Text

Annual Radioactive Effluent Release Report, January 1, 2016 Through December 31, 2016
	ML17128A451
Person / Time
Site:	Mcguire, McGuire
Issue date:	12/31/2016
From:	; Duke Energy Carolinas
To:	; Office of Nuclear Reactor Regulation
References
	MNS-17-019
	Download: ML17128A451 (327)
	v • d • e

McGuire Nuclear Station Units 1 and 2 Annual Radioactive Effluent Release Report January 1, 2016 through December 31, 2016 Dockets 50-369 and 50-370

Introduction The Annual Radioactive Effluent Release Report is pursuant to McGuire Nuclear Station Technical Specification 5.6.3 and Selected Licensee Commitment 16.11.17. The below listed attachments to this report provide the required information. In addition, the ODCM is included pursuant to McGuire Nuclear Station Technical Specification 5.5.1.

Attachment 1 Summary of Gaseous and Liquid Effluents Attachment 2 Supplemental Information Attachment 3 Solid Radioactive Waste Disposal Attachment 4 Meteorological Data Attachment 5 Unplanned Offsite Releases Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Attachment 7 Information to Support the NEI Ground Water Protection Initiative Attachment 8 Inoperable Equipment Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Attachment 10 Summary of Changes to the Process Control Program Attachment 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems Attachment 12 Errata to a Previous Year's ARERR

Attachment 1 Summary of Gaseous and Liquid Effluents McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 1 Summary of Gaseous and Liquid Effluents This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.

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Attachment 1 Summary of Gaseous and Liquid Effluents McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases

1. Total Release Ci 7.71E-01 3.88E-01 4.23E-01 5.60E-01 2.14E+00

2. Avg. Release Rate µCi/sec 9.80E-02 4.94E-02 5.32E-02 7.05E-02 6.78E-02 B. Iodine-131

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Avg. Release Rate µCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C. Particulates Half-Life 8 days

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Avg. Release Rate µCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Tritium

1. Total Release Ci 1.84E+01 2.19E+01 1.70E+01 2.31E+01 8.05E+01

2. Avg. Release Rate µCi/sec 2.34E+00 2.79E+00 2.14E+00 2.90E+00 2.54E+00 E. Carbon-14

1. Total Release Ci 5.18E+00 5.03E+00 5.51E+00 5.62E+00 2.13E+01

2. Avg. Release Rate µCi/sec 6.59E-01 6.39E-01 6.93E-01 7.07E-01 6.75E-01 F. Gross Alpha

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Avg. Release Rate µCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1-2

Attachment 1 Summary of Gaseous and Liquid Effluents McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Elevated Releases - Continuous Mode

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases N/A Ci - - - - -

Total for Period Ci - - - - -

B. Iodines N/A Ci - - - - -

Total for Period Ci - - - - -

C. Particulates Half-Life 8 days N/A Ci - - - - -

Total for Period Ci - - - - -

D. Tritium N/A Ci - - - - -

E. Carbon-14 N/A Ci - - - - -

F. Gross Alpha Total for Period Ci - - - - -

McGuire Nuclear Station Units 1 and 2 do not have elevated releases.

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Attachment 1 Summary of Gaseous and Liquid Effluents McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Elevated Releases - Batch Mode

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases N/A Ci - - - - -

Total for Period Ci - - - - -

B. Iodines N/A Ci - - - - -

Total for Period Ci - - - - -

C. Particulates Half-Life 8 days N/A Ci - - - - -

Total for Period Ci - - - - -

D. Tritium N/A Ci - - - - -

E. Carbon-14 N/A Ci - - - - -

F. Gross Alpha Total for Period Ci - - - - -

McGuire Nuclear Station Units 1 and 2 do not have elevated releases.

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Attachment 1 Summary of Gaseous and Liquid Effluents McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Ground Releases - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases XE-133 Ci 2.20E-01 0.00E+00 0.00E+00 0.00E+00 2.20E-01 Total for Period Ci 2.20E-01 0.00E+00 0.00E+00 0.00E+00 2.20E-01 B. Iodines None Ci - - - - -

Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C. Particulates Half-Life 8 days None Ci - - - - -

Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Tritium H-3 Ci 1.82E+01 2.06E+01 1.69E+01 2.30E+01 7.87E+01 E. Carbon-14

C-14 Ci 1.55E+00 1.51E+00 1.65E+00 1.69E+00 6.39E+00 F. Gross Alpha Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

30% of total C-14 released is assumed to be in continuous mode. See Attachment 2, Supplemental Information, of this report.

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Attachment 1 Summary of Gaseous and Liquid Effluents McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Ground Releases - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases AR-41 Ci 4.96E-01 3.61E-01 3.87E-01 5.35E-01 1.78E+00 KR-85 Ci 0.00E+00 0.00E+00 8.42E-05 0.00E+00 8.42E-05 KR-85M Ci 2.44E-04 0.00E+00 0.00E+00 0.00E+00 2.44E-04 XE-133 Ci 4.39E-02 2.58E-02 3.46E-02 2.37E-02 1.28E-01 XE-133M Ci 8.07E-04 0.00E+00 0.00E+00 0.00E+00 8.07E-04 XE-135 Ci 1.04E-02 1.45E-03 1.25E-03 1.24E-03 1.43E-02 Total for Period Ci 5.51E-01 3.88E-01 4.23E-01 5.60E-01 1.92E+00 B. Iodines None Ci - - - - -

Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C. Particulates Half-Life 8 days None Ci - - - - -

Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Tritium H-3 Ci 2.15E-01 1.36E+00 9.73E-02 1.08E-01 1.78E+00 E. Carbon-14 C-14 Ci 3.63E+00 3.52E+00 3.86E+00 3.93E+00 1.49E+01 F. Gross Alpha Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

70% of total C-14 released is assumed to be in batch mode. See Attachment 2, Supplemental Information, of this report.

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Attachment 1 Summary of Gaseous and Liquid Effluents McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Mixed-Mode Releases - Continuous Mode

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases N/A Ci - - - - -

Total for Period Ci - - - - -

B. Iodines N/A Ci - - - - -

Total for Period Ci - - - - -

C. Particulates Half-Life 8 days N/A Ci - - - - -

Total for Period Ci - - - - -

D. Tritium N/A Ci - - - - -

E. Carbon-14 N/A Ci - - - - -

F. Gross Alpha Total for Period Ci - - - - -

McGuire Nuclear Station Units 1 and 2 do not have mixed-mode releases.

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Attachment 1 Summary of Gaseous and Liquid Effluents McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Mixed-Mode Releases - Batch Mode

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases N/A Ci - - - - -

Total for Period Ci - - - - -

B. Iodines N/A Ci - - - - -

Total for Period Ci - - - - -

C. Particulates Half-Life 8 days N/A Ci - - - - -

Total for Period Ci - - - - -

D. Tritium N/A Ci - - - - -

E. Carbon-14 N/A Ci - - - - -

F. Gross Alpha Total for Period Ci - - - - -

McGuire Nuclear Station Units 1 and 2 do not have mixed-mode releases.

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Attachment 1 Summary of Gaseous and Liquid Effluents McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Products *

1. Total Release Ci 4.58E-03 6.06E-03 5.72E-03 1.43E-03 1.78E-02

2. Avg. Diluted Conc. µCi/ml 8.65E-14 6.15E-11 7.10E-14 1.05E-14 1.14E-11

3. Batch Releases µCi/ml 5.71E-12 4.23E-12 5.62E-12 1.59E-12 4.29E-12 B. Tritium

1. Total Release Ci 2.97E+02 2.42E+02 2.47E+02 1.13E+02 8.99E+02

2. Avg. Diluted Conc. µCi/ml 7.38E-09 3.54E-08 9.63E-09 1.14E-08 1.14E-08

3. Batch Releases µCi/ml 3.69E-07 2.58E-07 2.42E-07 1.25E-07 2.45E-07 C. Dissolved & Entrained Gases

1. Total Release Ci 0.00E+00 1.13E-05 0.00E+00 0.00E+00 1.13E-05

2. Avg. Diluted Conc. µCi/ml 0.00E+00 4.38E-17 0.00E+00 0.00E+00 2.26E-17

3. Batch Releases µCi/ml 0.00E+00 1.21E-14 0.00E+00 0.00E+00 3.09E-15 D. Gross Alpha

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Avg. Diluted Conc. µCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Batch Releases µCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Volume of Liquid Waste

1. Continuous Releases liters 7.65E+07 2.59E+08 7.47E+07 6.88E+07 4.79E+08

2. Batch Releases liters 1.18E+06 9.43E+05 9.56E+05 4.60E+05 3.54E+06 F. Volume of Dilution Water

1. Continuous Releases liters 9.88E+10 3.38E+10 3.18E+10 1.91E+10 1.84E+11

2. Batch Releases liters 8.02E+11 9.35E+11 1.02E+12 9.01E+11 3.66E+12

Excludes tritium, dissolved and entrained noble gases, and gross alpha.

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Attachment 1 Summary of Gaseous and Liquid Effluents McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Products CO-58 Ci 0.00E+00 1.65E-03 0.00E+00 0.00E+00 1.65E-03 CO-60 Ci 0.00E+00 4.50E-04 0.00E+00 0.00E+00 4.50E-04 Total for Period Ci 0.00E+00 2.10E-03 0.00E+00 0.00E+00 2.10E-03 B. Tritium H-3 Ci 1.79E-01 1.18E+00 2.12E-01 2.04E-01 1.78E+00 C. Dissolved & Entrained Gases None Ci - - - - -

Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Gross Alpha Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1-10

Attachment 1 Summary of Gaseous and Liquid Effluents McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Products BR-82 Ci 3.27E-07 0.00E+00 0.00E+00 0.00E+00 3.27E-07 CO-58 Ci 2.28E-04 5.77E-04 4.36E-04 7.24E-05 1.31E-03 CO-60 Ci 7.65E-04 8.90E-04 1.21E-03 3.14E-04 3.18E-03 CR-51 Ci 1.54E-05 5.75E-05 0.00E+00 0.00E+00 7.30E-05 CS-134 Ci 0.00E+00 2.12E-06 0.00E+00 0.00E+00 2.12E-06 CS-137 Ci 7.36E-06 2.12E-04 2.86E-04 2.01E-04 7.06E-04 FE-55 Ci 9.18E-04 1.73E-04 2.06E-04 6.21E-05 1.36E-03 MN-54 Ci 1.53E-05 6.25E-04 1.19E-05 4.74E-06 6.57E-04 NB-95 Ci 1.01E-06 1.23E-05 1.15E-06 0.00E+00 1.45E-05 NI-63 Ci 2.36E-03 9.59E-04 3.47E-03 7.16E-04 7.50E-03 SB-124 Ci 0.00E+00 7.12E-05 1.08E-05 8.66E-06 9.06E-05 SB-125 Ci 2.76E-04 3.67E-04 8.85E-05 4.94E-05 7.81E-04 ZN-65 Ci 0.00E+00 5.10E-06 0.00E+00 0.00E+00 5.10E-06 ZR-95 Ci 0.00E+00 2.63E-06 0.00E+00 0.00E+00 2.63E-06 Total for Period Ci 4.58E-03 3.95E-03 5.72E-03 1.43E-03 1.57E-02 B. Tritium H-3 Ci 2.96E+02 2.41E+02 2.47E+02 1.12E+02 8.97E+02 C. Dissolved & Entrained Gases XE-133 Ci 0.00E+00 9.06E-06 0.00E+00 0.00E+00 9.06E-06 Xe-135 Ci 0.00E+00 2.23E-06 0.00E+00 0.00E+00 2.23E-06 Total for Period Ci 0.00E+00 1.13E-05 0.00E+00 0.00E+00 1.13E-05 D. Gross Alpha Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1-11

Attachment 2 Supplemental Information McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 2 Supplemental Information This attachment includes supplemental information to the gaseous and liquid effluents report.

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Attachment 2 Supplemental Information McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 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 Gamma Dose = 10 mRAD

4. Calendar Year Beta Dose = 20 mRAD B. Liquid Effluents - Dose

1. Calendar Quarter Total Body Dose = 1.5 mREM

2. Calendar Quarter Organ Dose =5 mREM

3. Calendar Year Total Body Dose =3 mREM

4. Calendar Year Organ Dose = 10 mREM C. Gaseous Effluents - Iodine-131 & 133, Tritium, and Particulates with Half-lives > 8 days

1. Calendar Quarter Organ Dose = 7.5 mREM

2. Calendar Year Organ Dose = 15 mREM II. Maximum Permissible Effluent Concentrations A. Gaseous Effluents

1. Information found in Offsite Dose Calculation Manual B. Liquid Effluents

1. Information found in 10 CFR Part 20, 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 this attachment.

V. Batch Releases A. Liquid Effluents

1. Total Number of Batch Releases = 1.92E+02

2. Total Time (min) for Batch Releases = 1.11E+04

3. Maximum Time (min) for a Batch Release = 1.53E+02

4. Average Time (min) for Batch Releases = 5.77E+01

5. Minimum Time (min) for a Batch Release = 1.00E+00

6. Average Dilution Water Flow During Release (gpm) = 1.83E+06 B. Gaseous Effluents

1. Total Number of Batch Releases = 3.80E+01

2. Total Time (min) for Batch Releases = 1.05E+06

3. Maximum Time (min) for a Batch Release = 4.46E+04

4. Average Time (min) for Batch Releases = 2.76E+04

5. Minimum Time (min) for a Batch Release = 1.20E+02 VI. Abnormal Releases See Attachment 5, Unplanned Offsite Releases.

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Attachment 2 Supplemental Information McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Carbon-14 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. 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, many sites show C-14 has become a "principal radionuclide" for the gaseous effluent pathway, as defined in Regulatory Guide 1.21, Rev. 2. McGuire Nuclear Station 2016 ARERR contains estimates of C-14 radioactivity released in 2016, 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 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 McGuire Nuclear Station 2016 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 Nuclear Station in 2016 results in a site total C-14 gaseous release estimate to the environment of 2.13E+01 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 Nuclear Station 2016 ARERR a value of 80% organic C-14 is assumed.

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 McGuire ODCM. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released from McGuire Nuclear Station in 2016 is well below the 10CFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit).

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Attachment 2 Supplemental Information McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 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%

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Attachment 2 Supplemental Information McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Summary of Changes in Land Use Census Affecting Effluent Dose Calculations The 2016 Land Use Census was performed June 8-9, 2016, and the results were certified and made available for use on August 2, 2016. The following are changes to residences, gardens, and milk animals from the previous year.

Residences The residence in the E sector at 0.48 miles was replaced with a residence at 0.52 miles.

Gardens The non-irrigated garden in the ESE sector at 1.06 miles was replaced by a non-irrigated garden at 1.09 miles.

Milk Animals No changes to nearest milk animal in each sector.

Environmental Monitoring Locations No changes to environmental monitoring locations in each sector.

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Attachment 3 Solid Radioactive Waste Disposal McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 3 Solid Radioactive Waste Disposal This attachment includes a summary of the solid waste shipped off-site for burial and/or disposal, including:

Container volume

Total Curie content

Principal Radionuclides

Source/Type of waste

Solidification agent or absorbent

Type of shipping container

Number of shipments

Other relevant information as necessary Page 3-1

Attachment 3 Solid Radioactive Waste Disposal McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Burial Total Type of Number of Number of Waste Container Solidification Volume Activity Waste Shipped Shipments Containers Class Type Agent 3 (m ) (Curies)

1. Waste from Liquid Systems

a. Dewatered Powdex Resin 0 - - - - - -

(brokered)

b. Dewatered Powdex Resin 0 - - - - - -

c. Dewatered Bead Resin 0 - - - - - -

(brokered)

d. Dewatered Bead Resin 0 - - - - - -

e. Dewatered Radwaste System 0 - - - - - -

Resin

f. Dewatered Primary Bead 4 4 B B N/A 13.59 6.02E+02 Resins (brokered)

g. Dewatered Mechanical Filter 0 - - - - - -

Media

h. Dewatered Mechanical Filter 0 - - - - -

Media (brokered)

i. Solidified Waste 0 - - - - - -

2. Dry Solid Waste

a. Dry Active Waste 0 - - - - - -

(compacted)

b. Dry Active Waste 0 - - - - - -

(non-compacted)

c. Dry Active Waste 0 - - - - - -

(brokered / compacted)

d. Dry Active Waste 15 38 A/U DBP N/A 753.22 5.94E-01 (brokered / non-compacted)

e. Sealed Sources / Smoke 0 - - - - - -

Detectors

f. Sealed Sources 0 - - - - - -

g. Irradiated Components 0 - - - - - -

3. Total Waste 19 42 766.81 6.02E+02 Page 3-2

Attachment 3 Solid Radioactive Waste Disposal McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Type of Waste Shipped Radionuclide % Abundance

1. Waste from Liquid Systems

a. Dewatered Powdex Resin (brokered) N/A N/A

b. Dewatered Powdex Resin N/A N/A

c. Dewatered Bead Resin (brokered) N/A N/A

d. Dewatered Bead Resin N/A N/A

e. Dewatered Radwaste System Resin N/A N/A

f. Dewatered Primary Bead Resins (brokered)

RSR-2016-0017 Mn-54 0.98 Co-57 0.02 Co-58 0.05 Co-60 14.03 Cs-137 0.65 Cs-134 0.01 Fe-55 9.06 Ni-63 74.30 C-14 0.02 Ni-59 0.56 Ce-144 0.03 Sb-125 0.11 Sr-90 0.02 Zn-65 0.16 RSR-2016-0020 Mn-54 0.98 Co-57 0.02 Co-58 0.05 Co-60 14.03 Cs-137 0.65 Cs-134 0.01 Fe-55 9.06 Ni-63 74.30 C-14 0.02 Ni-59 0.56 Ce-144 0.03 Sb-125 0.11 Sr-90 0.02 Zn-65 0.16 RSR-2016-0021 Mn-54 0.91 Co-57 0.01 Co-58 0.04 Co-60 14.04 Cs-137 0.69 Cs-134 0.01 Fe-55 9.04 Ni-63 74.23 C-14 0.02 Ni-59 0.56 Ce-144 0.03 Sb-125 0.19 Sr-90 0.02 Zn-65 0.21 Page 3-3

Attachment 3 Solid Radioactive Waste Disposal McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 RSR-2016-0022 Mn-54 0.63 Co-60 14.04 Cs-137 1.51 Cs-134 0.01 Fe-55 9.20 Ni-63 73.41 C-14 0.02 Ni-59 0.55 Ce-144 0.07 Sb-125 0.31 Sr-90 0.04 Zn-65 0.22 Tc-99 0.01

g. Dewatered Mechanical Filter Media N/A N/A

h. Dewatered Mechanical Filter Media N/A N/A (brokered)

i. Solidified Waste N/A N/A

2. Dry Solid Waste

a. Dry Active Waste (compacted) N/A N/A

b. Dry Active Waste (non-compacted) N/A N/A

c. Dry Active Waste N/A N/A (brokered / compacted)

d. Dry Active Waste (brokered / non-compacted)

RSR-2016-0001 Cr-51 17.89 Mn-54 2.58 Co-57 0.06 Co-58 11.53 Co-60 19.08 Cs-137 0.03 Fe-55 14.32 Fe-59 0.54 Ni-63 2.15 H-3 0.05 C-14 0.01 Nb-95 18.77 Ce-144 0.10 Sb-124 0.28 Sb-125 0.81 Zr-95 11.06 Sr-90 0.01 Sn-113 0.40 Zn-65 0.34 Page 3-4

Attachment 3 Solid Radioactive Waste Disposal McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 RSR-2016-0002 Cr-51 7.11 Mn-54 3.67 Co-57 0.08 Co-58 10.36 Co-60 30.67 Cs-137 0.05 Fe-55 22.51 Fe-59 0.35 Ni-63 3.52 H-3 0.08 C-14 0.02 Nb-95 9.66 Ce-144 0.14 Sb-124 0.23 Sb-125 1.28 Zr-95 9.35 Sr-90 0.01 Sn-113 0.45 Zn-65 0.46 RSR-2016-0004 Cr-51 13.07 Mn-54 3.03 Co-57 0.07 Co-58 11.58 Co-60 23.28 Cs-137 0.04 Fe-55 17.38 Fe-59 0.48 Ni-63 2.64 H-3 0.06 C-14 0.01 Nb-95 15.30 Ce-144 0.11 Sb-124 0.27 Sb-125 0.99 Zr-95 10.86 Sr-90 0.01 Sn-113 0.44 Zn-65 0.39 RSR-2016-0006 Cr-51 44.85 Mn-54 2.63 Co-58 11.94 Co-60 11.10 Cs-137 0.07 Fe-55 8.42 Fe-59 0.85 Ni-63 3.22 H-3 0.35 Nb-95 8.62 Ce-144 0.26 Sb-125 0.55 Zr-95 6.24 Sn-113 0.21 Zn-65 0.48 Ag-110M 0.20 Page 3-5

Attachment 3 Solid Radioactive Waste Disposal McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 RSR-2016-0007 Cr-51 49.74 Mn-54 2.28 Co-58 11.19 Co-60 9.37 Cs-137 0.06 Fe-55 7.14 Fe-59 0.85 Ni-63 2.71 H-3 0.30 Nb-95 9.00 Ce-144 0.22 Sb-125 0.46 Zr-95 5.91 Sn-113 0.19 Zn-65 0.41 Ag-110M 0.18 RSR-2016-0008 Cr-51 49.89 Mn-54 2.26 Co-58 11.18 Co-60 9.31 Cs-137 0.06 Fe-55 7.09 Fe-59 0.85 Ni-63 2.70 H-3 0.30 Nb-95 9.03 Ce-144 0.22 Sb-125 0.46 Zr-95 5.91 Sn-113 0.19 Zn-65 0.41 Ag-110M 0.18 RSR-2016-0010 Cr-51 49.29 Mn-54 2.30 Co-58 11.28 Co-60 9.52 Cs-137 0.06 Fe-55 7.24 Fe-59 0.85 Ni-63 2.75 H-3 0.30 Nb-95 8.99 Ce-144 0.22 Sb-125 0.47 Zr-95 5.94 Sn-113 0.19 Zn-65 0.42 Ag-110M 0.18 RSR-2016-0012 Cr-51 48.79 Mn-54 2.34 Co-58 11.35 Co-60 9.70 Cs-137 0.06 Fe-55 7.38 Fe-59 0.85 Ni-63 2.81 H-3 0.31 Nb-95 8.92 Ce-144 0.23 Sb-125 0.48 Zr-95 5.98 Sn-113 0.20 Zn-65 0.43 Ag-110M 0.18 Page 3-6

Attachment 3 Solid Radioactive Waste Disposal McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 RSR-2016-0014 Cr-51 48.09 Mn-54 2.40 Co-58 11.47 Co-60 9.93 Cs-137 0.06 Fe-55 7.57 Fe-59 0.85 Ni-63 2.81 H-3 0.32 Nb-95 8.87 Ce-144 0.23 Sb-125 0.49 Zr-95 6.03 Sn-113 0.20 Zn-65 0.44 Ag-110M 0.19 RSR-2016-0016 Cr-51 36.05 Mn-54 3.34 Co-58 12.97 Co-60 14.58 Cs-137 0.09 Fe-55 10.98 Fe-59 0.82 Ni-63 4.25 H-3 0.47 Nb-95 7.67 Ce-144 0.32 Sb-125 0.71 Zr-95 6.65 Sn-113 0.25 Zn-65 0.60 Ag-110M 0.25 RSR-2016-0019 Cr-51 47.30 Mn-54 2.46 Co-58 11.55 Co-60 10.25 Cs-137 0.06 Fe-55 7.80 Fe-59 0.84 Ni-63 2.97 H-3 0.33 Nb-95 8.79 Ce-144 0.24 Sb-125 0.50 Zr-95 6.07 Sn-113 0.20 Zn-65 0.45 Ag-110M 0.19 RSR-2016-0023 Cr-51 49.24 Mn-54 2.31 Co-58 11.29 Co-60 9.52 Cs-137 0.06 Fe-55 7.25 Fe-59 0.85 Ni-63 2.76 H-3 0.30 Nb-95 8.99 Ce-144 0.22 Sb-125 0.47 Zr-95 5.95 Sn-113 0.19 Zn-65 0.42 Ag-110M 0.18 Page 3-7

Attachment 3 Solid Radioactive Waste Disposal McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 RSR-2016-0024 Cr-51 46.20 Mn-54 2.55 Co-58 11.76 Co-60 10.61 Cs-137 0.07 Fe-55 8.04 Fe-59 0.85 Ni-63 3.07 H-3 0.34 Nb-95 8.72 Ce-144 0.24 Sb-125 0.52 Zr-95 6.17 Sn-113 0.21 Zn-65 0.46 Ag-110M 0.20 LQS-2016-0047 Cr-51 43.57 Mn-54 2.74 Co-58 12.11 Co-60 11.56 Cs-137 0.07 Fe-55 8.79 Fe-59 0.84 Ni-63 3.36 H-3 0.37 Nb-95 8.49 Ce-144 0.26 Sb-125 0.57 Zr-95 6.33 Sn-113 0.22 Zn-65 0.49 Ag-110M 0.21

e. Sealed Sources / Smoke Detectors N/A N/A

f. Sealed Sources N/A N/A

g. Irradiated Components N/A N/A Page 3-8

Attachment 4 Meteorological Data McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 4 Meteorological Data This attachment includes a summary of meteorological joint frequency distributions of wind speed, wind direction, and atmospheric stability (hours of occurrence).

Page 4-1

Attachment 4 Meteorological Data McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.26-1.50 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1.51-2.00 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 2.01-3.00 3 0 2 1 1 0 0 0 1 2 1 2 2 0 0 0 A

3.01-4.00 1 4 0 0 0 0 0 0 0 1 1 0 1 0 1 0 4.01-5.00 2 1 0 0 0 0 0 0 0 0 0 0 0 1 0 0 5.01-6.00 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.01-8.00 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 8.01-10.00 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 10.01-max 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.26-1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51-2.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.01-3.00 1 3 0 1 0 0 0 0 0 2 1 0 1 0 0 0 B

3.01-4.00 2 4 0 1 0 0 0 0 0 5 3 0 0 0 0 0 4.01-5.00 2 3 0 1 0 0 0 0 0 4 0 0 1 0 2 0 5.01-6.00 1 0 0 0 0 0 0 0 0 0 2 2 0 0 0 2 6.01-8.00 4 5 0 0 0 0 0 0 0 0 0 0 0 0 0 2 8.01-10.00 8 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-2

Attachment 4 Meteorological Data McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.26-1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1.51-2.00 0 1 1 0 0 0 0 0 0 0 0 1 0 0 1 1 2.01-3.00 7 15 3 1 1 0 0 0 1 3 2 2 1 1 0 0 C

3.01-4.00 4 9 2 4 1 0 0 5 2 14 4 10 4 2 0 0 4.01-5.00 4 2 2 3 3 0 1 0 0 4 11 6 1 1 6 1 5.01-6.00 10 5 1 0 0 0 0 0 0 4 8 4 0 1 1 7 6.01-8.00 17 7 0 0 0 0 0 0 0 0 4 4 1 2 4 10 8.01-10.00 9 2 0 0 0 0 0 0 0 0 0 0 0 0 0 2 10.01-max 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0.46-0.75 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 3 4 2 0 2 0 0 0 2 3 0 1 1 0 1 1 1.01-1.25 14 6 5 2 0 1 0 2 3 2 4 3 7 7 5 6 1.26-1.50 22 14 9 11 3 5 6 6 10 8 10 6 9 12 8 16 1.51-2.00 43 65 67 44 26 30 20 43 32 22 30 50 38 30 18 31 2.01-3.00 91 131 222 206 158 105 117 56 89 148 206 178 102 45 50 34 D

3.01-4.00 58 75 240 178 110 78 39 20 25 102 219 120 56 41 48 45 4.01-5.00 57 58 187 46 16 13 2 5 7 43 108 40 37 26 53 41 5.01-6.00 36 56 76 14 2 0 0 0 6 8 58 19 14 13 42 43 6.01-8.00 53 28 24 1 0 0 0 0 2 7 13 14 7 12 45 57 8.01-10.00 7 8 2 0 0 0 0 0 0 0 2 5 2 14 16 8 10.01-max 0 0 0 0 0 0 0 0 0 0 0 1 1 2 4 2 Page 4-3

Attachment 4 Meteorological Data McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 0.46-0.75 0 1 1 0 0 2 0 1 0 2 1 2 1 0 0 0 0.76-1.00 2 2 1 1 1 4 4 1 4 6 4 4 5 6 4 2 1.01-1.25 2 6 3 1 5 5 3 4 5 14 15 13 8 7 2 5 1.26-1.50 9 7 11 3 3 2 7 22 32 23 23 30 25 7 5 7 1.51-2.00 10 12 12 8 5 10 24 47 70 70 54 59 42 16 13 4 2.01-3.00 10 8 8 10 15 31 37 24 46 161 175 103 29 13 18 15 E

3.01-4.00 3 6 0 1 3 2 7 2 6 20 62 15 14 15 18 8 4.01-5.00 4 2 0 1 0 1 1 0 0 1 3 1 3 2 11 5 5.01-6.00 5 0 1 0 0 0 0 0 0 0 1 1 0 0 4 2 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 1 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 0 1 0 0 0 0 0 0 0 3 6 5 1 1 1 1 0.76-1.00 2 1 1 0 0 1 0 5 7 18 18 11 8 3 1 1 1.01-1.25 2 0 0 0 0 0 0 1 6 19 16 15 5 3 7 0 1.26-1.50 1 2 1 1 0 1 2 3 19 23 25 12 10 2 0 2 1.51-2.00 1 1 0 0 1 0 2 5 39 39 30 24 10 2 1 1 2.01-3.00 0 1 0 0 1 0 0 2 24 20 33 38 10 4 0 0 F

3.01-4.00 0 0 0 1 0 0 0 0 0 2 1 3 3 1 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 0 1 0 1 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-4

Attachment 4 Meteorological Data McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 0.46-0.75 0 0 0 2 1 0 0 0 1 9 15 6 4 2 0 0 0.76-1.00 2 3 1 0 1 0 0 0 2 31 34 17 3 2 1 0 1.01-1.25 0 0 0 1 0 0 0 0 5 18 19 12 5 0 1 1 1.26-1.50 0 0 0 0 0 0 0 0 5 17 8 5 1 0 1 0 1.51-2.00 0 1 0 0 0 0 0 0 9 11 8 4 1 1 0 0 2.01-3.00 0 1 0 0 0 0 0 1 2 1 4 9 0 0 0 0 G

3.01-4.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-5

Attachment 5 Unplanned Offsite Releases McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 5 Unplanned Offsite Releases This attachment includes a summary of the unplanned offsite releases of gaseous and liquid radioactive effluents.

Page 5-1

Attachment 5 Unplanned Offsite Releases McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station experienced no unplanned offsite liquid effluent releases in 2016.

McGuire Nuclear Station experienced three (3) unplanned offsite gaseous effluent releases in 2016. Summaries are described on the following pages.

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Attachment 5 Unplanned Offsite Releases McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 January 13, 2016 Memorandum To: Annual Radioactive Effluent Release Report CC: Steve Mooneyhan, Brent Sherrill, Chris Courtenay, Kay Crane, Jimmy Glenn From: William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit 2 Vent, Reference NCR # 1987854 and 1987941 Event Summary:

See referenced NCRs for details.

On 1/3/2016 ~22:00 Operations was operating the NB Evaporator with discharge to the affected RMWST. The B Waste Gas (WG) Compressor spuriously tripped. This allowed pressure to build in the Evaporator shell. At 22:10 the Unit 2 Vent gas rad monitor increased to ~247 cpm above background (bkg) and reached Trip 1 alarm. Control room Operations notified RP Shift to investigate. RP trending of the Unit 2 radiation monitor 2 EMF 36L indicated an increased count rate and remained elevated above bkg for 47min. A Unit Vent gas grab sample collected indicated no activity identified. Elevated counts were seen on several monitoring points on Auxiliary building gas monitor 0EMF41.

Monitoring point eleven (NB Evaporator area) was the highest and reached 1177cpm which initiated Trip 2 actuation.

Unit 1 and Unit 2 VA was placed into filtered mode ~22:47 hours. It was also noted that a pressure drop of ~9.5 psig was identified from WGDT "D" starting ~22:00 hrs.

The highest count rate seen from the Unit Vent gas monitor was 270 cpm. Normal 2 EMF 36L bkg determined to be 23 cpm. The average count rate during the release period was ~40 cpm above bkg.

Operations secured the NB Evaporator. It is believed that the Evaporator Rupture disc failed which allowed gas to release as designed to the Auxiliary building ventilation system to the Unit 2 Vent.

A conservative calculation using Xe-133 noble gas equivalent activity was used to evaluate the release. No gas sample from the evaporator shell was available. Unit 2 vent flow and 2 EMF 36L gas monitor highest ten minute average response during the release period was used to quantify Noble gas released. The total Noble gas activity released during the event was conservatively determined to be 2.19E-1 Curies. The release was reported on Gaseous Waste Release (GWR) report # 2016003. No SLC or T/S limits were challenged by this release.

The total release of Noble gas radioactivity was evaluated against off site dose limits using current ODCM methodology on the attached spreadsheets. Procedure AD-RP-ALL-2003 "Investigation of Unusual Radiological Occurrences" was completed to document the event.

Safety Significance:

The health and safety of the public were not compromised by this event. Calculated dose and dose rate to the Total Body, Skin, Gamma Air, and Beta Air were all significantly below the limits specified by Selected Licensee Commitments and Code of Federal Regulations.

W.C. Spencer Brent Sherrill RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station Page 5-3

Attachment 5 Unplanned Offsite Releases McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 February 3, 2016 Memorandum To: Annual Radioactive Effluent Release Report CC: Steve Mooneyhan, Brent Sherrill, Chris Courtenay, Lee Hentz, Jimmy Glenn From: William C. Spencer RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit 1 Vent, Reference NCR # 01997836 Event Summary:

See referenced NCR for details.

On 2/3/16 @ 06:30 hrs a loss of inventory from in-service Waste Gas Decay Tank (WGDT) 'F' was identified.

Radiation Protection (RP) was notified to evaluate Aux. Bld Ventilation Rad monitor (1EMF 41) for indications of radioactive gas release. Follow up trending of 1EMF41 point 4 showed elevated count rate ~30 cpm above background starting around 11:00 hrs. No increase was seen on Unit 1 Vent gas Rad monitor during the period. The WGDT 'F' pressure drop and 1EMF41 point 4 activity increase started in conjunction with scheduled maintenance of the 'B' WGDT inlet and outlet sample isolation valve breach. Unit 1 and Unit 2 VCT purges were secured ~07:30 hrs.

1EMF 41 point 4 count rate returned to normal ~12:30 hrs.

Follow up conservative examination of the WGDT 'F' inventory loss shows that it started at 2/2/2016 ~10:50hrs (61.3psig) and leveled off at 49.9psig on 2/3/16 at ~10:28 hrs. Total volume loss of 11.4psig over 23.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months . This equates to a release of 465 cubic feet at a discharge rate of 0.328 cubic feet per minute (cfm). A Radioactive gas sample from the WGDT 'F' was collected on 2/3/16 at 14:28 hrs and was used to evaluate the radioactive noble gas release through the Unit 1 Vent stack.

The Unit 1 Vent 1EMF 36L gas monitor indicated normal background response during the release period. The total Noble gas activity released during the event was determined to be 0.0192 Curies. The release was reported on Gaseous Waste Release (GWR) report # 2016007. No Selected License Commitments (SLC) or T/S limits were challenged by this release.

The total release of Noble gas radioactivity was evaluated against off site dose limits using current ODCM methodology on the attached spreadsheet. Reporting and Notification criteria were evaluated in accordance with procedure AD-RP-ALL-2003 "Investigation of Unusual Radiological Occurrences". No regulatory notifications were required.

Safety Significance:

The health and safety of the public were not compromised by this event. Calculated dose and dose rate to the Total Body, Skin, Gamma Air, and Beta Air were all significantly below the limits specified by Selected Licensee Commitments and Code of Federal Regulations.

W.C. Spencer Brent Sherrill RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station Page 5-4

Attachment 5 Unplanned Offsite Releases McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 February 16, 2016 Memorandum To: Annual Radioactive Effluent Release Report CC: Steve Mooneyhan, Brent Sherrill, Chris Courtenay, Lee Hentz, Jimmy Glenn From: Tara Matheny RP Staff Radiation Protection McGuire Nuclear Station Re: Unplanned release to the Unit 1 Vent, Reference NCR # 02001853 Event Summary:

See referenced NCR for details.

On 2/16/16 @ 1100 hrs a loss of inventory from in-service Waste Gas Decay Tank (WGDT) 'A' was identified.

Radiation Protection (RP) was notified to evaluate Aux. Bld Ventilation Rad monitor (1EMF41) for indications of radioactive gas release. Follow up trending of 1EMF41 point 4 showed elevated count rate ~30 cpm above background starting around 11:00 hrs. No increase was seen on Unit 1 Vent gas rad monitor during the period. The WGDT 'A' pressure drop and 1EMF41 point 4 activity increase started in conjunction with scheduled maintenance of 1WG167 ("B" WG Recombiner Inlet Check Value). The valve bonnet was installed and work stopped when the 1EMF41 point 4 increase was identified pending an investigation. Radwaste Ops continued to monitor "A" WGDT and identified a slow inventory loss. The repaired valve was installed and closed at 1650. 1EMF41 point 4 count rate returned to normal ~17:00 hrs.

Follow up conservative examination of the WGDT 'A' inventory loss shows that it started at 2/16/2016 ~11:00hrs (61.5 psig) and leveled off at 57.9 psig on 2/16/16 at ~17:20 hrs. Total volume loss of 3.634 psig over 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .. This equates to a release of 148.2 cubic feet at a discharge rate of 0.379 cubic feet per minute (cfm). A Radioactive gas sample from the WGDT 'A' was collected on 2/16/16 at 15:56 hrs and was used to evaluate the radioactive noble gas release through the Unit 1 Vent stack.

The Unit 1 Vent 1EMF 36L gas monitor indicated normal background response during the release period. The total Noble gas activity released during the event was determined to be 4.86E-4 Curies. The release was reported on Gaseous Waste Release (GWR) report # 2016017. No Selected License Commitments (SLC) or T/S limits were challenged by this release.

The total release of Noble gas radioactivity was evaluated against off site dose limits using current ODCM methodology on the attached spreadsheet. Reporting and Notification criteria were evaluated in accordance with procedure AD-RP-ALL-2003 "Investigation of Unusual Radiological Occurrences". No regulatory notifications were required.

Safety Significance:

The health and safety of the public were not compromised by this event. Calculated dose and dose rate to the Total Body, Skin, Gamma Air, and Beta Air were all significantly below the limits specified by Selected Licensee Commitments and Code of Federal Regulations.

T. E. Matheny Brent Sherrill RP Staff Support General Supervisor Radiation Protection Radiation Protection McGuire Nuclear Station McGuire Nuclear Station Page 5-5

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)

This attachment includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of the report as well as the total dose for the calendar year.

This attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 8 km of the site for the calendar year of this report to show conformance with 40 CFR Part 190.

Methods for calculating the dose contribution from liquid and gaseous effluents are given in the Offsite Dose Calculation Manual (ODCM).

Page 6-1

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gaseous Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Noble Gases

1. Maximum Gamma Air mRAD 1.14E-02 8.13E-03 8.72E-03 1.20E-02 4.03E-02 (a) Limit mRAD 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 (b) % of Limit 1.14E-01 8.13E-02 8.72E-02 1.20E-01 2.01E-01

2. Maximum Beta Air mRAD 4.66E-03 2.93E-03 3.16E-03 4.30E-03 1.51E-02 (a) Limit mRAD 2.00E+01 2.00E+01 2.00E+01 2.00E+01 4.00E+01 (b) % of Limit 2.33E-02 1.47E-02 1.58E-02 2.15E-02 3.76E-02 Receptor Location 0.5 miles NNE B. Iodine, H-3, & Particulates

1. Maximum Organ Dose mREM 7.93E-01 7.70E-01 8.44E-01 8.60E-01 3.27E+00 (a) Limit mREM 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.00E+01 (b) % of Limit 5.29E+00 5.13E+00 5.62E+00 5.74E+00 1.09E+01 Receptor Location 1.0 miles NNE Critical Age CHILD Critical Organ BONE Critical Pathway VEGETATION Page 6-2

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Batch Mode

1. Maximum Organ Dose mREM 3.87E-02 2.80E-02 2.70E-02 1.42E-02 1.07E-01 (a) Limit mREM 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 (b) % of Limit 3.87E-01 2.80E-01 2.70E-01 1.42E-01 5.34E-01 (c) Critical Age Child Child Child Child Child (d) Critical Organ Liver Liver Liver Liver Liver (e) Critical Pathway Pt. Water Pt. Water Pt. Water Pt. Water Pt. Water

2. Maximum Total Body Dose mREM 3.86E-02 2.71E-02 2.59E-02 1.33E-02 1.04E-01 (a) Limit mREM 3.00E+00 3.00E+00 3.00E+00 3.00E+00 6.00E+00 (b) % of Limit 1.29E+00 9.04E-01 8.62E-01 4.45E-01 1.73E+00 (c) Critical Age Child Child Child Child Child (d) Critical Pathway Pt. Water Pt. Water Pt. Water Pt. Water Pt. Water B. Continuous Mode

1. Maximum Organ Dose mREM 1.89E-04 5.08E-03 7.01E-04 1.12E-03 4.81E-02 (a) Limit mREM 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 (b) % of Limit 1.89E-03 5.08E-02 7.01E-03 1.12E-02 2.40E-02 (c) Critical Age Child Adult Child Child Adult (d) Critical Organ Liver GI-LLI Liver Liver GI-LLI (e) Critical Pathway Pt. Water Pt. Water Pt. Water Pt. Water Pt. Water

2. Maximum Total Body Dose mREM 1.89E-04 4.18E-03 7.01E-04 1.12E-03 4.47E-03 (a) Limit mREM 3.00E+00 3.00E+00 3.00E+00 3.00E+00 6.00E+00 (b) % of Limit 6.29E-03 1.39E-01 2.34E-02 3.75E-02 7.45E-02 (c) Critical Age Child Child Child Child Child (d) Critical Pathway Pt. Water Pt. Water Pt. Water Pt. Water Pt. Water Page 6-3

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 40 CFR Part 190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40 CFR Part 190, 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 includes liquid and gaseous effluent dose contributions from McGuire Nuclear Station and direct and air-scatter dose from the onsite ISFSI. No other uranium fuel cycle facility contributes significantly to the maximum exposed individual. Included in the gaseous effluent dose calculations is an estimate of the dose contributed by Carbon-14 (Ref. Attachment 2, Supplemental Information, of this report for further information). The combined dose to a maximum exposed individual from effluent releases and direct and air-scatter dose from the ISFSI is below 40 CFR Part 190 limits as shown by the following summary.

Note: The 40 CFR Part 190 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).

40 CFR Part 190 Effluent Dose Summary A. Maximum Organ Dose (other than TB) 3.28E+00 mREM

1. Location 1.0 miles NNE

2. Critical Age CHILD

3. Critical Organ BONE

4. Gas Contribution % 99.72%

5. Liquid Contribution % 0.28%

B. Maximum Total Body Dose 1.01E+00 mREM

1. Location 1.0 miles NNE

2. Critical Age CHILD

3. Gas non-NG Contribution % 88.79%

4. Gas Contribution % 0.95%

5. Liquid Contribution % 10.26%

Direct and air-scatter radiation dose contributions from the onsite ISFSI have been determined from the 10 CFR 72.212 Evaluation Report, MAGNASTOR , Revision 04. The maximum dose rate to the nearest real individual from the ISFSI is conservatively calculated to be less than 4 mrem/yr.

The attached excerpt from the 10 CFR 72.212 Evaluation Report, MAGNASTOR , Revision 04 is provided to document the method used to calculate the dose from ISFSI as less than 4 mrem/yr to the nearest real individual.

Total dose from liquid and gaseous effluents from McGuire Nuclear Station and direct and air-scatter dose from the onsite ISFSI is conservatively estimated to be less than 8 mrem/yr to the nearest real individual. This meets the 40 CFR Part 190 requirements of an annual dose commitment to any member of the general public of less than 25 mrem total body or any organ and 75 mrem to the thyroid.

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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 10 CFR 72.212 Evaluation Report, MAGNASTOR , Revision 04 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 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 4 mrem. No other uranium fuel cycle facility contributes significantly to the dose received by the closest real individual.

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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Based on the above, the calculated annual dose (performed in December 2015 per Reference 10) revised the 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-UMS 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 4 mrem. Hence, the total annual dose to the closest real individual (less than 8 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.

Page 6-6

Attachment 7 Information to Support the NEI Ground Water Protection Initiative McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 7 Information to Support the NEI Ground Water Protection Initiative This attachment includes a summary of voluntary reports made in accordance with the NEI Ground Water Protection Initiative and a summary of ground water well sample data.

Page 7-1

Attachment 7 Information to Support the NEI Ground Water Protection Initiative McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Duke Energy implemented a Ground Water Protection program in 2007. This initiative 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 98 wells, 4 surface water points, and 1 leachate pond in 2016.

Wells are typically sampled quarterly or semi-annually. Ground water samples are regularly analyzed for tritium and gamma emitters, with select 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 2016. Results from sampling during 2016 confirmed existing knowledge of tritium concentrations in site ground water.

Results from sampling during 2016 are shown in the table below.

No events meeting the criteria for voluntary notification per NEI 07-07, Industry Ground Water Protection Initiative, occurred at McGuire Nuclear Station in 2016.

Key to below table.

Not scheduled to be sampled, not sampled due to insufficient NS -

volume in well, or well inaccessible during outage.

Ci/l - picocuries per liter.

< MDA - less than minimum detectable activity, typically 250 Ci/l.

the Environmental Protection Agency drinking water standard for 20,000 Ci/l -

tritium. This standard applies only to water used for drinking.

the 10 CFR Part 20, Appendix B, Table 2, Column 2, Effluent 1,000,000 Ci/l -

Concentration Limit for tritium.

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Attachment 7 Information to Support the NEI Ground Water Protection Initiative McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Well Tritium Concentration (pCi/l) # of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples M-100R MNS GWPI / M-100R / SE of WC 2.75E+02 <MDA 2.69E+02 2.54E+02 4 M-101 MNS GWPI / M-101 / SE of WC <MDA <MDA <MDA 3.07E+02 4 M-102 MNS GWPI / M-102 / SW of WC 2.76E+03 2.32E+03 2.33E+03 2.39E+03 4 M-103 MNS GWPI / M-103 / S of WC 9.42E+02 8.36E+02 8.02E+02 9.66E+02 4 M-103R MNS GWPI / M-103R / S of WC 1.05E+03 8.88E+02 9.21E+02 1.02E+03 4 M-104DR MNS GWPI / M-104DR / W of WC 1.23E+03 1.07E+03 1.11E+03 1.13E+03 4 M-104R MNS GWPI / M-104R / W of WC 1.43E+03 1.45E+03 1.35E+03 1.13E+03 4 M-105 MNS GWPI / M-105 / Landfarm NS 3.54E+02 NS 3.16E+02 2 M-20 MNS GWPI / M-20 / S of Hwy. 73 NS 6.14E+02 NS 7.07E+02 2 M-20R MNS GWPI / M-20R / S of Hwy. 73 NS 6.16E+02 NS 6.78E+02 2 M-21 MNS GWPI / M-21 / S of Hwy. 73 NS <MDA NS <MDA 2 M-22 MNS GWPI / M-22 / S of Hwy. 73 NS <MDA NS <MDA 2 M-22R MNS GWPI / M-22R / S of Hwy. 73 NS <MDA NS <MDA 2 M-23 MNS GWPI / M-23 / S of Acs. Rd. NS <MDA NS <MDA 2 M-30 MNS GWPI / M-30 / WWCB NS <MDA NS <MDA 2 M-30R MNS GWPI / M-30R / WWCB NS 2.15E+02 NS 1.97E+02 2 M-31 MNS GWPI / M-31 / Access road NS <MDA NS <MDA 2 M-32 MNS GWPI / M-32 / Main entrance NS <MDA NS <MDA 2 M-33 MNS GWPI / M-33 / Ballfield, HWY 73 NS NS <MDA <MDA 2 M-34DR MNS GWPI / M-34DR / Access road <MDA <MDA <MDA <MDA 4 M-34R MNS GWPI / M-34R / Access road <MDA <MDA <MDA <MDA 4 M-35 MNS GWPI / M-35 / Access road <MDA <MDA NS NS 2 M-42 MNS GWPI / M-42 / U-2 Rx. Bldg. 2.51E+03 2.12E+03 2.21E+03 2.31E+03 4 M-48DR MNS GWPI / M-48DR / U-2 SFP <MDA NS <MDA <MDA 3 M-48R MNS GWPI / M-48R / U-2 SFP 7.87E+02 NS 6.91E+02 6.09E+02 3 M-53 MNS GWPI / M-53 / N of plant 8.15E+02 7.25E+02 7.88E+02 8.65E+02 4 M-55 MNS GWPI / M-55 / NAB <MDA <MDA <MDA <MDA 4 M-59 MNS GWPI / M-59 / U-2 Doghouse 1.40E+03 1.39E+03 1.35E+03 1.36E+03 4 M-60 MNS GWPI / M-60 / MOC Parking NS <MDA NS <MDA 2 M-62 MNS GWPI / M-62 / S of RWF 2.14E+02 <MDA <MDA <MDA 4 M-64 MNS GWPI / M-64 / Rdwst. Bldg. 5.66E+02 5.86E+02 4.26E+02 4.84E+02 4 M-66 MNS GWPI / M-66 / S of SSF 7.53E+02 6.99E+02 7.35E+02 6.59E+02 4 M-66R MNS GWPI / M-66R / S of SSF <MDA <MDA <MDA <MDA 4 M-68 MNS GWPI / M-68 / U-1 RMWST 6.25E+02 6.49E+02 6.41E+02 6.85E+02 4 M-70 MNS GWPI / M-70 / U-1 SFP 5.93E+02 4.13E+02 4.29E+02 3.92E+02 4 M-70DR MNS GWPI / M-70DR / U-1 SFP <MDA <MDA <MDA <MDA 4 M-70R MNS GWPI / M-70R / U-1 SFP 2.21E+02 2.47E+02 2.04E+02 2.50E+02 4 M-72 MNS GWPI / M-72 / Rdwst. Trench 6.17E+02 6.50E+02 6.53E+02 6.77E+02 4 M-76 MNS GWPI / M-76 / W of U-1 SFP 5.20E+02 4.36E+02 NS 4.19E+02 3 M-82 MNS GWPI / M-82 / River 1.07E+03 1.31E+03 9.24E+02 9.70E+02 4 M-84 MNS GWPI / M-84 / River 1.56E+03 1.34E+03 1.64E+03 2.16E+03 4 M-84R MNS GWPI / M-84R / River 2.55E+03 2.53E+03 2.29E+03 2.25E+03 4 M-85 MNS GWPI / M-85 / River 6.74E+02 6.81E+02 6.80E+02 5.40E+02 4 M-87 MNS GWPI / M-87 / Landfarm 2.63E+02 2.14E+02 3.46E+02 3.76E+02 4 Page 7-3

Attachment 7 Information to Support the NEI Ground Water Protection Initiative McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Well Tritium Concentration (pCi/l) # of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples M-89 MNS GWPI / M-89 / Landfarm 4.19E+02 3.62E+02 4.80E+02 3.75E+02 4 M-90 MNS GWPI / M-90 / Landfarm NS 3.20E+02 NS 4.12E+02 2 M-91 MNS GWPI / M-91 / E of WC 4.26E+02 2.72E+02 3.43E+02 3.57E+02 4 M-91R MNS GWPI / M-91R / E of WC 4.04E+02 3.34E+02 4.07E+02 3.98E+02 4 M-92 MNS GWPI / M-92 / N of WC Ponds NS 3.84E+02 NS 4.15E+02 2 M-92R MNS GWPI / M-92R / N of WC Ponds NS <MDA NS <MDA 2 M-93 MNS GWPI / M-93 / N of IHUP NS 4.03E+02 NS 4.12E+02 2 M-93R MNS GWPI / M-93R / N of IHUP NS <MDA NS 2.11E+02 2 M-94 MNS GWPI / M-94 / SE of IHUP NS <MDA NS <MDA 2 M-95 MNS GWPI / M-95 / Lower Parking NS <MDA NS <MDA 2 M-95R MNS GWPI / M-95R / Lower Parking NS <MDA NS <MDA 2 M-96 MNS GWPI / M-96 / West Parking NS <MDA NS <MDA 2 M-96R MNS GWPI / M-96R / West Parking NS <MDA NS <MDA 2 M-97 MNS GWPI / M-97 / East Parking NS <MDA NS 2.00E+02 2 M-98 MNS GWPI / M-98 / S of Amin. Bldg. NS <MDA NS <MDA 2 M-98R MNS GWPI / M-98R / S of Amin. Bldg. NS <MDA NS <MDA 2 MNS_LEACHP MNS Landfill 2 / Leachate Pond NS 1.93E+03 NS 9.64E+02 2 MNS_MW-10A MNS Landfill 2 / MW-10A NS <MDA NS <MDA 2 MNS_MW-5 MNS Landfill 2 / MW-5 NS <MDA NS NS 1 MNS_MW-5A MNS Landfill 2 / MW-5A NS <MDA NS <MDA 2 MNS_MW-5R MNS Landfill 2 / MW-5R NS NS NS <MDA 1 MNS_MW-6 MNS Landfill 2 / MW-6 NS <MDA NS <MDA 2 MNS_MW-6A MNS Landfill 2 / MW-6A NS <MDA NS <MDA 2 MNS_MW-7 MNS Landfill 2 / MW-7 NS <MDA NS NS 1 MNS_MW-7A MNS Landfill 2 / MW-7A NS <MDA NS <MDA 2 MNS_MW-7R MNS Landfill 2 / MW-7R NS NS NS <MDA 1 MNS_MW-8 MNS Landfill 2 / MW-8 NS <MDA NS <MDA 2 MNS_MW-8A MNS Landfill 2 / MW-8A NS <MDA NS <MDA 2 MNS_MW-9 MNS Landfill 2 / MW-9 NS <MDA NS <MDA 2 MNS_MW-9A MNS Landfill 2 / MW-9A NS <MDA NS <MDA 2 MNS_SW-1 MNS Landfill 2 / SW-1 NS <MDA NS <MDA 2 MNS_SW-2 MNS Landfill 2 / SW-2 NS <MDA NS <MDA 2 MNS-MW-1 MNS Landfarm 2 / MW-1 NS NS NS <MDA 1 MNS-MW-1A MNS Landfarm 2 / MW-1A NS NS NS <MDA 1 MNS-MW-2 MNS Landfarm 2 / MW-2 NS NS NS <MDA 1 MNS-MW-2A MNS Landfarm 2 / MW-2A NS NS NS <MDA 1 MNS-MW-3 MNS Landfarm 2 / MW-3 NS NS NS <MDA 1 MNS-MW-3A MNS Landfarm 2 / MW-3A NS NS NS <MDA 1 MNS-MW-4 MNS Landfarm 2 / MW-4 NS NS NS <MDA 1 MNS-MW-4A MNS Landfarm 2 / MW-4A NS NS NS <MDA 1 MS-1 MNS GWPI / MS-1 / Surface Water <MDA NS NS 2.09E+02 2 MS-2 MNS GWPI / MS-2 / Surface Water 2.61E+02 2.63E+02 NS <MDA 3 MS-3 MNS GWPI / MS-3 / Surface Water <MDA NS NS 4.80E+02 2 MS-4 MNS GWPI / MS-4 / Surface Water 4.18E+02 NS NS NS 1 Page 7-4

Attachment 7 Information to Support the NEI Ground Water Protection Initiative McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Well Tritium Concentration (pCi/l) # of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples MW-1_ML1 MNS Landfill 1 / MW-1 <MDA NS <MDA NS 2 MW-11_ML1 MNS Landfill 1 / MW-11 <MDA NS <MDA NS 2 MW-11D_ML1 MNS Landfill 1 / MW-11D <MDA NS <MDA NS 2 MW-12_ML1 MNS Landfill 1 / MW-12 <MDA NS <MDA NS 2 MW-12D_ML1 MNS Landfill 1 / MW-12D <MDA NS <MDA NS 2 MW-1D_ML1 MNS Landfill 1 / MW-1D <MDA NS <MDA NS 2 MW-2A_ML1 MNS Landfill 1 / MW-2A <MDA NS <MDA NS 2 MW-2D_ML1 MNS Landfill 1 / MW-2D <MDA NS <MDA NS 2 MW-3_ML1 MNS Landfill 1 / MW-3 <MDA NS <MDA NS 2 MW-3D_ML1 MNS Landfill 1 / MW-3D <MDA NS <MDA NS 2 MW-4_ML1 MNS Landfill 1 / MW-4 <MDA NS <MDA NS 2 MW-4D_ML1 MNS Landfill 1 / MW-4D <MDA NS <MDA NS 2 MW-4DR_ML1 MNS Landfill 1 / MW-4DR <MDA NS <MDA NS 2 MW-4R_ML1 MNS Landfill 1 / MW-4R <MDA NS <MDA NS 2 SW-1_ML1 MNS Landfill 1 / SW-1 <MDA NS <MDA NS 2 Page 7-5

Attachment 8 Inoperable Equipment McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 8 Inoperable Equipment This attachment includes an explanation of inoperable instruments related to effluent monitoring in excess of allowed time defined by licensing bases and an explanation of unprotected permanent or temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases).

Page 8-1

Attachment 8 Inoperable Equipment McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station did not experience inoperable equipment relevant to effluent monitoring in excess of SLC limits during 2016.

McGuire Nuclear Station does not have unprotected permanent or temporary outside liquid storage tanks, therefore now exceeded 10 Curies total activity (excluding tritium and dissolved or entrained noble gases) during 2016.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 9 Summary of Changes to the Offsite Dose Calculation Manual This attachment includes a summary of changes to the ODCM and Radiological Effluent Controls.

Page 9-1

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ODCM Revision 58 ODCM Revision 58 is provided in entirety in this section.

All ODCM changes are reviewed by knowledgeable individual(s), and approved by either the Station Manager or Radiation Protection Manager. The changes below do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

ODCM Revision 58 was approved by the Radiation Protection Manager on March 9, 2017. Some changes reflected in ODCM Revision 58 were implemented prior to March 9, 2017 under a different change and approval process (e.g.,

land use census), and in those cases the implementation date is noted below. Changes driven by Document Revision Requests (DRR) are noted with DRR number.

Table of Contents - Page i and ii Marked 6.0-3, Land Use Census Map, as deleted in List of Figures. Marked 6.0-3, Land Use Census Results, as deleted in List of Tables. Adjusted remaining sub-section, Figure, and Table page numbers for Section 6 based on moving Section 6.0.2.

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions. This does not adversely impact the accuracy or reliability of dose calculations, as records of the Land Use Census are maintained in EnRad files and documented with procedure AD-CP-ALL-0014, Land Use Census Evaluation. Changes to Effluent Management Software are implemented based on results of annual Land Use Census, once approved.

Executive Summary - Page 2 Revised statements in second paragraph from:

"The ODCM has been prepared as generically as possible in order to minimize the need for revisions. However, some changes to the ODCM such as land use census data are expected on an annual basis. Any changes to the methodology and parameters to be used in this ODCM shall be reviewed by knowledgeable individual(s), and approved by the Station Manager prior to implementation. Changes to the ODCM shall be submitted to the Nuclear Regulatory Commission in accordance with the SLCs and Technical Specifications."

to:

"The ODCM has been prepared as generically as possible in order to minimize the need for revisions. Any changes to the methodology and parameters to be used in this ODCM shall be reviewed by knowledgeable individual(s), and approved by the Station Manager or Radiation Protection Manager prior to implementation. Changes to the ODCM shall be submitted to the Nuclear Regulatory Commission in accordance with the SLCs and Technical Specifications."

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions. Also updated ODCM approval authority statement based on NRC approved license amendments 276 and 256 to Technical Specification 5.5.1, allowing for Radiation Protection Manager approval.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Section 4 - Page 8 Removed reference to Table 6.0-3 in "*" note. Statement changed from:

"Dose is calculated only for pathways (e.g., garden, milk animal, etc.) that actually exist at each location as determined by the land use census shown in Table 6.0-3."

to:

"Dose is calculated only for pathways (e.g., garden, milk animal, etc.) that actually exist at each location as determined by the land use census."

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions.

Section 6.0.2 - Page 2 Revised from (previously on page 1):

"The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified, and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 6.0-3 and Figure 6.0-3."

to:

"The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified, and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. The land use census identifies nearest pathways to the exclusion area boundary (EAB, ~ 0.5 mile) for each of the 16 meteorological sectors. Global Positioning System field measurements are taken as close as possible to the item of interest and are accurate to within 2-5 meters. Locations beyond the nearest pathway for each sector are assumed to contain that pathway for dose calculation purposes. For the 4.5-5.0 mile sector all pathways, i.e., residence, garden, milk animal (goat), and meat animal (cow), are assumed to exist for dose calculation purposes. Results are maintained on file and data reviewed in accordance with procedure AD-CP-ALL-0014, Land Use Census Evaluation."

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions. This does not adversely impact the accuracy or reliability of dose calculations, as records of the Land Use Census are maintained in EnRad files and documented with procedure AD-CP-ALL-0014, Land Use Census Evaluation. Changes to Effluent Management Software are implemented based on results of annual Land Use Census, once approved.

Section 6.0.2 - Page 4 (previously)

Deleted Table 6.0-3 and moved relevant information fro "*" and "**" Note paragraphs to Section 6.0.2.

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions. This does not adversely impact the accuracy or reliability of dose calculations, as records of the Land Use Census are maintained in EnRad files and documented with procedure AD-CP-ALL-0014, Land Use Census Evaluation. Changes to Effluent Management Software are implemented based on results of annual Land Use Census, once approved.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Section 6.0.2 - Page 7 (previously)

Deleted Figure 6.0-3.

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions. This does not adversely impact the accuracy or reliability of dose calculations, as records of the Land Use Census are maintained in EnRad files and documented with procedure AD-CP-ALL-0014, Land Use Census Evaluation. Changes to Effluent Management Software are implemented based on results of annual Land Use Census, once approved.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radiological Effluent Controls (SLC 16.11)

The McGuire Nuclear Station Radiological Effluent Controls are contained in SLC 16.11 and are included in this section. SLC 16.11 was not revised in 2016.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Units 1 and 2 ODCM Offsite Dose Calculation Manual Page 9-6

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Units 1 and 2 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Revision 58 Prepared By:

1/17/2017 Christopher C. Courtenay Fleet Scientific Services RP Signature Date Reviewed By:

James F. Critz Jr.

MNS Radiation Protection Signature Date Approved By:

John S. Mooneyhan MNS Radiation Protection Manager Signature Date Page 9-7

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

TABLE OF CONTENTS Executive Summary. . . . . . . . . . . . . Executive Summary-1 1.0 Radwaste Systems . . . . . . . . . . . . . . . 1-1 1.0.1 Liquid Radwaste Processing . . . . . . . . . . . . 1-1 1.0.2 Gaseous Radwaste Processing . . . . . . . . . . . . 1-3 1.0.2.1 Gas Collection System . . . . . . . . . . . 1-3 1.0.2.2 Containment and Auxiliary Building Ventilation . . . . . . . 1-3 1.0.2.3 Secondary Systems . . . . . . . . . . . . 1-4 2.0 Release Rate Calculations . . . . . . . . . . . . . 2-1 2.0.1 Liquid Release Rate Limit Calculations . . . . . . . . . . 2-1 2.0.1.1 RC Discharge Release Rate Limit Calculation. . . . . . . . 2-1 2.0.1.2 WC and WWCB Discharge . . . . . . . . . . . 2-2 2.0.2 Gaseous Release Rate Limit Calculations . . . . . . . . . . 2-6 2.0.2.1 Unit Vent Discharge Release Rate Limit Calculation . . . . . . 2-6 3.0 Setpoint Calculations . . . . . . . . . . . . . . 3-1 3.0.1 Liquid Radiation Monitor Setpoint Calculations . . . . . . . . 3-1 3.0.1.1 Waste Monitor Tank Setpoints (EMF 49) . . . . . . . . 3-2 3.0.1.2 Containment Ventilation Unit Condensate Drain Tank Setpoints (EMF 44) . . 3-3 3.0.1.3 Turbine Building Sump to RC Setpoints (EMF 31) . . . . . . . 3-4 3.0.1.4 Turbine Building Sump to WC Setpoints (EMF 31). . . . . . . 3-5 3.0.2 Gaseous Radiation Monitor Setpoint Calculations . . . . . . . . 3-8 3.0.2.1 Containment Air Release and Addition (VQ) Setpoints (EMF 39) . . . . 3-9 3.0.2.2 Containment Purge (VP) and Incore Purge (IP) Setpoints (EMF 39, EMF 36) . . 3-10 3.0.2.3 Waste Gas Decay Tank (WGDT) Setpoints (EMF 50, EMF 36) . . . . 3-13 4.0 Effluent Dose Models . . . . . . . . . . . . . . 4-1 4.0.1 Liquid Effluent Dose Model for the Maximum Exposed Individual . . . . . 4-1 4.0.2 Gaseous Effluent Dose Model for the Maximum Exposed Individual . . . . . 4-7 4.0.3 Direct Radiation . . . . . . . . . . . . . . 4-22 4.0.4 Effluent Apportionment . . . . . . . . . . . . . 4-22 5.0 Fuel Cycle Calculations . . . . . . . . . . . . . . 5-1 5.0.1 Milling . . . . . . . . . . . . . . . . 5-1 5.0.2 Conversion . . . . . . . . . . . . . . . 5-1 5.0.3 Enrichment . . . . . . . . . . . . . . . 5-1 5.0.4 Fuel Fabrication . . . . . . . . . . . . . . 5-1 5.0.5 Nuclear Power Production . . . . . . . . . . . . 5-2 5.0.6 Fuel Reprocessing . . . . . . . . . . . . . . 5-2 5.0.7 40CFR190 Total Dose Determination . . . . . . . . . . 5-2 6.0 Environmental Locations . . . . . . . . . . . . . 6-1 6.0.1 Site Description and Sample Locations . . . . . . . . . . 6-1 6.0.2 Land Use Census Data . . . . . . . . . . . . . 6-2 6.0.3 McGuire Meteorology: Relative Air Concentrations and Deposition . . . . . 6-9 6.0.3.1 XOQDOQ Methodology and Assumptions . . . . . . . . 6-9 6.0.3.2 Meteorological Data . . . . . . . . . . . . 6-9 6.0.3.3 Annual XOQDOQ Comparison to the ODCM . . . . . . . 6-10 7.0 Licensee Initiated Changes . . . . . . . . . . . . . 7-1 i

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Appendices Appendix A: Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases . . . . A-1 Appendix B: P i Dose Factors for use in the Gaseous Release Rate Limit Calculations . . . . B-1 Appendix C: A i Adult Dose Factors for use in the Liquid Dose Calculations . . . . . C-1 Appendix D: A i Teen Dose Factors for use in the Liquid Dose Calculations . . . . . D-1 Appendix E: A i Child Dose Factors for use in the Liquid Dose Calculations . . . . . E-1 Appendix F: A i Infant Dose Factors for use in the Liquid Dose Calculations . . . . . F-1 Appendix G: R i Adult Dose Factors for use in the Gaseous Dose Calculations . . . . . G-1 Appendix H: R i Teen Dose Factors for use in the Gaseous Dose Calculations . . . . . H-1 Appendix I: R i Child Dose Factors for use in the Gaseous Dose Calculations . . . . . I-1 Appendix J: R i Infant Dose Factors for use in the Gaseous Dose Calculations . . . . . J-1 LIST OF FIGURES 1.0-1 Liquid Radwaste System . . . . . . . . . . . . . . 1-2 1.0-2 Gaseous Radwaste System (2 pages) . . . . . . . . . . . 1-5 2.0-1 Liquid Radwaste Discharge Locations . . . . . . . . . . . 2-3 2.0-2 RC Discharge to Lake Norman . . . . . . . . . . . . 2-4 2.0-3 WC and WWCB Discharge to the Catawba River . . . . . . . . . 2-5 2.0-4 Unit Vent Release Points . . . . . . . . . . . . . . 2-10 2.0-5 WMF, WHA, 2-SB Release Points . . . . . . . . . . . . 2-11 6.0-1 Sampling Locations Map (Site Boundary) . . . . . . . . . . . 6-6 6.0-2 Sampling Locations Map (Ten Mile Radius) . . . . . . . . . . 6-7 6.0-3 Land Use Census Map (Deleted). . . . . . . . . . . . . 6-8 LIST OF TABLES 3.0-1 Cs-137 Equivalents . . . . . . . . . . . . . . . 3-7 3.0-2 Xe-133 Equivalents . . . . . . . . . . . . . . . 3-14 6.0-1 Sampling Locations . . . . . . . . . . . . . . . 6-3 6.0-2 TLD Sites . . . . . . . . . . . . . . . . 6-4 6.0-3 Land Use Census Results (Deleted) . . . . . . . . . . . . 6-5 6.0-4 MNS Atmospheric Stability Frequency (1988-1992) . . . . . . . . . 6-10 6.0-5 MNS Frequency of Wind Direction (From) and Speed (1988-1992) . . . . . . 6-10 6.0-6 MNS Limiting /Q and D/Q Values (1988-1992) . . . . . . . . . 6-11 6.0-7 MNS Delta-T Ranges per Vertical Separation Distances . . . . . . . . 6-11 6.0-8 McGuire /Q Average Values (1988-1992) . . . . . . . . . . 6-12 6.0-9 McGuire D/Q Average Values (1988-1992) . . . . . . . . . . 6-13 ii Page 9-9

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

EXECUTIVE

SUMMARY

The McGuire Nuclear Station (MNS) Offsite Dose Calculation Manual (ODCM) provides the methodology and parameters to be used in the calculation of offsite doses due to normal operation radioactive liquid and gaseous effluents to assure compliance with the dose limitations of the Selected Licensee Commitments (SLCs, UFSAR Chapter

16) and Technical Specifications (TSs). These dose limitations assure that:

(1) the concentration of radioactive liquid effluents released from the site to the unrestricted area will be limited to 10 times the effluent concentration (EC) levels of 10CFR20, Appendix B, Table 2, and 2.0E-04 µCi/ml for dissolved and entrained noble gases (TS 5.5.5(a)(2), SLC 16.11.1);

(2) the exposures to any individual member of the public from radioactive liquid effluents will not result in doses greater than the ALARA design objectives of 10CFR50, Appendix I or the 10CFR20 limits (TS 5.5.5(a)(4), SLC 16.11.3);

(3) the dose rate at any time at the site boundary from radioactive gaseous effluents will be limited to: for noble gases; less than or equal to 500 mrem/yr to the whole body, and less than or equal to 3000 mrem/yr to the skin; and for iodine-131 and iodine-133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days; less than or equal to 1500 mrem/yr to any organ (TS 5.5.5(a)(7),

SLC 16.11.6);

(4) the exposure to any individual member of the public from radioactive gaseous effluents will not result in doses greater than the ALARA design objectives of 10CFR50, Appendix I or the 10CFR20 limits (TS 5.5.5(a) (8 and 9), SLCs 16.11.8 and 16.11.9); and (5) the dose to any individual member of the public from the nuclear fuel cycle will not exceed the limits of 40CFR190 (TS 5.5.5(a)(10), SLC 16.11.12).

