ML061350135

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Annual Radioactive Effluent Release Report for 2005
ML061350135
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 04/27/2006
From: Gordon Peterson
Duke Energy Carolinas, Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML061350135 (53)
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GARY R. PETERSON Duke Vice President A"Energyt7 McGuire Nuclear Station Duke Energy Corporation MGOI VP / 12700 Hagers Ferry Rd.

Huntersville, NC 28078 704 875 5333 704 875 4809 fax grpeters@duke-energy. corn April 27, 2006 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Subject Duke Power Company LLC d/b/a 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 Manual (SLC), attached is the Annual Radioactive Effluent Release Report. CD-Roms are attached containing the revised Offsite Dose Calculation Manual and Radioactive Waste Process Control Program Manual.

The following Attachments form the contents of the report:

Attachment I 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 Questions concerning this report should be directed to Kay Crane, McGuire Regulatory Compliance at (7Cz) 875- 6.

A7.)

Gary R. Peterson 4'8 www. duke-energy. corn

NRC Document Control Desk April 27, 2006 Page 2 cc: Mr. J. F. Stang, NRC Project Manager Office of Nuclear Reactor Regulation Mail Stop 8-H4A Washington, D.C. 20555 Mr. William D. Travers, 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, 2005 through December 31, 2005)

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 1/1/05 TO 1/1/06 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2005 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Gases

1. Total Release Ci 1.19E+00 8.55E-01 6.62E-01 8.09E-01 3.51E+00
2. Avg. Release Rate pCi/sec 1.53E-01 1.09E-01 8.33E-02 1.02E-01 1.llE-01 B. Iodine-131
1. Total Release Ci 0.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00
2. Avg. Release Rate ACi/sec 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 C. Particulates Half Life >. 8 days
1. Total Release Ci 6.12E-06 4.84E-05 1.31E-06 9.68E-08 5.60E-05
2. Avg. Release Rate pCi/sec 7.87E-07 6.16E-06 1.65E-07 1.22E-08 1.77E-06 D. Tritium
1. Total Release Ci 6.04E+01 6.42E+01 1.29E+02 8.83E+01 3.42E+02
2. Avg. Release Rate pCi/sec 7.77E+00 8.16E+00 1.62E+01 1.11E+01 1.08E+01 E. Gross Alpha Radioactivity
1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
2. Avg. Release Rate pCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2005 Unit QTR 1 gTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases
    • No Nuclide Activities **........ ........ ........ ........ ........
2. lodines
    • No Nuclide Activities **........ ........ ........ ........ ........
3. Particulates Half Life >- 8 days
    • No Nuclide Activities **........ ........ ........ ........ ........
4. Tritium
    • No Nuclide Activities **........ ........ ........ ........ ........
5. Gross Alpha Radioactivity
    • No Nuclide Activities ** ........ ........ ........ ........ ........

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2005 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 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2005 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 CO-58 Ci I6.12E-06 4.84E-05 1.31E-06 9.68E-08 5.60E-05 Totals for Period... Ci 6.12E-06 4.84E-05 1.31E-06 9.68E-08 5.60E-05
4. Tritium H-3 Ci 5.88E+01 6.38E+01 1.26E+02 8.75E+01 3.36E+02 Totals for Period... Ci 5.88E+01 6.38E+01 1.26E+02 8.75E+01 3.36E+02
5. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2005 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases AR-41 Ci 5.39E-01 4.56E-01 5.17E-01 4.03E-01 1.91E+00 C-ll ci 1.46E-04 0.00E+00 0.00E+00 2.23E-05 1.68E-04 KR-85 ci 5.81E-01 3.67E-01 8.13E-02 3.62E-01 1. 39E+00 KR-85K ci 0.00E+00 0.00E+00 0. 00E+00 2.391-04 2.39E-04 XE-133 ci 6.45E-02 3.12E-02 6.24E-02 4.35E-02 2.02E-01 XE-135 ci 4.07E-03 1.71E-03 1.62E-03 4.70E-05 7.45E-03

________ 8_55____ 6_62__01 ________ 3_51__00 Totals for Period... ci l.l9E+00 8.55E-01 6.62E-01 8.09E-01 3.51E+00

2. lodines
    • No Nuclide Activities **
3. Particulates Half Life >= 8 days
    • No Nuclide Activities **
4. Tritium H-3 Ci 1.64E+00 3.95E-01 2.87E+00 7.67E-01 5.67E+00

____ ____ 3__5____ 2_871_00 Totals for Period... Ci 1.64E+00 3.95E-01 2.87E+00 7.67E-01 5. 67E+00

5. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2005 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 2.49E-02 1.38E-02 1.58E-02 1.56E-02 7.02E-02
2. Average Diluted Concentration
a. Continuous Releases pCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
b. Batch Releases pCi/ml 3.43E-11 1.45E-11 1.65E-11 1.77E-11 1.99E-11 B. Tritium
1. Total Release Ci 2.86E+02 3.34E+02 4.69E+02 3.46E+02 1.43E+03
2. Average Diluted Concentration
a. Continuous Releases pCi/ml 1.91E-08 1.19E-08 1.33E-08 2.81E-08 1.73E-08
b. Batch Releases pCi/ml 3.94E-07 3.50E-07 4.88E-07 3.89E-07 4.06E-07 C. Dissolved and Entrained Gases
1. Total Release Ci 2.45E-05 7.55E-06 4.78E-06 7.81E-06 4.46E-05
2. Average Diluted Concentration
a. Continuous Releases ACi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
b. Batch Releases pCi/ml 3.37E-14 7.92E-15 4.99E-15 8.81E-15 1.27E-14 D. Gross Alpha Radioactivity
1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
2. Average Diluted Concentration
a. Continuous Releases pCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
b. Batch Releases pCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Volume of Liquid Waste
1. Continuous Releases liters 5.47E+07 6.14E+07 6.44E+07 7.89E+07 2.60E+08
2. Batch Releases liters 2.59E+07 8.65E+05 1.18E+06 8.50E+05 2.87E+07 F. Volume of Dilution Water
1. Continuous Releases liters 5.01E+10 5.84E+10 7.47E+10 4.78E+10 2.31E+ll
2. Batch Releases liters 7.25E+11 9.53E+11 9.59E+11 8.86E+11 3.52E+12

