Text

Annual Radioactive Effluent Release Report for 2011
	ML12170A867
Person / Time
Site:	McGuire, Mcguire
Issue date:	04/30/2012
From:	Repko R; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML12170A867 (69)
	v • d • e

Duke

REGIS T.

REPKO Vice President LP 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. com April 30, 2012 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Annual Radioactive Effluent Release Report Pursuant to the requirements of Technical Specification Reporting Requirement 5.6.3 and Section 16.11.17 of the McGuire Selected Licensee Commitments (SLC) Manual, attached is the Annual Radioactive Effluent Release Report. Also included in this report is a CD-Rom of the Offsite Dose Calculation Manual (Revision 53) and the 2011 Process Control Program (PCP) manual.

The following Attachments form the contents of the report: - Summary of Gaseous and Liquid Effluents Report - Supplemental Information - Solid Waste Disposal Report - Meteorological Data - Unplanned Offsite Releases - Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (Includes Fuel Cycle Dose Calculation Results) - Radioactive Waste Systems - Inoperable Monitoring Equipment - Groundwater Protection Program Questions concerning this report should be directed to Ken Ashe, McGuire Regulatory Compliance at (980) 875-4535.

Regis T. Repko Attachments www.duke-energy.comr

NRC Document Control Desk April 30, 2012 Page 2 cc:

Mr. Victor McCree, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Without CDs:

Mr. Jon Thompson NRC Project Manager Nuclear Regulatory Commission 11555 Rockville Pike (Mail Stop 0-8 G9A)

Rockville, MD 28052-2738 Mr. John Zeiler Senior Resident Inspector McGuire Nuclear Station Mr. W.L. Cox, III, Section Chief North Carolina Department of Environment and Natural Resources Division of Environmental Health Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645 INPO Records Center 700 Galleria Place, Suite 100 Atlanta, GA 30339-5957

Attachment I

Summary of Gaseous and Liquid Effluents Report

McGUIRE NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 2011 through December 31, 2011)

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 2011 (Ref.

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

TABLE IA EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 GASEOUS EFFLUENTS -

SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2011 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation

1. Total Release

2.

Avg. Release Rate B. Iodine-131

1. Total Release

2.

Avg. Release Rate C. Particulates Half Life

1. Total Release

2.

Avg. Release Rate D.

Tritium

1. Total Release

2.

Avg. Release Rate E.

Carbon-14

1. Total Release

2.

Avg. Release Rate Gases Ci 6.1OE-01 pCi/sec 7.85E-02 Ci 5.97E-06 pCi/sec 7.68E-07

>= 8 days Ci O.OOE+00 pCi/sec 0.OOE+00 Ci 2.61E+01 pCi/sec 3.35E+00 Ci 3.98E+00 pCi/sec 5.12E-01 1.01E+00 5.84E-01 4.90E-01 2.69E+00 1.28E-01 7.35E-02 6.17E-02 8.53E-02 1.81E-06 2.78E-06 0.OOE+00 1.06E-05 2.30E-07 3.50E-07 0.OOE+00 3.35E-07 0.OOE+00 2.78E-06 4.28E-06 7.06E-06 0.OOE+00 3.50E-07 5.39E-07 2.24E-07 3.14E+01 3.45E+01 3.81E+01 1.30E+02 3.99E+00 4.34E+00 4.79E+00 4.12E+00 5.21E+00 4.96E+00 5.01E+00 1.92E+01 6.62E-01 6.24E-01 6.31E-01 6.08E-01 F. Gross Alpha Radioactivity

1. Total Release Ci

2.

Avg. Release Rate pCi/sec

0. OOE+00

0. OOE-i-0

0. OOE+00

0. OOE+00 0.OOE+00 0.OOE+00 O.OOE+00

TABLE lB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 GASEOUS EFFLUENTS -

ELEVATED RELEASES -

CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2011 Unit QTR 1

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 QTR 2 QTR 3 QTR 4 YEAR

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 GASEOUS EFFLUENTS -

ELEVATED RELEASES -

BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2011 Unit QTR 1

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 QTR 2 QTR 3 QTR 4 YEAR

TABLE iC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 GASEOUS EFFLUENTS -

GROUND RELEASES -

CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2011 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases No Nuclide Activities

2.

Iodines 1-131 Totals for Period...

3. Particulates Half Life BE-7 CO-58 Totals for Period...

4.

Tritium H-3

5.

Carbon-14 C-14 Ci 5.97E-06 Ci 5.97E-06

>= 8 days Ci 0.00E+00 Ci 0.00E+00 Ci 0.00E+00

1. 81E-06 1.81E-06

0. 00E+00

0. OOE+00

0. 00E+00 2.78E-06 2.78E-06

0. 00E+00

2. 78E-06 2.78E-06

0. OOE+00

0. 00E+00

2. 90E-06

1. 38E-06 4.28E-06

1. 06E-05 1.06E-05

2. 90E-06 4.16E-06

7. 06E-06 Ci 2.54E+01 3.11E+01 3.38E+01 3.65E+01 1.27E+02 Ci 1.19E+00 1.56E+00 1.49E+00 1.50E+00 5.75E+00

6.

Gross Alpha Radioactivity

- No Nuclide Activities **

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 GASEOUS EFFLUENTS GROUND RELEASES -

BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2011 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Gases AR-41 Ci 5.81E-01 5.70E-01 5.66E-01 4.75E-01 2.19E+00 KR-85 Ci 9.37E-06 0.OOE+00 0.OOE+00 2.52E-07 9.62E-06 KR-85M Ci 0.OOE+00 2.53E-03 0.OOE+00 0.OOE+00 2.53E-03 KR-87 Ci 0.OOE+00 6.23E-05 0.OOE+00 0.OOE+00 6.23E-05 KR-88 Ci 0.OOE+00 3.23E-03 0.OOE+00 0.OOE+00 3.23E-03 XE-131M Ci 3.69E-06 0.00E+00 O.OOE+00 1.41E-14 3.69E-06 XE-133 Ci 2.61E-02 3.33E-01 1.66E-02 1.42E-02 3.90E-01 XE-133M Ci 7.45E-04 8.90E-03 0.OOE+00 0.OOE+00 9.65E-03 XE-135 Ci 2.64E-03 8.81E-02 2.12E-03 4.84E-04 9.33E-02 Totals for Period...

Ci 6.10E-01 1.01E+00 5.84E-01 4.90E-01 2.69E+00

2.

Iodines No Nuclide Activities

3. Particulates Half Life >= 8 days No Nuclide Activities

4.

Tritium H-3 Ci 6.23E-01 2.27E-01 6.85E-01 1.59E+00 3.13E+00

5.

Carbon-14 C-14 Ci 2.79E+00 3.65E+00 3.47E+00 3.51E+00 1.34E+01

6.

Gross Alpha Radioactivity

- No Nuclide Activities

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 LIQUID EFFLUENTS -

SUMMATION OF ALL RELEASES McGuire Nuclear Station Units 1 & 2 REPORT FOR 2011 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products

1. Total Release Ci 2.25E-02

2. Average Diluted Concentration

a.

Continuous Releases pCi/ml 0.OOE+00

b.

Batch Releases pCi/ml 3.06E-I1 B.

Tritium

1. Total Release Ci 8.71E+02

2. Average Diluted Concentration

a.

Continuous Releases pCi/ml 4.03E-08

b.

Batch Releases pCi/ml 1.18E-06 C. Dissolved and Entrained Gases

1. Total Release Ci 3.43E-05

2. Average Diluted Concentration

a.

Continuous Releases pCi/ml 0.00E+00

b.

Batch Releases pCi/ml 4.66E-14 D. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00

2.

Average Diluted Concentration

a.