The methodology and parameters used to assure compliance with the dose limitations described above shall be used to prepare the radioactive liquid and gaseous effluent reports required by the SLCs and Technical Specifications. Dose calculations that demonstrate compliance with 40CFR190 will be considered to Executive Summary - Page 1 Page 9-10

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) demonstrate compliance with the 10CFR20 0.1-rem annual dose limit. The ODCM also provides the methodology and parameters to be used in the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints to assure compliance with the concentration and dose rate limitations of the SLCs and Technical Specifications. Normally RETDAS, a computer code that implements NUREG-0133 methodology, is used for the calculation of offsite doses, but the ODCM also provides a method for the calculation of offsite doses when RETDAS is not available.

The ODCM has been prepared as generically as possible in order to minimize the need for revisions. Any changes to the methodology and parameters to be used in this ODCM shall be reviewed by knowledgeable individual(s), and approved by the Station Manager or Radiation Protection Manager prior to implementation. Changes to the ODCM shall be submitted to the Nuclear Regulatory Commission in accordance with the SLCs and Technical Specifications.

The ODCM does not replace any station implementing procedures. Programmatic controls for radioactive effluents and radiological environmental monitoring are contained in the Administrative Controls chapter of the Technical Specifications.

Procedural details for radioactive effluents and radiological environmental monitoring consisting of licensee commitments, applicability, remedial actions, surveillance requirements, and the bases for these requirements are contained in Section 16.11 of the SLCs.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 1.0 RADWASTE SYSTEMS 1.0.1 LIQUID RADWASTE PROCESSING The liquid radwaste system at McGuire Nuclear Station is used to collect and treat liquid chemical and radiochemical byproducts of unit operation. The system produces effluents that can be reused in the plant or discharged to the environment. The means of treatment vary with waste type and desired product in the various systems:

(A) Filtration - Waste sources are filtered during processing. In some cases, such as the Floor Drain Tank (FDT) subsystem of the Liquid Waste System (WL), filtration may be the only treatment required.

(B) Adsorption - Adsorption of halides and organic chemicals by activated charcoal (carbon filter) may be used in treating waste in the Laundry and Hot Shower Tank (LHST). The carbon filter is designed to remove organophosphates and free chlorine. Activated charcoal need not be used when these chemicals are not present (e.g., phosphate detergents are not used at the station). Ion exchange resin or other media may be used in the carbon filter vessel as desired.

(C) Ion Exchange - Ion exchange is used to remove radioactive cations from solution, as in the case of the FDT waste after removal of organics by carbon filtration (adsorption). Ion exchange can also be used in removing both cations (cobalt, manganese) and anions (chloride, fluoride) from evaporator distillates in order to purify the distillates for reuse as makeup water. Distillate from the Boron Recycle Evaporator in the Boron Recycle System (NB) can be treated by this method.

(D) Gas Stripping - Removal of gaseous radioactive fission products is accomplished in the NB Evaporator.

(E) Distillation - Production of pure water from the waste by boiling it away from the contaminated solution which it was originally contained is accomplished by the NB evaporator. Proper control of the process will yield water that can be reused for makeup. Polishing of this product can be achieved by ion exchange as pointed out above.

(F) Concentration - In the NB Evaporator, dissolved chemicals are concentrated in the lower shell as water is boiled away. The dilute boron is normally concentrated to 4%

so that it may be reused for makeup to the reactor coolant system.

Figure 1.0-1 is a schematic representation of the liquid radwaste system at McGuire.

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Figure 1.0-1 McGuire Nuclear Station Liquid Radwaste System Section 1 - Page 2 Page 9-13

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 1.0.2 GASEOUS RADWASTE PROCESSING The Gaseous Waste System (WG) for McGuire is designed with the capability of processing the fission product gases from contaminated reactor coolant fluids resulting from operation. The design basis for the WG shown schematically in Figure 1.0-2 is the retention, through the plant lifetime, of all the gaseous fission products to be discharged from the reactor coolant system to the Chemical and Volume Control System (NV) and other plant systems to eliminate the need for intentional discharge of radioactive gases from the waste gas holdup tanks. Actual system operation is aimed at maximizing storage time for decay prior to infrequent releases. Unavoidable sources of low level radioactive gaseous discharge to the environment will be from periodic purging operations of the containment, and through the secondary system air ejector. With respect to the former, the potential fission product gas is expected to arise from non-recyclable reactor coolant leakage. With respect to the air ejector, the potential source of fission product gas will be from leakage of the reactor coolant to the secondary system through defects in steam generator tubes. The gaseous waste disposal system includes two waste gas compressors, two catalytic hydrogen recombiners, six gas decay storage tanks for use during normal power generation, and two gas decay storage tanks for use during shutdown and startup operations.

1.0.2.1 GAS COLLECTION SYSTEM The gas collection system combines the waste hydrogen and fission gases from the volume control tanks, the boron recycle and liquid waste gas stripper evaporators, and other sources produced during normal operation or the gas collected during the shutdown degasification (high percentage of hydrogen), and cycles it through the catalytic recombiners to convert hydrogen to water. After the water vapor is removed, the resulting gas stream is transferred from the recombiner into the waste gas decay tanks (WGDTs), where the accumulated activity may be contained in six approximately equal parts. From the decay tanks, the gas flows back to the compressor suction to complete the loop circuit.

1.0.2.2 CONTAINMENT AND AUXILIARY BUILDING VENTILATION Non-recyclable reactor coolant leakage occurring either inside the containment or inside the auxiliary building will generate gaseous activity. Gases resulting from leakage inside the containment atmosphere will be circulated through a charcoal adsorber and a particulate filter prior to release to the atmosphere.

Gases resulting from leakage inside the auxiliary building are released, without further decay, to the atmosphere. The ventilation exhaust from potentially contaminated areas in the auxiliary building is passed through charcoal adsorbers and particulate filters to reduce releases to the atmosphere upon a radiation monitor alarm.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 1.0.2.3 SECONDARY SYSTEMS The gases removed from the secondary system by the air ejectors are discharged to the unit vent. If the secondary system contains activity, the steam generator blowdown may be either discharged directly to the condenser cooling water system or through demineralizers to reduce activity levels.

Gland leak-off steam, which represents a minor source of activity, is routed to the gland condenser. The non-condensable gases are exhausted to the unit vent; the condensables are condensed and drained to the condensate storage tank.

Some low radioactivity secondary system steam releases can occur at the site such as from infrequent lifts or testing of the main steam power operated relief valves (PORVs) and the code safety main steam relief valves. Radioactivity released from secondary system steam releases is documented and included in the site effluent release total.

Figure 1.0-2 is a schematic representation of the gaseous radwaste system at McGuire.

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Figure 1.0-2 McGuire Nuclear Station Gaseous Radwaste System Page 1 of 2 Section 1 - Page 5 Page 9-16

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

Figure 1.0-2 McGuire Nuclear Station Gaseous Radwaste System Page 2 0f 2 Section 1 - Page 6 Page 9-17

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 2.0 RELEASE RATE CALCULATIONS 2.0.1 LIQUID RELEASE RATE LIMIT CALCULATIONS There are two liquid radwaste discharge points to the environment at McGuire; (1) the Condenser Cooling Water System (RC) discharge point to Lake Norman, and (2) the Conventional Waste Water System (WC) and Waste Water Collection Basin (WWCB) discharge point to the Catawba River downstream of Cowan's Ford Dam (See Figure 2.0-1).

2.0.1.1 RC DISCHARGE RELEASE RATE LIMIT CALCULATION Liquid releases to Lake Norman through the RC pathway normally contain the radioactive releases from the site including effluents from the waste monitor tanks and containment ventilation unit condensate drain tanks. The RC discharge point can also contain Turbine Building Sump (TBS) releases, however TBS effluent is normally released through WC. Condenser unwatering (WU) is normally released to the WWCB discharge point. Each unit has four RC pumps that pump 2.5E5 gpm each and provide dilution for releases. Each release path has a radiation monitor (EMF) that is used to monitor the liquid effluent (See Figure 2.0-2).

To comply with Technical Specifications and Selected Licensee Commitments, and to assure that the concentration of radioactive liquid effluents released from the site to the unrestricted area is limited to 10 times the effluent concentrations (ECs) of 10CFR20, Appendix B, Table 2, Column 2, and 2.0E-04 µCi/ml for dissolved and entrained noble gases, the following release rate limit calculation shall be performed for liquid releases to Lake Norman via the RC discharge point:

f (F ÷ (DF 1)) Condition: DF > 1.0 Equation 2.1 where:

f = the undiluted effluent flow, in gpm.

F = the dilution flow available depending on the number (1-8) of RC pumps in service, in gpm.

= (2.50E+05 gpm/pump) x (# of RC pumps in service)

DF = required dilution factor to be applied to the undiluted effluent flow, unitless.

Ci DF = x (10 i x ECi )

Equation 2.2 Section 2 - Page 1 Page 9-18

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

Note:

If DF 1.0 then no dilution is required and the release rate is unrestricted.

If DF > 1.0 then dilution flow is required and the allowable release rate is calculated using Equation 2.1. Equation 2.1 is used only when DF > 1.0.

= the recirculation factor at equilibrium at the RC discharge location, (dimensionless).

The recirculation factor accounts for the fraction of discharged water reused by the station. Equation reference: McGuire Final Environmental Statement, (10/1972)

Qdf 3740

=1+ = 1+ = 2.26 Qcf 2976 where:

Q df = annual average RC dilution flow (3740 cfs). (1990-1994 average flow)

Q cf = annual average flow past Cowans Ford Dam (2970 cfs). (1990-1994 average flow)

Ci = the concentration of radionuclide, i, in the undiluted liquid effluent, in µCi/ml.

EC i = the concentration of radionuclide, i, from 10CFR20, Appendix B, Table 2, Column 2, in µCi/ml. Note: if radionuclide, i, is a dissolved noble gas, then EC i = 2.00E-05 µCi/ml.

2.0.1.2 WC AND WWCB DISCHARGE Liquid releases to the Catawba River through the WC and WWCB discharge pathways normally contain measurable activity above background. The WC/WWCB effluent typically accounts for <1% of the station total liquid activity released. Although designed for continuous discharge, inputs to WC, primarily from the Unit 1 and Unit 2 turbine building sumps, are normally held up in one of two WC Settling Ponds, and then released as a batch. There is a composite sampler at the discharge to the river. An EMF monitors the TBS and Condenser Drain (WU) output (See Figure 2.0-3). It is assumed that no activity is present in the TBS/WU effluent until indicated by radiation monitoring measurements. If an EMF alarms, the TBS/WU pumps are secured. At this time the discharge may be routed to the floor drain tank for processing or routed directly to the condenser cooling water (RC) flow rather than to WC.

Releases going directly to the WWCB are in continuous release. Some activity is planned for release through this pathway during condenser draining; therefore, grab samples are collected and retained for composite generation. Similar to WC, the only radiation monitoring is on the TBS/WU output (see Figure 2.0-3).

WZ (groundwater) Sump C discharges to the Standby Nuclear Service Water Pond (SNSWP). To account for WZ activity discharged into the SNSWP a composite sampler is installed in WZ Sump C (see Figure 2.0-3).

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Figure 2.0-1 Liquid Radwaste Discharge Locations Section 2 - Page 3 Page 9-20

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

Figure 2.0-2 RC Discharge to Lake Norman Section 2 - Page 4 Page 9-21

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

Figure 2.0-3 WC and WWCB Discharge to the Catawba River Section 2 - Page 5 Page 9-22

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 2.0.2 GASEOUS RELEASE RATE LIMIT CALCULATIONS The two unit vents are the primary gaseous radioactive release points at McGuire. The unit vents are the release points for waste gas decay tanks, containment building purges, auxiliary building ventilation, and the condenser air ejector (see Figure 2.0-4). Each unit vent contains multi-range radiation monitors (EMFs) and flow rate measuring instrumentation.

There are three other separate gaseous effluent release points at McGuire; the Waste Management Facility, Waste Handling Area and Unit 2 Staging Building. These three release points contribute a small percentage of the total site gaseous effluent. Each release point has an EMF, composite sampler, and flow totalizer (see Figure 2.0-5).

2.0.2.1 UNIT VENT DISCHARGE RELEASE RATE LIMIT CALCULATION In order to comply with Technical Specifications and Selected Licensee Commitments and to assure that the dose rate, at any time, at or beyond the site boundary due to radioactive materials released in gaseous effluents from the site is limited to: 500 mrem/yr to the total body, and 3000 mrem/yr to the skin for the noble gases, and is limited to 1500 mrem/yr to any organ for radioiodine and for radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than 8 days, the following release rate and radiation monitor setpoint calculations shall be performed for releases from the waste gas decay tanks and the containment building. The release rate calculations when solved for the flow rate,f, are the release rates for noble gases and for radioiodines, particulates and other radionuclides with half-lives greater than 8 days. The most conservative release rate calculated shall control the flow rate. The following equations are based on the site dose rate limits. For simultaneous releases a multiple release calculation is performed to ensure that the site dose rate limits are not exceeded.

a. Noble Gases Total Body:

K i x Q

x Qi < 500 mrem/yr Equation 2.3 i

Skin:

(L + 1.1M ) x i i Q

x Qi < 3000 mrem/yr Equation 2.4 i

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b. Radioiodines, Particulates, and Others Inhalation, Ingestion and Ground Organ Pathways:

(P p i opi x W x Qi x Ei ) < 1500 mrem/yr To include both the food and ground organ dose and the inhalation organ dose the equation can be expanded to:

({(P )

p i opi food/gr x WD / Q + (Popi )inhal x W / Q} x Qi x Ei ) < 1500 mrem/yr Equation 2.5 where:

Ki = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrem/yr per µCi/m3 (See Appendix A).

Li = the skin dose factor due to beta emissions for each identified noble gas radionuclide, i, in mrem/yr per µCi/m3 (See Appendix A).

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per µCi/m3 (See Appendix A).

1.1 = ratio to convert dose (mrad) to dose equivalent (mrem).

P opi = the dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem/yr per µCi/m3 and for the food and ground plane pathways in (m2 x (mrem/yr per µCi/sec)) for organ, o, and radionuclide, i, (See Appendix B for the pathway specific dose commitment factors). Note:

NUREG-1301, page 75, specifies use of the Child age group, Inhalation pathway, for the P opi values.

/Q = the highest calculated annual average dispersion parameter for any area at or beyond the site boundary in sec/m3. For McGuire this value is 7.611E-5 sec/m3.

The location is the NNE sector at 0.5 mile. The boundary for establishing gaseous effluent release limits is the Exclusion Area Boundary (EAB). As shown in McGuire UFSAR Figure 2-5, the EAB is defined as a 2500 foot (~0.5 mile) radius from the station center.

W = the highest calculated annual average dispersion or deposition parameter for estimating the maximum dose rate to an individual from the total inhalation, food, and ground plane pathways:

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W /Q = 7.611E-5 sec/m3, for the inhalation pathway and the airborne H-3 food pathway. The location is the NNE sector at 0.5 mile.

WD/Q = 1.403E-7 m-2, for the food and ground plane pathways. The location is the NNE sector at 0.5 mile.

Ei = the filter removal factor for radionuclide, i, e.g., for 99% removal E i = 0.01.

For VQ and VP releases E i = 0.1 for iodine, 0.01 for particulates. There is no filtration for WGDT releases.

Qi = the release rate of radionuclide, i, in gaseous effluent from all release points at the site, in µCi/sec.

Qi = k 1Cif ÷ k 2 = 472 x Cif Equation 2.6 where:

C i = the concentration of radionuclide, i, in undiluted gaseous effluent, in µCi/ml.

f = the undiluted effluent flow, in ft3/min.

k1 = conversion factor, 2.83E+04 cc/ft3.

k2 = conversion factor, 60 sec/min.

Substituting the expression for Q i in Equation 2.6 into Equations 2.3, 2.4, and 2.5, and solving for the flow rate, f, in each equation gives:

Noble Gases - Total Body Maximum Release Rate:

500 ftb <

472 x /Q x (Ki x Ci )

i Noble Gases - Skin Maximum Release Rate:

3000 fsk <

472 x /Q x [(Li + 1.1Mi ) x Ci ]

i Radioiodines, Particulates, and Others - Organ Maximum Release Rate:

1500 for <

472 x ({(P )

p i opi food/gr x WD / Q + (Popi )inhal x W / Q} x Ei x Ci )

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) f tb , f sk , and f or , are calculated for each batch prior to release. The most limiting gaseous release rate is used to assure that no instantaneous dose rate limit is exceeded.

Section 2 - Page 9 Page 9-26

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

Figure 2.0-4 Unit Vent Release Points Section 2 - Page 10 Page 9-27

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

Figure 2.0-5 WMF, WHA, 2-SB Release Points Section 2 - Page 11 Page 9-28

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (P opi )

Inhalation Pathway - Child Age Group Popi = K ( BR)( DFAoi )

Formula: from NUREG-0133, page 25.

Where:

P opi Dose commitment factor for Child age group, organ o, nuclide i, for the inhalation pathway (mrem/yr per µCi/m3). (See Appendix B for the pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

BR Breathing rate for the Child age group (m3/yr, from Regulatory Guide 1.109): Child - 3700 DFA oi Organ inhalation dose conversion factor for Child age group, organ o, nuclide i, (mrem/pCi), from Table E-9 of Regulatory Guide 1.109.

Section 2 - Page 12 Page 9-29

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 3.0 SETPOINT CALCULATIONS 3.0.1 LIQUID RADIATION MONITOR SETPOINT CALCULATIONS Once the liquid release rate parameters have been established radiation monitor setpoints shall be calculated to assure that the concentration of radioactive liquid effluents released from the site to the unrestricted area is limited to ten times the effluent concentrations (ECs) of 10CFR20, Appendix B, Table 2, Column 2, and 2.0E-04 µCi/ml for dissolved and entrained noble gases. By substituting the dilution factor (DF) from Equation 2.2 into Equation 2.1, solving for the undiluted liquid effluent concentration, C i , and accounting for the monitor background reading, the liquid radiation monitor setpoint can be readily obtained by multiplying C i by the radiation monitor correlation factor, CF i , as follows:

Ci (F + f ) x (10 x ECi )

Equation 3.1 x f SP (C i

i x CFi ) + bkg Equation 3.2 where:

Ci = the maximum allowable concentration of radionuclide, i, in the undiluted liquid effluent, in µCi/ml.

SP = radiation monitor setpoint, in cpm.

CF i = radiation monitor correlation factor for radionuclide, i, in cpm/µCi/ml. These correlation factors are controlled by station procedures.

bkg = background reading for the radiation monitor, in cpm.

All other parameters were previously defined.

Using conservative or "worst-case" parameters in Equation 3.1 and Equation 3.2 can provide a liquid radiation monitor setpoint that does not need to be revised for every release if activity is low enough to allow for this type of operation such as with continuous releases from the WC release point. However, for batch releases, e.g., waste monitor tanks, through the RC discharge the radiation monitor setpoint is calculated based on actual expected activity in the release. In general, liquid radiation monitors are calibrated to Cs-137, and their setpoints are calculated as follows:

Section 3 - Page 1 Page 9-30

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

CCs 137 = (C i

i x Eqi )

Expected cpm = (CCs 137 x CFCs 137 ) + bkg Equation 3.3 "Trip" setpoints are set based on a multiplier factor above the "expected" cpm calculated in Equation 3.3.

where:

C Cs-137 = Cs-137 equivalent concentration, in µCi/ml.

Eq i = Cs-137 equivalence factor for each isotope, excluding tritium, to that of Cs-137 due to different gamma energies and abundance. This factor includes a 4-hour decay time due to the average time between sample and release. (See Table 3.0-1).

All other parameters were previously defined.

3.0.1.1 WASTE MONITOR TANK SETPOINTS (EMF 49)

As shown on Figure 2.0-2, EMF 49 is the controlling radiation monitor for Waste Monitor Tank (WMT) releases. EMF 49 setpoints are based on actual tank activity, and are calculated as follows:

Expected cpm = (CCs 137 x CFCs 137 ) + bkg Trip 1 setpoint = (CCs - 137 x CFCs - 137 x 1.5 ) + bkg When Cs -137 equivalent concentration 1.43E-05 µCi/ml:

Trip 2 setpoint = (CCs - 137 x CFCs - 137 x 2.0 ) + bkg or 3 x bkg , whichever is higher.

If the Cs-137 equivalent concentration is 1.43E-05 µCi/ml, then 1.43E-05 is used in the Trip 1 and Trip 2 setpoint calculations. This is an indication of a low activity tank, and normal EMF fluctuation may cause Trip 2 alarms and release termination.

When Cs -137 equivalent concentration > 1.43E-05 µCi/ml:

Trip 2 setpoint = (CCs - 137 x CFCs - 137 x 2.0 ) + bkg where:

C Cs-137 = Cs-137 equivalent concentration, in µCi/ml.

Section 3 - Page 2 Page 9-31

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

CF Cs-137 = EMF 49 Cs-137 correlation factor, 3.42E+08 cpm/µCi/ml.

bkg = Background reading from EMF 49 after flushed from previous releases.

3.0.1.2 CONTAINMENT VENTILATION UNIT CONDENSATE DRAIN TANK SETPOINTS (EMF 44)

As shown on Figure 2.0-2, EMF 44 is the controlling radiation monitor for Containment Ventilation Unit Condensate Drain Tank (CVUCDT) releases. EMF 44 setpoints are based on actual tank activity, and are calculated as follows:

Expected cpm = CCs 137 x CFCs 137 or bkg, whichever is higher.

Trip 1 setpoint = any value between Expected cpm and Trip 2. Normally 2 x Expected cpm Trip 2 setpoint = The lesser of 3 x Expected cpm or 5.00E+06 cpm x #RC pumps where:

C Cs-137 = Cs-137 equivalent concentration, in µCi/ml.

CF Cs-137 = EMF 44 Cs-137 correlation factor, 3.42E+08 cpm/µCi/ml.

bkg = Background reading from EMF 44.

RC pumps = The least number of available RC pumps that will produce a setpoint greater than Expected cpm.

5.00E+06 = Derived as follows from Equation 3.1:

C (F + f ) x (10 x EC )

x f Given the following for each parameter:

C = The gross activity in the undiluted effluent, µCi/ml.

f = Tank flow which varies from 0-60 gpm, assumed to be 60 gpm.

EC = 9.00E-07 µCi/ml, from 10CFR20, the EC for Cs-134 which is the smallest EC value for any detectable radionuclide that is not known to be absent from the mixture.

Section 3 - Page 3 Page 9-32

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

= Recirculation factor, previously defined as 2.26 (see Section 2, Page 2).

F = Dilution flow available: # of RC pumps x 2.50E+05 gpm/pump. Minimum dilution of one pump is used.

Substituting results in C 1.66E-02 µCi/ml. Next multiply by the EMF 44 correlation factor of 3.42E+08 cpm/µCi/ml: 1.66E-02 x 3.42E+08 = 5.68E+06 cpm. Value is rounded down to 5.00E+06 cpm for added conservatism.

3.0.1.3 TURBINE BUILDING SUMP TO RC SETPOINTS (EMF 31)

As shown on Figure 2.0-2, EMF 31 is the controlling radiation monitor for releases from the Turbine Building Sump (TBS) to the condenser cooling water system (RC). EMF 31 setpoints are based on actual sump activity, and are calculated as follows:

Expected cpm = CCs 137 x CFCs 137 or bkg, whichever is higher.

Trip 1 setpoint = any value between Expected cpm and Trip 2. Normally 2 x Expected cpm Trip 2 setpoint = the lesser of 3 x Expected cpm or 2.10E+05 cpm x #RC pumps where:

C Cs-137 = Cs-137 equivalent concentration, in µCi/ml.

CF Cs-137 = EMF 31 Cs-137 correlation factor, 3.02E+08 cpm/µCi/ml.

bkg = Background reading from EMF 31.

RC pumps = The least number of available RC pumps that will produce a setpoint greater than Expected cpm.

2.10E+05 = Derived as follows from Equation 3.1:

C (F + f ) x (10 x EC )

x f Given the following for each parameter:

C = The gross activity in the undiluted effluent, µCi/ml.

f = Sump flow which varies from 0-1340 gpm, assumed to be 1340 gpm.

Section 3 - Page 4 Page 9-33

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

EC = 9.00E-07 µCi/ml, from 10CFR20, the EC for Cs-134 which is the smallest EC value for any detectable radionuclide that is not known to be absent from the mixture.

= Recirculation factor at the RC discharge point, = 2.26.

F = Dilution flow available: # of RC pumps x 2.50E+05 gpm/pump. Minimum dilution of one pump is used.

Substituting the values yields C 7.47E-04 µCi/ml. Next multiply by the EMF 31 correlation factor of 3.02E+08 cpm/µCi/ml: 7.47E-04 x 3.02E+08 = 2.26E+05 cpm.

Value is rounded down to 2.10E+05 cpm for added conservatism.

3.0.1.4 TURBINE BUILDING SUMP TO WC SETPOINTS (EMF 31)

As shown on Figure 2.0-3, EMF 31 is the controlling radiation monitor for releases from the Turbine Building Sump (TBS) to WC. EMF 31 setpoints are based on actual sump activity, and are calculated as follows:

Expected cpm = CCs 137 x CFCs 137 or bkg, whichever is higher.

Trip 1 setpoint = any value between Expected cpm and Trip 2. Normally 2 x Expected cpm Trip 2 setpoint = the lesser of 3 x Expected cpm or 8.46E+03 cpm where:

C Cs-137 = Cs-137 equivalent concentration, in µCi/ml.

CF Cs-137 = EMF 31 Cs-137 correlation factor, 3.02E+08 cpm/µCi/ml.

bkg = Background reading from EMF 31.

8.46E+03 = Derived as follows from Equation 3.1:

C (F x 0.1 + f ) x (10 x EC )

x f Given the following for each parameter:

C = The gross activity in the undiluted effluent, µCi/ml.

f = Sump flow which varies from 0-6700 gpm, assumed to be 6700 gpm.

Section 3 - Page 5 Page 9-34

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

EC = 9.00E-07 µCi/ml, from 10CFR20, the EC for Cs-134 which is the smallest EC value for any detectable radionuclide that is not known to be absent from the mixture.

= Recirculation factor at point where WC enters the Catawba River downstream of Cowans Ford Dam = 1.26.

F = Dilution flow available: Cowans Ford flow may vary from 80 to 50,000 cfs, but is conservatively estimated at 436 cfs (1.96E5 gpm), the historic minimum dilution flow available.

0.1 = Only 10% of Cowans Ford flow is assumed for dilution credit to account for incomplete mixing of the WC effluent downstream of Cowans Ford Dam.

Substituting the values yields C 2.80E-05 µCi/ml. Next multiply by the EMF 31 correlation factor of 3.02E+08 cpm/µCi/ml: 2.80E-05 x 3.02E+08 = 8.46E+03 cpm.

Value is rounded down to 8.00E+03 cpm for added conservatism.

Section 3 - Page 6 Page 9-35

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

Table 3.0-1 Cs-137 Equivalents Isotope Equivalence Isotope Equivalence Isotope Equivalence Factor Factor Factor Be-7 0.1282 Mo-99 0.3135 La-141 0.0132 F-18 0.5238 Tc-99m 0.5788 La-142 0.2785 Na-24 1.3013 Tc-101 0.00 Ce-141 0.4966 Cl-38 0.0068 Ru-103 1.1798 Ce-143 0.7066 K-40 0.0913 Ru-105 0.8673 Ce-144 0.1321 Cr-51 0.1207 Ru-106 0.4097 I-130 3.1610 Mn-54 1.0871 Ag-108m 3.2676 I-131 1.2074 Mn-56 0.4826 Ag-110m 3.5043 I-132 1.0137 Fe-59 0.9915 Cd-115 0.4739 I-133 1.0971 Co-57 0.8892 Cd-115m 0.0228 I-134 0.1396 Co-58 1.4883 In-115m 0.3048 I-135 0.8432 Co-60 1.8564 Sb-122 0.8691 Ar-41 0.1987 Cu-64 0.3577 Sb-124 2.0195 Kr-85 0.0054 Ni-65 0.1389 Sb-125 1.0467 Kr-85m 0.5240 Zn-65 0.5278 Sb-126 5.0018 Kr-87 0.1020 Zn-69m 0.9788 Sn-113 0.8413 Kr-88 0.4607 Se-75 1.9710 Sn-123 0.0062 Kr-89 0.00 Br-80m 0.0821 Sn-126 0.1747 Xe-131m 0.0211 Br-82 3.3664 Te-125m 0.0023 Xe-133 0.0520 Br-83 0.0054 Te-127 0.0116 Xe-133m 0.1176 Br-84 0.0056 Te-127m 0.0005 Xe-135 0.8334 Br-85 0.00 Te-129 0.0122 Xe-135m 0.00 Rb-86 0.0873 Te-129m 0.0526 Xe-137 0.00 Rb-88 0.00 Te-131 0.0016 Xe-138 0.00 Rb-89 0.00 Te-131m 1.9281 Nd-147 0.3706 Sr-89 0.0002 Te-132 1.0302 Hf-181 1.7053 Sr-91 0.6398 Te-134 0.0402 W-187 0.8499 Sr-92 0.3415 Cs-134 2.5843 Tl-208 0.00 Y-91 0.0028 Cs-136 3.1799 Bi-212 0.0140 Y-91m 0.0403 Cs-137 1.00 Bi-214 0.0003 Y-92 0.1281 Cs-138 0.0110 Pb-212 0.4507 Y-93 0.1009 Ba-133 1.2331 Pb-214 0.0018 Zr-95 1.1163 Ba-139 0.0255 Ra-226 0.0386 Zr-97 1.1163 Ba-140 0.5022 Ac-228 0.8370 Nb-95 1.1114 Ba-141 0.0002 Th-228 0.0090 Nb-95m 0.2929 Ba-142 0.00 Np-239 0.8989 Nb-97 0.1164 La-140 2.0586 Section 3 - Page 7 Page 9-36

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 3.0.2 Gaseous Radiation Monitor Setpoint Calculations In general, gaseous radiation monitors (EMFs) are calibrated to Xe-133, and for continuous release points, e.g., the two unit vents, are preset at a maximum value based on the 500 mrem/year total body gaseous release rate limit according to the following methodology. Note: when applied to the individual release points the 500 mrem/year site dose rate value is apportioned 40% to each unit vent, 7% to the Waste Handling Area, and 6.5% each to the Waste Management Facility and Unit 2 Staging Building.

KXe 133 x / Q x QXe 133 < 500 mrem/yr Solve for Q Xe-133 :

500 QXe 133 < Equation 3.4 KXe 133 x / Q From Equation 2.6:

QXe133 = 472 x CXe133 x f Equation 3.5 Substitute Equation 3.5 into Equation 3.4:

500 472 x CXe133 x f <

KXe133 x /Q Solve for C Xe-133 :

500 CXe133 <

472 x f x KXe133 x /Q SP = (CXe 133 x CF ) + bkg Equation 3.6 where:

K Xe-133 = 294, the total body dose factor due to gamma emissions for Xe-133, in mrem/year per µCi/m3 (See Appendix A).

/Q = the highest calculated annual average dispersion parameter for any area at or beyond the site boundary in sec/m3. For McGuire this value is 7.611E-5 sec/m3. The location is the NNE sector at 0.5 mile.

Q Xe-133 = Xe-133 equivalent release rate limit for the noble gas total body dose pathway, in µCi/sec.

Section 3 - Page 8 Page 9-37

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 472 = Conversion factor, (cc/ft3)/(sec/min).

C Xe-133 = the maximum allowable Xe-133 equivalent concentration in the gaseous effluent, in µCi/cc.

f = the gaseous effluent flow from the tank, building, or vent, in ft3/min.

SP = radiation monitor setpoint, in cpm.

CF = the Xe-133 equivalent monitor correlation factor, in cpm/µCi/cc. The correlation factors are controlled by station procedures.

bkg = the radiation monitor background reading, in cpm.

Equation 3.6 provides the methodology to calculate the maximum setpoint for continuous releases. However, most gaseous releases at McGuire are batch releases, e.g.,

Containment Purge (VP), in which the radiation monitor setpoint is calculated based on actual activity expected in the release. For batch releases with a low activity release rate, e.g., Containment Air Release and Addition (VQ), the expected monitor response is essentially no greater than the existing reading, and the trip setpoints are based on multiples of the existing cpm or a maximum based on flow rate. For batch releases where the effluent can contain activity significantly above background, e.g., Waste Gas Decay Tank (WGDT), the following setpoint methodology is used:

CXe 133 = (C i

i x Eqi )

Expected Cpm = (CXe 133 x CFXe 133 ) + bkg Equation 3.7 "Trip" setpoints are set based on a multiplier factor above the "expected" cpm calculated in Equation 3.7.

where:

C Xe-133 = Xe-133 equivalent concentration, in µCi/ml.

Eq i = Xe-133 equivalence factor for each isotope, excluding tritium, to that of Xe-133 due to different beta energies and abundance. (See Table 3.0-2).

All other parameters were previously defined.

3.0.2.1 CONTAINMENT AIR RELEASE AND ADDITION (VQ)

SETPOINTS (EMF 39)

As shown on Figure 2.0-4 and Figure 2.0-5, EMF 39 is the controlling radiation monitor for VQ releases from Containment to the Unit Vent. EMF 39 setpoints for VQ releases are calculated as follows:

Section 3 - Page 9 Page 9-38

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

Expected cpm = background = current reading Trip 1 setpoint = any number between Expected cpm and Trip 2, normally 2 x Expected cpm Trip 2 setpoint = 3 x Expected cpm or 2.9E+04 cpm (setpoint at VP maximum flow rate), whichever is largest, not to exceed 2.2E+06 cpm. 2.2E+06 cpm derived as follows:

From Equation 3.6 SP = (CXe 133 x CF ) + bkg where for a single unit vent release point:

200 CXe133 <

472 x f x KXe133 x /Q Substituting 300 cfm for the VQ flow rate (system max), 294 mrem/yr/µCi/m3 for the total body Xe-133 dose factor (See Appendix A), and the values for all the other previously defined parameters:

200 CXe-133 <

472 x 300 x 294 x 7.611E-05 CXe-133 < 6.3E-02 µCi/ml Substituting 3.54E+07 cpm/µCi/ml for the EMF 39 monitor correlation factor and given that background is negligible compared to the maximum Trip 2 setpoint yields:

SP = 6.3E-02 x 3.54E+07 2.2E+06 cpm 3.0.2.2 CONTAINMENT PURGE (VP) AND INCORE PURGE (IP)

SETPOINTS (EMF 39, EMF 36)

As shown on Figure 2.0-4 and Figure 2.0-5, EMF 39 is the controlling radiation monitor for VP and IP releases from Containment to the Unit Vent.

For VP and IP low activity releases (i.e. Expected cpm 1.0E+04 cpm) only EMF 39 setpoints are calculated. EMF 39 setpoints for VP and IP low activity releases are calculated as follows:

Expected cpm = background = current reading Section 3 - Page 10 Page 9-39

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

Trip 1 setpoint = any number between Expected cpm and Trip 2, normally 2 x Expected cpm Trip 2 setpoint = 2.9E+04 cpm, derived as follows:

From Equation 3.6 SP = (CXe 133 x CF ) + bkg where for a single unit vent release point:

200 CXe133 <

472 x f x KXe133 x /Q Substituting 2.31E+04 cfm for the VP flow rate, 294 mrem/yr/µCi/m3 for the total body Xe-133 dose factor (See Appendix A), and the values for all the other previously defined parameters:

200 CXe-133 <

472 x 2.31E+04 x 294 x 7.611E-05 CXe-133 < 8.20E-04 µCi/ml Substituting 3.54E+07 cpm/µCi/ml for the EMF 39 monitor correlation factor and given that background is negligible compared to the maximum Trip 2 setpoint yields:

SP = 8.20E-04 x 3.54E+07 2.9E+04 cpm Note: The flow rate used for VP is 2.31E+04 cfm, but the same setpoint would be used for IP. The IP flow rate is 800 cfm, therefore the 2.9E+04 cpm setpoint is conservative for IP.

For VP and IP high activity releases (i.e. Expected cpm > 1.0E+04 cpm) it may be necessary to give the "affected" unit (the unit making the VP or IP release) a greater allowable release rate than the 200 mrem/yr default value. For the VP and IP high activity cases, in addition to EMF 39 setpoints, the EMF 36 Trip 2 setpoint is calculated as follows:

VP x EMF 39 cpm x 0.75 EMF 36 Expected CPM =

(VP * + UV )

where:

EMF 39 cpm = EMF 39 present or expected reading.

Section 3 - Page 11 Page 9-40

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 0.75 = approximate value of EMF 36 correlation factor (2.60E+07)/EMF 39 correlation factor (3.54E+07).

UV = Unit Vent flow rate (cfm).

VP = VP calculated flow rate (cfm):

2.31E+04 cfm x 1.45E+04 cpm x M VP Flow Rate =

Desired EMF 39 Trip 2 minus bkg (normally 2.90E +04 cpm) where:

2.31E+04 cfm = Full VP flow rate.

1.45E+04 cpm = cpm related to 100 mrem at full VP flow rate.

M = Multiplication factor for dose assignment to the affected unit vent. M can be 2 (= 200 mrem/yr), but, if > 2, both unit vents together must be 4 (=400 mrem/yr). Note that increasing the Multiplication Factor is in effect giving the "affected" unit more of the station release rate limit, and decreasing the release rate limit for the "unaffected" unit.

VP* indicates that VP flow is not used in the denominator if VP is already running.

M AFFECTED EMF 36 Trip 2 = x 4.10E+03 cpm 2

where:

4.10E+03 cpm = Normal EMF 36 Trip 2 setpoint (derived below)

UNAFFECTED EMF 36 Trip 2 = 8.20E +03 cpm - AFFECTED EMF 36 Trip 2 where:

8.20E+03 cpm = Total cpm allowed for both unit vents (2 x 4.10E+03).

4.10E+03 cpm is derived as follows:

From Equation 3.6 SP = (CXe 133 x CF ) + bkg where for a single unit vent release point:

Section 3 - Page 12 Page 9-41

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 200 CXe133 <

472 x f x KXe133 x /Q Substituting 1.20E+05 cfm for the UV flow rate, 294 mrem/yr/µCi/m3 for the total body Xe-133 dose factor (See Appendix A), and the values for all the other previously defined parameters:

200 CXe-133 <

472 x 1.20E+05 x 294 x 7.611E-05 CXe-133 < 1.58E-04 µCi/ml Substituting 2.60E+07 cpm/µCi/ml for the EMF 36 monitor correlation factor and given that background is negligible compared to the maximum Trip 2 setpoint yields:

SP = 1.58E-04 x 2.60E+07 = 4.10E+03 cpm 3.0.2.3 WASTE GAS DECAY TANK (WGDT) SETPOINTS (EMF 50, EMF 36)

As shown on Figure 2.0-4 and Figure 2.0-5, EMF 50 (when operable) and EMF 36 (when EMF 50 is not operable) are the controlling radiation monitors for WGDT releases to the Unit Vent.

EMF 50 setpoints are based on actual tank activity, and are calculated as follows:

Expected cpm = (CXe 133 x CFXe 133 ) + bkg Trip 1 setpoint = (CXe - 133 x CFXe - 133 x 1.5) + bkg Trip 2 setpoint = (CXe - 133 x CFXe - 133 x 3.0 ) + bkg where:

C Xe-133 = Xe-133 equivalent concentration, in µCi/ml.

CF Xe-133 = EMF 50 Xe-133 correlation factor, 1.75E+06 cpm/µCi/ml.

bkg = Background reading from EMF 50.

If the Xe-133 equivalent concentration is 5.71E-05 µCi/ml, then 5.71E-05 is used in the Trip 1 and Trip 2 setpoint calculations. This is an indication of a low activity tank, and normal EMF fluctuation may cause Trip 2 alarms and release termination.

Section 3 - Page 13 Page 9-42

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

The unit vent gas radiation monitor, EMF 36, is used as the controlling monitor for WGDT releases if EMF 50 is inoperable. In the rare occurrence that EMF 36 must be used as the controlling monitor for WGDT releases only the "expected" cpm is calculated, and the EMF counts are monitored manually during the WGDT release. The EMF 36 expected counts from WGDT activity is calculated as follows:

40 cfm x CXe - 133 x CFXe - 133 Expected cpm = + bkg FUV where:

C Xe-133 = Xe-133 equivalent concentration, in µCi/ml.

CF Xe-133 = EMF 36 Xe-133 correlation factor, 2.60E+07 cpm/µCi/ml.

bkg = Background reading from EMF 36.

40 cfm = Maximum Waste Gas flow rate.

F UV = Current Unit Vent (U1) flow rate.

Table 3.0-2 Xe-133 Equivalents Isotope EMF 36/39 EMF 50 Equivalence Equivalence Factors Factors Kr-83m 0 0 Kr-85m 2.48 7.60 Kr-85 2.56 7.24 Kr-87 2.93 8.73 Kr-88 2.78 8.20 Kr-89 2.93 8.73 Kr-90 2.93 8.73 Xe-131m 1.69 3.10 Xe-133m 1.99 4.50 Xe-133 1.00 1.00 Xe-135m 0.83 1.44 Xe-135 2.63 7.60 Xe-137 2.93 8.73 Xe-138 2.93 8.73 Ar-41 2.82 8.40 C-11 2.70 8.20 Section 3 - Page 14 Page 9-43

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 4.0 EFFLUENT DOSE MODELS The effluent dose models used to show compliance with 10CFR50, Appendix I ALARA design objectives, 40CFR190 fuel cycle dose limits, and the dose values given in station SLCs are based on the methodology given in NUREG-0133 and Regulatory Guide 1.109.

Dose contributions to the maximum individual shall be calculated at least every 31 days, quarterly, and annually using the RETDAS computer code which implements the ODCM methodology. RETDAS, Radioactive Effluent Tracking and Dose Assessment Software, is a database application designed by Canberra Industries, Inc. to automate many of the tasks required in the administration of effluent releases at McGuire. RETDAS performs normal operation effluent dose assessment using NUREG-0133 and Regulatory Guide 1.109 methodology.

Station long-term historical and dose projection calculations are performed periodically to determine the station's status with respect to meeting annual ALARA goals specified in the McGuire SLCs. Such calculations are used to verify that adequate margin remains during a report period to allow normal station and radwaste system operation, including anticipated operational occurrences, for the remainder of the report period without exceeding applicable goals. Station 31-day dose projections that are used to assess the need to reduce effluent releases with the Gaseous Waste (WG) or Liquid Waste (WL) systems as required in the McGuire SLCs are estimated by the previous month's calculated dose results.

Fuel cycle dose calculations shall be performed annually or as required by special reports.

Dose contributions shall be calculated using the RETDAS computer program.

4.0.1 LIQUID EFFLUENT DOSE MODEL FOR THE MAXIMUM EXPOSED INDIVIDUAL Of the possible exposure pathways in the aquatic environment, only three contribute significantly to the total dose; these pathways are ingestion of potable water and aquatic foods, and direct exposure from radioactivity deposited on the shoreline. The dose contribution from these pathways for measured quantities of radioactive materials identified in liquid effluents released to unrestricted areas shall be calculated for the maximum exposed individual in each age group using the methodology provided in this section.

There are two liquid discharge points to the environment at McGuire; (1) the Condenser Cooling Water System (RC) discharge point to Lake Norman, and (2) the Conventional Waste Water System (WC) and Waste Water Collection Basin (WWCB) discharge point to the Catawba River downstream of Cowan's Ford Dam (See Figure 2.0-1). Liquid dose calculations for the maximum exposed individual are performed and documented in the Annual Radioactive Effluent Release Report for both locations using the applicable Section 4 - Page 1 Page 9-44

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) activity release and dilution data for each liquid effluent release point. The primary liquid effluent discharge point for McGuire is through RC to Lake Norman. In general, only low activity tritium releases (<1% station total) occur through the WC and WWCB discharge point to the Catawba River. Dose calculations are performed for each of the two liquid discharge points for dose reporting purposes. The highest calculated dose from the two dose calculations is used to define the maximum individual dose from liquid releases at McGuire.

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Liquid Dose Calculations The following equation is used for calculating liquid dose to the maximum exposed individual from each of the two liquid effluent release points:

Doseoa = (A p i oapi x Ci )x Dt x Fn f

Fn = x f +F Formula: adapted from NUREG-0133, pages 15-17.

Where:

Dose oa The cumulative dose commitment for organ o and age group a, from the liquid effluent for the total time period, Dt. (mrem)

A oapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i (mrem/hr per µCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).

C i The average concentration of nuclide i, in undiluted liquid effluent during the time period, Dt. (µCi/ml)

Dt The length of time over which C i and F n are averaged for all liquid releases. (hr)

F n The near field average dilution factor for C i during the period of interest, Dt. Includes the recirculation factor. (dimensionless) f Average liquid radwaste flow during the period of interest, Dt. (gpm)

F Average dilution flow during the period of interest, Dt. (gpm)

RC primary discharge location: RC average dilution flow WC discharge location: 10% of Cowans Ford Dam average dilution flow Recirculation factor*. (dimensionless)

Lake Norman (RC) = 2.26 for fish, shoreline; = 1.26 for potable water Catawba River (WC and WWCB) = 1.26 for fish, potable water, shoreline

The recirculation factor accounts for the fraction of discharged water reused by the station. The recirculation factors are based on methodology given in the McGuire Final Environmental Statement (10/1972), and historic annual average values based on 1990-1994 data. These values can be modified to account for deviations from average in a particular year for use in calculating maximum individual dose. A recirculation factor of 4.0 is currently being used for all pathways in the liquid dose calculation model for added conservatism.

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Derivation of Liquid Dose Commitment Factors (A oapi )

Potable Water U aw - t Aoapi = 1.14 x105 x x Daoi x e i p Dw Formula: from NUREG-0133, page 16, and Regulatory Guide 1.109, pg. 1.109-12.

Where:

A oapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per µCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).

1.14x105 Units conversion factor (pCi-yr-ml)/(µCi-hr-l).

U aw Water consumption rate in liters per year for age group a. From Table E-5, Regulatory Guide 1.109.

Adult - 730 Teen - 510 Child - 510 Infant - 330 D w Dilution factor from the near field area to the potable water intake;

=1.0 for McGuire.

D aoi Dose factor for age group a, organ o, nuclide i, in mrem/pCi. From tables E-11 through E-14 of Regulatory Guide 1.109.

i Decay constant for nuclide i, in sec-1.

t p Environmental transit time from release to receptor. Default =

4.32E+04 sec (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ). From Regulatory Guide 1.109, Table E-15.

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Aquatic Foods

- it p Aoapi = 1.14 x 105 x U af x BFi x Daoi x e Formula: from NUREG-0133, page 16, and Regulatory Guide 1.109, pg. 1.109-12.

Where:

A oapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per µCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).

5 1.14x10 Units conversion factor (pCi-yr-ml)/(µCi-hr-l).

U af Fish consumption rate for age group a (kg/yr). From Table E-5, Regulatory Guide 1.109.

Adult - 21 Teen - 16 Child - 6.9 Infant - 0 BF i Bioaccumulation factor for nuclide i, in fish, in units of (pCi/kg per pCi/liter). From Table A-1 of Regulatory Guide 1.109.

D aoi Dose factor for age group a, organ o, nuclide i, in mrem/pCi. From tables E-11 through E-14 of Regulatory Guide 1.109.

i Decay constant for nuclide i, in sec-1.

t p Environmental transit time from release to receptor. Default =

8.64E+04 sec (1 day). From Regulatory Guide 1.109, Table E-15.

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Shoreline Sediment 1

i t p Aoapi = 1.14 x 10 5 x 100 x DFGoi x w x U as x Ti 2 x e x (1 e itb )

Formula: adapted from Regulatory Guide 1.109, page 1.109-14.

Where:

A oapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per µCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).

5 1.14x10 Units conversion factor (pCi-yr-ml)/(µCi-hr-l).

100 Proportionality constant used in the sediment radioactivity model, (liters/(m2-day).

DFG oi Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/m2), from Table E-6 of Regulatory Guide 1.109.

w Shoreline width factor. For McGuire = 0.3, from Table A-2, Regulatory Guide 1.109.

U as Shoreline exposure rate for age group a (hr/yr), From Table E-5, Regulatory Guide 1.109.

Adult - 12 Teen - 67 Child - 14 Infant - 0 T i 1/2 Nuclide half life for nuclide i, in days.

i Nuclide decay constant for nuclide i.

t p Average transit time to point of exposure (0 hours0 days 0 hours 0 weeks 0 months ).

t b Sediment exposure time (15 years). Page 1.109-14.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 4.0.2 GASEOUS EFFLUENT DOSE MODEL FOR THE MAXIMUM EXPOSED INDIVIDUAL The dose contributions from measured quantities of radioactive materials identified in gaseous effluent released to unrestricted areas shall be calculated for the maximum gamma and beta air dose from noble gases, and for the maximum exposed individual from radioiodines, particulates, and others using the following equations:

Gaseous Dose Calculations Noble Gas Dose Calculations Gamma Air Dose Dose = 3.17 x 10 8 x / Q x (M i x Qi )

i Formula: adapted from NUREG-0133, page 28.

Where:

Dose Gamma air dose for the time period of interest (mrad).

3.17x10-8 Inverse number of seconds in year (year/seconds).

M i Gamma air dose factor due to gamma emissions for nuclide i (mrad/yr per µCi/m3). (See Appendix A).

/Q The highest calculated annual average relative concentration for any area at or beyond the site boundary (sec/m3). (See Table 6.0-8).

Q i Activity for nuclide i released during the time period of interest (µCi).

Beta Air Dose Dose = 3.17 x10 8 x / Q x (N i x Qi )

i Formula: adapted from NUREG-0133, page 28.

Where:

Dose Beta air dose for the time period of interest (mrad).

3.17x10-8 Inverse number of seconds in year (year/seconds).

N i Beta air dose factor due to beta emissions for nuclide i (mrad/yr per

µCi/m3). (See Appendix A).

/Q The highest calculated annual average relative concentration for any area at or beyond the site boundary (sec/m3). (See Table 6.0-8).

Q i Activity for nuclide i released during the time period of interest (µCi).

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Iodine, Particulates, and H-3 Dose Organ Dose Calculation Doseoa = 3.17 x 10 8 x W x p

(R i

oapi x Qi )

Formula: adapted from NUREG-0133, pages 29 & 30.

Where:

Dose oa The cumulative dose commitment to the total body or any organ o, for an individual of age group a (mrem).

-8 3.17x10 Inverse number of seconds in year (year/seconds).

R oapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i. The units are based on whether a dispersion or deposition factor is used. When a /Q is used the units are mrem/yr per µCi/m3.

When a D/Q is used the units are (m2

mrem/yr) per µCi/sec. (See Appendices G through J for age group and pathway specific dose commitment factors).

W Dispersion (/Q) or deposition factor (D/Q). The factor used is based upon the pathway. Note: /Q is always used for tritium and C-14.

Pathway Factor Used Ground Plane Deposition D/Q (m-2)

Inhalation /Q (sec/m3)

Vegetation D/Q (m-2)

Grass/Cow/Milk D/Q (m-2)

Grass/Goat/Milk D/Q (m-2)

Grass/Cow/Meat D/Q (m-2)

Q i ** Activity for nuclide i, released during the time period of interest (µCi).

Maximum individual organ dose is determined by calculating the organ dose at each of the /Q and D/Q locations shown in Table 6.0-8 and Table 6.0-9 (144 locations), and then choosing the maximum dose. Dose is calculated only for pathways (e.g., garden, milk animal, etc.) that actually exist at each location as determined by the land use census. The boundary for establishing gaseous effluent release limits is the Exclusion Area Boundary (EAB). As shown in McGuire UFSAR Figure 2-5, the EAB is defined as a 2500 foot (~0.5 mile) radius from the station center.

- C-14 airborne activity released to the environment is estimated based on actual power generation as discussed in Regulatory Guide 1.21, Revision 2. A value of 9.4 Ci/GWe-yr is used along with actual power generation to estimate C-14 activity released to the environment via gaseous effluents from McGuire. 9.4 Ci/GWe-yr is based on information from "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents",

EPRI, Palo Alto, CA: 2010. 1021106.

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Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (R oapi )

Ground Plane Deposition Pathway (1 e i t )

Roapi = K K ( SF ) DFGoi i

Formula: from NUREG-0133, page 32.

Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for ground plane deposition pathway (m2*mrem/yr per µCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

K" Units conversion factor 8760 hr/year.

SF Shielding factor (dimensionless) (0.7, from Regulatory Guide 1.109).

DFG oi Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/m2), from Table E-6 of Regulatory Guide 1.109.

-1 i Nuclide decay constant for nuclide i (sec ).

t Exposure time, 4.73x108 seconds (15 years).

Inhalation Pathway Roapi = K ( BRa )( DFAoi ) a Formula: from NUREG-0133, page 31.

Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for inhalation pathway (mrem/yr per µCi/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

BR a Breathing rate for age group a (m3/yr), from Regulatory Guide 1.109:

Adult - 8000 Teen - 8000 Child - 3700 Infant - 1400 (DFA oi ) a Organ inhalation factor dose conversion factor for organ o, nuclide i, age group a (mrem/pCi), from Tables E-7 through E-10 of Regulatory Guide 1.109.

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Vegetation Roapi = K (r )

[

x ( DFLo i ) a x U a f L e L i t L

+ U aS f g e i t h ]

Yv (i + w )

Formula: from NUREG-0133, page 35. Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for vegetation pathway (m2*mrem/yr per µCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

r Fraction of deposited activity retained on vegetation, from Regulatory Guide 1.109.

1.0 for radioiodine.

0.2 for particulates.

Y v Vegetation areal density (kg/m2) (2.0, from Regulatory Guide 1.109).

-1 i Nuclide decay constant for nuclide i (sec ).

w Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x10-7 sec-1, from NUREG-0133).

(DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Reg. Guide 1.109 (mrem/pCi).

L U a Consumption rate of fresh leafy vegetation for age group a (kg/yr)

(from Regulatory Guide 1.109).

Adult - 64 Teen - 42 Child - 26 Infant - 0 f L Fraction of annual intake of fresh leafy vegetation grown locally (1.0, from NUREG-0133).

t L Average time between harvest of leafy vegetation and consumption (8.6x104 seconds, (1 day), from Regulatory Guide 1.109).

US a Consumption rate of stored vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).

Adult - 520 Teen - 630 Child - 520 Infant - 0 f g Fraction of annual intake of stored vegetation (0.76, from Regulatory Guide 1.109).

t h Average time between harvest of stored vegetation and consumption (5.18x106 seconds, (60 days), from Regulatory Guide 1.109).

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Vegetation - Tritium

[ ]

Roapi = K' K' " U aL f L + U aS f g ( DFLoi ) a [0.75(0.5 / H )]

Formula: from NUREG-0133, page 36.

Where:

R oapi Dose commitment factor for organ o, age group a, for vegetation pathway and tritium (mrem/yr per µCi/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

K'" Units conversion factor gm/kg (103).

UL a Consumption rate of fresh leafy vegetation for age group a (kg/yr)

(from Regulatory Guide 1.109).

Adult - 64 Teen - 42 Child - 26 Infant - 0 f L Fraction of annual intake of fresh leafy vegetation grown locally (1.0, from NUREG-0133).

US a Consumption rate of stored vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).

Adult - 520 Teen - 630 Child - 520 Infant - 0 f g Fraction of annual intake of stored vegetation (0.76, from Regulatory Guide 1.109).

(DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

0.75 Fraction of total feed that is water. (From NUREG-0133).

0.5 Ratio of specific activity of feed grass water to atmospheric water.

(From NUREG-0133).

H Absolute humidity of the atmosphere (8 gm/m3, from Regulatory Guide 1.109).

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Vegetation - Carbon-14

[ ]

Roapi = K' K'" U aL f L + U aS f g ( DFLoi ) a [0.11 / 0.16]( p )( f I )

Formula: from NUREG-0133, page 36 and Regulatory Guide 1.109, page 26.

Where:

R oapi Dose commitment factor for organ o, age group a, for vegetation pathway and carbon-14 (mrem/yr per µCi/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

K'" Units conversion factor gm/kg (103).

UL a Consumption rate of fresh leafy vegetation for age group a (kg/yr)

(from Regulatory Guide 1.109).

Adult - 64 Teen - 42 Child - 26 Infant - 0 f L Fraction of annual intake of fresh leafy vegetation grown locally (1.0, from NUREG-0133).

US a Consumption rate of stored vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).

Adult - 520 Teen - 630 Child - 520 Infant - 0 f g Fraction of annual intake of stored vegetation (0.76, from Regulatory Guide 1.109).

(DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

0.11 Fraction of total plant mass that is natural carbon.

0.16 Concentration of natural carbon in the atmosphere (gm/m3).

p Ratio of the total annual C-14 release time to the total annual time during which photosynthesis occurs. This value is assumed to be 0.31, based on 70% of C-14 releases being from WGDTs, and 30% of C-14 releases being continuous from the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14", 2004).

f I The fraction of C-14 assumed to be in inorganic form (e.g., CO 2 ).

Assumed to be 20%. Reference EPRI TR-105715, "Characterization of Carbon-14 Generated by the Nuclear Power Industry", Table 5-1.

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Grass/Cow/Milk QF (U ap ) f p f s (1 f p f s )e i t h i t f Roapi = K Fmi ( r )( DFLoi ) a + e i + w pY Ys Formula: from NUREG-0133, pages 32 & 33. Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/milk pathway (m2*mrem/yr per µCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

Q F Cow consumption rate (50 kg/day, from Regulatory Guide 1.109)

U ap Consumption rate of cow milk for age group a (liters/yr, from Regulatory Guide 1.109).

Adult - 310 Teen - 400 Child - 330 Infant - 330 r Fraction of deposited activity retained on cows feed grass, (from Regulatory Guide 1.109).

1.0 for radioiodine.

0.2 for particulates.

Y p Agricultural productivity by unit area of pasture feed grass (0.7 kg/m2, from Regulatory Guide 1.109).

Y s Agricultural productivity by unit area of stored feed (2.0 kg/m2, from Regulatory Guide 1.109).

-1 i Nuclide decay constant for nuclide i (sec ).

w Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x10-7 sec-1, from NUREG-0133).

(DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

F mi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 of Regulatory Guide 1.109 for cow milk.

f p Fraction of year that the cow is on pasture (1.0, from RG 1.109).

f s Fraction of the cow feed that is pasture grass while the cow is on pasture (1.0, from Regulatory Guide 1.109).

t f Transport time for pasture to cow, to milk, to receptor (1.73E+05 seconds, from Regulatory Guide 1.109).

t h Transport time from pasture, to harvest, to cow, to milk, to receptor (7.78E+06 seconds, from Regulatory Guide 1.109).

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Grass/Cow/Milk - Tritium Roapi = K K Fmi Q f U ap ( DFLio ) a [0.75(0.5 / H )]

Formula: from NUREG-0133, page 34.

Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/milk pathway (mrem/yr per µCi/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

K'" Units conversion factor gm/kg (103).

Q F Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).

U ap Consumption rate of cow milk for age group a (liters/yr, from Regulatory Guide 1.109).

Adult - 310 Teen - 400 Child - 330 Infant - 330 (DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

F mi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 of Regulatory Guide 1.109 for cow milk.

0.75 Fraction of total feed that is water (from NUREG-0133).

0.5 Ratio of specific activity of feed grass water to atmospheric water (from NUREG-0133).

H Absolute humidity of the atmosphere (8 gm/m3, from Regulatory Guide 1.109).

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Grass/Cow/Milk - Carbon-14 Roapi = K' K'" Fmi QF Uap ( DFLoi ) a [0.11 / 0.16]( p )( f I )

Formula: from NUREG-0133, page 34 and Regulatory Guide 1.109, page 26.

Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (mrem/yr per µCi/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

K'" Units conversion factor gm/kg (103).

F mi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 of Regulatory Guide 1.109 for cow milk.

Q F Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).

U ap Consumption rate of cow milk for age group a (liters/yr) (from Regulatory Guide 1.109).

Adult - 310 Teen - 400 Child - 330 Infant - 330 (DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

0.11 Fraction of total plant mass that is natural carbon.

0.16 Concentration of natural carbon in the atmosphere (gm/m3).

p Ratio of the total annual C-14 release time to the total annual time during which photosynthesis occurs. This value is assumed to be 0.31, based on 70% of C-14 releases being from WGDTs, and 30% of C-14 releases being continuous from the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14", 2004).

f I The fraction of C-14 assumed to be in inorganic form (e.g., CO 2 ).

Assumed to be 20%. Reference EPRI TR-105715, "Characterization of Carbon-14 Generated by the Nuclear Power Industry", Table 5-1.

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Grass/Goat/Milk QF (U ap ) f p f s (1 f p f s )e i t h i t f Roapi = K Fmi ( r )( DFLoi ) a + e i + w pY Ys Formula: from NUREG-0133, pages 32 & 33. Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/milk pathway (m2*mrem/yr per µCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

Q F Goat consumption rate (6 kg/day, from Regulatory Guide 1.109).

U ap Consumption rate of goat milk for age group a (liters/yr, from Regulatory Guide 1.109).

Adult - 310 Teen - 400 Child - 330 Infant - 330 r Fraction of deposited activity retained on goats feed grass, from Regulatory Guide 1.109.

1.0 for radioiodine.

0.2 for particulates.

Y p Agricultural productivity by unit area of pasture feed grass (0.7 kg/m2, from Regulatory Guide 1.109).

Y s Agricultural productivity by unit area of stored feed (2.0 kg/m2, from Regulatory Guide 1.109).

-1 i Nuclide decay constant for nuclide i (sec ).

w Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x10-7 sec-1, from NUREG-0133).

(DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

F mi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-2 of Regulatory Guide 1.109 for goat milk.

f p Fraction of year that the goat is on pasture (1.0, from RG 1.109).

f s Fraction of the goat feed that is pasture grass while the goat is on pasture (1.0, from Regulatory Guide 1.109).

t f Transport time for pasture to goat, to milk, to receptor (1.73E+05 seconds, from Regulatory Guide 1.109).

t h Transport time from pasture, to harvest, to goat, to milk, to receptor (7.78E+06 seconds, from Regulatory Guide 1.109).

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Grass/Goat/Milk - Tritium Roapi = K K Fmi Q f U ap ( DFLoi ) a [0.75(0.5 / H )]

Formula: from NUREG-0133, page 34.

Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/milk pathway (mrem/yr per µCi/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

K'" Units conversion factor gm/kg (103).

Q F Goat consumption rate (6 kg/day, from Regulatory Guide 1.109).

U ap Consumption rate of goat milk for age group a (liters/yr, from Regulatory Guide 1.109).

Adult - 310 Teen - 400 Child - 330 Infant - 330 (DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

F mi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-2 of Regulatory Guide 1.109 for goat milk.

0.75 Fraction of total feed that is water (from NUREG-0133).

0.5 Ratio of specific activity of feed grass water to atmospheric water (from NUREG-0133).

H Absolute humidity of the atmosphere (8 gm/m3, from Regulatory Guide 1.109).

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Grass/Goat/Milk - Carbon-14 Roapi = K' K'" Fmi QF Uap ( DFLoi ) a [0.11 / 0.16]( p )( f I )

Formula: from NUREG-0133, page 34 and Regulatory Guide 1.109, page 26.

Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (mrem/yr per µCi/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

K'" Units conversion factor gm/kg (103).

F mi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-2 of Regulatory Guide 1.109 for goat milk (0.10).

