Text

Annual Radioactive Effluent Release Report, 2008
	ML081430413
Person / Time
Site:	McGuire, Mcguire
Issue date:	04/24/2008
From:	Brandi Hamilton; Duke Energy Carolinas, Duke Energy Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML081430413 (64)
	v • d • e

BRUCE H HAMILTON hDuke Vice President EEnergy McGuire Nuclear Station Duke Energy Corporation MG01 VP / 12700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy.com April 24, 2008 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 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 2008 Offsite Dose Calculation Manual and the 2008 Process Control Program (PCP) Manual.

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.

H. Hamilton (Dog www. duke-energy.com

U. S. Nuclear Regulatory Commission April 24, 2007 Page 3 bxc: RGC File Master File ECO50-ELL

NRC Document Control Desk April 24, 2008 Page 2 cc: Mr. John F. Stang, NRC Project Manager Office of Nuclear Reactor Regulation Mail Stop 8-H4A Washington, D.C. 20555 Mr. Victor M. McCree, Acting 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 Mr. William Nestel INPO Records Center 700 Galleria Place, Suite 100 Atlanta, GA 30339-5957

Attachment 1 Radioactive Effluent Releases and Supplemental Information

McGUIRE NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 2007 through December 31, 2007)

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

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Gases

1. Total Release Ci 4.96E-01 4.16E-01 5.82E-01 6.53E-01 2.15E+00

2. Avg. Release Rate pCi/sec 6.38E-02 5.29E-02 7.32E-02 8.22E-02 6.81E-02 B. Iodine-131

1. Total Release Ci 2.57E-06 0.OOE+00 0.OOE+00 0,00E+00 2.57E-06

2. Avg. Release Rate pCi/sec 3.30E-07 0.OOE+00 0.OOE+00 0.OOE+00 8.14E-08 C. Particulates Half Life >= 8 da'yss

1. Total Release Ci 2.40E-05 7.37E-06 1.46E-06 1.03E-05 4.32E-05

2. Avg. Release Rate pCi/sec 3.09E-06 9.37E-07 1.84E-07 1.30E-06 1.37E-06 D. Tritium

1. Total Release Ci 4.05E+01 7.28E+01 3.70E+01 5.'41E+01 2.05E+02

2. Avg. Release Rate pCi/sec 5.21E+00 9.26E+00 4.66E+00 6.81E+00 6.49E+00 E. Gross Alpha Radioactivity

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

2. Avg. Release Rate pCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases

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

2. Iodines

- 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 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases

- No Nuclide Activities **

2. Iodines

- 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 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases

- No Nuclide Activities **

2. Iodines 1-131 Ci 2.57E-06 0. OOE+00 0. 00E+00 0. OOE+00 2.57E-06 Totals for Period... Ci 2.57E-06 0. 00E+00 0. OOE+00 0. OOE+00 2.57E-06

3. Particulates Half Life >= 8 days CO-58 Ci 1.70E-05 7.37E-06 1.46E-06 1. 03E-05 3.61E-05 CR-51 Ci 6.85E-06 0. 00E+00 0. OOE+00 0.OOE+00 6.85E-06 Totals for Period... Ci 2.38E-05 7.37E-06 1. 46E-06 1. 03E-05 4.29E-05

4. Tritium H-3 Ci 3.91E+01 7.05E+01 3.69E+01 5.40E+01 2. OOE+02 Totals for Period;.. Ci 3.91E+61 7.05E+01 3. 69E+01 5.40E+01 2. OOE+02

5. Gross Alpha Radioactivity

- No Nuclide Activities **

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH ,MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR3 QTR4 YEAR

1. Fission and Activation Gases AR-41 Ci 4.61E-01 3.26E-01 5.63E-01 6.36E-01 1. 99E+00 C-11 Ci 0.00E+00 0. 00E+00 0. 00E+00 1. 34E-05 1.34E-05 KR-85 Ci 2.93E-02 7.22E-02 0. 00E1+0 0.00E+00 1. 01E-01 KR-85M Ci 0.00E+00 7.86E-05 0. 00E+00 1.37E-05 9.22E-05 KR-88 Ci 0.OOE+00 1.06E-04 0. 00E+00 1.86E-05' 1.25E-04 XX-133 Ci 4.,87E-03 1. 38E-02 1. 77E-02 1.70E-02 5.33E-02 XE-133M Ci 0.OOE+00 2. 81E-04 0. 00E+00 2.55E-05 3.06E-04 XE-135 Ci 1.09E-03 3.15E-03 7.03E-04 2.79E-04 5.22E-03 Totals for Period... Ci 4.96E-01 4.16E-01 5.82E-01 6.53E-01 2.15E+00

2. lodines

- No Nuclide Activities **

3. Particulates Half Life >= 8 days CL-38 Ci .07E-07 0. OOE+OQ 0.00E+00 0.00E+00 2.07E-07

,Totals for Period... Ci 2.07E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-07

4. Tritium H-3 Ci 1.38E+00 2.36E+00 1.19E701 1.82E-01 4.04E+00.

Totals for Period... Ci 1.38E+00 2.36E+00 1.19E-01 1.82E-01 4.04E+00

5. Gross Alpha Radioactivity

- No Nuclide Activities **

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 1.88E-02 1.98E-02 1.28E-02 9.81E-03 6.12E-02 2.-Average Diluted Concentration

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

b. Batch Releases pCi/ml 2.48E-11 2.23E-11 1.25E-11 1.02E-11 1.69E-11 B. Tritium

1. Total Release Ci 6.68E+02 4.38E+02 2.45E+02 2.82E+02 1.63E+03

2. Average Diluted Concentration

a. Continuous Releases pCi/ml 1.48E-08 3.59E-08 2.08E-08 2.44E-08 2.03E-08

b. Batch Releases pCi/ml 8.80E-07 4.92E-07 2.40E-07 2.94E-07 4.50E-07 C. Dissolved and Entrained Gases

1. Total Release Ci 0.OOE+00 0. 00E+00 0.OOE+00 0.OOE-I00 0. OOE+00

2. Average Diluted Concentration

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

b. Batch Releases pCi/ml 0.00E+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 0.00E+00 0.00E+00

2. Average Diluted Concentration

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

b. Batch Releases pCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+60 0.OOE+00 E. Volume of Liquid Waste

1. Continuous Releases liters 7.02E+07 6.08E+07 5.96E+07 5.79E+07 2.48E+08

2. Batch Releases liters 1.81E+06 2.80E+06 1.15E+06 6.38E+05 6.41E+06 F. Volume of Dilution Water

1. Continuous Releases liters 7.48E+10 2.22E+10 2.07E+10 1.26E+10 1.30E+lI

2. Batch Releases liters 7.57E+lI 8.88E+lI 1.02E+12 9.59E+Il 3.62E+12

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID EFFLUENTS - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products