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID EFFLUENTS - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2005 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products
    • No Nuclide Activities **
2. Tritium H-3 Ci 9.57E-01 6.95E-01 9.94E-01 1.34E+00 3.99E+00

______- _ 6.______ 3.______

Totals for Period... Ci 9.57E-01 6.95E-01 9.94E-01 1.34E+00 3.99E+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 1/1/05 TO 1/1/06 LIQUID EFFLUENTS - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2005 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products AG-108M Ci 1.26E-04 0.00E+00 5.02E-05 3.74E-05 2.13E-04 AG-110M Ci 4.86E-04 5.00E-05 2.24E-04 1.49E-04 9.08E-04 BE-7 Ci 0.00E+00 0.00E+00 0. 00E+00 2.00E-05 2.00E-05 CD-115 Ci 0.00E+00 0.00E+00 0. 00E+00 1.23E-05 1.23E-05 CO-57 Ci 1.28E-04 7.41E-06 5.44E-05 2.69E-06 1.93E-04 CO-58 Ci 5.51E-03 3.81E-03 2.53E-03 3.48E-03 1.53E-02 CO-60 Ci 9.78E-03 1.05E-03 7.55E-03 3.03E-03 2.14E-02 CR-51 Ci 4.21E-03 2.45E-03 1.18E-03 4.95E-03 1.28E-02 CS-134 Ci 2.04E-04 6.05E-05 8.21E-05 9.95E-05 4.47E-04 CS-137 Ci 3.24E-04 1.53E-04 3.28E-04 4.01E-04 1.21E-03 FE-59 Ci 1.57E-04 2.17E-04 2.49E-04 1.28E-04 7.51E-04 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 4.07E-06 4.07E-06 MN-54 Ci 1.73E-03 1.59E-04 9.66E-04 4.21E-04 3.28E-03 NB-95 Ci 1.80E-04 8.03E-05 4.60E-05 2.35E-04 5.42E-04 NB-97 Ci 2.46E-05 8.63E-06 1.31E-05 2.20E-05 6.83E-05 SB-124 Ci 9.68E-06 2.86E-04 8.38E-06 8.18E-05 3.86E-04 SB-125 Ci 1.89E-03 5.50E-03 2.53E-03 2.45E-03 1.24E-02 SN-113 Ci 1.13E-05 0.00E+00 6.35E-06 0. 00E+00 1.77E-05 SR-92 Ci 2.48E-05 0.00E+00 0.00E+00 0.00E+00 2.48E-05 ZN-65 Ci 4.87E-05 0.00E+00 0.00E+00 0.00E+00 4.87E-05 ZN-69M Ci 5.16E-06 0.00E+00 0.00E+00 0.00E+00 5.16E-06 ZR-95 Ci 3.15E-05 1.63E-05 1.59E-05 1.10E-04 1.74E-04 Totals for Period... Ci 2.49E-02 1.38E-02 1.58E-02 1.56E-02 7.02E-02
2. Tritium H-3 Ci 2.85E+02 3.33E+02 4.68E+02 3.44E+02 1.43E+03

______ __ 3_33__02 4___8__0 3_______ 1______0 Totals for Period... Ci 2. 85E+02 3.33E+02 4.68E+02 3.44E+02 1.43E+03

3. Dissolved and Entrained Gases XE-133 Ci 2.45E-05 7.55E-06 4.78E-06 7.81E-06 4.46E-05

-------- -------- -------- 4----

Totals for Period ... Ci 2.45E-05 7.55E-06 4.78E-06 7.81E-06 4.46E-05

4. Gross Alpha Radioactivity
    • No Nuclide Activities **

McGUIRE NUCLEAR STATION SUPPLEMENTAL INFORMATION

McGUIRE NUCLEAR STATION 2005 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 a 10 MRAD 2. CALENDAR QUARTER - ORGAN DOSE 5 KREM
3. CALENDAR YEAR - GAMMA DOSE - 10 MRAD 3. CALENDAR YEAR - TOTAL BODY DOSE - 3 MREM
4. CALENDAR YEAR - BETA DOSE a 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. 2.05E+02 - TOTAL NUMBER OF BATCH RELEASES
2. 4.20E+04 a TOTAL TIME (MIN.) FOR BATCH RELEASES.
3. 3.04E+04 - MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
4. 2.05E+02 - AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
5. 2.OOE+00 - MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
6. 1.77E+06 - AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B. GASEOUS EFFLUENT

1. 5.20Z+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. 2.02E+04
  • AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
5. 2.0OE+02
  • MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

VI. ABNORMAL RELEASES A. LIQUID

1. NUMBER OF RELEASES - 0
2. TOTAL ACTIVITY RELEASED (CURIES) - O B. GASEOUS
1. NUMBER OF RELEASES - 0
2. TOTAL ACTIVITY RELEASED (CURIES) - o

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

McGUIRE NUCLEAR STATION Assessment of Radiation Dose from Radioactive Effluents and all Uranium Fuel Cycle Sources to Members of the Public (January 1, 2005 through December 31, 2005)

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 190. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 l Quarter 2005

  • -- IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS------- Quarter 1 2005 *---

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD LUNG 1.71E-01 1.50E+01 1.14E+00 Maximum Organ Dose Receptor Location: 0.5 Mile E Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage

____0___0_

E-3 1.00E+02

  • -- NOBLE GAS DOSE LIMIT ANALYSIS --------------- S ....----.. Quarter 1 2005 *---

Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q1 - Maximum Gamma Air Dose 1.221-02 1.001+01 1.22E-01 Maximum Gama Air Dose Receptor Locationt 0.5 Mile MNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.92E+01 Q9 - Maximum Beta Air Dose 7.18E-03 2.001+01 3.59E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nucide Percentage AR-41 5. 94B+01 KR-85 3.80Z+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2005 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS ------ Quarter 2 2005 .--.

