Text

Annual Radiological Environmental Operating Report
	ML11153A138
Person / Time
Site:	Oconee
Issue date:	12/31/2010
From:	; Duke Energy Carolinas
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML11153A138 (89)
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE ENERGY CORPORATION OCONEE NUCLEAR STATION Units 1, 2, and 3 2010

TABLE OF CONTENTS 1.0 Executive Summary . . . . . . . . . . . . 1-1 2.0 Introduction . . . . . . . . . . . . . 2-1 2.1 Site Description and Sample Locations . . . . . . . 2-1 2.2 Scope and Requirements of the REMP . . . . . . . 2-1 2.3 Statistical and Calculational Methodology . . . . . . . 2-2 2.3.1 Estimation of the Mean Value . . . . . . . . 2-2 2.3.2 Lower Level of Detection and Minimum Detectable Activity . . 2-3 2.3.3 Trend Identification . . . . . . . . . 2-3 3.0 Interpretation of Results . . . . . . . . . . . 3-1 3.1 Airborne Radioiodine and Particulates . . . . . . . 3-2 3.2 Drinking Water . . . . . . . . . . . . 3-5 3.3 Surface Water . . . . . . . . . . . . 3-7 3.4 Milk . . . . . . . . . . . . . . 3-10 3.5 Broadleaf Vegetation . . . . . . . . . . 3-12 3.6 Fish . . . . . . . . . . . . . . 3-14 3.7 Shoreline Sediment . . . . . . . . . . . 3-17 3.8 Direct Gamma Radiation . . . . . . . . . . 3-20 3.8.1 Environmental TLD . . . . . . . . . . 3-20 3.8.2 ISFSI . . . . . . . . . . . . 3-20 3.9 Land Use Census . . . . . . . . . . . 3-25 4.0 Evaluation of Dose . . . . . . . . . . . . 4-1 4.1 Dose from Environmental Measurements . . . . . . . 4-1 4.2 Estimated Dose from Releases . . . . . . . . . 4-1 4.3 Comparison of Doses . . . . . . . . . . 4-2 5.0 Quality Assurance . . . . . . . . . . . . 5-1 5.1 Sample Collection . . . . . . . . . . 5-1 5.2 Sample Analysis . . . . . . . . . . . 5-1 5.3 Dosimetry Analysis . . . . . . . . . . . 5-1 5.4 Laboratory Equipment Quality Assurance . . . . . . . 5-1 5.4.1 Daily Quality Control . . . . . . . . . 5-1 5.4.2 Calibration Verification . . . . . . . . . 5-1 5.4.3 Batch Processing . . . . . . . . . . 5-2 5.5 Duke Energy Intercomparison Program . . . . . . . 5-2 5.6 ERA Proficiency Testing . . . . . . . . . . 5-2 5.7 Duke Energy Audits . . . . . . . . . . . 5-2 5.8 U.S. Nuclear Regulatory Commission Inspections . . . . . 5-2 5.9 State of South Carolina Intercomparison Program . . . . . 5-2 5.10 TLD Intercomparison Program . . . . . . . . . 5-3 5.10.1 Nuclear Technology Services Intercomparison Program . . . 5-3 5.10.2 Internal Crosscheck (Duke Energy) . . . . . . 5-3 6.0 References . . . . . . . . . . . . . 6-1 i

Appendices Appendix A: Environmental Sampling and Analysis Procedures . . . . A-1 I. Change of Sampling Procedures . . . . . . . . A-2 II. Description of Analysis Procedures . . . . . . . . A-2 III. Change of Analysis Procedures . . . . . . . . . A-3 IV. Sampling and Analysis Procedures . . . . . . . . A-3 A.1 Airborne Particulate and Radioiodine . . . . . . A-3 A.2 Drinking Water . . . . . . . . . . A-3 A.3 Surface Water . . . . . . . . . . . A-4 A.4 Milk . . . . . . . . . . . . A-4 A.5 Broadleaf Vegetation . . . . . . . . . A-4 A.6 Fish . . . . . . . . . . . . A-4 A.7 Shoreline Sediment . . . . . . . . . . A-4 A.8 Direct Gamma Radiation (TLD) . . . . . . . A-5 A.9 Annual Land Use Census . . . . . . . . . A-5 V. Global Positioning System (GPS) Analysis. . . . . . . A-5 Appendix B: Radiological Env. Monitoring Program - Summary of Results . . B-1 Air Particulate . . . . . . . . . . . . B-2 Air Radioiodine . . . . . . . . . . . B-3 Drinking Water . . . . . . . . . . . . B-4 Surface Water . . . . . . . . . . . . B-5 Milk . . . . . . . . . . . . . . B-6 Broadleaf Vegetation . . . . . . . . . . B-7 Fish . . . . . . . . . . . . . . B-8 Shoreline Sediment . . . . . . . . . . . B-9 Direct Gamma Radiation (TLD) . . . . . . . . B-10 Appendix C: Sampling Deviations and Unavailable Analyses . . . . . C-1 C.1 Sampling Deviations . . . . . . . . . . C-2 C.2 Unavailable Analyses . . . . . . . . . . C-3 Appendix D: Analytical Deviations . . . . . . . . . . D-1 Appendix E: Radiological Environmental Monitoring Program Results . . . E-1 LIST OF FIGURES 2.1-1 Sampling Locations Map (One Mile Radius) . . . . . . 2-4 2.1-2 Sampling Locations Map (Ten Mile Radius) . . . . . . 2-5 3.1 Concentration of Gross Beta in Air Particulate . . . . . . 3-4 3.2 Concentration of Tritium in Drinking Water . . . . . . 3-5 3.3 Concentration of Tritium in Surface Water . . . . . . . 3-8 3.5 Concentration of Cs-137 in Broadleaf Vegetation . . . . . 3-12 3.6-1 Concentration of Cs-137 in Fish . . . . . . . . 3-15 3.6-2 Concentration of Cs-134 in Fish . . . . . . . . 3-15 3.7-1 Concentration of Cs-137 in Shoreline Sediment . . . . . . 3-18 3.7-2 Concentration of Co-60 in Shoreline Sediment . . . . . . 3-18 3.8-1 Direct Gamma Radiation (TLD) Results . . . . . . . 3-21 3.8-2 Oconee Inner Ring (TLD) Results . . . . . . . . 3-23 3.8-3 Oconee Outer Ring (TLD) Results . . . . . . . . 3-24 3.9 2010 Land Use Census Map . . . . . . . . . 3-26 LIST OF TABLES 2.1-A Radiological Monitoring Program Sampling Locations . . . . 2-6 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites) . . 2-7 ii

2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples . . . . . . . . . . 2-8 2.2-B REMP Analysis Frequency . . . . . . . . . 2-8 2.2-C Maximum Values for the Lower Limits of Detection . . . . . 2-9 3.1-A Mean Concentration of Air Radioiodine (I-131) . . . . . . 3-3 3.1-B Mean Concentration of Gross Beta in Air Particulate . . . . . 3-4 3.2 Mean Concentrations of Radionuclides in Drinking Water . . . . 3-6 3.3 Mean Concentrations of Radionuclides in Surface Water . . . . 3-9 3.4 Mean Concentrations of Radionuclides in Milk . . . . . . 3-11 3.5 Mean Concentrations of Radionuclides in Vegetation . . . . 3-13 3.6 Mean Concentrations of Radionuclides in Fish . . . . . . 3-16 3.7 Mean Concentrations of Radionuclides in Shoreline Sediment . . . 3-19 3.8-A Direct Gamma Radiation (TLD) Results . . . . . . . 3-22 3.8-B Direct Gamma Radiation (TLD) Results Inner Ring . . . . . 3-23 3.8-C Direct Gamma Radiation (TLD) Results Outer Ring . . . . . 3-24 3.9 Oconee 2010 Land Use Census Results . . . . . . . 3-25 4.1-A 2010 Environmental and Effluent Dose Comparison . . . . . 4-3 4.1-B Maximum Individual Dose for 2010 based on Environmental Measurements for Oconee Nuclear Station . . . . . . . 4-5 5.0-A 2010 Cross-Check Results for EnRad Laboratories . . . . . 5-4 5.0-B 2010 Environmental Resource Associates QuikTM Response Program . . 5-9 5.0-C 2010 Environmental Dosimeter Cross-Check Results . . . . . 5-11 LIST OF ACRONYMS USED IN THIS TEXT (in alphabetical order)

BW BiWeekly C Control DEHNR Department of Environmental Health and Natural Resources DHEC Department of Health and Environmental Control EPA Environmental Protection Agency ERA Environmental Resource Associates GI-LLI Gastrointestinal - Lower Large Intestine GPS Global Positioning System ISFSI Independent Spent Fuel Storage Installation LLD Lower Limit of Detection M Monthly MDA Minimum Detectable Activity MOA Memorandum of Agreement mrem Millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual ONS Oconee Nuclear Station pCi/kg picocurie per kilogram pCi/l picocurie per liter pCi/m3 picocurie per cubic meter PIP Problem Investigation Program Q Quarterly REMP Radiological Environmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECs Technical Specifications TLD Thermoluminescent Dosimeter PCi/ml microcurie per milliliter UFSAR Updated Final Safety Analysis Report W Weekly iii

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the Oconee Nuclear Station Radiological Environmental Monitoring Program (REMP), and the program results for the calendar year 2010.

Included are the identification of sampling locations, descriptions of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and pre-operational environmental data, comparisons of doses calculated from environmental measurements and effluent data, analysis of trends in environmental radiological data as potentially affected by station operations, and a summary of environmental radiological sampling results. Quality assurance practices and program changes are also discussed.

Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLCs). Required analyses were performed and detection capabilities were met for all collected samples as required by SLCs. Nine-hundred seventy-nine samples were analyzed comprising 1,362 test results in order to compile data for the 2010 report. Based on the annual land use census, the current number of sampling sites for Oconee Nuclear Station is sufficient.

Concentrations observed in the environment in 2010 for station related radionuclides were within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in drinking water, surface water, shoreline sediment, and fish are higher than the activities reported for samples collected at control locations. All positively identified measurements were within limits as specified in SLCs.

Additionally, environmental radiological monitoring data is consistent with effluents introduced into the environment by plant operations. The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data, excluding TLD results, was 5.22E-02 mrem for 2010. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment.

Section 1 - Page 1

2.0 INTRODUCTION

2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Oconee Nuclear Station (ONS) is located in Oconee County, South Carolina, approximately 8 miles northeast of Seneca, South Carolina, on the shore of Lake Keowee. This lake was formed by damming the Keowee and Little Rivers in that location. Immediately to the south is the U.S.

Government Hartwell Project. The Keowee Hydroelectric Plant near the station joins Lake Keowee and the upper reaches of Lake Hartwell. To the north, the Jocassee Hydroelectric Plant joins Lake Jocassee and Lake Keowee. Jocassee is a pumped storage plant.

ONS consists of three pressurized water reactors. Each unit has an output of 846 megawatts net. Unit 1 license for operation was issued 2/6/1973. Unit 2 license for operation was issued 10/6/1973. Unit 3 license for operation was issued 7/19/1974. An independent spent fuel storage installation is also located at the site.

Figures 2.1-1 and 2.1-2 are maps depicting the Thermoluminescent Dosimeter (TLD) monitoring locations and the sampling locations. The location numbers shown on these maps correspond to those listed in Tables 2.1-A and 2.1-B. Figure 2.1-1 comprises all sample locations within a one mile radius of ONS. Figure 2.1-2 comprises all sample locations within a ten mile radius of ONS.

2.2 SCOPE AND REQUIREMENTS OF THE REMP An environmental monitoring program has been in effect at Oconee Nuclear Station since 1969, four years prior to operation of Unit 1 in 1973. The preoperational program provides data on the existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station. The operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.

This monitoring program is based on NRC guidance as reflected in the Selected Licensee Commitments Manual, with regard to sample media, sampling locations, sampling frequency, and analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other man-made environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related exposures from releases of radionuclides from Oconee Nuclear Station. This program satisfies the requirements of Section IV.B.2 of Appendix I to 10CFR50 and 10CFR72.44(d)(2) and provides surveillance of all appropriate critical exposure pathways to man and protects vital interests of the company, public, and state and federal agencies concerned with the environment. Reporting levels for radioactivity found in environmental samples are listed in Table 2.2-A. Table 2.2-B lists the REMP analysis and frequency schedule.

Section 2 - Page 1

The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 3.9.

Participation in an interlaboratory comparison program as required by Selected Licensee Commitments provides for independent checks on the precision and accuracy of measurements of radioactive material in REMP sample matrices. Such checks are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A summary of the results obtained as part of this comparison program are in Section 5 of this annual report.

2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium.

The mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the Radiological Environmental Monitoring Program. Net activity (or concentration)" is the activity (or concentration) determined to be present in the sample. No "Minimum Detectable Activity", "Lower Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of the mean. The following equation was used to estimate the mean (reference 6.8):

N x

i 1 i

x =

N Where:

x = estimate of the mean, i = individual sample, N = total number of samples with a net activity (or concentration),

Fi = net activity (or concentration) for sample i.

Section 2 - Page 2

2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE ACTIVITY The Lower Level of Detection (LLD) and Minimum Detectable Activity (MDA) are used throughout the Environmental Monitoring Program.

LLD - The LLD, as defined in the Selected Licensee Commitments Manual is the smallest concentration of radioactive material in a sample that will yield a net count, above the system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a "real" signal. The LLD is an a priori lower limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield, and the radioactive decay of the sample between sample collection and counting. The "required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.

MDA - The MDA is the net counting rate (sample after subtraction of background) that must be surpassed before a sample is considered to contain a scientifically measurable amount of a radioactive material exceeding background amounts. The MDA is calculated using a sample background and may be thought of as an "actual" LLD for a particular sample measurement.

2.3.3 TREND IDENTIFICATION One of the purposes of an environmental monitoring program is to determine if there is a buildup of radionuclides in the environment due to the operation of the nuclear station.

Visual inspection of tabular or graphical presentations of data (including preoperational) is used to determine if a trend exists. A decrease in a particular radionuclide's concentration in an environmental medium does not indicate that reactor operations are removing radioactivity from the environment but that reactor operations are not adding that radionuclide to the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the concentration.

Substantial increases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to completely interpret the trends, or lack of trends, determined from the environmental data. Some factors that may affect environmental levels of radionuclides include prevailing weather conditions (periods of drought, solar cycles or heavier than normal precipitation), construction in or around either the nuclear plant or the sampling location, and addition or deletion of other sources of radioactive materials (such as the Chernobyl accident). Some of these factors may be obvious while others are sometimes unknown. Therefore, how trends are identified will include some judgment by plant personnel.

