54 2.15E+02 FE-59 7.39E+01 CO-58 9.89E+03 CO-60 2.42E+03 ZR-95 5.14E+01 NB-95 1.79E+02 TE-125M 9.52E+03 I-132 3.30E+00 CS-134 6.08E+02 CS-13, 3.83E+02 Gamma 2.72E+04 KR-85 1.74E+03 XE-13 M 1.22E+01 XE-13',

2.90E+02 XE 2.75E+03 D&EG 4.79E+03 H-3 8.81E+08 Date/Time: 04/21/2006 15:29 retdasID: Retdas Page -

1 43 of 105

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.....

01/01/2005 00:00 Period End Date....... : 01/01/2006 00:00 Period Duration (mins): 5.256E+05

=== NUCLIDE DATA Nuclidce uCi Beta Total

____E___

8.81E+08 8.81E+08 Date/Time: 04/21/2006 15:29 retdasID: Retdas Page -

2 44 of 105

RETDAS v3.6.3

<BRA>

VS',I LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS -

BY UNIT) ------

Release ID............ : 1 All Liquid Release Types Period Start Date.....

01/01/2005 00:00 Period End Date.......

01/01/2006 00:00 Period Duration (mins): 5.256E+05 Unit.................. : 2 Receptor.......

0 Liquid Receptor

=== PERIOD DOSE BY AGEGROUP,

PATHWAY, ORGAN (mrem)-

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB APWtr AFWFSp TPWtr TFWFSp CPWtr CFWFSp IPWtr 1.53E-05 1.10E-02 1.48E-05 1.15E-02 4.28E-05 1.42E-02 4.79E-05 1.95E-02

2. 81E-02 1.37E-02

2. 67E-02 2.63E-02 2.28E-02 2.59E-02 1.94E-02 8.29E-03 1.37E-02 6.42E-03

2. 63E-02 5.43E-03 2.58E-02 1.95E-02 1.76E-02 1.37E-02 1.27E-02 2.63E-02

1. 06E-02 2.58E-02 1.94E-02 1.02E-02 1.37E-02 8.71E-03 2.63E-02

7. lOE-03 2.58E-02 1.95E-02 2.34E-02 1.37E-02 1.73E-02 2.63E-02 9.21E-03 2.58E-02

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 l.95E-02 2.34E-02 1.3'7E-02 1.50E-02

2. 63E-02

8. 6:3E-03 2.5.3E-02

=== PERIOD DOSE BY AGEGROUF I fVD) I-A7 Agegroup ADULT TEEN CHILD INFANT Bone 1.10E-02 1.15E-02 1.42E-02 4.79E-05 Liver 4.75E-02 4.04E-02 4.92E-02 2.59E-02 r,

une Thyroid 2.77E-02 2.01E-02 3.17E-02 2.58E-02 Kidney 3.71E-02 2.64E-02

3. 69E-02

2. 58E-02 Lung 2.97E-02 2.24E-02 3.34E-02 2.58E-02 GI-Lli 4.29E-02 3.10E-02 3.55E-02 2.58E-02 Skin

0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 (mrem) =

TB 4.2:3E-02

2. 87E-02 3.50E-02 2.5:3E-02 Date/Time: 04/21/2006 15:29 retdasID: Retdas Page -

3 45 of 105

RETDAS v3.6.3

<BRA>

V';SI LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS -

BY UNIT)

Releas e ID............

1 All Liquid Release Types Period Start Date.....

01/01/2005 00:00 Period End Date.......

01/01/2006 00:00 Period Duration (rmins): 5.256E+05 Unit..................

2 Receptor.......

0 O Liquid Receptor

=== MXIMUM PERIOD DOSE T(

Dose Age Period Group Organ O LIMIT (Any Organ)

Dose Limit Admin Admin

% T.Spec T.Spec %

(mrem)

Period Limit of Limit Limit of Limit Strt->End Qrtr->End Year-, -End CHILD CHILD CHILD LIVER LIVER LIVER 4.92E-02 4.92E-02 4.92E-02 31-day Quarter Annual 1.50E-01 3.75E+00 7.50E+00 3.28E+01 1.31E+00 6.56E-01 2.OOE-01

5. OOE+00 1.OOE+01 2.4:6E+01

9. 83E-01 4.92E-01 Critical Pathway.......

Major Contributors.....

Nuclide Percentage 0 Potable Water (PWtr) 0.0

% or greater to total H-3 CR-51 MN-54 FE-59 CO-58 CO-60 ZR-95 NB-95 TE-12'M I-132 CS-13 4 CS-13, 6.39E+01 0.00E+00 4.66E-02 1.03E-02 4.84E-02 3.48E-02 5.19E-07 2.36E-03 5.94E-01

4. 74E-06 2.34E+01 1.20E+01

=== MAIXIMUM PERIOD DOSE Dose Age Period Group Organ Strt-:

End ADULT TBODY Qrtr-:-End ADULT TBODY Year-:-End ADULT TBODY TO LIMIT Dose (mrem) 4.28E-0 4.28E-0 4.28E-0 (Tot Body)

Limit Period 2

31-day 2

Quarter 2

Annual Admin Admin T. Spec T. Spec %

Limit of Limit Limit of Limit 4.50E-02 9.51E+01 6.OOE-02 7.:-3E+01 1.13E+00 3.81E+00 1.50E+00 2.85E+00 2.25E+00 1.90E+00 3.00E+00 1.43E+00 Critical Pathway........

1 Fresh Water Fish -

Sport (FFSP)

Major Contributors......

0.0

% or greater to total Nuclide Percentage H-3 6.42E+01 CR-51 2.36E-02 MN-54 1.32E-02 FE-59 5.14E-03 CO-58 1.50E-01 CO-60 1.04E-01 Date/T'ime: 04/21/2006 15:29 retdasID: Retdas Page -

4 46 of 105

RETDAM v3.6.3

<BRA>

V';SI LIQUID RELEASE AND DOSE

SUMMARY

REPORT (PERIOD BASIS -

BY UNIT)

Release ID............

1 All Liquid Release Types Period Start Date.....

01/01/2005 00:00 Period End Date.......

01/01/2006 00:00 Period Duration (mins): 5.256E+05 Major Contributors......

0.0 Nuclide Percentage

% or greater to total ZR-95 NB-95 TE-125M I-132 CS-13 4 CS-137 3.25E-07 1.75E-03 2.41E-01 1.88E-06 2.57E+01 9.55E+00 Date/r'ime: 04/21/2006 15:29 retdasID: Retdas LAST Page -

5 47 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

ATTACHMENT 1 Tables 7-11 Wind Direction and Stability Classes 48 of 105

Braidwood Nuclear Station Period of Record: Jan.uary - iiarch' ^205 Stability Class - Ext-emely Unstable -

t599Ft-30Ft Delta-T (F)

Wiids lleasured at 34 Feet Wir.d Speed (in mph)

W-4nd Dfi:ecti ?on i-3 4-7 8-12 13-18 19-2L

> 24 Total I

0 0

4 0

0 1

0 a

0 1

0 3

9 0

0 0

12--

ENE ED E

1 0

0 0

7 S

SSW S V W

,nU O

1 23 o

a o

0 t

0 0

19 3

O G

4 0

0 0

4 o

I 4

a a

7

^

3 E

0 13 1

i 4 2

0 a

15 0

4 3

0 0

0 7

1 4

5 A

0 0

ai 0

5 5

0 0

14 o

14 4

a 0

a.

O E

l20 7

0 0

35 NtNW Variable 7otal 0

C.

t'.

0 O

O o

0 2D 0

0 0

2 55 5c 33 2

0 191 t-O-r, of calm in this stability class:

3

-ours of missing wind measurements in this stability class:

a

.0our-of nizzing ztabilitv measurements in all stability classes:

0 49 of 105

Ba-idwood Nuclear Station Pe-iod of Reco-d: January -

March 2005 Stabjlity Class -

Moderately Unatable -

199Ft-3OFt Winds Measured at 34 Feet Delta-T (F)

Wind Direction N

NNE NE Eta ESE SE SSE S

SST-7 SW WSW W

NN' Variable Wind Speed (-n mph) 4-7 8-12 13-18 1-3 0

0 0

I 0

0 0

0 19-24

> 24 Total 2

1 1

0 1

1 1

3 10 7

0 5

1 6

4 4

4

.2 1

4 4

7 6

7 3.3 0

Total 2

96 37 8

0 0

93 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

0 Hours of missing stability measurements in all stability classes:

0 50 of 105

Eraidwood Nuolear :ation Fer-od of R~ecord: January -

March 2005 Class -

Slightly Unzt1le -

199F:-30Ft D.-1-7 (F]

Winds Meamured at 34 Feet W-nd Direotion Wind speed (-n =-h) 48-12 13-18 19-24

> 24 Total.

I 0

0 0

0 1

'nTT 0

0 0

0 2

0 0

0 EIrE i

1.

0 0

0 S

i i

0 1

1 0

0 0

1 0

0 i

0 0

5 0

2 0

5 0

4 0

1 0

0 0

0 1

0 2

0 1

0 B

0 0

2 5

0 0

11 3

5 1

0 0

6 0

12 0

1, 1

0 Vari able 0

0 0

0 e

0 0

11 0

0 2

43 30 0

ES Hoars of Cal= in Hoars of rEiszing Hoar: of rinsing

-hi: 5tability class:

wind masure.-en:t in this stability

.eazurzerents in 0

tabiiti-c1a;s:

0 all E:-

coma es-V 51 of 105

2rald.;:cd Nuuclear S-aticr.

Pericd cf P.ecor: jan&ary - Marc:h ^005 Stabil:ty C:ass N1eutral -

1 -Ft-3CFt Oe' ta-T (F) t';nds Measured at 34 Fees Wind Directic.

1-3 W'ind Speed (ir r..ph)

-7 C-Z I ;- Z '

> ^! r T -- sa N

ll'iE ENE ESE SE ESE ES-SSW WSW I.5.

1. W variablle a

14

1.

AS9 4

45 El 4 B 1_

23 4

2E 5

U 1 2 0

B 2

1 13 9

4 19 03 4

43 0

0 1E 10

.w0 7 3 1

0

_ 3 CY 1 a 0

1 14 1 -11 O

CI 14 I-SE 4

43 12z 0

0 0

45 0

E.1 0

_I; 3 0

73 0

S E 0,

33 0

0 737 0

59 0

£0 0

32 0

57 0

7 -

0 2 02 0

O Tc -:a_

£0 3E9 425 114 E

0 HZE

Hours of calmn in this ssabil- -;y class:

Hours of rnissir.g wnr.d measulrsmer.ts -r.

this Hours of n.-ss-r.g stabil -i:y measursrner.ts

r.

0 s:ability class:

0 all ssability ctasses:

52 of 105

Braidw.,od NTuclear Staticn Pericd cf Record: January - }arch 2005 Stability Class -

Slightly Stable -

199-F-3Et, Delta-T (F)

TWinds Measured at 34 Feet Wind Direction Wind Speed (in mph) 1-3 4-7 E-12 73-18 1 9-2

> 24 Total vITE MiE ENE ESE SE SSE S

SSW SW WSW ITi

,Variable Wotal 11 27 6

4 2

1 1

13 20 12-0 147 17 12 20 29 S

30 8

17 10 14 14 7

29 23 19 0

01 0

1 0

6 1s 14 1e 13 a0 16 I

'7 C

0 0

2 0

0 0

2 o

43 0

21 0

28 0

57 0

31 0

42 0

Z7 0

36 0

38 0

28 0

43 0

32 0

21 0

51 0

44 0

42 0

0 0

574 263 30 Hours of calm in Hours of missing this stability class:

0 wir.d measuremnets in this 5stability class:

0 Hours of missirg stability msasursments Jr. all stability classes:

0 53 of 105

Eraidwood NTuclear 9taticn Ceriod of Record: January -

.'2rch 2005 Stability Clasa - Modezately Btable 199Ft-3OFt Delta-T 1F]

Winds Meamuzed at S4 Feet Wind Sreed (in

=rh)

Wind Direc:ion 1-S 4-7 e-32 12-1e 19--4

> 2Z Total IT 2

0 0

0 a

N1TE 7

0 0

0 7

A 0

0 0

7 EITE 1Z 0

0 0

12 E

1Z 0

0 0

12 ESE 5

1 0

0 0

0 6

BE 0

4 0

0 0

0 4

19E 1

9 0

0 0

0 10 9

0 c

0 0

4 S

0 2

0 0

0 2

2S z

0 1

0 0

0 3

n0 19 0

0 0

0 1

1 32 9

0 0

2 AIT 7

1 0

0 0

0 8

5 0

0 0

0 6

14 2

2 0

0 0

0 5

Variable 0

0 0

c tal 7a 41 3

0 0

0 122 Hours of ca1-in this sability =lass:

0 Hours of =.i'sing wind =easure=entz in this 5:ability c2a2:

0 Hours of =izzing stability neamureent5 in a21 stability classes:

C 54 of 105

Eraidwood Nuclear Staticn exi-cd of Record: January -

Mfarch 2005 Clae -

r-ntreely Stable -

199Ft-30F-Delta. (F]

Winds Measured at 24 Feet Wind Sreed (in =h)

Wind Direction 1-3 4-7 a-12 lS2-le 19 4

> Z4 Total IT ITE ITE E

E9E 9 E 39

.9 WSW Variable V

2 2

1 5

V 0

V 1

10 4

V

-otal 0

0 SO Hours of Cal= In flours of =issing Hours of i.ssing this atability class:

0 wind =masure~ents -n this ztahility class:

0 stabil easure.ents -n all stability classes:

V 55 of 105

Braidwood Nuclear Station Period of Record: January - March 2005 Stability Class -

Extremely Unstable -

199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Uind Speed (in nph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

>.4 Total N

0 0

4 0

0 0

4 Nl:E 0

0 2

0 0

0 2

N-_

0 0

1 0

0 0

1 ENE 0

1 12 3

0 0

le E

0 0

10 0

0 0

10 ESE 0

0 1

3 0

0 4

SE 0

0 2

3 0

0 5

SSE 0

0 2

1 4

0 7

S 0

1 1

3 4

4 13 SSW 1

5 7

0 2

0 15 SW 0

2 2

3 0

0 7

WSW 0

1 3

4 2

2 12 W

0 1

4 5

3 0

13 WNW 0

5 7

S 2

4 23 NH 0

1 11 11 9

1 33 MIN.r 0

0 7

17 0

0 24 Variable 0

0 0

Total 1

17 7

s 58 26 11 189 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

2 Hours of missing stab'lity measurements in all stability classes:

25 56 of 105

Braidwood Nuclear Station Period of Record: January - March 2005 Stability Class -.Ioderately Unstable -

l99Ft-30Ft Winds Measured at 203 Feet Delta-T (F)

Wind Direction N~l NE IJE ENTE E

ESE SE SSE S

SsW SW WSW wzr NW11 Irk nrM1 Variable Wind Speed (in mph) 4-7 8-12 13-18 1-3 0

0 0

1 0

.0 I

0 0

0 1 0 0

0 0

1 1

0 0

2 1

0 0

> 24 Tota:L 4

0 7

2 6

4 2

3 4

8 6

9 9

10 Total 2

i8 39 25 6

1 91 Hcars of calm in this stability class:

Hicurs of missing Hours of missing wind measurements in this stability measurements in 0

stability class:

2 all stability classes:

25 57 of 105

Braidwood Nuclear Station Period oF Record: January - March 2005 Stability Class -

Slightly Unstable -

199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Spe Wind D'irection NM NEE E-E ESE SE SSE SSEi S

5W SW WSW W

Er; 11W InTR Variable 1-3 4-7 0

0 1

0 0

0 1

1 1

3 1

1 1

1 2

0 1

2

.2 4

1 0

eed (in mph) 8-12 13-18 o

1 1

0 3

0 0

0 3

1 7

1 0

1 1

1 0

1 o

0 1

1 3

1 1

1 3

3 7

2 a

4 0

0 19-2 4 0

0 0

0 2

0 0

1 0

4 2

0 0

> 24 0

0 0

1 0

0 0

1 0

0 0

0 Total 1

2 5

1 7

3 2

3 4

2 5

12

'I5 1 3 0

Total 1

22 32 18 8

2 63 Ecurn of calm in this Hours of missing wind stability class:

measurements in this 0

stability class:

I all stability classes:

Houris of missing stability measurements in 25 58 of 105

Braidwood Nuclear Station Period of Recc-d: January -

M.arch 2005 5sabi-lisy Class -

NTeu:ral -

199Fs-313Fs Delza-T- (F)

Winds 'Measured a _203 Fees Wind Speed (:r. mph-)

Win-d Direction N

21-1 ENE E

ESE SE SSE S

SSW SW Vl5W W112r ir; Variable 1-3 4-7 a-i:

1 10 15 3

7 3E 1

3 51 c

16 32 1

12 30 1

10 12_

0 3

r 1

0 10 0

2 1i 0

0 5

1 3

17

.1 6

10 0

12 13 0

6 15 1

7 513 1

l0 59 0

0 0

1I

_3-18 19-24

> 24 Toacl 11 11 1 _

0 306 7

5 G

22

11 13 E

10 3

2 1 2 2 25 14 13

-2 S

7 11 G

16 277 411 0

G 0

48E 0

65 0

1 7 0

9 1 o

48 0

56 0

30 0

24 7

59 c

5£ 3

449 l

3-3 3

48 59 1

112 1

106 0

0 Total 1i 1 G7 379 323 141 27 995 Hc~u-z cf calr. _n Hlcu-s c: nissir.

licurs cf nissir.n this stability class:

wind measurenents in this stabili;r m.easurernents in stability cla ss:

7 all Stability classes:

59 of 105

Braidwood Nuclear Station Period of Record: January - March 2005 Stability Class -

Slightly Stable -

199Ft-30Ft Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 N

0 1-121E 0

NE 0

ENE N

E 1

ESE 1

SE 0

SSE 0

5 1

55S 1

SW 2

WSW 0

W 1

WIMn 1

2i1K' 0

NIIIN 1

Variable 0

8 6

8 9

13 5

6 7

2 1

2 2

4 7

0 8-12 13-18 30 1

13 2

19 0

25 1

24 1

14 22 6

8 9

22 5

21 3

11 11 14 8

19 6

8 6

10 48 6

24 10 o

o 19-274 0

0 1

0 0

3 4

7 E

11 7

2 3

S

.1 3

0

> 24 0

0 0

0 7

0 0

0

_0 0

Total 29 211 28 27 2 9 45 24 45 44 34 3 6 20 24 45 0

Total 11 E3 251 156 55 16 5712 Hours of calm in this stability class:

Hours of missina Hours of missina wind measurements in this stability measurements in 0

stability class:

13 all stability classes:

25 60 of 105

Biraidw-o-nl Nul-zlear Station Period of Reccrd: Januarv - Yarch 2'305 Stabil::yt Class - %oderately Stable -

19Ft-3OFt Del'a-T- (F) xinda Mea!ured at 203 Feet Nind D:rect+/-.on 1

NNlE ITZ_

ENE E

ESE SSE S

SSW WSW IIF5-W NN; Variab'le Wind SF 1-3

'-7 0-0 0

1 4

0 1

0 0

0 1

0 0

1 3

3 6

1 0 1

4 6

2 0

0 2

0 eed I'r.

mph)l 3_1-,

13-13 3

1 CI 1

0 1

C0 4

r 27 1

2 1

5 1

2 o

1 E

S 10 2

a 1

7 0

o cO 19-24 O

O C,

C, C,

0 0

> 2 4 0

0 0

IG-aJ.

5 6

14 IC 6

9

_ 4 9

0 Tot a 11 43 il 19 2

0 136 Hicurs c-caCl. -n this stability class:

icurs Crnissir:a ir mr.easureerlnts in th.is licurs c-- nissir.g stability m.easurements in 3

ssabilisy class:

2 all stability classes:

25 61 of 105

3Baidwood N1uclear Stat:on Stability Wind Direction 2eriod of Reccrd: January - Ma-ch 2OD5 Cla¢s

- Exzereely S:able - 1c9-t-3CFt Delta-T Winds Meamured a-2'C3 Feet Wind Speed (ir mph)

(F) 1-3 4-7 8-1 _

3-18 1?-24

> 24 Tozal 0

O

'0 0

CI I

0 n

ME=

7 1

2 1

4 NE 1

i0 0

1 2

C X,,

0 2

E 1

1 El Q

1 ESE 2

0 0

3 0

3 C

-0 D

I) 5 S SE S

SSW SW W5W 3

C0 0

4 0

0 0

2 0

0 0

0 I) 0 1

0 1

O 0

CI 0

0 1

0 C,

0 1

C.