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LUNG 1.82E-01 1.50E+01 1.213+00 Maximum Organ Dose Receptor Locations 0.5 Mile Z Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00+E02

  • -- NOBLE GAS DOSE LIMIT ANALYSIS------------------------- Quarter 2 2005 ----

Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose 1.03E-02 1.003+01 1.033-01 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 Q2 - Maximum Beta Air Dose 5.42E-03 2.003+01 2.713-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 6.653+01 KR-85 3.183+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2005

  • -- IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS..=.... Quarter 3 2005 ----

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LUNG 3.653-01 1.50E+01 2.44E+00 Maximum Organ Dose Receptor Location: 0.5 Mile E Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02

--. NOBLE GSM DOSE LIMIT ANALYSIS.------------------------- Quarter 3 2005 ....

Dose Limit  % of Period-Limit (mrad) (mred) Limit Q3 - Maximum Gamma Air Dose 1.17E-02 1.00E+01 1.171-01 Maximum Gamma Air Dose Receptor Locations 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.95E+01 Q3 - Maximum Beta Air Dose 4.641-03 2.00E+01 2.32Z-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 8.81E+01 KR-85 8.25E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4th Quarter 2005

  • -- IODINE, 83, AND PARTICULATE DOSE LIMIT ANALYSIS------- Quarter 4 2005 *---

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LUNG 2.50E-01 1.50E+01 1.67E+00 Maximum Organ Dose Receptor Location: 0.5 Mile E Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage 8-3 1.OOE+02

  • - NOBLE GAS DOSE LIMIT ANALYSIS ------------------------- Quarter 4 2005 ....

Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Gama Air Dose 9.11E-03 1.00E+01 9.111-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage

___94__+01 aR-41 9.94E+01 Q4 - Maximum Beta Air Dose 5.01Z-03 2.003+01 2.501-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 6.38Z+01 KR-85 3.403+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 AMNAL 2005 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS------- Annual 2005 *-------

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LUNG 9.69E-01 3.OOE+01 3.23E+00 Maximum Organ Dose Receptor Location: 0.5 Mile E Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.OOE+02

  • -- NOBLE GAS DOSE LIMIT ANALY15 .................-..-..-.. Annual 2005 *---....

Dose Limit  % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Gamma Air Dose 4.32E-02 2.00E+01 2.16E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.943+01 Yr - Maximum Beta Air Dose 2.23E-02 4.003+01 5.56E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 6.81E+01 KR-85 2.94E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 1t Quarter 2005

  • -- BATCH LIQUID RELEASES *--,.... C........ritia ==l. .... Quarter 1 2005 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD LIVER 4.45E-02 1.00E+01 4.453-01 Ql - Total Body Dose CHILD 4.173-02 3.00E+00 1.39E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.133+01 Total Body Critical Pathways Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.75E+01

--- CONTINUOUS LIQUID RELEASES (WC) ...................... Quarter 1 2005 ------

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD LIVER 1.973-03 1.00E+01 1.97E-02 Q1 - Total Body Dose CHILD 1.97E-03 3.00E+00 6.57E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage 8-3 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 1/1/05 TO 1/1/06 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2005

  • -- BATCH LIQUID RELEASES ...--..--. I...................... Quarter 2 2005 ------

CriticsLl Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 3.763-02 1.003+01 3.761-01 Q2 - Total Body Dose CHILD 3.671-02 3.001+00 1.22Z+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.718+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage 3-3 9.943+01

  • -- CONTINUOUS LIQUID RELEASES (WC) ... . .-. . . .. . . Quarter 2 2005 -----=

Critics Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (nrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 1.24E-03 1. 00+01 1.243-02 Q2 - Total Body Dose CHILD 1.24E-03 3.003+00 4.143-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00+E02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage K-3 1.00E+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2005

..- BATCH LIQUID RELEASES *-.,.............................. Quarter 3 2005 .--...

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 5.36E-02 1.00E+01 5.36Z-01 Q3 - Total Body Dose CHILD 5.20E-02 3.003+00 1.73E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage

____9_____

H-3 9.59Z+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.89Z+01 CONTINUOUS C-- LIQUID RELEASES (WC) *- Quarter 3 2005 -----

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 1.40E-03 1.003+01 1.403-02 Q3 - Total Body Dose CHILD 1.40E-03 3.00E+00 4.68E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or ggreater to total)

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

Nuclide Percentage H-3 1.00E+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4 th Quarter 2005

  • -- BATCH LIQUID RELEASES *..------.- Quarter 4 2005 -----

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 4.388-02 1.OOE+01 4.38E-01 Q4 - Total Body Dose CHILD 4.16E-02 3.00E+00 1.39E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage E-3 9.373+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.873+01

  • -- CONTINUOUS LIQUID RELEASES (WC) *-------------,------- Quarter 4 2005 ------

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 2.963-03 1.003+01 2.963-02 Q4 - Total Body Dose CHILD 2.96E-03 3.003+00 9.873-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.003+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/05 TO 1/1/06 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2005

  • -- BATCH LIQUID RELEASES -- --C..ritical Annual 2005 *--------

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

_.__________________________ _CHILD Yr - Maximum Organ Dose CHILD LIVER 1.79E-01 2.00+01 8.978-01 Yr - Total Body Dose CHILD 1.72E-01 6.00E+00 2.87E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.47E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage

________0_

H-3 9.87E+01

  • -- CONTINUOUS LIQUID RELEASES (WC) a----- .----

a.....--.. Annual 2005 ......=..

