ML101400136

2009 Annual Radiological Environmental Operating Report

ML101400136
Person / Time
Site:	Oconee
Issue date:	05/13/2010
From:	Baxter D Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML101400136 (89)

Text

DAVE BAXTER Duke *. 7.\ Vice President Energy Oconee Nuclear Station Duke Energy ON01 VP / 7800 Rochester Highway Seneca, SC 29672 864-873-4460 May 13, 2010 864-873-4208 fax dave. baxter@duke-energy.com U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station Docket Nos. 50-269, 50-270 and 50-287 Annual Radiological Environmental Operating Report

Dear Sir:

Pursuant to Oconee Nuclear Station Technical Specification 5.6.2, please find enclosed the Oconee Nuclear Site Annual Radiological Environmental Operating Report for 2009.

Any questions concerning this report may be directed to Judy Smith at 864-873-4309.

Sincerely, Dave/ Baxter Vice President Oconee Nuclear Station Attachment 1 Annual Radiological Environmental Operating Report (hard copy)

Attachment 2 Annual Radiological Environmental Operating Report (CD) www. duke-energy com

.11 U. S. Nuclear Regulatory Commission May 13, 2010 Page 2 xc: Luis Reyes, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 John Stang, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Andrew Sabisch Senior Resident Inspector Oconee Nuclear Station Susan E. Jenkins, Manager Radioactive & Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.

Columbia, SC 29201 American Nuclear Insurers 95 Glastonbury Blvd., Suite 300 Glastonbury, CT 06033-4443 Russell Keown, Supervisor Analytical & Radiological Environmental Services Division 2600 Bull Street Columbia, SC 29201 803-896-0856/KEOWNRH(adhec.sc.gov Sandra Flemming, Director Analytical & Radiological Environmental Services Division 8231 Parklane Road Columbia, SC 29223 803-896-3890/FLEMMISA(adhec.sc.aov

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S AREOR 0 Annual 0 Radiological Environmental S Operating Report S 2009

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• 0 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 3.9 Land Use Census 3-22 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 0

6.0 References 6-1

• Appendices Appendix A: Environmental Sampling and Analysis Procedures A-1 I. Change of Sampling Procedures. A-2

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Description of Analysis Procedures Change of Analysis Procedures .

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IV. Sampling and Analysis Procedures A-3 0 A. 1 Airborne Particulate and Radioiodine A.2 Drinking Water A-3 A-3 0

A.3 Surface Water. A-4 0 A.4 Milk A-4 A.5 Broadleaf Vegetation A-4 A.6 Fish A-4 0 A.7 Shoreline Sediment.

A.8 Direct Gamma Radiation (TLD)

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A.9 Annual Land Use Census . A-5 V. Global Positioning System (GPS) Analysis.

Appendix B: Radiological Env. Monitoring Program - Summary of Results.

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Air Particulate . B-2 0 Air Radioiodine.

Drinking Water.

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Surface Water . B-5 Milk. B-6 0 Broadleaf Vegetation Fish .B-8 B-7 0 Shoreline Sediment B-9 0 Direct Gamma Radiation (TLD)

Appendix C: Sampling Deviations and Unavailable Analyses

. . . B- 10 0 C-1 C.1 Sampling Deviations . C-2 0 C.2 Unavailable Analyses. C-2 Appendix D: Analytical Deviations . D-i 0 Appendix E: Radiological Environmental Monitoring Program Results E-1 0

LIST OF FIGURES 0 0

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 0 3.2 Concentration of Tritium in Drinking Water 3-5 3.3 Concentration of Tritium in Surface Water. 3-8 0 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 0 3.7-1 Concentration of Cs-137 in Shoreline Sediment 3-18 3.7-2 Concentration of Co-60 in Shoreline Sediment 3-18 0 3.8 Direct Gamma Radiation (TLD) Results 3-20 3.9 2009 Land Use Census Map 3-23 0

0 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 0 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 (1-131) . 3-3 3.1-B Mean Concentration of Gross Beta in Air Particulate . 3-4 ii

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3.2 Mean Concentrations of Radionuclides in Drinking Water 3-6 0 3.3 Mean Concentrations of Radionuclides in Surface Water 3-9 0 3.4 Mean Concentrations of Radionuclides in Milk . 3-11 3.5 Mean Concentrations of Radionuclides in Vegetation . 3-13 0 3.6 Mean Concentrations of Radionuclides in Fish 3-16 3.7 Mean Concentrations of Radionuclides in Shoreline Sediment 3-19 3.8 Direct Gamma Radiation (TLD) Results 3-21 0 3.9 4.1-A Oconee 2009 Land Use Census Results 2009 Environmental and Effluent Dose Comparison 3-22 4-3 4.1-B Maximum Individual Dose for 2009 based on Environmental Measurements for Oconee Nuclear Station. 4-6 5.0-A 2009 Cross-Check Results for EnRad Laboratories 5-4 0 5.0-B 2009 Environmental Resource Associates QuikTM Response Program 5-9 0 5.0-C 2009 Environmental Dosimeter Cross-Check Results . 5-11 0 LIST OF ACRONYMS USED IN THIS TEXT (in alphabeticalorder) 0 BW BiWeekly C Control 0 DEHNR DHEC Department of Environmental Health and Natural Resources Department of Health and Environmental Control 0 EPA Environmental Protection Agency ERA Environmental Resource Associates GI-LLI Gastrointestinal - Lower Large Intestine GPS Global Positioning System 0 LLD M

Lower Limit of Detection Monthly MDA Minimum Detectable Activity 0 MOA Memorandum of Agreement mrem Millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission 0 ODCM ONS Offsite Dose Calculation Manual Oconee Nuclear Station pCi/kg picocurie per kilogram 0 pCi/1 picocurie per liter pCi/m3 picocurie per cubic meter 0 PIP Problem Investigation Process Q Quarterly 0 REMP SA Radiological Environmental Monitoring Program Semiannually 0 SLCs SM Selected Licensee Commitments Semimonthly TECH SPECs Technical Specifications S TLD l.1Ci/ml Thermoluminescent Dosimeter microcurie per milliliter UFSAR Updated Final Safety Analysis Report W Weekly iii

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• 1.0 EXECUTIVE

SUMMARY

0 This Annual Radiological Environmental 7.r Operating Report describes the Oconee Nuclear

• Station Radiological Environmental Monitoring Program (REMP), and the program results for 0** the calendar year 2009.

• 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 0data as potentially affected by station operations, and a summary of environmental radiological sampling results. Quality assurance practices and program changes are also discussed.

SSampling activities were conducted as prescribed by Selected Licensee Commitments 0(SLC's). Required analyses were performed and detection capabilities were met for all collected samples as required by SLC's. Nine-hundred sixty-nine samples were analyzed

• comprising 1,346 test results in order to compile data for the 2009 report. Based on the annual land use census, the current number of sampling sites for Oconee Nuclear Station is 0*sufficient.

5 Concentrations observed in the environment in 2009 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 SLC's.

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• Additionally, environmental radiological monitoring data is consistent with effluents introduced into the environment by plant operations. The total body dose estimated to the 0maximum exposed member of the public as calculated by environmental sampling data,

• excluding TLD results, was 5.97E-02 mrem for 2009. It is therefore concluded that station

• operations has had no significant radiological impact on the health and safety of the public or the environment.

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2.0 INTRODUCTION

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• 2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS S

• 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 0by 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)

Smonitoring 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 0determine 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.

0 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 5projected 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 0the company, public, and state and federal agencies concerned with the environment. Reporting S

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S levels for radioactivity found in environmental samples are listed in Table 2.2-A. Table 2.2-B1 lists the REMP analysis and frequency schedule.

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 O 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 0 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. O O

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 O of the mean value for the indicator and the control samples for each sample medium. 0 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 0 concentrations are included in the calculation of the mean. The following equation was used to estimate the mean (reference 6.8):

N Where:

x = estimate of the mean, 1 =individual sample, N = total number of samples with a net activity (or concentration), 0 Xi = net activity (or concentration) for sample i. O 0

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• 2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE

• ACTIVITY The Lower Level of Detection (LLD) and Minimum Detectable Activity (MDA) are 0*

0 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.

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• 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 0calculated 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 0buildup 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 0concentration in an environmental medium does not indicate that reactor operations are 0removing 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.

0Substantial 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 0accident). Some of these factors may be obvious while others are sometimes unknown.

0Therefore, how trends are identified will include some judgment by plant personnel.

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• Section 2 -Page 3 0

Figure 2.1-1 Oconee Nuclear Station Sampling Locations Map (One Mile Radius)

Legend

• TLD Locations A All Other Locations 7 Public Roads

.s County Boundary Water Approximate location of features shown N

Projection NCSP NAD27 Section 2 - Page 4 000001001000000000000000000000000000000OOO000

0*0*0000*000000*00*000000000000000000000000o Figure 2.1-2 Oconee Nuclear Station Sampling Locations Map (Ten Mile Radius)

Legend

• TLD Locations A Al Other Locations

/tv/ Public Roads yts- Rail Roads Avs County Boundary Incorporated Areas Water Aopro)dmate location of features shovn 0m 1 2 3Mie Projecton Miles Projection NCSP NAD27

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TABLE 2.1-A 0 0

OCONEE RADIOLOGICAL MONITORING PROGRAM 0 SAMPLING LOCATIONS 0

0 Table 2. 1-A Codes 0 W Weekly SM Semimonthly BW BiWeekly Q Quarterly 0 M

C Monthly Control SA Semiannually 0 0

0 Site Location Description* Air Rad. & Surface Drinking Shoreline Fish Milk Broadleaf Particulate Water Water Sediment Vegetation 0 060 Greenville Water Intake Road (3.23 NE) 060 C ** Greenville Water Intake Road (2.28 NE)

M SA 0

062 C Lake Keowee Hydro Intake (0.85 mi ENE) M 0 Lake Hartwell Hwy 183 Bridge 063 (0.80 mi ESE) [000.7] SA SA 0 063.1 064 C Lake Hartwell Hwy 183 (0.79 mi E)

Seneca (6.67 mi SSW) [004.1]

