Text

2008 Annual Radioactive Effluent Release Report
	ML091280610
Person / Time
Site:	McGuire, Mcguire
Issue date:	04/28/2009
From:	Brandi Hamilton; Duke Energy Carolinas, Duke Energy Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML091280610 (70)
	v • d • e

BRUCE H HAMILTON P6Energy Duke' Vice President McGuire Nuclear Station Duke Energy Corporation MG01VP / 12700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy.com April 28, 2009 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC McGuire Nuclear Station Docket Nos. 50-369 and 50-370 2008 Annual Radioactive Effluent Release Report Pursuant to the requirements of Technical Specification 5.6.3 and Section 16.11-17 of the McGuire Selected Licensee Commitments (SLC) Manual, attached is the Annual Radioactive Effluent Release Report. Also included in this report is the 2009 Offsite Dose Calculation Manual. There were no changes to Process Control Program (PCP) Manual in 2008.

The following Attachments form the contents of the report:

Attachment 1 Radioactive Effluent Releases and Supplemental Information Attachment 2 Solid Waste Disposal Report Attachment 3 Unplanned Offsite Releases Attachment 4 Fuel Cycle Calculation Attachment 5 Inoperable Monitoring Equipment Attachment 6 Groundwater Protection Initiative Questions concerning this report should be directed to Kay Crane, McGuire Regulatory Compliance at (704) 875-4306.

Bruce H. Hamilton A-Dcr~

www. duke-energy. com

NRC Document Control Desk April 28, 2009 Page 2 cc: Mr. Jon Thompson NRC Project Manager Office of Nuclear Reactor Regulation Mail Stop 8-H4A Washington, D.C. 20555 Mr. L. A. Reyes, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth Street - Suite 23T85 Atlanta, GA 30323 Division of Radiation Protection State of North Carolina 3825 Barrett Drive Raleigh, N.C. 27609-7221 Mr. Joe Brady Senior Resident Inspector McGuire Nuclear Station INPO Records Center 700 Galleria Place, Suite 100 Atlanta, GA 30339-5957

U. S. Nuclear Regulatory Commission April 28, 2009 Page 3 bxc: RGC File Master File ECO50-ELL

Attachment 1 Radioactive Effluent Releases and Supplemental Information

McGUIRE NUCLEAR STATION EFFLUENT RELEASE DATA (January I, 2008 through December 31, 2008)

This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.

j TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Gases 1,. Total Release Ci 6.56E-01 5.68E-01 6.32E-01 3.79E-01 2.24E+00

2. Avg. Release Rate pCi/sec 8.35E-02 7.23E-02 7.96E-02 4.77E-02 7.07E-02 B. Iodine-131

1. Total Release Ci 2.23E-06 0.OOE+00 3.06E-06 0.OOE+00 5.29E-06

2. Avg. Release Rate ACi/sec 2.84E-07 0.00E+00 3.85E-07 0.OOE+00 1. 67E-07 C. Particulates Half Life >= 8 days

1. Total Release Ci 1.09E-05 1.60E-05 .2.83E-05 1.15E-05 6.66E-05

2. Avg. Release Rate ACi/sec 1.38E-06 2.03E-06 3.56E-06 1.45E-06 2.11E-06 D. Tritium

1. Total Release Ci 4.31E+01 5.14E+01 5.09E+01 8.10E+01 2.26E+02

2. Avg. Release Rate ,sCi/sec 5.48E+00 6.54E+00 6.40E+00 1.02E+01 7.16E+00 E. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE-i00 0.OOE+00 0.OOE+00

2. Avg. Release Rate pCi/sec 0.OOE+00 0.00E+00 0.00E+00 0.OOEi-00 0.OOE+00 I

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases

- No Nuclide Activities ** ........

2. lodines

- No Nuclide Activities **........

3. Particulates Half Life >= 8 days

- No Nuclide Activities **

4. Tritium

- No Nuclide Activities **

5. Gross Alpha Radioactivity

- No Nuclide Activities **

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS EFFLUENTS - ELEVATED RELEASES- BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases

- No Nuclide Activities **

........ ........ .....o . .° ........

2. lodines

- No Nuclide Activities **........

3. Particulates Half Life >= 8 days

- No Nuclide Activities **

4. Tritium

- No Nuclide Activities **

5. Gross Alpha Radioactivity

- No Nuclide Activities **

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR I QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases XE-133 Ci 0. 00E+00 0.OOE+00 0. 00E+00, 1.85E-04 1.85E-04 Totals for Period... Ci 0.OOE+00 0. 00E+00 0.OOE+00 1.85E-04 1.85E-04

2. lodines 1-131 Ci 2.23E-06 0.00E+00 3.06E-06 0.OOE+00 5.29E-06 1-133 Ci 0.OOE+00 0.OOE+00 6.93E-05 0.OOE+00 6.93E-05 Totals for Period... Ci 2.23E-06 0.OOE+00 7.23E-05 0.OOE+00 7.46E-05

3. Particulates Half Life >= 8 days BE-7 Ci 0.00E+00 0. 00E+00 0. OOE+00 3.56E-06 3.56E-06 CO-58 Ci 1.09E-05 1. 60E-05 2.83E-05 7.95E-06 6.30E-05 Totals for Period... Ci 1.09E-05 1.60E-05 2.83E-05 1.15E-05 6.66E-05

4. Tritium H-3 Ci 4.12E+01 5.12E+01 5.04E+01 7.63E+01 2.19E+02 Totals for Period... Ci 4.12E+01 5.12E+01 5.04E+01 7.63E+01 2. 19E+02

5. Gross Alpha Radioactivity

- No Nuclide Activities **

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases AR-41 Ci 5.73E-01 5.58E-01 6.11E-01 3 64E-01 2.l1E+00 C-1I Ci 2.48E-05 0.OOE+00 0.OOE+00 O.00E+00 2.48E-05 KR-85 Ci 6.51E-02 0.OOE+00' 8.43E-03 6.41E-03 7.99E-02 KR-85M Ci 2.25E-05 O.OOE+00 0.OOE+00 0.OOE+00 2.25E-05 KR-87 Ci 7.87E-06 0.OOE+00 0.OOE+00 0.OOE+00 7.87E-06 KR-88 Ci 5.22E-05 0.OOE+00 0.OOE+00 0.OOE+00 5.22E-05 XE-133 Ci 1.51E-02 9.65E-03 1.13E-02 8.33E-03 4.44E-02 XE-133M Ci 7.87E-05 0.OOE+00 0.OOE+00 0.OOE+00 7.87E-05 XE-135 Ci 3.19E-03 5.86E-05 1.54E-03 0.OOE+00 4.79E-03 Totals for Period... Ci 6.56E-01 5.68E-01 6.32E-01 3.79E-01 2.24E+00

2. Iodines

- No Nuclide Activities **........ ........ ...... .. ...... ........

3.. Particulates Half Life >= 8 days

- No Nuclide Activities **........ ........ ........ ........ ........

4. Tritium H-3 Ci 1.85E+00 2.24E-01 4.30E-01 4.71E+00 7.21E+00 Totals for Period... Ci 1.85E+00 2.24E-01 4.30E-01 4.71E+00 7.21E+00

5. Gross Alpha Radioactivity

- No Nuclide Activities **

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 2.11E-02 2.38E-02 4.07E-02 2.93E-02 1.15E-01

2. Average Diluted Concentration

a. Continuous Releases pCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

b. Batch Releases pCi/ml 2.93E-11 2.51E-.ll 4.14E-11 3.50E-11 3.29E-11 B. Tritium

1. Total Release Ci 4.36E+02 2.88E+,02 5.96E+,02 3.09E+02 1.63E+03

2. Average Diluted Concentration

a. Continuous Releases ACi/ml 4.11E-07 4.07E-08 3.72E-08 2.55E-08 8.99E-08

b. Batch Releases ACi/ml 5.96E-07 3.03E-07 6.05E-67 3.69E-07 4.65E-07 C. Dissolved and Entrained Gases

1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

2. Average Diluted Concentration

a. Continuous Releases pCi/ml 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00

b. Batch Releases ACi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 D. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

2. Average Diluted Concentration

a. Continuous Releases ACi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

b. Batch Releases ACi/ml 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 E. Volume of Liquid Waste

1. Continuous Releases liters 2.35E+08 7.17E+07 7.74E+07 8.57E+07 4.70E+08

2. Batch Releases liters 1.46E+06 8.73E+05 2.17E+06 9.37E+05 5.44E+06 F. Volume of Dilution Water

1. Continuous Releases liters 1.28E+10 2.09E+10 2.12E+1-0 3.16E+10 8.65E+10

2. Batch Releases liters 7.22E+ll 9.49E+ll 9.83E+11 8.36E+ll 3.49E+12

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID EFFLUENTS - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products

- No Nuclide Activities **

2. Tritium H-3 Ci 5.36E+00 8.55E-01 7.92E-01 8.07E-01 7.82E+00 Totals for Period... Ci 5.36E+00 8.55E-01 7.92E-01 8.07E-01 7.82E+00

3. Dissolved and Entrained Gases

- No Nuclide Activities **

4. Gross Alpha Radioactivity

- No Nuclide Activities ** ........ ........ ........ ........ ........

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09ý LIQUID EFFLUENTS - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2008 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products AG-108M Ci 0.00E+00 2.86E-05 4.30E-05 1.08E-05 8.23E-05 AG- IIOM Ci 4.39E-06 2.93E-05 4 .12E-05 2.19E-05 9. 68E-05 BE-7 Ci 1.68E-05 0.OOE+00 8 .22E-05 3.43E-04 4.42E-04 CO-57 Ci 2.25E-06 7.82E-07 6.30E-06 0. OOE+00 9.33E-06 CO-58 Ci 1.91E-03 3.18E-03 7. 74E-03, 7.72E-03 2.06E-02 CO- 60 Ci 9.14E-04 2.31E-03 4.29E-03 8.77E-04 8.39E-03 CR-51 Ci 1.28E-03 1.74E-03 1. 62E-03 2.39E-03 7.04E-03 CS-134 Ci 4.66E-04 3.83E-04 7 .81E-04 3.81E-04 2. O1E-03 CS-137 Ci 1.75E-03 1.55E-03 3 .18E-03 1.74E-03 8.22E-03 FE-59 Ci 7.67E-05 2.86E-04 2. 91E-05 1.49E-04 5.42E-04 MN- 54 Ci 5.81E-05 1.71E-04 4.45E-04 8.91E-05 7.64E-04 NA-24 Ci 0.00E+00 3.63E-06 0. 00E+00 0. OOE+00 3. 63E-06 NB-95 Ci 9.99E-06 6.84E-05 2. 09E-04 1.56E-04 4.43E-04 NB-97 Ci 2.72E-06 1.75E-05 2.60E-05 1. 84E-05 6.46E-05 SB-122 Ci 1.14E-05 1.73E-05 4 68E-06 5.93E-06 3.93E-05 SB-124 Ci 0.00E+00 3.35E-04 4 63E-04 4.87E-04 1.28E-03 SB-125 Ci 1.46E-02 1.36E-02 2. 17E-02 1.48E-02 6.48E-02 SR-92 Ci 0.00E+00 0.00E+00 0. 00E+00 8.70E-07 8.70E-07 ZN-65 Ci 0.00E+00 0.OOE+00 4-26E-06 0. OOE+00 4.26E-06 ZR-95 Ci 2.02E-06 3.45E-05 1.04E-04 5.17E-05 1.92E-04 ZR-97 Ci 0.00E+00 0. 00E+00 0 OOE+00 1.19E-06 1.19E-06 Totals for Period... Ci 2.11E-02 2.38E-02 4.07E-02 2.93E-02 1.15E-01