Section 2 - Page 3

Figure 2.1-1 Section 2 - Page 4

Figure 2.1-2 Section 2 - Page 5

TABLE 2.1-A OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 2.1-A Codes W Weekly SM Semimonthly BW BiWeekly Q Quarterly M Monthly SA Semiannually C Control I Indicator Site Measure Air Rad. & Surface Drinking Shoreline Fish Milk Broadleaf Location Description* Particulate Water Water Sediment Vegetation

Type 060 I Greenville Water Intake Road (3.23 NE) M 060 C** Greenville Water Intake Road (2.28 NE) SA 062 C Lake Keowee Hydro Intake (0.85 mi ENE) M Lake Hartwell Hwy 183 Bridge 063 I (0.80 mi ESE) [000.7] SA SA 063.1 I Lake Hartwell Hwy 183 (0.79 mi E) M 064 C Seneca (6.67 mi SSW) [004.1] M 066 I Anderson (18.9 mi SSE) [012] M Lawrence Ramsey Bridge Hwy 27 067 I (4.34 mi SSE) [005.2] SA SA 068 C High Falls County Park (1.82 mi W) SA 071 C Clemson Dairy (10.2 mi SSE) [006.3] SM 074 I Keowee Key Resort (2.36 mi NNW) W 077 I Skimmer Wall (1.00 mi SW) W M 078.1 I Recreation Site (0.53 mi WSW) W 079 I Keowee Dam (0.56 mi NE) W M 081 C Clemson Operations Center (9.33 mi SE) W M 084 I Sue Craig Road (2.58 mi NNE) W M

GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.

- Control for Fish Only

[ ] Location Numbers prior to 1984 Section 2 - Page 6

TABLE 2.1-B OCONEE RADIOLOCICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)

Table 2.1-B Codes IR Inner Ring OR Outer Ring C Control SI Special Interest Site Measure Location* Distance Sector Site Measure Location* Distance Sector

Type (miles) # Type (miles)

MICROWAVE TOWER, SIX 020 IR SITE BOUNDARY 0.16 N 040 OR MILE 4.74 E 021 IR SITE BOUNDARY 0.25 NNE 041 OR JCT HWY 101 & 133 4.25 ESE LAWRENCE CHAPEL 022 IR SITE BOUNDARY 0.53 NE 042 OR CHURCH, HWY 133 4.93 SE HWY 291 AT 023 IR SITE BOUNDARY 0.93 ENE 043 OR ISSAQUEENA PARK 4.09 SSE HWY 130 AT LITTLE 024 IR SITE BOUNDARY 0.79 E 044 OR RIVER DAM 3.96 S TERMINUS OF HWY 588 025 IR SITE BOUNDARY 0.42 ESE 045 OR AT CROOKED CREEK 4.78 SSW HWY 188 AT 026 IR SITE BOUNDARY 0.34 SE 046 OR CROOKED CREEK 4.61 SW NEW HOPE CHURCH, 027 IR SITE BOUNDARY 0.49 SSE 047 OR HWY 188 3.58 WSW 028 IR SITE BOUNDARY 0.46 S 048 OR JCT HWY 175 & 188 3.64 W 029 IR SITE BOUNDARY 0.56 SSW 049 OR JCT HWY 201 & 92 3.60 WNW STAMP CREEK LANDING, 030 IR SITE BOUNDARY 0.42 SW 050 OR END OF HWY 92 3.53 NW HWY 128, 1 MILE N OF 031 IR SITE BOUNDARY 0.27 WSW 051 OR HWY 130 4.64 NNW DPC BRANCH OFFICE 076 IR SITE BOUNDARY 0.19 W 052 SI SITE - PICKENS 12.4 ENE DPC BRANCH OFFICE 032 IR SITE BOUNDARY 0.19 WNW 053 SI SITE - LIBERTY 11.7 E POST OFFICE - HWY 93 033 IR SITE BOUNDARY 0.21 WNW 054 SI NORRIS 8.60 ESE CLEMSON 034 IR SITE BOUNDARY 0.22 NW 055 SI METEOROLOGY PLOT 9.27 SSE WATER TOWER - SENECA 035 IR SITE BOUNDARY 0.17 NNW 056 SI 7.30 SSW OCONEE MEMORIAL 036 OR MILE CREEK LANDING 4.18 N 057 SI HOSPITAL 8.42 SW KEOWEE CHURCH, BRANCH RD 037 OR HWY 327 4.85 NNE 058 C SUBSTATION,WALHALLA 9.39 WSW CONVENIENCE MART, 038 OR JCT HWY 183 & 133 4.24 NE 059 SI TAMASSEE DAR SCHOOL 9.20 NW HWY 133, 1 MILE EAST CLEMSON 039 OR OF JCT HWY 183 & 133 4.02 ENE 081 C OPERATIONS CENTER 9.33 SE

GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.

Section 2 - Page 7

TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water Air Particulates Fish Milk Broadleaf (pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) Vegetation (pCi/m3) (pCi/kg-wet)

H-3 20,000(a)

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 2(b) 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (a) For drinking water samples only. This is 40CFR Part 141 value.

(b) If low-level I-131 analyses are performed.

TABLE 2.2-B REMP ANALYSIS FREQUENCY Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic I-131 Beta Air Radioiodine Weekly X Air Particulate Weekly X X Direct Radiation Quarterly X Surface Monthly X Water Quarterly Composite X Drinking Monthly X (a) X Water Quarterly Composite X Shoreline Sediment Semiannually X Milk Semimonthly X X Fish Semiannually X Broadleaf Vegetation Monthly X (a) Low level I-131 analysis will be performed if abnormal releases occur which could reasonably result in > 1 pCi/liter of I-131 in drinking water. An LLD of 1 pCi/liter will be required for this analysis.

Section 2 - Page 8

TABLE 2.2-C MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION Analysis Water Air Fish Milk Broadleaf Sediment (pCi/liter) Particulates (pCi/kg-wet) (pCi/liter) Vegetation (pCi/kg-dry) or Gases (pCi/kg-wet)

(pCi/m3)

Gross Beta 4 0.01 H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 15 Nb-95 15 I-131 15(a) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) LLD for low-level I-131 analyses is 1 pCi/liter if performed Section 2 - Page 9

3.0 INTERPRETATION OF RESULTS Review of 2010 REMP analysis results was performed to identify changes in environmental levels as a result of station operations. The review is summarized in this section. Data from 2010 was compared to preoperational and historical data. Sample data for some media is not directly comparable to preoperational and earlier operational sample results because of either significant changes in the analysis methods or changes in the reporting of the results.

Evaluation for significant trends was performed for the radionuclides that have required LLDs listed in Selected Licensee Commitment 16.11.6. These radionuclides are collectively referred to as "Selected Licensee Commitments radionuclides" and include H-3, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, I-131, Cs-134, Cs-137, Ba-140, and La-140. Drinking water gross beta results are routinely trended. Trending of air particulate gross beta results was initiated in 1996 when the analysis was resumed. Trending is also performed for other radionuclides that are detected and could have been the result of station effluents. Only Selected Licensee Commitment radionuclides were detected in 2010.

Trending was performed by comparing annual mean concentrations of any effluent related detected radionuclide to historical results. Factors evaluated include the frequency of detection and the concentration in terms of the percent of the radionuclide's SLC reporting level (Table 2.2-A). All maximum percent of reporting level values were well below the 100% action level.

The highest value reached during 2010 was 1.97% for H-3 in a drinking water sample collected at location 066.

Changes in sample location, analytical technique, and presentation of results must be considered when reviewing for trends. Calculation of the annual mean concentrations has been performed differently over the history of the REMP. During 1979-1986, all net results (sample minus background), positive and negative, were included in the calculation of the mean. Only positive net activity results were used to calculate the mean for the other years. A change in gamma spectroscopy analysis systems in 1987 ended a period when many measurements yielded detectable low-level activity for both indicator and control location samples. It is thought that the method the previous system used to estimate net activity may have been vulnerable to false-positive results.

Data presented in Sections 3.1 - 3.8 support the conclusion that there were no significant increases in radionuclides in the environment around ONS due to station operations in 2010.

Section 3 - Page 1

3.1 AIRBORNE RADIOIODINE AND PARTICULATES In 2010, 318 radioiodine and particulate samples were analyzed, 265 from five indicator locations and 53 from the control location. Particulate samples were analyzed weekly for gamma and gross beta. Radioiodine samples received a weekly gamma analysis.

There was no detectable I-131 in air samples in 2010. Table 3.1-A gives the highest indicator location annual mean and control location annual mean for I-131 since the preoperational period.

The table shows similar concentrations for both the indicator and control locations and the activities decreasing from early in the operational history of the plant. No I-131 has been detected since 1994.

Cs-137 was not detected in air radioiodine samples in 2010. Cs-137 has been detected in cartridges in previous years. A study performed in 1990 determined Cs-137 to be an active constituent of the charcoal. A similar study was performed in 2001 again yielding this conclusion.

There were no detectable gamma emitting radionuclides detected in air particulate samples in 2010. No gamma emitting particulates have been detected in indicator location samples since the change in gamma spectroscopy analysis systems in 1987.

Beta analysis of particulate filters was initiated in March of 1996 and became required by Selected Licensee Commitments in 1998. Gross beta analysis was performed on particulate filters during the preoperational and early operational history of the plant but had not been required since 1984. Figure 3.1 summarizes gross beta results for the indicator location with the highest annual mean and the control location samples. Both the indicator and control location results are similar in concentration and are near the lower range of preoperational gross beta results.

K-40 and Be-7 are the naturally occurring radionuclides that were observed in air samples.

Section 3 - Page 2

Table 3.1-A Mean Concentration of Air Radioiodine (I-131)

Year Indicator Location (pCi/m3) Control Location (pCi/m3)

Preoperational 1969-1972 0.00E0 0.00E0 Feb. 1973 - June 1973 0.00E0 0.00E0 July 1973 - Dec. 1973 0.00E0 0.00E0 Jan. 1974 - June 1974 0.00E0 0.00E0 July 1974 - Dec. 1974 2.60E-2 8.00E-3 Jan. 1975 - June 1975 8.65E-2 3.12E-2 July 1975 - Dec. 1975 1.13E-2 9.52E-3 1976 2.76E-2 2.18E-2 1977 3.60E-2 3.60E-2 1978 2.19E-1 1.15E-1 1979 7.54E-3 4.75E-4 1980 3.07E-3 9.67E-4 1981 6.31E-3 5.39E-4 1982 2.87E-3 8.10E-4 1983 1.48E-3 3.05E-4 1984 8.11E-4 -2.30E-5 1985 7.71E-4 4.54E-4 1986 5.02E-3 7.86E-3 1987 4.29E-3 5.19E-3 1988 0.00E0 0.00E0 1989 4.99E-4 0.00E0 1990 0.00E0 0.00E0 1991 0.00E0 0.00E0 1992 0.00E0 0.00E0 1993 0.00E0 0.00E0 1994 1.03E-2 0.00E0 1995 0.00E0 0.00E0 1996 0.00E0 0.00E0 1997 0.00E0 0.00E0 1998 0.00E0 0.00E0 1999 0.00E0 0.00E0 2000 0.00E0 0.00E0 2001 0.00E0 0.00E0 2002 0.00E0 0.00E0 2003 0.00E0 0.00E0 2004 0.00E0 0.00E0 2005 0.00E0 0.00E0 2006 0.00E0 0.00E0 2007 0.00E0 0.00E0 2008 0.00E0 0.00E0 2009 0.00E0 0.00E0 2010 0.00E0 0.00E0 0.00E0 = no detectable measurements 1979 - 1986 mean based on all net activity results Section 3 - Page 3

Figure 3.1 pCi/m3 ConcentrationofGrossBetainAirParticulate 4.500E2 4.000E2 3.500E2 3.000E2 2.500E2 2.000E2 1.500E2 1.000E2 5.000E3 0.000E+0 1996 1998 2000 2002 2004 2006 2008 2010 IndicatorLocation ControlLocation Pre-operational sample results ranged from 0.04 to1.46 pCi/m3 There is no reporting level for gross beta in air particulate Table 3.1-B Mean Concentration of Gross Beta in Air Particulate Monitoring Period Indicator Location (pCi/m3) Control Location (pCi/m3) 1996 3.87E-2 3.69E-2 1997 2.87E-2 2.92E-2 1998 2.47E-2 1.56E-2 1999 2.85E-2 2.23E-2 2000 2.38E-2 1.85E-2 2001 2.05E-2 1.94E-2 2002 2.01E-2 1.84E-2 2003 1.86E-2 1.82E-2 2004 1.92E-2 1.90E-2 2005 1.95E-2 1.91E-2 2006 2.09E-2 2.00E-2 2007 2.31E-2 2.13E-2 2008 2.08E-2 2.04E-2 2009 1.82E-2 1.80E-2 Average (2000 - 2009) 2.05E-2 1.92E-2 2010 2.02E-2 2.04E-2 Section 3 - Page 4

3.2 DRINKING WATER Gross beta analysis and gamma spectroscopy were performed on 39 monthly drinking water samples. These samples were composited to form 12 quarterly period samples for Tritium analysis. Two indicator locations and a control location were sampled; however, only one of the indicator locations is downstream of the effluent release point.

Table 3.2 lists the highest indicator location annual mean and control location annual mean for gross beta results since the preoperational period. The indicator location had an average concentration of 1.10 pCi/liter in 2010, and the control location had a concentration of 0.97 pCi/liter. The 2009 indicator mean was 1.37 pCi/liter. The table shows that 2010 gross beta levels in drinking water are lower than preoperational concentrations. The dose for consumption of water was less than one mrem per year, historically and for 2010; therefore low-level iodine analysis is not required.

Tritium was detected in four of the twelve composite samples during 2010. The 2010 mean indicator location 066 concentration was 308 pCi/liter, which is 1.54% of the reporting level.

Table 3.2 and Figure 3.2 show the highest indicator and control location annual means for Tritium since analysis was initiated early in the operational period. Tritium concentrations have decreased at both the indicator and control locations. The closure of the Clemson water plant in 1989 is one reason for the decrease shown in the table and graph. The Clemson site was typically the high mean location when the plant was in operation.

There were no gamma emitting radionuclides identified in drinking water samples in 2010.

Gamma spectroscopy analysis has not detected any activity in the water supplies since 1988.

K-40 is the naturally occurring radionuclide that was observed in drinking water samples.