Q F Goat consumption rate (6 kg/day, from Regulatory Guide 1.109).

U ap Consumption rate of goat milk for age group a (liters/yr) (from Regulatory Guide 1.109).

Adult - 310 Teen - 400 Child - 330 Infant - 330 (DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

0.11 Fraction of total plant mass that is natural carbon.

0.16 Concentration of natural carbon in the atmosphere (gm/m3).

p Ratio of the total annual C-14 release time to the total annual time during which photosynthesis occurs. This value is assumed to be 0.31, based on 70% of C-14 releases being from WGDTs, and 30% of C-14 releases being continuous from the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14", 2004).

f I The fraction of C-14 assumed to be in inorganic form (e.g., CO 2 ).

Assumed to be 20%. Reference EPRI TR-105715, "Characterization of Carbon-14 Generated by the Nuclear Power Industry", Table 5-1.

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Grass/Cow/Meat QF (U ap ) f p f s (1 f p f s )e i t h i t f Roapi = K F fi (r )( DFLi ) a + e i + w pY Ys Formula: from NUREG-0133, pages 34 & 35. Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (m2*mrem/yr per µCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

Q F Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).

U ap Consumption rate of cow meat for age group a (kg/yr, from Regulatory Guide 1.109).

Adult - 110 Teen - 65 Child - 41 Infant - 0 r Fraction of deposited activity retained on cows feed grass (from Regulatory Guide 1.109).

1.0 for radioiodine.

0.2 for particulates.

Y p Agricultural productivity by unit area of pasture feed grass (0.7 kg/m2, from Regulatory Guide 1.109).

Y s Agricultural productivity by unit area of stored feed (2.0 kg/m2, from Regulatory Guide 1.109).

-1 i Nuclide decay constant for nuclide i (sec ).

w Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x10-7 sec-1, from NUREG-0133).

(DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

F fi Stable element transfer coefficient for nuclide i, in days/kg, from Table E-1 of Regulatory Guide 1.109 for cow meat.

f p Fraction of year that the cow is on pasture (1.0, from RG 1.109).

f s Fraction of the cow feed that is pasture grass while the cow is on pasture (1.0, from Regulatory Guide 1.109).

t f Transport time from pasture to receptor (1.73E+06 seconds, from Regulatory Guide 1.109).

t h Transport time from crop field to receptor (7.78E+06 seconds, from Regulatory Guide 1.109).

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Grass/Cow/Meat - Tritium Roapi = K K F fi QFU ap ( DFLoi ) a [0.75(0.5 / H )]

Formula: from NUREG-0133, page 35.

Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (mrem/yr per µCi/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

K'" Units conversion factor gm/kg (103).

Q F Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).

U ap Consumption rate of cow meat for age group a (kg/yr, from Regulatory Guide 1.109).

Adult - 110 Teen - 65 Child - 41 Infant - 0 (DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

F fi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 of Regulatory Guide 1.109 for cow meat.

0.75 Fraction of total feed that is water (from NUREG-0133).

0.5 Ratio of specific activity of feed grass water to atmospheric water (from NUREG-0133).

H Absolute humidity of the atmosphere (8 gm/m3, from Regulatory Guide 1.109).

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Grass/Cow/Meat - Carbon-14 Roapi = K' K'" Ffi QF Uap ( DFLoi ) a [0.11 / 0.16]( p )( f I )

Formula: from NUREG-0133, page 35 and Regulatory Guide 1.109, page 26.

Where:

R oapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (mrem/yr per µCi/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (106).

K'" Units conversion factor gm/kg (103).

F fi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 of Regulatory Guide 1.109 for cow meat.

Q F Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).

U ap Consumption rate of cow meat for age group a (kg/yr) (from Regulatory Guide 1.109).

Adult - 110 Teen - 65 Child - 41 Infant - 0 (DFL oi ) a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

0.11 Fraction of total plant mass that is natural carbon.

0.16 Concentration of natural carbon in the atmosphere (gm/m3).

p Ratio of the total annual C-14 release time to the total annual time during which photosynthesis occurs. This value is assumed to be 0.31, based on 70% of C-14 releases being from WGDTs, and 30% of C-14 releases being continuous from the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14", 2004).

f I The fraction of C-14 assumed to be in inorganic form (e.g., CO 2 ).

Assumed to be 20%. Reference EPRI TR-105715, "Characterization of Carbon-14 Generated by the Nuclear Power Industry", Table 5-1.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 4.0.3 DIRECT RADIATION Direct radiation is that radiation from confined sources, and does not include any external component from radioactive effluents. The point kernel method has been used to calculate offsite dose rates from radioactive materials stored in the refueling water storage tanks, reactor makeup water storage tanks, and temporary onsite radwaste storage tanks. Dose calculations using this method performed for McGuire Nuclear Station indicate direct radiation doses are much less than 0.01 mrem/yr and, therefore, make a negligible contribution to individual dose. Likewise, 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 10CFR72.212 evaluation report. The results of the calculation demonstrate that the annual dose to any "real individual" beyond the controlled area boundary is below the 10CFR72.104(a) and 40CFR190.10(a) limit of 25 mrem from direct and skyshine radiation, and all other fuel cycle sources (e.g., effluent). Direct radiation doses will not be calculated routinely.

4.0.4 EFFLUENT APPORTIONMENT For the McGuire Nuclear Station the effluent releases are apportioned equally to each unit for each site as recommended by Section 3.1 of NUREG-0133, because the shared radwaste treatment systems at each site make it impractical to accurately ascribe releases to a specific reactor unit. For Annual Radiological Effluent Release Report purposes effluent releases are summed for each unit, and the maximum individual dose to the public is reported as a site total.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 5.0 FUEL CYCLE CALCULATIONS 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. In accordance with the requirements of the Selected Licensee Commitments, the annual dose commitment shall also be calculated any time twice the specified quarterly dose limit of the Selected Licensee Commitments is exceeded; these annual dose commitments may not just be calculated for the calendar year.

The "Uranium fuel cycle" is defined in 40CFR Part 190.02(b) as:

"Uranium fuel cycle means the operations of milling of uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations at waste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle."

Based on this definition of the fuel cycle and the information in 10CFR51, Table S-3, and Wash-1248, the radiological impact of the following operations has been assessed for McGuire Nuclear Station:

5.0.1 MILLING No milling operations occur within fifty miles of the McGuire Nuclear Station.

5.0.2 CONVERSION No uranium hexafluoride production occurs within fifty miles of the McGuire Nuclear Station.

5.0.3 ENRICHMENT No uranium enrichment operations occur within fifty miles of the McGuire Nuclear Station.

5.0.4 FUEL FABRICATION No fuel fabrication operations occur within fifty miles of the McGuire Nuclear Station.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 5.0.5 NUCLEAR POWER PRODUCTION The production of electricity for public use using light-water-cooled nuclear power stations results in increments of dose to individuals within fifty miles of any station due to liquid and gaseous effluent releases and direct radiation or skyshine. The increments of dose resulting from liquid and gaseous effluent releases will be calculated using the ODCM methodology implemented in the RETDAS computer program. The dose from direct radiation, skyshine, and radiation from the station storage facilities has been estimated using conservative assumptions (see Section 4.0.3).

In certain situations more than one nuclear power station site may contribute to the doses to be considered in making fuel cycle dose assessments in accordance with 40CFR190.

However, since the McGuire and Catawba nuclear stations are located approximately 30 miles apart the relative dose contribution from each site to the other is insignificant, and can be ignored in assessing compliance with 40CFR190.

5.0.6 FUEL REPROCESSING No fuel reprocessing operations occur within fifty miles of the McGuire Nuclear Station.

5.0.7 40CFR190 TOTAL DOSE DETERMINATION To summarize, only dose increments from nuclear power production operations (Section 5.0.5) need be considered in calculations to demonstrate compliance with the requirements of 40CFR190. The fuel cycle dose assessments for McGuire Nuclear Station only include liquid and gaseous dose contributions from McGuire and dose from McGuire's ISFSI since no other uranium fuel cycle facility contributes significantly to McGuire's maximum exposed individual. For this dose assessment, the total body and maximum organ dose contributions to the maximum exposed individual from McGuire's liquid and gaseous effluents are estimated using the following calculations:

Dwb (T ) = Dwb (l ) + Dwb ( g )

Dmo(T ) = Dmo(l ) + Dmo( g )

where:

D wb (T) = Total estimated fuel cycle whole body dose commitment resulting from the combined liquid and gaseous effluents of McGuire during the calendar year of interest, in mrem.

D mo (T) = Total estimated fuel cycle maximum organ dose commitment resulting from the combined liquid and gaseous effluents of McGuire during the calendar year of interest, in mrem.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 6.0 ENVIRONMENTAL LOCATIONS 6.0.1 SITE DESCRIPTION AND SAMPLE LOCATIONS McGuire Nuclear Station is located geographically near the center of a highly industrialized region of the Carolinas. The land is predominantly rural non-farm with a small amount of land being used to support beef cattle and farming. Recreation in the area is confined mostly to the lake and shores of Lake Norman and Mountain Island reservoir. The McGuire site is in northwestern Mecklenburg County, North Carolina, 17 miles north-northwest of Charlotte, North Carolina. The site is bounded to the west by the Catawba River channel and to the north by 32,510 acre Lake Norman. Lake Norman is impounded by Duke Energys Cowans Ford Dam Hydroelectric Station, which is located immediately west of the site and on the Catawba River channel. The tailwater of Cowans Ford Dam is the upper limit of Mountain Island Reservoir. Mountain Island Dam is located 15 miles downstream from the site. Lookout Shoals Hydroelectric Station is at the upper reaches of Lake Norman. Marshall Steam Station is located on the western shore of Lake Norman, approximately 16 miles upstream from the site. The site exclusion radius is 2500 feet.

Table 6.0-1 and Table 6.0-2 define the sampling and TLD locations for the McGuire Radiological Monitoring Program. Figure 6.0-1 and Figure 6.0-2 illustrate these locations as compared to McGuire Nuclear Station.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 6.0.2 LAND USE CENSUS DATA The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified, and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. The land use census identifies nearest pathways to the exclusion area boundary (EAB, ~ 0.5 mile) for each of the 16 meteorological sectors. Global Positioning System field measurements are taken as close as possible to the item of interest and are accurate to within 2-5 meters. Locations beyond the nearest pathway for each sector are assumed to contain that pathway for dose calculation purposes. For the 4.5-5.0 mile sector all pathways, i.e., residence, garden, milk animal (goat), and meat animal (cow), are assumed to exist for dose calculation purposes. Results are maintained on file and data reviewed in accordance with procedure AD-CP-ALL-0014, Land Use Census Evaluation.

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TABLE 6.0-1 MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 6.0-1 Codes W Weekly SM Semimonthly BW BiWeekly Q Quarterly M Monthly SA Semiannually C Control Site Location Description Air Rad.

& Part.

Surface Water Drinking Water Shoreline Sediment Food Products Fish Milk Broad Leaf Veg.

101 North Mecklenburg Water Treatment Facility (3.31 mi E) M 102 C Amity Church Road (9.89 mi WNW) W M(b) 103 Cottonwood Substation (4.20 mi NE) W 104 5 mile radius Gardens (1.52 mi NNW) M (a )

119 Mt. Holly Municipal Water Supply ( 7.40 mi SSW ) M 120 HP Boathouse - Site Boundary ( 0.46 mi NNE ) W M(b) 121 Guardhouse - Site Boundary ( 0.47 mi NE ) W 125 Settling Ponds - Site Boundary ( 0.38 mi SW ) W M(b) 128 Discharge Canal Bridge ( 0.45 mi NE ) M 129 Discharge Canal Entrance to Lake Norman ( 0.51 mi ENE) SA SA 130 Hwy 73 Bridge Downstream ( 0.52 mi SW ) SA 131 Cowans Ford Dam ( 0.64 mi WNW ) M 132 Charlotte Municipal Water Supply ( 11.1 mi SSE ) M 133 Cornelius ( 6.23 mi ENE ) W 135 C Plant Marshall Intake Canal ( 11.9 mi N ) M 136 C Mooresville Municipal Water Supply ( 12.7 mi NNE ) M 137 C Pinnacle Access Area ( 12.0 mi N ) SA SA 141 C Lynch Dairy-Cows ( 14.8 mi WNW ) SM 193 Site Boundary ( 0.19 mi N ) M(b) 194 East Lincoln County Water Supply ( 6.73 mi NNW ) M 195 Fishing Access Road ( 0.19 mi N ) W (a) During Harvest Season (b) When Available

GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.

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TABLE 6.0-2 MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)

Site Location Distance Sector Site Location Distance Sector HAMBRIGHT &

143 SITE BOUNDARY 0.27 miles NW 164 BEATTIES FORD ROAD 4.64 miles SSE 144 SITE BOUNDARY 0.46 miles NNE 165 ARTHER AUTEN ROAD 4.57 miles S NECK ROAD 145 SITE BOUNDARY 0.47 miles NE 166 REFUGE BOUNDARY 4.44 miles SSW LUCIA RIVERBEND HWY/

146 SITE BOUNDARY 0.42 miles ENE 167 OLD FIREHOUSE 4.87 miles SW 147 SITE BOUNDARY 0.44 miles E 168 OLD PLANK ROAD BRIDGE 4.60 miles WSW 148 SITE BOUNDARY 0.46 miles ESE 169 GLOVER LANE 4.03 miles W 149 SITE BOUNDARY 0.50 miles SE 170 LITTLE EGYPT ROAD 4.32 miles WNW 151 SITE BOUNDARY 0.37 miles S 171 TRIANGLE ACE HARDWARE 3.95 miles NW LAKESHORE SOUTH RD &

152 SITE BOUNDARY 0.44 miles SSW 172 ISLAND VIEW COURT 4.69 miles NNW KEISTLER STORE /

153 SITE BOUNDARY 0.47 miles SW 173 SI GLENWOOD ROAD 8.39 miles NNW EAST LINCOLN JR. HIGH 154 SITE BOUNDARY 0.45 miles W 174 SI SCHOOL 8.85 miles WNW 156 SITE BOUNDARY 0.44 miles WNW 175 C BOGER CITY 15.5 miles WNW BELMARROW ROAD /

189 SITE BOUNDARY 0.43 miles SSE 177 SI COULWOOD COMMUNITY 8.77 miles S FLORIDA STEEL 190 SITE BOUNDARY 0.37 miles WSW 178 SI CORPORATION 9.36 miles SE THE MOORESVILLE WATER 157 POINTE/MOORESVILLE 4.69 miles N 180 SI TREATMENT FACILITY 12.7 miles NNE OLD DAVIDSON WATER 158 BETHEL CHURCH ROAD 4.33 miles NNE 181 SI TREATMENT FACILITY 7.02 miles NE 159 HENDERSON ROAD 4.77 miles NE 182 SI CORNELIUS / AIR SITE # 133 6.23 miles ENE ANCHORAGE MARINE MCGUIRE FISHING ACCESS 160 SHOWROOM 4.89 miles ENE 186 SI ROAD ON PENINSULA 0.24 miles NNW SAM FURR ROAD ENERGY EXPLORIUM /

161 & HWY 21 4.70 miles E 187 SI AIR SITE # 195 0.19 miles N PENINSULA DEVELOPMENT /

162 RANSON ROAD 4.53 miles ESE 191 SI JOHN CONNOR ROAD 2.84 miles NNE 163 MCCOY ROAD 4.94 miles SE C = Control SI = Special Interest

GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.

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TABLE 6.0-3 Land Use Census Results Deleted in ODCM Revision 58.

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Figure 6.0-1 Sampling Locations Map (Site Boundary)

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Figure 6.0-2 Sampling Locations Map (Ten Mile Radius)

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Figure 6.0-3 Land Use Census Map Deleted in ODCM Revision 58.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 6.0.3 MCGUIRE METEOROLOGY: RELATIVE AIR CONCENTRATIONS AND DEPOSITION Calculations of annually averaged air concentrations and deposition values from routine releases provide the air dispersion and deposition factors needed for dose assessment.

The methodology is based upon Regulatory Guide 1.111, as implemented by the NRC's computer model "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," NUREG/CR-2919, PNL-4380, September 1982.

Five years of hourly meteorological data from the onsite instruments are processed into a representative joint frequency distribution of winds and atmospheric stability for input into the XOQDOQ model (Version 2.0). Thus, the air dispersion and deposition factors

(/Q and D/Q) output by the model are based on a five-year climatology for the site.

6.0.3.1 XOQDOQ METHODOLOGY AND ASSUMPTIONS A continuous, routine release (non-purge) is simulated from each unit vent. The release type is treated as "ground-level" in the model, for which surrounding terrain elevations are not input. The locale does consist of gently rolling terrain, so the default open terrain recirculation factor is applied in XOQDOQ [KOPT(8)=1]. This correction factor is recommended in RG 1.111 to adjust the straight-line airflow of the model for spatial and temporal variations that are produced by large scale weather patterns, or other non-linear flow conditions at local and regional scales.

In order for XOQDOQ to treat the plume as a ground-level release, the exit velocity and the inside diameter of the unit vent must be input as zero. The heat emission rate of each vent is also assumed to be zero, as recommended by the model. The height of the vent (40.2 m) above plant grade elevation (760 ft msl) is then used to determine the plume centerline height. Using the building height (43.1 m) and minimum cross-sectional area of the containment building (1616 m2), XOQDOQ applies a building wake correction to the relative air concentrations from the ground level release.

Calculations of relative air concentrations and deposition are made for grid receptor distances per sector. The "no decay" assumption is used in the XOQDOQ model.

6.0.3.2 METEOROLOGICAL DATA Five years (1988-1992) of hourly, onsite meteorological data are used to produce the joint frequency distributions of wind speed and direction per stability class. The 10 m level winds are used. It is these joint frequency distributions which are input to the XOQDOQ model. Hours of calm winds are distributed by direction with the same frequency as the lowest "noncalm" wind speed class [KOPT(1)=1]. Thus, wind speed classes are established so that the lowest wind speed class is the starting threshold of the anemometer (i.e. the "calm" wind speed class). The largest wind speed class has the upper bound of Section 6 - Page 9 Page 9-76

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(5 m/s + max hourly wind speed). Stability classes (A-G) are based on the vertical temperature gradient, measured by the hourly averaged delta-T variable.

6.0.3.3 ANNUAL XOQDOQ COMPARISON TO THE ODCM Each year, the prevailing winds and stability class frequencies for MNS are compared to the 5-year period (1988-1992) upon which the /Q and D/Q calculations have been made.

The 5-year climatology is summarized in Table 6.0-4 and Table 6.0-5 below. Since the comparison is being made to a 5-year climatology, significant differences should not occur in the meteorological variables of concern (i.e. winds and delta-T). The meteorological comparison serves to verify this assumption.

Table 6.0-4 MNS Atmospheric Stability Frequency (1988-1992)

A B C D E F G Frequency

(%) 13.8 4.7 6.1 33.8 19.3 8.0 14.3 Table 6.0-5 MNS Frequency of Wind Direction (From) and Speed (1988-1992)

Wind Wind Speed Class Wind Speed Sector Direction (m/s) Frequency (%)

Frequency

(%)

N 5.6 CALM 1.3 NNE 8.8 0.45 - 0.74 m/s 4.3 NE 11.0 0.75 - 0.99 m/s 7.3 ENE 5.8 1.00 - 1.24 m/s 5.8 E 1.6 1.25 - 1.49 m/s 6.7 ESE 1.5 1.50 - 1.99 m/s 12.9 SE 2.3 2.00 - 2.99 m/s 23.5 SSE 3.2 3.00 - 3.99 m/s 17.0 S 13.2 4.00 - 4.99 m/s 10.8 SSW 17.9 5.00 - 5.99 m/s 5.6 SW 9.0 6.00 - 7.99 m/s 3.8 WSW 5.0 8.00 - 9.99 m/s 0.6 W 3.9 > 9.99 m/s 0.4 WNW 4.2 NW 3.5 NNW 3.5 Section 6 - Page 10 Page 9-77

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The joint frequency distributions of wind speed and direction versus atmospheric stability class are also determined from the annual data to provide input to the XOQDOQ model.

Modeled /Q and D/Q values for the 0.5 mile Exclusion Area Boundary at MNS are compared to the maximum of the (1988-1992) /Q and D/Q values from all sectors. If the newly calculated annual dispersion and deposition values do not result in a significant increase in the calculated offsite dose relative to the 10CFR50, Appendix I dose objectives then the 5-year /Q and D/Q values used in the Annual Radiological Effluent Release Report (ARERR) are not revised. An increase in calculated offsite dose that is greater than five percent of the 10CFR50, Appendix I dose objectives would be considered significant enough to warrant a change in the /Q and D/Q values used in the ARERR. If an increasing trend in the annual /Q and D/Q values compared to the 5-year values is noted then a revised set of 5-year /Q and D/Q values will be generated. These limiting values are listed in Table 6.0-6. The entire /Q and D/Q list based on directional sector and distance is given in Table 6.0-8 and 6.0-9.

Table 6.0-6 MNS Limiting /Q and D/Q Values (1988-1992)

(/Q,s/m3) Distance Sector (D/Q,1/m2)

Maximum /Q 7.611E-5 0.5 mile EAB NNE Maximum D/Q 1.403E-7 0.5 mile EAB NNE Note:

The McGuire 40 m tall meteorological tower was replaced with a new 60 m meteorological tower in August 1998 and relocated on site. The 60 m tower became operational at hour 0000 on September 1, 1998. Determination of atmospheric stability prior to this time uses the 30 m separation criteria shown in Table 6.0-7, while data after this time uses the 50 m separation criteria.

Table 6.0-7 MNS Delta-T Ranges per Vertical Separation Distances Stability 30 m separation Delta-T 50 m separation Delta-T Class (between 40m-10m levels) (between 60m-10m levels)

Starting at hour 0000 on SEPT 1, 1998.

A dT < -0.57 dT < -0.95 B -0.57 < dT < -0.51 -0.95 < dT < -0.85 C -0.51 < dT < -0.45 -0.85 < dT < -0.75 D -0.45 < dT < -0.15 -0.75 < dT < -0.25 E -0.15 < dT < 0.45 -0.25 < dT < 0.75 F 0.45 < dT < 1.2 0.75 < dT < 2.00 G 1.2 < dT 2.00 < dT Section 6 - Page 11 Page 9-78

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Table 6.0-8 McGuire /Q Average Values (1988-1992)

(sec/m3)

Sector 0.5-1.0* 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 4.795E-05 1.220E-05 5.144E-06 2.879E-06 1.871E-06 1.333E-06 1.009E-06 7.985E-07 6.529E-07 NNE 7.611E-05 1.910E-05 8.103E-06 4.553E-06 2.968E-06 2.118E-06 1.607E-06 1.274E-06 1.043E-06 NE 5.330E-05 1.329E-05 5.662E-06 3.191E-06 2.084E-06 1.490E-06 1.132E-06 8.978E-07 7.357E-07 ENE 2.950E-05 7.487E-06 3.166E-06 1.776E-06 1.155E-06 8.237E-07 6.243E-07 4.943E-07 4.044E-07 E 1.742E-05 4.506E-06 1.884E-06 1.049E-06 6.787E-07 4.818E-07 3.638E-07 2.872E-07 2.344E-07 ESE 1.206E-05 3.143E-06 1.303E-06 7.209E-07 4.646E-07 3.288E-07 2.476E-07 1.951E-07 1.589E-07 SE 7.697E-06 2.011E-06 8.234E-07 4.521E-07 2.897E-07 2.040E-07 1.531E-07 1.202E-07 9.763E-08 SSE 6.179E-06 1.613E-06 6.504E-07 3.533E-07 2.246E-07 1.572E-07 1.173E-07 9.173E-08 7.421E-08 S 6.262E-06 1.581E-06 6.263E-07 3.363E-07 2.120E-07 1.475E-07 1.095E-07 8.525E-08 6.872E-08 SSW 7.346E-06 1.836E-06 7.234E-07 3.872E-07 2.435E-07 1.690E-07 1.253E-07 9.745E-08 7.847E-08 SW 8.606E-06 2.206E-06 8.483E-07 4.456E-07 2.759E-07 1.890E-07 1.386E-07 1.066E-07 8.508E-08 WSW 6.424E-06 1.671E-06 6.526E-07 3.466E-07 2.165E-07 1.493E-07 1.101E-07 8.519E-08 6.829E-08 W 3.523E-06 9.147E-07 3.697E-07 2.012E-07 1.281E-07 8.973E-08 6.705E-08 5.245E-08 4.247E-08 WNW 4.063E-06 1.071E-06 4.351E-07 2.376E-07 1.516E-07 1.064E-07 7.963E-08 6.238E-08 5.056E-08 NW 5.543E-06 1.448E-06 5.898E-07 3.226E-07 2.061E-07 1.448E-07 1.085E-07 8.504E-08 6.898E-08 NNW 1.053E-05 2.735E-06 1.131E-06 6.250E-07 4.024E-07 2.845E-07 2.141E-07 1.686E-07 1.372E-07

Units are in miles from the station. Each /Q value is calculated at the closest location for the sector, e.g., 4.795E-05 sec/m3 is the /Q value at 0.5 miles (N) from the station.

The boundary for establishing gaseous effluent release limits is the Exclusion Area Boundary (EAB). As shown in McGuire UFSAR Figure 2-5, the EAB is defined as a 2500 foot (~0.5 mile) radius from the station center.

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Table 6.0-9 McGuire D/Q Average Values (1988-1992)

(m-2)

Sector 0.5-1.0* 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 1.031E-07 2.516E-08 9.037E-09 4.482E-09 2.639E-09 1.728E-09 1.216E-09 9.011E-10 6.944E-10 NNE 1.403E-07 3.424E-08 1.230E-08 6.100E-09 3.592E-09 2.352E-09 1.655E-09 1.226E-09 9.451E-10 NE 7.027E-08 1.715E-08 6.161E-09 3.055E-09 1.799E-09 1.178E-09 8.289E-10 6.143E-10 4.734E-10 ENE 3.893E-08 9.504E-09 3.414E-09 1.693E-09 9.969E-10 6.527E-10 4.593E-10 3.404E-10 2.623E-10 E 3.024E-08 7.381E-09 2.651E-09 1.315E-09 7.742E-10 5.069E-10 3.567E-10 2.643E-10 2.037E-10 ESE 3.299E-08 8.052E-09 2.892E-09 1.434E-09 8.445E-10 5.530E-10 3.891E-10 2.884E-10 2.222E-10 SE 2.733E-08 6.673E-09 2.397E-09 1.189E-09 6.999E-10 4.583E-10 3.225E-10 2.390E-10 1.842E-10 SSE 2.765E-08 6.749E-09 2.424E-09 1.202E-09 7.079E-10 4.635E-10 3.262E-10 2.417E-10 1.863E-10 S 4.360E-08 1.064E-08 3.823E-09 1.896E-09 1.116E-09 7.309E-10 5.143E-10 3.811E-10 2.937E-10 SSW 6.929E-08 1.691E-08 6.075E-09 3.013E-09 1.774E-09 1.162E-09 8.174E-10 6.058E-10 4.668E-10 SW 8.605E-08 2.100E-08 7.545E-09 3.742E-09 2.203E-09 1.443E-09 1.015E-09 7.523E-10 5.797E-10 WSW 4.562E-08 1.114E-08 4.000E-09 1.984E-09 1.168E-09 7.648E-10 5.382E-10 3.988E-10 3.073E-10 W 1.268E-08 3.094E-09 1.112E-09 5.512E-10 3.246E-10 2.125E-10 1.495E-10 1.108E-10 8.541E-11 WNW 1.213E-08 2.962E-09 1.064E-09 5.276E-10 3.107E-10 2.034E-10 1.431E-10 1.061E-10 8.175E-11 NW 1.785E-08 4.358E-09 1.565E-09 7.763E-10 4.571E-10 2.993E-10 2.106E-10 1.561E-10 1.203E-10 NNW 2.520E-08 6.152E-09 2.210E-09 1.096E-09 6.453E-10 4.225E-10 2.973E-10 2.203E-10 1.698E-10

Units are in miles from the station. Each D/Q value is calculated at the closest location for the sector, e.g., 1.031E-07 m-2 is the D/Q value at 0.5 miles (N) from the station.

The boundary for establishing gaseous effluent release limits is the Exclusion Area Boundary (EAB). As shown in McGuire UFSAR Figure 2-5, the EAB is defined as a 2500 foot (~0.5 mile) radius from the station center.

Section 6 - Page 13 Page 9-80

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM) 7.0 LICENSEE INITIATED CHANGES All ODCM changes are reviewed by knowledgeable individual(s), and approved by either the Station Manager or Radiation Protection Manager. The changes below do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

ODCM Revision 58 - Implementation Date: March 9, 2017 ODCM Revision 58 was approved by the Radiation Protection Manager on March 9, 2017.

Some changes reflected in ODCM Revision 58 were implemented prior to March 9, 2017 under a different change and approval process (e.g., land use census), and in those cases the implementation date is noted below. Changes driven by Document Revision Requests (DRR) are noted with DRR number.

Table of Contents - Page i and ii Marked 6.0-3, Land Use Census Map, as deleted in List of Figures. Marked 6.0-3, Land Use Census Results, as deleted in List of Tables. Adjusted remaining sub-section, Figure, and Table page numbers for Section 6 based on moving Section 6.0.2.

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions. This does not adversely impact the accuracy or reliability of dose calculations, as records of the Land Use Census are maintained in EnRad files and documented with procedure AD-CP-ALL-0014, Land Use Census Evaluation. Changes to Effluent Management Software are implemented based on results of annual Land Use Census, once approved.

Section 7 - Page 1 Page 9-81

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Executive Summary - Page 2 Revised statements in second paragraph from:

"The ODCM has been prepared as generically as possible in order to minimize the need for revisions. However, some changes to the ODCM such as land use census data are expected on an annual basis. Any changes to the methodology and parameters to be used in this ODCM shall be reviewed by knowledgeable individual(s), and approved by the Station Manager prior to implementation. Changes to the ODCM shall be submitted to the Nuclear Regulatory Commission in accordance with the SLCs and Technical Specifications."

to:

"The ODCM has been prepared as generically as possible in order to minimize the need for revisions. Any changes to the methodology and parameters to be used in this ODCM shall be reviewed by knowledgeable individual(s), and approved by the Station Manager or Radiation Protection Manager prior to implementation. Changes to the ODCM shall be submitted to the Nuclear Regulatory Commission in accordance with the SLCs and Technical Specifications."

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions. Also updated ODCM approval authority statement based on NRC approved license amendments 276 and 256 to Technical Specification 5.5.1, allowing for Radiation Protection Manager approval.

Section 4 - Page 8 Removed reference to Table 6.0-3 in "*" note. Statement changed from:

"Dose is calculated only for pathways (e.g., garden, milk animal, etc.) that actually exist at each location as determined by the land use census shown in Table 6.0-3."

to:

"Dose is calculated only for pathways (e.g., garden, milk animal, etc.) that actually exist at each location as determined by the land use census."

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions.

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Section 6.0.2 - Page 2 Revised from (previously on page 1):

"The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified, and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 6.0-3 and Figure 6.0-3."

to:

"The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified, and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. The land use census identifies nearest pathways to the exclusion area boundary (EAB, ~ 0.5 mile) for each of the 16 meteorological sectors. Global Positioning System field measurements are taken as close as possible to the item of interest and are accurate to within 2-5 meters. Locations beyond the nearest pathway for each sector are assumed to contain that pathway for dose calculation purposes. For the 4.5-5.0 mile sector all pathways, i.e., residence, garden, milk animal (goat), and meat animal (cow), are assumed to exist for dose calculation purposes. Results are maintained on file and data reviewed in accordance with procedure AD-CP-ALL-0014, Land Use Census Evaluation."

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions. This does not adversely impact the accuracy or reliability of dose calculations, as records of the Land Use Census are maintained in EnRad files and documented with procedure AD-CP-ALL-0014, Land Use Census Evaluation. Changes to Effluent Management Software are implemented based on results of annual Land Use Census, once approved.

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Section 6.0.2 - Page 4 (previously)

Deleted Table 6.0-3 and moved relevant information fro "*" and "**" Note paragraphs to Section 6.0.2.

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions. This does not adversely impact the accuracy or reliability of dose calculations, as records of the Land Use Census are maintained in EnRad files and documented with procedure AD-CP-ALL-0014, Land Use Census Evaluation. Changes to Effluent Management Software are implemented based on results of annual Land Use Census, once approved.

Section 6.0.2 - Page 7 (previously)

Deleted Figure 6.0-3.

Change made based on recommendation in DRR 02068937 to improve efficiency by eliminating annual ODCM revisions. This does not adversely impact the accuracy or reliability of dose calculations, as records of the Land Use Census are maintained in EnRad files and documented with procedure AD-CP-ALL-0014, Land Use Census Evaluation. Changes to Effluent Management Software are implemented based on results of annual Land Use Census, once approved.

Section 7 - Page 4 Page 9-84

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APPENDIX A Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases*

Ki Li Mi Ni Total Body Skin Gamma Air Beta Air Nuclide mrem/yr mrem/yr mrad/yr mrad/yr

µCi/m3 µCi/m3 µCi/m3 µCi/m3 AR-41 8.840E+03 2.690E+03 9.300E+03 3.280E+03 KR-83M 7.560E-02 0.000E+00 1.930E+01 2.880E+02 KR-85M 1.170E+03 1.460E+03 1.230E+03 1.970E+03 KR-85 1.610E+01 1.340E+03 1.720E+01 1.950E+03 KR-87 5.920E+03 9.730E+03 6.170E+03 1.030E+04 KR-88 1.470E+04 2.370E+03 1.520E+04 2.930E+03 KR-89 1.660E+04 1.010E+04 1.730E+04 1.060E+04 KR-90 1.560E+04 7.290E+03 1.630E+04 7.830E+03 XE-131M 9.150E+01 4.760E+02 1.560E+02 1.110E+03 XE-133M 2.510E+02 9.940E+02 3.270E+02 1.480E+03 XE-133 2.940E+02 3.060E+02 3.530E+02 1.050E+03 XE-135M 3.120E+03 7.110E+02 3.360E+03 7.390E+02 XE-135 1.810E+03 1.860E+03 1.920E+03 2.460E+03 XE-137 1.420E+03 1.220E+04 1.510E+03 1.270E+04 XE-138 8.830E+03 4.130E+03 9.210E+03 4.750E+03

Reference Regulatory Guide 1.109, Table B-1 Appendix A Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases - Page 1 of 1 Page 9-85

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APPENDIX B Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 0.000E+00 1.120E+03 C-14 3.590E+04 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 0.000E+00 6.730E+03 NA-24 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 0.000E+00 1.610E+04 P-32 2.600E+06 1.140E+05 0.000E+00 0.000E+00 0.000E+00 4.220E+04 0.000E+00 9.880E+04 CR-51 0.000E+00 0.000E+00 8.550E+01 2.430E+01 1.700E+04 1.080E+03 0.000E+00 1.540E+02 MN-54 0.000E+00 4.290E+04 0.000E+00 1.000E+04 1.580E+06 2.290E+04 0.000E+00 9.510E+03 MN-56 0.000E+00 1.660E+00 0.000E+00 1.670E+00 1.310E+04 1.230E+05 0.000E+00 3.120E-01 FE-55 4.740E+04 2.520E+04 0.000E+00 0.000E+00 1.110E+05 2.870E+03 0.000E+00 7.770E+03 FE-59 2.070E+04 3.340E+04 0.000E+00 0.000E+00 1.270E+06 7.070E+04 0.000E+00 1.670E+04 CO-58 0.000E+00 1.770E+03 0.000E+00 0.000E+00 1.110E+06 3.440E+04 0.000E+00 3.160E+03 CO-60 0.000E+00 1.310E+04 0.000E+00 0.000E+00 7.070E+06 9.620E+04 0.000E+00 2.260E+04 NI-63 8.210E+05 4.620E+04 0.000E+00 0.000E+00 2.750E+05 6.330E+03 0.000E+00 2.800E+04 NI-65 2.990E+00 2.960E-01 0.000E+00 0.000E+00 8.180E+03 8.400E+04 0.000E+00 1.640E-01 CU-64 0.000E+00 1.990E+00 0.000E+00 6.030E+00 9.580E+03 3.670E+04 0.000E+00 1.070E+00 ZN-65 4.260E+04 1.130E+05 0.000E+00 7.140E+04 9.950E+05 1.630E+04 0.000E+00 7.030E+04 ZN-69 6.700E-02 9.660E-02 0.000E+00 5.850E-02 1.420E+03 1.020E+04 0.000E+00 8.920E-03 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.740E+02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.480E+02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.530E+01 RB-86 0.000E+00 1.980E+05 0.000E+00 0.000E+00 0.000E+00 7.990E+03 0.000E+00 1.140E+05 RB-88 0.000E+00 5.620E+02 0.000E+00 0.000E+00 0.000E+00 1.720E+01 0.000E+00 3.660E+02 RB-89 0.000E+00 3.450E+02 0.000E+00 0.000E+00 0.000E+00 1.890E+00 0.000E+00 2.900E+02 SR-89 5.990E+05 0.000E+00 0.000E+00 0.000E+00 2.160E+06 1.670E+05 0.000E+00 1.720E+04 SR-90 1.010E+08 0.000E+00 0.000E+00 0.000E+00 1.480E+07 3.430E+05 0.000E+00 6.440E+06 SR-91 1.210E+02 0.000E+00 0.000E+00 0.000E+00 5.330E+04 1.740E+05 0.000E+00 4.590E+00 Appendix B Pi Child Inhalation - Page 1 of 3 Page 9-86

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX B Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.310E+01 0.000E+00 0.000E+00 0.000E+00 2.400E+04 2.420E+05 0.000E+00 5.250E-01 Y-90 4.110E+03 0.000E+00 0.000E+00 0.000E+00 2.620E+05 2.680E+05 0.000E+00 1.110E+02 Y-91 9.140E+05 0.000E+00 0.000E+00 0.000E+00 2.630E+06 1.840E+05 0.000E+00 2.440E+04 Y-91M 5.070E-01 0.000E+00 0.000E+00 0.000E+00 2.810E+03 1.720E+03 0.000E+00 1.840E-02 Y-92 2.030E+01 0.000E+00 0.000E+00 0.000E+00 2.390E+04 2.390E+05 0.000E+00 5.810E-01 Y-93 1.860E+02 0.000E+00 0.000E+00 0.000E+00 7.440E+04 3.880E+05 0.000E+00 5.110E+00 ZR-95 1.900E+05 4.180E+04 0.000E+00 5.960E+04 2.230E+06 6.110E+04 0.000E+00 3.700E+04 ZR-97 1.880E+02 2.720E+01 0.000E+00 3.880E+01 1.130E+05 3.510E+05 0.000E+00 1.600E+01 NB-95 2.350E+04 9.180E+03 0.000E+00 8.620E+03 6.140E+05 3.700E+04 0.000E+00 6.550E+03 MO-99 0.000E+00 1.720E+02 0.000E+00 3.920E+02 1.350E+05 1.270E+05 0.000E+00 4.260E+01 TC-99M 1.780E-03 3.480E-03 0.000E+00 5.070E-02 9.510E+02 4.810E+03 0.000E+00 5.770E-02 TC-101 8.100E-05 8.510E-05 0.000E+00 1.450E-03 5.850E+02 1.630E+01 0.000E+00 1.080E-03 RU-103 2.790E+03 0.000E+00 0.000E+00 7.030E+03 6.620E+05 4.480E+04 0.000E+00 1.070E+03 RU-105 1.530E+00 0.000E+00 0.000E+00 1.340E+00 1.590E+04 9.950E+04 0.000E+00 5.550E-01 RU-106 1.360E+05 0.000E+00 0.000E+00 1.840E+05 1.430E+07 4.290E+05 0.000E+00 1.690E+04 AG-110M 1.690E+04 1.140E+04 0.000E+00 2.120E+04 5.480E+06 1.000E+05 0.000E+00 9.140E+03 TE-125M 6.730E+03 2.330E+03 1.920E+03 0.000E+00 4.770E+05 3.380E+04 0.000E+00 9.140E+02 TE-127 2.770E+00 9.510E-01 1.960E+00 7.070E+00 1.000E+04 5.620E+04 0.000E+00 6.100E-01 TE-127M 2.490E+04 8.550E+03 6.070E+03 6.360E+04 1.480E+06 7.140E+04 0.000E+00 3.020E+03 TE-129 9.770E-02 3.500E-02 7.140E-02 2.570E-01 2.930E+03 2.550E+04 0.000E+00 2.380E-02 TE-129M 1.920E+04 6.840E+03 6.330E+03 5.030E+04 1.760E+06 1.820E+05 0.000E+00 3.040E+03 TE-131 2.170E-02 8.440E-03 1.700E-02 5.880E-02 2.050E+03 1.330E+03 0.000E+00 6.590E-03 TE-131M 1.340E+02 5.920E+01 9.770E+01 4.000E+02 2.060E+05 3.080E+05 0.000E+00 5.070E+01 TE-132 4.810E+02 2.720E+02 3.170E+02 1.770E+03 3.770E+05 1.380E+05 0.000E+00 2.630E+02 I-130 8.180E+03 1.640E+04 1.850E+06 2.450E+04 0.000E+00 5.110E+03 0.000E+00 8.440E+03 Appendix B Pi Child Inhalation - Page 2 of 3 Page 9-87

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX B Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 4.810E+04 4.810E+04 1.620E+07 7.880E+04 0.000E+00 2.840E+03 0.000E+00 2.730E+04 I-132 2.120E+03 4.070E+03 1.940E+05 6.250E+03 0.000E+00 3.200E+03 0.000E+00 1.880E+03 I-133 1.660E+04 2.030E+04 3.850E+06 3.380E+04 0.000E+00 5.480E+03 0.000E+00 7.700E+03 I-134 1.170E+03 2.160E+03 5.070E+04 3.300E+03 0.000E+00 9.550E+02 0.000E+00 9.950E+02 I-135 4.920E+03 8.730E+03 7.920E+05 1.340E+04 0.000E+00 4.440E+03 0.000E+00 4.140E+03 CS-134 6.510E+05 1.010E+06 0.000E+00 3.300E+05 1.210E+05 3.850E+03 0.000E+00 2.250E+05 CS-136 6.510E+04 1.710E+05 0.000E+00 9.550E+04 1.450E+04 4.180E+03 0.000E+00 1.160E+05 CS-137 9.060E+05 8.250E+05 0.000E+00 2.820E+05 1.040E+05 3.620E+03 0.000E+00 1.280E+05 CS-138 6.330E+02 8.400E+02 0.000E+00 6.220E+02 6.810E+01 2.700E+02 0.000E+00 5.550E+02 BA-139 1.840E+00 9.840E-04 0.000E+00 8.620E-04 5.770E+03 5.770E+04 0.000E+00 5.360E-02 BA-140 7.400E+04 6.480E+01 0.000E+00 2.110E+01 1.740E+06 1.020E+05 0.000E+00 4.330E+03 BA-141 1.960E-01 1.090E-04 0.000E+00 9.470E-05 2.920E+03 2.750E+02 0.000E+00 6.360E-03 BA-142 5.000E-02 3.600E-05 0.000E+00 2.910E-05 1.640E+03 2.740E+00 0.000E+00 2.790E-03 LA-140 6.440E+02 2.250E+02 0.000E+00 0.000E+00 1.830E+05 2.260E+05 0.000E+00 7.550E+01 LA-142 1.300E+00 4.110E-01 0.000E+00 0.000E+00 8.700E+03 7.580E+04 0.000E+00 1.290E-01 CE-141 3.920E+04 1.950E+04 0.000E+00 8.550E+03 5.440E+05 5.660E+04 0.000E+00 2.900E+03 CE-143 3.660E+02 1.990E+02 0.000E+00 8.360E+01 1.150E+05 1.270E+05 0.000E+00 2.870E+01 CE-144 6.770E+06 2.120E+06 0.000E+00 1.170E+06 1.200E+07 3.880E+05 0.000E+00 3.610E+05 PR-143 1.850E+04 5.550E+03 0.000E+00 3.000E+03 4.330E+05 9.730E+04 0.000E+00 9.140E+02 PR-144 5.960E-02 1.850E-02 0.000E+00 9.770E-03 1.570E+03 1.970E+02 0.000E+00 3.000E-03 ND-147 1.080E+04 8.730E+03 0.000E+00 4.810E+03 3.280E+05 8.210E+04 0.000E+00 6.810E+02 W-187 1.630E+01 9.660E+00 0.000E+00 0.000E+00 4.110E+04 9.100E+04 0.000E+00 4.330E+00 NP-239 4.660E+02 3.340E+01 0.000E+00 9.730E+01 5.810E+04 6.400E+04 0.000E+00 2.350E+01 Appendix B Pi Child Inhalation - Page 3 of 3 Page 9-88

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 8.740E+00 8.740E+00 8.740E+00 8.740E+00 8.740E+00 0.000E+00 8.740E+00 C-14 2.360E+02 4.730E+01 4.730E+01 4.730E+01 4.730E+01 4.730E+01 0.000E+00 4.730E+01 NA-24 8.140E+01 8.140E+01 8.140E+01 8.140E+01 8.140E+01 8.140E+01 0.000E+00 8.140E+01 P-32 1.570E+04 9.750E+02 0.000E+00 0.000E+00 0.000E+00 1.760E+03 0.000E+00 6.060E+02 CR-51 0.000E+00 0.000E+00 1.310E-01 4.820E-02 2.900E-01 5.500E+01 0.000E+00 2.190E-01 MN-54 0.000E+00 3.800E+02 0.000E+00 1.130E+02 0.000E+00 1.160E+03 0.000E+00 7.250E+01 MN-56 0.000E+00 3.800E-01 0.000E+00 4.820E-01 0.000E+00 1.210E+01 0.000E+00 6.740E-02 FE-55 2.290E+02 1.580E+02 0.000E+00 0.000E+00 8.820E+01 9.070E+01 0.000E+00 3.690E+01 FE-59 3.580E+02 8.420E+02 0.000E+00 0.000E+00 2.350E+02 2.810E+03 0.000E+00 3.230E+02 CO-58 0.000E+00 6.170E+01 0.000E+00 0.000E+00 0.000E+00 1.250E+03 0.000E+00 1.380E+02 CO-60 0.000E+00 1.780E+02 0.000E+00 0.000E+00 0.000E+00 3.340E+03 0.000E+00 3.930E+02 NI-63 1.080E+04 7.500E+02 0.000E+00 0.000E+00 0.000E+00 1.560E+02 0.000E+00 3.630E+02 NI-65 1.620E+00 2.100E-01 0.000E+00 0.000E+00 0.000E+00 5.340E+00 0.000E+00 9.600E-02 CU-64 0.000E+00 3.590E+00 0.000E+00 9.060E+00 0.000E+00 3.060E+02 0.000E+00 1.690E+00 ZN-65 4.020E+02 1.280E+03 0.000E+00 8.560E+02 0.000E+00 8.060E+02 0.000E+00 5.780E+02 ZN-69 1.070E-04 2.050E-04 0.000E+00 1.330E-04 0.000E+00 3.080E-05 0.000E+00 1.430E-05 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.480E-01 0.000E+00 1.030E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.270E-12 0.000E+00 6.710E-07 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.380E-77 RB-86 0.000E+00 1.720E+03 0.000E+00 0.000E+00 0.000E+00 3.400E+02 0.000E+00 8.030E+02 RB-88 0.000E+00 3.360E-12 0.000E+00 0.000E+00 0.000E+00 4.640E-23 0.000E+00 1.780E-12 RB-89 0.000E+00 3.090E-14 0.000E+00 0.000E+00 0.000E+00 1.790E-27 0.000E+00 2.170E-14 SR-89 2.550E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.080E+03 0.000E+00 7.310E+02 SR-90 6.310E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.820E+04 0.000E+00 1.550E+05 SR-91 1.960E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.350E+02 0.000E+00 7.930E+00 Appendix C - Ai Adult Potable Water - Page 1 of 3 Page 9-89

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 8.290E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.640E+02 0.000E+00 3.590E-01 Y-90 7.030E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.460E+03 0.000E+00 1.890E-02 Y-91 1.170E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.420E+03 0.000E+00 3.120E-01 Y-91M 3.360E-07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.860E-07 0.000E+00 1.300E-08 Y-92 6.710E-03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.170E+02 0.000E+00 1.960E-04 Y-93 9.770E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.100E+03 0.000E+00 2.700E-03 ZR-95 2.520E+00 8.070E-01 0.000E+00 1.270E+00 0.000E+00 2.560E+03 0.000E+00 5.460E-01 ZR-97 8.540E-02 1.720E-02 0.000E+00 2.600E-02 0.000E+00 5.340E+03 0.000E+00 7.880E-03 NB-95 5.130E-01 2.850E-01 0.000E+00 2.820E-01 0.000E+00 1.730E+03 0.000E+00 1.530E-01 MO-99 0.000E+00 3.160E+02 0.000E+00 7.160E+02 0.000E+00 7.330E+02 0.000E+00 6.020E+01 TC-99M 5.160E-03 1.460E-02 0.000E+00 2.210E-01 7.140E-03 8.630E+00 0.000E+00 1.860E-01 TC-101 1.130E-17 1.630E-17 0.000E+00 2.930E-16 8.320E-18 4.890E-29 0.000E+00 1.600E-16 RU-103 1.530E+01 0.000E+00 0.000E+00 5.820E+01 0.000E+00 1.780E+03 0.000E+00 6.570E+00 RU-105 1.970E-01 0.000E+00 0.000E+00 2.540E+00 0.000E+00 1.200E+02 0.000E+00 7.760E-02 RU-106 2.290E+02 0.000E+00 0.000E+00 4.410E+02 0.000E+00 1.480E+04 0.000E+00 2.890E+01 AG-110M 1.330E+01 1.230E+01 0.000E+00 2.420E+01 0.000E+00 5.020E+03 0.000E+00 7.300E+00 TE-125M 2.220E+02 8.030E+01 6.670E+01 9.020E+02 0.000E+00 8.850E+02 0.000E+00 2.970E+01 TE-127 3.780E+00 1.360E+00 2.800E+00 1.540E+01 0.000E+00 2.980E+02 0.000E+00 8.170E-01 TE-127M 5.620E+02 2.010E+02 1.440E+02 2.280E+03 0.000E+00 1.880E+03 0.000E+00 6.840E+01 TE-129 1.920E-03 7.230E-04 1.480E-03 8.080E-03 0.000E+00 1.450E-03 0.000E+00 4.690E-04 TE-129M 9.470E+02 3.530E+02 3.250E+02 3.950E+03 0.000E+00 4.770E+03 0.000E+00 1.500E+02 TE-131 3.520E-09 1.470E-09 2.900E-09 1.540E-08 0.000E+00 4.990E-10 0.000E+00 1.110E-09 TE-131M 1.090E+02 5.340E+01 8.450E+01 5.400E+02 0.000E+00 5.300E+03 0.000E+00 4.450E+01 TE-132 1.880E+02 1.220E+02 1.350E+02 1.170E+03 0.000E+00 5.770E+03 0.000E+00 1.140E+02 I-130 3.210E+01 9.460E+01 8.020E+03 1.480E+02 0.000E+00 8.140E+01 0.000E+00 3.730E+01 Appendix C - Ai Adult Potable Water - Page 2 of 3 Page 9-90

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.320E+02 4.740E+02 1.550E+05 8.130E+02 0.000E+00 1.250E+02 0.000E+00 2.720E+02 I-132 4.540E-01 1.220E+00 4.250E+01 1.940E+00 0.000E+00 2.280E-01 0.000E+00 4.250E-01 I-133 7.920E+01 1.380E+02 2.020E+04 2.400E+02 0.000E+00 1.240E+02 0.000E+00 4.200E+01 I-134 6.580E-04 1.790E-03 3.100E-02 2.840E-03 0.000E+00 1.560E-06 0.000E+00 6.390E-04 I-135 1.050E+01 2.750E+01 1.810E+03 4.400E+01 0.000E+00 3.100E+01 0.000E+00 1.010E+01 CS-134 5.170E+03 1.230E+04 0.000E+00 3.980E+03 1.320E+03 2.150E+02 0.000E+00 1.010E+04 CS-136 5.280E+02 2.080E+03 0.000E+00 1.160E+03 1.590E+02 2.370E+02 0.000E+00 1.500E+03 CS-137 6.630E+03 9.070E+03 0.000E+00 3.080E+03 1.020E+03 1.760E+02 0.000E+00 5.940E+03 CS-138 8.450E-07 1.670E-06 0.000E+00 1.230E-06 1.210E-07 7.120E-12 0.000E+00 8.260E-07 BA-139 1.990E-02 1.420E-05 0.000E+00 1.330E-05 8.050E-06 3.530E-02 0.000E+00 5.830E-04 BA-140 1.640E+03 2.070E+00 0.000E+00 7.020E-01 1.180E+00 3.390E+03 0.000E+00 1.080E+02 BA-141 5.440E-12 4.120E-15 0.000E+00 3.830E-15 2.340E-15 2.570E-21 0.000E+00 1.840E-13 BA-142 6.290E-21 6.470E-24 0.000E+00 5.460E-24 3.660E-24 8.860E-39 0.000E+00 3.960E-22 LA-140 1.690E-01 8.530E-02 0.000E+00 0.000E+00 0.000E+00 6.260E+03 0.000E+00 2.250E-02 LA-142 5.720E-05 2.600E-05 0.000E+00 0.000E+00 0.000E+00 1.900E-01 0.000E+00 6.480E-06 CE-141 7.710E-01 5.210E-01 0.000E+00 2.420E-01 0.000E+00 1.990E+03 0.000E+00 5.910E-02 CE-143 1.070E-01 7.890E+01 0.000E+00 3.470E-02 0.000E+00 2.950E+03 0.000E+00 8.730E-03 CE-144 4.060E+01 1.700E+01 0.000E+00 1.010E+01 0.000E+00 1.370E+04 0.000E+00 2.180E+00 PR-143 7.460E-01 2.990E-01 0.000E+00 1.730E-01 0.000E+00 3.270E+03 0.000E+00 3.700E-02 PR-144 7.350E-16 3.050E-16 0.000E+00 1.720E-16 0.000E+00 1.060E-22 0.000E+00 3.730E-17 ND-147 5.070E-01 5.860E-01 0.000E+00 3.430E-01 0.000E+00 2.810E+03 0.000E+00 3.510E-02 W-187 6.050E+00 5.050E+00 0.000E+00 0.000E+00 0.000E+00 1.660E+03 0.000E+00 1.770E+00 NP-239 8.550E-02 8.400E-03 0.000E+00 2.620E-02 0.000E+00 1.720E+03 0.000E+00 4.630E-03 Appendix C - Ai Adult Potable Water - Page 3 of 3 Page 9-91

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.260E-01 2.260E-01 2.260E-01 2.260E-01 2.260E-01 0.000E+00 2.260E-01 C-14 3.130E+04 6.260E+03 6.260E+03 6.260E+03 6.260E+03 6.260E+03 0.000E+00 6.260E+03 NA-24 1.350E+02 1.350E+02 1.350E+02 1.350E+02 1.350E+02 1.350E+02 0.000E+00 1.350E+02 P-32 1.320E+06 8.210E+04 0.000E+00 0.000E+00 0.000E+00 1.480E+05 0.000E+00 5.100E+04 CR-51 0.000E+00 0.000E+00 7.420E-01 2.740E-01 1.650E+00 3.120E+02 0.000E+00 1.240E+00 MN-54 0.000E+00 4.370E+03 0.000E+00 1.300E+03 0.000E+00 1.340E+04 0.000E+00 8.330E+02 MN-56 0.000E+00 1.730E-01 0.000E+00 2.200E-01 0.000E+00 5.530E+00 0.000E+00 3.070E-02 FE-55 6.580E+02 4.550E+02 0.000E+00 0.000E+00 2.540E+02 2.610E+02 0.000E+00 1.060E+02 FE-59 1.020E+03 2.400E+03 0.000E+00 0.000E+00 6.720E+02 8.010E+03 0.000E+00 9.220E+02 CO-58 0.000E+00 8.830E+01 0.000E+00 0.000E+00 0.000E+00 1.790E+03 0.000E+00 1.980E+02 CO-60 0.000E+00 2.560E+02 0.000E+00 0.000E+00 0.000E+00 4.810E+03 0.000E+00 5.650E+02 NI-63 3.110E+04 2.160E+03 0.000E+00 0.000E+00 0.000E+00 4.500E+02 0.000E+00 1.040E+03 NI-65 1.720E-01 2.230E-02 0.000E+00 0.000E+00 0.000E+00 5.660E-01 0.000E+00 1.020E-02 CU-64 0.000E+00 2.680E+00 0.000E+00 6.760E+00 0.000E+00 2.290E+02 0.000E+00 1.260E+00 ZN-65 2.310E+04 7.350E+04 0.000E+00 4.920E+04 0.000E+00 4.630E+04 0.000E+00 3.320E+04 ZN-69 7.730E-07 1.480E-06 0.000E+00 9.610E-07 0.000E+00 2.220E-07 0.000E+00 1.030E-07 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.500E-02 0.000E+00 3.820E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.850E-18 0.000E+00 1.250E-12 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 9.730E+04 0.000E+00 0.000E+00 0.000E+00 1.920E+04 0.000E+00 4.530E+04 RB-88 0.000E+00 1.290E-22 0.000E+00 0.000E+00 0.000E+00 1.780E-33 0.000E+00 6.830E-23 RB-89 0.000E+00 1.640E-26 0.000E+00 0.000E+00 0.000E+00 9.560E-40 0.000E+00 1.160E-26 SR-89 2.180E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.500E+03 0.000E+00 6.260E+02 SR-90 5.440E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.570E+04 0.000E+00 1.340E+05 SR-91 7.050E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.360E+02 0.000E+00 2.850E+00 Appendix C Ai Adult Fresh Water Fish - Page 1 of 3 Page 9-92

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 3.320E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.570E+00 0.000E+00 1.430E-02 Y-90 4.440E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.710E+03 0.000E+00 1.190E-02 Y-91 8.340E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.590E+03 0.000E+00 2.230E-01 Y-91M 1.070E-11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.150E-11 0.000E+00 4.150E-13 Y-92 4.600E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.060E+00 0.000E+00 1.340E-05 Y-93 3.080E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.770E+02 0.000E+00 8.500E-04 ZR-95 2.380E-01 7.620E-02 0.000E+00 1.200E-01 0.000E+00 2.410E+02 0.000E+00 5.160E-02 ZR-97 4.960E-03 1.000E-03 0.000E+00 1.510E-03 0.000E+00 3.100E+02 0.000E+00 4.570E-04 NB-95 4.380E+02 2.440E+02 0.000E+00 2.410E+02 0.000E+00 1.480E+06 0.000E+00 1.310E+02 MO-99 0.000E+00 8.020E+01 0.000E+00 1.820E+02 0.000E+00 1.860E+02 0.000E+00 1.530E+01 TC-99M 5.590E-04 1.580E-03 0.000E+00 2.400E-02 7.740E-04 9.340E-01 0.000E+00 2.010E-02 TC-101 2.610E-33 3.760E-33 0.000E+00 6.770E-32 1.920E-33 1.130E-44 0.000E+00 3.690E-32 RU-103 4.350E+00 0.000E+00 0.000E+00 1.660E+01 0.000E+00 5.080E+02 0.000E+00 1.870E+00 RU-105 8.670E-03 0.000E+00 0.000E+00 1.120E-01 0.000E+00 5.300E+00 0.000E+00 3.420E-03 RU-106 6.570E+01 0.000E+00 0.000E+00 1.270E+02 0.000E+00 4.250E+03 0.000E+00 8.320E+00 AG-110M 8.790E-01 8.130E-01 0.000E+00 1.600E+00 0.000E+00 3.320E+02 0.000E+00 4.830E-01 TE-125M 2.540E+03 9.190E+02 7.630E+02 1.030E+04 0.000E+00 1.010E+04 0.000E+00 3.400E+02 TE-127 1.790E+01 6.440E+00 1.330E+01 7.300E+01 0.000E+00 1.410E+03 0.000E+00 3.880E+00 TE-127M 6.440E+03 2.300E+03 1.650E+03 2.620E+04 0.000E+00 2.160E+04 0.000E+00 7.850E+02 TE-129 1.630E-05 6.120E-06 1.250E-05 6.850E-05 0.000E+00 1.230E-05 0.000E+00 3.970E-06 TE-129M 1.080E+04 4.020E+03 3.710E+03 4.500E+04 0.000E+00 5.430E+04 0.000E+00 1.710E+03 TE-131 8.710E-17 3.640E-17 7.160E-17 3.820E-16 0.000E+00 1.230E-17 0.000E+00 2.750E-17 TE-131M 9.510E+02 4.650E+02 7.370E+02 4.710E+03 0.000E+00 4.620E+04 0.000E+00 3.880E+02 TE-132 1.950E+03 1.260E+03 1.390E+03 1.210E+04 0.000E+00 5.960E+04 0.000E+00 1.180E+03 I-130 7.050E+00 2.080E+01 1.760E+03 3.250E+01 0.000E+00 1.790E+01 0.000E+00 8.210E+00 Appendix C Ai Adult Fresh Water Fish - Page 2 of 3 Page 9-93

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.370E+02 1.960E+02 6.420E+04 3.360E+02 0.000E+00 5.170E+01 0.000E+00 1.120E+02 I-132 5.270E-03 1.410E-02 4.940E-01 2.250E-02 0.000E+00 2.650E-03 0.000E+00 4.940E-03 I-133 2.290E+01 3.990E+01 5.860E+03 6.950E+01 0.000E+00 3.580E+01 0.000E+00 1.210E+01 I-134 2.120E-08 5.750E-08 9.960E-07 9.140E-08 0.000E+00 5.010E-11 0.000E+00 2.060E-08 I-135 1.290E+00 3.370E+00 2.220E+02 5.410E+00 0.000E+00 3.810E+00 0.000E+00 1.240E+00 CS-134 2.980E+05 7.080E+05 0.000E+00 2.290E+05 7.610E+04 1.240E+04 0.000E+00 5.790E+05 CS-136 2.960E+04 1.170E+05 0.000E+00 6.500E+04 8.900E+03 1.330E+04 0.000E+00 8.400E+04 CS-137 3.820E+05 5.220E+05 0.000E+00 1.770E+05 5.890E+04 1.010E+04 0.000E+00 3.420E+05 CS-138 8.940E-12 1.770E-11 0.000E+00 1.300E-11 1.280E-12 7.530E-17 0.000E+00 8.750E-12 BA-139 5.650E-06 4.030E-09 0.000E+00 3.760E-09 2.280E-09 1.000E-05 0.000E+00 1.660E-07 BA-140 1.840E+02 2.310E-01 0.000E+00 7.860E-02 1.320E-01 3.790E+02 0.000E+00 1.210E+01 BA-141 8.700E-25 6.580E-28 0.000E+00 6.120E-28 3.730E-28 4.100E-34 0.000E+00 2.940E-26 BA-142 2.570E-42 2.640E-45 0.000E+00 2.230E-45 1.490E-45 3.620E-60 0.000E+00 1.610E-43 LA-140 9.900E-02 4.990E-02 0.000E+00 0.000E+00 0.000E+00 3.660E+03 0.000E+00 1.320E-02 LA-142 2.210E-07 1.000E-07 0.000E+00 0.000E+00 0.000E+00 7.330E-04 0.000E+00 2.500E-08 CE-141 2.190E-02 1.480E-02 0.000E+00 6.890E-03 0.000E+00 5.670E+01 0.000E+00 1.680E-03 CE-143 2.380E-03 1.760E+00 0.000E+00 7.760E-04 0.000E+00 6.590E+01 0.000E+00 1.950E-04 CE-144 1.170E+00 4.870E-01 0.000E+00 2.890E-01 0.000E+00 3.940E+02 0.000E+00 6.260E-02 PR-143 5.230E-01 2.100E-01 0.000E+00 1.210E-01 0.000E+00 2.290E+03 0.000E+00 2.590E-02 PR-144 1.550E-28 6.440E-29 0.000E+00 3.630E-29 0.000E+00 2.230E-35 0.000E+00 7.880E-30 ND-147 3.530E-01 4.080E-01 0.000E+00 2.390E-01 0.000E+00 1.960E+03 0.000E+00 2.440E-02 W-187 1.470E+02 1.230E+02 0.000E+00 0.000E+00 0.000E+00 4.030E+04 0.000E+00 4.300E+01 NP-239 2.120E-02 2.090E-03 0.000E+00 6.510E-03 0.000E+00 4.280E+02 0.000E+00 1.150E-03 Appendix C Ai Adult Fresh Water Fish - Page 3 of 3 Page 9-94

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 6.410E-01 6.410E-01 6.410E-01 6.410E-01 6.410E-01 6.410E-01 7.440E-01 6.410E-01 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 2.500E-01 2.500E-01 2.500E-01 2.500E-01 2.500E-01 2.500E-01 2.960E-01 2.500E-01 MN-54 7.440E+01 7.440E+01 7.440E+01 7.440E+01 7.440E+01 7.440E+01 8.720E+01 7.440E+01 MN-56 4.840E-02 4.840E-02 4.840E-02 4.840E-02 4.840E-02 4.840E-02 5.720E-02 4.840E-02 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 1.460E+01 1.460E+01 1.460E+01 1.460E+01 1.460E+01 1.460E+01 1.720E+01 1.460E+01 CO-58 2.030E+01 2.030E+01 2.030E+01 2.030E+01 2.030E+01 2.030E+01 2.380E+01 2.030E+01 CO-60 1.150E+03 1.150E+03 1.150E+03 1.150E+03 1.150E+03 1.150E+03 1.360E+03 1.150E+03 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 1.590E-02 1.590E-02 1.590E-02 1.590E-02 1.590E-02 1.590E-02 1.850E-02 1.590E-02 CU-64 3.260E-02 3.260E-02 3.260E-02 3.260E-02 3.260E-02 3.260E-02 3.690E-02 3.260E-02 ZN-65 4.010E+01 4.010E+01 4.010E+01 4.010E+01 4.010E+01 4.010E+01 4.610E+01 4.010E+01 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 2.620E-04 2.620E-04 2.620E-04 2.620E-04 2.620E-04 2.620E-04 3.800E-04 2.620E-04 BR-84 1.090E-02 1.090E-02 1.090E-02 1.090E-02 1.090E-02 1.090E-02 1.270E-02 1.090E-02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 4.820E-01 4.820E-01 4.820E-01 4.820E-01 4.820E-01 4.820E-01 5.510E-01 4.820E-01 RB-88 1.780E-03 1.780E-03 1.780E-03 1.780E-03 1.780E-03 1.780E-03 2.030E-03 1.780E-03 RB-89 6.600E-03 6.600E-03 6.600E-03 6.600E-03 6.600E-03 6.600E-03 7.920E-03 6.600E-03 SR-89 1.160E-03 1.160E-03 1.160E-03 1.160E-03 1.160E-03 1.160E-03 1.350E-03 1.160E-03 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 1.150E-01 1.150E-01 1.150E-01 1.150E-01 1.150E-01 1.150E-01 1.350E-01 1.150E-01 Appendix C Ai Adult Shoreline Sediment - Page 1 of 3 Page 9-95