- No Nuclide Activities **

2. Tritium H-3 Ci 1.11E+00 8. OOE-01 4.32E-01 3.09E-01 2.65E+00 Totals for Period... Ci 1.11E+00 8. OOE-01 4.32E-01 3.09E-01 2.65E+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 1/1/07 TO 1/1/08 LIQUID EFFLUENTS - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2007 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR I. Fission and Activation Products AG-108M Ci 0.OOE+00 0.OOE+00 7.11E-06 0.OOE+00 7.11E-06 BA-140 Ci 0.OOE+00 9.70E-06 0.OOE+00 0.OOE+00 9..70E-06 BE-7 Ci .3.54E-05 0.OOE+00 0.OOE+00 0.OOE+00 3.54E-05 CO-57 Ci 5.01E-06 2.89E-06 0.OOE+00 5.10E-06 1.30E-05 CO-58 Ci 3.08E-03 5.67E-03 6.19E-04 5.50E-04 9.92E-03 CO-60 Ci 1.69E-03 7.40E-04 2.62E-04 6.05E-04 3.29E-03 CR-51 Ci 6.74E-05 2.67E-04 3.83E-05 0.OOE+00 3.72E-04 CS-134 Ci 1.19E-03 1.69E-04 5.71E-04 4.12E-04 2.34E-03 CS-137 Ci 3.61E-03 9.70E-04 2.02E-03 1.48E-03 8.09E-03 FE-59 Ci 0.OOE+00 2.07E-06 0.OOE+00 0.OOE+00 2.07E-06 1-131 Ci 2.04E-06 0.OOE+00 0.OOE+00 0.OOE+00 2.04E-06 MN-54 Ci 1.44E-04 4.85E-05 1.54E-05 6.58E-05 2.74E-04 NB-95 Ci 0.OOE+00 4.93E-05 3.03E-06 0.OOE+00 5.23E-05 SB-122 Ci 1.87E-05 4.03E-06 5.30E-06 0.OOE+00 2.80E-05 SB-124 Ci 7.92E-04 3.48E-04 1.22E-04 1.30E-05 1.28E-03 SB-125 Ci 8.14E-03 1.15E-02 9.13E-03 6.68E-03 3.54E-02 SN-113 Ci 0.OOE+00 1.10E-06 0.OOE+00 0.OOE+00 1.10E-06 ZR-95 Ci 0.OOE+00 2.22E-05 0.OOE+00 0.OOE+00 2.22E-05 Totals for Period... Ci 1.88E-02 1.98E-02 1.28E-02 9.81E-03 6.12E-02

2. Tritium H-3 Ci 6.66E+02 4.37E+02 2.45E+02 2.82E+02 1.63E+03 Totals for Period... Ci 6.66E+02 4.37E+02 2.45E+02 2.82E+02 1.63E+03

3. Dissolved and Entrained Gases

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

4. Gross Alpha Radioactivity

- No Nuclide Activities **

McGUIRE NUCLEAR STATION SUPPLEMENTAL INFORMATION

McGUIRE NUCLEAR STATION 2007 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS - PER UNIT A. NOBLE GASES - AIR DOSE B. LIQUID EFFLUENTS - DOSE

1. CALENDAR QUARTER - GAMMA 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

1. 2. 73E+02 = TOTAL NUMBER OF BATCH RELEASES

2. 2. 91E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.

3. 6.38E+03 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.

4. 1. 07E+02 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.

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

6. 1. 82E+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. 00E+00 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

VI. ABNORMAL RELEASES A. LIQUID

1. NUMBER OF RELEASES = 0

2. TOTAL ACTIVITY RELEASED (CURIES) = 0 B. GASEOUS

1. NUMBER OF RELEASES = '2

2. TOTAL ACTIVITY RELEASED (CURIES) = 1.43E-2 (see attachment for additional information)

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 = + 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, 2007 through December 31, 2007)

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 10 miles of McGuire for the calendar year of this report to show conformance with 40 CFR 19q. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 1 st Quarter 2007 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS==---= Quarter 1 2007 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Ql - Maximum Organ Dose TEEN THYROID 4.82E-02 1.50E+01 3.21E-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 2007 Dose Limit % of Period-Limit (mrad) (mrad) Limit Ql - Maximum Gsmma Air Dose 1.04E-02 1.00E+61 1.04E-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 Ql - Maximum Beta Air Dose 3.81E-03 2.OOE+01 1.90E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.59E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2007

- IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS=-== Quarter 2 2007 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose TEEN LUNG 8.65E-02 1.50E+01 5.77E-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 i. OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS ------------- Quarter 2 2007 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose 7.35E-03 1.OOE+01 7.35E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.95E+01 Q2 - Maximum Beta Air Dose 2.98E-03 2.OOE+01 1.49E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 8.67E+01 KR-85 1.14E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2007 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS=--=== Quarter 3 2007 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose TEEN LUNG 4.40E-02 1.50E+01 2.93E-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.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS= Quarter 3 2007 Dose, Limit % of Period-Limit (mrad) (mrad) Limit Q3 - Maximum Gamma Air Dose 1.27E-02 1.00E+01 1.27E-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 4.51E-03 2.OOE+01 2.25E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.89E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS'ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4t Quarter 2007 IODINE, H3, AND PARTICULATE DOSE LIMIT'ANALYSIS==...= Quarter 4 2007 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose TEEN LUNG 6.43E-02 1.50E+01 4.29E-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 2007 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Gamma Air Dose 1.43E-02 1.OOE+01 1.43E-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 Q4 - Maximum Beta Air Dose 5.08E-03 2.OOE+01 2.54E Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage 9.-91E+01 AR-41

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2007 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS====-- Annual 2007 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose TEEN LUNG 2.43E-01 3.00E+01 8.10E-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=------ -------- Annual 2007 Dose Limit % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Gamma Air Dose 4.46E-02 2.OOE+01 2.23E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.98E+01 Yr - Maximum Beta Air Dose 1.64E-02 .4.00E+01 4.09E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.61E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 1 st Quarter 2007

-- BATCH LIQUID RELEASES Quarter 1 2007 .....

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD LIVER 1. 20E-01 1.OOE+01 1.20E+00 Ql - Total Body Dose CHILD 9.59E-02 3.OOE+00 3.20E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.54E+01 CS-137 1. 75E+01 CS-134 7.07E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.48E+01 CONTINUOUS LIQUID RELEASES (WC) --- Quarter 1 2007 =-====

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Ql - Maximum Organ Dose CHILD LIVER 1.53E-03 1.00E+0*1 1.53E-02 Ql - Total Body Dose CHILD 1.53E-03 3.OOE+0( ) 5.11E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater 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 1.00E+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2007

-- BATCH LIQUID RELEASES - ==ý___ Quarter 2 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 5.73E-02 1.00E+01 5.73E-01 Q2 - Total Body Dose CHILD 5.23E-02 3.OOE+00 1. 74E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 8. 96E+01 CS-137 8.51E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.81E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 2 2007 .--

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 3.75E-03 1.OOE+01 3.75E-02 Q2 - Total Body Dose CHILD 3.75E-03 3.OOE+00 1.25E-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 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2007

. BATCH LIQUID RELEASES Quarter 3 2007 =-==

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 3.73E-02 1.OOE+01 3.73E-01 Q3 - Total Body Dose ADULT 2. 80E-02 3.OOE+00 9.34E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 6.78E+01 CS-137 2.39E+01 CS-134 8.29E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 6.78E+01 CS-137 2.18E+01 CS-134 .1.04e+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 3 2007 . ...

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 2.20E-03 1.OOE+01 2.20E-02 Q3 - Total Body Dose CHILD 2.20E-03 3.OOE+00 7.32E-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 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4t Quarter 2007 BATCH LIQUID RELEASES Quarter 4 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 4.04E-02 1.00E+01 4.04E-01 Q4 - Total Body Dose CHILD 3.26E-02 3.OOE+00 1.09E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7..68E+01 CS-137 1.73E+01 CS-134 5.88E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.52E+01

===CONTINUOUS LIQUID RELEASES (WC) ----------- Quarter 4 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose' CHILD LIVER 2.57E-03 I.OOE+01 2.57E-02 Q4,- Total Body Dose CHILD 2.57E-03 3.OOE+00 8.57E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater 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 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/07 TO 1/1/08 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2007

=-- BATCH LIQUID RELEASES Annual 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (orem) Limit CHILD Yr - Maximum Organ Dose LIVER 2.42E-01 2.OOE+01 1.21E+00 CHILD Yr - Total Body Dose 1.97E-01 6.00E+00 3.29E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7. 76E+01 CS-137 1. 65E+01 CS-134 5.85E+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 2007 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 8.50E-03 2.OOE+01 4.25E-02 Yr - Total Body Dose CHILD 8.50E-03 6.OOE+00 1.42E-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 - ---

H-3 1.00OE+02

Attachment 2 Solid Waste Disposal Report

REPORT PERIOD McGUIRE NUCLEAR STATION Attachment I JANUARY - DECEMBER 2007 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 2 2 HIC 55.89 1.58 B 2.18E+02 (G) dewatered mechanical filter media none (H) dewatered mechanical filter media (brokered) 4 25 HIC 131.94 3.74 C 1.81 E+02 (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) 16 78 DBP 4723.48 133.71 A/U 9.310E-01 (B) sealed sources/smoke detectors none (C) sealed sources none (D) irradiated components none Totals 22 105 4911.31 139.03 3.999E+02 2/25/2008

MCGUIRE NUCLEAR SITE

SUMMARY

OF MAJOR RADIONUCLIDE COMPOSITION 2007 1.

