ONS-2015-043, Oconee, Units 1, 2, and 3 - Submittal of 2014 Annual Radioactive Effluent Release Report (ARERR)

Oconee, Units 1, 2, and 3 - Submittal of 2014 Annual Radioactive Effluent Release Report (ARERR)

ML15138A113
Person / Time
Site:	Oconee
Issue date:	04/30/2015
From:	Batson S L Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15138A128	List: ML15138A113 ML15138A125 ONS-2015-043, Oconee, Units 1, 2, and 3 - Offsite Dose Calculation Manual (Odcm), Revision 56 ONS-2015-043, Oconee, Units 1, 2, and 3 - Submittal of 2014 Annual Radioactive Effluent Release Report (ARERR) ONS-2015-043, Radioactive Waste Process Control Program Manual, Revision 15
References
ONS-2015-043
Download: ML15138A113 (68)

Text

$DUKE----ENERGYS Scott L. Batson Vice President Oconee Nuclear Station Duke Energy ONO1VP I 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.3274 f 864.873. 4208 Scott. Batson@duke-energy.

corn ONS-2015-043 April 30, 2015 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 2014 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, 2014 through December 31, 2014. In accordance with TS 5.5.1, the Offsite Dose Calculation Manual (ODCM) is included in this submittal.

Attachment 1 Attachment 2 Attachment 3 Attachment 4 Attachment 5 Attachment 6 Attachment 7 Attachment 8 Attachment 9 Attachment 10 Attachment 11 Summary of Gaseous and Liquid Effluents Report Supplemental Information to the Gaseous and Liquid Effluents Report Solid Radioactive Waste Disposal Report Meteorological Data Unplanned Offsite Releases Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)Revisions to the Oconee UFSAR Section 16.11 Radiological Effluent Controls Revisions to the Radioactive Waste Process Control Program Manual (Compact Disc)Information to Support the NEI Groundwater Protection Initiative Inoperable Equipment

/ oc Radioactive Waste Systems Changes www.duke-energy.com U.S. Nuclear Regulatory Commission 2014 Annual Radioactive Effluent Release Report April 30, 2015 Page 2 Enclosure 2014 Offsite Dose Calculation Manual (Compact Disc)Any questions concerning this report should be directed to Judy Smith at 864-873-4309.

Sincerely, Scott Batson Vice President Oconee Nuclear Station Attachments (11)Enclosure (1)

U.S. Nuclear Regulatory Commission 2014 Annual Radioactive Effluent Release Report April 30, 2015 Page 3 xc (with attachments and enclosure):

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

& Infectious Waste Management SC Dept. of Health and Env. Control 2600 Bull St.Columbia, SC 29201 Mr. James Twiggs INPO 700 Galleria Place, Suite 100 Atlanta, GA 30339-5943 Mr. Gary Stewart, State Voluntary Cleanup Section S.C. Dept. of Health & Environmental Control 2600 Bull Street Columbia, SC 29201 Ms. Sandra Threatt, Nuclear Response and Emergency Environmental Surveillance S.C. Dept. of Health & Environmental Control 2600 Bull Street Columbia, SC 29201 Attachment 1 Summary of Gaseous and Liquid Effluents Report This attachment includes a sunmnary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Revision 1, Appendix B.(9 pages, including this cover sheet)

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2014 Units QTR I A. Fission and Activation Gases 1. Total Release Ci 6.11E+00 2. Avg. Release Rate uCi/sec 7.86E-01 B. Iodine-131

1. Total Release Ci 0.00E+00 2. Avg. Release Rate uCi/sec 0.OOE+00 C. Particulates Half Life >= 8 days 1. Total Release Ci 9.49E-07 2. Avg. Release Rate uCi/sec 1.22E-07_D ._T ri.tiu m .. .... ... ... ..... .... ........ .1. Total Release Ci 3.12E+01 2. Avg. Release Rate uCi/sec 4.01E+00 E. Carbon-14 1. Total Release Ci 6.06E+00 2. Avg. Release Rate uCi/sec 7.80E-01 F. Gross Alpha Radioactivity

1. Total Release Ci 0.00E+00 2. Avg. Release Rate uCi/sec 0.OOE+00 QTR 2 QTR 3 QTR 4 YEAR 2.27E+00 1.00E+01 2.36E+01 4.20E+01 2.89E~-02 1.26E+00 2.96E+00 1.33E+00 1.20E-07 0.OOE+00 4.90E-06 5.02E-06 1.53E-08 O.OOE+00 6.17E-07 1.59E-07 O.OOE+00 0.OOE+00 9.33E-12 9.49E-07 0.OOE+00O

.00E+00 1,17E-12 3.01E-08 3.04E+01 6.04E+01 7.13E+01 1.93E~+02 3.86E~+00 7.60E+00 8.97E+00 6.13E+00 5.38E+00 6.07E+00 5.23E+00 2.27E+01 6.85E-01 7.64E-01 6.58E-01 7.21E-01 0.00E~+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 GASEOUS EFFLUENTS

-ELEVATED RELEASES -CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2014 Units QTR 1 i. Fission and Activation Gases XE-133 Ci 6.10E+00 QTR 2 QTR 3 QTR 4 YMAR 2.11E+00 9.96E+00 2.34E+01 4.16E+01 2. Iodines 1-131 Ci 0.OOE--0 O .OOE-I00 0.OOE+00 4.90E-06 4.90E-06 3. Particulates Half Life >= 8 days** No Nuclide Activities

• • ...4. Tritium H-3.. Carbopn-14 C-14 Ci 3.06E+01 2.35E+01 5.72E+01 6.99E+01 1.81E+02 Ci. 1.82E+00 1.61E+00 1.82E+00 1.57E+00 6.81EO00 6. Gross Alpha Radioactivity

• • No Nuclide Activities

TABLE IB EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 GASEOUS EFFLUENTS

-ELEVATED RELEASES-BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2014 Units QTR 1 1. Fission and Activation Gases AR-41 Ci 4.70E-06 KR-85 Ci 3.41E-03 KR-85M Ci 3.09E-06 XE-131M Ci 1.00E-04 XE-133 Ci 1.17E-02 XE-133M Ci 2.40E-04 XE-135 Ci 7.53E-04 QTR 2 QTR 3 QTR 4 1. 62E-02 2. 14E-02 3. 10E-03 0. 00E+00 3. 66E-05 1. 30E-01 6. 29E-06 2. 43E-03 1. 57E-01 1..20E7.07.

0. OOE+00 1.20E-07 2. 67E-02 1.10E-02 0. OOE+00 9. 01E-05 2. 92E-02 3.45E-04 3. 90E-04 6.78E-02 0. OOE+00 0. OOE+00 0. OOE+00 1 .51E-02 5.22E-03 3. 45E-05 6. 81E-04 1.03E-01 1. 72E-03 6. 1OE-03 1. 32E-01 0. OOE+/-Q0 0. OOE+00 0. OOE+00 Totals for Period...

Ci 2. Iodines I 31 .............

Ci ....... ..... 0.OOE+00.1-133 Ci 2.43E-10 Totals for Period...

Ci 2.43E-10 YEAR 6.33E-02 2.27E-02 3. 76E-05 9. OBE-04 2. 74E-01 2.31E-03 9.68E-03 3. 73E-01 i.20E-07 2. 43E-10 1. 20E-07 9. 33E-12 2. 13E-01 1. 59E+01 3. Particulates Half Life CO-58 Ci>= 8 days 0. OOE+00 0.OOE+00 0.OOE+00 9.33E-12 4. Tritium H-3 5. Carbon-14 C-14 Ci 3. 60E-05 8. 49E-02 5. 87E-02 6. 99E-02 Ci 4.24E+00 3. 77E+00 4. 25E+00 3 .66E+00 6. Gross Alpha Radioactivity

• • No Nuclide Activities

• • 7. Others C-11 Ci 1.48E-08 0.OOE+00 0.OOE+00 0.OOE+00 1.48E-08 TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 GASEOUS EFFLUENTS

-GROUND RELEASES -CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2014 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1. Fission and Activation Gases** No Nuclide Activities

• • ........ ........ ........ ........ ........2. lodines** No Nuclide Activities

• • 3. Particulates Half Life >= 8 days CS-137 Ci 9.49E-07 0.OOE+00 0.OOE+00 0.OOE+00 9.49E-07 4. Tritium H-3 Ci 5.24E-01 6.79E+00 3.18E+00 1.26E+00 1.18E+01 5. Carbon-14** No Nuclide Activities

• • ........ ........ ........ ........ ........6. Gross Alpha Radioactivity

• • No Nuclide Activities

• • ........ ........ ........ ........ ........

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 GASEOUS EFFLUENTS

-GROUND RELEASES -BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2014 Units QTR 1 1. Fission and Activation Gases** No Nuclide Activities

........2. Iodines** No Nuclide Activities

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

• • ........QTR 2 QTR 3 QTR 4 YEAR 4. Tritium H-3 H- 3Ci. 0.OOE+00 4.54E-05 0.OOE+00 1.12E-01 1.12E-01 S. Carbon-14** No Nuclide Activities

• • 6. Gross Alpha Radioactivity

• • No Nuclide Activities

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 LIQUID EFFLUENTS

-SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2014 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products 1. Total Release Ci 3.74E-03 2. Average Diluted Concentration

a. Continuous Releases pCi/ml 0.OOE+00 b. Batch Releases pCi/ml 4.47E-10 B. Tritium 1. Total Release Ci 2.07E+02 2. Average Diluted Concentration

a. Continuous Releases pCi/ml 2.77E-08 b. Batch Releases pCi/ml 2.47E-05 C. Dissolved and Entrained Gases 1. Total Release Ci 0.OOE+00 2. Average Diluted Concentration

a. Continuous Releases pCi/ml 0.OOE+00 b. Batch Releases pCi/ml 0.OOE+00 D. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00 2. Average Diluted Concentration

a. Continuous Releases pCi/ml 0.OOE+00 b. Batch Releases uCi/ml 0.OOE+00 2.05E-03 1.56E-03 1.77E-03 9.12E-03 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 2.43E-10 1.82E-10 2.07E-10 2.69E-10 1.95E+02 9.74E+01 3.76E+02 8.75E+02 2.08E-08 3.68E-08 3.84E-08 3.09E-08 2. 31E-05 1.13E-05 4. 3 9E-Q-5.. -2.-.58.E-05.

0.OOE+00 0.OOE+00 2.24E-05 2.24E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 2.62E-12 6.61E-13 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.70E+08 5.47E+08 7.31E+08 2.69E+09 2.44E+06 7.95E+05 3.55E+06 8.15E+06 8.44E+09 8.55E+09 8.55E+09 3.39E+10 8.44E+09 8.55E+09 8.55E+09 3.39E+10 E. Volume of Liquid Waste 1. Continuous Releases 2. Batch Releases liters 7.41E+08 liters 1.36E+06 F. Volume of Dilution Water 1. Continuous Releases liters 8.37E+09 2. Batch Releases liters 8.37E+09 TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 LIQUID EFFLUENTS

-CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2014 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR 1. Fission and Activation Products** No Nuclide Activities

• • 2. Tritium H-3 Ci 2. 52E-01 1. 89E-01 3.35E-01 3.56E-01 1. 13E+00 3. Dissolved and Entrained Gases** No Nuclide Activities

• • 4. Gross Alpha Radioactivity

• • No Nuclide Activities

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 LIQUID EFFLUENTS

-BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2014 Units QTR 1 1. Fission and Activation Products QTR 2 QTR 3 QTR 4 YEAR AG-108M AG-I1OM CO-58 CO-60 CR-51 CS-134 CS-137 FE-55 FE-59 1-131 MN-54 NB-95.NB-97 NI-63 RU-103 S3-124 SB-125 SN-113 ZR-95 ZR-97 Ci 0.OOE+00 Ci 8.86E-05 Ci 1.94E-03 Ci 2.08E-04 Ci 0.004E-00 Ci 0.00E+00 Ci 4.05E-05 Ci 3.42E-04 Ci 1.48E-05 Ci 0.00E+00 Ci 4.36E-05 Ci .........

