ML101190025

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Submittal of 2009 Annual Radioactive Effluent Release Report
ML101190025
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 04/19/2010
From: Repko R
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML101190025 (69)
v • d • e


Text

Duke Dukeg REGIS T. REPKO Vice President

  • Energy, McGuire Nuclear Station Duke Energy MG01VP / 12700 Hagers Ferry Rd.

Huntersville, NC 28078 980-875-4111 980-875-4809 fax regis.repko@duke-energy. com April 19, 2010 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 2009 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 Report. Also included in this report is the 2010 Offsite Dose Calculation Manual and the 2009 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 Program Questions concerning this report should be directed to Kay Crane, McGuire Regulatory Compliance at (980) 875-4306.

Regis T. Repko www.duke energy.corn

NRC Document Control Desk April 19, 2010 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 11 Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 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

Attachment 1 Radioactive Effluent Releases and Supplemental Information

McGUIRE NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 2009 through December 31, 2009)

This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Rev. 1, Appendix B. Radioactive liquid and gaseous wastes are sampled and analyzed per the requirements in Selected Licensee Commitment (SLC) Table 16.11.1-1, "Radioactive Liquid Waste Sampling and Analysis Program", and SLC Table 16.11.6-1, "Radioactive Gaseous Waste Sampling and Analysis Program".

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Gases

1. Total Release Ci 5.30E-01 6.42E-01 1.47E+00 6.17E-01 3.26E+00
2. Avg. Release Rate pCi/sec 6.82E-02 8.16E-02 1.85E-01 7.77E-02 1.03E-01 B. Iodine-131
1. Total Release Ci 3.30E-07 4.27E-07 2.46E-06 5.21E-06 8.42E-06
2. Avg. Release Rate pCi/sec 4.24E-08 5.43E-08 3.10E-07 6.55E-07 2.67E-07 C. Particulates Half Life >= 8 days
1. Total, Release Ci 4.05E-06 1.99E-06 2.79E-06 8.59E-06 1.74E-05
2. Avg. Release Rate pCi/sec 5.20E-07 2.53E-07 3.51E-07 1.08E-06 5.52E-07 Df('Tritium
1. Total Release Ci 2.55E+01 3.03E+01 5.32E+01 5.74E+01 1.66E+02
2. Avg. Release Rate pCi/sec 3.28E+00 3.86E+00 6.69E+00 7.22E+00 5.28E+00 E. Gross Alpha Radioactivity
1. Total Release Ci 0.OOE+00 0.OOE+00 O.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 1/1/09 TO 1/1/10 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2009 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 lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2009 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 1/1/09 TO 1/1/10 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases AR-41 Ci- 8.27E-05 0.OOE+00 7. 66E-01 0.OOE+00 7.67E-01 C-11 Ci 4.41E-04 0. 00E+00 0 OOE+00 0.OOE+00 4.41E-04 KR-85 Ci 0.OOE+00 0.00E+00 8. 32E-04 0.OOE+00 8.32E-04 KR-85M Ci 1. 59E-04 0.OOE+00 2. 94E-03 0.OOE+00 3.lOE-03 KR-88 Ci 3.94E-04 0.OOE+00 3. 51E-03 0. OOE+00 3. 90E-03 XE-133 Ci 1.40E-02 0. OOE+00 1. 41E-02 0.OOE+00 2.81E-02 XE-133M Ci 4.33E-04 0.OOE+00 0 OOE+00 0. OOE+00 4.33E-04 XE-135 Ci 3.85E-03 0. OOE+00 2. 69E-02 0. OOE+00 3. 08E-02 Totals for Period... Ci 1. 93E-02 0.OOE+00 8.15E-01 0.OOE+00 8.34E-01
2. Iodines 1-131 Ci 3.30E-07 4. 27E-07 2.46E-06 5.21E-06 8.42E-06 1-133 Ci 0.OOE+00 0. OOE+00 2. 94E-05 0. OOE+00 2.94E-05 Totals for Period... Ci 3.30E-07 4.27E-07 3.19E-05 5.21E-06 3.78E-05
3. Particulates Half Life >= 8 days BE-7 Ci 0.00E+00 0. 00E+00 0. OOE+00 4. 90E-06 4. 90E-06 CO-58 Ci 4.05E-06 1. 99E-06 2.79E-06 3.69E-06 1. 25E-05 Totals for Period... Ci 4.05E-06 1. 99E-06 2.79E-06 8.59E-06 1. 74E-05
4. Tritium H-3 Ci 2.53E+01 3. 01E+01 5.20E+01 5.71E+01 1. 65E+02 Totals for Period... Ci 2.53E+01 3. 01E+01 5.20E+01 5.71E+01 1. 65E+02
5. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 -

REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases AR-41 Ci 4.99E-01 6.11E-01 6.40E-01 5.71E-01 2.32E+00 C-II Ci 0.OOE+00 0.OOE+00 0. OOE+00 2.88E-03 2.88E-03 KR-85 Ci 0.OOE+00 1. 87E-02 0. OOE+00 9. 92E-03 2.86E-02 XE-133 Ci 1.11E-02 1.06E-02 2. OOE-02 3.32E-02 7.49E-02 XE-135 Ci 5.94E-04 1.36E-03 0. 00E+00 2.40E-04 2.19E-03 Totals for Period... Ci 5.11E-01 6.42E-01' 6.60E-011 6.17E-01" 2.43E+00
2. lodines
    • No Nuclide Activities **
3. Particulates Half Life >= 8 days
    • No Nuclide Activities ** ........
4. Tritium H-3 Ci 1. 69E-01 2.13E-01 1. 12E+00 3.13E-01 1. 82E+60 Totals for Period... Ci 1. 69E-01 2. 13E-01 1. 12E+00 3.13E-01 1. 82E+00
5. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 3.41E-03 3.40E-03 9.44E-03 1.86E-02 3.49E-02
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 4.01E-12 3.56E-12 1.06E-11 2.01E-11 9.63E-12 B. Tritium
1. Total Release Ci 1.93E+02 4.05E+02 5.66E+02 3.31E+02 1.49E+03
2. Average Diluted Concentration
a. Continuous Releases pCi/ml 1.41E-08 4.72E-09 4.64E-08 9.48E-09 1.30E-08
b. Batch Releases pCi/ml 2.26E-07 4.24E-07 6.33E-07 3.57E-07 4.12E-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.OOE+00 0.OOE+00 0.00E+00
b. Batch Releases pCi/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 pCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
b. Batch Releases pCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 E. Volume of Liquid Waste
1. Continuous Releases liters 6.79E+07 5.98E+07 7.11E+07 7.35E+07 2.72E+08
2. Batch Releases liters 4.89E+05 9.16E+05 2.84E+07 9.35E+06 3.92E+07 F. Volume of Dilution Water
1. Continuous Releases liters 3.70E+10 7.50E+10 2.56E+10 7.79E+10 2.16E+ll
2. Batch Releases liters 8.51E+ll 9.54E+ll 8.92E+ll 9.25E+ll 3.62E+12