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 7.22E-03 2.00E+01 3.611-02 Yr - Total Body Dose CHILD 7.22E-03 6.00E+00 1.20E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage 3-3 1.001+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 1.00E+02

Attachment 2 Solid Waste Disposal Report

REPORT PERIOD McGUIRE NUCLEAR STATION Attachment I JANUARY - DECEMBER 2005 SOLID RADIOACTIVE WASTE SHIPPED TO DISPOSAL FACILITIES I TYPES OF WASTES SHIPPED i Number of Number of Container Disposal Volume Waste Total Waste from Liquid Systems Shipments Containers Type ftl m3 Class Curles (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 1 1 HIC 215 6.09 B 4.15E+00 (F) dewatered primary bead resin 1 1 HIC 120 3.40 B 5.51E+01 (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) 1 HIC 195 5.52 A/S 1.64E+00 dry active waste (brokered/compacted) dry active waste (brokered/non-compacted) 9 17 DBP 877.55 24.85 A/U 2.280E+00 (B) sealed sources/smoke detectors none (C) sealed sources none (D) irradiated components none Totals 12 20 1407.55 39.86 6.317E+01 4/24/2006

MCGUIRE NUCLEAR SITE

SUMMARY

OF MAJOR RADIONUCLIDE COMPOSITION 2005 l Type of waste Nijclide  % Abundance I

1. Waste from liquid systems:

A. Dewatered Powdex Resin (brokered) No shipments in 2005 B. Dewatered Powdex Resin No shipments in 2005 C. Dewatered Bead Resin (brokered) No shipments in 2005 D. Dewatered Bead Resin No shipments in 2005 E. Dewatered Radwaste System Resin (brokered) Nuclide  %/oAbundance 2005-20 Co-60 3.26 Cs-137 21.97 Fe-55 7.38 Ni-63 67.27 Sb-125 0.13 F. Dewatered Primary Bead Resin (brokered) Nuclide  %/cAbundance 2005-29 Mn-54 .73 Co-57 0.08 Co-58 1.48 CO-60 17.26 Cs-137 2.65 Cs-134 0.07 Ni-63 61.78 Fe-55 15.55 Sb-125 .33 H-3 .02 Sr-90 .03 G. Dewatered Mechanical Filter Media No shipments in 2005 H. Dewatered Mechanical Filter Media No shipments in 2005 (brokered)

I. Solidified Waste No shipments in 2005 1

2. Dry Solid Waste:

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

Dry Active Waste (non-compacted) 2005-07 DAW Nuclide %Abundance Cr-51 6.72 Mn-54 .55 Co-58 20.92 Co-60 2.76 Cs-137 .56 Fe-55 11.51 Ni-63 5.41 H-3 49.22 Zr-95 .83 Nb-95 1.52 Dry Active Waste (brokered/compacted) No shipments in 2005 Dry Active Waste (brokered/non-compacted) 2005-01 DAW Nuclide %Abundance Cr-51 7.28 Mn-54 0.55 Co-58 21.35 Co-60 2.71 Cs-137 0.55 Fe-55 11.31 Ni-63 5.28 H-3 48.51 Zr-95 0.84 Nb-95 1.61 2005-02 DAW Nuclide %Abundance Cr-51 6.83 Mn-54 0.55 Co-58 20.96 Co-60 2.74 Cs-137 0.55 Fe-55 11.44 Ni-63 5.36 H-3 49.20 Zr-95 0.83 Nb-95 1.54 2

2005-08 DAW Nuclide %Abundance Cr-51 9.28 Mn-54 0.53 H-3 45.90 Co-58 22.59 Co-60 2.57 Cs-1 37 .52 Ni-63 4.99 Fe-55 10.78 Zr-95 .91 Nb-95 1.93 2005-10 DAW Nuclide %Abundance Cr-S1 7.96 Mn-54 0.54 Co-58 21.80 Co-60 2.66 Cs-137 0.54 Fe-55 11.12 Ni-63 5.17 H-3 47.62 Zr-95 0.87 Nb-95 1.72 2005-16 DAW Nuclide %Abundance Cr-51 8.48 Mn-54 0.54 Co-58 22.16 Co-60 2.62 Cs-137 0.53 Fe-55 10.98 Ni-63 5.10 H-3 46.89 Zr-95 0.88 Nb-95 1.81 2005-19 DAW Nuclide %Abundance Cr-51 6.30 Mn-54 0.56 Co-58 20.51 Co-60 2.79 Cs-137 0.57 Fe-55 11.63 Ni-63 5.46 H-3 49.93 Zr-95 0.80 Nb-95 1.45 3

2005-22 DAW Nuclide %Abundance Cr-51 3.82 Mn-54 0.57 Co-58 17.61 Co-60 3.01 Cs-1 37 0.62 Fe-55 12.43 Ni-63 5.94 H-3 54.34 Zr-95 0.67 Nb-95 .99 2005-27 DAW Nuclide %Abundance Cr-51 7.04 Mn-54 0.55 Co-58 21.16 Co-60 2.73 Cs-137 0.55 Fe-55 11.42 Ni-63 5.32 H-3 48.82 Zr-95 0.83 Nb-95 1.57 2005-30 DAW Nuclide %Abundance Cr-51 3.85 Mn-54 0.57 Co-58 17.64 Co-60 3.01 Cs-137 0.62 Fe-55 12.44 Ni-63 5.94 H-3 54.25 Zr-95 0.68 Nb-95 .99 B. Sealed Sources No shipments in 2005 C. Sealed Sources/Smoke Detectors No shipments in 2005 D. Irradiated Components No shipments in 2005 4

Attachment 3 Unplanned Offsite Releases

McGUIRE NUCLEAR STATION UNPLANNED RELEASES (January 1, 2005 through December 31, 2005)

There were no unplanned gaseous or unplanned liquid radioactive effluent releases to the environment in 2005.