35E05 Ci 0.00E+00 Ci 2.47E-04 Ci 3.52E-06 Ci 5.06E-04 Ci 2.77E-04 Ci 0.00E+00 Ci 1.43E-05 Ci 0.00E+00 Ci 3.74E-03 3. 09E-06 0. 00E+00 1.23E-03 7. 34E-05 1. 92E-04 0. 00E+00 5. 84E-06 0.00E+00 0. 00E+00 0. 00E+00 0. 00E+00 S,21E05-0. 00E+00 2.54E-04 0. 00E+00 1. 77E-04 9.33E-05 2.88E-06 8.10E-06 0. 00E+00 2. 05E-03 0. OOE+00 0. 00E+00 8. 33E-04 3. 38E-05 0. 00E+00 7.27E-06 1. 23E-04 0. 00E+00 0. 00+E00 0. 00E+00 0. 00E+00 0.'00E+00-

0. 00E+00 5. 40E-04 0. 00E+00 0. OOE+00 2. 29E-05 0. OOE+00 0. 00E+00 0. OOE+00 1. 56E-03 0. OOE+00 9. 04E-06 6. 34E-04 9.09E-05 0. 00E+00 0. OOE+00 1. 33E-04 0. 00E+00 0. 00E+00 5.09E-06 0. OOE+00'0.00+E00 8. 91E-06 8. 28E-04 0. 00E+00 1. 62E-05 3.55E-05 0. OOE+00 0. 00E+00 8. 91E-06 1 .77E-03 3. 09E-06 9. 76E-05 4. 63E-03 4. 06E-04 1. 92E-04 7. 27E-06 3.02E-04 3. 42E-04 1. 48E-05 5. 09E-06 4. 36E-05 2:56E-05 8. 91E-06 1. 87E-03 3. 52E-06 7. 00E-04 4.29E-04 2.88E-06 2.24E-05 8.91E-06 9.12E-03 Totals for Period...2. Tritium H-3 Ci 2.07E+02 1.95E+02 9.71E+01 3.76E+02 8.74E+02 3. Dissolved and Entrained Gases XE-135 Ci 0.00E+00 0.00E+00 0.00E+00 2.24E-05 2.24E-05 4. Gross Alpha Radioactivity

• • No Nuclide Activities

Attachment 2 Supplemental Information to the Gaseous and Liquid Effluents Report (5 pages, including this cover sheet)

Oconee 2014 ARERR -Carbon-14 Supplemental Information Carbon-14 (C-14). with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere.

Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.

C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing.In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC recommends U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide".

and if so, report the amount of C- 14 released.

At Oconee. improvements over the years in effluent management practices and fuel performance have resulted in a decrease in gaseous radionuclide (non-C- 14) concentrations, and a change in the distribution of gaseous radionuclides released to the environment.

As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at Oconee, as defined in Regulatory Guide 1.21, Rev. 2.Oconee's 2014 Annual Radioactive Effluent Release Report (ARERR) contains estimates of C-14 radioactivity released in 2014. and estimates of public dose resulting from the C-14 effluent.Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste at Oconee is not required (Retf 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 -doctuments pir-oide infffinmtidhi related to the rnagnitudeF-ofCI4-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-vr for a Westinghouse PWR and 10.4 to 11.3 for a CE PWR (Ref. EPRI 1021106).

The EPRI report did not provide a source term scaling factor for a B&W PWR, but for the 2014 Oconee ARERR a source term scaling factor of 9.4 Ci/GWe-yr is assumed in order to be consistent with the scaling factor used for the Catawba and McGuire ARERRs. Using a source term scaling factor of 9.4 Ci/GWe-yr and actual electric generation (MWe-hrs) from Oconee in 2014 results in a site total C-14 gaseous release estimate to the environment of-22 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, (Ref. EPRI TR-105715).

For the Oconee 2014 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 in 2014 is well below the IOCFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit).

OCONEE NUCLEAR STATION 2014 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS -STATION A. NOBLE GASES -AIR DOSE 1. CALENDAR QUARTER -GAM DOSE = 15 MRAD 2. CALENDAR QUARTER -BETA DOSE = 30 MRAD 3. CALENDAR YEAR -GAMMA DOSE = 30 MRAD 4. CALENDAR YEAR -BETA DOSE = 60 MRAD B. LIQUID EFFLUENTS

-DOSE 1. CALENDAR QUARTER -TOTAL BODY DOSE = 4.5 MREM 2. CALENDAR QUARTER -ORGAN DOSE = 15 MREM 3. CALENDAR YEAR -TOTAL BODY DOSE = 9 MREM 4. CALENDAR YEAR -ORGAN DOSE = 30 MREM C. IODINE -131 AND 133, TRITIUM, PARTICULATES W/T 1/2 > 8 DAYS -ORGAN DOSE 1. CALENDAR QUARTER = 22.5 MREM 2. CALENDAR YEAR = 45 MREM II. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS A. GASEOUS EFFLUENTS

-INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL B. LIQUID EFFLUENTS

-INFORMATION FOUND IN 1OCFR20, APPENDIX B, TABLE 2, COLUMN 2 III. AVERAGE ENERGY -NOT APPLICABLE IV. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY ANALYSES OF SPECIFIC RADIONUCLIDES IN SELECTED OR COMPOSITED SAMPLES AS DESCRIBED IN THE SELECTED LICENSEE COMMITMENTS ARE USED TO DETERMINE THE RADIONUCLIDE COMPOSITION OF THE EFFLUENT.

A

SUMMARY

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

V. BATCH RELEASES A. LIQUID EFFLUENT 1. 9.40E+01 = TOTAL NUMBER OF BATCH RELEASES 2. 1.91E+04 = TOTAL TIME (HIN.) FOR BATCH RELEASES.3. 2.35E+02 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.4. 2.03E+02 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.5. 1. 14E+02 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.6. 1.70E+04 = AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).B. GASEOUS EFFLUENT 1. 7.10E+01 = TOTAL NUMBER OF BATCH RELEASES.2. 1.17E+05 = TOTAL TIME (MIN.) FOR BATCH RELEASES.3. 2.48E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.4. 1.65E+03 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.5. 9.00E+01 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.VI. ABNORMAL RELEASES (SEE "UNPLANNED OFFSITE RELEASES" ATTACHMENT)

OCONEE NUCLEAR STATION Overall Estimate of Error for Effluent Radioactivity Release Reported The estimated percentage of overall error for both Liquid and Gaseous effluent release data at 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: (I) Flow Rate Determining Devices (2) Counting Statistical Error (3) Calibration Error (4) Calibration Source Error (5) Sample Preparation Error S+/- 20%--20%=+/- 10%S+/- 2.5%= +/-3%

0 Oconee 2014 ARERR -Attachment 2 Supplemental Information Summary of Chanees in Land Use Census Affectin2 Effluent Dose Calculations The 2014 Land Use Census was performed May 12-13, 2014, and the results were certified and made available for use on September 2, 2014. ['he following are changes to residences.

gardens, and milk animals from the previous year.Residences No changes to nearest residence in each sector.Gardens Per Oconee SLC 16.11.6. broad leaf vegetation sampling shall be perfbrmed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census. For consideration of dose from effluents, a garden is assumed at the site boundary in every sector. '[herefore, no changes are anticipated to occur.Milk Animals No changes to nearest milk animal in each sector.

Attachment 3 Solid Radioactive Waste Disposal Report (13 pages, including this cover sheet)

OCONEE NUCLEAR STATION ANNUAL RADWASTE REPORT 3/1712015 DUKE ENERGY: Oconee Nuclear Station SOLID RADIOACTIVE WASTE SHIPPED TO A DISPOSAL FACILITY Report Period: January -Decemriber 2014 TOTAL Waste Type NUMBER OF NUMBER OF WASTE CLASS CONTAINER BURIAL VOLUME ACTIVITY SHIPMENTS CONTAINERS.

A-U A-S B C TYPE CU. FT. CU. M. CURIES 1) WASTE FROM LIQUID SYSTEM (A) Dewatered Powdex Resin 3 9 9 0 0 0 GDP 1866.6 52.86 2.28 (B) Dewatered Primary Resin 4 4 0 1 3 0 TYPE A 481.2 13.63 247.74 (C) Dewatered Mechanical Filters 1. Primary Filter Media 1 1 0 0 0 1 TYPE A 120.3 3.41 22.40 2. Secondary Filter Media 0 0 0 0 0 0 GDP 0 0.00 0.0000 (D) Solidified oil, liquid, sludge 0 0 0 0 0 0 GDP 0 0.00 0.00 2) DRY SOLID WASTE (A) Dry Active Waste -Processor to Burial 33 33 33 0 0 0 GDP 4759.8 134.79 0.26 Metal -Processor to Burial 16 16 16 0 0 0 GDP 837.96 23.73 2.70 (B) Dry Active Waste to Burial 3 3 0 3 0 0 TYPE A 360.9 10.22 2.01 (C) Dry Active Waste Brokered 0 0 0 0 0 0 0 0.00 0.00 (D) Irradiated Components 0 0 0 0 0 0 TYPE B 0 0.00 0.00 TOTAL 60 66 58 4 3 1 8426.81 238.63 277.39 Page 1 of I Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Period: January -December 2014 Waste Type: Dewatered Powdex Resin ISOTOPE: % ABUNDANCE OF LINERS SHIPPED TO ENVIROCARE 9 # OF SHIPMENTS TO ENVIROCARE 3 TOTAL AVE.CR-51 0.D000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 000 0.00 0.00 0 000 0.00 0.00 0.00 O 0 0.00 0.00 0ODO 0.00 0.00 0.00 MN-54 0.0498 0.0399 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.DO 0.00 0.DO 0.00 0.00 0.00 0.00 0.09 0.03 CO-57 0.0215 0.0181 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0 00 0.00 0.00 0.00 0.00 0.0O 0.00 0.00 0 00 0.00 0.06 0.02 CO-58 0.0014 0.0044 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.D0 000 0.00 0.O0 0.00 000 0.00 0.00 0.00 0.00 0.00 000 0.00 0.01 0.00 CO-60 2.1236 0.8910 1.35 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 4.36 1.45 NB-95 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ZR-95 0.0000 0.0000 0.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 0.00 CS-134 0.2561 0.2508 0.24 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 000 0.75 0.25 RU-103 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.DO 0.00 AG-110m 0.0550 0.0755 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.DO 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 0.06 SB-125 5.9459 0.3104 0.06 0.DO 0.00 0.00 0.00 0.00 0.00 000 0.00 000 DO0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 6.32 2.11 1-131 0.0000 0.00O0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.00 0.00 0.00 0.00 0.00 CS-137 1.5573 0.9000 0.78 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 000 000 000 0.00 0.00 0.00 0.00 0.00 0.0 0.00 0.00 3.24 1.05 H-3 77.3488 92.3881 76.34 0.00 0.00 0.00 0.00 0.DO 0.00 0.00 G.O0 0.00 0.00 0 .00 0 0.DO 0.00 0.00 0.00 0.00 0.00 0.00 246.08 82.03 NI-63 3.7709 1.3881 10.44 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 DO 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 15.60 5.20 FE-55 3.8739 1.8209 5.85 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 11.55 3.85 SR-90 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TE-125m 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0O 6-00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CS-136 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.0D 0.00 0.00 Q.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 XE-133 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.DO 0.00 0.00 0.00 00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.DO 0.00 0.00 C-14 4.8005 1.7612 4.60 0.00 0.00 0.00 0.00 0.00 0.00 0.00 6.00 0.00 0.00 0.00 0.00 0.00 0 0.00 000 0.00 000 0.00 0.00 11.16 3.72 PU-241 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ZN-65 0.0000 0.0000 0.01 0.00 0.00 0.00 0.00 0.00 0.00 00 00DO 0o00 000 00 o 000 0.00 0.0 0.00 0D00 0.00 0.00 0.00 0.01 0.00 FE-59 .000DO 0.0000 0.00 0.00 0.00 0.00 0.00 0.Do 0.00 0.00 0,00 0.00 0.00 000 0.00 0.00 0.00 000 0 DO 0.00 0 00 0.00 0.00 0.00 SB-124 0.0000 0.0000 0.00 000 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.O0 0.00 0.00 0.00 RU-106 0.1853 0.1776 0.10 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 000 0.00 000 0.00 0.DO 0.46 0.15 CE-144 0.0166 0.0173 0.01 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.DO 0.00 0.00 0.00 000 000 0.00 0.05 0.02 TE- 132 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 AM-241 0.DOO 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 TOTAL 100 100 100 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 299.92 99.97 CLASSC 0 0 0 0 0 0 0 0 0 0 b 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 3 3 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 9 CURIES 0.777 0.67 0.837 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.284 CU. FT. 622.2 622.2 622.2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1866.6 CU. M 17.61907 17.61907 17.61907 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 52.85722 RSR4 14-2001 14-2002 14-2017 Page 1 of I Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE!