Continuous Releases pCi/ml 0.OOE+00

b.

Batch Releases pCi/ml 0.00E+00 2.33E-02 2.32E-02 2.lOE-02 9.OOE-02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.44E-11 2.45E-11 2.21E-11 2.51E-11 1.85E+02 2.57E+02 1.99E+02 1.51E+03 8.25E-09 4.08E-08 7.94E-09 2.56E-08 1.93E-07 2.70E-07 2.10E-07 4.20E-07 1.73E-05 6.14E-06 2.04E-06 5.98E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.81E-14 6.48E-15 2.15E-15 1.67E-14 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 9.17E+07 9.63E+07 9.25E+07 5.64E+08 8.78E+05 1.40E+06 1.18E+06 5.80E+06 3.23E+10 2.61E+10 3.OOE+l0 1.36E+l1 9.57E+ll 9.47E+ll 9.49E+ll

'3.59E+12 E.

Volume of Liquid Waste

1. Continuous Releases

2. Batch Releases liters 2.84E+08 liters 2.33E+06 F. Volume of Dilution Water

1. Continuous Releases liters 4.76E+10

2.

Batch Releases liters 7.36E+l1

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 LIQUID EFFLUENTS -

CONTINUOUS MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2011 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Activation Products

- No Nuclide Activities **

2.

Tritium H-3 Ci 1.93E+00 2.67E-01 1.07E+00 2.39E-01 3.50E+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 1/1/11 TO 1/1/12 LIQUID EFFLUENTS BATCH MODE McGuire Nuclear Station Units 1 & 2 REPORT FOR 2011 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission AG-108M AG-1IOM BE-7 CD-115 CO-57 CO-58 CO-60 CR-51 CS-134 CS-137 FE-59 1-131 K-40 LA-140 MN-54 NB-95 NB-97 SB-122 SB-124 SB-125 SN-113 SR-90 SR-92 TE-123 ZN-65 ZR-95 ZR-97 and Activation Products Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 7.82E-06

2. 85E-04

1. 50E-04

0. OOE+00

1. 06E-04

3. 85E-03

1. 1OE-02 2.57E-03

5. 30E-05

1. 17E-03 7.33E-05

0. OOE+00

1. 01E-05

0. OOE+00 1.20E-03

3. 72E-04 3.78E-05

0. OOE+00 4.18E-05

1. 31E-03

7. 01E-05

0. OOE+00 3.78E-06

0. OOE+00 8.07E-05 8.80E-05

1. 78E-05

3. 61E-05 4.45E-05

2. 98E-04

0. OOE+00

6. 96E-05 4.19E-03 7.51E-03 6.40E-03

0. OOE+00 3.35E-04 3.22E-04

0. OOE+00

0. OOE+00 8.34E-04 5.03E-04

6. 02E-05

0. OOE+00

5. 04E-04

1. 86E-03

0. OOE+00

1. 57E-05

0. OOE+00

1. 12E-04 2.34E-04

3. 03E-06

4. 63E-05

1. 08E-04 5.45E-04

0. OOE+00

8. 1OE-05

2. 10E-03 1.40E-02

1. 59E-03

1. 57E-05

4. 91E-05 8.39E-05 2.56E-06

0. OOE+00

1. 91E-06

1. 26E-03 3.34E-04

8. 44E-05

7. 72E-06

1. 29E-04 2.47E-03

0. OOE+00

7. 94E-05 2.28E-06 9.16E-06

1. 57E-04

3. 45E-05

0. OOE+00 9.26E-06

3. 60E-05 6.46E-05

5. 1OE-06

8. 65E-06 4.34E-03 5.30E-03

7. 74E-03

0. OOE+00

1. 05E-05

1. 59E-04

0. OOE+00

0. OOE+00 4.15E-04 9.82E-04

1. 33E-05

0. OOE+00 2.75E-04

1. 05E-03

5. 66E-06

0. OOE+00

1. 66E-05 2.25E-05 5.41E-04

0. OOE+00

9. 95E-05

4. 73E-04

1. 06E-03

5. 1OE-06

2. 66E-04

1. 45E-02

3. 78E-02

1. 83E-02

6. 87E-05

1. 56E-03

6. 38E-04

2. 56E-06

1. 01E-05

1. 91E-06

3. 72E-03

2. 19E-03

1. 96E-04

7. 72E-06

9. 50E-04

6. 68E-03

7. 57E-05

7. 94E-05

2. 18E-05

2. 58E-05

3. 72E-04

8. 98E-04

2. 08E-05 Totals for Period...

Ci

2. Tritium H-3 Ci

3.

Dissolved and Entrained Gases AR-41 Ci XE-133 Ci XE-135 Ci XE-135M Ci 2.25E-02 2.33E-02 2.32E-02 2.10E-02 9.OOE-02 8.69E+02 1.84E+02 2.56E+02 1.99E+02 1.51E+03

0. OOE+00

1. 70E-05

1. 73E-05

0. OOE+00 5.06E-06

3. 66E-06

8. 63E-06

0. OOE+00

0. OOE+00 6.14E-06

0. OOE+00

0. OOE+00 2.04E-06

5. 06E-06

2. 68E-05

2. 60E-05 2.04E-06 Ci 3.43E-05 1.73E-05 6.14E-06 2.04E-06 5.98E-05 Totals for Period...

4.

Gross Alpha Radioactivity No Nuclide Activities Supplemental Information

McGUIRE NUCLEAR STATION SUPPLEMENTAL INFORMATION (January 1, 2011 through December 31, 2011)

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 2011 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 recommends 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 2011 Annual Radioactive Effluent Release Report (ARERR) contains estimates of C-14 radioactivity released in 2011, 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 2011 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 2011 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 CO2 (Ref. EPRI TR-105715). For the McGuire 2011 ARERR a value of 80% organic C-14 is assumed.

Page 2 of 2 Public dose estimates from airborne C-i14 are performed using dose models in NUREG-0 133 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 from McGuire in 2011 is well below the 1 OCFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit).

McGUIRE NUCLEAR STATION 2011 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I.

REGULATORY LIMITS -

PER UNIT A.

NOBLE GASES -

AIR DOSE

1.

CALENDAR QUARTER -

GAMMA DOSE =

5 MRAD

2.

CALENDAR QUARTER -

BETA DOSE

= 10 MRAD

3.

CALENDAR YEAR GAMIMA DOSE = 10 MRAD

4.

CALENDAR YEAR BETA DOSE

= 20 MRAD B.

LIQUID EFFLUENTS -

DOSE

1.

CALENDAR QUARTER -

TOTAL BODY DOSE =

2.

CALENDAR QUARTER -

ORGAN DOSE

=

3.

CALENDAR YEAR TOTAL BODY DOSE =

4.

CALENDAR YEAR ORGAN DOSE

=

1.5 MREM 5 MREM 3 MREM 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 IOCFR20, 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.

A

SUMMARY

DESCRIPTION OF THE METHOD USED FOR ESTIMATING OVERALL ERRORS ASSOCIATED WITH RADIOACTIVITY MEASUREMENTS IS PROVIDED AS PART OF THE "SUPPLEMENTAL INFORMATION" ATTACHMENT.

V.

BATCH RELEASES A. LIQUID EFFLUENT

1. 2.96E+02 = TOTAL NUMBER OF BATCH RELEASES

2.

2.15E+04 = TOTAL TIME (MIN.)

FOR BATCH RELEASES.

3.

1.50E+02 = MAXIMUM TIME (MIN.)

FOR A BATCH RELEASE.

4.

7.25E+01 = AVERAGE TIME (MIN.)

FOR A BATCH RELEASE.

5.

5.OOE+00 = MINIMUM TIME (MIN.)

FOR A BATCH RELEASE.

6.

