ONS-2016-039, Oconee, Units 1, 2, and 3 - Annual Radioactive Effluent Release Report for 2015

Oconee, Units 1, 2, and 3 - Annual Radioactive Effluent Release Report for 2015

ML16132A213
Person / Time
Site:	Oconee
Issue date:	05/02/2016
From:	Batson S L Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML16132A210	List: ML16132A213 ONS-2016-039, Oconee, Units 1, 2, and 3 - Annual Radioactive Effluent Release Report for 2015 ONS-2016-039, Offsite Dose Calculation Manual, Revision 27
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ONS-2016-039
Download: ML16132A213 (137)

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'Y ENERGY Scott L Batson Vice President Oconee Nuclear Station Duke Energy ON01 VP I 7800 Rochester Hwy Seneca, SC 29672 ONS-2016-039 o: 864.873.3274

f. 864.873. 4208 Scott.Batson@duke-energy.com May 2, 2016 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station, Docket Nos. 50-269, 50-270 and 50-287 2015 Annual Radioactive Effluent Release Report (ARERR) 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, 2015 through December 31, 2015. In accordance with TS 5.5.1, the Offsite Dose Calculation Manual (ODCM) is included in this submittal.

Attachment 1 Attachment 2 Attachment 3 Attachment 4 Attachment 5 Attachment 6 Attachment 7 Attachment 8 Attachment 9 Attachment 10 Attachment 11 Attachment 12 Summary of Gaseous and Liquid Effluents Supplemental Information Solid Radioactive Waste Disposal Meteorological Data Unplanned Offsite Releases Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Information to Support the NEI Ground Water Protection Initiative Inoperable Equipment Summary of Changes to the Offsite Dose Calculation Manual Summary of Changes to the Process Control Program Summary of Major Modifications to the Radioactive Waste Treatment Systems Errata to a Previous Year's ARERR Example www.duke-energy.com U.S. Nuclear Regulatory Commission 2015 Annual Radioactive Effluent Release Report May 2, 2016 Page2 Enclosure 2015 Offsite Dose Calculation Manual (Compact Disc) Any questions concerning this report should be directed to Pam Metler at 864-873-3856.

Sincerely, -5J/fl!/:1M-Scott Batson Site Vice President . Oconee Nuclear Station Attachments (12) Enclosure ( 1)

U.S. Nuclear Regulatory Commission 2015 Annual Radioactive Effluent Release Report May 2, 2016 Page3 xc (with attachments and enclosure):

Ms, Catherine Haney Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station xc (with attachments only): Mr. James R. Hall, Project Manager (by electronic mail only) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Mr. Jeffrey A. Whited, Project Manager (by electronic mail only) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Ms. Susan E. Jenkins, Manager Radioactive

& Infectious Waste Management SC Dept. of Health and Env. Control 2600 Bull St. Columbia, SC 29201 Mr. James Twiggs INPO 700 Galleria Place, Suite 100 Atlanta, GA 30339-5943 Mr. Gary Stewart, State Voluntary Cleanup Section S.C. Dept. of Health & Environmental Control 2600 Bull Street Columbia, SC 29201-1708 Ms. Sandra Threatt, Nuclear Response and Emergency Environmental Surveillance S.C. Dept. of Health & Environmental Control 2600 Bull Street Columbia, SC 29201-1708

ENERGY Oconee Nuclear Station Units 1, 2, and 3 Annual Radioactive Effluent Release Report January 1, 2015 through December 31, 2015 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 1/1/2015-12/31/2015 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

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Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Gaseous Effluents

-Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases 1. Total Release Ci 3.00E+OO 1.57E+OO 1.36E+OO 7.02E-01 6.63E+OO 2. Avg. Release Rate µCi/sec 3.85E-01 2.00E-01 1.71E-01 8.83E-02 2.10E-01 B. lodine-131

1. Total Release Ci 7.68E-10 O.OOE+OO O.OOE+OO 3.72E-10 1.14E-09 2. Avg. Release Rate µCi/sec 9.88E-11 O.OOE+OO O.OOE+OO 4.67E-11 3.61 E-11 C. Particulates Half-Life

8 days 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium 1. Total Release Ci 3.60E+01 2.31E+01 8.76E+01 3.34E+01 1.80E+02 2. Avg. Release Rate µCi/sec 4.63E+OO 2.93E+OO 1.10E+01 4.20E+OO 5.71 E+OO E. Carbon-14

1. Total Release Ci 5.98E+OO 6.10E+OO 5.97E+OO 5.51E+OO 2.36E+01 2. Avg. Release Rate µCi/sec 7.68E-01 7.76E-01 7.51 E-01 6.93E-01 7.47E-01 F. Gross Alpha 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+QO O.OOE+OO Page 1-2 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Gaseous Effluents

-Elevated Releases -Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases AR-41 Ci 3.39E-01 2.70E-01 5.19E-01 O.OOE+OO 1.13E+OO KR-85M Ci 1.11 E-03 2.44E-03 O.OOE+OO O.OOE+OO 3.55E-03 KR-87 Ci O.OOE+OO 2.61E-03 O.OOE+OO O.OOE+OO 2.61E-03 KR-88 Ci O.OOE+OO 4.62E-03 O.OOE+OO O.OOE+OO 4.62E-03 XE-133 Ci 1.90E+OO 1.17E+OO 7.81 E-01 6.65E-01 4.51E+OO XE-135 Ci 1.28E-02 3.51E-02 3.01E-02 O.OOE+OO 7.80E-02 XE-135M Ci 2.61E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.61E-03 Total for Period Ci 2.26E+OO 1.48E+OO 1.33E+OO 6.65E-01 5.73E+OO B. Iodines None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates 8 days None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO.

O.OOE+OO D. Tritium H-3 Ci 3.38E+01 2.04E+01 8.22E+01 2.64E+01 1.63E+02 E. Carbon-14 C-14 Ci 1.79E+OO 1.83E+OO 1.79E+OO 1.65E+OO 7.05E+OO F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO *0.00E+OO G. Others C-11 Ci O.OOE+OO 4.29E-03 O.OOE+OO O.OOE+OO 4.29E-03 Total for Period Ci O.OOE+OO 4.29E-03

• O.OOE+OO O.OOE+OO 4.29E-03 Page 1-3 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Gaseous Effluents

-Elevated Releases -Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases AR-41 Ci O.OOE+OO 4.93E-02 1.90E-02 4.21 E-05 6.84E-02 KR-85 Ci 4.14E-03 O.OOE+OO O.OOE+OO O.OOE+OO 4.14E-03 KR-85M Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.88E-06 4.88E-06 XE-131M Ci O.OOE+OO 3.27E-04 8.28E-05 O.OOE+OO 4.10E-04 XE-133 Ci 7.36E-01 4.05E-02 1.28E-02 3.67E-02 8.26E-01 XE-133M Ci O.OOE+OO 3.99E-04 1.88E-04 O.OOE+OO.

5.86E-04 XE-135 Ci O.OOE+OO 2.64E-04 1.23E-05 1.84E-04 4.60E-04 Total for Period *Ci 7.40E-01 9.09E-02 3.22E-02 3.69E-02 9.00E-01 B. Iodines 1-131 Ci 7.68E-10 O.OOE+OO O.OOE+OO 3.72E-10 1.14E-09 Total for Period Ci 7.68E-10 O.OOE+OO O.OOE+OO 3.72E-10 1.14E-09 C. Particulates Half-Life;;:

8 days None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium H-3 Ci 3.93E-05 6.08E-02 4.22E-02 4.91E-02 1.52E-01 E. Carbon-14 C-14 Ci 4.19E+OO 4.27E+OO 4.18E+OO 3.86E+OO 1.65E+01 F. Gross Alpha Total for Period Ci O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-4 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Gaseous Effluents

-Ground Releases -Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO B. Iodines None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates Half-Life<'=

8 days None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium H-3 Ci 2.13E+OO 2.62E+OO 5.35E+OO 6.93E+OO 1.70E+01 E. Carbon-14 C-14 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-5 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Gaseous Effluents

-Ground Releases -Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO B. Iodines None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates Half-Life;:::

8 days None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium H-3 Ci 6.03E-02 1.34E-02 1.77E-02 4.43E-02 1.36E-01 E. Carbon-14 C-14 Ci O.OOE+OO O.OOE+OO O.OOE+OO

• O.OOE+OO O.OOE+OO F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-6

• Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Liquid Effluents

-Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Products

• 1. Total Release Ci 2.59E-04 1.13E-03 9.48E-04 1.93E-03 4.27E-03 2. Avg. Diluted Cone. µCi/ml 4.82E-14 2.59E-13 2.82E-13 5.48E-13 2.72E-13

3. Batch Releases µCi/ml 3.10E-11 1.34E-10 1.11E-10 2.25E-10 1.26E-10 B. Tritium 1. Total Release Ci 2.04E+02 1.86E+02 3.90E+02 2.59E+02 1.04E+03 2. Avg. Diluted Cone. µCi/ml 6.83E-08 7.28E-08 1.48E-07 1.21 E-07 1.02E-07 3. Batch Releases µCi/ml 2.44E-05 2.20E-05 4.55E-05 3.02E-05 3.06E-05 C. Dissolved

& Entrained Gases 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 2. Avg. Diluted Cone. µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Batch Releases µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Gross Alpha 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Avg. Diluted Cone. µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Batch Releases µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E. Volume of Liquid Waste 1. Continuous Releases liters 6.04E+08 5.24E+08 5.57E+08 1.04E+09 2.73E+09 2. Batch Releases liters 9.41E+05 1.02E+06 1.42E+06 2.54E+06 5.92E+06 F. Volume of Dilution Water 1. Continuous Releases 8.37E+09 8.44E+09 8.55E+09 8.55E+09 3.39E+10 2. Batch Releases liters 8.37E+09 8.44E+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 1/1/2015 -12/31/2015 Liquid Effluents

-Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO B. Tritium H-3 Ci 2.73E-01 2.71 E-01 3.00E-01 4.63E-01 1.31E+OO C. Dissolved

& Entrained Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-8 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Liquid Effluents

-Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products AG-110M Ci O.OOE+OO 2.62E-05 9.91E-05 O.OOE+OO 1.25E-04 C0-58 Ci 5.77E-05 7.17E-04 6.66E-04 1.04E-03 2.48E-03 C0-60 Ci O.OOE+OO 6.16E-05 4.48E-05 O.OOE+OO 1.06E-04 CR-51 Ci O.OOE+OO 5.71E-05 O.OOE+OO O.OOE+OO 5.71E-05 CS-137 Ci 1.40E-04 6.64E-05 O.OOE+OO O.OOE+OO 2.07E-04 FE-55 Ci O.OOE+OO O.OOE+OO O.OOE+OO 8.56E-04 8.56E-04 1.-131 Ci O.OOE+OO O.OOE+OO O.OOE+OO 5.04E-06 5.04E-06 NB-95 Ci O.OOE+OO 6.21E-05 O.OOE+OO O.OOE+OO 6.21E-05 NB-97 .Ci O.OOE+OO 1.16E-05 O.OOE+OO O.OOE+OO 1.16E-05 Nl-63 Ci 6.15E-05 1.15E-04 1.38E-04 2.80E-05 3.43E-04 ZR-97 Ci O.OOE+OO 1.16E-05 O.OOE+OO O.OOE+OO 1.16E-05 TOtal for Period Ci 2.59E-04 1.13E-03 9.48E-04 1.93E-03 4.27E-03 B. Tritium H-3 Ci 2.04E+02 1.86E+02 3.89E+02 2.58E+02 1.04E+03 C. Dissolved

& Entrained Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-9 Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 2 Supplemental Information This attachment includes supplemental information to the gaseous and liquid effluents report. Page 2-1 I. A. B. Regulato!l'.

Limits -Per Unit Noble Gases -Air Dose 1. Calendar Quarter Gamma Dose 2. Calendar quarter Beta Dose 3. Calendar Year Gamma Dose 4. Calendar Year Beta Dose Liquid Effluents

-Dose Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015

=5 mRAD = 10 mRAD = 10 mRAD = 20 mRAD 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 B. Liquid Effluents

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

• V. Batch Releases A. Liquid Effluents

1. Total Number of Batch Releases 2. Total Time (min) for Batch Releases 3. Maximum Time (min) for a Batch Release 4. Average Time (min) for Batch Releases 5. Minimum Time (min) for a Batch Release 6. Average Dilution Water Flow During Release (gpm) B. Gaseous Effluents

1. Total Number of Batch Releases 2. Total Time (min) for Batch Releases 3. Maximum Time (min) for a Batch Release 4. Averag*e Time (min) for Batch Releases 5. Minimum Time (min) for a Batch Release VI. Abnormal Releases See Attachment 5, Unplanned Offsite Releases.

6.70E+01 1.34E+04 2.25E+02 2.00E+02 5.90E+01 1.70E+.04

• 4.90E+01 5.88E+04 1.62E+04 1.20E+03 3.50E+01 Page 2-2 Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 2015 ARERR contains estimates of C-14 radioactivity released in 2015, 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). Amore 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 Ocor:iee Nuclear Station 2015 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 2015 results in a site total C-14 gaseous release estimate to the environme*nt of 23.54 Curies. 70% of the C-14 gaseous effluent is assumed to be from batch releases (e.g. WGDTs), and 30% of C-14 gaseous effluent is assumed to be from continuous releases through the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14", 2004). C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. Since the PWR operates with a reducing chemistry, most, if not all, of the C-14 species initially produced are organic (e.g., methane).

As a general rule, C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment (e.g. during shutdown or refueling), a slow transformation from an organic to an inorganic chemical form can occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic with an average of 80% organic with the remainder being C0 2 (Ref. EPRI TR-105715).

For the Oconee Nuclear Station 2015 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 2015 is well below the 1 OCFR50, 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 1/1/2015-12/31/2015 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 1/1/2015 -12/31/2015 Summary of Changes in Land Use Census Affecting Effluent Dose Calculations The 2015 Land Use Census was performed May 19-20, 2015, and the results were certified and made available for use on June 4, 2015. The following are changes to residences, gardens, and milk animals from the previous year. Residences No changes to nearest residence in each sector. 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 No changes to nearest milk animal in each sector. 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 1/1/2015 -12/31/2015 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 1/1/2015 -12/31/2015 Type of Number of Number of Waste Container Solidification Burial Total Waste Shipped Shipments Containers Class Type Agent Volume Activity (m3) (Curies) 1. Waste from Liguid SJ£stems a. Dewatered Secondary Resins 4 12 AU GDP N/A 70.48 1.677 5-B Type A b. Dewatered Primary Resins 6 6 N/A 20.44 176.38 1 -AS GDP c. Evaporator Concentrates 0 d. Dewatered Mechanical Filters 2 2 c Type A N/A 6.81 8.48 e. Dewatered Demineralizers 0 f. Solidified (cement) Acids, 0 Oils, Sludge 2. Dry Solid Waste a. Dry Active Waste 0 (compacted)

b. Dry Active Waste (non-37-AU 19 38 GDP N/A 890.64 177.686 compacted) 1 -AS c. Dry Active Waste (brokered) 0 d. Irradiated Components 0 3. Total Solid Waste 31 58 988.37 364.223 Page 3-2 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Type of Waste Shipped Radionuclide

1. Waste from Liquid Systems a. Dewatered Secondary Resins 15-2007 AG-110m C-14 CE-144 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 MN-54 Nl-63 SB-125 AG-110m C-14 CE-144 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 MN-54 Nl-63 SB-125 AG-110m C-14 CE-144 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 MN-54 NB-95 Nl-63 SB-125 ZN-65 AG-110m C-14 CE-144 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 NB-95 Nl-63 SB-125 ZN-65 % Abundance 0.0768 7.9182 0.0348 0.0284 0.0379 2.3048 0.0998 0.7230 12.7509 55.5762 0.1093 19.8885 0.4721 0.0425 6.1575 0.0218 0.0150 0.0018 1.5776 0.1961 1.1074 7.7088 67.3031 0.0494 15.3938 0.4558 0.1287 5.0592 0.0182 0.0203 0.0825 1.4527 0.0530 0.4142 5.7692 73.9645 0.1059 0.0006 12.6923 0.2379 0.0340 0.0329 2.8774 0.0358 0.0262 0.0994 0.8355 0.0926 0.6613 4.5806 82.9032 0.0025 7.2258 0.3774 0.0209 Page 3-3 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015

b. Dewatered Primary Resins AG-110m AM-241 C-14 CE-144 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 1-129 MN-54 Nl-59 Nl-63 SB-125 SR-89 SR-90 TC-99 ZN-65 AG-110m AM-241 C-14 CE-144 CM-242 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 FE-59 MN-54 NB-95 Nl-63 SB-124 SB-125 SR-90 ZN-65 ZR-95 0.0566 0.0002 1.3411 0.0177 0.0002 0.5430 7.6159 4.4702 1.7980 7.4834 18.0464 0.3175 0.0005 0.8212 0.3709 56.9536 0.1298 0.0006 0.0338 0.0053 0.0573 0.0631 0.0012 1.8803 0.0631 0.0004 0.0012 0.5676 18.4556 6.6409 0.7626 3.7066 14.7683 0.0263 1.2259 0.0772 50.3861 0.2954 0.5097 0.0392 0.2297 0.0595 Page 3-4 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 AG-110m Be-7 C-14 CE-144 CM-242 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 FE-59 H-3 1-129 MN-54 NB-95 Nl-59 Nl-63 PU-238 PU-241 SB-124 SR-89 SR-90 TC-99 ZN-65 ZR-95 AG-110m AM-241 Be-7 C-14 CE-144 CM-242 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 MN-54 Nl-59 Nl-63 PU-238 . PU-241 SB-124 SB-125 SR-89 SR-90 TC-99 ZN-65 0.0652 3.2879 0.3561 0.0220 0.0001 0.0001 0.6561 18.4848 4.6970 0.4212 2.1364 17.1212 0.0270 0.1432 0.0002 2.4242 0.0703 0.2727 49.3939 0.0003 0.0049 0.0134 0.0261 0.0161 0.0014 0.2152 0.0491 0.1014 0.0001 1.3264 0.3069 0.0254 0.0001 0.0001 0.5938 12.7778 4.7917 0.9479 5.1389 16.7014 0.0090 1.7951 0.3083 54.5139 0.0004 0.0090 0.0462 0.0816 0.0111 0.0340 0.0022 0.1681 Page 3-5 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 AG-110m AM-241 Be-7 C-14 CE-144 CM-242 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 1-129 MN-54 NB-95 Nl-59 Nl-63 PU-238 PU-241 SB-124 SB-125 SR-90 TC-99 ZN-65 ZR-95 AG-110m AG-108m Be-7 C-14 CE-144 CM-242 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 1-129 MN-54 NB-95 Nl-59 Nl-63 PU-238 PU-241 SB-124 SB-125 SR-89 SR-90 TC-99 ZN-65 c. Evaporator Concentrates NIA 0.1680 0.0003 0.3688 1.5156 0.0452 0.0005 0.0004 0.5422 9.2188 6.3438 0.8125 4.6406 20.0000 0.0007 1.7344 0.1930 0.3484 52.9688 0.0011 0.0179 0.0805 0.1656 0.0341 0.0019 0.2797 0.1336 0.1302 0.0389 0.1398 0.0015 0.0802 0.0003 0.0004 0.4551 5.7485 5.0299 1.2395 7.6048 10.8683 0.0078 0.0001 1.6287 0.0461 0.6886 65.8683 0.0001 0.0179 . 0.0162 0.0832 0.0003 0.0012 0.0062 0.1964 N/A Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015

d. Dewatered Mechanical Filters 15-2006 AG-110m C-14 CE-144 C0-57 C0-58 C0-60 CR-51 CS-134 CS-137 FE-55 FE-59 H-3 MN-54 NB-95 Nl-63 SB-125 SR-90 ZN-65 ZR-95 AG-110m C-14 CE-144 HF-181 SC-46 C0-57 C0-58 C0-60 CR-51 CS-134 CS-137 FE-55 FE-59 H-3 1-129 MN-54 NB-95 Nl-63 SB-124 SN-113 SR-90 TC-99 . ZN-65 ZR-95 e. Dewatered Demineralizers NIA f. Solidified (cement) Acids, Oils, Sludge NIA 2. Dry Solid Waste a. Dry Active Waste (compacted)

NIA 0.0240 16.6167 0.7944 0.2377 8.3298 26.5525 0.0040 8.8865 25.4818 2.6124 0.0010 0.0042 4.0685 0.1015 4.2398 0.0621 0.0098 1.2355 0.7794 0.6010 -7.3228 0.6378 0.0003 0.0010 0.4672 9.2651 18.8714 0.4908 0.0745 1.5171 46.7192 0.0491 0.0596 0.2074 4.8556 0.2580 4.7769 0.0352 0.0003 0.0073 0.8110 2.3333 0.9895 NIA NIA NIA Page 3-7 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/3112015

b. Dry Active Waste (non-compacted) 15-2002 C-14 0.2781 CE-144 0.2933 C0-57 0.3337 C0-58 81.4050 C0-60 1.6405 CR-51 1.9656 CS-137 0.0844 FE-55 5.1694 FE-59 0.2317 MN-54 0.2559 NB-95 1.1598 Nl-63 5.9118 TC-99 0.1605 ZR-95 1.0179 15-2003 C-14 0.2329 CE-144 0.2573 C0-57 0.2934 C0-58 82.4883 C0-60 1.3873 CR-51 2.5869 CS-137 0.0705 FE-55 4.3897 FE-59 0.2606 MN-54 0.2099 NB-95 1.4047 Nl-63 4.9484 TC-99 0.1344 ZR-95 1.0516 15-2004 C-14 0.3228 CE-144 0.3263 M0-99 0.2711 C0-57 0.3709 C0-58 80.4825 C0-60 1.8921 CR-51 1.4737 CS-137 0.0978 FE-55 5.6667 FE-59 0.2089 MN-54 0.2711 NB-95 0.9588 Nl-63 6.8526 TC-99 0.1854 ZR-95 0.9856 15-2005 C-14 0.2696 CE-144 0.2872 C0-57 0.3264 C0-58 82.2336 C0-60 1.5916 CR-51 2.0047 CS-137 0.0817 FE-55 5.0215 FE-59 0.2365 MN-54 0.2510 NB-95 1.1879 Nl-63 5.7234 TC-99 0.6879 ZR-95 1.0299 Page 3-8 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 15-2009 C-14 0.3090 CE-144 0.3164 C0-57 0.3589 C0-58 80.5104 C0-60 1.8167 CR-51 1.5394 CS-137 0.0959 FE-55 5.6961 FE-59 0.2110 MN-54 0.2769 NB-95 0.9942 Nl-63 6.5661 TC-99 0.1774 ZR-95 0.2065 15-2013 AG-110m 0.0354 C-14 2.9454 CE-144 0.1250 C0-57 0.0605 C0-58 5.9876 C0-60 2.4101 CR-51 0.2236 CS-137 0.4985 FE-55 69.7786 FE-59 0.0199 MN-54 0.2043 NB-95 0.1214 Nl-63 16.9773 SB-125 0.3151 ZR-95 0.1352 15-2014 C-14 0.3451 CE-144 0.3422 C0-57 0.3862 C0-58 79.5519 C0-60 2.0170 CR-51 1.2759 CS-137 0.1042 FE-55 6.3100 FE-59 0.1948 MN-54 0.3005 NB-95 0.8719 Nl-63 7.3252 TC-99 0.1986 ZR-95 0.9656 15-2015 C-14 0.2933 CE-144 0.3053 C0-57 0.3465 C0-58 81.1321 C0-60 1.7324 CR-51 1.7015 CS-137 0.0889 FE-55 5.4374 FE-59 0.2196 MN-54 0.2676 NB-95 1.0635 Nl-63 6.2264 TC-99 0.1690 ZR-95 1.0069 Page 3-9 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 15-2016 C-14 0.3373 CE-144 0.3369 C0-57 0.3827 C0-58 79.52 C0-60 1.9801 CR-51 1.3150 CS-137 0.1023 FE-55 6.1774 FE-59 0.1974 MN-54 0.2954 NB-95 0.8914 Nl-63 7.1713 TC-99 0.1945 ZR-95 0.9709 15-2017 C-14 0.2330 CE-144 0.2577 C0-57 0.2924 C0-58 82.6667 C0-60 1.3861 CR-51 2.5805 CS-137 0.0706 FE-55 4.3813 FE-59 0.2609 MN-54 0.2240 NB-95 1.4048 Nl-63 4.9547 TC-99 0.1341 ZR-95 1.0611 15-2019 C-14 0.2013 CE-144 0.2314 C0-57 0.2642 C0-58 83.3724 C0-60 1.2064 CR-51 3.2682 CS-137 0.0613 FE-55 3.8411 FE-59 0.2867 MN-54 0.2013 NB-95 1.6419 Nl-63 4.2839 TC-99 0.1161 ZR-95 1.0793 15-2020 C-14 0.3053 CE-144 0.3113 C0-57 0.3537 C0-58 80.4000 C0-60 1.7943 CR-51 1.8323 CS-137 0.0925 FE-55 5.5967 FE-59 0.2203 MN-54 0.2723 NB-95 1.0883 Nl-63 6.4667 TC-99 0.1754 ZR-95 0.9963 Page 3-10 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 C-14 CE-144 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-95 Nl-63 TC-99 ZR-95 C-14 CE-144 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-95 Nl-63 TC-99 ZR-95 C-14 CE-144 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-95 NJ-63 TC-99 ZR-95 0.3578 0.3499 0.3979 79.053 2.0787 1.1958 0.1112 6.4912 0.1892 0.3074 0.8331 7.5762 0.2056 0.9583 0.2371 0.2343 0.2676 83.3333 1.2296 3.2579 0.0624 3.9057 0.2843 0.2031 1.6415 4.3679 0.1182 1.0786 0.1851 0.2172 0.2406 85.5227 1.1108 3.7500 0.0563 3.5653 0.3017 0.1879 1.7997 3.9631 0.1065 1.0895 Page 3-11 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 AG-110m CM-243 AM-241 C-14 CE-144 CM-242 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-94 NB-95 Nl-63 PU-238 PU-239/40 PU-241 SB-124 SB-125 SN-113 SR-90 ZN-65 ZR-95 AG-110m CM-243 AM-241 C-14 C0-57 C0-58 C0-60 CR-51 CS-134 CS-137 FE-55 FE-59 H-3 1-129 MN-54 NB-94 NB-95 Nl-63 PU-238 PU-239/40 PU-241 SB-124 SB-125 SN-113 SR-90 ZN-65 ZR-95 . 0.0033 0.0006 0.0015 0.5523 0.0044 0.0218 0.0033 0.1753 1.0483 0.0147 0.0031 94.0805 0.0943 0.0493 0.0024 0.0270 3.8621 0.0011 0.0006 0.0248 0.0096 0.0532 0.0021 0.0063 0.0224 0.0137 0.0280 0.0005 0.0014 0.0080 0.0009 0.2366 1.1066 0.0145 0.0185 0.0539 89.7971 0.0315 3.0368 0.0605 0.0605 0.0023 0.0329 4.5882 0.0011 0.0006 0.0234 0.0092 0.0823 0.0020 0.0065 0.0260 0.0132 Page 3-12 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 AG-110m CM-243 AM-241 C-14 CM-242 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-94 NB-95 Nl-63 PU-238 PU-239/40 PU-241 SB-124 SB-125 SN-113 SR-90 ZN-65 ZR-95 AG-110m CM-243 AM-241 C-14 CE-144 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-94 NB-95 Nl-63 PU-238 PU-239/40 PU-241 SB-124 SB-125 SN-113 SR-90 ZN-65 ZR-95 c. Dry Active Waste (brokered)

NIA d. Irradiated Components N/A 0.0033 0.0006 0.0015 0.0044 0.0001 0.0032 0.1743 1.0457 0.0146 0.0031 93.9948 0.0939 0.0493 0.0024 0.0269 3.8538 0.0001 0.0006 0.0143 0.0095 0.0531 0.0021 0.0069 0.0224 0.0136 0.0030 0.0002 0.0015 0.5695 0.0041 0.0030 0.1363 1.0605 0.0101 0.0032 94.1406 0.0685 0.0465 0.0025 0.0191 3.9805 0.0012 0.0006 0.0253 0.0073 0.0532 0.0018 0.0071 0.0207 0.0105 N/A N/A Page 3-13 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 4 Meteorological Data This attachment includes a summary of meteorological joint frequency distributions of wind speed, wind direction, and atmospheric stability (hours of occurrence).