Attachment 4 Fuel Cycle Calculation

McGuire Nuclear Station 2005 Radioactive Effluent Releases 40CFRl90 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. 2005 McGuire 40CFRl90 Effluent Dose Summary The 40CFRI90 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 = 1.15E+00 mrem Maximum Location: 0.5 Mile, East Sector Critical Age: Child Gas non-NG Contribution: 84%

Gas NG Contribution: 1%

Liquid Contribution: 15%

Maximum Organ (other than TB) Dose - 1.15E+00 mrem Maximum Location: 0.5 Mile, East Sector Critical Age: Child Critical Organ: Liver Gas Contribution: 84%

Liquid Contribution: 16%

II. 2005 McGuire 40CFRl90 ISFSI Dose Sunimary Direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at McGuire have been calculated and documented in the "McGuire Nuclear Site IOCFR72.212 Written Evaluations" report. The maximum dose rate to the nearest resident from the McGuire ISFSI is conservatively calculated to be 5.32 mrem/year.

The attached excerpt from the "McGuire Nuclear Site IOCFR72.212 Written Evaluations" report is provided to document the method used to calculate the McGuire ISFSI 5.32 mrem/year dose estimate.

C. IOCFR72.212(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 1 '03 2Q '03 3Q '03 4Q '03 1 '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

  1. of Days 91 92 91 92 98 83 98 Location # 76 indicates the greatest dose of 0.058 rems 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 mrem per hour. A normalization value is derived by dividing the actual dose by the calculated dose, which is 0.0247/0.744

= 0.0332.

ISFSI Controlled Area Boundary (ISFSI and Site Operations)

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

The combined and skyshine dose rates at various distances for one cask stored with 7 year cooled fuel (inner) and 10 year cooled fuel (outer) were analyzed by 3For McGuire, compliance with this regulation will also assure compliance with 40 CFR Part 190.

McGuire Nuclear Site (NAC UMS) 10CFR72.212 Written Evaluations, Rev. 0

Transnuclear. 4 The best-fit empirical equation for skyshine dose rate as a function of distance is y = 0.0156e-°00 12x for gammas and y = 0.0274e OI129 x 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-2.1688 for gammas and y =

166.95x-2°61 for neutrons, where y is dose rate (mremlhr) 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 IOCFR72.104 (cited above). For a conservative estimate, the individual is assumed to have a 100%

occupancy time (8750 hours0.101 days <br />2.431 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 5.3 mrem and the dose due to McGuire power generation is 3 mrem per year for a total dose of 8.3 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) 40CFRl90 applies to radiation doses received by members of the public in the general environment and to radioactive materials introduced to the general 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.

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

McGuire Nuclear Site (NAC UMS) 10CFR72.212 Written Evaluations, Rev. 0

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 40CFR190.1O(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 IOCFR 72.104(a), the calculated dose at the EAB is 8.3 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 the annual dose must be below 100 mrem within the controlled area. 6 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 <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 0.153 mrem per hour (direct radiation and skyshine), within the 6 IOCFR20.1301(b). See also 10CFR20.1301(a)(2).

McGuire Nuclear Site (NAC UMS)

IOCFR72.212 Written Evaluations, Rev. 0

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 3.1 mrem (skyshine only -

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

These calculations show that the McGuire ISFSI 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 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 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 E42 mrem/hr.

(10) Casks X 7.443 E42 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 McGuire Nuclear Site (NAC UMS) 10CFR72.212 Written Evaluations, Rev. 0

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 Twelve NAC UMS Casks (calculated) 0.0247 mrem per hr + 0.128 mrem per hr = 0.153 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 E03 mrem/hr.

(10) Casks X 8.24 E43 mrem/hr 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 <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 McGuire Nuclear Site (NAC UMS) 10CFR72.212 Written Evaluations, Rev. 0

Total Expected Dose at Waterway on Other Side of Berm Ten TN-32A Casks (actual) plus Twelve NAC UMS Casks (calculated) 0.410 mrem per year + 2.69 mrem per year = 3.10 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 04 mrem/hr.

(10) Casks X 2.48 E 04 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 = 0.0332 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.

Total Expected Dose at Exclusion Area Boundary Ten TN-32A Casks (actual) plus Twelve NAC UMS Casks (calculated) 0.720 mrem per year + 4.6 mrem per year = 5.32 mrem per year McGuire Nuclear Site (NAC UMS) 10CFR72.212 Written Evaluations, Rev. 0

McGUIRE NUCLEAR STATION 2005 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 (2005) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY A WIND SPEED CLASS I I

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

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- I 1 0.75-1 1.00-1 1.25-1 1.50-1 2.00-1 3.00-1 4.00-1 5.00-1 6.00-1 8.00-1>9.99 1 I l 0.99 l 1.24 l 1.49 l 1.99 ) 2.99 l 3.99 l 4.99 l 5.99 l 7.99 I 9.99 l M/S lTOTAL I I ------- +------+------+------+------+-_ ----+- -----

+-_ +- ---- +------+-----+------

I NO. I NO. I NO. I NO. j NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I lSECTOR I I I I I I I I I I I I I I-- - - - - - - -- - - - - - - -I I I I I I I I I I I I I l-N- I 1l 21 31 41 11 .1 *l *) 21 ill 9) 331 l-NNE- I .1 *) 21 51 51 21 31 .1 1) 1l .* 19)