REPORT Report Period: January -December 2014 Waste Type: Primary Resin# OF LINERS SHIPPED TO CNSI 4 ISO-OPE: % ABUNDANCE/LINER ID OF SHIPMENTS TO CNSI 4 TOTAL AVE AG-11om 0.0000 0.0000 0.0827 0.0824 0.0000 0.0000 0.0000 00000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 00000 0.0000 0.0000 0.0000 0.0000 0 1651 0.0413 AM-241 0.0000 0.0002 0 0004 0.0002 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0 0000 0.0000 0.0000 0.0000 0.0000 0.0008 0.0002 Be-7 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 C-14 0.3419 0.4618 0.5439 0.7677 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 00000 0.0000 0.0000 0.0000 0.0000 00000 00000 0.0000 2 1153 0 5288 CE-144 0.0566 0.0426 0.0219 0.0243 0.0000 0.0000 0.0000 0.0000 0.0000 00000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.1454 0.0364 CM-242 0.0000 0.0001 0.0001 0.0001 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 00000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0003 0.0001 CM-243144 0.0000 0.0002 0.0003 0.0002 0.0000 0.0000 0.0000 0 0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0007 0.0002 CO-57 0.3689 0.5171 0.4026 0.3203 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 1.6089 0.4022 CO-58 57.0258 22.6016 .14.3860 7.7237 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 101.7371 25.4343 CO-6D 2.0960 3.6748 3.6491 2.7786 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 12.1985 3.0496 CR-5I 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 D.0000 0.0000 0.0000 0.0000 0.0000 CS-134 1.6862 2.0813 2.0877 1.7115 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 7.5667 1.8917 CS-136 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000O 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 CS-137 5.6440 6.7805 7.4123 6.5149 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 26.3517 6.5879 FE-55 4.5316 15.7886 14.1228 18.6813 0.0000 0.0000 0.0000 00000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0D00 0.0000 0.0000 0.0000 0.0000 53.1243 13.2811 FE-59 0.0167 0.0081 0.0000 0.0000 0.0000 0 0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0248 0.0062 H-3 0.1230 0.0364 0.0000 0.0120 0.0000 0.0000 00000 00000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.1714 0.0429 1-129 0.0015 0.0000 0.0000 0.0007 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0022 0.0005 1-131 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 MN-54 0.4122 1.4911 0.8860 0.8421 0.0000 00000 0.0000 0.0000 0.0006 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 3.4314 0.8579 NB-94 0.0000 0.0000 0.0051 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 00000 00000 0.0000 0.000 00051 0.0013 NB-95 0.0870 0.0831 0.0461 0.0090 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 0.2252 0.0563 NI-59 0.1546 0.2683 0.3693 0.4396 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000 0.0000 0,0000 0.0000 0.0000 1.2318 0.3080 NI-63 26.5808 45.8537 55.3509 60.1256 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 187.9110 46.9778 PU-238 0.0000 0.0003 0.0000 0.0005 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0 0000 0,0000 0.0000 0.0000 0.0008 0.0002 PU-239/40 0.0000 0.0001 0.0002 0.0001 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 0.0004 0.0001 PU-241 0.0000 0.0061 0.0089. 0.0090 0.0000 0.0000 0.0000 00000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0 0000 0.0240 0.0060 RU-106 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 0.0000 0.0000 SB-124 0.4180 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 O0,000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 0.4180 0.1045 SB-125 0.2717 0.1184 0.0525 0.0526 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.4952 0.1238 SN-113 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 0.0000 0.0000 SR-89 0.0000 0.0132 0.0029 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 00000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0161 0.0040 SR-90 0.0267 0.0379 0.0516 0.0499 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000 0.0000 0.0000 0.1661 0.0415 TC-99 0.0158 0.0041 0.0000 0.0026 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 00000 00000 0.0000 00000 0.0000 0.0000 0.0225 0.0050 TE-125m 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.00010 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0,00 0.0000 0.0000 0.0000 0.0000 0.0000 XE-133 0.0000 0.000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 0,0000 0.0000 0.0000 0.0000 0.0000 ZN-65 0.0482 0.1015 0.0787 0.0468 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 00000 0.0000 0,0000 0.0000 0.0000 0.2752 0.0688 ZR-95 0.0508 0.0816 0.0289 0.0078 0.0000 0.0000 0.0000 0.0000 0.0006 0.0000 0.0000 0.0000 0.0000 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.1691 0,0423 TOTAL 99.96 100.05 99.43 99.95 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 399.16 9979 CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 CLASS AS 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 1 of 2 Oconee' Nuclear Station Annual Report CURIES 8.54 61 5 114 63.7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 247.74 CU. FT. 120.3 120.3 120.3 120.3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 481.2 CU. M 3.41 3.41 3.41 3.41 0.00 0.00 0.00 0.00 0.00: 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 13 63 RSR# 14-2007 14-2025 14-2034 14-2040 Page 2 of 2 OCONEE NUCLEAR STATION SOLID RADWA!Uf6WWI?!uclear Station Annual Report Report Period: January -December 2014 Waste Type: Primary filters I OF DRUMS/LINERS TO CNSI 1 ISOTOPE# OF SHIPMENTS TO CNSI I TOTAL AVE.AG-110m AM-241 BA-140 C-14 CD-109 CE-141 CE-144 CM-242 CM-243/44 CO-57 CO-58 CO-60 CR-51 CS-134 CS-136 CS-137 FE-55 FE-59 H-3 HG-203 1-129 MN-54 NB-94 NB-95 NI-59 NI-63 PU-238 PU-239 PU-241 RU-103 RU-106 SB-124 SB-125 SN-i 13 SR-89 SR-90 TC-99 TE-125m XE-133 ZN-65 ZR-95 0.38440 0.00 0.00000 0 00 0.00000 0.00 0.35670 0.00 0.00000 0.00 0.00000 0.00 0.08790 0.00 0.00000 0.00 0.00000 0.00 0.28840 0.00 4.68750 0.00 11.29460 0.00 0.00000 0.00 0.39688 0.00 0.00000 0.00 0.95090 D.OD 43.61610 0.00 0.02020 0.00 0.14640 0.00 0.00000 0.00 0.00000 0.00 2.10270 0.00 0.00000 0.00 0.02600 0.00 0.00000 0.00 34.59820 0.00 0.00000 0.00 0.00000 0.00 0.00000 0.00 0.00000 0.00 0.00000 0.00 0.00000 0.00 0.00000 0.00 0.01430 0.00 0.00000 0.00 0.00000 0.00 0.00000 0 00 0.00000 0.00 0.00000 0.00 0.72770 0.00 0.26160 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 o.do 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 000 0,00 0.00 0.00 0,00 0.00 0.00 0,00 0.00 0.00 0,00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 D.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00: 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00ý 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0 00 0.00 0.00 0.0D 0,00 0,00 0,00. 0.00 0.00 0.00. 000 0.00 0.00b 0.00 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 000 0.00 000 0.00 0.00 0.00 0.00 0.00 D.00 0.00: 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 0.00. 0.00 0.00 0.00; 0.00 0.00 000. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 0.00: 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00. 0.00 0.00 0.001 0.00 0.00 0.00. 0.00 0.00 0.00. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.38 0.384 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.000 0.00 0.00 0.D0 0.00 0.00 0.00 0.00 0.00 000 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.36 0 357 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 0.088 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.29 0.288 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4.69 4.688 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 11.2946 11.29460 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.40 0.397 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.95 0.951 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 43.62 43.616 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.020 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.15 0.146 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2.10 2.103 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 0.026 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 34.60 34.598 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 O0 0.00 0.000 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.014 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00000 0.0000000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0000 0.000 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.0000 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.7277 0.72770 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.2616 0.26160 TOTAL 99.96 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00: 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 9S.97 98.97 Page 1 of 2 Oconee Nuclear Station Annual Report CLASSC 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 CLASS B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0: 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0i 0 0 0 0 0 0 0 0 0 0 0 0 CURIES 22.4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 22.4 CU. FT. 120.3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 120.3 CU. M 3.406581 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.406581 RSR# 14-2044 Page 2 of 2 Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOUD RADWASTE REPORT Report Period: January -December 2014 Waste Type: Secondary Filters t OF CONTAINERS SHIPPED TO DURATEK# OF SHIPMENTS TO DURATEK 0 4 OF CONTAINERS SHIPPED TO CNSI I EfAVROCARE 0 1tOF SHIPMENTS TO CNSI I ENVIROCARE 0 ISOTOPE TOTAL AVE AG-108m AG-i 1Dm AM-241 C-14 CE-144 CM-242 CM-243 CO-57 CO-58 CO-60 CR-51 CS-134 CS-136 CS-137 FE-55 FE-59 H-3 1-131 MN-54 NB-95 NI-63 PU-2.38 PU-239 PU-241 RU-103 RU-106 SB-124 SB-125 SR-89 SR-90 TE-125m TRU XE-133 ZN-65 000 0.00 000 000 0.00 0.00 000 0.00 0.00 000 0.00 0.00 0.00 0.00 000 000 000 000 000 0.00D 000 0.00 000)000 000 000)000 0.00 000 0.00 0 00 0.00 0 DO 0.DO 000 0.00 006 0.00 0.00 000 000 000 000 0.00 0.00 0.00 0.00 000 000 000 000 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 000 000 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 ODO 0.00 0.06 0.00 0.DO 0.00 000 0.00 0.00 000)000 0.00 0.00 0.00 000O 0.00 0.00 0.00 0.00 0.00 0.00 000O 0 00 000 000 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 c~oo 0.00 000 0.00 0.00 000 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0. 000 0.00 0.00 6.C0 0.00 0.00 0.00 0.00 000 0.00 000 0 DO 0.00 0.00 000 0.00 000 0.06 0.00 000 0.00 000 0.00 O.DO 0000 000 0.00 0.00 0.00 0.00 0.00 0DD 0.00 000 000 0.DO 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0 DO 0.00 0.00 0 D0 0.00 0.00 0.00 0.00 0oo 0.00 0.00 0.00 0.00 0.00 6.00 0 00 0.00 0.00 0.00 0.00 0.00 O.DO 0.00 0.00 0.00 0.00 0.00 000 0 00 0.00 0 DO 0.00 6.00 0.00 0 00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0. DO 0.00 0.00 0.00 q.oo 0.00 0.00 0.00 0 O0 0.00 q.o0 0.00 0.00 0.00 000 0.00 0.00 0.00 000 000 000 000 .00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.DO 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 000 0.00 0.O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.DO 0.00 0.00 0.00 0.00 0.00 0.00 MO. 0.00 0.00 0.00 0.00 0.00 d.00 0.00 0.00 0.00 0.00 000 0.DO 000 0.00 0.00 0.00 0.00 0.00 0.DO 000 0.00 000 0.00 0.00 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.06 0.06 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.0O 0.00 000 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 000 000 0.00 0.00 000 0.00 000 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 000 O.0O 0 D0 0.00 D 00 0.00 000 000 000 000D 000 000 0.00 0.00 0.00 0.00 000 0.DO 0.00 0.00 ODO 0.00 000 0.00 0.00 0.00 000 O.00 0.00 0.00 0.00 0.00 000 0.0o 0.00 000 0.00 0.00 0.00 0.00 000 000 0DO 000 0.00 0 00 000 0DO 0.00 000 0.00 0DO 0.00 0.00 0.00 0.00 0.00 0OO 000 000 0.00 000 000 000 0 00 0.00 000 0.00 000 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.DO 0..00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.DO 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.DO 0.00 0.00 0.00 0.00 000 000 0.00 0.00 000 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 0.00 0.DO 0.00 0.00 0.00 000 0DO 000 0.DO 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 000 000 0 00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 O 00 006 0.00 0.00 0.00 0 00 0 00 0.00 0.00 0.00 0.DO 0.00 0.DO 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 000 0.00 0.00 0.00 000 0.00 0.00 000 000 000 000 000 000 0.DO 0.00 O.DO 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 000 0.00 000 0.00 0.00 #DIVI/O 0.00 ODIVIMI 000 #DIV/OI 0.00 #DIVIOI 0.00 #DOIVO!0.00 #DIV/0I 0.00 #DIV/O!0.00 #DrV/IO 00O0 #DIV/0D 0.DO #DIV/OI 0.00 #DOVID!0.00 #OIM/OI 000 UDIVIO!0.00 VDIVI/O 0 O #DIVID: 0 00 #DIV/!0.00 #D0VIO!0.00 #DIV/O!0.00 #DlVI0b 0.00 #OlVIO, 0.00 #0IVI0O-0.00 #DIVIO!0 O0 #DIV/OI 0.00 #OIV/OI 0.00 #ODIVIOI 0 Do #DIVt0I 000 #DIVI0!0.00 #DIVIOI 0.00 #DIVt0!000 #DIV/0!0.00 #DIVIO!0.00 #DIV/0I TOTAL 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 d.0o 0.00 0.00 000 0.00 0.00 000 000 0.00 0.00 000 0.00 #DIVSI0 CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 0 0 0 0 0 0 0 '0 0 0 0 0 0 0 0 0 0 5 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES 0.DOE-.00 0.OOE,00 0 0 0 0 0 0 0 0 FT3 Shipped 0 0 0 0 0 0 0 0 0 0 CU M Shipped 0.0000 0 0000 0.0000 0.0000 0 0 0 0 !0 0 FT3 Buried 0 0 0 0 0 0 0 0 i0 0 CU M Buried 00000 0.0000 O.DOO 0.0000 0000D0 .OO00 00000 00000 0 0000 00000 RSR#0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0O 0 0 0000 0 0 0.0000 0.0000 0.0000 0.0000 0.0000 0 0O00 ) 0000 0 0000 0 0000 Page 1 of 1 Oconee: Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Period: January -December 2014 Waste Type: Solidified Oil. Liquid, Sludge a OF CONTAINFRq SHIPPFF ISOTOPE.% ABUNDANCE/LINER

