Text

2017 Annual Radioactive Effluent Release Report (ARERR)
	ML18127A215
Person / Time
Site:	Oconee
Issue date:	04/30/2018
From:	Dills J; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	ONS-2018-024
	Download: ML18127A215 (136)
	v • d • e

ef,DUKE. Johnny R. Dills Plant Manager

~;ENERGY Oconee Nuclear Station Duke Energy ON01VP I 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.6413 f: 864.873.4208 John.Dills@duke-energy.com ONS-2018-024 April 30, 2018 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 2017 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, 2017, through December 31, 2017. No changes were made to the Offsite Dose Calculation Manual (ODCM) during this period, therefore, a copy is not included.

Any questions concerning this report should be directed to Kay Brocklesby at 864-873-6661.

Johnny R. Dills Plant Manager Oconee Nuclear Station*

Attachments ( 12) www.duke-energy.com

U.S. Nuclear Regulatory Commission 2017 Annual Radioactive Effluent Release Report April 30, 2018 Page2 xc (with attachments):

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 Mr. Stephen Koenick, Project Manager (by electronic mail only)

U.S. Nuclear RegulatQry Commission 11555 Rockville Pike Mail Stop OWFN/8F-14 Rockville, MD 20852 I

Ms. Susan E. Jenkins, Manager (by electronic mail only)

Radioactive & Infectious Waste Management SC Department. of Health and Environmental 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. Anuradha Nair Gimmi, Manager Nuclear Response and Emergency Environmental Surveillance Division of Emergency Response S.C. Dept. of Health & Environmental Control 2600 Bull Street Columbia, SC 29201-1708

(~DUKE .

~ ENERGY Oconee Nuclear Station Units 1, 2, and' 3 Annual Radioactive Effluent Release Report January 1, 2017 through December 31, 2017 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 1/1/2017 - 12/31/2017 ATTACHMENT 1 Summary of Gaseous and Liquid Effluents This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.

Page 1-1

Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Gaseous Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases

1. Total Release Ci 3.72E+OO 1.87E+OO 1.40E+OO 6.86E-01 7.68E+OO

2. Avg. Release Rate µCi/sec 4.79E-01 2.38E-01 1.76E-01 8.63E-02 2.44E-01 B. lodine-131

1. Total Release Ci O.OOE+OO O.OOE+OO 5.09E-09 O.OOE+OO 5.09E-09

2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO 6.40E-10 O.OOE+OO 1.61E-10 C. Particulates Half-Life;;: 8 days

1. Total Release Ci p.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 1.33E+01 2.81E+01 3.23E+01 2.82E+01 1.02E+02

2. Avg. Release Rate µCi/sec 1.71E+OO 3.57E+OO 4.06E+OO 3.55E+OO 3.23E+OO E. Carbon-14

1. Total Release Ci 5.90E+OO 6.09~+00 6.01E+OO

5.41E+OO 2.34E+01

2. Avg. Release Rate µCi/sec 7.58E-01 7.75E-01 7.56E-01 6.81 E-01 7.42E-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+OO O.OOE+OO Page 1-2

Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 Gaseous Effluents - Mixed Mode - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases XE-133 Ci 3.70E+OO 1.85E+OO 1.29E+OO 6.14E-01 7.45E+OO Total for Period Ci 3.70E+OO 1.85E+OO 1.29E+OO 6.14E-01 7.45E+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 1.20E+01 2.74E+01 2.70E+01 2.52E+01 9.15E+01 E. Carbon-14 C-14 Ci 1.77E+OO 1.83E+OO 1.80E+OO 1.62E+OO 7.02E+OO F. Gross Alpha Total for Period Ci 0.00E+OO O.OOE+OO O.OOE+O.O O.OOE+OO O.OOE+OO

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

_/

Page 1-3

Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Gaseous Effluents - Mixed Mode Releases - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases AR-41 Ci O.OOE+OO 2.24E-02 3.69E-02 9.85E-03 6.92E-02 KR-85M Ci O.OOE+OO O.OOE+OO 3.48E-04 O.OOE+OO 3.48E-04 KR-88 Ci O.OOE+OO O.OOE+OO 3.51E-04 O.OOE+OO 3.51E-04 XE-131M Ci 5.45E-05 O.OOE+OO 1.24E-04 6.36E-05 2.42E-04 XE-133 Ci 2.28E-02 4.87E-03 5.79E-02 5.96E-02 1.45E-01 XE-133M Ci 3.10E-04 O.OOE+OO 8.35E-04 2.02E-04 1.35E-03 XE-135 Ci 7.66E-04 O.OOE+OO 8.23E-03 1.90E-03 1.09E-02 Total for Period Ci 2.40E-02 2.73E-02 1.05E-01 7.17E-02 2.28E-01

8. Iodines 1-131 Ci 0.00E+OO O.OOE+OO 5.09E-09 O.OOE+OO 5.09E-09 Total for Period Ci O.OOE+OO O.OOE+OO 5.09E-09 O.OOE+OO 5.09E-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 7.28E-03 3.02E-02 4.14E-02 2.93E-02 1.0BE-01 E. Carbon-14 C-14 Ci 4.13E+OO 4.26E+OO 4.21E+OO 3.79E+OO 1.64E+01 F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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

Page 1-4

Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2,, & 3 Period 1/1/2017-12/31/2017 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 0.00E+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 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium H-3 Ci 1.31E+OO 6.89E-01 5.26E+OO 2.43E+OO 9.68E+OO 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 1/1/2017-12/31/2017 Gaseous Effluents - Ground Releases - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

8. 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 1.50E-02 8.55E-03 1.86E-02 5.41 E-01 5.83E-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 1/1/2017 - 12/31/2017 Liquid Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products *

1. Total Release Ci 2.91E-04 1.61 E-04 O.OOE+OO 8.51E-04 1.30E-03

2. Avg. Diluted Cone. µCi/ml 1.13E-13 3.67E-14 O.OOE+OO 4.40E-13 1.20E-13

3. Batch Releases µCi/ml 3.47E-11 1.90E-11 O.OOE+OO 9.95E-11 3.84E-11 B. Tritium

1. Total Release Ci 2.27E+02 2.00E+02 3.76E+02 2.32E+02 1.03E+03

2. Avg. Diluted Cone. µCi/ml 1.09E-07 6.73E-08 1.44E-07 1.38E-07 1.15E-07

3. Batch Releases µCi/ml 2.71E-05 2.36E-05 4.39E-05 2.71E-05 3.0SE-05 C. Dissolved & Entrained Gases

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 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. Batch Releases liters 1.52E+06 9.77E+05 1.33E+06 2.35E+06 6.18E+06

2. Continuous Releases liters 4.68E+08 5.04E+08 4.67E+08 5.29E+08 1.97E+09 F. Volume of Dilution Water

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

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

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

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Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 1.90E-01 1.95E-01 1.68E-01 1.67E-01 7.19E-01 C. Dissolved & Entrained Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+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 1/1/2017-12/31/2017

\

Liquid Effluents - Batch Mode '

Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products Fe-55 Ci Q;QQE+OO 3.0?E-05 O.OOE+OO O.OOE+OO 3.0?E-05 Co-57 Ci O.OOE+OO 1.09E-06 O.OOE+OO O.OOE+OO 1.09E-06 Co-58 Ci 2.91E-04 9.84E-05 O.OOE+OO 8.51E-04 1.24E-03 Co-60 Ci O.OOE+OO 8.96E-06 O.OOE+OO O.OOE+OO 8.96E-06 Ni-63 Ci O.OOE+OO 1.36E-05 O.OOE+OO O.OOE+OO 1.36E-05 Ag-110m Ci O.OOE+OO 8.16E-06 O.OOE+OO O.OOE+OO 8.16E-06 Total for Period Ci 2.91E-04 1.61 E-04 O.OOE+OO 8.51E-04 1.30E-03 B. Tritium H-3 Ci 2.27E+02 2.00E+02 3.76E+02 2.31E+02 1.03E+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 0,00E+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 1/1/2017 - 12/31/2017 ATTACHMENT 2 Supplemental Information This attachment includes supplemental information to the gaseous and liquid effluents report.

Page 2-1

Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 I. Regulaton! Limits - Per Unit A. Noble Gases - Air Dose

1. Calendar Quarter Gamma Dose =5 mRAD

2. Calendar Quarter Beta Dose = 10 mRAD

3. Calendar Year Gamma Dose = 10 mRAD

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

1. Calendar Quarter Total Body Dose = 1.5 mREM

2. Calendar Quarter Organ Dose =5 mREM

3. Calendar Year Total Body Dose =3 mREM

4. Calendar Year Organ Dose = 10 mREM C. Gaseous Effluents - 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 of this attachment.

V. Batch Releases A. Liquid Effluents

1. Total Number of Batch Releases 69

2. Total Time (min) for Batch Releases 1.32E+04

3. Maximum Time (min) for a Batch Release 2.17E+02

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

5. Minimum Time (min) for a Batch Release 1.29E+02

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

1. Total Number of Batch Releases 77

2. Total Time (min) for Batch Releases 8.87E+04

3. Maximum Time (min) for a Batch Release 1.12E+04

4. Average Time (min) for Batch Releases 1.15E+03

5. Minimum Time (min) for a Batch Release 1.00E+OO VI. Abnormal Releases See Attachment 5, Unplanned Offsite Releases.

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Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 2017 ARERR contains estimates of C-14 radioactivity released in 2017, and estimates of public dose resulting from the C-14 effluent.

Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required (Ref. Reg. Guide 1.21, Rev. 2). The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation (Ref. Reg. Guide 1.21, Rev. 2). Many documents provide information related to the magnitude of C-14 in typical effluents from commercial nuclear power plants. Those documents suggest that nominal annual releases of C-14 in gaseous effluents are approximately 5 to 7.3 curies from PWRs (Ref. Reg. Guide 1.21, Rev. 2). A more recent study recommends a higher C-14 gaseous source term scaling factor of approximately 9.0 to 9.8 Ci/GWe-yr for a PWR (Westinghouse) (Ref. EPRI 1021106). For the Oconee Nuclear Station 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 2017 results in a site total C-14 gaseous release estimate to the environment of 2.34E+01 Curies. 70% of the C-14 gaseous effluent is assumed to be from batch releases (e.g. WGDTs), and 30% of C-14 gaseous effluent is assumed to be from continuous releases through the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14",

2004).

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

organic with the remainder being CO 2 (Ref. EPRI TR-105715). For the Oconee Nuclear Station 2017 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 2017 is well below the 10CFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit).

Page 2-3

Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 1/1/2017-12/31/2017 Summary of Changes in Land Use Census Affecting Effluent Dose Calculations The 2017 Land Use Census was performed May 24-25, 2017, and the results were certified and made available for use on November 7, 2017. The following are changes to residences, gardens, and milk animals from the previous year.

Residences The residence in the SSW sector at 1.36 miles was replaced with a residence at 1.34 miles.

The residence in the SW sector at 1.31 miles was replaced with a residence at 1.27 miles.

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

Milk Animals The milk animal (goat) in the E sector at 3.27 miles was no longer present The milk animal (goat) in the E sector at 4.66 miles is no longer being used for human consumption. Owner still does not wish to participate in REMP.

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

Page 2-5

Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 ATTACHMENT 3 Solid Radioactive Waste Disposal This attachment includes a summary of the solid waste shipped off-site for burial and/or disposal, including:

Container volume

Total Curie content

Principal Radionuclides

Source/Type of waste

Solidification agent or absorbent

Type of shipping container

- Number of shipments

Other relevant information as necessary Page 3-1

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

1. Waste from Liquid Systems

a. Dewatered Secondary Resins 3 9 A-U GDP N/A 47.66 2.72E+OO 2 2 A-U Type A N/A 6.81 3.67E+OO

b. Dewatered Primary Resins 2 2 B Type A N/A 6.81 8.93E+01 C Type A N/A 3.41 9.83E+01

c. Evaporator Concentrates None

d. Dewatered Mechanical Filters 2 2 C Type A N/A 6.81 1.04E+01

e. Dewatered Demineralizers None

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

2. Dry Solid Waste

a. Dry Active Waste None (compacted)

b. Dry Active Waste (non-13 25 A-U GDP N/A 661.49 1.02E+OO compacted)

C. Dry Active Waste (brokered) None

d. Irradiated Components None

3. Total Solid Waste 23 41 732.99 2.05E+02 Page 3-2

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

1. Waste from Liquid Systems

a. Dewatered Secondary Resins Mn-54 0.073 Co-57 0.03 Co-58 0.20 Co-60 0.86 Cs-137 0.09 Ni-63 2.05 H-3 94.3 C-14 2.05 Sb-124 0.015 Sb-125 0.12 Zn-65 0.025 Tc-99 0.13 Ag-110m 0.13

b. Dewatered Primary Resins Mn-54 2.80 Co-57 0.47 Co-58 13.36 Co-60 11.09 Cs-137 5.56 Cs-134 0.52 Fe-55 19.51 Fe-59 0.01 Ni-63 37.60 H-3 0.46 C-14 5.15 Nb-95 0.025 Be-7 2.09 Ce-144 0.02 Sb-125 0.25 Zr-95 0.17 Sr-89 0.01 Sr-90 0.05 Zn-65 1.00 Tc-99 0.01 Ni-59 0.021 Ag-110m 0.32 Pu-241 0.02 Cm-243 0.01 Cr-51 0.01 Am-241 0.01 Nb-94 0.04 Sb-124 0.18

c. Evaporator Concentrates N/A N/A Page 3-3

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

d. Dewatered Mechanical Filters Cr-51 3.87 Mn-54 2.33 Co-57 0.46 Co-58 34.38 Co-60 11.12 Cs-137 3.88 Cs-134 1.03 Fe-55 2.57 Fe-59 0.03 Ni-63 7.64 H-3 3.89 C-14 6.27 Nb-95 8.75 Ce-144 1.26 Sb-124 0.05 Sb-125 0.01 Zr-95 8.90 Sr-89 2.57 Sr-90 0.225 Zn-65 1.05

e. Dewatered Demineralizers NIA NIA

f. Solidified (cement) Acids, Oils, Sludge NIA NIA

2. Dry Solid Waste

a. Dry Active Waste (compacted) NIA NIA

b. Dry Active Waste (non-compacted) Cr-51 4.00 Mn-54 0.32 Co-57 0.02 co-58 3.13 Co-60 1.26 Cs-137 0.39 Fe-55 82.82 Fe-59 1.64 Ni-63 4.10 C-14 0.48 Nb-95 1.60 Sb-124 0.05 Sb-125 0.05 Zr-95 0.06 Sr-90 0.01 Ce-144 0.0042 Zn-65 0.01 Nb-94 0.0021 Pu-238 0.001 Pu-239 0.0005 Cm-243 0.0005

c. Dry Active Waste (brokered) NIA NIA

d. Irradiated Components NIA NIA Page 3-4 I

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 ATTACHMENT 4 Meteorological Data This attachment includes a summary of meteorological joint frequency distributions of wind speed, wind direction, and atmospheric stability (hours of occurrence).

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Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Lower Level Wind Hours of Occurrence Stability Speed Sector Class (mis) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 1 1 0 0 0 0 0 0 0 0 0 1.26-1.50 0 0 1 0 0 0 1 0 1 3 0 0 0 0 1 1 1.51-2.00 4 0 3 1 0 0 0 0 1 13 36 20 2 0 2 1 2.01-3.00 0 1 5 15 7 4 0 1 4 48 111 22 2 1 1 0 A

3.01-4.00 0 1 0 7 1 0 0 0 0 8 27 3 3 5 3 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 5 1 3 2 1 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 4 3 1 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 2 0 1 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 0 2 0 0 0 1 0 1.26-1.50 0 0 1 1 0 0 0 0 0 0 8 1 1 1 1 1 1.51-2.00 3 8 6 7 5 2 0 0 6 15 39 21 11 4 1 3 2.01-3.00 2 0 3 15 16 3 1 5 6 66 62 24 5 2 0 2 B

3.01-4.00 0 1 0 6 1 0 0 1 0 14 9 0 3 3 0 0

1.

4.01-5.00 0 0 0 1 0 0 0 0 0 1 3 4 1 1 4 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 1 1 5 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 1 1 4 6 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 1. 1 1 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-2

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Lower Level Wind Hours of Occurrence Stability Speed Sector Class (mis) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1.01-1.25 2 0 1 0 0 0 0 0 0 0 2 0 3 0 1 0 1.26-1.50 5 2 2 0 0 1 0 2 1 3 11 6 2 2 1 2 1.51-2.00 4 5 2 14 5 3 1 4 5 20 40 23 12 3 3 4 2.01-3.00 1 2 11 14 18 5 3 3 7 37 36 9 3 1 2 2 C

3.01-4.00 0 1 0 9 1 0 0 0 2 17 10 5 1 0 1 0 4.01-5.00 0 0 0 2 0 0 0 0 0 2 2 1 2 2 2 1 5.01-6.00

0 0 0 0 0 0 0 0 0 1 1 6 2 6 2 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 1 6 5 3 2 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 4 0 0 1 4 1 1 1 1 0 6 3 2 1 3 0 0.76-1.00 11 13 7 2 8 10 13 5 11 10 13 9 14

16 17 24 1.01-1.25 28 30 14 8 17 5 11 16 9 15 18 26 24 24 19 29 1.26-1.50 28 29 27 27 35 28 32 23 22 20 33 40 47 33 22 24 1.51-2.00 18 20 42 81 88 26 61 32 30 41 64 64 39 15 6 10 2.01-3.00 10 18 60 168 75 17 31 16 18 89 138 78 31 22 13 10 D

3.01-4.00 1 1 15 37 7 0 0 2 0 52 87 84 39 25 18 8 4.01-5.00 0 1 3 3 2 0 0 0 0 13 46 36 31 25 7 1 5.01-6.00 0 0 0 1 0 0 0 0 0 1 15 25 12 21 5 0 6.01-8.00 0 0 1 1 0 0 0 0 0 0 4 17 11 15 3 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 1 1 2 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-3

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 Lower Level Wind Hours of Occurrence Stability Speed Sector Class (mis) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 24 14 13 12 12 17 8 4 13 7 19 17 23 26 19 24 0.76-1.00 96 71 43 32 33 32 32 23 44 33 47 44 72 90 97 100 1.01-1.25 61 30 35 36 37 34 31 39 36 23 32 32 43 48 50 72 1.26-1.50 50 19 31 46 44 47 64 63 43 27 36 37 14 17 33 38 1.51-2.00 33 16 47 74 72 43 62 73 54 41 44 49 17 8 18 8 2.01-3.00 6 5 29 55 53 12 9 21 16 56 97 55 28 14 8 6 E

3.01-4.00 2 1 4 10 0 2 2 2 3 23 36 26 21 1 0 0 4.01-5.00 0 0 4 1 2 1 0 0 1 9 9 19 6 5 0 1 5.01-6.00 0 0 2 0 1 0 0 0 0 0 4 6 1 2 1 0 6.01-8.00 0 0 3 7 0 0 0 0 0 0 0 2 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 3 0 2 0 0 2 1 0 0 0 0 5 8 11 3 3 0.76-1.00 4 2 1 1 3 0 3 2 4 2 5 5 26 34 33 11 1.01-1.25 6 3 3 0 4 5 3 1 1 6 5 8 5 26 34 6 1.26-1.50 2 1 3 1 2 10 5 4 2 1 3 0 0 11 16 0 1.51-2.00 1 0 3 0 2 11 4 1 1 2 5 2 1 3 3 1 2.01-3.00 0 3 1 1 2 0 7 1 2 1 4 9 1 1 0 0 F

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

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Lower Level Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 1 0 0 0 0 0 0 0 0 0 0 3 2 1 0 0.76-1.00 a_ 0 1 0 2 0 0 0 1 1 0 4 14 8 2 0 1.01-1.25 0 0 0 0 0 0 0 0 0 0 0 1 2 8 0 0 1.26-1.50 0 0 0 0 0 0 0 0 0 0 4 1 1 5 0 1 1.51-2.00 0 1 0 0 0 0 0 0 0 0 1 0 0 0 3 0 2.01-3.00 0 1 1 1 1 0 0 1 0 0 1 1 0 0 0 0 G

3.01-4.00 0 0 0 0 0 0 0 0 0 1 3 0 1 0 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0 1 0 0 2 1 0 0.

5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-5

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 Upper Level Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1.01-1.25 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 1.26-1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51-2.00 1 0 1 0 0 0 1 1 0 2 5 2 0 1 0 1 2.01-3.00 0 2 0 0 0 1 0 2 5 33 29 4 2 0 0 0 A

3.01-4.00 0 1 2 3 2 2 0 0 6 56 10 0 1 0 0 0 4.01-5.00 0 1 2 2 0 0 0 0 4 35 8 1 0 2 0 0 5.01-6.00 0 0 3 1 1 0 0 0 0 16 9 0 2 1 1 0 6.01-8.00 0 0 2 0 0 0 0 0 0 7 9 1 2 2 2 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 2 0 3 0 3 1 10.01-max 0 0 0 0 0 0 0 0 0 0 0 2 1 0 0 0 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.26-1.50 0 0 0 0 0 0 0 0 0 1 0 1 1 2 0 0 1.51-2.00 2 0 0 1 0 0 0 0 2 3 8 3 2 2 0 3 2.01-3.00 2 4 6 4 1 4 1 3 18 32 28 7 1 0 1 0 B

3.01-4.00 0 1 3 3 2 1 1 2 11 27 10 2 1 2 0 0 4.01-5.00 1 2 2 2 3 1 0 1 4 25 9 0 1 1 0 0 5.01-6.00 0 0 0 1 0 0 0 0 0 20 6 1 3 1 0 0 6.01-8.00 0 0 3 2 0 0 0 0 0 5 6 2 1 0 4 0 8.01-10.00 0 0 0 0 0 0 0 0 0 1 2 *o 3 4 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 2 1 5 1 0 Page 4-6

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 Upper Level Wind Hours of Occurrence Stability Speed Sector Class (mis) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 1 0 1 0 0 0 0 1.26-1.50 1 0 1 0 0 0 0 0 0 2 2 0 1 2 0 1 1.51-2.00 5 3 1 1 0 0 1 2 2 10 12 7 3 2 1 1 2.01-3.00 2 3 4 10 5 1 1 7 11 29 15 5 1 0 1 0 C

3.01-4.00 1 0 6 4 4 2 2 4 5 12 10 1 0 0 0 0 4.01-5.00 0 1 5 4 0 1 0 0 3 13 10 0 1 1 0 1 5.01-6.00 1 0 2 1 0 0 0 0 4 10 7 0 0 1 1 0 6.01-8.00 0 0 3 2 0 0 0 0 0 9 10 1 0 3 2 0 8.01-10.00 0 0 0 1 0 0 0 0 0 2 1 8 5 7 0 0 10.01-max 0 0 0 0 0 0 0 0 0 1 1 4 2 0 1 0 0.46-0.75 0 0 0 0 0 1 0 0 1 1 0 0 0 0 0 0 0.76-1.00 0 1 6 1 1 1 3 2 0 4 1 1 3 4 8 5 1.01-1.25 7 5 2 1 3 3 3 5 3 4 11 5 10 9 14 9 1.26-1.50 10 10 5 1 7 7 5 4 6 12 14 20 11 8 16 11 1.51-2.00 26 25 9 9 9 14 20 17 14 22 31 32 20 16 14 19 2.01-3.00 21 30 48 40 32 26 42 23 21 29 45 25 17 8 18 26 D

3.01-4.00 9 16 52 41 15 4 17 9 18 39 54 16 5 10 4 8 4.01-5.00 6 19 45 30 22 2 2 3 13 37 62 14 6 16 12 6 5.01-6.00 0 14 23 7 1 0 1 5 7 32 55 24 10 16 11 6 6.01-8.00 0 12 11 3 0 0 0 0 1 36 103 30 32 26 6 3 8.01-10.00 0 4 2 0 0 0 0 0 0 13 38 23 10 26 2 0 10.01-max 0 0 0 0 0 0 0 0 0 3 13 (;l 8 5 0 0 Page 4-7

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1; 2, & 3 Period 1/1/2017-12/31/2017 Upper Level Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 1 2 0 0 1 1 3 3 1 3 1 1 3 1 1 1 0.76-1.00 8 4 4 5 0 0 2 5 2 2 2 9 11 9 9 11 1.01-1.25 17 8 8 6 6 6 3 5 7 5 11 12 15 11 18 20 1.26-1.50 33 11 10 5 3 9 11 5 7 6 16 12 26 30 25 25 1.51-2.00 71 32 27 19 12 15 18 13 9 17 36 59 39 39 58 58 2.01-3.00 104 82 62 31 32 31 27 34 35 46 56 39 33 24 38 91 E

3.01-4.00 15 35 37 44 22 12 11 30 42 40 56 21 9 6 9 8 4.01-5.00 2 10 18 17 15 3 7 15 30 37 47 18 12 5 4 2 5.01-6.00 2 9 9 1 4 0 0 4 4 20 44 13 16 9 0 4 6.01-8.00 1 2 5 1 0 1 3 0 6 18 50 20 10 6 1 2 8.01-10.00 0 4 0 0 1 0 0 0 0 7 14 5 1 2 0 0 10.01-max 0 5 2 0 0 0 0 0 0 0 4 0 0 0 0 0 0.46-0.75 1 0 1 0 0 2 0 0 0 0 0 0 0 0 1 1 0.76-1.00 0 2 3 0 2 0 1 0 2 2 0 0 0 2 0 0 1.01-1.25 3 0 0 2 1 1 1 0 1 1 2 0 1 2 2 1 1.26-1.50 4 3 5 3 1 0 0 0 2 2 1 3 4 2 0 7 1.51-2.00 10 14 6 2 4 1 3 3 3 4 6 5 2 4 1 11 2.01-3.00 27 32 7 8 3 2 5 4 6 4 16 8 5 1 2 7 F

3.01-4.00 3 3 1 1 2 2 1 0 2 3 6 2 0 3 1 0 4.01-5.00 3 0 2 0 1 0 0 2 1 4 3 3 1 1 1 0 5.01-6.00 1 0 0 0 0 0 0 0 1 0 5 3 1 0 0 0 6.01-8.00 1 0 0 0 0 0 0 0 0 1 4 4 0 0 1 0 8.01-10.00 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-8

Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Upper Level Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 1 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 1 0 0 0 1 2 1 1 0 0 0 0 1.26-1.50 1 0 1 1 0 0 1 1 0 0 0 0 0 0 0 2 1.51-2.00 2 0 0 1 0 0 0 2 2 2 0 1 0 0 3 3 2.01-3.00 2 4 0 0 0 0 1 2 0 1 4 2 0 1 0 0 G

3.01-4.00 1 0 0 0 0 0 0 1 0 5 7 1 0 0 1 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 2 1 1 0 0 1 5.01-6.00 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 1 1 3 0 2 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-9

Attachment 5 Unplanned Offsite Releases Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 ATTACHMENT 5 Unplanned Offsite Releases This attachment includes a summary of the unplanned offsite releases of gaseous and liquid radioactive effluents.

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Attachment 5 Unplanned Offsite Releases Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Oconee Nuclear Station had zero (0) unplanned liquid offsite release radioactive effluents in 2017.

Oconee Nuclear Station had zero (0) unplanned gaseous offsite release of radioactive effluents in 2017.

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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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).

