RA-19-0211, 2018 Annual Radioactive Effluent Release Report (ARERR) and Offsite Dose Calculation Manual (ODCM)

2018 Annual Radioactive Effluent Release Report (ARERR) and Offsite Dose Calculation Manual (ODCM)

ML19121A608
Person / Time
Site:	Oconee
Issue date:	04/30/2019
From:	Fisk P Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-19-0211
Download: ML19121A608 (365)

Text

Paul V. Fisk J_., DUKE Plant Manager

~ ENERGY Oconee Nuclear Station Duke Energy ON01 VP I 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.6413 f 864.873.4208 Paul.Fisk@duke-energy.com RA-19-0211 April 30, 2019 Attention: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station Docket Nos. 50-269, 50-270, 50-287 2018 Annual Radioactive Effluent' Release Report (ARE RR)

Pursuant to Oconee Nuclear Station Technical Specification (TS) 5.6.3 and Selected Licensee Commitment 16.11.9, please find attached the Annual Radioactive Effluent Release Report for the period of January 1, 2018 through December 31, 2018. In accordance with TS 5.5.1, the Offsite Dose Calculation Manual (ODCM) is included in this submittal.

Should there be any questions concerning this report please contact Sam Adams, Oconee Regulatory Affairs, at 864-873-3348.

Sincerely,

~[Plant Manager Oconee Nuclear Station Attachments (12)

U. S. Nuclear Regulatory Commission April 30, 2019 .

Page2 cc:

Ms. Catherine Haney, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Ms. Audrey Klett, Project Manager (ONS)

U.S. Nuclear Regulatory Commission 11555 Rockville Pike M/S O-8G9A Rockville, MD 20852-27 46 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station Ms. Lynne Garner, Manager (by electronic mail only: garnerld@dhec.sc.gov)

Division of Waste Management, Bureau of Land & Waste Management SC Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Mr. James Twiggs INPO 700 Galleria Place, Suite 100 Atlanta, GA 30339-5943 Mr. Gary Stewart State Voluntary Cleanup Section SC Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29291 Ms. Anuradha Nair Gimmi, Manager Nuclear Response and Emergency Environmental Surveillance Division of Emergency Response SC Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201

.£a, DUKE *. *

~ ENERGY*

Oconee Nuclear Station*

Units 1, 2, and 3 Annual Radioac tive Effluen t Release Report

. January 1, 2018 through D.e cetnber 31, 2018 Dockets 50-269, 50-270, and 50-287

Introduction The Annual Radioactive Effluent Release Report is pursuant to Oconee Nuclear Station Technical Specification 5.6.3 and Selected Licensee Commitment 16.11-9. The below listed attachments to this report provide the required information. In addition, the ODCM is included pursuant to Oconee 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 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 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.

Page 1-1

Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Gaseous Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr3 Qtr4 Year A. Fission and Activation Gases

1. Total Release Ci 8.71E-01 3.78E-01 4.06E-01 1.32E-01 1.79E+00

2. Avg . Release Rate µCi/sec 1.12E-01 4 .80E-02 5.10E-02 1.66E-02 5.66E-02 B. Iodines and Halogens

1. Total Release Ci 0.00E+00 2 .12E-04 2.06E-07 2.35E-05 2.35E-04

2. Avg. Release Rate µCi/sec 0.00E+00 2 .69E-05 2.60E-08 2.96E-06 7.47E-06 C. Particulates Half-Life ;:: 8 days

1. Total Release Ci 0.00E+00 5.45E-10 0.00E+00 0.00E+00 5.45E-10

2. Avg . Release Rate µCi/sec 0.00E+00 6.93E-11 0.00E+00 0.00E+00 1.73E-11 D. Tritium

1. Total Release Ci 3.16E+01 2 .22E+01 4.34E+01 5.88E+01 1.56E+02 l 2. Avg. Release Rate µCi/sec 4.06E+00 2 .831;+00 5.46E+00 7.40E+00 4.95E+00 E. Carbon-14

1. Total Release Ci 6.05E+00 5.36E+00 6.08E+00 5.35E+00 2 .29E+01

2. Avg. Release Rate µCi/sec 7.79E-01 6.82E-01 7.65E-0 1 6.74E-01 7.25E-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 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Gaseous Effluents - Mixed Mode - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A Fission and Activation Gases Ar-41 Ci 0.00E+00 4.54E-02 0.00E+00 0.00E+00 4.54E-02 Xe-133 Ci 8.51 E-01 0.00E+00 3.12E-01 0.00E+00 1.16E+00 Total for Period Ci 8.51 E-01 4.54E-02 3.12E-01 0.00E+00 1.21E+00 B. Iodines and Halogens 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+O0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Tritium H-3 Ci 2.31E+01 1.87E+01 4.04E+01 4.85E+01 1.31E+02 E. Carbon-14 C-14 Ci 1.82E+00 1.61E+00 1.82E+00 1.61E+00 6.86E+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.

Page 1-3

Attachm1a-nt 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018 Gaseous Effluents - Mixed Mode Releases - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases Ar-41 Ci 1.52E-02 2.91E-02 7.38E-02 4.02E-02 1.58E-01 Xe-131m Ci 0.00E+00 9.42E-04 0.00E+00 0.00E+00 9.42E-04 Xe-133 Ci 4.50E-03 2.95E-01 1.82E-02 9.11 E-02 4.09E-01 Xe-133m Ci 0.00E+00 2.26E-03 7.55E-06 1.34E-04 2.40E-03 Xe-135 Ci 2.72E-04 4.95E-03 1.53E-03 5.35E-04 7.28E-03 Total for Period Ci 2.00E-02 3.32E-01 9.35E-02 1.32E-01 5.78E-01 B. Iodines and Halogens Br-82 Ci 0.00E+00 0.00E+00 2.06E-07 0.00E+00 2.06E-07 1-131 Ci 0.00E+00 2.31 E-07 0.00E+00 1.65E-09 2.33E-07 1-132 Ci 0.0OE+00 2.11E-04 0.00E+00 2.35E-05 2.35E-04 1-133 Ci 0.00E+00 2.74E-07 0.00E+00 4.21E-10 2.74E-07 Total for Period Ci 0.00E+O0 2.12E-04 2.06E-07 2.35E-05 2.35E-04 C. Particulates Half-Life ~ 8 days Co-58 Ci 0.00E+00 5.45E-10 0.00E+00 0.00E+00 5.45E-10 Total for Period Ci 0.00E+00 5.45E-10 0.00E+00 0.00E+00 5.45E-10 D. Tritium H-3 1.46E-02 9.74E-01 8.72E-02 2.49E+00 3.57E+O0 Ci E. Carbon-14 C-14 Ci 4.24E+00 3.75E+00 4.26E+00 3.75E+00 1.60E+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 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Gaseous Effluents - Ground Releases - Continuous Mode Units Qtr 1 Qtr 2 Qtr3 Qtr4 Year A. Fission and Activation Gases None Ci Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.0OE+00 B. Iodines and Halogens None Ci Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.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 8.49E+00 2.25E+00 ' 2.85E+00 7.79E+00 2.14E+01 E. Carbon-14 C-14 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F. Gross Alpha Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1-5

Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018 Gaseous Effluents - Ground Releases - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases None Ci Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 B. Iodines and Halogens None Ci Total for Period Ci 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 C. Particulates Half-Life 2= 8 days None Ci Total for Period Ci 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Tritium H-3 Ci ' 4.03E-02 3.22E-01 4.55E-02 4.63E-02 4.55'E-01 E. Carbon-14 C-14 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F. Gross Alpha Total for Period Ci 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1-6

Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018 Liquid Effluents - Summation of All Releases Units Qtr 1 Qtr2 Qtr 3 Qtr4 Year A. Fission and Activation Products *

1. Total Release Ci 3.36E-03 5.52E-04 1.41 E-04 2.83E-04 4.34E-03

2. Avg. Diluted Cone. µCi/ml 9.17E-13 3.70E-13 3.72E-14 3.36E-13 4.15E-13

3. Batch Releases µCi/ml 4.01E-10 6.52E-11 1.65E-11 3.31 E-11 1.28E-10 B. Tritium

1. Total Release Ci 2.72E+02 3.78E+02 1.71E+02 1.53E+02 9.74E+02

2. Avg. Diluted Cone. µCi/ml 9.47E-08 2.64E-07 7.02E-08 1.89E-07 1.54E-07

3. Batch Releases µCi/ml 3.25E-05 4.47E-05 1.99E-05 1.79E-05 2.87E-05 C. Dissolved & Entrained Gases

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+O0 0.00E+00

2. Avg. Diluted Cone. 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 O.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Gross Alpha

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

2. Avg. Dilu.ted Cone. µCi/ml 0.00E+00 0.00E+00 o.ooE*+oo O.00E+O0 0.00E+00

3. Batch Releases µCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+O0 0.00E+00 E. Volume of Liquid Waste

1. Batch Releases liters 1.36E+06 2.26E+06 1.11 E+06 2.89E+06 7.63E+06

2. Continuous Releases liters 5.93E+08 3.97E+08 4.94E+08 2.82E+08 1.77E+09 F. Volume of Dilution Water

1. Batch Releases liters 8.37E+09 8.46E+09 8.55E+09 8.55E+09 3.39E+10

2. Continuous Releases liters 8.37E+09 8.46E+09 8.55E+09 8.55E+09 3.39E+10

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

Page 1-7

Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Liquid Effluents - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products None Ci Total for Period Ci 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 B. Tritium H-3 Ci 1.83E-01 9.92E-02 2.31 E-01 6.42E-02 5.77E-01 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 O.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1-8

Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Liquid Effluents - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products Co-58 Ci 2.06E-03 5.22E-04 1.14E-04 1.43E-04 2.84E-03 Co-60 Ci 1.94E-04 0.0OE+O0 O.00E+00 2.34E-05 2.17E-04 Ni-63 Ci 4.25E-04 3.06E-05 2.73E-05 5.67E-05 5.40E-04 Nb-95 Ci 1.96E-04 0.O0E+00 0.00E+00 0.00E+00 1.96E-04 Zr-95 Ci 8.88E-05 0.00E+00 0.00E+00 0.00E+00 8.88E-05 Ag-110m Ci 7.41 E-05 0.00E+00 0.00E+00 3.67E-05 1.11E-04 Sb-124 Ci 2.64E-04 0.00E+00 0.00E+00 0.00E+00 2.64E-04 Sb-125 Ci 4.97E-05 0.00E+00 0.00E+00 0.00E+00 4.97E-05 Cs-137 Ci 1.0?E-05 0.00E+00 0.00E+00 0.00E+00 1.0?E-05 Ce-144 Ci 0.00E+00 0.00E+O0 0.00E+00 1.64E-05 1.64E-05 Np-239 Ci 0.00E+00 0.00E+00 0.00E+00 6.86E-06 6.86E-06 Total for Period Ci 3.36E-03 5.52E-04 1.41E-04 2.83E-04 4.34E-03 B. Tritium H-3 Ci 2.72E+02 3.78E+02 1.70E+02 1.53E+02 9.74E+02 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 1-9

Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 ATTACHMENT 2 Supplemental Information This attachment includes supplemental information to the gaseous and liquid effluents report.

Page 2-1

Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 I. Regulato[lr'. 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

8. 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 - lodine-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

8. Liquid Effluents

1. Information found in 10 CFR Part 20, Appendix 8, Table 2, Column 2 Ill. 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 84

2. Total Time (min) for Batch Releases 1.62E+04

3. Maximum Time (min) for a Batch Release = 2.21E+02

4. Average Time (min) for Batch Releases 1.92E+02

5. Minimum Time (min) for a Batch Release 1.23E+02

6. Average Dilution Water Flow During Release (1pm) = 6.46E+04

8. Gaseous Effluents

1. Total Number of Batch Releases 90

2. Total Time (min) for Batch Releases = 1.02E+05

3. Maximum Time (min) for a Batch Release = 1.03E+04

4. Average Time (min) for Batch Releases 1.14E+03

5. Minimum Time (min) for a Batch Release 7.00E+00 VI. Abnormal Releases See Attachment 5, Unplanned Offsite Releases.

Page 2-2

Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 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. Oconee Nuclear Station 2018 ARERR contains estimates of C-14 radioactivity released in 2018, 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 Oconee Nuclear Station 2018 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 Oconee Nuclear Station in 2018 results in a site total C-14 gaseous release estimate to the environment of 2.29E+01 Curies. 70% of the C-14 gaseous effluent is assumed to be from batch releases 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 Oconee Nuclear Station 2018 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 Oconee ODCM. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released from Oconee Nuclear Station in 2018 is well below the 10CFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit).

Page 2-3

Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Overall Estimate of Error for Effluent Radioactivity Release Reported The estimated percentage of overall error for both Liquid and Gaseous effluent release data at Oconee 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%

Page 2-4

Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Summary of Changes in Land Use Census Affecting Effluent Dose Calculations The 2018 Land Use Census was performed May 22-23, 2018, and the results were certified and made available for ,

use on June 20, 2018. The following are changes to residences, gardens, and milk animals from the previous year.

Residences The residence in the WSW sector at 1.76 miles was replaced with a residence at 1.73 miles.

Gardens Broad leaf vegetation samples are taken in lieu of a garden census for Oconee Nuclear Station. For dose calculation purposes a garden is assumed to exist at the site boundary and beyond for every sector since a garden location cannot be ruled out.

Milk Animals The milk animal (goat) in the E sector at 4.66 miles was no longer present.

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

Page 2-5

Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Burial Total Type of Number of Number of Waste Container Solidification Volume Activity Waste Shipped Shipments Containers Class Type Agent (m3) (Curies)

1. Waste from Liguid S~tems

a. Dewatered Secondary Resins None 2 2 2A-U GDP N/A 6.82 8.95E+00

b. Dewatered Primary Resins 2 2 28 Type A N/A 6.82 1.83E+02 15 1C Type A N/A 3.41 1.03E+02 C. Evaporator Concentrates None

d. Dewatered Mechanical Filters C Type A N/A 3.41 6.46E+00

e. Dewatered Demineralizers None

f. Solidified (cement) Acids, None Oils, Sludge

2. Dry Solid Waste

a. Dry Active Waste None (compacted)

b. Dry Active Waste (non- A-U GDP N/A 1018.27 1.47E+00 15 29 compacted)

C. Dry Active Waste (brokered) None

d. Irradiated Components None

3. Total Solid Waste 21 35 1038.73 302.43 Page 3-2

Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Type of Waste Shipped Radionuclide % Abundance

1. Waste from Liguid S~tems

a. Dewatered Secondary Resins N/A N/A

b. Dewatered Primary Resins Ag-110m 0.17 Be-7 2.28 C-14 1.71 Ce-144 0.02 Co-57 0.28 Co-58 16.35 Co-60 7.29 Cr-51 0.03 Cs-134 0.10 Cs-137 1.62 Fe-55 34.26 Fe-59 0.02 H-3 0.04 Mn-54 2.99 Nb-95 0.37 Ni-59 0.10 Ni-63 31.04 Pu-241 0.01 Sb-124 0.04 Sb-125 0.03 Sr-89 0.02 Sr-90 0.03 Zn-65 1.00 Zr-95 0.18 C. Evaporator Concentrates N/A N/A

d. Dewatered Mechanical Filters Ag-110m 0.34 C-14 9.21 Ce-144 0.44 Co-57 0.13 Co-58 0.57 Co-60 24.61 Cs-134 0.07 Cs-137 4.97 Fe-55 32.97 H-3 14.75 Mn-54 1.45 Nb-94 0.00 Nb-95 0.07 Ni-63 7.12 Sb-125 0.01 Tc-99 2.80 Zn-65 0.45 Zr-95 0.03

e. Dewatered Demineralizers N/A N/A

f. Solidified (cement) Acids, Oils, Sludge N/A N/A

2. Dry Solid Waste

a. Dry Active Waste (compacted) N/A N/A Page 3-3

Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017

b. Dry Active Waste (non-compacted) C-14 0.02 Co-57 0.42 Co-58 58.52 Co-60 7.90 Cs-137 8.88 H-3 0.58 Mn-54 6.35 Ni-63 17.32

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

d. Irradiated Components N/A N/A Page 3-4

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 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).

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Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Lower Level 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 1 0 1 0 0.76-1.00 0 0 0 0 1 1 0 0 0 1 1 0 1 1 0 0 1.01-1.25 2 2 1 2 0 0 0 1 2 0 0 3 2 3 1 0 1.26-1.50 3 3 1 1 0 1 0 2 2 5 8 0 0 0 0 0 1.51-2.00 3 3 5 2 2 4 1 1 3 23 52 11 9 3 5 2 2.01-3.00 1 2 2 13 6 2 1 0 2 72 84 24 2 3 2 2 A

3.01-4.00 0 0 1 4 0 0 0 0 1 22 26 6 2 0 0 0 4.01-5.00 0 0 0 1 0 0 0 0 0 3 2 1 7 3 2 2 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 2 2 4 3 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 3 1 5 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 2 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 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 1 0 0 0 1 0 0 0 0 0 0 0 0 0 1.01-1.25 1 1 0 0 1 0 1 0 0 3 1 0 0 1 0 0 1.26-1.50 2 6 2 1 1 0 1 0 0 7 8 1 0 1 3 0 1.51-2.00 5 5 10 16 2 0 2 2 6 29 40 22 10 7 4 1 2.01-3.00 2 3 7 15 4 2 4 3 7 58 37 19 4 4 3 1 B

3.01-4.00 4 0 0 2 1 0 0 0 1 25 12 4 3 1 1 0 4.01-5.00 0 0 0 1 0 0 0 0 0 3 1 8 3 2 0 1 5.01-6.00 0 0 0 0 0 0 0 0 0 0 1 1 2 2 3 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 1 0 6 5 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 4-2

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Lower Level Hours of Occurrence Wind Stability Sector Speed Class (m/s) N NNE NE ENE E ESE SE SSE s ss w w SW WSW 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 1 0 0 0 0 0 0 0 0 1.01-1.25 1 6 1 1 0 0 1 1 1 2 4 2 3 3 2 1 1.26-1.50 6 6 4 6 1 3 0 3 4 9 3 11 4 6 3 8 1.51-2.00 3 9 9 8 15 3 7 4 6 18 31 26 12 8 6 2 2.01-3.00 2 1 9 22 14 4 2 6 7 50 19 7 1 2 4 0 C

3.01-4.00 1 0 0 4 0 0 0 0 0 14 6 0 5 3 4 0 4.01-5.00 1 0 0 0 0 0 0 0 0 4 1 8 2 9 7 0 5.01-6.00 0 0 0 0 0 0 0 0 0 1 2 5 2 8 2 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 4 2 3 2 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 0.46-0.75 3 2 0 1 3 3 4 3 3 1 0 4 5 7 7 4 0.76-1.00 23 17 11 12 12 9 9 11 11 11 13 18 22 20 23 32 1.01-1.25 31 20 15 18 17 5 12 10 15 14 19 24 29 27 23 38 1.26-1.50 30 25 29 44 34 15 26 25 29 30 33 29 20 21 11 21 1.51-2.00 19 30 69 95 57 32 38 51 51 39 51 58 30 16 13 16 2.01-3.00 12 21 114 158 42 18 26 14 30 116 106 53 30 31 23 12 D

3.01-4.00 9 13 37 49 1 0 0 0 0 33 77 41 39 29 16 13 4.01-5.00 1 5 14 9 0 0 0 0 0 4 22 35 23 31 17 6 5.01-6.00 0 0 1 0 0 0 0 0 0 3 13 21 6 10 12 1 6.01-8.00 0 0 0 0 0 0 0 0 0 0 6 20 6 1 1 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 3 0 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-3

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Lower Level Hours of Occurrence Wind Stability Sector Speed Class (m/s) s ss w NNW N NNE NE ENE E ESE SE SSE w SW WSW WNW NW 0.46-0.75 28 17 20 13 18 13 10 10 13 8 18 15 32 35 44 25 0.76-1.00 83 55 46 33 36 46 31 27 27 32 32 39 59 63 102 114 1.01-1.25 63 29 33 52 51 45 33 50 22 20 24 21 38 42 46 86 1.26-1.50 21 22 46 62 56 54 57 43 32 29 28 30 19 29 27 36 1.51-2.00 19 13 50 89 74 48 35 66 41 32 45 34 19 7 10 15 2.01-3.00 6 9 46 106 30 19 10 11 22 56 53 34 15 7 6 8 E

3.01-4.00 2 3 9 29 0 0 1 1 1 15 25 8 7 2 2 2 4.01-5.00 2 1 1 4 0 0 0 0 0 5 16 9 4 0 1 0 5.01-6.00 0 0 0 0 0 0 0 0 0 1 7 2 1 1 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 1 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 0.46-0.75 0 2 2 0 2 2 1 0 0 3 0 0 5 10 5 5 0.76-1.00 4 6 0 4 2 4 2 4 5 1 4 8 14 29 25 6 1.01-1.25 3 2 1 1 1 5 2 2 0 3 2 4 4 23 17 6 1.26-1.50 1 1 0 1 3 5 8 2 1 2 4 0 3 12 16 3 1.51-2.00 0 0 0 2 2 13 4 5 2 0 6 1 1 2 5 0 2.01-3.00 0 0 0 0 0 1 2 1 2 2 4 1 1 1 1 0 F

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 1 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 4-4

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Lower Level

• 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 1 3 2 0 1 0.76-1.00 0 1 0 0 0 0 0 0 0 0 0 4 8 10 2 1 1.01-1.25 0 0 0 0 0 0 0 0 0 0 1 2 1 5 4 0 1.26-1.50 0 0 0 0 0 1 0 0 0 0 1 1 0 2 2 0 1.51-2.00 0 0 0 1 0 1 0 0 0 0 0 0 0 1 0 0 2.01-3.00 0 0 0 0 0 1 0 0 0 0 1 0 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 1 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 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Upper Level Hours of Occurrence Wind Stability Sector Speed 55 Class (m/s) N NNE NE ENE E ESE SE SSE 5 w 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 1 0.76-1.00 0 0 0 0 1 0 0 0 0 0 0 0 0 2 0 0 1.01-1.25 0 0 1 0 0 0 0 0 0 1 0 1 1 0 0 0 1.26-1.50 0 0 0 1 0 0 1 0 1 1 2 0 2 0 0 0 1.51-2.00 3 3 2 0 1 0 1 0 2 3 13 7 4 2 3 0 2.01-3.00 1 8 5 4 5 3 5 2 6 38 67 14 1 0 3 0 A

3.01-4.00 0 1 0 4 5 0 0 1 9 27 28 3 0 1 1 1 4.01-5.00 1 0 1 3 5 0 0 1 7 33 20 2 1 1 1 2 5.01-6.00 0 1 1 3 2 0 0 1 4 16 8 4 1 2 0 0 6.01-8.00 0 0 0 1 0 0 0 0 0 4 22 2 9 6 4 1 8.01-10.00 0 0 0 0 0 0 0 0 0 1 2 1 3 5 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 4 1 1 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 2 0 1 0 1 0 0 1.26-1.50 0 0 0 0 0 1 1 0 1 1 2 1 2 0 0 0 1.51-2.00 5 4 2 4 1 1 1 0 1 7 12 11 0 2 4 1 2.01-3.00 4 3 10 13 9 4 5 6 11 33 41 16 4 1 4 0 B

3.01-4.00 1 0 3 7 5 0 1 4 10 25 16 0 2 2 2 1 4.01-5.00 1 1 2 4 4 0 0 1 6 18 7 1 1 0 2 0 5.01-6.00 2 0 0 1 2 0 0 1 9 10 8 4 3 2 2 0 6.01-8.00 2 0 0 2 0 0 0 0 0 7 9 8 3 2 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 2 1 1 9 6 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 1 0 2 0 0 Page 4-6

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Upper Level Hours of Occurrence Wind Stability Sector Speed Class (m/s) N NNE NE ENE E ESE SE SSE s ss w w SW WSW 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 1 0 0 1.01-1.25 0 1 0 0 0 0 0 1 2 0 1 2 2 0 0 0 1.26-1.50 3 1 1 1 1 0 1 1 0 1 7 7 0 4 2 4 1.51-2.00 6 9 4 8 6 1 3 3 2 8 13 17 5 5 3 7 2.01-3.00 3 5 7 7 15 10 7 6 11 22 27 13 2 1 4 0 C

3.01-4.00 1 1 8 10 11 1 1 6 3 22 2 2 2 2 3 0 4.01-5.00 0 0 1 7 4 1 2 1 10 11 6 1 0 2 0 0 5.01-6.00 2 0 2 2 1 0 0 0 2 8 6 0 1 2 2 0 6.01-8.00 0 0 0 1 0 0 0 0 1 7 5 8 5 10 4 0 8.01-10.00 0 0 0 0 0 0 0 0 1 2 3 5 2 10 4 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 3 0 2 0 0 0.46-0.75 0 0 0 0 0 0 1 0 1 1 0 1 0 0 1 0 0.76-1.00 6 4 1 2 5 4 1 2 3 4 4 3 10 9 11 7 1.01-1.25 6 7 5 4 1 6 6 6 11 4 9 10 10 12 7 8 1.26-1.50 22 17 13 8 6 3 7 4 5 16 17 18 20 12 23 19 1.51-2.00 39 29 29 17 24 15 21 21 25 28 27 27 21 19 20 19 2.01-3.00 57 42 50 70 55 28 57 29 43 51 50 36 21 17 14 45 D

3.01-4.00 16 25 107 68 37 22 11 29 34 42 47 33 17 30 16 8 4.01-5.00 8 9 61 82 29 3 7 6 21 37 49 23 15 21 13 7 5.01-6.00 4 3 36 42 4 0 0 1 5 27 51 23 24 26 16 6 6.01-8.00 3 12 19 20 1 0 0 0 0 13 74 46 37 44 24 9 8.01-10.00 0 5 11 1 0 0 0 0 0 3 22 27 5 9 12 1 10.01-max 0 0 0 0 0 0 0 0 0 4 8 12 3 2 1 0 Page 4-7

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Upper Level Hours of Occurrence Wind Sector Stability Speed Class E s ss w WNW NW NNW (m/s) N NNE NE ENE ESE SE SSE w SW WSW 0.46-0.75 8 4 2 0 0 0 0 2 0 1 2 4 3 1 1 2 0.76-1.00 11 18 8 0 5 3 2 3 4 5 10 11 13 15 19 10 1.01-1.25 25 10 10 12 8 7 1 5 3 12 7 17 13 26 24 26 1.26-1.50 38 28 15 10 6 7 6 12 8 7 12 19 22 34 43 50 1.51-2.00 133 68 43 18 22 16 23 16 16 22 20 28 35 34 59 94 2.01-3.00 186 138 113 65 60 52 36 33 55 44 52 57 40 27 41 116 E

3.01-4.00 36 34 67 77 58 22 16 35 36 44 33 17 15 14 7 17 4.01-5.00 5 10 40 43 22 1 7 13 14 30 33 9 8 9 4 4 5.01-6.00 1 5 8 18 7 1 0 2 8 18 32 4 6 5 1 3 6.01-8.00 2 5 12 8 0 0 0 1 0 9 35 6 10 2 0 1 8.01-10.00 1 2 2 0 0 0 0 0 0 6 23 1 2 2 2 0 10.01-max 0 0 0 0 0 0 0 0 0 0 7 0 0 0 0 0 0.46-0.75 0 0 0 0 0 0 1 1 0 0 0 0 0 0 0 0 0.76-1.00 0 0 2 2 1 0 2 1 0 1 0 3 1 0 1 3 1.01-1.25 2 3 2 2 1 1 3 1 2 2 0 1 0 1 1 4 1.26-1.50 3 1 1 2 3 0 2 2 1 0 2 2 2 1 1 2 1.51-2.00 16 6 6 6 2 2 5 3 5 3 3 3 2 4 8 10 2.01-3.00 42 29 5 3 1 3 9 9 4 3 2 4 4 2 1 8 F

3.01-4.00 2 1 0 1 1 5 5 5 6 3 3 0 1 1 1 1 4.01-5.00 0 0 0 0 0 0 0 0 1 3 1 1 1 0 1 0 5.01-6.00 0 0 0 0 0 0 0 1 1 0 2 2 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 1 1 0 1 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 4-8

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Upper Level 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 1 0 0 1 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 1 0 0 0 0 0 1 0 1 1.26-1.50 0 2 0 1 1 2 2 0 0 1 0 0 1 2 1 2 1.51-2.00 1 2 0 0 0 0 0 2 0 0 2 1 1 0 0 3 2.01-3.00 4 2 0 0 0 0 0 1 1 3 2 1 0 2 0 0 G

3.01-4.00 0 0 1 0 0 0 0 1 1 1 2 1 0 0 0 0 4 .01-5.00 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 6.01-8.00 0 0 *O 0 0 0 0 0 1 0 0 0 o* 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 4-9

Attachment 5 Unplanned Offsite Releases Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018 ATTACHMENT 5 Unplanned Offsite Releases This attachment includes a summary of the unplanned offsite releases of gaseous and liquid radioactive effluents.

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Attachment 5 Unplanned Offsite Releases Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/20 18 Oconee Nuclear Station had zero (0) unplanned liquid offsite release radioactive effluents in 2018.

Oconee Nuclear Station had zero (0) unplanned gaseous offsite release of radioactive effluents in 2018.

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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 ATTACHMEN T 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).

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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Gaseous Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Noble Gases

1. Maximum Gamma Air mRAD 2.35E-05 4.28E-05 4.27E-05 2.16E-05 1.31 E-04 (a) Limit mRAD 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.00E+01 (b) % of Limit 1.57E-04 2.85E-04 2.85E-04 1.44E-04 4.35E-04

2. Maximum Beta Air mRAD 5.03E-05 3.02E-05 3.14E-05 1.21 E-05 1.24E-04 (a) Limit mRAD 3.00E+01 3.00E+01 3.00E+01 3.00E+01 6.00E+01 (b) % of Limit 1.68E-04 1.01 E-04 1.05E-04 4.05E-05 2.0?E-04 Receptor Location 1.0 miles SW B. Iodine, H-3, & Particulates

1. Maximum Organ Dose mREM 9.02E-02 7.98E-02 9.06E-02 7.97E-04 3.40E-01 (a) Limit mREM 2.25E+01 2.25E+01 2.25E+01 2.25E+01 4.50E+01 (b) % of Limit 4.01 E-01 3.55E-01 4.03E-01 3.54E-01 7.56E-01 Receptor Location 1.0 miles SW Critical Age CHILD Critical Organ BONE Page 6-2

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Liquid Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Batch & Continuous Mode

1. Maximum Organ Dose mREM 1.13E-01 5.21E-02 2.35E-02 2.11 E-02 2.07E-01 (a) Limit mREM 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.00E+01 (b) % of Limit 7.56E-01 3.48E-01 1.57E-01 1.41E-01 6.89E-01 (c) Critical Age Adult Child Child Child Adult (d) Critical Organ GILLI GILLI GILLI GILLI GILLI

2. Maximum Total Body Dose mREM 3.81E-02 5.21E-02 2.35E-02 2.11 E-02 1.35E-01 (a) Limit mREM 4.50E+00 4.50E+00 4.50E+00 4.50E+O0 9.00E+00 (b) % of Limit 8.47E-01 1.16E+00 5.22E-01 4.70E-01 1.50E+00 (c) Critical Age Child Child Child Child Child Page 6-3

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 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 Oconee Nuclear Station includes liquid and gaseous effluent dose contributions from Oconee 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) 3.48E-01 mREM

1. Location 1.0 miles SW

2. Critical Age CHILD

3. Critical Organ BONE

4. Gas Contribution % 97.83%

5. Liquid Contribution % 2.17%

B. Maximum Total Body Dose 2.53E-01 mREM

1. Location 1.0 miles SW

2. Critical Age CHILD

3. Gas non-NG Contribution % 46.78%

4. Gas Contribution % 0.05%

5. Liquid Contribution % 53.17%

Direct and air-scatter radiation dose contributions from the onsite ISFSI have been determined from 10 CFR 72.212 Evaluation Report for Phase VIII Standardized NUHOMS Cask System Rev. 00. The maximum dose rate to the nearest real individual from the ISFSI is conservatively calculated to be less than 11 mrem/yr.

The attached excerpt from the 10 CFR 72.212 Evaluation Report for Phase VIII Standardized NUHOMS Cask System Rev. 00 is provided to document the method used to calculate the dose from ISFSI as less than 11 mrem/yr to the nearest real individual.

Total dose from liquid and gaseous effluents from Oconee Nuclear Station and direct and air-scatter dose from the onsite ISFSI is conservatively estimated to be less than 12 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 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 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 ONS ISFSI.

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

6.2.1 §72.104(a)- Dose Limits 10 CFR 72.104, as clarified by ISG-13 1 stipulates that the licensee perform dose evaluations which establish that any real individual beyond the controlled area boundary not sustain a dose equivalent in excess of 0.25 mSv (25 mrem/year) due to direct radiation from the Independent Spent Fuel Storage Installation and other fuel cycle operations in the area. This same dose limit is stipulated by the EPA for the fuel cycle in 40 CFR 190.1 0(a). Also operational restrictions for ALARA and limits for effluents must be established.

In accordance with these requirements, Duke Energy Corporation has performed dose calculations that model the characteristics (initial enrichment, burnup and cooling time) of existing fuel in Phases I - VI, together with the characteristics of assumed "design basis" fuel for canisters in Phase VII and Phase VIII of the Oconee ISFSl 2

• Calculation OSC-86753 develops the radiation source terms used in subsequent shielding and skyshine calculations using the SCALE Code System. More specifically, the SAS2 Module of the SCALE Code System 4 was used to create a problem-dependent pin-cell model for the purpose of building cell-weighted, multigroup cross section sets for use in subsequent depletion calculations. The ORIGEN-S Module5 of the SCALE Code System was used to perform the fuel depletion and characterization calculations using the cross section sets created by SAS2. These characterization calculations yielded the photon and neutron source terms to be used as input to subsequent shielding calculations. As mentioned above, problem-dependent cross section sets were developed for these analyses since ORIGEN-S was used within the SAS2 sequence. Duke Energy Corporation Radiological Engineering is experienced in the use of the SCALE Code System, and the SCALE Code System is installed and maintained under the purview of the pertinent software and data quality assurance program.

The results of the radiation source term calculation were used as input to Calculation OSC-87066 to evaluate the shielding characteristics of a single Horizontal Storage Module. The MCNP Monte Carlo particle transport computer code 7 was used to perform the transport calculations and to write a surface flux file for use in subsequent skyshine calculations.

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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Appropriate software quality controls have been implemented for the computer codes and data used in these analyses (specifically, Calculation DPC-1201.30-00-00108 contains the verification and validation for MCNP5, while SDQA-30269-NGO9 documents the quality control measures in place for MCNP5).

6.2.2 §72.104(b) - Operational Restrictions Operational restrictions must be established to meet ALARA objectives for direct radiation levels associated with ISFSI.

Calculation OSC-8716 10 , Table 34.1-1, summarizes dose rate versus distance, showing a dose rate of 10.80 mRem per year at 500 meters, which is the longest distance at which results converge. The closest residence to the ISFSI is in the SW-SSW direction approximately 1 mile (-1600 meters) from the ISFSI, or 1.36 miles from the centerline of the site. 11 This is conservatively farther than the distance used for computation of dose rates. The 2016 40CFR190 Uranium Fuel Cycle Dose Calculation Results for the ONS site show a maximum total body dose of less than 1 mrem per year (last reported dose was 0.268 mrem 12 ). The total dose rate from all operations to the nearest real individual is therefore less than 12 mRem per year.

This calculation need not consider any effluent from Phase VIII. The Phase VIII HSMs use the NUHOMS-24PTH-S-LC DSCs, which are designed as "leak-tight." Per Appendix P, Section P.11.2.8 of the NUHOMS FSAR 13 , accidental releases are not credible.

6.2.3 §72.104(c) - Operational Limits Operational limits must be established for direct radiation levels associated with ISFSI to meet the limits given in 72.104(a).

The ISFSI is sited in such a way that direct radiation to the surroundings are minimized.

The station Radiation Protection Program limits for ISFSI boundary dose rates are established to maintain dose rates surrounding the ISFSI and at the owner control fence.

Calculation OSC-8716 10 uses the surface flux files developed in OSC-87066 in a repeating array. A skyshine calculation is performed to obtain near- and far-field dose results the Oconee ISFSI. This calculation need not consider any effluent from Phase VIII. The Phase VIII HSMs use the NUHOMS-24PTH-S-LC DSCs, which are designed as "leak-tight." Per Appendix P, Section P.11.2.8 of the NUHOMS FSAR13 , accidental releases are not credible.

6.3 Regulatory Compliance/Conclusion The evaluation summarized above demonstrates that Duke Energy meets the requirements of 10 CFR 72.212(b)(5)(iii) and 10 CFR 72.104 for the ONS ISFSI.

Page 6-6

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 6.4 References

1. United States Nuclear Regulatory Commission, Spent Fuel Project Office, Interim Staff Guidance - 13, "Real Individual."

2. "Design Basis" fuel (considering fuel burnup and initial enrichment) is assumed to reside in Phases VII-VIII of the Oconee ISFSI. The assumption of 5 years cooling time applies only to the most recent six dry storage casks, while the balance of the casks are assumed to have been loaded in increments of six dry storage canisters per year. This is consistent with reasonable engineering practice.

3. Calculation OSC-8675, "Oconee ISFSI Spent Fuel Radiation Source Terms," Revision 3.

4. 0. W. Hermann, C. V. Parks, "SAS2H: A Coupled One-Dimensional Depletion and Shielding Analysis Module," NUREG/CR-0200, Revision 6, Volume 1, Section S2, ORNLINUREG/CSD-2N21R6.

5. 0. W. Hermann, R. M. Westfall, "ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms," NUREG/CR-0200, Revision 6, Volume 2, Section F7, ORNLINUREG/CSD-2N21R6.

6. Calculation OSC-8706, "Oconee Horizontal Storage Module Shielding Evaluation," Revision 2.

7. LA-CP-03-0245, "MCNP - A General Monte Carlo N-Particle Transport Code, Version 5 (Volume 1: Overview and Theory, Volume II: User's Guide, Volume Ill: Developer's Guide).

8. Calculation DPC-1201.30-00-0010, Revision 0, "MCNP5 Computer Code Verification and Validation."

9. SDQA-30269-NGO, MCNP 5 Version 1.6

10. Calculation OSC-8716, "Oconee ISFSI Dose Rate Evaluations," Revision 2.

11. Dale E. Holden to Libby Wehrman, "2005 Oconee Annual Land Use Census," August 31, 2005, File No: OS-778.05 (Oconee Master File Record Retention No. 000377).

12. Thomas D. Ray to U.S. Nuclear Regulatory Commission, "2016 Annual Radioactive Effluent Release Report (ARERR)", May 1, 2017.

13. NUH-003, "Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel," Revision 14.

Page 6-7

Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 ATTACHMEN T 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 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 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, Oconee Nuclear Station monitored 63 wells in 2018. Tritium activity in wells GM-7R and GM-7DR was reported according to NEI 07-07, Industry Ground Water Protection Initiative, in February 2010. The probable source of this activity was determined to be discharges from the turbine building sumps to Chemical Treatment Pond #3 through the east yard drain. Discharges from the turbine building sump through this pathway were discontinued in 2008. Installation of a recovery well, currently RW-1, in 2011 has resulted in decreased tritium concentrations in well GM-7DR to below MDA.

Wells are typically sampled quarterly, semi-annually, or 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 2018. Results from sampling during 2018 confirmed existing knowledge of tritium concentrations in site ground water.

Results from sampling during 2018 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 Oconee Nuclear Station in 2018.

Key to below table.

Not scheduled to be sampled, not sampled due to insufficient NS volume in well, or well inaccessible during outage.

pCi/1 - picocuries per liter.

<MDA - less than minimum detectable activity, typically 250 pCi/1.

the Environmental Protection Agency drinking water standard for 20,000 pCi/I 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 pCi/I Concentration Limit for tritium.

Page 7-2

Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Well Tritium Concentration (pCi/I) #of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples A-1 ONS GWPI / A-1 / CTP 1/2 NS <MDA NS <MDA 2 A-10 ONS GWPI / A-10 I CTP 3 NS 301 NS 435 2 A-11 ONS GWPI / A-11 / CTP 3 NS <MDA NS <MDA 2 A-13 ONS GWPI / A-13 / CTP 1/2 NS 263 NS 323 2 A-14 ONS GWPI / A-14 / CTP 1/2 NS <MDA NS <MDA 2 A-2 ONS GWPI / A-2 / CTP 1/2 NS <MDA NS <MDA 2 BG-4 ONS GWPI / BG-4 / Ball Field NS <MDA NS <MDA 2 GM-10 ONS GWPI / GM-10 / 525 kv Sw Yard

<MDA <MDA <MDA <MDA 4 GM-10R ONS GWPI / GM-10R / 525 kv Sw Yard NS <MDA NS <MDA 2 GM-11 ONS GWPI / GM-11 / ONS Garage NS <MDA NS NS 1 GM-11R ONS GWPI / GM-11 R / ONS Garage NS <MDA NS NS 1 GM-12 ONS GWPI / GM-12 / E of Access Rd.

NS <MDA NS NS 1 GM-12R ONS GWPI / GM-12R / E of Access Rd.

NS <MDA NS NS 1 GM-13 ONS GWPI / GM-13 / 525 kv Sw Yard NS <MDA NS NS 1 GM-13R ONS GWPI / GM-13R / 525 kv Sw Yard NS <MDA NS NS 1 GM-14 ONS GWPI / GM-14 / Mnt. Trg. Facility NS <MDA NS <MDA 2 GM-14R ONS GWPI l GM-14R / Mnt. Trg. Facility NS <MDA NS <MDA 2 GM-15 ONS GWPI / GM-15 NS <MDA NS <MDA 2 GM-15R ONS GWPI / GM-15R NS <MDA NS NS 1 GM-16DDR ONS GWPI / GM-16DDR NS 355 NS NS 1 GM-16DR ONS GWPI / GM-16DR 6240 6080 5620 5730 4 GM-16R ONS GWPI / GM-16R NS 1250 1350 1150 3 GM-17DR ONS GWPI / GM-17DR 1780 1890 1810 1840 4 GM-17R ONS GWPI / GM-17R NS 1200 NS 1010 2 GM-18R ONS GWPI / GM-18R 4140 3800 3580 3580 4 GM-19 ONS GWPI / GM-19 1830 1820 1570 1630 4 GM-19R ONS GWPI / GM-19R 1470 1630 1520 1550 4 GM-1R ONS GWPI / GM-1R / CTP 1/2

<MDA <MDA <MDA <MDA 4 GM-20 ONS GWPI / GM-20 NS <MDA NS NS 1 GM-20R ONS GWPI / GM-20R NS <MDA NS NS 1 GM-21 ONS GWPI / GM-21 NS <MDA NS NS 1 GM-22 ONS GWPI / GM-22 NS <MDA NS NS 1 GM-23 ONS GWPI / GM-23 237 289 234 332 4 GM-24R ONS GWPI / GM-24R 1200 1380 1100 1040 4 GM-25R ONS GWPI / GM-25R 372 340 307 377 4 GM-2DR ONS GWPI / GM-2DR / U-1/2 SFP 233 <MDA <MDA 193 4 GM-2R ONS GWPI / GM-2R / U-1/2 SFP 1670 1910 1950 1190 4 GM-3DR ONS GWPI / GM-3DR / U-3 SFP NS 262 NS 301 2 GM-3R ONS GWPI / GM-3R / U-3 SFP 274 263 223 284 4 Page 7-3

Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Well Tritium Concentration (pCi/I) #of Location / Description 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples Name GM-4 ONS GWPI / GM-4 / Rad. Mat. WH 477 428 393 516 4 GM-5 ONS GWPI / GM-5 / Rdwst. Bldg. 220 <MDA 231 271 4 GM-SR ONS GWPI /GM-SR/ Rdwst. Bldg. NS <MDA NS <MDA 2 GM-6 ONS GWPI / GM-6 / Outflow to CTP-3 <MDA <MDA <MDA <MDA 4 GM-6R ONS GWPI / GM-6R / Outflow to CTP-3 NS <MDA NS <MDA 2 GM-7 ONS GWPI / GM-7 / 525 kv Sw Yard NS 221 NS 283 2 GM-7DR ONS GWPI / GM-7DR NS <MDA NS NS 1 GM-7R ONS GWPI / GM-7R / 525 kv Sw Yard 1260 1320 1020 1080 4 GM-8 ONS GWPI / GM-8 / E of U-3 TB 234 205 225 226 4 GM-BR ONS GWPI / GM-BR/ E of U-3 TB NS <MDA NS <MDA 2 GM-9 ONS GWPI / GM-9 / E of U-2 TB 317 379 284 284 4 GM-9R ONS GWPI / GM-9R / E of U-2 TB NS <MDA NS <MDA 2 MW-11 ONS GWPI / MW-11 / Landfill <MDA NS NS NS 1 MW-110 ONS GWPI / MW-110 / Landfill <MDA NS NS NS 1 MW-13 ONS GWPI / MW-13 / Landfill <MDA NS NS NS 1 MW-16 ONS GWPI / MW-16 / Landfill <MDA NS NS NS 1 MW-3R ONS GWPI / MW-3R / Landfill <MDA NS NS NS 1 MW-RP01 ONS GWPI / MW-RP01 / Landfarrn/Burial NS <MDA NS NS 1 MW-RP02 ONS GWPI / MW-RP02 / Landfarrn/Burial NS <MDA NS NS 1 MW-RP03 ONS GWPI / MW-RP03 / Landfarrn/Burial NS <MDA NS NS 1 Well Tritium Concentration (pCi/I) #of Location / Description 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples Name 011 ONS I 011 / Ball Field <MDA <MDA <MDA <MDA 4 013 ONS I 013 / WH 5 <MDA <MDA <MDA <MDA 4 015 ONS I 015 / Brown's Bottom <MDA <MDA <MDA <MDA 4 Well Tritium Concentration (pCi/I) # of Location / Description 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples Name RW-1 I 525 kv Sw. Yard T s31 T 600 I 440 I 399 l 4 Page 7-4

Attachment 8 Inoperable Equipment Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 ATTACH MENT 8 Inoperable Equipment This attachme nt includes an explanation of inoperable instruments related to effluent monitorin g in excess of allowed time defined by licensing bases and an explanation of 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 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station did not experience inoperable equipment relevant to effluent monitoring in excess of SLC limits during 2018.

Oconee Nuclear Station did not experience temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases) during 2018.

Page 8-2

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/201 8 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 Oconee Nuclear Station Units 1, 2, & ~

Period 1/1/2018 - 12/31/2018 ODCM Revision 59 ODCM Revision 59 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 below changes do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

ODCM Revision 59 was approved by the Radiation Protection Manager on October 9, 2018. Some changes reflected in ODCM Revision 59 were implemented prior to October 9, 2018 under a different change and approval process (e.g ., landuse census), and in those cases the implementation date is noted below.

Table of Contents Updated page numbers as necessary.

Section 4 - Page 7 Added 'Grass/Goat/Meat' Pathway and set Factor Used as 'D/Q (m-2 )' to W parameter in table for Doseoa formula per ORR 02209374.

Section 4 - Page 12, 15, 18, 21 Added reference EPRI Technical Report 1024827, Carbon-14 Dose Calculation Methods at Nuclear Power Plants, to 'p' factor description for all Roapi equations for Carbon-14.

Change made based on recommendation in ORR 02155454. Minor comments made by NRC during routine inspection at McGuire from review of ODCM to include all references used in development of ODCM parameters and methodologies.

Section 4 - Page 19 to 21 Updated description of parameter Ffi from :

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

to "Stable element transfer coefficient for nuclide i, in days/kg, from Table E-1 of Regulatory Guide 1. 109 for meat."

Editorial change made to correct units from days/liter to days/kg and remove "cow" label to match Table E-1 of Regulatory Guide 1.109 verbatim.

Section 4 - Page 23 to 25 Added Roapi equations and parameters for newly added Grass/Goat/Meat pathway per ORR 02209374.

Page 9-2

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018 Grass/Goat/Meat Formula: from NUREG-0133, pages 34 & 35. Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/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/uCi (10 6).

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

Uap Consumption rate of goat meat for age group a (kg/yr, from Regulatory Guide 1.109).

Adult - 110 Teen - 65 I

Child - 41 Infant - 0 r Fraction of deposited activity retained on goat's feed grass (from Regulatory Guide 1.109).

1.0 for radioiodine.

0.2 for particulates.

Yp Agricultural productivity by unit area of pasture feed grass (0.7 kg/m 2, from Regulatory Guide 1.109).

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

Ai Nuclide decay constant for nuclide i (sec*1).

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

(DFLoi)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).

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

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

fs Fraction of the go~t feed that is pasture grass while the goat is on pasture (1.0, from Regulatorv Guide 1.109).

tr Transport time from pasture to receptor ( 1. 73E+06 seconds, from ReQUlatorv Guide 1.109).

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

Page 9-3

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018 Grass/Goat/Meat - Tritium Formula: from NUREG-0133, page 35.

Where:

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

K' Units conversion factor pCi/µCi (10 6).

K"' Units conversion factor gm/kg (10 5 ).

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

Uap 1.0 Consumption rate of goat meat for age group a (kg/yr, from Regulatory Guide 1.109).

2.0 Adult - 110 Teen-65 Child - 41 Infant-0 (DFLoi)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 (mrern/pCi).

Ffi Stable element transfer coefficient for nuclide i, in days/kg, from Table E-1 of Regulatory Guide 1.109 for 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 grn/m\ from Regulatory Guide 1.109).

Page 9-4

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Grass/Goat/Meat - Carbon-14 Formula: from NUREG-0133, page 35 and Regulatory Guide 1.109, page 26.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/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 (10 6).

' K"' Units conversion factor gm/kg (l0j). '

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

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

Uaµ 3.0 Consumption rate of goat meat for age group a (kg/yr) (from Regulatory Guide 1.109).

4.0 Adult-110 5.0 Teen-65 Child-41 Infant-0 (DFLoi)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 0.35, 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; EPRI TR-1024827, "Carbon-14 Dose Calculation Methods atNuclear Power Plants", 2012, Section 3.2.5).

f1 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.

Page 9-5

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Section 6 - Page 3 Remove TLD Site # 047 from Table 6.0-2 and add 092 as replacement with Location "Hilton Circle stop sign, HWY 188", Distance 3.62 miles, Sector WSW. Change made per ORR 02216696 because TLD 047 was located in bushes/shrubs on private property and can no longer be accessed safely. New TLD 092 is in more suitable location.

Section 6 - Page 5 Updated Figure 6.0-1 to reflect standardization to legend descriptions. No changes to sampling locations.

Section 6 - Page 6 Updated Figure 6.0-2 to reflect removing TLD 047 and replacing with 092. Also standardized legend descriptions.

Change made per ORR 02216696 because TLD 047 was located in bushes/shrubs on private property and can no longer be accessed safely. New TLD 092 is in more suitable location.

Appendix C, D, E, and F Added dose factors for Se-75, Ag-108m, Sn-113, Sn-117m, Sb-124, Sb-125, Sb-126, Te- 123m, Ba-133, and Eu-152 to Appendix C, D, E, and F for all age groups and applicable pathways per ORR 02195642. Assessment of l l Oconee Count Room determined not all radionuclides listed on liquid waste release permits have dose factors in the ODCM. Dose factors developed using method described in CSD-RP-ALL-0028.

Appendix G, H, and I Added tables for Adult, Teen, and Child Grass/Goat/Meat pathway dose factors to Appendix G, H, and I respectively per ORR 02209374. Dose factors developed using method described in CSD-RP-ALL-0029.

Radiological Effluent Controls (SLC 16.11)

The Oconee Nuclear Station Radiological Effluent Controls are contained in SLC 16.11 and are included in this section. SLC 16.11 was not revised in 2018.

Page 9-6

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

£ 'J DUKE

~ ENERGY.

Oconee Nuclear Station Units 1, 2 and 3 ODCM Offsite Dose Calculation Manual Page 9-7

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 e1_., ouKE

~ ENERGY.

Oconee Nuclear Station Units 1, 2 and 3 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Prepared By:

9/27/2018 Christopher C. Courtenay Fleet Scientific Services RP Signature , Date Reviewed By:

Douglas J. Berkshire ONS Radiation Protection Approved By:

Lagrone D. Robinson ONS Radiation Protection Manager Signature Revision 59 Page 9-8

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12 /31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

TABLE OF CONTENTS Executive Summary. Executive Summary-I 1.0 Radwaste Systems 1-1 1.0.1 Liquid Radwaste Processing 1-1 1.0.2 Gaseous Radwaste Processing 1-3 2.0 Release Rate Calculations 2-1 2.0.1 Liquid Release Rate Limit Calculations 2-1 2.0.1.1 Liquid Radwaste Effluent Line Release Rate Limit Calculation 2-1 2.0.1.2 #3 Chemical Treatment Pond Effluent Line Discharge 2-2 2.0.2 Gaseous Release Rate Limit Calculations . 2-5 2.0.2.1 Unit Vent Discharge Release Rate Limit Calculation 2-5 3.0 Setpoint Calculations . 3-1 3.0.1 Liquid Radiation Monitor Setpoint Calculations' 3-1 3.0.2 Gaseous Radiation Monitor Setpciint Calculations 3-5 3.0.2.1 Unit Vents Setpoints (RIA-45 and RlA-46) 3-7 3.0.2.2 Radwaste Facility Setpoints (4RlA-45) 3-10 3.0.2.3 Interim Radwaste Building Setpoints (RIA-53) 3-11 3.0.2.4 Waste Gas Decay Tank Setpoints (RIA-37 and RlA-38) . 3-11 4.0 Effiuent 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 . 4-6 4.0.3 Direct Radiation 4-25 4.0.4 Effluent Apportionment 4-25 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 6-1 6.0.3 Oconee Meteorology: Relative Air Concentrations and Deposition 6-8 6.0.3.1 XOQDOQ Methodology and Assumptions 6-8 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 Page 9-9

Attachmerit 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2 , & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Appendices Appendix A: Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases A-1 Appendix B: Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations . B-1 Appendix C: Ai Adult Dose Factors for use in the Liquid Dose Calculations C-1 Appendix D: Ai Teen Dose Factors for use in the Liquid Dose Calculations D-1 Appendix E: Ai Child Dose Factors for use in the Liquid Dose Calculations E-1 Appendix F: Ai Infant Dose Factors for use in the Liquid Dose Calculations F-1 Appendix G: Ri Adult Dose Factors for use in the Gaseous Dose Calculations G-1 Appendix H: Ri Teen Dose Factors for use in the Gaseous Dose Calculations H-1 Appendix I: Ri Child Dose Factors for use in the Gaseous Dose Calculations I-1 Appendix J: Ri 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 (4 pages). 1-4 2.0-1 Liquid Radwaste Discharge Locations 2-4

• 6.-0-1 Sampling Locations Map (Site Boundary). 6-5 6.0-2 Sampling Locations Map (Ten Mile Radius) 6-6 6.0-3 Land Use Census Map (Deleted). 6-7 LIST OF TABLES 3.0-1 RIA-33 Cs-137 Equivalents. 3-4 3.0-2 Xe-133 Equivalents . 3-11 6.0-1 Sampling Locations. 6-2 6.0-2 TLD Sites 6-3 6.0-3 Land Use Census Results (Deleted) . . 6-4 6.0-4 Terrain Heights Above ONS Yard Grade Elevation (m) 6-9 6.0-5 ONS Atmospheric Stability Frequency (1988 - 1992) 6-10 6.0-6 ONS Frequency of Wind Direction and Speed (1988 - 1992) 6-10 6.0-7 ONS Limiting x/Q and D/Q Values (1988-1992) 6-11 6.0-8 ONS Delta-T Ranges per Vertical Separation Distances 6-11 6.0-9 Oconee Semi-Elevated x/Q and D/Q Average Values (1988-1992) 6-12 6.0-10 Oconee Ground Level x/Q and D/Q Average Values (1988-1992) 6-14 Page 9- 10

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

EXECUTIVE

SUMMARY

The Oconee Nuclear Station (ONS) 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(b), SLC 16.11.l(a));

(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(d), SLC 16.11.l(b));

(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(g),

SLC 16.11.2(a));

(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(h and i), SLC 16.11.2(b));

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(j), SLC 16.11.7).

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 demonstrate compliance with 10CFR20 0.1-rem annual dose limit.

Executive Summary - Page 1 Page 9-11

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Kuclear Station Offsite Dose Calculation Manual (ODCM) 1l1e ODCM also provides the methodology and parameters to be used in the calculation of radioactive liquid and gaseous etlluent monitoring instrumentation alannitrip setpoints to assure compliance with the concentration and dose rate limitations of the SLCs and Tedmical Specifkations. Sofiware implementing l\l.JREG-0133 methodology is used for the calculation of off.site doses, but the ODCM also provides a method for the calculation of offsite doses when the software is not available 1l1e ODCM has heen prepared a<; generically as possible in order to minimize the need for revisions. Any changes to the methodology and parameters to be used in this ODC~{

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 he submitted to the Nuclear Regulatory Commission in accordance with the SLCs and Tcclmical Specifications.

TI1e ODCM does not replace any station implementing procedures. Programmatic controls for radioactive etlluents and radiological environmental monitoring are contained in the Administrative Controls chapter of the Teclmical Specifications.

Procedural details for radioactive effluent<; 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 ofthe SLCs.

E~ccutive Summary - Pnge 2 Page 9-12

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) 1.0 RADWASTE SYSTEMS 1.0.l LIQUID RADWASTE PROCESSING The liquid radwaste system at Oconee Nuclear Station is used to collect and treat liquid chemical and radiochemical byproducts of unit operation. The system produces effiuents that are discharged in small, dilute quantities to the environment. The means of treatment vary with waste type and desired product in the various systems:

(A) Filtration - Waste sources are filtered prior to processing as necessary.

(B) Ion Exchange - Ion exchange is used to remove radioactive ions from solution. Also, ion exchange is normally used in removing cations (cobalt, cesium, manganese) and anions (chloride, fluoride) from the filtrate in order to purify the filtrate for release.

(C) Gas Stripping - Removal of gaseous radioactive fission products is accomplished through venting of atmospheric holdup tanks.

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

Section I - Page I Page 9-13

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Figure 1.0-1 Oconee Nuclear Station Liquid Radwaste System Section l - Page 2 Page 9-14

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) 1.0.2 GASEOUS RADWASTE PROCESSING The purpose of the gaseous waste disposal system is to:

(1) Maintain a non-oxidizing cover gas of nitrogen in tanks and equipment that contain potentially radioactive gas; (2) Hold up radioactive gas for decay; and (3) Release gases (radioactive and non-radioactive) to the atmosphere under controlled conditions.

During power operation of the facilities, radioactive materials released to the atmosphere in gaseous effluents include low concentrations of fission product noble gases (krypton and xenon), halogens (mostly iodines), tritium contained in water vapor, and particulate material including both fission products and activated corrosion products.

The primary source of gaseous radioactive wastes is from the degassing of the primary coolant during letdown of the cooling water into various holding tanks. Additional sources of gaseous waste activity include the auxiliary building exhaust, spent fuel area exhaust, the discharge from the steam jet air ejectors, and purging and venting of the reactor containment building. Some low radioactivity secondary system steam releases can occur at the site such as from infrequent lifts of the main steam relief valves and testing of the main steam manual atmospheric dump valves. Secondary side steam releases are reviewed for inclusion in the site effluent total.

All components that can contain potentially radioactive gases are vented to a vent header.

The vent gases are subsequently drawn from this header by one of four waste gas compressors or a waste gas exhauster. TI1e waste gas compressor discharges through a waste gas separator to one of seven waste gas tanks. The waste gas tanks and the waste gas exhauster discharge to the unit vent after passing through a filter bank consisting of a prefilter, an absolute filter, and a charcoal filter.

Radioactive gases may be released inside the reactor containment building when components of the primary system are opened to the building atmosphere for operational reasons or where mi.nor leaks occur in the primary system. Prior to access, the reactor contaimnent atmosphere will be monitored for radioactivity and, when necessary, purged through prefilters, high-efficiency particulate air (HEP A) filters, and charcoal filters, and released to the atmosphere through the unit vent. The purge equipment is sized for a flow rate of 50,000 cfm providing approximately 1.5 air changes per hour in the reactor building. Units 1, 2, and 3 have a separate vent stack which services each unit.

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

Section I - Page 3 Page 9-15

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Kuclear Station Offsite Dose Calculation Manual (ODCM)

Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 1 of 4 r ~

Ut.111 VE'IIT UllllT 1 LNIT l 8o 2 GAS HEHDER (fR[JM RE.HCTCft

oot..AHT S"Src*-15) 1-tEIGl-tT WCI FT

=

~

PAESSOFI I TD _rau10

. wmF SVSTFM GAS rrl(JN sr:AM Gc:Nrn~TO" tuac LCA<

Ml.L Ill-' _I:. PUllLJAKY STATlOI\ r.Rni ltln BU[LD[IIC: LDC:~Tl[)JS Lfl/'EL Sect ion 1 - Pnge 4 Page 9-16

• • Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Ocone~ Kuclear Station Offsite Dose C<Jlculation lvlanual (ODCM)

Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 2 of 4 um- 2 c* *~ocH::;cP.

rOR EJECTO'l 3TEl'.:M Sf!:TEM GtiS F'-!Cl-1 STEAM jENERATOR TIJBE LEt:K

-Q

~Ll)(JLJ~RY 8UILCJING VENT MUL HPL::: AUXllIARY ------i ' ~TATlO~J GnoutJO BUILDl~lG LOCtlTIOHS ~ LCV[_

Section 1 - Page 5 Page 9-17

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Kuclear Station Offsite DoSc Calculation Manual (ODCM)

Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page3 of'4 UNIT VENT 1-E]t;IT ;!00 FT 11\UL TIPLE 1<1!1 JLli:.ftY STA-lmJ GAClllNA 81.lLOJt<iClLITr E:(~UST

=

=

Sect ion 1 - P11gc 7 Page 9-19

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee 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 Oconee; (1) the liquid radwaste effluent line to the Keowee Hydroelectric Unit Tailrace, and (2) the #3 Chemical Treatment Pond effluent line to the Keowee River (See Figure 2.0-1).

2.0. 1.1 LIQUID RADWASTE EFFLUENT LINE RELEASE RA TE LIMIT CALCULATION Liquid releases to the Keowee Hydroelectric Unit Tailrace nonnally contain the radioactive releases from the site including effluents from the Waste Monitor Tanks, Recycle Monitor Tanks, and Decant Monitor. Tank. The Keowee Tailrace discharge point can also contain Turbine Building Sump Monitor Tank (TBSMT) releases, however TBS MT effluent normally contains very low (if any) activity, and, therefore is transferred to the #3 Chemical Treatment Pond prior to release. Dilution flow for the liquid radwaste effluent line is provided by the Keowee Hydroelectric Unit and the Keowee Hydro Fire Protection liquid waste release mixing line. For purposes of the release rate calculation, Keowee hydro dilution flow is assumed to be a minimum leakage flow of 38 cfs, and a maximum flow of 6600 cfs based on one hydro unit operating at 50% power. The Keowee Hydro Fire Protection liquid waste release mixing line provides an additional 38 cfs dilution flow. Since Keowee Hydro typically releases only a small percentage of time during the year, 76 cfs (38 cfs leakage + 38 cfs mixing line) is normally assumed for dilution flow when performing liquid release rate calculations.

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/nll for dissolved and entrained noble gases, the following release rate limit calculation shall be performed for liquid releases to the Keowee Hydro Tailrace via the liquid radwaste effluent line:

f ~ (F + (DF-1)) Condition: DF > 1.0 Equation 2.1 where:

f the undiluted effluent flow, in gpm.

Section 2 - Page I Page 9-20

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Kuclear Station Offsite Dose Calculation lvfanual (ODCM)

F the dilution flow available, in gpm.

nommlly 3.41E+04 gpm (76 cfa. based on a leakage rate of 38 cfs ( 19 cfs per Keowee Hydro m1it), plus the Keowee Hydro Fire Protection liquid waste release mixing line whose flow rate is 38 cfa When Keowee Hydro enters an outage one of the two unit5 is taken offline which temporarily reduces the amount of leakage by half. Therefore, during a Keowee Hydro outage the dilution flow is assumed to be 57 cfa (19 cfa leakage plus 38 cfs raw water. (2.56E+04 gpm)).

or 2.%E+06 gpm (6600 cfs, based on one hydro unit operating at 50%, power).

Tius value is only used if it is known that Keowee Hydro is discharging.

JJF required dilution factor to be applied to the undiluted eft1uent tlow. unitless.

JJF = (J' X I: c Equation 2.2

, (10 xEC.)

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 release rate is calculated using Equation 2.1. Equation 2.1 is used only when DF > 1.0.

cr the most restrictive recirculation factor at equilibrium, (dimensionless). Tue recirculation factor accounts for the fraction of discharged water reused by the station. This value equals 1.0 since discharged liquid etlluent is not reused at Oconee.

C; the concentrntion of radionuclide, 'i', in the undiluted liquid dlluent, in itCilml.

EC; the concentration of radionuclide. 'i', from 10CFR20, Appendix B. Table 2.

Column 2, in itCi/ml. Note: if radionuclide. 'i', is a dissolved noble ga~, then EC;

= 2.00E-05 µCi/ml.

Once the maximum release rate, f, is calculated the value 1s multiplied by 0.8 for additional conservatism.

Section 2 - Page 2 Page 9-21

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) 2.0.l.2 #3 CHEl\illCAL TREATMENT POND EFFLUENT LINE DISCHARGE The #3 Chemical Treatment Pond (CTP) effiuent line is the release point for station effluents that are nonnally considered to be non-radioactive; that is, the pond's effiuent will not normally contain measurable activity above background with the exception of very low tritium activity. Tritium releases from the #3 CTP typically account for much less than 1% of the station total tritium release. It is assumed that no activity is present in the effluent until indicated by radiation monitoring measurements on the pond's inputs and/or by periodic analyses of the composite sample collected at the pond's discharge point. Inputs to this pond include the station's yard drain system, #1 CTP discharge, #2 CTP discharge, recovery well water, the decant water from the Powdex system, and the discharge from the Turbine Building Sump/TBSMT system whose contents have been determined to be below lOEC. h1puts that have radiation monitors associated with them will be set to assure that Selected Licensee Commitment 16.11-1 will not be exceeded.

1. 3 CTP. is a continuous release path that discharges to the Keowee River (see Figure 2.0-1).

The #3 CTP may also be the discharge path for large volumes of slightly contaminated water following a primary-to-secondary leak so long as administrative procedures are implemented to assure that release rate calculations similar to that used in Section 2.0.1.1 are performed, that all detectable radionuclides will be accounted for, and that no station limits will be exceeded.

Section 2 - Page 3 Page 9-22

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station OfTsite Dose Calculation Manual (ODCl'vf)

Figure 2.0-1 Liquid Radwaste Discharge Locations Oconee Nuclear Station Figure 2.0-1 Liquid Radwaste Discharge Locations Lake Keowee Visitors Center ccw...,__

O,scharge r- ~eowee/"")

Keowe~ce Release Point Dam

\

j

\J Llqu,d

'l l;:.3

Effluent Intake Release to CTP-3

\

I N

&-ction 2 - Page -t Page 9-23

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) 2.0.2 GASEOUS RELEASE RA TE LIMIT CALCULATIONS 111e three unit vents are the primary gaseous radioactive release points at Oconee. The unit vents are the semi-elevated release points for waste gas decay tanks, containment building purges, auxiliary building ventilation, spent fuel pool ventilation, and the condenser air ejector (see Figure 1.0-2, pages 1, 2, and 3). Each unit vent contains multi-range radiation monitors (RIAs) and flow rate measuring instrumentation.

There are three other separate gaseous effluent release points at Oconee; the Hot Machine Shop, Interim Radwaste Building and Radwaste Facility that are normally considered non-radioactive; that is, it is possible but unlikely that the effluent will contain measurable activity above background. Each of these release points are considered ground-level, and each has an effluent sampler and flow monitoring device (see Figure 1.0-2, page 4). In addition, the Interim Radwaste Building and Radwaste Facility have a RIA.

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 lin1ited to: :5 500 mrem/yr to the total body, and :5 3000 mrem/yr to the skin for the noble gases, and is limited to :5 1500 mrem/yr to any organ for radioiodine and for radioactive materials in particulate fonn, 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. When applied to the individual release points the site dose rate values are apportioned 1/3 to each unit vent.

a. Noble Gases Total Body:

~( K; x & Q,)x < 500mrem/yr Equation 2.3 Skin:

~( (L + 1.1.M";) x & Q, )

x < 3000 mrem/yr Equation 2.4 Section 2 - Page 5 Page 9-24

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Kuclear Station Offsite DoSe Calculation Manual (ODCM)

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

L L(Poo* x 1V x Q, x E,) < 1500mrem/yr p

To include both the food and ground organ dose and the inhalation organ dose the equation can be expanded to:

L L ({(Pep, ftoocvgr x Wo; Q + (?.,,. )nhal x W.c, e} x Q, x E,) < 1500 mrem/yr r

Equation 2.5 where:

Ki = the total body dose factor due to gamma emissions for each identified noble gas radionut lide, 'i', in mrem/yr per ,uCi!m 3 (See Appendix A).

L, the skin dose factor due to beta emissions for each identified noble gas radionuclide, 'i', in mrem/yr per ,uCi/m 3 (See Appendix A).

M; the air dose factor due to gamma emissions for each identified noble ga~

radionuclide, 'i', in mradiyr per µCi/m3 (See Appendix A).

1.1 ratio to conve11 dose (mrad) to dose equivalent (mrem).

I' opi the dose parameter for radionuclides other than noble gases for the :inhalation pathway, in mrem/yr per itCilm 3 and for the food and ground plane pathways in (m 2 x (mrcm/yr per µCiisec)) for organ, *o', and radionuclide. *j*, (Sec Appendix B for the pathway spe.:i1fo dose L:ommilmenl factors). Nole:

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

z!Q the highest calculated annual average dispersion parameter for any area at or beyond the site boundary in sec/m3. For the Oconee Unit Vents this value is l.672E-6 seclni3. The location is the SW s.x:tor at 1.0 mile for semi-elevated releases. For the Hot Machine Shop. Interim Radwaste Building and Radwaste Facility this value is 7.308E-6 sec/m 3* The location is the SE sector at 1.0 mile for ground-level releases. A.s discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing ga~eous effluent relea~e limits is the exclusion area boundary (E.->\B). 'lbe EAB is defined a~ a 1 mile raditl~ from the station center.

1-V the highest calculated annual average dispersion or deposition parameter for estimating the ma.ximum dose rate to an individual from the total inhalation, food, and ground plane pathways resulting from semi-elevated releases or ground-level rdeases:

Section 2 - Page 6 Page 9-25

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Ocone~ Kuclear Station Offsite Dose Calculation Manual (ODCM) r,vz(Qs, l.672E-6 sec/m3, for the inhalation pathway and the airborne H-3 food pathway. 111e location is the SW sector at L.0 mile for semi-elevated releases.

l.295E-8 m-2, for the food and ground plane pathways. 111e location is the NE sector at 1.0 mile for semi-elevated releases.

7.308E-6 sec/m3, for the inhalation pathway and the airborne 11-3 food pathway. The location is the SE sector at 1.0 mile for ground-level releases.

2.259E-8 m-2, for the food and ground plane pathways. 111e location is the NE sector at 1.0 mile for ground-level relea~es.

E; - the filter removal factor for radionuclide, 'i *, e.g., for 99% removal£; - 0.01.

For iodine removal by charcoal adsorbers E; = 0.1.

For particulate removal by HEPA fi\ters E 1 = 0.01.

Q; the relea~e rate of radionuclide, *r, in gaseous eflluent from all release points at the site, in µCi/sec.

Q, = kiC,f + b = 472 x Cf Equation 2.6 where:

C; - the concentration of radionuclide_ 'i-, in undiluted gaseous effluent. in µCi/ml.

f the undiluted eftluent tlow, in ft 3/min.

k1 conversion factor, 2.83E+04 cc/ft 3

• k2 conY.:rsion factor, 60 s.:c/min.

Substituting the expression for Q; 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 j;h < - - - - - - - - -

472 x z!Q x I(K, x c.)

I Sect ion 2 - Page 7 Page 9-26

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Kuclear Station Offsite DoSe Calculation l\llanual (ODCM)

Noble Gases* Skin Maximum Release Rate:

fk < 3000 472 x x/ Q x ~::[(L. + 1.1.Af,) x c]

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

fi 1500 or < 472 x L L({(Po;i )j:>vd!g, x WntQ + (Pop, ).,,,ai x w.,Q} x E, x c) p i f,b, [sk, and [o,, are calculate<l for each batch prior to release. The most limiting gaseous release rate is used to a~sure that no instantaneous dose rate limit is exceeded.

Once the maximum release_ rate, f, is 'calculated the value is multiplied by 0.8 for additional conservatism.

Sect ion 2 - Pogo 8 Page 9-27

Attadhment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

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

Inhalation Pathway - Child Age Group P .

opz

= K'(BR)(DFA01.)

Formula: from NUREG-0133, page 25.

Where:

Popi Dose commitment factor for Child age group, organ o, nuclide i, for the inhalation pathway (mrem/yr per µCilm\ (See Appendi~ B for the pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (10 6) .

BR Breathing rate for the Child age group (m,/yr, from Regulatory Guide 1.109):

Child - 3700 DFAo; 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 9 Page 9-28

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) 3.0 SETPOINT CALCULATIONS 3.0.1 LIQUID RADIATION MONITOR SETPOINT CALCULATIONS As shown on Figure 1.0-1, RIA-33 is the controlling radiation monitor for liquid batch releases at Oconee. Once the liquid release rate parameters have been established radiation monitor setpoints shall be calculated to assure that the concentration of radioactive liquid eflluents released from the site to the unrestricted area is limited to ten times the eflluent 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 eflluent concentration, Ci, and accounting for the monitor background reading, the liquid radiation monitor setpoint can be readily obtained by multiplying C; by the radiation monitor correlation factor, CFi, as follows: *

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

C, ~ ~-~~~--~ Equation 3.1 o- x f SP ~ L (e, X CF,) + bkg Equation 3.2 where:

C; the maximum allowable concentration ofradionuclide, 'i', in the undiluted liquid eflluent, in µCi/ml.

SP radiation monitor setpoint, in cpm.

CF; = radiation monitor correlation factor for radionuclide, 'i', in cpm/µCi/ml, e.g.,

8.00E+07 cpm/µCi/ml (Cs-137) for RIA-33.

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

All other parameters were previously defined.

Using conservative or "worst-case" paran1eters 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 #3 CTP release point. However, for batch releases, e.g. ,

waste monitor tanks, through the liquid radwaste eflluent line to the Keowee hydro Section 3 - Page I Page 9-29

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Kuclear Station Offsite Dose Calculation Manual (ODCM) tailrace the RIA-33 radiation monitor setpoints are calculated ba~ed on tlte actual expected activity in the release as follows:

First the "Com:lation Concentration" (C CONC) is cakulat.:d:

CCONC = L (c, X EQ,)

where :

C; = Undiluted liquid effluent concentration for each isotope. excluding tritium,

~tCi/ml.

EQ; = RIA-33 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 Tabie 3.0-1)

Next the RIA-33 setpoints are determined as follows:

If C CONC is > 9.0E-6 µCi.Im) then three setpoint values are calculated. TI1e actual "expected count rate for the release is defined as the "Midpoint of Expected Range".

The "Alert" setpoint is defined as 1.5 times the expected counts from activity in the liquid effluent plus background. If the "Alert"' setpoint is exceeded, but there is no upward trend, the release will be allowed to continue. If RIA-33 continues to trend upward then the release will be manually terminated. The "Upper Limit of Expected Range" is defined as 3 times the expected counts from activity in the liquid eflluent plus background. Tite "Upper Limit of Expected Range" is called the "Trip" setpoint. Iftl1e "Trip"' setpoint is exceeded the release will be automatically terminated. The Lower Limit of Expected Range" is defmed as 3 times lower than the expected counts from activity in the liquid efiluent plus background. The "Lower Limit of Expect.:d Range"'

provides assurance that the correct liquid effluent is being released. If the RIA-33 count rate does not increase to at least the "Lower Limit of the Expected Range" then the release will be tenninated. and a new sample analysis will be perfom1ed. TI1e four RIA-33 setpoints are calculated as follows:

Lower Limit of Expected Range - C CONC ;,.: (8.00E7l3) cpm/(~tCi/ml) +

RIA-33 BKG Midpoint of Expected Range = C CONC " 8.00E7 cpm/(~tCi/ml) +

RIA-33 BKG Alert Setpoint = C CONC ,: (8.00E7xl.5) cpm/(~tCi/ml) +

RIA-33 BKG Upper Limit of Expected Range = C CONC )< (8.00E7 ~3) cpm/(µCi!ml) +

(Trip Setpoint) RIA-33 BKG Seel ion 3 - Puge 2 Page 9-30

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018 Oconee Kuclear Station Offsite DoSe Calculation :Manual (ODCM)

IfC CONC is::; 9.0E-6 ~tCi!ml then the RV\-33 setpoint is 2.16E3 cpm (9.0E-6 , 8.00E7 x 3) plus background (DKG) as the "Upper Limit of Expected Range". l11is setpoint is used for low activity releases, and is based on limiting the concentration in the effluent to 10 times the 10CFR20 EC of Cs-134 which has the lowest efiluent concentration value (9.0E-7 ~tCi/ml) for any detectable radionuclide in the effluent. Similarly, the RIA-33 "Alert setpoint for low activity releases is l.08E3 cpm (9.0E-6 x 8.00E7 > 1.5) plus background (8KG).

As shown in Figure 1.0-1, Turbine Building Sump (TBS) discharg<! can be routed to either #3 CTP or to the Turbine Building Sump Monitor Tank (TBSMT). The TBS discharge is monitored by RIA-54 which is operated as a continuous sampler. Nonnally, TBS disdiarge is sent to 1/-1 CTP or 1/-2 CTP where the effiuenl is prol:essed if it l:ontains chemicals prior to being sent to #3 CTP. However, if RIA-54 trips on high radiation, then the TBS discharge is processed through the TBSMT where it can go to f;3 CTP via the yard drain'system ifit is< lOEC or be released through RIA-33 ifit is:;:. l0EC. RIA-'

54 alam1 setpoints are S<!t to provide an early warning of increased activity, and prevent TBS ettluent releases in excess of station regulatory release limits (i.e., lOEC). Setpoint calculations are based on a monitor correlation factor of 7.81E-9 µCiiml/cpm (Cs-137 equivalent) and a Cs-134 10CFR20 Etlluent Concentration of 9E-7 µCi/ml. Cs-134 is the most limiting radionuclide 10CFR20 Eflluent Concentration not known to be absent from the TBS cfllucnt. 111c Cs-134 10CFR20 EC value of 9E-7 ~tCi/ml is conservatively used as a Cs-137 l:Onl:enlralion since Cs-137 has a 10CFR20 EC value of IE-6 µCilml.

Setpoints are conservatively calculated using a rounded RIA-54 correlation factor of 8E-9

~tCi/ml/cpm. The Alert setpoint limit is set to 1/2 of the I0EC release limit, and is based upon ten times the EC value for Cs-134 as follows:

RIA-54 Alert Setpoint = Background+ 562 cpm; (i.e., 1/2 :~ 10 ,, 9E-7/8E-9 = 562).

Similarly. the Ahum setpoint limit is set to the IOEC release limit, and is based upon ten times the EC value for Cs-134 as follows:

RIA-54 Alann Setpoint - Background + 1125 cpm; (i.e., 10 ,._ 9E-7/8E 1125).

Section 3 - Pngc 3 Page 9-31

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Table 3.0-1 RIA-33 Cs-137 Equivalents Isotope Equivalence Isotope Equivalence Isotope Equivalence Factor Factor Factor Be-7 0.1462 Mo-99 0.2668 La-141 0.0155 F-18 0.5788 Tc-99m 0.00 La-142 0.2942 Na-24 0.8519 Tc-101 0.00 Ce-141 0.00 Cl-38 0.0090 Ru-103 1.3368 Ce-143 0.7826 K-40 0.1094 Ru-105 0.8783 Ce-144 0.0273 Cr-51 0.1438 Ru-106 0.4429 1-130 3.3095 Mn-54 1.0617 Ag-108m 3.4473 1-131 1.4051 Mn-56 0.4992 Ag- ll0m 3.5179 1-132 1.0259 Fe-59 1.0556 Cd-115 0.5201, 1-133 1.1857 Co-57 0.0022 Cd-115m 0.0235 1-134 0.1388 Co-58 1.4735 In-115m 0.3631 1-135 0.9374 Co-60 2.0495 Sb-122 0.9218 Ar-41 0.2229 Cu-64 0.3954 Sb-124 2.1617 Kr-85 0.0059 Ni-65 0.1591 Sb-125 1.1308 Kr-85m 0.4280 Zn-65 0.5584 Sb-126 5.1762 Kr-87 0.1213 Zn-69m 1.1391 Sn-113 0.9971 Kr-88 0.5278 Se-75 1.3092 Sn-123 0.0066 Kr-89 0.00 Br-80m 0.0860 Sn-126 0.00 Xe-131m 0.0167 Br-82 3.4691 Te-125m 0.00 Xe-133 0.0006 Br-83 0.0059 Te-127 0.0134 Xe-133m 0.1172 Br-84 0.0053 Te-127m 0.0001 Xe-135 0.8564 Br-85 0.00 Te-129 0.0138 Xe-135m 0.00 Rb-86 0.0894 Te-129m 0.0507 Xe-137 0.00 Rb-88 0.00 Te-131 0.0008 Xe-138 0.00 Rb-89 0.00 Te-13lm 1.8463 Nd-147 0.2619 Sr-89 0.0002 Te-132 0.9766 Hf-181 1.4209 Sr-91 0.6460 Te-134 0.0408 W-187 0.8027 Sr-92 0.3900 Cs-134 2.5804 Tl-208 0.00 Y-91 0.0031 Cs-136 3.1916 Bi-212 0.0144 Y-91m 0.0439 Cs-137 1.00 Bi-214 0.0003 Y-92 0.1334 Cs-138 0.0120 Pb-212 0.4497 Y-93 0.1091 Ba-133 1.3648 Pb-214 0.0020 Zr-95 1.0909 Ba-139 0.0203 Ra-226 0.0320 Zr-97 1.1210 Ba-140 0.5307 Ac-228 0.8261 Nb-95 1.0821 Ba-141 0.0002 Th-228 0.0038 Nb-95m 0.2919 Ba-142 0.00 Np-239 0.3996 Nb-97 0.1164 La-140 2.3237 Section 3 - Page 4 Page 9-32

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) 3.0.2 GASEOUS RADIATION MONITOR SETPOINT CALCULATIONS The unit vent radiation monitor setpoints are established at the Oconee Nuclear Station to help ensure that gaseous release rate limits are not exceeded. For some release pathways in which a specific RIA exists, the setpoints also help to ensure that the effluent being released is the same concentration as indicated by manual samples, e.g. effluent from waste gas decay tanks, thereby reducing the likelihood of releasing the wrong tank. For instances in which the RIA which normally controls the release is not operable, or is "out of service", independent manual samples (IMS) are collected and the noble gas constituents from both samples are compared to help ensure that the intended "batch" is being released. For certain low potential release types, e.g. Integrated Leak Rate Tests, no RIA exists to ensure that release rate limits are not exceeded or to ensure that the effluent being released is the "expected" concentration. For such pathways, independent manual samples are required to be collected and noble gas constituents compared prior to release. The following list defines th~ controlling RIA for the various gaseous effluent release types at Oconee:

• Pathway Controlling RIA Unit 1 "A" Waste Gas Decay Tank 1&2 RIA 37/38 Unit 1 "B" Waste Gas Decay Tank 1&2 RIA 37/38 Unit 1 "C" Waste Gas Decay Tank 1&2 RIA 37/38 Unit 1 "D" Waste Gas Decay Tank 1&2 RIA 37/38 Unit 3 "A" Waste Gas Decay Tank 3 RIA 37/38 Unit 3 "B" Waste Gas Decay Tank 3 RIA 37/38 Unit 3 "C" Waste Gas Decay Tank 3 RIA 37/38 Unit 1 Reactor Building Purge 1 RIA45/46 Unit 2 Reactor Building Purge 2 RIA45/46 Unit 3 Reactor Building Purge 3 RIA45/46 Unit 1 Depressurization IMS 1 RIA 45/46 Alarm Only Unit 2 Depressurization IMS 2 RIA 45/46 Alarm Only Unit 3 Depressurization IMS 3 RIA 45/46 Alarm Only Unit 1 Hydrogen Recombiner IMS 1 RIA 45/46 Alann Only Unit 2 Hydrogen Recombiner IMS 2 RIA 45/46 Alarm Only Unit 3 Hydrogen Recombiner IMS 3 RIA 45/46 Alarm Only Unit 1 Integrated Leak Rate Test IMS Unit 2 Integrated Leak Rate Test IMS Unit 3 Integrated Leak Rate Test IMS 111e following sections describe the methods by which setpoints are established. In general, gaseous radiation monitors are calibrated to Xe-133, and for continuous release points, e.g., the three 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:

Section 3 - Page 5 Page 9-33

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Kuclear Station Offsite Dos.: Calculation Manual (ODCM)

Note : when applied to the individual release points the 500 nu*em!year site dose rate value is apportioned 30% to each Unit Vent (RIA-45 and RIA-46) semi-elevated relea~e point.

The remaining 10% is allocated to the three ground-level release points, the Hot Machine Shop (no monitor). Interin1 Radwa<;te Building (RIA-53) and Radwaste Fadlity (4RIA-45) that are normally considered non-radioactive. Recall from Section 2.0.2. l the following equation:

Kx,- m x z IQ x Qx,-1JJ < 500 mrem/yr Solve for Qx,-m:

500 QY,-J" < - - - - - - Equation 3.4 Kx, - l3J X X i Q F~om Equation 2.6:

Qx,-133 :: 472 X C.Ye-133 X f Equation 3.5 Substitute Equation 3.5 into Equation 3.4:

472 x Cx,-m x f < 500 K.1>-133 X 7./Q Solve for Cx,-133:

500 CAi:-l3J < ---------

472 X f X Kx,-133 X xiQ SP= Cx,-m + bkg Equation 3.6 CF where :

Kx,-133 2.94E+02. the total body dose fa-:tor due to gamma emissions for Xe-133, in mrem/year per µCi/m 3 (See Appendix A).

1JQ the highest calculated semi-elevated annual average dispersion parameter for any area at or beyond the site boundary in sec/m 3* For Oconee this value is l.672E-6 sec/m 3* TI1e location is the SW sector at 1.0 mile.

Qx,-1n Xe-133 equi,*alent release rate limit for the noble gas total body dose pathway, in ~tCi/sec.

472 = Conversion factor, (cc/ft 3 )/(sec/min).

Section 3 - Page 6 Page 9-34

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Cxe-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 ft 3/min.

SP = radiation monitor setpoint, in cpm.

CF = the Xe-133 equivalent monitor correlation factor, in µCi/cc/cpm.

bkg = the radiation monitor background reading, in cpm.

Equation 3.6 provides the methodology to calculate the maximum setpoint for releases from the Unit Vents (RIA-45 and RIA-46), Radwaste Facility (4RIA-45), and Interim Radwaste Building (RIA-53). The maximum setpoints are termed "High" setpoints.

In addition to High setpoints, Oconee uses "Alert" *setpoints that are approximately 1/3 of the High setpoint for each specific release point. Alert setpoints provide early indication to plant operating staff of increased radioactivity.

3.0.2.1 UNIT VENTS SETPOINTS (RIA-45 and RIA-46)

Reactor Building purges from all 3 units are released via the applicable unit vent, either Unit 1, Unit 2, or Unit 3. Each of the 3 unit vents are monitored by a normal/low range RIA (RIA-45) and a high range RIA (RIA-46). In addition to Reactor Building purges, all other releases from the main plant, including the Auxiliary Building ventilation, Waste Gas Decay Tanks, and the Spent Fuel Pools are monitored by each unit's RIA-45 and RIA-46. However, RIA-45 and RIA-46 on each unit vent have release termination authority only for Reactor Building purge releases. Each unit's RIA-45 and RIA-46 will, when operable, activate Control Room alarms if the unit vent concentration exceeds the monitor's setpoint value. The setpoints for each unit's RIA-45 and RIA-46 are established on a "worst case" basis, with the upper bound normally set at 30 percent of the station release rate limit for noble gases in Xe-133 equivalent concentration as follows:

Recall Equation 3.6:

SP= Cxe-m + bkg CF where:

500 Cxe-133 < ---------

472 X f X Kxe-133 X x!Q Section 3 - Page 7 Page 9-35

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee J\uclear Station Offsite Dose Calculation Manual (ODCM) 150 RJA-45an,lvat~higl, = - - - - - - - - - - - - - - - - - -

472 x 6.5E+04 x 294 x l.672E-06 x 7.09E-08 RJA-45 ..,,.,vmLhiglt =l.40E+05cpm + bkg where :

150 = 30% of the 500 mremiyr total hody release rate limit.

6.5E+04 = Unit V cnt flow rate with Reactor Building Purge off, ft 3/min.

l.672E-06 Highest S.:mi-Elevated release point dispersion factor, secim3*

7.09E-08 RIA-45 CotTelation Factor, itCi/ml/cpm.

All other facto.rs were prc~iously defined.

150 RJA - 46w,.lvo11l.higl1 =

472 x 6.5E+04 x 294 x 1.672E-06 x 3.17E-04 RL4.- 46un,mno.hif.h =31 cpm + bkg where :

3.17E-04 = RIA-46 Correlation Factor, ~LCi/ml/cpm.

All other fa1:tors were previously defined.

Alert setpoints are detennined as follows :

l RL4-45.,,,, ,..,a,a:ert = RJA-45wmvco~higbX-3 RL4.-45,.mtvmt.alert = 4.66E+04cpm + bkg 1

RL4- 46,,,,1 ""'* a!e,! = RIA. - 46ur.i! v"'~high X -

3 RL4- 46wu,v,n,.~~* =10 cpm + bkg l/3 - divisor to account for each of3 unit vent release points. dimensionless.

All other factors were previously defined.

