Text

Radioactive Effluent Report for January Through December 2002, Attachment a - G, Appendix a - C
	ML031250493
Person / Time
Site:	Quad Cities
Issue date:	04/24/2003
From:	Tulon T; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	SVP-03-032
	Download: ML031250493 (180)
	v • d • e

Attachment A Effluent and Waste Disposal Semiannual Report Quad Cities Nuclear Power Station, January - June 2002 SVP-03-052

CY-QC-120-722 Revision 0 Page 1 of 12 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 1 of 7 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Period: January - June 2002 A. FISSION & ACTIVATION GASES UNIT FIRST SECOND EST. TOTAL QUARTER QUARTER ERROR %

1. Total Release Ci 7.98E+01 1.13E+02 12.4

2. Average release rate for the period pCVsec 1.03E+01 1.44E+01

3. *Percent of ODCM limit Chimney & Stack 5.07E-03 5.78E-03 1.51 E-03 1.90E-03 B. IODINE

1. Total lodine-131.

Ci 9.55E-04 7.87E-04 l

j40.0jl

2. Average release rate for the period 4Ci/sec l_1.23E-04 1.OOE-04 C. PARTICULATES

1. Particulates with half-lives > 8 days Ci 4.01 E-03 2.51 E-03 30.1

2. Average release rate for the period tiCVsec 5.15E-04 3.20E-04

3. Gross alpha radioactivity Ci

<LLD**

4.95E-06 D. TRITIUM

1. Total Release Ci 3.51 E+01 3.16E+01 8.1

2. Average release rate for the period PCi/sec 4.51 EQO 4.02E00 E. IODINE 131 & 133, TRITIUM & PARTICULATE I

1. Percent of ODCM limit Chimney & Stack l

I 1.09E00 I

6.75E-01

% NOBLE GAS GAMMA/NOBLE GAS BETA DOSE LIMITS

- Gross Alpha LLD on page 6 of 7 K.\\CH\\Jim\\ODCM\\1 2QTR02.doc

CY-QC-1 20-722 Revision 0 Page 2 of 12 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 2 of 7 MAIN CHIMNEY GASEOUS EFFLUENTS NUCLIDES RELEASED CONTINUOUS MODE BATCH MODE

1. Fission gases Unit First Quarter Second Quarter First Quarter Second Quarter Kr-85 Ci

<LLD*

NA NA Kr-85m Ci 1.21 EO0 3.32EGO NA NA Kr-87 Ci 1.65EO0 2.27E00 NA NA Kr-88 Ci 2.OOEOO 2.02E00 NA NA Xe-131 m Ci 8.79E-03 3.92E-01 NA NA Xe-1 33 Ci 2.79E+01 4.27E+01 NA NA Xe-133m Ci 5.66E-02 1.38E-01 NA NA Xe-1 35 Ci 7.80E00 7.80E00 NA NA Xe-135m Ci 8.96E00 1.36E+01 NA NA Xe-138 Ci 3.01 E+01 3.28E+01 NA NA Ar-41 Ci 1.39E-01 1.97E-01 NA NA Total for Period Ci 7.98E+01 1.13E+02 NA NA

2. lodines Unit First Quarter Second Quarter First Quarter Second Quarter 1-131 Ci 7.38E-04 7.87E-04 NA NA 1-133 Ci 7.66E-04 9.41 E-04 NA NA 1-135 Ci

<LLD*

NA NA Total for Period Ci 1.50E-03 1.73E-03 NA NA

3. Particulates Unit First Quarter Second Quarter First Quarter Second Quarter Sr-89 Ci 3.55E-04 3.49E-04 NA NA Sr-90 Ci 2.09E-06 3.15E-05 NA NA Cs-1 34 Ci

<LLD*

NA NA Cs-1 37 Ci

<LLD*

NA NA Ba-1 40 Ci 4.63E-04 8.96E-04 NA NA La-1 40 Ci 1.85E-04 4.34E-04 NA NA Cr-51 Ci 9.52E-05

<LLD*

NA NA Mn-54 Ci 2.56E-05 1.41 E-05 NA NA Co-58 Ci

<LLD*

NA NA Co-60 Ci 3.57E-04 3.62E-04 NA NA Mo-99 Ci

<LLD*

NA NA Ag-11 Om Ci

<LLD*

2.12E-05 NA NA Ce-141 Ci

<LLD*

NA NA Ce-144 Ci

<LLD*

NA NA Total for Period Ci 1.48E-03 2.1 OE-03 NA NA

Actual gaseous LLD's reported on page 6 of 7 of this check list.

K:\\CH'Jim\\0DCM\\1 2TR02.doc

CY-QC-120-722 Revision 0 Page 3 of 12 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 3 of 7 REACTOR VENTILATION GASEOUS EFFLUENTS NUCLIDES RELEASED CONTINUOUS MODE BATCH MODE

1. Fission gases Unit First Quarter Second Quarter First Quarter Second Quarter Kr-85 Ci

<LLD*

NA NA Kr-85m Ci

<LLD*

NA NA Kr-87 Ci

<LLD*

NA NA Kr-88 Ci

<LLD*

NA NA Xe-1 33 Ci

<LLD*

NA NA Xe-1 35 Ci

<LLD*

NA NA Xe-1 35m Ci

<LLD*

NA NA Xe-1 38 Ci

<LLD*

NA NA Ar-41 Ci

<LLD*

NA NA Total for Period Ci

<LLD*

NA NA

2. lodines Unit First Quarter Second Quarter First Quarter Second Quarter 1-131 Ci 2.17E-04

<LLD*

NA NA 1-133 Ci 1.46E-04

<LLD*

NA NA 1-135 Ci

<LLD*

NA NA Total for Period Ci 3.63E-04

<LLD*

NA NA

3. Particulates Unit First Quarter Second Quarter First Quarter Second Quarter Sr-89 Ci

<LLD*

NA NA Sr-90 Ci

<LLD*

NA NA Cs-1 34 Ci

<LLD*

NA NA Cs-1 37 Ci 4.95E-06 1.07E-05 NA NA Ba-1 40 Ci

<LLD*

NA NA La-1 40 Ci

<LLD*

NA NA Cr-51 Ci

<LLD*

NA NA Mn-54 Ci 7.64E-04 2.19E-05 NA NA Co-58 Ci

<LLD*

NA NA Fe-59 Ci 5.44E-06

<LLD*

NA NA Co-60 Ci 1.76E-03 3.74E-04 NA NA Mo-99 Ci

<LLD*

NA NA Ag-11 Om Ci

<LLD*

NA NA Ce-141 Ci

<LLD*

NA NA Ce-1 44 Ci

<LLD*

NA NA Total for Period Ci 2.53E-03 4.07E-04 NA NA

Actual gaseous LLD's reported on page 6 of 7.

K.%CH\\Jim\\0DCM\\1 2QTRO2.doc

CY-QC-1 20-722 Revision 0 Page 4 of 12 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 4 of 7 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES A. FISSION & ACTIVATION PRODUCTS UNIT FIRST SECOND EST TOTAL QUARTER QUARTER ERROR%

1. Total Release (not including tritium, Ci 4.24E-02 4.53E-03 5.6 gases & alpha)

2. Average diluted concentration during pCi/mL 7.1 OE-09 5.45E-1 0 batch discharges for the period.

3. Percent of applicable limit*

1.19E-01 1.31 E-02 6.33E-02 6.90E-03

4. Maximum diluted concentration during gCGVmL 6.88E-09 6.35E-10 batch discharges l

B. TRITIUM

1. Total Release Ci 1.03E+01 6.22E00 4.1

2. Average diluted concentration during AICi/mL 1.73E-06 7.48E-07 batch discharges for the period

3. Percent of applicable limit 5.40E-02 3.21 E-02 C. DISSOLVED & ENTRAINED GASES

1. Total Release Ci

<LLD

<LLD 5.6

2. Average diluted concentration during IGCVmL

<LLD

<LLD batch discharges for the period

3. Percent of applicable limit NA NA D. GROSS ALPHA ACTIVITY

1. Total Release Ci

<LLD**

l 14.8

2. Average diluted concentration during hbtch discrharng fnr the neriod pCi/mL NA NA Liters 2.30E+06 1.24E+06 E. VOLUME OF WASTE RELEASED (prior to dilution)

Liters 5.97E+09 8.32E+09 F. VOLUME OF DILUTION WATER USED DURING BATCH DISCHARGES Liters 2.00E+1 1 4.48E+1 1 G. TOTAL VOLUME OF DILUTION WATER USED DURING PERIOD (quarter)

Whole Body/Organ (ODCM)

- Gross Alpha LLD on page 7 of 7 K:\\CH\\him\\ODCM\\12QTR02.doc

CY-QC-1 20-722 Revision 0 Page 5 of 12 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 5 of 7 LIQUID EFFLUENTS NUCLIDES RELEASED CONTINUOUS MODE BATCH MODE Unit First Quarter Second Quarter First Quarter Second Quarter Sr-89 Ci

<LLD*

Sr-90 Ci

<LLD*

Cs-1 34 Ci

<LLD*

Cs-1 37 Ci 1.47E-03 4.13E-05 2.25E-04 4.61 E-05 1-131 Ci 9.19E-04

<LLD*

Co-58 Ci 7.58E-04

<LLD*

1.39E-04

<LLD*

Co-60 Ci 7.28E-03 4.38E-04 3.12E-03 4.59E-04 Fe-59 Ci 1.78E-04

<LLD*

Zn-65 Ci 8.97E-03 1.39E-03 6.46E-04 1.39E-04 Mn-54 Ci 2.05E-03 1.11 E-04 1.06E-03 3.52E-05 Cr-51 Ci 1.88E-03

<LLD*

Zr-95 Ci

<LLD*

Nb-95 Ci 2.14E-04

<LLD*

Mo-99 Ci 4.38E-03

<LLD*

Tc-99m Ci 2.99E-03

<LLD*

Ag-1 Om Ci

<LLD*

6.13E-04 3.33E-05 Sb-1 22 Ci 1.37E-04

<LLD*

Sb-1 24 Ci 2.45E-04

<LLD*

2.47E-04

<LLD*

Ba-1 40 Ci

<LLD*

<LLD

<LLD*

La-1 40 Ci

<LLD*

Fe-55 Ci 7.96E-05

<LLD*

4.74E-03 1.84E-03 Total for Period (above)

Ci 3.16E-02 1.98E-03 1.08E-02 2.55E-03 Xe-1 33 Ci

<LLD*

Xe-1 35 Ci

<LLD*

Actual liquid LLD's reported on page 7.

Prepared by:

Approved by:

1il

__~

Date: o% is I (

Date: O'-,;--O

-k--

KA\\CH\\Jim\\0DCM\\1 2QTRO2.doc

CY-QC-120-722 Revision 0 Page 6 of 12 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 6 of 7 GASEOUS EFFLUENT LLD's (Most Restrictive)

CONTINUOUS MODE NUCLIDE LOWER LIMITS OF DETECTION (LLD's)

UNIT LLD Value ODCM Required LLD

1. Fission gases Kr-85 uCvcc 4 02E-06 None Kr-85m uCvcc 1 67E-08 None Kr-87 uCvcc 3 35E-08 1 E-04 Kr-88 uCVcc 4 18E-08 1E-04 Xe-131m uCvcc 6 OOE-07 None Xe-133 uCVcc 2 76E-08 1 E-04 Xe-1 33m uCvcc 8 88E-08 I E-04 Xe-135 uCicc 1.16E-08 1E-04 Xe-135m uCi/cc 1 58E-07 1E-04 Xe-138 uCicc 1.71E-07 1E-04 Ar-41 uCvcc 7.19E-08 None NUCLIDE LOWER LIMITS OF DETECTION (LLD's)

UNIT LLD Value ODCM Required LLD'

2. lodines 1.131 uCvcc 2 83E-13 1E-12 1-133 uCvcc 3 56E-12 IE-10 1-135 uCVcc 6 OOE-09 None NUCUDE LOWER UMITS OF DETECTION (LLD's)

UNIT LLD Value ODCM Required LLD'

3. Particulates and Tritium H-3 uCvcc 3 23E-1 1 1 E-06 Sr-89 uCicc 2 30E-1 4 1E-11 Sr-90 uC/cc 877E-15 1E-11 Cs-134 uC/cc:

1 47E-13 1E-11 Cs-137 uC/cc 249E*13 1E-11 Ba-140 uCvcc 4 25E-13 None La-140 uCvcc 6 22E-13 None Mn-54 uClcc 1 86E-13 1E-11 Co-58 uClcc 2 06E-13 1E-11 Fe-59 uC/cc 247E-13 1E-11 Co-60 uCi/cc 4 83E-13 1E-11 Zn-65 uCi/cc 4 31E-13 JE-11 Mo-99 uC/cc 312E-12 JE-11 Ce-141 uCi/cc 292E-13 JE-11 Ce-144 uCVcc 1.11E-12 1E-11 Gross Alpha A uC/cc 2 69E-14 1 E-11

ODCM RETS LLD's for weekly samples These may be increased by a factor of 10 for daily samples A Volume assumed to be 0 5 cfm for one week (1.43E+08 cc)

KA\\CH-\\Jim\\ODCM\\1 2QTR02.doc:

CY-QC-1 20-722 Revision 0 Page 7 of 12 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 7 of 7 LIQUID EFFLUENT LLD's (Most Restrictive)

BATCH MODE NUCLIDE LOWER LIMITS OF DETECTION (LD's)

UNiT LLD alue ODCM Required LLD

3. Liquids H-3 uCVcc 3.92E-06 1 E-05 Sr-89 uCVcc 8.12E-09 5E-08 Sr-90 uCvcc 2.13E-09 5E-08 Fe-55 uCvcc 1.23E-07 1 E-06 Kr-85 uCVcc 1.42E-05 None*

Kr-87 uCi/cc 1.50E-07 1 E-05 Kr-88 uCvcc 1.89E-07 1 E-05 Xe-133 uClcc 1.50E-07 1 E-5 Xe-133m uCL/cc 3.90E-07 1 E-05 Xe-135 uCVcc 4 66E-08 1 E-05 Xe-138 uC0cc 6 45E-07 1E-05 Mn-54 uC0cc 7.86E-08 5E-07 Co-58 uCLcc 6 29E-08 5E-07 Co-60 uCVcc 1.35E-07 5E-07 Zn-65 uC/cc 1.32E-07 5E-07 Mo-99 uCVcc 4.55E-07 5E-07 Ag-110m uCVcc 4.32E-08 None Sb-124 uCicc 4.23E-08 None 1-131 uClcc 5 44E-08 1 E-06 Cs-134 uCvcc 5 46E-08 5E-07 Ba-140 uCVcc 2.18E-07 None La-140 uC/co 2.75E-08 None Cs-137 uC0cc 6.14E-08 5E-07 Ce-141 uCvcc 1.01E-07 5E-07 Ce-144 uCVcc 3 78E-07 5E-06 Gross Alpha uCVcc 9.03E-08 1 E-07

Kr-85 required by UFSAR secton 9 1.3 3 K-\\CF-im\\ODCM\\12QTR02.doc

Attachment B Effluent and Waste Disposal Semiannual Report Supplemental Information Quad Cities Nuclear Power Station, January - June 2002 SVP-03-052

CY-QC-1 20-722 Revision 0 Page 8 of 12 ATTACHMENT 3 Annual Effluent Report Supplemental Information Page 1 of 5 Facility: Quad Cities Nuclear Power Station January - June 2002 Licensee: Exelon Generation Companv

1.

Regulatory Limits

a.

For Noble Gases: (per unit)

Dose rate

1.

Less than 500 mrem/year to the whole body

2.

Less than 3000 mrem/year to the skin.

Dose Gamma Radiation

1.

Less than or equal to 5 mrad/quarter.

2.

Less than or equal to 10 mrad/year.

Beta Radiation

1.

Less than or equal to 10 mrad/quarter.

2.

Less than or equal to 20 mrad/year.

b,c.

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

Dose Rate

1.

Less than 1500 mrem/year.

Dose

1.

Less than or equal to 7.5 mrem/quarter.

2.

Less than or equal to 15 mrem/year.

d.

For Liquid: (per site)

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

Less than or equal to 10 mrem to any organ during any calendar quarter.

Less than or equal to 6 mrem to the whole body during any calendar year.

Less than or equal to 20 mrem to any organ during any calendar year.

K:\\CH\\Jim\\ODCM\\1 2QTRO2.doc

CY-QC-1 20-722 Revision 0 Page 9 of 12 ATTACHMENT 3 Annual Effluent Report Supplemental Information Page 2 of 5

2.

Maximum Permissible Concentration a,b,c. For fission and activation gases, iodines, and particulates with half-lives greater than 8 days, allowable release limits are calculated by solving equations 10.1 and 10.2 from the Offsite Dose Calculation Manual. The alarm setpoint is conservatively set at approximately 10% of the 1 OCFR20 limit.

d.

For liquid effluents allowable release limits are calculated by solving equations 10.3 and 10.4 from the Offsite Dose Calculation Manual. The MPC values used for the monitors were as follows:

Radwaste discharge 7.17E-03 gCi/ml Service water 1.OE-05 gCVml

3.

Average Energy The average gamma energy used to calculate the alarm setpoints for the noble gas monitors was 0.893 Mev for the First quarter, and 0.928 Mev for the Second quarter.

4.

Measurements and Approximations of Total Radioactivity

a.

Fission and Activation Gases:

b.

lodines:

c.

Particulates:

The main chimney and reactor building ventilation exhaust systems are continually monitored for iodines and particulates. These samples are pulled every 7 days and analyzed by gamma isotopic. The particulate papers are composited every 31 days and sent to a vendor for Sr89/90 and gross alpha analysis. Noble gas grab samples are pulled and analyzed by gamma isotopic weekly. Tritium samples are pulled and analyzed every month.

The Sr89/90 and gross alpha curies released values reported are actual. On a real time basis, the portion of the "percent of applicable limit" for these contributors is reported based on projections using the previous six (6) months available data. The actual results are obtained by editing the ODCM software inputs when the vendor results become available. Therefore, the "percent of applicable limits" in this report are actual.

K:\\CH\\ilm\\ODCM\\120TR02 doc

CY-oC-1 20-722 Revision 0 Page 10 of 12 ATTACHMENT 3 Annual Effluent Report Supplemental Information Page 3 of 5 The continuous strip chart recorders for the monitors on the release points are reviewed monthly for spikes and the activity released is calculated. An additional calculated activity for noble gases is added to the main chimney release each month. This calculation is done because most of the grab samples show less than the lower limit of detection due to the low amount of activity and the large dilution flow at the sample point. The calculation takes into account the normal offgas train and the gland steam contribution to the release.

The average flow at the release points is used to calculate the curies released.

d.

Liquid Effluents The river discharge tanks are analyzed before discharge by gamma isotopic. A composite representative portion of this sample is saved. This is composited with other discharges that occurred every 31 days and is analyzed for tritium and gross alpha. The monthly composites are composited quarterly and sent to a vendor for Sr89/90 and Fe 55. The discharge bay is sampled every 31 days and analyzed by gamma isotopic, for tritium and gross alpha. It is sampled quarterly and sent to a vendor for Sr89/90 and Fe 55 analysis. On a real time basis, the portion of the "percent of applicable limit" for these contributors is based on projections using scaling factors. The actual results are obtained by editing the ODCM software inputs when the vendor results become available. Therefore, the "percent of applicable limits" in this report are actual.

The tank volumes and activities are used to calculate the curies released for the River Discharge Tank. The total water released during the quarter and the activity is used to calculate the diluted activity released at the discharge bay, from batch discharges.

e.

Estimated Total Error Percent The estimated total error percents were calculated by taking the square root of the sum of the squares of errors for sampling and measurement parameters.

K:\\CH\\Jim\\ODCM\\1 2QTR02.doc

CY-QC-1 20-722 Revision 0 Page 11 of 12 ATTACHMENT 3 Annual Effluent Report Supplemental Information Page 4 of 5

f.

Less than the lower limit of detection (<LLD*)

Samples are analyzed such that the Technical Specification LLD requirements are met. When a nuclide is not detected during the quarter, then <LLD is reported. The most conservative LLDs used for counting effluent samples are included in this report.

5.

Batch Releases

a.

Liquid

1.

Number of releases:

17

2.

Total time:

14,630 minutes

3.

Maximum time:

892 minutes

4.

Average time:

862 minutes

5.

Minimum time:

817 minutes

6.

Average stream flow:

63.9 gpm (discharge) 2.57E+05 gpm (dilution)

b.

Gaseous - None.

6. Abnormal Releases

a.

Liquid

1. In September 2001, a leak developed on the 1A RHR heat exchanger. While the RHR service water system is idle, leakage into the service water side of the heat exchanger can occur since the pressure is higher on the reactor (or suppression pool) side. The activity from this leak was included in the normal monthly liquid effluent releases and is reported under the "continuous" liquid section of this report. The leak was repaired in June 2002. There has continued to be a small amount of radioactivity identified in the service water side of this heat exchanger. Investigation continues to determine it's source.

At this time, the relatively small amount of radioactivity identified continues to be included in the normal monthly effluents and is also included in the "continuous" liquid section of this report.

K.\\CH\\alm\\ODCM\\12QTR02 doc

CY-QC-120-722 Revision 0 Page 12 of 12 ATTACHMENT 3 Annual Effluent Report Supplemental Information Page 5 of 5

b.

Gaseous

1. On May 20, 2002, a fuel leak developed on U-1. The leak was determined to be a pin hole leak and was successfully suppressed on May 27, 2002. The increased noble gas activity, due to the fuel leak, resulted in a slight increase in the calculated effluent releases and was included in the normal monthly effluent releases for May 2002. The leaking fuel was replaced in November 2002 during a refuel outage (Q1R17).

K:\\CHACim\\ODCM\\1 2QTR02.doc

Attachment C Effluent and Waste Disposal Semiannual Report Quad Cities Nuclear Power Station, July - December 2002 SVP-03-052

CY-oC-1 20-722 Revision 0 Page 1 of 11 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 1 of 7 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Period: July - December 2002 A. FISSION & ACTIVATION GASES UNIT THIRD FOURTH EST. TOTAL QUARTER QUARTER ERROR %

1. Total Release Ci 9.24E+01 5.06E+01 12.4

2. Average release rate for the period piCisec 1.1 6E+01 6.36E00

3. *Percent of ODCM limit Chimney & Stack 8.88E-03 4.94E-03 2.34E-03 1.45E-03 B. IODINE l

1. Total Iodine-131.

Ci 1.42E-03 2.29E-03 40.0

2. Average release rate for the period pCi/sec 1.79E-04 l+/-2.88E-04 C. PARTICULATES

1. Particulates with half-lives > 8 days Ci 4.28E-03 1.88E-02 30.1

2. Average release rate for the period gCi/sec 5.39E-04 2.36E-03

3. Gross alpha radioactivity Ci 8.53E-06 1.04E-05 D. TRITIUM

1. Total Release Ci l

6.01 E+01 5.55E+01 8.1

2. Average release rate for the period pCisec 7.56E00 6.98E0O I

J E. IODINE 131 & 133, TRITIUM & PARTICULATE

1. Percent of ODCM limit Chimney & Stack I

1.27E00 l

2.11 E00DO

% NOBLE GAS GAMMA/NOBLE GAS BETA DOSE LIMITS K:\\CH\\Im\\ODCM\\34QTR02.doc

CY-QC-1 20-722 Revision 0 Page 2 of 11 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 2 of 7 MAIN CHIMNEY GASEOUS EFFLUENTS NUCLIDES RELEASED CONTINUOUS MODE BATCH MODE

1. Fission gases Unit Third Quarter Fourth Quarter Third Quarter Fourth Quarter Kr-85 Ci

<LLD*

NA NA Kr-85m Ci 1.1OEOO 6.14E-01 NA NA Kr-87 Ci 2.41 EO0 4.51 EG0 NA NA Kr-88 Ci 1.82E00 1.31 EO0 NA NA Xe-131 m Ci 1.84E-01 6.54E-02 NA NA Xe-1 33 Ci 7.99E00 3.94E00 NA NA Xe-135 Ci 3.70EO0 1.49E00 NA NA Xe-135m Ci 1.51 E+01 7.62E00 NA NA Xe-1 38 Ci 5.99E+01 3.09E+01 NA NA Ar-41 Ci 1.75E-01 1.23E-01 NA NA Total for Period Ci 9.24E+01 5.06E+01 NA NA

2. lodines Unit Third Quarter Fourth Quarter Third Quarter Fourth Quarter 1-131 Ci 1.39E-03 2.15E-03 NA NA 1-133 Ci 2.16E-03 1.39E-03 NA NA 1-135 Ci

<LLD*

NA NA Total for Period Ci 3.55E-03 3.54E-03 NA NA

3. Particulates Unit Third Quarter Fourth Quarter Third Quarter Fourth Quarter Sr-89 Ci 7.27E-04 4.20E-04 NA NA Sr-90 Ci 4.57E-06

<LLD*

NA NA Cs-1 34 Ci

<LLD*

NA NA Cs-1 37 Ci

<LLD*

NA NA Ba-140 Ci 1.08E-03 4.98E-04 NA NA La-1 40 Ci 7.94E-04 5.06E-04 NA NA Cr-51 Ci

<LLD*

NA NA Mn-54 Ci 1.89E-05 1.45E-04 NA NA Co-58 Ci

<LLD*

1.55E-05 NA NA Co-60 Ci 5.13E-04 7.77E-04 NA NA Mo-99 Ci

<LLD*

5.26E-03 NA NA Ag-11 Om Ci 1.65E-05 7.52E-05 NA NA Ce-141 Ci

<LLD*

NA NA Ce-1 44 Ci

<LLD*

NA NA Total for Period Ci 3.15E-03 7.70E-03 NA NA

Actual gaseous LLD's reported on page 6 of 7 of this check list.

K:\\CHJm\\0DCM\\34QTR02.doc

CY-oC-1 20-722 Revision 0 Page 3 of 11 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 3 of 7 REACTOR VENTILATION GASEOUS EFFLUENTS NUCLIDES RELEASED CONTINUOUS MODE BATCH MODE

1. Fission gases Unit Third Quarter Fourth Quarter Third Quarter Fourth Quarter Kr-85 Ci

<LLD*

NA NA Kr-85m Ci

<LLD*

NA NA Kr-87 Ci

<LLD*

NA NA Kr-88 Ci

<LLD*

NA NA Xe-1 33 Ci

<LLD*

NA NA Xe-1 35 Ci

<LLD*

4.26E-02 NA NA Xe-1 35m Ci

<LLD*

NA NA Xe-1 38 Ci

<LLD*

NA NA Ar-41 Ci

<LLD*

NA NA Total for Period Ci

<LLD 4.26E-02 NA NA

2. lodines Unit Third Quarter Fourth Quarter Third Quarter Fourth Quarter 1-131 Ci 3.50E-05 1.42E-04 NA NA 1-133 Ci

<LLD*

NA NA 1-135 Ci

<LLD*

NA NA Total for Period Ci 3.50E-05 1.42E-04 NA NA

3. Particulates Unit Third Quarter Fourth Quarter Third Quarter Fourth Quarter Sr-89 Ci 3.21 E-06 6.34E-06 NA NA Sr-90 Ci

<LLD*

NA NA Cs-1 34 Ci

<LLD*

NA NA Cs-1 37 Ci

<LLD*

NA NA Ba-1 40 Ci

<LLD*

NA NA La-1 40 Ci

<LLD*

NA NA Cr-51 Ci

<LLD*

9.23E-03 NA NA Mn-54 Ci 1.04E-04 1.97E-04 NA NA Co-58 Ci

<LLD*

NA NA Co-60 Ci 1.03E-03 1.60E-03 NA NA Zn-65 Ci

<LLD*

6.89E-05 NA NA Mo-99 Ci

<LLD*

NA NA Ag-11 Om Ci

<LLD*

NA NA Ce-141 Ci

<LLD*

NA NA Ce-1 44 Ci

<LLD*

NA NA Total for Period Ci 1.14E-03 1.11 E-02 NA NA

Actual gaseous LLD's reported on page 6 of 7.

K.\\CH\\Jim\\0DCM\\34QTR02.doc

CY-QC-1 20-722 Revision 0 Page 4 of 11 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 4 of 7 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES A. FISSION & ACTIVATION PRODUCTS UNIT THIRD FOURTH EST TOTAL QUARTER QUARTER ERROR%

1. Total Release (not including tritium, Ci 2.71 E-03 2.72E-02 5.6 gases & alpha)

2. Average diluted concentration during JpCimL 1.90E-10 2.81 E-09 batch discharges for the period.

3. Percent of applicable limit*

2.16E-02 5.42E-02 1.03E-02 2.69E-02

4. Maximum diluted concentration during ACVmL 1.70E-10 6.83E-09 batch discharges l

B. TRITIUM

1. Total Release Ci 1.53E+01 1.24E+01 4.1

2. Average diluted concentration during

[LCMmL 1.08E-06 1.28E-06 batch discharges for the period

3. Percent of applicable limit 8.02E-02 6.40E-02 C. DISSOLVED & ENTRAINED GASES

1. Total Release Ci

<LLD 5.84E-05 5.6

2. Average diluted concentration during giCVmL

<LLD 6.04E-12 batch discharges for the period

3. Percent of applicable limit NA 3.02E-06 D. GROSS ALPHA ACTIVITY

1. Total Release Ci

<LLD**

14.8

2. Average diluted concentration during hbtrh riscrharnge for the neriod ACi/MI NA NA Liters 1.81 E+06 2.56E+06 E. VOLUME OF WASTE RELEASED (prior to dilution)

Liters 1.42E+10 9.67E+09 F. VOLUME OF DILUTION WATER USED DURING BATCH DISCHARGES Liters 4.86E+11 3.14E+11 G. TOTAL VOLUME OF DILUTION WATER USED DURING PERIOD (quarter)

Whole Body/Organ (ODCM)

- Gross Alpha LLD on page 7 of 7 K:\\CHfJim\\ODCM\\34QTR02.doc

CY-QC-1 20-722 Revision 0 Page 5 of 11 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 5 of 7 LIQUID EFFLUENTS NUCLIDES RELEASED CONTINUOUS MODE BATCH MODE Unit Third Quarter Fourth Quarter Third Quarter Fourth Quarter Sr-89 Ci

<LLD*

Sr-90 Ci

<LLD*

Cs-1 34 Ci

<LLD*

Cs-1 37 Ci 3.32E-05 5.OOE-04 1.70E-04 3.70E-04 1-131 Ci

<LLD*

1.98E-05 Co-60 Ci 5.18E-04 6.12E-03 7.01 E-04 3.20E-03 Co-58 Ci

<LLD*

2.29E-04

<LLD*

7.49E-05 Fe-59 Ci

<LLD*

Zn-65 Ci 8.18E-04 4.90E-03 4.28E-05 1.86E-04 Mn-54 Ci 1.98E-04 1.23E-03 3.82E-05 5.99E-04 Cr-51 Ci

<LLD*

1.01 E-04 4.79E-04 Zr-95 Ci

<LLD*

Nb-95 Ci

<LLD*

Mo-99 Ci

<LLD*

Ag-11 Om Ci

<LLD*

8.45E-05 1.82E-04 Ba-1 40 Ci

<LLD*

La-1 40 Ci

<LLD*

Fe-55 Ci

<LLD*

9.26E-03 Sb-1 24 Ci

<LLD*

3.04E-05 Total for Period (above)

Ci 1.57E-03 1.30E-02 1.14E-03 1.44E-02 Xe-1 33 Ci

<LLD*

5.84E-05 Xe-1 35 Ci

<LLD*

Actual liquid LLD's reported on page 7.

Prepared by:

Approved by:

(0 Date:

K \\CFh\\Jm\\0DCM\\34QTR02.doc

CY-QC-1 20-722 Revision 0 Page 6 of 11 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 6 of 7 GASEOUS EFFLUENT LLD's (Most Restrictive)

CONTINUOUS MODE NUCLIDE LOWER LIMITS OF DETECTION (LLD's)

UNIT LLD Value ODCM Required LLD

1. Fission gases Kr-85 uCVcc 4 02E-06 None Kr-85m uCVcc 1 67E-08 None Kr-87 uCVcc 3 35E-08 1 E-04 Kr-88 uCLcc 418E-08 1E-04 Xe-131m uCVcc 6 OOE-07 None Xe-133 uC/oc 2 76E-08 1E-04 Xe-1 33m uC /cc 8 88E-08 1 E-04 Xe-135 uCVcc 1.16E-08 1E-04 Xe-135m uCVcc 1 58E-07 1 E-04 Xe-138 uC/co 1.71 E-07 1 E-04 Ar-41 uC/co 7.19E-08 None NUCLIDE LOWER LIMITS OF DETECTION (LLD's)

UNIT LLD Value ODCM Required LLD*

2. lodines 1-131 uCVcc 2 83E-13 IE-12 1-133 uC/cc 3 56E-12 IE-10 1-135 uC/cG 6 OOE-09 None NUCLIDE LOWER LIMITS OF DETECTION (LLD'S)

UNIT LLD Value ODCM Required LLD'

3. Particulates and Tritium H-3 uCvcc 3 23E-11 1 E-06 Sr-89 uC/cc 2 30E-14 1E-11 Sr-90 uCYcc 877E-15 1E-11 Cs-134 uClcc 1 47E-13 1E-11 Cs-137 uC/cc 2 49E-13 IE-11 Ba-140 uCi/cc 4 25E-13 None La-140 uC/cc 622E-13 None Mn-54 uC/co 1 86E-13 1E-11 Co-58 uC/cc 2 06E-13 1E-11 Fe-59 uCfcc 2 47E-1 3 1 E-11 Co-60 uC/cc 4 83E-13 JE-11 Zn-65 uC0oc 4 31E-13 1E-11 Mo-99 uCvcc 3 12E-12 IE-11 Ce-141 uC~cc 2.92E-13 1E-11 Ce-144 uCfcc I1 IE-12 JE-11 Gross Alpha uCcoc 2 69E-14 IE-11

ODCM RETS LLD's for weekly samples These may be increased by a factor of 10 for daily samples A Volume assumed to be 0 5 cfm for one week (1.43E+08 cc)

K.\\CH\\Jim\\ODCM\\34QTR02.doc

CY-QC-1 20-722 Revision 0 Page 7 of 11 ATTACHMENT 1 Effluent & Waste Disposable Annual Report Page 7 of 7 LIQUID EFFLUENT LLD's (Most Restrictive)

BATCH MODE NUCLIDE LOWER LIMITS OF DETECTION (LLDs)

ODCM Required LLD UNIT LLD Value

3. Liquids H-3 uCicc 3.92E-06 1 E-05 Sr-89 uCu/oc 8.12E-09 5E-08 Sr-90 uCi/cc 2.13E-09 5E-08 Fe-55 uCicc 1.23E-07 1 E-06 Kr-85 uCVcc 1.42E-05 None' Kr-87 uCL1cc 1.50E-07 1 E-05 Kr-88 uCVcc 1 89E-07 1E-05 Xe-1 33 uC~cc 1.50E-07 1 E-05 Xe-133m uC~lcc 3.90E-07 1 E-05 Xe-135 uC~cc 4 66E-08 1E-05 Xe-138 uCoc 6 45E-07 1 E-05 Mn-54 uC~cc 7.86E-08 5E-07 Co-58 uCtoc 6 29E-08 5E-07 CO-60 uCtcc 1.35E-07 5E-07 Zn-65 uCvcc 1.32E-07 5E-07 Mo-99 uCicc 4 55E-07 5E-07 Ag-110m uCvcc 4.32E-08 None Sb-124 uCvcc 4.23E-08 None 1-131 uClcc 5 44E-08 1E-06 Cs-134 uC/cc:

5 46E-08 5E-07 Ba-1 40 uCI/cc 2.18E-07 None La-140 uClcC 2.75E-08 None Cs-137 uCicc 6 14E-08 5E-07 Ce-141 uCicc 1.01E-07 5E-07 Ce-144 uC/cc:

3 78E-07 5E-06 Gross Alpha uCioc 9 03E-08 1 E-07

+

I

Kr-85 required by UFSAR section 9.1.3.3.

K:\\CH\\Jim\\ODCM\\34QTRO2 doc

Attachment D Effluent and Waste Disposal Semiannual Report Supplemental Information Quad Cities Nuclear Power Station, July - December 2002 SVP-03-052

CY-QC-1 20-722 Revision 0 Page 8 of 11 ATTACHMENT 3 Annual Effluent Report Supplemental Information Page 1 of 4 Facility: Quad Cities Nuclear Power Station July - December 2002 Licensee: Exelon Generation Company

1.

Regulatory Limits

a.

For Noble Gases: (per unit)

Dose rate

1.

Less than 500 mrem/year to the whole body

2.

Less than 3000 mrem/year to the skin.

Dose Gamma Radiation

1.

Less than or equal to 5 mrad/quarter.

2.

Less than or equal to 10 mrad/year.

Beta Radiation

1.

Less than or equal to 10 mrad/quarter.

2.

Less than or equal to 20 mrad/year.

b,c.

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

Dose Rate

1.

Less than 1500 mrem/year.

Dose

1.

Less than or equal to 7.5 mrem/quarter.

2.

Less than or equal to 15 mrem/year.

d.

For Liquid: (per site)

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

Less than or equal to 10 mrem to any organ during any calendar quarter.

Less than or equal to 6 mrem to the whole body during any calendar year.

Less than or equal to 20 mrem to any organ during any calendar year.

KACH\\Jim\\ODCM\\34QTR02.doc

CY-QC-120-722 Revision 0 Page 9 of 11 ATTACHMENT 3 Annual Effluent Report Supplemental Information Page 2 of 4

2.

Maximum Permissible Concentration a,b,c. For fission and activation gases, iodines, and particulates with half-lives greater than 8 days, allowable release limits are calculated by solving equations 10.1 and 10.2 from the Offsite Dose Calculation Manual. The alarm setpoint is conservatively set at approximately 10% of the 1 OCFR20 limit.

d.

For liquid effluents allowable release limits are calculated by solving equations 10.3 and 10.4 from the Offsite Dose Calculation Manual. The MPC values used for the monitors were as follows:

Radwaste discharge 7.17E-03 i[CLml Service water 1.OE-05 jiCi/ml

3.

Average Energy The average gamma energy used to calculate the alarm setpoints for the noble gas monitors was 0.524 Mev for the third quarter, and 0.881 Mev for the fourth quarter.

4.

Measurements and Approximations of Total Radioactivity

a.

Fission and Activation Gases:

b.

lodines:

c.

Particulates:

The main chimney and reactor building ventilation exhaust systems are continually monitored for iodines and particulates. These samples are pulled every 7 days and analyzed by gamma isotopic. The particulate papers are composited every 31 days and sent to a vendor for Sr89/90 and gross alpha analysis. Noble gas grab samples are pulled and analyzed by gamma isotopic weekly. Tritium samples are pulled and analyzed every month.

The Sr89/90 and gross alpha curies released values reported are actual. On a real time basis, the portion of the "percent of applicable data. The actual results are obtained by editing the ODCM software inputs when the vendor results become available. Therefore, the "percent of applicable limits" in this report are actual.

K.\\CI-Uim\\ODCM\\34QTR02.doc

CY-QC-1 20-722 Revision 0 Page 10 of 1 1 ATTACHMENT 3 Annual Effluent Report Supplemental Information Page 3 of 4 The continuous strip chart recorders for the monitors on the release points are reviewed monthly for spikes and the activity released is calculated. An additional calculated activity for noble gases is added to the main chimney release each month. This calculation is done because most of the grab samples show less than the lower limit of detection due to the low amount of activity and the large dilution flow at the sample point. The calculation takes into account the normal offgas train and the gland steam contribution to the release.

The average flow at the release points is used to calculate the curies released.

d.

Liquid Effluents The river discharge tanks are analyzed before discharge by gamma isotopic. A composite representative portion of this sample is saved. This is composited with other discharges that occurred every 31 days and is analyzed for tritium and gross alpha. The monthly composites are composited quarterly and sent to a vendor for Sr89/90 and Fe 55. The discharge bay is sampled every 31 days and analyzed by gamma isotopic, for tritium and gross alpha. It is sampled quarterly and sent to a vendor for Sr89/90 and Fe 55 analysis. On a real time basis, the portion of the "percent of applicable limit" for these contributors is based on projections using scaling factors. The actual results are obtained by editing the ODCM software inputs when the vendor results become available. Therefore, the "percent of applicable limits" in this report are actual.

The tank volumes and activities are used to calculate the curies released for the River Discharge Tank. The total water released during the quarter and the activity is used to calculate the diluted activity released at the discharge bay, from batch discharges.

e.

Estimated Total Error Percent The estimated total error percents were calculated by taking the square root of the sum of the squares of errors for sampling and measurement parameters.

K\\CH\\J=m\\ODCM\\34QTR02.doc

CY-QC-120-722 Revision 0 Page 11 of 11 ATTACHMENT 3 Annual Effluent Report Supplemental Information Page 4 of 4

f.

Less than the lower limit of detection (<LLD)

Samples are analyzed such that the Technical Specification LLD requirements are met. When a nuclide is not detected during the quarter, then <LLD is reported. The most conservative LLD's used for counting effluent samples are included in this report.

5.

Batch Releases

a.

Liquid

1.

Number of releases:

21

2.

Total time:

18,822 minutes

3.

Maximum time:

1,037 minutes

4.

Average time:

896 minutes

5.

Minimum time:

837 minutes

6.

Average stream flow:

61.3 gpm (discharge) 3.32E+05 gpm (dilution)

b.

Gaseous NONE.

6.

Abnormal Releases

a.

Liquid

1.

In October 2002, a leak developed on the 2A RHR heat exchanger. While the RHR service water system is idle, the leakage into the service water side of the heat exchanger can occur since the pressure is higher on the reactor (or suppression pool) side. The activity from this leak was included in the normal monthly liquid effluent releases and is reported under the "continuous" liquid section of this report. The leak is scheduled to be repaired in September 2003.

b.

Gaseous NONE.