CD C

C1 0

co 0

0 1

WINr NW; S

C 0

C 2

1 Ci 3

0 0

Cam 0

S CI 0

S3 Va ri ab' e Cl 0

co 7

2A0 13 co 0

40 ieCirs cf calm Zn this EcUrs c-- nissir.g w;ind stability class:

measurernents in this tabii_

-'iclass:

all stability classes:

Iic1ars c-missina stability measurements in S5 62 of 105

Braidwood Nuclear Station Period of Record: 7pril -

June 2005 Stability Class -

Extremely Unstable -

199Ft-3OFt Delta-T (F)

Winds lleasured at 34 Feet 14nd Speed (in mph)

Ilind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total 1U 0

1 6

0 0

9 NJNE 0

8 13 9

0 0

30 NE 0

24 12 2

0 0

38 ENE 1

19 2

0 0

0 2Z E

0 21 6

0 0

0 27 ESE 0

8 a

0 0

0 1C SE 1

12 a

0 0

0 Z1 SSE 0

1S 15 1

0 0

31 S

1 30 27 1

0 0

59 SSN 1

16 19 1Z 1

0 49 Sl 1

12 9

0 0

29 WSZ 5

18 9

0 0

34 IJ 0

12 32 13 0

0 57 MW Z

9 39 3

0 0

53 NWI 0

10 12 S

0 0

27 NMI 0

9 2

9 0

0 20 Variable 0

0 0

Total 9

211 228 73 1

0 522 Fours of calm in this stability class:

0 Xours of missing wind measurements in this stability class:

0 Hours of missing stability measurements in all stability classes:

0 63 of 105

Braidood Nuclear Station Pericd of Record: April -

June 2005 Stability Class -

Moderately Unstable -

199Ft-30Ft Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in Wind Direction 1-3 N

0 NIlE 0

IJE 2

EItE 2

E 0

ESE 0

SE 0

SSE 0

S 0

55W 0

SW 0

WSW 2

W 1

Wnrii 0

N`W 0

iNm; 0

Variable 0

4-7 0

3 2

9 3

0 5

5 5

3 4

1 5

a 0

0 8-12 1

4 2

0 2

3 2

4 4

r 0

0 mph) 13-la 0

4 1

0 0

0 2

1 3

1 1

1 4

0 19-24

> 24 Total 1

8 9

11 S

0 7

9 8

27 7

6 8

5 4

0 Total 7

48 39 24 0

0 lie Hours of calm in this stability class:

0 Hours of missina wind measurements in this stability class:

0 Hours of missing stability measurements in all stability classes:

0 64 of 105

3raidwood Nuclear Station Period of Record: Ap-ril - June 2005 Stability Class -

Slightly Unstable -

199Ft-3OFt Winds Measured at 34 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total N

I)

C 2

C C!

C!

IflTE 0

ItE ENE E

ESE SE SSE S

S 55, SW wSW W

8 4

3 3

4 5

1 4

0 2

2 4

4 C,

0 C!

0 2.3 0

4 0

0 4

0 0

5 0

I) 1

,.0 1

1 0

3 3

0 2

3 0

1 1

2.

0 0

C!

0 0

0 4

6 0

Q 0

8 0

5 0

2 0

3 3

0

1 w!Thi NN-k; Variabl e 1

0 0

0 2

12 1

C, 0

1 1

3 co 5

0 0

0

!8 0

2 0

6 0

0 0

Total c

39 43 19 CI 0

107 Hours of calm in Hours of missing Hcurs of missing this stability class:

wind measurements in this stability m.easureraents in stability class:

0 all stability classes:

0 65 of 105

Braidwo:d N-tuclear Statrin Pericd *f '.ecord: AF-.2 - June ^CC25 Szabil-::y Class -

Neu,:ral -

19Ft-30F: Delta-(F)

Winds Measured az 34 Fee:

wi.nd Spe~

Wind Drrectlon 1-3 N

2 NNF 0

2.1_

4 E!JE 1'

E 13 SE 3

SSE 3

S 3

SS 0

SW 1

WSW 1

4 Tf,,24r; 1

11; 2

1nrA,;

0 Variable ed (in -rph)

,3-, z!

I 3 - I 19-24

> 24 ICt-l 26 1

A 9

'5 15 E

3 4

2 6 7

9 1

C 10 24 40 3

12 2 0 1'z 17 15 1 9 1_

10 3

0 14 13 I

C' C'

C1 3

6 7

2 5

2 C

5 C

0 26 o

67-0 47 0

3E LI-24 0

2_4 0

2t 10 31 0

24 0

34 0

35 0

31 0

21 0

24 0

co Tctal 50 1CE 23 licurs c4 c-lr. In thns stability class:

59 0

31 0

licurs c-nissirc w..i-nd reasurenents in this szabilizy class:

C licu-E c_ nissing stability reasurenents in all stabilisy classes:

0 66 of 105

Braidwood 1luclear Station Pe:iod of Record: April -

June ZOOS Stability Class -

Slightly Stable -

199Ft-3OFt relta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Nind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total t

4 4

1 0

0 0

9 NITE S

28 5

0 0

0 38 IJ 5

31 1

0 0

0 37 ENE 10 21 0

0 0

0 31 E

'0 5

2 0

0 0

.7 ESE 10 24 12 0

0 0

4C SE 6

41 4

0 0

0 51 SSE 3

33 18 0

0 0

59 S

3 32 47 2

0 0

84 SSW 0

18 31 0

0 0

49 SW 0

14 13 0

0 0

27 WSW 6

29 8

0 0

0 43 N

9 22 11 1

0 0

43 TV 6

14 3

0 0

0 3

NU 2

3 3

0 0

0 a

MtI1 2

3 0

0 0

e Variable 0

0 0

Total 90 326 162 3

0 0

581 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

0 Hours of missing stability measurements in all stability classes:

0 67 of 105

Braidw^ood Nuclear Station Period of Record: April -

June 2005 Stability Class -

Moderately Stable -

199Ft-30Ft Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wiind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total N

9 N1TE NE ENE 4

4 1

5 0

1 3

0 0

0 10 0

0 0

9 0

4 0

7 E

0 22 ESE SE SSE SSW 14 10 5

21 6

4 5

1 4

1 5

8 0

1 0

0 0

24 0

L7 0

IO 0

S 4

LO 0

9 WSW 6

14 0

0 0

16 20 0

0 0

0 26 WINW INrx 10 3

2 0

114 1

1 0

0 75 0

0 0

0

11 0

4 0

Variable Total 0

0 1

0 190 Hours of calm in Hours of missing Hours of nissing this stability class:

wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

0 68 of 105

Braidwood nuclear Station Period of Record: April - June 2005 Stability Class -

Extremely Stable Winds Measured at l99Ft-3OFt Delta-T (F) 34 Feet Wind Speed (in mph)

Wind Direction IINc 22JE NE ENE E

ESE SE SSE sW SW WSW WIri IrK Variable 1-3 4-7 1

0 11 0

3 0

0 1

3 1

0 0

2 0

0 1

2 1

0 0

1 0

0 0

8-12 0

0 0

13-18 19-24

> 24 Total o

0 o

o o

0 o

0 0

o 0

0 0

1 2

7 4

0 0

1 3

C 21 0

Total 4E 7

0 0

53 Hours of calm in this stability class:

Hours of missing wind measurements in this Hours of missing stability measurements in 0

stability class:

0 all stability classes:

0 69 of 105

Braidwood nuclear Station Period of Record: April -

June 2005 Stability Class -

Extremely Unstable -

l99Ft-30Ft Delta-I (F)

Winds Measured at 203 Feet Wind Direction Wind Speed (in mph) 1-3 4-7 8-12 13-18 19-24

> 24 Total.

M NINE NE ENE E

ESE SE SSE S

SSW SW WSW W

MNW i"nw Variable Total 0

2 5

0 2

6 0

10 15 0

14 13 o

9 12 1

1 6

1 8

9 0

8 10 0

17 33 1

10 8

0 7

b 0

5 3

0 9

6 0

5 11 0

2 15 0

3 7

0 0

0 4

10 5

5 2

6 5

10 16 13 21 28 24 13 1

0 171 1

7 2

0 3

1 0

10 3

6 S

6 11 0

62 0

12 0

25 0

32 0

32 o

26 0

17 0

-2 0

24 0

66 3

45 0

24 0

35 1

49 4

50 0

41 0

17 0

0 8

523 3

112 167 Hours of calm in Hours of missing Hours of missing this stability class:

wind measurements in this stability measurements in 0

stability class:

2 all stability classes:

0 70 of 105

Braid-ood 2Juclear Station Period of Record: April -

June 2005 Stability Class - Hoderately Unstable 199Ft-30Ft Delta-l JF)

Hinds M!easured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total U

0 0

0 1

0 0

1 0

2 1

0 0

0 3

RE 0

1 3

3 4

1 12 ENE 1

z 3

0 0

0 10 E

0 4

0 3

0 0

7 ESE 1

0 1

0 0

0 SE 0

3 2

1 0

0 E

SSE 0

1 5

4 0

0 10 S

0 1

4 1

0 2

8 SSW 0

3 5

3 0

1 12 SW 1

0 3

2 3

0 9

WSW 1

0 1

3 1

0 e

H 1

Z 2

3 5

1 14 0rrf o

1 2

z 3

0 8

0 1

1 3

1 1

7 NrW0 0

0 0

4 0

4 Variable 0

0 0

Total 5

25 33 29 21 E

119 Hours of calmr in this stability class:

0 Hours of missirg wind neasurements in this stability class:

0 Fours of missing stability measurements in all stability classes:

0 71 of 105

Braidwood Nuclear Station Period of Record: April -

June 2005 Stability Class -

Slightly Unstable -

199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in rnph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total 11 NE SEE E

E5E SE SSE 55 SW WSW SW NW Variable 0

0 Z

0 1

4 1

1 6

2 1

Z 0

1 2

0 1

Z 0

4 3

0 1

2 1

0 3

0 0

1 0

0 1

0 0

0 1

Z 0

0 0

3 1

0 1

0 0

0 1

2 2

1 2

3 0

1 0

3 Z

0 a

3 0

13 0

0 5

1 0

S 1

0 e

0 0

9 0

0 4

2 1

9 I

0 0

3 1

0 7

8 10 1

-2 1

0 0

3 1

4 0

5 0

0 0

0 Total e

12 32 29

f 3

108 Hours of call in Hours of mimssing Hours of missing this stability class:

0 wind measurements in this stability class:

0 stability measurements in. all stability classes:

0 72 of 105

Braidwood Nuclear Station Period of Record: April -

June 2005 Stability Class -

Neutral -

199Ft-30Ft Winds Measured at 203 Feet Delta-T (F)

Wind Speed (in mph)

Wind Direction NUE NE ENE E

ESE SE SSE S

S SM SW WSW NW NUTIN Vari+/-able 1-3 4-7 1

0 1

2 1

0 1

1 1

0 0

2 1

6 13 24 3

5 3

0 12 1

0 8-12 13-18 2

10 10 13 Z2 34 1C 10 14 10 7

e 9

7 Et 7

e 17 4

14 16 10 1Z 11 4

10 8

24 6

10 0

e 0

0 19-24 14 9

15 0

9 2

0 4

7 8

3 S

0 24 0

0 0

0 1

3 0

0 1

5 1

0 0

1 0

0 Total 29 33 79 40 57 29 23 20 30 31 3S

_8 S

44 19 13 0

Total 13 67 145 199 98 12 534 Hcurs of calm in thIs stabIlity class:

Mours of missing Hlours of miassing wind measurements in this stability measurements in 0

stability class:

0 all stability classes:

0 73 of 105

Braidwood l;clear Station Period of Record: April -

June 2005 Stability Class -

Sligh.tly Stable -

t 99Ft-30Ft Delta-T (F)

Winds Mteasured at 203 Feet W.ind Speed (in nph)

i. _.. m Direction 1.;z E

ESE SE SSE S

SSW WSW WNIW a-N e

Variable 1-3 e-7 8-12 13-18 19-24

> 24 Total 3

0 1S 10 12¢ 30 c

121 14 13 1'

Z7 7

18 8

4E 8

1E C

1 c

17 e

1 4

0 0

ID 0

0 0

1 7

14 11 0

1 1

1 0

0 0

E 0

2C 0

34 0

47 0

33 4

41 0

4 f 0

0 8S 0

0 37 0

41 0

27 0

13 0

0 0

Total Hours of calm in this stability class:

!ioura of misasing wind measurements in this Hours of missing stability measurements in 0

stability class:

I all stability classes:

0 74 of 105

Braidw0od Nuclear Station Per-od of Record: April -

June 2005 StabiLi4tv Class -

M-oderate'1y Stable 159Ft-3OFt Winds l-Measured at 203 Feet Delta-T (F)

Wind Speed (In mph)

D;rection 4-7 8

-to-,

13-1 8 I S --14.

> 24 Total 0

0 0

0 8

NNE_

0 i

0 0

7 NE WEN i

7 0

0 0

a 1

E 3

10 0) 0 0

0 0

14 0

12

'D 14 o

0

.3 ESE C.

i I

7 14-7 1-0 0

0 0

0 71 S

0 0

SSW SW WSW 0

4 3

ri 0

7 0

I 0

0 12 0

14 I

I 0

W 0

.1 IC 13 WITH 0

5 is

^.

10 NWH E

0 0

0 1e 0

2E 0

14 Nhw*

Variable Total 0

0 3

0 0

C 0

0 4

45 10^

0 21SI

.ouxs of Hiours of Mou=e of calmn nmssn'a n' s E L-n th:4z stability class:

wind measurenents in this stability neasurenents in 0

stability class:

3 all stability classes:

0 75 of 105

Braldwood 1uclear Station Period of Record: April -

Ju:ne 2005 Stability Class -

Extremely Stable -

lFSFt-30Ft Delta--

(r)

'inds Measured at 203 teet Wind Speed (ir.

mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total N

0 2

1 0

0 0

3 I:R C

0 0

0 3

R_

3 4

+/-

0 0

a ENT 0

1 2

0 0

0 3

E 0

S 3

0 0

0 4

ESE 0

1 1

7 0

0 9

S_

0 0

4

^

O O

e SS_

3 3

1 0

0 9

S 1

0 0

0 1

SS.

2 2

0 0

0 G SW 0

1 0

0 0

1 IISW 0

0 C

CE J

0 3

^

1 0

0 e

0IM O

3 3

0 0

0 e

MO 1

1 1

0 0

0 3

NMI 0

2 2

O 0

C 4

Variable O

0 0

Total 7

27 32

1.

0 0

7S Eours of calm in this stabIlity class:

a Fours of mitssrn wind measurements in this stability class:

0 Hiours of nmsisln stabIlIty measurements in all stability classes:

0 76 of 105

Braidwood Nuclear Station Period of Record: July -

September 2005 Stability Class -

Moderately Unstable -

199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Direction N

ENE NE ENE E

ESE SE SSE SW SW NW NNW Variable Wind 1-3 4-7 0

0 1

1 2

3 1

1 0

0 1

1 0

1 1

0 0

6 9

10 3

5 1

6 1

3 1

6 0

7 3

0 Speed (in mph) 8-12 13-18 0

0 4

0 5

0 o

0 0

0 o

o 0

0 0

0 1

0 2

1 7

1 3

0 0

0 1

0 2

0 0

0 19-24 0

0 0

0

0 0

0 0

> 24 0

0 0

Total 6

13 16 4

7 4

S 3

7 4

12 S

6 2

9 5

0 Total 13 67 26 0

0 108 flours of calm in this stability class:

0 flours of missing wind measurements in this stability class:

0 Hlours of missing stability measurements in all stability classes:

0 77 of 105

Braidwood Nuclear Period of Record: July -

Stability Class -

Extremely Unstable Winds 1Measured at Station September 005 159Ft-3OFt 34 Feet Delta-T (F)

Wind Direction NNE NE ENE E

ESE SE SSE SS-NSW SW W;tN WUWW Variable Total Wind Speed (in mph) 4-7 8-12 13-18 L-3 19-24

> 24 Total 1

13 1

6 3

13 1

15 Z

14 1

10 3

16 0

34 1

41 1

13 1

13 0

15 37 2

31 3

33 0

22 O

0 4

0 0

0 18 11 0

0 0

18 S

0 0

0 22 o

0 0

0 le o

0 0

0 le 2

0 0

0 13 1

0 0

0 20 1

0 0

0 35 9

0 0

0 51 34 2

0 0

S0 Z

0 0

41 10 0

0 0

25 le 1

0 0

56 1Z 0

0 0

45 8

0 0

0 44 12 0

0 0

34 00 0

0 0

t51 5

0 0

504 22 326 1

Hours of calm in this stability class:

0 Hours of missing Hours of missing wind measurements in this stability class:

0 stability measurements in all stability classes:

0 78 of 105

5ra'dwood 7l:clear Statior Period of Record: July -

September 20v5 Stabil ty C an

- SlIghtly Unstable 199Ft-3OFt Delta-: (8F

. indz tlea:z!ed at 34 Feet Wind Speed (in mph)

DIrectIon 1-3 4-7 3-12 13-18 l9-Z4

> :4 Tc II 0

£ 2

0 0

0 N N C

4 0

0 0

NE 0

3 C

0 0

0

tal 3

f C

ESS E

ES_

SSE SS S;W NSN ail Va:'iable 4

1 4

o a

a o

a a

a 0

0 o

a a

o a

a o

0 0

o a

a a

0 o

a a,

o a

a o

a a

o a

a 11 3

SZI 0

0 2

C 0

3 O

2 3

1 2

o a

o 1

£ C

o a

o A

8 1 1 a

Total 1

S 3 17 0

a 88 ourzs of calm in this stabIlIty class:

Hours of nlssiln; ¶nnd measurements in this Hours of =42i.sn; stabl ity measuremnenta in stability class:

0 all stability classes:

0 79 of 105

Braidwood Nuclear Static.n Period of Record: July - Septenber 2005 Stability Clazs -

Neutral 199Ft-3OFt Del!ta-(1-)

Winds lleasured at 34 Feet Wind Speed (im mph)

Direction 1-3 4-7 8-12 13-18 1S-24

> 24 Total N

2 t

12 0

10 0

2 0IJ_

G 34 27 0

0 0

El NEl 4

38 14 0

0 0

se ENE 10 2

0 0

32 11 7

0 0

18 ESE t

7 0

0 0

0 15 Se 60 0

0 0

0 lc SSE 2

- 4 3

0 0

0 19 S

0 17 8

0 0

0 25 SSW 0

4 0

0 33 Si 2

7 12 2

0 0

23 WST-5 4

0 0

0 10 W

5 2

0 0

0 c

T-,NW 4

7 0

0 0

0 11 NW 7

4 1

0 0

is NNW 7

15 E

3 0

0 28 Variable 0

0 0

_otal 3

207 117 7

0 0

404

ou-a of calm in th:: stability class:

0

-ours of mis.i:n2 wrnd measurements in this stability class:

0

-ours of nisasrg stability measurements in all stability classes:

0 80 of 105

8:radwood Nuclear Period of Record: July -

Stability Claas -

Slightly Stable Station September 2005 lS9Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction Il UNE NE ESE E

ESE 5E SSE 55 SSW ST-7 WSW NW N7U7 Variable Total 1-3 9

14 22 35 36

_7 12 7

1 3

.7 11 17 13 12 0

4-7 8-1Z 13-18 19-24 18 1

0 0

37 1

0 0

13 0

0 0

9 0

0 0

1 0

0 0

2:

0 0

0 17 0

0 0

65 10 0

0 65 30 0

0

> 2' 0

0 0

0 4

Total 28 52 40 44 37 44 24

) 7 102 42 22 Z 22 27 23 19 17 13 13 14 10 9

7 0

24 0

6 0

2 0

0 0

1 0

0 0

o 0

0 0

228 335 77 0

0 0

e40 Eours of calm in this stability class:

0 Hours of missing Hours of missing wind measurements in this stability class:

0 stability measurements in all stability classes:

0 81 of 105

Braidwood Nuclear Station Period of Record: July -

September C005 5tabil'ty Class - lloterately Stable

- lFt-30Ft relta-.

(F)

Winds Measured at 34 Feet WInd =peed (in Direction 11 UN _

ENE

.ES--

lE ESE S2 SEW S3't U

WNWt Variable

otal i -3 i-7 14 3

1o 3

10

'Z 13 0

27 0

13 14 14

!3 4

1 11 5

6 11 2

a 0

13 C

71 t

0 0

. 0 0

C 0

0 0

0 nph) 13-le 0

0 a

0 0

0 19-.S 0

0 0

0

> 24 Total 0

17 0

13 0

10 C

13 0

27 0

33 0

27-0 2-7 0

11 0

13 I

9 0

11 0

13 0

e 0

13 0

a 0

0 0

1 0

0 0

0 C

0 0

0 1la 7 E 1

0 0

0 z5a Hours of calm in thIs stabIlIty class:

Hours of nLssain wind neasurements in this Hours of mLssiln stab-lity neasurements in 0

stability class:

a all stability classes:

0 82 of 105

Braldwood Nuclear Station Period of Record: July -

September 2005 Stability Class -

Extremely Stable 195Ft-30Ft Delta-T (F)

Winds IUeasured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total 1;

3 0

0 0

3 NITE 7

1 0

0 0

0 a

NE 5

0 0

0 5

ENE 0

0 0

E ll 1

0 0

12 ESE 7

2 0

0 0

0 9

SE 2

2 0

0 0

0 4

SSE 0

0 0

S 0

0 0

SSW 0

4 0

0 0

0 4

SW 2

0 0

0 2

WSW 5

5 0

0 0

0 10 W

7 0

0 0

7 W8 0

0 0

a 11W 9

0 0

0 9

MMW 1

0 0

0 1

Variable 0

0 0

rotal 67 1S 0

0 0

0 e2 Fours of calm in this stability class:

0 Fours of missing wind measurements in this stability class:

0 Hours of missing stability measurements in all stability classes:

0 83 of 105

Braidwood nuclear Station Pertod of Record:

July September 2005 Stab4lity Class Extremely Unstable 199Ft-3OFt Winds Measured at 203 Feet Delta-T (F)

Wind Direction N

NlNE IE ENE E

ESE:

SE SSE S

sSST ST7 WSW W

larial Variable Wind Speed (In rip 1-3 4-7 a-12 I:

0 0

1 0

3 0

1 1

0 0

1 0

0 4

4 12 8

a 13

-4 2 1 6

7 9

28 23 11 Z2 0

8 7

9 8

2 10 31 14 10

'11 16 17 23 11 0

,h) 3-18 19-24 o

o 3

0 7

0 o

o 3

0 1

0 2

0 0

0 e

0 27 2

11 7

0 9

0 8

1 10 0

e 0

0 0

> 24 0

0 0

0 Total 12 14 20 1S 35 58 49 30 27 54 49 45 37 0

Total 203 191 100 S

0 507 Hours of calm In this stability class:

0 Hours of missing wind measurements In this stability class:

4 Hours of missing stability measurements in all stability classes:

0 84 of 105

Braidwood Nuclear Station Period of Record: July -

September 2005 Stab4lity Class -

M4oderately Unstable 199Ft-3OFt Delta-T Wir.ds Mieasured at 203 Feet (F)

Wind Direction 7

ITE E

ESE E

ESE SE 55E S

SSN

WSN, U

W NNW Variable

.otal Wind Speed (in mph) 4-7 8-12 13-18 1-3 19-24

> Z4 Total 0

4 1

0 6

3 1

6 1

3 3

1 5

2 1

0 0

5 0

1 2

1 0

2 2

0 1

5 0

2 1

0 2

1 2

4 2

1 0

I) 0 2

3 1

5

3 0

0 0

0 5

Z 0

0 10 6

0 0

16 0

0 0

7 0

0 0

e 0

0 0

3 O

0 0

5 0

0 0

4 1

0 0

5 2

1 0

9 2

3 0

a 1

0 0

4 1

0 0

9 0

0 3

0 0

0 o

9 0

0 11 46 32 18 4

0 111 Hours of calm in this stability class:

Hours of missing wind measurements in this Hours of missing stability measurements in 0

stability class:

0 all stability classes:

0 85 of 105

Braidwqood Nuclear Statlor.

