Text

Annual Radioactive Effluent Release Report (ARERR)
	ML13214A061
Person / Time
Site:	Oconee
Issue date:	04/30/2013
From:	Batson S; Duke Energy Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML13214A061 (74)
	v • d • e

Scott L Batson DUKE Vice President ENERGY. Oconee Nuclear Station Duke Energy ONO1VP 1 7800 Rochester Hwy.

Seneca, SC 29672 April 30, 2013 o: 864.873.3274 f: 864.873.4208 Scott.Batson@duke-enersY.com 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 2012 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, 2012 through December 31, 2012. In accordance with TS 5.5.1, the Offsite Dose Calculation Manual (ODCM) is included in this submittal.

Attachment 1 Summary of Gaseous and Liquid Effluents Report Attachment 2 Supplemental Information Attachment 3 Solid Waste Disposal Report Attachment 4 Meteorological Data Attachment 5 Unplanned Offsite Releases Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)

Attachment 7 Revisions to UFSAR Section 16.11 Radiological Effluent Controls Attachment 8 Revisions to the Radioactive Waste Process Control Program Manual (Compact Disc)

Attachment 9 Information to Support the NEI Groundwater Protection Initiative Attachment 10 Inoperable Equipment Attachment 11 Radioactive Waste Systems Changes www~duke-energy~

U.S. Nuclear Regulatory Commission 2012 Annual Radioactive Effluent Release Report April30, 2013 Page 2 012 Offsite Dose Calculation Manual (Compact Disc)

Any questions concerning this report should be directed to Kent Alter at 864-873-3255.

Sincerely, Scott Batson Vice President Oconee Nuclear Station Attachments and Enclosures (Process Control Program [PCP] Revision Compact Disc [CD]

Offsite Dose Calculation Manual [ODCM] Compact Disc [CD]

U.S. Nuclear Regulatory Commission 2012 Annual Radioactive Effluent Release Report April 30, 2013 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. Ed Crowe NRC Senior Resident Inspector Oconee Nuclear Station Mr. John Boska NRC Project Manager (File via E-mail)

U.S. Nuclear Regulatory Commission One White Flint North, M/S O-8G9A 11555 Rockville Pike Rockville, MD 20852-2746 xc (with attachments only):

Ms. Susan E Jenkins, Manager Analytical & Radiological Environmental Services Division 2600 Bull Street Columbia, SC 29201 Mr. Joseph T. Sears, Chemistry Manager INPO 700 Gallerla Place, Suite 100 Atlanta, GA 30339-5943 Mr. Russell Keown, Supervisor Environmental Quality Control Analytical & Radiological Environmental Services Division 2600 Bull Street Columbia, SC 29201

ATTACHMENT I Summary of Gaseous and Liquid Effluents Report This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined inRegulatory Guide 1.21, Revision 1,Appendix B.

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 1 PageI of 9

TABLE 1A EFFLUENT A14D 1ASTE DISPOSAL A14NUAL REPORT PERIOD 1/1/12 TO 1/1/13 i GASZOUS EFFLUENTS - SMMTION OF ALL RELEASES i

Oconee Nuclear Station Units 1, 2, & 3 hIPORT FOR 2012 uJnit QTR I QTR 2 QTR 3 QTR 4 YhAR A. Fission and Activation Gases

1. Total Release C1 1.643+01 2.47E+00 3.173-02 6.02Z-02 1.903+01

2. Avg. Release Rate pCi/seo 2.093+00 3.14Z-01" 3.993-03 7.573-03 6.00Z-01 S. Zodine-131

1. Total Release Cl 01.00Z+00, 0.00o+00 0.001+00 1.80X-08 1.803-08

2. Avg. Release Rate pCi/sec 01.00+E00 0.003+00 0.00E+00 2.262-09 5.693-10 C. Partioulates Half Life >= 8 days

1. Total Release C1 00.00O+00 0.00R+00 0.00z+00 0.06Z+00 0.001+00

2. Avg. Release Rate pCi/sea 01.001400 0.00Z+00 0.001+00 0.001+00 0.001+00 D. Tritium

1. Total Release Ci 1L.01Z+02 1.811+01 3.02E+01 3.16E+01 1.811+02

2. Avg. Release Rate pCi/sea .11.299+01 2.313+00 3.803+00 3.97Z+00 5.733+00

3. Carbon-14

1. Total Release Ci 6.11H+00 4.74E+00 5.953+00 5.37Z+00 2.223+01

2. Avg. Release Rate PCi/sea 1.77Z-01 6.033-01 7.483-01 6.763-01 7.012-01 F. Gross Alpha Radioactivity

1. Total Release ci 0.00+00 O.OOE+00 0.003+00 0.00Z+00 0.003+00

2. Avg. Release Rate pCi/sea ).00Z+00 0.009+00 0.003+00 0.003+00 0.003+00 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment I Page 2 of 9

TABIL 1B ZFIYLUZN! AND WNASTE DISPOSAL ARM=A REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS E.rLIINTS - ELEVATED RELEASES - CONTINOUS MMI Oconee Nuclear Station Units 1, 2, &3 RPORT1 0R 2012 Unit QT1 I QTR 2 QTR 3 QTR 4 YAR

1. Fission and Activation Games ER-133 Ci 1. 643+01 2.29Z+00 0.001+00 0.001+00 1.873+01 Totals for 0ld.... Ci 1630 2.293+00 0.001+00 0.001+00 1.872+01

2. lodines

- Noe Nucl~ide Acotivities 4

3. Particulates Ralf Life >- 8 days

- Noe NUOUid Aictivities **

4. Tritium B-3 Ci 9.593+01 1.332+01 2.663+01 2.601+01 1.62z+02 S. Carbon-14 C-1' Ci. 1.833+00 1.431+00 1.783+00 1.613+00 6.653+00

6. Gross Ai* lad.*~tioa.tivity

N No Nuolide Activities **

Oconee Nuclear Station 2012 Annual Radioactve Effluent Release Report Page 3 of 9

TABLE IB EFFLUEWT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 111112 TO 1/l/13 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE I;

Oconee Nuclear Station Units 1, 2, & 3 REPORT FO 2012 Unit QTRlI QTR 2 QTR 3 QTR 4 YEAR I. fissioc and Activation Gases AR-41 Ci 0. 00o+00 2.753-03 2.469-02 1.273-02 4.003-02 AR-85 Ci 1.273-02 7.289-03 5.841-03 1,293-03 2.71E-02 XR-93M CI 0.003+00 0. 00E+00 0.00E+00 1.473-05 1. 47B-05 X3-133 CL 0.00.,+00 1.623-01 1.32Z-03 4.022-02 2.04E-01 XX-133X Ci 0.003+00 0.003+00 0. 00M+00 7.023-04 7.028-04 ZE-135 Ci 0.003+00 3.909-03 0.003+00 5.30Z-03 9.193-03 Totals fo Pezuwd... Ci 1.27E-02 1.769-01 3.17,-02 6.02K-02 2. 813-01

2. Iodines 0.003+00 0.009+00 1.902-09 F

X-131 Ci 0.001+00 1.901-08 X-133 Ci 0.00K+00 0.003+00 0.002+00 3.043-08 3.04Z-08 Totals for Peziod... CL O.00E+00 0.003+00 0.00Z+00 4.84Z-08 4.843-08

3. PaztIoulatea Half Life >- 8 days

- No Nuolide Activities **

4. Tritium X-3 Ci 1.613-05 2.463-02 4.46E-02 6.41E-02 1.333-01

5. Carbon-14 C-14 Ci 4.27E+00 3.333+00 4.15E+00 3.763+00 1.55E+01

6. Gzoss Alpha Radioactivity

- No Muclida Activities **

Oconee Nuclear Station 2012 Annual Radioacive Effluent Release Report Attachment I Page 4 of 9

TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE I:

Oconee Nuclear Station Units 1, 2, &3 REPORT YO 2012 Unit QTR I QTR 2 QTR 3 QTR 4 TEAR

1. Fission and Activation Gaues

- No Nuclide Activities **

2. Iodine*

- No Nuclide Activities ........

3. Particulate. Half Life >- 8 days

- No Nuclide Activities ** ........

4. Tr;tiLm H-3 Ci 5.33E+00 4. 833400 3.542+00 5.493+00 1.92'+01 S. Carbon-14

- No Nuclide Activities **

6. Gross Alpha Radioactivity

- No Nuclids Activities **

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 5 of 9

TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2012 Utit QTR 1 QTR 2 QTR 3 QWR 4 YEAR

1. rission and Activation gases

- No Nucaide Activities ** P

2. lodines r.

- No Nuolide Activities **

L.

3. Particulate.* Halt Li.f > 8 days

- No Nualide Activities *

4. Tritium E-3 Ct. 0.00K+00 3.403-09 0.00E+00 3.40Z-09 6.901-09

5. Cazbcon-14

- No EUklid. Activities **

6. Gross Alpha Radioaativity

- No R*ulide Activities **

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 6 of 9

TABLE 2A I.

EFFLUE1T AND WASTE DISPOSAL ANNUAL REPORT PERIOD I/1/12 TO 1/1/13 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 1.

REPORT FOR 2012 fnit QTR1I 9M2 QTR 3 QTR 4 YEARR A. Fission and Activatton Products

1. Total Release Ci 2.29R-03 1.475-02 7.13E-03 1.55E-03 2.572-02

2. Average Diluted Conoentration a' Continuous Releases pCi/ml 0.003+00 0.003+00 0.003+00 0.003+00 0.003+00

b. Batch Releases pCi/ml 2.713-10 1.749-09 8.342-10 1.813-10 7.563-10 S. Tritium

1. Total Release Ci 1.512+02 1.903+02 2.548+02 1. 653+02 7.59R+02

2. Average Diluted Conoentration

a. Continuous Releases pCi/zl 3.042-09 2.943-08 3.74E-08 2.66Z-08 3.103-08 bk

b. Batch Releases pCi/ml 1.789-05 2.251-05 2.96E-05 1.923-05 2.23Z-05 C. Dissolved and Entrained Gages

1. Total Release Ci 0.00R+00 0.00z+00 0.003+00 0.00Z+00 0.00Z+00

2. Average Diluted Conoentration

a. Continuous Releases pCi/ml 0.003+00 0.009+00 0.00E+00 0.001+00 0.00B+00

b. Batch Releases pCi/ml 0.003+00 0.009+00 0.003+00 0.003+00 0.003+00 D. Gross Alpha Radioactivity

1. Total Release Ci 0.003+00 0.00E+00 0.00Z+00 0.003+00 0.003+00

2. Average Diluted Concentration

a. Continuous Releases pCi/ml 0.003+00 0.008+00 0.003+00 0.003+00 0.003+00 b, Batch R1lease. pCi/ml 0.003+00 0.0Oz+00 0.003+00 0.003+00

.0.00+00

3. Volume of Liquid Waste

1. Continuous Releases liters 5.573+08 6.083+08 6.25E+08 6.533+08 2.449+09

2. Batch Releases liters 1.033+06 3.143+06 1.463+06 2.443+06 8.07E+06 F. Volume of Dilution Water

1. Continuous Releases liters 8.463+09 8.463+09 8.553+09 9.553+09 3.403+10

2. Batch Releases liters 8.46X+09 8.463+09 8.55E+09 8.55E+09 3.403+10 1

1 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment I Page 7 of 9

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID E17LUENTS - CONTINUOUS MODE I.

Oconee Nuclear Station Units 1, 2, & 3 REPO0T FOR 2012 Unit Q= 1 QTR 2 QTR 3 QTR 4 YEAR

1. Fission and Autivation Products

- Ko N iuclid Activities ** ........ ........ ........ ........ ........

I.

2. Tritium H-3 Ci 2.14E-01 2.673-01 3.43R-01 2.45Z-01 1.133+00

3. Dissolved and Entrained Gases

- No Muclide Activities **

4. Gross Alpha Radioactivity

- No Nuolida Activities **

F Oconee Nuclear Station 2012 Annual Radioactve Effluent Release Report Page 8 of 9

TABLE 2B EFFLUENT AmD WASTE DISPOSAL AMAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID EFFLUENTS - BATCH MODE Oconee Nuclear Station Units 1, 2, a 3 IMPORT FOR 2012. Unit QTR I QTR 2 QTR 3 QTR 4 Tam

1. Fiasion and ActivatLon Products AS-110X Ci 3.621-05 2.353-04 4.071-05 8.463-05 3.961-04 C0-57 Ci 0.001+00 0.00Z+00 3.171-05 0.00g+00 3.171-05 CO-58 CL 1.561-03 1.123-02 4.001-03 1.181-03 1.803-02 CO-60 Ci 4.463-05 1.313-03 7.78Z-04 9' 571-05 2.221-03 Ca-51 Ci 0.001+00 4.49Z-04 0.001+00 0.00R+00 4.491-04 CB-134 C1L 0.003+00 2.70E-05 0.001+00 0.005+00 2.703-05 CS-137 U. 3.765-05 3.433-05 1.25E-05 0.003+00 8.45E-05 M43-54 Ci 0. 003+00 2.64X-04 8.201-05 0.001+00 3.463-04 H1-95 Ci 2.172-04 8. 551-04 2. 603-04 9.763-05 1.439-03 MB-97 Ci 0.001+00 5.689-05 6.81-05 2.822-05 1.53Z-04 88-122 Ci 0.001+00 0.001+00 0.001+00 1.235-05 1.233-05 SB-124 Ci 0.001+00 0.00Z+00 1.01E-04 0.001+00 1.013-04 SB-125 Ci 2.99E-04 8.743-05 1.589-03 0.001+00 1. 961-03 ZX-95 Ci 1.041-04 2.615-04 2.913-05 1.793-03 4.123-04 9R-97 Ci 0.001+00 0.005+00 6.812-05 2.829-05 9.631-05 Vot~als forPzio.. C1 2.29E-03 1.479-02 7.131-03 1.55]E-03 2.573-02

2. Tritium R-3 Ci 1.503+02 1.90E+02 2.531+02 1.643+02 7.58Z+02

3. Dissolved and Entrained Gases

- No NIolida ActLvities **

4. Gross Alpha Radioa*tiv-ity

- No Nuolide Activities **

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 1 Page 9 of 9

ATrACHMENT 2 Supplemental Information to the Gaseous and Liquid Effluents Report Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 1 of 5

Page 1 of 2 Oconee 2012 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 2012 Annual Radioactive Effluent Release Report (ARERR) contains estimates of C-14 radioactivity released in 2012, and estimates of public dose resulting from the C-14 effluent.

Because the dose contribution of C-14 firom 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 (Ref. Reg. Guide 1.21, Rev. 2). The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation (Ref. Reg. Guide 1.21, Rev. 2). Many documents provide information related to the magnitude of C-14 in typical effluents from commercial nuclear power plants. Those documents suggest that nominal annual releases of C-14 in gaseous effluents are approximately 5 to 7.3 curies from PWRs (Ref. Reg. Guide 1.21, Rev. 2). A more recent study recommends a higher C-14 gaseous source term scaling factor of approximately 9.0 to 9.8 Ci/GWe-yr for a 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 2012 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 CVGWe-yr and actual electric generation (MWe-hrs) from Oconee in 2012 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 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 2 Page 2 of 5

Page 2 of 2 an average of 80% organic with the remainder being CO 2 (Ref. EPRI TR-105715). For the Oconee 2012 ARERR a value of 80% organic C- 4 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 fiom airborne effluents released from Oconee~in 2012 is well below the 10CFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit).