Page 4-1 Lower Level Wind Stability Speed Class (mph) N NNE NE 0.46-0.75 a a a 0.76-1.00 a a a 1.01-1.25 a a a 1.26-1.50 1 a a 1.51-2.00 2 a 1 2.01-3.00 a a a A 3.01-4.00 0 a 3 4.01-5.00 a 0 a 5.01-6.00 a 0 a 6.01-8.00 0 0 0 8.01-10.00 a 0 0 10.01-max 0 0 0 0.46-0.75 0 0 0 0.76-1.00 0 0 0 1.01-1.25 0 0 1 1.26-1.50 a 0 0 1.51-2.00 3 2 1 2.01-3.00 2 1 6 B 3.01-4.00 1 2 2 4.01-5.00 0 0 1 5.01-6.00 0 0 0 6.01-8.00 0 0 0 8.01-10.00 0 0 0 10.01-max 0 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a 3 0 0 1 0 0 0 2 22 3 0 0 0 1 1 23 69 1 2 0 0 0 0 3 8 1 0 0 0 0 a a 1 0 0 0 a 0 a a 0 0 0 0 0 0 0 0 0 0 0 0 a 0 0 0 0 0 0 0 a 0 0 0 0 0 0 0 0 0 a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 0 0 a 1 3 3 2 1 0 . 0 1 . 14 33 10 6 1 0 2 6 42 61 3 3 a 0 0 0 16 13 0 0 a 0 0 0 0 2 0 0 0 0 0 0 0 1 0 0 0 0 0 a 0 2 0 0 0 0 a a 0 0 0 0 0 0 a a 0 0 WSW w WNW NW NNW a a a a a a a a a a a a a a a a a 1 a a 2 2 4 1 0 15 5 1 1 2 1 2 1 0 0 1 a 1 0 0 1 1 1 1 0 0 0 6 3 0 a 0 0 a 0 0 0 0 0 0 0 0 0 0 0 0 0 a 0 0 0 0 a 0 0 0 0 0 2 0 9 6 2 2 0 33 3 3 2 a 1 1 3 0 1 0 0 0 0 0 1 0 3 1 0 0 1 4 3 2 .o 1 1 1 0 0 0 0 0 0 Page 4-2 Lower Level Wind Stability Speed Class (mph) N NNE 0.46-0.75 0 0 0.76-1.00 0 0 1.01-1.25 0 0 1.26-1.50 2 0 1.51-2.00 4 7 2.01-3.00 0 1 c 3.01-4.00 0 3 4.01-5.00 0 1 5.01-6.00 0 0 6.01-8.00 0 0 8.01-10.00 0 0 10.01-max 0 0 0.46-0.75 0 0 0.76-1.00 12 11 1.01-1.25 28 21 1.26-1.50 19 28 1.51-2.00 19 38 2.01-3.00 22 21 D 3.01-4.00 4 10 4.01-5.00 0 1 5.01-6.00 0 0 6.01-8.00 0 0 8.01-10.00 0 0 10.01-max 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector NE ENE E ESE SE SSE s SSW SW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 1 0 0 0 0 0 2 3 5 5 6 2 4 1 3 7 16 33 13 22 12 7 6 5 6 55 36 1 2 3 0 0 0 2 16 17 1 0 0 0 0 0 0 3 6 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 1 0 2 2 1 1 1 1 12 10 5 3 3 0 4 8 14 10 8 9 7 8 12 8 15 21 29 31 25 19 22 21 25 44 52 61 99 75 30 36 48 42 67 89 139 197 78 24 25 16 29 136 161 54 67 5 1 0 0 1 54 74 16 9 0 0 0 0 0 8 25 3 0 0 0 0 0 0 2 4 1 0 0 0 0 0 .0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW w WNW NW NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 1 2 2 1 22 9 5 8 3 23 3 4 2 0 4 0 4 3 0 0 2 5 0 2 3 1 3 4 2 1 0 11 2 1 0 0 0 1 0 0 . 0 0 0 0 1 1 1 1 2 17 16 15 9 13 29 26 23 14 39 46 32 22 19 32 76 49 21 15 17 85 33 15 13 14 45 23 22 8 8 31 14 23 10 3 23 7 14 13 0 9 6 8 1 0 1 7 0 0 0 0 0 0 0 0 Page 4-3 Lower Level Wind Stability Speed Class (mph) N NNE NE 0.46-0.75 19 9 12 0.76-1.00 87 58 46 1.01-1.25 64 35 47 1.26-1.50 41 30 52 1.51-2.00 35 23 65 2.01-3.00 9 14 75 E 3.01-4.00 2 4 26 4.01-5.00 1 0 3 5.01-6.00 0 0 0 6.01-8.00 0 0 0 8.01-10.00 0 0 0 10.01-max 0 0 0 0.46-0.75 0 0 0 0.76-1.00 5 2 2 1.01-1.25 2 2 3 1.26-1.50 1 0 1 1.51-2.00 0 0 1 2.01-3.00 0 1 4 F 3.01-4.00

• 0 0 0 4.01-5.00 0 0 0 5.01-6.00 0 0 0 6.01-8.00 0 0 0 8.01-10.00 0 0 0 10.01-max 0 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW 11 6 9 3 3 8 7 11 42 46 33 35 18 26 .34 26 47 43 38 41 34 36 36 31 54 50 46 43 44 40 40 45 88 67 37 43 73 49 50 60 89 41 11 10 18 30 45 85 8 1 2 2 1 3 15 33 1 1 0 0 0 0 0 10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 0 0 1 0 1 3 3 1 1 3 1 2 3 3 2 6 0 2 1 2 0 1 3 6 1 1 0 2 4 2 2 8 3 1 3 3 3 4 1 1 1 0 1 1 5 2 0 1 0 0 0 1 1 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW w WNW NW NNW 10 13 19 19 11 49 55 85 134 138 41 38 63 79 89 31 20 34 48 32 27 15 27 23 19 45 20 12 11 10 28 14 2 0 1 9 3 2 2 0 1 2 2 2 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 6 1 0 9 14 22 20 8 3 4 30 15 1 2 2 25 22 3 1 1 2 9 0 2. 2 0 1 2 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-4 Lower Level Stability Wind Class Speed (mph) N NNE NE 0.46-0.75 0 0 0 0.76-1.00 1 1 1 1.01-1.25 0 2 1 1.26-1.50 1 0 1 1.51-2.00 0 0 0 2.01-3.00 0 0 0 G 3.01-4.00 0 0 0 4.01-5.00 0 0 0 5.01-6.00 0 0 0 6.01-8.00 0 0 0 8.01-10.00 0 0 0 10.01-max 0 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW w WNW NW NNW 0 0 0 0 0 1 0 3 4 0 0 2 7 4 0 1 2 2 4 0 1 0 1 2 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-5 Upper Level Wind Stability Speed Class (mph) N NNE NE 0.46-0.75 0 0 0 0.76-1.00 0 0 0 1.01-1.25 0 0 0 1.26-1.50 0 0 0 1.51-2.00 0 1 0 2.01-3.00 1 1 0 A 3.01-4.00 0 0 0 4.01-5.00 0 0 0 5.01-6.00 0 0 2 6.01-8.00 0 0 1 8.01-10.00 0 0 *o 10.01-max 0 0 0 0.46-0.75 0 0 0 0.76-1.00 0 0 0 1.01-1.25 0 0 0 1.26-1.50 0 0 0 1.51-2.00 0 0 1 2.01-3.00 2 3 2 B 3.01-4.00 0 1 1 4.01-5.00 2 1 1 5.01-6.00 0 0 1 6.01-8.00 0 0 2 8.01-10.00 0 0 0 10.01-max 0 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2. 0 0 0 0 0 0 0 3 1 0 1 0 0 1 11 34 1 1 0 0 1 0 20 28 0 2 0 0 0 1 6 13 0 2 0 0 0 0 4 10 1 0 0 0 0 0 0 2 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ,0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 6 8 3 4 1 1 3 2 15 53 4 6 0 0 0 7 27 18 5 9 0 0 0 1 17 12 0 1 0 0 0 1 10 14 1 0 0 0 0 0 0 5 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 WSW w WNW NW NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 3 1 0 10 2 2 1 1 6* 0 0 1 1 1 0 0 0 0 0 2 1 0 0 1 1 2 1 0 1 0 5 3 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 2 5 2 2 2 21 5 1 0 0 8 0 0 0 0 2 0 1 2 0 2 1 0 2 1 1 0 3 0 0 1 1 2 3 0 2 1 3 3 2 Page 4-6 Upper Level Wind Stability Speed Class (mph) N NNE 0.46*0.75 0 0 0.76-1.00 0 0 1.01-1.25 0 0 1.26-1.50 0 0 1.51-2.00 3 4 2.01-3.00 1 3 c 3.01-4.00 0 1 4.01-5.00 0 2 5.01-6.00 0 1 6.01-8.00 0 1 8.01-10.00 0 0 10.01-max 0 0 0.46-0.75 1 0 0.76-1.00 0 4 1.01-1.25 9 12 1.26-1.50 11 18 1.51-2.00 35 27 2.01-3.00 30 50 D 3.01-4.00 16 25 4.01-5.00 5 8 5.01-6.00 4 9 6.01-8.00 1 0 8.01-10.00 0 1 10.01-max 0 0 NE 0 0 0 0 0 7 3 1 1 1 0 0 1 2 8 7 29 58 83 95 47 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 3 0 0 1 1 1 2 4 17 11 5 5 3 7 10 21 29 16 9 3 2 3 8 31 13 7 9 2 0 0 2 16 13 3 1 0 0 0 2 10 11 1 0 0 0 0 0 4 16 0 0 0 0 0 0 0 3 0 0 0 0 0 0 0 1 0 0 0 0 1 0 1 1 2 0 1 0 1 1 1 3 1 2 1 6 0 3 8 12 11 7 0 5 9 7 12 26 13 28 9 25 29 16 42 54 63 83 28 38 47 52 71 68 94 76 20 13 16 31 57 87 74 43 3 1 2 3 52 76 41 13 0 0 0 3 26 70 37* 23 3 0 1 0 1 14 81 13 3 0 0 0 0 0 2 18 2 0 0 0 0 0 0 0 2 WSW w WNW NW NNW 0 0 0 0 0 0 0 0 0 0 1 0 1 0 0 1 1 2 1 0 13 8 2 3 3 23 0 2 0 3 1 2 o. 3 0 3 1 0 3 0 1 0 4 3 0 2 2 4 3 2 4 0 8 3 3 1 0 3 4 0 1 2 0 1 1 3 8. 4 2 7 13 12 16 13 7 24 22 16 15 23 46 24 17 15 33 64 30 25 26 28 42 14 15 9 12 29 19 18 3 11 29 12 19 10 6 49 15 40 20 5 15 10 12 11 0 3 11 3 1 0 Page 4-7 Upper Level Stability Wind Class Speed (mph) N NNE 0.46-0.75 2 1 0.76-1.00 10 6 1.01-1.25 25 16 1.26-1.50 50 32 1.51-2.00 134 84 2.01-3.00 232 182 E 3.01-4.00 44 42 4.01-5.00 11 18 5.01-6.00 1 5 6.01-8.00 1 1 8.01-10.00 1 1 10.01-max 0 0 0.46-0.75 0 0 0.76-1.00 3 2 1.01-1.25 1 1 1.26-1.50 7 1 1.51-2.00 18 13 2.01-3.00 21 22 F 3.01-4.00 4 4 4.01-5.00 1 1 5.01-6.00 0 2 6.01-8.00 0 1 8.01-10.00 0 0 10.01-max 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector NE ENE E ESE SE SSE s SSW SW 3 0 1 0 0 1 1 0 4 4 3 2 5 5 4 4 3 4 17 8 7 9 4 8 3 8 12 13 10 14 5 7 6 14 12 15 33 34 26 18 13 18 13 15 27 110 75 50 31 31 39 45 50 101 87 69 . 35 22 23 23 59 40 78 46 33 27 5 4 10 18 30 61 36 6 6 1 1 2 9 21 42 15 7 1 2 0 2 1 8 35 1 0 0 0-0 0 0 0 4 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 0 0 1 3 0 0 2 0 2 1 0 1 3 0 1 1 2 1 1 3 1 3 4 2 0 3 3 3 1 1 6 4 1 4 3 1 1 1 1 5 5 5 3 4 4 2 3 8 0 4 0 2 1 1 1 2 9 2 1 2 1 0 0 0 4 3 1 3 0 0 0 0 0 0 2 0 0 0 0 1 0 0 0 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW w WNW NW NNW 0 1 0 1 3 10 11 13 13 11 8 25 20 30 29 18 22 35 49 63 36 32 42 72 119 68 30 22 35 126 28 11 11 24 17 17 11 10 14 3 20 15 12 5 5 27 14 5 2 0 2 2 1 1 0 0 0 0 0 0 0 0 0 0 0 0 2 1 0 0 2 1 1 2 2 3 1 4 2 3 1 5 2 1 6 6 7 2 6 4 5 1 0 1 4 2 1 0 1 0 2 2 0 0 1 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-8 Upper Level Wind Stability Speed Class (mph) N NNE NE 0.46-0.75 0 0 0 0.76-1.00 0 0 0 1.01-1.25 0 0 0 1.26-1.50 0 0 0 1.51-2.00 2 0 1 2.01-3.00 2 2 1 G 3.01-4.00 1 0 1 4.01-5.00 0 0 . 0 5.01-6.00 0 0 0 6.01-8.00 0 0 0 8.01-10.00 0 0 0 10.01-max 0 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 0 2* 0 0 1 0 0 0 0 2 0 0 0 0 0 0 1 1 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW w WNW NW NNW 0 0 0 0 0 0 1 0 1 0 0 0 0 0 0 0 1 0 2 0 2 1 2 2 0 2 2 0 0 0 1 0 0 0 2 2 2 0 0 1 1 0 0 0 0 0 1 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 1/1/2015 -12/31/2015 ATTACHMENT 5 Unplanned Offsite Releases This attachment includes a summary of the unplanned offsite releases of gaseous and liquid radioactive effluents.

Page 5-1 Attachment 5 Unplanned Offsite Releases Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Oconee Nuclear Station had zero (0) unplanned liquid offsite release radioactive effluents.

Oconee Nuclear Station had one (1) unplanned gaseous offsite release of radioactive effluents.

Summary is provided below. Unplanned release of "38" Gaseous Waste Decay Tank: Reference NCR 01907276 Event Summary: On 1/27/15, during venting of U3 Let Down Storage Tank (LDST) to the 3B Gaseous Waste Decay Tank (GWDT), an increase in counts was observed on the unit vent normal range radiation monitor, 3 RIA 45, at 23:26 hours. The LDST venting was terminated and the 3B GWDT was isolated.

Once isolated the 3B GWDT pressure was observed to be decreasing and the GWDT radiation monitor, 3 RIA 37, had increased counts indicating the contents were being released to the unit vent. Radiation monitor 3RIA-45 exhibited increased count rates due to the release, but no setpoints or instantaneous release rate limits were exceeded.

The unplanned release was terminated when 3B GWDT reached 0 psig at 07:00 on 1/28/15. Investigation identified that a 3B GWDT relief valve failed to seat, causing the 3B GWDT to lose pressure.

The GWD valve was repaired and an additional test was added to the preventative maintenance.

procedure to prevent recurrence.

A separate release permit, 2015004, was created to account for the release activity and related dose. The release volume and activity were determined using count rates and flow rates for 3RIA-37. The release volume from the 3B tank was 4500 cubic feet based on the initial tank pressure of 45 psig and tank volume chart in OP/O/A/1108/001, Curves and General Information.

The total activity of the unplanned release was 0.735 Curies. Safety Significance:

The health and safety of the public were not compromised by this event. The total activity released was 0.735 Curies. Calculated dose and dose rates to the Total Body, Skin, Gamma Air, and Beta Air were all well below the limits specified by Selected Licensee Commitments Page 5-2 Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 ATTACHMENT 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results) This attachment includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of the report as well as the total dose for the calendar year. This attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 8 km of the site for the calendar year of this report to show conformance with 40 CFR Part 190. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the Offsite Dose Calculation Manual (ODCM). Page 6-1 Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Gaseous Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 A. Noble Gases 1. Maximum Gamma Air mRAD 2.18E-04 1.88E-04 2.83E-04 (a) Limit mRAD 1.50E+01 1.50E+01 1.50E+01 (b) % of Limit 1.46E-03 1.26E-03 1.89E-03 2. Maximum Beta Air mRAD 2.0BE-04 1.30E-04 1.42E-04 (a) Limit mRAD 3.00E+01 3.00E+01 3.00E+01 (b) % of Limit 6.93E-04 4.33E-04 4.72E-04 Receptor Location 1.0 miles SW B. Iodine, H-3, & Particulates

1. Maximum Organ Dose mREM 8.90E-02 9.0BE-02 8.88E-02 (a) Limit mREM 2.25E+01 2.25E+01 2.25E+01 (b) % of Limit 3.95E-01 4.04E-01 3.95E-01 Receptor Location 1.0 miles SW Critical Age CHILD Critical Organ BONE Critical Pathway VEGETATION Qtr4 Year 1.32E-05 7.03E-04 1.50E+01 3.00E+01 8.78E-05 2.34E-03 3.91E-05 5 .. 19E-04 3.00E+01 6.00E+01 1.30E-04 8.64E-04 8.20E-02 3.51 E-01 2.25E+01 4.50E+01 3.64E-01 7.79E-01 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 1/1/2015 -12/31/2015 Liquid Effluents Dose Summary Units Qtr 1 Qtr2 Qtr 3 Qtr4 Year A. Batch Mode 1. Maximum Organ Dose mREM 4.62E-02 4.93E-02 5.41 E-02 3.60E-02 1.71 E-01 (a) Limit mREM 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.00E+01 (b) % of Limit 3.08E-01 3.29E-01 3.61 E-01 2.40E-01 5.69E-01 (c) Critical Age Adult Adult Child Child Child (d) Critical Organ Liver GILLI Liver Liver Liver (e) Critical Pathway Fish Fish Pt. Water Pt. Water Pt. Water 2. Maximum Total Body Dose mREM 3.97E-02 3.09E-02 5.41E-02 3.59E-02 1.57E-01 (a) Limit mREM 4.50E+OO 4.50E+OO 4.50E+OO 4.50E+OO 9.00E+OO (b) % of Limit 8.81 E-01 6.86E-01 1.20E+OO 7.98E-01 1.75E+OO (c) Critical Age Adult Adult Child Child Adult' (d) Critical Pathway Fish Fish Pt. Water Pt. Water Fish B. Continuous Mode 1. Maximum Organ Dose mREM 3.53E-05 3.54E-05 3.90E-05 5.73E-05 1.68E-04 (a) Limit mREM 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.00E+01 (b) % of Limit 2.35E-04 2.36E-04 2.60E-04 3.82E-04 5.59E-04 (c) Critical Age Child Child Child Child Child (d) Critical Organ Liver Liver Liver Liver Liver (e) Critical Pathway Pt. Water Pt. Water Pt. Water Pt. Water Pt. Water 2. Maximum Total Body Dose mREM 3.53E-05 3.54E-05 3.90E-05 5.73E-05 1.68E-04 (a) Limit mREM 4.50E+OO 4.50E+OO 4.50E+OO 4.50E+OO 9.00E+OO (b) % of Limit 7.85E-04 7.87E-04 8.67E-04 1.27E-03 1.86E-03 (c) Critical Age Child Child Child Child Child (d) Critical Pathway Pt. Water Pt. Water Pt. Water Pt. Water Pt. Water Page 6-3 Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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) 1. Location 2. Critical Age 3. Critical Organ 4. Gas Contribution

% 5. Liquid Contribution

% B. Maximum Total Body Dose 1. Location 2. Critical Age 3. Gas non-NG Contribution

% 4. Gas Contribution

% 5. Liquid Contribution

% 3.82E-01 mREM 1.0 miles SW CHILD BONE 8.26% 91.74% 2.74E-01 mREM 1.0 miles SW CHILD 45.73% 0.24% 54.03% Direct and air-scatter radiation dose contributions from the onsite ISFSI have been determined from 10 CFR 72.212 Evaluation Report for Phase VII 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 7 mrem/yr. The attached excerpt from the 10 CFR 72.212 Evaluation Report for Phase VII Standardized NUHOMS Cask System Rev. 00 is provided to document the method used to calculate the dose from ISFSI as less than 7 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 8 mrem/yr to the nearest real individual.

This meets the 40 CFR Part 190 requirements of an annual dose commitment to any member of the general public of less than 25 mrem total body or any organ and 75 mrem to the thyroid. Page 6-4 Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 Coe 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 boay, 75 mrem to the thyroid, arid 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 (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-131, 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) due to direct radiation from the Independent Spent FuelStorage 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 O(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 -V and loaded canisters in Phase VI of the Oconee ISFSI, together with the characteristics of assumed "design basis" fuel for unloaded canisters in Phase VI and Phase VII of the Oconee ISFSl 2* Calculation OSC-8675 3 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 Module 5 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 SAS 2 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. Page 6-5 Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 The results of the radiation source term calculation were used as input to Calculation OSC-8706 6 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.

Appropriate software quality controls have been implemented for the computer codes and data used in these analyses (specifically, Calculation DPC 1201.30 00 0010 8 contains the verification and validation for MCNP5, while SDQA-30269-NG0 9 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 23.1-1, summarizes dose rate versus distance, showing a dose rate of 6.84 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 2009 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 0.266 mrem 12). The total dose rate from all operations to the nearest real individual is therefore less than 8 mRem per year. This calculation need not consider any effluent from Phase VII.

• The Phase VII HSMs use the NUHOMS-24PHB DSCs, which are designed as "leak-tight." Per Appendix N, Section N.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-8706 6 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 VII. The Phase VII HSMs use the NUHOMS-24PHB DSCs, which are designed as "leak-tight." Per Appendix N, Section N,11.2.8 of the NUHOMS FSAR 13 , 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 6.4 References Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015

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 unloaded HSMs for Phase VI-VII of the Oconee ISFSI. The assumption of 5 years cooling time applies only to the most recent eight dry storage casks, while the balance of the casks are assumed to have been loaded one year earlier to be consistent with reasonable engineering practice.

3. Calculation OSC-8675, "Oconee ISFSI Spent Fuel Radiation Source Terms," Revision 2. 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-2N21 R6. 6. Calculation OSC-8706, "Oconee Horizontal Storage Module Shielding Evaluation," Revision 1. 7. LA-UR-03-1987, "MCNP -A General Purpose 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 1.4 10. Calculation OSC-8716, "Oconee ISFSI Dose Rate Evaluations," Revision 1. 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. Scott L. Batson to U.S. Nuclear Regulatory Commission, "2014 Annual Radioactive Effluent Release Report (ARERR), April 30, 2014. 13. NUH-003, "Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel," Revision 9. Page 6-7 Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 7 Information to Support the NEI Ground Water Protection Initiative This attachment includes a summary of voluntary reports made in accordance with the NEI Ground Water Protection Initiative and a summary of ground water well sample data. Page 7-1 Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 67 wells in 2015. 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 or semi-annually.

Ground water samples are regularly analyzed for tritium and gamma emitters, with select wells being analyzed for difficult-to-detect radionuclides.