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID EFFLUENTS - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products
    • No Nuclide Activities **
2. Tritium H-3 Ci 5.22E-01 3.54E-01 1.19E+00 7.39E-01 2.81E+00 Totals for Period... Ci 5.22E-01 3.54E-01 1.19E+00 7.39E-01 2.81E+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 1/1/09 TO 1/1/10 LIQUID EFFLUENTS - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2009 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products AG-108M Ci 3.20E-06 9.46E-06 1. 09E-05 2.18E-05 4.54E-05 AG-1IOM Ci 0.00E+00 5.98E-06 3.13E-06 4.81E-06 1. 39E-05 BE-7 Ci 8.03E-05 5.71E-04 2. 92E-05 3.74E-04 1. 05E-03 CO-57 Ci 5.34E-06 1.24E-05 3.52E-05 2. 69E-05 7. 98E-05 CO-58 Ci 2.17E-03 1. 62E-03 1. 84E-03 5. 98E-03 1. 16E-02 CO-60 Ci 3.44E-04 8. 68E-04 4.33E-03 3. OOE-03 8.54E-03 CR-51 Ci 0.00E+00 0. 00E+00 1. 71E-03 6.60E-03 8.30E-03 CS-134 Ci 7.18E-05 6.55E-06 0. 00E+00 3.34E-06 8.16E-05 CS-137 Ci 3.25E-04 1. 04E-05 2..0E-05 9. 94E-05 4.55E-04 FE-59 Ci 0.00E+00 0. 00E+00 1. 55E-04 5.03E-04 6.58E-04 MN-54 Ci 3.31E-05 9.72E-05 6.18E-04 4.26E-04 1. 17E-03 NB-95 Ci 6.74E-06 2.50E-05 1. 41E-04 4.28E-04 6.01E-04 NB-97 Ci 1.81E-06 2.15E-06 5.03E-06 8. 97E-06 1. 80E-05 SB-124 Ci 1.95E-05 0. OOE+00 6.17E-06 2. 00E-04 2.26E-04 SB-125 Ci 3.54E-04 1.38E-04 4. 02E-04 7.03E-04 1. 60E-03 SN-113 Ci 0.OOE+00 1. 29E-05 4.19E-05 3.34E-06 5.81E-05 ZN-65 Ci 0.00E+00 1.57E-05 3.78E-05 4. 96E-05 1. 03E-04 ZR-95 Ci 0.OOE+00 5. 78E-06 5.08E-05 1. 98E-04 2.55E-04 Totals for Period... Ci 3.41E-03 3.40E-03 9.44E-03 1. 86E-02 3.49E-02
2. Tritium H-3 Ci 1.92E+02 4.04E+02 5.64E+02 3.31E+02 1. 49E+03 Totals for Period... Ci 1.92E+02 4.04E+02 5. 64E+02 3.31E+02 1. 49E+03
3. Dissolved and Entrained Gases
    • No Nuclide Activities **
4. Gross Alpha Radioactivity I
    • No Nuclide Activities ** .. .. ... . .. ... ... . .. ... ..

McGUIRE NUCLEAR STATION SUPPLEMENTAL INFORMATION

McGUIRE NUCLEAR STATION 2009 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. 2.12E+02 = TOTAL NUMBER OF BATCH RELEASES
2. 4.34E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
3. 1.09E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
4. 2.05E+02 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
5. 8.00E+00 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

6.' 1.82E+06 = AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B. GASEOUS EFFLUENT

1. 3.60E+01 = TOTAL NUMBER OF BATCH RELEASES.
2. 1.05E+06 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
3. 4.48E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
4. 2.91E+04 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
5. 1.92E+02 = 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 = 4
2. TOTAL ACTIVITY RELEASED (CURIES) = 8.33E-1 (Noble Gas) (see "Unplanned Releases" 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, 2009 through December 31,: 2009)

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. The effluent dose calculations consider radionuclides identified as part of the liquid and

.gaseous wastes sample and analysis program' Radioactive liquid and gaseous wastes are sampled and analyzed per the requirements in Selected Licensee Commitment (SLC) Table 16.11.1-1, "Radioactive Liquid Waste Sampling and Analysis Program", and SLC Table 16.11.6-1, "Radioactive Gaseous Waste Sampling and Analysis Program". Attachment 4, "Fuel Cycle Calculation", 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 1/1/09 TO 1/1/10 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 1 st Quarter 2009

-- IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSISý---= Quarter 1 2009 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose TEEN LUNG 3.03E-02 1.50E+01 2.02E-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 1 2009 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Ql - Maximum Gamma Air Dose 1.13E-02 1.OOE+01 1.13E-01 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 Ql - Maximum Beta Air Dose 4.05E-03 2.OOE+01 2.02E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.77E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2009 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS=---= Quarter 2 2009 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose TEEN THYROID 3.60E-02 1.50E+01 2.40E-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 2009 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose 1.37E-02 1.00E+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 Q2 - Maximum Beta Air Dose 4.96E-03 2.OOE+01 '2.48E-02.

Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.75E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2009 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS Quarter 3 2009 =

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose TEEN THYROID 6.32E-02 1.50E+01 4.22E-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 9.98E+01

= NOBLE GAS DOSE LIMIT ANALYSIS Quarter 3 2009 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q3 - Maximum Gamma Air Dose 3.18E-02 1.OOE+01 3.18E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.91E+01 Q3 - Maximum Beta Air Dose 1.14E-02 2.OOE+01 5.71E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.75E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4th Quarter 2009

- IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS Quarter 4 2009 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit, Q4 - Maximum Organ Dose TEEN THYROID 6.83E-02 1.50E+01 4.55E-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 4 2009 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Gamma Air Dose 1.28E-02 1.00E+01 1.28E-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 Q4 - Maximum Beta Air Dose 4.65E-03 2.00E+01 2.33E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.72E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2009

= IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS Annual 2009 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose TEEN THYROID 1.98E-01 3.OOE+01 6.60E-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 2009 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Gamma Air Dose 6.97E-02 2.00E+01 3.48E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.94E+01 Yr - Maximum Beta Air Dose 2.51E-02 4.00E+01 6.27E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.75E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 1 st Quarter 2009

= BATCH LIQUID RELEASES Quarter 1 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (rem) (mrem) Limit Q1 - Maximum Organ Dose CHILD LIVER 2.55E-02 1.OOE+01 2.55E-01 Q1 - Total Body Dose CHILD 2.37E-02 3.OOE+00 7. 90E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contri]butors (5% or greater to total)

Nuclide Percentage H-3 9.16E+01 CS-137 6. 61E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.84E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 1 2009 Critical Critical Dose Limit Max % of, Period-Limit Age Organ (mrem) (mrem) Limit Ql - Maximum Organ Dose CHILD LIVER 1.45E-03 1.OOE+01 1.45E-02 Ql - Total Body Dose CHILD 1.45E-03 3.OOE+00 4.84E-02 C

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 1/1/09 TO 1/1/10 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2009

= BATCH LIQUID RELEASES Quarter 2 2009 -

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (orem) Limit Q2 - Maximum Organ Dose CHILD GILLI 4.44E-02 1.OOE+01 4.44E-01 Q2 - Total Body Dose CHILD 4.43E-02 3.00E+00 1.48E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or g reater to total)

Nuclide Percentage H-3 9.97E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or g reater to total)

Nuclide Percentage H-3 9. 99E+01

= CONTINUOUS LIQUID RELEASES (WC) Quarter 2 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2- Maximum Organ Dose CHILD LIVER 4.93E-04 1.00E+01 4. 93E-03 Q2 - Total Body Dose CHILD' 4.93E-04 3.OOE+00 1. 64E-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 1.00E+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2009 BATCH LIQUID RELEASES Quarter 3 2009 -

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q3 - Maximum Organ Dose CHILD GILLI 6.75E-02 1.OOE+01 6.75E-01 Q3 - Total Body Dose CHILD 6.69E-02 3.OOE+00 2.23E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5%-or greater to total).

