ML11129A252
| ML11129A252 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/28/2011 |
| From: | Gillespie T Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML11129A252 (141) | |
Text
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T. PRESTON GILLESPIE, JR.
okEnergy, PDuke Vice President Oconee Nuclear Station Duke Energy ON01 VP / 7800 Rochester Hwy.
April 28, 2011 Seneca, SC 29672 864-873-4478 864-873-4208 fax U.S. Nuclear Regulatory Commission T.Gillespie@duke-energy.com Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Carolinas, LLC Oconee Nuclear Station, Docket Nos. 50-269, 50-270 and 50-287 2010 Annual Radioactive Effluent Release Report (ARERR)
Pursuant to the requirements of Technical Specification 5.6.3 and Oconee Nuclear Site Selected Licensee Commitment (SLC) 16.11-9, attached is the Oconee Annual Radioactive Effluent Release Report for the period of January 1, 2010, through December 31, 2010. Also, included in this report are the 2011 Offsite Dose Calculation Manual and the 2010 Process Control Program Manual.
Attachment 1 Effluent Release Data Attachment 2 Supplemental Information Attachment 3 Solid Waste Disposal Report Attachment 4 Meteorological Data Attachment 5 Unplanned Offsite Releases Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)
Attachment 7 SLC 16.11 Radiological Effluent Controls Attachment 8 Revisions to the Radioactive Waste Process Control Program Manual (Compact Disc)
Attachment 9 Information to Support the NE1 Groundwater Protection Initiative Attachment 10 Inoperable Equipment Enclosure 2011 Offsite Dose Calculation Manual (Compact Disc) (changes described in Chapter 7)
Any questions concerning this report should be directed to Judy Smith at (864) 873-4309.
A-ooq www. duke-energy.com
U. S. Nuclear Regulatory Commission April 28, 2011 Page 2 Sincerely, T. Preston Gillespie, Jr.
Vice President Oconee Nuclear Station Attachments and Enclosures (Process Control Program [PCP] Revision Compact Disc [CD] and Offsite Dose Calculation Manual [ODCM] Compact Disc [CD])
U. S. Nuclear Regulatory Commission April 28, 2011 Page 3 xc: Victor McCree, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 John Stang, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 G9A Washington, DC 20852-2738 Andrew Sabisch Senior Resident Inspector Oconee Nuclear Station Susan E. Jenkins, Manager Radioactive & Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.
Columbia, SC 29201 Mr. William Nestel INPO Records Center 700 Galleria Place, Suite 100 Atlanta, GA 30339-5957 Russell Keown, Supervisor Analytical & Radiological Environmental Services Division 2600 Bull Street Columbia, SC 29201 Sandra Flemming, Director Analytical & Radiological Environmental Services Division 8231 Parklane Road Columbia, SC 29223 Chris Staten Bureau of Land and Waste Management 2600 Bull Street Columbia, SC 29201 Crystal Rippy Bureau of Water 2600 Bull Street Columbia, SC 29201
Attachment I Oconee Nuclear Site Effluent Release Data
J.
OCONEE NUCLEAR STATION EFFLUENT RELEASE DATA This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Rev. 1, Appendix B. Radioactive liquid and gaseous wastes are sampled and analyzed per the requirements in Selected Licensee Commitment (SLC)
Table 16.11.4-1, "Minimum Sampling Frequency and Analysis Program". Included in the gaseous effluent releases is an estimate of Carbon-14 radioactivity released in 2010 (Ref.
"Carbon-14Supplemental Information", contained in the ARERR for further information).
TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Gases
- 1. Total Release Ci 2.45E+00 1.62E+01 6.22E+00 2.25E+01 4.74E+01
- 2. Avg. Release Rate pCi/sec 3.15E-01 2.06E+00 7.82E-01 2.84E+00 1.50E+00 B. Iodine-131
- 1. Total Release Ci 0.00E+00 3.51E-04 0.00E+00 9.92E-05 4.50E-04
- 2. Avg. Release Rate pCi/sec 0.00E+00 4.46E-05 0.00E+00 1.25E-05 1.43E-05 C. Particulates Half Life >= 8 days
- 1. Total Release Ci 0.00E+00 1.72E-06 0.00E+00 2.39E-07 1.96E-06
- 2. Avg. Release Rate pCi/sec 0.00E+00 2.19E-07 0.00E+00 3.00E-08 6.21E-08 D. Tritium
- 1. Total Release Ci 1.33E+01 1.46E+01 1.53E+01 2.41E+01 6.73E+01
- 2. Avg. Release Rate PCi/sec 1.71E+00 1.86E+00 1.93E+00 3.03E+00 2.14E+00 E. Carbon-14
- 1. Total Release Ci 6.03E+00 4.98E+00 6.00E+00 5.47E+00 2.25E+01
- 2. Avg. Release Rate pCi/sec 7.76E-01 6.34E-01 7.55E-01 6.88E-01 7.13E-01 F. Gross Alpha Radioactivity
- 1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Avg. Release Rate pCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Gases XE-133 Ci 1.66E+00 6.67E+00 5.47E+00 2.16E+01 3.54E+01 XE-135 Ci 2.65E-02 0.OOE+00 O.OOE+00 0.OOE+00 2.65E-02 Totals for Period... Ci 1.68E+00 6.67E+00 5.47E+00 2.16E+01 3.55E+01
- 2. Iodines 1-131 Ci 0.OOE+00 3.46E-04 0.OOE+00 9.86E-05 4.45E-04 1-133 Ci 0.OOE+00 3.16E-06 0.OOE+00 3.42E-05 3.74E-05 Totals for Period... Ci 0.OOE+00 3.49E-04 0.OOE+00 1.33E-04 4.82E-04
- 3. Particulates Half Life >= 8 days CS-137 Ci 0.OOE+00 1.72E-06 0.OOE+00 0.OOE+00 1.72E-06 Totals for Period... Ci 0.OOE+00 1.72E-06 0.OOE+00 0.OOE+00 1.72E-06
- 4. Tritium H-3 Ci 1.27E+01 1.32E+01 1.40E+01 1.97E+01 5.95E+01 Totals for Period... Ci 1.27E+01 1.32E+01 1.40E+01 1.97E+01 5.95E+01
- 5. Carbon-14 C-14 Ci 1.81E+00 1.50E+00 1.80E+00 1.64E+00 6.74E+00 Totals for Period... Ci 1.81E+00 1.50E+00 1.80E+00 1.64E+00 6.74E+00
- 6. Gross Alpha Radioactivity
- No Nuclide Activities **
TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS EFFLUENTS - ELEVATED RELEASES - BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Gases AR-41 Ci 1.10E-01 l.1E-02 3.22E-02 3.23E-02 1.86E-01 KR-85 Ci 7.43E-02 8.10E+00 6.69E-01 4.92E-01 9.34E+00 KR-85M Ci 1.33E-02 0.00E+00 0.00E+00 0.OOE+00 1.33E-02 KR-88 Ci 1.54E-02 0.OOE+00 0.00E+00 0.OOE+00 1.54E-02 XE-131M Ci 0.00E+00 1.59E-02 0.00E+00 1.95E-03 1.78E-02 XE-133 Ci 3.60E-01 1.35E+00 4.96E-02 3.88E-01 2.15E+00 XE-133M Ci 0.OOE+00 3.96E-03 0.OOE+00 0.OOE+00 3.96E-03 XE-135 Ci 1.94E-01 7.04E-03 2.69E-04 3.44E-03 2.05E-01 Totals for Period... Ci 7.68E-01 9.49E+00 7.51E-01 9.18E-01 1.19E+01
- 2. Iodines 1-131 Ci 0.00E+00 3.38E-06 0.00E+00 5.84E-07 3.96E-06 1-133 Ci 0.00E+00 3.65E-07 0.00E+00 0.00E+00 3.65E-07 Totals for Period... Ci 0.OOE+00 3.74E-06 0.00E+00 5.84E-07 4.33E-06
- 3. Particulates Half Life >= 8 days CS-137 Ci 0.OOE+00 0.00E+00 0.00E+00 1.16E-08 1.16E-08 K-40 Ci 0.00E+00 0.OOE+00 0.00E+00 2.27E-07 2.27E-07 Totals for Period... Ci 0.00E+00 0.00E+00 0.00E+00 2.39E-07 2.39E-07
- 4. Tritium H-3 Ci 1.13E-02 1.78E-01 5.36E-02 1.56E-01 3.99E-01 Totals for Period... Ci 1.13E-02 1.78E-01 5.36E-02 1.56E-01 3.99E-01
- 5. Carbon-14 C-14 Ci 4.22E+00 3.49E+00 4.19E+00 3.83E+00 1.57E+01 Totals for Period ... Ci 4.22E+00 3.49E+00 4.19E+00 3.83E+00 1.57E+01
- 6. Gross Alpha Radioactivity
- No Nuclide Activities **
TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Gases
- No Nuclide Activities **
- 2. Iodines 1-131 Ci 0.OOE+00 1. 30E-06 0. OOE+00 0. OOE+00 1. 30E-06 Totals for Period... Ci 0.OOE+00 1.30E-06 0.OOE+00 0.OOE+00 1.30E-06
- 3. Particulates Half Life >= 8 days
- No Nuclide Activities **
- 4. Tritium H-3 Ci 6.07E-01 1.28E+00 1. 32E+00 4.19E+00 7.39E+00 Totals for Period... Ci 6.07E-01 1.28E+00 1. 32E+00 4.19E+00 7.39E+00
- 5. Carbon-14
- No Nuclide Activities **
- 6. Gross Alpha Radioactivity
- No Nuclide Activities **
TABLE IC EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Gases
- No Nuclide Activities **
- 2. Iodines
- No Nuclide Activities **
- 3. Particulates Half Life >= 8 days
- No Nuclide Activities **
- 4. Tritium H-3 Ci 0.OOE+00 3. 40E-09 0.OOE+00 4.28E-07 4.32E-07 Totals for Period... Ci 0.OOE+00 3.40E-09 0.OOE+00 4.28E-07 4.32E-07
- 5. Carbon-14
- No Nuclide Activities **
- 6. Gross Alpha Radioactivity
- No Nuclide Activities **
TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2010 Unit , QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products
- 1. Total Release Ci 2.93E-03 8.16E-03 1.33E-02 2.1OE-02 4.54E-02
- 2. Average Diluted Concentration
- a. Continuous Releases pCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
- b. Batch Releases pCi/ml 3.50E-10 9.64E-10 1.56E-09 2.45E-09 1.34E-09 B. Tritium
- 1. Total Release Ci 4.08E+02 3.73E+02 1.86E+02 1.30E+02 1.10E+03
- 2. Average Diluted Concentration
- a. Continuous Releases pCi/ml 1.97E-08 2.43E-08 2.49E-08 2.98E-08 2.47E-08
- b. Batch Releases pCi/ml 4.88E-05 4.40E-05 2.17E-05 1.51E-05 3.23E-05 C. Dissolved and Entrained Gases
- 1. Total Release Ci 4.OOE-04 8.54E-05 3.85E-04 0.OOE+00 8.70E-04
- 2. Average Diluted Concentration
- a. Continuous Releases pCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
- b. Batch Releases pCi/ml 4.78E-11 1.01E-11 4.50E-11 0.OOE+00 2.56E-11 D. Gross Alpha Radioactivity
- 1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
- 2. Average Diluted Concentration
- a. Continuous Releases pCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
- b. Batch Releases pCi/ml 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 E. Volume of Liquid Waste
- 1. Continuous Releases liters 4.46E+08 6.30E+08 5.32E+08 5.84E+08 2.19E+09
- 2. Batch Releases liters 1.48E+06 3.59E+06 1.57E+06 2.31E+06 8.96E+06 F. Volume of Dilution Water
- 1. Continuous Releases liters 8.37E+09 8.46E+09 8.55E+09 8.55E+09 3.39E+I10
- 2. Batch Releases liters 8.37E+09 8.46E+09 8.55E+09 8.55E+09 3.39E+10
TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID EFFLUENTS - CONTINUOUS MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Products
- No Nuclide Activities **
- 2. Tritium H-3 Ci 1.74E-01 2.21E-01 2.26E-01 2.72E-01 8. 93E-01 Totals for Period... Ci 1.74E-01 2.21E-01 2.26E-01 2.72E-01 8.93E-01
- 3. Dissolved and Entrained Gases
- No Nuclide Activities **
- 4. Gross Alpha Radioactivity
- No Nuclide Activities **
TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID EFFLUENTS - BATCH MODE Oconee Nuclear Station Units 1, 2, & 3 REPORT FOR 2010 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Products 1, AG-1IOM Ci 1.82E-05 1.80E-04 2.48E-04 1.31E-04 5.77E-04 CO-58 Ci 7.92E-04 7.60E-03 9.41E-03 2.OOE-02 3.78E-02 CO-60 Ci 0.OOE+00 0.OOE+00 4.64E-04 2.04E-04 6.68E-04 CR-51 Ci 0.OOE+00 1.39E-04 6.03E-04 0.OOE+00 7.41E-04 CS-134 Ci 0.OOE+00 0.OOE+00 1.66E-04 0.OOE+00 1.66E-04 CS-137 Ci 4.77E-05 4.51E-05 3.92E-04 5.81E-05 5.43E-04 1-131 Ci 0.OOE+00 2.32E-05 0.OOE+00 0.OOE+00 2.32E-05 MN-54 Ci 0.OOE+00 0.OOE+00 1.28E-04 2.51E-05 1.53E-04 NB-95 Ci 0.OOE+00 5.92E-05 8.16E-04 4.04E-04 1.28E-03 NB-97 Ci 0.OOE+00 0.OOE+00 5.77E-05 0.OOE+00 5.77E-05 SE-125 Ci 2.07E-03 1.09E-04 6.88E-04 0.OOE+00 2.87E-03 ZR-95 Ci 0.OOE+00 0.OOE+00 3.40E-04 1.91E-04 5.31E-04 Totals for Period... Ci 2.93E-03 8.16E-03 1.33E-02 2.10E-02 4.54E-02
- 2. Tritium H-3 Ci 4.08E+02 3.72E+02 1.86E+02 1.29E+02 1.10E+03 Totals for Period... Ci 4.08E+02 3.72E+02 1.86E+02 1.29E+02 1.10E+03
- 3. Dissolved and Entrained Gases XE-133 Ci 4. OOE-04 8.54E-05 3.85E-04 0. OOE+00 8. 70E-04 Totals for Period... Ci 4.OOE-04 8.54E-05 3.85E-04 0. OOE+00 8.70E-04
- 4. Gross Alpha Radioactivity
- No Nuclide Activities **
Attachment 2 Oconee Nuclear Site Supplemental Information
OCONEE NUCLEAR STATION SUPPLEMENTAL INFORMATION (January 1, 20 10 through December 31, 2010)
This attachment includes:
(1) Carbon-14 Supplemental Information (2) Regulatory Guide 1.21, Revision 1, Supplemental Information (3) Overall Error Estimate for Liquid and Gaseous Effluent Release Data
Page 1 of 2 Oconee 2010 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 has recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and if so, report the amount of C- 14 released. At Oconee, improvements over the years in effluent management practices and fuel performance have resulted in a decrease in the concentration and a change in the distribution of gaseous radionuclides released to the environment. As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at Oconee, as defined in Regulatory Guide 1.21, Rev. 2. Oconee's 2010 Annual Radioactive Effluent Release Report (ARERR) contains estimates of C- 14 radioactivity released in 2010, and estimates of public dose resulting from the C-14 effluent.
Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste at Oconee is not required (Ref. Reg. Guide 1.21, Rev. 2). The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation (Ref. Reg. Guide 1.21, Rev. 2). Many documents provide information related to the magnitude of C-14 in typical effluents from commercial nuclear power plants. Those documents suggest that nominal annual releases of C-14 in gaseous effluents are approximately 5 to 7.3 curies from PWRs (Ref. Reg. Guide 1.21, Rev. 2). A more recent study recommends a higher C-14 gaseous source term scaling factor of approximately 9.0 to 9.8 Ci/GWe-yr for a Westinghouse PWR and 10.4 to 11.3 for a CE PWR (Ref. EPRI 1021106). The EPRI report did not provide a source term scaling factor for a B&W PWR, but for the 2010 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 2010 results in a site total C-14 gaseous release estimate to the environment of -22 Curies. 70% of the C-14 gaseous effluent is assumed to be from batch releases (e.g. WGDTs), and 30% of C-14 gaseous effluent is assumed to be from continuous releases through the unit vents (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14", 2004).