Figure 3.2 Current reporting level implemented 1984 pCi/liter ConcentrationofTritiuminDrinkingWater 5000 4500 4000 3500 3000 2500 2000 1500 1000 500 0

1974 1976 1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009 IndicatorLocation ControlLocation 20%ReportingLevel Section 3 - Page 5

Table 3.2 Mean Concentrations of Radionuclides in Drinking Water Gross Beta (pCi/l) Tritium (pCi/l)

Year Indicator Control Indicator Control Location Location Location Location Preoperational ending Jan. 1971 3.03 5.90 Analysis not required Preoperational ending Jan. 1973 3.58 4.94 Analysis not required Feb. 1973 - June 1973 Qualitative results reported Analysis not required June 1973 - Dec. 1973 7.15 21.78 Analysis not required Jan. 1974 - June 1974 3.13 6.98 Analysis not required July 1974 - Dec. 1974 2.24 2.02 525 330 Jan. 1975 - June 1975 1.98 1.59 600 300 July 1975 - Dec. 1975 2.01 1.22 2990 505 1976 2.38 2.00 2196 224 1977 2.70 2.30 1200 290 1978 2.56 2.17 1050 333 1979 1.83 1.36 576 235 1980 1.86 1.63 660 200 1981 1.98 1.88 830 127 1982 2.04 1.45 643 153 1983 1.85 1.54 937 220 1984 1.87 1.08 765 145 1985 2.14 1.16 856 210 1986 1.91 1.04 1240 503 1987 2.00 1.20 815 680 1988 2.00 1.40 1570 0.00 1989 2.30 1.80 1350 559 1990 3.00 2.70 0.00 0.00 1991 1.80 1.40 558 0.00 1992 3.20 1.60 0.00 0.00 1993 2.10 1.90 0.00 0.00 1994 1.90 2.10 0.00 0.00 1995 5.10 2.90 248 0.00 1996 2.07 1.77 214 0.00 1997 2.52 2.23 194 0.00 1998 2.48 1.70 0.00 0.00 1999 1.73 1.49 185 0.00 2000 2.07 1.68 251 0.00 2001 1.75 1.29 390 0.00 2002 1.61 1.21 338 0.00 2003 1.51 1.05 266 0.00 2004 1.58 1.25 225 0.00 2005 1.28 1.37 377 0.00 2006 1.54 1.75 340 0.00 2007 1.58 1.08 402 0.00 2008 1.82 1.25 372 0.00 2009 1.37 1.19 415 0.00 2010 1.10 0.97 308 0.00 0.00 = no detectable measurements 1989 - Clemson water plant closes; nearest downstream plant is Anderson.

1979 - 1986 mean based on all net activity results Section 3 - Page 6

3.3 SURFACE WATER Gamma spectroscopy was performed on 26 monthly surface water samples. These samples were composited to form eight quarterly samples for Tritium analysis. One indicator and one control location were sampled. The indicator location is near the liquid effluent release point.

Tritium was detected in the four indicator location samples. The 2010 average concentration was 12,313 pCi/liter. The individual samples ranged from 2,070 pCi/liter to 20,700 pCi/liter.

The 2009 mean concentration was 4,678 pCi/liter. Tritium was not detected in any control surface water samples.

The increase in the average Tritium concentration in 2010 resulted from liquid effluent releases.

Refueling and forced outages contributed to higher volumes of water requiring processing and release (reference 6.25).

Figure 3.3 shows the indicator and control annual means for Tritium since the preoperational period. Table 3.3 lists the indicator annual means. Tritium in the indicator location was elevated during an extended drought from 1998 through 2002.

The average tritium concentration decreased in 2003 with increased rainfall. Extreme drought conditions existed through much of 2008 and continued until mid-2009 (reference 6.16).

Drought conditions could impact surface water tritium concentrations.

Gamma spectroscopy analysis did not detect any station related activity during 2010. In 1999, gamma spectroscopy analysis detected Co-58 in one indicator sample at 27.3 pCi/liter.

Gamma spectroscopy analysis has not detected any other activity in surface water samples since 1992. Table 3.3 summarizes the indicator annual means of radionuclides detected since the change in the gamma spectroscopy analysis system in 1987. Visual inspection of the gamma spectroscopy tabular data covering the early operational period through 2010 did not reveal any increasing trends.

K-40 and Be-7 are the naturally occurring radionuclide observed in surface water samples in 2010.

Section 3 - Page 7

Figure 3.3 pCi/liter ConcentrationofTritiuminSurfaceWater 60000 50000 40000 30000 20000 10000 0

1969 1972 1975 1977 1980 1983 1986 1989 1992 1995 1998 2001 2004 2007 2010 IndicatorLocation ControlLocation There is no reporting level for Tritium in surface water Section 3 - Page 8

Table 3.3 Mean Concentrations of Radionuclides in Surface Water Year Co-58 (pCi/l) Co-60 (pCi/l) Nb-95 (pCi/l) Cs-137 (pCi/l) H-3 pCi/l)

Preoperational 1969 Qualitative results reported 4.86E2 Preoperational 1970 5.94E2 Preoperational 1971 4.01E2 Preoperational 1972 3.62E2 1973 0.00E0 1974 0.00E0 1.32E1 0.00E0 1.60E1 1.99E3 Jan. 1975 - June 1975 0.00E0 0.00E0 0.00E0 0.00E0 1.56E4 July 1975 - Dec. 1975 0.00E0 1.34E1 0.00E0 0.00E0 5.52E4 1976 1.08E2 3.30E1 0.00E0 3.50E1 2.95E4 1977 2.60E1 1.80E1 0.00E0 3.10E1 2.90E3 1978 2.96E2 0.00E0 0.00E0 2.22E1 8.00E2 1979 1.33E0 2.60E0 1.78E0 2.82E0 4.37E3 1980 1.56E0 2.30E0 1.22E0 5.40E0 4.93E3 1981 1.10E0 6.10E-1 1.70E0 3.90E0 7.21E3 1982 6.14E-1 1.99E0 2.29E0 4.85E0 6.13E3 1983 6.99E-1 3.02E0 3.91E-1 6.83E-1 8.40E3 1984 9.40E-1 6.30E-1 7.90E-1 4.83E-1 9.90E3 1985 2.15E-1 6.27E-1 4.95E-1 9.90E-1 1.05E4 1986 3.28E0 1.23E0 1.14E0 3.07E-1 1.26E4 1987 5.10E1 3.40E0 4.00E0 0.00E0 7.08E3 1988 6.20E0 5.00E0 2.50E0 3.50E0 1.10E4 1989 5.30E0 3.00E0 0.00E0 3.40E0 1.02E4 1990 1.70E0 1.60E0 0.00E0 0.00E0 1.03E4 1991 5.40E0 0.00E0 0.00E0 0.00E0 5.76E3 1992 2.50E0 0.00E0 0.00E0 0.00E0 6.22E3 1993 0.00E0 0.00E0 0.00E0 0.00E0 8.62E3 1994 0.00E0 0.00E0 0.00E0 0.00E0 5.75E3 1995 0.00E0 0.00E0 0.00E0 0.00E0 6.65E3 1996 0.00E0 0.00E0 0.00E0 0.00E0 4.54E3 1997 0.00E0 0.00E0 0.00E0 0.00E0 5.50E3 1998 0.00E0 0.00E0 0.00E0 0.00E0 3.35E3 1999 2.73E1 0.00E0 0.00E0 0.00E0 1.13E4 2000 0.00E0 0.00E0 0.00E0 0.00E0 1.48E4 2001 0.00E0 0.00E0 0.00E0 0.00E0 7.43E3 2002 0.00E0 0.00E0 0.00E0 0.00E0 1.00E4 2003 0.00E0 0.00E0 0.00E0 0.00E0 4.77E3 2004 0.00E0 0.00E0 0.00E0 0.00E0 3.86E3 2005 0.00E0 0.00E0 0.00E0 0.00E0 5.15E3 2006 0.00E0 0.00E0 0.00E0 0.00E0 6.72E3 2007 0.00E0 0.00E0 0.00E0 0.00E0 9.91E3 2008 0.00E0 0.00E0 0.00E0 0.00E0 9.43E3 2009 0.00E0 0.00E0 0.00E0 0.00E0 4.68E3 2010 0.00E0 0.00E0 0.00E0 0.00E0 1.23E4 0.00E0 = no detectable measurements 1979-1986 mean based on all net activity results Section 3 - Page 9

3.4 MILK Gamma spectroscopy and low level iodine analysis was performed on 26 milk samples collected in 2010. One control location was sampled. No indicator dairies were identified by the 2010 land use census.

There were no gamma emitting radionuclides identified in milk samples in 2010. Cs-137 is the only radionuclide, other than naturally occurring, reported in milk samples since 1988. Cs-137 in milk is not unusual. It is a constituent of nuclear weapons test fallout and has been observed in samples from indicator and control locations in previous years.

Table 3.4 lists the highest indicator location annual mean and control location annual mean for Cs-137 since the preoperational period.

The table shows similar concentrations for both indicator and control locations.

K-40 is a naturally occurring radionuclide observed in milk samples in 2010.

Section 3 - Page 10

Table 3.4 Mean Concentration of Radionuclides in Milk Year Cs-137 Indicator (pCi/l) Cs-137 Control (pCi/l)

Preoperational 1.57E1 1.46E1 Feb. 1973 - June 1973 Qualitative results reported Qualitative results reported July 1973 - Dec. 1973 5.80E0 Jan. 1974 - June 1974 5.30E0 0.00E0 July 1974 - Dec. 1974 1.11E1 0.00E0 Jan. 1975 - June 1975 1.51E1 9.45E0 July 1975 - Dec. 1975 0.00E0 0.00E0 1976 1.80E1 7.47E0 1977 0.00E0 0.00E0 1978 1.33E1 1.33E1 1979 7.25E0 2.52E0 1980 3.58E0 2.63E0 1981 5.52E0 5.51E0 1982 2.71E0 3.25E0 1983 5.04E0 -4.27E-1 1984 2.30E0 2.58E0 1985 2.38E0 1.31E0 1986 2.92E0 2.97E0 1987 4.90E0 4.90E0 1988 3.90E0 3.20E0 1989 4.70E0 2.90E0 1990 6.40E0 0.00E0 1991 5.00E0 0.00E0 1992 6.60E0 0.00E0 1993 0.00E0 0.00E0 1994 0.00E0 1.80E0 1995 2.30E0 2.00E0 1996 0.00E0 4.10E0 1997 0.00E0 0.00E0 1998 0.00E0 0.00E0 1999 0.00E0 0.00E0 2000 0.00E0 0.00E0 2001 0.00E0 0.00E0 2002 0.00E0 0.00E0 2003 0.00E0 0.00E0 2004 0.00E0 0.00E0 2005 0.00E0 0.00E0 2006 NO INDICATOR LOCATION 0.00E0 2007 NO INDICATOR LOCATION 0.00E0 2008 NO INDICATOR LOCATION 0.00E0 2009 NO INDICATOR LOCATION 0.00E0 2010 NO INDICATOR LOCATION 0.00E0 0.00E0 = no detectable measurements 1979 - 1986 mean based on all net activity results The Oconee milk program was updated to align with NUREG-1301 during 2005 and documented in PIP O-04-01179. Location 071 was designated as the new control site effective with the 7/12/2005 sampling. No indicator dairies were identified by the 2010 land use census.

Section 3 - Page 11

3.5 BROADLEAF VEGETATION Gamma spectroscopy was performed on 48 broadleaf vegetation samples during 2010. Three indicator locations and one control location were sampled. There were no gamma emitting radionuclides identified in vegetation samples in 2010.

Cs-137 is the only radionuclide, other than naturally occurring, reported in vegetation samples since the change in gamma spectroscopy analysis systems in 1987. Table 3.5 shows historical concentrations of Cs-137.

It is not unusual for Cs-137 to be present in vegetation. It is a constituent of nuclear weapons test fallout and has been observed in samples from indicator and control locations in previous years. Table 3.5 lists the highest indicator location annual mean and control location annual mean for Cs-137 since early in the stations operational history. Visual inspection of the tabular data did not reveal any increasing trends.

K-40 and Be-7 are naturally occurring radionuclides that were observed in broadleaf vegetation samples in 2010.

Figure 3.5 pCi/kg ConcentrationofCs137inBroadleafVegetation 2500 2000 1500 1000 500 0

1974 1976 1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009 IndicatorLocation ControlLocation ReportingLevel Section 3 - Page 12

Table 3.5 Mean Concentration of Radionuclides in Vegetation Year Cs-137 Indicator (pCi/kg) Cs-137 Control (pCi/kg)

July 1974 - Dec. 1974 1.54E3 0.00E0 Jan. 1975 - June 1975 1.55E3 1.59E3 July 1975 - Dec. 1975 0.00E0 0.00E0 1976 0.00E0 0.00E0 1977 0.00E0 7.90E2 1978 1.19E2 8.19E1 1979 5.04E1 2.96E1 1980 2.80E1 1.55E1 1981 2.99E1 2.60E1 1982 2.42E1 2.62E1 1983 7.44E0 5.35E-1 1984 1.37E1 4.74E2 1985 1.62E1 2.20E2 1986 3.28E1 3.12E2 1987 2.70E1 4.20E1 1988 2.40E1 7.50E1 1989 0.00E0 1.08E2 1990 2.73E2 1.74E2 1991 2.20E1 1.45E2 1992 0.00E0 1.46E2 1993 0.00E0 1.49E2 1994 0.00E0 1.06E2 1995 4.30E1 1.58E2 1996 3.79E1 1.83E2 1997 4.73E1 1.35E2 1998 7.28E1 1.61E2 1999 1.34E2 0.00E0 2000 1.06E2 0.00E0 2001 3.19E1 0.00E0 2002 8.44E1 0.00E0 2003 0.00E0 0.00E0 2004 0.00E0 5.96E1 2005 4.51E1 4.11E1 2006 1.77E1 0.00E0 2007 0.00E0 0.00E0 2008 0.00E0 0.00E0 2009 0.00E0 0.00E0 2010 0.00E0 0.00E0 0.00E0 = no detectable measurements Only qualitative results reported prior to 1974 Control location changed to 073 in 1984 Control location 081 added in 1998 Control location 073 was removed in 1999 1979 - 1986 mean based on all net activity results Section 3 - Page 13

3.6 FISH In 2010, gamma spectroscopy was performed on 12 fish samples. Two downstream indicator and one control location were sampled. Cs-137 was identified in six of the eight indicator location samples. Cs-137 was detected in one of the four control location samples at a mean concentration of 24.1 pCi/kg.

The highest average indicator concentration for Cs-137 was 26.9 pCi/kg (1.35% of reporting level). The highest individual indicator sample concentration for Cs-137 was 35.3 pCi/kg (1.77% of reporting level).

Figures 3.6-1 and 3.6-2 are graphs displaying the annual means for Cs-137 and Cs-134.