I-NE- I *1 .1 1) 41 13) ill 71 10) 61 *l1 . 521 l-ENE- I *l .1 .1 *) 15i ill 31 31 .l1 .1

  • 321 l_EI .1 *1 .l 41 1is 12) 1) 21 *1 .1 .1 341 l_ESE_ ' *1 1 .1
  • i 9) 10i 41 1l 1l .1 *1 261 l-SE- I *l .1 .1 *) 21 41 31 .1 .1 .1 .l 9) l-SSE- I *l .1 .1 .1 *l 21 5) 21 *l1 l1 1 9)

I-S- I 41 .1 .1 .1 31 61 41 31 .1 .1 .1 161 I-SSW- I .1 *1 .1 .1 .1 31 71 51 41 *1 .1 19)

Isw I 1 I1 .1 .1 21 91 101 91 21 *1 1 321 I-nSw- I *1 .1 .1 .1 .1 151 1is 51 31 *1 41 381 I-w- I *1 .1 *1 .1 21 21 11 *1 11 .1 *1 61 l-WNW- I *l *l

  • 1l 21 1l *l *l 51 41 1l 141 l-Nw- I * *l *l 1) 21 *1 *l *1 21 *1 *1 51 TT-NNW- I *l 2) *l 20 71 18 63 40 12 41 10 61 lTOTAL I 1l 21 61 201 711 891 631 401 281 201 10l 3501

McGuire NUCLEAR MTN.METEOROLOGY (2005) 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 0.75-1 1.00-f 1.25-f 1.50-f 2.00-1 3.00-1 4.00-1 5.00-f 6.00-f 8.00-1>9.99 1 l 0.99 f 1.24 f 1.49 1 1.99 l 2.99 f 3.99 l 4.99 I 5.99 1 7.99 l 9.99 l M/S lTOTAL I I---- +-- +-+-+-+-+--+-+-+-

I NO. I NO. I NO. I NO. I NO. I NO. I NO. f NO. I NO. I NO. I NO. I NO. I lSECTOR I I I I I I I I I I I I I f I f I fI I f f f f I I I f-N- I 1I 21 31 16s 18s 31 21 41 71 91 .f 651 f-NNE- I .f 41 61 15s 16f i1 17f 10o 13f 41 .f 961 f-NE- f .f .f .f 13f 21i 291 28 371 10o *f .f 138 f-ENE- I .1 .f .f 51 231 81 61 51 .f .f .f 471 f-E- I .f .1 .f 81 91 18 41 .1 .f .f .1 391 f-ESE- I .1 lf .f 41 191 71 31 .f .f .f l f 331 f-SE- I .f .f .f 41 151 91 21 1I .1 .f .f 311 f-SSE- f .f .f lf .f 91 61 1I .f .f *f .f 16f f-S- I .f .f .f 11 61 41 1I .f .f .f .1 121 I *1 11f-SSW-.1 1I 71 161 81 1I .1 .1 .f 341 f-Sw- I .f .f .f 61 11f 251 131 61 31 21 l1 661 f-WSW- I .1 .f lf 71 211 181 ilf 41 91 .1 .f 701 f-W- I .f . 31 31 51 41 41 1I .f .f lf 201 l-WNW- I 1I .1 21 51 71 31 1I 21 51 51 21 331 f-NW- I 1I 21 21 31 51 21 31 11 1I 21 21 241 f-NNW- I 1I 11 4f 31 21 31 21 .f 31 71 21 28S lTOTAL f 41 101 20f 941 194f 166s 106s 721 51I 291 61 7521

McGuire NUCLEAR STN. METEOROLOGY (2005) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY C WIND SPEED CLASS I I 1 0.75-1 1.00-1 1.25-1 1.50-1 2.00-1 3.00-1 4.00-1 5.00-1 6.00-1 8.00-1>9.99 I1 l 0.99 l 1.24 f 1.49 l 1.99 f 2.99 f 3.99 l 4.99 l 5.99 I 7-99 I 9-99 l M/S lTOTAL I I- ----- - -- - - - - - -- - - - - -------------

- - - -- - --- ----- I I NO. I NO. f NO. f NO. f NO. I NO. I NO. f NO. I NO. I NO. I NO. I NO. I I---+ ++-+-+-+-+-+-+-+-+-------- --- I fSECTOR I I I I I I I I I I I I I I-------------------------------I I I I I I I I I I I I I f-N- I 1I 21 101 19f 391 19f 131 91 13f .1 .1 125s l-NNE- I 1 31 .*1 201 3SI 481 231 22f 1sf 1i .1 168f f-NE- I l1 1I 31 12f 271 491 68f 371 41 .1 .f 2011 f-ENE- I *f 21 *f 141 28f 26f 17f 51 .1 .f .f 921 f-E- I *1 .1 .1 41 22f 10o 51 1i .1 .1 .1 421 f-ESE- I *f .f 21 41 9f 18s 21 .f .f .f .f 351 f-SE- I .f *l1

  • 31 26f 41 *1 .1 .f .1 .1 331 l-SSE- I l 1 1f 51 71 1f *1 *fl 1f .1 .f 16f f-S- I .1 .1 11 41 ilf 1f1 11 41 .1 .1 .1 281 I-SSW- I .* .f .1 21 131 171 91 21 21 .1 .1 451 f-SW- f .1 .1 21 31 291 291 161 71 21 11 .1 891 f-WSW- I 1f *1 21 71 161 131 el 71 81 11 .1 631 f-W- I .1 11 21 81 81 51 81 11 41 61 11 441 l-WNW- f .f 1I 1I 31 91 81 41 el 14f 12f *1 601 f-NW- I *f 21 21 41 31 71 71 71 9f 9f 71 571 I-NNW- I lf 51 41 9f 10o 61 31 9f 10o 9f 1i 66f lTOTAL l 31 18s 301 121f 292f 2711 184f 115s 82f 391 9f 1164f