1. OF SHIPMENTS 0 TOTAL AVE.CR-51 MN-54 CO-57 CO-58 CO-60 NB-95 ZR-95 CS-134 RU-103 AG- 110m SB-125 1-131 CS-137 H-3 NI-63 FE-55 SR-90 TE-125m CS-136 XE-133 C-14 PU-241 TRU FE-59 SB-124 RU-106 CE-144 CM-242 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 O0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 boo 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 000 000 Q.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00, 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 OD. 0.00 0.00 0.00 0.00 0.00 0.00 #D[V/0/0.00 0,00 0.00 #DIV/0I 0.00 000 0.00 #DIV/0!0.00 0.00 0.00 #DIV/0!0.00 0.00 0.00 #DIV/0!0.00 0.00 0.00 #OIV/0!0.00 0.00 0.00 #DIV/0I 0.00 0.00 0.00 #DIV/01 0.00 0.00 0.00 #DIV/0I!000 000 0.00 #DIVIOI 0.00 0.00 0.00 #DIV/O!000 0.00 0.00 #DIV/O!0.00 0.00 0.00 #DIV/0!0.00 0.00 0.00 #DIV/0!0.00 0.00 0.00 #DIV/0!0.00 0.00 0.00 #DIV/0'0.00 0.00 0.00 #DIV/0!0.00 0.00 0.00 #DIVI0!0.00 0.00 0.00 #DIVIO!000 0.00 0.00 #DIV/0!0.00 0.00 0.00 #DIV/0!0.00 0.00 0.00 #DIV/0l 0.00 0.00 0.00 #DIV/0!0.00 0.00 0.00 #DIV/OI 0.00 0.00 0.00 #DIV/0l 0.00 0.00 0.00 #DIV/OI 0.00 0.00 0.00 #DIV/01 0.00 0.00 0.00 #DIV/01 0.00 0.00 0.00 #DIV./I TOTAL 0.00 0.00 0.00 .0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DrV/0!CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS 8 0 0 0 0 0 0 0 0 0 0 .0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 "0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 ,0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES CU. FT.CU. M RSR#0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 so 0 0 0*0 0 0 0.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 1 of I Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Period: January -December 2014 Waste Type: DAW to Processor N OF SHIPMENTS FROM ONS TO ENERGY SOLUTIONS 31 # OF CONTAINERS FROM ONS TO ENERGY SOLUTIONS 56 N OF SHIPMENTS FROM PROCESSOR TO CLIVE 33 # OF CONTAINERS FROM PROCESSOR TO CLIVE 33# OF SHIPMENTS FROM PROCESSOR TO BARNWELL 0 # OF CONTAINERS FROM PROCESSOR TO BARNWELL 0 CU FT CURIES CU. FT. DISPOSAL CI TO DISPOSAL RSR A SHIPPED SHIPPED FACILITY FACILITY 13-2032 0 0 134.6857 0.008815 13-2050 0 0 334 :0003919 13-2049 0 0 116 0.028198 13-2048 0 0 366.8571 0.010006 14-2004 9344 0.00493 2.91429 4.05E-05 14-2005 1868.8 0.0206 198.5714 2.06E-02 14-2008 1868.8 0.00793 171.1429 7.94E-03 14-2010 1868.8 0.0499 262.8857 .4.51E-02 14-2011 18688 0.00629 291.7143 6.29E-03 14-2013 1868.8 0.0411 47.9 1 05E-02 14-2014 934.4 0.0024 115.9286 2.96E-03 14-2015 1868.8 0.00225 78.6 4.39E-04 14-2016 934.4 0.913 5.33E+01 6.83E-04 14-2019 934.4 0.00105 222.8571 7.93E-04 14-2021 1868.8 .0.0133 175.9286 1.33E-02 14-2022 1868.8 0.0287 177.4286 2.86E-02 14-2028 1868.8 0.0162 111.1714 1.68E-02 14-2029 18688 0.0916 0 0.00E+00 14-2035 1868 8 0.0146 77.85714 2.511-03 14-2036 1542.4 000805 220.6429 8 .04E-03 14-2037 1868.8 0.00576 206.2857 5.76E-03 14-2038 1868.8 0.00602 29.2 8.24E-04 14-2039 18688 0.00382 89.08571 1.04E-03 14-2041 1868.8 0.0126 229.8571 1.26E-02 14-2045 1401 6 0.0118 247.4286 1.18E-02 14-2046 18688 0.00207 58.48572 6.13E-04 14-2047 934.4 0.00314 359.7143 4.56E-03 14-2048 1868.8 0.00499 238.2429 4 65E-03 14-2049 934.4 0.00141 379.2571 2.58E-03 14-2050 22144 0.00301 336.2857 1 71E-03 14-2051 934.4 0.0048 0 0.00E+00 14-2056 1868.8 0.0104 159.4286 1.04E-02 14-2057 15744 0.0124 0 0.00E+00 14-2058 1868.8 0.0107 125.4286 9.15E-03 14-2059 1868.8 0.0347 92.26571 2.97E-02 TOTAL 50649.6 1.350 4759.84 0.25994 TOTAL CURIES BURIED 0.260 TOTAL CUBIC FEET BURIED 4759.84 TOTAL CUBIC METERS 134.79 Page 1 of 2 Oconee Nuclear Station Annual Report RSR NUMBER 14-2032 14-2042 14-2043 TOTAL TOTAL CUBIC ME OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Period: January -December 2014 Waste Type: DAW to Burial# OF SHIPMENTS FROM ONS TO CNSI 3 P OF CONTAINERS FROM ONS TO CNSI 3 CUBIC FEET CURIES A-U A-S B 120.3 1.51 0 1 0 120.3 0.12 0 1 0 120.3 0.276 1 360.9 2.006 0 3 0 TERS 10.22 C 0 0 0 Page 2 of 2 Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Period: January -December 2014 Waste Type: Metal# OF SHIPMENTS TO PROCESSOR# OF CONTAINERS TO PROCESSOR 7 9# OF SHIPMENTS TO CLIVE# OF CONTAINERS TO CLIVE: CURIES TO DISPOSAL FACILITY 16 16 CU. FT.. CURIES CU. FT TO TO PROCESSOR TO PROCESSOR DISPOSAL FACILITY RSR #13-2028 0 0 1128.511 0.0930655 13-2029 0 0 1040 5.229022 13-2034 0 0 110.835 0.0012235 13-2041 0 0 132.6571 0.0172859 13-2050 0 0 62.30015 8.38E-04 14-2014 480 0.00371 2211292 3.15E-03 14-2015 0 0 97.84358 6.62E-01 14-2016 864 0.796 139.4286 7.96E-04 14-2018 1152 4.52E-04 75.42857 2.03E-00 14-2019 576 2.30E-04 125.0341 4.88E-04 14-2039 15.67143 2.57E-04 14-2047 646.88 0.00143 0 O.00E+00 14-2049 479.2 0.00176 0 0.00E+00 14-2051 431.25 0.00118 163.4286 1.18E-03 TOTAL 4629.33 0.804762 837T96 2.69850 TOTAL CUBIC METERS 23.72895 Page 1 of I Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Period: January December 2014 Waste Type: Irradiated Components a OF CONTAINERS SHIPPED TO CNSIIDUIRATEK ISOTOPE:% ABUNDANCE/LINER

1. OF SHIPMENTS TO CNSIIDURATEK 0 TOTAL AVE.AG-110m C-14 CE-144 CM-242 CM-243 CO-57 CO-58 CO-60 CR-51 CS-134 CS-136 CS-137 FE-55 FE-59 H-3 1-131 MN-54 NB-95 NI-59 NI-63 PU-238 PU-241 RU-103 RU-106 SB-124 SB-125 TA-182 TE-125m TRU XE-133 ZR-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0..00 0.00 0.00 0.00 0O00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0 00 0.00 0.00 0.00 0 00 0 00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0 00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000. 000 0.00 0.00 0 00 o.00 000 0.00 0.00 0.00 0.00 0.00 000 000 0 00 0.00 0.00 0,00 o.06 0.00 000Q 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 000 000 0.00 0.00 o.oo o.oo 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 000.od 0.000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 O0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 000'0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 000 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0 00 0.00 0,00 0.00 0.00 0.00 0 00 0.00 0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 00 0.00 0.00 0 00 0.00 0.00 0.00 #DIV/O!0.00 0.00 #DIVO!0.00 0.00 #DIV/O!0.00 0.00 #DIV/O!0.00 0.00 #DIV/0!0.00 0.00 #DIV/OI 0 00 0.00 #DIVIO'0.00 0.00 #DIVJOI 0.00 0.00 #DIV/O!0.00 0.00 #DIV/0!0.00 0.00 #DIV/O!0.00 000 #DIV/O!0.00 0.00 #DIVO/O 0.00 0.00 #DIV/OI 0.00 000 #DIV,0?0.00 0.00 #DIV/0!0.00 0.00 #DIVtO!0.00 0.00 #DIV/0!0.00 0.00 #DIV/0!0.00 0.00 #DIVt0I 0.00 0.00 #DIV/0I 0.00 0 0000 #DIV/0!0.00 0.00 #DIV/01 0.00 0.00 #DIVIOf 0.00 0.00 #DIV/0!0.00 0.00 #DIV/01 0.00 0.00 #DIV/0I 0.00 0.00 #DIV/0'0.00 0.0000 #DIV/0!0.00 00000 #DIV/0l 0.00 0.0000 #DIV/01 TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES CU. FT.CU. M RSR#0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 1 of I Attachment 4 Meteorological Data Oconee Nuclear Station (3 pages, including this cover sheet)