Nuclide Percentage H-3 9.89E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.97E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 3 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit

,Q3 - Maximum Organ Dose CHILD LIVER 4.90E-03 1.OOE+01 4.90E-02 Q3 - Total Body Dose CHILD 4.90E-03 3.OOE+00 1. 63E-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

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4t Quarter 2009

= BATCH LIQUID RELEASES Quarter 4 2009 ---

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD GILLI 3. 95E-02 1.00E+01 3.95E-01 Q4 - Total Body Dose CHILD 3.79E-02 3.00E+00 1. 26E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.55E+01 Total Body Critical Pathway: PotableWater Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.94E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 4 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 -. Maximum Organ Dose CHILD LIVER 1.OOE-03 1.00E+01 1. OOE-02 Q4 - Total Body Dose , CHILD 1.00E-03 3.00E+00 3. 33E-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 00

2 H-3 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/09 TO 1/1/10 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2009

= BATCH LIQUID RELEASES Annual 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 1.75E-01 2.00E+01 8.77E-01 Yr - Total Body Dose CHILD 1.73E-01 6.00E+00 2.89E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.83E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.95E+01 CONTINUOUS LIQUID RELEASES (WC) Annual 2009 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 5.45E-03 2.OOE+01 2.72E-02 Yr - Total Body Dose CHILD 5.45E-03 6.OOE+00 9.08E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or g reater to total)

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

Nuclide Percentage H-3 1.OOE+02

McGUIRE NUCLEAR STATION 2009 METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS OF WIND SPEED, WIND DIRECTION, AND ATMOSPHERIC STABILITY

.USING WINDS AT THE 10 METER LEVEL (Hours of Occurrence)

McGuire Nuclear Station The SAS System The FREQ Procedure Table of STAB by CALM STAB CALM Frequency CALM WIND Total 1 0 596 596 2 0 462 462 3 0 487 487 4 1 4410 4411 5 1 1847 1848 6 3 529 532 7 7 240 247 Total 12 8571 8583 Frequency Missing = 177 1

The SAS System SECTOR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW No. No. No. No. No. No. No. No. No. No. No. No. No. No. No. No.

STAB WSCLS A 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.75-1.00 0 0 1 0 0 0 0 0 0 1 0 0 1 2 0 1 1.00-1.25 1 3 0 0 0 0 0 0 0 0 0 0 3 0 1 1 1.25-1.50 .6 7 1 1 0 0 0 1 0 .1 1 1 0 1 4 4 1.50-2.00 16 19 16 9 4 3 3 2 2 4 7 6 6 6 5 8

-2.00-3.00 17 24 22 20 13 4 5 7 6 13 11 14 10 6 3. 7 JJ 3.00-4.00 5 14 15 11 10 6 2 3 4 9 16 13 7 2 1 3 4.00-5.00 3 3 6 7 4 1 0 0 1 4 6 4 1 0 0 3 5.00-6.00 8 3 9 5 0 0 0 0 0 1 3 0- 0 0 2 1 6.00-8.00 12 6 3 4 0 0 0 0 0 0 4 1 0 0 3 10 8.00-10.00 5 0 0 0 0 0 0 0 0 0 0 0 0 0 2 5, 10.01-99.99 2 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 B 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.75-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.00-1.25 1 0 0 1 0 0 0 0 0 0 0 0 1 0 0 0 1.25-1.50 1 0 1 0 0 0 1 0 0 0 1 1 1 0 0 0 1.50-2.00 4 3 7 1 2 1 1 0 1 2 0 0 3 1 1 1 2.00-3.00 5 13 9 10 4 8 6 2 4 5 9 17 1 3 4 1

3.00-4.00 9 11 14 10 6 5 2 1 9 12 15 9 5. 8 1~ 1 4.00-5.00 3 7 15 7 4 1 0 0 1 7 18 9 2 3 2 5 5.00-6.00 0 7 14 1 1 0 0 0 0 2 7 6 0 0 2 5 6.00-.8.00 13 8 9 1 0 0 0 0 0 0 6 5 0 0 4 19 8.00-10.00 3 1 1 0 0 0 0l 0 0 0 1 0 0 1 1 1 1.19.9 0 1 0 0 0 0 0 0 0 0 0 0 0 0 1 1 C 0.46-0.75 0 0 -0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.75-1.00 0 0 0 -0 0 0 0 0 0 0 0 0 0 0 0 0 1.00-1.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1.25-1.50 0 0 2 0 0 0 1 1 0 1 1 0 2 0 0 0 1.50-2.00 1 2 1 2 3 2 0 2 3 0 4 2 2 2 0 1 2.00-3.00 10 8 7 7 5 2 4 7 2 4 9 8 3 2 1 1 3.00-4.00 5 8 10 8 2 5 4 2 .2 9 24 21 9 2 1 2 4.00-5.00 5 6 28 8 )5 0 1 0 0 9 14 11 1 1 0 5 5.00-6.00 12 3 13 3 0 0 0 0 0 1 11 6 0 1 5 5 6.00-8.00 10 9 8 2 0 0 0 0 0 1 5 4 5 3- 8 12 8.00-10.00 4 1 3 0 0 0 .0 0 0 0 2 2 0 6 7 4 10.01-99.99 0 4 0 0 0 0 0 0 0 0 0 0 0 0; 2 1 D0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0.75-1.00 5 1 0 0 0 1 2 2 .1 0 0 1 2 2 1 2 1.00-1.25 5 8 1 0 2 1 4 4 5 4 5 4 4 5 2 1 1.25-1.50 10 8 6 5 6 7 7 ,11 13 11 5 17 10 6 2 7 3

1 .50-2. 00 30 29 30 20 17 17 45 49 32 14 37 32 39 16 16 15 2 .00-3. 00 63 77 186 138 94 71 95 44 49 65 123 108 53 21 26 26

