ML051250109

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Annual Radioactive Effluent Release Data, 01/01/2004 Through 12/31/2004
ML051250109
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 12/31/2004
From:
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML051250109 (53)
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Text

McGUIRE NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 2004 through December 31, 2004)

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

TABLE IA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2004 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Gases

1. Total Release Ci 9.06E+00 5.71E-01 7.17E-01 7.05E-01 l.llE+01
2. Avg. Release Rate pCi/sec 1.15E+00 7.27E-02 9.02E-02 8.87E-02 3.50E-01 B. Iodine-131
1. Total Release Ci 1.62E-04 3.40E-06 0.OOE+00 0.OOE+00 1.66E-04
2. Avg. Release Rate pCi/sec 2.07E-05 4.32E-07 0.00E+00 0.OOE+00 5.24E-06 C. Particulates Half Life >- 8 days
1. Total Release Ci 4.47E-05 8.51E-06 0.OOE+00 1.37E-06 5.46E-05
2. Avg. Release Rate pCi/sec 5.69E-06 1.08E-06 0.00E+00 1.73E-07 1.73E-06 D. Tritium
1. Total Release Ci 5.63E+01 4.98E+01 4.15E+01 4.65E+01 1.94E+02
2. Avg. Release Rate pCi/sec 7.15E+00 6.33E+00 5.23E+00 5.85E+00 6.14E+00

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2004 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases
    • No Nuclide Activities ........ ........ ........ ........ ........
2. lodines
    • No Nuclide Activities **........ ........ ........ ........ ........
3. Particulates Half Life >= 8 days
    • No Nuclide Activities **........ ........ ........ ........ ........
4. Tritium
    • No Nuclide Activities **........ ........ ........ ........ ........

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2004 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

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

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2004 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases
    • No Nuclide Activities **
2. lodines 1-131 Ci 1.62E-04 3.40E-06 0.00E+00 0.00E+00 1.66E-04 I-133 Ci 7.28E-05 0.00E+00 0.00E+00 0.00E+00 7.28E-05 Totals for Period... Ci 2.35E-04 3.40B-06 0.003+00 0.00E+00 2.39E-04
3. Particulates Half Life >. 8 days CO-58 Ci 4.47E-05 8.51E-06 0.OOE+00 1.37E-06 5.46E-05 Totals for Period... Ci 4.47E-05 8.51E-06 0.00E+00 1.37E-06 5.46E-05
4. Tritium H-3 Ci 5.37E+01 4.97E+01 4.14E+01 4.62E+01 1.91E+02

___ _____ 4.______

Totals for Period... Ci 5.37E+01 4.97E+01 4.14E+01 4.62E+01 1.91E+02

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2004 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases AR-41 Ci 6.98E-01 5. 09E-01 6.32E-01 6.12E-01 2.45E+00 RR-85 Ci 4.04E-02 0.00E+00 O.OOE+00 3.10E-02 7.14E-02 KR-85M Ci 1.35E-03 0.00E+00 O.OOE+00 O.OOE+00 1.35E-03 KR-88 Ci 4.46E-05 0.00E+00 O.OOE+00 O.OOE+00 4.46E-05 XE-131M Ci 2.70E-02 0.00E+00 O.OOE+00 O.OOE+00 2.70E-02 XE-133 Ci 8.26E+00 5.9 9E-02 8.06E-02 6.14E-02 8.46E+00 XE-133M Ci 1.50E-02 0.OOE+00 O.OOE+00 O.OOE+00 1.50E-02 XE-135 Ci 1.87E-02 2.0 9E-03 3.86E-03 6.06E-04 2.53E-02 Totals for Period... Ci 9.06E+00 5.71E-01. 7.17E-01 7.05E-Ol 1.11E+01
2. lodines 1-131 Ci 9.14E-08 4.52E-10 O.OOE+00 O.OOE+00 9.19E-08 Totals for Period... Ci 9.14E-08 4.52E-10 O.OOE+00 O.OOE+00 9.19E-08
3. Particulates Half Life >= 8 days
    • No Nuclide Activities **
4. Tritium H-3 Ci 2.58E+00 1.13E-01 l.SlE-0l 2.35E-Ol 3.08E+00 Totals for Period... Ci 2.58E+00 1.13E-01 1.51E-01 2.35E-Ol 3.08E+00

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2004 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 3.77E-02 2.74E-02 1.42E-02 1.65E-02 9.58E-02
2. Average Diluted Concentration
a. Continuous Releases pCi/ml 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
b. Batch Releases yCi/ml 4.94E-11 2.86E-11 1.36E-21 1.71E-11 2.57E-11 B. Tritium
1. Total Release Ci 1.88E+02 2.18E+02 2.07E+02 3.94E+02 1.01E+03
2. Average Diluted Concentration
a. Continuous Releases pCi/ml 1.84E-08 6.08E-09 4.74E-09 4.43E-09 7.81E-09
b. Batch Releases yCi/ml 2.44E-07 2.28E-07 1.98E-07 4.10E-07 2.70E-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 O.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 D. Gross Alpha Radioactivity
1. Total Release Ci O.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 5.32E+07 5.46E+07 5.36E+07 5.30E+07 2.14E+08
2. Batch Releases liters 1.05E+06 8.67E+05 7.40E+05 6.98E+05 3.35E+06 F. Volume of Dilution Water
1. Continuous Releases liters 7.63E+10 9.S7E+l0 l.04E+ll 9.60E+10 3.72E+11
2. Batch Releases liters 7.63E+ll 9.57E+11 1.04E+12 9.60E+ll 3.72E+12