M 0 M

066 Anderson (18.9 mi SSE) [012] M 0 067 Lawrence Ramsey Bridge Hwy 27 (4.34 mi SSE) [005.2] SA SA 0

068 C High Falls County Park (1.82 mi W) SA 0 071 C Clemson Dairy (10.2 mi SSE) [006.3] SM 074 Keowee Key Resort (2.36 mi NNW) W 0

077 Skimmer Wall (1.00 mi SW) W M 0 078 (t) Recreation Site (0.58 mi WSW) W 078.1() Recreation Site (0.53 mi WSW) W 0 079 081 C Keowee Dam (0.56 mi NE)

Clemson Operations Center (9.33 mi SE)

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0 084 Sue Craig Road (2.58 mi NNE) W I M 0 (1) Location 078.1 (Air Radioiodine, Air Particulate) was added as a replacement for location 078 (Air Radioiodine, Air Particulate), which was removed from the program. Movement of the air radioiodine and air particulate location is described in reference 6.20. 0

• GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as 0 close as possible to the item of interest. 0

• • Control for Fish Only

[ Location Numbers prior to 1984 0 0

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TABLE 2.1-B OCONEE RADIOLOCICAL MONITORING PROGRAM SAMPLING LOCATIONS 0 (TLD SITES) 0 Site Location* Distance Sector Site Location* Distance Sector MICROWAVE TOWER, SIX 0 020 SITE BOUNDARY 0.16 miles N 040 MILE 4.74 miles E S 021 SITE BOUNDARY 0.25 miles NNE 041 JCT HWY 101 & 133 4.25 miles ESE LAWRENCE CHAPEL 022 SITE BOUNDARY 0.53 miles NE 042 CHURCH, HWY 133 4.93 miles SE 0 HWY 291 AT S 023 SITE BOUNDARY 0.93 miles ENE 043 ISSAQUEENA PARK HWY 130 AT LITTLE RIVER 4.09 miles SSE 0 024 SITE BOUNDARY 0.81 miles E 044 DAM TERMINUS OF HWY 588 3.96 miles S 025 SITE BOUNDARY 0.42 miles ESE 045 AT CROOKED CREEK 4.78 miles SSW 0 HWY 188 AT 026 SITE BOUNDARY 0.34 miles SE 046 CROOKED CREEK 4.61 miles SW 0 NEW HOPE CHURCH, HWY 027 SITE BOUNDARY 0.49 miles SSE 047 188 3.58 miles WSW 028 SITE BOUNDARY 0.46 miles S 048 JCT HWY 175 & 188 3.64 miles W 0 029 SITE BOUNDARY 0.56 miles SSW 049 JCT HWY 201 & 92 3.60 miles WNW 0 030 SITE BOUNDARY 0.42 miles SW 050 STAMP CREEK LANDING, END OF HWY 92 3.53 miles NW 0 HWY 128, 1 MILE N OF 031 SITE BOUNDARY 0.27 miles WSW 051 HWY 130 4.64 miles NNW 0 DPC BRANCH OFFICE SITE 076 SITE BOUNDARY 0.19 miles W 052 - PICKENS 12.4 miles ENE 0 032 SITE BOUNDARY 0.19 miles WNW 053 DPC BRANCH OFFICE SITE

- LIBERTY 11.7 miles E POST OFFICE - HWY 93 S 033 SITE BOUNDARY 0.21 miles WNW 054 NORRIS CLEMSON 8.60 miles ESE 034 SITE BOUNDARY 0.22 miles NW 055 METEOROLOGY PLOT 9.27 miles SSE 0

035 SITE BOUNDARY 0.17 miles NNW 056 WATER TOWER - SENECA 7.30 miles SSW OCONEE MEMORIAL 0 036 MILE CREEK LANDING KEOWEE CHURCH, 4.32 miles N 057 HOSPITAL BRANCH RD SUBSTATION, 8.42 miles SW 037 HWY 327 4.85 miles NNE 058 C WALHALLA 9.39 miles WSW 0 038 CONVENIENCE MART, JCT HWY 183 & 133 4.24 miles NE 059 TAMASSEE DAR SCHOOL 9.20 miles NW 0 HWY 133, 1 MILE EAST CLEMSON 039 OF JCT HWY 183 & 133 4.02 miles ENE 081 C OPERATIONS CENTER 9.33 miles SE 0

C = Control 0

• 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

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0 TABLE 2.2-A 0

REPORTING LEVELS FOR RADIOACTIVITY 0 CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 0

Analysis Water Air Particulates Fish Milk Broadleaf 0 (pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) Vegetation 0 (pCi/m 3) (pCi/kg-wet)

H-3 20,000(a) 0 Mn-54 1,000 30,000 0 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 0

Zn-65 300 20,000 0 Zr-Nb-95 400 1-131 2 (b) 0.9 3 100 0

Cs-134 30 10 1,000 60 1,000 0 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 0 0

(a) For drinking water samples only. This is 40CFR Part 141 value.

(b) If low-level 1-131 analyses are performed.

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0 TABLE 2.2-B 0 REMP ANALYSIS FREQUENCY 0 Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic _1-131 Beta S Air Radioiodine Air Particulate Weekly Weekly X

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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 1-131 analysis will be performed if abnormal releases occur which could reasonably result in> I pCi/liter of 1-131 in drinking water. An LLD of I pCi/liter will be required for this analysis.

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MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION 0

0 Analysis Water Air Fish Milk Broadleaf Sediment (pCi/liter) Particulates (pCi/kg-wet) (pCi/liter) Vegetation (pCi/kg-dry) 0 or Gases (pCi/m )

3 (pCi/kg-wet)

Gross Beta 4 0.01 0 H-3 2000 0 Mn-54 Fe-59 15 30 130 260 0 Co-58, 60 15 130 0 Zn-65 Zr-95 30 15 260 0 Nb-95 15 1-131 15(a) 0.07 1 60 0 Cs-134 15 0.05 130 15 60 150 0 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 0

0 (a) LLD for low-level 1-131 analyses is 1 pCi/liter if performed 0

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• 3.0 INTERPRETATION I OF RESULTS

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Review of 2009 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 2009 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 aglysis methods or changes in the reporting of the results.

• Evaluation for significant iret(ds 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, 0 Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140, and La-140. Drinking water gross Sbeta 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 2009.

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 2009 was 2.66% 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 0background), 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 2009.

Similarly, there was no significant increase in ambient background radiation levels in the surrounding areas.

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0 3.1 AIRBORNE RADIOIODINE AND PARTICULATES 0

In 2009, 312 radioiodine and particulate samples were analyzed, 260 from five indicator locations and 52 from the control location. Particulate samples were analyzed weekly for gamma and gross beta. Radioiodine samples received a weekly gamma analysis.

S There was no detectable 1-131 in air samples in 2009. Table 3.1-A gives the highest indicator location annual mean and control location annual mean for 1-131 since the preoperational period. *,4 The table shows similar concentrations for both the indicator and control locations and the activities decreasing from early in the operational history of 0 the sinceplant. No 1-131 has been detected 1994.,*H-i/L ,

Cs-137 was not detected in air radioiodine samples in 2009. 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 2009. 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.

0 K-40 and Be-7 are the naturally occurring radionuclides that were observed in air samples. 5 0

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• Table 3.1-A Mean Concentration of Air Radioiodine (1-131)

Year Indicator Location (eCi/m3) Control Location (eCi/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 8.1OE-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.OOEO 1989 4.99E-4 0.OOEO 1990 0.OOEO 0.OOEO 1991 0.00E0 0.OOEO 1992 0.OOEO 0.OOEO

• 1993 0.OOEO 0.OOEO 1994 1.03E-2 0.OOEO 1995 0.OOEO 0.OOEO 1996 0.OOEO 0.OOEO 1997 0.OOEO 0.OOEO 1998 0.OOEO 0.OOEO 1999 0.OOEO 0.OOEO 2000 0.OOEO 0.00E0 2001 0.OOEO 0.OOEO 2002 0.OOEO 0.OOEO

• 2003 0.OOEO 0.OOEO 2004 0.OOEO 0.OOEO 2005 0.OOEO 0.OOEO 2006 0.OOEO 0.OOEO 2007 0.OOEO 0.OOEO 2008 0.00E0 0.00E0 2009 0.OOEO 0.OOEO O.OOEO = no detectable measurements 1979 - 1986 mean based on all net activity results 0

0 0

0 0

• Section 3 -Page 3 0

S 0

0 Figure 3.1 S

pCi/m 3 Concentration of Gross Beta in Air Particulate 0 4.500E-2 4.OOOE-2 3.500E-2 0

S 3.000E-2 _

0 2.500E-2 _

0 2.OOOE-2 - -mw_____

1.500E-2 0

1.00011-2 0

5.OOOE-3 0

O.O00E+O 1996 1998 2000 2002 2004 2006 2008 1 --- Indicator Location -- Control Location S

0 Pre-operationalsample resultsrangedfrom 0.04 tol.46 pCi/m3 There is no reportinglevelfor gross beta in airparticulate 0

Table 3.1-B Mean Concentration of Gross Beta in Air Particulate Monitoring Period Indicator Location (pCi/m 3) Control Location (pCi/mr3) 1996 3.87E-2 3.69E-2 1997 2.87E-2 1998 2.47E-2 2.92E-2 1.56E-2 0

1999 2.85E-2 2.23E-2 0 2000 2001 2.38E-2 2.05E-2 1.85E-2 1.94E-2 0

2002 2.01E-2 1.84E-2 0 2003 2004 1.86E-2 1.92E-2 1.82E-2 1.90E-2 0

2005 1.95E-2 1.91E-2 0 2006 2007 2.09E-2 2.31E-2 2.OOE-2 2.131E-2 0

2008 2.08E-2 2.04E-2 Average (1999 - 2008) 2.15E-2 1.97E-2 2009 1.82E-2 1.80E-2 Section 3 - Page 4

0 3.2 DRINKING WATER 0

0 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 0 analysis. Two indicator locations and a control location were sampled; however, only one of the 0 indicator locations is downstream of the effluent release point.

0 Table 3.2 lists the highest indicator location annual mean and control location annual mean for S gross beta results since the preoperational period. The indicator location had an average concentration of 1.37 pCi/liter in 2009, and the control location had a concentration of 1.19 0 pCi/liter. The 2008 indicator mean was 1.82 pCi/liter. The table shows that 2009 gross beta 0 levels in drinking water are slightly lower than preoperational concentrations. The dose for consumption of water was less than one mrem per year, historically and for 2009; therefore low-S level iodine analysis is not required.