C- 14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. Since the PWR operates with a reducing chemistry, most, if not all, of the C-14 species initially produced are organic (e.g., methane). As a general rule, C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment (e.g. during shutdown or refueling), a slow transformation from an organic to an inorganic chemical form can occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic with
Page 2 of 2 an average of 80% organic with the remainder being CO 2 (Ref. EPRI TR-105715). For the Oconee 2010 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 2011 Oconee ODCM. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released at Oconee in 2010 is well below the 10CFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit).
OCONEE NUCLEAR STATION 2010 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION I. REGULATORY LIMITS - STATION A. NOBLE GASES - AIR DOSE B. LIQUID EFFLUENTS - DOSE
- 1. CALENDAR QUARTER - GAMMA DOSE = 15 MRAD 1. CALENDAR QUARTER - TOTAL BODY DOSE = 4.5 MREM 2.- CALENDAR QUARTER - BETA DOSE = 30 MRAD 2. CALENDAR QUARTER - ORGAN DOSE = 15 MREM
- 3. CALENDAR YEAR - GAMMA DOSE = 30 MRAD 3. CALENDAR YEAR - TOTAL BODY DOSE = 9 MREM
- 4. CALENDAR YEAR - BETA DOSE = 60 MRAD 4. CALENDAR YEAR - ORGAN DOSE = 30 MREM C. IODINE - 131 AND 133, TRITIUM, PARTICULATES W/T 1/2 > 8 DAYS - ORGAN DOSE
- 1. CALENDAR QUARTER = 22.5 MREM
- 2. CALENDAR YEAR = 45 MREM II. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS A. GASEOUS EFFLUENTS - INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL B. LIQUID EFFLUENTS - INFORMATION FOUND IN 10CFR20, APPENDIX B, TABLE 2, COLUMN 2 III. AVERAGE ENERGY - NOT APPLICABLE IV. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY ANALYSES OF SPECIFIC RADIONUCLIDES IN SELECTED OR COMPOSITED SAMPLES AS DESCRIBED IN THE SELECTED LICENSEE COMMITMENTS ARE USED TO DETERMINE THE RADIONUCLIDE COMPOSITION OF THE EFFLUENT. SUPPLEMENTAL REPORT, PAGE 2, PROVIDES A
SUMMARY
DESCRIPTION OF THE METHOD USED FOR ESTIMATING OVERALL ERRORS ASSOCIATED WITH RADIOACTIVITY MEASUREMENTS.
V. BATCH RELEASES A. LIQUID EFFLUENT
- 1. 1.05E+02 = TOTAL NUMBER OF BATCH RELEASES
- 2. 2.27E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
- 3. 2.61E+02 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
- 4. 2.17E+02 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
- 5. 1.47E+02 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
- 6. 1.70E+04 = AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).
- B. GASEOUS EFFLUENT
- 1. 6.80E+01 = TOTAL NUMBER OF BATCH RELEASES.
- 2. 8.79E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
- 3. 5.12E+03 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
- 4. 1.29E+03 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
- 5. 2.71E+02 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
VI. ABNORMAL RELEASES (See "Unplanned Releases" Attachment)
OCONEE NUCLEAR STATION Overall Estimate of Error for Effluent Radioactivity Release Reported The estimated percentage of overall error for both Liquid and Gaseous effluent release data at Oconee Nuclear Station has been determined to be +/- 30.3%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:
(1) Flow Rate Determining Devices +/- 20%
(2) Counting Statistical Error +/- 20%
(3) Calibration Error +/- 10%
(4) Calibration Source Error +/- 2.5%
(5) Sample Preparation Error +/-3%
Attachment 3 Oconee Nuclear Site Solid Waste Disposal Report
OCONEE NUCLEAR STATION ANNUAL RADWASTE REPORT 4/25/2011 DUKE POWER COMPANY OCONEE NUCLEAR STATION SOLID RADIOACTIVE WASTE SHIPPED TO A DISPOSAL FACILITY REPORT PERIOD: JANUARY- DECEMBER YEAR: 2010 TOTAL TYPES OF WASTE NUMBER OF NUMBER OF WASTE CLASS CONTAINER BURIAL VOLUME ACTIVITY SHIPPED SHIPMENTS CONTAINERS A-U A-S B C TYPE CU. FT. CU. M. CURIES
- 1) WASTE FROM LIQUID SYSTEM (A) DEWATERED POWDEX RESIN 0 0 0 0 0 STC 0 0.00 0.00 (B) DEWATERED BEAD RESIN 2 2 0 0 2 0 TYPE A 240.6 6.81 83.17 (C) EVAPORATOR CONCENTRATES 0 0 0 0 0 0 0.00 0.00 (D) DEWATERED MECHANICAL FILTERS
- 1. PRIMARY FILTER MEDIA 0 0 0 0 0 2 TYPE A 240.6 6.81 36.11
- 2. SECONDARY FILTER MEDIA 0 0 0 0 0 0 STC 0 0.00 0.0000 (F) SOLIDIFIED (CEMENT) OIL, ACIDS,SLUDGES 0 0 0 0 0 STC 0.00 0.00
- 2) DRY SOLID WASTE (A) DRY ACTIVE WASTE (COMPACTED) (1) 56 56 56 0 0 0 STC 8856.6 250.80 1.46 (2) 32 32 32 0 0 0 STC 5672.91 160.64 2,010.05 (B) DRY ACTIVE WASTE (NON-COMPACTED) 1 0 0 1 0 TYPE A 120.3 3.41 4.61 (C) DRY ACTIVE WASTE (BROKERED) 0 0 0 0 0.00 0.00 (D) IRRADIATED COMPONENTS 0 0 0 0 0 TYPE B 0.00 0.00 TOTAL 91 91 88 0 3 2 15131 428.47 2135.40 NOTE: (1) SHIPMENTS FROM DURATEK ENVIROCARE OF UTAH OR CNSI @ BARNWELL (DAW)
(2) SHIPMENTS FROM DURATEK TO ENVIROCARE OF UTAH OR CNSI @ BARNWELL (METAL)
- SHIPMENTS MADE FROM OTHER COMPANYS SO INFORMATION IS NOT KNOWN Page 1 of 14
Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER 2010 WASTE TYPE: POWDEX RESIN ISOTOPE: % ABUNDANCE/LINER # OF LINERS SHIPPED TO ENVIROCARE 0 # OF SHIPMENTS TO ENVIROCARE 0 TOTAL AVE.
CR-51 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 #DIV/0!
MN-54 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 #DIV/O!
CO-57 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 #DIV/0!
CO-58 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 #DIVIO!
CO-60 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 #DIV/0!
NB-95 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
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 #DIV/0!
CS-134 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 #DIV/0!
RU-103 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I!
AG-110m 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 #DIV/0!
SB-125 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 #DIV/01 1-131 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 #DIV/0I CS-1 37 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 #DIV/0!
H-3 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 #DIV/0!
NI-63 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 #DIV/0!
FE-55 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 #DIV/0!
SR-90 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
TE-125m 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 #DIV/0!
CS-136 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 #DIV/0I XE-133 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 #DIV/0!
C-14 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 #DIV/0!
PU-241 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I TRU 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 #DIV/O!
FE-59 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 #DIV/0!
SB-124 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 #DIV/0I RU-106 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CE-144 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 #DIV/0!
TE-132 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
AM-241 0.0000 0.0000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 . 0.00 0.00 #DIV/0!
TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.00 #DIV/O0 CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 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 2 of 14
Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY -DECEMBER 2010 WASTE TYPE: PRIMARY RESIN
- OF LINERS SHIPPED TO CNSI 2 ISOTOPE: % ABUNDANCE/LINER # OF SHIPMENTS TO CNSI TOTAL AVE.
AG-110m 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 AM-241 0.0086 0.0005 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0091 0.0046 Be-7 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 C-14 0.4747 0.2735 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.7482 0.3741 CE-144 5.2844 0.0879 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 5.3723 2.6862 CM-242 0.0059 0.0001 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0060 0.0030 CM-243/44 0.0104 0.0005 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0109 0.0055 CO-57 0.7497 0.8150 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 1.5647 0.7824 CO-58 38.8831 23.8095 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 62.6926 31.3463 CO-60 3.5264 4.3129 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 7.8393 3.9197 CR-51 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 CS-134 9.6070 7.2789 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 16.8859 8.4430 CS-136 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 CS-137 13.5471 13.1156 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 26.6627 13.3314 FE-55 3.5367 8.0816 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.6183 5.8092 FE-59 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 H-3 0.0293 0.0070 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0363 0.0182 1-129 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 1-131 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 MN-54 0.7384 1.7687 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 2.5071 1.2536 NB-95 0.0703 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0703 0.0352 NI-59 0.0505 0.1864 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.2369 0.1185 NI-63 10.7549 39.4558 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 50.2107 25.1054 PU-238 0.0164 0.0007 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0171 0.0086 PU-239140 0.0127 0.0004 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0131 0.0066 PU-241 0.5895 0.0265 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.6160 0.3080 RU-106 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 SB-124 0.0158 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0158 0.0079 SB-125 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 SNA 13 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 SR-89 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 SR-90 11.4788 0.3061 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 11.7849 5.8925 TC-99 0.4116 0.0815 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.4931 0.2466 TE-125m 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 XE-133 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 ZN-65 0.0000 0.2245 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.2245 0.1123 ZR-95 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 TOTAL 99.80 99.83 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 199.41 99.71 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 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 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 Page 3 of 14
Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY- DECEMBER 2010 WASTE TYPE: PRIMARY RESIN CURIES 9.67 73.5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 83.17 CU. FT. 120.3 120.3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 240.6 CU. M 3.41 3.41 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 6.81 RSR# 10-2006 10-2061 Page 4 of 14
Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER 2010 WASTE TYPE: COMPACTED DAW (DURATEK)
- OF SHIPMENTS FROM PROCESSOR TO ENVIROCARE 56 # OF CONTAINERS FROM PROCESSOR TO ENVIROCARE 56
- OF SHIPMENTS FROM PROCESSOR TO BARNWELL 0 # OF CONTAINERS FROM PROCESSOR TO BARNWELL 0 CU. FT.. CURIES CU. FT. DISPOSAL CI TO DISPOSAL RSR # SHIPPED SHIPPED FACILITY FACILITY COMPLETED 09-2058 0 0 1.78571 0.00105 09-2060 0 0 2.28571 0.00139 09-2061 0 0 260.5714 0.09038 09-2064 0 0 180 0.00213 10-2001 486.5 0.0031 486.500 0.00310 10-2002 486.5 0.0027 486.500 0.00270 10-2003 486.5 0.0028 486.500 0.00280 10-2004 1868.8 0.0482 197.714 0.04820 10-2005 224.94 0.5190 68.840 0.51949 10-2007 1868.8 0.0077 195.500 0.00706 10-2008 1159.34 0.3990 133.000 0.39924 10-2013 1868.6 0.0140 155.429 0.01392 10-2015 934.4 0.0042 86.000 0.00415 10-2016 897 0.0012 0.786 0.00001 10-2017 934.4 0.0012 56.000 0.00116 10-2018 1668.8 0.0142 163.429 0.01420 10-2019 486.5 0.0025 486.500 0.00250 10-2021 756 0.0573 206.857 0.00057 10-2023 0 0.0000 108.571 0.00095 10-2024 0 0.0000 31.500 0.00014 10-2025 0 0.0000 62.000 0.00037 10-2027 934.4 0.00396 70.157 0.00393 10-2028 934.4 0.0184 354.286 0.01997 10-2029 0 0.0000 193.129 0.00086 10-2030 934.4 0.0082 81.429 0.00821 10-2040 934.4 0.0008 49.714 0.00077 10-2041 934.4 0.0170 93.357 0.01693 10-2048 0 0.0000 167.357 0.00107 10-2049 931 0.0024 474.286 0.00244 10-2050 934.4 0.0013 175.429 0.00133 10-2051 934.4 0.0013 166.571 0.00130 10-2053 1868.8 0.0718 277.142 0.07187 10-2054 1668.8 0.0747 298.071 0.07467 10-2055 1868.8 0.0004 166.857 0.00041 10-2056 1868.8 0.0159 205.071 0.01575 10-2057 1868.8 0.0542 296.000 0.05417 10-2059 1814.8 0.0309 255.829 0.03090 10-2060 1868.8 0.0205 292.514 0.02044 10-2062 1599.4 0.01 08 248.643 0.00933 10-2065 1318.4 0.0028 324.571 0.00285 10-2066 1318.4 0.0045 291.429 0.00399 Page 5 of 14
Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER 2010 WASTE TYPE: COMPACTED DAW (DURATEK) 10-2067 1690.4 0.0101 8.143 0.00026 10-2074 1226.95 0.4040 155.500 0.02029 10-2068 1868.8 0.1360 354.857 0.08184 10-2075 1868.8 0.0340 0.000 0.00000 10-2076 1868.8 0.0335 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 0 0.0000 0.000 0.00000 TOTAL 31390.55 0.935 8856.61 1.46412 TOTAL CURIES BURIED 1.464 TOTAL CUBIC FEET BURIED 8856.61 TOTAL CUBIC METERS 250.80 Page 6 of 14
Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER 2010 WASTE TYPE: COMPACTED DAW (DURATEK)
- OF SHIPMENTS FROM ONS TO CNSI
- OF CONTAINERS FROM ONS TO CNSI RSR CUBIC NUMBER FEET CURIES A-U A-S B C 10-2073 120.3 4.61 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 120.3 4.61 0 TOTAL CUBIC METERS 3.41 Page 7 of 14
Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER 2010 WASTE TYPE: METAL (CNSI,DURATEK,ENVIROCARE)
- OF SHIPMENTS TO DECON FACILITY 21 # OF SHIPMENTS TO ENVIROCARE: 32
- OF CONTAINERS TO DECON FACILITY 22 # OF CONTAINERS TO ENVIROCARE: 32 DECONIDISP. CU. FT.. CURIES CU. FT. TO CURIES TO RSR # FACILITY TO PROCESSOR TO PROCESSOR DISPOSAL FACILITY DISPOSAL FACILITY COMPLETED 09-2019 0 0 30.00 0.00007 09-2046 0 0 18.86 0.00019 09-2047 0 0 419.23 0.00471 09-2061 0 0 1.43 0.00013 10-2007 0 0 22.21 0.00064 10-2012 504 0.0055 336.43 0.00518 10-2014 828 0.00837 346.86 0.00837 10-2015 399 0.00357 157.43 0.00357 10-2016 918.75 0.00153 199.64 0.00189 10-2017 532 0.00209 196.71 0.00209 10-2023 784 0.00193 124.00 0.00099 10-2024 931 0.00163 341.36 0.00149 10-2025 871.38 0.00244 248.60 0.00170 10-2032 855 0.00251 427.43 0.00251 10-2033 931 0.00234 445.14 0.00234 10-2027 1068.75 0.00150 267.14 0.00149 10-2028 931 0.00152 0.00 0.00000 10-2029 931 0.00156 159.73 0.00071 10-2030 931 0.00153 271.43 0.00153 10-2031 931 0.00185 326.86 0.00185 10-2040 931 0.00139 299.14 0.00139 10-2041 931 0.00132 201.00 0.00161 10-2042 1596 0.00209 274.29 0.00205 10-2043 931 0.00207 382.57 0.00208 10-2048 1862 0.00233 175.43 0.00084 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 Page 8 of 14
Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER 2010 WASTE TYPE: METAL (CNSI,DURATEK,ENVIROCARE) 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 0 0 0.00 0.00000 TOTAL 18597.88 0.04907 5672.91 2010.04940 TOTAL CUBIC METERS 160.642 Page 9 of 14
Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER 2010 WASTE TYPE: IRRADIATED COMPONANT
- OF CONTAINERS SHIPPED TO CNSI/DURATEK ISOTOPE: % ABUNDANCE/LINER # OF SHIPMENTS TO CNSI/DURATEK 0 TOTAL AVE.
