ML071590159
| ML071590159 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 12/31/2006 |
| From: | Duke Energy Carolinas, Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RG-1.021 | |
| Download: ML071590159 (58) | |
Text
Attachment 1 Radioactive Effluent Releases and Supplemental Information
McGUIRE NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 2006 through December 31, 2006)
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 1/1/06 TO 1/1/07 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2006 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Gases
- 1. Total Release Ci 7.18E-01 6.67E-01 6.90E-01 4.39E-01 2.51E+00
- 2. Avg. Release Rate yCi/sec 9.24E-02 8.48E-02 8.68E-02 5.53E-02 7.97E-02 B. Iodine-131
- 1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
- 2. Avg. Release Rate ILCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 C. Particulates Half Life >= 8 days
- 1. Total Release Ci 2.79E-07 0.OOE+00 2.28E-05 2.61E-05 4.92E-05
- 2. Avg. Release Rate pCi/sec 3.59E-08 0.OOE+00 2.86E-06 3.29E-06 1.56E-06 D. Tritium
- 1. Total Release Ci : 6.13E+01 6.23E+01 1.04E+02 1.05E+02 3.33E+02
- 2. Avg. Release Rate pCi/sec 7.88E+00 7.92E+00 1.31E+01 1.32E+01 1.06E+01 E. Gross Alpha Radioactivity
- 1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+i00 0.00E+00
- 2. Avg. Release Rate gCi/sec 0.OOE+00 0.OOE+i00 0.OOEi-00 0.OOE+i00 0.OOE+00
TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2006 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Gases
- No Nuclide Activities **
- 2. lodines
- No Nuclide Activities **
- 3. Particulates Half Life >= 8 days
- No Nuclide Activities **........
- 4. Tritium
- No Nuclide Activities **
- 5. Gross Alpha Radioactivity
- No Nuclide Activities **........
TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2006 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Gases
- No Nuclide Activities **
- 2. Iodines
- No Nuclide Activities **
- 3. Particulates Half Life >= 8 days
- No Nuclide Activities **........
- 4. Tritium
- No Nuclide Activities **
- 5. Gross Alpha Radioactivity
- No Nuclide Activities ** ........
TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2006 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Gases XE-133 Ci 2.74E-02 0.OOE+00 0.00E+00 0.OOE+00 2.74E-02 XE- 133M Ci 1.03E-03 0.OOE+00 0.OOE+00 0.OOE+00 1.03E-03 XE-135 Ci 4.34E-02 0.OOE+00 0.OOE+00 0.OOE+00 4.34E-02 Totals for Period... Ci 7.19E-02 0.OOE+00 0.OOE+00 0.OOE+00 7.19E-02
- 2. Iodines 1-133 Ci 0.OOE+00 0.OOE+00 0.00E+00 3.80E-06 3.80E-06 Totals for Period... Ci 0.OOE+00 0.OOE+00 0.OOE+00 3.80E-06 3.80E-06
- 3. Particulates Half, Life >= 8 days BE-7 Ci 0.OOE+00 0.OOE+00 0.OOE+00 1.39E-05 1.39E-05 CO-58 Ci 2.79E-07 0.OOE+00 2.28E-05 1.14E-05 3.44E-05 MN-54 Ci 0.OOE+00 0.OOE+00 0.OOE+00 8.60E-07 8.60E-07 Totals for Period... Ci 2.79E-07 0.OOE+00 2.28E-05 2.61E-05 4.92E-05
- 4. Tritium H-3 Ci 6.08E+01 6.20E+01 1.03E+02 1.01E+02 3.27E+02 Totals for Period... Ci 6.08E+01 6.20E+01 1.03E+02 1.01E+02 3.27E+02
- 5. Gross Alpha Radioactivity
- No Nuclide Activities **
TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2006 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Gases AR-41 Ci 4.94E-01 5.32E-01 5.37E-01 4.31E-01 1.99E+00 KR-85 Ci 9.22E-02 5.99E-02 8.96E-02 0. 00E+00 2.42E-01 XE-133 Ci 5.82E-02 7.25E-02 6.04E-02 7.86E-03 1.99E-01 XE-135 Ci 2.06E-03 1.81E-03 3.16E-03 0.OOE+00 7.03E-03 Totals for Period... Ci 6.46E-01 6.67E-01 6.90E-01 4.39E-01 2.44E+00
- 2. Iodines
- No Nuclide Activities **
- 3. Particulates Half Life >= 8 days
- No Nuclide Activities **
- 4. Tritium H-3 Ci 4.93E-01 3.42E-01 9.36E-01 4.40E+00 6.17E+00 Totals for Period... Ci 4.93E-01 3.42E-01 9.36E-01 4.40E+00 6.17E+00
- 5. Gross Alpha Radioactivity
- No Nuclide Activities **
TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2006 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products
- 1. Total Release Ci 1.12E-02 8.92E-03 1.84E-02 2.22E-02 6.08E-02
- 2. Average Diluted Concentration
- a. Continuous Releases pCi/ml 0.00E+00 0.00E+00 0.00+E00 0.00E+00 0.00E+00
- b. Batch Releases pCi/ml 1.32E-11 8.99E-12 1.95E-11 2.59E-11 1.67E-11 B. Tritium
- 1. Total Release Ci 3.29E+02 5.51E+02 9.61E+02 5.31E+02 2.37E+03
- 2. Average Diluted Concentration
- a. Continuous Releases pCi/ml 7.37E-09 2.64E-08 1.10E-07 6.34E-08 4.57E-08
- b. Batch Releases pCi/ml 3.86E-07 5.54E-07 1.02E-06 .6.15E-07 6.49E-07 C. Dissolved and Entrained Gases
- 1. Total Release Ci 0.00E+00 0.001+00 0.001+00 0.001+00 0.001+00
- 2. Average Diluted Concentration 0.00E+00 0.00E+00 0.OOE+00 0.00E+00
- a. Continuous Releases pCi/ml 0.00+E00 0.00E+00 0.00+E00 0.00E+00 0.00E+00
- b. Batch Releases pCi/ml 0.00E+00 D. Gross Alpha Radioactivity 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 1. Total Release Ci 0.00+E00
- 2. Average Diluted Concentration 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- a. Continuous Releases pCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- b. Batch Releases gCi/ml 0.00E+00 E. Volume of Liquid Waste
- 1. Continuous Releases liters 5.55E+07 4.76E+07 1.80E+08 1.78E+08 4.61E+08
- 2. Batch Releases liters 6.66E+05 7.94E+05 1.53E+06 1.59E+06 4.58E+06 F. Volume of-Dilution Water
- 1. Continuous Releases liters 5.58E+10 1.88E+10 2.69E+10 4.29E+10 1.44E+11
- 2. Batch Releases liters 8.51E+11 9.93E+II 9.43E+11 8.58E+11 3.65E+12
TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 LIQUID EFFLUENTS - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2006 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Products
- No Nuclide Activities **
- 2. Tritium H-3 Ci 4.12E-01 4.97E-01 2.98E+00 2.73E+00 6. 62E+00 Totals for Period... Ci 4.12E-01 4.97E-01 2.98E+00 2.73E+00 6. 62E+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 1/1/06 TO 1/1/07 LIQUID EFFLUENTS - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2006 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Products AG-108M Ci 1. 06E-04 2.30E-05 6.62E-05 9.73E-06 2. 05E-04 AG-IIOM Ci 1. 53E-04 2.49E-06 4.64E-05 0.OOE+00 2.01E-04 BE-7 Ci 0. OOE+00 0.OOE+00 1.03E-03 0.OOE+00 1.03E-03 CE-144 Ci 0. 00E+00 1.34E-05 0.OOE+00 0.OOE+00 1.34E-05 CO- 57 Ci 7. 05E-06 3.29E-06 2. 99E-06 2.74E-06 1.61E-05 CO-58 Ci 1.44E-03 3.74E-04 1.20E-03 6. 61E-03 9.63E-03 CO-60 Ci 6 .33E-03 3.09E-03 3.54E-03 6.82E-04 1.37E-02 CR-51 Ci 1. 97E-04 1.21E-05 1.51E-04 2.03E-04 5.63E-04 CS-134 Ci 2 .24E-04 4.20E-04 6.71E-04 2.07E-03 3.38E-03 CS-137 Ci 6 .36E-04 1.10E-03 1.88E-03 5.22E-03 8. 83E-03 FE-59 Ci 2 .40E-05 1.36E-05 4.41E-05 1.41E-05 9.57E-05 1-131 Ci 0 OOE+00 0.OOE+00 5..64E-05 0.OOE+00. 5.64E-05 1-133 Ci 0 00E+00 0.OOE+00 4.71E-08 0.OOE+00 4.71E-08 MN-54 Ci 5.24E-04 2.27E-04 3.52E-04 2.84E-05 1.13E-03 MN-56 Ci 0. 00E+00 5.86E-06 0.OOE+00 0.OOE+00 5.86E-06 NB-95 Ci 1. 09E-04 0.OOE+00 1.14E-05 2.26E-06 1.22E-04 NB-97 Ci 4 .42E-06 0.OOE+00 1.52E-05 0. OOE+00 1. 96E-05 RU-106 Ci 0 OOE+00 0.OOE+00 1.94E-05 0. OOE+00 1. 94E-05 SB-122 Ci 0 OOE+00 6.97E-06 9.61E-06 1.93E-05 3.59E-05 SB-124 Ci 0 OOE+00 0.OOE+00 1.65E-07 4.48E-06 4.65E-06 SB-125 Ci 1.45E-03 3.63E-03 9.33E-03 7.36E-03 2.18E-02 SN-113 Ci 0 OOE+00 0. OOE+00 5.96E-06 0.00E+00 5. 96E-06 SR-92 Ci 2. 03E-06 0. OOE+00 0. OOE+00 0. OOE+00 2.03E-06 ZR-95 Ci 2. 87E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.87E-05 Totals for Period... Ci 1.12E-02 8.92E-03 1.84E-02 2.22E-02 6.08E-02
- 2. Tritium H-3 Ci 3.29E+02 5.50E+02 9.58E+02 5.28E+02 2.36E+03 Totals for Period... Ci 3.29E+02 5.50E+02 9.58E+02 5.28E+02 2.36E+03
- 3. Dissolved and Entrained Gases
- No Nuclide Activities **
- 4. Gross Alpha Radioactivity
- No Nuclide Activities **