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.170E-02 4.170E-02 4.170E-02 4.170E-02 4.170E-02 4.170E-02 4.630E-02 4.170E-02 Y-90 2.410E-04 2.410E-04 2.410E-04 2.410E-04 2.410E-04 2.410E-04 2.850E-04 2.410E-04 Y-91 5.760E-02 5.760E-02 5.760E-02 5.760E-02 5.760E-02 5.760E-02 6.480E-02 5.760E-02 Y-91M 5.380E-03 5.380E-03 5.380E-03 5.380E-03 5.380E-03 5.380E-03 6.230E-03 5.380E-03 Y-92 9.680E-03 9.680E-03 9.680E-03 9.680E-03 9.680E-03 9.680E-03 1.150E-02 9.680E-03 Y-93 9.840E-03 9.840E-03 9.840E-03 9.840E-03 9.840E-03 9.840E-03 1.350E-02 9.840E-03 ZR-95 1.310E+01 1.310E+01 1.310E+01 1.310E+01 1.310E+01 1.310E+01 1.520E+01 1.310E+01 ZR-97 1.590E-01 1.590E-01 1.590E-01 1.590E-01 1.590E-01 1.590E-01 1.850E-01 1.590E-01 NB-95 7.340E+00 7.340E+00 7.340E+00 7.340E+00 7.340E+00 7.340E+00 8.630E+00 7.340E+00 MO-99 2.140E-01 2.140E-01 2.140E-01 2.140E-01 2.140E-01 2.140E-01 2.480E-01 2.140E-01 TC-99M 9.880E-03 9.880E-03 9.880E-03 9.880E-03 9.880E-03 9.880E-03 1.130E-02 9.880E-03 TC-101 1.090E-03 1.090E-03 1.090E-03 1.090E-03 1.090E-03 1.090E-03 1.210E-03 1.090E-03 RU-103 5.810E+00 5.810E+00 5.810E+00 5.810E+00 5.810E+00 5.810E+00 6.780E+00 5.810E+00 RU-105 3.420E-02 3.420E-02 3.420E-02 3.420E-02 3.420E-02 3.420E-02 3.870E-02 3.420E-02 RU-106 2.270E+01 2.270E+01 2.270E+01 2.270E+01 2.270E+01 2.270E+01 2.720E+01 2.270E+01 AG-110M 1.850E+02 1.850E+02 1.850E+02 1.850E+02 1.850E+02 1.850E+02 2.150E+02 1.850E+02 TE-125M 8.330E-02 8.330E-02 8.330E-02 8.330E-02 8.330E-02 8.330E-02 1.140E-01 8.330E-02 TE-127 1.600E-04 1.600E-04 1.600E-04 1.600E-04 1.600E-04 1.600E-04 1.760E-04 1.600E-04 TE-127M 4.920E-03 4.920E-03 4.920E-03 4.920E-03 4.920E-03 4.920E-03 5.810E-03 4.920E-03 TE-129 1.410E-03 1.410E-03 1.410E-03 1.410E-03 1.410E-03 1.410E-03 1.670E-03 1.410E-03 TE-129M 1.060E+00 1.060E+00 1.060E+00 1.060E+00 1.060E+00 1.060E+00 1.240E+00 1.060E+00 TE-131 1.570E-03 1.570E-03 1.570E-03 1.570E-03 1.570E-03 1.570E-03 1.850E+00 1.570E-03 TE-131M 4.310E-01 4.310E-01 4.310E-01 4.310E-01 4.310E-01 4.310E-01 5.080E-01 4.310E-01 TE-132 2.270E-01 2.270E-01 2.270E-01 2.270E-01 2.270E-01 2.270E-01 2.670E-01 2.270E-01 I-130 2.960E-01 2.960E-01 2.960E-01 2.960E-01 2.960E-01 2.960E-01 3.590E-01 2.960E-01 Appendix C Ai Adult Shoreline Sediment - Page 2 of 3 Page 9-96

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 9.240E-01 9.240E-01 9.240E-01 9.240E-01 9.240E-01 9.240E-01 1.120E+00 9.240E-01 I-132 6.680E-02 6.680E-02 6.680E-02 6.680E-02 6.680E-02 6.680E-02 7.860E-02 6.680E-02 I-133 1.320E-01 1.320E-01 1.320E-01 1.320E-01 1.320E-01 1.320E-01 1.600E-01 1.320E-01 I-134 2.400E-02 2.400E-02 2.400E-02 2.400E-02 2.400E-02 2.400E-02 2.850E-02 2.400E-02 I-135 1.360E-01 1.360E-01 1.360E-01 1.360E-01 1.360E-01 1.360E-01 1.580E-01 1.360E-01 CS-134 3.680E+02 3.680E+02 3.680E+02 3.680E+02 3.680E+02 3.680E+02 4.300E+02 3.680E+02 CS-136 8.100E+00 8.100E+00 8.100E+00 8.100E+00 8.100E+00 8.100E+00 9.180E+00 8.100E+00 CS-137 5.520E+02 5.520E+02 5.520E+02 5.520E+02 5.520E+02 5.520E+02 6.440E+02 5.520E+02 CS-138 1.930E-02 1.930E-02 1.930E-02 1.930E-02 1.930E-02 1.930E-02 2.200E-02 1.930E-02 BA-139 5.680E-03 5.680E-03 5.680E-03 5.680E-03 5.680E-03 5.680E-03 6.390E-03 5.680E-03 BA-140 1.100E+00 1.100E+00 1.100E+00 1.100E+00 1.100E+00 1.100E+00 1.260E+00 1.100E+00 BA-141 2.240E-03 2.240E-03 2.240E-03 2.240E-03 2.240E-03 2.240E-03 2.550E-03 2.240E-03 BA-142 2.410E-03 2.410E-03 2.410E-03 2.410E-03 2.410E-03 2.410E-03 2.740E-03 2.410E-03 LA-140 1.030E+00 1.030E+00 1.030E+00 1.030E+00 1.030E+00 1.030E+00 1.170E+00 1.030E+00 LA-142 4.080E-02 4.080E-02 4.080E-02 4.080E-02 4.080E-02 4.080E-02 4.890E-02 4.080E-02 CE-141 7.330E-01 7.330E-01 7.330E-01 7.330E-01 7.330E-01 7.330E-01 8.270E-01 7.330E-01 CE-143 1.240E-01 1.240E-01 1.240E-01 1.240E-01 1.240E-01 1.240E-01 1.410E-01 1.240E-01 CE-144 3.730E+00 3.730E+00 3.730E+00 3.730E+00 3.730E+00 3.730E+00 4.320E+00 3.730E+00 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 9.850E-05 9.850E-05 9.850E-05 9.850E-05 9.850E-05 9.850E-05 1.130E-04 9.850E-05 ND-147 4.510E-01 4.510E-01 4.510E-01 4.510E-01 4.510E-01 4.510E-01 5.410E-01 4.510E-01 W-187 1.260E-01 1.260E-01 1.260E-01 1.260E-01 1.260E-01 1.260E-01 1.470E-01 1.260E-01 NP-239 9.180E-02 9.180E-02 9.180E-02 9.180E-02 9.180E-02 9.180E-02 1.060E-01 9.180E-02 Appendix C Ai Adult Shoreline Sediment - Page 3 of 3 Page 9-97

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX D Ai Teen Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 6.160E+00 6.160E+00 6.160E+00 6.160E+00 6.160E+00 0.000E+00 6.160E+00 C-14 2.360E+02 4.720E+01 4.720E+01 4.720E+01 4.720E+01 4.720E+01 0.000E+00 4.720E+01 NA-24 7.690E+01 7.690E+01 7.690E+01 7.690E+01 7.690E+01 7.690E+01 0.000E+00 7.690E+01 P-32 1.570E+04 9.700E+02 0.000E+00 0.000E+00 0.000E+00 1.320E+03 0.000E+00 6.070E+02 CR-51 0.000E+00 0.000E+00 1.150E-01 4.530E-02 2.950E-01 3.470E+01 0.000E+00 2.070E-01 MN-54 0.000E+00 3.430E+02 0.000E+00 1.020E+02 0.000E+00 7.030E+02 0.000E+00 6.790E+01 MN-56 0.000E+00 3.640E-01 0.000E+00 4.610E-01 0.000E+00 2.400E+01 0.000E+00 6.480E-02 FE-55 2.200E+02 1.560E+02 0.000E+00 0.000E+00 9.880E+01 6.740E+01 0.000E+00 3.630E+01 FE-59 3.390E+02 7.900E+02 0.000E+00 0.000E+00 2.490E+02 1.870E+03 0.000E+00 3.050E+02 CO-58 0.000E+00 5.620E+01 0.000E+00 0.000E+00 0.000E+00 7.750E+02 0.000E+00 1.300E+02 CO-60 0.000E+00 1.630E+02 0.000E+00 0.000E+00 0.000E+00 2.130E+03 0.000E+00 3.680E+02 NI-63 1.030E+04 7.270E+02 0.000E+00 0.000E+00 0.000E+00 1.160E+02 0.000E+00 3.490E+02 NI-65 1.610E+00 2.050E-01 0.000E+00 0.000E+00 0.000E+00 1.110E+01 0.000E+00 9.350E-02 CU-64 0.000E+00 3.470E+00 0.000E+00 8.770E+00 0.000E+00 2.690E+02 0.000E+00 1.630E+00 ZN-65 3.340E+02 1.160E+03 0.000E+00 7.430E+02 0.000E+00 4.920E+02 0.000E+00 5.420E+02 ZN-69 1.070E-04 2.040E-04 0.000E+00 1.330E-04 0.000E+00 3.760E-04 0.000E+00 1.430E-05 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.030E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.500E-07 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.360E-77 RB-86 0.000E+00 1.700E+03 0.000E+00 0.000E+00 0.000E+00 2.520E+02 0.000E+00 7.990E+02 RB-88 0.000E+00 3.300E-12 0.000E+00 0.000E+00 0.000E+00 2.830E-19 0.000E+00 1.760E-12 RB-89 0.000E+00 2.960E-14 0.000E+00 0.000E+00 0.000E+00 4.540E-23 0.000E+00 2.090E-14 SR-89 2.540E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.030E+03 0.000E+00 7.280E+02 SR-90 4.830E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.350E+04 0.000E+00 1.190E+05 SR-91 1.950E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.850E+02 0.000E+00 7.760E+00 Appendix D Ai Teen Water - Page 1 of 3 Page 9-98

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX D Ai Teen Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 8.220E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.090E+02 0.000E+00 3.500E-01 Y-90 7.000E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.770E+03 0.000E+00 1.880E-02 Y-91 1.160E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.760E+03 0.000E+00 3.120E-01 Y-91M 3.330E-07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.570E-05 0.000E+00 1.270E-08 Y-92 6.710E-03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.840E+02 0.000E+00 1.940E-04 Y-93 9.760E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.980E+03 0.000E+00 2.670E-03 ZR-95 2.380E+00 7.520E-01 0.000E+00 1.100E+00 0.000E+00 1.730E+03 0.000E+00 5.170E-01 ZR-97 8.420E-02 1.670E-02 0.000E+00 2.530E-02 0.000E+00 4.510E+03 0.000E+00 7.670E-03 NB-95 4.730E-01 2.630E-01 0.000E+00 2.540E-01 0.000E+00 1.120E+03 0.000E+00 1.440E-01 MO-99 0.000E+00 3.090E+02 0.000E+00 7.070E+02 0.000E+00 5.530E+02 0.000E+00 5.890E+01 TC-99M 4.840E-03 1.350E-02 0.000E+00 2.010E-01 7.500E-03 8.870E+00 0.000E+00 1.750E-01 TC-101 1.120E-17 1.590E-17 0.000E+00 2.880E-16 9.700E-18 2.720E-24 0.000E+00 1.560E-16 RU-103 1.470E+01 0.000E+00 0.000E+00 5.180E+01 0.000E+00 1.230E+03 0.000E+00 6.280E+00 RU-105 1.940E-01 0.000E+00 0.000E+00 2.450E+00 0.000E+00 1.570E+02 0.000E+00 7.540E-02 RU-106 2.280E+02 0.000E+00 0.000E+00 4.390E+02 0.000E+00 1.090E+04 0.000E+00 2.870E+01 AG-110M 1.190E+01 1.130E+01 0.000E+00 2.150E+01 0.000E+00 3.160E+03 0.000E+00 6.850E+00 TE-125M 2.210E+02 7.980E+01 6.180E+01 0.000E+00 0.000E+00 6.530E+02 0.000E+00 2.960E+01 TE-127 3.790E+00 1.340E+00 2.610E+00 1.530E+01 0.000E+00 2.930E+02 0.000E+00 8.150E-01 TE-127M 5.600E+02 1.990E+02 1.330E+02 2.270E+03 0.000E+00 1.400E+03 0.000E+00 6.660E+01 TE-129 1.920E-03 7.150E-04 1.370E-03 8.040E-03 0.000E+00 1.050E-02 0.000E+00 4.660E-04 TE-129M 9.380E+02 3.480E+02 3.030E+02 3.920E+03 0.000E+00 3.520E+03 0.000E+00 1.480E+02 TE-131 3.490E-09 1.440E-09 2.690E-09 1.520E-08 0.000E+00 2.860E-10 0.000E+00 1.090E-09 TE-131M 1.080E+02 5.150E+01 7.750E+01 5.380E+02 0.000E+00 4.140E+03 0.000E+00 4.300E+01 TE-132 1.820E+02 1.150E+02 1.220E+02 1.110E+03 0.000E+00 3.660E+03 0.000E+00 1.090E+02 I-130 3.050E+01 8.830E+01 7.200E+03 1.360E+02 0.000E+00 6.790E+01 0.000E+00 3.530E+01 Appendix D Ai Teen Water - Page 2 of 3 Page 9-99

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX D Ai Teen Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.260E+02 4.560E+02 1.330E+05 7.850E+02 0.000E+00 9.020E+01 0.000E+00 2.450E+02 I-132 4.360E-01 1.140E+00 3.850E+01 1.800E+00 0.000E+00 4.970E-01 0.000E+00 4.100E-01 I-133 7.830E+01 1.330E+02 1.860E+04 2.330E+02 0.000E+00 1.010E+02 0.000E+00 4.050E+01 I-134 6.330E-04 1.680E-03 2.800E-02 2.640E-03 0.000E+00 2.210E-05 0.000E+00 6.020E-04 I-135 1.010E+01 2.600E+01 1.670E+03 4.100E+01 0.000E+00 2.880E+01 0.000E+00 9.630E+00 CS-134 4.860E+03 1.140E+04 0.000E+00 3.640E+03 1.390E+03 1.420E+02 0.000E+00 5.310E+03 CS-136 4.860E+02 1.910E+03 0.000E+00 1.040E+03 1.640E+02 1.540E+02 0.000E+00 1.290E+03 CS-137 6.510E+03 8.660E+03 0.000E+00 2.950E+03 1.150E+03 1.230E+02 0.000E+00 3.020E+03 CS-138 8.300E-07 1.590E-06 0.000E+00 1.180E-06 1.370E-07 7.230E-10 0.000E+00 7.970E-07 BA-139 1.990E-02 1.400E-05 0.000E+00 1.320E-05 9.670E-06 1.780E-01 0.000E+00 5.810E-04 BA-140 1.610E+03 1.970E+00 0.000E+00 6.680E-01 1.320E+00 2.480E+03 0.000E+00 1.040E+02 BA-141 5.420E-12 4.050E-15 0.000E+00 3.760E-15 2.770E-15 1.150E-17 0.000E+00 1.810E-13 BA-142 6.170E-21 6.170E-24 0.000E+00 5.220E-24 4.100E-24 1.890E-32 0.000E+00 3.800E-22 LA-140 1.650E-01 8.090E-02 0.000E+00 0.000E+00 0.000E+00 4.640E+03 0.000E+00 2.150E-02 LA-142 5.590E-05 2.480E-05 0.000E+00 0.000E+00 0.000E+00 7.550E-01 0.000E+00 6.180E-06 CE-141 7.650E-01 5.110E-01 0.000E+00 2.400E-01 0.000E+00 1.460E+03 0.000E+00 5.870E-02 CE-143 1.060E-01 7.730E+01 0.000E+00 3.460E-02 0.000E+00 2.320E+03 0.000E+00 8.630E-03 CE-144 4.040E+01 1.670E+01 0.000E+00 9.990E+00 0.000E+00 1.020E+04 0.000E+00 2.170E+00 PR-143 7.420E-01 2.960E-01 0.000E+00 1.720E-01 0.000E+00 2.440E+03 0.000E+00 3.700E-02 PR-144 7.330E-16 3.000E-16 0.000E+00 1.720E-16 0.000E+00 8.080E-19 0.000E+00 3.720E-17 ND-147 5.280E-01 5.750E-01 0.000E+00 3.370E-01 0.000E+00 2.070E+03 0.000E+00 3.440E-02 W-187 5.990E+00 4.880E+00 0.000E+00 0.000E+00 0.000E+00 1.320E+03 0.000E+00 1.710E+00 NP-239 8.830E-02 8.330E-03 0.000E+00 2.610E-02 0.000E+00 1.340E+03 0.000E+00 4.630E-03 Appendix D Ai Teen Water - Page 3 of 3 Page 9-100

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.740E-01 1.740E-01 1.740E-01 1.740E-01 1.740E-01 0.000E+00 1.740E-01 C-14 3.410E+04 6.810E+03 6.810E+03 6.810E+03 6.810E+03 6.810E+03 0.000E+00 6.810E+03 NA-24 1.390E+02 1.390E+02 1.390E+02 1.390E+02 1.390E+02 1.390E+02 0.000E+00 1.390E+02 P-32 1.440E+06 8.910E+04 0.000E+00 0.000E+00 0.000E+00 1.210E+05 0.000E+00 5.580E+04 CR-51 0.000E+00 0.000E+00 7.120E-01 2.810E-01 1.830E+00 2.150E+02 0.000E+00 1.280E+00 MN-54 0.000E+00 4.300E+03 0.000E+00 1.280E+03 0.000E+00 8.810E+03 0.000E+00 8.520E+02 MN-56 0.000E+00 1.810E-01 0.000E+00 2.300E-01 0.000E+00 1.190E+01 0.000E+00 3.230E-02 FE-55 6.890E+02 4.880E+02 0.000E+00 0.000E+00 3.100E+02 2.110E+02 0.000E+00 1.140E+02 FE-59 1.050E+03 2.460E+03 0.000E+00 0.000E+00 7.760E+02 5.820E+03 0.000E+00 9.500E+02 CO-58 0.000E+00 8.780E+01 0.000E+00 0.000E+00 0.000E+00 1.210E+03 0.000E+00 2.020E+02 CO-60 0.000E+00 2.560E+02 0.000E+00 0.000E+00 0.000E+00 3.340E+03 0.000E+00 5.770E+02 NI-63 3.230E+04 2.280E+03 0.000E+00 0.000E+00 0.000E+00 3.630E+02 0.000E+00 1.090E+03 NI-65 1.860E-01 2.370E-02 0.000E+00 0.000E+00 0.000E+00 1.290E+00 0.000E+00 1.080E-02 CU-64 0.000E+00 2.820E+00 0.000E+00 7.140E+00 0.000E+00 2.190E+02 0.000E+00 1.330E+00 ZN-65 2.100E+04 7.280E+04 0.000E+00 4.660E+04 0.000E+00 3.080E+04 0.000E+00 3.390E+04 ZN-69 8.410E-07 1.600E-06 0.000E+00 1.050E-06 0.000E+00 2.950E-06 0.000E+00 1.120E-07 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.160E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.320E-12 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.050E+05 0.000E+00 0.000E+00 0.000E+00 1.550E+04 0.000E+00 4.920E+04 RB-88 0.000E+00 1.380E-22 0.000E+00 0.000E+00 0.000E+00 1.180E-29 0.000E+00 7.360E-23 RB-89 0.000E+00 1.720E-26 0.000E+00 0.000E+00 0.000E+00 2.630E-35 0.000E+00 1.220E-26 SR-89 2.370E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.830E+03 0.000E+00 6.800E+02 SR-90 4.540E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.270E+04 0.000E+00 1.120E+05 SR-91 7.640E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.470E+02 0.000E+00 3.040E+00 Appendix D Ai Teen Fish - Page 1 of 3 Page 9-101

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 3.590E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.130E+00 0.000E+00 1.530E-02 Y-90 4.820E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.980E+03 0.000E+00 1.300E-02 Y-91 9.060E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.710E+03 0.000E+00 2.430E-01 Y-91M 1.160E-11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.470E-10 0.000E+00 4.430E-13 Y-92 5.020E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.380E+01 0.000E+00 1.450E-05 Y-93 3.350E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.020E+03 0.000E+00 9.190E-04 ZR-95 2.450E-01 7.740E-02 0.000E+00 1.140E-01 0.000E+00 1.790E+02 0.000E+00 5.320E-02 ZR-97 5.330E-03 1.050E-03 0.000E+00 1.600E-03 0.000E+00 2.850E+02 0.000E+00 4.860E-04 NB-95 4.410E+02 2.450E+02 0.000E+00 2.370E+02 0.000E+00 1.050E+06 0.000E+00 1.350E+02 MO-99 0.000E+00 8.550E+01 0.000E+00 1.960E+02 0.000E+00 1.530E+02 0.000E+00 1.630E+01 TC-99M 5.720E-04 1.600E-03 0.000E+00 2.380E-02 8.860E-04 1.050E+00 0.000E+00 2.070E-02 TC-101 2.820E-33 4.010E-33 0.000E+00 7.240E-32 2.440E-33 6.840E-40 0.000E+00 3.930E-32 RU-103 4.570E+00 0.000E+00 0.000E+00 1.610E+01 0.000E+00 3.820E+02 0.000E+00 1.950E+00 RU-105 9.350E-03 0.000E+00 0.000E+00 1.180E-01 0.000E+00 7.550E+00 0.000E+00 3.630E-03 RU-106 7.140E+01 0.000E+00 0.000E+00 1.380E+02 0.000E+00 3.420E+03 0.000E+00 8.990E+00 AG-110M 8.580E-01 8.120E-01 0.000E+00 1.550E+00 0.000E+00 2.280E+02 0.000E+00 4.940E-01 TE-125M 2.760E+03 9.950E+02 7.710E+02 0.000E+00 0.000E+00 8.150E+03 0.000E+00 3.690E+02 TE-127 1.960E+01 6.950E+00 1.350E+01 7.940E+01 0.000E+00 1.510E+03 0.000E+00 4.220E+00 TE-127M 7.010E+03 2.490E+03 1.670E+03 2.840E+04 0.000E+00 1.750E+04 0.000E+00 8.340E+02 TE-129 1.770E-05 6.600E-06 1.260E-05 7.430E-05 0.000E+00 9.680E-05 0.000E+00 4.310E-06 TE-129M 1.160E+04 4.320E+03 3.760E+03 4.870E+04 0.000E+00 4.370E+04 0.000E+00 1.840E+03 TE-131 9.400E-17 3.870E-17 7.240E-17 4.110E-16 0.000E+00 7.710E-18 0.000E+00 2.940E-17 TE-131M 1.020E+03 4.900E+02 7.370E+02 5.110E+03 0.000E+00 3.930E+04 0.000E+00 4.090E+02 TE-132 2.060E+03 1.300E+03 1.370E+03 1.250E+04 0.000E+00 4.130E+04 0.000E+00 1.230E+03 I-130 7.320E+00 2.120E+01 1.730E+03 3.260E+01 0.000E+00 1.630E+01 0.000E+00 8.460E+00 Appendix D Ai Teen Fish - Page 2 of 3 Page 9-102

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.470E+02 2.060E+02 6.000E+04 3.540E+02 0.000E+00 4.070E+01 0.000E+00 1.100E+02 I-132 5.520E-03 1.440E-02 4.870E-01 2.280E-02 0.000E+00 6.290E-03 0.000E+00 5.180E-03 I-133 2.470E+01 4.190E+01 5.850E+03 7.350E+01 0.000E+00 3.170E+01 0.000E+00 1.280E+01 I-134 2.220E-08 5.890E-08 9.810E-07 9.280E-08 0.000E+00 7.760E-10 0.000E+00 2.110E-08 I-135 1.350E+00 3.480E+00 2.240E+02 5.490E+00 0.000E+00 3.850E+00 0.000E+00 1.290E+00 CS-134 3.050E+05 7.180E+05 0.000E+00 2.280E+05 8.710E+04 8.930E+03 0.000E+00 3.330E+05 CS-136 2.970E+04 1.170E+05 0.000E+00 6.370E+04 1.000E+04 9.410E+03 0.000E+00 7.860E+04 CS-137 4.090E+05 5.440E+05 0.000E+00 1.850E+05 7.190E+04 7.730E+03 0.000E+00 1.890E+05 CS-138 9.580E-12 1.840E-11 0.000E+00 1.360E-11 1.580E-12 8.340E-15 0.000E+00 9.190E-12 BA-139 6.170E-06 4.340E-09 0.000E+00 4.090E-09 2.990E-09 5.510E-05 0.000E+00 1.800E-07 BA-140 1.960E+02 2.410E-01 0.000E+00 8.160E-02 1.620E-01 3.030E+02 0.000E+00 1.260E+01 BA-141 9.450E-25 7.050E-28 0.000E+00 6.550E-28 4.830E-28 2.010E-30 0.000E+00 3.150E-26 BA-142 2.750E-42 2.750E-45 0.000E+00 2.320E-45 1.830E-45 8.430E-54 0.000E+00 1.690E-43 LA-140 1.050E-01 5.160E-02 0.000E+00 0.000E+00 0.000E+00 2.960E+03 0.000E+00 1.370E-02 LA-142 2.350E-07 1.040E-07 0.000E+00 0.000E+00 0.000E+00 3.180E-03 0.000E+00 2.600E-08 CE-141 2.370E-02 1.590E-02 0.000E+00 7.460E-03 0.000E+00 4.540E+01 0.000E+00 1.820E-03 CE-143 2.590E-03 1.880E+00 0.000E+00 8.450E-04 0.000E+00 5.660E+01 0.000E+00 2.100E-04 CE-144 1.270E+00 5.240E-01 0.000E+00 3.130E-01 0.000E+00 3.180E+02 0.000E+00 6.810E-02 PR-143 5.680E-01 2.270E-01 0.000E+00 1.320E-01 0.000E+00 1.870E+03 0.000E+00 2.830E-02 PR-144 1.690E-28 6.900E-29 0.000E+00 3.960E-29 0.000E+00 1.860E-31 0.000E+00 8.550E-30 ND-147 4.020E-01 4.370E-01 0.000E+00 2.560E-01 0.000E+00 1.580E+03 0.000E+00 2.620E-02 W-187 1.590E+02 1.300E+02 0.000E+00 0.000E+00 0.000E+00 3.510E+04 0.000E+00 4.540E+01 NP-239 2.390E-02 2.260E-03 0.000E+00 7.080E-03 0.000E+00 3.630E+02 0.000E+00 1.250E-03 Appendix D Ai Teen Fish - Page 3 of 3 Page 9-103

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 3.580E+00 3.580E+00 3.580E+00 3.580E+00 3.580E+00 3.580E+00 4.150E+00 3.580E+00 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 1.400E+00 1.400E+00 1.400E+00 1.400E+00 1.400E+00 1.400E+00 1.650E+00 1.400E+00 MN-54 4.150E+02 4.150E+02 4.150E+02 4.150E+02 4.150E+02 4.150E+02 4.870E+02 4.150E+02 MN-56 2.700E-01 2.700E-01 2.700E-01 2.700E-01 2.700E-01 2.700E-01 3.200E-01 2.700E-01 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 8.180E+01 8.180E+01 8.180E+01 8.180E+01 8.180E+01 8.180E+01 9.610E+01 8.180E+01 CO-58 1.140E+02 1.140E+02 1.140E+02 1.140E+02 1.140E+02 1.140E+02 1.330E+02 1.140E+02 CO-60 6.440E+03 6.440E+03 6.440E+03 6.440E+03 6.440E+03 6.440E+03 7.580E+03 6.440E+03 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 8.900E-02 8.900E-02 8.900E-02 8.900E-02 8.900E-02 8.900E-02 1.030E-01 8.900E-02 CU-64 1.820E-01 1.820E-01 1.820E-01 1.820E-01 1.820E-01 1.820E-01 2.060E-01 1.820E-01 ZN-65 2.240E+02 2.240E+02 2.240E+02 2.240E+02 2.240E+02 2.240E+02 2.580E+02 2.240E+02 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 1.460E-03 1.460E-03 1.460E-03 1.460E-03 1.460E-03 1.460E-03 2.120E-03 1.460E-03 BR-84 6.070E-02 6.070E-02 6.070E-02 6.070E-02 6.070E-02 6.070E-02 7.080E-02 6.070E-02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 2.690E+00 2.690E+00 2.690E+00 2.690E+00 2.690E+00 2.690E+00 3.080E+00 2.690E+00 RB-88 9.910E-03 9.910E-03 9.910E-03 9.910E-03 9.910E-03 9.910E-03 1.130E-02 9.910E-03 RB-89 3.680E-02 3.680E-02 3.680E-02 3.680E-02 3.680E-02 3.680E-02 4.420E-02 3.680E-02 SR-89 6.490E-03 6.490E-03 6.490E-03 6.490E-03 6.490E-03 6.490E-03 7.530E-03 6.490E-03 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 6.440E-01 6.440E-01 6.440E-01 6.440E-01 6.440E-01 6.440E-01 7.530E-01 6.440E-01 Appendix D Ai Teen Shoreline Sediment - Page 1 of 3 Page 9-104

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 2.330E-01 2.330E-01 2.330E-01 2.330E-01 2.330E-01 2.330E-01 2.590E-01 2.330E-01 Y-90 1.350E-03 1.350E-03 1.350E-03 1.350E-03 1.350E-03 1.350E-03 1.590E-03 1.350E-03 Y-91 3.220E-01 3.220E-01 3.220E-01 3.220E-01 3.220E-01 3.220E-01 3.620E-01 3.220E-01 Y-91M 3.010E-02 3.010E-02 3.010E-02 3.010E-02 3.010E-02 3.010E-02 3.480E-02 3.010E-02 Y-92 5.410E-02 5.410E-02 5.410E-02 5.410E-02 5.410E-02 5.410E-02 6.420E-02 5.410E-02 Y-93 5.500E-02 5.500E-02 5.500E-02 5.500E-02 5.500E-02 5.500E-02 7.520E-02 5.500E-02 ZR-95 7.330E+01 7.330E+01 7.330E+01 7.330E+01 7.330E+01 7.330E+01 8.510E+01 7.330E+01 ZR-97 8.870E-01 8.870E-01 8.870E-01 8.870E-01 8.870E-01 8.870E-01 1.030E+00 8.870E-01 NB-95 4.100E+01 4.100E+01 4.100E+01 4.100E+01 4.100E+01 4.100E+01 4.820E+01 4.100E+01 MO-99 1.200E+00 1.200E+00 1.200E+00 1.200E+00 1.200E+00 1.200E+00 1.390E+00 1.200E+00 TC-99M 5.520E-02 5.520E-02 5.520E-02 5.520E-02 5.520E-02 5.520E-02 6.320E-02 5.520E-02 TC-101 6.100E-03 6.100E-03 6.100E-03 6.100E-03 6.100E-03 6.100E-03 6.780E-03 6.100E-03 RU-103 3.250E+01 3.250E+01 3.250E+01 3.250E+01 3.250E+01 3.250E+01 3.790E+01 3.250E+01 RU-105 1.910E-01 1.910E-01 1.910E-01 1.910E-01 1.910E-01 1.910E-01 2.160E-01 1.910E-01 RU-106 1.270E+02 1.270E+02 1.270E+02 1.270E+02 1.270E+02 1.270E+02 1.520E+02 1.270E+02 AG-110M 1.030E+03 1.030E+03 1.030E+03 1.030E+03 1.030E+03 1.030E+03 1.200E+03 1.030E+03 TE-125M 4.650E-01 4.650E-01 4.650E-01 4.650E-01 4.650E-01 4.650E-01 6.380E-01 4.650E-01 TE-127 8.920E-04 8.920E-04 8.920E-04 8.920E-04 8.920E-04 8.920E-04 9.820E-04 8.920E-04 TE-127M 2.750E-02 2.750E-02 2.750E-02 2.750E-02 2.750E-02 2.750E-02 3.250E-02 2.750E-02 TE-129 7.860E-03 7.860E-03 7.860E-03 7.860E-03 7.860E-03 7.860E-03 9.300E-03 7.860E-03 TE-129M 5.930E+00 5.930E+00 5.930E+00 5.930E+00 5.930E+00 5.930E+00 6.930E+00 5.930E+00 TE-131 8.750E-03 8.750E-03 8.750E-03 8.750E-03 8.750E-03 8.750E-03 1.030E+01 8.750E-03 TE-131M 2.410E+00 2.410E+00 2.410E+00 2.410E+00 2.410E+00 2.410E+00 2.840E+00 2.410E+00 TE-132 1.270E+00 1.270E+00 1.270E+00 1.270E+00 1.270E+00 1.270E+00 1.490E+00 1.270E+00 I-130 1.650E+00 1.650E+00 1.650E+00 1.650E+00 1.650E+00 1.650E+00 2.010E+00 1.650E+00 Appendix D Ai Teen Shoreline Sediment - Page 2 of 3 Page 9-105

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 5.160E+00 5.160E+00 5.160E+00 5.160E+00 5.160E+00 5.160E+00 6.260E+00 5.160E+00 I-132 3.730E-01 3.730E-01 3.730E-01 3.730E-01 3.730E-01 3.730E-01 4.390E-01 3.730E-01 I-133 7.350E-01 7.350E-01 7.350E-01 7.350E-01 7.350E-01 7.350E-01 8.930E-01 7.350E-01 I-134 1.340E-01 1.340E-01 1.340E-01 1.340E-01 1.340E-01 1.340E-01 1.590E-01 1.340E-01 I-135 7.570E-01 7.570E-01 7.570E-01 7.570E-01 7.570E-01 7.570E-01 8.830E-01 7.570E-01 CS-134 2.060E+03 2.060E+03 2.060E+03 2.060E+03 2.060E+03 2.060E+03 2.400E+03 2.060E+03 CS-136 4.520E+01 4.520E+01 4.520E+01 4.520E+01 4.520E+01 4.520E+01 5.130E+01 4.520E+01 CS-137 3.080E+03 3.080E+03 3.080E+03 3.080E+03 3.080E+03 3.080E+03 3.590E+03 3.080E+03 CS-138 1.080E-01 1.080E-01 1.080E-01 1.080E-01 1.080E-01 1.080E-01 1.230E-01 1.080E-01 BA-139 3.170E-02 3.170E-02 3.170E-02 3.170E-02 3.170E-02 3.170E-02 3.570E-02 3.170E-02 BA-140 6.150E+00 6.150E+00 6.150E+00 6.150E+00 6.150E+00 6.150E+00 7.030E+00 6.150E+00 BA-141 1.250E-02 1.250E-02 1.250E-02 1.250E-02 1.250E-02 1.250E-02 1.420E-02 1.250E-02 BA-142 1.340E-02 1.340E-02 1.340E-02 1.340E-02 1.340E-02 1.340E-02 1.530E-02 1.340E-02 LA-140 5.760E+00 5.760E+00 5.760E+00 5.760E+00 5.760E+00 5.760E+00 6.530E+00 5.760E+00 LA-142 2.280E-01 2.280E-01 2.280E-01 2.280E-01 2.280E-01 2.280E-01 2.730E-01 2.280E-01 CE-141 4.090E+00 4.090E+00 4.090E+00 4.090E+00 4.090E+00 4.090E+00 4.620E+00 4.090E+00 CE-143 6.930E-01 6.930E-01 6.930E-01 6.930E-01 6.930E-01 6.930E-01 7.870E-01 6.930E-01 CE-144 2.080E+01 2.080E+01 2.080E+01 2.080E+01 2.080E+01 2.080E+01 2.410E+01 2.080E+01 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 5.500E-04 5.500E-04 5.500E-04 5.500E-04 5.500E-04 5.500E-04 6.320E-04 5.500E-04 ND-147 2.520E+00 2.520E+00 2.520E+00 2.520E+00 2.520E+00 2.520E+00 3.020E+00 2.520E+00 W-187 7.050E-01 7.050E-01 7.050E-01 7.050E-01 7.050E-01 7.050E-01 8.190E-01 7.050E-01 NP-239 5.130E-01 5.130E-01 5.130E-01 5.130E-01 5.130E-01 5.130E-01 5.930E-01 5.130E-01 Appendix D Ai Teen Shoreline Sediment - Page 3 of 3 Page 9-106

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.180E+01 1.180E+01 1.180E+01 1.180E+01 1.180E+01 0.000E+00 1.180E+01 C-14 7.030E+02 1.410E+02 1.410E+02 1.410E+02 1.410E+02 1.410E+02 0.000E+00 1.410E+02 NA-24 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 0.000E+00 1.940E+02 P-32 4.680E+04 2.190E+03 0.000E+00 0.000E+00 0.000E+00 1.290E+03 0.000E+00 1.800E+03 CR-51 0.000E+00 0.000E+00 2.840E-01 7.750E-02 5.180E-01 2.710E+01 0.000E+00 5.110E-01 MN-54 0.000E+00 6.210E+02 0.000E+00 1.740E+02 0.000E+00 5.220E+02 0.000E+00 1.660E+02 MN-56 0.000E+00 7.700E-01 0.000E+00 9.320E-01 0.000E+00 1.120E+02 0.000E+00 1.740E-01 FE-55 6.680E+02 3.550E+02 0.000E+00 0.000E+00 2.010E+02 6.570E+01 0.000E+00 1.100E+02 FE-59 9.520E+02 1.540E+03 0.000E+00 0.000E+00 4.470E+02 1.600E+03 0.000E+00 7.670E+02 CO-58 0.000E+00 1.040E+02 0.000E+00 0.000E+00 0.000E+00 6.070E+02 0.000E+00 3.190E+02 CO-60 0.000E+00 3.080E+02 0.000E+00 0.000E+00 0.000E+00 1.700E+03 0.000E+00 9.070E+02 NI-63 3.130E+04 1.670E+03 0.000E+00 0.000E+00 0.000E+00 1.130E+02 0.000E+00 1.060E+03 NI-65 4.760E+00 4.480E-01 0.000E+00 0.000E+00 0.000E+00 5.490E+01 0.000E+00 2.610E-01 CU-64 0.000E+00 7.390E+00 0.000E+00 1.780E+01 0.000E+00 3.470E+02 0.000E+00 4.460E+00 ZN-65 7.950E+02 2.120E+03 0.000E+00 1.340E+03 0.000E+00 3.720E+02 0.000E+00 1.320E+03 ZN-69 3.190E-04 4.610E-04 0.000E+00 2.800E-04 0.000E+00 2.900E-02 0.000E+00 4.260E-05 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.060E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.780E-06 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.300E-76 RB-86 0.000E+00 3.820E+03 0.000E+00 0.000E+00 0.000E+00 2.460E+02 0.000E+00 2.350E+03 RB-88 0.000E+00 7.360E-12 0.000E+00 0.000E+00 0.000E+00 3.610E-13 0.000E+00 5.110E-12 RB-89 0.000E+00 6.300E-14 0.000E+00 0.000E+00 0.000E+00 5.490E-16 0.000E+00 5.600E-14 SR-89 7.620E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.950E+03 0.000E+00 2.180E+03 SR-90 9.880E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.330E+04 0.000E+00 2.510E+05 SR-91 5.810E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.280E+03 0.000E+00 2.190E+01 Appendix E Ai Child Water - Page 1 of 3 Page 9-107

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 2.430E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.610E+02 0.000E+00 9.760E-01 Y-90 2.100E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.980E+03 0.000E+00 5.620E-02 Y-91 3.480E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.640E+03 0.000E+00 9.310E-01 Y-91M 9.860E-07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.930E-03 0.000E+00 3.590E-08 Y-92 2.000E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.770E+02 0.000E+00 5.710E-04 Y-93 2.900E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.330E+03 0.000E+00 7.970E-03 ZR-95 6.710E+00 1.470E+00 0.000E+00 2.110E+00 0.000E+00 1.540E+03 0.000E+00 1.310E+00 ZR-97 2.480E-01 3.590E-02 0.000E+00 5.150E-02 0.000E+00 5.440E+03 0.000E+00 2.120E-02 NB-95 1.300E+00 5.040E-01 0.000E+00 4.740E-01 0.000E+00 9.330E+02 0.000E+00 3.600E-01 MO-99 0.000E+00 6.820E+02 0.000E+00 1.460E+03 0.000E+00 5.640E+02 0.000E+00 1.690E+02 TC-99M 1.350E-02 2.640E-02 0.000E+00 3.840E-01 1.340E-02 1.500E+01 0.000E+00 4.380E-01 TC-101 3.330E-17 3.480E-17 0.000E+00 5.940E-16 1.840E-17 1.110E-16 0.000E+00 4.410E-16 RU-103 4.210E+01 0.000E+00 0.000E+00 1.060E+02 0.000E+00 1.090E+03 0.000E+00 1.620E+01 RU-105 5.750E-01 0.000E+00 0.000E+00 5.060E+00 0.000E+00 3.750E+02 0.000E+00 2.090E-01 RU-106 6.800E+02 0.000E+00 0.000E+00 9.180E+02 0.000E+00 1.060E+04 0.000E+00 8.480E+01 AG-110M 3.130E+01 2.110E+01 0.000E+00 3.940E+01 0.000E+00 2.510E+03 0.000E+00 1.690E+01 TE-125M 6.590E+02 1.790E+02 1.850E+02 0.000E+00 0.000E+00 6.360E+02 0.000E+00 8.780E+01 TE-127 1.130E+01 3.050E+00 7.820E+00 3.210E+01 0.000E+00 4.410E+02 0.000E+00 2.420E+00 TE-127M 1.670E+03 4.510E+02 4.000E+02 4.780E+03 0.000E+00 1.360E+03 0.000E+00 1.990E+02 TE-129 5.730E-03 1.600E-03 4.090E-03 1.680E-02 0.000E+00 3.570E-01 0.000E+00 1.360E-03 TE-129M 2.800E+03 7.830E+02 9.030E+02 8.230E+03 0.000E+00 3.420E+03 0.000E+00 4.350E+02 TE-131 1.040E-08 3.160E-09 7.930E-09 3.140E-08 0.000E+00 5.450E-08 0.000E+00 3.090E-09 TE-131M 3.170E+02 1.100E+02 2.260E+02 1.060E+03 0.000E+00 4.450E+03 0.000E+00 1.170E+02 TE-132 5.280E+02 2.340E+02 3.400E+02 2.170E+03 0.000E+00 2.350E+03 0.000E+00 2.820E+02 I-130 8.650E+01 1.750E+02 1.930E+04 2.610E+02 0.000E+00 8.180E+01 0.000E+00 9.010E+01 Appendix E Ai Child Water - Page 2 of 3 Page 9-108

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 9.580E+02 9.630E+02 3.190E+05 1.580E+03 0.000E+00 8.580E+01 0.000E+00 5.470E+02 I-132 1.250E+00 2.300E+00 1.070E+02 3.520E+00 0.000E+00 2.710E+00 0.000E+00 1.060E+00 I-133 2.310E+02 2.850E+02 5.300E+04 4.750E+02 0.000E+00 1.150E+02 0.000E+00 1.080E+02 I-134 1.820E-03 3.370E-03 7.760E-02 5.160E-03 0.000E+00 2.240E-03 0.000E+00 1.550E-03 I-135 2.890E+01 5.210E+01 4.610E+03 7.990E+01 0.000E+00 3.970E+01 0.000E+00 2.460E+01 CS-134 1.360E+04 2.230E+04 0.000E+00 6.920E+03 2.480E+03 1.200E+02 0.000E+00 4.710E+03 CS-136 1.330E+03 3.660E+03 0.000E+00 1.950E+03 2.910E+02 1.290E+02 0.000E+00 2.370E+03 CS-137 1.900E+04 1.820E+04 0.000E+00 5.930E+03 2.130E+03 1.140E+02 0.000E+00 2.690E+03 CS-138 2.440E-06 3.390E-06 0.000E+00 2.380E-06 2.570E-07 1.560E-06 0.000E+00 2.150E-06 BA-139 5.940E-02 3.170E-05 0.000E+00 2.770E-05 1.860E-05 3.430E+00 0.000E+00 1.720E-03 BA-140 4.700E+03 4.120E+00 0.000E+00 1.340E+00 2.460E+00 2.380E+03 0.000E+00 2.740E+02 BA-141 1.620E-11 9.050E-15 0.000E+00 7.830E-15 5.310E-14 9.210E-12 0.000E+00 5.260E-13 BA-142 1.800E-20 1.300E-23 0.000E+00 1.050E-23 7.630E-24 2.350E-22 0.000E+00 1.010E-21 LA-140 4.780E-01 1.670E-01 0.000E+00 0.000E+00 0.000E+00 4.650E+03 0.000E+00 5.630E-02 LA-142 1.640E-04 5.210E-05 0.000E+00 0.000E+00 0.000E+00 1.030E+01 0.000E+00 1.630E-05 CE-141 2.280E+00 1.140E+00 0.000E+00 4.990E-01 0.000E+00 1.420E+03 0.000E+00 1.690E-01 CE-143 3.160E-01 1.710E+02 0.000E+00 7.180E-02 0.000E+00 2.510E+03 0.000E+00 2.480E-02 CE-144 1.210E+02 3.790E+01 0.000E+00 2.100E+01 0.000E+00 9.870E+03 0.000E+00 6.450E+00 PR-143 2.230E+00 6.690E-01 0.000E+00 3.620E-01 0.000E+00 2.400E+03 0.000E+00 1.110E-01 PR-144 2.200E-15 6.800E-16 0.000E+00 3.600E-16 0.000E+00 1.460E-12 0.000E+00 1.110E-16 ND-147 1.570E+00 1.270E+00 0.000E+00 6.990E-01 0.000E+00 2.020E+03 0.000E+00 9.860E-02 W-187 1.760E+01 1.040E+01 0.000E+00 0.000E+00 0.000E+00 1.460E+03 0.000E+00 4.680E+00 NP-239 2.630E-01 1.890E-02 0.000E+00 5.470E-02 0.000E+00 1.400E+03 0.000E+00 1.330E-02 Appendix E Ai Child Water - Page 3 of 3 Page 9-109

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.440E-01 1.440E-01 1.440E-01 1.440E-01 1.440E-01 0.000E+00 1.440E-01 C-14 4.380E+04 8.760E+03 8.760E+03 8.760E+03 8.760E+03 8.760E+03 0.000E+00 8.760E+03 NA-24 1.510E+02 1.510E+02 1.510E+02 1.510E+02 1.510E+02 1.510E+02 0.000E+00 1.510E+02 P-32 1.850E+06 8.680E+04 0.000E+00 0.000E+00 0.000E+00 5.130E+04 0.000E+00 7.150E+04 CR-51 0.000E+00 0.000E+00 7.580E-01 2.070E-01 1.380E+00 7.240E+01 0.000E+00 1.370E+00 MN-54 0.000E+00 3.360E+03 0.000E+00 9.420E+02 0.000E+00 2.820E+03 0.000E+00 8.950E+02 MN-56 0.000E+00 1.650E-01 0.000E+00 2.000E-01 0.000E+00 2.400E+01 0.000E+00 3.730E-02 FE-55 9.040E+02 4.790E+02 0.000E+00 0.000E+00 2.710E+02 8.880E+01 0.000E+00 1.490E+02 FE-59 1.280E+03 2.070E+03 0.000E+00 0.000E+00 5.990E+02 2.150E+03 0.000E+00 1.030E+03 CO-58 0.000E+00 7.010E+01 0.000E+00 0.000E+00 0.000E+00 4.090E+02 0.000E+00 2.150E+02 CO-60 0.000E+00 2.080E+02 0.000E+00 0.000E+00 0.000E+00 1.150E+03 0.000E+00 6.130E+02 NI-63 4.230E+04 2.270E+03 0.000E+00 0.000E+00 0.000E+00 1.530E+02 0.000E+00 1.440E+03 NI-65 2.370E-01 2.230E-02 0.000E+00 0.000E+00 0.000E+00 2.740E+00 0.000E+00 1.300E-02 CU-64 0.000E+00 2.590E+00 0.000E+00 6.260E+00 0.000E+00 1.220E+02 0.000E+00 1.570E+00 ZN-65 2.150E+04 5.730E+04 0.000E+00 3.610E+04 0.000E+00 1.010E+04 0.000E+00 3.560E+04 ZN-69 1.080E-06 1.560E-06 0.000E+00 9.470E-07 0.000E+00 9.840E-05 0.000E+00 1.440E-07 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.340E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.570E-12 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.020E+05 0.000E+00 0.000E+00 0.000E+00 6.530E+03 0.000E+00 6.250E+04 RB-88 0.000E+00 1.330E-22 0.000E+00 0.000E+00 0.000E+00 6.510E-24 0.000E+00 9.220E-23 RB-89 0.000E+00 1.580E-26 0.000E+00 0.000E+00 0.000E+00 1.370E-28 0.000E+00 1.400E-26 SR-89 3.070E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.190E+03 0.000E+00 8.780E+02 SR-90 4.010E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.400E+03 0.000E+00 1.020E+05 SR-91 9.800E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.160E+02 0.000E+00 3.700E+00 Appendix E Ai Child Fish - Page 1 of 3 Page 9-110

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.580E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.670E+00 0.000E+00 1.840E-02 Y-90 6.240E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.780E+03 0.000E+00 1.670E-02 Y-91 1.170E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.560E+03 0.000E+00 3.130E-01 Y-91M 1.480E-11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.900E-08 0.000E+00 5.390E-13 Y-92 6.440E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.860E+01 0.000E+00 1.840E-05 Y-93 4.300E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.420E+02 0.000E+00 1.180E-03 ZR-95 2.980E-01 6.550E-02 0.000E+00 9.370E-02 0.000E+00 6.830E+01 0.000E+00 5.830E-02 ZR-97 6.780E-03 9.790E-04 0.000E+00 1.410E-03 0.000E+00 1.480E+02 0.000E+00 5.780E-04 NB-95 5.210E+02 2.030E+02 0.000E+00 1.900E+02 0.000E+00 3.750E+05 0.000E+00 1.450E+02 MO-99 0.000E+00 8.130E+01 0.000E+00 1.740E+02 0.000E+00 6.720E+01 0.000E+00 2.010E+01 TC-99M 6.860E-04 1.350E-03 0.000E+00 1.950E-02 6.830E-04 7.650E-01 0.000E+00 2.230E-02 TC-101 3.610E-33 3.780E-33 0.000E+00 6.440E-32 2.000E-33 1.200E-32 0.000E+00 4.790E-32 RU-103 5.650E+00 0.000E+00 0.000E+00 1.420E+01 0.000E+00 1.460E+02 0.000E+00 2.170E+00 RU-105 1.190E-02 0.000E+00 0.000E+00 1.050E-01 0.000E+00 7.790E+00 0.000E+00 4.330E-03 RU-106 9.190E+01 0.000E+00 0.000E+00 1.240E+02 0.000E+00 1.430E+03 0.000E+00 1.150E+01 AG-110M 9.720E-01 6.570E-01 0.000E+00 1.220E+00 0.000E+00 7.810E+01 0.000E+00 5.250E-01 TE-125M 3.540E+03 9.610E+02 9.950E+02 0.000E+00 0.000E+00 3.420E+03 0.000E+00 4.730E+02 TE-127 2.520E+01 6.800E+00 1.750E+01 7.170E+01 0.000E+00 9.850E+02 0.000E+00 5.410E+00 TE-127M 9.040E+03 2.430E+03 2.160E+03 2.580E+04 0.000E+00 7.320E+03 0.000E+00 1.070E+03 TE-129 2.280E-05 6.370E-06 1.630E-05 6.680E-05 0.000E+00 1.420E-03 0.000E+00 5.420E-06 TE-129M 1.500E+04 4.190E+03 4.840E+03 4.410E+04 0.000E+00 1.830E+04 0.000E+00 2.330E+03 TE-131 1.210E-16 3.680E-17 9.220E-17 3.650E-16 0.000E+00 6.330E-16 0.000E+00 3.590E-17 TE-131M 1.300E+03 4.500E+02 9.250E+02 4.350E+03 0.000E+00 1.820E+04 0.000E+00 4.790E+02 TE-132 2.570E+03 1.140E+03 1.650E+03 1.050E+04 0.000E+00 1.140E+04 0.000E+00 1.370E+03 I-130 8.950E+00 1.810E+01 1.990E+03 2.700E+01 0.000E+00 8.460E+00 0.000E+00 9.320E+00 Appendix E Ai Child Fish - Page 2 of 3 Page 9-111

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.860E+02 1.870E+02 6.190E+04 3.070E+02 0.000E+00 1.670E+01 0.000E+00 1.060E+02 I-132 6.830E-03 1.250E-02 5.820E-01 1.920E-02 0.000E+00 1.480E-02 0.000E+00 5.770E-03 I-133 3.140E+01 3.880E+01 7.210E+03 6.470E+01 0.000E+00 1.560E+01 0.000E+00 1.470E+01 I-134 2.750E-08 5.100E-08 1.170E-06 7.800E-08 0.000E+00 3.380E-08 0.000E+00 2.350E-08 I-135 1.670E+00 3.010E+00 2.660E+02 4.610E+00 0.000E+00 2.290E+00 0.000E+00 1.420E+00 CS-134 3.680E+05 6.040E+05 0.000E+00 1.870E+05 6.710E+04 3.250E+03 0.000E+00 1.270E+05 CS-136 3.510E+04 9.640E+04 0.000E+00 5.130E+04 7.660E+03 3.390E+03 0.000E+00 6.240E+04 CS-137 5.140E+05 4.920E+05 0.000E+00 1.600E+05 5.770E+04 3.080E+03 0.000E+00 7.270E+04 CS-138 1.210E-11 1.690E-11 0.000E+00 1.190E-11 1.280E-12 7.770E-12 0.000E+00 1.070E-11 BA-139 7.930E-06 4.230E-09 0.000E+00 3.700E-09 2.490E-09 4.580E-04 0.000E+00 2.300E-07 BA-140 2.480E+02 2.170E-01 0.000E+00 7.060E-02 1.290E-01 1.250E+02 0.000E+00 1.450E+01 BA-141 1.210E-24 6.800E-28 0.000E+00 5.880E-28 3.990E-27 6.920E-25 0.000E+00 3.950E-26 BA-142 3.460E-42 2.490E-45 0.000E+00 2.020E-45 1.470E-45 4.510E-44 0.000E+00 1.930E-43 LA-140 1.310E-01 4.590E-02 0.000E+00 0.000E+00 0.000E+00 1.280E+03 0.000E+00 1.550E-02 LA-142 2.970E-07 9.470E-08 0.000E+00 0.000E+00 0.000E+00 1.880E-02 0.000E+00 2.960E-08 CE-141 3.060E-02 1.520E-02 0.000E+00 6.680E-03 0.000E+00 1.900E+01 0.000E+00 2.260E-03 CE-143 3.320E-03 1.800E+00 0.000E+00 7.550E-04 0.000E+00 2.640E+01 0.000E+00 2.610E-04 CE-144 1.630E+00 5.120E-01 0.000E+00 2.830E-01 0.000E+00 1.330E+02 0.000E+00 8.710E-02 PR-143 7.340E-01 2.200E-01 0.000E+00 1.190E-01 0.000E+00 7.920E+02 0.000E+00 3.640E-02 PR-144 2.180E-28 6.750E-29 0.000E+00 3.570E-29 0.000E+00 1.450E-25 0.000E+00 1.100E-29 ND-147 5.150E-01 4.170E-01 0.000E+00 2.290E-01 0.000E+00 6.610E+02 0.000E+00 3.230E-02 W-187 2.010E+02 1.190E+02 0.000E+00 0.000E+00 0.000E+00 1.680E+04 0.000E+00 5.350E+01 NP-239 3.080E-02 2.210E-03 0.000E+00 6.390E-03 0.000E+00 1.630E+02 0.000E+00 1.550E-03 Appendix E Ai Child Fish - Page 3 of 3 Page 9-112

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 7.480E-01 7.480E-01 7.480E-01 7.480E-01 7.480E-01 7.480E-01 8.680E-01 7.480E-01 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 2.920E-01 2.920E-01 2.920E-01 2.920E-01 2.920E-01 2.920E-01 3.450E-01 2.920E-01 MN-54 8.680E+01 8.680E+01 8.680E+01 8.680E+01 8.680E+01 8.680E+01 1.020E+02 8.680E+01 MN-56 5.650E-02 5.650E-02 5.650E-02 5.650E-02 5.650E-02 5.650E-02 6.680E-02 5.650E-02 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 1.710E+01 1.710E+01 1.710E+01 1.710E+01 1.710E+01 1.710E+01 2.010E+01 1.710E+01 CO-58 2.370E+01 2.370E+01 2.370E+01 2.370E+01 2.370E+01 2.370E+01 2.780E+01 2.370E+01 CO-60 1.350E+03 1.350E+03 1.350E+03 1.350E+03 1.350E+03 1.350E+03 1.580E+03 1.350E+03 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 1.860E-02 1.860E-02 1.860E-02 1.860E-02 1.860E-02 1.860E-02 2.160E-02 1.860E-02 CU-64 3.800E-02 3.800E-02 3.800E-02 3.800E-02 3.800E-02 3.800E-02 4.310E-02 3.800E-02 ZN-65 4.680E+01 4.680E+01 4.680E+01 4.680E+01 4.680E+01 4.680E+01 5.380E+01 4.680E+01 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 3.050E-04 3.050E-04 3.050E-04 3.050E-04 3.050E-04 3.050E-04 4.430E-04 3.050E-04 BR-84 1.270E-02 1.270E-02 1.270E-02 1.270E-02 1.270E-02 1.270E-02 1.480E-02 1.270E-02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 5.630E-01 5.630E-01 5.630E-01 5.630E-01 5.630E-01 5.630E-01 6.430E-01 5.630E-01 RB-88 2.070E-03 2.070E-03 2.070E-03 2.070E-03 2.070E-03 2.070E-03 2.370E-03 2.070E-03 RB-89 7.700E-03 7.700E-03 7.700E-03 7.700E-03 7.700E-03 7.700E-03 9.240E-03 7.700E-03 SR-89 1.360E-03 1.360E-03 1.360E-03 1.360E-03 1.360E-03 1.360E-03 1.570E-03 1.360E-03 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 1.350E-01 1.350E-01 1.350E-01 1.350E-01 1.350E-01 1.350E-01 1.570E-01 1.350E-01 Appendix E Ai Child Shoreline Sediment - Page 1 of 3 Page 9-113

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.860E-02 4.860E-02 4.860E-02 4.860E-02 4.860E-02 4.860E-02 5.410E-02 4.860E-02 Y-90 2.810E-04 2.810E-04 2.810E-04 2.810E-04 2.810E-04 2.810E-04 3.320E-04 2.810E-04 Y-91 6.720E-02 6.720E-02 6.720E-02 6.720E-02 6.720E-02 6.720E-02 7.560E-02 6.720E-02 Y-91M 6.280E-03 6.280E-03 6.280E-03 6.280E-03 6.280E-03 6.280E-03 7.270E-03 6.280E-03 Y-92 1.130E-02 1.130E-02 1.130E-02 1.130E-02 1.130E-02 1.130E-02 1.340E-02 1.130E-02 Y-93 1.150E-02 1.150E-02 1.150E-02 1.150E-02 1.150E-02 1.150E-02 1.570E-02 1.150E-02 ZR-95 1.530E+01 1.530E+01 1.530E+01 1.530E+01 1.530E+01 1.530E+01 1.780E+01 1.530E+01 ZR-97 1.850E-01 1.850E-01 1.850E-01 1.850E-01 1.850E-01 1.850E-01 2.160E-01 1.850E-01 NB-95 8.560E+00 8.560E+00 8.560E+00 8.560E+00 8.560E+00 8.560E+00 1.010E+01 8.560E+00 MO-99 2.500E-01 2.500E-01 2.500E-01 2.500E-01 2.500E-01 2.500E-01 2.900E-01 2.500E-01 TC-99M 1.150E-02 1.150E-02 1.150E-02 1.150E-02 1.150E-02 1.150E-02 1.320E-02 1.150E-02 TC-101 1.270E-03 1.270E-03 1.270E-03 1.270E-03 1.270E-03 1.270E-03 1.420E-03 1.270E-03 RU-103 6.780E+00 6.780E+00 6.780E+00 6.780E+00 6.780E+00 6.780E+00 7.910E+00 6.780E+00 RU-105 3.990E-02 3.990E-02 3.990E-02 3.990E-02 3.990E-02 3.990E-02 4.520E-02 3.990E-02 RU-106 2.640E+01 2.640E+01 2.640E+01 2.640E+01 2.640E+01 2.640E+01 3.170E+01 2.640E+01 AG-110M 2.150E+02 2.150E+02 2.150E+02 2.150E+02 2.150E+02 2.150E+02 2.510E+02 2.150E+02 TE-125M 9.720E-02 9.720E-02 9.720E-02 9.720E-02 9.720E-02 9.720E-02 1.330E-01 9.720E-02 TE-127 1.860E-04 1.860E-04 1.860E-04 1.860E-04 1.860E-04 1.860E-04 2.050E-04 1.860E-04 TE-127M 5.740E-03 5.740E-03 5.740E-03 5.740E-03 5.740E-03 5.740E-03 6.780E-03 5.740E-03 TE-129 1.640E-03 1.640E-03 1.640E-03 1.640E-03 1.640E-03 1.640E-03 1.940E-03 1.640E-03 TE-129M 1.240E+00 1.240E+00 1.240E+00 1.240E+00 1.240E+00 1.240E+00 1.450E+00 1.240E+00 TE-131 1.830E-03 1.830E-03 1.830E-03 1.830E-03 1.830E-03 1.830E-03 2.160E+00 1.830E-03 TE-131M 5.030E-01 5.030E-01 5.030E-01 5.030E-01 5.030E-01 5.030E-01 5.920E-01 5.030E-01 TE-132 2.650E-01 2.650E-01 2.650E-01 2.650E-01 2.650E-01 2.650E-01 3.120E-01 2.650E-01 I-130 3.450E-01 3.450E-01 3.450E-01 3.450E-01 3.450E-01 3.450E-01 4.190E-01 3.450E-01 Appendix E Ai Child Shoreline Sediment - Page 2 of 3 Page 9-114

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.080E+00 1.080E+00 1.080E+00 1.080E+00 1.080E+00 1.080E+00 1.310E+00 1.080E+00 I-132 7.800E-02 7.800E-02 7.800E-02 7.800E-02 7.800E-02 7.800E-02 9.180E-02 7.800E-02 I-133 1.540E-01 1.540E-01 1.540E-01 1.540E-01 1.540E-01 1.540E-01 1.870E-01 1.540E-01 I-134 2.800E-02 2.800E-02 2.800E-02 2.800E-02 2.800E-02 2.800E-02 3.320E-02 2.800E-02 I-135 1.580E-01 1.580E-01 1.580E-01 1.580E-01 1.580E-01 1.580E-01 1.850E-01 1.580E-01 CS-134 4.300E+02 4.300E+02 4.300E+02 4.300E+02 4.300E+02 4.300E+02 5.010E+02 4.300E+02 CS-136 9.450E+00 9.450E+00 9.450E+00 9.450E+00 9.450E+00 9.450E+00 1.070E+01 9.450E+00 CS-137 6.440E+02 6.440E+02 6.440E+02 6.440E+02 6.440E+02 6.440E+02 7.510E+02 6.440E+02 CS-138 2.250E-02 2.250E-02 2.250E-02 2.250E-02 2.250E-02 2.250E-02 2.570E-02 2.250E-02 BA-139 6.630E-03 6.630E-03 6.630E-03 6.630E-03 6.630E-03 6.630E-03 7.460E-03 6.630E-03 BA-140 1.290E+00 1.290E+00 1.290E+00 1.290E+00 1.290E+00 1.290E+00 1.470E+00 1.290E+00 BA-141 2.610E-03 2.610E-03 2.610E-03 2.610E-03 2.610E-03 2.610E-03 2.980E-03 2.610E-03 BA-142 2.810E-03 2.810E-03 2.810E-03 2.810E-03 2.810E-03 2.810E-03 3.200E-03 2.810E-03 LA-140 1.200E+00 1.200E+00 1.200E+00 1.200E+00 1.200E+00 1.200E+00 1.360E+00 1.200E+00 LA-142 4.760E-02 4.760E-02 4.760E-02 4.760E-02 4.760E-02 4.760E-02 5.710E-02 4.760E-02 CE-141 8.560E-01 8.560E-01 8.560E-01 8.560E-01 8.560E-01 8.560E-01 9.650E-01 8.560E-01 CE-143 1.450E-01 1.450E-01 1.450E-01 1.450E-01 1.450E-01 1.450E-01 1.650E-01 1.450E-01 CE-144 4.350E+00 4.350E+00 4.350E+00 4.350E+00 4.350E+00 4.350E+00 5.040E+00 4.350E+00 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.150E-04 1.150E-04 1.150E-04 1.150E-04 1.150E-04 1.150E-04 1.320E-04 1.150E-04 ND-147 5.260E-01 5.260E-01 5.260E-01 5.260E-01 5.260E-01 5.260E-01 6.310E-01 5.260E-01 W-187 1.470E-01 1.470E-01 1.470E-01 1.470E-01 1.470E-01 1.470E-01 1.710E-01 1.470E-01 NP-239 1.070E-01 1.070E-01 1.070E-01 1.070E-01 1.070E-01 1.070E-01 1.240E-01 1.070E-01 Appendix E Ai Child Shoreline Sediment - Page 3 of 3 Page 9-115

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX F Ai Infant Dose Factors for use in the Liquid Dose Calculations Agegroup: INFANT Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.160E+01 1.160E+01 1.160E+01 1.160E+01 1.160E+01 0.000E+00 1.160E+01 C-14 8.920E+02 1.900E+02 1.900E+02 1.900E+02 1.900E+02 1.900E+02 0.000E+00 1.900E+02 NA-24 2.190E+02 2.190E+02 2.190E+02 2.190E+02 2.190E+02 2.190E+02 0.000E+00 2.190E+02 P-32 6.240E+04 3.670E+03 0.000E+00 0.000E+00 0.000E+00 8.450E+02 0.000E+00 2.420E+03 CR-51 0.000E+00 0.000E+00 3.420E-01 7.470E-02 6.650E-01 1.530E+01 0.000E+00 5.240E-01 MN-54 0.000E+00 7.480E+02 0.000E+00 1.660E+02 0.000E+00 2.750E+02 0.000E+00 1.690E+02 MN-56 0.000E+00 1.220E+00 0.000E+00 1.050E+00 0.000E+00 1.110E+02 0.000E+00 2.100E-01 FE-55 5.230E+02 3.380E+02 0.000E+00 0.000E+00 1.650E+02 4.290E+01 0.000E+00 9.030E+01 FE-59 1.150E+03 2.010E+03 0.000E+00 0.000E+00 5.940E+02 9.590E+02 0.000E+00 7.910E+02 CO-58 0.000E+00 1.350E+02 0.000E+00 0.000E+00 0.000E+00 3.360E+02 0.000E+00 3.360E+02 CO-60 0.000E+00 4.060E+02 0.000E+00 0.000E+00 0.000E+00 9.670E+02 0.000E+00 9.590E+02 NI-63 2.390E+04 1.470E+03 0.000E+00 0.000E+00 0.000E+00 7.340E+01 0.000E+00 8.280E+02 NI-65 6.520E+00 7.380E-01 0.000E+00 0.000E+00 0.000E+00 5.620E+01 0.000E+00 3.360E-01 CU-64 0.000E+00 1.190E+01 0.000E+00 2.010E+01 0.000E+00 2.440E+02 0.000E+00 5.500E+00 ZN-65 6.910E+02 2.370E+03 0.000E+00 1.150E+03 0.000E+00 2.000E+03 0.000E+00 1.090E+03 ZN-69 4.390E-04 7.910E-04 0.000E+00 3.290E-04 0.000E+00 6.450E-02 0.000E+00 5.890E-05 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.200E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.220E-06 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.800E-76 RB-86 0.000E+00 6.280E+03 0.000E+00 0.000E+00 0.000E+00 1.610E+02 0.000E+00 3.100E+03 RB-88 0.000E+00 1.250E-11 0.000E+00 0.000E+00 0.000E+00 1.220E-11 0.000E+00 6.840E-12 RB-89 0.000E+00 9.960E-14 0.000E+00 0.000E+00 0.000E+00 3.390E-14 0.000E+00 6.860E-14 SR-89 9.380E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.930E+03 0.000E+00 2.690E+03 SR-90 6.960E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.690E+03 0.000E+00 1.770E+05 SR-91 7.830E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.270E+02 0.000E+00 2.830E+01 Appendix F Ai Infant Water - Page 1 of 3 Page 9-116