Historically, both are contributors to the calculated dose from liquid effluents from ingestion of fish. Radioactivity concentrations in downstream fish samples are higher than those reported in preoperational fish samples, however, concentrations in fish have decreased over time with decreases in radioactive material releases from the plant.

One factor affecting the trend analysis is a change in sampling locations. In 1984, a second downstream fish location was added. Location 063 is closer to the liquid effluent discharge point and has been the highest mean indicator since it was added.

K-40 was observed in fish samples in addition to the radionuclides discussed above.

Table 3.6 lists the highest indicator location annual means since the preoperational period for radionuclides detected in 2010.

Also included in the table are radionuclides that have been identified in this media since the change in analysis systems in 1987. Comparison of data to previous years does not indicate any increases in concentrations.

Section 3 - Page 14

Figure 3.6-1 pCi/kg ConcentrationofCs137inFish 2500 2000 1500 1000 500 0

1970 1974 1976 1978 1981 1984 1987 1990 1993 1996 1999 2002 2005 2008 IndicatorLocation ControlLocation ReportingLevel Figure 3.6-2 pCi/kg ConcentrationofCs134inFish 700 600 500 400 300 200 100 0

1970 1974 1976 1978 1981 1984 1987 1990 1993 1996 1999 2002 2005 2008 IndicatorLocation ControlLocation 50%ReportingLevel Current reporting levels implemented 1984 Section 3 - Page 15

Table 3.6 Mean Concentrations of Radionuclides in Fish Year Co-58 (pCi/kg) Co-60 (pCi/kg) Cs-134 (pCi/kg) Cs-137 (pCi/kg)

Preop ending Jan.1971 0.00E0 0.00E0 0.00E0 1.46E2 Preop ending Jan.1973 0.00E0 0.00E0 0.00E0 1.66E2 Feb. 1973 - June 1973 Qualitative results reported-no significant measurements above background July 1973 - Dec. 1973 0.00E0 0.00E0 0.00E0 1.89E2 Jan. 1974 - June 1974 0.00E0 0.00E0 0.00E0 2.47E1 July 1974 - Dec. 1974 0.00E0 0.00E0 0.00E0 4.85E1 Jan. 1975 - June 1975 0.00E0 0.00E0 3.81E1 1.05E2 July 1975 - Dec. 1975 8.50E1 0.00E0 7.00E1 3.13E2 1976 5.70E1 1.14E2 7.73E1 1.66E2 1977 0.00E0 0.00E0 1.80E2 3.60E2 1978 3.27E2 0.00E0 3.31E2 0.00E0 1979 1.91E0 1.56E1 9.26E1 3.88E2 1980 1.45E1 1.90E1 1.10E2 3.99E2 1981 2.25E1 1.49E1 1.40E2 4.51E2 1982 9.83E-1 8.03E0 1.17E2 2.94E2 1983 3.35E1 4.53E0 1.24E2 3.32E2 1984 1.21E2 6.23E1 3.87E2 1.04E3 1985 1.62E1 1.10E1 7.93E1 2.85E2 1986 9.56E1 2.59E1 2.57E2 7.36E2 1987 1.63E2 6.30E1 9.80E1 3.93E2 1988 9.60E1 0.00E0 7.20E1 2.60E2 1989 4.30E1 1.50E1 8.60E1 3.36E2 1990 1.50E1 0.00E0 4.80E1 1.19E2 1991 4.59E1 0.00E0 1.25E2 1.94E2 1992 6.10E1 0.00E0 4.80E1 1.36E2 1993 0.00E0 0.00E0 2.10E1 1.10E2 1994 0.00E0 0.00E0 2.80E1 1.05E2 1995 0.00E0 0.00E0 3.10E1 9.20E1 1996 0.00E0 0.00E0 4.49E1 1.25E2 1997 0.00E0 0.00E0 0.00E0 1.18E2 1998 0.00E0 0.00E0 0.00E0 5.79E1 1999 0.00E0 0.00E0 0.00E0 1.04E2 2000 0.00E0 0.00E0 0.00E0 7.54E1 2001 1.72E1 0.00E0 0.00E0 9.92E1 2002 0.00E0 0.00E0 0.00E0 9.37E1 2003 5.02E1 0.00E0 0.00E0 6.04E1 2004 0.00E0 0.00E0 0.00E0 5.29E1 2005 0.00E0 0.00E0 0.00E0 5.14E1 2006 0.00E0 0.00E0 0.00E0 5.58E1 2007 0.00E0 0.00E0 0.00E0 4.10E1 2008 0.00E0 0.00E0 0.00E0 3.13E1 2009 9.01E0 0.00E0 0.00E0 2.68E1 2010 0.00E0 0.00E0 0.00E0 2.69E1 0.00E0 = no detectable measurements 1979 - 1986 mean based on all net activity results Section 3 - Page 16

3.7 SHORELINE SEDIMENT Gamma spectroscopy was performed on six sediment samples. Two downstream indicator locations and one control location were sampled. Four samples were taken from indicator locations and two from the control location.

Cs-137 was identified in two of the four indicator location samples. Cs-137 was identified in one of the two control location samples. The highest 2010 individual sample Cs-137 concentration was 198 pCi/kg. The highest 2009 individual sample Cs-137 concentration was 69.7 pCi/kg. Table 3.7 lists the highest indicator location annual means since shoreline sediment was initiated in 1984. Included in the table are radionuclides that have been identified in this media since the change in analysis systems in 1987.

Visual inspection of the tabular data did not reveal any trends. Figure 3.7-1 is a graph of the Cs-137 annual means. Figure 3.7-2 is a graph of the Co-60 annual means. Historically, both are contributors to the calculated dose from liquid effluents from shoreline sediment. No trends are apparent.

K-40 and Be-7 are naturally occurring radionuclides observed in shoreline sediment samples in 2010.

Section 3 - Page 17

Figure 3.7-1 pCi/kg ConcentrationofCs137inShorelineSediment 1000 900 800 700 600 500 400 300 200 100 0

1984 1987 1990 1993 1996 1999 2002 2005 2008 IndicatorLocation063 IndicatorLocation067 ControlLocation068 Figure 3.7-2 pCi/kg ConcentrationofCo60inShorelineSediment 1000 900 800 700 600 500 400 300 200 100 0

1984 1987 1990 1993 1996 1999 2002 2005 2008 IndicatorLocation063 IndicatorLocation067 ControlLocation068 There are no reporting levels for shoreline sediment Section 3 - Page 18

Table 3.7 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/kg)

Year Mn-54 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ag-110m Sb-125 1984 1.10E1 1.09E1 1.19E1 0.00E0 7.77E1 5.16E1 0.00E0 0.00E0 1985 9.39E0 1.27E0 4.79E0 0.00E0 7.63E1 9.47E1 0.00E0 0.00E0 1986 2.24E1 1.62E1 2.50E1 0.00E0 1.41E2 7.12E2 0.00E0 0.00E0 1987 5.40E1 4.70E2 5.07E2 0.00E0 1.01E2 6.22E2 3.46E2 0.00E0 1988 3.30E1 1.20E2 1.87E2 6.70E1 6.60E1 7.59E2 1.62E2 3.67E2 1989 2.30E1 1.24E2 1.96E2 0.00E0 5.40E1 8.48E2 5.50E1 1.86E2 1990 3.40E1 8.00E1 2.59E2 0.00E0 4.50E1 5.36E2 1.71E2 9.00E1 1991 3.26E1 5.60E1 8.57E1 0.00E0 6.91E1 1.24E2 1.10E2 1.78E2 1992 8.79E1 1.79E2 1.12E2 0.00E0 5.60E1 3.31E2 1.69E2 2.08E2 1993 8.20E1 8.20E1 6.50E1 0.00E0 3.20E1 1.36E2 5.63E1 1.11E2 1994 5.30E1 7.00E1 1.49E2 0.00E0 6.70E1 2.38E2 1.04E2 1.29E2 1995 1.43E2 3.90E1 2.40E1 0.00E0 1.10E1 5.20E1 0.00E0 0.00E0 1996 0.00E0 5.10E1 0.00E0 0.00E0 1.98E1 1.19E2 0.00E0 0.00E0 1997 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1.06E2 0.00E0 0.00E0 1998 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1.01E2 0.00E0 0.00E0 1999 6.96E1 0.00E0 0.00E0 0.00E0 0.00E0 7.38E1 0.00E0 0.00E0 2000 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 8.54E1 0.00E0 0.00E0 2001 0.00E0 2.10E1 0.00E0 0.00E0 0.00E0 1.20E2 0.00E0 0.00E0 2002 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 6.96E1 0.00E0 0.00E0 2003 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1.93E2 0.00E0 0.00E0 2004 8.54E1 0.00E0 0.00E0 0.00E0 0.00E0 9.56E1 0.00E0 0.00E0 2005 2.00E2 0.00E0 0.00E0 0.00E0 0.00E0 6.53E1 0.00E0 0.00E0 2006 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 5.01E1 0.00E0 0.00E0 2007 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 2.97E2 0.00E0 0.00E0 2008 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1.78E2 0.00E0 0.00E0 2009 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 6.97E1 0.00E0 0.00E0 2010 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 1.15E2 0.00E0 0.00E0 0.00E0 = no detectable measurements 1984-1986 mean based on all net activity results Section 3 - Page 19

3.8 DIRECT GAMMA RADIATION 3.8.1 ENVIRONMENTAL TLD In 2010, 166 Thermoluminescent Dosimeters (TLD) were analyzed, 159 at indicator locations, 7 at the two control locations. TLDs are collected and analyzed quarterly.

The highest annual mean exposure for an indicator location was 113 milliroentgen.

This TLD is located at indicator location 042, 4.93 miles from the station. The annual mean exposure for the control locations was 103 milliroentgen.

Figure 3.8-1 and Table 3.8-A show TLD inner ring (site boundary), outer ring (4-5 miles), and control location annual averages in milliroentgen per year. Data is provided from 1984 when TLD locations were added and arranged in an inner ring and outer ring configuration. Preoperational data is also provided in the table. As shown in the graph, inner and outer ring averages historically compare closely, with control data somewhat higher. Inner and outer ring averages comprise a number of data points with control averages representing only two locations. The control locations have historically been higher than indicator locations. This is most likely an artifact of the underlying geologic structures at the control locations. The control locations are 9.39 miles WSW and 9.33 miles SE, well beyond the influence of the plant.

Figures 3.8-2 and 3.8-3 show the TLD mean for each inner and outer ring TLD location from 1984 through 2010. Data prior to 1984 was not included due to programmatic changes implemented in 1984.

The calculated total body dose (from gaseous effluents) for 2010 was 8.78E-2 mrem, which is 0.1% of the average inner ring TLD values. Therefore, it can be concluded that discharges from the plant had very little impact upon the measured TLD values.

A TLD intercomparison program is conducted as part of the quality assurance program. Results of this program are included in section 5.10.

3.8.2 ISFSI The Oconee Independent Spent Fuel Storage Installation (ISFSI) is a fenced, secured area constructed to provide dry storage for spent nuclear fuel. The principal components of the ISFSI are concrete horizontal storage modules that hold stainless steel dry storage canisters containing irradiated fuel assemblies.

The ISFSI is located in the southwest end of the plant, approximately 400 meters from Unit 2 reactor building. The radiological environmental monitoring program for Oconee also serves as the operational program for the ISFSI. No liquid or airborne effluents are anticipated from the passive storage provided by the ISFSI. Therefore any dose to offsite points would be from direct and scattered gamma radiation.

Several environmental TLD locations are presently located at the Oconee site Section 3 - Page 20

boundary fence near the ISFSI. The closest of these is 0.3 miles from the ISFSI, well within the 1-mile exclusion boundary. In addition, dose rates at the ISFSI restricted area fence are monitored with TLDs and used in monitoring occupational exposure controls.

Oconee began storage of spent fuel at the ISFSI in 1990. Seven storage modules were loaded with spent fuel in2010.

The maximum measurement from TLDs at the Independent Spent Fuel Storage Installation ISFSI) was 701 milliroentgen per standard quarter. This is consistent with previous measurements.

An upward trend in environmental TLD data was identified in 2009 (reference 6.24).

Additions of modules to the ISFSI are a possible cause. An evaluation of the increase is on-going. Additional environmental TLDs have been placed in the field to assist with this evaluation.

Figure 3.8-1 mR/year DirectGammaRadiation(TLD)Results 250 200 150 100 50 0

1984 1987 1990 1993 1996 1999 2002 2005 2008 InnerRing OuterRing Control There is no reporting level for Direct Radiation (TLD)

Section 3 - Page 21

Table 3.8-A Direct Gamma Radiation (TLD) Results Year Inner Ring Average Outer Ring Average Control (mR/yr) (mR/yr) (mR/yr)

Preoperational 113.1 123.9 148.9 1984 79.4 83.8 110.3 1985 116.9 121.5 156.6 1986 104.2 106.0 150.9 1987 84.3 88.8 104.3 1988 72.3 78.6 112.6 1989 63.7 61.7 89.4 1990 52.2 50.7 70.1 1991 61.2 65.0 88.0 1992 76.2 73.2 92.0 1993 74.8 80.6 93.0 1994 86.8 94.7 112.0 1995 93.6 101.7 132.0 1996 68.5 78.3 101.0 1997 72.8 83.8 104.5 1998 71.7 80.8 118.0 1999 74.5 82.5 104 2000 76.2 84.5 105.6 2001 73.6 82.4 102.2 2002 76.6 85.3 108.0 2003 77.4 86.6 108.8 2004 80.1 87.5 110.4 2005 79.3 89.0 104.7 2006 82.0 90.2 108.8 2007 81.0 90.0 108 2008 84.6 95.0 111 2009 83.7 93.0 110 Average (2000 - 2009) 79.5 88.5 108 2010 83.6 93.2 102.8 Section 3 - Page 22