McGUIRE NUCLEAR STATION SUPPLEMENTAL INFORMATION
McGUIRE NUCLEAR STATION 2006 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS - PER UNIT A. NOBLE GASES - AIR DOSE B. LIQUID EFFLUENTS - DOSE
- 1. CALENDAR QUARTER - GAMMA DOSE = 5 MRAD 1. CALENDAR QUARTER - TOTAL BODY DOSE = 1.5 MREM
- 2. CALENDAR QUARTER - BETA DOSE = 10 MRAD 2. CALENDAR QUARTER - ORGAN DOSE = 5 MREM
- 3. CALENDAR YEAR - GAMMA DOSE = 10 MRAD 3. CALENDAR YEAR - TOTAL BODY DOSE = 3 MREM
- 4. CALENDAR YEAR - BETA DOSE = 20 MRAD 4. CALENDAR YEAR - ORGAN DOSE - 10 MREM C. GASEOUS EFFLUENTS - IODINE - 131 AND 133, TRITIUM, PARTICULATES W/T 1/2 > 8 DAYS - ORGAN DOSE
- 1. CALENDAR QUARTER = 7.5 MREM
- 2. CALENDAR YEAR = 15 MREM II. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS A. GASEOUS EFFLUENTS - INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL B. LIQUID EFFLUENTS - INFORMATION FOUND IN 10CFR20, APPENDIX B, TABLE 2, COLUMN 2 III. AVERAGE ENERGY - NOT APPLICABLE IV. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY ANALYSES OF SPECIFIC RADIONUCLIDES IN SELECTED OR COMPOSITED SAMPLES AS DESCRIBED IN THE SELECTED LICENSEE COMMITMENTS ARE USED TO DETERMINE THE RADIONUCLIDE COMPOSITION OF THE EFFLUENT. SUPPLEMENTAL REPORT, PAGE 2, PROVIDES A
SUMMARY
DESCRIPTION OF THE METHOD USED FOR ESTIMATING OVERALL ERRORS ASSOCIATED WITH RADIOACTIVITY MEASUREMENTS.
V. BATCH RELEASES A. LIQUID EFFLUENT
- 1. 2.44E+02 TOTAL NUMBER OF BATCH RELEASES
- 2. 1.84E+04 TOTAL TIME (MIN.) FOR BATCH RELEASES.
- 3. 2.11E+02 MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
- 4. 7.56E+01 AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
- 5. 6.OOE+00 MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
- 6. 1.83E+06 AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).
B. GASEOUS EFFLUENT
- 1. 3.70E+01 TOTAL NUMBER OF BATCH RELEASES.
- 2. 9.54E+05 TOTAL TIME (MIN.) FOR BATCH RELEASES.
- 3. 4.49E+04 MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
- 4. 2.58E+04 AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
- 5. 2.38E+02 MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
VI. ABNORMAL RELEASES A. LIQUID
- 1. NUMBER OF RELEASES = 0
- 2. TOTAL ACTIVITY RELEASED (CURIES) = 0 B. GASEOUS
- 1. NUMBER OF RELEASES = 1
- 2. TOTAL ACTIVITY RELEASED (CURIES) = 7.19E-2 (see attachment for additional information)
SUPPLEMENTAL REPORT PAGE 2 McGUIRE NUCLEAR STATION The estimated percentage of error for both Liquid and Gaseous effluent release data at McGuire Nuclear Station has been determined to be + 25.2%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:
(1) Flow rate determining devices = + 20%
(2) Counting error = +15%
(3) Sample preparation error = +-3%
McGUIRE NUCLEAR STATION Assessment of Radiation Dose from Radioactive Effluents and all Uranium Fuel Cycle Sources to Members of the Public (January 1, 2006 through December 31, 2006)
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 1/1/06 TO 1/1/07 GASEOUS ANNUAL DOSE
SUMMARY
REPORT McGuire Nuclear Station Units 1 & 2 lt Quarter 2006 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 1 2006 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose TEEN LUNG 7.28E-02 1.50E+01 4.85E-01 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Inhalation Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS==-=======-=--............-Quarter 1 2006 Dose Limit % of Period-Limit (mrad) (mrad) Limit Ql - Maximum Gamma Air Dose 1.14E-02 1.00E+01 1.14E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage AR-41 9.75E+01 Q1 - Maximum Beta Air Dose 4.83E-03 2.00E+01 2.42E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage AR-41 8.09E+01 KR-85 8.98E+00 XE-135 5.59E+00
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 GASEOUS ANNUAL DOSE
SUMMARY
REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2006 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 2 2006 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose TEEN LIVER 7.40E-02 1.50E+01 4.93E-01 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Inhalation Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS==----------------------- Quarter 2 2006 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose 1.20E-02 1.00E+01 1.20E-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 Q2 - Maximum Beta Air Dose 4.69E-03 2.00E+01 2.34E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage AR-41 8.98E+01 KR-85 6.02E+00
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 GASEOUS ANNUAL DOSE
SUMMARY
REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2006 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 3 2006 ====
Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose TEEN LUNG 1.24E-01 1.50E+01 8.25E-01 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Inhalation Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS==----------------------- Quarter 3 2006 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q3 - Maximum Gamma Air Dose 1.21E-02 1.00E+01 1.21E-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 4.84E-03 2.OOE+01 2.42E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage AR-41 8.77E+01 KR-85 8.71E+00
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 GASEOUS ANNUAL DOSE
SUMMARY
REPORT McGuire Nuclear Station Units 1 & 2 4 th Quarter 2006 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 4 2006 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose TEEN LUNG 1.25E-01 1.50E+01 8.32E-01 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Inhalation Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS========================= Quarter 4 2006 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Ganmma Air Dose 9.69E-03 1.00E+01 9.69E-02 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage AR-41 9.99E+01 Q4 - Maximum Beta Air Dose 3.43E-03 2.00E+01 1.72E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage AR-41 9.94E+01
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 GASEOUS ANNUAL DOSE
SUMMARY
REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2006
=== IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Annual 2006 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose TEEN LUNG 3.95E-01 3.00E+01 1.32E+00 Maximum Organ Dose Receptor Location: 0.5 Mile ENE Critical Pathway: Inhalation Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS========================= Annual 2006 Dose Limit % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Gamma Air Dose 4.52E-02 2.00+E01 2.26E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage AR-41 9.90E+01 Yr - Maximum Beta Air Dose 1.78E-02 4.00E+01 4.45E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage AR-41 8.87E+01 KR-85 6.39E+00
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 LIQUID ANNUAL DOSE
SUMMARY
REPORT McGuire Nuclear Station Units 1 & 2 1 st Quarter 2006 BATCH LIQUID RELEASES Quarter 1 2006 ......
Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q1 - Maximum Organ Dose CHILD LIVER 4.47H-02 1.OOE+01 4.47E-01 Q1 - Total Body Dose CHILD 4.08E-02 3.OOE+00 1.36E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 8.91E+01 CS-137 7.37E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 9.76E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 1 2006 ======
Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q1 - Maximum Organ Dose CHILD LIVER 7.61E-04 1.00E+01 7.61E-03 Q1 - Total Body Dose CHILD 7.61E-04 3.OOE+00 2.54E-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 1/1/06 TO 1/1/07 LIQUID ANNUAL DOSE
SUMMARY
REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2006
=== BATCH LIQUID RELEASES Quarter 2 2006 ==--..
Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q2 - Maximum Organ Dose CHILD LIVER 6.51E-02 1.00E+01 6.51E-01 Q2 - Total Body Dose CHILD 5.91E-02 3.00E+00 1.97E÷00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 8.88E+01 CS-137 7.60E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 9 .78E+01 CONTINUOUS LIQUID RELEASES (WC)--==---=--==--==-====== Quarter 2 2006 ======
Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (orem) Limit Q2 - Maximum Organ Dose CHILD LIVER 2.75E-03 1.OOE+01 2.75E-02 Q2 - Total Body Dose CHILD 2.75E-03 3.OOE+00 9.17E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.00E÷02
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 LIQUID ANNUAL DOSE
SUMMARY
REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2006
=== BATCH LIQUID RELEASES Quarter 3 2006 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 1.20E-01 1.00E+01 1.20E+00 Q3 - Total Body Dose CHILD 1.09E-01 3.00E+00 3.65E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 8.92E+01 CS-137 7.47E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 9.79E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 3 2006 -- ====
Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 1.16E-02 1.00E+01 1.16E-01 Q3 - Total Body Dose CHILD 1.16E-02 3.OOE+00 3.87E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.OOE+02
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 LIQUID ANNUAL DOSE
SUMMARY
REPORT McGuire Nuclear Station Units 1 & 2 4 th Quarter 2006 BATCH LIQUID RELEASES Quarter 4 2006 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 1.06E-01 1.00E+01 1.06E+00 Q4 - Total Body Dose ADULT 8.00E-02 3.00E+00 2.67E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 6.14E+01 CS-137 2.59E+01 CS-134 1.26E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 6.09E+01 CS-137 2.34E+01 CS-134 1.57E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 4 2006 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 6.69E-03 1.OOE+01 6.69E-02 Q4 - Total Body Dose CHILD 6.69E-03 3.OOE+00 2.23E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.00OE÷02
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/06 TO 1/1/07 LIQUID ANNUAL DOSE
SUMMARY
REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2006 BATCH LIQUID RELEASES Annual 2006 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Yr - Maximum Organ Dose CHILD LIVER 3.36E-01 2.00E+01 1.68E+00 Yr - Total Body Dose CHILD 2.83E-01 6.00E+00 4.71E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 8.09E+01 CS-137 1.29E+01 CS-134 6.08E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total) e.'.; "
Nuclide Percentage H-3 .9.60E+01 CONTINUOUS LIQUID RELEASES (WC)-...................... Annual 2006 =========
Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 1.91E-02 2.OOE+01 9.57E-02 Yr - Total Body Dose CHILD 1.91E-02 6.00E+00 3.19E-01 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
(
Attachment 2 Solid Waste Disposal Report
MCGUIRE NUCLEAR SITE
SUMMARY
OF MAJOR RADIONUCLIDE COMPOSITION 2006 Type of waste Nuclide % Abundance 11
,. Waste from liquid syPwdexRe (o No shipments in 2006 A. Dewatered Powdex Resin (brokered)
B. Dewatered Powdex Resin No shipments in 2006 C. Dewatered Bead Resin (brokered) No shipments in 2006 D. Dewatered Bead Resin No shipments in 2006 E. Dewatered Radwaste System Resin (brokered)
Nuclide %Abundance 2006-32 Co-60 2.19 Cs-137 19.30 Fe-55 5.15 Ni-63 73.26 Sb-1 25 0.01 Mn-54 0.08 Co-57 A .vA-I v
F. Dewatered Primary Bead Resin (brokered)
Nuclide %Abundance 2006-01 Mn-54 0.41 Co-57 0.04 Co-60 17.80 Cs-1 37 6.93 Cs-1 34 0.09 Ni-63 56.34 Fe-55 18.02 Sb-125 0.22 H-3 0.06 Sr-90 0.09 I
Nuclide %Abundance 2006-05 Mn-54 1.69 Co-57 0.27 Co-58 0.39 Co-60 17.41 Cs-137 6.19 Cs-134 1.16 Ni-63 55.12 Fe-55 17.54 Zn-65 0.08 H-3 0.05 Sr-90 0.08 G. Dewatered Mechanical Filter Media No shipments in 2006 H. Dewatered Mechanical Filter Media No shipments in 2006 (brokered)
I. Solidified Waste No shipments in 2006 A. Dry Active Waste (compacted) Compaction no longer performed on-site.
Dry Active Waste (non-compacted) 2006-14 DAW Nuclide %Abundance Co-57 0.06 Mn-54 1.15 Co-58 6.85 Co-60 24.04 Cs-137 1.28 Fe-55 44.47 Ni-63 17.37 C-14 2.28 Zr-95 0.43 Sb-95 0.77 Sr-90 0.18 Nb-95 1.12 Dry Activ4 Waste (brokered/compacted) No shipments in 2006 2
Dry Active Waste (brokered/non-com pacted) 2006-02 DAW Nuclide %Abundance Cr-51 3.16 Mn-54 0.58 Co-58 16.57 Co-60 3.07 Cs-137 0.63 Fe-55 12.68 Ni-63 6.09 H-3 55.73 Zr-95 0.63 Nb-95 0.85 2006-06 DAW Nuclide %Abundance Co-57 0.06 Mn-54 1.14 Co-58 6.28 Co-60 24.30 Cs-137 1.29 Fe-55 44.75 Ni-63 17.58 C-14 2.32 Zr-95 0.39 Sb-1 25 0.77 Sr-90 0.18 Nb-95 0.93 2006-07 DAW Nuclide %Abundance Co-57 0.06 Mn-54 1.16 Co-58 7.33 Co-60 23.79 Cs-1 37 1.27 Fe-55 44.29 Ni-63 17.15 C-1 4 2.26 Zr-95 0.46 Sb-1 25 0.76 Sr-90 0.18 Nb-95 1.29 3
2006-09 DAW Nuclide %Abundance Co-57 0.06 Mn-54 1.15 Co-58 7.15 Co-60 23.88 Cs-1 37 1.27 Ni-63 17.29 Fe-55 44.30 Zr-95 0.45 C-14 2.27 Sb-1 25 0.76 Sr-90 0.18 Nb-95 1.23 2006-11 DAW Nuclide %Abundance Co-57 0.06 Mn-54 1.16 Co-58 7.21 Co-60 23.92 Cs-1 37 1.27 Fe-55 44.30 Ni-63 17.18 C-1 4 2.26 Zr-95 0.45 Sb-125 0.76 Sr-90 0.18 Nb-95 1.25 2006-16 DAW Nuclide %Abundance Co-57 0.06 Mn-54 1.16 Co-58 7.33 Co-60 23.88 Cs-1 37 1.27 Fe-55 44.23 Ni-63 17.12 C-1 4 2.26 Zr-95 0.46 Sb-125 0.76 Sr-90 0.18 Nb-95 1.29 4
2006-17 DAW Nuclide %Abundance Co-57 0.06 Mn-54 1.15 Co-58 6.84 Co-60 24.07 Cs-1 37 1.27 Fe-55 44.48 Ni-63 17.34 C-14 2.29 Zr-95 0.43 Sb-1 25 0.76 Sr-90 0.18 Nb-95 1.12 2006-20 DAW Nuclide %Abundance Co-57 0.06 Mn-54 1.15 Co-58 6.79 Co-60 24.05 Cs-137 1.28 Fe-55 44.51 Ni-63 17.38 C-i14 2.30 Zr-95 0.42 Sb-125 0.77 Sr-90 0.18 Nb-95 1.10 2006-23 DAW Nuclide %Abundance Co-57 0.06 Mn-54 1.16 Co-58 7.26 Co-60 23.85 Cs-137 1.27 Fe-55 44.27 Ni-63 17.19 C-1 4 2.26 Zr-95 0.46 Sb-125 0.76 sr-90 0.18 Nb-95 1.27 5
2006-27 DAW Nuclide %Abundance Co-57 0.06 Mn-54 1.15 Co-58 7.07 Co-60 23.96 Cs-1 37 1.27 Fe-55 44.33 Ni-63 17.29 C-1 4 2.28 Zr-95 0.44 Sb-125 0.76 Sr-90 0.18 Nb-95 1.20 2006-31 DAW Nuclide %Abundance Co-57 0.06 Mn-54 1.14 Co-58 6.12 Co-60 23.37 Cs-137 1.30 Fe-55 44.81 Ni-63 17.67 C-14 2.32 Zr-95 0.38 Sb-125 0.77 Sr-90 0.18 Nb-95 0.88 B. Sealed Sources No shipments in 2006 C. Sealed Sources/Smoke Detectors No shipments in 2006 D. Irradiated Components No shipments in 2006 6
REPORT PERIOD McGUIRE NUCLEAR STATION Attachment 1 JANUARY - DECEMBER 2006 SOLID RADIOACTIVE WASTE SHIPPED TO DISPOSAL FACILITIES TYPES OF WASTES SHIPPED Number of Number of Container Disposal Volume Waste Total Waste from Liquid Systems Shipments Containers Type ft 3 m3 Class Curies (A) dewatered powdex'resin (brokered) none (B) dewatered powdex resin none (C) dewatered bead resin (brokered) none (D) dewatered bead resin none (E) dewatered radwaste system resin 1 1 HIC 195 5.52 B 1.24E+01 (F) dewatered primary bead resin 2 2 HIC 240.6 6.86 B 1.71 E+02 (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) DBP 1350 38.23 A/U 5.00E-03 dry active waste (brokered/compacted) 11 dry active waste (brokered/non-compacted) 50 DBP 4596.35 130.17 A/U 1.286E+00 (B) sealed sources/smoke detectors none (C) sealed sources none (D) irradiated components none Totals 15 54 6381.95 180.78 1.847E+02 3/19/2007
Attachment 3 Unplanned Offsite Releases
McGUIRE NUCLEAR STATION UNPLANNED RELEASES (January 1, 2006 through December 31, 2006)
There was one unplanned gaseous radioactive release to the environment in 2006. There were no unplanned liquid radioactive effluent releases to the environment in 2006.