2. Tritium 9-3 Ci 4.31E+02 2. 87E+02 5. 95E+02 3. 09E+02 1. 62E+03 Totals for Period... Ci 4.31E+02 2. 87E+02 5.95E+02 3. 09E+02 1.62E+03

3. Dissolved and Entrained Gases

- No Nuclide Activities **

4. Gross Alpha Radioactivity

- No Nuclide Activities **

McGUIRE NUCLEAR STATION SUPPLEMENTAL INFORMATION

McGUIRE NUCLEAR STATION 2008 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS - PER UNIT A. NOBLE GASES - AIR DOSE B. LIQUID EFFLUENTS - DOSE

1. CALENDAR QUARTER - GAM4A DOSE = 5 MRAD 1. CALENDAR QUARTER - TOTAL BODY DOSE = 1.5 MREM

2. CALENDAR QUARTER - BETA DOSE = 10 MRAD 2. CALENDAR QUARTER - ORGAN DOSE = 5 MREM

3. CALENDAR YEAR - GAMMA DOSE = 10 MRAD 3. CALENDAR YEAR - TOTAL BODY DOSE = 3 MREM

4. CALENDAR YEAR - BETA DOSE = 20 MRAD 4. CALENDAR YEAR - ORGAN DOSE = 10 MREM C. GASEOUS EFFLUENTS - IODINE - 131 AND 133, TRITIUM, PARTICULATES W/T 1/2 > 8 DAYS - ORGAN DOSE

1. CALENDAR QUARTER = 7.5 MREM

2. CALENDAR YEAR = 15 MREM II. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS A. GASEOUS EFFLUENTS - INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL B. LIQUID EFFLUENTS - INFORMATION FOUND IN 10CFR20, APPENDIX B, TABLE 2, COLUMN 2 III. AVERAGE ENERGY - NOT APPLICABLE IV. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY ANALYSES OF SPECIFIC RADIONUCLIDES IN SELECTED OR COMPOSITED SAMPLES AS DESCRIBED IN THE SELECTED LICENSEE COMMITMENTS ARE USED TO DETERMINE THE RADIONUCLIDE COMPOSITION OF THE EFFLUENT. SUPPLEMENTAL REPORT, PAGE 2, PROVIDES A

SUMMARY

DESCRIPTION OF THE METHOD USED FOR ESTIMATING OVERALL ERRORS ASSOCIATED WITH' RADIOACTIVITY MEASUREMENTS.

V. BATCH RELEASES A. LIQUID EFFLUENT

i. 2.41E+02 TOTAL NUMBER OF BATCH RELEASES

2. 2. 06E+04 TOTAL TIME (MIN.) FOR BATCH RELEASES.

3. 3. 13E+03 MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.

4. 8 54E+01 AVERAGE TIME (MIN.) FOR A BATCH RELEASE.

5. 5. 00E+00 MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

6. 1. 75E+06 AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B. GASEOUS EFFLUENT

1. 4.40E+01 TOTAL NUMBER OF BATCH RELEASES.

2. 1.04E+06 TOTAL TIME (MIN.) FOR BATCH RELEASES.

3. 4.47E+04 MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.

4. 2.36E+04 AVERAGE TIME (MIN.) FOR A BATCH RELEASE.

5. 1.OOE+00 MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

VI. ABNORMAL RELEASES A. LIQUID

1. NUMBER OF RELEASES = 2

2. TOTAL ACTIVITY RELEASED (CURIES) = 1.77E-02 (Tritium) (see attachment for additional information)

B. GASEOUS

1. NUMBER OF RELEASES = 1

2. TOTAL ACTIVITY RELEASED (CURIES) = 3.15E-3 (Noble Gas) (see attachment for additional information) 7-

SUPPLEMENTAL REPORT PAGE 2 McGUIRE NUCLEAR STATION The estimated percentage of error for both Liquid and Gaseous effluent release data at McGuire Nuclear Station has been determined to be + 25.2%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:

(1) Flow rate determining devices = 4 20%

(2) Counting error - +15%

(3) Sample preparation error = +-3%

McGUIRE NUCLEAR STATION Assessment of Radiation Dose from Radioactive Effluents and all Uranium Fuel Cycle Sources to Members of the Public (January 1, 2008 through December 31, 2008)

This attachment includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, as well as the total dose for the calendar year. This attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 8 km of McGuire for the calendar year of this report to show conformance with .40 CFR 190. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ist Quarter 2008 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 1 2008 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose TEEN THYROID 5.12E-02 1.50E+01 3.41E-01 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Inhalation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.99E+01 NOBLE GAS DOSE LIMIT ANALYSIS===-....................... Quarter 1 2008 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q1 - Maximum Gamma Air Dose 1.29E-02 1.00E+01 1.29E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.97E+01 Q1 - Maximum Beta Air Dose 4.90E-03 2.00E+01 2.45E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.26E+01 KR-85 6.25E+00

.1'~

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2008 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 2 2008 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose TEEN LUNG 6.11E-02 1.50E+01 4.07E-01 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Inhalation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS========================= Quarter 2 2008 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose 1.25E-02 1.00E+01 1.25E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE

.Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage, AR-41 9.99E+01.

Q2 - Maximum Beta Air Dose 4.44E-03 ý2.OOE+01 2.22E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.94E+01 2

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2008 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 3 2008 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose TEEN THYROID 6.06E-02 1.50E+01 4.04E-01 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Inhalation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.96E+01 NOBLE GAS DOSE LIMIT ANALYSIS===---------------------- Quarter 3 2008 Dose Limit % of Period-Limit (mrad) (mrad) Limit

,Q3 - Maximum Gamma Air Dose 1.37E-02 1.OOE+01 1.37E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5%.or greater to total)

Nuclide Percentage AR-41 9.99E+01 Q3 - Maximum Beta Air Dose 4.91E-03 2.OOE+01 2.46E-02 Maximum Beta Air Dose Receptor-Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.84E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4th Quarter 2008 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 4 2008 Critical. Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose TEEN LUNG 9.62E-02 1.50E+01 6.41E-01 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Inhalation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS=====....... =============== Quarter 4 2008 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Gamma Air Dose 8.18E-03 1.00E+01 8.18E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.99E+01 Q4 - Maximum Beta Air Dose 2.94E-03 2.06E+01 1.47E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.82E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2008

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Annual 2008 =====

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Yr'J- Maximum Organ Dose TEEN THYROID 2.69E-01 3.OOE+01 8.97E-01 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Inhalation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.99E+01

==,'NOBLE GAS DOSE LIMIT ANALYSIS====================.-=-=== Annual 2008 Dose Limit % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Gamma Air Dose 4.73E-02 2.OOE+01 2.37E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.99E+01 Yr - Maximum Beta Air Dose 1.72E-02 4.OOE+01 4.30E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.70E+01

J EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 1 Bt Quarter 2008 BATCH LIQUID RELEASES Quarter 1 2008 .... =

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q1 - Maximum Organ Dose CHILD LIVER 7.66E-02 1.00E+01 7.66E-01 Q1 - Total Body Dose CHILD 6.46E-02 3.OOE+00 2.15E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 8.12E+01 CS-137 1.41E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.63E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 1 2008 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q1 - Maximum Organ Dose CHILD LIVER 4.29E-02 1.OOE+01 4.29E-01 Q1 - Total Body Dose CHILD 4.29E-02 3.OOE+00 1.43E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1.& 2 2 nd Quarter 2008 BATCH LIQUID RELEASES------------ Quarter 2 2008 ======

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit.

Q2 - Maximum Organ Dose CHILD LIVER 4.12E-02 1.00E+01 4.12E-01 Q2 - Total Body Dose CHILD 3.32E-02 3.00E+00 1.lIE+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.67E+01 CS-137 1.77E+01 CS-134 5.36E+00 Total Body Critical Pathway: Potable Water

,Major Isotopic Contributors (5% or greater to total)

Nudlide Percentage H-3 9.51E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 2 2008 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 4.25E-03 1.00E+01 4.25E-02 Q2 - Total Body Dose CHILD 4.25E-03 3.OOE+00 1.42E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or g reater to total)

Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 i.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2008 BATCH LIQUID RELEASES Quarter 3 2008 .....

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 8.30E-02 l.OOE+01 8.30E-01 Q3 - Total Body Dose CHILD. 6.71E-02 3.OOE+00 2.24E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.70E+01 CS-137 1.76E+01 CS-134 5.30E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.51E+01,'

CONTINUOUS LIQUID RELEASES (WC)........................ Quarter 3 2008 Critical Critical Dose Limit Max % of

.. Period-Limit Age Organ (mrem) (mrem) Limit Q3- Maximum Organ Dose CHILD LIVER 3.93ED03 1.OOE+01 3.93E-02 Q3 - Total Body Dose CHILD 3.93E-03 3.OOE+00 1.31E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or g reater to total)

Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4 th Quarter 2008 BATCH LIQUID RELEASES-----------------==--===---====== Quarter 4 2008 ======

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 5.09E-02 1.OOE+01 5.09E-01 Q4 - Total Body Dose CHILD 4.10E-02 3.OOE+00 1.37E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide 'Percentage H-3 7.65E+01 CS-137 1.84E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.51E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 4 2008 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q4 - Maximum Organ Dose CHILD LIVER 2.69E-03 1.OOE+01 2.69E-02 Q4 - Total Body Dose CHILD 2.69E-03 3.OOE+00 8.95E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/08 TO 1/1/09 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2008 BATCH LIQUID RELEASES =====----===-===---=---=--=-=-==-Annual 2008 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 2.50E-01 2.OOE+01 1.25E+00 Yr - Total Body Dose CHILD 2.04E-01 6.OOE+00 3.41E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.79E+01 CS-137 1.69E+01 CS-134 5.07E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.54E+01 CONTINUOUS LIQUID RELEASES (WC) Annual 2008 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 3.77E-02 2.OOE+01 1.89E-01 Yr - Total Body Dose CHILD 3.77E-02 6.00E+00 6.29E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02

