ML11117A251

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Annual Radioactive Effluent Release Report
ML11117A251
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 04/14/2011
From: Repko R
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML11117A251 (68)
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Text

REGIS T. REPKO Duke Vice President r Energy McGuire Nuclear Station Duke Energy MG01 VP / 12700 Hagers Ferry Rd.

Huntersville, NC 28078 980-875-4111 980-875-4809 fax regis.repko@duke-energy.corn April 14, 2011 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC McGuire Nuclear Station Docket Nos. 50-369 and 50-370 2010 Annual Radioactive Effluent Release Report Pursuant to the requirements of Technical Specification 5.6.3 and Section 16.11-17 of the McGuire Selected Licensee Commitments (SLC) Manual, attached is the Annual Radioactive Effluent Report. Also included in this report is a CD-Rom of the 2011 Offsite Dose Calculation Manual and the 2010 Process Control Program (PCP) manual.

The following Attachments form the contents of the report:

Attachment 1 - Summary of Gaseous and Liquid Effluents Report Attachment 2 - Supplemental Information Attachment 3 - Solid Waste Disposal Report Attachment 4 - Meteorological Data Attachment 5 - Unplanned Offsite Releases Attachment 6 - Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (Includes Fuel Cycle Dose Calculation Results)

Attachment 7 - Radioactive Waste Systems Attachment 8 - Inoperable Monitoring Equipment Attachment 9 - Groundwater Protection Program Questions concerning this report should be directed to Kay Crane, McGuire Regulatory Compliance at (980) 875-4306.

Regis T. Repko Attachments pP-L www. duke-energy.corn

Desk NRC Document Control April 14, 2011 Page 2 cc: Mr. Jon Thompson NRC Project Manager Regulation Office of Nuclear Reactor Mail Stop 8-H4A Washington, D.C. 20555 Administrator Mr. Victor McCree, Regional Commission, Region II U. S. Nuclear Regulatory Marquis One Tower NE Suite 1200 245 Peachtree Center Ave.,

Atlanta, Georgia 30303-1257 Division of Radiation Protection State of North Carolina 3825 Barrett Drive Raleigh, N.C. 27609-7221 Mr. Joe Brady Senior Resident Inspector McGuire Nuclear Station INPO Records Center 100 700 Galleria Place, Suite Atlanta, GA 30339-5957

Attachment 1 Summary of Gaseous and Liquid Effluents Report

McGUIRE NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 2010 through December 31, 2010)

This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Rev. 1, Appendix B. Radioactive liquid and gaseous wastes are sampled and analyzed per the requirements in Selected Licensee Commitment (SLC)

Table 16.11.1-1, "Radioactive Liquid Waste Sampling and Analysis Program", and SLC Table 16.11.6-1, "Radioactive Gaseous Waste Sampling and Analysis Program". Included in the gaseous effluent releases is an estimate of Carbon- 14 radioactivity released in 2010 (Ref.

"Carbon-14Supplemental Information", contained in the ARERR for further information).

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Gases

1. Total Release Ci 6.03E-01 4.90E-01 5.64E-01 6.10E-01 2.27E+00
2. Avg. Release Rate pCi/sec 7.76E-02 6.23E-02 7.10E-02 7.68E-02 7.19E-02 B. Iodine-131
1. Total Release Ci 3.52E-06 0.OOE+00 0.OOE+00 0.OOE+00 3.52E-06
2. Avg. Release Rate pCi/sec 4.53E-07 0.OOE+00 0.OOE+00 0.OOE+00 1.12E-07 C. Particulates Half Life >= 8 da:ys
1. Total Release Ci 1.12E-05 8.73E-08 0.OOE+00 1.48E-05 2.61E-05
2. Avg. Release Rate pCi/sec 1.44E-06 1.lE-08 0.OOE+00 1.86E-06 8.27E-07 D. Tritium
1. Total Release Ci 3.31E+01 3.81E+01 2.22E+01 3.07E+01 1.24E+02
2. Avg. Release Rate pCi/sec 4.25E+00 4.85E+00 2.80E+00 3.86E+00 3.94E4-00 E. Carbon-14
1. Total Release Ci 4.78E+00 4.61E+00 5.36E+00 5.48E+00 2.02E+01
2. Avg. Release Rate pCi/sec 6.15E-01 5.86E-01 6.74E-01 6.89E-01 6.41E-01 F. Gross Alpha Radioactivity
1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
2. Avg. Release Rate pCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-I00 0.OOE+00

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2010 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. Carbon-14
    • No Nuclide Activities **
6. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2010 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. Carbon-14
    • No Nuclide Activities **
6. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases
    • No Nuclide Activities **
2. Iodines 1-131 Ci 3.52E-06 0. 00E+00 0. OOE+00 0. OOE+00 3.52E-06 Totals for Period... Ci 3.52E-06 0.OOE+00 0. OOE+00 0.OOE+00 3.52E-06
3. Particulates Half Life >= 8 days CO-58 Ci 1.1OE-05 8.73E-08 0. OOE+00 8.54E-06 1. 96E-05 CO-60 Ci 0.00E+00 0. 00E+00 0. OOE+00 4.50E-06 4.50E-06 MN-54 Ci 0.OOE+00 0. OOE+00 0. OOE+00 1.74E-06 1. 74E-06 Totals for Period... Ci 1.10E-05 8.73E-08 0. OOE+00 1.48E-05 2.58E-05
4. Tritium H-3 Ci 3.22E+01 3.70E+01 2.21E+01 3.04E+01 1.22E+02 Totals for Period... Ci 3.22E+01 3.70E+01 2.21E+01 3.04E+01 1. 22E+02
5. Carbon-14 C-14 Ci 1.43E+00 1. 38E+00 1. 61E+00 1. 64E+00 6. 06E+00

,Totals for Period... Ci 1.43E+00 1.38E+00 1. 61E+00 1. 64E+00 6.06E+00

6. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases C-Il Ci 0.OOE+00 3.73E-04 0. OOE+00 0. 00E+00 3.73E-04 AR-41 Ci 5.51E-01 4.58E-01 5.38E-01 5.94E-01 2.14E+00 KR-85 Ci 0.OOE+00 1. 94E-03 1. 93E-03 1. 47E-03 5.34E-03 KR-85M Ci o.00E+00 2.47E-04 1. 53E-04 0. OOE+00 4.01E-04 KR-87 Ci 0.OOE+00 6. 91E-05 3.86E-05 0. OOE+00 1.08E-04 KR-88 Ci 0.00E+00 3.71E-04 2.38E-04 0. OOE+00 6.09E-04 XE-131M Ci 0.OOE+00 0. OOE+00 0. 00E+00 2.37E-05 2.37E-05 XE-133 Ci 4.99E-02 2.17E-02 2.06E-02 1. 44E-02 1. 07E-01 XE-133M Ci 0.OOE+00 0.00E+00 2.68E-04 0. OOE+00 2. 68E-04 XE-135 Ci 2.22E-03 7.35E-03 2. 94E-03 0. OOE+00 1.25E-02 Totals for Period... Ci 6.03E-01 4.90E-01 5.64E-01 6.lOE-01 2.27E+00
2. Iodines
    • No Nuclide Activities **
3. Particulates Half Life >= 8 days CL-38 Ci 2.28E-07 0. OOE+00 0. OOE+00 0.OOE+00 2.28E-07 Totals for Period... Ci 2.28E-07 0. OOE+00 0. OOE+00 0.OOE+00 2.28E-07
4. Tritium H-3 Ci 8.13E-01 1. 10E+00 1.20E-01 2.46E-01 2.28E+00 Totals for Period... Ci 8.13E-01 1.10E+00 1.20E-01 2.46E-01 2.28E+00
5. Carbon-14 C-14 Ci 3.35E+00 3.23E+00 3.75E+00 3.84E+00 1. 42E+01 Totals for Period... Ci 3.35E+00 3.23E+00 3.75E+00 3.84E+00 1. 42E+01
6. Gross Alpha Radioactivity
    • No Nuclide Activities **