Section J - Poge 8 Page 9-36

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

For instances in which the Reactor Building Purge is on, the High and Alert setpoints are multiplied by 0.65 (65,000 cfm/ (65,000 cfm + 35,000 cfm purge flow)).

3.0.2.2 RADWASTE FACILITY SETPOINTS (4RIA-45) 25 472 x l.297E+05 x 294 x 7.308E-06 4RIA - 45high = I .90E - 04 µCi/cc where:

25 = 5% of the 500 mrem/yr total body release rate limit.

l.297E+05 = Radwaste Facility Vent flow rate, ft 3/min.

7.308E-06 = Highest Ground-Level release point dispersion factor, sec/n/

All other factors were previously defined.

4RIA-45 reads in units of concentration, µCi/cc.

Alert setpoint is determined as follows:

4RJA- 45alut = 4RJA- 45high X -I 3

4RIA - 45a1 .., =6.33E - 05 µCi/cc+ bkg All factors were previously defined.

Section 3 - Page 9 Page 9-37

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) 3.0.2.3 INTERIM RADWASTE BUILDING SETPOINTS CRIA-53) 25 RL4-53bigh = --------- --------

472 x l.5E+04 x 294 x 7.308E-06 x 3.4E-08 RL4-53wgh == 4.8E+04cpm + bkg where:

25 = 5% of the 500 mrem/yr total body release rate limit.

l.5E+04 = Interim Radwaste Building Vent flow rate, ft 3/min.

7.308E-06 = Highest Ground-Level release point dispersion factor, sec/m 3.

3.4E-08 = RIA-53 Correlation Factor, µCi/ml/cpm.

All other factors were previously defined.

Alert setpoint is determined as follows :

1 RL4 - 53mert = RIA - 53wgh X -

3 RL4 - 53,,,rt == 1.6E + 04 cpm + bkg All factors were previously defined.

3.0.2.4 WASTE GAS DECAY TANK SETPOINTS CRIA-37 and RIA-38)

For batch releases where the effluent can contain activity significantly above background, e.g., Waste Gas Decay Tank (WGDT), two additional monitors, RIA-37 and RIA-38 are used to establish setpoints for each WGDT batch released. RIA-37 is the nonnal/low range noble gas monitor, and RIA-38 is the high range noble gas monitor. The following setpoint methodology is used:

Cx,-m= L(C. X Eq,)

I Cxe - 133 Expected Cpm = - - - + bkg CFxe - 133 Section 3 - Page 10 Page 9-38

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Kuclear Station Offsite DoS<J Calculation Manual (ODCM)

RL:A- 3 -. and RIA-38 Setpomt

, . =- Cx,-"'

- - x 1.5 + bkg Equation 3.7 CFx,-m where:

Cx,-JJJ = Xe-133 equivalent concentration of the WGDT to be released. in µCi/ml.

Eq; = Xe-133 equivalence factor for each noble gas isotope, excluding tritium, to that ofXe-133 due to different beta energies and abundance.

(See Table 3.0-2).

CFx,-m = The expected RIA response to a given Xe-133 equivalent concentration, in

µCi/ml/cpm. lRIA-37 = 4.20E-08 ~lCi/ml/cpm, 3RIA-37 = 4.20E-08

µCi/ml/cpm, lRIA-38 and 3RIA-38 = 1.34E-03 µCi 1ml/cpm.

1.5 - An adjustment factor to' account for expected minor variations in effluent concentrati~n and RIA background.

bkg = The radiation monitor background reading, in cpm.

When the release pathway is from any Unit 1 WGDT (A-D), and the Xe-133 equivalent concentration is less than 2.8E-0l ~lCi/ml, the 1&2 RIA-38 setpoint is established at 313 cpm, and the 1&2 RIA-37 setpoint is calculated using Equation 3.7.

When the release pathway is from any Unit 1 WGlH (A-IJ). and the Xe-133 equivalent concentration is greater than 2.8E-01 µCi/ml, the 1&2 RIA-37 setpoint is established as offacale high, and the 1&2 RIA-38 setpoint is calculated using Equation 3.7.

When the release pathway is from any Unit 3 WGDT (A-C). and the Xe-133 equivalent concentration is less than 2.8E-0l ~LCi/ml, the 3 RIA-38 setpoint is established at 313 cpm, and the 3 RIA-37 setpoint is calculated using Equation 3.7.

When the release pathway is from any Unit 3 WGDT (A-C), and the Xe-133 equivalent concentration is greater than 2.8E-01 ~tCi/ml, the 3 RIA-37 setpoint is established as omcale high, and the 3 RIA-38 setpoint is calculated using Equation 3. 7.

Low activity levels in the WGDTs can result in calculated setpoint values close to background. To prevent spurious alarms, if the 1&2 RIA-37 or 3 RIA-37 setpoint is calculated to be less than 2000 cpm. then the setpoint is established at 2000 cpm above background.

Section 3 - Page 11 Page 9-39

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

TableJ.0-2 Xe-133 Equivalents Isotope Equivalence Factor Kr-83m 0 Kr-85m 2.48 Kr-85 2.56 Kr-87 2.93 Kr-88 2.78 Kr-89 2.93 Kr-90 2.93 Xe-13lm 1.69 Xe-133m 1.99 Xe-133 1.0 Xe-135m 0.83 Xe-135 2.63 Xe-137 2.93 Xe-138 2.93 Ar-41 2.82 C-11 2.70 Section 3 - Page 12 Page 9-40

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee 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 software which implements the ODCM methodology. The software is designed to automate many of the tasks required in the administration of effluent releases at Oconee and perfonus 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 Oconee SLCs. Such calculations are used to verify that adequate margin remains during a report period to allow normal station and radwaste systeni 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 (GW) or Liquid Waste (LW) systems as required in the Oconee 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 software implementing the ODCM methodology.

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.

Liquid waste processed by the LW system can be released to the environment at Oconee from two liquid discharge points; (1) directly to the Keowee Tailrace through RIA-33 and (2) to the Chemical Treatment Pond #3 discharge point into the Keowee River (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 activity release and dilution data for each liquid effluent release point. The primary liquid effluent discharge point for Oconee is to the Keowee Tailrace through RIA-33 . In general, only low activity tritium releases (<l % station total) occur through the Chemical Treatment Pond #3 discharge point into the Keowee 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 Oconee.

Section 4 - Page I Page 9-41

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

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

Doseoa = L p L(Aoapixci)xMxFn x Dw

- f F,,----xa j+F Formula: adapted from NUREG-0133, pages 15-17. Where:

Doseoa TI1e cumulative dose commitment for organ o and age group a, from the liquid eflluent for the total time period, ~t. (mrem)

Aoapi 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).

Ci The average concentration of nuclide i, in undiluted liquid eflluent during the time period, ~t. (µCi/ml)

~t The length of time over which Ci and Fn are averaged for all liquid releases. (hr)

F11 TI1e near field average dilution factor for Ci during the period of interest,

~t. Includes the recirculation factor. (dimensionless) f Average liquid radwaste flow during the period of interest, ~t. ( gpm)

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

Nonnally this value is conservatively assumed to be l.71E+04 gpm (38 cfs ). A dilution flow of 76 cfs is more realistic since it includes bypass Keowee bypass leakage (19 cfs per Keowee Hydro unit, plus the Keowee Hydro Fire Protection liquid waste release mixing line whose flow rate is 38 cfs). No dilution credit is taken for the relatively short period of time during the year that the Keowee Hydro units are running.

cr Recirculation factor. (dimensionless)*

Dw Dilution factor from the near field area to the potable water intake;

= 30.0 for Oconee. This factor applies to the potable water pathway only. The nearest potable water intake to Oconee is located at the Anderson water intake approximately 31.5 miles from the site on a separate arm of Lake Hartwell. From a hydrology standpoint the Anderson water intake should not be significantly affected by liquid eflluent discharges from Oconee. 30.0 is a conservatively small dilution factor based on environmental sample data.

• The recircuiation factor accounts for the fraction of discharged water reused by the station.

Liquid eflluent discharge cannot be recirculated back into the Oconee station. Therefore, the recirculation factor is 1.0 at Oconee.

Section 4 - Page 2 Page 9-42

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Derivation of Liquid Dose Commitment Factors (Aoap1)

Potable Water Aoapi =1

• 14xl05 x Uaw xDaoi x e*A/p Formula: from NUREG-0133, page 16 and Regulatory Guide 1.109, page 1.109-12.

Where:

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

l.14:d0 5 Units conversion factor (pCi-vr-ml)/(µCi-hr-1). l Uaw 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 Daoi Dose factor for age group a, organ o, nuclide i, in rnrem/pCi. From tables E-11 through E-14 of Regulatory Guide 1.109.

A,j Decay constant for nuclide i, in sec*1.

tp Environmental transit time from release to receptor. Default =

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

Section 4 - Page 3 Page 9-43

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Aquatic Foods Aoapi = 1.14x 105 Xuef X BF; X Daoi X e*,l;tp Formula: from NUREG-0133, page 16 and Regulatory Guide 1.109, page 1.109-12.

Where:

Aoapi 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).

l.14 x10 5 Units conversion factor (oCi-vr-ml)/(µCi-hr-1).

Uar 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; Bioaccumulation factor for nuclide i, in fish, in units ofpCi/kg per pCi/liter. From Table A-1 of Regulatory Guide 1.109.

Daoi 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.

A.; Decay constant for nuclide i, in sec*1.

tp Environmental transit time from release to receptor. Default =

8.64E+04 sec (l dav). From Regulatorv Guide 1.109, Table E-15.

Section 4 - Page 4 Page 9-44

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Shoreline Sediment I

Aoapi = 1.14x 10 5 X lOOx DFGoi X w X uas X TJ, X e-A,lp X (l-e -"' 1b)

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

Where:

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

L14xl0 5 Units conversion factor (pCi-yr-ml)/(uCi-hr-1).

100 Proportionality constant used in the sediment radioactivity model, (liters/(m2-day), I DFGai Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/m 2), from Table E-6 of Regulatory Guide 1.109.

w Shoreline width factor. For Oconee = 0.2, from Table A-2, Regulatory Guide 1.109.

Uas Shoreline exposure rate for age group a (hr/yr), From Table E-5 ,

Regulatory Guide L 109, Adult - 12 Teen - 67 Child - 14 hlfant - 0 Tt' Nuclide half life for nuclide i, in days,

/\,j Nuclide decay constant for nuclide i.

to Average transit time to point of exposure (0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />).

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

Section 4 - Page 5 Page 9-45

• • Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) 4.0.2 GASEOUS EFFLUENT DOSE MODEL FOR THE MAXIMUM EXPOSED INDIVIDUAL TI1e 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 Doser =3.17xl0-8 x X !Qx I(M;x QJ

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

Where:

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

3.17xJ0*8 Inverse number of seconds in year (year/seconds).

M; Gamma air dose factor due to gamma emissions for nuclide i (mrad/yr per µCi/m 3 ) . (See Appendix A).

x/ Q The highest calculated annual average relative concentration for any area at or beyond the site boundary (sec/m 3)* . (See Table 6.0-9).

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

Beta Air Dose Dose /3 = 3 .17 X 1o-sX XI Q X L(N; X Qi) i Formula: adapted from NUREG-0133, page 28.

Where:

Dose11 Beta air dose for the time period of interest (mrad).

3.l 7xl0- 8 Inverse number of seconds in year (year/seconds).

N; Beta air dose factor due to beta emissions for nuclide i (mrad/yr per uCi/m3 ) . (See Aooendix A).

xJQ The highest calculated annual average relative concentration for any area at or beyond the site boundary (sec/m 3)*. (See Table 6.0-9).

Q; 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.l 7x 10-s X w X L L(Roapi X Q) p Formula: adapted from NUREG-0133, pages 29 & 30.

Where:

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

3.17xl0*8 Inverse number of seconds in year (year/seconds).

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

When a D/Q is used the units ~re (m2

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

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

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

Inhalation r./Q (sec/m 3)

Vegetation D/Q (m*2)

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

Grass/Goat/Milk D/O (m*2)

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

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

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

• The dose from noble gases released from semi-elevated release points, e.g., unit vent, is calculated using the semi-elevated dispersion factors. The dose from noble gases released from ground level release points, e.g., Radwaste Facility vent, is calculated using the ground level dispersion factors. TI1e total dose is the sum of the semi-elevated and ground level dose calculations. Maximum individual organ dose is determined by calculating the organ dose at each of the x /Q and D/Q locations shown in Table 6.0-9 and Table 6.0-10 (128 locations) for both semi-elevated release points and ground level release points, summing the two at each location, and then choosing the dose from the maximum location. Dose is calculated only for those pathways (e.g., garden, milk animal, etc.) that actually exist at each location as determined by the land use census. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous eflluent release limits is the exclusion area boundary (EAB). The EAB is defined as a l mile radius from the station center.

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• • 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 of9.4 Ci/GWe-~T is used along with actual power generation to estimate C-14 activity released to the environment via gaseous effluents from Oconee. 9.4 CiiGWe-)T is based on information from "Estimation of Ca,.bon-14 in Nuclear Power Plant Gaseous E[fluents", EPRI, Palo Alto, CA: 2010. 1021106.

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Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (Roap1)

Ground Plane Deposition Pathway R

oop,

. = K'K"(SF)DFG o,

• [(1-e-,i,t)]

A; Formula: from NUREG-0133, page 32.

Where:

Roapi 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 (10 6).

K" Units conversion factor 8760 hr/year. '

SF Shielding factor (dimensionless) (0.7, from Rel!.Ulatory Guide 1.109).

DFGoi Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/m 2), from Table E-6 ofRel!.Ulatorv Guide 1.109.

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

t Exposure time, 4.73x 10 8 seconds (15 years).

Inhalation Pathway Formula: from NUREG-0133, page 31.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for inhalation pathway (mrem/yr per µCi/m 3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (10 6).

BR, Breathing rate for age group (m 3/yr), from Regulatory Guide 1.109:

Adult - 8000 Teen - 8000 Child - 3700 Infant - 1400 (DFAoi)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

.=K'[ y R oapt V

(r)

(A + A )

J w

]x(DFL o .) a xruLre 1 ~ aJL

-Ah +Ua8 f.e g

- A.' th ]

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

Roapi 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 oCi/uCi (10 6).

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

1.0 for radioiodine.

0.2 for particulates.

Yv Vegetation areal density (kg/m 2 ) (2.0, from Re=latorv Guide 1.109).

A,j Nuclide decay constant for nuclide i (sec*1).

Aw Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10*7 sec*1, from NUREG-0133).

(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-I4 of Reg. Guide 1.109 (rnrem/pCi).

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

(from Regulatory Guide I . I 09).

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

tL Average time between harvest ofleafy vegetation and consumption (8.6x 104 seconds, (I day), from Re=latory Guide 1.109).

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

Adult - 520 Teen - 630 Child - 520 Infant - 0 fg Fraction of annual intake of stored vegetation (0. 76, from Regulatory Guide 1.109).

th Average time between harvest of stored vegetation and consumption (5. I8xI0 6 seconds, (60 days), from Regulatory Guide 1.109).

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Vegetation - Tritium Formula: from NUREG-0133, page 36.

Where:

Roapi Dose commitment factor for organ o, age group a, for vegetation pathway and tritium (mrem/yr per µCi/m 3 ). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (10 6).

K'" Units conversion factor gm/kg (10 3).

ULa Consumption i;ate of fresh leafy vegetation for age group a (kg/yr)

(from Regulatory Guide 1.109).

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

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

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

(DFLoi)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/m 3, from Regulatory Guide 1.109).

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Vegetation - Carbon-14 Formula: from NUREG-0133, page 36 and Regulatory Guide 1.109, page 26.

Where:

Roapi Dose commitment factor for organ o, age group a, for vegetation pathway and carbon-14 (mrem/yr per µCi/m 3 ). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/uCi (10 6).

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

u1. Consumption rate of fresh leafy vegetatiop. for age group a (kg/yr) (from Regulatory Guide 1.109).

Adult - 64 Teen - 42 Child - 26 Infant - 0 f1 Fraction of annual intake of fresh leafy vegetation grown locally (1.0, from NUREG-0133).

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

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

(DFLoi)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 (rnrem/pCi).

0.11 Fraction of total plant mass that is natural carbon.

0.16 Concentration of natural carbon in the atmosphere (gm/m 3 ) .

p Ratio of the total annual C-14 release time to the total arinual time during which photosynthesis occurs. This value is assumed to be 0.3 5, 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; EPRI TR-1024827, "Carbon-14 Dose Calculation Methods at Nuclear Power Plants", 2012, Section 3.2.5).

fi 111e fraction of C-14 assumed to be in inorganic fonn (e.g., CO2).

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 Fonnula: from NUREG-0133, pages 32 & 33. Where:

Roapi 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 (10 6).

OF Cow consumption rate (50 kl!/day, from Regulatory Guide 1.109)

Uap Consumption rate of cow milk for age ~roup a (liters/yr, from Regulatory Guide 1.109).

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

1. 0 for radioiodine.

0.2 for particulates.

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

Ys Agricultural productivity by unit area of stored feed (2.0 kg/m2, from Re211latorv Guide 1.109).

A,j Nuclide decay constant for nuclide i (sec*1) .

Aw Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10-7 sec*1, from NUREG-0133).

(DFLoi)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).

Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 ofRe211latory Guide 1.109 for cow milk.

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

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

tr Transport time for pasture to cow, to milk, to receptor (1.73E+05 seconds, from Re211latorv Guide 1.109).

th 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 Formula: from NUREG-0133, page 34.

Where :

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/milk pathway (mrem/yr per µCi/m 3) . (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor oCi/ uCi (10 6).

K"' Units conversion factor gm/kg (10 3).

QF Cow consumption rate (50 kg/day, from Regulatory Guide l.109).

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

Adult - 310 Teen - 400 Child - 330 Infant - 330 (DFLoi)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/oCi).

Fmi 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/m 3, from Regulatory Guide 1.109).

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Grass/Cow/Milk - Carbon-14 Roapi = K'K"'Fmi QF Uap (DFL ;t[O. l l/O. l6](p)(.fi,)

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

Where:

Raapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (mrern/yr per µCi/m 3). (See Appendices G throui!h J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (10 6).

l K'" Units conversion factor gm/kg (10 3) . l Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 ofReimlatory Guide 1.109 for cow milk.

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

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

Adult - 310 Teen - 400 Child - 330 Infant - 330 (DFLai)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 atmosohere ( mn/m 3).

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 0.35, 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; EPRI TR-1024827, "Carbon-14 Dose Calculation Methods at Nuclear Power Plants", 2012, Section 3.2.5).

fi The fraction of C-14 assumed to be in inorganic form (e.g., CO2).

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 Formula: from NUREG-0133, pages 32 & 33. Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/milk pathway (m 2 *rnrem/yr per µCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (10 6).

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

Uap Consumption rate of goat 111ilk for age group a (liters/yr, from Regulatory Guide 1.109).

Adult - 310 Teen - 400 Child - 330 lnfant - 330 r Fraction of deposited activity retained on goat's feed grass, from Regulatory Guide 1.109.

1.0 for radioiodine.

0.2 for particulates.

Yp Agricultural productivity by unit area of pasture feed grass (0.7 kg/m 2, from Regulatory Guide 1.109).

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

Ai Nuclide decay constant for nuclide i (sec*1) .

Aw Decay constant for removal of activity on leaf and plant surfaces by weathering (5 .73 x 10*7 sec*1, from NUREG-0133).

(DFLoi)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).

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

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

fs Fraction of the goat feed that is pasture grass while the goat is on pasture (1.0, from Regulatorv Guide 1.109).

tr Transport time for pasture to goat, to milk, to receptor (l.73E+05 seconds, from Regulatory Guide 1.109).

th 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 Fonnula: from NUREG-0133, page 34.

Where :

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/milk pathway (mrem/yr per µCi/m 3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor oCi/uCi (10 6).

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

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

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

Adult - 310 Teen - 400 Child - 330 Infant - 330 (DFLoi)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).

Fmi 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 ofthe atmosphere (8 gm/m 3, from Regulatory Guide 1.109).

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Grass/Goat/Milk - Carbon-14 Roapi = K'K'"Fmi QF Vap (DFL i)a[O. l l/O. l6](p)(h) 0 Formula: from NUREG-0133, page 34 and Regulatory Guide 1.109, page 26.

Where :

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

K' Units conversion factor pCi/µCi (10 6).

K'" Units conversion factor gm/kg (10 3).  :

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

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

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

Adult - 310 Teen - 400 Child - 330 Infant - 330 (DFLoi)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 (mrern/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 0.35, 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; EPRI TR-1024827, "Carbon-14 Dose Calculation Methods at Nuclear Power Plants", 2012, Section 3.2.5).

f1 The fraction of C-14 assumed to be in inorganic form (e.g., CO2).

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 Formula: from NUREG-0133, pages 34 & 35. Where:

Roapi 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/u.Ci (10 6) .

OF Cow consumption rate (50 kg/day, from Regulatory Guide 1. 109).

Uap 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 cow's feed grass (from Regulatory Guide 1.109).

1. 0 for radioiodine.

0.2 for particulates.

Yp Agricultural productivity by unit area of pasture feed grass (0. 7 kg/m2, from Regulatory Guide 1.109).

Ys Agricultural productivity by unit area of stored feed (2.0 kg/m2, from Re=latorv Guide 1.109).

Ai Nuclide decay constant for nuclide i (sec*1).

Aw Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10-7 sec*1, from NUREG-0133).

(DFLoi)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).

Fr, Stable element transfer coefficient for nuclide i, in days/kg, from Table E-1 ofRegulatorv Guide 1.109 for meat.

fa Fraction ofvear that the cow is on pasture (l.0, from RG 1.109).

fs Fraction of the cow feed that is pasture grass while the cow is on pasture (1.0, from Re=latorv Guide 1.109).

tr Transport time from pasture to receptor (l.73E+06 seconds, from Re=latorv Guide 1.109).

th Transpott time from crop field to receptor (7.78E+06 seconds, from Re=latorv Guide 1.109).

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Grass/Cow/Meat - Tritium Formula: from NUREG-0133, page 35.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (mrem/yr per µCi/m 3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor oCi/uCi (10 6 ).

K"' ,Units conversion factor gm/kg (10 3).

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

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

Adult - 110 Teen - 65 Child - 41 Infant - 0 (DFLoi)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).

Fti Stable element transfer coefficient for nuclide i, in days/kg, from Table E-1 of Regulatory Guide 1.109 for 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/m 3, from Regulatory Guide 1.109).

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Grass/Cow/Meat - Carbon-14 Roapi =K'K"'Ffi QF Uap (DFLaJJO.l l/0.16](p)(fi,)

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

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (mrem/yr per µCi/m\ (See Appendices G throu!!h J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (10 6).

K"' Units conversion factor gm/kg (10 3). I Fr, Stable element transfer coefficient for nuclide i, in days/kg, from Table E-1 of Regulatory Guide 1.109 for meat.

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

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

Adult - 110 Teen - 65 Child - 41 Infant - 0 (DFLoi)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 0.35, 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; EPRI TR-1024827, "Carbon-14 Dose Calculation Methods at Nuclear Power Plants", 2012, Section 3.2.5).

fi The fraction of C-14 assumed to be in inorganic form (e.g., CO2).

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

Section 4 - Page 21 Page 9-61

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Grass/Goat/Meat Formula: from NUREG-0133, pages 34 & 35. Where:

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

K' Units conversion factor pCi/uCi (10 6) .

QF Goat consumption rate (6 kg/dav, from Regulatory Guide 1.109).

Uap Consumption rate of goat meat for age group a (kg/yr, from Regulatory Guide 1.109).

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

1. 0 for radioiodine.

0.2 for particulates.

Yp Agricultural productivity by unit area of pasture feed grass (0.7 kg/m 2, from Re=latory Guide 1.109).

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

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

Aw Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73 x 10-7 sec*1, from NUREG-0133).

(DFLoi)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).

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

fo Fraction ofvear that the goat is on pasture (1.0, from RG 1.109).

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

tr Transport time from pasture to receptor (l.73E+06 seconds, from Regulatory Guide 1.109).

th Transport time from crop field to receptor (7. 78E +06 seconds, from Regulatory Guide 1.109).

Section 4 - Page 22 Page 9-62

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Grass/Goat/Meat - Tritium Formula: from NUREG-0133, page 35.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/meat pathway (mrem/yr per µCi/m 3) . (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (10 6).

K"' Units conversion factor gm/kg (10 3 ).

OF Goat consumption rate (6 kg/dav, from Regulatory Guide 1.109).

Uap Consumption rate of goat meat for age group a (kg/yr, from Regulatory Guide 1.109).

Adult - 110 Teen - 65 Child - 41 Infant - 0 (DFLoi)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).

Fr, Stable element transfer coefficient for nuclide i, in days/kg, from Table E-1 of Regulatorv Guide 1.109 for 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).

Section 4 - Page 23 Page 9-63

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Grass/Goat/Meat - Carbon-14 Roapi = K'K'" Ffi QF Vap (DFL JJO. J l/O. J6](p)(h) 0 Fonnula: from NUREG-0133, page 35 and Regulatory Guide 1.109, page 26.

Where :

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/meat pathway (mrem/yr per µCi/m 3). (See Appendices G throuQh J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (10 6).

K"' Units conversion factor gm/kg (10 3).

t Ffi Stable element transfer coefficient for nuclide i, in days/kg, from Table E-1 of Regulatory Guide 1. 109 for meat.

OF Goat consumption rate (6 kg/dav, from Regulatory Guide 1.109).

Uap Consumption rate of goat meat for age group a (kg/yr) (from Regulatory Guide 1.109).

Adult - llO Teen - 65 Child - 41 lnfant - 0 (DFLoi)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/m 3).

p Ratio of the total annual C-14 release time to the total annual time during which photosynthesis occurs. 111is value is assumed to be 0.35, 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; EPRI TR-1024827, "Carbon-14 Dose Calculation Methods at Nuclear Power Plants", 2012, Section 3.2.5).

f, The fraction of C- 14 assumed to be in inorganic form (e.g., CO2).

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

Section 4 - Page 24 Page 9-64

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee 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 Oconee 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 Oconee have been calculated and documented in the Oconee 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 Oconee 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 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.

Section 4 - Page 25 Page 9-65

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee 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 or 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 Oconee Nuclear Station:

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

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

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

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

Section 5 - Page 1 Page 9-66

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee 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 software implementing the ODCM methodology. 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 Oconee nuclear station is located over I 00 miles from the Catawba and McGuire nuclear stations, 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 Oconee 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 Oconee Nuclear Station only include liquid and gaseous dose contributions from Oconee and dose from Oconee's ISFSI since no other uranium fuel cycle facility contributes significantly to Oconee's maximum exposed individual. For this dose assessment, the total body and maximum organ dose contributions to the maximum exposed individual from Oconee's liquid and gaseous effluents are estimated using the following calculations:

Dwb(T) = Dwb([) + Dwb(g)

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

Dwb(I') = Total estimated fuel cycle whole body dose commitment resulting from the combined liquid and gaseous effluents of Oconee during the calendar year of interest, in mrem.

Dm0 (I') = Total estimated fuel cycle maximum organ dose commitment resulting from the combined liquid and gaseous effluents of Oconee during the calendar year of interest, in mrem.

Section 5 - Page 2 Page 9-67

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) 6.0 ENVIRONMENTAL LOCATIONS 6.0.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Oconee Nuclear Station (ONS) is located in Oconee County, South Carolina, approximately 8 miles northeast of Seneca, South Carolina, on the shore of Lake Keowee. This lake was formed by damming the Keowee and Little Rivers in that location. Immediately to the south is the U.S. Government Hartwell Project. The Keowee Hydroelectric Plant near the station joins Lake Keowee and the upper reaches of Lake Hartwell. To the north, the Jocassee Hydroelectric Plant joins Lake Jocassee and Lake Keowee. Jocassee is a pumped storage plant. The ONS exclusion area boundary is 1 mile.

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

6.0.2 LAND USE CENSUS DATA TI1e 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, - 1.0 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 assmned 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.

Section 6 - Page I Page 9-68

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

TABLE6.0-1 OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 6.0-1 Codes w Weekly SM Semimonthlv BW BiWeeklv 0 Ouarterlv M Mon1hlv SA Semiannuallv C Control Sile Location Description* Ah Rad. & Surface Drink.mg Shon llne Fhb Mik Broadleaf Partlrulate Water Water Sedimm t

1. Vegetatloo 060 Greenville Water Intake R.oad (3.23 NE) M 060 C *

• Greenville Water Intake Road (2.28 NE) SA 062 C Lake Keowee Hydro Intake (0 .85 mi ENE) M Lake Hartwell Hwy 183 Bridge 063 (0.80 mi ESE) f0 00.71 SA 063.1 Lake Hartwell Hwv 183 (0.79 mi E) M 064C Seneca Mllllicipal Water Supply (6.67 mi SSWl [004 .11 M 066 Anderson Mwticipal Water Supply (1 8.9 mi SSE) [0121 M Lawrence Ramsey Bridge Hwy 27 067 (4.34 mi SSE) [005.21 SA SA 068 C High Falls Countv Park (1.82 mi W) SA 07 1 C Clemson Dairv (I 0.2 mi SSE) f006.31 SM 077 Skimmer Wall (1.00 mi SW) w M 078.1 Recreation Site (0.53 mi WSW) w 079 Keowee Dam (0.56 mi NE) w M 08 1 C Clemson Ooerations Center (9 .33 mi SE) w M 084 Sue Craig Road (2.58 mi NNE) w M 085 Lake Services / Building B9 125 (0.88 mi NNW) w 09 1 Holders Lannirn, Road (2.09 miles S) SA

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

• • Control for Fish Only

[ ) Location Numbers prior to 1984 Section 6 - Page 2 Page 9-69

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

TABLE6.0-2 OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)

Site # Location* Distance* Sector Site # Location" Distance* Sector 020 Sile boundarv 0.16 miles N 044 HWY 130 al Lillie River Dam 3.96 miles s Tenninus of HWY 588 021 Sile boundarv 0.25 miles NNE 045 at Crooked Creek 4.78 miles SSW 022 Site boundarv 0.53 miles NE 046 HWY 188 at Crooked Creek 4.61 miles SW 023 Site bounrl~rv 0.93 miles ENE 048 JCT HWY 175 & 188 3.64 miles w 024 Site boundarv 0.81 miles E 049 JCT HWY 201 & 92 3.60 miles WNW Stamp Creek Landing.

025 Site bounrfo,n, 0.42 miles ESE 050 EndofHWY92 3.53 miles NW HWY 128, 026 Site boundarv 0.34 miles SE 051 1 mile N of HWY 130 4 .64 miles NNW 027 Site boundary 0.49 miles SSE 052 SI DPC Branch Office Site, Pickens 12.4 miles ENE 028 Site boundarv 0.46miles s 053 SI DPC Branch Office Site, Libertv 11.7 miles E 029 Site boundarv 0.56milcs SSW 054 SI Post Office - HWY 93 Norris 8.60 miles ESE 030 Site boundarv 0.42milcs SW 055 SI Clemson MctcoroloP:v Plot 9.27 miles SSE 031 Site boundarv 0.27 miles WSW 056 SI Water Tower. Sai.eca 7.30 miles SSW 076 Site boundarv 0.19 miles w 057 SI Oconee Memorial Hospital 8.42 miles SW 032 Site boundarv 0.19miles WNW 058 C Branch Rd Substation, Walhalla 9.39 miles WSW 033 Site boundarv 0.21 miles WNW 059 SI Tarnasscc Dar School 9.20 miles NW Skimmer wall stared with air 034 Site boundarv 0.22 miles NW 077 monitorinP: station 1.00 miles SW ONS Recreation Site shared with 035 Site boundarv 0.17 miles NNW 078.1 air monitorine: station 0.53 miles WSW 036 Mile Creek Landin, 4.18 miles N 081 C Clemson Operations Center 9.33 miles SE Lake Services Bldg 9125 shared 037 Keowee Church, HWY 327 4.85 miles NNE 085 with air monitoring location 0.88 miles NNW Convenience Mart, Lake Keowee Service Rd at Boat 038 JCT HWY 183 & 133 4.24 miles NE 086 Landin* 0.83 miles NW HWY 133, I mile East 039 of JCT HWY 183 & 133 4.02 miles ENE 087 End of Waterfall Rd 1.33 miles WNW Doug Hollow Rd ! Transmission 040 Microwave Tower Six Mile 4.74 miles E 088 Tower 1.00 miles SSW Intersection Hwy 130 & Keowee 041 JCT HWY 101 & 133 4.25 miles ESE 089 River Rd 1.19 miles s Lawrence Chapel Church, Crescent Resources, Keowee 042 HWY133 4.93 miles SE 090 River Rd at Beaver Darn 0.79 miles SE HWY291 at Hilton Circle stop sign 043 Issaaucena Park 4.09 miles SSE 092 HWY188 3.62 miles WSW 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.

Section 6 - Page 3 Page 9-70

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

TABLE6.0-3 Land Use Census Results Deleted in ODCM Revision 58.

Section 6 - Page 4 Page 9-71

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offs,te Dose Calculation Manual (ODCM)

Figure 6.0-1 Sampling Locations Map (Site Boundary)

Oconee Nuclear Station Sampling Locations Map (One Milo Radius)

• TLO Locohoos

• A'I Other Locottons

/"'v Radrcads Roads C)srMes c:Jcounties-

- W*t*nx>dy

• +*

025

---==:::i ..los 05 flrotect,a, '-CSP NA02!

M,ap~.ud~10 2019 Page 9-72

• • Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclcor Station Offsite Dose Calculaiion Manual (ODCM)

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

( \.

J Oconee Nuclear Station Sampling Locations Map (Ten Mlle Radius) e tl0l.Dc.abof15 A Al OtrM!::r Loc.,tions Roil05 c::Jsraie, c=Jeooot..

- w*""°">'

• t 0

-==--=::,Mies 1 2 3 S..:chon 6 Pag.c (i Page 9-73

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2 018 Ocone~ Kuclear Station Offsite Dos~ C~lculation Manual (ODCM)

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

Section 6 - Page 7 Page 9-74

Attachment 9 **

Summar y of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Statio.n Offsite Dose Calculation Manual (ODCM) 6.0.3 OCONEE 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 (x/Q and D/Q) output by the model are based on a five-year climatology for the site.

6.0.3.J XOODbO METHODOLOGY AND ASSUMPTIONS A continuous, routine release (non-purge) is simulated from each unit vent. The unit vent release type is categorized as semi-elevated, being elevated approximately 92% of the time and being at ground-level approximately 8% of the time. This is based on RG 1.111 criteria, with the ratio (i.e. 3.64) of the average exit velocity (11.39 m/s) to the mean wind speed at the 60 m release height (3.13 mis). To account for all release pathways, Oconee is modeled as both a totally "ground-level" release and as a "mixed-mode" release, with two model mns ofXOQDOQ.

Surrounding terrain heights are not input for ground-level releases, but are used for the elevated portion of mixed-mode releases. The locale consists of rolling terrain, so the default open terrain recirculation factor is applied in XOQDOQ [KOPT(8)=1]. This correction factor is recommended in RG 1. ll 1 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. A release height of 10 m is assumed for the ground-level release, with actual plant grade of 796 ft ms!. Using the building height (58 m) and minimum cross-sectional area of the containment building (2296 m2), XOQDOQ applies a building wake correction to the relative air concentrations.

For the mixed-mode release, the exit velocities (11.1, 11.3, and 11.7 m/s for Ul-U3, respectively) and inside diameters (1.8 m) of the unit vents are input to the XOQDOQ model for each vent. l11e heat emission rate of each vent is still assumed to be zero, as in the ground-level release. Plant grade elevation is now input as zero, however, to properly Section 6 - Page 8 Page 9-75

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) utilize the input terrain heights above yard grade elevation (Table 6.0-4). The height of the vent (60. 7 m) above plant grade is used to detennine the plume centerline height.

Table 6.0-4 Terrain Heights Above ONS Yard Grade Elevation (m)

Distance: 0.5 1 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 mile mile miles miles miles miles miles miles miles miles s 29 38 38 38 38 38 50 50 50 50 SSW 32 44 50 50 50 50 50 50 50 50 SW 38 44 44 44 50 50 50 50 50 50 WSW 44 44 44 44 44 44 44 48 48 57 w 48 48 48 48 48 55 58 73 73 73 WNW 29 29 29 38 65 65 71 71 77 80 NW 30 30 30 48 50 68 69 69 71 71 NNW 30 30 30 48 50 68 69 69 71 71 N 29 30 30 30 30 30 62 62 62 74 NNE 24 24 35 35 53 53 82 82 82 82 NE 7 13 35 44 44 50 78 88 99 100 ENE 4 23 35 38 53 62 74 80 99 100 E 1 24 24 24 57 68 68 74 84 84 ESE 1 1 13 35 62 62 62 65 71 71 SE 7 20 20 44 67 67 67 67 67 67 SSE 7 38 38 38 47 62 62 62 62 62 Calculations of relative air concentrations and deposition are made for gridded receptor distances per sector. The "no decay" assumption is used in the XOQDOQ model.

6.0.3.2 METEOROLOGICALDATA 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. XOQDOQ extrapolates the 10 m wind speed to the release height during the elevated portion of mixed-mode releases. Hours of calm winds are distributed by direction with the same frequency as the lowest "noncalm" wind speed class

[KOPT(l)= l]. 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 (5 mis + max hourly wind speed).

Stability classes (A-G) are based on the vertical temperature gradient, measured by the hourly averaged delta-T variable.

Section 6 - Page 9 Page 9-76

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) 6.0.3.3 ANNUAL XOODOO COMPARISON TO THE ODCM Each year, the prevailing winds and stability class frequencies for ONS are compared to the 5-year period (1988-1992) upon which the 7/ Q and DIQ calculations have been made.

The 5-year climatology is summarized in Table 6.0-5 and Table 6.0-6 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 6.0-5 ONS A tmospheric Stability Frequency (1988-1992)

A B C D E F G Frequency

(%) 8.8 5.6 6.2 40.4 32.5 5.0 1.4 Table 6.0-6 ONS Frequency of Wind Direction (From) and Speed (1988-1992)

Wind Direction Wind Speed Class Wind Speed Sector Frequencv (%) (mis) Frequencv (%)

N 5.3 CALM 1.0 NNE 5.2 0.45 - 0.74 mis 4.1 NE 9.0 0.75 - 0.99 mis 10.3 ENE 8.2 1.00 - 1.24 mis 10.9 E 5.2 1.25 - 1.49 mis 13.4 ESE 3.1 1.50 - 1.99 mis 18.3 SE 3.1 2.00 - 2.99 mis 22.2 SSE 3.5 3.00 - 3.99 mis 10.5 s 3.6 4.00 - 4.99 mis 4.9 SSW 8.6 5.00 - 5.99 mis 2.0 SW 11.8 6.00 - 7.99 mis 1.5 WSW 7.5 8.00 - 9.99 mis 0.3 w 5.2 > 9.99 mis 0.5 WNW 7.0 NW 7.3 NNW 6.4 TI1e 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 xlQ and DIQ values for the 1.0 mile Exclusion Area Boundary at ONS are compared to the maximum of the (1988-1992) x/ Q and DIQ values from all sectors. If Section 6 - Page 10 Page 9-77

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) 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 yjQ 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 yjQ and D/Q values used in the ARERR. If an increasing trend in the annual yjQ and D/Q values compared to the 5-year values is noted then a revised set of 5-year yjQ and D/Q values will be generated. These limiting values are listed in Table 6.0-7. The entire x/ Q and D/Q list based on directional sector and distance is given in Table 6.0-9 and Table 6.0-10.

Table 6.0-7 ONS Maximum 7./Q and D/Q Values (1988-1992)

(x/Q,s/m3) Distance Sectol' I

I (D/Q,1/m2)

Ground-level Release: Maximum "1/Q 7.308E-06 1 mile EAB SE Ground-level Release: Maximum D/Q 2.259E-08 1 mileEAB NE Mixed-mode Release: Maximum y/Q 1.672E-06 1 mile EAB SW Mixed-mode Release: Maximum D/Q 1.295E-08 1 mile EAB NE Note:

The Oconee meteorological instruments were relocated from the 46 m microwave tower to a new 60 m onsite meteorological tower in April 1988. The 60 m tower became operational at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on April 23, 1988. Therefore, determination of atmospheric stability should use the 36 m separation criteria for the period February 24, 1977-April 22, 1988 shown in Table 6.0-8. Data starting on April 23, 1988 or later should use the 50 m separation criteria.

Table 6.0-8 ONS Delta-T Ranges pel' Vertical Separation Distances Stability 36m sepal'ation Delta-T 50m separation Delta-T Class (between 46m-10m levels) (between 60m-10m levels)

FEB 24, 1977 - APRIL 18, 1988 Starting at houl' 1700 on (4/18/88 endine houl' 1430) April 23, 1988.

A dT < -0.68 dT < -0.95 B -0.68 < dT < -0.61 -0.95 < dT < -0.85 C -0.61 < dT < -0.54 -0.85 < dT < -0.75 D -0.54 < dT < -0.18 -0.75 < dT < -0.25 E -0.18 < dT < 0.54 -0.25 < dT < 0.75 F 0.54 < dT < 1.44 0.75 < c!T < 2.00 G 1.44 < dT 2.00 < dT Section 6 - Page 11 Page 9-78

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/201 8 Oconee Nuclear Station Offsite Dose Calculation l\,fanual (ODCM)

Table 6.0-9 (page 1 of2)

Oconee Semi-Elevated r/Q Average Values (1988-1992)

(sec/m 3)

Sector 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 5.220E-07 2.650E-07 1.5946-07 l.069E-07 7.7l9E-08 7.321E-08 5.665E-08 4.542E-08 NNE 8.379E-07 4.734E-07 2.6906-07 2.003E-07 l.385E-07 l.091E*07 8.379E-08 6.676E-08 NE 9.503E-07 6.350E-07 3.962E-07 2.535E-07 l.847E-07 l.497E-07 1.1576-07 9.246E-08 ENE 8.116E-07 4.856E-07 2.919E-07 2.196E-07 l.6l9E-07 l.239E-07 9.609E-08 7.720E-08 E 5.950E-07 3.202E-07 2.015E-07 2.270E-07 l.745E-07 l.292E-07 l.024E-07 8.308E-08 ESE 4.531E-07 3.300E-07 3.623E-07 4.020E-07 2.822E-07 2.l09E-07 1.688E-07 1.405E-07 SE 7.505E-07 4.573E-07 5.4906-07 5.l lOE-07 3.560E-07 2.648E-07 2.063E-07 1.665E-07 SSE l.419E-06 7.428E-07 4.527E-07 3.489E-07 2.866E-07 2.l31E-07' l.659E-07 l.337E-07 s 1.170E-06 6.099E-07 3.701E-07 2.496E-07 1.8l0E-07 J.552E-07 l.218E-07 9.867E-08 SSW l.214E-06 6.327E-07 3.564E-07 2.301E-07 1.621E-07 1.213E-07 9.481E-08 7.660E-08 SW l.672E-06 7.285E-07 4.057E-07 2.720E-07 l.89IE-07 l.400E-07 1.085E-07 8.708E-08 WSW l.558E-06 6.820E-07 3.8046-07 2.438E-07 l.708E-07 1.271E-07 l.OIOE-07 8.114E-08 w 1.193E-06 5.214E-07 2.9096-07 l.867E-07 l.372E-07 l.032E-07 8.326E-08 6.654E-08 WNW 4.658E-07 2.480E-07 1.7606-07 l.482E-07 l.024E-07 7.695E-08 5.9436-08 4.796E-08 NW 4.831E-07 2.524E-07 l.965E-07 l.291E-07 9.959E-08 7.356E-08 5.682E-08 4.566E-08 NNW 5.375E-07 2.769E-07 2.1286-07 l.394E-07 l.072E-07 7.913E-08 6.IIOE-08 4.907E-08

• Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is at a radius of 1.0 mile from the station center. Each x/ Q value is calculated at the closest location for the sector, e.g., l.672E-06 sec/m3 is the x/ Q value at 1.0 mile (SW) from the station.

Section 6 - Page 12 Page 9-79

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Table 6.0-9 (page 2 of2)

Oconee Semi-Elevated D/Q Average Values (1988-1992)

(m-2)

Sector 1.0-1.s* 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 2.890E-09 1.1 84E-09 6.225E-10 3.812E-10 2.586E-10 3.380E-10 2.5 10E-10 1.943 E-10 NNE 9.lllE-09 3.989E-09 2.0 l lE-09 l.248E-09 8.235E-10 8 .997E-10 6.667E-10 5.138E- 10 NE l. 295E-08 5.666E-09 2.91 9E-09 l.729E-09 l.145E-09 l.224E-09 9 .140E-10 7.06 7E-10 ENE 7.899E-09 3.385E-09 l.756E-09 l.095E-09 9.819E-10 7.671E-10 5.749E-1 0 4 .466E-10 E 4 .454E-09 l.775E-09 9.252E-10 7.164E-1 0 7.491E-10 5.267E-1 0 3 .981E-10 3.125E-10 ESE 4 .361E-09 l.838E-09 l.086E-09 l.3 22E-09 8.696E- 10 6.1 61E- 10 5 .153E-10 4.1 39E-10 SE 3.397E-09 l.3 85E-09 8.3 41 E-1 0 1.649E-09 l .OSOE-09 7 .595E-10 5.629E- 10 4.340E-10 SSE 3.333E-09 l.3 23E-09 68 20E-10 4 .404E-10 7.307E-10 5.202E-10 3.922E-1 0 3 .091E-10 s 3.1 92E-09

• l.256E-09 6.530E-10 4.020E-10 2.788E-10 2 .1 77E-10 1.759E-I O l.SOI E- 10 SSW 5.190E-09 l .972E-09 9.899E-10 5.895E-10 3.928E-10 2.842E-10 2 .1 92E-10 l.778E-10 SW l.205E -08 4 .399E-09 2.193E-09 l.2 99E-09 8.52 1E-10 6 .028E-1 0 4 .518E-10 3.546E- 10 WSW l .047E-08 3.824E-09 l .908E-09 l.1 27E-09 7.422E- 10 5.277 E-10 3.980E-10 3.145E- 10 w 5.577E-09 2.044E-09 l.025E-09 6.094E-10 4.134E-10 3 .405 E-1 0 3 .962E-1 0 3.052E-10 WNW 2.185E-09 9.042E-10 5.220E-10 6.464E-10 4.22 7E- 10 3.1 88E-10 2 .360E-10 l.868E-10 NW 2.097E-09 8.759E-10 5.225E- I O 3.196E-10 4.521E- 10 3.178E-10 2 .353E-I O l.812E-10 NNW 2.461E -09 l.028E-09 6.219E -10 3.765E-10 5.128E-10 3 .604E-10 2.667E-I O 2.054E-10

• Units are in miles from the station. As discussed in Oconee UFSAR Section 2. 1.1.3, the boundary for establishing gaseous effiuent release limits is the exclusion area boundary (EAB). TI1e EAB is defined as a 1 mile radius from the station center. Each D/Q value is calculated at the closest location for the sector, e.g., l.205E-08 m-2 is the D/Q value at 1.0 mile (SW) from the station.

Section 6 - Page 13 Page 9-80

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Table 6.0-10 (page 1 of2)

Oconee Ground Level 7./Q Average Values (1988-1992)

(sec/m 3)

Sector 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 2.115E-06 8.389E-07 4.495E-07 2.822E-07 l.952E-07 l .443E-07 l.l l 7E-07 8.96IE-08 NNE 2.898E-06 l.l 37E-06 6.047E-07 3.775E-07 2.602E-07 l.916E-07 l.480E-07 l.184E-07 NE 3.886E-06 l.529E-06 8.158E-07 5.108E-07 3.529E-07 2.604E-07 2.0l5E-07 l .6l6E-07 ENE 3.226E-06 l.277E-06 6.848E-07 4.305E-07 2.983E-07 2.207E-07 l.71IE-07 l.374E-07 E 3.522E-06 l.410E-06 7.658E-07 4.866E-07 3.400E-07 2.534E-07 l.977E-07 l.596E-07 ESE 5.964E-06 2.407E-06 l.321E-06 8.459E-07 5.950E-07 4.457E-07 3.493E-07 2.832E-07 SE 7.308E-06 2.972E-06 l.631E-06 l.044E-06 7.342E-07 5.497E-07 4.307E-07 3.490E-07 SSE 6.604E-06 2.657E-06 l.440E-06 9.117E-07 6.354E-07 4.723E-07 3.676E-07 2.962E-07 s 5.278E-06 2.121E-06 l.146E-06 7.237E-07 5.032E-07 3.734E-07 2.901E-07 2.335E-07 SSW 3.986E-06 1.589E-06 8.536E-07 5.370E-07 3.721E-07 2.753E-07 2.135E-07 1.714E-07 SW 4.I08E-06 l.620E-06 8.628E-07 5.390E-07 3.715E-07 2.735E-07 2.112E-07 l.689E-07 WSW 3.804E-06 l.503E-06 8.0ISE-07 5.015E-07 3.460E-07 2.549E-07 l.970E-07 l.577E-07 w 2.978E-06 l.186E-06 6.361E-07 3.995E-07 2.765E-07 2.043E-07 l.583E-07 l.270E-07 WNW 2.201E-06 8.791E-07 4.726E-07 2.974E-07 2.062E-07 l .526E-07 l.183E-07 9.502E-08 NW 2.104E-06 8.385E-07 4.499E-07 2.826E-07 l.957E-07 l.447E-07 l.121E-07 8.991E-08 NNW 2.221E-06 8.860E-07 4.755E-07 2.988E-07 2.069E-07 l.529E-07 l.185E-07 9.508E-08

• Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effiuent release limits is the exclusion area boundary (EAB). TI1e EAB is defined as a 1 mile radius from the station center. Each x/Q value is calculated at the closest location for the sector, e.g., 4.108£-06 sec/m3 is the x/ Q value at 1.0 mile (SW) from the station.

Section 6 - Page 14 Page 9-81

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Table 6.0-10 (page 2 of2)

Oconee Ground Level D/Q Average Values (1988-1992)

(m-2)

Sector 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 6.916E-09 2.484E-09 l.232E -09 7.255E-10 4.750E-10 3.342E-10 2.477E- 10 l.909E-10 NNE l.642E-08 5.897E-09 2.924E-09 1.722E-09 1.128E-09 7.934E-10 5.880E-10 4.531E- 10 NE 2.259E-08 8.l 14E-09 4.024E-09 2.369E-09 l.55 1E-09 l.092E-09 8.090E-10 6.235E-10 ENE l.428E-08 5.!JOE-09 2.544E-09 1.498E-09 9.810E-10 6.902E-10 5.115E-10 3.942E- 10 E 9.899E-09 3.556E-09 l.763E-09 1.038E-09 6.798E-10 4 .784E-10 3.545E-10 2.732E-10 ESE l.336E-08 4.798E-09 2.3 79E-09 l.401E*09 9.1 74E*l0 6.455E*l0 4 ,784E*l0 3.686E-10 SE l.401E-08 5.034E-09 2.496E-09 l.4 70E-09 9.625E-10 6.772E-10 5.019E-10 3.868E-10 SSE l .226E-08 4.404E-09 2.184E-09 l.286E-09 8.420E-10 5.925E-10 4.391E- I O 3.384E-10 s l.008E-08 3.620E-09 l.795E-09 l.057E-09 6.922E-10 4.871E-10 3.610E-10 2.782E-10 SSW 9.941E-09 3.571E-09 l.77 1E-09 l.043E-09 6.828E- JO 4 .804E-10 3.560E-10 2 .744E- J O SW 1.71 7E-08 6.169E-09 3.059E-09 l.801E-09 l.180E-09 8.JOOE-10 6.151E-10 4 .740E-JO WSW l.574E-08 5.655E-09 2.804E-09 l.651E-09 l.08JE-09 7.608E-10 5.638E-10 4.345E-10 w 9.988E-09 3.588E-09 1.779E-09 l .048E-09 6.860E-10 4 .827E-10 3.577E-10 2.757E-10 WNW 5.953E-09 2.l 38E-09 l .060E-09 6.244E-10 4.088E-10 2.877E-10 2.132E-10 1.643E-10 NW 5.891E-09 2.116E-09 1.049E-09 6.l 79E-10 4.046E-10 2.847E-10 2 .l!OE-10 l.626E-10 NNW 6.672E-09 2.397E-09 l.188E-09 6.998E-10 4.582E-10 3.224E-10 2.390E-10 l.841E-10

• Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effiuent release limits is the exclusion area boundary (EAB). 111e EAB is defined as a 1 mile radius from the station center. Each D/Q value is calculated at the closest location for the sector, e.g., l.717E-08 m*2 is the D/Q value at 1.0 mile (SW) from the station.

Section 6 - Page 15 Page 9-82

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODC:M) 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 below changes do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

ODCM Revision 59 ODCM Revision 59 was approved and implemented on the date shown on the cover sheet.

Some changes reflected in this revision were implemented prior to the above date under a different change and approval process (e.g., land use census), and in those cases the implementation date is noted below.

Table of Contents Updated page numbers as necessary.

Section 4 - Page 7 Added 'Grass/Goat/Meat' Pathway and set Factor Used as 'D/Q (m- 2)' to W parameter in table for Doseoa formula per DRR 02209374.

Section 4 - Page 12, 15, 18, 21 Added reference EPRl Technical Report 1024827, Carbon-14 Dose Calculation Methods at Nuclear Power Plants, to 'p' factor description for all Roapi equations for Carbon-14.

Change made based on recommendation in DRR 02155454. Minor comments made by NRC during routine inspection at McGuire from review of ODCM to include all references used in development of ODCM parameters and methodologies.

Section 4 - Page 19 to 21 Updated description of parameter Ffi from:

"Stable element transfer coefficient for nuclide i, in days/ liter.from Table E-1 ofRegulatory Guide 1.109 for cow meat. "

to" "Stable element transfer coefficient for nuclide i, in days/kg, from Table E-1 ofRegulatory Guide 1. 109 for meat. "

Editorial change made to correct units from days/liter to days/kg and remove "cow" label to match Table E-1 of Regulatory Guide 1.109 verbatim.

Section 4 - Page 23 to 25 Added Roapi equations and parameters for newly added Grass/Goat/Meat pathway per DRR 02209374.

Section 7 - Page I Page 9-83

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Grass/Goat/Meat Formula: from NUREG-0133, pages 34 & 35. Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/meat pathway (m 2 *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 (10 6) .

l OF Goat consumption rate (6 kg/day, from Regulatory Guide l. ~09).

Uap Consumption rate of goat 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 goat's feed grass (from Regulatory Guide 1.109).

l.0 for radioiodine.

0.2 for particulates.

Yp Agricultural productivity by unit area of pasture feed grass (0. 7 kg/m2, from Regulatory Guide 1.109).

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

Ai Nuclide decay constant for nuclide i (sec*1).

Aw Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10*7 sec*1, from NUREG-0133).

(DFLoi)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).

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

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

fs Fraction of the goat feed that is pasture grass while the goat is on pasture (1.0, from Regulatory Guide 1. 109).

tr Transport time from pasture to receptor (l.73E+06 seconds, from Regulatory Guide 1.109).

th Transport time from crop field to receptor (7.78E+06 seconds, from Regulatory Guide l.109).

Section 7 - Page 2 Page 9-84

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Grass/Goat/Me at - Tritium Formula: from NUREG-0133, page 35.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/mea t pathway (mrem/yr per µCi/m 3) . (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/µCi (10 6).

K"' Units conversion factor gm/kg (10 3).

OF Goat consumption rate (6 kg/day, from Reirulatory Guide l.109).

Uap Consumption rate of goat meat for age group a (kg/yr, from Regulatory Guide 1.109).

Adult - 110 Teen - 65 Child - 41 Infant - 0 (DFLoi)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).

Fti Stable element transfer coefficient for nuclide i, in days/kg, from Table E-1 of Regulatory Guide 1.109 for 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).

Section 7 - Page 3 Page 9-85

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2 018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Grass/Goat/Meat - Carbon-14 Roapi = K'K"' Ffi QF Uap (DFL JJO. l l /O. l6](p)(h) 0 F01mula: from NUREG-0133, page 35 and Regulatory Guide 1.109, page 26.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/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 (10 6 ).

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

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

OF Goat consumption rate (6 kg/dav, from Regulatory Guide 1.109).

Uap Consumption rate of goat meat for age group a (kg/yr) (from Regulatory Guide 1.109).

Adult - 110 Teen - 65 Child - 41 lnfant - 0 (DFLoi)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 0.35, based on 70% ofC-14 releases being from WGDTs, and 30% ofC-14 releases being continuous from the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14", 2004; EPRI TR-1024827, "Carbon-14 Dose Calculation Methods at Nuclear Power Plants", 2012, Section 3.2.5).

fi The fraction of C-14 assumed to be in inorganic fonn (e.g., CO2).

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

Section 7 - Page 4 Page 9-86

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

Section 6 - Page 3 Remove TLD Site # 047 from Table 6.0-2 and add 092 as replacement with Location "Hilton Circle stop sign. HWY 188", Distance 3.62 miles, Sector WSW. Change made per DRR 02216696 because TLD 047 was located in bushes/shrubs on private property and can no longer be accessed safely. '.'Jew TLD 092 is in more suitable location.

Section 6 - Page 5 Updated Figure 6.0-1 to refl.Jct standardization to legend descriptions. No changes to sampling locations.

Section 6 - Page 6 Updated :Figure 6.0-2 to reflect removing TLD 047 and replacing with 092. Also standardized legend descriptions. Change made per DRR 02216696 because TLD 047 was located in bushes/shrubs on private prope11y and can no longer be accessed safely. New TLD 092 is in more suitable location.

Appendix C, D. E, and F Added dose factors for Se-75, Ag-108m. Sn-113, Sn-117m, Sb-124, Sb-125, Sb-126, Te-123m, Ba-133, and Eu-152 to Appendix C, D, E, and F for all age groups and applicable pathways per DRR 02195642. ,<\ssessment of Oconee Count Room detennined not all radionuclides listed on liquid waste release pennits have dose factors in the ODCM. Dose factors developed using method described in CSD-RP-ALL-0028.

Appendix G, H. and I Added tables for Adult, Teen, and Child Grass/Goatltv[eat pathway dose factors to Appendix G, H, and I respectively per DRR 02209374. Dose factors developed using method described in CSD-RP-ALL-0029.

Section 7 - Page 5 Page 9-87

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APPENDIX A Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases*

K1 L1 M1 N1 Total Body Skin GammaAJJ- Beta Air Nuclide mrem/yr/ mrad/yr/ mrad/yr/

mrem/yr/

µCi/ni3 µCi/ml µCi/ml µCi/ni3 AR-41 8,840E+03 2.690E+03 9.300E+o3 3 280E+o3 KR-83M 7.560E-02 0.OO0E+OO l.930E+0l 2.880E+02 KR-85M 1.170E+03 l.460E+03 l .230E+03 1.970E+03 KR-85 1.610E+01 1.340E+03 1.720E+Ol 1.950E+03 KR-87 5.920E+03 9.730E+03 6.170E+03 l .030E+o4 KR-88 1.470E+04 2.370E+03 l.520E+04 2.930E+03 KR-89 1.660E+04 l.010E+04 l.730E+04 1.060£+(14 KR-90 1.560E+04 7.290E+03 1.630E+04 7.830E+03 XE-l3JM 9. l50E+01 4.760E+02 l .560E+02 I.I IOE+03 XE- 133M 2.510E+02 9.940E+02 3.270E+02 1.480E+o3 X'E-133 2.940E+02 3.060E+q2 3.530E,02 l.050E+03 XE-l35M 3.120E+03 7.l 10E+02 3.360E+03 7.390E+02 XE-13 5 1.810E+03 1.860E+03 l .9JOE+03 2.460E+o3 XE-137 1.4208+03 I 220E+04 l.510E+03 1 270ll+04 XE-138 8.830E+03 4.130E+03 9.210E+03 4.750E+03

• Reference Regulatory Guide I. l09, Table B-1 Appendix A Dose Faaars far Exposure to a Semi-Infinite Cloud of Noble Gases - Page 1 of I Page 9-88

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIXB P 1Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway: blhalation (INHL) Units: nu*em/yr I µCi/m3 Nuclide Bone Liver Thyroid Kidnev LUD!! Gilli Skin TotalBodv H-3 O.OOOE+OO 1.120E+o3 l.120E+03 l.120E+03 1.120E+03 1.120E+03 O.OOOE+OO l.l20E+03 C-14 3.590E+04 6.730E+03 6.730E+o3 6.730E+03 6.730E+03 6.730E+03 O.OOOE+OO 6.730E+03 NA-24 l.6IOE+04 l.610E+04 \.6lOE+o4 l.610E+04 1.6IOE+04 1.6IOE+04 O.OOOE+OO \.610E+04 P-32 2.600E+06 l .l40E+05 0.C)OOE-+-00 O.OOOE+OO O.OOOE+OO 4.220E+04 O.OOOE+OO 9.880E+04 CR-51 0.000E+oo O.OOOE+OO 8.550E+ol 2.430E+OJ l.700E+04 l.080E+03 O.OOOE+OO l.540E+02 MN-54 O.OOOE+OO 4.290E+04 0.000E+-00 l .OOOE+04 l.580E+06 2.290E+04 O.OOOE+OO 9.510E+03 MN-56 O.OOOE+OO l.660E+OO O.OOOE+OO l.670E+OO l .3IOE+04 1.230E+05 O.OOOE+OO 3.l 20E-OI FE-55 4.740E+04 2.520E+04 O.OOOE-t-00 O.OOOE+OO I.I IOE+OS 2.870E+03 O.OOOE+OO 7.770E+03 FE-59 2.070E+04 3.340E+04 O.OOOE+OO 0.000E+OO l.270E+06 7.070E+04 O.OOOE+OO l.670E+04 C0-5 8 O.OOOE+OO 1.770E+03 0.000E-+-00 O.OOOE+OO l.llOE+06 3.440E+04 O.OOOE+()() 3.160E+03 C0-60 O.OOOE+OO l.3lOE+04 O.OOOE-+-00 O.OOOE+OO 7.070E+06 9.620E+04 O.OOOE+OO 2.260E+04 NI-63 8.210E+05 4.620E+04 O.OOOE+OO 0.000E+OO 2.750E+05 6.330E+03 O.OOOE+OO 2.800E+04 NI-65 2.990E+OI) 2.%0E-01 O.OOOE-+-00 0.000E+oo 8.180E+03 8.400E+04 O.OOOE+OO l.640E-01 CU-64 O.OOOE+OO l.990E**OO 0.000E+OO 6.030E*100 9580E+03 3.670E+04 O.OOOE+OO l.070E+OO ZN-6 5 4.260E+04 l.l30E+-05 0.000E+OO 7.l40E+04 9.950E+05 i.630E+04 O.OOOE+()(l 7.030E+04 ZN-69 6.700E-02 9.660E-02 O.OOOE+oo 5.SSOE-02 1.420E+03 l.020E+04 0.000E+OO 8.920E-03 BR-83 0.000E+OO O.OOOE+oO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 4.740E+02 BR-84 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.480E+02 BR-85 O.OOOE-+-00 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.530E+OI RB-86 O.OOOE+OO l.980E+05 0.000E+{~J O.OOOE+OO O.OOOE+OO 7.990EHl3 0.000E+OO 1.140E+05 RB-88 0.000E+OO 5.620E+o2 O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.720E+OI O.OOOE+OO 3.660E+02 RB-89 O.OOOE+Oll 3.450E+02 O.OOOE+oO O.OOOE+OO O.OOOE+OO l.890E+OO 0.000E+OO 2.900E+02 SR-89 5.990E+05 0.000E+OO O.OOOE+OO O.OOOE+OO 2.160E+06 1.670E+05 O.OOOE+OO l.720E+04 SR-90 l.OIOE+08 O.OOOE+OO o.oom+oo O.OOOE+OO l.480E+07 3.430E+05 O.OOOE+()() 6.440E+06 SR-9 1 l.210E+02 O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.330E+04 l.740E+05 0.000E+OO 4.590E+OO Appendix B Pi Child Inhalation - Page I of 3 Page 9-89

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offa1te Dose Calculat,on Manual (ODCM)

APPENDIXB P1Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway: Inltalation (INHL) Units: mrem/y r / µCi/m 3 Nuclide Bone Liver Thyroid Kidney Lun2 Gilli Skin Total Bodv SR-92 l.3 10E+OI 0.000E+oO 0.000E+-00 O.OOOE+OO 2.400E+04 2.420E+05 0.000E+OO 5.250£-01 Y-90 4.110£+03 O.OOOE+OO O.OOOE+*JO O.OOOE+OO 2.620E+05 2.680E+o5 O.OOOE+OO 1.I IOE+02 Y-91 9.140E+0.5 O.OOOE+oo O.OOOE+oO O.OOOE+OO 2.630E+06 l.840E+05 O.OOOE+OO 2.440E+04 Y-9 1M 5.070£-01 O.OOOE+oo O.OOOE+OO O.OOOE+oo 2810E+<J3 1.720£+-03 O.OOOE+OO 1.840£.02 Y-92 2.030E+OI O.OOOE+oO O.OOOE+OO O.OOOE+OO 2.390E+04 2.390E+05 O.OOOE+OO 5.810E.01 Y-93 l.860E+02 O.OOOE+OO O.OOOE+-00 O.OOOE+OO 7.440£+04 3.880E+-05 0.000E+OO 5.II OE+OO ZR-95 l.900E+05 4.180£+04 O.OOOE+OO 5.960E+04 2.230E+06 6.110E+04 O.OOOHOO 3.700E+04 ZR-97 1.880£+02 2.720E+o l O.OOOE+oO 3.880E+OI l.1 30E+<l5 3.510£+05 O.OOOE+OO l.600E+OI NB-95 2.350£+04 9.180£+03 0.000E+OO 8.620E+03 6.140E+05 3.100E+04 0.000E+OO 6.550E+03 M0-99 0.000E+OO l.120E+02 O.OOOE+-00 3.920E+02 l.350E+-05 l.270E+05 O.OOOE+OO 4.260E+01 TC-99M l.780E-03 3.480E-03 U.OOOE+OO 5.070E.02 9. 510£+02 4.810E+o3 O.OOOE+OO 5.770£.02 TC-101 8.IOOE--05 8.510E-05 0.000E+-00 1.450£-03 5.850£+02 f.630E+Ol 0.000E+OO l.080E.Q3 RU-103 2.790£+03 O.OOOE+OO O.OOOE+OO 7.030E+03 6.620E+05 4.480E+o4 O.OOOE+OO l.070E+03 RU-105 1.530E+OO 0.000E+OO O.OOOE+OO 1.340E+OO l.590E+04 9.950E+04 O.OOOE+OO 5.550£.Ql RU- 106 1.360£+05 0.000E+OO O.OOOE+oO 1.840E+05 l.430E+01 4.290E+OS 0.000£+()1) l.690E+04 AG-llOM 1.690£+04 1.140£+04 0.000E+oO 2.120E+04 5.480E+06 1.000E+05 0.000E+OO 9.140E+03 TE-125M 6.730£+03 2.330E+o3 l.920E+o3 O.OOOE+OO 4.770E+05 3.380E+04 0.000E+OO 9. l40E+02 TE-127 2.770E+OO 9.510£-01 1.960E+OO 7.070E+OO 1.000E+04 5.620E+04 0.OOOE+OO 6.IOOE.01 TE-127 M 2.490E+04 8.550£+03 6.070£+()3 6.360E+04 1.480E+06 7.140E+04 O.OOOE+OO 3.020E+03 TE- 129 9 770E-02 3.500E-02 7.140E.02 2.570E-01 2.930E+03 2.550E+04 O.OOOE+OO 2.380£-02 TE-129M 1.920£+04 6.840E+03 6.330E+-03 5.030E+04 l.760E+06 I 820E+05 OOOOE+OO 3.040E+03 TE-131 2.170£-02 8.440E-03 1.700£.02 5.880E.02 2.0SOE+o3 l.330E+o3 O.OOOE+OO 6.590£.03 TE-131M l.340E+O: 5.920E+Ql 9.170£+0 I 4.000£+02 2.060E+05 3.080£+05 0.000E+OO 5.070E+Ol TE- 132 4.8l0E+02 2.720E+02 3. l10E+o2 l.710E+03 3.170E+-05 l.380E+05 O.OOOE+OO 2.630£+02 l-130 8.l80E+03 1.640E+04 1.850E+06 2.450E* 04 O.OOOE+OO 5.110E+03 O.OOOE+OO 8.440E+03 Appendix B Pi Child Inhafation

• Page 2 of 3 Page 9-90

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offaite Dose Calculation Manual (ODCM)

APPENDIXB P1Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway : Inhalation (INHL) Units : nu*em/yr / µCi/1113 Nuclide Bone Liver Thyroid Kidney Lon!! Gilli Skin 'fotalBody 1-131 4.810E+04 4.810E+o4 l.620E+07 7.880E+04 O.OOOE+OO 2.840E+03 0.000E+OO 2.730E+04 1-1 32 2. 120E+03 4.070E+03 1.940E+05 6.250E+03 O.OOOE+OO 3.200E+03 O.OOOE+OO l.880E+03 1-133 l.660E+04 2.030E+04 3.850E+06 3.380E+04 O.OOOE+OO 5.480E+03 O.OOOE+OO 7.700E+03 1-134 l.170E+03 2.160E+o3 5.070E+04 3.300E+03 O.OOOE+oO 9.550E+02 O.OOOE+OO 9.950E+o2 1-135 4.920E+03 8.730E+03 7.920E+05 l .340E+04 O.OOOE+OO 4.440E+03 0.000E+OO 4.140E+03 CS-134 6.510E+05 l.OIOE+06 O.OOOE+oO 3.300E+05 l.210E+05 3.850E+03 O.OOOE+OO 2.250E+05 CS-136 6.510E+04 l.710E+05 O.OOOE+OO 9.550E+04 1.450E+04 4.180E+03 O.OOOE+OO l.160E+05 CS-137 9.060E+05 8.250E+o5 0.000E+OO 2.820E+05 l.040E+o5 3.620E+03 O.OOOE+OO 1.280E+05 CS- 138 6.330E+02 8.400E+02 O.OOOE+OO 6.220E+02 6.8IOE+Ol 2.700E+02 0.000E+OO 5.550E+02 BA-139 l.840E+OO 9.840E-04 O.OOOE+OO 8.620E-04 5.770E+03 5.770E+04 0.000E+OO 5.360E-02 BA- 140 7.400E+04 6.480E+ol O.OOOE+OO 2.llOE+OI l.740E+06 l.020E+05 O.OOOE+OO 4.330E+03 BA-141 l.960E-Ol 1.090E-04 O.OOOE+OO 9.470E-05 . 2.920E+03 2.750E+02 0.000E+OO 6.360E-03 BA- 142 5.000E-02 3.600E-05 O.OOOE+OO 2.910E-05 l.640E+03 2.740E+OO O.OOOE+OO 2.790E-03 LA-140 6.440E+02 2.250E+02 O.OOOE+OO O.OOOE+OO I.830E+05 2.260E+05 O.OOOE+OO 7.550E+OI LA-142 l.300E+OO 4.IIOE-01 O.OOOE+oO O.OOOE+OO 8.700E+03 7.580E+04 O.OOOE+OO l.290E-Ol CE-141 3.920E+04 1.950E+04 O.OOOE+oO 8.550E+03 5.440E+05 5.660E+04 0.000E+OO 2.900E+03 CE-143 3.660E+02 l.990E+o2 O.OOOE+OO 8.360E+Ol l.150E+o5 l.270E+05 O.OOOE+OO 2.870E+Ol CE-144 6.770E+06 2.120E+06 O.OOOE+OO 1 J70E+06 1.200E+07 3.&80E+05 O.OOOE+OO 3.610E+05 PR-1 43 1.850E+o4 5.550E+03 O.OOOE+OO 3.000E+03 4.330E+05 9.730E+04 O.OOOE+OO 9.140E+02 PR-144 5.960E-02 1.8505-02 O.OOOE+{IO 9.770E-03 1.570E+03 1.970E+02 O.OOOE+OO 3.000E-03 ND-147 l.080E+04 8.730E+o3 O.OOOE+OO 4.810E+03 3.280E+05 8.210E+04 O.OOOE+OO 6.810E+02 W- 187 l.630E+Ol 9.660E+OO 0.000E+oO 0.000E+OO 4.1IOE+04 9.IOOE+04 0.000E+OO 4.330E+OO NP-239 4.660E+02 3.340E+O l 0.000E+OO 9.730E+Ol 5.810E+04 6.400E+04 O.OOOE+OO 2.350E+O l Appendix B Pi Child Inhalation - PRgc 3 of l Page 9-91

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation t.-fanual (ODCM)

APPENDIXC A1 Adult Dose Factors for use in the Liquid Dose Calculations Age group: ADULT Pathway : Potable Water (PWtr) Units: mrem/ltr / µCi/ml Nuclide Bone Liver Thyroid Kidnev Lun!! Gilli Skin TotalBodv H-3 O.OOOE+OO 8.740E+OO 8.740E+OO 8.740E+OO 8.740E+OO 8.740E+OO O.OOOE+OO 8.740E+OO C- 14 2.360E+02 4.730E+Ol 4.730E+<) l 4.730E+Ol 4.730E+Ol 4.730E+Ol O.OOOE+OO 4.730E+Ol NA-24 8.140E+OI 8.140E+OI 8.l40E+O I 8.l40E+Ol 8.l40E+OI 8.140E+O l O.OOOE+OO 8.l40E+OI p.32 l.570E+04 9.750E+02 O.OOOE+OO O.OOOE+OO O.OOOE+oo 1.760E+o3 0.000E+OO 6.060E+02 CR-51 0.000E+OO O.OOOE+OO l.3IOE-OI 4.820E-02 2.900E-Ol 5.500E+Ol O.OOOE+OO 2.190E-Ol MN-54 O.OOOE+OO 3.800E+02 0.000E+OO l.130E+02 O.OOOE+OO l.160E+o3 O.OOOE+OO 7.250E+Ol MN-56 O.OOOE+OO 3.SOOE-01 O.OOOE+OO 4.820E-OI 0.000E+OO l.210E+Ol O.OOOE+OO 6.740E-02 FE-55 2.290E+02 l.580E+o2 O.OO<)E+OO O.OOOE+OO 8.820E+O I 9.070E+OI O.OOOE+(K) 3.690E+OI FE-59 3.580E+02 8.420E+02 O.OOOE+OO O.OOOE+OO 2.350E+02 2.810E+03 0.000E+OO 3.230E+02 CO-58 0.000E+OO 6.l70E+OI 0.000E+OO O.OOOE+OO 0.000E+OO l.250E+03 O.OOOE+OO l.380E+02 C0-60 O.OOOE+OO l.780E+02 O.OOOE+OO 0.000E+OO O.OOOE+OO 3.340E+03 O.OOOE+OO 3.930E+02 NI-63 l.080E+04 f500E+02 0.000E+OO 0.000E+OO O.OOOE+OO 1.560E+02 O.OOOE+OO ' 3.630E+<)2 Nl-65 l.620E+OO 2.IOOE-01 O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.340E+OO O.OOOE+OO 9.600E-02 CU-64 0.000E+OO 3.590E+OO O.OOOE+OO 9.060£-100 O.OOOE+OO 3.060E+02 O.OOOE+OO l.690Et00 ZN-65 4.020E+02 1.280E+o3 O.OO<lE+oo 8.560E+02 O.OOOE+OO 8.060E+02 O.OOOE+OO 5.780E+02 ZN-69 J.O?OE-04 2.050E-04 O.OOOE+OO 1.330E-04 O.OOOE+OO 3.0800-05 O.OOOE+OO l.430E-05 SE-75 l.038E+02 3.991E+Ol 3.991E+Ol 7.983E+OO 9.579E+Ol l.l 18E+02 O.OOOE+OO 7.983E+02 I BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO l.480E-Ol O.OOOE+OO l.030E-01 BR-84 O.OOOE+-00 0.000E+OO 0.000E+OO O.OOOE+OO 0.000E+OO 5.2700-12 O.OOOE+OO 6.7IOE-07 BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+{IO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 4.380E-77 RB-86 0.000E+OO I 720E+o3 O.OOOE+otl O.OOOE+OO O.OOOE+OO 3.400E+02 0.000E+OO 8.030E+n2 RB-88 O.OOOE+OO 3.360E-12 0.000E+OO 0.000E+OO 0.000E+OO 4.640E-23 0.000E+OO l.780E-12 RB-89 O.OOOE+OO 3.090E- 14 O.OOOE+OO 0.000E+OO 0.000E+OO l.790E-27 O.OOOE+OO 2.170E-14 SR-89 2.550E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.080E+03 O.OOOE+OO 7.310E+02 SR-90 6.310E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO l.820E+04 O.OOOE+OO l.550E+05 Append.be C Ai Adtlt Water

• Page I of 4 Page 9-92

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIXC A1Adult Dose Factors for use in the Liquid Dose Calculations Age group: ADULT Pathway: Potable Water (PWtr) Units: nu-em/hr/ µCi/ml Nuclide Bone Liver Th:vroid Kidne:v Lun2 Gilli Skin TotalBod:v SR-91 1.960E+02 0.000E+oO O.OOOE+-00 O.OOOE+OO O.OOOE+oo 9.350E+02 O.OOOE+OO 7.930E+OO SR-92 8.290E+OO O.OOOE+oo O.OOOE+<lO O.OOOE+OO O.OOOE+OO 1.640E+o2 O.OOOE+OO 3.590E-Ol Y-90 7.030E-01 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 7.460E+03 O.OOOE+OO 1.890E-O'.!

Y-91 1.170E+OI 0.000E+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO 6.420E+03 O.OOOE+OO 3.120E-01 Y-91M 3.360E-07 O.OOOE+-00 O.OOOE+OO O.OOOE+OO O.CIOOE+OO 9.8600-07 O.OOOE+OO l .300E-08 Y-92 6.710E-03 0.000E+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO 1.170E+02 O.OOOE+OO 1.960E-04 Y-93 9.770E-02 O.OOOE+-00 O.OOOE+OO 0.000E+OO O.OOOE+OO 3.100E+03 O.OOOE+OO 2.700E-03 ZR-95 2.520E+oo 8.070E-01 O.OOOE+oo 1.270E+OO O.OOOE+oo 2.560E+03 O.OOOE+OO 5.460E-01 ZR-97 8.540E-02 1.720£..02 O.OOOE+OO 2.600E-02 O.OOOE+OO 5.340E+03 O.OOOE+OO 7.880E-03 NB-95 5.130E-OI 2.850E-OI 0.000E+OO 2.820E-Ol O.OOOE+oo l.730E+o3 O.OOOE+OO 1.530E-01 M0-99 O.OOOE+OO 3.160E+02 O.OOOE+OO 7.160E+02 O.OOOE+OO 7.330E+o2 0.000E+OO 6.020E+Ol TC-99M 5.160E-03 1.460E-02 O.OOOE+-00 2.2!0E-Ol 7.140E-03 8.630E+OO O.OOOE+OO 1.860E-OI TC-IOI 1.130E-l 7 1.630E-17 O.OOOE+OO 2.930E-16 8.320E-18 4.890E-29 O.OOOE+OO 1.600E-16 RU-103 1.530E+OI O.OOOE* OO O.OOOE+OO 5.820El0l O.OOOE+OO l.780E+03 O.OOOEl*OO 6.570E+OO RU-105 1.970E-OI O.OOOE+OO O.OOOE+OO 2.540E+OO O.OOOE+OO 1.200E+02 O.OOOE+OO 7.760E-02 RU-106 2.290E+02 O.OOOE+OO 0.000E+oo 4.410E+02 O.OOOE*OO l.480E+04 O.OOOE+OO 2.890E+Ol AG-!08M AG-llOM 9.207E+Ol 1 330E+OI 3.541E+OI 1230E+Ol 3.541E+ol O.OOOE+OO 7.082E+OO 2.420E+Ol 8.498E+Ol O.OOOE+OO 9.915E+Ol 5.020E+03 0.000E+oo O.OOOE+OO 7.082E+02 7.300E+OO I

SN-113 2.913Ei--Ol l.1 21E+OI 1.121E+ol 2.24\E+OO 2.689E+OI 3.137E+Ol O.OOOE+OO 2.241E+02 SN-117M 2.771E+Ol I.066E+01 1.066E+{II 2.131E+OO 2.557E+OI 2.984E+-Ol OOOOE+OO 2.131E+02 SB-124 2.317E+02 4.377E+OO 5.618E-01 O.OOOE+OO l.804E+02 6.578E+03 O.OOOE+OO 9.l84E+OI SB-125 l.489E+02 l.664E+OO l.514E-OI O.OOOE+oo l.148E+02 l.639E+03 0.000E+OO 3.544E+Ol SB-126 9.307E+OI 1.894E+OO 5.697E-Ol O.OOOE+OO 5.705E+OI 7.607E+03 0.000E+OO 3.358E+Ol TE-123M 5.588E+Ol 2.149E+ol 2.149E+ol 4.298E+OO 5.158E+Ol 6.018E+Ol O.OOOE+OO 4.298E+02 TE-125M 2.220E+02 8030E+Ol 6.670E+OI 9.020E* 02 O.OOOE+OO 8.850E+02 O.OOOE+OO 2.970E+Ol Appmd1x C Ai Ad1lt Wafer - Page 2 of 4 Page 9-93

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offs1te Dose Calculation Manwl (ODCM)

APPENDIXC A1 Adult Dose Factors for use in the Liquid Dose Calculations Age group: ADULT Pathway: Potable Water (PWtr) Units: nu*em/br / µ(.."'i/ml Nuclide Bone Liver Thyroid Kidnev Lune Gilli Skin TotalBodv TE-127 3.780E+OO l .360E+OO 2.800E+OO l.540E+01 O.OOOE+OO 2.980E+02 O.OOOE+OO 8.170E-OI TE-127M 5.620E+02 2.0IOE+02 l.440E+fJ2 2.280E+03 O.OOOE+OO l.880E+03 O.OOOE+OO 6.840E+01 TE-129 l.920E-03 7.2.lOE-04 l.480E-03 8.0SOE-03 0.000E+OO 1.4500-03 O.OOOE+OO 4.690E-04 TE-129M 9.470E+o2 3.530E+o2 3.250E+o2 3.950E+03 O.OOOE+oO 4.770E+03 O.OOOE+OO l .500E+02 TE-131 3.520E-09 1.470E-09 2.900E-09 l.540E-08 O.OOOE+OO 4.990E-10 O.OOOEf-00 l.1 lOE-09 TE-131M l.090E+02 5.340E+Ol 8.450E+O l 5.400E+02 0.000E+OO 5.300E+o3 O.OOOE+OO 4.450E+Ol TE-132 l.880E+02 l.220E+o2 1.350E+o2 1.170E+03 O.OOOE+OO 5.770E+03 O.OOOE+OO 1.140E+02 I-130 3.210E+01 9.460E+o l 8.020E+o3 l.480E+02 0.000E+OO 8. 140E+Ol O.OOOE+OO 3.730E+Ol I-131 3.320E+02 4.740E+02 l.550E+05 8.130E+02 O.OOOE+OO 1.250E+02 0.000E+OO 2.720E+02 1- 132 4.540E-0 1 l.220E+OO 4.250E+O l l.940E+OO O.OOOE+OO 2.280E-O l O.OOOE+OO 4.250E-O l 1- 133 7.920E+Ol l.380E+02 2.020E+04 2.400E+02 O.OOOE+OO l.240E+02 O.OOOE+OO 4.200E+Ol 1-134 6.580E-04 1.790E-03 3.IOOE-02

• 2.840E-03 O.OOOE+OO l.560E-06 0.000E+OO 6.390E-04 1-135 1.050E+01 2.750E+Ol l.8IOE+03 4.400E+Ol O.OOOE+OO 3.IOOE+OI O.OOOE+OO 1.0IOE+Ol CS-134 5.170E+03 l .2.30E+04 0.000E+OO 3.980E+03 1.320E+03 2.150E+02 O.OOOEIOO l.010E+04 CS-136 5.280E+02 2.081JE+03 O.OOOE+OO l.160E+03 l.590E+02 2.370E+02 O.OOOE+OO l.500E+03 CS-137 6.630E+03 9.070E+03 O.OOOE+OO 3.080E+03 l.020E+03 l.760E+02 O.OOOE+OO 5.940E+03 CS-13& 8.450E-07 l.670E-06 O.OOOE+OO U30E-06 l.2IOE-07 7.l20E-12 O.OOOE+OO 8.260E-07 BA-133 6.004E+Ol 2.309E+Ol 2.309E+Ol 4.6!8E+OO 5.542E+Ol 6.466E+Ol O.OOOE+OO 4.618E+02 I BA-139 1 990E-02 l.420E-05 O.OOOE+oO 1.330E-05 8.050E-06 3.530E-02 O.OOOE+OO 5.830E-04 BA-140 1.640E+03 2.070E+OO OOOOE+{IO 7.0208-01 1.180E+OO 3.390E+03 O.OOOE+OO l.080E+02 BA-14 1 5.440E-12 4.!20E- l 5 0.000E+-00 3.830E-15 2.340E-l5 2.570E-21 O.OOOE+OO l.840E-13 BA-142 6.290E-2l 6.470E-24 O.OOOE+oo 5.460E-24 3.660E-24 8.860E-39 O.OOOE+OO 3.960E-22 LA- 140 l .690E-Ol 8.530E-02 0.000E+oO 0.000E+OO O.OOOE+OO 6.260E+03 O.OOOE+OO 2.250E-02 LA-1.42 5.720E-05 2.600E-05 O.OOOE+oo O.OOOE+OO O.OOOE+OO l.900E-Ol O.OOOE+OO 6.480E-06 CE- 141 7.?IOE-01 5.2!0E-0I 0.000E+OO 2.420E-Ol O.OOOE+OO l.990E+03 O.OOOE+OO 5.9IOE-02 Appmd1x C Ai Adtlt Wafer

• P2gc 3 of 4 Page 9-94

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation !1,1anual (ODCM)

APPENDIXC A1Adult Dose Factors for use in the Liquid Dose Calculations Agegmup: ADULT Pathway: Potable Water (PWtr) Units: nu*em/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lun2 Gilli Skin TotalBodv CE-143 i.070E..QI 7.890E+ol O.OOOE+OO 3.470E..Q2 O.OOOE+OO 2950E+03 O.OOOE+OO 8.730E-03 CE-144 4.0(,()E+OI l.700E+Ol O.OOOE+OO l.OIOE+OI O.OOOE+OO l.370E+04 O.OOOE+OO 2.180E+OO PR-143 7.460E-OI 2.990E-Ol O.OOOE+OO l.730E-Ol O.OOOE+OO 3.270E+03 O.OOOE+OO 3.700E-O'.!

PR-144 7.350E-16 3.0SOE-16 O.OOOE+OO l.720E-16 O.OOOE+oO l.060E-22 O.OOOE+OO 3.730E-17 ND-147 5.Q70E-OI 5.860E-Ol O.OOOE+OO 3.430E-Ol 0.000E+OO 2.8\0E+03 O.OOOE+OO 3.5\0E-02 EU-152 W-187 l.623E+Ol 6.050E+OO 3.695E+OO 5.050E+o0 O.OOOE+-00 O.OOOE+OO 2.288E+OI 0.000E+OO O.OOOE+OO O.OOOE+OO 2.130E+o3 1.660E+03 0.000E+OO O.OOOE+OO 3.245E+OO l.770E+OO I

NP-239 8.550E..o:? 8.400E-03 O.OOOE+OO 2.620E-02 0.000E+OO i.720E+03 O.OOOE+OO 4.630E-03 Appendix C Ai A<ktlt Water* Page 4 of 4 Page 9-95

• - Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offa1tc Dose Calculatton Manual (ODCM.)