Attachment 2 Solid Waste Disposal Report

REPORT PERIOD McGUIRE NUCLEAR STATION JANUARY - DECEMBER 2008 SOLID RADIOACTIVE WASTE SHIPPED TO DISPOSAL FACILITIES TYPES OF WASTES SHIPPED Number of Number of Container Disposal Volume Waste Total Waste from Liquid Systems Shipments Containers Type ft 3 m3 Class Curies (A) dewatered powdex resin (brokered) none (B) dewatered powdex resin none (C) dewatered bead resin (brokered) none (D) dewatered bead resin none (E) dewatered radwaste system resin none (F) dewatered primary bead resin 1 1 HIC 27.49 0.78 B 1.17E+02 (G) dewatered mechanical filter media none (H) dewatered mechanical filter media (brokered) 3 24 HIC 42.78 1.21 C 3.44E+01 (I) solidified waste none Dry Solid Waste (A) dry active waste (compacted) none dry active waste (non-compacted) none dry active waste (brokered/compacted) dry active waste (brokered/non-compacted) 25 81 DBP 4537.01 128.48 A/U 1.840E+00 (B) sealed sources/smoke detectors none (C) sealed sources none (D) irradiated components none Totals 29 106 4607.28 130.47 1.532E+02 2/11/2009

MCGUIRE NUCLEAR SITE

SUMMARY

OF MAJOR RADIONUCLIDE COMPOSITION 2008 Type of waste NLuclide % Abundance

1. Waste from liquid systems:

A. Dewatered Powdex Resin (brokered) No shipments in 2008 B. Dewatered Powdex Resin No shipments in 2008 C. Dewatered Bead Resin (brokered) No shipments in 2008 D. Dewatered Bead Resin No shipments in 2008 E. Dewatered Radwaste System Resin (brokered) No shipments in 2008 F. Dewatered Primary Bead Resin (brokered) 2008-017 Nuclide %Abundance Mn-54 2.55 Co-57 1.29 Co-58 6.98 Co-60 16.90 Cs-1 37 1.37 Cs-1 34 .29 Ni-63 52.12 Fe-55 17.52 Sb-1 25 .84 H-3 .01 Sr-90 .02 Zn-65 .11 G. Dewatered Mechanical Filter Media No shipments in 2008 I

H. Dewatered Mechanical Filter Media (brokered) 2008- 001 Nuclide %Abundance Mn-54 3.13 Co-57 .15 Co-58 .09 Co-60 28.32 Cs-1 37 1.82 Cs-1 34 .36 Fe-55 47.11 Ni-63 16.88 Tc-99 .57 C-14 .73 Sb-1 25 .63 Ce-144 .06 Zn-65 .14 2008-004 Nuclide %Abundance Mn-54 6.82 Co-57 .39 Co-58 13.05 Co-60 21.53 Cs-137 1.24 Cs-134 .37 Fe-55 42.39 Fe-59 .03 Ni-63 11.33 Cr-51 .05 C-14 .48 Zr-95 .59 Sn-113 .10 Sb-125 .56 Ce-144 .15 Zn-65 .44 Tc-99 .38 Nb-95 .10 2

2008-006 Nuclide %Abundance Mn-54 3.96 Co-57 .22 Co-58 6.09 Co-60 26.12 Cs-1 37 1.78 Cs-134 .33 Fe-55 42.31 Fe-59 .01 Ni-63 16.60 Cr-51 .03 Zr-95 .28 Sn-113 .05 C-14 .72 Sb-125 .57 Ce-144 .08 Zn-65 .23 Tc-99 .56 Nb-95 .06 I. Solidified Waste No shipments in 2008

12. Dry Solid Waste: . I A. Dry Active Waste (compacted) Compaction no longer performed on-site.

Dry Active Waste (non-compacted) No shipments in 2008 Dry Active Waste (brokered/compacted) No shipments in 2008 Dry Active Waste (brokered/non-compacted) 2008-002 Nuclide %Abundance Mn-54 .02 H-3 98.26 Co-58 .12 Co-60 .42 Cs-I 37 .02 Fe-55 .77 Ni-63 .30 C-14 .04 Sb-125 .01 Zr-95 .01 Nb-95 .02

2008-003 Nuclide %Abundance Mn-54 .02 H-3 98.14 Co-58 .13 Co-60 .44 Cs-1 37 .02 Fe-55 .82 Ni-63 .32 C-14 .04 Zr-95 .01 Sb-125 .01 Nb-95 .02 2008-007 Nuclide %Abundance Mn-54 1.15 Co-57 .06 Co-58 6.88 Co-60 24.02 Cs-1 37 1.28 Fe-55 44.47 Ni-63 17.33 C-14 2.28 Zr-95 .43 Sb-125 .77 Sr-90 .18 Nb-95 1.14 2008-008 Nuclide %Abundance Mn-54 1.15 Co-57 .06 Co-58 6.55 Co-60 24.17 Cs-1 37 1.29 Ni-63 17.38 Fe-55 44.65 Zr-95 .41 C-14 2.29 Sb-125 .77 Sr-90 .18 Nb-95 1.02 4

2008-009 Nuclide %Abundance Mn-54 1.15 Co-57 .06 Co-58 7.03 Co-60 24.00 Cs-1 37 1.26 Fe-55 44.41 Ni-63 17.24 C-14 2.28 Zr-95 .44 Sb-1 25 .77 Sr-90 .18 Nb-95 1.17 2008-010 Nuclide %Abundance Mn-54 1.15 Co-57 .06 Co-58 7.06 Co-60 23.96 Cs-1 37 1.28 Fe-55 .44.36 Ni-63 17.29 C-14 2.27 Zr-95 .44 Sb-125 .76 Sr-90 .18 Nb-95 1.19 2008-011 Nuclide %Abundance Mn-54 1.14 Co-57 .06 Co-58 6.63 Co-60 24.18 Cs-137 1.28 Fe-55 44.58 Ni-63 17.41 C-14 2.30 Zr-95 .41 Sb-125 .77 Sr-90 .18 Nb-95 1.04 5

2008-012 Nuclide %Abundance Mn-54 1.15 Co-57 .06 Co-58 6.61 Co-60 24.19 Cs-1 37 1.29 Fe-55 44.55 Ni-63 17.46 C-1 4 2.30 Zr-95 .41 Sb-125 .77 Sr-90 .18 Nb-95 1.03 2008-013 Nuclide %Abundance Mn-54 1.15 Co-57 .06 Co-58 6.79 Co-60 24.05 Cs-1 37 1.28 Fe-55 44.54 Ni-63 17.37 C-14 2.29 Zr-95 .42 Sb-125 .77 Sr-90 .18 Nb-95 1.09 2008-014 Nuclide %Abundance Mn-54 1.16 Co-57 .06 Co-58 7.28 Co-60 23.88 Cs-I 37 1.27 Fe-55 44.25 Ni-63 17.17 C-14 2.26 Zr-95 .46 Sb-I 25 .76 Sr-90 .18 Nb-95 1.27 6

2008-018 Nuclide %Abundance Mn-54 1.16 Co-57 .06 Co-58 7.29 Co-60 23.85 Cs-137 1.27 Fe-55 44.27 Ni-63 17.14 C-14 2.26 Zr-95 .46 Sb-1 25 .76 Sr-90 .18 Nb-95 1.30 2008-019 Nuclide %Abundance Mn-54 1.12 Co-57 .06 Co-58 5.27 Co-60 24.69 Cs-1 37 1.32 Fe-55 45.18 Ni-63 18.02 C-14 2.38 Zr-95 .32 Sb-125 .78 Sr-90 .19 Nb-95 .68 2008-020 Nuclide %Abundance Mn-54 1.15 Co-57 .06 Co-58 7.02 Co-60 23.98 Cs-137 1.27 Fe-55 44.40 Ni-63 17.27 C-14 2.28 Zr-95 .44 Sb-125 .76 Sr-90 .18 Nb-95 1.18 7

2008-021 Nuclide %Abundance Mn-54 1.14 Co-57 .06 Co-58 6.52 Co-60 24.17 Cs-1 37 1.29 Fe-55 44.67 Ni-63 17.48 C-14 2.30 Zr-95 .40 Sb-1 25 .77 Sr-90 .18 Nb-95 1.00 2008-024 Nuclide %Abundance Mn-54 1.14 Co-57 .06 Co-58 6.05 Co-60 24.45 Cs-1 37 1.30 Fe-55 44.84 Ni-63 17.65 C-14 2.33 Zr-95 .37 Sb-125 .77 Sr-90 .18 Nb-95 .85 2008-025 Nuclide %Abundance Mn-54 1.12 Co-57 .06 Co-58 5.38 Co-60 24.65 Cs-137 1.32 Fe-55 45.23 Ni-63 17.93 C-14 2.37 Zr-95 .33 Sb-125 .78 Sr-90 .19 Nb-95 .66 8

2008-027 Nuclide %Abundance Mn-54 1.16 Co-57 .06 Co-58 7.15 Co-60 23.90 Cs-1 37 1.27 Fe-55 44.32 Ni-63 17.26 C-14 2.27 Zr-95 .45 Sb-125 .76 Sr-90 .18 Nb-95 1.22 2008-028 Nuclide %Abundance Mn-54 1.15 Co-57 .06 Co-58 6.96 Co-60 24.03 Cs-137 1.28 Fe-55 44.39 Ni-63 17.31 C-14 2.28 Zr-95 .44 Sb-125 .76 Sr-90 .18 Nb-95 1.16 2008-030 Nuclide %Abundance Mn-54 1.16 Co-57 .06 Co-58 7.26 Co-60 23.84 Cs-137 1.27 Fe-55 44.32 Ni-63 17.17 C-14 2.26 Zr-95 .46 Sb-125 .76 Sr-90 .18 Nb-95 1.27 9

2008-034 Nuclide %Abundance Mn-54 1.16 Co-57 .06 Co-58 7.20 Co-60 23.87 Cs-1 37 1.27 Fe-55 44.33 Ni-63 17.20 C-14 2.27 Zr-95 .45 Sb-125 .76 Sr-90 .18 Nb-95 1.25 2008-037 Nuclide %Abundance Mn-54 1.16 Co-57 .06 Co-58 7.18 Co-60 23.92 Cs-137 1.27 Fe-55 44.31 Ni-63 17.20 C-14 2.27 Zr-95 .45 Sb-125 .76 Sr-90 .18 Nb-95 1.25 2008-038 Nuclide %Abundance Mn-54 2.77 Co-57 .10 Co-58 .12 Co-60 37.34 Cs-1 37 .02 Fe-55 38.87 Ni-63 17.17 C-14 .02 Zr-95 .33 Sb-125 1.49 Sr-90 .04 Sn-113 .07 Ce-144 .02 Pu-238 .01 Am-241 .01 Nb-95 .62 10

2008-039 Nuclide %Abundance Mn-54 2.88 Co-57 .11 Co-58 1.44 Co-60 36.79 Cs-1 37 .02 Fe-55 38.78 Ni-63 16.82 C-14 .02 Zr-95 .43 Sb-125 1.49 Sr-90 .04 Sn-113 .08 Ce-144 .02 Pu-238 .01 Am-241 .01 Nb-95 1.06 2008-041 Nuclide %Abundance Mn-54 1.19 Co-57 .06 Co-58 7.06 Co-60 24.15 Cs-1 37 1.24 Fe-55 44.26 Ni-63 17.16 C-14 2.22 Zr-95 .45 Sb-125 .78 Sr-90 .18 Nb-95 1.24 2008-042 Nuclide %Abundance Mn-54 2.81 Co-57 .10 Co-58 1.21 Co-60 37.18 Cs-I 37 .02 Fe-55 38.86 Ni-63 17.05 C-14 .02 Zr-95 .36 Sb-125 1.49 Sr-90 .04 Sn-113 .07 Ce-144 .02 Pu-238 .01 Am-241 .01 Nb-95 .74 11

B. Sealed Sources No shipments in 2008 C. Sealed Sources/Smoke Detectors No shipments in 2008 D. Irradiated Components No shipments in 2008 12

Attachment 3 Unplanned Offsite Releases

McGUIRE NUCLEAR STATION UNPLANNED RELEASES (January 1, 2008 through December 31, 2008)

There were two unplanned liquid radioactive releases to the environment in 2008. There was one unplanned gaseous radioactive effluent release to the environment in 2008.

