ML14154A414
| ML14154A414 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/30/2014 |
| From: | Batson S L Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14154A413 | List: |
| References | |
| ONS-2014-044 | |
| Download: ML14154A414 (93) | |
Text
ENERwGY.Scott L. Batson Vice President Oconee Nuclear Station Duke Energy ONO1VP I 7800 Rochester Hw-y Seneca, SC 29672 o: 864.873.3274 f 864.873. 4208 Scott.Betson@duke-energy.com ONS-2014-044 April 30, 2014 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 2013 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, 2013 through December 31, 2013. In accordance with TS 5.5.1, the Offsite Dose Calculation Manual (ODCM) is included in this submittal.
Attachment 1 Attachment 2 Attachment 3 Attachment 4 Attachment 5 Attachment 6 Attachment 7 Attachment 8 Attachment 9 Attachment 10 Attachment 11 Attachment 12 Summary of Gaseous and Liquid Effluents Report Supplemental Information Solid Radioactive Waste Disposal Report Meteorological Data Unplanned Offsite Releases Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)Revisions to UFSAR Section 16.11 Radiological Effluent Controls Revisions to the Radioactive Waste Process Control Program Manual Information to Support the NEI Groundwater Protection Initiative Inoperable Equipment Radioactive Waste Systems Changes 0 0A o i Errata to Previous Reports www.duke-energy.com U.S. Nuclear Regulatory Commission 2013 Annual Radioactive Effluent Release Report April 30, 2014 Page 2 Enclosure 2013 Offsite Dose Calculation Manual (Compact Disc)Any questions concerning this report should be directed to Judy Smith at 864-873-4309.
Sincerely, Scott Batson Vice President Oconee Nuclear Station Attachments 1 through 12 Enclosures Offsite Dose Calculation Manual [ODCM] Compact Disc [CD]
U.S. Nuclear Regulatory Commission 2013 Annual Radioactive Effluent Release Report April 30, 2014 Page 3 xc (with attachments and enclosure):
Mr. Victor McCree Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station xc (with attachments only): Mr. James R. Hall NRC Project Manager (File via E-mail)U.S. Nuclear Regulatory Commission One White Flint North, M/S O-8B1 11555 Rockville Pike Rockville, MD 20852-2746 Ms. Susan E Jenkins Radioactive and Infectious Waste Management 2600 Bull Street Columbia, SC 29201 Mr. Joseph T. Sears, Chemistry Manager INPO 700 Galleria Place, Suite 100 Atlanta, GA 30339-5943 Mr. Gary Stewart State Voluntary Cleanup Section S.C. Dept. of Health & Environmental Control 2600 Bull Street Columbia, SC 29201 Ms. Sandra Threatt Nuclear Response and Emergency Environmental Surveillance S.C. Dept. of Health & Environmental Control 2600 Bull Street Columbia, SC 29201 ATTACHMENT I Summary of Gaseous and Liquid Effluents Report This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Revision 1, Appendix B.(Pages 1 -9)I TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 GASEOUS EFFLUENTS
-SUMOATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 RMPORT FOR 2013 Units QTR I A. Fission and Activation Gasnes 1. Total Release Ci 1.013+01 2. Avg. Release Rate uCi/sec 1.303+00 B. Iodine-131
- 1. Total Release Ci 0.003+00 2. Avg. Release Rate uCi/sec 0.003+00 C. Particulates Half Life >- 8 days 1. Total Release Ci 0.00E+00 2. Avg. Release Rate uCi/sec 0.003+00 D. Tritium 1. Total Release Ci 2.313+01 2. Avg. Release Rate uCi/sec 2.973+00 3. Carbon-14 1. Total Release Ci 6.063+00 2. Avg. Release Rate uCi/sec 7.793-01 QTR 2 QTR 3 QTR 4 WA 2.34Z-01 5.143+00 3.423-01 1.583+01 2.98Z-02 6.47Z-01 4.303-02 5.023-01 7.04Z-10 0.003+00 8.963-11 0.003+00 0.00Z+00 0.003+00 0.003+00 0.00Z+00 2.693+01 3.283+01 3.421+00 4.133+00 6.113+00 6.063+00 7.77Z-01 7.633-01 9.003-09 9.703-09 1.13Z-09 3.083-10 3.35Z-11 3.353-11 4.223-12 1.063-12 6.323+01 1.463+02 7.96Z+00 4.633+00 4.343+00 2.263+01 5.46Z-01 7.16Z-01 F. Gross Alpha Radioactivity
- 1. Total Release Ci 2. Avg. Release Rate uCi/sec 0.003+00 0.003+00 0.003+00 0.003+00 0.003+00 0.003+00 0.003+00 0.003+00 0.003+00 0.003+00 2 TABLE 1B EFTLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 GASEOUS EFFLUENTS
-ELEVATED RELEASES -CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2013 Units QTR 1 1. Fission and Activation Ganes AR-41 Ci 0.003+00 XZ-133 Ci 1.01E+01 QTR 2 QM 3 QTR 4 1. 011+01 0. 00Z+00 2.151-01 2. 153-01 9.983-03 5.09Z+00 5.103+00 0. 003+00 2.84Z-01 2.84Z-01 TEAR 9.983-03 1. 57Z+01 1.573+01 Totals for Period...
Ci 2. lodines** No Nuclide Activities , .3. Particulates Nalf Life >- 8 days** No Nuclide Activities
- No Nuclide Activities
- 3 TABLE 1B EFFLUENT AMD WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 GASEOUS EFFLUENTS
-ELEVATED RELEASES -BATCH MODE Oconee Nuclear Station Units 1, 2, G 3 REPORT FOR 2013 Units 1. Fission and Activation Gases AR-41 Ci XR-85 Ci XZ-131H Ci X1-133 Ci XB-133M Ci X1-135 ci Totals for Period...
Ci QTR I QTR 2 QTR 3 QTR 4 YEAR 0.001+00 5.591-04 0.001+00 4.611-04 0.003+00 0.003+00 1.021-03 6.193-03 3.873-04 1.911-04 1.20S-02 3.821-05 5.611-06 1.881-02 7.043-10 3. 05-10 1.011-09 2. 941-02 0. 001+00 1.143-04 1.561-02 6. 03Z-05 2.051-04 4.54Z-02 0.001+00 0.oo1+00 0.001+00 1. 72Z-04 8. 10-03 5.021-04 4.821-02 2.111-04 4.931-05 5.72Z-02 9.001-09 0.003+00 9.003-09 3.58Z-02 9.053-03 8.071-04 7.621-02 3.103-04 2.60Z-04 1.22Z-01 9.701-09 3.051-10 1.003-08 2. Iodines 1-131 Ci 0.001+00 1-133 Ci 0.001+00 Totals for Period...
Ci 0.001+00 3. Particulates Half Life CO-58 Ci>- 9 days 0.001+00 0.003+00 0.001+00 3.35Z-11 3.35Z-11 4. Tritium H-3 5. Carbon-14 C-14 Ci 4.563-05 1.851-02 3.563-02 6.541-02 1.20Z-01 Ci 4.241+00 4.261+00 4.241+00 3.043+00 1.581+01 6. Gross Alpha Radioactivity
- No Nuclide Activities
- 4 TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 GASEOUS EFFLUENTS
-GROUND RELEASES -CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 RMPORT FOR 2013 Units QTR 1 1. Fission and Activation Gases** No Nuclide Activities
- .2. Iodines** No Nuclide Activities
.*3. Particulates Half Life >- S days** No Nuclide Activities
- ........QTR2 QTR3 QTR4 YEAR 4. Tritium 9-3 Ci 1.763+00 4.503+00 3.44Z+00 7.393+00 1.71Z+01 5. Carbon-14** No Nuclide Activities
- 6. Gross Alpha Radioactivity t* No Nuclide Activities
- 5 TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 GASEOUS EFFLUENTS
-GROUND RELEASES -BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 RMIORT FOR 2013 Units QTR 1 1. Fission and Activation Ganes** No Nuclide Activities
..2. Iodines** No Nuclide Activities
- .3. Particulates Half Life >- 8 days** No Nuclide Activities
- 6. Gross Alpha Radioactivity 0* No Nuclide Activities
- 0 6 TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 LIQUID EFFLUENTS
-StM4ATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2013 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products 1. Total Release Ci 7.140-04 2. Average Diluted Concentration
- a. Continuous Releases pCi/ml 0.001+00 b. Batch Releases pCi/ml 8.541-11 B. Tritium 1. Total Release Ci 2.731+02 2. Average Diluted Concentration
- a. Continuous Releases pCi/ml 3.693-08 b. Batch Releases pCi/al 3.253-05 C. Dissolved and Entrained Gases 1. Total Release Ci 0.001+00 2. Average Diluted Concentration
- a. Continuous Releases pCi/ml 0.00E+00 b. Batch Releases pCi/ml 0.00Z+00 D. Gross Alpha Radioactivity
- 1. Total Release Ci 0.001+00 2. Average Diluted Concentration
- a. Continuous Releases PCL/ml 0.001+00 b. Batch Releases RCi/Ml 0.001+00 E. Volume of Liquid Waste 1. Continuous Releases liters 6.643+08 2. Batch Releases liters 1.023+06 r. Volume of Dilution Water 1. Continuous Releases liters 8.373+09 2. Batch Releases liters 8.37E+09 2.331-04 8.543-04 0.001+00 0.00E+00 2.761-11 9.981-11 1.48Z+02 1.681+02 2.811-08 4.44Z-08 1.751-05 1.96Z-05 1.391-02 1.571-02 0.003+00 0.001+00 1.62Z-09 4.631-10 4.803+02 1.071+03 1.88Z-08 3.213-08 5.60Z-05 3.153-05 0.001+00 0.001+00 2.113-06 0. 001+00 2.46Z-13 3. 651-03 0. 001+00 4.26Z-10 3.65Z-03 0.001+00 1.083-10 0.001+00 0.001+00 0.00M+00 0.001+00 0.003+00 0.001+00 6.311+08 9.871+08 7.161+05 1.541+06 8.441+09 8.551+09 8.441+09 8.551+09 0.001+00 0.001+00 0.001+00 0.003+00 0.003+00 0.003+00 5.091+08 2.69Z+09 3.88Z+06 7.161+06 8.551+09 3.391+10 8.55Z+09 3.391+10 7 TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 LIQUID EFFLUENTS
-CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2013 Unit QTR 1 QIR 2 QTR 3 QTR 4 TEAR 1. Fission and Activation Products* No Nuclide Activities
- ........
........ ........ ........ ........2. Tritium H-3 Ci 3.33Z-01 2.551-01 4.19--01 1.70Z-01 1.183+00 3. Dissolved and Entrained Gases** No Nuclide Activities
- 4. Gross Alpha Radioactivity
- No Nuclide Activities
- 8 TABLE 2B EFFUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 LIQUID EFFLUENTS
-BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2013 Units QTR 1 1. Fission and Activation Products QTR 2 QTR 3 QTR 4 YEAR AG-109M AG-110M CO-57 CO-Se CO-60 CR-51 CS-137 1F-55 13-59 1-131 MM-54 PS-95 NB-97 SS-124 BB-125 Zn-65 ZR-95 ZR-97 Ci 0.003+00 0.003+00 Ci 2.353-05 3.423-06 Ci 0.003+00 1.153-06 Ci 4.75Z-04 1.01Z-04 Ci 9.04Z-05 1.73Z-05 Ci 0.001+00 0.003+00 Ci 0.003+00 0.003+00 Ci 6.973-05 1.063-04 Ci 0.001+00 0.003+00 Ci 0.003+00 0.003+00 Ci 0.003+00 0.001+00 Ci 2.543-05 0.001+00 Ci 1.403-05 0.003+00 Ci 2.443-06 0.003+00 Ci 0.003+00 4.31Z-06 Ci O.O+00 0.003+00 Ci 0.003+00 0.003+00 Ci 1.403-05 0.003+00 Ci 7.14Z-04 2.333-04 Ci 2.72Z+02 1.48Z+02 0.003+00 4. 15Z-05 0.003+00 3. 00-04 1. 97Z-04 O.O+00 2.563-05 1.59Z-04 0.003+00 1.41Z-06 2.391-05 1. 92Z-05 1.073-05 0. 003+00 3.243-05 1.773-05 1.493-05 1.07Z-05 6.543-04 1.513-05 2.693-04 1. 34Z-05 1. 013-02 1.293-03 1.46Z-04 a.66Z-05 5. 743-04 7.47Z-05 0.003+00 2.561-04 3.423-04 0.003+00 8.343-05 5.242-04 4.861-05 1.03Z-04 0. 00+00 1. 39X-02 1.513-05 3.38Z-04 1. 46Z-05 1. 103-02 1. 59Z-03 1.46Z-04 1. 12Z-04 9.089-04 7.47Z-05 1.41Z-06 2.80Z-04 3.863-04 2.480-05 8.593-05 5.61Z-04 6.621-05 1.103-04 2.493-05 1. 57Z-02 1. 07Z+03 3.653-03 2.113-06 3.65Z-03 Totals for Period...2. Tritium K-3 3. Dissolved and Entrained Gases X-R5 Ci 0.003+00 0.003+00 X1-135 CL 0.003+00 0.003+00 Totals for Period...
Ci 0.003+00 0.003+00 1.67E+02 4.80X+02 0.003+00 3.653-03 2.11Z-06 0.003+00 2.11Z-06 3.653-03 4. Gross Alpha Radioactivity
- No Nuclide Activities
- 9 Attachment 2 Supplemental Information to the Gaseous and Liquid Effluents Report (Pages 10 -13)10 Oconee 2013 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-I 4 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 1.2 1, Rev. 2. Oconee's 2013 Annual Radioactive Effluent Release Report (ARERR) contains estimates of C-14 radioactivity released in 2013, and estimates of public dose resulting from the C-14 effluent.Because the dose contribution of C-I 4 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C- 14 in liquid radioactive waste at Oconee is not required (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-I 4 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 2013 Oconee ARERR a source term scaling factor of 9.4 Ci/GWe-yr is assumed in order to be consistent with the scaling factor used for the Catawba and McGuire ARERRs.Using a source term scaling factor of 9.4 Ci/GWe-yr and actual electric generation (MWe-hrs) from Oconee in 2013 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-1 4", 2004).C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system.Since the PWR operates with a reducing chemistry, most, if not all, of the C- 14 species initially produced are organic (e.g., methane).