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 1.48E-02 1.85E-02 7.43E-03 4.14E-03 4.48E-02
2. Average Diluted Concentration
a. Continuous Releases pCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
b. Batch Releases pCi/ml 1.93E-11 2.09E-11 7.29E-12 4.18E-12 1.22E-11 B. Tritium
1. Total Release Ci 5.68E+02 1.28E+02 3.36E+02 1.76E+02 1.21E+03
2. Average Diluted Concentration
a. Continuous Releases pCi/ml 5.58E-09 1.14E-08 9.34E-09 6.08E-09 7.41E-09
b. Batch Releases pCi/ml 7.41E-07 1.45E-07 3.29E-07 1.78E-07 3.30E-07 C. Dissolved and Entrained Gases
1. Total Release Ci 0.OOE+00 1.43E-05 0.OOE+00 0.OOE+00 1.43E-05
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 1.62E-14 0.OOE+00 0.OOE+00 3.90E-15 D. Gross Alpha Radioactivity
1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
2. Average Diluted Concentration
a. Continuous Releases pCi/ml 0.OOE+00 0.00E+60 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 8.96E+07 1.06E+08 8.61E+07 6.62E+07 3.48E+08
2. Batch Releases liters 1.45E+06 9.02E+05 1.16E+06 5.89E+05 4.11E+06 F. Volume of Dilution Water
1. Continuous Releases liters 1.08E+ll 4.40E+10 2.99E+10 2.65E+10 2.08E+ll
2. Batch Releases liters 7.66E+ll 8.83E+ll 1.02E+12 9.92E+ll 3.66E+12

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID EFFLUENTS - CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products
    • No Nuclide Activities **
2. Tritium H-3 Ci 6.03E-01 5.03E-01 2.80E-01 1.62E-01 1.55E+00 Totals for Period... Ci 6.03E-01 5.03E-01 2.80E-01 1.62E-01 1.55E+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 1/1/10 TO 1/1/11 LIQUID EFFLUENTS - BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products AG-108M Ci 1.29E-05 4.43E-05 0. 00E+00 4.49E-06 6.17E-05 AG-1IOM Ci 1. 29E-04 5.38E-05 0. 00E+00 0. OOE+00 1. 82E-04 BE-7 Ci 2. 97E-05 4.07E-04 0. OOE+00 3.83E-04 8.20E-04 CO-57 Ci 4. OOE-05 5. OOE-05 3. 93E-05 3.56E-05 1. 65E-04 CO-58 Ci 6.82E-03 8.32E-03 4.36E-03 1. 16E-03 2.07E-02 CO-60 Ci 4. 00E-03 2.34E-03 1. 34E-03 1.29E-03 8. 96E-03 CR-51 Ci 1. 57E-03 4. 11E-03 0. 00E+00 0. OOE+00 5. 68E-03 CS-134 Ci 6.44E-06 1. 40E-04 1. 83E-04 7.33E-05 4.02E-04 CS-137 Ci 2.14E-04 1. 07E-03 1. 37E-03 6.14E-04 3.27E-03 FE-59 Ci 2.05E-04 2.57E-04 0. 00E+00 0. OOE+00 4. 61E-04 K-40 Ci 6.71E-06 2.37E-05 0. OOE+00 0. OOE+00 3.04E-05 MN-54 Ci 4.82E-04 1. 72E-04 2.49E-06 1. 12E-04 7. 68E-04 NB-95 Ci 3.30E-04 1. 46E-04 0. OOE+00 0. OOE+00 4.76E-04 NB-97 Ci 1. 18E-05 2.02E-05 0.OOE+00 0.OOE+00 3.20E-05 SB-122 Ci 4.72E-06 0. 00E+00 0. OOE+00 0. OOE+00 4.72E-06 SB-124 *Ci 1. 39E-04 3.03E-04 0. OOE+00 2.75E-05 4. 70E-04 SB-125 Ci 5.1OE-04 8. 92E-04 1. 48E-04 4.21E-04 1. 97E-03 SN-113 Ci 1. 33E-05 2.21E-05 0. OOE+00 0.OOE+00 3.54E-05 SR-92 Ci 1.84E-06 1. 46E-06 0. OOE+00 0. OOE+00 3.30E-06 ZN-65 Ci 1.26E-04 3.09E-05 1. 62E-06 3.04E-05 1. 89E-04 ZR-95 Ci 1.22E-04 5.30E-05 0.OOE+00 0.OOE+00 1. 75E-04 Totals for Period... Ci 1. 48E-02 1. 85E-02 7.43E-03 4.14E-03 4.48E-02
2. Tritium H-3 Ci 5.67E+02 1.28E+02 3.36E+02 1.76E+02 1.21E+03 Totals for Period... Ci 5.67E+02 1.28E+02 3.36E+02 1.76E+02 1.21E+03
3. Dissolved and Entrained Gases XE-133 Ci 0.OOE+00 1.43E-05 0.OOE+00 0.OOE+00 1.43E-05 Totals for Period... Ci 0.OOE+00 1.43E-05 0.OOE+00 0.OOE+00 1.43E-05
4. Gross Alpha Radioactivity
    • No Nuclide Activities **

Attachment 2 Supplemental Information

McGUIRE NUCLEAR STATION SUPPLEMENTAL INFORMATION (January 1, 2010 through December 31, 2010)

This attachment includes:

(1) Carbon-14 Supplemental Information (2) Regulatory Guide 1.21, Revision 1, Supplemental Information (3) Overall Error Estimate for Liquid and Gaseous Effluent Release Data

Page 1 of 2 McGuire 2010 ARERR - Carbon-14 Supplemental Information Carbon-14 (C-14), with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing.

In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC has recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and if so, report the amount of C-14 released. At McGuire, improvements over the years in effluent management practices and fuel performance have resulted in a decrease in gaseous radionuclide (non-C-14) concentrations, and a change in the distribution of gaseous radionuclides released to the environment. As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at McGuire, as defined in Regulatory Guide 1.21, Rev. 2. McGuire's 2010 Annual Radioactive Effluent Release Report (ARERR) contains estimates of C-14 radioactivity released in 2010, and estimates of public dose resulting from the C-14 effluent.

Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste at McGuire is not required (Ref. Reg. Guide 1.21, Rev. 2). The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation (Ref. Reg. Guide 1.21, Rev. 2). Many documents provide information related to the magnitude of C-14 in typical effluents from commercial nuclear power plants. Those documents suggest that nominal annual releases of C-14 in gaseous effluents are approximately 5 to 7.3 curies from PWRs (Ref. Reg. Guide 1.21, Rev. 2). A more recent study recommends a higher C-14 gaseous source term scaling factor of approximately 9.0 to 9.8 Ci/GWe-yr for a PWR (Westinghouse)

(Ref. EPRI 1021106). For the 2010 McGuire ARERR a source term scaling factor of 9.4 Ci/GWe-yr is assumed. Using a source term scaling factor of 9.4 Ci/GWe-yr and actual electric generation (MWe-hrs) from McGuire in 2010 results in a site total C-14 gaseous release estimate to the environment of-20 Curies. 70% of the C-14 gaseous effluent is assumed to be from batch releases (e.g. WGDTs), and 30% of C-14 gaseous effluent is assumed to be from continuous releases through the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14", 2004).

C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. Since the PWR operates with a reducing chemistry, most, if not all, of the C-14 species initially produced are organic (e.g., methane). As a general rule, C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment (e.g. during shutdown or refueling), a slow transformation from an organic to an inorganic chemical form can occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic with an average of 80% organic with the remainder being CO 2 (Ref. EPRI TR-105715). For the McGuire 2010 ARERR a value of 80% organic C-14 is assumed.

Page 2 of 2 Public dose estimates from airborne C-14 are performed using dose models in NUREG-0133 and Regulatory Guide 1.109. The dose models and assumptions used are documented in the 2011 McGuire ODCM. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released at McGuire in 2010 is well below the 10CFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit).