APPENDIXC A1 Adult Dose Factors for use in the Liquid Dose Calculations Age group: ADULT Pathway: Fresh Water Fish - Sport (FFSP) Units: nu*em/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lun2 Gilli Skin Total Body H-3 0.000E+OO 2.260E-Ol 2.260E-Ol 2.2GOE-O l 2.260E-Ol 2.260E..O l O.OOOE+OO 2.260E..Ol C- 14 3.130E+04 6.260E+03 6.260E+<J3 6.260E+03 6.260E+03 6.260E+03 O.OOOE+OO 6.260E+03 NA-24 1.350E+02 J.350E+02 1.350E+02 l.350E+02 l.350E+02 l.350E+02 O.OOOE+OO l .350E+O~

P-32 l.320E+06 8.210E+04 O.OOOE+oO 0.000E+OO O.OOOE+OO 1.480E+05 O.OOOE+OO 5.IOOE+04 CR-51 O.OOOE+OO 0.000E+OO 7.420E-Ol 2.740E-Ol l.650E+OO 3. l20E+02 O.OOOE+OO l.240E+OO MN-54 O.OOOE+OO 4.370E+03 O.OOOE+OO l.300E+03 O.OOOE+OO l.340E+04 O.OOOE+OO 8.330E+02 MN-56 O.OOOE+OO l.730E-Ol O.OOOE+oo 2.2(U)E-0J O.OOOE+OO 5.530E+OO O.OOOE+OO 3.070E-02 FE-55 6.580E+02 4.550E+o2 O.OOOE+oo O.OOOE+OO 2.540E+o2 2.6lOE+02 O.OOOE+OO l.060E+02 FE-59 l.020E+03 2.400E+03 O.OOOE+OO O.OOOE+O<.l 6.720E+02 8.0lOE+03 O.OOOE+OO 9.220E+02 CO-58 O.OOOE+OO 8.830E+Ol O.OOOE+oo O.OOOE+OO 0.000E+OO 1.790E+03 O.OOOE+OO l.980E+02 C0-60 O.OOOE+OO 2.560E+02 O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.810E+03 O.OOOE+OO 5.650E+02 Nl-63 3.11 0E+04 2.160E+03 O.OOOE+OO O.OOOE+OO 0.000E+OO 4.500E+02 O.OOOE+OO l.040E+03 Nl-65 l.720E-Ol 2.230E-02 O.OOOE+oO O.OOOE+oo O.OOOE+OO 5.660E..O l O.OOOE+OO l.020E..02 CU-64 O.OOOE+OO 2.680E+OO O.OOOE+OO 6.760E+OO 0.000E+OO 2.290E+02 0.000El-00 l.260E+OO ZN-65 2.310E+04 7.350E+04 0.000E+OO 4.9208+04 O.OOOE+OO 4.630E+04 O.OOOE+OO 3.320E+04 ZN-69 7.730E-07 l.480E-06 O.OOOE+OO 9.610E..07 0.000E+OO 2.220E-07 O.OOOE+OO l .030E..07 SE-75 5.953E+02 :2.290E+02 2.290E+02 4.579E+OI 5.495E+02 6.41 IE+02 O.OOOE+OO 4.579E+03 I BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO 5.500E-02 O.OOOE+OO 3.820E-02 BR-84 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 9.850E-18 O.OOOE+OO l.250E-12 BR-85 O.OOOE+OO 0.000E+OO 0.000E+{IO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO RB-86 o OOOE+OO 9730E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO l.920E+04 O.OOOE+OO 4.530E+04 RB-88 O.OOOE+OO 1.290E-22 0.000E+OO 0.000E+OO O.OOOE+OO l.780E-33 O.OOOE+OO 6.830E-23 RB-89 O.OOOE+OO l.640E-26 0.000E+oo 0.000E+OO O.OOOE+OO 9.560E-40 O.OOOE+OO l.160E-26 SR-89 2.180E+04 0.000E+oo O.OOOE+oo 0.000E+OO O.OOOE+OO 3.500E+03 O.OOOE+OO 6.260E+02 SR-90 5.440E+05 O.OOOE+OO O.OOOE+OO O.OOOEl-00 O.OOOE+OO l. 570E+04 0.000E+OO l .340E+05 Appcndi.'- C Ai Adult Fi5h - Page 1 of 4 Page 9-96

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Ocano¢ Nuclear Station Offaite Dose Calculation Manual (ODCM)

APPENDIXC A1Adult Dose Factors for use in the Liquid Dose Calculations Age group: ADULT Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thvroid Kidnev Lune Gilli Skin TotalBod:v SR-91 7.050E+OI O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.360E+02 O.OOOE+OO 2.850E+OO SR-92 3.320E-01 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 6.570E+OO O.OOOE+OO l.430E-02 Y-90 4.440F.-O l O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.710E+03 O.OOOE+OO 1.l 90E-02 Y-91 8.340E+OO 0.000E+oo O.OOOE+-00 O.OOOE+OO O.OOOE+oo 4.590E+o3 O.OOOE+OO 2.230E-Ol Y-91M l.070E-ll 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 3.ISOE-l l 0.000E+OO 4.l50E-l3 Y-92 4.600E-04 0.0C)OE+OO O.OQOE+{IO O.OOOE+OO 0.000E+OO 8.060E+o0 O.OOOE+OO l.340E-05 Y-93 3.080E-02 O.OOOE+oo O.OOOE+-00 0.000E+OO 0.000E+OO 9.770E+02 O.OOOE+OO 8.SOOE-04 ZR-95 2.380E-Ol 7.620E-O'.! O.OOOE-t-00 l.200E-Ol O.OOOE+oo 2.410E+02 O.OOOE+OO 5.160E-02 ZR-97 4.960E-03 1.0008-03 0.000E+OO 1.SIOE-03 O.OOOE+oo 3.lOOE+02 0.000E+OO 4.570E-04 NB-95 4.380E+02 2.440E+02 0.000E-t-00 2.4lOE+02 0.000E+OO l.480E+o6 0.000E+OO l.310E+02 M0-99 O.OOOE+OO 8.020E+ol 0.000E+OO 1.820E+02 O.OOOE+oo 1.860E+02 O.OOOE+OO 1.530E+OI TC-99M 5.590E-04 l.580E-03 O.OOOE+OO 2.400E-02 ' 7.740E-04 9.340E-OI 0.000E+OO 2.0lOE-02 TC-IOI 2.610E-33 3.760E-33 O.OOOE+OO 6.770E-32 l.920E-33 1.l30E-44 O.OOOE+OO 3.690E-32 RU-103 4.350E+OO 0.000E* OO O.OOOE+OO l.660E* OI 0.000E+OO 5.080E+02 O.OOOE*IOO l.870E+-OO RU-105 8.670E-03 O.OOClE+oO 0.000E+oO 1.120E-OI 0.00,)E+OO 5.300E+OO O.OOOE+OO 3.420E-03 RU-106 6.570E+OI 0.000E+OO 0.000E+o0 l.270E+02 O.OOOE+OO 4.250E+03 0.000E+OO 8.320E+OO AG-l08M AG-llOM

.648E+OI 8.790E-OI l.019E+ol 8.1308-01 I.Ol9E+Ol O.OOOE+-00 2.037E+OO I 600E+OO 2.445E+Ol 0.000E+OO 2.852E+OI 3.320E+02 O.OOOE+oo O.OOOE+OO 2.037E+02 4.830E-01 I

SN-113 2.507E+03 9.6-11E+02 9.641Et02 l.928E+02 2.314E+03 2.699E+03 O.OOOE+OO 1.928E+04 SN-117M 2.331E+03 8.965E+02 8.965E+{l2 l.793E+02 2.152E+03 2.510E+03 O.(IOOE+OO 1.793E+04 SB-124 6.626E+02 U52E+ol l.607E+OO O.OOOE+OO 5.159E+02 l.88IE+04 O.OOOE+oo 2.627E+02 SB-125 4.282E+02 4.785E+OO 4.354E-Ol O.OOOE+OO 3.301E+02 4.7l3E+o3 O.OOOE+OO l.019E+02 SB-126 2.603£+02 5.297E+OO l.594E+OO 0.000E+OO l.596E+02 2.128E+04 O.OOOE+OO 9.395E+OI TE-123M 6.41\E+02 2.466E+o2 2.466E+o2 4.932E+OI 5.918E+02 6.904E+02 O.OOOE+OO 4.932E+03 TE-125M 2.540E+03 9.190E+02 7.630E+02 l.030E+04 O.OOOE+OO l.Ol0E+04 O.OOOEtOO 3.400E+02 Appendix C Ai Adnh Fish ~ Page 2 of 4 Page 9-97

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offsitc Dose Calculet,on Memml (ODCM)

APPENDIXC A, Adult Dose Factors for use in the Liquid Dose Calculations Age gmup: ADU LT Pathway: Fresh Water f<'lsh - Sp011 (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lune Gilli Skin Total Body TE-1 27 l.790E+Ol 6.440E+OO l.330E+OI 7.300E+OI O.OOOE+-00 l.410E+03 O.OOOE+OO 3.880E+OO TE-127M 6.440E+03 2.300E+03 l.650E+<l3 2.620E+04 O.OOOE+OO 2.160E+04 0.000E+OO 7.850E+02 TE-129 l.630E-05 6.120E-06 1.250E-05 6.850E-05 O.OOOE+OO 1.230E-05 O.OOOE+OO 3.970E-06 TE-129M 1.080E+04 4.010E+03 3.7IOE+-03 4.500E+04 O.OOOE+-00 5.430E+04 O.OOOE+OO 1.71 0E+03 TE-131 8.710E-17 3.640E-17 7.160E-17 3.820E-16 O.OOOE+OO l.230E-17 O.t11JOE+OO 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+OO 3.880E+02 TE-132 l.950E+03 l.260E+03 1.390E+03 1.210E+04 0.000E+OO 5.960E+04 O.OOOE+OCl l.l80E+03 I- 130 7.050E+-OO 2.080E+-O I 1.760E+03 3.250E+O l O.OOOE+-00 1.790E+Ol O.OOOE+OO 8.210E+OO I-131 1.370E+02 l.960E+02 6.420E+04 3.360E+02 0.000E+OO 5.170E+Ol O.OOOE+OO 1.120E+02 1-132 5.270E~)3 1.410E-02 4.940E-01 2.250E-02 O.OOOE+-00 2.650E-03 O.OOOE+OO 4.940E-03 I-133 2.290E+Ol 3.990E+Ol 5.860E+03 6.950E+Ol O.OOOE+OO 3.580E+-01 O.OOOE+OO l.210E+Ol 1-134 2.120E-08 5.750E-08 9.960E-07 9.140E-08 O.OOOE+OO 5.0IOE-1 1 0.000E+OO 2.060E-08 I-135 l.290E+OO 3.370E+OO 2.220E+02 5.41 0E+OO O.OOOE+OO 3.8JOE+OO O.OOOE+OO l.240E+OO CS-134 2.9SOE+05 7.080E

• 05 O.OOOE+OO 2.290E+05 7.610E+04 l..240E+04 O.OOOE+OO 5.790E+05 CS-136 2.960E+04 J.l 70E+-05 O.OOOE+{I() 6.500E+04 8.900E+03 1.330E+04 O.OOOE+OO 8.400E+04 CS-137 3.820E+05 5.220E+05 0.000E+-00 l.770E+05 5.890E+04 I.OlOE+04 0.000E+OO 3.420E+05 CS-138 8.940E-12 l.770E-11 O.OOOE+-00 l.300E-ll L280E- 12 7.530E-17 O.OOOE+OO 8.750E-12 BA-133 6.908E+OO 2.657E+OO 2.657E+-OO 5.31 4E-01 6.376E+OO 7.439E+otJ O.OOOE+OO 5.314E+Ol I BA-139 5.650E-06 4030E-09 O.OOOE+QO 3.760E-09 2.280E-09 l.OOOE-05 O.OOOE+OO l.660E-07 BA-140 1.840E+02 2.310E-01 O.OOOE+c10 7.860E-02 1.320E-Ol 3.790E*t-02 O.OOOE+OO 1.210E+OI BA-141 8.700E-25 6.580E-28 OOOOE+oll 6.120E-28 3.730E-28 4 JOOE-34 O.OOOE+OO 2.940E-26 BA-142 2.570E-42 2.640E-45 O.OOOE+-00 2.230E-45 l.490E-45 3.620E-60 O.OOOE+OO L610E-43 LA-140 9.900E-02 4.990E-02 O.OOOE+oo 0.000E+OO 0.000E+OO 3.660E+03 O.OOOE+OO l.320E-02 LA-142 2.210E-07 l.OOOE-07 O.OOOE+oo O.OOOE+OO O.OOOE+-00 7.3300-04 O.OOOE+O<) 2.500E-08 CE-141 2.190E-02 l.480E-02 O.OOOE+OO 6.890E-03 O.OOOE+OO 5.670E+OI O.OOOE* OO 1.680E-03 Appc:ndix C Ai Adult Fish

• Page 3 of 4 Page 9-98

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXC A1Adult Dose Factors for use in the Liquid Dose Calculations Age group: ADULT Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kldnev LUil!! Gilli Skin Total Body CE-143 2.380E-03 l.760E+o0 O.OOOE-t-00 7. 7GOE-04 O.OOOE+OO 6.590E+Ol O.OOOE+OO I.950E-04 CE-I44 1.170E+O(I 4.870E-OI O.OOOE+ilO 2.890E-OI O.OOOE+oo 3.940E+02 0.000E+OO 6.260E-02 PR-143 5.230E-O J 2.JOOE-01 O.OOOE+OO 1.210E-OJ O.OOOE+OO 2.290E+03 O.OOOE+OO 2.590E-02 PR-144 l .550E-28 6.440E-29 O.OOOE+OO 3.630E-29 O.OOOE+OO 2 2300-35 O.OOOE+OO 7.880E-30 ND-147 3.530E-Ol 4.080E-01 O.OOOE+OO 2.390E-01 O.OOOE+OO 1.960E+03 O.OOOE+OO 2.440E-02 EU-152 W-187 2.334E+OJ l.470E+02 5.314E+OO l.230E+o2 0.000E-t-00 O.OOOE+OO 3.29IE+OI 0.000E+OO O.OOOE+OO O.OOOE+oo 3.064E+03 4.030E+04 O.OOOE+OO O.OOOE+OO 4.668E+OO 4.300E+OI I

NP-239 2.120E-02 2.090E-03 O.OOOE+oO 6.510E-03 O.OOOE+oO 4.280E+02 O.OOOE+OO l.l50E-03 AppcndiK C Ai Aduh Fish* Page 4 of 4 Page 9-99

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXC A1 Adult Dose Factors for use in the Liquid Dose Calculations A ge group : A D ULT Pathway : Shoreline Sediment (SHDp) Units: nu-emlltr / µ(..l fm l Nuclide Bone Liver Thyl'Oid Kidney Lun2 Gilli Skin Total Body I-1-3 O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+oO O.OOOE+OO O.OOOE+lXl 0.000E+OO C- 14 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO NA-24 4.270E-Ol 4.270E-01 4.270E-01 4.270E-Ol 4.270E-Ol 4 270E-O\ 4.960E-Ol 4.270E-Ol P-32 O.OOOE+OO O.OOOE+oo O.OOOE+OO 0.000E+O(I O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO CR-51 l.670E-Ol l.670E-01 t.670E-Ot 1.670E-Ol 1.670E-Ot l.670E-O\ 1.970E-Ol 1.670E-Ol MN-54 4.960E+OI 4.960E+ol 4.960E+O\ 4.960E+Ol 4.960E+ol 4.960E+OI 5.820E+Ol 4.960E+OJ MN-56 3.230E-02 3.230E-02 3.230E-02 3.230E-02 3.230E--02 3.230E-02 3.820E-02 3.230E--02 FE-55 0.000E+OO 0.000E+OO 0.000E+OO 0.000E+OO O.OOOE+oo O.OOOE+OO 0.000E+O"J 0.000E+OO FE-59 9.770E+OO 9.770E+oo 9.770E+OO 9.770E+OO 9.770E+OO 9.770E+OO 1.150E+Ol 9.770E+OO CO-58 l.360E+OJ l.360E+Ot l.360E+OJ l.360E+Ol l.360E+Ol l.360E+Ol J.590E+ol l.360E+Ol CO-60 7.690E+02 7.690E+02 7.690E+o2 7.690E+02 7.690E+02 7.690E+02 9.0508+m 7.6908+02 NI-63 0.000.E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO NI-65 J.060E-02 1.0608-02 l .060E-02 l.060E-02 J.060E--02 l.060E-02 J.240E-02 J.060E-02 CU-64 2.170E-02 2.170E-02 2.170E-02 2.170E-02 2.170E--02 2.170E-02 2.4608-02 2.170E--02 ZN-65 2.670E+OJ 2.670E+O\ 2.670E+Ol 2.670E+Ol 2.670E+ol 2.670E+O I 3.080E+OJ 2.670E+OI ZN-69 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO SE-75 l.617E+Ol l.617E+Ol l.6\7E , Ol l.617E+Ol l.617E IO \ l.617E+Ol l.892E+Ol l.6 17E+Ol BR-83 I 740E-04 J.740E-04 I .740E-04 1.740E-04 l.740E--04 l.740E-04 2.530E-04 l.740E--04 BR-84 7.250E-03 7.250E-03 7.250E.03 7.250E-03 7.250E-03 7.250E-03 8.460E-03 7.250E-03 BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO RB-86 3.220E-Ol 3.220E-01 3.220E-0 1 3.220E-Ol 3.220E--Ol 3.220E-Ol 3.680E-O\ 3.220E-Ol RB-88 1.180E-03 I.ISOE-03 l.l 80E-03 1.180E-03 l.180E-03 l.l80E-03 l.350E-03 1.180E--03 RB-89 4.400E-03 4.400E-03 4.400E-03 4.400E-03 4.400E--03 4.400E-03 5.280E-03 4.400EJJ3 SR-89 7.740E-04 7.7408-04 7.740E-04 7.740E-04 7.740E--04 7.740E-04 8.990E-04 7.740E--04 SR-90 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO Appcndi" C Ai Adult Sh.orclinc Sediment - Page I of 4 Page 9-100

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCJM)

APPENDIXC A1 Adult Dose Factors for use in the Liquid Dose Calculations Age grou p: ADULT Pathway: Shoreline Sediment (SHDp) Units: mremlhr / µCi/ml Nuclide Bone Livea* Thvroid Kidnev Lun!! Gilli Skin Total Bodv SR-91 7.690E-02 7.690E-02 7.690E-02 7.690E-02 7.690E--02 7.690E-02 8.990E-02 7.690E--02 SR-92 2.7800--02 2.780E-02 2.780E-02 2.780E-02 2.780E--02 2.780E--02 3.090E--02 2.780E--02 Y-90 1.6lOE-04 J.6IOE-04 1.6JOE-04 l.610E-04 J.6JOE--04 1.610E-04 1.900E-04 l.610E--04 Y-91 3.8400--02 3.840E-02 3.840E-02 3.840E-02 3.840E--02 3.840E-02 4.320E-02 3.840E--02 Y-91M 3 5900-03 3.5906-03 3.590E-03 3.590E-03 3 590E--03 3.590E-03 4.150E-03 3.590E-03 Y-92 6.460E-03 6.460E-03 6.460E-03 6.460E-03 6.460E--03 6.460E-03 7.670E-03 6.460E--03 Y-93 6.560E-03 6.560E-03 6.560E-03 6.560E-03 6.560E--03 6.560E--03 8.980E-03 6.560E--03 ZR-95 8.760E+OO 8.760E+OO 8.760E+OO 8.760E+OO 8.760E+OO 8.760E+oo l.020E+01 8.760E+OO ZR-97 1.060E-Ol 1.060E--Ol 1.060E-01 J.060E-Ol L060E--01 L060E-01 l.230E-Ol L060E--Ol NB-95 4.890E+OO 4.890E+OO 4.890E+OO 4.890E+OO 4.890E+OO 4.890E+OO 5.750E+OO 4.890E+OO M0-99 l.4300-01 l.430E-Ol l.430E-01 l.430E-Ol l.430E--OI L430E-01 l.660E-Ol 1.430E--OI TC-99M 6.590E-03 6.5908-03° 6.590E-03 6.590E-03 6.590E--03 6.590E-03 7.5508-03 6.590E.--03 TC-101 7.280E-04 7.280E-04 7.280E-04 7.280E-04 7.280E--04 7.280E-04 8.090E-04 7.280E--04 RU-103 3.870E+OO 3.870E+OO 3.870E+OO 3.870E+OO 3.870E+OO 3.870E+OO 4.520E+OO 3.870E+(I()

RU-105 2.280E-02 2.280E-02 2.280E-02 2.280E-02 2.280E--02 2.280E--02 2.580E-02 2.280E--02 RU-106 l.510E+ol l.5JOE+ol 1.5IOE+OI l.510E+OI l.5IOE+OJ 1.510E+OI l.810E+Ol 1.5IOE+OI AG-108M l.846E+03 l.846E+03 J.846E+03 1.846E+03 l.846E+03 l.846E+03 2.l59E+03 l.846E+03 AG-llOM l.230E+02 1.230E+02 l.230E+02 l.230E+02 l.230E+02 l.230E+02 l.440E+02 l.230E+02 SN-113 5.34CIE--Ol 5.340E-OI 5.340E-OJ 5.340E-01 5.340E--Ol 5.340E--Ol 6.248E-Ol 5.340E--01 SN-ll7M 7.463E-Ol 7.463E-ot 7.463E-OI 7.463E-Ol 7.463E--OJ 7.463E-Ol 8.732E-01 7.463E~JI SB-124 2.141E+Ol 2.]4JE+01 2.141E+OI 2141E+Ol 2.14JE+Ol 2.l4lE+Ol 2.470E+OI 2.14!E+OI SB-125 8.349E+OI 8.349E+OI 8.349E+OI 8.349E+OI 8.349E+Ol 8.349E+OI 9.42o'E+Ol 8.349E+Ol SB-126 3.0l.9E+OO 3.0J9E+OO 3.019E+OO 3.0J9E+OO 3.019E-l (IO 3.0l9E+OO 3.393E+OO 3.019EI-OO TE-123M 6.059E+-OO 6.059E+OO 6.059E+OO 6.059E+OO 6.059E-t-OO 6.059E+OO 7.089E+OCI 6.059E+OO TE-125M 5.550E-02 5.550E-02 5.550E-02 5.550E-02 5.550E--02 5.550E-02 7.620E-02 5.550E--02 Appendix C Ai Adull Shoreline Sediment. Page 2 of 4 Page 9-101

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX C A1 Adult Dose Factors for use in the Liquid Dose Calculations Age group: ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µ(,'i/ml Nuclide Bone Liver Thvl'Oid Kidnev Lunl! Gilli Skin TotulBod:v TE-127 l.070E-04 1.070E-04 l .070E-(14 l.070E-04 l.070E-04 l.070E-04 l .170E-04 l .070E-04 TE-127M 3.280E-03 3.280E-03 3.280E-03 3.280E-03 3.280E-03 3.280E-03 3.880E-03 3.280E-03 TE-129 9.390E-04 9.390E-04 9.390E-(14 9.390E-04 9.390E-04 9.390E-04 l.l lOE-03 9.390E-04 TE-129M 7.080E-01 7.080E-OI 7.0SOE-01 7.080E-Ol 7.0S0E-01 7.080E-OI 8.270E-0I 7.080E-OI TE- 13 1 1040E-03 l.040E-03 l .040E-03 l.040E-03 1.040E-03 l.040E-03 l.230E-+-OO 1.040E-03 TE-131M 2.870E-0I 2.870E-Ol 2.870E-0l 2.870E-Ol 2.870E-O l 2.8706-01 3.390E-0I 2.870E-O l TE-132 l.520E-01 1.520E-0I l.520E-Ol l.520E-OI l.520E-Ol l.520E-0l l.780E-01 1.520E-O I 1-130 l.970E-0l l.970E-Ol l.970E-Ol 1.970E-01 l.970E-O l l.970E-Ol 2.390E-0 I l.970E-O I 1- 131 6.160E-01 6.160E-01 6.160E-OI 6.I60E-OI 6.160E-0 1 6. 160E-0I 7.480E-01 6.160E-O I 1-132 4.460E-02 4.4606-02 4.460E-02 4.460E-02 4.460E-02 4.460E-02 5.240E-02 4.460E-02 1- 133 8.770E-02 8.770E-02 8.770E-02 8.7706-02 8.770E-02 8.770E-02 l.070E-0l 8.770E-02 1-134 l.600E-02 1.6006-02 1.6006-02 1.600E-02 l.600E-O:)' 1.600E-02 l.900E-02 l.600E-02 I-135 9.040E-02 9.040E-02 9.040E-02 9.040E-02 9.040E-02 9.040E-02 1.0S0E-01 9.040E-02 CS-1 34 2.450E+02 2.450E+o2 2.450E+02 2.450E+02 2.450E+02 2.450E+02 2.860E+02 2.450E+02 CS-1 36 5.400E+00 5.400E+OO 5.400E+OO 5.400E+OO 5.400E+oo 5.400E+OO 6.120E+OO 5.400E+OO CS- 137 3.6806+02 3.680E+02 3.680E+02 3.680E+02 3.680E+02 3.680E+02 4.290E+02 3.680E+02 CS-138 1.280E-(12 l.280E-02 l.280E-<12 l.2S0E-02 l.280E-02 l.'.l80E-02 l.470E-02 l.280E-02 BA-133 3.155E+02 3.155E+02 3.155E+02 3.155E+02 3.155E+02 3.155E+02 3.69IE+02 3.155E+02 BA- 139 3.790E-03 3.790E-03 3.7906-03 3.790E-03 3.7906-03 3.7906-03 4.260E-03 3.790E-03 BA-140 7.350E-OI 7.350E-01 7.350E-0l 7.3506-01 7.350E-OI 7.350E-O I 8.400E-0l 7.350E-01 BA- 141 1.4906-03 1.4906-03 1.4906-03 1.490E-03 l.490E-03 1.4906-03 l.700E-03 1.490E-03 BA-142 l.610E-03 1.6106-03 1.6JOE-03 1.6IOE-03 1.6106-03 1.6106-03 l.830E-03 l.610E-03 LA- 140 6.8806-01 6.880E-01 6.880E-Ol 6.8806-01 6.880E-OI 6.880E-01 7.790E-0l 6.8806-01 LA- 142 2.720E-02 2.720E-02 2.7206-02 2.720E-02 2.720E-02 2.720E-02 3.260E-02 2.720E-02 CE-141 4.890E-01 4.890E-01 4.890E-Ol 4.890E-01 4.890E-Ol 4.890E-01 5.5 10E-Ol 4.890E-O I Appendix C Ai Adult Shoreline Sediment

• Page 3 of 4 Page 9-102

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXC A1 Adult Dose Factors for use in the Liquid Dose Calculations Age group: ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr I µCi/ml Nuclide Bone Liver Thyl'Oid KidnCJ' Lun11: Gilli Skin Total Bodv CE-143 8.270E-02 8.270E-02 8.270E-02 8.270E-02 8.270E-02 8.270E-02 9.400E-02 8.270E-02 CE-144 2.490E+-OO 2.490E+OO 2.490E+-OO 2.490E+OO 2.490E+-OO 2.490E+OO 2.880E+OO 2.490E+OO PR-143 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO PR-144 6.570E-05 6.570E-05 6.570E-05 6.570E-05 6.570E-05 6.570E-05 7.550E-05 6.570E-05 ND-147 3 OOOE-01 3.000E-01 3.000E-01 3.000E-01 3.000E-01 3.000E-01 3.600E-01 3.000E-01 EU-152 5.3 17E+02 5.3l7E+02 5.317E+02 5.3l7E+02 5.317E+02 5.317E+02 6.154E+02 5317E+02 W-187 8.420E-02 8.420E-02 8.420E-02 8.420E-02 8.420E-02 8.420E-02 9.780E-02 8.420E-02 NP-239 6. l20E-02 6.l20E-02 6.l'.!OE-02 6.120E-02 6.120E-02 6.120E-02 7.090E-02 6.120E-02 Appendix C Ai Aduh Shoreline Sedimait. Page 4 of 4 Page 9-103

Attachment 9*

Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIXD A1Teen Factors for use in the Liquid Dose Calculations Agegl'Oup: TEEN Pathway: Potable Water (PWti*) Uni.ls: mrem/hr / µCi/ml Nuclide Bone Liver Thyl"Oid Kidney Lun!!' Gilli Skin TotalBodv H-3 O.OOOE+OO 6.t60E+OO 6.160E+OO 6.160E+OO 6.t60E+OO 6.160E+OO O.OOOE+OO 6.160E+OO C-14 2.360E+02 4.720E+Ol 4.720E+-01 4.720E+OJ 4.720E+O l 4.720E+OI O.OOOE+OO 4.720E+OJ NA-24 7.690E+OI 7.690E+Ol 7.690E+OI 7.690E+OJ 7.690E+Ol 7.690E+Ol O.OOOE+OO 7.690E+OJ P-32 1.570E+04 9.700E+02 0.000E+OO O.OOOE+OO O.OOOE+OO l.320E+-03 O.OOOE+OO 6.070E+02 CR-51 0.000E+OO O.OOOE+OO J.150E-01 4.530E-02 2.950E-Ol 3.470E+O I O.OOOE+OO 2.070E-01 MN-54 0.000E+OO 3.430E+02 0.000E+-00 1.020E+02 O.OOOE+OO 7.030E+o2 O.OOOE+OO 6.790E+Ol MN-56 O.OOOE+OO 3.640E-01 O.OOOE+OO 4.610E-Ol O.OOOE+OO 2.400E+Ol 0.000E+OO 6.480E-02 FE-55 2.200E+02 1.560E+-02 O.OOOE+oO 0.000E+OO 9.880E+<) J 6.740E+Ol O.OOOE+OO 3.630E+Ol FE-59 3.390E+02 7.900E+02 O.OOOE+OO O.OOOE+OO 2.490E+02 l.870E+03 0.000E+OO 3.050E+02 C0-58 O.OOOE+OO 5.620E+Ol 0.000E+oO O.OOOE+OO 0.000E+OO 7.750E+02 0.000E+OO 1.300E+02 CO-60 O.OOOE+OO 1.630E+02 O.OOOE+-00 0.000E+OO O.OOOE+OO 2.130E+o3 O.OOOE+OO 3.680E+02 NI-63 1.030E+04 7.270E+02 O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.160E+02 O.OOOE+'oo 3.490E+02 Nl-65 1.610E+OO 2.050E-01 O.OOOE+{IO O.OOOE+OO O.OOOE+OO 1.1 IOE+OI O.OOOE+OO 9.350E-02 CU-64 0.000E+OO 3.470El*OO O.OOOE+OO 8.770E+OO 0.000fl+OO 2.690fl+02 O.OOOE+OO l.630E+OO ZN-65 3.340E+02 1.160E+03 O.OOOE+OO 7.430E+02 O.OOOE+OO 4.920E+02 O.OOOE+OO 5.420E+02 ZN-69 1.070E-04 2.040E-04 O.OOOE+OO 1.330E-04 0.000E+OO 3.760E-04 O.OOOE+OO 1.430E-05 SE-75 8.644E+Ol 3.325E+Ol 3 325E+ol 6.649E+OO 7.979E+Ol 9309E+Ol O.OOOE+OO 6.649E+02 I BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 1.030E-Ol BR-84 0.000E+oo O.OOOE+OO O.OOOE+oo 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 6.500E-07 BR-85 O.OOOE+OO 0.<lOOE+OO 0.000E+{10 O.OOOE+OO O.OOOE+OO 0.000E+OO 0.0006+00 4.360E-77 RB-86 O.OOOE+OO 1.700E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.520E+02 O.OOOE+OO 7.990E+02 RB-88 O.OOOE+OO 3.300E-12 O.OOOE+OO 0.000E+OO O.OOOE+OO 2.830E-19 O.OOOE+OO 1.760E-12 RB-89 O.OOOE+OO 2.960E-14 O.OOOE+oO 0.000E+OO 0.000E+OO 4.540E-23 O.OOOE+OO 2.090E-14 SR-89 2.540E+04 O.OOOE+oo O.OOOE+oO 0.000E+OO 0.000E+OO 3.030E+03 O.OOOE+OO 7.280E+02 SR-90 4.830E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.350E+04 O.OOOE+OO I. 190fl+05 Appendix D Ai Teen Water. Page I of 4 Page 9-104

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/201 8 - 12/31/2 018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPEND IXD A1 Teen Factors for use in the Liquid Dose Calculations Age group: TEEN Pathway: Potable Water (PWtr) Units: nu-em/hr/ µCi/ml Nuclide Bone Liver Thyroid Kidney Lun!! Gilli Skin TotalBodv SR-91 1.950E+02 O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO 8.850E+02 O.OOOE+OO 7.760E+OO SR-92 8.220E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.090E+o2 O.OOOE+OO 3.SOOE-01 Y-90 7.000E-01 O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.770E+o3 O.OOOE+OO 1.880E-O'.l Y-91 1.160E+01 O.OOOE+oo O.OOOE+oO O.OOOE+OO O.OOOE+oo 4.760E+o3 O.OOOE+oo 3.120E-Ol Y-91M 3.330E-07 O.OOOE+oo O.OOOE+OO O.OOOE+OO 0.000E+OO l.5700-05 O.OOOE+OO l .270E-08 Y-92 6.710E-03 0.000E+OO O.OOOE+oO 0.000E+OO O.OOOE+OO l.840E+-02 O.OOOE+OO 1.940E-04 Y-93 9.760E-02 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.980E+03 O.ilOOE+OO 2.670E-03 ZR-95 2.380E+OO 7.520E-01 0.000E+oO l.lOOE+OO 0.000E+oo l.730E+03 O.OOOE+OO 5.170E-Ol ZR-97 8.420E-02 l.670E--02 o.OOOE+OO 2.530E-02 O.OOOE+OO 4.510E+03 O.OOOE+OO 7.670E-03 NB-95 4.730E-01 2.630E-01 0.000E+oO 2.5406-01 0.000E+OO 1.120E+-03 0.000E+OO 1.440E-Ol M0-99 O.OOOE+OO 3.090E+02 0.000E+oO 7.070E+02 O.OOOE+OO 5.530E+02 O.OOOE+OO 5.890E+Ol TC-99M ' 4.840E-03 USOE-02 O.OOOE+OO 2.0IOE-01 7.SOOE-03 8.870E+OO O.OOOE+OO l.750E-OI TC-IOI 1.1 20E-17 1.590E-17 O.OOOE+OO 2.880E-16 9.700E-18 2.720E-24 O.OOOE+OO 1.560E-16 RU-103 1.470E+Ol O.OOOEt*OO O.OOOE+OO S.180E* OI O.OOOE+OO l.230E+03 O.OOOE+OO 6.280E+OO RU-105 1.940E-01 O.OOOE+oO O.OOOE+OO 2.450E+OO O.OOOE+OO 1.570E+02 O.OOOE+OO 7.5406-02 RU-106 2.280E+02 0.000E+-00 O.OOOE+oo 4.390E+02 O.OOOE+OO l.090E+04 O.OOOE+OO 2.870E+OI AG-108M 7.830E+OI 3.012E+-01 AG-llOM 1.190E+OI l .130E+Ol 3.012E+ol O.OOOE+oo 6.023E+OO 2150E+OI 7.228E+-01 0.000E+OO 8.433E+Ol 3.160E+-03 O.OOOE+OO O.OOOE+OO 6.023E+02 6 850E+OO I

SN-113 2.565E+-OI 9.866E+OO 9.866E+OO 1.973E+OO 2.368E+Ol 2.762E+OI O.OOOE+OO 1.973E+02 SN-117M 2.399E+Ol 9.227E+OO 9.227E-+{I() 1.845E+OO 2.215E+OI 2.584E+OI O.OOOE+OO l .845E+02 SB-124 2 237E+02 4 l22E+-OO 5.075E-01 0.000E+OO 1.954E+02 4.509E+03 O.OOOE+OO 8.729E+OI SB-125 l.441E+02 1.5 75E+()() 1.377E-01 O.OOOE+OO 1.267E+02 1.122E+-03 0.000E+OO 3.371E+OI SB-126 8.989E+OI l.837E+OO 5.083E-Ol 0.000E+OO 6.445E+OJ 5.320E+03 O.OOOE+OO 3.228E+Ol TE-l23M 4.740E+Ol 1.823E+Ol 1.823E+ol 3.646E+OO 4.376E+Ol 5.105E+Ol O.OOOE+OO 3.646E+02 TE-125M 2.210E+02 7.980E+OI 6.180E+O! O,OOOE* OO O.OOOE+OO 6.5308+02 O.OOOEt*OO 2.960E+Ol Appendix D Ai Teen Water - Page 2 of 4 Page 9-105

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Off.site Dose Calculation Manual (ODCM)

APPENDIXD A1Teen Factors for use in the Liquid Dose Calculations Age group: TEEN Patltway: Potable Water (PWtr) Units: nu*em/hr / µCi/ml Nuclide Bone Liver ThJ'roid Kidney Lune Gilli Skin TotalBodv 3.790E+OO l.340E+o0 2.610E+o0 l.530E+OI O.OOOE+OO 2.930E+02 O.OOOE+OO 8.150E-01 TE- 127 5.600E+02 l.990E+o2 l.330E+-02 2.270E+03 O.OOOE+OO 1.400E+03 O.OOOE+OO 6.660E+OI TE-127M l.920E-03 7.l50E-04 l.370E-03 8.040E-03 O.OOOE+OO l.OSOE-02 O.OOOE+OO 4.660E-04 TE- 129 9.380E+02 3.480E+02 3.0JOE-+-02 .l920E+03 O.OOOE+oo 3.520E+03 O.OOOE+OO l .480E+02 TE-129M l.440E-IJ9 2.690E-09 l.520E-08 O.OOOE+OO 2.860E-l0 O.OOOE+OO l .090E-09 TE-13 1 3.490E-09 l.080E+02 5.1506+01 7.7506+-0 I 5.3806+02 0.000E+OO 4.140E+o3 0.0006+00 4.300E+O l TE-IJIM l.820E+02 l.l50E+o2 1.220E+02 1.1106+03 O.OOOE+OO 3.660E+03 O.OOOE+OO l .090E+02 TE-132 3.050E+OI 8.8306+ol 7.200E+o3 1.3606+02 0.0006+00 6.790E+OI O.OOOE+OO 3.530E+O!

1- 130 3.260E+02 4.560E+02 l.330E+05 7.850E+02 0.000E+OO 9.020E+OI O.OOOE+OO 2.450E+02 1-131 4.360E-Ol l.140E+OO 3.850E+o l l.800E+OO O.OOOE+OO 4.970E-O I O.OOOE+OO 4.lOOE-01 I-132 7.830E+Ol l.330E+o2 I .860E+<j4 2.330E+02 O.OOOE+oo 1.0IOE+02 O.OOOE+OO 4.050E+OI I- 133 1- 134 6.330E-04 l.680E-03 2.SOOE-02 2.640E-03 O.OOOE+OO 2.2\0E-05 0.000E+OO 6.020E-04 2.600E+OI l.670E+o3 4.!00E+OI O.OOOE+OO 2.880E+OI O.OOOE+OO 9.630E+OO 1-135 1.0!0E+OI 4.860E+03 I. l40E+04 O.OOOE+OO 3.640E+03 l .390E+03 l.420E+02 O.OOOE+OO 5.3106+03 CS-134 4.860E+02 1.910E+-03 O.OOOE+-00 l.040E+03 1.640E+02 1.5406+02 O.OOOE+OO 1.290E+03 CS-136 6.510E+03 8.6606+03 0.000E+-00 2.950E+03 l.l50E+03 1.230E+02 O.OOOE+OO 3.020E+03 CS-137 CS-13& 8.3006-07 l.590E-06 O.OOOE+<JO l.1806-06 l.370E-07 7.230E-l0 O.OOOE+OO 7.970E-07 BA-133 2.041E+02 7.8516+01 7.851E+<ll L570E+ol 1.884E+02 2.198E+02 O.OOOE+OO 1.570E+03 I l.990E-02 1.4(>0E-05 0.000E+-00 l.320E-05 9.670E-06 l.780E-Ol O.OOOE+OO 5.SIOE-04 BA-139 1.6 l0E+03 I 970E+OO O.OOOE-!{10 6.6806-01 l.320E+OO 2.480E+03 O.OOOE+OO 1.040E+02 BA- 140 5.420E-1 2 4.050E-15 O.OOOE+oO 3.760E-15 2.770E-l5 l.150E-l7 OllOOE+OO l.8106-13 BA-141 BA-142 6.170E-21 6.l70E-24 0.000E+oo 5.220E-24 4.lOOE-24 1.890E-32 O.OOOE+OO 3.SOOE-22 l.650E-Ol 8.090E-02 0.000E+-00 0.0006+00 0.0006+00 4.6406+03 0.000E+OO 2.ISOE-02 LA-140 5.590E-05 2.480E-05 O.OOOE+-00 O.OOOE+OO O.OOOE+OO 7.550E-O I O.OOOE+OO 6.l 80E-06 LA-142 CE-1 4 1 7.650E-O I 5. llOE-01 O.OOOE+OO 2.4006-01 O.OOOE+OO l .460E+03 O.OOOE+OO 5.870E-02 Appendix D Ai Teen Water . Page 3 of 4 Page 9-106

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offs1te Dose Calculation :Manual (ODCM)

APPENDIXD A1Teen Factors for use in the Liquid Dose Calculations Age group: TEEN Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lune Gilli Skin Total Body CE-143 1.060E-OI 7.730E+OJ O.OOOE+-00 3.460E--02 O.OOOE+OO 2.320E+03 O.OOOE+OO 8.630E-03 CE-144 4.040E+Ol l.670E+Ol O.OOOE+OO 9.990E+OO 0.000E+OO 1.020E+04 O.OOOE+OO 2.1 70E+OO PR-143 7.420£-01 2.960E-OI O.OOOE+OO 1. 720E--O l 0.000E+OO 2.440E+o3 O.OOOE+OO 3. 700E--O'.!

PR-144 7.330E-16 3.000E-16 O.ClOOE+-00 1.720E-16 O.OOOE+OO 8 080E-!9 O.OOOE+oo 3.720E-17 ND-147 5.280£-01 5.750E-Ol O.OOOE+OO 3.370E--01 O.OOOE+OO 2.070E+03 O.OOOE+OO 3.440E-02 EU-152 W-187 l.424E+Ol 5.990E+OO 3.430E+OO 4.880E+OO O.OOOE+OO O.OOOE+OO l.593E+OI O.OOOE* OO O.OOOE+OO O.OOOE+OO l.262E+o3 l.320E+03 O.OOOE+OO O.IJOOE+OO 3.023E+OO I l.710E+OO NP-239 8.830£--02 8.330E-03 O.OOOE+oO 2.610E--02 O.OOOE+OO l.340E+03 O.OOOE+OO 4.630E--03 Appendix D Ai Teen Water

• Page 4 of 4 Page 9-107

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Slation Offs,tc Dose Calculation Manual (ODCM)

APPENDIXD A1 Teen Dose Factors for use in the Liquid Dose Calculations Age group : TEEN Pathway: Fresh Water Fish - Sport (Fl<'SP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thvroid Kldnev LUil!! Gilli Skin TotalBodv H-3 0.000E+OO 1.740E-01 l.740E-Ol 1.740E-01 l.740E-O l l.740E-01 O.OOOE+OO l.740E-01 C- 14 3.410E+04 6.810E+03 6.810E-H)3 6.810E+03 6.810E+03 6.810E+03 O.OOOE+OO 6.810E+03 NA-24 1.390E+02 l.390E+02 1.390E+o2 1.390E+02 l.390E+02 l.390E+02 O.OOOE+OO 1.390E+02 P-32 1.440E+06 8.910E+04 O.OOOE+oO 0.000E+OO O.OOOE+-00 l.210E+o5 O.OOOE+OO 5.580E+04 CR-51 O.OOOE+OO O.OOOE+OO 7.120E-01 2.SIOE-01 l.830E+OO 2.150E+02 0.000E+OO 1.280E+OO MN-54 O.OOOE+OO 4.300E+03 O.OOOE+oO l.280E+o3 O.OOOE+oo 8.810E+03 O.CIOOE+OO 8.520E+02 MN-56 O.OOOE+OO 1.8IOE-01 O.OOOE+OO 2300E-Ol O.OOOE+OO 1.1 90E+O l O.OOOE+OO 3.230E.02 FE-55 6.890E+02 4.880E+02 O.OOOE+oO 0.000E+OO 3.IOOE+02 2. II OE+02 O.OOOE+oo 1.1 40E+02 FE-59 1.050E+03 2.460E+03 O.OOOE+OO O.OOOE+OO 7.760E+02 5.820E+03 0.000E+OO 9.500E+02 C0-5& 0.000E+OO 8.780E+OI 0.000E+oO 0.000E+oo O.OOOE+oo l.210E+03 O.OOOE+OO 2.020E+o2 C0-60 O.OOOE+oO 2.560E+02 o.OOOE+OO O.OOOE+OO O.OOOE+oo 3.340E+03 O.OOOE+OO 5.770E+02 NI-63 3 230E+04 2.280E+03 0.000E+oO O.OOOE+OO O.OOOE+OO 3.630E+02 O.OOOE+OO l.090E+03 Nl-65 1.860E-01 2.370E-02 O.OOOE+oO O.OOOE+OO 0.000E+oo 1.290E+oo O.OOOE+OO l.080E-02 CU-64 O.OOOE+OO 2.820E

• OO O.OOOE+OO 7 !40E100 O.CIOOE+OO 2.190E+02 0.000El*OO l.330E+OO ZN-65 2.\ 00E+04 7.280E+04 O.OOOE+OO 4.660E+04 O.OOOE+OO 3.080E+04 O.OOOE+OO 3.390E+04 ZN-69 8.410E-07 1.600&06 0.000E+oO l.050E-06 O.OOOE+OO 2.9500-06 O.OOOE+OO l.l 20E--07 SE-75 5.408E+02 2.080E+02 2.080E+02 4.l60E+Ol 4.992E+02 5.824E+02 O.OOOE+OO 4.160E+03 I BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+<)O O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 4.160E-02 BR-&4 O.OOOE+oo O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 1.320E-12 BR-85 O.OOOE+<lO O.OOOE+OO 0.000E-t{l0 O.OOOE+OO O.OOOE+OO O.OOOE* -00 O.OOOE+OO O.OOOE+OO RB-&6 O.OOOE+OO l.050E+o5 O.OOOE+oO O.OOOE+OO 0.000E+OO l.550E+04 0.000E+OO 4 920E+04 RB-&& O.OOOE+OO 1.380&22 O.OOOE+-00 O.OOOE+oo O.OOOE+OO 1.ISOE-29 O.OOOE+OO 7.360E-23 RB-89 O.OOOE+OO l .720E-26 0.000E+oO O.OOOE+OO O.OOOE+OO 2.6300-35 O.OOOE+IJO J.220E-26 SR-89 2.370E+04 0.000E+OO O.OOOE+oO O.OOOE+OO O.OOOE+oo 2.830E+03 O.OOOE+OO 6.800E+02 SR-90 4.540E+05 O.OOOE+OO O.OOOE+OO O.OOOE* OO 0.000E+OO 1.270E+04 0.000E+OO l.120E+05 Appcndh; D Ai Teen Fish

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXD A1Teen Dose Factors for use in the Liguid Dose Calculations Age grou p: TEEN Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid I<.:idney Lun2 Gilli Skin Total Body SR-91 7.640E+OI O.OOOE-+-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.470E+02 O.OOOE+OO 3.040E+OO SR-92 3.590E-O I 0.000E+OO O.OOOE+ilO O.OOOE+OO O.OOOE+OO 9.130E+oo O.OOOE+OO l.530E-02 Y-90 4.820E-01 O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 3.980E+03 O.OOOE+OO l.300E-O'.l Y-91 9.060E+OO O.OOOE+OO O.OOOE-HJO O.OOOE+OO O.OOOE+oO 3.710E+03 O.OOOE+OO 2.430E-Ol Y-91M l.1 60E-l I O.OOOE+oo O.OOOE+OO 0.000E+OO O.OOOE+OO 5.470E-IO O.OOOE+OO 4.430E-13 Y-92 5.020E-04 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO l.380E+Ol O.OOOE+OO l.450E-05 Y-93 3.350E-02 0.000E+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO l .020E+03 0.IXlOE+OO 9.190E-04 ZR-95 2.450E-Ol 7.740E-02 O.OOJE+OO l.140E-Ol O.OOOE+OO 1.790E+02 O.OOOE+OO 5.320E-02 ZR-97 5.330E-03 1.0508-03 O.OOOE+OO l.600E-03 O.OOOE+OO 2.850E+02 O.OOOE+OO 4.860E-04 NB-95 4.410E+02 2.450E+02 O.OOOE-HJO 2.370E+o2 O.OOOE+OO l.050E+06 O.OOOE+OO I.350E+02 M0-99 O.OOOE+OO 8.550E+Ol O.OOOE+OO l.960E+02 O.OOOE+oo 1.530E+02 O.OOOE+OO l.630E+OI TC-99M 5.720E-04 l.600E-03 0.000E+OO 2.380E-02 8.860E-04 l.050E+OO O.OOOE+OO 2.070E-02 TC-IOI 2.820E-33 4.0IOE-33 O.OOOE+{IO 7.240E-32 2.440E-33 6.8400-40 O.OOOE+OO 3.930E-32 RU-103 4.570E+OO 0.000E!OO O.OOOE<OO l.610E10l OOOOE+OO 3.820E+02 0.000E!OO l.950Et00 RU-105 9.350£-03 O.OOOE+OO O.OO<JE+OO l.180E-Ol O.OOOE+OO 7.550E+OO O.OOOE+OO 3.630E-03 RU-106 7.l40E+OI 0.000E+OO O.OOOE+OO 1.380£+02 O.OOOE+OO 3.420E+03 0.000E+OO 8.990E+OO AG-108M AG-llOM 2.457E+Ol 8.580E-Ol 9.448E+o0 8.120E-01 9.448E+OO O.OOOE+OO l .890E+OO l 550E+OO 2.268E+Ol O.OOOE+oo 2.645E+Ol 2.280E+02 O.OOOE+OO O.OOOE+OO 1.890E+02 4.940E-01 I

SN-113 2.407E+o3 9.257E+02 9.257E+02 l.85lE+02 2.222E+03 2.592E+03 O.OOOE+OO l.851E+04 SN-117M 2.201E+03 8.466E+02 8 466E+{l2 l.693E+o2 2.032E+03 2.371E*t-03 O.OOOE+OO l .693E+04 SB-124 6.978E+02 l.286E+ol l.583E+OO O.OOOE+OO 6.095E+02 I 406E+04 O.OOOE+OO 2.723E+02 SB-125 4.520E+02 4.940E+OO 4.320E-Ol O.OOOE+OO 3.974E+02 3.5l8E+o3 0.000E+OO l.057E+02 SB-126 2.742E+02 5.606E+OO l.55 1E-Hl0 0.000E+OO 1.966E+02 1.623E+04 O.OOOE+OO 9.849E+Ol TE-l23M 5.931E+02 2.281E+02 2.281E+02 4.563E+OI 5.475E+02 6.388E+02 O.OOOE+OO 4.563E+03 TE-125M 2.760E+03 9.950E+02 7.710E+02 O.OOOE+OO O.OOOE+OO 8.150E+03 0.000E-100 3.690£+02 Appendix D Ai Teen Fish - Page 2 of 4 Page 9-109

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuckar Station Offs1te Dose Calculation Manual (ODCM)

APPENDIXD A, Teen Dose Factors for use in the Liquid Dose Calculations Age group: TEEN Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidne~' Luni Gilli Skin Total Bodv TE-127 l.960E+OI 6.950E+OO l.350E+O l 7.940E+OI 0.000E+OO l.5 10E+03 0.000E+OO 4.220E+OO TE-127M 7.0IOE+03 2.490E+03 l.670E+03 2.840E+04 O.OOOE+OO l.750E+04 O.OOOE+OO 8.340E+02 TE-129 l.770E-05 6.600E-06 l.260E-05 7.430E-05 O.OOOE+OO 9.680E-05 O.OOOE+OO 4.31 0E-06 TE-l29M 1.160E+04 4.320E+03 3.760E+03 4.870E+04 O.OOOE+<JO 4.370E+04 O.OOOE+OO I. 840E+03 TE-131 9.400E- l 7 3.870E- 17 7.240E-17 4. l lOE-16 O.OOOE+OO 7.71 0E- 18 O.OOOE+OO 2.940E-l 7 TE-l31M 1.020E+03 4.900E+02 7.370E+02 5.I IOE+-03 0.000E+OO 3.930E+04 O.OOOE+OO 4.090E+02 TE-132 2.060E+03 U OOE+03 l .370E+-03 l .250E+04 0.000E+OO 4.130E+04 O.OOOE+OO 1.230E+03 I-130 7.320E+OO 2.120E+o l 1.730E+03 3.260E+OI O.OOOE+OO l.630E+O I O.OOOE+OO 8.460E+OO I-131 I.470E+02 2.060E+02 6.000E+04 3.540E+02 0.000E+OO 4.070E+OI O.OOOE+OO I.I OOE+02 I-132 5.520E-03 l.440E-02 4.870E-Ol 2.280E-02 0.000E+OO 6.290E-03 O.OOOE+OO 5.ISOE-03 l-133 2.470E+O I 4.l90E+Ol 5.850E+o3 7.350E+OI O.OOOE+OO 3.l 70E+ol O.OOOE+OO 1.280E+OI I- 134 2.220E-08 5.890E-08 9.SIOE-07 9.280E-08 0.000E+OO 7.760E-10 0.000E+OO 2.IIOE-08 1-135 l.350E+OO 3.480E+OO 2.240E+02 5.490E+OO O.OOOE+OO 3.850E+OO O.OOOE+OO 1.290E+OO CS-134 3050E+05 7.180E**05 O.OOOE+OO 2.280E+05 8 71 0[l+04 8.930E+03 O.OOOE l*OO 3.330E+05 CS-136 2.970E+04 1.1 70E+o5 0.000E+OO 6.370E+04 l.OOOE+04 9.41 0E+03 O.OOOE+OO 7.860E+04 CS-137 4.090E+05 5.440E+05 0.000E+-00 l. 850E+05 7.190E >04 7.730E+03 0.000E+OO l.890E+05 CS-138 9.580E- 12 l.840E- l l O.OOOE+-00 l.360E-ll L580E- 11 8.340E-1 5 O.OOOE+OO 9.190E-12 BA-133 2.56IE+OI 9.85 1E+OO 9.85 1E+<Xl l.970E+OO 2 364E+O l 2.758E+OI O.OOOE+OO 1.970E+02 I BA-139 6.170E-06 4.340E-09 O.OOOE+OO 4.090E-09 2.990E-09 5.510E-05 O.OOOE+OO 1.SOOE-07 BA-140 l.960E+02 2.410E-01 O.OOOE+<IO 8.160E-02 1.620E-Ol 1.030E+02 0.000E+OO 1.260E+Ol BA-141 9.4500-25 7.050E-28 O.OOOE+OO 6.550E-28 4 830E-28 2 010E-30 OOOOE+CXl 3.ISOE-26 BA-142 2.750E-42 2. 750E-45 O.OOOE-+<IO 2.320E-45 1.830E-45 8.430E-54 O.OOOE+OO L690E-43 LA-140 l.050E-0 1 5.I60E-02 O.OOOE+oO 0.000E+OO 0.000E+OO 2.960E+03 O.OOOE+OO l.370E-02 LA-142 2.350E-07 l.040E-07 O.OOOE+-00 O.OOOE+OO O.OOOE+OO 3.IBOE-03 O.OOOE+OO 2.600E-08 CE-141 2.370E-IJ2 l.590E-02 O.OOOE+OO 7.460E-03 O.OOOE+OO 4.540E+Ol O.OOOE+OO l.820E-03 Appendix D Ai Teen Fish

• Page 3 nf 4 Page 9-110

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuckar Station Offsitc Dose Ca[culat,on .Manwl (ODCM)

APPENDIXD A1Teen Dose Factors for use in the Liquid Dose Calculations Age group: TEEN Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lu112 Gilli Skin Total Body CE-143 2.590E-03 l.880E+o0 O.OOOE-t-00 8.4508-04 O.OOOE+OO 5.660E+OI O.OOOE+OO 2.IOOE-04 CE-144 1.270E+OO 5.240E-01 O.OOOE+OO 3. 130E-01 O.OOOE+OO 3.180E-t-02 O.OOOE+OO 6.810E-02 PR-143 5.680E.Q1 2.270E-01 0.000E-t-00 1.320E-01 O.OOOE+OO 1.870E+o3 O.OOOE+OO 2.830E-02 PR-144 1.6900-28 6.900E-29 0.000E+OO 3.960E-29 I O.OOOE+oo l.860E-31 O.OOOE+OO 8.550E-30 ND-147 4.020E-Ol 4.370E-OI O.OOOE+OO 2.560E-01 O.OOOE+OO l.580E+03 O.OOOE+OO 2.620E-02 EU-152 W-187 2.234E+ol l.590E-t-02 5.380E+OO 1.300E+o2 0.000E-t-00 0.000E+OO 2.499E+OI O.OOOE+OO O.OOOE+oo O.OOOE+OO l.979E+o3 3.510E+04 O.OOOE+OO O.tlOOE+OO 4.742E+OO 4.540E+01 I

NP-239 2.390E-02 2.260E-03 O.OOOE-t-00 7.080E-03 O.OOOE+OO 3.630E+02 O.OOOE+OO 1.2SOE-03 Appendix D Al Teen Fisb - Page 4 of 4 Page 9-111

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXD A1 Teen Dose Factors for use in the Liquid Dose Calculations Age group: TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Livc1* Thy1-oid Kidney Lun2 Gilli Skin Total Body H-3 O.OOOE+OO O.orJOE+OO O.OOOE+OO 0.000E+OO 0.000E+oo 0.000E+OO O.OOOE+OO O.OOOE+OO C-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO NA-24 2.390E+OO 2.390E+OO 2390E+OO 2.390E+OO 2.390E+o0 2.390E+OO 2.770E+OO 2.390E+OO P-32 0.000E+oo 0.000E-l-00 O.OCK'JE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO CR-51 9.310E-01 9.3IOE-01 9.3 IOE-Ot 9.310E-01 9.3lOE-Ol 9.310E-01 l.lOOE+OO 9.310E-Ol MN-54 2.770E+02 2.770E+02 2.770E+02 2.770E+02 2.770E+o2 2.770E+02 3.250E+02 2 770E+02 MN-56 1.800E-01 1.800E-01 l.800E-01 1.800E-01 1.SOOE--0 1 1.800E-01 2.130E-01 1.800E--01 FE-55 O.OfJOE+OO 0.IJOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+oo 0.000E+OO O.OOOE+OO O.OOOE+OO FE-59 5.450E+OI 5.450E+Ol 5.450E+OI 5.450E+Ol 5.450E+ol 5.450E+Ol 6.410E+Ol 5.450E+Ol C0-58 7.570E+Ol 7..570E+Ol 7.570E+Ol 7.570E+ol 7.570E+ol 7.570E+Ol 8.870E+Ol 7.570E+Ol CO-60 4.300E+03 4.300E+03 4.300E+03 4.300E+03 4.300E+o3 4.300E+03 5.050E+03 4.300E+03 NI-63 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO NI-65 5.930E-02 5.930E-02 5.930E-02 5.930E-02 5.930E--02 5.930E-02 6.900E-02 5.930E--02 CU-64 1.210E-01 1.210E-OI 1.2 IOE-01 1.210E-01 l.210E--O l l.210E-01 l.370E-01 l. 210E--01 ZN-65 l.490E+02 1.490E+02 1.490E+02 l.490E+02 l.490E+o2 1.490E+02 l.720E+02 1.490E+02 ZN-69 O.OOOE+OO O.OOOE+oO O.OOOE+oo O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO SE-75 9.028E+OI 9.028E+Ol 9.028E+Ol 9.028E+Ol 9.028E+ol 9.028E+Ol l .056E+02 9.028E+Ol BR-83 9.730E-04 9.730E-04 9.730E-04 9.730E-04 9.730E--04 9.730E-04 l.410E-03 9.730E--04 BR-84 4.050E-02 4.0SOE-02 4.0SOE-02 4.050E-02 4.050E-02 4.0SOE-02 4.720E-02 4.050E--02 BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oO 0.000E+OO 0.1JOOE+OO O.OOOE+OO RB-86 l.800E+OO 1.800E+o0 l.800E+OO l.800E+OO 1.800E+OO 1.8(X)E+OO 2.0SOE+OO l .800E+OO RB-88 6.610E-03 6.610E-03 6.610E-03 6.610E-03 6.610E--03 6.610E-03 7.550E-03 6.610E--03 RB-89 2.460E-02 2.460E-02 2.460E-02 2.460E-02 2.460E--O" 2.460E-02 2.950E-02 2.460E--02 SR-89 4.320E-03 4.3208-03 4.320E-03 4.320E-03 4.320E--03 4.320E-03 5.020E-03 4.320E--03 SR-90 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO Appendix D Ai Tea1 Shoreline Scdima11 - Pagel of 4 Page 9-112

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXD A, Teen Dose Factors for use in the Liquid Dose Calculations Age group: TEEN Pathway: Shoreline Sediment (SHDp) Units: mremlhr / µCi/ml Nuclide Bone Live1* Thvroid Kidnev Lune: Gilli Skin TotalBodv SR-91 4.290E-0l 4.290E-0l 4.290E-0l 4.290E-0l 4.290E-Ol 4.2906-01 5020E-0l 4.290E-OJ SR-92 l.550E-Ol l.550E-Ol l.550E-0l 1.550E-0l l.550E-Ol l.550E-Ol l.720E-OI l.5506-0l Y-90 8.970E-04 8.970E-04 8.970E-04 8.970E-04 8.970E-04 8.970E-04 l.060E-03 8.9708-04 Y-91 2.l40E-0I 2.1406-01 2.l40E-0I 2.l40E-OI 2 J40E-Ol 2.l40E-Ol 2.4l0E-0J 2 l40E-Ol Y-91M 2000E-02 2000E-02 2.000E-02 2.000E-02 2.000E-02 2.000E-02 2.320E-02 2.000E-02 Y-92 3.600E-02 3.600E-02 3.600E-02 3.6008-02 3.600E-02 3.6006-02 4.280E-02 3.6006-02 Y-93 3.6606-02 3.660E-02 3.660E-02 3.660E-02 3.660E-02 3.660E-02 5.0I0E-02 3.660E-02 ZR-95 4.890E+0l 4.890E+OI 4.890E+0l 4.890E+Ol 4.890E+0I 4.890E+0I 5.670E+0l 4.890E+OI ZR-97 5.910E-01 5.9l0E-Ol 5.9106-01 5.9106-01 5.9l06-01 5.9106-01 6.8806-01 5.9106-01 NB-95 2.730E+0l 2.730E+0l 2.730E+0l 2.7306+01 2.7306+01 2.7306+01 3.2106+01 2.7306+01 M0-99 7.9806-01 7.980E-0l 7.980E-0l 7.9806-01 7.9806-01 7.9806-01 9.240E-OI 7.980E-Ol TC-99M 3.680E-02 3.6806-02 3.680E-02 3.6806-02 3.680E-02 3.680E-02 4.2I0E-02 3.6806-02 TC-101 4.0706-03 4.0706-03 4.0706-03 4.0706-03 4.070E-03 4.0706-03 4.520E-03 4.0706-03 RU-103 2.1606+0! 2.160E+Ol 2.1606+01 2.1606+01 2.160E+Ol 21606+01 2.520E+0l 2.160E+0l RU-105 1.2706-01 l.270E-0l 1.2706-0l l.270E-0l 1.2706-01 l.270E-OI l.440E-0l 1.2706-01 RU-106 8.4306+0I 8.430E+0l 8.430E+0J 8.4306+01 8.4306+0I 8.430E+0l l.0I0E+02 8.4306+0I AG-108M J.030E+04 1.030E+04 1.0306+04 1.0306+04 1.0306+04 1.0306+04 1.2066+04 l.030E+04 AG-llOM 6.870E+02 6.870E+02 6.8706+02 6.8706+02 6.8706+02 6.870E+02 8.0106+02 6.870E+02 SN-113 2.982E+OO 2.982E+OO 2 982E+OO 2.9826+00 2.9826+00 2.9826+00 3.4896+00 2.982E+OO SN-117M 4.1676+oo 4.1676+00 4.1676+00 4.1676+00 4.l67E+oo 4.1676+00 4.8756+00 4.1676+00 SB-124 1.195E+02 1.l95E+02 1.1956+02 l.195E+02 1.1956+02 1.1956+02 1.3796+02 I.I 9SE+02 SB-125 4.66IE+02 4.6616+02 4.6616+02 4.66IE+02 4.66IE+02 4.66IE+02 5.2636+02 4.66IE+02 SB-126 1.6866+01 l .686E+0l 1.686E+0J 1.686E+OI l.686E+OI 1.686E+0l l.894E+0I l.686E+0J TE-123M 3.383E+0I 3.383E+0I 3.3836+01 3.3836+0I 3.383E+OI 3.383E+0I 3.958E+OI 3.3836+0I TE-125M 3.JOOE-01 3.1006-01 3.IOOE-01 3. IOOE-01 3.1006-01 3.lOOE-01 4.250E-0I 3.IOOE-01 Appcndi~ D Ai Tcm Shoreline Sediment - Page 2 of 4 Page 9-113

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation lvfanual (ODCM)

APPENDIXD A1 Teen Dose Factors for use in the Liquid Dose Calculations Age group: TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Live1* Thnoid Kidnev Lun!! Gilli Skin Total Body TE-127 5.950E-04 5.950E-04 5.950E-04 5.9501?.-04 5.950E-04 5.950E-04 6.540E-04 5.950E-04 TE-127M 1.830E-02 1.830E-02 l.830E-02 l.830E-02 1.830E-02 l.830E-02 2.160E-02 1.830E-02 TE-129 5.240E-03 5.240E-03 5.240E-03 5.240E-03 5.240E-03 5.240E-03 6.200E-03 5.240E-03 TE-129M 3.950E+o0 3.950E+oo 3.950E+(IO 3.950E+OO 3.950ll+OO 3.950E+OO 4.620E+OO 3.9SOE+OO TE-131 5.830E-03 5.830E-03 5.830£-03 5.830E-03 5.830£-03 5.830E-03 6.890E+OO 5.830E-03 TE-131M l.600E+OO 1.600E+QO l.600E+OO l.600E+OO l.600E+o0 l.600E+OO l.890E+OO  !.600E+OO TE-132 8.460E-O l 8.460E-OI 8.460E-Ol 8.460E-Ol 8.460E-Ol 8.460E-Ol 9.950E-Ol 8.460E-Ol 1-130 l.l OOE+t~) l.lOOE+oO l.lOOE+OO I.IOOE+OO l.l OOE+OO l.!OOE+OO  ! .340E+OO l.! OOE+OO 1-131 3.440E+OO 3.440E+OO 3.440E+OO 3.440E+OO 3.440E+o0 3.440E+OO 4.l70E+OO 3.440E+OO 1-132 2.490E-01 2.490E-01 2.490E-Ol 2.490E-01 2.490E-O l 2.490E-O l 2.930E-Ol 2.490E-Ol 1-133 4.900E-Ol 4.900E-Ol 4.900E-Ol 4.900E-Ol 4.900E-O l 4.900E-0 1 5.960E-Ol 4.900E-OI 1-134 8.930E-02 8.930E-02 8.930E-02 8.930E-02 8.930£-02 8.930E-02 l .060E-OI 8.930E-02 I-135 5.050E-OI 5.0SOE-01 5.0SOE-01 5.0SOE-01 5.0SOE-0 1 5.0SOE-01 5.890E-OI 5.0SOE-0 1 CS-134 L370E+03 l.370E+03 l.370E+03 l.370E+03 l.370E+o3 l.370E+03 1.600E+03 l.370E+03 CS-136 3.0IOE+OI 3.0IOE+OI 3.0IOE+OI 3.0IOE+Ol 3.0 lOE+ol 3.0!0E+OI 3.420E+OI 3.0 IOE+OI CS-137 2.050E+03 2.050E+o3 2.050E+03 2.050E+03 2.050E+o3 2.050E+03 2.400E+03 2.050E+03 CS-138 7.170E-02 7.170E-02 7. I 70E-02 7.l70E-02 7.l 70E-02 7.170E-02 8.200E-02 7.170E-02 BA-133 l.761E+o3 1.76lE+03 l.761E+03 1.76IE+03 l.761E+o3 l.76IE+03 2.06IE+03 l.761E+03 BA-139 2. 120E-02 2.120£-02 2.12QE-02 2.I ZOE-02 2 120E-02 2.120E-02 2.380E-02 2.120E-02 BA-140 4.IOOE+OO 4.IOOE+oo 4.IOOE+OO 4.IOOE+OO 4.IOOE-t-00 4. IOOE+OO 4.690E+OO 4.I OOE+oo BA-141 8.330E-03 8.330E-03 8.330E-03 8.330E-03 8.330E-03 8.330E-03 9.490E-03 8.330E-03 BA-142 8.970E-03 8.970E-03 8.970£-03 8.970E-03 8.970E-03 8.970E-03 1.020E-02 8.970£-03 LA-140 3.840E+OO 3.840E+OO 3.840E+OO 3.840E+OO 3.840E+OO 3.840E+OO 4.350E+OO 3.840E+OO LA- 142 l.520E-OI l.520E-OI l .520E-Ol l.520E-OI 1.520E-O I l.520E-OI l.820E-01 l.520E-Ol CE-141 2.730E+OO 2.730E+OO 2.730E+CIO 2.730E+OO 2.730E+OO 2.730E+OO 3.080E+OO 2.730E+OO Appendlx D Ai Teen Shoreline Sedimait - Page 3 of 4 Page 9-114

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12 /31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXD A1 Teen Dose Factors for use in the Liquid Dose Calculations Age group: TEEN Pathway: Shoreline Sediment (SHDp) Units: nu-em/hr/ µCi/ml Nuclide Bone Liver Thvroid Kidne,, Lun11 Gilli Skin TotalBoclv CE-143 4.620E-O l 4.620E-Ol 4.620E-Ol 4.620E-01 4.620E--O I 4.620E--01 5.250E-OJ 4.620E--Ol CE-144 l.390E+-O I J.390E+OI l.390E+OI l.390E+OI 1.390E+o l l.390E+OI 1.610E+OI l.390E+OI PR-143 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO PR-144 3.670E-04 3.670E-04 3.670E--04 3.670E-04 3.670E-04 3.670E-04 4.220E-04 3.670E--04 ND-147 l.680E+OO l.680E+OO l.680E+OO l.680E+OO 1.680E+OO l.680E+OO 2.0IOE+OO l 680E+OO EU-152 2.969E+03 2.969E-+-03 2.969E+03 2.969E+03 2.969E-+-03 2.969E+03 3.436E+03 2.969E+03 W-187 4.700E-OI 4.700E-OI 4.700E--Ol 4.700E-01 4.700E--OI 4.700E-OI S.460E-OI 4.700E--Ol NP-239 3.420E-OI 3.420E-Ol 3.420E-Ol 3.420E-OI 3.420E-01 3.420E-OI 3.960E-Ol 3.4'.lOE-01 AppcndixD Ai Tec11 ShordincSedimau. Pagc4 of4 Page 9-115

Attachmeht 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manoal (ODCM)

APPENDIXE A 1Child Dose Factors for use in the Liquid Dose Calculations Age group: CHILD Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidnev Lum! Gilli Skin Total Body H-3 O.OOOE-100 1.180E+OI l.180E+OI 1.1 80E+Ol 1.180E+OI l.180E+O l O.OOOE+OO l.l80E+OI C- 14 7.030E+O: l.410E+OJ l.410E+02 1.410E+02 l.4IOE+o2 l.4l0E+02 O.OOOE+OO l.4\0E+02 NA-24 l.940E+02 l .940E+02 l.940E+02 l.940E+02 l.940E+02 1.940E+02 O.OOOE+OO 1.940E+02 P-32 4.680E+04 2.190E+03 0.000E+oO 0.000E+OO O.OOOE+oo l.290E+03 O.OOOE+OO l.800E+03 CR-5 1 0.000E+OO O.OOOE+OO 2.840E-01 7.750E-02 5.JSOE-01 2.710E+01 O.OOOE+OO 5.I JOE-01 l.VIN-54 O.OOOE+OO 6.210E+02 O.OOOE+OO l.740E+02 O.OOOE+OO 5.220E+02 0.000E+OO l .660E+02 MN-56 0.000E+oo 7.700E-OI O.OOOE+OO 9.320E-OJ O.OOOE+OO l.l20E+02 O.OOOE+OO l.740E-OJ FE-55 6.680E+02 3.550E+02 0.000E+OO 0.000E+OO 2.0lOE+02 6.570E+01 O.OOOE+OO l.lOOE+02 FE-59 9.5JOE+02 l.540E+03 O.OOOE+OO 0.000E+OO 4.470E+02 1.600E+03 O.OOOE+OO 7.670E+02 C0-58 O.OOOE+OO l.040E+02 O.OOOE+OO 0.000E+OO O.OOOE+OO 6.070E+02 O.OOOE+OO 3.190E+02 CO-60 o.ocr,E+oo 3.080E+02 O.OOOE+-00 O.OOOE+OO O.OOOE+oo l.700E+03 Q.OOOE+OO 9.070E+02 Nl-63 3.l 30E+04 l.670E+03 O.OOOE+OO O.OOOE+OO 0.000E:tOO l.130E+02 O.OOOE+OO l.060E+03 Nl-65 4.760E+OO 4.480E-Ol 0.000E+OO O.OOOE+oo 0.000E+OO 5.490E+Ol O.OOOE+OO 2.610E-OI CU-64 O.OOOE+OO 7.390E+OO O.OOOE+OO l.780E+Ol O.OOOE+OO 3.470E+02 O.OOOE+OO 4.460E+OO ZN-65 7.950E+02 2.120E+03 O.OOOE+OO l.340E+03 O.OOOE+oo 3.720E+02 0.000E+OO 1.320E+03 ZN-69 3.190E-04 4.610E-04 0.000E+OO 2.SOOE-04 O.OOOE+OO 2.900E-02 O.OOOE+OO 4.260E-05 SE-75 2.314E+02 8.902E+01 8.902E+O I 1.780E+Ol 2.136E+02 2.492E+02 O.OOOE+OO l .780E+03 I BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.060E-01 BR-84 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO l.780E-06 BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO l.300E-76 RB-86 0.000E+OO 3.820E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.460E+02 O.OOOE+OO 2.350E+03 RB-88 O.OOOE+OO 7.360E-12 0.000E+OO O.OOOE+OO 0.000E+OO 3.610E-l3 O.OOOE+OO 5.IIOE-12 RB-89 O.OOOE+OO 6.300E-l 4 O.OOOE+oO O.OOOE+OO O.OOOE+OO 5.490E-l6 O.OOOE+OO 5.600E-14 SR-89 7.620E+04 0.0008+00 O.OOOE+-00 0.0008+00 O.OOOE+OO 2.950E+03 0.(IOOE+OO 2.180E+03 SR-90 9.880E+05 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.330E+04 O.OOOE+OO 2.510E+05 Appendix F. Ai Child Water - Page I of 4 Page 9-116

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsito Dose Calculation Manual (ODCM)

APPENDIXE A, Child Dose Factors for use in the Liquid Dose Calculations Age group: CHILD Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidnc,* Lune GiUi Skin Total Boch SR-91 5.81 0E+02 O.OOOll+OO O.OOOE HlO O.OOOE+OO O.OOOE+oo l.280E+OJ O.OOOE+OO 2.190E+Ol SR-92 2.430E+Ol 0.000E+-00 O.OOOE+OO O.OOOE+OO O.OOOE+-00 4.610E+02 O.OOOE+OO 9.760E-01 Y-90 2.IOOE+OO O.OOOE+OO O.OOOE-+-00 O.OOOE+OO O.OOOE+OO 5.980E+03 0.000E+OO 5.620E-02 Y-91 3.480E+OI O.OOOE+-00 O.OOOE+OO O.OOOE+OO O.OOOE+-00 4.640E+-03 O.OOOE+OO 9.310E-01 Y-91M 9.860E-07 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO l.930E-03 O.OOOE+OO 3 590E-08 Y-92 2.000E-02 0.000E+OO 0.000E+-00 0.000E+OO O.OOOE+oo 5.770E+02 O.OOOE+OO 5.710E-04 Y-93 2.900E-Ol O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 4.330E+03 O.OOOE+OO 7.970E-03 ZR-95 6.71 0E+OO l.470E+OO O.OOOE+OO 21 JOE+OO 0.000E+OO 1.540E+OJ 0.000E+OO 1.310E+OO ZR-97 2.480E-O l 3.590E-02 O.OOOE+OO 5.ISOE-02 O.OOOE+oo 5.440E+03 0.000E+OO 2.120E-02 NB-95 l.300E+OO 5.040E-01 O.OOOE+OO 4.7408-01 0.000E+oo 9.330E+02 0.000E+OO 3.600E-OJ MQ-99 O.OOOE+OO 6.820E+02 O.OOOE+oo l.460E+03 O.OOOE+-00 , 5.640E+-02 O.OOOE+OO l.690E+02 TC-99M 1.350E-02 2.640E-02 0.000E+OO 3.840E-01 l.340E-02 l.500E+Ol 0.000E+OO 4.380E-Ol TC-101 3.330E-17 3.480E-17 O.OOOE+OO 5.9406-16 l.840E-17 l.l lOE-16 O.OOOE+OO 4.410E-16 RU-103 4.210E+Ol O.OOOE+OO O.OOOE+OO 1.060E+02 O.OOOE+OO 1.090E+03 O.OOOE+OO l.620E+Ol RU-105 5.750E-Ol O.OOOE+oo 0.()(JOE+0\1 5.060E+OO O.OOOE+-00 3.750E+02 O.OOOE+OO 2.090E-Ol RU-106 6.800E+02 O.OOOE+-00 O.OOOE+OO 9.180E+02 O.OOOE+-00 I.060E+04 0.000E+OO 8.480E+Ol AG-108M AG-JlOM l.81 8E+02 3.130E+Ol 6.991E+Ol 2.llOE+Ol 6.991E+OJ O.OOOE+OO 1.398E+Ol 3.940E+OI l.678E+02 O.OOOE+OO l .958E+02 2.510E+03 O.OOOE+OO O.OOOE+OO l.398E+03 I l.690E+Ol SN-113 7.249E+OJ 2.788E+-01 2.788E+Ol 5.576E+OO 6.692E+O\ 7.807E+Ol 0.000E+OO 5.576E+02 SN-117M 6.816E+Ol 2.62IE+Ol 2.621E+Ol 5.243E+OO 6.291E+<Jl 7.340E+-01 O.OOOE+OO 5.243E+02 SB-124 6.416E+02 8.324E+OO l.416E+o0 O.OOOE+OO 3.56IE+02 4.012E+03 0.000E+OO 2.249E+02 SB-125 4.161E+02 3.208E+OO 3.853E-Ol O.OOOE+OO 2.319E+-02 9.939E+02 O.OOOE+OO 8.71 8E+O l SB-126 2.488E+02 3.805E+OO l.459E+o0 O.OOOE+OO 1.187E+02 5.015E+03 0.000E+OO 8.933E+Ol TE-123M l .366E+02 5.255E+OI 5.255E+o l l.051E+OI L:!61E+02 l.471E+02 O.OOOE+OO l.051E+03 TE-125M 6.590E+02 l.790E+02 1.850E+02 0.000E+OO O.OOOEH)O 6.360E+02 O.OOOE+OO 8.780E+OI Appe1utix E Ai Child Water - Page 2 of 4 Page 9-117

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculnlion Manual (ODCM)

APPENDIXE A1 Child Dose Factors for use in the Liquid Dose Calculations Age group: CHILD Pathway: Potable Water (PWtr) Units: m1*em/hr / µCi/ml Nuclide Bone Liver l'hvroid Kidney Lun2 Gilli Skin Total Bodv TE-127 l.130E+OI 3.050E+OO 7.820E+OO 3.2l0E+01 O.OOOE+OO 4.41 0E+02 O.OOOE+OO 2.420E+OO TE-127M l.670E+03 4.5lOE+o2 4.000E+o2 4.780E+03 O.OOOE+OO l.360E+03 0.000E+OO l.99QE+02 TE-129 5.730E-03 1.600E-03 4.090E-03 1.680E-02 O.OOOE+OO 3.570E-01 O.OOOE+OO 1.360E-03 TE-129M 2.800E+03 7.830E+02 9.030E+-02 8.230E+03 O.OOOE+OO 3.420E+o3 O.OOOE+OO 4.350E+o2 TE-131 l.040E-08 3.160E-09 7.930E-09 3.140E-08 O.OOOE+OO 5.450E-08 O.OOOE+OO 3.090E-09 TE-131M 3.l70E+02 1.IOOE+02 2.260E+-02 l.060E+03 O.OOOE+OO 4.450E+03 0.000E+OO 1.170E+02 TE-132 5.280E+02 2.340E+o2 3.400E+02 2. l70E+03 O.OOOE+OO 2.350E+03 0.000E+oo 2.820E+02 I-130 8.650E+OI t.750E+02 l.930E+04 2.610E+02 O.OOOE+OO 8.180E<*OI 0.000E+OO 9.0IOE+OI l-131 9.580E+o2 9.630E+02 3.l90E+05 l .580E+03 O.OOOE+OO 8.580E+OI O.OOOE+OO 5.470E+02 I- 132 l .250E+OO 2.300E+OO l.070E+02 3.520E+OO O.OOOE+OO 2.71 0E+OO O.OOOE+OO 1.060E+OO I-133 2.3IOE+02 2.850E+02 5,300E+-04 4.750E+02 O.OOOE+OO 1.1 50E+o2 O.OOOE+OO l.080E+02 1-134 l.820E-.03 3.370E-03 7.760E-02 5.160E-03 O.OOOE+OO 2.240E-03 0.000E+OO 1.550E--03 l-135 2.890E+OI 5.2l0E+Ol 4.6l0E+o3 7.990E+OI O.OOOE+OO 3.970E+01 O.OOOE+OO 2.460E+OI CS-134 l.360E+04 2.230E+04 O.OOOE+-00 6.920E+03 2.480E+03 1.200E+02 O.OOOE+OO 4.710E+03 CS-136 l.330E+03 3.660E+03 0.000E+OO l.950E+03 2.9JOE+02 l.290E+02 O.OOOE+OO 2.370E+03 CS-137 l.900E+04 1.820E+o4 O.OOOE+oO 5.930E+03 2.130E+03 l.140E+<J2 O.OOOE+oo 2.69QE+<J3 CS-13& 2.440E--06 3.390E-06 O.OOOE+OO 2.380E-06 2.570E-07 l .5600-06 O.OOOE+OO 2.150E-06 BA- 133 l.091E+02 4. l94E+OI 4.194E+o l 8.389E+OO l.007E+02 I.I 74E+<J2 O.OOOE+OO 8.389E+o2 I BA- 139 5.9400-02 3.l70E-05 O.OOOE+OO 2.770E-05 l .860E-05 3.430E+OO O.OOOE+OO l.720E-03 BA- 140 4.700E+03 4.120E+OO O.OOOE+-0C1 1.340E+OO 2.460E+<JO 2.380E+<J3 O.OOOE+OO 2.740E+<J2 BA-141 l.620E-1l 9.050E-l 5 O.OOOE+OO 7.830E-15 5.310E-14 9.210E-12 O.OOOE+OO 5.260E-13 BA-142 1.800E-20 l.300E-23 O.OOOE+-00 I.OSOE-23 7.630E-24 2.350E-22 0.000E+OO 1.0IOE-2 l LA-140 4.780E.J)I 1.670E-01 O.OOOE+oO O.OOOE+OO O.OOOE+OO 4.650E+03 O.OOOE+OO 5.630E.J)2 LA-142 l.640E--04 5.210E-05 CI.OOOE+QO O.OOOE+OO O.OOOE+OO l.030E+OI 0.000E+OO l .630E-05 CE- 141 2.280E+OO l.140E+OO O.OOOE+OO 4.990E-OI O.OOOE+OO l.420E+03 O.OOOE+OO l.690E--O l Appmdix E Ai Child Water- Pagel of4 Page 9-118

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Siation Offsite Dose Calculation Manual (ODCM)

APPENDIXE A, Child Dose Factors for use in the Liquid Dose Calculations Age group: CHILD Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidnev Lun!! Gilli Skin Total Bodv CE-143 3. 160E-OI J.7 JOE+02 0.000E+OO 7. ISOE-02 O.OOOE+OO 2.5 l*E*OJ O.OOOE+OO 2.480E-02 CE-144 l.210E+02 3.790E+O l O.OOOE+-00 2.IOOE+O l O.OOOE+OO 9.870E+03 O.OOOE+OO 6.450E+OO PR-143 2.230E+OO 6.690E-01 O.OCN)E+OO 3.6208-01 O.OOOE+OO 2.400E+03 O.OOOE+OO 1.1 lOE-01 PR-144 2.200E-15 6.SOOE-16 O.OOOE+OO 3.600E-16 O.OOOE+-00 1.460E-12 O.OOOE+OO I.IIOE-16 ND-147 l.570E+OO l.270E+OO O.OOOE+OO 6.990E-01 O.OOOE+OO 2.020E+03 0.000E+OO 9.8608-02 EU-152 J.575E+OJ 6.5JIE+OO 0.000E-f-00 2.750E+OI O.OOOE+OO l.070E+03 O.OOOE+OO 7.732E+OO W-187 1.760E+OI l.040E+ol O.OOOE+OO O.OOOE+OO O.OOOE+OO l.460E+03 O.OOOE+OO 4.680E+OO NP-239 2.630E-OI J.890E-02 O.OOOE+OO 5.470E-02 0.000E,00 1.400E+OJ 0.000E+OO l.330E-02 Appendix E Ai Child Water - Page 4 of 4 Page 9-119

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offiute Dose Calculatton Manwl (ODCM)

APPENDIXE A, Child Dose Factors for use in the Liquid Dose Calculations Age group : CHILD Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/nil Nuclide Bone Liver l' hnoid Kidne]* LUO!! Gilli Skin TotalBodv H-3 O.OOOE+OO l.440E-01 l .440E-Ol l.440E--OI l.440E-01 l .440E-Ol O.OOOE+OO l.440E-Ol C-14 4.380E+04 8.760E+03 8.760E+03 8.760E+03 8.760E+03 8.760E+03 O.OOOE+OO 8.760E+03 NA-24 l.510E+02 1.510E+02 l.510E+02 l.SlOE+02 l.510E+02 l.S IOE+02 O.OOOE+oo l.S IOE+02 P-32 l.8SOE+06 8.680E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO S.130E+04 O.OOOE+OO 7.ISOE+04 CR-51 O.OOOE+OO O.OOOE+OO 7.580E-Ol 2.070E-01 l.380E+OO 7.240E+01 O.OOOE+OO l.370E+OO MN-54 0.000E+OO 3.360E+03 0.000E+-00 9.420E+02 O.OOOE+OO 2.820E+03 O.OOOE+OO 8.950E+02 MN-56 O.OOOE+OO I.650E-01 O.OOOE+OO 2.000E-01 O.OOOE+OO 2.400E+01 O.OOOE+OO 3.730E-02 FE-55 9.040E+02 4.790E+02 O.OOOE+OO O.OOOE+OO 2.710E+02 8.880E+O l O.OOOE+OO 1.490E+02 FE-59 l.280E+03 2.070E+03 O.OOOE+OO O.OOOE+OO 5.990E+02 2. 150E+03 O.OOOE+OO l.030E+03 C0-58 O.OOOE+OO 7.0lOE+Ol O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.090E+02 O.OOOE+OO 2.l50E+02 CO-60 O.OOOE+OO 2.080E+O:! O.OOOE+OO 0.000E+OO ,O.OOOE+OO l.150E+03 O.OOOE+OO 6.130E+02 NI-63 4.230Et04 2.270E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO l.530E+02 O.OOOE+OO l.440E+03 NI-65 2.370E-O l 2.230E-02 O.OOOE+-00 O.OOOE+OO O.OOOE+OO 2.740E+OO O.OOOE+OO 1.300E-02 CU-64 O.OOOE+OO 2.590E+-OO O.OOOE+OO 6.260E+OO O.OOOE+OO l.220E+02 O.OOOE+OO l.570E+OO ZN-65 2.150E+04 5.730E+04 O.OOOE+OO 3.6IOE+04 0.000E+OO l.OIOE+04 O.OOOE+OO 3.560E+04 ZN-69 l.080E-06 l.560E-06 O.OOOE+OO 9.470E-07 O.OOOE+OO 9.840E-OS O.OOOE+oo 1.440E-07 SE-75 6.244E+02 2.402E+02 2.402E+02 4.803E+Ol 5.764E+02 6.725E+02 0.000E+OO 4.803E+03 I BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+O/J O.OOOE+OO O.OOOE+oo 0.000E+OO O.OOOE+OO 5.340E-02 BR-84 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.570E-12 BR-85 O.OOOE+OO O.OOOE+OO OOOOE+-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.fJOOE+OO RB-86 O.OOOE+OO 1.020E+05 O.OOOE+OO 0.000E+OO O.OOOE+OO 6.530E+03 O.OOOE+OO 6.250E+04 RB-88 O.OOOE+OO l.330E-22 O.OOOE+OO O.OOOE+OO O.OOOE+OO 6.SIOE-24 O.OOOE+OO 9.220E-23 RB-89 O.OOOE+OO 1.580E-26 O.OOOE+OO O.OOOE+OO O.OOOE+OO l.370E-28 O.OOOE+OO l.400E-26 SR-89 3.070E+04 0.l~)OE+OO O.OOOE+-00 0.000E+OO O.OOOE+OO l.1901H03 0.(IOOE+OO 8.780E+02 SR-90 4.010E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 5.400E+03 O.OOOE+OO l.020E+05 Appendix E Ai Child fl'il1

• Page I of 4 Page 9-120

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation J\,fanual (ODCM)

APPENDIXE A, Child Dose Factors for use in the Liquid Dose Calculations Age group: CHILD Pathway: Frl'l!h Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidne,, Lune Gilli Skin Total Body SR-91 9.800E+Ol 0.000E+OO O.OOOE+-00 O.OOOE+OO O.OOOErOO 2.160E+02 0.000ErOO 3.700E+OO SR-92 4.580E-O l O.OOOE+OO 0.000E+-00 0.000E+OO O.OOOE+OO 8.670E+OO O.OOOE+OO l.840E-02 Y-90 6.240E-Ol 0.000E+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO 1.780E+03 O.OOOE+OO 1.670E-O'.l Y-91 1.170E+Ol O.OOOE+OO 0.000E+-00 0.000E+OO O.OOOE+oo l.560E+-03 O.OOOE+OO 3.130E-Ol Y-91M l.480E-11 O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO 2 900E-08 0.000E+OO 5.390E-13 Y-92 6.440E-04 0.000E+OO O.OOOE+-00 O.OOOE+OO O.OOOE+oo J.860E+Ol 0.000E+OO 1.840E-05 Y-93 4.JOOE-02 0.000E+oo O.OOOE+OO 0.000E+OO O.OOOE+OO 6.420E+02 O.OOOE+OO l.180E-03 ZR-95 2.980E-Ol 6.550E-02 O.OOOE>OO 9.370E-02 0.000E+OO 6.830E+Ol 0.000E+OO 5.830E-02 ZR-97 6.780E-03 9.790E-04 0.000E+-00 1.410E-03 0.000E+OO J.480E+02 O.OOOE+OO 5.780E-04 NB-95 5.210E+02 2.030E+02 O.OOOE+-00 l.900E+02 O.OOOE+OO 3.750E+05 O.OOOE+OO 1.450E+02 M0-99 O.OOOE+OO 8.l30E+Ol O.OOOE+-00 l.740E+o: O.OOOE+oo 6.720E+ol O.OOOE+OO 2.0IOE+Ol TC-99M 6.8608-04 USOE-03 0.0008+00 l.950E-02 6.8308-04 7.6500-01 O.OOOE+OO . 2.230E-02 TC-101 3.610E-33 3.7808-33 O.OOOE+-00 6.440E-32 2.000E-33 l.200E-32 0.000E+OO 4.790E-32 RU-103 5.6SOE+oo O.OOOE+oO O.OOOE+OO 1.420E+Ol O.OOOE+OO 1.460E+02 O.OOOE+OO 2.170E+OO RU-105 l.190E-02 0.000E+OO O.OOOE+-00 l.050E-01 0.000E+OO 7.790E+OO 0.000E+OO 4.330E-03 RU-106 9.190E+Ol O.OOOE+oo O.OOOE+-00 l.240E+02 O.OOOE+OO 1.430E+03 O.OOOE+oo l.150E+Ol AG-108M AG-llOM 2.459E+Ol 9.720E--Ol 9.459E+OO 6.570E-OI 9.459E+OO O.OOOE+-00 1.892E+OO 1.220E+oo 2.270E+Ol O.OOOE+OO 2.6488+01 7.810E+Ol O.OOOE+OO O.OOOE+OO 1.8926+02 5.250E--Ol I