Type of waste Niuclide % Abundance 1 Waste

i: frow s t ,-,: >'*

A. Dewatered Powdex Resin (brokered) No shipments in 2007 B. Dewatered Powdex Resin No shipments in 2007 C. Dewatered Bead Resin (brokered) No shipments in 2007 D. Dewatered Bead Resin No shipments in 2007 E. Dewatered Radwaste System Resin (brokered) No shipments in 2007 F. Dewatered Primary Bead Resin (brokered) 2007 - 20 Nuclide %Abundance Mn-54 2.18 Co-57 .37 Co-58 .90 Co-60 17.60 Cs-137 3.32 Cs-134 *.76 Ni-63 56.74 Fe-55 17.49 Sb-125 .30 H-3 .03 Sr-90 .04 Be-7 .28 2007- 35 Nuclide %Abundance Mn-54 4.29 Co-57 .59 Co-58 .65 Co-60 17.71 Cs-1 37 2.61 Cs-1 34 .81 Ni-63 54.80 Fe-55 18.29 H-3 .02 Sr-90 .03 Sb-1 25 .19

G. Dewatered Mechanical Filter Media H. Dewatered Mechanical Filter Media (brokered) 2007- 01 Nuclide %Abundance Mn-54 .36 Co-57 .01 Co-58 .02 Co-60 32.08 Cs-1 37 .01 Fe-55 39.63 Ni-63 27.36 H-3 .02 C-1 4 .31 Sb-1 25 .08 Ag-110m .04 Ce-1 44 .01 Pu-241 .06 2007-02 Nuclide %Abundance Mn-54 1.16 Co-57 .03 Co-58 .01 Co-60 28.16 Cs-1 37 ,01 Fe-55 54.91 Ni-63 15.23 H-3 .01 C-14 .15 Sb-125 .13 Ag-108m .01 Ag-11Om .1 Ce-144 .01 Zn-65 .01 Pu-241 .05 2007-33 Nuclide %Abundance Mn-54 5.47 Co-57 .29 Co-58 1.68 Co-60 18.68 Cs-1 37 .36 Cs-134 .03 Fe-55 41.45 Ni-63 11.27 H-3 25.93 C-1 4 .03 Sb-125 .29 Ce-144 .02 2

2007-37 Nuclide %Abundance Mn-54 5.47 Co-57 .29 Co-58 1.68 Co-60 26.03 Cs-1 37 1.52 Cs-134 .40 Fe-55 48.50 Ni-63 13.88 C-14 .59 Sb-125 .65 Ce-1 44 .11.

Zr-95 .06 Sn-113 .03 Zn-65 .30 Tc-99 .47 I. Solidified Waste No shipments in 2007

2. Dry SolidW \Nst:-

A. Dry Active Waste (compacted) Compaction no longer performed on-site.

Dry Active Waste (non-compacted) No shipments in 2007 Dry Active Waste (brokered/compacted) No shipments in 2007 Dry Active Waste (brokered/non-compacted) 2007- 03 Nuclide %Abundance Mn-54 1.15 CO-57 .06 Co-58 6.89 Co-60 24.01 Cs-137 1.28 Fe-55 44.48 Ni-63 17.32 C-14 2.28 Sb-125 .77 Zr-95 .43 Nb-95 1.14 Sr-90 .18

'I

2007-04 Nuclide %Abundance Co-57 .06 Mn-54 1.11 Co-58 5.21 Co-60 24.73 Cs-137 1.33 Fe-55 45.24 Ni-63 18.04 C-14 2.37 Zr-95 0.32 Sb-125 .78 Sr-90 .19 Nb-95 .62 2007- 06 Nuclide %Abundance Co-57 .06 Mn-54 1.15 Co-58 6.68 Co-60 24.10 Cs-137 1.29 Fe-55 44.55 Ni-63 17.45 C-14 2.29 Zr-95 .42 Sb-125 .77 Sr-90 .18 Nb-95 1.06 2007-11 Nuclide %Abundance Co-57 .06 Mn-54 1.15 Co-58 6.72 Co-60 24.10 Cs-137 1.28 Ni-63 17.38 Fe-55 44.58 Zr-95 .42 C-14 2.29 Sb-125 .77 Sr-90 .18 Nb-95 1.07 2007- 12 Nuclide %Abundance Co-57 .06 Mn-54 1.15 Co-58 6.82 Co-60 24.07 Cs-137 1.28 Fe-55 44.51 Ni-63 17.34 C-14 2.28 Zr-95 .43 Sb-125 .76 Sr-90 .18 Nb-95 1.10 4

2007-15 Nuclide %Abundance Co-57 .06 Mn-54 1.15 Co-58 6.88 Co-60 24.02 Cs-137 1.28 Fe-55 44.47 Ni-63 17.34 C-14 2.28 Zr-95 .43 Sb-1 25 .77 Sr-90 .18 Nb-95 1.13 2007- 17 Nuclide %Abundance Co-57 .06 Mn-54 1.15 Co-58 6.95 Co-60 24.02 Cs-137 1.28 Fe-55 44.40 Ni-63 17.31 C-14 2.28 Zr-95 .44 Sb-125 .76 Sr-90 .18 Nb-95 1.16 2007- 22 Nuclide %Abundance Co-57 .06 Mn-54 1.16 Co-58 7.26 Co-60 23.88 Cs-137 1.27 Fe-55 44.26 Ni-63 17.18 C-14 2.26 Zr-95 .46 Sb-1 25 .76 Sr-90 .18 Nb-95 1.27 2007- 26 Nuclide %Abundance Co-57 .06 Mn-54 1.11 Co-58 5.08 Co-60 24.76 Cs-137 1.33 Fe-55 45.31 Ni-63 18.09 C-14 2.38 Zr-95 .31 Sb-125 .78 Sr .19 Nb-95 .60 5

2007- 32 Nuclide %Abundance Co-57 .06 Mn-54 1.12 Co-58 5.48 Co-60 24.66 Cs-137 1.32 Fe-55 45.13 Ni-63 17.88 C-14 2.36 Zr-95 .33 Sb-125 .78 Sr-90 .19 Nb-95 .69 2007- 23 Nuclide %Abundance Co-57 .06 Mn-54 1.16 Co-58 7.19 Co-60 23.90 Cs-137 1.27 Fe-55 44.31 Ni-63 17.20 C-14 2.26 Zr-95 .45 Sb-125 .76 Sr-90 .18 Nb-95 1.25 2007- 29 Nuclide %Abundance Co-57 .06 Mn-54 1.16 Co-58 7.21 Co-60 23.92 Cs-137 1.27 Fe-55 44.24 Ni-63 17.22 C-14 2.27 Zr-95 .45 Sb-125 .76 Sr-90 .18 Nb-95 1.25 2007- 34 Nuclide %Abundance Co-57 .06 Mn-54 1.14 Co-58 6.13 Co-60 24.34 Cs-137 1.30 Fe-55 44.85 Ni-63 17.64 C-14 2.32 Zr-95 .38 Sb-125 .77 Sr-90 .18 Nb-95 .88 6

2007- 36 Nuclide %Abundance Co-57 .06 Mn-54 1.13 Co-58 5.83 Co-60 24.45 Cs-137 1.31 Fe-55 45.06 Ni-63 17.72 C-14 2.34 Zr-95 .36 Sb-125 .77 Sr-90 .18 Nb-95 .79 2007- 38 Nuclide %Abundance Co-57 .06 Mn-54 1.14 Co-58 6.57 Co-60 24.15 Cs-137 1.29 Fe-55 44.63 Ni-63 17.47 C-14 2.30 Zr-95 .41 Sb-1 25 .77 Sr-90 .18 Nb-95 1.02 2007- 39 Nuclide %Abundance Co-57 .06 Mn-54 1.15 Co-58 7.07 Co-60 23.93 Cs-137 1.27 Fe-55 44.37 Ni-63 17.27 C-14 2.27 Zr-95 .45 Sb-125 .76 Sr-90 .18 Nb-95 1.20 B. Sealed Sources No shipments in 2007 C. Sealed Sources/Smoke Detectors No shipments in 2007 D. Irradiated Components No shipments in 2007 7

Attachment 3 Unplanned Offsite Releases

McGUIRE NUCLEAR STATION UNPLANNED RELEASES (January 1, 2007 through December 31, 2007)

There were two unplanned gaseous radioactive releases to the environment in 2007. There were no unplanned liquid radioactive effluent releases to the environment in 2007.