McGUIRE NUCLEAR STATION 2010 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. 2.21E+02 = TOTAL NUMBER OF BATCH RELEASES
2. 1.54E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
3. 1.79E+02 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
4. 6.99E+01 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
5. 1.OOE+00 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
6. 1.84E+06 = AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B. GASEOUS EFFLUENT

1. 3.50E+01 = TOTAL NUMBER OF BATCH RELEASES.
2. 1.05E+06 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
3. 4.51E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
4. 3.OOE+04 = AVERAGE TINE (MIN.) FOR A BATCH RELEASE.
5. 9.OOE+00 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.

VI. ABNORMAL RELEASES (See "Unplanned Releases" Attachment)

McGUIRE NUCLEAR STATION Overall Estimate of Error for Effluent Radioactivity Release Reported The estimated percentage of overall error for both Liquid and Gaseous effluent release data at McGuire Nuclear Station has been determined to be + 30.3%. 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 Statistical Error = +20%

(3) Calibration Error = -10%

(4) Calibration Source Error = -2.5%

(5) Sample Preparation Error = +/-3%

Attachment 3 Solid Waste Disposal Report

REPORT PERIOD McGUIRE NUCLEAR STATION JANUARY - DECEMBER 2010 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 ft3 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 DBP 158.68 4.49 A/U 1.72E+01 (F) dewatered primary bead resin none (G) dewatered mechanical filter media none (H) dewatered mechanical filter media (brokered) 1 1 DBP 72.8 2.06 A/U 3.98E-01 (I) solidified waste none Dry Solid Waste (A) dry active waste (compacted) none dry active waste (non-compacted) I N/A N/A 43,794 1240.11 N/A 3.24E-03 dry active waste (brokered/compacted) none dry active waste (brokered/non-compacted) 16 44 DBP 3428.3428 97.02 A/U 9.212E-01 (B) sealed sources/smoke detectors none (C) sealed sources none (D) irradiated components none Totals 19 46 47453.8228 1343.68 1.852E+01 2/22/2011

MCGUIRE NUCLEAR SITE

SUMMARY

OF MAJOR RADIONUCLIDE COMPOSITION 2010 I

Type of waste Ntuclide %Abundance I1

1. Waste from liquid systems:.

A. Dewatered Powdex Resin (brokered) No shipments in 2010 B. Dewatered Powdex Resin No shipments in 2010 C. Dewatered Bead Resin (brokered) No shipments in 2010 D. Dewatered Bead Resin No shipments in 2010 E. Dewatered Radwaste System Resin (brokered) 2010- 0018A Nuclide %Abundance Mn-54 .43 Co-57 .01 Co-58 .01 Co-60 35.82 Cs-1 37 .80 Cs-1 34 .12 Fe-55 36.40 Ni-63 24.34 Ni-59 .06 C-14 .34 H-3 .04 Sb-125 1.28 Ag-108m .13 Ce-144 .03 Sr-90 .02 Tc-99 .18 F. Dewatered Primary Bead Resin (brokered) No Shipments in 2010 G. Dewatered Mechanical Filter Media No shipments in 2010 I

H. Dewatered Mechanical Filter Media (brokered) 2010-0026 Nuclide %Abundance Mn-54 2.24 Co-57 .10 Co-58 .01 Co-60 29.12 Cs-I 37 1.99 Cs-1 34 .34 Fe-55 45.44 Ni-63 18.58 C-14 .80 Sb-1 25 .61 Ce-144 .04 Zn-65 .09 Tc-99 .63 I. Solidified Waste No shipments in 2010

2. Dry Solid Waste:

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

Dry Active Waste (non-compacted)

Landfill 10-01 Nuclide %Abundance Co-60 11.55 Cs-137 7.25 H-3 81.20 Dry Active Waste (brokered/compacted) No shipments in 2010 2

Dry Active Waste (brokered/non-compacted) 2010-0001 Nuclide %Abundance Cr-51 22.93 Mn-54 1.46 Co-57 .12 Co-58 41.24 Co-60 5.73 Cs-I 37 .43 Fe-55 10.23 Fe-59 .99 Ni-63 3.88 H-3 2.35 C-14 .28 Zr-95 3.69 Ce-144 .08 Sn-113 .15 Zn-65 .22 Nb-95 6.27 2010-0002 Nuclide %Abundance Cr-51 23.85 Mn-54 1.42 Co-57 .11 Co-58 41.00 Co-60 5.55 Cs-137 .41 Fe-55 9.87 Fe-59 1.00 Ni-63 3.70 H-3 2.26 C-14 .27 Zr-95 3.68 Ce-144 .08 Sn-113 .15 Zn-65 .21 Nb-95 6.42 3

2010-0003 Nuclide %Abundance Cr-51 23.82 Mn-54 1.42 Co-57 .11 Co-58 41.03 Co-60 5.55 Cs-137 .41 Fe-55 9.88 Fe-59 1.00 Ni-63 3.70 H-3 2.27 C-14 .27 Zr-95 3.67 Ce-144 .08 Sn-113 .15 Zn-65 .21 Nb-95 6.42 2010-0004 Nuclide %Abundance Cr-51 23.54 Mn-54 1.43 Co-57 .12 Co-58 41.10 Co-60 5.61 Cs-137 .42 Fe-55 10.00 Fe-59 1.00 Ni-63 3.75 H-3 2.28 C-14 .27 Zr-95 3.68 Ce-144 .08 Sn-113 .15 Zn-65 .21 Nb-95 6.37 4

2010-0005 Nuclide %Abundance Cr-51 25.64 Mn-54 2.38 Co-57 .10 Co-58 21.12 Co-60 7.97 Cs-I 37 .02 Fe-55 26.94 Fe-59 1.82 Ni-63 1.63 H-3 .71 Zr-95 4.40 Ce-144 .06 Sb-1 24 .10 Sb-125 .30 Ru-103 .03 Sn-113 .22 Zn-65 .57 Hf-1 81 .04 Nb-95 5.97 2010- 0006 Nuclide %Abundance Cr-51 34.50 Mn-54 1.91 Co-57 .08 Co-58 20.14 Co-60 6.12 Cs-1 37 .01 Fe-55 20.89 Fe-59 1.98 Ni-63 1.24 H-3 .54 Zr-95 4.32 Ce-1 44 .05 Sb-124 .10 Sb-125 .23 Ru-103 .03 Sn-113 .19 Zn-65 .46 Hf-181 .04 Nb-95 7.15 5

2010-0007 Nuclide %Abundance Cr-51 30.91 Mn-54 2.09 Co-57 .09 Co-58 20.65 Co-60 6.81 Cs-1 37 .02 Fe-55 23.24 Fe-59 1.93 Ni-63 1.38 H-3 .61 Zr-95 4.38 Ce-144 .05 Sb-124 .10 Sb-1 25 .26 Ru-103 .03 Sn-113 .20 Zn-65 .51 Hf-1 81 .04 Nb-95 6.70 2010- 0008 Nuclide %Abundance Cr-51 31.12 Mn-54 2.08 Co-57 .08 Co-58 20.63 Co-60 6.79 Cs-I 37 .02 Fe-55 23.05 Fe-59 1.93 Ni-63 1.38 H-3 .60 Zr-95 4.38 Ce-1 44 .05 Sb-124 .10 Sb-125 .26 Ru-103 .03 Sn-113 .20 Zn-65 .50 Hf-181 .04 Nb-95 6.73 6