SN-113 2.9338+03 l.12!IB+o3 1.1288+03 2.256E+02 2 7088+03 3.1598+03 O.OOOE+OO 2.256E+04 SN-ll7M 2.697E+03 1.037E+03 1.037E+03 2.074E+02 2.489E+03 2.904E+03 OOOOE+OO 2.074E+o4 S13-124 8.631E+02 1.120E+Ol l.905E+OO O.OOOE+OO 4.790E+02 5.3968+03 O.OOOE+OO 3.025E+02 SB-125 5.628E+02 4.339E+OO 5.212E-Ol 0.000E+OO 3.l36E+02 l.344E+03 O.OOOE+OO l.179E+02 SB-126 3.273E+02 5.006E+oo l.9198+-00 O.OOOE+OO J.562E+02 6.598E+03 O.OOOE+OO 1.175E+02 TE-123M 7.373E+02 2. 836H+02 2.836E+02 5.671 E+Ol 6.806E+02 7.940E+02 0.0008+00 5.67!E+o3 TE-125M 3.540H+03 9.610E+02 9.950E+02 O.OOOE+OO O.OOOE+OO 3.420E+03 O.OOOE+OO 4.730E+02 Appendix E Ai Child Fish

• Page 2 of 4 Page 9-121

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculatton Manual (ODCM)

APPENDIXE A1 Child Dose Factors for use in the Liquid Dose Calculations Age group: CHILD Pathway: Fresh Wate r Fish - Sport (FFSP) Units: mrem/hr / µCl/ml Nuclide Bone Liver Thvroid Kidne,, Lune Gilli Skin Total Bod~*

TE-127 2.520E+OI 6.80/JE+OO 1.750E+OI 7.170E+OI 0.000E+OO 9.850E+02 O.OOOE+OO 5.41 0E+OO TE-1 27M 9.040E+o3 2.430E+03 2.IOOE+o3 2.580E+04 O.OOOE+OO 7.320E+03 O.OOOE+OO l.070E+03 TE-129 2.280E-05 6.370E-06 l.630E-05 6.680E-05 O.OOOE+OO l.420E-03 O.OOOE+OO 5.420E-06 TE-l29M l.500E+04 4.190E+03 4.840E+o3 4.4IOE+04 O.OOOE+oo l.830E+o4 O.OOOE+OO 2.330E+03 TE-131 l.210E-16 3.680E-17 9.220E-17 3.650E-16 O.OOOE+OO 6.330E-16 O.OOOE+OO 3 590E-17 TE-131 M l.300E+03 4.500E+02 9.250E+o2 4.350E+03 O.OOOE+OO 1.820E+04 O.OOOE+OO 4.790E+02 TE-132 2.570E+o3 1.140E+o3 l.650E+-03 l.050E+04 0.000E+OO l.l40E+04 O.OOOE+OO l.370E+03 1-130 8.950E+OO l.810E+OI l.990E+03 2.700E+OI O.OOOE+OO 8.460E+-OO O.OOOE+OO 9.320E+OO 1-131 l.860E+o2 l.870E+02 6.l90E+o4 3.070E+02 O.OOOE+Ot) l.670E+OI O.OOOE+OO 1.060E+02 1-132 6.830E-03 l.250E-02 5.820E-Ol l.920E-02 O.OOIJE+OO 1.4806-02 O.OOOE+OO 5.770E-03 I-133 J .140E+Ol 3.880E+Ol 7.210E+03 6,470E+OI 0.000E+oo l.560E+Ol O.OOOE+OO l.470E+OI 1-134 2.750E-08 5.IOOE-08 l .170E-06 7.SOOE-08 O.OOOE+OO 3.380E-08 0.000E+OO 2.350E-08 I-135 1.670E+OO 3.0IOE+OO 2.660E+-02 4.6l0E+OO 0.000E+oo 2.290E+OO O.OOOE+oo l.420E+OO CS-134 3.680E+o5 6.040E+o5 O.OOOE+-00 l.870E+05 6.710E+04 3.250E+03 O.OOOE+OO 1.270E+05 CS-1 36 3.510E+04 9.640E+o4 O.OOOE+-00 5.l30E+04 7.660E+o3 3.390E+03 0.000E+OO 6.240E+04 CS- 137 5.140E+05 4.920E+05 O.OOOE+oo l.600E+05 5 770E+04 3.080E+o3 O.OOOE+OO 7.270E+04 CS-138 l.2 10E- 11 l.690E-11 O.OOOE+oo 1.190E-11 l.280E-12 7.770E-l2 O.OOOE+OO l.070E- ll BA-133 5.901E+OO 2.270E+OO 2.270E+OO 4.539E-Ol 5.447E+OO 6.355E+OO O.OOOE+OO 4.539E+O I BA-139 7.930E-06 4.230E-09 O.OOOE+t)O 3.700E-09 2.490E-09 4.5800-04 O.OOOE+OO 2.JOOE-07 BA- 140 2.480E+02 2.170E-Ol O.OOOE+OO 7.060E-02 l.:!90E-OI l.250E+02 O.OOOE+OO l.450E+Ol BA- 141 l.2IOE-24 6.SOOE-28 O.OOOE+OO 5.880E-28 3.990E-27 6.920E-25 O.OOOE+OO 3.950E-26 BA- 142 3.460E-42 2.490E-45 O.OOOE+-00 2.020E-45 l.470E-45 4.510E-44 O.OOOE+OO l.930E-43 LA- 140 l.310E-01 4.590E-02 O.OOOE+oO O.OOOE+OO 0.OOOE+oo l.280E+03 O.OOOE+OO 1.550E-02 LA- 142 2.970E-07 9.470E-08 O.OOOE+OO O.OOOE+OO O.OOtlE+oo l.880E-02 O.CIOOE+OO 2.960E-08 CE- 141 3.060E-02 l.520E-02 O.OOOE+OO 6.680E-03 O.OOOE+OO l.900E+OI O.OOOE+OO 2.260E-03 Appendix E Ai Child Fish

• Page 3 of 4 Page 9-122

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Mama! (ODCM)

APPENDIXE A, Child Dose Factors for use in the Liquid Dose Calculations Age group: CHILD Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thnoid Kidne" Lun!! Gilli Skin TotalB01h CE-143 3.320E-03 I.SOOE+OO O.OOOE+-00 7.5508--04 O.OOOE+OO 2.640E+OI 0.000E

• OO 2.610E-04 CE-144 l.630E+OO 5.l20E-Ol O.OOOE+oO 2.830E-Ol O.OOOE+OO l.330E+02 O.OOOE+OO 8.710E-02 PR-143 7.340E-OI 2.200E-01 O.OOOE-t-00 1.190E-Ol O.OOOE+OO 7.920E+02 O.OOOE+oo 3.640E-02 PR-144 2.180E-28 6.750E-29 O.OOOE+oo 3.570E-29 O.OOOE+oo l.450E-25 O.OOOE+OO l.lOOE-29 ND-147 5 1500-01 4.1708-01 O.OOOE+OO 2.290E-01 O.OOOE+OO 6.610E+02 0.000E+OO 3.230E-02 EU-152 W-187 2.418E+OI 2.0IOE+02 4404E+OO 1.190E+02 O.OOOE+-00 O.OOOE+-00 1.860E+OI O.OOOE+OO O.OOOE+OO O.OOOE+OO 7.236E+02 l.680E+04 0.000E+OO O.OOOE+OO 5.230E+OO 5.350E+OI I

NP-239 3.0SOE-02 2.210E-03 O.OOOE+-00 6.390E-03 0.000E+OO l.630E-,02 0.000E+OO 1.550E-03 Appendix E Ai Child Fi<d1 - Page 4 of 4 Page 9-123

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXE A1 Child Dose Factors for use in the Liquid Dose Calculations Age group: CHILD Pathway: Shoreline Sediment (SHDp) Units: mremlhr / µCl/ml Nuclide Bone Liver Thvroid Kidne,, Lun!! Gilli Skin Total Bodv H-3 O.OOOE+OO O. OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO C-14 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.0(IOE+OO O.OOOE+OO O.OOOE+OO NA-24 4.990E-Ol 4.990E-OI 4.990E-Ol 4.990E-OI 4.990E-O I 4.990E-O l 5.780E-OI 4.990E-OI P-32 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.0006+00 O.OOOE+OO CR-51 1.950E-Ol l.950E-OI l .950E-Ol l.950E-Ol l.950E-OI 1.950E-01 2.300E-Ol 1.950E-OI MN-54 5.790E+Ol 5.790E+ol 5.790E+OI 5.790E+Ol 5.790E+ol 5.790E+Ol 6.790E+OI 5.790E+Ol MN-56 3.770E-02 3.770E-02 3.770E-02 3.770E-02 3.770E--02 3.770E-02 4.450E-02 3.770E-02 FE-55 O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+oO O.OOOE+OO 0.0006+00 O.OOOE+OO FE-59 l.l40E+OI l.l40E+Ol l.140E+OI 1.1406+01 1.1406+01 1.1406+01 1.3406+0I l.1406+0I CO-58 l.580E+OI 1.5806+0I l.580E+OI 1.5806+0I l.580E+ol l.580E+01 l.850E+OI l.580E+OI CO-60 8.980E+02 8.980E+02 , 8.980E+02 8.980E+02 8.980E+o2 8.980E+02 l.060E+03 8.980E+02 ,

Nl-63 O.OQOE+OO O.OOOE+OO O.OOOE+OO 0.0006+00 O.OOOE+oo O.OOOE+oo O.OOOE+OO O.OOOE+OO Nl-65 J.240E-02 1.2408-02 l.240E-02 l.240E-02 l .240E-02 l.240E--02 l.440E-02 l.240E-02 CU-64 2.530E-02 2.530E-02 2.530E-02 2.530E--02 2.5306-02 2.530E-02 2.870E-02 2.530E-02 ZN-65 3.l20E+Ol 3.1206+01 3.120E+OI 3.120E+Ol 3.120E+01 3.120E+01 3.590E+Ol 3.l 20E+01 ZN-69 0.000E+OO 0.000E+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.0006+00 0.000E+OO 0.0006+00 SE-75 1.886E+OI l.886E+OI l.886E+Ol l.886E+01 l.886E+ol l.886E+ol 2.207E+OI 1.886E+OI BR-83 2030E-04 2.030E-04 2.030E-04 2.030E-04 2.030E-04 2.030E-04 2.960E-04 2.030E-04 BR-84 8460E-03 8.460E-03 8.460E-03 8.460E-03 8.4606-03 8.460E-03 9.870E-03 8.460E-03 BR-85 0.000E+OO 0.000E+OO 0.000E+OO 0.000E+OO 0.000E+OO O.OOOE+OO 0.0006+00 O.OOOE+OO RB-86 3.750E-01 3.750E-OI 3.750E-OI 3.750E-01 3.750E-01 3.7506-01 4.2906-01 3.750E-01 RB-88 1.3806-03 l.380E-03 l.380E-03 l.380E-03 l.380E-03 l.380E-03 I.SSOE-03 l.380E-03 RB-89 5.l30E-03 5.l30E-03 5.130E-03 5.130E-03 5.l30E--03 5.1306-03 6.l60E-03 5.130E-03 SR-89 9.0306-04 9.030E-04 9.030E-04 9.030E-04 9.030E-04 9.030E-04 1.05/JE-03 9.030E-04 SR-90 0.000E+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.0006+00 O.OOOE+OO O.OOOE+OO O.OOOE+OO Appendix E Ai Olild Shoreline Scduncnt. Pagel of 4 Page 9-124

Attachment 9 **

Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXE A1 Child Dose Factors for use in the Liquid Dose Calculations Age group: CHILD Pathway: Shoreline Sediment (SHDp) Un.its: nu-em/hr I µCi/ml Nuclide Bone Liver Tltvroid Kidne,* Lun2 Gilli Skin TotalBodv SR-91 8.970E-02 8.970E-02 8.970E-02 8.970E-02 8.970E-02 8.970E-02 1.050E-OI 8.970E-02 SR-92 3.2400-02 3.240E-02 3.240E-02 3.240E-02 3.240E-02 3.240E-02 3.600E-02 3.240E-02 Y-90 l.880E-04 l .880E-04 l .880E-04 l.880E-04 l.880E-04 1.880E-04 2.220E-04 1.880E-04 Y-91 4.480E-02 4.480E-02 4.480E--02 4.480E-02 4.480E-02 4.480E-02 5.040E-02 4.4S0E-02 Y-9IM 4.190E-03 4.l90E-03 4.190E-03 4.190E-03 4.190E-03 4.190E-03 4.850E-03 4.190E-03 Y-92 7.530E-03 7.530E-03 7.530E-03 7.530E-03 7.530E-03 7.530E-03 8.940E-03 7.530E-03 Y-93 7.660E-03 7.660E-03 7.660E-03 7.660E-03 7.660E-03 7.660E--03 l.0S0E-02 7.660E-03 ZR-95 l.020E+0I l.020E+Ol l.020E+0I 1.020E+ol l.020E+ol l.020E+OI l.190E+Ol 1020E+OI ZR-97 l.240E-0l l.240E-0I l.240E-0I l.240E-OI 1.240E-0I l.240E--OI 1.440E-0I 1.240E-OI NB-95 5.710E+OO 5.710E+OO 5.7IOE+OO 5.710E+OO 5.710E+oo 5.7lOE+OO 6.710E+OO 5.710E+OO M0-99 l.670E-0I I l.670E-0l 1.670E-0l 1.670E-Ol l.670E-OI l.670E--OI l.930E-0,1 l.670E-Ol TC-99M 7.680E-03 7.680E-03 7.680E-03 7.680E-03 7.680E-03 7.680E-03 8.810E-03 7.680E-03 TC-101 8.500E-04 8.SOOE-04 8.500E-04 8.500E-04 8.S00E-04 8.SOOE-04 9.440E-04 8.500E-04 RU-103 4.520E+OO 4.520E+oo 4.520E+OO 4.520E+OO 4.520E+OO 4.520E+OO 5.270E+OO 4.520E+00 RU-105 2.660E-02 2.660E-02 2.660E-02 2.660E-02 2.660E-02 2.660E-02 3010E--02 2.660E-02 RU-106 l.760E+OI l.760E+ol l.760E+0I l.760E+OI l.760E+Ol l.760E+0I 2.II0E+0I l.760E+0I AG-108M 2.153E+03 2.l53E+03 2.l53E+03 2. l53E+03 2.153E+o3 2.l53E+03 2.519E+03 2.153E+03 AG-llOM l.440E+02 I 440E+o2 l.440E+02 l.440E+02 l.440E+02 l.440E+02 l .670E+02 l.440E+02 SN-I 13 6 230E-OI 6.230E-01 6.230E-01 6.230E-01 6.230E-Ol 6.230E-Ol 7.2906-01 6.230E-01 SN-117M 8.707E-0I 8.707E-0l 8.707E-0l 8.707E-Ol 8.707E-01 8.707E-Ol l.019E+oo 8.707.E-0I S13-124 2.497.E+0I 2.497E+Ol 2.497.E+0l 2.497E+OI 2.497.E+ol 2497.E+0I 2.882E+0I 2.497E+0l SB-125 9.740E+0I 9.740E+Ol 9.740E+0I 9.740E+0I 9.740E+OI 9.740E+0I l.l00E+02 9.740E+01 SB-126 3.523E+oo 3.523E+o0 3.523E+OO 3.523E+OO 3.523E+OO 3.523E+OO 3.958E+OO 3.523E+OO TE-l23M 7.069E+OO 7.069E+OO 7.0696+00 7.0696+00 7.069E+OO 7.069E+OO 8.2706+00 7.069E+OO TE-l25M 6.480E-02 6.480E-02 6.480E-02 6.480E-02 6.480E--02 6.480E-02 8.880E-02 6.480E-02 Appendix E Ai 01ild Shoreline Scdimcnl *Pagel of-4 Page 9-125

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXE A1 Child Dose Factors for use in the Liquid Dose Calculations Age group: CHILD Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lun2 Gilli Skin Total Bod~*

TE-127 l.240E-04 1.240E-04 l.240E-04 l.240E-04 l.240E.()4 1.240E-04 l.370E-04 l.240E-04 TE-l27M 3.830E-03 3.830E-03 3.830E-03 3.830E-03 3.830E-03 3.830E-03 4.520E-03 3.830E-03 TE-129 I.I00E-03 J.I00E-03 1.IOOE-03 J.IOOE-03 I.IOOE-03 J.I OOE-03 l.300E-03 J.I OOE-03 TE-l29M 8.260E-0I 8.260E-OI 8.260E-0l 8.260E-Ol 8.260E-01 8.260E-Ol 9.650E-OI 8.260E-OI TE-131 l.220E-03 l .220E-03 l .220E-03 l.220E-03 l.220E-03 l.220E-03 I .440E+-O0 l.220E-03 TE-l31M 3.350E-0I 3.350E-OI 3.350E-OI 3.350E-OI 3.350E-01 3.350E-O I 3.950E-0I 3.350E~ll TE-132 l.770E-0l 1.770E-0l l.770E-0l l.770E-Ol l.770E-Ol l.770E-Ol 2.080E-0l l.770E-OI I-130 2.300E-0I 2.300E-01 2.300E-01 2.300E-01 2.300E-OI 2.300E-0I 2.790E-0I 2.300E-01 I-131 7.180E-0I 7.180E-0I 7.ISOE-01 7. IS0E-01 7.180E-OI 7.180E-O I 8.720E-0l 7.180E-Ol 1-132 5.200E-02 5.200E-02 5.200E-02 5.200E-02 5.200E-02 5.200E-02 6. 120E-02 5.200E-02 1-133 l.020E-0I l.020E-0l l.020E-0l I.0WE-01 l.020E-Ol l.020E-Ol 1.240E-0l l.020E-Ol 1-134 1.870E-02 l.870E-02 1.870E-02 l.870E-02 ' l.870E-02 1.870E-02 2.210E-02 l.870E-02 1-135 l.0SOE-01 I.0S0E-01 I.0SOE-01 I.0S0E-01 l.0S0E-01 I.0S0E-01 l.230E-0l I.0S0E-01 CS-134 2.860E+02 2.860E+02 2.860E+02 2.860E+02 2.860E+-02 2.860E+02 3.340E+02 2.860E+02 CS-136 6.300E+OO 6.300E+OO 6.300E+00 6.300E+OO 6.300E+oo 6.300E+00 7.140E+OO 6.300E+OO CS-137 4.290E+-02 4.290E+02 4.290E+o2 4.290E+02 4.290E+o2 4.290E+02 5.0I0E+02 4.290E+o2 CS-138 l.500E-02 I.S00E-02 l .SOOE-02 I.SOOE-02 l.SOOE-02 1.500E-02 l.710E-02 1.SOOE-02 BA-133 3.680E+02 3.680E+o2 3.680E+02 3.680E+02 3.6S0E+o2 3.680E+02 4.306E+02 3.680E+02 BA-139 4.420E-03 4.420E-03 4.410E-03 4.420E-03 4.420E-03 4.420E-03 4.970E-03 4.420E--03 BA-140 8..570E-0I 8.570E-0l 8.570E-0l 8.570E-OI 8.570E-OI 8.570E-Ol 9.SOOE-01 8.570E-01 BA-141 l.740E-03 l.740E-03 l .740E-03 l.740E-03 l.740E-03 l.740E-03 l.980E-03 l.740E--03 BA-142 1.870E-03 1.870E-03 l.870E-03 1.870E-03 l.870E-03 1.870E-03 2. ]30E-03 l. 870E-03 LA-140 8.020E-0I 8.020E-0l 8.020E-0l 8.020E-0l 8.020E-OI 8.020E--O l 9.090E-0I 8.020E-Ol LA-142 3.170E-02 3.170E-02 3.l 70E-02 3.l70E-02 3.170E-02 3.l 70E-02 3.810E-02 3.170E-02 CE-141 5.700E-0I 5.700E-Ol 5.700E-0l 5.?00E-01 5.700E-01 5.?00E-01 6.430E-0l 5.700E~) I Appendix E Al 01ildShorclinc Sediment* Pagel of

• Page 9-126

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXE A1 Child Dose Factors for use in the Liquid Dose Calculations Age group: CHILD Pathway: Shoreline Sediment (SHDp) Units: nuem/hr I µCi/ml Nuclide Bone Liver Thyroid Kidney Lune Gilli Skin

• Total Bod~*

CE-143 9.650E-02 9.6508-02 9.650E-02 9.650E-02 9.650E-02 9.650E-02 1.IOOE-01 9.650E-02 CE-144 1.900E+OO 2.900E+oo 2.900E+OO 2.900E+OO 2.900E*t00 2.900E+OO 3.360E+OO 2.900E+OO PR-143 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO 0.000E+OO PR-144 7.660E-05 7.660E-05 7.660E-05 7.660E-05 7.660E-05 7.660E-05 8.8108--05 7.660E-05 ND-147 3.500E-OI 3.500E-Ol 3.SOOE-01 3.500E-01 3.SOOE-01 3.SOOE-01 4.200E-OI 3.500E-01 EU-152 6.203E+02 6.203E+02 6.203E+02 6.203E+02 6.203E+o2 6.203E+02 7.180E+02 6.203E+02 W-187 9.820E-02 9.820E-02 9.820E-02 9.820E-02 9.820E-02 9.820E-02 l.140E-OI 9.820E-02 NP-239 7.140E-02 7.140E-02 7.140E-02 7.l40E-02 7.l40E-02 7.140E-02 8.270E-02 7.140E-02 Appemfoc E Ai 01itd Shoreline Sediment. Pagc4 of 4 Page 9-127

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Ocone~ Nuclear Station Offaite Dose Calculatton Mam11l (ODCM)

APPENDIXF A1Infant Dose Factors for use in the Liquid Dose Calculations Age group: INFANT Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Thyroid Kidne,, Lun2 Gilli Skin Total Body H-3 O.OOOE+OO 1.160E+OI l.l 60E+O l l.l60E+OI l. l60E+O I l.160E+O I O.OOOE+OO 1.1 60E+O I C- 14 8.920E+02 l.900E+02 I.900E+02 l.900E+02 1.900E+02 l.900E+02 O.OOOE+OO l.900E+02 NA-24 2.l90E+02 2.l90E+02 2.l90E+02 2.l90E+02 2.190E+02 2.190E+02 O.OOOE+OO 2.l90E+02 P-32 6.240E+04 3.670E+03 O.OOOE+oO O.OOOE+OO O.OOOE+OO 8.450E+02 O.OOOE+OO 2.420E+03 CR-51 O.OOOE+OO O.OOOE+OO 3.420E-OI 7.470E-02 6.650E-Ol l.530E+OI 0.000E+OO 5.240E-01 MN-54 O.OOOE+OO 7.480E+02 O.OOOE+OO l.660E+02 O.OOOE+OO 2.750E+02 O.OOOE+OO l.690E+02 MN-56 O.OOOE+OO l.220E+OO 0.000E+OO I.OSOE+OO O.OOOE+OO 1.1 \OE+02 OJJOOE+OO 2.IOOE-01 FE-55 5.230E+02 3.380E+02 O.OOOE+oO O.OOOE+OO l.650E+02 4.290E+O I 0.000E+OO 9.030E+OI FE-59 l.1 50E+03 2.0IOE+03 0.000E+OO O.OOOE+OO 5.940E+02 9.590E+02 O.OOOE+OO 7.9 l0E+02 CO-58 O.OOOE+OO l.350E+02 O.OOOE+oO O.OOOE+OO 0.000E+OO 3.360E+02 O.OOOE+OO 3.360E+02 C0-60 O.OOOE+OO 4.060E+02 O.OOOE+OO O.OOOE+OO O.OOOE+OO 9.670E+o2 O.OOOE+OO 9.590E+02 NI-63 2.390E+o-1 l.470E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO 7.340E+O!' O.OOOE+OO 8.280E+02 NI-65 6.520E+OO 7.380E-01 O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.620E+o l O.OOOE+OO 3.360E-O l CU-64 0.000E+OO 1.190E+Ol O.OOOE+OO 2.0IOE+Ol 0.000E+OO 2.440E+02 0.000E l*OO 5.500E+OO ZN-65 6.910E+02 2.370E+o3 O.OOOE+OO 1.1 50E+03 O.OOOE+OO 2.000E+03 O.OOOE+OO I.090E+03 ZN-69 4.390E-04 7.9IOE-04 O.OOOE+oO 3.290E-04 0.000E+OO 6.4500-02 O.OOOE+OO 5.890E-05 SE-75 3.609E+02 l.388E+o2 l.388E+02 2.776E+OI 3.331E+02 3.886E+02 O.OOOE+OO 2.776E+03 4.200E-OI I

BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+oo BR-84 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.220E--06 BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+{IO O.OOOE+OO O.O()l)E+OO O.OOOE+oo OOOOE+OO I.SOOE-76 RB-86 0.000E+OO 6.280E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO l.6IOE+02 0.000E+OO 3.IOOE+03 RB-88 O.OOOE+OO l.250E-l I O.OOOE+OO 0.000E+OO O.OOOE+OO l.220E-l l O.OOOE+OO 6.840E-12 RB-89 0.000E+OO 9.960E-14 0.000E+oO 0.000E+OO O.OOOE+OO 3.3900-14 O.OOOE+OO 6.860E-14 SR-89 9.380E+04 O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO l .930E+o3 O.OOOE+OO 2.690E+03 SR-90 6.960E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 8.690E+03 O.OOOE+OO l.770E+05 Appendix F Ai Infant Water

• Page l of 4 Page 9-128

Attachm ent 9 Summar y of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station OfToitc Dose Calculation Manual (ODCM)

APPENDIXF A1Infant Dose Factors for use in the Liquid Dose Calculations Age group: INFANT Pathway: Potable Water (PWtr) Units: mrem/hr / µCi/ml Nuclide Bone Liver Th:vroid Kidne~* Lun2 Gilli Skin TotalBod:v SR-91 7.830E+02 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 9.270E+02 0.000E+OO 2.830E+Ol SR-92 3.350E+ol O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO 3.6 lOE+02 0.000E+OO l.240E+OO Y-90 2.870E+OO O.OOOE+OO 0.000E+{IO O.OOOE+OO O.OOOE+oo 3.970E+03 0.000E+OO 7.700E-02 Y-91 4.230E+OI 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.030E+03 O.OOOE*OO 1.\30E+OO Y-91M l.350E-06 O.OOOE+oo 0.000E+OO O.OOOE+OO O.OOOE+oo 4.SIOE-03 0.000E+OO 4.610E-08 Y-92 2.740E--02 O.OOOE+OO 0.000E+oo O.OOOE+OO O.OOOE+OO 5.240E+02 0.000E+OO 7.710E--04 Y-93 4 OIOE-01 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 3.170E+03 O.OOOE+OO l.090E--02 ZR-95 7.710E+OO l.880E+OO 0.000E+OO 2.020E+OO O.OOOE+OO 9.350E*r02 0.000E+OO l.330E+OO ZR-97 3.400E-Ol 5.840E-02 O.OOOE+OO 5.890E-02 O.OOOE+OO 3.720E+03 O.OOOE+OO 2.670E-02 NB-95 1.560E+OO 6.440E--Ol O.OOOE+OO 4.620E-01 O.OOOE+oo 5.440E+02 O.OOOE+OO 3.720E--Ol M0-99 0.000E+OO 1.130E+03 O.OOOE+oO l.680E+03 O.OOOE+f)O 3.710E+02 O.OOOE+oo 2.200E+02 TC-99M 1.SIOE-02 3.740E-02 O.OOOE+oo 4.020E--Ol 1.950E-02 1.090E+Ol 0.000E+OO 4.820E--Ol TC-101 4.570E-17 5.750E-17 0.000E+-00 6.840E-16 3.140E-17 9.780E-15 O.OOOE+OO 5.690E-16 RU-103 5.520E+OI O.OOOE+oo 0.000E+-00 l.150E+02 0.000E+OO 6.710E+02 O.OOOE+OO l.850E+Ol RU-105 7.850E--Ol O.OOOE+OO 0.000E+OO 5.770E+OO 0.000E+OO 3.120E+02 O.OOOE+OO 2.640E-OI RU-106 9.060E+O:? O.OOOE+oo O.OOOE+OO l.070E+03 O.OOOE+OO 6.880E+03 O.OOOE+OO 1.130E+02 AG-l08M 3.800E+02 l.462E+02 AG-llOM 3.740E+OI 2.730E+Ol l.462E+-02 O.OOOE+-00 2.923E+OI 3.910E+Ol 3.508E+02 O.OOOE+OO 4.09"'--E+02 l.420E+03 O.OOOE+OO O.OOOE+oo 2.923E+03 1.8lOE+OI I

SN-113 l.407E+02 5.4!2E+ol 5.412E+Ol l.082E+OI l.29\lE+02 l.5l5E+02 0.000E+OO l.082E+03 SN-117M l.358E+02 5.224E+Ol 5.224E+Ol 1.045E+OI 1.254E+02 l.463E+02 O.OOOE+OO l.045E+03 SB-124 8.004E+02 1.178E+-Ol 2.125E+OO 0.000E+OO 5.012E+O:? 2.469E+03 O.OOOE+oo 2.480E+02 SB-125 4.626E+02 4.475E+OO 5.791E-OI 0.000E+OO 2.903E+02 6.168E+02 0.000E+OO 9.515E+OI SB-126 2.949E+O:? 5.780E+OO 2.264E+OO O.OOOE+OO l.855E+02 3.055E+03 O.OOOE+OO l.065E+02 TE-123M 3.428E , 02 l.319E+02 l.319E ,02 2.637E+OI 3.164Er02 3.692E+02 O.OOOErOO 2.637E+03 TE-125M 8.710E+02 2.910E+-02 2.930E+o2 O.OOOE+OO O.OOOE+OO 4.150E+02 0.000E+OO 1.l80E+02 Appmdix F Ai lnfint Wafer - Page l of 4 Page 9-129

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation J\/lanual (ODCM)

APPENDIXF A1Infant Dose Factors for use in the Liquid Dose Calculations Age group: INFANT Pathway: Potable Water (PWtr) Units: nu*em/hr / µCi/ml Nuclide Bone Liver Thyroid Kidney Lun2 Gilli Skin Total Body TE-127 1.550E+O\ 5.200E+o0 l.260E+ol 3.790E+O\ 0.000E+OO 3.260E+02 O.OOOE+OO 3.340E+OO TE-1 27M 2.190E+03 7.280E+02 6.340E+o2 5.400E+03 O.OOOE+OO 8.850E+02 O.OOOE+OO 2.660E+02 TE-129 7.860E-03 2.7\0E-03 6.590E-03 1.960E-02 0.000E+OO 6.280E-01 O.OOOE+OO l.840E-03 TE-129M 3.7:!0E+03 \.280E+03 I .430E+03 9.3\0E+03 O.OOOE+OO 2.220E+03 O.OOOE+oo 5.730E+o2 TE-131 1.4200-08 5.250E-09 l.270E-08 3.640E-08 O.OOOE+OO 5.750E-07 O.OOOE+OO 3.990E-09 TE-131M 4.330E+02 1.740E+02 3.540E+o2 1.200E+03 O.OOOE+OO 2.940E+03 O.OOOE+OO l.440E+02 TE-132 7.030E+02 3.480E+o2 5. 140E+02 2.180E+03 O.OOOE+OO l.290E+03 O.OOOE+OO 3.250E+02 1-130 l.150E+02 2.530E+02 2.840E+-04 2.780E+02 O.OOOE+OO 5.430E+ol O.OOOE+OO l.020E+02 1-131 1.290E+03 l.520E+03 5.0IOE+05 1.780E+03 O.OOOE+OO 5.440E+O! O.OOOE+OO 6.700E+02 1-132 l.680E+OO 3.4\0E+OO l.600E+-02 3.800E+OO 0.000E+OO 2.760E+OO O.OOOE+OO 1.210E+OO 1-133 3.150E+02 4.590E+02 8.350E+04 5.400E+02 O.OOOE+OO 7.770E+Ol O.OOOE+OO 1.340E+02 1- 134 2.4400-03 4.990E-03 . l.160E-Ol 5.580E-03 O.OOOE+OO 5.1600-03 O.OOOE+OO l.780E-03 1- 135 3.900E+OI 7.750E+OI 6.950E+o3 8.640E+OI O.OOOE+OO 2.800E+OI O.OOOE+OO 2.830E+Ol CS-134 l.420E+04 2.640Et*04 O.OOOE+OO 6.810E+03 2.790E+03 7.180E+Ol O.OOOE* OO 2.670E+03 CS-136 l.680E+03 4.950E+03 O.OOOE+OO l.970E+03 4.030E+02 7.5IOE+OI O.OOOE+OO l.850E+03 CS-137 \.960E+04 2.300E+04 O.OOOE+oO 6. 170E+03 2.500E*03 7.\ 90E+OI O.OOOE+OO l.630E+03 CS-138 3.330E-06 5.4l0E-06 O.OOOE+oO 2.700E-06 4.210E-07 8.650E-06 O.OOOE+oo 2.620E-06 BA-133 3.98IE+02 1.531E+02 l.531E+<)2 3.062E+OI 3.674E+02 4.287E+02 O.OOOE+OO 3.062E+03 I BA-139 8.180E-02 5.420E-05 0.000E+OO 3.260E-05 3.290E-05 5.180E+OO O.OOOE+OO 2.370E-03 BA-140 6.260E+03 6.260E+OO O.OOOE+{IO l.490E+OO 3.840E+OO l.540E+03 O.OOOE+OO 3.230E+02 BA-141 2.220E-11 l.520E-14 O.OOOE+OO 9.140E-15 9.250E-1 5 2 7[QE.!I) O.OOOE+OO 7.000E-13 BA-142 2.460E-20 2.040E-c3 O.OOOE+oO l.180E-23 l.240E-23 I.OlOE-19 O.OOOE+OO \.2\0E-21 LA-140 6.460E-OI 2.550E-Ol O.OOOE+-00 0.000E+OO O.OOOE+OO 2.990E+03 O.OOOE+OO 6.SSOE-02 LA- 142 2.220E-04 8.\60E-05 O.OOOE+oO O.OOOE+OO 0.000E+OO l.390E+OI O.OOOE+CM) l.950E-05 CE-141 2.930E+OO 1.790E+OO O.OOOE+OO 5.SIOE-01 O.OOOE+OO 9.230E+02 O.OOOE+OO 2.IOOE-01 Appendix F Ai Infllnt Water

• Page 3 of 4 Page 9-130

Attachme nt *9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/201 8 Ocon<e Nuclear Station Off.site Dose Calculation 11,fanual (ODCM)

APPENDIXF A1Infant Dose Factors for use in the Liquid Dose Calculations Age group: INFANT Pathway: Potable Water (PWtr) Units: m.rem/hr / µCi/ml Nuclide Bone Liver Thvroid Kidnev Lun2 Gilli Skin Total Body CE-143 4.330E-Ol 2.870E+02 O.OOOE+OO 8.360E-02 0.000E+oo l.670E+03 O.OOOE+oo 3.270E-02 CE-144 1.120E+02 4.580E+Ol O.OOOE+<)O 1.850E+Ol O.OOOE+OO 6.430E+o3 O.OOOE+OO 6.270E+OO PR-143 2.980E+OO 1.1 lOE+OO O.OOOE+OO 4.140E-Ol O.OOOE+oo l.570E+03 O.OOOE+OO 1.480E-Ol PR-144 3.020E-15 1.l70E-15 O.OOOE+OO 4.240E-16 O.OOOE+OO 5.440E-l1 O.OOOE+OO l.520E-16 ND-147 2.020E+oo 2.070E+OO O.OOOE+OO 7.980E-Ol 0.CIOOE+OO l.310E+03 O.OOOE+OO l.270E-01 EU-152 2.535E+Ol W-187 2.400E+OI 6.734E+OO l.670E+Ol O.OOOE+OO O.OOOE+OO l.888E+OI O.OOOE+OO O.OOOE+OO O.CIOOE+OO 5.981E+02 9.790E+02 0.000E+OO O.OOOE+OO 5.680E+OO I 5.760E+OO NP-239 3.600E-Ol 3.220E-02 O.OOOE+OO 6.430E-02 O.OOOE+oo 9.320E+02 O.OOOE+OO J.820E-02 Appendix F Ai Infant Water

• Page 4 of 4 Page 9-131

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculat,on Manwl (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegmup: ADULT Pathway: Gl's/Cow/Milk (CMILK) Units: m 2 *mrcm/yr / µCi/sec; mrem/yr / 11Cilm1 (H.J C- 14)

Nuclide Bone Liver Thyroid Kidne,* L1m2 Gilli Skin Total Body H-3 O.OOOE+OO 7.630E+02 7.630E+02 7.630E+02 7.6308+02 7.6308+02 O.OOOF.+00 7.630E+02 C- 14 2.540E+04 5.080E+03 5.080E+03 5.080E+03 5.080E+03 5.080E+03 O.OOOE+OO 5.0800+03 NA-24 2.440E+06 2.440E+06 2.440E+06 2.440E+06 2.440E+o6 2.440E+06 O.OOOE+OO 2.440E+06 P-32 J.710E+IO l.060E+09 0.000E+-00 O.OOOE+OO 0.000E+OO 1.920E+09 0.000E+OO 6.6lOE+08 CR-51 0.000E+OO O.OOOE+OO l.710E+04 6.300E+03 3.790E+04 7.190E+06 O.OOOE+OO 2.860E+04 MN-54 0.000E+OO 8.410E+06 O.OOOE+OO 2.500E+06 O.OOOE+OO 2.580E+07 O.OOOE+OO 1.6lOE+06 MN-56 0.000E+-00 4.090E-03 0.000E+OO 5.l90E-03 O.OOOE+OO 1.310E-Ol O.OOOE+oo 7.260E-04 FE-55 2.510E+07 1.740E+07 O.OOOE+OO O.OOOE+OO 9.680E+06 9.950E+06 O.OOOE+OO 4.050E+06 FE-59 2.970E+07 6.980E+07 O.OOOE+-00 O.OOOE+oo l.950E+07 2.330E+o8 O.OOOE+OO 2.680E+07 CO-58 O.OOOE+OO 4.710E+06 OOOOE+OO O.OOOE+OO 0.000E+OO 9.550E+07 O.OOOE+OO l.060E+07 CO-60 0.000E+OO 1.640E+07 O.OOOE+-00 O.OOOE+OO 0.000E+OO 3.080E+08 O.OOOE+OO 3.620E+07 NI-63 6.730E+09 4.660E+08 O.OOOE+OO O.OOOE+do O.OOOE+OO 9.730E+07 O.OOOE+OO 2.260E+08 NI-6 5 3.?00E-01 4.SIOE-02 0.000E+OO 0.l)OOE+OO 0.000E+OO l.220E+O<J u.OOOE+OO 2.190E-02 CU-64 O.OOOE+OO 2.380E+04 O.OOOE+OO 6.0l0E+04 O.OOOE+OO 2.030E+06 O.OOOE+oo l.l20E+04 ZN-65 l.370E+09 4.370E+09 O.OOOE+OO 2.920E+09 O.OOOE+OO 2.750E+09 O.OOOE+OO l.970E+09 ZN-69 2.090E-12 4.000E-12 O.OOOE+-00 2.600E-12 0.000E+OO 6.0IOE-13 O.OOOE+OO 2.780E-13 BR-83 0.0()()E+OO 0.CIOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO l .400E-01 0.0<)0E+OO 9.720E~l2 BR-84 0.000E+OO O.OOOE+OO 0.000E+oO O.OOOE+OO O.OOOE+OO t.:!60E-28 0.000E+OO l.6lOE-23 BR-85 O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO RB-86 O.OOOE+OO 2.590E+09 O.OOOE+OO O.OOOE+OO 0.000E+OO 5. l20E+08 O.OOOE+OO l.210E+09 RB-88 U.OOOE+OO 2.140E-45 O.OOOE+-00 O.OOOE+OO O.OOOE+OO 2.960E-56 0.000E+OO l.l40E-45 RB-89 O.OOOE+OO 4.330E-S3 O.OOQE;*OO O.OOOE+OO 0.000E+OO 2.5100-66 0.000E+OO 3.0406-53 SR-89 1.450E+09 O.OOOE+oo O.OOOE+oO O.OOOE+OO 0.000E+OO 2.330E+08 O.OOOE+OO 4.160E+07 SR-90 4.680E+ IO 0.000.E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO l.350E+09 O.OOOE+OO 1.l50E+10 SR-91 2.890E+04 O.OOOE+OO O.OOOE+{IO 0.000E+OO O.OOOE+-00 l.380E+05 O.OOOE+oo l.l 70E+-03 Appendix G Ri A~l1 Cow Milk. - Page I of 3 Page 9-132

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegl'Oup: ADULT Pathway: G!'s/Cow /Milk (CMILK) Units: m 2 *mrem/yr I µCi/sec; mrem/vr /uCi/1n1 (H.J C-14)

Nudlde Bone Liver Thyroid Kidnev Lun2 Gilli Skin TotuIBody SR-92 4.880£-01 O.OOOE+oO O.OOOE+<lO O.OOOE+OO O.OOOE+OO 9.680E+OO 0.000E+OO 21 JOE.02 Y-90 7.080E+OI 0.000E+OO 0.000E+oO O.OOOE+OO OOOOE+OO 7.510E+05 0.000E+OO 1.900E+OO Y-91 8.590E+03 O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 4.730E+06 O.OOOE+OO 2.300E+02 Y-91M 5.980E-20 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO J.760E-19 O.OOOE+OO 2.320E-21 Y-92 5.580E.05 O.OOOE+OO O.OOOE+oo 0.000E+OO 0.000E+oO 9.770E-O\ O.OOOE+OO l.630E-06 y.93 2.230E-Ol 0.000E+OO O.OOOE+oo O.OOOE*HJO O.OOOE+OO 7.090E+03 U.OOOE+OO 6.170E-03 ZR-95 9.430E+02 3.030E+o2 O.OOOE+oO 4.750E+02 O.OOOE+OO 9.590E+05 0.000E+OO 2.050E+02 ZR-97 4.330E-Ol 8.740E-02 O.OOOE+OO l.320E-01 O.OOOE+OO 2.710E+04 O.OOOE+OO 4.000E.02 NB-95 8.260E+04 4.590E+04 O.OOOE+OO 4.540E+04 O.OOOE+OO 2.790E+08 0.000E+OO 2.470E+o4 M0-99 O.OOOE+OO 2.480E+07 O.OOOE+OO 5.610E+07 O.OOOE+OO 5.740E+07 O.OOOE+OO 4.7\0E+06 TC-99M 3.320E+OO 9.380E+OO O.OOOE+OO l.420E+02 4.600E+OO 5.550E+03 O.OOOE+OO l.200E+02 TC-101 2.590E-60 3.740E-60 0.0008"00 6.730E-59 J.910E-60 l.120E-71 O.OOOE+OO 3.670E-59 RU-103 l.020E+03 0.000E+OO O.OOOE+OO 3.890E+03 O.OOOE+OO l.190E+05 0.000E+OO 4.390E+02 RU-105 8.570E.04 0.000E+OO O.OOOE+OO I.I IOE-02 O.OOOE+OO 5.240E-OI O.OOOE+OO 3.380E-04 RU-106 2.040E+04 O.OOOE+OO O.OOOE+OO 3.940E+04 O.OOOE+OO l.320E+06 O.OOOE+OO 2.580E+03 AG-llOM 5.820E+07 S.390E+07 O.OOOE+oO l.060E+08 O.OOOE+OO 2200E+\0 0.000E+OO 3.200E+o7 TE-125M 1.630E+07 S.900E+06 4.900E+o6 6.630E+07 O.OOOE+OO 6.500E+07 O.OOOE+OO 2.180E+06 TE-127 6.530E+02 2.340E+02 4.840E+02 2.660E+03 O.OOOE+OO 5.150E+04 O.OOOE+OO l.410E+02 TE-127M 4.580E+07 l.640E+07 1.170E+-07 1.860E+08 O.OOOE+OO l.540E+08 O.OOOE+OO 5.580E+06 TE-129 2.830E-10 J.060E-10 '.!.l70E-10 l.190E-09 0.000E+OO 2.130E-IO O.OOOE+OO 6.SSOE-11 TE-J29M 6.020E+07 2.250E+o7 2.070E+o7 2.510E+08 O.OOOE+OO 3.030E+08 O.OOOE+OO 9.530E+06 TE-131 3.600E-33 l .SOOE-33 2.960E-33 1.5806-32 O.OOOE+OO 5.lOOE-34 O.OOOE,oo l.140E-33 TE-131M 3.610£+05 J.770E+OS 2.800E+o5 l.790E+06 O.OOOE+OO J.750E+07 O.OOOE+OO J.470E+05 TE-132 2.400E+06 J.S50E+06 J.720E+06 l .500E+07 0.000E+OO 7.350E+07 O.OOOE+OO J.460E+06 l-l30 4.200E+OS l.240E+06 1.0SOE+{IS l.930E+06 O.OOOE+OO 1.070E+06 O.OOOE+OO 4.890E+o5 Appendix G Ri Adllt Cow Milk. Page 2 of3 Page 9-133

Atta*chment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offsite Dose Calculat,on Manual (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegl'Oup: ADULT Pathway: G1-s/Cow~filk (CMILK) Units: m2 *mrcm/yr / µCi/sec; mrem/yr / 11Cilm1 (H.J. C-14)

Nuclide Bone Liver Thvroid Kidne,* Lun2 Gliil Skin Total Body I-131 2.960E+08 4.230E+08 1.390E+ll 7.260E+08 O.OOOE+OO l.120E+08 O.OOOE+OO 2.430E+08 I-132 l.640E-Ol 4.390E-OI l.540E+OI 7000E-Ol O.OOOE+OO 8.250E-02 0.000E+OO l.540E-Ol 1-133 3.870E+o6 6.730E+06 9.890E+o8 l.170E+07 O.OOOE+OO 6.050E+o6 O.OOOE+OO 2.050E+06 I-134 2.020E-12 5.480E-12 9.490E-1I 8.7JOE-l2 O.OOOE+OO 4.770E-15 0.000E+OO 1.960E-12 1-135 l.280E+04 3.360E+04 2.220E+o6 5.390E+04 O.OOOE+OO 3.800E+04 O.OOOE+OO 1.240E+04 CS-134 5.650E+09 1.350E+10 O.OOOE+OO 4.35oE+U9 1.450E+09 2.350E+08 O.OOOE+OO l.lOOE+l O CS-136 2.630E+08 l.040E+09 0.000E+oO 5.780E+08 7.930E+o7 l.180E+o8 O.OOOE+OO 7.480E+08 CS-137 7.380E+09 I.OJOE+JO O.OOOE+OO 3.430E+09 l.140E+09 l.950E+08 0.000E+OO 6.6l OE+09 CS-138 9.0SOE-24 1.790E-23 O.OOOE+OO l.3 10E-23 l.300E-24 7.620E-29 0.000E+OO 8.850E-24 BA-139 4.420E-08 3.JSOE-11 O.OOOE+OO 2.940E-11 l.790E-11 7.8300-08 O.OOOE+OO J.290E-09 BA- 140 2.690E+07 3.380E+04 O.OOOEtOO 1.150E+04 l.930E+04 5.530E+07 O.OOOE+OO l.760E+06 BA- 141 ' 4.090E-46 3.090E-49 2.720E-83 O.OOOE+OO 0.000E+OO 2.880E-49

2. 300E-83 J.760E-49 l.540E-83 l.930E'-55 3.720E-98 O.OOOE-1-00 0.000E+OO L380E-47 l.660E-81 BA-142 2.640E-80 LA-140 4.510E+OO 2.270E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.670E+o5 O.OOOE+OO 6.0IOE-01 LA-142 J.860E-11 8.460E-12 0.000E+OO 0.000E+OO O.OOOE+OO 6.J?OE-08 O.OOOE+OO 2. I l OE-12 CE-141 4.840E+03 3.280E+03 O.OOOE+OO l.520E+03 0.000E+OO l.250E+07 O.OOOE+OO 3.720E+02 CE-1.43 4.160E+OJ 3.070E+04 O.OOOE+OO J.350E+OI O.OOOE+OO l.150E+06 O.OOOE+OO 3.400E+OO CE-144 3.580E+05 l.500E+05 0.000E+OO U70E+04 0.000E+OO L2 10E+o8 0.000E+OO l.920E+04 PR-143 l.580E+02 6.330E+OI 0.000E+OO 3.660E+OI O.OOOE+OO 6.920E+05 0.000E+OO 7.830E+OO PR-144 5.870E-54 2.440E-54 O.OOOE+oo l.380E-54 0.000E+OO 8.450E-61 O.OOOE+OO 2.990E-55 ND-147 9.420E+OJ 1.090E+o2 O.OOOE+oO 6.360E+OI O.OOOE+OO 5.220E+o5 O.OOOE+OO 6.51 0E+OO W- 187 6.510E+03 5.450E+03 O.OOOE+OO O.OOOE400 O.OOOE+OO J.780E+06 O.OOOE , 00 1.900E+03 NP-239 3.670E+OO 3.610E-01 O.OOOE+OO l.130E+OO O.OOOE+OO 7.4 JOE+o4 O.OOOE+OO 1.990E-01 AWcndix G Ri Adult Caw Milk - Page 3 of 3 Page 9-134

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation tvlanual (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Goat/Milk (GMILK) Units: m 2*m1*em/yr / µCi/sec; mren1/vr / uCilm' ffi.J C-141 Nuclide Bone Liver Thyroid Kidney Lune Gilli Skin Total Body H-3 O.OOOE+OO l.560E+03 J.560E+03 l.560E+03 1.560E+03 l.560E+03 O.OOOE+OO l.560E+03 C-14 2.540E+04 5.080E+03 5.080E+03 5.080E+03 5.080E+OJ 5.080E+03 O.OOOE+OO 5.080E+03 NA-24 2.930E+05 2.930E+05 2.930E+05 2.930E+05 2.930E+05 2.930E+05 O.OOOE+OO 2.930E+05 P-32 2.050E+ IO 1.280E+09 O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.3JOE+09 O.OOOE+OO 7.930E+08 CR-51 0.000E+OO O.OOOE+OO 2.050E+03 7.550E+02 4.550E+03 8.620E+05 O.OOOE+OO 3.430E+03 MN-54 O.OOOE+OO 1.0JOE+06 0.000E+OO 3.000E+OS 0.000E+OO 3.090E+06 O.OOOE+OO l.930E+05 MN-56 O.OOOE+OO 4.910E-04 O.OOOE+OO 6.230E-04 0.000E+oo l .570E-02 O.OOOE+OO 8.710E-05 FE-55 3.260E+05 2.260E+05 0.000E+<lO O.OOOE+OO 1.260E+05 1.290E+05 O.OOOE+oo 5.260E+04 FE-59 3.860E+05 9.070E+05 0.000E+OO 0.000E+OO 2.540E+05 3.020E+06 O.OOOE+OO 3.480E+05 CO-58 O.OOOE+oo 5.660E+05 0.000E+OO O.OOOE+OO O.OOOE+OO I.ISOE+07 O.OOOE+OO 1.270E+06 CO-60 0.000E+OO l.970E+06 O.OOOE+OO O.OOOE+OO 0.000E+OO 3.700E+07 0.000E+OO 4.340E+06 NI-63 8.070E+08 5.600E+07 O.OOOE+oO O.OOOE+OO 0.00\)E+OO l.170E+07 O.OOOE+OO 2.710E+07 NI-65 4.440E-02 5.770E-03 0.000E+OQ O.OOOE+OO O.OOOE+OO l.460E-Ol 0.000E+OO 2.630E-03 CU-64 O.OOOE+OO 2.660E+03 O.OOOE+OO 6.700E+03 O.OOOE+oo 2.260E+05 0.000E+OO l .250E+03 ZN-65 1.650E+08 5.240E+08 0.000E+OO 3.500E+08 O.OOOE+OO 3.300E+08 0.000E+OO 2.370E+08 ZN-69 2.SIOE-13 4.800E-13 0.000E+OO 3.120E-13 O.OOOE+OO 7.210E-14 0.000E+OO 3.340E-14 BR-83 0.000E+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO l.680E-02 O.OOOE+oo l.l 70E--02 BR-84 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO l.520E-29 O.OOOE+OO l.930E-24 BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO RB-86 0.000E+OO 3.1IOE+08 O.OOOE+oo O.OOOE+OO 0.000E+OO 6.140E+07 O.OOOE+OO l.450E+08 RB-88 O.OOOE+OO 2.570E-46 O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.550E-57 O.OOOE+OO 1.360E-46 RB-89 0.000E+OO 5. 190E-54 0.000E+OO 0.000E+OO 0.000E+OO 3.0200-67 O.OOOE+OO 3.650E-54 SR-89 3.050E+09 0.000E+OO 0.000E+oO O.OOOE+OO 0.000E+OO 4.890E+08 0.000E+OO 8.750E+07 SR-90 9.830E+ IO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.840E+09 O.OOOE+OO 2.4 JOE+JO SR-9 1 6.070E+04 O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 2.890E+05 O.OOOE+OO 2.450E+03 AppcndixG Ri Adult Goat Milk-Page 1 ofl Page 9-135

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nucl011r Station Offsitc Dose Calculation !1,1anual (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Goat&filk (GMILK) Units: m 2*m1*em/yr I µCi/sec; mrem/vr f llCilot' (H-3 C-14)

Nuclide Hone Liver Thyroid Kidney Lun2 Gilli Skin Total Body SR-92 1.030E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.030E+OJ O.OOOE+OO 4.440E-02 Y-90 8.500E+OO O.OIJOE*OO 0.000E+OO O.OOOE+OO O.OOOE+OO 9.0IOE+04 O.OOOE>OO 2.280E-O I Y-91 1.030E+03 O.OOOE+OO O.OOOE tOO O.OOOE+OO O.OOOE+OO 5.670E+-05 O.OOOE+OO 2.760E+O I Y-91M 7.l70E-21 O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO 2. l lOE-20 O.OOOE+OO 2.780E-22 Y-92 6.690E-06 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 1.170E-O l O.OOOE+OO l.960E-07 y.93 2.680E-02 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 8.500E+02 0.000E+OO 7 400E-04 ZR-95 l.130E+02 3.630E+OI O.OOOE+oo 5.700E+O I O.OOOE+OO 1.150E+05 O.OOOE+OO 2.460E+OI ZR-97 5.200E-02 1.0SOE-02 O.OOOE+OO 1.580E-02 O.OOOE+OO 3.250E+03 O.OOOE+OO 4.SOOE-03 NB-95 9.9lOE+03 5.510E+03 0.000E+oo 5.450E+03 O.OOOE+OO 3.340E+07 O.OOOE+OO 2.960E+OJ MO-99 O.OOOE+OO 2.970E+06 O.OOOE+OO 6.730E+06 O.OOOE+OO 6.890E+06 O.OOOE+OO 5.660E+05 TC-99M 3.980E-O I l.130E+oo O.OOOE+OO l.710E+O I 5.520E-01 6.660E+02 O.OOOE+OO l.430E+OI TC-IOI 3. 1lOE-61 4.490E-pl O.OOOE+oo 8.0SOE-60 2.290E-61 l.350E-72 O.OOOE+OO 4.40(.IE-60 RU-103 l.220E+02 O.OOOE+OO 0.000E+OI) 4.660E+02 O.OOOE+OO l.430E+04. IJ.OOOE+OO 5.260E+O I RU-105 l.030E-04 O.OOOE+OO O.OOOE+oo l.330E-03 O.OOOE+OO 6.290E-02 O.OOOE+OIJ 4.060E-05 RU-106 2.450E+03 O.OOOE+oo O.OOOE+l)0 4.730E+03 O.OOOE+OO 1.580E+OS O.OOOE+OO 3.100E+02 AG-ll0M 6.990E+06 6.460E+06 O.OOOE+oo 1.270E+07 O.OOOE+OO 2.640E+09 0.000E+OO 3.840E+06 TE-l25M 1.950E+06 7.080E+05 5.880E+-05 7.950E+06 O.OOOE+OO 7.800E+o6 O.OOOE+OO 2.620E+05 TE-127 7.830E+OI 2.810E+-Ol 5.800E+-O l 3.190E+02 O.OOOE+OO 6.180E+03 0.000E+OO 1.700E+O I TE-127M 5.490E+06 l.960E+06 1.400E+06 2.230E+07 O.OOOE+OO 1.840E+07 O.OOOE+OO 6.690E+05 TE-129 3.390E-11 l.270E-11 2.600E- l 1 l.430E-10 O.OOOE+OO 2.560E-1 1 O.OOOE+OO 8.260E-12 TE-l29M 7.220E+06 2.690E+06 2.480E+06 3.020E+07 O.OOOE+OO 3.640E+o7 O.OOOE+oo 1.140E+06 TE-131 4.320E-34 1.810E-34 3.550E-34 l.890E-33 0.000E+OO 6.1200-35 0.000E*OO 1.360E-34 TE-131M 4.330E+04 2.l20E+04 3.360E+04 2.150E+05 O.OOOE+OO 2.IOOE+06 O.OOOE+OO  !.770E+04 TE-132 2.880E+05 l.860E+05 2.060E+05 l.800E+06 O.OOOE+OO 8.820E+06 O.OOOE+OO  !.750E+05 I-130 5.040E+05 l.490E+06 l.260E+-08 2.320E+06 O.OOOE+OO l.280E+06 O.OOOE+OO 5.870E+05 Appendix G Ri Adult Goat Milk

• Page 2 of3 Page 9-136

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIXG R1 Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Goat/Mllk (GMILK) Units: m 2*nll'em/yr / µCi/sec; mrem/vr / 11Cilm' (H.J C-14)

Nuclide Bone Liver Thvrold Kidnev Lunt! Gilli Skin TotalBodv 1-131 3.550E+08 5.080E+08 1.670E+ll 8.710E+08 O.OOOE+OO 1.340E+08 O.OOOE+OO 2.910E+08 1-132 1.970E-Ol 5.27013-01 l.840E-t-OI 8.4008-01 O.OOOE+OO 9.9000-02 O.OOOE+OO l.840E-Ol

[-133 4.640E+06 8.0808+06 l.190E+09 1.4108+07 O.OOOE+OO 7.260E+-06 0.0008+00 2.460E+06 1-134 2.420E-12 6.57013-12 l.140E-\O 1.0SOE-11 0.0008+00 5.730E-15 O.OOOE+OO 2.350E-12 I-135 l. 540E+04 4.030E+04 2.660E+06 6.470E+04 O.OOOE+oo 4.560E+o4 0.0008+00 1.4908+04 CS-134 1.7008+10 4.0-IOE+lO O.OOOE+OO l.310E+IO 4.340E+09 7.060E+08 O.OOOE+OO 3.3008+10 CS-136 7.9008+08 3.120E+09 O.OOOE-t-00 1.7308+09 2.380E+o8 3.540E+08 0.0008+00 2.240E+09 CS-137 2.210E+ IO 3.030E+JO O.OOOE+oO 1.0308+10 3.420E+09 5.8608+08 O.OOOE+OO 1.9808+10 CS-138 2.7108-'.!3 5.360E-23 O.OOOE+OO 3.940E-23 3.890E-24 2.290E-28 O.OOOE+OO 2.650E-23 BA- 139 5.300E-09 3.780E-12 O.OOOE+oO 3.530E-12 2.140E-12 9.400E-09 O.OOOE+OO l.550E-10 BA-140 3.230E+06 4.0508+o3 0.0008+00 l.380E+03 2.3208+03 6.6408+06 0.000E+OO 2.l lOE+OS BA- I41 4.91QE-47 3.7108-50 O.OOOE+OO 3.450E-50 2.IIOE-50 2.310E-56 o.pooE+oo l.660E-48 BA-142 3.170E-81 3.260E-84 O.UOOE+OO 2.750E-84 1.850E-84 O.OOOE+OO O.OOOE+OO 2.000E-82 LA- 140 5.4\0E-01 2.730E-01 O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.000E+o4 O.OOOE+oo 7.210E-02 LA-142 2.230E-12 1.0IOE-12 O.OOOE+OO O.OOOE+OO O.OOOE+OO 7.410E-09 0.000E+OO 2.530E-13 CE-141 5.810E+02 3.930E+02 O.OOOE+oO l.830E+02 O.OOOE+OO I.500E+06 O.OOOE+OO 4.460E+OI CE-143 4.990E+OO 3.690E+o3 O.OOOE+oO l.620E+OO O.OOOE+OO l.380E+05 O.OOOE+oo 4.0SOE-01 CE-144 4.290E+04 1.790E+o4 O.OOOE+OO l.060E+04 O.OOOE+OO 1.450E+07 O.OOOE+OO 2.300E+03 PR-143 l.890E+Ol 7.600E+OO 0.000E+OO 4.390E+OO O.OOOE+OO 8.300E+o4 O.OOOE+OO 9.390E-Ol PR-144 7.050E-55 2.930E-55 O.OOOE+OO l.6500-55 O.OOOE+OO l.OIOE-61 O.OOOE+OO 3.580E-56 ND-147 l.1 30E+Ol l.310E+ol O.OOOE+oO 7.630E+oo O.OOOE+OO 6.270E+04 O.OOOE+OO 7.8\0E-01 W-187 7.820E+02 6.530E

• 02 O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.140E+05 0.000E+OO 2.280E+02 NP-239 4.4 \0E-01 4.330E-02 O.OOOE+oo l.350E-Ol O.OOOE+OO 8.890E+o3 0.000E+OO 2.390E-02 Appendi,c G Ri Adult Goal Milk- Page 3 of 3 Page 9-137

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nucloar Station Off.site Dose Calculation Manual (ODCM)

APPENDIXG R, Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: A DULT Pathway: Grs/Cow/Meat (CMEAT) Units: m 2 *mrem/yr / µCi/sec; m.-em/vr / 1,1Cii111' (H-3, C-141 Nuclide Bone Liver Thvroid Kidnev Lun!" Gilli Skin Total Rodv H-3 O.OOOE+OO 3.250E+02 3.250E-t-02 3.250E+02 3.250E+02 3.250E+02 O.OOOE+OO 3.250E+02 C- 14 2.330E+04 4.660E+03 4.660E+03 4.660E+03 4.660E+03 4.660E+03 0.000E+OO 4.660E+03 NA-24 1.360E.03 1.360E-03 l.360E.03 l.360E.03 l.360E-03 1.360E.03 O.OOOE+OO 1.360E.03 P-32 4.660E+09 2.900E+08 O.OOOE-t-00 O.OOOE+OO O.OOOE+oo 5.240E+08 O.OOOE+OO l.800E+08 CR-51 O.OOOE-t-00 O.OOOE-+-00 4.210E+OJ 1.550E+03 9.350E+03 l.770E+06 O.OOOE+OO 7.050E+03 MN-54 O.OOOE+OO 9.180E+06 O.OOOE+OO 2.730E+06 O.OOOE+OO 2.810E+07 O.OOOE+oo 1.750E+06 MN-56 O.OOOE-+-00 l.320E-53 O.OOOE+OO 1.680E-53 O.OOOE+OO 4.220E-52 O.OOOE+OO 2.350E-54 FE-55 2.930E+08 2.030E+08 O.OOOE-+-00 O.OOOE+OO l .130E+08 l.160E-t-08 O.OOOE+OO 4.720E+07 FE-59 2.660E+08 6.240E-+-08 O.OOOE+OO O.OOOE+OO l.740E+08 2.080E+09 O.OOOE+OO 2.390E+08 CO-58 O.OOOE >OO 1.820E+07 O.OOOE+OO O.OOOE+OO O.OOOE* OO 3.690E+08 O.OOOHOO 4.090E+07 C0-60 O.OOOE+OO 7.520E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.410E+09 O.OOOE+OO 1.660E+08 NI-63 l.890E+I0 l.310E+09 O.OOOE-t-00 O.OOOE+OO O.OO)E+OO 2.730E+08 O.OOOE+OO 6.330E+08 NI-65 2.250E-52 2.9208--53 O.OOOE+oO O.OOOE+OO O.OOOE+OO 7.400E-52 O.OOOE+OO 1.330E-53 CU-64 O.OOOE+OO 2.710E-07 O.OOOE+oO 6.830E.07 O.OOOE+OO 2.310E-05 O.OOOE+OO l.270E.Q7 ZN-65 3.560E+08 1.130E+09 0.000E+OO 7.570E+08 0.000E+OO 7.130E+08 O.OOOE+OO 5.120E+08 ZN-69 O.OOOE+OO O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO BR-83 O.OOOE+OO 0.0<lOE+OO O.OOOE-+-00 O.OOOE+OO 0.000E+OO 8.650E-57 O.OOOE+OO 6.000E-57 BR-84 O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO BR-85 O.OOOE+O<) 0.000E+OO O.OOOE-t-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO RB-86 O.OOOE+OO 4.870E+08 O.OOOE+OO O.OOOE+OO O.OOOE+OO 9.600E+07 O.OOOE+OO 2.270E+08 RB-88 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO RB-89 0.000E+OO O.OOOE+OO O.OOOE-+-00 0.000E+OO O.OOJE+OO 0.000E+OO 0.000E+OO 0.000E+OO SR-89 3.020E+08 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.840E+07 O.OOOE+OO 8.660E+06 SR-90 l.240E+IO O.OOOE+OO 0.00(tE fOO O.OOOE+OO O.OOOE+OO 3.590E+08 O.OOOE H)O 3.050E+09 SR-91 l.520E-10 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 7.240E-IO O.OOOE+OO 6.140E-12 Appendef G Ri Aduk Caw Meat

• Page t of J Page 9-138

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXG R1 Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Meat (ClvlEAT) Units: m2*mrem/yr / µCi/sec; m1~m/v1* / 1J.CiJru' CH-3, C-14)

Nuclide Bone Liver 'fhyroid Kidnev Luno GilU Skin TotalBod:v SR-92 1.180E-49 0.000E+OO 0.000E+OO 0.000E+oo O.OOOE+OO 2.340E-48 O.OOOE+OO 5.IOOE-51 Y-90 l.080E+o2 O.OOOE * -00 O.OOOE+OO O.OOOE+OO 0.000E+OO 1.140E+06 0.000E+OO 2.890E+OO Y-91 l.130E+06 O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO 6.230E+08 O.OOOE+OO 3.030E+04 Y-91M O.OOOE+OO 0.000E+OO 0.000E+-00 O.OOOE+OO O.OOOE+oo 0.000E+OO O.OOOE+OO 0.000E+OO Y-92 1.5200-39 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 2.660E-35 O.OOOE+oo 4.430E-41 Y-93 4.690E-12 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.490E-07 0.000E+OO UOOE-13 ZR-95 1.870E+06 6.0IOE+OS O.OOOE+-00 9.420E+05 O.OOOE+OO l.900E+09 O.OOOE+-00 4.070E+05 ZR-97 2070E-05 4.170E-06 0.000E+oO 6.300E-06 O.OOOE+OO 1.290E+OO O.OOOE+OO 1.910E-06 NB-95 2.300E+06 l.280E+o6 0.000E+OO l.260E+06 O.OOOE+OO 7.760E+09 O.OOOE+OO 6.870E+05 MO-99 O.OOOEHlO 1.000E,05 O.OOOE+OO 2.260E1*05 O.OOOE-rOO 2.320Er05 0.000E+OO l .900E,04 TC-99M 4.450E-21 l.260E-20 0.1)9<JE+OO 1.910E-19 6.150E-21 7.430E-18 O.OOOE+OO l.600E-19 TC-IOI O.OOOE+OO O.OOOE+OO 0.000E+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO RU-103 1.050E+08 0.000E+OO O.OOOE+OO 4.0IOE+08 O.OOOE+OO l.230E+IO O.OOOE+OO 4.530E+07 RU-105 5.7800-28 O.OOOE+OO O.OOOE+OO 7.460E-27 O.OOOE+OO 3.530E-25 O.OOOE+OO 2.280E-28 RU-106 2.800E+09 0.000E+OO 0.000E+OO 5.400E+09 0.000E+OO 1.810E+ll 0.000E+OO 3.540E+08 AG-llOM 6.680E+o6 6.180E+06 O.OOOE+OO l.220E+07 O.OOOE+OO 2.520E+09 0.000E+OO 3.670E+06 TE-125M 3.590E+08 l.30tlE+08 1.080E+08 1.460E+09 O.OOOE+OO 1.430E+09 0.000E+OO 4.810E+07 TE-127 2.120E-10 7.610E-ll 1.570E-IO 8.640E-10 O.OOOE+OO l.670E-08 O.OOOE+OO 4.590E-l l TE-127M l.120E+09 3.990E+-08 2.850E+08 4.530E+09 O.OOOE+OO 3.740E+09 0.000E+OO l.360E+08 TE-129 0.000E+OO O.OOOE,00 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO TE-129M 1.1 30E+09 4.230E+08 3.900E+08 4.730E+09 O.OOOE+OO 5.710E+09 O.OOOE+OO l.790E+08 TE-131 O.OOOE+OO O.OOOE+OO 0.000E+oO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO TE-131M 4.510E+02 2.2IOE+02 3.490E+02 2.230E+03 O.OOOE+OO 2.190E+04 O.OOOE+oo l.840E+02 TE-132 1.420E , 06 9.180Et05 1.0!0E f06 8.840E+06 O.OOOE+OO 4.340E+07 O.OOOE+OO 8.620E+05 1-130 2. llOE-06 6.220E-06 5.270E-04 9.700E-06 O.OOOE+OO 5.350E-06 O.OOOE+OO 2.450E-06 Appendix G Ri Adult Cow Meat* P-sc 2 of J Page 9-139

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nucloar Station Off.site Dose Calculation Mamsl (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway : Grs/Cow/Meat (Cl\lIEAT) Units: m 2 *mrem/yr / µCl/sec; mrcm/vr / uCilm' lff.3, c.141 Nuclide Bone Liver Thy roid Kidney Lunt Gilli Skin Tota.I Body

(.l3J l.070E+07 l.540E+07 5.030E+o9 2.630E+07 O.OOOE+OO 4.050E+o6 O.OOOE+OO 8.800E+06 1- 132 6.970E.59 l.860E*58 6.53QE.57 2.970E--58 O.OOOE+OO 3.500E*59 O.OOOE+OO 6.53QE.59 1-133 3.650E.Ol 6.350E.OI 9.340E+o l 1.1 IOE+OO O.OOOE+OO 5.710E.Ol O.OOOE+OO l.940E.Ql J.134 O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO

1. 135 4.420E-17 l.160E*l6 7.640E.J5 l.860E*l6 0.000E+OO l.310E*l6 O.OOOE+OO 4.270E. !7 CS- 134 6.580E+08 1.5606+09 O.OOOE+OO 5.060E+08 1.6806+08 2.740E+07 O.OOOE+OO 1.2806+09 CS- 136 l.2 10E+07 4.760E+07 O.OOOE+OO 2.650E+07 3.630E+06 5.4lOE+06 O.OOOE+OO 3.4206+07 CS- 137 8.720E+08 1.1906+09 O.OOOE+OO 4.0506+08 l.350E+08 2.310E+07 O.OOOE+OO 7.810E+08 CS- 138 0.000E+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO BA* l39 O.OOOE >OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE>OO O.OOOE+OO BA*l4Q 2.870E+07 3.6l0E+04 O.OOOE+OO l.230E+04 2.070E+04 5.920E+07 O.OOOE+OO 1.8806+06 BA-14 1 O.OOOE+OO 0.0006+00 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.0006+00 BA*l42 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO LA-140 3.710E.Q2 1.8706-02 0.0006+00 O.OOOE+OO O.OOOE+OO 1.3706+03 0.0006+00 4.940E-03 LA- 142 3.4706*92 l.580E.92 O.OOOE+OO O.OOOE+OO O.OOOE+OO l.150E.88 O.OOOE+OO 3.940E*93 CE-14 1 1.400E+04 9.500E+03 0.0006+00 4.410E+03 O.OOOE+OO 3.6306+07 O.OOOE+OO l.080E+03 CE-1 43 2.0IOE-02 l.480E+Ol O.OOOE+OO 6.530E-03 O.OOOE+OO 5.550E+02 O.OOOE+OO l.640E-03 CE*l44 1.460E+06 6.090E+05 O.OOOE+OO 3.610E+05 0.000E+OO 4.930E+08 O.OOOE+OO 7.8306+04 PR-143 2.IOOE+04 8.4!0E+03 O.OOOE+OO 4.850E+03 O.OOOE+OO 9.180E+07 O.OOOE+OO l.040E+03 PR- 144 O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO ND* l 47 7.070E+o3 8.170E+03 O.OOOE+OI) 4.780E+03 0.0006+00 3.920E+07 O.OOOE+OO 4.890E+O'.!

W- 187 2.0706-02 l.730E*02 O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.660E+OO O.OOOE+OO 6.0406*03 NP-239 2.590E-01 2.5506-02 O.OOOE+<)O 7.950E*02 O.OOOE+OO 5.230E+03 O.OOOE+OO l.400E*02 Appendix G Ri Adult Cow Meat - Page 3 of 3 Page 9-140

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018 Oconee Nuclear Station Off.site Dose Calculation Manual (ODClvl)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Age group: ADULT Pathway: Grs/Goatlll,,leat (GMEAT) Units: m 2 *mrem/yr / µCi/sec;

,n.-em/yr / ~Ci/in* (H-3, C-14)

I Nuclide Bone Liver Thyroid Kidney LUO!! Gilli Skin TotnlBoclv H-3 O.OOOE+OO 3.900E+01 3.900E+o l 3.900E+Ol 3.900E+Ol 3.900E+Ol O.OOOE+OO 3.900E+Ol C-14 2.796E+03 5.592E+02 5.592E+02 5.592E+02 5 592E+02 5.592E+02 0.000E+OO 5.592E *02 NA-24 l.632E-04 l.632E-04 l.632E-04 l.632E-04 l.632E-04 l.632E-04 O.OOOE+OO l.632E-04 P-32 5.592E+08 3.480E+07 O.OOOE+oO 0.000E+OO 0.000E+OO 6.288E+07 0.000E+OO 2.160E+07 CR-51 0.000E+OO O.OOOE+oO 5.052E+o2 1.860E+02 l.122E+-03 2.124E+05 O.OOOE+OO 8.460E+02 MN-54 0.000E+OO l.102E+06 0.000E+OO 3.276E+05 O.OOOE+OO 3.372E+06 O.OOOE+oo 2.IOOE+o5 MN-56 0.000E+OO l.584E-54 0.000E+OO 2.016E-54 O.OOOE+OO 5.064E-53 0.000E+OO 2.820E-55 FE-55 3.516E+07 2.436E+07 O.OOOE+oO 0.000E+OO l.356E+07 l.392E+07 O.OOOE+OO 5.664E+06 FE-59 3.192E+o7 7.488E-t-07 O.OOOE+OO O.OOOE+OO 2.088E+07 2.496E+08 O.OOOE+OO 2.868E+07 CO-58 0.000E+OO 2.184E+06 O.OOOE+-00 O.OOOE"OO O.OOOE+OO 4.428E+07 O.OOOHOO 4.908E+06 C0-60 O.OOOE+OO 9.024E+06 O.OOOE+oo O.OOOE+OO O.OOOE+oo 1.692E+08 O.OOOE+OO l.992E+07 NI-63 2.268E+09 l.572E+08 O.OOJE+OO 0.000E+OO O.OOOE+OO 3.276E+07 0.000E+OO 7.596E+07 NI-65 2.700E-53 3.504E-54 0.000E+OO O.OOOE+OO O.OOOE+OO 8.880E-53 O.OOOE+OO l.596E-54 CU-64 O.OOOE+OO 3.252E-08 O.OOOE+OO 8.196E-08 O.OOOE+OO 2.772E-06 O.OOOE+OO l.524E-08 ZN-65 4.272E+07 1.356E+08 O.OOOE+OO 9.084E+07 O.OOOE+OO 8.556E+07 O.OOOE+OO 6.144E+07 ZN-69 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO BR-83 O.OOOE+OO O.OOOE+OO 0.000E+oo 0.000E+OO 0.000E+OO l.038E-57 O.OOOE+OO 7.200E-58 BR-84 O.OOOE+OO 0.000E+OO O.OOOE+oO O.OOOE+OO O.OOOE+oo O.OOOE+OO 0.000E+OO O.OOOE+OO BR-85 O.OOOE+OO O.OOOE+oo 0.0UOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO RB-86 0.000E+OO 5.844E+07 O.OOOE+oO 0.000E+OO O.OOOE+OO 1.152E+07 0.000E+OO 2.724E+07 RB-88 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO OJJOOE+OO RB-89 0.000E+OO 0.000E+OO 0.000E+oO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO SR-89 3.624E+07 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 5.808E+06 O.OOOE+OO l.039E+06 SR-90 l.488Er09 O.OOOE+OO O.OOOE+-00 0.000E+OO O.OOQE;QO 4.308E+07 O.OOOEl-00 3.660E+08 SR-91 l.824E-ll O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 8.688E-ll O.OOOE+OO 7.368E-13 Appendix G Ri Acl!lt Goet Mear. - Page l of 3 Page 9-141

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offs1te Dose Calculation 1-,,1anual (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Age group: ADULT Pathway: Grs/Goat/Meat (GMEAT) Units: m 1*mrem/yr / µCi/sec; I mr,m/vr / µCilru' <H-3, C-Ul Nuclide Bone Liver Thvroid Kidnev Lune Gilli Skin Total Bodv SR-92 l.416E-50 0.llOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 2.808E-49 O.OOOE+OO 6. !20E-52 Y-90 l.296E >Ol O.OOOEl-00 O.OOOE+OO O.OOOE-100 0.000E+OO l.368E:+05 O.OOOE100 3.468E-01 Y-91 l.356E+05 O.OOOE+oo O.OOOE+-00 O.OOOE+OO O.OOOE+OO 7.476E+o7 O.OOOE+OO 3.636E+03 Y-91M O.QOOE+OO 0.0l)OE+OO O.OOOE+oO O.OOOE+OO 0.000E+oo 0.000E+OO O.OOOE+OO O.OOOE+OO Y-92 l.824E-40 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo 3.192E-36 O.OOOE+()(J 5.316E-4J Y-93 5.628E-13 O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 1.788E:-08 0.000E+OO l.560E-14 ZR-95 2.244E+o5 7.212E+04 O.OOOE+oo 1.130E+05 O.OOOE+OO 2.280E+08 0.000E+OO 4.884E+04 ZR-97 2.484E-06 5.004E-07 O.OOOE+OO 7.560E-07 O.OOOE+OO l.548E-Ol O.OOOE+OO 2.292E-07 NB-95 2.760E+05 l.536E+05 O.OOOE+OO l.512E+05 O.OOOE+OO 9.312E+08 0.000E+OO 8.244E+04 M0-99 O.OOOE+OO l.200E*104 O.OOOE+OO 2.712E+04 0.000E+OO 2.784E+04 0.0008'00 2.280E r03 TC-99M 5.340E-22 l.51,2E-21 O.OOOE+oO 2.292E-20 7.380E-22 8.9 16E-!9 O.OOOE+OO J.920E-20 TC-IOI O.OOOE+OO O.OOOE+OO O.OOOE-t-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO RU-103 l.260E+07 O.OOOE+OO O.OOOE+OO 4.812E+07 0.000E+OO l.476E+09 O.OOOE+OO 5.436E+06 RU-105 6.936E-29 0.000E+oO O.OOOE+OO 8.952E-28 O.OOOE+OO 4.236E-26 O.OOOE+OO 2.736E-29 RU- 106 3.360E+08 O.OOOE+OO O.OOOE+OO 6.480E+08 O.OOOE+OO 2.172E+JO O.OOOE+OO 4.248E+07 AG-llOM 8.0J6E+05 7.4!6E+05 O.OOOE+OO 1.464E+06 0.000E+OO 3.024E+08 0.000E+OO 4.404E+05 TE-125M 4.308E+07 l.560E+07 1.296E+o7 1.752E+08 O.OOOE+OO l.716E+o8 O.OOOE+OO 5.772E+06 TE-127 2.544E- l l 9.l32E-l2 l.884E-ll 1.037E-10 O.OOOE+oO J .004E-09 O.OOOE+OO 5.508E-12 TE- 127M l.344E+08 4.788E+o7 3.420E+07 5.436E+08 0.000E+OO 4.488E+08 O.OOOE+OO 1.632E+07 TE-129 0.000E+OlJ 0.()l)OE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO 0.000E+OO TE-l29M 1.356E+o8 5.076E+07 4.680E+<l7 5.676E+08 O.OOOE+OO 6.852E+08 OOOQE+CXJ 2.!48E+07 TE- 131 0.000E+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO TE-BIM 5.412E+Ol 2.652E+Ol 4.188E+O l 2.676E+02 O.OOOE+OO 2.628E+03 O.OOOE+OO 2.208£+01 TE-132 l .704E+05 l.102E+05 l.212E!-05 l.061E+06 O.OOOE1-00 5.208E+06 O.OOOEH)O l.034E+05 1-130 2.532E-07 7.464E-07 6.324E-05 l.164E-06 O.OOOE+oo 6.420E-07 O.OOOE+OO 2.940E-07 Appendix G Ri Aci.1.1! Go11t Meat

• Page 2 of J Page 9-142

Attachm*ent 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nucloar Station Offsitc Dose Calculation Manool (ODCM)

APPENDIXG R,i Adult Dose Factors for use in the Gaseous Dose Calculations Age group: ADULT Pathway: G1-s/Goat/Meat (GMEAT) Units: m 2*mrem/yr / µCi/sec; I inrem/vr / u.Ci/ni' (H-3, C-Ul Nuclide Bone Liver Thvroid Kidney Lun2 Gilli Skin Total Bod:v

[-1.31 l.284E+06 l.848E+06 6.036E+(l8 3.!56E+06 O.OOOE+-00 4.860E+-05 O.OOOE+OO 1.056E+06 I-132 8.364E-60 2.232E-59 7.836E-58 3.S64E--59 O.OOOE+OO 4.200E-60 0.000E-100 7.836E-60 1-133 4.380E-O'.! 7.620E-02 l.1 21E+o l l.332E-O l O.OOOE+OO 6.852E-02 0.000E+OO 2.328E-02 I-134 0.000E+OO O.OOOE+OO 0.000E+-00 O.OOOE+OO O.OOOE+-00 O.OOOE+OO 0.000E+OO 0.000E+OO I-135 5.304E-18 l.392E-17 9.l68E-16 2.232E-17 O.OOOE+-00 J.S72E-17 O.OOOE+OO S.124E-18 CS-134 7.896E+07 J.872E+08 O.OOOE+OO 6.072E+07 2.016E+07 3.288E+06 O.OOOE+OO J.536E+08 CS-136 l.452E+06 5.7l2E+06 O.OOOE+-00 3.180E+06 4.356E+OS 6.492E+OS O.OOOE+OO 4.104E+06 CS-137 l.046E+08 l.428E+08 O.OOOE+OO 4.860E+07 l.620E+07 2.772E*Hl6 O.OOOE+OO 9.372E+07 CS-138 0.000E+OO O.OOOE+OO 0.000E+-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO BA-139 0.000E+OO O.OOOEHlO O.OOOE+OO O.OOOE1-()() O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO BA-140 3.,444E+06 4.332E+03 O.OOOE+OO l.476E+03 2.484E+o3 7. \04E+-06 0.000E+OO 2.256E+05 BA-141 O.OOOE+OO O.OOOE+oo O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO BA-142 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+-00 O.OOOE+-00 O.OOOE+OO O.OOOE+OO LA-140 4.452E-03 2.244E-03 O.OOOE+OO O.OOOE+OO O.OOOE+OO l.644E+02 O.OOOE+OO 5.928E-04 LA-142 4.\64E-93 l.896E-93 0.000E+OO O.OOOE+OO O.OOOE**OO \.380E-89 O.OOOE+OO 4.728E-94 CE-141 l.680E+o3 l .l40E+03 O.OOOE+-00 5.292E+02 O.OOOE+OO 4.356E+06 0.000E+OO l.296E+02 CE-143 2.412E-03 1.776E+OO O.OOOE+OO 7.836E-04 0.000E+-00 6.660E+-Ol O.OOOE+OO l.968E-04 CE-144 l.752E+05 7.308E+04 O.OOOE+oO 4.332E+04 O.OOOE+oo 5.916E+-07 0.000E+OO 9.396E+03 PR-143 2.520E+03 l.009E+03 0.000E+-00 5.820E+02 O.OOOE+oo \.102E+07 O.OOOE+OO J.248E+02 PR-144 O.OOOE+OO O.OOOE1-00 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO ND-147 8.484E+02 9.804E+02 O.OOOE+IJO 5.736E+02 O.OOOE+OO 4.704E+06 O.OOOE+OO 5.868E+OJ W-187 2.484E-03 2.076E-03 0.000E+oO O.OOOE+OO O.OOOE+OO 6.792E-O\ O.OOOE+OO 7.248E-04 NP-239 3.IOSE-02 3.060E-03 O.OOOE+OO 9.540E-03 O.OOOE+OO 6.276E+02 O.OOOE+OO l.680E-03 Appendix: G Ri AOOlt Goat Meat - Page 3 or J Page 9-143

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsttc Dose Calculation Manual (ODCM)

APPENDIXG R 1Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Vegetation (VEG) Units: m 2*m..em/yr I µCi/sec; mrem/vr / uCiim' (H-3 C-14)

Nuclide Bone Lh*er Thvroid Kidney I,un!! Gilli Skin Total Bodv H-3 O.OOOE+OO 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 O.OOOE+OO 2.260E+03 C- l4 6.280E+04 J.260E+04 J.260EHJ4 l.260E+04 l.260Et04 l.260E ~04 0.0006+00 1.260E+04 NA-24 2.690E+OS 2.690E+05 2.690E+05 2.690E+OS 2.690E+OS 2.690E+OS O.OOOE+OO 2.690E+05 P-32 l.400E+09 8.730E+07 O.OOOE+OO O.OOOE+OO 0.000E+OO 1.580E+08 0.000E+OO 5.430E+07 CR-5 1 O.OOOE+OO O.OOOE+OO 2.780E+04 l.020E+04 6.l60E+04 l.170E+07 O.OOOE+OO 4.640E+04 MN-54 O.OOOE+OO 3.130E+08 0.0006+00 9.310E+07 O.OOOE+OO 9.590E+08 O.OOOE+OO 5.970E+07 MN-56 O.OOOE+OO l.580E+Ol O.OOOE+OO 2.000E+OI 0.000E+OO 5.040E+02 0.000E+OO 2.800E+OO FE-55 2.!00E+08 1.450E+o8 O.OOOE+<lO O.OOOE+OO 8.080E+07 8.310E+07 O.OOOE+OO 3.380E+07 FE-59 l.260E+08 2.9606+08 0.000E*tOO 0.0006+00 8.280E+07 9.880E+08 0.000E+OO l.1 40E+08 C0-58 O.OOOE+OO 3.070E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO 6.230E+08 O.OOOE+OO 6.890E+07 C0-60 0.000E+OO l.670E+o8 O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.140E+09 O.OOOE+OO 3.6906+08 NI-63 l.040E+IO 7.210E+08 O.OOOE+-00 O.(JOOE+OO 0.000E+OO l.500E+08 O.OOOE+OO 3.490E+08 NI-65 6.1506+01 7.990E*l:00 O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.030E+02 O.OOOE+OO 3.640E+OIJ CU-64 O.OOOE+OO 9.200E+03 O.OOOE+OO 2.320E+04 O.OOOE+OO 7.840E+05 O.OOOE+OO 4.320E+03 ZN-65 3.170E+08 l.O!OE+09 O.OOOE+<lO 6.750E+08 O.OOOE+OO 6.360E* *08 O.OOOE+OO 4.560E+08 ZN-69 5.490E-06 l.050E-05 O.OOOE+OO 6.8306-06 O.OOOE+OO l.580E-06 O.OOOE+OO 7.3IOE-07 BR-83 0.000E+O(t O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 4.470E+OO O.OOOE+OO 3.1IOE+OO BR-84 O.OOOE+OO O.OOOE+oo 0.000E-t-00 O.OOOE+OO O.OOOE+OO l.940E-16 0.000E+OO 2.480E-l l BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO RB-86 O.OOOE+OO 2.190E+o8 O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.330E+07 0.000E+OO l .020E+08 RB-88 O.OOOE+OO 3.430E-22 O.OOOE+oO 0.000E+OO OOOOE+OO 4.740E-33 O.OOOE+OO l.!l20E-22 RB-89 O.OOOE..-00 3.890E-26 O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.260E-39 O.OOOEIOO 2.730E-26 SR-89 9.970E+09 0.000E+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO l.600E+09 O.OOOE+OO 2.860E+08 SR-90 6.050E+ll O.OOOE+oo O.OOOE+oO O.OOOE+OO O.OOOE+OO l.750E+IO O.OOOE+OO l.480E+l l SR-9 1 3.050E+05 0.000E+OO O.OO<lE+OO O.OOOE+OO O.OOOE+OO l.450E+06 O.OOOE+OO l.230E+04 Appcndi,: G Ri Adu[t Vegetation