1.80E+06 = AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).

B.

GASEOUS EFFLUENT

1. 4.20E+01 = TOTAL NUMBER OF BATCH RELEASES.

2.

1.11E+06 = TOTAL TIME (MIN.)

FOR BATCH RELEASES.

3.

5.32E+04 = MAXIMUM TIME (MIN.)

FOR A BATCH RELEASE.

4.

2.65E+04 = AVERAGE TIME (MIN.)

FOR A BATCH RELEASE.

5.

1.OOE+00 = MINIMUM TIME (MIN.)

FOR A BATCH RELEASE.

VI.

ABNORMAL RELEASES (SEE "UNPLANNED OFFSITE 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%

Solid Waste Disposal Report

REPORT PERIOD JANUARY - DECEMBER 2011 McGUIRE NUCLEAR STATION SOLID RADIOACTIVE WASTE SHIPPED TO DISPOSAL FACILITIES TYPES OF WASTES SHIPPED Waste from Liquid Systems (A) dewatered powdex resin (brokered)

(B) dewatered powdex resin (C) dewatered bead resin (brokered)

(D) dewatered bead resin (E) dewatered radwaste system resin (F) dewatered primary bead resin (G) dewatered mechanical filter media (H) dewatered mechanical filter media (brokered)

(I) solidified waste Dry Solid Waste (A) dry active waste (compacted) dry active waste (non-compacted) dry active waste (brokered/compacted) dry active waste (brokered/non-compacted)

(B) sealed sources/smoke detectors (C) sealed sources (D) irradiated components Totals Number of Shipments none none none none none none none 4

Number of Container Disposal Volume Waste Total Containers Type ft3 m3 Class Curies 4

DBP 291.2 8.25 A/U 1.43E+00 none none none none 25 none none none 29 77 DBP 4529.7286 128.27 A/U 4.080E-01 1.840E+00 81 4820.9286 136.52 3/1/2012

MCGUIRE NUCLEAR SITE

SUMMARY

OF MAJOR RADIONUCLIDE COMPOSITION 2011 Type of waste Nuclide

% Abundance Fl_- /aste from lquid system s:

A. Dewatered Powdex Resin (brokered)

No shipments in 2011 B. Dewatered Powdex Resin No shipments in 2011 C. Dewatered Bead Resin (brokered)

No shipments in 2011 D. Dewatered Bead Resin No shipments in 2011 E. Dewatered Radwaste System Resin (brokered)

No shipments in 2011 F. Dewatered Primary Bead Resin (brokered)

No Shipments in 2011 G. Dewatered Mechanical Filter Media No shipments in 2011 H. Dewatered Mechanical Filter Media (brokered) 2011 -0023 Nuclide

%Abundance Mn-54 3.88 Co-57

.38 Co-58 1.54 Co-60 29.64 Cs-137

.35 Fe-55 46.52 Ni-63 16.41 Zr-95

.03 Ce-144

.67 Sr-90

.09 Sn-113

.03 Zn-65

.44 I

2011-0024 Nuclide Mn-54 Co-57 Co-58 Co-60 Cs-137 Cs-134 Fe-55 Ni-63 C-14 Ce-144 Sb-1 25 Sr-90 Sn-113 Zn-65 Tc-99 Nuclide Mn-54 Co-57 Co-60 Cs-1 37 Cs-1 34 Fe-55 Ni-63 C-14 Ce-144 Sb-125 Zn-65 Tc-99 Nuclide 2011 -0028

%Abundance 3.11

.18

.10 29.03 1.43

.27 46.92 17.17

.52

.18

.46

.03

.01

.18

.41

%Abundance 2.03

.09 29.44 2.04

.33 44.81 19.06

.83

.04

.61

.08

.64

%Abundance

.18 3.51 3.12

.27 25.97 19.86

.11 20.18

.22 9.10 6.50

.49 4.14

.29

.32 1.94

.52

.02

.29

.21

.57

.01 2.18 2011 -0030 Be-7 Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 H-3 C-14 Zr-95 Ce-144 Sb-1 24 Sb-125 Sr-89 Sr-90 Sn-113 Ag-108M Zn-65 Hf-1 81 Nb-95 2

1. Solidified Waste No shipments in 2011

2. Dry Solid Waste:

A. Dry Active Waste (compacted)

Compaction no longer performed on-site.

Dry Active Waste (non-compacted)

No shipments in 2011 Dry Active Waste (brokered/compacted)

No shipments in 2011 Dry Active Waste (brokered/non-compacted) 2011 -0001 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 H-3 Zr-95 Ce-144 Sb-124 Sb-125 Ru-103 Sn-113 Zn-65 Hf-181 Nb-95

%Abundance 25.64 2.38

.10 21.17 7.92

.02 26.91 1.82 1.63

.71 4.41

.06

.10

.30

.03

.22

.57

.04 5.98 3

2011 -0002 2011 -0003 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-1 37 Fe-55 Fe-59 Ni-63 H-3 Zr-95 Ce-144 Sb-124 Sb-125 Ru-1 03 Sn-113 Zn-65 Hf-181 Nb-95 Nuclide Co-60 Cs-137 Cs-134 Fe-55 Ni-63 H-3 Ce-144 Sb-1 25 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 H-3 Zr-95 Ce-144 Sb-124 Sb-125 Ru-103 Sn-113 Zn-65 Hf-181 Nb-95

%Abundance 24.42 2.48

.10 20.13 8.59

.02 28.92 1.70 1.77

.77 4.18

.06

.10

.32

.03

.21

.59

.04 5.58

%Abundance 7.54 1.56

.43 25.20 1.57 57.54 4.21 1.97

%Abundance 22.37 2.59

.10 17.07 10.18

.03 33.30 1.46 2.15

.93 3.54

.06

.08

.38

.02

.19

.59

.03 4.93 2011 -0004 4

2011 -0005 2011 -0006 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-1 37 Fe-55 Fe-59 Ni-63 H-3 Zr-95 Ce-144 Sb-1 24 Sb-125 Ru-103 Sn-113 Zn-65 Hf-181 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-1 24 Sb-1 25 Sn-113 Zn-65 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-1 37 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-1 24 Sb-125 Sn-113 Zn-65 Nb-95

%Abundance 24.62 2.44

.10 21.25 8.18

.02 27.60 1.80 1.67

.73 4.42

.06

.10

.31

.03

.22

.58

.04 5.83

%Abundance 30.72 1.93

.07 22.97 10.44

.12 5.50

.67

.77 10.00

.46

.58

.85

.40

.38 14.13

%Abundance 32.40 1.82

.07 22.47 9.75

.11 5.13

.67

.72 9.84

.44

.57

.80

.39

.36 14.48 2011-0007 5

2011 -0008 2011 -0009 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-1 37 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-125 Sn-113 Zn-65 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-1 24 Sb-125 Sn-113 Zn-65 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-125 Sn-113 Zn-65 Nb-95

%Abundance 32.24 1.84

.07 22.49 9.78

.11 5.16

.67

.72 9.85

.44

.57

.80

.39

.36 14.52

%Abundance 32.11 1.84

.07 22.48 9.87

.11 5.20

.67

.73 9.89

.44

.57

.81

.39

.36 14.47

%Abundance 31.91 1.85

.07 22.60 9.92

.11 5.22

.67

.73 9.90

.44

.57

.81

.39

.36 14.44 2011 -0010 6

2011 -0011 2011 -0012 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-1 37 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-125 Sn-113 Zn-65 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-1 25 Sn-113 Zn-65 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-125 Sn-113 Zn-65 Nb-95