Tritium was detected in four of the twelve composite samples during 2009. The 2009 mean 0 indicator location 066 concentration was 415 pCi/liter, which is 2.08% of the reporting level.

Table 3.2 and Figure 3.2 show the highest indicator and control location annual means for 0 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 0 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.

0 There were no gamma emitting radionuclides identified in drinking water samples in 2009.

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

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

Figure 3.2 Current reporting level implemented 1984 0

Concentration of Tritium in Drinking Water 0 ___ 4 + 4 ______ + +

• 0 4000 1--

35a00 1 - 1-3000 2500 -f -f +----4 + I F I I 4-2000 1500 1000 500 m I* m E 1974 1976 1979 1982 1985 1988 1994 1997 2000 2003 2006 2009

--- Indicator Location Control Location - 20 % Reporting Level Section 3 - Page 5

0 0

0 0

Table 3.2 Mean Concentrations of Radionuclides in Drinking Water 0

Gross Beta (pCi/I) Tritium (pCi/I) 0 Year Indicator Control. Indicator Control 0 Location Location Location Location Preoperational ending Jan. 1971 3.03 5.90 Analysis not required 0

Preoperational ending Jan. 1973 3.58 4.94 Analysis not required 0 Feb. 1973 - June 1973 June 1973 -Dec. 1973 Qualitative results reported 7.15 21.78 Analysis not required Analysis not required 0

Jan. 1974 - June 1974 3.13 6.98 Analysis not required 0 July 1974 - Dec. 1974 2.24 2.02 525 330 0 Jan. 1975 - June 1975 1.98 1.59 600 300 July 1975 - Dec. 1975 2.01 1.22 2990 505 0 1976 2.38 2.00 2196 224 0 1977 2.70 2.30 1200 290 1978 2.56 2.17 1050 333 0

1979 1.83 1.36 576 235 0 1980 1981 1.86 1.98 1.63 1.88 660 830 200 127 0

1982 2.04 1.45 643 153 0 1983 1.85 1.54 937 220 0 1984 1.87 1.08 765 145 1985 2.14 1.16 856 210 0 1986 1.91 1.04 1240 503 0 815 680 1987 1988 2.00 2.00 1.20 1.40 1570 0.00 0

1989 2.30 1.80 1350 559 0 1990 1991 3.00 1.80 2.70 1.40 0.00 558 0.00 0.00 0

1992 3.20 1.60 0.00 0.00 0 1993 2.10 1.90 0.00 0.00 0 1994 1.90 2.10 0.00 0.00 1995 5.10 2.90 248 0.00 0 1996 2.07 1.77 214 0.00 0 2.52 2.23 194 0.00 1997 1998 2.48 1.70 0.00 0.00 0

1999 1.73 1.49 185 0.00 0 2000 2001 2.07 1.75 1.68 1.29 251 390 0.00 0.00 0

2002 1.61 1.21 338 0.00 0 2003 1.51 1.05 266 0.00 0 2004 1.58 1.25 225 0.00 2005 1.28 1.37 377 0.00 0 2006 1.54 1.75 340 0.00 0 2007 1.58 1.08 402 0.00 2008 1.82 1.25 372 0.00 0

2009 1.37 1.19 415 0.00 0 0.00 =no detectable measurements 1989 - Clemson water plant closes; nearest downstream plant is Anderson.

0 1979 - 1986 mean based on all net activity results 0 0

0 Section 3 - Page 6 0 0

0

0 0

O 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 0 location were sampled. The indicator location is near the liquid effluent release point.

0Tritium was detected in the four indicator location samples. The 2009 average concentration was

• 4,678 pCi/liter. The individual samples ranged from 1,440 pCi/liter to 9,760 pCi/liter. The 2008

~samples. mean concentration was 9,430 pCi/liter. Tritium was not detected in any control surface water s 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 0any station related activity during 2009. 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 2009 did not reveal any 0increasing trends.

0 K-40 and Be-7 are the naturally occurring radionuclide observed in surface water samples in 2009.

0 0

0 0

0 S

0 0

0 0

0 O ~Section 3 -Page 7 0

0 0

0 0

Figure 3.3 0 0

pCi/liter Concentration of Tritium in Surface Water 0 60000 0

0 50000 ----

0 40000 _

0 0

30000 - 0 0

20000 -

0 10000- 1 ,, .,-

0 0

0 1969 1972 1975 1977 1980 1983 1986 1989 1992 1995 1998 2001 2004 2007 0

-U- Indicator Location - Control Location 0 0

There is no reportinglevelfor Tritium in surface water 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

S 0

0 0

0 0

Section 3 - Page 8 0 0

0 0

0

• Table 3.3 Mean Concentrations of Radionuclides in Surface Water 0

Year Co-58 (pCi/l) Co-60 (pCi/I) 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.OOEO 1974 0.OOEO 1.32E1 0.OOEO 1.60E1 1.99E3 Jan. 1975 - June 1975 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.56E4 0 July 1975 - Dec. 1975 0.00E0 1.34E1 0.00E0 0.OOEO 5.52E4 1976 1.08E2 3.30E1 0.OOEO 3.50E1 2.95E4 1977 2.60E1 1.80El 0.00E0 3.10EI 2.90E3 1978 2.96E2 0.00E0 0.OOEO 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 1iOEO 6.1OE-1 1.70E0 3.90E0 7.21 E3 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-I 1.05E4 1986 3.28E0 1.23E0 1.14E0 3.07E- 1 1.26E4

• 1987 5.10E1 3.40E0 4.OOEO 0.OOEO 7.08E3 1988 6.20E0 5.OOEO 2.50E0 3.50E0 1.10E4 1989 5.30E0 3.OOEO 0.OOEO 3.40E0 1.02E4 1990 1.70E0 1.60E0 0.OOEO 0.OOEO 1.03E4 1991 5.40E0 0.OOEO 0.OOEO 0.OOEO 5.76E3 1992 2.50E0 0.OOEO 0.OOEO 0.OOEO 6.22E3 1993 0.OOEO 0.OOEO 0.OOEO 0.OOEO 8.62E3 1994 0.OOEO 0.OOEO 0.OOEO 0.OOEO 5.75E3 1995 0.OOEO 0.OOEO 0.OOEO 0.OOEO 6.65E3 1996 0.OOEO 0.OOEO 0.OOEO 0.OOEO 4.54E3

• 1997 0.OOEO 0.OOEO 0.OOEO 0.OOEO 5.50E3 1998 0.OOEO 0.OOEO 0.OOEO 0.OOEO 3.35E3 1999 2.73E1 0.OOEO 0.OOEO 0.OOEO 1.13E4

• 2000 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.48E4 2001 0.OOEO 0.OOEO 0.OOEO 0.OOEO 7.43E3 2002 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.00E4 2003 0.OOEO 0.OOEO 0.OOEO 0.OOEO 4.77E3 2004 0.OOEO 0.OOEO 0.OOEO O.O0EO 3.86E3 2005 0.OOEO 0.OOEO 0.OOEO 0.OOEO 5.15E3

• 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO 6.72E3 2007 0.OOEO 0.OOEO 0.OOEO 0.OOEO 9.91E3 2008 0.OOEO 0.OOEO 0.OOEO 0.OOEO 9.43E3 2009 0.OOEO 0.OOEO 0.OOEO 0.OOEO 4.68E3 O.OOEO = no detectable measurements 1979-1986 mean based on all net activity results S

0 0

0 0

O Section 3 - Page 9 0

0 0

0 3.4 MILK 0 0

Gamma spectroscopy and low level iodine analysis was performed on 26 milk samples collected in 2009. One control location was sampled. No indicator dairies were identified by the 2009 0 land use census. 0 0

There were no gamma emitting radionuclides identified in milk samples in 2009. Cs-137 is 0

the only radionuclide, other than naturally 0 occurring, reported in milk samples since 0 1988. Cs-137 in milk is not unusual. It is a 0 constituent of nuclear weapons test fallout and has been observed in samples from indicator 0

and control locations in previous years. 0 0

Table 3.4 lists the highest indicator location annual mean and control location annual mean 0

for Cs-137 since the preoperational period. 0 The table shows similar concentrations for 0 both indicator and control locations. 0 K-40 is a naturally occurring radionuclide observed in milk samples in 2009. 0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 Section 3 - Page 10 0

Table 3.4 Mean Concentration of Radionuclides in Milk 0

• Year Cs-137 Indicator (pCi/i) Cs-137 Control (pCi/I)

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 1.1IEl 0.00E0 Jan. 1975-June 1975 1.5IEJ 9.45E0 July 1975 - Dec. 1975 0.00E0 0.00E0 1976 1.80El 7.47E0 1977 0.OOEO 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.OOEO 1991 5.OOEO 0.OOEO 1992 6.60E0 O.00E0 1993 0.OOEO 0.OOEO

• 1994 0.OOEO 1.80E0 1995 2.30E0 2.OOEO 1996 0.OOEO 4.1OEO 1997 O.O0EO 0.OOEO 1998 0.OOEO 0.OOEO 1999 0.OOEO 0.OOEO 2000 0.OOEO 0.OOEO 2001 0.OOEO 0.OOEO 2002 0.OOEO 0.OOEO 2003 0.OOEO 0.OOEO 2004 0.OOEO 0.OOEO 2005 0.OOEO 0.OOEO 2006 NO INDICATOR LOCATION 0.OOEO 2007 NO INDICATOR LOCATION 0.OOEO 2008 NO INDICATOR LOCATION 0.OOEO 2009 NO INDICATOR LOCATION 0.OOEO 0 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 0-04-01179. Location 071 was designated as the new control site effective with the 7/12/2005 sampling. No indicator dairies were identified by the 2009 land use census.

S 0

0 O ~Section 3 - Page 11 0

0 0

3.5 BROADLEAF VEGETATION 0

Gamma spectroscopy was performed on 48 broadleaf vegetation samples during 2009. Three 0 indicator locations and one control location were sampled. There were no gamma emitting S radionuclides identified in vegetation samples in 2009.