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX F Ai Infant Dose Factors for use in the Liquid Dose Calculations Agegroup: INFANT Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 3.350E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.610E+02 0.000E+00 1.240E+00 Y-90 2.870E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.970E+03 0.000E+00 7.700E-02 Y-91 4.230E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.030E+03 0.000E+00 1.130E+00 Y-91M 1.350E-06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.510E-03 0.000E+00 4.610E-08 Y-92 2.740E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.240E+02 0.000E+00 7.710E-04 Y-93 4.010E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.170E+03 0.000E+00 1.090E-02 ZR-95 7.710E+00 1.880E+00 0.000E+00 2.020E+00 0.000E+00 9.350E+02 0.000E+00 1.330E+00 ZR-97 3.400E-01 5.840E-02 0.000E+00 5.890E-02 0.000E+00 3.720E+03 0.000E+00 2.670E-02 NB-95 1.560E+00 6.440E-01 0.000E+00 4.620E-01 0.000E+00 5.440E+02 0.000E+00 3.720E-01 MO-99 0.000E+00 1.130E+03 0.000E+00 1.680E+03 0.000E+00 3.710E+02 0.000E+00 2.200E+02 TC-99M 1.810E-02 3.740E-02 0.000E+00 4.020E-01 1.950E-02 1.090E+01 0.000E+00 4.820E-01 TC-101 4.570E-17 5.750E-17 0.000E+00 6.840E-16 3.140E-17 9.780E-15 0.000E+00 5.690E-16 RU-103 5.520E+01 0.000E+00 0.000E+00 1.150E+02 0.000E+00 6.710E+02 0.000E+00 1.850E+01 RU-105 7.850E-01 0.000E+00 0.000E+00 5.770E+00 0.000E+00 3.120E+02 0.000E+00 2.640E-01 RU-106 9.060E+02 0.000E+00 0.000E+00 1.070E+03 0.000E+00 6.880E+03 0.000E+00 1.130E+02 AG-110M 3.740E+01 2.730E+01 0.000E+00 3.910E+01 0.000E+00 1.420E+03 0.000E+00 1.810E+01 TE-125M 8.710E+02 2.910E+02 2.930E+02 0.000E+00 0.000E+00 4.150E+02 0.000E+00 1.180E+02 TE-127 1.550E+01 5.200E+00 1.260E+01 3.790E+01 0.000E+00 3.260E+02 0.000E+00 3.340E+00 TE-127M 2.190E+03 7.280E+02 6.340E+02 5.400E+03 0.000E+00 8.850E+02 0.000E+00 2.660E+02 TE-129 7.860E-03 2.710E-03 6.590E-03 1.960E-02 0.000E+00 6.280E-01 0.000E+00 1.840E-03 TE-129M 3.720E+03 1.280E+03 1.430E+03 9.310E+03 0.000E+00 2.220E+03 0.000E+00 5.730E+02 TE-131 1.420E-08 5.250E-09 1.270E-08 3.640E-08 0.000E+00 5.750E-07 0.000E+00 3.990E-09 TE-131M 4.330E+02 1.740E+02 3.540E+02 1.200E+03 0.000E+00 2.940E+03 0.000E+00 1.440E+02 TE-132 7.030E+02 3.480E+02 5.140E+02 2.180E+03 0.000E+00 1.290E+03 0.000E+00 3.250E+02 I-130 1.150E+02 2.530E+02 2.840E+04 2.780E+02 0.000E+00 5.430E+01 0.000E+00 1.020E+02 Appendix F Ai Infant Water - Page 2 of 3 Page 9-117

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX F Ai Infant Dose Factors for use in the Liquid Dose Calculations Agegroup: INFANT Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.290E+03 1.520E+03 5.010E+05 1.780E+03 0.000E+00 5.440E+01 0.000E+00 6.700E+02 I-132 1.680E+00 3.410E+00 1.600E+02 3.800E+00 0.000E+00 2.760E+00 0.000E+00 1.210E+00 I-133 3.150E+02 4.590E+02 8.350E+04 5.400E+02 0.000E+00 7.770E+01 0.000E+00 1.340E+02 I-134 2.440E-03 4.990E-03 1.160E-01 5.580E-03 0.000E+00 5.160E-03 0.000E+00 1.780E-03 I-135 3.900E+01 7.750E+01 6.950E+03 8.640E+01 0.000E+00 2.800E+01 0.000E+00 2.830E+01 CS-134 1.420E+04 2.640E+04 0.000E+00 6.810E+03 2.790E+03 7.180E+01 0.000E+00 2.670E+03 CS-136 1.680E+03 4.950E+03 0.000E+00 1.970E+03 4.030E+02 7.510E+01 0.000E+00 1.850E+03 CS-137 1.960E+04 2.300E+04 0.000E+00 6.170E+03 2.500E+03 7.190E+01 0.000E+00 1.630E+03 CS-138 3.330E-06 5.410E-06 0.000E+00 2.700E-06 4.210E-07 8.650E-06 0.000E+00 2.620E-06 BA-139 8.180E-02 5.420E-05 0.000E+00 3.260E-05 3.290E-05 5.180E+00 0.000E+00 2.370E-03 BA-140 6.260E+03 6.260E+00 0.000E+00 1.490E+00 3.840E+00 1.540E+03 0.000E+00 3.230E+02 BA-141 2.220E-11 1.520E-14 0.000E+00 9.140E-15 9.250E-15 2.710E-10 0.000E+00 7.000E-13 BA-142 2.460E-20 2.040E-23 0.000E+00 1.180E-23 1.240E-23 1.010E-19 0.000E+00 1.210E-21 LA-140 6.460E-01 2.550E-01 0.000E+00 0.000E+00 0.000E+00 2.990E+03 0.000E+00 6.550E-02 LA-142 2.220E-04 8.160E-05 0.000E+00 0.000E+00 0.000E+00 1.390E+01 0.000E+00 1.950E-05 CE-141 2.930E+00 1.790E+00 0.000E+00 5.510E-01 0.000E+00 9.230E+02 0.000E+00 2.100E-01 CE-143 4.330E-01 2.870E+02 0.000E+00 8.360E-02 0.000E+00 1.670E+03 0.000E+00 3.270E-02 CE-144 1.120E+02 4.580E+01 0.000E+00 1.850E+01 0.000E+00 6.430E+03 0.000E+00 6.270E+00 PR-143 2.980E+00 1.110E+00 0.000E+00 4.140E-01 0.000E+00 1.570E+03 0.000E+00 1.480E-01 PR-144 3.020E-15 1.170E-15 0.000E+00 4.240E-16 0.000E+00 5.440E-11 0.000E+00 1.520E-16 ND-147 2.020E+00 2.070E+00 0.000E+00 7.980E-01 0.000E+00 1.310E+03 0.000E+00 1.270E-01 W-187 2.400E+01 1.670E+01 0.000E+00 0.000E+00 0.000E+00 9.790E+02 0.000E+00 5.760E+00 NP-239 3.600E-01 3.220E-02 0.000E+00 6.430E-02 0.000E+00 9.320E+02 0.000E+00 1.820E-02 Appendix F Ai Infant Water - Page 3 of 3 Page 9-118

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 7.630E+02 7.630E+02 7.630E+02 7.630E+02 7.630E+02 0.000E+00 7.630E+02 C-14 2.250E+04 4.500E+03 4.500E+03 4.500E+03 4.500E+03 4.500E+03 0.000E+00 4.500E+03 NA-24 2.440E+06 2.440E+06 2.440E+06 2.440E+06 2.440E+06 2.440E+06 0.000E+00 2.440E+06 P-32 1.710E+10 1.060E+09 0.000E+00 0.000E+00 0.000E+00 1.920E+09 0.000E+00 6.610E+08 CR-51 0.000E+00 0.000E+00 1.710E+04 6.300E+03 3.790E+04 7.190E+06 0.000E+00 2.860E+04 MN-54 0.000E+00 8.410E+06 0.000E+00 2.500E+06 0.000E+00 2.580E+07 0.000E+00 1.610E+06 MN-56 0.000E+00 4.090E-03 0.000E+00 5.190E-03 0.000E+00 1.310E-01 0.000E+00 7.260E-04 FE-55 2.510E+07 1.740E+07 0.000E+00 0.000E+00 9.680E+06 9.950E+06 0.000E+00 4.050E+06 FE-59 2.970E+07 6.980E+07 0.000E+00 0.000E+00 1.950E+07 2.330E+08 0.000E+00 2.680E+07 CO-58 0.000E+00 4.710E+06 0.000E+00 0.000E+00 0.000E+00 9.550E+07 0.000E+00 1.060E+07 CO-60 0.000E+00 1.640E+07 0.000E+00 0.000E+00 0.000E+00 3.080E+08 0.000E+00 3.620E+07 NI-63 6.730E+09 4.660E+08 0.000E+00 0.000E+00 0.000E+00 9.730E+07 0.000E+00 2.260E+08 NI-65 3.700E-01 4.810E-02 0.000E+00 0.000E+00 0.000E+00 1.220E+00 0.000E+00 2.190E-02 CU-64 0.000E+00 2.380E+04 0.000E+00 6.010E+04 0.000E+00 2.030E+06 0.000E+00 1.120E+04 ZN-65 1.370E+09 4.370E+09 0.000E+00 2.920E+09 0.000E+00 2.750E+09 0.000E+00 1.970E+09 ZN-69 2.090E-12 4.000E-12 0.000E+00 2.600E-12 0.000E+00 6.010E-13 0.000E+00 2.780E-13 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.400E-01 0.000E+00 9.720E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.260E-28 0.000E+00 1.610E-23 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.590E+09 0.000E+00 0.000E+00 0.000E+00 5.120E+08 0.000E+00 1.210E+09 RB-88 0.000E+00 2.140E-45 0.000E+00 0.000E+00 0.000E+00 2.960E-56 0.000E+00 1.140E-45 RB-89 0.000E+00 4.330E-53 0.000E+00 0.000E+00 0.000E+00 2.510E-66 0.000E+00 3.040E-53 SR-89 1.450E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.330E+08 0.000E+00 4.160E+07 SR-90 4.680E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.350E+09 0.000E+00 1.150E+10 SR-91 2.890E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.380E+05 0.000E+00 1.170E+03 Appendix G Ri Adult Cow Milk - Page 1 of 3 Page 9-119

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.880E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.680E+00 0.000E+00 2.110E-02 Y-90 7.080E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.510E+05 0.000E+00 1.900E+00 Y-91 8.590E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.730E+06 0.000E+00 2.300E+02 Y-91M 5.980E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.760E-19 0.000E+00 2.320E-21 Y-92 5.580E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.770E-01 0.000E+00 1.630E-06 Y-93 2.230E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.090E+03 0.000E+00 6.170E-03 ZR-95 9.430E+02 3.030E+02 0.000E+00 4.750E+02 0.000E+00 9.590E+05 0.000E+00 2.050E+02 ZR-97 4.330E-01 8.740E-02 0.000E+00 1.320E-01 0.000E+00 2.710E+04 0.000E+00 4.000E-02 NB-95 8.260E+04 4.590E+04 0.000E+00 4.540E+04 0.000E+00 2.790E+08 0.000E+00 2.470E+04 MO-99 0.000E+00 2.480E+07 0.000E+00 5.610E+07 0.000E+00 5.740E+07 0.000E+00 4.710E+06 TC-99M 3.320E+00 9.380E+00 0.000E+00 1.420E+02 4.600E+00 5.550E+03 0.000E+00 1.200E+02 TC-101 2.590E-60 3.740E-60 0.000E+00 6.730E-59 1.910E-60 1.120E-71 0.000E+00 3.670E-59 RU-103 1.020E+03 0.000E+00 0.000E+00 3.890E+03 0.000E+00 1.190E+05 0.000E+00 4.390E+02 RU-105 8.570E-04 0.000E+00 0.000E+00 1.110E-02 0.000E+00 5.240E-01 0.000E+00 3.380E-04 RU-106 2.040E+04 0.000E+00 0.000E+00 3.940E+04 0.000E+00 1.320E+06 0.000E+00 2.580E+03 AG-110M 5.820E+07 5.390E+07 0.000E+00 1.060E+08 0.000E+00 2.200E+10 0.000E+00 3.200E+07 TE-125M 1.630E+07 5.900E+06 4.900E+06 6.630E+07 0.000E+00 6.500E+07 0.000E+00 2.180E+06 TE-127 6.530E+02 2.340E+02 4.840E+02 2.660E+03 0.000E+00 5.150E+04 0.000E+00 1.410E+02 TE-127M 4.580E+07 1.640E+07 1.170E+07 1.860E+08 0.000E+00 1.540E+08 0.000E+00 5.580E+06 TE-129 2.830E-10 1.060E-10 2.170E-10 1.190E-09 0.000E+00 2.130E-10 0.000E+00 6.880E-11 TE-129M 6.020E+07 2.250E+07 2.070E+07 2.510E+08 0.000E+00 3.030E+08 0.000E+00 9.530E+06 TE-131 3.600E-33 1.500E-33 2.960E-33 1.580E-32 0.000E+00 5.100E-34 0.000E+00 1.140E-33 TE-131M 3.610E+05 1.770E+05 2.800E+05 1.790E+06 0.000E+00 1.750E+07 0.000E+00 1.470E+05 TE-132 2.400E+06 1.550E+06 1.720E+06 1.500E+07 0.000E+00 7.350E+07 0.000E+00 1.460E+06 I-130 4.200E+05 1.240E+06 1.050E+08 1.930E+06 0.000E+00 1.070E+06 0.000E+00 4.890E+05 Appendix G Ri Adult Cow Milk - Page 2 of 3 Page 9-120

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 2.960E+08 4.230E+08 1.390E+11 7.260E+08 0.000E+00 1.120E+08 0.000E+00 2.430E+08 I-132 1.640E-01 4.390E-01 1.540E+01 7.000E-01 0.000E+00 8.250E-02 0.000E+00 1.540E-01 I-133 3.870E+06 6.730E+06 9.890E+08 1.170E+07 0.000E+00 6.050E+06 0.000E+00 2.050E+06 I-134 2.020E-12 5.480E-12 9.490E-11 8.710E-12 0.000E+00 4.770E-15 0.000E+00 1.960E-12 I-135 1.280E+04 3.360E+04 2.220E+06 5.390E+04 0.000E+00 3.800E+04 0.000E+00 1.240E+04 CS-134 5.650E+09 1.350E+10 0.000E+00 4.350E+09 1.450E+09 2.350E+08 0.000E+00 1.100E+10 CS-136 2.630E+08 1.040E+09 0.000E+00 5.780E+08 7.930E+07 1.180E+08 0.000E+00 7.480E+08 CS-137 7.380E+09 1.010E+10 0.000E+00 3.430E+09 1.140E+09 1.950E+08 0.000E+00 6.610E+09 CS-138 9.050E-24 1.790E-23 0.000E+00 1.310E-23 1.300E-24 7.620E-29 0.000E+00 8.850E-24 BA-139 4.420E-08 3.150E-11 0.000E+00 2.940E-11 1.790E-11 7.830E-08 0.000E+00 1.290E-09 BA-140 2.690E+07 3.380E+04 0.000E+00 1.150E+04 1.930E+04 5.530E+07 0.000E+00 1.760E+06 BA-141 4.090E-46 3.090E-49 0.000E+00 2.880E-49 1.760E-49 1.930E-55 0.000E+00 1.380E-47 BA-142 2.640E-80 2.720E-83 0.000E+00 2.300E-83 1.540E-83 3.720E-98 0.000E+00 1.660E-81 LA-140 4.510E+00 2.270E+00 0.000E+00 0.000E+00 0.000E+00 1.670E+05 0.000E+00 6.010E-01 LA-142 1.860E-11 8.460E-12 0.000E+00 0.000E+00 0.000E+00 6.170E-08 0.000E+00 2.110E-12 CE-141 4.840E+03 3.280E+03 0.000E+00 1.520E+03 0.000E+00 1.250E+07 0.000E+00 3.720E+02 CE-143 4.160E+01 3.070E+04 0.000E+00 1.350E+01 0.000E+00 1.150E+06 0.000E+00 3.400E+00 CE-144 3.580E+05 1.500E+05 0.000E+00 8.870E+04 0.000E+00 1.210E+08 0.000E+00 1.920E+04 PR-143 1.580E+02 6.330E+01 0.000E+00 3.660E+01 0.000E+00 6.920E+05 0.000E+00 7.830E+00 PR-144 5.870E-54 2.440E-54 0.000E+00 1.380E-54 0.000E+00 8.450E-61 0.000E+00 2.990E-55 ND-147 9.420E+01 1.090E+02 0.000E+00 6.360E+01 0.000E+00 5.220E+05 0.000E+00 6.510E+00 W-187 6.510E+03 5.450E+03 0.000E+00 0.000E+00 0.000E+00 1.780E+06 0.000E+00 1.900E+03 NP-239 3.670E+00 3.610E-01 0.000E+00 1.130E+00 0.000E+00 7.410E+04 0.000E+00 1.990E-01 Appendix G Ri Adult Cow Milk - Page 3 of 3 Page 9-121

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.560E+03 1.560E+03 1.560E+03 1.560E+03 1.560E+03 0.000E+00 1.560E+03 C-14 2.250E+04 4.500E+03 4.500E+03 4.500E+03 4.500E+03 4.500E+03 0.000E+00 4.500E+03 NA-24 2.930E+05 2.930E+05 2.930E+05 2.930E+05 2.930E+05 2.930E+05 0.000E+00 2.930E+05 P-32 2.050E+10 1.280E+09 0.000E+00 0.000E+00 0.000E+00 2.310E+09 0.000E+00 7.930E+08 CR-51 0.000E+00 0.000E+00 2.050E+03 7.550E+02 4.550E+03 8.620E+05 0.000E+00 3.430E+03 MN-54 0.000E+00 1.010E+06 0.000E+00 3.000E+05 0.000E+00 3.090E+06 0.000E+00 1.930E+05 MN-56 0.000E+00 4.910E-04 0.000E+00 6.230E-04 0.000E+00 1.570E-02 0.000E+00 8.710E-05 FE-55 3.260E+05 2.260E+05 0.000E+00 0.000E+00 1.260E+05 1.290E+05 0.000E+00 5.260E+04 FE-59 3.860E+05 9.070E+05 0.000E+00 0.000E+00 2.540E+05 3.020E+06 0.000E+00 3.480E+05 CO-58 0.000E+00 5.660E+05 0.000E+00 0.000E+00 0.000E+00 1.150E+07 0.000E+00 1.270E+06 CO-60 0.000E+00 1.970E+06 0.000E+00 0.000E+00 0.000E+00 3.700E+07 0.000E+00 4.340E+06 NI-63 8.070E+08 5.600E+07 0.000E+00 0.000E+00 0.000E+00 1.170E+07 0.000E+00 2.710E+07 NI-65 4.440E-02 5.770E-03 0.000E+00 0.000E+00 0.000E+00 1.460E-01 0.000E+00 2.630E-03 CU-64 0.000E+00 2.660E+03 0.000E+00 6.700E+03 0.000E+00 2.260E+05 0.000E+00 1.250E+03 ZN-65 1.650E+08 5.240E+08 0.000E+00 3.500E+08 0.000E+00 3.300E+08 0.000E+00 2.370E+08 ZN-69 2.510E-13 4.800E-13 0.000E+00 3.120E-13 0.000E+00 7.210E-14 0.000E+00 3.340E-14 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.680E-02 0.000E+00 1.170E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.520E-29 0.000E+00 1.930E-24 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 3.110E+08 0.000E+00 0.000E+00 0.000E+00 6.140E+07 0.000E+00 1.450E+08 RB-88 0.000E+00 2.570E-46 0.000E+00 0.000E+00 0.000E+00 3.550E-57 0.000E+00 1.360E-46 RB-89 0.000E+00 5.190E-54 0.000E+00 0.000E+00 0.000E+00 3.020E-67 0.000E+00 3.650E-54 SR-89 3.050E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.890E+08 0.000E+00 8.750E+07 SR-90 9.830E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.840E+09 0.000E+00 2.410E+10 SR-91 6.070E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.890E+05 0.000E+00 2.450E+03 Appendix G Ri Adult Goat Milk - Page 1 of 3 Page 9-122

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.030E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.030E+01 0.000E+00 4.440E-02 Y-90 8.500E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.010E+04 0.000E+00 2.280E-01 Y-91 1.030E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.670E+05 0.000E+00 2.760E+01 Y-91M 7.170E-21 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.110E-20 0.000E+00 2.780E-22 Y-92 6.690E-06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.170E-01 0.000E+00 1.960E-07 Y-93 2.680E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.500E+02 0.000E+00 7.400E-04 ZR-95 1.130E+02 3.630E+01 0.000E+00 5.700E+01 0.000E+00 1.150E+05 0.000E+00 2.460E+01 ZR-97 5.200E-02 1.050E-02 0.000E+00 1.580E-02 0.000E+00 3.250E+03 0.000E+00 4.800E-03 NB-95 9.910E+03 5.510E+03 0.000E+00 5.450E+03 0.000E+00 3.340E+07 0.000E+00 2.960E+03 MO-99 0.000E+00 2.970E+06 0.000E+00 6.730E+06 0.000E+00 6.890E+06 0.000E+00 5.660E+05 TC-99M 3.980E-01 1.130E+00 0.000E+00 1.710E+01 5.520E-01 6.660E+02 0.000E+00 1.430E+01 TC-101 3.110E-61 4.490E-61 0.000E+00 8.080E-60 2.290E-61 1.350E-72 0.000E+00 4.400E-60 RU-103 1.220E+02 0.000E+00 0.000E+00 4.660E+02 0.000E+00 1.430E+04 0.000E+00 5.260E+01 RU-105 1.030E-04 0.000E+00 0.000E+00 1.330E-03 0.000E+00 6.290E-02 0.000E+00 4.060E-05 RU-106 2.450E+03 0.000E+00 0.000E+00 4.730E+03 0.000E+00 1.580E+05 0.000E+00 3.100E+02 AG-110M 6.990E+06 6.460E+06 0.000E+00 1.270E+07 0.000E+00 2.640E+09 0.000E+00 3.840E+06 TE-125M 1.950E+06 7.080E+05 5.880E+05 7.950E+06 0.000E+00 7.800E+06 0.000E+00 2.620E+05 TE-127 7.830E+01 2.810E+01 5.800E+01 3.190E+02 0.000E+00 6.180E+03 0.000E+00 1.700E+01 TE-127M 5.490E+06 1.960E+06 1.400E+06 2.230E+07 0.000E+00 1.840E+07 0.000E+00 6.690E+05 TE-129 3.390E-11 1.270E-11 2.600E-11 1.430E-10 0.000E+00 2.560E-11 0.000E+00 8.260E-12 TE-129M 7.220E+06 2.690E+06 2.480E+06 3.020E+07 0.000E+00 3.640E+07 0.000E+00 1.140E+06 TE-131 4.320E-34 1.810E-34 3.550E-34 1.890E-33 0.000E+00 6.120E-35 0.000E+00 1.360E-34 TE-131M 4.330E+04 2.120E+04 3.360E+04 2.150E+05 0.000E+00 2.100E+06 0.000E+00 1.770E+04 TE-132 2.880E+05 1.860E+05 2.060E+05 1.800E+06 0.000E+00 8.820E+06 0.000E+00 1.750E+05 I-130 5.040E+05 1.490E+06 1.260E+08 2.320E+06 0.000E+00 1.280E+06 0.000E+00 5.870E+05 Appendix G Ri Adult Goat Milk - Page 2 of 3 Page 9-123

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.550E+08 5.080E+08 1.670E+11 8.710E+08 0.000E+00 1.340E+08 0.000E+00 2.910E+08 I-132 1.970E-01 5.270E-01 1.840E+01 8.400E-01 0.000E+00 9.900E-02 0.000E+00 1.840E-01 I-133 4.640E+06 8.080E+06 1.190E+09 1.410E+07 0.000E+00 7.260E+06 0.000E+00 2.460E+06 I-134 2.420E-12 6.570E-12 1.140E-10 1.050E-11 0.000E+00 5.730E-15 0.000E+00 2.350E-12 I-135 1.540E+04 4.030E+04 2.660E+06 6.470E+04 0.000E+00 4.560E+04 0.000E+00 1.490E+04 CS-134 1.700E+10 4.040E+10 0.000E+00 1.310E+10 4.340E+09 7.060E+08 0.000E+00 3.300E+10 CS-136 7.900E+08 3.120E+09 0.000E+00 1.730E+09 2.380E+08 3.540E+08 0.000E+00 2.240E+09 CS-137 2.210E+10 3.030E+10 0.000E+00 1.030E+10 3.420E+09 5.860E+08 0.000E+00 1.980E+10 CS-138 2.710E-23 5.360E-23 0.000E+00 3.940E-23 3.890E-24 2.290E-28 0.000E+00 2.650E-23 BA-139 5.300E-09 3.780E-12 0.000E+00 3.530E-12 2.140E-12 9.400E-09 0.000E+00 1.550E-10 BA-140 3.230E+06 4.050E+03 0.000E+00 1.380E+03 2.320E+03 6.640E+06 0.000E+00 2.110E+05 BA-141 4.910E-47 3.710E-50 0.000E+00 3.450E-50 2.110E-50 2.310E-56 0.000E+00 1.660E-48 BA-142 3.170E-81 3.260E-84 0.000E+00 2.750E-84 1.850E-84 0.000E+00 0.000E+00 2.000E-82 LA-140 5.410E-01 2.730E-01 0.000E+00 0.000E+00 0.000E+00 2.000E+04 0.000E+00 7.210E-02 LA-142 2.230E-12 1.010E-12 0.000E+00 0.000E+00 0.000E+00 7.410E-09 0.000E+00 2.530E-13 CE-141 5.810E+02 3.930E+02 0.000E+00 1.830E+02 0.000E+00 1.500E+06 0.000E+00 4.460E+01 CE-143 4.990E+00 3.690E+03 0.000E+00 1.620E+00 0.000E+00 1.380E+05 0.000E+00 4.080E-01 CE-144 4.290E+04 1.790E+04 0.000E+00 1.060E+04 0.000E+00 1.450E+07 0.000E+00 2.300E+03 PR-143 1.890E+01 7.600E+00 0.000E+00 4.390E+00 0.000E+00 8.300E+04 0.000E+00 9.390E-01 PR-144 7.050E-55 2.930E-55 0.000E+00 1.650E-55 0.000E+00 1.010E-61 0.000E+00 3.580E-56 ND-147 1.130E+01 1.310E+01 0.000E+00 7.630E+00 0.000E+00 6.270E+04 0.000E+00 7.810E-01 W-187 7.820E+02 6.530E+02 0.000E+00 0.000E+00 0.000E+00 2.140E+05 0.000E+00 2.280E+02 NP-239 4.410E-01 4.330E-02 0.000E+00 1.350E-01 0.000E+00 8.890E+03 0.000E+00 2.390E-02 Appendix G Ri Adult Goat Milk - Page 3 of 3 Page 9-124

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 3.250E+02 3.250E+02 3.250E+02 3.250E+02 3.250E+02 0.000E+00 3.250E+02 C-14 2.060E+04 4.130E+03 4.130E+03 4.130E+03 4.130E+03 4.130E+03 0.000E+00 4.130E+03 NA-24 1.360E-03 1.360E-03 1.360E-03 1.360E-03 1.360E-03 1.360E-03 0.000E+00 1.360E-03 P-32 4.660E+09 2.900E+08 0.000E+00 0.000E+00 0.000E+00 5.240E+08 0.000E+00 1.800E+08 CR-51 0.000E+00 0.000E+00 4.210E+03 1.550E+03 9.350E+03 1.770E+06 0.000E+00 7.050E+03 MN-54 0.000E+00 9.180E+06 0.000E+00 2.730E+06 0.000E+00 2.810E+07 0.000E+00 1.750E+06 MN-56 0.000E+00 1.320E-53 0.000E+00 1.680E-53 0.000E+00 4.220E-52 0.000E+00 2.350E-54 FE-55 2.930E+08 2.030E+08 0.000E+00 0.000E+00 1.130E+08 1.160E+08 0.000E+00 4.720E+07 FE-59 2.660E+08 6.240E+08 0.000E+00 0.000E+00 1.740E+08 2.080E+09 0.000E+00 2.390E+08 CO-58 0.000E+00 1.820E+07 0.000E+00 0.000E+00 0.000E+00 3.690E+08 0.000E+00 4.090E+07 CO-60 0.000E+00 7.520E+07 0.000E+00 0.000E+00 0.000E+00 1.410E+09 0.000E+00 1.660E+08 NI-63 1.890E+10 1.310E+09 0.000E+00 0.000E+00 0.000E+00 2.730E+08 0.000E+00 6.330E+08 NI-65 2.250E-52 2.920E-53 0.000E+00 0.000E+00 0.000E+00 7.400E-52 0.000E+00 1.330E-53 CU-64 0.000E+00 2.710E-07 0.000E+00 6.830E-07 0.000E+00 2.310E-05 0.000E+00 1.270E-07 ZN-65 3.560E+08 1.130E+09 0.000E+00 7.570E+08 0.000E+00 7.130E+08 0.000E+00 5.120E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.650E-57 0.000E+00 6.000E-57 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.870E+08 0.000E+00 0.000E+00 0.000E+00 9.600E+07 0.000E+00 2.270E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 3.020E+08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.840E+07 0.000E+00 8.660E+06 SR-90 1.240E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.590E+08 0.000E+00 3.050E+09 SR-91 1.520E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.240E-10 0.000E+00 6.140E-12 Appendix G Ri Adult Cow Meat - Page 1 of 3 Page 9-125

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.180E-49 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.340E-48 0.000E+00 5.100E-51 Y-90 1.080E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.140E+06 0.000E+00 2.890E+00 Y-91 1.130E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.230E+08 0.000E+00 3.030E+04 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-92 1.520E-39 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.660E-35 0.000E+00 4.430E-41 Y-93 4.690E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.490E-07 0.000E+00 1.300E-13 ZR-95 1.870E+06 6.010E+05 0.000E+00 9.420E+05 0.000E+00 1.900E+09 0.000E+00 4.070E+05 ZR-97 2.070E-05 4.170E-06 0.000E+00 6.300E-06 0.000E+00 1.290E+00 0.000E+00 1.910E-06 NB-95 2.300E+06 1.280E+06 0.000E+00 1.260E+06 0.000E+00 7.760E+09 0.000E+00 6.870E+05 MO-99 0.000E+00 1.000E+05 0.000E+00 2.260E+05 0.000E+00 2.320E+05 0.000E+00 1.900E+04 TC-99M 4.450E-21 1.260E-20 0.000E+00 1.910E-19 6.150E-21 7.430E-18 0.000E+00 1.600E-19 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.050E+08 0.000E+00 0.000E+00 4.010E+08 0.000E+00 1.230E+10 0.000E+00 4.530E+07 RU-105 5.780E-28 0.000E+00 0.000E+00 7.460E-27 0.000E+00 3.530E-25 0.000E+00 2.280E-28 RU-106 2.800E+09 0.000E+00 0.000E+00 5.400E+09 0.000E+00 1.810E+11 0.000E+00 3.540E+08 AG-110M 6.680E+06 6.180E+06 0.000E+00 1.220E+07 0.000E+00 2.520E+09 0.000E+00 3.670E+06 TE-125M 3.590E+08 1.300E+08 1.080E+08 1.460E+09 0.000E+00 1.430E+09 0.000E+00 4.810E+07 TE-127 2.120E-10 7.610E-11 1.570E-10 8.640E-10 0.000E+00 1.670E-08 0.000E+00 4.590E-11 TE-127M 1.120E+09 3.990E+08 2.850E+08 4.530E+09 0.000E+00 3.740E+09 0.000E+00 1.360E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-129M 1.130E+09 4.230E+08 3.900E+08 4.730E+09 0.000E+00 5.710E+09 0.000E+00 1.790E+08 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 4.510E+02 2.210E+02 3.490E+02 2.230E+03 0.000E+00 2.190E+04 0.000E+00 1.840E+02 TE-132 1.420E+06 9.180E+05 1.010E+06 8.840E+06 0.000E+00 4.340E+07 0.000E+00 8.620E+05 I-130 2.110E-06 6.220E-06 5.270E-04 9.700E-06 0.000E+00 5.350E-06 0.000E+00 2.450E-06 Appendix G Ri Adult Cow Meat - Page 2 of 3 Page 9-126

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.070E+07 1.540E+07 5.030E+09 2.630E+07 0.000E+00 4.050E+06 0.000E+00 8.800E+06 I-132 6.970E-59 1.860E-58 6.530E-57 2.970E-58 0.000E+00 3.500E-59 0.000E+00 6.530E-59 I-133 3.650E-01 6.350E-01 9.340E+01 1.110E+00 0.000E+00 5.710E-01 0.000E+00 1.940E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 4.420E-17 1.160E-16 7.640E-15 1.860E-16 0.000E+00 1.310E-16 0.000E+00 4.270E-17 CS-134 6.580E+08 1.560E+09 0.000E+00 5.060E+08 1.680E+08 2.740E+07 0.000E+00 1.280E+09 CS-136 1.210E+07 4.760E+07 0.000E+00 2.650E+07 3.630E+06 5.410E+06 0.000E+00 3.420E+07 CS-137 8.720E+08 1.190E+09 0.000E+00 4.050E+08 1.350E+08 2.310E+07 0.000E+00 7.810E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 2.870E+07 3.610E+04 0.000E+00 1.230E+04 2.070E+04 5.920E+07 0.000E+00 1.880E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 3.710E-02 1.870E-02 0.000E+00 0.000E+00 0.000E+00 1.370E+03 0.000E+00 4.940E-03 LA-142 3.470E-92 1.580E-92 0.000E+00 0.000E+00 0.000E+00 1.150E-88 0.000E+00 3.940E-93 CE-141 1.400E+04 9.500E+03 0.000E+00 4.410E+03 0.000E+00 3.630E+07 0.000E+00 1.080E+03 CE-143 2.010E-02 1.480E+01 0.000E+00 6.530E-03 0.000E+00 5.550E+02 0.000E+00 1.640E-03 CE-144 1.460E+06 6.090E+05 0.000E+00 3.610E+05 0.000E+00 4.930E+08 0.000E+00 7.830E+04 PR-143 2.100E+04 8.410E+03 0.000E+00 4.850E+03 0.000E+00 9.180E+07 0.000E+00 1.040E+03 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 7.070E+03 8.170E+03 0.000E+00 4.780E+03 0.000E+00 3.920E+07 0.000E+00 4.890E+02 W-187 2.070E-02 1.730E-02 0.000E+00 0.000E+00 0.000E+00 5.660E+00 0.000E+00 6.040E-03 NP-239 2.590E-01 2.550E-02 0.000E+00 7.950E-02 0.000E+00 5.230E+03 0.000E+00 1.400E-02 Appendix G Ri Adult Cow Meat - Page 3 of 3 Page 9-127

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Vegetation (VEG) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 0.000E+00 2.260E+03 C-14 5.560E+04 1.110E+04 1.110E+04 1.110E+04 1.110E+04 1.110E+04 0.000E+00 1.110E+04 NA-24 2.690E+05 2.690E+05 2.690E+05 2.690E+05 2.690E+05 2.690E+05 0.000E+00 2.690E+05 P-32 1.400E+09 8.730E+07 0.000E+00 0.000E+00 0.000E+00 1.580E+08 0.000E+00 5.430E+07 CR-51 0.000E+00 0.000E+00 2.780E+04 1.020E+04 6.160E+04 1.170E+07 0.000E+00 4.640E+04 MN-54 0.000E+00 3.130E+08 0.000E+00 9.310E+07 0.000E+00 9.590E+08 0.000E+00 5.970E+07 MN-56 0.000E+00 1.580E+01 0.000E+00 2.000E+01 0.000E+00 5.040E+02 0.000E+00 2.800E+00 FE-55 2.100E+08 1.450E+08 0.000E+00 0.000E+00 8.080E+07 8.310E+07 0.000E+00 3.380E+07 FE-59 1.260E+08 2.960E+08 0.000E+00 0.000E+00 8.280E+07 9.880E+08 0.000E+00 1.140E+08 CO-58 0.000E+00 3.070E+07 0.000E+00 0.000E+00 0.000E+00 6.230E+08 0.000E+00 6.890E+07 CO-60 0.000E+00 1.670E+08 0.000E+00 0.000E+00 0.000E+00 3.140E+09 0.000E+00 3.690E+08 NI-63 1.040E+10 7.210E+08 0.000E+00 0.000E+00 0.000E+00 1.500E+08 0.000E+00 3.490E+08 NI-65 6.150E+01 7.990E+00 0.000E+00 0.000E+00 0.000E+00 2.030E+02 0.000E+00 3.640E+00 CU-64 0.000E+00 9.200E+03 0.000E+00 2.320E+04 0.000E+00 7.840E+05 0.000E+00 4.320E+03 ZN-65 3.170E+08 1.010E+09 0.000E+00 6.750E+08 0.000E+00 6.360E+08 0.000E+00 4.560E+08 ZN-69 5.490E-06 1.050E-05 0.000E+00 6.830E-06 0.000E+00 1.580E-06 0.000E+00 7.310E-07 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.470E+00 0.000E+00 3.110E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.940E-16 0.000E+00 2.480E-11 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.190E+08 0.000E+00 0.000E+00 0.000E+00 4.330E+07 0.000E+00 1.020E+08 RB-88 0.000E+00 3.430E-22 0.000E+00 0.000E+00 0.000E+00 4.740E-33 0.000E+00 1.820E-22 RB-89 0.000E+00 3.890E-26 0.000E+00 0.000E+00 0.000E+00 2.260E-39 0.000E+00 2.730E-26 SR-89 9.970E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.600E+09 0.000E+00 2.860E+08 SR-90 6.050E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.750E+10 0.000E+00 1.480E+11 SR-91 3.050E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.450E+06 0.000E+00 1.230E+04 Appendix G Ri Adult Vegetation - Page 1 of 3 Page 9-128

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Vegetation (VEG) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.270E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.450E+03 0.000E+00 1.850E+01 Y-90 1.330E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.410E+08 0.000E+00 3.570E+02 Y-91 5.110E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.810E+09 0.000E+00 1.370E+05 Y-91M 5.220E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.530E-08 0.000E+00 2.020E-10 Y-92 9.150E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.600E+04 0.000E+00 2.680E-02 Y-93 1.700E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.380E+06 0.000E+00 4.680E+00 ZR-95 1.170E+06 3.770E+05 0.000E+00 5.910E+05 0.000E+00 1.190E+09 0.000E+00 2.550E+05 ZR-97 3.370E+02 6.810E+01 0.000E+00 1.030E+02 0.000E+00 2.110E+07 0.000E+00 3.110E+01 NB-95 1.420E+05 7.920E+04 0.000E+00 7.830E+04 0.000E+00 4.810E+08 0.000E+00 4.260E+04 MO-99 0.000E+00 6.150E+06 0.000E+00 1.390E+07 0.000E+00 1.430E+07 0.000E+00 1.170E+06 TC-99M 3.100E+00 8.770E+00 0.000E+00 1.330E+02 4.300E+00 5.190E+03 0.000E+00 1.120E+02 TC-101 8.220E-31 1.180E-30 0.000E+00 2.130E-29 6.050E-31 3.560E-42 0.000E+00 1.160E-29 RU-103 4.770E+06 0.000E+00 0.000E+00 1.820E+07 0.000E+00 5.570E+08 0.000E+00 2.060E+06 RU-105 5.390E+01 0.000E+00 0.000E+00 6.960E+02 0.000E+00 3.290E+04 0.000E+00 2.130E+01 RU-106 1.930E+08 0.000E+00 0.000E+00 3.720E+08 0.000E+00 1.250E+10 0.000E+00 2.440E+07 AG-110M 1.050E+07 9.750E+06 0.000E+00 1.920E+07 0.000E+00 3.980E+09 0.000E+00 5.790E+06 TE-125M 9.660E+07 3.500E+07 2.900E+07 3.930E+08 0.000E+00 3.860E+08 0.000E+00 1.290E+07 TE-127 5.660E+03 2.030E+03 4.190E+03 2.310E+04 0.000E+00 4.470E+05 0.000E+00 1.220E+03 TE-127M 3.490E+08 1.250E+08 8.920E+07 1.420E+09 0.000E+00 1.170E+09 0.000E+00 4.260E+07 TE-129 7.630E-04 2.870E-04 5.850E-04 3.210E-03 0.000E+00 5.760E-04 0.000E+00 1.860E-04 TE-129M 2.510E+08 9.380E+07 8.630E+07 1.050E+09 0.000E+00 1.270E+09 0.000E+00 3.980E+07 TE-131 1.500E-15 6.270E-16 1.230E-15 6.570E-15 0.000E+00 2.130E-16 0.000E+00 4.740E-16 TE-131M 9.120E+05 4.460E+05 7.060E+05 4.520E+06 0.000E+00 4.430E+07 0.000E+00 3.720E+05 TE-132 4.300E+06 2.780E+06 3.070E+06 2.680E+07 0.000E+00 1.320E+08 0.000E+00 2.610E+06 I-130 3.920E+05 1.160E+06 9.810E+07 1.810E+06 0.000E+00 9.960E+05 0.000E+00 4.570E+05 Appendix G Ri Adult Vegetation - Page 2 of 3 Page 9-129

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Vegetation (VEG) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 8.080E+07 1.160E+08 3.790E+10 1.980E+08 0.000E+00 3.050E+07 0.000E+00 6.620E+07 I-132 5.760E+01 1.540E+02 5.390E+03 2.450E+02 0.000E+00 2.890E+01 0.000E+00 5.390E+01 I-133 2.090E+06 3.630E+06 5.330E+08 6.330E+06 0.000E+00 3.260E+06 0.000E+00 1.110E+06 I-134 9.650E-05 2.620E-04 4.540E-03 4.170E-04 0.000E+00 2.290E-07 0.000E+00 9.380E-05 I-135 3.900E+04 1.020E+05 6.730E+06 1.640E+05 0.000E+00 1.150E+05 0.000E+00 3.770E+04 CS-134 4.670E+09 1.110E+10 0.000E+00 3.590E+09 1.190E+09 1.940E+08 0.000E+00 9.080E+09 CS-136 4.270E+07 1.680E+08 0.000E+00 9.380E+07 1.290E+07 1.910E+07 0.000E+00 1.210E+08 CS-137 6.360E+09 8.700E+09 0.000E+00 2.950E+09 9.810E+08 1.680E+08 0.000E+00 5.700E+09 CS-138 3.920E-11 7.730E-11 0.000E+00 5.680E-11 5.610E-12 3.300E-16 0.000E+00 3.830E-11 BA-139 2.860E-02 2.030E-05 0.000E+00 1.900E-05 1.150E-05 5.060E-02 0.000E+00 8.360E-04 BA-140 1.280E+08 1.610E+05 0.000E+00 5.490E+04 9.240E+04 2.650E+08 0.000E+00 8.420E+06 BA-141 1.150E-21 8.700E-25 0.000E+00 8.090E-25 4.940E-25 5.430E-31 0.000E+00 3.890E-23 BA-142 5.960E-39 6.120E-42 0.000E+00 5.170E-42 3.470E-42 8.390E-57 0.000E+00 3.750E-40 LA-140 1.980E+03 9.970E+02 0.000E+00 0.000E+00 0.000E+00 7.320E+07 0.000E+00 2.630E+02 LA-142 2.020E-04 9.190E-05 0.000E+00 0.000E+00 0.000E+00 6.710E-01 0.000E+00 2.290E-05 CE-141 1.970E+05 1.330E+05 0.000E+00 6.190E+04 0.000E+00 5.100E+08 0.000E+00 1.510E+04 CE-143 9.980E+02 7.380E+05 0.000E+00 3.250E+02 0.000E+00 2.760E+07 0.000E+00 8.160E+01 CE-144 3.290E+07 1.380E+07 0.000E+00 8.160E+06 0.000E+00 1.110E+10 0.000E+00 1.770E+06 PR-143 6.260E+04 2.510E+04 0.000E+00 1.450E+04 0.000E+00 2.740E+08 0.000E+00 3.100E+03 PR-144 3.090E-26 1.280E-26 0.000E+00 7.230E-27 0.000E+00 4.440E-33 0.000E+00 1.570E-27 ND-147 3.330E+04 3.850E+04 0.000E+00 2.250E+04 0.000E+00 1.850E+08 0.000E+00 2.310E+03 W-187 3.800E+04 3.180E+04 0.000E+00 0.000E+00 0.000E+00 1.040E+07 0.000E+00 1.110E+04 NP-239 1.430E+03 1.400E+02 0.000E+00 4.380E+02 0.000E+00 2.880E+07 0.000E+00 7.740E+01 Appendix G Ri Adult Vegetation - Page 3 of 3 Page 9-130

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.260E+03 1.260E+03 1.260E+03 1.260E+03 1.260E+03 0.000E+00 1.260E+03 C-14 1.820E+04 3.410E+03 3.410E+03 3.410E+03 3.410E+03 3.410E+03 0.000E+00 3.410E+03 NA-24 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 0.000E+00 1.020E+04 P-32 1.320E+06 7.710E+04 0.000E+00 0.000E+00 0.000E+00 8.640E+04 0.000E+00 5.010E+04 CR-51 0.000E+00 0.000E+00 5.950E+01 2.280E+01 1.440E+04 3.320E+03 0.000E+00 1.000E+02 MN-54 0.000E+00 3.960E+04 0.000E+00 9.840E+03 1.400E+06 7.740E+04 0.000E+00 6.300E+03 MN-56 0.000E+00 1.240E+00 0.000E+00 1.300E+00 9.440E+03 2.020E+04 0.000E+00 1.830E-01 FE-55 2.460E+04 1.700E+04 0.000E+00 0.000E+00 7.210E+04 6.030E+03 0.000E+00 3.940E+03 FE-59 1.180E+04 2.780E+04 0.000E+00 0.000E+00 1.020E+06 1.880E+05 0.000E+00 1.060E+04 CO-58 0.000E+00 1.580E+03 0.000E+00 0.000E+00 9.280E+05 1.060E+05 0.000E+00 2.070E+03 CO-60 0.000E+00 1.150E+04 0.000E+00 0.000E+00 5.970E+06 2.850E+05 0.000E+00 1.480E+04 NI-63 4.320E+05 3.140E+04 0.000E+00 0.000E+00 1.780E+05 1.340E+04 0.000E+00 1.450E+04 NI-65 1.540E+00 2.100E-01 0.000E+00 0.000E+00 5.600E+03 1.230E+04 0.000E+00 9.120E-02 CU-64 0.000E+00 1.460E+00 0.000E+00 4.620E+00 6.780E+03 4.900E+04 0.000E+00 6.150E-01 ZN-65 3.240E+04 1.030E+05 0.000E+00 6.900E+04 8.640E+05 5.340E+04 0.000E+00 4.660E+04 ZN-69 3.380E-02 6.510E-02 0.000E+00 4.220E-02 9.200E+02 1.630E+01 0.000E+00 4.520E-03 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.320E+02 0.000E+00 2.410E+02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.640E-03 0.000E+00 3.130E+02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.280E+01 RB-86 0.000E+00 1.350E+05 0.000E+00 0.000E+00 0.000E+00 1.660E+04 0.000E+00 5.900E+04 RB-88 0.000E+00 3.870E+02 0.000E+00 0.000E+00 0.000E+00 3.340E-09 0.000E+00 1.930E+02 RB-89 0.000E+00 2.560E+02 0.000E+00 0.000E+00 0.000E+00 9.280E-12 0.000E+00 1.700E+02 SR-89 3.040E+05 0.000E+00 0.000E+00 0.000E+00 1.400E+06 3.500E+05 0.000E+00 8.720E+03 SR-90 9.920E+07 0.000E+00 0.000E+00 0.000E+00 9.600E+06 7.220E+05 0.000E+00 6.100E+06 SR-91 6.190E+01 0.000E+00 0.000E+00 0.000E+00 3.650E+04 1.910E+05 0.000E+00 2.500E+00 Appendix G Ri Adult Inhalation - Page 1 of 3 Page 9-131

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 6.740E+00 0.000E+00 0.000E+00 0.000E+00 1.650E+04 4.300E+04 0.000E+00 2.910E-01 Y-90 2.090E+03 0.000E+00 0.000E+00 0.000E+00 1.700E+05 5.060E+05 0.000E+00 5.610E+01 Y-91 4.620E+05 0.000E+00 0.000E+00 0.000E+00 1.700E+06 3.850E+05 0.000E+00 1.240E+04 Y-91M 2.610E-01 0.000E+00 0.000E+00 0.000E+00 1.920E+03 1.330E+00 0.000E+00 1.020E-02 Y-92 1.030E+01 0.000E+00 0.000E+00 0.000E+00 1.570E+04 7.350E+04 0.000E+00 3.020E-01 Y-93 9.440E+01 0.000E+00 0.000E+00 0.000E+00 4.850E+04 4.220E+05 0.000E+00 2.610E+00 ZR-95 1.070E+05 3.440E+04 0.000E+00 5.420E+04 1.770E+06 1.500E+05 0.000E+00 2.330E+04 ZR-97 9.680E+01 1.960E+01 0.000E+00 2.970E+01 7.870E+04 5.230E+05 0.000E+00 9.040E+00 NB-95 1.410E+04 7.820E+03 0.000E+00 7.740E+03 5.050E+05 1.040E+05 0.000E+00 4.210E+03 MO-99 0.000E+00 1.210E+02 0.000E+00 2.910E+02 9.120E+04 2.480E+05 0.000E+00 2.300E+01 TC-99M 1.030E-03 2.910E-03 0.000E+00 4.420E-02 7.640E+02 4.160E+03 0.000E+00 3.700E-02 TC-101 4.180E-05 6.020E-05 0.000E+00 1.080E-03 3.990E+02 1.090E-11 0.000E+00 5.900E-04 RU-103 1.530E+03 0.000E+00 0.000E+00 5.830E+03 5.050E+05 1.100E+05 0.000E+00 6.580E+02 RU-105 7.900E-01 0.000E+00 0.000E+00 1.020E+00 1.100E+04 4.820E+04 0.000E+00 3.110E-01 RU-106 6.910E+04 0.000E+00 0.000E+00 1.340E+05 9.360E+06 9.120E+05 0.000E+00 8.720E+03 AG-110M 1.080E+04 1.000E+04 0.000E+00 1.970E+04 4.630E+06 3.020E+05 0.000E+00 5.940E+03 TE-125M 3.420E+03 1.580E+03 1.050E+03 1.240E+04 3.140E+05 7.060E+04 0.000E+00 4.670E+02 TE-127 1.400E+00 6.420E-01 1.060E+00 5.100E+00 6.510E+03 5.740E+04 0.000E+00 3.100E-01 TE-127M 1.260E+04 5.770E+03 3.290E+03 4.580E+04 9.600E+05 1.500E+05 0.000E+00 1.570E+03 TE-129 4.980E-02 2.390E-02 3.900E-02 1.870E-01 1.940E+03 1.570E+02 0.000E+00 1.240E-02 TE-129M 9.760E+03 4.670E+03 3.440E+03 3.660E+04 1.160E+06 3.830E+05 0.000E+00 1.580E+03 TE-131 1.110E-02 5.950E-03 9.360E-03 4.370E-02 1.390E+03 1.840E+01 0.000E+00 3.590E-03 TE-131M 6.990E+01 4.360E+01 5.500E+01 3.090E+02 1.460E+05 5.560E+05 0.000E+00 2.900E+01 TE-132 2.600E+02 2.150E+02 1.900E+02 1.460E+03 2.880E+05 5.100E+05 0.000E+00 1.620E+02 I-130 4.580E+03 1.340E+04 1.140E+06 2.090E+04 0.000E+00 7.690E+03 0.000E+00 5.280E+03 Appendix G Ri Adult Inhalation - Page 2 of 3 Page 9-132

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 2.520E+04 3.580E+04 1.190E+07 6.130E+04 0.000E+00 6.280E+03 0.000E+00 2.050E+04 I-132 1.160E+03 3.260E+03 1.140E+05 5.180E+03 0.000E+00 4.060E+02 0.000E+00 1.160E+03 I-133 8.640E+03 1.480E+04 2.150E+06 2.580E+04 0.000E+00 8.880E+03 0.000E+00 4.520E+03 I-134 6.440E+02 1.730E+03 2.980E+04 2.750E+03 0.000E+00 1.010E+00 0.000E+00 6.150E+02 I-135 2.680E+03 6.980E+03 4.480E+05 1.110E+04 0.000E+00 5.250E+03 0.000E+00 2.570E+03 CS-134 3.730E+05 8.480E+05 0.000E+00 2.870E+05 9.760E+04 1.040E+04 0.000E+00 7.280E+05 CS-136 3.900E+04 1.460E+05 0.000E+00 8.560E+04 1.200E+04 1.170E+04 0.000E+00 1.100E+05 CS-137 4.780E+05 6.210E+05 0.000E+00 2.220E+05 7.520E+04 8.400E+03 0.000E+00 4.280E+05 CS-138 3.310E+02 6.210E+02 0.000E+00 4.800E+02 4.860E+01 1.860E-03 0.000E+00 3.240E+02 BA-139 9.360E-01 6.660E-04 0.000E+00 6.220E-04 3.760E+03 8.960E+02 0.000E+00 2.740E-02 BA-140 3.900E+04 4.900E+01 0.000E+00 1.670E+01 1.270E+06 2.180E+05 0.000E+00 2.570E+03 BA-141 1.000E-01 7.530E-05 0.000E+00 7.000E-05 1.940E+03 1.160E-07 0.000E+00 3.360E-03 BA-142 2.630E-02 2.700E-05 0.000E+00 2.290E-05 1.190E+03 1.570E-16 0.000E+00 1.660E-03 LA-140 3.440E+02 1.740E+02 0.000E+00 0.000E+00 1.360E+05 4.580E+05 0.000E+00 4.580E+01 LA-142 6.830E-01 3.100E-01 0.000E+00 0.000E+00 6.330E+03 2.110E+03 0.000E+00 7.720E-02 CE-141 1.990E+04 1.350E+04 0.000E+00 6.260E+03 3.620E+05 1.200E+05 0.000E+00 1.530E+03 CE-143 1.860E+02 1.380E+02 0.000E+00 6.080E+01 7.980E+04 2.260E+05 0.000E+00 1.530E+01 CE-144 3.430E+06 1.430E+06 0.000E+00 8.480E+05 7.780E+06 8.160E+05 0.000E+00 1.840E+05 PR-143 9.360E+03 3.750E+03 0.000E+00 2.160E+03 2.810E+05 2.000E+05 0.000E+00 4.640E+02 PR-144 3.010E-02 1.250E-02 0.000E+00 7.050E-03 1.020E+03 2.150E-08 0.000E+00 1.530E-03 ND-147 5.270E+03 6.100E+03 0.000E+00 3.560E+03 2.210E+05 1.730E+05 0.000E+00 3.650E+02 W-187 8.480E+00 7.080E+00 0.000E+00 0.000E+00 2.900E+04 1.550E+05 0.000E+00 2.480E+00 NP-239 2.300E+02 2.260E+01 0.000E+00 7.000E+01 3.760E+04 1.190E+05 0.000E+00 1.240E+01 Appendix G Ri Adult Inhalation - Page 3 of 3 Page 9-133

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.390E+07 1.190E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530E+10 2.150E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.150E+06 Appendix G Ri Adult Ground Plane Deposition - Page 1 of 3 Page 9-134

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.310E+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.110E+05 1.840E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-110M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 TE-127 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04 TE-129 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 TE-129M 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 I-130 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.510E+06 Appendix G Ri Adult Ground Plane Deposition - Page 2 of 3 Page 9-135

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.090E+07 1.720E+07 I-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 I-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2.450E+06 I-134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 I-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS-134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.000E+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.710E+08 1.510E+08 CS-137 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 4.100E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.110E+04 4.490E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 2.110E+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.980E+06 1.710E+06 Appendix G Ri Adult Ground Plane Deposition - Page 3 of 3 Page 9-136

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 9.940E+02 9.940E+02 9.940E+02 9.940E+02 9.940E+02 0.000E+00 9.940E+02 C-14 4.150E+04 8.310E+03 8.310E+03 8.310E+03 8.310E+03 8.310E+03 0.000E+00 8.310E+03 NA-24 4.260E+06 4.260E+06 4.260E+06 4.260E+06 4.260E+06 4.260E+06 0.000E+00 4.260E+06 P-32 3.150E+10 1.950E+09 0.000E+00 0.000E+00 0.000E+00 2.650E+09 0.000E+00 1.220E+09 CR-51 0.000E+00 0.000E+00 2.770E+04 1.090E+04 7.130E+04 8.390E+06 0.000E+00 4.990E+04 MN-54 0.000E+00 1.400E+07 0.000E+00 4.180E+06 0.000E+00 2.870E+07 0.000E+00 2.780E+06 MN-56 0.000E+00 7.250E-03 0.000E+00 9.180E-03 0.000E+00 4.770E-01 0.000E+00 1.290E-03 FE-55 4.450E+07 3.160E+07 0.000E+00 0.000E+00 2.000E+07 1.370E+07 0.000E+00 7.360E+06 FE-59 5.180E+07 1.210E+08 0.000E+00 0.000E+00 3.810E+07 2.860E+08 0.000E+00 4.670E+07 CO-58 0.000E+00 7.940E+06 0.000E+00 0.000E+00 0.000E+00 1.090E+08 0.000E+00 1.830E+07 CO-60 0.000E+00 2.780E+07 0.000E+00 0.000E+00 0.000E+00 3.620E+08 0.000E+00 6.260E+07 NI-63 1.180E+10 8.350E+08 0.000E+00 0.000E+00 0.000E+00 1.330E+08 0.000E+00 4.010E+08 NI-65 6.770E-01 8.650E-02 0.000E+00 0.000E+00 0.000E+00 4.690E+00 0.000E+00 3.940E-02 CU-64 0.000E+00 4.250E+04 0.000E+00 1.070E+05 0.000E+00 3.290E+06 0.000E+00 2.000E+04 ZN-65 2.110E+09 7.320E+09 0.000E+00 4.680E+09 0.000E+00 3.100E+09 0.000E+00 3.410E+09 ZN-69 3.850E-12 7.330E-12 0.000E+00 4.790E-12 0.000E+00 1.350E-11 0.000E+00 5.130E-13 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.790E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.880E-23 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.730E+09 0.000E+00 0.000E+00 0.000E+00 7.000E+08 0.000E+00 2.220E+09 RB-88 0.000E+00 3.890E-45 0.000E+00 0.000E+00 0.000E+00 3.330E-52 0.000E+00 2.070E-45 RB-89 0.000E+00 7.660E-53 0.000E+00 0.000E+00 0.000E+00 1.170E-61 0.000E+00 5.420E-53 SR-89 2.670E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.190E+08 0.000E+00 7.660E+07 SR-90 6.610E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.860E+09 0.000E+00 1.630E+10 SR-91 5.310E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.410E+05 0.000E+00 2.110E+03 Appendix H Ri Teen Cow Milk - Page 1 of 3 Page 9-137

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 8.940E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.280E+01 0.000E+00 3.810E-02 Y-90 1.300E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.070E+06 0.000E+00 3.510E+00 Y-91 1.580E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.480E+06 0.000E+00 4.240E+02 Y-91M 1.090E-19 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.170E-18 0.000E+00 4.180E-21 Y-92 1.030E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.830E+00 0.000E+00 2.980E-06 Y-93 4.120E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.260E+04 0.000E+00 1.130E-02 ZR-95 1.650E+03 5.200E+02 0.000E+00 7.650E+02 0.000E+00 1.200E+06 0.000E+00 3.580E+02 ZR-97 7.880E-01 1.560E-01 0.000E+00 2.370E-01 0.000E+00 4.220E+04 0.000E+00 7.190E-02 NB-95 1.410E+05 7.810E+04 0.000E+00 7.570E+04 0.000E+00 3.340E+08 0.000E+00 4.300E+04 MO-99 0.000E+00 4.470E+07 0.000E+00 1.020E+08 0.000E+00 8.010E+07 0.000E+00 8.530E+06 TC-99M 5.760E+00 1.610E+01 0.000E+00 2.390E+02 8.920E+00 1.050E+04 0.000E+00 2.080E+02 TC-101 4.740E-60 6.750E-60 0.000E+00 1.220E-58 4.110E-60 1.150E-66 0.000E+00 6.630E-59 RU-103 1.810E+03 0.000E+00 0.000E+00 6.380E+03 0.000E+00 1.510E+05 0.000E+00 7.740E+02 RU-105 1.560E-03 0.000E+00 0.000E+00 1.970E-02 0.000E+00 1.260E+00 0.000E+00 6.070E-04 RU-106 3.750E+04 0.000E+00 0.000E+00 7.240E+04 0.000E+00 1.800E+06 0.000E+00 4.730E+03 AG-110M 9.630E+07 9.110E+07 0.000E+00 1.740E+08 0.000E+00 2.560E+10 0.000E+00 5.540E+07 TE-125M 3.000E+07 1.080E+07 8.390E+06 0.000E+00 0.000E+00 8.860E+07 0.000E+00 4.020E+06 TE-127 1.210E+03 4.290E+02 8.350E+02 4.900E+03 0.000E+00 9.340E+04 0.000E+00 2.600E+02 TE-127M 8.440E+07 2.990E+07 2.010E+07 3.420E+08 0.000E+00 2.100E+08 0.000E+00 1.000E+07 TE-129 5.200E-10 1.940E-10 3.720E-10 2.180E-09 0.000E+00 2.840E-09 0.000E+00 1.270E-10 TE-129M 1.100E+08 4.090E+07 3.550E+07 4.610E+08 0.000E+00 4.130E+08 0.000E+00 1.740E+07 TE-131 6.580E-33 2.710E-33 5.070E-33 2.880E-32 0.000E+00 5.400E-34 0.000E+00 2.060E-33 TE-131M 6.570E+05 3.150E+05 4.740E+05 3.290E+06 0.000E+00 2.530E+07 0.000E+00 2.630E+05 TE-132 4.290E+06 2.720E+06 2.870E+06 2.610E+07 0.000E+00 8.610E+07 0.000E+00 2.560E+06 I-130 7.380E+05 2.140E+06 1.740E+08 3.290E+06 0.000E+00 1.640E+06 0.000E+00 8.530E+05 Appendix H Ri Teen Cow Milk - Page 2 of 3 Page 9-138

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 5.370E+08 7.520E+08 2.190E+11 1.290E+09 0.000E+00 1.490E+08 0.000E+00 4.040E+08 I-132 2.910E-01 7.620E-01 2.570E+01 1.200E+00 0.000E+00 3.320E-01 0.000E+00 2.740E-01 I-133 7.070E+06 1.200E+07 1.670E+09 2.100E+07 0.000E+00 9.070E+06 0.000E+00 3.660E+06 I-134 3.580E-12 9.500E-12 1.580E-10 1.500E-11 0.000E+00 1.250E-13 0.000E+00 3.410E-12 I-135 2.280E+04 5.870E+04 3.780E+06 9.270E+04 0.000E+00 6.510E+04 0.000E+00 2.180E+04 CS-134 9.820E+09 2.310E+10 0.000E+00 7.340E+09 2.800E+09 2.870E+08 0.000E+00 1.070E+10 CS-136 4.480E+08 1.760E+09 0.000E+00 9.600E+08 1.510E+08 1.420E+08 0.000E+00 1.180E+09 CS-137 1.340E+10 1.780E+10 0.000E+00 6.060E+09 2.350E+09 2.530E+08 0.000E+00 6.200E+09 CS-138 1.640E-23 3.150E-23 0.000E+00 2.330E-23 2.710E-24 1.430E-26 0.000E+00 1.580E-23 BA-139 8.170E-08 5.750E-11 0.000E+00 5.420E-11 3.960E-11 7.290E-07 0.000E+00 2.380E-09 BA-140 4.850E+07 5.950E+04 0.000E+00 2.020E+04 4.000E+04 7.480E+07 0.000E+00 3.130E+06 BA-141 7.520E-46 5.620E-49 0.000E+00 5.210E-49 3.850E-49 1.600E-51 0.000E+00 2.510E-47 BA-142 4.790E-80 4.790E-83 0.000E+00 4.050E-83 3.190E-83 1.470E-91 0.000E+00 2.950E-81 LA-140 8.100E+00 3.980E+00 0.000E+00 0.000E+00 0.000E+00 2.290E+05 0.000E+00 1.060E+00 LA-142 3.360E-11 1.490E-11 0.000E+00 0.000E+00 0.000E+00 4.540E-07 0.000E+00 3.710E-12 CE-141 8.880E+03 5.930E+03 0.000E+00 2.790E+03 0.000E+00 1.700E+07 0.000E+00 6.810E+02 CE-143 7.640E+01 5.560E+04 0.000E+00 2.490E+01 0.000E+00 1.670E+06 0.000E+00 6.210E+00 CE-144 6.580E+05 2.720E+05 0.000E+00 1.630E+05 0.000E+00 1.660E+08 0.000E+00 3.540E+04 PR-143 2.900E+02 1.160E+02 0.000E+00 6.730E+01 0.000E+00 9.540E+05 0.000E+00 1.440E+01 PR-144 1.080E-53 4.430E-54 0.000E+00 2.540E-54 0.000E+00 1.190E-56 0.000E+00 5.490E-55 ND-147 1.810E+02 1.970E+02 0.000E+00 1.160E+02 0.000E+00 7.110E+05 0.000E+00 1.180E+01 W-187 1.190E+04 9.710E+03 0.000E+00 0.000E+00 0.000E+00 2.630E+06 0.000E+00 3.400E+03 NP-239 7.010E+00 6.610E-01 0.000E+00 2.070E+00 0.000E+00 1.060E+05 0.000E+00 3.670E-01 Appendix H Ri Teen Cow Milk - Page 3 of 3 Page 9-139