3. 00-4. 00 52 75 248 152 60 52 40 11 25 84 181 61 31 19 31 38 4 .00-5. 00 55 55 220 69 21 11 7 2 9 33 118 24 35 19 38 40
5. 00-6. 00 38 44 67 4 3 0 0 1 4 14 55 19 11 13 23 19
6. 00-8. 00 34 25 28 1 0 0 0 0 0 2 31 21 4 12 28 22 8 .00-10. 00 1 22 10 0 0 0 0 0 0 .1 4 5 1 2 21 3 10.01-99.99 0 6 0 0 0 0 0 0 0 0 1 4 1 3 2 "0 E 0.46-0.75 0 2 0 1 0 0 1 1 1 0 1 0 2 1 2 0 0.75-1.00 0 2 0 0 4 1 3 4 4 9 7 4 4 3 3 0 1 .00-1.25 1 4 5 6 2 3 8 11 4 7 7 9 14 5 1 1 1.25-1.50 4 5 7 3 4 2 14 25 23 22 28 25 19 4 4 2
1. 50-2. 00 15 19 21 11 10 14 36 28 51 43 46 57 29 14 12 6 2 .00-3. 00 10 12 17 24 29 29 71 24 81 143 149 72 -21 23 23 11
3. 00-4. 00 3 2 5 5 15 4 4 0 10 40 92 13 9 17 15 14 4.00-5.00 1 0 4 0 7 0 0 0 5 1 13 14 5 5 5 7 5.00-6.00 0 0 0 0 0 0 0 0 0 1 8 5 0 5 0 1 6.00-8.00 2 1 0 0 0 0 0 0 0 3 2 7 0 2 2 1 8.00-10.00 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 0 10.01-99.99 0 0 0 0 0 0 0 0 0 0 0 0,_ 0 0 0 0 F 0.46-0.75 0 0 0 0 0 0 1 1 4 5 4 1 3 0 2 0 0.75-1.00 2 1 0 2 0 0 0 2 6 12 14 13 1 1 0 1 1.00-1.25 1 1 0 1 1 0 0 4 6 17 11 9 12 0 1 0

-4

1.25:-1.50 1 1 0 2 1 5 16 23 11 10 7 2 2 0 1.50-2.00 0 2 1 0 0 12 42 25 28 16 9 3 1 1 2.00-3.00 1 0 0 0 1 9 39 34 22 23 19 4 3 0 3.00-4 .00 0 1 0 0 0 0 0 0 1 5 1 0 4 0 4.00-5.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.00-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.00-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.00-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-99.99 0 0 0 0 0 0 0 0 0 0 0 0 0 0 G 0.46-0.75 0 0 0 1 1 1 2 16 12 3 1 1 0 0 0.75-1.00 2 2 0 0 0 2 11 11 33 6 3 1 0 2 0 0 0 1.00-1.25 2 0 0 0 0 0 3 17 13 5 1 1.25-1.50 2 1 0 0 0 0 2 14 6 4 0 0 0 0 1.50-2.00 3 1 0 0 0 1 14 11 8 5 0 0 1 0 2.00-3.00 1 0 0 0 0 0 3 2 3 1 2 0 0 0

3. 00-4 .00 0 0 0 0 0 0 0 0 0 0 0 0 1 0 4.00-5. 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.00-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.00-8 .00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.00-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-99.99 0 0 0 0 0 0 0 0 0 .0 0 0 0 0 5

Attachment 2 Solid Waste Disposal Report

REPORT PERIOD McGUIRE NUCLEAR STATION JANUARY - DECEMBER 2009 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 ftW 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 none (G) dewatered mechanical filter media none (H) dewatered mechanical filter media (brokered) none (I) solidified waste none Dry Solid Waste (A) dry active waste (compacted) none dry active waste (non-compacted) 20 35 DBP 131102 3716.00 A/U 1.48E+02 dry active waste (brokered/compacted) none dry active waste (brokered/non-compacted) 13 33 DBP 2750.6 77.96 A/U 4.605E+00 (B) sealed sources/smoke detectors none (C) sealed sources none (D) irradiated components none Totals 33 68 133852.6 3793.96 1.529E+02 2/12/2010

MCGUIRE NUCLEAR SITE

SUMMARY

OF MAJOR RADIONUCLIDE COMPOSITION 2009 I

Type of waste Niuclide %Abundance I

1. Waste from liquid Pswstem es A. Dewatered Powdex Resin (brokered) No shipments in 2009 B. Dewatered Powdex Resin No shipments in 2009 C. Dewatered Bead Resin (brokered) No shipments in 2009
0. Dewatered Bead Resin No shipments in 2009 E. Dewatered Radwaste System Resin (brokered) No shipments in 2009 F. Dewatered Primary Bead Resin (brokered) No Shipments in 2009 G. Dewatered Mechanical Filter Media No shipments in 2009 H. Dewatered Mechanical Filter Media (brokered) No shipments in 2009 I. Solidified Waste No shipments in 2009 Dr. Solid Waste, A. Dry Active Waste (compacted) Cc*mpaction no longer performed on-site.

Dry Active Waste (non-compacted)

Landfill 09-01 Nuclide %Abundance Co-60 .48 Cs-1 37 2.06 H-3 97.47 I

2009-0005 Nuclide %Abundance C-14 1.66 Co-60 85.70 Cs-1 37 .42 Fe-55 1.04 H-3 .13 1-129 .01 Nb-94 .23 Ni-59 .10 Ni-63 6.05 Pu-241 .04 Sb-125 .38 Sr-90 .01 Tc-99 4.22 2009-0009 Nuclide %Abundance C-14 1.30 Co-60 86.87 Cs-1 37 .41 Fe-55 .95 H-3 .31 Nb-94 .39 Ni-59 .18 Ni-63 7.74 Pu-238 .01 Pu-239 .01 Pu-241 .05 Sb-125 .37 Sr-90 .01 Tc-99 1.39 2009-0012 Nuclide %Abundance C-14 1.82 Co-60 81.76 Cs-1 37 .41 Fe-55 1.06 H-3 .09 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 8.00 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.76 2

2009- 0015 Nuclide %Abundance C-14 1.25 Co-60 82.00 Cs-1 37 .41 Fe-55 1.07 H-3 .38 1-129 .01 Nb-94 .44 Ni-59 .20 Ni-63 8.01 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.77 2009-0023 Nuclide %Abundance C-14 1.81 Co-60 81.56 Cs-1 37 .41 Fe-55 1.05 H-3 .37 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.96 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.73 2009-0024 Nuclide %Abundance C-14 1.82 Co-60 81.54 Cs-1 37 .41 Fe-55 1.05 H-3 .38 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.97 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.74 3

2009-0027 Nuclide %Abundance C-14 1.82 Co-60 81.56 Cs-1 37 .41 Fe-55 1.05 H-3 .38 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.96 Pu-238 .01 Pu-239 .01 Pu-241 .05 Sb-125 .37 Sr-90 .01 Tc-99 5.74 2009-0028 Nuclide %Abundance C-14 1.82 Co-60 81.52 Cs-137 .41 Fe-55 1.04 H-3 .37 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.99 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-1 25 .37 Sr-90 .01 Tc-99 5.74 2009-0029 Nuclide %Abundance C-14 1.81 Co-60 81.55 Cs-1 37 .41 Fe-55 1.05 H-3 .37 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.96 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.74 4