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 2 Page 3 of 5

OCONEE NUCLEAR STATION 2012 EFFLUENT AND MASTE DISPOSAL SUPPLEMENTL INORNKTZON I. REGULATORY LIMITS - STATION A. NOBL MU.M - AIR DOSE a. Lx*vxD EMMEMIV - DON

1. CALNDAR U*MER - GlAlS DO*S - 15 MEAD 1. CALENDAR QUARDEUR

- TOTAL BDO DOEM - 4.5 BUM

2. CAZZNAR QZ*tR - BM DOSE - 30 bAW 2. CALENDAR 0AUTR - CRON DO=E = 15 amf

3. CALEDAiR YEAR - GMft DOSS - 30 b9W 3. CALE2DAR YEAR - TOT2,L BODY DOSE a 9 bim

4. CAIANDAR YUER - 33& DOSE - 60 MAD 4. CALENDAR YZAR - ORGAN DM a 30 1EWI C. ICODIE - 131 AN 133, TRITIUM, PARTZCU, T39 W/T 1/2 > 8 DANB - 04M DOSE

1. CALENDAR QUITEER - 22.55ENN

2. CALNDARU YAR - 45 MUM II. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS A. GASEOUIS RDWLDM - 1UPIYZQI POUND = ONWISE DOSS0ANUA CALCULATIN*'

3. LxQm suNE - ONwcTIwYomN 23 10ocR2o, ANPRDDZX a, Z=8 2, COZUM 2 III. AVERAGE ENERGY - NOT APPLICABLE IV. MEASUREMENTS AND APPROXIMATIONS. P.F. TOTAL RADIOACTIVITY, muALsE= or spECIxOc EADZOUmOLE IN SELECTED OR CUON"IYS SUMLES he DESCAIDED DI T811 SmLETED ICNOE CMMUENTS ARE USE TO DETEMIMU KE RADZONUCLIDE CONMOSITION OF THE ENIWENT. A BUMMU DBSCREZDTIO OF am mv "rON FM STEN&TM OVERALL ERZR8 ABSOCTNMD WITH RhDZOACTZVWTr )0ASUMEUMNS I8 PVROVIDED AS PART Or TIE "SUPDIfLzI.AL I1NONNTZIOt" ATTACHNW.

V. BATCH RELEASES A. LZQUID Zh1 .R

1. 9.302+01 w TOTAL NISR OF BACH RVI.EAS

2. 2.002-04 - TOM TIM OMI.) FOR. ,LTC RELEASES.

3. 2.47B+02 - M)t1flOR T'1H5 OM.) IOR1A BATCH RELZASE.

4. 2.15M02 - &VRAE T=* 0 N.) FOR A HAITCM REZLEE.

5. 1.06E+02 - M mZITMU OlIN.) NOR A H*MM RL0E1S1.

6. 1.702404 m AMUA D OrTON W*TER FLOW DURENG rEEASES CO(IO.

B. GASEOUS UFIL0UIT4

1. 4.S03*01 a TOJAL NUMER 01 A.TCH RmRam.

2. 1.233,+05 k TOTAL T, = (M.) lOR BATCH RELEBASS.

3. 3.60B3+04 - bsO TimZ OMIN.) FOR A BATCH suZIAu.

4. 2.73B+03 - AMBADE TI MOM.) ORMA BALCH REEASE.

5. 1.78,+02 - InDA TUDO OMa.) FOR A DANCE RELEASE.

VI. ABNORMAL RELEASES (SEE "UNWPLUANED OEWSITE RELEASES ATIACHIUM)

Oconee Nuclear Station 2012 Annual Radloactve Effluent Release Report Attachment 2 Page 4 of 5

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 -+30.30A This value was derived by taking the square root of the sum of the squares of the following discrete Individual estimates of error:

(1) Flow Rate Determining Devices = *20%

(2) Counting Statistical Error = *20%

(3) Calibration Error = *10%

(4) Calibration Source Error = *2.5%

(5) Sample Preparation Error = *3%

Oconee Nuclear Station 2012 Annual Radioactive Effluent.Release Report Page 5 of 5

Attachment 3 Oconee Nuclear Site Solid Waste Disposal Report Oconee Nuclear Station 2012 Annual Radloadve Effluent Release Report Page I of 14

DUKE ENERGY COMPANY OCONEE NUCLEAR STATION 155 EAST PICKENS HIGHWAY SENECA, S.C. 29672 March 21,2013 Judy Smith Regulatory Compliance

SUBJECT:

Oconee Nuclear Station "Annual Solid Waste Disposal Report - 2012" FILE NO: O8-770.05 Pursuant to Oconee Nuclear Station Technical Specifications 5.6.3, please find attached 2012 Annual Solid Waste Disposal Report for the period JANUARY 1, 2012 to DECEMBER 31, 2012. The format of the attachment meets all of the regulatory requirements for this type of reporting.

Lagrone D. Robinson Radiation Protection Manager HBN Attachments cc: Larry E. Haynes Victor Owens Cad Ingram Clay Lemons Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 2 of 14

OCONEE NUCLEAR STATION ANNUAL RADWASTE REPORT =10=203 DUKE ENERGY Owns Nuclear StlOn SOUD RADtOACflVE WASTE SHIPPED TO A DISPOSAL FACILITY Report Period: January. December 2012 TOTAL Waste Typ NUMBER OF NUMBER OF WASTE CLASS OONTAINER BURIAL VOLUME ACTIVITY SHIPMENTS CONTAINERS A-U A-3 B C TYPE CU. FT. CU. iM. CURIES

1) WASTE FROM LIQUID SYSTEM (A) DeWaterod Podex Reshi 0 0 0 0 0 0 GDP 0 0.00 0,00 (B) Dewatered Primary Resin 5 5 0 0 5 0 TYPE A 601-5 17.03 560.00 (C) Dewatermd Mechanical Filters $8.00 2 0 0 0 2 TYPEA 240.5 6,51

1. Primary Fire' Media 2

2. Secondary Filter Media 1 0 0 0 GOP go 2.54 0.0050 (D) SodMfludoil. lquld, shudge 0 0 0 0 0 GDP 0 0.00 0.00

2) DRY SOUD WASTE 60 GDP 6832.5 193.4A (A) Dry Active Waste - Proessor to Burial 60 60 0 0 0 4.77 Metal. Processor to Burial 17 .17 17 0 0 0 GOP 150628 42.65 0.21 (B) Dry Active Wasge to Burial 1 0 1 0 0 TYPE A 120.3 3.41 0.70 (C) Dry Active Wase Brokered 0 0 0 0 0 0 0.00 0.00 0

(D) Irradlated Components 0 0 0 0 0 0 0 0.00 0.00 TOTAL 98 86 78 1 5 2 9391.23 265.93 618.69 10 0.ý 0 0.

Page lofI

Ocone Nuclear $Waon Annual Report OCONE NUCLEA S1TATION SOLID RADWASTM REPORT RItpaft Poled: Januiny - December 20M Wasse Tw PCwa Raesi SPRI TO W.r0MCARE U 0?sIPLOCISIO DMftOOA TOTAl AVE, S AaUNIAM 11O LOOMS 0.00 0.00 0.00 on 0.00 0.00 Dam MOD 0.00 am #YALUE[

0.0000 DAM 0.00 U.00 0.00 G00 MN-44 0.0000 0.000 0.00 0.00 0.00 m~oo 0.00 0.00 0.00 0.00 0".00 .00 m O.00 a00 0.00 0. 0 4100 am 0,00 0.00 am WVALUGI 0.00 m.oo 0.00 0.00 0.00 0.00 0.00 0.00 0.00 am m.o0 0.00 0.00 0.00 0.00 0.00 0.00 AVALUEI CO.67 0.0000 0.0000 O.CO WYALUEI C0458 0.0000 0.00010 0.00 0.00 0.00 0600 0.00 0.00 0.0) 0.00 OA0 0.00 "ao am DADmoo. 0.0 0.00 a0.0 0.00 0.0o O.00 0.00 0.00 m.oo 0.00 0.00 DAD am 0.0 0.0 0.00 0.00 0.00 0.00 0.00 UJALUEI 0.0000 0=0010 0.00 am 0.00,

.AOO 0.0000 0.00 000 0600 ao~o 0.o0 0=0 0.00 0.00 0.00 Oam am am Dam am0 0.0 0.00 0.00 0.00 0.00 OVALLE]

0.0000 0.00 0.00 0M0 n.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 0. 0.00 0.00 0.0000 0.20 am 000 0.00 0.00 0.00 0.30 WALUME 0.0000 DAM00 0.00 0.00 000 o.00 0.00 am 0.00 0.00 0.00 0.00 0.00 0.0 0.0 C"-34 RU-IOU 0.0000 0.0000 0.00 0.00 0.00 0.00 Moo 0.00 0.00 OAm 0.00 am 0.00 0.00 m.00DAm 0.00 0.00 0.000.00 am 0.00 NVALUSI 0.00 0.00 0.00 am 0.00 0.00 O.00 AG-li0m 0.0000 0.0000 0.00 0.00 O.O0 0.00, 0,00 am 0.M0 0.00 0.00 #YALIJEI 0.00 OMO 0.OO 0.00 0.00 am 0.00 om 0.00 o.1D 0.00 0.00 o,<m oaoo oLUo 0.00 0.00 0.0000 0.00001 0.00 0.0o am 0.00 0.00 OVALUEI 1-131 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 Oam 0.00 0.00 aW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 am 0.00 WVALUEI:

am 0.00 O.00 0.00 0.00 0.00 0.00 0.00 0am ooam 0.00 D o.0o 0.0000 0.000 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 moo 0.00 NVALUM H-3 0.0000 0.0000 0.00 0 0.00DA 0.00 am 0.00 o.00 0=000 0.00 0.00 0.00 am 0.00 am 0.00 an 0.00 000 0.00 am 0.00 DAD 0.00 a.m0 0.00 0.00 0.00 WALUEI NI-O 0.0000 0.000 0.00 0.oo am 0.00 0.00 0.00 0.00 0.00 am am0.00 "o 0.00 0.00 o.00 OVALUE1 FE-US 0.0000 0.00 amo 0.a0 060W 0.00 0.00 am 0.00 omo 0.00 moo BR-90 0.0000 0.00 0.0M 0.00 0.00 0.00 0.00 0.00 0.00 0.00 o.0 0.0 am 0 0 0.0 #VALUE1 0.0000 0.0000 am 0mo 0.0m 0.00 0.00 am 0.00 0.00 OO 0.00 0.00 0m00 0.00 0.00 0.00 a.m o.oa o 0.00 omo 0.00 ao~o TE-I25M 0.0000 0.00 0.00 0.00 fVALUE1 0.0000 0.00 O.00 0.00 0.00 Oam 0.00 0.00 0.00 0.00 0.00 0a 0.00 0.0m am CS-135 0.0000 0.000 0.00 am 0.0o am 0.00 on am 0.00 0.00 0.00 0.00 0.00 0.00 0.00 am 0.(00 0.00 0.00 NVAWE!

XE-133 0.0000 O.00 am am 0.00 C-14 0.0000 0.000 CLO0 am 0.00 0.00 ojoo 0.00 0.00 0.00 am 0. 0.00 0. 00 0.00 0,00 0.00 am 0.00 o.00 UJALUEJ 0.o0 0.00 0.00 ODAD oa0a 0.00 PLO-241 0.000 am o.0 O.00 on 0.00 0.00 0.00 0.00 0.00 0.00 am tom om DA OVALUSI 0.0000 0.000 0.00 0.00 0.00 CLOD 0.00 am am 0.00 0.00 0.00 am DAm 0.00 0am 0.00 0.00 am .00 0.00 0.00 0.00 EVALUEI 0.0000 0.00 O.00 0.00 0.100 0.00 0.00 0.0000 0.00 0.00 GaO am0 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0JALUE1 am on 0.00 0.00 am0 0.0000 0.00 amO am 0A. 0.00 0.00 0.00 0.00 0.00 S9-124 0.0000 Gam00 0.00 0.00 O.OO 0.00 0.00 Oam 0.00 am 0.00 0.00 0.80 am 0.00m~oo0.00 DAD 0.00 0.00

VAWUEI RU-105 0=01)0 0.00 0L00 0.00 O.m 0.00, 0.00 MIALUEI 0.0000 0.00 0.00 0.00 .00 0.00 0.00 m.0o 0.00 000 am 0.00 0.00 0.00 CE-I44 0.000 0.00 0.00 0.0 O'O 0.00 am0 on DAD 0.00 O.OO 0.00) OVALUBI TE-132 0.0000 0.0000 0.oo am0 0.00 0.00 0.00 0.00 0.00 0.0 0.00 0am 0.00 am 0.00 0.00 0.00000 DAD0 0.00) O.00 0.00 am 0.00 0.00 0.00 0.00 0.00 0.00 am AM-341 a.0000 0.LO 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.30 #VALUEI TOTAL 0 0 0 0 0 0 0 0 0 0 a a 0 0 0 0 0 0 a0 0 a 0 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 It 0 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 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 a 0 0 0 0 0 0 0 0 0 0 0 a CURIES 0 CU. FT. 0 0 0 0 0 0 0 0 0 0 O 0 0 0 0 0 0 0 0 0 0 0 Z0-0 0 0 0 0 0 0 0 0 0 0 CU. M a 0 0 0 0 0 0 0 O 0 0 0 RSM a"

Page 1 of I

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOUP RADWASTE RORT Re Petlod: JunuWy - December 2012 Was%h1 Pft- Red aOFouwu SHIPPED TO CNsI 5 t607003 ASUNM1*CMCWFS OF SWIPMEIWS1 TO 0345 5 YOWL AVE.