As a general rule, C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment (e.g. during shutdown or refueling), a slow transformation from an organic to an inorganic chemical form can occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic with an average of 80% organic with the remainder being CO 2 (Ref. EPRI TR- 105715). For the Oconee 2013 ARERR a value of 80% organic C- 14 is assumed.Public dose estimates from airborne C-14 are performed using dose models in NUREG-0133 and Regulatory Guide 1.109.The dose models and assumptions used are documented in the Oconee ODCM. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released from Oconee in 2013 is well below the IOCFR50, Appendix 1, ALARA design objective (i.e., 15 mrem/yr per unit).11 OCONEE NUCLEAR STATION 2013 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS -STATION A. NOBLE GASES -AIR DOSE 1. CALENDAR QUARTER -GAMA DOSE -15 MEAD 2. CALENDAR QUARTER -BETA DOSE -30 MHAD 3. CALENDAR YEAR -GAMMA DOSE -30 MMAD 4. CALENDAR YEAR -BETA DOSE -60 MMAD B. LIQUID EFFLUENTS
-DOSE 1. CALENDAR QUARTER -TOTAL BODY DOSE -4.5 IPEM 2. CALENDAR QUARTER -ORGAN DOSE -15 HIEM 3. CALENDAR TEAR -TOTAL BODY DOSE -9 mEm 4. CALENDAR YEAR -ORGAN DOSE -30 1451)4 C. IODINE -131 AND 133, TRITIUM, PARTICULATES W/T 1/2 > B DAYS -ORGAN DOSE 1. CALENDAR QUARTER -22.5 MRZM 2. CALENDAR TEAR .45 H4EM II. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS A. GASEOUS EFFLUENTS
-INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL B. LIQUID EFFLUENTS
-INTORMATION FOUND IN 1OCFR20, APPENDIX B, TARLE 2, COLUIMI 2 III. AVERAGE ENERGY -NOT APPLICABLE IV. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY ANALYSES OF SPECIFIC RADIONUCLIDES IN SELECTED OR COMPOSITED SAMPLES AS DESCRIBED IN THE SELECTED LICENSEE COMMITMENTS ARE USED TO DETERMINE THE RADIONUCLIDE COMPOSITION OF THE EFFLUENT.
A
SUMMARY
DESCRIPTION OF THE METHOD USED FOR ESTIMATING OVERALL ERRORS ASSOCIATED WITH RADIOACTIVITY MEASUREMENTS IS PROVIDED AS PART or THE "SUPPLEMENTAL INFORMATION" ATTACHMENT.
V. BATCH RELEASES A. LIQUID EFFLUENT 1. 8.20Z+01 -TOTAL NUMBER OF BATCH RELEASES 2. 1.13Z+04 -TOTAL TIME (141N.) FOR BATCH RELEASES.3. 2.49E+02 -MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.4. 2.11E+02 -AVERAGE TIM (MIN.) FOR A BATCH RELEASE.5. 1.479+02 -MINIMJUM TIME (HIM.) FOR A BATCH RELEASE.6. 1.70Z+04 -AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).B. GASEOUS EFFLUENT 1. 5.10E+01 " TOTAL NUMBER OF BATCH RELEASES.2. 1.11Z+05 -TOTAL TIME (4HI.) FOR BATCH RELEASES.3. 2.89E+04 -MAXIMUM TIME (HIM.) FOR A BATCH RELEASE.4. 2.293+03 a AVERAGE TIME (HIN.) FOR A BATCH RELEASE.5. 4.40÷+01 -MINI)54 TIME (HIM.) FOR A BATCH RELEASE.VI. ABNORMAL RELEASES (SEE "UNPLANNED OUISITE RELEASES" ATTACHMENT) 12 OCONEE NUCLEAR STATION Overall Estimate of Error for Effluent Radioactivity Release Reported The estimated percentage of overall error for both Liquid and Gaseous effluent release data at Oconee Nuclear Station has been determined to be + 30.3%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error: (1) Flow Rate Determining Devices = 120%(2) Counting Statistical Error = +/- 20%(3) Calibration Error = + 10%(4) Calibration Source Error = +/- 2.5%(5) Sample Preparation Error = +/-3%13 Attachment 3 Solid Radioactive Waste Disposal Report (Pages 14 -26)14!
OCONEE NUCLEAR STATION ANNUAL RADWASTE REPORT DUKE ENERGY Oconee Nuclear Station SOLID RADIOACTIVE WASTE SHIPPED TO A DISPOSAL FACILITY 3/2512014 Report Period: January -December 2013 Waste Type NUMBER OF NUMBER OF SHIPMENTS CONTAINERS A-U WASTE CLASS A-S B C CONTAINER BURIAL VOLUME TYPE CU. FT. CU. M.TOTAL ACTIVITY CURIES 1) WASTE FROM LIQUID SYSTEM (A) Dewatered Powdex Resin (B) Dewalered Primary Resin (C) Dewatered Mechanical Filters 1. Prnmary Filter Media 2. Secondary Filter Media (D) Solidified oil. liquid. sludge 2) DRY SOLID WASTE (A) Dry Active Waste -Processor to Burial Metal -Processor to Burial (B) Dry Active Waste to Burial (C) Dry Active Waste Brokered (D) Irradiated Components 0 3 3 1 0 49 3 0 0 67 0 3 3 1 0 0 0 0 1 0 0 1 0 0 0 0 0 3 0 0 0 2 0 0 0 0 a 0 0 0 0 0 3 0 0 0 0 0 0 0 3 General Design TYPE A TYPE A General Design General Design General Design General Design TYPE A TYPE B 0 360.9 360.9 73 0 6394.6 533.96 360.9 0 0 0.00 10.22 10.22 2.54 0.00 181.08 15.12 10.22 0.00 0.00 0.00 222.42 95.53 0.0005 0.00 0.85 0.03 6.83 0.00 0.00 325.66 49 8 3 0 0 67 49 0 0 0 0 TOTAL 50 4 2 8084.24 229.40 a'Page I of I Oconee Nuclear Staton Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Repon Period: January -December 2013 Waste Type: Dewatered Powdox Resin ISOTOPE: % A8kUNWiCE 8 OF LJNERS TO ENVIROCARE 9 OF SHIPMENTS TO ENVIROCARE TOTAL AVE.CR-$1 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 VVALUEI MM-54 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #VALUEI CO-57 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.0 000 0.00 0.00 0.00 000 0.00 0.00 00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 #VALUE1 CO-S 0 0.0000 0.0000D 0.00 0.00 0.00 0.00 0.00 0.00 00 0.00 0.00 0,00 0.00 0.00 0 0 0.00 0.00 0.00 00 0.00 0.00 0.00 0.00 #VALUEI CO-60 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 IVALUEI NO-95 0.0000 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 0.00 WNALUEI ZR-95 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #VALUEI CS-134 0.0000 0.0000 0.30 0.00 0.00 0.00 00 0.00 0.00 00 0. 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.30 VNALUEI RU-103 0.0000 0.0000 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 XVALUEI AG-110rn 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 IVALUEI S-125 0.0000 00000 0.001 0.00 0.00 0.00 0.00 0.00 0.00 0.00 DM 0.00 0. 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 IVALUEI 1-131 0.0000 0.0000 0.00 0.00 0.00 0.00 000 0 00 0.00 0.00 0.00 0.00 0. 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 VVALUEI CS-137 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 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 0.00 0. 0.00 IVALUEI H-3 0.0000 0.0000 0.00 0.00 0.00 0.00 0 0M 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 fVALUEI NI-63 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.0 0.00 0.00 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 IVALUEI FE-55 0.0000 0.0000 0.00 0.00 0.00 0.00 00 00 0.00 0.00 0 0 00 000 M 0.00 000 M00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NWALUEI SR-SO 0.0000 0.0000 0.00 0.00 0.00 0.00 00 000 000 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 fVALUEI TE-125m 0.0000 0.0000 0.00 0.00 0.00 0.00 000 000 000 000 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 VALIJEJ CS-136 0.000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0 .00 G00 0.00 000 .00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 IVALUE[XE-133 0.0000 0.00100 0.00 0.00D 0.00 0.00 000 0.00 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 00 0.00 IVALUEI C-14 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 00 000 000 0.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 fVALUEI PU-241 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.001 .000 0.00 0.00 0.00 0.00 0.00 0 0.00 0.00 0.00 00 0.00 .VALUEI ZN-.S 0.0000 0.0000 0.00 0.00 00 0.00 0.00 0.00 000 00 00 00 00 00 00 0 0.00 0.00 0.00 0.00 0.00 0.00 00 #VALUEI FE-59 0.000D 0 0 .000 0.00 0.00 0.00 00 00 0.00 0.00 00 00 00 00 0.00 0.0 000 0.00 0.00 0.00 0.00 0.00 0.00 .0 IVALUEI S8-124 0.0000 0.0000 0.00 0.00 0.00 00000 0.00 0.00 0 0 000n 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 IVALUEI RU-106 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0 000 00 0.0 00 0.00 0.00 0.00, 0.00 0.00 0.00 0.00 NVALUEI CE-144 0.0000 0.0000 0.00 0.00 000 0.00. 0.00 0.001 0.00 000 000 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 IVALUEI TE-132 0.0000. 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0 .00 00 0,00 0.00 O000 0. 0.00 0.00 0.00 0.00 0.00 0.00 NVALUE!AM-241 0.0000 0.0000 000 000 0.00 0.00 0.00 0.00 0.00 00 000 0.00 000 000 000 000 0.00 0.00 0.00 0.00 0.00 0.00 M.00 OVALUEI TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.30 NWALUEI 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 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES 0 0 0 0 0 0 0 0 0 0 0 D 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 CU. M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 RSR#Page I of I Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Period: Jmnuwy -December 2013 Waste Type: Primeay Resin C OF UNERS SHIPPED TO CNSi 3 ISOTOPE.% A8UNDANCEJUNER
- OF SHIPMENTS TO CNSI 3 TOTAL AVE.AG-110m AM-241 80-7 C-14 CE-144 CM-242 CM-243144 CO-57 CO-58 CO-60 CR-51 CS-134 CS-136 CS-137 FE-55 FE-59 H-3 1-129 1-131 MN-44 W4-95 W61-9 NI1-83 PU-238 PU-239/40 PU-241 RU-106 SS-1 24 SB-125 SN-1 13 SR-ft SR-90 TC-99 TE-125m XE-i 33 ZN-65 ZR-95 0.1729 0.0015 0.0000 1.9470 0.0664 0.0010 0.0017 0.4081 22.5857 5.5919 0.0000 5.6542 0.0000 13.8785 16.6667 0.0000 0.4221 0.0000 0.0000 1.2850 0.2227 0.2165 29.9065 0.0014 0.0000 0.0000 0.0000 0.0960 0.381%0.0000 0.0000 0.0833 0.0000 0.0000 0.0000 0.1822 0.1364 0.1327 0,0002 3.3462 0.1971 0.0803 0.0000 0.0002 0.6192 43.9423 3.8077 0.0000 3.4712 0.0000 8.1635 8.5288 0.0000 0.0104 0.0002 0.0000 1.58m5 0.0990 0.1308 25.3848 0.0000 0.0001 0.0222 0.0000 0.0000 0.0000 0.0000 0.0082 0.0210 0.0042 0.0000 0.0000 0.1625 0.0658 0.0816 0.0003 0.4491 0.2134 0.0244 0.0000 0.0003 0.3420 9.6429 3.3038 0.0000 3.4018 0.0000 9.1071 16.1607 0.0000 0.0222 0.0002 0.0000 1.1339 0.0030 0.3563 55.1786 0.0004 0.0002 0.0072 0.0000 0.0000 0.0795 0.0000 0.0041 0.0384 0.0026 0.0000 0.0000 0.1071 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0,0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000 0.0000 0.0000 0.o000o 0.0000 0.0000 0.0000 0.0000 0.0000 o.o000 0.0000 0.0000 0.0000 0.00W 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 o.00oo 0.0000 o.o000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 O.000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 o.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 o.000o 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.O000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.3872 0.002M 3.7953 2.3575 0.1711 0.0010 0.0022 1.3893 76.1709 12.7032 0.0000 12.5272 0.0000 31.1491 41.3562 0.0000 0.4547 0.0005 0.0000 4.0054 0.3247 0.7036 110.4897 0.0018 0.0003 0.0294 0.0000 0.0960 0.4611 0.0000 0.0123 0.1427 0.0068 0.0000 0.0000 0.4518 0.2022 0.1291 0.0007 12651 0.7858 0.0570 0.0003 0.0007 0.4564 25.3903 4.2344 0.0000 4.1757 0.0000 10.3830 13.7854 0.0000 0.1516 0.0002 0.0000 1.3351 0.1082 0.2345 38.8232 0.0006 0.0001 0.0098 0.0000 0.0320 0.1537 0.0000 0.0041 0.0476 0.0023 0.0000 0.0000 0.1506 0.0874 TOTAL 99.91 99.78 99.51 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 298.70 99.57 CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 CLASS AS 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page I of 2 Oconre WuCi, Station Anua Repert.CURIES &.42 104 112 0 0 0 0 0 0 0' 0 0 0 0 0 0. 0 0 0 0 222.42 CU. FT. 120.3 120.3 120.3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 300.9 CU. M 3.41 3&41 3.41 0.00 0.00 0.00 0.00 0.00 0.00 -ý0.00 0.00 0.00 0.00 0.00- 0.00 0.00 0.00 0.00 0.00 0.00 10.22 RSRP 13-2000 13-2012 13-2027.0.