June 18,2007 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 to the Unit 1 Vent Reference PIP M-07-3543 Event Summary:

See referenced PIP for details.

On June 14, 2007 09:40 to 12:02 hours, a normal WGDT-A release was in progress to the Unit 1 Vent. Later in the release a pressure drop of 5 psi from WGDT-E was observed. The WGDT-A release was secured at 12:02 hrs. From trend analysis of 1 EMF 50, increased counts were seen in two discreet spikes above normal. 1 EMF 50 trip 2 actuation (auto release termination) was not reached. No off site release limits were challenged.

1.3E-2 curies of fission and activation gas (noble gas) was released to the unit 1 vent during this event. The source of the noble gas was determined to be due to leak-by from 1 WG-98 (E in-service WGDT sample isolation valve) into the WGDT-A release discharge line.

Sequence of events:

On 6/13/07 WGDT-A was sampled for a planned release on 6/14/07.

6/14/07 09:40 WGDT-A release started. A normal expected count per min (cpm) was seen on 1 EMF 50 and unit vent monitor 1 EMF 36.

10:00 1 EMF 50 trend shows increase cpm from - 8400 cpm to 18,600 cpm which lasts until 11:00hrs. 1

EMF 50 cpm return to normal.

11:20 1 EMF 50 cpm shows increase to 19,000 cpm.

12:02 release secured by Chemistry.

Chemistry reported 5 psi pressure drop (204 ft3) released from WGDT-E to RP.

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

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

The total Noble gas activity released was reported on (GWR) Gaseous Waste Release # 2007051.

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 doserate to the Total Body, Skin, Gamma Air, and Beta Air were all less than one tenth of one percent (<0.1%) 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

Decemner 06, 2007 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 to the Unit 1 Vent Reference PIP M-07-6220 Event Summary:

See referenced PIP for details.

On December 06, 2007 09:43 to 09:44 hours, a normal WGDT-C release was initiated to the Unit 1 Vent. At initiation of the release a high rad trip occurred on OEMF-50immediately terminating the release. While investigating the trip actuation a pressure drop of -1 psi from WGDT-E (in-service tank) was observed and a pressure increase of-1 psi was seen in WGDT-C. Attempts to release WGDT-C were terminated. From trend analysis of 1 EMF 50, increased counts were seen from one -66,000 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 1.27E-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 was determined to be due to leak-by from 1 WG-98 (E in-service WGDT sample isolation valve) into the WGDT-C tank and discharge line.

Sequence of events:

On 12/5/07 WGDT-C was sampled for a planned release on 12/6/07.

12/6/07 09:43 WGDT-C release started.

09:44 An instantaneous spike was seen on I EMF 50 of- 66,000 cpm and the release was auto terminated.

12:02 release secured by Chemistry.

Chemistry reported -0.2 psi pressure drop (8.2 ft3) released from WGDT-E to Unit I Vent.

0 WGDT-E sampled to account for activityreleased to the unit I vent.

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

The total Noble gas activity released was reported on (GWR) Gaseous Waste Release # 2007088.

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 doserate to the Total Body, Skin, Gamma Air, and Beta Air were all less than three tenths of one percent (<0.3%) 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 2007 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. 2007 McGuire 40CFR190 Effluent Dose Summary 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 = 4.40E-01 mrem Maximum Location: 0.5 Mile, East-Northeast Sector Critical Age: Adult Gas non-NG Contribution: 55%

Gas NG Contribution: 4%

Liquid Contribution: 41%

Maximum Organ (other than TB) Dose = 4.57E-01 mrem Maximum Location: 0.5 Mile, East-Northeast Sector Critical Age: Child Critical Organ: Liver Gas Contribution: 47%

Liquid Contribution: 53,%

II. 2007 McGuire 40CFR190 ISFSI Dose Summary Direct and air-scattertradiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at McGuire have been calculated and documented in the "McGuire Nuclear Site I0CFR72.212 Written Evaluations" report. The maximum dose rate to the nearest resident from the McGuire ISFSI is conservatively calculated to be 9.92 mrem/year.

The attached excerpt from the "McGuire Nuclear Site-10CFR72.212 Written Evaluations" report is provided to document the method used to calculate the McGuire ISFSI 9.92 mrem/year dose estimate.

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

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

Evaluation Historical TLD Monitoring The following table documents the actual radiological dose in rems at the owner controlled fence on top of the berm overlooking the ISFSI (Lotus Notes from Mary J. Foreman to Norman T. Simms, dated June 15, 2004). 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.

Location# 3Q '02 4Q '02 IQ '03 2Q '03 3Q '03 4Q '03 1Q '04 76 0.032 0.036 0.042 0.055 0.056 0.043 0.058 77 0.020 0.028 0.028 0.039 0.036 0.035 0.043

of Days 91 92 91 92 98 83 98 Location # 76 indicates the greatest dose of 0.058 reins during a 98 day period in the first quarter of 2004. This is equivalent to 0.0247 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 mremi per hour. A normalization value is derived by dividing the actual dose by the calculated dose, which is 0.0247/0.744

= 0.0332. (A recent Lotus Notes from Mary J. Foreman to N.T. Simms, dated April 24, 2006 indicates that the dose at Location # 76 is 0.044 rems for a period of 89 days during the IQ '06. Ten TN-32 casks and nine NAC UMS casks were on the ISFSI pad, but for simplicity and conservatism the 1Q '04 value will continue to be used. 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 IOCFR72.104(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 3 For McGuire, compliance with this regulation will also assure compliance with 40 CFR Part 190.

McGuire Nuclear Site (NAC UMS) Page 40 of 58 10CFR72.212 Written Evaluations, Rev. 2

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 = 0.0156e0 0 11 2x for gammas and y = 0.0274e-0O0 129x for neutrons, where y is dose rate (mrem/hr) and x is distance (meters), applicable from 20 to 1000 meters. Likewise, the best-fit empirical equation for total dose rate (direct and skyshine) as a function of distance is y = 492.69x 688 for gammas andy =

166.95x-2.0616 for neutrons, where y is dose rate (mrem/hr) and x is distance (meters), applicable from 20 to 80 meters. Based upon conservative engineering judgement, 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 and combined dose rates are located in Table 6-6 on page

14. 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 (8750 hours0.101 days 2.431 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 9.9 mrem and the dose due to McGuire power generation is 3 mrem per year for a total dose of 12.9 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 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.

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

McGuire Nuclear Site (NAC UMS) Page 41 of 58 10CFR72.212 Written Evaluations, Rev. 2

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.

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 40CFR190.10(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 12.9 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 10CFR72.106(c). Since the public is permitted access into the controlled area at McGuire, the dose rate must be below 2 mrem per hour and 6

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 6 10CFR20.1301(b). See also 10CFR20.1301(a)(2).