• Page l of l Page 9-144

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation 1-fanual (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Vegetation (VEG) Units: m 2 *nll'em/yr / µCi/se<";

mrem/vr i 11Ci/m3 (H-3, C-141 Nuclide Hone Liver Thvroid Kidnev Lum, Gilli Skin Total Bodv SR-92 4.270E+02 O.OOOE+oo O.OOOE+-00 0.000E+OO O.OOOE+OO 8.450E+03 O.OOOE+OO l.850E+Ol Y-90 l.330E+04 O.OOOE+OO O.OOOE+-00 O.OOOE+OO 0.000E+OO l.410Er08 O.OOOE+OO 3.570E+02 Y-91 5.1IOE+06 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.SIOE+-09 O.OOOE* -00 l.370E+OS Y-91M 5.2200-09 O.OOOE+OO O.OOOE+OO 0.l)OOE+OO O.OOOE+OO 1.5300-08 O.OOOE+OO 2.020E-10 Y-92 9.150E-OI O.OOOE+OO O.OOOE+-00 O.C>OOE+OO O.OOOE+OO l.600E+04 O.OOOE+OO 2.680E--02 Y-93 l.700E+o2 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.380E+06 O.OOOE+OO 4.680E+OO ZR-95 l.170E+06 3.770E+OS O.OOOE+-00 5.910E+05 O.OOOE+OO 1.190E+o9 O.OOOE+OO 2.5SOE+05 ZR-97 3.370E+02 6.SJOE+ol O.OOOE+-00 l.030E+02 O.OOOE+OO 2.l lOE+07 O.OOOE+OO 3.1 IOE+Ol NB-95 1.420E+05 7.920E+04 O.OOOE+OO 7.830E+04 0.000E+OO 4.810E+08 O.OOOE+OO 4.2606+04 M0-99 O.OOOE+OO 6.ISOE+06 O.OOOE+OO l.390E+07 O.OOOE+OO l.430E+07 O.OOOE+OO l.170E+06 TC-99M 3.lOOE+OO 8.770E+OO O.OOOE+OO l.330E+02 4.300E+OO 5. 190E+o3 0.000E+OO l.120E+02 TC-IOI 8.2206-31 1.ISOE-30 , O.OOOE+OO 2.130E-29 6.050E-3l 3.5600-42 O.OOOE+oo l.160E-29 I RU-103 4.770E+06 O.OOOE*-00 O.OOOE+OO l.820E+07 O.OOOE+OO 5.570El*08 0.000E+OO 2.060E+06 RU-105 5.390E+Ol O.OOOE+OO O.OOOE+-00 6.960E+02 O.OOOE+OO 3.290E+04 O.OOOE+OO 2.130E+OI RU-106 l.930E+08 0.000E+OO O.OOOE+OO 3.720E+08 O.OOOE+OO l.250El*l0 0.000E+OO 2.440E+07 AG-llOM 1.050E+07 9.750E+06 O.OOOE+oo l.920E+-07 0.000E+OO 3.980E+09 O.OOOE+OO S.790E+06 TE-125M 9.660E+07 3.SOOE+-07 2.900E+07 3.930E+08 O.OOOE+OO 3.860E+08 0.000E+OO l.290E+07 TE-127 5.660E+o3 2.030E+-03 4.190E+03 2.3l0E+04 O.OOOE+OO 4.470E+05 0.000E+OO l.220E+03 TE-l27M 3.490E+08 l.250E+08 8.920E+07 l.420E+09 O.OOOE+OO 1.170E+09 O.OOOE+OO 4.260E+07 TE-129 7.6300-04 2.870E-04 5.850E--04 3.2IOE-03 O.OOOE+OO 5.7600-04 O.OOOE+OO l.8608-04 TE-129M 2.51 0E+08 9.380E+07 8.630E+07 1.050E+09 O.OOOE+OO l.270E+09 O.OOOE+oo 3.980E+07 TE-131 i.500E-15 6.270E-16 l.230E-15 6.570E-15 O.OOOE+OO 2.130E-16 O.OOOE 1*00 4.740E-16 TE-131M 9.l20E+05 4.460E+05 7.060E+05 4.510E+06 O.OOOE+OO 4.430E+07 O.OOOE+OO 3.720E+05 TE-132 4.300E+06 2.780E+06 3070E+06 2.680E+07 O.OOOE+OO 1.320E+08 0.000E+OO 2.6IOE+06 I-130 3.920E+o5 l.160E+06 9.8IOE+07 l.8IOE+06 0.000E+OO 9.960E+05 O.OOOE+OO 4.570E+05 Appendix G Ri Adult Vcgdation - Page 2 of J Page 9-145

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offa1tc Dose Calculation Manual (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Vegetation (VEG) Units: m 2*mrem/yr I µCi/sec; mren1/yr / ~Ciim' (H-3, C-14}

Nuclide Bone Liver Thvroid Kidney Lun!! GiUi Skin Total Bodv 1- 131 8.080E+07 l.160E+08 3.790E+IO l.980E+08 O.OOOE+OO 3.050E+07 O.OOOE+OO 6.620E+07 1-132 5.760E+OI l.540E+02 5.390E+03 2.450E+02 O.OOOE+OO 2.890E+OI O.OOOE+OO 5.390E+OJ 1-133 2.090E+06 3.630E+06 5.330E+08 6.330E+06 O.OOOE+OO 3.260E+o6 O.OOOE+OO I.I IOE+06 1-134 9.650E-05 2.620E-04 4.540E-03 4. l 70E--04 O.OOOE+OO 2.290E-07 0.000E+OO 9.380E-05 1-135 3.900E+04 l.020E+05 6.730E+06 l.640E+05 O.OOOE+OO l.l50E+05 O.OOOE+OO 3.770E+04 CS-134 4.670E+09 1.I IOE+ IO O.OOOE+OO 3.590E+09 I 190E+09 l.940E+08 O.OOOE+O<J 9.080E+09 CS- 136 4.270E+07 J.680E+08 O.OOOE+oO 9.380E+07 l.290E+o7 1.910E+o7 O.OOOE+oo l.2 10E+08 CS-137 6.360E+09 8.700E+09 O.OOOE+OO 2.950E+09 9.810E+08 l.680E+08 O.OOOE+OO 5.700E+09 CS-138 3.920E- l I 7.730E-1I O.OOOE+OO 5.680E- ll 5.610E- 12 3.300E-16 O.OOOE+OO 3.830E-l I BA-139 2.860E-02 2.030E-05 O.OOOE+OO l.900E-05 1.150E-05 5.060E-02 0.000E+OO 8.360E-04 BA- 140 l .280E+08 l.6IOE+05 0.000E+OO 5.490E+04 9.240E+04 2.650E+08 0.000E+OO 8.420E+06 BA-,141 l.l50E-21 8.700E-25 O.OOOE+oo 8.090E-25 4.940E-25 , 5.430E-31 0.000E+OO 3.890E-23 BA-142 5.960E-39 6.120E-42 O.OOOE+OO 5. I 7QE-42 3.470E-42 8.390E-57 O.OOOE+OO 3.750E-40 LA-140 l.980E+03 9.970E+02 O.OOOE+OO O.OOOE+OO O.OOOE+oo 7.320E+07 O.OOOE+oo 2.630E+02 LA-142 2.0208-04 9.190E-05 O.OOOE+oO O.OOOE+OO O.OOOE+OO 6.7\ 0E-01 O.OOOE+OO 2.290E-05 CE-141 l.970E+05 l.330E+05 0.000E+OO 6.190E+04 0.000E+OO 5.IOOE+08 0.000E+OO l.5 10E+04 CE-143 9.980E+02 7.380E+o5 O.OOOE+OO 3.250E+02 O.OOOE+OO 2.760E+07 O.OOOE+OO 8.160E+OI CE-144 3.290E+07 l.380E+o7 O.OOOE+oO 8.160E+06 0.000E+OO l.l lOE+IO 0.000E+OU l.770E+06 PR- 143 6.260E+04 2.510E+04 O.OOOE+OO l.450E+04 O.OOOE+OO 2.740E+o8 O.OOOE+OO 3.IOOE+03 PR-144 3.090E-26 l.280E-26 O.OOOE+OO 7.230E-27 O.OOOE+OO 4.440E-33 0.000E+OO l.570E-27 ND-147 3.330E+04 3.850E+04 O.OOOE+OO 2.250E+04 O.OOOE+OO 1.850E+08 O.OOOE+OO 2.3 10E+03 W-187 3.800E+04 3.180E+04 0.000E+OO 0.000EfOO O.OOOE<OO l.040Ee07 O.OOOE+OO 1.I IOE+04 NP-239 l.430E+03 l.400E+02 O.OOOE+OO 4.380E+02 O.OOOE+OO 2.880E+07 O.OOOE+OO 7.740E+O l Appcndi'.'( G R.i Adult Vcgdation

• Page 3 of .l Page 9-146

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Inhalation (INHL) Units:

mrem/v1* / uC'i/1113 Nuclide Bone Live1* Thyroid Kidney Lune Gilli Skin Total Body H-3 0.000E+oo \. 260E+03 l.260E+03 l. 260E+03 t.260E+03 l.260E+03 0.000E+oo l .260E+03 C-14 1.820E+04 3.410E+o3 3.41 0E-t-03 3.4IOE+03 3.410E+03 3.410E+03 O.OOOE+OO 3.410E+03 NA-24 l.020E+04 \.020E+04 1.020E+o4 l.020E+04 l.020E+04 l .020E+04 O.OOOE+OO l.020E+04 P-32 l.320E+06 7.710E+o4 O.OOOE+OO O.OOOE+OO 0.000E+OO 8.640E+04 0.000E+OO 5.0IOE+04 CR-51 O.OOOE+OO OOOOE+OO 5.950E+OI 2.280E+OI L440E+04 3.3'.!0E+03 0.000E+OO 1.000E+02 MN-54 O.OOOE+oo 3.960E+04 O.OOOE+OO 9.840E+03 L400E+06 7.740E+04 0.000E+OO 6.300E+03 MN-56 0.000E+OO l.240E+OO O.OOOE+OO 1.300E+OO 9.440E+03 2.020E+04 O.OOOE+OO 1.830E-Ol FE-55 2.460E+04 1.700E+04 O.OOOE-t-00 O.OOOE+OO 7.210E+04 6.030E+03 0.000E+OO 3.940E+03 FE-59 l.180E+04 2.780E+04 O.OOOE-t-00 O.OOOE+OO l.020E+06 1.880E+05 O.OOOE+OO 1.060E+04 C0-58 O.OOOE+OO l.580E+03 O.OOOE+OO O.OOOE+OO 9.280E+05 l.060E+05 O.OOOE+OO 2.070E+03 CO-60 0.000E+OO 1.150E+04 O.OOOE+OO O.OOOE+OO 5.970E+06 2.850E+05 0.000E+OO 1.480E+04 NI-63 4.320E+05 3.140E+04 O.OOOE-t-00 O.OOOE+OO l.780E+o5 l.340E+04 O.OOOE+OO 1.450E+04 NI-65 1.540E+OO 2.IOOE-01 O.OOOE-t-00 O.OOOE+OO 5.600E+03 1.230E+04 O.OOOE+OO 9.l20E-02 CU-64 O.OOOE+OO l.460E+OO O.OOOE+OO 4.620E+OO 6.780E+03 4.900E+04 O.OOOE+OO 6.ISOE-01 ZN-65 3.240E+04 l.030E+05 O.OOOE+oO 6.900E+04 8.640E+05 5.340E+04 O.OOOE+oo 4.660E+04 ZN-69 3.380E-O:! 6..510E-02 O.OOOE+OO 4.220E-02 9.200E+02 i.630E*r01 O.OOOE+OO 4.520E-03 BR-83 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.320E+02 O.OOOE+OO 2.410E+02 BR-84 O.OOOE+OO O.OOOE+OO O.OOOE-t-00 O.OOOE+OO O.OOOE+OO l.640E-03 0.000E+Oll 3.130E+02 BR-85 0.000E+OO O.OOOE+OO 0.000E-t-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.280E+OI RB-86 O.OOOE+OO l.350E+05 O.OOOE-t-00 O.OOOE+oo O.OOOE+OO l.660E+04 0.000E+OO 5.900E+04 RB-88 O.OOOE+OO 3.870E+02 0.000E+{10 O.OOOE+OO O.OOOE+OO 3.340E-09 O.OOOE+OO l.930E+02 RB-89 O.OOOE+OO 2.560E+02 O.OOOE+<JO O.OOOE+OO O.OOOE+oo 9.280E-I:! O.OOOE+OO I.700E+02 SR-89 3.040E+05 0.000E+OO O.OOOE+OO O.OOOE+OO 1.400E+06 3.500E+05 O.OOOE+OO 8.7200* 03 SR-90 9.920E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO 9.600E+06 7.220E+05 0.000E+OO 6.IOOE+06 SR-91 6.190E+Ol O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.650E+04 1.9IOE1*05 O.OOOE+OO 2.500E+OO Appendix G Ri AOOlt lnhaJa1ion

• Page 1 of 3 Page 9-147

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offstte Dose Calculation Manual (ODCM)

APPENDIX G R1 Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Inhalation (INHL) Units:

rnrem/yr / uCi/m3 Nuclide Bone Live,* Thyroid Kidney Lune Gilli Skin Total Body SR-92 6.740E+OO 0.000E+OO O.OOOE+OO 0.000E+OO l.650E+04 4.300E+04 O.OOOE+OO 2.9\0E-01 Y-90 2.090E+03 O.OOOE+OO O.OOOE+oO O.OOOE+OO l.700E+05 5.060E+05 O.OOOE*t-00 5.6IOE+OI Y-91 4.620E+05 OOOOE+OO O.OOOE+OO O.OOOE+OO l.700E+06 3.850E+05 0.000E+OO l.240E+04 Y-91.M 2.6IOE-O I O.OOOE+oo O.OOOE+oO O.OOOE+OO l.920E+-03 l.330E+OO 0.000E+OO l.020E-02 Y-92 l.030E+Ol 0.000E+OO O.OOOE+oO O.OOOE+OO l.570E+04 7.35(1E+04 0.000E+OO 3.020E-Ol Y-93 9.440E+OI 0.000E+OO O.OOOE+oO O.OOOE+OO 4.850E+04 4.220E+05 O.OOOE+OO 2.6l0E+OO ZR-95 1.070E+OS 3.440E+04 O.OOOE+OO 5.420E+04 l.770E+06 l.SOOE+-05 O.OOOE+OO 2.330E+04 ZR-97 9.680E+ol l.960E+Ol O.OOOE+OO 2.970E+Ol 7.870E+o4 5.230E+05 O.OOOE+OO 9.040E+OO NB-95 1.410E+04 7.820E+-03 O.OOOE+oO 7.740E+03 5.0SOE+05 1.040E+05 O.OOOE+OO 4.2\0E+03 M0-99 O.OOOE+OO 1.210E+o2 0.000E+OO 2.910E+02 9.120E+04 2.480E+05 0.000E+OO 2.JOOE+OI TC-99M 1.030E-03 2.910E-03 O.OOOE+oO 4.420E-02 7.640E+02 4.1 60E+03 O.OOOE+OO 3.700E-02 TC-101 4.180E-05 6.020E-05 O.OOOE+oO 1.0SOE-03 3.990E+02 l.090E-11 O.OOOE+OO 5.900E-04 RU-103 l.530E+03 O.OOOE+OO 0.000E+OO 5.830E+03 5.050E+05 l.lOOE+05 O.OOOE+OO ' 6.580E+02 RU-105 7.900E-Ol 0.000E+OO O.OOOE*tOO 1.020E+OO l.lOOE+04 4.820E+04 O.OOOE+OO 3.l l OE-01 RU-106 6.910E+04 O.OOOE+OO O.OOOE+OO l .340E+05 9.360E+06 9.120E+05 O.OOOE+OO 8.720E+03 AG-110.M l.080E+04 I.OOOE+04 O.OOOE+OO 1.970E+04 4.630E+06 3.020E+05 O.OOOE+OO 5.940E+03 TE-125M 3.420E+o3 l.580E+03 l.050E+03 l .240E+04 3.140E+05 7.060E+04 O.OOOE+OO 4.670E+02 TE-127 1.400E+OO 6.420E-01 l.060E+-OO 5.IOOE+OO 6.5IOE+-03 5.740E+04 O.OOOE+OO 3.IOOE-01 TE-127M l.260E+04 5.770E+03 3.290E+o3 4.580E+04 9.600E+OS l.500E+o5 O.OOOE+OO l.570E+03 TE-129 4.980E-02 2.390E-02 3.900E-02 l.870E-01 l.940E+03 l.570E+02 O.OOOE+OO l .240E~l2 TE-129111 9.760E+03 4.670E+03 3.440E+o3 3.660E+04 1.160E+06 3.830E+05 0.000E+OO 1.580E+03 TE- Bl I.110E~l2 5.950E-03 9.360E-03 4.370E-02 l.390E+o3 l.840E+OI O.OOOE+OO 3.590E-03 TE-131M 6.990E+Ol 4.360E+OI 5.500E+o l 3.090E+02 1.460E+05 5.560E+05 O.OOOE+OO 2.900E+Ol TE-132 2.600E+02 2.150E+02 l .900E+-02 l.460E+03 2.880E+05 5.!00E+05 O.OOOE+OO l.620E+02 1-130 4.580E+03 l.340E+04 l.140E+06 2.090E+04 O.OOOE+OO 7.690E+03 O.OOOE+OO 5.280E+03 AppcndixG ru Ad!.lt Inhalation. Pagel of3 Page 9-148

Attach*rnent 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (OOCM)

APPENDIXG R1 Adult Dose Factors for use in the Gaseous Dose Calculations Age.group: ADULT Pathway: Inhalation (INHL) Units:

mrem/yr / uCl/m3 Nudide Bone Liver Thvroid Kidne:v Lun!! Gilli Skin Total Bod:v

[-131 2.520E+04 3.580E+04 l.l90E+07 6.130E+04 0.000E+OO 6.280E+03 O.OOOE+OO 2.050E+04

[-132 l.160E+03 3.260E+o3 l.1 40E+o5 5.180E+03 O.OOOE+OO 4.060E+o2 O.OOOE+OO l.160E+03 I-133 8.640E+03 l.480E+04 2.150E+06 2.580E+04 0.000E+OO 8.8808+03 0.000E+OO 4.5208+03 l-134 6.440E+02 l.730E+o3 2.980E+04 2.750E+03 O.OOOE+oo l.OlOE+oo O.OOOE+OO 6.l50E+02 I-135 2.680E+03 6.980E+03 4.480E+o5 l.l lOE+04 0.000E+OO 5.250E+03 0.000E+OO 2.570E+03 CS-134 3.730E+o5 8.480E+o5 O.OOOE+oO 2.870E+05 9.760E+04 l.040E+04 O.OOOE+oo 7.280E+05 CS-136 3.900E+04 1.460E+05 0.000E+OO 8.560E+04 l.200E+o4 l.170E+o4 O.OOOE+OO 1.IOOE+05 CS-137 4.780E+05 6.210E+05 O.OOOE+OO 2.220E+05 7.520E+o4 8.400E+03 O.OOOE+OO 4.280E+05 CS-138 3.310E+02 6.2!0E+o2 O.OOOE+OO 4.800E+02 4.860E+OI 1.860E-03 O.OOOE+OO 3.240E+02 BA-139 9.360E-01 6.660E-04 O.OOOE+OO 6.220E-04 3.760E+03 8.9608+02 0.000E+OO 2.740E-02 BA-140 3.900E+04 4.900E+Ol 0.000E+oO l.670E+01 1.270E+06 2.l 80E+o5 O.OOOE+OO 2.570E+03 BA-141 1.000E-01 7.5305-05 BA-142 ' 2.630E-02 2.700E-05 O.OOOE+oO O.OOOE+OO 7.0006-05 2.290E-05 1.940E+o3 l .190E+03 1.160E-07 ,

1.570E-16 0.000E+OO O.OOOE+OO 3.360E-03 l .660E-03 LA- 140 3.440E+02 1.7408+0:l O.OOOE+oO 0.0008+00 L360E+05 4.5808+05 O.OOOE+OO 4.580E+OI LA- 142 6.830E-Ol 3. IOOE-01 O.OOOE+OO O.OOOE+OO 6.3308+o3 2.1108+o3 O.OOOE+OO 7.720E-02 CE- 141 1,990E+04 l.350E+o4 O.OOOE+oO 6.260E+03 3.6208+05 1.2008+05 O.OOOE+OO 1.530E+03 CE-143 l.860E+02 l.380E+02 O.OOOE+OO 6.080E+OI 7.980E+04 2.2608+05 0.000E+OO 1.5308+01 CE- 144 3.430E+06 1.430E+o6 O.OOOE+oO 8.480E+05 7.780E+06 8.160E+o5 O.OOOE+oO l.840E+05 PR-143 9.360E+03 3.7508+03 O.OOOE+QO 2.160E+03 2.8IOE+o5 2.000E+o5 0.000E+OO 4.640E+02 PR-144 3.0 lOE-02 1.2508-02 0.0008+00 7.050E-03 1.020E+03 2.150E-08 O.OOOE+OO l.530E-03 ND-147 5.270E+<H 6.IOOE+03 O.OOOE+OO 3.560E+03 2.210E+05 l.730E+05 O.OOOE+OO 3.650E+02 W-187 8.480E+OO 7.080E+OO 0.0008+<]0 O.OOOE+OO 2.900E+o4 l.5508+o5 0.0008+oo 2.480E+OO NP-239 2.300E+02 2.260E+OI O.OOOE+OO 7.000E+Ol 3.760E+04 l.190E+05 0.000E+OO 1.240E+OI Appendix G Ri AWltlnhafatian. Pagc3 ofl Page 9-149

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation [1/(anual (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway : Ground Plane Deposition (GPD) Units: m1 *mrem/yr I µCi/sec Nuclide Bone Liwr Thyroid Kidne~* Lune Gilli Skin Total Body H-3 0.000E+OO O.OOOE+oo O.OOOE+-00 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO C- 14 O.OOOE+OO O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO NA-24 1.190E+07 1.190E *07 l.l90E+o7 l.190E+07 l.190E+07 l.190E+07 l .390E+07 l.190E+07 P-32 O.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO 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 l .390E+09 l.390E+09 l .390E+09 l.390E+09 l.390E+09 l .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+OO 0.000E+OO O.OOOE+-00 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO FE-59 2.730E+o8 2.730E+08 2.730E+08 2.730E+08 2.730Et*08 2.730E+08 3.2lOE+08 2.730Et*08 CO-58 3.790E+08 3.790E+08 3.790E+o8 3.790E+08 3.790E+o8 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+l0 2.150E+IO 2.150E+l0 2.150E+10 2.150E+10 2.530E+10 2.150E+10 Nl-63 0.000E+OO 0.0008+00 O.OOOE+QO 0.1JOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO Nl-65 2.970E+05 2.9J:OE+o5 2 970Et-05 2970E+05 2970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+o5 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.UOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 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+o5 2.030E+05 2.U30Et-05 2.0308+05 2.030E+U5 2.030E+05 2.360E+05 2.030E+05 BR-85 O.OOOE+OO 0.000E+OO 0.000E+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO RB-86 8.990E+06 8.990Et-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 3.3!0E*>04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 l.230E >05 l.230E<05 l.230E+05 l.230E+05 l.230E+05 l.230E+05 l.480E+05 1.230E+05 SR-89 2. 160E+04 2.160E+04 2.160Et-04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 O.OOOE+OO O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO SR-91 2.150E+06 2.l50E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.S10E+06 2.150E+06 Appendi:-t G Ri Adult O'ound Plane Deposition. Page l of l Page 9-150

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offaitc Dose Calculation 1,1anual (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegmup: ADULT Pathway: Ground Plane Deposition (GPD) Units: m1 *nu-em/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lune Gilli Skin TotalBod:v SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+o5 7.770E+o5 8.630E+o5 7.770E+05 Y-90 4.490E+03 4.490E+o3 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.3\0E+03 4.490E+03 Y-91 1.070E+06 l.070E+06 J.070E+06 l.070E+06 1.070E+06 l.070E+06 l.210E+06 l.070E+06 Y-91M 1.000E+05 l.OOOE+o5 l.OOOE+05 l.OOOE+05 I.OOOE+OS l.OOOE+05 l.160E+05 l.OOOE+05 Y-92 l.800E+05 1.800E+05 1.800E+05 l.800E+05 1.800E+05 l.800E+05 2.l40E+05 l.800E+05 Y-93 l.830E+05 l .830E+05 l .830E+05 l.830E+05 1.830E+05 l.830E+05 2.510E+05 l.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 l.370E+08 l.370E;-08 1.370E+08 1.370E* *08 l.370E+08 l.610E+08 l.370E+08 M0-99 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 l.840E+05 I 840E+o5 l.840E+05 l.840E+05 l.840E+05 1.840E+05 2.IIOE+oS 1.840E+05 TC-IOI 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 l.080E+08 l.080E+08 l.080E+08 1.080E+08 l.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 7.2JOE+05 6.360E+05 RU-106 4.220E+08 4.220E+o8 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-ll0M 3.440E+09 3.440E+09 3.4-lOE+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-l25M l.550E+06 l .550E+06 l.550E+06 l.550E+06 l.550E+06 l.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.l60E+04 9.l60E+04 9.160E+04 9.l60E+04 l.080E+05 9.!60E+04 TE-129 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.IOOE+04 2.620E+04 TE-129M l.980E+07 l .980E+07  !.980E f07 l.980E+07 l.980E+07 l.980E107 2.310E+07 l.980E+07 TE-13 1. 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.9WE+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+o6 4.980E+06 4.230E+06 I-130 5.5\0E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.5JOE+06 6.690E+06 5.5\0E+06 Appcndi:< G Ri Adult G'ound Plane Deposition

• Page 2 of 3 Page 9-151

• • Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Offa,tc Dose Calculat,on Manual (ODCM)

APPENDIXG R1Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Ground Plane Deposition (GPD) Units: m1 *nu-em/yr / µCi/sec Nuclide Bone Liver Thvroid Kidnev Lun2 Gilli Skin TotalBod:v 1-131 1.720E+07 1.720E+07 1.720E+07 l.720E+07 l.720E+07 l.720E+o7 2.090E+07 l.720E+07 l- l32 1.250E+06 1.250E+06 l.250E+06 1.250E+06 1.250E+06 1.250E+06 l.470E+06 l.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 1-134 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 l.510E+08 l.510E+o8 1.510E+08 l.510E+08 1.510E+08 l.710E+08 1.5IOE+08 CS-137 l.030E+ l0 l.030E+I0 l.030E+J0 l.030E+I0 l.030E+I0 1.030E+I0 l.200E+ I0 l.030E+I0 CS-138 3.590E+o5 3.590E+05 3.590E+05 3.590E+05 3.590E1*0S 3.590E+05 4.IOOE+05 3.590E+05 BA- 139 1.060E+05 l .060E+05 l .060E+o5 l .060E+05 l.060E+o5 l .060E+05 1.190E+05 l .060E+05 BA-140 2.050E+o7 2.0S0E+o7 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA- 141 4.170E+04 4.l70E+04 4.170E-lfJ4 4.170E+04 4.l 70E+04 4.170E+o4 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.l l0E+04 4.490E+04 LA-140 l.920E+07 l.920E+07 1.920E+o7 1.920E+07 1.920E+07 1.920E+07 2.180E+07 l.920E+07 LA-142 7.600E+o5 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+o5 7.600E+05 CE- 141 l.370E+07 l.370E+07 l .370E+07 l.370E+07 1.370E+07 l.370E+07 l .540E+07 l .370E+07 CE-143 2.310E+06 2.310E+o6 2.310E+06 2.3l0E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+o7 6.950E+07 6.950E+07 6.950E+o7 6.950E+07 8.040E+07 6.950E+07 PR-143 O.0OOE+OO 0.000E+OO O.OOOE+O0 0.000E+OO 0.OOOE+OO 0.000E+OO 0.000E+OO 0.000E+00 PR- 144 1.830E+03 1.830E+o3 l .830E+03 l .830E+03 l.830E+03 l.830E+03 2.\I 0E+03 l.830E+03 ND-1 47 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E 106 1.0I0E+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 l.710E+06 l.710E+o6 l.7l0E+o6 l.710E+06 l.710E+06 l.710E+06 l.980E+06 L710E+06 Appcndi:< G Ri Adult Cl'aund Plane Dcp09tioo

• Page 3 of .\

Page 9-152

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offatc Dose Calculation Manual (ODCM)

APPENDIXH R, Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m 1 *mrem/yr / µCi/sec; rurtm/vr / uCi/013 (H.J, C-14)

Nuclide Bone Liver Thyroid Kidney Lun2 Gilli Skin Total Rod)*

H-3 O.OOOE+OO 9.940E+02 9.940E+o2 9.940E+02 9.940E+02 9.940E+o2 O.OOOE+OO 9.940E+02 C-14 4.690E+04 9.380£ * -03 9.380E+03 9.380E+03 9.380E+03 9.380E+03 0.000E+OO 9.380E*03 NA-24 4.260E+06 4.260E+o6 4.260E+o6 4.260E+06 4.260E+06 4.260E+06 O.OOOE+OO 4.260E+06 P-32 3.J50E+l0 l.950E+09 O.OOOE+-00 O.OOOE+OO O.OOOE+OO 2.650E+09 O.OOOE+OO l.220E+09 CR-51 O.OOOE+OO 0.000E+oo 2.770E+o4 l.090E+04 7.130E+04 8.390E+06 0.000E+OO 4.990E+04 MN-54 O.OOOE+OO l.400E+07 O.OOOE+-00 4.180E+06 O.OOOE+OO 2.870E+07 O.OOOE+OO 2.780E+o6 MN-56 O.OOOE+-00 7.250E-03 O.OOOE+oO 9.180E-03 O.OOOE+OO 4.770E-Ol O.OOOE+OO l.290E--03 FE-55 4.450E+07 3.160E+07 O.OOOE*t-00 O.OOOE+OO 2.000E+07 1.370£+07 O.OOOE+OO 7.360E+06 FE-59 5. JSOE+-07 l.2!0E+08 O.OOOE+OO O.OOOE+OO 3.8IOE+07 2.860E+08 O.OOOE+OO 4.670E+07 CO-58 O.OOOE+OO 7.940E+o6 O.OOOE+oO O.OOOE+OO O.OOOE+OO l.090E+08 O.OOOHOO l.830E+07 C0-60 0.000E+OO 2.780E+07 O.OOOE+-00 O.OOOE+OO O.OOOE+-00 3.620E+08 O.OOOE+OO 6.260E+07 NI-63 1.180E+IO 8.350E+o8 O.OOOE+oO O.OOOE+OO O.OOOE+OO l.330E+08 O.OOOE+OO 4.010E+08 NI-65 6.770E-01 8.650£.02 O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.690E+OO O.OOOE+OO 3.9-lOE--02 CU-64 O.OOOE+OO 4.250E+04 O.OOOE+oo 1.070E+05 O.OOOE+OO 3.290E+06 0.000E+oo 2.000E+04 ZN-65 2.110E+09 7.320E+09 O.OOOE+OO 4.680E+09 O.OOOE+OO 3.IOOE+09 O.OOOE+OO 3.410E+09 ZN-69 3.850E-12 7.330E-12 O.OOOE+OO 4.790E-12 O.OOOE+OO l.350E-l l O.OOOE+OO 5.l30E-13 BR-83 O.OOOE+OO O.OOOE+oo 0.000E+oO O.OOOE+OO 0.000E+-00 O.OOOE+OO O.OOOE+OO l.790E.Ol BR-84 O.OOOE+OO O.OOOE+oo O.OOOE+oO O.OOOE+OO 0.000E+oo O.OOOE+OO O.OOOE+OO 2.880E-23 BR-85 O.OOOE+OO O.OOOE+uO O.OOOE+oO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO RB-86 O.OOOE+OO 4.730E+09 O.OOOE+-00 O.OOOE+OO O.OOOE+-00 7.000E+08 0.000E+OO 2.220E+09 RB-88 O.OOOE+OO 3.890E-45 O.OOOE+iJO O.OOOE+OO O.OOOE+OO 3.330E-52 O.OOOE+OO 2.070E-45 RB-89 O.OOOE+OO 7.660E-53 O.OOOE+-00 0.000E+OO O.OOOE+OO l.l70E-61 O.OOOE+OO 5.420E-53 SR-89 2.670E+09 O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 3.190E+08 O.OOOE+OO 7.660E+07 SR-90 6.610EHO O.OOOE+OO O.OOOE tOO O.OOOE+OO O.OOOEt*OO 1.860E+09 O.OOOE+OO l.630E+JO SR-91 5.310E+04 O.OOOE+OO OOOOE+oO O.OOOE+OO OOOOE+OO 2.410E+o5 O.OOOE+OO 2.1IOE+03 Append<< H Ri Teen Cow Milk - Page I of 3 Page 9-153

Attachment 9 *-

Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nucloar Station Offs1te Dose Calculation Manual (ODCM)

APPENDIXH R, Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrern/yr / µCi/sec; mrenJ/vr / .,cum' (H-3, C-14)

Nuclidt' Bone Linr Thvroid Kidney Luni! Gilli Skin Total Bodv SR-92 8.940E-C* I 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo 2.280E+ol O.OOOE+OO 3.810E-02 Y-90 l.300E+02 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO l .070E+06 0.000E+OO 3.5\0E+OO Y-91 l.580E+04 O.OOOE+oo O.OOOE+oo O.OOOE+oo O.OOOE+OO 6.480E+06 O.OOOE+OO 4.240E+02 Y-91M l.090E-19 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.170E-l8 O.OOOE+OO 4.180E-21 Y-92 1030E-04 O.OOOE+oO O.OOOE+oo O.OOOE+OO O.OOOE+oo 2.830E+oo 0.000E+OO 2.980E-06 Y-93 4.120E-01 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.260E+04 O.OOOE+OO l.1 30E-02 ZR-95 l.650E+o3 5.200E+02 0.000E+OO 7.650E+02 O.OOOE+OO l.200E+06 0.000E+OO 3.580E+02 ZR-97 7.880E-OJ 1.560E-01 O.OOOE+OO 2.370E-01 O.OOOE+OO 4.220E+04 O.OOOE+OO 7.190E-02 NB-95 l .410E+05 7.8lOE+04 0.000E+OO 7.570E+04 0.000E+OO 3.340E+08 O.OOOE+OO 4.300E+04 M0-99 0.000E+OO 4.470E*07 O.OOOE+OO l.020E+08 O.OOOE+OO 8.0l0E+07 0.000E+OO 8.530Er06 TC-99M 5.760E+OO l.6l0E+OI O.OOOE+-00 2.390E+02 8.920E+OO l.050E+o4 O.OOOE+OO 2.080E+02 TC-IOI 4.740E-60 6.750E-60 O.OOOE+OO 1.220E-58 4.1IOE-60 1.1500-66 O.OOOE+OO 6.630E-59 RU- 103 l.8\0E+03 0.000E+OO 0.000E+OO 6.380E+03 O.OOOE+OO l.510E+05 O.OOOE* *OO 7.740E+02 RU-105 l.560E-03 O.OOOE+OO O.OOOE+oo 1.970E-02 O.OOOE+OO l.260E+OO O.OOOE+OO 6.070E-04 RU- 106 3.750E+04 0.000E+OO 0.000E+OO 7.2408+04 O.OOOE*tOO l.800E+06 0.000E+OO 4.730E+03 AG-llOM 9.630E+07 9. I IOE+07 0.000E+OO l.740E+08 O.OOOE+OO 2.560E+IO 0.000E+oo 5.540E+07 TE-125 M 3.000£+07 l.080E+07 8.390£+06 o.ouoE+UO O.OOOE+OtJ 8.860E+o7 (J.OOOE+OO 4.020E+06 TE-127 l.2 l0E+03 4.290E+02 8.350E+o2 4.900E+03 O.OOOE+oO 9.340E+o4 O.OOOE+OO 2.600E+02 TE- 127M 8.440E+07 2.990E+07 2.0IOE+07 3.420E+08 O.OOOE+OO 2. IOOE+08 O.OOOE+OO l.OOOE+07 TE- 129 5.200E- IO l.940E- IO 3.720E-10 2.180E-09 O.OOOE+OO 2.840E-09 O.OOOE+OO l.270E-10 TE- 129M l.lOOE+08 4.090£+07 3.550E+07 4.610£+08 O.OOOE+OO 4.130E+08 O.OOOE+OO l.740E+07 TE-131 6.580E-33 2.7108-33 5.070E-33 2.880E-32 O.OOOE+OO 5.400E-34 O.OOOE+OfJ 2.060E-33 TE-131M 6.570E+05 3.150E+05 4.740E+05 3.290E+06 0.000E+OO 2.530E+07 0.000E+OO 2.630E+05 TE- 132 4.290E ,06 2.720E+06 2.870Er06 2.610E+07 O.OOOErOO 8.6l0E+o7 O.OOOE*tOO 2.560E+06 l- 130 7.380E+05 2.140E+06 1.740E+o8 3.290E+06 O.OOOE+OO l.640E+o6 O.OOOE+OO 8.530E+05 Appendix H Ri Teen Cow Milk - Page 2 cf 3 Page 9-154

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nucloar Station Offsitc Dose Calculation Manual (ODCM)

APPENDIX ff R1Teen Dose Factors for use in the Gaseous Dose Calculations Agegroop: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m 1*mrem/yr / µ(."'i/sec; mrem/vi- / 11Ci/o.' (H.J, C-14)

Noclidt> Bone Liver Thyroid Kidney Lun2 Gilli Skin Total Bodv I-1.31 5.370E+08 7.520E+08 2.J90E+ I I 1.290E+09 O.OOOE+-00 l.490E+o8 O.OOOE+OO 4.040E+08 I-132 2.910E-01 7.620E-Ol 2.570E+Ol l.200E+OO O.OOOE+OO 3.320E-OJ O.OOOE+OO 2.740E-Ol 1-133 7.070E+06 1.200E+o7 1.670E+09 2.lOOE+07 O.OOOE+OO 9.070E+06 O.OOOE+OO 3.660E+06 I-134 3.580E-12 9.500E-12 l.580E-10 1.500E-1 l O.OOOE+OO 1.2500-13 O.OOOE+OO 3.4JOE-l2 I- 135 2.280E+04 5.870E+o4 3.780E+o6 9.270E+04 O.OOOE+oo 6.5JOE+Q4 0.000E+OO 2. J80E+04 CS-134 9.820E+09 2.310E+JO O.OOOE+OO 7.340E+09 2.800E+09 2.870E+o8 O.OOOE+OO 1.070E+l0 CS-136 4.480E+o8 1.760E+09 O.OOOE+OO 9.600E+08 1.5JOE+08 1.420E+08 O.OOOE+oo 1.180E+09 CS-137 1.340E* JO 1.780E+JO O.OOOE+-00 6.060E+09 2.350Et-09 2.530E+-08 O.OOOE+OO 6.200E+09 CS-138 l .640E-23 3. lSOE-23 O.OOOE+OO 2.330E-23 2.7lOE-24 1.4300-26 O.OOOE+OO l .580E-23 BA-139 8.170E-08 5.750E-1 l O.OOOE ,00 5.420E-l 1 3.960E-ll 7.2900-07 O.OOOE*OO 2.380E-09 BA-14-0 4.850E+07 5.950E+04 O.OOOE+-00 2.020E+04 4.000E+-04 7.480E+p7 0.000E+OO 3.130E+06 BA-141 7.520E-46 5.620E-49 O.OOOE+-00 5.210E-49 3.850E-49 1.6000-51 O.OOOE+OO 2.SIOE-47 BA-142 4.790E-80 4.790E-83 O.OOOE+-00 4.050E-83 3.190E-83 1.470E-9l O.OOOE+OO 2.950E-81 LA-140 8.lOOE+oO 3.980E+OO O.OOOE+-00 Q_QQOE+OO O.OOOE+OO 2.290E+05 O.OOOE+OO 1.060E+OO LA-142 3.360E-1 I J.490E-11 O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.5400-07 0.000E+OO 3.710E-12 CE-141 8.880E+o3 5.930E+03 O.OOOE+OO 2.790E+03 O.OOOE+OO l.700E+07 O.OOOE+OO 6.810E+02 CE-143 7.640E+OI 5.560E+04 O.OOOE+-00 2.490E+OI O.OOOE+()(J 1.670E+-06 O.OOOE+OO 6.210E+OO CE-144 6.580E+05 2.720E+05 O.OOOE+oO 1.630E+05 O.OOOE+-00 J.660E+o8 0.000E+OO 3.540E+04 PR-143 2.900E+02 1. !60E+-02 0.UUUE+-00 6.730E+UI O.OOOE+OO 9.540E+05 0.000E+OO l.440E+OI PR-144 l.080E-53 4.430E--54 O.OOOE+OO 2.540E-54 O.OOOE+OO l.l90E-56 0.000E+OO 5.490E-55 ND-147 l.8lOE+o2 l.970E+02 O.OOOE+OO l.160E+02 O.OOOE+OO 7.JIOE+05 O.OOOE+OO 1.180E+OI W-187 l.190E+04 9.710E+03 O.OOOE+OO 0.000E+OO O.OOOE+OO 2.630E+-06 O.OOOE+OO 3.400E+03 NP-239 7.0I OE+OO 6.6IOE-01 O.OOOE+OO 2.070E+OO O.OOOE+OO 1.060E+05 O.OOOE+OO 3.670E~)l Appendix H Ri Tettt Cow Milk - Page 3 of l Page 9-155

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offs1tc Dose Calculat1on Manual (ODCM)

APPENDIXH R1Teen Dose Factors for use in the Gaseous Dose Calculations Ageg1*oup: TEEN Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / µCi/sec; 1nren,/vr / 11Cil111' (H-3, C-14)

Nuclidt- Bone Liver 'Fhvroid Kidnev LUU!! Gilli Skin. Total Bodv H-3 O.OOOE+OO 2030E+03 2030E+o3 2.030£+03 2.030£+03 2.030£+03 O.OOOE+OO 2.030E+03 C- 14 4.690E+o4 9.380E+03 9.380E+03 9.380E+03 9.380E+03 9.380E+03 0.000E+OO 9.380E+03 NA-24 5.110£+05 S.110E+o5 5.1lOE+oS 5.110E+05 5.1lOE+OS 5. l IOE+05 O.OOOE+OO 5.1lOE+05 P-32 3.780E+IO 2.3406+09 O.OOOE+oO O.OOOE+OO O.OOOE+OO 3.180E+09 O.OOOE+OO l.470E+09 CR-51 O.OOOE+OO O.OOOE+oo 3.330E+o3 l.310E+03 8.550E+o3 l.OIOE+06 O.OOOE+o<l 5.990E+03 MN-54 O.OOOE+OO l .680E+06 O.OOOE+oO 5.020E+05 O.OOOE+OO 3.450E+06 O.OOOE+OO 3.340E+o5 MN-56 O.OOOE+OO 8.700E-04 O.OOOE+OO I.IOOE-03 O.OOOE+OO 5.7300-02 0.000E+OO l.550E-04 FE-55 5.790£+05 4.l10E+05 O.OOOE+oO O.OOOE+OO 2.600E+05 1.780E+05 0.0006+00 9.570E+04 FE-59 6.740E+o5 l.570E+06 O.OOOE+oO O.OOOE+OO 4.960E+05 3.720E+06 O.OOOE+OO 6.070E+05 CO-5 8 O.OOOE+OO 9.520E+-05 O.OOOE+OO O.OOOEl*OO 0.000E+OO l.310E+07 O.OOOE>OO 2.190E+06 C0-60 O.OOOE+OO 3.340E+06 O.OOOE+oO O.OOOE+OO O.OOOE+oo 4.350E+07 O.OOOE+O<) 7.520E+06 NI-63 l.420E+09 1.000E-+-08 O.OOlE+oO O.OOOE+OO O.OOOE+OO l.590E+07 O.OOOE-+-00 4.810E+07 Nl-65 8.120E-02 1.0408-02 O.OOOE+oO O.OOOE+OO 0.000E+OO 5.6300-01 0.000E+OO 4.730£-03 CU-64 O.OOOE+oO 4.730E+03 O.OOOE+OO l.200E+04 O.OOOE+OO 3.670E+OS O.OOOE+oo 2.230E+03 ZN-65 2.530E+08 8 780E+08 O.OOOE+OO 5.620E+08 O.OOOE+OO 3.720E+08 O.OOOE+OO 4. IOOE+08 ZN-69 4.620£-13 8.SOOE-13 O.OOOE+oO 5.750E- 13 O.OOOE+OO l.620E-12 O.OOOE+OO 6.160E-14 BR-83 0.000E-,-00 0 OOOE+oo O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2. ISOE-02 BR-84 0.000E+OO 0.<lOOE+OO 0.000E+oO O.OOOE+oo O.OOOE+oo O.OOOE+OO O.OOOE-+-00 3.450E-24 BR-8 5 O.OOOE+OO O.OOOE+(J() 0.000E+oO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E-+-00 O.OOOE+OO RB-86 O.OOOE+O<) 5.6706+08 O.OOOE+oO O.OOOE+OO 0.000E+OO 8.400E+07 O.OOOE+OO 2.670E+08 RB-88 0.000E+oo 4.670E-46 O.OOOE-HJO 0.000E+OO O.OOOE+OO 4.000E-53 O.OOOE+OO 2.490E-46 RB-89 O.OOOE+OO 9.l90E-54 0.000E 00 0.000E+OO O.OOOE+OO l.410E-62 O.OOOE+OO 6.SOOE-54 SR-89 5.620E+09 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 6.690E+08 O.OOOE+OO l.610E+08 SR-90 l.390Erll O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.900E+09 O.OOOE* *OO 3.430E+IO SR-9 1 l.120E+05 O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+oo 5.060E+05 O.OOOE+OO 4.440E+03 Appendix H Ri Teen Goat Milk

• Page I of 3 Page 9-156

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offaite Dose Calculation Manual (ODCM)

APPENDIXH R 1Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Goat/Milk (GMILK) Units: m1 *mrem/yr / µCi/sec; m1-.,m/vr / 11,Cilm' (H-3, C-Ul Nuclide Bone Liver Thyroid Kidney Lun~ Gilli Skin Total Rodv SR-92 l.880E+oo O.OOOE+OO O.OOOE-t{I() O.OOOE+OO O.OOOE+OO 4.780E+ol O.OOOE+OO 8.000E-02 Y-90 l.560E+Ol O.OOOE*OO O.OOOE+OO 0.000E+OO O.OOOE+OO l.290E+05 O.OOOE*IOO 4.210E-01 Y-91 1.900E+03 O.OOOE-+-00 O.OOOE+oO O.OOOE+OO O.OOOE+OO 7.770E+05 0.000E+OO 5.080E+OI Y-9IM l.310E-20 O.OOOE+OO 0.000E+oo 0.000E+OO 0.000E+OO 6.200E-19 O.OOOE+oo 5.020E-22 Y-92 1.240E-05 O.OOOE+oo 0.000E+oO O.OOOE+OO O.OOOE+OO 3.390E-Ol 0.000E+OO 3.580E-07 y.93 4.940E-02 O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO l.510E+03 O.OOOE+OO l.360E-03 ZR-95 l .980E+o! 6.250E+Ol O.OOOE+OO 9.180E+OI O.OOOE+OO l.440E+05 O.OOOE+OO 4.300E+OI ZR-97 9.460E-02 1.870E-02 O.OOOE-t{I() 2.840E-02 O.OOOE+OO 5.070E+03 O.OOOE+OO 8.620E-03 NB-95 l.690E+04 9.370E+03 0.000E+oo 9.080E+03 0.000E+OO 4.0l0E+07 0.000E+OO 5.160E+03 MO-99 O.OOOE+OO 5.370Et-06 O.OOOE+OO l.230E+07 O.OOOE+OO 9.610E+06 O.OOOE*OO l.020E+06 TC-99M 6.910E-Ol l.930E+OO O.OOOE+OO 2.870E+OI l.070E+OO l.270E+o3 O.OOOE+oO 2.500j,+Ol TC-101 5.690E-61 8.IOOE-61 O.OOOE-t{I() l.460E-59 4.930E-61 l.380E-67 O.OOOE+OO 7.950E-60 RU- 103 2.170E+02 O.OOOE+OO O.OOOE+-00 7.660E+02 O.OOOE+OO l.810E+04 O.OOOE+OO 9.290E+OI RU-105 l.SSOE-04 O.OOOE+oo OOOOE-t{I() 2.370E-03 O.OOOE+oo 1.520E-01 O.OOOE+OO 7.290E~)5 RU-106 4.500E+03 0.000E+OO O.OOOE-t{I() 8.680E+03 O.OOOE+OO 2.160E+05 0.000E+OO 5.670E+02 AG-llOM 1.160E+07 1.090E+07 0.000E+oo 2.080E+07 O.OOOE+OO 3.070E+09 0.000E+OO 6.650E+06 TE-125M 3.600E+06 l.300E+06 l.OIOE+06 0.000E+OO 0.000E+OO l.060E+07 O.OOOE+OO 4.820E+05 TE-127 l.450E+02 5.150E+OI l.OOOE+02 5.880E+02 O.OOOE+oo 1.120E+o4 O.OOOE+oo 3.lWE+ol TE-127M l.OIOE+07 3.590E+06 2.410E+06 4.IOOE+07 0.000E+OO 2.520E+07 O.OOOE+OO l.200E+06 TE-129 6.240E-1I 2.3305-11 4.460E-ll 2.620E-10 O.OOOE+OO 3.410E-IO O.OOOE+OO 1520E-ll TE-129M l.320E+07 4.900E+o6 4.260E+06 5.530E+07 O.OOOE+OO 4.960E+07 O.OOOE+OO 2.090E+06 TE-131 7.900E-34 3.260E-34 6.090E-34 3.450E-33 O.OOOE+OO 6.480E-35 0.000E+OO 2.470E-34 TE-l31M 7.880E+04 3.780E+04 5.690E+o4 3.940E+05 O.OOOE+OO 3.030E+06 0.000E+oo 3.150E+04 TE-132 5.150E *05 3.260E+05 3.440E+05 3.130E+06 O.OOOE+OO l.030E+07 O.OOOE*IOO 3.070E+05 1-130 8.860E+05 2.560E+06 2.090E+08 3.950E+06 O.OOOE+OO l.970E+06 O.OOOE+OO l.020E+06 Appendix H Ri Teen Oont Milk - Page 2 of 3 Page 9-157

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Slation Offs1tc Dose Calculation Manwl (ODCM)

APPENDIXH R1Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: T EEN Pathway : Grs/Goat/Milk (GMILK) Units: m 2 *mrem/yr / µCi/sec;

,nrem/vr / 14Ci/ru' (H-3, C-14}

Nuclide Bone Liver Thvroid Kidnev Luno Gilli Skin Total Rodv I-131 6.450£+08 9.030E+08 2.630E+ll J.550E+09 O.OOOE+OO l.790E+08 O.OOOE+OO 4.850E+08 I-132 3.500E-Ol 9. 150E-Ol 3.080E+Ol l.440E+OO 0.000E+OO 3.980E-Ol 0.000IH OO 3.280E--Ol 1-133 8.480E+06 1. 440E+07 2.0IOE+09 2.520E+07 O.OOOE+OO l.090E+07 O.OOOE+OO 4.390E+06 I-134 4.300E-12 l.140E-l l l.900E- IO l.SOOE-11 O.OOOE+OO l.500E-l3 O.OOOE+OO 4.090E-l2 I- 135 2.740E+o4 7.040E+04 4.530E+06 l.l lOE+05 0.000E+oo 7.8l0E+04 O.OOOE+OO 2.610E+04 CS-134 2.940E+ IO 6.930E+IO O.OOOE+OO 2.200E+IO 8.410E+09 8.620E+08 O.OOOE+OO 3.220E+JO CS-136 l.340E+09 5.290E+09 O.OOOE+OO 2.880E+09 4.S40E+08 4.260E+08 O.OOOE+OO 3.550E+09 CS-137 4.020E+ IO 5.340E+l0 O.OOOE* -00 l.820E+10 7.060£+09 7.600E+08 O.OOOE+OO 1.860E+ IO CS-138 4.920E-23 9.450E-23 O.OOOE+-00 6.980E-23 8.120E-24 4.2900-26 O.OOOE+OO 4.730E-23 BA- 139 9.800E-09 6.900E-12 O.OOOE+-00 6.SOOE-12 4.750E-12 8.7500-08 0.000E+OO 2.860E-10 BA- 140 5.820E+06 7.130E+03 O.OOOE+OO 2.420E+03 4.800E+o~ 8.980E+06 O.OOOE+OO 3.750E+05 BA- 1.41 9.030E-47 6.740E-50 O.OOOE+oO 6.260E-50 4.610E-50 l.920E-52 O.OOOE+OO 3.0IOE-48 BA-142 5.750E-8 I 5.750E-84 O.OOOE+OO 4.860E-84 3.820E-84 1.7608-92 O.OOOE+OO 3.540E-82 LA-140 9.720E-Ol 4.780E-Ol O.OOOE+OO 0.000E+OO O.OOOE+OO 2.740E+04 O.OOOE+OO 1.270E--01 LA- 142 4.030E-12 1.790E-12 O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.440E-08 O.OOOE+OO 4.450E-13 CE-141 1.070E+03 7.l20E+02 O.OOOE+OO 3.350E+02 O.OOOE+OO 2.040E+06 O.OOOE+OO 8. l 70E+Ol CE-1 43 9.170E+OO 6.670E+03 O.OOOE+oO 2.990E+oo O.OOOE+OO 2.000E+o5 O.OOOE+OO 7.450E-Ol CE- 144 7.900E+04 3.270E+04 O.OOOE+-00 l.950E+04 O.OOOE+oo l.990E+o7 O.OOOE+oo 4.240E+03 PR-143 3.480E+Ol l.390E+Ol O.OOOE+oO 8.080E+OO O.OOOE+OO l.150E+05 0.000E+OO 1.730E+OO PR-144 l.300E-54 5.3208-55 0.000E+-00 3.0SOE-55 O.OOOE+OO 1.4308-57 0.000E+OO 6.590E-56 ND-147 2.170E+Ol 2.360E+Ol O.OOOE+OO l.390E+OJ O.OOOE+OO 8.530E+04 O.OOOE+OO l.420E+OO W-187 J.430E+03 l.l70E+03 O.OOOE+-00 O.OOOE+OO O.OOOE+OO 3.l50E+05 O.OOOE+OO 4.080E+02 NP-239 8.410E-Ol 7.930E-02 O.OOOE+-00 2.490E-Ol O.OOOE+OO l.280E+04 O.OOOE+OO 4.410E~)2 AppcndixH Ri Teen Gont Milk- Pagel cf3 Page 9-158

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Ocone,: Nucl "'" Station Offsite Dose Calculation Manual (ODCM)

APPENDIXH R1Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / µCi/sec; inrem/vr / uCi/ru3 (H-3, C-Ul Nuclide Bone Liver Thyroid Kidney Lun~ Gilli Skin. TotalBodv H-3 0.000E+OO 1.940E+02 l.940E+o2 1.940E+02 l.940E+o2 1.940E+o2 O.OOOE+OO l.940E+02 C-14 l.970E+o4 3.940E+03 3.940E+o3 3-940E+03 3.940E+03 3.940E+03 0.000E+OO 3.940E+03 NA-24 l.080E-03 1.080E-03 1.080E-03 1.080E-03 1.080E-03 1.080E-03 0.000E+OO 1.080E-03 P-32 3.930E+09 2.440E+08 0.000E+00 O.OOOE+OO O.OOOE+oo 3.3lOE+08 O.OOOE+OO l.530E+08 CR-51 O.OOOE+OO O.OOOE+OO 3.130E+o3 l.240E+03 8.050E-t03 9.470E+o5 0.000E+OO 5.640E+03 MN-54 O.OOOE+OO 7.000E* -06 O.OOOE+OO 2.090E+o6 O.OOOE+oo 1.440E+o7 O.OOOE+OO 1.390E+06 MN-56 O.OOOE+OO l.070E-53 O.OOOE+OO l.360E-53 O.OOOE+OO 7.070E-52 O.OOOE+OO 1.910E-54 FE-55 2.380£+08 J.690E+08 O.OOOE+OO O.OOOE+OO 1.070E+08 7.310E+o7 O.OOOE+OO 3.940E+07 FE-59 2.l20E+08 4.950£+08 O.OOOE+OO O.OOOE+OO 1.560E+08 1.170E+09 0.000E+OO l.9l0E+08 CO-58 O.OOOE+OO 1.4JOE+o7 O.OOOE ,00 O.OOOE~00 O.OOOE+OO 1.940E+08 O.OOOE,OO 3.240E+07 C0-60 \).OOOE+OO 5.830E+07 O.OOOE+OO O.OOOE+OO O.OOOE+oo 7.600E+08 0.000E+OO UIOE+-08 Nf-63 1.520E+IO 1.070E+09 O.OOOE+oO O.OOOE+OO O.OOOE+OO 1.710E+08 O.OOOE+OO 5.150E+08 Nf-65 l.880E-52 2.410E-53 O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.300E-51 O.OOOE+OO 1.IOOE-53 CU-64 O.OOOE+OO 2.210E-07 O.OOOE+OO 5.600E-07 O.OOOE+oo 1.720E-05 O.OOOE+OO 1.040E-07 ZN-65 2.500E+08 8.690E+08 O.OOOE+-00 5.560E+08 O.OOOE+OO 3.680E+08 O.OOOE+OO 4.050E+08 ZN-69 O.OOOE+oo 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+O(I 0.000E+OO O.OOOE+OO BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+oo O.OOOE+oo O.OOOE+OO 5.070E-57 BR-84 O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+oo O.OOOE+oo 0.000E+OO 0.000E+OO BR-85 O.OOOE+OO O.OOOE+-00 O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO RB-86 O.OOOE+OO 4.070E,08 O.OOOE+oO O.OOOE+OO 0.000E+OO 6.020E+07 O.OOOE+OO l.9lOE+08 RB-88 O.OOOE+oo 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO RB-89 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo 0.000E+oo O.OOOE+OO 0.000E+OO SR-89 2.550E+o8 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.030E+07 O.OOOE+OO 7.290E+06 SR-90 8.050E , 09 O.OOOE+OO O.OOOEtOO 0.000E+OO O.OOOEHJO 2.260E+08 0.000E* OO 1.990E+09 SR-91 1.280E-10 O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO 5.800E-10 0.000E+OO 5.090E-12 Appendix H Ri Teen Cow Mcar

• Page 1 <1t J Page 9-159

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculat,on lvlanual (ODCM)

APPENDIXH R 1Teen Dose Factors for use in the Gaseous Dose Calculations Agegronp: TEEN Pathway: Grs/Cow/Meat (CMEAT) Units: m 2*mrem/yr / µCi/sec; mrem/vr / 14Ci/ru 1 (H-3, C-14)

Nuclide Bone Liver Thvrnid Kidnev Luno Gilli Skin Total Bodv SR-92 9.880E-50 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.520E-48 O.OOOE+OO 4.210E-51 Y-90 9.060E+OI O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 7.470E+05 0.000E+OO 2.440E*OO Y-91 9.540E+05 0.000E+oo O.OOOE+oO OOOOE+OO O.OOOE+OO 3.910E+08 O.OOOE+OO 2.560E+04 Y-91M O.OOOE+OO O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 0.00()E+OO 0.000E+OO 0.000E+OO Y-92 1.280E-39 O.OOOE+OO O.OOOE+oO O.OOOE+OO 0.000E+-00 3.520E-35 0.000E+OO 3.710E-41 y.93 3.960E-12 O.OOOE+oo 0.000E+oO O.OOOE+OO O.OOOE+OO 1.210E-07 O.OOOE+OO 1.090E-13 ZR-95 l.500E+06 4.730E+05 O.OOOE+OO 6.950E+05 0.000E+OO l.090E+09 O.OOOE+OO 3.250E+05 ZR-97 1.720E-05 3.410E-06 O.OOOE+OO 5.1708-06 O.OOOE+OO 9.230E-Ol O.OOOE+OO 1.570E-06 NB-95 l.790E+06 9.950E+05 O.OOOE+OO 9.650E+05 0.000E+OO 4.260E+09 O.OOOE+OO 5.480E+05 MO-99 O.OOOE+OO 8.270E+04 O.OOOE+oO 1.890E+05 O.OOOE+OO l.480E+05 O.OOOHOO l.580E+04 TC-99M 3.530E-21 9.850E-21 O.OOOE+oO J.470E-19 5.470E-2l 6.470E-l8 O.OOOE+OO l.280E-19 TC- 101 O.OOOE+OO O.OOOE+OO O.OO<lE+oo O.OOOE+OO O.OOlE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO RU-103 8.570E+07 O.OOOE+OO O.OOOE+oO 3.020E+08 O.OOOE+OO 7.l60E+09 O.OOOE+OO 3.660E+07 RU-105 4.830E-28 O.OOOE+OO O.OOOE+oO 6.0908-27 O.OOOE+OO 3.900E-25 O.OOOE+OO l.880E-28 RU- 106 2.360E+09 O.OOOE+OO O.OOOE+OO 4550E+09 O.OOOE+OO l.130E+ ll O.OOOE+OO 2.970E+08 AG-llOM 5.060E+06 4.790E+06 O.OOOE+OO 9. l30E+06 O.OOOE+OO l.340E+09 O.OOOE+OO 2.910E+06 TE- 125M 3.030E+08 l.090E+o8 8.470E+07 O.OOOE+OO 0.000E+OO 8.940E+08 O.OOOE+OO 4.050E+07 TE-127 I.SOOE-10 6.380E- l l 1.240E- IO 7.290E-IO O.OOOE+oO l.390E-08 O.OOOE+OO 3.870E-1 l TE- 127M 9.4IOE+08 3.340E+o8 '.l.240E+o8 3.8208+09 O.OOOE+OO 2.350E+09 0.0008+00 1.120E+08 TE-1 29 O.OOOE+OO O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO TE- 129M 9.500E+o8 3.530E+08 3.070E+-08 3.970E+09 O.OOOE+OO 3.570E+09 O.OOOE+OO l.500E+08 TE-131 O.OOOE+OO O.OOOE+OO OOOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO TE- 131M 3.760E+02 l.800E+02 2.710E+02 l.880E+03 O.OOOE+OO 1.450E+04 O.OOOE+OO l.500E+02 TE-132 l.160E+06 7.360EH05 7.750Ef()5 7.060E+06 O.OOOE , 00 2.330E+07 O.OOOE+OO 6.920E+05 1-130 l.700E-06 4.910E-06 4.000E-04 7 56118-06 O.OOOE+OO 3.770E-06 O.OOOE+OO 1.960E-06 Appendix H Ri Teen Cow Meat. Page 2 of 3 Page 9-160

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIXH R 1Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Meat (CMEAT) Units: m 2*mrem/yr / µCi/sec; mrem/vr / uCilrn' (H-3, C-14}

Nuclide Bone Liver Thvroid Kidnev Lun!!' Gilli Skin. Total Bodv 1-131 8.920E+06 1.2506+07 3.650E+o9 2. 150E+07 O.OOOE+oo 2.470E+o6 0.000E+OO 6.710E+o6 I-132 5.660E-59 1.4806-58 4.990E-57 2. 330E-58 0.CKXJE+OO 6.450E-59 0.000E-100 5.320E-59 1-133 3.0SOE-01 5.ISOE-01 7.230E+o l 9.090E-Ol 0.000E+OO 3.920E-Ol O.OOOE+OO l.580E-Ol I-134 0.000E+OO O.OOOE+OO O.OOOE+oO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO I-135 3.600E-17 9.260E-17 5.960E-15 1.4608-16 O.OOOE+OO l.030E-16 O.OOOE+OO 3.430E-17 CS-134 5.230E+08 l.230E+o9 O.OOOE+oO 3.910E+08 1.490E+o8 1.530E+07 O.OOOE+OO 5.710E+o8 CS-136 9.400E+06 3.700E+07 O.OOOE+oo 2.010E+07 3.170E+06 2.980E+06 0.000E+OO 2.480E+07 CS-137 7.240E+08 9.630E+08 O.OOOE+OO 3.280E+08 l.270E+08 l.370E*07 O.OOOE+OO 3.360E+08 CS-138 0.000E+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO BA-139 O.OOOE eOO O.OOOE*OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO BA-140 2.380E+o7 2.910E+04 O.OOOE+oo 9.870E+03 l.%0E+04 3.660E+07 O.OOOE+OO l.530E+06 BA-141 O.OOOE+oo O.OOOE+OO O.OOJE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO BA-142 0.000E+OO O.OOOE+OO O.OOOE+oO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO LA-140 3.0SOE-02 1.500E-02 O.OOOE+oo O.OOOE+OO O.OOOE+OO 8.610E+o2 O.OOOE+OO 3.990E-03 LA-142 2.870E-92 J.280E-92 0.000E+oO 0.000E+OO 0.000E+OO 3.880E-88 O.OOOE+OO 3.180E-93 CE-141 1.180E+04 7.870E+03 O.OOOE+OO 3.710E+03 O.OOOE+OO 2.250E+07 0.000E+oo 9.040E+02 CE-143 l.690E-02 l.230E+Ol O.OOOE+oo 5.SIOE-03 O.OOOE+OO 3.690E+02 O.OOOE+OO l.370E-03 CE-144 1.230E+06 5.080E+05 OJJOOE-+-00 3.040E+05 O.OOOE+OO 3.090E+o8 0.000E+OO 6.600E+04 PR-143 l.760E+04 7.040E+o3 0.000E+oO 4.090E+03 O.OOOE+OO 5.800E+07 O.OOOE+OO 8.780E+02 PR-144 O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+oo 0.000E+OO 0.000E+OO ND-147 6.230E+o3 6.770E+03 0.000E+OO 3.980E+03 0.000E+OO 2.440E+07 0.000E+OO 4.060E+02 W-187 l.730E-02 l.410E-02 O.OOOE+OO O.OOOE+OO 0.000E+OO 3.820E+oo 0.000E+OO 4.940E-03 NP-239 2.260E-01 2.l40E-02 O.OOOE+OO 6.700E-02 O.OOOE+OO 3.440E+03 O.OOOE+OO l .190E-02 AppendixHRi Teen Cow Meat *Page3 of 3 Page 9-161

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Ocone~ Nucloar Station Offoitc Dose Calculation J:,.,1anual (ODCM)

APPENDIXH R 1Teen Dose Factors for use in the Gaseous Dose Calculations Age group: TEEN Pathway: G1'S/Goat/Meat (GMEAT) Units: m 2*mrem/yr / µCi/sec; I mrcmlvr / 11Ci/1n3 /H-3, C-Ul Nuclide Bon.e Liver Thyroid Kidney I, lllll! Gilli Skin Total Bod,*

H-3 0.000E+OO 2.328E+OI 2.328E-t-O I 2.3'.!8E+OI 2.328E+ol 2.328E+ol O.OOOE+OO 2.328E+OI C- 14 2.364E+03 4.728E+02 4.728E+02 4.728E+02 4.728E+02 4.728E+02 0.000E+OO 4.728E+02 NA-24 l.296E-04 l.296E-04 l.296E-04 l.296E-04 l.296E-04 1.296E-04 O.OOOE+OO l.296E-04 P-32 4.716E+08 2.928E+07 O.OOOE+OO O.OOOE+OO 0.000E+OO 3.972E+07 O.OOOE+OO l.836E+07 CR-5 1 O.OOOE+OO O.OOOE+oo 3.756E+02 1.488E+02 9.660E+02 1.136E+05 0.000E+OO 6.768E+02 MN-54 O.OOOE+OO 8.400E+05 0.000E+OO 2.508E+05 O.OOOE+OO l.728E+06 O.OOOE+OO l.668E+05 MN-56 O.OOOE+OO 1.284E-54 O.OOOE+-00 l.632E-54 O.OOOE+OO 8.484E-53 O.OOOE+OO 2.292E-55 FE-55 2.856E+07 2.028E+07 0.000E+-00 O.OOOE+OO l.284E+07 8.772E+06 0.000E+OO 4.728E+06 FE-59 2.544E+07 5.940E+07 0.000E+OO O.OOOE+OO l.872E+07 l.404E+08 O.OOOE+OO 2.292E+07 CO-58 O.OOOE+OO 1.692E+06 O.OOOE*t-00 O.OOOE+OO O.OOOE+OO 2 328E+07 O.OOOE+OO 3.888E+06 CQ-60 O.OOOE+OO 6.996E+06 O.OOOE+OO O.OOOE+OO O.OOOE+OO 9.120E+07 O.OOOE+OO l.572E+07 Nl-63 1.824E+09 1.284E+o8 O.OOOE+oO O.OOOE+OO O.OOOE+OO 2.052E+07 O.OOOE+OO 6.180E+07 Nf-65 2.256E-53 2.8928-54 O.OOOE+-00 0.000E+OO 0.000E+OO l.560E-52 O.OOOE+OO 1.320E-54 CU-64 O.OOOE+OO 2.652E-08 O.OOOE+oo 6.720E-08 O.OOOE+OO 2.064E-06 O.OOOE+OO l.248E-08 ZN-6 5 3.000E+07 l .043E+08 0.000E+OO 6.672E+07 O.OOOE+OO 4.416E+07 0.000E+OO 4.860E+07 ZN-69 0.000E+OO 0.000E+OO 0.000E+-00 0.000E+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO BR-83 O.OOOE+OO 0.000E+OO O.OOOE-t-00 O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+oo 6.084E-58 BR-84 O.OOOE+OO O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO BR-85 O.OOOE+OO 0.000E+oO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO RB-86 0.000E+OO 4.884E+07 O.OOOE+OO O.OOOE+OO 0.000E+OO 7.224E+06 O.OOOE+OO 2.292E+07 RB-88 O.OOOE+OO O.OOOE+OO O.OOOE+-00 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO RB-89 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO SR-89 3.060E+07 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.636E+06 O.OOOE+OO 8.748E+05 SR-90 9.660E+08 0.000EtOO 0.000E f00 O.OOOE+OO O.OOOErOO 2.7l2E+07 O.OOOE+OO 2.388E+08 SR-91 l.536E-1 1 O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO 6.960E-1 1 O.OOOE+OO 6.I08E-13 Appendix H Ri Teen Goat Meat

• Page l of .3 Page 9-162

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIXH R1Teen Dose Factors for use in the Gaseous Dose Calculations Age group: TEEN Pathway: Grs/Goat/)\,leat (GMEAT) Units: m2*mrem/yr I µCi/sec; I mrem/vr I LLCi/111 3 IH-3, C-Ul Nuclide Bon.e Liver Thyroid Kidney Lune Gilli Skin. Total Rodv SR-92 U 86E-50 O.OOOE+OO O.OOOE+oO 0.000E+OO O.OOOE+OO 3.024E-49 O.OOOE+OO 5.052E-52 Y-90 l.087E+ol O.OOOE+OO 0.000E+OO O.OOOE+OO 0.0001>+00 8.964E+04 0.000E+OO 2.928E-O\

Y-91 1.1 45E+05 O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 4.692E+07 O.OOOE+OO 3.072E+03 Y-91M O.OOOE+OO O.OOOE+OO 0.000E+oO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO Y-92 l.536E-40 O.OOOE+oo 0.000E+oo O.OOOE+OO O.OOOE+oO 4.224E-36 O.OOOE+OO 4.452E-42 Y-93 4.752E-\3 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO l.452E-08 0.000E+OO 1.308E-14 ZR-95 l.800E+o5 5.676E+04 O.OOOE+OO 8.340E+04 O.OOOE+OO l.308E+08 O.OOOE+OO 3.900E+04 ZR-97 2064E-06 4.092E-07 0.000E+oO 6.204E-07 O.OOOE+OO l.l08E-01 O.OOOE+OO \.884E-07 NB-95 2.148E+o5 1.194E+05 O.OOOE+-00 l.\58E+05 O.OOOE+oo 5.l\2E+08 O.OOOE+OO 6.576E+o4 MO-99 O.OOOE+OO 9.924E+03 O.OOOE+OO 2.268E+04 O.OOOE+OO l.776E+04 0.000E+OO J.896E+03 TC-99M 4.236E-22 1.182E-21 O.OOOE+OO 1.7646-20 6.5646-22 7.764E-19 O.OOOE+OO 1.5366-20 TC-101 O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO RU-103 \.028E+07 0.000E+OO O.OOOE+OO 3.624E+07 O.OOOE+OO 8.592E+08 0.000E+OO 4.392E+06 RU-105 5.796E-29 O.OOOE+OO O.OOOE+OO 7.3086-28 O.OOOE+OO 4.6806-26 0.000E+OO 2.2566-29 RU-106 2.832E+08 0.000E+OO O.OOOE+OO 5.460E+08 O.OOOE+OO l.356E+ IO 0.000E+OO 3.564E+07 AG-ll0M 6.072E+o5 5.748E+05 O.OOOE+oO l.096E+06 O.OOOE+OO l.608E+08 O.OOOE+OO 3.492E+05 TE-125M 3.6366+07 1.308E+07 l.Ol6E+o7 O.OOOE+OO O.OOOE+OO l.073E+08 0.000E+OO 4.860E+06 TE-127 2.160E-11 7.656E-12 l.488E-II 8.748E-11 O.OOOE+OO l.668E-09 O.OOOE+OO 4.644E-12 TE-127M \.l29E+08 4.008E+o7 2.688E+07 4.584E+08 O.OOOE+OO 2.820E+08 0.000E+OO 1.344E+07 TE-129 O.OOOE+OO O.OOOE+OO 0.000E+oO O.OOOE+OO O.OOOE+oo O.OOOE+OO 0.000E+OO O.OOOE+OO TE-129M l.140E+08 4.236E+07 3.684E+07 4.764E+08 O.OOOE+OO 4.284E+08 O.OOOE+OO 1.800E+07 TE-131 0.000E+OO 0.000E+OO O.OOOE+oO 0.0006+00 O.OOOE+OO 0.000E+OO 0.0006+00 0.000E+OO TE-13\M 4.51 2E+ol 2.l60E+ol 3.252E+OI 2.256E+02 O.OOOE+OO l.740E+03 0.000E+oo 1.800E+OI TE-132 1.392E f05 8.832E+04 9.300Et-04 8.472E+05 O.OOOEIOO 2.796E+06 O.OOOE+OO 8.304£+04 1-130 2.040E-07 5.892E-07 4.SOOE-05 9.0726-07 O.OOOE+OO 4.524E-07 O.OOOE+OO 2.3526-07 Appendix H Ri Teen Goat Meat* Pagel Clf3 Page 9-163

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIXH Ri Teen Dose Factors for use in the Gaseous Dose Calculations Age gmup : TEEN Pathway: G1-s/Goat/Meat (GMEAT) Units : m2 *mrem/yr / µCi/sec; I ml'em/vl' / u.Ci/1113 IH-3, C-Ul Nuclide Bone Liver Thyroid Kidney Lun!! Gilli Skin TotalBod:v 1-1.31 J.070E+06 UOOE+06 4.380E+o8 2.580E+06 O.OOOE+oo 2.964E+-05 O.OOOE+OO 8.05'.'.E+05 1- 132 6.792£.60 l.776E-59 5.988E-58 2.796E-59 0.000E+OO 7.740E-60 O.OOOE+OO 6.384E-60 1- 133 3.660E-02 6.2l6E-02 8.676E+OO l.091E-Ol O.OOOE+OO 4.704E-02 0.000E+OO 1.896E-02 1- 134 0.000E+OO O.OOOE+OO 0.000E+oO 0.000E+OO 0.000E+oo 0.000E+OO O.OOOE+OO 0.000E+OO 1- 135 4.3200-18 l.! I IE-17 7.152E-16 l .752E-17 O.OOOE+oo J.236E-l7 O.OOOE+OO 4.116E-18 CS-134 6.276E+07 l.476E+08 O.OOOE+oO 4.692E+07 1.788E+07 l.836E+06 0.000E+OO 6.852E+07 CS-136 1.128E+06 4.440E+06 O.OOOE+oO 2.4l2E+06 3.804E+05 3.576E+05 0.000E+OO 2.976E+06 CS-137 8.688E+07 l.156E+08 O.OOOE+oO 3.936E+07 1.524E+07 l.644E*Hl6 O.OOOE+OO 4.032E+07 CS-138 O.OOOE+-00 O.OOOE+oo 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO BA-139 O.OOOE+OO O.OOOE+OO O.OOOE ,00 O.OOOE+OO O.OOOE+OO O.OOOE , 00 O.OOOE+OO O.OOOE+OO BA- 140 2.856E+06 3.492E+03 O.OOOE+OO l.184E+03 2.352E+o3 4.392E+06 O.OOOE+oo l.836E+05 BA-141 O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO BA-142 O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO LA- 140 3.660E-03 l.SOOE-03 O.OOOE+OO O.OOOE+oo O.OOOE+oo l.033E+02 O.OOOE+OO 4.788E-04 LA- 142 3.444E-93 l.536E-93 0.000E+OO O.OOOE+OO 0.000E+OO 4.656E-89 0.000E+OO 3.816E-94 CE-141 l.4l6E+03 9.444E+02 O.OOOE+OO 4.452E+02 O.OOOE+OO 2.700E+06 O.OOOE+OO l.085E+02 CE- 143 2 028E-03 1.476E+OO O.OOOE+OO 6.612E-04 O.OOOE+OO 4.4J8E+ol O.OOOE+OO J.644E-04 CE- 144 l.476E+05 6.096E+04 O.OOOE+oO 3.648E+04 O.OOOE+OO 3.708E+o7 0.000E+OO 7.920E+03 PR-143 2.112E+03 8.448E+o2 0.000E+oO 4.908E+02 O.OOOE+OO 6.960E+06 O.OOOE+OO 1.054E+02 PR-144 O.OOOE+OO 0.000.E+OO 0.000E+oO 0.000.E+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO 0.000E+OO ND- 147 7.476E+02 8.124E+02 O.OOOE+OO 4.776E+02 O.OOOE+OO 2.928E+06 O.OOOE+OO 4.872E+O l W-1 87 2.076E-03 l .692E-03 O.OOOE+OO O.OOOE+oo O.OOOE+OO 4.584E-O l 0.000E+OO 5.928E-04 NP-239 2.712E-02 2.568E-03 O.OOOE+-00 8.040E-03 O.OOOE+OO 4.128E+02 0.000E+OO l.428E-03 Appendix H Ri Teen Goat Meat* Page 3 of 3 Page 9-164

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Ocone¢ Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIXH R 1Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Vegetation (VEG) Units: mi*mrem/yr I µCi/sec; rnrem/yr / JLCi/n1' IH-3, C-14)

Nuclide Bone Liver Thvroid Kid.nev Lune Gil.Ii Skin TotalBodv H-3 O.OOOE+Oll 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 O.OOOE+OO 2.590E+03 C-14 l.020E+05 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 0.000E+OO 2.040E+04 NA-24 2.390E+05 2.390E+05 2.390E+05 2.390E+05 2.390E+05 2.390E+05 O.OOOE+OO 2.390E+05 P-32 l.6!0E+09 9.970E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.350E+08 0.000E+OO 6.240E+07 CR-51 O.OOOE+oo 0.000E+OO 3.430E+04 l.350E+04 8.810E+04 1.040E+07 0.000E+-00 6.170E+04 MN-54 O.OOOE+OO 4.540E+08 O.OOOE+OO l.360E+08 O.OOOE+OO 9.320E+08 O.OOOE+OO 9.010E+07 MN-56 O.OOOE+OO l.420E+Ol O.OOOE+OO l.800E+Ol O.OOOE+OO 9.360E+02 O.OOOE+OO 2.530E+OO FE-55 3.260E+08 2.310E+08 O.OOOE+oO 0.000E+OO l.470E+08 I.OOOE+08 O.OOOE+OO 5.390E+07 FE-59 l.790E+o8 4.l90E+08 O.OOOE+OO O.OOOE+OO l.320E+08 9.900E+08 O.OOOE+OO l.620E+08 CO-58 O.OOOE+OO 4.360E+07 O.OOOE+OO O.OOOE*OO 0.000E+OO 6.0l0E+08 O.OOOE+OO LOOOE+08 C0-60 O.OOOE+OO 2.490E+08 O.OOOE+OO O.OOOE+OO O.OOOE+oo 3.240E+o9 0.000E+OO 5.600E+08 NI-63 1.6\0E+lO l.l30E+o9 O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.8\0E+OS O.OOOE+OO 5.450E+08 NI-65 5.720E+OI 7.310E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 3.970E+o2 O.OOOE+OO 3.330E+OO CU-64 O.OOOE+OO 8.340E+03 O.OOOE+OO 2. l\OE+04 O.OOOE+OO 6.470E+05 O.OOOE+OO 3.920E+03 ZN-65 4.240E+08 l.470E+09 O.OOOE+OO 9.420E+08 O.OOl)E+OO 6.230E+08 0.000E+OO 6.870E+08 ZN-69 5.140E-06 9.800E-06 O.OOOE+OO 6.400E-06 O.OOOE+OO l.SIOE-05 0.000E+OO 6.860E-07 BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO OJJOOE+oo O.OOOE+OO 2.910E+OO BR-84 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+oo O.OOOE+OO 2.250E-1 l BR-85 O.OOOE+OO 0.000E+oO O.OUOE+oO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO RB-86 O.OOOE+OO 2.740E+08 0.000E+OO O.OOOE+OO O.OOOE+OO 4.050E+07 O.OOOE+OO l.290E+08 RB-88 0.000E+OO 3.l?OE-22 0.000E+l)O O.OOOE+oo O.OOOE+OO 2.720E-29 O.OOOE+OO l.690E-22 RB-89 O.OOOE+OO 3.500E-26 O.OOOE+OO 0.000E+OO O.OOOE+OO 5.360E-35 0.000E+OO 2.470E-26 SR-89 l.5IOE+IO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+Oll l.800E+09 O.OOOE+OO 4.340E+08 SR-90 7.5\0Hll 0.000E+OO O.OOOE rOO 0.000E+OO O.OOOHOO 2.1 lOE+lO O.OOOE+OO l.850E+I I SR-91 2.850E+05 O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+oo l.290E+06 O.OOOE+OO l.130E+04 Appendix H Rt Teen Vcgctatjon -Page I of3 Page 9-165

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Off.site Dose Calculation Manual (ODCM)

APPENDIXH R1Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Vegetation (VEG) Uni.ts: m 1*mrem/yr / µCi/sec; 111rent1,*1* / uCifn** (H-3, C-14)

Nuclide Bone Lh*er Thyroid Kidnev LUU!? Gilli Skin. Total Body SR-92 3.970£+02 0.000E+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO I.OIOE+04 O.OOOE+OO l.690E+O l Y-90 l.240E+O-l O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO l.020E+08 0.000E+OO 3.350E *02 Y-91 7.840E+06 0.OOOE-+-00 O.OOOE+oO O.OOOE+OO O.OOOE+OO 3.2 l0E+09 O.OOOE+OO 2.100E+05 Y-91M 4.860E-09 0.000E+OO O.OOOE+oO O.OOOE+OO 0.000E+OO 2.290E-07 O.OOOE+OO l.860E-1 0 Y-92 8.600E-O l O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+oO 2.360E+04 O.OOOE+OO 2.490E-02 Y-93 1.590E+02 O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 4.860E+06 O.OOOE+OO 4.360E+o0 ZR-95 1.720E+06 5.430E+o5 O.OOOE+QO 7.980E+05 O.OOOE+OO l.250E+09 O.OOOE+OO 3.730E+05 ZR-97 3.120E+02 6.180E+01 O.OOOE-tOO 9.370E+o1 O.OOOE+OO 1.670E+07 O.OOOE+OO 2.850E+Ol NB-95 1.920E+OS 1.070E+o5 O.OOOE+oO l.030E+05 O.OOOE+OO 4.560E+08 O.OOOE+oo 5.870E+04 M0-99 O.OOOE+OO 5.650E+06 O.OOOE+oO 1.290E+07 O.OOOE+OO 1.010E+07 O.OOOE*OO l.080E+06 TC-99M 2.740E+OO 7.630E+OO O.OOOE+oO 1.140E+02 4.240E+OO 5.010E+03 O.OOOE+OO 9.890E+Ol TC-IOI 7.640E-31 l.090E-30 O.OOOE+OO l.970E-29 6.620E-31 1.860E-37 O.OOOE+oo 1.070E-29 RU- 103 6.820E+06 0.000E+OO O.OOOE+OO 2.400E+07 O.OOOE+OO 5.700E+08 O.OOOE+OO 2.920E+06 RU-105 5.000E+ol 0.000E+OO O.OOOE+OO 6.3IOE+02 O.OOOE+OO 4.040E+04 O.OOOE+OO 1.940E+O l RU-106 3.IOOE+08 0.000E+OO 0.000E+OO 5.970E+08 O.OOOE+OO l.480E+10 O.OOOE+OO 3.900E+07 AG-llOM l.520E+o7 l.430E+07 O.OOOE+oO 2.740E+07 O.OOOE+OO 4.030E+09 O.OOOE+OO 8.720E+06 TE-125M 1.480E+08 5.34t)E+07 4.140E+o7 O.OOOE+OO O.OOOE+OO 4.370E+08 O.OOOE+OO 1.980E+07 TE-127 5.330E+03 1. 890E+03 3.680E-H)3 2.160E+04 O.OOOE+OO 4.120E+05 0.000E+oo l.150E+03 TE-127M 5.510E+08 l.960E+o8 l.310E+o8 2.240E+09 O.OOOE+OO 1.370E+09 O.OOOE+OO 6.560E+07 TE-129 7.140E-04 2.6605-04 5.JOOE-04 3.000E-03 O.OOOE+OO 3.910E-03 O.OOOE+OO l.740E-04 TE- l29M 3.620E+o8 l.340E+08 l.170E+o8 J.510E+09 O.OOOE<*OO 1.360E+C>9 O.OOOE+OO 5.730E+07 TE-131 l.390E-15 5.750E-16 l.070E-15 6. lOOE-15 O.OOOE+OO l.140E- 16 0.000E+OO 4.360E-16 TE-HIM 8.440E+o5 4.050E+05 6.090E+05 4.220E+06 O.OOOE+OO 3.250E+07 O.OOOE+OO 3.380E+05 TE-132 3.910E+06 2.470E+06 2.6\0E f06 2.370El-07 0.000E+OO 7.840E+07 O.OOOE+OO 2.330E+06 l- 130 3.SJOE+OS l.OJOE+06 8.~80E+07 1.560E+06 O.OOOE+OO 7.800E+05 O.OOOE+OO 4.050E+05 Appendix H Ri Teen Vegetation. Pagc2 af3 Page 9-166

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX ff R 1Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Vegetation (VEG) Units: m:*mrem/yr / µCi/sec; rnrem/vr / uCilai' IH-3, C-141 Nuclide Bone Liver Thyroid Kid ney Lun2 Gilli Skin 'fotal Bodv I-131 7.690E+07 I 080E+08 3.1 40E+IO 1.850E+08 O.OOOE+OO 2.1 30E+07 O.OOOE+OO 5.780E+07 I- 132 5.190E+Ol 1.360E+02 4.580E+03 2.140E+02 0.000E+OO 5.920E+O I 0.000E+OO 4.880E*OI 1-133 1.940E+06 3.290E+06 4.590E+08 5.760E+06 O.OOOE+OO 2.490E+06 O.OOOE+OO 1.000E+06 I-134 8.7200-05 2.3JOE-04 3.850E-03 3.640E-04 O.OOOE+oo 3.050E-06 0.000E+OO 8.310E-05 I-135 3.520E+04 9.070E+o4 5.830E+06 1.430E+05 O.OOOE+OO 1.000E+05 O.OOOE+OO 3.360E+04 CS-134 7.JOOE+09 l .670E+IO O.OOOE+OO 5.310E+09 2.030E+09 2.080E+08 O.OOOE+OO 7.750E+09 CS-136 4.370E+07 l.720E+o8 O.OOOE+OO 9.370E+07 l.480E+07 1.380E+07 O.OOOE+OO 1.160E+08 CS-137 1.0IOE+IO l.350E+IO O.OOOE+oO 4.590E+09 1.780E+09 l.920Et-08 O.OOOE+OO 4.690E+09 CS-138 3.610E-ll 6.940E-ll O.OOOE+OO 5.120E-ll 5.960E-12 3.!SOE-14 O.OOOE+OO 3.470E-11 BA-139 2.690E-O:! l .890E-05 O.OOOE+oO 1.780E-05 l.300E-05 2.4000-01 O.OOOE+OO 7.830E-04 BA-140 l.380E+08 l.690E+05 O.OOOE+OO 5.740E+04 1.140E+05 2. !30E+o8 O.OOOE+OO 8.900E+\J6 BA-141 l.080E-21 8.040E-25 0.000E+OO 7.460E-25 5.500E-25 2.290E-27 O.OOOE+OO 3.590E-23 BA-142 5.490E-39 5.4908-42 O.OOOE+OO 4.640E-42 3.650E-42 1.6800-50 O.OOOE* *OO 3.380E-40 LA-140 l.810E+o3 8.880E+02 O.OOOE+oo O.OOOE+OO O.OOOE+OO 5.100E+07 O.OOOE+OO 2.360E-t02 LA-142 l.850E-04 8.240E-05 O.OOOE+OO 0.000E+OO O.OOOE+OO 2.510E+OO 0.000E+OO 2.050E-05 CE-141 2.830E+05 l .890E+05 O.OOOE+OO 8.890E+04 O.OOOE+OO 5.400E+08 0.000E+OO 2.170E+04 CE-143 9.330E+o2 6.790E+05 O.OOOE+OO 3.040E+02 O.OOOE+OO 2.040E+07 O.OOOE+OO 7.580E+Ol CE-144 5.270E+07 2.180E+07 O.OOOE+oO l.300E+07 O.OOOE+OO l.330E+JO O.OOOE+OO 2.830E+06 PR-143 7.000E* -04 2.800E+o4 O.OUOE+OO 1.630E+U4 O.OOOE+OO 2.300E+08 O.OOOE+OO 3.490E-t03 PR-144 2.900E-26 l.190E-26 0.000E+OO 6.800E-27 O.OOOE+OO 3.190E-29 0.000E+OO l.470E-27 ND-147 3.620E+04 3.940E+04 O.OOOE+OO 2.310E+04 O.OOOE+OO 1.420E+08 O.OOOE+OO 2.360E+03 W-187 3.540E+04 2.880E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO 7.800E+o6 0.000E+OO 1.0IOE+04 NP-239 l.390E+03 l.3 10E+02 O.OOOE+oo 4.100E+02 O.OOOE+OO 2.IOOE+07 0.000E+OO 7.260E+OI Appendix H Ri Tem VegetaUon. Page 3 of 3 Page 9-167

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Off.site Dose Calculation Manual (ODCM)