K:\\CH\\Jim\\ODCM\\S4QTR02.doc

Attachment E Quad Cities Station Meteorological Site Quarterly Joint-Frequency Wind Rose Tables for 2002 SVP-03-052

Quad Cities Nuclear Station 33 ft. Wind Speed and Direction January-March, 2002 196Ft-33Ft Delta-T (F)

Number of Observations = 2148 Values are Percent Occurrence SPED

WND DIRECION CLASSES ---------------------------------

CLASS N

NNE NE ENS E ESE SE SSE S

SSW SW WSW W WNW NW MNW TOTAL 3U EU MU CSu A N L SS M Ms ES EU Mu 1 SU

- N 3SS MS iS EU mu 4 SU

- N 7 SS Ms ES EU MU 8Su

- N 1 SS 2M5 ES EU 1MU 3 SU

- N 1 SS 8Ms ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.05 0.19 0.05 0.14 0.00 0.14 0.98 0.23 0.00 0.00 0.33 0.05 0.09 0.61 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.14 0.28 0.05 0.09 0.14 0.05 0.05 0.84 0.37 0.00 0.00 0.00 0.00 0.00 0.33 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.14 0.05 0.23 0.00 0.00 2.33 0.00 0.00 0.00 0.19 0.09 0.28 1.16 0.05 0.00 0.00 0.09 0.00 0.00 0.33 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.09 0.05 0.09 0.28 0.09 0.37 0.05 0.09 0.51 0.23 0.05 0.00 0.28 0.09 0.05 0.79 0.19 0.00 0.00 0.05 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.28 0.28 0.19 0.14 0.09 0.19 0.37 0.56 0.19 0.05 0.05 0.05 0.09 0.70 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.23 0.88 0.19 0.05 0.00 0.00 0.28 0.37 0.61 0.14 0.05 0.00 0.09 0.19 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.74 0.65 0.14 0.23 0.05 0.14 0.70 1.21 0.33 0.05 0.05 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.19 0.88 0.65 0.61 0.09 0.00 0.05 0.51 1.30 0.14 0.00 0.42 0.00 0.05 0.19 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.56 0.42 0.28 0.61 0.00 0.05 0.84 0.98 0.19 0.00 0.56 0.05 0.05 0.14 0.37 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.09 0.51 0.56 0.28 1.63 0.09 0.14 0.65 2.33 0.37 0.00 0.28 0.05 0.14 0.14 0.42 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.05 0.28 0.47 0.28 0.19 1.02 0.09 0.28 1.77 3.58 0.05 0.00 0.33 0.05 0.09 0.61 0.56 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.19 0.98 0.14 0.05 1.26 0.28 0.28 2.23 2.37 0.00 0.00 0.33 0.05 0.00 0.47 0.51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.19 0.00 0.42 1.40 0.79 0.09 1.16 0.14 0.19 1.82 1.68 0.00 0.00 1.91 0.33 0.23 2.47 0.33 0.00 0.00 0.05 0.05 0.09 0.56 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.65 1.16 0.56 0.14 0.42 0.00 0.05 2.14 0.88 0.00 0.00 1.77 0.19 0.37 4.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.05 0.28 0.51 0.09 0.00 0.37 0.05 0.23 2.09 0.79 0.00 0.00 0.28 0.00 0.09 1.49 0.00 0.00 0.00 0.28 0.05 0.00 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.14 0.19 0.09 0.05 0.28 0.05 0.19 1.44 0.33 0.00 0.00 0.05 0.05 0.19 0.93 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.47 0.47 0.37 0.51 3.07 8.33 6.05 2.47 8.15 8.15 0.93 2.05 19.51 17.23 1.91 0.23 STABILITY CLASSES ---------

MU SU N

SS MS ES E

OIAL 0.00 0.00 0.00 0.00 0.00 0.00 0.37 0.93 0.51 2.05 3.07 8.33 6.05 1.91 2.47 0.23 0.00 21.28 50.00 19.51 -

17.23 6.84 6.84 1.02 1.82 14.25 2.51 0.00 0.00 0.47 0.47 0.09 0.14 1.35 0.00 0.00 0.00 1.02 1.82 14.25 2.51 0.00 0.00 26.44 0.09 0.14 1.35 0.00 0.00 0.00 2.05

)o

Quad Cities Nuclear Station 33 ft. Wind Speed and Direction SPEED

WIND DIRECTION CLASSES January-March, 2002 196Ft-33Ft Delta-T (F)

STABILITY CLASSES ---------

CLASS N

NNE NE ENE B

ESE SE SSE S

SSW SW WSW W WN W NNW TOTAL EU MU SU N SS MS ES TOTAL EU 1MU 9 SU

- N 2 SS 4 MS ES EU GMU T SU N

2 SS 4MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.00 0.00 0.00 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TOT 3.12 2.37 5.03 3.49 3.26 3.21 4.47 5.21 5.26 7.77 9.82 9.22 14.20 12.48 7.03 4.05 100.00 15.92 2.42 4.52 38.41 28.07 7.96 2.70 100.00 Wind Direction by Stability N

NNE NE ENE 3 ESE SE SSE S

SSW SW WSW W NW NWNNW TOTAL 0.47 0.05 0.23 1.86 0.28 0.19 0.05 0.19 0.05 0.05 1.30 0.65 0.05 0.09 0.51 0.09 0.28 3.91 0.05 0.14 0.05 0.74 0.14 0.23 1.44 0.51 0.33 0.09 0.19 0.14 0.33 1.07 0.84 0.47 0.23 0.09 0.00 0.14 0.56 0.61 1.49 0.33 0.28 0.05 0.14 0.88 1.96 0.98 0.19 0.51 0.00 0.14 0.88 2.28 0.79 0.61 1.16 0.05 0.19 1.07 1.91 0.61 0.28 1.96 0.14 0.33 0.88 3.26 0.93 0.28 1.40 0.23 0.42 2.65 4.61 0.33 0.19 1.63 0.33 0.33 2.89 3.86 0.14 0.05 3.21 0.70 0.51 5.49 3.40 0.79 0.09 2.23 0.19 0.42 6.89 2.05 0.56 0.14 1.02 0.14 0.37 4.10 1.30 0.09 0.00 0.33 0.14 0.42 2.51 0.51 0.09 0.05 15.92 2.42 4.52 38.41 28.07 7.96 2.70

-STABILITY CLASSES-Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N

N0E NE EN B e ESE SE SSE S

SSW SW WSW W WNW NW NNW TOTAL 0.00 0.51 1.49 1.07 0.05 0.00 0.00 0.00 0.61 1.44 0.33 0.00 0.00 0.00 0.00 0.28 2.56 1.77 0.42 0.00 0.00 0.00 0.65 1.30 1.40 0.14 0.00 0.00 0.00 0.79 1.58 0.88 0.00 0.00 0.00 0.00 1.40 1.44 0.33 0.05 0.00 0.00 0.00 1.68 2.70 0.09 0.00 0.00 0.00 0.00 2.37 2.09 0.74 0.00 0.00 0.00 0.00 1.44 2.65 1.16 0.00 0.00 0.00 0.00 1.54 5.21 1.02 0.00 0.00 0.00 0.00 1.40 6.80 1.63 0.00 0.00 0.00 0.00 1.44 6.42 1.35 0.00 0.00 0.00 0.00 2.98 4.98 5.26 0.74 0.23 0.00 0.00 2.56 3.49 6.33 0.09 0.00 0.00 0.00 1.07 3.54 1.86 0.56 0.00 0.00 0.00 0.56 2.28 1.21 0.00 0.00 0.00 0.00 21.28 50.00 26.44 2.05 0.23 0.00

-WIND SPEED CLASSES-C A L M

< 3.5 mph 3.6 - 7.5mph 7.6 - 12.5 mph 12.6 - 18.5 mph 18.6 - 24.5 mph

> 24.5 mph

Quad Cities Nuclear Station 296 ft. Wind Speed and Direction January-March, 2002 296Ft-33Ft Delta-T (F)

Number of Observations = 2110 Values are Percent Occurrence SPEED ---------------------------------- ND DIRECTION CLASSES ----------------------------------

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

EU mu Su N SS MS ES TOML CLASS N

NNE NE EN E ESE SR SSE S SSW SW WSW W WNW NW NNW TOTAL EU MU C SU A N L SS MMS ES EU mu 1 SU

- N 3SS MS ES EU MU 4SU

- N 7 SS MS ES EU 8Su

- N ISS 2MS ES EU 3SU

- N ISS 8MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.05 0.24 0.00 0.09 0.00 0.14 0.14 0.09 0.66 0.57 0.19 0.00 0.00 0.05 0.14 0.90 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.33 0.00 0.05 0.00 0.14 0.05 0.05 0.62 0.14 0.05 0.00 0.00 0.00 0.00 0.38 0.24 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.05 0.00 0.05 0.09 0.09 0.85 0.24 0.00 0.00 0.00 0.05 0.05 2.13 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.14 0.09 0.05 0.33 0.05 0.05 0.00 0.00 0.14 0.19 0.57 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.05 0.05 0.00 0.00 0.09 0.00 0.28 0.28 0.05 0.00 0.00 0.05 0.00 0.14 1.14 0.28 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.05 0.09 0.05 0.00 0.00 0.00 0.00 0.05 0.24 0.38 0.00 0.00 0.05 0.05 0.43 0.38 0.24 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.05 0.09 0.14 0.09 0.00 0.00 0.05 0.05 0.38 0.28 0.19 0.00 0.14 0.00 0.00 0.43 0.33 0.62 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.05 0.05 0.05 0.09 0.00 0.00 0.09 0.14 0.33 0.19 0.05 0.05 0.00 0.00 0.47 1.47 0.24 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.05 0.05 0.05 0.14 0.09 0.14 0.00 0.00 0.05 0.00 0.09 0.57 0.33 0.05 0.24 0.09 0.09 0.95 1.09 0.71 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.09 0.14 0.00 0.00 0.05 0.05 0.57 0.05 0.00 0.33 0.43 0.09 0.09 0.47 0.14 0.14 0.57 2.23 0.43 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.28 0.14 0.09 0.00 0.05 0.05 0.28 0.14 0.09 0.38 0.52 0.14 0.09 0.05 0.09 0.28 1.47 2.13 0.24 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.09 0.05 0.00 0.00 0.09 0.14 0.19 0.09 0.14 0.00 0.52 0.28 0.24 0.76 0.43 0.19 0.05 0.28 0.38 0.24 0.66 2.04 0.19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.05 0.00 0.05 0.00 0.00 0.24 0.14 0.33 0.05 0.09 0.05 0.43 0.28 0.09 0.38 0.66 0.19 0.00 0.52 0.43 0.33 1.94 1.23 0.24 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.05 0.14 0.05 0.19 0.09 0.05 0.00 0.09 0.05 0.05 0.66 0.52 0.09 0.00 0.47 0.33 0.19 2.37 1.33 0.14 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.14 0.14 0.62 0.19 0.09 0.05 0.09 0.00 0.00 0.62 1.09 0.19 0.05 0.09 0.05 0.00 1.85 0.85 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.05 0.05 0.09 0.19 0.19 0.09 0.05 0.00 0.00 0.09 0.24 0.62 0.57 0.00 0.00 0.05 0.05 0.00 2.09 0.43 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.24 0.57 0.33 0.19 0.09 0.24 0.24 1.18 1.33 2.75 0.95 1.04 0.28 2.56 2.56 1.37 1.42 7.16 6.68 2.27 0.38 2.42 2.42 1.85 1.85 18.34 14.31 3.03 0.24 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.24 0.57 0.33 0.19 0.09 1.42 1.18 1.33 2.75 0.95 1.04 0.28 7.77 1.37 1.42 7.16 6.68 2.27 0.38 21.85 1.85 1.85 18.34 14.31 3.03 0.24 42.04

Quad Cities Nuclear Station 296 ft. Wind Speed and Direction January-March, 2002 296Ft-33Ft Delta-T (F)

SPEED ----------------------------------

W DIRECTION CLASSES ----------------------------------

STABILITY CASSES ----------

CLASS N

NNE N B RE E

ESE SE SSE S

SSW SW WSW WNW NW NNW TOTAL EU MU SU N

SS MS ES TOTAL EU 1 MU 9 SU

- N 2 SS 4 MS ES EU G MU T SU N

2 SS 4 MS ES 0.00 0.00 0.05 0.47 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.76 0.09 0.00 0.00 0.00 0.00 0.00 0.28 0.00 0.00 0.00 0.19 0.00 0.05 0.33 0.09 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.05 0.00 0.00 0.24 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.09 0.05 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.28 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.00 0.52 0.47 0.00 0.00 0.05 0.05 0.00 0.05 0.19 0.00 0.00 0.57 0.14 0.05 0.47 0.76 0.09 0.00 0.00 0.00 0.05 0.14 0.33 0.05 0.00 0.24 0.19 0.09 0.38 2.46 0.28 0.05 0.00 0.00 0.00 0.05 0.24 0.05 0.00 0.00 0.05 0.05 0.81 1.00 0.00 0.00 0.00 0.00 0.05 0.14 0.05 0.00 0.00 0.05 0.00 0.05 0.33 0.57 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.52 0.19 0.19 1.90 0.43 0.05 0.00 0.05 0.05 0.00 1.04 0.05 0.00 0.00 0.24 0.62 0.24 2.70 0.09 0.00 0.00 0.00 0.05 0.09 0.62 0.00 0.00 0.00 0.09 0.14 0.19 1.23 0.09 0.00 0.00 0.19 0.09 0.09 0.28 0.00 0.00 0.00 0.00 0.00 0.14 0.24 0.05 0.00 0.00 0.05 0.00 0.00 0.05 0.00 0.00 0.00 2.04 2.04 1.42 1.18 10.52 6.21 0.76 0.05 0.33 0.33 0.24 0.28 2.94 0.85 0.09 0.00 1.42 1.18 10.52 6.21 0.76 0.05 22.18 0.24 0.28 2.94 0.85 0.09 0.00 4.74 TOT 4.03 2.09 5.12 2.65 2.84 2.42 3.27 4.83 7.54 10.14 8.82 8.20 12.27 11.71 8.63 5.45 100.00 7.58 6.07 6.30 42.27 29.34 7.39 1.04 100.00 Wind Direction by Stability N

hNE NE ENE E ISE SE SSE S

SSW SW WSW W NW NW TOTAL 0.14 0.24 0.33 2.32 0.71 0.28 0.00 0.14 0.05 0.05 1.37 0.38 0.09 0,00 0.09 0.14 0.28 4.12 0.43 0.05 0.00 0.33 0.24 0.28 1.52 0.19 0.05 0.05 0.19 0.00 0.57 1.71 0.38 0.00 0.00 0.00 0.05 0.14 0.66 0.85 0.71 0.00 0.14 0.05 0.14 0.95 0.81 1.18 0.00 0.14 0.14 0.09 1.23 2.56 0.52 0.14 0.85 0.33 0.24 1.85 2.89 1.33 0.05 1.33 0.47 0.38 1.37 5.36 0.90 0.33 0.38 0.57 0.62 2.89 3.74 0.43 0.19 0.85 0.76 0.71 2.04 3.22 0.57 0.05 1.52 1.18 0.85 5.64 2.42 0.62 0.05 0.85 1.18 0.62 6.68 2.04 0.28 0.05 0.47 0.43 0.43 4.64 2.23 0.33 0.09 0.14 0.24 0.57 3.27 1.14 0.05 0.05 7.58 6.07 6.30 42.27 29.34 7.39 1.04

-STABILITY CLASSES-Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Etremely Stable Wind Direction by Wind Speed N

NE NE ENE I

ESE SE SSE S

SSW SW WSW W WNW NNNWTOTAL 0.00 0.05 0.43 1.80 1.23 0.52 0,00 0.00 0.05 0.38 1.04 0.62 0.00 0.00 0.00 0.14 0.14 1.33 2.32 0.90 0.28 0.00 0.05 0.14 0.71 0.95 0.66 0.14 0.00 0.00 0.24 0.71 1.61 0.28 0.00 0.00 0.05 0.24 0.66 1.14 0.28 0.05 0.00 0.05 0.38 0.95 1.52 0.38 0.00 0.00 0.09 0.24 0.81 2.23 1.14 0.33 0.00 0.09 0.52 1.09 3.18 2.09 0.57 0.00 0.05 0.38 1.56 4.12 3.70 0.33 0.00 0.05 0.66 1.66 4.31 1.90 0.24 0.00 0.19 0.66 2.46 3.79 1.00 0.09 0.00 0.19 0.90 2.04 4.69 3.27 1.18 0.00 0.14 0.57 1.47 4.88 3.89 0.76 0.00 0.09 1.23 2.04 2.84 1.75 0.66 0.00 0.14 0.66 1.52 2.61 0.43 0.09 0.00 1.42 7.77 21.85 42.04 22.18 4.74

-WIND SPEED CLASSES-C A L M

< 3.5mph 3.6 -

7.5 mph 7.6 - 12.5 mph 12.6 - 18.5 mph 18.6 - 24.5 mph

> 24.5 mph

Quad Cities Nuclear Station 33 ft. Wind Speed and Direction April-June, 2002 196Ft-33Ft Delta-T (F)

Number of Observations = 2164 Values are Percent Occurrence SPEED

WID DIRECTION CLASSES ---------------------------------

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

CLASS N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W WNW NWNNWTOTAL EU MU SU N

SS MS ES TOTAL EU KU C SU A N L SS M MS ES EU KU 1 SU

- X 3 SS MS ES EU MU 4 SU

- N 7 SS MS ES KU MU 8 SU

- N I SS 2 KS ES EU 1 MU 3 SU

- N 1 SS 8 KS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.14 0.23 0.00 0.05 0.09 0.09 0.83 0.09 0.05 0.00 0.05 0.05 0.05 0.79 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.28 0.05 0.23 0.23 0.09 0.05 0.05 0.18 0.09 0.05 0.00 0.37 0.05 0.00 0.18 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.18 0.42 0.14 0.32 0.14 0.14 0.83 0.14 0.05 0.00 0.32 0.05 0.14 0.55 0.14 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.60 0.42 0.42 0.51 0.18 0.32 1.06 0.79 0.00 0.00 0.23 0.09 0.00 0.69 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.60 0.69 0.65 0.46 0.09 0.23 0.92 0.69 0.05 0.00 0.14 0.00 0.05 1.48 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.28 0.55 1.20 1.25 0.65 0.09 0.14 0.83 0.97 0.18 0.14 0.05 0.05 0.00 1.16 0.14 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.09 0.46 1.52 0.83 0.69 0.14 0.05 0.32 0.97 0.28 0.00 0.69 0.00 0.00 0.28 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.18 0.55 0.88 0.55 0.92 0.09 0.23 0.79 1.66 0.18 0.00 1.02 0.00 0.05 0.05 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.23 0.55 0.83 0.83 1.02 0.05 0.14 0.65 1.20 0.18 0.00 0.32 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.09 0.14 0.88 0.69 0.18 1.76 0.18 0.05 0.60 1.25 0.09 0.00 1.43 0.14 0.05 0.23 0.55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.05 0.37 0.79 0.51 0.32 2.54 0.28 0.69 1.34 2.77 0.14 0.00 0.28 0.09 0.09 0.28 0.60 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.14 0.79 0.18 0.05 0.60 0.09 0.14 0.42 1.11 0.05 0.00 0.09 0.00 0.05 0.14 0.09 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.05 0.28 0.65 0.55 0.14 0.92 0.14 0.14 1.29 1.39 0.00 0.00 0.51 0.05 0.05 0.37 0.00 0.00 0.00 0.28 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.00 0.00 0.23 0.65 0.51 0.32 0.79 0.14 0.14 1.16 0.65 0.00 0.00 0.46 0.14 0.18 1.89 0.09 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.09 0.18 0.32 0.42 0.23 1.62 0.14 0.69 1.29 1.11 0.23 0.00 0.74 0.05 0.14 0.55 0.05 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.37 0.46 0.00 0.97 0.23 0.46 1.66 0.42 0.05 0.00 0.18 0.05 0.05 0.23 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.51 0.51 0.18 0.51 2.82 8.13 9.75 6.15 13.91 13.91 2.13 3.70 14.19 15.30 1.57 0.14 6.89 6.89 0.83 0.92 8.87 2.36 0.00 0.00 0.37 0.37 0.00 0.05 0.65 0.00 0.00 0.00 0.00 0.00 0.00 2.82 0.00 0.00 0.05 0.05 0.18 0.51 8.13 9.75 2.13 0.83 0.00 3.70 0.92 0.05 14.19 15.30 8.87 2.36 0.65 0.00 1.57 0.00 0.00 6.15 0.14 0.00 0.00 28.05 50.92 19.87 1.06

©

Quad Cities Nuclear Station 33 ft. Wind Speed and Direction April-Juno, 2002 196Ft-33Ft Delta-T (F)

SPEED

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

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

EU MU SU N

SS MS ES TOTAL MS N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W WNW NW 1N TOTAL EU 1 M 9SU

- N 2SS 4MS ES EU GMU T SU N

2 SS 4 MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 TOT 2.59 1.99 3.79 5.55 6.42 7.72 6.61 7.35 6.19 8.36 11.41 4.11 6.98 7.62 8.04 5.27 100.00 21.67 3.14 5.18 26.52 25.79 11.32 6.38 100.00 Wind Direction by Stability N

NNE NEENE B

ESESE SSE S

SSW SW WSW W

WNW NNW TOTAL 0.09 0.14 0.18 1.66 0.23 0.28 0.00 0.46 0.09 0.05 0.65 0.23 0.28 0.23 0.65 0.18 0.28 1.62 0.46 0.46 0.14 0.74 0.28 0.32 1.99 1.39 0.42 0.42 0.60 0.09 0.28 2.54 1.52 0.74 0.65 0.69 0.14 0.14 2.31 1.66 1.39 1.39 1.39 0.18 0.09 0.69 1.62 1.80 0.83 1.99 0.09 0.28 1.02 2.36 1.06 0.55 1.34 0.09 0.28 0.88 1.76 1.02 0.83 3.23 0.32 0.18 0.97 2.68 0.79 0.18 2.96 0.37 0.83 2.13 4.16 0.65 0.32 0.69 0.09 0.23 0.83 1.99 0.23 0.05 1.76 0.28 0.28 1.94 2.03 0.55 0.14 1.52 0.28 0.32 3.28 1.39 0.51 0.32 2.36 0.23 0.92 2.13 1.48 0.65 0.28 1.20 0.28 0.51 1.89 0.83 0.51 0.05 21.67 3.14 5.18 26.52 25.79 11.32 6.38

-STABILITY CLASSES-Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N NENE NE E

ESE SE SSE S SSW SW WSW W WNW NNW TOTAL 0.00 0.46 1.20 0.92 0.00 0.00 0.00 0.00 0.79 0.51 0.69 0.00 0.00 0.00 0.00 0.88 1.62 1.20 0.09 0.00 0.00 0.00 1.52 2.87 1.02 0.14 0.00 0.00 0.00 2.08 2.45 1.89 0.00 0.00 0.00 0.00 3.28 3.00 1.39 0.05 0.00 0.00 0.00 3.00 2.45 1.16 0.00 0.00 0.00 0.00 2.22 3.88 1.25 0.00 0.00 0.00 0.00 2.54 3.23 0.42 0.00 0.00 0.00 0.00 2.03 3.93 2.40 0.00 0.00 0.00 0.00 2.17 7.76 1.34 0.14 0.00 0.00 0.00 1.20 2.40 0.37 0.14 0.00 0.00 0.00 1.80 3.88 0.97 0.32 0.00 0.00 0.00 1.89 2.87 2.77 0.09 0.00 0.00 0.05 1.29 5.08 1.52 0.09 0.00 0.00 0.00 0.88 3.79 0.55 0.00 0.00 0.05 0.05 28.05 50.92 19.87 1.06 0.00 0.05

-WIND SPEED CLASSES-C A L M

< 3.5mph 3.6 -

7.5 mph 7.6 -12.5 mh 12.6 - 18.5 mph 18.6 - 24.5 mph

> 24.5 mph

Quad Cities Nuclear Station 296 ft. Wind Speed and Direction April-June, 2002 296Ft-33Ft Delta-T (F)

Number of Observations -

2175 Values are Percent Occurrence SPED ----------------------------------

W DIRECTION CLASSES

STABIL CLASSES ----------

EU MU SU N

SS MS ES TOTAL CLASS N

M NE ENE E

ESE SE SSE S

SSW SWWSW W WNW NW NNW TOTAL EU MU CSU A N L SS M MS ES EU MU 1SU

- N 3SS KS ES EU MU 4 SU

- N 7SS MS ES EU MU 8SU

- N lSS 2KS ES EU 1MU 3SU

- N 1SS 86S ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.05 0.05 0.00 0.18 0.09 0.18 0.18 0.00 0.05 0.09 0.05 0.55 0.51 0.14 0.05 0.00 0.05 0.00 0.83 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.05 0.18 0.09 0.28 0.00 0.00 0.14 0.00 0.05 0.18 0.23 0.00 0.23 0.05 0.09 0.23 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.14 0.05 0.05 0.14 0.14 0.09 0.23 0.37 0.23 0.00 0.09 0.32 0.28 0.60 0.09 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.18 0,23 0.37 0.18 0.09 0.05 0.14 0.18 0.28 0.64 0.23 0.14 0.00 0.00 0.09 0.09 0.74 0.18 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.05 0.14 0.18 0.46 0.28 0.09 0.05 0.18 0.09 0.09 0.83 0.64 0.28 0.00 0.05 0.05 0.05 1.15 0.14 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.09 0.00 0.00 0.14 0.14 0.00 0.00 0.23 0.14 0.05 0.55 0.46 0.09 0.00 0.05 0.00 0.00 0.55 0.78 0.09 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.18 0.09 0.00 0.18 0.18 0.05 0.00 0.46 0.09 0.05 0.28 0.41 0.18 0.00 0.28 0.09 0.09 0.28 0.46 0.55 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.09 0.09 0.09 0.09 0.09 0.28 0.00 0.05 0.32 0.05 0.09 0.14 0.60 0.46 0.14 0.32 0.00 0.09 0.55 1.20 0.78 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.09 0.05 0.09 0.00 0.09 0.23 0.09 0.14 0.14 0.46 0.18 0.09 0.32 0.23 0.97 0.14 0.64 0.18 0.05 0.92 1.47 1.10 0.37 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.23 0.18 0.09 0.14 0.18 0.09 0.14 1.20 0.23 0.14 0.46 1.38 0.32 0.51 1.01 0.18 0.09 0.78 0.74 0.87 0.32 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.41 0.37 0.18 0.18 0.23 0.05 0.09 0.74 0.41 0.23 0.83 0.69 0.18 0.32 0.23 0.32 0.14 0.97 1.24 0.64 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.05 0.00 0.00 0.00 0.14 0.05 0.05 0.14 0.00 0.00 0.23 0.23 0.00 0.41 0.28 0.14 0.05 0.05 0.00 0.00 0.23 0.28 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.00 0.46 0.09 0.09 0.14 0.09 0.09 0.05 0.09 0.00 0.00 0.46 0.46 0.05 0.00 0.09 0.09 0.05 0.41 0.97 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.05 0.05 0.28 0.14 0.05 0.05 0.69 0.09 0.14 0.87 0.41 0.05 0.00 0.41 0.14 0.09 1.20 0.83 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.14 0.32 0.23 0.14 0.18 0.00 0.00 0.69 0.41 0.51 0.64 0.37 0.23 0.00 0.51 0.32 0.09 1.20 0.74 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.05 0.14 0.23 0.18 0.14 0.09 0.00 0.32 0.23 0.32 0.87 0.32 0.09 0.00 0.05 0.28 0.14 1.24 0.69 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.14 0.09 0.46 0.23 0.37 0.18 2.02 2.02 1.79 1.75 2.99 2.67 1.24 0.64 5.93 5.93 2.71 2.11 8.14 7.54 3.77 1.20 4.00 4.00 2.16 1.33 11.86 9.89 4.78 0.92 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.09 0.46 0.23 0.37 0.18 1.52 1.79 1.75 2.99 2.67 7.54 1.24 3.77 2.71 2.16 0.64 1.20 2.11 13.10 31.40 8.14 1.33 11.86 9.89 4.78 0.92 34.94

Quad Cities Nuclear Station 296 ft. Wind Speed and Direction April-June, 2002 296Ft-33Ft Delta-T (F)

SPEED

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

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

EU MU SU N

SS MS ES TOTAL CLASS N NNE N3E EN1 ESE SE SSE S

SSW SW WSW W NW NW NW TOTAL EU 1MD 9 SU

. N 2SS 4 KS ES EU GMU T SU N

2 SS 4 MS ES 0.00 0.00 0.00 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.37 0.09 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.05 0.00 0.28 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.64 0.05 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 1.15 0.05 0.09 0.00 0.00 0.00 0.00 0.23 0.00 0.00 0.00 0.23 0.05 0.00 0.46 0.14 0.05 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.37 0.00 0.00 0.46 0.83 0.05 0.00 0.18 0.05 0.00 0.18 0.00 0.00 0.00 0.69 0.05 0.14 0.64 1.01 0.00 0.00 0.09 0.09 0.00 0.05 0.00 0.00 0.00 0.74 0.18 0.09 0.55 0.97 0.00 0.00 0.37 0.05 0.09 0.55 0.18 0.00 0.00 0.00 0.00 0.00 0.37 0.37 0.05 0.00 0.05 0.00 0.05 0.09 0.14 0.00 0.00 0.05 0.00 0.05 0.18 0.09 0.00 0.00 0.18 0.18 0.09 1.15 0.00 0.00 0.00 0.23 0.00 0.05 0.32 0.00 0.00 0.00 0.05 0.09 0.05 0.18 0.00 0.00 0.00 2.62 2.62 0.60 0.51 7.08 3.72 0.23 0.00 0.60 0.51 7.08 3.72 0.23 0.00 14.76 0.00 0.00 0.00 0.23 0.09 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.14 0.32 0.05. 0.14 0.00 0.05 0.09 0.14 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.37 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 1.10 1.10 0.37 0.18 2.30 0.32 0.00 0.00 0.37 0.18 2.30 0.32 0.00 0.00 4.28 TOT 3.40 1.93 3.63 4.46 5.70 5.01 5.01 7.77 10.85 13.20 9.75 2.85 4.55 8.05 7.82 6.02 100.00 15.72 7.77 5.98 32.83 24.37 10.39 2.94 100.00 Wind Direction by Stability NNN hNE ENE ESE SE SSE S SSW SW WS W WNW N NNW TOTAL 0.09 0.18 0.23 1.66 0.74 0.41 0.09 0.23 0.18 0.14 0.55 0.32 0.51 0.00 0.28 0.46 0.37 1.43 0.69 0.37 0.05 0.14 0.51 0.60 2.21 0.60 0.37 0.05 0.28 0.28 0.32 3.22 1.10 0.46 0.05 0.37 0.14 0.05 2.67 1.47 0.28 0.05 1.15 0.32 0.14 1.33 1.20 0.83 0.05 1.29 0.18 0.32 1.43 2.94 1.29 0.32 1.98 0.51 0.37 2.21 2.80 2.30 0.69 3.54 0.83 0.51 2.48 3.45 1.43 0.97 1.38 1.15 0.55 2.62 2.62 0.92 0.51 0.32 0.41 0.09 0.92 0.87 0,18 0.05 0.87 0.23 0.23 1.29 1.61 0.28 0.05 1.79 0.60 0.41 3.63 1.43 0.14 0.05 1.56 1.06 0.87 2.71 1.33 0.28 0.00 0.46 0.74 0.78 2.48 1.20 0.37 0.00 15.72 7.77 5.98 32.83 24.37 10.39 2.94

-STABILITY CLASSES-Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N

NNE NEE E

ESE SE SSE S

SSW SW WSW iWNW NW NNW TOTAL 0.00 0.14 0.69 1.43 0.97 0.18 0.00 0.00 0.05 0.60 0.60 0.64 0.05 0.00 0.00 0.00 0.37 1.20 1.47 0.51 0.09 0.00 0.09 1.10 1.61 1.20 0.32 0.14 0.00 0.05 1.24 2.11 1.52 0.69 0.09 0.00 0.09 0.37 1.52 1.52 1.29 0.23 0.00 0.09 0.69 1.47 1.79 0.92 0.05 0.00 0.18 0.69 1.79 2.99 1.70 0.41 0.00 0.18 0.7O 2.39 4.74 2.53 0.23 0.00 0.14 1.06 4.23 4.00 2.53 1.24 0.00 0.09 1.52 3.40 3,63 0.78 0.32 0.00 0.14 0.37 1.33 0.60 0.32 0.09 0.00 0.09 1.01 1.06 1.75 0.37 0.28 0.00 0.00 0.78 2.25 2.71 1.61 0.69 0.00 0.09 1.01 2.85 2.90 0.60 0.37 0.00 0.09 0.83 2.16 2.53 0.37 0.05 0.00 1.52 13.10 31.40 34.94 14.76 4.28

-WIND SPEED CLASSES-C A L M

< 3.5 uph 3.6 -

7.5 mph 7.6 - 12.5 ph 12.6 -18.5 mph 18.6 - 24.5 rph

> 24.5 mph

Quad Cities Nuclear Station 33 ft. Wind Speed and Direction July-September, 2002 196Ft-33Ft Delta-T (F)

Number of Observations 2068 Values are Percent Occurrence SPEED

WMNDIRECTION CLASSES

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

CMASS N

BIB NE ENE E

ESE SE SSE S

SSW SW WSW W WNW NW NW TOTAIL ED MU SU N

SS MS ES TOTAL EU MU CSU A N L SS M MS ES EU MU 1 SU

- N 3 SS MS ES EU MU 4SU

- N 7SS MS ES EU MU 8SU

- N 1 SS 2MS ES Eu 1KU 3 SU

- N 1SS 8MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.29 0.58 0.63 0.63 0.10 0.10 0.63 0.39 0.00 0.00 0.24 0.00 0.00 0.24 0.10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.15 0.44 0.77 0.87 0.58 0.10 0.10 0.73 0.19 0.00 0.00 0.15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.19 0.77 1.11 0.73 0.87 0.10 0.19 1.02 0.48 0.00 0.00 0.05 0.00 0.00 0.15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.10 0.05 0.05 0.19 0.73 0.73 0.63 1.55 0.15 0.44 1.11 2.03 0.10 0.00 0.48 0.05 0.00 0.19 0.10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.19 1.06 1.26 2.03 1.02 0.10 0.10 0.53 0.97 0.00 0.00 0.53 0.00 0.05 0.15 0.15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.34 1.02 0.92 3.19 1.40 0.10 0.15 0.53 1.06 0.15 0.00 0.44 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.00 0.00 0.29 0.63 0.97 0.87 1.40 0.10 0.34 0.87 0.58 0.05 0.00 0.00 0.05 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.19 0.48 0.97 0.24 1.16 0.10 0.24 0.34 0.73 0.00 0.00 0.10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.10 0.24 0.68 0.97 0.19 1.55 0.10 0.24 0.44 1.35 0.05 0.00 0.00 0.00 0.10 0.10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.15 0.15 0.68 0.77 0.29 2.27 0.15 0.19 0.77 1.74 0.15 0.00 0.53 0.00 0.05 0.10 0.19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.10 0.05 0.24 0.53 0.82 0.19 3.68 0.19 0.53 1.11 2.27 0.00 0.00 0.34 0.00 0.10 0.10 0.19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.15 0.15 0.10 0.34 1.06 0.53 0.05 2.32 0.15 0.29 0.77 0.48 0.00 0.00 0.05 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.34 0.00 0.05 0.29 0.87 0.53 0.53 1.35 0.05 0.05 0.58 0.24 0.05 0.00 0.19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.10 0.34 1.06 0.44 0.53 0.63 0.00 0.15 0.34 0.39 0.00 0.00 0.34 0.00 0.00 0.10 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.15 0.05 0.05 0.19 0.92 0.29 0.05 0.92 0.05 0.10 0.48 1.06 0.10 0.00 0.00 0.00 0.05 0.15 0.15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.19 0.48 0.24 0.73 0.05 0.05 0.39 0.82 0.00 0.00 0.10 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.26 1.26 0.44 0.73 3.48 11.41 12.14 11.27 22.05 22.05 1.55 3.24 10.64 14.80 0.63 0.00 3.53 3.53 0.10 0.34 1.40 1.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.44 0.73 3.48 11.41 12.14 11.27 40.72 1.55 3.24 10.64 14.80 0.63 0.00 52.90 0.10 0.34 1.40 1.02 0.00 0.00 6.38 0.00 0.00 0.00 0.00 0.00 0.00 0.00

Quad Cities Nuclear Station 33 ft. Wind Speed and Direction July-September, 2002 196Ft-33Ft Delta-T (F)

SPEND

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

CLASS N

NNE NE ENE B ESE SE SSE S

SSW SW WSW W W NW NW NW

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

TOTAL EU MU SU N

SS MS ES TOTAL EU 1MU 9 SU

- N 2 SS 4 MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 EU GMU T SU N

2SS 4MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TOT 4.01 4.11 5.71 8.66 8.17 9.33 6.43 4.59 6.14 8.22 10.49 6.48 5.13 4.55 4.74 3.24 100.00 26.84 2.08 4.30 15.52 27.22 12.77 11.27 100.00 Wind Direction by Stability N

BE N3 ENE I

ESE SE SSE S

SSW SW WSW W M

NW NNW TOTAL 0.87 0.10 0.10 0.97 0.77 0.58 0.63 0.77 0.10 0.10 0.87 0.63 0.77 0.87 0.97 0.10 0.19 1.35 1.26 1.11 0.73 2.13 0.24 0.48 1.50 2.85 0.82 0.63 1.55 0.10 0.19 0.87 2.18 1.26 2.03 1.89 0.10 0.15 0.87 2.08 1.06 3.19 1.60 0.15 0.34 1.21 1.26 1.02 0.87 1.26 0.10 0.29 0.53 1.21 0.97 0.24 1.55 0.15 0.44 0.77 2.03 1.02 0.19 2.85 0.15 0.39 1.02 2.61 0.92 0.29 4.06 0.29 0.68 1.45 3.00 0.82 0.19 2.51 0.29 0.39 1.16 1.55 0.53 0.05 1.89 0.05 0.10 0.87 1.11 0.58 0.53 1.02 0.Os 0.24 0.77 1.50 0.44 0.53 1.06 0.10 0.19 0.82 2.13 0.39 0.05 0.87 0.05 0.05 0.48 1.06 0.48 0.24 26.84 2.08 4.30 15.52 27.22 12.77 11.27

-STABILITY CLASSES-Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N NNE NEENE ESE SE SSE S SSW SW WSW W NW NW NW OTAL 0.00 1.60 1.84 0.58 0.00 0.00 0.00 0.00 2.27 1.69 0.15 0.00 0.00 0.00 0.00 2.85 2.66 0.19 0.00 0.00 0.00 0.00 2.47 5.37 0.82 0.00 0.00 0.00 0.00 4.59 2.71 0.87 0.00 0.00 0.00 0.00 5.51 3.38 0.44 0.00 0.00 0.00 0.00 2.95 3.34 0.15 0.00 0.00 0.00 0.00 1.93 2.56 0.10 0.00 0.00 0.00 0.00 2.22 3.72 0.19 0.00 0.00 0.00 0.00 2.08 5.27 0.87 0.00 0.00 0.00 0.00 1.98 7.79 0.73 0.00 0.00 0.00 0.00 2.37 4.01 0.10 0.00 0.00 0.00 0.00 2.61 2.32 0.19 0.00 0.00 0.00 0.00 2.56 1.50 0.48 0.00 0.00 0.00 0.00 1.69 2.71 0.34 0.00 0.00 0.00 0.00 1.02 2.03 0.19 0.00 0.00 0.00 0.00 40.72 52.90 6.38 0.00 0.00 0.00

-WIND SPEED CLASSES-CALM

< 3.5 mph 3.6 - 7.5 mph 7.6 - 12.5 mph 12.6 - 18.5 mph 18.6 - 24.5 mph

> 24.5 mph

Quad Cities Nuclear Station 296 ft. Wind Speed and Direction July-September, 2002 296Pt-33ft Delta-T (F)

Number of Observations = 2189 Values are Percent Occurrence SPEED DIRECTION CLASSES ----------------------------------

CLASS N

NE NE ENE E

ESE SE SSE S

SSW SW WSW W WNi W NNW TOTAL EU EU 0.00 Mu 0.00 CSU 0.00 A N 0.00 LSS 0.00 MMS 0.00 ES 0.00 EU 0.00 Mu 0.00 1SU 0.00 N 0.05 3 SS 0.00 MS 0.05 ES 0.00 EU 0.05 mU 0.14 4SU 0.14

- N 0.27 7SS 0.23 MS 0.09 ES 0.18 EU 0.41 Mu 0.18 8SU 0.05

- N 0.64 1 SS 0.09 2MS 0.14 ES 0.05 EU 0.23 1MU 0.00 3SU 0.00

- N 0.14 1 SS 0.46 8MS 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.32 0.09 0.09 0.18 0.09 0.05 0.00 0.32 0.09 0.09 0.41 0.27 0.18 0.09 0.09 0.00 0.00 0.27 0.14 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.18 0.14 0.09 0.32 0.23 0.14 0.09 0.32 0.05 0.14 0.59 0.37 0.23 0.05 0.00 0.00 0.05 0.09 0.14 0.09 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.09 0.09 0.00 0.87 0.32 0.37 0.37 0.09 0.18 0.05 0.32 0.14 0.27 0.41 1.23 0.23 0.23 0.05 0.05 0.05 0.41 0.59 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.14 0.14 0.09 0.05 0.50 0.41 0.05 0.27 0.32 0.41 0.18 0.59 0.05 0.18 0.73 1.37 1.19 0.14 0.37 0.00 0.05 0.55 0.46 0.18 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.82 0.27 0.18 0.27 0.27 0.14 0.00 0.46 0.14 0.05 0.50 0.73 1.01 0.18 0.18 0.05 0.05 0.23 0.69 0.59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.41 0.14 0.05 0.37 0.18 0.05 0.14 0.73 0.18 0.27 0.64 0.64 0.73 0.37 0.05 0.00 0.05 0.32 0.59 0.46 0.73 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.05 0.00 0.09 0.18 0.09 0.14 0.14 0.27 0.18 0.32 0.64 0.18 0.05 0.41 0.50 0.59 0.91 0.27 0.09 0.00 0.32 0.64 0.64 0.78 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.27 0.14 0.18 0.14 0.14 0.14 0.18 0.78 0.27 0.05 0.37 0.32 0.78 0.96 0.73 0.05 0.09 0.46 0.87 0.73 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.09 0.64 0.27 0.05 0.23 0.23 0.23 0.32 1.10 0.23 0.14 0.46 0.46 0.37 0.59 0.91 0.23 0.09 0.78 1.87 0.64 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.05 1.05 0.18 0.09 0.27 0.18 0.27 0.14 0.78 0.32 0,23 0.50 0.27 0.50 0.41 0.23 0.05 0.00 0.64 1.01 0.09 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.14 0.00 0,09 0.00 0.73 0.14 0.05 0.18 0.41 0.23 0.09 0.87 0.09 0.05 0.46 0.64 0.32 0.09 0.41 0.09 0.14 0.32 0.64 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.14 0.00 0.00 0.05 1.28 0.09 0.00 0.23 0.27 0.18 0.05 0.37 0.09 0.09 0.55 0.55 0.09 0.00 0.18 0.09 0.05 0.14 0.05 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.14 0.37 0.05 0.00 0.14 0.05 0.09 0.18 0.14 0.00 0.05 0.50 0.37 0.05 0.18 0.18 0.09 0.00 0.18 0.09 0.09 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.50 0.09 0.23 0.23 0.18 0.32 0.37 0.27 0.09 0.09 0.69 0.78 0.27 0.27 0.00 0.05 0.00 0.23 0.37 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.27 0.14 0.18 0.05 0.27 0.23 0.05 0.41 0.05 0.00 0.37 0.50 0.14 0.09 0.14 0.00 0.00 0.37 0.27 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.14 0.37 0.14 0.82 0.37 0.37 0.50 8.45 8.45 2.70 1.87 3.65 3.43 2.92 2.33 8.50 8.50 2.15 1.78 8.22 9.09 6.81 4.61 4.02 4.02 0.82 0.59 5.44 8.86 4,02 2.19 STABILITY CLASSES ----------

MU SU N SS MS ES TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.37 0.14 0.82 0.37 0.37 0.50 2.70 2.70 1.87 3.65 3.43 2.92 2.33 25.35 2.15 1.78 8.22 9.09 6.81 4.61 41.16 0.82 0.59 5.44 8.86 4.02 2.19 25.95

Quad Cities Nuclear Station 296 ft. Wind Speed and Direction July-SepteDber, 2002 296Ft-33Ft Delta-T (F)

SPEED

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

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

CLASS N

NNE NE ENE E

ESE SE SSE s

SSW SW WSW WNW NW hNW TOTAL EU MU SU N SS MS ES TOTAL Ku 1 mu 9Su

- N 2 SS 4MS ES 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.00 0.00 0.05 0.09 0.14 0.00 0.00 0.00 0.00 0.05 0.27 0.64 0.00 0.00 0.59 0.18 0.14 0.32 0.73 0.00 0.00 0.05 0.00 0.00 0.09 0.18 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.14 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.27 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.96 0.96 0.18 0.23 1.42 1.74 0.14 0.05 0.1B 0.23 1.42 1.74 0.14 0.05 4.71 EU Gmu T SU N

2 SS 4MKs ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.09 0.00 0.00 0.00 0.00 0.05 0.09 0.00 0.00 0.14 TOT 3.61 3.06 3.43 6.67 8.54 7.13 7.31 7.86 8.82 12.20 7.90 6.30 4.71 3.29 5.39 3.79 100.00 22.06 6.21 4.61 19.60 23.57 14.25 9.68 100.00 Wind Direction by Stability N NNE NE EN E

SE SE SSE S SSW SWWSW W WNWN NNW TOTAL 0.69 0.32 0.18 1.14 0.78 0.27 0.23 0.73 0.18 0.18 0.91 0.55 0.37 0.14 0.50 0.18 0.27 1.10 0.73 0.46 0.18 1.23 0.64 0.69 1.23 2.01 0.59 0.27 1.46 0.50 0.32 1.69 2.28 1.87 0.41 1.69 0.50 0.27 1.01 1.69 1.78 0.18 1.19 0.37 0.37 1.42 1.42 1.28 1.28 1.10 0.41 0.23 1.01 1.60 1.42 2.10 1.78 0.46 0.37 1.37 1.96 1.64 1.23 3.24 0.91 0.41 1.83 3.38 1.23 1.19 2.10 0.55 0.32 1.55 1.64 0.91 0.82 2.01 0.32 0.27 1.10 1.69 0.73 0.18 1.83 0.32 0.14 1.05 0.91 0.37 0.09 0.87 0.14 0.09 0.87 0.50 0.23 0.59 0.82 0.23 0.32 1.42 1.32 0.64 0.64 0.82 0.18 0.18 0.91 1.10 0.46 0.14 22.06 6.21 4.61 19.60 23.57 14.25 9.68

-STABILITY CLASSES-Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N

NNE NE ENE E SE SE SS E

SSW SW W NW WNW NW NNW TOTAL 0.00 0.09 1.10 1.55 0.82 0.05 0.00 0.00 0.09 0.82 1.46 0.64 0.05 0.00 0.00 0.05 1.19 1.74 0.41 0.05 0.00 0.00 0.32 2.24 2.83 1.23 0.05 0.00 0.00 0.50 2.15 4.25 1.64 0.00 0.00 0.00 0.09 1.96 3.06 1.78 0.23 0.00 0.00 0.09 1.32 3.56 2.19 0.09 0.05 0.00 0.23 1.32 3.29 2.74 0,27 0.00 0.00 0.14 1.19 3.52 3.02 0.96 0.00 0.00 0.14 1.96 3.33 4.71 1.96 0.09 0.00 0.09 2.19 3.02 2.24 0.37 0.00 0.00 0.27 1.83 2.51 1.69 0.00 0.00 0.00 0.23 2.10 1.74 0.59 0.05 0.00 0.00 0.23 0.87 1.28 0.73 0.18 0.00 0.00 0.05 1.92 2.47 0.69 0.27 0.00 0.00 0.09 1.19 1.55 0.82 0.14 0.00 0.00 2.70 25.35 41.16 25.95 4.71 0.14