Period of Record: July -

September 2005 3tabtlity Class -

Slightly Unstable 199Ft-3OFt WNrds tleaaured at 203 Feet Delta-C (F)

Wind Speed (In mph)

Wind Direction IIJE ENSE E

ESE SE SSW VWSW VW NW Var-able Total 1-3 4-7 0

4 0

3 0

1 0

7 3

1 I

0 2

0 0

2 0

0 5

0 0

8 0 S

1 0

4 I

3 I

3 0

13-18

+/-

1 1

1 3

0 13 19-24 0

0 0

a 0

0 0

0 1

0 0

0 a

> 2-4 0

0 0

a 0

0 0

0 C

0 0

0 Total 5

4 11 f

S 8

5 Is S

0 10 0

0 5

36 33 14 Z

0 50 Hours of calm in this stability class:

0 Hours of m rssing wind measurements in this stability class:

1 Hours of msitn;g stabiltty measurements in all stability classes:

86 of 105 0

Braidwood Nuclear Station Period of Record: July -

September 2005 Stability Class -

Neutral

'5SFt-3OFt tWinds Mleasured at 203 Feet Delta-T (F)

Wind Direction IMNE NE EUE NE ESE SE SSE SSE SW SW WSW 1.1 III NNW Variable Total Wind Speed (in mph) 4-7 8-12 13-le 1-3 o

11 10 e

2 9

16 19 0

9 33 21 2

11 23 1

3 10 10 0

0 10 7

1 0

12 7

1 0

4 10 5

0 2

13 7

0 1

7 24 0

2 e

E 0

2 4

3 0

4 2

1 5

0 7

7 4

4 S

9 3

0 0

9-:4

> 24 Total 1

0 28 0

0 if 0

0

£3 0

0 37 0

0 23 0

0 1s 0

0 20 0

0 19 0

0

-2 11 0

43 0

0 14 0

0 9

0 0

7 0

0 11 4

1 23 0

0 21 0

0 0

13 101 169 104 16 404 Hours of calm in this stability class:

Hours of missing wind measurements in this Xours of missing stability measurements in 0

stability class:

0 all stability classes:

0 87 of 105

Braidwood Nuclear Station Period of Record: July -

September 2005 Stability Class - Slightly Stable l9FFt-3OFt Delta-T (F)

W'nds leasured. at :03 Feet tinr.d Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total N

NNE ENE E

ESE SE SSE 5

SStU St7 WSW W111W Variable Total 0

F 16 1

8 25 0

7 37 2

IC 2a 0

21 0

S 1S 0

e 21 o

c 30 0

7 2

1 2

27 1

4 11 1

4 8

2 13 lf 0

4 14 0

10 12 2

C 13 0

0 0

0 Z5 4

0 0

38 3

0 0

47 0

0 0

4E 1

0 0

48 14 0

0 37 E

0 0

33 33 1

0 73 53 2

0 88 41 2

0 73 5

3 0

24 2

0 0

15 4

0 0

35 3

0 0

21 3

0 0

25 0

0 0

21 0

0 0

0 10 131 328 172 0

e49 Hours of calm in Hours of missing this stability class:

0 wind measurements in this stability class:

1 Hours of missing stability measurements in all stability classes:

0 88 of 105

Braidwood luclear Station Pe:Iod of Record: July -

September 2005 Stability Class -

IModerately Stable 199Ft-30Ft Winds Measu-ed at 203 Feet Delta-T (F)

Wind Speed (In mph)

Wi-nd Direction N

ENE tIE ESE SE 3SE 55 5511 SU W

1i-.

VraU Variable 1-3 0

0 0

0 C,.

O 0

0 1

+/-

'I 0

0 0

i-7

.3-1.1 13-1S 1"-.4 4

10 1

0 4

13 0

0 4

11 0

0 13 e

0 0

8 14 2

0 1

FE 11 0

3 21 5

0 9

17 3

0 3

18 3

0 3

1S 3

0 3

2 S

0 1

0 3

0 0

S 4

0 1

13 2

0 1

4 1

0 1

9 1

0 0

> 214 0

0 C

0 0

'2 0

0 io 0

03 0

0 0

0 Total 1S 17 is 21 24 29 2ZS ZP 10 8

17 e

11 0

2otal' 59 177 44 0

,sE Houra of calm in this stabilIty class:

0 Hours of misasn; wind measurements in this stability class:

0 Houra of mIssIng stabIlity measurements in all stability classes:

89 of 105

Braidwood Nuclear Station Period of Record: July -

September 2005 Stability Class -

Extremely Stable 199Ft-30Ft Delta-- (F)

Winds Measured at 203 Feet Wind Speed (ir. mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total N

0 S

3 0

0 0

8 1.t1E 1

S 3

0 0

0 8

NTE 0

e 2

3 0

0 11 ENE 2

0 1

0 0

0 3

E 2

1 5

2 0

0 10 E5E 1

4 5

2 0

0 12 SE 3

3 8

2 0

0 le SSE 2

S 1

0 0

0 1-S 6

2 1

0 0

0 9

SSW 1

3 1

1 0

0 6

SW 4

5 2

1 0

0 12 WSW 3

2 1

0 0

8 W

0 S

2 4

0 0

11 WIN 1

1 6

2 0

0 10 NW 2

0 3

2 0

0 7

1111 0

1 5

3 0

0 9

Variable 0

0 0

.otal 28 S1 S0 23 0

0 l'-

Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

3 Hours of 3issarg stability measurements in all stability classes:

0 90 of 105

Braidwood Iuclear Station Period of Record: October -

December 2005 Stability Clams -

Extremely Unstable 199Ft-30mt Delta-T (F)

Winds Neasured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 6-12 13-18 19-24

> 24 Total N

0 3

3 0

0 0

e NNE 0

1 3

1 0

0 5

NE 0

e 7

0 0

0 13 EtE 0

1 0

0 0

0 1

E 0

1 0

0 0

0 1

ESE0 0

0 0

0 SE 0

0 0

SSE 0

1 0

0 0

0 1

S 0

S 3

1 0

0 9

SSW 0

3 13 7

0 0

23 SW 0

1 11 0

0 0

12 WSW 0

3 a

0 0

0 11 W

0 13 13 0

2 1

29 M0 -

e 18 4

a 0

30 INI 1

6 9

1 0

0 17 0NW 0

2 9

4 0

0 15 Variable 0

0 0

Total 1

54 97 18 2

1 173 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

0 Eours of missing stability measurements in all stability classes:

0 91 of 105

Braidwood S'uclear Station Period of Record: October -

December 2005 Stability Claas -

Moderately Unstable -

199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

>.4 Total 1U 0

1 2

0 0

0 3

NilE 0

1 3

0 0

0 4

NE 0

2 5

0 0

0 7

ELIE 0

1 2

0 0

0 3

E 0

0 0

ESE 0

1 0

0 0

0 1

SE 0

0 0

SSE 0

0 0

S 0

3 0

2 0

0 5

SSW 0

2 8

4 0

0 14 SW 1

1 5

e 0

0 13 WSW 0

7 4

1 0

0 12 W

1 E

2 2

1 o

1e W1UW%

0 4

3 2

0 0

9 NW 0

e 1

1 0

0 8

MMIW 0

1 1

0 0

0 2

Variable 0

0 0

Total 2

3e 40 le 1

0 97 Hours of calm in this stability class:

0 Fours of missing wind measurements in this stability class:

0 Hours of missing stability measurements in all stability classes:

0 92 of 105

B:aidwood Nuclear Station Period of Record: October -

December 2005 Stability Class -

SI Wir lightly t'nstable

- 199Ft-30Ft Delta-T (F) ids Measured at 34 Feet Wind Speed (in mph) 4-7 8-12 13-18 19-24

> 24 Tot Wind Direction tNE t.

EIE E

ESE SE SSE 5

SSW SW; WSW WU NuW Variable Total 1-3 1

0 0

1 1

0 0

1 0

al 1

0 2

5 I

0 0

0 1

0 i

1 0

0 0

1 0

3 4

5 7

2 8

3 3

1 3

3 0

0 0

e 0

0 0

1 0

0 0

7 0

0 0

1 0

0 C'

0 0

1 0

0 0

3 0

a 0

0 0

4 4

3 0

a 2

0 0

5 1

0 0

11 3

2 0

1S 1

0 0

12 0

0 0

4 1

0 0

8 0

0 0

0 4

36 29 12 0

ee Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

0 Hours of missing stability measurements in all stability classes:

93 of 105

Braidwood luclear Station Period of Record: October -

December 2005 Stability Class -

lleutra Winds Ht L

19,Ft-30Ft Delta-T (F) easured at 34 Feet Wind Speed (in mph) 8-12 13-18 19-24

> 24 Total Wind Direction

E t7E ENE E

ESE SSE S

SSW SW WSW W

Variable 1-3 4-7 11 31 3

6 7

10 41 10 39 1

3 14 0

3 10 30 0

1C 30 1

9 31 0

3 23 0

10 37 2

F 23 8

31 45 2

24 32 4

19 13 4

25 47 0

0 0

6 1

0 52 1

0 0

23 0

0 0

36 0

0 0

53 0

0 0

50 0

0 0

17 2

0 0

45 3

0 0

49 9

1 0

51 38 1

0 e5 32 1

0 80 17 3

0 54 23 9

0 116 30 0

0 78 5

0 0

41 3

0 0

79 0

0 0

0 Total 60 295 359 159 1i 0

889 Hours of calm, in this stability class:

Hours of nissing wind measurements in this 0

stability class:

0 all stability classes:

Hours of missing stability measurements in 0

94 of 105

Braidwood Nuclear Station Period of Record: October -

December 200S Stability Class - Slightly Stable 199Ft-30Ft Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Win d Direction 1-3 S-7 8-12 13-18 19-24

> 24 Total N

6 14 6

0 0

0 26 ME 6

17 1

0 0

0 24 tE 15 6

0 0

21 ENE 14 1

a 0

0 0

15 E

1:

1 0

0 0

0 13 ESE 10 7

0 0

17 SE 3

11 9

0 0

0 23 SSE 3

16 1S 0

0 0

34 S

2 62 50 13 0

0 1Z7 SrW 0

14 Y4 32 4

0 54 SW 1

1S 23 9

0 0

4e W;Si 7

36 7

1 0

0 51 U

17 33 11 1

0 0

62 1411 26 49 12 2

0 0

89 tNW 13 19 0

0 0

0 32 MM 7

10 11 0

0 0

Z8 Variable 0

0 0

Total 142 311 189 58 4

0 704 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

0 Hours of misaing stability measurements in all stability classes:

0 95 of 105

Braidwood lNuclear Station Period of Record: October -

December 2005 Stability Class -

Moderately Stable l99Ft-3OFt Delta-T (F)

Winds Mtasured at 34 Feet Wind Speed (in mph)

Wind Direction l;E Et;E E

ESE SE SSE S

SSW WsW W

NW Variable L-3 4-7 8-12 13-18 19-24

> 24 Total 6

0 2Z 0

3 0

4 0

6 0

3 0

4 3

1 4

2 3

3 2

1 4

1 27

.3 16 0

0 0

0 C

3 4

3 I

34

.7 0

4 2

0 0

4 0

o a

0 0

o 0

0 0

o a

0 0

5 0

0 S

0 0

9 0

0 28 O

0 29 0

0 38 0

0 9

0 0

2 0

0 0

,otal 92 65 4

0 0

0 l1l Hours of calm in this Stability class:

0 Hours of missing wind measurements in this stability class:

0 Hours of missing stability measurementa in all stability classes:

0 96 of 105

rra'dwood Nuclear Station Period of Record: October - December 2005 Stability Class - Extremely Stable

- 199Ft-3CFt flelta-T (F)

Lnds Mleasured at 34 Feet Wind Speed (in mph) 141-nd Directio%

1-3 4-7 8-12 13-18 19-24

> 24 Tor al IN M 12^7 ENE ES' S3_

5 51.1 Z;11 NSW Variable i

G C

1 0

C o

C 1

0 o

a C

O 3

E 4

15 0

O C

C C

0a C.

c C

C C

0 o

a o

0 o

a o

a C

0 o

o 0

'S-a o

0 o

a a

0 o

o C

3 I)

I o

s I)

I O

O C

o i

£ 0

o ID s

o 1

o Is o

+/-1 o

o C

_otal S6 7

2 0

0 O

es Hours of calm in Hours of mIssIng Hours of m~ss ng this stabil'ty class:

wind measurements in this stabIlIty measurements in a

stability class:

C all stability classes:

a 97 of 105

Braidwood Nuclea: Station Period of Record: October - December 2005 Stability Class -

Extremely Unstable 159Ft-3OFt Delta-T (F)

Winds Heasured at 203 Feet Wind Speed (in mph)

WUnd Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total N

0 0

2 3

0 0

5 0IE O

0 1

3 0

0 4

0E O

0 9

4 1

0 14 ENE 0

0 1

0 0

0 1

E 0

0 1

0 0

0 1

ESE 0

0 0

SE 0

0 0

SSE 0

1 0

0 0

0 1

S 0

2 7

2 1

0 12 SStU 0

0 2

14 3

0 Z4 SW 1

0 S

3 0

0 9

WSW 0

2 S

1 0

0 9

W 0

S 17 5

0 3

30 0NN O

5 13 9

0 4

31 t*,

0 3

7 10 1

4 25 NNUW 0

1 4

2 0

0 7

Variable 0

0 0

Total 1

19 7S Se 11 11 173 Hours of calm in this stability class:

0 Eours of missing wind measurements in this stability class:

0 Fours of missing stability measurenents in all stability classes:

2 98 of 105

Braidwood nuclear Station Period of Record: October -

December 200S Stability Class -

}loderately Unstable -

199F:-3OFt Delta-T (F)

Winds 1leasured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> ^4 Total N

0 0

0 1

0 0

1

=WN 0

1 0

2 0

0 3

NE 0

0 5

0 0

7 ENE 0

1 0

2 0

0 3

E 0

0 0

ESE 0

1 0

0 0

0 1

SE 0

0 0

SSE 0

1 0

0 0

0 1

S 0

1 1

1 3

0 e

SSW 0

1 2

e 4

2 15 SW 0

2 S

1 3

0 11 WSR 0

5 7

0 1

0 13 W

0 4

2 0

2 14 1MM 0

0 5

0 1

2 8

MI 0

3

^

3 1

0 9

arQ 0

2 0

3 0

0 5

Variable 0

0 0

Total 0

22 30 26 13 e

97 Hours of calm in this stability class:

0 Hours of missing wind measurements in this stability class:

0 Hours of missing stability measurements in all stability classes:

2 99 of 105

Braidwood }:uclear Station Pexiod of Record: October -

December 2005 Stability Class -

Slightly Unstable l99Ft-30Ft Delta-T (F)

Iinr.ds Measured at 203 Feet Wind Speed (in mph)

Nind Direction 1-3 4-7 3-12 13-18 19-24

> 24 Total N1 0

2 0

3 0

0 5

MItE 0

1 0

0 0

0 1

VE 0

1 0

e 0

0 7

ENE 0

0 1

0 0

0 1

E 0

0 0

ESE 0

0 1

0 0

0 1

SE 0

0 3

0 0

0 3

SSE 0

0 0

5 0

1 2

1 0

0 4

SSW 0

0 1

2 3

4 10 SN 0

1 l

1 0

5 WSW 1

4 3

3 1

0 12 IJ 1

1 3

1 2

3 11 M0 6

2 2

0 12 MI 1

2 3

1 0

0 7

NN.

0 3

1 2

1 0

7 Variable 0

0 0

.otal 3

18 25 23 10 7

of Hours of calm in this stability class:

0 Fours of missing wind neasurements in this stability class:

0 Hours of missing stability measurements in all stability classes:

2 100 of 105

B:aidwood Iuclear Station Period of Record: October -

Decerber 2005 Stability Clasa

- Neutral l9SFt-3OFt Delta-T (F)

Windi Hleasured at 203 Feet Wind Speed (in mph)

Mind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total N

NNJE NE ESE E

ESE SE SSE Sn MSH w

Nw WN;;

Variable Total 2

0 I

2 1

1 2

0 0

0 1

3 1

3 0

0 8

5 8

'4 S

19 11 30 13 42 0

12 0

11 4

9 4

4 0

e 3

20 3

15 14 le 6

18 6

19 10 30 0

0 24 3

0 42 5

1 0

18 8

0 0

33 7

0 0

50 e

0 0

C2 4

0 0

17 22 1S 1

54 22 8

1 44 24 12 3

47 2-44 13 es 21 1S 2

f2 16 1s 9

Co 40 le 14 103 21 13 11 70 le 9

s c0 3C 1

4 81 0

0 0

0 19 9S 260 296 5SS 63 8ss Hours of calm in this stability class:

0 Hours of missing wind measurements in -his stability class:

1 Fours of missing stability measurements in all stability classes:

101 of 105

Braidwood Nuclear Station Period of Record: October -

December 2005 Stability Class - Slightly Stable 199Fr-30Ft Delta-T IF)

Winds IMeasured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24

> 24 Total NE UE EME E

ESE SE S5E SW SSJ WSW W

WNMW Variable Total I

0 0

1 0

9 17 4

0 7

11 1

0 3

15 3

0 3

a 0

0 a

4 0

0 5

11 3

0 1

9 f

f 4

7 28 2

1 ll 53

_4 1

20 El 50 6

8 12 2

6 16 Z3 2

9 14 18 1

15 31 32 6

4 35 11 0

S 9

16 0

0 0

0 7

11 0

0 1

0 0

31 19 21 12 14 19 24 41 96 143 28 49 43

85 02 30 0

0 0

1 0

01 0

9 87 22.3 271 93 21 707 Fours of calm in this stability class:

Fours of missing wind measurements in this Fours of missing stability measurements in stability class:

4 all stability classes:

102 of 105

Braidwood N:uclear Station Feriod of Record: October -

December 2005 Stability Class -

Moderately Stable 195Ft-30Ft Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction N

IIT NWE EIJE E

ESE SEs SE SSN SN NSW NW Variable 1-3 0

0 0

1 1

0 0

i-7 3

S 2

1 0

0 3

3 0

0 3

e-12 13-18 19-24

> 24 Total 3

S 1

2 3

4 f

1 0

0 0

0 9

7 3

0 0

0 3

0 0

0 3

1 0

0 3

1 0

0 8

1 0

0 10 4

Z 0

7 8

0 0

13 19 0

0 33 0

0 18 e

0 0

28 0

0 0

15 0

0 0

11 0

3 13 1

4 17 0

5 10 0

0 0

.otal 33 90 42 2

0 171 Hours of calm in this stability class:

Hours of missirg w-nd measurements in this Hours of missing stability measurements in 0

stability class:

2 all stability classes:

103 of 105

Braidwood Nuclear Staticn Period of Record: October -

December 2005 Stability Class -

Extremely Stable 199Ft-3OFt Delta-T (F)

Winds l-asured at 203 Feet Wind Speed (in mph)

Wird Direction 1-3 4-7 e-12 13-18 19-24

> 24 Totv 1J 0

0 8

0 0

0 1NNE 0

1 3

3 0

0 aI ITE 1

0 ENE E

ESE SE SSE S

SSW SW WSW WNN VIal Variable 0

1 1

0 0

2 0

0 0

1 0

0 0

1 1

1 0

1 1,

1 1

1 0

0 0

2 1

0 0

0 2

1 0

0 0

3 1

0 0

0 4

0 0

1 0

0 0

0 1

0 0

3 Z

0 0

0 Z

0 1

1 0

6 1

0 0

0 2

1 7

0 0

9 2

1 0

0 5

11 1

0 0

13 f

2 0

0 9

0 0

0 Total 8

15 38 15 1

0 77 Hours of calm in this stability class:

0 Fours of missing wind measurements in this stability class:

0 Hours of missing stability neasurements in all stability classes:

104 of 105

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2005 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

ATTACHMENT 2 Assessment of Offsite Doses from Inadvertent Releases of Water from the Blowdown Line at Braidwood Station 105 of 105

TR-01 -2006 DMA-TR-27 F,. X, -

0 1.