McGuire NUCLEAR STN. METEOROLOGY (2005) PROG-XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY D WIND SPEED CLASS I I I 0.45-1 0.75-f 1.00-f 1.25-f 1.50-f 2.00-f 3.00-f 4.00-f 5.00-f 6.00-f 8.00-1>9.99 I I l 0.74 f 0.99 f 1.24 l 1.49 l 1.99 l 2.99 l 3.99 l 4.99 I 5.99 I 7.99 l 9.99 l M/S lTOTAL l l NO. I NO. f NO. fNO. I NO. f NO. f NO. f NO. f NO. f NO. I NO. I NO. f NO. l lSECTOR I I I I I I I I I I I I I I I-------------------------------1I f-N- I 1I 1I 51 141 28 611 541 331 15f 15f 41 1i 2321 l-NNE- I *1 21 81 81 301 831 1121 701 371 251 SI 1i 3811 f-NE- I *f 21 31 51 301 195f 280f 219f 931 271 *1 .1 8541 l-ENE- I 1I 21 51 21 26S 1371 167f 711 71 .1 .1 .1 418f f-E- I *1 11 31 31 241 801 991 28s 71 *1 .1 .1 2451 l-ESE- I .l 31 51 61 19f 781 451 51 1i 1i *1 .1 1631 l-SE- I *1 21 21 71 261 108o 28s 31 3f *l1 .1

  • 1791 l-SSE- I lf .1 31 9f 271 331 31 1i .f *1 .1 l
  • 761 1_s_ I 4 *1 31 61 231 601 441 151 71 1i *1 .1 1591 I-SSW- I *1 21 41 51 14f eel 611 30f 101 21 .1 .1 2161 f-SW- I .1 21 41 51 201 1161 1381 1031 211 131 1i *1 4231 f-WSW- I .1 41 71 161 361 491 471 371 141 201 11 .1 2311

-W- I *1 51 91 91 301 361 311 261 131 31 31 .1 1651 I 1If-WNW- 51 31 71 201 341 28s 26f 121 231 51 31 1671 f-NW- f .f 21 21 11l 12f 16i 28 431 321 21f 16s 31 186s f-NNW- f .f .f 31 51 17f 231 231 19f 17f 18s 10o 31 138S l-CALM- l 51 .1 *f .1 .f .1 .1 .f *l *1 .1

  • f 51 lTOTAL I ef 331 69f 118s 382f 1197f 1188s 729f 2891 169f 45 11l 4238

M, McGuire NUCLEAR STN. METEOROLOGY (2005) PROG-XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY E WIND SPEED CLASS I I 1 0.45-f 0.75-f 1.00-f 1.25-f 1.50-f 2.00-f 3.00-f 4.00-f 5.00-f 6.00-f 8.00-f 1 l 0.74 f 0.99 1 1.24 l 1.49 1 1.99 f 2.99 l 3.99 l 4.99 l 5.99 1 7.99 l 9.99 lTOTAL I I NO. I NO. I NO. I NO. I NO. f NO. I NO. f NO. I NO. f NO. f NO. I NO. I lSECTOR I I I I I I I I I I I I I f-N- I 1I 1I l 31 51 81 41 1I 1I 61 l1 301 l-NNE- I .1 41 1I 1I 161 201 1I 1I 1I 1I *1 461 l-NE- I .1 .1 I11 11i 81 21 41 *l1 .* l 271 l-ENE- I *f 21 1I 51 81 5f 1I 31 11 *l *f 26f l-E- I 1I 1I 51 41 51 61 21 *1 .1 .f .f 241 l-ESE- I . *f 31 SI 10i 211 41 *l .* *l *l 431 f-SE- f .f 31 61 71 12f 421 81 1I .f lf .1 791 I i-SSE-11 31 ill 12f 321 251 21 31 f1 .f .f 891 l-S- I 1I 61 71 13f 281 491 41 1I 1I 1I .1 1i1f l-SSW- f 21 91 121 161 481 1061 161 41 1I .1 .1 2141 f-SW- I 11 31 121 161 341 1021 611 121 .1 11 *1 2421

-iWSW- I .1 61 1io 31I 501 Sof 17f 31 11 .1 1I 1691 f-W- I 11 51 51 161 17f 221 13f 31 .1 .1 .1 821 f-WNW- f 1I 21 91 91 151 1Sf iof sf 1I .f .f 6sf f-NW- fI 1i I 21 41 81 16f 91 61 11 1I .f 491 f-NNW- I .1 1I 1I 1I 41 10f 91 21 .f .f .f 28f l-CALM- l 1 l

  • l
  • l l
  • l
  • l 1

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

lTOTAL I ill 471 861 1441 3031 5031 1631 491 81 10l 1I 13251

MCGuire NUCLEAR STN. METEOROLOGY (2005) PROG.XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY F WIND SPEED CLASS I I 1 0.45-1 0.75-I 1.00-I 1.25-I 1.50-f 2.00-f 3.00-1 4.00-1 I l 0.74 l 0.99 l 1.24 l 1.49 l 1.99 l 2.99 l 3.99 I 4.99 lTOTAL I I---+- +- +- +- +-+-+-+-