AG-110m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
C-14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
CE-144 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
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 #DIV/O!
CM-243 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
CO-57 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CO-58 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CO-60 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CR-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 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CS-134 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CS-136 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 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/0I CS-1 37 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/01 FE-55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
FE-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
H-3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
I-131 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
MN-54 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
NB-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 #DIV/O!
NI-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
NI-63 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
PU-238 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
PU-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 #DIV/0!
RU-103 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
RU-106 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
SB-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
SB-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
TA-182 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
TE-125m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
TRU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 #DIV/0!
XE-1 33 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.0000 #DIV/0O 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 0.0000 #DIV/01 TOTAL 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CURIES 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 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 10 of 14
OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY- DECEMBER 2010 WASTE TYPE: PRIMARY FILTERS
- OF DRUMS/UNERS TO CNSI- 2 ISOTOPE: # OF SHIPMENTS TO CNSI -2 TOTAL AVE.
AG-110m 0.00000 0.57 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.57 #DIV/0!
AM-241 0.00540 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 #DIV/0!
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 #DIV/0I C-14 3.55630 5.55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 9.10 #DIV/0!
CD-109 0.00000 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
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 #DIV/0!
CE-144 0.18380 0.37 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.55 #DIV/0I CM-242 0.00000 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 #DIV/0!
CM-243/44 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 #DIV/O!
CO-57 0.16800 0.87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.04 #DIV/0!
CO-58 1.84150 67.15 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 0.00 68.99 #DIV/0!
CO-60 4.36620 6.33 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 10.7000 #DIV/0!
CR-51 0.00000 1.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.14 #DIV/0' CS-134 13.76761 4.43 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 18.20 #DIV/01 CS-1 36 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 #DIV/0' CS-137 29.82430 6.39 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 36.21 #DIV/0!
FE-55 41.90140 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 41.90 #DIV/0!
FE-59 0.00000 0.27 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.27 #DIV/0!
H-3 4.57750 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4.58 #DIV/0I 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 #DIV/0I 1-129 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 #DIV/0!
MN-54 0.51760 2.18 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2.70 #DIV/0!
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 #DIV/0!
NB-95 0.00070 0.90 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.90 #DIV/0!
NI-59 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 #DIV/O!
NI-63 0.00850 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 #DIV/0!
PU-238 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 #DIV/01 PU-239 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 #DIV/0O PU-241 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 #DIV/0I 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 #DIV/0!
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 #DIV/0!
SB-124 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 #DIV/0I SB-125 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 #DIV/0!
SN-113 0.00280 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 0.00 0.05 #DIV/0!
SR-89 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 #DIV/0I SR-90 0.02820 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.028 #DIV/OI 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 0.0000 #DIV/0I TE-125m 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 #DIV/0!
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 #DIV/0!
ZN-65 0.04230 0.43 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.4733 #DIV/0!
ZR-95 0.00000 3.34 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.3377 #DIV/0!
TOTAL 100.79 99.98 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 196.96 #DIV/0' CLASS C 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 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 (1 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 OCONEE NUCLEAR STATION SOLID RADWASTE REPORT Page 11 of 14
REPORT PERIOD: JANUARY- DECEMBER 2010 WASTE TYPE: PRIMARY FILTERS CURIES 28.5 7.61 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 36.11 CU. FT. 120.3 120.3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 240.6 CU. M 3.40658 3.40658 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.813162 RSR# 10-2070 10-2072 0 Page 12 of 14
Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY - DECEMBER 2010 WASTE TYPE: SECONDARY FILTERS
- OF CONTAINERS SHIPPED TODURATEK I # OF CONTAINERS SHIPPED TO CNSI I ENVIROCARE 0
- OF SHIPMENTS TO DURATEK 1 # OF SHIPMENTS TO CNSI / ENVIROCARE 0 ISOTOPE: TOTAL AVE.
AG-108m 0.08 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.08 0.08 AG-11Om 11.50 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 11.50 11.50 AM-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 C-14 20.42 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 20.42 20.42 CE-144 0.22 0.00 0.00 0.00 0.00 0.00 0.00 0,00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.22 0.22 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 CM-243 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CO-57 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 0.16 CO-58 1.19 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.19 1.19 CO-60 4.69 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 4.69 4.69 CR-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 0.00 0.00 0.00 0.00 CS-134 0.31 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.31 0.31 CS-136 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CS-137 7.94 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 0.00 7.94 7.94 FE-55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 FE-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 H-3 48.03 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 0.00 48.03 48.03 1-131 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 MN-54 0.45 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.45 0.45 NB-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 NI-63 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 PU-238 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 PU-239 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 PU-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 RU-103 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 RU-106 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SB-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SB-125 4.99 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SR-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 0.00 0.00 0.00 0.00 SR-90 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TE-125m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TRU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 XE-133 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ZR-95 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 TOTAL 100.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 95.01 95.01 CLASS C 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CLASS AU 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 CURIES 2.64E-04 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.00026 FT3 Shipped 54 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 54 CU. M Shipped 1.5291 0.0000 0.0000 0.0000 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.52914 FT3 Buried 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. M Buried 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0 RSR# 10-2059 Page 13 of 14
Oconee Nuclear Station Annual Report OCONEE NUCLEAR STATION SOLID RADWASTE REPORT REPORT PERIOD: JANUARY- DECEMBER 2010 WASTE TYPE: SOLIDIFIED (CEMENT) OIL, ACIDS, SLUDGES
- OF CONTAINERS SHIPPED 0 ISOTOPE: % ABUNDANCE/LINER # OF SHIPMENTS 0 TOTAL AVE.
CR-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 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
MN-54 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CO-57 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0I CO-58 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CO-60 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
NB-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 #DIV/0!
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 #DIV/0!
CS-134 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
RU-103 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
AG-11Om 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
SB-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
1-131 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CS-137 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
H-3 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
NI-63 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/O!
FE-55 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
SR-90 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
TE-125m 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CS-136 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
XE-1 33 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
C-14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
PU-241 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
TRU 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
FE-59 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
SB-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
RU-106 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
CE-144 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
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 #DIV/0I 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 #DIV/0!
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/0I 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 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CU. FT. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 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 0 RSR#
Page 14 of 14
Attachment 4 Oconee Nuclear Site Meteorological Data
OCONEE NUCLEAR STATION 2010 METEOROLOGICAL JOINT FREQUENCY DISTRIBUTIONS OF WIND SPEED, WIND DIRECTION, AND ATMOSPHERIC STABILITY USING WINDS AT THE 10 METER LEVEL (Hours of Occurrence)
ONS 2010 The SAS System 09:11 Wednesday, March 9, 2011 1 The FREQ Procedure Table of STAB by CALM STAB CALM Freque ncy CALM WIND Total
- 1. 0 723 723 2 0 609 609 3 0 688 688 4 2 3385 3387 5 2 2669 2671 6 0 405 405 7 0 138 138 Total 4 8617 8621 Frequency Missing = 138 The SAS System 09:11 Wednesday, March 9, 2011 2 The MEANS Procedure Analysis Variable : WS Maximum 10.4160320 The SAS System 09:11 Wednesday, March 9, 2011 3 SECTOR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW No. No. No. No. No. No. No. No. No. No. No. No. No. No. No. No.
STAB WSCLS (m/s)
A 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0.75-1.00 0 0 0 0 1 0 1 1 1 0 0 1.00-1.25 2 1 1 0 1 1 0 2 0 3 0 1.25-1.50 3 3 1 1 2 3 5 2 0 0 3 1.50-2.00 12 11 8 4 3 13 50 20 14 10 3 2.00-3.00 6 20 19 15 11 48 137 57 14 6 10 3.00-4.00 1 7 8 3 1 15 26 11 5 2 4 4.00-5.00 0 3 0 0 0 0 8 2 4 5 4 5.00-6.00 1 4 0 0 0 0 3 4 2 3 1 0 0 0 1 2 11 4 6.00-8.00 0 0 0 0 0 0 0 0 0 1 0 1 4 8.00-10.00 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 B 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0.75-1.00 0 1 0 0 0 1 0 1 0 0 0 1.00-1.25 1 2 0 1 0 4 2 1 0 0 0 1.25-1.50 7 2 0 1 2 1 7 2 6 9 3 1.50-2.00 11 19 7 2 3 14 53 19 13 11 12 I of 3
2.00-3.00 2 5 12 19 10 3 3 1 9 39 74 28 3 2 3 3 3.00-4.00 2 1 5 8 1 1 0 1 1 8 26 11 1 3 4 0 4.00-5.00 1 0 4 2 0 0 0 0 1 1 8 10 2 4 3 2 5.00-6.00 0 0 0 0 0 0 0 0 0 0 1 2 2 5 4 0 6.00-8.00 0 0 0 0 0 0 0 0 0 0 1 1 6 0 4 0 8.00-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 10.01-Max. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 c 0.46-0.75 0 0 .0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.75-1.00 0 1 1 1 0 0 0 0 0 0 1 1 0 0 0 0 1.00-1.25 2 2 4 0 0 3 0 0 2 1 7 5 0 1 2 2 1.25-1.50 4 13 1 1 3 1 1 3 4 0 15 8 7 7 4 4 1.50-2.00 7 18 14 13 7 4 5 6 10 18 30 17 20 10 5 1 2.00-3.00 2 6 8 31 17 5 4 1 10 26 64 20 5 5 2 0 3.00-4.00 1 1 11 13 1 0 0 0 1 13 19 5 10 3 6 0 4.00-5.00 Q 1 3 1 0 0 0 0 0 3 6 9 2 8 7 3 5.00-6.00 0 0 0 0 0 0 0 0 0 0 4 3 6 8 4 3 6.00-8.00 0 0 0 0 0 0 0 0 0 0 3 1 8 11 4 0 8.00-10.00 0 0 0 0 0 0 0 0 0 0 0 0 1 2 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 D 0.46-0.75 5 1 2 2 2 5 0 0 3 1 2 3 2 3 3 7 0.75-1.00 28 12 14 6 7 7 4 5 8 8 17 29 35 32 21 29 1.00-1.25 36 29 19 15 12 10 9 12 15 16 26 33 22 28 27 38 1.25-1.50 18 30 35 32 25 21 20 23 20 27 34 35 43 28 28 23 1.50-2.00 29 28 65 109 61 35 39 40 35 48 65 50 42 20 16 17 2.00-3.00 29 15 68 139 48 10 24 11 18 89 125 73 39 44 46 37 3.00-4.00 11 10 30 38 2 1 1 0 2 36 68 43 47 63 30 17 4.00-5.00 4 9 2 4 0 0 0 0 0 3 57 63 31 41 20 9 5.00-6.00 0 2 1 0 0 0 0 0 0 0 13 28 14 22 16 4 6.00-8.00 0 0 0 0 0 0 0 0 0 0 0 1 3 6 9 0 8.00-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0.46-0.75 13 14 14 9 6 4 5 3 4 3 7 10 15 18 22 13 0.75-1.00 92 58 41 34 23 19 23 18 15 20 33 45 64 96 118 100 1.00-1.25 54 31 31 29 33 26 24 23 31 28 17 20 50 58 70 62 1.25-1.50 31 12 29 29 45 32 35 24 26 21 39 27 23 21 37 38 1.50-2.00 15 12 26 28 30 28 45 33 41 19 36 19 7 16 27 20 2.00-3.00 1 3 7 13 16 7 12 12 6 25 18 21 17 12 18 8 3.00-4.00 2 1 0 4 0 0 0 0 0 3 5 16 7 2 2 0 4.00-5.00 0 0 0 3 0 0 0 0 0 0 1 5 1 1 0 0 5.00-6.00 0 0 0 0 0 0 0 0 0 0 0 2 1 0 0 0 6.00-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 of 3
8.00-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
- 10. 01-Max 0 0 0 0 1 1 3 4 1 F' 0.46-0.75 4 1 2 9 41 29 0.75-1.00 2 2 13 69 35 1.00-1.25 1, 2 1 5 22 32 1.25-1.50 1 3 1 0 2 13 4
1.50-2.00 3 3 0 0 1 0 2.00-3.00 0 1 0 0 3.00-4.00 0 0 0 0 0 0 4.00-5.00 0 0 0 0 0 0 0 0 5.00-6.00 0 0 0 0 0 0 6.00-8.00 0 0 0 0 0 0 8.00-10.00 0 0 0 0 0
- 10. 01-Max 0 0 4 4 2 1 0 G 0.46-0.75 0 6 22 8 0 0 0.75-1.00 0 0 4 16 13 1.00-1.25 0 0 3 18 13 0 0 1.25-1.50 0 0 1 0 1.50-2.00 0 0 0 0 0 0 0 0 2.00-3.00 0 0 0 0 0 0
3.00-4.00 0 0 0 0 0 4.00-5.00 0 0 0 0 0 5.00-6.00 0 0 0 0. 0 0 0 0
6.00-8.00 0 0 0 0 0 0 8.00-10.00 0 0 0 0
- 10. 01-Max 0 0 3 of 3
Attachment 5 Oconee Nuclear Site Unplanned OffsIte Releases The ONS SLC 16.11.9, Radioactive Effluent Release Report, states:
"The Annual Radioactive Effluent Release Report shall include the following information for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents:
- a. A description of the event and equipment involved;
- b. Cause(s) for the unplanned release;
- c. Actions taken to prevent recurrence; and,
- d. Consequences of the unplanned release."
There were no known unplanned releases of radioactivity (material, liquid, or airborne) from Oconee Nuclear Station in 2010.
Attachment 6 Oconee Nuclear Site Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)
OCONEE NUCLEAR STATION ASSESSMENT OF RADIATION DOSE FROM RADIOACTIVE EFFLUENTS AND ALL URANIUM FUEL CYCLE SOURCES TO MEMBERS OF THE PUBLIC This attachment includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter and for the calendar year of this report. The effluent dose calculations consider radionuclides identified as part of the liquid and gaseous wastes sample and analysis program.