S Cs-137 is the only radionuclide, other than naturally occurring, reported in vegetation S 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 0

test fallout and has been observed in samples from indicator and control locations in previous S years. Table 3.5 lists the highest indicator location annual mean and control location annual mean for Cs-137 since early in the station's operational history. Visual inspection of the 0 tabular data did not reveal any increasing trends. 0 K-40 and Be-7 are naturally occurring radionuclides that were observed in broadleaf 0 vegetation samples in 2009. 0 Figure 3.5 S pCi/kg Concentration of Cs-137 inBroadleaf Vegetation 0 2500 0

2000 - - - - - - - - - - - - - - - - -

0 1500 - -

0 1000 - ___ _ __

S 0

0 S

1974 1976 1979 1982 1985 1988 1991 1994 1997 2000 2003 2006 2009 0

--- Indicator Location -*- Control Location -Reporting Level 0 0

0 0

0 S

Section 3 - Page 12

S 0

0

• Table 3.5 Mean Concentration of Radionuclides in Vegetation

• Year Cs-137 Indicator (pCi/kg) Cs-137 Control (pCi/kgl)

July 1974 - Dec. 1974 1.54E3 0.OOEO

• Jan. 1975 - June 1975 1.55E3 1.59E3

• July 1975 - Dec. 1975 0.00E0 0.OOEO 1976 0.OOEO 0.OOEO 1977 0.00E0 7.90E2

• 1978 1.19E2 8.19E1 l 1979 5.04E1 2.96E1 1980 2.80E1 1.55E1

• 1981 2.99E1 2.60E1

• 1982 2.42E1 2.62E 1 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.OOEO 1.08E2 1990 2.73E2 1.74E2

• 1991 2.20E1 1.45E2

• 1992 0.OOEO 1.46E2 1993 0.OOEO 1.49E2

• 1994 0.OOEO 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.OOEO 2000 1.06E2 0.OOEO

• 2001 3.19E1 0.OOEO

• 2002 8.44E1 0.OOEO 2003 0.OOEO 0.OOEO

• 2004 0.OOEO 5.96E1

• 2005 4.51E1 4.11EI 2006 1.77E1 0.OOEO

• 2007 0.OOEO 0.OOEO

• 2008 0.OOEO 0.OOEO

• 2009 0.OOEO 0.OOEO 0.OOEO = no detectable measurements Only qualitative results reported prior to 1974 Control location changed to 073 in 1984 S Control location 081 added in 1998 Control location 073 was removed in 1999 1979 - 1986 mean based on all net activity results O Section 3 - Page 13

0 3.6 FISH 0 In 2009, gamma spectroscopy was performed on 12 fish samples. Two downstream indicator and one control location were sampled. Cs-137 was identified in all eight of the indicator location samples. Cs-137 was detected in three of th6 four control location samples at a mean concentration of 14.6 pCi/kg.

S The highest average indicator concentration for Cs-137 was 26.8 pCi/kg (1.34% of reporting level). The highest individual indicator sample concentration for Cs-137 was 51.4 pCi/kg (2.57% of reporting level).

0 Co-58 was identified in one of the eight indicator location samples at a concentration of 9.01 pCi/kg (0.03% of reporting level). Co-58 was not identified in any of the control samples.

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.

0 Table 3.6 lists the highest indicator location annual means since the preoperational period for radionuclides detected in 2009.

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.

S 0

0 0

0 0

0 0

Section 3 -Page 14 0 0

0

0 S

Figure 3.6-1 0 Concentration of Cs-137 in Fish pCi/kg pCi/kg Concentration of Cs-137 in Fish 0 2500=

0 2000 S 1500 1000 500 0

1970 1974 1976 1978 1981 1984 1987 1990 1993 1996 1999 2002 2005 2008

-U-I--Indicator Location -O--Control Location -Reporting Level Reprtig Lvel I 1 -M Inicaor Lcaton

-*-Contol ocaion-0 0 Figure 3.6-2 0

0 pCi/kg Concentration of Cs-134 in Fish 700 0

0 600 - ___ __ _

0 500~

0 400 300 - _ - __ ______ __ _ _

200 ___ __

S 0 100 - ___- - - -

Illi 0 - -~ -- '4.I * -

1970 1974 1976 1978 1981 1984 1987 1990 1993 1996 1999 2002 2005 2008 1 Indicator Location --- Control Location - 50% Reporting Level Currentreportinglevels implemented 1984 Section 3 - Page 15

Table 3.6 Mean Concentrations of Radionuclides in Fish S

Year Co-58 (pCi/kg) Co-60 (pCi/kg) Cs-134 (pCi/kg) Cs-137 (pCi/kg)

Preop ending Jan. 1971 0.OOEO 0.00E0 0.00E0 1.46E2 Preop ending Jan. 1973 0.00E0 0.OOEO 0.OOEO 1.66E2 Feb. 1973 - June 1973 Qualitative results reported-no significant measurements above background July 1973 - Dec. 1973 0.OOEO 0.OOEO 0.OOEO 1.89E2 Jan. 1974 - June 1974 0.OOEO 0.OOEO 0.OOEO 2.47E1 July 1974 - Dec. 1974 0.OOEO 0.OOEO 0.OOEO 4.85E1 Jan. 1975 - June 1975 0.OOEO 0.OOEO 3.81E1 1.05E2 July 1975 - Dec. 1975 8.50E1 0.OOEO 7.OOEl 3.13E2 1976 5.70E1 1.14E2 7.73E1 1.66E2 1977 0.OOEO 0.OOEO 1.80E2 3.60E2 1978 3.27E2 0.00E0 3.31E2 0.OOEO 1979 1.91E0 1.56E1 9.26E1 3.88E2 1980 1.45E1 1.90E1 1.10E2 3.99E2 1981 2.25E1 1.49E1 .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 L.1OEl 7.93E1 2.85E2 1986 9.56E1 2.59E1 2.57E2 7.36E2 1987 1.63E2 6.30E 1 9.80E 1 3.93E2 1988 9.60E1 0.OOEO 7.20E1 2.60E2 1989 4.30E1 1.50El 8.60E1 3.36E2 1990 1.50El 0.OOEO 4.80E1 1.19E2 1991 4.59E1 0.OOEO 1.25E2 1.94E2 1992 6.10El 0.OOEO 4.80E1 1.36E2 1993 0.OOEO 0.OOEO 2.10E1 1.10E2 1994 0.OOEO 0.OOEO 2.80E1 1.05E2 1995 O.00E0 0.OOEO 3.10El 9.20E1 1996 0.OOEO 0.00E0 4.49E I 1.25E2 1997 0.OOEO 0.00E0 0.00E0 1.18E2 1998 0.OOEO 0.OOEO 0.OOEO 5.79E1 1999 0.OOEO 0.OOEO 0.00E0 1.04E2 2000 0.OOEO 0.OOEO 0.OOEO 7.54E1 2001 1.72EI O.OOEO 0.OOEO 9.92E1 2002 0.OOEO 0.00E0 0.OOEO 9.37E1 2003 5.02E1 0.OOEO 0.OOEO 6.04E1 2004 0.OOEO 0.OOEO 0.OOEO 5.29E1 2005 0.OOEO 0.00E0 0.OOEO 5.14E 1 2006 0.OOEO 0.OOEO 0.OOEO 5.58E1 2007 0.OOEO 0.OOEO 0.OOEO 4.10El 2008 0.OOEO 0.OOEO 0.OOEO 3.13E1 2009 9.01EO 0.OOEO 0.OOEO 2.68E1 O.OOEO = no detectable measurements 1979 - 1986 mean based on all net activity results 0

0 Section 3 - Page 16 5 S

S

0 0

0 0

0 3.7 SHORELINE SEDIMENT Gamma spectroscopy was performed on six sediment samples. Two downstream indicator 0 locations and one control location were sampled. Four samples were taken from indicator locations and two from the control location.

0 Cs-137 was identified in two of the four indicator location samples. Cs-137 was not 0 observed in any control location samples. The highest 2009 individual sample Cs-137 0 concentration was 69.7 pCi/kg. The highest 2008 individual sample Cs-137 concentration was 240 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 0 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 S 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 0 trends are apparent.

0 K-40 and Be-7 are naturally occurring radionuclides observed in shoreline sediment samples in 2009.

0 0

0 0

0 0

0 0

0 0

0 Section 3 - Page 17

0 Figure 3.7-1 0

0 0

0 0

S 0

S S

S 0

Figure 3.7-2 0 pCi/kg Concentration of Co-60 in Shoreline Sediment S

1000 S 900 - 0 800 ______

0 700 -_____ _____

0 600 0

500 -

400 ______ ___

300 - - 1___ _____

200 100 -- I t o t 0I i r i 067 _ onrloain0 2008 1984 1987 1990 1993 1996 1999 2002 2005 There are no reportinglevels 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-ll0m Sb-125 1984 1.1OE1 1.09E1 1.19El 0.OOEO 7.77E1 5.16E1 0.OOEO 0.OOEO 1985 9.39E0 1.27E0 4.79E0 0.OOEO 7.63E1 9.47E1 0.OOEO 0.OOEO 1986 2.24E1 1.62E1 2.50E1 0.OOEO 1.41E2 7.12E2 0.OOEO 0.OOEO 1987 5.40E1 4.70E2 5.07E2 0.OOEO 1.01E2 6.22E2 3.46E2 0.OOEO 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.OOEO 5.40E1 8.48E2 5.50E1 1.86E2 1990 3.40E1 8.OOEI 2.59E2 0.OOEO 4.50E1 5.36E2 1.71E2 9.OOE1 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.OOEO 5.60E1 3.31E2 1.69E2 2.08E2 1993 8.20E1 8.20E1 6.50E1 0.OOEO 3.20E1 1.36E2 5.63E1 1.11E2 1994 5.30E1 7.OOEI 1.49E2 0.OOEO 6.70E1 2.38E2 1.04E2 1.29E2 1995 1.43E2 3.90E1 2.40E1 0.00E0 1.1OEI 5.20E1 0.OOEO 0.OOEO 1996 0.OOEO 5.10El 0.00E0 0.OOEO 1.98E1 1.19E2 0.OOEO 0.OOEO 1997 0.OOEO 0.OOEO 0.OOEO 0.00E0 0.OOEO 1.06E2 0.00E0 0.OOEO 1998 0.OOEO 0.OOEO 0.00E0 0.OOEO 0.OOEO 1.01E2 0.00E0 0.OOEO 1999 6.96E1 0.00E0 0.OOEO 0.OOEO 0.OOEO 7.38E1 0.OOEO 0.OOEO 2000 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 8.54E1 O.OOEO 0.OOEO 2001 0.00E0 2.10E1 0.OOEO 0.00E0 0.00E0 1.20E2 0.00E0 0.OOEO 2002 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 6.96E1 0.OOEO 0.OOEO 2003 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.93E2 0.00E0 0.OOEO 2004 8.54E1 O.OOEO 0.00E0 0.OOEO 0.OOEO 9.56E1 0.OOEO 0.OOEO 2005 2.00E2 0.OOEO 0.OOEO 0.OOEO 0.OOEO 6.53E1 0.OOEO 0.OOEO 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 5.01El 0.OOEO 0.OOEO 2007 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2.97E2 0.OOEO 0.OOEO 2008 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.78E2 0.OOEO 0.OOEO 2009 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 6.97E1 0.OOEO 0.OOEO O.OOEO = no detectable measurements 1984-1986 mean based on all net activity results 0