APPENDIXH Rl 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 Lun2 Gilli Skin Total Body H-3 O.OOOE+OO l .270E+03 l.270E+-03 l.270E+03 l.270E+o3 l.270E+03 O.OOOE+OO l.270E+03 C-14 2.600E+04 4.870E+03 4.870E+<)3 4.870E+03 4.870E+03 4.870E+-03 O.OOOE+OO 4.870E+03 NA-24 J.380E+04 l.380E+04 1.380E+o4 l.380E+04 l.380E+04 l.380E+04 O.OOOE+OO 1.380E+04 P-32 l.890E+06 I.IOOE+05 O.OOOE+oO O.OOOE+OO O.OOOE+oo 9.280E+o4 O.OOOE+OO 7.160E+04 CR-51 0.000E+OO O.OOOE+OO 7.500E+OI 3.070E+OI 2.IOOE+04 3.000E+03 O.OOOE+OO 1.350E+02 MN-54 O.OOOE+OO 5.110E+04 O.OOOE+oO 1.270E+04 1.980E+06 6.680E+04 O.OOOE+OO 8.400E+03 MN-56 O.OOOE+oO l.700E+oo 0.000E+oO l.790E+OO l.520E+04 5.740E+04 O.OOOE+OO 2.520E-01 FE-55 3.340E+04 2.380E+o4 O.OOOE+-00 O.OOOE+OO l.240E+o5 6.390E+03 O.OOOE+OO 5.540E+03 FE-59 l .590E+04 3.700E+04 0.000E+OO 0.000E+OO l.530E+06 l.780E+05 O.OOOE+OO l.430E+04 CO-58 0.000E+OO 2.070E+03 O.OOOE+oO O.OOOE+OO l.340E+o6 9.520E+<)4 O.OOOE+OO 2.780E+03 C0-60 O.OOOE+OO l.510E+04 O.OOOE+OO O.OOOE+OO 8.720E+06 2.590E+o5 O.OOOE+OO l.980E+04 NI-63 5.800E+05 4.340E+-04 O.OOOE+OO O.OOOE+OO 3.070E+05 l.420E+04 O.OOOE+OO l.980E+04 Nf-65 2.l80E+OO 2.930E-01 O.OOOE+OO O.OOOE+OO 9.360E+-03 3.670E+-04 O.OOOE+OO l.270E-Ol CU-64 0.000E+OO 2.030E 1*00 O.OOOE+OO 6.410E+OO UIOE+04 6.l40E+04 O.OOOE+OO 8.480E-Ol ZN-65 3.860E+04 l.340E+05 0.000E+OO 8.640E+04 l.240E+06 4.660E+04 O.OOOE+OO 6.240E+04 ZN-69 4.830E-02 9.200E-02 O.OOOE+oO 6.020E-02 1.580E+03 2.850E+02 O.OOOE-tOO 6.460E-03 BR-83 O.OOOE+OO O.OOOE+OO 0.000E+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.440E+02 BR-84 O.OOOE+OO O.OOOE+OO O.OOOE+<lO Q_OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 4.330E+02 BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO l.830E+OI RB-86 0.000E+OO l.900E+05 O.OOOE+{IO O.OOOE+OO O.OOOE+OO l.770E*Kl4 O.OOOE+OO 8.400E+04 RB-88 O.OOOE+OO 5.460E+02 O.OOOE+-00 O.OOOE+OO O.OOOE+OO 2.920E-05 O.OOOE+oo 2.720E+02 RB-89 O.OOOE+OO 3.520E+02 O.OOOE+-00 O.OOOE+OO O.OOOE+OO 3.380E-07 O.OOOE+OO 2.330E+02 SR-89 4.340E+05 0.000E+OO 0.000E+oO 0.000E+OO 2.420E+06 3.7l0E+05 O.OOOE+OO l.250E+04 SR-90 l.080E+08 O.OOOE+OO 0.000E+oO 0.000E+OO l.650E+07 7.650E+05 O.OOOE+OO 6.680E+06 SR-91 8.800E+0I O.OOOE+OO O.OOOE+OO O.OOOE+OO 6.070E+04 2.590E+05 O.OOOE+OO 3.5IOE+OO Appendix H Ri Teen [nhah1tion

• Page l of3 Page 9-168

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation l'vfanual (ODCM)

APPENDIXH R1Teen Dose Factors for use in the Gaseous Dose Calculations Age group: TEEN Pathway: hthalafion (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Liver Thyroid Kidney Lun!! Gilli Skin Total Body SR-92 9.520E+OO O.OOOE+oO O.OOOE+oO O.OOOE+OO 2.740E+04 Ll90E+05 O.OOOE+OO 4.060E-Ol Y-90 2.980E+03 O.OOOE+OO 0.000E-H)O O.OOOE+OO 2.930E+05 5.590E+05 O.OOOE+OO 8.000E+ol Y-91 6.6JOE+05 O.OOOE+oo O.OOOE+OO 0.000E+OO 2.940E+06 4.090E+05 0.000E+OO l.770E+04 Y-9IM 3.700E-01 O.OOOE+OO O.OOOE+oO O.OOOE+OO 3.200E+03 3.020E+Ol O.OOOE+OO l.420E-02 Y-92 l.470E+OI 0.000E+OO O.OOOE+OO O.OOOE+OO 2.680E+04 l.650E+05 O.OOOE+OO 4.290E-01 y.93 l.350E+02 0.000E+OO O.OOOE-+{10 O.OOOE+OO 8.320E+04 5.790E+05 0.000E+OO 3.720E+OO ZR-95 l.460E+o5 4.580E+04 O.OOOE+OO 6.740E+04 2.690E+06 l.490E+05 O.OOOE+OO 3.150E+04 ZR-97 l.380E+02 2.720E+OI O.OOOE-t-00 4.120E+OI l.300E+05 6.300E+05 O.OOOE+OO l.260E+Ol NB-95 l.860E+04 1.030E+04 0.000E+OO LOOOE+04 7.510E+05 9.680E+04 0.000E+OO 5.660E+03 l\'10-99 0.000E+OO l.690E+02 0.000E+OO 4.IIOE+o2 l.540E+05 2.690E+05 O.OOOE+OO 3.220E+OI TC-99M l.380E-03 3.860E-03 O.OOOE+OO 5.760E-02 l.150E+o3 6.130E+03 OJJOOE+oo 4.990E--02 TC-10I 5.920E-05 8.400E-05 0.000E+OO l.520E-03 6.670E+02 8.720E-07 O.OOOE+OO 8.240E-04 RU-103 2.IOOE+03 O.OOOE+OO O.OOOE+OO 7.430E+03 7.830E+05 l.090E+05 O.OOOE+OO 8.960E+02 RU-105 l .120E+OO O.OOOE100 O.OOOE+OO l.4IOE100 J.820E+04 9.040E+04 O.OOOE+OO 4.340E-01 RU-106 9.840E+04 O.OOOE+OO O.OOOE+OO l.900E+05 l.610E+07 9.600E+05 O.OOOE+OO 1.240E+04 AG-llOM l.380E+04 l.3JOE+04 0.000E+OO 2.500E+04 6.750E+06 2.730E+05 O.OOOE+OO 7.990E+03 TE-125M 4.880E+03 2.!40E+03 l.400E+03 O.OOOE+OO 5.360E+05 7.500E+04 0.000E+OO 6.670E+02 TE-127 2.0I OE+OO 9.120E-Ol l.420E+OO 7.280E+OO 1.l20E+04 8.080E+o4 O.OOOE+OO 4.420E.Ql TE-127M l. 800E+o4 8.160E+03 4.380E+o3 6.540E+04 l.660E+06 I 590E+05 O.OOOE+OO 2.180E+03 TE-129 7.IOOE-02 3.380E-02 5.180E-02 2.6608-01 3.300E+03 l .620E+03 0.000E+OO l.760E-02 TE-129M l.390E+04 6.580E+03 4.580E+03 5.190E+04 l .980E+06 4.050E+05 0.000E+OO 2.250E+03 TE-131 l.580E-02 8.320E-03 l.240E-02 6.l80E-02 2.340E+03 l.5l0E+Ol O.OOOE+OO 5.040E-03 TE-131 M 9.840E+OI 6.0IOE+OI 7.250E+ol 4.390E+02 2.380E+05 6.210E+05 0.000E+OO 4.020E+OI TE-132 3.600E+02 2.900E+02 2.460E+02 l.950E+03 4.490E+05 4.630E+05 O.OOOE+OO 2.l.90E+02 1-130 6.240E+03 L790E+04 1.490E+06 2.750E+04 O.OOOE+OO 9.120E+03 O.OOOE+OO 7.170E+03 AppcndhcH Ri Teen [nhafalion

• Page 2 of3 Page 9-169

Attachment 9 **

Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offs1tc Dose Calculation Manual (ODCM)

APPENDIXH R! Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: fuhalation (INHL) Units: mrem/yr / µCi/mJ Nuclide Bone Liver Thyl'Oid Kidney Lune Gilli Skin Total Body 1-131 3.540E+04 4.910E+o4 i.460E+07 8.400E+04 O.OOOE+OO 6.490E+03 O.OOOE+OO 2.640E+04 1-132 l.590E+03 4.380E+03 l .51 0E-Hl5 6.920E+03 O.OOOE+oo l.270E+o3 O.OOOE+OO 1.580E+03 1-133 l.220E+04 2.050E+04 2.920E+06 3.590E+04 O.OOOE+OO 1.030E+04 O.OOOE+OO 6.220E+03 I-134 8.880E+02 2.320E+03 3.950E+o4 3.660E+03 O.OOOE+oO 2.040E+o l O.OOOE+OO 8.400E+02 I-135 3.700E+03 9.440E+03 6.210E+05 l.490E+04 0.(IOOE+OO 6.950E+03 O.OOOE+OO 3.490E+03 CS-134 5.020E+05 l.130E+06 O.OOOE+oO 3.750E+05 l.460E+05 9.760E+03 O.OOOE+OO 5.490E+05 CS-136 5.150E+o4 1.940E+05 O.OOOE+OO l.100E+05 1.780E+04 l.090E+04 0.000E+OO l.370E+05 CS-137 6.700E+05 8.480E+05 0.000E+OO 3.040E+05 l.210E-H)5 8.480E+03 O.OOOE+OO 3.1lOE+OS CS-138 4.660E+02 8.560E+02 O.OOOE+OO 6.620E+02 7.870E+OI 2.7000-01 O.OOOE+OO 4.460E+02 BA-139 l .340E+OO 9.440E-04 0.000E+OO 8.8808-04 6.460E+03 6.450E+03 O.OOOE+OO 3.900E-02 BA-140 5.470E+04 6. 700E+OI O.OOOE+OO 2.280E+Ol 2.030E+06 2.290E+05 O.OOOE+OO 3.5'.!0E+03 BA-141 i.420E-Ol 1.060E-04 O.OOOE+OO 9.840E-05 3.290E+03 7.460E-04 O.OOOE+OO 4.740E-03 BA-142 3.700E-02 3.700E-05 0.000E+OO 3.140E-05 l.910E+03 4.790E-10 O.OOOE+OO 2.270E-03 LA-140 4.790E+02 2.360E402 0.000E+OO 0.000E+OO 2.140E+05 4.870E+05 O.OOOE+OO 6.260E+OI LA-142 9.600E-Ol 4.250E-OI O.OOOE+oO 0.000E+OO i.020E+04 1.200E+04 O.OOOE+OO l.060E-OI CE-141 2.840E+04 1.900E+04 O.OOOE+OO 8.880E+03 6.140E+05 l.260E+05 0.000E+OO 2.l 70E+03 CE-143 2.660E+02 l .940E+02 O.OOOE+OO 8.640E+OI l.300E+05 2.550E+05 O.OOOE+OO 2.l60E+OI CE-144 4.890E+06 2.020E+06 O.OOOE+OO l.210E+06 1.340E+07 8.640E+05 O_QOOE+oo 2.620E+05 PR-143 l.340E+Q.I 5.310E+03 O.OOOE+OO 3.090E+03 4.830E+05 2.140E+05 O.OOOE+OO 6.620E+02 PR-144 4.300E-02 1.7606-02 O.OOOE+(IO IOIOE-02 1.750E+03 2.350E-04 O.OOOE+OO 2.180E-03 ND-147 7 860E+03 8.560E+03 0.000E+OO 5.020E+03 3.720E+05 I 820E+05 O.OOOE+OO 5.130E+02 W-187 l.200E+ill 9.760E+OO O.OOOE+oO O.OOOE+OO 4.740E+04 l.770E+05 O.OOOE+OO 3.430E+OO NP-239 3.380E+02 3.190E+Ol O.OOOE-HlO I.OOOE+02 6.490E+04 l.320E+05 O.OOOE+OO l.770E+Ol AppcndixH Ri Teen inhalation* Page 3 of3 Page 9-170

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXH R1Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pafl1way: Ground Plane Deposition (GPD) Units: m 2*mrem/yr I µCi/sec Nuclide Bone Liver Thyroid Kidney Lun2 Gilli Skin Total Body H-3 O.OOOE+OO O.OOOE+oO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO C-14 O.OOOE+OO 0.000E+OO O.OOOE+<lO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO NA-24 l.1 90E+07 1.190E+o7 1.1 90E+07 l.1 90E+07 l.l90E+07 l.190E+07 l.390E+07 l.190E+07 P-32 O.OOOE+OO O.OOOE+OO O.OOOE+-00 0.000E+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO CR-51 4660E+06 4.660E+o6 4660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 l.390E+09 l .390E+09 l.390E+09 l.390E+09 l.390E+09 l.390E+09 l.630E+09 l.390E+09 MN-56 9.020E+05 9.020E+o5 9.020E+05 9.020E+05 9.020E+05 9.020E+05 l.070E+06 9.020E+05 FE-55 O.OOOE+OO O.OOOE+-00 O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+o8 3.210E+08 2.730E+08 C0-58 3.790E+08 3.790E+08 3.790E+o8 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 C0-60 2.!SOE+IO 2.150E+l0 2.lSOE+lO 2.ISOE+!O 2.!SOE+IO 2.150E+IO 2.530E+l0 2.150E+IO NI-63 0.000E+OO O.OOOE+-00 O.OOOE+-00 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO NI-65 2.970E+05 2.970E+05 2.970E+o5 2.970E+05 2.970E+05 2.970E+o5 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E f05 6.070E105 6070E+05 6.070E+05 6.880E*105 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+o8 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.000E+OO 0.000E+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+o3 4.870E+o3 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+o5 2.030E+05 2 360E+05 2.030E+05 BR-85 O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+o6 8.990E+o6 1 030E+07 8.990E+06 RB-88 3.3LOE+04 3.310E+04 3.3IOE+04 3.310E+04 3.310E+04 3.3IOE+04 3.780E+04 3.3l0E+04 RB-89 l.230E+05 l .230E+05 l.230E+o5 l .230E+05 l.230E+05 1.230E+o5 l.480E+05 l.230E+05 SR-89 2.160E+04 2.l60E+04 2.160E+04 2.160E+04 2.160E+04 2. l60E+04 2.5 10E+04 2.160E+04 SR-90 O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+-00 O.OOOE+OO 0.000E+OO SR-91 2.l50E+06 2.l50E+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 Depositioo - PHgc I of 3 Page 9-171

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Off.site Dose Calculation Manual (ODCM)

APPENDIXH R 1Teen Dose Factors for use in the Gaseous Dose Calculations Agegronp: TEEN Pathway: Ground Plane Deposition (GPD) Uni.ts: m1 *mrem/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lun2 Gilli Skin Total Body SR-92 7.770E+05 7.770E+o5 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-Hl3 4.490E+03 4.490E+03 4.490E+03 5.310E+03 4.490E+03 Y-91 J.070E+06 1.070E+06 J.070E+06 l.070E+06 1.070E+06 J.070E+06 1.210E+06 l.070E+06 Y-91M I.0OOE+05 1.000E+05 I.OOOE+o5 I.000E+05 1.000E+o5 I.OOOE+05 l.160E+o5 l.000E-H)5 Y-92 l.800E+05 1.SOOE+-05 1.800E+05 1.800E+05 1.800E+05 l.800E+05 2.140E+05 l.800E+05 Y-93 1.830E+05 1.830E+05 l.830E+o5 1.830E+05 1.830E+05 1.830E+o5 2.5l0E+05 1.830E+05 ZR-95 2.450E+o8 2.450E+08 2.450E+o8 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+o6 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+0S l.370E+08 1.370E+08 l .370E+08 1.610E+08 l.370E+08 M0-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+o6 4.630E+06 3.990E+06 TC-99.M 1.840E+05 1.840E+o5 l .840E+OS l.840E+05 1.840E+o5 l.840E+05 2.l lOE+05 l.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 l.080E+08 l.080E+08 l.080E+08 l.080E+08 1.260E+08 l.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6360E+0S 6.360E+05 7.2\ 0E , 05 6.360Et 05 RU-106 4.220E+08 4.220E+08 4.220E+o8 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-IIOM 3.440E+09 3.440E+09 3.440E+-09 3.440E+09 3.440E+09 3.440E+09 4.0l0E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 l.550E+06 l.550E+06 1.550E+06 1.550E+06 2.130E+o6 1.550E+06 TE-127 2.980E+03 2980E+03 2.980E+o3 2.980E+03 2.980E+o3 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.!60E+04 9.160E+04 9.l60E+04 9.160E+04 9.160E+04 l.080E+05 9.160E+04 TE-129 2.620E+04 2.620E+04 2.620E+{l4 2.620E+04 2.620E+04 2.620E+04 3.JOOE+04 2.620E+04 TE-129M l .980E+07 1.980E+o7 1.980E+07 l.980E+07 1.980E+07 l.980E+07 2.3IOE+07 l.980E+07 TE-131 2.920E+04 2.920E+04 2.9'.?0E+o4 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+o6 8.030E+06 8.030E+o6 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E-Hl6 4.230E+06 4.230E+06 4.980E+06 4.230E+06 I-130 5.5IOE+06 5.510E+06 5.510E+06 5.5!0E+06 5.5IOE+06 5.5\0E+06 6.690E+06 5.5lOE+06 Appendix H Ri Teen Ground Plane Dtpositioo - Page 2 of 3 Page 9-172

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXH R1Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Ground Plane Deposition (GPD) Units: m 1 *mrem/yr / µCi/sec Nuclide Bone Liver Thvroid Kidney Lun2 Gilli Skin Total Body 1-131 1.720E+o7 1.720E+-07 1.720E-t-07 l.720E+07 1.720E+07 l.720E+07 2.090E+-07 l.720E+07 1-132 1.250E+06 l.250E+06 l.250E+<)6 1.250E+06 1.250E+06 1.250E+06 l.470E+06 1.250E+06 I-133 2.450E+06 2.4S0E+o6 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+o5 4.470E+05 4.470E+o5 4.470E+o5 5.300E+05 4.470E+05 1-135 2.530E+06 2.530E+o6 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+o9 6.860E+09 6.860E+09 6.860E+09 8.000E+09 6.860E+09 CS-136 I.5IOE+08 l.SI0E+-08 1.5JOE+08 1.5JOE+08 1.5IOE+08 1.5IOE+08 l.710E+08 l.510E+08 CS-137 l.030E+l0 l.030E+IO l.030E+l0 l.030E+IO l.030E+!0 1.030E+IO l.200E+I0 l.030E+IO CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+-05 3.590E+05 3.590E+o5 4.IOOE+OS 3.590E+05 BA-139 1.060E+05 1.060E+05 l.060E-t-05 l.060E+-05 l.060E+05 l.060E+-05 l.190E+05 l.060E+o5 BA-140 2.0S0E+-07 2.0S0E+-07 2.050E+07 2.0S0E+-07 2050E+07 2.0S0E+-07 2.350E+07 2.050E+07 BA-141 4.170E+o4 4.170E+o4 4.l70E+-04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.l7*E+04 BA-142 4.490E+04 4.490E+04 4.490E+-04 4.490E+04 4.490E+04 4.490E+-04 5.II0E+04 4.490E+04 LA-140 l.920E+07 1.920E* 07 l.920E+07 l.920Et-07 1.920E+07 l.920E+07 2.180E107 l.920E+07 LA-142 7.600E+05 7.600E+o5 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 l.370E+07 l.370E+07 l .370E+-07 l.370E+07 l.370E+07 l.370E+07 l.540E+07 1.370E+07 CE-143  : .310E+06 2.310E+-06 2.310E+-06 2.310E+06 2.3J0E+06 2.310E+06 2.630E+06 2.3l0E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E-t-07 8.040E+07 6.950E+o7 PR-143 0.OOOE+OO 0.OOOE+OO 0.OOOE+OO 0.000E+OO 0.OOOE+OO 00OOE+OO O.0OOE+OO 0.0OOE+00 PR-144 1.830E+03 I 830E+03 1.830E+(13 1.830E+03 l.830E+03 1.830E-t-03 2.1 10E+03 l.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 l.0I0E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+o6 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 l.7 10E+-06 l.710E+06 l.710E+06 l.710E+06 l.710E+06 1.710E+06 1.980E+06 1.7l0E+06 Appcndix H Ri Teen Ground Plane Deposition. Page l of 3 Page 9-173

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nucl.ear Station Offsite Dose Calculat,on Mamnl (ODCM)

APPENDIX I R1Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD PathlVay: Grs/Cow/Milk. (CMILk") Units: m 2*m1*em/yr / µCi/sec; mr<m/yr / 1,1.Cilm' (H-l, C-14)

Nuclide Bone Liver Thvroid Kidney Lun11 Gilli Skin Tot.'ll Bodv H-3 0.000E+OO l.570E+03 1.570E+03 l.570E+03 l.570E+03 l.570E+03 O.OOOE+OO l.570E+03 C-14 1.1506+05 2.310E+04 2.3I06+-04 2.310E+04 2.310E+04 23106+04 0.000E+OO 2.3IOE+04 NA-24 8.850E+06 8.850E+06 8.850E+06 8.850E+06 ' 8.850E+06 8.850E+06 O.OOOE+OO 8.850E+06 P-32 7.780E+ l0 3.640E+09 0.000E+OO O.OOOE+OO O.OOOE+OO 2.150E+09 O.OOOE+OO 3.000E+09 CR-51 O.OOOE+OO 0.000E+OO 5.650E+04 l.540E+04 l .030E+o5 5.400E+06 O.OOOE+OO l.020E+05 MN-54 O.OOOE+OO 2.IOOE+07 O.OOOE+OO 5.880E+06 O.OOOE+OO l.760E+07 O.OOOE+OO 5.590E+06 MN-56 0.000E+OO l.260E-02 O.OOOE+OO l.530E-02 O.OOOE+oO 1.830E+OO O.OOOE+OO 2.860E-03 FE-55 1.1 206+08 5.930E+07 O.OOOE-H)O O.OOOE+OO 3.3506+07 l.100E+07 O.OOOE+OO l.840E+07 FE-59 l.200E+08 l .950E+08 O.OOOE+OO O.OOOE+OO 5.640E+07 2.030E+08 O.OOOE+OO 9.690E+07 C0-58 O.OOOE+OO 1.2l0E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO 7.070E+07 0.000E+OO 3.710E+07 C0-60 0.000E+OO 4.320E+o7 O.OOOE+oO O.OOOE+OO 0.000E+OO 2.390E+08 O.OOOE+OO 1.270E+08 Nl-63 2.960E+IO l.590E+09 O.OOOE+OO 0.000E+OO O.OOOE+po l.070E+08 O.OOOE+oo 1.010E+09 Nl-65 l.660E+OO 1.560E-OI O.OOOE+OO 0.000E+OO O.OOOE+OO l.910E+01 0.000E+OO 9.IOOE-02 CU-64 O.OOOE+OO 7.460E+04 O.OOOE+OO I.800E+05 O.OOOE+OO 3.500E+06 O.OOOE+oo 4.5IOE+04 ZN-65 4.130E+09 l.lOOE+IO O.OOOE+OO 6.940E+09 O.OOOE+OO l.930E+09 O.OOOE+OO 6.850E+09 ZN-69 9.460E-12 l.370E-1I O.OOOE+oO 8.300E-12 O.OOOE+OO 8.620E-IO O.OOOE+OO 1.260E-12 BR-83 O.OOOE+OO O.OOOE+oO 0.000E+oO O.OOOE+OO O.OOOE+oO 0.000E+OO O.OOOE+oo 4.400E-01 BR-84 0.000E+OO O.OOOE+oO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OU 6.5IOE-23 BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+oo 0.000E+OO 0.000E+OO 0.000E+OO RB-86 0.000E+OO 8.770E+09 O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.640E+08 O.OOOE+OO 5.390E+09 RB-88 O.OOOE+OO 7.160E-45 O.OOOE+OO O.OOOE+OO 0.000E+OO 3.5100-46 O.OOOE+oo 4.970E-45 RB-89 O.OOOE+OO l.340E-52 O.OOOE+OO 0.000E+OO O.OOOE+OO 1.1700-54 O.OOOF.+00 1.1 90E-52 SR-89 6.620E+09 O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO 2.560E+08 O.OOOE+OO 1.890E+08 SR-90 1.120E+ I I 0.000E+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO l.510E+09 O.OOOE+OO 2.830E+IO SR-91 l.300E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.880E+05 O.OOOE+OO 4.920E+03 Appendix IRi Child Cow Milk* Page 1 of3 Page 9-174

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Off.site Dose Calculation Manual (ODCM)

APPENDIX I R1Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Milk (CMILiq Units: m'*mrern/yr / µCi/sec; mrem/yr / 1<Ci/m3 (H.3 C-14)

Nuclide Bone Liver Thvroid Kidnev LUD!! Gilli Skin Total Bodv SR-92 2.180E+OO O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO 4.130E+01 O.OOOE+OO 8.750E--02 Y-90 3.220E+02 O.OOOE+OO O.OOOE+-00 0.000E+OO O.OOOE+OO 9.1706+05 O.OOOE+OO 8.620E+OO Y-91 3.900E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.200E+06 O.OOOE+OO l.040E+03 Y-91M 2.670E-19 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.2400-16 O.OOOE+OO 9.730E-21 Y-92 2.530E-04 O.OOOE+OO O.OOOE+-00 0.000E+OO O.OOOE+OO 7.310E+OO O.OOOE+oo 7.240E-06 Y-93 1.0IOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.510E+04 0.000E+OO 2 780E.02 ZR-95 3.830E+03 8.420E+02 O.OOOE+-00 l.210E+03 O.OOOE+OO 8.790E+05 O.OOOE+oo 7.500E+02 ZR-97 1.920E+OO 2.770E-Ol O.OOOE+-00 3.980E-01 O.OOOE+OO 4.200E+04 O.OOOE+OO 1.640E--Ol NB-95 3.!80E+05 l.240E+05 O.OOOE+-00 l.160E+05 O.OOOE+OO 2.290E+08 0.000E+OO 8.840E+04 M0-99 O.OOOE+OO 8.140E+07 O.OOOE+-00 l.740E+08 O.OOOE+OO 6.730E+07 O.OOOE+OO 2.0IOE+07 TC-99M l.320E+Ol 2.590E+ol O.C)()()E+oo 3.760E+02 l.320E+OI 1.470E+04 0.000E+OO 4.290E+02 TC-IOI 1.160E-59 1.220E-59 O.OOOE+-00 2.080p-58 6.440E-60 3.870E-59 O.OOOE+OO 1.540E-58 RU-103 4.280E+03 O.OOOE+OO. O.OOOE+OO l.080E+04 O.OOOE+OO l.110E+05 O.OOOE+OO 1.650E+03 RU-105 3.820E-03 O.OOOE+OO O.OOOE+-00 3.360E-02 O.OOOE+OO 2.490E+OO O.OOOE+OO l.390E-03 RU-106 9.240E+04 O.OOOE+oo O.OOOE+OO l.250E+05 O.OOOE+OO l.440E+06 O.OOOE+OO 1.150E+04 AG-llOM 2.090E+08 l.410E+08 O.OOOE+-00 2.630E+o8 O.OOOE+OO l.680E+IO O.OOOE+OO l.130E+08 TE-125M 7.380E+07 2.000E+07 2.070E+-07 O.OOOE+OO O.OOOE+OO 7.120E+07 O.OOOE+OO 9.840E+o6 TE-127 2.980E+03 8.020E+o2 2.060E+03 8.470E+03 O.OOOE+OO l.160E+05 O.OOOE+oo 6.380E+02 TE-127M 2.080E+08 5.600E+07 4.970E+o7 5.930E+08 O.OOOE+OO l.680E+08 O.OOOE+OO 2.470E+07 TE-129 l.280E--09 3.580E-IO 9.160E-IO 3.750E-09 O.OOOE+OO 7.9900-08 O.OOOE+OO 3.050E-IO TE-129M 2.71 0E+08 7 580E+o7 8.750E+-07 7.970E+08 O.OOOE+OO 3.3100+08 O.OOOE+oo 4.2IOE+07 TE-131 I 620E-32 4.920E-33 l.240E-32 4.890E-32 O.OOOE+OO 8.490E-32 O.OOOE+OO 4.810F~33 TE-l31M l.600E+06 5.530E+05 1.1 40E+Q6 5.350E+06 O.OOOE+OO 2.240E+07 0.llOOE+OO 5.890E+05 TE-132 l.020E+07 4.530E+06 6.600E+o6 4.210E+07 O.OOOE+OO 4.570E+07 O.OOOE+OO 5.480E+06 1-130 l.730E+06 3.490E+o6 3.840E+o8 5.220E+06 O.OOOE+OO 1.630E+06 O.OOOE+-00 l.800E+o6 Appendix r Ri Child Caw Mi lk

• Page 2 of 3 Page 9-175

Attachment *g Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offaite Dose Calculat,on Manual (ODCM)

APPENDIX I R1 Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Milk (CMILII..) Units: m 2 *mrern/y1* / µCi/sec; mrem/vr I µCi/m3 (H-3 C-14)

Nuclide Bone Liver Thyroid Kidney Lunl? Gilli Skin Total Body 1-131 l.300E+09 l.310E+09 4.330E+l I 2.150E+09 O.OOOE+OO l.170E+08 O.OOOE+OO 7.450E+08 I-132 6.890E-Ol 1.270E+OO 5.870E+OI l.940E+OO O.OOOE+OO l.490E+OO O.OOOE+OO 5.820E-Ol I-133 1.noE+o1 2.120E+07 3.940E+09 3.540E+07 O.OOOE+OO 8.560El-06 O.OOOE+OO 8.030E t06 I-134 8.480E-12 1.570E-11 3.620E-10 2.4108-11 O.OOOE+OO J.040E-11 0.0008+00 7.250E-12 1- 135 5.400E+04 9.720E+04 8.610E+06 l.490E+05 O.OOOE+OO 7.400E+04 0.0008+oo 4.600E+04 CS-134 2.260E+IO 3.720E+10 O.OOOE+OO l.150E+l0 4.130E+09 2000E+08 0.0008+00 7.840E+09 CS-136 l.010E+09 2.780E+09 O.OOOE+OO l.480E+09 2.210E+o8 9.770E+07 O.OOOE+OO 1.800E+09 CS-137 3.220E+ IO 3.090E+IO O.OOOE+OO J.OIOE+IO 3.620E+09 l .930E+08 O.OOOE+OO 4.550E+09 CS-138 3.980E-23 5.530E-23 O.OOOE*t-00 3.890E-23 4.190E-24 2.550E-23 O.OOOE+OO 3.SIOE-23 BA-139 2.0l OE-07 1.070E-10 O.OOOE+oO 9.360E-l l 6.300E-ll l.1 60E-05 0.000E+OO 5.820E-09 BA-140 l.170E+08 l.030E+05 O.OOOE+-00 3.340E+04 6.120E+04 5.930E+07 0.0008+00 6.840E+06 BA-141 l.850E-4~ 1.0408-48 O.OOOE+OO 8.960E-49 6.0908-48 1.0508-45 o.oooi,+oo 6.0208-47 BA- 142 l.150E-79 8.3IOE-83 O.OOOE+OO 6.7208-83 4.890E-83 l.S IOE-81 0.0008+00 6.4508-81 LA- 140 1.940E+Ol 6.780E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 1.890E+05 O.OOOE+OO 2.290E+OO LA-142 8. lOOE-11 2.580E- J l O.OOOE+OO O.OOOE* OO 0.0008+00 5.120E-06 O.OOOE+OO 8.0908-12 CE-141 2.190E+04 1.0908+04 O.OOOE+OO 4.780E+03 0.000E+OO l.360E+07 0.000E+OO 1.620E+03 CE-143 1.870E+02 1.020E+05 O.OOOE+OO 4.260E+OI O.OOOE+OO l.490E+06 O.OOOE+OO l.470E+O l CE-144 l.620E+06 5.090E+-05 0.0008+00 2.820E+05 0.000E+OO l.330E+08 O.OOOE+OO 8.660E+04 PR-143 7.180E+02 2.160E+02 O.OOOE+OO 1.170E+02 O.OOOE+OO 7.750E+05 O.OOOE+OO 3.560E+Ol PR-144 2.680E-53 8.290E-54 O.OOOE+OO 4.380E-54 O.OOOE+OO 1.7800-50 O.OtXl8+00 l.350E-54 ND-147 4.450E+02 3.600E+02 O.OOOE+-00 1.980E+02 O.OOOE+OO 5.700E+05 O.OOOE+OO 2.790E+ol W-187 2.890E+04 1.710E* 04 O.OOOE+OO 0.000E+OO 0.000E+OO 2.400E+06 O.OOOHOO 7.670E+03 NP-239 l.720E+Ol l.240E+oo 0.000E+-00 3.580E+OO 0.0008+00 9.170E+04 O.OOOE+OO 8.710E-Ol Appendix tRi Child Cow Milk. Page 3 of 3 Page 9-176

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12 /31/2018 Oconee Nuclear Station Offsite Dose Calculat,on Manual (ODCM)

APPENDIX I R1Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Goat/Milk (GMILk.') Units: m 1 *mrem/yr / µCi/sec; mrem/vr / u.Ci/m' (H,3, C-14\

Nuclide Bone Liver Thyroid Kldney Lnn2 Gilli Skin Total Body H-3 O.OOOE+OO 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 O.OOOE+OO 3.200E+03 C-14 l.150E+0.5 2.3JOE+04 2.3JOE+04 2.3l0E+04 2.3JOEl-()4 2.3 10E1-04 O.OOOE+OO 2.310E+04 NA-24 1.060E+06 1.060E+06 1.060E+06 l.060E+06 l.060E+06 1.060E+06 O.OOOE+OO 1.060E+06 P-32 9.330E+ IO 4.370E+09 O.OOOE+OO 0.000E+OO O.OOOE+OO 2.580E+09 O.OOOE+OO 3.600E+09 CR-51 O.OOOE+OO O.OOOE+OO 6.780E+03 l.850E+03 l.240E+o4 6.480E+05 0.000E+OO 1.220E+04 MN-54 O.OOOE+OO 2.520E+06 O.OOOE+OO 7.060E+05 O.OOOE+OO 2 IIOE+06 O.OOOE+OO 6.700E+OS MN-56 O.OOOE+OO l.520E-03 O.OOOE+OO l.840E--03 O.OOOE+OO 2.200E-Ol O.OOOE+OO 3.430E-04 FE-55 1.450E+06 7.7JOE+05 0.000E+OO O.OOOE+OO 4.360E+05 1.430E+05 O.OOOE+OO 2.390E+05 FE-59 l .560E+06 2.530E+06 O.OOOE+OO 0.000E+OO 7.330E+05 2.630E+06 O.OOOE+OO l.260E+06 CO-58 0.000E+OO 1.450E+06 O.OOOE+OO 0.000E+OO O.OOOE+OO 8.490E+06 O.OOOE+OO 4.4SOE+06 C0-60 0.000E+OO 5.l80E+06 O.OOOE+OO O.OOOE+OO 0.000E+oo 2.870E+07 O.OOOE+OO 1.530E+07 NI-63 , 3.560E+09 J.900E+08 O.OOOE+OO O.OOOE+OO O.OOOE+oO l.2~0E+07 0.000E+OO 1.2l0E+08 Nl-65 1.990E-Ol l.870E-02 O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.290E+OO O.OOOE+OO 1.090E--02 CU-64 O.OOOE+OO 8.320E+03 O.OOOE+OO 2.0IOE+04 O.OOOE+oo 3.900E+05 O.OOOE+OO 5.020E+03 ZN-65 4.960E+08 1.320E+09 O.OOOE+OO 8.330E+08 O.OOOE+OO 2.320E+08 O.OOOE+OO 8.220E+08 ZN-69 1.140E-12 l.640E-12 0.000E+OO 9.960E-13 0.000E+OO J.030E-10 O.OOOE+OO 1.520E-13 BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+oo 0.000E+OO O.OOOE+OO 5.280E--02 BR-84 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 7.820E-24 BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO RB-86 O.OOOE+OO l.050E+09 O.OOOE+OO 0.000E+OO O.OOOE+OO 6.770E+07 O.OOOE+OO 6.470E+08 RB-88 O.OOOE+OO 8.590E-46 O.OOOE+OO O.OOOE+OO O.OOOE+oo 4.2\0E-47 O.OOOE+oo S.970E-46 RB-89 O.OOOE+OO l.610E-53 O.OOOE+OO 0.000E+OO O.OOOE+OO l.4IOE-5.5 O.OOOE+OO l.430E-53 SR-89 1.390E+IO O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+otl S.380E+08 O.OOOE+OO 3.970E+08 SR-90 2.350E+ l I O.OOOE+OO O.OOOE+oO 0.000E+OO O.OOOE+OO 3.160E+09 O.OOOE+OO S.950E+IO SR-91 ~.740E+05 0.000E+OO 0.000E+OO 0.000E+OO O.OOOE+OO 6.040E+OS O.OOOE+OO l.030E+04 Appendix r Ri Oiild C-,oat Milk . Paget of .l Page 9-177

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculat,on Manual (ODCM)

APPENDIX I R1 Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Goat/Milk (GMILK) Units: m 2 *nll'emly r / µCi/sec; mrem/vr / µCiim' (H.3 C-141 Nuclide Bone Li\'er Thvroid Kidney LUD!! Gilli Skin Total Body SR-92 4.580E+OO 0.0006+00 0.0006+-00 0.0006+00 0.0006+00 8.6806+0 1 0.0006+00 1.8406>)1 Y-90 3.870E+Ol 0.0006+00 O.OOOE+-00 0.0006+00 O.OOOE+OO 1.IOOE+05 0.000E+OO l .030E+OO Y-9 1 4.680E+03 0. 0006+00 0.0006+00 0.0006+00 O.OOOE+OO 6.240E+-05 0.0006+00 1.2506 +02 Y-91M 3.210E-20 0.0006+00 0.000E+OO O.OOOE+OO 0.000E+OO 6.280E-17 0.0006+00 l.1706-2 1 Y-92 3.040E-05 0.0001;+00 O.OOOE+-00 0.000E+OO O.OOOE+OO 8.770E-O l 0.0006+-00 8.6906-07 Y-93 l.210E-OI 0.0006+00 0.0006+-00 0.0006+00 O.OOOE+OO l.SIOE+03 O.OOOE+OO 3.3306-03 ZR-95 4.6006+02 l.OIOE+02 O.OOOE+OO 1.4506+02 0.000E+OO l.050E+05 0.000E+OO 9.000E+Ol ZR-97 2.300E-O l 3.3306-02 0.0006+-00 4.7806-02 0.0006+00 5.040E+03 0.000E+OO l.960E-02 NB-95 3.810E+04 l.490E+04 0.000E+-00 l.400E+04 0.000E+OO 2.750E+07 O.OOOE+OO l .060E+04 M0-99 0.000E+OO 9.7606+-06 O.OOOE+-00 2.0906+07 O.OOOE+OO 8.080E+06 O.OOOE+OO 2.420E+06 TC-99M l.590E+OO 3.1IOE+OO O.OOOE+OO 4.520E+OI 1.580E+OO l.770E+03 0.000E+OO 5.150E+OI TC-IOI l.400E.60 l.460E-60 O.OOOE;'-00 2.490E-59 7.7206-61 4.6400-60 0.0006+00 l.850E-59 RU- 103 5.140E+02 0.0006+00 O.OOOE+OO l.290E+03 O.OOOE+OO l.330E+04 O.OOOE+OO l.980E+02 RU- 10 5 4.580E--04 O.OOOE+OO O.OOOE+-00 4.0306-03 O.OOOE+OO 2.990E.Ol 0.0006+00 1.6606-0-l RU- 106 l.l 10E+04 0.0006+00 O.OOOE+OO 1.5006+04 O.OOOE+OO l.720E+05 0.0006+00 l .380E+03 AG-IIOM 2.5lOE+07 l .690E+07 0.0006+00 3.1506+07 O.OOOE+OO 2.0IOE+09 0.0006+00 1.3506+07 TE- 125M 8.850E+06 2.4006+06 2.480E+-06 O.OOOE+OO O.OOOE+OO 8.540E+06 0.0006+00 l.l80E+06 TE-127 3.570E+02 9.6306+-0l 2.470E+02 1.020E+03 0.000E+OO l.390E+04 0.0006+00 7.660E+OI TE-127M 2.500E+07 6.7206+06 5.9706+06 7.120E+07 0.0006+00 2.0206+07 O.OOOE+OO 2.960E+06 TE-129 l.540E-IO 4.300E-1l 1. lOOE-10 4.5 106-10 O.OOOE+OO 9.590E-09 0.000EtOO 3.660E-1 1 TE-l29M 3.260E+07 9.0906+06 l.050E+o7 9.5606+-07 O.OOOE+OO 3.970E+07 O.OOOE+-00 5.060E+06 TE-131 I 9400-33 5.910E-34 l.480E-33 5.8606-33 O.OOOE<OO 1.0200-32 O.OOOE-t*OO 5.770E-34 TE- 131 M l.920E+05 6.640E+04 1.3606+-05 6.4206+05 0.0006+00 2.690E+06 0.0006+00 7.060E+04 TE- 132 l.230E+06 5.4406+-05 7.920E+-05 5.0506+06 O.OOOE+OO 5.480E+06 O.OOOE+OO 6.570E+05 1- 130 2.070E+06 4.l90E+06 4.610E+-08 6.2606+-06 0.000E+OO l.960E+06 O.OOOE+OO 2.160E+06 Appendix I R..i Child Goal Milk

• Page 2 of .l Page 9-178

Attachme nt 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIX I R1Child Dose Factors for use in the Gaseous Dose Calculations Agegroup,: CHILD Pathway: Grs/Goat/Milk (GMILK) Units: m2 *m1*em/yr / µCi/sec; mrem/yr / LlCilm' <H-3 C-14)

Nuclide Hone Liver Thyroid Kidney Gilli Skin L UD!! Total Body 1- 131 l.560E+09 l .570E+09 5.200E+11 2.580E+09 O.OOOE+OO l.400E+08 O.OOOE+OO 8.940E+08 I-132 8.2700-01 U 20E+OO 7.0SOE+ol 2.330E+OO O.OOOE-100 l.790Er00 0.000E+OO 6.990E-01 I-133 2.060E+07 2.550E+07 4.730E+09 4.250E+07 0.000E+OO l.030Er07 O.OOOE+OO 9.640E+06 1-134 l.020E-11 l .890E-l l 4.350E-10 2. 890E-ll O.OOOE+OO 1.2500-11 O.OOOE+OO 8.700E-l2 I- 135 6.480E+04 1.1 70E+05 l.030E+07 l.790E+05 O.OOOE+oo 8.880E+04 O.OOOE+OO 5.520E+04 CS-134 6.790E+IO 1.110E+I I O.OOOE+OO 3.450E+IO 1.240E+10 6.010E+08 O.OOOE+oo 2.350E+IO CS-136 3.030E+09 8.340E+09 0.000E+OO 4.440E+09 6.630E+08 2.930E-Hl8 O.OOOE+OO 5.400E+09 CS-137 9.670E+IO 9.260E+!O O.OOOE+OO 3.020E+IO 1.090E+l0 5.800E+08 O.OOOE+OO l.370E+10 CS-138 1.1900-22 l.660E-22 0.000E+OO l.l70E-22 l.260E-23 7.640E-23 0.000E+OO 1.0SOE-22 BA-139 2.410E-08 1.290E-ll 0.000E+OO l.120E-1 l 7.560E-12 l.390E-06 O.OOOE+oo 6.980E-10 BA-140 l.410E+07 l .230E+04 O.OOOE+OO 4.0IOE+03 7.340E+03 7. !20E+OO 0.000E+OO 8.200E+05 BA-141 2.220E-46 1.240E-49 O.OOOE+OO l.080E-49 7.300E-49 l.270E-46 O.OOOE+OO 7.230E-48 BA-142 J.390E-80 9.970E-84 O.OOOE+OO 8.070E-84 5.870E-84 I.SIOE,82 0.000HOO 7.740E-82 LA-140 2.330E+OO 8.140E-OI O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.270E-Hl4 O.OOOE+OO 2.740E-Ol LA-142 9.7300-12 3. lOOE- 12 O.OOOE+OO O.OOOE+OO O.OOOE+OO 6.140E-07 O.OOOE+OO 9.710E-13 CE-141 2.620E+03 1.3l0E+03 0.000E+OO 5.740E+02 0.000E+OO l.630E+-06 0.000E+OO 1.940E+02 CE-143 2.250E+O I 1.220E+04 O.OOOE+OO 5.l20E+oo O.OOOE+OO l.790E+05 O.OOOE+oo l.770E+OO CE-144 l.950E+-05 6.110E+04 O.OOOE+oO 3.380E+04 0.000E+OO 1.590E+07 O.OOOE+oo l.040E+04 PR-143 8.620E+Ol 2.590E+Ol O.OOOE+OO l.400E+Ol O.OOOE+OO 9.300E+04 O.OOOE+OO 4.280E+OO PR-144 3.2200-54 9.950E-55 O.OOOE+OO 5.260E-55 O.OOOE+OO 2.1400-51 O.OOOE+OO 1.620E-55 ND-147 5.330E+OI 4.320E+OI O.OOOE+OO 2.370E+OI O.OOOE+OO 6.850E+04 O.OOOE+OO 3.350E+OO W-187 3.470E+03 2.050E+03 O.OOOE+OO O.OOOE+OO O.OOClE+OO 2.880E+05 O.OOOEHlO 9.210E+02 NP-239 2.070E+OO l.490E-OI O.OOOE+OO 4.300E-01 O.OOOE+OO I.IOOE+04 O.OOOE+OO 1.040E-Ol Appendix I Ri Olild C",oat Milk - Page 3 of 3 Page 9-179

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIX I R1Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Meat (CMEAT) Units: m 2 *m1*em/y1*/ µCi/sec; mren1/vr / LLC iim' (H-3 C-141 Nuclide Bone Liver Thyroid Kidney Lune Gilli Skin Tot.'ll Bodv H-3 O.OOOE+OO 2.340E+02 2.340E+-02 2.340E+02 2.340E+02 2.340E+02 O.OOOE+OO 2.340E+02 C- 14 3.700E+04 7400E+03 7.400E+03 7.400E+03 7.400E+03 7.400E+03 O.OOOE+OO 7.400E+03 NA-24 l.720E-03 1.7206-03 l.720E.03 1.720E-03 l.720E-03 1.720E-03 O.OOOE+OO 1.720E-03 P-32 7.420E+09 3.470E+08 0.000E+OO O.OOOE+OO 0.000E+OO 2.050E+08 O.OOOE+OO 2.860E+08 CR-5 1 O.OOOE+OO 0.000E+OO 4.880E+-03 l.330E+03 8.910E+-03 4.660E+05 O.OOOE+oo 8.790E+03 MN-54 0.000E+OO 8.010E+06 O.OOOE+-00 2 250E+06 O.OOOE+OO 6.720E+06 O.OOOE+OO 2.130E+06 MN-56 0.000E+OO 1.430E-53 O.OOOE-t-00 1.730E-53 O.OOOE-t-00 2.070E-5 I 0.000E+OO 3.230E-54 FE-55 4.570E+08 2.420E-t-08 O.OOOE+-00 O.OOOE+OO 1.370E+08 4.490E+07 O.OOOE+oo 7.510E+07 FE-59 3.760E+08 6.090E+08 O.OOOE-t-00 O.OOOE+OO 1.770E+08 6.340E+08 O.OOOE+OO 3.030E+08 C0-58 O.OOOE+oo 1.640E+07 0.000E+oO O.OOOE+OO O.OOOE+OO 9.580E+07 O.OOOE+OO 5.020E+07 C0-60 O.OOOE+OO 6.930E+07 O.OOOE+oO O.OOOE+OO 0.000E+OO 3.840E+08 0.000E+OO 2.040E+08 Nl-63 2.9IOE+ IO 1.560E+09 O.OOOE+OO O.OOOE+OO O.OOQE+OO l.050E+08 O.OOOE+OO 9.9!0E+08 NI-65 3.520E-52 3.3!0E-53 0.000E+-00. O.OOOE+OO O.OOOE+OO 4.0600-51 O.OOOE+OO l.930E-53 CU-64 O.OOOE+OO 2.970E-07 O.OOOE+OO 7.ISOE-07 0.000E+oo l.390E-05 O.OOOE+OO 1.SOOE-07 ZN-65 3.750E+08 1.000E+09 O.OOOE+OO 6.300E+08 O.OOOE+OO 1.760E+08 O.OOOE+OO 6.220E+OS ZN-69 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+oo 9.520E-57 BR-84 O.OOOE+oO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO RB-86 0.000E+OO 5.770E+08 O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.7!0E+07 O.OOOE+OO 3.550E+08 RB-88 O.OOOE+OO O.OOOE+OO O.OOOE+-00 n.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO RB-89 O.OOOE+OO O.OOOE+OO 0.000E+-00 O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO SR-89 4.820E+08 O.OOOE+OO O.OOOE+OO O.OOOE+()(J O.OOOE+OI) l.870E+07 O.OOOE+OO 1.380E+07 SR-90 l.040E+!O O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO  !.400E+08 O.OOOE+OO 2.640E+09 SR-91 2.400E- 10 O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO 5.300E-!O O.OOOE+OO 9.0SOE-12 Appendix ( Ri Olild Cow Meat

• Page t of 3 Page 9-180

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Oft:sitc Dose Calculation Manual (ODCM)

APPENDIX I R1 Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Meat (CMEAT) Units: m'*mrem/y1* / µCi/sec; mrem/yr / µCiim' ffi-3 C-14)

Nuclide Bone Liver Thyroid Kidney Lun2 GiUi Skin Total Body SR-92 l.850E-49 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 3.490E-48 0.000E+OO 7.400E-51 Y-90 l.710E,02 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 4.880Et-05 0.000E+OO 4.590E+OO Y-91 1.800E+06 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.400E+08 0.000E+OO 4.820E+04 Y-9IM O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO Y-92 2.4 10E-39 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 6.960E-35 O.OOOE+OO 6.890E-4!

Y-93 7 440E-12 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 1.1100-07 O.OOOE+OO 2.040E-13 ZR-95 2.660E+06 5.850E+05 O.OOOE+OO 8.380E+o5 O.OOOE+oo 6.l lOE+08 0.000E+OO 5.210E+05 ZR-97 3.200E-05 4.630E-06 O.OOOE+OO 6.650E-06 O.OOOE+OO 7.0lOE-01 O.OOOE+OO 2.730E-06 NB-95 3.IOOE+06 1.210E+06 O.OOOE-+-00 1.l 30E+06 0.000E+OO 2.230E+09 0.000E+OO 8.620E+05 M0-99 0.000E+OO l.150E+05 O.OOOE+OO 2.460E+05 O.OOOE+OO 9.510E+04 0.000E+OO 2.840E+04 TC-99M 6.1900-21 1.210E-20 0.000E+OO 1.760E-19 6.160E-21 6.910E-18 0.000E+OO 2.0IOE-19 TC-IOI 0.000E+OO 0.000E+OO O.OOOE+OO O.pOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO RU-103 l.550E+08 OOOOEl:00 O.OOOE+OO 3.900E+08 O.OOOE+OO 4.010E+09 O.OOOE+OO 5.960E+07 RU-105 9.020E-28 O.OOOE+OO O.OOOE+OO 7.930E-27 O.OOOE+oo 5.890E-25 O.OOOE+oo 3.270E-28 RU-106 4.440E+09 O.OOOE+OO O.OOOE+OO 5.990E+09 O.OOOE+oO 6.900E+IO O.OOOE+OO 5.540E+08 AG-llOM 8.390E+06 5.670E+o6 0.000E+OO 1.060E+07 O.OOOE+OO 6.740E+08 0.000E+OO 4.530E+06 TE-125M 5.690E+08 l.540E+o8 1.600E+08 0.000E+OO O.OOOE+OO 5.490E+08 O.OOOE+OO 7.590E+07 TE-127 3.380E-10 9.l20E-ll 2.340E-10 9.630E-10 O.OOOE+OO 1.3200-08 0.000E+OO 7.260E-ll TE-127M l.770E+09 4.780E+08 4.240E+08 5.060E+09 O.OOOE+OO 1.440E+09 O.OOOE+OO 2.l 10E+08 TE-129 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE* OO O.OOOE+OO TE-129M l.790E+09 5.tlOOE+08 5.770E-t-08 5.260E+09 O.OOOE+OO 2180E+09 O.OOOE+OO 2.780E+08 TE-131 0.000E+OO 0.000.E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOEl*OO O.OOOE+OO TE-131M 7.000E+02 2.420E+02 4.980E-t-02 2.340E+03 0.000E+OO 9.820E+03 O.OOOE+OO 2.580E+02 TE-132 2.120E+06 9.380E+o5 l.370E+06 8.710E+06 O.OOOE+OO 9.450E+06 O.OOOE+OO l.130E+06 I-130 3.030E-06 6.130E-06 6.750E-04 9.l60E-06 O.OOOE+OO 2.870E-06 O.OOOE+OO 3.160E-06 Appendix [ Ri 01ild Cow Meat - Page 2 of 3 Page 9-181

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Off.site Dose Calculation Manual (ODCM)

APPENDIX I R1 Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Meat (CMEAT) Units: m 2*m1*em/y1* / µCi/sec; mrem/vr I u.Ci/m3 <H-3. C-14)

Nuclide Hone U\'er Thyroid Kidney Lun21 Gilli Skin Total Body 1-131 l.650E+07 l.660E+07 5.500E+09 2.730E+07 O.OOOE+OO l.480E+06 O.OOOE+OO 9.460E+06 I-132 l.020E-58 1.880E-58 8.730E-57 2.8808-58 0.000E+OO 2.210E-58 0.000E+OO 8.650E-59 1-133 5.670E-01 7.020E-Ol l.300E+02 1.170E+OO O.OOOE+OO 2.830E-01 O.OOOE+OO 2.660E-01 I-134 0.000E+OO O.OOOE+OO 0.000E+OO 0.000E+OO 0.000E+OO 0.000E+OO O.OOOE+OO 0.000E+OO 1-135 6.510E-17 1.1706-16 1.040E-14 l.800E-16 O.OOOE+OO 8.930E-17 O.OOOE+OO 5.550E-17 CS-134 9.220E+OS l.510E+09 O.OOOE+OO 4.690E+08 l .680E+08 8.160E+06 O.OOOE+OO 3.190E+08 CS-136 l.620E+07 4.460E+07 O.OOOE+OO 2.370E+07 3.540E+-06 1.570E+06 O.OOOE+OO 2.880E+07 CS-137 l.330E+09 l.280E+09 O.OOOE+OO 4.160E+08 1.500E+08 7.990E+06 O.OOOE+OO l.880E+08 CS-13& 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO BA-139 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.0006+00 O.OOOE+OO 0.0006+00 BA-140 4.380E+07 3.8406+o4 0.0006+00 l.250E+04 2.2906+04 2.2206+07 O.OOOE+OO 2.5606+06 BA- 141 0.000!,+00 0.000E+OO O.OOOE+{IO O.OOOE+OO O.OOOE+oo 0.0006+00 O.pOOE+OO O.OOOE+OO BA-142 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO LA-140 5.590E-02 l.950E-02 O.OOOE+OO O.OOOE+OO 0.0006+00 5.440E+02 O.OOOE+OO 6.580E-03 LA-142 5.]l)OE-92 1.690E-92 0.0006+00 O.OOOE+OO 0.0006+00 3.350E-87 O.OOOE+OO 5.290E-93 CE-141 2.220E+04 l.110E+04 0.000E+OO 4.850E+03 O.OOOE+OO l.380E+07 0.000E+OO l.640E+03 CE-143 3.170E-02 l.720E+Ol 0.0006+00 7.2 l0E-03 0.0006+00 2.520E+02 O.OOOE+OO 2.490E-03 CE-144 2.320E+06 7.260E+05 0.0006+00 4.020E+05 0.0006+00 l.890E+08 O.OOOE+oo 1.240E+05 PR-143 3.340E+04 1.0006+04 O.OOOE+OO 5.430E+03 0.0006+00 3.6006+07 O.OOOE+OO 1.6606+03 PR-144 0.000E+OO O.OOOE+OO 0.0006+00 0.0006+00 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.0006+00 ND-147 l.170E+04 9.470E+03 0.0006+00 5.1906+03 0.0006+00 l.500E+07 O.OOOE+OO 7.330E+02 W-187 3 210E-02 1900E-<>2 OJl(X)E+OO 0.llOOE+()(J O.OOOE+OO 2.670E+OO O.OOOE+OO 8.530E-03 NP-239 4.260E-Ol 3.060E-02 0.000E+OO 8.850E-02 0.0006+00 2.2606+03 0.llOOE+OO 2.1506-02 Appendix l Ri Child Cow Meat

• Page 3 ol' 3 Page 9-182

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIX I R1Child Dose Factors for use in the Gaseous Dose Calculations Age group: CHILD Pathway: Grs/Goat/Meat (GMEA T) Units: m 2*m1*ern/yr / µCi/sec; mrcm/vr / u.Ciim' (H.J C-14)

I Nuclide Bone Lh er 1 Thyroid Kidney Lun2 Gilli Skin Total Bod1*

H-3 0.000E+OO 2.808E+Ol 2.808E+ol 2. 808E+OI 2.808E+OI 2.808E+O I O.OOOE+OO 2.808E+Ol C-14 4.440Er03 8.880E+02 8.880E+o2 8.880E+02 8.880E+02 8.880E+02 O.OOOE+OO 8.880E+02 NA-24 2.064E.04 2.064E-04 2.064E.04 2.064E-04 2.064E-04 2.064E-04 O.OOOE+OO 2.064E.04 P-32 8.904E+08 4.164£+07 0.000E+OO O.OOOE+OO O.OOOE+OO 2460E+07 0.000E+OO 3.432E+07 CR-51 O.OOOE+OO 0.000E+OO 5.856E+o2 l.596E+o2 t.069E+o3 5.59"..E+o4 O.OOOE+OO l.055E+03 MN-54 O.OOOE+OO 9.612E+05 O.OOOE+OO 2.700E+05 O.OOOE+OO 8.064E+OS O.OOOE+oo 2.556E+OS MN-56 0.000E+OO l.716E-54 0.000E+oo 2.076E-54 O.OOOE+oo 2.484E-52 O.OOOE+OO 3.876E-55 FE-55 5.484E+07 2.904E+07 O.OOOE+oO O.OOOE+OO 1.644£+07 5.388E+06 O.OOOE+OO 9.0!2E+06 FE-59 4.512£+07 7.308E+07 0.000E+oo 0.000E+OO 2.124E+07 7.608E+07 0.000E+OO 3.636E+07 CO-58 0.000E+OO l.968E+06 O.OOOE+oO O.OOOE+OO O.OOOE+OO 1.150E+07 O.OOOE+OO 6.024E+06 C0-60 0.000E+OO 8.316E+06 O.OOOE+oO 0.000E+OO 0.000E+OO 4.608E+07 0.000E+OO 2.448E+07 NI-(\3 3.492E+09 l.872E+08 0.000E+oo O.OOOE+oo O.OOOE+OO ,L260E+o7 O.OOOE+OO l.189E+08 NI-65 4.224E-53 3.972E-54 O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.872E-52 O.OOOE+OO 2.316E-54 CU-64 O.OOOE+OO 3.564E-08 O.OOOE+oo 8.616E-08 O.OOOE+oo 1.668£-06 O.OOOE+OO 2.160£-08 ZN-65 4.500£+07 1.200£+08 O.OOOE+OO 7.560£+07 O.OOOE+OO 2.112E+07 O.OOOE+OO 7.464E+07 ZN-69 0.000E+OO O.OOOE+oO O.OOOE+oo O.OOOE+OO 0.000E+OO 0.000E+oO O.OOOE+oo 0.000E+OO BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+oo O.OOOE+oo O.OOOE+OO l.142E-57 BR-84 0.000E+OO O.OOOE+OO O.OOOE+oo 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+oo O.OOOE+oo O.OOOE+OO O.OOOE+OO RB-86 O.OOOE+OO 6.924E+o7 O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.452E+06 O.OOOE+OO 4.260E+07 RB-88 O.OOOE+OO O.OOOE+OO O.OOOE+oo 0.000E+OO O.OOOE+oo O.OOOE+OO O.OOOE+oo O.OOOE+OO RB-89 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO SR-89 5.784E+07 O.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+oo 2.244E+06 O.OOOE+OO l.656E+06 SR-90 1.248£+09 O.OOOE+-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.680E+07 O.OOOE+OO 3.168E+08 SR-91 2.880E-l 1 O.OOOE+oo O.OOOE+oO O.OOOE+OO O.OOOE+OO 6.360E-11 O.OOOE-l-00 l.086E-12 Appendix I Ri Cbild Goat Meat

• Page I af 3 Page 9-183

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offalte Dose Calculat,on Manual (ODCM)

APPENDIX I R1Child Dose Factors for use in the Gaseous Dose Calculations Age group: CHILD Pathway: Grs/Goat/Meat (GMEA T) Units: m 2*nu*em/yr / µCi/sec; I ntren>/yr / µCiim' (H.J C-14)

Nuclide Bone f...i\rer Thvroid Kidnev Lun!! Gilli Skin Total Bodv SR-92 2.220E-50 O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO 4.188E-49 O.OOOE+OO 8.880E-52 Y-90 2.052E+Ol 0.000E+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO 5.856E+04 0.000E+OO 5.508E-O l Y-91 2.160E+05 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.880E+07 O.OOOE+OO 5.784E+03 Y-91M O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO Y-92 2.892E-40 0.000E+OO 0.000E+-00 O.OOOE+OO O.OOOE+oo 8.352E-36 O.OOOE+OO 8.268E-42 Y-93 8.928E-13 O.OOOE+-00 O.OOOE+oO O.OOOE+OO O.OOOE+OO l.332E-08 O.OOOE+OO 2.448E-14 ZR-95 3.192E+05 7.020E+04 O.OOOE+oO 1.006E+05 O.OOOE+OO 7.332E+07 O.OOOE+OO 6.252E+04 ZR-97 3.840E-06 5.556E-07 O.OOOE-+<lO 7.980E-07 O.OOOE+OO 8.412E-02 O.OOOE+OO 3.276E-07 NB-95 3.720E+05 l.452E+05 0.000E+-00 L356E+05 0.000E+OO 2.676E+08 0.000E+OO l .034E+05 M0-99 O.OOOE+OO 1.380E+04 O.OOOE+-00 2.952E+04 O.OOOE+OO l.141E+04 O.OOOE+OO 3.408E+03 TC-99M 7.428E-22 1.452E-2I O.OOOE+-00 2.112E-20 7.392E-22 8.292E-19 O.OOOE+OO 2.412E-20 TC-101 O.OOOE+OO 0.000E+OO O.Of)OE+-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO RU- 103 l.860E+Q7 O.OOOE+OO O.UOOE+OO 4.680E+07 O.OOOE+OO 4.8l2E+08 O.OOOE+OO 7.152E+06 RU-105 1.082E-28 OOOOE+OO O.OOOE+-00 9.516E-28 O.OOOE+OO 7.068E-26 O.OOOE+OO 3.924E-29 RU-106 5.328E+O& O.OOOHOO O.OOOE+OO 7.188E+08 0.000E+OO 8.280E+09 O.OOOE+OO 6.648E+07 AG-l!OM l.007E+06 6.804E+05 O.OOOE+-00 l.272E+06 0.000E+-00 8.088E+07 O.OOOE+OO 5.436E+05 TE-125M 6.828E+07 l.848E+07 1.920E+07 O.OOOE+OO O.OOOE+OO 6.588E+07 O.OOOE+oo 9.l08E+06 TE-127 4.056E- I I 1.094E-1 l 2.808E- l l l.l56E-IO O.OOOE+OO l.584E-09 0.000E+OO 8.712E-12 TE-127M 2.124E+08 5.736E+07 5.088E+-07 6.072E+08 O.OOOE+OO 1.728E+08 O.OOOE+OO 2.532E+07 TE-129 O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+()l O.OOOE+OO TE-129M 2.148E+08 6.000E+-07 6.924E+o7 6.3l2E+u8 O.OOOE+OO 2.6l6E+08 O.OOOE+OO 3.336E+07 TE-131 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+IJO 0.000E+OO 0.000E+OO O.OOOE-1-00 O.OOOE >OO TE-131M 8.400E+01 2.904E+OI 5.976E+-Ol 2.808E+02 O.OOOE+OO 1.178E+03 O.OOOE+OO 3.096E+ol TE-132 2.544E+05 1.126E+o5 1.644E+05 1.045E+06 O.OOOE+OO l.134E+06 O.OOOE+OO l.356E+o5 1-130 3.636E-07 7.356E-07 8.IOOE--05 l.099E-06 O.OOOE+OO 3.444E-07 0.000E+()l 3.792E-07 Appendix I Ri Child Goat Meat

• Page 2 CJf J Page 9-184

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIX I R1 Child Dose Factors for use in the Gaseous Dose Calculations Age group: CHILD Pathway: Grs/Goat/Meat (GMEAT) Units: m 2 *nu*ern/yr / µCi/sec; I mrem/vr / u.Cilm' (H-3 C-14)

Nuclide Bone Liver Thvroid Kidnev Lun11 Gilli Skin Total Bodv 1-131 1.980E+06 l.992E+06 6.600E+08 3.276E+06 O.OOOE+OO I.776E+05 0.000E+OO l.135E+06 I-132 1.224E-59 2.25613-59 1.048E-57 3.456E-59 0.000E+OO 2.652E-59 0.000E+OO 1.038E-59 1-133 6.804E--02 8.424E-02 1.560E+Ol l.404E-Ol O.OOOE+OO 3.396E-02 O.OOOE* -00 3.192E--02 I-134 O.OOOE+OO 0.000E*HJO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO E-135 7.8!2E-!8  !.404E-l7 l.248E-!5 2.160E-17 O.OOOE+oo l.072E-!7 O.OOOE+OO 6.660E-18 CS-134 l.l06E+08 l.812E+08 O.OOOE+OO 5.628E+07 2.016E+07 9.792E+05 0.000E+OO 3.828E+07 CS-136 1.944E+06 5.352E+06 O.OOOE+OO 2.844E+06 4.248E+o5 l.884E+05 O.OOOE+OO 3.456E+06 CS-137 l.596E+08 l.536E+o8 O.OOOE-+-00 4.992E+07 1.800E+07 9.588E+o5 0.000E+OO 2.256E+07 CS-138 O.OOOE+OO O.OOOE+OO O.OOOE+oo 0.000E+OO 0.000E+OO O.OOOE+-00 0.000E+OO 0.000E+OO BA-139 O.OOOE+-00 O.OOOE+oo O.OOOE+OO O.OOOE+OO 0.000E+OIJ O.OOOE+OO 0.000E+OO O.OOOE+OO BA-140 5,256E+06 4.608E+03 O.OOOE+OO l.500E+03 2.748E+03 2.664E+06 0.000E+OO 3.072E+05 BA-141 O.OOOE+OO {l.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+oo O.OOOE+-00 O.OOOE+OO t O.OOOE+OO BA-142 0.000E+OO O.OOOE+OO O.UOOE+OO O.OOOE* OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO LA-140 6.708E--03 2.340E-03 O.OOOE+OO 0.000E+OO O.OOOE+oo 6.S28E+OI O.OOOE+OO 7.896E-04 LA-142 6.360E-93 2.028E-93 O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.020E-88 O.OOOE+OO 6.348E-94 CE-141 2.664E+03 l.332E+03 0.000E+OO 5.820E+02 0.000E+OO l.656E+06 0.000E+OO \.968E+02 CE-143 3.804E-03 2.064E+OO O.OOOE-+-00 8.652E-04 O.OOOE+oo 3.024E+-Ol O.OOOE+OO 2.988E~J4 CE-144 2.784E+05 8.712E+04 O.OOOE+OO 4.824E+04 O.OOOE+OO 2.268E+07 0.000E+OO l.488E+04 PR-143 4.008E+03 1.200E+03 O.OOOE+-00 6.5[6E+02 O.OOOE+oo 4.320E+-06 O.OOOE+OO 1.992E+02 PR-144 O.OOOE+OO O.OOOE+OO O.OOOE+OO OJJOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO ND-147 l.404E+03 1.136E+03 O.OOOE+OO 6.228E+02 O.OOOE+OO 1.&00E+-06 O.OOOE+-00 8.796E+OI W-187 3 852E-03 2.280E-03 O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.204E-01 0.000E+OO l .024E--03 NP-239 5.112E-02 3.6726-03 O.OOOE+oo l.062E-02 O.OOOE+OO 2 712E+o2 O.OOOE+OO 2.580E--03 Appendix I Ri Child Goat Meat - Page 3 of3 Page 9-185

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nucl.oar Station Offsite Dose Ca[culat,on Manual (ODCM)

APPENDIX I R1Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m 2*mrem/yr / µCi/sec; mrem/vr / u.Ci/m3 (H.J, C-14\

Nuclide Bone Lh1er Thy roid Kidney LURI? Gilli Skin Total Body H-3 O.OOOE+OO 4.0IOE+03 4.0lOE+-03 4.0IOE+03 4.0IOE+03 4.0IOE+03 O.OOOE+OO 4.0IOE+03 C-14 2.450E+05 4.9!08+04 4.910E+-04 4.9108+04 4.9\0E+04 4.910E+04 O.OOOE+OO 4.9IOE+04 NA-24 3.730E+05 3.730E+05 3.730E+05 3.730E+05 3.730E+05 3.730E+05 0.000E+OO 3.730E+05 P-32 3.370E+09 \.580E+08 0.000E+OO O.t)OOE+OO O.OOOE+OO 9.3108+07 O.OOOE+OO \.300E+08 CR-5 1 O.OOOE+OO O.OOOE+OO 6.500E+o4 l.780E+04 U90E+05 6.210E+06 O.OOOE+OO I.I 70E+05 MN-54 O.OOOE+OO 6.650E+08 O.OOOE+OO l .860E+08 O.OOOE+OO 5.580E+08 O.OOOE+OO 1.770E+08 MN-56 O.OOOE+OO l.860E+OI 0.000E+-00 2.250E+OI O.OOOE+oo 2.700E+03 O.OOOE+oo 4.200E+OO FE-55 8.010E+08 4.250E+o8 O.OOOE+-00 O.OOOE+OO 2.400E+08 7.870E+07 O.OOOE+oo 1.320E+08 FE-59 3.980E+08 6.4308+08 0.000EHJO 0.000E+OO l.8608+08 6.700E+08 O.OOOE+OO 3.2008+08 CO-58 0.0008+00 6.440E+07 0.0008+-00 0.0008+00 O.OOOE+OO 3.760E+08 0.0008+00 1.9708+08 C0-60 O.OOOE+OO 3.780E+o8 0.0008+00 0.0008+00 0.0008+()() 2.1008+09 O.OOOE+OO 1.1208+09 Nl-63 3.9508+10 2.1108+09 O.OOOE+oO 0.0008+00 Q.OOOE+OO l .420E+08 0.0008+00 1.3408+09 NI-65 1.050E+02 9.8908+00 O.OOOE.+00 0.0008+00 O.OOOE+OO l.2 \ 0E+03 O.OOOE ,00 5.770E+OO CU-64 0.0008+00 J.\OOE+04 O.OOOE+OO 2.6608+04 0.0008+00 5.1608+05 0.0008+00 6.640E+03 ZN-6 5 8.130E+08 2.\60E+09 O.OOOE+OO 1.3608+09 0.000E+OO 3.800E+08 O.OOOE+OO l.350E+09 ZN-69 9.490E-06 1.3708-05 0.0008-t-OO 8.3208-06 0.0008+00 8.640E-04 0.0008+00 1.2708-06 BR-83 O.OOOE+OO 0.0008+00 0.0008+-00 0.0008+00 O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.370E+OO BR-84 0.000E+OO 0.0008+-00 0.0008+00 O.OOOE+OO O.OOOE+OO 0.000E+OO 0.0008+00 3.820E- II BR-85 O.OOOE+OO 0.0008+00 0.0008+00 O.OOOE+OO 0.0008+00 0.000E+OO O.OOOE+OO O.OOOE+OO RB-86 0.0008+00 4.5208+08 O.OOOE+OO 0.0008+00 0.0008+00 2.9108+07 O.OOOE+OO 2.780E+08 RB-88 0.0008+00 4.380E-22 0.0008-tOO 0.0008+00 0.000E+OO 2. 1508-23 0.0008+00 3.0408-22 RB-89 O.OOOE+OO 4.610E-26 O.OOOE+oO 0.0008+00 0.000E+OO 4.020E-28 O.OOOE+OO 4.090E-26 SR-89 3.6008+\ 0 0.0008+00 0.0008-tOO 0.0008+00 O.OOOE+OO 1.3908+09 0.0008+00 l.030E+09 SR-90 1.2408+12 0.0008+00 0.0008+00 O.OOOE+OO 0.0008+00 1.6708+10 0.0008+00 3.150E+l1 SR-91 5.2408+05 0.0008+-00 0.0008+00 0.0008+00 0.0008+00 1.1608+06 0.0008+00 1.9808+04 Appcodix[Ri Oiild Vi:gctat£ort - Paget of3 Page 9-186

Attachme nt 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIX I R1 Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m 2*mnim/yr / µCi/sec; mrem/yr / 1>Ciim' (H.3, C-14)

Nuclide Bone Liver Thvroid Kidney Lun!! Gilli Skin TotalBodv SR-92 7.280E+02 0.000E+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO l.380E+04 O.OOOE+OO 2.920E+01 Y-90 2.310E+04 0.000E+OO O.OOOE+-00 0.000E+OO 0.000E+OO 6.570E+07 O.OOOE+OO 6.180E+02 Y-91 l.860E+07 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.480E+09 O.OOOE+OO 4.990E+05 Y-91M 8.910E-09 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 1.740E-05 O.OOOHOO 3.240E-IO Y-92 l.580E+OO 0.000E+OO O.OOOE+-00 0.000E+OO O.OOOE+OO 4.580E+04 0.000E+OO 4.S30E--02 Y-93 2.930E+02 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.370E+06 O.OOOE+OO 8.040E+OO ZR-93 3.860E+06 8.480E+05 O.OOOE+-00 l.210E+06 O.OOOE+OO 8.850E+08 0.000E+OO 7.550E+05 ZR-97 5.700E+02 8.240E+ol O.OOOE-HlO 1.180E+02 O.OOOE+OO 1.250E+07 O.OOOE+OO 4.860E+01 NB-95 4.I IOE+OS l.600E+05 0.000E+-00 1.500E+05 O.OOOE+OO 2.960E+08 0.000E+OO 1.140E+05 M0-99 0.000E+OO 7.710E+06 O.OOOE+-00 l.650E+07 O.OOOE+OO 6.380E+06 O.OOOE+OO l.910E+06 TC-99M 4.710E+OO 9.230E+oo O.OOOE+-00 l.340E+02 4.690E+OO 5.260E+03 0.000E+OO 1.530E+02 TC-101 l.4 10E-30 1.470E-30 O.OOOE+OO l 2.SIOE-29 7.780E-31 4.680E-30 O.OOOE+OO 1.870E-29 RU-103 l.530E+07 O.OOOE+OO O.OOOE+OO 3.860E* 07 O.OOOE+OO 3.970E+08 O.OOOErOO 5..900E+06 RU-105 9.160E+Ol O.OOOE+OO O.OOOE+-00 8.050E+02 O.OOOE+OO 5.980E+04 O.OOOE+OO 3.320E+Ol RU-106 7.450E+08 0.000E+oo O.OOOE-HlO I.OIOE+09 O.OOOE+OO 1.1601:l+IO O.OOOE+OO 9.300E+07 AG-llOM 3.21 0E+07 2.170E+07 O.OOOE+OO 4.040E+07 O.OOOE+OO 2.580E+09 O.OOOE+OO l.730E+07 TE-125M 3.510E+08 9.500E+07 9.840E+07 O.OOOE+OO O.OOOE+OO 3.380E+08 O.OOOE+OO 4.670E+07 TE-127 9.850E+03 2.650E+o3 6.8l0E+-03 2.800E+04 O.OOOE+OO 3.850E+05 O.OOOE+OO 2.I IOE+03 TE-127M l.320E+09 3.560E+08 3.160E+-08 3.770E+09 O.OOOE+OO l.070E+09 O.OOOE+OO 1.570E+08 TE-129 l .320E-03 3.690E-04 9.430E-04 3.870E-03 O.OOOE+OO 8.230E-02 O.OOOE+OO 3.140E-04 TE-l29M 8.410E+08 2 350E+08 2.7!0E+-08 2.470E+o9 O.OOOE+OO l.030E+09 0.000E+OO l.3IOE+08 TE-131 2 570E-15 7.830E-16 l.960E-15 7.770E-15 O.OOOE+OO l.350E-14 O.OOOE+OO 7.640E-16 TE-lJ!M l.540E+06 5.330E+05 1.IOOE+06 5.160E+06 O.OOOE+OO 2.160E+07 0.000E+OO 5.680E+05 TE-132 7.000E+06 3. IOOE+-06 4.510E+-06 2.880E+07 O.OOOE+OO 3.120E+07 O.OOOE+OO 3.740E+06 l-130 6.160E+05 l.240E+o6 l .370E+08 l.860E+06 O.OOOE+OO 5.820E+05 0.000E+OO 6.410E+05 Appendix: f Ri Qiild Vegetation~ Page 2 of 3 Page 9-187

Attachm*e nt 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offs1te Dose Calculation Manual (ODCM)

APPENDIX I R1 Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m2 *m1*em/yr / µCi/sec; mrem/vr / u.Ci/m3 (ff.J, C-141 Nuclide Bone Liver Thvroid Kidney Lun!!' Gilli Skin Total Bodv 1-131 1.430E+08 l.440E+08 4.750E+IO 2.360E+08 O.OOOE+OO 1.280E+07 O.OOOE+OO 8.170E+07 1-132 9.220E+Ol 1.6908+02 7.860E+03 2.5908+02 0.0008+00 1.9908+02 O.OOOE+OO 7.790E+Ol I-133 3.530E+06 4.370E+06 8.IIOE+08 7.280E+06 O.OOOE+OO l.760E+-06 0.000E+OO l.650E+06 1-134 l.550E-04 2.880E-04 6.620E-03 4.400E-04 O.OOOE+OO l.9IOE-04 O.OOOE+OO l.320E-04 I-135 6.260E+04 1.l30E+05 9.970E+06 l.730E+05 O.OOOE+OO 8.580E+04 O.OOOE+OO 5.330E+04 CS-134 l.600E+l0 2.630E+10 O.OOOE+OO 8150E+09 2.930E+09 l.420E+08 O.OOOE+OO 5.550E+09 CS-136 8.240E+07 2.2708+08 O.OOOE+OO 1.210E+08 l.800E+07 7.960E+-06 0.0008+00 l.470E+08 CS-137 2.3908+!0 2.290E+IO O.OOOE+OO 7.460E+09 2.6808+09 1.4308+08 O.OOOE+OO 3.380E+09 CS-138 6.570E-11 9.130E-ll O.OOOE+OO 6.4308-ll 6.920E- 12 4.210E-l l O.OOOE+OO 5.790E- l l BA- 139 4.950E-02 2.640E-05 O.OOOE+oo 2.310E-05 1.560E-05 2.860E+OO O.OOOE+OO l.440E-03 BA-140 2.770E+08 2.420E+05 O.OOOE+OO 7.890E+04 l.450E+05 l.400E+08 0.000E+OO 1.610E+07 BA-141 l ,990E-21 l.l lOE-24 O.OOOE+OO 9.620E-25 6.530E-24 l.l30E-2l , O.OOOE+OO 6.460E-23 BA-142 9.930E-39 7.ISOE-42 OOOOE+OO 5.7808-42 4.2<10E-42 UOOE-40 O.OOOE+OO 5.540E-40 LA-140 3.250E+03 l.l30E+03 O.OOOE+OO O.OOOE+OO O.OOOE+oo 3.160E+o7 O.OOOE+OO 3.820E+02 LA-142 3.360E-04 1.070E-04 O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.120E+OI 0.000E+OO 3.350E-05 CE-1 4 1 6.560E+05 3.270E+o5 O.OOOE+OO 1.430E+05 0.000E+OO 4.080E+08 O.OOOE+OO 4.860E+04 CE-143 l.720E+03 9.310E+o5 0.000E+oO 3.910E+02 O.OOOE+OO l.360E+o7 O.OOOE+oo J.350E+02 CE- 144 l.270E+08 3.980E+07 0.000E+OO 2.2IOE+07 O.OOOE+OO l.040E+IO O.OOOE+OO 6.780E+06 PR-143 1.460E+05 4.370E+04 O.OOOE+OO 2.370E+04 O.OOOE+OO l.570E+08 O.OOOE+OO 7.230E+03 PR-1 44 5.380E-26 l.660E-26 O.OOOE+OO 8.800E-27 O.OOOE+OO 3.580E-23 O.OOOE+OO 2.710E-27 ND- 147 7.150E+<)4 5.790E+04 O.OOOE-t-00 3.180E+04 O.OOOE+OO 9.170E+07 O.OOOE+OO 4.480E+03 W-187 6.430E+04 3.810E 104 O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.350E+06 O.OOOE H)O 1.710E+04 NP-239 2.560E+03 l.840E+02 0.000E+oo 5.310E+02 0.000E+OO l.360E+o7 O.OOOE+OO 1.290E+02 Appendix I Ri Oiild Vegetation* Page 3 of l Page 9-188

• - Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation J:vlanool (ODCM)

APPENDIX I R1Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr I µCi/m3 Nuclide Bone Live1* Thvroid Kidnev Luni? Gilli Skin Total Bodv H-3 0.000E+OO l.1 20E+o3 l.120E+03 l.1 20E+03 t.l 20E+-03 1.120E+03 O.OOOE+OO 1.120E+03 C-14 3.590E+04 6. 730E+-03 6.730E+o3 6.730E+03 6.730E+<J3 6.730E+03 O.OOOE+OO 6.730E+03 NA-24 l.6!0E+04 l.610E+04 1.610E+04 l.610E+04 l.610E+04 1.610E+04 O.OOOE+OO 1.610E+04 P-32 2.600E+06 1.1 40E+-05 O.OOOE+oo O.OOOE+OO 0.000E+-00 4.220E+-04 O.OOOE+oo 9.880E+04 CR-51 O.OOOE+OO 0.000E+OO 8.550E+-01 2.430E+Ol l.700E+04 1.080E+03 0.000E+OO 1.540E+02 MN-54 0.000E+oo 4.290E+04 O.OOOE+OO l.OOOE+04 l.580E+06 2.290E+04 O.OOOE+OO 9.5l0E+03 MN-56 O.OOOE+OO 1.660E+OO O.OOOE-t-00 1.670E+OO l.310E+-04 L230E+-05 O.OOOE+OO 3.120E-OI FE-55 4.740E+-04 2.520E+04 O.OOOE+oo O.OOOE+OO 1.llOE+05 2.870E+03 O.OOOE+-00 7.770E+03 FE-59 2.070E+04 3.340E+-04 O.OOOE+-00 O.OOOE+OO 1.270E+06 7.070E+04 O.OOOE+OO 1.670E+04 CO-58 O.OOOE+OO 1.770E+OJ O.OOOE+OO O.OOOE+OO l.l lOE+06 3.440E+04 0.000E* OO 3.160E+03 CO-60 O.OOOE+OO l.310E+-04 O.OOOE+-00 O.OOOE+OO 7.070E+06 9.620E+04 O.OOOE+OO 2.260E+04 NI-63 8.210E+05 4.620E+-O-l O.OOOE+-00 O.OOOE+OO 2.750E+-05 6.330E+03 O.OOOE+OO 2.800E+04 Nl-65 2.990E+oo 2.960E-OI O.OOOE+oo O.OOOE+OO 8.180E+03 8.400E+04 O.OOOE+OO 1.640E-OI CU-64 0.000E+OO 1.990E+OO O.OOOE+-00 6.030E+oo 9.580E+03 3.670E+04 O.OOOE+OO l.070E+OO ZN-65 4.260E+04 l.130E+05 O.OOOE+-00 7.140E+04 9.950E+o5 l.630E+-04 O.OOOE+OO 7.030E+04 ZN-69 6.700E-02 9.660E-02 O.OOOE+oO 5.850E-02 l 420E+03 l.020E+04 O.OOOE+OO 8.920E-03 BR-83 0.000E+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 4.740E+02 BR-84 O.OOOE+OO O.OOOE+oO O.OOOE+-00 O.OOOE+OO o.roJE+oo O.OOOE+OO O.OOOE+OO 5.480E+02 BR-85 O.OOOE+OO 0.<JOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+-00 O.OOOE+-00 O.OOOE+OO 2.530E+Ol RB-86 O.OOOE+OO l.980E+05 O.OOOE+-00 O.OOOE+OO O.OOOE+OO 7.990E+03 O.OOOE+OO l.140E+05 RB-88 O.OOOE+OO 5.620E+02 O.OOOE<*<JO O.OOOE+OO O.OOOE+OO 1.7'.?0E+OI O.OOOE+OO 3.660E+02 RB-89 O.OOOE+oo 3.450E+02 O.OOOE+<)O O.OOOE+OO O.OOOE+oo l.890E+OIJ O.OOOE+OO 2.900E+02 SR-89 5.990E+05 0.000E+OO 0.000E+-00 O.OOOE+OO 2.l60E+06 1.670E+05 O.OOOE+OO 1.720E+04 SR-90 l.01 0E+08 0.000E+OO O.OOOE+-00 O.OOOE+OO l.480E+07 3.430E+05 O.OOOE+OO 6.440E+06 SR-91 l.21 0E+02 O.OOOE+OO O.OOOE+-00 O.OOOE+OO 5.330E+04 l.740Er05 O.OOOE+OO 4.590E+-00 Appendhc I Ri Oiiht lnha.fltim

• Page Lofl Page 9-189

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offoite Dose Calculation Manual (ODClvl)

APPENDIX I R1Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Live1* Thvroid Kidnev Lunl! Gilli Skin Total Bodv SR-92 l.3l0E+0l 0.000E+OO 0.0OOE+00 0.0OOE+OO 2.400E+04 2.420E+05 0.0OOE+OO 5.250E-O l Y-90 4.1I0E+03 0.000E+o0 O.0OOE+o0 0.000E+OO 2.620E+05 2.680E+05 0.000E+oO l.lLOE+o2 Y-91 9.140E+05 0.0008+00 0.OOOE+o0 0.000E+OO 2.6308+06 l .840E+05 O.0OOE+OO 2.4408+04 Y-91M 5.070E-0l 0.OO0E+oo 0.OOOE+o0 0.000E+OO 2.810E+03 l.720E+o3 0.000E+OO l.840E-02 Y-92 2.030E+0l 0.0008+00 0.000E+O0 0.000E+OO 2.390E+04 2.390E+05 0.0008+00 5.810E-Ol Y-93 l.860E+02 0.OOOE+oo 0.OOOE+00 0.000E+OO 7.440E+04 3.880E+05 0.0OOE+oo 5.1l0E+00 ZR-95 l.900E+05 4.180E+04 0.OOOE+o0 5.960E+04 2.230E+06 6.II0E+04 O.0OOE+OO 3.700E+o4 ZR-97 l.880E+o2 2.720E+0l 0.0OOE+o0 3.880E+0l l.130E+05 3.510E+05 O.0OOE+OO l.600E+ol NB-95 2.350E+04 9.180E+o3 0.OOOE+-00 8.620E+03 6.140E+05 3.700E+04 0.0OOE+OO 6.550E+03 M0-99 0.000E+OO 1.7208+02 O.OO<lE+00 3.920E+02 l.350E+05 1.270E+05 0.000E!-00 4.260E+0 l TC-99M l.780E-03 3.480E-03 O.OOOE+-00 5.070E-02 9.510E+02 4.810E+03 0.0OOE+OO 5.770E-02 TC-101 8.IO0E-05 8.SI0E-05 ,0.OOOE+o0 l.450E-03 5.850E+02 l.630E+O I O.0OOE+OO l.080E-03 RU-103 2.790E+03 0.000E+OO 0.000E+O0 7.030E+03 6.620E+05 4.480E+04 0.0OOE+OO l.070E+03 RU- 105 l.530E+00 0.000E+00 O.OOOE+o0 1.340E+OO l.590E+04 9.950E+04 O.0OOE+OO 5.550E-Ol RU-106 l.360E+05 0.OO0E+00 0.OOOE+-00 l .840E+05 l.430E+07 4.290E+05 . 0.0OOE+OO l.690E+04 AG-llOM 1.6908+04 l .\40E+04 0.0OOE+-00 2.120E+04 5.480E+06 l.0OOE+05 0.0OOE+OO 9.140E+03 TE-125M 6.730E+o3 2.330E+o3 l.920E+-03 0.000E+OO 4.770E+05 3.380E+04 0.0OOE+OO 9.140E+02 TE-127 2.770E+OO 9.510E-01 l.960E+-O0 7.070E+OO l.OOOE+04 5.620E+04 0.0OOE+OO 6.IOOE-01 TE-127M 2.490E+04 8.550E+03 6.070E+o3 6.360E+04 l.480E+06 7.140E+04 0.0OOE+oo 3.020E+03 TE-129 9.7700-02 3.SOOE-02 7.140E-02 2.570E-01 2.930E+03 2.550E+04 0.0OOE+OO 2.380E-02 TE-129M 1.920E+rJ4 6. 840E+03 6.330E+o3 5.0308+04 l.760E+06 l.820E+05 0.000E+OO 3.040E+03 TE- 131 2.170E-02 8.440E-03 l.700E-02 5.880E-02 2.050E+03 l.330E+o3 O.0OOE+oo 6.590E-03 TE-131M l .340E+02 5.920E+Ol 9.770E+ol 4.000E+02 2.060E+05 3.080E+05 0.0OOE+OO 5.070E+0l TE-132 4.810E+o2 2.720E+02 3.170E+o2 l.770E+03 3.770E+05 l.380E+05 0.0OOE+OO 2.630E+02 1-130 8.180E+03 l .640E+04 l.850E+-06 2.450E+04 0.000E+OO 5.11 0E*t-03 0.0OOE+OO 8.440E+03 Appendix I Ri Olild lnhalatim - Page 2 of l Page 9-190