Figure 3.8-2 mR/year OconeeInnerRing(TLD)Results 220 200 180 160 140 120 100 80 60 40 20 N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW WNW NW NNW (020) (021) (022) (023) (024) (025) (026) (027) (028) (029) (030) (031) (076) (032) (033) (034) (035) 2010Mean 1984 2009High/Low/Mean Table 3.8-B Direct Gamma Radiation (TLD) Results Inner Ring Sector (Location) 1984 - 2009 Mean 1984 - 2009 Low 1984 - 2009 High 2010 Mean N (020) 8.32E+01 6.71E+01 1.36E+02 8.10E+01 NNE (021) 6.06E+01 3.72E+01 9.75E+01 6.10E+01 NE (022) 8.36E+01 5.44E+01 1.15E+02 9.60E+01 ENE (023) 9.46E+01 7.08E+01 1.26E+02 9.40E+01 E (024) 9.83E+01 8.09E+01 1.48E+02 1.00E+02 ESE (025) 7.28E+01 4.67E+01 1.12E+02 7.60E+01 SE (026) 7.04E+01 4.59E+01 1.21E+02 7.30E+01 SSE (027) 7.10E+01 4.63E+01 1.04E+02 8.30E+01 S (028) 6.84E+01 4.87E+01 1.06E+02 7.30E+01 SSW (029) 6.83E+01 4.94E+01 1.07E+02 6.80E+01 SW (030) 7.07E+01 5.05E+01 1.13E+02 7.50E+01 WSW (031) 6.97E+01 5.04E+01 1.13E+02 7.10E+01 W (076) 8.34E+01 7.19E+01 9.40E+01 9.40E+01 WNW (032) 9.61E+01 6.97E+01 1.46E+02 9.90E+01 WNW (033) 8.68E+01 6.77E+01 1.45E+02 8.20E+01 NW (034) 1.06E+02 8.21E+01 1.89E+02 9.50E+01 NNW (035) 9.20E+01 6.55E+01 1.28E+02 9.80E+01 Section 3 - Page 23

Figure 3.8-3 mR/year OconeeOuterRing(TLD)Results 220 200 180 160 140 120 100 80 60 40 20 N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW (036) (037) (038) (039) (040) (041) (042) (043) (044) (045) (046) (047) (048) (049) (050) (051) 2010Mean 1984 2009High/Low/Mean Table 3.8-C Direct Gamma Radiation (TLD) Results Outer Ring Sector (Location) 1984 - 2009 Mean 1984 - 2009 Low 1984 - 2009 High 2010 Mean N (036) 9.90E+01 6.72E+01 1.39E+02 1.10E+02 NNE (037) 8.17E+01 5.21E+01 1.22E+02 9.00E+01 NE (038) 9.59E+01 6.71E+01 1.43E+02 8.90E+01 ENE (039) 9.56E+01 6.14E+01 1.40E+02 1.01E+02 E (040) 9.91E+01 8.05E+01 1.44E+02 1.03E+02 ESE (041) 7.51E+01 5.06E+01 1.19E+02 7.20E+01 SE (042) 1.00E+02 7.13E+01 1.43E+02 1.13E+02 SSE (043) 9.49E+01 6.41E+01 1.45E+02 1.02E+02 S (044) 7.80E+01 5.86E+01 1.29E+02 8.30E+01 SSW (045) 7.30E+01 5.19E+01 1.14E+02 7.10E+01 SW (046) 8.36E+01 4.55E+01 1.19E+02 9.50E+01 WSW (047) 8.26E+01 5.22E+01 1.30E+02 9.70E+01 W (048) 9.91E+01 5.44E+01 1.47E+02 1.10E+02 WNW (049) 8.50E+01 5.33E+01 1.22E+02 1.01E+02 NW (050) 7.37E+01 5.09E+01 1.01E+02 7.30E+01 NNW (051) 7.78E+01 5.00E+01 1.14E+02 8.20E+01 N (036) 9.90E+01 6.72E+01 1.39E+02 1.10E+02 Section 3 - Page 24

3.9 LAND USE CENSUS The Land Use Census was conducted during the growing season (6/6 - 6/7/2010) as required by SLC 16.11.6. Table 3.9 summarizes census results. A map indicating identified locations is shown in Figure 3.9. The nearest residence is located in the NW sector at 1.04 miles. No program changes were required based on the results of the census.

Table 3.9 Oconee 2010 Land Use Census Results Sector Distance Sector Distance (Miles) (Miles)

Nearest Residence 2.98 Nearest Residence 1.96 N Nearest Milk Animal - S Nearest Milk Animal -

Nearest Residence 1.84 Nearest Residence 1.36 NNE Nearest Milk Animal - SSW Nearest Milk Animal -

Nearest Residence 1.20 Nearest Residence 1.31 NE Nearest Milk Animal - SW Nearest Milk Animal -

Nearest Residence 1.34 Nearest Residence 1.77 ENE Nearest Milk Animal - WSW Nearest Milk Animal -

Nearest Residence 1.64 Nearest Residence 1.58 E Nearest Milk Animal - W Nearest Milk Animal -

Nearest Residence 1.57 Nearest Residence 1.35 ESE Nearest Milk Animal - WNW Nearest Milk Animal -

Nearest Residence 1.46 Nearest Residence 1.04 SE Nearest Milk Animal - NW Nearest Milk Animal -

Nearest Residence 1.54 Nearest Residence 1.06 SSE Nearest Milk Animal - NNW Nearest Milk Animal -

- indicates no occurrences within the 5 mile radius

GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.

Section 3 - Page 25

Figure 3.9 Section 3 - Page 26

4.0 EVALUATION OF DOSE 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 2010 ONS REMP samples. The primary purpose of estimating doses based on sample results is to allow comparison to effluent program dose estimates. Doses based on sample results were conservatively calculated in a manner as equivalent as possible to effluent-based dose estimates.

Doses based on REMP sample results were calculated using the methodology and data presented in NRC Regulatory Guide 1.109. Measured radionuclide concentrations, averaged over the entire year for a specific radionuclide, indicator location, and sample type, were used to calculate REMP-based doses, after subtracting the applicable average background concentration (as measured at the corresponding control location). Regulatory Guide 1.109 consumption rates for the maximum exposed individual were used in the calculations. A dose factor of zero was assumed when the guide listed NO DATA as the dose factor for a given radionuclide and organ.

Maximum dose estimates calculated using drinking water, fish and shoreline sediment results are reported in Table 4.1-A. The individual critical population and pathway dose calculations are contained in Table 4.1-B.

No radionuclides were detected in broadleaf vegetation, milk, airborne radioiodine or airborne particulate samples other than naturally-occurring K-40 and Be-7. Dose estimates were not calculated for surface water samples because surface water is not considered a potable drinking water source although surface water tritium concentrations are used in calculating doses from fish. REMP TLD exposure results are discussed in Section 3.8.

The maximum environmental organ dose estimate for any single sample type (excluding TLD results) collected during 2010 was 3.19E-2 mrem to the child liver, total body, thyroid, kidney, lung, and GI-LLI from consuming drinking water.

4.2 ESTIMATED DOSE FROM RELEASES Throughout the year, dose estimates were calculated based on actual 2010 liquid and gaseous effluent release data. Effluent-based dose estimates were calculated using the RETDAS computer program which employs methodology and data presented in NRC Regulatory Guide 1.109. These doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimates. Summaries of RETDAS dose calculations are reported in the Annual Radioactive Effluent Release Report (reference 6.6).

The effluent-based liquid release doses are summations of the dose contributions of the drinking water, fish and shoreline pathways. For iodine, particulate, and tritium exposure the Section 4 - Page 1

effluent-based gaseous release doses are summations of the dose contributors from ground/plane, milk, inhalation and vegetation pathways.

4.3 COMPARISON OF DOSES The liquid environmental and release data doses given in Table 4.1-A agree reasonably well.

The similarity of the doses indicate that the radioactivity levels in the environment do not differ significantly from those expected based on effluent measurements and modeling of the environmental exposure pathways.

There are some differences in how effluent and environmental doses are calculated that affect the comparison. Doses calculated from environmental data are conservative because they are based on a mean that includes only samples with a net positive activity versus a mean that includes all sample results (i.e. zero results are not included in the mean). Also, airborne tritium is not measured in environmental samples but is used to calculate effluent doses.

In addition, Oconee began reporting estimated dose from effluent Carbon 14 (C-14). This change came about with the issuing of Regulatory Guide 1.21, Revision 2, Measuring, Evaluating and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste. A description of this change is found in the 2010 Annual Radiological Effluent Release Report. C-14 is not measured in the environment and therefore, environmental and effluent doses from C-14 cannot be compared directly.

In calculations based on liquid release effluent pathways, fish and drinking water were the predominant dose pathways based on environmental and effluent samples. The maximum total organ dose based on 2010 environmental sample results was 5.44E-2 mrem to the adult liver. The maximum total organ dose of 6.57E-1 mrem for liquid effluent-based estimates was to the adult GI-LLI.

In calculations based on gaseous release pathways, vegetation was the predominant dose pathway for effluent samples. The gaseous effluent dose is due to tritium on broadleaf vegetation. The maximum total organ dose for gaseous effluent estimates was 3.35E-1 mrem to the child bone. No radioactivity was detected from gaseous pathways in environmental samples; therefore, there is no calculated dose.

The doses calculated do not exceed 40CFR190 or 10CFR50 dose commitment limits for members of the public. Doses to members of the public attributable to the operation of ONS are being maintained well within regulatory limits.

Section 4 - Page 2

TABLE 4.1-A Page 1 of 2 OCONEE NUCLEAR STATION 2010 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIQUID RELEASE PATHWAY Environmental Critical Critical Maximum Dose (3)

Organ or Location Age (1) Pathway (2) (mrem)

Effluent Data Skin Environmental Teen Shoreline Sediment 063 (0.80 mi ESE) 2.15E-04 Skin Effluent Teen Shoreline Sediment Discharge Pt. 2.29E-03 Bone Environmental Child Fish 063 (0.80 mi ESE) 6.32E-03 Bone Effluent Child Fish Discharge Pt. 8.86E-02 Liver Environmental Adult Fish 063 (0.80 mi ESE) 5.44E-02 Liver Effluent Adult Fish Discharge Pt. 2.52E-01 T. Body Environmental Adult Fish 063 (0.80 mi ESE) 5.22E-02 T. Body Effluent Adult Fish Discharge Pt. 2.22E-01 Thyroid Environmental Adult Fish 063 (0.80 mi ESE) 4.80E-02 Thyroid Effluent Child Drinking Water 18.9 mi SSE 1.53E-01 Kidney Environmental Adult Fish 063 (0.80 mi ESE) 5.02E-02 Kidney Effluent Child Drinking Water 18.9 mi SSE 1.83E-01 Lung Environmental Adult Fish 063 (0.80 mi ESE) 4.88E-02 Lung Effluent Child Drinking Water 18.9 mi SSE 1.63E-01 GI-LLI Environmental Adult Fish 063 (0.80 mi ESE) 4.82E-02 GI-LLI Effluent Adult Fish Discharge Pt. 6.57E-01 (1) Critical Age is the highest total dose (all pathways) to an age group.

(2) Critial Pathway is the highest individual dose within the identified Critical Age group.

(3) Maximum dose is a summation of the fish, drinking water and shoreline sediment pathways.

Section 4 - Page 3

Page 2 of 2 GASEOUS RELEASE PATHWAY IODINE, PARTICULATE, and TRITIUM Environmental or Critical Critical Maximum Dose (3)

Organ Location Effluent Data Age (1) Pathway (2) (mrem)

Skin Environmental - - - 0.00E+00 Skin Effluent All Ground Plane 1.0 mi. SW 1.16E-05 Bone Environmental - - - 0.00E+00 Bone Effluent Child Vegetation 1.0 mi. SW 3.35E-01 Liver Environmental - - - 0.00E+00 Liver Effluent Child Vegetation 1.0 mi. SW 8.78E-02 T. Body Environmental - - - 0.00E+00 T. Body Effluent Child Vegetation 1.0 mi. SW 8.78E-02 Thyroid Environmental - - - 0.00E+00 Thyroid Effluent Child Vegetation 1.0 mi. SW 9.64E-02 Kidney Environmental - - - 0.00E+00 Kidney Effluent Child Vegetation 1.0 mi. SW 8.78E-02 Lung Environmental - - - 0.00E+00 Lung Effluent Child Vegetation 1.0 mi. SW 8.78E-02 GI-LLI Environmental - - - 0.00E+00 GI-LLI Effluent Child Vegetation 1.0 mi. SW 8.78E-02 (1) Critical Age is the highest total dose (all pathways) to an age group.

(2) Critial Pathway is the highest individual dose within the identified Critical Age group.

(3) Maximum dose is a summation of the ground/plane, inhalation, milk and vegetation pathways.

Section 4 - Page 4

TABLE 4.1-B Maximum Individual Dose for 2010 based on Environmental Measurements (mrem) for Oconee Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 3.13E-02 3.13E-02 3.13E-02 3.13E-02 3.13E-02 3.13E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL 0.00E+00 3.13E-02 3.13E-02 3.13E-02 3.13E-02 3.13E-02 3.13E-02 0.00E+00 Child Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 3.19E-02 3.19E-02 3.19E-02 3.19E-02 3.19E-02 3.19E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 6.32E-03 2.16E-02 1.64E-02 1.55E-02 1.75E-02 1.62E-02 1.56E-02 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 3.84E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.48E-05 TOTAL 6.32E-03 5.35E-02 4.83E-02 4.74E-02 4.94E-02 4.81E-02 4.75E-02 4.48E-05 Teen Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 1.67E-02 1.67E-02 1.67E-02 1.67E-02 1.67E-02 1.67E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 5.02E-03 2.55E-02 2.11E-02 1.88E-02 2.11E-02 1.97E-02 1.89E-02 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 1.84E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.15E-04 TOTAL 5.02E-03 4.22E-02 3.80E-02 3.55E-02 3.78E-02 3.64E-02 3.56E-02 2.15E-04 Adult Airborne 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Drinking Water 0.00E+00 2.36E-02 2.36E-02 2.36E-02 2.36E-02 2.36E-02 2.36E-02 0.00E+00 Milk 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Broadleaf Vegetation 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fish 4.69E-03 3.08E-02 2.86E-02 2.44E-02 2.66E-02 2.52E-02 2.46E-02 0.00E+00 Shoreline Sediment 0.00E+00 0.00E+00 3.29E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.84E-05 TOTAL 4.69E-03 5.44E-02 5.22E-02 4.80E-02 5.02E-02 4.88E-02 4.82E-02 3.84E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 5

Oconee Nuclear Station Dose from Drinking Water Pathway for 2010 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake in one year) = 330 l Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/l) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 066 308 0.00E+00 3.13E-02 3.13E-02 3.13E-02 3.13E-02 3.13E-02 3.13E-02 Dose Commitment (mrem) = 0.00E+00 3.13E-02 3.13E-02 3.13E-02 3.13E-02 3.13E-02 3.13E-02 Section 4 - Page 6

Oconee Nuclear Station Dose from Drinking Water Pathway for 2010 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake in one year)= 510 l Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/l) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C0-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 066 308 0.00E+00 3.19E-02 3.19E-02 3.19E-02 3.19E-02 3.19E-02 3.19E-02 Dose Commitment (mrem) = 0.00E+00 3.19E-02 3.19E-02 3.19E-02 3.19E-02 3.19E-02 3.19E-02 Section 4 - Page 7