2010-0010 Nuclide %Abundance Cr-51 34.11 Mn-54 1.93 Co-57 .08 Co-58 20.20 Co-60 6.20 Cs-1 37 .01 Fe-55 21.15 Fe-59 1.97 Ni-63 1.26 H-3 .55 Zr-95 4.33 Ce-144 .05 Sb-124 .10 Sb-125 .24 Ru-103 .03 Sn-113 .19 Zn-65 .47 Hf-I 81 .04 Nb-95 7.08 2010-0011 Nuclide %Abundance Cr-51 30.76 Mn-54 2.10 Co-57 .09 Co-58 20.68 Co-60 6.84 Cs-137 .02 Fe-55 23.33 Fe-59 1.92 Ni-63 1.40 H-3 .61 Zr-95 4.39 Ce-144 .05 Sb-1 24 .10 Sb-1 25 .26 Ru-103 .03 Sn-113 .20 Zn-65 .51 Hf-181 .04 Nb-95 6.68 7

2010-0012 Nuclide %Abundance Cr-51 32.83 Mn-54 2.00 Co-57 .08 Co-58 20.42 Co-60 6.44 Cs-1 37 .02 Fe-55 21.93 Fe-59 1.96 Ni-63 1.31 H-3 .57 Zr-95 4.35 Ce-144 .05 Sb-124 .10 Sb-125 .25 Ru-103 .03 Sn-113 .20 Zn-65 .48 Hf-181 .04 Nb-95 6.94 2010-0013 Nuclide %Abundance Cr-51 32.45 Mn-54 2.01 Co-57 .08 Co-58 20.49 Co-60 6.52 Cs-137 .02 Fe-55 22.17 Fe-59 1.95 Ni-63 1.33 H-3 .58 Zr-95 4.35 Ce-144 .05 Sb-124 .10 Sb-125 .25 Ru-103 .03 Sn-113 .20 Zn-65 .49 Hf-181 .04 Nb-95 6.90 8

2010-0015 Nuclide %Abundance Cr-51 32.12 Mn-54 2.03 Co-57 .08 Co-58 20.52 Co-60 6.57 Cs-1 37 .02 Fe-55 22.40 Fe-59 1.95 Ni-63 1.34 H-3 .58 Zr-95 4.37 Ce-144 .05 Sb-1 24 .10 Sb-1 25 .25 Ru-103 .03 Sn-113 .20 Zn-65 .49 Hf-181 .04 Nb-95 6.85 2010-0016 Nuclide %Abundance Cr-51 20.97 Mn-54 2.64 Co-57 .11 Co-58 21.19 Co-60 9.06 Cs-1 37 .02 Fe-55 30.61 Fe-59 1.69 Ni-63 1.87 H-3 .81 Zr-95 4.36 Ce-144 .06 Sb-124 .10 Sb-125 .34 Ru-103 .03 Sn-113 .23 Zn-65 .63 Hf-181 .04 Nb-95 5.24 9

2010-0019 Nuclide %Abundance Cr-51 33.74 Mn-54 1.95 Co-57 .08 Co-58 20.28 Co-60 6.27 Cs-1 37 .02 Fe-55 21.36 Fe-59 1.97 Ni-63 1.27 H-3 .55 Zr-95 4.34 Ce-144 .05 Sb-124 .10 Sb-125 .24 Ru-103 .03 Sn-113 .19 Zn-65 .47 Hf-181 .04 Nb-95 7.05 2010-0027 Nuclide %Abundance Cr-51 10.11 Mn-54 3.33 Co-57 .13 Co-58 19.40 Co-60 12.37 Cs-137 .03 Fe-55 41.05 Fe-59 1.21 Ni-63 2.59 H-3 1.11 Zr-95 3.83 Sn-113 .25 Ce-144 .08 Zn-65 .77 Sb-124 .09 Sb-125 .46 Ru-103 .02 Hf-181 .03 Nb-95 3.15 B. Sealed Sources No shipments in 2010 C. Sealed Sources/Smoke Detectors No shipments in 2010 D. Irradiated Components No shipments in 2010

Attachment 4 Meteorological Data

McGUIRE NUCLEAR STATION 2010 METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS OF WIND SPEED, WIND DIRECTION, AND ATMOSPHERIC STABILITY USING WINDS AT THE 10 METER LEVEL (Hours of Occurrence)

MNS 2010 The SAS System 16:13 Tuesday, March 8, 2011 The FREQ Procedure Table of STAB by CALM STAB CALM Frequency CALM WIND Total 1 0 53 53 2 0 214 215 3 0 606 606 4 0 5133 5133 5 0 1617 1617 6 0 560 560 7 2 435 437 Total 2 8618 8620 Frequency Missing = 140 The SAS System 16:13 Tuesday, March 8, 2011 2 The MEANS Procedure Analysis Variable  : WS Maximum 13.3664960 The SAS System 16:13 Tuesday, March 8, 2011 3 SECTOR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW No. No. No. No. No. No. No. No. No. No. No. No. No. No. No. No.

STAB WSCLS (m/s)

A 0.46-0.75 0.75-1.00 1.00-1.25 1.25-1.50 1.50-2.00 2.00-3.00 3.00-4.00 4.00-5.00 5.00-6.00 6.00-8.00 8.00-10.00 10.01-Max B 0.46-0.75 0.75-1.00 1.00-1.25 1.25-1.50 1.50-2.00 1 of 3

2.00-3.00 6 0 3 7 5 4 3.0 0d-'4. 00 2 2 1 3 14 3 4.00-5.00 2 0 0 2 19 9 5.00-6.00 0 0 0 0 10 4 6.00-8.00 0 0 0 0 8 2 8.00-10.00 0 0 0 0 0 0

10. 01-Max 0 0 0 0 0 0 0.46-0.75 0 0 0 0 0 0 0.75-1.00 0 0 0 0 0 0 1.00-1.25 0 0 1 0 0 0 1.25-1.50 1 0 0 0 1 0 1.50-2.00 .8 3 2 1 3 4 2.00-3.00 17 4 7 14 21 22 3.00-4.00 11 2 2 11 28 20 4.00-5.00 3 0 0 1 18 13 5.00-6.00 3 0 0 0 12 4 6.00-8.00 6 0 0 0 4 1 8.00-10.00 0 0 0 0 0 2
10. 01-Max 0 0 0 0 0 0 0.46-0.75 0 0 0 0 0 0 0.75-1.00 3 1 0 3 0 1 1.00-1.25 1 3 5 4 6 6 1.25-1.50 19 6 13 5 10 18 1.50-2.00 68 20 40 35 34 43 2.00-3.00 133 143 203 118 62 73 90 183 105 3.00-4. 00 73 110 215 125 32 20 69 183 75 4.00-5.00 42 73 124 49 1 7 44 65 19 5.00-6.00 59 49 39 11 0 9 9 40 16 6.00-8.00 44 36 11 0 0 2 2 5 18 8.00-10.00 7 5 0 0 0 0 0 0 3
10. 01-Max 1 0 0 0 0 0 0 0 0 E 0.46-0.75 0 0 0 0 0 2 1 1 0 0.75-1.00 1 2 2 2 3 6 4 7 7 1.00-1.25 3 0 3 1 3 13 18 8 8 1.25-1.50 10 6 3 4 11 21 15 11 19 1.50-2.00 20 13 11 8 13 44 42 43 45 2.00-3.00 18 15 15 17 14 78 115 132 64 3.00-4.00 3 8 17 3 4 5 15 35 11 4.00-5.00 5 5 11 0 0 0 3 16 3 5.00-6.00 0 1 6 0 0 1 0 9 0 6.00-8.00 2 1 0 0 0 3. 0 1 0 2 of 3

8.00-10.00 0 0 0 0

10. 01-Max 0 0 0 0 F 0.46-0.75 2 3 0 0 7 14 Ii 8 0.75-1.00 1.00-1.25 12 25 8 7 1.25-1.50 16 27 17 11 1.50-2.00 34 36 11 9 2.00-3.00 33 24 12 6 3.00-4.00 0 2 1 2 4.00-5.00 0 0 0 1 5.00-6.00 0 0 0 0 6.00-8.00 0 0 0 0 8.00-10.00 0 0 0 0
10. 01-Max 0 0 0 0