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 LIQUID EFFLUENTS - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2004 Unit QTR I QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products
    • No Nuclide Activities **
2. Tritium H-3 Ci 1.40E+00 5.82E-01 4.94E-01 4.25E-01 2.91E+00 Totals for Period... Ci 1.40E+00 5.82E-01 4.94E-01 4.25E-01 2.91E+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 1/1/04 TO 1/1/05 LIQUID EFFLUENTS - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2004 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products AG-108M Ci 0.OOE+00 1.53E-05 7.79E-05 1.20E-04 2.13E-04 AG-llOM Ci 1.22E-04 4.51E-04 4.35E-04 5.92E-04 1.60E-03 BE-7 Ci 0.OOE+00 O.OOE+00 1.93E-04 8.46E-04 1.04E-03 BR-82 Ci 0.OOE+00 1.57E-06 7.22E-06 O.OOE+00 8.79E-06 CO-57 Ci 1.69E-04 7.57E-05 1.14E-04 4.46E-05 4.03E-04 CO-58 Ci 3.04E-02 1.66E-02 6.88E-03 5.70E-03 5.96E-02 CO-60 Ci 3.89E-03 4.18E-03 5.06E-03 6.34E-03 1.95E-02 CR-51 Ci 8.75E-04 2.03E-03 O.OOE+00 9.40E-04 3.84E-03 CS-134 Ci 0.OOE+00 4.33E-05 O.OOE+00 6.2OE-05 1.05E-04 CS-137 ci 8.74E-05 1.21E-04 8.57E-06 1.03E-04 3.19E-04 FE-s9 ci 4.2 8E-05 2.38E-04 O.OOE+00 1.OOE-04 3.81E-04 1-131 ci 8.87E-07 8.94E-07 O.OOE+00 O.OOE+00 1.78E-06 MN-54 ci 6.60E-04 5.13E-04 4.29E-04 6.45E-04 2.25E-03 NB-95 Ci 2.7 6E-04 1.86E-04 8.42E-06 1.32E-04 6.02E-04 NB-97 ci 4.10E-05 1.76E-05 1. 61E-05 2.89E-05 1.04E-04 SB-122 Ci 0.OOE+00 O.OOE+00 O.OOE+00 2.71E-06 2.71E-06 SB-124 Ci 0. OOE+O0 1.80E-05 O.OOE+00 2.09E-05 3.89E-05 SB-125 Ci 1.OlE-03 2.83E-03 9.29E-04 7.59E-04 5.52E-03 SN-113 Ci 7.48E-06 O.OOE+00 O.OOE+00 O.OOE+00 7.48E-06 SR-92 Ci 1.50E-06 5.46E-06 2.93E-06 2.46E-06 1.23E-05 ZR-95 Ci 1.27E-04 1.24E-04 O.OOE+00 2.85E-05 2.80E-04 Totals for Period... Ci 3.77E-02 2.74E-02 1.42E-02 1.65E-02 9.58E-02
2. Tritium H-3 Ci 1.86E+02 2.18E+02 2.06E+02 3.94E+02 1.OOE+03 Totals for Period... Ci 1.86E+02 2.18E+02 2.06E+02 3.94E+02 1.OOE+03
3. Dissolved and Entrained Gases
    • No Nuclide Activities **
4. Gross Alpha Radioactivity
    • No Nuclide Activities **

McGUIRE NUCLEAR STATION SUPPLEMENTAL INFORMATION

McGUIRE NUCLEAR STATION 2004 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. 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 INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL V. BATCH RELEASES A. LIQUID EFFLUENT
1. 1.88E+02
  • TOTAL NUMBER OF BATCH RELEASES
2. 3.17E+04
  • TOTAL TIME (MIN.) FOR BATCH RELEASES.
3. 1.96E+04
  • MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
4. 1.68E+02
  • AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
5. 1.00E+00 - MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
6. 1.86E+06
  • AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B. GASEOUS EFFLUENT

1. 5.20E+01 - TOTAL NUMBER OF BATCH RELEASES.
2. 1.05E+06 - TOTAL TIME (MIN.) FOR BATCH RELEASES.
3. 4.47E+04 - MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
4. 2.01E+04 - AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
5. 1.60E+01 - MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

VI. ABNORMAL RELEASES A. LIQUID

1. NUMBER OF RELEASES - 0
2. TOTAL ACTIVITY RELEASED (CURIES) - 0 B. GASEOUS
1. NUMBER OF RELEASES - 2
2. TOTAL ACTIVITY RELEASED (CURIES) . 7.1E-02 (See attachments 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 = d 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, 2004 through December 31, 2004)

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 1/1/04 TO 1/1/05 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 I Quarter 2004

--- IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS-.....- Quarter 1 2004 .*..

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD THYROID 1.68E-01 1.50E+01 1.12E+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 9.46E+01 1-131 5.25E+00

  • -- NOBLE GAS DOSE LIMIT ANALYSIS..-....-----.------------ Quarter 1 2004 ----

Dose Limit  % of Period-Limit (mrad) (mrad) Limit Ql - Maximum Gamma Air Dose 2.28E-02 1.00E+01 2.28E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 6.86E+01 XE-133 3.08E+01 Ql - Maximum Beta Air Dose 2.69E-02 2.00E+01 1.34E-01 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 7.78E+01 AR-41 2.05E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2004

... IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS-=--.-. Quarter 2 2004 ---.

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD THYROID 1.41E-01 1.50E+01 9.42E-01 Maximum Organ Dose Receptor Location: 0.5 Mile E Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.99E+01

--. NOBLE GAS DOSE LIMIT ANALYSIS-.......-................ Quarter 2 2004 *---

Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose l l5E-02 1.00E+01 1.15E-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 4.20E-03 2.00E+01 2.10E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.61E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2004

.*- IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS------- Quarter 3 2004 ----

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 1.18E-01 1.50E+01 7.85E-01 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 GAS DOSE LIMIT ANALYSIS ....-- ..-------------.- Quarter 3 2004 ---

Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q3 - Maximum Gamma Air Dose 1.43E-02 1.00E+01 1.43E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.94E+01 Q3 - Maximum Beta Air Dose 5.23E-03 2.OOE+01 2.62E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage A.R-41 9.57E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4 th Quarter 2004

  • -- IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS-.-.-.. Quarter 4 2004 -.-.