AG-110m 02614 0.0000 0.1048 0.0370 0.1115 0.0000 0.0000 00.000 0.0000 0.0000 0.0000 o.0oooocoso 0.-00Q 0.0000 0.00030.0000 0.0000 0.0000 0.0000 0.5147 0.1029 AM-241 0.0001 0.0000 000000 .o.ooo 0.00000.O0OO 0.000O 0.0000 0.0009 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0004 0.0001 Be-7 0.0000 0.1902 0.ooo0 0.0aoc 0c0000 0.OOOO 01o0 o a.Oco o.cc0o Mo o.Oco 000.000 0.0000 0.0000 0.0000 0.OOO0 0.0000 0.0000 0.00 O 0.0000 0.1902 0.0360 C-14 0.8192 0.0000 0.1032 0.0737 0.3336 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 o.011 000 0.0000 0.0000 0.0000 O.0000 0.0000 1.3297 0.2659 CE-144 0.0oM 0.0518 0.0411 &.0054 0.0052 0.0000 0.0 000 0.0 0.000 0.0000D 0.0000 0.00000.00000.0000 0.001D 0.00oo0.0000 0.0oo0 0.0000 0.0000 0.1525 0.0M05 000 CM4242 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.o0oo 0.0000 o 0.oooo 0.oooo 0.o01c1o.oo 0.0002 0.000o CM-243M4 t.o003 0.cacO O0.oo0 O.noo 0.0000 0.000o 0.0000 0.0000 0.0000 0.0000 0.0.(0 0.0000 0.0000 0.0000 0.oooo 0.0000 0.0000 0.0000 0.0000 c.o00s O.oo01 Co-87 0.3508 o.e7 o.702o 0.2467 0.3566 MOND 0.0010 0.00100 cocA oc 0.000 0.0000 0.0000 0M0000 0.0000 0.0000 0.000o 0.0000 0.0000 0.0000 2.1306 0.4252 CO-08 44.2268 5.1954 19.5159 6.9737 10.4918 0.0000 0.0000 0.00100 0.0000000000 00000 0.00 000 .0000 0.0000 M0000 0 0.0000

.0.000 0.0000 0.0000 0.0000 140.4034 23.0807 C0-60 &1801 1.9195 3.6762 I.52=3 23115 O.000D 0.000 00 0.0000 0.0000 0.000 0 0.0000 0.0000 0.010 0.0000 0 0.0000 0.0000 0.0000 0.0000 0.0000 12.6143 2.5229 CR-6S 0.2919 0.0000 0.0000 0.o1oo 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.00000.0000 0.0000 0.0000 0.0000 0.oooo 0.0000 0.0000 0.2019 0.0584 CS-134 102832 &1494 7.0348 1.729 4.863D8 .00 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 0.00 27.3143 5.-529 CS-6IS4 0.0o00 0.oo 00110 0.00 0.0000 0.0000o.oooo 0.0000 0.000o 0.0000 0.0000 0.0000 0.0000 0.0000 0.0o0 0.00010 0.0300 0.0000o 0.00010 0.0000 MOo 0.0000 c8.137 12.6707 4.7989 11.0136 455B U.4428 0.0000 0.0009 0.0000 0.0000 0.0000 0.0000 0.0000 cOOOO 0.010 00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 41.600S6.3001 FE.55 6.9107 4.1609 113152 14"342 21.1476 0.000 000 0.0100 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0900 0.0000 61O4685 12.493 FE-SO to.9 0.0000 0.0000 tO 00.0 O0 0.0000 0.0000 0.0000 0.0000 0.0000tO 0.00000.0000 0.0001 0.000O0.0000 0.0000 0.000 0.O00 0.33 M0000 MO.066 0.0000 M-S 0.0000 0.02"7 0.0043 0.0048 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.00 0.0000 0 0 0.0000 0.0000 0.0000 0.0000 0.0000 0.0868 t0074 1-129 0.0000 0.0000 0.0006 0.OO01 0.0003 0.0000 0.00 0.0000 0.0000 0.000 0.0000 0.0000 0.0000 0.0000 0.0010 0.0000 0.0000 8.00 0.0000 0.0000 0.00 00101 9.151 o.oooo ca3ao 0.0ooo acorn 0.0000 0.00o0 00000 0.0000 0.0000 0.0o10 0.00o0 0.0000 0.00o0 DA0 0.0 0.0000 0.0000 0.0000 010 0,o000 0..000 0.ooo0 o0.000 MNM84 Oie98 0.6724 I.0107 0.3*49 0.410 0.0000 0.0000 0.0000 0.0000 0.0000 0.00O 0.0000 0.M0000.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.O000 34878 0.6938 NO-05 0.8039 0.0356 0.000 0.0000 0.0000 0.0000 0.00 0.00 0.O 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.8394 0.1679 N4 0.0639 02eW 0.2481 04342 0*7S 0.0000 0.00oo0.000.0000 0.0o00 0.0001 0.0000 0.0000 03000 0.0000 0.0OO0 0.0000 0.0000 o,oooo 0.0000 1.4246 0.2549 N1483 16.2527 25.0L7S 42.139 67.7832 51.1475 0.0000 0.0000 0.0000 0.0000 0.0 0.0000 000 0.0000 0.0000 0 000 0.000 0.0000 0.0000 0.000, 0.0000 203.0348 40.6070 U000 PuI-r2 0.0002 0.000 0.0000 0.000 0.00o4 0.0000 0.0100 0.0000 0. 0000 0 to 0.000 ON 0.0000 0.000 000U000o t s oooo c.ooo sooco 0.0000 cooo o.ooo2 0.00000000 Pu-23ww 0.0001 0.000c 0 c o0co.ooo 0o00 o 0.0 0000 0.0000 0.0000 0.0os 0.0000 0.0000 o0o000.0000 0.0000 0.0000 0.00000.0000 0.oooo 0.0000 0.0000 0.0001 0.0000 PU-241 co.ooo o.ooo 0.0000 0.0000 0.0o000.0000 0 .0000 0.0000 0.000 0 0.0000 0.000 0.00000.0100 o.oooo 0.0000 0.00oo 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 RU-106 0,0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 0.00 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 t 8B-124 0.0000 0.0000 0.MO00 0.0000 0.0018 0.0000 0.0000 0.0 O0 0.9000 0.0000 0.0000 0.0000 0.0000 0.000 0=000 0.0000 0.0000 0.0000 03009 0.0000 03*018 0.O004 a 88-125 0.0000 0.0000 0.1751 0.0504 0.0766 0.0000 0.0000 0.0000 0.0000 0.0000 0.000 0.000D 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 03000 0.3024 0.0605 8W-113 SR-SB SR.00 0.0000 0.0116 0.0115 0.0000 0.0002 0ao.o0 sc0con 0.0046 0.0281 0.oo46 0.032 oo 0.002 oao 0.0000 0.0000 0.oooo 0.0000 0acos 0.0000 0.0000 otococ 0.0000 0.0000 0.0000 000 0.00 00000 0.0000 000 0.0000 0.000 0.01aa o.0s caa00 0 0.0000 0 .0000 .0000 0.o00 c 00000 0.0000 0.0000 0.0000oo 000.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000

.00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0238 0.1192 0.0000 0.0047 0.0238 I

m TC-09 0.0088 0.003 0.0042 .0026 0.0013 0.0000 0.00cacaoc00 O.0o0ac 0 0.0000oo .taos0.0000 oDo 0.0000 0.00M 0.0000 0.o0o 0.0000 0.0000 O.(208 0.0042 TE-12Sm 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 03000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 C S

XE-133 0.0000 0.0000 0.0000 0.0000 O.aoao M000 0.0000 0.0000 coon cows o. oooo 0.0000 c.00a0.000co 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 ZN445 0.2309 0.0254 0.0577 0.0224 03203 0.00100 0.0000 0.0000 0.0000 0.0000 0.0000 0.00(0 0 000 0.0000 0.000 0000 0.0000 0.0000 5 0.0000 0.0000 0.3587 0.073? Lu ZR-9S 0.4841 0.0000 000000 0.0000 0.0000 0 0.000c 0.00o0 0.0000 0.0000 oo0000 0.0000 0.0000 t.ome 0.0000 oa 0.0000 0.0000 0.0000 0.0000 0.4641 0.0928 TOTAL 99.86 100.00 9. 99.85 100.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000.00 0.00 0.00 to 0.00 409.68 99.93

.11 CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS I 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 z C CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 , 0 0 0 0 0 0 0 0 g.~ E,~,

C eq 0 CURES 45.9 174 36.1 152 122 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 560 8;3 S' ON 'C0.

Page I of 2

Oconee Nuclear Station Annual Report 0 0 0 0 0 0 0 0 0 0 0 0 eaS CU.T. . 120 12. 120 120.3 120.3 0 0 0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 I100 0.00 0.00 0.00 0.00 17.03 CU. H 3.41 3.41 41 41 3.41 0.00 0.00 RNSI 12.,200 12-2014 1242041 12-2044 12,-204

'p.

CLu 013 z

aD C%LU Page 2 of 2

Ocone Nwulear Stdion Annual Report OCONEE NUCLEAR STATION SOLID RADWASIE REPORT Report PrWod: January- Decmber 212 WWM Tpm Pmrwfam.

0 0F ORUMBUNERB TO CNt 2 r TOT.L AVE.

ISOTOPE

OF SHIMMETO CIO 2 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 a.047 AG-il Om 0.00020 0.00 0.00 0.00 0.00 0.00 0.00 0.003 0.00 0.100 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 AM-241 0.00050 0.01 0.00 0.00 0.00 0.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 0.000 BA-i 40 0.00000 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.MO 0.00 0.00 0.00 0.00 2.66 1.273 C-14 0.O8770 246 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CD-109 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 o0 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CE-141 0.00000 0.00 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 0.56 0.282 CE-144 0C1210 0.06 0.00 0.00 0.00 0.00 0OO0 0.00 0.00 0.00 0.00 0.00 0.00 0M0O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CM-242 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CM2344 0.00070 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 0.00 0.44 0.221 co-57 O.40190 0.04 0.00 0.00 0.00 too 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 30.56 1,278 CO-611 30A487O 0.09 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 0.00 0.00 0.00 0.00 0.00 0.7880 4.10400 CO-80 &.13080 4.86 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0;46 0.223 CR-5i 0.44680 0.00 0.00 0.00 0.00 0.a0 0.00 0.00 0.00 0.00 ,0 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 17.10 8.649 CS-i34 10.72007 0.37 0.00 0.00 0.00 0.00 0.00 0.00 0.(00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0oo0 0.00 0.000 ce-las 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.O0 o.00 0.00 0.00 17m.5 8.776 CS-137 1iL82240 0.73 0.00 0.00 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 82.O5 41.023 FE-35 3.79440 78.25 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 0.00 0.00 0.00 0.029 FE-59 0.06790 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 2.72 1.361 H-3 2.71980 0.00 0.00 0.0o 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0. 0.00 0.00 0.00 0.00 0.00 0.00 0.00 am00 0.000 140-203 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 O00.00 0.00 0.04 0.021 1-129 0.00000 0.04 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 1.18 0.689 MN444 0.97200 0.21 0.00 0.00 0.0o 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MO00 0.00 0.00 o.00 0.00 O.00 0.00 0.00 0.000 NS-94 0.00000 0.00 0.00 0.00 0.00 O.00 0.00 0.00 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2.31 1.164 Ns-US 2.3080 0.00 0.00 MO00 0.00 O.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 0.013 141-11 0.O2600 0.00 0.00 0.O0 0.00 0.00 0.00 0.00

.O00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2V.76 13.8682 mm14 W1.14020 1822 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 o.00 0.00 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 PU-238 0.00080 0.00 0.00 MO00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 PU-m3 0.00030 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 .D0 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.001 PU-24i 0.01790 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.O0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.000 RU-1 03 0.00000 0.00 0.00 00oo 0.00 0.00 0.00 0.00 0.00 o,00 0.00 0.00 0.O0 0.00 0.00 0.00 0.00 0.00 0.0 0.00 0.001 RU-i05 0.00220 0.00 0.00 0.0o 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.0O 0.00 0.00 0.00 0.00 0.000 SB-124 0.00000 0.00 0.00 M.0O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.000 S13-125 0.01750 0.00 0.o0 MO00 0.00 0.00 0O00 .00 0.05 0.00 0.00 0.00 0.00 0.0O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.001 SN-it3 0.00000 0.00 0.00 o.n0 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 0.00000 0.0000000 SR-89 0.00000 0.00 0.00 0,00 0.00' 0.00 0.00 0.00 0.00 0,00 0M00 0.00 O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.006 0.003 SR-90 0.00560 0.00 O.00 0O00 0.00 0.00 0.00 0.00 Lu 0.00 0.00 0.00 0.00 0t00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.1097 O.O6486 TC-99 0.00020 0.11 0.00 0.00 0.00 0.00 0.00 0.00 OA, 0.OO 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 0.00000 TE-121,n 0.00000 0.00 0.00 o0.n 0.00 0.00 0.00 0.00 0.00 0.003 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.0000 0.00000 XE-133 O.00000 0.00 0.00 0.o0 0.00 0.12075 0.00 0.00 0,00 0.00 0.00 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0oo0 0.2636 ZN-GB 0.20M0 0.04 0.00 MOO 0.00 0.00 0.00 0.00 0.00 0.00 O,00 0.00 0.00 0.00 MOO0 0.00 0.00 0.00 0.00 0.00 4.3227 2.16135 ZR-05 4.31780 0.00 0.00 0o00 0.00 0.00 0.00 0oo0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 199.97 99.96 TOTAL 100.19 90.78 0.00 0.00 0.00 0.00 0.00 uj Z -

Page I of 2

..................... .' .:*; ... * *----v*

Oconee Nuclea Staon Annual Report CLA8 C I 1 0 0 0 0a 0 0 0 0 0 0 0 0 0 0 0 0 0 2 CLASS 8 0 0 a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CtLASS A a 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 a 0 0 0 0 0 0 0 0 a 0 0 CURES 10.7 4Z.3 0 0 0 0 a0 0 0 0 0 0 0 0 0 0 0 a 0 53 CU. FT. 120.3 120.3 a 0 0 0 0 0 0 0 0 0 0 0 0 0 a 0 0 0 240.0 CU. M 3.400581 3.406581 0 , 0 0 0 0 0 0 0 0a a 0 0 0 0 0 0 &013162 ROWN 124m0;0 12-2008 ti ca Ir z

'D r=O Vqf Page 2 of 2

Oconiee Nuclear StatIon Annual Reorat OCONEE NUCLEAR STATION 80I0 RADWASTE REPORT Rpow Padod: Jnmmy - Dasmubew 2012 WaWs Type: OAW to Prmegor f OF SHIPSIENTS FRO ON$ TO ENERY SOLUTIONS 81 # OF CONTAINERS FROM ONS TO ENERGY SOLUTlONS of S OF 81HP11T FRM PROCESSOR TO CUVE D0 0 OF CONTAINERS FROM PROCESSOR TO CLI9 so I OF SHIPMENTS FROM PROCESSOR TO BARNWELL 0 0 OF CONTAINERS FROM PROCESSOR TO BARNWEL 0 CU. FT.. CURES CU. FT. ODPOSAL 0TO ISPOSAL MRS SOHIPPED SHIPPED FACILITY FACLITY 11-2030 0 0 111.3063 3.04E+00 11-2041 0 0 30.3 4.94E-01 11.2054 0 0 141.24 0.005187 11-2057 0 0 73.18671 0.017128 11-2063 0 0 0.340 0.O0003 11-2064 0 0 17.271 0.00556 11-2065 0 0 12&,714 0.01321 12-2002 1888.8 0.0*85 174000 0.03$53 12-2003 1068.8 0.0016 170.8'7 0.00183 12-2004 1868.6 0.0118 25.004 0.00125 12.2000 1471.4 0.0024 184.114 0.00666 12-2007 684 0.0009 0.000 0.01000 12-2008 684 0.0008 42.714 0.00018 12-2013 1868.8 0.0033 206243 0.00326 12-2016 934.4 0.0008 200.643 0.00356 12-2016 199.4 00034 281.300 0,00495 12-2017 1668.8 0.0091 145.810 0.00788 12-2013 1688.8 0.0011 165.500 0.00075 12.2021 486.5 0.0019 468.500 0.00190 12-2023 1888.8 0.0121 190.571 0.01196 12-2026 1866.8 0.0285 128.929 0.01345 12-2=27 1888.8 0L0708 244.429 0.07060 12-2029 1846,8 0.0719 292.000 0.07193 :