2009-0032 Nuclide %Abundance C-1 4 1.82 Co-60 81.52 Cs-1 37 .41 Fe-55 1.05 H-3 .37 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.99 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.73 2009-0033 Nuclide %Abundance C-14 1.81 Co-60 81.57 Cs-1 37 .41 Fe-55 1.05 H-3 .37 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.96 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.72 2009-0034 Nuclide %Abundance C-14 1.81 Co-60 81.55 Cs-137 .41 Fe-55 1.05 H-3 .37 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.97 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.73 5

2009-0035 Nuclide %Abundance C-14 1.82 Co-60 81.62 Cs-I 37 .41 Fe-55 1.05 H-3 .36 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.97 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .31 Sr-90 .01 Tc-99 5.73 2009-0036 Nuclide %Abundance C-14 1.81 Co-60 81.57 Cs-1 37 .41 Fe-55 1.05 H-3 .37 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.95 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.73 2009-0037 Nuclide %Abundance C-14 1.81 Co-60 81.56 Cs-1 37 .40 Fe-55 1.05 H-3 .37 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.97 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.72 6

2009-0038 Nuclide %Abundance C-14 1.82 Co-60 81.53 Cs-1 37 .41 Fe-55 1.05 H-3 .37 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.98 Pu-238 .01 Pu-239 .01 Pu-241 .05 Sb-1 25 .37 Sr-90 .01 Tc-99 5.73 2009-0040 Nuclide %Abundance C-14 1.82 Co-60 81.51 Cs-1 37 .41 Fe-55 1.05 H-3 .38 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.97 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.76 2009-0041 Nuclide %Abundance C-14 1.81 Co-60 81.57 Cs-I 37 .41 Fe-55 1.04 H-3 .37 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.97 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.72 7

2009-0042 Nuclide %Abundance C-14 1.82 Co-60 81.53 Cs-137 .41 Fe-55 1.05 H-3 .37 1-129 .01 Nb-94 .43 Ni-59 .20 Ni-63 7.98 Pu-238 .01 Pu-239 .01 Pu-241 .06 Sb-125 .37 Sr-90 .01 Tc-99 5.74 Dry Active Waste (brokered/compacted) No shipments in 2009 Dry Active Waste (brokered/non-com pacted) 2009-0002 Nuclide %Abundance Mn-54 1.16 Co-57 .06 Co-58 7.21 Co-60 23.91 Cs-137 1.27 Fe-55 44.30 Ni-63 17.18 C-14 2.27 Zr-95 .45 Sb-125 .76 Sr-90 .18 Nb-95 1.25 8

2009-0003 Nuclide %Abundance Mn-54 2.81 Co-57 .10 Co-58 1.23 Co-60 37.14 Cs-1 37 .02 Fe-55 38.83 Ni-63 17.04 C-14 .02 Zr-95 .37 Sb-125 1.49 Sr-90 .04 Sn-113 .07 Ce-144 .02 Pu-238 .01 Am-241 .01 Nb-95 .80 2009-0004 Nuclide %Abundance Mn-54 .05 Co-60 27.60 Cs-137 2.46 Fe-55 28.07 Ni-63 36.06 C-14 4.91 Sb-125 .50 Sr-90 .35 2009-0006 Nuclide %Abundance Mn-54 2.85 Co-57 .11 Co-58 1.30 Co-60 37.00 Cs-1 37 .02 Fe-55 38.88 Ni-63 16.95 C-14 .02 Zr-95 .39 Sb-125 1.48 Sr-90 .04 Sn-113 .07 Ce-144 .02 Pu-238 .01 Am-241 .01 Nb-95 .86 9

2009-0008 Nuclide %Abundance Mn-54 2.15 Co-57 .08 Co-58 .61 Co-60 35.86 Cs-I 37 .38 Fe-55 38.95 Ni-63 19.36 C-14 .70, Zr-95 .17 Sb-125 1.33 Sr-90 .08 Sn-113 .04 Ce-144 .02 Am-241 .01 Nb-95 .23 2009-0010 Nuclide %Abundance Cr-51 22.64 Mn-54 1.47 Co-57 .12 Co-58 41.31 Co-60 5.82 Cs-137 .43 Fe-55 10.31 Fe-59 .99 Ni-63 3.88 C-14 .28 H-3 2.37 Zr-95 3.69 Sn-113 .15 Ce-144 .09 Zn-65 .22 Nb-95 6.22 2009- 0013 Nuclide %Abundance Cr-51 21.43 Mn-54 1.53 Co-57 .12 Co-58 41.62 Co-60 6.06 Cs-137 .45 Fe-55 10.79 Fe-59 .97 Ni-63 4.07 C-14 .30 H-3 2.48 Zr-95 3.70 Sn-113 .16 Ce-144 .09 Zn-65 .23 Nb-95 6.01 10

2009-0014 Nuclide %Abundance Cr-51 23.88 Mn-54 1.42 Co-57 .12 Co-58 40.93 Co-60 5.55 Cs-I 37 .41 Fe-55 9.89 Fe-59 1.00 Ni-63 3.71 C-14 .27 H-3 2.27 Zr-95 3.68 Sn-113 .15 Ce-144 .08 Zn-65 .21 Nb-95 6.42 2009-0016 Nuclide %Abundance Cr-51 23.52 Mn-54 1.4 Co-57 .12 Co-58 41.08 Co-60 5.62 Cs-1 37 .42 Fe-55 10.00 Fe-59 1.00 Ni-63 3.75 C-14 .27 H-3 2.29 Zr-95 3.69 Sn-113 .15 Ce-144 .08 Zn-65 .21 Nb-95 6.37 2009-0019 Nuclide %Abundance Cr-51 21.4 Mn-54 1.53 Co-57 .12 Co-58 41.58 Co-60 6.07 Cs-1 37 .45 Fe-55 10.78 Fe-59 .97 Ni-63 4.06 C-14 .29 H-3 2.48 Zr-95 3.70 Sn-113 .16 Ce-144 .09 Zn-65 .23 Nb-95 6.03 1I

2009-0021 Nuclide %Abundance Cr-51 23.80 Mn-54 1.42 Co-57 .11 Co-58 41.08 Co-60 5.56 Cs-I 37 .41 Fe-55 9.87 Fe-59 1.00 Ni-63 3.70 C-14 .27 H-3 2.26 Zr-95 3.67 Sn-113 .15 Ce-144 .08 Zn-65 .21 Nb-95 6.40 2009-0022 Nuclide %Abundance Cr-51 23.22 Mn-54 1.45 Co-57 .12 Co-58 41.18 Co-60 5.68 Cs-137 .42 Fe-55 10.09 Fe-59 .99 Ni-63 3.79 C-14 .28 H-3 2.31 Zr-95 3.69 Sn-113 .15 Ce-144 .08 Zn-65 .22 Nb-95 6.32 2009-0026 Nuclide %Abundance Cr-51 23.83 Mn-54 1.42 Co-57 .12 Co-58 40.96 Co-60 5.56 Cs-I 37 .41 Fe-55 9.91 Fe-59 1.00 Ni-63 3.71 C-14 .27 H-3 2.26 Zr-95 3.68 Sn-113 .15 Ce-144 .08 Zn-65 .21 Nb-95 6.42 12

B. Sealed Sources No shipments in 2009 C. Sealed Sources/Smoke Detectors No shipments in 2009 D. Irradiated Components No shipments in 2009 13

Attachment 3 Unplanned Offsite Releases

McGUIRE NUCLEAR STATION UNPLANNED RELEASES (January 1, 2009 through December 31, 2009)

There were no dhplanned liquid radioactive releases to the environment in 2009. There were four unplanned gaseous radioactive effluent releases to the environment in 2009.