-WIND SPEED CLASSES-C A L M

< 3.5mph 3.6 -

7.5 mph 7.6 - 12.5 uph 12.6 - 18.5 mph 18.6 - 24.5 mph

> 24.5 mph

Quad Cities Nuclear Station 33 ft. Wind Speed and Direction October-December, 2002 196Ft-33Ft Delta-T (F)

SPEED

WMD DIRECTION CLASSES ----------------------------------

STABILITY CLASSES ---------

CLASS N N N E3 ENE BE SE SE SSE S SSW SW WSW WNW NW NNW TOTAL EU Mu SU N

SS MS ES TOTAL EU 1Mu 9SU

- N 2 SS 4MS ES EU G mu T SU N

2SS 4 MS ES 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TOT 6.02 4.12 4.45 4.27 5.64 5.97 2.42 3.60 4.22 4.83 8.67 8.39 14.69 10.00 8.10 4.60 100.00 11.18 1.85 4.74 42.09 29.29 6.21 4.64 100.00 Wind Direction by Stability N

M NE ENE E

ESE SE SSE S

SSW SW WSW W W W NNW TOTAL 0.66 0.00 0.19 3.98 0.95 0.14 0.09 0.24 0.24 0.57 1.99 0.71 0.28 0.09 0.28 0.00 0.43 2.70 0.47 0.38 0.19 0.38 0.00 0.19 2.13 0.95 0.38 0.24 0.33 0.09 0.19 3.22 0.66 0.47 0.66 0.14 0.05 0.28 2.09 1.04 0.52 1.85 0.33 0.00 0.05 0.28 0.76 0.57 0.43 0.00 0.05 0.05 0.38 1.85 0.81 0.47 0.47 0.00 0.00 0.38 2.32 0.71 0.33 1.42 0.09 0.00 1.09 1.66 0.47 0.09 2.04 0.28 0.24 1.42 4.36 0.24 0.09 0.43 0.28 0.52 3.08 3.89 0.19 0.00 1.94 0.28 0.57 7.44 4.12 0.33 0.00 0.81 0.14 0.81 5.40 2.42 0.43 0.00 0.81 0.24 0.47 4.36 2.04 0.19 0.00 0.90 0.09 0.19 2.13 1.09 0.09 0.09 11.18 1.85 4.74 42.09 29.29 6.21 4.64

-STABILITY CLASSES-Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N

NE E

ENE E

ESE SE SSE S

SSW SW WSW W W NW NNW TOTAL 0.00 0.90 3.89 1.09 0.14 0.00 0.00 0.00 0.85 2.27 1.00 0.00 0.00 0.00 0.00 1.18 2.75 0.52 0.00 0.00 0.00 0.00 0.76 3.22 0.28 0.00 0.00 0.00 0.00 1.80 2.13 1.47 0.24 0.00 0.00 0.00 2.61 2.23 0.85 0.28 0.00 0.00 0.00 1.61 0.57 0.24 0.00 0.00 0.00 0.00 1.94 1.33 0.33 0.00 0.00 0.00 0.00 1.99 1.80 0.43 0.00 0.00 0.00 0.00 1.04 3.03 0.76 0.00 0.00 0.00 0.00 1.23 5.12 2.32 0.00 0.00 0.00 0.00 1.61 5.40 1.37 0.00 0.00 0.00 0.00 1.75 6.35 6.02 0.57 0.00 0.00 0.00 1.47 5.55 2.56 0.43 0.00 0.00 0.00 1.04 5.21 1.66 0.19 0.00 0.00 0.00 0.66 3.08 0.85 0.00 0.00 0.00 0.00 22.46 53.93 21.75 1.85 0.00 0.00

-WMhD SPEED CLASSES-CALM

< 3.5mph 3.6 - 7.5 mph 7.6 -12.5 mph 12.6 -18.5 mph 18.6 - 24.5 Mph

>24.5 mph

Quad Cities Nuclear Station 33 ft. Wind Speed and Direction October-December, 2002 196Ft-33Ft Delta-T (F)

NulDber of Observations = 2110 Values are Percent Occurrence SPEED WIND DIRECTION CLASSES ------------------------------

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

EU mU SU N

SS MS ES TOTAL CLASS N

NNE NE SEN E

ESE SS SSE S

SSW SW WSW W WNW W NNW TOTAL MUI C SU A N LSS MMS ES KU MU

- N 3SS MS ES EU MU 4 SU

- N 7 SS MS ES MU BSU

- N 1SS 2KS ES EU 1Mu 3SU

- N lSS 8KS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.38 0.24 0.14 0.09 0.47 0.00 0.14 2.61 0.66 0.00 0.00 0.14 0.00 0.05 0.85 0.05 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.38 0.19 0,09 0.24 0.14 0.24 1.23 0.33 0.09 0.00 0.00 0.09 0.33 0.57 0.00 0.00 0.00 0.00 D 0.00 I 0.00

0.00 I 0.00 I 0.00 0.00 I

I I

I 0.00 0.00 1 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.43 0.14 0.19 0.05 0.38 0.38 0.19 0.19 0.24 0.28 0.00 0.00 0.38 0.19 1.85 1.90 0.28 0.81 0.00 0.00 0.00 0.05 0.05 0.09 0.00 0.00 0.05 0.00 0.43 0.09 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.38 0.33 0.43 0.62 0.24 0.00 0.14 1.33 0.33 0.05 0.05 0.05 0.05 0.05 1.33 0.00 0.00 0.00 0.05 0.00 0.00 0.19 0.00 0.00 0.00 0.00 t 0.00 I 0.00 1 0.00 I 0.00 I 0.00 I 0.00 0.00 0.05 0.05 0.19 0.52 0.24 1.56 0.05 0.00 0.05 1.23 0.33 0.28 0.28 0.05 0.00 0.19 0.43 0.19 0.00 0.00 0.05 0.00 0.00 0.24 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.57 0.52 0.43 0.09 0.00 0.05 0,19 0.19 0.05 0.00 0.24 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.71 0.66 0.47 0.00 0.05 0.05 0.24 0.85 0.14 0.00 0.00 0.00 0.00 0.05 0.28 0.00 0.00 0.00 0.00 0.00 I 0.00 I 0.00 0 0.00 I 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.90 0.66 0.33 0.14 0.00 0.00 0.28 1.13 0.05 0.00 0.33 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.38 0.47 0.09 1.09 0.09 0.00 0.85 1.00 0.00 0.00 0.33 0.00 0.00 0.14 0.28 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.81 0.24 0.09 1.42 0.24 0.14 0.90 2.42 0.00 0.00 0.62 0.05 0.09 0.43 1.14 0.00 0.00 0.00 0.00 0.00 0.00

0.00 I 0.00 I 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.38 0.95 0.19 0.00 0.09 0.28 0.24 2.13 2.65 0.00 0.00 0.33 0.00 0.19 0.51 0.28 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.38 1.09 0.24 0.00 0.52 0.19 0.19 2.89 2.46 0.09 0.00 1.37 0.09 0.33 3.65 0.57 0.00 0.00 0.00 0.00 0.05 0.52 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.33 0.76 0.28 0,00 0.33 0.05 0.28 3.13 1.61 0.14 0.00 0.47 0.00 0.38 1.66 0.05 0.00 0.00 0.00 0.00 0.14 0.28 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.38 0.52 0.14 0.00 0.47 0.19 0.28 2.94 1.28 0.05 0.00 0.33 0.05 0.19 0.85 0,24 0.00 0.00 0.00 0.00 0.00 0.19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.19 0.28 0.09 0.09 0.52 0.09 0.19 1.47 0.81 0.00 0.00 0.38 0.00 0.00 0.47 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.09 0.19 0.14 3.84 8.67 5.26 4.27 6.21 6.21 1.33 2.56 25.17 17.35 0.95 0.38 4,79 4.79 0.33 1.85 11.52 3.27 0.00 0.00 0.09 0.09 0.00 0.19 1.56 0.00 0.00 0.00 0.00 0.19 1.33 0.33 0.00 0.00 0.14 2.56 1.85 0.1 0.00 3.84 25.17 11.52 1.56 0.00 8.67 17.35 3.27 0.00 5.26 0.95 0.00 0.00 4.27 0.38 0.00 0.00 22.46 53.93 21.75 0.00 0.00 0.00

Quad Cities Nuclear Station 296 ft. Wind Speed and Direction October-December, 2002 296Ft-33Ft Delta-T (F)

Number of Observations = 2195 Values are Percent Occurrence SPED

WIND DIRECMION CLASSES ----------------------------------

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

CSS N NNE NE ENE E

ESE SE SSE S

SSW SW WSW W RNW NW TOTAL EU mu SU N SS MS ES TOTAL EU 0.00 Mu 0.00 CSu 0.00 A N 0.00 L SS 0.00 MMS 0.00 ES 0.00 EU 0.00 Mu 0.00 1SU 0.00

- N 0.09 3 SS 0.05 MS 0.00 ES 0.00 RU 0.14 Mu 0.05 4SU 0.14

- N 0.36 7SS 0.00 MS 0.00 ES 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.05 0.14 0.23 0.59 0.27 0.09 0.00 0.00 0.05 0.00 1.23 0.73 0.09 0.00 0.00 0.00 0.14 0.73 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.09 0.09 0.46 0.05 0.05 0.00 0.09 0.09 0.09 1.09 0.27 0.14 0.00 0.00 0.05 0.00 1.05 0.18 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.05 0.00 0.00 0.05 0.14 0.14 0.05 0.09 0.05 0.00 0.05 0.09 1.37 0.14 0.05 0.00 0.05 0.00 0.00 1.14 0.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.09 0.09 0.50 0.09 0.27 0.09 0.00 0.00 0.14 1.00 0.23 0.55 0.14 0.00 0.00 0.05 0.68 0.09 0.09 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.05 0.05 0.00 0.00 0.00 0.00 0.68 0.09 0.09 0.14 0.00 0.09 0.00 0.68 0.14 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.05 0.00 0.00 0.00 0.05 0.00 0.18 0.00 0.14 0.09 0.09 0.05 0.00 0.14 0.27 0.64 0.23 0.14 0.00 0.00 0.09 0.36 0.46 0.46 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.09 0.00 0.00 0.00 0.05 0.09 0.36 0.27 0.14 0.00 0.00 0.05 0.23 0.46 0.23 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.05 0.14 0.00 0.00 0.14 0.05 0.00 0.14 0.14 0.00 0.14 1.05 0.14 0.23 0.14 0.09 0.00 0.55 1.23 0.73 0.32 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.27 0.18 0.14 0.09 0.18 0.00 0.05 0.32 0.23 0.18 0.64 1.28 0.36 0.36 0.59 0.23 0.09 0.59 1.55 0.55 0.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.05 0.00 0.05 0.09 0.05 0.09 0.14 0.14 0.00 0.36 0.18 0.23 0.59 0.68 0.32 0.05 0.09 0.23 0.14 0.73 1.69 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.09 0.14 0.14 0.00 0.18 0.00 0.09 0.09 0.09 0.91 0.96 0.09 0.00 0.09 0.23 0.14 1.05 1.59 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.05 0.00 0.09 0.09 0.09 0.18 0.05 0.00 0.00 0.14 0.09 0.18 1.00 1.23 0.09 0.00 0.59 0.50 0.32 2.82 1.32 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.18 0.14 0.05 0.32 0.14 0.14 0.00 0.00 0.05 0.14 1.87 1.05 0.14 0.00 0.09 0.18 0.27 1.78 1.18 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.18 0.36 0.09 0.05 0.05 0.14 0.14 0.23 1.64 0.73 0.18 0.00 0.32 0.09 0.05 2.10 1.32 0.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.14 0.05 0.27 0.05 0.00 0.00 0.14 0.18 0.09 1.09 0.68 0.36 0.00 0.23 0.05 0.00 1.05 0.59 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.64 0.27 0,18 0.05 0.91 0.91 1.41 1.37 3.92 1.32 1.32 0.36 1.55 1.55 1.50 1.73 15.44 10.07 3.64 1.28 2.32 2.32 1.78 1.23 15.99 12.71 2.73 1.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.64 0.27 0.18 0.05 EU MU 8 SU

- N 1 SS 2MS ES EU 1Mu 3SU

- N lSS 8MS ES 0.05 0.18 0.23 1.96 0.32 0.14 0.00 0.00 0.05 0.00 0.73 0.50 0.05 0.00 1.41 1.50 1.78 1.37 3.92 1.73 15.44 1.23 10.07 1.32 1.32 3.64 0.36 1.28 1.23 1.18 10.62 35.22 38.00 15.99 12.71 2.73

Quad Cities Nuclear Station 296 ft. Wind Speed and Direction October-December, 2002 296Ft-33Ft Delta-T (F)

SPEED ----------------------- WID DIRECTION CLASSES ---------------------------------

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

LASS N NE NE N3 E

ESE SE SSE S

SSW SW WSW W WNW NW NNW TOTAL EU MU SU N SS MS ES TOTAL EU 1MU 9 SU

- N 2SS 4 MS ES EU GMU T SU N

2SS 4 MS ES 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.64 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.41 0.23 0.05 0.00 0.00 0.00 0.00 0.23 0.05 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.18 0.05 0.00 0.00 0.00 0.00 0.00 0.27 0.00 0.00 0.00 0.18 0.05 0.00 0.18 0.87 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.18 0.05 0.32 0.96 0.05 0.00 0.00 0.00 0.00 0.00 0.36 0.00 0.00 0.00 0.18 0.00 0.50 0.68 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.14 0.05 0.05 0.32 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 0.05 0.05 2.55 0.32 0.00 0.00 0.00 0.00 0.05 0.77 0.00 0.00 0.00 0.05 0.05 0.00 1.09 0.00 0.00 0.00 0.00 0.00 0.05 0.46 0.00 0.00 0.00 0.00 0.00 0.00 0.59 0.05 0.00 0.00 0.00 0.00 0.00 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.68 0.59 0.32 7.29 3.46 0.09 0.05 0.00 0.00 0.09 1.91 0.50 0.00 0.00 0.68 0.59 0.32 7.29 3.46 0.09 0.05 12.48 0.00 0.00 0.09 1.91 0.50 0.00 0.00 2.51 TOT 5.15 4.74 4.01 3.87 4.87 3.37 3.51 2.78 6.61 10.25 7.47 6.83 12.89 9.48 8.84 5.33 100.00 5.47 5.28 4.78 45.19 28.34 7.97 2.96 100.00 Wind Direction by Stability N NE NE NE E

ESE SE SSE S

SSW SW WSW W WNW NW NNW TOTAL 0.18 0.27 0.36 3.23 0.87 0.18 0.05 0.05 0.18 0.36 2.64 1.23 0.23 0.05 0.09 0.23 0.18 2.78 0.50 0.23 0.00 0.05 0.09 0.23 2.69 0.59 0.18 0.05 0.00 0.09 0.32 2.87 0.41 0.91 0.27 0.00 0.09 0.14 2.23 0.55 0.23 0.14 0.23 0.14 0.05 0.41 0.68 1.23 0.77 0.05 0.00 0.09 0.87 0.91 0.59 0.27 0.50 0.41 0.00 0.87 3.33 0.91 0.59 1.32 0.82 0.46 1.64 4.37 0.96 0.68 0.50 0,68 0.41 2.05 3.28 0.50 0.05 0.32 0.46 0.41 2.51 2.78 0.36 0.00 0.96 0.73 0.68 7.38 2.96 0.18 0.00 0.32 0.41 0.50 5.56 2.37 0.32 0.00 0.46 0.32 0.46 4.87 2.19 0.50 0.05 0.46 0.36 0.14 2.60 1.32 0.46 0.00 5.47 5.28 4.78 45.19 28.34 7.97 2.96

-STABILITY CLASES-S Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N

NNE HE EN E ESE SE SSES SSW SWW W

NW NW TOTAL 0.00 0.14 0.73 2.87 1.32 0.09 0.00 0.00 0.09 1.37 2.10 1.09 0.09 0.00 0.00 0.05 0.73 1.78 1.32 0.14 0.00 0.00 0.14 0.50 1.69 1.46 0.09 0.00 0.00 0.05 1.14 2.05 0.96 0.68 0.00 0.00 0.05 0.27 1.00 0.96 0.82 0.27 0.00 0.09 0.46 1.41 1.50 0.05 0.00 0.00 0.05 0.18 0.91 1.09 0.27 0.27 0.00 0.05 0.36 1.82 3.05 1.32 0.00 0.00 0.05 0.91 3.37 3.87 1.69 0.36 0.00 0.18 0.55 2,41 2.87 1.37 0.09 0.00 0.09 0.55 2.23 3.19 0.77 0.00 0.00 0.14 0.50 2.73 5.60 3.10 0.82 0.00 0.05 0.96 3.23 3.55 1.18 0.50 0.00 0.00 0.82 3.05 4.15 0.64 0.18 0.00 0.00 0.59 2.55 2.00 0.18 0.00 0.00 1.18 10.62 35.22 38.00 12.48 2.51

-WIND SPEED CLASSES-C A L M c 3.5 mph 3.6 - 7.5 mph 7.6 -12.5 mph 12.6 - 18.5 mph 18.6 - 24.5 mph

>24.5 mph

Quad Cities Nuclear Station 33 ft. Wind Speed and Direction January-December, 2002 196Ft-33Ft Delta-T (F)

Number of Observations = 8490 Values are Percent Occurrence SPEED

WD DIRECTION CLASSES ----------------------------------

STABILITY CLASSES ---------

CLASS N

NRN NE ME E ESE SE SSE S

SSW SW WSW W WNW NW NNW OTAL EU MU SU N

SS MS ES TOTAL EU 0.00 MU 0.00 CSU 0.00 A N 0.00 L SS 0.00 MMS 0.00 ES 0.00 EU 0.01 Ku 0.00 1SU 0.01

- N 0.19 3 SS 0.18 MS 0.28 ES 0.19 EU 0.32 Mu 0.05 4SU 0.12

- N 1.26 7SS 0.34 MS 0.01 ES 0.00 EU 0.19 MU 0.02 aSU 0.05

- N 0.62 1 SS 0.04 2KS 0.00 ES 0.00 EU 0.00 1MU 0.00 3 SU 0.00

- N 0.05 1 SS 0.00 8MS 0.00 ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,02 0.00 0.00 0.19 0.28 0.31 0.32 0.26 0.08 0.11 0.74 0.25 0.04 0.00 0.13 0.04 0.08 0.27 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.21 0.28 0.51 0.27 0.41 0.06 0.18 1.51 0.22 0.01 0.00 0.15 0.04 0.12 0.5B 0.05 0.00 0.00 0.02 0.00 0.00 0.11 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.04 0.01 0.04 0.12 0.37 0.45 0.33 0.67 0.09 0.26 1.14 0.95 0.04 0.01 0.27 0.06 0.01 0.45 0.09 0.00 0.00 0,01 0.00 0.00 0.06 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.02 0.18 0.57 0.66 0.86 0.46 0.07 0.16 0.79 0.64 0.07 0.02 0.19 0.02 0.06 0.92 0.09 0.00 0.00 0.01 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.01 0.22 0.58 0.81 1.53 0.53 0.05 0.08 0.72 0.68 0.31 0.14 0.14 0.01 0.07 0.45 0.08 0.00 0.00 0.01 0.00 0.01 0.07 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.01 0.01 0.15 0.60 0.92 0.57 0.60 0.07 0.14 0.52 0.74 0.18 0.01 0.25 0.01 0.00 0.09 0.06 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.02 0.16 0.66 0.79 0.47 0.54 0.06 0.14 0.47 1.14 0.12 0.00 0.39 0.00 0.02 0.07 0.13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.07 0.16 0.67 0.72 0.41 0.82 0.04 0.11 0.55 1.21 0.12 0.00 0.31 0.02 0.05 0.06 0.12 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.04 0.00 0.07 0.12 0.61 0.62 0.21 1.68 0.13 0.09 0.72 1.58 0.15 0.00 0.65 0.05 0.06 0.15 0.37 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.06 0.05 0.04 0.25 0.65 0.46 0.20 2.16 0.20 0.41 1.28 2.77 0.05 0.00 0.39 0.05 0.09 0.35 0.62 0.00 0.00 0.00 0.00 0.00 0.04 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.04 0.07 0.26 0.94 0.26 0.04 1.06 0.20 0.24 1.39 1.66 0.01 0.00 0.20 0.01 0.06 0.31 0.22 0.00 0.00 0.00 0.00 0.00 0.04 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.13 0.07 0.02 0.34 1.00 0.53 0.19 0.99 0.13 0.14 1,65 1.45 0.04 0.00 1.00 0.12 0.15 1.63 0.22 0.00 0.00 0.08 0.01 0.05 0.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.07 0.04 0.02 0.39 0.91 0.45 0.25 0.54 0.05 0.15 1.70 0.88 0.04 0.00 0.77 0.08 0.24 1.93 0.05 0.00 0.00 0.02 0.00 0.04 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.06 0.04 0.05 0.26 0.57 0,24 0.07 0.85 0.11 0.33 1.71 1.06 0.09 0.00 0.34 0.02 0.12 0.77 0.11 0.00 0.00 0.07 0.01 0.00 0.13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.01 0.01 0.09 0.26 0.28 0.09 0.62 0.11 0.22 1.25 0.59 0.01 0.00 0.18 0.02 0.06 0.42 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.58 0.58 0.29 0.47 3.30 9.12 8.28 6.00 12.52 12.52 1.48 2.89 17.40 16.17 1.27 0.19 5.54 5.54 0.58 1.24 9.07 2.30 0.00 0.00 0.24 0.24 0.02 0.09 0.90 0.00 0,00 0.00 0.00 0.29 1.48 0.00 0.47 0.00 3.30 0.00 9.12 0.00 8.28 1.27 0.01 6.00 0.19 0.01 28.03 2.89 17.40 16.17 51.92 0.58 1.24 9.07 2.30 0.00 0.00 18.72 0.02 0.09 0.90 0.00 0.00 0.00 1.25

Quad Cities Nuclear Station 33 ft. Wind Speed and Direction January-December, 2002 196Ft-33Ft Delta-T (F)

SPEED --------------

W----------------

DIRECTION CLASSES ----------------------------------

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

Ws N

NNE3 N ENE E

ESE SE SSE S

SSW SW WSW W WNW VW NNW TOTAL EU MU SU EU 1MU 9 SU

- N 2SS 4 MS ES EU GMU T SU N

2 SS 4MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00.

0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.06 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.06 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 N

0.06 SS MS ES TOTAL 0.00 0.00 0.00 0.00 0.00 0.06 0.00 0.00 0.00 0.00 0.00 0.01 0.01 TOT 3.92 3.13 4.73 5.47 5.85 6.54 4.98 5.21 5.45 7.30 10.11 7.04 10.27 8.69 7.00 4.30 100.00 18.87 2.38 4.69 30.72 27.59 9.55 6.21 100.00 Wind Direction by Stability N

NE NE EN B ESE SE SSE S SSW SW WSW W WNW NW NW TOTAL 0.52 0.07 0.18 2.12 0.55 0.29 0.19 0.41 0.12 0.19 1.20 0.55 0.34 0.32 0.60 0.09 0.29 2.40 0.55 0.52 0.27 0.99 0.16 0.31 1.77 1.41 0.48 0,34 0.66 0.11 0.25 1.93 1.30 0.73 0.88 0.69 0.07 0.18 1.46 1.34 1.12 1.67 0.90 0.09 0.15 0.77 1.40 1.10 0.58 0.94 0.06 0.19 0.71 1.93 0.91 0.47 1.13 0.07 0.22 0.78 2.00 0.84 0.41 2.37 0.18 0.22 0.99 2.56 0.78 0.21 2.60 0.29 0.54 1.92 4.04 0.51 0.20 1.31 0.25 0.37 1.99 2.83 0.27 0.04 2.20 0.33 0.37 3.95 2.67 0.57 0.19 1.40 0.16 0.45 4.11 1.84 0.48 0.25 1.32 0.18 0.49 2.86 1.73 0.33 0.08 0.82 0.14 0.29 1.77 0.87 0.29 0.11 18.87 2.38 4.69 30.72 27.59 9.55 6.21

-STABILITY CLASSES-Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N

NNE NE ER E ESE SE SSE S SSW SW WSW W WNW NW OTAL 0.00 0.86 2.10 0.92 0.05 0.00 0.00 0.00 1.12 1.47 0.54 0.00 0.00 0.00 0.00 1.28 2.39 0.93 0.13 0.00 0.00 0.00 1.34 3.17 0.88 0.07 0.00 0.00 0.00 2.30 2.21 1.28 0.06 0.00 0.00 0.00 3.18 2.51 0.75 0.09 0.00 0.00 0.00 2.31 2.26 0.41 0.00 0.00 0.00 0.00 2.12 2.47 0.61 0.00 0.00 0.00 0.00 2.05 2.85 0.55 0.00 0.00 0.00 0.00 1.67 4.36 1.27 0.00 0.00 0.00 0.00 1.70 6.87 1.51 0.04 0.00 0.00 0.00 1.65 4.56 0.80 0.04 0.00 0.00 0.00 2.29 4.39 3.12 0.41 0.06 0.00 0.00 2.12 3.36 3.06 0.15 0.00 0.00 0.01 1.27 4.15 1.35 0.21 0.00 0.00 0.00 0.78 2.80 0.71 0.00 0.00 0.01 0.01 28.03 51.92 18.72 1.25 0.06 0.01

-WIND SPEED CLASSES-C A L M

< 3.5mph 3.6 -

7.5 mph 7.6-12.5 mph 12.6 - 18.5 mph 18.6 - 24.5 mph

> 24.5 mph

Quad Cities Nuclear Station 296 ft. Kind Speed and Direction January-December, 2002 296Ft-33Ft Delta-T (F)

Nunber of Observations, 8669 Values are Percent Occurrence SPEED NID DIRECTION CLASSES ----------------------------------

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

E MU SU N SS MS ES TOTAL CMASS N

NN3 NE ENE 3

ESE SE SSE S

SSW SW WSW W WNW NW KNWTOTAL EU MU C SU A N L SS MMS ES EU MU 15SU

- N 3 SS MS ES EU MU 4SU

- N 7 SS MS ES EU MU 8 SU

- N lSS 2MS ES EU 1MU 3SU

- N 1 SS 8 MS ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.05 0.01 0.02 0.01 0.06 0.06 0.13 0.24 0.10 0.09 0.06 0.16 0.15 0.10 0.96 0.37 0.15 0.02 0.06 0.03 0.03 0.65 0.29 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.01 0.01 0.02 0.09 0.06 0.09 0.32 0.12 0.12 0.00 0.12 0.08 0.03 0.58 0.33 0.14 0.02 0.08 0.01 0.06 0.40 0.16 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.03 0.00 0.00 0.00 0.05 0.06 0.06 0.24 0.10 0.07 0.03 0.15 0.09 0.10 0.69 0.31 0.15 0.01 0.02 0.10 0.09 0.96 0.13 0.06 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 0.00 0.02 0.03 0.05 0.01 0.22 0.14 0.18 0.25 0.08 0.09 0.03 0.15 0.12 0.17 0.69 0.42 0.12 0.06 0.02 0.07 0.08 0.72 0.28 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.06 0.03 0.02 0.01 0.14 0.16 0.12 0.32 0.18 0.20 0.08 0.22 0.03 0.17 0.72 0.58 0.51 0.07 0.12 0.01 0.07 0.88 0.24 0.09 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.00 0.02 0.02 0.00 0.00 0.23 0.07 0.06 0.16 0.14 0.06 0.00 0.17 0.07 0.02 0.45 0.38 0.39 0.08 0.06 0.05 0.02 0.47 0.50 0.24 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.03 0.02 0.00 0.00 0.15 0.07 0.02 0.21 0.13 0.08 0.06 0.32 0.09 0.09 0.36 0.40 0.44 0.15 0.15 0.02 0.03 0.28 0.44 0.52 0.31 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.02 0.03 0.01 0.05 0.07 0.05 0.06 0.08 0.16 0.08 0.12 0.24 0.06 0.07 0.20 0.45 0.38 0.31 0.16 0.02 0.03 0.39 0.93 0.47 0.24 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.06 0.02 0.02 0.01 0.12 0.08 0.08 0.13 0.12 0.12 0.08 0.35 0.16 0.03 0.23 0.54 0.55 0.35 0.44 0.10 0.06 0.72 1.17 0.82 0.20 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.01 0.03 0.02 0.30 0.18 0.10 0.12 0.15 0.09 0.14 0.80 0.18 0.12 0.47 0.89 0.29 0.39 0.75 0.20 0.10 0.68 1.59 0.62 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.06 0.01 0.01 0.01 0.39 0.23 0.12 0.16 0.14 0.13 0.07 0.54 0.27 0.20 0.58 0.54 0.29 0.22 0.15 0.17 0.14 0.95 1.51 0.24 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.02 0.07 0.03 0.03 0.00 0.18 0.12 0.09 0.14 0.16 0.14 0.02 0.43 0.17 0.09 0.63 0.58 0.18 0.05 0.21 0.17 0.13 0.57 1.13 0.10 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.01 0.03 0.06 0.01 0.02 0.01 0.46 0.13 0.08 0.22 0.12 0.09 0.03 0.25 0.12 0.09 0.60 0.73 0.10 0.00 0.35 0.28 0.18 1.33 0.89 0.13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.01 0.05 0.00 0.00 0.03 0.20 0.09 0.03 0.23 0.10 0.08 0.06 0.23 0.05 0.09 0.98 0.59 0.08 0.05 0.29 0.18 0.14 1.37 0.85 0.08 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.02 0.01 0.01 0.00 0.16 0.16 0.20 0.33 0.16 0.12 0.12 0.30 0.16 0.21 0.90 0.74 0.22 0.08 0.23 0.13 0.03 1.34 0.82 0.09 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.02 0.02 0.01 0.12 0.13 0.16 0.17 0.14 0.09 0.01 0.22 0.14 0.16 0.74 0.52 0.15 0.02 0.12 0.09 0.03 1.18 0.50 0.07 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.05 0.13 0.13 0.62 0.30 0.28 0.21 2.93 2.93 1.78 1.58 3.33 2.10 1.64 0.91 4.65 4,65 1.94 1.76 9.77 8.36 4.14 1.88 3.20 3.20 1.65 1.25 12.86 11.42 3.65 1.15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.13 0.13 0.62 0.30 0.28 0.21 1.71 1.78 1.58 3.33 2.10 1.64 4.14 1.94 1.65 0.91 1.88 1.76 1.25 14.27 32.51 9.77 8.36 12.86 11.42 3.65 1.15 35.17

Quad Cities Nuclear Station 296 ft. Wind Speed and Direction January-December, 2002 296Ft-33Ft Delta-T (F)

SPEBD IND DIRECTION CLASSES ----------------------------------

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

EU MU SU N

SS MS ES TOTAL CLASS N

NhE NE ENE E ESE SR SSE S

SSW SW WSW W WK NW NW TOTAL EU 9 SU

- N 2SS 4MS ES EU GMU T SU N

2 SS 4 MS ES 0.00 0.00 0.01 0.20 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.00 0.00 0.32 0.05 0.00 0.00 0.00 0.00 0.00 0.09 0.00 0.00 0.00 0.05 0.01 0.01 0.16 0.05 0.00 0.00 0.00 0.00 0.00 0.07 0.00 0.00 0.00 0.01 0.00 0.01 0.38 0.01 0.00 0.00 0.00 0.00 0.00 0.02 0.00 0.00 0.00 0.05 0.00 0.05 0.42 0.09 0.06 0.00 0.00 0.00 0.00 0.13 0.01 0.00 0.00 0.06 0.02 0.01 0.13 0.03 0.09 0.01 0.00 0.00 0.00 0.02 0.00 0.00 0.00 0.12 0.02 0.01 0.31 0.37 0.01 0.00 0.06 0.02 0.00 0.13 0.05 0.00 0.00 0.36 0.06 0.06 0.39 0.82 0.02 0.01 0.02 0.02 0.01 0.05 0.08 0.01 0.00 0.43 0.18 0.09 0.39 1.27 0.08 0.01 0.09 0.01 0.02 0.15 0.22 0.01 0.00 0.01 0.06 0.01 0.44 0.55 0.02 0.00 0.00 0.00 0.01 0.09 0.06 0.00 0.00 0.06 0.01 0.03 0.18 0.23 0.00 0.00 0.00 0.00 0.00 0.05 0.00 0.00 0.00 0.17 0.06 0.07 1.15 0.22 0.01 0.00 0.05 0.02 0.01 0.47 0.01 0.00 0.00 0.15 0.21 0.08 1.23 0.02 0.00 0.00 0.08 0.05 0.05 0.30 0.01 0.00 0.00 0.08 0.03 0.06 0.60 0.03 0.00 0.00 0.05 0.02 0.02 0.21 0.00 0.00 0.00 0.01 0.02 0.05 0.18 0.01 0.00 0.00 0.01 0.00 0.01 0.01 0.00 0.00 0.00 1.57 1.57 0.69 0.55 6.54 3.76 0.30 0.03 0.69 0.55 6.54 3.76 0.30 0.03 13.45 0.36 0.15 0.14 1.79 0.44 0.02 0.00 0.36 0.15 0.14 1.79 0.44 0.02 0.00 2.90 TOT 4.05 2.96 4.04 4.43 5.51 4.50 4.79 5.81 8.46 11.45 8.48 6.03 8.58 8.10 7.66 5.14 100.00 12.75 6.33 5.41 34.92 26.38 10.02 4.19 100.00 Wind Direction by Stability NNN NE BNEE ESE SE SSE S

SSW SW WSW W W NWNNW TOTAL 0.28 0.25 0.28 2.09 0.77 0.29 0.09 0.29 0.15 0.18 1.37 0.62 0.30 0.05 0.24 0.25 0.28 2.34 0.59 0.28 0.06 0.44 0.37 0.45 1.91 0.85 0.30 0.10 0.48 0.22 0.38 2.38 1.05 0.82 0.18 0.52 0.20 0.15 1.65 1.14 0.75 0.09 0.68 0.22 0.17 1.03 1.03 1.13 0.53 0.65 0,18 0.18 1.13 2.00 0.96 0.72 1.28 0.43 0.24 1.57 2.75 1.55 0.65 2.36 0.76 0.44 1.83 4.13 1.13 0.80 1.10 0.74 0.47 2.27 2.81 0.69 0.39 0.88 0.48 0.37 1.64 2.13 0.46 0.07 1.29 0.61 0.47 3.83 1.97 0.36 0.05 0.96 0.58 0.40 4.16 1.58 0.24 0.17 0.83 0.51 0.52 3.40 1.76 0.44 0.20 0.47 0.38 0.42 2.31 1.19 0.33 0.05 12.75 6.33 5.41 34.92 26.38 10.02 4.19

-STABILITY CLASSES-Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable Wind Direction by Wind Speed N 1E NE ENE 3

ESE SE SSE S SSW SW WSW W WNW WNNW TOTAL 0.00 0.10 0.74 1.91 1.08 0.21 0.00 0.00 0.07 0.80 1.30 0.75 0.05 0.00 0.00 0.06 0.61 1.51 1.37 0.39 0.09 0.00 0.15 1.00 1.72 1.21 0.28 0.07 0.00 0.15 1.20 2.30 1.43 0.42 0.02 0.00 0.07 0.72 1.57 1.35 0.66 0.14 0.00 0.08 0.72 1.86 1.75 0.36 0.02 0.00 0.14 0.61 1.71 2.26 0.84 0.25 0.00 0.12 0.72 2.21 3.50 1.72 0.20 0.00 0.09 1.08 3.14 4.18 2.46 0.51 0.00 0.10 1.23 2.63 3.25 1.10 0.16 0.00 0.17 0.85 2.13 2.31 0.52 0.05 0.00 0.16 1.13 1.89 3.15 1.68 0.57 0.00 0.10 0.80 2.06 2.95 1.70 0.48 0.00 0.06 1.25 2.61 2.64 0.81 0.30 0.00 0.08 0.82 1.95 1.98 0.28 0.03 0.00 1.71 14.27 32.51 35.17 13.45 2.90

-WIND SPEED CLASSES-C A L M

< 3.5mph 3.6 -

7.5 mph 7.6 -12.5 mph 12.6 -18.5 mph 18.6 - 24.5 mph

> 24.5 mph

DO)

Attachment F Solid Waste Disposition Summary SVP-03-052

NRC REGULATORY GUIDE 1.21 REPORTS Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period from 01/01/2002 to 12/31/2002.

Waste Stream: Resins, Filters, and Evaporator Bottoms Waste Class Volume Curies

% Error (Ci)

Ft3 M3 Shipped A

2.88E+03 8.16E+01 5.17E+02

+/- 12.3%

B 1.20E+02 3.41 E+00 3.78E+01

+/- 12.3%

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

+/- 12.3%

All 3.OOE+03 8.50E+01 5.55E+02

+/- 12.3%

Waste Stream: Dry Active Waste Waste Class Volume Curies

% Error (Ci)

Ft3 M3 Shipped A

7.84E+04 2.22E+02 2.19E+01

+/- 12.3%

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

+/- 12.3%

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

+/- 12.3%

All 7.84E+04 2.22E+03 2.19E+01

+/- 12.3%

Waste Stream: Irradiated Components Waste Class Volume Curies

% Error (Ci)

Ft3 M3 Shipped A

0.00E+00 0.00E+00 0.OOE+00 N/A B

0.OOE+00 0.OQE+00 0.OOE+00 N/A C

0.OOE+00 0.00E+00 0.OOE+00 N/A All 0.OOE+00

.OOE+00 0.OOE+00 N/A Solid Waste Disposition Number of Shipments Mode of Transportation Destination 41 Highway Waste Processor 15 Highway Disposal Site 5

Rail Waste Processor

Attachment G Offsite Dose Calculation Manual Revision 2002 SVP-03-052

Exe kn.M Nuclear Offshte Dose Calculation Manual Docket Numbers:

Dresden Quad Cities Zion LaSalle Byron Braidwood 50-10, 50-237, 50-249 50-254, 50-265 50-295, 50-304 50-373, 50-374 50-454, 50-455 50-456, 50-457

Revision 3 January 2001 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Part 1: GENERIC SECTIONS TABLE OF CONTENTS PAGE Chapter I Introduction I

Chapter 2 Regulations and Guidelines 2

Chapter 3 Pathways 12 Chapter 4 Introduction to Methodology 15 Chapter 5 Measurement 28 Chapter 6 Implementation of Offsite Dose Assessment Program 30 Chapter 7 References 31 Chapter 8 Intentionally Left Blank Chapter 9 Intentionally Left Blank Appendix A Compliance Methodology A-i Appendix B Models and Parameters for Airbome and Liquid Effluent Calculations B-i Appendix C Generic Data C-i Appendix D Intentionally Left Blank Appendix E Intentionally Left Blank Part 2: SITE SPECIFIC SECTIONS Chapter 10 Radiological EffluentTreatmentand Monitoring Chapter 11 Radiological Environmental Monitoring Program Chapter 12 Radiological Effluent Technical Standards Appendix F Station Specific Data ODCM Generic Chap Rev 3 doc ii 0012110928

Revision 3 January 2001 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)

CHAPTER 1 INTRODUCTION PAGE

1.0 INTRODUCTION

1 1.1 STRUCTURE OFTHIS MANUAL 1

CHAPTER 2 REGULATIONS AND GUIDELINES 2

2.0 INTRODUCTION

2 2.1 CODE OF FEDERAL REGULATIONS 2

1.

1 OCFR20, Standards for Protection Against Radiation 2

2.

Design Criteria (Appendix A of 10CFR50) 2

3.

ALARA Provisions (Appendix I of 1 OCFR50) 2

4.

40CFRI90, Environmental Radiation Protection Standards for Nuclear Power Operations 3

5.

40CFR141, National Primary Drinking Water Regulations 3

2.2 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS/STANDARDS 3

1.

Categories 4

2.3 OFFSITE DOSE CALCULATION MANUAL 4

2.4 OVERLAPPING REQUIREMENTS 5

2.5 DOSE RECEIVER METHODOLOGY 5

CHAPTER 3 EXPOSURE PATHWAYS 12

3.0 INTRODUCTION

12 3.1 AIRBORNE RELEASES 12 3.2 LIQUID RELEASES 12 3.3 RADIATION FROM CONTAINED SOURCES 13 ODCM Genenc Chap Rev 3.doc iii 0012110928 1

Revision 3 January 2001 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)

PAGE CHAPTER 4 METHODOLOGY 15

4.0 INTRODUCTION

15 4.1 IMPORTANT CONCEPTS AND PARAMETERS 15

1. Dose 15

2.

Exposure Pathways 15

3.

Categories of Radioactivity 16

4.

Atmospheric Release Point Classifications 16

5.

Historical Average Atmospheric Conditions 17

6.

Relative Concentration Factor X/Q and Gamma-X/Q 18

7.

Relative Deposition Factor DIQ 18

8.

Dose Factors 19 4.2 AIRBORNE RELEASES 19

1. Gamma Air Dose 19

1. Finite Cloud Gamma Air Dose Factor 19

2. Semi-Infinite Cloud Gamma Air Dose Factor 20

2.

Beta Air Dose 20

3. Total Body Dose and Dose Rate 20

4.

Skin Dose and Dose Rate 21

5. Ground Radiation 21

6. Inhalation 22

7.

Ingestion 22 4.3 LIQUID RELEASES 23 4.4 CONTAINED SOURCES OF RADIOACTIVITY 23

1. BWR Skyshine 23

2. Onsite Radwaste Storage Facilities 24 4.5 TOTAL DOSE REQUIREMENTS 24

1. Total Effective Dose Equivalent Limits of 10CFR20 24

2.

Total Dose for Uranium Fuel Cycle 24 CHAPTER 5 MEASUREMENT 28

5.0 INTRODUCTION

28 5.1 EFFLUENT AND PROCESS MONITORING 28 5.2 METEOROLOGICAL MONITORING 28 5.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 28

1. Interlaboratory Comparison Program 28 ODCM Generc Chap Rev 3.doc iv 0011210934 l

Revision 3 January 2001 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)

CHAPTER 6 IMPLEMENTATION OF OFFSITE DOSE ASSESSMENT 6.1 NUCLEAR POWER STATION 6.2 METEOROLOGICAL CONTRACTOR 6.3 REMP CONTRACTOR CHAPTER 7 REFERENCES PAGE l

30 1

30 30 1

30 31 0011210934 ODCM Genenc Chap Rev 3 doc V

Revision 3 January 2001 OFFSITE DOSE CALCULA TION MANUAL LIST OF TABLES FOR THE ODCM GENERIC SECTIONS SECTION TABLE NUMBER TITLE Chapter 2 2-1 Regulatory Dose Limit Matrix 2-2 Dose Assessment Receivers 2-3 Dose Component/Regulation Matrix Chapter 4 4-1 Radionuclide Types Considered For Airborne Effluent Exposure Pathways 4-2 Radiation Dose Factors Appendix A A-0 Average Annual Concentrations Assumed to Produce a Total Body or Organ Dose of 4 mrem/yr A-1 Compliance Matrix A-2 Release Point Classifications A-3 Nearest Downstream Community Water Systems A-4 40CFR1 90 Compliance Appendix B B-0 Noble Gas Nuclide Fraction B-1 Portion of an Example Joint Frequency Distribution Appendix C C-1 Miscellaneous Dose Assessment Factors Environmental Parameters C-2 Miscellaneous Dose Assessment Factors -

Consumption Rate Parameters C-3 Stable Element Transfer Data C-4 Atmospheric Stability Classes C-5 Vertical Dispersion Parameters C-6 Allowable Concentrations of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste C-7 Radiological Decay Constants (1,) in h('

C-8 Bio-accumulation Factors B, to be Used in the Absence of Site-Specific Data C-9 Dose Factors for Noble Gases C-10 External Dose Factors for Standing on Contaminated Ground C-1 1 Sector Code Definitions ODCM Generc Chap Rev 3 doc Ai 001 1210934

Revision 3 January 2001 OFFSITE DOSE CALCULATION MANUAL LIST OF FIGURES FOR THE ODCM GENERIC SECTIONS SECTION FIGURE NUMBER TITLE Chapter 2 2-1 Simplified Flow Chart of Offsite Dose Calculations Chapter 3 3-1 Radiation Exposure Pathways to Humans Appendix B B-1 Instantaneous View of a Plume B-2 A Gaussian Curve B-3 Effect of Observation Period on Plume Shape B4 A Gaussian Plume ODCM Generic Chap Rev 3.doc; vii 0011210934

Revision 3 January 2001 CHAPTER 1 INTRODUCTION

1.0 INTRODUCTION

The Offsite Dose Calculation Manual (ODCM) presents a discussion of the following:

The basic concepts applied in calculating offsite doses from nuclear plant effluents.