12-2030 1888.8 0.407 210.000 0.027611 12-2031 158.08 0.0166 334.000 0.01618 12-2034 1868.8 0.0243 243.094 0.02060 12-208 tm.8 0.CAM7 9.420 0.00738 12-2037 9344 0.0005 380.446 0.00134 12-2042 1888.8 0.0463 318.571 0.04532 12-2043 1868.8 0.03"7 329.786 0.03757 "6 12-2047 1425 0.0080 174.643 O.0D048 12-2048 18888 0m0o8 2M1.343 0.03749 12-2040 1888.8 0.0263 231.571 0.02007 12-208 188MS 0.5020 17I.800 0.34023 12-2052 1868.8 0.031S 192.571 0.03147 12-2053 1868.8 0.0072 0.000 0.00000 12-208 1888.8 0.1760 206.8W7 0.17638 12-2080 1868.8 0.18 .. 250.200 0,17790 TOTAL 51201.5 1.482 683.s5 4.77261 TOTAL CURES BURIED 4.T7- E., -

TOTAL CUBIC FEET BURIED 6832.65 TOTAL CUBIC METERS 193.4f Pagl I of 2

Oconees Nuclear Station Annual Repoit OCONEE NUCLEAR &1ATION SOLID RADWASIE REPORT RepstPtdodLJIm3yr .Decembr 2012 Wut TVyp: DAW to Buwll 0 OF SIIPMENTS FROM GNS TO CNII 8 OF CONTAINERS FROM ONS TO CNN 12-2019 120.3 0.690 0 1 0 0 0 0 0 a TOTAL 120.3 0.699 0 1 0 TOTAL CUBIC METERS 3.41 0"C:4 Z 0 E

C3N Page 2 of 2

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Repmt Plodt Janunay- Decomber 2012 Wabs Type: Ilubi 0 OF SMISSTSTO PROCESSOR 2 OF SIR 17.

OF CONTAIDRSTh PROCESSOR 2 FCOF MUM~STO CLIVE: 17 DECONIOISP. CU. FT. CUREIS CU. FT. TO CRIREST(

FACILITY TO PROCESSOR TO PROCESSOR DISPOSAL FACIlITY DISPOSAL FACILITY BI 11-2040 0 0 0.08 2.00E4.46 11-2049 0 0 1A2057 3.171 11-2054 0 0 722851 1.22E 112055 0 a 163.9 0.Me11 as 11W2057 0 0 295.0143 0.182618 11-2063 0 0 2892533 7.51E-0 12-2004 0 0 17.6 1.31E.0 12-2007 0 0 26L3334 6.71E.

12-2008 0 0 173.163 6.271.0 12-2013 0 0 0.010131 7.00E-0 12-2015 760 M.OM791 020362 6.00E.0 .4 12-2018 0 0 6.77E.01 3.25E-09 12-2023 0 0 17.A671 1.30F.0 12-2030 0 0 79.14286 t.$1E-0 12-2034 0 0 44.78571 8.6E.-0 120w 856 85E.04 14.42B67 4.54E-0 I

TOTAL 1815 0.008773 1508.2 0.2111t TOTAL CUBIC METERS 42.59 I1 ID Oe'(0 Page I of I

Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOUD RADWASTE REPORT Report Putlo: Jammy -.bmacaW=012 Waste "lypr.tIadlad Comupaswit

OF CON"AMMn_ G4rPED TO CNIIDURATEK 0 40OMPt % AIOANCEIAHER 9 OF OIPMERTI TO CNM81URMEK 0 TOTAL VE, G-h110M 0.00 0.00 0.o0 0.00 0.0[0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 OMO 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 fSIVJOI C-14 0.00 0.00 otoo 0.00 0.0 0 0.00 O.OD 0.00 0.00 0.00 CLOD O.OD 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIVMI 0.00 0.00 0.00 0.00 0.00 0.00 0.00 XCIVAI CE-144 0.00 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 CM.242 0.00 0.0o 0.00 t~oo 0.0 O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0100 otoo 0.00 0.O0 0.00 XDIVIl 0.00 0.00 O.OO 0.00 MOO0 0.00 0.00 #DIVAIN CM-243 0.00 0.00 0.00 0.0O0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 0.00 0.00 0.00 0.00 0.00 #DIVANI CO-58 0.00 0.00 0.00 0.00 0.00 O.OOICIVAII 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ODIII 0.00 0.00 0.04 0 0.00 0.00 0.00 0.00 0.00 0.00 0oo 0.00 0.00 0.00 CR-51 0.00 0.00 0.00 0.00 0.0O0 0.00 0.00 0.00 0.00 0.00 0LOD 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MO.O 0.00 0.00 #DIVIOI 0.00 0.00 0.00 M.OO 0.00 0.00 CS-134 0.00 0.00 0.04 0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 O.O0 0.00 0.00 0.00 0.00 #OIVI0I 0.00 0.00 0,00 0.00 0.00 0.00 0.00 #DOIP CS-138 0.00 0.00 0.010 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.O0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 IolIvtI CS-137 0.00 0.00 0.00 0.04 O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.010 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #MIVDO 0.00 &o~o 0.00 FE-,O 0.00 0.00 O.OO 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0 0.00 0.00 0.00 0.00 CL00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #IMVOI M-3 0.00 0.00 0.00 0.04 0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ICIVAII 0.00 0.00 0.00 1.181 0.00 0.00 omoo 0.00 0.04O 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 #OIVIOI 0.00 0.00 0.00 MN-,54 0.00 0.00 0.00 0.04 0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 IOMNOl N64164 0.00 0.00 0.00 0.00 0.00 0.01 00.00 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 o.00 0.00 ONVIOI 0.00 0.00 o.00 0.00 0.00 0.00 0.00 0.00 O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DN0 I NI..O9 0.00 0.00 0.00 0.00 0.00 0.00 o 0.00 O.O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 o.00 M.OO 0.00 O.0 0.00 0.00 I01VIOI 0.00 0.00 0.00 0.00 0 a.0 0.00 0.00 0.00 0.00 0.00 0.00 O.OO 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00o tOIVIO 0.00 0.00 0.00 PU.-241 0.00 0.00 "0a.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 iDIVIOI 0.00 0.00 O.00 0.00 RU-103 0.00 0.00 0.00 O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 M.0D 0.00 o.0o #OWMI!

0.00 0.00 0.40 0.00 0.00 0.00 0.00 ICINiOl RU-1O0 0.00 o.00 0.01 O 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0o 0.00 0.00 0.00 38-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00

( 0.00 0.00 0.00 CLOD 0.00 0.00 M.OO 0.00 0.00 0.00 0.00 0O00 #DMIOI 0.00 0.00 0.00 0.01 0.00 0n00 0.00 S13.125 0.00 0.00 0.00 t 0.00 0.00 0.00 0.00 0.OO 0.00 0.00 0.oo 0.00 0.00 0.00 0.00 0.00 1=1001 0.00 0.00 0.00 0.00 TA-162 0.00 0.00 0.00 0.00 0.000 o 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 #1DIVJOI TE-125rn o.0o 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #ODIOV 0.00 0.00 0.00 tOO O.DO0 SDIVAHl TRU 0.00 0.00 0.00 0.00 0 0.00 0.00 0.00 0.00 0.00 0.00 O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 XE--13 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 0.00 O.00 0.00 0.0000 #DIVIO 0.00 0.00 ZR-95 0.00 0.00 0.000 0.00 0.00 0.00 mo00 0.00 0.oo 0.00 0.00 0.00 0.00 0.00 M.0OO#MANOI 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 00 0.00 0.00 0.00 0.0 00 0.00 l00001 CLASSC CLASS8 CLASS AS 0

0 0

0 a

a 0

0 0

+ia C CLASS AU 0 0 0 0 0 0 0 0 a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 cu. F.* 0 o U 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 cuI. M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 RSR#

0 0a.

Page of I

Oconm Nuclear Station Annual Rep ODWWS 5TA110t SOUD RADWASTO REPORT

.UCLEAR RwOMPod. Jximy"-@ neb 2012 cOP OaffMNEfia U lT0D*IA ** OF cOmr4ITAR WPM TOCNINCffOCORE 0 IOF SOP M TOOURATlK 1 OOF ShMoIUN TO CNWIVIENUAW.CR 0 TOTN. ANE.

0.0 O 0.00 0.00 . .00 0.0 0.00 0.CO 0.00 0.00 a0 0.00 00 000 0.00 0.00 AC-lOnei 0.C0 0.00 0.O0 0.00 0.00 0.0 an am mo0 0.0 mo0 000 00 .0 0.00 0.00 0.00 0.00 00 0.77 0.7y AC-1l1M 0.77 0.00 0.00 0.00 am ROD 0.00 0 . 0.00 .00 o.00 0.00 0.00 0.00 0,0o 0.0o 0.00 0.00 0.00 0o.

AM**41 0.00 0.00 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0O. 0.00 0.00 0.00 2.06 9.96 0-14 2.s. 0.00 0.000 0.

&0 0.00 0.00 0.08 0.0m 0.08 0.00 0.00 R0O .0.00 0.00 0.00 0.0 0.00 0.00 0.00 0.00 o0.0 0.00 0.00 0.00 CE-144 0O. 0.0O Q0.

0.0 0.0a 0 0.00 0.00 O. 0.00 0.0 0.00 GLOB o.00 .00 0.00 .00 0.00 0.00 o .00 0.00 CM-242 0.00 0.00 0.00 0.00 0.00) 0.00 .0 0.0 0. 00 0 0.0 0.00 00 00 o.00 mo0 0.00 0.0o M-M 0.00 0.00 0.12 0.00 0.00 0.0 0.(0L 0 0. 00 000 0.00 00 0.00 O.00 o.0 0 0.00 0.00 0 0.00 R 0.00 00o 0.0 0.12 0.12 00-7 1.24 1.24 124 . 0.00 o 00 0.00 0.00 0.00 0.00 0.00 0 .O0 0.00 00 0.00 R0.0 0.0o 0.00 0.O0 co-00 C0D 2 0.00 0.00 ano o.0 0 0.0 0.00

& .00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 0.0 0o 0 0. 0.00 0.0O 2.8 2.59 RO 0.0 0.00 0.00 O0 0.0 020 (L00 0.0 mo0 0.00 0.00 0.0 0.00 0.00 0.00 0.00 CR61 0.00 0.00 0 0.00 00 O0 0.0 0.00 0.00 0.00 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.10 CS-134 0.10 0.0 0.o00 a0 C0-136 0.00 I00 0.00 0.00 R.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.0a 0.0R 0.00 CR

0.00 0.00 00 0.00 0.00 0.00 0.00 0.00 000 0.00 am0 0.00 0.00 0.0 0.00 0.00 0.RO 0.D 0.00 0110 0.00 0.R4 M04 C0-137 0.64 R00 0.00 64 6.64 F-S 0.6 0.00 0.00 0.00 0.00 am O0 RD 0 0.00 RO 0m a.0 0.00 0.00 0.00 0.00 0.0. 0.00 0.00 0.0O 0.00 0.GO 0.00 0.O0 ROD 0.00 0.00 0.00 0.0 o00 0.00 0.00 0.00 0.00 000 0.0 0 0.00 0.D RO0 770 00.00 0.0 0 0. 0.00 00 0 . 0.00 0.00 m00 0.00 0.0O 0.00 0.00 0.00 0.00 RO 77.00 7.0 I-3 0.00 0.00 O0A 0.00 0 1-151 0.R0 0.00 0.00 0.00 am0.00o 0.00 0.00 0.o00 020 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 00 0.00 0.00 00 0.00 0.00 0,00 0.00 0.00 0.0O 0.00 0.00 0.00 0.00 0.32 0.32 IM-54 0.x 0.00 N54-05 0.00 0.. moo 0.00 0.0 0.0 0.00 00 0 0.00 m0.0 0.0 0. 0.00 00 0.0 0.00 0.00 0.00 0.00 1M1,63 &20 0.00 0.00 0.00 0 0 0.00 0.00 0.00 0.00 0.00 "0.00 0.00 0.00 0.00 0 0.00 0.00 0.00 320 3.&2 PU-235 0.0 0.00 0.00 0.00 0.0 0.0 0 0.00 00 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 0.00 0.0 0.00 0.00 0.00 0.0 0.00 0.00 0CA00 0..00 0.00 0.0o 0.00 0.00 0.00 0.00 0.00 0.00 0m00 0.00 0.00 P0.0 0.00 0.00 0.00 0.00 0.00 0.00 PU-241 0.00 0.00 0.00 0.00 0.00 ROD00.00.00 0 00 0.00 0.00 0.0O 0.00 0.00 a0 00 0.0 00 0600 0.00 0000o0.0 00 0.00 0.0 moo EL0 00 00 0.00 0 0.00 0.00 0.00 0.00 RU-103 0.00 O.0 0.42 0.42 RU-10W 0.42 0.0 0 D 0.0 0 D o.0 . 0.& 0.00 M0.0 0.00 0.00 0.00 o.00 0.00 0.00 0.00 0.00 Q 0.00 0.00 0.0 0.00 0 0.00 0.0 0.0 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3-M124 0.00 0.00 0.00 83-126 2.20 0.0 0.0 0.00 0.a0 0.00 0.o0 0.OD 0.oo 0.00 0.00 0.00 0.0o 0o2 0.00 0.00 0.00 0.0O 0.00 0.00 0.00 ROD o 0 0.00 0.0 0.oo 0.00 C0 0.o0 o.0 00o .00 0.00 0.00 0.00 0.00 0.00 0.00 R-8 900 0.00 0.00 0.00 0.00 0. C.L0 0.00 too 0.00

&M0 0.00 0.0 0.00 0.00 0.MO 0.O 0.00 CLO0 BR-0 0.0 0.00 0.00 0.00 0.00 .