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0 3.8 DIRECT GAMMA RADIATION 0 0

In 2009, 168 Thermoluminescent Dosimeters (TLD) were analyzed, 160 at indicator locations, 8 at the two control locations. TLDs are collected and analyzed quarterly. The 0 highest annual mean exposure for an indicator location was 110 milliroentgen. This TLD is located at indicator location 042, 4.93 miles from the station. The annual mean exposure for the control locations was 110 milliroentgen. S 0

Figure 3.8 and Table 3.8 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 0 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. 0 The calculated total body dose (from gaseous effluents) for 2009 was 2.02E-2 mrem, which is 0

0.02% of the average inner ring TLD values. Therefore, it can be concluded that discharges S from the plant had very little impact upon the measured TLD values.

The maximum measurement from TLDs at the Independent Spent Fuel Storage Installation ISFSI) was 699 milliroentgen per standard quarter. This is consistent with previous measurements. TLD measurements in the inner ring (site boundary) have remained relatively 0 constant.

Figure 3.8 0 mR/year 0

Direct Gamma Radiation (TLD) Results 250 0 0

200 0

0 150 50 0

1984 1987 1990 1993 1996 1999 2002 2005 2008

-A- Inner Ring -W- Outer Ring Control There is no reportinglevel for Direct Radiation (TLD)

Section 3 - Page 20

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• Table 3.8 Direct Gamma Radiation (TLD) Results 0

Year Inner Ring Average Outer Ring Average Control (mR*yr) (mRgyr) (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 Average (1999 - 2008) 78.5 87.3 107 2009 83.7 93.0 110 0

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0 3.9 LAND USE CENSUS 0 0

The Land Use Census was conducted during the growing season (6/15 - 6/16/2009) as 0 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 0 miles. No program changes were required based on the results of the census. 0 0

Table 3.9 Oconee 2009 Land Use Census Results 0 0

Sector Distance Sector Distance (Miles) (Miles) 0 Nearest Residence 2.98 Nearest Residence 1.96 0 N Nearest Milk Animal - S Nearest Milk Animal -

0 Nearest Residence 1.84 Nearest Residence 1.36 0 NNE Nearest Milk Animal - SSW Nearest Milk Animal 0 Nearest Residence 1.20 Nearest Residence 1.31 0 NE Nearest Milk Animal - sw Nearest Milk Animal -

0 Nearest Residence 1.34 Nearest Residence Nearest Milk Animal 1.77 0

ENE Nearest Milk Animal - WSW 0

Nearest Residence 1.64 Nearest Residence 1.76 0 E Nearest Milk Animal - W Nearest Milk Animal -

0 Nearest Residence 1.57 Nearest Residence 1.35

- WNW Nearest Milk Animal - 0 ESE Nearest Milk Animal 0

Nearest Residence 1.46 Nearest Residence 1.04 SE Nearest Milk Animal - NW Nearest Milk Animal - 0 Nearest Residence 1.54 Nearest Residence 1.06 0

SSE Nearest Milk Animal - NNW Nearest Milk Animal - 0

"-" indicates no occurrences within the 5 mile radius 0

• GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as 0 close as possible to the item of interest. 0 0

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Figure 3.9 Oconee Nuclear Station 2009 Land Use Census Map Legend Residence Public Roads

/ Rail Road

'*,., County Boundary Water Approximate location of features shown N

0 0.5 1 2 Miles Projection NCSP NAD27 June 2009

£ Section 3 - Page 23

4.0 EVALUATION OF DOSE

• 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS 0

Annual doses to maximum exposed individuals were estimated based on measured

• concentrations of radionuclides in 2009 ONS REMP samples. The primary purpose of estimating doses based on sample results is to allow comparison to effluent program dose 0estimates. Doses based on sample results were conservatively calculated in a manner as 0equivalent 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 0over 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 0 are contained in Table 4.1-B.

SNo 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 5drinking water source although surface water tritium concentrations are used in calculating 0doses from fish. REMP TLD exposure results are discussed in Section 3.8.

S The maximum environmental organ dose estimate for any single sample type (other than direct radiation from gaseous effluents) collected during 2009 was 7.54E-2 mrem to the child Sliver 0 from consuming drinking water and fish.

• 4.2 ESTIMATED DOSE FROM RELEASES 0

• Throughout the year, dose estimates were calculated based on actual 2009 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 5dose 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 0drinking water, fish and shoreline pathways. The effluent-based gaseous release doses report Section 4 - Page 1 0

0

0 noble gas exposure separately from iodine, particulate, and tritium exposure. For noble gas exposure there is no critical age group; as the maximum exposed individuals are assumed to receive the same doses, regardless of their age group. For iodine, particulate, and tritium exposure the effluent-based gaseous release doses are summations of the dose contributors from ground/plane, milk, inhalation and vegetation pathways.

4.3 COMPARISON OF DOSES 0 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.

0 In addition, 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 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 2009 environmental sample results was 7.54E-2 mrem to the child liver. The maximum total organ dose of 1.46E-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 2.75E-2 mrem to the child thyroid. No radioactivity was detected from gaseous pathways in environmental samples; therefore, there is no calculated dose.

0 Noble gas samples are not collected as part of the REMP, preventing an analogous comparison of effluent-based noble gas exposure estimates.

The doses calculated do not exceed the 40CFRI90 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.

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TABLE 4.1-A Page 1 of 3 OCONEE NUCLEAR STATION 2009 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON 0 LIQUID RELEASE PATHWAY 0

Environmental Critical Critical Maximum Dose (3)

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

Skin Environmental Teen Shoreline Sediment 063 (0.83 mi ESE) 1.83E-04 Skin Effluent Teen Shoreline Sediment Discharge Pt. 5.67E-04 Bone Environmental Child Fish 063 (0.83 mi ESE) 2.75E-02 Bone Effluent Child Fish Discharge Pt. 1.07E-02 Liver Environmental Child Drinking Water 066 (18.9 mi SSE) 7.54E-02 Liver Effluent Adult Fish Discharge Pt. 6.46E-02 T. Body Environmental Adult Drinking Water 066 (18.9 mi SSE) 5.97E-02 T. Body Effluent Adult Fish Discharge Pt. 6.11E-02 0

Thyroid Environmental Child Drinking Water 066 (18.9 mi SSE) 4.89E-02 0 Thyroid Effluent Child Drinking Water 18.9 mi SSE 5.17E-02 Kidney Environmental Child Drinking Water 066 (18.9 mi SSE) 5.75E-02 0 Kidney Effluent Child Drinking Water 18.9 mi SSE 5.49E-02 0 Lung Environmental Child Drinking Water 066 (18.9 mi SSE) 5.20E-02 Lung Effluent Child Drinking Water 18.9 mi SSE 5.21E-02 0

0 GI-LLI Environmental Child Drinking Water 066 (18.9 mi SSE) 4.97E-02 GI-LLI Effluent Adult Fish Discharge Pt. 1.46E-01 S

0 (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.

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

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GASEOUS RELEASE PATHWAY 0

IODINE, PARTICULATE, and TRITIUM 0

Critical Maximum Dose (3)

Organ Effluent Dataor Environmental Critical Age (1) Pathway (2) (mrem) 0 Skin Environmental - - 0.OOE+00 Skin Effluent All Ground Plane 1.0 mi. SW 9.32E-06 S Bone Environmental - - 0.OOE+00 Bone Effluent Child Vegetation 1.0 mi. SW 4.22E-05 0 0

Liver Environmental - 0.OOE+00 Liver Effluent Child Vegetation 1.0 mi. SW 2.02E-02 T. Body Environmental 0.OOE+00 T. Body Effluent Child Vegetation 1.0 mi. SW 2.02E-02 Thyroid Environmental 0.OOE+00 Thyroid Effluent Child Vegetation 1.0 mi. SW 2.75E-02 Kidney Environmental - 0.00E+00 Kidney Effluent Child Vegetation 1.0 mi. SW 2.02E-02 Lung Environmental - 0.00E+00 Lung Effluent Child Vegetation 1.0 mi. SW 2.01E-02 GI-LLI Environmental - 0.OOE+00 0 GI-LLI Effluent Child Vegetation 1.0 mi. SW 2.01E-02 0

0 (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.