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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Gaseous Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Noble Gases

1. Maximum Gamma Air mRAD 6.97E-05 4.57E-05 4.46E-05 1.77E-05 1.78E-04 (a) Limit mRAD 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.00E+01 (b) % of Limit 4.65E-04 3.04E-04 2.98E-04 1.1 BE-04 5.92E-04

2. Maximum Beta Air mRAD 2.0?E-04 1.0?E-04 8.28E-05 3.9qE-05 4.36E-04 (a) Limit mRAD 3.00E+01 3.00E+01 3.00E+01 3.00E+01 6.00E+01 (b) % of Limit 6.91E-04 3.56E-04 2.76E-04 1.32E-04 7.27E-04 Receptor Location 1.0 miles SW B. Iodine, H-3, & Particulates

1. Maximum Organ Dose mREM 8.78E-02 9.0?E-02 8.95E-02 8.06E-02 3.49E-01 (a) Limit mREM 2.25E+01 2.25E+01 2.25E+01 2.25E+01 4.50E+01 (b) % of Limit 3.90E-01 4.03E-01 3.98E-01 3.58E-01 7.75E-01 Receptor Location 1.0 miles SW Critical Age CHILD Critical Organ BONE Page 6-2

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 Liquid Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Batch & Continuous Mode

1. Maximum Organ Dose mREM 3.13E-02 2.75E-02 5.18E-02 3.20E-02 1.43E-01 (a) Limit mREM 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.00E+01 (b) % of Limit 2.09E-01 1.84E-01 3.45E-01 2.13E-01 4.75E-01 (c) Critical Age Child Child Child Child Child (d) Critical Organ GILLI GILLI GILLI GILLI GILLI

2. Maximum Total Body Dose mREM 3.13E-02 2.75E-02 5.18E-02 3.19E-02 1.43E-01 (a) Limit mREM 4.50E+OO 4.50E+OO 4.50E+OO 4.50E+OO 9.00E+OO (b) % of Limit 6.95E-01 6.12E-01 1.15E+OO 7.1 OE-01 1.58E+OO (c) Critical Age Child Child Child Child Child Page 6-3

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 40 CFR Part 190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40 CFR Part 190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. The fuel cycle dose assessment for Oconee Nuclear Station includes liquid and gaseous effluent dose contributions from Oconee Nuclear Station and direct and air-scatter dose from the onsite ISFSI. No other uranium fuel cycle facility contributes significantly to the maximum exposed individual. Included in the gaseous effluent dose calculations is an estimate of the dose contributed by Carbon-14 (Ref. Attachment 2, Supplemental Information, of this report for further information). The combined dose to a maximum exposed individual from effluent releases*and direct and air-scatter dose from the ISFSI is below 40 CFR Part 190 limits as shown by the following summary.

Note: The 40 CFR Part 190 effluent dose analysis to the maximum exposed individual from liquid and gas releases includes the dose from noble gases (i.e., total body and skin).

40 CFR Part 190 Effluent Dose Summary A. Maximum Organ Dose (other than TB) 3.49E-01 mREM

1. Location 1.0 miles SW

2. Critical Age CHILD

3. Critical Organ BONE

4. Gas Contribution % 0.05 %

5. Liquid Contribution % 99.95 %

B. Maximum Total Body Dose 2.44E-01 mREM

1. Location 1.0 miles SW

2. Critical Age CHILD

3. Gas non-NG Contribution % 41.47 %

4. Gas Contribution % 0.06%

5. Liquid Contribution % 58.47 %

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

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

Total dose from liquid and gaseous effluents from Oconee Nuclear Station and direct and air-scatter dose from the onsite ISFSI is conservatively estimated to be less than 12 mrem/yr to the nearest real individual. This meets the 40 CFR Part 190 requirements of an annual dose commitment to any member of the general public of less than 25 mrem total body or any organ and 75 mrem to the thyroid.

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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 6.0 10 CFR 72.212(b)(5)(iii) - Radioactive Materials in Effluents and Direct Radiation 6.1 Purpose 10 CFR 72.212(b)(5)(iii) requires the general licensee to perform written evaluations, before use and before applying the changes authorized by an amended CoC to a cask loaded under the initial Coe or an earlier amended CoC, that establish that the requirements of 10 CFR 72.104 have been met. A copy of this record shall be retained until spent fuel is no longer stored under the general license issued under 10 CFR 72.210 .

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

This section provides the written evaluation required by 10 CFR 72.212(b)(5)(iii), demonstrating Duke Energy's compliance with the requirements of 10 CFR 72.104 for the ONS ISFSI.

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

6.2.1 §72.104(a) - Dose Limits 10 CFR 72.104, as clarified by ISG-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/year) due to direct radiation from the Independent Spent Fuel Storage Installation and other fuel cycle operations in the area. This same dose limit is stipulated by the EPA for the fuel cycle in 40 CFR 190.1 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 - VI, together with the 2

characteristics of assumed "design basis" fuel for canisters in Phase VII and Phase VIII of the Oconee ISFSl

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 Module5 of the SCALE Code System was used to perform the fuel depletion and characterization calculations using the cross section sets created by SAS2. These characterization calculations yielded the photon and neutron source terms to be used as input to subsequent shielding calculations. As mentioned above, problem-dependent cross section sets were developed for these analyses since ORIGEN-S was used within the SAS2 sequence. Duke Energy Corporation Radiological Engineering is experienced in the use of the SCALE Code System, and the SCALE Code System is installed and maintained under the purview of the pertinent software and data quality assurance program.

6 The results of the radiation source term calculation were used as input to Calculation OSC-8706 to evaluate the shielding characteristics of a single Horizontal Storage Module. The MCNP Monte Carlo particle transport computer 7

code was used to perform the transport calculations and to write a surface flux file for use in subsequent skyshine calculations.

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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 9

SDQA-30269-NG0 documents the quality control measures in place for MCNP5).

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

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

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

6.2.3 §72.104(c)-Operationallimits 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.

6 Calculation OSC-8716 10 uses the surface flux files developed in OSC-8706 in a repeating array. A skyshine calculation is performed to obtain near- and far-field dose results the Oconee ISFSI. This calculation need not consider any effluent from Phase VIII. The Phase VIII HSMs use the NUHOMS-24PTH-S-LC DSCs, which are designed as "leak-tight." Per Appendix P, Section P.11.2.8 of the NUHOMS FSAR13 , accidental releases are not credible.

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

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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3

Period 1/1/2017 - 12/31/2017 6.4 References

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

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

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

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

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

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

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

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

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

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

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

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

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

Page 6-7

Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 1/1/2017 - 12/31/2017 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 66 wells in 2017. 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 2017. Results from sampling during 2017 confirmed existing knowledge of tritium concentrations in site ground water.

Results from sampling during 2017 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 2017.

Key to below table.

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

pCi/1 * - picocuries per liter.

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

the Environmental Protection Agency drinking water standard for 20,000 pCi/1 tritium. This standard applies only to water used for drinking.

the 10 CFR Part 20, Appendix B, Table 2, Column 2, Effluent 1,000,000 pCi/1 Con*centration Limit for tritium.

Page 7-2

Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Well Tritium Concentration (pCi/1) #of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples A-1 ONS GWPI / A-1 / CTP 1/2 <MDA <MDA NS <MDA 3 A-10 ONS GWPI / A-10 / CTP 3 3.52E+02 3.65E+02 NS 5.27E+02 3 A-11 ONS GWPI / A-11 / CTP 3 <MDA <MDA NS <MDA 3 A-13 ONS GWPI / A-13 / CTP 1/2 3.14E+02 4.15E+02 NS 2.95E+02 3 A-14 ONS GWPI / A-14 / CTP 1/2 <MDA <MDA NS <MDA 3 A-17 ONS GWPI / A-17 / CTP 1/2 <MDA NS NS NS 1 A-18 ONS GWPI / A-18 / CTP 1/2 <MDA NS NS NS* 1 A-2 ONS GWPI / A-2 / CTP 1/2 <MDA <MDA NS <MDA 3 A-9 ONS GWPI / A-9 / CTP 1/2 2.41E+02 NS NS NS 1 BG-4 ONS GWPI / BG-4 / Ball Field <MDA <MDA NS <MDA 3 GM-10 ONS GWPI / GM-10 / 525 kv Sw Yard NS <MDA <MDA <MDA 3 GM-10R ONS GWPI /GM-10R / 525 kvSwYard NS <MDA NS <MDA 2 GM-11 ONS GWPI / GM-11 / ONS Garaoe NS <MDA NS NS 1 GM-11R ONS GWPI / GM-11 R / ONS Garaoe NS <MDA NS NS 1 GM-12 ONS GWPI / GM-12 / E of Access Rd. NS <MDA NS NS 1 GM-12R ONS GWPI / GM-12R / E of Access Rd. NS <MDA NS NS 1 GM-13 ONS GWPI / GM-13 / 525 kv SwYard NS <MDA NS NS 1 GM-13R ONS GWPI / GM-13R / 525 kv SwYard NS <MDA NS NS 1 GM-14 ONS GWPI / GM-14 / Mnt. Tro. Facilitv NS <MDA <MDA <MDA 3 GM-14R ONS GWPI / GM-14R / Mnt. Tro. Facility NS <MDA NS <MDA 2 GM-15 ONS GWPI / GM-15 <MDA <MDA <MDA <MDA 4 GM-15R ONS GWPI / GM-15R <MDA <MDA NS NS 2 GM-16DDR ONS GWPI / GM-16DDR <MDA 2.46E+02 NS NS 2 GM-16DR ONS GWPI / GM-16DR 6.91E+03 6.75E+03 7.26E+03 6.77E+03 4 GM-16R ONS GWPI / GM-16R 9.69E+02 9.56E+02 1.09E+03 1.27E+03 4 GM-17DR ONS GWPI / GM-17DR 2.06E+03 2.09E+03 2.06E+03 2.22E+03 4 GM-17R ONS GWPI / GM-17R 6.40E+02 8.00E+02 NS 1.13E+03 3 GM-18R ONS GWPI / GM-18R 4.85E+03 3.97E+03 4.33E+03 4.11E+03 4 GM-19 ONS GWPI / GM-19 1.79E+03 1.71E+03 1.67E+03 1.98E+03 4 GM-19R ONS GWPI / GM-19R 1.09E+03 1.22E+03 1.30E+03 1.35E+03 4 GM-1R ONS GWPI / GM-1 R / CTP 1/2 <MDA <MDA <MDA <MDA 4 GM-20 ONS GWPI / GM-20 <MDA <MDA NS NS 2 GM-20R ONS GWPI / GM-20R <MDA <MDA NS NS 2 GM-21 ONS GWPI / GM-21 NS <MDA NS NS 1 GM-22 ONS GWPI / GM-22 NS <MDA NS NS 1 GM-23 ONS GWPI / GM-23 2.50E+02 2.46E+02 <MDA <MDA 4 GM-24R ONS GWPI / GM-24R 9.50E+02 8.74E+02 1.17E+03 1.21E+03 4 GM-25R ONS GWPI / GM-25R 2.78E+02 2.35E+02 3.55E+02 2.34E+02 4 GM-2DR ONS GWPI / GM-2DR / U-1/2 SFP 3.15E+02 <MDA <MDA <MDA 4 GM-2R 111 ONS GWPI / GM-2R / U-1/2 SFP 1.15E+03 3.62E+03 1.84E+03 1.79E+03 4 GM-3DR ONS GWPI / GM-3DR / U-3 SFP 2.98E+02 2.92E+02 NS 2.69E+02 3 GM-3R ONS GWPI / GM-3R / U-3 SFP 2.12E+02 2.99E+02 2.75E+02 2.19E+02 4 (1) H-3 resample 13JUN2017 yielded activity 1.50E+03 pCi/1, NCR# 02136161 Page 7-3

Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Well Tritium Concentration (pCi/1) #of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples GM-4 ONS GWPI / GM-4 I Rad. Mat. WH <MDA 5.52E+02 4.37E+02 5.35E+02 4 GM-5 ONS GWPI / GM-5 / Rdwst. Bldg. <MDA <MDA 3.01E+02 <MDA 4 GM-5R ONS GWPI / GM-5R / Rdwst. Bldg. <MDA <MDA NS <MDA 3 GM-6 ONS GWPI / GM-6 I Outflow to CTP-3 1.92E+02 <MDA <MDA <MDA 4 GM-6R ONS GWPI / GM-6R / Outflow to CTP-3 <MDA <MDA NS <MDA 3 GM-7 ONS GWPI / GM-7 / 525 kv Sw Yard <MDA 4.14E+02 3.85E+02 2.64E+02 4 GM-7DR ONS GWPI / GM-7DR <MDA <MDA NS NS 2 GM-7R ONS GWPI / GM-7R / 525 kv Sw Yard 9.54E+02 1.20E+03 1.37E+03 1.30E+03 4 GM-8 ONS GWPI / GM-8 I E of U-3 TB 5.83E+02 <MDA 2.98E+02 2.32E+02 4 GM-8R ONS GWPI / GM-8R / E of U-3 TB 5.23E+02 <MDA NS <MDA 3 GM-9 ONS GWPI / GM-9 I E of U-2 TB 2.55E+02 <MDA 2.12E+02 2.71E+02 4 GM-9R ONS GWPI / GM-9R / E of U-2 TB <MDA <MDA NS <MDA 3 MW-11 ONS GWPI / MW-11 / Landfill <MDA NS <MDA NS 2 MW-110 ONS GWPI / MW-11 D / Landfill <MDA NS <MDA NS 2 MW-13 ONS GWPI / MW-13 / Landfill <MDA NS <MDA NS 2 MW-16 ONS GWPI / MW-16 / Landfill <MDA NS <MDA NS 2 MW-3 ONS GWPI / MW-3 / Landfill NS NS <MDA NS 1 MW-RP01 ONS GWPI / MW-RP01 / Landfarm/Burial NS <MDA NS NS 1 MW-RP02 ONS GWPI / MW-RP02 / Landfarm/Burial NS <MDA NS NS 1 MW-RP03 ONS GWPI / MW-RP03 / Landfarm/Burial NS <MDA NS NS 1 Well Tritium Concentration (pCi/1) # of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples 011 ONS / 011 / Ball Field <MDA <MDA <MDA <MDA' 4 013 ONS / 013 /WH 5 <MDA <MDA <MDA <MDA 4 015 ONS / 015 / Brown's Bottom <MDA <MDA <MDA <MDA 4 Well Tritium Concentration (pCi/1) # of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples RW-1 I 525 kv Sw. Yard I 7.89E+02 I 6.49E+02 I 7.62E+02 I 6.69E+02 I 4 NOTE: Frequency of sampling was reduced in 2017 for wells with long standing, stable trends.

I.

Page 7-4

Attachment 8 Inoperable Equipment Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 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 1/1/2017 - 12/31/2017 Oconee Nuclear Station did not experience inoperable equipment relevant to effluent monitoring in excess of SLC limits during 2017.

Oconee Nuclear Station did not experience temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases) during 2017.

Page 8-2

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 ATTACHMENT 9 Summary of Changes to the Offsite Dose Calculation Manual This attachment includes a summary of changes to the ODCM and Radiological Effluent Controls.

Page 9-1

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 ODCM Revision 58 The most recent ODCM revision is 58 and was provided with the 2016 ARERR.

Radiological Effluent Controls (SLC 16.11)

The Oconee Nuclear Station Radiological Effluent Controls are contained in SLC 16.11 and are included in this section. SLC 16.11 was not revised in 2017.

Page 9-2

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS SECTION TITLE NO 16.0 SELECTED LICENSEE COMMITMENTS 16.1-1

16.1 INTRODUCTION

16.1-1 16.2 APPLICABILITY 16.2-1 16.3 DEFINITIONS 16.3-1 16.4 COMMITMENTS RELATED TO REACTOR COMPONENTS Pending 16.5 REACTOR COOLANT SYSTEM 16.5.1-1 16.5.1 Reactor Coolant System Vents 16.5.1-1 16.5.2 Low Temperature Overpressure Protection (L TOP) System 16.5.2.1 16.5.3 Loss of Decay Heat Removal 16.5.3-1 16.5.4 Reactor Coolant System (RCS) Boron Sampling 16.5.4-1 16.5.5 [DELETED] 16.5.5-1 16.5.6 [DELETED] 16.5.6-1 16.5.7 Chemistry Requirements 16.5.7-1 16.5.8 Pressurizer 16.5.8-1 16.5.8a [DELETED] 16.5.8a-1 16.5.9 Testing Following Opening of System (Core Barrel Bolt Inspections) 16.5.9.1 16.5.10 Loss of Reactor Coolant 16.5.10-1 16.5.11 Subcriticality 16.5.11-1 16.5.12 RCS Leakage Testing Following Opening of System 16.5.12-1 16.5.13 High Pressure Injection and the Chemical Addition Systems 16.5.13-1 16.6 COMMITMENTS RELATED TO ENGINEERED SAFETY FEATURES 16.6.1-1 (NON-ESF SYSTEMS) 16.6.1 Containment Leakage Tests 16.6.1-1 16.6.2 Reactor Building Post-Tensioning System 16.6.2-1 16.6.3 Containment Heat Removal Verification Frequency 16.6.3-1 16.0-1 Rev. 006 I 9-3

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)

SECTION TITLE NO 16.6.4 Low Pressure Injection System Leakage 16.6.4-1 16.6.5 Core Flood Tank Discharge Valve Breakers 16.6.5-1 16.6.6 Core Flooding System Test 16.6.6-1 16.6.7 BWST Outlet Valve Control 16.6.7-1 16.6.8 LPI System Valve Test Restrictions 16.6.8-1 16.6.9 Containment Purge Valve Testing 16.6.9-1 16.6.10 Trisodium Phosphate (TSP) 16.6.10-1 16.6.11 Containment Debris Sources 16.6.11-1 16.6.12 Additional High Pressure Injection (HPI) Requirements 16.6.12-1 16.6.13 Additional Requirements to Support Low Pressure Injection (LPI) 16.6.13-1 Operability 16.6.14 Control of HPI and LPI/RBS Pump Room Temperatures 16.6.14-1 16.6.15 High Pressure Injection (HPI) and Liquid Waste Disposal (LWD) 16.6.15-1 Leakage 16.7 INSTRUMENTATION 16.7.1-1

16. 7.1 Accident Monitoring Instrumentation 16.7.1-1 16.7.2 Anticipated Transient Without Scram 16.7.2-1 16.7.3 Emergency Feedwater System 16.7.3-1 16.7.4 Hydrogen Analyzers 16.7.4-1 16.7.5 Steam Generator Overfill Protection 16.7.5-1 16.7.6 Diverse Actuation Systems 16.7.6-1 16.7.7 Position Indicator Channels 16.7.7-1 16.7.8 lncore Instrumentation 16.7.8-1 16.7.9 RCP Monitor, 16.7.9-1 16.7.10 Core Flood Tank Instrumentation 16.7.10-1 16.7.11 Display Instrumentation 16.7.11-1 16.0-2 Rev.006 9-4

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)

SECTION TITLE PAGE NO

16. 7.12 SSF Diesel Generator (DG) Air Start System Pressure 16.7.12-1 Instrumentation

16. 7.13 SSF Instrumentation 1.6.7.13-1.

16.7.14 Rod Withdrawal Alarm Limit 16.7.14-1

16. 7.15 Engine~red Safeguards Protective System (ESPS) Voter Trouble Alarm 16. 7.15..:1 16.7.16 Spent Fuel Pool -Wide Range Level Instrumentation 16.7.16-1 16.7.17 Reactor Protective System Instrumentation Setpoints 16.7.17-1 16.8 ELECTRIC POWER SYSTEMS 16.8.1-1 16.8.1 Control of Room Temperatures for Station Blackout 16.8.1-1 16.8.2 Additional Requirements to Support Keowee Hydro Unit (KHU) 16.8.2-1 OPERABILITY 16.8.3 Power Battery Parameters 16.8.3-1 16.8.4 Keowee Operational Restrictions 16.8.4-1 16.8.5 [DELETED] 16.8.5-1 16.8.6 Lee/Central Alternate Power System 16.8.6-1 16.8. 7 Auctioneering Diodes 16.8.7-1 16.8.8 External Grid Trouble Protection 16.8.8-1 16.8.9 Keowee Governor Speed Out Of Tolerance (OOT) Alarm 16.8.9-1 16.9 AUXILIARY SYSTEMS 16.9.1-1 16.9.1 Fire Suppression Water System 16.9.1-1 16.9.2 Sprinkler and Spray Systems 16.9.2-1 16.9.3 [DELETED] 16.9.3-1 16.9.4 Fire Hose Stations 16.9.4-1 16.9.5 Fire Barriers 16.9.5-1 16.9.6 Fire Detection Instrumentation 16.9.6-1 16.9.7 Keowee Lake Level 16.9.7-1 16.0-3 Rev. 006 I 9-5

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)

SECTION TITLE NO 16.9.8 Control Room Ventilation System (CRVS) Booster Fans 16.9.8-1 16.9.8a HPSW System Requirements to Support Loss of LPSW 16.9.8a-1 16.9.9 Additional Protected Service Water (PSW) System Commitments 16.9.9-1 16.9.10 Component Cooling and HPI Seal Injection to Reactor 16.9.10-1 Coolant Pumps 16.9.11 Turbine Building Flood Protection Measures 16.9.11-1 16.9.11 a Auxiliary Building Flood Protection Measures 16.9.11a-1 16.9.12 Additional Low Pressure Service Water (LPSW) And 16.9.12-1 Siphon Seal Water (SSW) System Operability Requirements 16.9.13 Spent Fuel Cooling System 16.9.13-1 16.9.14 SSF Diesel Generator (DG) Inspection Requirements 16.9.14-1 16.9.15 Radioactive Material Sources 16.9.15-1 16.9.16 Reactor Building Polar Crane and Auxiliary Hoist 16.9.16-1 (RCS System Open) 16.9.17 Reactor Building Polar Crarie (RCS at elevated 16.9.17-1 temperature and pressure) 16.9.18 Snubbers 16.9.18-1 16.9.19 Gravity Induced Reverse Flow to Standby Shutdown Facility (SSF) 16.9.19-1 Through a Unit 2 Condensate Cooler 16.9.20 Diesel Driven Service Air Compressors 16.9.20-1 16.9.21 Standby Shutdown Facility External Flood Protection 16.9.21-1 16.9.22 [DELETED] 16.9.22-1 16.9.23 Alternate Chilled Water (AWC) and Alternate Reactor Building Cooling 16.9.23-1 (RBC) Systems 16.9.24 FLEX - Equipment and Connections 16.9.24...:1 16.9.25 Spent Fuel Pool Area Isolation 16.9.25-1 16.0-4 Rev. 006 I 9-6

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)

SECTION TITLE NO 16.10 COMMITMENTS RELATED TO STEAM & POWER CONVERSION 16.10.1-1 SYSTEMS 16.10.1 Local Start of Turbine Driven Emergency Feedwater (EFW) Pump 16.10.1-1 16.10.2 Steam Generator Secondary Side Pressure and 16.10.2-1 Temperature (PIT) Limits 16.10.3 Emergency Feedwater (EFW) Pump and Valve Testing 16.10.3-1 16.10.4 Low Presssure Service Water System Testing 16.10.4-1 16.10.5 . [DELETED] 16.10.5-1 16.10.6 Emergency Feedwater Controls 16.10.6-1 16.10. 7 Alternate Source of Emergency Feedwater (EFW) 16.10.7-1 16.10.8 Upper Surge Tank (UST) Riser Branch Line Automatic Isolation Valves 16.10.8-1 16.10.9 Air Operated Valves (AOVs) Required to Support Standby Shutdown 16.10.9-1 Facility (SSF) During Station Blackout (SBO) 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.1-1 16.11.1 Radioactive Liquid effluents 16.11.1-1 16.11.2 Radioactive Gaseous Effluents 16.11.2-1 16.11.3 Radioactive Effluent Monitoring Instrumentation 16.11.3-1 16.11.4 Operational Safety Review 16.11.4-1 16.11.5 Solid Radioactive Waste 16.11.5-1 16.11.6 Radiological Environmental Monitoring 16.11.6-1 16.11. 7 Dose calculations 16.11.7-1 16.11.8 Reports 16.11.8-1 16.11.9 Radioactive effluent release report 16.11.9-1 16.11.10 Radiological Environmental Operating Reports 16.11.10-1 16.11.11 Iodine Radiation Monitoring Filters

16.11.11-1 16.0-5 Rev. 006 I 9-7

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)

SECTION TITLE NO 16.11.12 Radioactive Material in Outside Temporary 16.11.12-1 Tanks Exceeding Limit 16.11.13 Radioactive Material in Wast~ Gas Holdup 16.11.13-1 Tank Exceeding Limit 16.11.14 Explosive Gas Mixture 16.11.14-1 16.12 REFUELING OPERATIONS 16.12.1-1 16.12.1 Decay Time for Movement of Irradiated Fuel 16.12.1-1 16.12.2 Area Radiation Monitoring for Fuel Loading and Refueling 16.12.2-1 16.12.3 Communication Between Control Room and Refueling Personnel 16.12.3-1 16.12.4 Handling of Irradiated Fuel Assemblies 16.12.4-1 16.12.5 Loads Suspended over Spent Fuel in Spent Fuel Pool 16.12.5-1 16.12.6 Fuel Damage During Fuel Handling Operations in Containment 16.12.6-1 16.13 CONDUCT OF OPERATION 16.13.1-1 16.13.1 Minimum Station Staffing Requirements 16.13.1-1 16.13.2 [DELETED] 16.13.2-1 16.13.3 [DELETED] 16.13.3-1 16.13.4 Reactivity Anomaly 16.13.4-1 16.13.5 Deleted 16.13.5-1 16.13.6 Retraining and Replacement of Station Personnel 16.13.6-1 16.13. 7 Procedures for Control of Ph in Recirculated 16.13.7-1 Coolant after Loss-of-coolant Accident & Long-term Emergency Core Cooling Systems 16.13.8 Respiratory Protective Program 16.13.8-1 16.13.9 Startup Report 16.13.9-1 16.13.10 Core Ope.rating Limits Reports

16.13.10-1 16.13.11 Procedure for Station Survey Following an Earthquake 16.13.11-1 16.0-6 Rev. 006 I 9-8

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)

SECTION TITLE NO 16.14 CONTROL RODS AND POWER DISTRIBUTION 16.14.1-1 16.14.1 APSR Movement 16.14.1-1 16.14.2 Control Rod Program Verification 16.14.2-1 16.14.3 Power Mapping 16.14.3-1 16.14.4 [DELETED] 16.14.4-1 16.14.4.a Engineering Work Station 16.14.4.a-1 16.15 VENTILATION FILTER TESTING PROGRAM 16.15.1-1 16.15.1 [DELETED] 16.15.1-1 16.15.2 Control Room Pressurization and Filtering System 16.15.2-1 16.15.3 Spent Fuel Pool Ventilation System 16.15.3-1 16.0-7 Rev. 006 I 9-9

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Oconee Nuclear Station Selected Licensee Commitments Revised 01/08/18 List of Effective Pages Page Revision Number Implementation Date 16.0 005 08/16/17 16.1 000 10/15/07 16.2 000 08/25/14 16.3 001 06/29/15 16.4 PENDING 16.5.1 000 11/26/12 16.5.2 000 11/15/12 16.5.3 000 02/21/07 16.5.4 000 11/15/12 16.5.5 Deleted 5/16/09 16.5.6 Deleted 02/10/14 16.5.7 000 12/13/06 16.5.8 000 01/31/07 16.5.8a Deleted 5/19/05 16.5.9 000 11/15/12 16.5.10 000 10/08/03 16.5.11 000 01/31/00 16.5.12 000 03/27/99 16.5.13 000 03/27/99 16.6.1 000 07/23/12 16.6.2 000 01/31/07 16.6.3 000 11/15/12 16.6.4 000 11/15/12 16.6.5 000 12/14/00 16.6.6 000 11/15/12 16.6.7 000 03/27/99 16.6.8 000 03/27/99 16.6.9 000 11/15/12 16.6.10 000 11/15/12 16.6.11 000 11/15/12 16.6.12 000 11/15/12 16.6.13 000 03/31/08 16.6.14 000 04/21/14 16.6.15 000 11/15/12 16.7.1 000 11/15/12 Oconee Nuclear Station LOEP 1 Revision 023 9-10