. G 0.46-0.75 4 14 3 5 0.75-1.00 14 45 16 8 1.00-1.25 6 32 16 4 1.25-1.50 2 20 12 5 1.50-2.00 10 18 8 2 2.00-3.00 4 4 5 3 3.00-4.00 0 0 0 0 4.00-5.00 0 0 0 0 5.00-6.00 0 0 0 0 6.00-8.00 0 0 0 0 8.00-10.00 0 0 0 0

10. 01-Max 0 0 0 0 3 of 3

Attachment 5 Unplanned Offsite Releases

Memorandum To: 2010 Annual Radioactive Effluent Release Report cc: Steve Mooneyhan, Joyce Correll, Caryl Ingram, Duncan Brewer, Ken Ashe, Kay Crane From: Harry Sloan RP General Supervisor

Reference:

Unplanned Gaseous Release PIP M-10-3672 Event Summary On 5/17/10 at about 17:15 the Auxiliary Building Ventilation EMF41 Trip 2 alarm occurred at Point #11 reaching about 420 cpm above background and the Unit 2 Vent EMF36L increased about 30 cpm above background. Upon investigation the NB evaporator was being started when the alarm came in and was secured at Operations request. A valve (1NB-158) was found to be not fully closed by Radwaste. When the valve was closed, the EMFs began to return to normal values. Radwaste reported that 10 psig (408 cu. ft. ) was lost from WGDT 'F'. Trending of 2EMF36L data showed an increase for about 30 minutes then a return to normal background after another 30 minutes.

Using HP/0/B/1003/008 2EMF36L 30 cpm increase represents only 0.3%. of the SLC Limit of 500 mr/yr total body ;therefore, there is no reporting criteria. This was communicated to Operations at 18:45.

A sample from WGDT 'F' was used to evaluate the doserate and dose to the public. Based on the isotopic mix the calculations were 1.57 mrem/yr total body, 2.8 mrem/yr skin, 9.55E-5 mrad gamma air, and 9.08E-5 mrad beta air.

Gaseous Waste Release number 2010-032 was generated to account for the activity released.

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

Harry Sloan CHP 9oyc'eCorrell RP General Supervisor RP Supervising Scientist McGuire Nuclear Station McGuire Nuclear Station

Memorandum To: McGuire Nuclear Station 2010 Annual Radioactive Effluent Release Report (August 2, 2010) cc: Steve Mooneyhan, Joyce Correll, Caryl Ingram, Duncan Brewer, Ken Ashe, Kay Crane From: William C Spencer RP Staff

Reference:

. Unplanned Gaseous Release (PIP M-10-4908)

Event Summary:

On 7/26/10 at about 16:24 the Auxiliary Building Ventilation EMF41 Trip 2 alarm occurred at Point #11 reaching about 900 cpm above background and the Unit 2 Vent EMF36L increased about 30 cpm above background. The duration of the release from the Unit 2 Vent is estimated to be 26 minutes based on the response seen on Unit 2 EMF36L.

Immediate investigation discovered that radwaste Chemistry was starting the NB evaporator when EMF 41 point 11 alarm came in and RP was notified by Operations. It is suspected that valve (1NB-158) was not fully closed or that an associated check valve 1NB-159 did not seat properly during alignment of the evaporator. A short time after 1NB-158 valve was checked closed; the affected EMFs began to return to normal values. Radwaste estimates that two (2) psig (81.63 cu. ft.) was lost from in-service WGDT 'B'. Trending of 2EMF36L data showed an increase for about 13 minutes then returned to normal background after another 13 minutes. Total time of release was 26 minutes.

Using HP/O/fB/1003/008 2EMF36L 30 cpm increase represents only 0.13% of the SLC Limit of 500 mrem/yr total body; therefore, there are no reporting requirements necessary. This was communicated to Operations at 17:50hrs by RP Staff.

A follow up sample from WGDT 'B' was used to evaluate the doserate and dose to the public. Based on the isotopic mix from the WGDT sample, calculations indicate the following:

  • 0.63 mrem/yr total body SLC Limit: 500 mrem/yr
  • 1.22 mrem/yr skin SLC Limit: 3000 mrem/yr
  • 3.35E-5 mrad gamma air SLC Limit: 40 mrad
  • 4.3E-5 mrad beta air. SLC Limit: 20 mrad Gaseous Waste Release number 2010049 was generated to account for the activity released from the Unit 2 Vent.

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 the limits of Selected Licensee Commitments and the Code of Federal Regulations.

Harry Sloan CHP William Spencer RP General Supervisor RP Staff Scientist McGuire Nuclear Station McGuire Nuclear Station

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (Includes fuel cycle dose calculation results)

McGuire Nuclear Station 2010 Radioactive Effluent and ISFSI

.40CFR190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFR190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. The fuel cycle dose assessment for McGuire Nuclear Station only includes liquid and gaseous effluent dose contributions from McGuire and direct and air-scatter dose from McGuire's onsite Independent Spent Fuel Storage Installation (ISFSI) since no other uranium fuel cycle facility contributes significantly to McGuire's maximum exposed individual. Included in the gaseous effluent dose calculations is an estimate of the dose contributed by Carbon-14 (Ref. "Carbon-14 Supplemental Information",contained in the ARERR for further information). The combined dose to a maximum exposed individual from McGuire's effluent releases and direct and air-scatter dose from McGuire's ISFSI is below 40CFR190 limits as shown by the following summary:

I. 2010 McGuire 40CFR190 Effluent Dose Summary The 40CFRI 90 effluent dose analysis to the maximum exposed individual from liquid and gas releases includes the dose from noble gases (i.e., total body and skin).

Maximum Total Body Dose = 4.41E-01 mrem Maximum Location: 1.5 Mile, Northeast Sector Critical Age: Child Gas non-NG Contribution: 67%

Gas NG Contribution: 1%

Liquid Contribution: 32%

Maximum Organ (other than TB) Dose = 9.37E-01 mrem Maximum Location: 1.5 Mile, Northeast Sector Critical Age: Child Critical Organ: Bone Gas Contribution: 98%

Liquid Contribution: 2%

II. 2010 McGuire 40CFR190 ISFSI Dose Summary Direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at McGuire have been calculated and documented in the "McGuire Nuclear Site 10CFR72.212 Written Evaluations" report. The maximum dose rate to the nearest resident from the McGuire ISFSI is conservatively calculated to be 14.5 mrem/year.

The attached excerpt from the "McGuire Nuclear Site 10CFR72.212 Written Evaluations" report is provided to document the method used to calculate the McGuire ISFSI 14.5 mrem/year dose estimate.

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

10CFR72.21.2 Evaluation report.

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

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

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

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

Independent Spent Fuel Storage Installation (ISFSI).

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

6.2.1 §72.104(a)- Dose Limits Historical TLD Monitoring Attachment 2 documents the actual radiological dose at the owner controlled fence on top of the berm overlooking the ISFSI. Actual dose to the public from the ISFSI is only available at this owner controlled fence. Therefore, a normalization factor is derived by comparing the actual dose to the calculated dose. The normalization factor is applied to the calculated values for the intake waterway and the exclusion area boundary to approximate McGuire Nuclear Station ISFSI Page 48 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

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

From Attachment 2, the greatest dose is 0.058 rems during a 97 day period in the second quarter of 2004 (TLD location #76). This is equivalent to 0.0249 mrem per hour for a total population of ten TN-32A casks. The calculated dose for this same location using conservative computer models is 0.744 mrem per hour. A normalization value is derived by dividing the actual dose by the calculated dose, which is 0.0249/0.744 = 0.0335. Please note that the normalization factor will only be used for the TN-32A casks.

ISFSI Controlled Area Boundary (ISFSI and Site Operations)

It is stipulated in 10CFR72.104(a) that the annual dose equivalent to any real individual who is located beyond the controlled area of the ISFSI (as defined in 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. (For McGuire, compliance with this regulation will also assure compliance with 40 CFR Part 190.) This dose equivalent must include contributions from planned releases to the environment, direct radiation from ISFSI operations, and any other radiation from uranium fuel cycle operations within the region.