0 (3) Maximum dose is a summation of the ground/plane, inhalation, milk and vegetation pathways. 0 0

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Air Environmental or Critical Critical Maximum Dose Dose Effluent Data Age Pathway (mrad)

Beta Environmental Not Sampled Beta Effluent N/A Noble Gas 1.0 mi. SW 1.42E-03 0

Gamma Environmental Not Sampled 0 Gamma Effluent N/A Noble Gas 1.0 mi. SW 3.34E-04 0

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Section 4 - Page 5

TABLE 4.1-B Maximum IndividualDose for 2009 based on EnvironmentalMeasurements (mrem) for Oconee Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 4.22E-02 4.22E-02 4.22E-02 4.22E-02 4.22E-02 4.22E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL O.OOE+00 4.22E-02 4.22E-02 4.22E-02 4.22E-02 4.22E-02 4.22E-02 O.OOE+00 Child Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 4.30E-02 4.30E-02 4.30E-02 4.30E-02 4.30E-02 4.30E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Broadleaf Vegetation O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fish 2.75E-02 3.24E-02 1.01E-02 5.90E-03 1.45E-02 8.99E-03 6.71E-03 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 3.28E-05 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 3.83E-05 TOTAL 2.75E-02 7.54E-02 5.31E-02 4.89E-02 5.75E-02 5.20E-02 4.97E-02 3.83E-05 Teen Airborne O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Drinking Water 0.OOE+00 2.24E-02 2.24E-02 2.24E-02 2.24E-02 2.24E-02 2.24E-02 0.OOE+00 Milk 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Broadleaf Vegetation 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Fish 2.19E-02 3.64E-02 1.76E-02 7.14E-03 1.70E-02 1.1OE-02 9.49E-03 0.OOE+00 Shoreline Sediment 0.OOE+00 O.OOE+00 1.57E-04 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 1.83E-04 TOTAL 2.19E-02 5.88E-02 4.02E-02 2.95E-02 3.94E-02 3.34E-02 3.19E-02 1.83E-04 Adult Airborne O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Drinking Water O.OOE+00 3.18E-02 3.18E-02 3.18E-02 3.18E-02 3.18E-02 3.18E-02 0.OOE+00 Milk O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Broadleaf Vegetation 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Fish 2.04E-02 3.73E-02 2.79E-02 9.28E-03 1.88E-02 1.24E-02 1.27E-02 0.OOE+00 Shoreline Sediment O.OOE+00 0.OOE+00 2.81E-05 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 3.28E-05 TOTAL 2.04E-02 6.91E-02 5.97E-02 4.11E-02 5.06E-02 4.42E-02 4.45E-02 3.28E-05 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6

Oconee Nuclear Station Dosefrom Drinking Water Pathwayfor 2009 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 1.OSE-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 066 415 0.OOE+00 4.22E-02 4.22E-02 4.22E-02 4.22E-02 4.22E-02 4.22E-02 Dose Commitment (mrem) = 0.OOE+00 4.22E-02 4.22E-02 4.22E-02 4.22E-02 4.22E-02 4.22E-02 Section 4 - Page 7

Oconee Nuclear Station Dosefrom Drinking Water Pathwayfor 2009 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GULLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA 8.98E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+/-00 0.OOE+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+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.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+400 0.OOE+00 0.OOE+/-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.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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 O.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+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.OOE+00 0.OOE-i00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+/-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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BaLa-140 8.3 1E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0.00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+/-00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 066 415 0.OOE+00 4.30E-02 4.30E-02 4.30E-02 4.30E-02 4.30E-02 4.30E-02 Dose Commitment (mrem) = 0.OOE+00 4.30E-02 4.30E-02 4.30E-02 4.30E-02 4.30E-02 4.30E-02 Section 4 - Page 8 000000000000000000000.000000000000000000000oo

0000000000000000000000000000000000000000000o Oconee Nuclear Station Dose from Fish Pathwayfor 2009 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/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/! = 4678 pCi/i x 0.9 = 4210 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.OOE-06 NO DATA 8.98E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 063 9.01 0.00E+00 1.12E-04 3.43E-04 0.OOE+00 0.OOE+00 0.OOE+00 6.53E-04 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 2.34E-04 3.84E-04 8.1OE-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 063 12.2 2.75E-02 2.63E-02 3.89E-03 0.OOE+00 8.59E-03 3.09E-03 1.65E-04 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 063.1 4210 0.OOE+00 5.90E-03 5.90E-03 5.90E-03 5.90E-03 5.90E-03 5.90E-03 Dose Commitment (mrem) = 2.75E-02 3.24E-02 l.OtE-02 5.90E-03 1.45E-02 8.99E-03 6.71E-03 Section 4 - Page 9

Oconee Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2009 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 2

Dose Factor (mrem/hr per pCi/m ) x Shore Width Factor x Sediment Surface Mass (kg/M 2 ) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration 2

(mrem/hr per pCi/m ) 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 69.7 3.28E-05 3.83E-05 Dose Commitment (mrem) = 3.28E-05 3.83E-05 Section 4 - Page 10

Oconee NuclearStation Dose from Drinking Water Pathwayfor 2009 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 o.ooE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 5.76E-06 2.OOE-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-400 0.OOE+/-00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE÷00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 066 415 0.OOE+00 2.24E-02 2.24E-02 2.24E-02 2.24E-02 2.24E-02 2.24E-02 Dose Commitment (mrem)= 0.OOE+00 2.24E-02 2.24E-02 2.24E-02 2.24E-02 2.24E-02 2.24E-02 Section 4 - Page 11

Oconee Nuclear Station Dosefrom Fish Pathwayfor 2009 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/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/1 = 4678 pCi/I x 0.9 = 4210 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 063 9.01 0.OOE+00 1.40E-04 3.23E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.93E-03 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.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 5.76E-06 2.OOE-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0,OOE+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.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 063 12.2 2.19E-02 2.91 E-02 1.01E-02 0.00E+00 9.90E-03 3.85E-03 4.14E-04 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 063.1 4210 0.OOE+00 7.14E-03 7.14E-03 7.14E-03 7.14E-03 7.14E-03 7.14E-03 Dose Commitment (mrem) = 2.19E-02 3.64E-02 1.76E-02 7.14E-03 1.70E-02 1.1OE-02 9.49E-03 Section 4 - Page 12 0 0 0 *000000000000 0 0 0 0 000 0 0 *0 00 0 0

• eO@@@@eO@O*@@O0e0e0eO@O@@O0eOOO0e@O0e@@e@@@

Oconee NuclearStation Dosefrom Shoreline Sediment Pathwayfor 2009 Data Maximum Exposed Teen Shoreline Recreation = 67 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass: 40 kg/m 2 Teen Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m 2) x Shore Width Factor x Sediment Surface Mass (kg/m 2) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground M ean Concentration 2

(mrem/hr per pCi/m ) Indiicator Sediment (mrem)

Radionuclide T. Body Skin Loc ation (pCi/kg) T. Body Skin Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.OOE+00 0.OOE+00 Cs-137 4.20E-09 4.90E-09 063 69.7 1.57E-04 1.83E-04 Dose Commitment (mrem) = 1.57E-04 1.83E-04 Section 4 - Page 13

Oconee Nuclear Station Dose from Drinking Water Pathwayfor 2009 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (i) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+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.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-s00 0.OOE+00 0.OOE+00 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOEi-00 0.OOE+00 0.OOE+00 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 066 415 0.OOE+00 3.18E-02 3.18E-02 3.18E-02 3. 18E-02 3. 18E-02 3.18E-02 Dose Commitment (mrem) = 0.OOE+00 3.18E-02 3.18E-02 3.18E-02 3.18E-02 3.18E-02 3.18E-02 Section 4 - Page 14 00000000000000000000000000000000000900000000

Oconee NuclearStation Dosefrom Fish Pathwayfor 2009 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/I = 4678 pCi/I x 0.9 = 4210 pCi/kg Usage (intake in one year) = 21 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Radionuclide Bone Liv'er 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 7.45EE-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 063 9.01 0.OOE+00 1.41E-04 3.16E-04 0.OOE+00 0.OOE+00 0.OOE+00 2.86E-03 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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.14EE-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 4.84E-06 1.541 -05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 6.22E-05 1.481 -04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 7.97E-05 1.091 -04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 063 12.2 2.04E-02 2.79E-02 1.83E-02 0.OOE+00 9.48E-03 3.15E-03 5.4 1E-04 H-3 NO DATA 1.051 -07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 063.1 4210 0.OOE+00 9.28E-03 9.28E-03 9.28E-03 9.28E-03 9.28E-03 9.28E-03 Dose Commitment (mrem) = 2.04E-02 3.73E-02 2.79E-02 9.28E-03 1.88E-02 1.24E-02 1.27E-02 Section 4 - Page 15

Oconee Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2009 Data Maximum Exposed Adult Shoreline Recreation = 12 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass: 40 kg/mr Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m 2 ) x Shore Width Factor x Sediment Surface Mass (kg/M 2) x Sediment Concentration (pCi/kg)

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

(mrem/hr per pCi/m 2) 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 69.7 2.81E-05 3.28E-05 Dose Commitment (mrem) = 2.81E-05 3.28E-05 Section 4- Page 16

• 0ooe000e@OQOe@00@O@@e00000o0000000o00000000

0 5.0 QUALITY ASSURANCE 5.1 SAMPLE COLLECTION 0

EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures.

5.2 SAMPLE ANALYSIS 0

EnRad Laboratories performed the environmental sample analyses as specified by approved analysis procedures. EnRad

• Laboratories is located in Huntersville, North Carolina, at Duke Energy Corporation's

• Environmental Center.

Duke Energy Corporation's 5.3 DOSIMETRY ANALYSIS Environmental Center 0The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

0 5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 0*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 0used to monitor instrument performance.

S 5.4.2 CALIBRATION VERIFICATION National Institute of Standards and Technology (NIST) standards that represent 0counting geometries are analyzed as unknowns at various frequencies ranging

• from weekly to annually to verify that efficiency calibrations are valid. The 5frequency is dependent upon instrument use and performance. Investigations are

• performed and documented should calibration verification data fall out of limits.

S 0

S S

• Section 5 -Page 1 0

0

0 0

0 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 0 analyses.

0 5.5 DUKE ENERGY INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Energy Nuclear Generation Department Intercomparison Program during 2009. 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 2009 is documented in Table 5.0-A.

5.6 ERA PROFICIENCY TESTING 0 0

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 2009 is documented in Table 5.0-B.

5.7 DUKE ENERGY AUDITS 0

The Oconee Radiation Protection Section was not audited by the Quality Assurance Group in 2009, but was audited in 2008 (reference 6.14). There were some REMP safety enhancements identified as a result of the 2008 audit.

EnRad Laboratories was not audited by the Quality Assurance Group in 2009, but was audited in 2008 (reference 6.15). There were some REMP recommendations as a result of the 2008 audit.

5.8 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS 0

The Oconee Nuclear Station Radiological Environmental Monitoring Program was not audited by the NRC in 2009. The program was audited by the NRC in 2008 (reference 6.12). No findings were noted in the 2008 report.