%Abundance 32.61 1.80

.07 22.40 9.63

.11 5.09

.67

.71 9.81

.43

.57

.79

.38

.36 14.57

%Abundance 32.14 1.84

.07 22.53 9.82

.11 5.19

.67

.72 9.89

.44

.57

.81

.39

.36 14.44

%Abundance 32.25 1.83

.07 22.51 9.79

.11 5.16

.67

.72 9.85

.44

.57

.80

.39

.36 14.48 2011 -0013 7

2011 -0017 2011 -0019 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-1 37 Fe-55 Fe-59 Ni-63 H-3 C-14 Zr-95 Ce-144 Sb-1 24 Sb-1 25 Sn-113 Zn-65 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-1 24 Sb-1 25 Sn-113 Zn-65 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-1 25 Sn-113 Zn-65 Nb-95

%Abundance 27.31 2.09

.08 25.24 11.31

.16 6.53

.68 1.13

.20

.02 9.74

.48

.54

.87

.41

.40 12.80

%Abundance 27.80 2.16

.08 23.67 11.88

.14 6.22

.65

.88 10.25

.51

.59

.97

.43

.42 13.35

%Abundance 27.75 2.15

.08 23.82 11.79

.13 6.18

.65

.87 10.29

.51

.59

.96

.43

.42 13.38 2011 -0020 8

2011 -0022 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-1 37 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-1 24 Sb-1 25 Sn-113 Zn-65 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-1 37 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-125 Sn-113 Zn-65 Nb-95 Nuclide 2011 -0025

%Abundance 27.44 2.18

.08 23.81 12.04

.14 6.29

.65

.89 10.29

.52

.59

.98

.44

.42 13.25

%Abundance 23.68 2.47

.09 24.73 13.91

.16 7.28

.63 1.03 10.53

.59

.60 1.13

.47

.48 12.22

%Abundance 32.99 1.78

.07 22.26 9.50

.11 5.01

.67

.70 9.77

.43

.57

.78

.38

.35 14.63 2011 -0026 Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-1 25 Sn-113 Zn-65 Nb-95 9

2011 -0027 2011 -0032 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-1 37 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-125 Sn-113 Zn-65 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-1 25 Sn-113 Zn-65 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-125 Sn-113 Zn-65 Nb-95

%Abundance 32.48 1.82

.07 22.38 9.71

.11 5.11

.67

.71 9.85

.43

.57

.79

.39

.36 14.55

%Abundance 31.80 1.86

.07 22.65 9.98

.11 5.25

.67

.73 9.91

.45

.57

.81

.39

.36 14.38

%Abundance 32.48 1.81

.07 22.39 9.72

.11 5.11

.67

.72 9.85

.44

.57

.79

.39

.36 14.54 2011-0033 10

2011-0035 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-1 37 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-125 Sn-113 Zn-65 Nb-95 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-137 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-125 Sn-113 Zn-65 Nb-95

%Abundance 33.68 1.73

.06 22.04 9.20

.10 4.85

.67

.68 9.71

.42

.56

.75

.37

.34 14.82

%Abundance 21.34 2.65

.10 25.24 15.22

.17 7.90

.62 1.13 10.66

.63

.60 1.23

.49

.51 11.50 2011-0037 1I

2011-0038 Nuclide Cr-51 Mn-54 Co-57 Co-58 Co-60 Cs-1 37 Fe-55 Fe-59 Ni-63 Zr-95 Ce-144 Sb-124 Sb-125 Sn-1 13 Zn-65 Nb-95

%Abundance 16.64 3.11

.11 25.67 18.39

.21 9.52

.57 1.38 10.66

.74

.59 1.48

.54

.59 9.80 B. Sealed Sources C. Sealed Sources/Smoke Detectors D. Irradiated Components No shipments in 2011 No shipments in 2011 No shipments in 2011 12 Meteorological Data

MCGUIRE NUCLEAR STATION 2011 METEOROLOGICAL JOINT FREQUENCY DISTRIBUTION TABLE OF WIND SPEED, WIND DIRECTION, AND ATMOSPHERIC STABILITY USING WINDS AT THE lOm LEVEL (HOURS OF OCCURRENCE) 4

The SAS System

/!7/V/

QoI SECTOR N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW No.

No.

STAB WSCLS (m/s)

A 0.46-0.75 0

0 0

0 0.76-1.00 0

0 0

0 1.01-1.25 0

0 0

0 1.26-1.50 0

0 0

0 1

0 0

1 0

0 0

0 1.51-2.00 1

0 1

0 0

0 1

0 0

0 2.01-3.00 0

0 0

1 0

0 0

1 0

1 3.01-4.00 1

1 0

0 0

0 3

0 0

2 0

0 4.01-5.00 0

0 0

0 1

0 0

1 0

0 0

0 1

0 5.01-6.00 0

0 0

1 2

0 0

1 0

0 6.01-8.00 0

0 0

0 8.01-10.00 0

0 0

0 10.01-Max 0

0 0

0 B

0.46-0.75 0

0 0

0 0.76-1.00 0

0 0

0 1.01-

/

1.25 0

0 0

0 1.26-1.50 0

1 0

0 0

0 1.51-2.00 0

0 0

0 1

0 0

0 2.01-3.00 0

2 2

3 1

0 2

1 0

0 2

0 0

0 3.01-4.00 0

1 0

2 7

0 0

0 4

6 1

2 0

0 0

0 4.01-

5.00 0

0 0

1 0

5 5

2 0

0 1

0 5.01-6.00 0

0 0

1 0

1 4

1 0

0 6.01-8.00 2

0 0

0 4

0 0

0 8.01-10.00 5

0 0

0 10.01-Max 0

0 0

0 C

0.46-0.75 0

0 0

0 0.76-1.00 0

0 0

0 1.01-1.25 0

0 0

0 1.26-1.50 1

2 0

0 0

0 2

0 0

0 2

1 1.51-2.00 5

3 2

1 1

2 0

0 1

5 0

0 0

0 2.01-3.00 2

4 6

11 9

6 2

1 4

9 14 9

5 6

0 0

3.01-4.00 0

6 8

11 5

2 3

1 5

12 33 15 2

1 0

0 4.01-5.00 1

2 5

4 0

1 0

0 2

10 32 9

2 0

1 2

5.01-6.00 3

4 4

0 0

2 0

4 18 5

2 4

8 6

6.01-8.00 12 3

0 0

3 1

0 3

6 13 8.01-10.00 6

5 0

0 0

0 1

0 0

0 3

4 10.01-Max 0

0 0

0 D

0.46-0.75 0

1 1

0 0

0 1

0 0

1 0.76-1.00 2

3 1

1 0

1 3

2 1

1 1

7 1

4 1.01-1.25 11 13 8

2 1

6 2

5 4

2 2

1 5

5 4

9 1.26-1.50 29 18 13 4

13 6

7 9

10 10 15 11 11 14 10 25 1.51-2.00 69 75 49 46 32 26 19 28 42 32 44 54 39 21 26 39 2.01-3.00 123 150 208 135 99 70 64 46 88 109 184 122 60 45 38 45 3.01-4.00 65 103 257 106 72 40 37 6