IN-125 0.00 0 RO0 0.00 0.00 a 00 0.00 .00 0.00 0.00 0.0 0o00000.00A.M0 0.00 0.00 0.00 0.00 0.00 L0 0 0.000 0.00 0.0 0 0.0 0 0CA 0.00 00 0.00 0.00 0.00 0.00 0.00 0.00 00 TNJ 0.00 0.00 0.00 0.00 0.00 0.00 am (L00 DAD 00 am am DA 0.00 0.00 0.00 0.00 0.0 0.OD 0.00 MO00 XE-13S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.00 . 0.1 C

S0.1S 0 0.0 0.00 0.00 0.00 0.00 0.00 0.0O 020 G0.0 0.00 10.00 0.00 0.00 0.00 67.789 7.7,0 I TOTAl 90.09 0.00 0.00 0.10 0.00 0 0 0 O 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS A 0 O 0 a 0 0 0 0 a 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 0.005 CURIES SU003. 05 90 10 0 "

1S Shkipod 90 0 0 0 0 0 0 0 0 0 0 0 0

0 0

0 0 0 0 0 0 00 2-I54 .0OA0c1 0000 0 0 0 0 0 0 0 CU, M Stled 2.,54 0.0000 0.00D0A so 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 90 F73 Owled o.0990 is" CU. MS 2 0.0000 0.o00 0.0ooo0.00 0.020 o0.o o00 0.0000 00 0.000 oo10 0.000 0.0o00 0.0U0M o.0000 0.M o .OOM 0.ROOo 00000 n

RSW 124O co Page I of I

Oconee Nuclear Sltlon Annual Report OCONEE NUCLEAR STATION SOLID RAOWASTH REPOffr bPAW PmroW: J.mmy - Docmmb 2012 wab'TYPK SoaUfed OI, Uqu4kF Sudgw 0 OF CONTAINERS MOMP 0 O TOTIA.AVE.

ISOTOPE: %ABUIQANCEIJIUM 0 OF SHUIPENTS 0 TOrN. AW.

0.00 0.00 0.00 0.01) 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 0.00 o.00 8iIVIO, CR-61 0.00 0.00 0.00 0.00 0.00 0100 0.00 0.00 0.00 o.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SID0VAN MN-44 0.00 0.00 0.00 o.00 o.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 'CVMW CO-57 0.00 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CO-ES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 'Civic' 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 C040O 0.00 0.00 0.00 CLOD 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 o.oo 0.00 NEI-95 0.00 0.00 0.00 0.00 O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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-1 34 0.00 0.00 0.00 0.00 0.00 0.00 0.00 o.00 0.o00 RU-103S 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #'I1v0I 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIVANI AG-I1COM 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 S3-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 I-131 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 CS-137 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NDMOI W-S 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0o 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NM-63 0.00 0.00 0.00 0.00 0.00 0.00 m.oo 0.00 0.00 0.00 0.00 0.00 0.00 o.00 0.00 0.00 0.00 0.00 0.00 0.00 o.00 0.00 0.00 0.00 FE-65 0.00 0.00 0.00 91DIVIc, 0.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 SR-90 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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-12Sm 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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-Isa1 0.00 0.00 0.00 0.00- 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 CODo 0.00 0.00 0.00 0.00 0.00 C044 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 'CiIiOI 0.00 0.00 0.00 0.00 0.00 PU-24I 0.00 mo00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 JO~IVA 0.00 0.00 0.00 0.00 0.00 TRU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.o0 .00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 *DIVAN FE-SB 0.00 0.00 0.00 o.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 9IYANi 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 B.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 M3124 0.00 0.00 O.00 0.00 0,00 'Dlvi 0.00 0.00 0.00 0.00 O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 RU-106 0.00 0.00 0.00 0.00 0.00 MM1vic 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CE-144 'CIv/c 0.00 O.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CAA-242 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.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 . 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 41D1,Icl TOTAL 0.00 0.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 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 0 0 V 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 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 E::

CLASS AU 0 0 CURIES 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 r4<I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. FT. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. M 0 RSRI Page1 of I

Attachment 4 Oconee Nuclear Site Meteorological Data Oconee Nuclear Station 2012 Annual Radloactive Effluent Release Report Page I of 4

MONS 2012: SECTOR SN iNNE NE..ENE:I:- ESE SRI SSE :8 8W 8W WSW W WNW NW:NNW

No. No. No., No. No.: No. :No. No.f No. No. No. No. No. No. No. No.

STABWSCLS(

MI/S* .

0 0 0 0 :.0:.:.

0 0 "0 .0 .0 0 0 a 0 :0 0.76 . 0 0 0 0 0 0 .0 .::.01.:.0 2 1 .0 0 .0 .0

'~~ ... . .. ... ~~~ ~.i.. . . .. '. . " .. :.

.. : 0 0.0 0 20 1 . 4 0 1. 00 2 1.21 1.26-i:. ... 2:.:2 .f2 ::0 "0 I0 2 A1 8 10 1 2 2 :2 :0 1.50 41.51- 4 :6 : 4 2 ::1.0 0 1 15.5 46 19 4 5 2 .2 2.00 2.0t -0 :6 9 203 5:65:118 3 0

~4::::3.01

i~~~~ ~::.

3.00: : ~!~:.:~li:

~.' ~~1~~~~~. ::i*::::::::.

"...oo .... 1.::'

....... : :::. ~i:i030 :::: . ..1' 53:: : ... : 2- 4: 2 0

.8.00':I . " -::.. ... ... ..4.01 . : :

.5.01 -:: *: ::0 ...

" :T.*:: .. .i....... .0 i : .. .:..

. ... ... : . ... O..: :, : : :; : :. 1 . . :

.00 3 A :,

8.01: " 0 mm: :.0 0 04 41: 4 1 8.01- 0 0 .... 0 0 0 0 0 0 I 0 2 0 -0 .

10.00 . . .....-...

..0.46- 0 0000 0 0 0 000 0 0 00a 0.76-. 0 0 1 .0 0 0 .'00 0 4 :2 1 2 0 1 AM1.01: 2 00200 1 0 1 1:3 3 0 0 2

" 1.26-.

1.:::60 .

3 ':" 12: ' 0 1 : 1 1 0

4. 11 2 1 2 4 2

. . .1-3 '9 5 4 i:: 5' 0 2 4 22 54 27 12 7 4. 0

.:2.00 - - - . :- - - -

. 2.01-.. . 2 ::3 .8 29 15 8 0 26 1

3 .00 3.1- 1 1: 6 20086 .22 0 2 a 3;0.

5.00 :Th :76 : 0. :0 - 1.. 2 0 6.01- 0. D .0 0 0 0 o2.0 2 3 2 2 0 8.00 : . . . ..

6.01.. ......-.. ..:0 0 ... 0 000.0 . 00 0 3 08 81.

T.. 6.01.7 7. 0. 0.i:0 . 0 0 0 o0 2 1 0 e68

-: 10.0-9:0- 0.0 0- - :0 0 .. 2 2. :. 0 C .O.46.l 01. 0 0 :0 A0 :: *01 1i: .:I 01 0 0 C a 1

...... 0.7- 1 00101 0 0 2::0 . -

2 -

1 1 1.26, 0 * :::: i : : : . : : : : : ! : .:. . . . . . : .:i . : : : . . :*:: : . : : .:. . . . : *: : - . . . .

1A.0: 1- 5 2 66 1: 5 .... 2 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 4 Page 2 of 4

1.26- .. 5.5 8 2 :2 3 1 1 1: 31 7 12 8 7 :31 4 1.01. 10 9 16 3 10. 7 5 8 9 24 39 17 8 7 :5 1 72.01. 1412.217 452 5 2552133 2 0 42.002 2 3.01. .. i~- 0.......

/4,20 .. ...0 i.. 3 i..12 .0 ,i 0.. 0 1 2 8 20 3 21. 1 0 2

, .,- --..... .:0.

4.01- ...... 0 ... * : .::.t h::0 0 0 :0 2 2 1 1 i. 2 15.00 - -- - - - -

5.01-. .: 0 -0 0 .: 0 0 0.0 00 3 6:5 11 6 16.01- 0 0 0 0 0 0 0' 0. 0 0 3 41 01:

8.00 1 .*0 T.". 01.0 0 0 0 0 0 :C . 1I D 0.46, -9 I -4~--I -9 Q~l[ 0

.i04 .31,:: 4 - - 9~9 - U- I* 14 01

.. .3 51 8 5 1" Bf 113

06. 32!8!:A5F10 T7 116 14 . 15 26 24 26 .25R 27 .46

.1.01.: 4 ::23 :38::19 17 I5 22 22 222127 :24 29 18 23 3 1.225.

F 73

.JA

1.26-.::. :- 20 .39 : 31 47: :41 .. : :30: 21. :28 33 20 :.44 38 36 18 :26 2._200 1.651. "25 '.. 30... .:61 *....:

.108 : e.4 : *26 " 44 :56...52

. 51 51 34 32 17 14 20 2.01. 12 18 78 :152 :58 .14 17 1.1 28 98 118 8.61 32 28 14 22 3.00:

3.01-... .i..14 5 ::

..:4. ::24

... 45

.: .:0.. 4 0 00 5 22 83 35 23 33 M 25 18 4.01. 2 2 0 2 1 . 0 0 1 14 33 41 33 25 18 0 5.01 -.. 1 s 0. 0 0 0 0. 0 1 :17 24 13 11 11.1 1 6.00 6.01-.

.8;00 .:.. :. 0 ... 0*..... .-0 - 0 .0 0 "0 0 0 1 4 18 -

10 11 7 0

0 010 0 .0 0 0j 01 1 1 7 1l 2 0 .C

."8.01-.

10.00 1. 0 .01 E 11

.~ ~

_ _, _ I

.1 .OA6-.

0.78.... :3: " 4j . 27 ..1611 181 3 9 22 10 10 ic 1.61 22 42 31

.7.. :84 525437 :41 27 13 28 19 25

.1.01- .:-. :41 .35 29 .:-33 43 25 24 :49 73 :87 67 32 21 23 23 31 36 28 25 46 75. 58 "1.26 ... . .

1.26 25.. 26.38 4 448 34 43 25 25 1IS 24 12 32 4123 1.51 . 7 212 A 43 . 30 :26 55 50 39 22 28 2.00 14 :10 :9 23 1 201. - : 0 : .13... 441 8 14 1 23 30 24 14 4

30t;: i

..... ...8.4 12T:

0 :.:!; .::0:::2 .. ... .1 : 0 0 1

i

. . .5 . .:.....

120 ;8 3.1. 10 0.02 0 1 5 15 22 4 i;:2 *i: 0:

4.01. 70 1 010 .01 3 700 7 7 1 1

-- - - .:0 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 4 Page 3 of 4

..01- :0 . .0 0 0 30 0 0 11 0 1 :0. 0 0.

6.00 . .... 0' 6:.0 I.8009 "

0 ole

. . .. o -.-.-

0 0o000 0,

11 0010

.0 OjO01 0 0 010: 01 0 ...0 i.8.01- ..0 01.. 0101 0 pF :0 -719 . .. ..... .. .

... 1 I 01 0 0 21 41 31 1 :

07- .. 0 ... " .:.:6 . :1: .....: .. :2 :.1 70 .0 11 3 1 2 3 2 '17 . .. .. :: ...37... 2 . .. ..

1.01 4 :0 0 2 3 2 :3 0. 0 1 5 .3 .. 57 :40 17

0i~ i : :i

.26:/: I i::.8:::.3 0.-

.i.. ....0::.:

.0: ... . ...'1 3 1 5 0 2 1 1 2 1 18 :23 :0

. , " . i i :. i 1.611 01..

.....0..i. ii .:.:...i:.

'. :: .... i. 1 i 4 :. 4 6 2 0 0 0 013 3 80 0 0 0 0 1 222.01-1 1 :0 4 2 0 : 0 ::0 3.01iii1::.A:.0 . ::.::i:*: 00 ..0 :0 0 0 0.. . 0..0

. ....... 0 ..: ::: .0.:ii ...::::i

.. .:o

.....0. ... i:::i0 ~ a 400- :i*18 i i *:.oo~~~~~~~~~~~~~~~~

Ii 00

. * :::*: ~i:* .ii!:!:~ . . :. . .: .:.* I........... ...

4.01 000. 0 000 0 00 0 00

80..01.

.00 :i :. 0i. .i i 0. . i :i.i . i .

0 00 0 0 00 0 0 MOO0 00. :00..::00

.10.00 0 .0 0 0 0 :0 0 0. .0 0 01 .-0 Cii1

- 01I -: 01I -4.-6a

4. 6-4. - I - .4 "G b-b 03 -6~ 0 1C 0 01: '0 .0 2 ýC 0.75 1::: 01. .1. 0.

000.*6 mss.D0 0 0 . 0 0 0 : 0 T.. T T .112i 3 1

...... ... :. ...:0 ~0 . .. 2 13

. . ::2 . 0..

1t .5:21.::. : i :*01 * : ::i 1-.25 : . .:: o~ b 0 0 0, 0 o r: o i . .. o :0 *6 ..01i . . : :. .a::

l .e- . .1. 1 0 0 .. 0 0 1.50 2.000 2.1 00000 0 01 0100101 0

'.:1:

3.00ý -:0 : 0 0 0 01 0 0 0 0 0 0 0 :o 0 77Z

.4.01-i 0 00000.0 .0 0 0 0 00000 0 C 5 0o.01-o o01. 0 0 0 o0 a0 o0. :0 C 8.00 : :..:.. . * :...

.001- . "

0... 0. 0 0 0 0 0 0 0 0 0. :i 01l -: :0 - : . 0 - 01 - -

1- - .0" ).0 - 13 ::- --.-::-

I8,001. 0 01 01.0 0 :'C 0 01 0j .a 01 01 ...ý0 0

'I'1.00: ::0:::

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 4 Page 4 of 4

Attachment 8 Oconee Nuclear Site Unplanned Offsite Releases The ONS SLC 16.11.9, Radioactive Effluent Release Report, states:

'"he Annual Radioactive Effluent Release Report shall Include the following Information for all unplanned releases to unrestricted areas of radioacUve materials in gaseous and liquid effluents:

a. A description of the event and equipment involved;

b. Cause(s) for the unplanned release;

c. Actions taken to prevent recurrence; and,

d. Consequences of the unplanned release."

There were no known unplanned releases of radioactivity (material, liquid, or airborne) from Oconee Nuclear Station in 2012.

Oconee Nuclear Statfon 2012 Annual Radioactive Effluent Release Report Attachment 5 Page 1 of I

ATTACHMENT 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle, dose calculation results)

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

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

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

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 6 Page 1 of 18

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS ANNUAL DOSE SUHHRPX REPORT Oconee Nuclear Station Units 1, 2, A 3 1*t Quarte 2012

=-W0o1, 33, and PARtZCUL D0W03 Lnll' 31, YSZBT Quarter 1. 2012 Critical Critical DoSe TLmit Max % of Period-Li4mt Age organ (aret) (lur) 7Lmit Q1 - Nazime Organ Dom. CHID BOM 9.09Z-02 2.251+01. 4.043-01 Miaxi Organ Dome Receptor Location: 1.0 Mile 81 Critical Pathway: vegetation Major Imotopic Coatr*b*tozo (5% or greater to total)

NUolide Percentage C-14 1.003+02

--- W 0063 LXll! A3LYSB Quarter 1 2012 -

Does Limit % of Period-Limit (mrad) (zurad) Limit Q0 - Muaxi=m QWM Air Doe 3.073-04 1.503+01 2.052-03 Xaxlinm *aAir Do"e Receptor Location: 1.0 Mile SW Matjor Isotopic Contribto re (5% or greater to total) wwaoide. percentage 2M-133 1.003+02 Q. - Maxm Sta. Air Does Be 9.148-04 3.001+01 3.05X-03 Maiumm atai Alr Done Receptor Location: 1.0 MLie ON Major Contributorm (5% or greater to total.)