Oconee Nuclear Station., Attachment 3.1.1 ONS 2014 Lower JFD (Hours of Occurrence)

SECTOR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW No. No. No. No. No. No. No. No. No. No. No. No. No. No. No. No.A 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 1 0 0 0 0 0 0 0 1 4 1 1 0 1 1 2 1.26-1.50 0 3 2 0 1 0 0 2 2 12 7 4 2 2 4 1 1.51-2.00 14 14 10 10 5 2 3 2 13 42 69 22 9 10 4 4 2.01-3.00 6 6 19 43 12 1 2 2 18 146 140 22 15 5 4 3 3.01-4.00 1 2 11 22 7 0 2 1 5 57 30 13 5 6 2 1 4.01-5.00 2 0 5 0 0 0 0 0 0 7 11 9 6 2 1 4 5.01-6.00 0 1 1 01 0 0 0 0 0 0 1 2 1 2 5 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 1 1 0 0 2 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 B 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 2 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1.01-1.25 3 3 1 0 0 0 0 1 3 0 2 3 2 2 0 2 1.26-1.50 5 0 2 1 2 0 1 0 0 7 6 5 4 2 1 0 1.51-2.00 5 3 5 8 5 5 2 1 4 16 15 12 12 2 3 3 2.01-3.00 1 5 14 32 12 2 1 4 3 44 47 12 1 1 3 1 3.01-4.00 0 1 1 8 1 0 1 0 1 30 14 7 1 3 1 3 4.01-5.00 0 0 2 2 1 0 0 0 0 3 7 7 4 1 1 1 5.01-6.00 0 0 0 0 0 0 0 0 0 1 1 3 0 2 2 1 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 1 0 2 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 10.01-Max 0 0 0 01 0 0 0 0 0 0 0 0 0 0 0 0 C 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 1 0 0 1 0 11 2 1 1 1 1.01-1.25 5 3 2 0 1 1 0 1 3 3 1 2 3 2 1 1 1.26-1.50 7 4 4 4 3 1 1 4 6 4 8 5 11 3 3 3 1.51-2.00 2 10 14 15 14 5 3 5 9 19 22 16 10 8 4 0 2.01-3.00 1 1 17 41 17 31 6 3 61 33 36 13 3 0 3 0 3.01-4.00 0 0 6 13 2 0 0 1 0 16 12 7 1 2 3 1 4.01-5.00 0 0 1 1 0 0 0 0 0 3 14 6 5 2 4 2 5.01-6.00 0 0 0 0 0 0 0 0 0 2 4 10 0 3 4 1 6.01-8.00 0 0 0 0 0 0 0 0 0 0 1 5 1 4 3 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D 0.46-0.75 3 0 3 1 3 2 4 0 2 4 3 2 5 5 1 3 0.76-1.00 17 11 15 11 10 6 6 10 8 7 9 28 14 23 16 23 1.01-1.25 25 18 16 16 15 9 16 13 12 12 21 26 18 25 28 30 1.26-1.50 25 17 30 46 39 18 32 27 22 19 24 32 24 20 15 32 1.51-2.00 12 23 91 122 109 40 38 34 33 61 55 41 29 12 12 17 2.01-3.00 19 20 138 222 122 13 28 13 23 101 104 64 41 22 25 21 3.01-4.00 4 5 25 38 12 2 3 21 21 411 821 611 351 231 231 13 Oconee Nuclear Station E-i F 4.01-5.00 0 2 12 14 3 1 01 0 0 17 31 54 27 26 10 3 5.01-6.00 0 0 2 1 0 0 0 0 0 2 17 26 14 15 7 1 6.01-8.00 0 0 0 0 0 0 0 0 0 0 5 19 10 7 2 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 3 2 1 2 0 10.01-Max 0 0 0 01 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 17 8 7 0 6 6 1 4 8 3 11 8 10 20 26 20 0.76-1.00 55 48 30 36 26 23 23 16 26 21 38 34 66 64 78 68 1.01-1.25 45 27 22 33 43 32 19 23 28 24 32 30 36 50 55 65 1.26-1.50 18 25 35 30 43 36 33 34 28 29 37 34 16 26 31 25 1.51-2.00 11 6 24 521 45 39 41 46 40 44 42 24 23 15 13 8 2.01-3.00 5 6 8 26 17 5 10 18 8 44 46 28 17 12 10 5 3.01-4.00 0 0 0 1 0 0 0 0 0 14 23 17 9 4 2 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 5 9 0 0 1 0 5.01-6.00 0 0 0 0 0 0 0 0 0 1 7 2 2 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 01 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 0.46-0.75 0 0 2 2 0 2 0 2 1 2 0 4 7 3 3 0.76-1.00 0 4 2 2 2 2 2 1 8 3 3 6 17 34 18 9 1.01-1.25 3 3 3 01 2 0 1 1 0 2 5 5 14 44 18 0 1.26-1.50 0 1 0 1 0 2 3 4 1 2 71 1 3 31 23 0 1.51-2.00 1 0 0 0 1 1 10 0 0 3 9 0 6 5 4 0 2.01-3.00 1 0 0 0 0 1 1 0 0 3 6 1 0 1 0 0 3.01-4.00 0 0 0 0 0 0 0 0 0 0 3 1 0 0 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 01 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 0.46-0.75 1 0 0 0 0 0 0 0 1 0 0 2 3 1 2 0 0.76-1.00 0 1 0 0 0 0 0 0 0 1 2 5 11 12 8 0 1.01-1.25 0 0 0 0 0 0 1 0 0 0 01 2 7 15 2 1 1.26-1.50 0 0 0 0 0 0 0 0 0 0 4 2 1 13 8 0 1.51-2.00 0 0 0 0 0 0 0 0 0 0 0 1 1 1 3 0 2.01-3.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.01-4.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.01-8.00 0 0 0 3 3 3 0 -3 3 0-0 0a 0- 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 G 10.01-Max 0 0 0 0 0 0 0 01 0 0 0 0 01 0 0 0-I I a a kk & A J A A a J -J -J Attachment 5 Unplanned Offsite Releases Unplanned Offsite Release of Oconee Nuclear Station "3A" Gaseous Waste Decay (GWD) Tank Event Summary: Release of "3C" GWD Tank began at 16:22 on 6/1/14 as Gaseous Waste Release (GWR) 2014-047.

The rate of release was slowly increased until stable counts were observed on radiation monitor 3RIA-37. The "3C" GWD Tank release was terminated at 18:53 on 6/1/14 when an unexpected decrease in "3A" GWD Tank pressure was observed.

The "3A" GWD Tank pressure decreased from 16.2 psig to 15.5 psig during the GWR 2014-047 release. When GWR 2014-047 release was stopped, the "3A" GWD Tank pressure stopped decreasing.

Investigation identified two GWD system valves that were leaking past the seat during the release.The two GWD valves were repaired to prevent future occurrences.

A separate "3A" GWD Tank release permit, 2014-056, was created to account for the release activity and related dose. Based on the GWD Tank volume chart in OP/0/A/1 108/001, Curves And General Information, a 0.7 psig decrease corresponds to a release volume of 100 ft 3.The concentrations of the radionuclides during the unplanned release were estimated to be the sampled concentrations identified during the "3A" GWD release 2014-048, which occurred on 6/3/2014.

The total activity of the unplanned release was 1.29E-06 Curies.Safety Significance:

The health and safety of the public were not compromised by this event. The total activity released was 1.29E-06 Curies. Calculated dose and dose rates to the Total Body, Skin, Gamma Air, and Beta Air were all well below the limits specified by Selected Licensee Commitments (Page 1 of 1)

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)(13 pages, including this cover sheet)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3Quarter 2014 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=-

Quarter 1 2014 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 -Maximum Organ Dose CHILD BONE 9.03E-02 2.25E+01 4.01E-01 Maximum Organ Dose Receptor Location:

1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)Nuclide Percentage C-14 1.0OE+02 NOBLE GAS DOSE LIMIT ANALYSIS Quarter 1 2014 Dose Limit % of Period-Limit (mrad) (mrad) Limit Ql -Maximum Gamma Air Dose 1.14E-04 1.50E+01 7.63E-04 Maximum Gamma Air Dose Receptor Location:

1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage XE-133 9.99E+01 Q1 -Maximum Beta Air Dose 3.40E-04 3.00E+01 1.13E-03 Maximum Beta Air Dose Receptor Location:

1.0 Mile SW Major Contributors (5% or greater to total)Nuclide Percentage XE-133 9.99E+01 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 2- Quarter 2014 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS-Quarter 2 2014 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 -Maximum Organ Dose CHILD BONE 8.02E-02 2.25E+01 3.56E-01 Maximum Organ Dose Receptor Location:

1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)Nuclide Percentage C-14 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS.

Quarter 2 2014 =Dose Limit % of Period-Limit (mrad) (mrad) Limit Q2 -Maximum Gamima-Air Dose ... ......................

3;52E-04 -Maximum Gamma Air Dose Receptor Location:

1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage AR-41 2.00E+01 XE-133 7.95E+01 Q2 -Maximum Beta Air Dose 1.29E-04 3.00E+01 4.31E-04 Maximum Beta Air Dose Receptor Location:

1.0 Mile SW Major Contributors (5% or greater to total)Nuclide Percentage XE-133 9.66E+01 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 3-L Quarter 2014 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS a -Quarter 3 2014 Critical Critical Dose Limit Max % of Period-Limit Age Organ (arem) (mrem) Limit Q3 -Maximum Organ Dose CHILD BONE 9.04E-02 2.25E+01 4.02E-01 Maximum Organ Dose Receptor Location:

1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)Nuclide Percentage C-14 1.00+E02 NOBLE GAS DOSE LIMIT ANALYSIS Quarter 3 2014 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q3 -Maximum Gamma Air Dose 2.00E-04 1.50E+01 1.33E-03 Maximum Gamma Air Dose Receptor Location:

1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage AR-41 6.59E+00 XE-133 9.34E+01 Q3 -Maximum Beta Air Dose 5.62E-04 3.00E+01 1.87E-03 Maximum Beta Air Dose Receptor Location:

1.0 Mile SW Major Contributors (5% or greater to total)Nuclide Percentage XE-133 9.90E+01 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 4-h Quarter 2014 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=-

Quarter 4 2014 =Critical Critical Dose Limit Max % of Period-Limit Age Organ (arem) (arem) Limit Q4 -Maximum Organ Dose CHILD BONE 7.79E-02 2.25E+01 3.46E-01 Maximum Organ Dose Receptor Location:

1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)Nuclide Percentage C-14 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS Quarter 4 2014 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q4 -Maximum Gamma Air Dose 4.48E-04 1.50E+01 2.99E-03 Maximum Gamma Air Dose Receptor Location:

1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage XE-133 9.82E+01 Q4 -Maximum Beta Air Dose 1.31E-03 3.OOE+01 4.38E-03 Maximum Beta Air Dose Receptor Location:

1.0 Mile SW Major Contributors (5% or greater to total)Nuclide Percentage KE-133 9.97E+01 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 GASEOUS ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 ANNUAL 2014 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS -Annual 2014 Critical Critical Dose Limit Max % of Period-Limit Age Organ (trem) (arer) Limit..............................................................................