-w. Page 2of 2 OCONEE NUCLEAR STATION SOLID RADW AV vaclear Station Annual Report Report Perod: January -Decenul 2013 Waste tType: Primary filters* OF DRLUM&LINERS TO CNS1 3 ISOTOPE- OF SHIPMENTS TO CNS1 3 TOTAL AVE.AG-110m 0.00050 0.01 0.07 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.08 0.028 AM-241 000280 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.001 BA-140 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 C-14 1.98910 3.52 1.88 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 7.38 2.459 CD-109 0.00000 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 CE-144 0.00000 0-39 0,06 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.45 0151 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 CM-243144 0.00290 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.001 CO-57 0.31300 0.42 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.76 0.253 CO-58 4.86420 10.35 0.03 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 15.24 5.081 CO-60 6.97500 13.73 2.94 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 23.6451 7.88170 CR-51 0.00070 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.05 0.017 CS-134 34.75306 10.11 0.15 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 45.01 15.004 CS-136 0.00000 0.00 0.93 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.93 0.310 CS-137 4006170 13.97 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 54.04 18.012 FE-65 1.38270 12.64 67.79 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 81.81 27.270 FE-59 0.00110 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.002 H-3 0.21480 0.21 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.43 0.142 HG-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 0.00 0.00 0.00 0.00 0.00 0.000 1-129 0.00000 0.16 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.16 0.053 MN-54 0.90740 1.21 0.13 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 0.00 0.00 0.00 0.00 2.24 0.747 NB-94 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 NB-OS 0.00560 0.23 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 0.078 NI-19 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 NI-63 7.28400 31.59 25.88 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 54.75 21.585 PU-238 0.00390 0-00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.001 PU-239 0.00200 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.001 PU-241 0.10190 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 0.034 RU-103 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 RU-106 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 SB-124 0.00000 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.000 S8-125 0.03540 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.04 0.013 SN-i 13 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 SR-80 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 0.00000 0.0000000 SR-90 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 0.004 0.001 TC-99 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 0.0036 0.00120 TE-125mi 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 0.0000 0.00000 XE-133 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 0.0000 0.00000 ZN-65 0.41910 0.16 0.04 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.8240 0.20800 ZR-05 0.19380 1.22 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.4089 0.48963 TOTAL 99.49 09.95 99.89 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 297.38 99.13 Page I of 2 Oconee Nuclear Station Annual Report CLASS C 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 CLASS B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES 18.2 8.23 71.1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 95.53 CU. FT. 120.3 120.3 120.3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 360.9 CU. M 3.406581 3.406581 3.406581 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.21974 RSRN 13-2001 13-2011 13-2W25 M Page 2 of 2 Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION 8OUD RADWASTE REPORT Repor Peded: Jnuary -D04caae 2013 Wists Type: Secoinary Fi a OF CONTAMERS SHPME TO OURATE*(8 OF SHIPMENTS TO OUAATEK 0 OF CONTAMIR SHOWEDl TO CAM I EMVLIROCARE 0 OF 9IIPUENTS TO CF$4I I E)MROCARE 0 MOTOPE TOTAL AVE.AG-I Oli AG-i I08 AM-24i C-14 CE-144 CM-242 CM-243 CAW6 CO-58 CO060 CR-51 CS-i134 CS-136 CS-137 FE-Se FE-5B H-3 1-131 MIN-5 NB-95 NWZ3 PU-238 PU4-239 PU-241 RU-103 RU-10S SO-124 SSB-25 SR-89 SR-90 TE-i25Bm TRU XE-133 ZN-65 0.00 0.65 0.00 4.09 0.05 0.00 0.00 0.00 0.00 2.58 0.00 0.10 0.00 0.65 6.49 0.00 78.57 0.00 0.28 0.00 3.27 0.00 0.00 0.00 0.00 0.38 0.00 2.14 0.00 0.00 0.00 0.00 0.00 008 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0,00 0,00 0.00 0.00 0,00 000 0,00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 000 000 0.00 000 000 0.00 0.00 000 0.00 000 0.00 000 000 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 000 000 000 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 000 0.00 000 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 000 000 0.00 0.00 0.00 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 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 000 0.00 0.00 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 .00 GOO O.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00.00 000 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0OO 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 O.0 000 0.00 000 000 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 000D O.OO OOO 0.00 0.00 0,00 0.00 0.00 000 0.00 O.00 0.00 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 O.O0 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 000 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 0.00 0.00 O.00 0.00 0.00 0.00 0.00 O.OO 0.00 O.OO 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0-00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0-00 MODO 0.00 000 0.00 0.00 0.00 0,00 000 ,00 0.00 0.00 0.00 0-00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 000 0.00 0.00 0.00 0.00 0.00.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 O00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0o0 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.65 0.00 409 0.05 0.00 0.00 0.00 0.00 2.58 0.00 0.10 0.00 0.65 6.49 0.00 78.57 0.00 0.28 0.00 3.2?0.00 0.00 0.00 0.00 0.38 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.08 0.00 0.65 0.00 4.00 0.05 0.00 0.00 000 0.00 2.58 0.00 0.10 0.00 0.65 6.49 0,00 78.57 0.00 0.28 0.00 3.27 0.00 0.00 0.00 0.00 0.38 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.08 TOTAL 99.35 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 97.21 97.21 CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS 8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASSAU 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 CULIES 5.04E-04 0.00i.OO 0 mShipped 73 0 0 CU. M SkQiped 2.0672 0.000 0.00o00 FmI Burmd 0 0 0 0 0 0 0 0.0000 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.000504 0 0 0 0 0 0 0 73 146 0 0 0 0 0 0 0 2.067169 4.1343 0 0 0 0 0 0 0 0 0.000 0.ODD 0.0000 0.GOW 0.0000 0.0000 0.D000 0 cu. WI Burma 0.000 Q.Q 0A 0.0000 MO0.OM RSRX 13-2016 0.0000 0.AM0 0.000 O.ODO D.D 0.000 0.0000 Mi Page 1 of I Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Period: January- December 2013 Wals Type: Soidified OIL U.quid Sludge# OF CONTAINERS SKIPPED 0 0 ISOTOPE.% ABLUNFANCEI.NER
- OF SHIPMENTS TOTAL AVE.CR-51 MN-54 CO-57 CO-58 CO-60 NB-95 ZR-95 CS-134 RU-103 AG-110m SB-125 1-131 CS-137 H4-3 N1-3 FE-55 SR-90 TE-125m CS-138 XE-133 C-14 PU-241 TRU FE-59 SB-124 RU-106 CE-,14 CM-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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 XDMIV0 IDMI10 NOMv/a#DOIVD SDIV101 8OMIVD#wI/o[iON/al 1DOIV0#DIV10I XON1Ol SDIV/0l SDiv/al SOiv/a NDIV/0l#SON/al*DIV/Ol 8Div/al ODiv/al 0OMI10 8Div/al SOMI10 SON/OlI SON/al0#Oiv/al SODN/al#DON/al ODiv/al#DIVIOf TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 "DIV/al CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS 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 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES CU. FT.CU. M RSR#0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Vh3 Page I of I Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Period: Janumy -December 2013 Waste Type: DAW to Processor 0 OF SHIPMENTS FROM ONS TO ENERGY SOLUTIONS* OF SHIPMENTS FROM PROCESSOR TO CLIVE 6 OF SHIPMENTS FROM PROCESSOR TO BARNWELL s 45 0 0 OF CONTAINERS FROM ONS TO ENERGY SOLUTIONS 9 OF CONTAINERS FROM PROCESSOR TO CLIVE I OF CONTAINERS FROM PROCESSOR TO BARNWELL 63 49 0 CU. FT..SHIPPED CURIES SHIPPED CU. FT. DISPOSAL FACILITY CI TO DISPOSAL FACILITY RSR 6 12-2015 12-2017 12-2026 12-2031 12-2038 12-2037 12-2048 12-2060 12-2053 13-2003 13-2004 13-2005 13-2013 13-2014 13-2015 13-2016 13-2017 13-2021 13-2022 13-2023 13-2024 13-2028 13-2029 13-2031 13-2032 13-2033 13-2034 13-2035 13-2038 13-2038 13-2039 13-2040 13-2041 13-2047 13-2048 13-2049 13-2050 0 0 0 0 0 0 0 0 0 1888.8 1888.8 18"8.8 18"8.8 18"8.8 1868.8 1795.8 1868.8 1868.8 934.4 1784 1505 1669.4 1032 1888.8 1868.8 1888.8 1888.8 1868.8 18"8.8 18"8.8 1861.8 18888 18"8.8 18"8.8 1888.8 934.4 934.4 0 0 0 0 0 0 0 a 0 0.0792 0.0910 0.0074 0.00878 0.0101 0.00484 0.00701 0.00427 0.00531 0.01 37 0.0935 5.23 0.00595 0.01 24 0.0181 0.0232 0.032 0.0392 0.047?0.106 0.0482 0.0400 0.0671 0.1 0.0282 0.00475 0.92857 46.92857 119.3571 64.28571 0.05021 0.68 0.4 16 138.8572 259.683 250.6437 182.5143 260.8571 295.2143 372.1239 311.1429 234.5714 211.4288 288 314.9143 680.2471 88.71428 48.05714 242.2857 0 177.7143 209.7857 299.8286 249.7143 202-5714 384.3 285.3 235.0571 234 0 0 0 6.40E-08 1.25E-03 1.50E-02 1.43E-03 7.50E-06 3.60E-06 1.05E-04 0.205144 0.007225 7.90E-02 9.17E-02 6.32E-03 8.76E-03 9.35E-03 4.61E-03 8.58E-03 7.01E-03 5.49E-03 1.29E-02 4.58E-03 9.95E-03 4.24E-04 8.58E-04 5.95E-03 0.00E+00 1.67E-02 2.19E-02 3.17E-02 3.92E-02 4.77E-02 1.02E-01 4.37E-02 Z35E-02 5.71E-02 0.00E+00 0.00E+00 O.OOE+00 4120/2013 3/28/2013 8113/2013 5/1/2013 3/2212013 5/12=2013 4/14/2013 8/412013 11/25/2013 8/2212013 8/2212013 8/20=2013 9/3/2013 9/4r2013 10423/2013 11114/2013 11/25/2013 1215/2013 11/25013 12117/2013 12/17/2013 12/18/2013 TOTAL TOTAICURIES BURIED 479865.4 8.129 8394.59 0.84982 0.860 Page I of 2 Oconee Nuclear Station Annual Report TOTAL CUBIC FEET BURIED TOTAL CUBIC METERS 6394.59 181.08 OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Period: January -December 2013 Waste Type: DAW to Burial* OF SHIPMENTS FROM ONS TO CNSI f OF CONTANERS FROM ONS TO CNSI 3 3 RSR 13-2006 13-2010 13-2020 TOTAL TOTAL CUBIC METERS CUBIC EUI 120.3 120.3 120.3 360.9 2.66 1.63 2.54 A0 0 0 1 1 1 0 0 0 a 6.83 0 3 0 0 10.22 4%Page 2 of 2 Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Pelod: Janumy -December 2013 Warn Type: Metal# OF SHIPMENTS TO PROCESSOR 0 OF CONTANERS TO PROCESSOR* OF SHIPMENTS TO CLIVE 0 OF CONTAINERS TO CLIVE: a 8 CU. FT.. CURIES CU. FT. TO CURIES TO RSR 9 TO PROCESSOR TO PROCESSOR DISPOSAL FACILITY DISPOSAL FACILITY 12-2047 0 0 34.21429 9.75E-04 12-2048 0 0 17.35714 7.87E-04 12-2050 0 0 35.41429 7.93E-03 13-2006 0 0 25.77143 1.05E-03 13-2014 0 0 25.64266 6.9574-4 13-2022 570 0.008C6 268 1.29E-02 13-2023 0 0 43.942W6 7.23E-04 13-2029 0 0 57.65714 1.03E-03 13-2034 0 0 5.92857 9.20E-05 13-2035 0 0 20.02857 3.42E-04 TOTAL 570 0.00886 533.96 0.02589 TOTAL CUBIC METERS 15.12027 a'n Page I of I Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Report Pa ed: Januuy -Decemba 2013 WaII Type: admilad Conwe a OF CONTAINERS SHIPPD TO CUS1MRATEK
% ABUNDANGEMNER
- OF SHaPENM TO GNSVLMATEK 0 0 GOTOPE-TOTAL AWL C-14 CE-114 CM-242 CM-243 CO-68 CO-80 CR-51 CS-134 CS-137 FE-65 FE-IS 1-131 Ne-05 PU-238 PU-241 RU-103 RU-106 58I-124 58,-125 TA-182 TE-125M TRU KE-133 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.W 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 O.W 0.00 0.00 0.00 0.00 0.00 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 0.0 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.W 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.W 0.00 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 0o00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00: 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.66 0.00 0.00 0.00 0.00% 0.00 0.00 0.00 0.00 "0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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 0.06 0.60 0.00 O.0 0..0 0.00 0.00 0.00 0o. 0.00o 0.00 0.00 0.00 0.00 0.00. 0.0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 &0.00 0.001 0.00 0.00 0.00 0.00 0.00 0.0 0.00 0.00 4,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 o0o 000 IViIO 0.00 0.00 .0.00 0.00- OIV/0I 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 OIVIOI 0.00 0.00 0.00 0.00-IOIV0Ji 0.00 0.00 0.00 0.00 MI9VMI 0.00 0.00 0.00 0.00 'IVI01 0.00 0.00 0.00 0.00 0ONIO/I 0.O0 0.00 0.00 0.00 s4V1i0 0.00 0.00 0.000 0.00 sOI0ioi 0.00 0.00 0.00 0.00 I=OI01 0.00 0.00. 0.00 0.00 #fVJOI 0.00 0.00:ý:. 0.00 0.00 9tf1 I0 " 0.00 0.00 0.00 0.00 0I0IO1 0.00 0.00 0.00 0.00 01IV/0l 0.00 0.00 0O .0o o0.0 omt 0.00 0.00 0.00 0.001 ODNMII 0A.00., 0.00. 0.00 0. 00 OVIOI.0.00 0.00 0.00 0.00 sm0(VO 0~o.00 0 0.o 0 .00 0.00WIV/Ci o-oo.......0.oo omo o.W.oo 0.00 0.00 O.00 0.00 90NoiO1 0.0 0.00 0.00 0.0000 0.00 0.00 0.00 0.00 0604101 0.00 0.00 0.00 O.00 OMOI..0.00 0.00 0.00. 0.00 0M(IOI 0.00 o.00 0.00 O.00 mVW101 0.00 0.00 0.00 0.00 l0MN1 0&00 0.00 0.00 0.00 DON/ICl 0.00 0.00 0.00 0.000 #OIVIO1 0.00 0.00 0.00 0.0000 #WOI1 0.00 0.00 0.00 .0.0000 ODIV1OI TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 .:!0.00'.