36 82 256 78 42 41 39 39

4.01-5.00 39 87 192 32 14 15 12 5

18 51 134 43 32 24 49 39 5.01-6.00 27 48 56 2

1 1

6 1

6 11 80 16 12 17 28 37 6.01-8.00 33 26 16 2

1 0

1 5

5 7

37 19 12 15 25 33 8.01-10.00 7

4 2

0 0

1 9

9 1

8 21 17 10.01-Max 1

1 0

0 0

4 0

0 1

2 E

0.46-0.75 1

0 1

1 0

2 1

1 4

5 4

0 1

0 2

0 0.76-1.00 2

1 3

2 1

4 4

4 10 10 11 11 4

2 2

1 1.01-1.25 0

2 1

6 4

10 12 13 10 14 10 7

2 2

1.26-1.50 3

3 5

2 2

3 10 23 14 14 18 17 18 11 6

2 1.61-2.00 6

9 13 9

9 15 22 47 44 59 40 65 29 24 10 6

2.01-3.00 8

14 8

14 19 19 60 26 77 148 151 70 37 17 25 11 3.01-4.00 5

2 9

10 10 9

6 4

12 34 77 22 10 9

19 12 4.01-5.00 1

4 9

0 2

1 1

4 3

6 12 4

2 8

9 8

5.01-6.00 2

4 2

0 0

1 4

2 4

3 1

3 4

1 6.01-8.00 1

0 1

0 0

1 1

10 1

2 2

1 8.01-10.00 0

0 0

2 0

0 1

1 10.01-Max 0

0 0

0 2

1 F

0.46-0.75 1

0 1

1 1

1 0

5 5

10 5

4 2

0 1

1 0.76-1.00 1

2 0

1 1

2 10 16 19 19 11 3

1 4

1.01-1.25 0

0 0

1 0

0 0

0 9

22 22 17 8

2 1

1 1.26-1.50 0

2 1

0 0

0 2

9 15 29 16 18 7

5 1

0 1.51-2.00 1

1 1

0 0

1 1

18 26 49 20 26 10 2

4 1

2.01-3.00 0

2 0

0 0

1 2

7 27 26 39 28 17 9

0 0

3.01-

4.00 4.01-5.00 5.01-6.00 6.01-8.00 8.01-10.00 10.01-Max G

0.46-0.75 0.76-1.00 1.01-1.25 1.26-1.50 1.51-2.00 2.01-3.00 3.01-4.00 4.01-5.00 5.01-6.00 6.01-8.00 8.01-10.00 10.01-Max 0

0 0

0 1

1 1

2 4

2 2

1 0

0 o

0 1

0 o

o o

0 o

0 3

1 o

o o

0 o

0 0

1 0

0 0

0 o

o 0

0 o

0 0

0 o

0 0

0 o

0 0

0 o

o 0

0 o

o 0

0 o

o 3

3 o

o 2

5 o

o 0

4 o

o 0

1 o

o 0

6 o

o 0

4 o

0 0

0 o

0 0

0 o

o 0

0 o

0 0

0 o

o 0

0 0

0 o

1 0

0 o

o 25 11 36 31 38 22 16 14 17 7

5 8

0 1

0 0

0 o

o 0

o o

o 0

10 4

9 4

5 4

5 2

6 1

3 2

0 0

Unplanned Offsite Releases

Jmanuy25,2011 Memorandum To: Annual Radioactive Effluent Release Report CC:

Steve Mooneyhan, H. J. Sloan, Chris Whitener, C.D. Ingram, Kay Crane From:

William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit 1 Vent Reference PIP M-11-0141 Event Summary:

See referenced PIP for details.

On 1/08/11 Radiation Protection (RP) Shift Group was performing routine weekly sampling of the Unit 1 Vent which includes noble gas and tritium grab samples. The airborne tritium concentration from the vent sample was within normal limits. The Xe-133 identified @ -9.OE-8 uci/ml was not expected. RP Supervision was contacted and investigation indicated a loss of volume from the Waste Gas Decay Tank (WGDT)-E. There was no indication seen during the event on Vent gas monitor EMF 36 (L) due to Xe-133 activity being below EMF delectability limit. Chemistry personnel verified WGDT-E isolation valves closed. Follow up sampling at the Unit 1 Vent indicated no activity identified on 1/9/11 @ 05:32. WGDT-E was later sampled to identify nuclides present during the loss of volume event. This sample was used to account for radioactivity released out the Unit 1 Vent via Gaseous Waste Release #2011003. Conservative estimate 1.66E-4 curies of fission and activation gas (noble gas) were released. The quantity of gas released was insignificant. Trending the Unit Vent Monitor 1EMF-36 (L) indicated no counts above normal background. No offsite release limits were challenged. No reporting criteria thresholds reached.

The total Noble gas activity released was reported on (GWR) Gaseous Waste Release # 2011003.

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 many orders of magnitude below the limit specified by Selected Licensee Commitments and Code of Federal Regulations.

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

Mardh28,2011 Memorandum To: Annual Radioactive Effluent Release Report CC:

Steve Mooneyhan, H. J. Sloan, Chris Whitener, C.D. Ingram, Kay Crane From:

William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit 1 Vent Reference PIP M-11-1946 Event Summary:

See referenced PIP for details.

On 3/9/11 Chemistry staff rioted a pressure drop in the in-service WGDT-B of-8.Opsi. The WGDT-B pressure loss started on 3/3/11 15:00 hrs and continued until the in-service tank was re-aligned to WGDT-E on 3/9/11 21:32hrs.

Two psi was accounted for in WGDT-A and WGDT-C determined by a pressure increase seen in each tank during the period. Radiation Protection was contacted to perform trending to evaluate unit vent and auxiliary building radioactive gas monitors over the period for any indication of noble gas released to the environment. No indication was identified of a radioactive gas release off site during the period.

WGDT-B was sampled on 3/10/11 to identify the specific radioisotopes and their concentration of the gas potentially leaked off site.

Follow up investigation identified bank isolation valve I WG-263 as having a very small external leak into room 617 which exhausts to the auxiliary building ventilation and to the Unit I vent.

The total Noble gas activity released (1.02E-2 Curies) was reported on (GWR) Gaseous Waste Release

2011018.

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 orders of magnitude below the limit specified by Selected Licensee Commitments and Code of Federal Regulations.

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

May 17,2011 Memorandum To: Annual Radioactive Effluent Release Report CC:

Steve Mooneyhan, H. J. Sloan, Chris Whitener, C.D. Ingram, Kay Crane From:

William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit 1 Vent Reference PIP M-11-3864 Event Summary:

See referenced PIP for details.

On 5/17/11 at 09:26 Operations received a trip I alarm (trip I setpoint 75 cpm) on 1 EMF 36 Unit Vent gas monitor. At 09:43 Operations received a trip 2 alarm on EMF 41(Aux Bid ventilation gas monitor) point #1.

The following time line is established to describe the event:

09:24 WG compressor "A" placed in service by Rad-Waste Chemistry to perform functional verification on 1 WG-23 8 post repair.

09:26 Operations received trip 1 alarm on Unit Vent monitor 1 EMF 36 at -77cpm up from -27cpm.

09:43 Operations received trip 2 alarm on EMF 41 point #1 Auxiliary bld ventilation gas monitor at 590 cpm.

09:45 Operations received annunciator alarm on point #2 at 159 cpm followed by point #4 at 234 cpm.

At - 09:45 Rad-Waste Chemistry performed snoop check of lWG-238 and found it to be leaking externally. Rad-Waste Chemistry immediately secured the alignment to the WGDT-B in-service tank.

Follow up trending showed EMF 41 point #4 returning to 50 cpm at 10:06. (normal is -60 cpm)

Follow up trending of IEMF 36 showed increase from 22 cpm, going to 77 cpm then returning to 35 cpm at 10:01. 1 EMF 36 reached a high of 105 cpm during the event. (normal is 25-30 cpm)

Follow up investigation indicated a loss of 17 psig (694 cubic feet) from WGDT-B.

The most recent sample from WGDT-B in-service tank was used to evaluate radioactive gas released to the Unit 1 Vent. The total Noble gas activity released (2.04E-1 Curies) was reported on (GWR) Gaseous Waste Release (GWR) # 2011039.

The unplanned release of radioactivity 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 Noble gas activity released was 0.204 curies. Calculated dose and doserate to the Total Body, Skin, Gamma Air, and Beta Air were all well below the limits specified by Selected Licensee Commitments and Code of Federal Regulations.