-clid. percentage 22.-139 9.993+01O Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 2 of 16

ETL,3 M ANMD WhsB DISPOS*A ANNAM REPORT PERIOD 1/1/12 TO 1/1/13 GIAEOUS ANNUAL DOSE SMOG= MORT Oconee Nuclear Station Units 1, 2, & 3 20d kater 2012 Z* D03, B3, and hARZCULM DOSE I,1 A1. AL, MUTSa Quter 2 2012 Critical Critical Dose LA.udt n4m % of Period-Limit Agm . Organ (aneW) (arm) Lim.it Q2 - Maximum Organ Dose CXZD DON 7.063-02 2.253+01 3.143-01 Imaximm Organ Dose Receptor Location: 1.0 Mlae of Critical Pathway: Vegetation

)DJoC zootopic Contributors (50 or greater to total) c-14 1.00R+02 NOBLE Q8 DOSS LDET AT5ZY.. . Quarter 2 2012 DoSe Limit %iof Period-Lialit (alad) (Jared) lmt 02 - bioaftm Gamma Air Dose 4.765-0S 1.50&+01 3.198-04 aziaU G0ma Air Dose Receptor Lo*ation.t 1.0 Mile BY Mb-o*r Isotopia Contributors (5% or greater to total)

N ,lidem Parcitade M-133 9.63X.01 Q2 - Nbxtmr meDta Air Dose 1.392-04 3.001001 4.61Z-04 Maximum Beta At. Dome Receptor Location: 1.0 Mile SM major Contributors (M% ogreater to total) mulaxde Percentage Ux-13 9.e73+01 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 3 of 18

EILUEUT AMD VRST3 DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS ANNUAL DOSE SUMuar¥ REPORT Ocon Nucolear Station Units 1, 2, & 3 3" Quarter 2012

- ZODZU, 33, and PARIEczAU DOSS LXnII AN*SZS-- QuLarter 3 2012 CzI*.tcal Critical Dose Limit um % of PBOVed-Limit AM Organ (mrm) (area) Limit Q3 - MaxbimI Organ Dose Cs= Ban 8.83-02 2.253+01 3.94U-01 Maximum Organ Dose emoietor Looation: 1.0 MiL20 W critical Vathmw: Vegetation Major Isotopic Contributore (5O or greater to total)

Nualidce Percentage C-14 1.004+02

- 03 GA DOSE LIMI AMLYS" . ... Quarter 3-2012 -

DoW. TiJJit

of Period-Ldmit (mrad) ed) Limit Q3 - Maxim GamOa Air Do"e 1.213-05 1.50I+01 8.10Z-05 M)taximjum Ge Air Dose Receptor Location: 1.0 Mile W Major Isotopic Contributors (5% or greater to total)

Awolide ftrwowtage AR-41 9.983+01 Q3 - lbxamI seta Air Dose 4.95n-06 3.008+01 1.65r-OS Maximuxm Data Air Dome Recaptor Location: 1.0 Mile 9W Major Contri.bmtor (50 or greater to total)

N.olidad Percentage AR-41 8.653+01 1CR-85 1.22Z+01 Oconee Nuclear Station 2012 Annual Radloactive Effluent Release Report Page 4 of 16

EIIWEN AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 GASEOUS AHNUL DOSE SU*MARY REPORT-Ooonee uholear Station Units 1, 2, & 3 4 e" Quarte. 2012

-= D*OIN, U3, and P]UAWCUULM DOU LIT AMTBz8'- - Quarter 4 2012 Critc.aal Critical Dose Limit wma %of Period-Limit Age Orgam (ure) (uroa) T.4tL Q4 - MamAiuas Organ Dote CHILD BONN 8.001-02 2.253+01 3.563-01 Maximum Ozgan Dose ecwptmor Location. 1.0 Mile 8W Critical athwaV: Vegetation maor isotopic Contributors (M% or greatar to total) vulctI Percentags C-14 1.005+02 N OBaLE 98 DOSE LIMIT A ,YBZU Quarter 4 2012 DOn Limit % of Period-,Limit (red) Owed) Limit 04 - Maximum Gama Air Dome 7.S72-06 1.30]+01 3.041-05

)MxJLMM Gamme Air Dose ecmeptox Location: 1.0 Nile BE Major Isotopia Contributors (5% or greater to total)

A*-421 8.23]+01 X]-133 9.935+00 XR-135 7.123400 Q4 - Maximum Beta Air Done 5.323-06 3.00]+01 1.772-05 Nazimuim Data Air Dowe Receptor Location: 1.0 idle BE Mawor Contributors (5s or greater to total) iluclids Pefrcentage 13:-133 4.203+01 J&-41 4.158+01 XE-135 1.305*01 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 5 of 1I

EF1LUENT A1D WASTR DISPOSL AIMUAL REPORT PERIOD 1/1/12 TO 1/1/13 GMEOUS AMWAL DOSE U8A14RR REPORT Oconee z NUclear Station Units 1, 2, & 3 AMMAL 2012 ZOOZDN, H3, and VATIWMLS DOSE L-IZMT ]MUoL8ZU- Annual 2012 =

Critical Critical Dose Limit Max of veriod-11mit a"e orgaf cacao) (MEMO Limit Tv - Mazion Organ Dose CHID BGM 3.30B-01 4.502401 7.343-01 iaximum Org**n Dose ascleptor Loa-tiont 1.0 Mile SW Critical Pathway: Vegetation Majoz Zsotopic Contxibutors (5% or greater to total)

N-34 20r0eetag2 C-14 1.0018+02

-MG)M03 Q8 DOS LII"T A=ALY.. . Arnml 2012 Dose Limit '. of (saed) (XXV) Y.1L4-Pegiod-Limit YI - Mnaxmum Gemma Air Do"e 3.743-04 3.003+01 1.213-03 Maxium Gamma air Dose Recaptor Location: 1.0 mile. OW Major soltopic Contributors (53 or gzester to total)

?%iclide Percentage M-133 9.453+01 AR-41 5.273+00 Yr - Ma3dmm Sets, Air Dose 1.068-03 6.009+01 1.773-03 Maximum Sets air Dose Recaptor LoaJtion: 1.0 Mile SW Major Contributors (5% or greater to total)

Nuclide Percentage XR-133 9.903401 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 6 of 16

EVIEM AND .WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID AMUAL DOSE SUM]*MM REPORT Oconee Nuclear Station Units 1, 2, & 3 1". Quarter 2012

£MM3 LZMUD RK5MM3U I l Quarter 1 2012 ==ý critical critical Doae iit. f ax 4 of Period-Limit A"e (aw.m) ,TL.it 01- Natxinm Organ Domes WDU QZ-LLI 1.04-01 1.502+01 6.923-01 Qi - Tftal Body DO"e ROMK 2.353-02 4.503+00 5.223-01 aX&iam organ Critical Pathma: ]reas Water Wish Major Isotopic Contributors (SO. or greater to total)

HUCIL"d Percentage M8-95 7.988+01 R-3 1.938+01 Tot"l Rfto Critical Wath-aW. Trash Water Fish (ajos Zsot*opJo Contuibutors (5t or grmater to total)

Nualide Percentage H-3 8.545+O1 C8-137 1.42]+01 005323000MM8 LIQUED L3M38 (OTP 3) Quarter 1 2012 Critical DOe Limit ax a of Period-Limit A" Organ (-are) (areW) Limit Q2 - ibximm Organ Dose CH=L ,LIVE. 3.57B-05 1,503+01 2.383-04 Q1 - 2otal soft Doese H 3.573-05 4.503+00 7.932-04 maxiwmm organ Critical Pathway: Potable Wfater Major zsotoplc Contributors (S or greater to total)

Wuali- P.rqe-ta B-3 1.003+02 Total Body Critical Patbvay: Potable Water Ifajar Isotopic Contributorm (51kor greater to total)

MUolide Percentage R-3 1.00N+02 Oconee Nuclear Station 2012 Annual Radloadve Effluent Release Report Page 7 of 16

EFFLUENT AM WASTZ DISPOSRL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID AMUAL DOSE SMMRY REPORT Ooonee Nuclear Station Units 1, 2, & 3 2nd Quoat.ev 2012 m .ATO LIQU/D 23L32B8U ..... criti"al Quarter 2 2012 -

Done T.L-4it Max & of Period-Limit Age Organ (marm) (arm) Limit

-2

- m um Organ Does .,DUIT GI-LLI 3.602-01 1.50*+01 2.40*+00 Q2 - Total Body Does ADLT 3.39M-02 4.509+00 7.472-01 XwmmOrgan Critical Pathway: rabsh Water .ish Ma'jor Isotopic Contributors (5% or greater to total)

N sercentage 1X-95 9.0'102.

H-3 7.O4I.0 Total Body Critical Pithway: Frsh Water Fish Major Ibotopi.c Contributors (5% or greater to total)

Muclids Percentage H-3 7.553+01 CB-134 1.203+01 CB-137 9.023+00 ctITzMoos LIQUID RHImM82 (CTP 3) Quarter 2 2012 -

critical Critical Dose Limit Maz % of Period-Limi4t Age Organ (urem) (Mxem) Limit Q2 - blazi-u Organ Done CHILD LrAI 3.453-05 1.502+01 2.303-04 92 - Total Body Do"e01 3.453-05 4.50z+00 7.672-04 Mxsiin Organ Critical Pathwaly Potable Water MAj.or Isotopic Contributors (5% or greater to total)

Nuclide Percentage B-3 1.00o+02 Total Bodir Critical iathwW: Potable Water Mb.jor Isotopic Contributor* (5% or greater to total)

Maclid. Percentage B-3 1.003+02 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 8 of 15

EFMMNEN AND WASTE DISPOSAL ANNUAL REPOT PERIOD 1/1/12 TO 1/1/13 LIQUID ANNUAL DOSE S*MMARY REPORT Oconee Nuo.ear Station Units 1, 2, & 3 3z' Quarter 2012

- B&!CH LIQUID RWM3&83 critical Critical Quarter 3 2012 DoM. LiAmit 31 o%

Period-Limit A"e (urem) Limit 03 - Maximum Organ Dow GK-LI.! 1.378-01 1.502+01 9.103-01 0 - Total Bow DO" cum 3.603-02 4.503+00 8.003-01 Critical Pathway: Fresh Water Fish major Isotopic Contributors (5% or greater to total)

Mutolde Percentage 3m-95 7.27N+01 H-3 2.40Z+01 Total DOft Critical Pathway: Potable Water bMajor Isotopic Contributors (5% or greater to total)

Muolide Percentage H-3 9.77*+01 COMMIUOGU8 LIQUID 33L3BM8 (CTP 3) Quarter 3 2012 ,=

Critical Critical DoSe LiAm4t Nax % of Periad-Limuit Ag Organ - (aMe) Limit Q3- bMaximum Organ Does CUILD LIVZR 4.44B-05 1.503+01 2.969-04 93 - Total Body DOMe CHL 4.443-05 4.503+00 9.866-04 amj-Organ Critical Pathway: Potable Water MNjor I"sotopi Contributors MS4Or greater to total)

Maclid. Perentage H-3 1.002+02 Total Body Critical Pathway: Potable Water major Isotopia Contributors (5% or greater to total) muclid. Percentage H-3 1.003+02 Oconee Nuclear Station 2012 Annual Radloactlve Effluent Release Report .

Page 9 of 16

EFILUENT AND WASTE DISPOSAL ANNUAL REPORT PZfIOD 1/1/12 TO 1/1/13 LIQUID ANNUAL DOSE SMWOUAR RE*ORT Oconee Nucoear Station Units 1, 2, & 3 4t Quarter 2012

-ULMO LIQUD mMSA - - Quarter 4 2012.

critical critical Dose Limit Max1 of Pericd-ldnit, *ge (ure.) (urea) Imxit 04 - Maxdism Organ Doese ADUx GZ.-LL 6.00"-02 1.50X+01 4.003-01 g4 - Total BocV Dose Cana 2.29i-02 4.30+00 5.093-01 bmda- Organ Critical Pathway: Fresh Water *ish Maoor "sotopic Contributtors (5t or greater to t.otal)

Tulide percentage UB-95 6.22v401 H-3 3.663+01 Total Body Crit:Lcal Pathway: Potable Water beaom Isotopic Contributorsa (3t or greater to total) uo[i-9 Percentage R-3 9.955+01 CMO0UT=l= LIQUID M3L3A83 (CTOP 3) - Quarter 4 2012 -

critical Critical Dose Limit a % of PQer--od-LiittAM Organ (ar..) (area) Zdait

- MtdMUM Organ Does CHID LIR 3.169-OS 1.S02+01 2.113-04 Q4 - Total B Dom CoILD 3.163-05 4.508+00' 7.02"-04 maxmao Organ Critical Pathway: Potable Wlater Major Isotopic Contributors (S5 or greater to total)

Maclide percentage B-3 1.00+02 Total Body Critical Pathway: Potable Water Major Isotopio Contributors (5% oc greater to total) imaclide Percentage B-3 1.00E+02 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 10 of 16

EFFLUENT A1D WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/12 TO 1/1/13 LIQUID ANNUAL DOSE SAEARY REPORT Oconee Nualeax Station Units 1, 2, &3 ANMML 2012

- DAMO LIQUID OtLUM2S1 IIrIt-cal Annmual 2012 "

Critical Dose Limit Max % of Pear.od-Li 04t Age Organ (nrem) (na=) Limit Yr - mzimm Organ Done AD= 1.133-01 3.002+01 2.203+00 YZ - Total Dody Dose AD 9.00z+00 1.273+00

]wmnlm Organ Critical Patxay;: Fresh Water Irish Major Isotopia Contributors 1St or greater to total)

Muclide, Percentage 38-96 8.265+01 3-3 1.5311101 Total sodf Critical Pathwar: Fresh Water Fish Major ZIotopic Contributors (5t or greater to total) uailide Percentage 9-3 8.03+01 CB-137 6.51E+00

-c0111211113Uo LIQUID RELUaSKS (CTP 3) , Annual 2012 critical critic* Done Limit N.z 4 of Period-LiMit, Age Organ. (Earm) (nra.) Limi~t Yr - MximOrgau. nose CNZL LIM 1.461-04 3.001+01 4..1172-04 Itr - Total 3043' DO"e CNU 1.463-04 9.002+00 1.623-03 Critical Pathmay: Potable Water mtajor Isotopic Contributors (St or greater to total) y d,,Peretage X-3 1.00Z+02 Total Body Critical Pathwayt Potable Water

)b~ov ZIotopiL Contributors (51 or greater to total)

MualidaPercentage H-3 1.00,+02 Oconee Nuclear Staton 2012 Annual Radioactive Effluent Release Report Page 11 of 16

Oconee Nuclear Station 2012 Radioactive Effluent and ISFSI 40CFRI90 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of40CFR190, the annual dose commitment to any member of the general public shall be calculated to assure that doses ame limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. The fuel cycle dose assessment for Oconee Nuclear Station 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-14Supplemental Information", contained in the ARERR for farther information). The combined dose to a maximum exposed individual from Oconees effluent releases and direct and air-scatter dose from Oconee's ISFSI is below 40CFR190 limits as shown by the following summary.