0.00 0.00 0.00 0.00. 0.00 0.00 0.00 0.00:. 10.00 0.00 ' O.O lOIC 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e 0 MLASS B 0 0 0 0 0 0 0 0 0 0 0 0. 0 0 0 0 0 0 0 0 0 0 0 aASSAS 0 0 0 0 0 0 0 0 Of 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M.ASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 a 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 t~3 Page I of I Attachment 4 Meteorological Data (Pages 27 -36)27 Attachment 4 -Meteorological Data ONS 2013 Lower JFD SECTOR N NNE NE EN E ESE SE SSE S SSW SW WSW W WNW NW NNW E No. No. No. No. No. No. No. No. No. No. No. No. No. No. No. No.A 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 01 0 0 0 0 0 0 0 1 0 0 1 0 0 1.01-1.25 3 0 1 1 1 3 0 2 0 2 3 2 0 1 0 0 1.26-1.50 2 1 2 0 5 01 2 4 8 16 7 4 2 1 2 1.51-2.00 1 4 9 1 7 5 7 5 16 22 66 36 10 9 5 4 2.01-3.00 4 6 14 35 14 5 4 12 24 64 140 60 12 5 3 3 3.01-4.00 2 0 12 29 20 5 0 3 3 18 35 11 5 8 4 2 4.01-5.00 0 2 6 51 0 0 0 0 4 11 2 4 7 4 5 8.01-6.00 0 0 2 0 0 0 0 0 0 0 2 4 0 6 5 2 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 8 16 0 0 8&01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 3 3 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 B 0.46-0.75 0 0 01 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 1 1 0 0 0 0 0 0 0 0 0 0 0 1 o 1.01-1.25 0 1 0 1 1 1 2 0 1 0 4 1 0 0 0 1 1.26-1.50 3 3 1 4 0 0 2 1 2 7 7 4 4 3 5 2 1.51-2.00 3 6 10 9 5 5 11 5 17 13 34 23 7 8 2 3 2.01-3.00 1 2 5 25 13 5 6 7 8 23 45 15 3 3 2 0 3.01-4.00 0 0 10 13 5 0 0 1 6 10 9 3 5 214 1 28 4.01-5.00 0 0 1 4 0 0 0 0 0 1 7 0 1 2 2 1 5.01-6.00 0 0 0 0 0 00 0 0 0 4 1 0 2 1 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 4 4 6 4 0 8.01- 1 10.00 0 01 0 0 0 0 0 0 0 0 0 1 0 1 1 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 C 0.46-0.75 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0.76-1.00 1 0 1 2 1 0 1 0 1 0 2 1 1 1 1 1 1.01-1.25 5 5 2 3 1 1 3 1 1 3 5 5 4 9 5 1 1.26-1.50 5 3 9 1 31 71 2 10 11 11 4 10 1 8 3 1.51-2.00 7 10 11 9 8 2 12 10 15 19 21 11 10 3 6 1 2.01-3.00 3 5 14 23 19 4 9 8 6 2714 8 5 5 1 1 3.01-4.00 0 0 6 21 6 0 0 2 1 12 14 5 1 1 3 1 4.01-5.00 0 1 00 2 1 0 0 0 0 2 13 3 1 3 4 0 5.01-6.00 0 0 0 0 0 0 0 00 0 0 2 1 2 7 7 11 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 5 1 4 5 0 8.01-10.00 0 0 00 0 0 0 0 0 0 0 0 0 0 1 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D O.46-0.75 10 8 5 7 4 3 8 3 3 4 7 6 4 5 15 16 0.76-1.00 45 15 15 12 12 11 20 17 12 15 37 21 31 18 23 39 1.01-1.25 42 16 18 21 25 13 15 27 25 20 21 27 24 17 18 44 1.26-1.50 29 23 32 33 31 18 23 41 31 29 33 35 29 12 15 19 1.51-2.00 17 41 721105 83 40 47 46 41 57 55 38 25 14 13 22 2.01-3.00 12 22 96247 93 25 16 19 34 96 119 6325 273122 29 3.01-4.00 7 3 20 56 14 0 0 3 8 47 57 42 22 29 29 12 4.01-5.00 3 2 4 9 7 0 0 0 2 3 34 32 23 38 20 6 5.01-6.00 0 0 0 0 0 0 0 1 00 1 14 20 17 14 15 3 6.01-8.00 1 0 0 0 0 0 0 0 01 0 7 14 16 7 3 2 8.01-10.00 0 0 0 0 0 0 0 0 01 0 0 1 0 0 0 1 10.01-Max 0 0 (] 0 00 0 00 0 0 00 0 0 0 E 0.46-0.75 30 22 16 17 11 11 8 8 10 10 5 14 25 31 20 19 0.76-1.00 87 47 44 21 27 35 20 17 29 33 36 32 42 45 91 59 1.01-1.25 40 37 32 29 30 19 33 231 2933 1817 395554 1.26-1.50 15 22 27 32 46 29 41 34 22 24 27 12 11 17 36 33 1.51-2.00 9 18 34 47 49 26 46 51 38 20 25 18 17 13 12 12 2.01-3.00 7 3 10 22 13 9 12 5 10 27 331 17 8 8 6 8 3.01-4.00 0 0f 0 0 0 0 0 0 0 1 9 7 7 2 1 0 4.01-5.00 0 0 0 0 1 0 1 0 0 0 3 2 2 1 1 0 5.01-6.00 0 0 0 0 00 0 0 0 0 0 0 0 2 0 0 03 0.01-8.00 0 01 01 0 0 01 0 0 0 0 0 3 0 0 0 0 8.01-10.00 0 0 0 0 0 01 0 0 0 0 0 0 0 0 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 O0 0 0 0 0 0 0 F 0.46-.0.75 1 2 1 1 0 1 1 0 1 0 3 2 5 11 3 0 0.76-1.00 3 2 1 3 2 1 0 1 2 2 4 7 8 23 24 6 1.01-1.25 0 0 2 1 2 4 2 1 0 4 2 3 1 10 19 4 1.26-1.50 0 2 4 0 2 4 0 1 1 0 1 2 2 6 22 3 1.51-2.00 0 0 0 0 4 4 91 0 1 0 0 1 0 0 4 2 30 2.01-3.00 0 0 0 0 2 21 0 0 0 1 0 0 0 0 1 3.01-4.00 0 0 0 0 0 0 0 0 1 0 0 2 0 0 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0l 0 0 0 0 0 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 01 8.01-8.00 0 0 0 0 0 0 .0 0 0 0 0 0 0 0 0 0 8.01-10.00 00 0000 00 0 0 0 0 0o0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 01 11 0 2 0.76-1.00 0 0 0 0 0 1 0 0 0 0 1 0 1 6 1 1 1.01-1.25 0 0 0 0 0 0 0 0 1 0 0 0 0 1 2 01 1.26-1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 1 4 1 1.51-2.00 0 0 0 0 0 0 0 O0 0 0 0 0 0 0 1 0 2.01-3.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3.01-4.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0i 0 0 6.01-8.00 000000000 00 00 00 0 8.01-10.00 0 0 0 0 0 0 0Ol 0 0 0 0 0 0 0 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 31 Attachment 4 -Meteorological Data ONS 2013 Upper JFD SECTOR N NNE NE EN E ESE SE SSE SSSSW SW WSW W WNWINWNNW E No. No. No. No. No. No. No. No. No. No. No. No. No. No. No. No.A 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 00 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 1 2 0 0 0 01 1 1 1 1 1 0 0 1.26-1.50 1 0 1 0 0 3 0 1 0 2 7 2 1 0 0 1 1.51-2.00 1 2 1 3 1 0 4 0 5 13 20 8 7 5 2 2.01-3.00 2 3 7 8 4 5 9 3 24 60 77 36 3 3 2 1 3.01-4.00 1 2 9 12 7 01 5 11 67 47 4 0 0 2 4.01-5.00 3 3 10 20 13 40 0 0 5 40 17 1 1 2 0 1 5.01-6.00 3 3 12 19 5 0 0 0 2 22 15 3 3 5 1 2 6.01-8.00 0 5 71 15 4 0 0 1 3 10 13 7 5 15 11 1 6.01-10.00 0 1 0 0 0 0 0 0 0 1 8 3 4 13 4 0 10.01-Max 0 0 0 0 0 0 0 00 0 1 8 4 4 0 0 B 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 1 0 0 1 0 0 0 0 1 3 0 1 0 0 0 32 1.26-1.50 0 0 1 1 0 1 0 1 0 1 6 2 2 3 4 1 1.51-2.00 5 4 2 0 2 3 0 1 5 7 16 5 4 2 0 5 2.01-3.00 0 5 11 14 6 7 3 4 9 25 241 6 0 2 1 1 3.01-4.00 0 1 5 7 11 22010 24 14 0 4 0 0 0 4.01-5.00 0 1 2 9 1 1 0 0 5 16 10 1 4 1 0 0 5.01-6.00 0 2 6 8 4 0 0 0 3 5 4 3 2 21 2 0 6.01-8.00 0 2 3 10 0 0 0 1 0 5 3 2 1 2 5 0 8.01-10.00 0 0 0 0 0 0 0 0 0 1 3 6 3 101 1 0 10.01-Max 0 0 01 0 0 01 0 0 0 0 0 3 0 2 0 01 C 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 1 0 0 1 1 0 0 0 o 1 0 0 0 1.01-1-25 10 1 1 1 0 0 1 0 0 3 2 1 5 2 3 1 1.26-1.50 2 7 3 3 1 2 0 11 1 2 6 5 4 7 1 2 1.51-2.00 3 10 6 4 4 6 6 3 2 11 8 7 7 7 2 3 2.01-3.00 1 7 9 6 12 6 10 9 11 18 17 5 3 1 2 2 3.01-4.00 1 3 8 9 10 0 3 0 5 17 6 1 2 1 1 1 4.01-5.00 0 2 4 6 7 1 0 01 3 11 3 2 2 1 1 0 5.01-8.00 0 0 10 11 3 0 0 0 2 7 7 1 1 4 2 01 6.01-8.00 0 0 3121 00( 1 0 516 2 2 10 3 0 33 8.01-10.00 0 0 0 0 0 0 0 0 0 1 5 6 2 11 3 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 2 0 1 2 0 D 0.46-0.75 0 1 0 0 1 1 1 0 0 0 1 0 1 0 0 0 0.76-1.00 5 4 5 0 41 1 1 6 4 6 8 6 4 8 6 8 1.01-1.25 9 15 7 3 6 4 5 1 8 4 11 9 9 6 19 101 1.28-1.50 19 8 6 3 2 5 8 8 81 10 14 18 18 6 19 21 1.51-2.00 62 25 15 17 15 11 12 21 18 28 265 26 25 19 32 49 2.01-3.00 62 53 91 58 46 20 21 37 51 55 54 33 33 11 25 49 3.01-4.00 15 28 96 95 53 16 13 12 34 42 68 20 12 21 26 13 4.01-5.00 5 8 84 92 25 9 4 7 26 45 47 25 13 22 23 3 5.01-6.00 1 5 37 51 11 001 6 5 22 50 28 18 28 19 6 6.01-8.00 4 4 13 28 2 0 0 2 8 24 75 50 17 52 20 6 8.01-10.00 0 .0 0 1 0 0 0 0 0 6 33 28 8 18 9 0 10.01-Max 1 01 00 0 00 0 0 0 0 0 10 10 0 2 1 0 E 0.40-0.75 1 1 0 3 0 1 0 1 1 2 1 1 1 3 4 4 0.76-1.00 10 10 3 3 0 4 4 6 5 1 4 4 9 10 14 12 1.01-1.25 15 13 4 1 3 2 3 1 6 4 12 11 14 21 21 24 1.26-1.50 48 24 11 10 3 8 4 2 4 10 3 13 17 26 31 29 1.51-2.00 111 40 32 12 11 15 5 11 10 15 21 24 27 37 50 75 34 2.01-3.00 138 97 63 33 24 2318 12 34 41 45 40 26 22 26 71 3.01-4.00 11 12 34 33 20 12 9 16 30 23 34 8 3 8 9 12 4.01-5.00 5 0 12 13 141 2 0 11 13 17 18 6 5 8 10 3 5.01-6.00 1 0 1 4 2 00 1 2 7 16 7 8 3 2 2 0.01-8.00 0 0 0 0 3 0 0 0 0 2 19 4 3 3 1 0 8.01-10.00 0 0 0 0 0 01 0 0 0 1 2 2 0 0 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 3 0 0 0 0 0 F 0.46-0.75 0 0 01 0 0 1 0 0 0 1 0 0 0 0 0.76-1.00 0 0 1 0 0 1 2 3 2 10 01 1 0 0 1.01-1.25 2 0 1 2 0 1 0 1 2 1 2 0 1 2 3 2 1.26-1.50 6 3 1 3 2 0 2 2 1 0 1 0 1 1 3 2 1.51-2.00 15 14 5 1 0 1 0 3 3 2 3 2 2 01 5 7 2.01-3.00 24 21 6 5 3 8 1 1 6 1 7 4 3 01 8 3.01-4.00 2 2 2 2 4 2 2 2 7 0 1 1 0 1 0 1 4.01-5.00 0 01 0 0 2 0 0 1 0 0 01 0 01 1 0 2 5.01-6.00 0 0 0 0 0 0 0 0 1 0 0 1 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 8.01-10.50 0 03 0 0 0 0 0 0 0 0 1 0 0 0 0 0 10.01-Max 0 0 0 0 0 0 a 0 0 0 0 0 0 0 0 35 Q 0.46-0.75 0 O 0 0 0 01 0 0 01 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 2 1.26-1.50 0 0 0 0 0 0 0 1 0 0 0 0 0 1 0 1 1.51-2.00 1 0 0 0 2 1 0 0 0 0 0 0 0 1 1 1 2.01-3.00 0 0 o 0 0 1 0 4 5 1 o 0 0 0 0 0 3.01-4.00 0 0 0 0 0 0 0 1 1 0 0 0 0 0 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0o 0 0 0 0 0 0 0 10.01-Max 0 0 0 0 0] 0 0 0 0 0 0 0 0 0 0 0 36 Attachment 5 Unplanned Offsite Releases Unplanned release of 1B Gaseous Waste Decay Tank (GWDT)Event Summary: On 8/2/13 Operations identified a pressure decrease in Unit 1 GWDT-B of 3.6 psig during the period of 7/16/13 through 8/2/13. Noble gas monitors 1 RIA 37 (GWD Effluent Monitor) and 1 RIA 45 (Unit Vent) showed no increase above normal background during the period A leak investigation was initiated by Operations and Engineering and was unable to determine the source of the slow leak.Unit 1 GWDT-B was sampled on 8/3/13 to account for the noble gas activity released to the Unit 1 Vent. The sample of Unit 1 WGDT-B in-service tank was used to evaluate radioactive gas released to the Unit 1 Vent. The total Noble gas activity of the unplanned release (7.24E-05 Curies) was included in Gaseous Waste Release (GWR) # 2013049. GWR 2013049 accounts for the both the unplanned and normal release of Unit 1 WGDT-B by using the isolated pressure on 7/16/13 to determine the volume released.Safety Significance:
The health and safety of the public were not compromised by this event. The total activity released was 7.24E-05 Curies. Calculated dose and dose rates to the Total Body, Skin, Gamma Air, and Beta Air were all well below the limits specified by Selected Licensee Commitments (Page 37)37 Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)(Pages 38 -50)38 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 GASEOUS ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 1lth Quarter 2013 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS -Quarter 1 2013 Critical Critical Dose Limit Max % of Period-Limit Age Organ (erom) (orme) Limit Q1 -Maximum Organ Dose CHILD BONE 9.023-02 2.251+01 4.013-01 Maximum Organ Dose Receptor Location:
1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)Nuclide Percentage C-14 1.00Z+02-NOBLE GAS DOSE LIMIT ANALYSIS Quarter 1 2013 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q1 -Maximum Gamma Air Dose 1.893-04 1.503+01 1.263-03 Maximum Gamma Air Dose Receptor Location:
1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage XZ-133 1.00E+02 Ql -Maximum Beta Air Dose 5.623-04 3.00E+01 1.87E-03 Maximum Beta Air Dose Receptor Location:
1.0 Mile SW Major Contributors (5% or greater to total)Nuclide Percentage XZ-133 1.00E+02 39 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 GASEOUS ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 2- Qarter 2013 IODINE, 33, and PARTICULATE DOSE LIMIT ANALYSISe, -Quarter 2 2013 Critical Critical Dome Limit Max % of Period-Limit Age Organ (tam) (Mura) Limit Q2 -Maximum Organ Dose CHILD SOME 9.093-02 2.253+01 4.043-01 Maximum Organ Dose Receptor Location:
1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)Nuclide Percentage C-24 1.009+02-NOBLE GAS DOSE LIMIT ANALYSI Quarter 2 2013 -Dome Limit I of Period-Limit (mrad) (nucad) Limit Q2 -Maximum Gamma Air Done 7.31Z-06 1.503+01 4.870-05 Maximum Gamma Air Done Receptor Location:
1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage AR-41 4.18E+01 xM-133 5.823+01 Q2 -Maximum Beta Air Done 1.383-05 3.003+01 4.593-05 Maximum Beta Air Dose Receptor Location:
1.0 Mile SW Major Contributors (5% or greater to total)Nuclide Percentage7.81Z+00)M-133 9.18E+01 40 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 GASEOUS ANNUAL DOSE SUb24ARY REPORT Oconee Nuclear Station Units 1, 2, & 3 3EA Quarter 2013-IODINE, 83, and PARTICULATE DOSE LIMIT ANALYSIS -Quarter 3 2013 -Critical Critical Done Limit Max % of Period-Limit Age Organ (Drom) (axon) Limit Q3 -Maximum Orgam Dome CHILD BONE 9.03Z-02 2.25E+01 4.01E-01 Maximum Organ Dome Receptor Location:
1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Nuolide C-14 Contributors (5% or greater to total)Percentage 1.005+02 NOBLE GAB DOSE LIMIT ANALTSIS Quarter 3 2013 Dome Limit S of Period-Limit (mrad) (mrad) Limit Q3 -Maximum Gamma Air Dose 1.15Z-04 1.505+01 7.66Z-04 Maximum Gamma Air Dome Receptor Location:
1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage AR-41 1.69E+01 XE-133 8.31E+01 Q3 -Maxim Beta Air Dome 2.915-04 3.00E+01 9.70Z-04 Maximum Beta Air Dose Receptor Location:
1.0 Mile SW Major Contributors Nuclide XE-133 (5% or greater to total)Percentage 9.76Z+01 41 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 GASEOUS ANNUAL DOSE SUMMJARY REPORT Oconee Nuclear Station Units 1, 2, & 3 41A Quarter 2013-IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS -Quarter 4 2013 Critical Critical Dose Limit Max % of Period-Limit Age Organ (Eren) (arLe) Limit Q4 -Maximum Organ Dose CHILD BONE 6.46Z-02 2.253+01 2.873-01 Maximum Organ Dome Receptor Location:
1.0 Mile 8M Critiocl Pathway: Vegetation Major Isotopic Contributors (s5 or greater to total)Nud ide Percentage C-14 1.003+02 NOBLE GAS DOSE LIMIT ANALYSIS Quarter 4 2013 -Dose Limit % of Period-Limit (urad) (mrad) Limit Q4 -Maximum Gamae Air Dose 6.33Z-06 1.503+01 4.22Z-05 Maximum Gamma Air Dome Receptor Location:
1.0 Mile SW Major Isotopio Contributors (5% or greater to total)Nuolids Percentage XE-133 9.83E+01 Q4 -Maximum Beta Air Dose 1.94Z-05 3.00E+01 6.489-05 Maximum Beta Air Dose Receptor Location:
1.0 Mile SW Major Contributors (5% or greater to total)Nuolide Percentage
- m-133 9.532+01 42 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 GASEOUS ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, a 3 ANNUAL 2013-IODINE, B3, and PARTICULATE DOSE LIMIT ANALYSIS Annual 2013 Critical Critical Dose Limit Max % of Period-Limit Age Organ (ores) (arem) Limit Yr -Maximum Organ Dose CRILD BONE 3.36Z-01 4.50Z+01 1.41E-01 Maximum Organ Dose Receptor Location:
1.0 Kilo SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)Nuclide Percentage C-14 1.003+02 NOBLE GAS DOSE LIMIT ANALYSIS Annual 2013 Dose Limit % of Period-Limit (mrad) (mrad) Limit Tr -Maximum Gamma Air Dose 3.173-04 3.003+01 1.063-03 Maximum Gamma Air Dose Receptor Location:
1.0 Mile SW Major Isotopic Contributors (5% or greater to total)Nuclide Percentage AR-41 7.10E+00 XE-133 9.293+01 Yr -Maximum Beta Air Dose 8.863-04 6.00E+01 1.48E-03 Maximum Beta Air Dose Receptor Location:
1.0 Mile SW Major Contributors (S% or greater to total)Nuolide Percentage XE-133 9.90Z+01 43 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 LIQUID ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 1111 Quarter 2013-BATCH LIQUID RELEASES Quarter 1 2013 Critical Critical Dome Limit Max P of Period-Limit Age Organ (urae) (arem) Limit QI -Maximum Organ Dose ADULT GI-LLI 4.64Z-02 1.50Z+01 3.09Z-01 Q1 -Total Body Dome CHILD 3.789-02 4.50R+00 8.412-01 Maximum Organ Critical Pathway: Iresh Water Irmh Major Isotopic Contributors (5% or greater to total)Nuolide Percentage v-3 7.833+01 NB-95 2.093+01 Total Body Critical Pathway: Potable Water Major Imotopic Contributors (5% or greater to total)Nuclide Percentage S-3 9.98E+01-CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 1 2023 Critical Critical Dose Limit Max % of Period-Limit Age Organ (urea) (mrea) Limit Qi -Maximum Organ Dome CHILD LIVER 4.283-05 1.50+01 2.86z-04 Ql -Total Body Dome CHILD 4.289-05 4.50X+00 9.52z-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuolide Percentage n-3 1.009+02 Total Body Critical Pathway: Potable Water Major Imotopic Contributors (5% or greater to total)Nuclide Percentage n-3 1.00Z+02 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 LIQUID ANNUAL DOSE SUMMIARY REPORT Oconee Nuclear Station Units 1, 2, & 3 2E Quarter 2013-BATCH LIQUID RELEASES Period-Limit Q2 -Maimum Organ Dose 02 -Total Body Dose Critical age CHILD CHILD Critical Organ GI-LLI Dome 2.062-02 2.06E-02 Quarter 2 2013 =Limit Max % of (,rom) Limit 1.503+01 1.373-01 4.503+00 1.37Z-01 Maximum Organ Critical Pathway: Potable Water Major Isotopio Contributors (5%Nuclide Percentage B-3 9.99Z+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5%Nuclida Percentage H-3 9.99E+01 or greater to total)or greater to total)-CONTINUOUS LIQUID RELEASES (CTP 3)Critical Period-Limit Age Q2 -Maximum Organ Dooe CHILD Q2 -Total Body Dose CHILD Quarter 2 Critical Dose Limit Organ (aref) (area)LIVER 3.293-05 1.50E+01 3.29Z-05 4.50Z+00 2013 -Max I of Limit 2.203-04 7.32--04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage 3-3 1.00Z+02 Total Body Critical Pathway: Potable Water Major Isotopio Contributors (5% or greater to total)Nuolide Percentage H-3 1.00E+02 45 ZEFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 LIQUID ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 3_- Quarter 2013-BATCH LIQUID RELEASES Period-Limit Q3 -Maximum Organ Dose Q3 -Total Body Dome Critical Age ADULT ADULT Critical Organ 01-LLU Quarter 3 Dose Limit (area) (arem)3.05Z-02 1.501+01 2.49Z-02 4.50+00 2013 Has % of T.4.:4 t 2.03Z-01 5.522-01 Maximum Organ Critical Pathway: Fresh Water aish Major Isotopic Contributors (5 or greater to total)Nuclide Percentage n-3 7.329+01 5-g95 2.419+01 Total Body Critical Pathway: Potable Water Major isotopic Contributors (50 or greater to total)Nuclide Percentage 8-3 8.99Z+01 CS-137 9.09X+00 CONTINUOUS LIQUID RZLZASES (CTP 3)Critical Period-Limit Age Q3 -Maximum Organ Dome CHILD Q3 -Total Body Doze CNILD Quarter 3 Critical Dose Limit Organ (area) (arem)LIVER 5.26Z-05 1.501+01 5.261-0S 4.50+00 2013 Mas I of Limit 3.51-04 1.17E-03 Maximum Organ Critical Pathway: Potable Water Major isotopic Contributors (54 or greater to total)Wuclida Percentage H-3 1.009+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (54 or greater to total)Nuclids Percentage x-3 1.001+02 46 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 LIQUID ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 41b Quarter 2013-BATCH LIQUID RELEASES *Period-Limit Q4 -Maximum Organ Dome Q4 -Total Body DoSe Critical Ago ADULT ADULT Critical Organ G!-LLI Dose (m.rem)2.03Z-01 7.323-02 Quarter 4 2013 -Limit Max % of (Owem) Limit 1.50E+01 1.35E+00 4.503+00 1.633+00 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)Nuclide Percentage 3-3 3.153+01 MB-93 6.42Z+01 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)Nuolide Percentage B-3 8.14Z+01 CS-137 1.052+01 CONTINUOUS LIQUID RELEASES (CTP 3)Critical Period-Limit Age Q4 -Maximum Organ Dome CHILD Q4 -Total Body Dose CHILD Quarter 4 Critical Dose Limi t Organ (marm) (mrea)LIVER 2.23Z-05 1.50E+01 2.23Z-05 4.50Z+00 2013 -Max % of Limit 1.48E-04 4.953-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuolide Percentage H-3 1.003+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage u-3 1.003+02 47 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/13 TO 1/1/14 LIQUID ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 ANNUAL 2013-BATCH LIQUID RELEASES -Period-Limit Yr -Maxiisum Organ Does Yr -Total Body Dose Critical Age ADULT ADULT Critical Organ GI-LLI DOs*(area)3.003-01 1.543-01 Annual 2013 Limit 14. % of (arem) Limit 3.003+01 1.003+00 9.00E+00 1.72t+00 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (SO or greater to total)Nuclide Percentage n-3 4.75E+01 NS-95 4.92E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5S or greater to total)Nuclide Percentage H-3 9.24E+01 Cs-137 6.43E+00-CONTINUOUS LIQUID RELEASES (CTP 3)Critical Period-Limit Age Yr -Maximum Organ Dose CHILD Yr -Total Body Dome CHILD-" Annual 2013 Critical Done Limit Max % of Organ (Mrea) (mrem) Limit LIVER 1.51Z-04 3.003+01 5.043-04 1.511-04 9.00E+00 1.68Z-03 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)Nuclide Percentage x-3 1.001+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (50 or greater to total)Nuclide Percentage H-3 1.00E+02 48 Oconee Nuclear Station 2013 Radioactive Effluent and ISFSI 40CFR190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40CFR190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems.
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-14 Supplemental Information", contained in the ARERR for further information).
The combined dose to a maximum exposed individual from Oconee's effluent releases and direct and air-scatter dose from Oconee's ISFSI is below 40CFR190 limits as shown by the following summary: 1. 2013 Oconee 40CFRI90 Effluent Dose Summary The 40CFRI90 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 = 2.66E-01 mrem Maximum Location:
1.0 Mile, Southwest Sector Critical Age: Child Gas non-NG Contribution:
42.67%Gas NG Contribution:
0.10%Liquid Contribution:
57.23%Maximum Organ (other than TB) Dose = 3.52E-01 mrem Maximum Location:
1.0 Mile, Southwest Sector Critical Age: Child Critical Organ: Bone Gas Contribution:
95.45%Liquid Contribution:
4.55%1I. 2013 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 I OCFR72.212 Written Evaluations" report. As discussed in the report, the dose rate at 500 meters is 6.84 mrem per year. The nearest resident from the Oconee ISFSI is -1600 meters so the dose rate at the nearest resident location would be much less than 6.84 mrem per year.The following excerpt, "C. I 0CFR72.212(b)(2)(i)(C)-
Requirements of 72.104", from the"Oconee Nuclear Site I OCFR72.212 Written Evaluations" report is provided to document the method used to estimate the Oconee ISFSI dose to the nearest "real individual".
49 C. 10CFR72.212(b)(2Xi)(C)-
Requirements of 72.104" ...the requirements of§ 72.104 have been met. " 10 CFR 72.104, as clarified by ISG-13, stipulates that the licensee perform dose evaluations which establish that any real individual beyond the controlled area boundary not sustain a dose equivalent in excess of 0.25 mSv (25 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 cooling time) of existing fuel in Phases I -V of the Oconee ISFSI, together with the characteristics of assumed "design basis" fuel in Phase VI of the Oconee ISFSI. Calculation OSC-8675 develops the radiation source terms used in subsequent shielding and skyshine calculations using the SCALE Code System.More specifically, the SAS2 Module of the SCALE Code System was used to create a problem-dependent pin-cell model for the purpose of building cell- weighted, multigroup cross section sets for use in subsequent depletion calculations.
The ORIGEN-S Module of the SCALE Code System was used to perform the fuel depletion and characterization calculations using the cross section sets created by SAS2. These characterization calculations yielded the photon and neutron source terms to be used as input to subsequent shielding calculations.
As mentioned above, problem-dependent cross section sets were developed for these analyses since ORIGEN-S was used within the SAS2 sequence.
Duke Energy Corporation Radiological Engineering is experienced in the use of the SCALE Code System, and the SCALE Code System is installed and maintained under the purview of the pertinent software and data quality assurance program.The results of the radiation source term calculation were used as input to Calculation OSC-8706 to evaluate the shielding characteristics of a single Horizontal Storage Module. The MCNP Monte Carlo particle transport computer code 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 contains the verification and validation for MCNP5, while SDQA-30269-NGO documents the quality control measures in place for MCNP5).Calculation OSC-8716 uses the surface flux files developed in OSC-8706 in a repeating array representing all of the Horizontal Storage Modules in the ISFSI, including Phase VI fully loaded with spent fuel. 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 ISFSL.Calculation OSC-8716 Table 23. 1-1, summarizes dose rate versus distance, showing a dose rate of 6.84 mRem per year at 500 meters, which is the longest distance at which results converge.
The closest residence to the ISFSI is in the SW-SSW direction approximately I mile (-1600 meters) from the ISFSI, or 1.36 miles from the centerline of the site. This is conservatively farther than the distance used for computation of dose rates. The 2009 40CFRI90 Uranium Fuel Cycle Dose Calculation Results for the ONS site show a maximum total body dose of 0.0754 mrem per year. The total dose rate from all operations to the nearest real individual is therefore less than 7 mRem per year.These calculations need not consider any effluent from Phase VI. The Phase VI HSMs use the NUHOMS-24PHB DSCs, which are designed as "leak-tight".
Per Appendix N, Section N.11.2.8 of the NUHOMS FSAR3 accidental releases are not credible.50 Attachment 7 Revisions to UFSAR Section 16.11 Radiological Effluent Controls SLC Change 2013-02 revised the Lower Limits of Detection (LLD) equation in SLC 16.11.4, Operational Safety Review, and SLC16.11.6, Radiological Environmental Monitoring.
The LLD equation currently in SLCs is a simplification of the technically correct full equation.