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) Cmrem) Limit Q4 - Maximum Organ Dose CHILD LUNG 1.32E-01 1.50E+01 8.78E-01 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 GAS DOSE LIMIT ANALYSIS---...................... Quarter 4 2004 ....

Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Gamma Air Dose 1.38E-02 1.00E+01 1.38E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.96E+01 Q4 - Maximum Beta Air Dose 5.15E-03 2.OOE+01 2.57E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage

_-________ 9_________

AR-41 9.41E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2004

  • -- IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS------- Annual 2004 .-.--.-.

Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD THYROID 5.59E-01 3.OOE+01 1.86E+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 9.83E+01

... NOBLE GAS DOSE LIMIT ANALYSIS-......................-- Annual 2004 *-......

Dose Limit  % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Gamma Air Dose 6.24E-02 2.OOE+01 3.12E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 8.82E+01 XE-133 1.16E+01 Yr - Maximum Beta Air Dose 4.15E-02 4.OOE+01 1.04E-01 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage XE-133 5.17E+01 AR-41 4.68E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 1st Quarter 2004

... BATCH LIQUID RELEASES -- Quarter 1 2004 -----

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Ql - Maximum Organ Dose CHILD GI-LLI 2.72E-02 1.00E+01 2.72E-01 Ql - Total Body Dose CHILD 2.59E-02 3.00E+00 8.63E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.35E+01 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 2004 ....

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD LIVER 1.92E-03 1.00E+01 1.92E-02 Q1 - Total Body Dose CHILD 1.92E-03 3.00E+00 6.40E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2 ,d Quarter 2004

  • -- BATCH LIQUID RELEASES ........................... =..=.. Quarter 2 2004 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD GI-LLI 2.47E-02 1.OOE+01 2.47E-01 Q2 - Total Body Dose CHILD 2.41E-02 3.OOE+00 8.03E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.60E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.86E+01

  • -- CONTINUOUS LIQUID RELEASES (WC) *---..--..------------ Quarter 2 2004 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 6.34E-04 1.00E+01 6.34E-03 02 - Total Body Dose CHILD 6.34E-04 3.OOE+00 2.11E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2004

... BATCH LIQUID RELEASES - ............ Criticalas===== . Quarter 3 2004 sas-..

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

____________________________ CHILD--

Q3 - Maximum Organ Dose CHILD GI-LLI 2.12E-02 1.OOE+01 2.12E-01 Q3 - Total Body Dose CHILD 2.llE-02 3.OOE+00 7.03E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.86E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.92E+01 a-s CONTINUOUS LIQUID RELEASES (WC) ....... a.a............ Quarter 3 2004 ----

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 5.OOE-04 1.00E+01 5.00E-03 Q3 - Total Body Dose CHILD 5.00E-04 3.OOE+00 1.67E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.OOE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4th Quarter 2004

  • -- BATCH LIQUID RELEASES tea .............................. Quarter 4 2004 *-....

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 4.42E-02 1.00E+01 4.42E-01 Q4 - Total Body Dose CHILD 4.36E-02 3.OOE+00 1.45E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.78E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-__3__ __________

H-3 9.92E+01

.-. CONTINUOUS LIQUID RELEASES (WC) *------------------- Quarter 4 2004 ......

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 4.67E-04 1.OOE+01 4.67E-03 Q4 - Total Body Dose CHILD 4.67E-04 3.00E+00 1.56E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.00E+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/04 TO 1/1/05 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2004

.== BATCH LIQUID RELEASES .................... ===. ===-- Annual 2004 .........

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD GI-LLI 1.17E-01 2.00E+01 5.84E-01 Yr - Total Body Dose CHILD 1.14E-01 6.OOE+00 l.91E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.69E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.89E+01

  • == CONTINUOUS LIQUID RELEASES (WC) ----------- =--=------- Annual 2004 .........

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 3.28E-03 2.OOE+01 1.64E-02 Yr - Total Body Dose CHILD 3.28E-03 6.00E+00 5.46E-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

McGUIRE NUCLEAR STATION 2004 METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS OF WIND SPEED, WIND DIRECTION, AND ATMOSPHERIC STABILITY USING WINDS AT THE 10 METER LEVEL (Hours of Occurrence)

Mccuire NUCLEAR STN. METEOROLOGY (2004) PROG=XOQFREQ 09:50 Monday, March 14, 2005 1OM 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--

1 1.25-1 1.50-1 2.00-1 3.00-1 4.00-1 5.00-1 8.00-1>9.99 1 I l 1.49 l 1.99 l 2.99 l 3.99 I 4.99 I 5.99 I 9.99 l M/S lTOTAL I I------- +------+------+_____-_-+___-+--- _-+__-- - -+------+------ I I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I I------------------------------+- _ _ ___-_

___+_

+___ __-+___ ___+___ ___+-___-+___ -+_ -__-+__ 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-NE- I .1 .I *1 *l 1 *1 *l 21 l-ENE- *l .I .1 31 *I 21 *I 1 51 l_E_ I .l .l .l 1l .l .l .l .l 1l l_SE_ I .l .l 1l .l. .l .l .l .l 1l l-SSE- I .I 1l .I .1 .1 .1 .l .* 1l I-s- I *1 11 *1 .1 .1 1 1 *1 11 I-wsw- I 11 *1 11 *1 *1 *1 *1 *1 21 l_NW_ I .l .l .l .l 1l .l .l .l 1l I-NNW- I *I *I .* .* *l *l 41 21 61 ITOTAL I 1l 21 31 41 1I 31 51 21 21I

Mccuire NUCLEAR STN. METEOROLOGY (2004) PROG=XOQFREQ 09:50 Monday, March 14, 2005 2 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY B WIND SPEED CLASSI I1.50-i 2.00-1 3.00-I 4.00-I 5.00-I 6.00-1 8.00-1>9.99 I I 11.99 2.99 I 3.99 I 4~.99 I 5.99 I 7.99 I 9.99 I MIS ITOTAL I I---------------------------- ++ -- - +------I I NO. I NO. I NO. I NO. I NO. j NO. I NO. I NO. I NO. I I---------------------------------------------++ -- - +------I ISECTOR I I I I I I I I I I I-- - - - - - - -- - - - - - - -I I I I I I I I I I I-N- I 1i ij *I .1 *1 31 21 .1 71 I-NNE- I 21 2j ii -I 1i *1 *I *I 410