L 2012 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 - 2.33E-_1 mr-em Maximum Location: 1.0 Mile, Southwest Sector Critical Age: Child Gas non-NG Contribution: 53%

Gas NO Contribution: <1%

Liquid Contribution: 47%

Maximum OMnn (other than TM Dow =- 7.19E-01 mrem Maximum Location: 1.0 Mile, Southwest Sector Critical Age: Adult Critical Organ: GI-LLI Gas Contribution: 8%

Liquid Contribution: 92%

IL 2012 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 I0CFR72.212 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. IOCFR72.212(b)(2Xi)(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".

Oconee Nuclear Station 2012 Annual Radloactive Effluent Release Report Page 12 of 16

The following three pages are excerpted from the Oconee Nuclear Site, "Independent Spent Fuel Storage Installation",

10CFR72.212 Evaluation for Phase VI report (Rev. 0, 6/7/2010).

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 13of 1l

C. 10CFR72.212(b)(2)(l)(C)- Requirements of 72.104

"...the requbiments of§ 72.104 have been met."

10 CFR 72.104, as clarified by ISO-133, stipulates that the licensee perform dose evaluations which establish that any real individual beyond the controlled area boundary not sustain a dose equivalent in excess of 0.25 mSv (25 mrem) due to direct radiation from the Independent Spent 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 (initial enrichment, burnup and Oconee Nuclear Site IOCFR72.212 Written Evaluations for Phase VI, Rev. 0 Page 20 of 27 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 14 of 16

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 ISFS 137 . Calculation OSC-8675 3s develops the radiation source terms used in subsequent shielding and skyshine calculations using the SCALE Code System.

More specifically, the SAS2 Module of the SCALE Code System39 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 Module40 of the SCALE Code System was used to perform the fuel depletion and characterization calculations using the cross section sets created by SAS2. These characterization calculations yielded the photon and neutron source terms to be used as input to subsequent shielding calculations. As mentioned above, problem-dependent cross section sets were developed for these analyses since ORIGEN-S was used within the SAS2 sequence. Duke Energy Corporation Radiological Engineering is experienced in the use of the SCALE Code System, and the SCALE Code System is installed and maintained under the purview of the pertinent software and data quality assurance program.

The results of the radiation source term calculation were used as input to Calculation OSC-8706 4' to evaluate the shielding characteristics of a single Horizontal Storage Module. The MCNP Monte Carlo particle transport computer code42 was used to perform the transport calculations and to write a surface flux file for use in subsequent skyshine calculations.

Appropriate software quality controls have been implemented for the computer codes and data used in these analyses (specifically, Calculation DPC-1201.30-00-0010 43 contains the verification and validation for MCNP5, while SDQA-30269-NO009 documents the quality control measures in place for MCNP5).

Calculation OSC-871644 uses the surface flux files developed in OSC-8706 4 1 in a repeating array representing all of the Horizontal Storage Modules in the ISFSI, including Phase VI fully loaded with spent fuel. The 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 HSM.

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", Table 23.1-1, summarizes dose rate versus distance, showing a dlose 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) firom the ISFSI, or 1.36 miles from the centerline of the site. 5 This is conservatively farther than the distance used for computation of dose rates. The 2009 40CFR 190 Uranium Fuel Cycle Dose Calculation Results for the ONS site show a maximum total body Oconee Nuclear Site IOCFR72.212 Written Evaluations for Phase VI, Rev. 0 Page 21 of 27 Oconee Nuclear Station 2012 Annual Radioactive Efflue,,t Release Report Page 15of 16

dose of 0.0754 mrem per year.49 The total dose rate from all operations to the nearest real individual is therefore less than 7 mnRem per year.

These calculations need not consider any effluent from Phase VI. The Phase VI HSMs use the NUHOMS-24PHB DSCs, which are desirned as "leak-tightV. Per Appendix N, Section N. 11.2.8 of the NUHOMS PSAR, accidental releases are not credible.

Oconee Nuclear Site IOCFR72.212 Written Evaluations for Phase VI, Rev. 0 Page 22 of 27 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 16 of 16

Attachment 7 Oconee Nuclear Site Revisions to UFSAR Section 16.11 Radiological Effluent Controls Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page I of 11

Radiological Environmental Monitoring 16.11.6 18.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.6 Radiological Environmental Monitoring COMMITMENT a. The radiological environmental monitoring samples shall be collected in accordance with Table 16.11.6-1 and shall be analyzed pursuant to the requirements of Tables 16.11.6-1 and 16.11.6-2.

b. A land use census shall be conducted and shall identify the location of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of eight kilometers (five miles). Broad leaf vegetation sampling shall be performed at the site boundary in the direction sector with the highest D/Q In lieu of the garden census.

c. Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program. A summary of the results obtained as part of the Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report. The Interlaboratory Comparison Program shall be described in the Annual Radiological Environmental Operating Report.

d. The results of the land use census shall be Included in the Annual Radiological Environmental Operating Report.

NOTE-If samples required by Commitment part a, become permanently unavailable from any of the required sample locations, the locatlons from which samples were unavailable may then be deleted from the program provided replacement samples were obtained and added to the environmental monitoring program, if available. These new locations will be identified in the Annual Radioactive Effluent Release Report.

APPLICABILITY: At all times 16.11.6-1 05/31/12 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 7 Page 2 of 11

Radiological Environmental Monitoring 16.11.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radiological A.1 Submit a description of May 15 of following environmental the reason for not calendar year monitoring program Is conducting the program not conducted as as required and plans to required. prevent a recurrence shall be included In the Annual Radiological Environmental Operating Report B. Land use census B.1 -- NOTE identifies a Location The sampling location which yields a having the lowest calculated dose or dose calculated dose or dose commitment (via the commitment (via the same exposure same exposure pathway) 20% greater pathway) may be than a location from deleted from this which samples are monitoring program currently being after October 31 of the obtained. year in which this land use census was conducted.

Add new location to the 30 days radiological environmental monitoring program.

AND B.2 Identify new locations in April 30 of following the next Annual calendar year Radioactive Effluent Release :Report.

16.11.6-2 05131112 1 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 7 Page 3 of 11

Radiological Environmental Monitoring 18.11.6 ACTIONS (continued) I l

CONDITION REQUIRED ACTION COMPLETION TIME C. Interlaboratory C.1 Report corrective May 15 of following Comparison Program actions In the Annual calendar year analyses not performed Radiological as required. Environmental Operating Report.

D. Radioactivity level D.1 Prepare and submit a 30 days resulting from plant Special report that effluents In identifies the cause for environmental sampling exceeding the limits and medium at a specified defines the corrective location in excess of actions to be taken to reporting limits of Table reduce radioactive 16.11.6-3 when effluents so that the averaged over a potential annual dose to calendar quarter. a MEMBER OF THE PUBLIC is less than the calendar year limits of SLC 16.11.1 or 16.11.2.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.6.1 Conduct land use census during growing 12 months season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authortles.

16.11.6-3 05131/12 1 Oconee Nuclear Station 2012 Annual Radloactive Effluent-Release Report Attachment 7 Page 4 of11

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Exposure Pathway SapeSample and/or Number of Frequency (nd)C~toTime and Frequency of Analysis Sample Locations (b) Frequency (d)

1. AIRBORNE Radlolodine and 5 Continuous sampler Radiolodine canister:

Particulates operation with sample I-131 analysis weekly. Particulate collection weekly. or sampler. Gross bets radioactivity more frequently If analysis following filter change; and required by dust loading, gamma Isotopic analysis of composite (by location) quarterly. (c)

2. DIRECT RADIATION 40 Quarterly. Gamma dose quarterly.

3. WATERBORNE

a. Surface 2 Composite (a) sample Gamma Isotopic analysis monthly.

over a 1-month period.

Compos1te for tritMum analysis quarterly.

b. Drinking 3 Composite (a) sample Composite for gross beta and gamma over a 1-month period, isotopic analyses monthly.

Composite for tritiun analysis quarterly.

c. Sediment from 2 Semiannually. Gamma Isotopic analysis Shoreline semiannually.

16.11.6-4 05/31/12 1 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 7 Page 5 of 11

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Exposure Pathway mndlor Number of Sampling and Collection Time and Frequency of Analysis sap Sample Frequency (d)

4. INGESTION

a. Milk 4(e) Semimonthly when Gamma Isotopic and 1-131 analysis animals are on pasture: semimonthly when animals are on monthly at other times. pasture; monthly at other times.

b. Fish 2 Semiannually. One Gamma Isotopic analysis sample each semiannually on edible portion.

commerdally and recreationally Important spades.

c. Broad-leaf 2 Monthly. Gamma Isotopic analysis monthly.

Vegetation (a) Composite samples shall be collected by collecting an aliquot at Intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

(b) Sample locations are Identified inthe ODCM.

(c) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow radon and thoron daughter decay. If gross beta activity in air particulate samples Is greater than 10 times the yearly mean of control samples, gamma Isotopic analysis shall be performed on the Individual samples.

(d) Deviations are permitted from the required sampling schedule Ifspecimens are unobtainable due to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment. ifthe letter, every effort shall be made to complete corrective action prior to the end of the next sampling period.

(e) Samples from milking animals Inthree locations within 5 km distance having the highest dose potential. If there are none, then one sample from milking animals In each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per year. One sample from milking animals at a control location, as for example 15 to 30 km distant and inthe least prevalent wind direction.

16.11.6-5 05/31/12 I Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 7 Page a of 11

Radiological Environmental Monitoring 16.11.6 Table 18.11.6-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)

Airborne Fish Broad-leaf Water Particulate or Milk Veeon Sediment Analys (pCa) Gem (PCkg, (pClA) (pCI/kg, dry) wo (pc , wet)

(Pcvm'w)

Gross Beta 4 iE-02

1. 2,000 Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-50 15 130 Zn-66 30 260 Zr-95 15 Nb-95 15 1-131 15(b) 7E-02 1 80 CS-134 15 5E-02 130 15 60 150 Cs-137 18 GE-02 150 18 80 ISO Ba-140 15 60 La-140 15 16 (a) The LLD Is defined, for purposes of these commitments, as the smallest concentration of radioactive material In a sample with 05% probability of detection and with 5% probability of falsely concluding that a blank observation represents a "real" signet.

For a particular measurement system (which may Include radlochemical separation):

LLD =4.6 Sb E xV x 2.22 x Y x exp (-X& t)

Where:

LWD Is the lower limit of detection as defined above (as pCI per unit mass or volume)

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) 16.11.6-6 05/31/12 1 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 7 Page 7 of 11

Radiological Environmental Monitoring 16.11.6 Table 16.11.8-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)

E Is the counting efficiency (as counts per disintegration)

V Is the sample size (In units of mass or volume) 2.22 Is the number of disintegrations per minute per picocurle Y is the fractional radlochemical yield (when applicable)

X Is the radioactive decay constant for the particular radlonudide A t Is the elapsed time between sample collection (or end of the sample collection period) and time of counting Typical values of E, V, Y and A t should be used In the calculation.

The LLD Is defined as an a priod (before the fact) limit representing the capebility of a measurement system and not as a postedorl (after the fact) lImit for a particular measurement Analyses shall be performed In such a manner that the stated LIDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of Interfering nuclides, or other uncontrollable circumstances, may render these LLDs unachlevable. In such cases, the contributing factors will be Identified and described In the Annual Radiological Environmental Operating Report.

(b) LLD for gamma Isotopic analysis for 1-131 In drnking water samples. Low level 1-131 analysis on drinking water will not be routinely performed because the calculated dose from 1-131 In drinking water at all locations Is less then I mmm per year. Low level 1-131 analyses will be performed Ifabnormal releases occur which could reasonably result In > 1 pCAiter of 1-131 in drinking water. For low level analyses of 1-131 an LILD of 1 pCi/llter will be achieved.

(c) Other peaks which are measurable and Identifiable, together with the radionuclldes In Table 18.11.6-2, shall be Identified and reported.

Oconee Nuclear Station 18.11A-7 05/31/12 2012 Annual Radioactive Effluent Release Report Attachment 7 Page 8 of 11

Radiological Environmental Monitoring 16.11.6 Table 16.11.6-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples (c) (d) I Airborne Bodl Water Particulate or (Fishi/ ,we) Milk p i/)Vegetation Broad-leaf Analysis ( i/)Gages e(PCVm (pCkg, wet) (pCll) (pCUkg, wet)

H-3 2E04(a)

Mn-54 IE03 3E04 Fe-S9 4E02 1E04 Co-68 1E03 3E04 Co-60 3E02 IE04 Zn-O6 3E02 2E04 Zr-Nb-S6 4E02 1-131 2(b) 0.9 3 IE02 Cs-134 30 10 1E03 80 1E03 Cs-837 60 20 2E03 70 2E03 Ba-La-140 2E02 3E02 (a) For drinking water samples. This Is 40 CFR Part 141 value.

(b) If low level 1-431 analyses are performed.

(c) Report shell be submitted when any single radlonuclide exceeds the reporting level In Table 16.11.6-3 or when more than one of the radlonucildes In Table 15.11.6-3 are detected In sampling medium and concentration(1)*4oncentrtion.(2) + ... 2 1.0 reportinglevel (1) reportinglevel (2)

(d) Report shael be submitted when radlonucides other than those In table 1.11.8-3 are detected and are the result of plant effluents Ifthe potential annual dose to a MEMBER OF THE PUBLIC from all radlonucldes Is equal to or greater than the calendar year limits of SLC 16.11.1 or 16.11.2.

16.11.6-8 05/31/12 I Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 7 Page 9 of 11

Radiological Environmental Monitoring 16.11.6 BAISES The environmental monitoring program required by this commitment provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of exposure pathways. The Initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The detection capabilities required by Table 16.11.6-2 are considered optimum for routine environmental measurements in industrial laboratories. The specified lower limits of detection correspond to less than the 10 CFR 50. Appendix I, design objective does-equivalent of 45 mrem/year for atmospheric releases to the most sensitive organ and Individual. The land use census commitment is provided to assure that changes in the use of unrestricted areas are Identified and that modifications to the monitoring program are provided if required by the results of this census.

The requirements for participation in an Interlaboratory Comparison Program is provided to assure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring In order to demonstrate that the results are reasonably valid.