Febuay3, 2006 Memorandum To: Annual Radioactive Effluent Release Report CC: Steve Mooneyhan, 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 2 Vent Reference PIP M-06-0404 Event Summary: See referenced PIP for details.
On January 28, 2006 12:20 to 14:30 hours, 7.19E-2 curies of fission and activation gas (noble gas) was released to the unit 2 vent. The source of the noble gas was associated with an unplanned release of -250 gallons of primary system water. The water was contained in the floor drain system and collected in the floor drain tank (FDT). No normally clean areas were contaminated because of this spill.
The leak was believed to have emanated from a component associated with the normal operation of aligning the 2A NV mixed bed demineralizer for B10 saturation. A portion of normal letdown is diverted to the recycle holdup tank (RHT). This NV letdown divert to the (RHT) involves valves and components of the Boron Recycle (NB) system.
Sequence of events:
On 1/28/06 11:36 hrs. 2A mixed bed demin was aligned for boron saturation.
12:20 Counts per minute (cpm) above background were seen in the unit vent.
12:40 Trip 2 on 1EMF 41 (auxiliary building ventilation monitor) point 11 (NB components area).
Highest cpm seen (25 cpm above bkg) on unit vent gas monitor (2EMF 36L).
Auxiliary building ventilation automatically placed in filtered mode.
12:46 Mixed bed 2 A removed from service.
13:15 1EMF 41 trip 2 cleared.
13:40 1EMF 41 trip 1 cleared.
14:30 2EMF36L (unit vent gas monitor) returned to normal bkg.
Monitoring 1 EMF 41 (auxiliary building ventilation monitor) and 2EMF 36L (Unit Vent gas monitor) indicated elevated counts of 270 cpm above bkg on 1EMF41 and counts ranging up to 25 cpm above background on 2EMF 36L for approximately 130 minutes. No personnel were exposed to the undiluted release.
SRPMP 8-2 "Investigation of Unusual Radiological Occurrences" was completed to document the Unplanned Release. See attached completed procedure.
The total Noble gas activity released was reported on (GWR) Gaseous Waste Release # 2006007.
The unplanned activity was evaluated against off site dose limits using current ODCM methodology on the attached spreadsheet.
Safety Significance:
The health and safety of the public were not compromised by this event. The total activity released was insignificant. Calculated dose and doserate to the Total Body, Skin, Gamma Air, and Beta Air were all less than two tenths of one percent (<0.2%) of the limits specified by Selected Licensee Commitments and Code of Federal Regulations.
W.C. Spencer Y Correll RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station
Attachment 4 Fuel Cycle Calculation
McGuire Nuclear Station 2006 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 40CFR190 limits as shown by the following summary:
I. 2006 McGuire 40CFR190 Effluent Dose Summary The 40CFR190 effluent dose analysis to the maximum exposed individual from liquid and gas releases includes the dose from noble gases (i.e., total body and skin).
Maximum Total Body Dose = 6.61E-01 mrem Maximum Location: 0.5 Mile, East-Northeast Sector Critical Age: Adult Gas non-NG Contribution: 59%
Gas NG Contribution: 3%
Liquid Contribution: 38%
Maximum Organ (other than TB) Dose = 6.84E-01 mremn Maximum Location: 0.5 Mile, East-Northeast Sector Critical Age: Child Critical Organ: Liver Gas Contribution: 51%
Liquid Contribution: 49%
II. 2006 McGuire 40CFR190 ISFSI Dose Summary Direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at McGuire have been calculated and documented in the "McGuire Nuclear Site 10CFR72.212 Written Evaluations" report. The maximum dose rate to the nearest resident from the McGuire ISFSI is conservatively calculated to be 9.92 mrem/year.
The attached excerpt from the "McGuire Nuclear Site 10CFR72.212 Written Evaluations" report is provided to document the method used to calculate the McGuire ISFSI 9.92 mrem/year dose estimate.
C. 10CFR72.212(b)(2)(iii)- Requirements of 72.104 Criterion
"...therequirementsof 72.104 have been met."
Evaluation Historical TLD Monitoring The following table documents the actual radiological dose in reins at the owner controlled fence on top of the berm overlooking the ISFSI (Lotus Notes from Mary J. Foreman to Norman T. Simms, dated June 15, 2004). Actual dose to the public from the ISFSI is only available at this owner controlled fence. Therefore, a normalization factor. is derived by comparing the actual dose to the calculated dose. The normalization factor is applied to the calculated values for the intake waterway and the exclusion area boundary to approximate the actual ,dose values from the ISFSI in those areas around the plant.
Location# 3Q'02 4Q'02 IQ'03 2Q'03 3Q'03 4Q'03 1Q'04 76 0.032 0.036 0.042 0.055 0.056 0.043 0.058 77 0.020 0.028 0.028 0.039 0.036 0.035 0.043
- of Days 91 92 91 92 98 83 98 Location # 76 indicates the greatest dose of 0.058 reins during a 98 day period in the first quarter of 2004. This is equivalent to 0.0247 mrem per hour for a total population of ten TN-32 casks. The calculated dose for this same location using conservative computer models is 0.744 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. (A recent Lotus Notes from Mary J. Foreman to N.T. Simms, dated April 24, 2006 indicates that the dose at Location # 76 is 0.044 reins for a period of 89 days during the 1Q '06. Ten TN-32 casks and nine NAC UMS casks were on the ISFSI pad, but for simplicity and conservatism the IQ '04 value will continue to be used. Please note that the normalization factor will only be used for the TN-32 casks).
ISFSI Controlled Area Boundary (ISFSI and Site Operations)
It is stipulated in 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 3 For McGuire, compliance with this regulation will also a'ssure compliance with 40 CFR Part 190.
McGuire Nuclear Site (NAC UMS)
IOCFR72.212 Written Evaluations, Rev. 2
planned releases to the environment, direct radiation from ISFSI operations, and any other radiation from uranium fuel cycle operations within the region.
The combined and skyshine dose rates at various distances for one cask stored with 7 year cooled fuel (inner) and 10 year cooled fuel (outer) were analyzed by Transnuclear. 4 The best-fit empirical equation for skyshine dose rate as a function of distance is y = 0.0156e-00112x for gammas and y = 0.0274e-°o.12%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-21688 for gammas and y =
166.95x-2°696 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 'andneutrons.
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 9.9 mrem and the dose due to McGuire power generation is 3.
mrem per year for a total dose of 12.9 mrem per year. Therefore, the ISFSI controlled area boundary radiation limits are met for the McGuire ISFSI.
The selection of an individual on the LAB south of the dam is totally arbitrary in order to choose the closest point on the LAB to the ISFSI. This location is owned by Duke Energy and no member of the public would be permitted to occupy this location continuously. The regulations speak of the "real individual" when
/
4 TN Cale 1083-20, "TN-32 Cask for Duke Power, TN-32 MCMP Models for Determining Off-Site Doses," Rev. 0, dated 4/06/2000.