-ENE- I 21 21 1I 41 21 .1 .1 .1 181 I-EN- I .1 31 9 *1 21 21 .1 .1 318 1-ESEI .1 ii 1 .1 *I 1 21 *1 .1 3 I-ESE- I ij ii 1 .1 .1 1 21 .1 *1 21 I-SSE- I *I 'I 1 .1 .1 .1 1 .1 .1 21 I-SS- I .1 *I 31 *I .1 .1 *I .1 31 I-SSW- I 41 'I 81 31 .1 .1 .1 *1 12[

ISW_ I *I 21 41 sj 61 31 .1 .1 201 I-wSw- I .1 ii *1 ii *1 11 11 *I 4 I-NW- I ii .1 *I .1 1i *1 .1 *1 21 I-NNW- 1 *I .1 .1 .1 *1 101 21 1i 131 ITOTAL I 71 141 261 171 131 211 El 1i 105!

McGuire NUCLEAR STN. METEOROLOGY (2004) PROG=XOQFREQ 09:50 Monday, March 14, 2005 3 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY C WIND SPEED CLASS I I I - - - -- - -- - - - - - -- - - - -- - - -- - - -- - - -- - - - - -- - - - -- - - -- - - -- - - -- - - - - -- - - - I--

I 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 I I l 1.24 I 1.49 l 1.99 l 2.99 I 3.99 l 4.99 I 5.99 l 7.99 l 9.99 l M/S ITOTAL I I--------------------------------------------------------

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

-- ------ ---- ----- I--- I I-N- I 11 1i 1I 31 *1 1l 1i 131 21 21 251 I--------------------------------------------------------------------I I-NNE- I .1 1i 71 ll 41 21 21 51 21 .1 341 I-NE- I .1 1l 31 121 141 101 91 41 .1 .I 531 I-ENE- I .1 .1 21 101 161 101 11 1l .1 .1 401 l_E I *l 21 *I 31 41 1' .1 .1 *1 .1 101 l-ESE- I .1 .1 .I 21 21 21 1l 21 .1 .I 91 I-S- - - -++E+- - - -

I-SE- I .1 .1 .1 .1 1I .1 .1 .1 .1 .1 21 I-S- I .1 .1 11 31 91 11 .1 .1 *1 *1 141 1-SSW- I .1 .1 31 161 191 111 .1 .1 .1 .1 491 I-SW- I *1 .1 31 121 301 221 91 91 21 *1 871 I-WSW- I .1 .1 31 61 121 121 21 1I .1 .1 361 I-W- I 1 1l 21 51 31 21 *1 .1 .1 *1 131 I-WNW- I *1 *1 1i 31 .1 31 31 21 21 1l 151 l_NW_ I .I 31 31 21 l1 31 31 51 21 11 221 I-NNW- I *I 21 .1 41 *l 21 7I 171 31 l1 351 lTOTAL I 1l ill 291 931 1151 821 381 591 131 41 4451

Mcauire NUCLEAR STN. METEOROLOGY (2004) PROG=XOQFREQ 09:50 Monday, March 14, 2005 4 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 1 0.45-f 0.75-1 1.00-f 1.25-f 1.50-f 2.00-f 3.00-1 4.00-f 5.00-f 6.00-f a.00-f>9.99 1 I 10.74 f0.99 f 1.24 f 1.49 f 1.99 f 2.99 f 3.99 1 4.99 I 5.99 I 7.99 1 9.99 1 M/S ITOTAL I I-- - - - - -- - - - - - -- - - - - - -- - - - - - -- - - - - - -- - ---------------------- I I NO. I NO. I NO. f NO. f NO. I NO. I NO. f NO. f NO. I NO. f NO. f NO. I NO. I I--------------------------------------------------------------------++ - +- -- I ISECTOR I I I I I I I I I I I I I I I-- - - - - - - -- - - - - - - -I I I I I I I I I I I I I I f-N- f *f 41 8f 161 471 83f 651 43f 141 37f Sf 21 3271 f-NNE- f 2f if 81 81 461 11sf 1281 761 44f 321 if *1 4611 I------------------------------------------------------------------++ - + + -- -- I f-NE- I -f 21 6f 121 6sf 1941 1951 2231 67f 401 if .1 80sf I-ENE- I *f if 2f Sf 461 11sf l57f Bif 211 4f .1 .1 435f f-E_ I .1 if 21 ef 261 elf 741 57f 12f 21 *f .1 263f I-ESE- I *I if ii Sf 19f 71f sif ilf 41 .1 .1 *f 1641 f-SE- I *1 .1 5I 7I 261 elf 23f ef 2f sf *1 *f 1571 f-SSE- I .f 4f sf 19f 4sf 411 ilf 6f .1 41 .f *1 135f f-S_ I .1 2f sf Sf 34f elf 29f ilf 61 31 .1 .1 176f f-ssW- I .1 .1 61 af 27f 96f 941 41f 6f 7f *1 .1 28sf f-SW- I .1 if sf lof 40f 2071 2171 131f 59f 37f if *1 '7081 f-WSW- I if 21 8f 16f 40f 11sf 82f 37f 26f 1sf 21 *1 3441 f-W_ f .f 4f 71 16f 21f 431 43f 35f 12f 7f .1 .1 leaf I-WNW- I if 3f 6f lof 26f 371 48f 31f 27f 23f 4f if 2171 f-NW- I .1 if 3f Sf 17f 2sf 331 411 2sf 431 12f 2f 213f I-NNW- f if 2f 6f 8f 291 42f 3Sf 39f 33f 39f 12f 3f 249f f-CALM- f if *1 .1 .f .f *1 .1 *f .f .f *1 1 if fTOTAL 1 6f 29f 83f 16Sf 554f 1427f 12851f 871f 361f 298f 41f ef 5128f