Januaiy 28, 2009 Memorandum To: Annual Radioactive Effluent Release Report CC: Steve Mooneyhan, H. J. Sloan, Joyce Correll, C.D. Ingram, Duncan Brewer, Ken Ash, Kay Crane From: William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit 2 Vent Reference PIP M-09-0418 Event Summary:

See referenced PIP for details.

On January 26, 2009 19:45 to 20:45 hours, an unplanned WG release event occurred allowing 139cubic feet (cf) of noble gas tobe release to the Auxiliary Bld ventilation (VA) system out to the Unit 2 Vent release path.

-. -: Auxiliary Bld VA system gas monitor EMF 41 presented with a trip 2 alarm, at --20:00hrs. Both the Unit 2 Vent gas monitor 2EMF36 and EMF41 were trended with both indicating elevated counts. EMF41 peaked @

-380cpm and 2EMF36 peaked @ -35cpm. Both monitors indication were well below offsite limits with the release clearing to normal within an hour.

At initiation of the release a high rad trip occurred on EMF-41 point #11. This caused the VA system to be switched to the filtered mode. While investigating the trip actuation samples were obtained in the area of the Boron Recycle (NB) Evaporator which indicated residual noble gas. Initial investigation indicates WG compressor tripped causing the compressor suction line to become pressurized and push gas to the NB Evaporator which allowed gas to be leaked by evaporator seals and valve 1NB-158 to the Aux. Bldg ventilation duct to the Unit Vent.

No off site release limits were challenged. A conservative calculation indicates 1.94E-2 curies of fission and activation gas (noble gas) were released to the Unit 2 Vent during this event. The source of the noble gas was determined to be from (B in-service WGDT) which was sampled to document activity released.

Sequence of events:

  • 19:45 WG- A compressor tripped and elevated counts were seen on 2 EMF36
  • 20:10 EMF41 Point 11 trip 2 actuation
  • 20:35 WG- A compressor restarted. A small drop in WGDT-B pressure was noted which indicates the activity source.

& 1/27/09 WGDT-B sampled to account for activity released to the unit 2 vent.

  • 1/27/09 SRPMP 8-2 "Investigation of Unusual Radiological Occurrences" was initiated to document the Unplanned Release investigation.
  • 1/27/09 Special meetingconducted to plan repair and restoration of the NB Evaporator.

The total Noble gas activity released was reported on (GWR) Gaseous Waste Release # 2009003.

The unplanned activity was evaluated against off site dose limits using current ODCM methodology on the attached spreadsheet and confirmed with RETDAS dose assessment software.

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 Harry Sloan RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station

September4, 2009 Memorandum To: Annual Radioactive Effluent Release Report CC: Steve Mooneyhan, H. J. Sloan, Joyce Correll, C.D. Ingram, Duncan Brewer, 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-09-4874 Event Summary:

See referenced PIP for details.

On September 4, 2009 at about 18:24 operations received an annunciator alarm on Auxiliary Bldg Ventilation (VA) monitor EMF 41, point #1 with a reading of 717 cpm. Radiation Protection was notified to investigate and sample Unit 1 Vent. The trip actuation caused Auxiliary Bldg VA filters to automatically be placed in service. Radwaste Chemistry staff was performing maintenance on the portable Orbisphere Analyzer which is used to support primary system degas operations. The Hydrogen probe had been removed and cleaned, the flow gauge was removed to remove water, and then was reattached. The probe and associated tubing was purged with inert gas for an extended period of time prior to. re-attachment. After re-attaching the tubing, system gas from VCT was aligned. EMF-41 alarmed shortly following this evolution. Radwaste Chemistry staff re-tightened the tubing previously removed. Unit I Vent monitor 1 EMF-36 and EMF-41 elevated count rate returned to normal. The release lasted 80 min. The Unit I Venthad a 10 min average peak response of 200 cpm above background (30 cpm). This 200 cpm increase is 5% of the calculated maximum allowed 41 00cpm. No off site release limits were challenged during this event. A sample was obtained from the B shut down WGDT which was representative of the activity released.

Sequence of Events:

  • At 17:51 1EMF36L entered Trip 1 reading 113 cpm and peaked at 242 cpm at

-18:24. (Trip I Setpoint is 60 cpm and Trip 2 is set at 500 cpm)

  • At 18:24, OEMF41 entered Trip 2 on Point 1 at 757 cpm (Trip 1 is set at 150 cpm and Trip 2 is set at 200 cpm). Point 4 also went into Trip 2 alarm reading 1210 cpm.
  • At 18:25, RP Shift initiated HP/0/B/1009/026 (EMF Alarm/Unusual Event Response) in response to the Trip 2 alarms on OEMF4 1.

" At 18:27, 1EMF36L was sampled with the following results: Ar-41 at 1.496E-06 uCi/ml and Xe-135 at 3.585E-08 uCi/ml.

  • At 18:30, RP S&C was notified and proceeded to restrict entry into the Auxiliary Building by posting guards at the north and south Aux. Bldg. entry turnstiles.
  • At 18:35, Chemistry was called to inform them of the Trip 2 alarms on OEMF41.

" At 18:55, RP verified with Operations that Unit 1 and 2 VA were in Filtered mode.

" At 19:08, the Control Room was notified by RP that OEMF41 levels had returned to normal and that 0EMF41 could be reset.

  • At 19:09, RP informed Chemistry that their recovery efforts were successful and EMF readings were returning to normal.
  • 4t 19:13, 1EMF36L had returned to normal at -22 cpm.

" At 19:13, RP S&C were informed that entry into the Aux. Bldg could now be resumed.

" At 19:43, RP verified with Operations that the Unit I & 2 VA Filtered Exhaust was now back in Bypass.

The total Noble gas activity released is reported on (GWR) Gaseous Waste Release

  1. 2009056.

The unplanned activity was evaluated against off site dose limits using current ODCM methodology on the attached spreadsheet and confirmed with RETDAS dose assessment software.

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 limits specified by Selected Licensee Commitments and Code of Federal Regulations.

W.C. Spencer Harry Sloan RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station

September 11,2009 Memorandum To: Annual Radioactive Effluent Release Report CC: Steve Mooneyhan, H. J. Sloan, Joyce Correll, C.D. Ingram, Duncan Brewer, Ken Ashe, Kay Crane From: William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit I Vent from WGDT-C Reference PIP M-09-05081 Event Summary:

See referenced PIP for details.