Radioactive liquid and gaseous wastes are sampled and analyzed per the requirements in Selected Licensee Commitment (SLC) Table 16.11.4-1, "Minimum Sampling Frequency and Analysis Program". Included in the gaseous effluent dose calculations is an estimate of the dose contributed by Carbon-14 (Ref. "Carbon-14Supplemental Information", contained in the ARERR for furtherinformation). The "Fuel Cycle Calculation" attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 8 km of Oconee for the calendar year of this report to show conformance with 40CFR190. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 1 st Quarter 2010
= IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS- Quarter 1 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD BONE 8.98E-02 2.25E+01 3.99E-01 Maximum Organ Dose Receptor Location: 1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage C-14 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS Quarter 1 2010 Dose Limit % of Period-Limit (mrad) (mrad) Limit Ql - Maximum Gamma Air Dose 1.28E-04 1.50E+01 8.52E-04 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage AR-41 4.25E+01 XE-133 2.95E+01 XE-135 1.75E+01 KR-88 9.71E+00 Ql - Maximum Beta Air Dose 1.72E-04 3.OOE+01 5.72E-04 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)
Nuclide Percentage XE-133 6.54E+01 XE-135 1.68E+01 AR-41 1.12E+01
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 2 nd Quarter 2010
= IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS=...= Quarter 2 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD BONE 7.42E-02 2.25E+01 3.30E-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 9.99E+01 NOBLE GAS DOSE LIMIT ANALYSIS Quarter 2 2010 =
Dose Limit % of Period-Limit (mrad) (mrad) Limit Q2 - Maximum Gamma Air Dose 1.64E-04 1.50E+01 1.09E-03 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage XE-133 9.16E+01 Q2 - Maximum Beta Air Dose 1.29E-03 3.OOE+01 4.29E-03 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)
Nuclide Percentage KR-85 6.50E+01 XE-133 3.47E+01
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 3 rd Quarter 2010 IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS ---- Quarter 3 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD BONE 8.94E-02 2.25E+01 3.97E-01 Maximum Organ Dose Receptor Location: 1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage C-14 1.00E+02
-- NOBLE GAS DOSE LIMIT ANALYSIS Quarter 3 2010 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q3 - Maximum Gamma Air Dose 1.20E-04 1.50E+01 7.98E-04 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage XE-133 8.62E+01 AR-41 1.33E+01 Q3 - Maximum Beta Air Dose 3.82E-04 3.OOE+01 1.27E-03 Maximum Beta Air Dose Receptor Location: 1.0,Mile SW Major Contributors (5% or greater to total)
Nuclide Percentage XE-133 8.04E+01 KR-85 1.81E+01
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 4th Quarter 2010
= IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS Quarter 4 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD BONE 8.14E-02 2.25E+01 3.62E-01 Maximum Organ Dose Receptor Location: 1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage C-14 1.00E+02 NOBLE GAS DOSE LIMIT ANALYSIS Quarter 4 2010 Dose Limit % of Period-Limit (mrad) (mrad) Limit Q4 - Maximum Gamma Air Dose 4.29E-04 1.50E+01 2.86E-03 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage XE-133 9.61E+01 Q4 - Maximum Beta Air Dose 1.28E-03 3.OOE+01 4.27E-03 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)
Nuclide Percentage XE-133 9.56E+01
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 GASEOUS ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 ANNUAL 2010
=,IODINE, H3, and PARTICULATE DOSE LIMIT ANALYSIS Annual 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD BONE 3.35E-01 4.50E+01 7.44E-01 Maximum Organ Dose Receptor Location: 1.0 Mile SW Critical Pathway: Vegetation Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage C-14 1.OOE+02 NOBLE GAS DOSE LIMIT ANALYSIS Annual 2010 Dose Limit % of Period-Limit (mrad) (mrad) Limit Yr - Maximum Gamma Air Dose 8.40E-04 3.OOE+01 2.80E-03 Maximum Gamma Air Dose Receptor Location: 1.0 Mile SW Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage XE-133 8.37E+01 AR-41 1.09E+01 Yr - Maximum Beta Air Dose 3.12E-03 6.OOE+01 5.21E-03 Maximum Beta Air Dose Receptor Location: 1.0 Mile SW Major Contributors (5% or greater to total)
Nuclide Percentage XE-133 6.69E+01 KR-85 3.09E+01
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 1st Quarter 2010
= BATCH LIQUID RELEASES Quarter 1 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (orem) (mrem) Limit Q1 - Maximum Organ Dose CHILD LIVER 6.27E-02 1.50E+01 4.18E-01 Q1 - Total Body Dose ADULT 5.87E-02 4.50E+00 1.31E+00 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 9.03E+01 CS-137 9.68E+00 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 9.27E+01 CS-137 7.17E+00
-= CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 1 2010 --
Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q1 - Maximum Organ Dose CHILD LIVER 2.29E-05 1.50E+01 1.53E-04 Q1 - Total Body Dose CHILD 2.29E-05 4.50E+00 5.09E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.OOE+02
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 2 nd Quarter 2010
= BATCH LIQUID RELEASES Quarter 2 2010 -
Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q2 - Maximum Organ Dose ADULT GI-LLI 7.61E-02 1.50E+01 5.07E-01 Q2 - Total Body Dose ADULT 5.41E-02 4.50E+00 1.20E+00 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 6.53E+01 NB-95 2.97E+01 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 9.18E+01 CS-137 7.36E+00 CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 2 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q2 - Maximum Organ Dose CHILD LIVER 2.86E-05 1.50E+01 1.90E-04 Q2 - Total Body Dose CHILD 2.86E-05 4.50E+00 6.35E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1. OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.00E+02
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 3 rd Quarter 2010
= BATCH LIQUID RELEASES Quarter 3 2010 -
Critical Critical Dose Limit Max % of Period-Limit Age Organ (torem) (mrem) Limit Q3 - Maximum Organ Dose ADULT GI-LLI 3. 44E-01 1. 50E+01 2.29E+00 Q3 - Total Body Dose ADULT 8.51E-02 4.50E+00 1. 89E+00 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage NB-95 9.07E+01 H-3 7.21E+00 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage CS-137 4.07E+01 CS-134 2. 93E+01 H-3 2.91E+01
= CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 3 2010 -
Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q3 - Maximum Organ Dose CHILD LIVER 2.95E-05 1.50E+01 1.97E-04 Q3 - Total Body Dose CHILD 2.95E-05 4.50E+00 6.56E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1. OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.00OE+02
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 4t Quarter 2010
-- BATCH LIQUID RELEASES Quarter 4 2010 -=
Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (trem) Limit Q4 - Maximum Organ Dose ADULT GI-LLI 1.82E-01 1.50E+01 1. 21E+00 Q4 - Total Body Dose ADULT 2.36E-02 4.50E+00 5. 25E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage NB-95 8.49E+01 H-3 9.50E+00 CO-58 5.23E+00 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 7.31E+01 CS-137 2.17E+01 CONTINUOUS LIQUID RELEASES (CTP 3) Quarter 4 2010 -
Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Q4 - Maximum Organ Dose CHILD LIVER 3.53E-05 1.50E+01 2.36E-04 Q4 - Total Body Dose CHILD 3.53E-05 4.50E+00 7.86E-04 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1. OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.00OE+02
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/10 TO 1/1/11 LIQUID ANNUAL DOSE
SUMMARY
REPORT Oconee Nuclear Station Units 1, 2, & 3 ANNUAL 2010
= BATCH LIQUID RELEASES - Annual 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose ADULT GI-LLI 6.57E-01 3.OOE+01 2.19E+00 Yr - Total Body Dose ADULT 2.22E-01 9.OOE+00 2.46E+00 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage NB-95 7.44E+01 H-3 2.23E+01 Total Body Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 6.60E+01 CS-137 2.17E+01 CS-134 1.12E+01 CONTINUOUS LIQUID RELEASES (CTP 3) Annual 2010 Critical Critical Dose Limit Max % of Period-Limit Age Organ (mrem) (mrem) Limit Yr - Maximum Organ Dose CHILD LIVER 1.16E-04 3.OOE+01 3.88E-04 Yr - Total Body Dose CHILD 1.16E-04 9.OOE+00 1.29E-03 Maximum Organ Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1. OOE+02 Total Body Critical Pathway: Potable Water Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.OOE+02
Oconee Nuclear Station 2010 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-14Supplemental 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:
I. 2010 Oconee 40CFR190 Effluent Dose Summary The 40CFR190 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 = 2.59E-01 mrem Maximum Location: 1.0 Mile, Southwest Sector Critical Age: Child Gas non-NG Contribution: 34%
Gas NG Contribution: <1%
Liquid Contribution: 66%
Maximum Organ (other than TB) Dose = 6.90E-01 mrem Maximum Location: 1.0 Mile, Southwest Sector Critical Age: Adult Critical Organ: GI-LLI Gas Contribution: 5%
Liquid Contribution: 95%
II. 2010 Oconee 40CFR190 ISFSI Dose Summary Direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at Oconee have been calculated and documented in the "Oconee Nuclear Site IOCFR72.212 Written Evaluations" report. As discussed in the report, the dose rate at 500 meters is 6.84 mrem per year. The nearest resident from the Oconee ISFSI is ~
1600 meters so the dose rate at the nearest resident location would be much less than 6.84 mrem per year.
The following excerpt, "C. 10CFR72.212(b)(2)(i)(C)- Requirements of 72.104", from the "Oconee Nuclear Site 10CFR72.212 Written Evaluations" report is provided to document the method used to estimate the Oconee ISFSI dose to the nearest "real individual".
The following three pages are excerpted from the Oconee Nuclear Site, "Independent Spent Fuel Storage Installation",
10CFR72.212 Evaluation for Phase VI report (Rev. 0, 6/7/2010).
C. 10CFR72.212(b)(2)(i)(C)- Requirements of 72.104
"...the requirementsoff 72.104 have been met."
10 CFR 72.104, as clarified by ISG-133 6 , stipulates that the licensee perform dose evaluations which establish that any real individual beyond the controlled area boundary not sustain a dose equivalent in excess of 0.25 mSv (25- mrem) due to direct radiation from the Independent Spent Fuel Storage Installation and other fuel cycle operations in the area. This same dose limit is stipulated by the EPA for the fuel cycle in 40 CFR 190.10(a). Also operational restrictions for ALARA and limits for effluents must be established.
In accordance with these requirements, Duke Energy Corporation has performed dose calculations that model the characteristics (initial enrichment, burnup and Oconee Nuclear Site 10CFR72.212 Written Evaluations for Phase VI, Rev. 0 Page 20 of 27
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 ISFS137 . Calculation OSC-8675 38 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 39 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 4° of the SCALE Code System was used to perform the fuel depletion and characterization calculations using the cross section sets created by SAS2. These characterization calculations yielded the photon and neutron source terms to be used as input to subsequent shielding calculations. As mentioned above, problem-dependent cross section sets were developed for these analyses since ORIGEN-S was used within the SAS2 sequence. Duke Energy Corporation Radiological Engineering is experienced in the use of the SCALE Code System, and the SCALE Code System is installed and maintained under the purview of the pertinent software and data quality assurance program.
The results of the radiation source term calculation were used as input to Calculation OSC-8706 4 1 to evaluate the shielding characteristics of a single Horizontal Storage Module. The MCNP Monte Carlo particle transport computer code 42 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-1201.30-00-001043 contains the verification and validation for MCNP5, while SDQA-30269-NG0 69 documents the quality control measures in place for MCNP5).
Calculation OSC-871644 uses the surface flux files developed in OSC-870641 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 Qf the Oconee ISFSI.
Calculation OSC-871644, Table 23.1-1, summarizes dose rate versus distance, showing a dose rate of 6.84 mRem per year at 500 meters, which is the longest distance at which results converge. The closest residence to the ISFSI is in the SW-SSW direction approximately 1 mile (-1600 meters) from the ISFSI, or 1.36 miles from the centerline of the site.45 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 Oconee Nuclear Site 10CFR72.212 Written Evaluations for Phase VI, Rev. 0 Page 21 of 27
dose of 0.0754 mrem per year.4 9 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 FSAR, accidental releases are not credible.
Oconee Nuclear Site 10CFR72.212 Written Evaluations for Phase VI, Rev. 0 Page 22 of 27
Attachment 7 Oconee Nuclear Site SLC 16.11 Radiological Effluent Controls
Radioactive Liquid Effluents 16.11.1 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.1 Radioactive Liquid Effluents COMMITMENT Establish conditions for the controlled release of radioactive liquid effluents. Implement the requirements of 10 CFR 20, 10 CFR 50.36a, Appendix A to 10 CFR 50, Appendix I to 10 CFR 50, 40 CFR 141 and 40 CFR 190.
- a. Concentration The concentration of radioactive material released at anytime from the site boundary for liquid effluents to Unrestricted Areas [denoted in Figure 2-5 of the Oconee Nuclear Station Updated Final Safety Analysis Report] shall be limited to 10 times the effluent concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases the concentration shall be limited to 2 x 10-4 gCi/ml total activity.
- b. Dose The dose or dose commitment to a Member Of The Public from radioactive materials in liquid effluents to Unrestricted Areas shall be limited to:
- 1. during any calendar quarter:
_ 4.5 mrem to the total body
< 15 mrem to any organ; and
- 2. during any calendar year:
< 9 mrem to the total body
< 30 mrem to any organ.
- c. Liquid Waste Treatment The appropriate subsystems of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge, if the projected dose due to liquid effluent releases to unrestricted areas, when averaged over 31 days would exceed 0.18 mrem to the total body or 0.6 mrem to any organ.
16.11.1-1 03/15/11 I
Radioactive Liquid Effluents 16.11.1
- NO T E OTE....................... ----...
Appendix I dose limits for radioactive liquid effluent releases are applicable only during normal operating conditions which include expected operational occurrences, and are not applicable during unusual operating conditions that result in activation of the Oconee Emergency Plan.
APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of A.1 Restore concentration to Immediately radioactive material within the limit.
released in liquid effluents to Unrestricted Areas exceeds the limits specified in Commitment a.
16.11.1-2 03/15/11 I
Radioactive Liquid Effluents 16.11.1 CONDITION REQUIRED ACTION -COMPLETION TIME B. Calculated dose from B. 1 ------------- NOTE --------------
the release of Not required during radioactive materials in unusual operating liquid effluents exceeds conditions that result in any of the limits in activation of the Oconee Commitment b. Emergency Plan.
Submit report to the 30 days from the end of regional NRC Office which the quarter during which includes the following: the release occurred
- a. Cause(s) for exceeding the limit(s).
- b. A description of the program of corrective action initiated to:
reduce the releases of radioactive materials in liquid effluents, and to keep these levels of radioactive materials in liquid effluents in compliance with the above limits, or as low as reasonably achievable.
- c. Results of radiological analyses of the drinking water source and the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141.
16.11.1-3 03/15/11 1
Radioactive Liquid Effluents 16.11.1 CONDITION REQUIRED ACTION COMPLETION TIME C. Radioactive liquid C-1 Submit report to the 30 days waste is discharged regional NRC Office which without treatment and includes the following:
in excess of the specified limit. a. Cause of equipment or subsystem inoperability.
- b. Corrective action to restore equipment and prevent recurrence.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11. 1.1 N/A N/A 16.11.1-4 03/15/11 1
Radioactive Liquid Effluents 16.11.1 BASES The concentration commitment is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than 10 times the effluent concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. The concentration limit for noble gases is based upon the assumption that Xe-1 35 is the controlling radioisotope and its EC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
The basic requirements for Selected Licensee Commitments concerning effluent from nuclear power reactors are stated in 10 CFR 50.36a. Compliance with effluent Selected Licensee Commitments will ensure that average annual releases of radioactive material in effluents will be small percentages of the limits specified in the old 10 CFR 20.106 (new 10 CFR 20.1302).
The requirements contained in 10 CFR 50.36a further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10 CFR 20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem. It is further indicated in 10 CFR 50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as reasonably achievable (ALARA) as set forth in 10 CFR 50 Appendix I. Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements-of 40 CFR 141. Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with this SLC are based on ten times the instantaneous dose rate value of 50 mrem/year to apply at all times. Compliance with the limits of the new 10 CFR 20.1001 will be demonstrated by operating within the limits of 10 CFR 50, Appendix I, 40 CFR 141 and 40 CFR 190.
Section I of Appendix I of 10 CFR 50 states that this appendix provides specific numerical guides for design objectives and limiting conditions for operation, to assist holders of licenses for light water cooled nuclear power reactors in meeting the requirements to keep releases of radioactive material to unrestricted areas as low as practical and reasonably achievable, during normal reactor operations, including expected operational occurrences. Using the flexibility granted during unusual operating conditions, and the stated applicability of the design objectives for the Oconee Nuclear Station, Appendix I dose limits for radioactive liquid effluent releases are concluded to be not applicable during unusual operating conditions that result in the activation of the Oconee Emergency Plan.
For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This SLC implements the requirements of 10 CFR Part 50.36a.
General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section II.D of Appendix A to 10 CFR Part 50.
16.11.1-5 03/15/11 1
Radioactive Liquid Effluents 16.
11.1 REFERENCES
- 2. 40 CFR Part 141.
- 3. 10 CFR Part 50, Appendices A and I.
- 4. 40 CFR Part 190.
- 7. NUREG-1301 16.11.1-6 03/15/11 1
Radioactive Gaseous Effluents 16.11.2 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.2 Radioactive Gaseous Effluents COMMITMENT Establish conditions for the controlled release of radioactive gaseous effluents. Implement the requirements of 10 CFR 20, 10 CFR 50.36a, Appendix A to 10 CFR 50, Appendix I to 10 CFR 50, and 40 CFR 190.
- a. Dose Rate The instantaneous dose rate at the site (exclusion area) boundary for gaseous effluents [Figure 2.1-4(a) of the Oconee Nuclear Station Updated Final Safety Analysis Report] due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
- 1. The dose rate limit for noble gases shall be:
<500 mrem/yr to the total body
<3000 mrem/yr to the skin; and
- 2. The dose rate limit for all radioiodines and for all radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than 8 days shall be _<1500 mrem/yr to any organ.
- b. Dose
- 1. The air dose due to noble gases released in gaseous effluent from the site shall be limited to the following:
- i. During any calendar quarter:
_ 15 mrad for gamma radiation
< 30 mrad for beta radiation ii. During any calendar year:
< 30 mrad for gamma radiation
_ 60 mrad for beta radiation
- 2. The dose to a Member Of The Public from radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from the site, shall be limited to the following:
16.11.2-1 01/31/00 1
Radioactive Gaseous Effluents 16.11.2
- i. During any calendar quarter:
< 22.5 mrem to any organ ii. During any calendar year:
< 45 mrem to any organ.