-J

Febmiy03,2008 Memorandum To: Annual Radioactive Effluent Release Report CC: Steve Mooneyhan, H. J. Sloan, Joyce Correll, C.D. Ingram, Jim Kammer, Ken Ashe, Kay Crane From: William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release from the WC system Final Hold up Pond Reference PIP M-08-0585 Event Summary:

See referenced PIP for details.

Assuming the water was leaked from the pond to the under surface of the ground and the total volume reached the Catawba River. A conservative calculation indicates 5.OE-3 curies of tritium were released from the FHP during this event. This would equate to a Total Body dose of 5.39E-5 mRem.

Sequence of events:

1/28/08 Water transfer from Mix pond B to the FHP was initiated to allow for treatment to resolve a foaming issue seen at outfall #002 during a normal WC pond release to Catawba river.

1/29/08 @ 1620 Gravity drain to FHP was secured. FHP placed in recirculation as part of the treatment plan to resolve the foaming issue. FHP level -0.8 mg (million gallons).

2/1/08 @ 1020 FHP recirculation secured. FHP level -0.75 mg. CHM suspected leak in recirculation piping. No evidence of uncontrolled discharge identified at outfall #002 (normal WC release path). FHP level was marked with tape to check for further decrease in level.

(Recirculation pumps off and valves isolated.)

2/3/08 @ 0930 CHM verified FHP level @ -0.66 mg. Notified EH&S on duty contact. Sampled FHP & initiated PIP M-08-00585. Started pumping FHP to "B"mix pond. CHM performed surveillance around and below the pond to identify any spill sites. None were found. No water was seen coming from the ground as a result of this event.

2/4/08 @ 0900 FHP level @ 0.43 mg. Secured FHP pumping to "B" mix pond. Sampled and started "A" mix pond discharge to river. CHM made decision to monitor level of FHP and if still dropping, secure discharge on 2/5/05 and pump FHP to in-service mix pond.

2/4/08 @ -1100 sampling was requested from monitoring wells 84, 84R, 82, 103,103R to identify ground water impact below the Pond.

2/4/08 @ 1600 No change in level of FHP noted since 0900. Started pumping FHP to "B" mix pond. Total volume lost from FHP conservatively estimated to be -140K gallons.

The total liquid activity released was reported on Liquid Waste Release (LWR) # 2008014.

The unplanned activity was evaluated against off site dose limits using current ODCM methodology on the attached reports.

Safety Significance:

The health and safety of the public were not compromised by this event. The total activity released was insignificant. Calculated dose to the Total Body (5.39E-5 toRem) is less than one tenth of one percent

(<0.10%) of the dose limit specified by Selected Licensee Commitments and Code of Federal Regulations.

W.C. Spencer Joyce Correll RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station

Fexuay 15,2008 Memorandum To: Annual Radioactive Effluent Release Report CC: Steve Mooneyhan, H. J. Sloan, Joyce Correll, C.D. Ingram, Jim Kammer, Ken Ashe, Kay Crane From: William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release from the WC discharge pH analyzer Reference PIP M-08-0692 Event Summary:

See referenced PIP for details.

Sample water from pH test probes was found to be released to the ground southwest of the WC system Final Holdup Pond (FHP). The flow from test probes is 1.3 gpm triggered by normal WC discharge to the Catawba River. This event was discovered via follow up investigation from loss of volume from the FHP. (See PIP M-08-0585) The WC release was secured stopping the pH sampler release.

Assuming the water discharged from the analyzer to the ground on site and the total annual volume reached the Catawba River. Using 2006 WC release data a conservative calculation indicates 1.27E-2curies (8.35E-3 Ci in 2007) of tritium was released to an area southwest of the (FHP). This would equate to a Total Body dose of 1.36E-4 mRem for the year. The highest total activity from the previous 3 years was used as the most conservative estimate.

The total liquid activity released each year from this path is insignificant and will not be included in the annual dose from effluents. Regulatory Guide 1.109 "Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR part 50, Appendix I" allows insignificant dose from pathways that are not more than 10% of the total from all pathways considered in the guide to be ignored. The annual dose from this event conservatively estimated is less than 1% of the total from all pathways.

The unplanned activity was evaluated against off site dose limits using current ODCM methodology on the attached reports.

Preliminary on site soil samples taken in the discharge plume identified Cs-137 at levels -200pCi/L which are similar in concentration to REMP sediment samples normally obtained down stream of the WC discharge outfall. Follow up sampling activities will be reported in PIP M-08-0692.

Safety Significance:

The health and safety of the public have not been compromised by this event. The total activity released was insignificant. Calculated annual dose to the Total Body (1.36E-4 mRem) is less than one tenth of one percent (<0.10%) of the dose limit specified by Selected Licensee Commitments and Code of Federal Regulations.

W.C. Spencer Joyce Correll RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station

Jamaiy 22, 2008 Memorandum To: Annual Radioactive Effluent Release Report CC: Steve Mooneyhan, H. J. Sloan, Joyce Correll, C.D. Ingrarrm Jim Kammer, Ken Ashe, Kay Crane From: William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit 1 Vent Reference PIP M-08-0379 Event Summary:

See referenced PIP for details.

On January 22, 2008 10:15, a normal WGDT-E release was initiated to the Unit 1 Vent. At initiation of the release a high rad trip occurred on OEMF-50 immediately terminating the release. While investigating the trip actuation a pressure drop of-0.5 psig from WGDT-B (in-service tank) was observed and a pressure increase of

-0.5 psig was seen in WGDT-E. Attempts to release WGDT-E were terminated. From trend analysis of 0 EMF 50, increased counts were seen from one -76,000 cpm spike which caused the Trip 2 actuation (auto release termination). Trending the Unit Vent Monitor 1EMF-36 indicated no counts above normal background.

No off site release limits were challenged.

A conservative calculation indicates 3.15E-3 curies of fission and activation gas (noble gas) were released to the Unit 1 Vent during this event. The source of the noble gas is suspected to be due to leak-by from 1 WG-288 (Hydrogen re-combiner isolation valve) into the WGDT-E tank and discharge line.

Sequence of events:

On 1/21/08 WGDT-E was sampled for a planned release on 1/22/08.

1/22/08 10:15 WGDT-E release started.

10:15 an instantaneous spike was seen on 0 EMF 50 of- 76,000 cpm and the release was auto terminated.

10:15 release secured by Chemistry.

Chemistry reported -0.5 psig pressure drop (20 ft3) released from WGDT-B to Unit 1 Vent.

WGDT-B sampled to account for activity released to the unit 1 vent.

SRPMP 8-2 "Investigation of Unusual Radiological Occurrences" was completed to document the Unplanned Release investigation.

HP/0/B/1003/050 RP procedure for WGDT release put on Technical Hold.

The total Noble gas activity released was reported on (GWR) Gaseous Waste Release # 2008004.

The unplanned activity was evaluated against off site dose limits using current ODCM methodology on the attached spreadsheet.

Safety Significance:

The health and safety of the public were not compromised by this event. The total activity released was insignificant. Calculated dose and dose rate to the Total Body, Skin, Gamma Air, and Beta Air were all less than one percent (<1.0%) of the limits specified by Selected Licensee Commitments and Code of Federal Regulations.

W.C. Spencer Joyce Correll RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station

Attachment 4 Fuel Cycle Calculation

McGuire Nuclear Station 2008 Radioactive Effluent Releases 40CFRI90 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFRl90, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. The fuel cycle dose assessment for McGuire Nuclear Station only includes liquid and gaseous effluent dose contributions from McGuire and direct and air-scatter dose from McGuire's onsite Independent Spent Fuel Storage Installation (ISFSI) since no other uranium fuel cycle facility contributes significantly to McGuire's maximum exposed individual. The combined dose to a maximum exposed individual from McGuire's effluent releases and direct and air-scatter dose from McGuire's ISFSI is well below 40CFR190 limits as shown by the following summary:

I. 2008 McGuire 40CFR190 Effluent Dose Sununary The 40CFR190 effluent dose analysis to the maximum exposed individual from liquid and gas releases includes the dose from noble gases (i.e., total body and skin).

Maximum Total Body Dose = 4.72E-01 mrem Maximum Location: 0.5 Mile, East-Northeast-Sector Critical Age: Adult Gas non-NG Contribution: 56%

Gas NG Contribution: 4%

Liquid Contribution: 40%

Maximum Organ (other than TB) Dose = 4.87E-01 mrem Maximum Location: 0.5 Mile, East-Northeast Sector Critical Age: Child Critical Organ: Liver Gas Contribution: 49%

LiquidContribution: 51%

II. 2008 McGuire 40CFR190 ISFSI Dose Summary Direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at McGuire have been calculated and documented in the "McGuire Nuclear Site IOCFR72.212 Written Evaluations" report. The maximum dose rate to the nearest resident from the McGuire ISFSI is conservatively calculated to be 14.5 mrem/year.

The attached excerpt from the "McGuire Nuclear Site IOCFR72.212 Written Evaluations" report is provided to document the method used to calculate the McGuire ISFSI 14.5 mrem/year dose estimate.

a

The following six pages are taken from the McGuire Nuclear Site, "Independent Spent Fuel Storage Installation",

10CFR72.212 Evaluation report.

C. 10CFR72.212(b)(2)(i)(C) - Requirements of 72.104 Criterion

"...the requirements of 72.104 have been met."

Evaluation Historical TLD Monitoring Attachment 3 documents the actual radiological dose at the owner controlled fence on top of the berm overlooking the ISFSI: Actual dose to the public from the ISFSI is only available at this owner controlled fence. Therefore, a normalization factor is derived by comparing the actual dose to the calculated dose. The normalization factor is applied to the calculated values for the intake waterway and the exclusion area boundary to approximate the actual dose values from the ISFSI in those areas around the plant.