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.030E+03 2.030E+03 2.030E+03 2.030E+03 2.030E+03 0.000E+00 2.030E+03 C-14 4.150E+04 8.310E+03 8.310E+03 8.310E+03 8.310E+03 8.310E+03 0.000E+00 8.310E+03 NA-24 5.110E+05 5.110E+05 5.110E+05 5.110E+05 5.110E+05 5.110E+05 0.000E+00 5.110E+05 P-32 3.780E+10 2.340E+09 0.000E+00 0.000E+00 0.000E+00 3.180E+09 0.000E+00 1.470E+09 CR-51 0.000E+00 0.000E+00 3.330E+03 1.310E+03 8.550E+03 1.010E+06 0.000E+00 5.990E+03 MN-54 0.000E+00 1.680E+06 0.000E+00 5.020E+05 0.000E+00 3.450E+06 0.000E+00 3.340E+05 MN-56 0.000E+00 8.700E-04 0.000E+00 1.100E-03 0.000E+00 5.730E-02 0.000E+00 1.550E-04 FE-55 5.790E+05 4.110E+05 0.000E+00 0.000E+00 2.600E+05 1.780E+05 0.000E+00 9.570E+04 FE-59 6.740E+05 1.570E+06 0.000E+00 0.000E+00 4.960E+05 3.720E+06 0.000E+00 6.070E+05 CO-58 0.000E+00 9.520E+05 0.000E+00 0.000E+00 0.000E+00 1.310E+07 0.000E+00 2.190E+06 CO-60 0.000E+00 3.340E+06 0.000E+00 0.000E+00 0.000E+00 4.350E+07 0.000E+00 7.520E+06 NI-63 1.420E+09 1.000E+08 0.000E+00 0.000E+00 0.000E+00 1.590E+07 0.000E+00 4.810E+07 NI-65 8.120E-02 1.040E-02 0.000E+00 0.000E+00 0.000E+00 5.630E-01 0.000E+00 4.730E-03 CU-64 0.000E+00 4.730E+03 0.000E+00 1.200E+04 0.000E+00 3.670E+05 0.000E+00 2.230E+03 ZN-65 2.530E+08 8.780E+08 0.000E+00 5.620E+08 0.000E+00 3.720E+08 0.000E+00 4.100E+08 ZN-69 4.620E-13 8.800E-13 0.000E+00 5.750E-13 0.000E+00 1.620E-12 0.000E+00 6.160E-14 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.150E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.450E-24 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 5.670E+08 0.000E+00 0.000E+00 0.000E+00 8.400E+07 0.000E+00 2.670E+08 RB-88 0.000E+00 4.670E-46 0.000E+00 0.000E+00 0.000E+00 4.000E-53 0.000E+00 2.490E-46 RB-89 0.000E+00 9.190E-54 0.000E+00 0.000E+00 0.000E+00 1.410E-62 0.000E+00 6.500E-54 SR-89 5.620E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.690E+08 0.000E+00 1.610E+08 SR-90 1.390E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.900E+09 0.000E+00 3.430E+10 SR-91 1.120E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.060E+05 0.000E+00 4.440E+03 Appendix H Ri Teen Goat Milk - Page 1 of 3 Page 9-140

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.880E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.780E+01 0.000E+00 8.000E-02 Y-90 1.560E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.290E+05 0.000E+00 4.210E-01 Y-91 1.900E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.770E+05 0.000E+00 5.080E+01 Y-91M 1.310E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.200E-19 0.000E+00 5.020E-22 Y-92 1.240E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.390E-01 0.000E+00 3.580E-07 Y-93 4.940E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.510E+03 0.000E+00 1.360E-03 ZR-95 1.980E+02 6.250E+01 0.000E+00 9.180E+01 0.000E+00 1.440E+05 0.000E+00 4.300E+01 ZR-97 9.460E-02 1.870E-02 0.000E+00 2.840E-02 0.000E+00 5.070E+03 0.000E+00 8.620E-03 NB-95 1.690E+04 9.370E+03 0.000E+00 9.080E+03 0.000E+00 4.010E+07 0.000E+00 5.160E+03 MO-99 0.000E+00 5.370E+06 0.000E+00 1.230E+07 0.000E+00 9.610E+06 0.000E+00 1.020E+06 TC-99M 6.910E-01 1.930E+00 0.000E+00 2.870E+01 1.070E+00 1.270E+03 0.000E+00 2.500E+01 TC-101 5.690E-61 8.100E-61 0.000E+00 1.460E-59 4.930E-61 1.380E-67 0.000E+00 7.950E-60 RU-103 2.170E+02 0.000E+00 0.000E+00 7.660E+02 0.000E+00 1.810E+04 0.000E+00 9.290E+01 RU-105 1.880E-04 0.000E+00 0.000E+00 2.370E-03 0.000E+00 1.520E-01 0.000E+00 7.290E-05 RU-106 4.500E+03 0.000E+00 0.000E+00 8.680E+03 0.000E+00 2.160E+05 0.000E+00 5.670E+02 AG-110M 1.160E+07 1.090E+07 0.000E+00 2.080E+07 0.000E+00 3.070E+09 0.000E+00 6.650E+06 TE-125M 3.600E+06 1.300E+06 1.010E+06 0.000E+00 0.000E+00 1.060E+07 0.000E+00 4.820E+05 TE-127 1.450E+02 5.150E+01 1.000E+02 5.880E+02 0.000E+00 1.120E+04 0.000E+00 3.120E+01 TE-127M 1.010E+07 3.590E+06 2.410E+06 4.100E+07 0.000E+00 2.520E+07 0.000E+00 1.200E+06 TE-129 6.240E-11 2.330E-11 4.460E-11 2.620E-10 0.000E+00 3.410E-10 0.000E+00 1.520E-11 TE-129M 1.320E+07 4.900E+06 4.260E+06 5.530E+07 0.000E+00 4.960E+07 0.000E+00 2.090E+06 TE-131 7.900E-34 3.260E-34 6.090E-34 3.450E-33 0.000E+00 6.480E-35 0.000E+00 2.470E-34 TE-131M 7.880E+04 3.780E+04 5.690E+04 3.940E+05 0.000E+00 3.030E+06 0.000E+00 3.150E+04 TE-132 5.150E+05 3.260E+05 3.440E+05 3.130E+06 0.000E+00 1.030E+07 0.000E+00 3.070E+05 I-130 8.860E+05 2.560E+06 2.090E+08 3.950E+06 0.000E+00 1.970E+06 0.000E+00 1.020E+06 Appendix H Ri Teen Goat Milk - Page 2 of 3 Page 9-141

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 6.450E+08 9.030E+08 2.630E+11 1.550E+09 0.000E+00 1.790E+08 0.000E+00 4.850E+08 I-132 3.500E-01 9.150E-01 3.080E+01 1.440E+00 0.000E+00 3.980E-01 0.000E+00 3.280E-01 I-133 8.480E+06 1.440E+07 2.010E+09 2.520E+07 0.000E+00 1.090E+07 0.000E+00 4.390E+06 I-134 4.300E-12 1.140E-11 1.900E-10 1.800E-11 0.000E+00 1.500E-13 0.000E+00 4.090E-12 I-135 2.740E+04 7.040E+04 4.530E+06 1.110E+05 0.000E+00 7.810E+04 0.000E+00 2.610E+04 CS-134 2.940E+10 6.930E+10 0.000E+00 2.200E+10 8.410E+09 8.620E+08 0.000E+00 3.220E+10 CS-136 1.340E+09 5.290E+09 0.000E+00 2.880E+09 4.540E+08 4.260E+08 0.000E+00 3.550E+09 CS-137 4.020E+10 5.340E+10 0.000E+00 1.820E+10 7.060E+09 7.600E+08 0.000E+00 1.860E+10 CS-138 4.920E-23 9.450E-23 0.000E+00 6.980E-23 8.120E-24 4.290E-26 0.000E+00 4.730E-23 BA-139 9.800E-09 6.900E-12 0.000E+00 6.500E-12 4.750E-12 8.750E-08 0.000E+00 2.860E-10 BA-140 5.820E+06 7.130E+03 0.000E+00 2.420E+03 4.800E+03 8.980E+06 0.000E+00 3.750E+05 BA-141 9.030E-47 6.740E-50 0.000E+00 6.260E-50 4.610E-50 1.920E-52 0.000E+00 3.010E-48 BA-142 5.750E-81 5.750E-84 0.000E+00 4.860E-84 3.820E-84 1.760E-92 0.000E+00 3.540E-82 LA-140 9.720E-01 4.780E-01 0.000E+00 0.000E+00 0.000E+00 2.740E+04 0.000E+00 1.270E-01 LA-142 4.030E-12 1.790E-12 0.000E+00 0.000E+00 0.000E+00 5.440E-08 0.000E+00 4.450E-13 CE-141 1.070E+03 7.120E+02 0.000E+00 3.350E+02 0.000E+00 2.040E+06 0.000E+00 8.170E+01 CE-143 9.170E+00 6.670E+03 0.000E+00 2.990E+00 0.000E+00 2.000E+05 0.000E+00 7.450E-01 CE-144 7.900E+04 3.270E+04 0.000E+00 1.950E+04 0.000E+00 1.990E+07 0.000E+00 4.240E+03 PR-143 3.480E+01 1.390E+01 0.000E+00 8.080E+00 0.000E+00 1.150E+05 0.000E+00 1.730E+00 PR-144 1.300E-54 5.320E-55 0.000E+00 3.050E-55 0.000E+00 1.430E-57 0.000E+00 6.590E-56 ND-147 2.170E+01 2.360E+01 0.000E+00 1.390E+01 0.000E+00 8.530E+04 0.000E+00 1.420E+00 W-187 1.430E+03 1.170E+03 0.000E+00 0.000E+00 0.000E+00 3.150E+05 0.000E+00 4.080E+02 NP-239 8.410E-01 7.930E-02 0.000E+00 2.490E-01 0.000E+00 1.280E+04 0.000E+00 4.410E-02 Appendix H Ri Teen Goat Milk - Page 3 of 3 Page 9-142

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 0.000E+00 1.940E+02 C-14 1.740E+04 3.490E+03 3.490E+03 3.490E+03 3.490E+03 3.490E+03 0.000E+00 3.490E+03 NA-24 1.080E-03 1.080E-03 1.080E-03 1.080E-03 1.080E-03 1.080E-03 0.000E+00 1.080E-03 P-32 3.930E+09 2.440E+08 0.000E+00 0.000E+00 0.000E+00 3.310E+08 0.000E+00 1.530E+08 CR-51 0.000E+00 0.000E+00 3.130E+03 1.240E+03 8.050E+03 9.470E+05 0.000E+00 5.640E+03 MN-54 0.000E+00 7.000E+06 0.000E+00 2.090E+06 0.000E+00 1.440E+07 0.000E+00 1.390E+06 MN-56 0.000E+00 1.070E-53 0.000E+00 1.360E-53 0.000E+00 7.070E-52 0.000E+00 1.910E-54 FE-55 2.380E+08 1.690E+08 0.000E+00 0.000E+00 1.070E+08 7.310E+07 0.000E+00 3.940E+07 FE-59 2.120E+08 4.950E+08 0.000E+00 0.000E+00 1.560E+08 1.170E+09 0.000E+00 1.910E+08 CO-58 0.000E+00 1.410E+07 0.000E+00 0.000E+00 0.000E+00 1.940E+08 0.000E+00 3.240E+07 CO-60 0.000E+00 5.830E+07 0.000E+00 0.000E+00 0.000E+00 7.600E+08 0.000E+00 1.310E+08 NI-63 1.520E+10 1.070E+09 0.000E+00 0.000E+00 0.000E+00 1.710E+08 0.000E+00 5.150E+08 NI-65 1.880E-52 2.410E-53 0.000E+00 0.000E+00 0.000E+00 1.300E-51 0.000E+00 1.100E-53 CU-64 0.000E+00 2.210E-07 0.000E+00 5.600E-07 0.000E+00 1.720E-05 0.000E+00 1.040E-07 ZN-65 2.500E+08 8.690E+08 0.000E+00 5.560E+08 0.000E+00 3.680E+08 0.000E+00 4.050E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.070E-57 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.070E+08 0.000E+00 0.000E+00 0.000E+00 6.020E+07 0.000E+00 1.910E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 2.550E+08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.030E+07 0.000E+00 7.290E+06 SR-90 8.050E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.260E+08 0.000E+00 1.990E+09 SR-91 1.280E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.800E-10 0.000E+00 5.090E-12 Appendix H Ri Teen Cow Meat - Page 1 of 3 Page 9-143

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 9.880E-50 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.520E-48 0.000E+00 4.210E-51 Y-90 9.060E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.470E+05 0.000E+00 2.440E+00 Y-91 9.540E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.910E+08 0.000E+00 2.560E+04 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-92 1.280E-39 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.520E-35 0.000E+00 3.710E-41 Y-93 3.960E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.210E-07 0.000E+00 1.090E-13 ZR-95 1.500E+06 4.730E+05 0.000E+00 6.950E+05 0.000E+00 1.090E+09 0.000E+00 3.250E+05 ZR-97 1.720E-05 3.410E-06 0.000E+00 5.170E-06 0.000E+00 9.230E-01 0.000E+00 1.570E-06 NB-95 1.790E+06 9.950E+05 0.000E+00 9.650E+05 0.000E+00 4.260E+09 0.000E+00 5.480E+05 MO-99 0.000E+00 8.270E+04 0.000E+00 1.890E+05 0.000E+00 1.480E+05 0.000E+00 1.580E+04 TC-99M 3.530E-21 9.850E-21 0.000E+00 1.470E-19 5.470E-21 6.470E-18 0.000E+00 1.280E-19 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 8.570E+07 0.000E+00 0.000E+00 3.020E+08 0.000E+00 7.160E+09 0.000E+00 3.660E+07 RU-105 4.830E-28 0.000E+00 0.000E+00 6.090E-27 0.000E+00 3.900E-25 0.000E+00 1.880E-28 RU-106 2.360E+09 0.000E+00 0.000E+00 4.550E+09 0.000E+00 1.130E+11 0.000E+00 2.970E+08 AG-110M 5.060E+06 4.790E+06 0.000E+00 9.130E+06 0.000E+00 1.340E+09 0.000E+00 2.910E+06 TE-125M 3.030E+08 1.090E+08 8.470E+07 0.000E+00 0.000E+00 8.940E+08 0.000E+00 4.050E+07 TE-127 1.800E-10 6.380E-11 1.240E-10 7.290E-10 0.000E+00 1.390E-08 0.000E+00 3.870E-11 TE-127M 9.410E+08 3.340E+08 2.240E+08 3.820E+09 0.000E+00 2.350E+09 0.000E+00 1.120E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-129M 9.500E+08 3.530E+08 3.070E+08 3.970E+09 0.000E+00 3.570E+09 0.000E+00 1.500E+08 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 3.760E+02 1.800E+02 2.710E+02 1.880E+03 0.000E+00 1.450E+04 0.000E+00 1.500E+02 TE-132 1.160E+06 7.360E+05 7.750E+05 7.060E+06 0.000E+00 2.330E+07 0.000E+00 6.920E+05 I-130 1.700E-06 4.910E-06 4.000E-04 7.560E-06 0.000E+00 3.770E-06 0.000E+00 1.960E-06 Appendix H Ri Teen Cow Meat - Page 2 of 3 Page 9-144

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 8.920E+06 1.250E+07 3.650E+09 2.150E+07 0.000E+00 2.470E+06 0.000E+00 6.710E+06 I-132 5.660E-59 1.480E-58 4.990E-57 2.330E-58 0.000E+00 6.450E-59 0.000E+00 5.320E-59 I-133 3.050E-01 5.180E-01 7.230E+01 9.090E-01 0.000E+00 3.920E-01 0.000E+00 1.580E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 3.600E-17 9.260E-17 5.960E-15 1.460E-16 0.000E+00 1.030E-16 0.000E+00 3.430E-17 CS-134 5.230E+08 1.230E+09 0.000E+00 3.910E+08 1.490E+08 1.530E+07 0.000E+00 5.710E+08 CS-136 9.400E+06 3.700E+07 0.000E+00 2.010E+07 3.170E+06 2.980E+06 0.000E+00 2.480E+07 CS-137 7.240E+08 9.630E+08 0.000E+00 3.280E+08 1.270E+08 1.370E+07 0.000E+00 3.360E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 2.380E+07 2.910E+04 0.000E+00 9.870E+03 1.960E+04 3.660E+07 0.000E+00 1.530E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 3.050E-02 1.500E-02 0.000E+00 0.000E+00 0.000E+00 8.610E+02 0.000E+00 3.990E-03 LA-142 2.870E-92 1.280E-92 0.000E+00 0.000E+00 0.000E+00 3.880E-88 0.000E+00 3.180E-93 CE-141 1.180E+04 7.870E+03 0.000E+00 3.710E+03 0.000E+00 2.250E+07 0.000E+00 9.040E+02 CE-143 1.690E-02 1.230E+01 0.000E+00 5.510E-03 0.000E+00 3.690E+02 0.000E+00 1.370E-03 CE-144 1.230E+06 5.080E+05 0.000E+00 3.040E+05 0.000E+00 3.090E+08 0.000E+00 6.600E+04 PR-143 1.760E+04 7.040E+03 0.000E+00 4.090E+03 0.000E+00 5.800E+07 0.000E+00 8.780E+02 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 6.230E+03 6.770E+03 0.000E+00 3.980E+03 0.000E+00 2.440E+07 0.000E+00 4.060E+02 W-187 1.730E-02 1.410E-02 0.000E+00 0.000E+00 0.000E+00 3.820E+00 0.000E+00 4.940E-03 NP-239 2.260E-01 2.140E-02 0.000E+00 6.700E-02 0.000E+00 3.440E+03 0.000E+00 1.190E-02 Appendix H Ri Teen Cow Meat - Page 3 of 3 Page 9-145

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Vegetation (VEG) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 0.000E+00 2.590E+03 C-14 9.010E+04 1.800E+04 1.800E+04 1.800E+04 1.800E+04 1.800E+04 0.000E+00 1.800E+04 NA-24 2.390E+05 2.390E+05 2.390E+05 2.390E+05 2.390E+05 2.390E+05 0.000E+00 2.390E+05 P-32 1.610E+09 9.970E+07 0.000E+00 0.000E+00 0.000E+00 1.350E+08 0.000E+00 6.240E+07 CR-51 0.000E+00 0.000E+00 3.430E+04 1.350E+04 8.810E+04 1.040E+07 0.000E+00 6.170E+04 MN-54 0.000E+00 4.540E+08 0.000E+00 1.360E+08 0.000E+00 9.320E+08 0.000E+00 9.010E+07 MN-56 0.000E+00 1.420E+01 0.000E+00 1.800E+01 0.000E+00 9.360E+02 0.000E+00 2.530E+00 FE-55 3.260E+08 2.310E+08 0.000E+00 0.000E+00 1.470E+08 1.000E+08 0.000E+00 5.390E+07 FE-59 1.790E+08 4.190E+08 0.000E+00 0.000E+00 1.320E+08 9.900E+08 0.000E+00 1.620E+08 CO-58 0.000E+00 4.360E+07 0.000E+00 0.000E+00 0.000E+00 6.010E+08 0.000E+00 1.000E+08 CO-60 0.000E+00 2.490E+08 0.000E+00 0.000E+00 0.000E+00 3.240E+09 0.000E+00 5.600E+08 NI-63 1.610E+10 1.130E+09 0.000E+00 0.000E+00 0.000E+00 1.810E+08 0.000E+00 5.450E+08 NI-65 5.720E+01 7.310E+00 0.000E+00 0.000E+00 0.000E+00 3.970E+02 0.000E+00 3.330E+00 CU-64 0.000E+00 8.340E+03 0.000E+00 2.110E+04 0.000E+00 6.470E+05 0.000E+00 3.920E+03 ZN-65 4.240E+08 1.470E+09 0.000E+00 9.420E+08 0.000E+00 6.230E+08 0.000E+00 6.870E+08 ZN-69 5.140E-06 9.800E-06 0.000E+00 6.400E-06 0.000E+00 1.810E-05 0.000E+00 6.860E-07 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.910E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.250E-11 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.740E+08 0.000E+00 0.000E+00 0.000E+00 4.050E+07 0.000E+00 1.290E+08 RB-88 0.000E+00 3.170E-22 0.000E+00 0.000E+00 0.000E+00 2.720E-29 0.000E+00 1.690E-22 RB-89 0.000E+00 3.500E-26 0.000E+00 0.000E+00 0.000E+00 5.360E-35 0.000E+00 2.470E-26 SR-89 1.510E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.800E+09 0.000E+00 4.340E+08 SR-90 7.510E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.110E+10 0.000E+00 1.850E+11 SR-91 2.850E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.290E+06 0.000E+00 1.130E+04 Appendix H Ri Teen Vegetation - Page 1 of 3 Page 9-146

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Vegetation (VEG) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 3.970E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.010E+04 0.000E+00 1.690E+01 Y-90 1.240E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.020E+08 0.000E+00 3.350E+02 Y-91 7.840E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.210E+09 0.000E+00 2.100E+05 Y-91M 4.860E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.290E-07 0.000E+00 1.860E-10 Y-92 8.600E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.360E+04 0.000E+00 2.490E-02 Y-93 1.590E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.860E+06 0.000E+00 4.360E+00 ZR-95 1.720E+06 5.430E+05 0.000E+00 7.980E+05 0.000E+00 1.250E+09 0.000E+00 3.730E+05 ZR-97 3.120E+02 6.180E+01 0.000E+00 9.370E+01 0.000E+00 1.670E+07 0.000E+00 2.850E+01 NB-95 1.920E+05 1.070E+05 0.000E+00 1.030E+05 0.000E+00 4.560E+08 0.000E+00 5.870E+04 MO-99 0.000E+00 5.650E+06 0.000E+00 1.290E+07 0.000E+00 1.010E+07 0.000E+00 1.080E+06 TC-99M 2.740E+00 7.630E+00 0.000E+00 1.140E+02 4.240E+00 5.010E+03 0.000E+00 9.890E+01 TC-101 7.640E-31 1.090E-30 0.000E+00 1.970E-29 6.620E-31 1.860E-37 0.000E+00 1.070E-29 RU-103 6.820E+06 0.000E+00 0.000E+00 2.400E+07 0.000E+00 5.700E+08 0.000E+00 2.920E+06 RU-105 5.000E+01 0.000E+00 0.000E+00 6.310E+02 0.000E+00 4.040E+04 0.000E+00 1.940E+01 RU-106 3.100E+08 0.000E+00 0.000E+00 5.970E+08 0.000E+00 1.480E+10 0.000E+00 3.900E+07 AG-110M 1.520E+07 1.430E+07 0.000E+00 2.740E+07 0.000E+00 4.030E+09 0.000E+00 8.720E+06 TE-125M 1.480E+08 5.340E+07 4.140E+07 0.000E+00 0.000E+00 4.370E+08 0.000E+00 1.980E+07 TE-127 5.330E+03 1.890E+03 3.680E+03 2.160E+04 0.000E+00 4.120E+05 0.000E+00 1.150E+03 TE-127M 5.510E+08 1.960E+08 1.310E+08 2.240E+09 0.000E+00 1.370E+09 0.000E+00 6.560E+07 TE-129 7.140E-04 2.660E-04 5.100E-04 3.000E-03 0.000E+00 3.910E-03 0.000E+00 1.740E-04 TE-129M 3.620E+08 1.340E+08 1.170E+08 1.510E+09 0.000E+00 1.360E+09 0.000E+00 5.730E+07 TE-131 1.390E-15 5.750E-16 1.070E-15 6.100E-15 0.000E+00 1.140E-16 0.000E+00 4.360E-16 TE-131M 8.440E+05 4.050E+05 6.090E+05 4.220E+06 0.000E+00 3.250E+07 0.000E+00 3.380E+05 TE-132 3.910E+06 2.470E+06 2.610E+06 2.370E+07 0.000E+00 7.840E+07 0.000E+00 2.330E+06 I-130 3.510E+05 1.010E+06 8.280E+07 1.560E+06 0.000E+00 7.800E+05 0.000E+00 4.050E+05 Appendix H Ri Teen Vegetation - Page 2 of 3 Page 9-147

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Vegetation (VEG) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 7.690E+07 1.080E+08 3.140E+10 1.850E+08 0.000E+00 2.130E+07 0.000E+00 5.780E+07 I-132 5.190E+01 1.360E+02 4.580E+03 2.140E+02 0.000E+00 5.920E+01 0.000E+00 4.880E+01 I-133 1.940E+06 3.290E+06 4.590E+08 5.760E+06 0.000E+00 2.490E+06 0.000E+00 1.000E+06 I-134 8.720E-05 2.310E-04 3.850E-03 3.640E-04 0.000E+00 3.050E-06 0.000E+00 8.310E-05 I-135 3.520E+04 9.070E+04 5.830E+06 1.430E+05 0.000E+00 1.000E+05 0.000E+00 3.360E+04 CS-134 7.100E+09 1.670E+10 0.000E+00 5.310E+09 2.030E+09 2.080E+08 0.000E+00 7.750E+09 CS-136 4.370E+07 1.720E+08 0.000E+00 9.370E+07 1.480E+07 1.380E+07 0.000E+00 1.160E+08 CS-137 1.010E+10 1.350E+10 0.000E+00 4.590E+09 1.780E+09 1.920E+08 0.000E+00 4.690E+09 CS-138 3.610E-11 6.940E-11 0.000E+00 5.120E-11 5.960E-12 3.150E-14 0.000E+00 3.470E-11 BA-139 2.690E-02 1.890E-05 0.000E+00 1.780E-05 1.300E-05 2.400E-01 0.000E+00 7.830E-04 BA-140 1.380E+08 1.690E+05 0.000E+00 5.740E+04 1.140E+05 2.130E+08 0.000E+00 8.900E+06 BA-141 1.080E-21 8.040E-25 0.000E+00 7.460E-25 5.500E-25 2.290E-27 0.000E+00 3.590E-23 BA-142 5.490E-39 5.490E-42 0.000E+00 4.640E-42 3.650E-42 1.680E-50 0.000E+00 3.380E-40 LA-140 1.810E+03 8.880E+02 0.000E+00 0.000E+00 0.000E+00 5.100E+07 0.000E+00 2.360E+02 LA-142 1.850E-04 8.240E-05 0.000E+00 0.000E+00 0.000E+00 2.510E+00 0.000E+00 2.050E-05 CE-141 2.830E+05 1.890E+05 0.000E+00 8.890E+04 0.000E+00 5.400E+08 0.000E+00 2.170E+04 CE-143 9.330E+02 6.790E+05 0.000E+00 3.040E+02 0.000E+00 2.040E+07 0.000E+00 7.580E+01 CE-144 5.270E+07 2.180E+07 0.000E+00 1.300E+07 0.000E+00 1.330E+10 0.000E+00 2.830E+06 PR-143 7.000E+04 2.800E+04 0.000E+00 1.630E+04 0.000E+00 2.300E+08 0.000E+00 3.490E+03 PR-144 2.900E-26 1.190E-26 0.000E+00 6.800E-27 0.000E+00 3.190E-29 0.000E+00 1.470E-27 ND-147 3.620E+04 3.940E+04 0.000E+00 2.310E+04 0.000E+00 1.420E+08 0.000E+00 2.360E+03 W-187 3.540E+04 2.880E+04 0.000E+00 0.000E+00 0.000E+00 7.800E+06 0.000E+00 1.010E+04 NP-239 1.390E+03 1.310E+02 0.000E+00 4.100E+02 0.000E+00 2.100E+07 0.000E+00 7.260E+01 Appendix H Ri Teen Vegetation - Page 3 of 3 Page 9-148

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.270E+03 1.270E+03 1.270E+03 1.270E+03 1.270E+03 0.000E+00 1.270E+03 C-14 2.600E+04 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 0.000E+00 4.870E+03 NA-24 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 0.000E+00 1.380E+04 P-32 1.890E+06 1.100E+05 0.000E+00 0.000E+00 0.000E+00 9.280E+04 0.000E+00 7.160E+04 CR-51 0.000E+00 0.000E+00 7.500E+01 3.070E+01 2.100E+04 3.000E+03 0.000E+00 1.350E+02 MN-54 0.000E+00 5.110E+04 0.000E+00 1.270E+04 1.980E+06 6.680E+04 0.000E+00 8.400E+03 MN-56 0.000E+00 1.700E+00 0.000E+00 1.790E+00 1.520E+04 5.740E+04 0.000E+00 2.520E-01 FE-55 3.340E+04 2.380E+04 0.000E+00 0.000E+00 1.240E+05 6.390E+03 0.000E+00 5.540E+03 FE-59 1.590E+04 3.700E+04 0.000E+00 0.000E+00 1.530E+06 1.780E+05 0.000E+00 1.430E+04 CO-58 0.000E+00 2.070E+03 0.000E+00 0.000E+00 1.340E+06 9.520E+04 0.000E+00 2.780E+03 CO-60 0.000E+00 1.510E+04 0.000E+00 0.000E+00 8.720E+06 2.590E+05 0.000E+00 1.980E+04 NI-63 5.800E+05 4.340E+04 0.000E+00 0.000E+00 3.070E+05 1.420E+04 0.000E+00 1.980E+04 NI-65 2.180E+00 2.930E-01 0.000E+00 0.000E+00 9.360E+03 3.670E+04 0.000E+00 1.270E-01 CU-64 0.000E+00 2.030E+00 0.000E+00 6.410E+00 1.110E+04 6.140E+04 0.000E+00 8.480E-01 ZN-65 3.860E+04 1.340E+05 0.000E+00 8.640E+04 1.240E+06 4.660E+04 0.000E+00 6.240E+04 ZN-69 4.830E-02 9.200E-02 0.000E+00 6.020E-02 1.580E+03 2.850E+02 0.000E+00 6.460E-03 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.440E+02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.330E+02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.830E+01 RB-86 0.000E+00 1.900E+05 0.000E+00 0.000E+00 0.000E+00 1.770E+04 0.000E+00 8.400E+04 RB-88 0.000E+00 5.460E+02 0.000E+00 0.000E+00 0.000E+00 2.920E-05 0.000E+00 2.720E+02 RB-89 0.000E+00 3.520E+02 0.000E+00 0.000E+00 0.000E+00 3.380E-07 0.000E+00 2.330E+02 SR-89 4.340E+05 0.000E+00 0.000E+00 0.000E+00 2.420E+06 3.710E+05 0.000E+00 1.250E+04 SR-90 1.080E+08 0.000E+00 0.000E+00 0.000E+00 1.650E+07 7.650E+05 0.000E+00 6.680E+06 SR-91 8.800E+01 0.000E+00 0.000E+00 0.000E+00 6.070E+04 2.590E+05 0.000E+00 3.510E+00 Appendix H Ri Teen Inhalation - Page 1 of 3 Page 9-149

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 9.520E+00 0.000E+00 0.000E+00 0.000E+00 2.740E+04 1.190E+05 0.000E+00 4.060E-01 Y-90 2.980E+03 0.000E+00 0.000E+00 0.000E+00 2.930E+05 5.590E+05 0.000E+00 8.000E+01 Y-91 6.610E+05 0.000E+00 0.000E+00 0.000E+00 2.940E+06 4.090E+05 0.000E+00 1.770E+04 Y-91M 3.700E-01 0.000E+00 0.000E+00 0.000E+00 3.200E+03 3.020E+01 0.000E+00 1.420E-02 Y-92 1.470E+01 0.000E+00 0.000E+00 0.000E+00 2.680E+04 1.650E+05 0.000E+00 4.290E-01 Y-93 1.350E+02 0.000E+00 0.000E+00 0.000E+00 8.320E+04 5.790E+05 0.000E+00 3.720E+00 ZR-95 1.460E+05 4.580E+04 0.000E+00 6.740E+04 2.690E+06 1.490E+05 0.000E+00 3.150E+04 ZR-97 1.380E+02 2.720E+01 0.000E+00 4.120E+01 1.300E+05 6.300E+05 0.000E+00 1.260E+01 NB-95 1.860E+04 1.030E+04 0.000E+00 1.000E+04 7.510E+05 9.680E+04 0.000E+00 5.660E+03 MO-99 0.000E+00 1.690E+02 0.000E+00 4.110E+02 1.540E+05 2.690E+05 0.000E+00 3.220E+01 TC-99M 1.380E-03 3.860E-03 0.000E+00 5.760E-02 1.150E+03 6.130E+03 0.000E+00 4.990E-02 TC-101 5.920E-05 8.400E-05 0.000E+00 1.520E-03 6.670E+02 8.720E-07 0.000E+00 8.240E-04 RU-103 2.100E+03 0.000E+00 0.000E+00 7.430E+03 7.830E+05 1.090E+05 0.000E+00 8.960E+02 RU-105 1.120E+00 0.000E+00 0.000E+00 1.410E+00 1.820E+04 9.040E+04 0.000E+00 4.340E-01 RU-106 9.840E+04 0.000E+00 0.000E+00 1.900E+05 1.610E+07 9.600E+05 0.000E+00 1.240E+04 AG-110M 1.380E+04 1.310E+04 0.000E+00 2.500E+04 6.750E+06 2.730E+05 0.000E+00 7.990E+03 TE-125M 4.880E+03 2.240E+03 1.400E+03 0.000E+00 5.360E+05 7.500E+04 0.000E+00 6.670E+02 TE-127 2.010E+00 9.120E-01 1.420E+00 7.280E+00 1.120E+04 8.080E+04 0.000E+00 4.420E-01 TE-127M 1.800E+04 8.160E+03 4.380E+03 6.540E+04 1.660E+06 1.590E+05 0.000E+00 2.180E+03 TE-129 7.100E-02 3.380E-02 5.180E-02 2.660E-01 3.300E+03 1.620E+03 0.000E+00 1.760E-02 TE-129M 1.390E+04 6.580E+03 4.580E+03 5.190E+04 1.980E+06 4.050E+05 0.000E+00 2.250E+03 TE-131 1.580E-02 8.320E-03 1.240E-02 6.180E-02 2.340E+03 1.510E+01 0.000E+00 5.040E-03 TE-131M 9.840E+01 6.010E+01 7.250E+01 4.390E+02 2.380E+05 6.210E+05 0.000E+00 4.020E+01 TE-132 3.600E+02 2.900E+02 2.460E+02 1.950E+03 4.490E+05 4.630E+05 0.000E+00 2.190E+02 I-130 6.240E+03 1.790E+04 1.490E+06 2.750E+04 0.000E+00 9.120E+03 0.000E+00 7.170E+03 Appendix H Ri Teen Inhalation - Page 2 of 3 Page 9-150

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.540E+04 4.910E+04 1.460E+07 8.400E+04 0.000E+00 6.490E+03 0.000E+00 2.640E+04 I-132 1.590E+03 4.380E+03 1.510E+05 6.920E+03 0.000E+00 1.270E+03 0.000E+00 1.580E+03 I-133 1.220E+04 2.050E+04 2.920E+06 3.590E+04 0.000E+00 1.030E+04 0.000E+00 6.220E+03 I-134 8.880E+02 2.320E+03 3.950E+04 3.660E+03 0.000E+00 2.040E+01 0.000E+00 8.400E+02 I-135 3.700E+03 9.440E+03 6.210E+05 1.490E+04 0.000E+00 6.950E+03 0.000E+00 3.490E+03 CS-134 5.020E+05 1.130E+06 0.000E+00 3.750E+05 1.460E+05 9.760E+03 0.000E+00 5.490E+05 CS-136 5.150E+04 1.940E+05 0.000E+00 1.100E+05 1.780E+04 1.090E+04 0.000E+00 1.370E+05 CS-137 6.700E+05 8.480E+05 0.000E+00 3.040E+05 1.210E+05 8.480E+03 0.000E+00 3.110E+05 CS-138 4.660E+02 8.560E+02 0.000E+00 6.620E+02 7.870E+01 2.700E-01 0.000E+00 4.460E+02 BA-139 1.340E+00 9.440E-04 0.000E+00 8.880E-04 6.460E+03 6.450E+03 0.000E+00 3.900E-02 BA-140 5.470E+04 6.700E+01 0.000E+00 2.280E+01 2.030E+06 2.290E+05 0.000E+00 3.520E+03 BA-141 1.420E-01 1.060E-04 0.000E+00 9.840E-05 3.290E+03 7.460E-04 0.000E+00 4.740E-03 BA-142 3.700E-02 3.700E-05 0.000E+00 3.140E-05 1.910E+03 4.790E-10 0.000E+00 2.270E-03 LA-140 4.790E+02 2.360E+02 0.000E+00 0.000E+00 2.140E+05 4.870E+05 0.000E+00 6.260E+01 LA-142 9.600E-01 4.250E-01 0.000E+00 0.000E+00 1.020E+04 1.200E+04 0.000E+00 1.060E-01 CE-141 2.840E+04 1.900E+04 0.000E+00 8.880E+03 6.140E+05 1.260E+05 0.000E+00 2.170E+03 CE-143 2.660E+02 1.940E+02 0.000E+00 8.640E+01 1.300E+05 2.550E+05 0.000E+00 2.160E+01 CE-144 4.890E+06 2.020E+06 0.000E+00 1.210E+06 1.340E+07 8.640E+05 0.000E+00 2.620E+05 PR-143 1.340E+04 5.310E+03 0.000E+00 3.090E+03 4.830E+05 2.140E+05 0.000E+00 6.620E+02 PR-144 4.300E-02 1.760E-02 0.000E+00 1.010E-02 1.750E+03 2.350E-04 0.000E+00 2.180E-03 ND-147 7.860E+03 8.560E+03 0.000E+00 5.020E+03 3.720E+05 1.820E+05 0.000E+00 5.130E+02 W-187 1.200E+01 9.760E+00 0.000E+00 0.000E+00 4.740E+04 1.770E+05 0.000E+00 3.430E+00 NP-239 3.380E+02 3.190E+01 0.000E+00 1.000E+02 6.490E+04 1.320E+05 0.000E+00 1.770E+01 Appendix H Ri Teen Inhalation - Page 3 of 3 Page 9-151

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.390E+07 1.190E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530E+10 2.150E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.150E+06 Appendix H Ri Teen Ground Plane Deposition - Page 1 of 3 Page 9-152

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.310E+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.110E+05 1.840E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-110M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 TE-127 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04 TE-129 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 TE-129M 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 I-130 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.510E+06 Appendix H Ri Teen Ground Plane Deposition - Page 2 of 3 Page 9-153

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.090E+07 1.720E+07 I-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 I-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2.450E+06 I-134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 I-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS-134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.000E+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.710E+08 1.510E+08 CS-137 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 4.100E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.110E+04 4.490E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 2.110E+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.980E+06 1.710E+06 Appendix H Ri Teen Ground Plane Deposition - Page 3 of 3 Page 9-154

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.570E+03 1.570E+03 1.570E+03 1.570E+03 1.570E+03 0.000E+00 1.570E+03 C-14 1.020E+05 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 0.000E+00 2.040E+04 NA-24 8.850E+06 8.850E+06 8.850E+06 8.850E+06 8.850E+06 8.850E+06 0.000E+00 8.850E+06 P-32 7.780E+10 3.640E+09 0.000E+00 0.000E+00 0.000E+00 2.150E+09 0.000E+00 3.000E+09 CR-51 0.000E+00 0.000E+00 5.650E+04 1.540E+04 1.030E+05 5.400E+06 0.000E+00 1.020E+05 MN-54 0.000E+00 2.100E+07 0.000E+00 5.880E+06 0.000E+00 1.760E+07 0.000E+00 5.590E+06 MN-56 0.000E+00 1.260E-02 0.000E+00 1.530E-02 0.000E+00 1.830E+00 0.000E+00 2.860E-03 FE-55 1.120E+08 5.930E+07 0.000E+00 0.000E+00 3.350E+07 1.100E+07 0.000E+00 1.840E+07 FE-59 1.200E+08 1.950E+08 0.000E+00 0.000E+00 5.640E+07 2.030E+08 0.000E+00 9.690E+07 CO-58 0.000E+00 1.210E+07 0.000E+00 0.000E+00 0.000E+00 7.070E+07 0.000E+00 3.710E+07 CO-60 0.000E+00 4.320E+07 0.000E+00 0.000E+00 0.000E+00 2.390E+08 0.000E+00 1.270E+08 NI-63 2.960E+10 1.590E+09 0.000E+00 0.000E+00 0.000E+00 1.070E+08 0.000E+00 1.010E+09 NI-65 1.660E+00 1.560E-01 0.000E+00 0.000E+00 0.000E+00 1.910E+01 0.000E+00 9.100E-02 CU-64 0.000E+00 7.460E+04 0.000E+00 1.800E+05 0.000E+00 3.500E+06 0.000E+00 4.510E+04 ZN-65 4.130E+09 1.100E+10 0.000E+00 6.940E+09 0.000E+00 1.930E+09 0.000E+00 6.850E+09 ZN-69 9.460E-12 1.370E-11 0.000E+00 8.300E-12 0.000E+00 8.620E-10 0.000E+00 1.260E-12 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.400E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.510E-23 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 8.770E+09 0.000E+00 0.000E+00 0.000E+00 5.640E+08 0.000E+00 5.390E+09 RB-88 0.000E+00 7.160E-45 0.000E+00 0.000E+00 0.000E+00 3.510E-46 0.000E+00 4.970E-45 RB-89 0.000E+00 1.340E-52 0.000E+00 0.000E+00 0.000E+00 1.170E-54 0.000E+00 1.190E-52 SR-89 6.620E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.560E+08 0.000E+00 1.890E+08 SR-90 1.120E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.510E+09 0.000E+00 2.830E+10 SR-91 1.300E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.880E+05 0.000E+00 4.920E+03 Appendix I Ri Child Cow Milk - Page 1 of 3 Page 9-155

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 2.180E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.130E+01 0.000E+00 8.750E-02 Y-90 3.220E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.170E+05 0.000E+00 8.620E+00 Y-91 3.900E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.200E+06 0.000E+00 1.040E+03 Y-91M 2.670E-19 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.240E-16 0.000E+00 9.730E-21 Y-92 2.530E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.310E+00 0.000E+00 7.240E-06 Y-93 1.010E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.510E+04 0.000E+00 2.780E-02 ZR-95 3.830E+03 8.420E+02 0.000E+00 1.210E+03 0.000E+00 8.790E+05 0.000E+00 7.500E+02 ZR-97 1.920E+00 2.770E-01 0.000E+00 3.980E-01 0.000E+00 4.200E+04 0.000E+00 1.640E-01 NB-95 3.180E+05 1.240E+05 0.000E+00 1.160E+05 0.000E+00 2.290E+08 0.000E+00 8.840E+04 MO-99 0.000E+00 8.140E+07 0.000E+00 1.740E+08 0.000E+00 6.730E+07 0.000E+00 2.010E+07 TC-99M 1.320E+01 2.590E+01 0.000E+00 3.760E+02 1.320E+01 1.470E+04 0.000E+00 4.290E+02 TC-101 1.160E-59 1.220E-59 0.000E+00 2.080E-58 6.440E-60 3.870E-59 0.000E+00 1.540E-58 RU-103 4.280E+03 0.000E+00 0.000E+00 1.080E+04 0.000E+00 1.110E+05 0.000E+00 1.650E+03 RU-105 3.820E-03 0.000E+00 0.000E+00 3.360E-02 0.000E+00 2.490E+00 0.000E+00 1.390E-03 RU-106 9.240E+04 0.000E+00 0.000E+00 1.250E+05 0.000E+00 1.440E+06 0.000E+00 1.150E+04 AG-110M 2.090E+08 1.410E+08 0.000E+00 2.630E+08 0.000E+00 1.680E+10 0.000E+00 1.130E+08 TE-125M 7.380E+07 2.000E+07 2.070E+07 0.000E+00 0.000E+00 7.120E+07 0.000E+00 9.840E+06 TE-127 2.980E+03 8.020E+02 2.060E+03 8.470E+03 0.000E+00 1.160E+05 0.000E+00 6.380E+02 TE-127M 2.080E+08 5.600E+07 4.970E+07 5.930E+08 0.000E+00 1.680E+08 0.000E+00 2.470E+07 TE-129 1.280E-09 3.580E-10 9.160E-10 3.750E-09 0.000E+00 7.990E-08 0.000E+00 3.050E-10 TE-129M 2.710E+08 7.580E+07 8.750E+07 7.970E+08 0.000E+00 3.310E+08 0.000E+00 4.210E+07 TE-131 1.620E-32 4.920E-33 1.240E-32 4.890E-32 0.000E+00 8.490E-32 0.000E+00 4.810E-33 TE-131M 1.600E+06 5.530E+05 1.140E+06 5.350E+06 0.000E+00 2.240E+07 0.000E+00 5.890E+05 TE-132 1.020E+07 4.530E+06 6.600E+06 4.210E+07 0.000E+00 4.570E+07 0.000E+00 5.480E+06 I-130 1.730E+06 3.490E+06 3.840E+08 5.220E+06 0.000E+00 1.630E+06 0.000E+00 1.800E+06 Appendix I Ri Child Cow Milk - Page 2 of 3 Page 9-156

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.300E+09 1.310E+09 4.330E+11 2.150E+09 0.000E+00 1.170E+08 0.000E+00 7.450E+08 I-132 6.890E-01 1.270E+00 5.870E+01 1.940E+00 0.000E+00 1.490E+00 0.000E+00 5.820E-01 I-133 1.720E+07 2.120E+07 3.940E+09 3.540E+07 0.000E+00 8.560E+06 0.000E+00 8.030E+06 I-134 8.480E-12 1.570E-11 3.620E-10 2.410E-11 0.000E+00 1.040E-11 0.000E+00 7.250E-12 I-135 5.400E+04 9.720E+04 8.610E+06 1.490E+05 0.000E+00 7.400E+04 0.000E+00 4.600E+04 CS-134 2.260E+10 3.720E+10 0.000E+00 1.150E+10 4.130E+09 2.000E+08 0.000E+00 7.840E+09 CS-136 1.010E+09 2.780E+09 0.000E+00 1.480E+09 2.210E+08 9.770E+07 0.000E+00 1.800E+09 CS-137 3.220E+10 3.090E+10 0.000E+00 1.010E+10 3.620E+09 1.930E+08 0.000E+00 4.550E+09 CS-138 3.980E-23 5.530E-23 0.000E+00 3.890E-23 4.190E-24 2.550E-23 0.000E+00 3.510E-23 BA-139 2.010E-07 1.070E-10 0.000E+00 9.360E-11 6.300E-11 1.160E-05 0.000E+00 5.820E-09 BA-140 1.170E+08 1.030E+05 0.000E+00 3.340E+04 6.120E+04 5.930E+07 0.000E+00 6.840E+06 BA-141 1.850E-45 1.040E-48 0.000E+00 8.960E-49 6.090E-48 1.050E-45 0.000E+00 6.020E-47 BA-142 1.150E-79 8.310E-83 0.000E+00 6.720E-83 4.890E-83 1.510E-81 0.000E+00 6.450E-81 LA-140 1.940E+01 6.780E+00 0.000E+00 0.000E+00 0.000E+00 1.890E+05 0.000E+00 2.290E+00 LA-142 8.100E-11 2.580E-11 0.000E+00 0.000E+00 0.000E+00 5.120E-06 0.000E+00 8.090E-12 CE-141 2.190E+04 1.090E+04 0.000E+00 4.780E+03 0.000E+00 1.360E+07 0.000E+00 1.620E+03 CE-143 1.870E+02 1.020E+05 0.000E+00 4.260E+01 0.000E+00 1.490E+06 0.000E+00 1.470E+01 CE-144 1.620E+06 5.090E+05 0.000E+00 2.820E+05 0.000E+00 1.330E+08 0.000E+00 8.660E+04 PR-143 7.180E+02 2.160E+02 0.000E+00 1.170E+02 0.000E+00 7.750E+05 0.000E+00 3.560E+01 PR-144 2.680E-53 8.290E-54 0.000E+00 4.380E-54 0.000E+00 1.780E-50 0.000E+00 1.350E-54 ND-147 4.450E+02 3.600E+02 0.000E+00 1.980E+02 0.000E+00 5.700E+05 0.000E+00 2.790E+01 W-187 2.890E+04 1.710E+04 0.000E+00 0.000E+00 0.000E+00 2.400E+06 0.000E+00 7.670E+03 NP-239 1.720E+01 1.240E+00 0.000E+00 3.580E+00 0.000E+00 9.170E+04 0.000E+00 8.710E-01 Appendix I Ri Child Cow Milk - Page 3 of 3 Page 9-157

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 0.000E+00 3.200E+03 C-14 1.020E+05 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 0.000E+00 2.040E+04 NA-24 1.060E+06 1.060E+06 1.060E+06 1.060E+06 1.060E+06 1.060E+06 0.000E+00 1.060E+06 P-32 9.330E+10 4.370E+09 0.000E+00 0.000E+00 0.000E+00 2.580E+09 0.000E+00 3.600E+09 CR-51 0.000E+00 0.000E+00 6.780E+03 1.850E+03 1.240E+04 6.480E+05 0.000E+00 1.220E+04 MN-54 0.000E+00 2.520E+06 0.000E+00 7.060E+05 0.000E+00 2.110E+06 0.000E+00 6.700E+05 MN-56 0.000E+00 1.520E-03 0.000E+00 1.840E-03 0.000E+00 2.200E-01 0.000E+00 3.430E-04 FE-55 1.450E+06 7.710E+05 0.000E+00 0.000E+00 4.360E+05 1.430E+05 0.000E+00 2.390E+05 FE-59 1.560E+06 2.530E+06 0.000E+00 0.000E+00 7.330E+05 2.630E+06 0.000E+00 1.260E+06 CO-58 0.000E+00 1.450E+06 0.000E+00 0.000E+00 0.000E+00 8.490E+06 0.000E+00 4.450E+06 CO-60 0.000E+00 5.180E+06 0.000E+00 0.000E+00 0.000E+00 2.870E+07 0.000E+00 1.530E+07 NI-63 3.560E+09 1.900E+08 0.000E+00 0.000E+00 0.000E+00 1.280E+07 0.000E+00 1.210E+08 NI-65 1.990E-01 1.870E-02 0.000E+00 0.000E+00 0.000E+00 2.290E+00 0.000E+00 1.090E-02 CU-64 0.000E+00 8.320E+03 0.000E+00 2.010E+04 0.000E+00 3.900E+05 0.000E+00 5.020E+03 ZN-65 4.960E+08 1.320E+09 0.000E+00 8.330E+08 0.000E+00 2.320E+08 0.000E+00 8.220E+08 ZN-69 1.140E-12 1.640E-12 0.000E+00 9.960E-13 0.000E+00 1.030E-10 0.000E+00 1.520E-13 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.280E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.820E-24 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.050E+09 0.000E+00 0.000E+00 0.000E+00 6.770E+07 0.000E+00 6.470E+08 RB-88 0.000E+00 8.590E-46 0.000E+00 0.000E+00 0.000E+00 4.210E-47 0.000E+00 5.970E-46 RB-89 0.000E+00 1.610E-53 0.000E+00 0.000E+00 0.000E+00 1.410E-55 0.000E+00 1.430E-53 SR-89 1.390E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.380E+08 0.000E+00 3.970E+08 SR-90 2.350E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.160E+09 0.000E+00 5.950E+10 SR-91 2.740E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.040E+05 0.000E+00 1.030E+04 Appendix I Ri Child Goat Milk - Page 1 of 3 Page 9-158

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.580E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.680E+01 0.000E+00 1.840E-01 Y-90 3.870E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.100E+05 0.000E+00 1.030E+00 Y-91 4.680E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.240E+05 0.000E+00 1.250E+02 Y-91M 3.210E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.280E-17 0.000E+00 1.170E-21 Y-92 3.040E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.770E-01 0.000E+00 8.690E-07 Y-93 1.210E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.810E+03 0.000E+00 3.330E-03 ZR-95 4.600E+02 1.010E+02 0.000E+00 1.450E+02 0.000E+00 1.050E+05 0.000E+00 9.000E+01 ZR-97 2.300E-01 3.330E-02 0.000E+00 4.780E-02 0.000E+00 5.040E+03 0.000E+00 1.960E-02 NB-95 3.810E+04 1.490E+04 0.000E+00 1.400E+04 0.000E+00 2.750E+07 0.000E+00 1.060E+04 MO-99 0.000E+00 9.760E+06 0.000E+00 2.090E+07 0.000E+00 8.080E+06 0.000E+00 2.420E+06 TC-99M 1.590E+00 3.110E+00 0.000E+00 4.520E+01 1.580E+00 1.770E+03 0.000E+00 5.150E+01 TC-101 1.400E-60 1.460E-60 0.000E+00 2.490E-59 7.720E-61 4.640E-60 0.000E+00 1.850E-59 RU-103 5.140E+02 0.000E+00 0.000E+00 1.290E+03 0.000E+00 1.330E+04 0.000E+00 1.980E+02 RU-105 4.580E-04 0.000E+00 0.000E+00 4.030E-03 0.000E+00 2.990E-01 0.000E+00 1.660E-04 RU-106 1.110E+04 0.000E+00 0.000E+00 1.500E+04 0.000E+00 1.720E+05 0.000E+00 1.380E+03 AG-110M 2.510E+07 1.690E+07 0.000E+00 3.150E+07 0.000E+00 2.010E+09 0.000E+00 1.350E+07 TE-125M 8.850E+06 2.400E+06 2.480E+06 0.000E+00 0.000E+00 8.540E+06 0.000E+00 1.180E+06 TE-127 3.570E+02 9.630E+01 2.470E+02 1.020E+03 0.000E+00 1.390E+04 0.000E+00 7.660E+01 TE-127M 2.500E+07 6.720E+06 5.970E+06 7.120E+07 0.000E+00 2.020E+07 0.000E+00 2.960E+06 TE-129 1.540E-10 4.300E-11 1.100E-10 4.510E-10 0.000E+00 9.590E-09 0.000E+00 3.660E-11 TE-129M 3.260E+07 9.090E+06 1.050E+07 9.560E+07 0.000E+00 3.970E+07 0.000E+00 5.060E+06 TE-131 1.940E-33 5.910E-34 1.480E-33 5.860E-33 0.000E+00 1.020E-32 0.000E+00 5.770E-34 TE-131M 1.920E+05 6.640E+04 1.360E+05 6.420E+05 0.000E+00 2.690E+06 0.000E+00 7.060E+04 TE-132 1.230E+06 5.440E+05 7.920E+05 5.050E+06 0.000E+00 5.480E+06 0.000E+00 6.570E+05 I-130 2.070E+06 4.190E+06 4.610E+08 6.260E+06 0.000E+00 1.960E+06 0.000E+00 2.160E+06 Appendix I Ri Child Goat Milk - Page 2 of 3 Page 9-159

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.560E+09 1.570E+09 5.200E+11 2.580E+09 0.000E+00 1.400E+08 0.000E+00 8.940E+08 I-132 8.270E-01 1.520E+00 7.050E+01 2.330E+00 0.000E+00 1.790E+00 0.000E+00 6.990E-01 I-133 2.060E+07 2.550E+07 4.730E+09 4.250E+07 0.000E+00 1.030E+07 0.000E+00 9.640E+06 I-134 1.020E-11 1.890E-11 4.350E-10 2.890E-11 0.000E+00 1.250E-11 0.000E+00 8.700E-12 I-135 6.480E+04 1.170E+05 1.030E+07 1.790E+05 0.000E+00 8.880E+04 0.000E+00 5.520E+04 CS-134 6.790E+10 1.110E+11 0.000E+00 3.450E+10 1.240E+10 6.010E+08 0.000E+00 2.350E+10 CS-136 3.030E+09 8.340E+09 0.000E+00 4.440E+09 6.630E+08 2.930E+08 0.000E+00 5.400E+09 CS-137 9.670E+10 9.260E+10 0.000E+00 3.020E+10 1.090E+10 5.800E+08 0.000E+00 1.370E+10 CS-138 1.190E-22 1.660E-22 0.000E+00 1.170E-22 1.260E-23 7.640E-23 0.000E+00 1.050E-22 BA-139 2.410E-08 1.290E-11 0.000E+00 1.120E-11 7.560E-12 1.390E-06 0.000E+00 6.980E-10 BA-140 1.410E+07 1.230E+04 0.000E+00 4.010E+03 7.340E+03 7.120E+06 0.000E+00 8.200E+05 BA-141 2.220E-46 1.240E-49 0.000E+00 1.080E-49 7.300E-49 1.270E-46 0.000E+00 7.230E-48 BA-142 1.390E-80 9.970E-84 0.000E+00 8.070E-84 5.870E-84 1.810E-82 0.000E+00 7.740E-82 LA-140 2.330E+00 8.140E-01 0.000E+00 0.000E+00 0.000E+00 2.270E+04 0.000E+00 2.740E-01 LA-142 9.730E-12 3.100E-12 0.000E+00 0.000E+00 0.000E+00 6.140E-07 0.000E+00 9.710E-13 CE-141 2.620E+03 1.310E+03 0.000E+00 5.740E+02 0.000E+00 1.630E+06 0.000E+00 1.940E+02 CE-143 2.250E+01 1.220E+04 0.000E+00 5.120E+00 0.000E+00 1.790E+05 0.000E+00 1.770E+00 CE-144 1.950E+05 6.110E+04 0.000E+00 3.380E+04 0.000E+00 1.590E+07 0.000E+00 1.040E+04 PR-143 8.620E+01 2.590E+01 0.000E+00 1.400E+01 0.000E+00 9.300E+04 0.000E+00 4.280E+00 PR-144 3.220E-54 9.950E-55 0.000E+00 5.260E-55 0.000E+00 2.140E-51 0.000E+00 1.620E-55 ND-147 5.330E+01 4.320E+01 0.000E+00 2.370E+01 0.000E+00 6.850E+04 0.000E+00 3.350E+00 W-187 3.470E+03 2.050E+03 0.000E+00 0.000E+00 0.000E+00 2.880E+05 0.000E+00 9.210E+02 NP-239 2.070E+00 1.490E-01 0.000E+00 4.300E-01 0.000E+00 1.100E+04 0.000E+00 1.040E-01 Appendix I Ri Child Goat Milk - Page 3 of 3 Page 9-160

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.340E+02 2.340E+02 2.340E+02 2.340E+02 2.340E+02 0.000E+00 2.340E+02 C-14 3.280E+04 6.560E+03 6.560E+03 6.560E+03 6.560E+03 6.560E+03 0.000E+00 6.560E+03 NA-24 1.720E-03 1.720E-03 1.720E-03 1.720E-03 1.720E-03 1.720E-03 0.000E+00 1.720E-03 P-32 7.420E+09 3.470E+08 0.000E+00 0.000E+00 0.000E+00 2.050E+08 0.000E+00 2.860E+08 CR-51 0.000E+00 0.000E+00 4.880E+03 1.330E+03 8.910E+03 4.660E+05 0.000E+00 8.790E+03 MN-54 0.000E+00 8.010E+06 0.000E+00 2.250E+06 0.000E+00 6.720E+06 0.000E+00 2.130E+06 MN-56 0.000E+00 1.430E-53 0.000E+00 1.730E-53 0.000E+00 2.070E-51 0.000E+00 3.230E-54 FE-55 4.570E+08 2.420E+08 0.000E+00 0.000E+00 1.370E+08 4.490E+07 0.000E+00 7.510E+07 FE-59 3.760E+08 6.090E+08 0.000E+00 0.000E+00 1.770E+08 6.340E+08 0.000E+00 3.030E+08 CO-58 0.000E+00 1.640E+07 0.000E+00 0.000E+00 0.000E+00 9.580E+07 0.000E+00 5.020E+07 CO-60 0.000E+00 6.930E+07 0.000E+00 0.000E+00 0.000E+00 3.840E+08 0.000E+00 2.040E+08 NI-63 2.910E+10 1.560E+09 0.000E+00 0.000E+00 0.000E+00 1.050E+08 0.000E+00 9.910E+08 NI-65 3.520E-52 3.310E-53 0.000E+00 0.000E+00 0.000E+00 4.060E-51 0.000E+00 1.930E-53 CU-64 0.000E+00 2.970E-07 0.000E+00 7.180E-07 0.000E+00 1.390E-05 0.000E+00 1.800E-07 ZN-65 3.750E+08 1.000E+09 0.000E+00 6.300E+08 0.000E+00 1.760E+08 0.000E+00 6.220E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.520E-57 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 5.770E+08 0.000E+00 0.000E+00 0.000E+00 3.710E+07 0.000E+00 3.550E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 4.820E+08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.870E+07 0.000E+00 1.380E+07 SR-90 1.040E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.400E+08 0.000E+00 2.640E+09 SR-91 2.400E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.300E-10 0.000E+00 9.050E-12 Appendix I Ri Child Cow Meat - Page 1 of 3 Page 9-161

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.850E-49 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.490E-48 0.000E+00 7.400E-51 Y-90 1.710E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.880E+05 0.000E+00 4.590E+00 Y-91 1.800E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.400E+08 0.000E+00 4.820E+04 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-92 2.410E-39 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.960E-35 0.000E+00 6.890E-41 Y-93 7.440E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.110E-07 0.000E+00 2.040E-13 ZR-95 2.660E+06 5.850E+05 0.000E+00 8.380E+05 0.000E+00 6.110E+08 0.000E+00 5.210E+05 ZR-97 3.200E-05 4.630E-06 0.000E+00 6.650E-06 0.000E+00 7.010E-01 0.000E+00 2.730E-06 NB-95 3.100E+06 1.210E+06 0.000E+00 1.130E+06 0.000E+00 2.230E+09 0.000E+00 8.620E+05 MO-99 0.000E+00 1.150E+05 0.000E+00 2.460E+05 0.000E+00 9.510E+04 0.000E+00 2.840E+04 TC-99M 6.190E-21 1.210E-20 0.000E+00 1.760E-19 6.160E-21 6.910E-18 0.000E+00 2.010E-19 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.550E+08 0.000E+00 0.000E+00 3.900E+08 0.000E+00 4.010E+09 0.000E+00 5.960E+07 RU-105 9.020E-28 0.000E+00 0.000E+00 7.930E-27 0.000E+00 5.890E-25 0.000E+00 3.270E-28 RU-106 4.440E+09 0.000E+00 0.000E+00 5.990E+09 0.000E+00 6.900E+10 0.000E+00 5.540E+08 AG-110M 8.390E+06 5.670E+06 0.000E+00 1.060E+07 0.000E+00 6.740E+08 0.000E+00 4.530E+06 TE-125M 5.690E+08 1.540E+08 1.600E+08 0.000E+00 0.000E+00 5.490E+08 0.000E+00 7.590E+07 TE-127 3.380E-10 9.120E-11 2.340E-10 9.630E-10 0.000E+00 1.320E-08 0.000E+00 7.260E-11 TE-127M 1.770E+09 4.780E+08 4.240E+08 5.060E+09 0.000E+00 1.440E+09 0.000E+00 2.110E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-129M 1.790E+09 5.000E+08 5.770E+08 5.260E+09 0.000E+00 2.180E+09 0.000E+00 2.780E+08 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 7.000E+02 2.420E+02 4.980E+02 2.340E+03 0.000E+00 9.820E+03 0.000E+00 2.580E+02 TE-132 2.120E+06 9.380E+05 1.370E+06 8.710E+06 0.000E+00 9.450E+06 0.000E+00 1.130E+06 I-130 3.030E-06 6.130E-06 6.750E-04 9.160E-06 0.000E+00 2.870E-06 0.000E+00 3.160E-06 Appendix I Ri Child Cow Meat - Page 2 of 3 Page 9-162

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.650E+07 1.660E+07 5.500E+09 2.730E+07 0.000E+00 1.480E+06 0.000E+00 9.460E+06 I-132 1.020E-58 1.880E-58 8.730E-57 2.880E-58 0.000E+00 2.210E-58 0.000E+00 8.650E-59 I-133 5.670E-01 7.020E-01 1.300E+02 1.170E+00 0.000E+00 2.830E-01 0.000E+00 2.660E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 6.510E-17 1.170E-16 1.040E-14 1.800E-16 0.000E+00 8.930E-17 0.000E+00 5.550E-17 CS-134 9.220E+08 1.510E+09 0.000E+00 4.690E+08 1.680E+08 8.160E+06 0.000E+00 3.190E+08 CS-136 1.620E+07 4.460E+07 0.000E+00 2.370E+07 3.540E+06 1.570E+06 0.000E+00 2.880E+07 CS-137 1.330E+09 1.280E+09 0.000E+00 4.160E+08 1.500E+08 7.990E+06 0.000E+00 1.880E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 4.380E+07 3.840E+04 0.000E+00 1.250E+04 2.290E+04 2.220E+07 0.000E+00 2.560E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 5.590E-02 1.950E-02 0.000E+00 0.000E+00 0.000E+00 5.440E+02 0.000E+00 6.580E-03 LA-142 5.300E-92 1.690E-92 0.000E+00 0.000E+00 0.000E+00 3.350E-87 0.000E+00 5.290E-93 CE-141 2.220E+04 1.110E+04 0.000E+00 4.850E+03 0.000E+00 1.380E+07 0.000E+00 1.640E+03 CE-143 3.170E-02 1.720E+01 0.000E+00 7.210E-03 0.000E+00 2.520E+02 0.000E+00 2.490E-03 CE-144 2.320E+06 7.260E+05 0.000E+00 4.020E+05 0.000E+00 1.890E+08 0.000E+00 1.240E+05 PR-143 3.340E+04 1.000E+04 0.000E+00 5.430E+03 0.000E+00 3.600E+07 0.000E+00 1.660E+03 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 1.170E+04 9.470E+03 0.000E+00 5.190E+03 0.000E+00 1.500E+07 0.000E+00 7.330E+02 W-187 3.210E-02 1.900E-02 0.000E+00 0.000E+00 0.000E+00 2.670E+00 0.000E+00 8.530E-03 NP-239 4.260E-01 3.060E-02 0.000E+00 8.850E-02 0.000E+00 2.260E+03 0.000E+00 2.150E-02 Appendix I Ri Child Cow Meat - Page 3 of 3 Page 9-163

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 4.010E+03 4.010E+03 4.010E+03 4.010E+03 4.010E+03 0.000E+00 4.010E+03 C-14 2.170E+05 4.340E+04 4.340E+04 4.340E+04 4.340E+04 4.340E+04 0.000E+00 4.340E+04 NA-24 3.730E+05 3.730E+05 3.730E+05 3.730E+05 3.730E+05 3.730E+05 0.000E+00 3.730E+05 P-32 3.370E+09 1.580E+08 0.000E+00 0.000E+00 0.000E+00 9.310E+07 0.000E+00 1.300E+08 CR-51 0.000E+00 0.000E+00 6.500E+04 1.780E+04 1.190E+05 6.210E+06 0.000E+00 1.170E+05 MN-54 0.000E+00 6.650E+08 0.000E+00 1.860E+08 0.000E+00 5.580E+08 0.000E+00 1.770E+08 MN-56 0.000E+00 1.860E+01 0.000E+00 2.250E+01 0.000E+00 2.700E+03 0.000E+00 4.200E+00 FE-55 8.010E+08 4.250E+08 0.000E+00 0.000E+00 2.400E+08 7.870E+07 0.000E+00 1.320E+08 FE-59 3.980E+08 6.430E+08 0.000E+00 0.000E+00 1.860E+08 6.700E+08 0.000E+00 3.200E+08 CO-58 0.000E+00 6.440E+07 0.000E+00 0.000E+00 0.000E+00 3.760E+08 0.000E+00 1.970E+08 CO-60 0.000E+00 3.780E+08 0.000E+00 0.000E+00 0.000E+00 2.100E+09 0.000E+00 1.120E+09 NI-63 3.950E+10 2.110E+09 0.000E+00 0.000E+00 0.000E+00 1.420E+08 0.000E+00 1.340E+09 NI-65 1.050E+02 9.890E+00 0.000E+00 0.000E+00 0.000E+00 1.210E+03 0.000E+00 5.770E+00 CU-64 0.000E+00 1.100E+04 0.000E+00 2.660E+04 0.000E+00 5.160E+05 0.000E+00 6.640E+03 ZN-65 8.130E+08 2.160E+09 0.000E+00 1.360E+09 0.000E+00 3.800E+08 0.000E+00 1.350E+09 ZN-69 9.490E-06 1.370E-05 0.000E+00 8.320E-06 0.000E+00 8.640E-04 0.000E+00 1.270E-06 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.370E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.820E-11 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.520E+08 0.000E+00 0.000E+00 0.000E+00 2.910E+07 0.000E+00 2.780E+08 RB-88 0.000E+00 4.380E-22 0.000E+00 0.000E+00 0.000E+00 2.150E-23 0.000E+00 3.040E-22 RB-89 0.000E+00 4.610E-26 0.000E+00 0.000E+00 0.000E+00 4.020E-28 0.000E+00 4.090E-26 SR-89 3.600E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.390E+09 0.000E+00 1.030E+09 SR-90 1.240E+12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.670E+10 0.000E+00 3.150E+11 SR-91 5.240E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.160E+06 0.000E+00 1.980E+04 Appendix I Ri Child Vegetation - Page 1 of 3 Page 9-164