- c. Gaseous Radwaste Treatment
- 1. The Gaseous Radwaste Treatment System shall be used to reduce the noble gases in gaseous wastes prior to their discharge, if the projected gaseous effluent air dose due to gaseous effluent release from the site, when averaged over 31 days exceeds 0.6 mrad for gamma radiation and 1.2 mrad for beta radiation.
- 2. The Ventilation Treatment Exhaust System shall be used to reduce radioactive materials other than noble gases in gaseous waste prior to their discharge when the projected doses due to effluent releases to unrestricted areas when averaged over 31 days would exceed 0.9 mrem to any organ.
- d. Used Oil Incineration During incineration of used oil contaminated by radioactive material in the Station Auxiliary Boiler, the dose to a Member Of The Public from radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released from the Station Auxiliary Boiler shall be < 0.045 mrem to any organ in any calendar year.
NOTE ----------------------------------
The requirement of c.2 does not apply to the Auxiliary Building Exhaust System since it is not "treated" prior to release.
APPLICABILITY: At all times 16.11.2-2 03/27/99
Radioactive Gaseous Effluents 16.11.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Dose rate exceeds the A. 1 Restore release rate to Immediately limits specified in within limits.
Commitment a.
B. Calculated dose B. 1 Submit report to the 30 days from the end of exceeds specified limits. regional NRC Office which the quarter during which includes the following: the release occurred
- a. Cause(s) for exceeding the limit(s),
and
- b. A description of the program of corrective action initiated to:
reduce the releases of radioactive materials in gaseous effluents, and to keep these levels of radioactive materials in gaseous effluents in compliance with the specified limits or as low as reasonably achievable.
16.11.2-3 01/31/00 1
Radioactive Gaseous Effluents 16.11.2 CONDITION REQUIRED ACTION COMPLETION TIME C. Radioactive gaseous C. 1 Submit a report to the 30 days waste is discharged regional NRC Office which greater than limits includes the following:
specified in Commitment c.1 or a. Cause of equipment c.2. or subsystems inoperability, and AND
- b. Corrective action to Radioactive gaseous restore equipment waste is discharged and prevent without treatment for recurrence.
more than 31 days.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.2.1 N/A N/A 16.11.2-4 03/27/99
Radioactive Gaseous Effluents 16.11.2 BASES The basic requirements for Selected Licensee Commitments concerning effluent from nuclear power reactors are stated in 10CFR50.36. Compliance with effluent Selected Licensee Commitments will ensure that average annual releases of radioactive material in effluents will be small percentages of the limits specified in the old I0CFR20.106 (new IOCFR20.1302). The requirements contained in IOCFR50.36a further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10CFR20.106 which references Appendix B, Table II concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem to the total body, 3000 mrem to the skin, and 1500 mrem to an infant via the milk animal-milk-infant pathway. It is further indicated in IOCFR50.36a that when using operational flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents as low as reasonably achievable (ALARA) as set forth in IOCFR50 Appendix I. Therefore, to accommodate operational flexibility needed for effluent releases, the limits associated with gaseous release rate SLCs will be maintained at the current instantaneous dose rate limit for noble gases of 500 mrem/year to the total body and 3000 mrem/year to the skin; and for Iodine-1 31, for Iodine-1 33, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days. an instantaneous dose rate limit of 1500 mrem/year.
The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1,. October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors."
Equations in the ODCM are provided for determining the actual doses based upon the historical average atmospheric conditions. The release rate commitments for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides into green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This commitment implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section lID of Appendix I to 10 CFR Part 50.
16.11.2-5 01/31/00 1
Radioactive Gaseous Effluents 16.
11.2 REFERENCES
1 10 CFR Part 20, Appendix 8.
- 2. 10 CFR Part 50, Appendices A and I.
- 4. 40 CFR Part 190.
16.11.2-6 01/31/00 1
Radioactive Effluent Monitoring Instrumentation 16.11.3 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.3 Radioactive Effluent Monitoring Instrumentation COMMITMENT Radioactive Effluent Monitoring Instrumentation shall be OPERABLE as follows:
- a. Liquid Effluents The radioactive liquid effluent monitoring instrumentation channels shown in Table 16.11.3-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.11.1 .a are not exceeded.
- b. Gaseous Process and Effluents The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 16.11.3-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of SLC 16.11.2.a are not exceeded.
- c. The setpoints shall be determined in accordance with the methodology described in the ODCM and shall be recorded.
Correction to setpoints determined in accordance with Commitment c may be permitted without declaring the channel inoperable.
APPLICABILITY: According to Table 16.11.3-1 and Table 16.11.3-2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Alarm/trip setpoint less A.1 Declare channel Immediately conservative than inoperable.
required for one or more effluent OR monitoring instrument channels. A.2 Suspend release of Immediately effluent monitored by the channel.
16.11.3-1 11/20/08 I
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B. 1 Enter the Condition Immediately liquid effluent monitoring referenced in Table instrument channels 16.11.3-1 for the inoperable. function.
AND B.2 Restore the 30 days instrument(s) to OPERABLE status.
C. One or more required C. 1 Enter the Condition Immediately gaseous effluent referenced in Table monitoring instrument 16.11.3-2 for the channels inoperable. function.
AND C.2 Restore the 30 days instrument(s) to OPERABLE status.
D. Required Action and D.1 Explain in next Annual April 30 o f following associated Completion Radiological Effluent calendar year Time of Required Action Release Report why B.2 or C.2 not met. inoperability was not corrected in a timely manner.
16.11.3-2 11/20/08 1
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1.1 Analyze two Prior to initiating Action B.1 and independent samples subsequent release referenced in Table in accordance with 16.11.3-1. (RIA-33) SLC 16.11.4.
AND E. 1.2 Conduct two Prior to initiating independent data entry subsequent release checks for release rate calculations AND E.1.3 Conduct two Prior to initiating independent valve subsequent release lineups of the effluent pathway.
OR E.2 Suspend release of Immediately radioactive effluents by this pathway.
F. As required by Required F.1 Suspend release of Immediately Action B.1 and radioactive effluents by referenced in Table this pathway.
16.11.3-1. (RIA-54)
OR F.2 Collect and analyze Prior to each discrete grab samples for gross release of the sump radioactivity (beta and/or gamma) at a lower limit of detection of at least 10-7 gCi/ml.
16.11.3-3 11/20/08 I
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME G. As required by Required --- --------------- NOTE ------------------
Action B.1 and Not required during short, referenced in Table controlled outages of liquid 16.11.3-1. (Liquid effluent monitoring Radwaste Effluent Line instrumentation. Short controlled Flow Rate Monitor) outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.
G.1 Suspend release of Immediately radioactive effluents by this pathway.
OR G.2 Estimate flow rate Immediately during actual releases.
AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter 16.11.3-4 11/20/08 I
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITIONI REQUIRED ACTION COMPLETION TIME H. As required by Required --- --------------- NOTE ------------------
Action B.1 and Not required during short, referenced in Table controlled outages of liquid 16.11.3-1. (RIA-35, #3 effluent monitoring Chemical Treatment instrumentation. Short controlled Pond Composite outages are defined as planned Sampler and Sampler removals from service for Flow Monitor (Turbine durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Building Sumps for purposes of sample filter Effluent)) changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.
H.1 Suspend release of Immediately radioactive effluents by this pathway.
OR H.2 Collect and analyze Immediately grab samples for gross radioactivity (beta AND and/or gamma) at a lower limit of detection Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of at least 10-7 [Ci/ml. thereafter 16.11.3-5 11/20/08 I
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION ] REQUIRED ACTION ] COMPLETION TIME As required by Required --------------- NOTE ------------------
Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2 for effluent effluent monitoring releases from waste gas instrumentation. Short controlled tanks (RIA-37, RIA-38) outages are defined as planned or containment purges removals from service for (RIA-45). durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.
1.1.1 Analyze two Prior to initiating independent samples. subsequent release AND 1.1.2 Conduct two Prior to initiating independent data entry subsequent release checks for release rate calculations AND 1.1.3 Conduct two Prior to initiating independent valve subsequent release lineups of the effluent pathway.
OR 1.2 Suspend release of Immediately radioactive effluents by this pathway.
16.11.3-6 11/20/08 I
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME J. As required by Required -------
NO----------TE.
Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (Effluent effluent monitoring Flow Rate Monitor (Unit instrumentation. Short controlled Vent, Containment outages are defined as planned Purge, Interim removals from service for Radwaste Exhaust, Hot durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Machine Shop Exhaust, for purposes of sample filter Radwaste Facility changeouts, setpoint Exhaust, Waste Gas adjustments, service checks, Discharge)) and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.
J. 1 Suspend release of Immediately radioactive effluents by this pathway.
OR J.2 Estimate flow rate Immediately AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter 16.11.3-7 11/20/08 1
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION [COMPLETION TIME K. As required by Required --- --------------- NOTE ---------
Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (RIA-45, effluent monitoring RIA-53, 4RIA-45) instrumentation. Short controlled outages are defined as planned removals from service for durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.
K.1 Suspend release of Immediately radioactive effluents by this pathway.
OR K.2.1 Collect grab sample. Immediately AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> AND K.2.2 Analyze grab samples 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from collection for gross activity (beta of sample and/or gamma).
16.11.3-8 11/20/08 I
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME L. As required by Required --- --------------- NOTE ---------
Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2. (Unit Vent effluent monitoring Monitoring Iodine instrumentation. Short controlled Sampler, Unit Vent outages are defined as planned Monitoring Particulate removals from service for Sampler, Interim durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Radwaste Building for purposes of sample filter Ventilation Monitoring changeouts, setpoint Iodine Sampler, Interim adjustments, service checks, Radwaste Building and/or routine maintenance Ventilation Monitoring procedures. This guidance may Particulate Sampler, Hot be applied successively, Machine Shop Iodine provided that time between Sampler, Hot Machine successive short, controlled Shop Particulate outages is always at least equal Sampler, Radwaste to duration of immediately Facility Iodine Sampler, preceding outage.
Radwaste Facility Particulate Sampler)
L.1 Suspend release of Immediately radioactive effluents by this pathway.
OR L.2.1 -------- NOTE------
The collection time of each sample shall not exceed 7 days.
Collect samples Immediately continuously using auxiliary sampling equipment..
AND L.2.2 Analyze each sample. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from end of each sample collection 16.11.3-9 11/20/08 I
Radioactive Effluent Monitoring Instrumentation 16.11.3 CONDITION REQUIRED ACTION COMPLETION TIME M. As required by Required --- --------------- NOTE ------------------
Action C.1 and Not required during short, referenced in Table controlled outages of gaseous 16.11.3-2 for effluent effluent monitoring from ventilation system instrumentation. Short controlled or condenser air outages are defined as planned ejectors. (RIA-40) removals from service for durations not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, for purposes of sample filter changeouts, setpoint adjustments, service checks, and/or routine maintenance procedures. This guidance may be applied successively, provided that time between successive short, controlled outages is always at least equal to duration of immediately preceding outage.
M. 1 Continuously monitor Immediately release through the unit vent.
OR M.2 Suspend release of Immediately radioactive effluents by this pathway.
OR M.3.1 Collect grab sample. Immediately AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> AND M.3.2 Analyze grab sample for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from collection gross activity (beta of grab sample and/or gamma).
16.11.3-10 11/20/08 1
Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.3.1 ----------------- NOTE---------------
The Channel Response check shall consist of verifying indications during periods of release.
Channel response checks shall be made at least once per calendar day on days in which continuous, periodic or batch releases are made.
Perform Channel Response Check. During each release via this pathway SR 16.11.3.2 ----------------- NOTE ---------------
The Channel Response check shall consist of verifying indications during periods of release.
Channel response checks shall be made at least once per calendar day on days in which continuous, periodic or batch releases are made.
Perform Channel Response Check. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 16.11.3.3 Perform Source Check. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 16.11.3.4 Perform Source Check. 31 days SR 16.11.3.5 Perform Source Check. 92 days 16.11.3-11 11/20/08 1
Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE FREQUENCY SR 16.11.3.6 ---------------
NOTE ----------------
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alarm/trip setpoint.
- 2. Circuit failure (downscale only).
Perform CHANNEL FUNCTIONAL TEST. 92 days SR 16.11.3.7 ---------------
NOTE ------------
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alarm/trip setpoint.
- 2. Circuit failure (downscale only).
92 days Perform CHANNEL FUNCTIONAL TEST.
SR 16.11.3.8 Perform CHANNEL FUNCTIONAL TEST. 92 days 16.11.3-12 11/20/08 I
Radioactive Effluent Monitoring Instrumentation 16.11.3 SURVEILLANCE FREQUENCY SR 16.11.3.9 ------------------------- NOTE ---------------------------
The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with the National Institute of Standards and Technology (NIST). The standards shall permit calibrating the system over its intended range of energy and measurement. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (Operating plants may substitute previously established calibration procedures for these requirements.)
12 months Perform CHANNEL CALIBRATION.
SR 16.11.3.10 Perform CHANNEL CALIBRATION. 12 months SR 16.11.3.11 Perform leak test. When cylinder gates or wicket gates are reworked SR 16.11.3.12 Perform Source Check. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to each release via associated pathway 16.11.3-13 11/20/08 1
Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABILITY REQUIREMENTS ACTION B.1 Monitors Providing Automatic Termination of Release
- a. Liquid Radwaste Effluent 1 At all times SR 16.11.3.1 E Line Monitor, RIA-33 SR 16.11.3.3 SR 16.11.3.6 SR 16.11.3.9
- b. Turbine Building Sump, 1 At all times SR 16.11.3.2 F RIA-54 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9
- 2. Monitors not Providing Automatic Termination of Release Low Pressure Service Water 1 At all times SR 16.11.3.2 H RIA-35 SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9
- 3. Flow Rate Measuring Devices
- a. Liquid Radwaste Effluent 1 At all times SR 16.11.3.1 G Line Flow Rate Monitor SR 16.11.3.10 (OLW CR0725 or OLW SS0920)
- b. Liquid Radwaste Effluent NA NA SR 16.11.3.1 NA Line Minimum Flow SR 16.11.3.10 Device
- c. Turbine Building Sump NA NA SR 16.11.3.1 NA Minimum Flow Device SR 16.11.3.10
- d. Low Pressure Service NA NA SR 16.11.3.1 NA Water Minimum Flow SR 16.11.3.10 Device 16.11.3-14 11/20/08 I
Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-1 LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS CONDITION REFERENCED MINIMUM FROM OPERABLE SURVEILLANCE REQUIRED INSTRUMENT CHANNELS APPLICABILITY REQUIREMENTS ACTION B.1
- e. Keowee Hydroelectric NA NA SR 16.11.3.11 NA Tailrace Discharge (a)
- 4. Continuous Composite Sampler
- 3 Chemical Treatment 1 At all times SR 16.11.3.2 H Pond Composite Sampler SR 16.11.3.10 and Sampler Flow Monitor (Turbine Building Sumps Effluent)
(a) Flow is determined from the number of hydro units operating. Ifno hydro units are operating, leakage flow will be assumed to be 38 cfs based on historical data.