From Attachment 3, the greatest dose is 0.058 rems during a 97 day period in the second quarter of 2004 (TLD location #76). This is equivalent to 0.0249 mrem per hour for a total population of ten TN-32 casks. The calculated dose for this same location using conservative computer models is 0.744 mrem per hour. A normalization value is derived by dividing the actual dose by the calculated dose, which is 0.0249/0.744 = 0.0335. Please note that the normalization factor will only be used for the TN-32 casks.

ISFSI Controlled Area Boundary (ISFSI and Site Operations)

It is stipulated in 10CFR72.104(a) that the annual dose equivalent to any real individual who is located beyond the controlled area of the ISFSI (as defined in 10CFR 72.3) must not exceed 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any critical organ during normal operations and anticipated occurrences.3 This dose equivalent must include contributions from planned releases to the environment, direct radiation from ISFSI operations, and any other radiation from uranium fuel cycle operations within the region.

The combined and skyshine dose rates at various distances for one cask stored with 7 year cooled fuel (inner) and 10 year cooled fuel (outer) were analyzed by Transnuclear. 4 The best-fit empirical equation for skyshine dose rate as a function of distance is y = 0.0156e-.0112x for gammas and y = 0.0274e°0 1 29x for neutrons, where y is dose rate (mrem/hr) and x is distance (meters), applicable from 20 to 1000 meters (page 22 of the calculation). Likewise, the best-fit empirical equation for total dose rate (direct and skyshine) as a function of distance is 3 For McGuire, compliance with this regulation will also assure compliance with 40 CFR Part 190.

4 TN Calc 1083-20, "TN-32 Cask for Duke Power, TN-32 MCMP Models for Determining Off-Site Doses," Rev. 0, dated 4/06/2000.

McGuire Nuclear Station (NAC-UMS) Page 39 of 57 10CFR72.212 Written Evaluations, Rev. 03

y = 492.69x-21 688 for gammas and y = 166.95x-2° 696 for neutrons, where y is dose rate (mremihr) and x is distance (meters), applicable from 20 to 80 meters (page 23 of the calculation).

Based upon conservative engineering judgment, the McGuire power generation contribution at the Exclusion Area Boundary (EAB) is determined to be 3 mrem per year. The 3 mrem per year is independent of the ISFSI.

The combined and skyshine dose rates at various distances for a 2x6 cask array with 5 year cooled fuel were analyzed by NAC. 5 Skyshine dose rates are located in Table 6-4 on page 12 of the calculation and combined dose rates are located in Table 6-6 on page 14 of the calculation. Both tables account for the effects of both gammas and neutrons.

The controlled area of the MNS ISFSI is defined to be coextensive with the McGuire Nuclear Site EAB. The annual dose for a maximally exposed individual at this boundary must be below 25 mrem in accordance with 10CFR72.104 (cited above). For a conservative estimate, the individual is assumed to have a 100%

occupancy time (8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months per year) at the boundary. The individual is also considered to be occupying the point on the EAB closest to the ISFSI, which would be just south of the Cowans Ford Dam close to the river. This point on the EAB is determined to be 425 meters from the ISFSI and the calculated dose only considers skyshine radiation. Direct radiation from the casks is shielded by the ground due to the significant drop in elevation from the ISFSI to the river. The combination of calculated and actual dose to an individual due to the ISFSI is determined to be 14.5 mrem and the dose due to McGuire power generation is 3 mrem per year for a total dose of 17.5 mrem per year. Therefore, the ISFSI controlled area boundary radiation limits are met for the McGuire ISFSI.

The selection of an individual on the EAB south of the dam is totally arbitrary in order to choose the closest point on the EAB to the ISFSI. This location is owned by Duke Energy and no member of the public would be permitted to, occupy this location continuously. The regulations speak of the "real individual" when addressing radiation exposure. Factually, this "real individual" is located beyond the EAB on the eastern side of the plant.

General Environment from Total Nuclear Fuel Cycle (ISFSI and Site Operations) 40CFR190 applies to radiation doses received by members of the public in the general environment and to radioactive materials introduced to the general environment as the result of all operations which are part of the Nuclear Fuel Cycle. The McGuire ISFSI is located in the immediate proximity of McGuire Nuclear Station and as such compliance with 40CFR190 must be demonstrated.

NAC Calc 12418-5001, "Skyshine Evaluation of McGuire ISFSI," Rev.0, dated 11/26/03.

McGuire Nuclear Station (NAC-UMS) Page 40 of 57 10CFR72.212 Written Evaluations, Rev. 03

The McGuire UFSAR (Section 2.1.2.2, "Boundaries for Establishing Effluent Release Limits") and Selected Licensee Commitments Manual (Section 16.11, "Radiological Effluents Control") defines "unrestricted areas" to be coextensive with the EAB and beyond. Likewise, "general environment" is defined to be coextensive with the EAB and beyond.

It is stipulated in 40CFRI 90.10(a) that the annual dose equivalent shall not exceed 25 mrems to the whole body, 75 mrems to the thyroid, and 25 mrems to any other organ of any member of the public as a result of exposures to planned discharges of radioactive materials, radon and its daughters excepted, to the general environment from uranium fuel cycle operations and to radiation from these operations. As illustrated previously in showing compliance with 10CFR 72.104(a), the calculated dose at the EAB is 17.5 mrem per year, within the 25 mrem allowable limit. The summation of the doses from the ISFSI and McGuire power generation to the General Environment are well within the allowable limits.

Dose Inside ISFSI Controlled Area (ISFSI Operations)

Regulations permit the controlled area to' be traversed by public roads and waterways as cited in IOCFR72.106(c). Since the public is permitted access into the controlled area at McGuire, the dose rate must be below 2 mrem6 per hour and the annual dose must be below 100 mrem within the controlled area.

A member of the public is postulated to be located between the owner controlled fence and the EAB at a point close to the security buoys near the intake structure of the nuclear station, the closest approach for such an individual to the ISFSI.

This area is accessible as shoreline covered with large stones for erosion control and is not a location where individual members of the public would typically be found. Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," provides a recommended value of 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year of "shoreline recreation" for the maximum exposed individual in the vicinity of a nuclear station. Although the shoreline area near McGuire is not recreational in nature,_use of this value as an occupancy factor would be conservative. For additional conservatism the residence time was more than doubled to 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months and utilized in the dose calculations for an individual in the vicinity of the McGuire intake structure close to the ISFSI.

The maximum dose rate at the owner controlled fence closest to the ISFSI was determined to be 0.409 mrem per hour (direct radiation and skyshine), within the 2 mrem per hour allowable limit. Finally, the annual dose resulting from ISFSI to the public inside the McGuire EAB in the vicinity of the intake structure, using a 6 OCFR20.1301(b). See also IOCFR20.1301 (a)(2).

McGuire Nuclear Station (NAC-UMS) Page 41 of 57 10CFR72.212 Written Evaluations, Rev. 03

residence time of 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months , is determined to be 8.48 mrem (skyshine only -

earthen berm acts as a shield), within the 100 mrem allowable limit.

These calculations show that the McGuire ISFSI containing ten TN-32A casks and up to 36 NAC UMS casks meets the radiological requirements of 10CFR72.104, 10CFR20.1301 and 40CFRI 90.

Tabulations Normalization Factor (NF)

TN-32A Casks Actual radiological dose at the owner controlled fence divided by the calculated dose.

Actual dose =

(0.058 rem X 1000 mrem/rem) / (97 days X 24-hrs/day) = 0.0249 mrem/hr Calculated dose = 0.744 mrem/hr (see "top of berm at owner controlled fence" below)

NF = 0.0249/0.744 = 0.0335 Due to the amount of conservatisms utilized in the computer models, the actual measured dose at the owner controlled fence is only approximately 3% of the calculated values. Since historical TLD measurements are not available for the waterway and exclusion area boundary, the NF and calculated values are used to approximate the actual dose from the TN-32 casks for those two areas.

Top of berm at owner controlled fence - 70 meters from ISFSI TN-32A casks Using the previous equations for total dose and a distance of 70 meters the total dose rate (gammas and neutrons) for one cask is 7.443 E-0 2 mrem/hr.

(10) Casks X 7.443 E°2 mrem/hr = 0.744 mrem per hour Actual measured dose rate for the first ten casks stored in the ISFSI 0.0249 I mrem per hour McGuire Nuclear Station (NAC-UMS) Page 42 of 57 10CFR72.212 Written Evaluations, Rev. 03

NAC -'UMS Casks Using the calculated value from the NAC evaluation located in Table 6-6, "2x6 Cask Array Combined Dose Rates", the total dose rate (gammas and neutrons) at a distance of 70 meters is 1125.6 mrem/yr. This equates to:

(1125.6 mrem/yr) / (8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months per yr) = 0.128 mrem per hour Total Expected Dose Rate at Owner Controlled Fence at Top of Berm Ten TN-32A Casks (actual) plus (3X) 2X6 Array NAC UMS Casks (calculated) 0.0249 mrem per hr + 3(0.128) mrem per hr = 0.409 mrem per hr Waterway beyond security buoys on other side of berm from ISFSI - 135 meters from ISFSI TN-32A Casks Using the previous equations for skyshine and a distance of 135 meters the skyshine dose (gammas and neutrons) for one cask is 8.24 E-0 3 mrem/hr.

(10) Casks X 8.24 E"03 mrem/hr X 150 hrs (residence time/yr) = 12.36 mrem per year Normalized actual dose = 0.033 5 X 12.36 mrem/yr = 0.414 mrem per year Total expected dose for-ten TN-32A casks (actual) 0.414 mrem per year NAC-UMS Casks Using the calculated value from the NAC evaluation located in Table 6-4, "2x6 Cask Array Scattered Dose Rates", the total dose rate (gammas and neutrons) at a distance of 135 meters is 157.3 mrem/yr. For a residence time of 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months this equates to :

(157.3 mrem/yr) /(8760 hrs/yr) x 150 hrs (residence time/yr) 2.69 mrems / yr McGuire Nuclear Station (NAC-UMS) Page 43 of 57 10CFR72.212 Written Evaluations, Rev. 03

Total Expected Dose at Waterway on Other Side of Berm Ten TN-32A Casks (actual) plus (3X) 2X6 Array NAC UMS Casks (calculated) 0.414 mrem per year + 3(2.69) mrem per year = 8.48 mrem per year Individual Sited on Exclusion Area Boundary Below Dam - 425 meters from ISFSI TN-32A Casks Using the previous equations for skyshine and a distance of 425 meters the skyshine dose (gammas and neutrons) for one cask is 2.48 E°4 mrem/hr.

(10) Casks X 2.48 E"04 mrem/hr X 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months per year = 21.7 mrem / yr Normalized actual dose = 0.0335 X 21.7 mrem/yr = 0.727 mrem / yr Total expected dose for ten TN-32A casks (actual) 0.727 mrem / yr NAC-UMS Casks Using the calculated value from the NAC evaluation located in Table 6-4, "2x6 Cask Array Scattered Dose Rates", the total dose rate (gammas and neutrons) at a distance of 425 meters is 4.6 mrem/yr.