No gamma or difficult-to-detect radionuclides, other than naturally occurring radionuclides, were identified in well samples during 2015. Results from sampling during 2015 confirmed existing knowledge of tritium concentrations in site ground water. Results from sampling during 2015 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 2015. Key to below table. NS pCi/I <MDA 20,000 pCi/I 1,000,000 pCi/I Not scheduled to be sampled, not sampled due to insufficient volume in well, or well inaccessible during outage. -picocuries per liter. -less than minimum detectable activity, typically 250 pCi/I. the Environmental Protection Agency drinking water standard for tritium. This standard applies only to water used for drinking.

the 10 CFR Part 20, Appendix B, Table 2, Column 2, Effluent Concentration Limit for tritium. Page 7-2 Well Name A-1 A-10 A-11 A-12 A-13 A-14 A-17 A-18 A-2 A-9 BG-4 GM-10 GM-10R GM-11 GM-11R GM-12 GM-12R GM-13 GM-13R GM-14 GM-14R GM-15 GM-15R GM-16DDR GM-16DR GM-16R GM-17DR GM-17R GM-18R GM-19 GM-19R GM-1R GM-20 GM-20R GM-21 GM-22 GM-23 GM-24R GM-25R GM"2DR GM-2R GM-3DR GM-3R GM-4 Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Location I Description Tritium Concentration (pCi/I) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr ONS GWPI I A-11CTP1/2 2.13E+02 <MDA <MDA <MDA ONS GWPI I A-10 I CTP 3 4.01E+02 3.23E+02 3.79E+02 4.46E+02 ONS GWPI I A-11 / CTP 3 <MDA <MDA <MDA

<MDA ONS GWPI I A-12 / CTP 3 NS <MDA NS <MDA ONS GWPI I A-13 / CTP 1/2 5.72E+02 5.32E+02 4.74E+02 5.57E+02 ONS GWPI I A-14 / CTP 1/2 <MDA <MDA 2.02E+02 <MDA ONS GWPI I A-17 / CTP 1/2 <MDA <MDA 2.43E+02 1.94E+02 ONS GWPI I A-18 / CTP 1/2 <MDA <MDA <MDA 2.19E+02 ONS GWPI I A-21 CTP 1/2 <MDA <MDA <MDA 2.32E+02 ONS GWPI I A-91CTP1/2

<MDA 2.48E+02 2.15E+02

<MDA ONS GWPI I BG-41 Ball Field <MDA <MDA <MDA

<MDA ONS GWPI I GM-10 I 525 kv Sw Yard NS <MDA NS <MDA ONS GWPI I GM-10R / 525 kv SwYard NS <MDA NS <MDA ONS GWPI I GM-11 I ONS Garage NS <MDA NS <MDA ONS GWPI I GM-11 RI ONS Garage NS <MDA NS <MDA ONS GWPI I GM-12 / E of Access Rd. NS <MDA NS <MDA ONS GWPI I GM-12R I E of Access Rd. NS <MDA NS <MDA ONS GWPI I GM-13 / 525 kv Sw Yard NS <MDA NS <MDA ONS GWPI I GM-13R / 525 kv Sw Yard NS <MDA NS <MDA ONS GWPI I GM-14 / Mnt. Trg. Facility NS <MDA NS <MDA ONS GWPI I GM-14R I Mnt. Trg. Facility NS <MDA NS <MDA ONS GWPI I GM-15 <MDA NS NS 2.02E+02 ONS GWPI I GM-15R <MDA NS NS 2.36E+02 ONS GWPI I GM-16DDR NS 2.07E+02 4.25E+02 3.66E+02 ONS GWPI I GM-16DR 8.61E+03 8.20E+03 7.47E+03 7;04E+03 ONS GWPI I GM-16R NS NS 1.28E+03 1.25E+03 ONS GWPI I GM-17DR 2.51E+03 2.58E+03 2.37E+03 2.30E+03 ONS GWPI I GM-17R 1.14E+03 1.18E+03 1.26E+03 1.15E+03 ONS GWPI I GM-18R 6.30E+03 5.89E+03 5.73E+03 5.39E+03 ONS GWPI I GM-19 1.78E+03 1.84E+03 1.84E+03 1.97E+03 ONS GWPI I GM-19R 5.02E+02 7.15E+02 8.49E+02 7.17E+02 ONS GWPI I GM-1R I CTP 1/2 <MDA <MDA <MDA <MDA ONS GWPI I GM-20 <MDA <MDA <MDA <MDA ONS GWPI I GM-20R <MDA <MDA <MDA <MDA ONS GWPI I GM-21 NS <MDA NS <MDA ONS GWPI I GM-22 NS <MDA NS <MDA ONS GWPI I GM-23 3.47E+02 NS NS 2.07E+02 ONS GWPI I GM-24R NS 1.27E+03 1.24E+03 1.28E+03 ONS GWPI I GM-25R 2.66E+02 3.21E+02 3.84E+02 NS ONS GWPI I GM-2DR I U-1/2 SFP <MDA 2.69E+02 1.97E+02 <MDA ONS GWPI I GM-2R I U-1/2 SFP 3.96E+02 1.04E+03 6.03E+02 6.00E+02 ONS GWPI I GM-3DR I U-3 SFP 3.87E+02 2.97E+02 3.12E+02 2.51E+02 ONS GWPI I GM-3R I U-3 SFP 2.36E+02 3.20E+02 2.87E+02 2.26E+02 ONS GWPI I GM-4 I Rad. Mat. WH 5.23E+02 4.61E+02 4.57E+02 4.82E+02 #of Samples 4 4 4 2 4 4 4 4 4 4 4 2 2 2 2 2 2 2 2 2 2 2 2 3 4 2 4 4 4 4 4 4 4 4 2 2 2 3 3 4 4 4 4 4 Page 7-3 Well Name GM-S GM-SR GM-6 GM-6R GM-7 GM-7DR GM-7R GM-8 GM-8R GM-9 GM-9R MW-11 MW-110 MW-13 MW-16 MW-3 MW-RP01 MW-RP02 MW-RP03 Well Name 011 013 01S Well Name Rw-1<1 l Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Location I Description Tritium Concentration (pCi/I) #of 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples ONS GWPI I GM-S / Rdwst. Bldg. 2.00E+02 2.02E+02 2.30E+02 <MDA 4 ONS GWPI I GM-SR I Rdwst. Bldg. <MDA <MDA

<MDA <MDA 4 ONS GWPI I GM-6 I Outflow to CTP-3 <MDA <MDA NS NS 2 ONS GWPI I GM-6R I Outflow to CTP-3 <MDA <MDA NS NS 2 ONS GWPI I GM-7 I S2S kv Sw Yard 2.30E+02 2.63E+02 4.02E+02 2.70E+02 4 ONS GWPI I GM-7DR <MDA <MDA

<MDA <MDA 4 ONS GWPI I GM-7R I S2S kv Sw Yard 2.SOE+03 2.28E+03 1.91E+03 1.68E+03 4 ONS GWPI I GM-8 I E of U-3 TB 2.48E+02 2.94E+02 2.77E+02

<MDA 4 ONS GWPI I GM-8R I E of U-3 TB <MDA 2.7SE+02 2.11E+02 <MDA 4 ONS GWPI I GM-9 I E of U-2 TB 3.34E+02 3.S4E+02 3.3SE+02 3.21E+02 4 ONS GWPI I GM-9R I E of U-2 TB NS <MDA <MDA <MDA 3 ONS GWPI I MW-11 I Landfill <MDA NS <MDA NS 2 ONS GWPI I MW-11 DI Landfill <MDA NS <MDA NS 2 ONS GWPI I MW-13 /Landfill

<MDA NS <MDA NS 2 ONS GWPI I MW-16 /Landfill

<MDA NS <MDA NS 2 ONS GWPI I MW-3 I Landfill <MDA NS <MDA NS 2 ONS GWPI I MW-RP01 I Landfann/Burial NS <MDA NS NS 1 ONS GWPI I MW-RP02 / Landfann/Burial NS <MDA NS NS 1 ONS GWPI I MW-RP03 I Landfann/Burial NS <MDA NS NS 1 Location I Description Tritium Concentration (pCi/I) #of 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples ONS I 011 I Ball Field <MDA <MDA <MDA <MDA 4 ONS I 013 /WH S <MDA <MDA <MDA

<MDA 4 ONS I 01 S I Brown's Bottom NS <MDA <MDA <MDA 3 Location I Description Tritium Concentration (pCi/I) # of Min Avg Max Samples I S2S kv Sw. Yard I 1.01 E+03 I 1.29E+03 I 1.S9E+03 I 13 (1) Monthly sampling performed for this location during 201S. Page 7-4 Attachment 8 Inoperable Equipment Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 8 Inoperable Equipment This attachment includes an explanation of inoperable instruments related to effluent monitoring in excess of allowed time defined by licensing bases and an explanation of permanent or temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases). / Page 8-1 Attachment 8 Inoperable Equipment Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Oconee Nuclear Station did not experience inoperable equipment relevant to effluent monitoring in excess of SLC limits during 2015. Oconee Nuclear Station did not experience permanent or temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases) during 2015. Page 8-2 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 9 Summary of Changes to the Offsite Dose Calculation Manual Example 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 ODCM Revision 57 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ODCM Revision 57 is provided in entirety on the enclosed CD. 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 57 was approved by the Station Manager on March 7, 2016. Some changes reflected in ODCM Revision 57 were implemented prior to March 7, 2016 under a different change and approval process (e.g., land use census}, and in those cases the implementation date is noted below. Executive Summary -Page 1 Revised bottom statement from: "The methodology and parameters used to assure compliance with the dose limitaions described above shall be used to prepare the radioactive liquid and gaseous effluent reports required by the SCLs and Technical Specifications." to: "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." Revision made to correct typos to "limitaions" and "SCLs" to "limitations" and "SLCs". Section 3 -Page 7 Deleted paragraphs: "In addition to High setpoints, Oconee uses "Alert" setpoints that, in total, are based on 10% of the reporting requirement from 10CFR50.73(a)(2)(viii)(A), which allows 20 times a Xe-133 Effluent Concentration (EC) value of 5.0E-07 µCi/ml at the site boundary.

Accounting for the percent apportioned to each monitored release point, each unit vent Alert setpoint is based on 60% of the Xe-133 EC. The Radwaste Facility and Interim Radwaste Building Alert setpoints are both based on 10% of the Xe-133 EC. The method used to calculate the Alert setpoints is similar to that used to calculate the maximum setpoints except the limit is based on concentration rather than dose rate. The Alert setpoints are approximately 42% of the maximum setpoints.

ONS ODCM revision 43 implemented a change-to remove the residential structure shielding factor of 0.7 from Ki, the total body dose factor due to exposure from a semi-infinite cl9ud of noble gases. KXe-133_ was changed from 206 to 294 mrem/yr per µCi/m3. Since Alert setpoints are based on concentration and not dose rate, but concentration will affect dose, the setpoints are multiplied by a unit-less factor of 206/294 (0. 7) to account for the added risk of exposure." Added paragraph: "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." Previous paragraphs deleted and replaced with new paragraph describing improved Alert setpoint methodology.

Previous methodology was confusing, requiring extensive explanation, and prone to error. New methodology provides clarity and still satisfies previous identified issue from PIP 0-05-965 where general observations from NRC inspectors in Component Design Basis Inspections, not related to the ODCM, resulted in minor violations due to lack of clearly documented figure or equations.

This change does not adversely impact setpoint calculations, as the new setpoints are more conservative.

Page 9-2 Section 3 -Page 8 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Revised RIA-45 and RIA-46 Alert setpoint methodology from: 3.0E-07 206 RJA-451111i1vent,alert

= --------------------X--

4.72E-04 x 6.5E+04 x l.672E...:.o6 x 7.09E-08 294 RJA-45unitvent,alert

= 5.8E+04cpm

+ bkg where: 3.0E-07 = 60% of Xe-133 EC value of 5.0E-07 µCi/ml. 4.72E-04 = Conversion factor, (1 min/60 sec)*(1 m3/35.314 ft3). 206 = Previous KXe-133, total body dose factor due to gamma emissions for Xe-133, in mrem/year per µCi/m3, using shielding factor of 0.7. All other factors were previously defined. to: 1 RJA-45rmitvent, alert = RJA-45unitvent,highX-3 RJA-45unitvent,alert

= 4.66E+04cpm

+ bkg RIA -46unil vent, alert = 1 RIA -46unit vent, high X -3 RIA -46unit vent. alert := 10 cpm + bkg 1/3 = divisor to account for each of 3 unit vent release points, dimensionless.

Previous methodology was confusing, requiring extensive explanation, and prone to error. New methodology provides clarity and still satisfies previous identified issue from PIP 0-05-965 where general observations from NRC inspectors in Component Design Basis Inspections, not related to the ODCM, resulted in minor violations due to lack of clearly documented figure or equations.

This change does not adversely impact setpoint calculations, as the new setpoints are more conservative.

Page 9-3 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Section 3 -Page 9 Revised 4RIA-45high setpoint units from "µCi/ml" to "µCi/cc".

Revised statement of 4RIA-45 units from: "4RIA-45 reads in units of concentration, µCi/ml." to: "4RIA-45 reads in units of concentration, µCi/cc." Revisions made to match units 4RIA-45 displays explicitly.

Revised 4RIA-45 Alert setpoint methodology from: 4RL4-45a!ert 5.0E-08 206 4RJA-45alert

4. 72E-04 x l.297E + 05 x 7.308E -06 294 =:: 7.7E-05 µCi/ml where: 5.0E-08 = 10% of Xe-133 EC value of 5.0E-07 All other factors were previously defined." to: 4 RL4 -45a!ert 1 = 4R/A-4511ighX-3 4RL4-45aiert

=:: 6.33E -05 µCi/cc+ bkg All factors were previously defined." DCi/ml. Previous methodology was confusing, requmng extensive explanation, and prone to error. New* methodology provides clarity and still satisfies previous identified issue from PIP 0-05-965 where general observations from NRC inspectors in Component Design Basis lnspeCtions, not related to the ODCM, resulted in minor violations due to lack of clearly documented figure or equations. This change does not adversely impact setpoint calculations, as the new setpoints are more conservative.

Page 9-4 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Section 3 -Page 10 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Revised RIA-53 Alert setpoint methodology from: 5.0E-08 206 RIA-53alert

= -------------------X--

4.72E-04 x 1.5E+04 x 7.308E-06 x 3.4E-08 294 RIA-53a!ert

= 2.0E+04cpm

+ bkg to: . 1 RIA -53alert = RIA -53high x -3 RIA -53a1er1 :::: 1.6E + 04 cpm + bkg Previous methodology was confusing, requmng extensive explanation, and prone to error. New methodology provides clarity and still satisfies previous identified issue from PIP 0-05-965 where general observations from NRC inspectors in Component Design Basis Inspections, not related to the ODCM, resulted in minor violations due to lack of clearly documented figure or equations.

This change does not adversely impact setpoint calculations, as the new setpoints are more conservative.

Section 6 -Page 3 Changed Table 6.0-2 Site# 024 Distance from "0.79 miles" to "0.81 miles". Change made to update distance based on new GPS data. Section 6 -Page 4 Changed title of Table 6.0-3 to: "Oconee 2015 Land Use Census Results." Land use census dates were changed to reflect 2015 census dates. The 2015 land use census was performed May 19-20, 2015, and the results were certified and made available for use 011 June 4, 2015. No changes were required from the 2015 land use census. Reformatted notes into table. Change made for clarity. Section 6 -Page 7 Changed title of Figure 6.0-3 to "ONS 2015 Land Use Census Map." Figure 6.0-3 was regenerated using ESRI ArcGIS Version 9.3.1 software by Orbis, Incorporated, Charlotte, NC. ' Page 9-5 __J Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radiological Effluent Controls (SLC 16.11) The Oconee Nuclear Station Radiological Effluent Controls are contained in SLC 16.11 as follows: Page 9-6 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 2-5 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 would exceed 0.18 mrem to the total body or 0.6 mrem to any organ. 16.11.1-1 03115111 I Page 9-7

• Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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. APPLICABILITY:

At all times ACTIONS CONDITION A. Concentration of A.1 radioactive material released in liquid effluents to Unrestricted Areas exceeds the limits specified in Commitment

a. REQUIRED ACTION Restore concentration to within the limit. 16.11.1-2 COMPLETION TIME Immediately 0311s111 I Page 9-8 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION B. Calculated dose from the release of radioactive materials in liquid effluents exceeds any of the limits in Commitment

b. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 REQUIRED ACTION B.1 -------------NOTE--------------

Not required during unusual operating conditions that result in activation of the Oconee Emergency Plan. Submit report to the regional NRG Office which includes the following:

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 40 CFR 141. 16.11.1-3 Radioactive Liquid Effluents 16.11.1 COMPLETION TIME 30 days from the end of the quarter during which the release occurred 0311 s111 I Page 9-9 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 REQUIRED ACTION Radioactive Liquid Effluents 16.11.1 COMPLETION TIME c. Radioactive liquid waste is discharged without treatment and in excess of the specified limit. C.1 Submit report to the 30 days SURVEILLANCE REQUIREMENTS regional NRC Office which includes the following:

a. Cause of equipment or subsystem inoperability.

b. Corrective action to restore equipment and prevent recurrence.

SURVEILLANCE SR 16.11.1.1 N/A 16.11.1-4 N/A FREQUENCY 0311 s111 I Page 9-10 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual BASES Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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) was 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 requirements contained in 10 CFR 50.36a 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 10 CFR 20.106 which references ApP.,endix 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 mrem/year 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 141and40 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 area_s 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, App-endix 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 03115111 I Page 9-11 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual

REFERENCES:

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015

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 Radioactive Liquid Effluents 16.11.1 03115111 I Page 9-12 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual *Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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

[Figure 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 mrem/yr 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 ::::;; 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

30 mrad for beta radiation ii. During any calendar year

:::;; 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 9-13 APPLICABILITY:

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 the projected gaseous 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. At all times 16.11.2-2 03/27/99 Page 9-14 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual ACTIONS CONDITION A. Dose rate exceeds the limits specified in Commitment

a. B. Calculated dose exceeds specified limits. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Gaseous Effluents 16.11.2 REQUIRED ACTION A.1 Restore release rate to within limits. B.1 Submit report to the regional NRC Office which includes the following:

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 COMPLETION TIME Immediately 30 days from the end of the quarter during which the release occurred 01131100 I Page 9-15 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION C. Radioactive gaseous Oconee Nuclear Station,Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 REQUIRED ACTION C.1 Submit a report to the Radioactive Gaseous Effluents 16.11.2 COMPLETION TIME 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 SR 16.11.2.1 N/A 16.11.2-4 N/A FREQUENCY 03/27/99 Page 9-16 BASES Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Gaseous Effluents 16.11.2 The basic requirements for Selected Licensee Commitments concerning effluent from nuclear power reactors are stated in IOCFR50.36.

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 IOCFR20.1302).

The _ requirements contained in IOCFR50.36a 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 IOCFR20.106

• 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 IOCFR50.36a 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 IOCFR50 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 mrem/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 mrem/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 low as 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 llD of Appendix I to 1 O CFR Part 50. 16.11.2-5 01131100 I Page 9-17 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual

REFERENCES:

1 10 CFR Part 20, Appendix 8. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015

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 Radioactive Gaseous Effluents 16.11.2 01131100 I Page 9-18 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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.

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N 0 TE------------------------------------------

Co rrectio n 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 A Alarm/trip setpoint less A.1 conservative than required for one or more effluent OR monitoring instrument channels.

A.2 REQUIRED ACTION Declare channel inoperable.

Suspend release of effluent monitored by the channel. 16.11.3-1 COMPLETION TIME Immediately Immediately 111201oa I Page 9-19 B. C. D. Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION One or more required liquid effluent monitoring instrument channels inoperable.

One or more required gaseous effluent monitoring instrument channels inoperable.

Required Action and associated Completion Time of Required Action B.2 or C.2 not met. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION B.1 Enter the Condition referenced in Table 16.11.3-1 for the function.

AND B.2 Restore the instrument(s) to OPERABLE status. C.1 Enter the Condition referenced in Table 16.11.3-2 for the function.

AND C.2 Restore the instrument(s) to OPERABLE status. D.1 Explain in next Annual Radiological Effluent Release Report why inoperability was not corrected in a timely manner. 16.11.3-2 COMPLETION TIME Immediately 30 days Immediately 30 days April 30 of following calendar year 111201oa I Page 9-20 E. F. Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION As required by Required Action 8.1 and referenced in Table 1 S.11.3-1. (RIA-33) As required by Required Action B.1 and referenced in Table 16.11.3-1. (RIA-54) Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION COMPLETION TIME E.1.1 Analyze two Prior to initiating independent samples subsequent release in accordance with 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.1 Suspend release of Immediately radioactive effluents by this pathway. OR 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 111201oa I Page 9-21 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION G. As required by Required Action 8.1 and referenced in Table 16.11.3-1. (Liquid Radwaste Effluent Line Flow Rate Monitor) Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION -----------------N 0 TE------------------

N ot required during short, controlled outages of liquid effluent monitoring 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. G.1 OR G.2 Suspend release of radioactive effluents by this pathway. Estimate flow rate during actual releases.

16.11.3-4 COMPLETION TIME Immediately Immediately Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter 111201os I Page 9-22 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION H. As required by Required Action B.1 and referenced in Table 16.11.3-1. (RIA-35, #3 Chemical Treatment Pond Composite Sampler and Sampler Flow Monitor (Turbine Building Sumps Effluent))

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION -----------------N 0 TE------------------

N ot required during short, controlled outages of liquid effluent monitoring 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. H.1 H.2 Suspend release of . radioactive effluents by this pathway. *Collect and analyze grab samples for gross radioactivity (beta and/or gamma) at a lower limit of detection of at least 10-7 µCi/ml. 16.11.3-5 COMPLETION TIME Immediately Immediately Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter 111201os I Page 9-23 I. Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION As required by Required Action C.1 and referenced in Table 16.11.3-2 for effluent releases from waste gas tanks (RIA-37, RIA-38) or containment purges (RIA-45).

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION ----------------NOTE------------------

N ot required during short, controlled outages of gaseous effluent monitoring 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. 1.1.1 1.1.2 1.1.3 OR 1.2 Analyze two independent samples. Conduct two independent data entry checks for release rate calculations Conduct two independent valve lineups of the effluent pathway. Suspend release of radioactive effluents by this pathway. 16.11.3-6 COMPLETION TIME Prior to initiating subsequent release Prior to initiating subsequent release Prior to initiating subsequent release Immediately 11120108 I Page 9-24 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION J. As required by Required Action C.1 and referenced in Table 16.11.3-2. (Effluent Flow Rate Monitor (Unit Vent, Containment Purge, Interim Radwaste Exhaust, Hot Machine Shop Exhaust, Radwaste Facility Exhaust, Waste Gas Discharge))

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12131/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION ---------------NOTE--------------------

N ot required during short, controlled outages of gaseous effluent monitoring 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. J.1 OR .J.2 Suspend release of radioactive effluents by this pathway. Estimate flow rate 16.11.3-7 COMPLETION TIME Immediately Immediately Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter 111201oa I Page 9-25 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION K. As required by Required Action C.1 and referenced in Table 16.11.3-2. (RIA-45, RIA-53, 4RIA-45) Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION -----------------NOTE------------------

N ot required during short, controlled outages of gaseous effluent monitoring 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 K.2.1 Suspend release of radioactive effluents by this pathway. Collect grab sample. K.2.2 Analyze grab samples for gross activity (beta and/or gamma). 16.11.3-8 COMPLETION TIME Immediately Immediately Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 24 hours from collection of sample 11120108 I Page 9-26 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION L. As required by Required Action C.1 and referenced in Table 16.11.3-2. (Unit Vent Monitoring Iodine Sampler, Unit Vent Monitoring Particulate Sampler, Interim Radwaste Building Ventilation Monitoring Iodine Sampler, Interim Radwaste Building Ventilation Monitoring Particulate Sampler, Hot Machine Shop Iodine Sampler, Hot Machine Shop Particulate Sampler, Radwaste Facility Iodine Sampler, Radwaste.

Facility Particulate Sampler) Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION -----------------NOTE------------------

N ot required during short, controlled outages of gaseous effluent monitoring 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. L.1 Suspend release of *radioactive effluents by this pathway. OR L.2.1 -----------NOTE-----------.

The collection time of each sample shall not exceed 7 days. -------------------------------

Collect samples continuously using auxiliary sampling equipment.

AND L.2.2 Analyze each sample. 16.11.3-9 COMPLETION TIME Immediately Immediately 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 11120108 I Page 9-27 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual *coNDITION M. As required by Required Action C.1 and referenced in Table 16.11.3-2 for effluent from ventilation system or condenser air ejectors: (RIA-40) Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION COMPLETION TIME -----------------N 0 TE------------------

N ot required during short, controlled outages of gaseous effluent monitoring 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. M.1 Continuously monitor Immediately release through the unit OR M.2 vent. Suspend release of radioactive effluents by this pathway. M.3.1 Collect grab sample. Immediately 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 111201os I Page 9-28 1-Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE REQUIREMENTS SR 16.11.3.1 SR 16.11.3.2 SR 16.11.3.3 SR 16.11.3.4 SR 16.11.3.5 SURVEILLANCE

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NOTE----------------------------

The Channel Response check shall consist of verifying indications during periods of r_elease.

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. ------------------------N 0 TE----------------------------

T he 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 relea$es are made. Perform Channel Response Check. Perform Source Check. Perform Source Check. Perform Source Check. 16.11.3-11 FREQUENCY During each release via this pathway 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours 31 days 92 days 111201os I Page 9-29 SR 16.11.3.6 SR 16.11.3.7 SR 16.11.3.8 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE

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N 0 TE----------------------------

Th e 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. ------------------------N 0 TE----------------------------

T he 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). Perform CHANNEL FUNCTIONAL TEST. Perform CHANNEL FUNCTIONAL TEST. 16.11.3-12 FREQUENCY 92 days 92 days 92 days 11120108 I Page 9-30 SR 16.11.3.9 SR 16.11.3.10 SR 16.11.3.11 SR 16.11.3.12 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE

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N 0 TE---------------------------

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 su.bstitute previously established calibration procedures for these requirements.)

Perform CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

Perform leak test. Perform Source Check. 16.11.3-13 FREQUENCY 12 months 12 months When cylinder gates or wicket gates are reworked 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 111201oa I Page 9-31

1. 2. 3. Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS INSTRUMENT Monitors Providing Automatic Termination of Release a. Liquid Radwaste Effluent Line Monitor, RIA-33 b. Turbine Building Sump, RIA-54 Monitors not Providing Automatic Termination of Release Low Pressure Service Water RIA-35 Flow Rate Measuring Devices a. Liquid Radwaste Effluent Line Flow Rate Monitor (OLW CR0725 cir OLW SS0920) b. Liquid Radwaste Effluent Line Minimum Flow Device c. Turbine Building Sump Minimum Flow Device d. Low Pressure Service Water Minimum Flow Device MINIMUM OPERABLE CHANNELS NA NA NA APPLICABILITY At all times At all times At all times At all times NA NA NA 16.11.3-14 SURVEILLANCE REQUIREMENTS SR 16.11.3.1 SR 16.11.3.3 SR 16.11.3.6 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 SR 16.11.3.1 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.10 CONDITION REFERENCED FROM REQUIRED ACTION B.1 E F H G NA NA NA 111201oa I Page 9-32 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS INSTRUMENT

e. Keowee Hydroelectric Tailrace Discharge<*>

4. Continuous Composite Sampler #3 Chemical Treatment Pond Composite Sampler and Sampler Flow Monitor (Turbine Building Sumps Effluent)

MINIMUM OPERABLE CHANNELS NA APPLICABILITY NA At all times SURVEILLANCE REQUIREMENTS SR 16.11.3.11 SR 16.11.3.2 SR 16.11.3.10 CONDITION REFERENCED FROM REQUIRED ACTION B.1 NA H (a) Flow is determined from the number of hydro units operating.