The regulations and requirements for the ODCM and related programs.

The methodology and parameters for the offsite dose calculations used by the nuclear power stations to assess impact on the environment and compliance with regulations.

The methodology detailed in this manual is intended for the calculation of radiation doses during routine (i.e., non-accident) conditions. The calculations are normally performed using a computer program.

Manual calculations may be performed in lieu of the computer program.

The dose effects of airborne radioactivity releases predominately depend on meteorological conditions (wind speed, wind direction, and atmospheric stability). For airborne effluents, the dose calculations prescribed in this manual are based on historical average atmospheric conditions. This methodology is appropriate for estimating annual average dose effects and is stipulated in the Bases Section of the Radiological Effluent Technical Standards (RETS) of all Exelon Nuclear nuclear power stations.

1.1 STRUCTURE OF THIS MANUAL This manual is the ODCM for the following Exelon Nuclear power stations: Braidwood, Byron. Dresden, LaSalle, Quad Cities and Zion. It is divided into two parts. The material in the first part is generic (applicable to more than one station) and consists of Chapters 1 through 7 and Appendices A through C.

The material in the second part is station (or site) specific. Therefore, there are six separate sets of station-specific sections each containing three chapters (chapters 10, 11, 12) and an appendix (App. F).

The chapters of the generic section provide a brief introduction to and overview of Exelon Nuclear's offsite dose calculation methodology and parameters. Appendices A and B provide detailed information on specific aspects of the methodology. Appendix C contains tables of values of the generic parameters used in offsite dose equations.

The station-specific section provides specific requirements for the treatment and monitoring of radioactive effluents, for the contents of the Radiological Environmental Monitoring Program (REMP) and the Radiological Effluent Technical Standards (RETS). These three programs are detailed in ODCM Chapters 10, 11 and 12, respectively. Appendix F contains tables of values for the station-specific parameters used in the offsite dose equations. References are provided as required in each station-specific chapter and appendix.

An ODCM Bases and Reference Document (see Reference 101) provides description of the bases for the methodology and parameters discussed in the generic section of the ODCM. This is a stand-alone document and is not considered to be a part of the ODCM.

ODCM Genenc Chap Rev 3.doc 1

0011210934

Revision 3 January 2001 CHAPTER 2 REGULATIONS AND GUIDELINES

2.0 INTRODUCTION

This chapter of the ODCM serves to illustrate the regulations and requirements that define and are applicable to the ODCM. Any information provided in the ODCM concerning specific regulations are not a substitute for the regulations as found in the Code of Federal Regulations (CFR) or Technical Specifications.

2.1 CODE OF FEDERAL REGULATIONS Various sections of the Code of Federal Regulations (CFR) require nuclear power stations to be designed and operated in a manner that limits the radiation exposure to members of the public. These sections specify limits on offsite radiation doses and on effluent radioactivity concentrations and they also require releases of radioactivity to be "As Low As Reasonably Achievable". These requirements are contained in 10CFR20, IOCFR50 and 40CFR190. In addition, 40CFR141 imposes limits on the concentration of radioactivity in drinking water provided by the operators of public water systems.

2.1.1 10CFR20, Standards for Protection Against Radiation This revision of the ODCM addresses the requirements of 10CFR20. The 10CFR20 dose limits are summarized in Table 2-1.

2.1.2 Design Criteria (Appendix A of 1 OCFR50)

Section 50.36 of 1 OCFR50 requires that an application for an operating license include proposed Technical Specifications. Final Technical Specifications for each station are developed through negotiation between the applicant and the NRC. The Technical Specifications are then issued as a part of the operating license, and the licensee is required to operate the facility in accordance with them.

Section 50.34 of 1 OCFR50 states that an application for a license must state the principal design criteria of the facility. Minimum requirements are contained in Appendix A of 1 OCFR50.

2.1.3 ALARA Provisions (Appendix I of 10CFR50)

Sections 50.34a and 50.36a of IOCFR50 require that the nuclear plant design and the station RETS have provisions to keep levels of radioactive materials in effluents to unrestricted areas "As Low As Reasonably Achievable" (ALARA). Although 10CFR50 does not impose specific limits on releases, Appendix I of 1 OCFR50 does provide numerical design objectives and suggested limiting conditions for operation.

According to Section I of Appendix I of 10CFR50, design objectives and limiting conditions for operation, conforming to the guidelines of Appendix I "shall be deemed a conclusive showing of compliance with the "As Low As Reasonably Achievable" requirements of 10CFR50.34a and 50.36a."

An applicant must use calculations to demonstrate conformance with the design objective dose limits of Appendix I. The calculations are to be based on models and data such that the actual radiation exposure of an individual is "unlikely to be substantially underestimated" (see 1 OCFR50 Appendix I, Section 11.A.1).

The guidelines in Appendix I call for an investigation, corrective action and a report to the NRC whenever the calculated dose due to the radioactivity released in a calendar quarter exceeds one-half of an annual design objective. The guidelines also require a surveillance program to monitor releases, monitor the environment and identify changes in land use.

2.1.4 40CFRI90, Environmental Radiation Protection Standards for Nuclear Power Operations ODCM Generc Chap Rev 3.doc 2

0011210934 1

Revision 3 January 2001 Under an agreement between the NRC and the EPA, the NRC stipulated to its licensees in Generic Letter 79-041 that "Compliance with Radiological Effluent Technical Specifications (RETS), NUREG-0472 (Rev.2) for PWR's or NUREG-0473 (Rev.2) for BWR's, implements the LWR provisions to meet 4OCFR190". (See Reference 103 and 49.)

The regulations of 40CFR1 90 limit radiation doses received by members of the public as a result of operations that are part of the uranium fuel cycle. Operations must be conducted in such a manner as to provide reasonable assurance that the annual dose equivalent to any member of the public due to radiation and to planned discharges of radioactive materials does not exceed the following limits:

25 mrem to the total body 75 mrem to the thyroid 25 mrem to any other organ An important difference between the design objectives of 10CFR50 and the limits of 40CFRI90 is that 1 OCFR50 addresses only doses due to radioactive effluents. 40CFR190 limits doses due to effluents and also to radiation sources maintained on site. See Section 2.4 for further discussion of the differences between the requirements of 10CFR50 Appendix I and 40CFR1 90.

2.1.5 40CFR141, National Primary Drinking Water Regulations The following radioactivity limits for community water systems were established in the July, 1976 Edition of 40CFRI41:

I Combined Ra-226 and Ra-228: < 5 pCi/L.

Gross alpha (particle activity including Ra-226 but excluding radon and uranium): < 15 pCiIL.

The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 mremlyr.

The regulations specify procedures for determining the values of annual average radionuclide concentration which produce an annual dose equivalent of 4 mrem. Radiochemical analysis methods are also specified.

The responsibility for monitoring radioactivity in a community water system falls on the supplier of the water.

However, some of the Exelon Nuclear stations have requirements related to 40CFR141 in their specific RETS. For calculation methodology, see Section A.6 of Appendix A.

2.2 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS The Radiological Effluent Technical Standards (RETS) were formerly a subset of the Technical Specifications. They implement provisions of the Code of Federal Regulations aimed at limiting offsite radiation dose. The NRC published Standard Radiological Effluent Technical Specifications for PWRs (Reference 2) and for BWRs (Reference 3) as guidance to assist in the development of technical specifications. These documents have undergone frequent minor revisions to reflect changes in plant design and evolving regulatory concerns. The Radiological Effluent Technical Specifications have been removed from the Technical Specifications and placed in the ODCM as the Radiological Effluent Technical Standards (RETS) (see Reference 90). The RETS of each station are similar but not identical to the guidance of the Standard Radiological Effluent Technical Specifications.

2.2.1 Categories ODCM Generc Chap Rev 3.doc 3

0011210934

Revision 3 January 2001 The major categories found in the RETS are the following:

Definitions A glossary of terms (not limited to the ODCM).

Instrumentation This section states the Operability Requirements (OR) for instrumentation performance as well as the associated Surveillance Requirements. The conservative alarm/trip setpoints ensure regulatory compliance for both liquid and gaseous effluents. Surveillance requirements are listed to ensure ORs are met through testing, calibration, inspection and calculation. Also included are the bases for interpreting the requirements. The Operability Requirement (OR) is the ODCM equivalent of a Limiting Condition for Operation (LCO) as defined in both the NRC published Standard Radiological Effluent Technical Specifications and the stations' Technical Specifications.

Liquid Effluents This section addresses the limits, special reports and liquid waste treatment systems required to substantiate the dose due to liquid radioactivity concentrations to unrestricted areas.

Surveillance Requirements and Bases are included for liquid effluents.

Gaseous Effluents This section addresses the limits, special reports and gaseous radwaste and ventilation exhaust treatment systems necessary for adequate documentation of the instantaneous offsite radiation dose rates and doses to a member of the public. Surveillance Requirements and Bases are included for gaseous effluents.

Radiological Environmental Monitoring Program This section details the Radiological Environmental Monitoring Program (REMP) involving sample collection and measurements to verify that the radiation levels released are minimal.

This section describes the annual land use census and participation in an interlaboratory comparison program. Surveillance Requirements and Bases are included for environmental monitoring.

Reports and Records This section serves as an administrative guide to maintain an appropriate record tracking system.

The management of procedures, record retention, review/audit and reporting are discussed.

2.3 OFFSITE DOSE CALCULATION MANUAL The NRC in Generic Letter 89-01 defines the ODCM as follows (not verbatim) (see Reference 90):

The Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs and (2) descriptions of the Information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

Additional requirements for the content of the ODCM are contained throughout the text of the RETS.

2.4 OVERLAPPING REQUIREMENTS ODCM Genenc Chap Rev 3.doc 4

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Revision 3 Januaxy 2001 In 10CFR20, 10CFR50 and 40CFR190, there are overlapping requirements regarding offsite radiation dose and dose commitment to the total body. In 10CFR20.1301 the total effective dose equivalent (or TEDE) to a member of the public is limited to 100 mrem per calendar year. In addition, Appendix Ito 1 OCFR50 establishes design objectives on annual total body dose or dose commitment of 3 mrem per reactor for liquid effluents and 5 mrem per reactor for gaseous effluents (see 1 OCFR50 Appendix I, Sections I.A and 11.8.2(a)). Finally, 40CFR190 limits annual total body dose or dose commitment to a member of the public to 25 mrem due to all uranium fuel cycle operations.

While these dose limits/design objectives appear to overlap, they are different and each is addressed separately by the RETS. Calculations are made and reports are generated to demonstrate compliance to all regulations. Refer to Tables 2-1, 2-2 and 2-3 for additional information regarding instantaneous effluent limits, design objectives and regulatory compliance.

2.5 DOSE RECEIVER METHODOLOGY Table 2-2 lists the location of the dose recipient and occupancy factors, if applicable. Dose is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. The dose calculation methodology is consistent with the methodology of Regulatory Guide 1.109 (Reference 6) and NUREG 0133 (Reference 14). Dose is therefore calculated to a maximum individual. The maximum individual is characterized as "maximum" with regard to food consumption, occupancy and other usage of the area in the vicinity of the plant site.

Such a "maximum individual" represents reasonable deviation from the average for the population in general. In all physiological and metabolic respects the maximum individual is assumed to have those characteristics that represent averages for their corresponding age group. Thus, the dose calculated is very conservative compared to the "average" (or typical) dose recipient who does not go out of the way to maximize radioactivity uptakes and exposure.

Finally Table 2-3 relates the dose component (or pathway) to specific ODCM equations and the appropriate regulation.

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Revision 3 January 2001 Table 2-1 Regulatory Dose Limit Matrix REGULATION l

DOSE TYPE 1 DOSE LIMIT(s) 1 ODCM EQUATION Airborne Releases:

(quarterly)

(annual) 1 OCFR50 App. 13 Gamma Dose to Air due to Noble Gas 5 mrad 10 mrad A-1 Radionuclides (pr reactor unit)

Beta Dose to Air Due to Noble Gas 10 mrad 20 mrad A-2 Radionuclides (per reactor unit)

Organ Dose Due to Specified Non-Noble 7.5 mrem 15 mrem A-7 Gas Radionuclides (per reactor unit)

Total Body and Skin Total Body 2.5 mrem A-3 Dose (if air dose is exceeded)

Skin 7.5 mrem l mrem A-4 Technical Specifications Total Body Dose Rate Due to Noble Gas 500 mrem/yr A-5 Radionuclides (instantaneous limit, per site)

Skin Dose Rate Due to Noble Gas 3,000 mremlyr A-6 Radionuclides (instantaneous limit, per site)

Organ Dose Rate Due to Specified Non-1,500 mremlyr A-16 Noble Gas Radionuclides (instantaneous limit, per site)

Liquid Releases:

(quarterly)

(annual) 1 OCFR50 App. I Whole (Total) Body Dose 1.5 m m

rem 3 A-17 (per reactor unit)

Organ Dose (per reactor unit) 5 mrem 10 mre A-17 Technical Specifications The concentration of radioactivity in liquid Ten (10) times the effluents released to unrestricted areas concentration values A-21 listed in 10CFR20 Appendix B; Table 2.

Column 2, Table C-6 of ODCM Appendix C for Noble Gases Total Doses :

1 0 CFR 20.1301 (a)(1)

Total Effective Dose Equivalent 4 100 mremlyr A-25 10CFR20.1301 (d)

Total Body Dose 25 mrem/vr A-25 and 40CFR190 Thvroid Dose 75 mrem/vr A-25 OtherLimitsOther Organ Dose 25 mremlvrA-25 Other Lmits 40CFR141 Total Body Dose Due to Drinking Water 4 mrernlyr A-17 From Public Water Systems Organ Dose Due to Drinking Water From 4 mrem/yr A-17 Public Water Systems These doses are calculated considering all sources of radiation and radioactivity in effluents.

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Revision 3 January 2001 2 These limits are not directly applicable to nuclear power stations. They are applicable to the owners or operators of public water systems. However, the RETS of some of the Exelon Nuclear nuclear I

power stations require assessment of compliance with these limits. For additional information, see Section A.6 of Appendix A.

3 Note that I OCFR50 provides design objectives not limits.

4 Compliance with 10CFR20.1301(a)(1) is demonstrated by compliance with 4OCFR190. Note that it may be necessary to address dose from on-site activity by members of the public as well.

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Revision 3 January 2001 TABLE 2-2 DOSE ASSESSMENT RECEIVERS Location; Occupancy If Dose Component or Pathway Different than 100%

'Instantaneous" dose rates from airborne Unrestricted area boundary location that results in radioactivity the maximum dose rate "Instantaneous" concentration limits in liquid Point where liquid effluents enter the unrestricted effluents area Annual average concentration limits for liquid Point where liquid effluents enter the unrestricted effluents area Direct dose from contained sources Receiver spends part of this time in the controlled area and the remainder at his residence or fishing nearby; occupancy factor is considered and is site-specific. See Appendix F, Table F-8 for occupancy factors for N-16 skyshine.

Direct dose from airborne plume Receiver is at the unrestricted area boundary location that results in the maximum dose.

Dose due to radioiodines, tritium and Receiver is at the location in the unrestricted area particulates with half-lives greater than 8 days where the combination of existing pathways and for inhalation, ingestion of vegetation, milk and receptor age groups indicates the highest potential meat, and ground plane exposure pathways.

exposures.

Ingestion dose from drinking water The drinking water pathway is considered as an additive dose component in this assessment only if the public water supply serves the community immediately adjacent to the plant.

Ingestion dose from eating fish The receiver eats fish from the receiving body of water (lake or river)

Total Organ Doses Summation of ingestioniinhalation doses Total Dose Summation of above data (Note it may also be necessary to address dose from on-site activity by members of the public.)

I I

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Revision 3 January 2001 1

TABLE 2-3 DOSE COMPONENTIREGULATION MATRIX Regulation in which dose component is utilized Dose Component or Reference equation; 10CFR50 Pathway Comments IOCFR20 40CFRI90 App. I

'Instantaneous' dose rates from airborne A-5:

Total Body radioactivity (RETS requirement only)

A-6:

Skin A-16:

Organ

'Instantaneous" concentration limits in liquid A-21:

effluents Ten times the limits of Table 2,

)t2)

Col. 2,10CFR20. Appendix B to

§§20.1001 - 20.2402. Table C-6 of Appendix C for Noble Gases Annual average concentration limits for liquid 10CFR20, Appendix B to effluents

§§20.1001 - 20.2402(2)

Direct dose from contained sources A-23 and Section A.3.2 X

X Direct dose from airborne plume A-1:

Gamma air dose X

A-2:

Beta air dose X

A-3:

Total body dose X

X X

A-4:

Skin dose X

Direct dose from radioactivity deposited on the ground A-7 and A-8 X

X X

Inhalation dose from airborne effluents A-7 and A-9 X

X X

Ingestion dose from vegetables A-7, Al0 and A-1i C')

X X

X Ingestion dose from milk A-7, A-12 and A-131)

X X

X Ingestion dose from meat A-7, A-14 and A-15 (1)

X X

X Ingestion dose from drinking water A-17, A-18 and A-19~1 x'

X XX l

Ingestion dose from eating fish A-17, A-18 and A-201 f

X X

X Total Organ Doses A-25 x

X Total Effective Dose Equivalent A-25 X

I I

Ingestionlinhalation dose assessment is evaluated for adult/teen/child and infant for IOCFR50 Appendix I compliance and for 10CFR20140CFR190 compliance. Ingestion/inhalation dose factors are taken from Reg. Guide 1.109 (Reference 6).

2 Technical Specifications for most stations have been revised to allow 10 times the I OCFR20 value or specifically states the maximum instantaneous dose rate limit.

3 Optional for 10CFR20 compliance.

4 Compliance with the Total Effective Dose Equivalent limits of 10CFR20 is demonstrated by compliance with 40CFR190. It may also be necessary to address dose from on-site activity by members of the public.

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Revision 3 January 2001 Fiqure 2-1 Simplified Chart of Offsite Dose Calculations2 IlI Catecorv Radionuclides Pathwav Text Receptor Code and Limits Frequency of Section Calculation' Airborne Releases:

Noble Gases Plume A-1.3.1 Total Body RETS:

As Required by 500 mrem/yr Instantaneous Noble Gases, Plume -? and pb A.1.3.2 Skin RETS:

Station 3000 mrem/yr Procedure Instantaneous Noble Gases:

Plume A.1.2.1 Air4 10CFR50:

5 mradlqtr, 10 mrad/yr Noble Gases:

Plume pb A.1.2.2 Air4 10CFR5O3:

Monthly 10 mrad/qtr, 20 mrad/yr Non-Noble lnhalationb AI.5 Child RETS:

As required by Gases:

(Any Organ) 1500 mremlyr Station Instantaneous Procedure Ground A1.A.1 Total body Deposibionc Non-Noble Inhalaton' A.1.A.2 Gases:

d 10CFR5o3:

Vegetaon A.1 A.3.1 Four Age groups Monthly and Milko A

(All Organs) 7.5 m 15 mremvy Annually Meate A.1.4 3.3 Uquid Releases:

An Water A-2.2 RETS, 10 times I0CFR20 As Required by Appendix B; Table 2; Col. 2.

Station Table C-6 of Appendix C for Procedure Noble Gases Non-Noble Water" and A-2.1 Total Body 10CFR50:

Gases Fish t

1.5 mrem/qtr 3 mrernyr Non-Noble Water' and A.2.1 4 Age Groups 10CFR503:

Monthly Gases Fish' (All Organs) 5 mremlqtr 10 mremlyr Non-Noble Water" A.6 Adult (Total 40CFR141:

When Required Gases Body and all 4 mrem/yr by RETS

~O rgans)

Total Body 40CFRI90:

Uranium 25 mremlyr Fuel AR All releases plus A-42 Thyroid (Adult) 40CFR190.

Annually direct radiation 75 mrem/yr Cycle:

from contained sources All Other Organs 40CFR190:

(Adult) 25 mrem/yr TEDE:

An Extemnal + Internal A.5 Total Body+

10CFR20:

Annually I__

organs (Adult) 100 mrem/yr_

ODCM Generic Chap Rev 3.doc 10 0011210934 1

Revision 3 January 2001 Figure 2-1 (Cont'd)

Notes for Figure 2-1:

1.

Definiton: Monthly means at least once per 31 days or once per month. See station RETS for exact requirements.

2.

Additional Calculations-In addition to the calculations shown in this figure. monthly projections of doses due to radioactive materials are required for gaseous and liquid effluents from Exelon Nuclear nuclear power stations. See Sections A-1.6 and A.2.5 of Appendix A.

Also, projections of drinking water doses are required at least once per 92 days for Dresden and Quad Cities. See Section A.7 of Appendix A.

3 10 CFR 50 prescribes design objectives not limits

4.

If the air dose is exceeded, doses to the total body and skin are calculated. Total body objectives are 2.5 mrerrlqtr and 5.0 mremlyear; the skin dose objectives are 7.5 mremlqtr and 15 mremlyear.

a Evaluated at the unrestricted area boundary.

b Evaluated at the location of maximum offsite X/O.

c Ground plane and inhalation pathways are considered to be present at all offsite locations.

d Evaluated at the fccalion in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures If no real pathway exists then a hypothetical cow-milk producer is evaluated at 5 miles in the highest D/O sector.

e Evaluated for the nearest downstream community water supply as specified in Table A-3 of Appendix A. The flow and dilution factors specified In Table F-1 of Appendix F are used.

f Evaluated for fish caught in the near-field region downstream of plant using the flow and dilution factors specified in Table F-1 of Appendix F.

ODCM Generic Chap Rev 3 doc0 11 001 1210934 l

Revision 3 Januaiy 2001 CHAPTER 3 EXPOSURE PATHWAYS

3.0 INTRODUCTION

Figure 3-1 illustrates some of the potential radiation exposure pathways to humans due to routine operation of a nuclear power station. These exposure pathways may be grouped into three categories:

Airborne Releases Exposures resulting from radioactive materials released with gaseous effluents to the atmosphere.

Liquid Releases Exposures resulting from radioactive materials released with liquid discharges to bodies of water.

Radiation from Contained Sources Exposures to radiation from contained radioactive sources.

When performing radiation dose calculations, only exposure pathways that significantly contribute (2 10%)

to the total dose of interest need to be evaluated. The radiation dose from air and water exposure pathways are routinely evaluated. (see Regulatory Guide 1.109, Reference 6.)

3.1 AIRBORNE RELEASES For airborne releases of radioactivity, the NRC considers the following pathways of radiation exposure of persons:

External radiation from radioactivity airborne in.the effluent plume.

External radiation from radioactivity deposited by the plume on the ground.

Ingestion of radioactivity on, or in, edible vegetation (from direct plume deposition).

Ingestion of radioactivity that entered an animal food product (milk or meat) because the animal ingested contaminated feed, with the contamination due to direct deposition on foliage.

Inhalation of radioactivity in the plume.

Dose for airborne releases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures.

3.2 LIQUID RELEASES For liquid releases of radioactivity (Figure 3-1), the NRC considers the following pathways of radiation exposure of persons:

Ingestion of aquatic food (e.g., fish or inverterbrate) obtained from the body of water to which radioactive station effluents are discharged.

Ingestion (drinking) of potable water contaminated by radioactive liquid effluents discharged from the station.

For the aquatic food pathway, only fish is considered since it is the only significant locally produced aquatic food consumed by humans.

The stations omit the pathways involving irrigation and animal consumption of contaminated water because these pathways were determined to be insignificant. The stations also omit the pathway of ODCM Genenc Chap Rev 3.doc 12 0011210934 1

Revision 3 January 2001 radiation exposure from shoreline sediment because this pathway was also found to be insignificant (see ODCM Bases and Reference Document, Section 0.3.2).

The stations have also verified that the dose contribution to people participating in water recreational activities (swimming and boating) is negligible. (See ODCM Bases and Reference Document, Reference 101, Tables 0-3 and 0-4) This pathway was not addressed explicitly in Regulatory Guide 1.109. Thus, the stations also omit dose assessments for the water recreational activities pathway.

Periodically the Illinois Army Corps of Engineers dredges silt and debris from the river beds near Exelon Nuclear nuclear stations. As a part of the land use census, Exelon Nuclear will determine if the Corps performed dredging within one mile of the discharge point. If so, Exelon Nuclear will obtain spoils samples, through it's REMP vendor, for analysis. The impact to the offsite dose will be evaluated on a case by case basis and added to the station annex of the ODCM when applicable.

In addition, to assure that doses due to radioactivity in liquid effluents will be ALARA, concentrations will be limited to ten times (1Ox) the values given in 1 OCFR20 Appendix B, Table 2; Column 2. Specific limitations for concentrations of entrained noble gases are contained in the stations' Radiological Effluent Technical Standards (RETS).

3.3 RADIATION FROM CONTAINED SOURCES Radioactivity contained within tanks, pipes or other systems and contained radioactive material or waste stored on site can produce radiation at offsite locations. Annual offsite radiation doses near the stations due to such sources were judged to be negligible in comparison with applicable limits except for doses due to BWR turbine skyshine and potential doses due to radioactive waste storage facilities (excludes radioactive material storage). See ODCM Bases and Reference Document, Reference 101. Changes or modifications lo-the power station that may impact the offsite dose through increases to the direct radiation levels need to be evaluated on a case by case basis and added to Chapter 12 of the station annex to the ODCM when applicable (e.g.; the Old Steam Generator Storage Facilities).

ODCM Generic Chap Rev 3.doc 13 0011210934 l

Revision 3 January 2001 1

Figure 3-1 Radiation Exposure Pathways to Humans ODCM Generic Chap Rev 3.doc 14 0011210934 l

Revision 3 January 2001 CHAPTER 4 METHODOLOGY

4.0 INTRODUCTION

This chapter provides an introduction to the methodology used by Exelon Nuclear to calculate offsite radiation doses resulting from the operation of nuclear power stations. Additional explanation and details of the methodology are provided in Appendices A and B. Appendix A discusses each dose limit in the RETS and provides the associated assessment equations. Appendix B describes methods used to determine values of parameters included in the equations.

4.1 IMPORTANT CONCEPTS AND PARAMETERS 4.1.1 Dose The dose calculation equations contained in the ODCM are based on two types of exposure to radiation; external and internal exposure. The first type of exposure is that resulting from radioactive sources external to the body (including radiation emanating from an effluent plume, radiation emanating from radioactivity deposited on the ground and radiation emanating from contained sources (also referred to as direct radiation)). Exposure to radiation external to the body only occurs while the source of the radioactivity is present.

Internal exposure occurs when the source of radioactivity is inside the body. Radiation can enter the body by breathing air containing the radioactivity, or by consumption of food or drinking water containing radioactivity. Once radioactivity enters the body and becomes internal radiation, a person will continue to

-receive radiation dose until the radioactivity has decayed or is eliminated by biological processes. The dose from this type of exposure is also termed dose commitment, meaning that the person will continue to receive dose even-though the plume containing the radioactivity has passed by the individual, or even-though the individual is no longer drinking water containing radioactivity.

The regulations addressed by the ODCM may require assessment of either type of exposure to radiation or of both types in summation.

The term dose is used instead of the term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). When applied to the evaluation of internal deposition of radioactivity, the term "dose," as used in the ODCM, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is evaluated over a period of 50 years.

4.1.2 Exposure Pathways All of the exposure pathways are discussed in Chapter 3. This section presents the exposure pathways addressed by Exelon Nuclear nuclear stations in the ODCM and associated software.

For releases of radioactivity in airborne effluents the primary pathways are the following:

Direct radiation from an effluent plume.

Direct radiation from radioactivity deposited on the ground by a plume.

Inhalation of radioactivity in a plume.

Ingestion of radioactivity that entered the food chain from a plume that deposited radioactivity on vegetation.

For releases of radioactivity in liquid effluents, the exposure pathways considered are human consumption of water and fish.

ODCM Generc Chap Rev 3.doc 15 0011210934

Revision 3 January 2001 When determining total doses, as required by 1 OCFR20 and 40CFR1 90, the BWR stations also consider direct radiation due to skyshine from nitrogen-16 (16N) in turbines and associated piping. All nuclear power stations will consider exposure to radiation emanating from onsite radwaste storage facilities when they are put into operation.

4.1.3 Categories of Radioactivity Radionuclide content of effluent releases from nuclear power stations can be categorized according to the characteristics of the radionuclides. In evaluating doses associated with a particular pathway, only those categories of radionuclides that significantly contribute to the dose need to be included in the dose calculations (See Section 3.0). The categories of radionuclides considered by the Exelon Nuclear nuclear power stations for each of the airborne pathways are summarized in Table 4-1. Selection of the significant airborne pathways was based on the following:

The requirements in the RETS (see discussion in Appendix A)

Applicable regulatory guidance (References 6 and 14), and

-A study of the potential radiological implications of nuclear facilities in the upper Mississippi River basin (Reference 20).

Calculations were used to determine which radionuclides were significant for a particular pathway. For example, in the case of direct radiation from a plume of airborne radioactivity, it was found that radiation from noble gases is significant and radiation from radioactive iodine was not. The dose rate per unit of airborne radioactivity concentration is about the same for noble gases and radioactive iodine since they emit comparable types and energies of radiation. However, the quantity of noble gas radioactivity released in routine nuclear plant operation typically exceeds the quantity of radioactive iodine by a factor of about 10,000.

As another example, consider the inhalation pathway. Here, the calculations showed that the dose commitment due to radioactive iodine was significant but the dose commitment due to radioactive noble gases was not significant and can be excluded from the compliance calculations for the inhalation pathway. This is true despite the fact that a much larger quantity of noble gas radioactivity is released.

The reason for this is that the solubility of noble gas in body tissue is very low, whereas the inhaled radioactive iodine does concentrate in specific body organs such as the thyroid (see the discussion on Pages 228 and 231 to 234 of Reference 38).

4.1.4 Atmospheric Release Point Classifications The dose impact from airborne release of radioactivity is determined by the height of the release of the effluent plume relative to the ground and by the location of the dose recipient.

The height an effluent plume maintains as it travels above the ground is related to the elevation of the release point and to the height of structures immediately adjacent as follows:

If the elevation of the release point is sufficiently above the height of any adjacent structures, the plume will remain elevated for considerable distances.

If the elevation of the release point is at or below the heights of adjacent structures, the plume is likely to be caught in the turbulence of the wakes created by wind passing over the buildings. The plume elevation would then drop to ground level.

If the elevation of the release point is not significantly above the heights of adjacent structures, then the plume may be elevated or at ground level.

For the calculations of this manual, each established release point has been designated as belonging to one of three release point classifications:

ODCM Generic Chap Rev 3 doc1 16 0011210934 1

Revision 3 January 2001 Stack (or Elevated) Release Points (denoted by the letter S or subscript s)

These are release points approximately twice the height of adjacent solid structures.

Releases are treated as elevated releases unaffected by the presence of the adjacent structures.

Ground Level Release Points (denoted by the letter G or subscript g)

These are release points at ground level or lower than adjacent solid structures. Releases are considered drawn into the downwind wake of these structures and are treated as ground level releases.

Vent (or Mixed Mode) Release Points (denoted by the letter V or subscript v)

These are release points as high or higher than adjacent solid structures but lower than twice the structure's heights. These releases are treated as a mixture of elevated and ground level releases. The proportion of the release attributed to either elevated or ground level in a vent release is determined by the ratio of stack exit velocity to the wind speed (see Section B.1.2.4 of Appendix B).

The definitions of these classifications are based on Regulatory Guide 1.111 (Reference 7). A list of the classifications of specific airborne release points for each of the Exelon Nuclear nuclear power stations is contained in Table A-2 in Appendix A.

4.1.5 Historical Average Atmospheric Conditions The dispersion characteristics of airborne effluents from a nuclear power station are dependent on weather conditions. Meteorological factors that directly affect the concentration of airborne radioactivity in a plume include the following:

Wind Direction The concentration of radioactivity is highest in the direction toward which the wind is blowing.

Wind Speed Greater wind speeds produce more dispersion and consequently lower concentrations of radioactivity.

Atmospheric Turbulence The greater the atmospheric turbulence, the more a plume spreads both vertically and horizontally. For calculations in this manual, the degree of turbulence is classified by use of seven atmospheric stability classes, designated A (extremely unstable) through G (extremely stable). The seven classes and some of their characteristics are listed in Table C-4 of Appendix C.

Meteorological conditions strongly impact the values of various parameters applied in the dose calculations of this manual. These include:

The Relative Concentration Factors X/Q and gamma-XlQ (Section 4.1.6)

The Relative Deposition Factor D/Q (Section 4.1.7)

The bases sections of the Standard Radiological Effluent Technical Specifications (guidance documents NUREGs 0472, 0473, 1301 and 1302) and the RETS specify that dose calculations be based on historical average atmospheric conditions". Therefore, this manual provides values for the above ODCM Genenc Chap Rev 3.d=c 17 0011210934 1

Revision 3 January 2001 parameters that are based on station-specific historical average meteorological conditions. These values were obtained by averaging hourly values of the parameters over a long-term, several-year period of record. The averaging period was based on calendar years in order to avoid any bias from weather conditions associated with any one season. The period of record is identified in each of the tables providing the values (see Appendix F).

4.1.6 Relative Concentration Factors X/Q and Gamma-X/Q A person immersed in a plume of airborne radioactivity is exposed to radiation from the plume and may also inhale some of the radioactivity from the plume. The concentration of radioactivity in air near the exposed person must be calculated to adequately evaluate doses resulting from any inhalation. The relative concentration factor X/Q (referred to as "chi over Q") is used to simplify these calculations. XIQ is the concentration of radioactivity in air, at a specified location, divided by the radioactivity release rate.

X/Q has the following units:

Units of X/Q = (CiIm 3) I (AiCi/sec) = sec/m 3 Station-specific values of X/Q are provided for each nuclear power station in Table F-5 of Appendix F.

These values are based on historical average atmospheric conditions (see Section 4.1.5).

For each of the release point classifications (eg. stack, vent and ground level) and for the 16 compass-direction sectors (N, NNE, etc.), Table F-5 provides the maximum value of X7Q for locations at or beyond the unrestricted area boundary.

The value of X/Q for each sector reflects the fraction of time that the wind blew into that sector and the distribution of wind speeds and atmospheric stability classes during that time. Note that the value would be zero if the wind never blew into the sector.

The gamma-xIQ provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. It is used in place of the semi-infinite plume model that tends to underestimate gamma air dose for elevated plumes. Use of the gamma-XIO also corrects for the tendency of the semi-infinite plume model to overestimate gamma air dose for mixed mode and ground level releases.

The methodologies for determining XIQ and gamma-XJQ are discussed in detail in Section B.3 of Appendix B.

4.1.7 Relative Deposition Factor D/Q As a plume travels away from its release point, portions of the plume may touch the ground and deposit radioactivity on the ground and/or on vegetation. Occurrences of such deposition are important to model since any radioactivity deposited on the ground or on vegetation may directly expose people and/or may be absorbed into food products which can ultimately be ingested by people. The relative deposition factor is used to simplify the dose calculations for these pathways.

The relative deposition factor D/Q is the rate of deposition of radioactivity on the ground divided by the radioactivity release rate. Its value was determined for specific conditions. In this manual it has the following units:

Units of DIQ = [(pCilsec)1m 2] / (pCilsec) = 11m2 The values of DIQ are affected by the same parameters that affect the values of x/Q: release characteristics, meteorological conditions and location (see Section 4.1.6). Station-specific values of D/Q are provided for each Exelon Nuclear nuclear power station in Appendix F Tables F-5 and F-6. These values are based on historical average atmospheric conditions (see Section 4.1.5).

For each release point classification and for each of the 16 compass-direction sectors (N, NNE, etc.),

Table F-5 provides the maximum value of D/Q for locations at or beyond the unrestricted area boundary.

ODCM Generic Chap Rev 3 doc 18 0011210934

Revision 3 January 2001 In Table F-6, values of D/Q are given for the locations of the nearest milk and meat producers within 5 miles of the nuclear power station. The methodology for determining DIQ is discussed in Section B.4 of Appendix B.

4.1.8 Dose Factors Various dose factors are used in this manual to simplify the calculation of radiation doses. These factors are listed in Table 4-2. Definitions of these factors are given in the remainder of this chapter. Methods of determining their values are addressed in Appendix B.

4.2 AIRBORNE RELEASES 4.2.1 Gamma Air Dose The term 'gamma air dose' refers to the component of dose absorbed by air resulting from the absorption of energy from photons emitted during nuclear and atomic transformations, including gamma rays, x-rays, annihilation radiation, and Bremsstrahlung radiation (see footnote on page 1.109-19 of Regulatory Guide 1.109).

The noble gas dose factors of Reg. Guide 1.109, Table B-1 are based upon assumption of immersion in a semi-infinite cloud. For ground level and mixed mode releases this tends to over estimate the gamma air dose arising from a plume that is actually finite in nature.

For elevated releases, the Reg. Guide 1.109 noble gas dose factors will underestimate exposure as they consider only immersion and not that portion of exposure arising from sky shine. At distances close in to the point of elevated release, the ground level concentration as predicted by x/Q will be essentially zero. In such a case, the sky shine component of the exposure becomes significant and must be considered.

The gamma-X/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. The methodology of Reg. Guide 1.J 09, Section C.2 and Appendix B provide the methodology for calculating finite cloud gamma air dose factors from which the gamma-XIQ values can be derived. Section B.5 addresses the calculation of these dose factors.

Three gamma-xIQ values are defined: (X/Q).", (X/Q)v7 and (X/Q)gy for stack, vent and ground level releases, respectively. Section B.3.5 addresses the calculation of the gamma-XIQ values.

4.2.1.1 Finite Cloud Gamma Air Dose Factor The finite cloud gamma air dose factor is determined by calculating the gamma dose rate to air (at a specific location and corresponding to a given release rate) and dividing that dose rate by the corresponding release rate:

Finite Cloud Gamma Air Dose Factor = [(mrad/yr)I(gtCi/sec)]

The methodology for this calculation is discussed in Section B.5 of Appendix B. The calculation is complex because the dose rate at any given point is affected by the radioactivity concentration and distance. Calculation of the finite cloud gamma air dose factor takes into consideration release characteristics, meteorological conditions and location (see Section 4.1.6). Additionally, the value is affected by radiological parameters: the distribution of energies and intensities for gamma emissions from each specific radionuclide and the photon attenuation characteristics of air.

In the ODCM, station-specific values of gamma dose factors are provided for each station in Appendix F.

Table F-7. These values are based on historical average atmospheric conditions (see Section 4.1.5). For the release point classification and for each of the 16 compass-direction sectors, Table F-7 provides the maximum value of the gamma air dose factor for noble gas radionuclides at the unrestricted area ODCM Genenc Chap Rev 3 doc 19 0011210934

Revision 3 January 2001 boundary. The value includes a correction for radioactive decay during transport of the radionuclide from the release point to the dose calculation location.

4.2.1.2 Semi-Infinite Cloud Gamma Air Dose Factor The semi-infinite cloud gamma dose factor is the gamma air dose rate divided by the concentration of radioactivity in air at the dose calculation location. Values of these gamma dose factors are radionuclide specific and are provided in Appendix C, Table C-9.

The semi-infinite cloud gamma dose factor is used in conjunction with gamma-XIQ to calculate noble gas gamma air dose and dose rate for elevated and finite noble gas plumes. The gamma-YJQ is defined such that for a given finite cloud the semi-infinite cloud methodology will yield the same gamma air dose as the finite cloud methodology.

4.22 Beta Air Dose The term 'beta air dose' refers to the component of dose absorbed by air resulting from the absorption of l

energy from emissions of beta particles, mono-energetic electrons and positrons during nuclear and atomic transformations (see the footnote on Page 1.109-20 of Regulatory Guide 1.109).

l The Beta Air Dose Factor The beta air dose factor is the beta air dose rate divided by the concentration of radioactivity in air at the dose calculation location. Values of the beta air dose factor are radionuclide specific and are provided in l

Appendix C Table C-9.

4.2.3 Total Body Dose and Dose Rate I

Total Body Dose I

Equation A-3 of Appendix A is used to calculate dose to the total body from noble gas radionuclides I

released in gaseous effluents. The total body dose equation is similar to that used to calculate gamma air dose (Equation A-1 of Appendix A).

Total Body Dose Rate I

Equation A-5 of Appendix A is used to calculate dose rate to the total body. The assumptions used for this equation are the same as those used in the calculation of total body dose (Equation A-3 of Appendix l

A) except that any shielding benefit (dose attenuation) provided by residential structures is not applied.

Since the calculation is for the maximum instantaneous dose rate, the dose recipient may be out of doors when exposed and would not be shielded from the exposure by any structural material.

The Total Body Dose Factor The total body dose factor is the total body dose rate divided by the radioactive release rate. Values for l

the total body dose factor are site specific and are provided in Table C-9 of Appendix C.

l ODCM Generic Chap Rev 3 do2 20 0011210934 l

Revision 3 January 2001 4.2.4 Skin Dose and Dose Rate Skin Dose Equation A-4 of Appendix A is used to calculate dose to skin from noble gas radionuclides released in gaseous effluents. The skin dose is the summation of dose to the skin from beta and gamma radiation.

The equation for beta dose to skin is similar to that used to calculate beta dose to air (Equation A-2 of Appendix A) except that beta skin dose factors are used instead of beta air dose factors. The beta skin dose factor differs from the beta air dose factor by accounting for the attenuation of beta radiation by the dead layer of skin. The dead layer of skin is not susceptible to radiation damage and therefore is not of concern. The beta dose to the skin from non-noble gases is insignificant and is not calculated for the reason described in Section 4.1.3. When calculating the beta contribution to skin dose, no reduction is included in the calculations due to shielding provided by occupancy of residential structures.

The equation for. gamma dose to skin is similar to that used to calculate gamma dose-to-air except for the following:

f Equation A-4 of Appendix A includes a units conversion factor 1.11 rem/rad to convert from units of gamma air dose (rad) to units of tissue dose equivalent (rem).

Equation A-4 of Appendix A includes a dimensionless factor of 0.7 to account for the shielding due to occupancy of residential structures.

Equation A4 of Appendix A uses gamma air dose factors not gamma total body dose factors. When l

calculating gamma dose to skin, no reduction is applied for the attenuation of radiation due to passage through body tissue (dead layer of skin).

Skin Dose Rate Equation A-6 of Appendix A is used to calculate dose rate to skin. The assumptions are the same as those used in the calculation of skin dose (Equation A4 of Appendix A) except that no credit is taken for shielding of gamma radiation by residential structures. The dose recipient may be outdoors when exposed and the maximum instantaneous dose rate is of concern.

The Skin Dose Factor Values of the beta air dose factors and skin dose factors are nuclide specific and are provided in Table C-9 of Appendix C for 15 noble gas radionuclides.

4.2.5 Ground Radiation Equations A-7 and A-8 of Appendix A are used to calculate the total body dose due to non-noble gas radionuclides released in gaseous effluents and deposited on the ground.

Comment Note that if there is no release of radionuclide I during a given time period, then the deposition rate is zero, the ground plane concentration is zero and the resulting dose due to ground deposition is zero. If there is a release of radionuclide i, the ground concentration is computed as if that release had been occurring at a constant rate for the ground deposition time period.

The Ground Plane Dose Conversion Factor The ground plane dose conversion factor is the dose rate to the total body per unit of radioactivity concentration on the ground. Values of the ground plane dose conversion factor that are calculated by ODCM Generc Chap Rev 3 doc 21 0011210934

Revision 3 January 2001 assuming constant concentration over an infinite plane are provided for various radionuclides in Table C-10 of Appendix C.

4.2.6 Inhalation Dose Radioactivity from airborne releases of radioactive iodine, particulate and tritium can enter the body through inhalation. Equations A-7 and A-9 of Appendix A are used to calculate dose commitment to the total body or organs due to inhalation of non-noble gas radionuclides released in gaseous effluents.

The Inhalation Dose Factor Values for the inhalation dose commitment factor are nuclide specific and are taken from Reg. Guide 1.109 (Reference 6) Tables E-7, 8, 9 and 10. These tables include data for four age groups (adult, teenager, child and infant) and seven body organs.

Dose Rate The inhalation dose rate is the rate at which dose is accrued by an individual breathing contaminated air.

Equation A-1 6 of Appendix A is used to calculate dose commitment rate to an organ due to inhalation of non-noble gas radionuclides. The assumptions are the same as used in the calculation of inhalation dose.

The dose rate is determined for the child age group in accordance with the guidance found in NUREGs 0472, 0473, 1301 and 1302 (References 2, 3, 105 and 106).

4.2.7 Ingestion Airborne releases of radioactive iodine, particulate and tritium can enter the food chain through deposition on vegetation. The radioactivity can be ingested by humans who consume the vegetation or who consume products (e.g., milk or meat) of animals who have fed on the contaminated vegetation. Each Exelon Nuclear nuclear power station considers the following ingestion pathways:

Vegetables Milk Meat.