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

ISECTOR I I I I I I I I I I II- -I-- - --I-- -I-- --- ---I--I I I-N- I 1I *l 1I I l l l 41 I-NNE- l 21 21 41 .1l

  • 21 *1 *I 101 l-NE- I 1I 1I *l *l *l *l *l - *l 21 l-ENE- I -1 11 .1 *l *l l1 *l l 1I I-E- I .1 11 .1 .1 *1 *f *1 li 21 l-ESE- I .1 .1 21 .1 21 .1 .1 *1 41 I-SE- I *1 31 *1 .1l1 .1 1i *1 51 I-SSE- I 21 31 41 1l 81 21 .1 .f 201 I-S- I 21 81 61 101 321 161 .1 .1 741 f-SSW- f 21 61 151 271 481 251 21 *1 1251 I-SW- I 31 101 ill 161 211 331 31 .1 971 l-WSW- I 71 91 91 191 221 191 81 .1 931 f-W- I 31 i1 51 31 81 31 1i *1 241 I-WNW- I 1I 21 31 51 21 61 51 *1 241 I-NW- I 11 *I 1f *1 11 1I *I .1 41 l-NNW- I *1 l1 l1 21 1I *1 .1 11 41 f-CALM- I 11 .1 *1 .1 .1 *1 *1 *1 1I lTOTAL I 261 481 601 841 1471 1081 201 1l 4941

t)

McGuire NUCLEAR STN. METEOROLOGY (2005) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY G WIND SPEED CLASS I I 1 0.45-1 0.75-1 1.00-f 1.25-f 1.50-f 2.00-f 3.00-f 1 l 0.74 l 0.99 f 1.24 l 1.49 l 1.99 l 2.99 l 3.99 lTOTAL I

-+-+-+-+-+-+- +- I I NO. f NO. I NO. I NO. I NO. I NO. f NO. f NO. I SECTOR I I I I I I I I I I-- - - - - - -- - - - - - - -I I I I I I I II f-N- I 21 31 *l 1I 11 lf .1 71 l-NNE- l 21 1I 31 11 1I 1I l 91 f-NE- l 21 *1 i1 1I *1 .1 *1 41 l-ENE- I if .1 .1 .1l 1l 1 .1 1f l + - + - + - + - + - + - + - + - l f-E- I 1 1 *1l f .f .* .f 21 l-ESE- I 1I *1 *l *1 .1 .1 .1 11 f-SE- I *f 1I .f *1 *1 .1 .1 1I l + - + - + - + - + - + - + - + - l f-SSE- l 21 61 *1 11 *1 1I .f 101 l-S- I 61 31 31 51 41 61 *1 271 l + - + - + - + - + - + - + - + - I I-SSW- I 91 211 291 231 181 61 .1 1061 f-SW- I 41 251 121 141 71 41 21 681 f-WSW- I 41 131 10o 91 ef 71 1I 521 l + - + - + - + - + - + - + - + - l l-W- I 21 1I 1I 31 1I 21 1 1of

-WNW- 1 1 .1 1 .1 .1 .1 21 f-NW- f 11 11 l1 lf .f .f *f 21

-NNW- I 1I 1I *l .* .1 .1 .1 21 l-CALM- l 41 .1 .1 .1 *f .1 .1 41 UTOTAL l 431 781 591 581 401 271 31 308f

C, McGuire NUCLEAR STN. METEOROLOGY (2005) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS ALL STABILITY CLASSES WIND SPEED CLASS I I 1 0.45-f 0.75-f 1.00-1 1.25-f 1.50-f 2.00-1 3.00-f 4.00-f 5.00-f 6.00-f 8.00-1>9.99 I 1 1 0.74 1 0.99 1 1.24 1 1.49 1 1.99 1 2.99 1 3.99 1 4.99 1 5.99 1 7.99 1 9.99 1 M/S lTOTAL I I NO. f NO. I NO. I NO. I NO. I NO. I NO. I NO. f NO. fNO. I NO. f NO. I NO. I lSECTOR I I I I I I I I I I I I I I

- - - -I I I I I I I I I I I I I l-N- l 51 91 ilf 351 741 1271 801 491 291 431 241 101 4961 l-NNE- I 41 10i 231 1S1 871 1621 1741 1141 701 S51 ill 1I 7291 f-NE- I 31 31 61 ilf 701 2641 3711 326f 1771 471 *1 .1 1278f l-ENE- l 21 51 81 71 531 2081 2131 1001 21f *1 *l *1 6171 l-E- l 21 41 eI 71 461 1321 141f 381 101 *1 *1 *1 3881 l-ESE- I 11 31 101 131 401 1361 841 14f 21 21 l1 l1 3051 f-SE- I .1 91 ef 141 451 194f 541 91 41 .f .1 .1 3371 f-SSE- l 51 12f 19f 241 721 771 141 10f 21 1I *1 .1 2361 I-S- I 91 17f 191 351 921 1511 691 221 ill 21 *1 .1 4271 l-SSW- I 131 381 611 71I 1311 2451 1151 581 19f 81 *1 .1 7591 f-SW- I 81 401 391 531 91f 2971 2671 154f 431 211 41 *1 1017f f-WSW- I ill 331 361 771 1301 1621 1191 741 31I 401 31 *1 7161 f-W- 1 61 121 211 361 671 781 561 421 151 81 91 11 3511 l-WNW- l 41 ill 16f 241 461 71I 5sf 361 231 471 26f 61 36Sf f-NW- f 31 51 91 19f 291 431 461 591 411 341 271 12f 3271 f-NNW- I 1I 31 10o 161 341 451 421 271 26f 321 301 61 272f f-CALM- I ilf .1 .1 .1 .1 .1 *f *l *l *1 *1 *l1 i lTOTAL I 88s 214f 3041 4601 1107f 2392f 1900o 1132f 5241 3401 134f 361 8631i

Attachment 5 Inoperable Monitoring Equipment

McGuire Nuclear Station Inoperable Monitoring Equipment (January 1, 2005 through December 31, 2005)

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

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