5.9 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM 0 0

Oconee Nuclear Station routinely participates with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) in an Section 5 -Page 2 0

0 0

0 0

0 0 intercomparison program. The Memorandum of Agreement (MOA) between SC DHEC and Duke Energy describes the sampling frequency and analysis parameters for drinking water, surface water, milk, fish, vegetation, and shoreline sediment samples collected by 0 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.

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

0 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.

0 Nuclear Technology Services irradiates environmental dosimeters quarterly and 0 sends them to the Radiation Dosimetry and Records group for analysis of the 0 unknown estimated delivered exposure. A summary of the Nuclear Technology 0 Services Intercomparison Report is documented in Table 5.0-C.

S 5.10.2 INTERNAL CROSSCHECK (DUKE ENERGY) 0 0 Radiation Dosimetry and Records participates in a quarterly TLD intracomparison 0 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 S (Duke Energy) Result is documented in Table 5.0-C.

0 0

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0 Section 5 - Page 3

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0 TABLE 5.0-A 0 DUKE ENERGY 0 INTERLABORATORY COMPARISON PROGRAM 0 2009 CROSS-CHECK RESULTS FOR 0 ENRAD LABORATORIES 0 Cross-Check samples are normally analyzed a minimum of three times. A status of"3 Pass" indicates that all 0 three analyses yielded results within the designated acceptance range. A status of"I Pass" indicates that one 0 analysis of the cross check was performed 0

If applicable, footnote explanations are included following this table. 0 Gamma in Water 3.5 liters 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value pCi/I pCi/I pCi/I Status 0

3/5/2009 Q091GWL Cr-51 1.54-2.73 E5 2.05 E5 2.06 E5 3 Pass 0 Mn-54 4.68- 8.30 E4 6.24 E4 6.47 E4 3 Pass 0 Co-58 4.88- 8.65 E4 6.50 E4 6.52 E4 3 Pass 0 Fe-59 4.40-7.80 E4 5.87 E4 6.15 E4 3 Pass 0 Co-60 5.08-9.02 E4 6.78 E4 7.05 E4 3 Pass 0

Zn-65 5.79 - 10.26 E4 7.72 E4 8.01 E4 3 Pass Cs-134 3.38-5.99 E4 4.50 E4 4.13 E4 3 Pass 0

Cs-137 3.96-7.03 E4 5.28 E4 5.05 E4 3 Pass 0

Ce-141 4.55- 8.07 E4 6.07 E4 5.99 E4 3 Pass 0 0

7/29/2009 Q093GWS Co-57 1.22-2.16 E5 1.62 E5 1.73 E5 2 Pass 0 Co-60 1.88-3.33 E5 2.50 E5 2.65 E5 2 Pass 0 Y-88 1.22-2.16 E5 1.62 E5 1.63 E5 2 Pass 0

Sn-1l3 1.91-3.38 E5 2.54 E5 2.46 E5 2 Pass Cs-137 3.28- 5.81 E5 4.37 E5 4.46 E5 2 Pass 0

0 0

Gamma in Water 1.0 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status 0 pCi/I pCi/I pCi/I 3/5/2009 Q091GWL Cr-51 1.54-2.73 E5 2.05 E5 2.04 E5 3 Pass 0

Mn-54 4.68-8.30 E4 6.24 E4 6.53 E4 3 Pass 0 Co-58 4.88-8.65 E4 6.50 E4 6.48 E4 3 Pass 0 Fe-59 4.40-7.80 E4 5.87 E4 6.17 E4 3 Pass 0 Co-60 5.08- 9.02 E4 6.78 E4 6.96 E4 3 Pass 0 Zn-65 5.79 - 10.26 E4 7.72 E4 7.98 E4 3 Pass 0 Cs-134 3.38- 5.99 E4 4.50 E4 4.03 E4 3 Pass 0

Cs-137 3.96-7.03 E4 5.28 E4 5.03 E4 3 Pass Ce-141 4.55- 8.07 E4 6.07 E4 5.94 E4 3 Pass 0

0 0

Section 5 - Page 4 0 0

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0 Gamma in Water 1.0 liter, continued 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status 0 pCi/I pCi/l pCi/I 7/29/2009 Q093GWS Co-57 1.22-2.16 E5 1.62 E5 1.64 E5 3 Pass Co-60 1.88-3.33 E5 2.50 E5 2.59 E5 3 Pass 0 Y-88 1.22-2.16 E5 1.62 E5 1.58 E5 3 Pass Sn-113 1.91-3.38 E5 2.54 E5 2.40 E5 3 Pass 0 Cs-137 3.28- 5.81 E5 4.37 E5 4.28 E5 3 Pass 0

Gamma in Water 0.5 liter 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/l pCi/I 0

3/5/2009 Q091GWL Cr-51 1.54-2.73 E5 2.05 E5 2.05 E5 3 Pass 0 Mn-54 4.68-8.30 E4 6.24 E4 6.35 E4 3 Pass Co-58 4.88-8.65 E4 6.50 E4 6.27 E4 3 Pass Fe-59 4.40-7.80 E4 5.87 E4 6.10 E4 3 Pass 0

Co-60 5.08- 9.02 E4 6.78 E4 6.94 E4 3 Pass 0 Zn-65 5.79 - 10.26 E4 7.72 E4 8.01 E4 3 Pass 0 Cs-134 3.38- 5.99 E4 4.50 E4 3.88 E4 3 Pass Cs-137 3.96-7.03 E4 5.28 E4 4.90 E4 3 Pass 0

Ce-141 4.55- 8.07 E4 6.07 E4 5.80 E4 3 Pass 0

0 7/29/2009 Q093GWS Co-57 1.22-2.16 E5 1.62 E5 1.61 E5 3 Pass Co-60 1.88-3.33 E5 2.50 E5 2.55 E5 3 Pass 0

Y-88 1.22-2.16 E5 1.62 E5 1.58 E5 3 Pass 0 Sn-1l3 1.91-3.38 E5 2.54 E5 2.36 E5 3 Pass 0 Cs-137 3.28-5.81 E5 4.37 E5 4.27 E5 3 Pass 0

Gamma in Water 0.25 liter 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status 0 pCi/l pCi/I pCi/l 0 3/5/2009 Q091GWL Cr-51 1.54-2.73 E5 2.05 E5 2.08 E5 3 Pass Mn-54 4.68- 8.30 E4 6.24 E4 6.51 E4 3 Pass 0 Co-58 4.88-8.65 E4 6.50 E4 6.43 E4 3 Pass 0 Fe-59 4.40-7.80 E4 5.87 E4 6.15 E4 3 Pass Co-60 5.08- 9.02 E4 6.78 E4 7.13 E4 3 Pass Zn-65 5.79 - 10.26 E4 7.72 E4 7.93 E4 3 Pass Cs-134 3.38- 5.99 E4 4.50 E4 4.00 E4 3 Pass Cs-137 3.96- 7.03 E4 5.28 E4 5.07 E4 3 Pass Ce-141 4.55- 8.07 E4 6.07 E4 5.97 E4 3 Pass Section 5 - Page 5

0 0

0 Gamma in Water 0.25 liter,continued 0 Reference Date Sample I.D. Nuclide Acceptance Range Reference Value Mean Reported Value Cross Check Status 0

pCi/l pCi/l pCi/I 0 7/29/2009 Q093GWS Co-57 1.22-2.16 E5 1.62 E5 1.58 E5 2 Pass 0 Co-60 1.88- 3.33 E5 2.50 E5 2.57 E5 2 Pass 0 Y-88 1.22-2.16 E5 1.62 E5 1.58 E5 2 Pass 0

Sn-113 1.91-3.38 E5 2.54 E5 2.32 E5 2 Pass Cs-137 3.28-5.81 E5 4.37 E5 4.13 E5 2 Pass 0

0 0

Gamma in Filter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status 0 pCi pCi pCi 6/18/2009 E6701-37 Cr-51 0.29-10.17 E2 1.73 E2 1.61 E2 2 Pass 0

Mn-54 4.45- 7.89 El 5.93 El 5.96 El 2 Pass 0 Co-58 2.94-5.36 El 3.97 El 3.95 El 2 Pass 0 Fe-59 2.06 - 13.54 El 5.29 El 4.50 El 2 Pass 0 Co-60 1.01- 1.80 E2 1.35 E2 1.36 E2 2 Pass 0 Zn-65 5.68 - 10.07 El 7.57 El 8.01 El 2 Pass 0 Cs-134 5.38- 9.54 El 7.17 El 6.50 El 2 Pass 0

Cs-137 6.23 - 11.04 E1 8.30 El 7.61 El 2 Pass Ce-141 0.92-1.64 E2 1.23 E2 1.30 E2 2 Pass 0

0 0

Iodine in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range pCi/l Value pCi/I Value pCi/l Status 0 7/21/2009 Q093LIWI 1-131 1.99-3.53 E2 2.65 E2 2.29 E2 3 Pass 0

0 7/21/2009 Q093LIW2 1-131 0.87-1.55 El 1.16 El 0.89 El 1/3 Low 1 0 0

7/21/2009 Q093LIW3 1-131 5.09-9.03 E2 6.79 E2 5.99 E2 3 Pass 0 0

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Section 5 - Page 6 0 0

Iodine in Milk Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status pCi/l pCi/l pCi/l 0 1-131 3.30-5.85 E3 4.40 E3 2.65 E3 3/3 Low( 2 )

3/4/2009 Q091LIM2 0

1-131 1.41 -2.51 E2 1.88 E2 1.38 E2 2/3 Low (3) 3/4/2009 Q091LIM3 0

6/8/2009 Q092LIM1 1-131 3.36-5.95 E2 4.48 E2 4.54 E2 3 Pass 6/8/2009 Q092LIM2 1-131 0.86- 1.53 E3 1.15 E3 1.08 E3 3 Pass 0

0 6/8/2009 Q092LIM3 1-131 7.49- 13.28 El 9.99 E1 9.61 El 3 Pass Iodine on Cartridge 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S Date Range Value Value Status pCi pCi pCi 0

6/18/2009 E6702-37 1-131 7.24- 12.83 El 9.65 El 9.53 El 3 Pass 0

0 Beta Air Particulate Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status 0 12/10/2009 E6903-37 Cs-137 1.97 - 3.50 E2 2.63 E2 2.36 E2 3 Pass 0

0 Tritium in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status pCi/I pCi/l pCi/I S 1/28/2009 Q091TWR1 H-3 4.30-7.62 E3 5.73 E3 5.54 E3 3 Pass S

1/28/2009 Q091TWR2 H-3 0.86- 1.53 E4 1.15 E4 1.09 E4 3 Pass 0

7/22/2009 Q093TWS1 H-3 0.88- 1.56 E4 1.18 E4 1.13 E4 3 Pass 0

7/22/2009 Q093TWS2 H-3 3.43- 6.61 E2 4.76 E2 5.10 E2 3 Pass 11/12/2009 Q094TWS1 H-3 5.30-9.40 E8 7.07 E8 7.82 E8 3 Pass 11/12/2009 Q094TWS2 H-3 0.77- 1.36 E5 1.02 E5 0.97 E5 3 Pass Section 5 - Page 7

S S

Table 5.0-A Footnote Explanations 0

S (1) Iodine in Water, Sample ID Q093LIW2, Reference Date 7/21/2009 S One of three results was outside of the acceptance range (reference 6.17).