Equations A-7 and A-10 through A-15 of Appendix A are used to calculate the dose due to ingestion of food containing non-noble gas radionuclides released in gaseous effluents. Dose is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures.

Values of the ingestion dose commitment factor are the same for each Exelon Nuclear nuclear power station. The components of this factor are not impacted by station-specific parameters. The station-specific aspects of the calculation of ingestion dose only concern the quantity of radioactivity ingested. Values of the ingestion dose commitment factors are taken from Reg. Guide 1.109 Tables E-11, 12, 13 and 14. These tables include data for four age groups and seven organs.

The equations used for radioactivity concentration on vegetation and in milk, and meat are discussed in Appendix A.

ODCM Generic Chap Rev 3 doc 2-2 0011210934

Revision 3 January 2001 4.3 LIQUID RELEASES The evaluation of dose due to releases of radioactivity in liquid effluents is required to confirm compliance l

with the provisions of RETS related to 10CFR50 Appendix I. ODCM Section 3.2 and Figure 3-1 list some of the pathways by which radioactivity in liquid effluents can impact man. The pathways used by Exelon Nuclear to calculate dose from liquid effluents are ingestion by drinking water and by eating fish from the l

body of water receiving station liquid discharges. The nuclear power stations obtain the dose commitment due to radioactivity in liquid effluent releases by summing the dose commitments from the drinking water l

and fish pathways depending upon their presence.

I Equations A-17 through A-20 of Appendix A are used to calculate dose for the member of the public due l

to consumption of drinking water and fish.

The radioactivity concentration in water is obtained by dividing the quantity of radioactivity released by the volume of water in which the release is diluted. The result can be modified by a factor to represent any l

-additional dilution that might occur.

I The radioactivity concentration in fish is the product of the radioactivity concentration in water and a bioaccumulation factor. The dilution factors for fish may be different from those for water. (The fish may be caught at a location different from where drinking water is drawn.)

The bioaccumulation factor accounts for the fact that the quantity of radioactivity in fish can build up with l

time to a higher value relative to the concentration of the radioactivity in the water they consume. The bioaccumulation factor is the equilibrium ratio of the concentration of radionuclide i in fish to its l

concentration in water. The same values are used for the bio-accumulation factor at each station. These values are provided in Appendix C, Table C-8.

4.4 CONTAINED SOURCES OF RADIOACTIVITY In addition to the total body, skin and single organ dose assessments previously described, an additional assessment is required. The additional assessment addresses radiation dose due to radioactivity contained within the nuclear power station and its structures.

There are presently two types of contained sources of radioactivity which are of concern in offsite radiological dose assessments. The first is that due to gamma rays resulting from nitrogen-16 carry-over to the turbine in BWR steam (skyshine). The second is that due to gamma rays associated with radioactive material contained in onsite radwaste and radioactive material storage facilities.

l 4.4.1 BWR Skyshine The most significant dose component to members of the public produced by "contained sources" is nitrogen-16 (16N) within the turbine building of BWRs. Although primary side shielding is around the turbine and its piping, 16N gamma rays scattered by air molecules in the overhead air space above the turbine and piping cause a measurable "skyshine" radiation dose in the local power plant environs.

Equation A-23 of Appendix A is used to evaluate skyshine dose. A complicating factor in the calculation is the practice at some stations of adding hydrogen to reactor coolant to improve coolant chemistry. The addition of hydrogen can increase the dose rate due to skyshine up to a factor of 10 times expected levels depending on injection rates and power levels (Reference 39). Increasing the hydrogen injection rate will increase the dose rates even further. (See Reference 102) The skyshine dose determined by Equation A-23 of Appendix A depends on the following factors:

l The distance of the dose recipient location from the turbine.

The number of hours per year that the location is occupied by a dose recipient.

The total energy [MWe-hr] generated by the nuclear power station with hydrogen addition.

The total energy LMWe-hr] generated by the nuclear power station without hydrogen addition.

ODCM Generic Chap Rev 3 doc 23 0011210934 1

Revision 3 January 2001 4.4.2 Onsite Radwaste and Rad Material Storage Facilities Low-level radioactive waste may be stored at any Exelon Nuclear nuclear power station in the following types of storage facilities:

Process Waste Storage Facilities Interim Radwaste Storage Facility (IRSF) structure Concrete vaults containing 48 radwaste liners (Also referred to as "48-pack";)

DAW Storage Facilities Dry Active Waste (DAW) facilities (may include Butler buildings/warehouses)

Replaced Steam Generator Storage Facilities Rad Material may be stored in facilities on site Rad Material Storage Facilities Contaminated tools and equipment in seavans and/or warehouses Spent Fuel may be stored in facilities on site:

ISFSI Facilities Independent spent fuel storage installation facilities Administrative controls are implemented by each station to ensure compliance to applicable regulations.

The impact to the offsite dose will be evaluated on a case by case basis and added to the station annex of the ODCM when applicable. In addition, a 10CFR50.59 analysis may be required for radwaste storage facilities.

4.5 TOTAL DOSE REQUIREMENTS 4.5.1 Total Effective Dose Equivalent Limits; IOCFR20 and 40CFR190 10CFR20 requires compliance to dose limits expressed as 'Total Effective Dose Equivalent" (TEDE).

Although annual dose limits in 1 OCFR20 are now expressed in terms of TEDEs, 40CFR190 limits remain stated as organ dose. The NRC continues to require IOCFR50 Appendix I and 40CFR190 doses to be reported in terms of organ dose and not TEDE. Due to the fact that organ dose limits set forth in 40CFR190 are substantially lower than those of 10CFR20 (25 mrem/yr vs 100 mrem/yr), the NRC has stated that demonstration of compliance with the dose limits in 40CFR190 will be deemed as demonstration of compliance with the dose limits of 1 OCFR20 for most facilities (Reference 104). In addition to compliance with 40CFR1 90, it may be necessary for a nuclear power plant to address dose from on-site activity by members of the public.

4.5.2 Total Dose For Uranium Fuel Cycle The nuclear power stations are required to determine the total dose to a member of the public due to all uranium fuel cycle sources in order to assess compliance with 40CFR190 as part of demonstrating compliance with 10CFR20.

The total dose for the uranium fuel cycle is the sum of doses due to radioactivity in airborne and liquid effluents and the doses due to direct radiation from contained sources at the nuclear power station. When evaluation of total dose is required for a station, the following contributions are summed:

Doses due to airborne and liquid effluents from the station.

ODCM Generc Chap Rev 3.doc 24 0011210934 1

Revision 3 January 2001I Doses due to liquid effluents from nuclear power stations upstream.

Doses due to nitrogen-16 (16N) skyshine, if the station is a boiling water reactor.

I Doses due to any onsite radioactive waste storage facilities; if applicable.

Section A.5.2 of Appendix A discusses the details of evaluations.

ODCM Generic Chap Rev 3.doc 25 0011210934 l

Revision 3 January 2001 1

Table 4-1 Radionuclide Types Considered For Airborne Effluent Exposure Pathways Extemal Radiation Plume Ground Categorv Noble Gases Internal Radiation Inhalation Inaestion x

Tritium (H-3)

Iodine9 x

x x

x l

Particulate" x

x a

The nuclear power stations are not required to consider all iodine radionuclides. Only particulates with half-life greater than 8 days need be considered. For details, see Generic Letter 89-01 and the RETS.

I ODCM Genenc Chap Rev 3.doc 26 0011210934 l

Revision 3 January 2001 Table 4-2 Radiation Dose Factors Name and Symbol Units Definition Gamma Air Dose Factor M,

Total Body Dose Factor.

K1 Beta A~ir Dose Factor N.

Beta Skin Dose Factor L Ground Plane Dose Conversion Factor DFG1 Inhalation Dose Commitment Factor

DFAp, Ingestion Dose Commitment Factor

DFIO, mradlyr per pCi/r 3 mren/yr per pCrM3 mrad/yr per pCim 3 rnremldyr per pCUm3 pere/hr per pCir rnrem per pCi mrem per pci Gamma air dose rate per unit of radioactivity concentration for radionuclide 1.

Total body dose rate per unit of radioactivity concentration for radionuclide I.

Beta air dose rate per unit of radioactivity concentration for radionuclide I.

Beta skin dose rate per unit of radioactivity concentration for radionuclide I.

Dose rate per unit of ground radioactivity concentration for radionuclide I.

Dose to organ j of age group a per unit of radioactivity inhaled for radionuclide i.

(see Note 1)

Dose to organ j of age group a per unit of radioactivity ingested for radionuclide i.

(see Note p)

Table RG 1.109 Table B-1, Column 4 RG 1.109 Table B-1, Column 5 RG 1.109 Table B-1, Column 2 RG 1.109 Table B-1, Column 3 RG 1.109 Table E-6, Column 2 RG 1.109 Tables; E-7, E-8.

E-9, E-10 RG 1.109 Tables; E-11, E-12, E-13, E-14 I

Note 1:

Doseassessmentsforl0CFR20and4OCFR 190 compliance are madeforan adui only.

Dose assessments for 1 OCFR5O Appendix I are made using dose factors of Regulatory Guide 1.109 (Reference 6) for all age groups.

I ODCM Generic Chap Rev 3.doc1 27 0011210934 l

Revision 3 January 2001 CHAPTER 5 MEASUREMENT

5.0 INTRODUCTION

Each nuclear station has three measurement programs associated with offsite dose assessment:

Measurement of releases of radioactivity from the station.

Measurement of meteorology at the station site.

Measurement of levels of radiation and radioactivity in the environs surrounding the station.

5.1 EFFLUENT AND PROCESS MONITORING Radioactivity in liquid and gaseous effluents is measured in order to provide data for calculating radiation doses and radioactivity concentrations in the environment of each nuclear power station. Measurement of effluent radioactivity is required by 10CFR20.1302 and 10CFR50. The RETS of each nuclear power station provide detailed requirements for instrumentation, sampling and analysis. Relevant Regulatory Guides are 1.21 (Reference 4) and 4.15 (Reference 13). Chapter 10 of the ODCM includes brief descriptions of effluent monitoring instruments at each nuclear power station. The RETS of each nuclear power station require submission to the NRC of reports of effluent radioactivity releases and environmental measurements.

5.2 METEOROLOGICAL MONITORING Meteorological parameters are measured in the vicinity of each nuclear power station in order to provide data for calculating radiation doses due to airborne effluent radioactivity. Some nuclear power stations' Technical Specifications state applicable requirements (typically under the subheading, 'Meteorological Instrumentation," in the instrumentation section). Regulatory guidance is given in Regulatory Guide 1.23 (Reference 5). Wind speed, wind direction and the temperature gradient are measured using instruments at two or more elevations on a meteorological tower at each Exelon Nuclear station. The elevations are chosen to provide meteorological data representative of the elevations of the airborne releases from the station. The Annual Radiological Environmental Operating Report includes a summary of meteorological data collected over the reporting year. These data are used to calculate optional isopleths of radiation dose and radioactivity concentration.

5.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

Each nuclear power station has a REMP that provides representative measurements of radiation and radioactive material in the environment. The program provides verification that measurable radiological impacts from the power station on the environment are within expectations derived from effluent measurements and calculations. The REMP is required by 1 OCFR50 (see Appendix I, Sections IV.B.2 and IV.B.3). General requirements of the program are prescribed in each station's RETS and more precise details (such as specific monitoring locations) are specified in ODCM Chapter 11.

5.3.1 Interlaboratory Comparison Program The laboratory which performs the REMP analyses is required by the RETS to participate in an interlaboratory comparison program. The purpose is to provide an independent check on the laboratory's analytical procedures and to alert it to potential problems (e.g. accuracy). In order to assess the measurements of radioactivity in environmental media, an independent agency supplies participating laboratories with samples of environmental media containing unspecified amounts of radioactivity. The ODCM Generic Chap Rev 3.doc 28 0011210934 1

Revision 3 January 2001 laboratories measure the radioactivity concentrations and report the results to the agency. At a later time, the agency informs the participating laboratories of the actual concentrations and associated uncertainties.

Any significant discrepancies are investigated by the participating laboratories. A similar process is used to assess measurements of environmental radiation by passive thermoluminescent dosimeters.

ODCM Generic Chap Rev 3.doc 29 00111210934

Revision 3 January 2001 CHAPTER 6 IMPLEMENTATION OF OFFSITE DOSE ASSESSMENT PROGRAM 6.1 NUCLEAR POWER STATION The nuclear power station staff is responsible for effluent monitoring. The staff determines effluent radioactivity concentration and flow rate. These data are used to determine the radioactivity release information required for the Radioactive Effluent Release Report and to perform monthly calculations and projections of offsite radiation dose.

The nuclear power station staff is also responsible for control of effluent radioactivity. Procedures are implemented for determining, calculating and implementing setpoints. Liquid and gaseous radwaste treatment systems and ventilation exhaust treatment systems are utilized when appropriate. The nuclear power station staff implements the Process Control Program (PCP) for solid radwaste and measures tank radioactivity and BWR off-gas radioactivity.

The nuclear power station staff maintains instrumentation associated with these activities and demonstrates operability of the instrumentation in accordance with the surveillance requirements of the RETS. In the event that any RETS requirements are violated, the nuclear power station staff is responsible for taking one of the actions allowed by the RETS and issuing any required reports to the NRC.

The nuclear power station staff assembles and distributes the Radioactive Effluent Release Report.

6.2 - M-ETEOROL:OGICAL CONTRACTOR The meteorological contractor operates and maintains the meteorological tower instrumentation at each nuclear power station. The contractor collects and analyzes the data and issues periodic reports. The contractor prepares the meteorological data summary required for the Annual Radiological Environmental Operating Report (AREOR) and also computes and plots isopleths included in the AREOR.

6.3 REMP CONTRACTOR The radiological environmental contractor collects environmental samples and performs radiological analyses as specified in the nuclear power station's REMP (see ODCM Chapters 11 and 12). The contractor issues reports of results to appropriate points of contact and each nuclear station. The contractor participates in an interlaboratory comparison program and reports results in the Annual Radiological Environmental Operating Report. The contractor performs the annual land use census and assembles the Annual Radiological Environmental Operating Report.

ODCM Generc Chap Rev 3.doc 30 0011210934 1

Revision 3 January 2001 CHAPTER 7 REFERENCES

1.

Deleted

2.

U.S. Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, NUREG-0472, Rev. 3, Draft, January 1983 (frequently revised).

3.

U.S. Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for Boiling Water Reactors, NUREG-0473, Rev. 3, Draft, September 1982 (frequently revised).

4.

U.S. Nuclear Regulatory Commission, Measuring. Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants. Regulatory Guide 1.21. Revision 1, June 1974.

5.

U.S. Nuclear Regulatory Commission, Onsite Meteorological Programs, Regulatory Guide 1.23, Safety Guide 23, February 17,1972.

6.

U.S. Nuclear Regulatory Commission, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I, Regulatory Guide 1.109, Rev. 1, October 1977.

7.

U.S. Nuclear Regulatory Commission, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Regulatory Guide 1.111, Rev. 1, July 1977.

8.

U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors, Regulatory Guide 1.112, Rev. O-R, April 1976; reissued May 1977.

9.

U.S. Nuclear Regulatory Commission, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, Regulatory Guide 1.113, Rev. 1, April 1977.

10.

U.S. Nuclear Regulatory Commission, Proarams for Monitoring Radioactivity in the Environs of Nuclear Power Plants, Regulatory Guide 4.1, Rev. 1, April 1975.

11.

U.S. Nuclear Regulatory Commission, Preparation of Environmental Reports for Nuclear Power Stations, Regulatory Guide 4.2, Rev. 2, July 1976.

12.

U.S. Nuclear Regulatory Commission, Environmental Technical Specifications for Nuclear Power Plants, Regulatory Guide 4.8, Rev. 1, December 1975. (See also the related Radiological Assessment Branch Technical Position, Rev. 1, November 1979.)

13.

U.S. Nuclear Regulatory Commission, Quality Assurance for Radiological Monitoring Programs (Normal Operations)--Effluent Streams and the Environment, Regulatory Guide 4.15, Rev. 1, February 1979.

14.

U.S. Nuclear Regulatory Commission, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, edited by J. S. Boegli et al. NUREG-0133, October 1978.

ODCM Generic Chap Rev 3.doc 31 0011210934

Revision 3 January 2001

15.

U.S. Nuclear Regulatory Commission, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, J. F. Sagendorf et al.

NUREG/CR-2919, PNL-4380, September 1982.

16.

U.S. Nuclear Regulatory Commission, Radiological Assessment, edited by J. E. Till and H. R.

Meyer, NUREG/CR-3332, ORNL-5968, September 1983.

17.

U.S. Nuclear Regulatory Commission, Standard Review Plan, NUREG-0800, July 1981.

18.

U.S. Atomic Energy Commission, Meteorology and Atomic Enerav 1968, edited by D. H. Slade, TID-21940, July 1968.

19.

U.S. Atomic Energy Commission, Plume Rise, G. A. Briggs, TID-25075,1969.

20.

U.S. Atomic Energy Commission, The Potential Radiological Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000, WASH 1209, January 1973.

21.

U.S. Atomic Energy Commission, HASL Procedures Manual, Health and Safety Laboratory, HASL-300 (revised annually).

22.

U.S. Department of Energy, Models and Parameters for Environmental Radiological Assessments, edited by C. W. Miller, DOE/TIC-1 1468, 1984.

23.

U.S. Department of Energy, Atmospheric Science and Power Production, edited by D. Randerson, DOEITIC-27601,1984.

24.

U.S. Environmental Protection Agency, Workbook of Atmospheric Dispersion Estimates, D. B.

Turner, Office of Air Programs Publication No. AP-26, 1970.

25.

U.S. Environmental Protection Agency, 40CFRI90 Environmental Radiation Protection Requirements for Normal Operations of Activities in the Uranium Fuel Cycle, Final Environmental Statement, EPA 520/4-76-016, November 1, 1976.

26.

U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle, EPA-520/9-73-003-C, November 1973.

27.

American Society of Mechanical Engineers, Recommended Guide for the Prediction of the Dispersion of Airbome Effluents, 1973.

28.

Eisenbud, M., Environmental Radioactivity, 3rd Edition, (Academic Press, Orlando, FL, 1987).

29.

Glasstone, S., and Jordan, W. H., Nuclear Power and Its Environmental Effects (American Nuclear Society, LaGrange Park, IL, 1980).

30.

International Atomic Energy Agency, Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine Releases, Safety Series, No. 57, 1982.

31.

National Council on Radiation Protection and Measurements, Radiological Assessment:

Predicting the Transport. Bioaccumulation, and Uptake by Man of Radionuclides Released to the Environment, NCRP Report No. 76, March 15,1984.

32.

American National Standards Institute, Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities, ANSI N 13.1-1969, February 19, 1969.

ODCM Genenc Chap Rev 3.doc 32 0011210934

Revision 3 January 2001

33.

Institute of Electrical and Electronics Engineers, Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N13.10-1974, September 19,1974.

34.

American National Standards Institute, Testing and Procedural Specifications for Thermoluminescence Dosimetry (Environmental Applications), ANSI N545-1975, August 20, 1975.

35.

American Nuclear Insurers, Effluent Monitoring, ANIIMAELU Engineering Inspection Criteria for Nuclear Liability Insurance, Section 5.1, Rev. 2, October 24, 1986.

36.

American Nuclear Insurers, Environmental Monitorinq, ANI/MAELU Engineering Inspection Criteria for Nuclear Liability Insurance, Section 5.2, Rev. 1, March 23, 1987.

37.

American Nuclear Insurers, Environmental Monitoring Programs, ANI/MAELU Information Bulletin 86-1, June 9, 1986.

38.

Cember, H., Introduction to Health Physics, 2nd Edition (Pergamon Press, Elmsford, NY 1983).

39.

Electric Power Research Institute, Guidelines for Permanent BWR Hydrogen Water Chemistry Installations-1987 Revision, EPRI NP-5283-SR-A, Special Report, September 1987.

40.

Commonwealth Edison Company, Information Relevant to Keeping Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable. LaSalle County Station, Units 1 and 2, June 4, 1976.

41.

U.S.-Nuclear Regulatory Commission, Branch Technical Position, Radiological Assessment Branch, Revision 1, November 1979. (This is a branch position on Regulatory Guide 4.8.)

42.

Deleted

43.

U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code),

NUREG-0017, April 1976.

44.

U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWR-GALE Code), NUREG-0016, April 1976.

45.

Sargent & Lundy, N-16 Skyshine from BWR Turbine Systems and Piping, NSLD Calculation No.

D2-2-85, Rev. 0, 2/1185.

46.

Sargent & Lundy Calculation ATD-0138, Rev. 0, N-16 Skyshine Ground Level Dose from Dresden Turbine Systems and Piping. July 14, 1992.

47.

Sargent & Lundy Calculation ATD-01 39, Rev. 0, N-16 Skyshine Ground Level Dose from LaSalle Turbine Systems and Piping. July 28, 1992.

48.

Sargent & Lundy Calculation ATD-0140, Rev. 0, N-16 Skyshine Ground Level Dose from Quad Cities Turbine Systems and Piping, July 28, 1992.

49.

U.S. Nuclear Regulatory Commission, Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), NUREG-0543, February 1980.

ODCM Generic Chap Rev 3.doc 33 0011210934

Revision 3 January 2001

50.

International Commission on Radiological Protection, Report of Committee Two on Permissible Dose for Internal Radiation, Recommendations of the International Commission on Radiological Protection, ICRP Publication 2, 1959.

51.

U.S. Nuclear Regulatory Commission, Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, Battelle Pacific Northwest Laboratories, NUREG-0172, 1977.

52.

W. C. Ng, Transfer Coefficients for Prediction of the Dose to Man via the Forage-Cow-Milk Pathway from Radionuclides Released to the Biosphere, UCRL-51939.

53.

E. C. Eirnutis and M. G. Konicek, Derivations of Continuous Functions for the Lateral and Vertical Atmospheric Dispersion Coefficients, Atmospheric Environment 6, 859 (1972).

54.

D. C. Kocher, Editor, Nuclear Decay Data for Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities, ORNL/NUREG/TM-102, August 1977.

55.

R. L. Heath, Gamma-Ray Spectrum Catalog, Aerojet Nuclear Co., ANCR-1 000-2, third or subsequent edition.

56.

S. E. Thompson, Concentration Factors of Chemical Elements in Edible Aquatic Organisms, UCRL-50564. Rev. 1, 1972.

57.

U.S. Nuclear Regulatory Commission, Instruction Concerning Risks from Occupational Radiation Exposure, Regulatory Guide 8.29, July 1981.

58.

Dresden Nuclear Power Station, Radioactive Waste and Environmental Monitoring, Annual Report 1987, March 1988.

59.

Reserved reference number

60.

Sargent & Lundy Calculation ATD-0173, Rev. 0, 9/21/92, Annual Dose to Members of the Public Due to the LaSalle IRSF.

61.

Sargent & Lundy Calculation ATD-0174, Rev. 0, 9/21/92, Annual Dose to Members of the Public Due to the Zion IRSF.

62.

Sargent & Lundy Calculation ATD-0175, Rev. 0, 9/21/92, Annual Dose to Members of the Public Due to the Quad Cities IRSF.

63.

Sargent & Lundy Calculation ATD-0176, Rev. 0, 9/21/92, Annual Dose to Members of the Public Due to the Dresden IRSF.

64.

Reserved reference number

65.

Sargent & Lundy Calculation ATD-0180, Rev. 0, 9/25192, Dose Information Around Braidwood DAW Sea/Land Van Storage Area.

66.

Sargent & Lundy Calculation ATD-0181, Rev. 0, 9125/92, Dose Information Around Byron DAW Sea/Land Van Storage Area.

67.

Sargent & Lundy Calculation ATD-0182, Rev. 0, 9125/92, Dose Information Around Dresden DAW Sea/Land Van Storage Area.

68.

Sargent & Lundy Calculation ATD-0183, Rev. 0, 9/25192, Dose Information Around LaSalle DAW Sea/Land Van Storage Area.

ODCM Genenc Chap Rev 3 doc 34 001 1210934

Revision 3 January 2001

69.

Catalytic, Inc., Determination of Roof and Wall Shielding for Onsite and Offsite Radiation Protection from Skvshine, Calculation Index Number 70161-19, August 22, 1984 (applies to Dresden).

70.

D. C. Kocher, Radioactivity Decay Data Tables, DOEITIC-11026, 1981.

71.

J. C. Courtney, A Handbook of Radiation Shielding Data, ANS/SD-76114, July 1976.

72.

Commonwealth Edison Company, Information Relevant to Keepinq Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable. Zion Station. Units I and 2, June 4, 1976.

73.

Commonwealth Edison Company, Information Relevant to KeeDing Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable. Dresden Station. Units 2 and 3, June 4,1976.

74.

Commonwealth Edison Company, Information Relevant to Keeping Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable. Quad Cities Station. Units 1 and 2, June 4, 1976.

75.

Sargent & Lundy, METWRSUM, S&L Program Number 09.5.187-1.0.

76.

Sargent & Lundy, Comments on CECo ODCM and List of S&L Calculations, Internal Office Memorandum, P. N. Derezotes to G. R. Davidson, November 23, 1988.

77.

Sargent & Lundy, AZAP. A Computer Program to Calculate Annual Average Offsite Doses from Routine Releases of Radionuclides in Gaseous Effluents and Postaccident X/Q Values, S&L Program Number 09.8.054-1.7.

78.

National Oceanic and Atmospheric Administration, A Program for Evaluating Atmospheric Dispersion from a Nuclear Power Station, J. F. Sagendorf, NOAA Technical Memorandum ERL ARL-42, Air Resources Laboratory, Idaho Falls, Idaho, May 1974.

79.

G. P. Lahti, R. S. Hubner, and J. C. Golden, Assessment of Gamma-Ray Exposures Due to Finite Plumes, Health Physics 41, 319 (1981).

80.

National Council of Radiation Protection and Measurements, Ionizing Radiation Exposure of the Population of the United States. NCRP Report No. 93, September 1, 1987.

81.

Reserved reference number

82.

W. R. Van Pelt (Environmental Analysts, Inc.), Letter to J. Golden (Exelon Nuclear) dated January 3, 1972.

83.

Electric Power Research Institute, Radiological Effects of Hydrogen Water Chemistry, EPRI NP4011, May 1985.

84.

U.S. Nuclear Regulatory Commission, Draft Generic Environmental Impact Statement on Uranium Milling, NUREG-0511, April 1979.

85.

U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle. Part I -

Fuel Supply, EPA-520/9-73-003-B, October 1973.

86.

U.S. Nuclear Regulatory Commission, Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors, NUREG-0002, August 1976.

ODCM Generic Chap Rev 3.doc 35 0011210934

Revision 3 January 2001

87.

U.S. Nuclear Regulatory Commission, Demographic Statistics Pertaining to Nuclear Power Reactor Sites, NUREG-0348, Draft, December 1977.

88.

Nuclear News 31, Number 10, Page 69 (August 1988).

89.

General Electric Company, Irradiated Fuel Storage at Morris Operation, Operating Experience Report, January 1972 through December 1982, K. J. Eger, NEDO-20969B.

90.

U.S. Nuclear Regulatory Commission, Generic Letter 89-01, "Guidance For The Implementation of Programmatic Controls For RETS In The Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program", January 1989.

91.

"Assessment of the Impact of Liquid Radioactive Effluents from Braidwood Station on Proposed Public Water Intakes at Wilmington, Illinois", J.C. Golden, NSEP, January 1990

92.

NRC Safety Evaluation Report (SER)/lIdaho Notional Engineering Laboratory Technical Evaluation Report (TER) of the Commonwealth Edison Offsite Dose Calculation Manual (ODCM), Revision OA, December 2,1991.

93.

Deleted

94.

Deleted.

95.

U.S. Nuclear Regulatory Commission, Standards for Protection Against Radiation (10CFR20).

96.

U.S. Nuclear Regulatory Commission, Licensing of Production and Utilization Facilities (10CFR50).

97.

Federal Register, Vol. 57, No. 169, Monday, August 31, 1992, page 39358.

98.

Miller, Charles W., Models and Parameters for Environmental Radiological Assessments, U.S.

Dept. of Energy, DE8102754, 1984, pages 32, 33,48, and 49.

99.

Kocher, D. C., "Dose-Rate Conversion Factors For External Exposure To Photons and Electrons",

Health Physics Vol. 45, No. 3 (September), pp. 665-686, 1983.

100.

U.S. Department of Health, Education and Welfare Public Health Service, Radiological Health Handbook, January 1970.

101.

ODCM Bases and Reference Document, rev.0, November, 1998.

102.

G. Moran, D. Goff, Ouad Cities Nuclear Power Station: 1993 Hydrogen Water Chemistry Stress Corrosion Monitoring Test - Unit 2, 9/17-23/93.

103.

U.S. Nuclear Regulatory Commission, Generic Letter 79-041, September 17, 1979.

104.

Federal Register, Vol. 56, No. 98, Tuesday, May 21, 1991, page 23374, column 3.

105.

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

106.

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

ODCM Generic Chap Rev 3.doc 36 0011210934

Revision 3 January 2001 107.

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

ODCM Geneic Chap Rev 3.doc 37 0011210934

Revision 4 September 2002 APPENDIX A COMPLIANCE METHODOLOGY TABLE OF CONTENTS PAGE A.0 INTRODUCTION A-1 A.1 AIRBORNE RELEASES A-1

1.

Release Point Classifications A-1

2.

Dose Due to Noble Gas Radionuclides A-1

1.

Gamma Air Dose A-1

2.

Beta Air Dose A-3

3.

Total Body Dose A-4

4.

Skin Dose A-4

3.

Dose Rate Due to Noble Gas Radionuclides A-5 I.

Total Body Dose Rate A-5

2.

Skin Dose Rate A-6

4.

Dose Due to Non-Noble Gas Radionuclides A-7

1.

Ground Deposition A-8

2.

Inhalation A-9

3.

Food Ingestion Pathway Dose Factors A-10

- 1.

Vegetation A-10

2.

Milk A-12

3.

Meat A-1 3

5.

Dose Rate Due to Non-Noble Gas Radionuclides A-14

6.

Operability and Use of Gaseous Effluent Treatment Systems A-15 A.2 LIQUID RELEASES A-16

1.

Dose A-16

1.

Potable Water Pathway A-17

2.

Fish Ingestion Pathway A-1 8

2.

Liquid Effluent Concentrations Requirement A-18

3.

Tank Discharges A-19

4.

Tank Overflow A-20

5.

Operability and Use of the Liquid Radwaste Treatment System A-20

6.

Drinking Water A-20

7.

Non-routine Liquid Release Pathways A-21 A.3 DOSE DUE TO CONTAINED SOURCES A-21

1.

BWR Skyshine A-21

2.

Dose from Onsite Radwaste Storage Facilities A-23 A4 TOTAL DOSE LIMITS (IOCFR20 and 40CFRI 90)

A-23

1.

Total External Total Body Dose A-23

2.

Total Dose A-24 ODCM Appendix A Rev 4 doc A-l 0208140916 1

Revision 4 September 2002 APPENDIX A TABLE OF CONTENTS (Cont'd)

PAGE A.5 COMPLIANCE TO TOTAL DOSE LIMITS A-25

1.

Total Dose Limit - IOCFR20 Compliance A-25

1.

Dose to a Member of the Public in the Unrestricted Area A-25

2.

Dose to a Member of the Public in the Restricted Area A-25

2.

Total Dose Due to the Uranium Fuel Cycle (40CFR1 90)

A-25

3.

Summary of Compliance Methodology A-26 A.6 DOSE DUE TO DRINKING WATER (40CFR141)

A-26

1.

40CFRI41 Restrictions on Manmade Radionuclides A-26

2.

Application A-27 LIST OF TABLES NUMBER TITLE PAGE A-0 Average Annual Concentrations Assumed to Produce A-27 a Total Body or Organ Dose of 4 mrem/yr.

A-1 Compliance Matrix A-28 A-2 Release Point Classifications A-29 A-3 Nearest Downstream Community Water Systems A-30 A-4 40CFRI90 Compliance A-31 ODCM Appendix A Rev 4 doc A-ii 0208140916 1

Revision 4 September 2002 APPENDIX A COMPLIANCE METHODOLOGY A.0 INTRODUCTION This appendix reviews the offsite radiological limits applicable to the nuclear power stations and presents in detail the equations and procedures used to assess compliance with these limits. An introduction to the calculational approach used here is given in Chapter 4. The approach incorporates simplifications such as the following:

Use of pre-calculated atmospheric transport parameters based on historical average atmospheric conditions (see Section 4.1.5). These atmospheric dispersion and deposition factors are defined in Chapter 4.

The equations and parameters of this appendix are for use in calculating offsite radiation doses during routine operating conditions. They are not for use in calculating doses due to non-routine releases (e.g.,

accident releases).

This section of the ODCM provides the methodological details for demonstrating compliance with the 1 OCFR20, I OCFR50 Appendix I and 40CFRI 90 radiological limits for liquid and gaseous effluents.

An overview of the required compliance is given in Tables 2-1, 2-2, and 2-3. In Table 2-1, the dose components are itemized and referenced, and an indication of their regulatory application is noted. A more detailed compliance matrix is given in Table 2-3. Additionally, the locations of dose receivers for each dose component are given in Table 2-2.

The following sections detail the required radiological dose calculations.

A.1 AIRBORNE RELEASES A.1.1 Release Point Classifications The pattern of dispersion of airborne releases is dependent on the height of the release point relative to adjacent structures. For the equations of this appendix, each release point Is classified as one of the following three height-dependent types, which are defined in Section 4.1.4:

Stack (or Elevated) Release Point (denoted by the letter S or subscript s)

Ground Level Release Point (denoted by the letter G or subscript g)

Vent (or Mixed Mode) Release Point (denoted by the letter V or subscript v)

The release point classifications of routine release points at the nuclear power stations are stated in Table A-2.

A.1.2 Dose Due to Noble Gas Radionuclides A.1.2.1 Gamma Air Dose Requirement RETS limit the gamma air dose due to noble gas effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:

Less than or equal to 5 mrad per calendar quarter.

Less than or equal to 10 mrad per calendar year.

ODCM Appendix A Rev 4 doc A-1 0208140916 1

Revision 4 September 2002 Equation The gamma air dose due to noble gases released in gaseous effluents is calculated by the following expression:

D = (3.1 7E - 8)

M, I (X/Q)Y A.s +(XfQ) A, +(X/Q)AAjg A

(A-1)

The summation is over noble gas radionuclides i.

D-Gamma Air Dose

[mrad]

Dose to air due to gamma radiation from noble gas radionuclides released in gaseous effluents.

3.17E-8 Conversion Constant (seconds to years)

[yr/sec]

M, Gamma Air Dose Conversion Factor

[(mrad/yr)/(ICiCm 3)]

Gamma air dose rate factor per unit of radioactivity release rate for radionuclide i. From Table C-9 of Appendix C.

(X/Q)s, (X/Q)4, (X/Q)y Gamma-x/Q Factor

[secIm3l Radioactivity concentration based on finite cloud methodology at a specific location per unit of radioactivity release rate from a stack, vent or ground level release, respectively. See Section B.3.5 and Table F-5b of appendix F.

AX, A,,,, Au Cumulative Radionuclide Release

[uCi Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively.

Application RETS require determination of cumulative and projected gamma air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days (see Sections 12.4 of each station's RETS or Technical Specifications).

Gamma air dose is calculated for the sector with the highest offsite (X/Q)T and is compared with the RETS limits on gamma air dose.

For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10.

ODCM Appendix A Rev 4.doc A-2 0208140916 1

Revision 4 September 2002 A.1.2.2 Beta Air Dose Requirement RETS limit the beta air dose due to noble gases in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:

Less than or equal to 10 mrad per calendar quarter.

Less than or equal to 20 mrad per calendar year.

Equation The beta air dose due to noble gases released in gaseous effluents is calculated by the following expression:

Do = (3.17E - 8)Z { N1[(x/Q)1A, + (/Q)vA, + (x/Q)gAg }

(A-2)

The summation is over noble gas radionuclides i.

Do Beta Dose

[mrad]

Dose to air due to beta radiation from noble gas radionuclides released in gaseous effluents.

3.17E-8 Conversion Constant (seconds to years)

[yr/sec]

N.

Beta Air Dose Conversion Factor

[(mrad/yr)I(gCi/m 3)]

Beta air dose rate per unit of radioactivity concentration for radionuclide i. Take from Table C-9 of Appendix C.

(X/Q)-

Relative Concentration Factor

[sec/m3]

(xIQ)X (xIQ)0 Radioactivity concentration based on semi-infinite cloud methodology at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F.

A. AXv, Aig Cumulative Radionuclide Release

[JLCi]

Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively.

Application RETS require determination of cumulative and projected beta air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days (see Section 12.4 of each station's RETS or Technical Specification).

Beta air dose is calculated for the sector with the highest offsite (XIQ) and is compared with the RETS limit on beta air dose.

00CM Appendix A Rev 4 doc A-3 0208140916

Revision 4 September 2002 For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10.

A.1.2.3 Total Body Dose Requirement The total body dose, to any receiver is due, in part, to gamma radiation emitted from radioactivity in airborne effluents. This component is added to others to demonstrate compliance to the requirements of 40CFRI90 and 1QCFR20.

Equation The total body dose component due to gamma radiation from noble gases released in gaseous effluents is calculated by the following expression:

DTB =(3.17E-8)YK1J(X/Q)YA1. + (X/Q) Al,, +(X/Q)YAw (A-3)

The summation is over noble gas radionuclides i.

DT8 Total Body Dose

[mrem]

Dose to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents.

3.17E-8 Conversion Constant (seconds to years)

[yr/sec]

Ka Gamma Total Body Dose Conversion Factor

[(mremlyr)/(uCi/m3)]

Gamma total body dose factor due to gamma emissions for noble gas radionuclide i released from a stack, vent or ground level release point, respectively. Taken from Table C-9 of Appendix C.

A,, A,, Au Cumulative Radionuclide Release

[PCi]

Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively.

Application The total body dose is also calculated for the 40CFR190 and 1 OCFR20 compliance assessments. In some cases, the total body dose may be required in 1 OCFR50 Appendix I assessments (See Table 2-1).

A.1.2.4 Skin Dose Requirement There is no regulatory requirement to evaluate skin dose. However, this component is evaluated for reference as there is skin dose design objective contained in IOCFR50 Appendix I. Note that in the unlikely event that if beta air dose guideline is exceeded, then the skin dose will require evaluation.

ODCM Appendix A Rev 4 doc A-4 0208140916 l

Revision 4 September 2002 Equation The part of skin dose due to noble gases released in gaseous effluents is calculated by the following expression:

DSK = (3.17E - 8) { L. [ (X/Q). Al + (X/Q)v Aw + (X/Q)9 Au,]

+ (1.11)M, [ (X/Q)TA,. +(X/Q)vAh +(/Q) Au ]

(A-4)

The summation is over noble gas radionuclides i.

DSK Skin Dose

[mrem]

Dose to the skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents.

L, Beta Skin Dose Conversion Factor

[(mrem/yr)/(pCi/m 3)]

Beta skin dose rate per unit of radioactivity concentration for radionuclide i. Taken from Table C-9 of Appendix C.

1.11 Conversion Constant (rads in air to rem in tissue)

[mrem/mrad]

All other terms have been previously defined.

Application The skin dose is calculated for reference only.

A.1.3 Dose Rate Due to Noble Gas Radionuclides A.1.3.1 Total Body Dose Rate Requirement RETS limit the total body dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to 500 mrem/yr at all times. (see Section 12.4 of each station's RETS and Technical Specifications)

Equation The total body dose rate due to noble gases released in gaseous effluents is calculated by the following expression:

DTB = EKI {(X/Q)yQ1 + (XIQ)VQa

+(X/Q)'Q1 9}

(A-5)

The summation is over noble gas radionuclides i.

DTB Total Body Dose Rate

[mrem/yr]

Dose rate to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents.

ODCM Appendix A Rev 4 doc A-5 0208140916 l

Revision 4 September 2002 Q,5, Q,, Q1g Release Rate

[pCi/sec]

Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively.

All other terms have been previously defined.

Application RETS require the dose rate due to noble gases in gaseous effluents be determined to be within the above limit in accordance with methodology specified in the ODCM (see Section 12.4 of each station's RETS and Technical Specifications).

To comply with this specification, each station uses an effluent radiation monitor setpoint corresponding to an offsite total body dose rate at or below the limit (see Chapter 10). In addition, each station assesses compliance by calculating offsite total body dose rate on the basis of periodic samples obtained in accordance with station procedures.

A.1.3.2 Skin Dose Rate Requirement RETS limit the skin dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to a dose rate of 3000 mrem/yr at all times. (See Section 12.4 of each station's RETS and/or Technical Specifications)

Equation The skin dose rate due to noble gases released in gaseous effluents is calculated by the following expression:

DSK =

{Lj[ (l/Q).

Q + (X/Q), Qw + (X/Q)g Qg]

+ (1.11) Ml [ (X/Q): Q1 + (X/Q)V QI + (X/Q)yQ Q ]A6 The summation is over noble gas radionuclides i.

DSK Skin Dose Rate

[mrem/yr]

Dose rate to skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents.

Qjs Qh,, Qjg Release Rate

[pCi/sec]

Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively.

All other terms been previously defined.

Application RETS require the dose rate due to noble gases in gaseous effluents to be determined to be within the above limit in accordance with methodology specified in the ODCM. (See Section 12.4 of each station's RETS and Technical Specifications.)

ODCM Appendix A Rev 4.doc A-6 0208140916 l

Revision 4 September 2002 To comply with this specification, each station uses an effluent radiation monitor setpoint corresponding to an offsite skin dose rate at or below the limit (see Chapter 10). In addition, each station assesses compliance by calculating offsite skin dose rate on the basis of samples obtained periodically in accordance with station procedures.

A.1.4 Dose Due to Non-Noble Gas Radionuclides Requirement RETS provide the following limits, based on I OCFR50 Appendix I, on the dose to a member of the public from specified non-noble gas radionuclides in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary:

Less than or equal to 7.5 mrem to any organ during any calendar quarter.

Less than or equal to 15 mrem to any organ during any calendar year.

The individual dose components are also required as part of the 40CFRI90 assessments and combined as part of the 10CFR20 assessment (See Section A.4). The dose due to radionuclides deposited on the ground is considered to be a component of the deep dose equivalent for I OCFR20 compliance and an organ (and total body) dose component for 1 OCFR50 Appendix I and 40CFR190 compliance.

In accordance with the definition of dose in Regulatory Guide 1.109. the term "dose" in this document when applied to individuals, is used instead of the more precise term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). When applied to the evaluation of internal deposition of radioactivity, the term "dose' as used here, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is evaluated over a period of 50 years. Assessments for IOCFR50 Appendix I compliance are made for 4 age groups (adultlteenager/childlinfant) using Regulatory Guide 1.109 (Reference 6) dose conversion factors.

Equation The dose is calculated for releases in the time period under consideration.

Specifically, the dose is calculated as follows:

DNNG = (3.17E - 8)O A[WRapAj

+WvRaipjAv +WgRaipjAig]

(A-7)

P i

The summation is over pathways p and non-noble gas radionuclides i.

DNJNG Dose Due to Non-Noble Gas Radionuclides

[mrem]

Dose due to non-noble gases (radioiodines, tritium and particulates) to age group a, and to organ j.

3.17E-8 Conversion Constant (seconds to years)

[yr/sec]

Ws, WV, WC Relative Concentration Factor ODCM Appendix A Rev 4 doc A-7 02081409t6 I

Revision 4 September 2002 Radioactive concentration at a specific location per unit of radioactivity release rate or concentration for stack, vent or ground level release, respectively.

W., W,, or W. = (X/Q)s, (X/Q), or (X/Q)g for immersion, inhalation and all tritium pathways.

Ws, W, or W. = (D/Q)s, (D/Q), or (DIQ)g for ground plain and all ingestion pathways.

(xIQ)s, (XIQ)I, (XIQ)9 Relative Concentration Factor

[sec/m3]

Radioactivity concentration based on semi-infinite cloud model at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F.

(DIQ), (DIQ),, (DIQ),g Relative Deposition Factor

[1/m Radioactivity concentration at a specified location per unit of radioactivity release concentration for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-6 of Appendix F.

R, Site-Specific Dose Factor

[(m2 mrern/yr)/(plCi/sec)]

or

[(mrem/yr)/(fLCi/m 3)]

Site-specific dose factor for age group a, nuclide i, pathway p and organ

j. Pathway included are ground plane exposure, inhalation, vegetation ingestion, milk ingestion and meat ingestion. Values of Rp, are provided in Appendix F.

A.,

A1 A

Cumulative Radionuclide Release

[1 Ci]

Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively.