Yr -Maximum Organ Dose CHILD BONE 3.39E-01 4.50E+01 7.53E-01 Maximum Organ Dose Receptor Location:

1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Nuclide C-14 Contributors (5% or greater to total)Percentage 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS Annual 2014 Dose Limit % of Period-Limit (mrad) (mrad) Limit Yr -Maximum Gamma Air Dose 8.16E-04 3.00E+01 2.72K-03 Maximum Gamma Air Dose Receptor Location:

1.0 Mile SW Major Isotopic Nuclide XE-133 Contributors (5% or greater to total)Percentage 9.60E+01 Yr -Maximum Beta Air Dose 2.35E-03 6.00E+01 3.91E-03 Maximum Beta Air Dose Receptor Location:

1.0 Mile SW Major Contributors Nuclide XE-133 (5% or greater to total)Percentage 9.94E+01 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 12-5 Quarter 2014= BATCH LIQUID RELEASES Period-Limit Q1 -Maximum Organ Dose Q1 -Total Body Dose Critical Critical Age ADULT ADULT Critical Organ GI-LLI Dose (mtrem)3. 44E-02 3.15E-02 Quarter 1 2014 =Limit Max % of (mrem) Limit 1.50E+01 2.29E-01 4.50E+00 6.99E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or gre Nuclide Percentage H-3 8.04E+01 NB-95 1.50E+01 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or gre Nuclide Percentage H-3 8.77E+01 CS-137 1.14E+01 CONTINUOUS LIQUID RELEASES (CTP 3)Critical Period-Limit Age Q1 -Maximum Organ Dose CHILD Q1 -Total Body Dose CHILD ater to total)atar to total)Quarter 1 2014 Critical Dose Limit Max % of Organ (mrem) (mrem) Limit LIVER 3.21E-05 1.50E+01 2.14E-04 3.21E-05 4.50E+00 7.13E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 1.00E+02 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 2na Quarter 2014 BATCH LIQUID RELEASES Quarter 2 2014 Critical Critical Dose Limit Max % of Pertod-Limit Age Organ (mrem) (mrem) Limit Q2 -Maximum Organ Dose ADULT GI-LLI 3.14E-02 1.50E+01 2.10E-01 Q2 -Total Body Dose CHILD 2.74E-02 4.50E+00 6.09E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 8.29E+01 NE-95 1.47E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H 3 .... ..... ... .9 89E+01 ....................

..................................

CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 2 2014 =Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 -Maximum Organ Dose CHILD LIVER 2.44E-05 1.50E+01 1.62E-04 Q2 -Total Body Dose CHILD 2.44E-05 4.50E+00 5.42E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage Hý3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 1.OOE+02 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3Quarter 2014 BATCH LIQUID RELEASES Quarter 3 2014 Critical Critical Dose Limit Max % of Period-Limit Age Organ (arem) (mrem) Limit Q3 -Maximum Organ Dose ADULT LIVER 3.12E-02 1.50E+01 2.08E-01 Q3 -Total Body Dose ADULT 2.51E-02 4.50E+00 5.58E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 4.16E+01 CS-137 5.31E+01 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 .... ............

.... .5'16E+01 ..............

..CS-137 4.32E+01 CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 3 2014 =Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 -Maximum Organ Dose CHILD LIVER 4.36E-05 1.50E+01 2.91E-04 Q3 -Total Body Dose CHILD 4.36E-05 4.50E+00 9.69E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)fluclide Percentage H-3 1.0OE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 1.00E+02 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 4-n Quarter 2014= BATCH LIQUID RELEASES =Period-Limit Q4 -Maximum Organ Dose Q4 -Total Body Dose Critical Age CHILD ADULT Critical Organ LIVER Dose (aorero)6. 95E-02 6.22E-02 Quarter 4 2014 -Limit Max % of (mrem) Limit 1.50E+01 4.64E-01 4.50E+00 1.38E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 7.49E+01 CS-137 2.43E+01 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 ..... ..... 8.06E+01 CS-137 1.89E+01 CONTINUOUS LIQUID RELEASES (CTP 3)Critical Period-Limit Age Q4 -Maximum Organ Dose CHILD Q4 -Total Body Dose CHILD Quarter 4 2014 =Critical Dose Limit Max % of Organ (trem) (trem) Limit LIVER 4.55E-05 1.50E+01 3.03E-04 4.55E-05 4.50E+00 1.01E-03 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or Nuclide Percentage R-3 I-OE+02 greater to total)greater to total)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/14 TO 1/1/15 LIQUID ANNUAL DOSE

SUMMARY

REPORT Oconee Nuclear Station Units 1, 2, & 3 ANNUAL 2014 BATCH LIQUID RELEASES Critical Period-Limit Age Yr -Maximum Organ Dose CHILD Yr -Total Body Dose ADULT Critical Organ LIVER Dose (mrem)1. 62E-01 1. 46E-01 Annual 2014 Limit Max % of (mrem) Limit 3.009+01 5.41E-01 9.00E+00 1.62E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 7.47E+01 CS-137 2.37E+01 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 ...........

.. .8.03E+01 -CS-137 1.84E+01 CONTINUOUS LIQUID RELEASES (CTP 3)Critical Period-Limit Age Yr -Maximum Organ Dose CHILD Yr -Total Body Dose CHILD Critical Dose Organ (mrem)LIVER 1.46E-04 1.46E-04 Annual 2014 =Limit Max % of (mrem) Limit 3.OOE+01 4.85E-04 9.00E+00 1.62E-03 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage H-3 1.00E+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclida Percentage H-3 1.00E+02 Oconee Nuclear Station 2014 Radioactive Effluent and ISFSI 40CFRI90 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFRI90, 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 fLiel cycle dose assessment for Oconee Nuclear Station only includes liquid and gaseous effluent dose contributions from Oconee and direct and air-scatter dose from Oconee's onsite Independent Spent Fuel Storage Installation (ISFSI) since no other uranium fuel cycle facility contributes significantly to Oconee's maximum exposed individual.

Included in the gaseous effluent dose calculations is an estimate of the dose contributed by Carbon-14 (Ref. "Carbon-14 Supplemental Infbornation", contained in the ARERR for further information).

The combined dose to a maximum exposed individual from Oconee's effluent releases and direct and air-scatter dose from Oconee's ISFS1 is below 40CFR 190 limits as shown by the following summary:[. 2014 Oconee 40CFRI90 Effluent Dose Summary The 40CFR 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).Maximum Total Body Dose = 2.54E-01 mrem Maximum Location:

1.0 Mile., Southwest Sector Critical Age: Child Gas non-NG Contribution:

49.10%Gas NG Contribution:

0.27%Liquid Contribution:

50.63%Maximum Organ (other than TB) Dose = 4.OIE-01 mrem Maximum Location:

1.0 Mile. Southwest Sector Critical Age: Child Critical Organ: Bone Gas Contribution:

84.53%Liquid Contribution:

15.47%1I. 2014 Oconee 40CFRI90 ISFSi Dose Summary Direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at Oconee have been calculated and documented in the "Oconee Nuclear Site IOCFR72.212 Written Evaluations" report. As discussed in the report, the dose rate at 500 meters is 6.84 mrem per year. The nearest resident from the Oconee ISFSI is -1600 meters so the dose rate at the nearest resident location would be much less than 6.84 mrem per year.The following excerpt. "C. I OCFR72.212(b)(2)(i)(C)-

Requirements of 72.104". from the"Oconee Nuclear Site I OCFR72.212 Written Evaluations" report is provided to document the method used to estimate the Oconee ISFSI dose to the nearest "real individual".

C. IOCFR72.212(b)(2)(i)(C)-

Requirements of 72.104...the requirements ot, 72.104 have been met.10 CFR 72.104. as clarified by ISG-13, 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 torem) 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 190.10(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 Iinitial enrichment.

burnup and cooling time) of existing fuel in Phases I -V of the Oconee ISFSI, together with the characteristics of assumed "design basis" fuel in Phase VI of the Oconee ISFSI. Calculation OSC-8675 develops the radiation source terms used in subsequent shielding and skvshinc calculations using the SCALE Code System.More specifically, the SAS2 Module of the SCALE Code System was used to create a problem-dependent pin-cell model for the purpose of building cell- weighted, multigroup cross section sets for use in subsequent depletion calculations.

The ORIGEN-S Module 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 sofltare and data quality assurance program.i[he results of the radiation source term calculation w-ere 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 code was used to perform the transport calculations and to write a surface flux file for use in subsequent skyshine calculations.

Appropriate sollware quality controls have been implemented for the computer codes and data used in these analyses (specificallv.

Calculation DPC-1201.30-00-0010 contains the verinication and validation for MCNP5. while SDQA-30269-NG0 documents the quality control measures in place for MICNP5).Calculation OSC-8716 uses the surface flux Files developed in OSC-8706 in a repeating array representing all of the Horizontal Storage Modules in the ISFSI, including Phase VI fully loaded with spent fuel. he source description in the MCNP input is constructed with source probabilities for each Horizontal Storage Module to represent the appropriate decay time associated with each HISM. Finally, a skyshine calculation is performed to obtain near- and far-field dose results from Phases I -VI of the Oconee ISFSI.Calculation OSC-8716 '[able 23. 1-I, summarizes dose rate versus distance, showing a dose rate of 6.84 mRem per year at 500 meters, which is the longest distance at which results converge.

The closest residence to the ISFSI is in the SW-SSW direction approximately I mile (-1600 meters) from the ISFSI. or 1.36 miles from the centerline of the site. This is conservatively farther than the distance used for computation of dose rates. The 2009 40CFRI90 Uranium Fuel Cycle Dose Calculation Results for the ONS site show a maximum total body dose of 0.0754 mrem per year. The total dose rate fiom all operations to the nearest real individual is therefore less than 7 mRem per year.T'hese calculations need not consider any effluent from Phase VI. [he Phase VI HSMs use the NUI-IOMS-24PHB DSCs. which are designed as "leak-tight".

Per Appendix N. Section N.11.2.8 of the NUI-IOMS FSAR3 accidental releases are not credible.

Attachment 7 Revisions to the Oconee UFSAR Section 16.11 Radiological Effluent Controls SLC Change 2014-02 revised SLC 16.11.10, Radiological Effluent Control to clarify Routine Radiological Environmental Operating Reports are submitted by May 15 of each year per TS 5.6.2. Previously it has said "prior to" each year.SLC Change 2012-13 revised SLC 16.11.4, Operational Safety Review. The change eliminates an inconsistency in SLC Table 16.11.4 -1 between a footnote requiring samples to be changed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a statement in the table requiring a "week" sample change frequency.