5 NAC Calc 12418-5001, "Skyshine Evaluation of McGuire ISFSI," Rev.0, dated 11/26/03.
McGuire Nuclear Site (NAC UMS) 10CFR72.212 Written Evaluations, Rev. 2
addressing radiation exposure. Factually, this "real individual" is located beyond the EAB on the eastern side of the plant.
General Environment from Total Nuclear Fuel Cycle (ISFSI and Site Operations) 40CFR190 applies to radiation doses received by members of the public in the general environment and to radioactive materials introduced to the general environment as the result of all operations which are part of the Nuclear Fuel Cycle. The McGuire ISFSI is located in the immediate proximity of McGuire Nuclear Station and as such compliance with 40CFR190 must be demonstrated.
The McGuire UFSAR (Section 2.1.2.2, "Boundaries for Establishing Effluent Release Limits") and Selected Licensee Commitments Manual (Section 16.11, "Radiological Effluents Control") defines "unrestricted areas" to be coextensive with the EAB and beyond. Likewise, "general environment" is defined to be coextensive with the EAB and beyond.
It is stipulated in 40CFR 190.10(a) that the annual dose equivalent shall not exceed 25 mrems to the whole body, 75 mrems to the thyroid, and 25 mrems to any other organ of any member of the public as a result of exposures to planned discharges of radioactive materials, radon and its daughters excepted, to the general environment from uranium fuel cycle operations and to radiation from these operations. As illustrated previously in showing compliance with 10CFR 72.104(a), the calculated dose at the EAB is 12.9 mrem per year, within the 25 mrem allowable limit. The summation of the doses from the ISFSI and McGuire power generation to the General Environment are well within the allowable limits.
Dose Inside ISFSI Controlled Area (ISFSI Operations)
Regulations permit the controlled area to be traversed by public roads and waterways as cited in IOCFR72.106(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 6 10CFR20.1301(b). See also I0CFR20.1301 (a)(2).
McGuire Nuclear Site (NAC UMS)
IOCFR72.212 Written Evaluations, Rev. 2
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 0.28 mrem per hour (direct radiation and skyshine), within the 2 mrem per hour allowable limit. Finally, the annual dose resulting from ISFSI to the public inside the McGuire EAB in the vicinity of the intake structure, using a residence time of 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />, is determined to be 5.79 mrem (skyshine only -
earthen berm acts as a shield), within the 100 mrem allowable limit.
These calculations show that the McGuire ISFSI containing ten TN-32A casks and 24 NAC UMS casks meets the radiological requirements of 10CFR72.104, 10CFR20.1301 and 40CFR 190.
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 from the TN-32 casks for those two areas.
Top of berm at owner controlled fence - 70 meters from ISFSI TN-32A casks Using the previous equations for total dose and a distance of 70 meters the total dose rate (gammas and neutrons) for one cask is 7.443 E-0 2 mremrhr.
McGuire Nuclear Site (NAC UMS) 10CFR72.212 Written Evaluations, Rev. 2
(10) Casks X 7.443 E-02 mrem/hr = 0.744 mrem per hour Actual measured dose rate for the first ten casks stored in the ISFSI = 0.0247 mrem per hour NAC - UMS Casks Using the calculated value from the NAC evaluation located in Table 6-6, "2x6 Cask Array Combined Dose Rates", the total dose rate (gammas and neutrons) at a distance of 70 meters is 1125.6 mrem/yr. This equates to :
(1125.6 mrem/yr) / (8760 hours0.101 days <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 (2X) 2X6 Array NAC UMS Casks (calculated) 0.0247 mrem per hr + 2(0.128) mrem per hr = 0.2807 mrem per hr Waterway beyond security buoys on other side of berm from ISFSI - 135 meters from ISFSI TN-32A Casks Using the previous equations for skyshine and a distance of 135 meters the skyshine dose (gammas and neutrons) for one cask is 8.24 E-°' mrem/hr.
(10) Casks X 8.24 E-0 3 mrem/hr X 150 hrs (residence time/yr) = 12.36 mrem per year Normalized actual dose = 0.0332 X 12.36 mrem/yr = 0.410 mrem per year Total expected dose for ten TN-32A casks (actual) 0.4 10 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)
IOCFR72.212 Written Evaluations, Rev. 2
Total Expected Dose at Waterway on Other Side of Berm Ten TN-32A Casks (actual) plus (2X) 2X6 Array NAC UMS Casks (calculated) 0.4 10 mrem per year + 2(2.69) mrem per year = 5.79 mrem per year Individual Sited on Exclusion Area Boundary Below Dam - 425 meters from ISFSI TN-32A Casks Using the previous equations for skyshine and a distance of 425 meters the skyshine dose (gammas and neutrons) for one cask is 2.48 E-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 I 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 (2X) 2X6 Array NAC UMS Casks (calculated) 0.720 mrem per year + 2(4.6) mrem per year = 9.92 mrem per year IX. 10CFR72.212(b)(3)- Evaluation of Reactor Site Parameters Criterion "Review the Safety Analysis Report (SAR) referenced in the Certificate of Compliance and the related NRC Safety Evaluation Report, prior to use of the general license, to determine whether or not the reactor site parameters, including analyses of earthquake intensity and tornado missiles, are enveloped by McGuire Nuclear Site (NAC UMS) 10CFR72.212 Written Evaluations, Rev. 2
McGUIRE NUCLEAR STATION 2006 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 (2006) 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 11.00-1 1.25-I 1.50-I 2.00-1 3.00-1 4.00-1 5.00-f 6.00-1 8.00-1>9.99 I I 1.24 f 1.49 f 1.99 1 2.99 1 3.99 I 4.99 I 5.99 I 7.99 I 9.99 f M/S ITOTAL I I- - -- - -- - -- - -- --------------
-- - -- - --+- - -----
--- I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. NO.
- +--+-..-..-+.....-+....+-...---..---...-- ------- +-- +....---- ...------ .- I SECTOR I I I I I I I I I I F I I I I I I I I I f-N- f .1 .f 4 f .I -1 if .f s5 sf 131 1 --
- --------- - -- - -- - - - - -- - - --- - - -- - -- - - -- - - - -- -- - - -- - -- -- - - -- - -- - - -- - - - -- - -- - -- - - - -- - - - .- I.
I- E- . . 21 1f .1 11 .f 1i 31 1 91 f-NE- f .f 21 11 .1 .1 .f .I 31 f-E- f .f ff .f .f .f .f11
-....---.....- - +--- - +.....--- -.....---.....---.....---.....---------
+-.....-+-.....-
-ssW- f . .f if f if f1 . 41
- +- +- -- +. .. + -.. .+-.. .. + -.. .+ -.. .+ -.. .+ -.. .+ -.. .+ -...
f-Sw- f .f .f 11 21 .f sf 21 21 .f .f 121 1+--
- --- --------- - - -- - - - - -- - - -- - - -- - - -- - -- - - - -- - - -- -- - -- -- - - -- - - -- - -- -- - -- - - -- -- - - - -- - - - .- I.
f-WSW- f .1 .f .f .f .1 .f -I .i 11 f-NEW- f .f .f .f .f .f .f - .1 2 21 TOTAL f 11 2f 61 Sf 11 7f sf 3f 8f 8f 461
McGuire NUCLEAR STN. METEOROLOGY (2006) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY B WIND SPEED CLASS I I
I I 11.00-I 1 .25-I 1.50-I 2.00-I 3.00-I 4.00-I 5.00-I 6.00-I 8.00-1>9.99 1 1 1.24 I 1.49 1 1.99 1 2.99 1 3.99 1 4.99 1 5.99 1 7.99 I 9.99 I M/S ITOTAL I-- +----... +......--------+----..-+. .------
+--+- -+ --- +-.+- I I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I I----------------------------------------------- + - - +- - -+- --------- +-- .+- . I SECTOR I I I I I I- ---------------------- I I I I I I I II f-N- 1 .1 " '11 F1 11 11 5 41 .1 121 1 ---------------------------------------------- +-+--+--+-+-+-----------+----+--
I-NNE- 1 .1 I 51 31 21 21 F1 71 31 11 241
. +-+--+--+-+-+---- -------- +--- +--
F-NE- I *1 21 41 51 s5 31 1' .1 11 *1 211
---- ---7 --------------------------- +---+.-----+- I
-ENE- I 1 *1 .1 101 61 11 1 .1 1 .I 171 I .....----....----....----..------------------------- - --- +----------+- -+-r---
I-E- 1 .1 1 71 31 11 1 . 1 .*I 12 I --....-- --....-- .....----....--------------------------- +..-------- + -- - --+ I
-ESE- 21 31 31 .1 .1 .I *1 1 81 I -- - - - - - - - - - - - -- - - - - - - ---------------------------------------- --------- +-- - --I I-SE- 1 *1 .1 21 21 11 .1 .1 .I *F 1 5 I------------------------------------------+-+--+---+-+ +-+- +-------- +I+-
I-SSE- I .l *1 .1 11 1 .I .1 1 .1 1 21 I------------------------------------------+-+---+- +-+-+-+- +-------- +I+-
I-S- I *1 1 1 61 11 .1II 1 .1 1 8j I--------------------------------------+-+--+---+-+ +- +- +----------+-+-
I-SSW- I .I *1 31 41 61 51 1I .1 1 I 191 I-------------------------------------------- +--+-+ - - -+- +--+-----------+- +------
I-SW- I .1 1 .1 21 101 221 61 61 .1 I 461 I---------------------------------------------+--+-+--+--+-+-+ +-+-. ----- +--------- -
I-WSW- I 1 *1 21 61 ill 191 s8 41 1 1 51 1----------------------------------+--+-+--+--+-+- +- +---------- I+-+-.