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Oconee Nuclear Station Selected Licensee Commitments Revised 01 /08/18 List of Effective Pages Page Revision Number Implementation Date 16.7.2 000 11/15/12 16.7.3 000 11/15/12 16.7.4 000 07/14/05 16.7.5 000 11/15/12 16.7.6 000 04/08/14 16.7.7 000 11/15/12 16.7.8 000 03/27/99 16.7.9 000 10/23/03 16.7.10 000 11/15/12 16.7.11 000 11/15/12 16.7.12 000 06/30/04 16.7.13 000 12/05/12 16.7.14 000 11/15/12 16.7.15 000 04/08/14 16.7.16 000 10/14/15 16.7.17 000 07/14/16 16.8.1 000 08/09/01 16.8.2 000 02/10/05 16.8.3 001 01/26/16 16.8.4 000 02/10/05 16.8.5 000 05/21/15 16.8.6 000 01/04/07 16.8.7 000 01/31/00 16.8.8 000 01/31/00 16.8.9 000 06/21/05 16.9.1 001 08/16/16 16.9.2 002 08/16/16 16.9.3 Deleted 01 /08/18 16.9.4 001 08/16/16 16.9.5 002 08/16/16 16.9.6 005 12/19/17 16.9.7 001 08/16/16 16.9.8 000 02/15/06 16.9.8a 000 02/07/05 16.9.9 002 08/16/17 Oconee Nuclear Station LOEP2 Revision 023 9-11

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Oconee Nuclear Station Selected Licensee Commitments Revised 01 /08/18 List of Effective Pages Page Revision Number Implementation Date 16.9.10 000 01/12/04 16.9.11 001 06/29/15 16.9.11a 001 06/06/17 16.9.12 001 09/21/15 16.9.13 000 01/31/07 16.9.14 000 10/28/04 16.9.15 000 03/27/99 16.9.16 000 10/15/14 16.9.17 000 05/23/01 16.9.18 000 07/15/14 16.9.19 000 03/31/05 16.9.20 001 12/14/16 16.9.21 000 07/09/09 16.9.22 Deleted 08/16/17 16.9.23 001 08/16/17 16.9.24 003 11/18/16 16.9.25 001 08/16/17 16.10.1 000 11/15/12 16.10.2 000 12/02/03 16.10.3 000 03/27/99 16.10.4 000 11/15/12 16.10.5 Deleted 08/24/04 16.10.6 000 03/27/99 16.10.7 001 09/21/15 16.10.8 000 11/27/06 16.10.9 000 11/25/09 16.11.1 000 03/15/11 16.11.2 000

01/31/00 16.11.3 000 11/20/08 16.11.4 000 06/30/14 16.11.5 000 10/30/02 16.11.6 000 11/08/13 16.11.7 000 01/31/00 16.11.8 000 12/21/09 16.11.9 000 03/22/10 Oconee Nuclear Station LOEP3 Revision 023 9-12

" Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Oconee Nuclear Station Selected Licensee Commitments Revised 01 /08/18 List of Effective Pages Page Revision Number Implementation Date 16.11.10 000 05/14/14 16.11.11 000 03/27/99

.16.11.12 000 04/10/03 16.11.13 000 03/27/99 16.11.14 000 03/27/99 16.12.1 000 03/27/99 16.12.2 000 05/03/07 16.12.3 000 05/01/03 16.12.4 000 03/27/99 16.12.5 000 03/27/99 16.12.6 000 11/08/07 16.13.1 001 12/22/15 16.13.2 000 12/15/04 16.13.3 000 12/15/04 16.13.4 000 03/27/99 16.13.5 Deleted 11 /30/99 16.13.6 000 03/27/99 16.13.7 000 12/15/04 16.13.8 000 03/27/99 16.13.9 000 03/27/99 16.13.10 000 03/27/99 16.13.11 000 03/27/99 16.14.1 000 11/15/12 16.14.2 000 07/23/12 16.14.3 000 03/27/99 16.14.4 Deleted 03/15/11 16.14.4.a 000 03/15/11 16.15.1 000 04/12/06 16.15.2 000 11 /15/12 16.15.3 000 11/15/12 Note: With the introduction of Fusion in June 2015, all controlled documents require a three-digit revision number. Thus, the revision numbers were set to "000" in the summer of 2015. As such, the revision dates for Revision 000 are based on the implementation dates for revisions in effect prior to this change.

Oconee Nuclear Station LOEP4 Revision 023 9-13

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 4

be limited to 2 x 10- 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 9-14

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Liquid Effluents 16.11.1

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

Appendix 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 REQUIRED ACTION COMPLETION TIME A. Concentration of A.1 Restore concentration to Immediately radioactive material within the limit.

released in liquid effluents to Unrestricted Areas exceeds the limits specified in Commitment a.

16.11.1-2 0311 s,11 I 9-15

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Liquid Effluents 16.11.1 CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose from B.1 -------------NOTE--------------

the release of Not required during radioactive materials in unusual operating liquid effluents exceeds conditions that result in any of the limits in

activation of the Oconee Commitment b. Emergency Plan.

Submit report to the 30 days from the end of

regional NRC Office which the quarter during which includes the following: the release occurred

a. Cause(s) for exceeding the limit(s).

b. A description of the program of corrective action initiated to:

reduce the releases of radioactive materials in liquid effluents, and to keep these levels of radioactive materials in liquid effluents in compliance with the above limits, or as low as reasonably achievable.

c. Results of radiological analyses of the drinking water source and the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141.

16.11.1-3 0311s111 I 9-16

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Liquid Effluents 16.11.1 CONDITION REQUIRED ACTION COMPLETION TIME C. Radioactive liquid C.1 Submit report to the 30 days waste is discharged regional NRC Office which without treatment and includes the following:

in excess of the specified limit. a. Cause of equipment or subsystem inoperability.

b. Corrective action to restore equipment and prevent recurrence.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.1.1 N/A N/A 16.11.1-4 0311 s111 I 9-17

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Liquid Effluents 16.11.1 BASES 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 Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem. It is further indicated in 10 CFR 50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as reasonably achievable (ALARA) as set forth in 10 CFR 50 Appendix I. Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with this SLC are based on ten times the instantaneous dose rate value of 50 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 141 and 40 CFR 190.

Section I of Appendix I of 10 CFR 50 states that this appendix provides specific numerical guides for design objectives and limiting conditions for operation, to assist holders of licenses for light water cooled nuclear power reactors in meeting the requirements to keep releases of radioactive material to unrestricted areas as low as practical and reasonably achievable, during normal reactor operations, including expected operational occurrences. Using the flexibility granted during unusual operating conditions, and the stated applicability of the design objectives for the Oconee Nuclear Station, Appendix I dose limits for radioactive liquid effluent releases are concluded to be not applicable during unusual operating conditions that result in the activation of the Oconee Emergency Plan.

For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

The requirements that the appropriate portions of this system be used when specified provides assurance that the relea*ses 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 9-18

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Liquid Effluents 16.

11.1 REFERENCES

1. 10 CFR Part 20, Appendix B.

2. 40 CFR Part 141.

3. 10 CFR Part 50, Appendices A and I.

4. 40 CFR Part 190.

5. Offsite Dose Calculation Manual.

6. Regulatory Guide 1.109.

7. NUREG-1301 16.11.1-6 03/15/11 9-19

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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:

s;; 500 mrem/yr to the total body

s;; 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 :s;; 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:

s;; 15 mrad for gamma radiation

s;; 30 mrad for beta radiation ii. During any calendar year:

s;; 30 mrad for gamma radiation

s;; 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 9-20

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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.

N OT E---------------------------------------------

T he requirement of c.2 does not apply to the Auxiliary Building Exhaust System since it is not "treated" prior to release.

APPLICABILITY: At all times 16.11.2-2 03/27/99 9-21

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Gaseous Effluents 16.11.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Dose rate exceeds the A.1 Restore release rate to Immediately limits specified in within limits.

Commitment a.

B. Calculated dose B.1 Submit report to the 30 days from the end of exceeds specified limits. regional NRC Office which the quarter during which includes the following: the release occurred

a. Cause(s) for exceeding the limit(s),

and

b. A description of the program of corrective action initiated to:

reduce the releases of radioactive materials in gaseous effluents, and to keep these levels of radioactive materials in gaseous effluents in compliance with the specified limits or as low as reasonably achievable.

16.11.2-3 01131100 I 9-22

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Pe;riod 1/1/2017 -12/31/2017 Radioactive Gaseous Effluents 16.11.2 CONDITION REQUIRED ACTION COMPLETION TIME C. Radioactive gaseous C.1 Submit a report to the 30 days waste is discharged regional NRC Office which greater than limits includes the following:

specified in Commitment c.1 o*r a. Cause of equipment c.2. or subsystems inoperability, and AND

b. Corrective action to Radioactive gaseous restore equipment waste is discharged and prevent without treatment for recurrence.

more than 31 days.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.2.1 N/A N/A

/

16.11.2-4 03/27/99 9-23

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Gaseous Effluents 16.11.2 BASES 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 110 of Appendix I to 10 CFR Part 50.

16:11.2-5 01131100 I 9-24

l Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Gaseous Effluents 16.

11.2 REFERENCES

1 10 CFR Part 20, Appendix 8.

2. 10 CFR Part 50, Appendices A and I.

3. Regulatory Guide 1.109.

4. 40 CFR Part 190.

5. Offsite Dose Calculation Manual.

~ .

16.11.2-6 01131100 I 9-25

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 b.e OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.11.1.a are not exceeded.

b. Gaseous Process and Effluents The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 16.11.3-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.11.2.a are not exceeded.

c. The setpoints shall be determined in accordance with the methodology described in the ODCM and shall be recorded.

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

Correction to setpoints determined in accordance with Commitment c may be permitted without declaring the channel inoperable.

APPLICABILITY: According to Table 16.11.3-1 and Table 16.11.3-2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Alarm/trip setpoint less A.1 Declare channel Immediately conservative than inoperable.

required for one or more effluent monitoring instrument channels. A.2 Suspend release of Immediately

effluent monitored by the channel.

16.11.3-1 11120,oa I 9-26

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B.1 Enter the Condition Immediately liquid effluent monitoring referenced in Table instrument channels 16.11.3-1 for the inoperable. function.

AND B.2 Restore the 30 days instrument(s) to OPERABLE status.

C. One or more required C.1 Enter the Condition Immediately gaseous effluent referenced in Table monitoring instrument 16.11.3-2 for the channels inoperable. function.

AND C.2 Restore the 30 days instrument(s) to OPERABLE status.

D. Required Action and D.1 Explain in next Annual April 30 of following associated Completion Radiological Effluent calendar year Time of Required Action Release Report why B.2 or C.2 not met. inoperability was not corrected in a timely manner.

16.11.3-2 11120,os I 9-27

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1.1 Analyze two Prior to initiating Action 8.1 and independent samples subsequent release referenced in Table in accordance with 16.11.3-1. (RIA-33) SLC 16.11.4.

AND E.1.2 Conduct two Prior to initiating independent data entry subsequent release checks for release rate calculations AND E.1.3 Conduct two Prior to initiating independent valve subsequ.ent release lineups of the effluent pathway.

OR E.2 Suspend release of Immediately radioactive effluents by th is pathway.

F. As required by Required F.1 Suspend release of Immediately Action 8.1 and radioactive effluents by referenced in Table this pathway.

16.11.3-1. (RIA-54)

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 7

of at least 10- µCi/ml.

16.11.3-3 11120,oa I 9-28

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required -----------------NOTE------------------

Action B.1 and Not required during short, referenced in Table controlled outages of liquid 16.11.3-1. (Liquid effluent monitoring Radwaste Effluent Line instrumentation. Short controlled Flow Rate Monitor) outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

G.1 Suspend release of Immediately radioactive effluents by this pathway.

G.2 Estimate flow rate Immediately during actual releases.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter 16.11.3-4 11120,os I 9-29

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME H. As required by Required ---------"-----NOTE------------------

Action 8.1 and Not required during short, referenced in Table controlled outages of liquid 16.11.3-1. (RIA-35, #3 effluent monitoring Chemical Treatment instrumentation. Short controlled Pond Composite outages are defined as planned Sampler and Sampler removals from service for Flow Monitor (Turbine durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Building Sumps for purposes of sample filter Effluent)) changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

H.1 Suspend release of Immediately radioactive effluents by this pathway.

OR H.2 Collect and analyze Immediately grab samples for gross radioactivity (beta AND and/or gamma) at a lower limit of detection Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1

of at least 10- µCi/ml. thereafter 16.11.3-5 11120,os I 9-30

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required -----------. -----NOTE------------------

Action C.1 and Not required during short; referenced in Table controlled outages of gaseous 16.11.3-2 for effluent effluent monitoring releases from waste gas instrumentation. Short controlled tanks (RIA-37, RIA-38) outages are defined as planned or containment purges removals from service for (RIA-45). durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

1.1.1 Analyze two Prior to initiating independent samples. subsequent release 1.1.2 Conduct two Prior to initiating independent data entry subsequent release checks for release rate

calculations 1.1.3 Conduct two Prior to initiating independent valve subsequent release lineups of the effluent pathway.

OR 1.2 Suspend release of Immediately radioactive effluents by this pathway.

16.11.3-6 . 11120,os I 9-31

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required ---------------NOTE--------------------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (Effluent effluent monitoring Flow Rate Monitor (Unit instrumentation. Short controlled Vent, Containment outages are defined as planned Purge, Interim removals from service for Radwaste Exhaust, Hot durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Machine Shop Exhaust, for purposes of sample filter Radwaste Facility changeouts, setpoint Exhaust, Waste Gas adjustments, service checks, Discharge)) and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

J.1 Suspend release of Immediately radioactive effluents by this pathway.

OR J.2 Estimate flow rate Immediately Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter 16.11.3-7 11120,os I 9-32

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME K. As required by Required -----------------NOTE------------------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (RIA-45, effluent monitoring RIA-53, 4RIA-45) instrumentation. Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.

K.1 Suspend release of Immediately radioactive effluents by this pathway.

OR K.2.1 Collect grab sample. Immediately Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months K.2.2 Analyze grab samples 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from collection for gross activity (beta of sample and/or gamma).

16.11.3-8 11120108 I 9-33

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME L. As required by Required -----------------NOTE------------------

Action C.1 and N ot required during short, referenced in Table controlled ou_tages of gaseous 16.11.3-2. (Unit Vent effluent monitoring Monitoring Iodine instrumentation. Short controlled Sampler, Unit Vent outages are defined as planned Monitoring Particulate removals from service for Sampler, Interim durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Radwaste Building for purposes of sample filter '

Ventilation Monitoring changeouts, setpoint Iodine Sampler, Interim adjustments, service checks Radwaste Building and/or routine maintenance '

Ventilation Monitoring procedures. This guidance may Particulate Sampler, Hot be applied successively, Machine Shop Iodine provided that time between Sampler, Hot Machine successive short, controlled Shop Particulate outages is always at least equal Sampler, Radwaste to duration of immediately Facility Iodine Sampler, preceding outage.

Radwaste Facility Particulate Sampler)

L.1 Suspend release of Immediately radioactive effluents by this pathway.

OR L.2.1 -----------NOTE-----------

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

Collect samples Immediately continuously using auxiliary sampling equipment.

AND L.2.2 Analyze each sample. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from end of each sample collection 16.11.3-9 11120108 I 9-34

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME M. As required by Required -----------------NOTE------------------

Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2 for effluent effluent monitoring*

from ventilation system instrumentation. Short controlled or condenser air outages are defined as planned ejectors. (RIA-40) removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 Contfnuously monitor Immediately release through the unit vent.

OR M.2 Suspend release of Immediately radioactive effluents by this pathway.

OR M.3.1 Collect grab sample. Immediately Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months M.3.2 Analyze grab sample for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from collection gross activity (beta of grab sample .

and/or gamma).

16.11.3-10 1112010s I 9-35

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.3.1 ------------------------NO 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 releases are made.

Perform Channel Response Check. During each release via this pathway SR 16.11.3.2 ------------------------NOTE----------------------------

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

Channel response checks shall be made at least once per calendar day on days in which continuous, periodic or batch releases are made.

Perform Channel Response Check. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 16.11.3.3 Perform Source Check. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 16.11.3.4 Perform Source Check. 31 days SR 16.11.3.5 Perform Source Check. 92 days 16.11.3-11 1112010a I 9-36

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE FREQUENCY SR 16.11.3.6 -----------------------NOTE----------------------------

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following c:'onditions exist:

1. Instrument indic:;ates measured levels above the alarm/trip setpoint.

2. Circuit failure (downscale only).

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 16.11.3.7 ------------------------NOTE----------------------------

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure (downscale only).

92 days Perform CHANNEL FUNCTIONAL TEST.

SR 16.11.3.8 Perform CHANNEL FUNCTIONAL TEST. 92 days 16.11.3-12 11120108 I 9-37

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE FREQUENCY SR 16.11.3.9 -------------------------NOTE---------------------------

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have*been obtained from suppliers that participate in measurement assurance activities with the National Institute of Standards and Technology (NIST). The standards shall permit calibrating the system over its intended range of energy and measurement. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (Operating plants may substitute previously established calibration procedures for these requirements.)

12 months Perform CHANNEL CALIBRATION.

SR 16.11.3.10 Perform CHANNEL CALIBRATION. 12 months SR 16.11.3.11 Perform leak test. When cylinder gates or wicket gates are reworked SR 16.11.3.12 Perform Source Check. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to each release via associated pathway 16.11.3-13 1112010a I 9-38

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABILITY REQUIREMENTS ACTION B.1

1. Monitors Providing Automatic Termination of Release

a. Liquid Radwaste Effluent At all times SR 16.11.3.1 E Line Monitor, RIA-33 SR 16.11.3.3 SR 16.11.3.6 SR 16.11.3.9

b. Turbine Building Sump, At all times SR 16.11.3.2 F RIA-54 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9

2. Monitors not Providing Automatic Termination of Release Low Pressure Service Water At all times SR 16.11.3.2 H RIA-35 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9

3. Flow Rate Measuring Devices

a. Liquid Radwaste Effluent At all times SR 16.11.3.1 G Line Flow Rate Monitor SR 16.11.3.10 (OLW CR0725 or OLW SS0920)

b. Liquid Radwaste Effluent NA NA SR 16.11.3.1 NA Line Minimum Flow SR 16.11.3.10 Device

c. Turbine Building Sump NA NA SR 16.11.3.1 NA Minimum Flow Device SR 16.11.3.10

d. Low Pressure Service NA NA SR 16.11.3.1 NA Water Minimum Flow SR 16.11.3.10 Device 16.11.3-14 11120,os I 9-39

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABILITY REQUIREMENTS ACTION B.1

e. Keowee Hydroelectric NA NA SR 16.11.3.11 NA Tailrace Discharge<*>

4. Continuous Composite Sampler

3 Chemical Treatment At all times SR 16.11.3.2 H Pond Composite Sampler SR 16.11.3.10 and Sampler Flow Monitor (Turbine Building Sumps Effluent)

(a) Flow is determined from the number of hydro units operating. If no hydro units are operating, leakage flow will be assumed to be 38 cfs based on historical data.

16.11.3-15 11120,os I 9-40

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE SURVEILLANCE REQUIRED INSTRUMENT PATH) APPLICABILITY REQUIREMENTS ACTION C.1

1. 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 Purge Isolation Function)

b. Noble Gas Activity At all times SR 16.11.3.2 K Monitor Providing Alarm. SR 16.11.3.4 (RIA 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 L

d. Particulate Sampler At All Times SR 16.11.3.2 L

.e. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Unit Vent Flow) SR 16.11.3.10 (MSC CR0001)

f. Sampler Flow Rate At All Times SR 16.11.3.2 NA Monitor<*> (Annunciator) SR 16.11.3.10

g. Effluent Flow Rate During Containment SR 16.11.3.2 J Monitor (Containment Purge Operation SR 16.11.3.10 Purge)(MSC CR0001)

h. CSAE Off Gas Monitor During Operation SR 16.11.3.2 M (RIA-40) ofCSAE SR 16.11.3.5 SR 16.11.3.8 SR 16.11.3.9

2. Interim Radwaste Building Ventilation Monitoring System

a. Noble Gas Activity At All Times SR 16.11.3.2 K 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 L C. Particulate Sampler At All Times SR 16.11.3.2 L

d. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Interim SR 16.11.3.10 Radwaste Exhaust)

(GWD FT0082)

e. Sampler Flow Rate At All Times SR 16.11.3.2 NA Monitor<*/ (Annunciator)

SR 16.11.3.10 16.11.3-16 1.112010a I 9-41

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE ,SURVEILLANCE REQUIRED INSTRUMENT PATH) APPLICABILITY REQUIREMENTS ACTION C.1

3. Hot Machine Shop Ventilation Sampling System

a. Iodine Sampler At All Times SR 16.11.3.2 L

b. Particulate Sampler At All Times SR 16.11.3.2 L C. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Hot Machine SR 16.11.3.10 Shop Exhaust)

(Totalizer)

d. Sampler Flow Rate At All Times SR 16.11.3.2 NA Monitor <*l (Annunciator) SR 16.11.3.10

4. Radwaste Facility Ventilation Monitoring System

a. Noble Gas Activity At All Times SR 16.11.3.2 K Monitor (4-RIA-45) SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9

b. Iodine Sampler At All Times SR 16.11.3.2 L C. Particulate Sampler At All Times SR 16.11.3.2 L

d. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Radwaste SR 16.11.3.10 Facility Exhaust) (OVS CR2060)

e. Sampler Flow Rate At All Times SR 16.11.3.2 NA Monitor <*l (Annunciator) SR 16.11.3.10

5. Waste Gas Holdup Tanks

a. Noble Gas Activity During Waste Gas SR 16.11.3.1 Monitor - Providing Holdup Tank Releases SR 16.11.3.6 Alarm and Automatic SR 16.11.3.9 Termination of Release SR 16.11.3.12 (RIA-37,-38)b

b. Effluent Flow Rate During Waste Gas SR 16.11.3.1 J Monitor (Waste Gas Holdup Tank Releases SR 16.11.3.10 Discharge Flow) (MSC CR0001)

(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 11120,os I 9-42

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRG 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 radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarm/trip will occur prior to exceeding applicable dose limits in SLC 16.11.2. The operability end use of this instrumentation is consistent 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months end every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ), Action is not required.

Failures such as blown instrument fuses, defective indicators, and faulted amplifiers are, in many cases, revealed by alarm or annunciator action. Comparison of output and/or state of independent channels measuring the same variable supplements this type of built-in surveillance. Based on experience in operation of both conventional and nuclear systems, when the unit is in operation, the minimum checking frequency stated is deemed adequate.

REFERENCES:

1. 10 CFR Part 20.

2. 10 CFR Part 50, Appendix A.

3. Of~site Dose Calculation Manual.

4. UFSAR, Section 7.2.3.4.

16.11.3-18 11120108 I 9-43

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Operational Safety Review 16.11.4 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.4 Operational Safety Review COMMITMENT Required sampling should be performed as detailed in Table 16.11.4-1.

APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.4.1 N/A N/A 16.11.4-1 06130114 I 9-44

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection of Lab Analysis for Waste

1. Decant Monitor a. Principal Gamma Composite Grab Sample <5E-06 µCi/ml (Ce-144)
Tank, Turbine Emitters<c) including prior to release of each <5E-07 µCi/ml (Other Gamma Nuclides)
Building Sump Dissolved Noble batch<h> <1E-05 µCi/ml (Dissolved Gases)
Monitor Tanks, Gases <1E-06 µCi/ml (l-131)
Waste and Recycle MonitorTanks
b. Radiochemical Quarterly from all <5E-08 µCi/ml Analysis Sr-89 and composited batches<n Sr-90
c. Tritium Monthly Composite <1 E-05 µCi/ml
d. Gross Alpha Activity Monthly Composite <1E-07 µCi/ml
2. Unit Vent Sampling a. Iodine Spectrum<a> Continuous monitor, <1E-10 µCi/cc (1-133)0>
(Includes Waste weekly sample<*> <1E-12 µCi/cc (l-131)0>
Gas Decay Tanks, Reactor Building Purges, Auxiliary b. Particulates<*)
Building Ventilation, Spent Fuel Pool i. Ce-144 & Mo-99 Weekly Composite<*) <5E-10 µCi/ccU><k>
Ventilation, Air Ejectors) ii. Other Principle Weekly Composite<*> < 1E-11 µCi/ccm Gamma Emitters (d) iii. Gross Alpha Monthly, using composite <1E-11 µCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 µCi/cc Analysis Sr-89, Sr-90 C. Gases by Principle Weekly Grab Sample <1 E-04 µCi/cc Gamma Emitters<d>
d. Tritium Weekly Grab Sample <1 E-06 µCi/cc
3. Waste Gas Decay a. Principle Gamma Grab Sample prior to <1 E-04 µCi/cc (gases)
Tank Emitters<d> release of each batch <1 E-1 O µCi/cc (particulates and iodines)
<5E-09 µCi/cc (Ce-144 and Mo-99)
b. Tritium Grab Sample prior to <1 E-06 µCi/cc release of each batch
4. Reactor Building a. Principle Gamma Grab sample each purge <1E-04 µCi/cc (gases)
Emitters<dJ <1E-10 µCi/cc (particulates and iodines)
<5E-09 µCi/cc (Ce-144 and Mo-99)
b. Tritium Grab sample each purge <1 E-06 µCi/cc 16.11.4-2 06/30/14
g-45
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection<b) of Lab Analysis for Waste
5. Not Used
6. #3 Chemical a. Principle Gamma Weekly Continuous <5E-07 µCi/ml Treatment Pond Emitters<0l Composite<9l Effluent<0
b. 1-131 Weekly Continuous <1 E-06 µCi/ml Composite<9l
c. Tritium Monthly Continuous <1E-05 µCi/ml Composite<9l
d. Gross Alpha Monthly Continuous <1 E-07 µCi/ml Activity Composite<9l
e. Sr-Bg & Sr-go Quarterly Continuous <5E-08 µCi/ml Composite<9l
f. Dissolved and Monthly Grab <1 E-05 µCi/ml Entrained gases (Gamma Emitters)
7. Radwaste Facility a. Iodine Spectrum<*> Continuous monitor, (l-133) <1E-Qg µCi/cc Ventilation weekly sample<*) (l-131) <1E-11 µCi/cc
b. Particulate<*)
i. Ce-144 and Mo- Weekly Composite<*) <5E-10 µCi/ccm gg ii. Other Principle Weekly Composite<*> < 1E-11 µCi/ccOl Gamma Emitters<dl iii. Gross Alpha Monthly, using composite <1 E-11 µCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1 E-11 µCi/cc Analysis Sr-Bg, Sr-go C. Gases by Weekly Grab Sample <1 E-04 µCi/cc Principle Gamma<dl Emitters
d. Tritium Weekly Grab Sample <1 E-06 µCi/cc 16.11.4-3 06/30/14 9-46
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection(b) of Lab Analysis for Waste
8. Hot Machine Shop a. Iodine Spectrum Weekly Sample(*> (1-133) <1E-10 µCi/cc(J)
Ventilation (l-131) <1E-12 µCi/cc(J)
b. Particulate
i. Ce-144 and Mo- Weekly Composite(*> <5E-10 µCi/cc(J)(k) gg ii. Other Principle Weekly Composite<*> < 1E-11 µCi/ccO>
Gamma Emitters (d) iii. Gross Alpha Monthly, using composite <1E-11 µCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 µCi/cc Analysis Sr-89, Sr-90 C. Gases by NA NA Principle Gamma Emitters
d. Tritium NA NA
9. Interim Radwaste a. Iodine Spectrum Weekly sample(*> (1-133) <1E-10 µCi/ccO>
Building (1-131) <1 E-12 µCi/cc(J)
Ventilation
b. Particulate
i. Ce-144 and Mo- Weekly Composite(*> <5E-10 µCi/cc 0>
gg
< 1E-11 µCi/ccO>
ii. Other Principle Weekly Composite<*>
Gamma Emitters(d) iii. Gross Alpha Monthly, using composite <1 E-11 µCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 µCi/cc Analysis Sr-89, Sr-90 C. Gases by Weekly Grab Sample <1 E-04 µCi/cc Principle Gamma<d>
Emitters
d. Tritium Weekly Grab Sample <1E-06 µCi/cc 16.11.4-4 06/30/14 9-47
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 / T) + 4.65 Sb E x V x 2.22E06 x Y x exp (-Mt)
Where:
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),
Eis the counting efficiency (as counts per disintegration),
Vis the sample size (in units of mass or volume),
2.22E06 is the number of disintegrations per minute per micro Curie, Y is the fractional radiochemical yield (when applicable),
" is the radioactive decay constant for the particular nuclide
!J. tis 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.
T is the sample counting time in minutes Typical values of E, V, Y and !J. t 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 9-48
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (on or after removal from sampler).
0) When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. Samples shall be analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (on or after removal from sampler).
(k) Ce-144 and Mo-99 LLD as approved by NRC SER dated January 16, 1984 (Reference 1).
16.11.4-6 06/30/14 9-49
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 06130114 I
9-50
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 9-51
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Solid Radioactive Waste 16.11.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Applicable regulatory A.1 Suspend shipments of Immediately requirements for defectively packaged solidified or dewatered solid radioactive wastes wastes are not from the site.
satisfied.
AND A.2 Initiate action to correct Prior to next shipment for PCP, procedures, or disposal of solidified or solid waste equipment dewatered wastes as necessary to prevent recurrence.
8. A solidification test as 8.1 Suspend solidification of Immediately described in the PCP the batch under test and fails to verify follow PCP guidance for Solidification. test failures until solidification of the batch is verified by subsequent tests.
AND 8.2 The PCP shall be Prior to next solidification modified as required to for shipment of waste for assure Solidification of disposal at a 10 CFR 61 subsequent batches of disposal site waste.
16.11.5-2 10130102 I 9-52
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Solid Radioactive Waste 16.11.5 CONDITION REQUIRED ACTION COMPLETION TIME C. With solidification or C.1 Reprocess or repackage Prior to shipment for dewatering for disposal the waste in accordance disposal of the not performed in with PCP requirements. inadequately processed accordance with the waste that requires PCP. OR solidiffcation or dewatering C.2 Follow PCP or procedure guidance for alternative free standing liquid verification to ensure the waste in each container meets disposal requirements and take appropriate administrative action to prevent recurrence.
D. With the solid waste D.1 Restore the equipment to In a time frame that equipment incapable of OPERABLE status or supports the meeting commitment or provide for alternative commitment not in service. capability to process wastes as necessary to satisfy all applicable disposal requirements.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.5.1 The Process Control Program shall be used Every tenth batch of each to verify the solidification of at least one type of radioactive waste representative test specimen from at least to be solidified.
every tenth batch of each type of radioactive waste to be solidified for disposal at a 10 CFR 61 disposal site.
16.11.5-3 10130102 I 9-53
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 10CFR61 waste form criteria for solidified and dewatered radioactive wastes.
REFERENCES:
1. 10 CFR Part 50, "Domestic Licensing of. Production and Utilization Facilities".
2. 10 CFR Part 50, Appendix A.
3. 10 CFR20, "Standards for Protection Against Radiation".
4. 10 CFR61, "Licensing 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 Co'ntrols 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 9-54
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.6 Radiological Environmental Monitoring COMMITMENT a. The radiological environmental monitoring samples shall be collected in accordance with Table 16.11.6-1 and shall be analyzed pursuant to the requirements of Tables 16.11.6-1 and 16.11.6-2.
b. A land use census shall be conducted and shall identify the location of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of eight kilometers (five miles). Broad leaf vegetation sampling shall be performed at the site boundary in the direction sector with the highest 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---------------------------------------------

1f 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.
APPLICABILITY: At.all times 16.11.6-1 111a113 I 9-55
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A Radiological A.1 Submit a description of May 15 of following environmental the reason for not calendar year monitoring program is conducting the program not conducted as as required and plans to required. prevent a recurrence shall be included in the Annual Radiological Environmental Operating Report.
B. Land use census B.1 -----------NOTE-----------
identifies a Location The sampling location which yields a having the lowest calculated dose or dose calculated dose or dose commitment (via the commitment (via the same exposure same exposure pathway) 20% greater pathway) may be than a location from deleted from this which samples are monitoring program currently being after October 31 of the obtained. year in which this land use census was conducted.
Add new location to the 30 days radiological environmental monitoring program.
AND B.2 Identify new locations in April 30 of following the next Annual calendar year Radioactive Effluent Release Report.
16.11.6-2 11,a,13 I 9-56
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Interlaboratory C.1 Report corrective May 15 of following Comparison Program actions in the Annual calendar year analyses not performed Radiological as required. Environmental Operating Report.
D. Radioactivity level D.1 Prepare and submit a 30 days resulting from plant Special report that effluents in identifies the cause for environmental sampling exceeding the limits and medium at a specified defines the corrective location in excess of actions to be taken to reporting limits of Table reduce radioactive 16.11.6-3 when effluents so that the averaged over a potential annual dose to calendar quarter. a MEMBER OF THE PUBLIC is less than the calendar year limits of SLC 16.11.1 or 16.11.2.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.6.1 Conduct land use census during growing 12 months season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.
16.11.6-3 111s113 I 9-57
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Number of Exposure Pathway and/or Sampling and Collection Sample Time and Frequency of Analysis Sample Frequency (d)
Locations (b)
1. AIRBORNE Radioiodine and 5 Continuous sampler Radioiodine canister:
Particulates operation with sample 1-131 analysis weekly. Particulate collection weekly, or sampler: Gross beta radioactivity more frequently if analysis following filter change; and required by dust loading. gamma isotopic analysis of composite (by location) quarterly. (c)
2. DIRECT RADIATION 40 Quarterly. Gamma dose quarterly.
3. WATERBORNE
a. Surface 2 Composite (a) sample Gamma isotopic analysis monthly.
over a 1-month period.
Composite for tritium analysis quarterly.
b. Drinking 3 Composite (a) sample Composite for gross beta and gamma over a 1-month period. isotopic analyses monthly.
Composite for tritium analysis quarterly.
c. Sediment from 2 Semiannually. Gamma isotopic analysis Shoreline semiannually.
16.11.6-4 111a113 I 9-58
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Number of Exposure Pathway and/or Sampling and Collection Sample Time and Frequency of Analysis Sample Frequency (d)
Locations (b)
4. INGESTION
a. Milk 4(e) Semimonthly when Gamma isotopic and 1-131 analysis animals are on pasture; semimonthly when animals are on monthly at other times. pasture; monthly at other times.
b. Fish 2 Semiannually. One Gamma isotopic analysis sample each semiannually on edible portion.
commercially and recreationally important species.
c. Broad-leaf 2 Monthly. Gamma isotopic analysis monthly.
Vegetation (a) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
(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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 11,a,13 I 9-59
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)
Airborne Fish Broad-leaf Water Particulate or Milk Sediment Analysis Vegetation Gases (pCi/kg, (pCi/1) (pCi/1) (pCi/kg, dry) 3 wet) (pCi/kg, wet)
Ci/m Gross Beta 4 1E-02 H3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 15 Nb-95 15 1-131 15(b) ?E-02 60 Cs-134 15 5E-02 130 15 60 150 Cs-137 18 6E-02 150 18 80 180 Ba-140 15 60 La-140 15 15 (a) The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample with 95% probability of detection and 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 IT) + 4.65 Sb E xV x 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 9-60
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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)
'A is the radioactive decay constant for the particular radionuclide 11 tis 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 11 t should be used in the calculation.
The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances, may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual 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 pCi/liter of 1-131 in drinking water. For low level analyses of 1-131 an LLD of 1 pCi/liter will be achieved.
(c) Other peaks which are measurable and identifiable, together with the radionuclides in Table 16.11.6-2, shall be identified and reported.
16.11.6-7 111s113 I 9-61
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples (c) (d)
Airborne Broad-leaf Water Particulate or Fish Milk Analysis Vegetation Gases (pCi/1) (pCi/kg, wet) (pCi/1) 3 (pCi/kg, wet)
Ci/m H-3 2E04(a)
Mn-54 1 E03 3E04 Fe-59 4E02 1E04 Co-58 1E03 3E04 Co-60 3E02 1E04 Zn-65 3E02 2E04 Zr-Nb-95 4E02 1-131 2(b) 0.9 3 1E02 Cs-134 30 10 1E03 60 1E03 Cs-137 50 20 2E03 70 2E03 Ba-La-140 2E02 3E02 (a) For drinking water samples. This is 40 CFR Part 141 value.
(b) If low level 1-131 analyses are performed.
(c) Report shall be submitted when any single radionuclide exceeds the reporting level in Table 16.11.6-3 or when more than one of the radionuclides in Table 16.11.6-3 are detected in sampling medium and concentration (1) + concentration (2) + ... .:: 1.0 reporting level (1) reporting level (2)
(d) Report shall be submitted when radionuclides other than those in table 16.11.6-3 are detected and are the result of plant effluents if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of SLC 16.11.1 or 16.11.2.
16.11.6-8 1118113 I 9-62
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 111/2017 -12/3112017 Radiological Environmental Monitoring 16.11.6 BASES 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 requirements for participation in an lnterlaboratory Comparison Program is provided to assure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
With the level of radioactivity in an environmental sampling medium at a specified location exceeding the reporting levels of Table 16.11.6-3 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days a Special Report that defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of SLC 16.11.1 or SLC 16.11.2. When more than one of the radionuclides in Table 16.11.6-3 are detected in the sampling medium, this report shall be submitted if concentration (1) + concentration (2) + ... ~ 1. 0 reporting level (1) reporting level (2)
When radionuclides other than those in Table 16.11.6-3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of SLC 16.11.1 or SLC 16.11.2. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2. The methodology and parameters used to estimate the potential annual dose to a MErv]BER OF THE PUBLIC shall be indicated in the 30-day Special Report.
16.11.6-9 111a113 I 9-63
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 9-64
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Dose Calculations 16.11.7 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.7 Dose Calculations COMMITMENT The annual (calendar year) dose or dose commitment, to any Member- of the Public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to ::; 25 mrems to the total body or to any organ, except the thyroid, which shall be limited to::; 75 mrems.
APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A Calculated doses from A.1 Determine by None the release of calculation, including radioactive materials in direct radiation liquid or gaseous contributions from the effluents exceeding reactor units and from twice the limits of SLC outside storage tanks, 16.11.1.b, SLC whether the limits of 16.11.2.b.1, or SLC Commitment 16.11. 7 16.11 .2.b.2 have been exceeded.
16.11.7-1 01131100 I 9-65
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Dose Calculations 16.11.7 CONDITION REQUIRED ACTION COMPLETION TIME
8. Calculated dose -------------------N OT E----------------
exceeds limits of T his Special Report, as defined Commitment 16.11.7. in 10 CFR Part 20.2203(a), shall include an analysis that estimates the radiation exposure (dose) to a Member of the Public from uranium fuel cycle sources, (including all effluent pathways and direct radiation), for the calendar year that includes the release(s) covered by this report.
It shall also describe the levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations.
8.1 Prepare and submit to the Commission a 30 days Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the specified limits and includes the schedule for achieving conformance with the specified limits.
16.11.7-2 01131100 I 9-66
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 Determine cumulative dose contributions from 31 days liquid effluents in accordance with Offsite Dose Calculation Manual.
SR 16.11.7.2 Determine cumulative dose contributions from 31 days gaseous effluents in accordance with Offsite Dose Calculation Manual.
BASES 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 ac.hievable." 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 9-67
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Dose Calculations 16.
11.7 REFERENCES
1. 10 CFR Part 20.
2. 40 CFR Part 190.
3. Offsite Dose Calculation Manual.
4. 10 CFR Part 50, Appendix I.
16.11. 7-4 01131100 I 9-68
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Reports 16.11.8 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.8 Reports COMMITMENT Special reports shall be submitted to the Regional Administrator, Region II, 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 REQUIRED ACTION COMPLETION TIME A. Individual milk samples A.1 Submit plan advising 7 days show 1-131 the NRC of the concentrations of 1O proposed action to picocuries per liter or ensure the plant related greater. annual doses will be within the design objective of 45 mrem/yr to the thyroid of any individual.
16.11.8-1 1212110s I 9-69
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Reports 16.11.8 CONDITION REQUIRED ACTION COMPLETION TIME B. Milk samples collected B.1 Submit a plan advising 30 days over a calendar quarter the NRC of the show 1-131 average proposed action to concentrations of 4.8 ensure the plant related picoCuries per liter or annual doses will be greater within the design objective of 45 mrem/yr to the thyroid of any individual.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.8.1 NA 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 12121109 I 9-70
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 efflu'ents 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 riot corrected in a timely manner per SLC 16.11.3.
- 16.11.9-1 03122110 I 9-71
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 9-72
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Release Report 16.11.9 I
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. N/A 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.
16.1.1.9-3 03122110 I 9-73
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 obtained 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 characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and, the result of land use censuses. Subsequent reports shall describe all substantial changes in these aspects.
APPLICABILITY: At all times.
16.11.10-1 05114114 I 9-74
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 1 Radiological Environmental Operating Report 16.11.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.10.1 NA NA BASES NA
REFERENCES:
1. Oconee ITS
2. Offsite Dose Calculation Manual 16.11.10-2 05114114 I 9-75
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Iodine Radiation Monitoring filters 16.11.11 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.11 Iodine Radiation Monitoring Filters COMMITMENT Assure that the iodine radiation monitoring filters perform their intended function.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.11.1 Remove and replace iodine radiation 30 days of operation monitoring filters in RIA-44.
SR 16.11.11.2 Discard spare iodine radiation monitoring After 24 months of shelf filters. life.
BASES 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 9-76
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Material in Outside Temporary Tanks Exceeding Limit 16.11.12 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.12 Radioactive Material in Outside Temporary Tanks Exceeding Limit COMMITMENT The quantity of radioactive material in outside temporary storage tanks shall not exceed the limit specified in ITS 5.5.13.c.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The quantity of A.1 Suspend addition of Immediately radioactive material in radioactive material to outside temporary tank.
storage tank not within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.12.1 Verify the quantity of radioactive material Within 7 days after contained in each of the outside temporary addition of radioactive tanks is within the limit by analyzing a materials to an representative sample of the tanks' contents. outside temporary tank OR Verify the quantity of radioactive material in Prior to addition of each of the outside temporary tanks does not radioactive materials to result in exceeding the limit by analyzing a an outside temporary representative sample of radioactive material tank.
to be added.
16.11.12-1 04110103 I 9-77
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Material in Outside Temporary Tanks Exceeding Limit 16.11.12 BASES 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 10CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
REFERENCES N/A 16.11.12-2 04110103 I 9-78
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 COMPLETION TIME A. The quantity of A.1 Suspend addition of Immediately radioactive material in radioactive material to the Waste Gas Holdup tank.
tank not within limit.
AND A.2 Reduce tank contents 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.13.1 Verify quantity of radioactive materials in each 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when tank is tank is within limit. being filled BASES 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 9-79
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 9-80
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1;, 2, & 3 Period 1/1/2017 -12/31/2017 Explosive Gas Mixture 16.11.14 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.14 Explosive Gas Mixture COMMITMENT The concentration of Hydrogen in the Waste Gas Holdup Tanks shall be
~ 3% by volume.
APPLICABILITY: At all times.
ACTIONS