This is a table consistency/

clarification issue. Samples are collected and analyzed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Additionally, a new footnote (k) and reference to support Ce-144 and Mo-99 sampling were added.(10 pages, including this cover sheet)

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 Interlaboratory Comparison Program. The Interlaboratory 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 05/14/14 I 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:

1.2.Oconee ITS Offsite Dose Calculation Manual 16.11.10-2 05/14/14 I 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 06/30/14 I 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 Decant Monitor Tank, Turbine Building Sump Monitor Tanks, Waste and Recycle Monitor Tanks a. Principal Gamma Emitters(c) including Dissolved Noble Gases b. Radiochemical Analysis Sr-89 and Sr-90 Composite Grab Sample prior to release of each batch"h)<5E-06 pCi/ml (Ce-144)<5E-07 pCi/ml (Other Gamma Nuclides)<1E-05 pCi/ml (Dissolved Gases)<1E-06 pCi/ml (1-131)c. Tritium Quarterly from all composited batches(f)

Monthly Composite Monthly Composite Continuous monitor, weekly sample(e)<5E-08 pCi/ml<1E-05 pCi/ml 2. Unit Vent Sampling (Includes Waste Gas Decay Tanks, Reactor Building Purges, Auxiliary Building Ventilation, Spent Fuel Pool Ventilation, Air Ejectors)d. Gross Alpha Activity a. Iodine Spectrum(a)

b. Particulates(a)

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

<1E-07 pCi/mI<1 E-10 pCi/cc (1-133)(j<1 E-12 pCi/cc (1-131)0)Weekly Composite(e)

Weekly Compositeme)

Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample Grab Sample prior to release of each batch Grab Sample prior to release of each batch Grab sample each purge Grab sample each purge<5E-10 pCi/cc 1)(k)<1E-11 p.Ci/cco)<1E-11 pCi/cc<1E-11 pCi/cc<1E-04 pCi/cc d. Tritium<1E-06 pCi/cc 3. Waste Gas Decay Tank a. Principle Gamma Emitters(d)

b. Tritium<1 E-04 pCi/cc (gases)<1 E-10 pCi/cc (particulates and iodines)<5E-09 pCi/cc (Ce-1 44 and Mo-99)<1E-06 pCi/cc<1E-04 pCi/cc (gases)<1E-10 pCi/cc (particulates and iodines)<5E-09 pCi/cc (Ce-144 and Mo-99)<1E-06 pCi/cc 4. Reactor Building a. Principle Gamma Emitters(d)

b. Tritium 16.11.4-2 06/30/14 I 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 Treatment Pond EffluentOi)

a. Principle Gamma Emitters(c)

b. 1-131 c. Tritium d. Gross Alpha Activity e. Sr-89 & Sr-90 f. Dissolved and Entrained gases (Gamma Emitters)Weekly Continuous Composite(g)

Weekly Continuous Composite(g)

Monthly Continuous Composite(g)

Monthly Continuous Composite(g)

Quarterly Continuous Composite(g)

Monthly Grab<5E-07 jiCi/ml<1E-06 pCi/mI<1E-05 pCi/ml<1E-07 pCi/mI<5E-08 pCi/ml<1E-05 pCi/mI 7. Radwaste Facility Ventilation a.b.Iodine Spectrum(a)

Continuous monitor, weekly sample(e)(1-133) <1E-09 pCi/cc (1-131) <1E-11 p.Ci/cc Particulate(a)

i. Ce-144 and Mo-99 ii. Other Principle Gamma Emitters(d) iii. Gross Alpha Activity iv. Radiochemical Analysis Sr-89, Sr-90 c. Gases by Principle Gamma(d)Emitters d. Tritium Weekly Composite(e)

Weekly Composite(e)

Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample<5E-10 pCi/ccj)<1E-11 pCi/ccO)<1E-11 pCi/cc<1E-11 pACi/cc<1E-04 pCi/cc* 1 E-06 pCi/cc 16.11.4-3 06/30/14 I 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 Ventilation

a. Iodine Spectrum Weekly Sample(e)(1-133) <1E-10 j.Ci/ccj)(1-131) <1E-12 pCi/cco)b. Particulate i.Ce-144 and Mo-99 ii. Other Principle Gamma Emitters (d)iii. Gross Alpha Activity iv. Radiochemical Analysis Sr-89, Sr-90 c. Gases by Principle Gamma Emitters d. Tritium Weekly Composite(e)

Weekly Composite(e)

Monthly, using composite samples of one week Quarterly Composite<5E-10 pCi/cc(JXk)

<1E-11 piCi/cca)<1E-11 pCi/cc<1E-11 g.Ci/cc NA NA NA Weekly sample(e)9. Interim Radwaste Building Ventilation a.NA (1-133) <1E-10 pCi/cc 0)(1-131) <1E-12 .Ci/cco)Iodine Spectrum b.Particulate

i. Ce-144 and Mo-99 ii. Other Principle Gamma Emitters(d) iii. Gross Alpha Activity iv. Radiochemical Analysis Sr-89, Sr-90 c. Gases by Principle Gamma(d)Emitters d. Tritium Weekly Composite(e)

Weekly Composite(e)

Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample<5E-10 p.Ci/ccJ)<1E-11 I.Ci/ccaj)

<1E-11 l.Ci/cc<lE-11 i.Ci/cc<1 E-04 1.Ci/cc<1E-06 pCi/cc 16.11.4-4 06/30/14 1 Operational Safety Review 16.11.4 (a) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.

When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analyses show that the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.(b) The LLD is defined for purposes of these commitments as the smallest concentration of radioactive material in a sample that would be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which may include radiochemical separation):

LLD = (2.71 I T) + 4.65 sb E x V x 2.22E06 x Y x exp (-XAt)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), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22E06 is the number of disintegrations per minute per micro Curie, Y is the fractional radiochemical yield (when applicable), X is the radioactive decay constant for the particular nuclide A t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

NOTE: This assumes decay correction is applied (at the time of analysis) for the duration of sample collection, for the 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 A t should be used in the calculation.

It should be recognized that the LLD is an a prior (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 i.Ci/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-1 33. Xe-1 33m, Xe-1 35. and Xe-1 38 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 1 Operational Safety Review 16.11.4 (g) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.(h) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, each batch shall be isolated, and then thoroughly mixed, to assure representative sampling.(i) A continuous release is the discharge of liquid wastes of a non-discrete volume, e.g., from a volume of a system that has an input flow during the continuous release. Samples shall be analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (on or after removal from sampler).(j) When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. Samples shall be analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (on or after removal from sampler).(k) Ce-144 and Mo-99 LLD as approved by NRC SER dated January 16, 1984 (Reference 1).16.11.4-6 06/30/14 1 Operational Safety Review 16.11.4 BASES N/A

REFERENCES:

1. Safety Evaluation Report dated January 16, 1984, supporting Amendment Nos.125, 125, and 122 for Oconee Nuclear Station to revise Technical Specifications to incorporate changes to the Radiological Effluent Technical Specifications (RETS) in order to bring them into compliance with Appendix I of 10 CFR Part 50.16.11.4-7 06/30/14 I Attachment 8 Revisions to the Radioactive Waste Process Control Program Manual (4 pages, including this cover sheet, and Compact Disc)

March 11, 2015 CJ Wasik Manager Regulatory Affairs Oconee Nuclear Organizational Effectiveness Attention:

J. E. Smith

Subject:

Oconee Nuclear Station 2014 Annual Radioactive Effluent Release Report Process Control Program Changes File: GS-764.25, OS-215.06 Enclosed are CD copies of the PDF file of the Radioactive Waste Process Control Program Manual to be included in the NRC distribution of the Annual Radioactive Effluent Release Report for Oconee Nuclear Station for the period of January 1, 2014 through December 31, 2014. This version of the Manual contains all the changes implemented during 2014 and is designated on the CD cover as the "2014 ARERR, 2015 Submittal, Radioactive Waste Process Control Program Manual".The PCP Manual is revised using the review and approval process in APPENDIX F of the PCP Manual,"Administration of the PCP and Support Documents" prior to publication on the NEDL Portal.The attachment summarizes the scope of the changes during 2014.The PDF file "DEC 2014-15 PCP Manual.pdf' on the CDs was reviewed and verified against the control copies of the PCP Manual published on the NEDL Portal. Two CD copies are for internal distribution, one is for SC DHEC and four CDs are for the NRC as follows: DUKE 1. ELL 2. Master File SC STATE 3. DHEC primary contact Russell Keown NRC 4. NRC Document Control Desk 5. Oconee NRC Project Manager 6. Oconee Senior Resident Inspector 7. NRC Regional Administrator If you have any questions, please call David Vaught @ 980-373-5302.

James A. Mockridge Supervising Scientist Nuclear Chemistry by: David L Vaught Lead Engineer Nuclear Chemistry

-Radwaste ATTACHMENT:

Appendix L -ARERR Attachment 8

Appendix L -ARERR ATTACHMENT 8 Revisions to the Radioactive Waste Process Control Program Manual A brief summary of the 2014 changes to the Duke Energy Radioactive Waste PCP Manual is found below. These are described in more detail in APPENDIX H "Revision Summary -Licensee Initiated Changes".

The Duke Energy Carolinas (DEC) PCP Manual is a Corporate document used by the 3 DEC sites. The Duke Energy Progress (DEP) site PCPs have not been incorporated into this PCP Manual and they have their own individual PCPs that will be submitted in their ARERRs.

SUMMARY

OF PCP MANUAL CHANGES The PCP Manual revisions described in this summary were implemented as a result of the project to transfer of the Chemistry department operating programs to the Operations department.

PIP G-14-00619 describes the PCP Manual changes and documents the reviews and approvals.

These revisions also reflect the organizational and program/ process changes from the Duke Energy &Progress Energy merger.PCP MANUAL SECTIONS CHANGED APPENDIX A: "ONS PCP" Rev 16 APPENDIX B: "MNS PCP" Rev 19 APPENDIX C: "CNS PCP" Rev 13 APPENDIX E: "PCP Manual Review and Approval Requirements" Rev 3 DESCRIPTION OF CHANGES BY SECTION APPENDICES A, B & C Summary of changes The Site PCP Sections Appendix A, B & C were all changed in the following manner: 1. Added the new Operations PCP implementing procedures developed from the Radwaste Chemistry procedures (both are listed to support the transition)

2. Changes in the management approvals:

replaced site Station Manager with Nuclear AOM Shift approval (Manager over Operations Radwaste Core Team)3. Chemistry Manager Approval remains in place since Chemistry will provide technical support to the PCP METHODOLOGY During the transfer of the Chemistry department operating programs to the Operations department, the PCP implementing procedures that were used by Chemistry Radwaste will be superseded by the new Operations procedures as the new procedure implementation requirements are completed.

Appendix L -ARERR ATTACHMENT 8 Revisions to the Radioactive Waste Process Control Program Manual These revisions to the site PCP sections of the PCP Manual change the organization of the site PCP sections to address the transitional conditions of the step-wise process used in training, qualification and procedure validation that the transition to the new procedures requires.

This format allows the following methodology to be used: " Both procedures are listed in the site PCP section for this revision so either may be used when needed by the site." As each new Operations procedure is implemented, the Chemistry procedure will be no longer available in NEDL.APPENDIX E: "PCP Manual Review and Approval Requirements" Rev 3 Changed the technical reviews and management approvals designated for each section of the PCP Manual affected by the project to move operating functions from Chemistry to Operations.

Table E-1: Revision Review and Approval 1. Corporate PCP Section;* Changed to specify DEC Station Managers approvals since the PCP Manual has not yet been revised to incorporate the DEP Sites* Added the DEC Nuclear AOM Shift approval (Manager over Ops Radwaste Core Team)* Specified DEC Chemistry Managers Approvals* Changed Technical review from Station Chemistry Staff to Station Radwaste Staff 2. Site Specific PCP Sections:

Appendix A, B & C* Changed site technical review from Chemistry to Radwaste* Added the DEC Nuclear AOM Shift approval (Manager over Ops Radwaste Core Team)Table E-2: Minor Change Review and Approval Changed technical review from Chemistry to Radwaste Attachment 9 Information to Support the Nuclear Energy Institute (NEI) Groundwater Protection Initiative (4 pages, including this cover sheet)

Oconee 2014 ARERR -Ground Water Well Tritium Data Duke Energy implemented a Ground Water Protection program in 2007. This initiative was developed to ensure timely and effective management of situations involving inadvertent releases of licensed material to ground water. As part of this program, Oconee Nuclear Station monitored 67 wells in 2014. 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-I, in 2011 has resulted in decreased tritium concentrations in well GM-7DR to below MDA.Wells are typically sampled quarterly or semi-annually.

The recovery well discharge composite was collected weekly through 3/3/2014, then monthly thereafter.

The decisions to decrease recovery well analysis was based on long term trending showing consistent tritium concentrations.

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 2014. Results from sampling during 2014 confirmed existing knowledge of tritium concentrations in site ground water.On 5/28/2014, it was discovered samples from monitoring wells A-I, A-10, A-I 1 and A-13 for the April 2014 timeframe were not shipped to a South Carolina (SC) certified laboratory, as required, for gamma and tritium analyses due to personnel oversight.

This was documented in Corrective Action Program (CAP) entry PIP G-14-1208.

Upon discovery, samples were immediately analyzed for gamma and tritium by Duke Energy EnRad laboratory and then shipped to SC certified laboratory for tritium analysis.