Total Expected Dose at Exclusion Area Boundary Ten TN-32A Casks (actual) plus (3X) 2X6 Array NAC UMS Casks (calculated) 0.727 mrem per year + 3(4.6) mrem per year = 14.5 mrem per year McGuire Nuclear Station (NAC-UMS) Page 44 of 57 10CFR72.212 Written Evaluations, Rev. 03

McGUIRE NUCLEAR STATION 2008 METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS OF WIND SPEED, WIND DIRECTION, AND ATMOSPHERIC STABILITY USING WINDS AT THE 10 METER LEVEL (Hours of Occurrence)

McGuire NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES. BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY A WIND SPEED CLASS I I I--------I--------------------------------------------------------- I I I 0.75-1 1.00-1 1.25-1 1.50-I 2.00-1 3.00-1 4.00-1 5.00-I 6.00-1 8.00-1>9.99 I I 1 0.99 1 1.24 I 1.49 I 1.99 I 2.99 I 3.99 1 4.99 I 5.99 I 7.99 I 9.99 I M/S ITOTAL I.--- +--- ------- -----

+-- +-...-- -- - -- - +--- -- +-...... ......-- ......------.- --. I I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO.

I-----------------------------------------------------------------------+--+---+ - - - I SECTOR I I I I I I I I I I I I I I ---------------------- I I I I I" I I I I I I I . I I-N- 1 11 31 11 101- 81 11 .1 .I 11 21 21 291 I - -

I-NNE-I

I

- I 11 31 121 91 7I 1 I

.1 *I- 331 I- - - -- - - - - - - - - - - - - - -- - - - - - -- - - - - - -- - - ------------------------------------

---- -- I I-NE- 1 .1 .I 21 71 1ll 21 41 11 .*1 I .I 271 I -+-------------------------------- --- ---------------------------------

+-+ + - I+-

-ENE- I. 1 41 8t 15 - 31 1 . I__ .1 311 I----- - - -- - - - -- - - -- - - - -- - - - -- - - -- - - - -- - - - --- ---------------------------------

+- + - ++ - I I-E- - -. - 1-- -1 1-- 31 8- 51 '1- . 1 .1 17-I-ESE-I -- - ------------- I ---- 1 - --.1-------31 -- 71 .I I 1

.I1 1

+- .1+ - 1I I-SE- I *1 I-------------------------------------------------------------------------------- .I .1 .1 41 11 I .1 . I - I - -I I -- -- -- -- -- --- -- -- - -- -- -- -- -- -- -- - ---- -- -- -- -- -- - -------------------------------- +-+- +.+ - I

-SSE- I *I *I I 11 11 21 .1 .1 1 I .1 41 I------- +-- ---- -------------------------

+- + +I+

I-SW- I .1 .1 *I 11 '91 21 1l .i .1 .1 *I 91 I-sW- . I .1 .I 11 21 41 41 41 2I .i *I .1 161 I------ -------------- ------- ------- - ---------------------------------------------- I I-sW - I .1 11 21 .I 19 91 61 - 11 *1 .1 36G I

I------------------------------------------------------------------------------------------+

- - - - - - - - - - - - - - -- - - - -- - - - - -- - - - - - -- - - -- - ----------------------------------- ++ - ++ -I+ -- I I-Wsw- I . .1 21 8 141 41 .I 11 *2j 1 .1 291 I - - - - - - ----- - - - - -- - - - - - - - - - - - -L -----------------------------------------------------

++- + - + - + - + - + - I I-W- I .2 I 1 21 .1 .1 El 21 .I 1o I - -- - -- - -- --- - - -- - -- - -- - - -- - -- - -- - -- - - -- - -- - -- - - --------------------------

++ -- +-- + - -+- I T-WNW I .I .I 1 2 41 11 11 2 1 11 11 2 1 .1 131 I-NW- 1 11 .1 21 41 31 .1 1 1 .21 61 .1 201 I-NNW- 1 1 21 11 31 21 11 11 .1 61 211 51 431 1+--

ITOTAL 1 31 71 131 631 1131 541 211 81 ill 291 71 3291

McGuire NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY B WIND SPEED CLASS I I

I I S0.45-I 0.75-I 1.00-1 1.2S-I 1.50-12.00-1 3.00-1 4.00-1 5.00-.I 6.00-1 8.00-1>9.99 I I 0.74 0.99 0 1 1.24 I 1.49 1 1.99 1 2.99 1 3.99 I 4.99 1 5.99 1 7.99 9 j M/S 4tTOTAL I I.- +-++-. .. .+ - -... -- + -......-. *-...-- +-......-+ -......- + .....--- +-....-..+ .....- I I NO. I NO. I NO. INO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO.

I- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------ ------- ------- ------ I SECTOR I I I I I I I I I I I---------------------- I I I I I I I I I I I I I-N- I l .1 .* 41 41 4f 41 21 11 21 41 11 231 L------------- ------- ------- ------- -------- ------ -----

------- --------- +- + I

-NNE- 1 1 11 41 11 51 161 101 11 1i 31 21 44 I- - - - - - - - - - - - - - -- - - - - -- - - - -- - - - - - -- - - - - - -- --------------------------------------------- I I-NE- 1 21 l 1 21 41 61 61 711 21 *I .1 351 I- - - - - - - - - - - - - - -- - - - - -- - - - -- - - - - - -- - - - - - -- --------------------------------------------- I I-ENE- I I *I I 11 31 ill 131 41 i . *I.1 33 I - --- --- --- -- - -+--

-- --- --- - ---- - -- --- .+

+-----------------------------+ -. + - .+-. .+. .- I l-E- 1 1 1 I1 "1 S1 81 21 1 1 11 161 I - - - - - - - - - - - - - +-- - - - - -- - - - - - ---- - --- -------------------------------- +--- I I+-

-ESE-11--

1 .1 .1 11 11 _ 41 31 21 .1I ".1 ill

- --- - --------------------------------------------- :----------------++ ----- - I

-SSE- . 11 11 51 11 .I .I I

.1 81 1I-_s .1- - -. - 3 - 1 - 1- --------------------------------------------

. 11 .1 . .1 14 I 1

..---. +- . ..-

..--- . . ..-- . . ..-- . . ..-- I+

I-ssw- I *I *1 .1 -1 .I 131 81 81 81 .1 1 .1 37 I +---- ----

+- + - I+--+--

I-Sw- I .1 *I fl ii 21 131 271 221 18j 71 i .I 921 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ----------------------------

+ -- + -- I

-WSW- 1 *I 1 11 11 41 221 181 81 81 41 *l .*I 661 I1-w-1

- - - - - - - - - - - - - - -- - - -11 - -- - - - -- 11 - - 11 - - - -- .1 - - 41 - - - -- 41 --------------------------------------

31 31+ -- 11 +

.-- .1 I 17I I- - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - -------------------------------------- ++ - ++ - +I I-WNW- 1 .I 11 11 11 101 31 51 31 'I 1 .l 25l I +- --- ------------------------------------------- . +-. .+-. t.-------- +- I I-NW- 1 *I .1 21 11 31 I1 11 21 8l ill 8I .1 421 1I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------------------------------------- +I I-NNW- I1 .1 . 71 11 11 21 71 231 101 .1- 521 I- - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - -- - - ------------------------------------- ++ - ++ - +I TOTAL I 21 21l 2I SI 381 1271 1081 681 641 541 251 11 siSj

McGuire NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY C WIND SPEED CLASS I I

I I 0.45-I 0.75-I 1.00-1 1.25-I 1.50-I 2.00-1 3.00-1 4.00-1 5.00-I 6.00-1 8.00-1>9.991 I 0.74 1 0.99 I 1.24 I 1.49 1 1.99 I 2.99 3.99 I 4.99 I 5.99 1 7.99 1 9.99 I M/S ITOTAL I----- +--------+-------+------+--- --- +-- -- ------ .....

+--- +...-...-+...-...+..-+--- ... I I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO.

I------------------------------------------------------------------------------------------

+-+-- + - + - + - + - + - + - +. .- . I SECTOR I I I I I I I I I I I I II I ----------------------I II I I I I I1 I I I I I-N- I "1 24 21 11 141 171 81 21 51 101 81 *1 681 I- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------------------- ++ - ++ - +I I-NNE- I 1. .1 11 21 71 191 181 ill 61 ioj 41 11 79I I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------------------------------------- +I I-NE- 1 I 1 .1 . 61 211 191 241 "il 71 11 .1 891 I- - - - - - - --- - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - ------------------------------------- ++ - ++ - +I

-ENE- I .1 '1 11 71 151 101 41 1I '1 1 *1 381 1I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------------------- ++ - ++ - +I

-E-.I .1 61 91 131 11 .1 11 .1 301 1----------------------------------------------------------------------------------+- -+-- +

-ESE- I .1 1 I .1 21 S 21 11 .1 .I .1 .1 101 I- -+ - - - - - - - -+------ -...... -- ......

+----- ......--+- +-...... ... --..

-+- +.......- ... .+..-.

-SE- I 11 .1 11 .1 .1 i 1I 1i .1 .I .1 S 1I - -

I-SSE- - - - - - - - - - - - - - -1I1 - - - - - - - - - - - - - - - - - 1 - - 1

.I

. .1 21 - - --------------------------------------------

1 , 1I1 .1 .1 7 I1 I- - - - - - - - - - - - - - -- - - - - -- - - - -- - - - - - - - - - - - - -- --------------------------------------

+ -- + -- I I-S- I .1 .1 *1

.I 11 1 17j 11 .I .1 .1 81 I-SsW-

- - - - - --- - - - - - -- I - .1- - -- 11 - -- .1 - - -- .1 - - 71 - - - 19 -- - -31 1 - 18 ++ 8 s1

-++- ----------------------------------- 1 -- 31 *1 - 441I

-~sw- I , .1I 1 .1 . 21 161 351 171 181 81 31 . 991 I- - - - - --- - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - ------------------------------------- ++ - ++ - +I I-WSWz I 11 *1 1 1 .1 121 171 161 81 61 3l 1i 641 1 - - - - - - - - - - - - - - - - - - - ----- - - - - --- - --7---------

- - - - - - - - - - ----------------- - -+--- - -- I I-W I .1 .1 .1 21 121 101 21 1i 21 1i *1 301

-- . +--------------------------------------------------- - ---------------------

+-......-+-......-+-.. .+- I I-WNW- I .I 11 .1 1 41 21 41 5l 21 21 31 *1 241

- - - - - - . - - - - - - - - - - - -------------------------------------- +- +------I I-NW- I .I 2I 21 *I 11 31 21 61 6 191. 141 *1 551

- -- --.- .- .-..-- - . . . .. . --- ----- +-..+ - - -- -- -- -- - -- I I-NNW- I 11 21 11 41 21 sI 81 11 12I 25l 101 31 711 I-- - - - - - - - - - - - - - -- - - -- -------------------------- I ITOTAL 1 31 71 71 9I 631 1551 1631 97I 75I Sal 47I1~ 721l

McGuire NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY D WIND SPEED CLASS I

I 10.45-1 0.75-I 1.00-1 1.25-I 1.50-I 2.00-1 3.00-I 4.00-I 5.00-I 6.00-I 8.00-1>9.99 1 I 0.74 10.99 1 1.24 1 1.49 1 1.99 I' 2.99 1 3.99 1 4.99 1 5.99 1 7.99'1 9.99 1 M/S ITOTAL I I I--- - +- - -- - - - - - - - - - - - - - - ------------------

- - - - - - - - - - - - - - --- I I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO.