If 1.

It a1.

at t-i,

-/

Assessment of Offsite Doses from Inadvertent Releases of Water from the Blowdown Line at Braidwood Station I_-

12W ISi n.

0<

U._

IZ IS Tracy A. Ikenberry, CHP Dade Moeller & Associates, Inc.

Harvey C. Farr Radiation Safety & Control Services William H. Barley, CHP Bartlett Nuclear, Inc.

March 2006 Approved by: John S. Moser Radiation Protection Manager, Braidwood Station sser Date Independent Review by: John W. Poston, Sr., PhD Texas A&M University Prepared for Exelon.

Exelon Nuclear Braidwood Station Braidwood, Illinois

TR-01-.2006 LIMITATIONS This technical report was prepared by independent technical experts in accordance with our signed agreements with Exelon Nuclear. Representatives of Dade Moeller & Associates, Inc.,

Radiation Safety & Control Services, and Bartlett Nuclear, Inc. prepared this work based on information provided by Exelon Nuclear. This report reflects information available at the time of document submittal.

iiMarc, 2006 ii Marco 2006

TR-01 -2006 TABLE OF CONTENTS Section Rage SU M M A R Y....................................................................................................................................

I....

1.

INTRODUCTION

.2

2.

BACKGROUND 4

2.1 General Description

.4 2.2 Groundwater Sampling

.7 2.3 History of VB Releases

.8 2.4 Groundwater Study.12 2.5 Applicable Regulatory Requirements.........................................................................14

3.

METHODOLOGY 18 3.1 Ingestion Dose Conversion Factors for Tritium 18 3.2 Calculating Doses from Ingestion of Tritium 18 3.3 Calculating Doses from Eating Fish and Game Animals

.20 3.4 Calculating Water and Food Intake Rates for Game Animals

.21 3.5 Calculating Other Radionuclide Concentrations in the VB-3 Release.

.21 3.6 Calculating External Radiation Doses 26

4.

BOUNDING ESTIMATES OF DOSE

.28 4.1 Tritium Doses from the VB-I Release (1996) 28 4.1.1 Wading in the Drainage Ditch.29 4.1.2 Consuming Wild Game Animals That Drink Ditch Water.29 4.2 Doses from the VB-3 Release (1998).30 4.2.1 External Exposure from Radionuclides Deposited in Smiley Road Ditch.31 4.2.2 Consuming Wild Game That Drinks Pooled Surface Water.31 4.2.3 Consuming Wild Game Ingesting Water and Vegetation from the Surface Spill Area.32 4.2.4 Drinking Well Water.33 4.2.5 Consuming Irrigated Garden Produce.34 4.2.6 Consuming Fish from the Exelon Pond.35 4.2.7 Consuming Wild Game That Use Exelon Pond.36 4.2.8 Swimming in the Exelon Pond.36 4.2.9 Exposure to Center Street Ditch Water.37 4.3 Dose from the VB-2 Release (2000) 37 4.4 Tritium Dose from the VB-4 Release (2003) 38 4.5 Tritium Dose from VB-6 and VB-7 Releases (dates undetermined).

.39 4.6 Summary of Bounding Exposure Scenario Dose Estimates

.39

5.

REALISTIC ESTIMATES OF DOSE 40 5.1 Evaluation of Exposure Scenarios.41 5.2 Realistic Estimates of Dose.42

6.

CONCLUSIONS 44

7.

REFERENCES 46 iii March 2006 iii March 2006

TR-01-2006 LIST OF TABLES Table Pase S-I Doses to the public from vacuum breaker releases.............................................................I 1

Summary of selected tritium groundwater sampling results............................................... 7 2

Summary of releases from Braidwood Station blowdown line VB valves.............

........... 9 3

Tritium ingestion dose conversion factors........................................................................ 18 4

Usage factors from Regulatory Guide 1.109 for maximum and average exposed individual in lieu of site-specific data.....................................................

20 5

Total radioactivity released from October through January 1998.......................

22 6

Radionuclide screening for ingestion and external dose exposure pathways................... 23 7

Calculated 1998 VB-3 spill area water and soil concentrations..........................

............. 24 8

VB-3 spill area soil sample results (2001).....................

................................ 25 9

External radiation dose calculation data......................................................

27 IC, Dose from ditch wading/inadvertent water ingestion scenario, VB-I................

.............. 29 11 Dose from ingesting venison and goose from ditch water scenario, VB-I............

.......... 30 12 External dose from radionuclides in the Smiley Road Ditch scenario, VB-3...........

....... 31 13 Dose from eating deer that drinks ditch water scenario, VB-3......................................... 32 14 Dose from ingesting venison from overland release scenario, VB-3................

............... 34 1i Dose from ingesting well water scenario, VB-3...................................................... 34 16 Dose from consuming garden produce scenario, VB-3.................................................... 35 17 Dose from consuming fish from the Exelon Pond scenario, VB-3................................... 35 18 Dose from consuming deer that use the Exelon Pond scenario, VB-3...............

.............. 36 19 Dose from swimming in the Exelon Pond scenario, VB-3............................................... 37 20 Dose from ingesting venison consuming tritiated vegetation scenario, VB-4.................. 38 21 Summary of bounding exposure scenarios and maximum doses.....................

................ 39

22.

Summary of realistic exposure scenarios and doses to the public....................

................ 43 iv March 2006

TR-01-2006 LIST OF FIGURES Figure Page I

The Braidwood Station site, blowdown line, and VB-I, VB-2, and VB-3......................... 5 2

Location of blowdown line and all VBs to Kankakee River..............................................

6 3

Contour map of tritium in groundwater at depths of I 1 to 21 ft, shallow sand aquifer.......................................................................................................................

11 4

Contour map of tritium in groundwater at depths of 21 to 41 ft, shallow sand aquifer.......................................................................................................................

12 5

Soil sampling grid around the VB-3 vault........................................................................ 25 V

March 2036 v

Marchl 2006

TR-01-2006 ACRONYMS AND ABBREVIATIONS ALARA as low as reasonably achievable CFR Code of Federal Regulations cm centimeter d

day ft ft g

gram gal gallon G]-LLI gastrointestinal/lower large intestine gph gallons per hour g9m gallons per minute hr hour kg-kilogram L

liter lb pound LLD lower limit of detection m

meter MDA minimum detectable activity mL milliliter mrem millirem mSv millisievert N/A Not applicable NCRP National Council on Radiation Protection and Measurements N(RL negligible individual risk level O.DCM Offsite Dose Calculation Manual 02; ounce pCi picocurie RG Regulatory Guide VB vacuum breaker yr year ACi microcurie vi viMarc) 2006

TR-01-2006

SUMMARY

Since 1996 the Braidwood Station has experienced several inadvertent releases of cooling water from vacuum breaker valves in the blowdown line that returns water from the cooling lake to the Kankakee River. These releases contained tritium (hydrogen-3) and much smaller concentrations of other radionuclides. Groundwater monitoring initiated in 2005 determined the extent and concentration of tritium groundwater plumes originating at vacuum breakers on and off the site. This report assesses the potential offsite radiation doses that could have been re.eived by members of the public from exposure to tritium that reached the offsite environment around the Braidwood Station.

Conservative exposure scenarios were evaluated to develop bounding dose estimates-the highest reasonable radiation doses that could have been received by members of public. These conservative scenarios were then evaluated in more detail to develop realistic estimates of dose.

The methodology of U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.109 was used as the basis for estimating doses from all scenarios.

The estimated bounding dose to a member of the public was about 0.16 mrem/yr from ingestion of drinking water from a residential groundwater well containing tritium from a vacuum breaker release. The highest realistic estimates of radiation dose were from the same drinking water scenario. The estimated maximum realistic dose was 0.068 mrem/yr with an average or expected value about one-half that or 0.034 mrem/yr. When doses from the realistic exposure scenarios were summed, the maximum dose was estimated to be 0.072 mrem/yr. Table E-1 lists these dose estimates.

The estimated doses from the vacuum breaker releases at the Braidwood Station are well below the design objective of 6 mremlyr for the two-unit site provided in Title 10 of the Code of Federal Regulations Part S0 (10 CFR 50, Appendix I). The doses are even further below the IC 0 mrem/yr regulatory dose limit for a member of the public provided in 10 CFR 20, Subpart D. The estimated radiation dose represents a negligible increased risk-less than 0.1 percent of the risk from natural background radiation-to members of the public.

Table S-1. Doses to the public from vacuum breaker releases (mrem/yr).

. Average Exposure Scenario Minimum (expected)

Maximum Drinking well water (2 adults)

- 0 0.034 0.068 Eating fish from Exelon Pond (multiple individuals) 0 0.0011 0.0034 Maximum individual summed dose

-0

< 0.04

< 0.072

1. Based on average individual drinking water ingestion rate of 370 L/yr.

2.

Based on maximum individual drinking water ingestion rate of 730 L/yr.

1 March 2006

TR-01-2006 Assessment of Offsite Doses from Inadvertent Releases of Water from the Blowdown Line at Braidwood Station

1.

INTRODUCTION The Braidwood Station is located in Will County in northeastern Illinois. It has two Westinghouse pressurized light-water reactors that each have a net generating capacity of approximately 1,200 megawatts of electricity. Unit 1 began commercial operation in July 1988 and Unit 2 followed in October 1988. Since 1996, the Braidwood Station has experienced several inadvertent releases of cooling water discharged from vacuum breaker (VB) valves in the blowdown line that returns water from the cooling lake to the Kankakee River. These releases contained tritium (hydrogcn-3, or 3H) and much smaller concentrations of other radionuclides.

Groundwater monitoring initiated in 2005 determined the extent and concentration of tritium groundwater plumes originating on the site at VB-1, VB-2, VB-3 and smaller plumes originating off the site at VB-4, VB-6, and VB-7. No tritium has been detected in offsite groundwater around VB-5, VB-8, VB-9, VB-10, and VB-l 1.

This report assesses the potential offsite radiation doses that could have been received by members of the public from exposure to tritium that reached the offsite environment around the Braidwood Station. Tritium has been detected off the site in shallow groundwater and in the Exelon Pond, which lies northeast of the station and is currently owned by Exelon Corporation.

Section 2 of this report provides background information on releases of cooling water from ihe V13s and on the locations and concentrations of tritium discovered in offsite groundwater and the Ex.elon Pond. The section also provides a discussion of the regulatory framework under which the doses to the public were evaluated.

Section 3 describes the methods and calculations used to estimate the potential of doses. The equations are taken from the U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.109 (NRC 1977).

Section 4 presents bounding estimates of the radiation dose that members of the public could have received from exposure to tritium. The bounding estimates are the highest reasonable radiation doses that could have been received by members of public. The exposure scenarios developed for and described in this section could have resulted in public dose. These scenarios may or may not have actually occurred. In addition, this section hypothesizes potential exposure to radionuclides other than tritium in a limited number of scenarios, even though none of these other radionuclides has been detected off the site.

Section 5 provides more realistic estimates of radiation dose that members of the public could have received. This section describes the application of a graded approach to the analysis in.

which (1) the broad umbrella of bounding exposure scenarios in the previous section are more closely evaluated and unrealistic scenarios are eliminated from further consideration, (2) exposure scenarios that could have occurred but would result in extremely low doses and 2

March. 2006

TR-01-2006 therefore negligible risk under bounding conditions are also eliminated from further consideration, and (3) the remaining exposure scenarios evaluate the actual exposure that could have occurred using assumptions and parameter values that more closely reflect the actual environmental conditions, characteristics, and lifestyles of nearby residents.

Section 6.0 presents report conclusions. It compares the calculated realistic dose estimates to the applicable regulatory limit and to the background radiation dose.

3 March 2006

TR-01-2006

2.

BACKGROUND As noted in Section 1, the Braidwood Station has experienced several inadvertent releases of cooling water from VB valves in the blowdown line that returns water from the cooling lake to th,- Kankakee River. Groundwater monitoring initiated in 2005 determined the extent and concentration of tritium groundwater plumes from onsite valves VB-1, VB-2, and VB-3 and sampled the groundwater around the offsite VBs. Smaller tritium groundwater plumes were discovered near VB-4, VB-6, and VB-7. This section provides background information to understand the source of the tritium releases and the extent and concentration of tritium in the groundwater that is a potential source of exposure to members of the public.

2.1 General Description Figure I is a map showing the Braidwood Station layout and the blowdown line with VB-1, V13-2, and VB-3. Figure 2 shows the other VBs, where the blowdown line continues to the Kankakee River.

The blowdown line returns water from the station cooling lake back to the Kankakee River for the purposes of reducing the dissolved mineral concentration of the lake water. The cooling lake provides a heat sink for the main condensers. Because the lake is warm and has a large surface area, it loses much of its water to evaporation. Evaporation of the water concentrates dissolved and suspended minerals in the lake. High concentrations of dissolved minerals, especially calcium carbonate, can result in calcium deposits on the heat exchangers, reducing their performance. Water flows continuously through the blowdown line. Typical blowdown line flc~w rates were 10,000 to 12,000 gallons per minute (gpm) before August of 2003. Since then, the average flow rates have been increased to 20,000-25,000 gpm as a result of station modifications.

Tritium is formed in reactor coolant water during normal operating conditions when a neutron is captured by boron or lithium present in the coolant. Excess station water that contains tritiun is collected in a liquid radioactive waste tank and periodically released to the blowdown line.

These intermittent and noncontinuous releases are conducted under State and Federal permits.

During normal operation the station releases a waste tank volume to the blowdown line about every 3 days, which can increase to daily releases during outages. The tritium concentration of water flowing within the blowdown line changes depending on whether there is a waste tank be ing discharged at the time of the measurement. When no tank is being discharged, the tritium concentration is the concentration of the cooling lake, essentially the ambient or background level. During a release, the tritium concentration of the line will be significantly higher. The average tritium concentration during releases can exceed I million pCi/L. This would also be the concentration as it enters the river, but before dilution in the river. This is an average of water flowing in the blowdown line for only the period that the waste tank is actually discharging to the blowdown line, which typically lasts from I to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. If a composite water sample was drawn by extracting a small continuous sample from the line over a longer period when muli:iple radioactive waste tank releases occurred, followed by longer periods of blowdown from the cooling lake, then the composite concentration would be much less than 1 million pCi/L and on the order of 40,000 to 100,000 pCi/L depending on the blowdown line flow. Because the tritium concentration in the blowdown line can vary greatly, it is important to recognize that a 4

March 2006

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TR-01-2006 Insert 1 Insert 2 I

_Continued on Insert 3 Figure 2. Location of blowdown line and all VBs to Kankakee River.

6 ach20 6

March 2006

TR-01-2006 continuous VB leak would have an average concentration equal to the composite concentration of the blowdown line during the time the leak was active.

2.2 Groundwater Sampling The first Exelon studies in the early spring of 2005 evaluated the presence or lack of tritium in surface water and groundwater. These initial studies included sampling private wells to the west of the site in the Village of Godley and sampling the perimeter ditch flow from east to southwest around the main generating station perimeter. Discovery of tritium above background concentrations in the perimeter ditch on the east side of the Braidwood Station property prompted a series of groundwater studies in the summer and fall of 2005. A comprehensive groundwater investigation program was implemented by Exelon in mid-November 2005 and is continuing. As part of the groundwater studies, and the overall site characterization program, Exelon has installed over 157 groundwater monitoring points at the site, collected surface water samples, and sampled 14 private wells on many occasions. A routine program of private well sampling and groundwater monitoring is currently on-going at the site. As of early March 2006, nearly 700 samples had been collected and analyzed. Table I lists a summary of selected groundwater sampling results that are directly relevant to the dose assessment documented in this report. These results reflect sampling in the shallow sand aquifer; shallow wells are from 11 to 21 ft below the ground surface and deep wells are from 21 to 41 ft below the ground surface.

Figures 3 and 4 show groundwater monitoring and private well locations, as well as the various ponds around the site.

Table 1. Summary of selected tritium groundwater sampling results (pCi/L).'

Sample Location Samples Minimum Median Maximum VB-I 20

< ELD' 206 22,928 VB-2 26

< LLD" 1,696 6,193 VB-3 23

< LLD 19,605 108,736 VB-4 77

< LED-56 31,459 VB-5 9

< LLD 22 112 VB-6 19

< LLD' 23 2,222 VB-7 25

< LLD238 2,776 VB-8 10

< LED7 50 209 VB-9 10

< LD7 31 109 VB-10 10

<LLD2 16 179 VB-1 9

<LLD" 44 92 Private wells (15) 25

<LLD,'

38 1,524 Private well #8 3

1,151 1,367 1,524 Sampling well P13 14 217,122 226,251 442,990

1. Results through March 2,2006.

2.

Lower limit of detection (LLD) for the analytical laboratory is 200 pCi/L.

The groundwater sampling program was planned using knowledge of past onsite failures at V13-1, VB-2, and VB-3 (see Figure 1). Station records coupled with existing groundwater data indicate that the tritium detected in the groundwater in 2005 and 2006 is a result of past failures at these VB valves. There are specific identified events that can explain the levels of the tritium detected on and off the property in the vicinity of the site. Integrity testing of the blowdown line pipe and focused groundwater studies along the full length of the blowdown line at the site do 7

March 2006

TR-01-2006 not indicate that the line itself is the source of the tritium. Figures 3 and 4 show maps of the tritium groundwater plumes created by leaks at these VBs.

2.3 History of VB Releases Exelon has identified and evaluated VB releases and determined that releases and detectable tritium groundwater concentrations have resulted from leaks at six valves (VB-I, VB-2, VB-3, V:B-4, VB-6, and VB-7). Relatively large releases of tritium have occurred only from the three onsite VBs (VB-1, VB-2, and VB-3). Table 2 summarizes the blowdown line VB releases, including minor releases from other VB valves. The most significant events for VB-I, VB-2, and VB-3 are items 1, 3, and 4 in the table. The following paragraphs discuss additional information on the releases from VB-I, VB-2, and VB-3.

Vi3-1. A leak was discovered at VB-l on December 1, 1996. The leak was in the 1-inch pipe to the air release valve. The valve had been previously inspected in June of 1995 at which tim.v no leaks had been noticed. The line eventually broke and was repaired in June of 1997. Total leakage from VB-I has been estimated at a maximum of 380,000 gal. Because the leakage occurred over many weeks, this leak would have included tank water releases containing triilium in addition to the lake water.

Later leaks from VB-I occurred but resulted in no or minimal tritium releases. A leak was di covered on November 20, 2000, and is estimated to have been a maximum of 4 million gal.

This leak contained no tritium because no tanks were discharged while the leak occurred. More recently, a leak was discovered on May 19, 2005, at the pilot (air-release) valve seat. The total leakage was estimated to be a maximum of 140 gal with the tritium concentration estimated to be the composite tritium concentration in the line during 2005.

V13-2. A leak was detected from VB-2 in November 2000 as a result of VB valve float failure.

The float was repaired in December 2000. A resident reported flooding of the ditch adjacent to Btaidwood Station in November 2000. The leakage was estimated at a maximum of 3 million gal. Analysis of plant release data for the 30 d before leak isolation revealed:

The average tritium concentration during releases was 167,000 pCi/L.

The highest tritium concentration in the pipeline during this period was 3,103,000 pCi/L.

A continuous composite sample concentration would have been 91,400 pCi/L.

An important remedial aspect of the November 2000 release was that standing water from this leak was pumped back into the blowdown line, minimizing the quantity of tritium-containing water that reached the groundwater.

VIB-3. A leak occurred from VB-3 in December 1998 as a result of a failed VB float; the float was repaired on December 4. The leaking valve was found due to flooding of the Smiley Road ditch on December 3. This valve had been previously inspected in December 1997, and no leakage was noted. The amount of leakage was not recorded but later estimated to be 2.9 million gal over a 30-d period. Analysis of plant release data for 1998 and the 30 d prio: to isolating the leak revealed:

8 March 2006

(0 Table 2. Summary of releases from Braidwood Station blowdown line VB valves.

Other

Date Event Leak Size Radionuclides Tritium Sample Resolution 1 11/27/96 VB-I

-250,000 gal No sampling at time No sampling at time of spill.

06/19/97 1" pipe to air release valve broke. Tritium plume leak of spill.

was identified around VB-I in 2006.

2 1/5/98 VB-2 leak Small leak No sampling at time No sampling at time of spill.

11/08/00 replaced the float, replaced VB and isolation of spill.

Tritium plume was identified in valve. Tritium plume was identified around VB-2 in 2005.

2005.

3 12/4/98 VB-3 Caused 04/26/01 No sampling at time of spill.

05/20/02 1" pipe to the air release valve broke due to leak - seat flooding Soil radioactivity Tritium plume was identified in corrosion. Guide post sheared weld off float. Entire VB

-3 million gal above background.

2005.

replaced (July 2001). Tritium plume was identified around VB-3 in 2005.

4 11/6/00 VB-2 leak-Caused Radioactivity above Tritium plume was identified 11/06/00 Float broke on VB. Tritium plume was identified seat flooding background.

around VB-2 in 2005.

- 3 million gal 5 11/10/00 VB-6 Small leak No sampling at time No sampling at time of spill.

10/17/05 Valve assembly replaced. 2006 remediation leak seat of spill.

2006 samples show no tritium in sampling showed no tritium in the groundwater at this the groundwater location.

6 11/20/00 VB-I VB lifting 11/20/00 samples no Tritium sampling was performed 11/21/00 Rebuilt valve internals. Tritium plume was leak detectable activity.

no detectable activity.

identified around VB-I in 2006.