With the level of radioactivity in an environmental sampling medium at a specified location exceeding the reporting levels of Table 16.11.6-3 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days a Special Report that defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of SLC 16.11.1 or SLC 16.11.2. When more than one of the radionuclides in Table 16.11.6-3 are detected in the sampling medium, this report shall be submitted If concentration (11 + conentration(2) +... > 1.0 reportinglevel (1) reportinglevel (2)

When radionuclides other than those in Table 16.11.6-3 are detected and are the result of plant effluents, this report shall be submitted If the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of SLC 16.11.1 or SLC 16.11.2. This report Is not required ifthe measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2. The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in the 30-day Special Report.

16.11.6-9 05131112 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 7 Page 10 of 11

Radiological Environmental Monitoring 16.11.6 The following requirement(s) were relocated from the CTS 6.4.4.f during the conversion to ITS.

The station shall have a program to monitor the radiation and radionudides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity In the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in UFSAR Chapter 16, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1. Monitoring, sampling, analysis, and reporting of radiation and radlonuclides In the environment In accordance with the methodology and parameters In the ODCM;

2. A Land Use Census to ensure that changes In the use of areas at and beyond the SITE BOUNDARY amr Identified and that modifications to the monitoring program are made if required by the results of this census; and,

3. Participation In an Interlaboratory Comparison Program to ensure that Independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

REFERENCES:

1. 10 CFR Part 50, Appendix I.

2. Offsite Dose Calculation Manual.

16.11.6-10 05/31112 1 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 7 Page 11 of 11

Attachment 8 Oconee Nuclear Site Revisions to the Radioactive Waste Process Control Program Manual The following letter dated March 27,2013, from David L. Vaught, Senior Engineer, Nuclear Chemistry, summarizes how the Process Control Program (PCP) manual has been revised. This version of the PCP Manual contains all the changes implemented during 2012 and is designated on the Compact Disc cover as the "2012 ARERR".

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 8 Page 1 of 4

Duke Energy Radioactive Waste Process Control Program Manual Summary of 2012 Changes March 27, 2013 KR Alter Regulatory Affairs Oconee Nuclear Safety Assurance Attention: J. F. Smith

Subject:

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Process Control Program Changes File: GS-76415, 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, 2012 through December 31, 2012. This version of the Manual contains all the changes implemented during 2012 and is designated an the CD cover as the "2012 Report Year.

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 2012.A more detailed summary of changes and basis are in the Appendix H of the PCP Manual.

The PDF file "DukeEnergy-2013-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 fbr SC DHEC and four CDs are for the NRC as follows:

DUKE

1. ELL

2. Master File SC STATI

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 Ifyou have any questions, please call David Vaught @ 980-373-5302.

Larry A. Wilson Supervising Scientist Nudear Chemistry by: David L Vaught Senior Engineer Nuclear Chemistry - Radwaste ATTACHMENT Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 8 Page 2 of 4

Appendix L - ARERR ATTACHMENT 8 Revisions to the Radioactive Waste Process Control Program Manual A brief summary of the 2012 changes to the Duke Energy Radioactive Waste PCP Manual is found below. These are described in more detail in APPENDIX H "Revision Summary -

Licensee Ikltiated Changes" PCP MANUAL SECTIONS CHANGED APPENDIX A: "ONS PCP" Rev 15 Minor Change APPENDIX D: "Approved Suppliers of PCP Services" Rev 3 APPENDIX E: "PCP Manual Review and Approval Requirement." Rev 2 DESCRIPTION OF CHANGES BY SECTION APPENDIX A: "ONR PCP" Rev 15 Minor Change A Minor Change was published to address a NOS Audit Deficiency identified during the 2012 ONS Radiological Effluent Controls Audit.

1. Two procedures listed in the manual have been revised from "B" to "Am procedures.

2. The procedure CP/O/B/5200/054, "Radwaste Liquid Waste Processing" was removed from the implementing procedure list after it was determined that it does not implement or impact any part of the PCP.

3. Two editorial changes were included to correct procedure title wording APPENDIX D: "Approved Suppliers of PCP Services" Rev 3 CHANGES:

1. Added Waste Management Group (WMG) to the Approved Suppliers of PCP Services table.

2. Edited details of the DOCUMENTATION section to clarify applicability.

3. Added the PIP reference G-04-00113 that documents the review and approval of the Studsvik Processing Facility, LLC previously added to the table.

4. Deleted section 2.2 due to changes in internal Duke administrative processes outside the PCP Manual purview.

APPENDIX E: "PCP Manual Review and Approval Requirements" Rev 2 CHANGES:

1. Changed titles to reflect post merger.

2. Changed the approval protocol for the PCP Manual sections to simplify the approval process by lowering the management approval level required based on significance of the section being changed and whether it is a revision or a minor change.

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 8 Page 3 of 4

A brief' summary of the 2012 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" PCP MANUAL SECTIONS CHANGED APPENDIX A: "ONS PCP" Rev 15 Minor Change APPENDIX D: "Approved Suppliers of PCP Services Rev 3 APPENDIX E: vPCP Manual Review and Approval Requirements" Rev 2 DESCRIPTION OF CHANGES BY SECTION APPENDIX A: "ONS PCP" Rev 15 Minor Change A Minor Change was published to address a NOS Audit Deficiency Identified during the 2012 ONS Radiological Effluent Controls Audit.

1. Two procedures listed in the manual have been revised from "B"to "A"procedures.

2. The procedure CP/0/B/5200/054, "Radwaste Liquid Waste Processing" was removed from the Implementing procedure list after it was determined that It does not Implement or impact any part of the PCP.

3. Two editorial changes were Included to correct procedure title wording APPENDIX D: *Approved Suppliers of PCP Service? Rev 3 CHANGES:

1. Added Waste Management Group (WMG) to the Approved Suppliers of PCP Services table.

2. Edited details of the DOCUMENTATION section to clarify applicability.

3. Added the PIP reference G-04-00113 that documents the review and approval of the Studsvik Processing Facility, LLC previously added to the table.

4. Deleted section 2.2 due to changes in Internal Duke administrative processes outside the PCP Manual purview.

APPENDIX E: aPCP Manual Review and Approval Requirements? Rev 2 CHANGES:

1. Changed titles to reflect post merger.

2. Changed the approval protocol for the PCP Manual sections to simplify the approval process by lowering the management approval level required based on significance of the section being changed and whether it is a revision or a minor change.

Vavw~dL MhaugA NGO Nuclear Chemistry/ Radwaste Support Office Ph: 980-373-5302 Pager: 704-777-7392 Dayid.Vaulhtd8duke-enermvcom Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 8 Page 4 of 4

Attachment 9 Oconee Nuclear Site Information to Support the Nuclear Energy Institute (NEI)

Groundwater Protection iniative Oconee Nuclear Station 2012 Annual Radioactive Effuent Release Report Page 1 of 4

2012 Annual Radiological Effluent Release Report Ground Water Well Data Duke Energy implemented a Ground Water Protection program in 2007. This program 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 monitored sixty-six ground wat wells during 2012. Tritium activity in wells GM-7R and GM-7DR was reported per NEI 07-07 in February, 2010. The probable source of this activity was determined to be discharges of the turbine building sumps to Chemical Treatment Pond #3 through the east yard drain. Discharges of the turbine building sump through this pathway were discontinued in 2008. Installation of a recovery well in 2011 has resulted in decreased tritium concentrations in well GM-7DR.

Monitoring wells are sampled quarterly, semi-annually or annually. The recovery well discharge composite is collected weekly. Ground water samples are regularly analyzed for tritium and gamma emitters with selected 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 2012.

Results from sampling during 2012 are shown in the table below.

WeN Location Tritium Concentration (pCi/I) # Of Name Ist Qtr. 2nid Qtr. 3rd Qtr. 4th Qtr. Samples GM-1R CTP-1/2 <MDA <MDA <MDA <MDA 4 GM-2R U-1/2 SFP 415 956 1,120 822 4 GM-2DR U-1/2 SFP 340 386 381 354 4 GM-3R U-3 SFP 190 271 287 174 4 GM-3DR U-3 SFP 393 378 299 294 4 GM-4 Warehouse 10 366 413 432 319 4 GM-5 Rdwst. Bldg. <MDA 189 190 <MDA 4 GM-5R Rdwst. Bldg. NS' <MDA <MDA <MDA 3 GM-6 Outflow to CTP-3 <MDA 189 NS <MDA 3 GM-6R Outflow to CTP-3 <MDA <MDA NS <MDA 3 GM-7 525 kv Sw. Yard 474 652 943 906 4 GM-7R 525 kv Sw. Yard 7.500 4,610 3,390 2,800 4 GM-7DR 525 kv Sw. Yard <MDA <MDA <MDA <MDA 4 GM-8 E of U-3 TB 391 348 222 300 .4 GM-SR E of U-3 TB 377 457 432 .335 4 GM-9 E of U-2 TB 217 246 301 253 4 GM-9R E of U-2 TB <MDA 180 <MDA <MDA 4 GM-10 525 kv Sw. Yard <MDA <MDA <MDA <MDA 4 GM-I OR 525 kv Sw. Yard <MDA <MDA <MDA <MDA 4 GM-Il ONS Garage 282 <MDA NS <MDA 3 GM-IIR ONS Garage <MDA <MDA NS <MDA 3 GM-12 E of Access Rd. <MDA <MDA <MDA <MDA 4 GM-12R E of Access Rd. <MDA <MDA <MDA <MDA 4 Oconee Nuclear Station 2012 Annual Radioactive Efftuant Release Report Page 2 of 4

2012 Annual Radiological Effluent Release Report Ground Water Well Data Well Location Tritium Concentration (pCi/i) # Of Name Ist Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Samples i

GM-13 525 kv Sw. Yard <MDA <MDA <MDA <MDA 4 !

GM-13R 525 kv Sw. Yard <MDA <MDA <MDA ,MDA .4 E

GM-14 Mnt. Trg. Facility <MDA <MDA <MDA <MDA 4 GM-14R Mat. Trg. Facility <cM[A <MDA <MDA <MDA 4 =

OM-15 525 kv Sw. Yard <MDA <MDA 235 cMDA 4 i GM-15R 525 kv Sw. Yard 255 <MDA <MDA 222 4 !

GM-16R TBSMT 2,440 NS NS 2 2.,30 GM-16DR TBSMT 10.700 9,570 9,960 9,450 4 GM-16DDR TBSMT 477 343 458 332 4 GM-17R Oil Drum Storage 2,420 1640 1,510 1,470 4 GM-17DR Oil Drum Storage 3.290 3,240 3,180 3,140 4 GM-18R RCP RafUrb.Bldg 10,300 9,880 8,490 8,280 4 GM-19 525 kv Sw. Yard 488 242 364 494 4 GM-19R 525 kv Sw. Yard 351 319 315 421 4 GM-20 SG Retire. Facility <MDA <MDA <MDA <MDA 4 GM-20R SG Retir Facility <MDA <MDA <MDA <MDA 4 OM-21 Sec.Trg. Facility <MDA <MDA <MDA <MDA 4 GM-22 Sec.Trg. Facility <MDA <MDA <MDA <MDA 4 GM-23 525 kv Sw. Yard 353 325 344 287 4 GM-24R 3T Transformer 2,090 1.400 1,600 J1,5t 4 GM-25R CD3 Transformer 218 318 350 432 4 BO-4 Ball Field <MDA <MDA <MDA <MDA 4 MWA-I CTP-I/2 <MDA <MDA <MDA NS 3 MW A-2 CTP-1/2 <MDA <MDA . MDA <MDA 4 MW A-8 CTP-1/2 NS NS NS NS 0 MWA-9 CrP-1/2 199 <MDA <MDA 183 4 MWA-10 CTP-3 435 457 462 801 4 WA-I1 CTP'3 <MDA <MDA <MDA <MDA 4 MW_A-12 CTP-3 <MDA <MDA <MDA <MDA 4 MWA-13 CTP-It2 872 507 449 50 4 MW.A-14 CTP-I/2 <MDA 370 489 489 4 MWA-17 CTP-1/2 <MDA <MDA <MDA 189 4 MW A-18 CTP-1/2 <MDA <MDA <MDA <MDA 4 Well Location Tritium Concentration (pCi/1) # of Name 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Samples

011 (IW-1) Ball Field <MDA <MDA <MDA cMDA 4 "013 (IW-2) WH-5 <MDA <MDA <MDA <MDA 4

015 Browds Bottom <MDA <MDA <MDA <MDA 4 Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 3 of 4

2012 Annual Radiological Effluent Release Report Ground Water Well Data Well Tritium Concentration (pCi/I) # of Name L t 1/30/12 4/17/12 7/9/12 Samples MW-3 Landfill <MDA <MDA 2 MW-11 Landfill <MDA <MDA 2 MW-lID Landfill <MDA <MDA 2 MW-13 Landfill <MDA <MDA 2 MW-16 Landfill <MDA <MDA 2 MW-RPOI Landfarm/Burial <MDA 1 MW-RP02 Landfarm/Burial <MDA 1 L MW-RP03 Landfarn/Burial I <MDA I 9.

Well L Tritium Concentration (pCi/) # of Name Location Minimum Average Maximum Samples

RW-1 525kvSw.Yard 1950 2605 3110 47 NS - Not sampled due-to insufficient volume in well or well inacesstile due to construction in area.

These are irrigation wells and may not meet current requiremwets for ground water monitoring well construction.

"This is a recovery well not intended for long term monitoring.

pCi/l - pico curies per liter

< - less than minimum detectable activity, typically,250 pCi/liter 20,000 pCi/I - the Environmental Protection Agency drinking water standard for tritium.

This standard applies only to water that is used for drinking.

1,000,000 pCi/I - the I0CFR20, Appendix B, Table 2, Column 2, Effluent Concenation limit for tritium.

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Page 4 of 4

Attachment 10 Oconee Nuclear Site Inoperable Equipment 1 RIA-40 and 2RIA-40, Condenser Steam Air Ejector Off Gas Monitors, were declared out-of-service on August 5, 2010, due to moisture (water) carryover into the detector chamber.

Selected Licensee Commitment (SLC) 16.11.3, Condition C, required action to return 1RIA-40 and 2RIA-40 to service within 30 days was not successful. This condition continued through 2011 and 2012 with grab samples being taken to detect any primary to secondary leakage on Units 1 and 2.

Modifications to add moisture separators and drains are being installed on I RIA-40 and 2RIA-

40. The Unit 2 modification installation Is complete as of April 16, 2013 with post modification testing waiting on warmer ambient temperatures to ensure the modification is effective. Unit I modification is in progress as of April 16, 2013.

The inoperability of 1RIA-40 and 2RIA-40 could not be corrected in a timely manner (ess than 30 days) due to the need for a station modification to effectively resolve the moisture carryover I"

Issue.

Reference Corrective Action Program documents PIP 0-11-08384, 0-11-08365 and 0 01873.

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 10 Page 1 of I

Attachment 11 Oconee Nuclear Site 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, 2012 to December 31, 2012.

There were no changes made to the radioactive waste systems during 2012 at the Oconee Nuclear Station.

Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Attachment 11 Page I of I

Enclosure 2012 Offite Dose Calculation Manual Compact Disc Oconee Nuclear Station 2012 Annual Radioactive Effluent Release Report Enclosure Page 1 of I

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