Mcauire NUCLEAR STN. METEOROLOGY (2004) PROG=XOQFREQ 09:50 Monday, March 14, 2005 5 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY E WIND SPEED CLASS I I I 0.45-1 0.75-I 1.00-I 1.25-1 1.50-I 2.00-1 3.00-1 4.00-I 5.00-I 6.00-I 8.00- I 1 0.74 1 0.99 11.24 11.49 11.99 I 2.99 1 3.99 I 4.9 5. I~99 I 7.99 I 9.9 jTOTAL I I NO. I NO. I NO. I NO. I NO. I NO. j NO. I NO. I NO. I NO. I NO. I NO. I I---------------------------------------------------------------+- + + -- -- I ISECTOR I I I I I I I I I I I I I I-- - - - - - - -- - - - - - - -I I I I I I I I I I I I I I-N- I .1 ii 41 21 41 131 21 31 21 1I *1 321 I-NNE- 41 f 31 *1 81 7I 41 .1 41 .1 *1 231 I-NE- I if 'I 21 31 El 101 21 1i *1 .1 .1 261 I-ENE- I *I *1 21 fl 121 101 31 *I .1 .1 *1 281 I-ESE- I 21 21 31 7I 7I 251 21 .1 *I .1 .1 481 I-SE- I 21 3I 41 41 161 651 8I fl .1 41 4 1031 I-SSE- I 21 sI 7l '5I 291 16I SI 21 11 *1 .1 83 I-SSW- I .1 51 141 101 551 1441 24! 41 ii .1 .I 2571 I- - - - - - - - - - - - - - - - - - -- - - - -- - - +---------------4I ISW_ I ii 41 121 181 54l 1411 941 191 *1 .1 .1 3431 l-WSW- I fl 101 '5I 281 461 S31 201 61 21 *1 .1 laif I-W_ I fl 6j 7I 14l 241 211 '7l 31 41 1i .1 981 I-WNW- I 1! 31 4I 1.21 211 301 211 91 1i *1 21 1041 I-NW- I 21 1i 11 4I 261 191 181 121 5I ii *1 891 I-NNW- I .1 21 .I 51 81 8I 31 61 21 .1 .1 341 ITOTAL I 131 541 88j 1411 3671 6541 2351 671 181 31 21 16421

McGuire NUCLEAR STN. METEOROLOGY (2004) PROG-XOQFREQ 09:50 Monday, March 14, 2005 6 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY F WIND SPEED CLASS l l 1 0.45-f 0.75-1 1.00-1 1.25-1 1.50-1 2.00-1 3.00-1 5.00-1 I f 0.74 f 0.99 f 1.24 f 1.49 f 1.99 l 2.99 f 3.99 l 5.99 fTOTAL I I ------- +-_ ----

+- ___-- +__ _--+___--- +------ +___-- -+------+------ I I NO. f NO. I NO. I NO. I NO. f NO. I NO. I NO. I NO. I I------------------- _ _ +____-_ +____-_+____-

__+_ _ +____-+____-_+___---+-_----+-------

lSECTOR I I I I I I I I I I I---- --- ---- --- --- -- -- --- II f-N_ I .l i *l *l i if *l

  • 31 l-NNE- f 1i 1f il 1f 31 :I .1 .1 71 f-NE- I 1f .1 31 1i 1i *1 .1 .1 61 f-ENE- I .1 1i *1 21 1l *1 .1 .1 41 f-E- f 1 .*1 1I 1 1 1 .1 .1 51 f-ESE- f 21 .* *l .1 21 1i .* .f 51 f-SE- f .f *l 21 .f 21 1i .1 .1 51 l iSSEf 1l 1i .f 71 141 10l .f .1 331 I-S- 1 21 91 81 131 361 371 .1 .1 1051 I-SSW- f 61 141 121 191 391 321 .1 .1 1221 f-SW- f 41 ilf 121 131 211 311 51 11 981 f-WSW- f 31 21 161 161 221 241 41 .1 871 f-W- f 11 41 91 91 ilf 61 51 .1 451 lfWNW_ I 1l 31 51 51 51 71 31 *f 291 f-NW- f .* 1f 21 .f 1f 21 *f .f 61 f-NNW- f 21 1i 1f .f 21 1l .f .f 71 f-CALM- f 31 *f .f .f .f .f .f .f 31 lTOTAL f 28f 491 71f 871 162f 155l 171 1f 5701

McGuire NUCLEAR STN. METEOROLOGY (2004) PROG-XOQFREQ 09:50 Monday, March 14, 2005 7 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 1.00-1 1.25-1 1.50-1 2.00-1 3.00-1 I l 0.74 l 0.99 l 1.24 l 1.49 l 1.99 l 2.99 l 3.99 lTOTAL I I------- +-____+_- _+__-+---+____-_+_-+____- I I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I I-----------+-_ -+- +- +- +-+-_-_-- + _-+-

lSECTOR I I I I I I I I I I-- - - - - - - -- - - - - - - -I I I I I I I II j_N_ I .1 1l 1l .1 .1 .1 *l 21 I-NE- I 1l 1l 1 *l1 .1 .1 *1 31 I-E- I 1I .l .l .l .l .- l-l 1I l-SE- I l1 .l .l l1 1I l *l 11 I-SSE- I 1I 21 .1 .1 l * .1 .1 31 I-S- 1 -- 31 81 +- 61 51 .1 281 I-SSW- I 101 191 181 161 81 21 .1 731 I-Sw- 1 81 151 161 101 81 11 .*1 58 I-WSW- I 5I 61 61 61 31 1i *1 271 I-W- 1 41 61 41 11 .1 21 11 181 I-WNW- I 31 21 11 *1 1l .1 .1 71 I-NW- I 21 11 1j *l1 i *l1 .1 s I-CALM- l 81 *l *1 .1 .1 .1