If no hydro units are operating, leakage flow will be assumed to be 38 cfs based on historical data. 16.11.3-15 111201oa I Page 9-33 _J

1. 2. Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM OPERABLE CHANNELS (PER RELEASE SURVEILLANCE INSTRUMENT PATH) APPLICABILITY REQUIREMENTS Unit Vent Monitoring System a. Noble Gas Activity At All Times SR 16.11.3.2 Monitor Providing Alarm SR 16.11.3.4 and Automatic SR 16.11.3.7 Termination of SR 16.11.3.9 Containment Purge Release (RIA-45 -Purge Isolation Function)

b. Noble Gas Activity At all times SR 16.11.3.2 Monitor Providing Alarm. SR 16.11.3.4 (RIA-45 -Vent Stack SR 16.11.3.7 Monitor Function)

SR 16.11.3.9

c. Iodine Sampler At All Times SR 16.11.3.2

d. Particulate Sampler At All Times SR 16.11.3.2

e. Effluent Flow Rate At All Times SR 16.11.3.2 Monitor (Unit Vert Flow) SR 16.11.3.10 (MSC CR0001) f. Sampler Flow Rate At All Times SR 16.11.3.2 Monitor <*l (Annunciator)

SR 16.11.3.10

g. Effluent Flow Rate During Containment SR 16.11.3.2 . Monitor (Containment Purge Operation SR 16.11.3.10 Purge)(MSC CR0001) h. CSAE Off Gas Monitor During Operation SR 16.11.3.2 (RIA-40) ofCSAE SR 16.11.3.5 SR 16.11.3.8 SR 16.11.3.9 Interim Radwaste Building Ventilation Monitoring System a. Noble Gas Activity At All Times SR 16.11.3.2 Monitor (RIA -53) SR 16.11.3.4 SR 16.11.3. 7 SR 16.11.3.9

b. Iodine Sampler At All Times SR 16.11.3.2

c. Particulate Sampler At All Times SR 16.11.3.2

d. Effluent Flow Rate At All Times SR 16.11.3.2 Monitor (Interim SR 16.11.3.10 Radwaste Exhaust) (GWD FT0082) e. Sampler Flow Rate At All Times SR 16.11.3.2 Monitor<*l (Annunciator)

SR 16.11.3.10 16.11.3-16 CONDITION REFERENCED FROM REQUIRED ACTION C.1 K L L J NA J M K L L J NA 111201os I Page 9-34 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED FROM MINIMUM OPERABLE CHANNELS (PER RELEASE PATH) SURVEILLANCE REQUIRED INSTRUMENT APPLICABILITY REQUIREMENTS ACTION C.1 3. Hot Machine Shop Ventilation Sampling System a. Iodine Sampler b. Particulate Sampler c. Effluent Flow Rate Monitor (Hot Machine Shop Exhaust) (Totalizer)

d. Sampler Flow Rate Monitor <*l (Annunciator)

4. Radwaste Facility Ventilation Monitoring System *5. a. Noble Gas Activity Monitor (4-RIA-45)

b. Iodine Sampler c. Particulate Sampler d. Effluent Flow Rate Monitor (Radwaste Facility Exhaust) (OVS CR2060) e. Sampler Flow Rate Monitor <*l (Annunciator)

Waste Gas Holdup Tanks a. Noble Gas Activity Monitor -Providing Alarm and Automatic Termination of Release (RIA-37 ,-38)b b. Effluent Flow Rate Monitor (Waste Gas Discharge Flow) (MSC CR0001) At All Times At All Times At All Times At All Times At All Times At All Times At All Times At All Times At All Times During Waste Gas Holdup Tank Releases SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.6 SR 16.11.3.9 SR 16.11.3.12 During Waste Gas SR 16.11.3.1 Holdup Tank Releases SR 16.11.3.10 (a)Alarms indicating low flow 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 L L J NA K L L J NA J 111201os I Page 9-35

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*--Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual BASES Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 with the requirements of General Design Criteria 60, 63, and 64.of Appendix A to 10 CFR Part 50. The ra<;fioactive 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 with 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 between 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 deenied 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 9-36 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11 .4 Operational Safety Review Operational Safety Review 16.11.4 COMMITMENT Required sampling should be performed as detailed in Table 16.11.4-1.

APPLICABILITY:

At all times ACTIONS CONDITION A. NA REQUIRED ACTION A.1 NA SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 16.11.4.1 N/A 16.11.4-1 COMPLETION TIME NA FREQUENCY N/A 06130114 I Page 9-37 Item 1. Decant Monitor Tank, Turbine Building Sump Monitor Tanks, Waste and Recycle Monitor Tanks 2. Unit Vent Sampling (Includes Waste Gas Decay Tanks, Reactor Building Purges, Auxiliary Building Ventilation, Spent Fuel Pool Ventilation, Air Ejectors)

3. Waste Gas Decay Tank 4. Reactor Building Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Table 16.11.4-1 Operational Safety Review 16.11.4 Minimum Sampling Frequency and Analysis Program Check Frequency Lower Limit of Detection(b) of Lab Analysis for Waste a. Principal Gamma Emitters<<>

including Dissolved Noble Gases b. Radiochemical Analysis Sr-89 and Sr-90 c. Tritium d. Gross Alpha Activity a. Iodine Spectrum(*>

b. Particulates(*)

i. Ce-144 & Mo-99 ii. Other Principle Gamma Emitters (d) iii. Gross Alpha Activity iv. Radiochemical Analysis Sr-89, Sr-90 c. Gases by Principle Gamma Emitters<dl

d. Tritium a. Principle Gamma Emitters(dl

b. Tritium a. Principle Gamma Emitters(d)

b. Tritium Composite Grab Sample prior to release of each batch(hl Quarterly from all composited batches(Q Monthly Composite Monthly Composite Continuous monitor, weekly sample<*>

Weekly Composite(*)

Weekly Composite(e>

Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample Grab Sample prior to release of each batch Grab Sample prior to release of each batch Grab sample each purge Grab sample each purge 16.11.4-2

<5E-06 µCi/ml (Ce-144) <5E-07 µCi/ml (Other Gamma Nuclides)

<1 E-05 µCi/ml (Dissolved Gases) <1E-06 µCi/ml (1-131) <5E-08 µCi/ml <1 E-05 µCi/ml <1 E-07 µCi/ml <1E-10 µCi/cc (l-133)ID

<1E-12 µCi/cc (l-131)(1)

<5E-1 O µCi/ccO>O<> < 1 E-11 µCi/ccOl <1 E-11 µCi/cc <1 E-11 µCi/cc <1 E-04 µCi/cc <1E-06 µCi/cc <1E-04 µCi/cc (gases) <1E-10 µCi/cc (particulates and iodines) <5E-09 µCi/cc (Ce-144 and Mo-99) <1 E-06 µCi/cc . <1 E-04 µCi/cc (gases) <1E-10 µCi/cc (particulates and iodines) <5E-09 µCi/cc (Ce-144 and Mo-99) <1 E-06 µCi/cc 06/30/14 Page 9-38 Item 5. Not Used 6. #3 Chemical Treatment Pond EffiuentCQ Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Table 16.11.4-1 Operational Safety Review 16.11.4 Minimum Sampling Frequency and Analysis Program Check a. Principle Gamma Emitters Cc> b. 1-131 c. Tritium d. Gross Alpha Activity e. Sr-89 & Sr-go f. Dissolved and Entrained gases (Gamma Emitters)

Frequency Lower Limit of Detection(bJ of Lab Analysis for Waste Weekly Continuous Composite(gl

<5E-07 µCi/ml Weekly Continuous Composite(gJ

<1E-06 µCi/ml Monthly Continuous

<1 E-05 µCi/ml Composite<gJ Monthly Continuous Composite(gJ

<1E-07 µCi/ml Quarterly Continuous Composite<gJ

• <5E-08 µCi/ml Monthly Grab <1E-05 µCi/ml 7. Radwaste Facility a. Iodine Spectrum(*)

Continuous monitor, weekly sample<*>

(1-133) < 1 E-og µCi/cc (1-131) <1E-11 µCi/cc Ventilation

b. Particulate<*>

i. ii. iii. iv. c. d. Ce-144 and gg Other Principle Gamma Emitters<d>

Gross Alpha Activity Radiochemical Analysis Sr-89, Sr-go Gases by Principle Gamma<dJ Emitters Tritium Weekly Composite<*>

Weekly Composite<*>

Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample 16.11.4-3

<5E-10 µCi/cc© <1 E-11 µCi/ccm <1 E-11 µCi/cc <1 E-11 µCi/cc <1E-04 µCi/cc <1E-06 µCi/cc 06/30/14 Page 9-3g Item 8. Hot Machine Shop Ventilation

9. Interim Radwaste Building Ventilation Check Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Table 16.11.4-1 Operational Safety Review 16.11.4 Minimum Sampling Frequency and Analysis Program Frequency Lower Limit of DetectionCb>

of Lab Analysis for Waste a. Iodine Spectrum Weekly SampleCe>

(1-133) <1 E-10 µCi/ccOl (l-131) <1E-12 µCi/ccOl b. Particulate

i. ii. iii. iv. c. d. a. b. i. ii. iii. iv. c. d. Ce-144 and Mo-99 Other Principle Gamma Emitters (d) Gross Alpha Activity Radiochemical Analysis Sr-89, Sr-90 Gases by Principle Gamma Emitters Tritium Iodine Spectrum Particulate Ce-144 and Mo-99 Other Principle Gamma Emitters Cd> Gross Alpha *Activity Radiochemical Analysis Sr-89, Sr-90 Gases by Principle Gamma Cd) Emitters Tritium Weekly Composite<*>

Weekly Composite<*>

Monthly, using composite samples of one week Quarterly Composite NA NA Weekly sample<*>

Weekly Composite<*>

Weekly Composite<*>

Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample 16.11.4-4

<SE-10 µCi/ccOlCkl < 1 E-11 µCi/ccOl <1 E-11 µCi/cc <1E-11 µCi/cc NA NA (l-133) <1E-10 µCi/ccOl (l-131) <1E-12 µCi/ccm <SE-10 µCi/cc 01 <1 E-11 µCi/cc 01 <1 E-11 µCi/cc <1 E-11 µCi/cc <1E-04 µCi/cc <1 E-06 µCi/cc 06/30/14 Page 9-40 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Operational Safety Review 16.11.4 (a) Samples shall be changed at least once per 7 days 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 /> after changing, or after 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 RA TED 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 concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation)

LLD= (2.71 I Tl + 4.65 Sb Where: E x V x 2.22E06 x Y x exp (-Mt) LLD is the "a priori" lower limit of detection as defined above (as micro Curies per unit mass or volume), sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22E06 is the number of disintegrations per minute per micro Curie, Y is the fractional radiochemical yield (when applicable), A. is the radioactive decay constant for the particular nuclide !it 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 time 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 time in minutes Typical values of E, V, Y and !it should be used in the calculation.

It 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 fact) limit for a particular measurement. (c) The principal gamma emitters for which the LLD control applies include the following 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 of 5E-06 µCi/ml. This list does not mean that only these nuclides are to 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 to 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 the sample flow rate to the sampled stream flow 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. (f) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

16.11.4-5 06/30/14 Page 9-41 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 to sampling for analysis, each batch shall be isolated, and then thoroughly mixed, to assure representative sampling. (i) A continuous release is the discharge of liquid 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 /> after changing (on or after removal from sampler).

U) 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. 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). (k) Ce-144 and Mo-99 LLD as approved by NRG SER dated January 16, .1984 (Reference 1). 16.11.4-6 06/30/14 Page 9-42 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Operational Safety Review 16.11.4 BASES N/A

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 9-43 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 accordance 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 wet solid wastes and must adequately verify that the final product of solidification or dewatering meets all applicable Federal, State and disposal site requirements.

APPLICABILITY:

At all times 16.11.5-1 10130102 I Page 9-44 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual ACTIONS CONDITION A Applicable regulatory requirements for solidified or dewatered wastes are not satisfied.

B. A solidification test as described in the PCP fails to verify Solidification.

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 REQUIRED ACTION A.1 Suspend shipments of defectively packaged solid radioactive wastes from the site. AND A.2 Initiate action to correct PCP, procedures, or solid waste equipment as necessary to prevent recurrence.

B.1 Suspend solidification of the batch under test and follow PCP guidance for test failures until solidification of the batch is verified by subsequent tests. AND B.2 The PCP shall be modified as required to assure Solidification of subsequent batches of waste. 16.11.5-2 Solid Radioactive Waste 16.11.5 COMPLETION TIME Immediately Prior to next shipment for disposal of solidified or dewatered wastes Immediately Prior to next solidification for shipment of waste for disposal at a 1 O CFR 61 disposal site 10130102 I Page 9-45 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION C. With solidification or dewatering for disposal not performed in accordance with the PCP. D. With the solid waste equipment incapable of meeting commitment or not in service. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 REQUIRED ACTION C.1 Reprocess or repackage the waste in accordance with PCP requirements.

OR 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.1 Restore the equipment to OPERABLE status or provide for alternative capability to process wastes as necessary to satisfy all applicable disposal requirements.

SURVEILLANCE REQUIREMENTS SR 16.11.5.1 SURVEILLANCE The Process Control Program shall be used to verify the solidification of at least one representative test specimen from at least 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 Solid Radioactive Waste 16.11.5 COMPLETION TIME Prior to shipment for disposal of the inadequately processed waste that requires solidification or dewatering In a time frame that supports the commitment FREQUENCY Every tenth batch of each type of radioactive waste to be solidified.

10130102 I Page 9-46 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Solid Radioactive Waste 16.11.5 BASES 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 1 OCFR61 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 Requirements 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 9-47 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radiological Environmental Monitoring 16.11.6 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.6 Radiological Environmental Monitoring COMMITMENT APPLICABILITY:

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 D/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---------------------------------------------

lf 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 were obtained and added to the environmental monitoring program, if available.

These new locations will be identified in the Annual Radioactive Effluent Release Report. At all times 16.11.6-1 111a113 I Page 9-48 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual ACTIONS CONDITION A. Radiological environmental monitoring program is not conducted as required.

8. Land use census identifies a Location which yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than a location from which samples are currently being obtained.

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radiological Environmental Monitoring 16.11.6 REQUIRED ACTION COMPLETION TIME A.1 Submit a description of May 15 of following the reason for not calendar year conducting the program as required and plans to prevent a recurrence shall be included in the Annual Radiological Environmental Operating Report. 8.1 -----------N 0 TE-----------

The sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

---

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 111a113 I Page 9-49 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radiological Environmental Monitoring 16.11.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME c. I nterlaboratory 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 16.11.1or16.11.2.

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 111a113 I Page 9-50 Exposure Pathway and/or Sample 1. AIRBORNE Radioiodine and Particulates

2. DIRECT RADIATION

3. WATERBORNE

a. Surface b. Drinking c. Sediment from Shoreline Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Table 16.11.6-1 Radiological Environmental Monitoring 16.11.6 Radiological Environmental Monitoring Program Number of Sample Locations (b) 5 40 2 3 2 Sampling and Collection Frequency (d) Continuous sampler operation with sample collection weekly, or more frequently if required by dust loading. Quarterly.

Composite (a) sample over a 1-month period. Composite (a) sample over a 1-month period. Semiannually.

16.11.6-4 Time and Frequency of Analysis Radioiodine canister:

1-131 analysis weekly. Particulate sampler: Gross beta radioactivity analysis following filter change; and gamma isotopic analysis of composite (by location) quarterly. (c) Gamma dose quarterly.

Gamma isotopic analysis monthly. Composite for tritium analysis quarterly.

Composite for gross beta and gamma isotopic analyses monthly. Composite for tritium analysis quarterly.

Gamma isotopic analysis semiannually.

111a113 I Page 9-51 Exposure Pathway and/or Sample 4. INGESTION

a. Milk b. Fish c. Broad-leaf Vegetation Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Table 16.11.6-1 Radiological Environmental Monitoring 16.11.6 Radiological Environmental Monitoring Program Number of Sample Locations (b) 4(e) 2 2 Sampling and Collection Frequency (d) Semimonthly when animals are on pasture; monthly at other times. Semiannually.

One sample each commercially and recreationally important species. Monthly. Time and Frequency of Analysis Gamma isotopic and 1-131 analysis semimonthly when animals are on pasture; monthly at other times. Gamma isotopic analysis semiannually on edible portion. Gamma isotopic analysis monthly. (a) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 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 complete 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 111a113 I Page 9-52 Analysis Gross Beta H3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Table 16.11.6-2 Radiological Environmental Monitoring 16.11.6 Maximum Values for the Lower Limits of Detection (LLD) (a) (c) Water (pCi/I) 4 2,000 15 30 15 15 30 15 15 15(b) 15 18 15 15 Airborne Particulate or Gases Ci/m 3 1E-02 7E-02 5E-02 6E-02 Fish (pCi/kg, wet) 130 260 130 130 260 130 150 Milk (pCi/I) 15 18 60 15 Broad-leaf Vegetation (pCi/kg, wet) 60 60 80 Sediment (pCi/kg, dry) 150 180 (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 with 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation):

LLD= (2.71 I Tl + 4.65 Sb E xVx 2.22 xY x exp (-Mt) Where: LLD is the lower 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 111a113 I Page 9-53 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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)

/.. is the radioactive decay constant for the particular radionuclide

!>.. t is the elapsed time between sample collection (or end of the sample collection period) and time of counting Tis the sample counting time 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 perfonmed 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 Radiological 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 pCifliter of 1-131 in drinking water. For low level analyses of 1-131 an LLD of 1 pCifliter will be achieved. (c) other peaks which are measurable and identifiable, together with the radionuclides in Table 16.11.6-2, shall be identified and reported.

16.11.6-7 111a113 I Page 9-54 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Table 16.11.6-3 Radiological Environmental Monitoring 16.11.6 Reporting Levels for Radioactivity Concentrations in Environmental Samples (c) (d) Airborne Broad-leaf Water Particulate or Fish Milk Analysis Gases Vegetation (pCi/I) (pCi/kg, wet) (pCi/I) (pCi/kg, wet) Ci/m 3 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 1 E02 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 equal to or greater than the calendar year limits of SLC 16.11.1 or 16.11.2. 16.11.6-8 1118113 I Page 9-55 BASES Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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.

Following 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 lower limits of detection correspond to less than 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 requirementsfor 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 111a113 I Page 9-56 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 required 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 111a113 I Page 9-57 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11. 7 Dose Calculations Dose Calculations 16.11.7 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 A Calculated doses from A.1 the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of SLC 16.11.1.b, SLC 16.11.2.b.1, or SLC 16.11.2.b.2 REQUIRED ACTION Determine by calculation, including direct radiation contributions from the reactor units and from outside storage tanks, whether the limits of Commitment 16.11.7 have been exceeded.

16.11.7-1 COMPLETION TIME None 01131100 I Page 9-58 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION B. Calculated dose exceeds limits of Commitment 16.11.7. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 REQUIRED ACTION -------------------NOTE----------------

Th is Special Report, as defined 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 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 Dose Calculations 16.11.7 COMPLETION TIME 30 days 01131100 I Page 9-59 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Dose Calculations 16.11.7 CONDITION REQUIRED ACTION COMPLETION TIME C. Calculated dose C.1 -----------NOTE-----------

exceeds limit of Submittal of the report Commitment 16.11. 7. is considered a timely request, and a variance AND is granted until staff action on the request is Release condition complete.

resulting in violation of -------------------------------

40 CFR 190 not corrected at time of Include a request for a 30 days from exceeding report submittal.

variance in accordance the limit with the provisions of 40 CFR Part 190. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.7.1 SR 16.11.7.2 BASES Determine cumulative dose contributions from 31 days liquid effluents in accordance with Offsite Dose Calculation Manual. 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 9-60 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual

REFERENCES:

1. 10 CFR Part 20. 2. 40 CFR Part 190. Oconee Nuclear Station Units 1, 2, & 3 Period 111/2015-12/31/2015

3. Offsite Dose Calculation Manual. 4. 10 CFR Part 50, Appendix I. 16.11.7-4 Dose Calculations 16.11.7 01131100 I Page 9-61 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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:

At all times. ACTIONS CONDITION A. Individual milk samples A.1 show 1-131 concentrations of 1 0 picocuries per liter or greater. REQUIRED ACTION Submit plan advising the NRC of the proposed action to ensure the plant related annual doses will be within the design objective of 45 mrem/yr to the thyroid of any individual.

16.11.8-1 COMPLETION TIME 7 days 12121109 I Page 9-62 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 REQUIRED ACTION Reports 16.11.8 COMPLETION TIME B. Milk samples collected 8.1 Submit a plan advising 30 days over a calendar quarter show 1-131 average concentrations of 4.8 picoCuries per liter or greater SURVEILLANCE REQUIREMENTS the NRG of the proposed action to ensure the plant related annual doses will be within the design objective of 45 mrem/yr to the thyroid of any

• individual.

SURVEILLANCE SR 16.11.8.1 NA BASES Reference applicable commitments.

REFERENCES:

1. 10 CFR Part 20. 2. 40 CFR Part 190. 3. Offsite Dose Calculation Manual. 16.11.8-2 FREQUENCY NA 12121109 I Page 9-63 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 waste 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 9-64 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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:

At all times. 16.11.9-2 03122110 I Page 9-65 ACTIONS CONDITION A. N/A Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Release Report 16.11.9 REQUIRED ACTION COMPLETION TIME A.1 N/A N/A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.9.1 N/A N/A BASES N/A

REFERENCES:

1. Oconee ITS. 2. Offsite Dose Calculation Manual. 16.11.9-3 03122110 I Page 9-66 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 shall 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 obta_ined as part of the required lnterlaboratory Comparison Program. The lnterlaboratory Comparison 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 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 9-67 ACTIONS CONDITION A. NA Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radiological Environmental Operating Report 16.11.10 REQUIRED ACTION COMPLETION TIME A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.10.1 NA NA BASES NA

REFERENCES:

1. Oconee ITS 2. Offsite Dose Calculation Manual 16.11.10-2 os114114 I Page 9-68 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1 /1/2015 -12/3112015 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.11 Iodine Radiation Monitoring Filters Iodine Radiation Monitoring filters 16.11.11 COMMITMENT Assure that the iodine radiation monitoring filters perform their intended function.

APPLICABILITY:

At all times. ACTIONS CONDITION REQUIRED ACTION A NA A.1 NA SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 16.11.11.1 Remove and replace iodine radiation monitoring filters in RIA-44. SR 16.11.11.2 Discard spare iodine radiation monitoring filters. BASES COMPLETION TIME NA FREQUENCY 30 days of operation After 24 months of shelf life. The purpose of this commitment is to assure the reliability of the iodine radiation monitoring charcoal filters.

REFERENCES:

1. Oconee CTS Amendment No. 3/3 SER date July, 1974. 16.11.11-1 03/27/99 Page 9-69

---

*----* -Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 A. The quantity of A.1 Suspend addition of radioactive material to tank. radioactive material in outside temporary storage tank not within *limit. SURVEILLANCE REQUIREMENTS SR 16.11.12.1 SURVEILLANCE Verify the quantity of radioactive material contained in each of the outside temporary tanks is within the limit by analyzing a representative sample of the tanks' contents.

Verify the quantity of radioactive material in each of the outside temporary tanks does not result in exceeding the limit by analyzing a representative sample of radioactive material to be added. 16.11.12-1 COMPLETION TIME Immediately FREQUENCY Within 7 days after addition of radioactive materials to an outside temporary tank Prior to addition of radioactive materials to an outside temporary tank. 04110103 I Page 9-70 BASES *Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 would be less than the limits of 1 OCFR 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 9-71 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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:

At all times. ACTIONS ---------------------------------------------------------NOTE------------------------------------------------------------

Separate Condition Entry is allowed for each tank. CONDITION REQUIRED ACTION A The quantity of A.1 Suspend addition of radioactive material in radioactive material to the Waste Gas Holdup tank. tank not within fimit. AND A.2 Reduce tank contents to within limit. SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 16.11.13.1 BASES Verify quantity of radioactive materials in each tank is within limit. COMPLETION TIME Immediately 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> FREQUENCY 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when tank is 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 9-72 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 UFSAR, Section 15.10 16.11.13-2 03/27/99 Page 9-73 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.14 Explosive Gas Mixture Explosive Gas Mixture 16.11.14 COMMITMENT The concentration of Hydrogen in the Waste Gas Holdup Tanks shall be 3% by volume. APPLICABILITY:

At all times. ACTIONS -------------------------------------------------------------NOTE--------------------------------------------------------

Separate Condition Entry is allowed for each tank. CONDITION REQUIRED ACTION A. Concentration of A.1 Reduce Concentration Hydrogen in Waste of Hydrogen to within Gas Holdup tank is> limit. 3% and by volume. B. Concentration of B.1 Suspend addition of Hydrogen in Waste waste gases to tank. Gas Holdup tank is > 4% by volume. AND B.2 Reduce Concentration of Hydrogen to within limit. 16.11.14-1 COMPLETION TIME 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Immediately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 03/27/99 Page 9-74 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 SURVEILLANCE REQUIREMENTS SR 16.11.14.1 BASES SURVEILLANCE Verify Hydrogen concentration in Waste Gas Holdup Tank is 3% by volume. Explosive Gas Mixture 16.11.14 FREQUENCY 5 times/week on each 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 9-75 Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 10 Summary of Changes to the Process Control Program This attachment includes a summary of changes to the PCP. l Page 10-1 Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 The Oconee Nuclear Station PCP was not revised in 2015. The most recent revision was provided with the Oconee Nuclear Station 2014 ARERR. Page 10-2 Attachment 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 1/1/2015-12/31/2015 No major modifications to Oconee Nuclear Station liquid, gaseous, solid, or mobile radioactive waste treatment systems occurred in 2015. Page 11-2 Attachment 12 Errata to a Previous Year's ARERR Example Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 Example Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 There are no changes to a previous year's ARERR. Page 12-2

'Y ENERGY Scott L Batson Vice President Oconee Nuclear Station Duke Energy ON01 VP I 7800 Rochester Hwy Seneca, SC 29672 ONS-2016-039 o: 864.873.3274

f. 864.873. 4208 Scott.Batson@duke-energy.com May 2, 2016 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station, Docket Nos. 50-269, 50-270 and 50-287 2015 Annual Radioactive Effluent Release Report (ARERR) 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, 2015 through December 31, 2015. In accordance with TS 5.5.1, the Offsite Dose Calculation Manual (ODCM) is included in this submittal.