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.280E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.380E+04 0.000E+00 2.920E+01 Y-90 2.310E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.570E+07 0.000E+00 6.180E+02 Y-91 1.860E+07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.480E+09 0.000E+00 4.990E+05 Y-91M 8.910E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.740E-05 0.000E+00 3.240E-10 Y-92 1.580E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.580E+04 0.000E+00 4.530E-02 Y-93 2.930E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.370E+06 0.000E+00 8.040E+00 ZR-95 3.860E+06 8.480E+05 0.000E+00 1.210E+06 0.000E+00 8.850E+08 0.000E+00 7.550E+05 ZR-97 5.700E+02 8.240E+01 0.000E+00 1.180E+02 0.000E+00 1.250E+07 0.000E+00 4.860E+01 NB-95 4.110E+05 1.600E+05 0.000E+00 1.500E+05 0.000E+00 2.960E+08 0.000E+00 1.140E+05 MO-99 0.000E+00 7.710E+06 0.000E+00 1.650E+07 0.000E+00 6.380E+06 0.000E+00 1.910E+06 TC-99M 4.710E+00 9.230E+00 0.000E+00 1.340E+02 4.690E+00 5.260E+03 0.000E+00 1.530E+02 TC-101 1.410E-30 1.470E-30 0.000E+00 2.510E-29 7.780E-31 4.680E-30 0.000E+00 1.870E-29 RU-103 1.530E+07 0.000E+00 0.000E+00 3.860E+07 0.000E+00 3.970E+08 0.000E+00 5.900E+06 RU-105 9.160E+01 0.000E+00 0.000E+00 8.050E+02 0.000E+00 5.980E+04 0.000E+00 3.320E+01 RU-106 7.450E+08 0.000E+00 0.000E+00 1.010E+09 0.000E+00 1.160E+10 0.000E+00 9.300E+07 AG-110M 3.210E+07 2.170E+07 0.000E+00 4.040E+07 0.000E+00 2.580E+09 0.000E+00 1.730E+07 TE-125M 3.510E+08 9.500E+07 9.840E+07 0.000E+00 0.000E+00 3.380E+08 0.000E+00 4.670E+07 TE-127 9.850E+03 2.650E+03 6.810E+03 2.800E+04 0.000E+00 3.850E+05 0.000E+00 2.110E+03 TE-127M 1.320E+09 3.560E+08 3.160E+08 3.770E+09 0.000E+00 1.070E+09 0.000E+00 1.570E+08 TE-129 1.320E-03 3.690E-04 9.430E-04 3.870E-03 0.000E+00 8.230E-02 0.000E+00 3.140E-04 TE-129M 8.410E+08 2.350E+08 2.710E+08 2.470E+09 0.000E+00 1.030E+09 0.000E+00 1.310E+08 TE-131 2.570E-15 7.830E-16 1.960E-15 7.770E-15 0.000E+00 1.350E-14 0.000E+00 7.640E-16 TE-131M 1.540E+06 5.330E+05 1.100E+06 5.160E+06 0.000E+00 2.160E+07 0.000E+00 5.680E+05 TE-132 7.000E+06 3.100E+06 4.510E+06 2.880E+07 0.000E+00 3.120E+07 0.000E+00 3.740E+06 I-130 6.160E+05 1.240E+06 1.370E+08 1.860E+06 0.000E+00 5.820E+05 0.000E+00 6.410E+05 Appendix I Ri Child Vegetation - Page 2 of 3 Page 9-165

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.430E+08 1.440E+08 4.750E+10 2.360E+08 0.000E+00 1.280E+07 0.000E+00 8.170E+07 I-132 9.220E+01 1.690E+02 7.860E+03 2.590E+02 0.000E+00 1.990E+02 0.000E+00 7.790E+01 I-133 3.530E+06 4.370E+06 8.110E+08 7.280E+06 0.000E+00 1.760E+06 0.000E+00 1.650E+06 I-134 1.550E-04 2.880E-04 6.620E-03 4.400E-04 0.000E+00 1.910E-04 0.000E+00 1.320E-04 I-135 6.260E+04 1.130E+05 9.970E+06 1.730E+05 0.000E+00 8.580E+04 0.000E+00 5.330E+04 CS-134 1.600E+10 2.630E+10 0.000E+00 8.150E+09 2.930E+09 1.420E+08 0.000E+00 5.550E+09 CS-136 8.240E+07 2.270E+08 0.000E+00 1.210E+08 1.800E+07 7.960E+06 0.000E+00 1.470E+08 CS-137 2.390E+10 2.290E+10 0.000E+00 7.460E+09 2.680E+09 1.430E+08 0.000E+00 3.380E+09 CS-138 6.570E-11 9.130E-11 0.000E+00 6.430E-11 6.920E-12 4.210E-11 0.000E+00 5.790E-11 BA-139 4.950E-02 2.640E-05 0.000E+00 2.310E-05 1.560E-05 2.860E+00 0.000E+00 1.440E-03 BA-140 2.770E+08 2.420E+05 0.000E+00 7.890E+04 1.450E+05 1.400E+08 0.000E+00 1.610E+07 BA-141 1.990E-21 1.110E-24 0.000E+00 9.620E-25 6.530E-24 1.130E-21 0.000E+00 6.460E-23 BA-142 9.930E-39 7.150E-42 0.000E+00 5.780E-42 4.200E-42 1.300E-40 0.000E+00 5.540E-40 LA-140 3.250E+03 1.130E+03 0.000E+00 0.000E+00 0.000E+00 3.160E+07 0.000E+00 3.820E+02 LA-142 3.360E-04 1.070E-04 0.000E+00 0.000E+00 0.000E+00 2.120E+01 0.000E+00 3.350E-05 CE-141 6.560E+05 3.270E+05 0.000E+00 1.430E+05 0.000E+00 4.080E+08 0.000E+00 4.860E+04 CE-143 1.720E+03 9.310E+05 0.000E+00 3.910E+02 0.000E+00 1.360E+07 0.000E+00 1.350E+02 CE-144 1.270E+08 3.980E+07 0.000E+00 2.210E+07 0.000E+00 1.040E+10 0.000E+00 6.780E+06 PR-143 1.460E+05 4.370E+04 0.000E+00 2.370E+04 0.000E+00 1.570E+08 0.000E+00 7.230E+03 PR-144 5.380E-26 1.660E-26 0.000E+00 8.800E-27 0.000E+00 3.580E-23 0.000E+00 2.710E-27 ND-147 7.150E+04 5.790E+04 0.000E+00 3.180E+04 0.000E+00 9.170E+07 0.000E+00 4.480E+03 W-187 6.430E+04 3.810E+04 0.000E+00 0.000E+00 0.000E+00 5.350E+06 0.000E+00 1.710E+04 NP-239 2.560E+03 1.840E+02 0.000E+00 5.310E+02 0.000E+00 1.360E+07 0.000E+00 1.290E+02 Appendix I Ri Child Vegetation - Page 3 of 3 Page 9-166

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 0.000E+00 1.120E+03 C-14 3.590E+04 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 0.000E+00 6.730E+03 NA-24 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 0.000E+00 1.610E+04 P-32 2.600E+06 1.140E+05 0.000E+00 0.000E+00 0.000E+00 4.220E+04 0.000E+00 9.880E+04 CR-51 0.000E+00 0.000E+00 8.550E+01 2.430E+01 1.700E+04 1.080E+03 0.000E+00 1.540E+02 MN-54 0.000E+00 4.290E+04 0.000E+00 1.000E+04 1.580E+06 2.290E+04 0.000E+00 9.510E+03 MN-56 0.000E+00 1.660E+00 0.000E+00 1.670E+00 1.310E+04 1.230E+05 0.000E+00 3.120E-01 FE-55 4.740E+04 2.520E+04 0.000E+00 0.000E+00 1.110E+05 2.870E+03 0.000E+00 7.770E+03 FE-59 2.070E+04 3.340E+04 0.000E+00 0.000E+00 1.270E+06 7.070E+04 0.000E+00 1.670E+04 CO-58 0.000E+00 1.770E+03 0.000E+00 0.000E+00 1.110E+06 3.440E+04 0.000E+00 3.160E+03 CO-60 0.000E+00 1.310E+04 0.000E+00 0.000E+00 7.070E+06 9.620E+04 0.000E+00 2.260E+04 NI-63 8.210E+05 4.620E+04 0.000E+00 0.000E+00 2.750E+05 6.330E+03 0.000E+00 2.800E+04 NI-65 2.990E+00 2.960E-01 0.000E+00 0.000E+00 8.180E+03 8.400E+04 0.000E+00 1.640E-01 CU-64 0.000E+00 1.990E+00 0.000E+00 6.030E+00 9.580E+03 3.670E+04 0.000E+00 1.070E+00 ZN-65 4.260E+04 1.130E+05 0.000E+00 7.140E+04 9.950E+05 1.630E+04 0.000E+00 7.030E+04 ZN-69 6.700E-02 9.660E-02 0.000E+00 5.850E-02 1.420E+03 1.020E+04 0.000E+00 8.920E-03 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.740E+02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.480E+02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.530E+01 RB-86 0.000E+00 1.980E+05 0.000E+00 0.000E+00 0.000E+00 7.990E+03 0.000E+00 1.140E+05 RB-88 0.000E+00 5.620E+02 0.000E+00 0.000E+00 0.000E+00 1.720E+01 0.000E+00 3.660E+02 RB-89 0.000E+00 3.450E+02 0.000E+00 0.000E+00 0.000E+00 1.890E+00 0.000E+00 2.900E+02 SR-89 5.990E+05 0.000E+00 0.000E+00 0.000E+00 2.160E+06 1.670E+05 0.000E+00 1.720E+04 SR-90 1.010E+08 0.000E+00 0.000E+00 0.000E+00 1.480E+07 3.430E+05 0.000E+00 6.440E+06 SR-91 1.210E+02 0.000E+00 0.000E+00 0.000E+00 5.330E+04 1.740E+05 0.000E+00 4.590E+00 Appendix I Ri Child Inhalation - Page 1 of 3 Page 9-167

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.310E+01 0.000E+00 0.000E+00 0.000E+00 2.400E+04 2.420E+05 0.000E+00 5.250E-01 Y-90 4.110E+03 0.000E+00 0.000E+00 0.000E+00 2.620E+05 2.680E+05 0.000E+00 1.110E+02 Y-91 9.140E+05 0.000E+00 0.000E+00 0.000E+00 2.630E+06 1.840E+05 0.000E+00 2.440E+04 Y-91M 5.070E-01 0.000E+00 0.000E+00 0.000E+00 2.810E+03 1.720E+03 0.000E+00 1.840E-02 Y-92 2.030E+01 0.000E+00 0.000E+00 0.000E+00 2.390E+04 2.390E+05 0.000E+00 5.810E-01 Y-93 1.860E+02 0.000E+00 0.000E+00 0.000E+00 7.440E+04 3.880E+05 0.000E+00 5.110E+00 ZR-95 1.900E+05 4.180E+04 0.000E+00 5.960E+04 2.230E+06 6.110E+04 0.000E+00 3.700E+04 ZR-97 1.880E+02 2.720E+01 0.000E+00 3.880E+01 1.130E+05 3.510E+05 0.000E+00 1.600E+01 NB-95 2.350E+04 9.180E+03 0.000E+00 8.620E+03 6.140E+05 3.700E+04 0.000E+00 6.550E+03 MO-99 0.000E+00 1.720E+02 0.000E+00 3.920E+02 1.350E+05 1.270E+05 0.000E+00 4.260E+01 TC-99M 1.780E-03 3.480E-03 0.000E+00 5.070E-02 9.510E+02 4.810E+03 0.000E+00 5.770E-02 TC-101 8.100E-05 8.510E-05 0.000E+00 1.450E-03 5.850E+02 1.630E+01 0.000E+00 1.080E-03 RU-103 2.790E+03 0.000E+00 0.000E+00 7.030E+03 6.620E+05 4.480E+04 0.000E+00 1.070E+03 RU-105 1.530E+00 0.000E+00 0.000E+00 1.340E+00 1.590E+04 9.950E+04 0.000E+00 5.550E-01 RU-106 1.360E+05 0.000E+00 0.000E+00 1.840E+05 1.430E+07 4.290E+05 0.000E+00 1.690E+04 AG-110M 1.690E+04 1.140E+04 0.000E+00 2.120E+04 5.480E+06 1.000E+05 0.000E+00 9.140E+03 TE-125M 6.730E+03 2.330E+03 1.920E+03 0.000E+00 4.770E+05 3.380E+04 0.000E+00 9.140E+02 TE-127 2.770E+00 9.510E-01 1.960E+00 7.070E+00 1.000E+04 5.620E+04 0.000E+00 6.100E-01 TE-127M 2.490E+04 8.550E+03 6.070E+03 6.360E+04 1.480E+06 7.140E+04 0.000E+00 3.020E+03 TE-129 9.770E-02 3.500E-02 7.140E-02 2.570E-01 2.930E+03 2.550E+04 0.000E+00 2.380E-02 TE-129M 1.920E+04 6.840E+03 6.330E+03 5.030E+04 1.760E+06 1.820E+05 0.000E+00 3.040E+03 TE-131 2.170E-02 8.440E-03 1.700E-02 5.880E-02 2.050E+03 1.330E+03 0.000E+00 6.590E-03 TE-131M 1.340E+02 5.920E+01 9.770E+01 4.000E+02 2.060E+05 3.080E+05 0.000E+00 5.070E+01 TE-132 4.810E+02 2.720E+02 3.170E+02 1.770E+03 3.770E+05 1.380E+05 0.000E+00 2.630E+02 I-130 8.180E+03 1.640E+04 1.850E+06 2.450E+04 0.000E+00 5.110E+03 0.000E+00 8.440E+03 Appendix I Ri Child Inhalation - Page 2 of 3 Page 9-168

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 4.810E+04 4.810E+04 1.620E+07 7.880E+04 0.000E+00 2.840E+03 0.000E+00 2.730E+04 I-132 2.120E+03 4.070E+03 1.940E+05 6.250E+03 0.000E+00 3.200E+03 0.000E+00 1.880E+03 I-133 1.660E+04 2.030E+04 3.850E+06 3.380E+04 0.000E+00 5.480E+03 0.000E+00 7.700E+03 I-134 1.170E+03 2.160E+03 5.070E+04 3.300E+03 0.000E+00 9.550E+02 0.000E+00 9.950E+02 I-135 4.920E+03 8.730E+03 7.920E+05 1.340E+04 0.000E+00 4.440E+03 0.000E+00 4.140E+03 CS-134 6.510E+05 1.010E+06 0.000E+00 3.300E+05 1.210E+05 3.850E+03 0.000E+00 2.250E+05 CS-136 6.510E+04 1.710E+05 0.000E+00 9.550E+04 1.450E+04 4.180E+03 0.000E+00 1.160E+05 CS-137 9.060E+05 8.250E+05 0.000E+00 2.820E+05 1.040E+05 3.620E+03 0.000E+00 1.280E+05 CS-138 6.330E+02 8.400E+02 0.000E+00 6.220E+02 6.810E+01 2.700E+02 0.000E+00 5.550E+02 BA-139 1.840E+00 9.840E-04 0.000E+00 8.620E-04 5.770E+03 5.770E+04 0.000E+00 5.360E-02 BA-140 7.400E+04 6.480E+01 0.000E+00 2.110E+01 1.740E+06 1.020E+05 0.000E+00 4.330E+03 BA-141 1.960E-01 1.090E-04 0.000E+00 9.470E-05 2.920E+03 2.750E+02 0.000E+00 6.360E-03 BA-142 5.000E-02 3.600E-05 0.000E+00 2.910E-05 1.640E+03 2.740E+00 0.000E+00 2.790E-03 LA-140 6.440E+02 2.250E+02 0.000E+00 0.000E+00 1.830E+05 2.260E+05 0.000E+00 7.550E+01 LA-142 1.300E+00 4.110E-01 0.000E+00 0.000E+00 8.700E+03 7.580E+04 0.000E+00 1.290E-01 CE-141 3.920E+04 1.950E+04 0.000E+00 8.550E+03 5.440E+05 5.660E+04 0.000E+00 2.900E+03 CE-143 3.660E+02 1.990E+02 0.000E+00 8.360E+01 1.150E+05 1.270E+05 0.000E+00 2.870E+01 CE-144 6.770E+06 2.120E+06 0.000E+00 1.170E+06 1.200E+07 3.880E+05 0.000E+00 3.610E+05 PR-143 1.850E+04 5.550E+03 0.000E+00 3.000E+03 4.330E+05 9.730E+04 0.000E+00 9.140E+02 PR-144 5.960E-02 1.850E-02 0.000E+00 9.770E-03 1.570E+03 1.970E+02 0.000E+00 3.000E-03 ND-147 1.080E+04 8.730E+03 0.000E+00 4.810E+03 3.280E+05 8.210E+04 0.000E+00 6.810E+02 W-187 1.630E+01 9.660E+00 0.000E+00 0.000E+00 4.110E+04 9.100E+04 0.000E+00 4.330E+00 NP-239 4.660E+02 3.340E+01 0.000E+00 9.730E+01 5.810E+04 6.400E+04 0.000E+00 2.350E+01 Appendix I Ri Child Inhalation - Page 3 of 3 Page 9-169

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.390E+07 1.190E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530E+10 2.150E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.150E+06 Appendix I Ri Child Ground Plane Deposition - Page 1 of 3 Page 9-170

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.310E+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.110E+05 1.840E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-110M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 TE-127 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04 TE-129 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 TE-129M 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 I-130 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.510E+06 Appendix I Ri Child Ground Plane Deposition - Page 2 of 3 Page 9-171

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.090E+07 1.720E+07 I-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 I-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2.450E+06 I-134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 I-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS-134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.000E+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.710E+08 1.510E+08 CS-137 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 4.100E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.110E+04 4.490E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 2.110E+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.980E+06 1.710E+06 Appendix I Ri Child Ground Plane Deposition - Page 3 of 3 Page 9-172

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.380E+03 2.380E+03 2.380E+03 2.380E+03 2.380E+03 0.000E+00 2.380E+03 C-14 2.000E+05 4.270E+04 4.270E+04 4.270E+04 4.270E+04 4.270E+04 0.000E+00 4.270E+04 NA-24 1.540E+07 1.540E+07 1.540E+07 1.540E+07 1.540E+07 1.540E+07 0.000E+00 1.540E+07 P-32 1.600E+11 9.430E+09 0.000E+00 0.000E+00 0.000E+00 2.170E+09 0.000E+00 6.210E+09 CR-51 0.000E+00 0.000E+00 1.050E+05 2.300E+04 2.050E+05 4.700E+06 0.000E+00 1.610E+05 MN-54 0.000E+00 3.900E+07 0.000E+00 8.640E+06 0.000E+00 1.430E+07 0.000E+00 8.840E+06 MN-56 0.000E+00 3.100E-02 0.000E+00 2.660E-02 0.000E+00 2.810E+00 0.000E+00 5.340E-03 FE-55 1.350E+08 8.730E+07 0.000E+00 0.000E+00 4.270E+07 1.110E+07 0.000E+00 2.330E+07 FE-59 2.240E+08 3.920E+08 0.000E+00 0.000E+00 1.160E+08 1.870E+08 0.000E+00 1.540E+08 CO-58 0.000E+00 2.420E+07 0.000E+00 0.000E+00 0.000E+00 6.040E+07 0.000E+00 6.050E+07 CO-60 0.000E+00 8.820E+07 0.000E+00 0.000E+00 0.000E+00 2.100E+08 0.000E+00 2.080E+08 NI-63 3.490E+10 2.160E+09 0.000E+00 0.000E+00 0.000E+00 1.070E+08 0.000E+00 1.210E+09 NI-65 3.510E+00 3.970E-01 0.000E+00 0.000E+00 0.000E+00 3.020E+01 0.000E+00 1.800E-01 CU-64 0.000E+00 1.850E+05 0.000E+00 3.140E+05 0.000E+00 3.810E+06 0.000E+00 8.590E+04 ZN-65 5.550E+09 1.900E+10 0.000E+00 9.230E+09 0.000E+00 1.610E+10 0.000E+00 8.780E+09 ZN-69 2.020E-11 3.630E-11 0.000E+00 1.510E-11 0.000E+00 2.960E-09 0.000E+00 2.700E-12 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.340E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.260E-22 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.230E+10 0.000E+00 0.000E+00 0.000E+00 5.690E+08 0.000E+00 1.100E+10 RB-88 0.000E+00 1.880E-44 0.000E+00 0.000E+00 0.000E+00 1.830E-44 0.000E+00 1.030E-44 RB-89 0.000E+00 3.290E-52 0.000E+00 0.000E+00 0.000E+00 1.120E-52 0.000E+00 2.260E-52 SR-89 1.260E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.590E+08 0.000E+00 3.610E+08 SR-90 1.220E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.520E+09 0.000E+00 3.100E+10 SR-91 2.720E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.220E+05 0.000E+00 9.830E+03 Appendix J Ri Infant Cow Milk - Page 1 of 3 Page 9-173

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.640E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.000E+01 0.000E+00 1.720E-01 Y-90 6.810E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.410E+05 0.000E+00 1.830E+01 Y-91 7.330E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.250E+06 0.000E+00 1.950E+03 Y-91M 5.670E-19 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.890E-15 0.000E+00 1.930E-20 Y-92 5.380E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.030E+01 0.000E+00 1.510E-05 Y-93 2.160E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.700E+04 0.000E+00 5.870E-02 ZR-95 6.800E+03 1.660E+03 0.000E+00 1.790E+03 0.000E+00 8.260E+05 0.000E+00 1.180E+03 ZR-97 4.060E+00 6.970E-01 0.000E+00 7.030E-01 0.000E+00 4.450E+04 0.000E+00 3.180E-01 NB-95 5.930E+05 2.440E+05 0.000E+00 1.750E+05 0.000E+00 2.060E+08 0.000E+00 1.410E+05 MO-99 0.000E+00 2.080E+08 0.000E+00 3.110E+08 0.000E+00 6.850E+07 0.000E+00 4.060E+07 TC-99M 2.750E+01 5.670E+01 0.000E+00 6.100E+02 2.960E+01 1.650E+04 0.000E+00 7.300E+02 TC-101 2.470E-59 3.110E-59 0.000E+00 3.700E-58 1.700E-59 5.280E-57 0.000E+00 3.080E-58 RU-103 8.670E+03 0.000E+00 0.000E+00 1.800E+04 0.000E+00 1.050E+05 0.000E+00 2.900E+03 RU-105 8.050E-03 0.000E+00 0.000E+00 5.920E-02 0.000E+00 3.200E+00 0.000E+00 2.710E-03 RU-106 1.900E+05 0.000E+00 0.000E+00 2.250E+05 0.000E+00 1.440E+06 0.000E+00 2.380E+04 AG-110M 3.860E+08 2.820E+08 0.000E+00 4.030E+08 0.000E+00 1.460E+10 0.000E+00 1.860E+08 TE-125M 1.510E+08 5.040E+07 5.070E+07 0.000E+00 0.000E+00 7.180E+07 0.000E+00 2.040E+07 TE-127 6.320E+03 2.120E+03 5.140E+03 1.540E+04 0.000E+00 1.330E+05 0.000E+00 1.360E+03 TE-127M 4.210E+08 1.400E+08 1.220E+08 1.040E+09 0.000E+00 1.700E+08 0.000E+00 5.100E+07 TE-129 2.720E-09 9.380E-10 2.280E-09 6.770E-09 0.000E+00 2.170E-07 0.000E+00 6.350E-10 TE-129M 5.570E+08 1.910E+08 2.140E+08 1.390E+09 0.000E+00 3.330E+08 0.000E+00 8.580E+07 TE-131 3.430E-32 1.270E-32 3.060E-32 8.760E-32 0.000E+00 1.380E-30 0.000E+00 9.610E-33 TE-131M 3.380E+06 1.360E+06 2.750E+06 9.350E+06 0.000E+00 2.290E+07 0.000E+00 1.120E+06 TE-132 2.110E+07 1.040E+07 1.540E+07 6.530E+07 0.000E+00 3.870E+07 0.000E+00 9.750E+06 I-130 3.550E+06 7.810E+06 8.750E+08 8.580E+06 0.000E+00 1.670E+06 0.000E+00 3.130E+06 Appendix J Ri Infant Cow Milk - Page 2 of 3 Page 9-174

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 2.720E+09 3.200E+09 1.050E+12 3.740E+09 0.000E+00 1.140E+08 0.000E+00 1.410E+09 I-132 1.430E+00 2.900E+00 1.360E+02 3.240E+00 0.000E+00 2.350E+00 0.000E+00 1.030E+00 I-133 3.630E+07 5.280E+07 9.600E+09 6.210E+07 0.000E+00 8.930E+06 0.000E+00 1.550E+07 I-134 1.760E-11 3.600E-11 8.400E-10 4.030E-11 0.000E+00 3.720E-11 0.000E+00 1.280E-11 I-135 1.120E+05 2.230E+05 2.000E+07 2.490E+05 0.000E+00 8.080E+04 0.000E+00 8.140E+04 CS-134 3.650E+10 6.800E+10 0.000E+00 1.750E+10 7.180E+09 1.850E+08 0.000E+00 6.870E+09 CS-136 1.980E+09 5.810E+09 0.000E+00 2.320E+09 4.740E+08 8.820E+07 0.000E+00 2.170E+09 CS-137 5.150E+10 6.020E+10 0.000E+00 1.620E+10 6.550E+09 1.880E+08 0.000E+00 4.270E+09 CS-138 8.390E-23 1.360E-22 0.000E+00 6.800E-23 1.060E-23 2.180E-22 0.000E+00 6.610E-23 BA-139 4.270E-07 2.830E-10 0.000E+00 1.700E-10 1.720E-10 2.710E-05 0.000E+00 1.240E-08 BA-140 2.410E+08 2.410E+05 0.000E+00 5.720E+04 1.480E+05 5.920E+07 0.000E+00 1.240E+07 BA-141 3.930E-45 2.690E-48 0.000E+00 1.620E-48 1.640E-48 4.800E-44 0.000E+00 1.240E-46 BA-142 2.430E-79 2.020E-82 0.000E+00 1.160E-82 1.220E-82 1.000E-78 0.000E+00 1.200E-80 LA-140 4.050E+01 1.600E+01 0.000E+00 0.000E+00 0.000E+00 1.880E+05 0.000E+00 4.110E+00 LA-142 1.700E-10 6.250E-11 0.000E+00 0.000E+00 0.000E+00 1.060E-05 0.000E+00 1.500E-11 CE-141 4.340E+04 2.640E+04 0.000E+00 8.150E+03 0.000E+00 1.370E+07 0.000E+00 3.110E+03 CE-143 3.970E+02 2.630E+05 0.000E+00 7.670E+01 0.000E+00 1.540E+06 0.000E+00 3.000E+01 CE-144 2.330E+06 9.520E+05 0.000E+00 3.850E+05 0.000E+00 1.330E+08 0.000E+00 1.300E+05 PR-143 1.490E+03 5.550E+02 0.000E+00 2.060E+02 0.000E+00 7.840E+05 0.000E+00 7.360E+01 PR-144 5.690E-53 2.200E-53 0.000E+00 7.980E-54 0.000E+00 1.020E-48 0.000E+00 2.870E-54 ND-147 8.810E+02 9.050E+02 0.000E+00 3.490E+02 0.000E+00 5.740E+05 0.000E+00 5.550E+01 W-187 6.080E+04 4.230E+04 0.000E+00 0.000E+00 0.000E+00 2.480E+06 0.000E+00 1.460E+04 NP-239 3.650E+01 3.260E+00 0.000E+00 6.510E+00 0.000E+00 9.430E+04 0.000E+00 1.840E+00 Appendix J Ri Infant Cow Milk - Page 3 of 3 Page 9-175

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4.860E+03 0.000E+00 4.860E+03 C-14 2.000E+05 4.270E+04 4.270E+04 4.270E+04 4.270E+04 4.270E+04 0.000E+00 4.270E+04 NA-24 1.850E+06 1.850E+06 1.850E+06 1.850E+06 1.850E+06 1.850E+06 0.000E+00 1.850E+06 P-32 1.920E+11 1.130E+10 0.000E+00 0.000E+00 0.000E+00 2.600E+09 0.000E+00 7.460E+09 CR-51 0.000E+00 0.000E+00 1.260E+04 2.760E+03 2.460E+04 5.640E+05 0.000E+00 1.940E+04 MN-54 0.000E+00 4.680E+06 0.000E+00 1.040E+06 0.000E+00 1.720E+06 0.000E+00 1.060E+06 MN-56 0.000E+00 3.720E-03 0.000E+00 3.190E-03 0.000E+00 3.380E-01 0.000E+00 6.410E-04 FE-55 1.760E+06 1.130E+06 0.000E+00 0.000E+00 5.550E+05 1.440E+05 0.000E+00 3.030E+05 FE-59 2.920E+06 5.100E+06 0.000E+00 0.000E+00 1.510E+06 2.430E+06 0.000E+00 2.010E+06 CO-58 0.000E+00 2.910E+06 0.000E+00 0.000E+00 0.000E+00 7.250E+06 0.000E+00 7.260E+06 CO-60 0.000E+00 1.060E+07 0.000E+00 0.000E+00 0.000E+00 2.520E+07 0.000E+00 2.500E+07 NI-63 4.190E+09 2.590E+08 0.000E+00 0.000E+00 0.000E+00 1.290E+07 0.000E+00 1.450E+08 NI-65 4.210E-01 4.760E-02 0.000E+00 0.000E+00 0.000E+00 3.620E+00 0.000E+00 2.170E-02 CU-64 0.000E+00 2.070E+04 0.000E+00 3.500E+04 0.000E+00 4.240E+05 0.000E+00 9.570E+03 ZN-65 6.660E+08 2.280E+09 0.000E+00 1.110E+09 0.000E+00 1.930E+09 0.000E+00 1.050E+09 ZN-69 2.420E-12 4.360E-12 0.000E+00 1.810E-12 0.000E+00 3.550E-10 0.000E+00 3.240E-13 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.120E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.510E-23 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.670E+09 0.000E+00 0.000E+00 0.000E+00 6.830E+07 0.000E+00 1.320E+09 RB-88 0.000E+00 2.250E-45 0.000E+00 0.000E+00 0.000E+00 2.190E-45 0.000E+00 1.230E-45 RB-89 0.000E+00 3.940E-53 0.000E+00 0.000E+00 0.000E+00 1.340E-53 0.000E+00 2.720E-53 SR-89 2.640E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.430E+08 0.000E+00 7.580E+08 SR-90 2.550E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.190E+09 0.000E+00 6.500E+10 SR-91 5.700E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.750E+05 0.000E+00 2.060E+04 Appendix J Ri Infant Goat Milk - Page 1 of 3 Page 9-176

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 9.750E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.050E+02 0.000E+00 3.620E-01 Y-90 8.170E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.130E+05 0.000E+00 2.190E+00 Y-91 8.790E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.300E+05 0.000E+00 2.340E+02 Y-91M 6.810E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.270E-16 0.000E+00 2.320E-21 Y-92 6.450E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.230E+00 0.000E+00 1.810E-06 Y-93 2.590E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.040E+03 0.000E+00 7.050E-03 ZR-95 8.170E+02 1.990E+02 0.000E+00 2.140E+02 0.000E+00 9.910E+04 0.000E+00 1.410E+02 ZR-97 4.870E-01 8.360E-02 0.000E+00 8.430E-02 0.000E+00 5.340E+03 0.000E+00 3.820E-02 NB-95 7.120E+04 2.930E+04 0.000E+00 2.100E+04 0.000E+00 2.480E+07 0.000E+00 1.700E+04 MO-99 0.000E+00 2.500E+07 0.000E+00 3.730E+07 0.000E+00 8.220E+06 0.000E+00 4.870E+06 TC-99M 3.300E+00 6.800E+00 0.000E+00 7.320E+01 3.550E+00 1.970E+03 0.000E+00 8.760E+01 TC-101 2.960E-60 3.730E-60 0.000E+00 4.440E-59 2.030E-60 6.340E-58 0.000E+00 3.690E-59 RU-103 1.040E+03 0.000E+00 0.000E+00 2.170E+03 0.000E+00 1.270E+04 0.000E+00 3.480E+02 RU-105 9.660E-04 0.000E+00 0.000E+00 7.110E-03 0.000E+00 3.840E-01 0.000E+00 3.250E-04 RU-106 2.280E+04 0.000E+00 0.000E+00 2.700E+04 0.000E+00 1.730E+05 0.000E+00 2.850E+03 AG-110M 4.630E+07 3.380E+07 0.000E+00 4.830E+07 0.000E+00 1.750E+09 0.000E+00 2.240E+07 TE-125M 1.810E+07 6.050E+06 6.090E+06 0.000E+00 0.000E+00 8.620E+06 0.000E+00 2.450E+06 TE-127 7.580E+02 2.540E+02 6.170E+02 1.850E+03 0.000E+00 1.590E+04 0.000E+00 1.630E+02 TE-127M 5.050E+07 1.680E+07 1.460E+07 1.240E+08 0.000E+00 2.040E+07 0.000E+00 6.120E+06 TE-129 3.260E-10 1.130E-10 2.740E-10 8.130E-10 0.000E+00 2.610E-08 0.000E+00 7.620E-11 TE-129M 6.690E+07 2.290E+07 2.570E+07 1.670E+08 0.000E+00 3.990E+07 0.000E+00 1.030E+07 TE-131 4.110E-33 1.520E-33 3.670E-33 1.050E-32 0.000E+00 1.660E-31 0.000E+00 1.150E-33 TE-131M 4.050E+05 1.630E+05 3.310E+05 1.120E+06 0.000E+00 2.750E+06 0.000E+00 1.350E+05 TE-132 2.530E+06 1.250E+06 1.850E+06 7.840E+06 0.000E+00 4.640E+06 0.000E+00 1.170E+06 I-130 4.260E+06 9.370E+06 1.050E+09 1.030E+07 0.000E+00 2.010E+06 0.000E+00 3.760E+06 Appendix J Ri Infant Goat Milk - Page 2 of 3 Page 9-177

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; mrem/yr / µCi/m3 (H-3, C-14)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.260E+09 3.850E+09 1.260E+12 4.490E+09 0.000E+00 1.370E+08 0.000E+00 1.690E+09 I-132 1.720E+00 3.480E+00 1.630E+02 3.890E+00 0.000E+00 2.820E+00 0.000E+00 1.240E+00 I-133 4.350E+07 6.340E+07 1.150E+10 7.450E+07 0.000E+00 1.070E+07 0.000E+00 1.860E+07 I-134 2.110E-11 4.320E-11 1.010E-09 4.830E-11 0.000E+00 4.470E-11 0.000E+00 1.540E-11 I-135 1.350E+05 2.680E+05 2.400E+07 2.990E+05 0.000E+00 9.700E+04 0.000E+00 9.770E+04 CS-134 1.090E+11 2.040E+11 0.000E+00 5.250E+10 2.150E+10 5.540E+08 0.000E+00 2.060E+10 CS-136 5.930E+09 1.740E+10 0.000E+00 6.950E+09 1.420E+09 2.650E+08 0.000E+00 6.510E+09 CS-137 1.540E+11 1.810E+11 0.000E+00 4.850E+10 1.960E+10 5.650E+08 0.000E+00 1.280E+10 CS-138 2.520E-22 4.090E-22 0.000E+00 2.040E-22 3.190E-23 6.540E-22 0.000E+00 1.980E-22 BA-139 5.130E-08 3.400E-11 0.000E+00 2.040E-11 2.060E-11 3.250E-06 0.000E+00 1.480E-09 BA-140 2.890E+07 2.890E+04 0.000E+00 6.870E+03 1.780E+04 7.100E+06 0.000E+00 1.490E+06 BA-141 4.720E-46 3.230E-49 0.000E+00 1.940E-49 1.960E-49 5.760E-45 0.000E+00 1.490E-47 BA-142 2.920E-80 2.430E-83 0.000E+00 1.400E-83 1.470E-83 1.200E-79 0.000E+00 1.440E-81 LA-140 4.860E+00 1.920E+00 0.000E+00 0.000E+00 0.000E+00 2.250E+04 0.000E+00 4.930E-01 LA-142 2.040E-11 7.500E-12 0.000E+00 0.000E+00 0.000E+00 1.270E-06 0.000E+00 1.790E-12 CE-141 5.200E+03 3.170E+03 0.000E+00 9.790E+02 0.000E+00 1.640E+06 0.000E+00 3.740E+02 CE-143 4.760E+01 3.160E+04 0.000E+00 9.200E+00 0.000E+00 1.840E+05 0.000E+00 3.600E+00 CE-144 2.790E+05 1.140E+05 0.000E+00 4.620E+04 0.000E+00 1.600E+07 0.000E+00 1.560E+04 PR-143 1.780E+02 6.670E+01 0.000E+00 2.480E+01 0.000E+00 9.410E+04 0.000E+00 8.840E+00 PR-144 6.830E-54 2.640E-54 0.000E+00 9.570E-55 0.000E+00 1.230E-49 0.000E+00 3.440E-55 ND-147 1.060E+02 1.090E+02 0.000E+00 4.190E+01 0.000E+00 6.880E+04 0.000E+00 6.650E+00 W-187 7.300E+03 5.070E+03 0.000E+00 0.000E+00 0.000E+00 2.980E+05 0.000E+00 1.750E+03 NP-239 4.380E+00 3.910E-01 0.000E+00 7.810E-01 0.000E+00 1.130E+04 0.000E+00 2.210E-01 Appendix J Ri Infant Goat Milk - Page 3 of 3 Page 9-178

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 6.470E+02 6.470E+02 6.470E+02 6.470E+02 6.470E+02 0.000E+00 6.470E+02 C-14 2.650E+04 5.310E+03 5.310E+03 5.310E+03 5.310E+03 5.310E+03 0.000E+00 5.310E+03 NA-24 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 0.000E+00 1.060E+04 P-32 2.030E+06 1.120E+05 0.000E+00 0.000E+00 0.000E+00 1.610E+04 0.000E+00 7.740E+04 CR-51 0.000E+00 0.000E+00 5.750E+01 1.320E+01 1.280E+04 3.570E+02 0.000E+00 8.950E+01 MN-54 0.000E+00 2.530E+04 0.000E+00 4.980E+03 1.000E+06 7.060E+03 0.000E+00 4.980E+03 MN-56 0.000E+00 1.540E+00 0.000E+00 1.100E+00 1.250E+04 7.170E+04 0.000E+00 2.210E-01 FE-55 1.970E+04 1.170E+04 0.000E+00 0.000E+00 8.690E+04 1.090E+03 0.000E+00 3.330E+03 FE-59 1.360E+04 2.350E+04 0.000E+00 0.000E+00 1.010E+06 2.480E+04 0.000E+00 9.480E+03 CO-58 0.000E+00 1.220E+03 0.000E+00 0.000E+00 7.770E+05 1.110E+04 0.000E+00 1.820E+03 CO-60 0.000E+00 8.020E+03 0.000E+00 0.000E+00 4.510E+06 3.190E+04 0.000E+00 1.180E+04 NI-63 3.390E+05 2.040E+04 0.000E+00 0.000E+00 2.090E+05 2.420E+03 0.000E+00 1.160E+04 NI-65 2.390E+00 2.840E-01 0.000E+00 0.000E+00 8.120E+03 5.010E+04 0.000E+00 1.230E-01 CU-64 0.000E+00 1.880E+00 0.000E+00 3.980E+00 9.300E+03 1.500E+04 0.000E+00 7.740E-01 ZN-65 1.930E+04 6.260E+04 0.000E+00 3.250E+04 6.470E+05 5.140E+04 0.000E+00 3.110E+04 ZN-69 5.390E-02 9.670E-02 0.000E+00 4.020E-02 1.470E+03 1.320E+04 0.000E+00 7.180E-03 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.810E+02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.000E+02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.040E+01 RB-86 0.000E+00 1.900E+05 0.000E+00 0.000E+00 0.000E+00 3.040E+03 0.000E+00 8.820E+04 RB-88 0.000E+00 5.570E+02 0.000E+00 0.000E+00 0.000E+00 3.390E+02 0.000E+00 2.870E+02 RB-89 0.000E+00 3.210E+02 0.000E+00 0.000E+00 0.000E+00 6.820E+01 0.000E+00 2.060E+02 SR-89 3.980E+05 0.000E+00 0.000E+00 0.000E+00 2.030E+06 6.400E+04 0.000E+00 1.140E+04 SR-90 4.090E+07 0.000E+00 0.000E+00 0.000E+00 1.120E+07 1.310E+05 0.000E+00 2.590E+06 SR-91 9.560E+01 0.000E+00 0.000E+00 0.000E+00 5.260E+04 7.340E+04 0.000E+00 3.460E+00 Appendix J Ri Infant Inhalation - Page 1 of 3 Page 9-179

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.050E+01 0.000E+00 0.000E+00 0.000E+00 2.380E+04 1.400E+05 0.000E+00 3.910E-01 Y-90 3.290E+03 0.000E+00 0.000E+00 0.000E+00 2.690E+05 1.040E+05 0.000E+00 8.820E+01 Y-91 5.880E+05 0.000E+00 0.000E+00 0.000E+00 2.450E+06 7.030E+04 0.000E+00 1.570E+04 Y-91M 4.070E-01 0.000E+00 0.000E+00 0.000E+00 2.790E+03 2.350E+03 0.000E+00 1.390E-02 Y-92 1.640E+01 0.000E+00 0.000E+00 0.000E+00 2.450E+04 1.270E+05 0.000E+00 4.610E-01 Y-93 1.500E+02 0.000E+00 0.000E+00 0.000E+00 7.640E+04 1.670E+05 0.000E+00 4.070E+00 ZR-95 1.150E+05 2.790E+04 0.000E+00 3.110E+04 1.750E+06 2.170E+04 0.000E+00 2.030E+04 ZR-97 1.500E+02 2.560E+01 0.000E+00 2.590E+01 1.100E+05 1.400E+05 0.000E+00 1.170E+01 NB-95 1.570E+04 6.430E+03 0.000E+00 4.720E+03 4.790E+05 1.270E+04 0.000E+00 3.780E+03 MO-99 0.000E+00 1.650E+02 0.000E+00 2.650E+02 1.350E+05 4.870E+04 0.000E+00 3.230E+01 TC-99M 1.400E-03 2.880E-03 0.000E+00 3.110E-02 8.110E+02 2.030E+03 0.000E+00 3.720E-02 TC-101 6.510E-05 8.230E-05 0.000E+00 9.790E-04 5.840E+02 8.440E+02 0.000E+00 8.120E-04 RU-103 2.020E+03 0.000E+00 0.000E+00 4.240E+03 5.520E+05 1.610E+04 0.000E+00 6.790E+02 RU-105 1.220E+00 0.000E+00 0.000E+00 8.990E-01 1.570E+04 4.840E+04 0.000E+00 4.100E-01 RU-106 8.680E+04 0.000E+00 0.000E+00 1.070E+05 1.160E+07 1.640E+05 0.000E+00 1.090E+04 AG-110M 9.980E+03 7.220E+03 0.000E+00 1.090E+04 3.670E+06 3.300E+04 0.000E+00 5.000E+03 TE-125M 4.760E+03 1.990E+03 1.620E+03 0.000E+00 4.470E+05 1.290E+04 0.000E+00 6.580E+02 TE-127 2.230E+00 9.530E-01 1.850E+00 4.860E+00 1.030E+04 2.440E+04 0.000E+00 4.890E-01 TE-127M 1.670E+04 6.900E+03 4.870E+03 3.750E+04 1.310E+06 2.730E+04 0.000E+00 2.070E+03 TE-129 7.880E-02 3.470E-02 6.750E-02 1.750E-01 3.000E+03 2.630E+04 0.000E+00 1.880E-02 TE-129M 1.410E+04 6.090E+03 5.470E+03 3.180E+04 1.680E+06 6.900E+04 0.000E+00 2.230E+03 TE-131 1.740E-02 8.220E-03 1.580E-02 3.990E-02 2.060E+03 8.220E+03 0.000E+00 5.000E-03 TE-131M 1.070E+02 5.500E+01 8.930E+01 2.650E+02 1.990E+05 1.190E+05 0.000E+00 3.630E+01 TE-132 3.720E+02 2.370E+02 2.790E+02 1.030E+03 3.400E+05 4.410E+04 0.000E+00 1.760E+02 I-130 6.360E+03 1.390E+04 1.600E+06 1.530E+04 0.000E+00 1.990E+03 0.000E+00 5.570E+03 Appendix J Ri Infant Inhalation - Page 2 of 3 Page 9-180

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.790E+04 4.440E+04 1.480E+07 5.180E+04 0.000E+00 1.060E+03 0.000E+00 1.960E+04 I-132 1.690E+03 3.540E+03 1.690E+05 3.950E+03 0.000E+00 1.900E+03 0.000E+00 1.260E+03 I-133 1.320E+04 1.920E+04 3.560E+06 2.240E+04 0.000E+00 2.160E+03 0.000E+00 5.600E+03 I-134 9.210E+02 1.880E+03 4.450E+04 2.090E+03 0.000E+00 1.290E+03 0.000E+00 6.650E+02 I-135 3.860E+03 7.600E+03 6.960E+05 8.470E+03 0.000E+00 1.830E+03 0.000E+00 2.770E+03 CS-134 3.960E+05 7.030E+05 0.000E+00 1.900E+05 7.970E+04 1.330E+03 0.000E+00 7.450E+04 CS-136 4.830E+04 1.350E+05 0.000E+00 5.640E+04 1.180E+04 1.430E+03 0.000E+00 5.290E+04 CS-137 5.490E+05 6.120E+05 0.000E+00 1.720E+05 7.130E+04 1.330E+03 0.000E+00 4.550E+04 CS-138 5.050E+02 7.810E+02 0.000E+00 4.100E+02 6.540E+01 8.760E+02 0.000E+00 3.980E+02 BA-139 1.480E+00 9.840E-04 0.000E+00 5.920E-04 5.950E+03 5.100E+04 0.000E+00 4.300E-02 BA-140 5.600E+04 5.600E+01 0.000E+00 1.340E+01 1.600E+06 3.840E+04 0.000E+00 2.900E+03 BA-141 1.570E-01 1.080E-04 0.000E+00 6.500E-05 2.970E+03 4.750E+03 0.000E+00 4.970E-03 BA-142 3.980E-02 3.300E-05 0.000E+00 1.900E-05 1.550E+03 6.930E+02 0.000E+00 1.960E-03 LA-140 5.050E+02 2.000E+02 0.000E+00 0.000E+00 1.680E+05 8.480E+04 0.000E+00 5.150E+01 LA-142 1.030E+00 3.770E-01 0.000E+00 0.000E+00 8.220E+03 5.950E+04 0.000E+00 9.040E-02 CE-141 2.770E+04 1.670E+04 0.000E+00 5.250E+03 5.170E+05 2.160E+04 0.000E+00 1.990E+03 CE-143 2.930E+02 1.930E+02 0.000E+00 5.640E+01 1.160E+05 4.970E+04 0.000E+00 2.210E+01 CE-144 3.190E+06 1.210E+06 0.000E+00 5.380E+05 9.840E+06 1.480E+05 0.000E+00 1.760E+05 PR-143 1.400E+04 5.240E+03 0.000E+00 1.970E+03 4.330E+05 3.720E+04 0.000E+00 6.990E+02 PR-144 4.790E-02 1.850E-02 0.000E+00 6.720E-03 1.610E+03 4.280E+03 0.000E+00 2.410E-03 ND-147 7.940E+03 8.130E+03 0.000E+00 3.150E+03 3.220E+05 3.120E+04 0.000E+00 5.000E+02 W-187 1.300E+01 9.020E+00 0.000E+00 0.000E+00 3.960E+04 3.560E+04 0.000E+00 3.120E+00 NP-239 3.710E+02 3.320E+01 0.000E+00 6.620E+01 5.950E+04 2.490E+04 0.000E+00 1.880E+01 Appendix J Ri Infant Inhalation - Page 3 of 3 Page 9-181

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.390E+07 1.190E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530E+10 2.150E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.150E+06 Appendix J Ri Infant Ground Plane Deposition - Page 1 of 3 Page 9-182

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.310E+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.110E+05 1.840E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-110M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 TE-127 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04 TE-129 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 TE-129M 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 I-130 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.510E+06 Appendix J Ri Infant Ground Plane Deposition - Page 2 of 3 Page 9-183

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.090E+07 1.720E+07 I-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 I-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2.450E+06 I-134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 I-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS-134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.000E+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.710E+08 1.510E+08 CS-137 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 4.100E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.110E+04 4.490E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 2.110E+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.980E+06 1.710E+06 Appendix J Ri Infant Ground Plane Deposition - Page 3 of 3 Page 9-184

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 SELECTED LICENSEE COMMITMENTS (SLC)

LOES SLCs ARE REVISED PER SECTION SECTION REVISION NUMBER DATE 16.1 REVISION 148 2/27/15 16.2 REVISION 134 3/6/13 16.3 REVISION 134 3/6/13 16.4 Not Issued 16.5.1 REVISION 151 9/29/15 16.5.2 REVISION 148 2/27/15 16.5.3 REVISION 151 9/29/15 16.5.4 REVISION 148 2/27/15 16.5.5 REVISION 148 2/27/15 16.5.6 DELETED - REVISION 120 12/30/10 16.5.7 REVISION 53 1/13/04 16.5.8 REVISION 0 12/14/99 16.5.9 REVISION 108 06/10/09 16.5.10 REVISION 134 3/6/13 16.6.1 REVISION 0 12/14/99 16.6.2 DELETED - REVISION 43 6/11/03 16.6.3 REVISION 134 3/6/13 16.6.4 REVISION 27 06/12/02 16.7.1 REVISION 149 2/25/15 16.7.2 REVISION 134 3/6/13 16.7.3 REVISION 136 4/26/13 16.7.4 REVISION 134 3/6/13 16.7.5 REVISION 134 3/6/13 16.7.6 REVISION 139 8/28/13 16.7.7 REVISION 134 3/6/13 16.7.8 REVISION 134 3/6/13 16.7.9 REVISION 134 3/6/13 16.7.10 REVISION 134 3/6/13 16.7.11 REVISION 134 3/6/13 16.7.12 REVISION 144 9/18/14 16.7.13 REVISION 146 10/14/14 16.7.14 REVISION 152 9/23/15 16.8.1 REVISION 135 3/18/13 16.8.2 REVISION 148 2/27/15 16.8.3 REVISION 121 12/30/10 16.9.1 REVISION 134 3/6/13 16.9.2 REVISION 134 3/6/13 16.9.3 REVISION 134 3/6/13 16.9.4 REVISION 134 3/6/13 16.9.5 REVISION 134 3/6/13 16.9.6 REVISION 142 10/27/15 16.9.7 REVISION 153 10/1/15 McGuire Units 1 and 2 1 Revision 133 Page 9-185

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 SELECTED LICENSEE COMMITMENTS (SLC)

LOES SLCs ARE REVISED PER SECTION SECTION REVISION NUMBER DATE 16.9.8 REVISION 134 3/6/13 16.9.9 REVISION 154 10/1/15 16.9.10 DELETED - REVISION 13 2/26/01 16.9.11 REVISION 22 2/25/02 16.9.12 REVISION 148 2/27/15 16.9.13 DELETED - REVISION 13 2/26/01 16.9.14 REVISION 22 2/25/02 16.9.15 REVISION 134 3/6/13 16.9.16 REVISION 111 09/09/09 16.9.17 REVISION 86 1/17/07 16.9.18 REVISION 0 12/14/99 16.9.19 REVISION 134 3/6/13 16.9.20 REVISION 8 11/30/00 16.9.21 REVISION 0 12/14/99 16.9.22 REVISION 109 8/13/09 16.9.23 REVISION 134 3/6/13 16.9.24 DELETED - REVISION 74 6/27/05 16.9.25 REVISION 87 1/17/07 16.9.26 REVISION 150 5/11/16 16.10.1 REVISION 56 4/6/04 16.11.1 REVISION 137 5/13/13 16.11.2 REVISION 134 3/6/13 16.11.3 REVISION 0 12/14/99 16.11.4 REVISION 134 3/6/13 16.11.5 REVISION 0 12/14/99 16.11.6 REVISION 137 5/13/13 16.11.7 REVISION 134 3/6/13 16.11.8 REVISION 0 12/14/99 16.11.9 REVISION 0 12/14/99 16.11.10 REVISION 134 3/6/13 16.11.11 REVISION 134 3/6/13 16.11.12 REVISION 67 2/28/05 16.11.13 REVISION 137 5/13/13 16.11.14 REVISION 21 1/17/02 16.11.15 REVISION 21 1/17/02 16.11.16 REVISION 134 3/6/13 16.11.17 REVISION 143 5/30/14 16.11.18 REVISION 0 12/14/99 16.11.19 REVISION 0 12/14/99 16.11.20 REVISION 0 12/14/99 16.12.1 REVISION 0 12/14/99 16.12.2 REVISION 0 12/14/99 McGuire Units 1 and 2 2 Revision 133 Page 9-186

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 SELECTED LICENSEE COMMITMENTS (SLC)

LOES SLCs ARE REVISED PER SECTION SECTION REVISION NUMBER DATE 16.13.1 REVISION 51 10/1/03 16.13.2 DELETED - REVISION 75 7/20/05 16.13.3 DELETED - REVISION 75 7/20/05 16.13.4 REVISION 148 2/27/15 16.14.1 REVISION 0 12/14/99 16.14.2 REVISION 104 3/18/09 McGuire Units 1 and 2 3 Revision 133 Page 9-187

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Concentration 16.11.1 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.1 Liquid Effluents - Concentration COMMITMENT The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 16.11.1-1) shall be limited:

a. For radionuclides other than dissolved or entrained noble gases, 10 times the effluent concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, and

b. For dissolved or entrained noble gases, the concentration shall

-4 be limited to 2 x 10 microCurie/ml total activity.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of A.1 Restore the concentration Immediately radioactive material to within limits.

released in liquid effluents to UNRESTRICTED AREAS not within limits.

TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.1.1 ---------------------------------NOTE--------------------------------

The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits.

Sample and analyze radioactive liquid wastes according According to to Table 16.11.1-1. Table 16.11.1-1 McGuire Units 1 and 2 16.11.1-1 Revision 137 Page 9-188

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Concentration 16.11.1 TABLE 16.11.1-1 (Page 1 of 3)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE SAMPLING MINIMUM TYPE OF LOWER LIMIT TYPE FREQUENCY ANALYSIS ACTIVITY OF DETECTION FREQUENCY ANALYSIS (LLD) microCi/ml (1)

1. Batch Waste P P Principal Release Tanks Each Batch Each Batch Gamma 5x10-7 (WMT and Emitters(6)

RMT)(4)

-6 I-131 1x10 P M Dissolved and

-5 One Batch/M Entrained 1x10 Gases (Gamma emitters)(7)

P M H-3 1x10-5 Each Batch Composite(2)

-7 Gross Alpha 1x10 P Q Sr-89, Sr-90 5x10-8 Each Batch Composite(2)

(3)

2. Continuous Continuous W Principal Releases Composite(3) Gamma 5x10-7 (6)

(VUCDT Emitters discharge, CWWTS outlet and Turbine Building Sump (5) to RC)

I-131 1x10-6 M M Dissolved and Grab Sample Entrained 1x10-5 Gases (Gamma emitters)(7)

(3) -5 Continuous M H-3 1x10 (3)

Composite Gross Alpha 1x10-7 Continuous(3) Q Sr-89, Sr-90 5x10-8 (3)

Composite McGuire Units 1 and 2 16.11.1-2 Revision 137 Page 9-189

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Concentration 16.11.1 TABLE 16.11.1-1 (Page 2 of 3)

NOTES:

(1) The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

(2.71 / T ) + 4.65S b LLD =

E V 2.22 x 10 6 Y exp (t )

Where:

LLD is the "a priori" lower limit of detection as defined above (as microCurie per unit mass or volume),

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per disintegration),

V is the sample size (in units of mass or volume),

6 2.22 x 10 is the number of disintegrations per minute per microCurie, Y is the fractional radiochemical yield (when applicable),

is the radioactive decay constant for the particular radionuclide, t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples), and T is the background and sample counting time in minutes.

Typical values of E, V, Y and t shall be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

(2) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

McGuire Units 1 and 2 16.11.1-3 Revision 137 Page 9-190

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(3) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously or intermittently in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

(4) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and thoroughly mixed to assure representative sampling.

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g.,

from a volume of system that has an input flow during the continuous release.

(6) The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. The LLD for Ce-144 is 5x10-6 microCi/ml. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified and reported in the Annual Radioactive Effluent Release Report.

(7) The principal gas gamma emitters for which the LLD specification applies are Xe-133 and Xe-135. These are the reference nuclides in Regulatory Guide 1.21.

McGuire Units 1 and 2 16.11.1-4 Revision 137 Page 9-191

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Concentration 16.11.1 FIGURE 16.11.1-1 SITE BOUNDARY / EXCLUSION AREA BOUNDARY McGuire Units 1 and 2 16.11.1-5 Revision 137 Page 9-192

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Concentration 16.11.1 BASES This commitment is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the effluent concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.1301 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its EC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. This commitment applies to the release of liquid effluents from all reactors at the site.

The basic requirements for the Selected Licensee Commitments concerning effluents from nuclear power reactors are stated in 10CFR50.36a. These requirements indicate that compliance with effluent Selected Licensee Commitments will keep average annual releases of radioactive material in effluents to small percentages of the limits specified in the old 10CFR20.106 (new 10CFR20.1301). These requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10CFR20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem. It is further indicated in 10CFR50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as is reasonably achievable (ALARA) as set forth in 10CFR50, Appendix I.

As stated in the Introduction to Appendix B of the new 10CFR20, the effluent concentration (EC) limits given in Appendix B, Table 2, Column 2, are based on an annual dose of 50 mrem. Since a release concentration corresponding to a limiting dose rate of 500 mrem/year has been acceptable as a SLC limit for liquid effluents, which applies at all times as an assurance that the limits of 10CFR50, Appendix I are not likely to be exceeded, it should not be necessary to reduce this limit by a factor of 10.

Operational history at Catawba/McGuire/Oconee has demonstrated that the use of the concentration values associated with the old 10CFR20.106 as SLC limits has resulted in calculated maximum individual doses to members of the public that are small percentages of the limits of 10CFR50, Appendix I. Therefore, the use of concentration values which correspond to an annual dose of 500 mrem should not have a negative impact on the ability to continue to operate within the limits of 10CFR50 Appendix I and 40CFR190.

Having sufficient operational flexibility is especially important in establishing a basis for effluent monitor setpoint calculations. As discussed above, the concentrations stated in the new 10CFR20, Appendix B, Table 2, Column 2, relate to a dose of 50 mrem in a year.

When applied on an instantaneous basis, this corresponds to a dose rate of 50 mrem/year.

This low value is impractical upon which to base effluent monitor setpoint calculations for many liquid effluent release situations when monitor background, monitor sensitivity, and monitor performance must be taken into account.

BASES (continued)

McGuire Units 1 and 2 16.11.1-6 Revision 137 Page 9-193

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Concentration 16.11.1 Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with SLC 16.11.1 are based on ten times the concentrations stated in the new 10CFR20, Appendix B, Table 2, Column 2 to apply at all times. The multiplier of ten is proposed because the annual dose of 500 mrem, upon which the concentrations in the old 10CFR20, Appendix B, Table II, Column 2 are based, is a factor of ten higher than the annual dose of 50 mrem, upon which the concentrations in the new 10CFR20, Appendix B, Table 2, Column 2, are based. Compliance with the limits of the new 10CFR20.1301 will be demonstrated by operating within the limits of 10CFR50, Appendix I and 40CFR190.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K.,

"Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

REFERENCES

1. McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

2. International Commission on Radiological Protection (ICRP) Publication 2 McGuire Units 1 and 2 16.11.1-7 Revision 137 Page 9-194

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Liquid Effluent Monitoring Instrumentation 16.11.2 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.2 Radioactive Liquid Effluent Monitoring Instrumentation COMMITMENT The radioactive liquid effluent monitoring instrumentation channels shown in Table 16.11.2-1 shall be FUNCTIONAL with their Alarm/Trip Setpoints set to ensure that the limits of SLC 16.11.1 are not exceeded.

AND The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY As shown in Table 16.11.2-1.

REMEDIAL ACTIONS

NOTE-----------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more radioactive A.1 Suspend the release of Immediately liquid effluent monitoring radioactive liquid effluents channels Alarm/Trip monitored by the affected setpoint less channel.

conservative than required. OR A.2 Declare the channel non- Immediately functional.

OR A.3 Adjust setpoint to within Immediately limit.

B. One or more radioactive B.1 Enter the Remedial Action Immediately liquid effluent monitoring specified in Table 16.11.2-instrument channels 1 for the channel(s).

non-functional.

(continued)

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Liquid Effluent Monitoring Instrumentation 16.11.2 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One channel non- C.1.1 Analyze two independent Prior to initiating a functional. samples per TR 16.11.1.1. release AND C.1.2 Perform independent Prior to initiating a verification of the discharge release line valving.

AND C.1.3.1 Perform independent Prior to initiating a verification of manual release portion of the computer input for the release rate calculations performed by computer.

OR C.1.3.2 Perform independent Prior to initiating a verification of entire release release rate calculations for calculations performed manually.

AND C.1.4 Restore channel to 14 days FUNCTIONAL status.

OR C.2 Suspend the release of Immediately radioactive effluents via this pathway.

(continued)

McGuire Units 1 and 2 16.11.2-2 Revision 134 Page 9-196

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Liquid Effluent Monitoring Instrumentation 16.11.2 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more channels D.1 Obtain grab samples from Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months non-functional. the effluent pathway. during releases.

AND D.2 Perform an analysis of To meet LLD grab samples for requirements per radioactivity. Table 16.11.1-1.

AND D.3 Restore the channel to 30 days FUNCTIONAL status.

E. One or more flow rate E.1 -------------NOTE---------------

measurement channels Pump performance curves non-functional. generated in place may be used to estimate flow.

Estimate the flow rate of Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the release. during releases AND E.2 Restore the channel to 30 days FUNCTIONAL status.

F. RC minimum flow F.1 Verify that the number of Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months interlock non-functional. pumps providing dilution is during releases greater than or equal to the number of pumps required.

AND F.2 Restore the channel to 30 days FUNCTIONAL status.

(continued)

McGuire Units 1 and 2 16.11.2-3 Revision 134 Page 9-197

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Liquid Effluent Monitoring Instrumentation 16.11.2 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Explain why the non- In the next associated Completion functionality was not scheduled Annual Time of Condition C, D, corrected within the Radioactive Effluent E or F not met. specified Completion Time Release Report in the Annual Radioactive Effluent Release Report.

McGuire Units 1 and 2 16.11.2-4 Revision 134 Page 9-198

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Liquid Effluent Monitoring Instrumentation 16.11.2 TESTING REQUIREMENTS

NOTE-------------------------------------------------------

Refer to Table 16.11.2-1 to determine which TRs apply for each Radioactive Liquid Effluent Monitoring channel.

TEST FREQUENCY TR 16.11.2.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TR 16.11.2.2 --------------------------------NOTE-----------------------------------

The CHANNEL CHECK shall consist of verifying indication of flow.

Perform CHANNEL CHECK. Every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during periods of release TR 16.11.2.3 Perform SOURCE CHECK. Prior to each release TR 16.11.2.4 Perform SOURCE CHECK. 31 days TR 16.11.2.5 ---------------------------------NOTES--------------------------------

1. For Instrument 1, the COT shall also demonstrate that automatic isolation of the pathway occurs if the instrument indicates measured levels above the Alarm/Trip Setpoint.

2. For Instruments 1 and 2, the COT shall also demonstrate that control room alarm annunciation occurs if the instrument indicates measured levels above the Alarm/Trip Setpoint; circuit failure and, a downscale failure.

Perform CHANNEL OPERATIONAL TEST. 92 days TR 16.11.2.6 Perform a CHANNEL CALIBRATION. 18 months (continued)

McGuire Units 1 and 2 16.11.2-5 Revision 134 Page 9-199

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Liquid Effluent Monitoring Instrumentation 16.11.2 TESTING REQUIREMENTS (continued)

TEST FREQUENCY TR 16.11.2.7 ----------------------------NOTE--------------------------------------

The initial CHANNEL CALIBRATION shall be performed using standards certified by the National Institute of Standards and Technology (NIST) or using standards obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

Perform a CHANNEL CALIBRATION. 24 months McGuire Units 1 and 2 16.11.2-6 Revision 134 Page 9-200

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Liquid Effluent Monitoring Instrumentation 16.11.2 TABLE 16.11.2-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM REMEDIAL APPLICABILITY TESTING CHANNELS ACTION REQUIREMENTS FUNCTIONAL

1. Radioactivity Monitors Providing Alarm And Automatic Termination of Release

a. Waste Liquid Effluent Line (EMF-49) 1 per station A, C, G During liquid TR 16.11.2.1 effluent releases TR 16.11.2.3 TR 16.11.2.5 TR 16.11.2.7

b. EMF-49 Minimum Flow Device 1 per station C, G During liquid TR 16.11.2.5 (2) effluent releases TR 16.11.2.7

c. Containment Ventilation Unit Condensate 1 A, D, G At all times TR 16.11.2.1 Line (EMF-44) TR 16.11.2.4 TR 16.11.2.5 TR 16.11.2.7

d. EMF-44 Minimum Flow Device 1 D, G At all times TR 16.11.2.5 (2) TR 16.11.2.7

2. Radioactivity Monitors Providing Alarm But Not Automatic Termination of Release

a. Conventional Waste Water Treatment 1 A, D, G At all times TR 16.11.2.1 Line or Turbine Building Sump to RC TR 16.11.2.4 (EMF- 31)

TR 16.11.2.5 TR 16.11.2.7 1 D, G At all times TR 16.11.2.5

b. EMF-31 Minimum Flow Device (2)

TR 16.11.2.7

3. Continuous Composite Samplers

a. Containment Ventilation Unit Condensate 1 D, G At all times TR 16.11.2.2 Line TR 16.11.2.5 TR 16.11.2.6

b. Conventional Waste Water Treatment Line 1 per station D, G At all times TR 16.11.2.2 TR 16.11.2.5 TR 16.11.2.6

c. Turbine Building Sump to RC 1 D, G At all times TR 16.11.2.2 TR 16.11.2.6 (Continued)

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Liquid Effluent Monitoring Instrumentation 16.11.2

4. Flow Rate Measurement Devices

a. Waste Liquid Effluent Line 1 per station E, G During liquid TR 16.11.2.2 effluent releases TR 16.11.2.5 TR 16.11.2.6

b. Containment Ventilation Unit Condensate 1 E, G At all times TR 16.11.2.2 Line TR 16.11.2.5 TR 16.11.2.6

c. Conventional Waste Water Treatment Line 1 per station E, G At all times TR 16.11.2.2 TR 16.11.2.5 TR 16.11.2.6

d. Turbine Building Sump to RC 1 E, G At all times TR 16.11.2.2 TR 16.11.2.6

5. RC Minimum Flow Interlock (1) 1 per station F, G At all times TR 16.11.2.5 NOTES:

1. Minimum flow dilution is assured by an interlock which terminates waste liquid release if the number of RC pumps running falls below the number of pumps required for dilution. The required number of RC pumps for dilution is determined per station procedures.