7 6/18/01 VB-3

'/2 gph leak No sampling at time Tritium plume was identified 05/20/02 Rebuilt valve. Tritium plume was identified leak from main VB of spill.

around VB-3 in 2005.

8 6/18/01 VB-9 Water in vault Negative for other No sampling at time of spill. No No active leak. Attributed to groundwater. 2006 radionuclides.

tritium in groundwater at this remediation sampling showed no tritium in the location reported in 2006.

groundwater at this location.

9 6/18/01 VB-10 Water in vault Negative for other No sampling at time of spill..

No active leak. Attributed to groundwater. 2006 radionuclides.

No tritium in groundwater at this remediation sampling showed no tritium in the location in 2006.

groundwater at this location.

10 6/18/01 VB-I I Water in vault No sampling at time No sampling at time of spill. No No active leak. Attributed to groundwater. 2006 of spill.

tritium in groundwater in 2006.

remediation sampling showed no tritium in the groundwater at this location.

11 5/4/02 VB-3 Seepage Sample showed above No sampling at time of spill.

05/20/02 replaced air release valve. Tritium plume was Leak vent background activity.

identified around VB-3 in 2005.

12 8/20/03 VB-4 I gpm to vault, Sample analysis No sampling at time of spill.

9-9-03 replaced seat ring/float and top gasket.

8/27/03 seat no flooding detected no detectable Tritium plume was identified in Tritiiim n1iime was idintifida romind VuA in 2Q6.

Radioactivity 2006.

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Table 2 (Continued). Summary of releases from Braidwood Station blowdown line VB valves.

Other

Date Event Leak Size Radionuclides Tritium Sample Resolution 13 9/11/03 VB-4 20-40 No sampling at time No sampling at time of spill.

10/22/03 No work performed. Leak determined to be from seat drops/min of spill.

Tritium plume was identified in operating the system at low flow. Tritium plume was 2006.

identified around VB-4 in 2006.

14 11/18/04 VB-8 Popping/

No sampling at time No sampling at time of spill.

10/18/05 replaced valve assembly. 2006 remediation leaking, small of spill.

sampling showed no tritium in the groundwater at this leak within pit location.

15 5/19/05 VB-I 20 drop per No sampling at time Sampling was performed.

12/18/05 replaced the VB assembly. Tritium plume was minute leak of spill.

Tritium plume was identified in identified around VB-I in 2006.

from the air 2006.

release valve.

16 5/24/05 VB-6 Seepage from No sampling at time Sampling was performed.

10/19/05 rebuilt main valve and replaced air release valve.

seat float / seat area of spill.

2006 remediation sampling showed no tritium in the with one foot groundwater at this location.

of water in pit.

17 1/16/06 VB-7 Bushing no detectable No detectable tritium in surface No resolution noted.

failure. Not radioactivity water from this leak. Prior to this significant.

leak, tritium above background

& below EPA drinking water limit identified in 2006 in wells used to characterize conditions near this VB.

Information in this table provided by Exelon Nuclear.

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The average tritium concentration during releases was 624,000 pCi/L.

The highest tritium concentration in the pipeline during this period was 1,852,000 pCi/L.

A continuous composite sample concentration would have been 112,000 pCi/L.

11 March 2006 1 1 March 2006

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TRTlIUM FEMtLT200.00 TO 20ROIE W 1tfW JE TRI11ASREUITS 0,T 20 OD TWTW AR EWS 60.OWTO 10.0 TRITIUU fm&.Ts 4R 0W -o TOAN0 TFTRIUM RESLLTS X0ItW T 4O0.5 TTRIUM RESILTS 1%50 TO 20AD Figure 4. Contour map of tritium in groundwater at depths of 21 to 41 ft, shallow sand aquifer (January 2006).

Unlike the VB-2 release that occurred later, there was no remediation of standing water for this VB-3 release.

2.4 Groundwater Study Exelon commissioned a groundwater and surface water study, the results of which are presented in a Focused Site Characterization Report (Conestoga-Rovers & Associates 2006). That report addressed releases from the three onsite valves (VB-1, VB-2, and VB-3) and is the source of much of the general information in earlier sections of this chapter. The report's key findings about the source, migration, and extent of tritium in groundwater at the site are:

12 March 2006 12 March 2006

TR-01 -2006

Groundwater flow in the shallow sand aquifer, where the tritium is detected, is from south to north.

Groundwater flow is influenced by the perimeter ditch and by the ponds to the north and off the Braidwood Station property.

The underlying deeper groundwater supply aquifers are separated from the tritium in the shallow sand aquifer by the regional Wendron Formation (clayey till) and shale formations including the 70-ft-thick Scales Shale.

Groundwater flowing from the area on the Braidwood Station property south of Smiley Road discharges into Exelon Pond located to the north.

The distribution of tritium in groundwater (and indicators in the cooling lake water) :is consistent with historical releases from each of the three onsite VBs.

The Braidwood Station records of valve failures and releases of water from the three onsite VBs correlate well with the current distribution of tritium in groundwater.

Localized areas on the site where tritium has been detected above the drinking water standard (20,000 pCi/L) are shown in Figures 3 and 4. The main area is approximately 4.5 acres near Smiley Road at the southeast corner of the pond and just wvest of the blowdown line as it leaves the Station property.

The data indicate tritium has migrated into the Exelon Pond north of Smiley Road and past the pond to a limited extent. The distance to the leading edge of this tritium plume from VB-2 and VB-3 is approximately 2,400 to 2,800 ft.

Only one private well has had groundwater samples that were above background tritium concentrations; these were below the drinking water standard.

In the main areas of groundwater affected by tritium (i.e., where concentrations are above the drinking water standard), the tritium is detected at higher concentrations at depth.

The cause of the vertical differences (over a small saturated interval of 20 ft) is expected to be clean water recharge through precipitation. The depth to groundwater is at times less than 5 ft below ground surface and, as such, the upper water table will be regula!:ly flushed with clean precipitation recharge.

Deeper private water wells down gradient of the main tritium impacts were sampled and found to have background levels of tritium. This supports the role of the regional aquitards (e.g., Wendron clayey till and the Scales Shale) as vertical barriers to deep'r migration of tritium. In addition, the lack of any steep downward vertical hydraulic gradients in the shallow sand aquifer would minimize vertical movement of tritium into the clay.

Routine monitoring at key groundwater and surface water sample points since November 2005 has indicated stable or decreasing trends in tritium levels in the groundwater.

13 March 2006

TR-01 -2006

The distribution of tritium in groundwater on the up gradient side (to the south) of the pond located north of Smiley Road and the distribution of tritium in groundwater down gradient or north of the pond indicates that the pond is acting to attenuate the elevated levels of tritium discharging into it along Smiley Road. The pond is mixing on a seasonal basis and therefore diluting the tritium that seeps into it on the south side. In other words, the pond has played a significant role in preventing higher concentrations of tritium from migrating north.

Groundwater flow and tritium migration is expected to occur at a rate of 50 to 100 ft/yr within the upper sand aquifer.

2.5 Applicable Regulatory Requirements A nuclear power plant must comply with two separate NRC regulatory requirements and one U.S. Environmental Protection Agency (EPA) requirement that pertain to radioactive effluents and doses to members of the public. First is a general regulation that applies to all radioactive material licensees, whether a power plant, hospital, or an industrial user. That regulation is contained in 10 CFR 20, Subpart D, Radiation Dose Limits for Individual Members of the Public.

In this subpart, 10 CFR 20.1302(a) states:

The licensee shall make or cause to be made, as appropriate, surveys of radiation levels in unrestricted and controlled areas and radioactive materials in effluents released to unrestricted and controlled areas to demonstrate compliance with the dose limits for individual members of the public in § 20.1301.

The dose limit referred to in § 20.1301 is 100 mrem/yr. Demonstration requirements associated with doses to a member of the public are contained in 10 CFR 20.1302(b):

A licensee shall show compliance with the annual dose limit in § 20.1301 by--

(1) Demonstrating by measurement or calculation that the total effective dose equivalent to the individual likely to receive the highest dose from the licensed operation does not exceed the annual dose limit; or (2) Demonstrating that--

(i) The annual average concentrations of radioactive material released in gaseous and liquid effluents at the boundary of the Unrestricted area do not exceed the values specified in table 2 of appendix B to part 20; and (i) Ifan individual were continuously present in an unrestricted area, the dose from external sources would not exceed 0.002 remn (0.02 mSv) in an hour and 0.05 rem (0.5 mSv) in a year.

Tle NRC regulation also recognizes an EPA rule. 10 CFR 20.1301(e) states:

14 March 2006

TR-0 1-2006 In addition to the requirements of this part, a licensee subject to the provisions of EPA 's generally applicable environmental radiation standards in 40 CFR part 190 shall comply with those standards.

EPA regulations at 40 CFR Part 190 require that any operations that are part of a nuclear fu-1 cycle provide reasonable assurance that doses to members of the public from all fuel-cycle activities are limited to 25 mrem/yr to the whole body. This is contained in 40 CFR 190, Subpart B, Environmental Standards for the Uranium Fuel Cycle, paragraph 190. 10, which contains the standards for normal operations:

Operations covered by this subpart shall be conducted in such a manner as to provide reasonable assurance that:

(a) The annual dose equivalent does not exceed 25 millirems to the whole body, 75 millirems to the thyroid, and 25 millirems to any other organ of any member of the public as the result of exposures to planned discharges of radioactive materials, radon and its daughters excepted, to the general environment from uranium ftel cycle operations and to radiation from these operations.

(b) The total quantity of radioactive materials entering the general environment from the entire uranium fuel cycle, per gigawatt-year of electrical energy produced by the fiel cycle, contains less than 50, 000 curies of krypton-85, 5 millicuries of iodine-129, and 0.5 millicuries combined ofplutonium-239 and other alpha-emitting transuranic radionuclides with half-lives greater than one year.

In addition to the requirements of 10 CFR Part 20 and 40 CFR Part 190, nuclear power plants must also comply with 10 CFR Part 50 which governs nuclear power plant operations. The section on design objectives for equipment to control releases of radioactive material in effluents from nuclear power reactors [10 CFR 50.34(a)] states:

An application for a permit to constnrct a nuclear power reactor shall include a description of the prelimninary design of equipment to be installed to maintain control over radioactive materials in gaseous and liquid effluents produced during normal reactor operations, including expected operational occurrences.

In the case of an application filed on or after January 2, 1971, the application shall also identify the design objectives, and the means to be employed for keeping levels of radioactive material in effluents to unrestricted areas as low as is reasonably achievable. The term "as low as is reasonably achievable

[ALAMRAJ" as used in this part means as low as is reasonably achievable taking into account the state of technology, and the economics of improvements in relation to benefits to the public health and safety and other societal and socioeconomic considerations, and in relation to the utilization of atomic energy in the public interest. The guides set out in appendix Ito this part provide numerical guidance on design objectives for light-water-cooled nuclear polver reactors to meet the requirements that radioactive material in effluents released 15 arh 00 15 March :2006

TR-01 -2006 to unrestricted areas be kept as low as is reasonably achievable. These numerical guides for design objectives and limiting conditions for operation are not to be construed as radiation protection standards. [Emphasis added.]

Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low as is Reasonably Achievable [ALARA] "for Radioactive Material in Light-W ater-Cooled Nuclear PowerReactor Effluents (10 CFR 50 Appendix I), states in part:

Sec. I. Gutides on design objectives for light-water-cooled nuclear power reactors licensed under 10 CFR Part 50. The guides on design objectives set forth in this section may be used by an applicant for a permit to construct a light-water-cooled nuclear power reactor as guidance in meeting the requirements of§ 50.34a(a). The applicant shall provide reasonable assurance that the following design objectives will be met.

The calculated annual total quantity of all radioactive material above background' to be releasedfrom each light-water-cooled nuclear power reactor to unrestricted areas will not result in an estimated annual dose or dose commitmentfrom liquid effluentsfor any individual in an unrestricted areafromn allpathways of exposure in excess of 3 millirems to the total body or 10 millirems to any organ.

SEC IV. Guides on technical specifications for limiting conditions for operation for light-water-cooled nuclear power reactors licensed under 10 CFR part 5O.

The guides on limiting conditions for operation for light-water-cooled nuclear power reactors setforth below may be used by an applicantfor a license to operate a light-water-cooled nuclear power reactor or a licensee who has submitted a certification ofpermanent cessation of operations under § 50.82(a)(1) as guidance in developing technical specifications under § 50.36a(a) to keep levels of radioactive materials in effluents to Unrestricted areas as low as is reasonably achievable.

B. The licensee shall establish an appropriate surveillance and monitoring program to:

1. Provide data on quantities of radioactive material released in liquid and gaseous effluents to assure that the provisions ofparagraph A of this section are met;

2. Provide data on measurable levels of radiation and radioactive materials in the environment to evaluate the relationship between quantities of radioactive material released in effluents and resultant radiation doses to individuals from principalpathwvays of exposure; and

3. Identify changes in the Use of unrestricted areas (eg., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathways of exposure.

16 March 2006

TR-0 1-2006 C. Ifthe data developed in the surveillance and monitoring program described in paragraph B of Section III orfrom other monitoring programs show that the relationship between the quantities of radioactive material released in liquid and gaseous effluents and the dose to individuals in unrestricted areas is significantly different from that assumed in the calculations used to determine design objectives pursuant to Sections II and II, the Commission may modify the quantities in the technical specifications defining the limiting conditions in a license to operate a light-water-cooled nuclear power reactor or a license whose holder has submitted a certification ofpermanent cessation of operations under

§ 50.82 (a)(1).

Appendix I therefore lays out a design objective based on the ALARA principle, while 10 CFR 50.34(a) clearly states this is not a regulatory limit. For comparison to dose estimates, the B:-aidwood site annual effluent reports use the design objective as a performance standard of 3 mrem/yr to the total body or 1O mrem/yr to any organ for each reactor.

Because the calculation of doses to members of the public from effluent releases is complex, and to ensure consistency of calculation between the NRC and licensees, the NRC developed a Regulatory Guide (RG) to be used when performing the calculations required by 10 CFR 20.1302 and 10 CFR 50, Appendix I. That document is RG 1.109, Calculation ofAnnual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, AppendixI (NRC 1977).

It is under this regulatory framework that this report documents the evaluation of potential radiation doses from water released from VB valves in the blowdown line of the Braidwood Station.

17 March 2006

TR-01-2006

3.

METHODOLOGY Th1is analysis estimated doses to members of the public from exposure scenarios (see Sections 4 and 5) calculated using the methods and equations of Regulatory Guide (RG) 1.109 (NRC 1977).

These equations assume continuous exposure and equilibrium conditions. They are conservative estimates of exposures that could occur on a one-time or intermittent basis, and they are conservative for the scenarios evaluated in Section 4 and Section 5.

All of the exposure pathways evaluated in this report originate from the water released from. the VB valves in the blowdown line; therefore, most of the scenarios involve what is considered the liquid effluent pathway described in RG 1.109. The exception is for the evaluation of external exposure from beta/gamma-emitting radionuclides deposited on the soil surface.

Some modifications to the RG 1.109 methods were made because the RG does not address all th. potential exposure scenarios. For example, consumption of wild game animals that drink water and eat vegetation containing tritium required modifications to consumption rates and other parameters. These are explained in the sections below and in Section 4.

3.1 Ingestion Dose Conversion Factors for Tritium Most of the exposure scenarios include ingestion of tritium as a major exposure pathway. The ingestion dose conversion factors are provided in RG 1.109 (NRC 1977). These dose factors are used for the bounding exposure scenarios in Section 4. The dose factors were subsequently revised for use in the LADTAP computer program, which is NRC-approved and published in N1JREG/CR-4013 (Strenge et. al 1985). These factors are the basis of the tritium dose factors in the Exelon Offsite Dose Calculation Manual (ODCM). The newer NUREG/CR-4013 tritiurn ingestion dose factors are 57 percent lower than those in RG 1.109 because of updates that occurred in the calculational methodology; those are used in realistic dose scenarios in Section 5.

Table 3 lists both sets of dose factors for the age groups in RG 1.109.

Table 3. Tritium ingestion dose conversion factors (mrem/pCi).

Ratio, Age NUREG/CR4013 Group (a)

RG 1.109 NUREG/CR4013 to RG 1.109 Adult 1.05E-07 5.99E-08 Teenager 1.06E-07 6.04E-08 Child 2.03 E-07 1.16E-07 0.57 Infant 3.08E-07 1.76E-07 3.2 Calculating Doses from Ingestion of Tritium Doses from ingestion of tritium were calculated in accordance with RG 1.109, Equation A-1, which provides the generalized equation below for calculating doses to man from liquid pathways (NRC 1977).

18 March 2006

TR-0 1-2006 Generalized Equation for Calculating Doses from Liquid Pathways Rairi =Cip Uap Daipi (Equation 1) where:

Cip=

concentration of nuclide i in the media of pathway p, pCi/L, pCi/kg, or pCi/mr2 Daipj = the dose factor, specific to age group a, radionuclide i, pathwayp and organj.

It represents the dose from intake of a radionuclide in mrem/pCi, or from exposure to a given concentration or radionuclide in sediment in mrem/hr per pCi/M2 Raipj = the annual dose to organj of an individual of age group a from nuclide i via pathwayp, mrem/yr U,,p =

the exposure time or intake rate (usage) associated with pathways for age group a, hr/yr, L/yr, or kg/yr as appropriate Because only the dose from one pathway at a time is being considered in these calculations, the subscripts can be eliminated as a designator. Similarly, only tritium is being considered, and the dose conversion factor for tritium is the same for all organs. Therefore, the designators i and]

can be dropped from the equation, and the equation used to calculate dose from tritium ingestion becomes:

Simplified Equation for Calculating Dose from Ingestion of Tritium Ra =CUa Da (Equation 2) where:

C = concentration of tritium in the material ingested, pCi/L or pCi/kg Da = the dose factor, specific to age group a, mrem/pCi (see Equation 1 above)

Ra = the annual dose to an individual of age group a, mrem/yr Ua = the intake rate (usage) associated for age group a, L/yr or kg/yr Equation A-10 of RG 1.109 states that for tritium the concentration in vegetation (Ci) can bec assumed to equal the concentration in water (Cw).

Tritium Equilibrium between Vegetation and Water C, (tritiurm) = Cl (tritiurm)

(Equation 3) 19 March 2006

TR-01-2006 Therefore, the dose is calculated using Equation 2 with the tritium concentration in the vegetation (e.g., garden produce) equal to the concentration in the water used to irrigate or water the garden. Table 4 lists the RG 1.109 age-specific usage factors (U0 ) used in this report.

Table 4. Usage factors' (U0) from Regulatory Guide 1.109 for maximum and average exposed individual in lieu of site-specific data.

Age Group Maximum (Av rage) Consu ption Rates Fruits, vegetables & grain (kg/yr) 520 (200) 630 (240) 520 (190)

Fish, fresh water (kg/yr) 6.9 (2.2) 16 (5.2) 21 (6.9)

Drinking Water (L/yr) 330 -

510 (260) 510 (260) 730 (370)

1. Only usage factors used in this report are presented. Maximum individual values are from RG 1.109, Table E-5; average individual values are from RG 1.1 09, Table E-4.

3.3 Calculating Doses from Eating Fish and Game Animals The potential dose from eating fish from Exelon Pond was evaluated using the guidance in RG 1.109 (NRC 1977).

Calculating Dose from Fish Consumption R, =B C,, Ua Da (Equation 4) where:

Ra = the annual dose to an individual of age group a, mrem/yr B = aquatic bioaccumulation factor, L/kg C = concentration of tritium in the pond, pCi/L Ua = the intake rate (usage) associated for age group a, kg/yr Da = the dose factor, specific to age group a in mrem/pCi (see Equation I above)

The bioaccumulation factor (B) for freshwater fish taken from Table A-I of RG 1.109 is 0.9 pCi/kg of fish per pCi/L of water. The bioaccumulation factor accounts for how the tritium water concentration (CG) relates to the concentration in consumable parts of the fish. Table.4 lists the usage factors.

TLe dose was also calculated from consumption of game animals that consumed water contaminated with tritium. RG 1.109, Equation A-15, was used to calculate the concentration in a game animal that drinks tritiated water.

Calculating Hydrogen-3 Concentration in Meat from Contaminated Drinking Water CA =FFA CZ. QA4 (Equation 5) weCre:

CA =concentration of tritium in the animal, pCi/kg 20 March 2006 20 March 2006

TR-01 -2006 FA = Stable element transfer factor for meat, d/kg CG = concentration of tritium in the water the animal drinks, pCi/L QAW = the quantity of water the animal drinks daily, L/d The tritium transfer factor of 0.012 d/kg, which is the activity concentration (pCi/kg) in meat per the intake (pCi/d) in vegetation or water by the animal, is from Table E-1 of RG 1.109. These transfer factors are for domestic animals but for purposes of this report are assumed to apply to game animals.

The quantity of water the game animal drinks was calculated as described below. The concentration of the tritium in the game animal (CA) was then used in Equation 2 with the estimated quantity of meat consumed by the individual.

3.4 Calculating Water and Food Intake Rates for Game Animals Water intake rates (Uh,) of game animals were calculated using the guidance of DOE-STD-I 153-2002 (DOE 2002). Equation 29 of this standard is for calculating the water intake of an animal based on its body mass:

T.alr =0.099M0 90 (Equation 6) where:

Tiater = animal water consumption rate, L/d M= body mass of the animal, kg The mass of feed an animal consumed daily (Uf) was based on an estimate of dry feed consumption equal to 3 to 5 percent of the wet body mass of the animal (Halls, date unavailable).