I --.....--- ---

- -......-- - - - -------- - ---- ------- ++------- ---- - -- -

+ ---- -..+- . .+ ..-. .I ISECTOR I I I I I I I I I I I I I I I ---------------------- I I I I I I I I I I I I I I-N- I .1 .1 61 61 331 521 361 561 281 201 ii I 2381 I - - - - - - - - --- - - - - - - - - -- - -- - - - - - - - - - - - - -- ------------------------------------------------ I

-N E- 21 11 51 61 291 701 861 701 75 271 21 .1 3731 I - - - - - - - - - - - - - - -- - --- - - - - - -- - - - ---------- - -- ---------------------- ------- -------------I I-NE- 1 1 I 41 61 371 1371 2081 2391 1221 191 61 *I 7781 I------------------------------------------------------------------------------------------------ + - +-- . I

-ENE- .1 .I 31 SI 411 1091 981 671 lli 11 1 .1 3351 1 ......

+ I+-

j-E- 1 1 1. 21 21 211 731 961 131 31 1 .1 .1 2111 1 ......----.....---

-.....----.....---------------------- -...-..- +-......+..- .. .+..-.- . -+---- +----- +-. .- I

-ESE- 1 *1 11 11 ill 221 611 4 191 81 11 *I .1 1701 I. -.. .. ...-- ....---. .. ...---... - - - -.. - -...--

- - -...---. - - - -- -. ..-- .....-- -- ----- -I++

I-SE- I 'I . 1 6E 131 311 791 421 51 21 11 .1 .1 1801 l-SSE- I i 5I 81 141 421 421 161 .1 .1 .1 .1 .1 1281 I-s- I i1 21 41 201 361 591 251 81 11 21 *I *1 1581 I ------- ----- --- ----- ---- ------------------

------------- - ---- -- -I I-SSW- I I 31 21 61 261 831 1081 591 251 121 .1 3251 I ---------------------------------- --- ---- ---- ---- ---- ---- ---- --------------- - ---- --- I I-sw-i 11 41 sj 251 1251 1551 1281 541 361 sI 11 5401 I - - - - - - - - - - - - - - - - - - - - -- - - - -- - - - - - - - - - - - - -- --------------------------------------

+ -- + -- I l-WSW- I .1 .1 1I 131 491 881 511 271 241 241 31 11 2811 I -- -- - -- . - --------------------------------------------------------- I++

-w- 1 .1 31 5I 91 261 331 34 251 81 91 51 11 1581 I--------------------- --------------------- --------------------- -------- ----------------------- -I I+-

l-WNW- 4I 11 31 9j 161 261 241 321 201 141 61 21 153l I - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - -------------------------------------------- +I I-NW- 1 ii 41 71 91 101 35 43l 321 281 291 8l 21 2081 I --------------------------------------- ---- +------------------+-+- --- II I-NNW- I .l 31 8l 101 isj 291 41l 411 241 251 71 21 205l II-CALM-

-- 1 31 .1I1 - .I

. 1 .I I1-----------------------------------------------------------------------.1 .I1 .1+ -

3 II+-

1 I -- - +- ----------------- ---- ---------------------------------------------------

+ - + -I+- + -

TOTAL I iij 251 691 1441 459 11011 1109 8211 4331 2201 43I 91 44441

McGuire NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY E WIND SPEED CLASS I I

I I 10.45-1 0.75-I 1.00-1 1.25-I 1.50-I 2.00-1 3.00-1 4.00-1 s.o00- 6.00-1 8.00-1 1 I 0.74 I 0.99 1 1.24 1 1.49 1 1.99 1 2.99 j 3.99 1 4.99 I 5.99 I 7.99 I 9.99 ITOTAL I- - - ---+---- --- - ----- - + - ---- --------

+-......-+-... .+- . .+ ..-.- + ..-.- +-.-..+-.- I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I I --.....----.....----.....----.....---------------------- ......-- -....--- +- ...... +...-..+..-+..-..+. .- I SECTOR I I I I I I I I I I I I I I- I I I I I I I I I I I I I I-N- I 11 21 .1 41 71 81 41 11 .1 .1 *1 271

-- +--+--+-

S--------------------------------------------------+ ++. - - --------- - - - +---+-

I-NNE- I 1 11 61 31 101 21 31 " 1 -1 261 I- - - -- - - - - - - - - - - - - - --- - -- - - - - - -- - - - - - -- -------------------------------------------. - I I-NE- I 11 1 .1 71 71 91 21 1 .1

-1 .1 271 1 - - - - - - - - - - - - - - -- - - - - - -- - - - - - -- - - - - - ------------------------

4 -- +- ----- -- - - - -I I-ENE- 1 .1 . 1 31 41 61 ill- - 41 .1 .1 11 291 I-E- -- - - - - - - - - - - - - - --

1- ----

.1 - - - ---------------------

11 61 91 101 -- 11 --- -- -- 4 -------- -- -- --- -- -----

,1.1 . .1 311I 1 -.....--- -.....--- ......--- -.....--- -.....-- -- .....-- ------------------------- + -- - I+

-ESE- 1 .1 21 31 41 151 151 71 1 11 .*1 1 481 1I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------------------------------- +-- + - +I I-SE- I 11 8I 41 121_ 181 541 15! .1 *I .1 *1 1121 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - +-- - -

- - +--+ - - - - --------------------- - - -

+--- - -I I-SSE- 1 11 41 81' 181 391 331 21 1j .1 *1 .1 1061 IS 1 I 121 61 131 451 1171 5I 1! ii 21 *1 2021 I- - - - - - - - - - - - - - - - - --- ++ - -- - - - -++- - -- -- - -++ - - -- -- --------------------------

+---+-- I I-55W- I 81 31 151 101 33! i5ij 391 31 ii 21 *1 2651 I

I-SW-I

- - -+---- - - - - --+ - - - -++- - --

3I

- ----- - - -------------------------- 4 - ++ - +I

.I 11! 161 30I 7 1 141 41 21 21 2221 I-WSW- I 21 . 11+ 201 37 811 191 91 21 21 _ . .1 1881 I

I-w-

- - - - - - - - - - - -- +- - --- + --

+ -- + -- -+ - -I I 11 41 61 81 22! 381 131 21 21 21 .1 981 I- - - - - - - - - - - - - - --+- - - -+ - --- -- - - -+ - -- --+4 - - - - -- --+ --- ------------------------ 4 - ++ - +I I-WNW- I '1 5I 5I 5I 161 221 221 31 - 21 11 .1 821 I--- 4--.....--4+ t ------------------------------------------------------------ 4 - I I+-

I-NW- .I 11 41 41 61 ill 151 101 31 21 21 58!

I- - - - - - - - - - - - - - -- - - -+---- - - - - --+ - - - -++- - -- - - - -+ - --------------------------

-- + - ++ - +I I-NNW- I 11 . 1 ...

+ . . 31 101 41 21 31 1+ 271 I---------------------------------------------------------------------------------------------++ - + - + - +-. .I I-CALM- I 31 1 .I1 .1 .1 .1 1 .. .1 .1 .1 I ---- ---- -- -- ----- --- ---- ---------------- -- -- ---- ---- - -- --....- ---- +- .....- + ..-. -+..- + ..-.- + ..-.- +-.- I TOTAL I 231 55! 791 138! 2961 6571 2121 50o 181 181 5I 1551!

McGuire NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY F WIND SPEED CLASS I

- - --------------------------------------------- I I 0.45-1 0.75-l 1.00-1 1 .25-I 1.50-I 2.00-1 3.00-I 4.00-1 5.00-1 I 1 o.74 I 0.99 I 1.24 I 1.49 I 1.99 1 2.99 I 3.99 1 4.99 I 5.99 tTOTAL I I. + ......- + ......- + ... +-- -+- -- +----+--- +.- ...- +.....-I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I

- +------------ +- ......- +- ......- +-......+.-.....-+.- ... +.....-.+...-.-+-.- I SECTOR I I I I I I I I I I I

- I I I I I I I I I I I I-N- I 11 11 11 .1 11 21 11 .1 .1 71

+-------- +- . +- . + . +---+-+--------+------- .+.....-I l-NNE- I .. 1 1I .I *1 .1 I -I .1 i1

- +-- -+. ..- +-----+---- +----- .... I I-NE- I 1 11 1 "1 11 "l

1 .1 31

- - +----.---+-.....-.+.....-.-+-------......-+-- -- +----- ... .I

-E- I *1 41 11 .1 2 .I I

-1 7 I-ESE-

- 1I . 11

+--- ---

-1I. 2 1 11

-+--

.1

+-----

.1

... .I 41

-+.....---+--- +-....-- ...... - + ...... - +......-+....-.+---+----- ......

I-SE- I *1 21 *1 21 31 21 .1 .1 .1 91 I--- - -- - - - -- - - - - - - - - -- -- -- - - - - - -- - - ---------------------------------------- I I-SSE- I 21 31 21 71 ill 71 .1 11 .1 331 I-S- 21 ill 121 131 241 .481 21 "1 " 1121 1I- - - - - - - - -- - - -- --+ -- - -+ - ---------------- -- - - - - - -- - ------------------------ I 1-ssW- I 31 131 151 241 311 231 1i 11 .1 1111 I-SW 21 171 131 171 151 211 21 . .1 871

- +- -

+-- ----- -----

+--- +- -----......- +-......-- ----------- +.....- I l-WSW- 1 5I 121 141 191 271 271 41 .I 1 1081

- +---- - +-------+-..- .... +......-.-+...-.+-- - +----- .... .I l-w- 31 61 101 10j 141 161 11 11 .1 611

- +-- - -+-+----.-+- +---+----- -+-.....I I-WNW- I 41 31 51 21 81 41 . . 261

- ......----.....----.....- +--....--

+---+---+- ......- +....-..-+...- I I-NW- 1 I 31 31 11 1 .1 1 .1 11 101 I-NNW- I 11 31 1i .1 .1 11 .1 .1 .I 61

. .+- - -+ . . .+ -... .+-. . .+ -... .+ -... .+ -... .+ -... .+ -... .+ -....