Attachment 9 **

Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12 /31/2018 Oconee Nuclear Station Offaite Dose Calculation Manual (ODCM)

APPENDIX I R1Chilli Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Live1* Thyroid Kidne" Lon!! Gilli Skin Total Body I-13 1 4.810E+04 4.810E+04 1.620E+o7 7.880E+04 O.OOOE+OO 2.840E+03 0.000E+oo 2.730E+04

(-132 2.120E+03 4.070E+o3 l.940E+o5 6.250E+03 O.OOOE+OO 3.200E+o3 O.OOOE+oo 1.880E+03 I-133 1.660E+04 2.030E+04 3.850E+06 3.380E+04 O.OOOE+OO 5.480E+03 O.OOOE+OO 7.700E+03 I-134 l.170E+03 2.l60E+03 5.070E-t-04 3.300E+o3 0.000E+oo 9.550E+o2 0.000E+OO 9.950E+02 I-135 4.920E+03 8.730E+03 7.920E+o5 l.340E+04 O.OOOE+OO 4.440E+03 0.000E+OO 4.140E+03 CS-134 6.510E+o5 l.OIOE+o6 O.OOOE+OO 3.300E+05 l.210E+05 3.850E+03 O.OOOE+OO 2.250E+05 CS-136 6.510E+04 I.710E+05 O.OOOE+-00 9.550E+04 1.450E+04 4.180E+03 0.000E+OO l.160E+05 CS-137 9.060E+05 8.250E+05 O.OOOE+oO 2.820E+05 1.040E+o5 3.620E+03 O.OOOE+OO l.280E+05 CS-138 6.330E+02 8.400E+02 O.OOOE+OO 6.220E+02 6.SIOE+OI 2.700E+o2 0.000E+OO 5.550E+02 BA-139 l .840E+OO 9.840E-04 O.OOOE+oO 8.620E-04 5.770E+03 5.770E+04 O.OOOE+OO 5.360E-02 BA-140 7.400E+04 6.480E+OI O.OOOE+OO 2.llOE+OI l.740E+o6 l.020E+05 O.OOOE+oo 4.330E+03 BA-141 1.960E-Ol 1.0905-04 O.OOOE+OO 9.470E-05 2.920E+o3 2.750E+o2 O.OOOE+OO. 6.360E-03 BA--142 5.000E-02 3.600E-05 O.OOOE+oo 2.910E--05 l.640E+03 .2.740E+OO O.OOOE+OO 2.790E-03 LA-140 6.440E+02 2.250E+02 O.OOOE+OO O.OOOE+OO 1.830E+o5 2.260E+o5 O.OOOE+OO 7.550E+OI LA-142 l.300E+OO 4.IIOE--01 O.OOOE+OO O.OOOE+OO 8.700E+03 7.580E+o4 O.OOOE+OO l.290E-OI CE-141 3.920E+04 1.950E+04 O.OOOE+oo &.550E+03 5.440E+05 5.660E+04 O.OOOE+OO 2.900E+03 CE-143 3.660E+02 l.990E+02 O.OOOE+OO 8.360E+Ol l.l50E+05 1.270E+05 O.OOOE+OO 2.870E+OI CE-144 6.770E+06 2.120E+o6 0.000E+oO l.l 70E+06 l.200E+07 3.880E+o5 O.OOOE+OO 3.6IOE+05 PR-143 l.850E+04 5.550E+03 O.OOOE+OO 3.000E+03 4.330E+o5 9.730E+o4 O.OOOE+OO 9.l40E+02 PR-144 5.9600-02 l.850E-02 O.OOOE+OO 9.770E-03 l.570E+03 l.970E+02 0.000E+OO 3.000E-03 ND-147 1.080E+04 8.730E+03 O.OOOE+{l() 4.810E+03 3.280E+05 8.2l0E+04 0.0001.l+O() 6.810E+02 W-187 I.630E+OI 9.660E+OO O.OOOE-HlO O.OOOE+OO 4.IIOE+o4 9.IOOE+o4 O.O(IOE+oO 4.330E+OO NP-239 4.660E+02 3.340E+OI O.OOOE+-00 9.730E+OI 5.8IOE+04 6.400E+04 O.OOOE+OO 2.350E* OI Appendix I Ri ClJifd lnhalatioo

• Page 3 of l Page 9-191

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offs,te Dose Calculation 1-1anual (ODCJ\,{)

APPENDIX I R1Child Dose Factors for use in the Gaseous Dose Calculations Agegmup: CHILD Pathway : Gmund Plane Deposition (GPD) Units: m2 *nu-em/yr / µCl/sec Nudide Bone Liver Thyroid Kidney Lune Gilli Skin Total Bod y H-3 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO C-14 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oO NA-24 l.l90E+07 1.190E+07 1.190E+07 l.190E+07 l.l90E+07 l.190E+07 l.390E+07 l.190E+07 P-32 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E*HJ6 4.660E+06 5.510E+06 4.660E+06 MN-54 l.390E+09 l .390E+09 l.390E+09 l.390E+09 l.390E+09 l.390E+09 l.630E+09 l.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+o5 FE-55 O.OOOE+oO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO FE-59 2.730E+08 2.730E+08 2.730E+o8 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+o8 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+l 0 2.150E+JO 2.150E+10 2.ISOE+lO 2.150E+l0 2.150E+IO 2.530E+10 2.ISOE+ IO NI-63 0.000E+OO 0.000E+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO NI-65 2.970E+05 2.970E+05 2.9JOE+o5 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 H70E+o8 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 O.OOOE+OO O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+OJ 4.870E+03 4.870E+03 7080E+OJ 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+-05 2.030E+05 2.030E+05 2.030E+o5 2.360E+05 2.030E+05 BR-85 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+oo 0.000E+OO RB-86 8.990E+06 8.990E+06 8.990E+o6 8.990E+06 8.990E+06 8.990E+06 l.030E+07 8.990E+06 RB-88 3.310E+04 3.310E+04 3.3lOE+;.l4 3.310E+04 3.310EHJ4 3.3l0E+04 3.780E+04 3.310E+04 RB-89 l.230E+05 l.230E+05 l .230E+05 l.230E+05 l.230E+05 l.230E+05 l.480E+05 L230E+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 O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO SR-91 2.150E+06 2.150E+06 2.150Et06 2.l 50E+06 2.l50E+06 2.ISOE* -06 2.5 10E+06 2.150E+06 Appendix[ Ri OlildGround Plane Deposition - P:igc 1 of3 Page 9-192

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offaitc Dose Calculation Manual (ODCM)

APPENDIX I R1 Chiltl Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Ground Plane Deposition (GPO) Units: m2*nu-em/yr / µCl/sec Nuclide Bone Liver Thyroid Kidney Lune Gilli Skin TotalBodv SR-92 7.770E+05 7.770E+o5 7.TT0E+o5 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+o3 4.490E+o3 4.490E+03 4.490E+03 4.490E+03 5.3LOE+03 4.490E+03 Y-91 l.070E+06 l.070E+06 1.070E+o6 l.070E+06 1.070E+06 1.070E+06 l.2l0E+06 l.070E+06 Y-91M l.0OOE+05 I.OOOE+o5 l.OOOE+o5 l.0OOE+05 l.OOOE+05 l.OOOE+05 l.160E+05 l.0OOE+05 Y-92 l.800E+05 l.800E+05 l .800E**05 l.800E+05 l.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 l.830E+o5 l.830E+05 l.830E+o5 l.830E+05 l.830E+05 I.830E+05 2.5l0E+05 l.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+o8 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+o6 2.960E+06 2.960E+06 2.960E+06 3.440E+o6 2.960E+06 NB-95 J.370E+08 l .370E+o8 l.370E+o8 1.3708+08 1.370E+08 l.370E+08 l.6IOE+08 l.370E+08 M0-99 3.990E+06 3.990E

• 06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E H)5 3.990E+06 TC-99M l.840E+05 l.840E+05 1.840E+o5 l.840E+05 l.840E+05 l.840E+05 2.II0E+05 l.840E+05 TC-IOI 2.040E+04 2.040E+04 2.040E+o4 , 2.040E+04 2.040E+04 2.0406+04 2.260E+04 2.040E+04 RU-103 l.080E+08 l.080E+08 l .080E+08 1.080E+08 J.080E+08 l.080E+08 l.260E+o8 l.080E+08 RU-105 6.360E+05 6.3606+05 6.3606+-05 6.3606+05 6.360E+05 6.3606+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-ll0M 3.440E+09 3.4406+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.0106+09 3.440E+09 TE-125M l.550E+06 l.550E+06 l.550E+o6 l.550E+06 1.550E+06 l.550E+06 2.130E+06 l.550E+06 TE-127 2.980E+03 2.980E+o3 2.980E+03 2.980E+03 2.980E+03 2.980E+03 3.280E+o3 2.9806+03 TE-127M 9.160E+04 9.160E+04 9.160E+o4 9.160E+04 9.l60E+04 9.160E+04 l.080E+o5 9. l60E+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 1.980Ef07 l.9806+07 l.980E+07 I 9806+07 2.3!0E+07 1.980E+07 TE-131 2.9206+04 2.9206+04 2.9206+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE-131 M 8.030E+06 8.030E+06 8.030E+o6 8.030E+06 8.0306+06 8.030E+06 9.4606+06 8.0306* 06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+o6 4.2306+06 4.980E+06 4.230E+06 I-130 5.5lOE+06 5.510E+06 5.5I 0E+-06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.5IOE+06 Appendix: [ Ri d1ild GroW1dPlaneOcposirjon. Pagel of3 Page 9-193

Attach*ment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offs1tc Dose Calculatt0n Manual (ODCM)

APPENDIX I R1 Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Ground Plane Deposition (GPD) Units: m 2 *mrem/yr / µCi/sec Nu.elide Bone Live1* Thyroid Kidney Luni Gilli Skin Total Bodv I-131 l.720E+o7 1.7208+07 l.720E+07 L720E+07 1.720E+07 L720E+07 2.090E+07 1.720E+07 I- 132 l.250E+06 l.250E+o6 l.250E+06 l.250E+06 l.250E+06 l.250E+06 l.470E+06 l.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 f-134 4.470E+05 4.470E+o5 4.470E+05 4.470E+05 4.470E+o5 4.470E+05 5.300E+05 4.470E+05 I-135 2.530E+CJ6 2.530E+06 2.530E+o6 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 l.5 10E+08 l.5I0E+08 l.5 10E+o8 l.5l0E+08 l.510E+08 l.5l0E+o8 l.7 10E+08 l. 510E+08 CS-137 l.030E+ I0 l.030E+!0 l.030E+I0 l.030E+IO l.030E+I0 l.030E+IO l.200E+I0 L030E+ l0 CS-138 3.590E+05 3.590E+o5 3.590E+o5 3.590E+05 3.590E+05 3.590E+05 4.IOOE+05 3.590E+05 BA-139 l.060E+05 l.060E+05 l.060E+05 l .060E+05 l.060E+05 l .060E+05 l.190E+05 l.060E+05 BA-140 2.050E+07 2050E+o7 2.050E+o7 2.050E+07 2.050E+o7 2.050E+07 2.350E+07 2.050E+07 BA-14 1 , 4.l70E+04 4.1?0E+Q.1 4.170E+o4 4.l70E+04 4.170E+o4 4.l 70E+o4 , 4.750E+04 4. l70E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.IIOE+04 4.490E+04 LA-1 40 l.920E+07 l.920E+07 I.920E+o7 I.920E+07 l.920E+07 l.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+o5 7.600E+05 7.600E+05 7.600E+o5 9.120E+05 7.600E+05 CE-141 1.370E+07 l.370E+07 l.370E+07 l.370E+07 l.370E+07 1.370E+07 1.540E+07 l.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.3IOE+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+o7 6.950E+o7 6.950E+o7 6.950E+o7 6.950E+07 8.040E+07 6.950E+07 PR-143 0.0OOE+OO 0.000E+oo 0.OOOE+oo 0.OO0E+OO 0.OOOE+oo 0.000E+oo 0.000E+OO 0.OOOE+OO PR-144 l.830E+03 l.830E+03 l.830E+03 l.830E+03 l.830E+03 l.830E+03 2. I IOE+03 L830E+03 ND- 147 8.390E+06 8.390E+06 8.390E+-06 8.390E+06 8.390E+06 8.390E* 06 l.0 l0E+07 8.390E+06 W- .187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+o6 2.730E+06 2.350E+06 NP-239 1.710E+06 l.710E+06 1.710E+o6 l.710E+06 l.710E+06 l.7l0E+06 l .980E+06 l.7 10E+06 Appendix I Ri Child Ground Plane Deposition* Page 3 of3 Page 9-194

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Oconee Nuclear Station Off.site Dose Calculation Manwl (ODCM)

APPENDIXJ R1Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Cow/Milk (CMILk) Units: m2*ml-em/y1* / µCi/sec; mr,m/vr I uCilm' (H.J C-14)

Nuclide Bone Liver Thyroid Kidney Lunl!! Gilli Skin Total Body H-3 O.OOOE+OO 2.380E+03 2.380E+-03 2.380E+03 2.380E+03 2.380E+03 O.OOOE+OO 2.380E+03 C-14 2.260E+05 4.8206+04 4.820E+o4 4.820E+04 4.820E+04 4.820E+04 O.OOOE+OO 4.820Ef04 NA-24 1.540E+07 1. 540Et 07 1.S40E+07 1.S40E+07 I.S40E+07 l.540E+07 O.OOOE+OO 1.540E+07 P-32 1.600E+ l l 9.430E+09 O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.170E+09 O.OOOE+OO 6.210E+09 CR-51 O.OOOE+OO 0.000E+OO 1.050E+o5 2.300E+04 2.0SOE+05 4.700E+06 O.OOOE+OO 1.610E+05 MN-54 O.OOOE+-00 3.900E+07 O.OOOE+OO 8.640E+06 O.OOOE+OO  !.430E+07 O.OOOE+OO 8.840E+06 MN-56 O.OOOE+OO 3.IOOE.02 0.000E+oo 2.660E.02 O.OOOE+OO 2810E+OO O.OOOE+OO 5.340E-03 FE-55 l.350E+08 8.730E+07 O.OOOE+OO O.OOOE+OO 4.270E+07 l.l lOE+07 O.OOOE+OO 2.330E+07 FE-59 2.240E+08 3.920E+08 0.000E+oO O.OOOE+OO l.160E+08 l.870E+08 O.OOOE+OO 1.S40E+08 CO-58 0.000E+oo 2.420E+o7 0.000E+OO O.OOOE+OO O.OOOE+OO 6.040E+07 0.000E+oo 6.050E+07 C0-60 0.000E+OO 8.820E+07 O.OOOE+oo O.OOOE+OO O.OOOE+OO 2.IOOE+08 O.OOOE+OO 2.080E+08 NI-63 3.490E+IO ] .160E+09 O.OOOE+OO 0.000E+OO O.OOOE+O!) 1.070E+08 O.OOOE+oo l.210E+09 NI-65 3.510E+OO 3.9701:l-Ol 0.UOOE+OO O.OOOE+OO O.OOOE+OO 3.020E+Ol O.OOOE+OO l.SOOE-01 CU-64 O.OOOE+OO l .850E+oS O.OOOE+oO 3.140E+OS O.OOOE+oo 3.8IOE+06 O.OOOE+OO 8.590E+04 ZN-65 5.550E+09 l.900E+JO O.OOOE+OO 9.230E+09 O.OOOE+OO 1.610E+10 O.OOOE+OO 8.780E+09 ZN-69 2.020E-1I 3.6306-11 O.OOOE+OO l.510E-ll 0.000E+OO 2.960E-09 O.OOOE+OO 2.700E-12 BR-83 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo 0.000E+OO O.OOOE+oo 9.340E-01 BR-84 O.OOOE+OO O.OO<)E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.260E-22 BR-85 O.OOOE+OO O. OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO RB-86 O.OOOE+OO 2.230E+JO O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.690E+08 O.OOOE+OO l.JOOE+JO RB-88 O.OOOE+OO l.880E-44 O.OOOE+OO O.OOOE+OO 0.000E+OO l.830E-44 O.OOOE+oo 1.030E-4-l RB-89 O.OOOE+OO 3.290E-52 O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.120E-52 0.000E+OO 2.260E-52 SR-89 1.260E+IO O.OOOE+OO O.OOOE+-00 0.000E+OO O.OOOE+OO 2590E+08 0.000E+OO 3.610E+08 SR-90 1.220E+ I I O.OOOE+-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO l.520E+09 O.OOOE+OO 3.JOOE+IO SR-91 2.720E+05 O.OOOE+OO O.OOOE+oO O.OOOE+OO 0.000E+OO 3.220E+05 O.OOOE+OO 9.830E+03 Appendix J Ri Jnfimt Caw Milk

• Page I of3 Page 9-195

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXJ R1Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Cow/Milk (CMILk) Units: m2 *nll'em/yr / µCi/sec; mron,/vr / u.Ci/m3 (H-3 C-L41 Nuclide Bone Lh,er Thvroid Kidney LUDI! Gilli Skin Total Body SR-92 4.640E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 5.000E+O J O.OOOE+OO l.720E--OJ Y-90 6.8IOE+02 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 9.410E+05 O.OOOE+OO l.830E+OI Y-91 7.330E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO S.2SOE+06 O.OOOE+OO l.9SOE+03 Y-9IM S.670E-l 9 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO l.890E-15 O.OOOE+OO J.930E-20 Y-92 S.380E-04 O.OOOE+OO 0.000E+oO O.OOOE+OO O.OOOE+OO l.OJOE+-01 O.OOOE+OO l.510E--05 Y-93 2.160E+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO J.700E+04 O.OOOE+OO 5.870E--02 ZR-95 6.800E+03 l.660E+03 O.OOOE+oO l.790E+03 O.OOOE+OO 8.260E+05 O.OOOE+OO 1.180E+03 ZR-97 4.060E+OO 6.970E-Ol O.OOOE+oO 7.030E-Ol O.OOOE+OO 4.450E+-04 O.OOOE+OO 3.180E--01 NB-95 5.930E+05 2.440E+05 0.000E+oo 1.750E+05 O.OOOE+OO 2.060E+08 0.000E+OO l.4lOE+05 MO-99 O.OOOE+oO 2.080E+08 O.OOOE+oO 3.1IOE+08 O.OOOE+OO 6.850E+07 O.OOOE+OO 4.060E+07 TC-99M  : .750E+Ol 5.670E+Ol O.OOOE+oo 6. JOOE+o2 2.960E+O l l.650E+04 0.000E+OO 7.300E+02 TC-IOI 2.470E-59 3.l lOE-59 t O.OOOE+oo 3.700E-58 l.700E-59 5.280E-57 O.OOOE+OO 3.0SOE-5~

RU-103 8.,670E >03 O.OOOEtOO O.OOOE+OO 1.800E+04 O.OOOE+OO l.050E+05 . O.OOOE+OO 2.900E+03 RU-105 8.0SOE-03 O.OOOE+oO O.OOOE+oo 5.920E-02 O.OOOE+OO 3.200E+OO O.OOOE+OO 2.710E--03 RU-106 l .900E+05 0.000E+OO O.OOOE+OO 2.250E+05 O.OOOE+OO l.440E+06 O.OOOE+OO 2.380E+04 AG-IIOM 3.860E+08 2.820E+08 O.OOOE+OO 4.030E+08 0.000E+OO l.460E+IO O.OOOE+OO l.860E+08 TE-l25M l.510E+08 5.040E+07 5.070E+o7 O.OOOE+OO O.OOOE+OO 7.l 80E+o7 O.OOOE+OO 2.040E+07 TE-127 6.320E+03 2.120E+o3 5.140E+o3 l.540E+04 O.OOOE+OO l.330E+05 0.0OOE+oo l.360E+03 TE-l27M 4.210E+08 l.400E+08 l .220E+o8 l.040E+09 O.OOOE+OO l.700E+o8 O.OOOE+OO 5.IOOE+07 TE-129 2.720E-09 9.380E- IO 2.280E-09 6.770E-09 O.OOOE+OO 2.170E-07 O.OOOE+OO 6.350E-rn TE-129M 5.570E+08 l.910E+o8 2 140E+o8 1.390E+tl9 0.000E+OO 3.330E+08 O.OOOE+OO 8.580E+07 TE-131 3 430E-32 l.270E-32 3.il60E-32 8.760E-32 O.OOOE+OO l.380E-30 O.OOOE+OO 9.610E-33 TE-131M 3.380E+06 l.360E+06 2.750E+o6 9.350E+06 O.OOOE+OO 2.290E+07 O.OOOE+OO 1.120E+o6 TE-132 2. 1!OE+07 1.040E+07 l.540E+o7 6.530E+07 O.OOOE+OO 3.870E+o7 O.OOOE+OO 9.750E+06 1-130 3.550E+06 7.810E+o6 8.750E+o8 8.580E+06 O.OOOE+OO 1.670E+06 0.000E+OO 3.130E+06 Appendix J Ri Infunt Cow Milk* Page 2 of3 Page 9-196

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Off.site Dose Calculation J\Aanual (ODCM)

APPENDIXJ R1Infant Dose Factors for use in the Gaseous .Dose Calculations Agegroup: INFANT Pathway: Gt'S/Cow/Milk (CMILk.') Units: m2 *mrem/yr / 1,1Ci/sec; mrem/vr / uCllm' (H-3 C -14)

Nuclide Bone Liver Thyroid Kidney Lune Gilli Skin Total Body 1-131 2.720E+09 3.200E+09 1.050E+12 3.740E+09 O.OOOE+OO 1.140E+08 O.OOOE+OO 1.410E+09 I-132 J.430E+OO 2.900E+OO l.360E+-02 3.240E+OO O.OOOEI-()() 2.350E+OO O.OOOE+OO l.030E+OO I- 133 3.630E+07 5.280E+07 9.600E+09 6.210E+07 O.OOOE+OO 8.930E+-06 O.OOOE+OO l.550E+07 I-134 l.760E-ll 3.600E-ll 8.400E- 10 4.030E-11 O.OOOE+OO 3.720E-ll 0.000E+OO l.280E-ll I-135 l.l20E+05 2.230E+05 2.000E+07 2.490E+05 O.OOOE+OO 8.080E+04 O.OOOE+OO 8.l40E+04 CS-134 3.650E+!O 6.800E+IO O.OOOE+OO l.750E+IO 7.180E+09 l.850E+08 O.OOOE+OO 6.870E+09 CS-136 l.980E+09 5.810E+09 O.OOOE+OO 2.320E+09 4.740E+08 8.820E+o7 O.OOOE+OO 2.170E+09 CS-137 5.150E+ IO 6.020E+JO O.OOOE+oo l.620E+10 6.550E+09 1.880E+08 O.OOOE+OO 4.270E+09 CS-13& 8.390E-23 l.360E-22 0.000E+-00 6.SOOE-23 l.060E-23 2.ISOE-22 O.OOOE+OO 6.610E-23 BA-139 4.270E-07 2.830E-10 0.000E+OO l.700E-10 J.720E-IO 2.7100-05 0.000E+oo l.240E-08 BA-140 2.410E+08 2.410E+05 0.(lOOE+OO 5.720E+04 1.480E+o5 5.920E+07 0.000E+OO 1.240E+07 BA-141 3.930E-45, 2.690E-48 O.OOOE+OO l.620E-48 l.640E-48 4.SOOE-44 O.OOOE;t-00 l.240E-46 BA-142 2.430E-79 2.020E-82 O.OOOE+OO l.l60E-82 l.220E-82 1.000E-78 O.OOOE+OO l.200E-80 LA-140 4.0SOE+OI 1.600E+Ol O.OOOE+OO O.OOOE+OO O.OOOE+-00 l.880E+-05 O.OOOE+OO 4.1 IOE+OO LA-142 l.700E-IO 6.250E-l l O.OOOE+OO O.OOOE+OO O.OOOE+OO l .060E-05 O.OOOE+OO I.SOOE-11 CE-141 4.340E+04 2.640E+04 0.000E+OO 8.150E+03 O.OOOE+-00 l.370E+-07 O.OOOE+OO 3.l lOE+03 CE-143 3.970E+02 2.630E+05 O.OOOE+OO 7.670E+Ol O.OOOE+OO l.540E+-06 O.OOOE+OO 3.000E+Ol CE-144 2.330E+06 9.520E+05 O.OOOE+OO 3.850E+05 O.OOOE+OO 1.330E+08 O.OOOE+oo l.300E+05 PR-143 l.490E+03 5.550E+02 O.OOOE+OO 2.060E+02 O.OOOE+-00 7.840E+05 O.OOOE+OO 7.360E+OJ PR-144 5.690E-53 2.200E-53 O.OOOE+OO 7.980E-54 O.OOOE+OO 1.0200-48 0.000E+OO 2.870E-54 ND-147 8.8IOE+02 9.050E+02 O.OOOE+OO 3.490E+02 O.OOOE+-00 5.740E+o5 O.OOOE+oo 5.550E+Ol W-187 6.080E+04 4.230E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.480E+06 O.OOOEt*OO l.460E+04 NP-239 3.650E+Ol 3.260E+OO O.OOOE+OO 6.5IOE+OO O.OOOE+OIJ 9.430E+04 0.000E+OO 1.840E+OO Appendix J Ri Infunl Cow Milk~ Pitgc l of J Page 9-197

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offs1te Dose Calculation Manual (ODCM)

APPENDIXJ R1Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Goa~ lilk (GMILK) Units: m 2 *m1*ern/y1* / µCi/sec; mr<n1/yr / 1-<Cilm' (H.J C-14)

Nuclide Bone Liver Thvroid Kidnev Lunl! Gilli Skin TotalBodv H-3 O.OOOE+0(1 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4.860E+03 O.OOOE+OO 4.860E+03 C-14 2.260E+05 4.820E+04 4.820E+04 4.820E+04 4.820E+04 4.820E+04 O.OOOE*OO 4.820E+04 NA-24 1.850E+06 1.850E+06 1.850E+06 1.850E+06 l.850E+06 1.850E+06 O.OOOE+OO 1.850E+06 P-32 1.920E+II 1.130E+10 0.000E+OO O.OOOE+OO O.OOOE+OO 2.600E+09 O.OOOE+OO 7.460E+09 CR-51 O.OOOE+OO O.OOOE+OO 1.260E+04 2.760E+03 2.460E+o4 5.640E+05 O.OOOE+OO l.940E+04 MN-54 O.OOOE+OO 4.680E+06 O.OOOE+OO l.040E+06 O.OOOE+OO 1.720E+06 O.OOOE+OO 1.060E+06 MN-56 O.OOOE+OO 3.720E-03 O.OOOE+OO 3.190E-03 O.OOOE+oo 3.380E-O l O.OOOE+OO 6.4 10E-04 FE-55 1.760E+06 l.l30E+06 O.OOOE+OO O.OOOE+OO 5.550E+05 1.440E+05 O.OOOE+OO 3.030E+05 FE-59 2.920E+06 5.100E+06 0.000E+-00 0.000E+OO l.5l0E+06 2.430E+06 0.000E+OO 2.0 lOE+06 CO-58 O.OOOE+OO 2.910E+06 O.OOOE+OO O.OOOE+OO 0.000E+OO 7.250E+06 O.OOOE+OO 7.260E+06 C0-60 0.000E+OO 1.060E+o7 O.OOOE+<JO O.OOOE+OO O.OOOE+OO 2.520E+07 O.OOOE+OO 2.SOOE+O?

NI-63 4.l90E+09 2.590E+08 O.OOOE-lfJO O.OOOE+OO, O.OOOE+oo 1.290E+o7 O.OOOE+OO 1.450E+08 N l-65 4.210E-O I 4.760E-02 .O.UOOE+-00 0.000E+OO O.OOOE+OO 3.620E+OO O.OOOE+OO '.!.170E-02 CU-64 O.OOOE+OO 2.070E+04 O.OOOE+oO 3.500E+04 O.OOOE+OO 4.240E+05 O.OOOE+OO 9.570E+o3 ZN-65 6.660E+08 2.280E+09 O.OOOE+OO l.l 10E+09 O.OOOE+OO l.930E+09 O.OOOE+OO 1.050E+09 ZN-69 2.4'.!0E-12 4.360E-12 O.OOOE+oO l.8l0E-t'.! 0.000E+OO 3.550E-IO O.OOOE+OO 3.240E-13 BR-83 0.000E+O(I 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+<)O O.OOOE+oo l.1 20E~)1 BR-84 O.OOOE+OO O.OOOE+oo 0.000E+oO 0.000E+OO 0.000E+OO O.OOOE+OO 0.000E+OO 1.SlOE-23 BR-85 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO RB-86 O.OOOE+OO 2.6708+09 O.OOOE11)0 O.OOOE+OO 0.OOOE<*OO 6.830E+07 O.OOOE+OO l.320E+09 RB-88 O.OOOE+OO 2.250E-45 O.OOOE+OO 0.000E+OO O.OOOE+OO 2.190E-45 O.OOOE+OO 1.230E-45 RB-89 0.0008+00 3.940B-53 O.OOOE+OO 0.000E+OO 0.000E+OO I 340E-53 O.OOOE+OO 2 720E-53 SR-89 2.640E+10 O.OOOE+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO 5.430E+08 O.OOOE+Ol) 7.580E+08 SR-90 2.5508+1l O.OOOE+OO 0.0008+00 O.OOOE+OO 0.0008+00 3.1908+09 O.OOOE+OO 6.500E+10 SR-91 5.700E+05 O.OOOE+oo O.OOOE+oO 0.000E+OO O.OOOE+OO 6.750E+05 O.OOOE+OO 2.060E+04 Appendix 1 Ri Infant Goal Mile - Ptgc t of J Page 9-198

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)

APPENDIXJ RJ Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Goat/Milk (GMILK) Units: m 2*nu-em/yr / µ.Ci/sec; mrem/vr / u.Ciim' (H-3 C-Ul Nuclide Bone Liver Thvroid Kidnev I,un!l' GiUi Skin TotalBodv SR-92 9.750E+OO O.OOOE+OO O.OOOE+-00 O.OOOE+OO O.OOOE+OO 1.050E+02 0.000E+OO 3.620E~)I Y-90 8.170E t*Ol 0.000E+OO O.OOOEt-00 0.000E+OO O.OOOE+OO l.l30E+05 0.000E rOO 2.190E+OO Y-91 8.790E+03 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 6.300E+05 O.OOOEi-00 2.3-IOE+02 Y-91M 6.810E-20 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 2.270E-16 O.OOOE+OO 2.320E-21 Y-92 6.450E-05 0.000E+OO 0.000E+-00 O.OOOE+OO O.OOOE+oo l.230E+oo O.OOOE+OO l.8lOE-06 Y-93 2.590E-01 O.OOOE+-00 O.OOOE+OO 0.000E+OO O.OOOE+OO 2.040E+03 0.000E+OO 7.0SOE--03 ZR-95 8.170E+02 1.990E+02 O.OOOE+-00 2.l40E+o2 O.OOOE+OO 9.910E+04 O.OOOE+OO l.4LOE+02 ZR-97 4.870E-Ol 8.360E-02 0.000E+-00 8.430E-02 O.OOOE+OO 5.340E+03 O.OOOE+OO 3.820E-02 NB-95 7.120E+04 2.930E+04 O.OOOE+-00 2.lOOE+04 0.000E+OO 2.480E>07 0.000E+OO l.700E+04 M0-99 O.OOOE+oo 2.500E+o7 0.000E+oO 3.730E+07 0.000E+oo 8.220E+06 O.OOOE+OO 4.870E+06 TC-99M 3.300E+OO 6.SOOE+-00 O.OOOE+oO 7.320E+O l 3.SSOE+OO l.970E+03 0.000E+OO 8.760E+Ol TC-101 2.960E-60 3.730E-60 O.OOOE+pO 4.440E-59 2.030E-60 6.340E-58 O.OOOE+oo 3.690E-59 RU-103 l.040E+03 O.OOOE+OO O.OOOE+OO 2. l 70E-t03 O.OOOE+OO J.270E+04 O.OOOE+OO. 3.480E+02 RU-105 9.660E--04 O.OOOE+OO O.OOOE+oO 7.llOE-03 O.OOOE+-00 3.840E-01 O.OOOE+OO 3.250E-O-l RU-106 2.280E+04 O.OOOE+oo O.OOOE+OO 2.700E+04 O.OOOE+OO 1.730E+05 O.OOOE+OO 2.850E+03 AG-IIOM 4.630E+07 3.380E+07 0.000E+oO 4.830E+07 0.000E+OO 1.750E+09 0.000E+oo 2.240E+07 TE-125M l.8 lOE+07 6.050E+o6 6.090E+-06 O.OOOE+OO O.OOOE+-00 8.620E+06 O_OOOE+OO 2.450E+06 TE-127 7.580E+o2 2.540Et02 6.170E+-02 l.850E+03 0.000E+OO l.590E+04 O.OOOE+oo l.630E+02 TE-127M 5.050E+07 l.680E+07 l.460E+-07 1.240E+08 O.OOOE+-00 2.040E+07 O.OOOE+OO 6.120E+06 TE-129 3.260E-l0 l.130E-l0 2.740E-JO 8.130E-10 O.OOOE+OO 2.610E-08 O.OOOE+OO 7.620E-11 TE- 129M 6.690E+07 2.290E+07 2.570Ei-07 l.670E+-08 O.OOOE+OO 3.990E+07 O.OOOE+OO l.030E+07 TE-131 4.llOE-33 1.520E-33 3.670E-33 l.050E-32 O.OOOE+OO 1.660E-3I O.OOOE+OO I ISOE-33 TE-131M 4.050E+05 l .630E+05 3.3lOE+-05 l.l20E+06 O.OOOE+OO 2.750E+o6 O.OOOE+OO l.350E+05 TE-132 2.530E+06 l.250Et06 1.850E+06 7.840E+06 O.OOOE+OO 4.640E+06 O.OOOE+OO l.l 70E+06 1-130 4.260E+06 9.370Et06 l.050E+o9 l.030E+07 O.OOOE+OO 2.0l0E+06 0.000E+-00 3.760E+06 Appcndbc JRi Infant Goat Mi De

• Page 2 of 3 Page 9-199

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Off.site Dose Calculation Manual (ODCM)

APPENDIXJ R1Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Goa~ llik (GMILK) Units: m 2 *m1*em/yr / µCi/sec; mremlvr I µCi/m3 (H-3 C-141 Nuclide Bone Liver Thyroid Kidney Lune Gilli Skin Total Body 1-131 3.260E+09 3.850E+09 l.260E+12 4.490E+09 O.OOOE+OO l.370E+08 O.OOOE+OO l.690E+09 1-132 l.720E+OO 3.480E+OO l.630E+02 3.890E+OO O.OOOE+OO 2.820E+OO O.OOOE+OO 1.240E+OO 1- 133 4.350E+07 6.340E+07 l.150E+IO 7.450E+07 O.OOOE "OO 1.070E+07 O.OOOE+OO 1.860E+07 1-134 2.llOE-11 4.320E-11 l.OIOE-09 4.830E-II O.OOOE+OO 4.4700-11 O.OOOE+OO l.540E-II I-135 l.350E+05 2.680E+05 2.400E+07 2.990E+05 0.000E+OO 9.700E+o4 O.OOOE+OO 9.770E+04 CS-134 1.090E+ l l 2.0-IOE+l I O.OOOE+OO 5.250E+IO 2.l50E+l0 5.540E+08 O.OOOE+OO 2.060E+IO CS-136 5.930E+09 l.740E+IO O.OOOE+OO 6.950E+09 l.420E+09 2.650E+o8 O.OOOE+OO 6.5IOE+09 CS- 137 l.540E+ l l l.810E+ll O.OOOE+OO 4.850E+IO 1.960E+IO S.650E+08 O.OOOE+OO 1.280E+IO CS-138 2.520E-'.?2 4.090E-22 0.000E+OO 2.040E-22 3.190E-23 6.5400-22 O.OOOE+OO 1.980E-2:?

BA-139 5.l30E-08 3.400E-11 O.OOOE+oO 2.040E-11 2.060E-11 3.250E-06 0.000E+OO 1.480E-09 BA- 140 2.890E+07 2.890E+04 O.OOOE+OO 6.870E+03 1.780E+04 7. IOOE+06 0.000E+OO 1.490E+06 BA- 141 4.720E-46 3.230E-49 O.OOOE+fJO l.940E-49 l .960E-49 5.760E-i5 O.OOOE+OO l.490E-47 BA-142 ' 2.920E-80 2.430E-83 OOOOE+OO l .400E-83 l .470E-83 1.200!, *79 O.OOOE+OO 1.440E-81 LA- 1.40 4.860E+OO 1.920E+QO O.OOOE+OO 0.000E+OO O.OOOE+OO 2.250E+o4 O.OOOE+OO 4.930E-01 LA-142 2.040E-II 7.SOOE-12 O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.2700-06 0.000E+OO 1.790E-12 CE-1 4 1 5.200E+03 3.170E+03 O.OOOE+OO 9.790E+02 0.000E+OO l.640E+06 O.OOOE+OO 3.740E+02 CE-143 4.760E+OI 3.160E+04 O.OOOE+OO 9.200E+OO O.OOOE+OO l.840E+OS O.OOOE+OO 3.600E+OO CE-144 2.790E+05 l.140E+<JS 0.00UE+OO 4.620E+04 0.000E+OO 1.600E+07 O.OOOE+OO l.560E+04 PR-1 43 1.780E+02 6.670E+Ol O.OOOE+OO 2.480E+OI O.OOOE+OO 9.410E+o4 0.000E+OO 8.840E+OO PR-144 6.830E-54 2.640E-54 O.OOOE+c)O 9.570E-55 O.OOOE*1*00 1.230!, -49 O.OOOEtOO 3.440E-55 ND-1 47 1.060E+02 l .090E+02 O.OOOE+OO 4.l90E+Ol O.OOOE+OO 6.880E+o4 O.OOOE+OO 6.650E+OO W-187 7.300E+03 5.07QE+03 0.000E+OO 0.000E+OO 0.000E+OO 2.980E+05 O.OOOE!-00 l.750E+03 NP-239 4.380E+OO 3.910E-01 O.OOOE+OO 7.810E-0I O.OOOE+OO 1.130E+04 O.OOOE+OO 2.2IOE-01 Appendix J Ri [nfn:nt Goat Mi De - Page 3 cf J Page 9-200

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIXJ R1Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Inhalation (INHL) Units: mnm!yr I µCi/m3 Nuclide Bone Live,* Thyroid Kidney Lune Gilli Skin Total Body H-3 0.000E+OO 6.470E+o2 6.470E+o2 6.470E+02 6.470E+o2 6.470E+02 O.OOOE+OO 6.470E+02 C-14 2.650E+04 5.3\0E-t-03 5.310E+-03 5.3 IOE+o3 5.310E+03 5.310E+03 O.OOOE+oO 5.310E+03 NA-24 l .060E+04 1.060E+04 1.060E+04 l.060E+04 l.060E+04 1.060E+04 O.OOOE+OO 1.060E+04 P-32 2.030E+06 l.120E+o5 O.OOOE+-00 O.OOOE+OO O.OOOE+OO l.610E+04 O.OOOE+oo 7.740E+04 CR-51 0.000E+OO 0.000E+OO 5.750E*+-Ol 1.320E+OI l.280E+04 3.570E+02 0.000E+OO 8.950E+Oi MN-54 0.000E+OO 2.530E+04 O.OOOE+-00 4.980E+03 I.OOOE+06 7.060E+03 O.OOOE+OO 4.980E+03 MN-56 O.OOOE+OO l.540E+OO O.OOOE+OO 1.IOOE+oo l.250E+04 7.l70E+04 0.(IOOE+oo 2.210E-0I FE-55 l .970E+04 l.170E+04 O.OOOE+OO 0.000E+OO 8.690E+04 l.090E+03 O.OOOE+OO 3.330E+03 FE-59 1.360E+04 2.350E+o4 O.OOOE+-00 O.OOOE+OO 1.0IOE+06 2.480E+04 O.OOOE+OO 9.480E+03 C0-58 O.OOOE+OO I.220E+03 O.OOOE+OO 0.000E+OO 7.TTOE+OS I.I 10E+04 0.000E+OO l.820E+03 CO-60 O.OOOE+OO 8.020E+o3 O.OOOE+-00 O.OOOE+OO 4.SIOE+o6 3.l90E+04 O.OOOE+OO I.180E+04 Nl-63 3.390E+05 2.040E+04 O.OOOE+OO O.OOOE+OO 2.090E+o5 2.420E+03 O.OOOE+OO 1.160E+04 NI-65 2.390E+o0 2.840E-Ol O.OOOE+OO. O.OOOE+OO 8.120E+03 5.0IOE+04 O.OOOE+OO l.230E-OI CU-64 O.OOOE+OO l.880E+OO O.OOOE+OO 3.980E+OO 9.300E+03 1.500E+04 O.OOOE+OO 7.740E-OI ZN-65 l.930E+04 6.260E+o4 O.OOOE+-00 3.250E+04 6.470E+OS 5.l40E+o4 O.OOOE+oo 3.IIOE+04 ZN-69 5 390E-0'.! 9.670E-02 O.OOOE+oO 4.020E-02 I 470E+03 1 320E+04 0.000E+OO 7.180E-03 BR-83 O.OOOE+OO 0.000E+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO OOOOE+OO 3.810E+02 BR-84 0.000E+OO O.OOOE+OO O.OOOE+-00 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+{)() 4.CIOOE+02 BR-85 0.000E+OO 0.000E+OO O.OOOE+oO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+oo 2.040E+Ol RB-86 0.000E+oo 1.900E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO 3.040E+03 O.OOOE+OO 8.820E+04 RB-88 O.OOOE+OO 5.570E+02 O.OOOE+OO O.OOOE+OO 0. OOOE+UO 3.390E+02 O.UOOE+OO 2.870E+02 RB-89 O.OOOE+OO 3.210E+02 O.OOOE-H)O O.OOOE+OO O.OOOE+OO 6.820E+OI O.OOOE+OO 2.060E+02 SR-89 3.980E+05 0.000E+OO O.OOOE+OO O.OOOE+OO 2.030E+06 6.400E+04 O.OOOE+OO 1.l40E* 04 SR-90 4.090E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO l.l20E+07 l.3 l 0E+05 O.OOOE+OO 2.590E+06 SR-91 9.560E+01 O.OOOE+OO O.OOOEt-00 O.OOOE+OO 5.260E+04 7.340E+04 O.OOOE+OO 3.460E+OO Appc:ndix J R..i Infant Inhalation

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Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculation Manual (ODCM)

APPENDIXJ R1Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / 1,1Ci/m3 Nuclide Bone Liver Thyroid Kidney Lun2 Gilli Skin Total Body SR-92 I.OSOE+OI O.OOOE+OO O.OOOE+oO O.OOOE+OO 2.380E+04 l.400E+05 O.OOOE+OO 3.910E-OI Y-90 3.290E+03 O.OOOE+OO O.OOOE+oO O.OOOE+OO 2.690E+05 1.040E+05 O.OOOE+OO 8.820E+OI Y-91 5.880E+05 0.000E+OO O.OOOE+OO O.OOOE+OO 2.450E+06 7.030E+04 O.OOOE+OO 1.570E+04 Y-9JM 4.070E-OI O.OOOE+OO O.OOOE+oO 0.000E+OO 2.790E+03 2350E+03 0.000E+OO l.390E-02 y.92 l.640E+OI 0.000E+OO O.OOOE+OO O.OOOE+OO 2.450E+04 1.270E+05 0.000E+OO 4.610E-OI Y-93 l.500E+02 O.OOOE+OO 0.000E+oo 0.000E+OO 7.640E+04 1.670E+05 O.OOOE+OO 4.070E+OO ZR-95 l.150E+05 2.790E+04 O.OOOE+OO 3.I IOE+04 l.750E+06 2.l70E+o4 O.OOOE+OO 2.030E+o4 ZR-97 l.500E+o2 2.560E+Ol O.OOOE+OO 2.590E+OI I.IOOE+05 1.400E+05 O.OOOE+OO 1.170E+Ol NB-95 1.570£+04 6.430E+03 O.OOOE+OO 4.720E+03 4.790E+05 1.270E+04 O.OOOE+OO 3.780£+03 MO-99 0.000E+OO 1.650E+02 O.OOOE+OO 2.650E+02 J.350E+05 4.870E+04 O.OOOE!-00 3.230E+OI TC-99M 1.400E-03 2.880E-03 O.OOOE+oO 3.II OE-02 8.1IOE+02 2.030E+03 0.000E+OO 3.720E-02 TC-IOI 6.SWE--05 8.230.E-06 O.OOOE+OO 9.790E-04 5.840E+02 8.440E+02 O.OOOE+OO 8.120E--04 RU-103 2.020E+03 O.OOOE+OO O.OOOE+oo 4.240E+03 5.520E+05 1.610E+04 . O.OOOE+OO 6.790E+02 RU-105 l.220E+OO O.OOOE+OO 0.000E+oO 8.990E-OI 1.570E+04 4.840E+04 O.OOOE+OO 4.IOOE--01 RU-106 8.680E+04 O.OOOE+OO O.OOOE+oO 1.070E+05 1.160E+07 l .640E+05 O.OOOE+OO 1.090E+04 AG-JIOM 9.980E+03 7.220E +03 O.OOOE+OO 1.090E+04 3.670E+06 3.300E+04 O.OOOE+OO 5.000E+03 TE-125M 4.760E+03 l.990E+03 1.620E+03 O.OOOE+OO 4.470E+05 l .290E+04 O.OOOE+OO 6.580E+02 TE-127 2.230E+OO 9.530E-01 1.850E+o0 4.860E+OO l.030E+04 2.440E+04 0.000E+OO 4.890E--O I TE-127M 1.670E+04 6.900E+03 4.870E+o3 3.750E+04 l.310E+06 2.730E+04 0.000E+OO 2.070E+03 TE-129 7.880E-02 3.470E-02 6.750E-02 J.750E-0I 3.000E+03 2.630E+04 0.000E+OO l.880E-02 TE-129M l.410JH 04 6.0CXlE+03 5.470E+{13 3.l80E+04 l.680E+06 6.900E+04 0.000E+OO 2.230E+03 TE-13 l l.740E-02 8.220&-03 l.580E-02 3.990E-02 2.060E+03 8.220E+o3 0.000E+OO 5.000E-03 TE-DIM l .070E+02 S.500E+OI 8.930E+ol 2.650E+02 l.990E+05 l.190E+05 O.OOOE+OO 3.630E+OI TE-132 3.720E+02 2.370E+o2 2.790E+o2 l.030E+03 3.400E+OS 4.410E+04 O.OOOE+OO l.760E+02 1-130 6.360E+03 1.390E+04 l.600E+o6 l.530E+04 O.OOOE+OO 1.990E+o3 O.OOOE+OO 5.570E+03 Appendix J Ri Infant Inhalation

• Pilge 2 of 3 Page 9-202

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsite Dose Calculation Manual (OOCM)

APPENDIXJ R1 Infant Dose Factors for use in the Gaseous Dose Calculations Ageg1'0up: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / µCi/m3 Nuclide Bone Live1* Thyroid Kidney Lun2 Gilli Skin Total Bod1' I-131 3.790E+04 4.440E+04 1.480E+07 5.180E+04 O.OOOE+OO I.OC,OE+03 O.OOOE+OO l.960E+04 I-132 1.690E+o3 3.540E+o3 1.690E+05 3.950E+03 O.OOOE+OO 1.900E+03 O.OOOE+-00 1.260E+03 I-133 l .320E+04 1.920E+04 3.560E+06 2.240E+04 O.OOOE+OO 2.160E+03 0.000E+OO 5.600E+03 1-134 9.210E+02 l.880E+o3 4.450E+04 2.090E+03 0.000E+oo L290E+o3 O.OOOE+OO 6.650E+02 I-135 3.860E+ 03 7.6001H03 6.960E+05 8.470E+03 O.OOOE+OO l.830E+03 0.000E+OO 2.770E+03 CS-134 3.960E+o5 7.030E+05 0.000E+OO 1.900E+05 7.970E+04 l.330E+03 O.OOOE+oo 7.450E+04 CS-136 4.830E+04 1.350E+05 O.OOOE-+{IO 5.640E+04 l.180E+04 l.430E+o3 0.000E+OO 5.290E+04 CS-137 5.490E+o5 6.l20E+o5 O.OOOE+oO l.720E+05 7.l30E+04 l.330E+03 O.OOOE+oo 4.550E+04 CS-138 5.050E+02 7.810E+o2 0.OOOE+-00 4.IOOE+02 6.540E+Ol 8.760E+02 0.000E+OO 3.980E+02 BA-139 l.480E+oo 9.840E-04 0.000E+OO 5.920E-04 5.950E+03 5.100E+04 O.OOOEt*OO 4.300E-02 BA-140 5.600E+04 5.600E+Ol O.OOOE-+{IO 1.340E+Ol l.600E+06 3.840E+04 0.000E+OO 2.900E+03 BA-141 l.570E-OI l.OSOE-04 0.000E+oO 6.SOOE-05 2.970E+o3 4.750E+o3 O.O(JOE+OO 4.970E-03 BA-142 3.9800-02 3.300E-05 O.OOOE+OO 1.900E-05 l.550E+03 6.930E+02 O.OOOE+OO 1.960E-03 LA-140 5.050E+02 2.000E+02 O.OOOE-+{IO O.OOOE+OO l.680E+OS 8.480E+04 O.OOOE+OO 5.lSOE+Ol LA-142 l.030E+OO 3.770E-01 O.OOOE+oO O.OOOE+oo 8.220E+o3 5.950E+o4 O.OOOE+OO 9.040E-02 CE-141 2.770E+04 1.670E+04 O.OOOE+oO 5.250E+03 5.170E+05 2.160E+04 O.OOOE+OO 1.990E+03 CE-143 2.930E+o2 l.930E+o2 O.OOOE+OO 5.640E+Ol l .l60E+05 4.970E+04 0.000E+OO 2.210E+Ol CE-144 3.190E+06 l.210E+06 O.OOOE+oo 5.380E+05 9.840E+o6 l.480E+05 O.OOOE+oO 1.760E+05 PR-143 1.400E+04 5.240E+03 O.OOOE+oO l.970E+03 4.330E+o5 3.720E+04 O.OOOE+OO 6.990E+02 PR-144 4.7900-02 1.850E-02 O.OOOE+OO 6.720E-03 l.6IOE+03 4.280E+03 O.OOOE+OO 2.410E-03 ND-147 7.940E+03 8.l30E+03 O.OOOE+{IO 3.ISOE+03 3.220E+05 3.l20E+04 0.000E+OO 5.000E+02 W-187 l.300E+OI 9.020E+oo O.OOOE-H)O O.OOOE+OO 3.960E+04 3.560E+04 O.OOOE+OO 3.120E+OO NP-239 3.710E+02 3.320E+Ol 0.000E+OO 6.620E+Ol 5.950E+04 2.490E+04 O.OOOE+OO 1.880E* Ol Appendix J Ri Infant Inhalation

• Page l of 3 Page 9-203

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Offsitc Dose Calculat,on !vlanual (OOCM)

APPENDIXJ RJ Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m1 *mrem/yr / µCi/sec Nudide Bone Live!' Thyroid Kidney Luni! Gilli Skin TotalBodv H-3 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000.E+OO 0.000.E+OO C- 14 O.OOOE+OO O.OOOE+oo O.OOOE-t-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO NA-24 1.1 90E+07 1.190E+o7 1.190E+07 1.1 90E+07 1.190E+07 1.190E+07 1.390E+07 1.!90E+07 P-32 0.000E+OO O.OOOE+oo O.OOOE-t-00 O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO 0.000E+OO CR-51 4.660E+06 4.660E+06 4.660E+o6 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54  !.390E+09 l.390E+09  !.390E+09 l.390E+09 l.390E+09  !.390E+09 1.630E+09 l.390E+09 MN-56 9.020E+05 9020E+05 9.0JOE-t-05 9.020E+o5 9.020E+05 9.020E+o5 1.070E+06 9.020E+o5 FE-55 O.OOOE+OO O.OOOE+OO 0.000E-t-00 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+oo O.OOOE+OO FE-59 2.730E+08 2.730E+08 2.730E-t-08 2.730E+08 2.730E+08 2.730E+08 3.2IOE+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+o8 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.!SOE+IO 2.150E+IO 2.ISOE+IO 2.150E+IO 2.150E+l0 2.150E+!O 2.530E+ IO 2.150E+ IO NI-63 O.OOOE+OO 0.000E+OO O.OOOE+oO O.OOOF;.t OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO Nl-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+OS CU-64 6.070E+05 6.070E+05 6.070E+o5 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+o8 7.470E+08 8.590E+08 7.470E+08 ZN-69 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 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 2030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+o5 BR-85 0.000E+OO 0.000E+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 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 3.31 0E f04 3.3!0E+04 3.310E+04 3.31 0E+04 3.780E+04 3.3 LOE+04 RB-89 l.230E+05 l.230E+05 l.230E+<l5 1.230E+05 l.230E+05 l.230E+u5 1.480E+05 l.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+o4 2.160E+04 2.160E+04 2. 160E+04 2.5!0E+04 2.!60E+04 SR-90 O.OOOE+OO 0.0ClOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.l50E+06 Appendix J Ri [nfant Ground Plane Dc.positioo - Page 1 of 3 Page 9-204

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Offs1tc Dose Calculat,on Manual (ODCM)

APPENDIXJ RJ Infant .Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: G1-ound Plane Deposition (GPD) Units: m2*nuem/yr / µCl/sec Nuclide Bone Liver Thvroid Kid nev Lung Gilli Skin Total Bodv SR-92 7.770E+05 7.7706+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 5.3IOE+o3 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 l.210E+06 1.070E+06 Y-91.M l.OOOE+05 1.000E+o5 1.000E+o5 1.000E+05 1.000E+05 l.OOOE+05 l.160E+05 1.000E+05 y.92 l.800E+05 \.800El+05 1.800E+05 1.800E+05 l.800E+05 1.800E+05 2.140E+05 l.800E+05 Y-93 l .830E+o5 l.830E+05 l.830E+05 1.830E+05 1.830E+05 1.830E+05 2.5!0E+05 l.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E-+-08 2.450E+o8 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+o8 1.370E+08 1.370E+08 1.370E+08 l.6IOE+08 1.370E+08 M0-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.9906+06 3.990E+06 4.630E106 3.990E+06 TC-99M 1.840E+05 l.840E+05 1.840E+o5 l.840E+05 1.840E+05 l.840E+05 2.IIOE+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 l .080E+O& 1.080E+08 1.080E+o8 1.080E+08 1.080E+08 1.080E+08 l.260E.+08 1.080E+08 RU-1O5 6.360E+05 6.360E+05 6.360E+o5 6.360E+05 6.360E+05 6.360E+05 7.2IOE+05 6.360E+05 RU-1O6 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-110.M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+o9 TE-125.M l.550E+06 1.550E+06 l.550E+06 1.550E+06 1.550E+06 l.550E+06 2 !30E+06 I 550E+06 TE-127 2.980E+03 2.980E+-03 2.980E+o3 2.980E+03 2.980E+03 2.980E+o3 3.280E+03 2.980E+03 TE-127M 9.!60E+04 9.160E+04 9.160E+o4 9.160E+04 9.160E+o4 9.160E+04 l .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.!00E+04 2.620E+04 TE-129M 1.980£+()7 l.980E+07 1.98UE+l17 1.980E+07 l.980E , 07 1.980E+07 2.3lOE+07 1.980E+07 TE-131 2.920E+04 2.920E+04 2.920E+o4 2.920E+04 2920E+o4 2.920E+04 3.450E+o7 2.920E+04 TE-13IM 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+o6 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 I-130 5.5!0E+06 5.5!0E+06 5.510E+o6 5.510E+06 5.5JOE+06 5.5!0E+06 6.690E+06 5.5IOE+06 Awcndix J Ri rnfanl Ground Plane Dc.positioo

• Page 2 of 3 Page 9-205

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconeo Nucl oar Station Offsitc Dose CalculatLon Manual (ODCM)

APPENDIXJ R1Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Ground Plane Deposition (GPO) Units: m 1*m1-em/yr / µCi/sec Nuclide Bone Liver Thyroid Kidney Lun2 Gilli Skin Total BodJ*

I-131 l.720E+o7 l.720E+07 1.720E+o7 l.720E+07 l.720E+07 l.720E+07 2.090E+07 l.720E+07 I-132 l.250E+06 l.250E+06 l.250E+-06 1.250E+06 L250E+<)6 l.250E+06 l.470E+()6 1.250E+06 I-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2A50E+06 2.450E+06 2.980E+06 2.450E+06 1- 134 4.470E+05 4.470E+-05 4.470E+o5 4.470E+05 4.470E+-05 4.470E+o5 5.300E+o5 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+o9 6.860E+o9 6.860E+09 6.860E+09 6.860E+09 8.000E+09 6.860E+09 CS-136 l.5 10E+08 l.510E+08 1.SIOE-+{18 1.510E+08 I.SIOE+-08 1.SIOE+-08 l.710E+08 l.5 10E+08 CS-137 l.030E+ IO l.030E+IO l.030E+ IO l.030E+l0 l.030E+IO l.030E+IO l.200E+ l 0 l.030E+IO CS- 138 3.590E+05 3.590E+05 3.590E+-05 3.590E+05 3.590E+05 3.590E+05 4.IOOE+05 3.590E+05 BA-139 l.060E+05 1.060E+05 1.060E+05 l .060E+05 l.060E+05 l.060E+05 l.l90E+05 l .060E+05 BA- 140 2.050E+07 2.050E+07 2.0SOE+-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+o4 4.170E+04 4. l70E+04 4. l70E+04 4.750E+04 4. l70E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5. IIOE+04 4.490E+04 LA- 140 1.920E+07 1.920E+07 l.920E+-07 l.920E+07 1.920E+07 l.920E+07 2.180E+07 1.920E+07 LA- 142 7.600E+05 7.600E+05 7.600E+o5 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 l .370E+07 1370E+-07 1370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE- 143 2.3l0E+o6 2.310E+06 2.3l0E+06 2.310E+06 2.3lOE+06 2.310E+06 2.630E* 06 2.3 l 0E+06 CE- 144 6.950E+07 6.950E+o7 6.950E+o7 6.950E+07 6.950E+<)7 6.950E+07 8.040E+o7 6.950E+07 PR- 143 0.000E+OO 0.000E+OO O.OOOE+-00 O.OOOE+OO O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO PR-144 l.830E+03 l.830E+03 l .830E+03 l.830E+03  !.830E+03 l.830E+03 2. l !OE+03 l.830E+03 ND- 147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+U6 8.39QE+06 l.(IIOIH 07 8.390E+06 W-1 87 2.350E+06 2.350E+o6 2.350E+<)6 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 l.710E+06 l.710E+06 l.7 l 0E+o6 1.710E+06 l.710E+06 l.710E+06 l .980E+06 1.7 10E+06 Appendix JRi Infant Ground Plane Depositicn

• Pt.l!C 3 af3 Page 9-206

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Selected Licensee Commitments Revised 11/28/2018 List of Effective Pages Revision Number Implementation Date 16.0 005 08/16/17 16.1 000 10/15/07 16.2 000 08/25/14 16.3 001 06/29/15 16.4 PENDING 16.5.1 000 11/26/12 16.5.2 000 11/15/12 16.5.3 000 02/21/07 16.5.4 Deleted 03/28/18 16.5.5 Deleted 05/16/09 16.5.6 Deleted 02/10/14 16.5.7 000 12/13/06 16.5.8 000 01/31/07 16.5.8a Deleted 05/19/05 16.5.9 000 11/15/12 16.5.10 000 10/08/03 16.5.11 000 01/31/00 16.5.12 001 10/17/18 16.5.13 000 03/27/99 16.6.1 000 07/23/12 16.6.2 000 01/31/07 16.6.3 000 11/15/12 16.6.4 000 11/15/12 16.6.5 000 12/14/00 16.6.6 000 11/15/12 16.6.7 000 03/27/99 16.6.8 000 03/27/99 16.6.9 000 11/15/12 16.6.10 000 11/15/12 16.6.11 000 11/15/12 16.6.12 000 11/15/12 16.6.13 000 03/31/08 16.6.14 000 04/21/14 16.6.15 000 11/15/12 16.7.1 000 11/15/12 Oconee Nuclear Station LOEP 1 Revision 029 Page 9-207

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Selected Licensee Commitments Revised 11/28/2018 List of Effective Pages Revision Number Implementation Date 16.7.2 000 11/15/12 16.7.3 000 11/15/12 16.7.4 000 07/14/05 16.7.5 000 11/15/12 16.7.6 000 04/08/14 16.7.7 000 11/15/12 16.7.8 000 03/27/99 16.7.9 000 10/23/03 16.7.10 000 11/15/12 16.7.11 000 11/15/12 16.7.12 000 06/30/04 16.7.13 000 12/05/12 16.7.14 000 11/15/12 16.7.15 000 04/08/14 16.7.16 000 10/14/15 16.7.17 000 07/14/16 16.8.1 000 08/09/01 16.8.2 000 02/10/05 16.8.3 001 01/26/16 16.8.4 000 02/10/05 16.8.5 000 05/21/15 16.8.6 000 01/04/07 16.8.7 000 01/31/00 16.8.8 000 01/31/00 16.8.9 000 06/21/05 16.9.1 001 08/16/16 16.9.2 002 08/16/16 16.9.3 Deleted 01/08/18 16.9.4 003 07/17/18 16.9.5 002 08/16/16 16.9.6 005 . 12/19/17 16.9.7 001 08/16/16 16.9.8 Deleted 09/26/18 16.9.8a 000 02/07/05 16.9.9 002 08/16/17 Oconee Nuclear Station LOEP2 Revision 029 Page 9-208

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Oconee Nuclear Station Selected Licensee Commitments Revised 11/28/2018 List of Effective Pages Revision Number Implementation Date 16.9.10 000 01/12/04 16.9.11 001 06/29/15 16.9.11a 001 06/06/17 16.9.12 001 09/21/15 16.9.13 000 01/31/07 16.9.14 000 10/28/04 16.9.15 000 03/27/99 16.9.16 000 10/15/1~

16.9.17 000 05/23/01 16.9.18 000 07/15/14 16.9.19 000 03/31/05 16.9.20 003 07/17/18 16.9.21 000 07/09/09 16.9.22 Deleted 08/16/17 16.9.23 001 08/16/17 16.9.24 003 11/18/16 16.9.25 001 08/16/17 16.10.1 000 11/15/12 16.10.2 000 12/02/03 16.10.3 000 03/27/99 16.10.4 000 11/15/12 16.10.5 Deleted 08/24/04 16.10.6 000 03/27/99 16.10.7 001 09/21/15 16.10.8 000 11/27/06 16.10.9 000 11/25/09 16.11.1 000 03/15/11 16.11.2 000 01/31/00 16.11.3 000 11/20/08 16.11.4 000 06/30/14 16.11.5 000 10/30/02 16.11.6 000 11/08/13 16.11.7 000 01/31/00 16.11.8 000 12/21/09 16.11.9 000 03/22/10 Oconee Nuclear Station LOEP3 Revision 029 Page 9-209

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Oconee Nuclear Station Selected Licensee Commitments Revised 11/28/2018 List of Effective Pages Page Revision Number lm12lementation Date 16.11.10 000 05/14/14 16.11.11 000 03/27/99 16.11.12 000 04/10/03 16.11.13 000 03/27/99 16.11.14 000 03/27/99 16.12.1 000 03/27/99 16.12.2 000 05/03/07 16.12.3 000 ' 05/01/03 16.12.4 000 03/27/99 16.12.5 000 03/27/99 16.12.6 000 11/08/07 16.13.1 002 11/28/18 16.13.2 000 12/15/04 16.13.3 000 12/15/04 16.13.4 000 03/27/99 16.13.5 Deleted 11/30/99 16.13.6 000 03/27/99 16.13.7 000 12/15/04 16.13.8 000 03/27/99 16.13.9 000 03/27/99 16.13.10 ODO 03/27/99 16.13.11 000 03/27/99 16.14.1 000 11/15/12 16.14.2 000 07/23/12 16.14.3 ODO 03/27/99 16.14.4 Deleted 03/15/11 16.14.4.a ODO 03/15/11 16.15.1 000 04/12/06 16.15.2 ODO 11/15/12 16.15.3 000 11/15/12 Note: With the introduction of Fusion in June 2015, all controlled documents require a three-digit revision number. Thus, the revision numbers were set to "000" in the summer of 2015. As such, the revision dates for Revision 000 are based on the implementation dates for revisions in effect prior to this change.

Oconee Nuclear Station LOEP4 Revision 029 Page 9-210

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Liquid Effluents 16.11 .1 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.1 Radioactive Liquid Effluents COMMITMENT Establish conditions for the controlled release of radioactive liquid effluents . Implement the requirements of 10 CFR 20, 10 CFR 50.36a, Appendix A to 10 CFR 50, Appendix I to 10 CFR 50, 40 CFR 141 and 40 CFR 190.

a . Concentration The concentration of radioactive material released at anytime from the site boundary for liquid effluents to Unrestricted Areas [denoted in Figure ~-5 of the Oconee Nuclear Station Updated Final Safety Analysis Report) shall be limited to 10 times the effluent.

concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases the concentration shall be limited to 2 x 10-4 µCi/ml total activity.

b. Dose The dose or dose commitment to a Member Of The Public from radioactive materials in liquid effluents to Unrestricted Areas shall be limited to:

1. during any calendar quarter:

4.5 mrem to the total body

15 mrem to any organ; and

2. during any calendar year:

9 mrem to the total body

30 mrem to any organ.

c. Liquid Waste Treatment The appropriate subsystems of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge, if the projected dose due to liquid effluent releases to unrestricted areas, when averaged over 31 days v.ould exceed 0.18 mrem to the total body or 0 .6 mrem to any organ .

16.11.1-1 03115111 I Page 9-211

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Liquid Effluents 16.11.1

---

NOTE-----------------------------------------

Append ix I dose limits for radioactive liquid effluent releases are applicable only during normal operating conditions which include expected operational occurrences, and are not applicable during unusual operating conditions that result in activation of the Oconee Emergency Plan.

~PPLICABI LITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of A.1 Restore concentration to Immediately radioactive material within the limit.

released in liquid effluents to Unrestricted Areas exceeds the limits specified in Commitment a.

16.11 .1-2 0311 s,11 I Page 9-212

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Radioactive Liquid Effluents 16.11.1 CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose from 8.1 ------------NOTE-------------

the release of Not required during radioactive materials in unusual operating liquid effluents exceeds conditions that result in any of the limits in activation of the Oconee Commitment b. Emergency Plan.

Submit report to the 30 days from the end of regional NRC Office which the quarter during which includes the folldvving: the release occurred

a. Cause(s) for exceeding the limit(s).

b. A description of the program of corrective action initiated to:

reduce the releases of radioactive materials in liquid effluents, and to keep these levels of radioactive materials in liquid effluents in compliance with the above limits, or as low as reasonably achievable.

c. Results of radiological analyses of the drinking water source and the radiological impact on finished drinking water supplies with regard to the requirements of 40CFR 141.

16.11.1-3 03115111 I Page 9-213

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Liquid Effluents 16.11.1 CONDITION REQUIRED ACTION COMPLETION TIME C. Radioactive liquid C.1 Submit report to the 30 days waste is discharged regional NRC Office which without treatment and includes the following:

in excess of the specified limit. a. Cause of equipment or subsystem inoperability.

b. Corrective action to restore equipment and prevent recurrence .

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.1.1 N/A NIA 16.11 .1-4 03/15/11 I Page 9-214

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Radioactive Liquid Effluents 16.11.1 The concentration commitment is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site 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. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its EC in air (submersion) vvas converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The basic requirements for Selected Licensee Commitments concerning effluent from nuclear power reactors are stated in 10 CFR 50.36a. Compliance with effluent Selected Licensee Commitments will ensure that average annual releases of radioactive material in effluents will be small percentages of the limits specified in the old 10 CFR 20.106 (new 10 CFR 20.1302).

The requi'rements contained in 10 CFR 50.36a further indicate that operation~! 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 10 CFR 20.106 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 10 CFR 50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as reasonably achievable (ALARA) as set forth in 10 CFR 50 Appendix I. Also, for fresh water sites with drinking water supplies which 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 141. Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with this SLC are based on ten times the instantaneous dose rate value of 50 mrerrlyear to apply at all times . Compliance with the limits of the new 10 CFR 20.1001 will be demonstrated by operating within the limits of 10 CFR 50, Appendix I, 40 CFR 141 and 40 CFR 190.

Section I of Appendix I of 10 CFR 50 states that this appendix provides specific numerical guides for design objectives and limiting conditions for operation, to assist holders of licenses for light water cooled nuclear power reactors in meeting the requirements to keep releases of radioactive material to unrestricted areas as low as practical and reasonably achievable, during normal reactor operations, including expected operational occurrences. Using the flexibility granted during unusual operating conditions, and the stated applicability of the design objectives for the Oconee Nuclear Station, Appendix I dose limits for radioactive liquid effluent releases are concluded to be not applicable during unusual operating conditions that result in the activation of the Oconee Emergency Plan.

For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

The requirements 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 SLC implements the requirements of 10 CFR Part 50.36a.

General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section 11.D of Appendix A to 10 CFR Part 50.

16.11.1-5 03/15/11 I Page 9-215

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Liquid Effluents 16.11 .1

REFERENCES:

1. 10 CFR Part 20, Appendix B.

2. 40 CFR Part 141.

3. 10 CFR Part 50, Appendices A and I.

4. 40 CFR Part 190.

5. Offsite Dose Calculation Manual.

6. Regulatory Guide 1.109.

7. NUREG-1301 16.11.1 -6 0311 s111 I Page 9-216

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Gaseous Effluents 16.11.2 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.2 Radioactive Gaseous Effluents COMMITMENT Establish conditions for the controlled release of radioactive gaseous effluents. Implement the requirements of 10 CFR 20, 10 CFR 50.36a, Appendix A to 10 CFR 50, Appendix I to 10 CFR 50, and 40 CFR 190.

a. Dose Rate The instantaneous dose rate at the site (exclusion area) boundary for gaseous effluents [Rgure 2.1-4(a) of the Oconee Nuclear Station Updated Final Safety Analysis Report] due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

1. The dose rate limit for noble gases shall be:

$ 500 mremlyr to the total body

$ 3000 mrem/yr to the skin; and

2. The dose rate limit for all radioiodines and for all radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than 8 days shall be :5 1500 mrem/yr to any organ.

b. Dose

1. The air dose due to noble gases released in gaseous effluent from the site shall be limited to the following:

i. During any calendar quarter:

$15 mrad for gamma radiation

5 30 mrad for beta radiation ii. During any calendar year:

5 30 mrad for gamma radiation

$ 60 mrad for beta radiation

2. The dose to a Member Of The Public from radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from the site, shall be limited to the following:

16.11.2-1 01131100 I Page 9-217

• • Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Gaseous Effluents 16.11.2

i. During any calendar quarter:

~ 22.5 mrem to any organ ii. During any calendar year:

~ 45 mrem to any organ .

c. Gaseous Radwaste Treatment

1. The Gaseous Radwaste Treatment System shall be used to reduce the noble gases in gaseous wastes prior to their discharge, if toe projected gaseo~s effluent air dose due to gaseous effluent release from the site , when averaged over 31 days exceeds 0 .6 mrad for gamma radiation and 1.2 mrad for beta radiation .

2. The Ventilation Treatment Exhaust System shall be used to reduce radioactive materials other than noble gases in gaseous waste prior to their discharge when the projected doses due to effluent releases to unrestricted areas when averaged over 31 days would exceed 0 .9 mrem to any organ .

d. Used Oil Incineration During incineration of used oil contaminated by radioactive material in the Station Auxiliary Boiler, the dose to a Member Of The Public from radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from the Station Auxiliary Boiler shall be ~ 0.045 mrem to any organ in any calendar year.

---

NOTE------------------------------------------

The requirement of c.2 does not apply to the Auxiliary Building Exhaust System since it is not "treated" prior to release.

APPLICABILITY: At all times 16.11.2-2 03/27/99 Page 9-218

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Gaseous Effluents 16.11 .2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Dose rate exceeds the A.1 Restore release rate to Immediately limits specified in within limits.

Commitment a.

B. Calculated dose 8.1 Submit report to the 30 days from the end of exceeds specified limits. regional NRC Office which the quarter during which includes the foll011ving: the release occurred

a. Cause(s) for exceeding the limit(s),

and

b. A description of the program of corrective action initiated to :

reduce the releases of radioactive materials in gaseous effluents, and to keep these levels of radioactive materials in gaseous effluents in compliance with the specified limits or as low as reasonably achievable .

16.11.2-3 01131100 I Page 9-219

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Gaseous Effluents 16.11.2 CONDITION REQUIRED ACTION COMPLETION TIME C. Radioactive gaseous C.1 Submit a report to the 30 days waste is discharged regional NRC Office which greater than limits includes the following:

specified in Commitment c.1 or a. Cause of equipment c.2. or subsystems inoperability, and AND

b. Corrective action to Radioactive gaseous restore equipment waste is discharged and prevent without treatment for recurrence.

more than 31 days.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.2.1 N/A N/A 16.11 .2-4 03/27/99 Page 9-220

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Gaseous Effluents 16.11.2 The basic requirements for Selected Licensee Commitments concerning effluent from nuclear power reactors are stated in I0CFRS0.36. Compliance with effluent Selected Licensee Commitments will ensure that average annual releases of radioactive material in effluents will be small percentages of the limits specified in the old IOCFR20.106 (new I0CFR20.1302). The requirements contained in I0CFR50.36a 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 I0CFR20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem to the total body, 3000 mrem to the skin, and 1500 mrem to an infant via the milk animal-milk-infant pathway. It is further indicated in I0CFR50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as reasonably achievable (ALARA) as set forth in I0CFR50 Appendix I. Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with gaseous release rate SLCs will be maintained at the current instantaneous dose rate limit for noble gases of 500 mrem/year to the total body and 3000 rrrem/year to the skin; and for lodine-131, for lodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days. an instantaneous dose rate limit of 1500 mrern/year.

The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculating 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."

Equations in the ODCM are provided for determining the actual doses based upon the historical average atmospheric conditions. The release rate commitments for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides into 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.

The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as Iowas is reasonably achievable." This commitment implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section 11D of Appendix I to 10 CFR Part 50.

16.11 .2-5 01131100 I Page 9-221

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Gaseous Effluents 16.11 .2

REFERENCES:

1 10 CFR Part 20, Appendix 8.

2. 10 CFR Part 50, Appendices A and I.

3. Regulatory Guide 1.109.

4. 40 CFR Part 190.

5. Offsite Dose Calculation Manual.

16.11 .2-6 01131100 I Page 9-222

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11 .3 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11 .3 Radioactive Effluent Monitoring Instrumentation COMMITMENT Radioactive Effluent Monitoring Instrumentation shall be OPERABLE as follows:

a. Liquid Effluents The radioactive liquid effluent monitoring instrumentation channels shown in Table 16.11.3-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.11.1.a are not exceeded.

b. Gaseous Process and Effluents The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 16.11.3-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.11.2.a are not exceeded.

c. The setpoints shall be determined in accordance with the methodology described in the ODCM and shall be recorded.

---

NOTE----------------------------------------

Correction to setpoints determined in accordance with Commitment c may be permitted without declaring the channel inoperable.

APPLICABILITY: According to Table 16.11 .3-1 and Table 16.11.3-2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Alarm/trip setpoint less A.1 Declare channel Immediately conservative than inoperable.

required for one or more effluent monitoring instrument channels. A.2 Suspend release of Immediately effluent monitored by the channel.

16.11.3-1 11I20,oa I Page 9-223

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11 .3 CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required 8.1 Enter the Condition Immediately liquid effluent monitoring referenced in Tabla instrument channels 16.11 .3-1 for the inoperable. function.

AND 8.2 Restore the 30 days instrument(s) to OPERABLE status.

C. One or more required C.1 Enter the Condition Immediately gaseous effluent referenced in Table monitoring instrument 16.11 .3-2 for the channels inoperable. function.

AND C.2 Restore the 30 days instrument(s) to OPERABLE status.

D. Required Action and D.1 Explain in next Annual April 30 of following associated Completion Radiological Effluent calendar year Time of Required Action Release Report why 8 .2 or C.2 not met. inoperability was not corrected in a timely manner.

16.11.3-2 11120,oa I Page 9-224

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1.1 Analyze two Prior to initiating Action B.1 and independent samples subsequent release referenced in Table in accordance with 16.11.3-1 . (RIA-33) SLC 16.11.4.

AND E.1.2 Conduct two Prior to initiating independent data entry subsequent release checks for release rate calculations AND E.1.3 Conduct two Prior to initiating independent valve subsequent release lineups of the effluent pathway.

OR E.2 Suspend release of Immediately radioactive effluents by this pathway.

F. As required by Required F.1 Suspend release of Immediately Action B.1 and radioactive effluents by referenced in Table this pathway.

16.11 .3-1 . (RIA-54)

QR F.2 Collect and analyze Prior to each discrete grab samples for gross release of the sump radioactivity (beta and/or gamma) at a lower limit of detection of at least 10- 7 µCi/ml.

16.11.3-3 11120,oa I Page 9-225

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11 .3 CONDITION REQUIRED ACTION COMPLETION TIME

---

NOTE-----------------

G. As required by Required Not required during short, Action 8 .1 and controlled outages of liquid referenced in Table effluent monitoring 16.11 .3-1. (Liquid instrumentation. Short controlled Radwaste Effluent Line outages are defined as planned Flow Rate Monitor) removals from service for durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

G.1 Suspend release of Immediately radioactive effluents by this path1,,Wy.

G.2 Estimate flow rate Immediately during actual releases.

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter 16.11.3-4 11120,oa I Page 9-226

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME H. As required by Required -----------------NO TE----------------

Action B.1 and Not required during short, referenced in Table controlled outages of liquid 16.11.3-1. (RIA-35, #3 effluent monitoring Chemical Treatment instrumentation. Short controlled Pond Composite outages are defined as planned Sampler and Sampler removals from service for Flow Monitor (Turbine durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Building Sumps for purposes of sample filter Effluent)) changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

H.1 Suspend release of Immediately radioactive effluents by this path\11/ay.

OR H.2 Collect and analyze Immediately grab samples for gross radioactivity (beta AND and/or gamma) at a lower limit of detection Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of at least 10*7 µCi/ml. thereafter 16.11.3-5 11120,oa I Page 9-227

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11 .3 CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required ---------------NOTE-----------------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2 for effluent effluent monitoring releases from waste gas instrumentation. Short controlled tanks (RIA-37, RIA-38) outages are defined as planned or containment purges removals from service for (RIA-45). durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

1.1 .1 Analyze two Prior to initiating independent samples. subsequent release 1.1.2 Conduct two Prior to initiating independent data entry subsequent release checks for release rate calculations 1.1 .3 Conduct two Prior to initiating independent valve subsequent release lineups of the effluent pathway.

OR 1.2 Suspend release of Immediately radioactive effluents by this pathvvay.

16.11 .3-6 11120,oa I Page 9-228

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required ---------------NOTE-------------------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (Effluent effluent monitoring Flow Rate Monitor (Unit instrumentation. Short controlled Vent, Containment outages are defined as planned Purge, Interim removals from service for Radwaste Exhaust, Hot durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Machine Shop Exhaust, for purposes of sample filter Radwaste Facility changeouts, setpoint Exhaust, Waste Gas adjustments, service checks, Discharge)) and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

J.1 Suspend release of Immediately radioactive effluents by this pathway.

OR J.2 Estimate flow rate Immediately Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter 16.11.3-7 11120,os I Page 9-229

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME K. As required by Required ----------------NOTE-----------------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (RIA-45, effluent monitoring RIA-53, 4RIA-45) instrumentation. Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

K.1 Suspend release of Immediately radioactive effluents by this pathvvay.

K.2.1 Collect grab sample. Immediately Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> K.2.2 Analyze grab samples 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from collection for gross activity (beta of sample and/or gamma).

16.11 .3-8 11120,oa I Page 9-230

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11 .3 CONDITION REQUIRED ACTION COMPLETION TIME L. As required by Required -----------------NO TE ----------------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (Unit Vent effluent monitoring Monitoring Iodine instrumentation. Short controlled Sampler, Unit Vent outages are defined as planned Monitoring Particulate removals from service for Sampler, Interim durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Radwaste Building for purposes of sample filter Ventilation Monitoring changeouts, setpoint Iodine Sampler, Interim adjustments, service checks, Radwaste Building and/or routine maintenance Ventilation Monitoring procedures. This guidance may Particulate Sampler, Hot be applied successively, Machine Shop Iodine provided that time between Sampler, Hot Machine successive short, controlled Shop Particulate outages is always at least equal Sampler, Radwaste to duration of immediately Facility Iodine Sampler, preceding outage.

Radwaste Facility Particulate Sampler)

L.1 Suspend release of Immediately radioactive effluents by this pathV1Tc1y.

OR L.2.1 -----------NOTE-----------

The collection time of each sample shall not exceed 7 days.

Collect samples Immediately continuously using auxiliary sampling equipment.

AND L.2.2 Analyze each sample. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from end of each sample collection 16.11.3-9 11120,oa I Page 9-231

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME M. As required by Required -----------------NOTE-----------------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2 for effluent effluent monitoring from ventilation system instrumentation. Short controlled or condenser air outages are defined as planned ejectors. (RIA-40) removals from service for durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

M.1 Continuously monitor Immediately release through the unit vent.

M.2 Suspend release of Immediately radioactive effluents by this pathv.ay.

OR M.3.1 Collect grab sample. Immediately Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> M.3.2 Analyze grab sample for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from collection gross activity (beta of grab sample and/or gamma).

16.11.3-10 11120,oa I Page 9-232

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.3.1 ---------------------- NOTE---------------------------

The Channel Response check shall consist of verifying indications during periods of release.

Channel response checks shall be made at least once per calendar day on days in which continuous, periodic or batch releases are made.

Perform Channel Response Check. During each release via this pathway SR 16.11.3.2 -----------------------NOTE----------------------------

The Channel Response check shall consist of verifying indications during periods of release.

Channel response checks shall be made at least once per calendar day on days in which continuous, periodic or batch releases are made.

Perform Channel Response Check. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 16.11 .3.3 Perform Source Check. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 16.11.3.4 Perform Source Check. 31 days SR 16.11.3.5 Perform Source Check. 92 days 16.11.3-11 11120,os I Page 9-233

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11 .3 SURVEILLANCE FREQUENCY SR 16.11.3.6 ----------------------NOTE-------------------------

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm'trip setpoint.

2. Circuit failure (downscale only).

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 16.11 .3.7 ----------------------NOTE---- - - - - - - - - -

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm'trip setpoint.

2. Circuit failure (downscale only).

92 days Perform CHANNEL FUNCTIONAL TEST.

SR 16.11 .3.8 Perform CHANNEL FUNCTIONAL TEST. 92 days 16.11 .3-12 11120,oe I Page 9-234

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE FREQUENCY SR 16.11.3.9 ------------------------NOTE---------------------------

T he initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with the National Institute of Standards and Technology (NIST). The standards shall permit calibrating the system over its intended range of energy and measurement. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (Operating plants may substitute previously established calibration procedures for these requirements.)

12 months Perform CHANNEL CALIBRATION.

SR 16.11.3.10 Perform CHANNEL CALIBRATION. 12 months SR 16.11.3.11 Perform leak test. When cylinder gates or wicket gates are reworked SR 16.11.3.12 Perform Source Check. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to each release via associated pathway 16.11.3-13 1112010a I Page 9-235

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQU ID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABILITY REQUIREMENTS ACTION B.1

1. Monitors Providing Automatic Termination of Release

a. Liquid Radwaste Effluent Af all times SR 16.11.3.1 E Line Monitor. RIA-33 SR 16.11.3.3 SR 16.11.3.6 SR16.11 .3.9

b. Turbine Building Sump, At all times SR16.11.3.2 F RIA-54 SR 16.11.3.4 SR16.11.3.7 SR16.11.3.9

2. Monitors not Providing Automatic Termination of Release Low Pressure Service Water At all times SR 16.11.3.2 H RIA-35 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9

3. Flow Rate Measuring Devices

a. Liquid Radwaste Effluent At au times SR 16.11.3.1 G Line Flow Rate Monitor SR 16.11.3.10 (OLW CR0725 or OLW SS0920)

b. Liquid Radwaste Effluent NA NA SR 16.11.3.1 NA Line Mnimum Flow SR 16 .11.3. 10 Device C. Turbine Building sump NA NA SR 16 .11 .3. 1 NA Minimum Flow Device SR 16.11.3.10

d. Lem Pressure Service NA NA SR 16.11.3.1 NA Water Minimum Flow SR 16.11.3.10 Device 16.11.3-14 11I20,oa I Page 9-236

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQU ID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABILITY REQUIREMENTS ACTION B.1 e Keowee Hydroelectric NA NA SR16 .11 .311 NA Tailrace Discharge:,;

4. Continuous Composite Sampler

1. 3 Chemical Trealment At all times SR 16.11.3.2 H Pond Composile Sampler SR 16.11.3.10 and Sampler Flow Monitor (Turbine Building Sumps Effluent)

(a) Flow is determined from the number of hydro units operating. If no hydro units are operating, leakage now will be assumed to be 38 cfs based on historical data .

16.11.3-15 11I20,oa I Page 9-237

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE SURVEILLANCE REQUIRED INSTRUMENT PATH) APPLICABILITY REQUIREMENTS ACTIONC.1

1. Unit Vent Monitoring System

a. Noble Gas Activity Al All nmes SR 16.11 .3.2 Monitor Providing Alam, SR 16.11.3.4 and Automatic SR 16.11.3.7 Tennination of SR 16.11.3.9 Containment Purge Release (RIA Purge Isolation Function I

b. Noble Gas Activity Al all-times SR 16.11.3.2 K Monitor Providing Alann . SR 16.11.3.4 (RIA Vent stack SR 16.11.3.7 Monitor Function) SR 16.11.3.9 C. Iodine Sampler AIAII nmes SR 16.11.3.2 L

d. Particulate Sampler AIAII nmes SR 16.11.3.2 L

e. Effluent Flow Rate AIAII nmes SR 16.11.3.2 J Monitor(Unit Vent Fl<m) SR1611310 (MSC CR0001)

f. Sampler Flow Rate AtAII Times SR 16.11.3.2 NA Monitor <*I (Annunciator) SR 16.11.3.10

g. Effluent Flow Rate During Containment SR 16.11.3.2 J Monitor (Containment Purge Qperatlon SR 16.11.3.10 Purge)(MSC CR0001)

h. CSAE Off Gas Monitor During Operation SR 16.11.3.2 M (RIA-401 ofCSAE SR 16.11.3.5 SR 16.11.3.8 SR 16.11 .3.9

2. Interim Radwaste Building Ventilation Monitoring System

a. Noble Gas Activity AIAII Times SR 16.11.3.2 K Monltor(RIA- 53) SR16.11.3.4 SR 16.11 .3.7 SR 16.11.3.9

b. Iodine Sampler AIAII Times SR 16.11.3.2 L C. Particulate Sampler AIAII Times SR 16.11.3.2 L

d. Effluent Flow Rate AIAII Times SR 16.11.3.2 J Monitor ( Interim SR 16.11.3.10 Radwasle Exhaust)

(GWD FT0082)

e. Sampler Flow Rate At All Times SR 16.11 .32 NA Monitor<'> (Annunciator)

SR 16.11 .3.10 16.11.3-16 11120,oa I Page 9-238

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE SURVEILLANCE REQUIRED INSTRUMENT PATH) APPLICABILITY REQUIREMENTS ACTION C.1

3. Hot Machine Shop Ventilation Sampling System

a. Iodine Sampler At All Times SR 16.11.3.2 L

b. Particulate Sampler AIAII Times SR 16.11.3.2 L C. Effluent Flow Rate AIAII Times SR 16.11.3.2 J Monilor (Hot Machine SR 16.11.3.10 Shop Exhaust)

(Totalizer)

d. Sampler Flow Rate Al All Times SR 16.11.3.2 NA Monitor i* l (Annunciator) SR 16.11.3.10

4. Radwaste Facility Ventilation Monitoring System

a. Noble Gas Activity Al All Times SR 16.11.3.2 K Monitor ( 4-RIA-45) SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9

b. Iodine Sampler AIAII Times SR 16.11 .3.2 L

c. Particulate Sampler AIAII Times SR 16.11.3.2 L

d. Effluent Flow Rate AIAII Times SR 16.11 .3.2 J Monitor (Radwaste SR 16.11.3.10 Facility Exhaust) (0VS CR2060)

e. Sampler Flow Rate Al All Times SR 16.11.3.2 NA Monitor <*i (Annunciator) SR 16.11.3.10

5. Waste Gas HoldJp Tanks

a. Noble Gas Activity During Waste Gas SR 16.11.3.1 Monilor - Providing Holdup Tank Releases SR 16.11.3.6 Alarm and Automatic SR 16.11 .3.9 Termination of Release SR 16.11 .3.12 (RIA-37,-38)b

b. Effluent Flow Rate Du ringWasleGas SR 16.11.3.1 Monilor (Waste Gas Holdup Tank Releases SR 16.11.3.10 Discharge Flow) (MSC CR0001)

(a)Alarms indicating low f ow may be substituted for flow measuring devices.

(b)Either Normal or High Range monitor is required dependent upon activity in tank being released.

16.11.3-17 1112010a I Page 9-239

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Radioactive Effluent Monitoring Instrumentation 16.11.3 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. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarm/trip will occur prior to exceeding 10 times the limits of 10 CFR Part 20. The operability and use of this instrumentation is consistent 'Mth the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

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. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarm/trip will occur prior to exceeding applicable dose limits in SLC 16.11.2. The operability end use of this instrumentation is consistent wth the requirements of General Design Criteria 60, 63, and 64 _of Appendix A to 10 CFR Part 50.

For certain applicable cases, grab samples or flow estimates are required at frequencies bet\11/een every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> end every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> upon RIA removal from service. SLC 16.11.3 does not explicitly require Action (grab samples or flow estimates) to be initiated immediately upon RIA removal from service, when removal is for the purposes of sample filter changeouts, setpoint adjustments, service checks, or routine maintenance. Therefore, during the defined short, controlled outages, Action is not required.