McGuire Nuclear Site (NAC UMS) Page 42 of 58 IOCFR72.212 Written Evaluations, Rev. 2

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 0.28 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 residence time of 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months , is determined to be. 5.79 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 24 NAC UMS casks meets the radiological requirements of 10CFR72.104, 10CFR20.1301 and 40CFR190.

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) / (98 days X 24 hrs/day) 0.0247 mrem/hr Calculated dose = 0.744 mrem/hr (see "top of berm at owner controlled fence". below)

NF = 0.0247/0.744 = 0.0332 Due to the amount of conservatisms utilized in the computer models, the actual measured dose at the owner controlled fence is only 3% of the calculatedvalues.,

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 mrerm/hr.

McGuire Nuclear Site (NAC UMS) Page 43 of 58 10CFR72.212 Written Evaluations, Rev. 2

(10) Casks X 7.443 E-0 2 mrem/hr = 0.744 mrem per hour Actual measured dose rate for the first ten casks stored in the ISFSI = 0.0247 mrem per hour 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 (2X) 2X6 Array NAC UMS Casks (calculated) 0.0247 mrem per hr + 2(0.128) mrem per hr = 0.2807 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"03 mrem/hr.

(10) Casks X 8.24 E-0 3 mremrrhr X 150 hrs (residence time/yr) = 12.36 mrem per year Normalized actual dose = 0.0332 X 12.36 mrem/yr = 0.410 mrem per year Total expected dose for ten TN-32A casks (actual) 0.410 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 Site (NAC UMS) Page 44 of 58 10CFR72.212 Written Evaluations, Rev. 2

Total Expected Dose at Waterway on Other Side of Berm Ten TN-32A Casks (actual) plus (2X) 2X6 Array NAC UMS Casks (calculated) 0.410 mrem per year + 2(2.69) mrem per year = 5.79 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 0 4 mrem/hr.

(10) Casks X 2.48 E-0 4 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 = 0.0332 X 21.7 mrem/yr = 0.720 mrem / yr Total expected dose for ten TN-32A casks (actual) 0.720 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.

t Total Expected Dose at Exclusion Area Boundary Ten TN-32A Casks (actual) plus (2X) 2X6 Array NAC UMS Casks (calculated) 0.720 mrem per year + 2(4.6) mrem per year = 9.92 mrem per year McGuire Nuclear Site (NAC UMS) Page 45 of 58 10CFR72.212 Written Evaluations, Rev. 2

McGUIRE NUCLEAR STATION 2007 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 (2007) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES.BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY A PASQUILL STABILITY A-WIND SPEED CLASS -I 0.75-1 1.00-1 1.25-1 1.50- 2.00-1 3.00-j 4.00-1 5.00-1 6.00-I 8.00-1>9.99 0.99.1 1.24 1 1.49 1 1.99 1 2.99 1 3.99 I 4.99 I 5.99 I 7.99 I 9.99 1 M/S TOT'AL NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. NO. I NO. I NO. NO).

.....- + ... . .... + .. .. + .... . ... ... . .... + .. .. + ....---------....-.- + ...- .. I SECTOR I I* lII I I I I

I I I I I I

-N- ii 1 sl 12 1 31 I .I .I 51 11 271

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

+ - + - + - + - +

-NNE- I I .I 21 17 1 14 1 1 .I I 1 -I 361

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

+ -. .+-. .+.- . . +- -+- ----- -+I 491

-NE- 1 I I .1 9 251 9j 51 i .I *1

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

- ENE - 1 *1 I 1I i l 261 191 5l i1 'I 641

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

-E-1 I1 I l 61 121 12 11 .1 .I 311

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

-ESE- 1 I I .1 1 5 91 21 .1 1 .I 161

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

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

+ .1 31 51

-SSE- 1 .1 1 *1 21 5s .1 .1 .1 .1 .1

-- - - - -+ - - - -++ * - - -- - - - - - - ----.-- -- ---+ ------------ - -+ - - - -+ - - -+ - - ----

--- +- +

+- - +--- - - I 1 .1 .1 .1 31 91 21 211 1 .21 1 121

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

+- +- .. + .. - + ... - +...+-------+--:--+

+- + -. +-.+-.+-. +- . 351

-SW-1 .1 1 .1 21 191 91 51 .1 -I .1

.1 801

--- - - -.1 .1- -. .-+L.. ..-- - -. . ..---. . ..--- -. 251. ..--- -.. 26I 211 . -..--11. ..--

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

21,

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

-WSW- -I

.1 .1 1 21 351 341 101 21 31 11 881 1 1I . 21 91 151 91 11 -1.1 . 371

-WNW- 161

-NW- I1 - 21 41 31 .i 1 51 21 'I 41 201

. + ---- --- +

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

4-- .1-1 +- 11 25!

I 31 41 10o

+ . . . . . + . . . . . + . . . . . + . . . . -- . __- ___+-. . . . .+ . . . . . + . . . . . +

__- . . . .+ . . . .+ . . . .+ . . . .

TOTAL I 11 41 171 1021 214I 1231 491 5 1 11i 61 5441

McGuire NUCLEAR STN. METEOROLOGY (2007) 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 10.75-i 1.00-i 1.25-1 1.50-F 2.00-F 3.00-i 4.00-I 5.00-F 6.00-I 8.00-1>9.99 1 F 1 0.99 1 1.24 1 1.49 1 1.99 1 2.99 F 3.99 1 4.99 1 5.99 F 7.99 1 9.99 1M/S ITOTAL I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. NO. F I----------------------------- -+- ------------------------------------------- I SECTOR I A I l F F I F F I F I ---------------------- F F F I-N- I .1 .1 1F 131 141 81 21 5F 91 81l1 601 F- - - - - - - - - - - - - - -- - - -- - - - -- - - - --------------------------------------- + - -- -F-- --

-NNE- 1I 2F1 1 251 211 91 71 91 41 F 93 F----- ---- ---- ---- ---- ---- ---- ---- ---- ---- ---- ---- ------------------------------ + + -

F-NE- F F

.1 21 8F 151 101 131 iF 21 F .l 6I F ---------------- --- --- --- --- ----------------------------------

++ -- --- --

+-F--

F-ENE- F .F F

SF isl 121 41 21 1 .1 41 1w- - - - - - - - - - - - - - - - - - - - - - - - - - --- ---- - - - - - - - - - ---- ------ -------+ ------- -

F-E-

I F1 F 121 F .1 I . F *F 221 F --- --------- ---- - -- --- -------------

-- --- ---------------------------- -- +--F--

-ESE- I I1 1 1 F .' .' -F 8F I ---------------- --- --- --- --- ---------------------------------------- -- +-F---

I-SE- I *1 .1 *F F 51 21 .1 I - .F 8 I ------------------------- r-------------------------------------+------ - F----

F-SSE- F F *F 1I 21 31 31 -F - .F 9F F ------------------------------------------------------------------

Fs .l

+ - +- -F-- --

F .I 3 131 F .F F .I .1 17 I - - - - - - - - - - - - - - -- -- - - - - - -------- - - - - - - - - - ---------------------------- ------ - I I-SsW- F .1

11 21 201 13 41 3F .1 .1 43 I - - - - - - - - - - - - - - -- -- - - - - - -------- - - - - - - - - - ---------------------------- ------ - I I-sw- . 11 3F 131 331 20F 1oF 61 *1 .1 861 I- - - - - - - - - - - - - - -- -- - - - - - -------- - - - - - - - - - ---------------------------- ------ - I lWsw- I -I .1 'F 4F 231 161 "i 3F 61 F .1 661 I - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - -------------------------------------

I .1 .1 F

+- + + - +I F-W- 81 .51 41 71 'I 1F *F .1 271 I- - - - - - - - - - - - - - -- - - - - - - - - - - - - - ---------------------------------------------- I I-WNW- 1 21 *1 21 1I 61 61 'I 1 21 F *F 201 F- - - - - - - - - - - - -*-- - -- -- - -- -- - --

+ -

-NW- 1 .F .1 61 I 5I 31 21 sl 9 61 39 F .....- - -----

+-+-+- ---- -

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

- - 1 .1 71 71 41 . ' 121 41 21 37 F---------------------------------------------------------- +-+-+- + - + - +-r ..---- +- -+-- -+ -+- -

TOTAL I 21 1F 26F 81F 179F 1421 751 43F 541 251 91 6371

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .- z. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

-McGuire NUCLEAR STN. METEOROLOGY (2007) 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 1.00-I 1.25-F 1.50-F 2.00-F 3 .00 -1 4.00-1 5.00-F 6.00-1 8.00-1>9.99 I F 1.24 1 1.49 1 1.99 1 2.99 F 3 .99 I 4.99 F 5.99 I 7.99 F 9.99 I M/S TOTAL

. . . -I.