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

Separate Condition Entry is allowed for each tank.
CONDITION REQUIRED ACTION COMPLETION TIME A Concentration of A.1 Reduce Concentration 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Hydrogen in Waste of Hydrogen to within Gas Holdup tank is> limit.
3% and~ 4% by volume.
B. Concentration of B.1 Suspend addition of Immediately Hydrogen in Waste waste gases to tank.
Gas Holdup tank is >
4% by volume. AND B.2 Reduce Concentration 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of Hydrogen to within limit.
16.11.14-1 03/27/99 9-81
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Explosive Gas Mixture 16.11.14 SURVEILLANCE REQUIREMENTS S.URVEILLANCE FREQUENCY SR 16.11 .14.1 Verify Hydrogen concentration in Waste Gas 5 times/week on each Holdup Tank is~ 3% by volume. tank when in service once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after isolation of the tank BASES 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 9-82
Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 ATTACHMENT 10 Summary of Changes to the Process Control Program This attachment includes a summary of changes to the PCP.
Page 10-1
Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 The Oconee Nuclear Station PCP was not revised in 2017. 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 1/1/2017 - 12/31/2017 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 1/1/2017 - 12/31/2017 No major modifications to Oconee Nuclear Station *liquid, gaseous, solid, or mobile radioactive waste treatment systems occurred in 2017.
Page 11-2
Attachment 12 Errata to a Previous Year's ARERR Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 ATTACHMENT 12 Errata to a Previous Year's ARERR This attachment includes any amended pages from a previous year's ARERR.
Page 12-1
Attachment 12 Errata to a Previous Year's ARERR Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 There is one (1) change to a previous year's ARERR.
The following contains amended pages to the Oconee Nuclear Station 2016 ARERR. Amended pages are identified with "Amendment#" on page. Specific changes are' identified with change bars in right margin.
The Oconee Nuclear Station 2016 ARERR Amendment #1 requires the following changes to Attachment 1 (Reference NCR 02139552).
Oconee Nuclear Station 2016 ARERR Attachment 1 Page 1-2 as submitted:
B. lodine-131
1. Total Release Ci O.OOE+OO O.OOE+OO 0.00E+OO 4.92E-10 4.92E-10
2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO 6.19E-11 1.56E-11 Oconee Nuclear Station 2016 ARERR Attachment 1 Page 1-2 Amendment #1 as revised:
B. lodine-131
1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.92E-09 4.92E-09
2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO 6.19E-10 1.56E-10 Oconee Nuclear Station 2016 ARERR Attachment 1 Page 1-4 as submitted:
B. Iodines 1-131 Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.92E-10 4.92E-10 1-133 Ci O.OOE+OO 8.22E-10 O.OOE+OO 4.84E-10 1.31 E-09 Total for Period Ci O.OOE+OO 8.22E-10 0.00E+OO 9.76E-10 1.80E-09 Oconee Nuclear Station 2016 ARERR Attachment 1 Page 1-4 Amendment #1 as revised:
B. Iodines 1-131 Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.92E-09 4.92E-09 1-133 Ci O.OOE+OO 8.22E-10
O.OOE+OO 4.84E-10 1.31 E-09 Total for Period Ci O.OOE+OO 8.22E-10 O.OOE+OO 5.41 E-09 6.23E-09 Page 12-2
Attachment 12 Errata to a Previous Year's ARERR Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2016 ~ 12/31/2016 Gaseous Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases
1. Total Release Ci 1.06E+OO . 2.56E+OO 7.60E+OO 9.71E+OO 2.09E+01
2. Avg. Release Rate µCi/sec 1.35E-01 3.26E-01 9.57E-01 1.22E+OO 6.62E-01
8. lodine-131
1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.92E-09 4.92E-09
2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO 6.19E-10 1.56E-10 C. Particulates Half-Life::: 8 days
1. Total Release Ci O.OOE+OO 1.74E-10 1.58E-10 O.OOE+OO 3.32E-10
2. Avg. Release Rate µCi/sec O.OOE+OO 2.22E-11 1.98E-11 O.OOE+OO 1.05E-11 D. Tritium
1. Total Release Ci 3.07E+01 3.08E+01 2.23E+01 4.93E+01 1.33E+02
2. Avg. Release Rate µCi/sec 3.90E+OO 3.92E+OO 2.81 E+OO 6.20E+OO 4.21E+OO E. Carbon-14
1. Total Release Ci 5.54E+OO 5.52E+OO 6.02E+OO 5.60E+OO 2.27E+01
2. Avg. Release Rate µCi/sec 7.05E-01 7.02E-01 7.57E-01 7.05E-01 7.18E-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+OO O.OOE+OO Page 1-2 Oconee Nuclear Station 2016 ARERR Attachment 1 Amendment #1 Page 12-3
Attachment 12 Errata to a Previous Year's ARERR Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2016-12/31/2016 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 1.61E-02 2.37E-02 2.44E-04 4.01E-02 KR-85M Ci O.OOE+OO 6.78E-05 4.27E-06 O.OOE+OO 7.20E-05 KR-88 Ci O.OOE+OO 5.42E-05 O.OOE+OO O.OOE+OO 5.42E-05 XE-131M Ci O.OOE+OO O.OOE+OO 1.15E-04 2.33E-04 3.49E-04 XE-133 Ci 2.16E-03 7.59E-02 1.48E-02 4.40E-02 1.37E-01 XE-133M Ci O.OOE+OO 4.99E-04 1.76E-04 3.58E-04 1.03E-03 XE-135 Ci 1.14E-06 4.89E-03 3.74E-04 6.71E-04 5.93E-03 XE-138 Ci O.OOE+OO O.OOE+OO 8.81E-04 O.OOE+OO 8.81E-04 Total for Period Ci
2.16E-03 9.75E-02 4.01E-02 4.70E-02 1.85E-01 B. Iodines 1-131 Ci 0.00E+OO O.OOE+OO O.OOE+OO 4.92E-09 4.92E-09 1-133 Ci O.OOE+OO 8.22E-10 O.OOE+OO 4.84E-10 1.31 E-09 Total for Period Ci O.OOE+OO 8.22E-10 O.OOE+OO 5.41E-02 6.23E-09 C. Particulates Half-Life .:: 8 days C0-58 Ci O.OOE+OO 1.74E-10 O.OOE+OO O.OOE+OO 1.74E-10 CS-137 Ci O.OOE+OO O.OOE+OO 1.58E-10 O.OOE+OO 1.58E-10 Total for Period Ci O.OOE+OO 1.74E-10 1.58E-10 O.OOE+OO 3.32E-10 D. Tritium H-3 Ci 3.31E-05 2.19E-02 4.23E-02 1.29E-01 1.93E-01 E. Carbon-14 C-14 .Ci. 3.88E+OO 3.86E+OO 4.21E+OO 3.92E+OO 1.59E+01 F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO
70% of total C-14 released is assumed to be in batch mode. See Attachment 2, Supplemental Information, of this report.
Page 1-4 Oconee Nuclear Station 2016 ARERR Attachment 1 Amendment #1 Page 12-4
ef,DUKE. Johnny R. Dills Plant Manager
~;ENERGY Oconee Nuclear Station Duke Energy ON01VP I 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.6413 f: 864.873.4208 John.Dills@duke-energy.com ONS-2018-024 April 30, 2018 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 2017 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, 2017, through December 31, 2017. No changes were made to the Offsite Dose Calculation Manual (ODCM) during this period, therefore, a copy is not included.
Any questions concerning this report should be directed to Kay Brocklesby at 864-873-6661.
Johnny R. Dills Plant Manager Oconee Nuclear Station*
Attachments ( 12) www.duke-energy.com
U.S. Nuclear Regulatory Commission 2017 Annual Radioactive Effluent Release Report April 30, 2018 Page2 xc (with attachments):
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 Mr. Stephen Koenick, Project Manager (by electronic mail only)
U.S. Nuclear RegulatQry Commission 11555 Rockville Pike Mail Stop OWFN/8F-14 Rockville, MD 20852 I
Ms. Susan E. Jenkins, Manager (by electronic mail only)
Radioactive & Infectious Waste Management SC Department. of Health and Environmental 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. Anuradha Nair Gimmi, Manager Nuclear Response and Emergency Environmental Surveillance Division of Emergency Response S.C. Dept. of Health & Environmental Control 2600 Bull Street Columbia, SC 29201-1708
(~DUKE .
~ ENERGY Oconee Nuclear Station Units 1, 2, and' 3 Annual Radioactive Effluent Release Report January 1, 2017 through December 31, 2017 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 1/1/2017 - 12/31/2017 ATTACHMENT 1 Summary of Gaseous and Liquid Effluents This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.
Page 1-1
Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Gaseous Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases
1. Total Release Ci 3.72E+OO 1.87E+OO 1.40E+OO 6.86E-01 7.68E+OO
2. Avg. Release Rate µCi/sec 4.79E-01 2.38E-01 1.76E-01 8.63E-02 2.44E-01 B. lodine-131
1. Total Release Ci O.OOE+OO O.OOE+OO 5.09E-09 O.OOE+OO 5.09E-09
2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO 6.40E-10 O.OOE+OO 1.61E-10 C. Particulates Half-Life;;: 8 days
1. Total Release Ci p.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 1.33E+01 2.81E+01 3.23E+01 2.82E+01 1.02E+02
2. Avg. Release Rate µCi/sec 1.71E+OO 3.57E+OO 4.06E+OO 3.55E+OO 3.23E+OO E. Carbon-14
1. Total Release Ci 5.90E+OO 6.09~+00 6.01E+OO
5.41E+OO 2.34E+01
2. Avg. Release Rate µCi/sec 7.58E-01 7.75E-01 7.56E-01 6.81 E-01 7.42E-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+OO O.OOE+OO Page 1-2
Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 Gaseous Effluents - Mixed Mode - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases XE-133 Ci 3.70E+OO 1.85E+OO 1.29E+OO 6.14E-01 7.45E+OO Total for Period Ci 3.70E+OO 1.85E+OO 1.29E+OO 6.14E-01 7.45E+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 1.20E+01 2.74E+01 2.70E+01 2.52E+01 9.15E+01 E. Carbon-14 C-14 Ci 1.77E+OO 1.83E+OO 1.80E+OO 1.62E+OO 7.02E+OO F. Gross Alpha Total for Period Ci 0.00E+OO O.OOE+OO O.OOE+O.O O.OOE+OO O.OOE+OO
30% of total C-14 released is assumed to be in continuous mode. See Attachment 2, Supplemental Information, of this report.
_/
Page 1-3
Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Gaseous Effluents - Mixed Mode Releases - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases AR-41 Ci O.OOE+OO 2.24E-02 3.69E-02 9.85E-03 6.92E-02 KR-85M Ci O.OOE+OO O.OOE+OO 3.48E-04 O.OOE+OO 3.48E-04 KR-88 Ci O.OOE+OO O.OOE+OO 3.51E-04 O.OOE+OO 3.51E-04 XE-131M Ci 5.45E-05 O.OOE+OO 1.24E-04 6.36E-05 2.42E-04 XE-133 Ci 2.28E-02 4.87E-03 5.79E-02 5.96E-02 1.45E-01 XE-133M Ci 3.10E-04 O.OOE+OO 8.35E-04 2.02E-04 1.35E-03 XE-135 Ci 7.66E-04 O.OOE+OO 8.23E-03 1.90E-03 1.09E-02 Total for Period Ci 2.40E-02 2.73E-02 1.05E-01 7.17E-02 2.28E-01
8. Iodines 1-131 Ci 0.00E+OO O.OOE+OO 5.09E-09 O.OOE+OO 5.09E-09 Total for Period Ci O.OOE+OO O.OOE+OO 5.09E-09 O.OOE+OO 5.09E-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 7.28E-03 3.02E-02 4.14E-02 2.93E-02 1.0BE-01 E. Carbon-14 C-14 Ci 4.13E+OO 4.26E+OO 4.21E+OO 3.79E+OO 1.64E+01 F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
70% of total C-14 released is assumed to be in batch mode. See Attachment 2, Supplemental Information, of this report.
Page 1-4
Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2,, & 3 Period 1/1/2017-12/31/2017 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 0.00E+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 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Tritium H-3 Ci 1.31E+OO 6.89E-01 5.26E+OO 2.43E+OO 9.68E+OO 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 1/1/2017-12/31/2017 Gaseous Effluents - Ground Releases - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
8. 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 1.50E-02 8.55E-03 1.86E-02 5.41 E-01 5.83E-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 1/1/2017 - 12/31/2017 Liquid Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products *
1. Total Release Ci 2.91E-04 1.61 E-04 O.OOE+OO 8.51E-04 1.30E-03
2. Avg. Diluted Cone. µCi/ml 1.13E-13 3.67E-14 O.OOE+OO 4.40E-13 1.20E-13
3. Batch Releases µCi/ml 3.47E-11 1.90E-11 O.OOE+OO 9.95E-11 3.84E-11 B. Tritium
1. Total Release Ci 2.27E+02 2.00E+02 3.76E+02 2.32E+02 1.03E+03
2. Avg. Diluted Cone. µCi/ml 1.09E-07 6.73E-08 1.44E-07 1.38E-07 1.15E-07
3. Batch Releases µCi/ml 2.71E-05 2.36E-05 4.39E-05 2.71E-05 3.0SE-05 C. Dissolved & Entrained Gases
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 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. Batch Releases liters 1.52E+06 9.77E+05 1.33E+06 2.35E+06 6.18E+06
2. Continuous Releases liters 4.68E+08 5.04E+08 4.67E+08 5.29E+08 1.97E+09 F. Volume of Dilution Water
1. Batch Releases liters 8.37E+09 8.46E+09 8.55E+09 8.55E+09 3.39E+10
2. Continuous Releases liters 8.37E+09 8.46E+09 8.55E+09 **8.55E+09 3.39E+10
Excludes tritium, dissolved and entrained noble gases, and gross alpha.
Page 1-7
Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 1.90E-01 1.95E-01 1.68E-01 1.67E-01 7.19E-01 C. Dissolved & Entrained Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+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 1/1/2017-12/31/2017
\
Liquid Effluents - Batch Mode '
Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products Fe-55 Ci Q;QQE+OO 3.0?E-05 O.OOE+OO O.OOE+OO 3.0?E-05 Co-57 Ci O.OOE+OO 1.09E-06 O.OOE+OO O.OOE+OO 1.09E-06 Co-58 Ci 2.91E-04 9.84E-05 O.OOE+OO 8.51E-04 1.24E-03 Co-60 Ci O.OOE+OO 8.96E-06 O.OOE+OO O.OOE+OO 8.96E-06 Ni-63 Ci O.OOE+OO 1.36E-05 O.OOE+OO O.OOE+OO 1.36E-05 Ag-110m Ci O.OOE+OO 8.16E-06 O.OOE+OO O.OOE+OO 8.16E-06 Total for Period Ci 2.91E-04 1.61 E-04 O.OOE+OO 8.51E-04 1.30E-03 B. Tritium H-3 Ci 2.27E+02 2.00E+02 3.76E+02 2.31E+02 1.03E+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 0,00E+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 1/1/2017 - 12/31/2017 ATTACHMENT 2 Supplemental Information This attachment includes supplemental information to the gaseous and liquid effluents report.
Page 2-1
Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 I. Regulaton! Limits - Per Unit A. Noble Gases - Air Dose
1. Calendar Quarter Gamma Dose =5 mRAD
2. Calendar Quarter Beta Dose = 10 mRAD
3. Calendar Year Gamma Dose = 10 mRAD
4. Calendar Year Beta Dose = 20 mRAD B. Liquid Effluents - Dose
1. Calendar Quarter Total Body Dose = 1.5 mREM
2. Calendar Quarter Organ Dose =5 mREM
3. Calendar Year Total Body Dose =3 mREM
4. Calendar Year Organ Dose = 10 mREM C. Gaseous Effluents - 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 of this attachment.
V. Batch Releases A. Liquid Effluents
1. Total Number of Batch Releases 69
2. Total Time (min) for Batch Releases 1.32E+04
3. Maximum Time (min) for a Batch Release 2.17E+02
4. Average Time (min) for Batch Releases 1.92E+02
5. Minimum Time (min) for a Batch Release 1.29E+02
6. Average Dilution Water Flow During Release (1pm) 6.46E+04 B. Gaseous Effluents
1. Total Number of Batch Releases 77
2. Total Time (min) for Batch Releases 8.87E+04
3. Maximum Time (min) for a Batch Release 1.12E+04
4. Average Time (min) for Batch Releases 1.15E+03
5. Minimum Time (min) for a Batch Release 1.00E+OO VI. Abnormal Releases See Attachment 5, Unplanned Offsite Releases.
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Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 2017 ARERR contains estimates of C-14 radioactivity released in 2017, and estimates of public dose resulting from the C-14 effluent.
Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required (Ref. Reg. Guide 1.21, Rev. 2). The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation (Ref. Reg. Guide 1.21, Rev. 2). Many documents provide information related to the magnitude of C-14 in typical effluents from commercial nuclear power plants. Those documents suggest that nominal annual releases of C-14 in gaseous effluents are approximately 5 to 7.3 curies from PWRs (Ref. Reg. Guide 1.21, Rev. 2). A more recent study recommends a higher C-14 gaseous source term scaling factor of approximately 9.0 to 9.8 Ci/GWe-yr for a PWR (Westinghouse) (Ref. EPRI 1021106). For the Oconee Nuclear Station 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 2017 results in a site total C-14 gaseous release estimate to the environment of 2.34E+01 Curies. 70% of the C-14 gaseous effluent is assumed to be from batch releases (e.g. WGDTs), and 30% of C-14 gaseous effluent is assumed to be from continuous releases through the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14",
2004).
C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. Since the PWR operates with a reducing chemistry, most, if not all, of the C-14 species initially produced are organic (e.g., methane). As a general rule, C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment (e.g. during shutdown or refueling), a slow transformation from an organic to an inorganic chemical form can occur. Various. studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic with an average of 80%
organic with the remainder being CO 2 (Ref. EPRI TR-105715). For the Oconee Nuclear Station 2017 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 2017 is well below the 10CFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit).
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Attachment 2 Supplemental Information Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 1/1/2017-12/31/2017 Summary of Changes in Land Use Census Affecting Effluent Dose Calculations The 2017 Land Use Census was performed May 24-25, 2017, and the results were certified and made available for use on November 7, 2017. The following are changes to residences, gardens, and milk animals from the previous year.
Residences The residence in the SSW sector at 1.36 miles was replaced with a residence at 1.34 miles.
The residence in the SW sector at 1.31 miles was replaced with a residence at 1.27 miles.
Gardens Broad leaf vegetation samples are taken in lieu of a garden census for Oconee Nuclear Station. For dose calculation purposes a garden is assumed to exist at the site boundary and beyond for every sector since a garden location cannot be ruled out.
Milk Animals The milk animal (goat) in the E sector at 3.27 miles was no longer present The milk animal (goat) in the E sector at 4.66 miles is no longer being used for human consumption. Owner still does not wish to participate in REMP.
Environmental Monitoring Locations No changes to environmental monitoring locations in each sector.
Page 2-5
Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 ATTACHMENT 3 Solid Radioactive Waste Disposal This attachment includes a summary of the solid waste shipped off-site for burial and/or disposal, including:
Container volume
Total Curie content
Principal Radionuclides
Source/Type of waste
Solidification agent or absorbent
Type of shipping container
Number of shipments
Other relevant information as necessary Page 3-1
Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 Burial Total Type of Number of Number of Waste Container Solidification Volume Activity Waste Shipped Shipments Containers Class Type Agent (m3) (Curies)
1. Waste from Liquid Systems
a. Dewatered Secondary Resins 3 9 A-U GDP N/A 47.66 2.72E+OO 2 2 A-U Type A N/A 6.81 3.67E+OO
b. Dewatered Primary Resins 2 2 B Type A N/A 6.81 8.93E+01 C Type A N/A 3.41 9.83E+01
c. Evaporator Concentrates None
d. Dewatered Mechanical Filters 2 2 C Type A N/A 6.81 1.04E+01
e. Dewatered Demineralizers None
f. Solidified (cement) Acids, None Oils, Sludge
2. Dry Solid Waste
a. Dry Active Waste None (compacted)
b. Dry Active Waste (non-13 25 A-U GDP N/A 661.49 1.02E+OO compacted)
C. Dry Active Waste (brokered) None
d. Irradiated Components None
3. Total Solid Waste 23 41 732.99 2.05E+02 Page 3-2
Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Type of Waste Shipped Radionuclide % Abundance
1. Waste from Liquid Systems
a. Dewatered Secondary Resins Mn-54 0.073 Co-57 0.03 Co-58 0.20 Co-60 0.86 Cs-137 0.09 Ni-63 2.05 H-3 94.3 C-14 2.05 Sb-124 0.015 Sb-125 0.12 Zn-65 0.025 Tc-99 0.13 Ag-110m 0.13
b. Dewatered Primary Resins Mn-54 2.80 Co-57 0.47 Co-58 13.36 Co-60 11.09 Cs-137 5.56 Cs-134 0.52 Fe-55 19.51 Fe-59 0.01 Ni-63 37.60 H-3 0.46 C-14 5.15 Nb-95 0.025 Be-7 2.09 Ce-144 0.02 Sb-125 0.25 Zr-95 0.17 Sr-89 0.01 Sr-90 0.05 Zn-65 1.00 Tc-99 0.01 Ni-59 0.021 Ag-110m 0.32 Pu-241 0.02 Cm-243 0.01 Cr-51 0.01 Am-241 0.01 Nb-94 0.04 Sb-124 0.18
c. Evaporator Concentrates N/A N/A Page 3-3
Attachment 3 Solid Radioactive Waste Disposal Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017
d. Dewatered Mechanical Filters Cr-51 3.87 Mn-54 2.33 Co-57 0.46 Co-58 34.38 Co-60 11.12 Cs-137 3.88 Cs-134 1.03 Fe-55 2.57 Fe-59 0.03 Ni-63 7.64 H-3 3.89 C-14 6.27 Nb-95 8.75 Ce-144 1.26 Sb-124 0.05 Sb-125 0.01 Zr-95 8.90 Sr-89 2.57 Sr-90 0.225 Zn-65 1.05
e. Dewatered Demineralizers NIA NIA
f. Solidified (cement) Acids, Oils, Sludge NIA NIA
2. Dry Solid Waste
a. Dry Active Waste (compacted) NIA NIA
b. Dry Active Waste (non-compacted) Cr-51 4.00 Mn-54 0.32 Co-57 0.02 co-58 3.13 Co-60 1.26 Cs-137 0.39 Fe-55 82.82 Fe-59 1.64 Ni-63 4.10 C-14 0.48 Nb-95 1.60 Sb-124 0.05 Sb-125 0.05 Zr-95 0.06 Sr-90 0.01 Ce-144 0.0042 Zn-65 0.01 Nb-94 0.0021 Pu-238 0.001 Pu-239 0.0005 Cm-243 0.0005
c. Dry Active Waste (brokered) NIA NIA
d. Irradiated Components NIA NIA Page 3-4 I
Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 ATTACHMENT 4 Meteorological Data This attachment includes a summary of meteorological joint frequency distributions of wind speed, wind direction, and atmospheric stability (hours of occurrence).
Page 4-1
Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Lower Level Wind Hours of Occurrence Stability Speed Sector Class (mis) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 1 1 0 0 0 0 0 0 0 0 0 1.26-1.50 0 0 1 0 0 0 1 0 1 3 0 0 0 0 1 1 1.51-2.00 4 0 3 1 0 0 0 0 1 13 36 20 2 0 2 1 2.01-3.00 0 1 5 15 7 4 0 1 4 48 111 22 2 1 1 0 A
3.01-4.00 0 1 0 7 1 0 0 0 0 8 27 3 3 5 3 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 5 1 3 2 1 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 4 3 1 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 2 0 1 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 0 2 0 0 0 1 0 1.26-1.50 0 0 1 1 0 0 0 0 0 0 8 1 1 1 1 1 1.51-2.00 3 8 6 7 5 2 0 0 6 15 39 21 11 4 1 3 2.01-3.00 2 0 3 15 16 3 1 5 6 66 62 24 5 2 0 2 B
3.01-4.00 0 1 0 6 1 0 0 1 0 14 9 0 3 3 0 0
1.
4.01-5.00 0 0 0 1 0 0 0 0 0 1 3 4 1 1 4 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 1 1 5 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 1 1 4 6 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 1. 1 1 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-2
Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Lower Level Wind Hours of Occurrence Stability Speed Sector Class (mis) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1.01-1.25 2 0 1 0 0 0 0 0 0 0 2 0 3 0 1 0 1.26-1.50 5 2 2 0 0 1 0 2 1 3 11 6 2 2 1 2 1.51-2.00 4 5 2 14 5 3 1 4 5 20 40 23 12 3 3 4 2.01-3.00 1 2 11 14 18 5 3 3 7 37 36 9 3 1 2 2 C
3.01-4.00 0 1 0 9 1 0 0 0 2 17 10 5 1 0 1 0 4.01-5.00 0 0 0 2 0 0 0 0 0 2 2 1 2 2 2 1 5.01-6.00
0 0 0 0 0 0 0 0 0 1 1 6 2 6 2 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 1 6 5 3 2 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 4 0 0 1 4 1 1 1 1 0 6 3 2 1 3 0 0.76-1.00 11 13 7 2 8 10 13 5 11 10 13 9 14
16 17 24 1.01-1.25 28 30 14 8 17 5 11 16 9 15 18 26 24 24 19 29 1.26-1.50 28 29 27 27 35 28 32 23 22 20 33 40 47 33 22 24 1.51-2.00 18 20 42 81 88 26 61 32 30 41 64 64 39 15 6 10 2.01-3.00 10 18 60 168 75 17 31 16 18 89 138 78 31 22 13 10 D
3.01-4.00 1 1 15 37 7 0 0 2 0 52 87 84 39 25 18 8 4.01-5.00 0 1 3 3 2 0 0 0 0 13 46 36 31 25 7 1 5.01-6.00 0 0 0 1 0 0 0 0 0 1 15 25 12 21 5 0 6.01-8.00 0 0 1 1 0 0 0 0 0 0 4 17 11 15 3 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 1 1 2 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-3
Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 Lower Level Wind Hours of Occurrence Stability Speed Sector Class (mis) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 24 14 13 12 12 17 8 4 13 7 19 17 23 26 19 24 0.76-1.00 96 71 43 32 33 32 32 23 44 33 47 44 72 90 97 100 1.01-1.25 61 30 35 36 37 34 31 39 36 23 32 32 43 48 50 72 1.26-1.50 50 19 31 46 44 47 64 63 43 27 36 37 14 17 33 38 1.51-2.00 33 16 47 74 72 43 62 73 54 41 44 49 17 8 18 8 2.01-3.00 6 5 29 55 53 12 9 21 16 56 97 55 28 14 8 6 E
3.01-4.00 2 1 4 10 0 2 2 2 3 23 36 26 21 1 0 0 4.01-5.00 0 0 4 1 2 1 0 0 1 9 9 19 6 5 0 1 5.01-6.00 0 0 2 0 1 0 0 0 0 0 4 6 1 2 1 0 6.01-8.00 0 0 3 7 0 0 0 0 0 0 0 2 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 3 0 2 0 0 2 1 0 0 0 0 5 8 11 3 3 0.76-1.00 4 2 1 1 3 0 3 2 4 2 5 5 26 34 33 11 1.01-1.25 6 3 3 0 4 5 3 1 1 6 5 8 5 26 34 6 1.26-1.50 2 1 3 1 2 10 5 4 2 1 3 0 0 11 16 0 1.51-2.00 1 0 3 0 2 11 4 1 1 2 5 2 1 3 3 1 2.01-3.00 0 3 1 1 2 0 7 1 2 1 4 9 1 1 0 0 F
3.01-4.00 0 0 0 0 0 0 0 0 0 0 5 2 0 0 0 1 4.01-5.00 1 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-4
Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Lower Level Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 1 0 0 0 0 0 0 0 0 0 0 3 2 1 0 0.76-1.00 a_ 0 1 0 2 0 0 0 1 1 0 4 14 8 2 0 1.01-1.25 0 0 0 0 0 0 0 0 0 0 0 1 2 8 0 0 1.26-1.50 0 0 0 0 0 0 0 0 0 0 4 1 1 5 0 1 1.51-2.00 0 1 0 0 0 0 0 0 0 0 1 0 0 0 3 0 2.01-3.00 0 1 1 1 1 0 0 1 0 0 1 1 0 0 0 0 G
3.01-4.00 0 0 0 0 0 0 0 0 0 1 3 0 1 0 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0 1 0 0 2 1 0 0.
5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-5
Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 Upper Level Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1.01-1.25 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 1.26-1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51-2.00 1 0 1 0 0 0 1 1 0 2 5 2 0 1 0 1 2.01-3.00 0 2 0 0 0 1 0 2 5 33 29 4 2 0 0 0 A
3.01-4.00 0 1 2 3 2 2 0 0 6 56 10 0 1 0 0 0 4.01-5.00 0 1 2 2 0 0 0 0 4 35 8 1 0 2 0 0 5.01-6.00 0 0 3 1 1 0 0 0 0 16 9 0 2 1 1 0 6.01-8.00 0 0 2 0 0 0 0 0 0 7 9 1 2 2 2 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 2 0 3 0 3 1 10.01-max 0 0 0 0 0 0 0 0 0 0 0 2 1 0 0 0 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.26-1.50 0 0 0 0 0 0 0 0 0 1 0 1 1 2 0 0 1.51-2.00 2 0 0 1 0 0 0 0 2 3 8 3 2 2 0 3 2.01-3.00 2 4 6 4 1 4 1 3 18 32 28 7 1 0 1 0 B
3.01-4.00 0 1 3 3 2 1 1 2 11 27 10 2 1 2 0 0 4.01-5.00 1 2 2 2 3 1 0 1 4 25 9 0 1 1 0 0 5.01-6.00 0 0 0 1 0 0 0 0 0 20 6 1 3 1 0 0 6.01-8.00 0 0 3 2 0 0 0 0 0 5 6 2 1 0 4 0 8.01-10.00 0 0 0 0 0 0 0 0 0 1 2 *o 3 4 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 2 1 5 1 0 Page 4-6
Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 Upper Level Wind Hours of Occurrence Stability Speed Sector Class (mis) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 1 0 1 0 0 0 0 1.26-1.50 1 0 1 0 0 0 0 0 0 2 2 0 1 2 0 1 1.51-2.00 5 3 1 1 0 0 1 2 2 10 12 7 3 2 1 1 2.01-3.00 2 3 4 10 5 1 1 7 11 29 15 5 1 0 1 0 C
3.01-4.00 1 0 6 4 4 2 2 4 5 12 10 1 0 0 0 0 4.01-5.00 0 1 5 4 0 1 0 0 3 13 10 0 1 1 0 1 5.01-6.00 1 0 2 1 0 0 0 0 4 10 7 0 0 1 1 0 6.01-8.00 0 0 3 2 0 0 0 0 0 9 10 1 0 3 2 0 8.01-10.00 0 0 0 1 0 0 0 0 0 2 1 8 5 7 0 0 10.01-max 0 0 0 0 0 0 0 0 0 1 1 4 2 0 1 0 0.46-0.75 0 0 0 0 0 1 0 0 1 1 0 0 0 0 0 0 0.76-1.00 0 1 6 1 1 1 3 2 0 4 1 1 3 4 8 5 1.01-1.25 7 5 2 1 3 3 3 5 3 4 11 5 10 9 14 9 1.26-1.50 10 10 5 1 7 7 5 4 6 12 14 20 11 8 16 11 1.51-2.00 26 25 9 9 9 14 20 17 14 22 31 32 20 16 14 19 2.01-3.00 21 30 48 40 32 26 42 23 21 29 45 25 17 8 18 26 D
3.01-4.00 9 16 52 41 15 4 17 9 18 39 54 16 5 10 4 8 4.01-5.00 6 19 45 30 22 2 2 3 13 37 62 14 6 16 12 6 5.01-6.00 0 14 23 7 1 0 1 5 7 32 55 24 10 16 11 6 6.01-8.00 0 12 11 3 0 0 0 0 1 36 103 30 32 26 6 3 8.01-10.00 0 4 2 0 0 0 0 0 0 13 38 23 10 26 2 0 10.01-max 0 0 0 0 0 0 0 0 0 3 13 (;l 8 5 0 0 Page 4-7
Attachment 4 Meteorological Data Oconee Nuclear Station Units 1; 2, & 3 Period 1/1/2017-12/31/2017 Upper Level Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 1 2 0 0 1 1 3 3 1 3 1 1 3 1 1 1 0.76-1.00 8 4 4 5 0 0 2 5 2 2 2 9 11 9 9 11 1.01-1.25 17 8 8 6 6 6 3 5 7 5 11 12 15 11 18 20 1.26-1.50 33 11 10 5 3 9 11 5 7 6 16 12 26 30 25 25 1.51-2.00 71 32 27 19 12 15 18 13 9 17 36 59 39 39 58 58 2.01-3.00 104 82 62 31 32 31 27 34 35 46 56 39 33 24 38 91 E
3.01-4.00 15 35 37 44 22 12 11 30 42 40 56 21 9 6 9 8 4.01-5.00 2 10 18 17 15 3 7 15 30 37 47 18 12 5 4 2 5.01-6.00 2 9 9 1 4 0 0 4 4 20 44 13 16 9 0 4 6.01-8.00 1 2 5 1 0 1 3 0 6 18 50 20 10 6 1 2 8.01-10.00 0 4 0 0 1 0 0 0 0 7 14 5 1 2 0 0 10.01-max 0 5 2 0 0 0 0 0 0 0 4 0 0 0 0 0 0.46-0.75 1 0 1 0 0 2 0 0 0 0 0 0 0 0 1 1 0.76-1.00 0 2 3 0 2 0 1 0 2 2 0 0 0 2 0 0 1.01-1.25 3 0 0 2 1 1 1 0 1 1 2 0 1 2 2 1 1.26-1.50 4 3 5 3 1 0 0 0 2 2 1 3 4 2 0 7 1.51-2.00 10 14 6 2 4 1 3 3 3 4 6 5 2 4 1 11 2.01-3.00 27 32 7 8 3 2 5 4 6 4 16 8 5 1 2 7 F
3.01-4.00 3 3 1 1 2 2 1 0 2 3 6 2 0 3 1 0 4.01-5.00 3 0 2 0 1 0 0 2 1 4 3 3 1 1 1 0 5.01-6.00 1 0 0 0 0 0 0 0 1 0 5 3 1 0 0 0 6.01-8.00 1 0 0 0 0 0 0 0 0 1 4 4 0 0 1 0 8.01-10.00 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 1 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-8
Attachment 4 Meteorological Data Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Upper Level Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 1 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 1 0 0 0 1 2 1 1 0 0 0 0 1.26-1.50 1 0 1 1 0 0 1 1 0 0 0 0 0 0 0 2 1.51-2.00 2 0 0 1 0 0 0 2 2 2 0 1 0 0 3 3 2.01-3.00 2 4 0 0 0 0 1 2 0 1 4 2 0 1 0 0 G
3.01-4.00 1 0 0 0 0 0 0 1 0 5 7 1 0 0 1 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 2 1 1 0 0 1 5.01-6.00 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 1 1 3 0 2 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 10.01-max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-9
Attachment 5 Unplanned Offsite Releases Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 ATTACHMENT 5 Unplanned Offsite Releases This attachment includes a summary of the unplanned offsite releases of gaseous and liquid radioactive effluents.
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Attachment 5 Unplanned Offsite Releases Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Oconee Nuclear Station had zero (0) unplanned liquid offsite release radioactive effluents in 2017.
Oconee Nuclear Station had zero (0) unplanned gaseous offsite release of radioactive effluents in 2017.
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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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).
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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Gaseous Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Noble Gases
1. Maximum Gamma Air mRAD 6.97E-05 4.57E-05 4.46E-05 1.77E-05 1.78E-04 (a) Limit mRAD 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.00E+01 (b) % of Limit 4.65E-04 3.04E-04 2.98E-04 1.1 BE-04 5.92E-04
2. Maximum Beta Air mRAD 2.0?E-04 1.0?E-04 8.28E-05 3.9qE-05 4.36E-04 (a) Limit mRAD 3.00E+01 3.00E+01 3.00E+01 3.00E+01 6.00E+01 (b) % of Limit 6.91E-04 3.56E-04 2.76E-04 1.32E-04 7.27E-04 Receptor Location 1.0 miles SW B. Iodine, H-3, & Particulates
1. Maximum Organ Dose mREM 8.78E-02 9.0?E-02 8.95E-02 8.06E-02 3.49E-01 (a) Limit mREM 2.25E+01 2.25E+01 2.25E+01 2.25E+01 4.50E+01 (b) % of Limit 3.90E-01 4.03E-01 3.98E-01 3.58E-01 7.75E-01 Receptor Location 1.0 miles SW Critical Age CHILD Critical Organ BONE Page 6-2
Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 Liquid Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Batch & Continuous Mode
1. Maximum Organ Dose mREM 3.13E-02 2.75E-02 5.18E-02 3.20E-02 1.43E-01 (a) Limit mREM 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.00E+01 (b) % of Limit 2.09E-01 1.84E-01 3.45E-01 2.13E-01 4.75E-01 (c) Critical Age Child Child Child Child Child (d) Critical Organ GILLI GILLI GILLI GILLI GILLI
2. Maximum Total Body Dose mREM 3.13E-02 2.75E-02 5.18E-02 3.19E-02 1.43E-01 (a) Limit mREM 4.50E+OO 4.50E+OO 4.50E+OO 4.50E+OO 9.00E+OO (b) % of Limit 6.95E-01 6.12E-01 1.15E+OO 7.1 OE-01 1.58E+OO (c) Critical Age Child Child Child Child Child Page 6-3
Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 40 CFR Part 190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40 CFR Part 190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. The fuel cycle dose assessment for Oconee Nuclear Station includes liquid and gaseous effluent dose contributions from Oconee Nuclear Station and direct and air-scatter dose from the onsite ISFSI. No other uranium fuel cycle facility contributes significantly to the maximum exposed individual. Included in the gaseous effluent dose calculations is an estimate of the dose contributed by Carbon-14 (Ref. Attachment 2, Supplemental Information, of this report for further information). The combined dose to a maximum exposed individual from effluent releases*and direct and air-scatter dose from the ISFSI is below 40 CFR Part 190 limits as shown by the following summary.
Note: The 40 CFR Part 190 effluent dose analysis to the maximum exposed individual from liquid and gas releases includes the dose from noble gases (i.e., total body and skin).
40 CFR Part 190 Effluent Dose Summary A. Maximum Organ Dose (other than TB) 3.49E-01 mREM
1. Location 1.0 miles SW
2. Critical Age CHILD
3. Critical Organ BONE
4. Gas Contribution % 0.05 %
5. Liquid Contribution % 99.95 %
B. Maximum Total Body Dose 2.44E-01 mREM
1. Location 1.0 miles SW
2. Critical Age CHILD
3. Gas non-NG Contribution % 41.47 %
4. Gas Contribution % 0.06%
5. Liquid Contribution % 58.47 %
Direct and air-scatter radiation dose contributions from the onsite ISFSI have been determined from 10 CFR 72.212 Evaluation Report for Phase VIII Standardized NUHOMS Cask System Rev. 00. The maximum dose rate to the nearest real individual from the ISFSI is conservatively calculated to be less than 11 mrem/yr.
The attached excerpt from the 10 CFR 72.212 Evaluation Report for Phase VIII Standardized NUHOMS Cask System Rev. 00 is provided to document the method used to calculate the dose from ISFSI as less than 11 mrem/yr to the nearest real individual.
Total dose from liquid and gaseous effluents from Oconee Nuclear Station and direct and air-scatter dose from the onsite ISFSI is conservatively estimated to be less than 12 mrem/yr to the nearest real individual. This meets the 40 CFR Part 190 requirements of an annual dose commitment to any member of the general public of less than 25 mrem total body or any organ and 75 mrem to the thyroid.
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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 6.0 10 CFR 72.212(b)(5)(iii) - Radioactive Materials in Effluents and Direct Radiation 6.1 Purpose 10 CFR 72.212(b)(5)(iii) requires the general licensee to perform written evaluations, before use and before applying the changes authorized by an amended CoC to a cask loaded under the initial Coe or an earlier amended CoC, that establish that the requirements of 10 CFR 72.104 have been met. A copy of this record shall be retained until spent fuel is no longer stored under the general license issued under 10 CFR 72.210 .
. 10 CFR 72.104 provides the regulatory criteria for radioactive materials in effluents and direct radiation from an independent spent fuel storage installation (ISFSI) during normal operation and anticipated occurrences. Specifically, 10 CFR 72.104(a) limits the annual dose equivalent to any real individual who is located beyond the controlled area to 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other critical organ. This dose equivalent must include contributions from (1) planned discharges of radioactive materials (radon and its decay products excepted) to the general environment, (2) direct radiation from ISFSI operations, and (3) any other radiation from uranium fuel cycle operations within the region. In addition, 10 CFR 72.104(b) requires that operational restrictions be established to meet as low as is reasonably achievable (ALARA) objectives for radioactive materials in effluents and direct radiation levels associated with ISFSI operations. Also, 10 CFR 72.104(c) requires that operational limits be established for radioactive materials in effluents and direct radiation levels associated with ISFSI operations to meet the above-mentioned dose limits.
This section provides the written evaluation required by 10 CFR 72.212(b)(5)(iii), demonstrating Duke Energy's compliance with the requirements of 10 CFR 72.104 for the ONS ISFSI.
6.2 Evaluation This evaluation addresses the radiological dose rate from a composite population of all ONS ISFSI cask types.
6.2.1 §72.104(a) - Dose Limits 10 CFR 72.104, as clarified by ISG-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/year) due to direct radiation from the Independent Spent Fuel Storage Installation and other fuel cycle operations in the area. This same dose limit is stipulated by the EPA for the fuel cycle in 40 CFR 190.1 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 - VI, together with the 2
characteristics of assumed "design basis" fuel for canisters in Phase VII and Phase VIII of the Oconee ISFSl
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 Module5 of the SCALE Code System was used to perform the fuel depletion and characterization calculations using the cross section sets created by SAS2. These characterization calculations yielded the photon and neutron source terms to be used as input to subsequent shielding calculations. As mentioned above, problem-dependent cross section sets were developed for these analyses since ORIGEN-S was used within the SAS2 sequence. Duke Energy Corporation Radiological Engineering is experienced in the use of the SCALE Code System, and the SCALE Code System is installed and maintained under the purview of the pertinent software and data quality assurance program.
6 The results of the radiation source term calculation were used as input to Calculation OSC-8706 to evaluate the shielding characteristics of a single Horizontal Storage Module. The MCNP Monte Carlo particle transport computer 7
code was used to perform the transport calculations and to write a surface flux file for use in subsequent skyshine calculations.
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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 9
SDQA-30269-NG0 documents the quality control measures in place for MCNP5).
6.2.2 §72.104(b)- Operational Restrictions Operational restrictions must be established to meet ALARA objectives for direct radiation levels associated with ISFSI.
Calculation OSC-8716 10 , Table 34.1-1, summarizes dose rate versus distance, showing a dose rate of 10.80 mRem per year at 500 meters, which is the longest distance at which results converge. The closest residence to the ISFSI is in the SW-SSW direction approximately 1 mile (-1600 meters) from the ISFSI, or 1.36 miles from the centerline of the site. 11 This is conservatively farther than the distance used for computation of dose rates.* The 2016 40CFR190 Uranium Fuel Cycle Dose Calculation Results for the ONS site show a maximum total body dose of less than 1 mrem per year (last reported dose was 0.268 mrem 12). The total dose rate from all operations to the nearest real individual is therefore less than 12 mRem per year.
Thi~ calculation need not consider any effluent from Phase VIII. The Phase VIII HSMs use the NUHOMS-24PTH-S-13 LC DSCs, which are designed as "leak-tight." Per Appendix P, Section P.11.2.8 of the NUHOMS FSAR , accidental releases are not credible.
6.2.3 §72.104(c)-Operationallimits 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.
6 Calculation OSC-8716 10 uses the surface flux files developed in OSC-8706 in a repeating array. A skyshine calculation is performed to obtain near- and far-field dose results the Oconee ISFSI. This calculation need not consider any effluent from Phase VIII. The Phase VIII HSMs use the NUHOMS-24PTH-S-LC DSCs, which are designed as "leak-tight." Per Appendix P, Section P.11.2.8 of the NUHOMS FSAR13 , accidental releases are not credible.
6.3 Regulatory Compliance/Conclusion The evaluation summarized above demonstrates that Duke Energy meets the requirements of 10 CFR 72.212(b)(5)(iii) and 10 CFR 72.104 for the ONS ISFSI.
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Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Oconee Nuclear Station Units 1, 2, & 3
Period 1/1/2017 - 12/31/2017 6.4 References
1. United States Nuclear Regulatory Commission, Spent Fuel Project Office, Interim Staff Guidance - 13, "Real Individual."
2. "Design Basis" fuel (considering fuel burnup and initial enrichment) is assumed to reside in Phases VII-VIII of the Oconee ISFSI. The assumption of 5 years cooling time applies only to the most recent six dry storage casks, while the balance of the casks are assumed to have been loaded in increments of six dry storage canisters per year. This is consistent with reasonable engineering practice.
3. Calculation OSC-8675, "Oconee ISFSI Spent Fuel Radiation Source Terms," Revision 3.
4. 0. W. Hermann, C. V. Parks, "SAS2H: A Coupled One-Dimensional Depletion and Shielding Analysis Module," NUREG/CR-0200, Revision 6, Volume 1, Section S2, ORNLINUREG/CSD-2N21R6.
5. 0. W. Hermann, R. M. Westfall, "ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms," NUREG/CR-0200, Revision 6, Volume 2, Section F7, ORNLINUREG/CSD-2N21R6.
6. Calculation OSC-8706, "Oconee Horizontal Storage Module Shielding Evaluation," Revision 2.
7. LA-CP-03-0245, "MCNP - A General Monte Carlo N-Particle Transport Code, Version 5 (Volume 1: Overview and Theory, Volume II: User's Guide, Volume Ill: Developer's Guide).
8. Calculation DPC-1201.30-00-0010, Revision 0, "MCNP5 Computer Code Verification and Validation."
9. SDQA-30269-NGO, MCNP 5 Version 1.6
10. Calculation OSC-8716, "Oconee ISFSI Dose Rate Evaluations," Revision 2.
11. Dale E. Holden to Libby Wehrman, "2005 Oconee Annual Land Use Census," August 31, 2005, File No: OS-778.05 (Oconee Master File Record Retention No. 000377).
12. Thomas D. Ray to U.S. Nuclear Regulatory Commission, "2016 Annual Radioactive Effluent Release Report (ARERR)", May 1, 2017.
13. NUH-003, "Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel," Revision 14.
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Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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.
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Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 66 wells in 2017. 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 2017. Results from sampling during 2017 confirmed existing knowledge of tritium concentrations in site ground water.
Results from sampling during 2017 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 2017.
Key to below table.
Not scheduled to be sampled, not sampled due to insufficient NS volume in well, or well inaccessible during outage.
pCi/1 * - picocuries per liter.
<MDA - less than minimum detectable activity, typically 250 pCi/1.
the Environmental Protection Agency drinking water standard for 20,000 pCi/1 tritium. This standard applies only to water used for drinking.
the 10 CFR Part 20, Appendix B, Table 2, Column 2, Effluent 1,000,000 pCi/1 Con*centration Limit for tritium.
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Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Well Tritium Concentration (pCi/1) #of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples A-1 ONS GWPI / A-1 / CTP 1/2 <MDA <MDA NS <MDA 3 A-10 ONS GWPI / A-10 / CTP 3 3.52E+02 3.65E+02 NS 5.27E+02 3 A-11 ONS GWPI / A-11 / CTP 3 <MDA <MDA NS <MDA 3 A-13 ONS GWPI / A-13 / CTP 1/2 3.14E+02 4.15E+02 NS 2.95E+02 3 A-14 ONS GWPI / A-14 / CTP 1/2 <MDA <MDA NS <MDA 3 A-17 ONS GWPI / A-17 / CTP 1/2 <MDA NS NS NS 1 A-18 ONS GWPI / A-18 / CTP 1/2 <MDA NS NS NS* 1 A-2 ONS GWPI / A-2 / CTP 1/2 <MDA <MDA NS <MDA 3 A-9 ONS GWPI / A-9 / CTP 1/2 2.41E+02 NS NS NS 1 BG-4 ONS GWPI / BG-4 / Ball Field <MDA <MDA NS <MDA 3 GM-10 ONS GWPI / GM-10 / 525 kv Sw Yard NS <MDA <MDA <MDA 3 GM-10R ONS GWPI /GM-10R / 525 kvSwYard NS <MDA NS <MDA 2 GM-11 ONS GWPI / GM-11 / ONS Garaoe NS <MDA NS NS 1 GM-11R ONS GWPI / GM-11 R / ONS Garaoe NS <MDA NS NS 1 GM-12 ONS GWPI / GM-12 / E of Access Rd. NS <MDA NS NS 1 GM-12R ONS GWPI / GM-12R / E of Access Rd. NS <MDA NS NS 1 GM-13 ONS GWPI / GM-13 / 525 kv SwYard NS <MDA NS NS 1 GM-13R ONS GWPI / GM-13R / 525 kv SwYard NS <MDA NS NS 1 GM-14 ONS GWPI / GM-14 / Mnt. Tro. Facilitv NS <MDA <MDA <MDA 3 GM-14R ONS GWPI / GM-14R / Mnt. Tro. Facility NS <MDA NS <MDA 2 GM-15 ONS GWPI / GM-15 <MDA <MDA <MDA <MDA 4 GM-15R ONS GWPI / GM-15R <MDA <MDA NS NS 2 GM-16DDR ONS GWPI / GM-16DDR <MDA 2.46E+02 NS NS 2 GM-16DR ONS GWPI / GM-16DR 6.91E+03 6.75E+03 7.26E+03 6.77E+03 4 GM-16R ONS GWPI / GM-16R 9.69E+02 9.56E+02 1.09E+03 1.27E+03 4 GM-17DR ONS GWPI / GM-17DR 2.06E+03 2.09E+03 2.06E+03 2.22E+03 4 GM-17R ONS GWPI / GM-17R 6.40E+02 8.00E+02 NS 1.13E+03 3 GM-18R ONS GWPI / GM-18R 4.85E+03 3.97E+03 4.33E+03 4.11E+03 4 GM-19 ONS GWPI / GM-19 1.79E+03 1.71E+03 1.67E+03 1.98E+03 4 GM-19R ONS GWPI / GM-19R 1.09E+03 1.22E+03 1.30E+03 1.35E+03 4 GM-1R ONS GWPI / GM-1 R / CTP 1/2 <MDA <MDA <MDA <MDA 4 GM-20 ONS GWPI / GM-20 <MDA <MDA NS NS 2 GM-20R ONS GWPI / GM-20R <MDA <MDA NS NS 2 GM-21 ONS GWPI / GM-21 NS <MDA NS NS 1 GM-22 ONS GWPI / GM-22 NS <MDA NS NS 1 GM-23 ONS GWPI / GM-23 2.50E+02 2.46E+02 <MDA <MDA 4 GM-24R ONS GWPI / GM-24R 9.50E+02 8.74E+02 1.17E+03 1.21E+03 4 GM-25R ONS GWPI / GM-25R 2.78E+02 2.35E+02 3.55E+02 2.34E+02 4 GM-2DR ONS GWPI / GM-2DR / U-1/2 SFP 3.15E+02 <MDA <MDA <MDA 4 GM-2R 111 ONS GWPI / GM-2R / U-1/2 SFP 1.15E+03 3.62E+03 1.84E+03 1.79E+03 4 GM-3DR ONS GWPI / GM-3DR / U-3 SFP 2.98E+02 2.92E+02 NS 2.69E+02 3 GM-3R ONS GWPI / GM-3R / U-3 SFP 2.12E+02 2.99E+02 2.75E+02 2.19E+02 4 (1) H-3 resample 13JUN2017 yielded activity 1.50E+03 pCi/1, NCR# 02136161 Page 7-3
Attachment 7 Information to Support the NEI Ground Water Protection Initiative Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Well Tritium Concentration (pCi/1) #of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples GM-4 ONS GWPI / GM-4 I Rad. Mat. WH <MDA 5.52E+02 4.37E+02 5.35E+02 4 GM-5 ONS GWPI / GM-5 / Rdwst. Bldg. <MDA <MDA 3.01E+02 <MDA 4 GM-5R ONS GWPI / GM-5R / Rdwst. Bldg. <MDA <MDA NS <MDA 3 GM-6 ONS GWPI / GM-6 I Outflow to CTP-3 1.92E+02 <MDA <MDA <MDA 4 GM-6R ONS GWPI / GM-6R / Outflow to CTP-3 <MDA <MDA NS <MDA 3 GM-7 ONS GWPI / GM-7 / 525 kv Sw Yard <MDA 4.14E+02 3.85E+02 2.64E+02 4 GM-7DR ONS GWPI / GM-7DR <MDA <MDA NS NS 2 GM-7R ONS GWPI / GM-7R / 525 kv Sw Yard 9.54E+02 1.20E+03 1.37E+03 1.30E+03 4 GM-8 ONS GWPI / GM-8 I E of U-3 TB 5.83E+02 <MDA 2.98E+02 2.32E+02 4 GM-8R ONS GWPI / GM-8R / E of U-3 TB 5.23E+02 <MDA NS <MDA 3 GM-9 ONS GWPI / GM-9 I E of U-2 TB 2.55E+02 <MDA 2.12E+02 2.71E+02 4 GM-9R ONS GWPI / GM-9R / E of U-2 TB <MDA <MDA NS <MDA 3 MW-11 ONS GWPI / MW-11 / Landfill <MDA NS <MDA NS 2 MW-110 ONS GWPI / MW-11 D / Landfill <MDA NS <MDA NS 2 MW-13 ONS GWPI / MW-13 / Landfill <MDA NS <MDA NS 2 MW-16 ONS GWPI / MW-16 / Landfill <MDA NS <MDA NS 2 MW-3 ONS GWPI / MW-3 / Landfill NS NS <MDA NS 1 MW-RP01 ONS GWPI / MW-RP01 / Landfarm/Burial NS <MDA NS NS 1 MW-RP02 ONS GWPI / MW-RP02 / Landfarm/Burial NS <MDA NS NS 1 MW-RP03 ONS GWPI / MW-RP03 / Landfarm/Burial NS <MDA NS NS 1 Well Tritium Concentration (pCi/1) # of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples 011 ONS / 011 / Ball Field <MDA <MDA <MDA <MDA' 4 013 ONS / 013 /WH 5 <MDA <MDA <MDA <MDA 4 015 ONS / 015 / Brown's Bottom <MDA <MDA <MDA <MDA 4 Well Tritium Concentration (pCi/1) # of Location / Description Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples RW-1 I 525 kv Sw. Yard I 7.89E+02 I 6.49E+02 I 7.62E+02 I 6.69E+02 I 4 NOTE: Frequency of sampling was reduced in 2017 for wells with long standing, stable trends.
I.
Page 7-4
Attachment 8 Inoperable Equipment Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 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 1/1/2017 - 12/31/2017 Oconee Nuclear Station did not experience inoperable equipment relevant to effluent monitoring in excess of SLC limits during 2017.
Oconee Nuclear Station did not experience temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases) during 2017.
Page 8-2
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017-12/31/2017 ATTACHMENT 9 Summary of Changes to the Offsite Dose Calculation Manual This attachment includes a summary of changes to the ODCM and Radiological Effluent Controls.
Page 9-1
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 ODCM Revision 58 The most recent ODCM revision is 58 and was provided with the 2016 ARERR.
Radiological Effluent Controls (SLC 16.11)
The Oconee Nuclear Station Radiological Effluent Controls are contained in SLC 16.11 and are included in this section. SLC 16.11 was not revised in 2017.
Page 9-2
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS SECTION TITLE NO 16.0 SELECTED LICENSEE COMMITMENTS 16.1-1
16.1 INTRODUCTION
16.1-1 16.2 APPLICABILITY 16.2-1 16.3 DEFINITIONS 16.3-1 16.4 COMMITMENTS RELATED TO REACTOR COMPONENTS Pending 16.5 REACTOR COOLANT SYSTEM 16.5.1-1 16.5.1 Reactor Coolant System Vents 16.5.1-1 16.5.2 Low Temperature Overpressure Protection (L TOP) System 16.5.2.1 16.5.3 Loss of Decay Heat Removal 16.5.3-1 16.5.4 Reactor Coolant System (RCS) Boron Sampling 16.5.4-1 16.5.5 [DELETED] 16.5.5-1 16.5.6 [DELETED] 16.5.6-1 16.5.7 Chemistry Requirements 16.5.7-1 16.5.8 Pressurizer 16.5.8-1 16.5.8a [DELETED] 16.5.8a-1 16.5.9 Testing Following Opening of System (Core Barrel Bolt Inspections) 16.5.9.1 16.5.10 Loss of Reactor Coolant 16.5.10-1 16.5.11 Subcriticality 16.5.11-1 16.5.12 RCS Leakage Testing Following Opening of System 16.5.12-1 16.5.13 High Pressure Injection and the Chemical Addition Systems 16.5.13-1 16.6 COMMITMENTS RELATED TO ENGINEERED SAFETY FEATURES 16.6.1-1 (NON-ESF SYSTEMS) 16.6.1 Containment Leakage Tests 16.6.1-1 16.6.2 Reactor Building Post-Tensioning System 16.6.2-1 16.6.3 Containment Heat Removal Verification Frequency 16.6.3-1 16.0-1 Rev. 006 I 9-3
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)
SECTION TITLE NO 16.6.4 Low Pressure Injection System Leakage 16.6.4-1 16.6.5 Core Flood Tank Discharge Valve Breakers 16.6.5-1 16.6.6 Core Flooding System Test 16.6.6-1 16.6.7 BWST Outlet Valve Control 16.6.7-1 16.6.8 LPI System Valve Test Restrictions 16.6.8-1 16.6.9 Containment Purge Valve Testing 16.6.9-1 16.6.10 Trisodium Phosphate (TSP) 16.6.10-1 16.6.11 Containment Debris Sources 16.6.11-1 16.6.12 Additional High Pressure Injection (HPI) Requirements 16.6.12-1 16.6.13 Additional Requirements to Support Low Pressure Injection (LPI) 16.6.13-1 Operability 16.6.14 Control of HPI and LPI/RBS Pump Room Temperatures 16.6.14-1 16.6.15 High Pressure Injection (HPI) and Liquid Waste Disposal (LWD) 16.6.15-1 Leakage 16.7 INSTRUMENTATION 16.7.1-1
16. 7.1 Accident Monitoring Instrumentation 16.7.1-1 16.7.2 Anticipated Transient Without Scram 16.7.2-1 16.7.3 Emergency Feedwater System 16.7.3-1 16.7.4 Hydrogen Analyzers 16.7.4-1 16.7.5 Steam Generator Overfill Protection 16.7.5-1 16.7.6 Diverse Actuation Systems 16.7.6-1 16.7.7 Position Indicator Channels 16.7.7-1 16.7.8 lncore Instrumentation 16.7.8-1 16.7.9 RCP Monitor, 16.7.9-1 16.7.10 Core Flood Tank Instrumentation 16.7.10-1 16.7.11 Display Instrumentation 16.7.11-1 16.0-2 Rev.006 9-4
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)
SECTION TITLE PAGE NO
16. 7.12 SSF Diesel Generator (DG) Air Start System Pressure 16.7.12-1 Instrumentation
16. 7.13 SSF Instrumentation 1.6.7.13-1.
16.7.14 Rod Withdrawal Alarm Limit 16.7.14-1
16. 7.15 Engine~red Safeguards Protective System (ESPS) Voter Trouble Alarm 16. 7.15..:1 16.7.16 Spent Fuel Pool -Wide Range Level Instrumentation 16.7.16-1 16.7.17 Reactor Protective System Instrumentation Setpoints 16.7.17-1 16.8 ELECTRIC POWER SYSTEMS 16.8.1-1 16.8.1 Control of Room Temperatures for Station Blackout 16.8.1-1 16.8.2 Additional Requirements to Support Keowee Hydro Unit (KHU) 16.8.2-1 OPERABILITY 16.8.3 Power Battery Parameters 16.8.3-1 16.8.4 Keowee Operational Restrictions 16.8.4-1 16.8.5 [DELETED] 16.8.5-1 16.8.6 Lee/Central Alternate Power System 16.8.6-1 16.8. 7 Auctioneering Diodes 16.8.7-1 16.8.8 External Grid Trouble Protection 16.8.8-1 16.8.9 Keowee Governor Speed Out Of Tolerance (OOT) Alarm 16.8.9-1 16.9 AUXILIARY SYSTEMS 16.9.1-1 16.9.1 Fire Suppression Water System 16.9.1-1 16.9.2 Sprinkler and Spray Systems 16.9.2-1 16.9.3 [DELETED] 16.9.3-1 16.9.4 Fire Hose Stations 16.9.4-1 16.9.5 Fire Barriers 16.9.5-1 16.9.6 Fire Detection Instrumentation 16.9.6-1 16.9.7 Keowee Lake Level 16.9.7-1 16.0-3 Rev. 006 I 9-5
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)
SECTION TITLE NO 16.9.8 Control Room Ventilation System (CRVS) Booster Fans 16.9.8-1 16.9.8a HPSW System Requirements to Support Loss of LPSW 16.9.8a-1 16.9.9 Additional Protected Service Water (PSW) System Commitments 16.9.9-1 16.9.10 Component Cooling and HPI Seal Injection to Reactor 16.9.10-1 Coolant Pumps 16.9.11 Turbine Building Flood Protection Measures 16.9.11-1 16.9.11 a Auxiliary Building Flood Protection Measures 16.9.11a-1 16.9.12 Additional Low Pressure Service Water (LPSW) And 16.9.12-1 Siphon Seal Water (SSW) System Operability Requirements 16.9.13 Spent Fuel Cooling System 16.9.13-1 16.9.14 SSF Diesel Generator (DG) Inspection Requirements 16.9.14-1 16.9.15 Radioactive Material Sources 16.9.15-1 16.9.16 Reactor Building Polar Crane and Auxiliary Hoist 16.9.16-1 (RCS System Open) 16.9.17 Reactor Building Polar Crarie (RCS at elevated 16.9.17-1 temperature and pressure) 16.9.18 Snubbers 16.9.18-1 16.9.19 Gravity Induced Reverse Flow to Standby Shutdown Facility (SSF) 16.9.19-1 Through a Unit 2 Condensate Cooler 16.9.20 Diesel Driven Service Air Compressors 16.9.20-1 16.9.21 Standby Shutdown Facility External Flood Protection 16.9.21-1 16.9.22 [DELETED] 16.9.22-1 16.9.23 Alternate Chilled Water (AWC) and Alternate Reactor Building Cooling 16.9.23-1 (RBC) Systems 16.9.24 FLEX - Equipment and Connections 16.9.24...:1 16.9.25 Spent Fuel Pool Area Isolation 16.9.25-1 16.0-4 Rev. 006 I 9-6
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)
SECTION TITLE NO 16.10 COMMITMENTS RELATED TO STEAM & POWER CONVERSION 16.10.1-1 SYSTEMS 16.10.1 Local Start of Turbine Driven Emergency Feedwater (EFW) Pump 16.10.1-1 16.10.2 Steam Generator Secondary Side Pressure and 16.10.2-1 Temperature (PIT) Limits 16.10.3 Emergency Feedwater (EFW) Pump and Valve Testing 16.10.3-1 16.10.4 Low Presssure Service Water System Testing 16.10.4-1 16.10.5 . [DELETED] 16.10.5-1 16.10.6 Emergency Feedwater Controls 16.10.6-1 16.10. 7 Alternate Source of Emergency Feedwater (EFW) 16.10.7-1 16.10.8 Upper Surge Tank (UST) Riser Branch Line Automatic Isolation Valves 16.10.8-1 16.10.9 Air Operated Valves (AOVs) Required to Support Standby Shutdown 16.10.9-1 Facility (SSF) During Station Blackout (SBO) 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.1-1 16.11.1 Radioactive Liquid effluents 16.11.1-1 16.11.2 Radioactive Gaseous Effluents 16.11.2-1 16.11.3 Radioactive Effluent Monitoring Instrumentation 16.11.3-1 16.11.4 Operational Safety Review 16.11.4-1 16.11.5 Solid Radioactive Waste 16.11.5-1 16.11.6 Radiological Environmental Monitoring 16.11.6-1 16.11. 7 Dose calculations 16.11.7-1 16.11.8 Reports 16.11.8-1 16.11.9 Radioactive effluent release report 16.11.9-1 16.11.10 Radiological Environmental Operating Reports 16.11.10-1 16.11.11 Iodine Radiation Monitoring Filters
16.11.11-1 16.0-5 Rev. 006 I 9-7
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)
SECTION TITLE NO 16.11.12 Radioactive Material in Outside Temporary 16.11.12-1 Tanks Exceeding Limit 16.11.13 Radioactive Material in Wast~ Gas Holdup 16.11.13-1 Tank Exceeding Limit 16.11.14 Explosive Gas Mixture 16.11.14-1 16.12 REFUELING OPERATIONS 16.12.1-1 16.12.1 Decay Time for Movement of Irradiated Fuel 16.12.1-1 16.12.2 Area Radiation Monitoring for Fuel Loading and Refueling 16.12.2-1 16.12.3 Communication Between Control Room and Refueling Personnel 16.12.3-1 16.12.4 Handling of Irradiated Fuel Assemblies 16.12.4-1 16.12.5 Loads Suspended over Spent Fuel in Spent Fuel Pool 16.12.5-1 16.12.6 Fuel Damage During Fuel Handling Operations in Containment 16.12.6-1 16.13 CONDUCT OF OPERATION 16.13.1-1 16.13.1 Minimum Station Staffing Requirements 16.13.1-1 16.13.2 [DELETED] 16.13.2-1 16.13.3 [DELETED] 16.13.3-1 16.13.4 Reactivity Anomaly 16.13.4-1 16.13.5 Deleted 16.13.5-1 16.13.6 Retraining and Replacement of Station Personnel 16.13.6-1 16.13. 7 Procedures for Control of Ph in Recirculated 16.13.7-1 Coolant after Loss-of-coolant Accident & Long-term Emergency Core Cooling Systems 16.13.8 Respiratory Protective Program 16.13.8-1 16.13.9 Startup Report 16.13.9-1 16.13.10 Core Ope.rating Limits Reports
16.13.10-1 16.13.11 Procedure for Station Survey Following an Earthquake 16.13.11-1 16.0-6 Rev. 006 I 9-8
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 TABLE OF CONTENTS (continued)
SECTION TITLE NO 16.14 CONTROL RODS AND POWER DISTRIBUTION 16.14.1-1 16.14.1 APSR Movement 16.14.1-1 16.14.2 Control Rod Program Verification 16.14.2-1 16.14.3 Power Mapping 16.14.3-1 16.14.4 [DELETED] 16.14.4-1 16.14.4.a Engineering Work Station 16.14.4.a-1 16.15 VENTILATION FILTER TESTING PROGRAM 16.15.1-1 16.15.1 [DELETED] 16.15.1-1 16.15.2 Control Room Pressurization and Filtering System 16.15.2-1 16.15.3 Spent Fuel Pool Ventilation System 16.15.3-1 16.0-7 Rev. 006 I 9-9
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Oconee Nuclear Station Selected Licensee Commitments Revised 01/08/18 List of Effective Pages Page Revision Number Implementation Date 16.0 005 08/16/17 16.1 000 10/15/07 16.2 000 08/25/14 16.3 001 06/29/15 16.4 PENDING 16.5.1 000 11/26/12 16.5.2 000 11/15/12 16.5.3 000 02/21/07 16.5.4 000 11/15/12 16.5.5 Deleted 5/16/09 16.5.6 Deleted 02/10/14 16.5.7 000 12/13/06 16.5.8 000 01/31/07 16.5.8a Deleted 5/19/05 16.5.9 000 11/15/12 16.5.10 000 10/08/03 16.5.11 000 01/31/00 16.5.12 000 03/27/99 16.5.13 000 03/27/99 16.6.1 000 07/23/12 16.6.2 000 01/31/07 16.6.3 000 11/15/12 16.6.4 000 11/15/12 16.6.5 000 12/14/00 16.6.6 000 11/15/12 16.6.7 000 03/27/99 16.6.8 000 03/27/99 16.6.9 000 11/15/12 16.6.10 000 11/15/12 16.6.11 000 11/15/12 16.6.12 000 11/15/12 16.6.13 000 03/31/08 16.6.14 000 04/21/14 16.6.15 000 11/15/12 16.7.1 000 11/15/12 Oconee Nuclear Station LOEP 1 Revision 023 9-10
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Oconee Nuclear Station Selected Licensee Commitments Revised 01 /08/18 List of Effective Pages Page Revision Number Implementation Date 16.7.2 000 11/15/12 16.7.3 000 11/15/12 16.7.4 000 07/14/05 16.7.5 000 11/15/12 16.7.6 000 04/08/14 16.7.7 000 11/15/12 16.7.8 000 03/27/99 16.7.9 000 10/23/03 16.7.10 000 11/15/12 16.7.11 000 11/15/12 16.7.12 000 06/30/04 16.7.13 000 12/05/12 16.7.14 000 11/15/12 16.7.15 000 04/08/14 16.7.16 000 10/14/15 16.7.17 000 07/14/16 16.8.1 000 08/09/01 16.8.2 000 02/10/05 16.8.3 001 01/26/16 16.8.4 000 02/10/05 16.8.5 000 05/21/15 16.8.6 000 01/04/07 16.8.7 000 01/31/00 16.8.8 000 01/31/00 16.8.9 000 06/21/05 16.9.1 001 08/16/16 16.9.2 002 08/16/16 16.9.3 Deleted 01 /08/18 16.9.4 001 08/16/16 16.9.5 002 08/16/16 16.9.6 005 12/19/17 16.9.7 001 08/16/16 16.9.8 000 02/15/06 16.9.8a 000 02/07/05 16.9.9 002 08/16/17 Oconee Nuclear Station LOEP2 Revision 023 9-11
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Oconee Nuclear Station Selected Licensee Commitments Revised 01 /08/18 List of Effective Pages Page Revision Number Implementation Date 16.9.10 000 01/12/04 16.9.11 001 06/29/15 16.9.11a 001 06/06/17 16.9.12 001 09/21/15 16.9.13 000 01/31/07 16.9.14 000 10/28/04 16.9.15 000 03/27/99 16.9.16 000 10/15/14 16.9.17 000 05/23/01 16.9.18 000 07/15/14 16.9.19 000 03/31/05 16.9.20 001 12/14/16 16.9.21 000 07/09/09 16.9.22 Deleted 08/16/17 16.9.23 001 08/16/17 16.9.24 003 11/18/16 16.9.25 001 08/16/17 16.10.1 000 11/15/12 16.10.2 000 12/02/03 16.10.3 000 03/27/99 16.10.4 000 11/15/12 16.10.5 Deleted 08/24/04 16.10.6 000 03/27/99 16.10.7 001 09/21/15 16.10.8 000 11/27/06 16.10.9 000 11/25/09 16.11.1 000 03/15/11 16.11.2 000
01/31/00 16.11.3 000 11/20/08 16.11.4 000 06/30/14 16.11.5 000 10/30/02 16.11.6 000 11/08/13 16.11.7 000 01/31/00 16.11.8 000 12/21/09 16.11.9 000 03/22/10 Oconee Nuclear Station LOEP3 Revision 023 9-12
" Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Oconee Nuclear Station Selected Licensee Commitments Revised 01 /08/18 List of Effective Pages Page Revision Number Implementation Date 16.11.10 000 05/14/14 16.11.11 000 03/27/99
.16.11.12 000 04/10/03 16.11.13 000 03/27/99 16.11.14 000 03/27/99 16.12.1 000 03/27/99 16.12.2 000 05/03/07 16.12.3 000 05/01/03 16.12.4 000 03/27/99 16.12.5 000 03/27/99 16.12.6 000 11/08/07 16.13.1 001 12/22/15 16.13.2 000 12/15/04 16.13.3 000 12/15/04 16.13.4 000 03/27/99 16.13.5 Deleted 11 /30/99 16.13.6 000 03/27/99 16.13.7 000 12/15/04 16.13.8 000 03/27/99 16.13.9 000 03/27/99 16.13.10 000 03/27/99 16.13.11 000 03/27/99 16.14.1 000 11/15/12 16.14.2 000 07/23/12 16.14.3 000 03/27/99 16.14.4 Deleted 03/15/11 16.14.4.a 000 03/15/11 16.15.1 000 04/12/06 16.15.2 000 11 /15/12 16.15.3 000 11/15/12 Note: With the introduction of Fusion in June 2015, all controlled documents require a three-digit revision number. Thus, the revision numbers were set to "000" in the summer of 2015. As such, the revision dates for Revision 000 are based on the implementation dates for revisions in effect prior to this change.
Oconee Nuclear Station LOEP4 Revision 023 9-13
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 4
be limited to 2 x 10- 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 9-14
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Liquid Effluents 16.11.1