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

May31,2011 Memorandum To: Annual Radioactive Effluent Release Report CC:

Steve Mooneyhan, H. J. Sloan, Chris Whitener, C.D. Ingram, Kay Crane From:

William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit 1 Vent Reference PIP M-11-4129 Event Summary:

See referenced PIP for details.

On the afternoon 5/25/11 the waste gas (WG) system was returned to service after maintenance activities completed. The B WG compressor was used with WGDT-A as the in-service tank.

On 5-27-11 while performing morning rounds the chemistry technician noted WGDT-A was indicating a loss of pressure since the WG system start-up on 5-25-11. Chemistry management was contacted and increased monitoring of WGDT-A was put into place to verify pressure changes.

On the morning of 5-29-11 long term trending of WGDT-A pressure indicated a loss of three psig or 123 cubic feet of noble gas over the period of 5-25-11 through 5-29-11. Radiation Protection was notified and trending of Unit Vent gas monitor (I EMF 36) as well as the Auxiliary bid noble gas monitor (OEMF 41 point 4) showed no increase above background for the period.

On 5-29-11 Chemistry initiated steps to secure WG-B compressor and start WG-A compressor. Follow up pressure trending of WGDT-A showed no pressure loss.

On 5-31-11 WGDT-A in-service tank was sampled to evaluate radioactive gas released to the Unit 1 Vent during this event. The total Noble gas activity released (7.59E-3 Curies) was reported on (GWR) Gaseous Waste Release (GWR) # 2011040.

The unplanned release of radioactivity 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 Noble gas activity released was 0.0076 curies. Calculated dose and doserate to the Total Body, Skin, Gamma Air, and Beta Air were all orders of magnitude below the limits specified by Selected Licensee Commitments and Code Of Federal Regulations.

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

Jn 1,2011 Memorandum To: Annual Radioactive Effluent Release Report CC:

Steve Mooneyhan, H. J. Sloan, Chris Whitener, C.D. Ingram, Kay Crane From:

William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit 1 Vent Reference PIP M-11-3695 Event Summary:

See referenced PIP for details.

On or about 4/9/11 Chemistry technicians identified a pressure decrease in WGDT-B during the period of 4/28/11 through 5/9/11. Noble gas monitors EMF 41 (Aux Bid ventilation) and 1EMF 36 (Unit 1 Vent) showed no increase above normal background during the period. A leak investigation was initiated by Chemistry and I WG-238 diaphragm valve was identified with an external leak. The WG system was shutdown to repair the valve.

Follow up investigation of the decrease in tank pressure indicated a loss of 17 psig (694 cubic feet) from the in-service WGDT-B during the period of 4/3/11 to 5/10/11. WGDT-B was sampled on 5/10/11 to account for the noble gas activity released to the Unit I Vent.

The sample from WGDT-B in-service tank was used to evaluate radioactive gas released to the Unit 1 Vent.

The total Noble gas activity released (2.04E-1 Curies) was reported on (GWR) Gaseous Waste Release (GWR) # 2011043.

The unplanned release of radioactivity 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 Noble gas activity released was 0.204 curies. Calculated dose and doserate to the Total Body, Skin, Gamma Air, and Beta Air were all well below the limits specified by Selected Licensee Commitments and Code of Federal Regulations.

W.C. Spencer Harry J Sloan RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (Includes fuel cycle dose calculation results)

McGUIRE NUCLEAR STATION ASSESSMENT OF RADIATION DOSE FROM RADIOACTIVE EFFLUENTS AND ALL URANIUM FUEL CYCLE SOURCES TO MEMBERS OF THE PUBLIC (January 1, 2011 through December 31, 2011).

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-14 Supplemental 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 1/1/11 TO 1/1/12 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 1 st Quarter 2011

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 1 2011 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q1 -

Maximum Organ Dose CHILD BONE 1.81E-01 1.50E+01 1.20E+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 2011 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Ql -

Maximum Gamma Air Dose 1.31E-02 1.00E+01 1.31E-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 Q1 - Maximum Beta Air Dose 4.68E-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 9.82E+01 6

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2011

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 2 2011 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q2 -

Maximum Organ Dose CHILD BONE 2.36E-01 1.50E+01 1.58E+00 Maximum Organ Dose Receptor Location: 1.5 Mile NE Critical Pathway: Vegetation Major Isotopic Nuclide C-14 Contributors (5% or greater to total)

Percentage 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS===---

Quarter 2 2011 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Q2 -

Maximum Gamma Air Dose 1.36E-02 1.00E+01 1.36E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 Contributors (5% or greater to total)

Percentage 9.39E+01 Q2 -

Maximum Beta Air Dose 5.95E-03 2.OOE+01 2.97E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 XE-133 XE-135 Contributors (5% or greater to total)

Percentage 7.59E+01 1.42E+01 8.79E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2011

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS=======

Quarter 3 2011 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q3 - Maximum Organ Dose CHILD BONE 2.25E-01 1.50E+01 1.50E+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 2011 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Q3 - Maximum Gamma Air Dose 1.27E-02 1.00E+01 1.27E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.98E+01 Q3 - Maximum Beta Air Dose 4.53E-03 2.OOE+01 2.27E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage AR-41 9.88E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4 th Quarter 2011

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Quarter 4 2011 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q4 - Maximum Organ Dose CHILD BONE 2.28E-01 1.50E+01 1.52E+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 2011 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Q4 -

Maximum Gamma Air Dose 1.07E-02 1.OOE+01 1.07E-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 3.80E-03 2.OOE+01 1.90E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 Contributors (5% or greater to total)

Percentage 9.90E+01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 GASEOUS ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2011

IODINE, H3, AND PARTICULATE DOSE LIMIT ANALYSIS======= Annual 2011 Critical Critical Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Yr - Maximum Organ Dose CHILD BONE 8.70E-01 3.OOE+01 2.90E+00 Maximum Organ Dose Receptor Location: 1.5 Mile NE Critical Pathway: Vegetation Major Isotopic Nuclide C-14 Contributors (5% or greater to total)

Percentage 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS===-

Annual 2011 Dose Limit

% of Period-Limit (mrad)

(mrad)

Limit Yr - Maximum Gamma Air Dose 5.01E-02 2.00E+01 2.50E-01 Maximum Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 Contributors (5% or greater to total)

Percentage 9.82E+01 Yr - Maximum Beta Air Dose 1.90E-02 4.00E+01 4.74E-02 Maximum Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Nuclide AR-41 XE-133 Contributors (5% or greater to total)

Percentage 9.15E+01 5.22E+00

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 1't Quarter 2011

=== BATCH LIQUID RELEASES Period-Limit Critical Critical Dose Age Organ (mrem)

Quarter Limit (mrem) 1 2011==....

Max % of Limit Q1 - Maximum Organ Dose CHILD Q1 - Total Body Dose CHILD LIVER 1.30E-01 1.OOE+01 1.30E+00 1.23E-01 3.OOE+00 4.12E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 CS-137 9.40E+01

5. 41E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3

9. 87E+01 CONTINUOUS LIQUID RELEASES (WC)

Critical Critical Dose Period-Limit Age Organ (mrem)

Q1 - Maximum Organ Dose CHILD LIVER 4.16E-03 Q1 - Total Body Dose CHILD 4.16E-03 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 Quarter 1 Limit (mrem) 1.OOE+01 3.OOE+00 2011===-==

Max % of Limit

4. 16E-02

1. 39E-01

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 LIQUID ANNUAL DOSE

SUMMARY

REPOT McGuire Nuclear Station Units 1 & 2 2 nd Quarter 2011 BATCH LIQUID RELEASES Critical Critical Dose Period-Limit Age Organ (mrem)

Quarter 2 Limit (mrem) 2011===...