Oconee Nuclear Station Dose from Fish Pathway for 2010 Data Maximum Exposed Child Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 12313 pCi/l x 0.9 = 11082 pCi/kg Usage (intake in one year) = 6.9 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Fish Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C0-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 063 2.80 6.32E-03 6.05E-03 8.93E-04 0.00E+00 1.97E-03 7.09E-04 3.79E-05 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 063 11082 0.00E+00 1.55E-02 1.55E-02 1.55E-02 1.55E-02 1.55E-02 1.55E-02 Dose Commitment (mrem) = 6.32E-03 2.16E-02 1.64E-02 1.55E-02 1.75E-02 1.62E-02 1.56E-02 Section 4 - Page 8

Oconee Nuclear Station Dose from Shoreline Sediment Pathway for 2010 Data Maximum Exposed Child Shoreline Recreation = 14 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/m2 Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/m2) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/m2) Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 063 81.7 3.84E-05 4.48E-05 Dose Commitment (mrem) = 3.84E-05 4.48E-05 Section 4 - Page 9

Oconee Nuclear Station Dose from Drinking Water Pathway for 2010 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake in one year)= 510 l Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/l) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 066 308 0.00E+00 1.67E-02 1.67E-02 1.67E-02 1.67E-02 1.67E-02 1.67E-02 Dose Commitment (mrem)= 0.00E+00 1.67E-02 1.67E-02 1.67E-02 1.67E-02 1.67E-02 1.67E-02 Section 4 - Page 10

Oconee Nuclear Station Dose from Fish Pathway for 2010 Data Maximum Exposed Teen Teen Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 12313 pCi/l x 0.9 = 11082 pCi/kg Usage (intake in one year) = 16 kg Highest Annual Ingestion Dose Factor Net Mean Dose (mrem)

Concentration Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 063 2.80 5.02E-03 6.68E-03 2.33E-03 0.00E+00 2.27E-03 8.83E-04 9.50E-05 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 063 11082 0.00E+00 1.88E-02 1.88E-02 1.88E-02 1.88E-02 1.88E-02 1.88E-02 Dose Commitment (mrem) = 5.02E-03 2.55E-02 2.11E-02 1.88E-02 2.11E-02 1.97E-02 1.89E-02 Section 4 - Page 11

Oconee Nuclear Station Dose from Shoreline Sediment Pathway for 2010 Data Maximum Exposed Teen Shoreline Recreation = 67 hr (in one year)

Shore Width Factor = 0.2 2

Sediment Surface Mass = 40 kg/m Teen Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/m2) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/m2) Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 063 81.7 1.84E-04 2.15E-04 Dose Commitment (mrem) = 1.84E-04 2.15E-04 Section 4 - Page 12

Oconee Nuclear Station Dose from Drinking Water Pathway for 2010 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (l) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake in one year) = 730 l Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/l) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 066 308 0.00E+00 2.36E-02 2.36E-02 2.36E-02 2.36E-02 2.36E-02 2.36E-02 Dose Commitment (mrem) = 0.00E+00 2.36E-02 2.36E-02 2.36E-02 2.36E-02 2.36E-02 2.36E-02 Section 4 - Page 13

Oconee Nuclear Station Dose from Fish Pathway for 2010 Data Maximum Exposed Adult Adult Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 12313 pCi/l x 0.9 = 11082 pCi/kg Usage (intake in one year) = 21 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 063 2.80 4.69E-03 6.41E-03 4.20E-03 0.00E+00 2.18E-03 7.23E-04 1.24E-04 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 063 11082 0.00E+00 2.44E-02 2.44E-02 2.44E-02 2.44E-02 2.44E-02 2.44E-02 Dose Commitment (mrem) = 4.69E-03 3.08E-02 2.86E-02 2.44E-02 2.66E-02 2.52E-02 2.46E-02 Section 4 - Page 14

Oconee Nuclear Station Dose from Shoreline Sediment Pathway for 2010 Data Maximum Exposed Adult Shoreline Recreation = 12 hr (in one year)

Shore Width Factor = 0.2 2

Sediment Surface Mass = 40 kg/m Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/m2) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem)

(mrem/hr per pCi/m2) Indicator Sediment Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.00E+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 063 81.7 3.29E-05 3.84E-05 Dose Commitment (mrem) = 3.29E-05 3.84E-05 Section 4 - Page 15

5.0 QUALITY ASSURANCE 5.1 SAMPLE COLLECTION EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.

5.2 SAMPLE ANALYSIS EnRad Laboratories performed the environmental sample analyses as specified by approved analysis procedures. EnRad Laboratories is located in Huntersville, North Carolina, at Duke Energy Corporations Environmental Center.

Duke Energy Corporations 5.3 DOSIMETRY ANALYSIS Environmental Center The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 5.4.1 DAILY QUALITY CONTROL EnRad Laboratories has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.

5.4.2 CALIBRATION VERIFICATION National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Investigations are performed and documented should calibration verification data fall out of limits.

Section 5 - Page 1

5.4.3 BATCH PROCESSING Method quality control samples are analyzed with sample analyses that are processed in batches. These include gross beta in drinking water and all tritium analyses.

5.5 DUKE ENERGY INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Energy Nuclear Generation Department Intercomparison Program during 2010. Interlaboratory cross-check standards, including, Marinelli beakers, air filters, air cartridges, gross beta on smears, and tritium in water samples were analyzed at various times of the year. A summary of the EnRad Laboratory program results for 2010 is documented in Table 5.0-A.

5.6 ERA PROFICIENCY TESTING EnRad Laboratories performed method proficiency testing through a program administered by Environmental Resource Associates (ERA) of Arvada, CO. ERA supplied requested method proficiency samples for analysis and nuclide concentration determination. ERA reported proficiency test results to the North Carolina Department of Health and Human Services, North Carolina Public Health Drinking Water Laboratory Certification Program. A summary of these proficiency test data for 2010 is documented in Table 5.0-B.

5.7 DUKE ENERGY AUDITS The Oconee Nuclear Station Radiological Environmental Monitoring Program was audited by the Quality Assurance Group in 2010. Additional discussion of TLD trending in Section 3.8 was added as a result of this audit (reference 6.14, 6.22).

During the McGuire 2010 Quality Assurance audit an item was identified concerning the calibration media used for fish and vegetation. Special tests were performed to confirm that the existing calibration media are acceptable. Additional information is included in Table 5.0-A and reference 6.15, 6.23.

5.8 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The Oconee Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in 2010 (reference 6.12). No findings were noted in the report.

5.9 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM Oconee Nuclear Station routinely participates with the Bureau of Radiological Health of the States Department of Health and Environmental Control (DHEC) in an intercomparison program. The Memorandum of Agreement (MOA) between SC DHEC Section 5 - Page 2

and Duke Energy describes the sampling frequency and analysis parameters for drinking water, surface water, milk, fish, vegetation, and shoreline sediment samples collected by EnRad Laboratories. Samples are routinely split with DHEC for intercomparison analysis. DHEC collects air samples near two of the locations sampled for air by ONS.

Results of the analyses performed on split and duplicate samples are sent to DHEC.

5.10 TLD INTERCOMPARISON PROGRAM 5.10.1 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM Radiation Dosimetry and Records participates in a quarterly TLD intercomparison program administered by Nuclear Technology Services, Inc. of Roswell, GA. Nuclear Technology Services irradiates environmental dosimeters quarterly and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the Nuclear Technology Services Intercomparison Report is documented in Table 5.0-C.

5.10.2 INTERNAL CROSSCHECK (DUKE ENERGY)

Radiation Dosimetry and Records participates in a quarterly TLD intracomparison program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff irradiates environmental dosimeters quarterly and submits them for analysis of the unknown estimated delivered exposure. A summary of the Internal Cross Check (Duke Energy) Result is documented in Table 5.0-C.

Section 5 - Page 3

TABLE 5.0-A DUKE ENERGY INTERLABORATORY COMPARISON PROGRAM 2010 CROSS-CHECK RESULTS FOR ENRAD LABORATORIES Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all three analyses yielded results within the designated acceptance range. A status of "1 Pass" indicates that one analysis of the cross check was performed If applicable, footnote explanations are included following this table.

Gamma in Water 3.5 liters Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 2/22/2010 Q101GWR Co-57 0.86 - 1.52 E4 1.14 E4 1.16 E4 3 Pass Co-60 2.72 - 4.82 E3 3.62 E3 3.66 E3 3 Pass Ba-133 5.31 - 9.43 E3 7.09 E3 5.70 E3 3 Pass Cs-137 4.67 - 8.27 E3 6.22 E3 6.15 E3 3 Pass 6/2/2010 Q102GWSL Cr-51 1.15 - 2.05 E5 1.54 E5 1.85 E5 3 Pass Mn-54 4.91 - 8.70 E4 6.54 E4 6.65 E4 3 Pass Co-58 3.10 - 5.49 E4 4.13 E4 4.37 E4 3 Pass Fe-59 3.79 - 6.72 E4 5.05 E4 5.87 E4 3 Pass Co-60 5.63 - 9.99 E4 7.51 E4 7.39 E4 3 Pass Zn-65 6.00 - 10.63 E4 7.99 E4 8.28 E4 3 Pass Cs-134 3.62 - 6.42 E4 4.82 E4 4.33 E4 3 Pass Cs-137 4.29 - 7.61 E4 5.72 E4 5.38 E4 3 Pass Ce-141 3.66 - 6.49 E4 4.88 E4 5.70 E4 3 Pass 9/9/2010 Q103GWSL Cr-51 1.00 - 1.77 E5 1.33 E5 1.35 E5 3 Pass Mn-54 4.34 - 7.69 E4 5.79 E4 6.05 E4 3 Pass Co-58 2.82 - 5.00 E4 3.76 E4 3.82 E4 3 Pass Fe-59 3.64 - 6.46 E4 4.86 E4 5.21 E4 3 Pass Co-60 6.13 - 10.86 E4 8.17 E4 8.38 E4 3 Pass Zn-65 7.44 - 13.19 E4 9.92 E4 10.43 E4 3 Pass Cs-134 3.35 - 5.94 E4 4.47 E4 4.13 E4 3 Pass Cs-137 3.38 - 6.00 E4 4.51 E4 4.45 E4 3 Pass Ce-141 5.41 - 9.59 E4 7.21 E4 7.37 E4 3 Pass Gamma in Water 1.0 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 2/22/2010 Q101GWR Co-57 0.86 - 1.52 E4 1.14 E4 1.12 E4 3 Pass Co-60 2.72 - 4.82 E3 3.62 E3 3.73 E3 3 Pass Ba-133 5.31 - 9.43 E3 7.09 E3 5.56 E3 3 Pass Cs-137 4.67 - 8.27 E3 6.22 E3 6.06 E3 3 Pass Section 5 - Page 4

Gamma in Water 1.0 liter, continued Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 6/2/2010 Q102GWSL Cr-51 1.15 - 2.05 E5 1.54 E5 1.85 E5 2 Pass Mn-54 4.91 - 8.70 E4 6.54 E4 6.70 E4 2 Pass Co-58 3.10 - 5.49 E4 4.13 E4 4.38 E4 2 Pass Fe-59 3.79 - 6.72 E4 5.05 E4 5.91 E4 2 Pass Co-60 5.63 - 9.99 E4 7.51 E4 7.44 E4 2 Pass Zn-65 6.00 - 10.63 E4 7.99 E4 8.35 E4 2 Pass Cs-134 3.62 - 6.42 E4 4.82 E4 4.25 E4 2 Pass Cs-137 4.29 - 7.61 E4 5.72 E4 5.39 E4 2 Pass Ce-141 3.66 - 6.49 E4 4.88 E4 5.69 E4 2 Pass 9/9/2010 Q103GWSL Cr-51 1.00 - 1.77 E5 1.33 E5 1.33 E5 3 Pass Mn-54 4.34 - 7.69 E4 5.79 E4 5.98 E4 3 Pass Co-58 2.82 - 5.00 E4 3.76 E4 3.76 E4 3 Pass Fe-59 3.64 - 6.46 E4 4.86 E4 5.16 E4 3 Pass Co-60 6.13 - 10.86 E4 8.17 E4 8.32 E4 3 Pass Zn-65 7.44 - 13.19 E4 9.92 E4 10.43 E4 3 Pass Cs-134 3.35 - 5.94 E4 4.47 E4 3.98 E4 3 Pass Cs-137 3.38 - 6.00 E4 4.51 E4 4.43 E4 3 Pass Ce-141 5.41 - 9.59 E4 7.21 E4 7.24 E4 3 Pass Gamma in Water 0.5 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 2/22/2010 Q101GWR Co-57 0.86 - 1.52 E4 1.14 E4 1.12 E4 3 Pass Co-60 2.72 - 4.82 E3 3.62 E3 3.73 E3 3 Pass Ba-133 5.31 - 9.43 E3 7.09 E3 5.53 E3 3 Pass Cs-137 4.67 - 8.27 E3 6.22 E3 6.04 E3 3 Pass 6/2/2010 Q102GWSL Cr-51 1.15 - 2.05 E5 1.54 E5 1.81 E5 3 Pass Mn-54 4.91 - 8.70 E4 6.54 E4 6.45 E4 3 Pass Co-58 3.10 - 5.49 E4 4.13 E4 4.22 E4 3 Pass Fe-59 3.79 - 6.72 E4 5.05 E4 5.73 E4 3 Pass Co-60 5.63 - 9.99 E4 7.51 E4 7.24 E4 3 Pass Zn-65 6.00 - 10.63 E4 7.99 E4 8.10 E4 3 Pass Cs-134 3.62 - 6.42 E4 4.82 E4 4.10 E4 3 Pass Cs-137 4.29 - 7.61 E4 5.72 E4 5.17 E4 3 Pass Ce-141 3.66 - 6.49 E4 4.88 E4 5.46 E4 3 Pass 9/9/2010 Q103GWSL Cr-51 1.00 - 1.77 E5 1.33 E5 1.26 E5 3 Pass Mn-54 4.34 - 7.69 E4 5.79 E4 5.55 E4 3 Pass Co-58 2.82 - 5.00 E4 3.76 E4 3.47 E4 3 Pass Fe-59 3.64 - 6.46 E4 4.86 E4 4.85 E4 3 Pass Co-60 6.13 - 10.86 E4 8.17 E4 7.80 E4 3 Pass Zn-65 7.44 - 13.19 E4 9.92 E4 9.76 E4 3 Pass Cs-134 3.35 - 5.94 E4 4.47 E4 3.69 E4 3 Pass Cs-137 3.38 - 6.00 E4 4.51 E4 4.11 E4 3 Pass Ce-141 5.41 - 9.59 E4 7.21 E4 6.68 E4 3 Pass Section 5 - Page 5