Attachment 1 Attachment 2 Attachment 3 Attachment 4 Attachment 5 Attachment 6 Attachment 7 Attachment 8 Attachment 9 Attachment 10 Attachment 11 Attachment 12 Summary of Gaseous and Liquid Effluents Supplemental Information Solid Radioactive Waste Disposal Meteorological Data Unplanned Offsite Releases Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Information to Support the NEI Ground Water Protection Initiative Inoperable Equipment Summary of Changes to the Offsite Dose Calculation Manual Summary of Changes to the Process Control Program Summary of Major Modifications to the Radioactive Waste Treatment Systems Errata to a Previous Year's ARERR Example www.duke-energy.com U.S. Nuclear Regulatory Commission 2015 Annual Radioactive Effluent Release Report May 2, 2016 Page2 Enclosure 2015 Offsite Dose Calculation Manual (Compact Disc) Any questions concerning this report should be directed to Pam Metler at 864-873-3856.

Sincerely, -5J/fl!/:1M-Scott Batson Site Vice President . Oconee Nuclear Station Attachments (12) Enclosure ( 1)

U.S. Nuclear Regulatory Commission 2015 Annual Radioactive Effluent Release Report May 2, 2016 Page3 xc (with attachments and enclosure):

Ms, Catherine Haney Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station xc (with attachments only): Mr. James R. Hall, Project Manager (by electronic mail only) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Mr. Jeffrey A. Whited, Project Manager (by electronic mail only) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Ms. Susan E. Jenkins, Manager Radioactive

& Infectious Waste Management SC Dept. of Health and Env. Control 2600 Bull St. Columbia, SC 29201 Mr. James Twiggs INPO 700 Galleria Place, Suite 100 Atlanta, GA 30339-5943 Mr. Gary Stewart, State Voluntary Cleanup Section S.C. Dept. of Health & Environmental Control 2600 Bull Street Columbia, SC 29201-1708 Ms. Sandra Threatt, Nuclear Response and Emergency Environmental Surveillance S.C. Dept. of Health & Environmental Control 2600 Bull Street Columbia, SC 29201-1708

ENERGY Oconee Nuclear Station Units 1, 2, and 3 Annual Radioactive Effluent Release Report January 1, 2015 through December 31, 2015 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 1/1/2015-12/31/2015 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

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Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Gaseous Effluents

-Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases 1. Total Release Ci 3.00E+OO 1.57E+OO 1.36E+OO 7.02E-01 6.63E+OO 2. Avg. Release Rate µCi/sec 3.85E-01 2.00E-01 1.71E-01 8.83E-02 2.10E-01 B. lodine-131

1. Total Release Ci 7.68E-10 O.OOE+OO O.OOE+OO 3.72E-10 1.14E-09 2. Avg. Release Rate µCi/sec 9.88E-11 O.OOE+OO O.OOE+OO 4.67E-11 3.61 E-11 C. Particulates Half-Life

8 days 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium 1. Total Release Ci 3.60E+01 2.31E+01 8.76E+01 3.34E+01 1.80E+02 2. Avg. Release Rate µCi/sec 4.63E+OO 2.93E+OO 1.10E+01 4.20E+OO 5.71 E+OO E. Carbon-14

1. Total Release Ci 5.98E+OO 6.10E+OO 5.97E+OO 5.51E+OO 2.36E+01 2. Avg. Release Rate µCi/sec 7.68E-01 7.76E-01 7.51 E-01 6.93E-01 7.47E-01 F. Gross Alpha 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+QO O.OOE+OO Page 1-2 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Gaseous Effluents

-Elevated Releases -Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases AR-41 Ci 3.39E-01 2.70E-01 5.19E-01 O.OOE+OO 1.13E+OO KR-85M Ci 1.11 E-03 2.44E-03 O.OOE+OO O.OOE+OO 3.55E-03 KR-87 Ci O.OOE+OO 2.61E-03 O.OOE+OO O.OOE+OO 2.61E-03 KR-88 Ci O.OOE+OO 4.62E-03 O.OOE+OO O.OOE+OO 4.62E-03 XE-133 Ci 1.90E+OO 1.17E+OO 7.81 E-01 6.65E-01 4.51E+OO XE-135 Ci 1.28E-02 3.51E-02 3.01E-02 O.OOE+OO 7.80E-02 XE-135M Ci 2.61E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.61E-03 Total for Period Ci 2.26E+OO 1.48E+OO 1.33E+OO 6.65E-01 5.73E+OO B. Iodines None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates 8 days None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO.

O.OOE+OO D. Tritium H-3 Ci 3.38E+01 2.04E+01 8.22E+01 2.64E+01 1.63E+02 E. Carbon-14 C-14 Ci 1.79E+OO 1.83E+OO 1.79E+OO 1.65E+OO 7.05E+OO F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO *0.00E+OO G. Others C-11 Ci O.OOE+OO 4.29E-03 O.OOE+OO O.OOE+OO 4.29E-03 Total for Period Ci O.OOE+OO 4.29E-03

• O.OOE+OO O.OOE+OO 4.29E-03 Page 1-3 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Gaseous Effluents

-Elevated Releases -Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases AR-41 Ci O.OOE+OO 4.93E-02 1.90E-02 4.21 E-05 6.84E-02 KR-85 Ci 4.14E-03 O.OOE+OO O.OOE+OO O.OOE+OO 4.14E-03 KR-85M Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.88E-06 4.88E-06 XE-131M Ci O.OOE+OO 3.27E-04 8.28E-05 O.OOE+OO 4.10E-04 XE-133 Ci 7.36E-01 4.05E-02 1.28E-02 3.67E-02 8.26E-01 XE-133M Ci O.OOE+OO 3.99E-04 1.88E-04 O.OOE+OO.

5.86E-04 XE-135 Ci O.OOE+OO 2.64E-04 1.23E-05 1.84E-04 4.60E-04 Total for Period *Ci 7.40E-01 9.09E-02 3.22E-02 3.69E-02 9.00E-01 B. Iodines 1-131 Ci 7.68E-10 O.OOE+OO O.OOE+OO 3.72E-10 1.14E-09 Total for Period Ci 7.68E-10 O.OOE+OO O.OOE+OO 3.72E-10 1.14E-09 C. Particulates Half-Life;;:

8 days None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium H-3 Ci 3.93E-05 6.08E-02 4.22E-02 4.91E-02 1.52E-01 E. Carbon-14 C-14 Ci 4.19E+OO 4.27E+OO 4.18E+OO 3.86E+OO 1.65E+01 F. Gross Alpha Total for Period Ci O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-4 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Gaseous Effluents

-Ground Releases -Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO B. Iodines None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates Half-Life<'=

8 days None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium H-3 Ci 2.13E+OO 2.62E+OO 5.35E+OO 6.93E+OO 1.70E+01 E. Carbon-14 C-14 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-5 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Gaseous Effluents

-Ground Releases -Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO B. Iodines None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates Half-Life;:::

8 days None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium H-3 Ci 6.03E-02 1.34E-02 1.77E-02 4.43E-02 1.36E-01 E. Carbon-14 C-14 Ci O.OOE+OO O.OOE+OO O.OOE+OO

• O.OOE+OO O.OOE+OO F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-6

• Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Liquid Effluents

-Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Products

• 1. Total Release Ci 2.59E-04 1.13E-03 9.48E-04 1.93E-03 4.27E-03 2. Avg. Diluted Cone. µCi/ml 4.82E-14 2.59E-13 2.82E-13 5.48E-13 2.72E-13

3. Batch Releases µCi/ml 3.10E-11 1.34E-10 1.11E-10 2.25E-10 1.26E-10 B. Tritium 1. Total Release Ci 2.04E+02 1.86E+02 3.90E+02 2.59E+02 1.04E+03 2. Avg. Diluted Cone. µCi/ml 6.83E-08 7.28E-08 1.48E-07 1.21 E-07 1.02E-07 3. Batch Releases µCi/ml 2.44E-05 2.20E-05 4.55E-05 3.02E-05 3.06E-05 C. Dissolved

& Entrained Gases 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 2. Avg. Diluted Cone. µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Batch Releases µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Gross Alpha 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2. Avg. Diluted Cone. µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3. Batch Releases µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E. Volume of Liquid Waste 1. Continuous Releases liters 6.04E+08 5.24E+08 5.57E+08 1.04E+09 2.73E+09 2. Batch Releases liters 9.41E+05 1.02E+06 1.42E+06 2.54E+06 5.92E+06 F. Volume of Dilution Water 1. Continuous Releases 8.37E+09 8.44E+09 8.55E+09 8.55E+09 3.39E+10 2. Batch Releases liters 8.37E+09 8.44E+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 1/1/2015 -12/31/2015 Liquid Effluents

-Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO B. Tritium H-3 Ci 2.73E-01 2.71 E-01 3.00E-01 4.63E-01 1.31E+OO C. Dissolved

& Entrained Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-8 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Liquid Effluents

-Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products AG-110M Ci O.OOE+OO 2.62E-05 9.91E-05 O.OOE+OO 1.25E-04 C0-58 Ci 5.77E-05 7.17E-04 6.66E-04 1.04E-03 2.48E-03 C0-60 Ci O.OOE+OO 6.16E-05 4.48E-05 O.OOE+OO 1.06E-04 CR-51 Ci O.OOE+OO 5.71E-05 O.OOE+OO O.OOE+OO 5.71E-05 CS-137 Ci 1.40E-04 6.64E-05 O.OOE+OO O.OOE+OO 2.07E-04 FE-55 Ci O.OOE+OO O.OOE+OO O.OOE+OO 8.56E-04 8.56E-04 1.-131 Ci O.OOE+OO O.OOE+OO O.OOE+OO 5.04E-06 5.04E-06 NB-95 Ci O.OOE+OO 6.21E-05 O.OOE+OO O.OOE+OO 6.21E-05 NB-97 .Ci O.OOE+OO 1.16E-05 O.OOE+OO O.OOE+OO 1.16E-05 Nl-63 Ci 6.15E-05 1.15E-04 1.38E-04 2.80E-05 3.43E-04 ZR-97 Ci O.OOE+OO 1.16E-05 O.OOE+OO O.OOE+OO 1.16E-05 TOtal for Period Ci 2.59E-04 1.13E-03 9.48E-04 1.93E-03 4.27E-03 B. Tritium H-3 Ci 2.04E+02 1.86E+02 3.89E+02 2.58E+02 1.04E+03 C. Dissolved

& Entrained Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-9 Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 2 Supplemental Information This attachment includes supplemental information to the gaseous and liquid effluents report. Page 2-1 I. A. B. Regulato!l'.

Limits -Per Unit Noble Gases -Air Dose 1. Calendar Quarter Gamma Dose 2. Calendar quarter Beta Dose 3. Calendar Year Gamma Dose 4. Calendar Year Beta Dose Liquid Effluents

-Dose Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015

=5 mRAD = 10 mRAD = 10 mRAD = 20 mRAD 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 B. Liquid Effluents

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

• V. Batch Releases A. Liquid Effluents

1. Total Number of Batch Releases 2. Total Time (min) for Batch Releases 3. Maximum Time (min) for a Batch Release 4. Average Time (min) for Batch Releases 5. Minimum Time (min) for a Batch Release 6. Average Dilution Water Flow During Release (gpm) B. Gaseous Effluents

1. Total Number of Batch Releases 2. Total Time (min) for Batch Releases 3. Maximum Time (min) for a Batch Release 4. Averag*e Time (min) for Batch Releases 5. Minimum Time (min) for a Batch Release VI. Abnormal Releases See Attachment 5, Unplanned Offsite Releases.

6.70E+01 1.34E+04 2.25E+02 2.00E+02 5.90E+01 1.70E+.04

• 4.90E+01 5.88E+04 1.62E+04 1.20E+03 3.50E+01 Page 2-2 Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 2015 ARERR contains estimates of C-14 radioactivity released in 2015, 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). Amore 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 Ocor:iee Nuclear Station 2015 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 2015 results in a site total C-14 gaseous release estimate to the environme*nt of 23.54 Curies. 70% of the C-14 gaseous effluent is assumed to be from batch releases (e.g. WGDTs), and 30% of C-14 gaseous effluent is assumed to be from continuous releases through the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14", 2004). C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. Since the PWR operates with a reducing chemistry, most, if not all, of the C-14 species initially produced are organic (e.g., methane).

As a general rule, C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment (e.g. during shutdown or refueling), a slow transformation from an organic to an inorganic chemical form can occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic with an average of 80% organic with the remainder being C0 2 (Ref. EPRI TR-105715).

For the Oconee Nuclear Station 2015 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 2015 is well below the 1 OCFR50, 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 1/1/2015-12/31/2015 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 1/1/2015 -12/31/2015 Summary of Changes in Land Use Census Affecting Effluent Dose Calculations The 2015 Land Use Census was performed May 19-20, 2015, and the results were certified and made available for use on June 4, 2015. The following are changes to residences, gardens, and milk animals from the previous year. Residences No changes to nearest residence in each sector. 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 No changes to nearest milk animal in each sector. 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 1/1/2015 -12/31/2015 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 1/1/2015 -12/31/2015 Type of Number of Number of Waste Container Solidification Burial Total Waste Shipped Shipments Containers Class Type Agent Volume Activity (m3) (Curies) 1. Waste from Liguid SJ£stems a. Dewatered Secondary Resins 4 12 AU GDP N/A 70.48 1.677 5-B Type A b. Dewatered Primary Resins 6 6 N/A 20.44 176.38 1 -AS GDP c. Evaporator Concentrates 0 d. Dewatered Mechanical Filters 2 2 c Type A N/A 6.81 8.48 e. Dewatered Demineralizers 0 f. Solidified (cement) Acids, 0 Oils, Sludge 2. Dry Solid Waste a. Dry Active Waste 0 (compacted)

b. Dry Active Waste (non-37-AU 19 38 GDP N/A 890.64 177.686 compacted) 1 -AS c. Dry Active Waste (brokered) 0 d. Irradiated Components 0 3. Total Solid Waste 31 58 988.37 364.223 Page 3-2 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Type of Waste Shipped Radionuclide

1. Waste from Liquid Systems a. Dewatered Secondary Resins 15-2007 AG-110m C-14 CE-144 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 MN-54 Nl-63 SB-125 AG-110m C-14 CE-144 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 MN-54 Nl-63 SB-125 AG-110m C-14 CE-144 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 MN-54 NB-95 Nl-63 SB-125 ZN-65 AG-110m C-14 CE-144 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 NB-95 Nl-63 SB-125 ZN-65 % Abundance 0.0768 7.9182 0.0348 0.0284 0.0379 2.3048 0.0998 0.7230 12.7509 55.5762 0.1093 19.8885 0.4721 0.0425 6.1575 0.0218 0.0150 0.0018 1.5776 0.1961 1.1074 7.7088 67.3031 0.0494 15.3938 0.4558 0.1287 5.0592 0.0182 0.0203 0.0825 1.4527 0.0530 0.4142 5.7692 73.9645 0.1059 0.0006 12.6923 0.2379 0.0340 0.0329 2.8774 0.0358 0.0262 0.0994 0.8355 0.0926 0.6613 4.5806 82.9032 0.0025 7.2258 0.3774 0.0209 Page 3-3 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015

b. Dewatered Primary Resins AG-110m AM-241 C-14 CE-144 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 1-129 MN-54 Nl-59 Nl-63 SB-125 SR-89 SR-90 TC-99 ZN-65 AG-110m AM-241 C-14 CE-144 CM-242 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 FE-59 MN-54 NB-95 Nl-63 SB-124 SB-125 SR-90 ZN-65 ZR-95 0.0566 0.0002 1.3411 0.0177 0.0002 0.5430 7.6159 4.4702 1.7980 7.4834 18.0464 0.3175 0.0005 0.8212 0.3709 56.9536 0.1298 0.0006 0.0338 0.0053 0.0573 0.0631 0.0012 1.8803 0.0631 0.0004 0.0012 0.5676 18.4556 6.6409 0.7626 3.7066 14.7683 0.0263 1.2259 0.0772 50.3861 0.2954 0.5097 0.0392 0.2297 0.0595 Page 3-4 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 AG-110m Be-7 C-14 CE-144 CM-242 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 FE-59 H-3 1-129 MN-54 NB-95 Nl-59 Nl-63 PU-238 PU-241 SB-124 SR-89 SR-90 TC-99 ZN-65 ZR-95 AG-110m AM-241 Be-7 C-14 CE-144 CM-242 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 MN-54 Nl-59 Nl-63 PU-238 . PU-241 SB-124 SB-125 SR-89 SR-90 TC-99 ZN-65 0.0652 3.2879 0.3561 0.0220 0.0001 0.0001 0.6561 18.4848 4.6970 0.4212 2.1364 17.1212 0.0270 0.1432 0.0002 2.4242 0.0703 0.2727 49.3939 0.0003 0.0049 0.0134 0.0261 0.0161 0.0014 0.2152 0.0491 0.1014 0.0001 1.3264 0.3069 0.0254 0.0001 0.0001 0.5938 12.7778 4.7917 0.9479 5.1389 16.7014 0.0090 1.7951 0.3083 54.5139 0.0004 0.0090 0.0462 0.0816 0.0111 0.0340 0.0022 0.1681 Page 3-5 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 AG-110m AM-241 Be-7 C-14 CE-144 CM-242 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 1-129 MN-54 NB-95 Nl-59 Nl-63 PU-238 PU-241 SB-124 SB-125 SR-90 TC-99 ZN-65 ZR-95 AG-110m AG-108m Be-7 C-14 CE-144 CM-242 CM-243/44 C0-57 C0-58 C0-60 CS-134 CS-137 FE-55 H-3 1-129 MN-54 NB-95 Nl-59 Nl-63 PU-238 PU-241 SB-124 SB-125 SR-89 SR-90 TC-99 ZN-65 c. Evaporator Concentrates NIA 0.1680 0.0003 0.3688 1.5156 0.0452 0.0005 0.0004 0.5422 9.2188 6.3438 0.8125 4.6406 20.0000 0.0007 1.7344 0.1930 0.3484 52.9688 0.0011 0.0179 0.0805 0.1656 0.0341 0.0019 0.2797 0.1336 0.1302 0.0389 0.1398 0.0015 0.0802 0.0003 0.0004 0.4551 5.7485 5.0299 1.2395 7.6048 10.8683 0.0078 0.0001 1.6287 0.0461 0.6886 65.8683 0.0001 0.0179 . 0.0162 0.0832 0.0003 0.0012 0.0062 0.1964 N/A Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015

d. Dewatered Mechanical Filters 15-2006 AG-110m C-14 CE-144 C0-57 C0-58 C0-60 CR-51 CS-134 CS-137 FE-55 FE-59 H-3 MN-54 NB-95 Nl-63 SB-125 SR-90 ZN-65 ZR-95 AG-110m C-14 CE-144 HF-181 SC-46 C0-57 C0-58 C0-60 CR-51 CS-134 CS-137 FE-55 FE-59 H-3 1-129 MN-54 NB-95 Nl-63 SB-124 SN-113 SR-90 TC-99 . ZN-65 ZR-95 e. Dewatered Demineralizers NIA f. Solidified (cement) Acids, Oils, Sludge NIA 2. Dry Solid Waste a. Dry Active Waste (compacted)

NIA 0.0240 16.6167 0.7944 0.2377 8.3298 26.5525 0.0040 8.8865 25.4818 2.6124 0.0010 0.0042 4.0685 0.1015 4.2398 0.0621 0.0098 1.2355 0.7794 0.6010 -7.3228 0.6378 0.0003 0.0010 0.4672 9.2651 18.8714 0.4908 0.0745 1.5171 46.7192 0.0491 0.0596 0.2074 4.8556 0.2580 4.7769 0.0352 0.0003 0.0073 0.8110 2.3333 0.9895 NIA NIA NIA Page 3-7 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/3112015

b. Dry Active Waste (non-compacted) 15-2002 C-14 0.2781 CE-144 0.2933 C0-57 0.3337 C0-58 81.4050 C0-60 1.6405 CR-51 1.9656 CS-137 0.0844 FE-55 5.1694 FE-59 0.2317 MN-54 0.2559 NB-95 1.1598 Nl-63 5.9118 TC-99 0.1605 ZR-95 1.0179 15-2003 C-14 0.2329 CE-144 0.2573 C0-57 0.2934 C0-58 82.4883 C0-60 1.3873 CR-51 2.5869 CS-137 0.0705 FE-55 4.3897 FE-59 0.2606 MN-54 0.2099 NB-95 1.4047 Nl-63 4.9484 TC-99 0.1344 ZR-95 1.0516 15-2004 C-14 0.3228 CE-144 0.3263 M0-99 0.2711 C0-57 0.3709 C0-58 80.4825 C0-60 1.8921 CR-51 1.4737 CS-137 0.0978 FE-55 5.6667 FE-59 0.2089 MN-54 0.2711 NB-95 0.9588 Nl-63 6.8526 TC-99 0.1854 ZR-95 0.9856 15-2005 C-14 0.2696 CE-144 0.2872 C0-57 0.3264 C0-58 82.2336 C0-60 1.5916 CR-51 2.0047 CS-137 0.0817 FE-55 5.0215 FE-59 0.2365 MN-54 0.2510 NB-95 1.1879 Nl-63 5.7234 TC-99 0.6879 ZR-95 1.0299 Page 3-8 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 15-2009 C-14 0.3090 CE-144 0.3164 C0-57 0.3589 C0-58 80.5104 C0-60 1.8167 CR-51 1.5394 CS-137 0.0959 FE-55 5.6961 FE-59 0.2110 MN-54 0.2769 NB-95 0.9942 Nl-63 6.5661 TC-99 0.1774 ZR-95 0.2065 15-2013 AG-110m 0.0354 C-14 2.9454 CE-144 0.1250 C0-57 0.0605 C0-58 5.9876 C0-60 2.4101 CR-51 0.2236 CS-137 0.4985 FE-55 69.7786 FE-59 0.0199 MN-54 0.2043 NB-95 0.1214 Nl-63 16.9773 SB-125 0.3151 ZR-95 0.1352 15-2014 C-14 0.3451 CE-144 0.3422 C0-57 0.3862 C0-58 79.5519 C0-60 2.0170 CR-51 1.2759 CS-137 0.1042 FE-55 6.3100 FE-59 0.1948 MN-54 0.3005 NB-95 0.8719 Nl-63 7.3252 TC-99 0.1986 ZR-95 0.9656 15-2015 C-14 0.2933 CE-144 0.3053 C0-57 0.3465 C0-58 81.1321 C0-60 1.7324 CR-51 1.7015 CS-137 0.0889 FE-55 5.4374 FE-59 0.2196 MN-54 0.2676 NB-95 1.0635 Nl-63 6.2264 TC-99 0.1690 ZR-95 1.0069 Page 3-9 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 15-2016 C-14 0.3373 CE-144 0.3369 C0-57 0.3827 C0-58 79.52 C0-60 1.9801 CR-51 1.3150 CS-137 0.1023 FE-55 6.1774 FE-59 0.1974 MN-54 0.2954 NB-95 0.8914 Nl-63 7.1713 TC-99 0.1945 ZR-95 0.9709 15-2017 C-14 0.2330 CE-144 0.2577 C0-57 0.2924 C0-58 82.6667 C0-60 1.3861 CR-51 2.5805 CS-137 0.0706 FE-55 4.3813 FE-59 0.2609 MN-54 0.2240 NB-95 1.4048 Nl-63 4.9547 TC-99 0.1341 ZR-95 1.0611 15-2019 C-14 0.2013 CE-144 0.2314 C0-57 0.2642 C0-58 83.3724 C0-60 1.2064 CR-51 3.2682 CS-137 0.0613 FE-55 3.8411 FE-59 0.2867 MN-54 0.2013 NB-95 1.6419 Nl-63 4.2839 TC-99 0.1161 ZR-95 1.0793 15-2020 C-14 0.3053 CE-144 0.3113 C0-57 0.3537 C0-58 80.4000 C0-60 1.7943 CR-51 1.8323 CS-137 0.0925 FE-55 5.5967 FE-59 0.2203 MN-54 0.2723 NB-95 1.0883 Nl-63 6.4667 TC-99 0.1754 ZR-95 0.9963 Page 3-10 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 C-14 CE-144 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-95 Nl-63 TC-99 ZR-95 C-14 CE-144 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-95 Nl-63 TC-99 ZR-95 C-14 CE-144 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-95 NJ-63 TC-99 ZR-95 0.3578 0.3499 0.3979 79.053 2.0787 1.1958 0.1112 6.4912 0.1892 0.3074 0.8331 7.5762 0.2056 0.9583 0.2371 0.2343 0.2676 83.3333 1.2296 3.2579 0.0624 3.9057 0.2843 0.2031 1.6415 4.3679 0.1182 1.0786 0.1851 0.2172 0.2406 85.5227 1.1108 3.7500 0.0563 3.5653 0.3017 0.1879 1.7997 3.9631 0.1065 1.0895 Page 3-11 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 AG-110m CM-243 AM-241 C-14 CE-144 CM-242 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-94 NB-95 Nl-63 PU-238 PU-239/40 PU-241 SB-124 SB-125 SN-113 SR-90 ZN-65 ZR-95 AG-110m CM-243 AM-241 C-14 C0-57 C0-58 C0-60 CR-51 CS-134 CS-137 FE-55 FE-59 H-3 1-129 MN-54 NB-94 NB-95 Nl-63 PU-238 PU-239/40 PU-241 SB-124 SB-125 SN-113 SR-90 ZN-65 ZR-95 . 0.0033 0.0006 0.0015 0.5523 0.0044 0.0218 0.0033 0.1753 1.0483 0.0147 0.0031 94.0805 0.0943 0.0493 0.0024 0.0270 3.8621 0.0011 0.0006 0.0248 0.0096 0.0532 0.0021 0.0063 0.0224 0.0137 0.0280 0.0005 0.0014 0.0080 0.0009 0.2366 1.1066 0.0145 0.0185 0.0539 89.7971 0.0315 3.0368 0.0605 0.0605 0.0023 0.0329 4.5882 0.0011 0.0006 0.0234 0.0092 0.0823 0.0020 0.0065 0.0260 0.0132 Page 3-12 Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 AG-110m CM-243 AM-241 C-14 CM-242 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-94 NB-95 Nl-63 PU-238 PU-239/40 PU-241 SB-124 SB-125 SN-113 SR-90 ZN-65 ZR-95 AG-110m CM-243 AM-241 C-14 CE-144 C0-57 C0-58 C0-60 CR-51 CS-137 FE-55 FE-59 MN-54 NB-94 NB-95 Nl-63 PU-238 PU-239/40 PU-241 SB-124 SB-125 SN-113 SR-90 ZN-65 ZR-95 c. Dry Active Waste (brokered)

NIA d. Irradiated Components N/A 0.0033 0.0006 0.0015 0.0044 0.0001 0.0032 0.1743 1.0457 0.0146 0.0031 93.9948 0.0939 0.0493 0.0024 0.0269 3.8538 0.0001 0.0006 0.0143 0.0095 0.0531 0.0021 0.0069 0.0224 0.0136 0.0030 0.0002 0.0015 0.5695 0.0041 0.0030 0.1363 1.0605 0.0101 0.0032 94.1406 0.0685 0.0465 0.0025 0.0191 3.9805 0.0012 0.0006 0.0253 0.0073 0.0532 0.0018 0.0071 0.0207 0.0105 N/A N/A Page 3-13 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 4 Meteorological Data This attachment includes a summary of meteorological joint frequency distributions of wind speed, wind direction, and atmospheric stability (hours of occurrence).