Max % of Limit Q2 -

Maximum Organ Dose Q2 - Total Body Dose ADULT CHILD GI-LLI 2.29E-02 1.OOE+01 2.29E-01 2.06E-02 3.OOE+00 6.87E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 NB-95

6. 59E+01 2.97E+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)

Critical Critical Dose Period-Limit Age Organ (mrem)

Q2 -

Maximum Organ Dose CHILD LIVER 8.61E-04 Q2 - Total Body Dose CHILD 8.61E-04 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- ---

00

-+02 Quarter 2 Limit (mrem) 2011 --====

Max % of Limit 1.00E+01 8.61E-03 3.00E+00 2.87E-02 H-3 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/i1 TO 1/1/12 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 3 rd Quarter 2011

=== BATCH LIQUID RELEASES Critica Period-Limit Age Q3 - Maximum Organ Dose CHILD Q3 - Total Body Dose CHILD

.1 Critical Dose Organ (mrem)

Quarter Limit (mrem) 3 2011 -_....

Max % of Limit GI-LLI 3.03E-02 1.00E+01 3.03E-01 2.92E-02 3.00E+00 9.74E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.40E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.74E+01 CONTINUOUS LIQUID RELEASES (WC)

Critical Critical Dose Period-Limit Age Organ (mrem)

Q3 - Maximum Organ Dose CHILD LIVER 4.30E-03 Q3 -

Total Body Dose CHILD 4.30E-03 Quarter 3 Limit (mrem) 1.OOE+01 3.OOE+00 2011======

Max % of Limit

4. 30E-02

1. 43E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5%

Nuclide Percentage or greater to total)

H-3

1. OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5%

Nuclide Percentage 3

or greater to total)

H-3 1.00OE+02

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/11 TO 1/1/12 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 4 th Quarter 2011

=== BATCH LIQUID RELEASES Period-Limit Q4 -

Maximum Organ Dose Q4 - Total Body Dose

==

Critical Age ADULT CHILD Critical Organ GI-LLI Dose (trem)

3. OBE-02 2.23E-02 Quarter 4 Limit (mrem) 1.OOE+01 3.OOE+00 2011 Max % of Limit 3.08E-01 7.44E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 NB-95 5.38E+01 4.39E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.92E+01 CONTINUOUS LIQUID RELEASES (WC)---

Critical Critical Dose Period-Limit Age Organ (mrem)

Q4 -

Maximum Organ Dose CHILD LIVER 8.38E-04 Q4 - Total Body Dose CHILD 8.38E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage Quarter Limit (trem) 4 2011======

Max % of Limit 1.OOE+01 8.38E-03 3.OOE+00 2.79E-02 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 1/1/11 TO 1/1/12 LIQUID ANNUAL DOSE

SUMMARY

REPORT McGuire Nuclear Station Units 1 & 2 ANNUAL 2011

=== BATCH LIQUID RELEASES Period-Limit Critical Critical Dose Age Organ (mrem)

Annual Limit (mrem) 2011 Max % of Limit Yr - Maximum Organ Dose CHILD Yr -

Total Body Dose CHILD GI-LLI 1.86E-01 2.OOE+01 9.30E-01 1.79E-01 6.OOE+00 2.98E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.46E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)

Nuclide Percentage H-3 9.84E+01 CONTINUOUS LIQUID RELEASES (WC)

Critical Critical Dose Period-Limit Age Organ (mrem)

Yr -

Maximum Organ Dose CHILD LIVER 1.07E-02 Yr - Total Body Dose CHILD 1.07E-02 Annual 2011 Limit Max % of (mrem)

Limit 2.OOE+01 5.37E-02 6.OOE+00 1.79E-01 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5%

Nuclide Percentage or greater to total)

H-3

1. OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5%

Nuclide Percentage or greater to total)

H-3 1.00OE+02

McGuire Nuclear Station 2011 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 40CFRl90 limits as shown by the following summary:

I. 2011 McGuire 40CFR190 Effluent Dose Summary The 40CFR1 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 = 4.74E-01 mrem Maximum Location: 1.5 Mile, Northeast Sector Critical Age: Child Gas non-NG Contribution: 62%

Gas NG Contribution: <1%

Liquid Contribution: 38%

Maximum Organ (other than TB) Dose = 8.80E-01 mrem Maximum Location: 1.5 Mile, Northeast Sector Critical Age: Child Critical Organ: Bone Gas Contribution: 99%

Liquid Contribution: 1%

lI. 2011 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 Evaluation Report". The maximum dose rate to the nearest real individual from the McGuire ISFSI is conservatively calculated to be less than 4 mrem/yr.

The attached excerpt from the "McGuire Nuclear Site 10CFR72.212 Evaluation Report" is provided to document the method used to calculate the McGuire ISFSI less than 4 mrem/year dose estimate to the nearest real individual.

The following two pages are excerpted from the McGuire Nuclear Site, Independent Spent Fuel Storage Installation, "10CFR72.212 Evaluation Report".

6.0 10 CFR 72.212(b)(5)(iii) - Radioactive Materials in Effluents and Direct Radiation 6.1 Purpose 10 CFR 72.212(b)(5)(iii) requires the general licensee to perform written evaluations, before use and before applying the changes authorized by an amended CoC to a cask loaded under the initial CoC or an earlier amended CoC, that establish that the requirements of 10 CFR 72.104 have been met. A copy of this record shall 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)(5)(iii), demonstrating Duke Energy's compliance with the requirements of 10 CFR 72.104 for the MNS ISFSI.

6.2 Evaluation This evaluation addresses the radiological dose rate from a composite population of all MNS ISFSI cask types.

6.2.1 §72.104(a) - Dose Limits Duke Energy Engineering Instruction MCEI-0400-241 determined that the distance from the nearest residence to the ISFSI is 0.65 miles (1046 meters). Hence, it is conservative to assume that the closest real individual is at least 700 meters from the ISFSI.

Enercon determined the annual total dose (gamma plus neutron) at a distance of 700 meters from all currently loaded casks (10 TN-32A casks and 28 NAC-UMS casks) to be approximately 1.62 mrem. The evaluation was based on actual cask average burn-up (as loaded) and considering cooling time on the storage McGuire Nuclear Station ISFSI Page 43 10 CFR 72.212 Evaluation Report, MAGNASTOR, Rev. 00

pads as of September 1, 2010. The distance at which this dose is calculated (700 meters) is conservative compared to the distance to the closest real individual.

NAC International determined the annual total dose (gamma plus neutron) at a distance of 700 meters from a (future) 2x6 array of MAGNASTOR casks to be approximately 1.01 mrem (2.02 mrem for two arrays). The evaluation was conservatively based on full cask loads of 37 fuel assemblies at the maximum allowable heat load of 35.5 kW. The distance at which this dose is calculated (700 meters) is conservative compared to the distance to the closest real individual.

The total calculated annual public dose from liquid and gaseous effluent pathways averaged over a ten-year period is less than 1 mrem. No other uranium fuel cycle facility contributes significantly to the dose received by the closest real individual.

Based on the above, the calculated annual dose to the closest real individual due to the ISFSI, which is comprised of the currently existing ten TN-32A casks and 28 NAC-UMS5 casks, and up to two 2x6 arrays of MAGNASTOR casks (see Note below), is determined to be less than 4 mrem, and the estimated annual dose due to McGuire power generation is less than 1 mrem. Hence, the total annual dose to the closest real individual (less than 5 mrem) is within the 10 CFR 72.104(a) limit.