Application RETS require cumulative and projected dose contributions for the current calendar quarter and the current calendar year for the specified non-noble gas radionuclides in airborne effluents to be determined at least once per 31 days (see Section 12.4 of each station's RETS and Technical Specifications).

To comply with this specification, each nuclear power station obtains and analyzes samples in accordance with the radioactive gaseous waste or gaseous effluent sampling and analysis program in its RETS. In accordance with NUREG 0133 (Reference 14), dose due to non-noble gases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure. The inhalation and ground plane exposure pathways are considered to exist at all locations. The food ingestion pathways at a specific location are considered based on their existence as determined by land use census. The values used for (X/Q) and (D/Q) correspond to the applicable pathway location.

ODCM Appendix A Rev 4.doc A-8 0208140916 1

Revision 4 September 2002 For a release attributable to a processing or effluent system shared by more than one reactor, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system.

The allocation procedure is specified in ODCM Chapter 10.

The dose evaluated is also included as part of the 1 OCFR20 and 40CFR1 90 assessment (See Section A.4).

A.1.4.1 Ground Deposition The site-specific dose factor for ground deposition of radioactivity is considered to be a total body dose component and is calculated by the following expression:

R.I(GP)J [D/Q] = K'KM (O.7)DFG,[ - e ]

(A-8)

RI(GP)i [D/Q]

Ground Plane Deposition Dose Factor

[(mi2 mrem/yr)/(pCi/sec)]

Site-specific ground plane dose factor for age group a, nuclide i and organ j. The ground plane dose is calculated using (D/Q).

K' Conversion Constant (1 E6 pCi per pCi)

[PCi/pCi]

K' Conversion Constant (8760 hr/yr)

[hr/yr]

0.7 Shielding Factor; a factor which accounts for dimensionless shielding due to occupancy of structures.

DFG, Ground Plane Dose Conversion Factor i(mrem/hr)/(pCi/m2)]

Dose rate to the total body per unit of surface radioactivity concentration due to standing on ground uniformly contaminated with radionuclide i. Taken from Table C-1 0 of Appendix C.

Note that ground plane dose factors are only given for the total body and no age group. Doses to other organs are assumed to be equal to the total body dose. All age groups are assumed to receive the same dose.

Radiological Decay Constant

[hr1]

Radiological decay constant for radionuclide i. See Table C-7 of Appendix C.

th Time Period of Ground Deposition

[hr]

Time period during which the radioactivity on the ground is assumed to have been deposited. See Table C-1 of Appendix C.

Application The ground plane exposure pathway is considered to exist at all locations.

ODCM Appendix A Rev 4.doc A-9 0208140916

Revision 4 September 2002 A.1.4.2 Inhalation The site-specific dose factor for inhalation is calculated by the following expression:

RaI(inhaI)[X/Q] = K'BR.DFAa (A-9)

Ra1(1nhl")) [X/Q]

Inhalation Pathway Dose Factor

[(mrem/yr)/(pCi/m 3)]

Site-specific inhalation dose factor for age group a, nuclide i and organ j.

The inhalation dose is calculated using (XIQ).

K' Conversion Constant (1E6 pCi per pCi)

[pCi!/fC]

BR.

Individual Air Inhalation Rate

[m3/yr]

The air intake rate for individuals in age group a. See Table C-2 of Appendix C.

DFA,,a Inhalation Dose Conversion Factor

[mremfpCg Dose commitment to an individual in age group a to organ J per unit of activity of radionuclide i inhaled. Taken from Tables E-7 through E-10 of Regulatory Guide 1.109. The values for H-3 and for Sr-90 are taken from NUREG 4013 (Reference 107).

Application The inhalation exposure pathway is considered to exist at all locations.

A.1.4.3 Food Ingestion Pathway Dose Factors Application Food ingestion pathway doses are calculated at locations indicated by the land use census survey. If no real pathway exists within 5 miles of the station, the cow-milk pathway is assumed to be located at 5 miles. Food pathway calculations are not made for sectors in which the offsite regions near the station are over bodies of water.

A.1.4.3.1 Vegetation Ingestion Pathway Dose Factor The dose factor for consumption of vegetables is calculated by the following expression:

Raqvog)j [D/Q] = K' [

(xr)

(DFLaIJ) [UafLe IAL +Ufe U

Ith]

(A-10)

R al(vq)j[D/Q]

Vegetation Ingestion Pathway Dose Factor

[(m2 mremryr)/(.iCi/sec)]

Site-specific vegetation ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the vegetation dose is calculated using (DIQ).

K' Conversion Constant (IE6 pCi per pCi)

[pCi/PCi]

ODCM Appendix A Rev 4 doc A-1 0 0208140916 1

Revision 4 September 2002 r

Vegetation Retention Factor dimensionless Ye Agricultural Productivity Yield

[kg/ ml Radiological Decay Constant

[1/sec]

Radiological decay constant for radionuclide i. See Table C-7 of Appendix C.

Weathering Decay Constant

[1Isec]

Removal constant for physical loss of activity by weathering. See Table C-1 of Appendix C.

DFL,,j Ingestion Dose Conversion Factor

[mrem/pCil Ingestion dose conversion factor for age group a, nuclide i and organ j.

Converts pCi ingested to mrem. Taken from Tables E-1 I though E-14 of Regulatory Guide 1.109. The values for H-3 and Sr-90 are taken from NUREG 4013 (Reference 107).

UL Consumption Rate for Fresh Leafy Vegetation

[kg/yr]

Consumption rate for fresh leafy vegetation for age group a.

Uas Consumption Rate for Stored Vegetation

[kg/yr]

Consumption rate for stored vegetation for age group a.

f, Local Leafy Vegetation Fraction dimensionless Fraction of the annual intake of fresh leafy vegetation which is grown locally.

fa Local Stored Vegetation Fraction dimensionless Fraction of the annual intake of stored vegetation which is grown locally.

tL Environmental Transport Time - Fresh Vegetation

[sec]

Average time between harvest of leafy vegetation and its consumption.

th Environmental Transport Time - Stored Vegetation

[sec]

Average time between harvest of stored vegetation and its consumption.

The tritium dose from the vegetation pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium vegetation pathway is:

R.(H-3XVeg)J [X/0] = K' K - (ULfL + USfg )DFLl(H-3 )J [0.75(0.5/H)]

(A-1I1)

R.(H-3XV'g)j[XfQ]

Tritium Vegetation Ingestion Pathway Dose Factor

[(mrem/yr)/(gCilm 3l ODCM Appendix A Rev 4.doc A-1 1 0208140916 1

Revision 4 September 2002 l

Kl'e H

0.75 Site-specific tritium vegetation ingestion dose factor for age group a and organ j. The tritium vegetation dose is calculated using X/Q.

Conversion Constant (1 E3 gm per Kg)

[gm/Kg Absolute Atmospheric Humidity

[gm/ml Water Fraction dimensionless The fraction of total vegetation that is water.

Specific Activity Ratio dimensionless I]

0.5 A.1.4.3.2 Milk Ingestion Pathway Dose Factor The dose factor for consumption of milk is calculated by the following expressions:

R g(MIIk)J D/Q] = K' QF(UX_) F (r)(DF

[LY.+

( 1 yfj)e-'1'- e'A t' alMl)XI

+ X, YF 8U (A-12)

RaI(MIIk)J [D/Q]

K' QF Uam Fm Milk Ingestion Pathway Dose Factor

[(M2 mremlyr)/(jiCi/sec)]

Site-specific milk ingestion dose factor for age group a, nuclide I and organ j. With the exception of H-3, the milk dose factor is calculated using (D/Q).

Conversion Constant (1 E6 pCi per pCi)

[pCi/i+/-Cq Feed Consumption

[Kg/da]

Amount of feed consumed by milk animal each day. See Table C-1 of Appendix C.

Milk Consumption Rate f1/yr]

Milk consumption rate for age group a.

Stable Element Transfer Coefficient for Milk

[daA]

Fraction of animal's daily intake of a particular chemical element which appears in each liter of milk (pCi/I in milk per pCi/da ingested by animal).

See Table C-3 of Appendix C.

Pasture Time Fraction dimensionless Fraction of year that animal is on pasture.

ODCM AppendIK A Rev 4 doc A-12 0208140916 l

Revision 4 September 2002 Pasture Grass Fraction dimensionless Fraction of animal feed that is pasture grass while animal is on pasture.

YP Agricultural Productivity Yield - Pasture Grass

[kg/m2]

The agricultural productivity by unit area of pasture feed grass.

Ys Agricultural Productivity Yield - Stored Feed

[kg/ml The agricultural productivity by unit area of stored feed.

th Environmental Transport Time - Stored Feed

[sec]

Average time between harvest to consumption of stored feed by milk animal.

tf Environmental Transport Time - Pasture to Consumption

[sec]

Average time from pasture, to milk animal, to milk, to consumption.

All other terms have been previously defined.

The tritium dose from the milk pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium milk pathway is:

R. (H-3XMIkIk/

Q] = K' KY F. Q FU.DFL(H-3j) [0.75(0.5/H)]

Tritium Milk Ingestion Pathway Dose Factor (A-13)

[(mrem/yr)/(pCim 3)]

Ra(H3XMjIk) [x/Q]

Site-specific tritium milk ingestion dose factor for age group a and organ

j. The tritium milk dose is calculated using X/Q.

K"'

Conversion Constant (1 E3 gm per Kg)

[gm/Kg H

Absolute Atmospheric Humidity

[gm/r 3 0.75 Water Fraction dimensionless The fraction of total vegetation that is water.

0.5 Specific Activity Ratio dimensionless All other terms have been previously defined.

A.1.4.3.3 Meat The dose factor for consumption of meat is calculated by the following expression:

I I

R.I(Meat)j [D/Q] - K'QF(Uf) Ff(r)(DFL. )

+f k

+(1-ff 5)e h'leitf XI +XW IL Y.

(A-14)

ODCM Appendix A Rev 4 doc A-13 0208140916

Revision 4 September 2002 l

R al(MeaZ)J [D/QJ Meat Ingestion Pathway Dose Factor

[(M2 mrem/yr)/I(Ci/sec)]

Site-specific meat ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the meat dose factor is calculated using (D/Q).

U.,

Meat Consumption Rate

[I/yr]

Meat consumption rate for age group a.

Ft Stable Element Transfer Coefficient for Meat fda/Kg]

Fraction of animal's daily intake of a particular chemical element which appears in each liter of meat (pCi/Kg in meat per pCida ingested by animal). See Table C-3 of Appendix C.

th Environmental Transport Time - Stored Feed

[sec]

Average time between harvest to consumption of stored feed by meat animal.

Environmental Transport Time - Pasture to Consumption

[sec]

Average time from pasture, to meat animal, to meat, to consumption.

All other terms have been previously defined.

The tritium dose from the meat pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium meat pathway is:

Ra(H-3XI1at)j[/Q] = K'K - Ff QFUafDFL(H-3j[o.75(o.5/H)]

Tritium Meat Ingestion Pathway Dose Factor (A-1 5)

[(mrem/yr)/(VCi/m 3)]

Ra(H-3XMat)J [/Q]

Site-specific tritium meat ingestion dose factor for age group a and organ

j. The tritium meat dose is calculated using X/Q.

K"'

Conversion Constant (1E3 gm per Kg)

[gm/Kg]

H Absolute Atmospheric Humidity

[gm/m3]

0.75 Water Fraction dimensionless The fraction of total vegetation that is water.

0.5 Specific Activity Ratio dimensionless All other terms have been previously defined.

ODCM Appendix A Rev 4.doc A-14 0208140916 1

Revision 4 September 2002 A.1.5 Dose Rate Due to Non-Noble Gas Radionuclides Requirement RETS limit the dose rate to any organ, due to radioactive materials in gaseous effluents released from a site to areas at and beyond the site boundary, to less than or equal to a dose rate of 1500 mrem/yr (see Section 12.4 of each station's RETS and Technical Specifications).

Typically the child is considered to be the limiting receptor in calculating dose rate to organs due to inhalation of non-noble gas radionuclides in gaseous effluents.

Equation The dose rate to any child organ due to inhalation is calculated by the following expression:

. NNG D(Ch1d)1(1nha1)j =

R(Ch1d)1(1nha1){(N/Q)M. Q1 + (X/Q)" Q, + (W/Q) 9 QJ}

(A-1 6)

The summation is over non-noble gas radionuclides i.

. NNG D(Chi1d)I(InhaI)J Inhalation Dose Rate

[mrem/yr]

Dose rate to the child age group from radionuclide i, via the inhalation pathway to organ j due to non-noble gas radionuclides.

R(chId)iinha1)J Inhalation Dose Factor

[(mrem/yr)I(pCi/m3)]

Inhalation dose factor for child age group for radionuclide i, and organ j.

This dose factor is defined by Equation A-9.

Qi, QO, Q.9 Radionuclide Release Rate

[pCi/sec]

Measured release rate of radionuclide i from a stack, vent, or ground level release point, respectively.

All other terms have been previously defined.

Application RETS require the dose rate due to non-noble gas radioactive materials in airborne effluents be determined to be within the above limit in accordance with a sampling and analysis program specified in the RETS (see Section 12.4 of each station's RETS and Technical Specifications).

To comply with this specification, each station obtains and analyzes samples in accordance with the sampling and analysis program in its RETS. The child organ dose rate due to inhalation is calculated in each sector at the location of the highest offsite X/Q. The result for the sector with the highest organ inhalation dose rate is compared to the limit.

ODCM Appendix A Rev 4 doc A-1 5 0208150716

Revision 4 September 2002 A.1.6 Operability and Use of Gaseous Effluent Treatment Systems Requirement 1 OCFR50 Appendix I and the station RETS require that the ventilation exhaust treatment system and the waste gas holdup system be used when projected offsite doses in 31 days, due to gaseous effluent releases, from each reactor unit, exceed any of the following limits:

0.2 mrad to air from gamma radiation.

0.4 mrad to air from beta radiation.

0.3 mrem to any organ of a member of the public.

The nuclear power stations are required to project doses due to gaseous releases from the site at least once per 31 days.

Equation Offsite doses due to projected releases of radioactive materials in gaseous effluents are calculated using Equations A-1, A-2 and A-7. Projected cumulative radionuclide releases are used in place of measured cumulative releases A,, A,, and Ag.

Application For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in Chapter 10 of this manual.

A.2 LIQUID RELEASES A.2.1 Dose Requirement The design objectives of 10CFR50, Appendix I and RETS provide the following limits on the dose to a member of the public from radioactive materials in liquid effluents released from each reactor unit to restricted area boundaries:

During any calendar quarter, less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ.

During any calendar year, less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ.

The organ doses due to radioactivity in liquid effluents are also used as part of the 40CFR1 90 compliance and are included in the combination of doses to determine the total dose used to demonstrate IOCFR20 compliance. (See Section A.4)

Dose assessments for I OCFR50 Appendix I compliance are made for four age groups (adult/teenager/child/infant) using NUREG 0133 (Reference 14) methodology and Regulatory Guide 1.109 (Reference 6) dose conversion factors.

Equation The dose from radioactive materials in liquid effluents considers the contributions for consumption of fish and potable water. All of these pathways are considered in the dose assessment unless demonstrated not to be present. While the adult is normally considered the maximum individual, the methodology provides for dose to be calculated for all four age groups. The dose to each organ (and to the total body) is calculated by the following expression:

ODCM Appendix A Rev 4 doc A-16 0208140916

Revision 4 September 2002 l

DLJq =F At1ZAApjCi P I The summation is over exposure pathways p and radionuclides i.

Duq Organ and Total Body Dose Due to Liquid Effluents (A-17)

[mrem]

F Dose to organ j (including total body) of age group a due to radioactivity in liquid effluents.

Near Field Average Dilution Factor dimensionless Dilution in the near field averaged over the period of interest.

Defined as:

Waste Flow Dilution Flow x Z (A-1 8)

Waste Flow Dilution Flow z

At C,

Liquid Radioactive Waste Flow jgpm]

The average flow during disposal from the discharge structure release point into the receiving water body.

Dilution Water Flow During Period of Interest

[gpm]

Discharge Structure Mixing Factor dimensionless Site-specific factor to account for the mixing effect of the discharge structure. The factor addresses the dilution which occurs in the near field between the discharge structure and the body of water containing the fish in the liquid ingestion pathway. From Table F-1, Appendix F.

Duration of Release

[hrs]

Average Radionuclide Concentration

[PCi/ml]

Average concentration of radionuclide i, in the undiluted liquid effluent during time period At.

Site-Specific Liquid Dose Factor

[(mrem/hr)/(jiCi/ml)]

Site-specific dose factor for age group a, nuclide i, liquid pathway p and organ j. The pathways included are potable water and fish ingestion.

A,,p, is defined for these pathways in the following sections. Values for A,,p, are provided in Appendix F.

A 2.1.1 Potable Water Pathway The site-specific potable water pathway dose factor is calculated by the following expression:

Aa(pw)1 = k. f{W} I DFL3 (A-19)

Where:

ODCM Appendix A Rev 4.doc A-17 0208140916 1

Revision 4 September 2002 A.,{pM Site-Specific Dose Factor for Potable Water

[(mremlhr)/(pCi/ml)]

Pathway Site-specific potable water ingestion dose factor for age group a, nuclide I and organ J.

k.

Conversion Constant (1.14E05)

[(yr-pCi-mlY(hr-pCi-i)]

Units constant to convert years to hours, pCi to pCi and liters to ml.

uVW Potable Water Consumption Rate

[i/yr]

Potable water consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109.

Dw Potable Water Dilution Factor dimensionless Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake. From Table F-1, Appendix F.

DFL,,Ij Ingestion Dose Conversion Factor

[mrem/pCi]

Ingestion dose conversion factor for age group a, nuclide i and organ j.

Converts pCi ingested to mrem. Taken from Tables E-1 1 though E-14 of Regulatory Guide 1.109. The values for H-3 and Sr-90 are taken from NUREG 4013 (Reference 107).

A.2.1.2 Fish Ingestion Pathway The site-specific fish ingestion pathway dose factor is calculated by the following expression:

Aal(Fth)J = koU.FBFIDFLaI (A-20)

Where:

A l(Fbh)

Site-Specific Dose Factor for Potable Water

[(mrem/hr)y(VtC/ml)]

Pathway Site-specific fish ingestion dose factor for age group a, nuclide i and organ j.

UF Fish Consumption Rate

[kg/yr]

Fish consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109.

BF1 Bioaccumulation Factor

[(pCikg)/(pCVI)]

Bioaccumulation factor for nuclide i in fresh water fish. Taken from Table C-8 of Appendix C.

All other terms have been previously defined.

ODCM Appendix A Rev 4.doc A-18 02081409165 I

Revision 4 September 2002 Application RETS require determination of cumulative and projected dose contributions from liquid effluents for the current calendar quarter and the current calendar year at least once per 31 days. (see Section 12.3 of each station's RETS and/or Technical Specifications).

For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10.

A.2.2 Liquid Effluent Concentrations Requirement Requirement One method of demonstrating compliance to the requirements of 10CFR20.1301 is to demonstrate that the annual average concentrations of radioactive material released in gaseous and liquid effluents do not exceed the values specified in 10CFR20 Appendix B, Table 2, Column 2. (See 10CFR 20.1302(b)(2).)

However, as noted in Section A.5.1, this mode of 10CFR20.1301 compliance has not been elected.

As a means of assuring that annual concentration limits will not be exceeded, and as a matter of policy assuring that doses by the liquid pathway will be ALARA; RETS provides the following restriction:

'The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402."

This also meets the requirement of Station Technical Specifications and RETS.

Equation According to the footnotes to 10CFR20 Appendix B, Table 2, Column 2, if a radionuclide mix of known composition is released, the concentrations must be such that 1

CL )S1 (A-21) where the summation is over radionuclide i.

C, Radioactivity Concentration in

[PLCi/ml]

Liquid Effluents to the Unrestricted Area Concentration of radionuclide i in liquid released to the unrestricted area.

ECLI Effluent Concentration Limit in Liquid

[pCi/ml]

Effluents Released to the Unrestricted Area The allowable annual average concentration of radionuclide i in liquid effluents released to the unrestricted area. This concentration is specified in 10CFR20 Appendix B, Table 2; Column 2. Concentrations for noble gases are different and are specified in the stations' Technical Specifications/RETS.

10 Multiplier to meet the requirements of Technical Specifications.

If either the identity or concentration of any radionuclide in the mixture is not known, special rules apply.

These are given in the footnotes in 10CFR20 Appendix B, Table 2, Column 2.

ODCM Appendix A Rev 4 doc A-19 0208140916 1

Revision 4 September 2002 Application The RETS and Technical Specifications require a specified sampling and analysis program to assure that liquid radioactivity concentrations at the point of release are maintained within the required limits.

To comply with this provision, each nuclear power station obtains and analyzes samples in accordance with the radioactive liquid waste (or effluent) sampling and analysis program in its RETS. Radioactivity concentrations in tank effluents are determined in accordance with Equation A-22 in the next section.

Comparison with the Effluent Concentration Limit is made using Equation A-21.

A.2.3 Tank Discharges When radioactivity is released to the unrestricted area with liquid discharge from a tank (e.g., a radwaste discharge tank), the concentration of a radionuclide in the effluent is calculated as follows:

C =0 Waste Flow (A-22)

Dilution Flow

(-2 Cl Concentration in Liquid effluent to the unrestricted area.

[gCi/ml]

Concentration of radionuclide i in liquid released to the unrestricted area.

C,'

Concentration in the Discharge Tank

[giCi/ml]

Measured concentration of radionuclide i in the discharge tank.

All other terms have been previously defined.

A.2.4 Tank Overflow Requirement To limit the consequences of tank overflow, the RETS/Technical Specifications may limit the quantity of radioactivity that may be stored in unprotected outdoor tanks. Unprotected tanks are tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. The specific objective is to provide assurance that in the event of an uncontrolled release of a tank's contents, the resulting radioactivity concentrations beyond the unrestricted area boundary, at the nearest potable water supply and at the nearest surface water supply, will be less than the limits of I OCFR20 Appendix B, Table 2; Column 2.

The Technical Specifications and RETS may contain a somewhat similar provision. For most nuclear power stations, specific numerical limits are specified on the number of curies allowed in affected tanks.

Application Table F-I of Appendix F provides information on the limits applicable to affected stations. The limits are as stated for some stations in the station Technical Specifications.

A.2.5 Operability and Use of the Liquid Radwaste Treatment System Requirement The design objectives of 1 OCFR50, Appendix I and RETS/Technical Specifications require that the liquid radwaste treatment system be operable and that appropriate portions be used to reduce releases of radioactivity when projected doses due to the liquid effluent from each reactor unit to restricted area boundaries exceed either of the following (see Section 12.3 of each station's RETS or Technical Specifications);

ODCM Appendix A Rev 4.doc A-20 0208140916 1

Revision 4 September 2002 0.06 mrem to the total body in a 31 day period.

0.2 mrem to any organ in a 31 day period.

Equation Offsite doses due to projected releases of radioactive materials in liquid effluents are calculated using Equation A-17. Projected radionuclide release concentrations are used in place of measured concentrations, C,.

A.2.6 Drinking Water Five nuclear power stations (Braidwood, Dresden, LaSalle, Quad Cities, and Zion) have requirements for calculation of drinking water dose that are related to 40CFR141, the Environmental Protection Agency National Primary Drinking Water Regulations. These are discussed in Section A.6.

A.2.7 Non-routine Liquid Release Pathways Cases in which normally non-radioactive liquid streams (such as the Service Water) are found to contain radioactive material are non-routine will be treated on a case specific basis if and when this occurs. Since each station has sufficient capacity to delay a liquid release for reasonable periods of time, it is expected that planned releases will not take place under these circumstances. Therefore, the liquid release setpoint calculations need not and do not contain provisions for treating multiple simultaneous release pathways.

A.3 DOSE DUE TO CONTAINED SOURCES There are presently two types of contained sources of radioactivity which are of concern in Exelon Nuclear offsite radiological dose assessments. The first source is that due to gamma rays from nitrogen-16 ('6N) carried over to the turbine in BWR (boiling water reactor) steam. The second source is that due to gamma rays associated with radioactive material resident in onsite radwaste storage facilities.

Gamma radiation from these sources contributes to the total body dose.

A.3.1 BWR Skyshine The contained onsite radioactivity source which results in the most significant offsite radiation levels at Exelon Nuclear nuclear power stations is skyshine resulting from '6N decay inside turbines and steam piping at boiling water reactor (BWRs).

The 16N that produces the skyshine effect is formulated through neutron activation of the oxygen atoms (oxygen-16, or 160) in reactor coolant as the coolant passes through the operating reactor core. The 16N travels with the steam produced in the reactor to the steam driven turbine. While the 16N is in transport, it radioactively decays with a half-life of about 7 seconds and produces 6 to 7 MeV gamma rays. Typically, offsite dose points are shielded from a direct view of components containing '6N, but there can be skyshine radiation at offsite locations due to scattering of gamma rays off the mass of air above the steamlines and turbine.

The offsite dose rate due to skyshine has been found to have the following dependencies:

The dose rate decreases as distance from the station increases.

The dose rate increases non-linearly as the power production level increases.

The dose rate increases when hydrogen is added to the reactor coolant, an action taken

)

to improve reactor coolant chemistry characteristics (see Reference 39).

ODCM Appendix A Rev 4 doc A-21 0208140916

Revision 4 September 2002 To calculate offsite dose due to skyshine in a given time period, a BWR must track the following parameters:

The total gross energy Eh produced with hydrogen being added.

The total gross energy E, produced without hydrogen being added.

The turbines at BWR sites are sufficiently close to each other that energy generated by the two units at each site may be summed.

An initial estimate of BWR skyshine dose is calculated per the following equation:

DSky =(K)(E. +MhEh)X{OFk SFk e-0. 7R, }

(A-23) k The summation is over all locations k occupied by a hypothetical maximally exposed member of the public characterized by the parameters specified in Table F-8 of Appendix F of the Dresden, LaSalle, and Quad Cities ODCMs. The parameters in Equation A-23 are defined as follows:

D Dose Due to N-1 6 Skyshine

[mrem]

External direct gamma dose due to BWR N-16 skyshine for the time period of interest.

K Empirical Constant

[mreml(MWe-hr)]

A constant determined by fitting data measured at each station.

E0 Electrical Energy Generated Without Hydrogen Addition

[MWe-hr]

Total gross electrical energy generated without hydrogen addition in the time period of interest.

Eh Electrical Energy Generated with Hydrogen Addition

[MWe-hr]

Total gross electrical energy generated with hydrogen addition in the period of interest.

Mt Multiplication Factor for Hydrogen Addition dimensionless Factor applied to offsite dose rate when skyshine is present. Hydrogen addition increases main steam line radiation levels typically up to a factor of approximately 5 (see Page 8-1 of Reference 39). Mh is station specific and is given in Table F-8, Appendix F of Dresden, LaSalle and Quad Cities ODCMs.

OFk Occupancy Factor dimensionless The fraction of time that the dose recipient spends at location k during the period of interest. See Table F-8, Appendix F of Dresden, LaSalle and Quad Cities ODCMs.

SFk Shielding Factor dimensionless A dimensionless factor that accounts for shielding due to occupancy of structures.

ODCM Appendix A Rev 4.doc A-22 0208140916

Revision 4 September 2002 SFk = 0.7 if there is a structure at location k; SFk = 1.0 otherwise. See Table F-8, Appendix F of Dresden, LaSalle and Quad Cities ODCMs.

0.007 Empirical Constant

[m-]

A constant determined by fitting data measured at the Dresden station (see Reference 45).

Rk Distance

[m]

Distance from the turbine to location k. See Table F-8, Appendix F of Dresden, LaSalle and Quad Cities ODCMs.

A.3.2 Dose from Onsite Radwaste Storage Facilities Low-level radioactive waste may be stored at any, or all Exelon Nuclear nuclear power stations in the following types of storage facilities:

Interim Radwaste Storage Facility (IRSF)

Concrete vaults containing 48 radwaste liners (48-Pack)

Dry Active Waste (DAW) facilities Butler buildings/warehouses Steam generator storage facilities Independent Spent Fuel Storage Installation (ISFSI) facilities The "48-Pack' is a shielded concrete vault which is designed to hold three tiers of radwaste liners in a four by four array. The outer shell of the "48-Pack" is a three-foot thick concrete wall and a two and one-half foot thick concrete cover slab. The vault is placed on a poured concrete slab. The liners may have an average surface dose rate of fifteen (15) rem per hour (or up to 380 rem/hr if a 50.59 evaluation has been completed).

The DAW facility will contain low-level radioactive waste that would result in dose rates less than the 1 OCFR20 requirements.

The dose rates resulting from these radwaste and spent fuel storage facilities will be monitored frequently as they are being utilized, and if necessary, a dose calculation model similar to that of Equation A-23 will be developed and placed in the ODCM.

A.4 Total Dose Limits (IOCFR20 and 40CFR1 90)

The regulatory requirements of IOCFR20 and 40CFR190 each limit total dose to individual members of the public without regard to specific pathways. The only significant exposure pathways for light water reactors included in 10CFR20 and 40CFRI90 not addressed by IOCFR50 Appendix I are the direct radiation pathway and exposure from on-site activity by members of the public. Sections A.1 and A.2 considered organ doses from the gaseous and liquid effluent streams for purposes of compliance with 1 OCFR50 Appendix I. Section A.3 addresses the direct radiation component that must be considered for 10CFR20 and 40CFR190 compliance. The following sections will describe the methodology of assessing direct radiation dose and then the manner in which the various doses are combined to obtain the appropriate "total" for regulatory compliance purposes.

Although annual dose limits in 1 OCFR20 are now expressed in terms of Total Effective Dose Equivalent (TEDE) 40CFR190 limits are still stated as organ dose. The NRC continues to require 10CFR50 Appendix ODCM Appendix A Rev 4 doc A-23 0208140916

Revision 4 September 2002 I and 4OCFR190 doses to be reported in terms of organ dose. Due to the fact that organ dose limits set forth in 40CFR1 90 are substantially lower than those of 1 OCFR20 (25 mremlyr vs 100 mremlyr), the NRC has stated that demonstration of compliance with the dose limits in 40CFRI 90 will be deemed as demonstration of compliance with the dose limits of 10CFR20 for most facilities (Reference 104). In addition to compliance with 40CFR190 it may be necessary for a nuclear power plant to address dose from on-site activity by members of the public.

A.4.1 Extemal Total Body Dose The external total body dose is comprised of the following parts:

1)

Total body dose due to noble gas radionuclides in gaseous effluents (Section A.1.2),

2)

Dose due to N-16 skyshine and other contained sources (Sections A.3.1 and A.3.2) and

3)

Total body dose due to radioactivity deposited on the ground (Section A.1.4.1).

The external total body dose due to radioactivity deposited on the ground is accounted for in the determination of the non-noble gas dose (See Equations A-7 and A-8) and is not considered here.

The total external total body dose, DEx, is given by:

DEx= DT" + DSky + DOSF (A-24)

Du Total External Total Body Dose

[mrem]

Total external total body dose due to irradiation by external sources at the location of interest.

DT1 Noble Gas Total Body Dose

[mrem]

External total body dose due to gamma radiation from noble gas radionuclides released in gaseous effluents at the location of interest.

See Equation A-3.

Duy N-16 Skyshine Total Body Dose

[mrem]

External total body dose due to N-16 skyshine for the period and location of interest. See Equation A-23.

D OF Dose From On-Site Storage Facilities fmrem]

External total body dose due to gamma radiation from on-site storage facilities at the location of interest. See Section A.3.2.

A.4.2 Total Dose The total dose, D', in the unrestricted area to a member of the public due to plant operations is given by:

DTot = DEx + DLiq + DNNG (A-25) where:

DTot Total Dose To Member of Public

[mrem]

Total off-site dose to a member of public due to plant operations.

ODCM Appendix A Rev 4 doc A-24 0208140916

Revision 4 September 2002 DEx Total External Total Body Dose

[mrem]

Total body dose due to external exposure to noble gases, N-16 skyshine and on-site storage facilities.

Duq Liquid Effluent Dose

[mrem]

Dose due to liquid effluents to age group a and organ j. The age group and organ with the highest dose from liquid effluents is used.

DNJNG Non-Noble Gaseous Effluent Dose

[mrem]

Dose due to non-noble gaseous effluents to age group a and organ j.

The age group and organ with the highest dose from non-noble gas effluents is used.

A.5 COMPLIANCE TO TOTAL DOSE LIMITS A.5.1 Total Effective Dose Equivalent Limit - IOCFR2O Compliance Requirement Each station's RETS limits the Total Effective Dose Equivalent (TEDE) to an annual limit of 100 mrem, as required by 1 OCFR20.1301 (a)(1). Demonstration of compliance with the limits of 40CFR1 90 (per Section 4.5.2) will be considered to demonstrate compliance with the 100 mrem/year limit.

A.5.1.1 Dose to a Member of the Public in the Unrestricted Area The NRC has stated that demonstration of compliance with the limits of 40CFR190 or with the design objectives of Appendix I to 1 OCFR50 will be deemed to demonstrate compliance with the limits of 10CFR20.1301(a)(1). Power reactors that comply with Appendix I may also have to demonstrate that they are within the 25 mrem limit of 40CFR190 (See Reference 104).

A.5.1.2. Dose to a Member of the Public in the Restricted Area In August of 1995, a revision to 10CFR20 was implemented that changed the definition of a member of the public. As a result, for each nuclear station, estimated doses were calculated for a member of the public who enters the site boundary, but is not authorized for unescorted access to the protected area of the site and does not enter any radiologically posted areas on the site. Realistic assumptions were made for occupancy times and locations visited while within the site boundary.

These evaluations indicate that the doses estimated for these members of the public are well within the 1 OCFR20 limits. These dose evaluations will be performed annually and if necessary, a model will be developed and included in the ODCM.

Application Evaluation of the 40CFR1 90 dose is used to demonstrate compliance to 1 OCFR20 and satisfy station RETS and Technical Specifications (see Chapter 12).

ODCM Appendix A Rev 4.doc A-25 0208140916 1

Revision 4 September 2002 A.5.2 Total Dose due to the Uranium Fuel Cycle (40CFRI90)

Requirement RETS and 40CFRI90 limit the annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources to the following:

Less than or equal to 25 mrem to the total body.

Less than or equal to 25 mrem to any organ except the thyroid.

Less than or equal to 75 mrem to the thyroid.

Total Dose Components This requirement includes the total dose from operations at the nuclear power station. This includes doses due to radioactive effluents (airborne and liquid) and dose due to direct radiation from non-effluent sources (e.g., sources contained in systems on site). It also includes dose due to plants under consideration, neighboring plants and dose due to other facilities in the uranium fuel cycle.

The operations comprising the uranium fuel cycle are specified in 40CFRI90.02(b). The following are included to the extent that they directly support the production of electrical power for public use utilizing nuclear energy:

Milling of uranium ore.

Chemical conversion of uranium.

Isotopic enrichment of uranium.

Fabrication of uranium fuel.

Generation of electricity by a light-watered-cooled nuclear power plant using uranium fuel.

Reprocessing of spent uranium fuel.

Excluded are:

Mining operations.

Operations at waste disposal sites.

Transportation of any radioactive material in support of these operations.

The re-use of recovered non-uranium special nuclear and by-product materials from the cycle.

When Compliance Assessment is Required Compliance with the 40CFR190 regulations is now required as part of demonstration of compliance to 10CFR20 regulations per 10CFR20.1301(d).

Equation The dose due to the uranium fuel cycle is determined by equation A-25.

A.5.3 Summary of Compliance Methodology The required compliance is given in Tables 2-1, 2-2 and 2-3. In Table 2-1, the dose components are itemized and referenced, and an indication of their regulatory application is noted. A more detailed ODCM Appendix A Rev 4 doc A-26 0208140916

Revision 4 September 2002 l compliance matrix is given in Table 2-3. The locations of dose receivers for each dose component are given in Table 2-2.

Further, Table 2-2 states the location of the receiver and occupancy factors, if applicable. In general, the receiver spends time in locations that result in maximum direct dose exposure and inhales and ingests radioactivity from sites that yield maximum pathway doses. Thus, the dose calculated is a very conservative one compared to the "average" receiver who does not go out of his way to maximize radioactivity uptakes. Finally, the connection between regulations, the ODCM equations and the station RETS and Technical Specifications is given in Table 12-0.

A.6 DOSE DUE TO DRINKING WATER (40CFRI41)

The National Primary Drinking Water Regulations, 40CFR141, contain the requirements of the Environmental Protection Agency applicable to public water systems. Included are limits on radioactivity concentration. Although these regulations are directed at the owners and operators of public water systems, several stations have requirements in their Technical Specifications related to 40CFR141.

A.6.1 40CFR141 Restrictions on Manmade Radionuclides Section 141.16 states the following (not verbatim):

(a)

The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 millirem/year.

(b)

Except for the radionuclides listed in Table A-0, the concentration of man-made radionuclides causing 4 mrem total body or organ dose equivalents shall be calculated on the basis of drinking 2 liter of water per day. (Using the 168 hour0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months data listed in "Maximum Permissible Body Burdens and Maximum Permissible Concentration of Radionuclides in Air or Water for Occupational Exposure, "NBSHandbook 69 as amended August 1963, U.S. Department of Commerce.). If two or more radionuclides are present, the sum of their annual dose equivalents to the total body or any organ shall not exceed 4 millirem/year.

TABLE A-0 AVERAGE ANNUAL CONCENTRATIONS ASSUMED TO PRODUCE A TOTAL BODY OR ORGAN DOSE OF 4 MREMIYR Radionuclide Critical Organ pCi I liter Tritium Total body 20,000 Strontium-90 Bone marrow 8

A.6.2 Application The projection or calculation of dose due to the drinking water pathway is made using Equations A-1 7 and A-19. Projections are made using projected radionuclide releases in place of measured releases A.

Doses calculated using Equations A-1 7 and A-19 may differ from doses determined by the methodology prescribed in 40CFR141.16.

ODCM Appendix A Rev 4.doc A-27 0208140916

Revision 4 September 2002 When required, a nuclear power station prepares a special report on radiological impact at the nearest community water system. This system is taken as the one listed in Table A-3 of this appendix. The report should include the following:

The doses calculated by Equations A-17 and A-19.

A statement identifying the dose calculation methodology (e.g., a reference to this manual).

A statement that the doses calculated by the ODCM methodology are not necessarily the same as doses calculated by the methodology prescribed in 40CFR141.16.

The data used to calculate the doses. This information includes the amounts of radioactivity released and the flow rate and dilution values used (see Table F-1). This information is provided to assist the operator of the community water system in performing its own dose assessment.

ODCM Appendix A Rev 4 doc A-28 0208140916

Revision 4 September 2002 l

Table A-1 COMPLIANCE MATRIX Regulation l Dose to be compared to limit I OCFR50 Gamma air dose and beta air dose due to airborne radioactivity in effluent Appendix I plume.

Total body and skin dose due to airborne radioactivity in effluent plume are reported only if certain gamma and beta air dose criteria are exceeded.

Dose for all organs and all four age groups due to iodine and particulate in effluent plume. Existing pathways are considered.

Dose for all organs and all four age groups due to radioactivity in liquid effluents.

IOCFR20 Adherence determined by compliance with dose limits of 40CFRI90.

40CFR190 Total body dose due to direct radiation, ground and plume exposure from (now, by reference, all sources at a station.

also part of 1 OCFR20 Organ doses to an adult due to all pathways.

RETS/ODCM Instantaneous" noble gas total body and skin dose rates and radioiodine, tritium and particulate inhalation dose rates to a child due to radioactivity in airborne effluents.

"Instantaneous' concentration limits for liquid effluents.

ODCM Appendix A Rev 4.doc A-29 0208140916 1

Revision 4 September 2002 l

Station Braidwood 1 & 2 Byron 1 & 2 Table A-2 Release Point Classifications Release Point Vent Stacks Vent Stacks Release Point Classificationa Vent (Mixed Mode)

Vent (Mixed Mode)

Dresden 1 Dresden 2 & 3 LaSalle 1 & 2 Quad Cities I & 2 Zion 1 &2 Plant Chimney Chemical Cleaning Chimney Reactor Building Ventilation Exhaust Stack Main Station Vent Stack Standby Gas Treatment Stackb Chimney Reactor Building Ventilation Exhaust Stack Vent Stacks Stack (Elevated)

Vent (Mixed Mode)

Stack (Elevated)

Vent (Mixed Mode)

Stack (Elevated)

Vent (Mixed Mode)

Ground Level "The definitions of release point classifications (stack, vent and ground level) are given in Section 4.1.4.

bThe LaSalle standby gas treatment stack is located inside the main station vent stack.

ODCM Appendix A Rev 4 doc A-30 0208140916 1

Revision 4 September 2002 l

Table A-3 Nearest Downstream Community Water Systems Characteristics of Nearest Affected Downstream Community Water SuoolV Exelon Nuclear Facilities Upstream of Station None Station Braidwood Location and Distancea Wilmington, 5 river miles Other Exelon Nuclear Stations Upstream of Water SUDDIV None Byron Dresden LaSalle Quad Cities Zion None Braidwood Braidwood Dresden None None None within 115 river miles

Peoria, 106 river miles

Peoria, 97 river miles E. Moline, 16 river miles Lake County

Intake, 1.4 miles NAb Braidwood LaSalle Braidwood Dresden None None IODCM Bases and Reference Document (Reference 101) Table 0-2 and 0-6 provide the bases of the location and distance data.

bNA = not applicable. For purposes of the calculations in the ODCM, there are no community water supplies affected by liquid effluents from Byron Station. This is based on the absence of community water supplies between the Byron Station liquid discharge to the Rock River and the confluence of the Rock and Mississippi Rivers, 115 miles downstream.

ODCM Appendix A Rev 4.doc A-31 0208140916 1

Revision 4 September 2002 i

Table A-4 40CFRI90 Compliance 40CFRI90 Dose Annual Limit ODCM Dose and Equation Number (mrem)

Total Body 25 Total Body Dose; A-25 evaluated for total body Thyroid 75 Thyroid Dose; A-25 evaluated for thyroid Other Organs 25 Organ Dose; A-25 evaluated for all organs except thyroid Notes:

1.

The evaluation is made considering the following sources:

a.

Radioactivity in contained sources within the station;

b.

Radioactivity in station gaseous and liquid effluents;

c.

Dose contributions from neighboring stations and other facilities in the nuclear fuel cycle.

ODCM Appendix A Rev 4.doc A-32 0208140916

Revision 3 January 2001 APPENDIX B MODELS AND PARAMETERS FOR AIRBORNE and LIQUID EFFLUENT CALCULATIONS TABLE OF CONTENTS PAGE SECTION 1:

Models and Parameters for AIRBORNE Effluent Calculations B.0 INTRODUCTION B-1 B.1 METEOROLOGICAL DATA AND PARAMETERS B-1

1.

Data B-2

2.

Joint Frequency Distribution B-2

1.

Downwind Direction Versus Upwind Direction B-2

2.

Stack JFD B-3

3.

Ground Level JFD B-3

4.

Vent JFDs B-3

3.

Average Wind Speed B-4

1.

Stack Release B-5

2.

Ground Level Release B-5

3.

Vent Release B-5 B.2 GAUSSIAN PLUME MODELS B-6

1.

Mathematical Representation B-6

2.

Sector-Averaged Concentration B-7 B.3 RELATIVE CONCENTRATION FACTOR X/Q B-7

1.

Stack Release B-8

1.

Effective Release Height B-9

1. Plume Rise B-10

2. Terrain Effects B-11

2.

Ground Level Release B-11

3.

Vent Release B-12

4.

Removal Mechanisms B-12

5.

Gamma-r/Q B-13 B.4 RELATIVE DEPOSITION FACTOR D/Q B-14

1.

Stack Release B-15

2.

Ground Level Release B-16

3.

Vent Release B-16 B.5 GAMMA AIR DOSE FACTORS (Si, V;, Gj)

B-17

1.

Stack Release B-17

2.

Ground Level Release B-1 9

3.