  • 1 81 lTOTAL I 461 611 531 391 271 71 1l 2341

Mccuire NUCLEAR STN. METEOROLOGY (2004) PROG=XOQFREQ 09:50 Monday, March 14, 2005 8 iOM WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS ALL STABILITY CLASSES WIND SPEED CLASS I I I 0.45-1 0.75-I 1.00-I 1.25-I i.so-1 2.00-I 3.00-1 4.00-I 5.00-I 6.00-1 8.00-1>9.99 I I 10.74 0.99 1.24 1.49 I 1.99 1 2.99 3.99 I I.9 5.99 I 7.99 I 9.99 I M/S ITOTAL I I------- ------------------------------------------------- +- + I IINO. I NO. I NO. J NO. I NO. I NO. I NO. j NO. J NO. J NO. I NO. I NO. j NO. I I--------------- --------- ------------------------------------------------- +- +I ISECTOR I I I I I I I I I I I I I I I-- - - - - - - -- - - - - - - -I I I I I I I I I I I I I I I-N- I *1 7I 141 191 541 l0fl 671 47 171 54I 131 41 3971 I-NNE- I 31 31 ill 101 661 1341 1361 781 47 37I 41 *1 5291 I-NE- I 31 41 121 171 771 2191 2121 2381 781 44I ii .1 9051 I----------------------------------------------------------------- -- - +------ I I-ENE- I .1 21 4I ill 611 1381 1881 951 261 5I .1 .1 5301 I-E- 21 SI 4I 141 331 98j 84 581 121 41 .1 .1 3141 I-ESE- I 41 3I 41 131 281 1001 S5l 131 71 41 *I .1 2311 I-SE- j 21 31 ill ill 461 1491 321 9I 21 5I .1 .1 2701 I-SSE- I 41 121 121 411 891 691 181 81 il 4I .1 *I 2581 1-s- I sj 251 271 391 1221 201.1 481 131 61 31 .1 .1 4891 1-55W- I 161 381 501 531 1321 2911 1451 591 7I 7I -I .1 7981 I---------------------------------------------------------+- + + -- +- -- ------

+--

I-Sw- I 131 311 451 511 1261 394I 3501 1771 75I 491 31 .1 13141 I-----------------------------------------------------+- ---- + - ------- - +------I I-WSW- I 101 201 45I 671 1141 2011 1181 561 301 171 31 .1 6811 1-14 1 61 201 271 411 581 77j 69J 401 i61 81 *1 .1 3621 I-WIN- I 61 lii 161 271 54I 781 721 43l 311 251 81 21 373l I-NW- I 41 41 71 iSI 491 481 SlI 57I 37 491 141 31 3381 I-NNW- I 31 5I 71 iSI 391 551 381 47 421 661 211 61 344I I------------------- +------------------------------------+- + + ---- + + -- +------

I-CALM- I 121 .1 .1 .1 .1 .1 .1 *I .1 .1 *1 *1 121 ITOTAL I 93I 1931 2961 444 114sf 23S31 16831 10381 434 3811 671 iSI 81451

Attachment 2 Solid Waste Disposal Report

MCGUIRE NUCLEAR SITE

SUMMARY

OF MAJOR RADIONUCLIDE COMPOSITION 2004 I Type of waste Nuclide  % Abundance JI A. Dewatered Powdex Resin (brokered) No shipments in 2004 B. Dewatered Powdex Resin No shipments in 2004 C. Dewatered Bead Resin (brokered) No shipments in 2004 D. Dewatered Bead Resin No shipments in 2004 E. Dewatered Radwaste System Resin (brokered) Nuclide %Abundance 2004-21 Mn-54 0.35 Co-60 15.80 Cs-137 4.20 Fe-55 37.80 NI-63 41.00 Sb-125 0.49 F. Dewatered Primary Bead Resin (brokered) Nuclide %Abundance 2004-11 Mn-54 4.80 Co-57 0.53 Co-58 6.30 CO-60 16.60 Cs-1 37 3.20 Cs-134 0.26 Ni-63 51.00 2004-13 Nuclide %Abundance Mn-54 5.50 Co-57 0.54 Co-58 5.30 Co-60 16.40 Cs-134 0.23 Cs-137 3.30 Be-7 1.30 Fe-55 16.90 Ni-63 51.00 1

2004-17 Nuclide %Abundance Mn-54 2.39 Co-57 0.28 Co-58 2.00 Co-60 17.56 Cs-1 37 3.30 Cs-134 0.20 Fe-55 17.80 Be-7 0.60 Ni-63 55.60 2004-19 Nuclide %Abundance Mn-54 2.40 Co-57 0.30 Co-58 0.70 Co-60 18.20 Cs-137 1.70 Fe-55 18.50 Ni-63 57.70 Sb-125 0.27 2

G. Dewatered Mechanical Filter Media No shipments in 2004 H. Dewatered Mechanical Filter Media (brokered) 2004-03 Nuclide %Abundance Co-60 29.00 Fe-55 48.00 Ni-63 22.00 2004-20 Nuclide %Abundance Mn-54 0.13 Co-60 31.00 Fe-55 36.00 NI-63 26.00 C-14 0.29 2004-27 Nuclide %Abundance Mn-54 0.43 Co-60 31.90 Cs-134 0.09 Fe-55 34.40 Ni-63 33.00 C-14 0.32 I. Solidified Waste No shipments in 2004 A. Dry Active Waste (compacted) Compaction no longer performed on-site.