The wet mass of the feed was assumed to be 5 times higher than the calculated dry weight. This estimate is conservative in comparison to the consumption values for white-tailed deer provided by Murphy (1970); whitetail deer are the principle potential game animal in the area.

Consumption of Canadian or other species of geese was also considered.

3.5 Calculating Other Radionuclide Concentrations in the VB-3 Release The bounding assessment of dose in Section 4 evaluates the possibility that radionuclides other than tritium might have been present in trace quantities in the liquid releases that flowed overland from the VB-3 vault, even though there is no supporting evidence for other radionuclides reaching the offsite environment. Concentrations of these other radionuclides were estimated based on available 1998 liquid release data and post-event soil sampling in the area around the VB-3 vault in 1998. The VB-3 area was not sampled until April 2001 when it was realized that potential soil contamination existed based on the 10 CFR 50.75(g) follow-up sampling results conducted in response to the November 2000 VB-2 spill.

21 March 2006

TR-0 1-2006 The VB-3 spill occurred in late 1998 over an estimated 30 d. To determine the relative distribution of radionuclides in the spill water, the total activity of each nuclide for each tank release was summed from October of 1998 to January of 1999. Table 5 lists the results. In addition, Table 5 lists scaling factors for each nuclide relative to tritium and cobalt-60. The tritium scaling factor was used to estimate the quantities of other radionuclides in the spill water based on the estimated tritium concentration of the water. Cobalt-60 was the only radionuclide directly attributable to reactor operations that was detected in soil samples, and then only in the immediate vicinity of the vault where the leak originated (see Figure 5 below). Cesium-137 was al o detected in soil samples but is likely present as part of the environmental baseline from atmospheric fallout.

The 10 CFR 50.75(g) file from which the data were obtained described sample grids with low but detectable levels of cesium-137 as clean (Figure 5). Regardless of the origin, cesium-137 was included in applicable dose calculations. Similarly, the reported minimum detectable activities (MDAs) for cobalt-60 and cesium-137 from the sample analysis results were included in the calculation of the average soil concentrations in the VB-3 spill area. The approach overestimates the cobalt-60 and cesium-137 soil concentrations which could have been present in th-area. Cobalt-60 scaling factors from Table 5 were used to estimate the concentrations of the ot 'aer radionuclides in the soil based on the cobalt-60 concentration of soil samples.

Table 5. Total radioactivity released from October through January 1998.

Fraction of Activity 11-3 Scaling Co-60 Scaling Nuclide Activity pCi (excluding H-3)

Factor Factor 11-3 3.7 E+8 (not included) 1.0 E+0 9.5 E+4 Cr-51 9.7 E+3 8.9 E-2 2.7 E-5 2.5 E+0 Mn-54 1.4 E+3 1.2 E-2 3.7 E-6 3.5 E-1 Co-57 3.4 E+1 3.1 E-4 9.3 E-8 8.8 E-3 Co-58 5.6 E+4 5.2 E-l 1.5 E-4 1.5 E+l Fe-59 1.0 E+3 9.6 E-3 2.9 E-6 2.7 E-l Co-60 3.9 E+3 3.5 E-2 1.1 E-5 1.0 E+0 Nb-95 9.9 E+2 9.1 E-3 2.7 E-6 2.6 E-l Zr-95 4.3 E+2 4.0 E-3 1.2 E-6 1.1 E-1 Sn-117m 8.5 E+2 7.8 E-3 2.3 E-6 2.2 E-1 Sb-122 1.1 E+l 9.7 E-5 2.9 E-8 2.8 E-3 Sb-124 1.1 E+4 9.9 E-2 2.9 E-5 2.8 E+O Sb-125 6.1 E+3 5.6 E-2 1.7 E-5 1.6 E+0 Te-125m 1.4 E+4 1.3 E-1 3.8 E-5 3.6 E+O Sb-126 1.1 E+2 1.0 E-3 3.1 E-7 2.9 E-2 Cs-134 5.6 E+ l 5.1 E-4 1.5 E-7 1.5 E-2 Cs-137 3.6 E+3 3.4 E-2 1.0 E-5 9.5 E-1 The 17 radionuclides in Table 5 were evaluated to determine which were potentially significant contributors to dose through the ingestion and external radiation exposure pathways. This screening allowed the calculations to be simplified by reducing the number of nuclides included in calculations. The level of significance was established at greater than 99 percent of the exposure pathway screening dose. The radionuclides with the highest doses would be included un:il greater than 99 percent of the total pathway dose was reached. At this point, radionuclides 22 March 2006 22 March 2006

TR-01 -2006 contributing lower doses would not be considered. Each exposure pathway was evaluated separately using water screening factors from NCRP Report No. 123 (NCRP 1996).

Table 6 lists the results of the radionuclide screening for the ingestion and external dose exposure pathways. The screening eliminated 12 radionuclides from further consideration for each pathway, but retained radionuclides that contributed only 0.5 percent and 0.7 percent of the total dose for the ingestion and external dose pathways, respectively to reach the greater than 99 percent of total dose significance level. For the external exposure pathway, the radionuclides contributing greater than 99 percent of the dose were cobalt-60, cobalt-58, antimony-124, antimony-125, and cesium-137. For the ingestion exposure pathway, the radionuclides contributing greater than 99 percent of the dose were tritium, cobalt-60, cobalt-58, antimony-124, and cesium-137. The ingestion pathway screening included water and meat ingestion.

Table 6. Radionuclide screening for ingestion and external dose exposure pathways.

Ingestion Pathway External Dose Pathway Fraction of Cumulative Fraction of Cumulative Radionuclide Dose Percentage Radionuclide Dose Percentage 11-3 0.86 86.4%

- Cs-137 0.79 78.9%

Cs-137 0.075 93.8%

Co-60 0.16 95.0%

Co-58 0.028 96.6%

Sb-125 0.023 97.3%

Co-60 0.023 98.8%

Co-58 0.013 98.6%

Sb-124 0.0053 99.4%

Sb-124 0.0071 99.3%

Not included in scenario dose calculations:

Te-125m 0.0027 99.6%

Cs-134 0.0027 99.6%

Cs-134 0.0010 99.7%

Te-125m 0.0024 99.8%

Fe-59 0.0009 99.8%

Mn-54 0.0010 99.9%

Sb-125 0.0009 99.9%

Fe-59 0.0003 100.0%

Cr-51 0.0002 99.9%

Zr-95 0.0002 100.0%

Sn-117m 0.0002 100.0%

Nb-95 0.0001 100.0%

Mn-54 0.0002 100.0%

Sn-117m 0.0000 100.0%

Nb-95 0.0001 100.0%

Cr-51 0.0000 100.0%

Zr-95 0.0001 100.0%

Sb-126 0.0000 100.0%

Sb-126 0.0001 100.0%

Co-57 0.0000 100.0%

Sb-122 0.0000 100.0%

11-3 0

TLe tritium water concentration of the spill was estimated based on a median groundwater plume concentration of approximately 230,000 pCi (Table 1, well P-13). The tritium spill concentration was estimated based on radioactive decay correction of the February 2006 plume concentration to June of 1998. Although the spill was detected in January, and was only thought to have oc-urred for 30 d, June was chosen to ensure a conservative estimate by adding additional tirne for radioactive decay correction.

Decay Correction Equation

° C CO=e-(Equatizn 7) where:

23 March 2006 23 March 2006

TR-O"'-2006 Co = concentration of tritium in original spill C = median concentration of tritium in the plume (230,000 pCi/L)

A = tritium decay constant of 5.634 E-2 based on a 12.3-year half-life I

the time in years from the spill to the plume sample (7.68 yr)

The calculated spill concentration was 354,460 pCi/L; a value of 350,000 pCi/L was used for the calculation. The other significant ingestion nuclides were scaled to the 350,000-pCi/L tritium concentration using the hydrogen-3 scaling factors in Table 5. Table 7 lists the scaled, estimated radionuclide concentrations for the spill water. RG 1.109 does not provide factors for antimony, so lumped parameters from DOE (2002) were used. These parameters are concentrations ratios that allow concentrations in soil and water to be used to make estimates of concentrations in animal and plant mass.

Table 7. Calculated 1998 VB-3 spill area water and soil concentrations.

Pooled Vault Area DOE-STD-1 153 Fr CA Water C,,

Soil Conc Bi, Vegetation lumped parameter Meat Meat

.Nuclide pCi/L C. pCi/kg Veg/Soil pCi/kg Soil Water d/kg pCi/kg H-3 3.5 E+5 3.5 E+5 1.2 E-2 1.0 E+4 Sb-124 1.0 E+l 5.8 E+2 4.3 E4 5.2 E-3 3.0 E-1 Sb-125 3.3 E+2 I

Co-58 5.4 E+1 3.0 E+3 9.4 E-3 2.8 E+l 1.3 E-2 1.1 E+0 Co-60 3.7 E+0 2.1 E+2 9.4 E-3 1.9 E+0 1.3 E-2 7.8 E-2 Cs-137 3.5 E+0 1.9 E+2 1.0 E-2 1.9 E+0 4.0 E-3 2.3 E-2

1. Sb-125 is only considered in the external dose pathway; other parameters listed are not needed.

A; part of the 10 CFR 50.75(g) documentation for the VB-3 leak, soil samples were collected in 2001, in the immediate vicinity of the vault. Figure 5 shows the grid of 10- by 10-m soil-sampling locations around the vault with the cobalt-60 results. The soil samples from two grids immediately adjacent to the vault were the only ones with detectable concentrations of' cobalt-60. Table 8 lists the sample data.

Although most positive cesium-137 results are probably due to environmental background from fallout, they were included to ensure a conservative dose calculation. MDAs reported for the gamma spectroscopy results also were used when samples results reported no detectable activity.

This biased the overall results to higher concentrations, which resulted in more conservative estimates of dose. The average cobalt-60 concentration was 1.4 E-7 giCi/g. The average cesium-137 result was 1.8 E-7 pCi/g. The average soil concentrations in April 2001 were decay corrected using a 5.26-yr half-life for cobalt-60, a 30.2-yr half-life for cesium-137, a 2.9-yr decay time, and Equation 7. These decay-corrected average results reflect the soil contamination levels around the valve in 1998. When applied to the entire spill area, they conservatively es:imate the soil contamination levels in which food eaten by white-tailed deer was grown.

The average cobalt-60 soil concentration and the scaling factors for cobalt-60 from Table 5 were used to calculate the soil concentration of radionuclides other than cesium-137 and hydrogen-3.

The average value for cesium-137 was used as the soil concentration with no scaling. Tritium water concentrations were assumed to equal those in the vegetation consumed by the deer in accordance with Equation 3. Table 8 lists the calculated soil concentrations.

24 March 2006 24 March 2006

TR-01 -2006 91 58 59 60 61 62 63 64 90 57 32 33 34 35 36 17 S9 56 31 la011 1

4 18 63 55 30 L

19 87 54 29 0

a1X1,0 l

20 86 53 28

/

21 85 52 27 26 25 24 23 22 Grid Sampled Grid Not Contaminated Sampled Figure 5. Soil sampling grid around the VB-3 vault.

Table 8. VB-3 spill area soil sa ple results (2001).1 2 Co-60 Concentration Cs-137 Concentration Grid No.

,Ci/g ltCi/g 1

2.5 E-7 8.6 E-8 2

ND (6.5 E-8)

ND (6.8 E-8) 3 ND (5.4 E-8) 2.1 E-7 4

1.0 E-6 3.0 E-7 5

ND (8.0 E-8) 1.3 E-7 6

ND (7.2 E-8) 1.4 E-7 7

ND (4.8 E-8) 1.9 E-7 8

ND (1.0 E-7) 5.8 E-7 9

ND (6.3 E-8)

ND (6.7 E-8) 10 ND (9.3 E-8) 1.3 E-7 11 ND (8.7 E-8) 2.4 E-7 12 ND (6.3 E-8) 1.6 E-7 13 ND (6.9 E-8) 1.7 E-7 14 ND(9.1 E-8) 1.8 E-7 15 ND (8.6 E-8) 1.3 E-7 16 ND(1.4E-8)

ND(5.6E-8)

Average 1.4 E-7 1.8 E-7

1. ND = sample results reported as nondetectable and assumed to be at the minimum detectable concentration (MDC).

2.

Sample date is April 26, 2001.

3.

The average includes the nondetectable results at the MDC.

The calculated soil concentrations were used as the basis for calculating the radionuclide concentrations that could have been in spill area vegetation and consumed by game animals.

25 March 2006

TR-01-2006 Calculating Radionuclide Concentrations in Vegetation from Soil Concentrations CAY =Biv CS, (Equation 8) where:

CiG = concentration of radionuclide i in the vegetation, pCi/kg Bi, = concentration ratio of vegetation to soil, unitless Csi = concentration of radionuclide i in the soil, pCi/kg The concentration ratio (Bi,) is the concentration in vegetation (pCi/kg) per unit soil concentration (pCi/kg); values for this parameter were taken from Table E-I of RG 1.109 (NRC 1977).

These spill water and soil concentrations were used to calculate the concentration in meat of game animals for each radionuclide (Equation A-14 from RG 1.109).

Calculating Radionuclide Concentrations in Meat CAI =FA, (Crj QA. + Cfi QAJ (Equation 9) where, for radionuclide i:

CAi = radionuclide concentration in meat of the animal, pCi/kg FAi = stable element transfer factor for meat, d/kg (Table E-1, RG 1.109)

Ci = radionuclide concentration in the water the animal drinks, pCi/L QA, = the quantity of water the animal drinks daily, L/d Cfl = radionuclide concentration in feed (I) the animal eats, pCi/kg QAf= quantity of animal feed consumed daily, kg/d 3.6 Calculating External Radiation Doses Dose from exposure to direct radiation from radionuclides deposited in the soil was calculated in accordance with RG 1. 109, Equation A-6, without correction for radioactive decay (NRC 1977).

Nco correction for radioactive decay is a simplification that is conservative for shorter-lived radionuclides but has little effect for longer-lived radionuclides over a 1-yr exposure period.

R

'=SUDW (Equation 10) where, for radionuclide i:

Si= radionuclide area concentration in soil, pCi/M2 Di= dose factor, mrem per hr/pCi per M2 Ri= annual dose, mrem/yr 26 March 2006 26 March 2006

TR-01 -2006 U = exposure time, hr/yr W= geometry factor, unitless (Table A-2, RG 1.109)

Because most of the spill area is inside the fenced Exelon property, the only publicly accessible portion of the spill area is in the ditch adjacent to Smiley Road. The hypothetical soil concentrations in the ditch in 1998 following the VB-3 release were calculated based on ratios determined from VB-2 spill information. For the VB-2 spill in 2000, the ratio of the tritium concentration in water samples from the ditch (35,000 pCi/L) to the composite tritium level in the blowdown line at the time (91,400 pCi/L, see Section 2.3) was 0.38. The spill area concentrations determined near the VB-3 vault in Table 7 (original spill concentration) were multiplied by this ratio to estimate the potential soil concentrations in the ditch. Table 9 list, the calculated hypothetical soil concentrations in the ditch. The ditch soil concentration was used to calculate the estimated area concentration (pCi/h 2) by assuming the activity was distributed in the soil surface to a depth of 5 cm and using a soil density of 1.3 g/cm3, as shown in Equation 11:

Si= qsx 10,000 cM2 /m12 x 5cm deep x 1.3g/cn 3 x 0.OOlkg/g (Equation 11)

= CQx 65kg/rm2 where, for radionuclide i:

Si = radionuclide area soil concentration, pCi/M2 G = radionuclide mass concentration in soil, pCi/kg Table 9. External radiation dose calculation data.

VB-3 Vault Area Soil Derived Ditch Soil Derived Ditch Area Dose Factor Nuclide Concentration pCi/kg Concentration pCi/kg Concentration pCi/m2 mrem/hr per pCi/m2 Sl--124 5.8 E+2 2.2 E+2 1.4 E+4 2.3 E-8 Sb-125 3.3 E+2 1.3 E+2 8.1 E+3 5.7 E-9 Co-58 3.0 E+3 1.2 E+3 7.5 E+4 7.0 E-9 Co-60 2.1 E+2 7.9 E+l 5.1 E+3 1.7 E-8 C:;-137 1.9 E+2 7.2 E+l 4.7 E+3 4.2 E-9_

The external dose factors were from RG 1.109, Table E-6, except for the antimony isotopes that are not included in RG 1. 109. Federal Guidance Report No. 12 (EPA 1993) was the source of external dose factors for antimony-124 and antimony-125.

27 March 2006 27 Marchs 2006

TR-01-2006

4.

BOUNDING ESTIMATES OF DOSE This section presents bounding estimates of the radiation dose that members of the public could have received from exposure to tritium. The bounding estimates are the highest reasonable radiation doses that could have been received by members of public. The exposure scenarios developed for and described in this section could have resulted in public dose, regardless or whether or not they actually occurred. This section also hypothesizes potential exposure to radionuclides other than tritium in a limited number of scenarios, even though none of these other radionuclides have been detected offsite.

The bounding exposure scenarios are characterized in three different ways:

Reconstructed exposure scenarios have been prepared for the 1998 release from VB-3.

These scenarios reconstruct the conditions that could have existed at the time of these releases-especially considering potential exposure from water that flowed over the surface of the ground-to make bounding estimates of public exposure that could have occurred. These reconstructed scenarios do not represent present or future exposure potential.

Current exposure scenarios are based on environmental conditions and radionuclide concentrations that currently exist around the Braidwood Station. These scenarios represent the bounding estimates of dose that nearby residents could be receiving in the present from the water that has leaked from the blowdown line VBs.

Hypothetical future scenarios assume no remediation and have the same types of exposures as the current scenarios but assume that residents are exposed to higher concentrations of tritium in the groundwater plume. Because the tritium concentrations are higher, the hypothetical future scenarios are the highest dose estimates presented.

The following sections present exposure scenarios and estimates of dose from VB releases in chronological order. The first release occurred in 1996.

4.1 Tritium Doses from the VB-1 Release (1996)

No reconstructed tritium dose scenarios were developed for the VB-1 1996 release because all released water remained on the site and did not flow overland to the ditch (the paved road into the Site provides an effective barrier between the vault and the ditch), and because groundwater has only recently reached the vicinity of the drainage ditch. Groundwater can flow into the drainage ditch and the potential exists for it to flow off the site. For purposes of the scenario the groundwater is assumed to flow undiluted directly into the drainage ditch on a seasonal basis (i.e., spring) and be present long enough to fulfill the exposure assumptions in the scenarios below. The groundwater/ditch water tritium concentration is assumed to be undiluted by rainwater or runoff, with a concentration of 1,200 pCi/L, the current concentration of tritium in groundwater at the ditch.

Two scenarios were considered for the VB-1 releases, based on the potential for groundwater to enter the drainage ditch and flow off the site; these scenarios were evaluated for possible current 28 March 2006 28 March 2006

TR-01-2006 and hypothetical future exposure scenarios. The current scenario assumes a water concentral ion of 1,200 pCi/L (the current groundwater concentration at the ditch), while the hypothetical fiuture scenario assumes a water concentration of 20,000 pCi/L (the concentration at the plume centerline that could reach the ditch sometime in the future with no remediation and be transported off the site).

4.1S.1 Wading in the Drainage Ditch The first scenario assumed children or teenagers play and wade in the water and inadvertently ingest some of the water containing tritium. A child or teenager was assumed to play in the ditch when water was present for 90 d and ingest 250 mL (8.5 oz) each time for a total of 22.5 L (23.8 quarts). There is minimal potential for dose from wading in the water and absorbing tritium through the skin. NUREG/CR-4013 considers absorption to be 0 (Strenge et. al 1985). The assumptions made for ingestion of the ditch water are considered to include any potential do:;e from absorption through the skin from wading in the water.

Table 10 lists the tritium dose for the ditch-wading/inadvertent water ingestion exposure scenario. The dose to a child from tritium under the current scenario with water concentration of 1,200 pCi/L would be about 0.004 mrem. Under the hypothetical future scenario with water concentration of 20,000 pCi/L the highest estimated tritium dose would be about 0.06 mrem to a ch'ld. This exposure and dose received is assumed to take place in I yr.

Table 10. Dose from ditch wading/inadvertent water ingestion scenario, VB-1 (mrcm).

Current Scenario llypothetical/Future Scenario Water Concentration:

1 pCL 20,000 pCi/L Age Group' Adult N/A N/A Teenager 2.0 E-3 3.3 E-2 Child 3.8 E-3 6.4 E-2 Infant N/A N/A I.

Adults and infants would not be exposed during this scenano.

The estimated lifetime dose from this scenario would depend on how many years a child or teenager played in the ditch. An estimate of continuing exposure for 10 yr for the hypothetical future groundwater concentrations would result in a dose of about 0.5 mrem.

4.1.2 Consuminq Wild Game Animals That Drink Ditch Water Standing water in the drainage ditch could be consumed by wild game. This scenario evaluated the dose to a nearby resident that consumed wild game (deer and geese) that drink only the tritium-containing water standing in the drainage ditch. The evaluation assumed a 90-kg (200-Ib) deer drinking 5.7 L/d and 5-kg (1 I-lb) geese drinking 0.42 L/d from the ditch for a period of time sufficient for the tritium concentration in meat to reach equilibrium with the tritium concentration in the ditch water (normally at least 30 d). An adult resident consumes all of the venison from the deer (30 kg), a teenager consumes about 18 kg, and a child consumes about 11 kg, while an infant would not consume venison. To provide a direct comparison of 29 March 2006

TR-01-2006 doze from consumption of the two types of wild game, the consumption rate of goose meat was assumed to be the same as the consumption rate of venison.

Table 11 lists the tritium dose from consuming the venison from ditch water exposure scenario.