F-w- I *I .* 21 41 'F .*
- 1 1 I7 1----------------------------------------------++ ++
+----+- -+ ---- I+-+-
F-WNW- 1 .1 .1 21 41 .1 1F1 .F .1 71 1 .....----....----....----....--
+- ++ ---- --------------------------
+ - + - + - + - +.- I
- - 11 .1 21 21 .1 *1 31 1 . 81 I --- ------------- --- +- --- ---
--- --------------------------- + - ---- I
-N - if .1 1 31 1l .1 *1 'I *1 .1 61 1 -- -- -- -- -- ------ -- -- -- -- -- -- -- -- -----------------------------..- +-.. . +-- -. - ---
TOTAL I 21 31 241 631 531 531 19I 261 9j 11 253j
McGuire NUCLEAR STN. METEOROLOGY (2006) 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-] 4.00-1 5.00-1 6.00-] 8.00-1>9.99 I 1 0.99 1 1.24 1 1.49 1 1.99 1 2.99 1 3.99 I 4.99 1 5.99 I 7.99 1 9.99 I M/S ITOTAL I I - ---+-- - -+-..... +...-..-+-.....+-.....+-.....-+ -...- +.---+-.-.+..--+-.- . I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO.
I------------------------------------------------------------------------------- +- -- + -- +. - -+ +
SECTOR I I I I I I I I I I I I I ---------------------- I I I I I I I I I I I I
-N- I *1 11 41 121 15i 1 41 41 171 81 *1 651 I- - - - - - - - - - - - - - -- - -- - -- - -- - -- - ------------------------------------------- +-I
]-NNE- I .1 11 21 241 211 21! 11i 131 311 161 *1 1401 I ---------------- --- --- --- --- --- ----------------------------------
+- + + ---- - I
]-NE- I .1 .1 31 131 211 231 61 51 1I 31 751 I --------------------------------------------------
+-- ++ - +-+-++ - + - + - .+.- I
-ENE- 1 *1 .1 1] 71 151 l 311 "1I 1 371 II-E-1 1I 11 11 91 71 "11
'1 I+
1 18 1 II-ESE-
- - - - - - - - - - - - - - - --. - -- .1- -- -
11 -- - --
21 - -----------------------------------
81 41++ -
.1I1+ +
.1II . 151 I- - - - - - - - - - - - -- -- - -- - -- - -- - -- - -- - -----------------------------------
++ - + + - - I
-SE- 1 .1 .1 .1 2] 4] 71 .1 1] .1 .1 .1 141 II-SSE-
- - - - - - - - - - - - -- - -- . - -- 11- -- -
.1-- - ----------------------------------
31++ -
.1I1+ +
.1I I . 101 I----------------- --- --- --- --- --- --------------------------------------
- I
-s- 1 .1 11 11 51 7] 41 .1 .1 .1 .1 .1 181 I - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - ------ 7-------------------------------+ - + + -I
-ssW- 1 .1 .1 1[ 21 13] 131 5s 21 1] .1 *] 371 I- - - - - - - - - - - - - - -- - -- - - - - -- - -- - ------------------------------------------- +-I
-SW- 1 .1 .1 .1 51 31] 411 28] 131 ill 21 .1 1311 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------------------------- --- ---- ---- - -
]-WSW- 1 *1 .1 21 41 14] 421 21] ill 10i .1 .1 1041 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------------------------- --- ---- ---- - -
-w- 21 -1 51 1] 81 6] 31 21 21 L1 451 1 - - - - - - - - - - - - - - -- - -- - -- - -- - -- -----------------------
]-WNW- 1 1] 11 21 41 6] 61 51 21 21 11 .1 301 I -------------------------------------------------------- --------------------------- +.--- -- I
-NW- 1 i1 "1 11 41 ]8 71 11 21 31 51 .1 321 1I - - - - - - - - - - - - - - -- -- - - - - - - - - - - - - - - ------------------------------------- + ---- - I
-iw- 11 11 11 91 31 2] 11 51 131 81 1] 45]
TOTA1
-------------------- ------ I ITOTAL 1 31 8] 20] 101] 196] 199] 91] 61] 9i] 451 11 816]
McGuire NUCLEAR STN..METEOROLOGY (2006) 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 I 1 0.45-i 0.75-I 1.00-I 1.25-I 1.50-1 2.00-1 3.00-1 4.00-1 s.0o-1 6.00-1 8.00-1>9.99 1 1 0.74 1 0.99 I 1.24 1 1.49 I 1.99 I 2.99 I 3.99 I 4.99 I 5.99 I 7.99 I 9.99 I M/S ITOTAL I.--- +---- +--+-- +-- ------ ....
+--- +..-...-+.-....-+..-...-+..--+--- - - - I+
I NO. I NO. I NO. j NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. NO. I NO. I I --------------------------
+--------------------------
+ -- + -- --------.-----------
+- + - + + - + - + - +- -+-+ - I SECTOR I I I I I I I I I I I I I
I I I I I I I I I I I I I-N- I .1 21 121 201 301 931 521 671 551 481 71 *I 3861
.. .. + . .. + -.. .+. . .+.+--- .. - + - + -.. .+ -.. .+ -.. .+ -.. .+ -.. .+ -...
-N E- 1 1 .1 5I 181 591 1071 911 751 491 511 151 51 4751 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------- + -- + ------ -- ----- I I-NE- 1 1 .1 21 8j 381 1551 1941 1351 621 491 14j 11 6581 1--------------------------------------------------------- + + +------
--- ---- +--
-- -- +-I I
-ENE- 1 .1 11 41 91 361 1121 991 471 91 11 .1 .1 318!
1 - - - - - - - - - - - - - - -- - -- - -- - -- - -- - -- ---------------------------
--- ---- - -- - -- I 1 .E. .. 21 21
.77 101 231 591 181 21 . 1 . .1 1931 1 - - - - - - - - - - - - - - -- - -- - -- - -- - -- - -- - -- ---------------------------
+ -- --- -
+-- - -- I
-ESE- I .1 11 31 5I 271 631 361 51 1i .1 .1 *1 1411 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------------------------------- - I I-SE- 1 I .1 21 91 221 741 31I 91 -I .1 .1 *I 1471 1 -- -- -- -- -- - -- -- -- +----+--
_--- +-+-++ - ++ -. .+. .- I I-SSE- I .1 .1 11 9! 251 461 181 81 41 11 .1 1 1121 1 - - - - - - - - - - - - - - -- - -- - -- - -- - -- - -- ---------------------------
--- ---- - -- - -- I IS 1 1 21 21 101 311 531 181 151 31 71 21 I1 1431 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------------------------------- - I I-SSW- I .1 .1 41 7I 251 971 1041 321 171 5I 11 *I 2921 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------------------------------- - I I-Sw- I *1 *1 31 61 271 1421 2001 1231 621 371 41 *1 6041 I -- ---- - - -- -- - --- --- --- - -- - -- --- --- -------------------------------------- + ---- - I j-WSW- I .1 .1 71 91 371 1071 811 541 341 251 ill 11 3661 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------------------------------------- - I I-W- I I
..1 1 61 121 241 521 39I 331 191 12j 21 11 2041 I-WNW- I 1i 41 6l 91 221 31l 36l 32l 24l 191 5I .I 1891 1 -....--- -....--- .....---
-....--- -....--- -....-- --------------------------------------- ++ - + I+-
I-NW- I .1 11 81 4I 19l 34I 481 32l 231 341 18J 61 227I 1 - - - - - - - - - - - - - - -- - -- - -- - -- - -- - -- --------------------------
+ -- --- +---- ---- - -
I-NNW- I .1 21 71 5I 20l 371 401 461 391 44 211 41 265I 1------ ------ ------ ------ ------ ------ ------ ---- -------------- ------ ---- - I+
TOTAL I ii 19l 741 1501 46sF 12621 11641 7311 4031 3331 1001 181 47201
McGuire NUCLEAR STN. METEOROLOGY (2006) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY E WIND SPEED CLASS I I
I I 1 0.45-i 0.75-I 1.00-I 1.25-I 1.50-I 2.00-I 3.00o - 4.00-I 5.00-I 6.00-I 8.00-I I 1 0.74 1 0.99 I 1.24 I 1.49 1 1.99 1 2.99 I 3.99 14.99 I 5.99 I 7.99 I 9.99 ITOTAL I-------- +---- +-.....-+.- -- . . . +-
.------- -+--- +-- --- -------+---- I I NO. I NO. I NO. I NO. I NO. I NO. I NO. [ NO. I NO. I NO. I NO. NO.