The SC certified laboratory was unable to meet the gamma lower limits of detection for ground water due to long decay time, Monitoring wells A-I, A-10, A-I I and A-13 were resampled on 6/5/2014 and sent to SC certified laboratory for immediate gamma and tritium analyses.

All analyses exhibited typical values. Results obtained from resampling on 6/5/2014 are included in table below.One event meeting the criteria for voluntary notification per NEI 07-07 occurred at Oconee in 2014 as documented in CAP entry PIP 0-14-5 180. On 5/6/2014, while transferring water from Chemical Treatment Pond-I (CTP-I) to CTP-3, water was observed seeping from the ground at a location near the transfer piping between the ponds. The transfer was terminated and the ground seepage subsided.

The leakage path was identified as a 3 inch hole drilled in the side of the Yard Drain catch basin. The hole had been drilled over two years earlier per an Engineering Change for the installation of security cables. The as found orientation of the catch basin lid contributed to the amount of leakage that occurred.

The 3 inch hole was repaired and the catch basin lid was reoriented.

Tritium concentration in CTP-1 at the time was approximately 4E+03 picocuries per liter. Total estimated tritium activity released over the lifetime of the leak was 2.4E-06 Curies and represents a small fraction of total tritium activity released in liquid effluents shown in Oconee 2014 ARERR Attachment I. Monitoring wells A-13 and A-14 are down gradient from the leak location.

The wells were sampled on 5/15/2014 to detect any changes to the tritium concentration in ground water. The results did not indicate any significant changes to tritium concentration in ground water, as both wells exhibited typical values.Results from sampling during 2014 are shown in the tables below.

Oconee 2014 ARERR -Ground Water Well Tritium Data WellL D Tritium Concentration (pCi/I) # of Name Location / Description ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples A-I ONS GWPI / A-I /CTP 1/2 <MDA <MDA <MDA <MDA 4 A-IO ONS GWPI / A-10 / CTP 3 3.87E+02 3,37E+02 2.74E+02 3.03EE+02 4 A- Il ONS GWPI / A-1 I /CTP 3 <MDA <MDA <MDA <MDA 4 A-12 ONS GWPI / A-12/CTP 3 <MDA <MDA <MDA <MDA 4 A-13 ONS GWPI /A-13 /CTP 1/2 3.72E+02 6.48E+02 7.65E+02 9.30E+02 4 A-14 ONS GWPI / A-14/CTP 1/2 2.63E+02 <MDA 2.1OE+02 <MDA 4 A-17 ONS GWPI / A-1 7 / CTP 1/2 1.78E+02 <MDA <MDA <MDA 4 A-18 ONS GWPI / A-18 / CTP 1/2 1.60E+02 <MDA <MDA <MDA 4 A-2 ONS GWPI / A-2 / CTP 1/2 <MDA <MDA <MDA <MDA 4 A-9 ONS GWPI / A-9 / CTP 1/2 1.79E+02 <MDA <MDA NS 3 BG-4 ONS GWPI / BG-4 / Ball Field <MDA <MDA <MDA <MDA 4 GM-10 ONS GWPI / GM-10 / 525 kv Sw Yard NS <MDA NS <MDA 2 GM-10R ONS GWPI / GM-10R / 525 kv Sw Yard NS <MDA NS <MDA 2 GM-Il ONS GWPI / GM-I I / ONS Garage NS <MDA NS <MDA 2 GM-IIR ONS GWPI / GM-I I R / ONS Garage NS <MDA NS <MDA 2 GM-12 ONS GWPl / GM-12 / E of Access Rd. NS <MDA NS <MDA 2 GM-12R ONS GWPI / GM-12R / E of Access Rd. NS <MDA NS <MDA 2 GM-13 ONS GWPI / GM-13 / 525 kv Sw Yard NS <MDA NS <MDA 2 GM-13R ONS (WPI / GM-13R /525 kv Sw Yard NS <MDA NS <MDA 2--GM-14 --ONSGWPI-/GM-I4/Mnt.

Trg.Facility NS .<MDA NS .<MDA GM-14R ONSGWPI/GM-14R/Mnt.

Trg. 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 <MDA <MDA 4 GM-16DDR ONS GWPI / GM-I6DDR 3.37E+02 2.79E+02 3.91EE+02 NS 3 GM-16DR ONS GWPI/GM-I6DR 7.86E+03 8.05E+03 8.53E+03 NS 3 GM-16R ONS GWPI /GM-16R 1.31E+03 1.23E+03 1.50E+03 NS 3 GM-17DR ONS GWPI / GM-I7DR 2.62E+03 2.61E+03 2.66E+03 2.51E+03 4 GM-17R ONS GWPI / GM-17R 1.36E+03 1.13E+03 1.45E+03 1.07E+03 4 GM-18R ONS GWPI/GM-18R 7.44E+03 6.69E+03 6.98E+03 6.66E+03 4 GM-19 ONS GWPI / GM-19 1.28E+03 1.31E+03 1.47E+03 1.72E+03 4 GM-19R ONSGWPI/GMI-19R 4.60E+02 3.42E+02 4.73E402 6.02E+02 4 GM-IR ONS GWPI / GM-IR / CTP 1/2 <MDA <MDA <MDA <MDA 4 GM-20 ONS GWPI / GM-20 <MDA <MDA <MDA <MDA 4 GM-20R ONS GWPI / GM-20R <MDA <MDA <MDA <MDA 4 GM-21 ONS GWPI / GM-21 NS <MDA NS <MDA 2 GM-22 ONS GWPI / GM-22 NS <MDA NS <MDA 2 GM-23 ONS GWPI / GM-23 2.98E+02 2.46E+02 3.72E+02 4.1OE+02 4 GM-24R ONS GWPI / GM-24R 1.59E+03 1.04E+03 1.17 E+03 NS 3 GM-25R ONS GWPI / GM-25R 3-03E+02 2.64E+02 3.86E+02 3.50E+02 4 GM-2DR ONS GWPI / GM-2DR / U-I/2 SFP 2.151,+02 2.22E+02 2.82E+02 3.66E+02 4 GM-2R ONS GWPI/GM-2R/U-1/2 SFP 4.43E+02 5.99E+02 4.19E402 5.14E+02 4 GM-3DR ONS GWPI / GM-3DR / U-3 SFP 1.91E+02 <MDA 2.46E+02 4.68 E+02 4 GM-3R ONS GWPI / GM-3R / U-3 SFP 2.60E+02 <MDA 3.20E+02 4.38E+02 4 GM-4 ONS GWPI / GM-4 / Rad. Mat. W11 5.24E+02 4.57E+02 4.92E+02 5.66E+02 4 GM-5 ONS GWPI / GM-5 / Rdwst. Bldg. 1.94E+02 <MDA <MDA NS 3 GM-5R ONS GWPI / GM-5R / Rdwst. Bldg. <MDA <MDA <MDA NS 3 GM-6 ONS GWPI / GM-6 / Outflow to CTP-3 <MDA <MDA <MDA <MDA 4 GM-6R ONS GWPI / GM-6R / Outflow to CTP-3 <MDA <MDA <MDA <MDA 4 GM-7 ONS GWPI / GM-7 / 525 kv Sw Yard 3.02E+02 <MDA 3.54E+02 3.74E+02 4 GNM-7DR ONS GWPI / GM-7DR <MDA <MDA <MDA <MDA 4 Oconee 20.14 ARERR -Ground Water Well Tritium Data Well Tritium Concentration (pCi/!) # of Name Location / Description 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples GM-7R ONSGWPI/GM-7R/525kvSwYard 4.96E+03 4.68E+03 3.80E+03 3.12E+03 4 GM-8 ONS GWPl / GM-8 / E of U-3 TB 2.46E+02 2.43E+02 2.75E+02 2.24E+02 4 GM-SR ONSGWPI /GM-8R /Eof U-3"rB <MDA 2.13E+02 3.08E+02 <MDA 4 GM-9 ONSGWPI/GM-9/EofU-2TB 2.87E+02 3.60E+02 4.12E+02 2.21E+02 4 GM-9R ONS GWPI / GM-9R / E of U-2T " <MDA <MDA 1.87E+02 <MDA 4 MW-I I ONS GWPI / MW-! I / Landfill <MDA NS <MDA NS 2 MW-lID ONSGWPI/MW-IID/Landfill

<MDA NS <MDA NS 2 MW-13 ONS GWPI / MW- 13/Landfill

<MDA NS <MDA NS 2 MW-16 ONS GWPI / MW-1 6 / Landfill <MDA NS <MDA NS 2 MW-3 ONS GWPI / MW-3 / Landfill <MDA NS <MDA NS 2 MW-RPOI ONS GWPI / MW-RPOl / Landfarm/Burial NS <MDA NS NS I MW-RP02 ONS GWPI / MW-RP02 / Landfarn/Burial NS <MDA NS NS I MW-RP03 ONS GWPI / MW-RP03 / Landfarrn/Burial NS <MDA NS NS I Well ..... Tritium Concentration (pCi/!) # of NameLocation

/ Description st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples Oil ONS / 011 / Ball Field <MDA <MDA <MDA <MDA 4 013 ONS/013/WII5

<MDA <MDA <MDA <MDA 4-01-5 .<NIDA <MDA <MDA <MDA 4 I Well Location / Description Tritium Concentration (pCi/I) # of Name Minimum Average Maximum Samples RW-I]') 525 kv Sw. Yard 1.45E+03 I 1.73E+03 I 1.99E+03 19 (I) Weekly sampling 12/30/2013

-3/3/2014, monthly thereafter.

Sampling through 12/8/2014 indicated.

Key to above tables.NS< MDA 20,000 pCi/l 1,000,000 pCi/I Not scheduled to be sampled or not sampled due to insufficient volume in well or well inaccessible during outage.picocuries per liter.less than minimum detectable activity, typically 250 pCi/I.the Environmental Protection Agency drinking watcr standard for tritium. This standard applies only to water used for drinking.the IOCFR20, Appendix B, Table 2, Column 2, Effluent Concentration Limit for tritium.

Attachment 10 Inoperable Equipment The Oconee Nuclear Station Radwaste Control Room "low flow annunciator" associated with 4RIA-45 (Radwaste Facility Ventilation System gaseous effluent discharge monitor) was declared out of service on 4/14/2014 and remained out of service until 6/17/2014.

The annunciator was not returned to service within 30 days as specified in Selected Licensee Commitment (SLC) 16.11.3, Condition "C" Required Action "C.2".Troubleshooting indicated that the interposing relay contacts of the flow relay were not consistently changing state to the closed position once the relay was de-energized.

Therefore, the low flow annunciator did not actuate in all circumstances as required by procedure.

Inability to locate a replacement flow relay in a timely manner caused the failure to return the low flow annunciator to service within 30 days. A replacement relay was eventually located and installed in the 4RIA-45 flow switch assembly.

Once replaced, the relay consistently operated as expected on an intentionally-imposed loss of flow condition.

The radiation monitor and associated particulate and iodine samplers were unaffected and were considered operable during the subject time frame.(Page 1 of 1)

Attachment 11 Radioactive Waste Systems Changes This attachment documents the changes made to the radioactive waste systems at the Oconee Nuclear Station during the period January 1, 2014 to December 31, 2014.There were no changes made to the radioactive waste systems during 2014 at the Oconee Nuclear Station. However the Spent Fuel Reverse Osmosis unit does create a new input to the Waste Stream.Reverse Osmosis Unit EC. # 100744 The Reverse Osmosis Unit (RO Unit) removes dissolved silica from the SFPs and the BWSTs.Suction is taken directly from the SFPs and from the purification loop for the BWSTs. Discharge from the RO Unit goes back into the system after the last filter of the purification loop. The water is recirculated with the source being purified under a number of limitations needed to prevent undesirable effects, since the RO Unit removes boron along with the silica and has a waste stream of water from the source being purified.

A separate antimony filter/resin partially removes antimony from the waste stream.(Page 1 of 1) 014 Offsite Dose Calculation Manual Compact Disc