On September 9th, 2009 Radwaste Chemistry 7 day trending identified a pressure loss indication from the Waste Gas Decay Tank C (WGDT-C). Data trending indicated the pressure loss started on 8/29/09 around 01:1 5hrs and continued until 9/09/09 11:30hrs. Immediate contact with Radiation Protection was made and monitoring of Unit 1 vent 1EMF 36L and EMF 41Auxilliary building gas monitor was performed. No count rate increases were seen on either monitor during the period of pressure loss from WGDT-C. Since no count rate increase was seen on plant monitors it indicates that the activity in the WGDT-C was at a concentration below detection limits of the monitors. No pressure increases were seen in other WGDTs during the release period. Valves associated with WGDT-C were snooped with no visible leak seen. It is surmised that the gas escaped from the tank through a leaking component or valve into the auxiliary building ventilation and exhausted through the Unit I vent. Follow up leak investigation will be required to identify the leak site. Chemistry has calculated a 26 psi pressure loss or 1061 cubic ft of noble gas released over the period. Chemistry transferred the remaining tank contents into WGDT-A on 9/09/09 11:30hrs. The A tank was sampled to determine radioactivity released. The A tank had received several recent system inputs and it was found to contain a number of short lived nuclides not normally found in an aged WGDT. Further investigation shows the WGDT-C had been secured from system use on May 19, 2009. No additional inputs were received by the C tank until the leak occurred.

Therefore using a conservative estimate of 112 day decay period (10 half lives), all short lived nuclides would have decayed leaving only KR-85 with a 10.72 year half life. The concentration of KR-85 in the WGDT-A tank was 2.77E-5 uci/ml. This value is used to estimate offsite release impact to the public.

The unplanned activity was evaluated against off site dose limits using currant ODCM methodology on the attached spreadsheet and confirmed with RETDAS dose assessment software. No off site release limits were challenged. A conservative calculation indicates 8.32E-4 curies of KR-85 noble gas were released to the Unit I Vent during this event. The source of the noble gas was from WGDT-C. The total Noble gas activity released is reported and accounted for in (GWR) Gaseous Waste Release # 2009057.

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 Harry Sloan RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station

Demnbr4, 2009 Memorandum To: Annual Radioactive Effluent Release Report CC: Joe Smith, H. J. Sloan, Joyce Correll, C.D. Ingram, From: William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Abnormal release to the Unit 1 Vent from leaking IWG-122 post maintenance ReferencePIP M-09-07303 Event Summary:

See referenced PIP for details.

Maintenance was performed on 1 WG-122 due to a leak previously identified during a waste gas decay tank (WGDT) loss of volume event involving WGDT-C. See PIP M-09-5081 event details.

After notification of ongoing leak, RP took the following actions in response to 1 WG-122 leak associated with planned maintenance.

EMF 41 (aux bld noble gas monitor) point # 4 and Unit I vent noble gas monitor I EMF 36 L were trended and evaluated for any response to the potential waste gas leak. No response was observed on either EMF.

The WGDT-C was initially pressurized at 12/3/09 15:52hrs. The leak check was performed around 17:30hrs and RP was notified that a small weeping leak was ongoing. Chemistry and RP maintained surveillance of the tank pressure and EMF response to ensure radiological conditions remained unchanged.

The very small leak rate did not present a radiological hazard.

The area at and around the valve was checked and no contamination found.

The WGDT-C was sampled at 21:32 hrs and Kr-85 at 8.2E-6 uCi/ml concentration was identified. This compared well with expected residual activity remaining in the tank from the last noble gas transfer from the tank. RP prepared gaseous waste release permit (GWR) #2009081 in preparation for a WGDT-C release to relieve the pressure on the leaking valve in preparation for follow up valve maintenance and re-check of valve integrity. The WGDT-C release was initiated at 12/4/09 09:45hrs and terminated at 13:l2hrs.

The KR-85 activity release during the period fiom IWG-122 to the unit I vent was calculated to be 106.1 cubic ft (2.46E-5 curies). The average release rate was 0.1 cfin over 17.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. No response above background was seen on unit vent or auxiliary building noble gas monitors during the period. No off site limits were jeopardized. GWR #2009082 was generated to document the Unit I vent abnormal release.

Safety Significance:

The health and safety of the public were not compromised by this event. The total activity released was insignificant.

W.C. Spencer Harry Sloan RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station

Attachment 4 Fuel Cycle Calculation

McGuire Nuclear Station 2009 Radioactive Effluent Releases 40CFR190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFR190, 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. 2009 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 = 3.73E-01 mrem Maximum Location: 0.5 Mile, East-Northeast Sector Critical Age: Child Gas non-NG Contribution: 47%

Gas NG Contribution: 7%

Liquid Contribution: 46%

Maximum Organ (other than TB) Dose = 3.50E-01 mrem Maximum Location: 0.5 Mile, East-Northeast Sector Critical Age: Child Critical Organ: Liver Gas Contribution: 50%

Liquid Contribution: 50%

II. 2009 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 10CFR72.212 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 10CFR72.212 Written Evaluations" report is provided to document the method used to calculate the McGuire ISFSI 14.5 mrem/year dose estimate.

  • The effluent dose calculations consider radionuclides identified as part of the liquid and gaseous wastes sample and analysis program per SLC Table 16.11.1-1 and SLC Table 16.11.6-1.

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

10CFR72.212 Evaluation report.

j

6.0 10 CFR 72.212(b)(2)(i)(C) - Radioactive Materialsin Effluents and Direct Radiation 6.1 Purpose 10 CFR 72.212(b)(2)(i)(C) requires the general licensee to perform written evaluations, prior to use, that establish that the requirements of 10 CFR 72.104 have been met. A copy of this record must be retained until spent fuel is no longer stored under the general license issued under 10 CFR 72.210.

10 CFR 72.104 provides the regulatory criteria for radioactive materials in effluents and direct radiation from an independent spent fuel storage installation (ISFSI) during normal operation and anticipated occurrences.

Specifically, 10 CFR 72.104(a) limits the annual dose equivalent to any real individual who is located beyond the controlled area to 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other critical organ. This dose equivalent must include contributions from (1) planned discharges of radioactive materials (radon and its decay products excepted) to the general environment, (2) direct radiation from ISFSI operations, and (3) any other radiation from uranium fuel cycle operations within the region. In addition, 10 CFR 72.104(b) requires that operational restrictions be established to meet as low as is reasonably achievable (ALARA) objectives for radioactive materials in effluents and direct radiation levels associated with ISFSI operations. Also, 10 CFR 72.104(c) requires that operational limits be established for radioactive materials in effluents and direct radiation levels associated with ISFSI operations to meet the above-mentioned dose limits.

This section provides the written evaluation required by 10 CFR 72.212(b)(2)(i)(C) demonstrating Duke Energy's compliance with the requirements of 10 CFR 72.104 for the McGuire Nuclear Station (MNS)

Independent Spent Fuel Storage Installation (ISFSI).

6.2 Evaluation This evaluation addresses the radiological dose rate from a composite population of both the NAC-UMS and the TN-32A casks.