I---------------------------------------------------------- - -------------- -----
+ - -I ISECTOR I I I I I I I I I I I ---------------------- I I I I I-N- 1 -1 21 11 5l 61 171 21 21 11 .1 1 361 I- - - - - - - - - - - - - - -- -- - - - - - ----------- - - - - - - - - - ---------------------------- --- - I I-NNE- 1 1 I1 21 41 131 141 sj 31 1 . I 421 I-------------------------------------------------------------++ - +-+- + - + - + - + +-. + .- I I-NE- I 11 .1 21 41 81 81 1j .1 .1 *1 241 I- - - - - - - - - - - - - - -- -- - - - - - -------- - - - - - - - - - ---------------------------- ------- I
-ENE- I .1 21 41 11 15I 81 ii '1 .1 I I 311 l-E- I 11 31 3I 61 101 71 31 I .1 I 331 I - - - - - - - - - - - - - - -- -- - - - - - -------- - - - - - - - - - ---------------------------- ------- I
-ESE- 1 1 1i 41 11 91 161 21 '1 .1 " 1 34 I- - - - - - - - - - - - - - -- - - - - - - - - - ----------------------------
-- - - - - - ----------- --- - I I-SE- I .1 21 61 91 291 561 6j .1 *1 .1 *1 1081 I- - - - - - - - - - - - - - -- -- - - - - - -------- - - - - - - - - - ---------------------------- ------- I I-SSE- I 11 s5 7j 171 281 331 I .I I .1 I 961 I- - - - - - - - - - - - - - -- -- - - - - - -------- - - - - - - - - - ---------------------------- ------- I 1-s- 31 41 101 141 411 871 51 .*1 *1 1 *1 1641 I ---------------- --- --- ---------------------------------------------------- - I I-SSW- I 41 61 iij 141 421 1831 34 91 ii -1 .1 3041 II-sw-
- - -------- ------- I I .1 51 81 151 401 1451 691 191 21 *1 .1 3031 I - -....-- .....-- --- ----------------------------------------------------
+-+- + - + - + + - + - + - + - I l-WSW- I .1 71 121 281 54 761 231 5I 61 .I 1 2111 I - - - - - - - - - - - - - - -- - - - - - - - - - - - - - ---------------------------------------------- I l-W- I 1i 41 ill 121 251 221 121 . 61 21 .1 .1 951 I------------------------------------------------------------.------------------------ -+ - I I-WNW- I .1 SI 21 91 261 251 191 61 2L 21 *1 961 I---------------------------------------------------------------------------------++ + - +.-. I I-NW- I 11 11 .1 31 91 191 161 121 81 .1 11 701 I - - - - - - - - - - - - - - -- -- - - - - - -------- - - - - - - - - - ---------------------------- ------- I I-NNW- I 1I 21 61 101 161 5I 21 21 11 *1 461 I -------------------------- +-+- ------ +- -----
- ---+-..-...+....-.-+-- I TOTAL 1 141 501 841 1481 3651 7321 2081 641 241 31 11 16931
McGuire NUCLEAR STN. METEOROLOGY (2006) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY E WIND SPEED CLASS I I
I I 1 0.45-1 0.75-I 1.00-I 1.25-I 1.so-1 2.00-I 3.00-I 4.00-I 5.0071 6.00-I 8.00-I I 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 I 9.99 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 NO.
I .....----....----....----....---
-....----....----....---- -----------------------.-- + I SECTOR I I I I I I I I I I I ---------------------- I I I I I I I I I I-N- I .1 21 11 sI 61 171 21 21 11 *1 1 361 1I - --- - - - - - - - - - - -- - -- --- - -- - -- - ----------------------------------------- +--- - I
-NNE- .1 11 21 41 131 141 3 . *1 421 I-------------------------------------------------------+--+-+--+--+-+-+-+-+ +.-- I+
I-NE- I I .I 21 41 81 81 1i .1 .1 .1 .1 241 I- ---- -- --- -- -- -- --- --- --- --- ------------------------------------------ +--- - I
-ENE- I .1 21 41 'I 151 81 1I1 .1 .1 311 I+-.. .. + -.. .+ .
-. .+ .
-. .+-.. .. + -.. .+ -.. .+ -.. .+ -.. .+- +- - +-+ . .
I-E-I ---------------- I --------------------------------------------
31 21 -------------- 1 61 101 5 1 31 1 *1 -.1 I 1 331 I-ESE- I 11 1i 41 11 91 161 21 1 .1 *1 1 341 1I-------------------------------------------------------------------+---- ---- I I-SE- 1 21 6i 91 291 s6 871 6 1 .1 .1 1081 I ------------------------------------------------------------ --------------- I I-SSE- I 41 61 7l 171 21 331 51 I1 1 1 I 961 I ------------------------------------------------------------
I-SW-
I 1 31 41 01 141 401 871 61 '1 21 1 1 1641 I-----------------------------------
I --------------------------------------------------------------------------- ------- +-.....+-.....+-....+-. -+-. -+-. -+-. -+.-.. +-I I l-sSW- 1 41 61 11 141 424 1831 341 91 11 1 *I 3041 I-sW I 1 151 81 401 1421 691 191 21 .1 .1 303 I
I ------------------------------------------------------------
- - - - - -+-- ---------------
+- + - + - +--+ + + + - II+-
I-WW- I .1 71 121 281 41 761 231 5 66 211 *1 91 I------------------------------------------------------------------------------- -- +- I I-w- I I 41 i1 121 25 1 221 12 61 21 1 j 91
-W-NW- .1 l5 21 91 261 251 191 61 21 211 961 II-N--------------------------------------------------------------------------
- . 1 11 1I . 31 91 191 161 121 81 .1 I 1 701 I-NNW- I i 21 i1 61 101 161 sI 21 21 1I .I 461 I ------------------------ +-+---- * -- +- ------
- ---+--- .... +..-...-+- II TOTAL I 141 S01 841 1481 3651 7321 2081 641 241 31 11 16931
McGuire NUCLEAR STN. METEOROLOGY (2006) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS PASQUILL STABILITY F WIND SPEED CLASS I
I I.
1 0.45-1 0.75-1 1.00-1 1.25-1 1.50-1 2.00-1 3.00-1 4.00-1 1 I 0.74 I 0.99 1 1.24 I 1.49 I 1.99 I 2.99 I 3.99 I 4.99 ITOTAL I-- -+ --------------------------------
+- -+- -+- + - +- +.--- I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I I--------------------------------*--+-+-+-+ ----------- ++-- I SECTOR I I I I I I I I II-N- ---------------------- I1 21I 21I 41I 31I I
.1 .I 21I .1I 131 I----------------- -- -------------------------------
+-+- + - + + - I I-N E- I .1 *l 31 .1 31 .1 'i I 71 I ---------------- --- --- ------------------------------------- + - - I I-NE- I 11 21 .1 .1 1I .1 .1 41 I- - - - - - - - - - - - - - -- - -- - ----------------------------------------- + -
-ENE- I I 11 21
- 21 .1 I 2I I-E- I
21 *1 21 .1 21 .1+ - .1- I I1 SI I-ESE-I I
21 .1 31 .1 + - -I - I I i1 2s1 1
+- I I------------------------------------------------+
I-SE- 1 31 31 71 - + -
311 + - + -
31+ -
11 *1 201 l-SSE- I 31 61 61 61 91 81 .1 I 381 I------------------------------------------------- +I-+--+ - + - + - + -
I-S- I 31 161 141 7I 441 35 11 I 1201 I- - - - - - - - - - - - -- - - - - - - - -+- - - -+ ---------------------------- + ----- I I-SSW- I 31 191 231 281 521 351 31 I 1631 I ---------------- --- --- ------------------------------------- + - - I I-SW- I 5I 121 141 181 361 47 51
- 1371 I ------------------------------------- + - + - + - + - --- ---- +----+-..-.I
-wsw- I 31 121 61 221 311 231 41 21 1031 I ---------------- --- --- ------------------------------------- + - - I l-W- I 11 81 61 5l 101 61 21 *I 381 I --- - -- ---------- --- - -- ------------------------------------- + - - I l-WNW- I 41 1 81 31 31 61 31 1i 291 I ---------------- --- -------------------------------------------- +- - I I-NW- I 11 1i 11 I 21 21 11 1i 91 I--- - - - - - - - - - - - - -- - -- - -- - ------------------------------------ + - - I
--NNW- I 21 11 21 1j 1l 11 .1 2I lol I-- - - - -I-- - - - - - - - - - - - - - - - - - ----------------------------------- + ---
+ - I I-CALM- I 61 .1
- .1 *I .I1I I 6 I - - - - - - - -I-- - - -- - - -- - - - - - - - ---------------------------------- --- - I TOTAL I 391 85 lool 96 194I 166I 231 61 709I
McGuire NUCLEAR STN. METEOROLOGY (2006) 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 I 1 0.45-1 0.75-I 1.00-1 1.25-I 1.so-1 2.00-1 3.00-[ 1 0.74 1 0.99 I 1.24 1 1.49 I 1.99 I 2.99 I 3.99 TOTAL
- +-------+-- . ---- ---- I I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO.