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

Appendix 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 REQUIRED ACTION COMPLETION TIME A. Concentration of A.1 Restore concentration to Immediately radioactive material within the limit.
released in liquid effluents to Unrestricted Areas exceeds the limits specified in Commitment a.
16.11.1-2 0311 s,11 I 9-15
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Liquid Effluents 16.11.1 CONDITION REQUIRED ACTION COMPLETION TIME B. Calculated dose from B.1 -------------NOTE--------------
the release of Not required during radioactive materials in unusual operating liquid effluents exceeds conditions that result in any of the limits in
activation of the Oconee Commitment b. Emergency Plan.
Submit report to the 30 days from the end of
regional NRC Office which the quarter during which includes the following: the release occurred
a. Cause(s) for exceeding the limit(s).
b. A description of the program of corrective action initiated to:
reduce the releases of radioactive materials in liquid effluents, and to keep these levels of radioactive materials in liquid effluents in compliance with the above limits, or as low as reasonably achievable.
c. Results of radiological analyses of the drinking water source and the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141.
16.11.1-3 0311s111 I 9-16
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Liquid Effluents 16.11.1 CONDITION REQUIRED ACTION COMPLETION TIME C. Radioactive liquid C.1 Submit report to the 30 days waste is discharged regional NRC Office which without treatment and includes the following:
in excess of the specified limit. a. Cause of equipment or subsystem inoperability.
b. Corrective action to restore equipment and prevent recurrence.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.1.1 N/A N/A 16.11.1-4 0311 s111 I 9-17
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Liquid Effluents 16.11.1 BASES 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 Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem. It is further indicated in 10 CFR 50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as reasonably achievable (ALARA) as set forth in 10 CFR 50 Appendix I. Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with this SLC are based on ten times the instantaneous dose rate value of 50 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 141 and 40 CFR 190.
Section I of Appendix I of 10 CFR 50 states that this appendix provides specific numerical guides for design objectives and limiting conditions for operation, to assist holders of licenses for light water cooled nuclear power reactors in meeting the requirements to keep releases of radioactive material to unrestricted areas as low as practical and reasonably achievable, during normal reactor operations, including expected operational occurrences. Using the flexibility granted during unusual operating conditions, and the stated applicability of the design objectives for the Oconee Nuclear Station, Appendix I dose limits for radioactive liquid effluent releases are concluded to be not applicable during unusual operating conditions that result in the activation of the Oconee Emergency Plan.
For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
The requirements that the appropriate portions of this system be used when specified provides assurance that the relea*ses 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 9-18
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Liquid Effluents 16.
11.1 REFERENCES
1. 10 CFR Part 20, Appendix B.
2. 40 CFR Part 141.
3. 10 CFR Part 50, Appendices A and I.
4. 40 CFR Part 190.
5. Offsite Dose Calculation Manual.
6. Regulatory Guide 1.109.
7. NUREG-1301 16.11.1-6 03/15/11 9-19
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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:
s;; 500 mrem/yr to the total body
s;; 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 :s;; 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:
s;; 15 mrad for gamma radiation
s;; 30 mrad for beta radiation ii. During any calendar year:
s;; 30 mrad for gamma radiation
s;; 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 9-20
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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.

N OT E---------------------------------------------

T he requirement of c.2 does not apply to the Auxiliary Building Exhaust System since it is not "treated" prior to release.
APPLICABILITY: At all times 16.11.2-2 03/27/99 9-21
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Gaseous Effluents 16.11.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Dose rate exceeds the A.1 Restore release rate to Immediately limits specified in within limits.
Commitment a.
B. Calculated dose B.1 Submit report to the 30 days from the end of exceeds specified limits. regional NRC Office which the quarter during which includes the following: the release occurred
a. Cause(s) for exceeding the limit(s),
and
b. A description of the program of corrective action initiated to:
reduce the releases of radioactive materials in gaseous effluents, and to keep these levels of radioactive materials in gaseous effluents in compliance with the specified limits or as low as reasonably achievable.
16.11.2-3 01131100 I 9-22
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Pe;riod 1/1/2017 -12/31/2017 Radioactive Gaseous Effluents 16.11.2 CONDITION REQUIRED ACTION COMPLETION TIME C. Radioactive gaseous C.1 Submit a report to the 30 days waste is discharged regional NRC Office which greater than limits includes the following:
specified in Commitment c.1 o*r a. Cause of equipment c.2. or subsystems inoperability, and AND
b. Corrective action to Radioactive gaseous restore equipment waste is discharged and prevent without treatment for recurrence.
more than 31 days.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.2.1 N/A N/A
/
16.11.2-4 03/27/99 9-23
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Gaseous Effluents 16.11.2 BASES 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 110 of Appendix I to 10 CFR Part 50.
16:11.2-5 01131100 I 9-24
l Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Gaseous Effluents 16.
11.2 REFERENCES
1 10 CFR Part 20, Appendix 8.
2. 10 CFR Part 50, Appendices A and I.
3. Regulatory Guide 1.109.
4. 40 CFR Part 190.
5. Offsite Dose Calculation Manual.
~ .
16.11.2-6 01131100 I 9-25
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 b.e OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.11.1.a are not exceeded.
b. Gaseous Process and Effluents The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 16.11.3-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.11.2.a are not exceeded.
c. The setpoints shall be determined in accordance with the methodology described in the ODCM and shall be recorded.

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

Correction to setpoints determined in accordance with Commitment c may be permitted without declaring the channel inoperable.
APPLICABILITY: According to Table 16.11.3-1 and Table 16.11.3-2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Alarm/trip setpoint less A.1 Declare channel Immediately conservative than inoperable.
required for one or more effluent monitoring instrument channels. A.2 Suspend release of Immediately
effluent monitored by the channel.
16.11.3-1 11120,oa I 9-26
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B.1 Enter the Condition Immediately liquid effluent monitoring referenced in Table instrument channels 16.11.3-1 for the inoperable. function.
AND B.2 Restore the 30 days instrument(s) to OPERABLE status.
C. One or more required C.1 Enter the Condition Immediately gaseous effluent referenced in Table monitoring instrument 16.11.3-2 for the channels inoperable. function.
AND C.2 Restore the 30 days instrument(s) to OPERABLE status.
D. Required Action and D.1 Explain in next Annual April 30 of following associated Completion Radiological Effluent calendar year Time of Required Action Release Report why B.2 or C.2 not met. inoperability was not corrected in a timely manner.
16.11.3-2 11120,os I 9-27
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1.1 Analyze two Prior to initiating Action 8.1 and independent samples subsequent release referenced in Table in accordance with 16.11.3-1. (RIA-33) SLC 16.11.4.
AND E.1.2 Conduct two Prior to initiating independent data entry subsequent release checks for release rate calculations AND E.1.3 Conduct two Prior to initiating independent valve subsequ.ent release lineups of the effluent pathway.
OR E.2 Suspend release of Immediately radioactive effluents by th is pathway.
F. As required by Required F.1 Suspend release of Immediately Action 8.1 and radioactive effluents by referenced in Table this pathway.
16.11.3-1. (RIA-54)
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 7
of at least 10- µCi/ml.
16.11.3-3 11120,oa I 9-28
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required -----------------NOTE------------------
Action B.1 and Not required during short, referenced in Table controlled outages of liquid 16.11.3-1. (Liquid effluent monitoring Radwaste Effluent Line instrumentation. Short controlled Flow Rate Monitor) outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.
G.1 Suspend release of Immediately radioactive effluents by this pathway.
G.2 Estimate flow rate Immediately during actual releases.
Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter 16.11.3-4 11120,os I 9-29
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME H. As required by Required ---------"-----NOTE------------------
Action 8.1 and Not required during short, referenced in Table controlled outages of liquid 16.11.3-1. (RIA-35, #3 effluent monitoring Chemical Treatment instrumentation. Short controlled Pond Composite outages are defined as planned Sampler and Sampler removals from service for Flow Monitor (Turbine durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Building Sumps for purposes of sample filter Effluent)) changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.
H.1 Suspend release of Immediately radioactive effluents by this pathway.
OR H.2 Collect and analyze Immediately grab samples for gross radioactivity (beta AND and/or gamma) at a lower limit of detection Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1
of at least 10- µCi/ml. thereafter 16.11.3-5 11120,os I 9-30
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required -----------. -----NOTE------------------
Action C.1 and Not required during short; referenced in Table controlled outages of gaseous 16.11.3-2 for effluent effluent monitoring releases from waste gas instrumentation. Short controlled tanks (RIA-37, RIA-38) outages are defined as planned or containment purges removals from service for (RIA-45). durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.
1.1.1 Analyze two Prior to initiating independent samples. subsequent release 1.1.2 Conduct two Prior to initiating independent data entry subsequent release checks for release rate
calculations 1.1.3 Conduct two Prior to initiating independent valve subsequent release lineups of the effluent pathway.
OR 1.2 Suspend release of Immediately radioactive effluents by this pathway.
16.11.3-6 . 11120,os I 9-31
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required ---------------NOTE--------------------
Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (Effluent effluent monitoring Flow Rate Monitor (Unit instrumentation. Short controlled Vent, Containment outages are defined as planned Purge, Interim removals from service for Radwaste Exhaust, Hot durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Machine Shop Exhaust, for purposes of sample filter Radwaste Facility changeouts, setpoint Exhaust, Waste Gas adjustments, service checks, Discharge)) and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.
J.1 Suspend release of Immediately radioactive effluents by this pathway.
OR J.2 Estimate flow rate Immediately Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter 16.11.3-7 11120,os I 9-32
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME K. As required by Required -----------------NOTE------------------
Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (RIA-45, effluent monitoring RIA-53, 4RIA-45) instrumentation. Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.
K.1 Suspend release of Immediately radioactive effluents by this pathway.
OR K.2.1 Collect grab sample. Immediately Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months K.2.2 Analyze grab samples 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from collection for gross activity (beta of sample and/or gamma).
16.11.3-8 11120108 I 9-33
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME L. As required by Required -----------------NOTE------------------
Action C.1 and N ot required during short, referenced in Table controlled ou_tages of gaseous 16.11.3-2. (Unit Vent effluent monitoring Monitoring Iodine instrumentation. Short controlled Sampler, Unit Vent outages are defined as planned Monitoring Particulate removals from service for Sampler, Interim durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Radwaste Building for purposes of sample filter '
Ventilation Monitoring changeouts, setpoint Iodine Sampler, Interim adjustments, service checks Radwaste Building and/or routine maintenance '
Ventilation Monitoring procedures. This guidance may Particulate Sampler, Hot be applied successively, Machine Shop Iodine provided that time between Sampler, Hot Machine successive short, controlled Shop Particulate outages is always at least equal Sampler, Radwaste to duration of immediately Facility Iodine Sampler, preceding outage.
Radwaste Facility Particulate Sampler)
L.1 Suspend release of Immediately radioactive effluents by this pathway.
OR L.2.1 -----------NOTE-----------
The collection time of each sample shall not exceed 7 days.
Collect samples Immediately continuously using auxiliary sampling equipment.
AND L.2.2 Analyze each sample. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from end of each sample collection 16.11.3-9 11120108 I 9-34
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME M. As required by Required -----------------NOTE------------------
Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2 for effluent effluent monitoring*
from ventilation system instrumentation. Short controlled or condenser air outages are defined as planned ejectors. (RIA-40) removals from service for durations not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 Contfnuously monitor Immediately release through the unit vent.
OR M.2 Suspend release of Immediately radioactive effluents by this pathway.
OR M.3.1 Collect grab sample. Immediately Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months M.3.2 Analyze grab sample for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from collection gross activity (beta of grab sample .
and/or gamma).
16.11.3-10 1112010s I 9-35
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.3.1 ------------------------NO 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 releases are made.
Perform Channel Response Check. During each release via this pathway SR 16.11.3.2 ------------------------NOTE----------------------------
The Channel Response check shall consist of verifying indications during periods of release.
Channel response checks shall be made at least once per calendar day on days in which continuous, periodic or batch releases are made.
Perform Channel Response Check. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 16.11.3.3 Perform Source Check. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 16.11.3.4 Perform Source Check. 31 days SR 16.11.3.5 Perform Source Check. 92 days 16.11.3-11 1112010a I 9-36
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE FREQUENCY SR 16.11.3.6 -----------------------NOTE----------------------------
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following c:'onditions exist:
1. Instrument indic:;ates measured levels above the alarm/trip setpoint.
2. Circuit failure (downscale only).
Perform CHANNEL FUNCTIONAL TEST. 92 days SR 16.11.3.7 ------------------------NOTE----------------------------
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if any of the following conditions exist:
1. Instrument indicates measured levels above the alarm/trip setpoint.
2. Circuit failure (downscale only).
92 days Perform CHANNEL FUNCTIONAL TEST.
SR 16.11.3.8 Perform CHANNEL FUNCTIONAL TEST. 92 days 16.11.3-12 11120108 I 9-37
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE FREQUENCY SR 16.11.3.9 -------------------------NOTE---------------------------
The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have*been obtained from suppliers that participate in measurement assurance activities with the National Institute of Standards and Technology (NIST). The standards shall permit calibrating the system over its intended range of energy and measurement. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (Operating plants may substitute previously established calibration procedures for these requirements.)
12 months Perform CHANNEL CALIBRATION.
SR 16.11.3.10 Perform CHANNEL CALIBRATION. 12 months SR 16.11.3.11 Perform leak test. When cylinder gates or wicket gates are reworked SR 16.11.3.12 Perform Source Check. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to each release via associated pathway 16.11.3-13 1112010a I 9-38
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABILITY REQUIREMENTS ACTION B.1
1. Monitors Providing Automatic Termination of Release
a. Liquid Radwaste Effluent At all times SR 16.11.3.1 E Line Monitor, RIA-33 SR 16.11.3.3 SR 16.11.3.6 SR 16.11.3.9
b. Turbine Building Sump, At all times SR 16.11.3.2 F RIA-54 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9
2. Monitors not Providing Automatic Termination of Release Low Pressure Service Water At all times SR 16.11.3.2 H RIA-35 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9
3. Flow Rate Measuring Devices
a. Liquid Radwaste Effluent At all times SR 16.11.3.1 G Line Flow Rate Monitor SR 16.11.3.10 (OLW CR0725 or OLW SS0920)
b. Liquid Radwaste Effluent NA NA SR 16.11.3.1 NA Line Minimum Flow SR 16.11.3.10 Device
c. Turbine Building Sump NA NA SR 16.11.3.1 NA Minimum Flow Device SR 16.11.3.10
d. Low Pressure Service NA NA SR 16.11.3.1 NA Water Minimum Flow SR 16.11.3.10 Device 16.11.3-14 11120,os I 9-39
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABILITY REQUIREMENTS ACTION B.1
e. Keowee Hydroelectric NA NA SR 16.11.3.11 NA Tailrace Discharge<*>
4. Continuous Composite Sampler
3 Chemical Treatment At all times SR 16.11.3.2 H Pond Composite Sampler SR 16.11.3.10 and Sampler Flow Monitor (Turbine Building Sumps Effluent)
(a) Flow is determined from the number of hydro units operating. If no hydro units are operating, leakage flow will be assumed to be 38 cfs based on historical data.
16.11.3-15 11120,os I 9-40
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE SURVEILLANCE REQUIRED INSTRUMENT PATH) APPLICABILITY REQUIREMENTS ACTION C.1
1. 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 Purge Isolation Function)
b. Noble Gas Activity At all times SR 16.11.3.2 K Monitor Providing Alarm. SR 16.11.3.4 (RIA 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 L
d. Particulate Sampler At All Times SR 16.11.3.2 L
.e. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Unit Vent Flow) SR 16.11.3.10 (MSC CR0001)
f. Sampler Flow Rate At All Times SR 16.11.3.2 NA Monitor<*> (Annunciator) SR 16.11.3.10
g. Effluent Flow Rate During Containment SR 16.11.3.2 J Monitor (Containment Purge Operation SR 16.11.3.10 Purge)(MSC CR0001)
h. CSAE Off Gas Monitor During Operation SR 16.11.3.2 M (RIA-40) ofCSAE SR 16.11.3.5 SR 16.11.3.8 SR 16.11.3.9
2. Interim Radwaste Building Ventilation Monitoring System
a. Noble Gas Activity At All Times SR 16.11.3.2 K 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 L C. Particulate Sampler At All Times SR 16.11.3.2 L
d. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Interim SR 16.11.3.10 Radwaste Exhaust)
(GWD FT0082)
e. Sampler Flow Rate At All Times SR 16.11.3.2 NA Monitor<*/ (Annunciator)
SR 16.11.3.10 16.11.3-16 1.112010a I 9-41
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE ,SURVEILLANCE REQUIRED INSTRUMENT PATH) APPLICABILITY REQUIREMENTS ACTION C.1
3. Hot Machine Shop Ventilation Sampling System
a. Iodine Sampler At All Times SR 16.11.3.2 L
b. Particulate Sampler At All Times SR 16.11.3.2 L C. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Hot Machine SR 16.11.3.10 Shop Exhaust)
(Totalizer)
d. Sampler Flow Rate At All Times SR 16.11.3.2 NA Monitor <*l (Annunciator) SR 16.11.3.10
4. Radwaste Facility Ventilation Monitoring System
a. Noble Gas Activity At All Times SR 16.11.3.2 K Monitor (4-RIA-45) SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9
b. Iodine Sampler At All Times SR 16.11.3.2 L C. Particulate Sampler At All Times SR 16.11.3.2 L
d. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Radwaste SR 16.11.3.10 Facility Exhaust) (OVS CR2060)
e. Sampler Flow Rate At All Times SR 16.11.3.2 NA Monitor <*l (Annunciator) SR 16.11.3.10
5. Waste Gas Holdup Tanks
a. Noble Gas Activity During Waste Gas SR 16.11.3.1 Monitor - Providing Holdup Tank Releases SR 16.11.3.6 Alarm and Automatic SR 16.11.3.9 Termination of Release SR 16.11.3.12 (RIA-37,-38)b
b. Effluent Flow Rate During Waste Gas SR 16.11.3.1 J Monitor (Waste Gas Holdup Tank Releases SR 16.11.3.10 Discharge Flow) (MSC CR0001)
(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 11120,os I 9-42
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Monitoring Instrumentation 16.11.3 BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRG 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 radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarm/trip will occur prior to exceeding applicable dose limits in SLC 16.11.2. The operability end use of this instrumentation is consistent 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months end every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ), Action is not required.
Failures such as blown instrument fuses, defective indicators, and faulted amplifiers are, in many cases, revealed by alarm or annunciator action. Comparison of output and/or state of independent channels measuring the same variable supplements this type of built-in surveillance. Based on experience in operation of both conventional and nuclear systems, when the unit is in operation, the minimum checking frequency stated is deemed adequate.
REFERENCES:
1. 10 CFR Part 20.
2. 10 CFR Part 50, Appendix A.
3. Of~site Dose Calculation Manual.
4. UFSAR, Section 7.2.3.4.
16.11.3-18 11120108 I 9-43
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Operational Safety Review 16.11.4 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.4 Operational Safety Review COMMITMENT Required sampling should be performed as detailed in Table 16.11.4-1.
APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.4.1 N/A N/A 16.11.4-1 06130114 I 9-44
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection of Lab Analysis for Waste
1. Decant Monitor a. Principal Gamma Composite Grab Sample <5E-06 µCi/ml (Ce-144)
Tank, Turbine Emitters<c) including prior to release of each <5E-07 µCi/ml (Other Gamma Nuclides)
Building Sump Dissolved Noble batch<h> <1E-05 µCi/ml (Dissolved Gases)
Monitor Tanks, Gases <1E-06 µCi/ml (l-131)
Waste and Recycle MonitorTanks
b. Radiochemical Quarterly from all <5E-08 µCi/ml Analysis Sr-89 and composited batches<n Sr-90
c. Tritium Monthly Composite <1 E-05 µCi/ml
d. Gross Alpha Activity Monthly Composite <1E-07 µCi/ml
2. Unit Vent Sampling a. Iodine Spectrum<a> Continuous monitor, <1E-10 µCi/cc (1-133)0>
(Includes Waste weekly sample<*> <1E-12 µCi/cc (l-131)0>
Gas Decay Tanks, Reactor Building Purges, Auxiliary b. Particulates<*)
Building Ventilation, Spent Fuel Pool i. Ce-144 & Mo-99 Weekly Composite<*) <5E-10 µCi/ccU><k>
Ventilation, Air Ejectors) ii. Other Principle Weekly Composite<*> < 1E-11 µCi/ccm Gamma Emitters (d) iii. Gross Alpha Monthly, using composite <1E-11 µCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 µCi/cc Analysis Sr-89, Sr-90 C. Gases by Principle Weekly Grab Sample <1 E-04 µCi/cc Gamma Emitters<d>
d. Tritium Weekly Grab Sample <1 E-06 µCi/cc
3. Waste Gas Decay a. Principle Gamma Grab Sample prior to <1 E-04 µCi/cc (gases)
Tank Emitters<d> release of each batch <1 E-1 O µCi/cc (particulates and iodines)
<5E-09 µCi/cc (Ce-144 and Mo-99)
b. Tritium Grab Sample prior to <1 E-06 µCi/cc release of each batch
4. Reactor Building a. Principle Gamma Grab sample each purge <1E-04 µCi/cc (gases)
Emitters<dJ <1E-10 µCi/cc (particulates and iodines)
<5E-09 µCi/cc (Ce-144 and Mo-99)
b. Tritium Grab sample each purge <1 E-06 µCi/cc 16.11.4-2 06/30/14
g-45
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection<b) of Lab Analysis for Waste
5. Not Used
6. #3 Chemical a. Principle Gamma Weekly Continuous <5E-07 µCi/ml Treatment Pond Emitters<0l Composite<9l Effluent<0
b. 1-131 Weekly Continuous <1 E-06 µCi/ml Composite<9l
c. Tritium Monthly Continuous <1E-05 µCi/ml Composite<9l
d. Gross Alpha Monthly Continuous <1 E-07 µCi/ml Activity Composite<9l
e. Sr-Bg & Sr-go Quarterly Continuous <5E-08 µCi/ml Composite<9l
f. Dissolved and Monthly Grab <1 E-05 µCi/ml Entrained gases (Gamma Emitters)
7. Radwaste Facility a. Iodine Spectrum<*> Continuous monitor, (l-133) <1E-Qg µCi/cc Ventilation weekly sample<*) (l-131) <1E-11 µCi/cc
b. Particulate<*)
i. Ce-144 and Mo- Weekly Composite<*) <5E-10 µCi/ccm gg ii. Other Principle Weekly Composite<*> < 1E-11 µCi/ccOl Gamma Emitters<dl iii. Gross Alpha Monthly, using composite <1 E-11 µCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1 E-11 µCi/cc Analysis Sr-Bg, Sr-go C. Gases by Weekly Grab Sample <1 E-04 µCi/cc Principle Gamma<dl Emitters
d. Tritium Weekly Grab Sample <1 E-06 µCi/cc 16.11.4-3 06/30/14 9-46
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection(b) of Lab Analysis for Waste
8. Hot Machine Shop a. Iodine Spectrum Weekly Sample(*> (1-133) <1E-10 µCi/cc(J)
Ventilation (l-131) <1E-12 µCi/cc(J)
b. Particulate
i. Ce-144 and Mo- Weekly Composite(*> <5E-10 µCi/cc(J)(k) gg ii. Other Principle Weekly Composite<*> < 1E-11 µCi/ccO>
Gamma Emitters (d) iii. Gross Alpha Monthly, using composite <1E-11 µCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 µCi/cc Analysis Sr-89, Sr-90 C. Gases by NA NA Principle Gamma Emitters
d. Tritium NA NA
9. Interim Radwaste a. Iodine Spectrum Weekly sample(*> (1-133) <1E-10 µCi/ccO>
Building (1-131) <1 E-12 µCi/cc(J)
Ventilation
b. Particulate
i. Ce-144 and Mo- Weekly Composite(*> <5E-10 µCi/cc 0>
gg
< 1E-11 µCi/ccO>
ii. Other Principle Weekly Composite<*>
Gamma Emitters(d) iii. Gross Alpha Monthly, using composite <1 E-11 µCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 µCi/cc Analysis Sr-89, Sr-90 C. Gases by Weekly Grab Sample <1 E-04 µCi/cc Principle Gamma<d>
Emitters
d. Tritium Weekly Grab Sample <1E-06 µCi/cc 16.11.4-4 06/30/14 9-47
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 / T) + 4.65 Sb E x V x 2.22E06 x Y x exp (-Mt)
Where:
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),
Eis the counting efficiency (as counts per disintegration),
Vis the sample size (in units of mass or volume),
2.22E06 is the number of disintegrations per minute per micro Curie, Y is the fractional radiochemical yield (when applicable),
" is the radioactive decay constant for the particular nuclide
!J. tis 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.
T is the sample counting time in minutes Typical values of E, V, Y and !J. t 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 9-48
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (on or after removal from sampler).
0) When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. Samples shall be analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (on or after removal from sampler).
(k) Ce-144 and Mo-99 LLD as approved by NRC SER dated January 16, 1984 (Reference 1).
16.11.4-6 06/30/14 9-49
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 06130114 I
9-50
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 9-51
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Solid Radioactive Waste 16.11.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Applicable regulatory A.1 Suspend shipments of Immediately requirements for defectively packaged solidified or dewatered solid radioactive wastes wastes are not from the site.
satisfied.
AND A.2 Initiate action to correct Prior to next shipment for PCP, procedures, or disposal of solidified or solid waste equipment dewatered wastes as necessary to prevent recurrence.
8. A solidification test as 8.1 Suspend solidification of Immediately described in the PCP the batch under test and fails to verify follow PCP guidance for Solidification. test failures until solidification of the batch is verified by subsequent tests.
AND 8.2 The PCP shall be Prior to next solidification modified as required to for shipment of waste for assure Solidification of disposal at a 10 CFR 61 subsequent batches of disposal site waste.
16.11.5-2 10130102 I 9-52
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Solid Radioactive Waste 16.11.5 CONDITION REQUIRED ACTION COMPLETION TIME C. With solidification or C.1 Reprocess or repackage Prior to shipment for dewatering for disposal the waste in accordance disposal of the not performed in with PCP requirements. inadequately processed accordance with the waste that requires PCP. OR solidiffcation or dewatering C.2 Follow PCP or procedure guidance for alternative free standing liquid verification to ensure the waste in each container meets disposal requirements and take appropriate administrative action to prevent recurrence.
D. With the solid waste D.1 Restore the equipment to In a time frame that equipment incapable of OPERABLE status or supports the meeting commitment or provide for alternative commitment not in service. capability to process wastes as necessary to satisfy all applicable disposal requirements.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.5.1 The Process Control Program shall be used Every tenth batch of each to verify the solidification of at least one type of radioactive waste representative test specimen from at least to be solidified.
every tenth batch of each type of radioactive waste to be solidified for disposal at a 10 CFR 61 disposal site.
16.11.5-3 10130102 I 9-53
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 10CFR61 waste form criteria for solidified and dewatered radioactive wastes.
REFERENCES:
1. 10 CFR Part 50, "Domestic Licensing of. Production and Utilization Facilities".
2. 10 CFR Part 50, Appendix A.
3. 10 CFR20, "Standards for Protection Against Radiation".
4. 10 CFR61, "Licensing 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 Co'ntrols 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 9-54
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.6 Radiological Environmental Monitoring COMMITMENT a. The radiological environmental monitoring samples shall be collected in accordance with Table 16.11.6-1 and shall be analyzed pursuant to the requirements of Tables 16.11.6-1 and 16.11.6-2.
b. A land use census shall be conducted and shall identify the location of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of eight kilometers (five miles). Broad leaf vegetation sampling shall be performed at the site boundary in the direction sector with the highest 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---------------------------------------------