Page 4-1 Lower Level Wind Stability Speed Class (mph) N NNE NE 0.46-0.75 a a a 0.76-1.00 a a a 1.01-1.25 a a a 1.26-1.50 1 a a 1.51-2.00 2 a 1 2.01-3.00 a a a A 3.01-4.00 0 a 3 4.01-5.00 a 0 a 5.01-6.00 a 0 a 6.01-8.00 0 0 0 8.01-10.00 a 0 0 10.01-max 0 0 0 0.46-0.75 0 0 0 0.76-1.00 0 0 0 1.01-1.25 0 0 1 1.26-1.50 a 0 0 1.51-2.00 3 2 1 2.01-3.00 2 1 6 B 3.01-4.00 1 2 2 4.01-5.00 0 0 1 5.01-6.00 0 0 0 6.01-8.00 0 0 0 8.01-10.00 0 0 0 10.01-max 0 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a 3 0 0 1 0 0 0 2 22 3 0 0 0 1 1 23 69 1 2 0 0 0 0 3 8 1 0 0 0 0 a a 1 0 0 0 a 0 a a 0 0 0 0 0 0 0 0 0 0 0 0 a 0 0 0 0 0 0 0 a 0 0 0 0 0 0 0 0 0 a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 0 0 a 1 3 3 2 1 0 . 0 1 . 14 33 10 6 1 0 2 6 42 61 3 3 a 0 0 0 16 13 0 0 a 0 0 0 0 2 0 0 0 0 0 0 0 1 0 0 0 0 0 a 0 2 0 0 0 0 a a 0 0 0 0 0 0 a a 0 0 WSW w WNW NW NNW a a a a a a a a a a a a a a a a a 1 a a 2 2 4 1 0 15 5 1 1 2 1 2 1 0 0 1 a 1 0 0 1 1 1 1 0 0 0 6 3 0 a 0 0 a 0 0 0 0 0 0 0 0 0 0 0 0 0 a 0 0 0 0 a 0 0 0 0 0 2 0 9 6 2 2 0 33 3 3 2 a 1 1 3 0 1 0 0 0 0 0 1 0 3 1 0 0 1 4 3 2 .o 1 1 1 0 0 0 0 0 0 Page 4-2 Lower Level Wind Stability Speed Class (mph) N NNE 0.46-0.75 0 0 0.76-1.00 0 0 1.01-1.25 0 0 1.26-1.50 2 0 1.51-2.00 4 7 2.01-3.00 0 1 c 3.01-4.00 0 3 4.01-5.00 0 1 5.01-6.00 0 0 6.01-8.00 0 0 8.01-10.00 0 0 10.01-max 0 0 0.46-0.75 0 0 0.76-1.00 12 11 1.01-1.25 28 21 1.26-1.50 19 28 1.51-2.00 19 38 2.01-3.00 22 21 D 3.01-4.00 4 10 4.01-5.00 0 1 5.01-6.00 0 0 6.01-8.00 0 0 8.01-10.00 0 0 10.01-max 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector NE ENE E ESE SE SSE s SSW SW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 1 0 0 0 0 0 2 3 5 5 6 2 4 1 3 7 16 33 13 22 12 7 6 5 6 55 36 1 2 3 0 0 0 2 16 17 1 0 0 0 0 0 0 3 6 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 1 0 2 2 1 1 1 1 12 10 5 3 3 0 4 8 14 10 8 9 7 8 12 8 15 21 29 31 25 19 22 21 25 44 52 61 99 75 30 36 48 42 67 89 139 197 78 24 25 16 29 136 161 54 67 5 1 0 0 1 54 74 16 9 0 0 0 0 0 8 25 3 0 0 0 0 0 0 2 4 1 0 0 0 0 0 .0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW w WNW NW NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 1 2 2 1 22 9 5 8 3 23 3 4 2 0 4 0 4 3 0 0 2 5 0 2 3 1 3 4 2 1 0 11 2 1 0 0 0 1 0 0 . 0 0 0 0 1 1 1 1 2 17 16 15 9 13 29 26 23 14 39 46 32 22 19 32 76 49 21 15 17 85 33 15 13 14 45 23 22 8 8 31 14 23 10 3 23 7 14 13 0 9 6 8 1 0 1 7 0 0 0 0 0 0 0 0 Page 4-3 Lower Level Wind Stability Speed Class (mph) N NNE NE 0.46-0.75 19 9 12 0.76-1.00 87 58 46 1.01-1.25 64 35 47 1.26-1.50 41 30 52 1.51-2.00 35 23 65 2.01-3.00 9 14 75 E 3.01-4.00 2 4 26 4.01-5.00 1 0 3 5.01-6.00 0 0 0 6.01-8.00 0 0 0 8.01-10.00 0 0 0 10.01-max 0 0 0 0.46-0.75 0 0 0 0.76-1.00 5 2 2 1.01-1.25 2 2 3 1.26-1.50 1 0 1 1.51-2.00 0 0 1 2.01-3.00 0 1 4 F 3.01-4.00

• 0 0 0 4.01-5.00 0 0 0 5.01-6.00 0 0 0 6.01-8.00 0 0 0 8.01-10.00 0 0 0 10.01-max 0 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW 11 6 9 3 3 8 7 11 42 46 33 35 18 26 .34 26 47 43 38 41 34 36 36 31 54 50 46 43 44 40 40 45 88 67 37 43 73 49 50 60 89 41 11 10 18 30 45 85 8 1 2 2 1 3 15 33 1 1 0 0 0 0 0 10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 2 0 0 1 0 1 3 3 1 1 3 1 2 3 3 2 6 0 2 1 2 0 1 3 6 1 1 0 2 4 2 2 8 3 1 3 3 3 4 1 1 1 0 1 1 5 2 0 1 0 0 0 1 1 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW w WNW NW NNW 10 13 19 19 11 49 55 85 134 138 41 38 63 79 89 31 20 34 48 32 27 15 27 23 19 45 20 12 11 10 28 14 2 0 1 9 3 2 2 0 1 2 2 2 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 6 1 0 9 14 22 20 8 3 4 30 15 1 2 2 25 22 3 1 1 2 9 0 2. 2 0 1 2 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-4 Lower Level Stability Wind Class Speed (mph) N NNE NE 0.46-0.75 0 0 0 0.76-1.00 1 1 1 1.01-1.25 0 2 1 1.26-1.50 1 0 1 1.51-2.00 0 0 0 2.01-3.00 0 0 0 G 3.01-4.00 0 0 0 4.01-5.00 0 0 0 5.01-6.00 0 0 0 6.01-8.00 0 0 0 8.01-10.00 0 0 0 10.01-max 0 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW w WNW NW NNW 0 0 0 0 0 1 0 3 4 0 0 2 7 4 0 1 2 2 4 0 1 0 1 2 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-5 Upper Level Wind Stability Speed Class (mph) N NNE NE 0.46-0.75 0 0 0 0.76-1.00 0 0 0 1.01-1.25 0 0 0 1.26-1.50 0 0 0 1.51-2.00 0 1 0 2.01-3.00 1 1 0 A 3.01-4.00 0 0 0 4.01-5.00 0 0 0 5.01-6.00 0 0 2 6.01-8.00 0 0 1 8.01-10.00 0 0 *o 10.01-max 0 0 0 0.46-0.75 0 0 0 0.76-1.00 0 0 0 1.01-1.25 0 0 0 1.26-1.50 0 0 0 1.51-2.00 0 0 1 2.01-3.00 2 3 2 B 3.01-4.00 0 1 1 4.01-5.00 2 1 1 5.01-6.00 0 0 1 6.01-8.00 0 0 2 8.01-10.00 0 0 0 10.01-max 0 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2. 0 0 0 0 0 0 0 3 1 0 1 0 0 1 11 34 1 1 0 0 1 0 20 28 0 2 0 0 0 1 6 13 0 2 0 0 0 0 4 10 1 0 0 0 0 0 0 2 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ,0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 6 8 3 4 1 1 3 2 15 53 4 6 0 0 0 7 27 18 5 9 0 0 0 1 17 12 0 1 0 0 0 1 10 14 1 0 0 0 0 0 0 5 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 WSW w WNW NW NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 3 1 0 10 2 2 1 1 6* 0 0 1 1 1 0 0 0 0 0 2 1 0 0 1 1 2 1 0 1 0 5 3 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 2 5 2 2 2 21 5 1 0 0 8 0 0 0 0 2 0 1 2 0 2 1 0 2 1 1 0 3 0 0 1 1 2 3 0 2 1 3 3 2 Page 4-6 Upper Level Wind Stability Speed Class (mph) N NNE 0.46*0.75 0 0 0.76-1.00 0 0 1.01-1.25 0 0 1.26-1.50 0 0 1.51-2.00 3 4 2.01-3.00 1 3 c 3.01-4.00 0 1 4.01-5.00 0 2 5.01-6.00 0 1 6.01-8.00 0 1 8.01-10.00 0 0 10.01-max 0 0 0.46-0.75 1 0 0.76-1.00 0 4 1.01-1.25 9 12 1.26-1.50 11 18 1.51-2.00 35 27 2.01-3.00 30 50 D 3.01-4.00 16 25 4.01-5.00 5 8 5.01-6.00 4 9 6.01-8.00 1 0 8.01-10.00 0 1 10.01-max 0 0 NE 0 0 0 0 0 7 3 1 1 1 0 0 1 2 8 7 29 58 83 95 47 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 3 0 0 1 1 1 2 4 17 11 5 5 3 7 10 21 29 16 9 3 2 3 8 31 13 7 9 2 0 0 2 16 13 3 1 0 0 0 2 10 11 1 0 0 0 0 0 4 16 0 0 0 0 0 0 0 3 0 0 0 0 0 0 0 1 0 0 0 0 1 0 1 1 2 0 1 0 1 1 1 3 1 2 1 6 0 3 8 12 11 7 0 5 9 7 12 26 13 28 9 25 29 16 42 54 63 83 28 38 47 52 71 68 94 76 20 13 16 31 57 87 74 43 3 1 2 3 52 76 41 13 0 0 0 3 26 70 37* 23 3 0 1 0 1 14 81 13 3 0 0 0 0 0 2 18 2 0 0 0 0 0 0 0 2 WSW w WNW NW NNW 0 0 0 0 0 0 0 0 0 0 1 0 1 0 0 1 1 2 1 0 13 8 2 3 3 23 0 2 0 3 1 2 o. 3 0 3 1 0 3 0 1 0 4 3 0 2 2 4 3 2 4 0 8 3 3 1 0 3 4 0 1 2 0 1 1 3 8. 4 2 7 13 12 16 13 7 24 22 16 15 23 46 24 17 15 33 64 30 25 26 28 42 14 15 9 12 29 19 18 3 11 29 12 19 10 6 49 15 40 20 5 15 10 12 11 0 3 11 3 1 0 Page 4-7 Upper Level Stability Wind Class Speed (mph) N NNE 0.46-0.75 2 1 0.76-1.00 10 6 1.01-1.25 25 16 1.26-1.50 50 32 1.51-2.00 134 84 2.01-3.00 232 182 E 3.01-4.00 44 42 4.01-5.00 11 18 5.01-6.00 1 5 6.01-8.00 1 1 8.01-10.00 1 1 10.01-max 0 0 0.46-0.75 0 0 0.76-1.00 3 2 1.01-1.25 1 1 1.26-1.50 7 1 1.51-2.00 18 13 2.01-3.00 21 22 F 3.01-4.00 4 4 4.01-5.00 1 1 5.01-6.00 0 2 6.01-8.00 0 1 8.01-10.00 0 0 10.01-max 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector NE ENE E ESE SE SSE s SSW SW 3 0 1 0 0 1 1 0 4 4 3 2 5 5 4 4 3 4 17 8 7 9 4 8 3 8 12 13 10 14 5 7 6 14 12 15 33 34 26 18 13 18 13 15 27 110 75 50 31 31 39 45 50 101 87 69 . 35 22 23 23 59 40 78 46 33 27 5 4 10 18 30 61 36 6 6 1 1 2 9 21 42 15 7 1 2 0 2 1 8 35 1 0 0 0-0 0 0 0 4 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 0 0 1 3 0 0 2 0 2 1 0 1 3 0 1 1 2 1 1 3 1 3 4 2 0 3 3 3 1 1 6 4 1 4 3 1 1 1 1 5 5 5 3 4 4 2 3 8 0 4 0 2 1 1 1 2 9 2 1 2 1 0 0 0 4 3 1 3 0 0 0 0 0 0 2 0 0 0 0 1 0 0 0 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW w WNW NW NNW 0 1 0 1 3 10 11 13 13 11 8 25 20 30 29 18 22 35 49 63 36 32 42 72 119 68 30 22 35 126 28 11 11 24 17 17 11 10 14 3 20 15 12 5 5 27 14 5 2 0 2 2 1 1 0 0 0 0 0 0 0 0 0 0 0 0 2 1 0 0 2 1 1 2 2 3 1 4 2 3 1 5 2 1 6 6 7 2 6 4 5 1 0 1 4 2 1 0 1 0 2 2 0 0 1 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-8 Upper Level Wind Stability Speed Class (mph) N NNE NE 0.46-0.75 0 0 0 0.76-1.00 0 0 0 1.01-1.25 0 0 0 1.26-1.50 0 0 0 1.51-2.00 2 0 1 2.01-3.00 2 2 1 G 3.01-4.00 1 0 1 4.01-5.00 0 0 . 0 5.01-6.00 0 0 0 6.01-8.00 0 0 0 8.01-10.00 0 0 0 10.01-max 0 0 0 Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector ENE E ESE SE SSE s SSW SW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 0 2* 0 0 1 0 0 0 0 2 0 0 0 0 0 0 1 1 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW w WNW NW NNW 0 0 0 0 0 0 1 0 1 0 0 0 0 0 0 0 1 0 2 0 2 1 2 2 0 2 2 0 0 0 1 0 0 0 2 2 2 0 0 1 1 0 0 0 0 0 1 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 1/1/2015 -12/31/2015 ATTACHMENT 5 Unplanned Offsite Releases This attachment includes a summary of the unplanned offsite releases of gaseous and liquid radioactive effluents.

Page 5-1 Attachment 5 Unplanned Offsite Releases Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Oconee Nuclear Station had zero (0) unplanned liquid offsite release radioactive effluents.

Oconee Nuclear Station had one (1) unplanned gaseous offsite release of radioactive effluents.

Summary is provided below. Unplanned release of "38" Gaseous Waste Decay Tank: Reference NCR 01907276 Event Summary: On 1/27/15, during venting of U3 Let Down Storage Tank (LDST) to the 3B Gaseous Waste Decay Tank (GWDT), an increase in counts was observed on the unit vent normal range radiation monitor, 3 RIA 45, at 23:26 hours. The LDST venting was terminated and the 3B GWDT was isolated.

Once isolated the 3B GWDT pressure was observed to be decreasing and the GWDT radiation monitor, 3 RIA 37, had increased counts indicating the contents were being released to the unit vent. Radiation monitor 3RIA-45 exhibited increased count rates due to the release, but no setpoints or instantaneous release rate limits were exceeded.

The unplanned release was terminated when 3B GWDT reached 0 psig at 07:00 on 1/28/15. Investigation identified that a 3B GWDT relief valve failed to seat, causing the 3B GWDT to lose pressure.

The GWD valve was repaired and an additional test was added to the preventative maintenance.

procedure to prevent recurrence.

A separate release permit, 2015004, was created to account for the release activity and related dose. The release volume and activity were determined using count rates and flow rates for 3RIA-37. The release volume from the 3B tank was 4500 cubic feet based on the initial tank pressure of 45 psig and tank volume chart in OP/O/A/1108/001, Curves and General Information.

The total activity of the unplanned release was 0.735 Curies. Safety Significance:

The health and safety of the public were not compromised by this event. The total activity released was 0.735 Curies. Calculated dose and dose rates to the Total Body, Skin, Gamma Air, and Beta Air were all well below the limits specified by Selected Licensee Commitments Page 5-2 Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 ATTACHMENT 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results) This attachment includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of the report as well as the total dose for the calendar year. This attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 8 km of the site for the calendar year of this report to show conformance with 40 CFR Part 190. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the Offsite Dose Calculation Manual (ODCM). Page 6-1 Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Gaseous Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 A. Noble Gases 1. Maximum Gamma Air mRAD 2.18E-04 1.88E-04 2.83E-04 (a) Limit mRAD 1.50E+01 1.50E+01 1.50E+01 (b) % of Limit 1.46E-03 1.26E-03 1.89E-03 2. Maximum Beta Air mRAD 2.0BE-04 1.30E-04 1.42E-04 (a) Limit mRAD 3.00E+01 3.00E+01 3.00E+01 (b) % of Limit 6.93E-04 4.33E-04 4.72E-04 Receptor Location 1.0 miles SW B. Iodine, H-3, & Particulates

1. Maximum Organ Dose mREM 8.90E-02 9.0BE-02 8.88E-02 (a) Limit mREM 2.25E+01 2.25E+01 2.25E+01 (b) % of Limit 3.95E-01 4.04E-01 3.95E-01 Receptor Location 1.0 miles SW Critical Age CHILD Critical Organ BONE Critical Pathway VEGETATION Qtr4 Year 1.32E-05 7.03E-04 1.50E+01 3.00E+01 8.78E-05 2.34E-03 3.91E-05 5 .. 19E-04 3.00E+01 6.00E+01 1.30E-04 8.64E-04 8.20E-02 3.51 E-01 2.25E+01 4.50E+01 3.64E-01 7.79E-01 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 1/1/2015 -12/31/2015 Liquid Effluents Dose Summary Units Qtr 1 Qtr2 Qtr 3 Qtr4 Year A. Batch Mode 1. Maximum Organ Dose mREM 4.62E-02 4.93E-02 5.41 E-02 3.60E-02 1.71 E-01 (a) Limit mREM 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.00E+01 (b) % of Limit 3.08E-01 3.29E-01 3.61 E-01 2.40E-01 5.69E-01 (c) Critical Age Adult Adult Child Child Child (d) Critical Organ Liver GILLI Liver Liver Liver (e) Critical Pathway Fish Fish Pt. Water Pt. Water Pt. Water 2. Maximum Total Body Dose mREM 3.97E-02 3.09E-02 5.41E-02 3.59E-02 1.57E-01 (a) Limit mREM 4.50E+OO 4.50E+OO 4.50E+OO 4.50E+OO 9.00E+OO (b) % of Limit 8.81 E-01 6.86E-01 1.20E+OO 7.98E-01 1.75E+OO (c) Critical Age Adult Adult Child Child Adult' (d) Critical Pathway Fish Fish Pt. Water Pt. Water Fish B. Continuous Mode 1. Maximum Organ Dose mREM 3.53E-05 3.54E-05 3.90E-05 5.73E-05 1.68E-04 (a) Limit mREM 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.00E+01 (b) % of Limit 2.35E-04 2.36E-04 2.60E-04 3.82E-04 5.59E-04 (c) Critical Age Child Child Child Child Child (d) Critical Organ Liver Liver Liver Liver Liver (e) Critical Pathway Pt. Water Pt. Water Pt. Water Pt. Water Pt. Water 2. Maximum Total Body Dose mREM 3.53E-05 3.54E-05 3.90E-05 5.73E-05 1.68E-04 (a) Limit mREM 4.50E+OO 4.50E+OO 4.50E+OO 4.50E+OO 9.00E+OO (b) % of Limit 7.85E-04 7.87E-04 8.67E-04 1.27E-03 1.86E-03 (c) Critical Age Child Child Child Child Child (d) Critical Pathway Pt. Water Pt. Water Pt. Water Pt. Water Pt. Water Page 6-3 Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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) 1. Location 2. Critical Age 3. Critical Organ 4. Gas Contribution

% 5. Liquid Contribution

% B. Maximum Total Body Dose 1. Location 2. Critical Age 3. Gas non-NG Contribution

% 4. Gas Contribution

% 5. Liquid Contribution

% 3.82E-01 mREM 1.0 miles SW CHILD BONE 8.26% 91.74% 2.74E-01 mREM 1.0 miles SW CHILD 45.73% 0.24% 54.03% Direct and air-scatter radiation dose contributions from the onsite ISFSI have been determined from 10 CFR 72.212 Evaluation Report for Phase VII 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 7 mrem/yr. The attached excerpt from the 10 CFR 72.212 Evaluation Report for Phase VII Standardized NUHOMS Cask System Rev. 00 is provided to document the method used to calculate the dose from ISFSI as less than 7 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 8 mrem/yr to the nearest real individual.

This meets the 40 CFR Part 190 requirements of an annual dose commitment to any member of the general public of less than 25 mrem total body or any organ and 75 mrem to the thyroid. Page 6-4 Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 Coe 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 boay, 75 mrem to the thyroid, arid 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 (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-131, 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) due to direct radiation from the Independent Spent FuelStorage 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 O(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 -V and loaded canisters in Phase VI of the Oconee ISFSI, together with the characteristics of assumed "design basis" fuel for unloaded canisters in Phase VI and Phase VII of the Oconee ISFSl 2* Calculation OSC-8675 3 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 Module 5 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 SAS 2 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. Page 6-5 Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 The results of the radiation source term calculation were used as input to Calculation OSC-8706 6 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.

Appropriate software quality controls have been implemented for the computer codes and data used in these analyses (specifically, Calculation DPC 1201.30 00 0010 8 contains the verification and validation for MCNP5, while SDQA-30269-NG0 9 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 23.1-1, summarizes dose rate versus distance, showing a dose rate of 6.84 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 2009 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 0.266 mrem 12). The total dose rate from all operations to the nearest real individual is therefore less than 8 mRem per year. This calculation need not consider any effluent from Phase VII.

• The Phase VII HSMs use the NUHOMS-24PHB DSCs, which are designed as "leak-tight." Per Appendix N, Section N.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-8706 6 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 VII. The Phase VII HSMs use the NUHOMS-24PHB DSCs, which are designed as "leak-tight." Per Appendix N, Section N,11.2.8 of the NUHOMS FSAR 13 , 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 6.4 References Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015

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 unloaded HSMs for Phase VI-VII of the Oconee ISFSI. The assumption of 5 years cooling time applies only to the most recent eight dry storage casks, while the balance of the casks are assumed to have been loaded one year earlier to be consistent with reasonable engineering practice.

3. Calculation OSC-8675, "Oconee ISFSI Spent Fuel Radiation Source Terms," Revision 2. 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-2N21 R6. 6. Calculation OSC-8706, "Oconee Horizontal Storage Module Shielding Evaluation," Revision 1. 7. LA-UR-03-1987, "MCNP -A General Purpose 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 1.4 10. Calculation OSC-8716, "Oconee ISFSI Dose Rate Evaluations," Revision 1. 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. Scott L. Batson to U.S. Nuclear Regulatory Commission, "2014 Annual Radioactive Effluent Release Report (ARERR), April 30, 2014. 13. NUH-003, "Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel," Revision 9. Page 6-7 Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 7 Information to Support the NEI Ground Water Protection Initiative This attachment includes a summary of voluntary reports made in accordance with the NEI Ground Water Protection Initiative and a summary of ground water well sample data. Page 7-1 Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 67 wells in 2015. 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 or semi-annually.

Ground water samples are regularly analyzed for tritium and gamma emitters, with select wells being analyzed for difficult-to-detect radionuclides.