16.11.3-15 11/20/08
Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE SURVEILLANCE REQUIRED INSTRUMENT PATH) APPLICABILITY REQUIREMENTS ACTION C.1
- 1. Unit Vent Monitoring System
- a. Noble Gas Activity 1 At All Times SR 16.11.3.2 Monitor Providing Alarm SR 16.11.3.4 and Automatic SR 16.11.3.7 Termination of SR 16.11.3.9 Containment Purge Release (RIA Purge Isolation Function)
- b. Noble Gas Activity 1 At all times SR 16.11.3.2 K Monitor Providing Alarm. SR 16.11.3.4 (RIA Vent Stack SR 16.11.3.7 Monitor Function). SR 16.11.3.9
- c. Iodine Sampler 1 At All Times SR 16.11.3.2 L 1
- d. Particulate Sampler At All Times SR 16.11.3.2 L 1
- e. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Unit Vent Flow) SR 16.11.3.10 (MSC CR0001)
- f. Sampler Flow Rate 1 At All Times SR 16.11.3.2 NA Monitor (a) (Annunciator) SR 16.11.3.10
- g. Effluent Flow Rate During Containment SR 16.11.3.2 M Monitor (Containment Purge Operation SR 16.11.3.10 Purge)(MSC CR0001)
- h. CSAE Off Gas Monitor During Operation SR 16.11.3.2 M (RIA-40) of CSAE SR 16.11.3.5 SR 16.11.3.8 SR 16.11.3.9
- 2. Interim Radwaste Building Ventilation Monitoring System
- a. Noble Gas Activity At All Times SR 16.11.3.2 K Monitor (RIA - 53) SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9
- b. Iodine Sampler At All Times SR 16.11.3.2 L
- c. Particulate Sampler At All Times SR 16.11.3.2 L
- d. Effluent Flow Rate 1 At All Times SR 16.11.3.2 J Monitor (Interim SR 16.11.3.10 Radwaste Exhaust)
(GWD FT0082)
- e. Sampler Flow Rate NA 1 At All Times SR 16.11.3.2 Monitor(a) (Annunciator)
SR 16.11.3.10 16.11.3-16 11/20/08 1
Radioactive Effluent Monitoring Instrumentation 16.11.3 Table 16.11.3-2 GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERATING CONDITIONS AND SURVEILLANCE REQUIREMENTS MINIMUM CONDITION OPERABLE REFERENCED CHANNELS FROM (PER RELEASE SURVEILLANCE REQUIRED INSTRUMENT PATH) APPLICABILITY REQUIREMENTS ACTION C.1
- 3. Hot Machine Shop Ventilation Sampling System
- a. Iodine Sampler At All Times SR 16.11.3.2 L
- b. Particulate Sampler At All Times SR 16.11.3.2 L
- c. Effluent Flow Rate 1 At All Times SR 16.11.3.2 J Monitor (Hot Machine SIR 16.11.3.10 Shop Exhaust)
(Totalizer)
- d. Sampler Flow Rate I At All Times SR 16.11.3.2 NA Monitor (a)(Annunciator) SR 16.11.3.10
- 4. Radwaste Facility Ventilation Monitoring System
- a. Noble Gas Activity At All Times SR 16.11.3.2 K Monitor (4-RIA-45) SR 16.11.3.4 SR 16.11.3.7 SR 16.11.3.9
- b. Iodine Sampler At All Times SR 16.11.3.2 L
- c. Particulate Sampler At All Times SR 16.11.3.2 L
- d. Effluent Flow Rate At All Times SR 16.11.3.2 J Monitor (Radwaste SR 16.11.3.10 Facility Exhaust) (OVS CR2060)
- e. Sampler Flow Rate At All Times SR 16.11.3.2 NA 1
Monitor (a)(Annunciator) SR 16.11.3.10
- 5. Waste Gas Holdup Tanks
- a. Noble Gas Activity During Waste Gas SR 16.11.3.1 Monitor - Providing Holdup Tank Releases SR 16.11.3.6 Alarm and Automatic SR 16.11.3.9 Termination of Release SR 16.11.3.12 (RIA-37,-38)b 1
- b. Effluent Flow Rate During Waste Gas SR 16.11.3.1 J Monitor (Waste Gas Holdup Tank Releases SR 16.11.3.10 Discharge Flow) (MSC CR0001)
(a)Alarms indicating low flow may be substituted for flow measuring devices.
(b)Either Normal or High Range monitor is required dependent upon activity in tank being released.
16.11.3-17 11/20/08 1
Radioactive Effluent Monitoring Instrumentation 16.11.3 BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarm/trip will occur prior to exceeding 10 times the limits of 10 CFR Part 20. The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to assure that the alarm/trip will occur prior to exceeding applicable dose limits in SLC 16.11.2. The operability end use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
For certain applicable cases, grab samples or flow estimates are required at frequencies between every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> end every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> upon RIA removal from service. SLC 16.11.3 does not explicitly require Action (grab samples or flow estimates) to be initiated immediately upon RIA removal from service, when removal is for the purposes of sample filter changeouts, setpoint adjustments, service checks, or routine maintenance. Therefore, during the defined short, controlled outages, Action is not required.
For the cases in which Action is defined as continuous sampling by auxiliary equipment (Action L) initiation of continuous sampling by auxiliary sampling equipment requires approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. One hour is the accepted reasonable time to initiate collect and change samples.
Therefore. for the defined short, controlled outages (not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), Action is not required.
Failures such as blown instrument fuses, defective indicators, and faulted amplifiers are, in many cases, revealed by alarm or annunciator action. Comparison of output and/or state of independent channels measuring the same variable supplements this type of built-in surveillance. Based on experience in operation of both conventional and nuclear systems, when the unit is in operation, the minimum checking frequency stated is deemed adequate.
REFERENCES:
- 1. 10CFRPart20.
- 4. UFSAR, Section 7.2.3.4.
16.11.3-18 11/20/08 1
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 09/30/09 1
Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection (b) of Lab Analysis for Waste Decant Monitor a. Principal Gamma Composite Grab Sample <5E-06 j.Ci/ml (Ce-144)
Tank, Turbine Emitters(c) including prior to release of each <5E-07 j.Ci/mI (Other Gamma Nuclides)
Building Sump Dissolved Noble batch(h) <1 E-05 ptCi/ml (Dissolved Gases)
Monitor Tanks, Gases <1E-06 pCi/ml (1-131)
Waste and Recycle Monitor Tanks
- b. Radiochemical Quarterly from all <5E-08 pCi/ml Analysis Sr-89 and composited batches(f)
- c. Tritium Monthly Composite <1 E-05 p.Ci/mI
- d. Gross Alpha Activity Monthly Composite <1E-07 pCi/ml
- 2. Unit Vent Sampling a. Iodine Spectrum (a) Continuous monitor, <1E-10 p.Ci/cc (I-133)(j)
(Includes Waste weekly sample(e) <1E-12 pCi/cc (1-131)(j)
Gas Decay Tanks, Reactor Building Purges, Auxiliary b. Particulates (a)
Building Ventilation, Spent Fuel Pool i. Ce-144 & Mo-99 Weekly Composite(e) <5E-10 p.Ci/cc(j)
Ventilation, Air Ejectors) ii. Other Principle Weekly Composite(e) <1E-11 pCi/cc(j)
Gamma Emitters (d) iii. Gross Alpha Monthly, using composite <1E-11 p.Ci/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 pCi/cc Analysis Sr-89, Sr-90
- c. Gases by Principle Weekly Grab Sample <1 E-04 p.Ci/cc Gamma Emitters(d)
- d. Tritium Weekly Grab Sample <1E-06 pCi/cc
- 3. Waste Gas Decay a. Principle Gamma Grab Sample prior to < 1E-04 pCi/cc (gases)
Tank Emitters(d) release of each batch <1E-10 pCi/cc (particulates and iodines)
<5E-09 [tCi/cc (Ce-144 and Mo-99)
- b. Tritium Grab Sample prior to <1 E-06 p.Ci/cc release of each batch
- 4. Reactor Building a. Principle Gamma Grab sample each purge <1 E-04 pCi/cc (gases)
Emitters(d) <1E-10 pgCi/cc (particulates and iodines)
<5E-09 pCi/cc (Ce-144 and Mo-99)
- b. Tritium Grab sample each purge <1 E-06 gCi/cc 16.11.4-2 09/30/09 1
Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection (b) of Lab Analysis for Waste
- 5. Not Used
- 6. #3 Chemical a. Principle Gamma Weekly Continuous <5E-07 jiCi/mI Treatment Pond Emitters(c) Composite(g)
Effluent(')
- b. 1-131 Weekly Continuous <1E-06 jaCi/mI Composite(g)
- c. Tritium Monthly Continuous <1E-05 pCi/ml Composite(g)
- d. Gross Alpha Monthly Continuous <1 E-07 j.Ci/mI Activity Composite(g)
- e. Sr-89 & Sr-90 Quarterly Continuous <5E-08 l.Ci/ml Composite(g)
- f. Dissolved and Monthly Grab <1E-05 pCi/mI Entrained gases (Gamma Emitters)
- 7. Radwaste Facility a. Iodine Continuous monitor, (1-133) <1E-09 !iCi/cc Ventilation Spectrum(a) weekly sample(e) (1-131) <1E-11 ipCi/cc
- b. Particulate(a)
- i. Ce-144 and Mo- Weekly Composite(e) <5E-10 liCi/cc(j) 99 ii. Other Principle Weekly Composite(e) <1E-11 p.Ci/ccj)
Gamma Emitters(d) iii. Gross Alpha Monthly, using composite <1E-11 pCi/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 gCi/cc Analysis Sr-89, Sr-90
- c. Gases by Weekly Grab Sample < 1E-04 gC i/cc Principle Gamma(d)
Emitters
- d. Tritium Weekly Grab Sample <1 E-06 !*Ci/cc 16.11.4-3 09/30/09 1
Operational Safety Review 16.11.4 Table 16.11.4-1 Minimum Sampling Frequency and Analysis Program Item Check Frequency Lower Limit of Detection (b) of Lab Analysis for Waste
- 8. Hot Machine Shop a. Iodine Spectrum Weekly Sample(e) (1-133) <1 E-10 jiCi/cc(j)
Ventilation (1-131) <1 E-12 j+/-Ci/cc(j)
- b. Particulate
- i. Ce-144 and Mo- Weekly Composite(e) <5E-10 itCi/cc(j) 99 ii. Other Principle Weekly Composite(e) <1E-11 g.Ci/cc(j)
Gamma Emitters (d)
Monthly, using composite iii. Gross Alpha <1E-11 g.Ci/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1E-11 iiCi/cc Analysis Sr-89, Sr-90
- c. Gases by NA NA Principle Gamma Emitters
- d. Tritium NA NA
- 9. Interim Radwaste a. Iodine Spectrum Weekly sample(e) (1-133) <1 E-10 i.Ci/cc(j)
Building (1-131) <1E-12 pCi/cc(j)
Ventilation
- b. Particulate
- i. Ce-144 and Mo- Weekly Composite(e) <5E-10 ,.Ci/cc(j) 99
<1E-11 V.Ci/cca)
Other Principle Weekly Composite(e)
Gamma Emitters(d) iii. Gross Alpha Monthly, using composite <1E-11 g.Ci/cc Activity samples of one week iv. Radiochemical Quarterly Composite <1 E-101 gCi/cc Analysis Sr-89, Sr-90
- c. Gases by Weekly Grab Sample <1 E-04 g.Ci/cc Principle Gamma(d)
Emitters
- d. Tritium Weekly Grab Sample <1 E-06 g+/-Ci/cc 16.11.4-4 09/30/09 I
Operational Safety Review 16.11.4 (a) Samples shall 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 "real" signal.
For a particular measurement system (which may include radiochemical separation)
LLD= 4.66 sb E x V x 2.22E06 x Y x exp (-X,.t)
Where:
LLD is the "a priori" lower limit of detection as defined above (as micro Curies per unit mass or volume),
sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per disintegration),
V is the sample size (in units of mass or volume),
2.22E06 is the number of disintegrations per minute per micro Curie, Y is the fractional radiochemical yield (when applicable),
X is the radioactive decay constant for the particular nuclide A t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples). NOTE: This assumes decay correction is applied (at the time of analysis) for the duration of sample collection, for the time between collection and analysis, and for the duration of the counting.
Additionally, it does not apply to isolated systems such as Waste Gas Decay Tanks and Waste Monitor Tanks.
Typical values of E, V, Y and A t should be used in the calculation.
It should be recognized that the LLD is an a priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.
(c) The principal gamma emitters for which the LLD control applies include the following radionuclides: Mn-54. Fe-59, Co-58, Co-60. Zn-65, Mo-99, Cs-134, Cs-137. and Ce-141. Ce-144 shall also be measured, but with a LLD of 5E-06 piCi/ml. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with the above nuclides shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.
(d) The principal gamma emitters for which the LLD commitment applies exclusively are the following radionuclides: Kr-87. Kr-88, Xe-1 33. Xe-1 33m, Xe-1 35. and Xe-1 38 for gaseous emissions and Mn-54, Fe-59. Co-58, Co-60, Zn-65.
Mo-99, Cs-1 34, Cs-1 37, Ce-1 41, and Ce-1 44 for particulates. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides shall also be identified and reported.
(e) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with SLC 16.11.2.a, SLC 16.11.2.b.1, and SLC 16.11.2.b.2.
(f) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
(g) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
16.11.4-5 09/30/09 I
Operational Safety Review 16.11.4 (h) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, each batch shall be isolated, and then thoroughly mixed, to assure representative sampling.
(i) A continuous release is the discharge of liquid wastes of a non-discrete volume, e.g., from a volume of a system that has an input flow during the continuous release.
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 09/30/09 1
Operational Safety Review 16.11.4 BASES N/A
REFERENCES:
N/A 16.11.4-7 09/30/09 1
Solid Radioactive Waste 16.11.5 16.11 RADIOLOGICAL.EFFLUENTS CONTROL 16.11.5 Solid Radioactive Waste COMMITMENT Radioactive wastes shall be processed and packaged to ensure compliance with the applicable requirements of 10 CFR Part 20, 10 CFR Part 61, 10 CFR Part 71., and State regulations governing the transportation and disposal of radioactive wastes.
The Solid Radwaste System or an approved alternative process shall be used in accordance with a Process Control Program (PCP), for the solidification of liquid or wet radioactive wastes or the dewatering of wet radioactive wastes to be shipped for direct disposal at a 10 CFR 61 licensed disposal site. Wastes shipped for off site processing in accordance with the processor's specifications and transportation requirements are not required to be solidified or dewatered to meet disposal requirements.
" The PCP describes administrative and operational controls used for the solidification of liquid or wet solid radioactive wastes in order to meet applicable 10 CFR 61 waste form requirements.
- The PCP describes the administrative and operational controls used for the dewatering of wet radioactive wastes to meet 10 CFR 61 free standing water requirements.
" The process parameters used in establishing the PCP shall be based on demonstrated processing of actual or simulated liquid or wet solid wastes and must adequately verify that the final product of solidification or dewatering meets all applicable Federal, State and disposal site requirements.
APPLICABILITY: At all times 16.11.5-1 10/30/02 1
Solid Radioactive Waste 16.11.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Applicable regulatory A. 1 Suspend shipments of Immediately requirements for defectively packaged solidified or dewatered solid radioactive wastes wastes are not from the site.
satisfied.
AND A.2 Initiate action to correct Prior to next shipment for PCP, procedures, or disposal of solidified or solid waste equipment dewatered wastes as necessary to prevent recurrence.
B. A solidification test as B. 1 Suspend solidification of Immediately described in the PCP the batch under test and fails to verify follow PCP guidance for Solidification. test failures until solidification of the batch is verified by subsequent tests.
AND B.2 The PCP shall be Prior to next solidification modified as required to for shipment of waste for assure Solidification of disposal at a 10 CFR 61 subsequent batches of disposal site waste.
16.11.5-2 10/30/02 1
Solid Radioactive Waste 16.11.5 CONDITION REQUIRED ACTION COMPLETION TIME C. With solidification or C. 1 Reprocess or repackage Prior to shipment for dewatering for disposal the waste in accordance disposal of the not performed in with PCP requirements. inadequately processed accordance with the waste that requires PCP. OR solidification or C.2 Follow PCP or dewatering procedure guidance for alternative free standing liquid verification to ensure the waste in each container meets disposal requirements and take appropriate administrative action to prevent recurrence.
D. With the solid waste D.1 Restore the equipment to In a time frame that equipment incapable of OPERABLE status or supports the meeting commitment or provide for alternative commitment not in service. capability to process wastes as necessary to satisfy all applicable disposal requirements.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.5.1 The Process Control Program shall be used Every tenth batch of each to verify the solidification of at least one type of radioactive waste representative test specimen from at least to be solidified.
every tenth batch of each type of radioactive waste to be solidified for disposal at a 10 CFR 61 disposal site.