1f 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.
APPLICABILITY: At.all times 16.11.6-1 111a113 I 9-55
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A Radiological A.1 Submit a description of May 15 of following environmental the reason for not calendar year monitoring program is conducting the program not conducted as as required and plans to required. prevent a recurrence shall be included in the Annual Radiological Environmental Operating Report.
B. Land use census B.1 -----------NOTE-----------
identifies a Location The sampling location which yields a having the lowest calculated dose or dose calculated dose or dose commitment (via the commitment (via the same exposure same exposure pathway) 20% greater pathway) may be than a location from deleted from this which samples are monitoring program currently being after October 31 of the obtained. year in which this land use census was conducted.
Add new location to the 30 days radiological environmental monitoring program.
AND B.2 Identify new locations in April 30 of following the next Annual calendar year Radioactive Effluent Release Report.
16.11.6-2 11,a,13 I 9-56
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Interlaboratory C.1 Report corrective May 15 of following Comparison Program actions in the Annual calendar year analyses not performed Radiological as required. Environmental Operating Report.
D. Radioactivity level D.1 Prepare and submit a 30 days resulting from plant Special report that effluents in identifies the cause for environmental sampling exceeding the limits and medium at a specified defines the corrective location in excess of actions to be taken to reporting limits of Table reduce radioactive 16.11.6-3 when effluents so that the averaged over a potential annual dose to calendar quarter. a MEMBER OF THE PUBLIC is less than the calendar year limits of SLC 16.11.1 or 16.11.2.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.6.1 Conduct land use census during growing 12 months season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.
16.11.6-3 111s113 I 9-57
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Number of Exposure Pathway and/or Sampling and Collection Sample Time and Frequency of Analysis Sample Frequency (d)
Locations (b)
1. AIRBORNE Radioiodine and 5 Continuous sampler Radioiodine canister:
Particulates operation with sample 1-131 analysis weekly. Particulate collection weekly, or sampler: Gross beta radioactivity more frequently if analysis following filter change; and required by dust loading. gamma isotopic analysis of composite (by location) quarterly. (c)
2. DIRECT RADIATION 40 Quarterly. Gamma dose quarterly.
3. WATERBORNE
a. Surface 2 Composite (a) sample Gamma isotopic analysis monthly.
over a 1-month period.
Composite for tritium analysis quarterly.
b. Drinking 3 Composite (a) sample Composite for gross beta and gamma over a 1-month period. isotopic analyses monthly.
Composite for tritium analysis quarterly.
c. Sediment from 2 Semiannually. Gamma isotopic analysis Shoreline semiannually.
16.11.6-4 111a113 I 9-58
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Number of Exposure Pathway and/or Sampling and Collection Sample Time and Frequency of Analysis Sample Frequency (d)
Locations (b)
4. INGESTION
a. Milk 4(e) Semimonthly when Gamma isotopic and 1-131 analysis animals are on pasture; semimonthly when animals are on monthly at other times. pasture; monthly at other times.
b. Fish 2 Semiannually. One Gamma isotopic analysis sample each semiannually on edible portion.
commercially and recreationally important species.
c. Broad-leaf 2 Monthly. Gamma isotopic analysis monthly.
Vegetation (a) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
(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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 11,a,13 I 9-59
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)
Airborne Fish Broad-leaf Water Particulate or Milk Sediment Analysis Vegetation Gases (pCi/kg, (pCi/1) (pCi/1) (pCi/kg, dry) 3 wet) (pCi/kg, wet)
Ci/m Gross Beta 4 1E-02 H3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 15 Nb-95 15 1-131 15(b) ?E-02 60 Cs-134 15 5E-02 130 15 60 150 Cs-137 18 6E-02 150 18 80 180 Ba-140 15 60 La-140 15 15 (a) The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample with 95% probability of detection and 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 IT) + 4.65 Sb E xV x 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 9-60
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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)
'A is the radioactive decay constant for the particular radionuclide 11 tis 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 11 t should be used in the calculation.
The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances, may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual 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 pCi/liter of 1-131 in drinking water. For low level analyses of 1-131 an LLD of 1 pCi/liter will be achieved.
(c) Other peaks which are measurable and identifiable, together with the radionuclides in Table 16.11.6-2, shall be identified and reported.
16.11.6-7 111s113 I 9-61
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples (c) (d)
Airborne Broad-leaf Water Particulate or Fish Milk Analysis Vegetation Gases (pCi/1) (pCi/kg, wet) (pCi/1) 3 (pCi/kg, wet)
Ci/m H-3 2E04(a)
Mn-54 1 E03 3E04 Fe-59 4E02 1E04 Co-58 1E03 3E04 Co-60 3E02 1E04 Zn-65 3E02 2E04 Zr-Nb-95 4E02 1-131 2(b) 0.9 3 1E02 Cs-134 30 10 1E03 60 1E03 Cs-137 50 20 2E03 70 2E03 Ba-La-140 2E02 3E02 (a) For drinking water samples. This is 40 CFR Part 141 value.
(b) If low level 1-131 analyses are performed.
(c) Report shall be submitted when any single radionuclide exceeds the reporting level in Table 16.11.6-3 or when more than one of the radionuclides in Table 16.11.6-3 are detected in sampling medium and concentration (1) + concentration (2) + ... .:: 1.0 reporting level (1) reporting level (2)
(d) Report shall be submitted when radionuclides other than those in table 16.11.6-3 are detected and are the result of plant effluents if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of SLC 16.11.1 or 16.11.2.
16.11.6-8 1118113 I 9-62
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 111/2017 -12/3112017 Radiological Environmental Monitoring 16.11.6 BASES 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 requirements for participation in an lnterlaboratory Comparison Program is provided to assure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
With the level of radioactivity in an environmental sampling medium at a specified location exceeding the reporting levels of Table 16.11.6-3 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days a Special Report that defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of SLC 16.11.1 or SLC 16.11.2. When more than one of the radionuclides in Table 16.11.6-3 are detected in the sampling medium, this report shall be submitted if concentration (1) + concentration (2) + ... ~ 1. 0 reporting level (1) reporting level (2)
When radionuclides other than those in Table 16.11.6-3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of SLC 16.11.1 or SLC 16.11.2. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2. The methodology and parameters used to estimate the potential annual dose to a MErv]BER OF THE PUBLIC shall be indicated in the 30-day Special Report.
16.11.6-9 111a113 I 9-63
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 9-64
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Dose Calculations 16.11.7 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.7 Dose Calculations COMMITMENT The annual (calendar year) dose or dose commitment, to any Member- of the Public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to ::; 25 mrems to the total body or to any organ, except the thyroid, which shall be limited to::; 75 mrems.
APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A Calculated doses from A.1 Determine by None the release of calculation, including radioactive materials in direct radiation liquid or gaseous contributions from the effluents exceeding reactor units and from twice the limits of SLC outside storage tanks, 16.11.1.b, SLC whether the limits of 16.11.2.b.1, or SLC Commitment 16.11. 7 16.11 .2.b.2 have been exceeded.
16.11.7-1 01131100 I 9-65
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Dose Calculations 16.11.7 CONDITION REQUIRED ACTION COMPLETION TIME
8. Calculated dose -------------------N OT E----------------
exceeds limits of T his Special Report, as defined Commitment 16.11.7. in 10 CFR Part 20.2203(a), shall include an analysis that estimates the radiation exposure (dose) to a Member of the Public from uranium fuel cycle sources, (including all effluent pathways and direct radiation), for the calendar year that includes the release(s) covered by this report.
It shall also describe the levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations.
8.1 Prepare and submit to the Commission a 30 days Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the specified limits and includes the schedule for achieving conformance with the specified limits.
16.11.7-2 01131100 I 9-66
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 Determine cumulative dose contributions from 31 days liquid effluents in accordance with Offsite Dose Calculation Manual.
SR 16.11.7.2 Determine cumulative dose contributions from 31 days gaseous effluents in accordance with Offsite Dose Calculation Manual.
BASES 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 ac.hievable." 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 9-67
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Dose Calculations 16.
11.7 REFERENCES
1. 10 CFR Part 20.
2. 40 CFR Part 190.
3. Offsite Dose Calculation Manual.
4. 10 CFR Part 50, Appendix I.
16.11. 7-4 01131100 I 9-68
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Reports 16.11.8 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.8 Reports COMMITMENT Special reports shall be submitted to the Regional Administrator, Region II, 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 REQUIRED ACTION COMPLETION TIME A. Individual milk samples A.1 Submit plan advising 7 days show 1-131 the NRC of the concentrations of 1O proposed action to picocuries per liter or ensure the plant related greater. annual doses will be within the design objective of 45 mrem/yr to the thyroid of any individual.
16.11.8-1 1212110s I 9-69
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Reports 16.11.8 CONDITION REQUIRED ACTION COMPLETION TIME B. Milk samples collected B.1 Submit a plan advising 30 days over a calendar quarter the NRC of the show 1-131 average proposed action to concentrations of 4.8 ensure the plant related picoCuries per liter or annual doses will be greater within the design objective of 45 mrem/yr to the thyroid of any individual.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.8.1 NA 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 12121109 I 9-70
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 efflu'ents 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 riot corrected in a timely manner per SLC 16.11.3.
- 16.11.9-1 03122110 I 9-71
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 9-72
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Effluent Release Report 16.11.9 I
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. N/A 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.
16.1.1.9-3 03122110 I 9-73
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 obtained 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 characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and, the result of land use censuses. Subsequent reports shall describe all substantial changes in these aspects.
APPLICABILITY: At all times.
16.11.10-1 05114114 I 9-74
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 1 Radiological Environmental Operating Report 16.11.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.10.1 NA NA BASES NA
REFERENCES:
1. Oconee ITS
2. Offsite Dose Calculation Manual 16.11.10-2 05114114 I 9-75
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Iodine Radiation Monitoring filters 16.11.11 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.11 Iodine Radiation Monitoring Filters COMMITMENT Assure that the iodine radiation monitoring filters perform their intended function.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.11.1 Remove and replace iodine radiation 30 days of operation monitoring filters in RIA-44.
SR 16.11.11.2 Discard spare iodine radiation monitoring After 24 months of shelf filters. life.
BASES 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 9-76
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Material in Outside Temporary Tanks Exceeding Limit 16.11.12 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.12 Radioactive Material in Outside Temporary Tanks Exceeding Limit COMMITMENT The quantity of radioactive material in outside temporary storage tanks shall not exceed the limit specified in ITS 5.5.13.c.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The quantity of A.1 Suspend addition of Immediately radioactive material in radioactive material to outside temporary tank.
storage tank not within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.12.1 Verify the quantity of radioactive material Within 7 days after contained in each of the outside temporary addition of radioactive tanks is within the limit by analyzing a materials to an representative sample of the tanks' contents. outside temporary tank OR Verify the quantity of radioactive material in Prior to addition of each of the outside temporary tanks does not radioactive materials to result in exceeding the limit by analyzing a an outside temporary representative sample of radioactive material tank.
to be added.
16.11.12-1 04110103 I 9-77
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Radioactive Material in Outside Temporary Tanks Exceeding Limit 16.11.12 BASES 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 10CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
REFERENCES N/A 16.11.12-2 04110103 I 9-78
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 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 COMPLETION TIME A. The quantity of A.1 Suspend addition of Immediately radioactive material in radioactive material to the Waste Gas Holdup tank.
tank not within limit.
AND A.2 Reduce tank contents 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.13.1 Verify quantity of radioactive materials in each 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when tank is tank is within limit. being filled BASES 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 9-79
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 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 9-80
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1;, 2, & 3 Period 1/1/2017 -12/31/2017 Explosive Gas Mixture 16.11.14 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.14 Explosive Gas Mixture COMMITMENT The concentration of Hydrogen in the Waste Gas Holdup Tanks shall be
~ 3% by volume.
APPLICABILITY: At all times.
ACTIONS

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

Separate Condition Entry is allowed for each tank.
CONDITION REQUIRED ACTION COMPLETION TIME A Concentration of A.1 Reduce Concentration 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Hydrogen in Waste of Hydrogen to within Gas Holdup tank is> limit.
3% and~ 4% by volume.
B. Concentration of B.1 Suspend addition of Immediately Hydrogen in Waste waste gases to tank.
Gas Holdup tank is >
4% by volume. AND B.2 Reduce Concentration 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of Hydrogen to within limit.
16.11.14-1 03/27/99 9-81
Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 Explosive Gas Mixture 16.11.14 SURVEILLANCE REQUIREMENTS S.URVEILLANCE FREQUENCY SR 16.11 .14.1 Verify Hydrogen concentration in Waste Gas 5 times/week on each Holdup Tank is~ 3% by volume. tank when in service once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after isolation of the tank BASES 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 9-82
Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 ATTACHMENT 10 Summary of Changes to the Process Control Program This attachment includes a summary of changes to the PCP.
Page 10-1
Attachment 10 Summary of Changes to the Process Control Program Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 The Oconee Nuclear Station PCP was not revised in 2017. 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 1/1/2017 - 12/31/2017 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 1/1/2017 - 12/31/2017 No major modifications to Oconee Nuclear Station *liquid, gaseous, solid, or mobile radioactive waste treatment systems occurred in 2017.
Page 11-2
Attachment 12 Errata to a Previous Year's ARERR Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 ATTACHMENT 12 Errata to a Previous Year's ARERR This attachment includes any amended pages from a previous year's ARERR.
Page 12-1
Attachment 12 Errata to a Previous Year's ARERR Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 -12/31/2017 There is one (1) change to a previous year's ARERR.
The following contains amended pages to the Oconee Nuclear Station 2016 ARERR. Amended pages are identified with "Amendment#" on page. Specific changes are' identified with change bars in right margin.
The Oconee Nuclear Station 2016 ARERR Amendment #1 requires the following changes to Attachment 1 (Reference NCR 02139552).
Oconee Nuclear Station 2016 ARERR Attachment 1 Page 1-2 as submitted:
B. lodine-131
1. Total Release Ci O.OOE+OO O.OOE+OO 0.00E+OO 4.92E-10 4.92E-10
2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO 6.19E-11 1.56E-11 Oconee Nuclear Station 2016 ARERR Attachment 1 Page 1-2 Amendment #1 as revised:
B. lodine-131
1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.92E-09 4.92E-09
2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO 6.19E-10 1.56E-10 Oconee Nuclear Station 2016 ARERR Attachment 1 Page 1-4 as submitted:
B. Iodines 1-131 Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.92E-10 4.92E-10 1-133 Ci O.OOE+OO 8.22E-10 O.OOE+OO 4.84E-10 1.31 E-09 Total for Period Ci O.OOE+OO 8.22E-10 0.00E+OO 9.76E-10 1.80E-09 Oconee Nuclear Station 2016 ARERR Attachment 1 Page 1-4 Amendment #1 as revised:
B. Iodines 1-131 Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.92E-09 4.92E-09 1-133 Ci O.OOE+OO 8.22E-10
O.OOE+OO 4.84E-10 1.31 E-09 Total for Period Ci O.OOE+OO 8.22E-10 O.OOE+OO 5.41 E-09 6.23E-09 Page 12-2
Attachment 12 Errata to a Previous Year's ARERR Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2016 ~ 12/31/2016 Gaseous Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases
1. Total Release Ci 1.06E+OO . 2.56E+OO 7.60E+OO 9.71E+OO 2.09E+01
2. Avg. Release Rate µCi/sec 1.35E-01 3.26E-01 9.57E-01 1.22E+OO 6.62E-01
8. lodine-131
1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.92E-09 4.92E-09
2. Avg. Release Rate µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO 6.19E-10 1.56E-10 C. Particulates Half-Life::: 8 days
1. Total Release Ci O.OOE+OO 1.74E-10 1.58E-10 O.OOE+OO 3.32E-10
2. Avg. Release Rate µCi/sec O.OOE+OO 2.22E-11 1.98E-11 O.OOE+OO 1.05E-11 D. Tritium
1. Total Release Ci 3.07E+01 3.08E+01 2.23E+01 4.93E+01 1.33E+02
2. Avg. Release Rate µCi/sec 3.90E+OO 3.92E+OO 2.81 E+OO 6.20E+OO 4.21E+OO E. Carbon-14
1. Total Release Ci 5.54E+OO 5.52E+OO 6.02E+OO 5.60E+OO 2.27E+01
2. Avg. Release Rate µCi/sec 7.05E-01 7.02E-01 7.57E-01 7.05E-01 7.18E-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+OO O.OOE+OO Page 1-2 Oconee Nuclear Station 2016 ARERR Attachment 1 Amendment #1 Page 12-3
Attachment 12 Errata to a Previous Year's ARERR Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2017 - 12/31/2017 Attachment 1 Summary of Gaseous and Liquid Effluents Oconee Nuclear Station Units 1, 2, & 3 Period 1/1/2016-12/31/2016 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 1.61E-02 2.37E-02 2.44E-04 4.01E-02 KR-85M Ci O.OOE+OO 6.78E-05 4.27E-06 O.OOE+OO 7.20E-05 KR-88 Ci O.OOE+OO 5.42E-05 O.OOE+OO O.OOE+OO 5.42E-05 XE-131M Ci O.OOE+OO O.OOE+OO 1.15E-04 2.33E-04 3.49E-04 XE-133 Ci 2.16E-03 7.59E-02 1.48E-02 4.40E-02 1.37E-01 XE-133M Ci O.OOE+OO 4.99E-04 1.76E-04 3.58E-04 1.03E-03 XE-135 Ci 1.14E-06 4.89E-03 3.74E-04 6.71E-04 5.93E-03 XE-138 Ci O.OOE+OO O.OOE+OO 8.81E-04 O.OOE+OO 8.81E-04 Total for Period Ci
2.16E-03 9.75E-02 4.01E-02 4.70E-02 1.85E-01 B. Iodines 1-131 Ci 0.00E+OO O.OOE+OO O.OOE+OO 4.92E-09 4.92E-09 1-133 Ci O.OOE+OO 8.22E-10 O.OOE+OO 4.84E-10 1.31 E-09 Total for Period Ci O.OOE+OO 8.22E-10 O.OOE+OO 5.41E-02 6.23E-09 C. Particulates Half-Life .:: 8 days C0-58 Ci O.OOE+OO 1.74E-10 O.OOE+OO O.OOE+OO 1.74E-10 CS-137 Ci O.OOE+OO O.OOE+OO 1.58E-10 O.OOE+OO 1.58E-10 Total for Period Ci O.OOE+OO 1.74E-10 1.58E-10 O.OOE+OO 3.32E-10 D. Tritium H-3 Ci 3.31E-05 2.19E-02 4.23E-02 1.29E-01 1.93E-01 E. Carbon-14 C-14 .Ci. 3.88E+OO 3.86E+OO 4.21E+OO 3.92E+OO 1.59E+01 F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO
70% of total C-14 released is assumed to be in batch mode. See Attachment 2, Supplemental Information, of this report.
Page 1-4 Oconee Nuclear Station 2016 ARERR Attachment 1 Amendment #1 Page 12-4

ONS-2018-024, 2017 Annual Radioactive Effluent Release Report (ARERR)

Contents

Text

Subject:

16.1 INTRODUCTION

11.1 REFERENCES

11.2 REFERENCES

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11.7 REFERENCES

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16.1 INTRODUCTION

11.1 REFERENCES

11.2 REFERENCES

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11.7 REFERENCES

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ONS-2018-024, 2017 Annual Radioactive Effluent Release Report (ARERR)

Text

Subject:

16.1 INTRODUCTION

11.1 REFERENCES

11.2 REFERENCES

REFERENCES:

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REFERENCES:

11.7 REFERENCES

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Subject:

16.1 INTRODUCTION

11.1 REFERENCES

11.2 REFERENCES

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11.7 REFERENCES

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