No gamma or difficult-to-detect radionuclides, other than naturally occurring radionuclides, were identified in well samples during 2015. Results from sampling during 2015 confirmed existing knowledge of tritium concentrations in site ground water. Results from sampling during 2015 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 2015. Key to below table. NS pCi/I <MDA 20,000 pCi/I 1,000,000 pCi/I Not scheduled to be sampled, not sampled due to insufficient volume in well, or well inaccessible during outage. -picocuries per liter. -less than minimum detectable activity, typically 250 pCi/I. the Environmental Protection Agency drinking water standard for tritium. This standard applies only to water used for drinking.

the 10 CFR Part 20, Appendix B, Table 2, Column 2, Effluent Concentration Limit for tritium. Page 7-2 Well Name A-1 A-10 A-11 A-12 A-13 A-14 A-17 A-18 A-2 A-9 BG-4 GM-10 GM-10R GM-11 GM-11R GM-12 GM-12R GM-13 GM-13R GM-14 GM-14R GM-15 GM-15R GM-16DDR GM-16DR GM-16R GM-17DR GM-17R GM-18R GM-19 GM-19R GM-1R GM-20 GM-20R GM-21 GM-22 GM-23 GM-24R GM-25R GM"2DR GM-2R GM-3DR GM-3R GM-4 Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Location I Description Tritium Concentration (pCi/I) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr ONS GWPI I A-11CTP1/2 2.13E+02 <MDA <MDA <MDA ONS GWPI I A-10 I CTP 3 4.01E+02 3.23E+02 3.79E+02 4.46E+02 ONS GWPI I A-11 / CTP 3 <MDA <MDA <MDA

<MDA ONS GWPI I A-12 / CTP 3 NS <MDA NS <MDA ONS GWPI I A-13 / CTP 1/2 5.72E+02 5.32E+02 4.74E+02 5.57E+02 ONS GWPI I A-14 / CTP 1/2 <MDA <MDA 2.02E+02 <MDA ONS GWPI I A-17 / CTP 1/2 <MDA <MDA 2.43E+02 1.94E+02 ONS GWPI I A-18 / CTP 1/2 <MDA <MDA <MDA 2.19E+02 ONS GWPI I A-21 CTP 1/2 <MDA <MDA <MDA 2.32E+02 ONS GWPI I A-91CTP1/2

<MDA 2.48E+02 2.15E+02

<MDA ONS GWPI I BG-41 Ball Field <MDA <MDA <MDA

<MDA ONS GWPI I GM-10 I 525 kv Sw Yard NS <MDA NS <MDA ONS GWPI I GM-10R / 525 kv SwYard NS <MDA NS <MDA ONS GWPI I GM-11 I ONS Garage NS <MDA NS <MDA ONS GWPI I GM-11 RI ONS Garage NS <MDA NS <MDA ONS GWPI I GM-12 / E of Access Rd. NS <MDA NS <MDA ONS GWPI I GM-12R I E of Access Rd. NS <MDA NS <MDA ONS GWPI I GM-13 / 525 kv Sw Yard NS <MDA NS <MDA ONS GWPI I GM-13R / 525 kv Sw Yard NS <MDA NS <MDA ONS GWPI I GM-14 / Mnt. Trg. Facility NS <MDA NS <MDA ONS GWPI I GM-14R I Mnt. Trg. Facility NS <MDA NS <MDA ONS GWPI I GM-15 <MDA NS NS 2.02E+02 ONS GWPI I GM-15R <MDA NS NS 2.36E+02 ONS GWPI I GM-16DDR NS 2.07E+02 4.25E+02 3.66E+02 ONS GWPI I GM-16DR 8.61E+03 8.20E+03 7.47E+03 7;04E+03 ONS GWPI I GM-16R NS NS 1.28E+03 1.25E+03 ONS GWPI I GM-17DR 2.51E+03 2.58E+03 2.37E+03 2.30E+03 ONS GWPI I GM-17R 1.14E+03 1.18E+03 1.26E+03 1.15E+03 ONS GWPI I GM-18R 6.30E+03 5.89E+03 5.73E+03 5.39E+03 ONS GWPI I GM-19 1.78E+03 1.84E+03 1.84E+03 1.97E+03 ONS GWPI I GM-19R 5.02E+02 7.15E+02 8.49E+02 7.17E+02 ONS GWPI I GM-1R I CTP 1/2 <MDA <MDA <MDA <MDA ONS GWPI I GM-20 <MDA <MDA <MDA <MDA ONS GWPI I GM-20R <MDA <MDA <MDA <MDA ONS GWPI I GM-21 NS <MDA NS <MDA ONS GWPI I GM-22 NS <MDA NS <MDA ONS GWPI I GM-23 3.47E+02 NS NS 2.07E+02 ONS GWPI I GM-24R NS 1.27E+03 1.24E+03 1.28E+03 ONS GWPI I GM-25R 2.66E+02 3.21E+02 3.84E+02 NS ONS GWPI I GM-2DR I U-1/2 SFP <MDA 2.69E+02 1.97E+02 <MDA ONS GWPI I GM-2R I U-1/2 SFP 3.96E+02 1.04E+03 6.03E+02 6.00E+02 ONS GWPI I GM-3DR I U-3 SFP 3.87E+02 2.97E+02 3.12E+02 2.51E+02 ONS GWPI I GM-3R I U-3 SFP 2.36E+02 3.20E+02 2.87E+02 2.26E+02 ONS GWPI I GM-4 I Rad. Mat. WH 5.23E+02 4.61E+02 4.57E+02 4.82E+02 #of Samples 4 4 4 2 4 4 4 4 4 4 4 2 2 2 2 2 2 2 2 2 2 2 2 3 4 2 4 4 4 4 4 4 4 4 2 2 2 3 3 4 4 4 4 4 Page 7-3 Well Name GM-S GM-SR GM-6 GM-6R GM-7 GM-7DR GM-7R GM-8 GM-8R GM-9 GM-9R MW-11 MW-110 MW-13 MW-16 MW-3 MW-RP01 MW-RP02 MW-RP03 Well Name 011 013 01S Well Name Rw-1<1 l Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Location I Description Tritium Concentration (pCi/I) #of 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples ONS GWPI I GM-S / Rdwst. Bldg. 2.00E+02 2.02E+02 2.30E+02 <MDA 4 ONS GWPI I GM-SR I Rdwst. Bldg. <MDA <MDA

<MDA <MDA 4 ONS GWPI I GM-6 I Outflow to CTP-3 <MDA <MDA NS NS 2 ONS GWPI I GM-6R I Outflow to CTP-3 <MDA <MDA NS NS 2 ONS GWPI I GM-7 I S2S kv Sw Yard 2.30E+02 2.63E+02 4.02E+02 2.70E+02 4 ONS GWPI I GM-7DR <MDA <MDA

<MDA <MDA 4 ONS GWPI I GM-7R I S2S kv Sw Yard 2.SOE+03 2.28E+03 1.91E+03 1.68E+03 4 ONS GWPI I GM-8 I E of U-3 TB 2.48E+02 2.94E+02 2.77E+02

<MDA 4 ONS GWPI I GM-8R I E of U-3 TB <MDA 2.7SE+02 2.11E+02 <MDA 4 ONS GWPI I GM-9 I E of U-2 TB 3.34E+02 3.S4E+02 3.3SE+02 3.21E+02 4 ONS GWPI I GM-9R I E of U-2 TB NS <MDA <MDA <MDA 3 ONS GWPI I MW-11 I Landfill <MDA NS <MDA NS 2 ONS GWPI I MW-11 DI Landfill <MDA NS <MDA NS 2 ONS GWPI I MW-13 /Landfill

<MDA NS <MDA NS 2 ONS GWPI I MW-16 /Landfill

<MDA NS <MDA NS 2 ONS GWPI I MW-3 I Landfill <MDA NS <MDA NS 2 ONS GWPI I MW-RP01 I Landfann/Burial NS <MDA NS NS 1 ONS GWPI I MW-RP02 / Landfann/Burial NS <MDA NS NS 1 ONS GWPI I MW-RP03 I Landfann/Burial NS <MDA NS NS 1 Location I Description Tritium Concentration (pCi/I) #of 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples ONS I 011 I Ball Field <MDA <MDA <MDA <MDA 4 ONS I 013 /WH S <MDA <MDA <MDA

<MDA 4 ONS I 01 S I Brown's Bottom NS <MDA <MDA <MDA 3 Location I Description Tritium Concentration (pCi/I) # of Min Avg Max Samples I S2S kv Sw. Yard I 1.01 E+03 I 1.29E+03 I 1.S9E+03 I 13 (1) Monthly sampling performed for this location during 201S. Page 7-4 Attachment 8 Inoperable Equipment Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 8 Inoperable Equipment This attachment includes an explanation of inoperable instruments related to effluent monitoring in excess of allowed time defined by licensing bases and an explanation of permanent or temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases). / Page 8-1 Attachment 8 Inoperable Equipment Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Oconee Nuclear Station did not experience inoperable equipment relevant to effluent monitoring in excess of SLC limits during 2015. Oconee Nuclear Station did not experience permanent or temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases) during 2015. Page 8-2 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 9 Summary of Changes to the Offsite Dose Calculation Manual Example 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 ODCM Revision 57 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ODCM Revision 57 is provided in entirety on the enclosed CD. 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 57 was approved by the Station Manager on March 7, 2016. Some changes reflected in ODCM Revision 57 were implemented prior to March 7, 2016 under a different change and approval process (e.g., land use census}, and in those cases the implementation date is noted below. Executive Summary -Page 1 Revised bottom statement from: "The methodology and parameters used to assure compliance with the dose limitaions described above shall be used to prepare the radioactive liquid and gaseous effluent reports required by the SCLs and Technical Specifications." to: "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." Revision made to correct typos to "limitaions" and "SCLs" to "limitations" and "SLCs". Section 3 -Page 7 Deleted paragraphs: "In addition to High setpoints, Oconee uses "Alert" setpoints that, in total, are based on 10% of the reporting requirement from 10CFR50.73(a)(2)(viii)(A), which allows 20 times a Xe-133 Effluent Concentration (EC) value of 5.0E-07 µCi/ml at the site boundary.

Accounting for the percent apportioned to each monitored release point, each unit vent Alert setpoint is based on 60% of the Xe-133 EC. The Radwaste Facility and Interim Radwaste Building Alert setpoints are both based on 10% of the Xe-133 EC. The method used to calculate the Alert setpoints is similar to that used to calculate the maximum setpoints except the limit is based on concentration rather than dose rate. The Alert setpoints are approximately 42% of the maximum setpoints.

ONS ODCM revision 43 implemented a change-to remove the residential structure shielding factor of 0.7 from Ki, the total body dose factor due to exposure from a semi-infinite cl9ud of noble gases. KXe-133_ was changed from 206 to 294 mrem/yr per µCi/m3. Since Alert setpoints are based on concentration and not dose rate, but concentration will affect dose, the setpoints are multiplied by a unit-less factor of 206/294 (0. 7) to account for the added risk of exposure." Added paragraph: "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." Previous paragraphs deleted and replaced with new paragraph describing improved Alert setpoint methodology.

Previous methodology was confusing, requiring extensive explanation, and prone to error. New methodology provides clarity and still satisfies previous identified issue from PIP 0-05-965 where general observations from NRC inspectors in Component Design Basis Inspections, not related to the ODCM, resulted in minor violations due to lack of clearly documented figure or equations.

This change does not adversely impact setpoint calculations, as the new setpoints are more conservative.

Page 9-2 Section 3 -Page 8 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Revised RIA-45 and RIA-46 Alert setpoint methodology from: 3.0E-07 206 RJA-451111i1vent,alert

= --------------------X--

4.72E-04 x 6.5E+04 x l.672E...:.o6 x 7.09E-08 294 RJA-45unitvent,alert

= 5.8E+04cpm

+ bkg where: 3.0E-07 = 60% of Xe-133 EC value of 5.0E-07 µCi/ml. 4.72E-04 = Conversion factor, (1 min/60 sec)*(1 m3/35.314 ft3). 206 = Previous KXe-133, total body dose factor due to gamma emissions for Xe-133, in mrem/year per µCi/m3, using shielding factor of 0.7. All other factors were previously defined. to: 1 RJA-45rmitvent, alert = RJA-45unitvent,highX-3 RJA-45unitvent,alert

= 4.66E+04cpm

+ bkg RIA -46unil vent, alert = 1 RIA -46unit vent, high X -3 RIA -46unit vent. alert := 10 cpm + bkg 1/3 = divisor to account for each of 3 unit vent release points, dimensionless.

Previous methodology was confusing, requiring extensive explanation, and prone to error. New methodology provides clarity and still satisfies previous identified issue from PIP 0-05-965 where general observations from NRC inspectors in Component Design Basis Inspections, not related to the ODCM, resulted in minor violations due to lack of clearly documented figure or equations.

This change does not adversely impact setpoint calculations, as the new setpoints are more conservative.

Page 9-3 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Section 3 -Page 9 Revised 4RIA-45high setpoint units from "µCi/ml" to "µCi/cc".

Revised statement of 4RIA-45 units from: "4RIA-45 reads in units of concentration, µCi/ml." to: "4RIA-45 reads in units of concentration, µCi/cc." Revisions made to match units 4RIA-45 displays explicitly.

Revised 4RIA-45 Alert setpoint methodology from: 4RL4-45a!ert 5.0E-08 206 4RJA-45alert

4. 72E-04 x l.297E + 05 x 7.308E -06 294 =:: 7.7E-05 µCi/ml where: 5.0E-08 = 10% of Xe-133 EC value of 5.0E-07 All other factors were previously defined." to: 4 RL4 -45a!ert 1 = 4R/A-4511ighX-3 4RL4-45aiert

=:: 6.33E -05 µCi/cc+ bkg All factors were previously defined." DCi/ml. Previous methodology was confusing, requmng extensive explanation, and prone to error. New* methodology provides clarity and still satisfies previous identified issue from PIP 0-05-965 where general observations from NRC inspectors in Component Design Basis lnspeCtions, not related to the ODCM, resulted in minor violations due to lack of clearly documented figure or equations. This change does not adversely impact setpoint calculations, as the new setpoints are more conservative.

Page 9-4 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Section 3 -Page 10 Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Revised RIA-53 Alert setpoint methodology from: 5.0E-08 206 RIA-53alert

= -------------------X--

4.72E-04 x 1.5E+04 x 7.308E-06 x 3.4E-08 294 RIA-53a!ert

= 2.0E+04cpm

+ bkg to: . 1 RIA -53alert = RIA -53high x -3 RIA -53a1er1 :::: 1.6E + 04 cpm + bkg Previous methodology was confusing, requmng extensive explanation, and prone to error. New methodology provides clarity and still satisfies previous identified issue from PIP 0-05-965 where general observations from NRC inspectors in Component Design Basis Inspections, not related to the ODCM, resulted in minor violations due to lack of clearly documented figure or equations.

This change does not adversely impact setpoint calculations, as the new setpoints are more conservative.

Section 6 -Page 3 Changed Table 6.0-2 Site# 024 Distance from "0.79 miles" to "0.81 miles". Change made to update distance based on new GPS data. Section 6 -Page 4 Changed title of Table 6.0-3 to: "Oconee 2015 Land Use Census Results." Land use census dates were changed to reflect 2015 census dates. The 2015 land use census was performed May 19-20, 2015, and the results were certified and made available for use 011 June 4, 2015. No changes were required from the 2015 land use census. Reformatted notes into table. Change made for clarity. Section 6 -Page 7 Changed title of Figure 6.0-3 to "ONS 2015 Land Use Census Map." Figure 6.0-3 was regenerated using ESRI ArcGIS Version 9.3.1 software by Orbis, Incorporated, Charlotte, NC. ' Page 9-5 __J Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radiological Effluent Controls (SLC 16.11) The Oconee Nuclear Station Radiological Effluent Controls are contained in SLC 16.11 as follows: Page 9-6 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 2-5 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 would exceed 0.18 mrem to the total body or 0.6 mrem to any organ. 16.11.1-1 03115111 I Page 9-7

• Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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. APPLICABILITY:

At all times ACTIONS CONDITION A. Concentration of A.1 radioactive material released in liquid effluents to Unrestricted Areas exceeds the limits specified in Commitment

a. REQUIRED ACTION Restore concentration to within the limit. 16.11.1-2 COMPLETION TIME Immediately 0311s111 I Page 9-8 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION B. Calculated dose from the release of radioactive materials in liquid effluents exceeds any of the limits in Commitment

b. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 REQUIRED ACTION B.1 -------------NOTE--------------

Not required during unusual operating conditions that result in activation of the Oconee Emergency Plan. Submit report to the regional NRG Office which includes the following:

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 40 CFR 141. 16.11.1-3 Radioactive Liquid Effluents 16.11.1 COMPLETION TIME 30 days from the end of the quarter during which the release occurred 0311 s111 I Page 9-9 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 REQUIRED ACTION Radioactive Liquid Effluents 16.11.1 COMPLETION TIME c. Radioactive liquid waste is discharged without treatment and in excess of the specified limit. C.1 Submit report to the 30 days SURVEILLANCE REQUIREMENTS regional NRC Office which includes the following:

a. Cause of equipment or subsystem inoperability.

b. Corrective action to restore equipment and prevent recurrence.

SURVEILLANCE SR 16.11.1.1 N/A 16.11.1-4 N/A FREQUENCY 0311 s111 I Page 9-10 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual BASES Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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) was 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 requirements contained in 10 CFR 50.36a 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 10 CFR 20.106 which references ApP.,endix 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 mrem/year 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 141and40 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 area_s 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, App-endix 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 03115111 I Page 9-11 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual

REFERENCES:

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015

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 Radioactive Liquid Effluents 16.11.1 03115111 I Page 9-12 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual *Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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

[Figure 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 mrem/yr 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 ::::;; 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

30 mrad for beta radiation ii. During any calendar year

:::;; 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 9-13 APPLICABILITY:

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 the projected gaseous 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. At all times 16.11.2-2 03/27/99 Page 9-14 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual ACTIONS CONDITION A. Dose rate exceeds the limits specified in Commitment

a. B. Calculated dose exceeds specified limits. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Gaseous Effluents 16.11.2 REQUIRED ACTION A.1 Restore release rate to within limits. B.1 Submit report to the regional NRC Office which includes the following:

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 COMPLETION TIME Immediately 30 days from the end of the quarter during which the release occurred 01131100 I Page 9-15 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION C. Radioactive gaseous Oconee Nuclear Station,Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 REQUIRED ACTION C.1 Submit a report to the Radioactive Gaseous Effluents 16.11.2 COMPLETION TIME 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 SR 16.11.2.1 N/A 16.11.2-4 N/A FREQUENCY 03/27/99 Page 9-16 BASES Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Gaseous Effluents 16.11.2 The basic requirements for Selected Licensee Commitments concerning effluent from nuclear power reactors are stated in IOCFR50.36.

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 IOCFR20.1302).

The _ requirements contained in IOCFR50.36a 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 IOCFR20.106

• 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 IOCFR50.36a 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 IOCFR50 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 mrem/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 mrem/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 low as 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 llD of Appendix I to 1 O CFR Part 50. 16.11.2-5 01131100 I Page 9-17 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual

REFERENCES:

1 10 CFR Part 20, Appendix 8. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015

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 Radioactive Gaseous Effluents 16.11.2 01131100 I Page 9-18 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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.

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N 0 TE------------------------------------------

Co rrectio n 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 A Alarm/trip setpoint less A.1 conservative than required for one or more effluent OR monitoring instrument channels.

A.2 REQUIRED ACTION Declare channel inoperable.

Suspend release of effluent monitored by the channel. 16.11.3-1 COMPLETION TIME Immediately Immediately 111201oa I Page 9-19 B. C. D. Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION One or more required liquid effluent monitoring instrument channels inoperable.

One or more required gaseous effluent monitoring instrument channels inoperable.

Required Action and associated Completion Time of Required Action B.2 or C.2 not met. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION B.1 Enter the Condition referenced in Table 16.11.3-1 for the function.

AND B.2 Restore the instrument(s) to OPERABLE status. C.1 Enter the Condition referenced in Table 16.11.3-2 for the function.

AND C.2 Restore the instrument(s) to OPERABLE status. D.1 Explain in next Annual Radiological Effluent Release Report why inoperability was not corrected in a timely manner. 16.11.3-2 COMPLETION TIME Immediately 30 days Immediately 30 days April 30 of following calendar year 111201oa I Page 9-20 E. F. Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION As required by Required Action 8.1 and referenced in Table 1 S.11.3-1. (RIA-33) As required by Required Action B.1 and referenced in Table 16.11.3-1. (RIA-54) Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION COMPLETION TIME E.1.1 Analyze two Prior to initiating independent samples subsequent release in accordance with 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.1 Suspend release of Immediately radioactive effluents by this pathway. OR 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 111201oa I Page 9-21 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION G. As required by Required Action 8.1 and referenced in Table 16.11.3-1. (Liquid Radwaste Effluent Line Flow Rate Monitor) Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION -----------------N 0 TE------------------

N ot required during short, controlled outages of liquid effluent monitoring 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. G.1 OR G.2 Suspend release of radioactive effluents by this pathway. Estimate flow rate during actual releases.

16.11.3-4 COMPLETION TIME Immediately Immediately Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter 111201os I Page 9-22 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION H. As required by Required Action B.1 and referenced in Table 16.11.3-1. (RIA-35, #3 Chemical Treatment Pond Composite Sampler and Sampler Flow Monitor (Turbine Building Sumps Effluent))

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION -----------------N 0 TE------------------

N ot required during short, controlled outages of liquid effluent monitoring 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. H.1 H.2 Suspend release of . radioactive effluents by this pathway. *Collect and analyze grab samples for gross radioactivity (beta and/or gamma) at a lower limit of detection of at least 10-7 µCi/ml. 16.11.3-5 COMPLETION TIME Immediately Immediately Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter 111201os I Page 9-23 I. Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION As required by Required Action C.1 and referenced in Table 16.11.3-2 for effluent releases from waste gas tanks (RIA-37, RIA-38) or containment purges (RIA-45).

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION ----------------NOTE------------------

N ot required during short, controlled outages of gaseous effluent monitoring 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. 1.1.1 1.1.2 1.1.3 OR 1.2 Analyze two independent samples. Conduct two independent data entry checks for release rate calculations Conduct two independent valve lineups of the effluent pathway. Suspend release of radioactive effluents by this pathway. 16.11.3-6 COMPLETION TIME Prior to initiating subsequent release Prior to initiating subsequent release Prior to initiating subsequent release Immediately 11120108 I Page 9-24 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION J. As required by Required Action C.1 and referenced in Table 16.11.3-2. (Effluent Flow Rate Monitor (Unit Vent, Containment Purge, Interim Radwaste Exhaust, Hot Machine Shop Exhaust, Radwaste Facility Exhaust, Waste Gas Discharge))

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12131/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION ---------------NOTE--------------------

N ot required during short, controlled outages of gaseous effluent monitoring 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. J.1 OR .J.2 Suspend release of radioactive effluents by this pathway. Estimate flow rate 16.11.3-7 COMPLETION TIME Immediately Immediately Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter 111201oa I Page 9-25 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION K. As required by Required Action C.1 and referenced in Table 16.11.3-2. (RIA-45, RIA-53, 4RIA-45) Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION -----------------NOTE------------------

N ot required during short, controlled outages of gaseous effluent monitoring 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 K.2.1 Suspend release of radioactive effluents by this pathway. Collect grab sample. K.2.2 Analyze grab samples for gross activity (beta and/or gamma). 16.11.3-8 COMPLETION TIME Immediately Immediately Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 24 hours from collection of sample 11120108 I Page 9-26 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION L. As required by Required Action C.1 and referenced in Table 16.11.3-2. (Unit Vent Monitoring Iodine Sampler, Unit Vent Monitoring Particulate Sampler, Interim Radwaste Building Ventilation Monitoring Iodine Sampler, Interim Radwaste Building Ventilation Monitoring Particulate Sampler, Hot Machine Shop Iodine Sampler, Hot Machine Shop Particulate Sampler, Radwaste Facility Iodine Sampler, Radwaste.

Facility Particulate Sampler) Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION -----------------NOTE------------------

N ot required during short, controlled outages of gaseous effluent monitoring 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. L.1 Suspend release of *radioactive effluents by this pathway. OR L.2.1 -----------NOTE-----------.

The collection time of each sample shall not exceed 7 days. -------------------------------

Collect samples continuously using auxiliary sampling equipment.

AND L.2.2 Analyze each sample. 16.11.3-9 COMPLETION TIME Immediately Immediately 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 11120108 I Page 9-27 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual *coNDITION M. As required by Required Action C.1 and referenced in Table 16.11.3-2 for effluent from ventilation system or condenser air ejectors: (RIA-40) Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 REQUIRED ACTION COMPLETION TIME -----------------N 0 TE------------------

N ot required during short, controlled outages of gaseous effluent monitoring 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. M.1 Continuously monitor Immediately release through the unit OR M.2 vent. Suspend release of radioactive effluents by this pathway. M.3.1 Collect grab sample. Immediately 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 111201os I Page 9-28 1-Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE REQUIREMENTS SR 16.11.3.1 SR 16.11.3.2 SR 16.11.3.3 SR 16.11.3.4 SR 16.11.3.5 SURVEILLANCE

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NOTE----------------------------

The Channel Response check shall consist of verifying indications during periods of r_elease.

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. ------------------------N 0 TE----------------------------

T he 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 relea$es are made. Perform Channel Response Check. Perform Source Check. Perform Source Check. Perform Source Check. 16.11.3-11 FREQUENCY During each release via this pathway 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours 31 days 92 days 111201os I Page 9-29 SR 16.11.3.6 SR 16.11.3.7 SR 16.11.3.8 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE

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N 0 TE----------------------------

Th e 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. ------------------------N 0 TE----------------------------

T he 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). Perform CHANNEL FUNCTIONAL TEST. Perform CHANNEL FUNCTIONAL TEST. 16.11.3-12 FREQUENCY 92 days 92 days 92 days 11120108 I Page 9-30 SR 16.11.3.9 SR 16.11.3.10 SR 16.11.3.11 SR 16.11.3.12 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE

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N 0 TE---------------------------

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 su.bstitute previously established calibration procedures for these requirements.)

Perform CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

Perform leak test. Perform Source Check. 16.11.3-13 FREQUENCY 12 months 12 months When cylinder gates or wicket gates are reworked 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 111201oa I Page 9-31

1. 2. 3. Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS INSTRUMENT Monitors Providing Automatic Termination of Release a. Liquid Radwaste Effluent Line Monitor, RIA-33 b. Turbine Building Sump, RIA-54 Monitors not Providing Automatic Termination of Release Low Pressure Service Water RIA-35 Flow Rate Measuring Devices a. Liquid Radwaste Effluent Line Flow Rate Monitor (OLW CR0725 cir OLW SS0920) b. Liquid Radwaste Effluent Line Minimum Flow Device c. Turbine Building Sump Minimum Flow Device d. Low Pressure Service Water Minimum Flow Device MINIMUM OPERABLE CHANNELS NA NA NA APPLICABILITY At all times At all times At all times At all times NA NA NA 16.11.3-14 SURVEILLANCE REQUIREMENTS SR 16.11.3.1 SR 16.11.3.3 SR 16.11.3.6 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 SR 16.11.3.1 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.10 CONDITION REFERENCED FROM REQUIRED ACTION B.1 E F H G NA NA NA 111201oa I Page 9-32 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS INSTRUMENT

e. Keowee Hydroelectric Tailrace Discharge<*>

4. Continuous Composite Sampler #3 Chemical Treatment Pond Composite Sampler and Sampler Flow Monitor (Turbine Building Sumps Effluent)

MINIMUM OPERABLE CHANNELS NA APPLICABILITY NA At all times SURVEILLANCE REQUIREMENTS SR 16.11.3.11 SR 16.11.3.2 SR 16.11.3.10 CONDITION REFERENCED FROM REQUIRED ACTION B.1 NA H (a) Flow is determined from the number of hydro units operating.