The combined and skyshine dose rates at various distances for one cask stored with 7 year cooled fuel (inner) and 10 year cooled fuel (outer) were analyzed by Transnuclear (Reference 1). The best-fit empirical equation for skyshine dose rate as a function of distance is y = 0.0156e"o°112x for gammas and y = 0.0274e 0. 129x for neutrons, where y is dose rate (mrem/hr) and x is distance (meters), applicable from 20 to 1000 meters (page 22 of the calculation). Likewise, the best-fit empirical equation for total dose rate (direct and skyshine) as a function of distance is y = 492.69x2 16 88 for gammas and y = 166.95x"2 0 696 for neutrons, where y is dose rate (mrem/hr) and x is distance (meters),

applicable from 20 to 80 meters (page 23 of the calculation).

Based upon conservative engineering judgment, the McGuire power generation contribution at the Exclusion Area Boundary (EAB) is determined to be 3 mrem per year. The 3 mrem per year is independent of the ISFSI.

The combined and skyshine dose rates at various distances for a 2x6 cask array with 5 year cooled fuel were analyzed by NAC (Reference 2). Skyshine dose rates are located in Table 6-4 on page 12 of the calculation and combined dose rates are located in Table 6-6 on page 14 of the calculation. Both tables account for the effects of both gammas and neutrons.

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

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

occupancy time (8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> per year) at the boundary. The individual is also considered to be occupying the point on the EAB closest to the ISFSI, which would be just south of the Cowans Ford Dam close to the river. This point on the EAB is determined to be 425 meters from the ISFSI and the calculated dose only considers skyshine radiation. Direct radiation from the casks is shielded by the ground due to the significant drop in elevation from the ISFSI to the river. The combination of calculated and actual dose to an individual due to the ISFSI is determined to be 14.5 mrem and the dose due to McGuire power generation is 3 mrem per year for a total dose of 17.5 mrem per year. Therefore, the ISFSI controlled area boundary radiation limits are met for the McGuire ISFSI.

The selection of an individual on the EAB south of the dam is totally arbitrary in order to choose the closest point on the EAB to the ISFSI. This location is owned by Duke Energy and no member of the public would be permitted to occupy this location continuously.

The regulations speak of the "real individual" when addressing radiation exposure. Factually, this "real individual" is located beyond the EAB on the eastern side of the plant.

General Environment from Total Nuclear Fuel Cycle (ISFSI and Site Operations) 40 CFR 190 applies to radiation doses received by members of the public in the general environment and to radioactive materials introduced to the general environment as the result of all operations which are part of the Nuclear Fuel Cycle. The McGuire ISFSI is located in the immediate proximity of McGuire Nuclear Station and as such compliance with 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") define "unrestricted areas" to be coextensive with the EAB and beyond.

Likewise, "general environment" is defined to be coextensive with the EAB and beyond.

It is stipulated in 40 CFR 190.10(a) that the annual dose equivalent shall not exceed 25 mrems to the whole body, 75 mrems to the thyroid, and 25 mrems to any other organ of any member of the public as a result of exposures to planned discharges of radioactive materials, radon and its daughters excepted, to the general environment from uranium fuel cycle operations and to radiation McGuire Nuclear Station ISFSI Page 50 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

from these operations. As illustrated previously in showing compliance with 10CFR 72.104(a), the calculated dose at the EAB is 17.5 mrem per year, within the 25 mrem allowable limit. The summation of the doses from the ISFSI and McGuire power generation to the General Environment are well within the allowable limits.

Dose Inside ISFSI Controlled Area (ISFSI Operations)

Regulations permit the controlled area to be traversed by public roads and waterways as cited in 10 CFR 72.106(c). Since the public is permitted access into the controlled area at McGuire, the dose rate must be below 2 mrem per hour and the annual dose must be below 100 mrem within the controlled area (10 CFR 20.1301(b); see also 10 CFR 20.1301(a)(2)).

A member of 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 0.409 mrem per hour (direct radiation and skyshine), within the 2 mrem per hour allowable limit.

Finally, the annual dose resulting from ISFSI to the public inside the McGuire EAB in the vicinity of the intake structure, using a residence time of 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />, is determined to be 8.48 mrem (skyshine only - earthen berm acts as a shield), within the 100 mrem allowable limit.

These calculations show that the McGuire ISFSI containing ten TN-32A casks and up to 36 NAC-UMS casks meets the radiological requirements of 10CFR72.104, 10CFR20.1301 and 40CFR1 90. Note that only 28 NAC-UMS casks are included in the McGuire ISFSI.

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

Tabulations Normalization Factor (NF)

TN-32A Casks Actual radiological dose at the owner controlled fence divided by the calculated dose.

Actual dose =

(0.058 rem X 1000 mrem/rem) / (97 days X 24 hrs/day) =

0.0249 mrem/hr Calculated dose = 0.744 mrem/hr (see "top of berm at owner controlled fence" below)

NF = 0.0249/0.744 = 0.0335 Due to the amount of conservatisms utilized in the computer models, the actual measured dose at the owner controlled fence is only approximately 3% of the calculated values. Since historical TLD measurements are not available for the waterway and exclusion area boundary, the NF and calculated values are used to approximate the actual dose from the TN-32A casks for those two areas.

Top of berm at owner controlled fence - 70 meters from ISFSI TN-32A casks Using the previous equations for total dose and a distance of 70 meters the total dose rate (gammas and neutrons) for one cask is 7.443 E-02 mrem/hr.

(10) Casks X 7.443 E-02 mrem/hr = 0.744 mrem per hour Actual measured dose rate for the first ten casks stored in the ISFSI =0.0249 mrem-per, hour.

NAC-UMS Casks Using the calculated value from the NAC evaluation located in Table 6-6, "2x6 Cask Array Combined Dose Rates", the total dose rate (gammas and neutrons) at a distance of 70 meters is 1125.6 mrem/yr. This equates to:

(1125.6 mrem/yr) / (8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> per yr) = 0.128 mrem per hour Total Expected Dose Rate at Owner Controlled Fence at Top of Berm Ten TN-32A Casks (actual) plus (3X) 2X6 Array NAC-UMS Casks (calculated) 0.0249 mrem per hr + 3(0.128) mrem per hr = 0.409 mrem per hr McGuire Nuclear Station ISFSI Page 52 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

Waterway beyond security buoys on other side of berm from ISFSI - 135 meters from ISFSI TN-32A Casks Using the previous equations for skyshine and a distance of 135 meters the skyshine dose (gammas and neutrons) for one cask is 8.24 E-°3 mrem/hr.

(10) Casks X 8.24 E-03 mrem/hr X 150 hrs (residence time/yr) =

12.36 mrem per year Normalized actual dose = 0.0335 X 12.36 mrem/yr = 0.414 mrem per year Total expected dose for ten TN-32A casks (actual) 0.414 mrem per year NAC-UMS Casks Using the calculated value from the NAC evaluation located in Table 6-4, "2x6 Cask Array Scattered Dose Rates", the total dose rate (gammas and neutrons) at a distance of 135 meters is 157.3 mrem/yr. For a residence time of 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> this equates to:

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

2.69 mrems / yr Total Expected Dose at Waterway on Other Side of Berm Ten TN-32A Casks (actual) plus (3X) 2X6 Array NAC-UMS Casks (calculated) 0.414 mrem per year + 3(2.69) mrem per year = 8.48 mrem per year Individual Sited on Exclusion Area Boundary Below Dam -

425 meters from ISFSI.

TN-32A Casks Using the previous equations for skyshine and a distance of 425 meters the skyshine dose (gammas and neutrons) for one cask is 2.48 E-0 4 mrem/hr.

(10) Casks X 2.48 E"04 mrem/hr X 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> per year =

21.7 mrem / yr Normalized actual dose = 0.0335 X 21.7 mremlyr = 0.727 mrem / yr Total expected dose for ten TN-32A casks (actual) 0.727 mrem / yr NAC-UMS Casks Using the calculated value from the NAC evaluation located in Table 6-4, "2x6 Cask Array Scattered Dose Rates", the total dose McGuire Nuclear Station ISFSI Page 53 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

rate (gammas and neutrons) at a distance of 425 meters is 4.6 mrem/yr.