Dry Active Waste (non-compacted) No shipments in 2004 Dry Active Waste (brokered/compacted) No shipments in 2004 Dry Active Waste (brokered/non-compacted) 2004-04 DAW Nuclide %Abundance Cr-51 9.30 Mn-54 0.54 Co-58 23.09 Co-60 2.61 Cs-137 0.53 Fe-55 10.99 Ni-63 . 5.09 H-3 46.86 Zr-95 0.92 Nb-95 1.94 3

2004-06 DAW Nuclide %Abundance Cr-51 6.60 Mn-54 0.55 Co-58 21.00 Co-60 2.80 Cs-137 0.55 Fe-55 11.50 Ni-63 5.40 H-3 49.50 Zr-95 0.80 Nb-95 1.50 2004-07 DAW Nuclide %Abundance Cr-51 0.62 Mn-54 0.55 Co-58 8.00 Co-60 3.50 Cs-137 0.74 Fe-55 14.00 Ni-63 7.20 H-3 65.00 Zr-95 0.28 Nb-95 0.21 2004-12 DAW Nuclide %Abundance Cr-51 10.80 Mn-54 0.62 Co-58 80.20 Co-60 1.70 Fe-59 0.33 Zr-95 2.70 Nb-95 3.30 2004-14 DAW Nuclide %Abundance Cr-51 8.60 Mn-54 0.70 Co-57 0.19 Co-58 82.40 Co-60 2.00 Fe-59 0.31 Zr-95 2.70 Nb-95 2.80 2004-15 DAW Nuclide %Abundance Cr-51 7.30 Mn-54 0.79 Co-57 0.21 Co-58 85.30 Co-60 2.30 Fe-59 0.29 Zr-95 2.70 Nb-95 2.57 4

2004-23 DAW Nuclide %Abundance Cr-51 9.30 Mn-54 0.50 Co-58 23.00 Co-60 2.60 Cs-137 0.50 Fe-55 11.00 Ni-63 5.10 H-3 46.90 Zr-95 0.90 Nb-95 1.90 B. Sealed Sources No shipments in 2004 C. Sealed Sources/Smoke Detectors No shipments in 2004 D. Irradiated Components No shipments in 2004 5

REPORT PERIOD McGUIRE NUCLEAR STATION Attachment I JANUARY - DECEMBER 2004 SOLID RADIOACTIVE WASTE SHIPPED TO DISPOSAL FACILITIES TYPES OF WASTES SHIPPED Number of Number of Container Burial Volume Waste Total Waste from Liquid Systems Shipments Containers Type ft3 m3 Class Curies (A) dewatered powdex resin (brokered) 0 0 N/A 0 0.00 N/A 0.00E+00 (B) dewatered powdex resin 0 0 N/A 0 0.00 N/A 0.002+00 (C) dewatered bead resin (brokered) 0 0 N/A 0 0.00 N/A 0.OOE+00 (D) dewatered bead resin 0 0 N/A 0 0.00 N/A 0.00E+00 (E) dewatered radwaste system resin 1 1 14-195 9.55 0.27 A/U 4.45E+00 (F) dewatered primary bead resin (brokered) 4 4 8-120 162.88 4.61 B 3.24E+02 (G) dewatered mechanical filter media 0 0 N/A 0 0.00 N/A 0.00E+00 (H) dewatered mechanical filter media (brokered) 3 24 60 gal. HIC 89.13 2.53 C 5.47E+01 (I) solidified waste 0 0 N/A 0 0.00 N/A 0.00E+00 Dry Solid Waste (A) dry active waste (compacted) 0 0 N/A 0 0.00 N/A 0.00E+00 dry active waste (non-compacted) 0 0 N/A 0 0.00 N/A O.OOE+00 dry active waste (brokered/compacted) 0 0 N/A 0 0.00 NtA 0.0002+00 dry active waste (brokered/non-compacted) 7 13 GDP 937.24 26.54 A/U 1.259E+00 (B) sealed sources/smoke detectors 0 0 N/A 0 0.00 N/A O.OOE+00 (C) sealed sources 0 0 N/A 0 0.00 N/A O.OOE+00 (D) irradiated components 0 0 N/A 0 Totals 15 42 1198.8 33.95 3.840E+02 4/13/2005

Attachment 3 Unplanned OMfsite Releases

McGUIRE NUCLEAR STATION UNPLANNED RELEASES (January 1, 2004 through December 31, 2004)

There were two unplanned gaseous and no unplanned liquid radioactive effluent releases to the environment in 2004. The unplanned gaseous radioactive effluent releases are described in the following pages.

Memorandum To: Annual Radioactive Effluent Release Report CC: Lance Loucks, H. J. Sloan, Joyce Correll, C.D. Ingram, Jim Kammer, Kay Crane From: William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit 1 Vent Reference PIP M-04-0277 Event Summary: See referenced PIP for details On January 20, 2004 @ 09:30 to 09:50 hours, 32.6 cubic feet of fission and activation gas was inadvertently released to the unit 1 vent. The A train WG Hydrogen Recombiner was being swapped to the B train WG Hydrogen Recombiner to facilitate valve repair on 1 WG-200. Within moments of the train swap, auxiliary bid monitor EMF 41 point I reached Trip 2 alarm level. Operations notified Radwaste Chemistry and the A train was returned to service at 09:50 hours. Conditions returned to normal within minutes. Based on electronic data the inservice WGDT "F" indicated a loss of 32.6 cubic feet during the release period.

Radiation Protection monitoring the EMF 41 and 1 EMF 36L (Unit Vent gas monitor) indicated elevated counts (28 cpm) above background on I EMF 36L for approximately 24 minutes.

A gas sample was obtained from the inservice WGDT SF" at 13:22 hours to account for activity released. The gas released into the Auxiliary bid. Room 615 was removed by aux. bld.VA and exhausted to the unit vent. No personnel were exposed to the undiluted release. A nitrogen test on the B train WG Hydrogen Recombiner identified three leak sites.

Investigation of Unusual Radiological Occurrences procedure SH/0/1B2001/004 completed to document the Unplanned Release.

The total Noble gas activity released was reported on (GWR) Gaseous Waste Release # 2004006.

The unplanned activity was evaluated against off site dose limits using current ODCM methodology.

Safety Significance:

The health and safety of the public were not compromised by this event. The total activity released was insignificant. Calculated dose and dose rate to the Total Body, Skin, Gamma Air, and Beta Air were all less than two tenths of one percent (<0.2%) of the limits specified by Selected Licensee Commitments and Code of Federal Regulations.