2. Radioactivity Monitor (EMF) shall not be declared functional unless both the EMF and the associated EMF's Minimum Flow Device are rendered functional.

BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The minimum flow devices for EMFs listed in Table 16.11.2-1 are required to provide assurance of representative sampling during actual or potential releases of liquid effluents. An interlock between the EMF's minimum flow device and its associated flow rate measurement device disables the remove alarm during non-release timeframes for the purpose of the control room black board annunciator criteria that disable expected alarms. An EMF flow rate measurement device measures total flow of the effluent while the EMF minimum flow device measures the sample flow rate through the EMF. The Alarm/Trip Setpoints of these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm/Trip will occur prior to exceeding the limits stated in SLC 16.11.1. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The Turbine Building Sump to RC Discharge Flow Measurement and Sampler Devices are for monitoring only and do not alarm or have any controls that require a COT.

REFERENCES

1. McGuire Nuclear Station Offsite Dose Calculation Manual (ODCM)

2. 10 CFR Part 50, Appendix A McGuire Units 1 and 2 16.11.2-8 Revision 134 Page 9-202

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Dose - Liquid Effluents 16.11.3 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.3 Dose - Liquid Effluents COMMITMENT The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS (see Figure16.11.1-1) shall be limited:

a. During any calendar quarter, to < 1.5 mrem to the total body and to < 5 mrem to any organ, and

b. During any calendar year, to < 3 mrem to the total body and to

< 10 mrem to any organ.

APPLICABILITY At all times.

REMEDIAL ACTIONS

NOTES-----------------------------------------------------

Enter applicable Conditions and Required Actions of SLC 16.11.12, "Total Dose," when the limits of this SLC are exceeded by twice the specified limit.

CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated dose from ---------------------NOTE--------------

release of radioactive The Special Report shall include materials in liquid the results of radiological analyses effluents exceeding of the drinking water source, and above limits. the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act, as applicable.

A.1 Prepare and submit a 30 days Special Report to the NRC which identifies the causes for exceeding the limits, corrective actions taken to reduce releases, and actions taken to ensure that subsequent releases are within limits.

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Dose - Liquid Effluents 16.11.3 TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.3.1 Determine cumulative dose contributions from liquid 31 days effluents for current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM.

BASES This commitment is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The commitment implements the guides set forth in Section Il.A of Appendix I. The REMEDIAL ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. These requirements are applicable only if the drinking water supply is taken from the river 3 miles downstream of the plant discharge.

The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in 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," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977.

This commitment applies to the release of liquid effluents from each unit at the site. For units with shared Radwaste Treatment Systems, the liquid effluents from the shared system are to be proportioned among the units sharing that system in accordance with the guidance given in NUREG-0133, Chapter 3.1.

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11.3 REFERENCES

1. McGuire Nuclear Station, Off site Dose Calculation Manual

2. 40 CFR Part 141, Safe Drinking Water Act

3. 10 CFR Part 50, Appendix I

4. 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," Revision 1, October 1977.

5. Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977.

McGuire Units 1 and 2 16.11.3-3 Revision 0 Page 9-205

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Radwaste Treatment System 16.11.4 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.4 Liquid Radwaste Treatment System COMMITMENT The Liquid Radwaste Treatment System shall be FUNCTIONAL and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent from each unit to UNRESTRICTED AREAS (see Figure16.11.1-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive liquid waste A.1 Prepare and submit a 30 days being discharged without Special Report to the NRC treatment and in excess which identifies the reasons of above limits. liquid radwaste was discharged without AND treatment, identification of non-functional equipment Any portion of Liquid and reasons for non-Radwaste Treatment functionality, corrective System not in operation. actions taken to restore the equipment to FUNCTIONAL status, and actions taken to prevent recurrence.

McGuire Units 1 and 2 16.11.4-1 Revision 134 Page 9-206

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Radwaste Treatment System 16.11.4 TESTING REQUIREMENTS

NOTE-------------------------------------------------

The Liquid Radwaste Treatment System shall be demonstrated FUNCTIONAL by meeting SLC 16.11.1 and16.11.3.

TEST FREQUENCY TR 16.11.4.1 Project liquid release doses from each unit to 31 days UNRESTRICTED AREAS, in accordance with the methodology and parameters in the ODCM, when water systems are being released without being processed by its radwaste treatment system.

BASES The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

This commitment applies to the release of liquid effluents from each reactor at the site. For units with shared Radwaste Treatment Systems, the liquid effluents from the shared system are to be proportioned among the units sharing that system in accordance with the guidance given in NUREG-0133, Chapter 3.1.

REFERENCES

1. McGuire Nuclear Station, Off site Dose Calculation Manual

2. 10 CFR Part 50

3. 10 CFR Part 50, Appendix I McGuire Units 1 and 2 16.11.4-2 Revision 134 Page 9-207

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Chemical Treatment Ponds 16.11.5 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.5 Chemical Treatment Ponds COMMITMENT The quantity of radioactive material contained in each chemical treatment pond shall be limited by the following expression (excluding tritium and dissolved or entrained noble gases):

264 Aj

< 1 .0 V j (C j x 10)

Where:

A j = pond inventory limit for single radionuclide j, in Curies C j = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide j, microCuries/ml; V = design volume of liquid and slurry in the pond, in gallons; and 264 = conversion unit, microCuries/Curie per milliliter/gallon.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Quantity of radioactive A.1 Suspend all additions of Immediately material in any of the radioactive material to the chemical treatment pond.

ponds exceeding above limit. AND A.2 Initiate corrective action to Immediately reduce the pond contents to within limits.

McGuire Units 1 and 2 16.11.5-1 Revision 0 Page 9-208

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Chemical Treatment Ponds 16.11.5 TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.5.1 Verify quantity of radioactive material in each batch of Prior to each slurry (powdex resin) to be transferred to chemical transfer treatment ponds is within limits by analyzing a representative sample of the slurry. Each batch to be transferred to the chemical treatment ponds is limited by:

Q j pCi / gm

< 6.0 x 10 5 j (C j x 10) µCi / ml BASES The inventory limits of the chemical treatment ponds (CTP) are based on limiting the consequences of an uncontrolled release of the pond inventory. The expression in SLC 16.11.5 assumes the pond inventory is uniformly mixed, that the pond is located in an uncontrolled area as defined in 10 CFR Part 20, and that the concentration limit in Note 4 to Appendix B of 10 CFR Part 20 applies.

The batch limits of slurry to the chemical treatment ponds assure that radioactive material in the slurry transferred to the CTP are "as low as is reasonably achievable" in accordance with 10 CFR Part 50.36a. The expression in SLC 16.11.5 assures no batch of slurry will be transferred to the CTP unless the sum-of the ratios of the activity of the radionuclides to their respective concentration limitation is less than the ratio of the 10 CFR Part 50, Appendix I, Section II.A, total body dose level to the instantaneous whole body dose rate limitation, or that:

c j 3 mrem / yr

< = 0.006 j (C j x 10) 500 mrem / yr Where:

c j = Radioactive slurry concentration for radionuclide j entering the UNRESTRICTED AREA chemical treatment ponds, in microCuries/milliliter; and Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide j, in microCuries/milliliter.

McGuire Units 1 and 2 16.11.5-2 Revision 0 Page 9-209

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Chemical Treatment Ponds 16.11.5 BASES (continued)

For the design of filter/demineralizers using powder resin, the slurry wash volume and the weight of resin used per batch is fixed by the cell surface area, and the slurry volume to resin weight ratio is constant at 100 ml/gram of wet, drained resin with a moisture content of approximately 55 to 60% (bulk density of about 58 pounds per cubic feet). Therefore, cj Q j

= < 0.006, and j (C j x 10) j (C j x 10) (10 ml / gm) (10 6 pCi / µCi )

2 Q j pCi / gm

< 6.0 x 10 5 j (C j x 10) µCi / ml Where:

Qj = concentration of radioactive materials in wet, drained slurry (powdex resin) for radionuclide j, excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8-day half-life. The analysis shall include at least Ce-144, Cs-134, Cs-137, Co-58 and Co-60, in picoCuries/gram. Estimates of the Sr-89 and Sr-90 batch concentration shall be included based on the most recent monthly composite analysis (within 3 months); and Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for single radionuclide j, in microCuries/milliliter.

The batch limits provide assurance that activity input to the chemical treatment ponds will be minimized, and a means of identifying radioactive material in the inventory limitation of SLC 16.11.5.

The basic requirements for the Selected Licensee Commitments concerning effluents from nuclear power reactors are stated in 10CFR50.36a. These requirements indicate that compliance with effluent Selected Licensee Commitments will keep average annual releases of radioactive material in effluents to small percentages of the limits specified in the old 10CFR20.106 (new 10CFR20.1301). These requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10CFR20.106 which references Appendix B, Table II concentrations- (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem. It is further indicated in 10CFR50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as is reasonably achievable (ALARA) as set forth in 10CFR50, Appendix I.

McGuire Units 1 and 2 16.11.5-3 Revision 0 Page 9-210

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Chemical Treatment Ponds 16.11.5 BASES (continued)

As stated in the Introduction to Appendix B of the new 10CFR20, the effluent concentration (EC) limits given in Appendix B, Table 2, Column 2, are based on an annual dose of 50 mrem. Since a release concentration corresponding to a limiting dose rate of 500 mrem/year has been acceptable as a SLC limit for liquid effluents, which applies at all times as an assurance that the limits of 10CFR50, Appendix I are not likely to be exceeded, it should not be necessary to reduce this limit by a factor of 10.

Operational history at Catawba/McGuire/Oconee has demonstrated that the use of the concentration values associated with the old 10CFR20.106 as SLC limits has resulted in calculated maximum individual doses to members of the public that are small percentages of the limits of 10CFR50, Appendix I. Therefore, the use of concentration values which correspond to an annual dose of 500 mrem should not have a negative impact on the ability to continue to operate within the limits of 10CFR50, Appendix I and 40CFR190.

Having sufficient operational flexibility is especially important in establishing a basis for effluent monitor setpoint calculations. As discussed above, the concentrations stated in the new 10CFR20, Appendix B, Table 2, Column 2, relate to a dose of 50 mrem in a year.

When applied on an instantaneous basis, this corresponds to a dose rate of 50 mrem/year.

This low value is impractical upon which to base effluent monitor setpoint calculations for many liquid effluent release situations when monitor background, monitor sensitivity, and monitor performance must be taken into account.

Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with SLC 16.11.1 are based on ten times the concentrations stated in the new 10CFR20, Appendix B, Table 2, Column 2 to apply at all times. The multiplier of ten is proposed because the annual dose of 500 mrem, upon which the concentrations in the old 10CFR20, Appendix B, Table II, Column 2 are based, is a factor of ten higher than the annual dose of 50 mrem, upon which the concentrations in the new 10CFR20, Appendix B, Table 2, Column 2, are based. Compliance with the limits of the new 10CFR20.1301 will be demonstrated by operating within the limits of 10CFR50, Appendix I and 40CFR190.

REFERENCES

1. McGuire Nuclear Station, Off site Dose Calculation Manual

2. 10 CFR 20, Appendix B

3. 10 CFR 50, Appendix I, Section II.A

4. 10 CFR 20

5. 10 CFR 50.36a McGuire Units 1 and 2 16.11.5-4 Revision 0 Page 9-211

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Dose Rate - Gaseous Effluents 16.11.6 16.11 RADIOLOGICAL EFFLUENT CONTROL 16.11.6 Dose Rate - Gaseous Effluents COMMITMENT The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure16.11.1-1) shall be limited to the following:

a. For noble gases: < 500 mrem/yr to the whole body and < 3000 mrem/yr to the skin, and

b. For Iodine - 131 and 133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days:

< 1500 mrem/yr to any organ.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Dose rate not within A.1 Restore the release rate to Immediately limit. within limits.

TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.6.1 Verify dose rates due to noble gases in gaseous effluents In accordance with are within limits in accordance with the methodology and the ODCM parameters in the ODCM.

TR 16.11.6.2 Verify dose rates due to radioactive materials, other than In accordance with noble gases, in gaseous effluents are within limits in Table 16.11.6-1 accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with Table16.11.6-1.

McGuire Units 1 and 2 16.11.6-1 Revision 137 Page 9-212

Dose Rate - Gaseous Effluents 16.11.6 TABLE 16.11.6-1 (Page 1 of 4)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Sampling Frequency Minimum Analysis Type of Activity Analysis Lower Limit of (1)

Frequency Detection (LLD)

(µCi/ml)

1. Waste Gas Storage Tanks P P (6) -4 Each Tank Each Tank Principal Gas Gamma Emitters 1x10 Grab Sample

2. Containment Purge P P (6) -4 Each PURGE Each PURGE Principal Gas Gamma Emitters 1x10 Grab Sample

-6 M H-3 1x10 (2) (6) -4

3. Unit Vent W W Principal Gas Gamma Emitters 1x10 Grab Sample

-6 McGuire Nuclear Station Units 1 & 2 H-3 1x10 Attachment 9 (6) -4 4.a. Radwaste Facility Vent W W Principal Gas Gamma Emitters 1x10

b. Waste Handling Building Grab Sample

-6

c. Equipment Staging Building H-3 1x10 (5) (8) -12

5. Unit Vents Continuous W I-131 1x10 Period 1/1/2016 - 12/31/2016 Charcoal Sample

-10 I-133 1x10 (5) (8) (6) -11 Continuous W Principal Gamma Emitters 1x10 Summary of Changes to the Offsite Dose Calculation Manual Particulate (I-131, Others)

Sample (5) (7) -11 Continuous M Gross Alpha 1x10 Composite Particulate Sample (5) -11 Continuous Q Sr-89, Sr-90 1x10 Composite Particulate Page 9-213 Sample McGuire Units 1 and 2 16.11.6-2 Revision 137

Dose Rate - Gaseous Effluents 16.11.6 TABLE 16.11.6-1 (Page 2 of 4)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Sampling Frequency Minimum Analysis Type of Activity Analysis Lower Limit of (1)

Frequency Detection (LLD)

(µCi/ml)

(5) (8) -12

6. All Release Types as listed in 4 above. Continuous W I-131 1x10 Charcoal Sample

-10 I-133 1x10 (5) (8) (6) -11 Continuous W Principal Gamma Emitters 1x10 Particulate (I-131, Others)

Sample (5) (7) -11 Continuous M Gross Alpha 1x10 Composite Particulate McGuire Nuclear Station Units 1 & 2 Sample Attachment 9 (5) -11 Continuous Q Sr-89, Sr-90 1x10 Composite Particulate Sample Period 1/1/2016 - 12/31/2016 Summary of Changes to the Offsite Dose Calculation Manual Page 9-214 McGuire Units 1 and 2 16.11.6-3 Revision 137

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Dose Rate - Gaseous Effluents 16.11.6 TABLE 16.11.6-1 (Page 3 of 4)

NOTES:

1. The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

(2.71 / T ) + 4.65S b LLD =

E V 2.22 x 10 6 Y exp (t )

Where:

LLD = the a priori lower limit of detection as defined above (as microCurie per unit mass or volume);

Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute);

E = the counting efficiency (as counts per disintegration);

V = the sample size (in units of mass or volume);

2.22 x106 = the number of disintegrations per minute per microCurie; Y = the fractional radiochemical yield (when applicable);

= the radioactive decay constant for the particular radionuclide; t = the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples); and T = The background and sample counting time in minutes.

Typical values of E, V, Y and t shall be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

McGuire Units 1 and 2 16.11.6-4 Revision 137 Page 9-215

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Dose Rate - Gaseous Effluents 16.11.6 TABLE 16.11.6-1 (Page 4 of 4)

NOTES:

2. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

3. Not used.

4. Not used.

5. The ratio of the sample flow volume to the sampled stream flow volume shall be known for the time period covered by each dose or dose rate calculation made in accordance with SLCs 16.11.6, 16.11.8 and 16.11.9.

6. The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137,

-9 and Ce-141 in iodine and particulate releases. The LLD for Ce-144 is 5x10 microCi/ml.

This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.

7. The composite filter(s) will be analyzed for alpha activity by analyzing the filter media used during the collection period.

8. Samples shall be changed at least once per 7 days and analyses shall be completed to meet LLD after changing, or after removal from sampler. If the particulate and charcoal sample frequency is changed to a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months frequency the corresponding LLDs may be increased by a factor of 10 (i.e., LLD for I-131 from 1 x 10-12 to 1 x 10-11 microCi/ml).

McGuire Units 1 and 2 16.11.6-5 Revision 137 Page 9-216

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Dose Rate - Gaseous Effluents 16.11.6 BASES Specific release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the whole body, and 3000 mrem/year to the skin from noble gases, and 1500 mrem/year to any organ from Iodine 131, Iodine 133, tritium, and all radionuclides in particulate form with half-lives greater than eight days. This commitment applies to the release of gaseous effluents from all reactors at the site. The Exclusion Area Boundary (Site Boundary) is set as the boundary for gaseous effluent release limits. The Exclusion Area Boundary (EAB) is formed by a 2500 ft radius centered on the Reactor Buildings centerlines as shown on Figure 16.11.1-1.

The basic requirements for the Selected Licensee Commitments concerning effluents from nuclear power reactors are stated in 10CFR50.36a. These requirements indicate that compliance with effluent Selected Licensee Commitments will keep average annual releases of radioactive material in effluents to small percentages of the limits specified in the old 10CFR20.106 (new 10CFR20.1301). These requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10CFR20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem. It is further indicated in 10CFR50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as is reasonably achievable (ALARA) as set forth in 10CFR50, Appendix I.

As stated in the Introduction to Appendix B of the new 10CFR20, the effluent concentration (EC) limits given in Appendix B, Table 2, Column 1, are based on an annual dose of 50 mrem for isotopes for which inhalation or ingestion is limiting or 100 mrem for isotopes for which submersion (noble gases) is limiting. Since release concentrations corresponding to limiting dose rates of less than or equal to 500 mrem/year to the whole body, 3000 mrem/year to the skin from noble gases, and 1500 mrem/year to any organ from Iodine 131, Iodine 133, tritium and for all radionuclides in particulate form with half-lives greater than eight days at the site boundary has been acceptable as a SLC limit for gaseous effluents to assure that the limits of 10CFR50, Appendix I and 40CFR190 are not likely to be exceeded, it should not be necessary to restrict the operational flexibility by incorporating the EC value for isotopes based on ingestion/inhalation (50 mrem/year) or for isotopes with the EC based on submersion (100 mrem/year).

Having sufficient operational flexibility is especially important in establishing a basis for effluent monitor setpoint calculations. As discussed above, the concentrations stated in the new 10CFR20, Appendix B, Table 2, Column 1, relate to a dose of 50 or 100 mrem in a year. When applied on an instantaneous basis, this corresponds to a dose rate of either 50 or 100 mrem/year. These low values are impractical upon which to base effluent monitor setpoint calculations for many effluent release situations when monitor background, monitor sensitivity, and monitor performance must be taken into account. Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with SLC 16.11.6 will be maintained at the current dose rate limit for noble gases of 500 mrem/year to the whole body and 3000 mrem/year to the skin, for Iodine 131, Iodine 133, tritium and all radionuclides in particulate form with half-lives greater than eight days an instantaneous dose rate limit of 1500 mrem/year to any organ.

McGuire Units 1 and 2 16.11.6-6 Revision 137 Page 9-217

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Dose Rate - Gaseous Effluents 16.11.6 BASES (continued)

Compliance with the limits of the new 10CFR20.1301 will be demonstrated by operating within the limits of 10CFR50, Appendix I and 40CFR190. Operational history at Catawba/McGuire/Oconee has demonstrated that the use of the dose rate values listed above (i.e. 500 mrem/year, 3000 mrem/year and 1500 mrem/year) as SLC limits has resulted in calculated maximum individual doses to members of the public that are small percentages of the limits of 10CFR50, Appendix I and 40CFR190.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Anal. Chem. 40, 586-93* (1968), and Hartwell, J. K.

"Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

REFERENCES

1. McGuire Nuclear Station, Off site Dose Calculation Manual

2. 10 CFR Part 20, Appendix B

3. 10 CFR Part 20

4. 10 CFR Part 50 McGuire Units 1 and 2 16.11.6-7 Revision 137 Page 9-218

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11.7 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.7 Radioactive Gaseous Effluent Monitoring Instrumentation COMMITMENT The radioactive gaseous effluent monitoring instrumentation channels shown in Table 16.11.7-1 shall be FUNCTIONAL with Alarm/Trip Setpoints set to ensure that the limits of SLC 16.11.6 are not exceeded.

AND The Alarm/Trip setpoints shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

NOTE--------------------------------------

Brief periods of routine sampling (not to exceed 15 minutes) do not make the instrumentation non-functional.

APPLICABILITY As shown in Table 16.11.7-1.

REMEDIAL ACTIONS

NOTE-----------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more radioactive A.1 Suspend the release of Immediately gaseous effluent radioactive gaseous monitoring channels effluents monitored by the Alarm/Trip setpoint less affected channel.

conservative than required. OR A.2 Declare the channel non- Immediately functional.

OR A.3 Adjust setpoint to within Immediately limit.

(continued)

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11.7 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more radioactive B.1 Enter the Remedial Action Immediately gaseous effluent specified in Table 16.11.7-1 monitoring instrument for the channel(s).

channels non-functional.

C. One channel non- C.1.1 Analyze two independent Prior to initiating a functional. samples of the tank release contents.

AND C.1.2 Perform independent Prior to initiating a verification of the discharge release valve lineup.

AND C.1.3.1 Perform independent Prior to initiating a verification of manual release portion of the computer input for the release rate calculations performed by computer.

OR C.1.3.2 Perform independent Prior to initiating a verification of entire release release rate calculations for calculations performed manually.

AND C.1.4 Restore channel to 14 days FUNCTIONAL status.

OR C.2 Suspend the release of Immediately radioactive effluents via this pathway.

(continued)

McGuire Units 1 and 2 16.11.7-2 Revision 134 Page 9-220

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11.7 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more flow rate D.1 Estimate the flow rate of Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months measurement channels the release. during releases non-functional.

AND D.2 Restore the channel to 30 days FUNCTIONAL status.

E. One or more noble gas E.1 Obtain grab samples from Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months activity monitor channels the effluent pathway. during releases non-functional.

AND E.2 Perform an analysis of grab To meet LLD samples for radioactivity. requirements per Table 16.11.6-1 AND E.3 Restore the channel to 30 days FUNCTIONAL status.

F. Noble gas activity F.1 Suspend PURGING or Immediately monitor providing VENTING of radioactive automatic termination of effluents via this pathway.

release non-functional.

G. One or more sampler G.1 Perform sampling with Continuously channels non-functional. auxiliary sampling equipment as required by Table 16.11.6-1.

AND G.2 Restore the channel to 30 days FUNCTIONAL status.

(continued)

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11.7 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. One or more Sampler H.1 Verify flow through the Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Minimum Flow Device sampling apparatus. during releases Channels non-functional.

AND H.2 Restore the channel to 30 days FUNCTIONAL status.

I. Required Action and I.1 Explain why the non- In the next associated Completion functionality was not scheduled Annual Time of Condition C, D, corrected within the Radioactive Effluent E, F, G, or H not met. specified Completion Time Release Report in the Annual Radioactive Effluent Release Report.

TESTING REQUIREMENTS

NOTE-------------------------------------------------------

Refer to Table 16.11.7-1 to determine which TRs apply for each Radioactive Gaseous Effluent Monitoring channel.

TEST FREQUENCY TR 16.11.7.1 Perform CHANNEL CHECK. Prior to each release TR 16.11.7.2 --------------------------------NOTE----------------------------------- Prior to each The SOURCE CHECK for these channels shall be the release qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity or a simulated source of radioactivity such as a light emitting diode.

Perform SOURCE CHECK.

TR 16.11.7.3 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TR 16.11.7.4 Perform CHANNEL CHECK. 7 days (continued)

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11.7 TESTING REQUIREMENTS (continued)

TEST FREQUENCY TR 16.11.7.5 --------------------------------NOTE-----------------------------------

The SOURCE CHECK for these channels shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity or a simulated source of radioactivity such as a light emitting diode.

Perform SOURCE CHECK. 31 days TR 16.11.7.6 ---------------------------------NOTES--------------------------------

1. For noble gas activity monitors providing automatic termination of release, the COT shall also demonstrate that automatic isolation of the pathway occurs if the instrument indicates measured levels above the Alarm/Trip Setpoint.

2. For all noble gas activity monitors, the COT shall also demonstrate that control room alarm annunciation occurs if the instrument indicates measured levels above the Alarm/Trip Setpoint; circuit failure and, a downscale failure.

Perform CHANNEL OPERATIONAL TEST. 92 days TR 16.11.7.7 ----------------------------NOTE--------------------------------------

For all noble gas activity monitors, the initial CHANNEL CALIBRATION shall be performed using standards certified by the National Institute of Standards and Technology (NIST) or using standards obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

18 months Perform a CHANNEL CALIBRATION.

McGuire Units 1 and 2 16.11.7-5 Revision 134 Page 9-223

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11.7 TABLE 16.11.7-1 (Page 1 of 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENTS MINIMUM REMEDIAL APPLICABILITY TESTING CHANNELS ACTION REQUIREMENTS FUNCTIONAL

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor - 1 per station A, C, I During gas effluent TR 16.11.7.1 Providing Alarm and Automatic releases. TR 16.11.7.2 Termination of Release (Low TR 16.11.7.6 Range- EMF-50 or 1EMF-36, low- TR 16.11.7.7 range)

b. Effluent System Flow Rate 1 per station D, I At all times except TR 16.11.7.3 Measuring Device when isolation TR 16.11.7.6 valve is closed & TR 16.11.7.7 locked.

2. Condenser Evacuation System - Noble 1 A, E, I When air ejectors TR 16.11.7.3 Gas Activity Monitor (EMF-33) are operable. TR 16.11.7.5 TR 16.11.7.6 TR 16.11.7.7

3. Vent System

a. Noble Gas Activity Monitor (Low 1 A, E, I At all times. TR 16.11.7.3 Range - EMF-36) TR 16.11.7.5 TR 16.11.7.6 TR 16.11.7.7

b. Iodine Sampler 1 G, I At all times, except TR 16.11.7.4 during routine sampling.

c. Particulate Sampler (EMF-35) 1 G, I At all times, except TR 16.11.7.4 during routine sampling.

d. Unit Vent Flow Rate Monitor 1 D, I At all times. TR 16.11.7.3 (Totalizer) TR 16.11.7.6 TR 16.11.7.7

e. Iodine Sampler Minimum Flow 1 H,I At all times, except TR 16.11.7.3 Device during routine TR 16.11.7.6 sampling. TR 16.11.7.7

f. Particulate Sampler Minimum Flow 1 G,I At all times, except TR 16.11.7.3 Device (1) during routine TR 16.11.7.6 sampling. TR 16.11.7.7

4. Containment Purge System - Noble 1 A, F, I Modes 1 through 6, TR 16.11.7.2 Gas Activity Monitor - Providing Alarm except when TR 16.11.7.3 and Automatic Termination of Release isolation valve is TR 16.11.7.6 (Low Range - EMF-39) closed & locked. TR 16.11.7.7 (continued)

McGuire Units 1 and 2 16.11.7-6 Revision 134 Page 9-224

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11.7 TABLE 16.11.7-1 (Page 2 of 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENTS MINIMUM REMEDIAL APPLICABILITY TESTING CHANNELS ACTION REQUIREMENTS FUNCTIONAL

5. Auxiliary Building Ventilation System - 1 A, E, I At all times. TR 16.11.7.3 Noble Gas Activity Monitor (EMF-41 or TR 16.11.7.5 EMF-36) TR 16.11.7.6 TR 16.11.7.7

6. Fuel Storage Area Ventilation System - 1 A, E, I At all times. TR 16.11.7.3 Noble Gas Activity Monitor (EMF-42 or TR 16.11.7.5 EMF-36) TR 16.11.7.6 TR 16.11.7.7

7. Contaminated Parts Warehouse Ventilation System

a. Noble Gas Activity Monitor 1 per station A, E, I During gaseous TR 16.11.7.3 (EMF-53) effluent releases. TR 16.11.7.5 TR 16.11.7.6 TR 16.11.7.7

b. Flow Rate Monitor 1 per station D, I During gaseous TR 16.11.7.3 effluent releases. TR 16.11.7.6 TR 16.11.7.7

c. EMF-53 Sampler Minimum Flow 1 per station H,I During gaseous TR 16.11.7.3 Device (1) effluent releases. TR 16.11.7.6 TR 16.11.7.7

8. Radwaste Facility Ventilation System

a. Noble Gas Activity Monitor 1 per station A, E, I During gaseous TR 16.11.7.3 (EMF-52) effluent releases. TR 16.11.7.5 TR 16.11.7.6 TR 16.11.7.7

b. Flow Rate Monitor 1 per station D, I During gaseous TR 16.11.7.3 effluent releases. TR 16.11.7.6 TR 16.11.7.7

c. EMF-52 Sampler Minimum Flow 1 per station H, I During gaseous TR 16.11.7.3 Device (1) effluent releases. TR 16.11.7.6 TR 16.11.7.7 (continued)

McGuire Units 1 and 2 16.11.7-7 Revision 134 Page 9-225

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11.7 TABLE 16.11.7-1 (Page 3 of 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION INSTRUMENTS MINIMUM REMEDIAL APPLICABILITY TESTING CHANNELS ACTION REQUIREMENTS FUNCTIONAL

9. Equipment Staging Building Ventilation System

a. Noble Gas Activity Monitor 1 per station A, E, I During gaseous TR 16.11.7.3 (EMF-59) effluent releases. TR 16.11.7.5 TR 16.11.7.6 TR 16.11.7.7

b. Flow Rate Monitor 1 per station D, I During gaseous TR 16.11.7.3 effluent releases. TR 16.11.7.6 TR 16.11.7.7

c. EMF-59 Sampler Minimum Flow 1 per station H, I During gaseous TR 16.11.7.3 Device (1) effluent releases. TR 16.11.7.6 TR 16.11.7.7

10. Containment Air Release and Addition 1 A, E, I At all times except TR 16.11.7.3 System - Noble Gas Activity Monitor when isolation TR 16.11.7.5 (EMF-39L or EMF-36L) valve is closed & TR 16.11.7.6 locked. TR 16.11.7.7 NOTES:

1. Radioactivity monitor (EMF) shall not be declared FUNCTIONAL unless both the EMF and the associated EMF's Minimum Flow Device are rendered FUNCTIONAL.

McGuire Units 1 and 2 16.11.7-8 Revision 134 Page 9-226

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Gaseous Effluent Monitoring Instrumentation 16.11.7 BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The instrumentation consists of monitoring and sampling instrumentation. Monitors provide continuous display of process parameters with appropriate alarms and trip setpoints established. Samplers collect a portion of the desired process for subsequent laboratory analysis, and do not have alarm/trip capability. Samplers and the analysis program provide a method to assure that long term effluent release quantities do not exceed the requirements of SLC 16.11.6.

Monitors provide assurance that instantaneous effluent releases do not exceed the requirements of SLC 16.11.6. The minimum flow devices for EMFs listed in Table 16.11.7-1 are required to provide assurance of representative sampling during actual or potential releases of gaseous effluents. The flow rate monitor quantifies the total gaseous effluent (both non-radioactive and radioactive) released to the environment.

During routine sampling, instrumentation may be turned off for short periods of time (not to exceed 15 minutes) in order to meet analysis requirements of SLC 16.11.6. This is considered to be a normal function of the equipment. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the Alarm/Trip will occur prior to exceeding the limits stated in SLC 16.11.6. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

REFERENCES

1. McGuire Nuclear Station, Offsite Dose Calculation Manual

2. 10 CFR Part 50, Appendix A McGuire Units 1 and 2 16.11.7-9 Revision 134 Page 9-227

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Noble Gases 16.11.8 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.8 Noble Gases COMMITMENT Air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure16.11.1-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY At all times.

REMEDIAL ACTIONS

NOTES-----------------------------------------------------

Enter applicable Conditions and Required Actions of SLC 16.11.12, "Total Dose," when the limits of this SLC are exceeded by twice the specified limit.

CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated air dose from A.1 Prepare and submit a 30 days radioactive noble gases Special Report to the NRC in gaseous effluents which identifies the causes exceeding any of above for exceeding the limits, limits. corrective actions taken to reduce releases, and actions taken to ensure that subsequent releases are within limits.

McGuire Units 1 and 2 16.11.8-1 Revision 0 Page 9-228

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Noble Gases 16.11.8 TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.8.1 Determine cumulative dose contributions from noble 31 days gases in gaseous effluents for current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM.

BASES This commitment is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I.

The REMEDIAL ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

The TESTING REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially under-estimated.

The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in 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," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.

The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This commitment applies at all times to the release of gaseous effluents from each reactor at the site. For units with shared Radwaste Treatment Systems, the gaseous effluents from the shared system are to be proportioned among the units sharing that system in accordance with the guidance given in NUREG-0133, Chapter 3.1.

McGuire Units 1 and 2 16.11.8-2 Revision 0 Page 9-229

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Noble Gases 16.

11.8 REFERENCES

1. McGuire Nuclear Station, Off site Dose Calculation Manual

2. 10 CFR Part 50, Appendix I McGuire Units 1 and 2 16.11.8-3 Revision 0 Page 9-230

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Dose - Iodine-131 and 133, Tritium and Radioactive Materials in Particulate Form 16.11.9 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.9 Dose - Iodine-131 and 133, Tritium and Radioactive Materials in Particulate Form COMMITMENT The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas at and beyond the SITE BOUNDARY (see Figure 16.11.1-1) shall be limited to the following:

a. During any calendar quarter: less than or equal to 7.5 mrem to any organ, and

b. During any calendar year: less than or equal to 15 mrem to any organ.

APPLICABILITY At all times.

REMEDIAL ACTIONS

NOTES-----------------------------------------------------

Enter applicable Conditions and Required Actions of SLC 16.11.12, "Total Dose," when the limits of this SLC are exceeded by twice the specified limit.

CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated dose from A.1 Prepare and submit a 30 days the release of Iodine 131 Special Report to the NRC and 133, tritium, and which identifies the causes radioactive materials in for exceeding the limits, particulate form with corrective actions taken to half-lives greater than 8 reduce releases, and days in gaseous actions taken to ensure effluents exceeding any that subsequent releases of the above limits. are within limits.

McGuire Units 1 and 2 16.11.9-1 Revision 0 Page 9-231

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Dose - Iodine-131 and 133, Tritium and Radioactive Materials in Particulate Form 16.11.9 TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.9.1 Determine cumulative dose contributions for Iodine 131 31 days and 133, tritium, and radioactive material in particulate form with half lives greater than 8 days in gaseous effluents for current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM.

BASES This commitment is provided to implement the requirements-of Sections- II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

The REMEDIAL ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable.

The ODCM calculational methods specified in the TESTING REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in 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," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors, Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides; (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man; (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man; and, (4) deposition on the ground with subsequent exposure of man.

McGuire Units 1 and 2 16.11.9-2 Revision 0 Page 9-232

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Dose - Iodine-131 and 133, Tritium and Radioactive Materials in Particulate Form 16.11.9 BASES (continued)

This commitment applies at all times to the release of gaseous effluents from each reactor at the site. For units with shared Radwaste Treatment Systems, the gaseous effluents from the shared system are to be proportioned among the units sharing that system in accordance with the guidance given in NUREG 0133, Chapter 3.1.

REFERENCES

1. McGuire Nuclear Station, Off site Dose Calculation Manual

2. 10 CFR Part 50, Appendix I McGuire Units 1 and 2 16.11.9-3 Revision 0 Page 9-233

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gaseous Radwaste Treatment System 16.11.10 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.10 Gaseous Radwaste Treatment System COMMITMENT The VENTILATION EXHAUST TREATMENT and WASTE GAS HOLDUP SYSTEMS shall be FUNCTIONAL and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 16.11.1-1) would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radioactive gases being A.1 Prepare and submit a 30 days discharged without Special Report to the NRC treatment and in excess which identifies non-of above limits. functional equipment and reasons for non-functionality, actions taken to restore the equipment to FUNCTIONAL status, and actions taken to prevent recurrence.

McGuire Units 1 and 2 16.11.10-1 Revision 134 Page 9-234

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gaseous Radwaste Treatment System 16.11.10 TESTING REQUIREMENTS

NOTE-------------------------------------------------

The installed Gaseous Radwaste Treatment System shall be demonstrated FUNCTIONAL by meeting SLC 16.11.6, 16.11.8 and16.11.9.

TEST FREQUENCY TR 16.11.10.1 Project gaseous release doses from each unit to areas 31 days at and beyond the SITE BOUNDARY, in accordance with the methodology and parameters in the ODCM, when gaseous systems are being released without being processed by its radwaste treatment system.

BASES The FUNCTIONALITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

This commitment implements the requirements of 19 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This commitment applies at all times to the release of radioactive materials in gaseous effluents from each unit at the site. For units with shared Radwaste Treatment Systems, the gaseous effluents from the shared system are to be proportioned among the units sharing that system in accordance with NUREG-0133, Chapter 3.1.

REFERENCES

1. McGuire Nuclear Station, Off site Dose Calculation Manual

2. 10 CFR Part 50, Appendix I

3. 10 CFR Part 50 McGuire Units 1 and 2 16.11.10-2 Revision 134 Page 9-235

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Solid Radioactive Waste 16.11.11 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.11 Solid Radioactive Waste COMMITMENT Radioactive wastes shall be processed and packaged to ensure compliance with the applicable requirements of 10 CFR Part 20, 10CFR Part 61, 10 CFR Part 71, and State regulations governing the transportation and disposal of radioactive wastes.

The Solid Radwaste System or an approved alternative process shall be used in accordance with a PROCESS CONTROL PROGRAM (PCP) for the solidification of liquid or wet radioactive wastes or the dewatering of wet radioactive wastes to be shipped for direct disposal at a 10CFR61 licensed disposal site. Wastes shipped for off site processing in accordance with the processors specifications and transportation requirements are not required to be solidified or dewatered to meet disposal requirements.

The PCP describes administrative and operational controls used for the solidification of liquid or wet solid radioactive wastes in order to meet applicable 10CFR61 waste form requirements.

The PCP describes the administrative and operational controls used for the dewatering of wet radioactive wastes to meet 10CFR61 free standing water requirements.

The process parameters used in establishing the PCP shall be based on demonstrated processing of actual or simulated liquid or wet solid wastes and must adequately verify that the final product of solidification or dewatering meets all applicable Federal, State and disposal site requirements.

APPLICABILITY At all times.

McGuire Units 1 and 2 16.11.11-1 Revision 134 Page 9-236

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Solid Radioactive Waste 16.11.11 REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Applicable regulatory A.1 Suspend shipments of Immediately requirements for defectively packaged solid solidified or dewatered radioactive wastes from the wastes are not site.

satisified.

AND A.2 Initiate action to correct the Prior to next PROCESS CONTROL shipment for disposal PROGRAM, procedures, or of solidified or solid waste equipment as dewatered wastes.

necessary to prevent recurrence.

B. A solidification test as B.1 Suspend solidification of the Immediately described in the PCP batch under test and follow fails to verify PCP guidance for test Solidification. failures.

B.2 Once a subsequent test Prior to next verifies Solidification, solidification for solidification of the batch shipment of waste may then be resumed as for disposal at a directed by the PCP. The 10CFR61 disposal PCP shall be modified as site.

required to assure Solidification of subsequent batches of waste (continued)

McGuire Units 1 and 2 16.11.11-2 Revision 134 Page 9-237

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Solid Radioactive Waste 16.11.11 REMEDIAL ACTIONS (continued)

C. With solidification or C.1 Reprocess the waste in Prior to shipment for dewatering for accordance with PCP disposal of the disposal not requirements. inadequately processed performed in waste that requires accordance with the OR solidification of dewatering PROCESS CONTROL C.2 Follow PCP or procedure PROGRAM. quidance for alternative free standing liquid verification to ensure the waste in each container meets disposal requirements and take appropriate administrative action to prevent recurrence.

D. With the solid waste D.1 Restore the equipment In a time frame that equipment incapable to FUNCTIONAL status supports the of meeting SLC or provide for alternative COMMITMENT section of 16.11.11 or not in capability to process SLC 16.11.11 service wastes as necessary to satisfy all applicable disposal requirements TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.11.1 The Process Control Program shall be used to verify the Every tenth batch Solidification of at least one representative test of each type of specimens from at least every tenth batch of each type radioactive waste of radioactive waste to be solidified for disposal at a to be solidified.

10CFR61 disposal site per the COMMITMENT of this SLC.

McGuire Units 1 and 2 16.11.11-3 Revision 134 Page 9-238

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Solid Radioactive Waste 16.11.11 BASES:

This commitment implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and requirements to use a Process Control Program to meet applicable 10CFR61 waste form criteria for solidified and dewatered radioactive wastes.

REFERENCES:

1. 10CFR Part 50, Domistic Licensing of Production and Utilization Facilities

2. 10 CFR Part 50, Appendix A

3. 10CFR20, Standards for Protection Against Radiation

4. 10CFR61, Licensing Requirements for Land Disposal of Radioactive Waste

5. 10CFR71, Packaging and Transportation of Radioactive Materials

6. DPCo Process Control Program Manual

7. NRC Generic Letter 84-12, Compliance With 10 CFR Part 61 And Implementation Of the Radiological Effulent Technical Specifications (Rets) and Attendant Process Control Program (PCP)

8. NRC Generic Letter 89-01, Implementation of Programmatic Controls for Radiological Effulent Technical Specifications In the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of Rets to the Offsite Dose Calculation Manual or to the Process Control Program McGuire Units 1 and 2 16.11.11-4 Revision 134 Page 9-239

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Total Dose 16.11.12 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.12 Total Dose COMMITMENT The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to < 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to < 75 mrem.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated doses from A.1 Verify, by calculation, the Immediately releases exceeding cumulative dose from direct twice the specified limits radiation contributions, the of SLC 16.11.3, 16.11.8 ISFSI, outside storage or 16.11.9. tanks, and radioactivity releases are within the total dose limit.

AND A.2 --------------NOTE------------

Only required to be performed if the total dose limit is exceeded.

Prepare and submit a 30 days Special Report to the NRC which identifies corrective actions to be taken to reduce subsequent releases to prevent recurrence and schedule for achieving conformance with specified limits.

McGuire Units 1 and 2 16.11.12-1 Revision 67 Page 9-240

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Total Dose 16.11.12 TESTING REQUIREMENTS

NOTE-------------------------------------------------

Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with SLC 16.11.3, 16.11.8 and16.11.9, and in accordance with the methodology and parameters specified in the ODCM.

TEST FREQUENCY TR 16.11.12.1 Determine cumulative dose contributions from direct When calculated radiation from the units, the ISFSI, and from radwaste doses from storage tanks in accordance with the methodology and effluent releases parameters specified in the ODCM. exceeds twice the limits of SLCs 16.11.3, 16.11.8 or 16.11.9 BASES This commitment is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of 10 CFR Part 50, Appendix I, and if direct radiation doses from the units and outside storage tanks are kept small.

This Special Report, as defined in 10 CFR Part 20.2203(a)(4), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER of the PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.

If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in McGuire Units 1 and 2 16.11.12-2 Revision 67 Page 9-241

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Total Dose 16.11.12 BASES (continued) accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 and a variance is granted until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in SLCs 16.11.1 and 16.11.6.

An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

REFERENCES

1. McGuire Nuclear Station, Offsite Dose Calculation Manual

2. 10 CFR Part 20

3. 40 CFR Part 190

4. 10 CFR Part 50, Appendix I McGuire Units 1 and 2 16.11.12-3 Revision 67 Page 9-242

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radiological Environmental Monitoring Program 16.11.13 16.11 RADIOLOGICAL EFFLUENT MONITORING 16.11.13 Radiological Environmental Monitoring Program COMMITMENT The Radiological Environmental Monitoring Program shall be conducted as specified in Table 16.11.13-1.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radiological A.1 Identify the reasons for not Within the next Environmental conducting the program as scheduled Annual Monitoring Program not required and the plans for Radiological being conducted as preventing a recurrence in Environmental specified in Table the Annual Radiological Operating Report 16.11.13-1. Environmental Operating Report.

B. Radioactivity level of B.1 Prepare and submit a 30 days environmental sampling Special Report that defines medium at a specified the corrective actions to be location in excess of taken to reduce radioactive reporting limits of Table effluents so that the 16.11.13-2. potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of SLC 16.11.3, 16.11.8, and 16.11.9.

(continued)

McGuire Units 1 and 2 16.11.13-1 Revision 137 Page 9-243

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radiological Environmental Monitoring Program 16.11.13 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Milk or fresh leafy C.1 --------------NOTE-------------

vegetable samples Specific locations from unavailable from one or which samples were more required sample unavailable may be deleted locations. from the program.

Revise the Radiological 30 days Environmental Monitoring Program to identify locations for obtaining replacement samples.

AND C.2 Identify the cause of the Within the next unavailability of samples scheduled Annual and identify new location(s) Radioactive Effluent for obtaining replacement Release Report samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.13.1 --------------------------------NOTES--------------------------------

The maximum values for the lower limits of detection shall be as specified in Table16.11.13-3.

The radiological environmental monitoring samples shall In accordance with be collected from the locations given in the table and Table 16.11.13-1 figure in the ODCM and shall be analyzed pursuant to the requirements of Tables16.11.13-1.

McGuire Units 1 and 2 16.11.13-2 Revision 137 Page 9-244

Radiological Environmental Monitoring Program 16.11.13 TABLE 16.11.13-1 (Page 1 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND TYPE AND FREQUENCY PATHWAY AND/OR AND SAMPLE LOCATIONS(1) COLLECTION OF ANALYSIS SAMPLE FREQUENCY

1. Direct Radiation(2) Forty routine monitoring stations either with Quarterly Gamma dose quarterly.

two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; An outer ring of stations, one in each McGuire Nuclear Station Units 1 & 2 Attachment 9 meteorological sector in the 6- to 8-km range from the site; and The balance of the stations placed in special Period 1/1/2016 - 12/31/2016 interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

(continued)

Summary of Changes to the Offsite Dose Calculation Manual Page 9-245 McGuire Units 1 and 2 16.11.13-3 Revision 137

Radiological Environmental Monitoring Program 16.11.13 TABLE 16.11.13-1 (Page 2 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND TYPE AND FREQUENCY (1)

PATHWAY AND/OR AND SAMPLE LOCATIONS COLLECTION OF ANALYSIS SAMPLE FREQUENCY

2. Airborne Samples from five locations: Continuous sampler Radioiodine Canister:

Radioiodine and operation with sample I-131 analysis weekly.

Particulates Three samples from close to the three SITE collection weekly, or BOUNDARY locations, in different sectors, of more frequently if Particulate Sampler:

the highest calculated annual average required by dust Gross beta radioactivity ground level D/Q. loading. analysis following filter (4) change ; Gamma isotopic One sample from the vicinity of a community analysis(5) of composite (by having the highest calculated annual average location quarterly).

McGuire Nuclear Station Units 1 & 2 Attachment 9 ground level D/Q.

One sample from a control location, as for example 15-30 km distant and in the least Period 1/1/2016 - 12/31/2016 prevalent wind direction(3).

3. Waterborne One sample upstream. Composite sample Gamma isotope analysis(5)

a. Surface(6) One sample downstream. over 1-month period(7). monthly. Composite for Summary of Changes to the Offsite Dose Calculation Manual tritium analysis quarterly.

b. Ground Samples from one or two sources only if Quarterly Gamma isotopic(5) and likely to be affected(8) tritium analysis quarterly.

(continued)

Page 9-246 McGuire Units 1 and 2 16.11.13-4 Revision 137

Radiological Environmental Monitoring Program 16.11.13 TABLE 16.11.13-1 (Page 3 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND TYPE AND FREQUENCY (1)

PATHWAY AND/OR AND SAMPLE LOCATIONS COLLECTION OF ANALYSIS SAMPLE FREQUENCY

c. Drinking One sample of each of one to three of the Composite sample I-131 analysis on each nearest water supplies that could be affected over 2-week period(7) composite when the dose by its discharge. when I-131 analysis is calculated for the performed; monthly consumption of the water is One sample from a control location. composite otherwise. greater than 1 mrem per year(9). Composite for gross beta and gamma isotopic analyses(5) monthly.

Composite for tritium McGuire Nuclear Station Units 1 & 2 Attachment 9 analysis quarterly.

d. Sediment from One sample from downstream area with Semiannually Gamma isotopic analysis(5) the shoreline existing or potential recreational value. semiannually. Period 1/1/2016 - 12/31/2016

4. Ingestion Samples from milking animals in three Semimonthly when Gamma isotopic(5) and I-131

a. Milk locations within 5-km distance having the animals are on analysis semimonthly when highest dose potential. If there are none, pasture; monthly at animals are on pasture; then one sample from milking animals in other times. monthly at other times.

Summary of Changes to the Offsite Dose Calculation Manual each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per year (9).

One sample from milking animals at a control location 15 to 30 km distant and in the least prevalent wind direction.

(continued)

Page 9-247 McGuire Units 1 and 2 16.11.13-5 Revision 137

Radiological Environmental Monitoring Program 16.11.13 TABLE 16.11.13-1 (Page 4 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND TYPE AND FREQUENCY PATHWAY AND/OR AND SAMPLE LOCATIONS(1) COLLECTION OF ANALYSIS SAMPLE FREQUENCY

b. Fish and One sample each commercially and Sample in season, or Gamma isotopic analysis(5)

Invertebrates recreationally important species in vicinity of semiannually if they on edible portions plant discharge area. are not seasonal One sample of same species in areas not influenced by plant discharge.

(10) (5)

c. Food Products One sample of each principal class of food At time of harvest Gamma isotopic analyses products from any area that is irrigated by on edible portion.

McGuire Nuclear Station Units 1 & 2 Attachment 9 water in which liquid plant wastes have been discharged.

Samples of three different kinds of broad leaf Monthly, when Gamma isotopic(5) and I-131 vegetation grown nearest each of two available. analysis.

Period 1/1/2016 - 12/31/2016 different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed.

Summary of Changes to the Offsite Dose Calculation Manual One sample of each of the similar broad leaf Monthly, when Gamma isotopic(5) and I-131 vegetation grown 15 to 30 km distant in the available. analysis.

least prevalent wind direction if milk sampling is not performed.

Page 9-248 McGuire Units 1 and 2 16.11.13-6 Revision 137

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radiological Environmental Monitoring Program 16.11.13 TABLE 16.11.13-1 (Page 5 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NOTES:

1. Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 16.11.13-1 in a table and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practical to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program. In lieu of an Licensee Event Report, identify the cause of the unavailability of samples for that pathway and identify the new locations(s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

2. One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The forty stations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g.,

at an ocean site, some sections will be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

3. The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.

4. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

McGuire Units 1 and 2 16.11.13-7 Revision 137 Page 9-249

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radiological Environmental Monitoring Program 16.11.13 TABLE 16.11.13-1 (Page 6 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NOTES (continued):

5. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

6. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in an area beyond but near the mixing zone. "Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall be sampled only when the receiving water is utilized for recreational activities.

7. A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g.,

hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

8. Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

9. The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

10. If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuborous and root food products.

McGuire Units 1 and 2 16.11.13-8 Revision 137 Page 9-250

Radiological Environmental Monitoring Program 16.11.13 TABLE 16.11.13-2 (Page 1 of 1)

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS ANALYSIS WATER AIRBOURNE FISH MILK BROAD LEAF (pCi/l) PARTICULATE OR (pCi/kg, wet) (pCi/l) VEGETATION GASES (pCi/m3) (pCi/kg, wet)

(1)

H-3 20,000 N/A N/A N/A N/A Mn-54 1,000 N/A 30,000 N/A N/A Fe-59 400 N/A 10,000 N/A N/A Co-58 1,000 N/A 30,000 N/A N/A Co-60 300 N/A 10,000 N/A N/A McGuire Nuclear Station Units 1 & 2 Attachment 9 Zn-65 300 N/A 20,000 N/A N/A Zr-Nb-95 400 N/A N/A N/A N/A Period 1/1/2016 - 12/31/2016 I-131 2 0.9 N/A 3 100 Cs-134 30 10 1,000 60 1,000 Summary of Changes to the Offsite Dose Calculation Manual Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 N/A N/A 300 N/A NOTES:

1. For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

Page 9-251 McGuire Units 1 and 2 16.11.13-9 Revision 137

Radiological Environmental Monitoring Program 16.11.13 TABLE 16.11.13-3 (Page 1 of 3)

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) (1)(2)(3)

ANALYSIS WATER AIRBORNE FISH MILK BROAD LEAF SEDIMENT (pCi/l) PARTICULATE (pCi/kg, wet) (pCi/l) VEGETATION (pCi/kg, dry)

OR GASES (pCi/kg, wet)

(pCi/m3)

Gross Beta 4 0.01 N/A N/A N/A N/A H-3 2000* N/A N/A N/A N/A N/A Mn-54 15 N/A 130 N/A N/A N/A Fe-59 30 N/A 260 N/A N/A N/A McGuire Nuclear Station Units 1 & 2 Attachment 9 Co-58, 60 15 N/A 130 N/A N/A N/A Zn-65 30 N/A 260 N/A N/A N/A Zr-95 15 N/A N/A N/A N/A N/A Period 1/1/2016 - 12/31/2016 Nb-95 15 N/A N/A N/A N/A N/A I-131 1(4) 0.07 N/A 1 60 N/A Summary of Changes to the Offsite Dose Calculation Manual Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 15 N/A N/A 15 N/A N/A La-140 15 N/A N/A 15 N/A N/A Page 9-252

If no drinking water pathway exists, a value of 3000 pCi/l may be used.

McGuire Units 1 and 2 16.11.13-10 Revision 137

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radiological Environmental Monitoring Program 16.11.13 TABLE 16.11.13-3 (Page 2 of 3)

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

NOTES:

1. The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

(2.71/ T ) + 4.65S LLD = b E V 2.22 Y exp (t )

Where:

LLD is the "a priori" lower limit of detection as defined above (as picoCurie per unit mass or volume),

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency (as counts per disintegration),

V is the sample size (in units of mass or volume),

2.22 is the number of disintegrations per minute per picoCurie, Y is the fractional radiochemical yield (when applicable),

is the radioactive decay constant for the particular radionuclide, t is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples), and T is the background and sample counting time in minutes.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.

Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

McGuire Units 1 and 2 16.11.13-11 Revision 137 Page 9-253

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radiological Environmental Monitoring Program 16.11.13 TABLE 16.11.13-3 (Page 3 of 3)

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

NOTES (continued):

2. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

3. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

4. LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

McGuire Units 1 and 2 16.11.13-12 Revision 137 Page 9-254

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radiological Environmental Monitoring Program 16.11.13 BASES The Radiological Environmental Monitoring Program is established to monitor the radiation and radionuclides in the environs of the plant. The program provides representative measurements of radioactivity in the highest potential exposure pathways, and verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program is contained in SLC 16.11.13 - 16.11.16 and conforms to the guidance of Appendix I to 10 CFR Part 50.

The program includes the following:

1. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

2. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and

3. Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

The portion of the Radiological Environmental Monitoring Program required by this commitment provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 16.11.13-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

With the level of radioactivity in an environmental sampling medium at a specified location exceeding the reporting levels of Table 16.11.13-3 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days a Special Report that defines the corrective actions to be McGuire Units 1 and 2 16.11.13-13 Revision 137 Page 9-255

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radiological Environmental Monitoring Program 16.11.13 BASES (continued) taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of SLCs 16.11.6, 16.11.8, and 16.11.9. When more than one of the radionuclides in Table 16.11.13-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + K... > 1.0 limit level (1) limit level (2)

When radionuclides other than those in Table 16.11.13-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of SLCs 16.11.6, 16.11.8 and 16.11.9. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report. The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem.

40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

REFERENCES

1. McGuire Nuclear Station, Off site Dose Calculation Manual

2. 10 CFR Part 50, Appendix I McGuire Units 1 and 2 16.11.13-14 Revision 137 Page 9-256

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Land Use Census 16.11.14 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.14 Land Use Census COMMITMENT A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of:

a. the nearest milk animal,

b. the nearest residence, and

c. the nearest garden of greater than 50 m2 (500 ft2) producing broad leaf vegetation.

For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall identify within a distance of 5 km (3 miles) the location in each of the 16 meteorological sectors of:

a. all milk animals, and

b. all gardens of greater than 50 m2 producing broad leaf vegetation.

NOTE--------------------------------------

Broad leaf vegetation sampling of three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 16.11.13-1 4c shall be followed, including analysis of control samples.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Location(s) identified A.1 Identify the new location in In next scheduled which yields a calculated the Annual Radioactive Annual Radioactive dose/dose commitment Effluent Release Report. Effluent Release greater than values Report currently calculated in SLC 16.11.9.

(continued)

McGuire Units 1 and 2 16.11.14-1 Revision 21 Page 9-257

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Land Use Census 16.11.14 REMEDIAL ACTIONS (continued)

B. Location(s) identified B.1 Add the new location to the 30 days which yields a Radiological Environmental calculated dose or dose Monitoring Program.

commitment (via same exposure pathway) 20% AND greater than at a location from which samples are B.2 --------------NOTES-----------

currently being obtained If samples cannot be in accordance with SLC obtained, an explanation of 16.11.13. why samples are not obtainable (substitute representative locations if possible) shall be included.

Identify the new In the next location(s), revised figures scheduled Annual and tables for the ODCM, Radiological Release in the next Annual Report Radiological Release Report.

TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.14.1 -----------------------------NOTE----------------------------------

The results of the land use census shall be included in the Annual Radiological Environmental Operating Report.

Conduct a land use census during the growing season 12 months using the information which will provide the best results such as a door-to-door survey, aerial survey, or consultation with local agricultural authorities.

McGuire Units 1 and 2 16.11.14-2 Revision 21 Page 9-258

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Land Use Census 16.11.14 BASES This commitment is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey, or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and 2

cabbage), and (2) a vegetation yield of 2 kg/m .

With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with SLC 16.11.13, add the new location to the Radiological Environmental Monitoring Program. The sampling location(s),

excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

REFERENCES

1. McGuire Nuclear Station, Off site Dose Calculation Manual

2. 10 CFR Part 50, Appendix I McGuire Units 1 and 2 16.11.14-3 Revision 21 Page 9-259

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Interlaboratory Comparison Program 16.11.15 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.15 Interlaboratory Comparison Program COMMITMENT Analyses shall be performed on radioactive materials, supplied as part of an Interlaboratory Comparison Program (ICP), that correspond to samples required by SLC 16.11.13.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Analyses not being A.1 Report corrective actions In next scheduled performed as required. taken to prevent recurrence Annual Radiological in the Annual Radiological Environmental Environmental Operating Operating Report Report.

TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.15.1 Report a summary of the results of the Interlaboratory 12 months Comparison Program in the Annual Radiological Environmental Operating Report.

McGuire Units 1 and 2 16.11.15-1 Revision 21 Page 9-260

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Interlaboratory Comparison Program 16.11.15 BASES This requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

The Interlaboratory Comparison Program (ICP) shall be described in the Annual Radiological Environmental Operating Report.

REFERENCES

1. 10 CFR Part 50, Appendix I McGuire Units 1 and 2 16.11.15-2 Revision 21 Page 9-261

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Annual Radiological Environmental Operating Report 16.11.16 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.16 Annual Radiological Environmental Operating Report COMMITMENT Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with pre-operational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by SLC 16.11.14.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following:

a summary description of the Radiological Environmental Monitoring Program;

at least two legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor (one map shall cover stations near the site boundary; a second shall include the more distant stations);

the results of licensee participation in the Interlaboratory Comparison Program, required by SLC 16.11.15;

a discussion of all deviations from the sampling schedule of Table 16.11.13-1; and McGuire Units 1 and 2 16.11.16-1 Revision 134 Page 9-262

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Annual Radiological Environmental Operating Report 16.11.16 COMMITMENT (continued)

a discussion of all analyses in which the LLD required by Table 16.11.13-3 was not achievable.

A single submittal may be made for a multiple unit station..

APPLICABILITY At all times.

REMEDIAL ACTIONS None TESTING REQUIREMENTS None BASES None REFERENCES

1. Technical Specification 5.6.2 McGuire Units 1 and 2 16.11.16-2 Revision 134 Page 9-263

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Effluent Release Reports 16.11.17 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.17 Radioactive Effluent Release Reports COMMITMENT Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous calendar year of operation shall be submitted before May 1 of each year.

The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data provided for the reporting period using Appendix B as guidance.

The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous calendar year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. A five year average of representative onsite meteorological data shall be used in the gaseous effluent dose pathway calculations. Dispersion factors (X/Qs) and deposition factors (D/Qs) shall be generated using the computer code XOQDOQ (NUREG/CR-2919) which implements NRC Regulatory Guide 1.111.

The meteorological conditions concurrent with the time of release shall be reviewed annually to determine if the five-year average values should be revised. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

McGuire Units 1 and 2 16.11.17-1 Revision 143 Page 9-264

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Effluent Release Reports 16.11.17 COMMITMENT (continued)

The Radioactive Effluent Release Reports shall include the following information for each type of solid waste shipped offsite or disposed of in the site landfill during the report period:

a. Total container volume, in cubic meters,

b. Total Curie quantity (determined by measurement or estimate),

c. Principal radionuclides (determined by measurement or estimate),

d. Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

e. Number of shipments, and

f. Solidification agent or absorbent (e.g., cement, or other approved agents (media)).

The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to SLC 16.11.14.

The Radioactive Effluent Release Reports shall also identify any licensee initiated major changes to the Radioactive Waste Systems (liquid, gaseous, and solid). Otherwise, this information may be included in the annual UFSAR update. The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;

d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License application and amendments thereto; McGuire Units 1 and 2 16.11.17-2 Revision 143 Page 9-265

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Radioactive Effluent Release Reports 16.11.17 COMMITMENT (continued)

e. An evaluation of the change, which shows expected maximum exposures to individual in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

g. An estimate of the exposure to plant operating personnel as a result of the change; and

h. Documentation of the fact that the change was reviewed and found acceptable by the Station Manager or the Chemistry Manager.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate Radwaste Systems, the submittal shall specify the releases of radioactive material from each unit.

APPLICABILITY At all times REMEDIAL ACTIONS None TESTING REQUIREMENTS None BASES None REFERENCES

1. Technical Specification 5.6.3 McGuire Units 1 and 2 16.11.17-3 Revision 143 Page 9-266

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Holdup Tanks 16.11.18 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.18 Liquid Holdup Tanks COMMITMENT The quantity of radioactive material contained in each unprotected outdoor radwaste tank shall be limited to < 10 Curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Quantity of radioactive A.1 Suspend all additions of Immediately material in tank not radioactive material to the within limit. tank.

AND A.2 Reduce the tank contents 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to within limit.

AND A.3 Describe the events Within the next leading to this condition in scheduled Annual the next Annual Radioactive Effluent Radioactive Effluent Release Report Release Report.

TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.18.1 Verify the quantity of radioactive material contained in 7 days unprotected outdoor radwaste tanks is within limits by analyzing a representative sample of the tanks contents when radioactive materials are being added to the tank.

McGuire Units 1 and 2 16.11.18-1 Revision 0 Page 9-267

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Liquid Holdup Tanks 16.11.18 BASES The tanks applicable to this SLC include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

REFERENCES None McGuire Units 1 and 2 16.11.18-2 Revision 0 Page 9-268

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Explosive Gas Mixture 16.11.19 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.19 Explosive Gas Mixture COMMITMENT The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be limited to < 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of oxygen A.1 Reduce oxygen 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months in the WASTE GAS concentration to within HOLDUP SYSTEM limits.

> 2% but < 4% by volume.

B. Concentration of oxygen B.1 Suspend all additions of Immediately in the WASTE GAS waste gases to the system.

HOLDUP SYSTEM

> 4% and hydrogen AND concentration > 4% by volume. B.2 Reduce the concentration Immediately of oxygen to < 4% by volume.

AND B.3 Reduce oxygen 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months concentration to within limits.

McGuire Units 1 and 2 16.11.19-1 Revision 0 Page 9-269

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Explosive Gas Mixture 16.11.19 TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.19.1 Verify the concentrations of hydrogen and oxygen in the During WASTE WASTE GAS HOLDUP SYSTEM is within limits by GAS HOLDUP monitoring waste gases in the WASTE GAS HOLDUP SYSTEM SYSTEM with the hydrogen and oxygen monitors operation required by SLC 16.7.8.

BASES This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is maintained below the flammability limits of hydrogen and oxygen. Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

REFERENCES None McGuire Units 1 and 2 16.11.19-2 Revision 0 Page 9-270

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gas Storage Tanks 16.11.20 16.11 RADIOLOGICAL EFFLUENT CONTROLS 16.11.20 Gas Storage Tanks COMMITMENT The quantity of radioactivity contained in each gas storage tank shall be limited < 49,000 Curies noble gases (considered as Xe-133).

APPLICABILITY At all times.

REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Quantity of radioactive A.1 Suspend all additions of Immediately material in tank not radioactive material to the within limit. tank.

AND A.2 Reduce the tank contents 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to within limit.

TESTING REQUIREMENTS TEST FREQUENCY TR 16.11.20.1 Verify the quantity of radioactive material contained in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months each gas storage tank is within limit when radioactive materials are being added to the tank.

McGuire Units 1 and 2 16.11.20-1 Revision 0 Page 9-271

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 Gas Storage Tanks 16.11.20 BASES This SLC considers postulated radioactive releases due to a waste gas system leak or failure, and limits the quantity of radioactivity in each pressurized gas storage tank in the WASTE GAS HOLDUP SYSTEM to assure that a release would be substantially below the dose guideline values of 10 CFR Part 100 for a postulated event.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure, in NUREG-0800, July 1981.

REFERENCES None McGuire Units 1 and 2 16.11.20-2 Revision 0 Page 9-272

Attachment 10 Summary of Changes to the Process Control Program McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 10 Summary of Changes to the Process Control Program This attachment includes a summary of changes to the PCP.

Page 10-1

Attachment 10 Summary of Changes to the Process Control Program McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 The McGuire Nuclear Station PCP was not revised in 2016. The most recent revision was provided with the McGuire Nuclear Station 2014 ARERR.

Page 10-2

Attachment 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems This attachment includes a description of major modifications to the radioactive waste treatment systems that are anticipated to affect effluent releases.

Page 11-1

Attachment 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 No major modifications to McGuire Nuclear Station liquid, gaseous, solid, or mobile radioactive waste treatment systems occurred in 2016.

Page 11-2

Attachment 12 Errata to a Previous Year's ARERR McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 ATTACHMENT 12 Errata to a Previous Year's ARERR This attachment includes any amended pages from a previous year's ARERR.

Page 12-1

Attachment 12 Errata to a Previous Year's ARERR McGuire Nuclear Station Units 1 & 2 Period 1/1/2016 - 12/31/2016 There are no changes to a previous year's ARERR.

Page 12-2

MNS-17-019, Annual Radioactive Effluent Release Report, January 1, 2016 Through December 31, 2016

Contents

Text

SUMMARY

11.3 REFERENCES

11.8 REFERENCES

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MNS-17-019, Annual Radioactive Effluent Release Report, January 1, 2016 Through December 31, 2016

Text

SUMMARY

11.3 REFERENCES

11.8 REFERENCES

REFERENCES:

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