The simplified equation errs in the non-conservative direction when background count rates are low.(Pages 51 -81)51 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective Pages Page Revision Date LOEP 1 04/21/14 LOEP 2 02/10/14 LOEP 3 04/21/14 LOEP 4 04/08/14 LOEP 5 12/31/12 LOEP 6 02/10/14 LOEP 7 11/08/13 LOEP 8 11/08/13 LOEP 9 11/14/13 LOEP 10 11/14/13 LOEP 11 11/08/13 LOEP 12 11/08/13 LOEP 13 11/08/13 16.0-1 02/10/14 16.0-2 02/10/14 16.0-3 02/10/14 16.0-4 02/10/14 16.0-5 02/10/14 16.0-6 02/10/14 16.1-1 10/15/07 16.2-1 3/27/99 16.2-2 3/27/99 16.2-3 3/27/99 16.3-1 3/27/99 16.5.1-1 11/26/12 16.5.1-2 11/26/12 16.5.1-3 11/26/12 16.5.2-1 11/15/12 16.5.2-2 11/15/12 16.5.2-3 11/15/12 16.5.2-4 Delete 5/11/99 16.5.2-5 Delete 5/11/99 16.5.3-1 02/21/07 16.5.3-2 02/21/07 16.5.3-3 02/21/07 16.5.4-1 11/15/12 16.5.4-2 11/15/12 16.5.5-1 Delete 5/16/09 16.5.5-2 Delete 5/16/09 16.5.5-3 Delete 5/16/09 16.5.5-4 Delete 5/16/09 LOEP 1 52 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective Pages Page Revision Date 16.5.5-5 Delete 5/16/09 16.5.6-1 Delete 02/10/14 16.5.6-2 Delete 02/10/14 16.5.7-1 12/13/06 16.5.7-2 12/13/06 16.5.7-3 12/13/06 16.5.7-4 12/13/06 16.5.7-5 12/13/06 16.5.7-6 12/13/06 16.5.8-1 01/31/07 16.5.8-2 01/31/07 16.5.8-3 01/31/07 16.5.8-4 01/31/07 16.5.8-5 01/31/07 16.5.8a-1 5/19/05 16.5.8a-2 5/19/05 (Delete)16.5.8a-3 5/19/05 (Delete)16.5.9-1 11/15/12 16.5.9-2 11/15/12 16.5.10-1 10/8/03 16.5.10-2 10/8/03 16.5.11-1 1/31/00 16.5.12-1 3/27/99 16.5.13-1 3/27/99 16.5.13-2 12/01/99 16.5.13-3 12/01/99 16.6.1-1 07/23/12 16.6.1-2 07/23/12 16.6.1-3 07/23/12 16.6.1-4 07/23/12 16.6.1-5 Delete 16.6.2-1 01/31/07 16.6.2-2 01/31/07 16.6.2-3 01/31/07 16.6.2-4 01/31/07 16.6.2-5 01/31/07 16.6.2-6 01/31/07 16.6.2-7 01/31/07 16.6.2-8 Delete 16.6.2-9 Delete 16.6.2-10 Delete LOEP 2 53 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective Pages Page Revision Date 16.6.2-11 Delete 16.6.2-12 Delete 16.6.3-1 11/15/12 16.6.4-1 11/15/12 16.6.4-2 11/15/12 16.6.4-3 11/15/12 16.6.4-4 11/15/12 16.6.4-5 11/15/12 16.6.4-6 11/15/12 16.6.5-1 12/14/00 16.6.6-1 11/15/12 16.6.7-1 3/27/99 16.6.8-1 3/27/99 16.6.9-1 11/15/12 16.6.9-2 11/15/12 16.6.10-1 11/15/12 16.6.10-2 11/15/12 16.6.10-3 11/15/12 16.6.11-1 11/15/12 16.6.11-2 11/15/12 16.6.12-1 11/15/12 16.6.12-2 11/15/12 16.6.12-3 11/15/12 16.6.12-4 5/17/05 (Delete)16.6.12-5 Delete 16.6.12-6 Delete 16.6.12-7 Delete 16.6.13-1 03/31/08 16.6.13-2 03/31/08 16.6.13-3 03/31/08 16.6.14-1 04/21/14 16.6.14-2 04/21/14 16.6.14-3 04/21/14 16.6.14-4 04/21/14 16.6.15-1 11/15/12 16.6.15-2 11/15/12 16.7.1-1 11/15/12 16.7.1-2 11/15/12 16.7.2-1 11/15/12 16.7.2-2 11/15/12 16.7.2-3 11/15/12 LOEP 3 54 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective Pages Pa e Revision Date 16.7.3-1 11/15/12 16.7.3-2 11/15/12 16.7.4-1 7/14/05 16.7.4-2 7/14/05 16.7.4-3 7/14/05 16.7.5-1 11/15/12 16.7.5-2 11/15/12 16.7.5-3 11/15/12 16.7.5-4 11/15/12 16.7.6-1 04/08/14 16.7.6-2 04/08/14 16.7.6-3 04/08/14 16.7.6-4 04/08/14 16.7.7-1 11/15/12 16.7.7-2 11/15/12 16.7.8-1 3/27/99 16.7.8-2 3/27/99 16.7.9-1 10/23/03 16.7.10-1 11/15/12 16.7.10-2 11/15/12 16.7.11-1 11/15/12 16.7.11-2 11/15/12 16.7.11-3 11/15/12 16.7.12-1 6/30/04 16.7.12-2 6/30/04 16.7.13-1 12/05/12 16.7.13-2 12/05/12 16.7.13-3 12/05/12 16.7.14-1 11/15/12 16.7.14-2 11/15/12 16.7.14-3 11/15/12 16.7.14-4 11/15/12 16.7.15-1 04/08/14 16.7.15-2 04/08/14 16.7.15-3 04/08/14 16.8.1-1 8/09/01 16.8.1-2 8/09/01 16.8.2-1 2/10/05 16.8.2-2 2/10/05 LOEP 4 55 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective Pages Paqe Revision Date 16.8.3-1 10/20/09 16.8.3-2 10/20/09 16.8.3-3 10/20/09 16.8.3-4 10/20/09 16.8.3-5 10/20/09 16.8.3-6 10/20/09 16.8.3-7 10/20/09 16.8.4-1 2/10/05 16.8.4-2 2/10/05 16.8.4-3 2/10/05 16.8.4-4 2/10/05 16.8.4-5 Delete 2/10/05 16.8.4-6 Delete 2/10/05 16.8.4-7 Delete 2/10/05 16.8.4-8 Delete 2/10/05 16.8.4-9 Delete 9/25/04 16.8.5-1 07/23/12 16.8.5-2 07/23/12 16.8.5-3 07/23/12 16.8.5-4 Delete 12/21/04 16.8.5-5 Delete 12/21/04 16.8.6-1 01/04/07 16.8.6-2 01/04/07 16.8.6-3 01/04/07 16.8.7-1 1/31/00 16.8.8-1 1/31/00 16.8.9-1 6/21/05 16.8.9-2 6/21/05 16.8.9-3 6/21/05 16.8.9-4 6/21/05 16.9.1-1 12/05/12 16.9.1-2 12/05/12 16.9.1-3 12/05/12 16.9.1-4 12/05/12 16.9.1-5 12/05/12 16.9.1-6 12/05/12 16.9.2-1 12/31/12 16.9.2-2 12/31/12 16.9.2-3 12/31/12 16.9.2-4 12/31/12 16.9.2-5 12/31/12 LOEP 5 56 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective Pages Page Revision Date 16.9.2-6 12/31/12 16.9.3-1 12/31/12 16.9.3-2 12/31/12 16.9.4-1 11/11/13 16.9.4-2 11/11/13 16.9.4-3 11/11/13 16.9.4-4 11/11/13 16.9.4-5 11/11/13 16.9.4-6 11/11/13 16.9.4-7 11/11/13 16.9.4-8 11/11/13 16.9.4-9 11/11/13 16.9.5-1 12/31/12 16.9.5-2 12/31/12 16.9.5-3 12/31/12 16.9.5-4 12/31/12 16.9.5-5 12/31/12 16.9.6-1 02/10/14 16.9.6-2 02/10/14 16.9.6-3 02/10/14 16.9.6-4 02/10/14 16.9.6-5 02/10/14 16.9.6-6 02/10/14 16.9.6-7 02/10/14 16.9.6-8 02/10/14 16.9.6-9 02/10/14 16.9.6-10 02/10/14 16.9.6-11 02/10/14 16.9.7-1 07/23/12 16.9.7-2 07/23/12 16.9.7-3 07/23/12 16.9.7-4 07/23/12 16.9.7-5 07/23/12 16.9.7-6 07/23/12 16.9.7-7 07/23/12 16.9.7-8 07/23/12 16.9.7-9 Delete 16.9.8-1 2/15/06 16.9.8-2 2/15/06 16.9.8-3 Delete 2/15/06 16.9.8-4 Delete LOEP 6 57 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective Pages Page Revision Date 16.9.8-5 Delete 16.9.8-6 Delete 16.9.8-7 Delete 16.9.8a-1 2/7/05 16.9.8a-2 217/05 16.9.8a-3 217/05 16.9.9-1 11/15/12 16.9.9-2 11/15/12 16.9.9-3 11/15/12 16.9.9-4 11/15/12 16.9.10-1 1/12/04 16.9.10-2 1/12/04 16.9.11-1 11/15/12 16.9.11-2 11/15/12 16.9.11-3 11/15/12 16.9.11-4 11/15/12 16.9.11-5 11/15/12 16.9.11-6 11/15/12 16.9.11-7 11/15/12 16.9.11-8 11/15/12 16.9.11 a-1 11/15/12 16.9.11a-2 11/15/12 16.9.1 la-3 11/15/12 16.9.11a-4 11/15/12 16.9.11a-5 11/15/12 16.9.11a-6 11/15/12 16.9.11a-7 11/15/12 16.9.11 a-8 11/15/12 16.9.11 a-9 11/15/12 16.9.11la-10 11/15/12 16.9.11a-1 1 11/15/12 16.9.11la-12 11/15/12 16.9.11a-13 11/15/12 16.9.11a-14 11/15/12 16.9.1 la-i5 11/15/12 16.9.1 la-16 Deleted 3/10/08 16.9.12-1 12/01/13 16.9.12-2 12/01/13 16.9.12-3 12/01/13 16.9.12-4 12/01/13 16.9.12-5 12/01/13 LOEP 7 58 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective Pages Page Revision Date 16.9.12-6 12/01/13 16.9.12-7 12/01/13 16.9.12-8 12/01/13 16.9.12-9 12101/13 16.9.12-10 12/01/13 16.9.12-11 12/01/13 16.9.12-12 12/01/13 16.9.12-13 12/01/13 16.9.12-14 12/01/13 16.9.12-15 12/01/13 16.9.12-16 12/01/13 16.9.12-17 12/01/13 16.9.12-18 12/01/13 16.9.12-19 Deleted 12/01/13 16.9.12-20 Deleted 12/01/13 16.9.12-21 Deleted 12/01/13 16.9.12-22 Deleted 12/01/13 16.9.13-1 01/31/07 16.9.13-2 01/31/07 16.9.13-3 01/31/07 16.9.13-4 01/31/07 16.9.14-1 10/28/04 16.9.14-2 10/28/04 16.9.15-1 3/27/99 16.9.15-2 3/27/99 16.9.15-3 3/27/99 16.9.16-1 4/01/08 16.9.16-2 4/01/08 16.9.16-3 4/01/08 16.9.17-1 5/23/01 16.9.17-2 3/27/99 16.9.18-1 11/15/12 16.9.18-2 11/15/12 16.9.18-3 11/15/12 16.9.18-4 11/15/12 16.9.18-5 11/15/12 16.9.18-6 11/15/12 16.9.18-7 11/15/12 16.9.18-8 11/15/12 16.9.18-9 11/15/12 16.9.18-10 11/15/12 LOEP 8 59 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 Page 16.9.18-11 16.9.18-12 16.9.18-13 16.9.18-14 16.9.18-15 16.9.18-16 16.9.19-2 16.9.1 M2 16.9.2041'16.9.20-2
-16.9.20-3 16.9.20-4 16.9.20-5 16.9.21-1 16.9.21-2:16.9.22-16.9.21-,4
- 16.9.22-1 16.91.221-2
-.16.9.22-3.
16.,9..22-4 16.10.1-1 16.10.-2..16.10.1-3.... ~16.10.2:1,:
16.10.2-2,",. I. ..AA 16.10.3-1 16.10.3-2 16.10.741.16.10.7-1 16.10.7-1 16.10.7-1 16.10.7-2 16.10.7-3 16.10.78-16.10.7-6 16.10.7-7 16.10.7-8 16.10.7-9 16.10.8-1 Ust of Effective Pages Revision Date 11/15/12 11/15/12 11115112.11/115/12.
11/15/12 1116/112 3/31/05::3/31/05i.12/21/09 , .2l/9 ..12/21/09',
- 1i2/21/09 12/21/09 07/09/09-07/09/09... 07/09/09 07/09/09 111/114113 11/14/13 11/14/13 11/14/13 11i15/12.1 11/15/12 Deleted 9/18/03 12/2/03 12/2/03 3/27/99 3/27/99 11/15/12 Deleted 8/24/04 3/27/99 4/29/99 4/29/99 1/31/00 4/29/99 4/29/99 4/29/99 4/29/99 4/29/99 4/29/99 11/27/06 LOEP 9 60 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective Pages Page Revision Date 16.10.8-2 11/27/06 16.10.8-3 11/27/06 16.10.8-4 11/27/06 16.10.8-5 11/27/06 16.10.9-1 11/25/09 16.10.9-2 11/25/09 16.10.9-3 11/25/09 16.10.9-4 11/25/09 16.10.9-5 11/25/09 16.11.1-1 3/15/11 16.11.1-2 3/15/11 16.11.1-3 3/15/11 16.11.1-4 3/15/11 16.11.1-5 3/15/11 16.11.1-6 3/15/11 16.11.1-7 3/15/11 16.11.2-1 1/31/00 16.11.2-2 3/27/99 16.11.2-3 1/31/00 16.11.2-4 3/27/99 16.11.2-5 1/31/00 16.11.2-6 1/31/00 16.11.3-1 11/20/08 16.11.3-2 11/20/08 16.11.3-3 11/20/08 16.11.3-4 11/20/08 16.11.3-5 11/20/08 16.11.3-6 11/20/08 16.11.3-7 11/20/08 16.11.3-8 11/20/08 16.11.3-9 11/20/08 16.11.3-10 11/20/08 16.11.3-11 11/20/08 16.11.3-12 11/20/08 16,11.3-13 11/20/08 16.11.3-14 11/20/08 16.11.3-15 11/20/08 16.11.3-16 11/20/08 16.11.3-17 11/20/08 16.11.3-18 11/20/08 16.11.3-19 11/10/04 (Deleted)LOEP 10 61 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective Pages Page Revision Date 16.11.4-1 11/08/13 16.11.4-2 11/08/13 16.11.4-3 11/08/13 16.11.4-4 11/08/13 16.11.4-5 11/08/13 16.11.4-6 11/08/13 16.11.4-7 11/08/13 16.11.4-8 11/10/04 (Delete)16.11.5-1 10/30/02 16.11.5-2 10/30/02 16.11.5-3 10/30/02 16.11.5-4 10/30/02 16.11.6-1 11/08/13 16.11.6-2 11/08/13 16.11.6-3 11/08/13 16.11.6-4 11/08/13 16.11.6-5 11/08/13 16.11.6-6 11/08/13 16.11.6-7 11/08/13 16.11.6-8 11/08/13 16.11.6-9 11/08/13 16.11.6-10 11/08/13 16.11.7-1 1/31/00 16.11.7-2 1/31/00 16.11.7-3 3/27/99 16.11.7-4 1/31/00 16.11.8-1 12/21/09 16.11.8-2 12/21/09 16.11.9-1 03/22/10 16.11.9-2 03/22/10 16.11.9-3 03/22/10 16.11.10-1 2/25/03 16.11.10-2 2/25/03 16.11.11-1 3/27/99 16.11.12-1 4/10/03 16.11.12-2 4/10/03 16.11.13-1 3/27/99 16.11.13-2 3/27/99 16.11.14-1 3/27/99 16.11.14-2 3/27/99 LOEP 11 62 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective Pages Page Revision Date 16.12.1-1 3/27/99 16.12.2-1 5/3/07 16.12.2-2 5/3/07 16.12.3-1 5/1/03 16.12.3-2 5/1/03 16.12.4-1 3/27/99 16.12.5-1 3/27/99 16.12.6-1 11/08/07 16.13.1-1 5/13/04 16.13.1-2 5/13/04 16.13.1-3 5/13/04 16.13.1-4 5/13/04 16.13.1-5 5/13/04 16.13.1-6 5/13/04 16.13.1-7 5/13/04 16.13.1-8 5/13/04 16.13.1-9 5/13/04 16.13.2-1 12/15/04 16.13.2-2 Delete 12/15/04 16.13.2-3 Delete 12/15/04 16.13.2-4 Delete 12/15/04 16.13.3-1 12/15/04 16.13.3-2 Delete 12/15/04 16.13.4-1 3/27/99 16.13.5-1 Delete 16.13.5-2 Delete 16.13.6-1 3/27/99 16.13.7-1 12/15/04 16.13.7-2 12/15/04 16.13.8-1 3/27/99 16.13.9-1 3/27/99 16.13.9-2 3/27/99 16.13.10-1 3/27/99 16.13.11-1 3/27/99 16.14.1-1 11/15/12 16.14.2-1 07/23/12 16.14.2-2 07/23/12 16.14.3-1 3/27/99 16.14.4-1 Deleted 3/15/11 16.14.4.a-1 3/15/11 16.15.1-1 4/12/06 LOEP 12 63 Oconee Nuclear Station Selected Licensee Commitments Revised 04/21/14 List of Effective PagesRevision Date 16.15.1-2 Deleted 4/12/06 16.15.1-3 Deleted 4/12/06 16.15.1-4 Deleted 4/12/06 16.15.1-5 Deleted 4/12/06 16.15.2-1 11/15/12 16.15.2-2 11/15/12 16.15.2-3 11/15/12 16.15.2-4 11/15/12 16.15.2-5 11/15/12 16.15.3-1 11/15/12 16.15.3-2 11/15/12 16.15.3-3 11/15/12 16.15.3-4 11/15/12 16.15.3-5 11/15/12 LOEP 13 64 Operational Safety Review 16.11.4 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.4 Operational Safety Review COMMITMENT Required sampling should be performed as detailed in Table 16.11.4-1.