NO. I NO. I NO. I NO. FN0. I NO. I-NO. I NO. I NO. I NO. F NO.

F- - - -F---F-421-- - ------ ----- --- --- +- +--.+-

-- F SECTOR II 9F F II II FI FI

-N- 1 41 31 131 421 2 iI 9F '4F 191 61 1 1311 1 1471

-NNE- 1 *F 5F 1sF 291 17 331 131 241 il

-+ - +-+...+-...+-...+-...+-...+-...+-...+-...+- ÷- F 1 971

-NE- I 11 41 61 ill 221 301 18F s

+- +-- +-...+----+-+--- -+--.....+.-....+- +- I 1 361

-ENE- F -F 11 4F lOF "F 81 1F 1F

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

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

-E- 1 231 I .F 21 4F 'oF 61 1 1F 1

-+-+-..+- ..... +- +--+- +-+- 4 -- + ... +- +- F 181

-ESE- I 11 'F 2F "l 21 . '1F F

- SE-

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

F-----

F F1 1l 21 61 21 .F F1

-SSE-

-+--- +----- .---- +-- +---- ------ ---+-- .. +.-....-+.-....-+- +- F 9 1 1 .F 1 91 .F 1 *1 .F 1

-S-

-+-- +------ -- +-- +-------------------+-+ - + - +- -+ - F 1 261 F .F -F 4F 181 3 11 -F

- -- +- .... +..-...+..-.+- +-- ... . ---- . .. + -..... +....-I 17 11 I 1 351

-SSW- F F F1 21 sI *1

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

1 1061

-SW-

+- - -- 4

F -- 11

+ ..... +

21.. .. + ..

301.. + ....

251 + . . ...

241 . ....

13F+ . ...

1i

+ .. .. + ....

1 631

-WSW- I 11. 31 2F 211 14F 61 4F 121

- -- +- ..... + ....-. +.....+-+/------+-+-+-+- +- +- F 1 381 1

-+- -- +.

11 .. +

31 -.. .+

2F-.. .+-..

"Fl .. +

zo

-.. .+--,--+

61 -.. .+

s -.. .+

.F-.. .+ -....

1 1 261

-WNW- F4 11 31.. 31-.. .+. 31..- + 7F.+ 61 21 11 -.. F1

+- . . +-+ . .

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

F '1 3F *F- 4F 2F 12F 81 loF 101 21 521 F-NW-F

+ .

-. .+

31 -.. .+

21 -.. .+

2F1 -.. .+ -..

1.+ -..

'F .+

1-.. .+

121-.. .+

1 -.. .+-

2SF +-

81 F 6j 721

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

+-- + ..-... + ....-. + ....-. +-I I TOTAL F 131 321. 631 2371 1601 1431 911 108F 35l 81 8901

McGuire NUCLEAR STN. METEOROLOGY (2007) 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

F------ I 1 O.45-1 0.75-1 1.00-i 1.25-1, 1.so-I 2.00-I 3.00-I 4.00-I 5.00-I 6.00-I 8.00-1>9.99 1 0.74 1 0.99 1.24 I 1.49 I 1.99 1 2.99 1 3.99 1 4.99 I 5.99 I 7.99 1 9.99 I M//S TOTAL

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

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

I I I I I I I I I

-N- I I .1 41 81 241 571 481 531 311 141 31 .1 2421

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

-NNE- I I 21 21 101 211 621 Sol 561 301 181 41 1 2551

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

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

-NE- I I 1 21 111 241 1491 2031 1721 1141 351 -1 -1 7101

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

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

-ENE- I .1 .1 I 71 291 1151 1031 421 S1 21 -l 3031

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

-E- I *1 1I 11 71 181 901 911 91 21 .1 .I 2191

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

-ESE- I 1 21 31 31 231 621 451 101 41 . I .1 1521

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

-SE- I I i1 51 l 341 1031- 361 71 .1 .1 -1 1921

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

-SSE- 1 1 .1 21 101 261 Sol 91 11 .21 11 .I 1011

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

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

-s- I 1 10 241 841 2S5 61 31 21 .I 1541

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

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

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

-SSW- I 1 11 51 5I .181 901 .681 i 41 21 - 2041

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

-SW- 1 1 21 1I 91 301 1181 1991 1221 641 171 iJ .1 5631

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

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

-WSW- I 1 11 41 101 311 75l 591 381 261 221 91 2751

+ .. .. .. .. +... ...+ ...

4----...+ +-... I Iw I 11 7 81 211 41 47 251 101 101 41 1871

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

+---

-WNW- I 11 31 21 5I 121 311 221 401 181 91 31 21 1481

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

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

.+ . . +-I I

- IN *I I 21 71 s5 . 271 421 361 -311 311 131 111 2051

+

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

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

-I- I 11 5 61 221 341 371 301 271 411 141 21 2191 TOTA--------- ---- F -------------------- + - I TOTAL 1 lj 151 451 1221 3621 12011 10841 6581 3711 . 2041 511 151 41291

McGuire NUCLEAR STN. METEOROLOGY (2007) 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

FI F 0.4571 0.75-F 1.00-1 1.25-F 1.50-1 2.00-1 3.00-1 4.00-1 5.00-1 6.00-1 F 0.74 1 0.99 1 1.24 1 1.49 1 1.99 1 2.99 1 3.99 F 4.99 1 5.99 I 7.99 ITOTAL I------- -------. +-...--...--

..--- ..---------------------- + - +- -- I I NO. I NO. I NO. FNO. I NO. I NO. I NO. I NO. I NO. I NO. FNO. F F----------------------------------------------------------------------- -+- + -+-

-- - + -+

SECTOR I F F F F F F F F I-N- 1S-----------------------F 11 11F 11 F 41 81 161 41 31 .1 11 391 F-- - - -- - - -- - - -- - - - -------------------------------------

+-+- + - + - +-- +-- F I

F-NNE- F F 1' '1 41 71 81 51 1' 21 1 29 F ----------- ----------------------------------------

+- - + + + - - - - - ----- +-- F--

F-E- F *F .1F *F 21F 141 '1 11 'F 24 FI-ENE- - ----.-- - - F 1I . 31 .1 41 81 61 11 1t . .1 231 F- - - - - - - - - - - - - -- - - - - - - - - - - - ---------------------------------- --- --- -- +-- - F-F-E- F 21 41 , 5 1 ". 81 . F1 1 - 30 F----------------------------- +------+--------+-...-.+- ---- F I

-ESE- F 1 21 71 21 16F 141 21 -1 - 44F F ---------------- --- --- ---

--- --------------------------+ + - -- +-- F--

F-SE- I '1 81 5 8F 22 451 151 .F .1 104 F----------------------- -------

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

F-SSE- F 2 31 91 221 44 24F 11 .I .1 1o5 F --....-- --....-- .....--

+--++ +- - + -- - FI

-s- 1 61 91 22F 5so 1 F 21 .1 .1 171 F----------------------------+--+- .+----+----+--- - + -+- -- -- FI

-ssW- F 11 8F 141 20F 54F 1601 29F 21 F *F 288F F . .. .. .. .. . ..7 .. .. .. --------------------------------------------