I --------- ------------ ---------------------------- ".---- -+- II
[SECTOR I I I I I I I I II-N - ---------------------- I 1 2 I1 . I1I1 II1 I
.I1 I -1 I1 I 2I 1
[-NNE- 1 S5 1i 21 1 1 .1 .1 9 I-ESE- 1
-+-------------+-------+-------+-------+-------+--
.1 . 11 .1_- .1 -+- I
. 11
--- - -- -+-- + . . ..-. . +--- + -.....- + -.....-
- +....- I
[-SSE- 1 11 31 .1 .1 4 S+------- ....
+--- + ..... +---..---- + ----
....---- + ...- + - II
[-s- I 31 91 31 6[ 101 81 *1 39[
I ---------------------------------------------+ -- +-+-I+- + - + - +
I-SSW- 1 61 281 301 231 191 i[ .[ 107[
I- - - - - - - - - - - - - - -- - -- -------------------------------------- + -
I-Sw- I----------------- I -+
181 43I
+-...
151 16[
+-".----+-...+-...+-...+-...
61 6I *1 104[
l-WSW- 1 121 201 141 9[ 21 6l *1 63[
I ---------------- --- --- -------------------------------- + + - - I I-w- I 71 sI 41 21 41 2[ 2[ 26[
I ---------------- --- --- -------------------------------- + + - - I I-WNW- I sI 31 11 .1 11 1i 1I 12[
I ---------------- --- --- -------------------------------- + + - - I I-NW- I 31 21 21 .l .1 7 I --------------------------------------------------------- - I I-NNW- I 31 .1 11 1 11 -I 51 s1 II-CALM-
1 --- sl --- .1 --------------------------------
. . 1 +
.1 + - - I-1 5 S1 I ---------------- --- --- -------------------------------- + + - - I TOTAL I 701 1141 31 S7 431 241 31 3841
McGuire NUCLEAR STN. METEOROLOGY (2006) PROG=XOQFREQ 10M WIND SPEED/DIRECTION/DELTA-T STABILITY STABILITY CLASSES BASED ON DELTA-T BETWEEN UPPER-LOWER LEVELS ALL STABILITY CLASSES WIND SPEED CLASS I I
I I 10.45-I 0.75-I 1.00-1 1.25-I 1.50-I 2.00-1 3.00-1 4.00-1 5.00-1 6.00-1 8.00-1>9.99 I I 0.74 1 0.99 1 1.24 1 1.49 I 1.99 I 2.99 1 3.99 I 4.99 I 5.99 I 7.99 I 9.99 1 M/S ITOTAL I.---- +-------+------+--.....+.--.-+. . . . . . . .. . ...------------- +-. .+- . . +.-------- I I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. I NO. NO.
I .....
- - -- + - ----
+ - - I SECTOR I I I I I I I I I I I I
I I I I I I I I I I I I I I I-N- I 41 61 181 321 501 1271 561 731 621 701 241 51 5271 1- - - - - - - - - - - - - - - - - - - - - - - ------
--- + - I I-NNE- 1 sI 21 131 251 1061 1461 1201 921 631 901 371 71 7061 1------------------------------------------------------------------------------------+-+-+-+- + - + - + +- +. .- I I-NE- I 21 21 41 191 651 1891 2231 1441 681 501 181 11 7851 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------------------------------------- +- - I
-ENE- 1 .1 41 91 ill 581 1451 117 511 91 1 .I 4051 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------------------ - I I-E- 11 61 71 181 371 821 901 191 21 *I .1 1 2621 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------------------------------------------- + - I
-ESE- 1 31 21 ill 71 401 901 45I 5l 1I *1 .1 I 2041 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------------------ - I I-SE- j 31 5j 151 211 ssl 1391 461 91 1I *I .1 1 2941 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------------ -------------- - I I-SSE- I sI 141 151 321 641 921 271 81 41 1 -I
.1 2621 1 --....--- -....--- .....-- -....-- --....-- ------------------- + - + -
+ -
- -+-- -+- ------- + -
1-S- 91 311 301 381 1321 1961 291 151 31 71 21 1 492I 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------- --- +----- - --- z---- - -
I-SSW- I 131 31 681 731 1431 3341 1611 521 221 61 11 1 9261 I-SW- I 231 601 401 551 1151 37s5 3251 1971 851 561 61 1 13371 1 - - - - - - - - - - - - - - -- - -- - -- - -- - -- - -- - --------------------------------- - - +-I-- - -
I-WSW- I 151 391 391 70j 1301 2321 1611 l011 601 391 121 11 8991 1 -....-- - -....--.....--- - -....-- ---------------------------
+-----+---+ -- + -- + -- +- .+-.. +. .- I I-w- 1 9I 211 301 311 701 1031 ý641 451 241 141 41 11 4161 1 - - - - - - - - - - - - - - - - - - - - -- - -- - -- - - - - - - - -------------------------------------- - I I-WNW- 1 101 141 181 231 581 731 651 441 291 231 61 .I 3631 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------------------------------- - I I-NW- 1 s5 61 121 81 34I 6s1 74I 461 331 401 241 61 3531 1- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -+- - - - - - ---------------------- + ---- - I I-NNW- 1 61 6I 131 131 411 601 481 511 461 591 291 71 379I 1-------------------------------------------------------------------------- +- w- -- +-- ---.-+ . - .-. I I-CALM- I 1 ill I I . . I 1 I --- -- -- --- -- -- -448-- 12--- -1-- -- -- -- 2--5----------------- - I ITOTAL I 1241 2711 3421 4761 11981 24481 16511 9521 5121 4561 1631 281 86211
Attachment 5 Inoperable Monitoring Equipment
McGuire Nuclear Station Inoperable Monitoring Equipment (January 1, 2006 through December 31, 2006)
No SLC related effluent monitoring instruments were out of service greater than the SLC limits for operability.
Attachment 6 Groundwater Protection Initiative
McGUIRE NUCLEAR STATION INFORMATION TO SUPPORT THE NUCLEAR ENERGY INSTITUTE (NEI)
GROUNDWATER PROTECTION INITIATIVE
AREOR/ARERR Groundwater Well Data Section Rev. 2 Duke Energy is implementing 'a voluntary groundwater investigation project to determine optimal locations for groundwater monitoring wells. These wells are expected to be installed during 2007. Results from monitoring wells that are within the McGuire owner controlled area will be reported in the Annual Radiological Effluent Release Report. This information will meet the criteria specified by Nuclear Energy Institute (NEI)
Groundwater Protection Initiative (June 2006).
The following existing monitoring wells were sampled during 2006. These locations may or may not be included in the final set of wells determined as part of the groundwater investigation project and the name designations may be changed as part of the project.
Well Name Well Location Sampling Annual Average Tritium Frequency Concentration in pCi/1
- 26 N of Access Road Quarterly <MDA
- 31 E of Access Road Quarterly <MDA
- 35 Admin. Parking Lot Quarterly <MDA RPMW-101 S of WC Pond Quarterly 301 RPMW-102 SW of WC Pond Quarterly 6,180 MW-2 W of Plant Quarterly 1,110 MW-4 SW of Plant Quarterly 244 2WZLS 5060 ALT Near U-2 Rx. Bldg. Quarterly 695 U-1 Fuel Pool Ramp Near U-I Rx. Bldg. Quarterly 224 pCi/1 - pico curies per liter 20,000 pCi/1 - the Environmental Protection Agency drinking water standard for tritium.
This standard applies only to water that is used for drinking.
1,000,000 pCi/1 - the 10CFR20, Appendix B, Table 2, Column 2, Effluent Concentration limit for tritium.