Note: As stated above, up to two 2x6 arrays of MAGNASTOR casks are assumed in this evaluation. The first eight MAGNASTOR casks are planned to be placed on a concrete pad currently containing four NAC-UMS casks. This will conservatively count as one 2x6 array. Additional MAGNASTOR casks will be placed on their own concrete pad (the second 2x6 array). Hence, this §72.104(a) evaluation bounds up to 20 MAGNASTOR casks, arranged as described.

McGuire Nuclear Station ISFSI Page 44 10 CFR 72.212 Evaluation Report, MAGNASTOR, Rev. 00 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).

There were 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 2011 period.

Inoperable Monitoring Equipment

ATTACHMENT 8 Inoperable Equipment 1EMF39L - Containment Purge System Noble Gas Monitor Equipment Out of Service 1EMF39L - Containment Purge System Noble Gas Monitor Low Range Duration of Out of Service:

9/19/2011 to 10/4/2011 Out of Service date was based on the day system configuration was potentially affected and found as documented in M-11-7542, Sequence of Event section.

Function of Equipment:

Upon detection of high radiation level, provide alarm and automatic termination of release via containment ventilation isolation.

Regulatory Requirement SLC 16.11.7 - Radioactive Gaseous Effluent Monitoring Instrumentation Not Met:

TABLE 16.11-7-1 INSTRUMENTS - 4. Containment Purge System - Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release (Low Range - EMF - 39)

MODE 1-6, except when isolation valve is closed & locked REMEDIAL ACTION - A, F, I APPLICABILTY - Modes 1 through 6, except when isolation valve is closed & locked.

REMEDIAL ACTIONS - F CONDITION: Noble gas activity monitor providing automatic termination of release inoperable REQUIRED ACTION - F. 1: Suspend PURGING or VENTING of radioactive effluents via this path way.

COMPLETION TIME: Immediately Summary of Issue Reference letter attached.

OTHERS:

There were no other radiation monitor related failures that were not corrected within the specified required completion time in accordance with McGuire SLC.

Memo to: 2011 Annual Radiological Effluent Release Report

Subject:

SLC 16.11.7 F. Suspension of Containment Purge (VP) when 1 EMF39L is inoperable.

PIP M-11-07542 SSPS containment ventilation isolation slave relays are the method 1 EMF39L utilizes to shutdown containment purge upon detection of high radiation (TRIP 2). Without either train of SSPS available, this automatic termination was non-functional. SLC 16.11.7 F. requires immediate suspending of containment purge (VP) when 1 EMF39L is inoperable, this was not performed.

Topic: The above auto termination unavailability was due to Jumpers being incorrectly installed in the Unit 1 SSPS cabinets, such that the VP valves would not have closed after receiving a trip signal from EMF-39. Unit 1 was in Mode 6 at the time of discovery.

Risk Assessment: SSPS containment ventilation isolation slave relays are the method 1 EMF39L utilizes to shutdown containment purge upon detection of high radiation. Without either train of SSPS available, this automatic termination was non-functional.

It was also unknown that this automatic system was inoperable until the time installed jumpers in SSPS cabinets A & B were to be removed from service post-outage.

Normal Unit 1 containment and Unit Vent sampling was performed during the period. No radioactivity above expected outage conditions was identified. Evaluations revealed normal Gaseous Release accounting was being performed during the outage period and no unusual activity was seen during this period.

Summary of Cause: There were two jumpers found to be out of correct configuration in SSPS cabinets A and B. In cabinet A, a jumper had been placed into the incorrect terminal rendering its intended functions described above inoperable and a jumper in Cabinet B had been knocked loose altogether from its correct terminal also rendering its function inoperable. This configuration error was attributed to attention to detail and configuration control of plant equipment. The inoperability was not corrected in the specified completion time because the jumpers in question were inside closed cabinets and was not discovered until it was time to remove them.

Steve Mooneyhan Radiation Protection Mana McGuire Nuclear Station Groundwater Protection Program

2011 ARERR Groundwater Well Data Section 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 2011.

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 2011.

Results from sampling during 2011 confirmed existing knowledge of tritium concentrations in site ground water (shown in the table below).

Results from sampling during 2011 are shown in the table below.

Avg. Tritium Conc.(pCi/1)

Conc.

Range

of Samples Well Name Well Location M-20 South of Hwg. 73 642 626 - 658 2

M-20R South of Hwg. 73 554 539-568 2

M-21 South of Hwg. 73 2

M-22 South of Hwg. 73 2

M-22R South of Hwg. 73 2

M-23 South of Acs. Rd.

2 M-30 WWCB 2

M-30R WWCB 281 261 -300 2

M-31 Access road 2

M-32 Main entrance 2

M-34R Access road 3

M-34DR Access road 4

M-35 Access road 4

M-42 U-2 Rx. Bldg.

2,425 2,100 - 2,720 4

M-48 U-2 SFP 0

M-48R U-2 SFP 782 660 - 946 4

M-48DR U-2 SFP 326 274 - 387 3

M-53 North of plant 1,003 919 - 1,210 4

M-55 North Admin. Bldg.

268 243 - 293 4

M-59 U-2 Doghouse 2,090 1,710 - 2,510 4

M-60 MOC Parking 2

M-62 S of RWF 4

M-64 Rdwst. Bldg.

533 477 - 562 4

M-66 S of SSF 529 473-602 4

M-66R S of SSF 4

M-68 U-1 RMWST 802 728 - 888 4

M-70 U-1 SFP 526 417-700 4

M-70R U-1 SFP 244 212-277 4

2011 ARERR Groundwater Well Data Section M-70DR U-1 SFP

< - 336-4 M-72 Rdwst. Trench 810 794-828 4

M-76 West of U-1 SFP 357 313-399 4

M-82 River 2,220 2,108 - 2,330 4

M-84 River 6,280 5,220 - 6,990 4

M-84R River 7,555 7,300 - 7,830 4

M-85 River 1,575 1,440 - 1,690 4

M-87 Landfarm 656 585 - 697 4

M-89 Landfarm 901 742-1,020 4

M-90 Landfarm 476 467 - 485 2

M-91 East of WC 324 259-395 4

M-91R East of WC 272

< - 325 4

M-92 N of WC Ponds 321 295-347 2

M-92R N of WC Ponds 2

M-93 North of IHUP 560 546 - 574 2

M-93R North of IHUP 223 209 - 236 2

M-94 SE of IHUP 2

M-95 Lower Parking 2

M-95R Lower Parking 2

M-96 West Parking 2

M-96R West Parking 2

M-97 East Parking 227 206 - 248 2

M-98 S of Admin. Bldg.

2 M-98R S of Admin. Bldg.

2 M-100R SE of WC 284 222-401 4

M-101 SE of WC 323 247-395 4

M-102 SW of WC 7,965 7,450 - 8,410 4

M-103 South of WC 2,120 1,930 - 2,240 4

M-103R South of WC 2,150 1,980 - 2,380 4

M-104R West of WC 6,060 3,910 - 7,960 4

M-104DR West of WC 4,328 3,970 - 4,520 4

M-105 Landfarm 292 243 - 340 2

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-11 Landfill #1 2

MW-11D Landfill #1 2

MW-12 Landfill #1 2

MW-12D Landfill #1 2

MW-5 Landfill #2 1

2011 ARERR Groundwater Well Data Section MW-5A Landfill #2 2

MW-6 Landfill #2 2

MW-6A Landfill #2 2

MW-7 Landfill #2 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-10A Landfill #2 2

Insufficient volume in well to sample.

pCi/1 - pico curies per liter

< - less than minimum detectable activity, typically 250 pCi/liter 20,000 pCi/1 - the Environmental Protection Agency drinking water standard for tritium.

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

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

ML12170A867

Contents

Text

Subject:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

==

SUMMARY

Subject:

Navigation menu

ML12170A867

Text

Subject:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

==

SUMMARY

Subject:

Navigation menu

Search