. + - + - - + - + - _- - - -------- ----- ---- ' F

-sw- F 21 61 91 8 46 15S61 83 121 21 11 325F F----+-------- ------- ------- ------- ---- -------------------------- -- - - - F F-WSW- F 1 71 9F 20F 5S 611 17 .F 5 31 17F

-_w- 1 -. 31 121 131 181 261 81 .1 . 11 81l F------..... 7 ----------------.....-

.....----....---.....---- ....-- ---- - +-. . -- -- FI

- -- FI . 31 81 8 15F 171 5F 51 11 .1 62 F--------------------------------------------------------+- -+ - + - + - +-- -+- -+- -- F F-NW- F 21 21 41 71 01 191 18 . 61 .F .1 68 F----- ----------- -- FI I-NN - 1 .1 -+-- 1---

+-

1 - +-.-+---31 .1 1+-+. 1.2 1 51 +---+ .* 1.1--

1 -I 26 1 F ------------------------------------------------ ------ +---- ----- I TOTAL F 121 561 951 149F 3741 667 1961 32F 10F 61 1597F

McGuire NUCLEAR STN, METEOROLOGY (2007) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY F I WIND SPEED CLASS

I 1 0.45-j 0.7.5-F 1.00-1 1.25-1-1.50-F 2.00-F 3.00-1 4.00-1 5.00-F 6.00-I 1 1 0.74 1 0.99 F 1.24 F 1.49 F 1.99 F 2.99 1 3.99 1 4.99 F 5.99 F 7.99 TOTAL F F.-------------- - +------+-..-. ----.....- +-----. +-..+-. .+.- F I

I NO. INO. I NO. I NO. INO. I NO. I NO. I NO. I NO. I NO. F NO. F F - - - - - - - - - - - - - -- - - - - - - - - - - - - ------------------------------------------- + -

SECTOR I I F. F F F F F F I- ---------------------F F I F I-N- F 21 11 11 .F .1I I F1 F I1--- --------------------------- +- I I-NNE- 1 .I ' 1 11 1' .*F1 .1 F *F F- - - - - - - - - -- - - - - - - - - - - - - - - - ---------------------------------------------- - I F-NE- F 11 .F 21 F

.1 -1 .* .* 3 F -- - - - -- - - - -- - - --- - -- - -- ----- -- --- - ----------------------------

----- I I-ENE- 'F 11 'F 11 *F 'F - 3 I -- ----- ----- - --- - -- - -- ------- --- - ----------------------------

----- I I-E- 1 .1 F 11 F1 . .* 1 I----- ---- -------------------------- . . +------------------------+- -+- -+--+-+----.-- F-I I-ESE- F

11 21 11 21 * -* I .1 6F F----------------------------------------------- --------------------------- +-. - - F-I F-SE- 21 21 21 51I s4 50 F ----------------------------------------------------- - - + - - - -+---------F--

I-SSE- F 21 3j 31 81 41 1 '1 11 *F 241 F - -

I-s-1 61 8 111 20F 411

+ -

.1 F1 . F

.. 871 I--- -- - - - - - - - - - -- - --- - - - - - - - - - - - - - - ----------------------------- + + - I-I-SEW- 3 171 19F 211 41F 181 F 1 . 119 F- - - - - - - - - - - - - -- - - - - - - - - - -++- - ----------------------------- -------------- - F I-Sw- 1 2F 191 20F 191 23 391 2F .I F

1241 I----------------- --- --- ---

- - - - - - - +----- -- F--

.I-WSw- F 2F 171 ilF 171 19F 281 F I 94 I -------------------- ------------------------------------- +----------+- -F-----

__1__+ .... 4....1 .... ... 2 .1 . .. . ..6 +1 . .. . .. 2 .1 . . .. 1 . 1.4 F--- - ---- +---------------------------+- I F-N - F F 11 11 31 21 51 'F 13F 1 --- - - --------------------------------

+-+-+-+-+-+- +- F I-NNW 1F 1 11 21 .F 2 1 .F . 11 F--------------------------------------------------------- +-+-+-+- + - + - + - + - +-----+ - F ITOTAL F 181 841 77l 881 1331 1521 81 31 1 'F 11

McGuire NUCLEAR STN. METEOROLOGY (2007.) 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 1 0.45-1 0.75-1 1.00-1 1.25-I 1.50-1 2.00-1 4.00-I 0.74 0.99 0 1 1.24 1.49 1 1.99 I 2.99 I 4.99 TOTAL I-------------- +-.....+-.....+.....----+-+- +-

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

*-+- + - + - + - I SECTOR I -II Il I IllI I lIl

-N- --- - +-

l+l.I - -

ii- + - - +

.+ . 21

- NNE - I 21 1 21 *1 .I .41

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

-NNE-21 ENE -

--NE- I 1'1 .. 1 . 1. .1 . 1 . 1 11

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

41 1111+1 . . . . .. L ....

-ESE-I 1 i1 11 .1 .1 11

-SE- I 1 1- Ii--l*i 21

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

-. .+ .

-. .+ -.. .+ .

-. .4 . . I

-SSE- 71 1 i 2 21 11 22 *

-S-1 31 61 41 71 61 31 . 291

-SSW-I 71 201 19I 161 101 11 .1 731

-SW-1I 251 231 61 5I .11 661

-WSW- 121 231 81 71 3-1 4 471

-WSW-I 21<ý 31 41 51 31 11 . 181 I 31 81 11 21 21 'I 171

-NW- 31 TOTAL

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

3- - -- -- ----- - +- +-------

1+-- - -

. 27911

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

-CALM- 21 1 41 7 .1+

+ .1 21

- +---- -- -+ - + m --------------- +- -- --- +

TOTAL I 321 921 1 451 301 131 i1 2-791

McGuire NUCLEAR STN. METEOROLOGY (2007) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS ALL STABILITY CLASSES 1 WIND SPEED CLASS l I-----------------------------------------------------------------------I 10.45-10.75-I 1.00-1 1.25-1 1.50-1 2.00-1 3.00-1 4.00-1 s.oo-1 6.00-1 8.00-1>9.99 1 10.74 1 0.99 1.24 1 1.49 1 1.99 1 2.99 1 3.99 1 4.99 I 5.99 I 7.99 I 9.99 I M/S ITOTAL I -------- +-----+ .....- + ...-..----.... +..-...-+.---+-------- ---

7. I I NO. I NO. I NO. I NO. I NO. I NO. I NO. L NO. I NO. I NO. I NO. L NO. I NO.

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 41 21 121 211 701 1321 821 671 Sol 431 221 *1 sos5 1- - - - - - - - - - - - - - - -- - - - - - - - - - - - - - -

- --------------- - - - - - - - ------------------- - I l-NNE- 1 21 41 61 241 761 1381 94l 99I 521 511 201 21 5681 1 .....----....----....---

-- +- - -- +--- --- + - I I-NE- 1 21 11 5J 191 531 2141 2451 2211 1441 421 *1 *1 9461 1---------------------------------------------------------------....-------------------.-- -- +..-.-+-I I

-ENE- I 21 41 1 131 611 1721 1461 601 71 61 *1 1 4711 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------------------------------- - I

-E- I .61 71 141 44 1321 1141 101 31 -I *1 *1 3301 1 -....--- -....--- .....---

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

-ESE- 1 1! 61 131 81 491 971 561 i 1 41 .I *1 2451 1 - - - - - - - - - - - - - - -- - -- - -- - -- - -- - -- --------------------------

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

I-SE- 1 4I 121 121 191 651 1641 5s5 81 1 .I *11 340!