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

Memorandum To: Annual Radioactive Effluent Release Report CC: Lance Loucks, H. J. Sloan, Joyce Correll, C.D. Ingram, Jim Kammer, Kay Crane From: William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned Release to the Unit 1 Vent Reference PIP M-04-05703 Event Summary: See referenced PIP for details On December 8, 2004 @ - 10:00 hours, a volume of fission and activation gas from WGDT-B was inadvertently released to the unit I vent. Approximately 20 cpm above background was seen at the peak of the release. Conditions returned to normal within 120 minutes. Based on Tank pressure loss the WGDT- B indicated a release of 302 cubic feet during the release period.

MGMM 15044 was in progress to install a new WG valve I WG-342. WG system piping was cut as part of this process. Radwaste Chemistry monitored WGDT pressure during the evolution. At approximately 10:30 hours, Chemistry notified RP that a drop in WGDT-B pressure had been identified. Radiation Protection was notified. Auxiliary building gas monitor EMF 41 indicated an increase in cpm to -150 cpm above bkg at the monitoring point in the area of the modification work.

Subsequent monitoring of EMF 41 and 1 EMF 36L (Unit Vent gas monitor) indicated elevated counts (20 ccpm max) above background on I EMF 36L for a approximately 120 minutes. Follow-up sampling in the work area was performed. Chemistry verified WGDT-B isolation valves closed and count rate on EMF 41 and 1 EMF 36 returned to normal. Initial calculation of the activity released based on the unit vent monitor response indicated no regulatory reporting concerns.

The gas released into the auxiliary building was removed by auxiliary building ventilation and exhausted to the unit vent. No personnel were exposed to the undiluted release. Monitoring of EMF 41 and 1 EMF 36 indicated no further release of activity. The mod was complete, waste gas system returned to service and a gas sample obtained from WGDT-B on 12/11/04 @ 10:25 hours to account for activity released.

Investigation of Unusual Radiological Occurrences procedure SH/0/B/2001/004 completed to document the Unplanned Release.

The total Noble gas activity released is reported on (GWR) Gaseous Waste Release # 2004085.

==

Conclusion:==

The radioactivity released was evaluated against off site dose limits using current ODCM methodology. The health and safety of the public were not compromised by this event. The total activity released was insignificant. Calculated dose and dose rate to the Total Body, Skin, Gamma Air, and Beta Air were all less than two one hundredths of one percent (<0.02%) of the limits specified by Selected Licensee Commitments and Code of Federal Regulations.

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

Attachment 4 Fuel Cycle Calculation

McGuire Nuclear Station 2004 Radioactive Effluent Releases 40CFR190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFRl90, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. The fuel cycle dose assessment for McGuire Nuclear Station only includes liquid and gaseous effluent dose contributions from McGuire and direct and air-scatter dose from McGuire's onsite Independent Spent Fuel Storage Installation (ISFSI) since no other uranium fuel cycle facility contributes significantly to McGuire's maximum exposed individual. The combined dose to a maximum exposed individual from McGuire's effluent releases and direct and air-scatter dose from McGuire's ISFSI is well below 40CFRl90 limits as shown by the following summary:

I. 2004 McGuire 40CFRl90 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 = 6.78E-01 mrem Maximum Location: 0.5 Mile, East Sector Critical Age: Child Gas non-NG Contribution: 81%

Gas NG Contribution: 2%

Liquid Contribution: 17%

Maximum Organ (other than TB) Dose = 6.73E-01 mrem Maximum Location: 0.5 Mile, East Sector Critical Age: Child Critical Organ: Thyroid Gas Contribution: 83%

Liquid Contribution: 17%

II. 2004 McGuire 40CFR190 ISFSI Dose Suimnary 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 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. 10CFR72.212(b)(2)(iii)- Requirements of 72.104 Criterion

"...the requirementsof 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#l 3Q '02 4Q '02 1Q '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 reins during a 98 day period in the first quarter of 2004. This is equivalent to 0.0247 mrem per hour for a total population of ten TN-32 casks. The calculated dose for this same location using conservative computer models is 0.744 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 I OCFR 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 wvill also assure compliance with 40 CFR Part 190.

McGuire Nuclear Site (NAC UMS)

IOCFR72.212 Written Evaluations, Rev. 0

Transnuclear. 4 The best-fit empirical equation for skyshine dose rate as a function of distance is y = 0.0156e-Oi12 x for gammas and y = 0.0274e4OI2 9 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,'688 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. Based upon conservative engineering judgement, the McGuire power generation contribution at the Exclusion Area Boundary (EAB) is determined to be 3 mrem per year. The 3 mrem per year is independent of the ISFSI.

The combined and skyshine dose rates at various distances for a 2x6 cask array with 5 year cooled fuel were analyzed by NAC.5 Skyshine dose rates are located in Table 6-4 on page 12 and combined dose rates are located in Table 6-6 on page

14. Both tables account for the effects of both gammas and neutrons.

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

occupancy time (8750 hours0.101 days <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) 40CFRI90 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 Powver, TN-32 MCMP Models for Determining Off-Site Doses," Rev. 0, dated 4/06/2000.

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

McGuire Nuclear Site (NAC UMS)

IOCFR72.212 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 40CFR190.10(a) that the annual dose equivalent shall not exceed 25 mrems to the whole body, 75 mrems to the thyroid, and 25 mrems to any other organ of any member of the public as a result of exposures to planned discharges of radioactive materials, radon and its daughters excepted, to the general environment from uranium fuel cycle operations and to radiation from these operations. As illustrated previously in showing compliance with 10CFR 72.104(a), the calculated dose at the EAB is 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 IOCFR20.1301(a)(2).

McGuire Nuciear Site (NAC UMS) 10CFR72.212 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 E02 mrem/hr.

(10) Casks X 7.443 E02 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) 0.0247mremperhr + 0.128mremperhr = 0.153mremperhr Waterwav 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 E03 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 Watervay 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 mremlhr 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

Attachment 5 Inoperable Monitoring Equipment

McGuire Nuclear Station Inoperable Monitoring Equipment (January 1, 2004 through December 31, 2004)

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

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