APPLICABILITY:
At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A.1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.4.1 N/A N/A 16.11.4-1 11/8/13 1 65 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Umit of Detection (b) of Lab Analysis for Waste Decant Monitor Tank, Turbine Building Sump Monitor Tanks, Waste and Recycle Monitor Tanks 2. Unit Vent Sampling (includes Waste Gas Decay Tanks, Reactor Building Purges, Auxiliary Building Ventilation, Spent Fuel Pool Ventilation, Air Ejectors)a. Principal Gamma Emitters(c)
Including Dissolved Noble Gases b. Radiochemical Analysis Sr-89 and Sr-90 C. Tritium d. Gross Alpha Activity a. Iodine Spectrum (a)b. Particulates (a)i. Ce-144 & Mo-99 II. Other Principle Gamma Emitters (d)ill. Gross Alpha Activity iv. Radiochemical Analysis Sr-89, Sr-90 c. Gases by Principle Gamma Emitters(d)
- d. Tritium a. Principle Gamma Emitters(d)
Composite Grab Sample prior to release of each batch(h)Quarterly from all composited batches(f)
Monthly Composite Monthly Composite Continuous monitor, weekly sample(e)<5E-08 i+/-CiI/m<1 E-05 1+/-CVmI<1 E-1O0 iiCicc (1-133)0)<1E-12 giClcc (1-131)0)<5E-06 IaCi/ml (Ce-144)<5E-07 g+/-Ci/ml (Other Gamma Nuclides)<1 E-05 p.CI/ml (Dissolved Gases)<1E-06 pCi/ml (1-131)Weekly Composite(e)
Weekly Composite(e)
Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample Grab Sample prior to release of each batch Grab Sample prior to release of each batch Grab sample each purge Grab sample each purge<1E-1O 1 CVcc)<11E-06 gCi~cc 3. Waste Gas Decay Tank b. Titium<1E-04 I/Cicc (gases)<1E-10 gCi/cc (particulates and lodines)<5E-09 ICVcc (Ce-144 and Mo-99)<1E-06 giCVcc<1 E-04 p.CVcc (gases)<1 E-10 u+/-Ci/cc (particulates and lodines)<5E-09 ICil/cc (Ce-144 and Mo-99)<1 E-06 i/CVcc 4. Reactor Building a. Principle Gamma Emitters(d)
- b. Tritium 16.11.4-2 11/8/13 I 66 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection (b) of Lab Analysis for Waste 5. Not Used 6. #3 Chemical Treatment Pond Effluent 0)7. Radwaste Facility Ventilation
- a. Principle Gamma Emitters(c)
- b. 1-131 C. Tritium d. Gross Alpha Activity e. Sr-89 & Sr-90 f. Dissolved and Entrained gases (Gamma Emitters)a. Iodine Spectrum(a)
- b. Particulate(a)
- i. Ce-144 and Mo-99 ii. Other Principle Gamma Emitters(d) ill. Gross Alpha Activity iv. Radiochemical Analysis Sr-89, Sr-90 c. Gases by Principle Gamma(d)Emitters d. Tritium Weekly Continuous Composite(g)
Weekly Continuous Composite(g)
Monthly Continuous Composite(g)
Monthly Continuous Composite(g)
Quarterly Continuous Composite(g)
Monthly Grab Continuous monitor, weekly sample(e)Weekly Composite(e)
Weekly Composite(e)
Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample<5E-07 pCVml (<1 E-06 pCI/ml (<1 E-05 pCi/m I<1E-07 .Cil/ml<5E-08 ILCI/ml<1E-05 gCi/ml (1-133) <1 E-09 (1-131) <1 E-1 1 1gCi/cc<5E-10 igCi/ccU)<I1E-11I pCI/ccUj)<1E-11 gICicc<1E-11 IgCI/cc<1E-04 ILCi/cc<1E-06 iiCi/cc 16.11.4-3 11/8/13 I 67 Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection (b) of Lab Analysis for Waste 8. Hot Machine Shop Ventilation
- a. Iodine Spectrum b. Particulate
- i. Ce-144 and Mo-99 II. Other Principle Gamma Emitters (d)Ill. Gross Alpha Activity iv. Radlochemical Analysis Sr-89, Sr-90 C. Gases by Principle Gamma Emitters d. Tritium Weekly Sample(s)(1-133) <1E-110 p.Ciccj)(1-131) <1E-12 pICicc(j)Weekly Composite(e)
Weekly Composite(*)
Monthly, using composite samples of one week Quarterly Composite NA NA Weekly sample(e)<5E- 10 g+/-CiccU)<1E-11 gzClcc<1E-11 .CI/co NA NA (1-133) <1E-10 gCI/ccij)(1-131) <1E-12 pCi/cc(J)9. Interim Radwaste Building Ventilation a.b.Iodine Spectrum Particulate
- i. Ce-144 and Mo-99 ii. Other Principle Gamma Emitters(d) iii. Gross Alpha Activity iv. Radlochemical Analysis Sr-89, Sr-90 c. Gases by Principle Gamma(d)Emitters d. Tritium Weekly Composite(e)
Weekly Composite(e)
Monthly, using composite samples of one week Quarterly Composite Weekly Grab Sample Weekly Grab Sample<5E-10 gCi/ccU)<lE-1l gCl/ccU)<lE-li j+/-Cicc<11E-11 j+/-CIicc<1 E-04 iCi/cc<11E-06 liClcc 16.11.4-4 11/8/13 1 68 Operational Safety Review 16.11.4 (a) Samples shal be changed at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and analysis shall be, completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (on or after removal from sampler).(b) The LLD Is defined for purposes of these commitments as the smallest concentration of radioactive material In a sample *that would be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a'rear signal.For a particular measurement system (which may Include radiochemical separation):
LLD ii (2.71/1 +T 4.65 5" E x V x 2.22EO x Y x exp(-,t)Wh ere: LLD Is the "a prorr lower lmit of detection as defined above (as micro Curies per unit mass or volume), sb Is the stahdard deviation of the background counting.rate or of the counting rate of a blank sample as"appropriate (as cou.nt per minute), E Is the counting efficiency (ascounts per disintegration),, V Is the samplebsize an units of mass or volume), 2.22E06 Is the number of disintegrations per mlcro Cude, Y .Is the fractional radlochemloal yield (when applicable), x isthe radioacte decay constant for the particular nuclid6 A t Is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not envir6oinntal'sample).
NOTE: This assumes decay correction Is applied (at the time of analysis) for the duration of sample collection.
for the time between collection and analysis, and for the duration of the counting.Additionally, it does not apply to Isolated systems such as Waste Gas Decay Tanks and Waste Monitor Tanks.T.Is the sample-counting time In minutes --I Ty*'al values of EV. V nd A t shouldbe used In the calculation.
It houd b reognzedtha th IL len admi(before the fact) limit repre senting the capability ofa measurement system sand not an a psthiffri (afte the fact) limit for a particular measuremdnt.
Mc The principal gamma emitters for which the LLD contril applis Include the .following radionucildes:
Wn5 .4. Fe-SO, Co-68, Co-60. Zn-65. M6-99, Cs-I!34, C-I37. and Ce-141. Ce-144 shaD also be measured,.but with a LLD of 5E-06 ILCI/ml. This list does not mean that only these nudildes are to be considered.:
Other gamma peaks that ar Identifiable, together with the above nucIdes shall also W analyzed and reported In the Annual Radioactive Effluent Release Reo1L (d) The principal gamma emitters for which the LID commitment applies exclusively are the following radionuclides:
Kr-87. Kr-88, XeI 33. Xe-1 33m, XeI .and Xe-I 38 for gaseous emidslons and Mn-54 Fe-59. Co-58, Co-60, Zn-OS.Mo-99, Cs-134, Cs-137. Ce-141, and Ce-144 for particulates.
This list does not men that only tiese nuclides are to be detected and reported.
Other peaks which are measurable and identiflableltogether with the above nuclides shag also be Identifledand reported.:..(e) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made In accordance with SLC 16.11.2.a, SLC 16.11.2.b.1, and SLC 16.11.2.b.2.(f) A composite sample Is one In which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and In which the method of sampling employed results In a specimen which Is representative of the liquids released.(g) To be representative of the quantities and concentrations of radioactive materiais In liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analysis, aD samples taken for the composite shall be thoroughly mixed In order for the composite sample to be representative of the effluent release.16.11.4-5 1118/13 1 89 (h)(i)(J)Operational Safety Review 16.11.4 A batch release Is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, each batch shall be isolated, and then thoroughly mixed, to assure representative sampling.A continuous release Is the discharge of liquid wastes of a non-discrete volume, e.g., from a volume of a system that has an input flow during the continuous release.When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be Increased by a factor of 10.16.11.4-6 11/8/13 I 70 Operational Safety Review 16.11.4 BASES N/A
REFERENCES:
N/A 16.11.4-7 11/8/13 I 71 Radiological Environmental Monitoring 16.11.6 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.6 Radiological Environmental Monitoring COMMITMENT
- a. The radiological environmental monitoring samples shall be collected in accordance with Table 16.11.6-1 and shall be analyzed pursuant to the requirements of Tables 16.11.6-1 and 16.11.6-2.
- b. A land use census shall be conducted and shall identify the location of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of eight kilometers (five miles). Broad leaf vegetation sampling shall be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.c. Analyses shall be performed on radioactive materials supplied as part of an 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 locations from which samples were unavailable may then be deleted from the program provided replacement samples were obtained and added to the environmental monitoring program, if available.
These new locations will be identified in the Annual Radioactive Effluent Release Report.APPLICABILITY:
At all times 16.11.6-1 11/8/13 72 Radiological Environmental Monitoring 16.11.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Radiological A.1 Submit a description of May 15 of following environmental the reason for not calendar year monitoring program is conducting the program not conducted as as required and plans to required.
prevent a recurrence shall be included in the Annual Radiological Environmental Operating Report.B. Land use census B.1 --------NOTE -----identifies a Location The sampling location which yields a having the lowest calculated dose or dose calculated dose or dose commitment (via the commitment (via the same exposure same exposure pathway) 20% greater pathway) may be than a location from deleted from this which samples are monitoring program currently being after October 31 of the obtained.
year in which this land use census was conducted.
Add new location to the 30 days radiological environmental monitoring program.AND B.2 Identify new locations in April 30 of following the next Annual calendar year Radioactive Effluent Release Report.16.11.6-2 11/8/13 I 73 Radiological Environmental Monitoring 16.11.6 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Interlaboratory C.1 Report corrective May 15 of following Comparison Program actions in the Annual calendar year analyses not performed Radiological as required.
Environmental Operating Report.D. Radioactivity level D.1 Prepare and submit a 30 days resulting from plant Special report that effluents in identifies the cause for environmental sampling exceeding the limits and medium at a specified defines the corrective location in excess of actions to be taken to reporting limits of Table reduce radioactive 16.11.6-3 when effluents so that the averaged over a potential annual dose to calendar quarter. a MEMBER OF THE PUBLIC is less than the calendar year limits of SLC 16.11.1 or 16.11.2.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.6.1 Conduct land use census during growing 12 months season using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.
16.11.6-3 11/8/13 1 74 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Exposure Pathway and/or Number of Sampling and Collection Time and Frequency of Analysis Sample LocatnSample Frequency (d)e Sample ~~Locations (b) Frqec(d 1. AIRBORNE Radioiodine and Particulates
- 2. DIRECT RADIATION 5 Continuous sampler operation with sample collection weekly, or more frequently if required by dust loading.40 Quarterly.
Radioiodine canister: 1-131 analysis weekly. Particulate sampler Gross beta radioactivity analysis following filter change; and gamma Isotopic analysis of composite (by location) quarterly. (c)Gamma dose quarterly.
- 3. WATERBORNE
- a. Surface 2 Composite (a) sample over a 1-month period.3 Composite (a) sample over a 1-month period.Gamma isotopic analysis monthly.Composite for tritium analysis quarterly.
Composite for gross beta and gamma isotopic analyses monthly.Composite for tritium analysis quarterly.
- b. Drinking c. Sediment from Shoreline 2 Semiannually.
Gamma isotopic analysis semiannually.
16.11.6-4 11/8/13 1 75 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Exposure Pathway and/or Number of Sampling and Collection lime and Frequency of Analysis Sample ~Sample Feuny() Tm n rqec fAayi Sample Locations (b) 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.commercially and recreationally Important species.c. Broad-leaf 2 Monthly. Gamma isotopic analysis monthly.Vegetation (a) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.(b) Sample locations are identified in the ODCM.(c) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.(d) Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment.
If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.(e) Samples from milking animals in three locations within 5 km distance having the highest dose potential.
If there are none, then one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per year. One sample from milking animals at a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.
16.11.6-5 11/8/13 1 76 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)Fish Broad-leaf Water Particulate or MilkVegetation Sediment (pCi/I) Gases (pCI/kg, (pCi/I) (iget) (pCi/kg, dry)(pCi/m 3) wet) (pCikg, wet)Gross Beta 4 1 E-02 H 3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 15 Nb-95 15 1-131 15(b) 7E-02 1 60 Cs-134 15 5E-02 130 15 60 150 Cs-137 18 6E-02 150 18 80 180 Ba-140 15 60 La-140 15 15 (a) The LLD is defined, for purposes of these commitments, as the smallest concentration of radioactive material in a sample with 95% probability of detection and with 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system (which may include radiochemical separation):
LLD = (2.71 / T) + 4.65 Sb E xV x 2.22 x Y x exp (-XA t)Where: LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)I 16.11.6-6 11/8/13 1 77 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)E is the counting efficiency (as counts per disintegration)
V is the sample size (in units of mass or volume)2.22 is the number of disintegrations per minute per picocune Y is the fractional radiochemical yield (when applicable)
X Is the radioactive decay constant for the particular radionuclide A t Is the elapsed time between sample collection (or end of the sample collection period) and time of counting T is the sample counting time In minutes 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 capability of a measurement system and not as a posterori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances, may render these LLDs unachievable.