The concentration of tritium in venison is about 14 times higher than the concentration in goose meat, and the dose from venison would be 14 times higher than the dose from goose. The highest dose would be to an adult who ingested the venison; doses to teenagers and children would be lower. Adults receive higher doses because of the higher venison consumption rate.

Under the current scenario the estimated dose from tritium would be less than 0.0003 mrem.

Under the hypothetical future scenario the adult would also receive the highest dose, with about 0.004 mrem.

Table 11. Dose from ingesting venison and goose from ditch water scenario, VB-I (mrem.

Current Scenariol Hypothetical/Future Scenario Water Concentration:

1,200 pCi/L 20,000 pCiIL Age Group' Venison (goose)

Venison (goose)

Adult 2.6 E-4 (1.9 E-5) 4.3 E-3 (3.1 E-4)

Teenager 1.5 E-4 (1.1 E-5) 2.6 E-3 (1.9 E-4)

Child 1.9 E-4 (1.4 E-5) 3.1 E-3 (2.2 E-4)

Infant N/A N/A

1. Infants would not be exposed during this scenario, because there are no usage factors for infants.

A lifetime dose of about 0.07 mrem from the hypothetical future scenario was estimated, bas;ed on an adult consuming 30 kg of venison every year for 70 yr.

4.2 Doses from the VB-3 Release (1998)

The November 1998 release fromVB-3 could have resulted in potential exposures from both groundwater and surface water because it was a large leak. It was estimated to be 3 million gal (see Table 2) that flowed out of the vault and over the ground surface, pooling in low-lying areas and the Smiley Road ditch before eventually soaking into the soil and reaching the groundwater.

Water in the radioactive waste tanks that were released to the blowdown line (see Section 2) contained trace concentrations of radionuclides other than tritium. There is no indication that any of these other radionuclides ever reached the offsite environment. Information compiled for the 10 CFR 50.75(g) documentation files in 2001 show that cobalt-60 was detected in a few soil samples in the immediate area of the VB-3 vault where the leak originated; no other radionuclides were detected. To provide bounding estimates of the exposure and dose that could have been received, these other radionuclides are assumed to have been present in the water that flowed overland. Section 3.5 presents the method used to identify other radionuclides and their potential concentrations that could have been present in the offsite environment.

The following sections present a number of different types of exposure scenarios. They include reconstructed exposure scenarios that could have resulted in exposures to nearby residents around the time of the release in 1998, as well as current and hypothetical future exposure scenarios that could result from the presence of tritium in groundwater and in the water of the Exelon Pond.

30 March 2006 30 March 2006

TR-01-.2006 4.2.1 External Exposure from Radionuclides Deposited in Smiley Road Ditch The other radionuclides detected in water samples from the radioactive waste tank that was released to the blowdown line were assumed to have been in the water released from the VB-3 vault (see Section 3.5) that accumulated in the Smiley Road ditch. The other radionuclides (tritium is not a contributor to external dose) were assumed to have been deposited on the soil surface as the water drained. These beta/gamma radiation-emitting radionuclides were assumed to deliver an external dose to a person walking nearby on Smiley Road. This person was assumed to routinely pass the ditch for I hour/d for 1 yr; radioactive decay of the radionuclides and shielding from leaching into deeper layers of the soil were not considered. The geometry of the ditch was assumed to be similar to the geometry of a river bank and a geometry factor of 0.2 (Uv) was applied to account for the difference in dose compared to standing in the middle of an infinite plane source (W= 1.0) using the factor from RG 1.109.

Table 12 lists the dose to a routine passerby from beta/gamma-emitting radionuclides present in the Smiley Road ditch. There would be no difference in external dose to the adult, teenager, child, or infant. The dose to this hypothetical individual under the reconstructed exposure scenario would be about 0.001 mrem. This exposure and dose is assumed to take place over the coirse of I yr.

Table 12. External dose from radionuclides in the Smiley Road Ditch scenario, VB-3 (mrem).

Reconstructed Scenario Age Groupi Co-58 I Sb-124 l Co-60 Sb-125 Cs-137 Total Adult Teenager 5.9 E-4 3.7 E4 9.8 E-5 5.2 E-5 2.2 E-5 1.1 E-3 Child I Infant__

I.

Infants would likely not be exposed (luring this scenario, except as infant in arms.

The radionuclides in the ditch soil would continue to decay radioactively after being deposite-d.

They could also leach through the soil or become covered by additional soil layers, further reducing the dose rate at the road. After a period of about 2 yr, the samples in 2001 showed only co 3alt-60 to be present above minimum detectable activities. Therefore, radionuclides were assumed to decrease to the levels measured in 2001. A conservative estimate of the lifetime dose frcm external exposure would be 2 times the value presented above because short-lived radionuclides (cobalt-58, antimony-124) would have decayed away, and there is no indication of longer-lived radionuclides (antimony-125, cesium-137) that should have been detected if present.

4.2.2 Consuming Wild Game That Drinks Pooled Surface Water As described in the earlier sections, leakage from the VB-3 vault flowed across the ground surface and pooled in low-lying areas and filled the ditch on the south side of Smiley Road. The concentration of this water was not sampled during the release in 1998. Therefore, tritium concentrations in pooled surface water were estimated by using the median concentration detected in groundwater near the location (230,000 pCi/L) and accounting for radioactive decay sirce the time of the release. The assumed initial concentration in the pooled surface water from the VB-3 release was 350,000 pCi/L.

31 March 2006 31 March 2006

TR-01-2006 This scenario was evaluated to reconstruct any potential dose from the 1998 release. There are no current or hypothetical future exposure scenarios because the pooled and standing ditch water frcm the line existed only at the time of release. It was assumed a 90-kg (200-lb) deer drank the water and the venison was subsequently consumed by a nearby resident. The deer drank 5.7 L/d for a period of time sufficient for the tritium concentration in deer meat to reach equilibrium with thc tritium concentration in the ditch water (normally at least 30 d). Only a portion of the deer's drinking water (12 percent) was from the pooled water or Smiley Road ditch because the deer's normal range would provide it the opportunity to drink from numerous other sources of surfice water in the area (see carrying capacity basis presented in Section 4.2.3). An adult resident was assumed to consume all of the venison from the deer (30 kg), a teenager to consume about I8 kg, and a child to consume about 11 kg. The potential dose from consumption of wild geese was also considered; however, Section 4.1.2 (Table I1) demonstrated that consumption of goose results in a dose that is about 7 percent of that from consuming venison, so no further evaluation was done.

Table 13 lists the tritium dose from consuming the venison from the ditch water exposure scenario. The highest dose would be to an adult who ingested the venison; doses to teenagers and children would be lower. Adults receive higher doses because of the higher venison consumption rate. Under the reconstructed exposure scenario the estimated adult dose from triiium would be about 0.01 mrem.

Table 13. Dose from eating deer that drinks ditch water scenario, VB-3 (mrem).

Reconstructed Scenario Water Concentration: L!

350,000 pCi/L Age Group' l

Adult 9.5 E-3 Teenager 5.4 E-3 Child 6.5 E-3 Infant N/A

1. Infants would not be exposed during this scenario, because there are no usage factors for infants.

The estimated lifetime dose from this scenario would be the same as shown in Table 13. No continuing dose from this scenario would occur because the water drained from the ditch.

4.2.3 Consuming Wild Game Ingesting Water and Vegetation from the Surface SPDiI Area This scenario is similar to that in Section 4.2.2, but it also includes game animal consumption of ve getation growing in the area where the surface flow from the VB-3 vault occurred. The tritium coacentration of the water flowing over the surface was assumed to the same as that detected at the centerline of the tritium groundwater plume, corrected for radioactive decay since the release occurred in 1998. The concentration used in calculations was 350,000 pCi/L. Other radionuclides also could have been deposited in these areas when the water drained into the soil.

The standing water could have been drunk by game and later the following spring vegetation growing in these areas could have absorbed the deposited radionuclides and then be consumed by game animals. The area of the water flow across the surface and standing water were 32 March 2006 32 March 2006

TR-01 -2006 estimated to cover an area of about 15,000 m2 between VB-3 vault and the Exelon Pond. This is a triangular area that roughly approximates the current area of the groundwater tritium pluma.

Deer have been shown to be the wild game animal with the greatest potential for dose to humans through consumption of venison. A 90-kg (200-lb) deer was assumed to drink 5.7 L/d of water and consume 15 kg/d of vegetation. The deer was assumed to consume a portion of its water and feed from the area where the standing water and overland transport of water took place. This consumption was assumed to take place for a period of time sufficient for the radionuclide concentrations in deer meat to reach equilibrium with the radionuclides in water and vegetation.

Murphy (1970) cites research by Hosley (1956) as to the relatively consistent carrying capacity of white-tailed deer in the Midwest of I deer per 32 acres (13 hectares). Based on this carrying capacity the presumed surface area of the overland release would comprise about 12 percent of the range of a deer. Therefore, a deer around the Braidwood Station was assumed to get 12 percent of its food and water from the area of the spill. This is a conservative assumption that results in an overestimation of dose because the standing water was present for no more than 30 d (shorter than the time required for equilibrium with tritium to be reached) and tritium is the main contributor to ingestion dose. Also, radionuclides are assumed to be deposited evenly over the entire area of the spill, when it is more likely that surface flow and any radionuclide deposition occurred only in the low-lying area, reducing the percentage of potentially contaminated vegetation consumed.

As in the game consumption scenarios discussed above, an adult resident was assumed to consume all of the venison from the deer (30 kg), a teenager to consume about 18 kg, and a child to consume about 11 kg.

Table 14 lists the dose to nearby residents from consuming the venison obtained from a deer drinking this water and consuming the vegetation. The dose to the highest exposed organ is also presented in this table because ingestion of radionuclides other than tritium differentially affect different organs, while dose from tritium is the same for all organs and presented as a total body dose. Tritium is by far the dominant dose contributor from this pathway, contributing greater than 99 percent of the dose. The dose is highest to an adult because of consumption rates of venison and water. The total body dose is about 0.03 mrem and the dose to the maximally exposed organ, the gastrointestinal tract/lower large intestine (GI-LLI) is also about 0.03 mram.

The radionuclides in the soil and vegetation would continue to decay radioactively and to become less available as they moved deeper into the soil. They could also migrate through the soil (especially tritium) and become less available for uptake by plants. After a period of about 2 yr the samples in 2001 showed only cobalt-60 to be present above its MDA. Lifetime total body doses would be less than double those presented above, mainly due to tritium becoming less available in water and surface soil. The lifetime dose would be about 0.05 mrem.

4.2.4 Drinking Well Water The leakage from VB-3 resulted in a plume of groundwater containing tritium. This plume has extended north from VB-3, underneath and through the Exelon Pond, and into a private weli north of the pond. This scenario assumed the well was used for drinking water consumed by onsite residents. The identified tritium concentration in this water well at the present time for the 33Mac320 33 March 2006

TR-01 -2006 Table 14. Dose from ingesting venison from overland release scenario, VB-3 (mrem).

Reconstructed Scenario Water Concentration:

350 000 pCiL Age Group' Total body2 Organ7 - GI-LLI Adult 3.3 E-2 3.4 E-2 Teenager 2.0 E-2 2.0 E-2 Child 2.4 E-2 2.4 E-2 Infant N/A N/A

1. Infants would not be exposed during this scenario, because there are no usage factors for infants.

2.

Contributing radionuclides include cobalt-60, cobalt-58, antimony-125, and cesium-137 as wvell as tritium (H-3).

current scenario is approximately 1,500 pCi/L. This is a conservative concentration for the current scenario because the concentration has been increasing as the plume moves north toward the well; at previous times the well concentration would have been lower, resulting in less dose.

For the hypothetical future scenario, the well water concentration is assumed to increase to $,000 pCi/L. For both current and future scenarios, an adult resident drinks 730 L/yr from the well, a teenager and child each drink 510 L/y, and an infant drinks 330 L/yr (values from RG 1.109).

Table 15 lists the tritium dose from using well water as a source of all drinking water. The highest annual dose would be to a child, with slightly lower dose to an infant. Under the culTent scenario based on 1,500 pCi/L the estimated dose to a child from tritium would be about 0.:.5 mrem. Under the hypothetical future scenario the dose to the child would be about 0.3 mrcm.

Table 15. Dose from ingesting well water scenario, VB-3 (mrem).

Current Scenario lHvpotheticaUFuture Scenario Water Concentration:

1,500 pCI/L l3,000 pCi/L Age Group Adult 1.2 E-l 2.3 E-l Teenager 8.2 E-2 1.6 E-l Child 1.6 E-l 31 E-l Infant

._ E-l 3_0 E-l A lifetime dose of about 4 mrem from the hypothetical future scenario was estimated, based on 70 yr of an adult consuming 730 L of well water every year.

4.2.5 Consuming Irrigated Garden Produce This scenario uses the information and groundwater concentrations from the private well drinking water scenario and assumes this water is used to fully irrigate a backyard produce garden that is consumed by a local resident. This is an unlikely scenario and was specifically excluded from the Braidwood Offsite Dose Calculation Manual, but is included so a complete set of potential exposure scenarios is evaluated. As noted above for the well drinking water scenario, the water concentration is approximately 1,500 pCi/L for the current scenario and 3,000 pCi/L for the hypothetical future scenario. An adult resident consumes 520 kg/yr from the garden, a teenager 630 kg/yr, and a child 520 kg/yr. An infant consumes no produce from the garden.

34 Marci-2006 34 March 2006

TR-01.-2006 Table 16 lists the tritium dose from using well water as a source of irrigation for a backyard garden. The highest annual dose would be to a child. Under the current scenario based on 1,500 pCi/L the estimated dose to a child from tritium would be less than 0.2 mrem. Under the hypothetical future scenario based on 3,000 pCi/L, the annual dose to the child would be slightly more than 0.3 mrem.

Table 16. Dose from consuming garden produce scenario, VB-3 (mrem).

Current Scenario Hypothetical/Future Scenario Water Concentration:

1,500 pCi/L 3,000 pCi/L Age Group' Adult 8.3 E-2 1.6 E-1 Teenager 1.0 E-I 2.0 E-l Child 1.6 E-I 3.2 E-l Infant N/A N/A

1. Infants would not be exposed during this scenario, because there are no usage factors for infants.

A lifetime dose of less than 3 mrem from the hypothetical future scenario was estimated, based on 70 yr of an adult consuming 520 kg/yr of garden produce irrigated with the well water.

4.2.6 Consuming Fish from the Exelon Pond The tritium groundwater plume resulting from the VB-3 release has migrated into the Exelon Pond. This scenario evaluates potential doses that could be received from ingesting fish caught in the pond. The current tritium concentration of water in the Exelon Pond is approximately 3,000 pCi/L. This is a conservative concentration for the current scenario because the concentration has been increasing as the plume moves north toward the pond; for any earlier ex:osures the pond concentration would have been lower, resulting in less dose. For the hypothetical future scenario the pond tritium concentration was assumed to increase to 6,000 pCi/L. An adult resident consumes 21 kg/yr of fish from the pond, a teenager 16 kg/y, and a child 6.9 kg/y. An infant consumes no fish from the pond.

Table 17 lists the tritium dose from consuming fish from the Exelon Pond. The highest dose would be to an adult because of the higher fish consumption rates. Under the current scenario based on 3,000 pCi/L, the estimated annual dose to an adult would be 0.006 mrem. Under the hypothetical future scenario based on 6,000 pCi/L, the annual dose to the adult would be slightly more than 0.01 mrem.

Table 17. Dose from consuming fish from the Exelon Pond scenario, VB-3 (mrem).

Current Scenario Hypothetical/Future Scenario Water Concentration:

3,000 pCi/L 6,000 pCi/L Age Group' Adult 6.0 E-3 1.2 E-2 Teenager 4.6 E-3 9.2 E-3 Child 3.8 E-3 7.6 E-3 Infant N/A N/A

1. Infants would not be exposed during this scenario, because there are no usage factors for infants.

35 March 2006 35 March 2006

TR-01 -2006 A lifetime dose of about 0.2 mrem from the hypothetical future scenario was estimated, bascd on 70 yr of an adult consuming 21 kg/yr of fish from the Exelon Pond.

4.2.7 Consuming Wild Game That Use Exelon Pond This scenario evaluates potential doses from consuming wild game - deer and geese - that use the Exelon Pond as a sole source of drinking water. A 90-kg (200-lb) deer is assumed to drink 5.7 L/d from the pond. Five-kg (I I lb) geese are assumed to consume 0.42 L/d of pond water.

Art adult resident consumes all of the venison from the deer (30 kg), a teenager consumes about 18 kg, and a child consumes about I I kg. For a consistent comparison, the same quantities of goose meat (30 kg, 18 kg, 11 kg) were assumed to be consumed. As discussed under the fish consumption scenario above, the current scenario tritium concentration in the pond is 3,000 pCi/L and the hypothetical future scenario concentration is assumed to be 6,000 pCi/L.

Table 18 lists the tritium dose from consuming the venison from deer that use the Exelon Pond for drinking water. The potential dose from consumption of wild geese was also considered; however, Section 4.1.2 (Table 11) demonstrated that consumption of goose results in a dose that is about 7 percent of that from consuming venison, so no further evaluation was done.

Table 18. Dose from consuming deer that use the Exelon Pond scenario, VB-3 (mrem).

Current Scenario llypotheticat/Future Scenario Water Concentration:

3,000 pCi/L 6,000 pCi/L Age Group' Adult 6.5 E4 1.3 E-3 Teenager 3.9 E4 7.7 E4 Child 4.7 E4 9.3 E4 Infant N/A N/A

1. Infants would not be exposed during this scenario, because there are no usage factors for infants.

The highest dose would be to an adult who ingested the venison; doses to teenagers and children would be lower. Adults receive higher doses because of the higher venison consumption rate.

Under the current scenario the estimated dose to an adult from tritium would be less than 0.0007 mrem. Under the hypothetical future scenario the estimated dose to adult would be about 0.001 mrem.

A lifetime dose of 0.02 mrem from the hypothetical future scenario was estimated, based on 70 yr of an adult consuming 30 kg/yr of venison from deer drinking from the Exelon Pond.

4.2.8 Swimming in the Exelon Pond Children or teenagers could swim in the Exelon Pond and inadvertently ingest some of the water containing tritium. A child or teenager was assumed to swim for 90 d over the course of a sunmer, and ingest 250 mL (8.5 oz) each time, ingesting a total of 22.5 L (23.8 quarts). There is minimal potential for dose from absorbing tritium through the skin; the NUREG/CR 4013 (S-xenge et. al 1985) dose factor for absorption through the skin in water is 0.

36 March 2006

TR-01-2006 Table 19 lists the tritium dose from swimming in the Exelon Pond. The dose to a child from trilium under the current scenario with a pond water concentration of 3,000 pCi/L would be less than 0.01 mrem. Under the hypothetical future scenario, with a water concentration of 6,000 pCi/L, the highest estimated tritium dose would be about 0.02 mrem to a child. The dose to a teenager would be less.

Table 19. Dose from swimming in the Exelon Pond scenario, VB-3 (mrem).

Current Scenario HIypotheticaLFuture Scenario Water Concentration:

3,000 pCi/L 6,000 pCi/L Age Group' Adult N/A N/A Teenager 5.0 E-3 1.0 E-2 Child 9.6 E-3 1.9 E-2 Infant N/A N/A

1. Adults and infants would not be exposed during this scenario.

The estimated lifetime dose from the hypothetical future scenario would depend upon how many years a child or teenager swam in the pond. An estimate of continuing exposure for 1 0 yr would result in a dose of less than 0.2 mrem.

4.2.9 Exposure to Center Street Ditch Water Recent samples of water collected from the Center Street ditch (see Figure 1) were found to coitain tritium concentrations less than 1,000 pCi/L. This tritium likely originated from the shallow groundwater plume underlying the area (see Figure 3) and reached the ditch through drainage tiles in nearby fields during the winter and early spring when the groundwater table rises. Potential exposure scenarios for this water have been previously evaluated at higher trii ium concentrations in the site drainage ditch in Section 4.1.1 (ditch wading), the Smiley Road ditch in Sections 4.1.2 and 4.2.2 (consuming animals that drink the water), and possibly the V1-3 spill area in Section 4.2.3 (consuming animals that drink the water and eat vegetation growing there). Because these other scenarios bound potential doses that could be received from exposure to tritium in the Center Street ditch water, no estimates of dose are provided here.

4.3 Dose from the VB-2 Release (2000)

The 2000 release fromVB-2 was similar in volume to the earlier 1998 release from VB-2, but concentrations of radionuclides were less than those in the VB-3 release (see Section 2.3). In addition, standing water from the VB-2 release was removed from the ground surface by pumping it back into the blowdown line. This resulted in a significantly smaller groundwater plume and lower tritium concentrations in the plume than for releases from VB-3. Groundwater monitoring determined that the VB-2 groundwater plume has not moved off the site (Figures 3 ani 4); therefore, none of the offsite groundwater exposure scenarios apply for VB-2.

The information presented in Section 2.3 indicates the average tritium concentration in water at the time of the VB-2 release was about 27 percent of that during the VB-3 release. There was surface flow of water from the VB-2 vault and pooling on the surface of the ground and collecting in the Smiley Road ditch. Therefore, exposure scenarios that apply to VB-2 include:

37 March 2006 37 March 2006

TR-01-2006

Consuming wild game that use ditch water, Section 4.2.1 (tritium)

External exposure from radionuclides deposited in ditch, Section 4.3.1 (other radionuclides)

Consuming wild game that ingests water and vegetation, Section 4.3.2 (tritium, othei radionuclides)

The doses from the VB-2 release are estimated to be about 27 percent of the VB-3 doses calculated in Section 4.2, because the VB-2 tritium release concentration was estimated to be 27 percent of the VB-3 tritium release concentration. Therefore, the doses calculated for the V13-3 release bound the VB-2 doses in cases applicable to both of these onsite VBs and no additional calculations are performed for the VB-2 release.