If no hydro units are operating, leakage flow will be assumed to be 38 cfs based on historical data. 16.11.3-15 111201oa I Page 9-33 _J

1. 2. Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM OPERABLE CHANNELS (PER RELEASE SURVEILLANCE INSTRUMENT PATH) APPLICABILITY REQUIREMENTS Unit Vent Monitoring System a. Noble Gas Activity At All Times SR 16.11.3.2 Monitor Providing Alarm SR 16.11.3.4 and Automatic SR 16.11.3.7 Termination of SR 16.11.3.9 Containment Purge Release (RIA-45 -Purge Isolation Function)

b. Noble Gas Activity At all times SR 16.11.3.2 Monitor Providing Alarm. SR 16.11.3.4 (RIA-45 -Vent Stack SR 16.11.3.7 Monitor Function)

SR 16.11.3.9

c. Iodine Sampler At All Times SR 16.11.3.2

d. Particulate Sampler At All Times SR 16.11.3.2

e. Effluent Flow Rate At All Times SR 16.11.3.2 Monitor (Unit Vert Flow) SR 16.11.3.10 (MSC CR0001) f. Sampler Flow Rate At All Times SR 16.11.3.2 Monitor <*l (Annunciator)

SR 16.11.3.10

g. Effluent Flow Rate During Containment SR 16.11.3.2 . Monitor (Containment Purge Operation SR 16.11.3.10 Purge)(MSC CR0001) h. CSAE Off Gas Monitor During Operation SR 16.11.3.2 (RIA-40) ofCSAE SR 16.11.3.5 SR 16.11.3.8 SR 16.11.3.9 Interim Radwaste Building Ventilation Monitoring System a. Noble Gas Activity At All Times SR 16.11.3.2 Monitor (RIA -53) SR 16.11.3.4 SR 16.11.3. 7 SR 16.11.3.9

b. Iodine Sampler At All Times SR 16.11.3.2

c. Particulate Sampler At All Times SR 16.11.3.2

d. Effluent Flow Rate At All Times SR 16.11.3.2 Monitor (Interim SR 16.11.3.10 Radwaste Exhaust) (GWD FT0082) e. Sampler Flow Rate At All Times SR 16.11.3.2 Monitor<*l (Annunciator)

SR 16.11.3.10 16.11.3-16 CONDITION REFERENCED FROM REQUIRED ACTION C.1 K L L J NA J M K L L J NA 111201os I Page 9-34 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED FROM MINIMUM OPERABLE CHANNELS (PER RELEASE PATH) SURVEILLANCE REQUIRED INSTRUMENT APPLICABILITY REQUIREMENTS ACTION C.1 3. Hot Machine Shop Ventilation Sampling System a. Iodine Sampler b. Particulate Sampler c. Effluent Flow Rate Monitor (Hot Machine Shop Exhaust) (Totalizer)

d. Sampler Flow Rate Monitor <*l (Annunciator)

4. Radwaste Facility Ventilation Monitoring System *5. a. Noble Gas Activity Monitor (4-RIA-45)

b. Iodine Sampler c. Particulate Sampler d. Effluent Flow Rate Monitor (Radwaste Facility Exhaust) (OVS CR2060) e. Sampler Flow Rate Monitor <*l (Annunciator)

Waste Gas Holdup Tanks a. Noble Gas Activity Monitor -Providing Alarm and Automatic Termination of Release (RIA-37 ,-38)b b. Effluent Flow Rate Monitor (Waste Gas Discharge Flow) (MSC CR0001) At All Times At All Times At All Times At All Times At All Times At All Times At All Times At All Times At All Times During Waste Gas Holdup Tank Releases SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.2 SR 16.11.3.10 SR 16.11.3.1 SR 16.11.3.6 SR 16.11.3.9 SR 16.11.3.12 During Waste Gas SR 16.11.3.1 Holdup Tank Releases SR 16.11.3.10 (a)Alarms indicating low flow 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 L L J NA K L L J NA J 111201os I Page 9-35

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*--Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual BASES Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 with the requirements of General Design Criteria 60, 63, and 64.of Appendix A to 10 CFR Part 50. The ra<;fioactive 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 with 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 between 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 deenied 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 9-36 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11 .4 Operational Safety Review Operational Safety Review 16.11.4 COMMITMENT Required sampling should be performed as detailed in Table 16.11.4-1.

APPLICABILITY:

At all times ACTIONS CONDITION A. NA REQUIRED ACTION A.1 NA SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 16.11.4.1 N/A 16.11.4-1 COMPLETION TIME NA FREQUENCY N/A 06130114 I Page 9-37 Item 1. Decant Monitor Tank, Turbine Building Sump Monitor Tanks, Waste and Recycle Monitor Tanks 2. Unit Vent Sampling (Includes Waste Gas Decay Tanks, Reactor Building Purges, Auxiliary Building Ventilation, Spent Fuel Pool Ventilation, Air Ejectors)

3. Waste Gas Decay Tank 4. Reactor Building Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Table 16.11.4-1 Operational Safety Review 16.11.4 Minimum Sampling Frequency and Analysis Program Check Frequency Lower Limit of Detection(b) of Lab Analysis for Waste a. Principal Gamma Emitters<<>

including Dissolved Noble Gases b. Radiochemical Analysis Sr-89 and Sr-90 c. Tritium d. Gross Alpha Activity a. Iodine Spectrum(*>

b. Particulates(*)

i. Ce-144 & Mo-99 ii. Other Principle Gamma Emitters (d) iii. Gross Alpha Activity iv. Radiochemical Analysis Sr-89, Sr-90 c. Gases by Principle Gamma Emitters<dl

d. Tritium a. Principle Gamma Emitters(dl

b. Tritium a. Principle Gamma Emitters(d)

b. Tritium Composite Grab Sample prior to release of each batch(hl Quarterly from all composited batches(Q Monthly Composite Monthly Composite Continuous monitor, weekly sample<*>

Weekly Composite(*)

Weekly Composite(e>

Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample Grab Sample prior to release of each batch Grab Sample prior to release of each batch Grab sample each purge Grab sample each purge 16.11.4-2

<5E-06 µCi/ml (Ce-144) <5E-07 µCi/ml (Other Gamma Nuclides)

<1 E-05 µCi/ml (Dissolved Gases) <1E-06 µCi/ml (1-131) <5E-08 µCi/ml <1 E-05 µCi/ml <1 E-07 µCi/ml <1E-10 µCi/cc (l-133)ID

<1E-12 µCi/cc (l-131)(1)

<5E-1 O µCi/ccO>O<> < 1 E-11 µCi/ccOl <1 E-11 µCi/cc <1 E-11 µCi/cc <1 E-04 µCi/cc <1E-06 µCi/cc <1E-04 µCi/cc (gases) <1E-10 µCi/cc (particulates and iodines) <5E-09 µCi/cc (Ce-144 and Mo-99) <1 E-06 µCi/cc . <1 E-04 µCi/cc (gases) <1E-10 µCi/cc (particulates and iodines) <5E-09 µCi/cc (Ce-144 and Mo-99) <1 E-06 µCi/cc 06/30/14 Page 9-38 Item 5. Not Used 6. #3 Chemical Treatment Pond EffiuentCQ Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Table 16.11.4-1 Operational Safety Review 16.11.4 Minimum Sampling Frequency and Analysis Program Check a. Principle Gamma Emitters Cc> b. 1-131 c. Tritium d. Gross Alpha Activity e. Sr-89 & Sr-go f. Dissolved and Entrained gases (Gamma Emitters)

Frequency Lower Limit of Detection(bJ of Lab Analysis for Waste Weekly Continuous Composite(gl

<5E-07 µCi/ml Weekly Continuous Composite(gJ

<1E-06 µCi/ml Monthly Continuous

<1 E-05 µCi/ml Composite<gJ Monthly Continuous Composite(gJ

<1E-07 µCi/ml Quarterly Continuous Composite<gJ

• <5E-08 µCi/ml Monthly Grab <1E-05 µCi/ml 7. Radwaste Facility a. Iodine Spectrum(*)

Continuous monitor, weekly sample<*>

(1-133) < 1 E-og µCi/cc (1-131) <1E-11 µCi/cc Ventilation

b. Particulate<*>

i. ii. iii. iv. c. d. Ce-144 and gg Other Principle Gamma Emitters<d>

Gross Alpha Activity Radiochemical Analysis Sr-89, Sr-go Gases by Principle Gamma<dJ Emitters Tritium Weekly Composite<*>

Weekly Composite<*>

Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample 16.11.4-3

<5E-10 µCi/cc© <1 E-11 µCi/ccm <1 E-11 µCi/cc <1 E-11 µCi/cc <1E-04 µCi/cc <1E-06 µCi/cc 06/30/14 Page 9-3g Item 8. Hot Machine Shop Ventilation

9. Interim Radwaste Building Ventilation Check Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Table 16.11.4-1 Operational Safety Review 16.11.4 Minimum Sampling Frequency and Analysis Program Frequency Lower Limit of DetectionCb>

of Lab Analysis for Waste a. Iodine Spectrum Weekly SampleCe>

(1-133) <1 E-10 µCi/ccOl (l-131) <1E-12 µCi/ccOl b. Particulate

i. ii. iii. iv. c. d. a. b. i. ii. iii. iv. c. d. Ce-144 and Mo-99 Other Principle Gamma Emitters (d) Gross Alpha Activity Radiochemical Analysis Sr-89, Sr-90 Gases by Principle Gamma Emitters Tritium Iodine Spectrum Particulate Ce-144 and Mo-99 Other Principle Gamma Emitters Cd> Gross Alpha *Activity Radiochemical Analysis Sr-89, Sr-90 Gases by Principle Gamma Cd) Emitters Tritium Weekly Composite<*>

Weekly Composite<*>

Monthly, using composite samples of one week Quarterly Composite NA NA Weekly sample<*>

Weekly Composite<*>

Weekly Composite<*>

Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample 16.11.4-4

<SE-10 µCi/ccOlCkl < 1 E-11 µCi/ccOl <1 E-11 µCi/cc <1E-11 µCi/cc NA NA (l-133) <1E-10 µCi/ccOl (l-131) <1E-12 µCi/ccm <SE-10 µCi/cc 01 <1 E-11 µCi/cc 01 <1 E-11 µCi/cc <1 E-11 µCi/cc <1E-04 µCi/cc <1 E-06 µCi/cc 06/30/14 Page 9-40 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Operational Safety Review 16.11.4 (a) Samples shall be changed at least once per 7 days 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 /> after changing, or after 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 RA TED 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 concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation)

LLD= (2.71 I Tl + 4.65 Sb Where: E x V x 2.22E06 x Y x exp (-Mt) LLD is the "a priori" lower limit of detection as defined above (as micro Curies per unit mass or volume), sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22E06 is the number of disintegrations per minute per micro Curie, Y is the fractional radiochemical yield (when applicable), A. is the radioactive decay constant for the particular nuclide !it 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 time 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 time in minutes Typical values of E, V, Y and !it should be used in the calculation.

It 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 fact) limit for a particular measurement. (c) The principal gamma emitters for which the LLD control applies include the following 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 of 5E-06 µCi/ml. This list does not mean that only these nuclides are to 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 to 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 the sample flow rate to the sampled stream flow 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. (f) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

16.11.4-5 06/30/14 Page 9-41 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 to sampling for analysis, each batch shall be isolated, and then thoroughly mixed, to assure representative sampling. (i) A continuous release is the discharge of liquid 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 /> after changing (on or after removal from sampler).

U) 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. 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). (k) Ce-144 and Mo-99 LLD as approved by NRG SER dated January 16, .1984 (Reference 1). 16.11.4-6 06/30/14 Page 9-42 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Operational Safety Review 16.11.4 BASES N/A

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 9-43 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 accordance 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 wet solid wastes and must adequately verify that the final product of solidification or dewatering meets all applicable Federal, State and disposal site requirements.

APPLICABILITY:

At all times 16.11.5-1 10130102 I Page 9-44 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual ACTIONS CONDITION A Applicable regulatory requirements for solidified or dewatered wastes are not satisfied.

B. A solidification test as described in the PCP fails to verify Solidification.

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 REQUIRED ACTION A.1 Suspend shipments of defectively packaged solid radioactive wastes from the site. AND A.2 Initiate action to correct PCP, procedures, or solid waste equipment as necessary to prevent recurrence.

B.1 Suspend solidification of the batch under test and follow PCP guidance for test failures until solidification of the batch is verified by subsequent tests. AND B.2 The PCP shall be modified as required to assure Solidification of subsequent batches of waste. 16.11.5-2 Solid Radioactive Waste 16.11.5 COMPLETION TIME Immediately Prior to next shipment for disposal of solidified or dewatered wastes Immediately Prior to next solidification for shipment of waste for disposal at a 1 O CFR 61 disposal site 10130102 I Page 9-45 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION C. With solidification or dewatering for disposal not performed in accordance with the PCP. D. With the solid waste equipment incapable of meeting commitment or not in service. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 REQUIRED ACTION C.1 Reprocess or repackage the waste in accordance with PCP requirements.

OR 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.1 Restore the equipment to OPERABLE status or provide for alternative capability to process wastes as necessary to satisfy all applicable disposal requirements.

SURVEILLANCE REQUIREMENTS SR 16.11.5.1 SURVEILLANCE The Process Control Program shall be used to verify the solidification of at least one representative test specimen from at least 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 Solid Radioactive Waste 16.11.5 COMPLETION TIME Prior to shipment for disposal of the inadequately processed waste that requires solidification or dewatering In a time frame that supports the commitment FREQUENCY Every tenth batch of each type of radioactive waste to be solidified.

10130102 I Page 9-46 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Solid Radioactive Waste 16.11.5 BASES 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 1 OCFR61 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 Requirements 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 9-47 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radiological Environmental Monitoring 16.11.6 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.6 Radiological Environmental Monitoring COMMITMENT APPLICABILITY:

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 D/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---------------------------------------------

lf 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 were obtained and added to the environmental monitoring program, if available.

These new locations will be identified in the Annual Radioactive Effluent Release Report. At all times 16.11.6-1 111a113 I Page 9-48 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual ACTIONS CONDITION A. Radiological environmental monitoring program is not conducted as required.

8. Land use census identifies a Location which yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than a location from which samples are currently being obtained.

Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radiological Environmental Monitoring 16.11.6 REQUIRED ACTION COMPLETION TIME A.1 Submit a description of May 15 of following the reason for not calendar year conducting the program as required and plans to prevent a recurrence shall be included in the Annual Radiological Environmental Operating Report. 8.1 -----------N 0 TE-----------

The sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

---

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 111a113 I Page 9-49 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radiological Environmental Monitoring 16.11.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME c. I nterlaboratory 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 16.11.1or16.11.2.

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 111a113 I Page 9-50 Exposure Pathway and/or Sample 1. AIRBORNE Radioiodine and Particulates

2. DIRECT RADIATION

3. WATERBORNE

a. Surface b. Drinking c. Sediment from Shoreline Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Table 16.11.6-1 Radiological Environmental Monitoring 16.11.6 Radiological Environmental Monitoring Program Number of Sample Locations (b) 5 40 2 3 2 Sampling and Collection Frequency (d) Continuous sampler operation with sample collection weekly, or more frequently if required by dust loading. Quarterly.

Composite (a) sample over a 1-month period. Composite (a) sample over a 1-month period. Semiannually.

16.11.6-4 Time and Frequency of Analysis Radioiodine canister:

1-131 analysis weekly. Particulate sampler: Gross beta radioactivity analysis following filter change; and gamma isotopic analysis of composite (by location) quarterly. (c) Gamma dose quarterly.

Gamma isotopic analysis monthly. Composite for tritium analysis quarterly.

Composite for gross beta and gamma isotopic analyses monthly. Composite for tritium analysis quarterly.

Gamma isotopic analysis semiannually.

111a113 I Page 9-51 Exposure Pathway and/or Sample 4. INGESTION

a. Milk b. Fish c. Broad-leaf Vegetation Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Table 16.11.6-1 Radiological Environmental Monitoring 16.11.6 Radiological Environmental Monitoring Program Number of Sample Locations (b) 4(e) 2 2 Sampling and Collection Frequency (d) Semimonthly when animals are on pasture; monthly at other times. Semiannually.

One sample each commercially and recreationally important species. Monthly. Time and Frequency of Analysis Gamma isotopic and 1-131 analysis semimonthly when animals are on pasture; monthly at other times. Gamma isotopic analysis semiannually on edible portion. Gamma isotopic analysis monthly. (a) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 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 complete 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 111a113 I Page 9-52 Analysis Gross Beta H3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Table 16.11.6-2 Radiological Environmental Monitoring 16.11.6 Maximum Values for the Lower Limits of Detection (LLD) (a) (c) Water (pCi/I) 4 2,000 15 30 15 15 30 15 15 15(b) 15 18 15 15 Airborne Particulate or Gases Ci/m 3 1E-02 7E-02 5E-02 6E-02 Fish (pCi/kg, wet) 130 260 130 130 260 130 150 Milk (pCi/I) 15 18 60 15 Broad-leaf Vegetation (pCi/kg, wet) 60 60 80 Sediment (pCi/kg, dry) 150 180 (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 with 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation):

LLD= (2.71 I Tl + 4.65 Sb E xVx 2.22 xY x exp (-Mt) Where: LLD is the lower 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 111a113 I Page 9-53 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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)

/.. is the radioactive decay constant for the particular radionuclide

!>.. t is the elapsed time between sample collection (or end of the sample collection period) and time of counting Tis the sample counting time 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 perfonmed 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 Radiological 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 pCifliter of 1-131 in drinking water. For low level analyses of 1-131 an LLD of 1 pCifliter will be achieved. (c) other peaks which are measurable and identifiable, together with the radionuclides in Table 16.11.6-2, shall be identified and reported.

16.11.6-7 111a113 I Page 9-54 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Table 16.11.6-3 Radiological Environmental Monitoring 16.11.6 Reporting Levels for Radioactivity Concentrations in Environmental Samples (c) (d) Airborne Broad-leaf Water Particulate or Fish Milk Analysis Gases Vegetation (pCi/I) (pCi/kg, wet) (pCi/I) (pCi/kg, wet) Ci/m 3 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 1 E02 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 equal to or greater than the calendar year limits of SLC 16.11.1 or 16.11.2. 16.11.6-8 1118113 I Page 9-55 BASES Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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.

Following 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 lower limits of detection correspond to less than 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 requirementsfor 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 111a113 I Page 9-56 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 required 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 111a113 I Page 9-57 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11. 7 Dose Calculations Dose Calculations 16.11.7 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 A Calculated doses from A.1 the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of SLC 16.11.1.b, SLC 16.11.2.b.1, or SLC 16.11.2.b.2 REQUIRED ACTION Determine by calculation, including direct radiation contributions from the reactor units and from outside storage tanks, whether the limits of Commitment 16.11.7 have been exceeded.

16.11.7-1 COMPLETION TIME None 01131100 I Page 9-58 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION B. Calculated dose exceeds limits of Commitment 16.11.7. Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 REQUIRED ACTION -------------------NOTE----------------

Th is Special Report, as defined 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 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 Dose Calculations 16.11.7 COMPLETION TIME 30 days 01131100 I Page 9-59 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Dose Calculations 16.11.7 CONDITION REQUIRED ACTION COMPLETION TIME C. Calculated dose C.1 -----------NOTE-----------

exceeds limit of Submittal of the report Commitment 16.11. 7. is considered a timely request, and a variance AND is granted until staff action on the request is Release condition complete.

resulting in violation of -------------------------------

40 CFR 190 not corrected at time of Include a request for a 30 days from exceeding report submittal.

variance in accordance the limit with the provisions of 40 CFR Part 190. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.7.1 SR 16.11.7.2 BASES Determine cumulative dose contributions from 31 days liquid effluents in accordance with Offsite Dose Calculation Manual. 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 9-60 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual

REFERENCES:

1. 10 CFR Part 20. 2. 40 CFR Part 190. Oconee Nuclear Station Units 1, 2, & 3 Period 111/2015-12/31/2015

3. Offsite Dose Calculation Manual. 4. 10 CFR Part 50, Appendix I. 16.11.7-4 Dose Calculations 16.11.7 01131100 I Page 9-61 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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:

At all times. ACTIONS CONDITION A. Individual milk samples A.1 show 1-131 concentrations of 1 0 picocuries per liter or greater. REQUIRED ACTION Submit plan advising the NRC of the proposed action to ensure the plant related annual doses will be within the design objective of 45 mrem/yr to the thyroid of any individual.

16.11.8-1 COMPLETION TIME 7 days 12121109 I Page 9-62 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual CONDITION Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 REQUIRED ACTION Reports 16.11.8 COMPLETION TIME B. Milk samples collected 8.1 Submit a plan advising 30 days over a calendar quarter show 1-131 average concentrations of 4.8 picoCuries per liter or greater SURVEILLANCE REQUIREMENTS the NRG of the proposed action to ensure the plant related annual doses will be within the design objective of 45 mrem/yr to the thyroid of any

• individual.

SURVEILLANCE SR 16.11.8.1 NA BASES Reference applicable commitments.

REFERENCES:

1. 10 CFR Part 20. 2. 40 CFR Part 190. 3. Offsite Dose Calculation Manual. 16.11.8-2 FREQUENCY NA 12121109 I Page 9-63 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 waste 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 9-64 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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:

At all times. 16.11.9-2 03122110 I Page 9-65 ACTIONS CONDITION A. N/A Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 Radioactive Effluent Release Report 16.11.9 REQUIRED ACTION COMPLETION TIME A.1 N/A N/A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.9.1 N/A N/A BASES N/A

REFERENCES:

1. Oconee ITS. 2. Offsite Dose Calculation Manual. 16.11.9-3 03122110 I Page 9-66 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 shall 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 obta_ined as part of the required lnterlaboratory Comparison Program. The lnterlaboratory Comparison 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 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 9-67 ACTIONS CONDITION A. NA Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 Radiological Environmental Operating Report 16.11.10 REQUIRED ACTION COMPLETION TIME A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.10.1 NA NA BASES NA

REFERENCES:

1. Oconee ITS 2. Offsite Dose Calculation Manual 16.11.10-2 os114114 I Page 9-68 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1 /1/2015 -12/3112015 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.11 Iodine Radiation Monitoring Filters Iodine Radiation Monitoring filters 16.11.11 COMMITMENT Assure that the iodine radiation monitoring filters perform their intended function.

APPLICABILITY:

At all times. ACTIONS CONDITION REQUIRED ACTION A NA A.1 NA SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 16.11.11.1 Remove and replace iodine radiation monitoring filters in RIA-44. SR 16.11.11.2 Discard spare iodine radiation monitoring filters. BASES COMPLETION TIME NA FREQUENCY 30 days of operation After 24 months of shelf life. The purpose of this commitment is to assure the reliability of the iodine radiation monitoring charcoal filters.

REFERENCES:

1. Oconee CTS Amendment No. 3/3 SER date July, 1974. 16.11.11-1 03/27/99 Page 9-69

---

*----* -Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 A. The quantity of A.1 Suspend addition of radioactive material to tank. radioactive material in outside temporary storage tank not within *limit. SURVEILLANCE REQUIREMENTS SR 16.11.12.1 SURVEILLANCE Verify the quantity of radioactive material contained in each of the outside temporary tanks is within the limit by analyzing a representative sample of the tanks' contents.

Verify the quantity of radioactive material in each of the outside temporary tanks does not result in exceeding the limit by analyzing a representative sample of radioactive material to be added. 16.11.12-1 COMPLETION TIME Immediately FREQUENCY Within 7 days after addition of radioactive materials to an outside temporary tank Prior to addition of radioactive materials to an outside temporary tank. 04110103 I Page 9-70 BASES *Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 would be less than the limits of 1 OCFR 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 9-71 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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:

At all times. ACTIONS ---------------------------------------------------------NOTE------------------------------------------------------------

Separate Condition Entry is allowed for each tank. CONDITION REQUIRED ACTION A The quantity of A.1 Suspend addition of radioactive material in radioactive material to the Waste Gas Holdup tank. tank not within fimit. AND A.2 Reduce tank contents to within limit. SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 16.11.13.1 BASES Verify quantity of radioactive materials in each tank is within limit. COMPLETION TIME Immediately 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> FREQUENCY 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when tank is 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 9-72 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 UFSAR, Section 15.10 16.11.13-2 03/27/99 Page 9-73 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.14 Explosive Gas Mixture Explosive Gas Mixture 16.11.14 COMMITMENT The concentration of Hydrogen in the Waste Gas Holdup Tanks shall be 3% by volume. APPLICABILITY:

At all times. ACTIONS -------------------------------------------------------------NOTE--------------------------------------------------------

Separate Condition Entry is allowed for each tank. CONDITION REQUIRED ACTION A. Concentration of A.1 Reduce Concentration Hydrogen in Waste of Hydrogen to within Gas Holdup tank is> limit. 3% and by volume. B. Concentration of B.1 Suspend addition of Hydrogen in Waste waste gases to tank. Gas Holdup tank is > 4% by volume. AND B.2 Reduce Concentration of Hydrogen to within limit. 16.11.14-1 COMPLETION TIME 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Immediately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 03/27/99 Page 9-74 Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 SURVEILLANCE REQUIREMENTS SR 16.11.14.1 BASES SURVEILLANCE Verify Hydrogen concentration in Waste Gas Holdup Tank is 3% by volume. Explosive Gas Mixture 16.11.14 FREQUENCY 5 times/week on each 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 9-75 Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 ATTACHMENT 10 Summary of Changes to the Process Control Program This attachment includes a summary of changes to the PCP. l Page 10-1 Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 The Oconee Nuclear Station PCP was not revised in 2015. The most recent revision was provided with the Oconee Nuclear Station 2014 ARERR. Page 10-2 Attachment 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015-12/31/2015 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 1/1/2015-12/31/2015 No major modifications to Oconee Nuclear Station liquid, gaseous, solid, or mobile radioactive waste treatment systems occurred in 2015. Page 11-2 Attachment 12 Errata to a Previous Year's ARERR Example Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 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 Example Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2015 -12/31/2015 There are no changes to a previous year's ARERR. Page 12-2