Vent Release B-19 ODCM Appendix B Rev 3 doc B-i 0011031240

Revision 3 January 2001 APPENDIX B Table of Contents (Cont'd)

PAGE B.6 GAMMA TOTAL BODY DOSE CONVERSION FACTORS (K, )

B-20 B.7 BETA AIR AND SKIN DOSE FACTORS (N,, L)

B-20 B.8 GROUND PLANE DOSE CONVERSION FACTOR DFGi B-20 B.9 INHALATION DOSE COMMITMENT FACTOR DFAija B-20 B.10 INGESTION DOSE COMMITMENT FACTOR DFlija B-20 B.11 MEASURED RELEASE PARAMETERS B-21 B.12 RADIOLOGICAL DECAY CONSTANTS B-21 B.13 PRODUCTIONIEXPOSURE PARAMETERS B-21 SECTION 2:

Models and Parameters for LIQUID Effluent Calculations:

B.14 INTRODUCTION B-22 B.15 DOSE B-22

1. Drinking Water B-22

2. Aquatic Foods (Fish)

B-22

3. Parameters B-23

1. Flow and Dilution B-23

1. River Model B-23

2. Lake Michigan Model B-23

2. Dose Factors B-23

3. Measured Releases B-23

4. Consumption B-24 B.16 CONCENTRATION IN TANK DISCHARGES B-24 ODCM Appendix B Rev 3 doc B-ii 0011031240

Revision 3 January 2001 l

APPENDIX B LIST OF TABLES NUMBER TITLE PAGE B-0 Noble Gas Nuclide Fraction B-25 B-1 Portion of an Example Joint Frequency Distribution B-26 LIST OF FIGURES NUMBER TITLE PAGE I

B-1 B-2 B-3 B4 Instantaneous View of a Plume A Gaussian Curve Effect of Observation Period on Plume Shape A Gaussian Plume B-27 B-28 B-29 B-30 ODCM Appendix B Rev 3 doc B-iii 0011031240

Revision 3 January 2001 SECTION 1:

MODELS AND PARAMETERS FOR AIRBORNE EFFLUENT CALCULATIONS B.0 INTRODUCTION The equations used for calculation of doses due to radioactive airborne effluents are given in Section A.1 of Appendix A. The equations involve the following types of parameters:

Meteorological Parameters These include XIQ, gamma-XIQ, DIQ and wind speed. Their values are based on historical average atmospheric conditions at a site for a selected multi-year historical period (see Section 4.1.5).

Dose Factors These parameters are used to provide a simple way to calculate doses and dose rates due to gamma and beta radiation. These parameters are independent of meteorological conditions and therefore generic (i.e., not station-specific).

o Measured Release Parameters These are measured values of radioactivity releases and release rates.

Radiological Decay Constants These are used to account for the radioactive decay between the release of radioactivity to the environment and the exposure of persons to it.

ProductionlExposure Parameters These are parameters characterizing agricultural production (e.g., length of growing season, transport times) and human exposure patterns (e.g., exposure period, breathing rate, food consumption rates). These parameters affect the quantities of radioactivity to which persons may be exposed.

This appendix discusses the methodology used to determine values of these parameters. Section B.1 addresses how the historical meteorology of a site is characterized by use of a function called the joint frequency distribution. Section B.1 and Sections 8.3 through B.5 present equations that use the joint frequency distribution to obtain values for site-specific meteorological parameters. These equations involve a mathematical model of a plume known as the Gaussian plume model. This model is developed in Section 8.2. Various generic dose factors are discussed in Sections B.6 through 8.10. The other parameters are discussed in the remaining sections.

B.1 METEOROLOGICAL DATA AND PARAMETERS Predicting where airborne effluent will travel requires information on the following:

Wind speed Wind direction Atmospheric turbulence The greater the atmospheric turbulence, the more an effluent plume will tend to broaden and the more dilute the concentration will be. Atmospheric turbulence is affected by the general condition of the atmosphere (e.g., the vertical temperature distribution) and by local features (e.g., objects that protrude into the wind stream). A commonly used classification scheme for the degree of atmospheric turbulence associated with the general condition of the atmosphere involves seven stability classes:

A Extremely Unstable B

Moderately Unstable C

Slightly Unstable D

Neutral ODCM Appendix B Rev 3 doc B-1 0011031240

Revision 3 January 2001 E

Slightly Stable F

Moderately Stable G

Extremely Stable This classification scheme is based on Reference 5. Table 1. Each class is associated with a particular range of wind direction fluctuations and of vertical temperature gradients in the atmosphere. These are specified in Table C4 of Appendix C.

B.1.1 Data Historical atmospheric conditions at each nuclear power station were recorded by an instrumented meteorological tower that measured wind speed, wind direction, and temperature at various heights.

Hourly average values of wind speed, wind direction, and stability class were determined. The difference in temperature between two heights was used to assign an atmospheric stability class based on the correlation between temperature gradient and stability class in Table CA4 of Appendix C.

In obtaining the data, quality assurance checks and corrections were made. Also, corrections were applied to compensate for the limitations of wind sensors at low speeds. A -alm was said to exist if the wind speed was less than that of the threshold of either the anemometer (wind speed meter) or the wind direction vane. For calm conditions, a wind speed equal to one-half of the higher threshold was assigned.

For each stability class, the wind directions during calm conditions were assumed to be distributed in proportion to the observed wind direction distribution of the lowest non-calm wind speed class.

B.1.2 Joint Frequency Distribution The data for a particular historical period are summarized by developing a joint frequency distribution (JFD). Each such distribution specifies the fraction of time during the historical period that the following jointly occur:

Wind speed within a particular range (wind speed class).

Downwind direction in one of the 16 sectors corresponding to the 16 principal compass directions (N, NNE, etc.).

Atmospheric conditions corresponding to one of the seven atmospheric stability classes discussed in Section B.1. Table B-1 of this appendix displays a portion of an example JFD.

Different JFDs are associated with the different release classifications defined in Section 4.1.4. One JFD is defined for stack releases, and another JFD is defined for ground level releases. Two JFDs are associated with vent (mixed mode) releases, one for the portion of the time the release is treated as elevated and the other for the portion of the time the release is treated as ground level.

B.1.2.1 Downwind Direction Versus Upwind Direction Unless otherwise noted, any reference to wind direction in this document represents downwind direction, i.e., the direction in which the wind is blowing toward. This is because the parameters developed in this document are used to calculate radioactivity concentration and radiation dose downwind of a release point. In contrast, it is conventional for meteorologists to provide JFDs based on upwind direction, the direction from which the wind is blowing. For example, the JFDs presented in the annual operating reports of the nuclear power stations are obtained from a meteorological contractor and the directions specified in the reports are upwind directions. Users of JFDs should always be careful to ascertain whether the directions specified are upwind or downwind.

ODCM Appendix B Rev 3.doc 0011031240

Revision 3 January 2001 B.1.2.2 Stack JFD For a stack release, the JFD is defined as follows:

Zfs(n,O,c)

Joint Frequency Distribution, Stack Release The fraction of hours during a period of observation that all of the following hold:

The average wind speed is within wind speed class n.

The downwind direction is within the sector denoted by 0.

The atmospheric stability class is c.

This function is defined for application to a stack release point (see Section 4.1.4). Its value is based on hourly average wind data obtained at a height representative of the release point height.

The stack JFD is normalized to 1:

1: f,(n,,,c) = 1 (B-I)

The summation is over all wind speed classes n, all compass direction sectors 0, and all stability classes C.

B.1.2.3 Ground Level JFD For a ground level release, the JFD fg(n, 0,c) is defined in the same way as for a stack release except that the wind data are obtained at a height representative of a ground level release point. This height is taken as about 10 meters.

The ground level JFD is normalized to 1:

Z: fg(n,O,c) = I (B-2)

The summation is over all wind speed classes n, all compass direction sectors, and all stability classes c.

B.1.2.4 Vent JFDs In accordance with the approach recommended in Regulatory Guide 1.111 (Reference 7), the plume from a vent release is treated as elevated part of the time and as ground level the rest of the time. Two JFDs are determined:

fvelev(n,O,c) characterizes the plume during the part of the time that it is considered elevated; fvgnd(n,O,c) characterizes the plume during the part of the time that it is considered ground level.

Their definitions are as follows:

fvelev(n,O,c) Joint Frequency Distribution, Elevated Portion of a Vent Release ODCM Appendix B Rev 3 doc B-3 0011031240

Revision 3 January 2001 The fraction of hours during a period of observation that the plume is considered elevated and that all of the following hold:

The average wind speed is within wind speed class n.

The downwind direction is within the sector denoted by 0.

The atmospheric stability class is c.

fvgnd(n,0,c) Joint Frequency Distribution, Ground Level Portion of a Vent Release The fraction of hours during a period of observation that the plume is considered ground level and that all of the following hold:

The average wind speed is within wind speed class n.

The downwind direction is within the sector denoted by 0.

The atmospheric stability class is c.

The value Of fvelev(n, 0,c) is based on hourly average wind data at a height representative of the vent release point. Where the measurement height differed considerably from the release height, wind speed data for the release height was obtained by extrapolation. The value Of fvgnd(n, 0,c) is based on hourly average wind data obtained at a height representative of a ground level release point. This is taken as about 10 meters.

The sum of these two JFDs is normalized to 1:

7{ fv,elev(n' %,c) + fvgnd(n, 0,c) } = I (B-3)

The summation is over all wind speed classes n, all compass direction sectors 0, and all stability classes C.

The prescription of Regulatory Guide 1.111 is used in determining the fraction of time that the plume is considered elevated and the fraction of time that it is considered ground level. The fractions are obtained from the ratio of stack exit velocity WO to hourly average wind speed u at the height of the vent release point as follows:

if Wodu > 5, then the plume is considered elevated for the hour.

-If Wolu < 1, then the plume is considered ground level for the hour.

-if I < WoIu < 5, the plume is considered to be a ground level release for a fraction Gt of the hour and an elevated release for a fraction (1 - Gt) of the hour where Gt is defined as follows:

Gt = 2.58 - 1.58(Wolu) for 1.0 < Wc/u < 1.5 (B-4)

Gt = 0.30 - 0.06(WOIu) for 1.5 < Wo/u < 5.0 (B-5)

B.1.3 Average Wind Speed Using the joint frequency distribution, average wind speeds are obtained for each station. Values are obtained for each downwind direction (N, NNE, etc.) and for various release point classifications (stack, vent, and ground level).

ODCM Appendix B Rev 3.doc B4 0011031240

Revision 3 January 2001 l B.1.3.1 Stack Release For a stack release, the following formula is used:

us(O) = 1{ fs(n, 0,c)un }I/ ( f5(n, 0,c) }

(B-6) where the summations are over wind speed classes n and stability classes c.

u5(O)

Average Wind Speed, Stack Release

[im/sec]

The average wind speed in downwind direction 0 for a stack release.

Un Wind Speed for Class n

[mlsec]

A wind speed representative of wind speed class n. For each wind speed class except the highest, un is the average of the upper and lower limits of the wind speed range for the class. For the highest wind speed class, un is the lower limit of the wind speed range for the class.

The parameter f5 is defined in Section B.1.2.2.

B.1.3.2 Ground Level Release For a ground level release, the following formula is used:

ug(O) = E{ fg(n, 8,c)un }1 Z{ fg(n, O,c) }

(B.7) where the summations are over wind speed classes n and stability classes c.

Ug(O)

Average Wind Speed, Ground Level Release

[mlsec]

The average wind speed in downwind direction 0 for a ground level release.

The parameter fg is defined in Section B.1.2.3.

B.1.3.3 Vent Release For a vent release, the following formula is used:

Uv(0) = v { [fv,elev(n. OMc) + fvgnd(n, 0,c)]un }

(B-8)

I of fvelev(nOc) + fvgnd(nOC) }

where the summations are over wind speed classes n and stability classes c.

uv(e)

Average Wind Speed, Vent

[m/sec]

Release The average wind speed in downwind direction 0 for a vent release.

The parameters fv,elev and fvgnd are defined in Section B.1.2.4.

ODCM Appendix B Rev 3 doc B-5 001 1031240

Revision 3 January 2001 B.2 GAUSSIAN PLUME MODELS As a plume of airborne effluents moves away from an elevated release point, the plume both broadens and meanders. It has been found that the time-averaged distribution of material in an effluent plume can be well represented mathematically by a Gaussian function.

B.2.1 Mathematical Representation In a widely used form of the Gaussian plume model, the distribution of radioactivity in a plume is represented mathematically by the equation below:

x(x,y,z)

[Q/(27n ay czu)]exp(-y 2I2a2y) x {exp[-(z-he) 212a2 z1 + exp[-(z+he)212a2z1)

(B1-9)

X(XY.Z)

Radioactivity Concentration

[pCim/3 l

The concentration of radioactivity at point (x,y,z). The x, y, and z axis are defined as follows:

x Downwind Distance

[m]

Distance from the stack along an axis parallel to the wind direction.

y Crosswind Distance

[ml Distance from the plume centerline along an axis parallel to the crosswind direction.

z Vertical Distance

[ml Distance from the ground (grade level at the stack) along an axis parallel to the vertical direction.

Q Release Rate

[pCi/sec]

Release rate of radioactivity.

cry, FZ Horizontal and Vertical Dispersion Coefficients

[m]

Standard deviations of the Gaussian distributions describing the plume cross-sections in the y and z directions, respectively. The values of cy and crz depend on several parameters:

Downwind distance x.

Because a plume broadens and meanders as it travels away from its release point, the values of cy and '3z increase as x increases.

Atmospheric stability class.

The plume is broadest for extremely unstable atmospheric conditions (Class A) and narrowest for extremely stable conditions (Class G).

Time period of averaging plume concentration.

ODCM Appendix B Rev 34doc B-6 0011031240

Revision 3 January 2001 The values of oy and caz increase as the averaging period increases.

u Average Wind Speed

[m/sec]

The average wind speed. The average speed of travel of the plume in the x direction.

he Effective Release Height

[m]

The effective height of effluent release above grade elevation.

This may be greater than the actual release height (see Section B.3.1.1.1).

The two exponential functions of z in the curly brackets of Equation B-9 represent the emitted and reflected components of the plume. The reflected component (represented by the exponential with (z +

he) in its argument) arises from the assumption that all material in a portion of the plume that touches ground is reflected upward. This assumption is conservative if one is calculating airborne radioactivity concentration.

B.2.2 Sector-Averaged Concentration Sometimes, it is desired to determine the average concentration of radioactivity in a sector due to release at a constant rate over an extended period of time (e.g., a year). For such a case, it is reasonable to assume that the wind blows with equal likelihood toward all directions within the sector. From Equation B-9, the following equation for ground level radioactivity concentration can be derived:

Xsector = 12.032 f Q/(cz u x)]exp(-h 2e/2a22)

(B-10)

Xsector Sector-Averaged Ground Level

[pCi/m 3j Concentration The time-averaged concentration of airborne radioactivity in a sector at ground level at a distance x from the release point.

2.032 A dimensionless constant.

f Sector Fraction The fraction of time that the wind blows into the sector.

Q Release rate of radioactivity.

[pCi/sec]

The other parameter definitions are the same as for Equation B-9.

B.3 RELATIVE CONCENTRATION FACTOR XIQ The relative concentration factor XIQ (called 'chi over Q") provides a simplified method of calculating the radioactivity concentration at a given point in an effluent plume when the release rate is known:

X = Q (X/Q)

(B-1I1)

X Concentration of Radioactivity

[pCi/m3l Concentration of radioactivity at point (x,y,z) in the atmosphere.

ODCM Appendix B Rev 3.doc B-7 0011031240

Revision 3 Januaiy 200 1 Q

Release Rate

[pCi/sec]

Release rate of radioactivity.

XIQ Relative Concentration Factor

[sec/m3]l Relative concentration factor for point (x,y,z). The airborne radioactivity concentration at (x,y,z) per unit release rate.

Expressions for X/Q based on Gaussian plume models can be obtained from the equations for concentration X in Section B.2 simply by dividing both sides of each equation by the release rate Q. For example, from Equation B-10, we obtain the following expression for the sector-averaged X/Q:

(XsectorlQ) = [2.032 fl(az u x)]exp(-h2el2a2 z)

(B-12)

The values of X/Q used in ODCM calculations are both sector-averaged and time-averaged. The time averaging is based on the historical average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is accomplished by use of the joint frequency distribution discussed in Section B.1.2. The formulas used to obtain the time-and sector-averaged X/Q are based on Equation B-12, but vary depending on whether the release is a stack, ground level, or vent release. The three cases are discussed below.

B.3.1 Stack Release For a stack release, the relative concentration factor is designated (x/Q)s. Its value is obtained by the following formula:

(XIQ)s = (2.0321R) i( fs(n,O,c) x [exp (-h2 e12a2z)]I(un ar)}

(B-13)

The summation is over wind speed classes n and atmospheric stability classes c.

(xJQ)S Relative Concentration Factor,

[sec/m3]

Stack Release The time-and sector-averaged relative concentration factor due to a stack release for a point at ground level at distance R in downwind direction 8.

2.032 Constant A dimensionless constant.

R Downwind Distance

[m]

The downwind distance from the release point to the point of interest.

f,(n,O,c)

Joint Frequency Distribution, Stack Release This function is defined in Section 8.1.2.2.

he Effective Release Height

[m]

ODCM Appendax B Rev 3 doc B-8 0011031240

Revision 3 Januaxy 2001 The effective height of an effluent release above grade elevation. For a stack release, he is obtained by correcting the actual height of the release point for plume rise, terrain effects, and downwash as described in Section B.3.1.1, below.

cGZ Standard Vertical Dispersion Coefficient

[m]

A coefficient characterizing vertical plume spread in the Gaussian model for stability class c at distance R (see Table C-5 of Appendix C).

Un Wind Speed

[m/sec]

A wind speed representative of wind speed class n. For each wind speed class except the highest, un is the average of the upper and lower limits of the wind speed range for the class. For the highest wind speed class, un is the lower limit of the wind speed range for the class.

This expression is recommended by the NRC in Regulatory Guide 1.111 (Reference 7) and is based on a model designated there as the "constant mean wind direction model." In this model it is assumed that the mean wind speed, the mean wind direction, and the atmospheric stability class determined at the release point also apply at all points within the region in which airborne concentration is being evaluated.

B.3.1.1 Effective Release Height For a stack release, the effective height of an effluent plume is the height of the release point corrected for plume rise and terrain effects:

If (hs + hpr - ht) < 100 meters, then he = hs + hpr ht (B-14)

If (hs + hpr - ht) > 100 meters, then; he = 100 meters (B-15) he Effective Release Height

[m]

The effective height of an effluent release above grade elevation.

hs Actual Release Height Em]

The actual height of the release above grade elevation.

hpr Plume Rise

[m]

The rise of the plume due to its momentum and buoyancy.

(See Section B.3.1.1.1.)

ht Terrain Correction Parameter

[m]

A parameter to account for the effect of terrain elevation on the effective height of a plume. Taken as zero (see Section B.3.1.1.2).

ODCM Appendix B Rev 3.doc B-9 0011031240

Revision 3 January 2001 B.3.1.1.1 Plume Rise Because nuclear power stations generally have plumes that are not significantly warmer than room temperature, plume rise due to buoyancy is neglected. The formulas used to calculate plume rise due to momentum are given below.

Stability Classes A, B, C, and D For these stability classes (corresponding to unstable and neutral conditions), hpr is taken as the lesser of two quantities:

hpr = Minimum of [(hpr)i, (hpr)2]

(B-16)

(hpr)i = (1.44)(WoIu)2/3(R/d)113(d) - hd (B-17)

(hpr)2 = (3)(Wolu)(d)

(B-18)

WO Stack Exit Velocity

[m/sec]

The effluent stream velocity at the discharge point.

u Wind Speed

[mlsec]

R Downwind Distance

[ml The downwind distance from the release point to the point of interest.

d Internal Stack Diameter

[m]

The internal diameter of the stack from which the effluent is released.

hd Downwash Correction

[m]

A parameter to account for downwash at low exit velocities.

The parameter hd is calculated by the following equations:

hd = (3)(1.5 - WoIu)(d) if Wo.cl5u (B-19) hd = ° if Wo1.Su (B1-20)

Note that (hpr)1 can increase without limit as R increases; thus, the effect of (hpr)2 is to limit calculated plume rise at large distances from the nuclear power station.

Stability Classes E, F, and G For these stability classes (corresponding to stable conditions), hpr is taken as the minimum of four quantities:

hpr

= Minimum of [(hpr)l, (hpr)2. (hpr)3, (hpr)4]

(B-21)

(hpr)3

= (4)(FIS)114 (B-22)

(hpr)4

= (1j5)(FIu)113(S)-116 (B-23)

ODCM Appendx B Rev 3 doc B-1 0 0011031240

Revision 3 January 200 1 F

Momentum Flux Parameter

[m4/sec 2]

A parameter defined as:

F = WO2 (d/2)2 (B-24)

S Stability Parameter

[1/sec2I A parameter defined as follows:

Stability Class S

E 8.70E-4 F

1.75E-3 G

2.45E-3 The quantities (hpr)i and (hpr)2 are as defined by Equations B-17 and B-18.

B.3.1.1.2 Terrain Effects Due to general flatness of the terrain in the vicinity of the stations, the terrain correction parameter ht was taken as zero in all calculations of meteorological dispersion and dose parameters for this Manual.

B.3.2 Ground Level Release For a ground level release, the relative concentration factor is designated (XIQ)g. Its value is obtained by the following formula:

(XJQ)g =

(2.0321R) o{ fg(nO,c)I(unSz) }

(B-25)

The summation is over wind speed classes n and atmospheric stability classes c.

(xIQ)g Relative Concentration Factor, Ground Level Release

[secrm 3

l The time-and sector-averaged relative concentration factor due to a ground level release for a point at ground level at distance R in downwind direction 0.

fg(n,O,c)

Joint Frequency Distribution, Ground Level Release This function is defined in Section B.1.2.3.

SZ Wake-Corrected Vertical Dispersion Coefficient

[M]

The vertical dispersion coefficient corrected for building wake effects. The correction is made as described below.

The remaining parameters are defined in Section B.3.1.

Wake-Corrected Vertical Dispersion Coefficient ODCM Appendix B Rev 3Idoc B-1 I 0011031240

Revision 3 January 2001 The wake-corrected vertical dispersion coefficient SZ in Equation B-25 is taken as the lesser of two quantities:

I Sz (Sz)i (SZ)2

= Minimum of [(Sz)1, (Sz)21

= [a 2z + D2/(27n)]

= (oz)(3 2 )

(B-26)

(B-27)

(B-28)

Sz az D

Wake-Corrected Vertical Dispersion Coefficient

[m]

The vertical dispersion coefficient corrected for building wake effects.

Standard Vertical Dispersion Coefficient

[m]

The coefficient characterizing vertical plume spread in the Gaussian model for stability class c at distance R (see Table C-5 of Appendix C).

Maximum Height of Neighboring Structure

[ml The maximum height of any neighboring structure causing building wake effects (see Table F-2 of Appendix F).

B.3.3 Vent Release For a vent release, the relative concentration factor is designated (X/Q)v. Its value is obtained by the following formula:

(X/Q)v = (2.0321R) 2{ fvelev(nOc)

(B-29) x [exp(-h2e/2a2z)]/(un OG)

+ fvgnd(n-ec)I(unsz)

The summation is over wind speed classes n and atmospheric stability classes c.

(X/Q)v Relative Concentration

[sec/m3 ]

Factor, Vent Release The time and sector averaged relative concentration factor due to a vent release for a point at ground level at distance R in downwind direction 0.

The parameters fvelev(nfOEc) and fvtgnd(nOc) are defined in Section B.1.2.4. The parameter SZ is defined in Section B.3.2. The remaining parameters are defined in Section B.3.1.

B.3.4 Removal Mechanisms In Regulatory Guide 1.1 11, the NRC allows various removal mechanisms to be considered in evaluating the radiological impact of airborne effluents. These include radioactive decay, dry deposition, wet deposition, and deposition over water. For simplicity, these removal mechanisms cited by the NRC are not accounted for in the evaluation or use of XlQ in this manual. This represents a conservative approximation as ignoring removal mechanisms increases the value of XIQ.

I I

lI ODCM Appendix B Rev 3.doc B-12 0011031240

Revision 3 January 2001 B.3.5 Gamma-XQ The noble gas dose factors of Reg. Guide 1.109, Table B-1 are based upon assumption of immersion in a semi-infinite cloud. For ground level and mixed mode releases this tends to overestimate the gamma air dose arising from a plume that is actually finite in nature.

For elevated releases, the Reg. Guide 1.109 noble gas dose factors will underestimate exposure as they consider only immersion and not that portion of exposure arising from sky shine. At distances close in to the point of elevated release, the ground level concentration as predicted by XIQ will be essentially zero.

In such a case, the sky shine component of the exposure becomes significant and must be considered.

The gamma-XIQ provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. The methodology of Reg. Guide 1.109, Section C.2 and Appendix B provides the methodology for calculating finite cloud gamma air dose factors from which the gamma-X/Q values can be derived. Section B.5 addresses the calculation of these dose factors.

The gamma-XIQ is defined such that for a given finite cloud the semi-infinite cloud methodology will yield the same gamma air dose as the finite cloud methodology.

Three gamma-XJQ values are defined: (XIQ)87, (XIQ)V. and (X/Q)9" for stack, vent and ground level releases, respectively. These gamma-x/Q values are calculated as follows:

For stack releases:

(X/Q)Y = I (B-30)

The summation is over all noble gas radionuclides i.

(X/QY, Gamma-y/Q for Stack Releases

[sec/m3]

f, Noble Gas Nuclide Fraction dimensionless Fraction of total noble gas release that is due to radionuclide i. Values for f, are listed in Table B-0.

S.

Stack Release Gamma Air Dose Factor

[(mrad/yr)/(LtCisec)]

Gamma air dose factor for radionuclide i for stack releases as defined in Section B.5.1. Taken from Appendix F. Table 7.

Ml Semi-Infinite Cloud Dose Factor

[(mrad/yr)/(RCi/m 3)]

Dose factor for immersion exposure to a semi-infinite cloud of noble gas.

Taken from Reg. Guide 1.109, Table B-1, Col 4. (Note that the units in Reg. Guide 1.109 must be multiplied by 1E6 to convert pCi to pCi.)

For vent releases:

If(vB (C/Q)v =D£M (B-31)

ODCM Appendix B Rev 3 doc B-13 0011031240

Revision 3 January 2001 The summation is over all noble gas radionuclides i.

(X/Q)t Gamma-yIQ for Vent Releases

[seclm3]

V, Vent Release Gamma Air Dose Factor j(mradlyr)/(ICilsec)]

Gamma air dose factor for radionuclide i for stack releases as defined in Section B.5.3. Taken from Appendix F, Table 7.

All other terms have been previously defined.

For ground level releases:

(XIQ)Y = I f1 DIM I(-2 (B-32)

The summation is over all noble gas radionuclides I.

(X/Q)

Gamma-yIQ for Vent Releases

[seclm3]

GI Ground Level Release Gamma Air Dose Factor

[(mrad/yr)I(I+/-Ci/sec)]

Gamma air dose factor for radionuclide i for ground level releases as defined in Section B.5.2. Taken from Appendix F, Table 7.

All other terms have been previously defined.

The Noble Gas Nuclide Fraction, f, is determined from historical release data and defined as:

EA, (B-33)

The summation is over all noble gas radionuclides i.

Ai Cumulative Radionuclide Release units of activity Cumulative release of noble gas radionuclide i over a period of time.

B.4 RELATIVE DEPOSITION FACTOR DIQ The quantity DIQ (called 'D over Q") is defined to provide the following simple way of calculating the rate of deposition of radioactivity at a given point on the ground when the release rate is known.

d = Q (D/Q)

(B-34)

I d

Q Deposition Rate f(pCi/m 2)/sec]

Rate of deposition of radioactivity at a specified point on the ground.

Release Rate of radioactivity.

[pCi/sec]

ODCM Appendix B Rev 3.doc B-14 0011031240

Revision 3 January 2001 DIQ Relative Deposition Factor 11/m 2]

Relative deposition factor for a specified point on the ground. The deposition rate per unit release rate.

The values of DIQ used in this manual are time-averaged. The time averaging is based on the historical average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is accomplished by use of the joint frequency distribution described in Section B.1.2. The formulas used to obtain DIQ vary depending on whether the release is a stack, ground level, or vent release. The three cases are discussed below.

B.4.1 Stack Release For a stack release, the relative deposition factor is designated (DIQ)s. Its value is obtained by the following formula:

(D/Q)s = [11(2nR116)] l~ff(n,e,c) Dr(c,R,he) }(B-35) l The summation is over wind speed classes n and stability classes c.

(DIQ)s Relative Deposition Factor, Stack Release

[1/r 2]

The time-averaged relative deposition factor due to a stack release for a point at distance R in the direction Q.

2nJl 6 Sector Width

[radians]

The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section B.2.2). Taken as 1/16 of a circle.

R Downwind Distance

[m]

The downwind distance from the release point to the point of interest.

f5(n,O,c)

Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2.

Dr(c,R,he)

Relative Deposition Rate, Stack Release

[m-1J The deposition rate per unit downwind distance [pCV(sec-m)] divided by the source strength [pCi/sec] due to a stack release for stability class c, downwind distance R, and effective release height he.

The value is based on Figures 7 to 9 of Regulatory Guide 1.1 11, which apply, respectively, to release heights of 30, 60, and 100 m. Linear interpolation is used to obtain values at intermediate release heights. If the effective release height is greater than 100 meters, then the data for 100 meters are used.

he Effective Release Height

[ml ODCM Appendix B Rev 3.doc B-15 0011031240

Revision 3 January 2001 The effective height of the release above grade elevation.

See Section B.3.1.1.

B.4.2 Ground Level Release For ground level release, the relative deposition factor is designated (D/Q)g. Its value is obtained by the following formula:

(DIQ)g = [11(2tR/1 6)] D,(R) 2{ f,(n,O,c) }

(B-36)

The summation is over wind speed classes n and stability classes c.

(DIQ)g Relative Deposition Factor,

[1/m2]

Ground Level Release The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction 0.

fg(n,O,c)

Joint Frequency Distribution, Ground Level Release This function is defined in Section B.1.2.3.

Dr(R)

Relative Deposition Rate, Ground Level

[m-1 The deposition rate per unit downwind distance [pCiI(sec-m)] divided by the source strength [pCi/sec] due to a ground level release for downwind distance R. The value is taken from Figure 6 of Regulatory Guide 1.111 and is the same for all atmospheric stability classes.

The remaining parameters are defined in Section B.4.1.

B.4.3 Vent Release For a vent release, the relative deposition factor is designated (DIQ)v. Its value is obtained by the following formula:

(D/Q)v = [1I1(2ntR116)] X [P{ fvelev(nOc) Dr(cRhe) ) + Dr(R) 1{ fvgnd(nO.c)}]

(B-37)

The summation is over wind speed classes n and stability classes c.

(DIQ)v Relative Deposition Factor, Vent Release

[1/m2]

The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction 0.

The parameters fvelev(n,Oc) and fvygnd(nOc) are defined in Section B.1.2.4. The remaining parameters are defined in Sections B.4.1 and B.4.2.

ODCM Appendix B Rev 3.doc B-16 0011031240

Revision 3 l January 2001 B.5 GAMMA AIR DOSE FACTORS (SI, V1, G1)

The gamma air dose factors provide a simple way of calculating doses and dose rates to air due to gamma radiation. For example, using a dose factor DFI, gamma air dose rate may be calculated as follows:

D - 2:Di (B-38)

Di = 2:{QDFj }

(B-39)

The summations are over i radionuclides.

D Gamma Air Dose Rate

[mrad/yr]

The gamma air dose rate due to all radionuclides released.

Gamma Air Dose Rate Due to Radionuclide I

[mrad/yr]

Release Rate of Radionuclide I

[pCi/see)

DF1 Gamma Air Dose Factor for f(mradlyr)/ (pCi/sec)]

Radionuclide i A factor used to calculate gamma air dose or dose rate due to release of radionuclide i. Gamma air dose rate at a particular location per unit release rate.

Three gamma air dose factors are defined: Si, V,, and G1. They are used for stack, vent, and ground level releases, respectively. These three release point classifications are defined in Section 4.1.4. The calculation of the three dose factors is discussed below.

B.5.1 Stack Release For a stack release, the gamma air dose factor Si is obtained by a model similar to that of Equation 6 of Regulatory Guide 1.109 (Reference 6). A sector-averaged Gaussian plume is assumed and the dose factor is evaluated on the basis of historical average atmospheric conditions. The value of SI depends on distance R from the release point and on downwind sector 0.

The following equation is used:

S = [2601(2nRI16)] x 2{f5(n,6,c)[exp(-X1R/36O0uj)] xEk pa(Ek)AK l(helUnpCo zEk)/Un)

(B40)

The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k.

Si Gamma Air Dose Factor, Stack Release

[(mrad/yr)l (pCi/sec)]

The gamma air dose factor at ground level for a stack release for radionuclide i, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period.

ODCM Appendix B Rev 3 doc B-1 7 0011031240

Revision 3 January 2001 260 Conversion factor 1(mrad-radians-m 3 -disintegrations)/(sec-MeV-Ci)]

Reconciles units of Equation B-36.

2i416 Sector Width

[radians]

The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section 8.2.2). Taken as 1/16 of a circle.

f.(n,O,c)

Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2.

A4 Radiological Decay Constant 1hr1]

Radiological Decay Constant for radionuclide i (see Table C-7 of Appendix C).

3600 Conversion Factor

[sec/hr]

The number of seconds per hour. Used to convert wind speed in meters/sec to meters/hr.

Ek Photon Group Energy

[MeV/photon]

An energy representative of photon energy group k. The photons emitted by each radionuclide are grouped into energy groups in order to facilitate analysis. All photons with energy in energy group k are assumed to have energy Ek-Va(Ek)

Air Energy Absorption Coefficient

[m-1]

The linear energy absorption coefficient for air for photon energy group k. The fraction of energy absorbed in air per unit of distance traveled for a beam of photons of energy Ek. Distance is measured in units of linear thickness (meters).

AM Effective Photon Yield

[photons/disintegration]

The effective number of photons emitted with energy in energy group k per decay of nuclide i. On the basis of Section B.1 of Regulatory Guide 1.109 (Reference 6), the parameter An is calculated as follows:

Ak, = [I{A, Em pa(Em)1]/[Ek lJa(Ek)]

(B41)

The summation in the numerator is over the index m.

Am True Photon Yield

[photons per disintegration]

The actual number of photons emitted with energy E, per decay of nuclide i.

ODCM Appendix B Rev 3.doc B-18 0011031240

Revision 3 Januay 2001 Em Photon Energy

[MeV/photon]

The energy of the meh photon within photon energy group k.

Ia(Em)

Air Energy Absorption Coefficient

[m-1]

The linear energy absorption coefficient for air for photon energy Em.

I Function A dimensionless parameter obtained by numerical evaluation of integrals that arise in the plume gamma dose problem. The value of I depends on the arguments (... ) listed in Equation B-40. A specific definition for I is given by Equation F-13 of Regulatory Guide 1.109.

The integrals involved in calculating I arise from conceptually dividing up the radioactive plume into small elements of radioactivity and adding up the doses produced at the point of interest by all of the small elements.

The distribution of radioactivity in the plume is represented by a sector-averaged Gaussian plume model like that discussed in Section B.2.2.

The parameters R, he, ut,, and a. are defined in Section B.3.1.

B.5.2 Ground Level Release The gamma air dose factor GI for a ground level release is defined as follows:

GI Gamma Air Dose Factor, Ground Level Release

[(mrad/yr)I(pCilsec)]

The gamma air dose factor at ground level for a ground level release for radionuclide i, downwind sector 8, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period.

The value of GI is obtained by the same equation as used for a stack release, Equation B-36 of Section B.5.1, with the following modifications:

The joint frequency distribution for a ground level release (fg of Section B.1.2.3) is used in place of the one for a stack release (fQ).

In evaluating the I function, the effective release height h, is taken as zero.

This corresponds to use of a finite plume model.

B.5.3 Vent Release For a vent release, the gamma air dose factor is calculated as follows:

VI = [260/(2nRJ16)] x :(fv...,ev(nO,c)[exp(-4,Rl36OOun)] x AkIEkpa(Ek) l(h.,ufcazEk)ufl.

(B-42) j

+ fV. 9 gnd(nEc)[exp(-IR/3600un)] x AiEkp,(Ek) l(O,un,c,Oz,Ek)Un}

The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k.

ODCM Appendlix B Rev 3.oc B-19 0011031240

Revision 3 January 2001 Vi Gamma Air Dose Factor, Vent Release

[(mrad/yr)/(pCi/sec)]

The gamma air dose factor at ground level for a vent release for radionuclide i, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period.

The parameters fv,.e,,(n,0,c) and fV,9nd(n,O,c) are defined in Section 8.1.2.4. The parameter cr, is defined in Section B.3.2. The remaining parameters are discussed in Section B.5.1.

B.6 Gamma Total Body Dose Conversion Factor (K,)

The gamma total body dose conversion factors (Ki) are used to calculate doses and dose rates due to gamma irradiation of the whole body. The gamma total body dose conversion factors are taken from Reg.

Guide 1.109, Table B-1, Column 5. The gamma total body dose conversion factors in Table B-1 of Reg.

Guide 1.109 are based upon the semi-infinite cloud model.

B.7 BETA AIR AND BETA SKIN DOSE CONVERSION FACTORS (NiL 1)

The beta air (NI) and beta skin (LI) dose conversion factors are used to calculate doses and dose rates due to noble gas beta exposure. The beta air dose conversion factors are taken from Reg, Guide 1.109, Table B-1, Column 2. The beta skin dose conversion factors are taken from Column 5 of that same table.

The values are based on a semi-infinite cloud model.

B.8 GROUND PLANE DOSE CONVERSION FACTOR DFGI The ground plane dose conversion factor DFG, is used to calculate dose due to standing on ground contaminated with radionuclide I (see Equation A-8 of Appendix A). The units of DFG1 are (mremlhr) per l

(pCUM2).

Values are provided (see Table C- 0 of Appendix C) for dose to the whole body. The values are taken from Regulatory Guide 1.109 and are based on a model that assumes a uniformly contaminated ground plane.

B.9 INHALATION DOSE COMMITMENT FACTOR DFAija The inhalation dose commitment factor DFAI,, is used to calculate dose and dose rate to organ j of an individual of age group a due to inhalation of radionuclide i (see Equations A-7 and A-9 of Appendix A).

Values of DFAija for IOCFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFAjj, are mrem per pCi inhaled. Values are provided for seven organs, with the whole body considered as an organ (see Tables E-7, E-8, E-9 and E-10 in Reg. Guide 1.109).

B.10 INGESTION DOSE COMMITMENT FACTOR DFL 1jj The ingestion dose commitment factor DFL1j is used to calculate dose to organ j of an individual of age group a due to ingestion of radionuclide i (see Equations A-7 and Al 0 through A20 of Appendix A).

Values of DFLja for 1 OCFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFLIj, are mrem per pCi ingested. In Tables E-11, E-12, E-13 and E-14 of Reg. Guide 1.109, values are provided for seven organs, with the whole body considered as an organ.

ODCM Appendax B Rev 3.doc B-20 0011031240

Revision 3 January 2001 B.11 MEASURED RELEASE PARAMETERS Input parameters required for calculations of dose or dose rate due to airborne effluents include measured values of radioactivity release (A4, Als and Ag) or release rate (Q1,, Q1,, and Qig) (see Section A.1 of Appendix A). These are obtained per the nuclear power station procedures.

B.12 RADIOLOGICAL DECAY CONSTANTS Values used for these are obtained from the literature and are specified in Table C-7 of Appendix C.

B.13 PRODUCTIONIEXPOSURE PARAMETERS These parameters characterize various aspects of agricultural production and human exposure. Values used for generic (site-independent) parameters are specified in Appendix C.

Values of site-specific parameters are given in Appendix F. Many of the values are based on Reg. Guide 1.109, while others are based on site-specific considerations.

ODCM Appendix B Rev 3 doc B-21 0011031240

Revision 3 January 2001 SECTION 2:

MODELS AND PARAMETERS FOR LIQUID EFFLUENT CALCULATIONS B.14 INTRODUCTION Equations for radiation dose and radioactivity concentration due to liquid effluents are given in Section A.2 of Appendix A. The equations involve the following types of parameters:

Flow and Dilution Parameters.

Dose Factors.

Measured Release Parameters.

Transport/Consumption Parameters.

This section discusses the methodology used to determine these parameters. Section B.15 addresses dose calculations and Section B.16 addresses concentration calculations for tank discharges. For dose calculations, flow and dilution parameters are discussed for two different models; the River Model, which is used for all nuclear power stations except Zion, and the Lake Michigan Model, which is used for Zion.

B.15 DOSE B.15.1 Drinking Water The radiation dose due to consumption of drinking water containing released radioactivity is calculated by Equations A-17, A-18 and A-19 of Appendix A:

D., = F M II A,,"CI (A-17)

P I

F Waste Flow (A-18)

Dilution Flow x Z Atp w=k0 f DFL}

(A-1 9)

The summation is over index i (radionuclides) and p (pathways). The parameters are defined in Section A.2.1 of Appendix A.

This methodology addresses the following considerations:

The duration of the release, At.

The concentration of the activity released, C,.

The dilution that takes place in the environment is represented by the parameters F and Z.

Receptor consumption rate, UaW.

Dilution which occurs from the near field discharge area to potable water intake as represented by Dw.

The dose commitment per unit of ingested radioactivity is DFL,,j.

B.15.2 Aquatic Foods (Fish)

Near the nuclear power stations, the only aquatic food of significance for human consumption is fish. The liquid dose due to consumption of fish containing released radioactivity is calculated by Equations A-17, A-18 and A-20 of Appendix A.

ODCM Appendix B Rev 3.doc B-22 0011031240

Revision 3 January 2001 A&,(F,.h,, = kU:BFIDFL,,I (A-20)

The parameters are defined in Section A.2.1 of Appendix A.

This is similar to the methodolgy used for calculating the dose due to drinking water except for the addition of the bioaccumulation factor, BF1. This factor is the equilibrium ratio of the concentration of radionuclide i in fish (pCi/kg) to its concentration in water (pCiIL). It accounts for the fact that radioactivity ingested by fish can accumulate in their bodies to a higher concentration than in the waters in which the fish live.

B.15.3 Parameters B.15.3.1 Flow and Dilution The values of dilution can differ for potable water and fish. The dilution for potable water will depends on where water is drawn, while that for fish will depends on where the fish are caught. Models used to determine these parameters are discussed below. The values used for each station are summarized in Table F-1 of Appendix F.

B.15.3.1.1 River Model For the purpose of calculating the drinking water dose from liquid effluents discharged into a river, it is assumed that total dilution of the discharge in the river flow occurs prior to consumption. The measure of dilution for the potable water pathway is described by the parameter DW. A value of Dw = 1 represents no dilution.

For the fish consumption pathway, the dilution in the near-field is described by the parameter Z. This is an estimate of the dilution of released radioactivity in the water consumed by fish caught near the station downstream of its discharge. No additional dilution is assumed to occur.

B.15.3.12 Lake Michigan Model Only (Zion) discharges liquid effluents into Lake Michigan. For this nuclear power station, it is assumed that the dilution in the near-field (Z) is dictated by the initial entrainment dilution is a factor of 10. The potable water pathway dilution factor of 6 (DW) is derived from the plume dilution (a factor of 3 over approximately 1 mile) and the current direction frequency (annual average factor of 2).

B.15.3.2 Dose Factors Equations A-17 through A-20 of Appendix A determine dose due to ingested radioactivity using the same ingestion dose factor DFLija as used in the evaluation of airborne radioactivity which is ingested with foods. The units of DFLija are:

(mrem) per (pCi ingested)

For 10CFR50 Appendix I compliance, the data of Tables E-1, E-12, E-13 and E-14 of Reg. Guide 1.109, are used for four age groups and for seven organs, with the whole body considered as an organ.

B.1 5.3.3 Measured Releases Calculations of dose due to liquid effluents require measured values of radioactivity concentration release (Ci) for input. These release values are obtained per the nuclear power station procedures.

ODCM Appendix B Rev 3.doc B-23 001 1031240

Revision 3 January 2001 B.15.3.4 Consumption I

Equations A-1 9 and A-20 of Appendix A involve consumption rates for water and fish (Uap and UF). The l

values used are specified for each nuclear power station in Table F-1 of Appendix F.

B.16 CONCENTRATION IN TANK DISCHARGES The concentration of radioactivity in a release to the unrestricted area due to a tank discharge is calculated by Equation A-22 of Appendix A l

C =C Waste Flow (A-22)

Dilution Flow l

The parameters are defined in Section A.2.3 of Appendix A.

The radioactivity concentration released from the tank (Ct1 at flow rate Fr) is diluted by mixing with the initial dilution stream (with flow rate Fd) to yield a lower concentration (C1) in the combined streams.