4.4 Tritium Dose from the VB-4 Release (2003)

V13-4 is located off the site between the Braidwood Station and the termination of the blowdown line at the Kankakee River. A small, low-flow leak occurred at VB-4 in 2003. No liquids reached the surface of the ground, and the tritium groundwater plume remains small. The highest concentration of tritium detected in the plume is approximately 32,000 pCi/L (Table 1).

Although the VB location is off the site, there is little opportunity for exposure to this plume.

Vegetation could have roots that reach the upper groundwater plume and absorb tritium into vegetation consumed by wildlife such as deer. Using the guidance of RG 1. 109, the concentration of tritium in this vegetation is conservatively assumed to be the same as the groundwater concentration. No other radionuclides would be a source of exposure, and therm are no other exposure pathways or scenarios.

Table 20 lists the dose from a hypothetical scenario of ingesting venison from deer that consumed vegetation with tritium from the VB-4 groundwater plume. The highest dose would be to an adult who ingested the venison, because of the higher venison consumption rate. Doses to teenagers and children would be lower. Under the current and hypothetical future scenarios the estimated dose from tritium would less than 0.02 mrem.

Table 20. Dose from ingesting venison consuming tritiated vegetation scenario, VB-4 (mrem).

Current and Hypothetical/ Future Scenarios Water Concentration:

32,000 pCi/L Age Group' Adult 1.8 E-2 Teenager 1.1 E-2 Child 1.3 E-2 Infant N/A

1. Infants would not be exposed during this scenario, because there are no usage factors for infants.

The estimated lifetime dose from this scenario, although unlikely, is based on 70 yr of an adult consuming 30 kg/yr of venison from deer consuming vegetation in equilibrium with tritium in the VB-4 groundwater plume. Assuming the tritium groundwater concentration would remain at 32,000 pCi/L, the lifetime dose would be about 1.3 mrem.

38 March 2006

TR-01..2006 4.5 Tritium Dose from VB-6 and VB-7 Releases (dates undetermined)

V11-6 and VB-7 are also located off the site between the Braidwood Station and the termination of the blowdown line at the Kankakee River. Small, low flow leaks have occurred at these VIBs in the past; low concentrations of tritium in groundwater were discovered in 2006 (see Table 1).

No liquids reached the surface of the ground, and the tritium groundwater plume remains small.

The highest concentration of tritium detected around both VB vaults is less than 3,000 pCi/L.

Although the VB locations are offsite, there is little opportunity for exposure to this plume. The VJ3s are located in areas where crops (corn or sorghum stubble was observed) can be grown to feed livestock. The area of the plume under the cropland is small, and tritium would reach only a srrall portion of the crop if roots reached the upper groundwater plume and absorbed tritium.

Other vegetation outside the cropland could absorb the tritium and be consumed by deer as de scribed in Section 4.4. The tritium dose from consumption of livestock or deer by nearby residents is expected to be bounded by the dose estimates for releases from VB-4 presented in Section 4.4.

4.6 Summary of Bounding Exposure Scenario Dose Estimates Table 21 summarizes the bounding exposure scenario dose estimates. The bounding potential dose to a member of the public from a bounding exposure scenario was estimated to be about

0. 1 6 mrem/yr, from a child drinking water from a groundwater well north of the Exelon Pond.

The exposure scenario of a child consuming a large amount of home-grown garden produce that was irrigated with the same well water resulted in about the same dose.

Table 21. Summary of bounding exposure scenarios and maximum doses (mremyr).

Age Hypothetical VB, year of release Exposure Scenario Group' Dose Future Dose VB-1, 1996 Ditch wading/swimming Child 0.0038 0.02 Eating game that drinks ditch water Adult 0.00026 0.004 External exposure from ditch (R)2 All ages 0.0011 N/A 3 Eating game that drinks ditch water (R)2 Adult 0.0095 N/A3=

Eating game consuming vegetation & water from Adult 0.033 N/A 3 overland release (R)2 VB-3, 1998 Drinking well water Child 0.16 0.3 Eating irrigated garden produce Child 0.16 0.3 Exelon Pond: eating fish Adult 0.0060 0.01 Exelon Pond: eating game that drink from the pond Adult 0.00065 0.001 Exelon Pond: swimming Child 0.0096 0.02 VB-2, 2000 Less than applicable VB-3 scenarios-VB4, 2003 Eating game consuming vegetation Adult 0.018 0.01:3 VB-6, VB-7 4 Less than VB14 scenario

1. The age group (adult, teenager, child, or infant) with the highest dose for each scenario.

2.

(R) indicates a reconstructed exposure scenario.

3.

N/A = not applicable for this exposure scenario.

4.

Exact release date undetermined, but maximum plume concentration determined.

The hypothetical future doses from continuing exposure to increased concentrations of tritium in groundwater are also presented. The same two exposure scenarios as above would result in the maximum doses of about 0.3 mrem/yr.

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TR-01-2006

5.

REALISTIC ESTIMATES OF DOSE Section 4 presented bounding estimates of dose that were the highest reasonable estimates of dose that could have been received by nearby residents from the inadvertent releases of water from the blowdown line. The reconstructed exposure scenarios could only have occurred immediately following the releases, while other exposure scenarios were examined to evaluate current or future radiation dose potential. This section evaluates the exposure scenarios developed in Section 4 to develop more realistic estimates of radiation dose that members of the public could receive and to identify and focus on scenarios with the highest potential dose. A graded approach to this evaluation ensured that the appropriate level of analysis was used. The process started with the broad-based, conservative assessment of exposure scenarios in Section 4.

This section refines that assessment with a more realistic, sharply defined analysis. The graded approach for this evaluation included the following criteria:

1. Likely scenarios. The broad umbrella of bounding exposure scenarios in Section 4 were more closely evaluated, and unrealistic scenarios were eliminated from further consideration.

2. Very low dose. Exposure scenarios that could have occurred but would result in very low doses under bounding conditions were eliminated from further consideration.

3. Realism. After criteria 1 and 2 were applied, the remaining exposure scenarios were adjusted to evaluate the actual exposure that could have occurred using assumptions and parameter values that more closely reflect the actual environmental conditions, characteristics, and lifestyles of nearby residents, wherever additional information was available and could be justified.

The purpose of applying this graded approach was to identify exposure pathways to which nearby residents could have actually been exposed, and to make realistic estimates of the radiation doses received from these exposures. These dose estimates can then be compared to the applicable NRC limits for radiation dose to members of the public.

An initial step was to establish a threshold for very low dose, below which no further consideration of a particular exposure scenario would be needed. An annual dose of 0.001 rnrem was selected as a threshold screening level. This dose was considered to provide an adequate margin of conservatism below which there would be negligible health or regulatory concerns.

From a health perspective this screening level corresponds to an annual risk level of 5.25 x I 0 0/yr (<I in 1,000,000,000) using the Federal Guidance Report No. 13 mortality risk coefficient (EPA 1999). From a regulatory perspective, this screening level is well below the ALARA-based design objective of 6 mrem/yr for a two-unit site in 10 CFR 50, Appendix I 'see Section 2.5), and even further below the 100-mrem/yr regulatory dose limit for a member of the public provided in 10 CFR 20, Subpart D. This screening level of 0.001 mrem is also a small fraction of the doses to the maximally exposed individual presented in the Braidwood Station annual radiological environmental operating reports (Commonwealth Edison 1999, 2001; Exelon 2002, 2003, 2004, 2005). A bounding scenario could be immediately eliminated from further consideration if the annual dose was less than 0.001 mrem. If a realistic scenario was determined to result in a dose lower than 0.001 mrem, then that scenario also was no longer considered.

40 March 2006

TR-01-2006 5.1 Evaluation of Exposure Scenarios None of the VB-i, VB-4, VB-6, or VB-7 exposure scenarios were considered a realistic source of exposure. The drainage ditch associated with VB-1 flows only intermittently and then mainly with runoff from rainwater rather than only with groundwater inflow. It is approximately 1/3 of a mile from the leading edge of the groundwater plume to the edge of the site, so any flow beginning in the area of the groundwater plume would have significant additional dilution before flowing off the site. The scenario of deer drinking ditch water and a nearby resident consuming the venison was already less than 0.001 mrem. The certain dilution in water present in the ditch would reduce all potential VB-I exposures below 0.001 mrem/yr.

The VB-4 exposure scenario assumed that all of the vegetation consumed by deer was in equilibrium with tritium in the groundwater plume and that the deer ate only this vegetation. In reality this is a small plume that could comprise only a small fraction of deer's browsing/grazing range. It is also very unlikely that all of the consumable vegetation above the plume is in equilibrium with the tritium in the plume. The actual dose from this scenario would be less than 0.001 mrem/yr, so it was not considered further.

Exposure scenarios for releases from VB-6 and VB-7 were determined to be very similar to scenarios for VB-4 releases. The VB-4 scenario would bound VB-6 and VB-7 doses because the VB-4 groundwater tritium concentration is approximately 10 times higher than that around VB-6 and VB-7. Therefore, the dose would be less than 0.001 mrem/yr for VB-6 and VB-7 scenarios, and they were not considered further.

The exposures scenarios for VB-2 releases were determined to be a subset of the scenarios evaluated for VB-3 releases. As such, the VB-3 doses would bound the VB-2 doses due to (1) the higher concentrations of tritium in the VB-3 water released and (2) the VB-2 release was remediated by pumping standing water back into the blowdown line. Therefore, the potential doses from VB-2 exposure scenarios were encompassed by the following evaluation of VB-:3 scenarios. VB-2 exposure scenarios were not explicitly considered further.

Exposure scenarios for the VB-3 releases represented the largest and most diverse set of potential exposures from any YB release. The following scenarios were evaluated and eliminated from fauther consideration:

The reconstructed VB-3 exposure scenarios were eliminated from further consideration because they could have occurred only soon after the release and would have been of short duration. Any dose received would have been less than 0.001 mrem.

Irrigation of a backyard garden that provides all of the produce for a resident is not considered a realistic exposure scenario because there is little irrigation in this area due to the substantial rainfall. Fulltime irrigation would be required for vegetation to be in equilibrium concentration with tritium in groundwater. Further, there is no indication within the existing groundwater plume footprint of a sufficiently large garden that could produce a large quantity of produce for individual consumption. There is only one private well with identified tritium concentrations attributable to the VB releases.

Therefore, the actual dose from this scenario would be less than 0.001 mrem.

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TR-01.-2006

The Exelon Pond is not the type of pond that children or teenagers would routinely swim in for 90 d/yr. Further, the amount of pond water assumed to be ingested is quite conservative. The dose under the bounding scenario was estimated at approximately 0.01 mrem/yr. A more realistic exposure would be less than 0.001 mrem/yr.

Game animals that drink from the Exelon Pond are unlikely to use this pond as the only source of drinking water due to the large amount of surface water available in the area. It is more likely that a deer would use this pond for only a fraction of its drinking water.

The bounding case dose estimate for this pathway was already less than 0.001 mreml/yr.

The remaining VB-3 exposure scenarios that required additional evaluation for realistic exposure conditions and realistic estimates of radiation dose were:

Drinking well water (Section 4.2.5)

Consuming fish from the Exelon Pond (Section 4.2.6) 5.2 Realistic Estimates of Dose More realistic exposure scenarios were evaluated using assumptions and parameter values that more closely reflect the actual environmental conditions, characteristics, and lifestyles of nearby residents.

Evaluation of realistic exposure scenarios included calculation of dose using the tritium dose factors from NUREG/CR-4013 (Strenge et al. 1985) that are the basis for current Braidwood OD)CM ingestion dose factors instead of the more conservative RG 1.109 (NRC 1977) values.

These dose factors reduced the dose to 57 percent of the dose calculated under the bounding scenario.

Only one private well north of the Exelon Pond has tritium attributed to the VB releases (private well #8 in Table 1). Indications are that two adult residents have used the well for some portion of their drinking water, but the actual consumption rate is unknown. As shown in Table 4, the RG 1.109 water consumption rate for a maximally exposed individual is 730 L/yr, while the consumption rate for an average individual is 370 L/yr. The range of reasonable doses is from near zero if bottled water were the primary source of drinking water to 0.068 mrcm/yr for wll water consumption characteristic of a maximally exposed individual. The dose from average consumption of groundwater for drinking would be 0.034 mrem/yr.

It is possible for fish to be caught and consumed from the Exelon Pond, or at least the scenario cannot be excluded with information currently available. As shown in Table 4, the RG 1.109 fresh fish consumption rate for a maximally exposed individual is 21 kg/yr, while the consumption rate for an average individual is 6.9 kg/yr. The range of reasonable doses is from ze:-o if no fish were caught and consumed from the Exelon Pond to 0.0034 mrem/yr for fish consumption characteristic of a maximally exposed individual. The dose from average consumption of fish from the Exelon Pond would be 0.0011 mrem/yr.

TLe highest realistic scenario of drinking water from the groundwater well is a potential exposure pathway for two adults using the well noted above. Summing the two realistic 42 March 2006

TR-01 -2006 exposure scenarios (drinking water and fish consumption), the maximum realistic dose that these two adults could receive would be less than 0.072 mrem/yr. The highest dose any other individual could realistically receive would be 0.0034 mrem/yr. Table 22 summarizes the realistic exposure scenarios and the range of doses that could be received by members of the public.

Table 22. Summary of realistic exposure scenarios and doses to the public (mrem/vr).

Average Exposure Scenario Minimum (expected)

Maximum Dinking well water (2 adults)

- 0 0.034 0.068 Eating fish from Exelon Pond (more individuals) 0 0.0011 0.0034 Maximum individual summed dose 0

0

< 0.04

< 0.072

1. Based on average individual drinking water ingestion rate of 370 L/yr.

2.

Based on maximum individual drinking water ingestion rate of 730 L/yr.

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TR-01..2006

6.

CONCLUSIONS This report documents the assessment of bounding and realistic doses that could have resulted, or might in the future result, from inadvertent releases from VBs in the blowdown lines at the Braidwood Station. Sections 1 and 2 provide the background, and Section 3 describes the evolution of potential exposure scenarios. Section 4 uses conservative scenarios from that evaluation to develop dose estimates that are likely to be the upper bound of any actual doses that could have been or could be received by members of the public. Section 5 further evaluates these conservative scenarios to eliminate from consideration those scenarios that are not realistic, and it describes the graded approach used to further refine the scenarios to present realistic estimates of dose, in accordance with 10 CFR Part 20; 10 CFR Part 50, Appendix I; and Regulatory Guide 1.109 (NRC 1997).

Evaluation of potential exposures from the VB releases using conservative exposure scenarios showed all potential doses to be very low. None of the bounding scenarios resulted in a dose over 0.3 mrem/yr or 0.3 mrem per event in any of the reconstructed, current, or hypothetical future scenarios. These bounding dose estimates are a small percentage of the 6 mrem/yr design objective for the site presented in 10 CFR 50, Appendix I, and even further below the 1OD-mrcmlyr regulatory limit in 10 CFR Part 20. The estimated maximum realistic dose was 0.068 mrem/yr from drinking water consumption from a private well north of Exelon Pond; the average or expected value would be 0.034 mrem/yr. The maximum dose from summing the dose received from the two realistic exposure scenarios would be 0.072 mrcm/yr. The average or expected dose from all realistic pathways would be less than 0.04 mrem/yr. These doses could be received by two adults who may have used private well #8 for drinking water. The maximum realistic estimate is only 1.2 percent of the 6-mrem/yr design objective in 10 CFR Part 50, Appendix I, and 0.07 percent of the 10 CFR Part 20 limit. This dose is less than the dose to the critical receptor at Wilmington, Illinois, from routine blowdown line releases to the Kankakee River during 2004, which was 0.088 mrem/yr (Exelon Nuclear 2005). It is also less than doses to the critical receptor at Wilmington from 1998 to 2004.

The National Council on Radiation Protection and Measurements (NCRP) was chartered by the United States Congress in 1964 with a mission to formulate and widely disseminate information, guidance, and recommendations on radiation protection and measurements that represent the co:nsensus of leading scientific thinking. It has had a role in radiation protection in the United States and the world since 1929 and has published well over 100 scientific reports. NCRP Report No. 116 (NCRP 1993) identifies a negligible individual risk level (NIRL) of 1 x 10 7.yr.

The NIRL is "... the level of average annual excess risk offatal health effects attributable to radiation below which efforts to reduce radiation exposure to the individual is unwvarranted."

This level of risk corresponds to a Negligible Individual Dose of 0.01 mSv/yr, or I mrem/yr. All of the doses estimated to occur from the blowdown line releases are below the NCRP's negligible levels.

NC(RP Report No. 93 presents estimates of the average annual background radiation dose received by the United States population (NCRP 1987). The average annual dose to a member of the public from natural background radiation is 300 mrem/yr. When man-made sources cf radiation are considered, of which medical x-rays, nuclear medicine, and consumer products are the major contributors, the background radiation dose increases to 360 mrem/yr.

44 March 2006 44 March 2006

TR-01-2006 The estimated doses from the blowdown line releases at the Braidwood Station are well below the applicable regulatory limits and present negligible risk-less than 0.1 percent of the risk from natural background radiation-to members of the public.

45 March 2006 45 March 2006

TR-01 -2006

7.

REFERENCES 10 CFR 20, Subpart D. Radiation Dose Limits for Individual Members of the Public.

10 CFR 50, Appendix I. Numerical Guides for Design Objectives and Limiting Conditions for Operation To Meet the Criterion "As Low as is Reasonably Achievable "for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents.

40 CFR 190, Subpart B. Environmental Standards for the Uranium Fuel Cycle.

Commonwealth Edison. 1999. Braidwood Station Annual Radiological Environmental Operating Report 1998. Commonwealth Edison, Braidwood, Illinois.

Commonwealth Edison. 2001. Braidwood Station Annual Radiological Environmental Operating Report 2000. Commonwealth Edison, Braidwood, Illinois.

Ccnestoga-Rovers & Associates. 2006. Tritium Investigation. 16841-12-RPT. Conestoga-Rovers & Associates, Chicago, Illinois.

DOE (U.S. Department of Energy) 2002. A Graded Approach for Evaluating Radiation Do.;es to Aquatic and Terrestrial Biota. DOE-STD-1 153-2002. U.S. Department of Energy, Washington, D.C.

EPA (U.S. Environmental Protection Agency) 1993. External Exposure to Radionuclides in Air, Water, and Soil Federal Guidance Report No. 12. EPA-402-R-93-081. U.S.

Environmental Protection Agency, Washington, D.C.

EPA (U.S. Environmental Protection Agency). 1999. Cancer Risk Coefficients for Environmental Exposure to Radionuclides Federal Guidance Report 13. EPA 02-R 001. U.S. Environmental Protection Agency, Washington, D.C.

Exelon Nuclear. 2002. Braidutood Station Annutal Radiological Environmenttal Operating Report 2001. Exelon Nuclear, Braidwood, Illinois.

Exelon Nuclear. 2003. Braidwood Station Annual Radiological Environmental Operating Report 2002. Exelon Nuclear, Braidwood, Illinois.

Exelon Nuclear. 2004. Braidwood Station Annual Radiological Environmental Operating Report 2003. Exelon Nuclear, Braidwood, Illinois.

Exelon Nuclear. 2005. Braidwood Station Annual Radiological Environmental Operating Report 2004. Exelon Nuclear, Braidwood, Illinois.

Halls, L. K. (date unavailable). "What Do Deer Eat and Why?" in Wildlife Management Handbook. [1]

46 March 2006

TR-01 -2006 Hcosley, N. W. 1956. "Management of the White-Tailed Deer in its Environment" in The Deer of North America. Harrisburg, PA: Stackpole Co., and Washington, D.C.: Wildlife Manage. Inst. p. 187-259.

[cited in Murphy 1970]

Murphy, D.A. 1970. "Deer Range Appraisal in the Midwest" in WVhite-Tailed Deer in the Midwest, symposium presented at the 30th Midwest Fish and Wildlife Conference, Columbus, Ohio, December 9, 1968. USDA Forest Service Research Paper NC-39, North Central Forest Experiment Station, Forest Service, United States Department of Agriculture, St. Paul, MN.

NC(RP (National Council on Radiation Protection & Measurements). 1987. Ionizing Radialion Exposure of the Population of the United States. NCRP Report No. 93. National Council on Radiation Protection & Measurements, Bethesda, Maryland.

NC(RP (National Council on Radiation Protection & Measurements). 1996. Screening Models for Releases of Radiontclides to Atmosphere, Surface IVater, and Groutnd. NCRP Report No. 123 (two volumes). National Council on Radiation Protection & Measurements.,

Bethesda, Maryland.

NC(RP (National Council on Radiation Protection & Measurements). 1993. Limitation on Exposure to Ionizing Radiation. NCRP Report No. 116. National Council on Radiation Protection & Measurements, Bethesda, Maryland.

NRC (Nuclear Regulatory Commission). 1977. Calcutlation ofAnnumal Dose to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with JO CFR Part 50, Appendix I. Regulatory Guide 1.109, Revision. Nuclear Regulatory Commission, Washington, D.C.

Strenge, D.L., R.A. Peloquin, and G. Whelan. 1985. LADTAP II - Technical Reference and User Guide. NUREG/CR-4013. Nuclear Regulatory Commission, Washington, D.C.

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BW060049, Radioactive Effluent Release Report

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