Gamma in Water 0.25 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 2/22/2010 Q101GWR Co-57 0.86 - 1.52 E4 1.14 E4 1.09 E4 3 Pass Co-60 2.72 - 4.82 E3 3.62 E3 3.71 E3 3 Pass Ba-133 5.31 - 9.43 E3 7.09 E3 5.56 E3 3 Pass Cs-137 4.67 - 8.27 E3 6.22 E3 5.88 E3 3 Pass 6/2/2010 Q102GWSL Cr-51 1.15 - 2.05 E5 1.54 E5 1.77 E5 3 Pass Mn-54 4.91 - 8.70 E4 6.54 E4 6.39 E4 3 Pass Co-58 3.10 - 5.49 E4 4.13 E4 4.20 E4 3 Pass Fe-59 3.79 - 6.72 E4 5.05 E4 5.68 E4 3 Pass Co-60 5.63 - 9.99 E4 7.51 E4 7.21 E4 3 Pass Zn-65 6.00 - 10.63 E4 7.99 E4 8.09 E4 3 Pass Cs-134 3.62 - 6.42 E4 4.82 E4 4.09 E4 3 Pass Cs-137 4.29 - 7.61 E4 5.72 E4 5.19 E4 3 Pass Ce-141 3.66 - 6.49 E4 4.88 E4 5.34 E4 3 Pass 9/9/2010 Q103GWSL Cr-51 1.00 - 1.77 E5 1.33 E5 1.35 E5 3 Pass Mn-54 4.34 - 7.69 E4 5.79 E4 5.90 E4 3 Pass Co-58 2.82 - 5.00 E4 3.76 E4 3.67 E4 3 Pass Fe-59 3.64 - 6.46 E4 4.86 E4 5.18 E4 3 Pass Co-60 6.13 - 10.86 E4 8.17 E4 8.25 E4 3 Pass Zn-65 7.44 - 13.19 E4 9.92 E4 10.33 E4 3 Pass Cs-134 3.35 - 5.94 E4 4.47 E4 3.92 E4 3 Pass Cs-137 3.38 - 6.00 E4 4.51 E4 4.33 E4 3 Pass Ce-141 5.41 - 9.59 E4 7.21 E4 7.09 E4 3 Pass Gamma on Filter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 6/17/2010 E7153-37 Cr-51 2.46 - 4.36 E2 3.28 E2 3.76 E2 2 Pass Mn-54 1.23 - 2.18 E2 1.64 E2 1.65 E2 2 Pass Co-58 7.34 - 13.02 E1 9.79 E1 9.93 E1 2 Pass Fe-59 0.86 - 1.53 E2 1.15 E2 1.05 E2 2 Pass Co-60 1.43 - 2.53 E2 1.90 E2 1.86 E2 2 Pass Zn-65 1.49 - 2.65 E2 1.99 E2 1.92 E2 2 Pass Cs-134 0.92 - 1.62 E2 1.22 E2 1.13 E2 2 Pass Cs-137 1.09 - 1.93 E2 1.45 E2 1.40 E2 2 Pass Ce-141 0.80 - 1.42 E2 1.07 E2 1.01 E2 2 Pass Gamma in Soil (Special Testing)*

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/kg pCi/kg pCi/kg 12/9/2010 E7380-37 Cr-51 2.60 - 9.98 E2 5.09 E2 5.85 E2 4 Pass Mn-54 1.01 - 1.78 E2 1.34 E2 1.42 E2 4 Pass Co-58 0.76 - 1.34 E2 1.01 E2 0.96 E2 1/4 Low (1)

Fe-59 0.95 - 2.25 E2 1.46 E2 1.42 E2 4 Pass Co-60 2.52 - 4.47 E2 3.36 E2 3.27 E2 4 Pass Zn-65 1.46 - 2.58 E2 1.94 E2 1.97 E2 4 Pass Cs-134 1.31 - 2.33 E2 1.75 E2 1.54 E2 4 Pass Cs-137 2.24 - 3.96 E2 2.98 E2 2.89 E2 4 Pass

INOS Audit 10-15(INOS)(REC)(MNS) 2010, PIP M-10-06597 Section 5 - Page 6

Gamma in Vegetation (Special Testing)*

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/kg pCi/kg pCi/kg 12/9/2010 E7381-37 Cr-51 2.36 - 11.11 E2 5.12 E2 5.10 E2 1 Pass Mn-54 1.01 - 1.78 E2 1.34 E2 1.51 E2 1 Pass Co-58 0.76 - 1.34 E2 1.01 E2 1.00 E2 1 Pass Fe-59 0.84 - 2.57 E2 1.47 E2 1.54 E2 1 Pass Co-60 2.54 - 4.50 E2 3.38 E2 3.38 E2 1 Pass Zn-65 1.46 - 2.59 E2 1.95 E2 2.24 E2 1 Pass Cs-134 1.32 - 2.34 E2 1.76 E2 1.51 E2 1 Pass Cs-137 1.57 - 2.78 E2 2.09 E2 2.03 E2 1 Pass

INOS Audit 10-15(INOS)(REC)(MNS) 2010, PIP M-10-06597 Iodine in Milk Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/2/2010 Q101LIM1 I-131 2.29 - 4.06 E1 3.06 E1 2.38 E1 1 Pass 3/2/2010 Q101LIM2 I-131 1.25 - 2.21 E3 1.66 E3 1.39 E3 3 Pass 3/2/2010 Q101LIM3 I-131 6.27 - 11.13 E3 8.37 E3 6.44 E3 2 Pass Iodine on Cartridge Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 6/17/2010 E7154-37 I-131 6.01 - 10.65 E1 8.01 E1 8.39 E1 3 Pass Tritium in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 2/22/2010 Q101TWS1 H-3 6.68 - 11.84 E5 8.91 E5 9.00 E5 3 Pass 2/22/2010 Q101TWS2 H-3 0.79 - 1.40 E7 1.05 E7 1.00 E7 3 Pass 11/4/2010 Q104TWR1 H-3 3.14 - 5.56 E3 4.18 E3 3.91 E3 3 Pass 11/4/2010 Q104TWR2 H-3 3.40 - 6.02 E4 4.53 E4 4.26 E4 3 Pass 11/4/2010 Q104TWR3 H-3 4.98 - 8.83 E2 6.64 E2 6.12 E2 3 Pass Gross Beta in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 11/18/2010 Q104ABW1 Cs-137 5.43 - 9.63 E1 7.24 E1 6.79 E1 3 Pass 11/18/2010 Q104ABW2 Cs-137 4.88 - 8.66 E1 6.51 E1 6.44 E1 3 Pass 11/18/2010 Q104ABW3 Cs-137 1.15 - 2.03 E1 1.53 E1 1.52 E1 3 Pass Section 5 - Page 7

Table 5.0-A Footnote Explanations (1) Gamma in Soil (Special Testing), Sample ID E7380-37, Reference Date 12/9/2010 One of four Co-58 results was biased low and outside of the acceptance range (reference 6.17).

Section 5 - Page 8

TABLE 5.0-B ENVIRONMENTAL RESOURCE ASSOCIATES (ERA)

QUIK' RESPONSE PROGRAM 2010 PROFICIENCY TEST RESULTS FOR ENRAD LABORATORIES ERA LABORATORY CODE: D242401 Proficiency test samples are received, prepared, analyzed, and reported to Environmental Resource Associates as described in the "Quik" Response instruction package within the study period. Proficiency test data are reported to ERA for evaluation. ERA reports proficiency test results to the North Carolina Department of Health and Human Services, North Carolina Public Drinking Water Laboratory Certification Program.

If applicable, footnote explanations are included following this data table.

Gamma Emitters in Water Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check Date Range Value Value Status pCi/l pCi/l pCi/l 4/5/2010 RAD-81* Ba-133 5.49 - 7.25 E1 6.59 E1 7.26 E1 High (1)

Cs-134 5.84 - 7.88 E1 7.16 E1 6.74 E1 Pass Cs-137 1.31 - 1.63 E2 1.46 E2 1.33 E2 Pass Co-60 7.60 - 9.53 E1 8.45 E1 8.40 E1 Pass Zn-65 1.67 - 2.19 E2 1.86 E2 1.93 E2 Pass 1/10/2010 Quik 120810K** Ba-133 6.10 - 8.02 E1 7.29 E1 7.75 E1 Pass Cs-134 5.15 - 6.97 E1 6.34 E1 6.18 E1 Pass Cs-137 1.08 - 1.34 E2 1.20 E2 1.14 E2 Pass Co-60 8.10 - 10.1 E1 9.00 E1 9.90 E1 Pass Zn-65 1.89 - 2.46 E2 2.10 E2 2.12 E2 Pass Tritium in Water Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check Date Range Value Value Status pCi/l pCi/l pCi/l 4/5/2010 RAD-81* H-3 1.08 - 1.36 E4 1.24 E4 1.16 E4 Pass 1/10/2010 Quik 120810K** H-3 3.16 - 4.10 E3 3.72 E3 3.58 E3 Pass

ERA study period 4/5/2010 - 5/20/2010, ERA data report issue date 5/26/2010

- ERA study period 12/8/2010 - 3/30/2011, ERA data report issue date 3/30/2010 Section 5 - Page 9

Table 5.0-B Footnote Explanations (1) Gamma Emitters in Water, Sample ID RAD-81, Reference Date 4/5/2010 Reported result for Ba-133 was above the acceptance range limit (reference 6.18).

Section 5 - Page 10

TABLE 5.0-C 2010 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Nuclear Technology Services 1st Quarter 2010 2nd Quarter 2010 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 102379 105.0 101.9 3.04 <+/-15% Pass 102501 71.0 73.0 -2.74 <+/-15% Pass 102385 103.0 101.9 1.08 <+/-15% Pass 102013 73.0 73.0 0.00 <+/-15% Pass 102403 103.0 101.9 1.08 <+/-15% Pass 100309 73.0 73.0 0.00 <+/-15% Pass 102480 101.0 101.9 -0.88 <+/-15% Pass 100623 70.0 73.0 -4.11 <+/-15% Pass 102505 103.0 101.9 1.08 <+/-15% Pass 102060 72.0 73.0 -1.37 <+/-15% Pass Average Bias (B) 1.08 Average Bias (B) -1.64 Standard Deviation (S) 1.39 Standard Deviation (S) 1.79 Measure Performance lBl+S 2.47 <15% Pass Measure Performance lBl+S 3.43 <15% Pass 3rd Quarter 2010 4th Quarter 2010 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 100252 56.1 55.9 0.36 <+/-15% Pass 102367 88.0 84.0 4.76 <+/-15% Pass 100403 55.2 55.9 -1.25 <+/-15% Pass 102399 91.0 84.0 8.33 <+/-15% Pass 101143 55.3 55.9 -1.07 <+/-15% Pass 102402 87.0 84.0 3.57 <+/-15% Pass 100065 54.2 55.9 -3.04 <+/-15% Pass 102480 90.0 84.0 7.14 <+/-15% Pass 100054 57.2 55.9 2.33 <+/-15% Pass 102510 90.0 84.0 7.14 <+/-15% Pass Average Bias (B) -0.54 Average Bias (B) 6.19 Standard Deviation (S) 2.00 Standard Deviation (S) 1.96 Measure Performance lBl+S 2.54 <15% Pass Measure Performance lBl+S 8.15 <15% Pass Section 5 - Page 11

Internal Crosscheck (Duke Energy) 1st Quarter 2010 2nd Quarter 2010 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 102384 21.5 22.0 -2.18 <+/-15% Pass 101183 29.2 30.0 -2.60 <+/-15% Pass 102399 21.4 22.0 -2.82 <+/-15% Pass 100709 29.8 30.0 -0.70 <+/-15% Pass 102406 21.9 22.0 -0.50 <+/-15% Pass 101167 29.0 30.0 -3.30 <+/-15% Pass 102487 20.5 22.0 -6.68 <+/-15% Pass 101290 28.2 30.0 -6.07 <+/-15% Pass 102260 21.1 22.0 -4.27 <+/-15% Pass 100027 28.2 30.0 -6.07 <+/-15% Pass 102504 21.2 22.0 -3.45 <+/-15% Pass 101310 28.6 30.0 -4.67 <+/-15% Pass 102393 20.8 22.0 -5.45 <+/-15% Pass 101189 29.6 30.0 -1.33 <+/-15% Pass 102261 21.2 22.0 -3.68 <+/-15% Pass 101158 29.7 30.0 -1.03 <+/-15% Pass 102343 20.9 22.0 -5.09 <+/-15% Pass 101386 31.0 30.0 3.47 <+/-15% Pass 101235 21.5 22.0 -2.36 <+/-15% Pass 101398 32.4 30.0 8.03 <+/-15% Pass Average Bias (B) -3.65 Average Bias (B) -1.43 Standard Deviation (S) 1.81 Standard Deviation (S) 4.38 Measure Performance lBl+S 5.46 <15% Pass Measure Performance lBl+S 5.81 <15% Pass 3rd Quarter 2010 4th Quarter 2010 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 102264 96.8 100.0 -3.21 <+/-15% Pass 102301 33.1 35.0 -5.46 <+/-15% Pass 102406 101.4 100.0 1.41 <+/-15% Pass 102471 34.8 35.0 -0.49 <+/-15% Pass 102399 99.7 100.0 -0.30 <+/-15% Pass 102083 33.7 35.0 -3.66 <+/-15% Pass 102403 97.0 100.0 -2.97 <+/-15% Pass 102442 33.4 35.0 -4.60 <+/-15% Pass 102480 98.8 100.0 -1.17 <+/-15% Pass 102389 33.4 35.0 -4.46 <+/-15% Pass 102505 99.0 100.0 -1.00 <+/-15% Pass 102362 33.9 35.0 -3.20 <+/-15% Pass 102440 95.1 100.0 -4.95 <+/-15% Pass 101413 33.4 35.0 -4.66 <+/-15% Pass 102479 95.7 100.0 -4.33 <+/-15% Pass 102007 33.1 35.0 -5.57 <+/-15% Pass 101136 98.2 100.0 -1.84 <+/-15% Pass 102509 34.9 35.0 -0.31 <+/-15% Pass 102339 95.6 100.0 -4.41 <+/-15% Pass 102058 33.2 35.0 -5.23 <+/-15% Pass Average Bias (B) -2.28 Average Bias (B) -3.76 Standard Deviation (S) 2.05 Standard Deviation (S) 1.92 Measure Performance lBl+S 4.33 <15% Pass Measure Performance lBl+S 5.68 <15% Pass Section 5 - Page 12

6.0 REFERENCES

6.1 Oconee Selected License Commitment Manual 6.2 Oconee Technical Specifications 6.3 Oconee Updated Final Safety Analysis Report 6.4 Oconee Offsite Dose Calculation Manual 6.5 Oconee Annual Radiological Environmental Operating Report 1969-2009 6.6 Oconee Annual Radioactive Effluent Release Report 2010 6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery, 1969, pages 287-293.