ODCM Appendix B Rev 3 doc B-24 0011031240

Revision 3 January 2001 1

Table B-O Noble Gas Nuclide Fractions Nuclide Braidwood' Byron' Dresden" LaSalie' QuadCities' Zion' Ar-41 8.90E-01 8.90E-01 I 46E-02 O.00E+00 1.85E-02 0.00E+00 Kr-83m 0 OOE200 0.OOE+00 O.OOE+OO 4.50E-03 0 00E+00 0 OOE+00 Kr-85 2.49E+01 2.49E+01 3.50E-05 2 60E-05 3.11 E-02 1.OOE+00 Kr-85m 1.80E-01 1.80E-01 3.68E-02 8 OOE-03 2.39E-02 O.OOE+0O Kr-87 4 OOE-02 4 OOE-02 3.71E-02 2 60E-02 3.25E-02 0.00E+00 Kr-88 2.80E-01 2.80E-01 4.47E-02 2.60E-02 3.tOE-02 O.OOE+00 Kr-89 O.OOE+00 O.OOE+00 O.OOE+00 1.70E-01 0.00E+00 0 OOE+00 Kr-90 0 OOE+00 O.OOE+00 O.OOE+00 3 70E-01 0 OOE+00 0.00E+00 Xe-131m 1.40E+00 1.40E+00 O.OOE+00 2.00E-05 1.15E-03 O.OOE+00 Xe-133 7.11 E+01 7.11 E+01 4.88E-02 1.10E-02 6.34E-02 O.OOE+00 Xe-1 33m 5.70E-01 5.70E-01 3.17E-04 3 80E-04 5.00E-05 O.OOE+00 Xe-1 35 5.30E-01 5.30E-01 2.71 E-01 2.90E-02 4.95E-02 O.OOE+00 Xe-I 35m 0.OOE+00 O.OOE+00 1.10E-01 3 40E-02 1.77E-01 O.OOE+00 Xe-1 37 O.OOE+00 O.OOE+00 O.OOE+00 2 OOE-01 0.OOE+00 0.002E+0 Xe-138 4.00E-02 4 OOE-02 4 37E-01 1.20E-01 5.72E-01 0 OOE+00 NoreS:

(1)

(2)

(3)

From Table 10-1.

From 1998 and 1999 Dresden Station Radiological Environmental Operating Reports.

From 1998 and 1999 Quad Cities Station Radiological Environmental Operating Reports.

ODCM Appendix B Rev 3.doc B-25 0011031240

Revision 3 January 2001 Table B-1 Portion of an Example Joint Frequency Distribution summary Table of Percent by Direction and Class Clas N

NNE ME ENE E

ESE SE SSE S

A

.209

.317

.301

.244

.249

.190

.198

.197

.335 a

.190

.187

.178

.15B

.125

.065

.079

.130

.193 c

.269

.226

.252

.218

.190

.113

.152

.189

.302 D

3.298 2.327 2.338 2.684 1.992 1.334 1.365 2.172 3.012 E

1.466 1.198

.988 1.331 1.681 1.226 1.472 2.553 3.528 F

.504

.313

.185

.278

.6es

.648

.803 1.293 1.722 a

.202

.091

.061

.099

.253

.250

.355

.400

.624 Total 6.217 4.663 4.304 10Ot1 6.169 2.330 4.424 6.933 9.626 Sumary Table ot Percent by Direction and Speed Speed N

NNE NE ENE E

ESE SE SSE S

.45

.098

.099

.078

.030

.009

.000

.014

.032

.046 1.05

.308

.154

.125

.137

.121

.093

.090

.127 2.05

.939

.602

.458

.594

.s43

.60G

.598

.605 t.008 3.0s 1.164 1.030

.779

.991 1.463 1.075 1.093 1.473 1.182 4.05 1.179 1.024

.878

.995 1.243

.53t 1.027 1.727 2.110 s.os

.839

.631

.a85

.798

.724

.474

.652 1.254 1.636 6.05

.E12

.467

.496

.589

.417

.313

.413

.803 1.153 8.05

.755

.437

.612

.695

.310

.313

.405

.735 1.319 10.0s

.253

.157

.183

.155

.032

.093

.103

.ta0

.374 13.05

.053

.061

.034

.027

.001

.031

.025

.028

.072 18.00

.016

.001

.004

.000

.001

.002

.000 99.oo

.000

.000 Total 6.217 4.663 4.304 1.011 1.169 3.330 4.424 6.933 9.322 Summary Table of Petcent by Speed and Class Class A

B C

D E

F Speed

.45

.004

.001

.000

.09E

.257

.275

.346 1.05

.01E

.012

.027

.508 1.035 1.080

.780 2.05

.286

.171

.246 3.256 Z.023 3.228 1.419

3. 05

.744

.428

.616 6.258 7.173 3.272

.s85 4.05

.992

.5B1

.781 3.165 6.404 1.902

.460 5.05

.909

.506

.80a 7.302 4.357

.607

.077 6.05

.7t2

.358

.613 6.167 2.938

.164

.013 8.05

.819

.500

.755 7.518 2.734

.081

.011 10.05

.230

.150

.196 2.606

.667

.009

.000 13.05

.075

.022

.055

.785

.161

.001

.000 18.00

.004

.000

.013

.117

.012

.000

.000 99.00

.000

.001

.000

.006 ODCM Appendix B Rev 3 doc B-26 0011031240

Revision 3 January 2001 Figure B-1 Instantaneous View of Plume y

Wind X

This figure represents a snapshot of a projection of a plume on the horizontal plane. As it moves downwind, the plume meanders about the average wind direction and broadens (adapted from Reference 18).

ODCM Appendix B Rev 3 doc B-27 0011031240

Revision 3 January 2001 Figure 1-2 A Gaussian Curve V

a -

1.0 o.9 0.5 0.7 0.1 0.5 0.4 0.:

0.2 0.1 0.0 T

-Sa I-8P L X-vr)

-3

-2

-1 a

1 2

K.*I a

(Adapted from Reference 24 of Chapter 9, Page 61.)

3 ODCM Appendix B Rev 3.doc B-28 001103 1240

Revision 3 January 2001 Figure B-3 Effect of Observation Period on Plume Shape IRL^TawL CO"CLUtNATao This sketch represents the approximate outlines of a smoke plume observed instataneously and averaged over periods of 10 minutes and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . The diagram on the right shows the corresponding cross plume distribution patterns. The plume width increases as the period of observation increases (from Reference 18).

ODCM Appendix B Rev 3 doc B-29 001 1031240

Revision 3 January 2001 Figure B-4 A Gaussian Plume 2

(S.-y. Z)

(z..Yo)

This sketch illsutrates a plume characterized by Equation B-9. The plume is moving downwind in the x direction. Both the horizontal dispersion parameter sz increases as x increases. The reflected component has been omitted in this illustration (adapted from Reference 24).

ODCM Appendix B Rev 3.doc B-30 0011031240

Revision 3 January 2001 APPENDIX C GENERIC DATA TABLE OF CONTENTS PAGE C.1 INTRODUCTION C-1 C.2 10CFR50 DOSE COMMITMENT FACTORS C-1 LIST OF TABLES NUMBER TITLE PAGE C-1 Miscellaneous Dose Assessment Factors C-2

- Environmental Parameters C-2 Miscellaneous Dose Assessment Factors C-3

- Consumption Rate Parameters C-3 Stable Element Transfer Data C-4 C-4 Atmospheric Stability Classes C-6 C-5 Vertical Dispersion Parameters C-7 C-6 Allowable Concentrations of C-8 Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste C-7 Radiological Decay Constants (go) in hrW C-9 C-8 Bioaccumulation Factors B. to be Used in the C-11 Absence of Site-Specific Data C-9 Dose Factors for Noble Gases C-13 C-10 External Dose Factors for Standing on C-14 Contaminated Ground C-1I Sector Code Definitions C-17 ODCM Appendix C Rev 3 doc C-i 0011091215 l

Revision 3 January 2001 APPENDIX C GENERIC DATA C.1 INTRODUCTION This appendix contains generic (common to one or more of the stations) offsite dose calculation parameter factors, or values. Site specific factors are provided in the station annex Appendix F. The factors described in section C.2 are found in the prescribed references and are not repeated in this appendix.

C.2 IOCFR50 DOSE COMMITMENT FACTORS With the exception of H-3, the dose commitment factors for 10CFR50 related calculations are exactly those provided in Regulatory Guide 1.109 (Reference 6). The following table lists the parameters and the corresponding data tables in the RG 1.109:

PATHWAY ADULT TEENAGER CHILD INFANT Inhalation RG 1.109:Table E-7 RG 1.109:Table E-8 RG 1.109:Table E-9 RG 1.109.Table E-10 Ingestion RG 1.109:Table E-11 RG 1.109:Table E-12 RG 1.109:Table E-13 RG 1.109:Table E-14 These tables are contained in Regulatory Guide 1.109 (Reference 6). Each table (E-7 through E-14) provides dose factors for seven organs for each of 73 radionuclides. For radionuclides not found in these tables, dose factors will be derived from ICRP 2 (Reference 50) or NUREG-0172 (Reference 51). The values for H-3 are taken from NUREG-4013 (Reference 107).

00CM Appendix C Rev 3 doc C-1 00111091215 I

Revision 3 January 2001 Table C-1 Miscellaneous Dose Assessment Factors -

Environmental Parameters Parameter Value Comment Equation Basis' fQ 0.76 A-1 0, A-11 A

fL 1.0 A-10, A-11 A

f, 1.0 A-12,A-14 A

1.0 A-1 2, A-14 A

t 9.46E8 sec 30 years A-Z C

t 1.73E5 sec Cow Milk Pathway (48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months )

A-12 A

tf 1.73E6 sec Cow Meat Pathway (480 hours0.00556 days 0.133 hours 7.936508e-4 weeks 1.8264e-4 months )

A-14 A

th 5.18E6 sec 60 days for produce - human consumption A-10 A

t 7.78E6 sec 90 days for produce - animal consumption A-12, A-14 A

tL 8.64E4 sec I day for leafy vegetables A-10 A

OF 50 Kg/da Cow Consumption Rate A-12, A-13, A-14, A-15 B

r 1.0 For lodines A-10, A-12, A-14 A

r 0.2 For Particulates A-10, A-12, A-14 A

YD 0.7 K

_Im A-12, A-14 A

YS 2.0 Kqg/m A-12, A-14 A

Y v

j42.0 K

g/m_

A-10 A

0.0021 hr A-10, A-12, A-14 A

H 8 gm/ma Absolute Atmospheric Humidity A-11, A-13, A-15 D

'Basis key:

A:

Reference 6. Table E-15.

B:

Reference 6, Table E-3.

C:

The parameter tb is taken as the midpoint of plant operating life (based upon an assumed 60 year plant operating lifetime).

D:

Reference 14, Section 5.3.1.3.

ODCM Appendix C Rev 3 doc C-2 0012111034

Revision 3 January 2001 Table C-2 Miscellaneous Dose Assessment Factors -

Consumption Parameters Type Variable Infant Child Teenager Adult Air BR.

1400 3700 8000 8000 (m3lyr)

Milk U.

330 330 400 310 (LUyr)

Produce Uab 0

520 630 520 (Kg/yr)

Leafy UaL 0

26 42 64 Vegetables (Kg/yr)

Meat U0 41 65 110 (Kglyr)

Water Ua VW 330 510 510 730 (L/yr)

Fish UTy 0

6.9 16 21 (Kg.yr)

From Regulatory Guide 1.109, Table E-5.

ODCM Appendix C Rev 3 doc C-3 0011091215 l

Revision 3 January 2001 l Table C-3 Stable Element Transfer Data Ft FM(Cow)

Element Meat (dlkq)

Milk (d/L)

Reference H

1.2E-02 1.OE-02 6

Be 1.5E-03 3.2E-03 Footnote I C

3.1 E-02 1.2E-02 6

F 2.9E-03 1.4E-02 Footnote 2 Na 3.OE-02 4.OE-02 6

Mg 1.5E-03 3.2E-03 Footnote I Al 1.5E-02 1.3E-03 Footnote 3 P

4.6E-02 2.5E-02 6

Cl 2.9E-03 1.4E-02 Footnote 2 Ar NA NA NA K

1.8E-02 7.2E-03 16 Ca 1.6E-03 1.1E-02 16 Sc 2.4E-03 7.5E-06 Footnote 4 T1 3.4E-02 5.OE-06 Footnote 5 V

2.8E-01 1.3E-03 Footnote 6 Cr 2.4E-03 2.2E-03 6

Mn 8.OE-04 2.5E-04 6

Fe 4.OE-02 1.2E-03 6

Co 1.3E-02 1.OE-03 6

Ni 5.3E-02 6.7E-03 6

Cu 8.OE-03 1.4E-02 6

Zn 3.OE-02 3.9E-02 6

Ga 1.5E-02 1.3E-03 Footnote 3 Ge 9.1 E-04 9.9E-05 Footnote 7 As 1.7E-02 5.OE-04 Footnote 8 Se 7.7E-02 1.0E-03 Footnote 9 Br 2.9E-03 2.2E-02 Ff Footnote 2;Fm from Ref. 16 Kr NA NA NA Rb 3.1 E-02 3.OE-02 6

Sr 6.OE-04 8.OE-04 6

Y 4.6E-03 1.OE-05 6

Zr 3.4E-02 5.0E-06 6

Nb 2.8E-01 2.5E-03 6

Mo 8.0E-03 7.5E-03 6

Tc 4.OE-41 2.5E-02 6

Ru 4.0E-01 1.0E-06 6

Rh 1.5E-03 1.0E-02 6

Pd 5.3E-02 6.7E-03 Footnote 10 Cd 3.0E-02 2.OE-02 Footnote 11 In 1.5E-02 1.3E-03 Footnote 3 Sn 9.1 E-04 9.9E-05 Footnote 7 Sb 5.OE-03 2.OE-05 98 Ag 1.7E-02 5.OE-02 6

Te 7.7E-02 1.OE-03 6

1 2.9E-03 6.OE-03 6

Xe NA NA NA Cs 4.OE-03 1.2E-02 6

Ba 3.2E-03 4.OE-04 6

La 2.OE-04 5.OE-06 6

Ce 1.2E-03 1.OE-04 6

Pr 4.7E-03 5.OE-06 6

Nd 3.3E-03 5.OE-06 6

ODCM Appendix C Rev 3 doc C-4 0011091215 1

Revision 3 Januaiy 2001 Table C-3 (Cont'd)

Stable Element Transfer Data Ff FM (Cow)

Element Meat (d/kq)

Milk (d/L)

Reference Pm 2.9E-04 2.OE-05 16 Sm 2.9E-04 2.OE-05 16 Eu 2.9E-04 2.OE-05 16 Gd 2.9E-04 2.OE-05 16 Dy 2.9E-04 2.OE-05 16 Er 2.9E-04 2.OE-05 16 Tm 2.9E-04 2.OE-05 16 Yb 2.9E-04 2.OE-05 16 Lu 2.9E-04 2.OE-05 16 Hf 3.4E-02 5.OE-06 Footnote 5 Ta 2.8E-01 1.3E-03 Fm - Ref.16; F, -Footnote 6 W

1.3E-03 5.OE-04 6

Re 1.OE-01 1.3E-03 FM - Ref.16; F, -Footnote 12 Os 2.2E-01 6.OE-04 Footnote 13 Ir 7.3E-03 5.5E-03 Footnote 14 Pt 5.3E-02 6.7E-03 Footnote 10 Au 1.3E-02 3.2E-02 Footnote 15 Hg 3.0E-02 9.7E-06 FM - Ref.16; F,-Footnote 11 Tn 1.5E-02 1.3E-03 FM - Ref.1 6; Ff -Footnote 3 Pb 9.1E-04 9.9E-05 98 Bi 1.7E-02 5.OE-04 98 Ra 5.5E-04 5.9E-04 98 Th 1.6E-06 5.OE-06 98 U

1.6E-06 1.2E-04 98 Np 2.OE-04 5.OE-06 6

Am 1.6E-06 2.OE-05 98 Notes:

1.

NA It is assumed that noble gases are not deposited on the ground.

2.

Elements listed are those considered for 1 OCFR20 assessment and compliance.

Footnotes:

There are numerous F. and Fu values that were not found in published literature. In these cases, the periodic table was used in conjunction with published values. The periodic table was used based on a general assumption that elements have similar characteristics when in the same column of the periodic table. The values of elements in the same column of the periodic table, excluding atomic numbers 58-71 and 90-103, were averaged then assigned to elements missing values located in the same column of the periodic table. This method was used for all columns where there were missing values except column 3A, where there was no data, hence, the average of column 2B and 4A were used.

1.

Values obtained by averaging Reference 6 values of Ca. Sr, Ba and Ra.

2.

F, value obtained by assigning the Reference 6 value for 1. Fu value obtained by averaging l(Ref. 6) and Br (Ref.1 6).

3.

Fe values obtained by averaging Zn (Ref.6) and Pb (Ref. 98); there were novalues for elements in the same column; an average is taken between values of columns 2B and 4A on the periodic table. Fu values obtained by using the value for Tl from Reference 16.

4.

Values obtained by averaging Reference 6 values of Y and La

5.

Values obtained by assigning the Reference 6 value for Zr.

6.

F, values obtained from Ref. 6 value for Nb. FM values obtained by averaging values for Nb (Ref.6) and Ta (Ref. 16)

7.

Values obtained from the Reference 6 values for Pb.

8.

Values obtained from the Reference 6 values for Bi.

9.

Values obtained from the Reference 6 values for Te.

10.

Values obtained from the Reference 6 values for Ni.

11.

F, values obtained from Ref. 6 values for Zn Fm values obtained by averaging the Reference 6 values for Zn and Hg.

12.

Values obtained by averaging Reference 6 values for Mn, Tc, Nd and Reference 98 value for U.

13.

Values obtained by averaging Reference 6 values from Fe and Ru.

14.

Values obtained by averaging Reference 6 values from Co and Rh.

15.

Values obtained by averaging Reference 6 values from Cu and Ag.

ODCM Appendix C Rev 3 doc C-5 0011091215 1

Revision 3 January 2001 Table C-4 Atmospheric Stability Classes Pasquill Stability aGO Class (degree A

>22.

Description Extremely Unstable Moderately Unstable Slightly Unstable Neutral Slightly Stable Moderately Stable Extremely Stable es)

B 17.5 to 22.5 C

12.5 to 17.5 Temperature Change with Height

( 0C/100 m)

<-1.9

-1.9 to -1.7

-1.7 to -1.5

-1.5 to -0.5

-0.5 to 1.5 1.5 to 4.0

>4.0 D

E 7.5 to 12.5 3.8 to 7.5 F

2.1 to 3.8 G

0 to 2.1 Sao is the standard deviation of horizontal wind direction fluctuation over a period of 15 minutes to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

From Regulatory Guide 1.21, Table 4B.

ODCM Appendix C Rev 3.doc C-6 0011091215 l

Revision 3 January 2001 1

Table C-5 Vertical Dispersion Parameters Section 1 Vertical Dispersion Parameters c, a, (meters) = aRb+c with a, limited to a maximum of 1000 meters R = downwind range (meters)

a. b and c have the values listed below:

Stability Class 100 <R< 1000 b

R > 1000 b

a A

B C

D E

F G

0.113 0.222 0.211 0.086 0.052 0.911 0.725 0.678 0.74 0.74 0.0

-,.7

-1.3

-0.35

-0.21 0.00024 2.094 1.26 6.73 18.05 10.83 0.516 0.305 0.18 0.18

-9.6

-13.0

-34.0

-48.6

-29.2 Basis: Reference 53, except for cases denoted by an asterisk. In these cases, the value of cr is obtained by a polynomial approximation to the data from Reference 53 (see Section 2 of this table). The functions given in Reference 50 are not used because they are discontinuous at 1000 meters.

Section 2 Polynomial Approximation for a,;

cy, (meters) = exp [aO + a1P + a2P2 + a3P3) with a. limited to a maximum of 1000 meters P = log, [R(meters)]

ao, a,, a2 and a3 have the values listed below:

Stability Class A

B B

C Ran1e 100 < R < 1000 100 c R < 1000 R > 1000 R> 1000 Coefficients ao =

-10.50 a1 =

6.879 a2 =

-1.309 a3 =

0.0957 ao =

-0.449 a1 =

0.218 a2 =

0.112 a3 =

-0.00517 ao =

319.148 a1 =

-127.806 a2 =

17.093 a3 =

-0.750 ao =

5.300 a1 =

-1.866 a2 =

0.3509 a3 =

-0.01514 ODCM Appendix C Rev 3 doc C-7 0011091215 l

Revision 3 Januaiy 2001 l Table C-6 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste Allowable Concentration (pCi/mL)9 Dresden LaSalle Braidwood Quad Cities Nuclide Byron Zion Kr 85m 2E-4 2E-4 Kr 85 2E-4 5E-4 Kr 87 2E-4 4E-5 Kr 88 2E-4 9E-5 Ar 41 2E-4 7E-5 Xe 131m 2E-4 7E-4 Xe 133m 2E-4 5E-4 Xe 133 2E-4 6E-4 Xe 135m 2E-4 2E-4 Xe 135 2E-4 2E-4 "Computed from Equation 17 of ICRP Publication 2 (Reference 47) adjusted for infinite cloud submersion in water, and R = 0.01 rem/week, pw = 1.0 gm/cm3, and P, /Pt = 1.0.

ODCM Appendix C Rev 3 doc C-8 001 10912t5 l

Revision 3 January 2001 Table C-7 Radiological Decay Constants At ) in sec' I

Isotope Lambda Isotope Lambda

-sotope Lambda H-3 1.79E-09 As-73 1.OOE-07 Tc-1 04 6.42E-04 Be-7 1.50E-07 As-74 4.50E-07 Ru-97 2.77E-06 C-14 3.83E-12 As-76 7.31E-06 Ru-103 2.04E-07 F-18 1.05E-04 As-77 4.97E-06 Ru-1 05 4.33E-05 Na-22 8.44E-09 Se-73 2.69E-05 Ru-106 2.18E-08 Na-24 1.28E-05 Se-75 6.69E-08 Rh-106 2.31E-02 Mg-27 1.22E-03 Br-77 3.36E-06 Pd-I 09 1.43E-05 Mg-28 9.19E-06 Br-80 6.61 E-04 Cd-109 1.73E-08 Al-26 3.06E-14 Br-82 5 44E-06 In-ill 2.83E-06 Al-28 5.14E-03 Br-83 8.06E-05 In-1 15M 4.42E-05 P-32 5.61E-07 Br-84 3.61E-04 In-1 16 2.13E-04 CI-38 3.11 E-04 Br-85 4.03E-03 Sn-113 6.97E-08 Ar-41 1.05E-04 Kr-79 5.50E-06 Sn-117M, 5.89E-07 K-40 1.72E-17 Kr-81 1.05E-13 Sn-119M 2.74E-08 K-42 1.56E-05 Kr-83M 1.05E-04 Sb-117 6.89E-05 K-43 8.53E-06 Kr-85M 4.31 E-05 Sb-122 2.97E-06 Ca-47 1.77E-06 Kr-85 2.05E-09 Sb-124 1.33E-07 Sc-4 4.89E-05 Kr-87 1.51 E-04 Sb-125 7.94E-09 Sc-46M 3.69E-02 Kr-88 6.78E-05 Sb-126 6.47E-07 Sc-46 9.56E-08 Kr-90 2.14E-03 Ag-108M 1.73E-10 Sc-47 2.34E-06 Rb-84 2.44E-07 Ag-108 4.86E-03 Ti-44 4.64E-10 Rb-86 4.31 E-07 Aq-11 A

M 3.22E-08 V-48 5.03E-07 Rb-87 4.64E-19 Ag-Ill 1.08E-06 Cr-51 2.89E-07 Rb-88 6.47E-04 Te-121M 5.22E-08 Mn-52M 5.39E-04 Rb-89 7.47E-04 Te-121 4.78E-07 Mn-52 1.43E-06 Sr-85 1.24E-07 Te-123M 6.69E-08 Mn-54 2.56E-08 Sr-87M 6.86E-05 Te-125M 1.38E-07 Mn-56 7.47E-05 Sr-89 1.59E-07 Te-125 O.OOE+00 Fe-52 2.33E-05 i

Sr-90 7.69E-10 Te-127M 7.36E-08 Fe-55 8.14E-09 Sr-91 2.03E-05 Te-127 2.06E-05 Fe-59 1.80E-07 Sr-92 7.11E-05 Te-129M 2.39E-07 Co-57 2.97E-08 Y-86 1.31E-05 Te-129 1.66E-04 Co-58 1.13E-07 Y-87 2.40E-06 Te-131M 6.42E-06 Co-60 4.17E-09 Y-88 7.53E-08 Te-131 4.61E-04 Ni-63 2.19E-10 Y-90 3.00E-06 Te-132 2.46E-06 Ni-65 7.64E-05 Y-91M 2.32E-04 Te-134 2.76E-04 Cu-64 1.52E-05 Y-91 1.37E-07 1-123 1.47E-05 Cu-67 1.30E-07 Y-92 5.44E-05 1-124 1.92E-06 Cu-68 2.31E-02 Y-93 1.91E-05 1-125 1.33E-07 Zn-65 3.28E-08 Zr-95 1.25E-07 1-130 1.56E-05 Zn-69M 1.40E-05 Zr-97 1.14E-05 1-131 9.97E-07 Zn-69 2.07E-04 Nb-94 1.08E-12 1-132 8.36E-05 Ga-66 2.05E-05 Nb-95 2.22E-06

_1-133 9.25E-06 Ga-67 2.46E-06 Nb-97M 1.15E-02 1-134 2.19E-04 Ga-68 1.69E-04 Nb-97 1.60E-04 1-135 2.92E-05 Ga-72 1.36E-05 Mo-99 2.92E-06 Xe-127 2.20E-07 Ge-77 1.70E-05 Tc-99M 3.19E-05 Xe-129M 9.03E-07 As-72 7.42E-06 I Tc-101 8.11 E-04 Xe-131 M 6.78E-07 ODCM Appendix C Rev 3.doc c-9 0012111034 1

Revision 3 January 2001 1

Table C-7 (Cont'd)

Radiological Decay Constants (Xi) in sec 1 I

Isotope Lambda isotope Lambda Xe-133M 3.67E-06 Yb-1 75 1.91 E-06 Xe-133 1.53E-06 Lu-177 i.19E-06 Xe-135M 7.50E-04 Hf-181 1.89E-07 Xe-135 2.11 E-05 Ta-182 7.OOE-08 Xe-137 3.O0E-03 Ta-183 1.61 E-06 Xe-138 8.17E-04 W-187 8.08E-06 Cs-129 6.OOE-06 Re-188 1.13E-05 Cs-132 1.24E-06 Os-191 5.22E-07 Cs-134 1.07E-08 Ir-194 1.01E-05 Cs-136 6 08E-07 Pt-195M 1.99E-06 Cs-137 7.28E-10 Pt-197 1.05E-05 Cs-1 38 3.58E-04 Au-1 95M 2.26E-02 Cs-139 1.23E-03 Au-195 4.39E-08 Ba-131 6.81 E-07 Au-198 2.97E-06 Ba-133M 4.94E-06 Au-199 2.56E-06 Ba-1 33 2.09E-09 Hg-197 8.08E-06 Ba-135M 6.69E-06 Hg-203 1.72E-07 Ba-1 37M 4.53E-03 TI-201 2.64E-06 Ba-137 O.OOE+00 TI-206 2.75E-03 Ba-139 1.39E-04 TI-208 3.78E-03 Ba-140 6.28E Pb-203 3.69E-06 Ba-141 6.31 E-04 Pb-210 9.86E-10 Ba-142 1.08E-03 Pb-212 1.81E-05 La-140 4.78E-06 Pb-214 4.31E-04 La-142 1.21 E-04 Bi-206 1.29E-06 Ce-139 5.83E-08 Bi-207 6.58E-10 Ce-141 2.47E-07 Bi-214 5.81E-04 Ce-143 5.83E-06 Ra-226 1.37E-11 Ce-144 2.83E-08 Th-232 1.56E-18 Pr-142 1.01E-05 U-238 4.92E-18 Pr-143 5.92E-07 Np-239 3.42E-06 Pr-144 6.67E-04 Am-241 5.08E-1 I Nd-147 7.31 E-07 Nd-149 1.11 E-04 Pm-145 i.24E-09 Pm-148M 1.94E-07 Pm-148 1.49E-06 Pm-149 3.64E-06 Sm-153 4.11E-06 Eu-152 1.62E-09 Eu-154 2.50E-09 Eu-1 55 4.42E-09 Gd-153 3.33E-08 Dy-1 57 2.39E-05 Er-169 8.53E-07 Er-171 2.56E-05 Tm-170 6.25E-08 Yb-169 2.51 E-07 (A1) =Radiological Decay Constant

= 0.693rTr T-. Radiological Half-Life in hours (from Reference 70).

Except for Cu-68, Tc-1 04, Ba-1 37, Ta-1 83, TL-206, Bi-206 which are from References 100.

ODCM Appendix C Rev 3.doc C-10 0012111034 1

Revision 3 January 2001 Table C-8 Bioaccumulation Factors (BFj) to be Used in the Absence of Site-Specific Data BF, for Freshwater Fish Element (pCi/kg per pCUL)

Reference H

9.OE-01 6

Be 2.8E+01 Footnote 2 C

4.6E+03 6

F 2.2E+02 Footnote 16 Na 1.OE+02 6

Mg 2.8E+01 Footnote 2 Al 2.2E+03 Footnote 13 P

1.0E+05 6

Cl 2.2E+02 Footnote 16 Ar NA NA K

1.0E+03 Footnote 1 Ca 2.8E+01 Footnote 2 Sc 2.5E+01 Footnote 3 Ti 3.3E+O0 Footnote 4 V

3.0E+04 Footnote 5 Cr 2.0E+02 6

Mn 4.0E+02 6

Fe 1.0E+02 6

Co 5.OE+01 6

Ni 1.0E+02 6

Cu 5.OE+01 6

Zn 2.OE+03 6

Ga 2.2E+03 Footnote 13 Ge 2.4E+03 Footnote 12 As 3.3E+04 Footnote 14 Se 4.OE+02 Footnote 15 Br 4.2E+02 6

Kr NA NA Rb 2.OE+03 6

Sr 3.OE+01 6

Y 2.5E+01 6

Zr 3.3E+00 6

Nb 3.OE+04 6

Mo 1.OE+01 6

Tc 1.5E+01 6

Ru 1.OE+01 6

Rh 1.OE+01 6

Pd 1.OE+02 Footnote 9 Cd 2.OE+03 Footnote 11 In 2.2E+03 Footnote 13 Sn 2.4E+03 Footnote 12 Sb 1.0E+00 98 Ag 2.3E+00 56 Te 4.OE+02 6

1 1.5E+01 6

Xe NA NA Cs 2.OE+03 6

Ba 4.OE+00 6

La 2.5E+01 6

Ce 1.0E+00 6

Pr 2.5E+01 6

Nd 2.5E+01 6

Pm 3.OE+01 98 Sm 3 OE+01 Footnote 3 ODCM Appendix C Rev 3.doc C-11 0011091215 l

Revision 3 January 2001 Table C-8 (Cont'd)

Bioaccumulation Factors (BFi) to be Used in the Absence of Site-Specific Data I

Element Eu Gd Dy Er Tm Yb Lu Hf Ta W

Re Os Ir Pt Au Hg T1 Pb Bi Ra Th U

Np Am BF1 for Freshwater Fish (pCi/kq per pCi[L) 1.OE+02 2.6E+01 2.2E+03 3.3E+04 4.OE+02 2.2E+02 2.5E+01 3.3E+00 3.OE+04 1.2E+03 2.1 E+02 5.5E+01 3.OE+01 1.OE+02 2.6E+01 2.OE+03 2.2E+03 3.OE+02 2.OE+01 5.OE+01 3.OE+01 1.OE+01 1.OE+01 3.OE+01 I

Reference Footnote 3 Footnote 3 Footnote 3 Footnote 3 Footnote 3 Footnote 3 Footnote 3 Footnote 4 Footnote 5 6

Footnote 6 Footnote 7 Footnote 8 Footnote 9 Footnote 10 Footnote 11 Footnote 13 98 98 98 98 98 6

98 Footnotes:

NA = It is assumed that noble gases are not accumulated.

In Reference 6, see Table A-1.

A number of bioaccumulation factors could not be found in literature. In this case, the penodic table was used in conjunction with published element values. This method was used for periodic table columns except where there were no values for column 3A so the average of columns 2B and 4A was assigned.

1.

Value is the average of Reference 6 values in literature for H. Na. Rb and Cs.

2.

Value is the average of Ref. 6 values in literature for Sr. Ba and Ref. 98 values for Ra.

3.

Value is the same as the Reference 6 value used for Y.

4.

Value is the same as the Reference 6 value used for Zr.

5 Value is the same as the Reference 6 value used for Nb.

6.

Value is the average of Reference 6 values in literature for Mn and Tc.

7.

Value is the average of Reference 6 values in literature for Fe and Ru.

8.

Value is the average of Reference 6 values in literature for Co and Rh.

9 Value is the same as the Reference 6 value used for Ni.

10.

Value is the average of Reference 6 values in literature for Cu and Reference 56 value for Ag.

11.

Value used Is the same as the Reference 6 value used for Zn.

12.

Value is the average of Reference 6 value in literature for C and Reference 98 value for Pb.

13.

Value is the average of columns 2B and 4A. where column 2B is the 'Reference 6 value for Zn' and column 4A is the average of 'Reference 6 value for C and Reference 98 value for Pb'.

14.

Value is the average of Ref. 6 value found in literature for P and the Ref. 98 values for Si and Sb.

15.

Value is the same as the Reference 6 value used for Te.

16.

Value is the average of Reference 6 values found in literature for Br and 1.

ODCM Appendix C Rev 3.doc C-12 0011091215 1

Revision 3 January 2001 1 Table C-9 Dose Factors for Noble Gases Beta Skin Gamr Dose Factor Dose I Beta Air Dose Factor N,

(mraqdtvr npr tiCilm 3 I na Air Factor Gamma Total Body Dose Factor K,

(mrem/vr per uCi/m3)

LI M.

(mremlvr ner ui/ilm 3) (mrad/vr nr i Cri/m 3 )

Nuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-1 33m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 l _ _ _.

c, w_.

2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.01 E+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.11 E+02 1.86E+03 1.22E+04 4.13E+03 2.69E+03 1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04 1.56E+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.51 E+03 9.21 E+03 9.30E+03 7.56E-02 1.17E+03 1.61E+01 5.92E+03 1.47E+04 1.66E+04 1.56E+04 9.15E+01 2.51 E+02 2.94E+02 3.12E+03 1.81 E+03 1.42E+03 8.83E+03 8.84E+03 Source: Table B-1 of Reference 6.

ODCM Appendx C Rev 3.doc G-13 0011091215

Revision 3 January 2001 Table C-10 External Dose Factors for Standing on Contaminated Ground DFG1, (mremlhr per pCi/ M2)

Whole Body Element Dose Factor Reference Element Dose Factor Reference H-3 0 OOE+OO 6

Be-7 5.95E-10 99 C-14 0.WOE+00 6

F-18 1.19E-0B 99 Na-22 2.42E-08 99 Na-24 2.50E-08 6

Mg-27 1.14E-08 99 Mg-28 1A8E-08 99 AJ-26 2.95E-08 99 Al-28 2.OOE-08 99 P-32 0.OOE1+W 6

C-38 1.70E-08 99 Ar-41 1.39E-08 99 K-40 2.22E-09 99 K-42 4.64E-09 99 K-43 1.1 9E-08 99 Ca-47 1.14E-08 99 Sc-44 2.50E-08 99 Sc-46m 1.21E-09 99 Sc-46 2.24E-08 99 Sc-47 1 46E-09 99

-"44 1.95E09 99 V.48 3.21 E-08 99 Cr-51 2.20E-1 0 6

Mn-52m 2.79E-08 99 Mn-52 3.80E-08 99 Mn-54 5.80E-09 6

Mn-56 1.1OE-08 6

Fe-52 9.12E-09 99 Fe-55 0 OOE+0O 6

Fe-59 8.0OE-09 6

Co-57 1.65E-09 99 Co-58 7.OOE-09 6

Co-60 1.70E-08 6

Ni-63 0 OOE+00 6

Ni-65 3.70E-09 6

Cu-64 1.50E-09 6

Cu-67 1.52E-09 99 Cu-68 8 60E-09' Zn-65 4.OOE-09 6

Zn-69m 5.06E-09 99 Zn-69 O.OOE+OO 6

Ga-66 2.70E-08 99 Ga-67 1.89E-09 99 Ga-68 1.24E-08 99 Ga-72 3.OOE-08 99 Ge-77 1.34E-08 99 As-72 2.23E-08 99 As-73 1.16E-10 99 As-74 9.41E-09 99 As-76 6 46E.09 99 As-77 1.79E-10 99 Se-73 i.38E-08 99 Se-75 4.98E-09 99 Br-77 3 84E-09 99 Br-80 2.01E-09 99 Br-82 3 OOE-08 99 Br-83 6 40E-1 1 6

Br-84 1.20E-08 6

Br-85 0.OOE+0O 6

Kr-79 3 07E-09 99 Kr-81

.59E-1 0 99 Kr-83m 1.42E-1 1 99 Kr-85m 2.24E-09 99 Kr-85 1.35E-10 99 Kr-87 1.03E-08 99 Kr-88 2.07E-08 99 Kr-90 1.56E-08 99 Rb-84 1.07E-08 99 Rb-86 6.30E-1 0 6

Rb-87 0.OOE+OO 99 Rb-88 3.50E-09 6

Rb-89 1.5OE-08 6

Sr-85 6.1 6E-09 99 Sr-87m 3.92E-09 99 Sr-89 5 60E-13 6

Sr-90 1.84E-11 99 Sr-91 7.10E-09 6

Sr-92 9.0OE-09 6

Y-86 4.OOE-08 99 Y-87 5.53E-09 99 Y-88 2.88E-08 99 Y-90 2.20E-12 6

Y-91m 3.80E-09 6

Y-91 2.40E-11 6

Y-92 1.60E-09 6

Y-93 5.70E-10 6

Zr-95 5.OOE-09 6

Zr-97 5.50E-09 6

Nb-94 1.84E-08 99 Nb-95 5.10E-09 6

Nb-97m 8 57E-09 99 Nb-97 8 48E-09 99 Mo-99 1.90E-09 6

Tc-99m 9.60E-10 6

Tc-101 2.70E-09 6

Tc-104 1.83E-08' Ru-97 2.99E-09 99 Ru-103 3.60E-09 6

Ru-105 4.50E-09 6

Ru/Rh-106 5.76E-093

6. 99 Pc-109 3.80E-10 99 Cc-109 1.12E-10 99 In-111 5.11E-09 99 In-I 15m 2.01 E-09 99 In-116 O.OOE+002 Sn-113 1.15E-09 99 Sn-17m 1.96E-08 99 Sn-119m 7.05E-11 99 Sb-117 0 OOE+002 Sb-122 2.71E-O9' Sb-124 1.16E-08' Sb-125 4.56E-09 99 Sb-126 7.13E-10 99 Ag-108m 1.92E-08 99 Ag-108 1.14E-09 99 Ag-110m 1.80E-08 6

Ag-111 6.75E-10 99 Te-121m 2.65E-09 99 Te-121 6.75E-09 99 Te-123m 1.88E-09 99 Te-125m 3.50E-1 6

Te-125 O.OOE+002 Te-127m 1.102-12 6

Te-127 1.OOE-11 6

Te-1 29m 7.70E-10 6

Te-129 7.1OE-10 6

Te-131m 8.40E-09 6

ODCM Appendix C Rev 3 doc C-14 0011091215 1

Revision 3 l January 2001 Table C-10 (cont.)

External Dose Factors for Standing on Contaminated Ground DFG, (rmremlhr per pCi/ mi2)

Whole Body Element Dose Factor Reference Element Dose Factor Reference Te-131 2.20E-09 6

Te-1-132 3.40E-095 6

Te-134 1.05E-08 99 1-123 2.12E-09 99 1-124 t.23E-08 99 1-125 2 89E-10 99 1-130 1.40E-08 6

1-131 2.80E-09 6

1-133 3 70E-09 6

1-134 t.60E-08 6

1-135 1.20E-08 6

Xe-127 3 44E-09 99 Xe-129m 5.57E-10 99 Xe-131m 2.13E-10 99 Xe-133m 4 81E-10 99 Xe-133 5.91E-10 99 Xe-t35m 5 23E-09 99 Xe-135 3.36E-09 99 Xe-I 37 4 26E-09 99 Xe-138 t.30E-08 99 Cs-129 3 39E-09 99 Cs-132 8.40E-09 99 Cs-134 1.20E-08 6

Cs-136 1.50E-08 6

Cs-1371Ba-137m 1.14E-08' 6,99 Cs-138 2.10E-08 6

Cs-139 5 15E-09 99 Ba-131 5.74E-09 99 Ba-133m 8.1OE-tO 99 Ba-133 4.85E-09 99 Ba-135m 7.26E-1O 99 Ba-137m 7.17E-09 99 Ba-137 0 OOE+002 Ba-139 2.40E-09 6

Ba-La-140 t 71E-086 6

Ba-141 4.30E-09 6

Ba-142 7.90E-09 6

La-142 1.50E-08 6

Ce-139 2.04E-09 99 Ce-141 5.50E-10 6

Ce-143 2.20E-09 6

Ce-Pr-t44 5.20E-107 6

Pr-142 1.84E-09 99 Pr-143 0 OOE+00 6

Nc-147 1.OOE-09 6

Nc-149 5.32E-09 99 Pm-145 3 38E-10 99 Pm-148m 2.35E-08 99 Prn-148 7.22E-09 99 Pm-149 5.32E-10 99 Sm-153 8 95E-10 99 Eu-152 1.30E-08 99 Eu-154 1.4tE-08 99 Eu-155 827E-10 99 Gc-153 I 46E-09 99 Dy-157 4.39E-09 99 Er-169 612E-14 99 Er-171 5.11E-09 99 Tm-170 3 41E-10 99 Yb-169 4.12E-09 99 Yb-175 4 94E-10 99 Lu-177 4.60E-10 99 Hf-i 81 6 67E-09 99 Ta-182 1A2E-08 99 Ta-183 2.93E-09' W-187 3.1OE-09 6

Re-188 1.89E-09 99 Os-191 9.83E-10 99 Ir-194 2.31 E-09 99 Pt-1 95m 9.79E-10 99 Pt-I 97 3 57E-10 99 Au-195m 2.54E-09 99 Au-195 1.14E-09 99 Au-198 5.19E-09 99 Au-199 I.t8E-09 99 Hg-197 9.33E-10 99 Hg-203 2.89E-09 99 TI-201 1.24E-09 99 T1-206 0 DOE+OC9 T1-208 3.58E-OB 99 Pb-203 3.88E-09 99 Pb-21 0 3.57E-1 1 99 Pt-2112 1.91E-09 99 Pb-214 3.18E-09 99 B6-206 3.74E-08 99 Bi-207 1.77E-08 99 Bi-214 1.71E-08 99 Ra-226 8.78E-t1 99 Th-232 8 14E-12 99 U-238 7.98E-12 99 Np-239 9.50E-10 6

Am-241 3A8E-10 99 1

Valued derived by comparing the percentage and MeV of the nucdide's gammas and then comparing to Cesium-1 37, as a value was not available in the literature.

2 0.0 due to low yield and short half life. A value was not available in the literature.

3 Value is the sum of Ru-106 (1.50E-9) and Rh-t06 (4.26E-9). The Rh-106 value is from Reference 99 and the Ru-106 value is from Reference 6.

4 Value is the sum of Cs-137 (4.20E-9) and Ba-137m (7.i7E-9) The values are from references 6 and 99, respectively.

ODCM Appendix C Rev 3 doc C-15 0011091215 1

Revision 3 January 2001 l

5 Value is the sum of Te-132 (1.70E-9) and 1-132 (1.70E-9).

6 Value is the sum of Ba-140 (2.1OE-9) and La-140 (1.50E-8) from reference 6. In Reference 6, see Table E-6.

7 Value is the sum of Ce-144 (3.20E-10) and Pr-144 (2.OQE-10) from reference 6.

Note-Dose assessments for 10CFR20 and 40CFR19O compliance are made for an adult only.

I Dose assessments for 10CFRS0 Appendix are made using dose factors of Regulatory Guide 1.109 (Reference 6) for an age groups.

ODCM Appendix C Rev 3 doc C-16 0011091215

Revision 3 January 2001 Table C-11 Sector Code Definitions Angle Sector Sector from North Code Direction (Degrees)

A N

348.75 c 0 < 11.25 B

NNE 11.25 c 0 < 33.75 C

NE 33.75 < 0 < 56.25 D

ENE 56.25 < 0 < 78.75 E

E 78.75 < 0 < 101.25 F

ESE 101.25 < 0_ 123.75 G

SE 123.75 < 0 < 146.25 H

SSE 146.25 < 0 < 168.75 J

S 168.75 < 0 < 191.25 K

SSW 191.25 < 0 < 213.75 L

SW 213.75 < 0 < 236.25 M

WSW 236.25 < 0 < 258.75 N

W 258.75 < 8 < 281.25 p

WNW 281.25 < 0 < 303.75 Q

NW 303.75 < 0 < 326.25 R

NNW 326.25 < 0 < 348.75 ODCM Appendix C Rev 3 doc C-17 0011091215 l

ML031250493

Text

1.0 INTRODUCTION

2.0 INTRODUCTION

3.0 INTRODUCTION

4.0 INTRODUCTION

5.0 INTRODUCTION

1.0 INTRODUCTION

2.0 INTRODUCTION

3.0 INTRODUCTION

4.0 INTRODUCTION

5.0 INTRODUCTION

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