Total Expected Dose at Exclusion Area Boundary Ten TN-32A Casks (actual) plus (3X) 2X6 Array NAC-UMS Casks (calculated) 0.727 mrem per year + 3(4.6) mrem per year = 14.5 mrem per year 6.2.2 §72.104(b) - OperationalRestrictions The ISFSI is sited in such a way that direct radiation to the surroundings are minimized due to the berm to the north and the fall of the land to the west, which are the two directions the ISFSI is closest to the public.

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

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

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

6.4 References

1. TN Calc 1083-20, "TN-32 Cask for Duke Power, TN-32 MCMP Models for Determining Off-Site Doses," Rev. 0, dated 4/06/2000
2. NAC Calc 12418-5001, "Skyshine Evaluation of McGuire ISFSI,"

Rev.0, dated 11/26/03

3. NRC Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I"
4. Duke Energy McGuire Nuclear Station Procedure No. RPMP 7-8, "Maintaining RCZs Associated with ISFSI" McGuire Nuclear Station ISFSI Page 54 of 70 10 CFR 72.212 Evaluation Report, NAC-UMS, Rev. 04

McGUIRE NUCLEAR STATION ASSESSMENT OF RADIATION DOSE FROM RADIOACTIVE EFFLUENTS AND ALL URANIUM FUEL CYCLE SOURCES TO MEMBERS OF THE PUBLIC (January 1, 2010 through December 31, 2010)

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 and for the calendar year of this report. The effluent dose calculations consider radionuclides identified as part of the liquid and gaseous wastes sample and analysis program.

Radioactive liquid and gaseous wastes are sampled and analyzed per the requirements in Selected Licensee Commitment (SLC) Table 16.11.1-1, "Radioactive Liquid Waste Sampling and Analysis Program", and SLC Table 16.11.6-1, "Radioactive Gaseous Waste Sampling and Analysis Program". Included in the gaseous effluent dose calculations is an estimate of the dose contributed by Carbon-14 (Ref. "Carbon-14Supplemental Information",contained in the ARERR for further information). The "Fuel Cycle Calculation" attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 8 km of McGuire for the calendar year of this report to show conformance with 40CFR1 90. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 1 st Quarter 2010 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS Quarter 1 2010 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD BONE 2.17E-01 1.50E+01 1.45E+00 Maximum Organ Dose Receptor Location: 1.5 Mile NE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage C-14 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS Quarter 1 2010 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Ql - Maximum Gamma Air Dose 1.24E-02 i.OOE+01 1.24E-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 Ql - Maximum Beta Air Dose 4.50E-03 2.OOE+01 2.25E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide' Percentage AR-41 9.69E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2nd Quarter 2010

-- IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS Quarter 2 2010 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD BONE 2.09E-01 1.50E+01 1.40E+00 Maximum Organ Dose Receptor Location: 1.5 Mile NE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage C-14 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS Quarter 2 2010 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose 1.03E-02 1.00E+01 1.03E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.93E+01 Q2 - Maximum Beta Air Dose 3.74E-03 2.00E+01 1.87E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.70E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2010

- IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS Quarter 3 2010 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD BONE 2.43E-01 1.50E+01 1.62E+00 Maximum Organ Dose Receptor Location: 1.5 Mile NE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage C-14 1.OOE+02

= NOBLE GAS DOSE LIMIT ANALYSIS= Quarter 3 2010 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q3 - Maximum Gamma Air Dose 1.21E-02 1.OOE+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 9.97E+01 Q3 - Maximum Beta Air Dose 4.34E-03 2.OOE+01 2.17E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.81E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4t Quarter 2010 IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS Quarter 4 2010 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD BONE 2.49E-01 1.50E+01 1.66E+00 Maximum Organ Dose Receptor Location: 1.5 Mile NE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage C-14 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS Quarter 4 2010 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Gamma Air Dose 1.33E-02 1.OOE+01 1.33E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.99E+01 Q4 - Maximum Beta Air Dose 4.75E-03 2.OOE+01 2.37E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.91E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2010

= IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS Annual 2010 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD BONE 9.18E-01 3.OOE+01 3.06E+00 Maximum Organ Dose Receptor Location: 1.5 Mile NE Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage C-14 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS Annual 2010 Dose Limit  % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Gamma Air Dose 4.82E-02 2.OOE+01 2.41E-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 Yr - Maximum Beta Air Dose 1.73E-02 4.00E+01 4.33E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.78E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 1 st Quarter 2010

= BATCH LIQUID RELEASES Quarter 1 2010 -

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD GILLI 7.82E-02 1.OOE+01 7.82E-01 Q1 - Total Body Dose CHILD 7.69E-02 3.OOE+00 2.56E+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 9.94E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 1 2010 -

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (orem) Limit Ql - Maximum Organ Dose CHILD LIVER 5.76E-04 1.00E+01 5.76E-03 Ql - Total Body Dose CHILD 5.76E-04 3.OOE+00 1. 92E-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 1.00OE+02

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

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2010 BATCH LIQUID RELEASES Quarter 2 2010 -

Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (orem) Limit Q2 - Maximum Organ Dose CHILD LIVER 2.15E-02 1.00E+01 2.15E-01 Q2 - Total Body Dose CHILD 1.62E-02 3.00E+00 5.40E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 7.03E+01 CS-137 2.52E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.31E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 2 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 1.19E-03 1.OOE+01 1. 19E-02 Q2 - Total Body Dose CHILD 1.19E-03 3.OOE+00 3.96E-02 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

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

Nuclide Percentage H-3 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2010

= BATCH LIQUID RELEASES Quarter 3 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q3 - Maximum Organ Dose CHILD LIVER 4.18E-02 1.OOE+01 4.18E-01 Q3 - Total Body Dose CHILD 3.59E-02 3.00E+00 1.20E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 8.31E+01 CS-137 1.45E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.678+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 3 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 9.85E-04 1.OOE+01 9.85E-03 Q3 - Total Body Dose CHILD 9.85E-04 3.OOE+00 3.28E-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 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4 th Quarter 2010

= BATCH LIQUID RELEASES Quarter 4 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 2.20E-02 1.OOE+01 2.20E-01 Q4 - Total Body Dose CHILD 1.93E-02 3.OOE+00 6.43E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 8.52E+01 CS-137 1.27E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.71E+01 CONTINUOUS LIQUID RELEASES (WC) Quarter 4 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 6.42E-04 1.OOE+01 6.42E-03 Q4 - Total Body Dose CHILD 6.42E-04 3.OOE+00 2.14E-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 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2010

= BATCH LIQUID RELEASES Annual 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Yr - Maximum Organ Dose CHILD LIVER 1.57E-01 2.OOE+01 7.83E-01 Yr - Total Body Dose CHILD 1.41E-01 6.OOE+00 2.35E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 8.80E+01 CS-137 1.02E+01 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) Annual 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit

-ganDose CHILD LIVER 3.10E-03 Yr - Maximum Or

  • Dose 2.00E+01 1.55E-02 CHILD 3.10E-03 Yr - Total Body 6.00E+00 5.17E-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 00

-+-2 H-3 1.00OE+02

Attachment 7 Radioactive Waste Systems

MEMO TO:

Annual Radioactive Effluent Release Report Reference SLC 16.11.17 element to identify any licensee initiated major changes to Radioactive Waste Systems (liquid, gaseous, and solid).

No major changes to design or function and no UFSAR updates resulting from major changes to the Radioactive Waste Systems (liquid, gaseous and solid) during the 2010 period.

Attachment 8 Inoperable Monitoring Equipment

Memo to: 2010 Annual Radiological Effluent Release Report

Subject:

SLC 16.11.2 Radioactive Liquid Effluent Monitoring Instrumentation, TABLE 16.11.2-1, Item 1.c. Radiation Monitor EMF-44 Containment Ventilation Unit Condensate Line, Item 1.d.