1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------------------------- - I

-SSE- I S! 61 161 371 811 971 13! 21 21 11 .1 *1 2601 1----------------------------- -+- - ---+--- +---- +------_+..-.-. .+..-..+..-.-+.-.-+.- .+..-.+----- I

-s- S 181 211 50 1101 2491 311 71 - 3 21 .1 .1 4961 1 --- -- --- -- ----

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

-- .. +...- ..-+..-.-+-I I I-SSW- I ill 461 571 631 1291 3231 1361 231 71 21 .1 I 7971 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------- + ----- ----------- I I-Sw- 1 101 521 531 441 114! 3821 368! 1991 90! 371 i1 I 13501 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------------------------------- - I j-WSW- I 5l 481 33I 59 116! 2471 1421 651 401 461 10j . 8111 1 - - - - - - - - - - - - - - -- - -- - -- - -- - -- - -- --------------------------

+ -- --- +/----- ---- - -

I-W- 31 171 271 381 671 1181 801 391 161 121 41 .1 4211 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------------------------------------- + - I I-WNW- I 5I 201 14! 221 411 741 441 541 221 121 3! 21 3131 1 --------------------------------------- +- ---- ------ - ----- - -------------- +-- -- I I-NW- I 21 41 9I 291 22l 631 641 58I 41 51! 34 231 400I 1-------------------------------- ------ ------ ------ ------ ------ ------ --------------------- + - + - + + -+I I- - 1 .1 41 16l 191 47 611 431 381 39 801 281 111 3861 I-CALM - I 21 .1 I - I .I .I I .I .I 21 1-------- -------- -------- ----- --- -- ------ --------------------- --- - I ITOTAL 1 631 2S01 3011 479 1145I 26631 17131 961I 5211 3851 1221 381 8641I

Attachment 5 Inoperable Monitoring Equipment

Failure to meet Remedial Action F.2 "Restore the channel to Operable status" for inoperable instrument from SLC TABLE 16.11.2, 4.d.

October 29, 2007 1WPFT5120 (Flow Rate Monitor) measuresland totalizes the flow rate from the turbine building sump (TBS) discharge to the conventional cooling (RC) system. SLC 16.11.2 has a 30 day completion time requirement for effluent flow rate measurement instrumentation. The normal operational alignment for the turbine building sump discharge is to one of two hold-up ponds via the conventional waste (WC) system. SLC 16.11.2 requires flow rate monitors at all times when the turbine build sump discharge is aligned to the RC flow path. It also requires an 18 month channel calibration for this instrumentation.

Performance of the channel calibration on 1WPFT5120 requires re-alignment of the turbine building sump to the RC cross-over release path to process flow through 1WPF-I5120 flow instrumentation. When flow verification was performed on 5/23/2007, the totalized flow was consistently found to be out of tolerance (OOT) low. Due to maintenance limited resources for unit startup from 1EOC18, repair work was rescheduled. During the flow rate monitor inoperable period, operations realigned the turbine building sump discharge flow path to the normal alignment (TBS to WC). The normal alignment flow path does not utilize 1WPFTF5120.

1WPFT5120 is a Rosemount magnetic flow transmitter that requires removal from. the system for internal inspection of the measurement electrodes. When maintenance recommenced work on 6/12/2007, the totalizer output was again found OOT low.

Engineering was consulted'and additional testing validated that 1WPF-I5120 output was the problem. The flow element was removed and the electrodes were found coated and required cleaning. After restoration of the flow element into the flow path, the totalized output now indicated OOT high. A decision was then made to order a replacement instrument. However, there was no duplicate replacement model available from the manufacturer. An expedited order from the manufacturer was made. In addition a plant modification was required for installation of the updated replacement model.

During preparations for installation of the new replacement model 8705, it was found to be 3.5 inches shorter than the original model 8701. This required an additional piping modification to allow mate up to the new instrumentation.

Once installed and testing of the new transmitter completed, the positive zero return (PZR) function was found to require a different (positive) voltage for activation. Another field modification was required for installation of a new power supply to perform this PZR function. All required modifications were completed and instrumentation passed calibration criteria on 9/06/2007.

These actions required 106 days from start of channel calibration when 1WPFT5120 was declared inoperable for PM, until instrumentation was replaced and satisfactorily tested and declared operable. The effluent release alignment (TBS to RC) which required 1WPFT5120 was only aligned to this flow path during the period of time testing was required for comparison of totalized output to volumetric calculation of turbine building sump discharge.

Event Time Line:

5/23/2007: Start Channel Calibration, 30 day clock starts 5/24/2007: Mode 4 startup support, reschedule work for two weeks 6/12/2007: Maintenance recommences work (20 days into LCO) 6/22/2007: Flow element clean, and still OOT, decided to replace (LCO expires) 7/26/2007: Attempt to install replacement instrumentation, requires piping modification 8/06/2007: Installed replacement flow element and transmitter 8/15/2007: New flow instrumentation passes calibration criterion.

9/06/2007: Replacement instrumentation required additional power supply for PZR 9/06/2007: New flow instrumentation passes functional verification 9/06/2007: 1WPFT5120 removed from TSAIL.

W. C. Spencer Joyce Correll RP Staff Scientist Supervising Scientist McGuire Nuclear Station McGuire Nuclear Station

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 has implemented the Nuclear Energy Institute (NEI) Groundwater Protection Initiative (June 2007), a voluntary groundwater investigation project adopted by the United States commercial nuclear power industry. This initiative was developed to ensure timely and effective management of situations involving inadvertent releases of licensed material to ground water. As part of this program, the McGuire Nuclear Station installed fifty ground water monitoring wells. With the existing ten wells there are now a total of 60 ground water monitoring wells in place at McGuire. 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 2007 confirmed existing knowledge of tritium concentrations in the site ground water (shown in the table below). No new potential problem areas were identified.

The following monitoring wells were sampled during 2007.

Well Name Well Location Annual Average Tritium Concentration in pCi/l M-20 South of Hwg. 73 658 M-20R South of Hwg. 73 627 M-21 South of Hwg. 73 229 M-22 South of Hwg. 73 193 M-22R South of Hwg. 73 581 M-23 South of Acs. Rd. 293 M-30 WWCB <MDA M-30R WWCB 277 M-31 Access road <MDA M-32 Main entrance 762 M-33 Main entrance 1130 M-34R Access road 443 M-34DR Access road 396 M-42 U-2 Rx. Bldg. 975 M-48 U-2 SFP 638 M-48R U-2 SFP 743 M-48DR U-2 SFP 747 M-53 North of plant 921 M-55 North Admin. Bldg. <MDA M-59 U-2 Doghouse 472 M-60 MOC Parking <MDA M-62 S of RWF 570 M-64 Rdwst. Bldg. 449 M-66 S ofSSF 554 M-66R S of SSF 285 M-68 U-1 RMWST 830

ARERR Groundwater Well Data Section Rev. 1 M-70 U-1 SFP 305 M-70R U-1 SFP 282 M-70DR U-1 SFP 191 M-72 Rdwst. Trench 650 M-76 West of U-1 SFP 470 M-82 River 1,581 M-84 River 5,036 M-84R River 6,407 M-85 River 1,255 M-87 Landfarm 250 M-89 Landfarm 446 M-90 Landfarm 270 M-91 East of WC 292 M-91R East of WC 376 M-92 N of WC Ponds 247 M-92R N of WC Ponds 173 M-93 North of IHUP 265 M-93R North of IIIUP 493 M-94 SE of IHUP 221 M-95 Lower Parking 385 M-95R Lower Parking <MDA M-96 West Parking <MDA M-96R West Parking 255 M-97 East Parking 356 M-98 S of Admin. Bldg. <MDA M-98R S of Admin. Bldg. <MDA.

M-100R SE of WC 330 M-1l01 SE of WC 456 M-102 SW of WC 7,727 M-103 South of WC 2,431 M-103R South of WC 2,427 M-104R West of WC 11,050 M-104DR West of WC 5,563 M-105 Landfarm 394 pCi/l - pico curies per liter MDA - Minimum detectable activity 20,000 pCi/1 - the Environmental Protection Agency drinking water standard for tritium.

This standard applies only to waterthat is used for drinking.

1,000,000 pCi/l - the 10CFR20, Appendix B, Table 2, Column 2, Effluent Concentration limit for tritium.

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