I-CALM- 1 1 . 1 .1 . -.I . 1 .1 .1 11

+ +

- -+-+------ +......---......-- ----..... +...- ... I TOTAL 1 241 7 1 77I 981 1341 1561 161 31 11 5861

McGuire NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY G WIND SPEED CLASS I

I 1 0.45-I 0.75-I 1.00-I 1.25-I 1.s0-1 2.00-I 3.00-I 1 0.74 1 0.99 1 1.24 1 1.49 1 1.99 1 2.99 I 3.99 ]TOTAL

.------ +-......-+-.....+-. .+..-.-+_.--- +..-.+--- ....

NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO.

-- - - - - - - - - - - - -- - - - - -- ------------------------------------------- I

.ISECTOR

I I I I ---------------------- I I I I I I I-N- I I I -I I 'I I I I-I-- E- -- -- -- - - - - - - -I- - -*l .1 1I

- - - ------------------------------------- .1 11 I 21 I-E- I I ----------------------------------------------------------------- i1 21 .1 *l .l .1 I - 21 I II-SE- 1 -_-----+-..

1......----.....----------------------

.1 11 .1+-.. .+..-..+..-..+..-..I

.1 .1 I1 21 l-SSE- I 'I 21 ii -I 21 11 I1 1 I--

I-S- - - - - - - - - - - - - -- - - - - - -- - - - ----------------------------------

I 31 41 31 5l 101 21

+ -I

.1 271 I- - - - - - -- - - - - - -- - - - -- - - -- - -------------------------------------- I I-SSW- I 181 251 361 101 91 31 I 1011 I--- - - - - - - - - - - - - - - - - - - - -- - - - ---------------------------------- + - +I

-sw- 1 71 421 201 91 91 .I I 871 I - - - - - - - - - - - - - -- - - - - - - - - - - - ---------------------------------- + - +I I-wsw- I 9I il lo 80 s5 51 i 421 I - - - - - - -- - - - - - -- -- - - -+ - - -- - - --------------------------+I LW-w 21 91 4I 31 11 41 23 I- - - - -- -- -- - - - -- - - - -- - - - - - -------------------------------------- I I-WNW- 31 41 *I 31 .1 11 1Iill W 1 ..

+- .. .1 . . .1 . . +1 . . 1. . . 1. . . +1. ..... + ... .

I-------------------- ---------------------------------------- + - +I I-CALM- I i l . I .l .I .1 I i11 I- - - - - - - - - - - - - -- - - - -- - - - - - ----------------------------------- + - +I TOTAL 46 991 76l 361 361 131 i 3071

.I.-.- -- - - -- - - - -- - - -- - - - -- - - - -- - - - - - - - - -- - -- - - - - -- - --

McGuire NUCLEAR STN. METEOROLOGY (2008) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS ALL STABILITY CLASSES WIND SPEED CLASS I I I j---------------------------------------------------------------- --------------------------- I I 1 0.45-1 0.75-1 1.00-1 1.25-1 1.50-1 2.00-1 3.00-I 4.00-1 5.00-1 6.00-1 8.00-1>9.99 I I 0.74 1 0.99 1 1.24 1 1.49 1 1.99 I 2.99 1 3.99 I 4.99 I 5.99 I 7.99 1 9.99 1 M/S ITOTAL I- -. - . ---------- + ..-

+------- .- -.-+......- ....... + ....-..- + ...- ... + -...... + ....- + ..-- + ..- + ..-.

I NO. I NO. I NO. I NO. I NO. INO. I NO. I NO. INO. LNO. I NO. NO. I NO.

I--- -- -- -- -- -- -- --- -- -- -- -- - - -- -- - -- -- -- -- -- -- -- ------------------- +----- ------- +---- -- +---- ----- + -+ - I SECTOR I I I I I I I I I I I I I I I ---------------------- I I I I I I I I I I I I I I I-N- 31 s5 121 16f .691 911 sil 611 341 331 1 1 31 393I 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- -- --- - - --------

- - - - - - - - - ++ - - - - - ---- - ++ - +I------

I-NNE- . 21 2 1 131 '91 561 1251 1231 851 831 411 81 11 5581 I-NE- 1 31 11 61 171 621 1841 3371 2751 1391 281 71 .I 9591 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- -- --- ---------- - - - - - - - - -++ - - - - - - ---- ++ - +I------

-ENE- .1I 61 121 611 1541 1401 781 131 21 I *1 4661 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------------------------

+ ---- - - --

+--- -

I-E- 1

ill 41 81 41I 1051 1231 171 41 11 .I .1 3141 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- -------------------------------

+ ---- - ---- - - -I

-ESE- I 1 41 41 161 451 931 581 231 91 1t .I .1 2531 1......-+-......-+-......-+-......-+----------..............---. +--------------------- .I -

f-SE- I 41 101 121 271 521 1401 S99 61 21 11 .1 .1 313f 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------------------------- ----------------I I-SSE- I 51 141 191 401 98 931 221 21 ,I .I 1. 2931 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------ +- + -------

-- ----- I

-s- 1 61 291 251 511 1201 2431 391 ill 21 41 1 .1 5S301 1I- - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - -------------------------------------------- +I l-ssw- I 301 451 681 501 1081 2861 177f 801 411 141 .1 .1 8991 1I- - - - - - - - - - - - - - -- - - - - -- - - - -- - - - - - -- - - - - - -- --------------------------------------------- I I-sw- 1 131 651 Sol 481 831 2711 2861 1871 951 531 il 11 11631 l-WSW- 1 171 281 371 591 1301 2451 1141 601 431 371 6l 21 7781 1 - - - - - - - - - - - - - - -- - - - - - -- - - - - - - - - - - - ------------------------------

+---- - ----- -- - - - -I

-w- 61 221 261 311 661 1161 621 331 141 141 61 1i 3971 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------------------------

+ ---- - ---- - - -I I-WNW- 1 81 1i1 121 261 43l 701 581 4Sf 281 191 91 21 3311 1--a- - - - - - - - - - - - - - - - - - - - - ---- - - --------- -- -- -- -- -- -- -- -- -- ------------ - ---- - - -I I-NW- 1 i1 ill 181 17I 251 581 621. 511 4 631 381 21 3931 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -++- - - - - - - -++ - --------------------- ---- I I-NNW- I 31 101 141 161 301 481 521 461 45I 821 491 -101 4051 1 -------------------------- - --- - I I-CALM- 81 *1 1 1 .1 .1

I *I *I .1 8j 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------ -------------- ------ I TOTAL I 1091 268f 3261 4531 10891 23221 16631 10601 5991 3931 1491 221 84531

Attachment 5 Inoperable Monitoring Equipment

McGuire Nuclear Station Inoperable Monitoring Equipment (January 1, 2008 through December 31, 2008)

There were no SLC related effluent monitoring instruments out of service greater than the SLC limits for operability.

Attachment 6 Groundwater Protection Initiative

McGUIRE NUCLEAR STATION INFORMATION TO SUPPORT THE NUCLEAR ENERGY INSTITUTE (NEI)

GROUNDWATER PROTECTION INITIATIVE

ARERR Groundwater Well Data Section Rev. 1 Duke Energy implemented a Groundwater Protection Program in 2007. This program is designed to ensure timely and effective management of situations involving inadvertent releases of licensed material to ground water. As part of this program, McGuire Nuclear Station has sixty ground water monitoring wells. These wells are currently being sampled quarterly. All samples are being analyzed for tritium and gamma emitters, with selected wells being analyzed for Strontium 89 and 90. No gamma activity (other than naturally occurring radionuclides) or Strontium was identified in any of the well samples.

Results from sampling during 2008 confirmed existing knowledge of tritium concentrations in the site ground water (shown in the table below). No new areas for investigation were identified.

Results from sampling during 2008 are shown in the table below.

Avg. Tritium Conc. # of Well Name Well Location Conc.(pCi/1) Range Samples M-20 South of Hwg. 73 647 577-738 5 M-20R South of Hwg. 73 610 495-759 5 M-21 South of Hwg. 73 223 < - 229 5 M-22 South of Hwg. 73 176 <- 175 5 M-22R South of Hwg. 73 565 422 -ý857 5 M-23 South of Acs. Rd. -293 < - 293 5 M-30 WWCB < < 4 M-30R WWCB 251 208-282 4 M-31 Access road < < 5 M-32 Main entrance < < 4 M-34R Access road < < 4 M-34DR Access road 167 <- 167 4 M-35 Access road < < 5 M-42 U-2 Rx. Bldg. 1,160 970 - 1,390 4 M-48 U-2 SFP 818 769-879 3 M-48R U-2 SFP 808 747 - 884 4 M-48DR U-2 SFP 689 589-753 4 M-53 North of plant 1,140 1,040 - 1,200 4 M-55 North Admin. Bldg. 243 < - 312 4 M-59 U-2 Doghouse 819 645 - 991 4 M-60 MOC Parking 194 < - 194 5 M-62 S of RWT 251 < - 251 4 M-64 Rdwst. Bldg. 588 505 - 644 4 M-66 S of SSF 561 405-707 4 M-66R S of SSF < < 4 M-68 U-1 RMWST 1,073 843 - 1,280 4 M-70 U-1. SFP 361 301-405 4 M-70R U-1 SFP 252 169-315 4 M-70DR U-1 SFP < < 4

ARERR Groundwater Well Data Section Rev. 1 M-72 Rdwst. Trench 635 541 - 799 4 M-76 West of U-1 SFP 469 277 - 936 4 M-82 River 1,601 1,590 - 1,820 13 M-84 River 5,174 4,890 - 6,150 14 M-84R River 6,913 6,930 - 7,490 14 M-85 River 1,463 1,390 - 1,530 4 M-87 Landfarm 309 258 - 345 4 M-89 Landfarm 763 510 - 956 4 M-90 Landfarm 246 246 1 M-91 East of WC 294 242-356, 5 M-91R East of WC 276 185 - 543 5 M-92 N of WC Ponds 278 219-354 4 M-92R N of WC Ponds < < 4 M-93 North of IHUP 298 249 - 343 4 M-93R North of IHUP 330 276-446 4 M-94 SE of IHUP < < 4 M-95 Lower Parking 273 <- 385 4 M-95R Lower Parking < < 4 M-96 West Parking < < 4 M-96R West Parking < < 4 M-97 East Parking 245 < - 285 4 M-98 S of Admin. Bldg. < < 4 M-98R S of Admin. Bldg. < < 4 M-1OOR SE of WC 343 < - 393 4 M-101 SEofWC 282 / 174-358 4 M-102 SW of WC 7,895 7,610 - 8,200 4 M-103 South of WC 2,924 2,560 - 3,960 13 M-103R South of WC 2,058 1,740 - 3,010 13 M-104R West of WC 10,650 10,200 - 11,000 4 M-104DR West of WC 5,753 5,480 - 6,030 4 M-105 Landfarm 387 387 1 pCi/1 - pico curies per liter

< - less than minimum detectable activity, typically 250 pCi/liter 20,000 pCi/1 - the Environmental Protection Agency drinking water standard for tritium.

This standard applies only to water that is used for drinking.

1,000,000 pCi/i - the 10CFR20, Appendix B, Table 2, Column 2, Effluent Concentration

-limit for tritium.

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