Radiation Monitor EMF-44 Minimum Flow Device, Item 3.a. Continuous Composite Sampler Containment Ventilation Unit Condensate Line, and Item 4.b. Containment Ventilation Unit Condensate Line Flow Rate Measurement Device. All of these instruments were considered inoperable due to 1WLLP-5900 flow was inoperable which affected the operability of all instruments.

Topic: The above instrument(s) exceeded the SLC condition E when the channel was NOT restored to OPERABLE status within 30 days. Condition G requires a report in the 2010 Annual Radioactive Effluent Report explaining why the inoperability was not corrected within the specified Completion Time. PIP M-10-4207 was generated to ensure the report is submitted as required per SLC.

Risk Assessment: The Containment Ventilation Unit Condensate Drain Tank (CVUCDT) receives drains from the VL units condensate and normally contain tritium and Cesium-137. Any reactor coolant leakage which becomes airborne will condensate and collect in the CVUCDT. Any suspected reactor coolant leakage is monitored closely. The design of the system is based on a continuous release with automatic pump down; however, the system is normally operated as a batch release since the input rate is very low. Procedurally, samples are obtained prior to release. Inoperable actions are to perform 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab sampling if in the continuous release mode; however, continuous releases were not required. Prior to release sampling was performed and sufficient radioactive accountability was maintained.

Summary of Cause for exceeding the 30 days requirement. Reference PIP M-10-4207 for more details. Other PIPs generated were M-10-1219, M-10-2498, M-10-3769.

On 5/19/10 a periodic test of the flow loop failed just outside the acceptable tolerance. At this time the loop was placed in TSAILS. A decision was made to clean the flow element which required a scaffold; however, the scaffold was not erected for about two weeks. Once the scaffold was erected additional testing failed. The unit experienced a forced shutdown due to control rod drop which caused resources to be redirected. Once the unit was back on line additional testing found that the flow loop needed a design/equipment modification change.

Once this was completed the flow loop testing was satisfactory; however, the 30 day action was exceeded.

PIP M-10-4207 states that the cause was a lack of clear communication between I/O Coordinators, Work Window Managers and information provided in the Site Direction Meeting resulted in no one adequately tracking this event for resolution. Even though the loop was

tracked in the daily status OSM report under the Tech Spec action statements requiring action in less than 30 days, it did not elevate into a concern and remained a "I"priority until day 29.

The work order was elevated to an E2 priority per Operations on day 29. This was too late to complete the repairs prior to the 30 day period expiring.

Harry Sloan -7 4&-017-RP General Supervisor McGuire Nuclear Station 3/22/11

Attachment 9 Groundwater Protection Program

2010 ARERR Groundwater Well Data Section Rev. 0 Duke Energy implemented a Groundwater Protection Program in 2007. This program was developed to ensure timely and effective management of situations involving inadvertent releases of licensed material to ground water. As part of this program, McGuire Nuclear Station monitored sixty ground water wells during 2010.

Wells are sampled quarterly, semi-annually or annually. Ground water samples are regularly analyzed for tritium and gamma emitters, with selected wells being analyzed for difficult to detect radionuclides. No gamma or difficult to detect radionuclides (other than naturally occurring radionuclides) were identified in well samples during 2010.

Results from sampling during 2010 confirmed existing knowledge of tritium concentrations in site ground water (shown in the table below).

Results from sampling during 2010 are shown in the table below.

Avg. Tritium Conc. # of Well Name Well Location Conc.(pCi/1) Range Samples M-20 South of Hwg. 73 629 586 - 690 3 M-20R South of Hwg. 73 554 507-610 3 M-21 South of Hwg. 73 209 194-224 3 M-22 South of Hwg. 73 < < 3 M-22R South of Hwg. 73 < < 3 M-23 South of Acs. Rd. < < 3 M-30 WWCB < < 3 M-30R WWCB 261 234 - 276 3 M-31 Access road < < 3 M-32 Main entrance < < 3 M-34R Access road < < 3 M-34DR Access road < < 4 M-35 Access road < < 4 M-42 U-2 Rx. Bldg. 1,893 1,830 - 1,960 4 M-48 U-2 SFP *

  • 0 M-48R U-2 SFP 871 796 - 938 4 M-48DR U-2 SFP 407 285 - 553 4 M-53 North of plant 1,143 1,040 - 1,220 4 M-55 North Admin. Bldg. 169 <- 169 4 M-59 U-2 Doghouse 1,423 1,280 - 1,550 4 M-60 MOC Parking < < 3 M-62 S of RWF 184 169- 198 4 M-64 Rdwst. Bldg. 645 552 - 783 4 M-66 S of SSF 625 588-727 4 M-66R S of SSF < < 4 M-68 U-1 RMWST 942 855- 1,020 4 M-70 U-1 SFP 488 394 - 607 4 M-70R U-1 SFP 209 < - 209 4

2010 ARERR Groundwater Well Data Section Rev. 0 M-70DR U-1 SFP < < 4 M-72 Rdwst. Trench 833 808 - 853 4 M-76 West of U-1 SFP 315 263 - 396 4 M-82 River 2,100 1,170 - 2,700 4 M-84 River 4,315 2,810 - 5,730 4 M-84R River 7,638 7,510 - 7,710 4 M-85 River 1,548 1,320 - 1,700 4 M-87 Landfarm 402 205 - 495 4 M-89 Landfarm 887 553 - 1,040 4 M-90 Landfarm 380 380 1 M-91 East of WC 290 < - 334 4 M-91R East of WC 326 < - 357 4 M-92 N of WC Ponds 378 < - 464 4 M-92R N of WC Ponds < < 3 M-93 North of IHUP 477 404-539 3 M-93R North of IHUP 211 < - 211 3 M-94 SE of IHUP < < 3 M-95 Lower Parking < < 3 M-95R Lower Parking < < 3 M-96 West Parking < < 3 M-96R West Parking < < 3 M-97 East Parking 241 175 - 323 3 M-98 S of Admin. Bldg. < < 3 M-98R S of Admin. Bldg. < < 3 M-100R SE of WC 293 252-348 4 M-101 SE of WC 304 242-355 4 M-102 SW of WC 7,885 7,580 - 8,220 4 M-103 South of WC 2,318 1,900 - 2,660 4 M-103R South of WC 2,825 2,500 - 3 190 4 M-104R West of WC 8,211 7,650 - 9,062 4 M-104DR West of WC 4,963 4,590 - 5,450 4 M-105 Landfarm 352 352 1 MW-i Landfill #1 < < 2 MW-1D Landfill #1 < < 2 MW-2A Landfill #1 < < 2 MW-2D Landfill #1 < < 2 MW-3 Landfill #1 < < 2 MW-3D Landfill #1 < < 2 MW-4 Landfill #1 < < 2 MW-4D Landfill #1 < < 2 MW- 1l Landfill #1 < < 2 MW-l1D Landfill #1 < < 2 MW-12 Landfill #1 < < 2 MW-12D Landfill #1 < < 2 MW-5 Landfill #2 < < 2

2010 ARERR Groundwater Well Data Section Rev. 0 MW-5A Landfill #2 < < 2 MW-6 Landfill #2 < < 2 MW-6A Landfill #2 411 < - 411 2 MW-7 Landfill #2 296 < - 295 2 MW-7A Landfill #2 < < 2 MW-8 Landfill #2 < < 2 MW-8A Landfill #2 < < 2 MW-9 Landfill #2 < < 2 MW-9A Landfill #2 < < 2 MW-I1A Landfill #2 < < 2

  • Insufficient volume in well to sample.

pCi/l - pico curies per liter

< - less than minimum detectable activity, typically 250 pCi/liter 20,000 pCi/I - the Environmental Protection Agency drinking water standard for tritium.

This standard applies only to water that is used for drinking.

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

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