6.2.1 §72.104(a) - Dose Limits Historical TLD Monitoring Attachment 2 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 McGuire Nuclear Station ISFSI Page 48 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

the actual dose values from the ISFSI in those areas around the plant.

From Attachment 2, 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-32A 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-32A 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 1OCR 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. (For McGuire, compliance with'this regulation will also assure compliance with 40 CFR Part 190.) 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 (Reference 1). The best-fit empirical equation for skyshine dose rate as a function of distance is y = 0.0156eýOll 2 x for gammas and y = 0.0274e-°.°129x 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 y = 492.69x2 1688 for gammas and y = 166.95x 20696 for neutrons, where y is dose rate (mrem/hr) 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 (Reference 2). 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.

McGuire Nuclear Station ISFSI Page 49 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

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 <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> 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) 40 CFR 190 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 40CFRI90 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") define "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 40 CFR 190.10(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 McGuire Nuclear Station ISFSI Page 50 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

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 10 CFR 72.106(c). Since the public is permitted access into the controlled area at McGuire, the dose rate must be below 2 mrem per hour and the annual dose must be below 100 mrem within the controlled area (10 CFR 20.1301(b); see also 10 CFR 20.1301(a)(2)).

A member of thepublic 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 <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> 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 <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> 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 residence time of 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />, 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 40CFR1 90. Note that only 28 NAC-UMS casks are included in the McGuire ISFSI.

McGuire Nuclear Station ISFSI Page 51 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

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-32A 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"02 mrem/hr.

(10) Casks X 7.443 E-02 mrem/hr = 0.744 mrem per hour Actual measured dose rate for the first ten casks stored in the ISFSI = 0.0249 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 <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> 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 McGuire Nuclear Station ISFSI Page 52 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

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"0 3 mrem/hr X 150 hrs (residence time/yr) =

12.36 mrem per year Normalized actual dose = 0.0335 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 <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> this equates to:

(157.3 mrem/yr) / (8760 hrs/yr) x 150 hrs (residence time/yr) =

2.69 mrems / yr 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 -

4-25 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-04 mrem/hr.

(10) Casks X 2.48 E°4 mrem/hr X 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> 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 McGuire Nuclear Station ISFSI Page 53 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

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 6.2.2 §72.104(b) - OperationalRestrictions The ISFSI is sited in such a way that direct radiation to the surroundings are minimized due to the berm to the north and the fall of the land to the west, which are the two directions the ISFSI is closest to the public.

The station Radiation Protection Program limits for ISFSI boundary dose rates (as described in RPMP 7-8) are established to maintain dose rates surrounding the ISFSI and at the owner control fence north of the ISFSI ALARA. The dose rate limit of 0.05 mrem/hr at the owner control fence assumes an occupancy time of 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, which is far more conservative than the 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> used in the previous evaluation section for this area.

6.2.3 §72.104(c) - OperationalLimits Cask radiation limits are established by the NAC-UMS Technical Specification (TS) LCO 3.2.2 (50 mrem/hr on cask side and top and 100 mrem/hr on vents) to meet the limits of 10 CFR 72.104(a). Site procedures are written in accordance with this TS and demonstrate compliance with each cask load by performance of the TS radiation survey exactly as prescribed by the TS.

6.3 Regulatory Compliance/Conclusion

-The evaluation summarized above demonstrates that Duke meets the requirements of 10 CFR 72.212(b)(2)(i)(C) and 10 CFR 72.104 for the MNS ISFSI.

6.4 References

1. 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
2. NAC Calc 12418-5001, "Skyshine Evaluation of McGuire ISFSI,"

Rev.0, dated 11/26/03

3. NRC 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"
4. Duke Energy McGuire Nuclear Station Procedure No. RPMP 7-8, "Maintaining RCZs Associated with ISFSI" McGuire Nuclear Station ISFSI Page 54 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

Attachment 5 Inoperable Monitoring Equipment

McGuire Nuclear Station Inoperable Monitoring Equipment (January 1, 2009 through December 31, 2009)

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

Attachment 6 Groundwater Protection Program

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 2009 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 2009 are shown in the table below.

Avg. Tritium Conc. # of Well Name Well Location Conc.(pCi/1) Range Samples M-20 South of Hwg. 73 568 436-658 4 M-20R South of Hwg. 73 567 561 - 575 4 M-21 South of Hwg. 73 < < 4 M-22 South of Hwg. 73 < < 4 M-22R South of Hwg. 73 219 < - 219 4 M-23 South of Acs. Rd. < << 4 M-30 WWCB < << 4 M-30R WWCB 212 182-268 4 M-31 Access road < < 4 M-32 Main entrance < < 4 M-34R Access road < < 4 M-34DR Access road < < 4 M-35 Access road < << 4 M-42 U-2 Rx. Bldg. 1680 1270 - 1870 4 M-48 U-2 SFP *

  • 0 M-48R U-2 SFP 967 872 - 1010 4 M-48DR U-2 SFP 581 503 - 678 4 M-53 North of plant 1265 1190- 1420 4 M-55 North Admin. Bldg. 315 <- 315 4 M-59 U-2 Doghouse 1090 849 - 1180 4 M-60 MOC Parking < < 4 M-62 S of RWF 220 <-220 4 M-64 Rdwst. Bldg. 640 558 - 746 4 M-66 S of SSF 586 474-661 4 M-66R S of SSF < << 4 M-68 U-1 RMWST 1056 810-1270 4 M-70 U-1 SFP 433 300 - 659 4 M-70R U-1 SFP 280 < - 324 4 M-70DR U-1 SFP 183 <- 191 4

ARERR Groundwater Well Data Section Rev. 1 M-72 Rdwst. Trench 668 549 - 793 4 M-76 West of U-I SFP 396 251 -489 4 M-82 River 2103 1770-2400 4 M-84 River 3910 2490-5050 4 M-84R River 7498 7320 - 7800 4 M-85 River 1663 1500- 1780 4 M-87 Landfarm 485 363 - 555 4 M-89 Landfarm 817 676- 885 4 M-90 Landfarm 295 295 1 M-91 East of WC 272 < - 347 4 M-91R East of WC 279 <- 388 4 M-92 N of WC Ponds 292 220 - 496 4 M-92R N of WC Ponds 203 < - 203 4 M-93 North of IHUP 369 275-486 4 M-93R North of IHUP 303 174-388 4 M-94 SE of IHUP < < 4 M-95 Lower Parking < < 4 M-95R Lower Parking < < 4 M-96 West Parking < < 4 M-96R West Parking < < 4 M-97 East Parking 279 179 - 339 3 M-98 S of Admin. Bldg. < < 4 M-98R S of Admin. Bldg. < < 4 M-IOOR SE of WC 243 210-268 4 M-101 SE of WC 324 253 -423 4 M-102 SW of WC 7893 7810-8160 4 M-103 South of WC 3653 3270-4150 4 M-103R South of WC 3305 2490-3620 4 M-104R West of WC 8655 7590-9740 4 M-104DR West of WC 5738 5350-6050 4 M-105 Landfarm 294 294 1

  • Well dry; no sample available.

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

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