16.11.5-3 10/30/02 1
Solid Radioactive Waste 16.11.5 BASES This commitment implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of 10 CFR Part 50, Appendix A and requirements to use a Process Control Program to meet applicable 10CFR61 waste form criteria for solidified and dewatered radioactive wastes.
REFERENCES:
- 1. 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities".
- 3. 10 CFR20, "Standards for Protection Against Radiation".
- 4. 10 CFR61, "Licensing Requirements for Land Disposal of Radioactive Waste".
- 5. 10 CFR71, "Packaging and Transportation of Radioactive Materials".
- 6. DPCo Process Control Program Manual.
- 7. NRC Generic Letter 87-12, "Compliance with 10 CFR Part 61 And Implementation Of the Radiological Effluent Technical Specifications (Rets) and Attendant Process Control Program (PCP)".
- 8. NRC Generic Letter 89-01, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications In the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of Rets to the Offsite Dose Calculation Manual or to the Process Control Program".
16.11.5-4 10/30/02 I
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, 16.11.6-2 and 16.11.6-3.
- 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 02/01/05 1
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 02/01/05 1
Radiological Environmental Monitoring 16.11.6 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.
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 02/01/05 1
Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Exposure Pathway and/or Number of Sampling and Collection Sample Sample Frequency (d) Time and Frequency of Analysis Locations (b)
- 1. AIRBORNE Radioiodine and 5 Continuous sampler Radioiodine canister:
Particulates operation with sample 1-131 analysis weekly. Particulate collection weekly, or sampler: Gross beta radioactivity more frequently if analysis following filter change; and required by dust loading. gamma isotopic analysis of composite (by location) quarterly. (c)
- 2. DIRECT RADIATION 40 Quarterly. Gamma dose quarterly.
- 3. WATERBORNE
- a. Surface 2 Composite (a) sample Gamma isotopic analysis monthly.
over a 1-month period.
Composite for tritium analysis quarterly.
- b. Drinking 3. Composite (a) sample Composite for gross beta and gamma over a 1-month period. isotopic analyses monthly.
Composite for tritium analysis quarterly.
- c. Sediment from 2 Semiannually. Gamma isotopic analysis Shoreline semiannually.
16.11.6-4 02/01/05 1
Radiological Environmental Monitoring 16.11.6 Table 16.11.6-1 Radiological Environmental Monitoring Program Exposure Pathway and/or Number of Sampling and Collection Sample Sample Frequency (d) Time and Frequency of Analysis Locations (b)
- 4. INGESTION
- a. Milk 4(e) Semimonthly when Gamma isotopic and 1-131 analysis animals are on pasture; semimonthly when animals are on monthly at other times. pasture; monthly at other times.
- b. Fish 2 Semiannually. One Gamma isotopic analysis sample each semiannually on edible portion.
commercially and recreationally important species.
- c. Broad-leaf 2 Monthly. Gamma isotopic analysis monthly.
Vegetation (a) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <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 rriade 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 02/01/05 1
Radiological Environmental Monitoring 16.11.6 Table 16.11.6-2 Maximum Values for the Lower Limits of Detection (LLD) (a) (c)
Airborne Fish Broad-leaf Particulate or Milk Vegetation Sediment Analysis Water (pCi/I) Gases (pCi/kg, (pCi/I) (pCi/kg, dry) 3 (pCi/m ) wet) (pCi/kg, wet)
Gross Beta 4 1 E-02 H3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 15 Nb-95 15 1-131 15(b) 7E-02 1 60 Cs-134 15 5E-02 130 15 60 150 Cs-1 37 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 4.66 Sb E x V 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) 16.11.6-6 02/01/05 1
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 picocurie Y is the fractional radiochemical yield (when applicable)
? 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 Typical values of E, V, Y and A t should be used in the calculation.
The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances, may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
(b) LLD for gamma isotopic analysis for 1-131 in drinking water samples. Low level 1-131 analysis on drinking water will not be routinely performed because the calculated dose from 1-131 in drinking water at all locations is less than 1 mrem per year. Low level 1-131 analyses will be performed if abnormal releases occur which could reasonably result in > 1 pCi/liter of 1-131 in drinking water. For low level analyses of 1-131 an LLD of 1 pCi/liter will be achieved.
(c) Other peaks which are measurable and identifiable, together with the radionuclides in Table 16.11.6-2, shall be identified and reported.
16.11.6-7 02/01/05 1
Radiological Environmental Monitoring 16.11.6 Table 16.11.6-3 Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Broad-leaf Water Particulate or Fish Milk Vegetation (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 1E02 Cs-134 30 10 1E03 60 1E03 Cs-137 50 20 2E03 70 2E03 Ba-La-140 2E02 3E02 (a) For drinking water samples. This is 40 CFR Part 141 value.
(b) If low level 1-131 analyses are performed.
16.11.6-8 02/01/05 1
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 1, 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.
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.
16.11.6-9 02/01/05 1
Radiological Environmental Monitoring 16.
11.6 REFERENCES
16.11.6-10 02/01/05 1
Dose Calculations 16.11.7 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.7 Dose Calculations COMMITMENT The annual (calendar year) dose or dose commitment, to any Member of the Public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to < 25 mrems to the total body or to any organ, except the thyroid, which shall be limited to < 75 mrems.
APPLICABILITY: At all times ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated doses from A.1 Determine by None the release of calculation, including radioactive materials in direct radiation liquid or gaseous contributions from the effluents exceeding reactor units and from twice the limits of SLC outside storage tanks, 16.11.1.b, SLC whether the limits of 16.11.2.b.1, or SLC Commitment 16.11.7 16.11.2.b.2 have been exceeded.
16.11.7-1 01/31/00 i
Dose Calculations 16.11.7 CONDITION I REQUIRED ACTION I COMPLETION TIME B. Calculated dose ------------------- NOTE ----------------
exceeds limits of This Special Report, as defined Commitment 16.11.7. in 10 CFR Part 20.2203(a), shall include an analysis that estimates the radiation exposure (dose) to a Member of the Public from uranium fuel cycle sources, (including all effluent pathways and direct radiation), for the calendar year that includes the release(s) covered by this report.
It shall also describe the levels of radiation and concentration of radioactive material involved, and the cause of the exposure levels or concentrations.
B. 1 Prepare and submit to the Commission a 30 days Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the specified limits and includes the schedule for achieving conformance with the specified limits.
16.11.7-2 01/31/00 1
Dose Calculations 16.11.7 CONDITION REQUIRED ACTION COMPLETION TIME C. Calculated dose C. 1 ----------- NOTE -----------
exceeds limit of Submittal of the report Commitment 16.11.7. is considered a timely request, and a variance AND is granted until staff action on the request is Release condition complete.
resulting in violation of -------------------------------
40 CFR 190 not corrected at time of Include a request for a 30 days from exceeding report submittal. variance in accordance the limit with the provisions of 40 CFR Part 190.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.7.1 Determine cumulative dose contributions from 31 days liquid effluents in accordance with Offsite Dose Calculation Manual.
SR 16.11.7.2 Determine cumulative dose contributions from 31 days gaseous effluents in accordance with Offsite Dose Calculation Manual.
BASES The dose commitment is provided to assure that the release of radioactive material in liquid and gaseous effluents will be kept "as low as is reasonably achievable." The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I in that conformance with the guides of Appendix I is to be shown by calculations and procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
16.11.7-3 03/27/99
Dose Calculations 16.
11.7 REFERENCES
- 1. 10 CFR Part 20.
- 2. 40 CFR Part 190.
- 4. 10 CFR Part 50, Appendix I.
16.11.7-4 01/31/00 1
Reports 16.11.8 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.8 Reports COMMITMENT Special reports shall be submitted to the Regional Administrator, Region II, within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable SLC:
- c. Radiological Environmental Monitoring Program, SLC 16.11.6.a, b, and c
- d. Land Use Census, SLC 16.11.6.d
- e. Dose Calculations, SLC 16.11.7 APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Individual milk samples A.1 Submit plan advising 7 days show 1-131 the NRC of the concentrations of 10 proposed action to picocuries per liter or ensure the plant related greater. annual doses will be within the design objective of 45 mrem/yr to the thyroid of any individual.
16.11.8-1 12/21/09 1
Reports 16.11.8 CONDITION REQUIRED ACTION COMPLETION TIME B. Milk samples collected B.1 Submit a plan advising 30 days over a calendar quarter the NRC of the show 1-131 average proposed action to concentrations of 4.8 ensure the plant related picoCuries per liter or annual doses will be greater within the design objective of 45 mrem/yr to the thyroid of any individual.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.8.1 NA NA BASES Reference applicable commitments.
REFERENCES:
- 1. 10 CFR Part 20.
- 2. 40 CFR Part 190.
16.11.8-2 12/21/09 I
Radioactive Effluent Release Report 16.11.9 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.9 Radioactive Effluent Release Report COMMITMENT The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
A single submittal may be made for a multiple unit station. The submittal shall combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit.
The Annual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the station during the reporting period.
The annual Radioactive Effluent Release Report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter.
The Annual Radioactive Effluent Release Report shall include the following information for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents:
- a. A description of the event and equipment involved;
- b. Cause(s) for the unplanned release; C. Actions taken to prevent recurrence; and,
- d. Consequences of the unplanned release.
The Annual Radioactive Effluent Release Report shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the station during each calendar quarter. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The annual average meteorological conditions shall be used for determining the gaseous pathway doses. Approximate and conservative approximate methods are acceptable. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual.
The Annual Radioactive Effluent Release Report shall include an explanation of why the inoperability of liquid or gaseous effluent monitoring instrumentation out of service for greater than 30 days was not corrected in a timely manner per SLC 16.11.3.
16.11.9-1 03/22/10 1
Radioactive Effluent Release Report 16.11.9 The Annual Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the report period:
- a. Total container volume (cubic meters);
- b. Total curie quantity (determined by measurement or estimate);
C. Principal radionuclides (determined by measurement or estimate);
- d. Type of waste, (e.g., spent resin, compacted dry waste evaporator bottoms);
- e. Number of shipments; and,
- f. Solidification agent (e.g., cement, or other approved agents (media)).
The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to Unrestricted Areas of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the Offsite Dose Calculation Manual (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census.
The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed Member of the Public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Methods for calculating the dose contribution from liquid and gaseous effluents are given in the ODCM.
APPLICABILITY: At all times.
16.11.9-2 03/22/10 1
Radioactive Effluent Release Report 16.11.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. N/A A. 1 N/A N/A SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.9.1 N/A N/A BASES N/A
REFERENCES:
- 1. Oconee ITS.
16.11.9-3 03/22/10 I
Radiological Environmental Operating Report 16.11.10 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11. 10 Radiological Environmental Operating Report COMMITMENT Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of each year.
The Annual Radiological Environmental Operating Report shall include summaries, interpretations. and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the land use censuses. If harmful effects are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
The Annual Radiological Environmental Operating Report shall include a summary of the results obtained as part of the required Interlaboratory Comparison Program. The Interlaboratory Comparison Program shall be described in the Annual Radiological Environmental Operating Report.
The Annual Radiological Environmental Operating Report shall include summarized and tabulated results of the radiological environmental samples required by SI-Cs taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as practical in a supplementary report.
The initial report shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and, the result of land use censuses. Subsequent reports shall describe all substantial changes in these aspects.
APPLICABILITY: At all times.
16.11.10-1 02/25/03 1
Radiological Environmental Operating Report 16.11.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A. 1 NA NA SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.10.1 NA NA BASES NA
REFERENCES:
- 1. Oconee ITS
- 2. Offsite Dose Calculation Manual 16.11.10-2 02/25/03 I
Iodine Radiation Monitoring filters 16.11.11 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.11 Iodine Radiation Monitoring Filters COMMITMENT Assure that the iodine radiation monitoring filters perform their intended function.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. NA A. 1 NA NA I I SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.11.1 Remove and replace iodine radiation 30 days of operation monitoring filters in RIA-44.
SR 16.11.11.2 Discard spare iodine radiation monitoring After 24 months of shelf filters. life.
I BASES The purpose of this commitment is to assure the reliability of the iodine radiation monitoring charcoal filters.
REFERENCES:
16.11.11-1 03/27/99
Radioactive Material in Outside Temporary Tanks Exceeding Limit 16.11.12 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.12 Radioactive Material in Outside Temporary Tanks Exceeding Limit COMMITMENT The quantity of radioactive material in outside temporary storage tanks shall not exceed the limit specified in ITS 5.5.13.c.
APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The quantity of A. 1 Suspend addition of Immediately radioactive material in radioactive material to outside temporary tank.
storage tank not within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.12.1 Verify the quantity of radioactive material Within 7 days after contained in each of the outside temporary addition of radioactive tanks is within the limit by analyzing a materials to an representative sample of the tanks' contents. outside temporary tank OR Verify the quantity of radioactive material in Prior to addition of each of the outside temporary tanks does not radioactive materials to result in exceeding the limit by analyzing a an outside temporary representative sample of radioactive material tank.
to be added.
16.11.12-1 04/10/03 1
Radioactive Material in Outside Temporary Tanks Exceeding Limit 16.11.12 BASES The requirement(s) of this SLC section were relocated from CTS 3.9.1.c during the conversion to ITS.
The tanks included in this specification are all those outdoor radwaste liquid storage tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of a tank's contents, the resulting concentrations would be less than the limits of 10CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
REFERENCES N/A 16.11.12-2 04/10/03 1
Radioactive Material in Waste Gas Holdup tank Exceeding Limit 16.11.13 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.13 Radioactive Material in Waste Gas Holdup Tank Exceeding Limit COMMITMENT The quantity of radioactive material in the Waste Gas Holdup tanks shall not exceed the limit specified in ITS 5.5.13.b.
APPLICABILITY: At all times.
ACTIONS
-NOTE-Separate Condition Entry is allowed for each tank.
CONDITION REQUIRED ACTION COMPLETION TIME A. The quantity of A.1 Suspend addition of Immediately radioactive material in radioactive material to the Waste Gas Holdup tank.
tank not within limit.
AND A.2 Reduce tank contents 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.13.1 Verify quantity of radioactive materials in each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when tank is tank is within limit. being filled BASES The requirement(s) of this SLC section were relocated from CTS 3.10.1.b and 3.10.1.c during the conversion to ITS.
16.11.13-1 03/27/99
Radioactive Material in Waste Gas Holdup tank Exceeding Limit 16.11.13 Restricting the quantity of radioactivity contained in each waste gas holdup tank provides assurance that in the event of an uncontrolled release of the tank contents, the resulting total body exposure to an individual at the exclusion area boundary will not exceed 0.5 rem.
REFERENCE LIFSAR, Section 15.10 16.11.13-2 03/27/99
N.
Explosive Gas Mixture 16.11.14 16.11 RADIOLOGICAL EFFLUENTS CONTROL 16.11.14 Explosive Gas Mixture COMMITMENT The concentration of Hydrogen in the Waste Gas Holdup Tanks shall be
< 3% by volume.
APPLICABILITY: At all times.
ACTIONS
NOTE.
Separate Condition Entry is allowed for each tank.
CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of A.1 Reduce Concentration 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Hydrogen in Waste of Hydrogen to within Gas Holdup tank is > limit.
3% and *<4% by volume.
B. Concentration of B.1 Suspend addition of Immediately Hydrogen in Waste waste gases to tank.
Gas Holdup tank is >
4% by volume. AND B.2 Reduce Concentration 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of Hydrogen to within limit.
16.11.14-1 03/27/99
Explosive Gas Mixture 16.11.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 16.11.14.1 Verify Hydrogen concentration in Waste Gas 5 times/week on each Holdup Tank issý 3% by volume. tank when in service AND once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after isolation of the tank BASES The requirement(s) of this SLC section were relocated from CTS 3.10.2 and Table 4.1-3, Item 13 during the conversion to ITS.
This Commitment is provided to ensure that the concentration of potentially explosive gas mixtures contained in the Waste Gas Holdup Tanks is maintained below the flammability limits of hydrogen. (Administrative controls are used to prevent the hydrogen concentrations from reaching the flammability limit.) These controls include sampling each tank 5 times a week while in service, and/or once in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after isolation of the tank; injection of dilutants to reduce the concentration of hydrogen below its flammability limits provides assurance that the releases of radioactive material will be controlled in conformance with the requirements of GDC 60 of Appendix A to CFR Part 50.