In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.(b) LLD for gamma isotopic analysis for 1-131 in drinking water samples. Low level 1-131 analysis on drinking water will not be routinely performed because the calculated dose from 1-131 in drinking water at all locations is less than 1 mrem per year. Low level 1-131 analyses will be performed if abnormal releases occur which could reasonably result in > 1 pCi/liter of 1-131 in drinking water. For low level analyses of 1-131 an LLD of 1 pCi/liter will be achieved.(c) Other peaks which are measurable and identifiable, together with the radionuclides in Table 16.11.6-2, shall be identified and reported.16.11.6-7 11/8/13 78 Radiological Environmental Monitoring 16.11.6 Table 16.11.6-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples (c) (d)Airborne Broad-leaf Water Particulate or Fish Milk Vegettion Analysis (pCi/I) Gases (pCi/kg, wet) (pCi/I)(pCi/m 3) (pCi/kg, wet)H-3 2E04(a)Mn-54 1 E03 3E04 Fe-59 4E02 1 E04 Co-58 1 E03 3E04 Co-60 3E02 1 E04 Zn-65 3E02 2E04 Zr-Nb-95 4E02 1-131 2(b) 0.9 3 1 E02 Cs-134 30 10 1E03 60 1E03 Cs-1 37 50 20 2E03 70 2E03 Ba-La-140 2E02 3E02 (a) For drinking water samples. This is 40 CFR Part 141 value.(b) If low level 1-131 analyses are performed.(c) Report shall be submitted when any single radionuclide exceeds the reporting level in Table 16.11.6-3 or when more than one of the radionuclides in Table 16.11.6-3 are detected in sampling medium and concentration (1) + concentration (2) + ... > 1.0 reporting level (1) reporting level (2)(d) Report shall be submitted when radionuclides other than those in table 16.11.6-3 are detected and are the result of plant effluents if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of SLC 16.11.1 or 16.11.2.16.11.6-8 11/8/13 1 79 Radiological Environmental Monitoring 16.11.6 BASES The environmental monitoring program required by this commitment provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.
This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of exposure pathways.
The initially specified monitoring program will be effective for at least the first three years of commercial operation.
Following this period, program changes may be initiated based on operational experience.
The detection capabilities required by Table 16.11.6-2 are considered optimum for routine environmental measurements in industrial laboratories.
The specified lower limits of detection correspond to less than the 10 CFR 50. Appendix I, design objective dose-equivalent of 45 mrem/year for atmospheric releases to the most sensitive organ and individual.
The land use census commitment is provided to assure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are provided if required by the results of this census.The requirements for participation in an 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 (1) + concentration (2) + ... > 1.0 reporting level (1) reporting level (2)When radionuclides other than those in Table 16.11.6-3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of SLC 16.11.1 or SLC 16.11.2. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Technical Specification 5.6.2. The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in the 30-day Special Report.16.11.6-9 11/8/13 80 Radiological Environmental Monitoring 16.11.6 The following requirement(s) were relocated from the CTS 6.4.4.f during the conversion to ITS.The station shall have a program to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
The program shall (1)be contained in UFSAR Chapter 16, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
- 1. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM;2. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census; and, 3. Participation in an 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 11/8/13 81 Attachment 8 Revisions to the Radioactive Waste Process Control Program Manual There have been no revisions to the Radioactive Waste Process Control Program Manual since the 2012 ARERR transmittal in 2013.(Page 82)82 Attachment 9 Information to Support the Nuclear Energy Institute (NEI) Groundwater Protection Initiative (Pages 83 -86)83 2013 Annual Radiological Effluent Release Report Groundwater Well Data Duke Energy implemented a Groundwater Protection program in 2007. This program was developed to ensure timely and effect management of situations involving inadvertent releases of licensed material to groundwater.
As part of this program, Oconee monitored sixty-six groundwater wells during 2013.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 was collected weekly in 2013. Groundwater 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 2013.Results from sampling during 2013 are shown in the table below.Well Location / Description Tritium Concentration (pC/I) # of Name 1st Qtr 2nd Qtr 3rd Qtr 4th ýQtr Samples A-1 ONS GWPI / A-1 / CTP 1/2 <MDA <MDA <MDA <MDA 4 A-i1 ONS GWPI / A-10 / CTP 3 5.38E+02 4.34E+02 4.85E+02 4.31E+02 4 A-11 ONS GWPI / A-11 / CTP 3 <MDA <MDA <MDA <MDA 4 A-12 ONS GWPI / A-12 / CTP 3 <MDA <MDA <MDA <MDA 4 A-13 ONS GWPI/ A-13 / CTP 1/2 4.96E+02 5.35E+02 6.02E+02 5.45E+02 4 A-14 ONS GWPI / A-14 / CTP 1/2 3.67E+02 2.09E+02 2.80E+02 3.15E+02 4 A-17 ONS GWPI / A-17 / CTP 1/2 2.48E+02 1.93E+02 1.86E+02 3.07E+02 4 A-18 ONS GWPI / A-18 / CTP 1/2 <MDA <MDA 2.17E+02 1.98E+02 4 A-2 ONS GWPI / A-2 / CTP 1/2 <MDA <MDA <MDA <MDA 4 A-8 ONS GWPI /A-8 /CTP 1/2 NS NS NS NS 0 A-9 ONS GWPI / A-9 / CTP 1/2 1.90E+02 <MDA NS <MDA 3 BG-4 ONS GWPI/ BG-4 / Ball Field <MDA <MDA <MDA <MDA 4 GM-10 ONS GWPI / GM-10 / 525 kv Sw. Yard <MDA <MDA <MDA <MDA 4 GM-10R ONS GWPI / GM-10R / 525 kv Sw. Yard <MDA <MDA <MDA <MDA 4 GM-11 ONS GWPI /GM-11 / ONS Garage <MDA <MDA <MDA <MDA 4 GM-11R ONS GWPI /GM-11R / ONS Garage <MDA <MDA <MDA <MDA 4 GM-12 ONS GWPI / GM-12 i E of Access Rd. <MDA <MDA <MDA <MDA 4 GM-12R ONS GWPI /GM-12R / E of Access Rd. <MDA <MDA <MDA <MDA 4 GM-13 ONS GWPI / GM-13 / 525 kv Sw. Yard <MDA <MDA <MDA <MDA 4 GM-13R ONS GWPI / GM-13R / 525 kv Sw. Yard <MDA <MDA <MDA <MDA 4 84 Well Location / Description Tritium Concentration (pCi/I) # of Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples GM-14 ONS GWPI / GM-14 / Mnt. Trg. Facility <MDA <MDA <MDA <MDA 4 GM-14R ONS GWPI / GM-14R / Mnt. Trg. Facility <MDA <MDA <MDA <MDA 4 GM-15 ONS GWPI / GM-15 / 525 kv Sw. Yard <MDA 1.75E+02 2.25E+02 <MDA 4 GM-15R ONS GWPI / GM-15R / 525 kv Sw. Yard 2107E+02 1.64E+02 <MDA <MDA 4 GM-16DDR ONS GWPI /GM-16DDR
/ TBSMT 4.19E+02 3.89E+02 3.77E+02 <MDA 4 GM-16DR ONS GWPI / GM-16DR / TBSMT 9.66E+03 8.73E+03 8.54E+03 8.81E+03 4 GM-16R ONS GWPI /GM-16R / TBSMT 1.75E+03 1.83E+03 1.65E+03 1.61E+03 4 GM-17DR ONS GWPI /GM-17DR /O Drum Storage 3.35E+03 3.03E+03 3.04E+03 3.10E+03 4 GM-17R ONS GWPI /GM-17R /Oil Drum Storage 1.49E+03 1.51E+03 1.40E+03 1.37E+03 4 GM-18R ONS GWPI /GM-18R RCP Refurb.Bldg 9.21E+03 8.02E+03 7.96E+03 8.40E+03 4 GM-19 ONS GWPI / GM-19 / 525 kv Sw. Yard 5.52E+02 5.47E+02 3.73E+02 6.99E+02 4 GM-19R ONS GWPI / GM-19R /525 kv Sw. Yard 4.01E+02 4.55E+02 4.61E+02 4.46E+02 4 GM-1R ONS GWPI /GM-1R/ CTP 1/2 <MDA <MDA <MDA <MDA 4 GM-20 ONS GWPI / GM-20 / SG Retire. Facility <MDA <MDA <MDA <MDA 4 GM-20R ONS GWPI / GM-20R / SG Retire. Facility <MDA <MDA <MDA <MDA 4 GM-21 ONS GWPI / GM-21 /Sec. Trg. Facility <MDA <MDA <MDA <MDA 4 GM-22 ONS GWPI / GM-22 /Sec. Trg. Facility <MDA <MDA <MDA <MDA 4 GM-23 ONS GWPI GM-23 / 525 kv Sw. Yard 4.35E+02 3.58E+02 4.22E+02 2.01E+02 4 GM-24R ONS GWPI / GM-24R I 3T Transformer 1.71E+03 1.47E+03 1.47E+03 1.19E+03 4 GM-25R ONS GWPI / GM-25R / CT3 Transformer 3.43E+02 4.56E+02 4.03E+02 3.89E+02 4 GM-2DR ONS GWPI /GM-2DR /U-1/2 SFP 3.06E+02 1.91E+02 2.62E+02 2.08E+02 4 GM-2R ONS GWPI /GM-2R / U-1/2 SFP 8.28E+02 6.55E+02 5.79E+02 3.77E+02 4 GM-3DR ONS GWPI / GM-3DR / U-3 SFP 2.37E+02 <MDA 2.03E+02 3.29E+02 4 GM-3R ONS GWPI /GM-3R / U-3 SFP 3.04E+02 2.13E+02 2.18E+02 2.16E+02 4 GM-4 ONS GWPI /GM-4 /Rad. Mat. WH 3.16E+02 2.74E+02 3.85E+02 4.21E+02 4 GM-5 ONS GWPI / GM-5 / Rdwst. Bldg. 1.96E+02 <MDA <MDA <MDA 4 GM-SR ONS GWPI / GM-SR / Rdwst. Bldg. <MDA <MDA <MDA <MDA 4 GM-6 ONS GWPI / GM-6 / Outflow to CTP-3 <MDA <MDA <MDA <MDA 4 GM-6R ONS GWPI / GM-6R / Outflow to CTP-3 <MDA <MDA <MDA <MDA 4 GM-7 ONS GWPI / GM-7 / 525 kv Sw. Yard 9.54E+02 6.47E+02 4.99E+02 3.80E+02 4 GM-7DR ONS GWPI / GM-7DR / 525 kv Sw. Yard <MDA <MDA <MDA <MDA 4 GM-7R ONS GWPI /GM-7R / 525 kv Sw. Yard 2.90E+03 2.98E+03 4.OOE+03 4.32E+03 4 GM-8 ONS GWPI GM-8 / E of U-3 TB 3.01E+02 2.75E+02 3.39E+02 2.08E+02 4 GM-8R ONS GWPI /GM-8R / E of U-3 TB 3.46E+02 2.OOE+02 1.75E+02 2.27E+02 4 GM-9 ONS GWPI / GM-9 / E of U-2 TB <MDA 2.36E+02 2.90E+02 2.06E+02 4 GM-9R ONS GWPI / GM-9R / E of U-2 TB <MDA <MDA <MDA <MDA 4 MW-11 ONS GWPI /MW-11 /Landfill
<MDA NS <MDA NS 2 MW-liD ONS GWPI / MW-liD / Landfill <MDA NS <MDA NS 2 85 Well Location / Description Tritium Concentration (pCi/I) # of Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples MW-13 ONS GWPI / MW-13 / Landfill <MDA NS <MDA NS 2 MW-16 ONS GWPI / MW-16 / Landfill <MOA NS <MDA NS 2 MW-3 ONS GWPI / MW-3 / Landfill <MDA NS <MDA NS 2 MW-RP01 ONS GWPI / MW-RPO1 / Landfarm/Burial NS <MDA NS NS 1 MW-RP02 ONS GWPI / MW-RP02 / Landfarm/Burial NS <MDA NS NS 1 MW-RP03 ONS GWPI / MW-RP03 / Landfarm/Burial NS <MDA NS NS 1 Well Location / Description Tritium Concentration (pCi/I) # of Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples*011 ONS / 011 / Ball Field <MDA <MDA <MDA <MDA 4*013 ONS / 013 I WH 5 <MDA <MDA <MDA <MDA 4*015 ONS / 015 / Brown's Bottom <MDA <MDA <MDA <MDA 4 Well Location / Description Tritium Concentration (pCi/I) # of Name Minimum Average Maximum Samples"'RW-1 525 kvSw. Yard 1770 1 2086 1 2460 52 NS -Not sampled due to insufficient volume in well or well inaccessible due to construction in area.*These are irrigation wells and may not meet current requirements for groundwater 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 lOCFR20, Appendix B, Table 2, Column 2, Effluent Concentration limit for tritium.86 Attachment 10 Inoperable Equipment 1 RIA-40 and 2 RIA-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 1 RIA-40 and 2 RIA-40 to service within 30 days was not successful.
This condition continued into 2013 with grab samples being taken to detect any primary to secondary leakage on Units 1 and 2.Modifications to add moisture separators and drains were completed on I RIA-40 and 2 RIA-40 in 2013. Unit 1 RIA-40 was declared operable on November 6, 2013. Unit 2 RIA-40 was declared operable on August 5, 2013. The inoperability of 1 RIA-40 and 2 RIA-40 could not be corrected in a timely manner (less than 30 days) due to the need for a station modification to effectively resolve the moisture carryover issue.The Rad Waste Facility (RWF) ventilation exhaust particulate and Iodine samplers AM7, AM8 and AM9 were determined to be out of service on 11/18/2012 and were returned to service on 06/20/2013.
The samplers were not returned to service within 30 days as specified in Selected Licensee Commitment (SLC) 16.11.3, Condition C Required Action. The work order to investigate and repair the low AM7, AM8 and AM9 sampler flows was initially not given adequate priority to return the samplers to service within 30 days. On 11/18/2012, auxiliary sampling initiated to satisfy SLC 16.11.3 sampling requirements was determined to be adequate to satisfy the requirement of SLC and no SLC entry was made. On 05/03/13, it was recognized that SLC 16.11.3 Condition C and Condition L should have been entered due to AM7, AM8 and AM9 samplers being out of service. Once the SLC entry was made, the Work Order was given a high priority.
Investigation was performed and the cause of the low flow was due to imbalanced RIA skid flow that resulted in low flow in the sample lines. RIA skid flows were rebalanced and samplers AM7, AM8 and AM9 were returned to service on 06/20/2013.(Page 87)87 Attachment 11 Radioactive Waste Systems Changes This attachment documents the changes made to the radioactive waste systems at the Oconee Nuclear Station during the period January 1, 2013 to December 31, 2013.There were no changes made to the radioactive waste systems during 2013 at the Oconee Nuclear Station.(Page 88)88 Attachment 12 Errata to Previous Reports The previous report, 2012 ARERR, Attachment 10, should have included the following information:
The Rad Waste Facility (RWF) ventilation exhaust particulate and Iodine samplers AM7, AM8 and AM9 were determined to be out of service on 11/18/2012 and were returned to service on 06/20/2013.
The samplers were not returned to service within 30 days as specified in Selected Licensee Commitment (SLC) 16.11.3, Condition C Required Action.The work order to investigate and repair the low AM7, AM8 and AM9 sampler flows was initially not given adequate priority to return the samplers to service within 30 days. On 11/18/2012, auxiliary sampling initiated to satisfy SLC 16.11.3 sampling requirements was determined to be adequate to satisfy the requirement of SLC and no SLC entry was made. On 05/03/13, it was recognized that SLC 16.11.3 Condition C and Condition L should have been entered due to AM7, AM8 and AM9 samplers being out of service. Once the SLC entry was made, the Work Order was given a high priority.Investigation was performed and the cause of the low flow was due to imbalanced RIA skid flow that resulted in low flow in the sample lines. RIA skid flows were rebalanced and samplers AM7, AM8 and AM9 were returned to service on 06/20/2013.(Page 89)89 013 Offsite Dose Calculation Manual Compact Disc (Page 90)90