For the cases in which Action is defined as continuous sampling by auxiliary equipment (Action L) initiation of continuous sampling by auxiliary sampling equipment requires approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. One hour is the accepted reasonable time to initiate collect and change samples.

Therefore. for the defined short, controlled outages (not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), Action is not required.

Failures such as blown instrument fuses, defective indicators, and faulted amplifiers are, in many cases, revealed by alarm or annunciator action. Comparison of output and/or state of independent channels measuring the same variable supplements this type of built-in surveillance. Based on experience in operation of both conventional and nuclear systems, when the unit is in operation, the minimum checking frequency stated is deemed adequate .

REFERENCES:

1. 10 CFR Part 20.

2. 10 CFR Part 50, Appendix A.

3. Offsite Dose Calculation Manual.

4. UFSAR, Section 7.2.3.4.

16.11.3-18 11120108 I Page 9-240

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Operational Safety Review 16.11.4 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.4 Operational Safety Review COMMITMENT Required sampling should be performed as detailed in Table 16.11.4-1.

APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.4.1 N/A N/A 16.11.4-1 o6t3Dl14 I Page 9-241

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection 10 ' of Lab Analysis for Waste

1. Decant Monitor a. Principal Gamma Composite Grab Sample <SE-06 µCilml (Ce-144)

Tank, Turbine Emillersl including prior to release of each <SE-07 µCilml (Other Gamma Nuclides)

Building Sump Dissolved Noble batch'h; <1E-05 µCilml (Dissolved Gases)

Monitor Tanks, Gases <1E-06 µCilml (1-131)

Waste and Recycle Monitor Tanks

b. Radiochemical Quarterly from all <SE-08 µCilml Analysis Sr-89 and composited batches111 Sr-90 C. Tritium Monthly Composite <1E-0511Cilml

d. Gross Alpha Activity Monthly Composite <1 E-07 µCilml 2 Unit Vent Sampling a. Iodine Spectrum<*> Continuous monitor. <1E-10 µCi/cc (1-133)6>

(Includes Waste weekly sample1' 1 <1E-12 µCi/cc (1-131)0>

Gas Decay Tanks.

Reactor Building Purges, Auxiliary b. Particu lates1' 1 Building Ventilation, Spent Fuel Pool i. Ce-144 & Mo-99 Weekly Composite'., <SE-10 µCi/ccO)(<)

Ventilation. Air Ejectors) ii. Other Principle Weekly Composite 1' 1 <1E-11 µCi/ecol Gamma Emitters (d) iii. Gross Alpha Monthly, using composite <1E-11 µCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-1111Ci/cc Analysis Sr-69, Sr-90 C. Gases by Principle Weekly Grab Sample <1 E-04 µCi/cc Gamma Emitters'" :

d. Tritium Weekly Grab Sample <1E-06 µCi/cc

3. Waste Gas Decay a. Principle Gamma Grab Sample prior to <1 E-04 µCi/cc (gases)

Tank Emitters"i release of each batch <1E-10 µCi/cc (particulates and iodines)

<SE-09 µCi/cc (Ce-144 and Mo-99)

b. Tritium Grab Sample prior to <1E-06 µCi/cc release of each batch

4. Reactor Building a. Principle Gamma Grab sample ea ch purge <1E-04 µCi/cc (gases)

Emitters 1, 1 <1E-10 µCi/cc (particulates and iodines)

<SE-09 µCi/cc (Ce-144 and Mo-99)

b. Tritium Grab sample each purge <1 E-06 µCi/cc 16.11.4-2 05130114 I Page 9-242

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection'b) of Lab Analysis for Waste

5. Not Used

6. #3 Chemical a. Principle Gamma Weekly Continuous <SE-07 µCi/ml Treatment Pond Emitters 1=> Composite 10>

Effluent11

b. 1-131 Weekly Continuous <1E-06 µCi/ml Cornposite 19l

c. Tlitium Monthly Continuous <1 E-05 µCi/ml Cornposite 1 1

d. Gross Alpha Monthly Continuous <1 E-07 ftCilml Activity Cornposite 19 l

e. Sr-89 & Sr-90 Quarterly Continuous <SE-08 µCi/ml Cornposite 1'11

f. Dissolved and Monthly Grab <1 E-05 µCi/ml Entrained gases (Gamma Emitters)

7. Radwaste Facility a. Iodine Spectrum<*! Continuous monitor, (1-133) <1 E-09 µCi/cc Ventilation weekly sample(,) (1-131) <1 E-11 µCi/cc

b. Particulate 1" 1 Ce-144 and Mo- Weekly Compositel*l <5E-10 µCi/cc*>

99 ii. Other Principle Weekly Composite 1' 1 <1 E-11 µCi/cc 1'1 Gamma Emillers" 1 iii. Gross Alpha Monthly, using composite <1 E-11 fl Ci/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 µCi/cc Analysis Sr-89.

Sr-90 C. Gases by Weekly Grab Sample <1 E-04 µCi/cc Prtnclple Gamma<dl Emitters

d. Tritium Weekly Grab Sample <1 E-06 µCi/cc 16.11.4-3 osI30114 I Page 9-243

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection 101 of Lab Analysis for Waste

8. Hot Machine Shop a. Iodine Spectrum Weekly Sample1' 1 (1-133) <1 E-10 µCi/ecol Ventilation (1-131) <1 E-12 µCi/cc0l

b. Particulate Ce-144 and Mo- Weekly Composite 1'l <5E-10 µCi/ccul(*<l 99 ii. Other Principle Weekly Compositer,i <1 E-11 µCi/cc 11 Gamma Emitters ldl iii. Gross Alpha Monthly, using composite <1E-11 µCi/cc Activity samples or one week iv. Radiochemical Quarterly Composite <1 E-11 µCi/cc Analysis Sr-89 ,

Sr-90

c. Gases by NA NA Principle Gamma Emitters

d. Tritium NA NA

9. Interim Radwaste a. Iodine Spectrum Weekly sample'"' (1-133) <1 E-10 µCi/cc 01 Building (1-131) <1E-12 µCi/cc 0l Ventilation

b. Particulate Ce-144 and Mo- Weekly Compositel*l <5E-10 µCi/cc 0>

99

<1 E-11 µCi/cc 01 ii. Other Principle Weekly Compositel*l Gamma Emittersl'i iii. Gross Alpha Monthly, using composite <1 E-11 µCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1 E-11 µCi/cc Analysis Sr-89, Sr-90 C. Gases by Weekly Grab Sample <1 E-04 µCi/cc Principle Gamma1" 1 Emitters

d. Tritium Weekly Grab Sample <1 E-06 !LCi/cc 16.11.4-4 06/30/14 I Page 9-244

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Operational Safety Review 16.11.4 (a) Samples shall be changed at least once per 7 days and analyses shall be completed wrthin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> alter changing, or alter removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown. startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply If (1) analyses show that the DOSE EQUIVALENT 1-131 concentration In the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3 (b) The LLD is defined for purposes of these commitments as the smallest concentration of radioactive material in a sample that would be detected with 95% probability with 5% probability of falsely condudlng that a blank observation represents a "real" signal.

For a particular measurement system (which may Include radiochemical separation) :

LLD= (2.71 / Tl + 4.65 l!u Ex V x 2.22E06 x Y x exp (-Ml)

Where :

LLD is the "a priori" lower limit of detection as defined above (as micro Curies per unit mass or volume).

so is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

Eis the counting efficiency (as counts per disintegration).

Vis the sample size (in units of mass or volume).

2.22E06 is the number of disintegrations per minute per micro Curie.

Y is the fractional radiochemical yield (when applicable),

), is the radioactive decay constant for the particular nuclide t,, t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples). NOTE: This assumes decay correction is applied (at the time of analysis) for the duration of sample collection, for the lime between collection and analysis and for the duration of the counting.

Additionally, it does not apply to isolated systems such as Waste Gas Decay Tanks and Waste Monitor Tanks.

Tis the sample counting lime in minutes Typical values of E. V, Y and l1 t should be used in the calculation.

II should be recognized that the LLD is an a priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the facl) limit for a particular measurement.

(c) The principal gamma emitters for which the LLD control applies include the fdlowing radionuclides:

Mn-54. Fe-59, Co-58, Co-60. Zn-65, Mo-99, Cs-134, Cs-137. and Ce-141. Ce-144 shall also be measured, but with a LLD of5E-06 µCi/ml. This list does not mean that only these nuclides are lo be considered. other gamma peaks that are identifiable. together with the above nuclides shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.

(d) The principal gamma emitters for which the LLD commitment applies exclusively are the following radionuclides: Kr-87 . Kr-88, Xe-133. Xe-133m, Xe-135. and Xe-138 for gaseous emissions and Mn-54, Fe-59. Co-58, Co-60, Zn-65.

Mo-99, Cs-134, Cs-137, Ce-141. and Ce-144 for particulates. This list does not mean that only these nuclides are lo be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides shall also be identified and reported.

(e) The ratio of lhe sample flow rate to the sampled stream fl011,1 rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with SLC 16.11.2.a, SLC 16.11.2.b.1, and SLC 16.11.2.b.2.

(fl 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 represenlative of the liquids released.

16.11.4-5 05130114 I Page 9-245

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Operational Safety Review 16.11.4 (g) To be representative of the quantities and concentrations of radioactive materials in liquid effluents. samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

(h) A batch release is the discharge of liquid wastes of a discrete volume. Prior lo sampling for analysis, each batch shall be isdated, and then thoroughly mixed, to assure representative sampling.

(i) A continuous release is the discharge ofliquid wastes of a non-discrete volume, e.g., from a volume of a system that has an input flow during the continuous release. Samples shall be analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> alter changing (on or after removal from sampler).

(i) When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the correspcnding LL Os may be increased by a factor of 10. Samples shall be analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (on or after removal from sampler).

(kl Ce-144 and Mo-99 LLD as approved by NRG SER dated January 16, 1984 (Reference 1).

16.11.4-6 05130114 I Page 9-246

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Operational Safety Review 16.11.4 NIA

REFERENCES:

1. Safety Evaluation Report dated January 16, 1984, supporting Amendment Nos.

125, 125, and 122 for Oconee Nuclear Station to revise Technical Specifications to incorporate changes to the Radiological Effluent Technical Specifications (RETS) in order to bring them into compliance with Appendix I of 10 CFR Part 50.

16.11.4-7 06/30/14 Page 9-247

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Solid Radioactive Waste 16.11.5 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.5 Solid Radioactive Waste COMMITMENT Radioactive wastes shall be processed and packaged to ensure compliance with the applicable requirements of 10 CFR Part 20, 10 CFR 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 10 CFR 61 licensed disposal site. Wastes shipped for off site processing in acco~dance with the processor's 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 10 CFR 61 waste form requirements.

• The PCP describes the administrative and operational controls used for the dewatering of wet radioactive wastes to meet 10 CFR 61 free standing water requirements .

• The process parameters used in establishing the PCP shall be based on demonstrated processing of actual or simulated liquid or \Net 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 16.11 .5-1 10130102 I Page 9-248

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Solid Radioactive Waste 16.11.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Applicable regulatory A.1 Suspend shipments of Immediately requirements for defectively packaged solidified or dewatered solid radioactive wastes 1Nastes are not from the site.

satisfied.

AND A.2 Initiate action to correct Prior to next shipment for PCP, procedures, or disposal of solidified or solid waste equipment dewatered wastes as necessary to prevent recurrence.

B. A solidification test as 8.1 Suspend solidification of Immediately described in the PCP the batch under test and fails to verify follow PCP guidance for Solidification. test failures until solidification of the batch is verified by subsequent tests.

AND 8.2 The PCP shall be Prior to next solidification modified as required to for shipment of waste for assure Solidification of disposal at a 10 CFR 61 subsequent batches of disposal site waste.

16.11.5-2 10130102 I Page 9-249

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Solid Radioactive Waste 16.11.5 CONDITION REQUIRED ACTION COMPLETION TIME C. With solidification or C.1 Reprocess or repackage Prior to shipment for dewatering for disposal the waste in accordance disposal of the not performed in with PCP requirements. inadequately processed accordance with the waste that requires PCP. OR solidification or dewatering C.2 Follow PCP or procedure guidance 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 to In a time frame that equipment incapable of OPERABLE status or supports the meeting commitment or provide for alternative commitment not in service. capability to process wastes as necessary to satisfy all applicable disposal requirements.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.5.1 The Process Control Program shall be used Every tenth batch of each to verify the solidification of at least one type of radioactive waste representative test specimen from at least to be solidified.

every tenth batch of each type of radioactive waste to be solidified for disposal at a 10 CFR 61 disposal site.

16.11.5-3 10130102 I Page 9-250

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Solid Radioactive Waste 16.11 .5 This commitment implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of 10 CFR Part 50, Appendix A and requirements to use a Process Control Program to meet applicable 10CFR61 waste form criteria for solidified and dewatered radioactive wastes.

REFERENCES:

1. 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities".

2. 10 CFR Part 50, Appendix A.

3. 10 CFR20, "Standards for Protection Against Radiation".

4. 10 CFR61, "Licensing Requir~ments for Land Disposal of Radioactive Waste".

5. 10 CFR71, "Packaging and Transportation of Radioactive Materials".

6. DPCo Process Control Program Manual.

7. NRC Generic Letter 87-12, "Compliance with 10 CFR Part 61 And Implementation Of the Radiological Effluent Technical Specifications (Rets) and Attendant Process Control Program (PCP)".

8. NRC Generic Letter 89-01, "Implementation of Programmatic Controls for Radiological Effluent 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".

16.11.5-4 10130102 I Page 9-251

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radiological Environmental Monitoring 16.11.6 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11 .6 Radiological Environmental Monitoring COMMITMENT a. The radiological environmental monitoring samples shall be collected in accordance with Table 16.11.6-1 and shall be analyzed pursuant to the requirements of Tables 16.11.6-1 and 16.11.6-2.

b. A land use census shall be conducted and shall identify the location of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of eight kilometers (five miles). Broad leaf vegetation sampling shall be performed at the site boundary in the direction sector with the highest 0/Q in lieu of the garden census.

c. Analyses shall be performed on radioactive materials supplied as part of an lnterlaboratory Comparison Program. A summary of the results obtained as part of the lnterlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report. The lnterlaboratory Comparison Program shall be described in the Annual Radiological Environmental Operating Report.

d. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report.

---

NOTE------------------------------------------

If samples required by Commitment part a, become permanently unavailable from any of the required sample locations, the locations from which samples were unavailable may then be deleted from the program provided replacement samples vvere obtained and added to the environmental monitoring program, if available . These new locations will be identified in the Annual Radioactive Effluent Release Report.

APPLICABILITY: At all times 16.11.6-1 1118113 I Page 9-252

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radiological Environmental Monitoring 16.11.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radiological A.1 Submit a description of May 15 of following environmental the reason for not calendar year monitoring program is conducting the program not conducted as as required and plans to required. prevent a recurrence shall be included in the Annual Radiological Environmental Operating Report.

8. Land use census 8.1 -----------NOTE-----------

identifies a Location The sampling location which yields a having the lowest calculated dose or dose calculated dose or dose commitment (via the commitment (via the same exposure same exposure pathway) 20% greater pathway) may be than a location from deleted from this which samples are monitoring program currently being after October 31 of the obtained. year in which this land use census was conducted.

Add new location to the 30 days radiological environmental monitoring program.

AND 8.2 Identify new locations in April 30 of following the next Annual calendar year Radioactive Effluent Release Report.

16.11.6-2 1118113 I Page 9-253

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radiological Environmental Monitoring 16.11.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. lnterlaboratory C.1 Report corrective May 15 of following Comparison Program actions in the Annual calendar year analyses not performed Radiological as required. Environmental Operating Report.

D. Radioactivity level D.1 Prepare and submit a 30 days resulting from plant Special report that effluents in identifies the cause for environmental sampling exceeding the limits and medium at a specified defines the corrective location in excess of actions to be taken to reporting limits of Table reduce radioactive 16.11 .6-3 when effluents so that the averaged over a potential annual dose to calendar quarter. a MEMBER OF THE PUBLIC is less than the calendar year limits of SLC 16.11 .1 or 16.11.2.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.6.1 Conduct land use census during growing 12 months season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

16.11 .6-3 1118113 I Page 9-254

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Number of Exposure Pathway and/or Sampling and Collection Sample Time and Frequency of Analysis Sample Frequency (d)

Locations (b)

1. AIRBORNE Radioiodine and 5 Continuous sampler Radioiodine canister:

Particulates operation with sample 1-131 analysis weekly. Particulate collection weekly, or sampler: Gross beta radioactivity more frequently if analysis follo'Ning filter change; and required by dust loading. gamma isotopic analysis of composite (by location) quarterly. (c)

2. DIRECT RADIATION 40 Quarterly. Gamma dose quarterly.

3. WATERBORNE

a. Surface 2 Composite (a) sample Gamma isotopic analysis monthly.

over a 1-rnonth period.

Composite for tritium analysis quarterly.

b. Drinking 3 Composite (a) sample Composite for gross beta and gamma over a 1-rnonth period. isotopic analyses monthly.

Composite for tritium analysis quarterly.

C. Sediment from 2 Semiannually. Gamma isotopic analysis Shoreline semiannually.

16.11.6-4 1118113 I Page 9-255

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Number of Exposure Pathway and/or Sampling and Collection Sample Time and Frequency of Analysis Sample Frequency (d)

Locations (b)

4. INGESTION

a. Milk 4(e) Semimonthly when Gamma isotopic and 1-131 analysis animals are on pasture; semimonthly Vllhen animals are on monthly at other times. pasture; monthly at other times

b. Fish 2 Semiannually. One Gamma isotopic analysis sample each semiannually on edible portion.

comme"rcially and recreationally important species.

c. Broad-leaf 2 Monthly. Gamma isotopic analysis monthly.

Vegetation (a) Composite samples shall be collected by collecting an aliquot at intervals not exceed ing 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

(b) Sample locations are identified in the ODCM.

(c) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(d) Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment. If the latter, every effort shall be made to oomplete corrective action prior to the end of the next sampling period.

(e) Samples from milking animals in three locations within 5 km distance having the highest dose potential. If there are none, then one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per year. One sample from milking animals at a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.

16.11 .6-5 1118113 I Page 9-256

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)

Airborne Fish Broad-leaf Water Particulate or Milk Sediment Analysis (pCi/kg, Vegetation (pCi/I) Gases (pCi/Q (pCi/kg, dry)

Ci/m~ \/Yet) (pCi/kg, wet)

Gross Beta 4 1E-02 H; 2,000 Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 15 Nb-95 15 1-131 15(b) ?E-02 60 Cs-134 15 5E-02 130 15 60 150 Cs-137 18 6E-02 150 18 80 180 Ba-140 15 60 La-140 15 15 (a) The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample with 95% probability of detection and IIVith 5% probability of falsely conclud ing that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD= (2. 71 IT) + 4.65 St.

Ex V x 2.22 x Y x exp (-A.!i t)

Where:

LLD is the IOI/Yer limit of detection as defined above (as pCi 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) 16.11.6-6 1118113 I Page 9-257

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)

E is the counting efficiency (as counts per disintegration)

Vis 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) 11, is the radioactive decay constant for the particular radionuclide l!i. tis the elapsed time between sample collection (or end of the sample collection period) and time of counting T is the sample counting t ime in minutes Typical values of E, V, Y and,',, t should be used in the calculation .

The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as 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, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances, may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Rad iological Environmental Operating Report.

(b) LLD for gamma isotopic analysis for 1-131 in drinking water samples. Low level 1-131 analysis on drinking water will not be routinely performed because the calculated dose from 1-131 in drinking water at all locations is less than 1 mrem per year. Low level 1-131 analyses will be performed if abnormal releases occur which could reasonably result in > 1 pCi/liter of 1-131 in drinking water. For low level analyses of 1-131 an LLD of 1 pCi/liter will be achieved.

(c) Other peaks wh ich are measurable and identifiable, together with the radionuclides in Table 1611 .6-2, shall be identified and reported.

16.11.6-7 1118113 I Page 9-258

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/201 8 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples (c) (d)

Airborne Water Particulate or Fish Broad-leaf Milk Analysis Vegetation (pCi/Q Gases (pCi/kg, wet) (pCi/1)

Ci/m' (pCi/kg, wet)

H-3 2E04(a)

Mn-54 1E03 3E04 Fe-59 4E02 1E04 Co-58 1E03 3E04 Co-60 3E02 1E04 Zn-65 3E02 2E04 Zr-Nb-95 4E02 1-131 2(b) 0.9 3 1E02 Cs-134 30 10 1E03 60 1E03 Cs-137 50 20 2E03 70 2E03 Ba-La-140 2E02 3E02 (a) For drinking water samples. This is 40 CFR Part 141 value.

(b) If low level 1-131 analyses are performed.

(c) Report shall be submitted when any single radionuclide exceeds the reporting level in Table 16.11.6-3 or when more than one of the radionuclides in Table 16.11.6-3 are detected in sampling medium and concentration (1) + concentration (2/ + . .. ~ 1.0 reporting level (1) reporting level (2)

(d) Report shall be submitted when radionuclides other than those in table 16.11.6-3 are detected and are the result of plant effluents if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equa l to or greater than the calendar year limits of SLC 16.11 .1 or 16.11.2.

16.11.6-8 1118113 I Page 9-259

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radiological Environmental Monitoring 16.11 .6 The environmental monitoring program required by this commitment provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program 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 modeling of exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Follov.ing this period, program changes may be initiated based on operational experience.

The detection capabilities required by Table 16.11.6-2 are considered optimum for routine environmental measurements in industrial laboratories. The specified lovver limits of detection correspond to less th,rn the 10 CFR 50. Appendix I, design objective dose-equivalent of 45 mrem/year for atmospheric releases to the most sensitive organ and individual. The land use census commitment is provided to assure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are provided if required by the results of this census.

The requirements for participation in an lnterlaboratory Comparison Program is provided to assure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

With the level of radioactivity in an environmental sampling medium at a specified location exceeding the reporting levels of Table 16.11 .6-3 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 action to be 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 SLC 16.11 .1 or SLC 16.11 .2. When more than one of the radionuclides in Table 16.11 .6-3 are detected in the sampling medium, this report shall be submitted if concentration (1) + concentration (2) + ... ;,; 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 16.11 .6-3 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 from all radionuclides is equal to or greater than the calendar year limits of SLC 16.11.1 or SLC 16.11 .2. 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 required by Technical Specification 5.6.2. The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in the 30-day Special Report.

16.11 .6-9 1118113 I Page 9-260

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radiological Environmental Monitoring 16.11.6 The following requirement(s) were relocated from the CTS 6.4.4.f during the conversion to ITS.

The station shall have a program to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in UFSAR Chapter 16, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include 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 (equired by the results of this census; and,

3. Participation in an lnterlaboratory 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.

REFERENCES:

1. 10 CFR Part 50, Appendix I.

2. Offsite Dose Calculation Manual.

16.11.6-10 1118113 I Page 9-261

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Dose Calculations 16.11 .7 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.7 Dose Calculations COMMITMENT The annual (calendar year) dose or dose commitment, to any Member of the Public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to :; 25 mrems to the total body or to any organ, except the thyroid, which shall be limited to:; 75 mrems.

APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated doses from A.1 Determine by None the release of calculation , including radioactive materials in direct radiation liquid or gaseous contributions from the effluents exceeding reactor units and from twice the limits of SLC outside storage tanks, 16.11 .1.b, SLC whether the limits of 16.11 .2.b.1, or SLC Commitment 16.11 .7 16.11.2.b.2 have been exceeded.

16.11 .7-1 01131100 I Page 9-262

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Dose Calculations 16.11.7 CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose -------------------NOTE---------------

exceeds limits of Th is Special Report, as defined Commitment 16.11. 7. in 10 CFR Part 20.2203(a), 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 the levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations.

8.1 Prepare and submit to the Commission a 30 days Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the specified limits and includes the schedule for achieving conformance with the specified limits.

16.11.7-2 01131100 I Page 9-263

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Dose Calculations 16.11 .7 CONDITION REQUIRED ACTION COMPLETION TIME C.1 -----------NOTE-----------

C . Calculated dose exceeds limit of Submittal of the report is considered a timely Commitment 16.11 .7.

request, and a variance is granted until staff action on the request is complete.

Release condition resulting in violation of 40 CFR 190 not Include a request for a 30 days from exceeding corrected at time of variance in accordance the limit report submittal.

with the provisions of 40 CFR Part 190.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11 .7.1 Determine cumulative dose contributions from 31 days liquid effluents in accordance with Offsite Dose Calculation Manual.

SR 16.11.7.2 Determine cumulative dose contributions from 31 days gaseous effluents in accordance with Offsite Dose Calculation Manual.

The dose commitment is provided to assure that the release of radioactive material in liquid and gaseous effluents will be kept "as low as is reasonably achievable ." The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix I in that conformance with the guides of Appendix I is to be shown by calculations and procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

16.11.7-3 03/27/99 Page 9-264

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Dose Calculations 16.

11.7 REFERENCES

1. 10 CFR Part 20.

2. 40 CFR Part 190.

3. Offsite Dose Calculation Manual.

4. 10 CFR Part 50, Appendix I.

16.11.7-4 01131100 I Page 9-265

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Reports 16.11.8 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.8 Reports COMMITMENT Special reports shall be submitted to the Regional Administrator, Region 11, within the time period specified for each report . These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable SLC:

a. Radioactive Liquid Effluents, Dose, SLC 16.11 .1.b Liquid Waste Treatment, SLC 16.11 .1.c

b. Radioactive Gaseous Effluents, Dose, SLC 16.11 .2.b Gaseous Radwaste Treatment, SLC 16.11.2.c

c. Radiological Environmental Monitoring Program, SLC 16.11 .6.a, b, and c

d. Land Use Census , SLC 16.11.6.d

e. Dose Calculations, SLC 16.11.7 APPLICABILITY: Af. all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Individual milk samples A.1 Submit plan advising 7 days show 1-131 the N RC of the concentrations of 1O proposed action to picocuries per liter or ensure the plant related greater. annual doses will be within the design objective of 45 mrem/yr to the thyroid of any individual.

16.11.8-1 12121,os I Page 9-266

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Reports 16.11.8 CONDITION REQUIRED ACTION COMPLETION TIME B. Milk samples collected 8.1 Submit a plan advising 30 days over a calendar quarter the NRC of the show 1-131 average proposed action to concentrations of 4.8 ensure the plant related picoCuries per liter or annual doses will be greater wthin the design objective of 45 mrem/yr to the thyroid of any individual.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.8.1 NA NA Reference applicable commitments.

REFERENCES:

1. 10 CFR Part 20.

2. 40 CFR Part 190.

3. Offsite Dose Calculation Manual.

16.11.8-2 1212110s I Page 9-267

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Release Report 16.11 .9 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11 .9 Radioactive Effluent Release Report COMMITMENT The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

A single submittal may be made for a multiple unit station. The submittal shall combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit.

The Annual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid vvaste released from the station during the reporting period .

The annual Radioactive Effluent Release Report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter.

The Annual Radioactive Effluent Release Report shall include the following information for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents:

a. A description of the event and equipment involved;

b. Cause(s) for the unplanned release;

c. Actions taken to prevent recurrence ; and,

d. Consequences of the unplanned release .

The Annual Radioactive Effluent Release Report shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the station during each calendar quarter. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The annual average meteorological conditions shall be used for determining the gaseous pathway doses. Approximate and conservative approximate methods are acceptable. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual.

The Annual Radioactive Effluent Release Report shall include an explanation of why the inoperability of liquid or gaseous effluent monitoring instrumentation out of service for greater than 30 days was not corrected in a timely manner per SLC 16.11.3.

16.11.9-1 03122110 I Page 9-268

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Release Report 16.11.9 The Annual Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the report period:

a. Total container volume (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., spent resin, compacted dry waste evaporator bottoms);

e. Number of shipments; and,

f. Solidification agent (e.g., cement, or other approved agents (media)).

The Annual Radioactive Effluent Release Report 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 Annual Radioactive Effluent Release Report shall include any changes made during the reporting period 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.

The Annual 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 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.

APPLICABILITY: Af all times.

16.11.9-2 03122110 I Page 9-269

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Effluent Release Report 16.11 .9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. N/A A.1 N/A N/A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11 .9.1 NIA NIA NIA

REFERENCES:

1. Oconee ITS.

2. Offsite Dose Calculation Manual.

16.11 .9-3 03122110 I Page 9-270

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radiological Environmental Operating Report 16.11.10 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.10 Radiological Environmental Operating Report COMMITMENT Routine 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 Report shall include summaries, interpretations. and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports stiall also include the results of the land use censuses. If harmful effects are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The Annual Radiological Environmental Operating Report shall include a summary of the results obtained as part of the required lnterlaboratory Comparison Program. The lnterlaboratory Corrparison Program shall be described in the Annual Radiological Environmental Operating Report.

The Annual Radiological Environmental Operating Report shall include summarized and tabulated results of the radiological environmental samples required by SLCs taken during the report period. In the event that some 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 practical in a supplementary report.

The initial report shall also include the following : a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and, the result of land use censuses . Subsequent reports shall describe all substantial changes in these aspects.

APPLICABILITY: At all times.

16.11.10-1 05114114 I Page 9-271

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radiological Environmental Operating Report 16.11.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.10.1 NA NA NA

REFERENCES:

1. Oconee ITS

2. Offsite Dose Calculation Manual 16.11.10-2 05114114 I Page 9-272

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Iodine Radiation Monitoring filters 16.11 .11 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.11 Iodine Radiation Monitoring Filters COMMITMENT Assure that the iodine radiation monitoring filters perform their intended function.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.11.1 Remove and replace iodine radiation 30 days of operation monitoring filters in RIA-44.

SR 16.11.11.2 Discard spare iodine radiation monitoring After 24 months of shelf filters. life.

The purpose of this commitment is to assure the reliability of the iodine radiation monitoring ct)arcoal filters.

REFERENCES:

1. Oconee CTS Amendment No. 3/3 SER date July, 1974.

16.11.11-1 03/27/99 Page 9-273

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Material in Outside Temporary Tanks Exceeding Limit 16.11.12 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.12 Radioactive Material in Outside Temporary Tanks Exceeding Limit COMMITMENT The quantity of radioactive material in outside temporary storage tanks shall not exceed the limit specified in ITS 5.5.13.c.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The quantity of A1 Suspend addition of Immediately radioactive material in radioactive material to outside temporary tank.

storage tank not within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.12.1 Verify the quantity of radioactive material Within 7 days after contained in each of the outside temporary addition of radioactive tanks is vvithin the limit by analyzing a materials to an representative sample of the tanks' contents. outside temporary tank OR Verify the quantity of radioactive material in Prior to addition of each of the outside temporary tanks does not radioactive materials to result in exceeding the limit by analyzing a an outside temporary representative sample of radioactive material tank.

to be added.

16.11.12-1 04110103 I Page 9-274

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018 Radioactive Material in Outside Temporary Tanks Exceeding Limit 16.11 .12 The requirement(s) of this SLC section were relocated from CTS 3.9.1.c during the conversion to ITS.

The tanks included in this specification are all those outdoor radwaste liquid storage 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 a tank's contents, the resulting concentrations \NOuld be less than the limits of 10CFR 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 N/A 16.11.12-2 04110103 I Page 9-275

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018- 12/31/2018 Radioactive Material in Waste Gas Holdup tank Exceeding Limit 16.11.13 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.13 Radioactive Material in Waste Gas Holdup Tank Exceeding Limit COMMITMENT The quantity of radioactive material in the Waste Gas Holdup tanks shall not exceed the limit specified in ITS 5.5.13.b.

APPLICABILITY: Af all times.

ACTIONS

---

NOTE----------------------------------------------------------

Se pa rate Condition Entry is allowed for each tank.

CONDITION REQUIRED ACTION COMPLETION TIME A. The quantity of A.1 Suspend addition of Immediately radioactive material in radioactive material to the Waste Gas Holdup tank.

tank not within limit.

AND A.2 Reduce tank contents 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.13.1 Verify quantity of radioactive materials in each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when tank is tank is within limit. being filled The requirement(s) of this SLC section were relocated from CTS 3.10.1.b and 3.10.1.c during the conversion to ITS.

16.11.13-1 03/27/99 Page 9-276

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Material in Waste Gas Holdup tank Exceeding Limit 16.11 .13 Restricting the quantity of radioactivity contained in each waste gas holdup tank provides assurance that in the event of an uncontrolled release of the tank contents, the resulting total body exposure to an individual at the exclusion area boundary will not exceed 0.5 rem.

REFERENCE U FSAR, Section 15. 10 16.11.13-2 03/27/99 Page 9-277

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Explosive Gas Mixture 16.11 .14 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11 .14 Explosive Gas Mixture COMMITMENT The concentration of Hydrogen in the Waste Gas Holdup Tanks shall be

$ 3% by volume .

APPLICABILITY: At all times.

ACTIONS

---

------------------NOTE--------------- --------------------------------------

Se pa rate Con.dition Entry is allovved for each tank.

CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of A.1 Reduce Concentration 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Hydrogen in Waste of Hydrogen to within Gas Holdup tank is > limit.

3% and$ 4% by volume .

B. Concentration of 8.1 Suspend addition of Immediately Hydrogen in Waste waste gases to tank .

Gas Holdup tank is>

4% by volume. AND 8.2 Reduce Concentration 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of Hydrogen to within limit.

16.11.14-1 03/27/99 Page 9-278

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Explosive Gas Mixture 16.11.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.14.1 Verify Hydrogen concentration in Waste Gas 5 times/week on each Holdup Tank is:,; 3% by volume. tank when in service once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after isolation of the tank The requirement(s) of this SLC section were relocated from CTS 3 .10.2 and Table 4.1-3, Item 13 during the conversion to ITS.

This Commitment is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup Tanks is maintained below the flammability limits of hydrogen. (Administrative controls are used to prevent the hydrogen concentrations from reaching the flammability limit.) These controls include sampling each tank 5 times a week while in service, and/or once in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after isolation of the tank; injection of dilutants to reduce the concentration of hydrogen below its flammability limits provides assurance that the releases of radioactive material will be controlled in conformance with the requirements of GDC 60 of Appendix A to CFR Part 50.

REFERENCES N/A 16.11.14-2 03/27/99 Page 9-279

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 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 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 The Oconee Nuclear Station PCP was revised in 2018. The revised PCP is included in this attachment.

The summary of changes for the revision made in 2018 is below:

This revision 16 is essentially a rewrite of the entire document, retaining the general structure with changes in every section. Ref: (ORR 02212730)

The previous PCP documents for the DEC fleet [ONS, MNS, CNS] included the Corporate PCP and Appendices A-H for the remaining documents. The revision of the Corporate PCP, the site PCPs, Appendix A: ONS PCP, Appendix B: MNS PCP and Appendix C: CNS PCP are being completed concurrently. The convention of using Appendices for the site PCPs has been removed and the document numbers in Fusion for the revised documents are ONS PCP, MNS PCP and CNS PCP. The document titles in Fusion are ONS Process Control Program, MNS Process Control Program and CNS Process Control Program. The remainder of the Appendices D-H are being superseded by the DEC Corporate PCP through incorporation of the still applicable guidance and administrative processes or replaced using other fleet governing Document Control programs and the document administrative processes in our electronic resources. e.g., EDMS, CAS.

The Corporate PCP document title was changed to reflect applicability of the document to DEC sites only. [ONS, MNS, CNS]

The cover page and approvals will be generated using the Fusion E-Signature process.

Below is a summary by section of the types of changes made.

1.

Introduction:

Purpose:

Edited to simplify wording, clarify focus, reduce redundant information addressed elsewhere in the document, and to distinguish between the use of in-house employees and programs and the use of contracted service providers

• Deleted details and specificity from references that is not needed

• Updated the description and location of DEC PCP guidance documents

2. Applicability:

• Made references more generic rather than specific to reduce future changes

• Edited wording to clarify differences in how the requirements differ for LLW being placed in final waste form onsite and shipped for direct disposal and LLW being shipped to an off- site processor Page 10-2

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

• Updated wording for mixed waste, waste oil and packaging for interim storage

3. References

• Updated References and reorganized to consolidate lists

• Added new post-merger documents

4. Definitions

• Updated "Solidification" wording to clarify the current practices in meeting 10CFR61 waste form stability requirements

• Clarified the definition of "Unwatering" to include synonyms that may be used interchangeably, "gross dewatering", "dewatering to loss of vacuum"

• Boundary Conditions/ Acceptance Criteria: removed unnecessary details for current solidification practices, added filter packaging in disposal containers designed to remove water from the container

• Updated Topical report wording since the NRC no longer approves them

5. Responsibilities

• Changed specific references to position and group names to program roles where feasible to mitigate impact of continuous changes in nuclear organization and program ownership.

• Removed references to groups that no longer have PCP involvement throughout thedocument.

(e.g., Chemistry, Nuclear Supply Chain)

6. Administration of PCP and support documents

• Removed references to Appendix F that is being deleted and incorporated guidance that is still applicable and needed

• Incorporated updated revision and minor change guidance from Appendix F

• Incorporated updated approval guidance for DEC PCP documents

• Updated PCP ARERR guidance Page 10-3

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

• Updated record retention guidance

• Deleted PCP section "Periodic cross checks & comparisons" created by PIP 0-03-0624 (ONS FSL Failure). The CAPR change is described in NTM 02125727 (ONS PIOC meeting minutes & approval) and CR#: 01740840-29. ONS PIOC approved this change based on changes since the 2003 event, including ONS improvements in equipment, and procedures, the addition of formal processes in the PCP documents and consistency of current equipment and processes at the DEC sites.

• Updated PCP implementing procedure requirements

7. Updated approval process for QA Approved Suppliers

8. PCP Requirements for Vendor Processes and Services

• Editorial changes to reflect current administrative programs and processes.

• Updated document references

• Editorial changes to simplify wording and make more generic.

• Clarified use of QA Approved Suppliers

9. PCP Dewatering Process Description

• Updated use of filter packaging in disposal containers designed to remove water from the container to clarify process

• Clarified wording for guidance from 2003 ONS root cause CAPRs

• Changed wording (See step 9.3.3.5) to reflect ONS PIOC approved revision of PIP 0 0624 CAPR, CR# 01740840-04. Changed a constraint that is not applicable to the enhanced Self Engaging Dewatering System (SEDS) technology now being used. (see NTM 02125727) The vendor procedure for the SEDS does not include the requirement to use the bottom dewatering laterals to compact the media. This is only applicable to the Universal Fill Head technology that was the original type of equipment used in the 1985 liner dewatering Topical Report testing performed by EnergySolutions (then Chem-Nuclear Topical Report CNSI-DW-1111 8-01-P-A)

• Reduced inclusion of SLC Remedial Action Requirements details

10. PCP Solidification Process Description Page 10-4

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018

• Rewrote entire section deleting the detailed content that was required in the original implementation of 10CFR61

• Updated references to current requirements Page 10-5

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

~DUKE

~ ENERGY.

Facility Code : NGD Applicable Facilities : CN;MC;ON Document Number : DEC Corporate PCP Document Revision Number : 016 Document EC Number :

Change Reason : DRR 02212730 Document Title : DEC Corporate Process Control Program Vaught, David L Preparer 11/26/2018 Hammel, Lee A . PCP SME Reviewer 11/26/2018 Bowser, Ricky A. PCP SME ONS RP 11/28/2018 Wald, Johnny D PCP SME ONS Operations 11/26/2018 Reid, Orlando M PCP SME MNS Operations 11/27/2018 Litaker, Jeffrey R PCP SME MNS RP 11/26/2018 Williams, Doug PCP SME CNS Operations 11/30/2018 Campbell, Darcy L. PCP SME CNS RP 11/26/2018 Tate, Michael S Approver Mgmt ONS Operations 12/3/2018 Jackson, Patrick R Approver Mgmt MNS Operations 12/17/2018 Eurey, Chad M PCP SME CNS Operations 12/5/2018 Curry, Clark E Approver Plant Manager CNS 11/30/2018 Haynes, Larry E Approver Mgmt Fleet Scientific Services 11/30/2018 Notes:

Page 10-6

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

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({; ENERGY.

Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP Revision 16 (ORR 02212730}

Page 10-7

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP TABLE OF CONTENTS

1. INTRODUCTION .......................................................................................................................... 1 1.1 Purpose ........................................................................................................... ...................... 1 1.2 Description of Duke Energy PCP Documents .......................................... ...................... 1 1.3 Radioactive Wast.e Process Control Program Document Location....... ...................... I

2. APPLICABILITY ........................................................................'................................................. 2 2.1 Liquid and Wet Radioactive Waste Disposal... ............................................................... 2 2.2 Mixed Wast.e ........................................................................................................................ 2 2.3 Radioactive Wast.e Oil ................................................................... ...... .... ........................... 3 2.4 Radioactive Wast.e Interim Storage .................................................................................. 3

3. REFERENCES ............................................................................................................................. 3 3.1 Regulatory Requirements .................................................................................................. 3 3.2 Regulatory Guidance and lndust.ry Standards ............................................................... 4 3.3 DEC License Documents Referencing the PCP ............................................................ 5 3.4 DEC PCP Interfaces With Other Programs .................................................................... 5

4. DEFINITIONS ............................................................................................................................... 6 4.1 Safety Analysis Report (SAR) ........................................................................................... 6 4.2 Selected Licensee Commitments (SLCs) ....................................................................... 6 4.3 10CFR Part 61 "Licensing Requirements for Land Disposa l of Radioactive Waste"6 4.4 Free Standing Liquid (FSL) ............................................................................................... 6 4.5 Liquid Radioactive Wastes ....................... .......................................................... ............... 6 4.6 Wet Radioactive Wastes .................................................................................................... 6 DEC Corporate PCP Rev.16 Page 10-8

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018 Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 4.7 Solidification ........................... .............................................................................................. 6 4.8 High Integrity Container (HIC) ............... ............................................................................ 7 4.9 Dewatering ........... ...... .......................................................................................................... 7 4.10 Unwatering ("Gross Dewatering", "dewatering to loss of vacuum") ............................ 7 4.11 Mixed Waste .. ...................................................................................................................... 8 4.12 QA Approved Supplier List ................................................................................................ 8 4.13 Waste Batch ......................................................................................................................... 8 4.14 Waste Batch Mixing ........... ................................................................................................. 8 4.15 Process Parameters ........................................................................................................... 8 4.16 Boundary Conditions/ Acceptance Criteria ..................................................................... 8 4.17 PCP Topical Report (PIPs 0-03-0624, M-03-2515, C-03-3385) ................................. 9

5. DEC RESPONSIBILITIES ........................................................................................................ 10 5.1 Process Control Program Content and Implementation ............................................. 10 5.2 Oversight and Audits ........................................................................................................ to 5.3 DEC PCP Responsibilities ............................................................................................... 10

6. ADMINISTRATION OF THE DEC PCP AND SUPPORT DOCUMENTS ........................ 11 6.1 PCP Changes: Revisions and Minor Changes ............................................................. I l 6.2 PCP Revision Reports to the NRC ................................................................................. 13 6.3 PCP Document Revision Record Retention Requirements ................... .................... 13 6.4 PCP Implementing Procedure Requirements ............................................................... 13

7. APPROVAL PROCESS FOR QA APPROVED SUPPLIERS ............................................ 14 7.1 Technical Review and Approval ..................................................................................... 14 DEC Corporate PCP ii Rev.16 Page 10-9

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018 Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP

8. PCP REQUIREMENTS FOR VENDOR PROCESSES AND SERVICES ........................ 14 8.1 Topical Report (or equivalent) .................................... ................................. ...... .............. 14 8.2 10CFR61 Waste Form Compliance ........................................................... ............... .... 15 8.3 10CFR61 Waste Classification Compliance .................................................................. 15 8.4 Minimum Requirements for Onsite Process Vendors ............................................... .. 15 8.5 Minimum Requirements for Offsite PCP Process Vendors .. ............................ ,......... 16

9. PCP DEWATERING PROCESS DESCRIPTION ................................................................. 16 9.1 Dewatering Mechanical Filters (e.g., cartridge, bag, membrane) ............................. 16 9.2 Dewatering Slurries ....................................... ............ ......... ......... ...................................... 17 9.3 Additional Conservatism in Slurry Dewatering Procedures to Address Variation from the Topical Report (PIP 0-03-0624, M-03-2515, C-03-3385)........................... 18 9.4 Dewatering Process Requirements ............................. ................................................... 20 9.5 Product Verification ............... ..... .................................. ..................................................... 21 9.6 Dewatering Document Retention .......................................................... ...... .................... 22 10.PCP SOLIDIFICATION PROCESS DESCRIPTION ............................................................ 22

11. REVISION

SUMMARY

..............................................................."' ............................................ 23 DEC Corporate PCP iii Rev.16 Page 10-10

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

.-(~DUKE

~ ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP

1. INTRODUCTION 1.1 Purpose The Duke Energy Carolinas (DEC) Radioactive Waste Process Control Program (PCP) addresses the requirements for solid radioactive waste referenced in Selected Licensing Commitments and Technical Specifications for DEC nuclear stations.

1.1.1 A Process Control Program (PCP) describes the administrative and operational controls used for the solidification of liquid or wet radioactive wastes and the dewatering of wet radioactive wastes. Its purpose is to assure that the final disposal waste product meets applicaQle Federal, State and Disposal Site waste form requirements for burial at a 10CFR61 licensed Low-Level Waste (LLW) disposal site.

1.1.2 Waste processing (solidification or dewatering) equipment and services may be provided by Duke Energy or approved vendors. Vendor services may be performed onsite or offsite. Any process used shall meet all applicable requirements of the Process Control Program.

1.1.3 For waste processed onsite for direct disposal it is the responsibility of the LLW generator/ shipper to ensure that PCP requirements are met and that the condition of the waste is acceptable upon arrival at the disposal site.

1.1.4 For waste packaged and shipped to an approved off-site processor contracted to meet the requirements for direct disposal at a 10CFR61 licensed Low-Level Waste (LLW) disposal site, the final waste form requirements are not applicable prior to shipment to the processor for final processing and disposition.

1.2 Description of Duke Energy PCP Documents 1.2.1 [ONS, MNS, CNS] The DEC PCP guidance is contained in the following documents published in the EDMS

• DEC Corporate PCP: Program requirements

• DEC Site PCP Documents: PCP Implementing documents 1.2.2 [BNP, HNP, RNP] The Duke Energy Progress (DEP) PCP documents are site specific licensing documents maintained by the DEP site PCP SM Es 1.3 Radioactive Waste Process Control Program Document Location The Duke Radioactive Waste PCP documents satisfy NRC requirements for a Process Control Program. They are published electronically as controlled copy files of the documents maintained in the Duke EDMS.

DEC Corporate PCP 1 Rev.16 Page 10-11

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

'° ENERGY.

~~DUKE Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP

2. APPLICABILITY 2.1 Liquid and Wet Radioactive Waste Disposal 2.1 .1 Licensing documents, e.g., Final Safety Analysis Reports (FSAR), tech Specs and SLCs, require that the Solid Radwaste System be operated in a manner to assure compliance with requirements for the transportation and disposal of LLW. They refer to the NRC requirement to follow a process control program for 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 such that the final product meets all applicable disposal site requirements.

l 2.1.2 These "Process Control Program requirements are applicable to all liquid or wet radioactive wastes that are being prepared for direct disposal at a 10CFR61 LLW disposal facility.

2.1.3 Radioactive wastes shipped for off-site processing in accordance with the processor's specifications and transportation requirements are not required to be solidified or dewatered to meet disposal requirements prior to shipment to an offsite processor. They are not subject to the final waste form solidification or devvatering requirements of this PCP as specified in 10CFR61 when an offsite processor is contracted to perform the PCP processing for disposal.

2.2 Mixed Waste 2.2.1 AD*EN-ALL-0700 "WASTE MANAGEMENT AND RECYCLING" (Superseded DEC EWP 2.9 "Mixed Waste") describes handling of mixed waste at Duke Energy nuclear stations.

2.2.2 Disposal of Mixed Waste at a Low Level Radioactive Waste disposal site is prohibited unless it is approved by the disposal site, meets federal, state and disposal site requirements. (E.g ., 40CFR, 10CFR61, site WAC) 2.2.3 All vendors supplying services for Mixed Waste using solidification shall meet the applicable requirements of the PCP and be a DEC Approved Supplier of PCP Services.

2.2.4 PCP Subject Matter Experts (SMEs) and disposal site regulators shall approve the use of solidification for disposal of Mixed Waste .

2.2.5 If Mixed Waste is to be rendered non-hazardous for disposal at a 10CFR61 disposal site using solidification the final product and packaging must meet all the LLW disposal site requirements.

DEC Corporate PCP 2 Rev.16 Page 10-12

Attachment 1o Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

°"' ENERGY.

.-(~DUKE Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 2.3 Radi,oactive Waste Oil 2.3.1 Radioactively contaminated oil is to be managed as described in ENV-20 "Managing Used Oil" (superseded EWP 2.8 "Used Oil"). This procedure is part of the Environmental Compliance Manual.

2.3.2 Offsite processors are available for waste oil treatment, (e.g., incineration) reducing the regulatory burden on the generating site. Nuclear site programs address the specific waste oil management processes available at the site.

2.3.3 Each LLW disposal site defines the acceptable threshold for incidental levels of waste petroleum-based oil (e.g., less than 1% by volume). Solidified waste containing oil shipped to a 10CFR61 disposal site shall meet the applicable requirements of the PCP and all applicable disposal site acceptance criteria.

2.3.4 If a LLW site accepts greater than incidental concentrations of oil to be solidified for disposal, an oil-specific procedure must meet the requirements of the PCP and the acceptance criteria of that disposal site.

2.4 Radioactive Waste Interim Storage Sites that have LLW requiring interim storage shall ensure that all of the following requirements that are applicable are met.

2.4.1 Any radioactive waste that is stored for an interim period in a shipping/ disposal container shall be packaged such that there is no detrimental interaction between the waste and its container.

2.4.2 If applicable, Certificates of Compliance shall be maintained at each station for all waste shipping/ disposal containers used for interim storage.

2.4.3 Vendor supplied containers used for storage shall be handled and stored according to applicable guidance in vendor documents, including chemical compatibility requirements.

3. REFERENCES 3.1 Regulatory Requirements The use of and content of the PCP addresses requirements found in the following regulations:

3.1.1 10CFR20, "Standards for Protection Against Radiation" 3.1.2 10CFR50, "Domestic Licensing of Production and Utilization Facilities" DEC Corporate PCP 3 Rev.16 Page 10-13

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

,,l'-,,.DUKE

'\,"ENERGY.

Radioactive Waste Process Control Program Duke Energy CaroUnas (DEC) Corporate PCP 3.1.3 10CFR61, "licensing Requirements for Land Disposal of Radioactive Waste" 3.1.4 I0CFR71, "Packaging and Transportation of Radioactive Materials" 3.1.5 40CFR, "Protection of Environment" 3.1.6 40 CFR Part 266 "Storage, Treatment, Transportation, and Disposal of Mixed Waste" 3.1.7 Licensed radioactive waste burial site criteria 3.1.8 State hazardous waste regulations 3.2 Regulatory Guidance and Industry Standards Technical guidance is provided in the following documents to standardize compliance with the applicable regulations:

3.2.1 NUREG-0133, "Preparation of Radiological EfftuentTechnical Specifications for Nuclear Power Plants" 3.2.2 NUREG-0452, "Standard Technical Specifications for Westinghouse PWR's" (Superseded by NUREG 1431) 3.2.3 NUREG-1431 "Standard Technical Specifications Westinghouse Plants" 3.2.4 NUREG-1430 "Standard Technical Specifications Babcock and Wilcox Plants" 3.2.5 NUREG-800 "Standard Review Plan", Section 11.4 "Solid Waste Management Systems" 3.2.6 NUREG 800, Section 11.4, Appendix -A, "Design Guidance for Temporary Onsite Storage of Low Level Radioactive Waste" 3.2.7 Branch Technical Position* ETSB 11-3, "Design Guidance of Solid Radioactive Waste Management Systems" 3.2.8 NRC Review Criteria for Solid Waste Management Systems 3.2.9 Regulatory Guide 1.143, "Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Plants" 3.2.10 NRC "TECHNICAL POSITION ON WASTE FORM" Revision 1 (January 1991)

DEC Corporate PCP 4 Rev.16 Page 10-14

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

.-t:_~ DUKE

~ ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 3.2.11 NRC "Concentration Averaging and Encapsulation Branch Technical Position",

Rev 1 (2015) 3.2.12 ANSI/ANS-40.37-2009 "mobile radioactive waste processing systems" 3.3 DEC License Documents Referencing the PCP 3.3.1 ONS Technical Specifications 5 3.3.2 CNS SLC 16 3.3.3 MNS SLC 1p 3.3.4 ONS SLC 16 3.3.5 ONS UFSAR Chapter 11 3.3.6 CNS UFSAR Chapter 11 3.3.7 MNS UFSAR Chapter 16 3.3.8 Duke Energy Corporation Topical Report: Quality Assurance Program Description Operating Fleet (DUKE-QAPD-001 -A) 3.4 DEC PCP Interfaces With Other Programs 3.4.1 AD-RP-ALL-5000, Preparation and Shipment of Radioactive Material and Radioactive Waste 3.4.2 AD-RP-ALL-5002, 10 CFR 61 Radioactive Waste Classification 3.4.3 Duke Energy Information Retention Policy Ref: (Legal 109, 10CFR20 Appendix G (111.A.3), 10CFR61.80) 3.4.4 AD-DC-ALL-0002 Records Management 3.4.5 AD-DC-ALL-0201 Development and Maintenance of Controlled Procedure Manual Procedures 3.4.6 ENV-20-40 "Managing Used Oil" 3.4.7 AD-EN-ALL-0700 "WASTE MANAGEMENT AND RECYCLING" DEC Corporate PCP 5 Rev.16 Page 10-15

Attachmerit 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018

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~ ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP

4. DEFINITIONS 4.1 Safety Analysis Report (SAR)

The station's Technical Specifications (Tech Specs) updated final safety analysis report, licensee commitments, safety evaluation reports and the facility operating license.

4.2 Selected Licensee Commitments (SLCs)

Commitments to control important plant equipment and operating conditions not controlled elsewhere. Operational commitments which are to be removed from existing station Tech Specs rpay be included in the SLC program. Also included in this program can ~ selected NRC commitments contained in licensing documents such as the station's SERs, LERs, violation responses, generic letter and bulletin responses, submittal documents and other Duke letters to the NRC.

4.3 10CFR Part 61 "Licensing Requirements for Land Disposal of Radioactive Waste" This NRC regulation requires that low-level radioactive waste (LLVV) meet certain waste form acceptance criteria to be received for disposal at NRC and Agreement State licensed radioactive waste disposal sites.

4.4 Free Standing Liquid (FSL)

FSL is liquid that is in a disposal container but is not bound by the waste in the container.

FSL is the liquid available for release if disposal container integrity is lost (e.g., punctured).

The amount of FSL in a radioactive waste disposal container shall be less than a specified threshold to meet 10CFR61, state and disposal site requirements for disposal.

4.5 Liquid Radioactive Wastes Radioactive wastes comprised primarily of water containing a combination of dissolved and suspended solids (e.g., evaporator concentrates, lab wastes, floor and equipment drain water, laundry, 1,Wt waste decant or drainage, etc.).

4.6 Wet Radioactive Wastes Wet radioactive wastes are solid radioactive wastes containing loosely bound liquid that can collect in the disposal container as FSL (e.g., slurry wastes are comprised primarily of solid particles suspended in loosely bound interstitial water, spent mechanical filters are solid materials that are adsorbent or porous and retain liquid).

4.7 Solidification The meaning of the term Solidification during the original implementation of 10CFR61 was a process that converted radioactive waste into a product meeting 10CFR61, State and DEC Corporate PCP 6 Rev.16 Page 10-16

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018

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~"ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP disposal site requirements for waste-form stability and FSL. Solidification was accomplished by mixing measured amounts of liquid or wet radioactive waste, binder and required additives that, after sufficient curing time, produce a solid homogeneous, freestanding monolith. At the end of the curing period, the absence of excessive FSL was verified either by confirmation that the PCP boundary conditions were met or by physical verification/testing. Under current practices, generally the solidified waste does not meet waste form stability requirements since few of the processes tested during the early implementation were able to do so. The waste container or barriers in site design or process used at the disposal site meet the stability requirements. The process requirements described in the solidification section do not apply to encapsulation of discrete LLW items as described in the BTP for waste form.

4.8 High Integrity Container (HIC) .

Disposal containers that have been approved by the NRC for disposal of Class A unstable, Class B or Class C LLW and meet the long term disposal requirements of 10CFR61 and the disposal site.

4.9 Oewatering Dewatering as used in this document is the removal of liquid using a process that is required to meet the requirements of this PCP. Dewatering removes the loosely bound liquid from a wet radioactive waste such that accumulation of Free Standing Liquid in the disposal container is unlikely to approach the disposal limit threshold values as defined by applicable regulations and disposal site criteria. NRC regulations require that the process used to dewater radioactive wastes to meet disposal criteria shall be governed by a PCP.

4.9.1 10CFR61 FSL criteria requires less than 0.5% FSL by waste volume per container or less than 1.0"/4 FSL if a high integrity container (HIC) is used.

4.9.2 Typically, liquid and wet wastes are pre-staged in vented tanks or containers and are therefore degassed prior to the dewatering process. However, all vendor-required venting practices should be adhered to.

4.10 Unwatering ("Gross Dewatering", "dewatering to loss of vacuum")

Unwatering as used in this document is the removal of water using a process that is not required to meet the requirements for direct disposal at a 10CFR61 disposal site.

Uni.vatering removes loosely bound excess or freeboard water from v-.et radioactive wastes such that only the requirements for transportation set forth in 49CFR are satisfied (e.g.,

unwatering may be to complete the first dewatering cycle for a specific container and waste stream to loss of vacuum to prepare waste for shipment to an approved offsite processor

'M'\O will perform additional processing that will meet the final disposal requirements).

DEC Corporate PCP 7 Rev.16 Page 10-17

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

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~_.ENERGY.

Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 4.11 Mixed Waste Defined in Resource Conservation Recovery Act (RCRA) as amended by the Federal Facility Compliance Act of 1992, a Mixed Waste contains both RCRA hazardous waste and source, special nuclear, or byproduct material subject to the Atomic Energy Act of 1954, as amended. The use of solidification to render Mixed Wastes non-hazardous shall ensure that the final product meets all waste form requirements applicable to radioactive waste disposal at a 10CFR61 disposal site (Ref: 3.1.6. "40 CFR Part 266").

4.12 QA Approved Supplier List Radwaste vendors approved to,provide PCP processing are included on the Duke QA Approved Supplier .List and are subject to the requirements and audits of that program.

4.13 Waste Batch A "batch" shall be defined as an isolated quantity of waste to be processed having essentially consistent physical and chemical characteristics.

4.14 Waste Batch Mixing A Waste Batch shall be adequately mixed using a proceduralized process such as agitation via mixers, air sparging or recirculating flow which meets a specified minimum rate that has been determined to provide a representative sample for the vessel.

4.15 Process Parameters Those conditions measured or observed during a solidification or dewatering process to ensure an acceptable product. These are determined for each waste type and are specific to the process method used.

4.16 Boundary Conditions/ Acceptance Criteria 4.16.1 Solidification Boundary Conditions or Acceptance Criteria are defined as, the bounding numerical values for solidification process parameters that produce an acceptable product 'Mlen shipped for direct disposal at a 10CFR61 disposal site.

4.16.2 De-.vatering Boundary Conditions or Acceptance Criteria are defined as the bounding numerical values for process parameters that ensure free standing liquid requirements are met when shipped for direct disposal at a 10CFR61 disposal site.

DEC Corporate PCP 8 Rev.16 Page 10-18

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

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~"ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 4.16.2.1 Media: Acceptance Criteria for dewatering process media in disposal containers ( e.g., H!Cs) have been determined by vendor tests using real or simulated waste to demonstrate the adequacy of the dewatering process for each combination of waste type and container. These tests are documented in dewatering Topical Reports, or equivalent, that shall be approved by the NRC or other appropriate authority before the containers are certified for use. The Acceptance Criteria are then incorporated into the dewatering procedures for each combination of waste type and container.

4.16.2.2 Filters: Acceptance criteria for mechanical filters (e.g., cartridge, bag, membranes, etc.) may be derived from tests per.formed on the various types of filters in use. Tests performed by Duke Energy should be documented in a retrievable manner. Acceptance criteria are then incorporated into the applicable procedure for each filter type (e.g.,

drainage time. drainage conditions, etc.).

4.16.2.3 Filters may also be packaged in disposal containers designed to allow the removal of free standing liquid from the container prior to shipment for direct disposal based on the disposal site's waste acceptance criteria f!MAC).

4.17 PCP Topical Report (PIPs 0-03-0624, M-03-2515, C-03-3385)

A Topical Report provides the basis for a PCP technology & process. It documents test results that demonstrate regulatory requirements were met during the regulatory required testing for solidification or dewatering technologies and processes. For a time period after implementation of 10CFR61 the NRC approved processes developed to dewater or solidify waste based their review of the Topical Report for that process. The NRC no longer performs the approval of Topical Reports so this approval is typically the responsibility of the disposal site host agreement state regulatory authorities. Topical report testing was designed to envelope the worst-case dewatering scenarios given the industry's then current practices. As with any topical based program, the critical conditions and parameters identified during testing are incorporated into the implementing process with enough conservative margin to ensure success if you operate v,iithin the enveloping conditions and assumptions of the tests performed. When actual conditions vary from the conditions in the specific tests performed for the Topical Report, the correlation with the Topical testing is diminished and degree of processing conservatism may need to increase to compensate.

DEC Corporate PCP 9 Rev.16 Page 10-19

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

~DUKE ENERGY. Radioactive Waste Process Control Program Duke Energy CaroUnas (DEC) Corporate PCP

5. DEC RESPONSIBILITIES 5.1 Process Control Program Content and Implementation 5.1.1 The PCP is owned, sponsored, and administrated by individuals designated by management pursuant to the requirements of site licensing documents. These individuals may be designated as PCP subject matter experts (SME) or program OIIVl'l.ers. Their responsibilities may include:

5.1.1.1 Revise and publish the DEC PCP.

5.1.1.2 Technical contact for PCP issues ,

5.1.1.3 Ensure corporate programs comply with applicable PCP requirements.

5.1.1.4 Support nuclear site programs in complying with applicable PCP requirements.

5.1.1 .5 Provide review and approval of PCP service providers.

5.1.1.6 Provide review and approval of radioactive waste processors and manage vendor service and disposal contracts for the fleet 5.1.1.7 Review PCP revisions.

5.2 Oversight and Audits Audits of the Process Control Program and implementing procedures for processing of radioactive wastes shall be performed per Duke OADP-OO1-A 5.3 DEC PCP Responsibilities The PCP applies to liquid or wet radioactive waste generated at the nuclear site when it is solidified or dewatered for direct disposal at a 10CFR61 disposal site. Any group that has responsibility for activities that generate or manage these wastes shall ensure their programs and processes comply with and support compliance with the applicable portions of the PCP. The following responsibilities are currently identified at the nuclear sites, and will be applicable to any group that has the responsibility. Any changes in these responsibilities and the groups to whom they are assigned should be evaluated for impact and potential incorporation into applicable PCP documents.

5.3.1 DEC management approves PCP revisions as defined in licensing documents.

5.3.2 Line Management responsible for programs impacting the PCP ensures those programs are consistent with the applicable PCP documents.

DEC Corporate PCP 10 Rev.16 Page 10-20

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Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 5.3.3 Staff and Line Supervisors ensure applicable area-specific procedures and activities comply 'Mth the PCP.

5.3.4 PCP related document reviewers 5.3.4.1 Ensure site PCP documents and processes comply with the Corporate PCP (e.g., site dewatering or solidification procedures).

5.3.4.2 Review applicable PCP revisions.

5.3.4.3 PCP document sponsors and users ensure current documents are

, used to implement PCP-related activities 5.3.4.4 Support incorporation of the PCP revision summary report into the site Annual Radiological Effluent Release Report (ARERR).

6. ADMINISTRATION OF THE DEC PCP AND SUPPORT DOCUMENTS 6.1 PCP Changes: Revisions and Minor Changes PCP document revisions and minor changes are initiated, reviewed and approved following the applicable guidance in licensing documents and administrative procedures. The EDMS document management processes should be used to document and issue the new versions.

V\Jhere appropriate CAS ORR documentation may be used to document the bases for the changes and identify other DRRS being incorporated. The guidance for and descriptions of v,.,tiat constitutes a minor change and revision are:

6.1.1 The Duke Energy QADP implementation guidance is in procedure AD-LS-ALL-0019, On-Site Review Committee. This procedure describes \o\ttlen a,n ORC should be notified of changes to site documents. E.g., where NRC notification of the change is required prior to implementation.

6.1.2 Tal:ile 1 REVISIONS: Technical or significant changes to PCP documents shall be implemented as a Revision to the affected documents and include the reviews and approvals described in Table 1 below. Revisions will be documented in EDMS using EDMS processes and the changes summarized in the document revision summary section.

6.1.3 Table 2 DEC PCP MINOR CHANGES: If a change meets the following criteria it does not require a revision. Minor Changes wll be documented in EDMS using EDMS processes and the changes summarized in the document revision summary section. Reviews and approvals are in Table 2 below:

DEC Corporate PCP 11 Rev.18 Page 10-21

Attachment 1O Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

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~ ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 8.1.3.1 The change is editorial in nature; e.g., spelling, grammar, format, numbering, procedure name change, adding, deleting or changing a reference, only includes administration of the documents affecting only the preparer.

6.1.3.2 The change does not alter the scope, results, requirements, or methods by which the dewatering or solidification process is performed from requirements described in the applicable PCP document.

6.1.3.3 The change does not alter the responsibilities of site personnel in meetrng the PCP requirements.

6.1.3.4 The change does not alter a PCP QA approved provider 'dewatering or solidification process, responsibilities for fulfilling PCP requirements or the vendor interface with the station personnel or work processes described in the PCP documents.

TABLE 1: DEC PCP Revision Review and Approval Technical Roles PCP Document Title Approvals Author & Review DEC Corporate Process Control Preparer Corporate Management Program PCPSMEs DEC Station Management Preparer Corporate Management ONS PCP PCPSMEs ONS Management Preparer Corporate Management MNS PCP PCPSMEs MNS Management Preparer Corporate Management CNS PCP PCPSMEs CNS Management DEC Corporate PCP 12 Rev.16 Page 10-22

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

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"'ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP TABLE 2: DEC PCP Minor Change Review and Approval Technical Roles PCP Document Title Approvals Author & Review Preparer DEC Corporate Process Control Preparer Management Program PCPSMEs Preparer ONSPCP Preparer Management PCPSMEs Preparer MNS PCP Preparer Management PCPSMEs Preparer CNS PCP Preparer Management PCPSMEs 6.2 PCP Revision Reports to the NRC Revisions to the DEC PCP shall be reported to the NRC each year as described in each site's licensing documents. The required documentation for the NRC ARERR shall be provided using the process and procedures for preparation of the ARERR.

6.3 PCP Document Revision Record Retention Requirements See Duke Energy Record Retention Requirements.

6.4 PCP Implementing Procedure Requirements 6.4.1 DEC station procedures that implement PCP requirements shall ensure that all requirements for solidification or dewatering are met \Mlen performed by Duke Energy workers per DEC PCP documents.

6.4.2 The DEC PCP implementing procedures are listed in the DEC site specific PCP published in the Duke EDMS.

DEC Corporate PCP 13 Rev.16 Page 10-23

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~ ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 6.4.2.1 Completed procedures documenting the onsite solidification verification records shall be retained by the site on each vessel of solidified waste.

6.4.2.2 Documentation of the onsite dewatering verification records shall be retained on each vessel of dewatered waste.

6.4.3 The technical PCP implementing procedures shall identify the fact that they are PCP related to ensure technical reviews consider the PCP requirements.

6.4.4 All revisions to technical PCP implementing procedures listed in the site PCPs shall be reviewed to determine if they alter or inhibit the prooedure's performance of the .Corporate PCP requirements .

6.4.5 QA Approved Suppliers' procedures may be used for onsite PCP activities using non-installed equipment as described in applicable administrative procedures.

(e.g., AD-DC-ALL-0201 Development and Maintenance of Controlled Procedure Manual Prooedures)

7. APPROVAL PROCESS FOR QA APPROVED SUPPLIERS Any PCP service supplier shall be approved and incorporated into the QA Approved Supplier Program prior to being used as contracted for process services that use a dewatering or solidification PCP to meet final waste form requirements at a 10CFR61 disposal site .

7.1 Technical Review and Approval Before vendors can provide PCP related services, they shall be evaluated against the app[icable Duke PCP documents and approved by the appropriate designees.

7.1 .1 If the vendor provides PCP related services, the vendor PCP and other related program documents are evaluated to ensure they meet the applicable requirements of the Duke PCP documents.

7.1.2 The results ofthese reviews should be documented appropriately for future reference.

8. PCP REQUIREMENTS FOR VENDOR PROCESSES AND SERVICES 8.1 Topical Report (or equivalent)

My vendor service or vendor supplied processes utilized for solidification or dewatering by Duke Energy shall have a Topical Report or other form of certification documenting appropriate regulatory approval of the process and associated containers, or shall supply to Duke Energy sufficient documentation of the process and test results to demonstrate that an DEC Corporate PCP 14 Rev.18 Page 10-24

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018

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~"ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP acceptable product will be produced using the described solidification or dewatering process.

8.2 10CFR61 Waste Form Compliance 8.2.1 The vendor(s) approved for solidification or dewatering services shall have regulatory certification documenting compliance with waste form requirements in the final product, or shall supply Duke Energy sufficient documentation to demonstrate waste form compliance.

8.2.2 Any vendor providing High Integrity Containers (H[C's) to Duke Energy shall provide proof of regulatory approval documenting compliance with waste form requirements, or shall supply Duke Energy suffic1ent documentation to demonstrate waste form compliance.

8.2.3 All vendor Topical Reports or equivalent shall certify that the final product conforms to the applicable waste form for Class A, B, or C waste.

8.2.4 Vendor PCP Service Quality Requirements QA Approved PCP Service Suppliers shall meet the applicable quality requirements set forth in their contract or specific Purchase Order.

8.3 10CFR61Waste Classification Compliance Each container of processed (i.e ., solidified or dewatered) waste shall meet the requirements in AD-RP-ALL-5002, 10 CFR 61 Radioactive Waste Classification prior to disposal.

8.4 Minimum Requirements for Onsite Process Vendors 8.4.1 Vendors providing PCP services onsite shall be approved QA Suppliers.

8.4.2 PCP Vendors shall fulfill all the applicable requirements in the vendor Radioactive Waste PCP and the applicable quality requirements set forth in the contract prior to shipment of the solidified or dewatered waste for direct disposal.

8.4.3 Onsite Vendor System/Equipment Interface Requirements:

8.4.3.1 The vendor documentation, drawings or diagrams supplied to Duke Energy shall include adequate system or process description including all vendor interfaces with installed plant equipment and potential release pathways.

8.4.3.2 Solidification system radioactive effluents are treated or routed to the appropriate plant system to meet effluent discharge requirements.

DEC Corporate PCP 15 Rev.16 Page 10-25

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

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~ ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 8.4.3.3 Decanted radioactive liquid is processed as required or routed to the station liquid radwaste systems.

8.4.4 Onsite Vendor Supplied System Design Requirements 8.4.4.1 The vendor proposal and contract shall verify that the design, construction, operation and quality assurance provisions are in accordance with applicable portions of NRC ETSB Branch Technical Positron 11-3 and Regulatory Guide 1.143.

8.4.4.2 Permanent or portable solidification and dewatering systems used at nuclear sites shall meetthe applicable design, construction, operation and quality assurance provisions of NRC ETSB Branch Technical Position 11-3 and Regulatory Guide 1.143.

8.5 Minimum Requirements for Offsite PCP Process Vendors QA Approved Supplier Vendors providing PCP services offsite shall meet the requirements of their PCP process and the applicable quality requirements set forth in the contract and/or purchase order prior to disposal of the final product.

9. PCP CEWATERING PROCESS DESCRIPTION The methods used for removal of liquid from wet wastes for final disposal shall comply with the specific requirements of the disposal site at 'M'lich the waste is being disposed. Dewatering of wet wastes shall be performed in accordance with the applicable PCP requirements e.quivalent to the process described below. PCP w:>rkers shall use approved procedures in a controlled and quality fashion which ensures that art applicable license documents and disposal site criteria are met.

Procedures used to direct clewatering shall include enough detail to ensure requirements are met.

9,_1 Dewatering Mechanical Filters (e.g., cartridge, bag, membrane)

The gutdance below addresses dewatering methods and PCP issues unique to removal of FSL for direct disposal of mechanical filters at a 10CFR61 disposal site.

s,."t .1 The dewatering process must ensure subsequent accumulation of free standing liquid in the disposal container is not likety to approach disposal site limits.

9.1.2 The FSL requirements for direct disposal may be met using a container and procedure designed to remove any subsequent FSL accumulation in the container prior to disposal.

9'.1 .3 Wet spent mechanical filters can be de\1\/atered by several methods including allowing tiquid to gravity drain from the filter, blowing the filter down with air, compacting the filter, etc.

DEC Corporate PCP 16 Rev.16 Page 10-26

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.-(~DUKE Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 9.1.4 The method of delf-l!ltering shall be in accordance with a defined, evaluated, and documented process.

9.1.5 The parameters of the process, referred to as boundary conditions, shall be defined and used to ensure quality in the process, which in turn serves to ensure an acceptable characteristic of the waste. An example of a boundary condition is the specified period of time for v.hich a mechanical filter shall be allowed to drain freely to ensure FSL \'\All be less than disposal requirements.

0,.1.6 Filters placed in a ftlter disposal container designed for removal of FSL shall meet the PCP boundary conditions for dewatering the container.

9.1.6.1 If PCP boundary conditions are met after placing the filter in the disposal container, the container shall be dewatered to ensure the contafner FSL meets disposal requirements.

9.1.6.2 If the PCP boundary conditions have been met prior to placing the filters in the disposal container, dewatering the container to remove incidental FSL is at site discretion.

9.1.6.3 Case-by case circumstances, such as the following, should be considered in determining the appropriateness of performing additional filter disposal container dewatering:

• The time interval be1'M3en removal of the filters from ~t service and placement into the disposal container

• SFZe of the disposal container relative to the moisture content in the filters

• The number of filters

• The variety of filter types in a single container

• The environmental conditions of filter staging and interim storage 9.1.7 Use of absorbent package material in mechanical filter disposal containers is subject to the requirements of the disposal site acceptance criteria.

9.2 Dewate.ring Slurries The guidance below addresses dewatering issues associated with slurry wastes.

9.2.1 Dewatering of "slurried" wet wastes (e.g., resin, carbon, Zeolite, filter precoat, filter backwash solids) removes the loosely bound interstitial liquid from. solids such that the disposal container meets applicable regulatory and burial site FSL criteria for disposal.

DEC Corporate PCP 17 Rev.16 Page 10-27

Attachment 1o Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

~~DUKE "I!' ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 9.2.2 Wet spent process media dewatering shall be performed using processes, containers and procedures that have met the Duke PCP approval requirements.

9.2.3 Typical container dev.iatering processes use a vacuum pump that takes suction from the container through a filter system in the container. The v.iater is returned to a station liquid radwaste system and the waste solids are retained in the vessel by the container filter(s).

9.3 Additional Conservatism in Slurry Dewatering Procedures to Address Variation from the Topical Report (PIP 0-03-0624, M-03-2515, C-03-3385)

This section only applies to dewatering for direct disposal at a 10CFR61 disposal site performed by Duke Energy Carolinas (DEC) workers using Duke Energy dewatering procedures. This section does not apply to QA Approved Suppliers performing PCP activities.

Devvatering processes based on approved and documented testing (e.g., Topical Reports) are applied to actual conditions that can vary from the conditions of the original testing. The results of a Root Cause investigation at ONS (PIP 0-03-0624) identified several issues and resolutions that should be incorporated into applicable Duke dewatering implementing procedures. Vendor procedures applicable to the technologies and processes used by Duke Energy in implementing the PCP provide the basis for minimal requirements in PCP implementing procedures. In addition, the guidance below was added based on the Root Ca.use findings at ONS:

9.3.1 All Duke Energy Carolinas (DEC) PCP dewatering procedures shall include flexibility/ guidance for the worker to add conservatism to the dewatering process if waste content and/ or process conditions are atypical in a non-conservative manner relative to the testing performed for the Topicaf report. (e.g., presence of greater than normal non- media solids, dewatering boundary parameters are not easily met, higher than normal volume of FSL is collected during the final dewatering cycle, etc.)

9.3.1.1 Additional conservatism can include but is not limited to the following examples:

A. Additional dewatering cycles B. Additional settling time between pumping periods C. Additional processing by an approved offsite vendor to verify FSL prior to disposal DEC Corporate PCP 18 Rev.16 Page 10-28

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/2018

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~"ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 9.3.2 Guidance for dewatering all liners using the DEC PCP and procedures for direct disposal at Barnwell (PIP 0-03-0624 CAPR) 9 .3.2.1 Require liner functional testing prior to filling liner with waste to ensure there are no leaks in the liner dewatering system. This testing should include:

A. filling the liner with water B. testing each level of the liner dewatering laterals using the dewatering procedure to un""'8ter the liner t

C. 11erifying that vacuum is not broken prior to exposing the filters for each set of laterals as described in the procedure 9.3.2.2 Ensure ambient temperature guidance for dewatering will preclude localized freezing conditions during the dewatering sequence. After most of the water is removed during the first dewatering cycle, subsequent cycles pull air through the interstitial spaces of the media and the loss of heat due to evaporation can depress the temperature on surface of the media and dewatering filters below ambient temperature.

A. Follow g.uidance in the vendor documentation for the process in use B. If no other guidance is provided, dewatering should not be performed unless ambient temperature of air entering the liner is 40 degrees Fahrenheit or higher (ref. EnergySolutions procedure FO-OP-022) 9.3.2.3 Ensure final water collection sample point is representative (e.g., as close as possible to the pump discharge) 9.3.3 Mixed Media: Additional guidance for dewatering liners containing Mixed Media with significant non- media solids using a PCP for direct disposal at a 10CFR61 disposal site. (PIP 0-03-0624 CAPR)

The guidance below applies to liners containing combinations of different media with significant quantities of non-media solids (e.g., layered spent zeolite, carbon, resin, etc. containing a large amount of non-media particulate) 9.3.3.1 Require dewatering filters with maximized surface area (e.g., Ecodex filter or equivalent) in all liners that contain mixed media with significant non-media solids DEC Corporate PCP 19 Rev.16 Page 10-29

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'\, .. ENERGY.

Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 9.3.3.2 Clearly specify media loading sequence if media is not homogeneously mixed to minimize potential blinding of the lowest level offilters. (e.g., for layered media, use the media 'Mth the fewest non-media solids and most consistent and largest diameter beads in the bottom of the liner) 9.3.3.3 Require additional devvatering Cycles (e.g. 3 additional cycles after the acceptance criteria in the vendor procedure have been met) 9.3.3.4 Require longer settling periods during the additional dewatering cycles (e.g., 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> instead of the 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> required in the vendor pr0icedure) 9.3.3.5 The PCP implementing procedures must comply with the vendor PCP guidance and procedures applicable to the dewatering system and disposal containers in use. e.g., If the vendor process control program and procedures applicable to the current system and process require dewatering through the bottom 2 laterals during liner filling this must be reflected in the Duke procedures.

9.4 Dewatering Process Requirements The procedures directing d.ewatering processes shall address all the following activities that apply to the specific waste type being dewatered.

9.4.1 Waste Characterizatron Dewatering procedures shall describe how each type of waste is characterized.

The characterization information determines what disposal and container requirements apply and may also be utilized to determine shipment packaging requirements (e.g., shielding). Much of the required information for slurry waste is obtained using a representative sample of the waste media. Characterization requires the following types of information:

9.4.1.1 Radioactivity content A. To determine 10CFR61 waste class, form and container requirements B. To provide waste radiological characteristics for packaging, transportation and disposal requirements 9.4.1.2 Waste compatibility with disposal container and process method A. Chemical Compatibility: Process knowledge can be applied to determine chemical compatibility with the container.

DEC Corporate PCP 20 Rev.16 Page 10-30

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~ ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP B. Hazardous Characteristics: Process knowledge can be applied to determine if the waste is a Mixed Waste.

C. If process knowledge is uncertain due to a potential input of incompatible or hazardous materials, then chemical analysis using an approved method shall be performed to determine chemical compatibility or hazardous characteristics.

9.4.2 PCP process parameters shall be identified in implementing procedures. Typical parameters are based on:

9.4.2.1 Waste form (e.g ., physical, chemical and tfadiological characteristics) 9.4.2.2 Settling time 9.4.2.3 Drain (or pump) time 9.4.2.4 Temperature 9.4.2.5 Drying time 9.4.3 PCP boundary conditions shall be established for applicable process parameters to verify FSL threshold limits are met.

9*.4.4 Sample analysis results and boundary conditions shall be reviewed by the appropriate knowledgeable individual responsible for the dewatering process.

9.4.5 Actual dewatering shall be performed using approved procedures that ensure the process is performed within the established boundary conditions.

9.5 Product Verification The amount of free-standing liquid shall be verified to be within disposal site criteria for each container of dewatered waste prior to disposal (e.g., 10CFR61 requires that each container shall have less than 0.5% free-standing liquids by waste volume or less than 1.0% free-standing liquid if a High Integrity Container (HIC) is used). Procedures should include guidance for problems during container loading or processing that preclude or fail to meet PCP requirements as required in SLC Remedial Action Requirements.

9.5.1 PCP Verification may be accomplished by documenting that the Process Control Program was followed.

9.5.2 A disposal site may define a product verification testing method approved for use for specific waste disposal categories in lieu of a process control method.

DEC Corporate PCP 21 Rev.18 Page 10-31

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~ ENERGY.

Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP 9 .5.2.1 That approved product verification process may be used for that category of disposal on a case-by-case basis, (e.g., bulk waste non-containerized disposal).

9 .5 .2.2 Documentation of the method used for product verification and the results shall be included in the dewatering record as described in the Dewatering Documentation Retention section below.

9.5.2.3 Make programmatic changes as necessary to address any problems identified.

9.5.3 The PCP and site procedures must address the Commitments in the "The Solid Radioactive Wa'stes" sections ofSLC ]6 "RADIOLOG ICAL EFFLUENTS CONTROLS" for CNS, MNS, and ONS. l11ese Commitmen ts include a description of the PCP purpose, and requirements for the use of the PCP to process LLW for direct disposal.

9.5.3.1 Remedial Actions address tbe following conditions:

A. Requirements not met by process or packaging conditions B. Solidification ve1ification failures C. Processing not perfo11ned per PCP D. Inoperable Equipment 9.5.3.2 Solidification processes must meet Testing or Surveillance requirements and frequencies 9.6 Dewatering Document Retention Documentation of dewatering or solidification completed onsite for direct disposal at a 10CFR61 disposal site shall be retained as part oftlhe radiological shipping and disposal records as described in the applicable procedures andJ documents. (e.g., PCP implementing procedures, AD-RP-ALL-5000, vendor documents)

10. PCP SOLIDIFICATION PROCESS DESCRIPTION This section historically described a solidification process for liquid or media LLW in v.tiich a radioactive liquid or slurry waste was uniformly mixed into a binding matrix to create a physically uniform final waste form that is a homogeneous, free standing monolith and meets10CFR61 waste form stability and FSL disposal requirements.

DEC Corporate PCP 22 Rev.18 Page 10-32

Attachment 10 **

Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018-12/31/ 2018

~DUKE ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP No installed solidification systems are operational at the DEC sites because they were not able to meet all the 10CFR61 dfsposal requirements and or were not cost effective. The solidification of liquids and slurry media if required is now pertormed via contracts with PCP QA approved suppliers under their PCP in controlled and quality fashion which ensures that an applicable regulatory, licensing and disposal site criteria are met. e.g. the applicable Commitments in the "The Solid Radioactive Wastes" sections of SLC 16 "RADIOLOGICAL EFFLUENTS CONTROLS" Only the FSL disposal requirements apply to solidification for encapsulation of discrete LLW items as described in the BTP for waste form. Encapsulation is also pertormed via contracts with PCP QA approved suppliers.

Documentation of onsite solidification for direct disposal at a 10CFR61 disposal site shall be retained as part of the rad[ological shipping and disposal records as described in the applicable procedures and documents. (e.g., PCP implementing procedures, AD-RP-ALL-5000, vendor documents).

11. REVISION

SUMMARY

This section describes the changes in the current revision of the DEC Corporate PCP.

This revision 16 is essentiaBy a rewrite of the entire document, retaining the general structure with changes in every section . Ref: (DRR 02212730)

The previous PCP documents for the DEC fleet (ONS, MNS, CNS] included the Corporate PCP and Appendices A-H for the remaining documents. The revision of the Corporate PCP, the site PCPs, Appendix A: ONS PCP, Appendix B: MNS PCP and Appendix C: CNS PCP are being completed concurrently. The convention of using Appendices for the site PCPs has been removed and the document numbers in Fusion for the revised documents are ONS PCP, MNS PCP and CNS PCP.

The document titles in Fusion are ONS Process Control Program, MNS Process Control Program and CNS Process Control Program. The remainder of the Appendices 0-H are being superseded by the DEC Corporate PCP through incorporation of the still applicable guidance and administrative processes or replaced using other fleet governing Document Control programs and the document administrative processes in our electronic resources. e.g., EDMS, CAS.

The Corporate PCP document title was changed to reflect applicability of the document to DEC sites only. [ONS, MNS, CNS]

The cover page and approvals will be generated using the Fusion E-Signature process.

Below is a summary by section of the types of changes made.

1.

Introduction:

Purpose:

Edited to simplify wording, clarify focus, reduce redundant information addressed elsewhere in the document, and to distinguish between the use of in-house employees and programs and the use of contracted service providers DEC Corporate PCP 23 Rev.18 Page 10-33

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

,~DUKE ENERGY. Radioac*t ive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP

• Deleted details and specificity from references that is not needed

• Updated the description and location of DEC PCP guidance documents

2. Applicability:

• Made references more generic rather than specific to reduce future changes

• Edited wording to clarify differences in how the requirements differ for LLW being placed in final waste form onsite and shipped for direct disposal and LLW being shipped to an off-site processor

• Updated 'M:>rding for mixed waste, waste oil and packaging for interim storage

3. References

• Updated References and reorganized to consolidate lists

• Added new post-merger documents

4. Definitions

• Updated "Solidification" wording to clarify the current practices in meeting 10CFR61 waste form stability requirements

• Clarified the definition of "Unwatering" to include synonyms that may be used interchangeably, "gross dewatering", "dewatering to loss of vacuum

• Boundary Conditions/ Acceptance Criteria: removed unnecessary details for current solidification practices, added filter packaging in disposal containers designed to remove water from the container

• Updated Topical report wording since the NRC no longer approves them

5. Responsibilities

• Changed specific references to position and group names to program roles where feasible to mitigate impact of continuous changes in nuclear organization and program ownership.

• Removed references to groups that no longer have PCP involvement throughout thedocument. (e.g., Chemistry, Nuclear Supply Chain)

6. Administration of PCP and support documents DEC Corporate PCP 24 Rev.16 Page 10-34

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

,,1-,,.DUKE

~"ENERGY. Radioactive Waste Process Control Program Duke Energy Carolinas (DEC) Corporate PCP

• Removed references to Appendix F that is being deleted and incorporated guidance that is still applicable and needed

• Incorporated updated revision and minor change guidance from Appendix F

• Incorporated updated approval guidance for DEC PCP documents

• Updated PCP ARERR guidance

• Updated record retention guidance

• Deleted PCP section "Periodic cross checks & comparisons" created by PIP 0-03-0624 (ONS FSL Failure). The CAPR change is described in NTM 02125727 (ONS PIOC meeting minutes & approval) and CR#: 01740840-29. ONS PIOC approved this chang.e based on changes since the 2003 event, including ONS improvements in equipment, and procedures, the addition of formal processes in the PCP documents and consistency of current equipment and processes at the DEC sites.

• Updated PCP implementing procedure requirements

7. Updated approval process for QA Approved Suppliers

8. PCP Requirements for Vendor Processes and Services

• Editorial changes to reflect current administrative programs and processes.

• Updated document references

• Editorial changes to simplify wording and make more generic.

• Clarified use of QA Approved Suppliers

9. PCP Dewatering Process Description

• Updated use of filter packaging in disposal containers designed to remove water from the container to clarify process

• Clarified wording for guidance from 2003 ONS root cause CAPRs DEC Corporate PCP 25 Rev.16 Page 10-35

Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018

..(~DUKE

~ ENERGY. Radioactive Waste Process Control Program Duke Energy CaroUnas (DEC) Corporate PCP

• Changed IA/Ording (See step 9.3.3.5) to reflect ONS PICC approved revision of PIP 0 0624 CAPR, CR# 01740040-04. Changed a constraint that is not applicable to the enhanced Self Engaging Dewatering System (SEDS) technology now being used. (see NTM 02125727) The vendor procedure for the SEDS does not include the requirement to use the bottom dewatering laterals to compact the media. This is only applicable to the Universal Fill Head technology that was the original type of equipment used in the 1985 liner dewatering Topical Report testrng performed by EnergySolutions (then Chem-Nuclear Topical Report CNSI-DW-11118-01-P-A)

• Reduced inclusion of SLC Remedial Action Requirements details

10. PCP Solidification Process Description

• Rewrote entire section deleting the detailed content that was required in the original implementation of 10CFR61

• Updated references to current requirements DEC Corporate PCP 26 Rev.16 Page 10-36

• - Attachment 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 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 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 No major modifications to Oconee Nuclear Station liquid, gaseous, solid, or mobile radioactive waste treatment systems occurred in 2018.

Page 11-2

Attachment 1'2 Errata to a Previous Year's ARERR Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 -12/31/2018 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 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2018 - 12/31/2018 There are no changes to a previous year's ARERR.

Page 12-2