6.8 Practical Statistics for the Physical Sciences, Havilcek and Crain, 1988, pages 83-93.

6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix I.

6.10 EnRad Laboratories Operating Procedures 6.11 RETDAS, Radiological Effluent Tracking and Dose Assessment Software, Canberra Version 3.5.1, DPC Revision #4.0 6.12 NRC Integrated Inspection Report 05000269/2010004, 05000270/2010004, 05000287/2010004 6.13 Duke Energy Corporation EnRad Laboratory Charcoal Cartridge Study, performed 2001 6.14 Radiological Effluent Controls INOS Audit 10-14 (INOS)(REC)(ONS) 6.15 Radiological Effluent Controls INOS Audit 10-15 (INOS)(REC)(MNS) 6.16 South Carolina State Climatology Office 2009, South Carolina Department of Natural Resources, Land, Water, and Conservation Division State Climate Office, Columbia, South Carolina, viewed 9 April 2009,

<http://www.dnr.sc.gov/climate/sco/Drought/drought_current_info.php>

6.17 Problem Investigation Program Database, V 3.4.1, Duke Energy Company, G-11-00581 Section 6 - Page 1

6.18 Problem Investigation Program Database, V 3.4.1, Duke Energy Company, G-11-00598 6.19 Problem Investigation Program Database, V 3.4.1, Duke Energy Company, G-10-01029 6.20 Problem Investigation Program Database, V 3.4.1, Duke Energy Company, G-09-01293 6.21 Nuclear System Directive (NSD) 701, Records Management 6.22 Problem Investigation Program Database, V 3.4.1, Duke Energy Company, O-10-06760 6.23 Problem Investigation Program Database, V 3.4.1, Duke Energy Company, M-10-06597 6.24 Problem Investigation Program Database, V 3.4.1, Duke Energy Company, G-09-00424 6.25 Problem Investigation Program Database, V 3.4.1, Duke Energy Company, O-11-00631 Section 6 - Page 2

APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PROCEDURES Appendix A - Page 1

APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at Oconee Nuclear Station is required to ensure compliance with Station Selected Licensee Commitments. Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved.

Environmental sampling and analyses were performed by EnRad Laboratories, Dosimetry and Records, and Fisheries and Aquatic Ecology.

Section IV of this appendix describes the environmental sampling frequencies and analysis procedures by media type.

I. CHANGE OF SAMPLING PROCEDURES TLD Location 024 (Site Boundary TLD) was relocated due to site degradation from soil erosion. Distance was updated from East sector 0.81 miles to 0.79 miles (reference 6.19).

Location 036 (Site Boundary TLD) was determined to be in the N sector at 4.18 miles following an assessment. Distance updated from 4.32 miles to 4.18 miles (reference 6.20).

II. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software. Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy.

Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry.

Low-level iodine analyses are performed by passing a designated sample aliquot through a pre-weighed amount of ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried, mixed thoroughly, and a net resin weight determined before being transferred to appropriate counting geometry and analyzed by gamma spectroscopy.

Tritium analyses are performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system or Perkin-Elmer 2900TR liquid scintillation system. Tritium samples are distilled and batch Appendix A - Page 2

processed with a tritium spike and blank to verify instrument performance and sample preparation technique are acceptable.

Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by Tennelec XLB Series 5 gas-flow proportional counters.

Samples are batch processed with a blank to ensure sample contamination has not occurred.

III. CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 2010.

IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE Airborne particulate and radioiodine samples at each of six locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge positioned behind the filter in the sampler. The samplers are designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute. Filters and cartridges were collected weekly. A separate weekly gamma analysis was performed on each charcoal cartridge and air particulate. A weekly gross beta analysis was performed on each filter. The continuous composite samples were collected from the locations listed below.

Location 074 = Keowee Key Resort (2.36 mi. NNW)

Location 077 = Skimmer Wall (1.00 mi. SW)

Location 078.1 = Recreation Site (0.53 mi. WSW)

Location 079 = Keowee Dam (0.56 mi. NE)

Location 081 = Clemson Operations Center (9.33 mi. SE)

Location 084 = Sue Craig Road (2.58 mi. NNE)

A.2 DRINKING WATER Monthly composite samplers were operated to collect an aliquot at least every two hours. Gross beta and gamma analysis was performed on the monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected monthly from the locations listed below.

Location 060 = Greenville Water Intake Rd. (3.23 mi. NE)

Location 064 = Seneca (6.67 mi. SSW)

Location 066 = Anderson (18.9 mi SSE)

Appendix A - Page 3

A.3 SURFACE WATER Monthly composite samplers were operated to collect an aliquot at least every two hours. Gamma analysis was performed on the monthly composites. Tritium analysis was performed on the quarterly composites sample. The composites were collected monthly from the locations listed below.

Location 062 = Lake Keowee Hydro Intake (0.85 mi. ENE)

Location 063.1 = Lake Hartwell Hwy 183 Bridge (0.79 mi. E)

A.4 MILK Semimonthly grab samples were collected at one location. A gamma and low-level Iodine-131 analysis was performed on each sample. The semimonthly grab samples were collected from the location listed below.

Location 071 = Clemson Dairy (10.2 mi. SSE)

A.5 BROADLEAF VEGETATION Monthly samples were collected and a gamma analysis was performed on each sample. The samples were collected from the locations listed below.

Location 077 = Skimmer Wall (1.00 mi. SW)

Location 079 = Keowee Dam (0.56 mi. NE)

Location 081 = Clemson Operations Center (9.33 mi. SE)

Location 084 = Sue Craig Road (2.58 mi. NNE)

A.6 FISH Semiannual samples were collected and a gamma analysis was performed on the edible portions of each sample. The samples were collected from the locations listed below.

Location 060 = Greenville Water Intake Rd. (2.28 mi. NE)

Location 063 = Lake Hartwell Hwy 183 Bridge (0.80 mi. ESE)

Location 067 = Lawrence Ramsey Bridge Hwy 27 (4.34 mi. SSE)

A.7 SHORELINE SEDIMENT Semiannual samples were collected and a gamma analysis was performed on each sample following the drying and removal of rocks and clams. The samples were collected from the locations listed below.

Location 063 = Lake Hartwell Hwy 183 Bridge (0.80 mi. ESE)

Location 067 = Lawrence Ramsey Bridge Hwy 27 (4.34 mi. SSE)

Location 068 = High Falls County Park (1.82 mi. W)

Appendix A - Page 4

A.8 DIRECT GAMMA RADIATION (TLD)

Thermoluminescent dosimeters (TLD) were collected quarterly at forty-two locations. A gamma exposure rate was determined for each TLD. The TLDs were placed as indicated below.

An inner ring of 17 TLDs, one in each meteorological sector in the general area of the site boundary.

An outer ring of 16 TLDs, one in each meteorological sector in the 6 to 8 kilometer range.

The remaining TLDs were placed in special interest areas such as population centers, residential areas, schools, and control locations.

TLD Locations are listed in Table 2.1-B.

A.9 ANNUAL LAND USE CENSUS An annual Land Use Census was conducted to identify within a distance of 8 kilometers (5.0 miles) from the station, the following locations in each of the sixteen meteorological sectors:

The Nearest Residence

The Nearest Milk-giving Animal (cow, goat, etc.) where milk is used for human consumption The census was conducted during the growing season from 6/6 to 6/7/2010.

Results are shown in Table 3.9. No changes were made to the sampling procedures during 2010 as a result of the 2010 census.

V. GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS The Oconee site centerline used for GPS measurements was referenced from the Oconee Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1.1, Specification of Location. Waypoint coordinates used for ONS GPS measurements were latitude 34°-47'-38.2"N and longitude 82°-53'-55.4"W. Maps and tables were generated using North American Datum (NAD) 27. Data normally reflect accuracy to within 2 to 5 meters from point of measurement. GPS field measurements were taken as close as possible to the item of interest. Distances for the locations are displayed using three significant figures.

Appendix A - Page 5

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF RESULTS 2010 Appendix B - Page 1

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 Type and No. of Non-Medium or Location with Highest Total Lower Limit Control Routine Pathway All Indicator Locations Annual Mean Number of Detection Location Report Sampled Name, Distance, Direction of Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

(LLD)

Measurement Performed Range Code Range Range Air Particulate (pCi/m3) 081 (9.33 mi SE)

BETA 318 1.00E-02 1.96E-2 (265/265) 074 2.02E-2 (53/53) 2.04E-2 (53/53) 0 7.89E 3.80E-2 (2.36 mi NNW) 9.19E 3.56E-2 9.45E 3.72E-2 CS-134 318 5.00E-02 0.00 (0/265) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 318 6.00E-02 0.00 (0/265) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 318 7.00E-02 0.00 (0/265) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 5/3/2011 06:59 Appendix B - Page 2

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

(LLD)

Measurement Performed Range Code Range Range Air Radioiodine (pCi/m3) 081 (9.33 mi SE)

CS-134 318 5.00E-02 0.00 (0/265) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 318 6.00E-02 0.00 (0/265) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 318 7.00E-02 0.00 (0/265) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 5/3/2011 06:59 Appendix B - Page 3

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

(LLD)

Measurement Performed Range Code Range Range Drinking Water 064 (pCi/liter) (6.67 mi SSW)

BALA-140 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 BETA 39 4 0.99 (22/26) 066 1.10 (12/13) 0.97 (8/13) 0 0.59 - 1.51 (18.9 mi SSE) 0.61 - 1.51 0.72 - 1.31 CO-58 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 39 18 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 12 2000 308 (4/8) 066 308 (4/4) 0.00 (0/4) 0 254 - 393 (18.9 mi SSE) 254 - 393 0.00 - 0.00 I-131 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 5/3/2011 07:00 Appendix B - Page 4

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

(LLD)

Measurement Performed Range Code Range Range Surface Water 062 (pCi/liter) (0.85 mi ENE)

BALA-140 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 26 18 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 8 2000 12313 (4/4) 063.1 12313 (4/4) 0.00 (0/4) 0 2070 - 20700 (0.79 mi E) 2070 - 20700 0.00 - 0.00 I-131 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 5/3/2011 07:00 Appendix B - Page 5

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269, 270, 287 Location: Oconee County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

(LLD)

Measurement Performed Range Code Range Range Milk NO INDICATOR 071 (10.2 mi SSE)

(pCi/liter) LOCATION BALA-140 26 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 26 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 26 18 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 26 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLI-131 26 1 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 5/3/2011 07:01 Appendix B - Page 6

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

(LLD)

Measurement Performed Range Code Range Range Broadleaf Vegetation 081 (9.33 mi SE)

(pCi/kg-wet)

CS-134 48 60 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 48 80 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 48 60 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 5/3/2011 07:01 Appendix B - Page 7

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

(LLD)

Measurement Performed Range Code Range Range Fish 060 (pCi/kg-wet) (2.28 mi NE)

CO-58 12 130 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 12 130 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 12 130 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 12 150 25.3 (6/8) 063 26.9 (2/4) 24.1 (1/4) 0 9.16 - 35.3 (0.80 mi ESE) 24.4 - 29.3 24.1 - 24.1 FE-59 12 260 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 12 130 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 12 260 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 5/3/2011 07:02 Appendix B - Page 8

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 No. of Non-Medium or Type and Total Lower Location with Highest All Indicator Control Routine Pathway Number Limit of Annual Mean Locations Location Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

(LLD)

Measurement Performed Range Code Range Range Shoreline 068 Sediment (1.82 mi W)

(pCi/kg-dry)

CS-134 6 150 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 6 180 115 (2/4) 063 115 (2/2) 33.3 (1/2) 0 32.3 - 198 (0.80 mi ESE) 32.3 - 198 33.3 - 33.3 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 5/3/2011 07:02 Appendix B - Page 9

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 No. of Non-Type and Total Lower Location with Highest Medium or All Indicator Control Routine Number Limit of Annual Mean Pathway Sampled Locations Location Report of Detection Name, Distance, Direction Meas.

Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Unit of Measurement (LLD)

Performed Range Code Range Range Direct Radiation TLD 058 (9.39 mi WSW)

(mR/standard quarter) 081 (9.33 mi SE) 166 0.00E+00 22.2 (159/159) 042 28.3 (4/4) 25.7 (7/7) 0 13.0 - 33.0 (4.93 mi SE) 25.0 - 31.0 20.0 - 30.0 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 5/3/2011 07:03 Appendix B - Page 10

APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES Appendix C - Page 1

APPENDIX C OCONEE NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES DEVIATION & UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair IW Inclement Weather SL Sample Loss/Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Torn Filter PI Power Interrupt VN Vandalism PM Preventive Maintenance CN Construction C.1 SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power to sampling equipment was interrupted due to breaker trip. Breaker 078.1 6/14 - 6/21/2010 6/14 - 6/16/2010 PI reset and normal sampling resumed.

Power to sampling equipment was interrupted due to breaker trip. Breaker 081 8/2 - 8/9/2010 8/2 - 8/7/2010 PI reset and normal sampling resumed.

Drinking Water Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power to sampling equipment was interrupted. A grab sample was taken.

Power was restored and normal sampling 060 7/26 - 8/23/2010 8/23/2010 PI resumed.

Surface Water Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Continuous flow reservoir pump found inoperative at time of collection. A grab sample was taken. Work request 80137 written. Reservoir pump restored to operation and normal sampling resumed 2JUN2010. Grab sample was combined 062 6/1 - 6/28/2010 6/1 - 6/28/2010 PS with composite.

Appendix C - Page 2

Surface Water, continued Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Submersible pump inoperative at time of collection. A grab sample was taken.

Work request 75256 written. Site services determined an opened breaker had interrupted pump operation. Breaker reset and normal sampling resumed 063.1 1/11 - 2/8/2010 1/11 - 2/8/2010 PS 13JAN2010.

C.2 UNAVAILABLE ANALYSES TLD Scheduled Reason Location Collection Dates Code Corrective Action 040 6/15 - 9/14/2010 CN TLD missing. 4th quarter 2010 TLD placed in field.

058 12/15 - 3/16/2010 VN TLD missing. 2nd quarter 2010 TLD placed in field.

Appendix C - Page 3

APPENDIX D ANALYTICAL DEVIATIONS No Analytical deviations were incurred for the 2010 Radiological Environmental Monitoring Program Appendix D - Page 1

APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes sample analysis reports and supportive data generated from each sample medium. Appendix E is located separately from this report and is permanently archived in the Nuclear Electronic Document Library (NEDL) as described in reference 6.21.

Appendix E - Page 1

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