REFERENCES N/A 16.11.14-2 03/27/99
Attachment 8 Oconee Nuclear Site Revisions to the Radioactive Waste Process Control Program Manual The following letter dated April 7, 2011, from David L. Vaught, Senior Engineer, Nuclear Chemistry, summarizes how the Process Control Program (PCP) manual has been revised. The updated version of the manual contains all the changes implemented during 20 10 and is designated as the "20 10 Update" on the enclosed Compact Disc.
April 7, 2011 KR Alter Regulatory Compliance Manager Oconee Regulatory Compliance Attention: J. E. Smith
Subject:
Oconee Nuclear Station 2010 Annual Radioactive Effluent Release Report Process Control Progam Changes File: GS-764.25, OS-215.06 Enclosed are CD copies of the PDF file of the Radioactive Waste Process Control Program Manual to be included in the NRC distribution of the Annual Radioactive Effluent Release Report for Oconee Nuclear Station for the period of January 1, 2010 through December 3 1, 2010. This version of the Manual contains all the changes implemented during 2010 and is designated as the "2010 Report Year".
The PCP Manual is revised using the review and approval process in APPENDIX F of the Manual, "Administration of the PCP and Support Documents" prior to publication on the NEDL Portal.
The attachment summarizes the scope of the changes during 2010.
The PDF files on the CDs were reviewed and verified against the control copies of the PCP Manual published on the NEDL Portal.
Three CD copies are for internal distribution and DHEC and four CDs are for the NRC as follows:
File: 201 0-Duke-Energy-ARERRPCP-Manua- Update. pdf Duke
- 1. ELL-CD
- 2. Master File - CD DHEC
- 3. DHEC primary contact Russell Keown - CD NRC
- 4. NRC Document Control Desk
- 5. Oconee NRC Project Manager
- 6. Oconee Senior Resident Inspector
- 7. NRC Regional Administrator If you have any questions, please call David Vaught @ 980-373-5302.
Larry A. Wilson Supervising Scientist Nuclear Chemistry by: David L Vaught Senior Engineer Nuclear Chemistry - Radwaste ATTACHMENT
ATTACHMENT Duke Energy Radioactive Waste Process Control Program Manual Summary of 2010 Changes A brief summary of the 2010 changes to the Duke Energy Radioactive Waste PCP Manual is found below. These are described in more detail in APPENDIX H "Revision Summary -
Licensee Initiated Changes" Revised Section; APPENDIX A: "ONS PCP" Rev 14 to Rev 15 Description of Changes G-9-00901: Document the changes, review and approval of a revision to the PCP Manual Appendix A "ONS PCP" due to changes in the PCP implementing procedures at ONS.
- 1. Changed the list of implementing procedures to reflect that CP/O/B/5400/001 has been changed to an "A" procedure, CP/0/A/5400/00 1.
- 2. Added the new procedure CP/O/A/5400/013 "RADWASTE POWDEX LINER DEWATERING &
OPERATING GUIDELINES" to the list of PCP implementing procedures.
- 3. Incorporated information from three new vendor technical procedures for the Energy Solutions Self-Engaging Dewatering System (S.E.D.S) being implemented at ONS.
Attachment 9 Oconee Nuclear Site Information to Support the Nuclear Energy Institute (NEI)
Groundwater Protection Initiative
2010 Annual Radiological Effluent Release Report Ground Water Well Data Duke Energy implemented a Ground Water Protection program in 2007. This program was developed to ensure timely and effective management of situations involving inadvertent releases of licensed material to ground water. As part of this program, Oconee monitored sixty-six ground water wells during 2010. Tritium activity in wells GM-7R and GM-7DR was reported per NEI 07-07 in February, 2010. The source of this activity is still under investigation.
Wells are sampled quarterly, semi-annually or annually. Ground water samples are regularly analyzed for tritium and gamma emitters with selected wells being analyzed for difficult to detect radionuclides. No gamma or difficult to detect radionuclides (other than naturally occurring radionuclides) were identified in well samples during 2010.
Results from sampling during 2010 are shown in the table below.
Avg. Tritium Conc. # of Well Name Well Location Conc.(pCi/1) Range Samples BG-4 Ball Field < < 4 MW-3 Landfill < < 2 MW-1I Landfill < < 2 MW-11D Landfill 251 251 2 MW-13 Landfill 208 208 2 MW-16 Landfill 195 195 2 MW-RPO1 Landfarm/Burial < < 4 MW-RP02 Landfarm/Burial < < 4 MW-RP03 Landfarm/Burial < < 4 MW A-1 CTP- 1/2 208 187-228 4 MW A-2 CTP- 1/2 < < 4 MW A-8 CTP-1/2 279 193-326 3 MW A-9 CTP-1/2 170 170 4 MW A-10 CTP-3 280 239-312 4 MW A-11 CTP-3 < < 4 MW A-12 CTP-3 < < 4 MWA-13 CTP- 1/2 851 681-1120 4 MW A-14 CTP-1/2 354 328-397 4 MWA-17 CTP- 1/2 < < 4 MWA-18 CTP-1/2 < < 4 GM-1R CTP-1/2 168 168 4 GM-2R U-l/2 SFP 2,630 2,140 - 4,020 4 GM-2DR U-1/2 SFP 1,628 1,400 - 1,900 4 GM-3R U-3 SFP 228 227 - 228 3 GM-3DR U-3 SFP 196 192- 199 3 GM-4 WH-10 415 306-466 4 GM-5 Rdwst. Bldg. 212 183 -241 4 GM-5R Rdwst. Bldg. I _< < 1 4 Prepared January 10, 2011
2010 Annual Radiological Effluent Release Report Ground Water Well Data GM-6 Outflow to CTP-3 < < 4 GM-6R Outflow to CTP-3 < < 4 GM-7 525 kv Sw. Yard 1,135 618- 1,480 5 GM-7R 525 kv Sw. Yard 29,620 24,400 - 35,600 5 GM-7DR 525 kv Sw. Yard 7,397 229 - 35,400 5 GM-8 E of U-3 TB 203 176 -229 4 GM-8R E of U-3 TB 245 218 -277 4 GM-9 E of U-2 TB 213 213 4 GM-9R E of U-2 TB < < 4 GM-10 525 kv Sw. Yard 600 600 4 GM-10R 525 kv Sw. Yard 195 195 4 GM-11 525 kv Sw. Yard < < 4 GM-11R 525 kv Sw. Yard < < 4 GM-12 E of Access Rd. < < 4 GM-12R E of Access Rd. 200 200 4 GM-13 525 kv Sw. Yard 165 165 4 GM-13R 525 kv Sw. Yard < < 4 GM-14 Mnt. Trg. Facility < < 4 GM-14R Mnt. Trg. Facility < < 4 GM-15 525 kv Sw. Yard 3,778 2,560 - 5,140 4 GM-15R 525 kv Sw. Yard 471 417-607 4 GM-16R TBSMT 9,358 5,240 - 14,100 4 GM-16DR TBSMT 11,400 10,700 - 12,600 4 GM-16DDR TBSMT 359 322-416 3 GM-17R Oil Drum Storage 8,865 6,020 - 13,500 4 GM-17DR Oil Drum Storage 2,993 2,150 - 3,630 4 GM-18R RCP Refurb. Bldg 9,697 8,190 - 10,500 3 GM-19 525 kv Sw. Yard 321 282-364 4 GM-19R 525 kv Sw. Yard 345 238-410 4 GM-20 SG Retire. Facility < < 4 GM-20R SG Retire. Facility < < 4 GM-21 Sec.Trg. Facility < < 4 GM-22 Sec.Trg. Facility < < 4 GM-23 525 kv Sw. Yard 659 459-1,010 4 GM-24R 3T Transformer 5,597 3,660 - 6,640 3 GM-25R CT3 Transformer 419 348 - 501 3
- 011 (IW-I) Ball Field < < 4
- 013 (IW-2) WH-5 < < 4
- 015 Brown's Bottom < < 4 Prepared January 10, 2011
2010 Annual Radiological Effluent Release Report Ground Water Well Data
- These are irrigation wells and may not meet current requirements for ground water well construction.
pCi/1 - 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/l - the 10CFR20, Appendix B, Table 2, Column 2, Effluent Concentration limit for tritium.
Prepared January 10, 2011
Vt Duke DukeVice DAVEPresident BAXTER POcEnergye onee Nucleat Station Duke Energy ONOI VP / 7800 Rochester Highway Seneca, SC 29672 864-873-4460 864.873-4208 fax dabaxter@dukeenergy.com March 3, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C., 20555-001
Subject:
Duke Energy Carolinas, LLC Oconee Nuclear Station, Units 1, 2, and 3 Renewed Facility Operating License, DPR-38, DPR-47, and DPR-55 Docket Numbers 50-269, 50-270, and 50-287 30-Day Report Pursuant to the Ground Water Protection Initiative Concerning Oconee Nuclear Station Ground Water Monitoring Wells GM-7R and GM-7DR Duke Energy Carolinas, LLC (Duke Energy) is submitting the attached 30-day report pursuant to NEI 07-07 [FINAL], "Industry Ground Water Protection Initiative," dated August, 2007. Samples obtained from ground water monitoring wells GM-7R and GM-7DR on January 26, 2010, contained tritium concentrations that triggered the communication protocol of NEI 07-07 on February 8, 2010.
There are no regulatory commitments contained in this letter. If you have any questions on this matter, please contact Bob Meixell, Oconee Regulatory Compliance, at (864) 873-3279.
Sincerely,
( Dave Baxter, Vice President Oconee Nuclear Station
Attachment:
30-Day Report per NEI 07-07 [FINAL, ."Industry Ground Water Protection Initiative,"
Oconee Nuclear Station, Units 1, 2 and 3 www.duke-energ,.corn
V U.S. Nuclear Regulatory Commission March 3, 2010 Page 2 bc w/attachment:
Mr. Luis Reyes USNRC - Region II Sam Nun Atlanta Federal Center Suite 23T85, 61 Forsyth St., SW Atlanta, GA 30303-8931 Mr. John Stang Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8 G9A Washington, DC 20555 Mr. Andy Sabisch NRC Senior Resident Inspector Oconee Nuclear Station Ms. Susan E. Jenkins Manager, Infectious and Radioactive Waste Management Bureau of Land and Waste Management Department of Health & Environmental Control 2600 Bull Street, Columbia, SC 29201 Mr. Tom Knight Manager, Aboveground Storage Tank (AST)
Petroleum Restoration & Site Environmental Investigations Bureau of Land and Waste Management Department of Health & Environmental Control 2600 Bull Street, Columbia, SC 29201
U.S. Nuclear Regulatory Commission March 3, 2010 Page 3 bcc w/attachment:
K.R. Alter T.P. Gillespie, Jr.
R.M. Glover S.L. Batson J.W. Pitesa J.E. Burchfield J.E. Bohlmann R.J. Freudenberger L.E. Haynes L.D. Robinson S.E. Spear W.S. Pursley R.L. Gill - NRI&IA C.J. Thomas - Fleet Regulatory Compliance R.D. Hart - CNS K.L. Ashe - MNS D. Repka D.A. Cummings NSRB, EC050 ELL, EC050 File - TS Working ONS Document Management
-I ATTACHMENT 30-DAY REPORT PER NEI 07-07 [FINAL],
INDUSTRY GROUND WATER PROTECTION INITIATIVE, OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 This report is being submitted in support of NEI 07-07, Industry Ground Water Protection Initiative.
- a. This report was generated as a result of the ground water monitoring results for wells GM-7R and GM-7DR. These results triggered the co~mmunication protocol of NEI 07-07 on February 8, 2010.
ii. Samples obtained from groundwater monitoring wells contained tritium in the following concentrations:
- a. GM-7R; 24,400 picocuries per liter (pCi/I)
- b. GM-7DR; 35,400 picocuries per liter (pCi/I) iii. On February 8, 2010, Oconee was notified by the Duke Energy Environmental Lab that samples taken from ground water monitoring wells GM-7R and GM-7DR on January 26, 2010, contained tritium levels that triggered the NEI 07-07 ground water communication protocol. On February 9, 2010, Duke Energy verbally notified the NRC (NRC Event Notification number 45690) and appropriate state and local agencies of the on-site environmental monitoring well sample results indicated in (ii) above.
Elevated tritium levels in ground water samples were identified in well GM-7R and adjacent well GM-7 in 2008. Duke Energy began investigation by pressure testing the Liquid Waste Discharge (LWD) piping. A portion of the LWD piping is located in the vicinity of the area showing elevated tritium concentrations. This piping was pressure tested from the Turbine Building to Keowee Hydro. This testing did not indicate any leakage present.
Remote video inspection of the Turbine Building Sump Monitor Tank discharge piping along the east side of the Turbine Building has been conducted. This piping is immediately up-gradient of GM-7 wells. As part of the investigation, Duke Energy has limited pumping Turbine Building Sump water into this yard drainage system.
A hydro-geologic model has been developed by an independent engineering firm with expertise in groundwater flow. Since December 2009, Duke Energy has installed 14 additional ground water monitoring wells and installation of additional wells is in progress. The additional wells will be used, along with existing wells, to refine the model and define the horizontal and vertical extent of tritium observed in ground water.
2 ATTACHMENT 30-DAY REPORT PER NEI 07-07 [FINAL],
INDUSTRY GROUND WATER PROTECTION INITIATIVE, OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 iv. The wells displaying tritium activity are ground water monitoring wells, and not drinking water wells. Samples from surrounding ground water monitoring wells indicate that tritium has not migrated to the site boundary. South Carolina Department of Health and Environmental Control (DHEC) sampling of residential wells around the Oconee Nuclear Station, and Duke Energy samples from surrounding monitoring wells indicate that tritium in ground water has not migrated off the plant site. Therefore there is no public exposure pathway and Duke Energy determined that there is no estimated annual dose to any member of the public associated with this event.
V. Since there is no estimated annual dose increase to a member of the public from this event, no corrective actions are necessary to reduce the projected annual dose to a member of the public to less than the limits of 10 CFR 50 Appendix 1.
Attachment 10 Oconee Nuclear Site Inoperable Monitoring Equipment 1 RIA-40 and 2RIA-40, Condenser Steam Air Ejector Off Gas Monitors, were declared out-of-service on August 5, 2010, at 1745 due to water carryover in the detector.
Selected Licensee Commitment (SLIC) 16.11.3, Condition C, required action to return 1RIA-40 and 2RIA-40 to service within 30 days has not been completed.
Because condensation is visible in the rotameters for 1 RIA-40 and 2RIA-40, it is plausible that water droplets condensing on the face of the detector for 1 RIA-40 and 2RIA-40 can effectively shield some of the beta energy from expected sources (Xe-1 33). This shielding effect would
-adversely impact the sensitivity of 1 RIA-40 and 2RIA-40 to detect and alarm for increased activity resulting from a primary to secondary leak. The amount of water within the sample chambers for 1 RIA-40 and 2RIA-40 is unknown. Since the amount of water and its relative effect on sensitivity cannot be quantified, as a conservative measure 1 RIA-40 and 2RIA-40 were declared inoperable. However, the effluent pathway is still being monitored by 1 RIA-45 and 2RIA-45 Unit Vent Monitors.
On September 4, 2010, at 1745, Oconee Units 1 and 2 entered S.L.C. 16.11.3, Condition D, which states that the Annual Radioactive Effluent Release Report to the NRC shall include an explanation of why the inoperability of liquid or gaseous effluent monitoring instrumentation, out of service for greater than 30 days, was not corrected in a timely manner.
A modification is being developed to either eliminate the water in the system or use another type of detector that is not affected by water. A modification will require more than 30 days to complete either of these actions. The modification will be implemented for 1 RIA-40, 2RIA-40 and 3RIA-40. Until 1RIA-40 and 2RIA-40 are returned to service, SLC.16.11.3, Condition C, will remain in effect for Units I and 2.
3RIA-40, Condenser Steam Air Ejector Off Gas Monitor, has been calibrated and there is no indication of condensation on the rotometers. Therefore, 3RIA-40 is functional and capable of meeting its design requirements for Unit 3.
Enclosure 2011 Offsite Dose Calculation Manual Compact Disc