S S

(2) Iodine in Milk, Sample ID Q091 LIM2, Reference Date 3/4/2009 S Three results for this cross-check were reported. All three of the reported results S

trended low and were outside of the acceptance range (reference 6.18). S S

(3) Iodine in Milk, Sample ID Q091 LIM3, Reference Date 3/4/2009 S Three results for this cross-check were reported. Two of the three reported results S trended low and were outside of the acceptance range (reference 6.18). S S

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0 0

0 TABLE 5.0-B ENVIRONMENTAL RESOURCE ASSOCIATES (ERA) 0 QUIKTm RESPONSE PROGRAM 0 2009 PROFICIENCY TEST RESULTS FOR ENRAD LABORATORIES 0

ERA LABORATORY CODE: D242401 Proficiency test samples are received, prepared, analyzed, and reported to Environmental Resource Associates 0 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.

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

0 Gamma Emitters in Water 0 Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check Date Range Value Value Status 0 pCi/I pCi/l pCi/I 0 4/6/2009 RAD-77* Ba-133 4.34 - 5.83 El 5.27 El 6.18 El High (.)

0 Cs-134 5.95 - 8.02 El 7.29 E1 6.86 El Pass Cs-137 1.51 - 1.87 E2 1.68 E2 1.52 E2 Pass Co-60 8.00 - 10.0 El 8.89 E1 9.56 El Pass S Zn-65 7.60 - 10.1 El 8.44 E1 9.97 El Pass 0

0 10/5/2009 RAD-79** Ba-133 7.83 - 10.2 E1 9.29 E1 9.35 El Pass Cs-134 6.50 - 8.73 El 7.94 E1 7.60 El Pass 0

Cs-137 4.91 - 6.29 E1 5.46 E1 5.51 El Pass 0 Co-60 1.05 - 1.31 E2 1.17 E2 1.15 E2 Pass Zn-65 8.96 - 11.9 E1 9.95 El 1.11 E2 Pass Tritium in Water Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check Date Range Value Value Status pCi/I pCi/I pCi/I 4/6/2009 RAD-77* H-3 1.78 - 2.23 E4 2.03 E4 1.87 E4 Pass 10/5/2009 RAD-79** H-3 1.43 - 1.80 E4 1.64 E4 1.53 E4 Pass

• ERA study period 4/6/2009 - 5/21/2009, ERA data report issue date 6/3/2009

• • ERA study period 10/5/2009 - 11/19/2009, ERA data report issue date 12/4/2009 Section 5 - Page 9

0 0

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Table 5.0-B Footnote Explanations 0 0

(1) Gamma Emitters in Water, Sample ID RAD-77, Reference Date 4/6/2009 0

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0 0 TABLE 5.0-C 2009 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS 0

Nuclear Technology Services 0

0 1st Quarter 2009 2nd Quarter 2009 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail 0 Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 100125 110.1 104.0 5.87 <+/-15% Pass 102077 106 101.0 4.95 <+/-15% Pass 100203 109.2 104.0 5.00 <+/-15% Pass 102243 100 101.0 -0.99 <+/-15% Pass 101141 105.4 104.0 1.35 <+/-15% Pass 102244 108 101.0 6.93 <+/-15% Pass 100210 104.5 104.0 0.48 <+/-15% Pass 102323 102 101.0 0.99 <+/-15% Pass 100386 108.6 104.0 4.42 <+/-15% Pass 102329 101 101.0 0.00 <+/-15% Pass Average Bias (B) 3.42 Average Bias (B) 2.38 Standard Deviation (S) 2.37 Standard Deviation (S) 3.40 Measure Performance IB[+S 5.79 <15% Pass Measure Performance JB +S 5.78 <15% Pass 3rd Quarter 2009 4th Quarter 2009 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 102228 69.5 70.2 -1.00 <+/-15% Pass 100140 14.0 14.0 0.00 <+/-15% Pass 102492 71.1 70.2 1.28 <+/-15% Pass 100358 14.0 14.0 0.00 <+/-15% Pass S 102007 69.9 70.2 -0.43 <+/-15% Pass 100404 13.0 14.0 -7.14 <+/-15% Pass 102041 73.4 70.2 4.56 <+/-15% Pass 100405 14.0 14.0 0.00 <+/-15% Pass 102078 70.6 70.2 0.57 <+/-15% Pass 100415 15.0 14.0 7.14 <+/-15% Pass Average Bias (B) 1.00 Average Bias (B) 0.00 0 Standard Deviation (S) 2.18 Standard Deviation (S) 5.05 0 Measure Performance IBI+S 3.17 <15% Pass Measure Performance IBI+S 5.05 <15% Pass 0

S 0

0 Section 5 - Page 11

Internal Crosscheck (Duke Energy) 1st Quarter 2009 2nd Quarter 2009 TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 101297 18.3 19.0 -3.95 <+/-15% Pass 102325 49.1 50.0 -1.78 <+/-15% Pass 101286 18.5 19.0 -2.58 <+/-15% Pass 102491 48.7 50.0 -2.68 <+/-15% Pass 101258 18.2 19.0 -4.26 <+/-15% Pass 102374 48.4 50.0 -3.26 <+/-15% Pass 101216 18.4 19.0 -3.42 <+/-15% Pass 102084 47.6 50.0 -4.88 <+/-15% Pass 101252 18.1 19.0 -4.74 <+/-15% Pass 102404 51.3 50.0 2.56 <+/-15% Pass 101356 18.7 19.0 -1.74 <+/-15% Pass 102396 47.8 50.0 -4.32 <+/-15% Pass 101339 18.2 19.0 -4.32 <+/-15% Pass 102346 48.7 50.0 -2.60 <+/-15% Pass 101127 17.6 19.0 -7.47 <+/-15% Pass 102485 48.6 50.0 -2.80 <+/-15% Pass 101278 19.4 19.0 1.89 <+/-15% Pass 102059 48.2 50.0 -3.68 <+/-15% Pass 101305 18.4 19.0 -3.05 <+/-15% Pass 102263 50.0 50.0 -0.08 <+/-15% Pass Average Bias (B) -3.36 Average Bias (B) -2.35 Standard Deviation (S) 2.40 Standard Deviation (S) 2.18 Measure Performance IBI+S 5.76 <15% Pass Measure Performance IBI+S 4.53 <15% Pass 3rd Quarter '2009 4th Quarter 2009 0

TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail 0 Number (mrem) 102400 25.9 (mrem) 27.0

(% diff)

-3.93 Criteria Pass/Fail Number (mrem) (mrem) (% diff)

<+/-15% Pass 100955 20.4 22.0 -7.14 Criteria Pass/Fail

<+/-15% Pass 0

102486 25.7 27.0 -4.70 <+/-15% Pass 100050 20.0 22.0 -9.18 <+/-15% Pass 0 102402 25.9 27.0 -4.04 <+/-15% Pass 100885 21.2 22.0 -3.68 <+/-15% Pass 0 102406 26.9 27.0 -0.44 <+/-15% Pass 101409 19.2 22.0 -12.77 <+/-15% Pass 102435 26.6 27.0 -1.63 <+/-15% Pass 100389 20.3 22.0 -7.82 <+/-15% Pass 0 102442 25.3 27.0 -6.48 <+/-15% Pass 100401 20.4 22.0 -7.18 <+/-15% Pass 0 102436 25.9 27.0 -3.93 <+/-15% Pass 101383 21.0 22.0 -4.45 <+/-15% Pass 102440 25.1 27.0 -7.19 <+/-15% Pass 100551 20.4 22.0 -7.14 <+/-15% Pass 0

102479 25.2 27.0 -6.81 <+/-15% Pass 100748 20.9 22.0 -4.95 <+/-15% Pass 0 102384 26.0 27.0 -3.67 <+/-15% Pass 100263 20.9 22.0 -4.91 <+/-15% Pass Average Bias (B) -4.28 Average Bias (B) -6.92 0

Standard Deviation (S) 2.17 Standard Deviation (S) 2.68 0 Measure Performance IBI+S 6.45 <15% Pass Measure Performance IBI+S 9.61 <15% Pass 0 0

0 Section 5 - Page 12

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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 1969-2008 6.6 Oconee Annual Radioactive Effluent Release Report 2009 0

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 3.5.1, DPC Revision #4.0 0*Version 6.12 NRC Integrated Inspection Report 50-269/08-04, 50-270/08-04, and 50-287/08-04 6.13 Duke Energy Corporation EnRad Laboratory Charcoal Cartridge Study, performed 2001 0

6.14 Radiological Effluent Controls Audit GO-08-21 (INOS)(REC)(ONS) 0 6.15 Radiological Effluent Controls Audit GO-08-23 (INOS)(REC)(NGO) 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-currentinfo.php>

6.17 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-09-01278 0

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• Section 6 -Pagel1 0

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6.18 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-09-00423 0

6.19 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-09-01295 0 0

6.20 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-07-01048 0 0

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APPENDIX A 0 ENVIRONMENTAL SAMPLING AND 0 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.

0 I. CHANGE OF SAMPLING PROCEDURES Indicator location 078.1 (Air Radioiodine, Air Particulate) was added as a replacement for indicator location 078 (Air Radioiodine, Air Particulate), which was removed from the program (reference 6.20).

0 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.

0 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.

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

A 0

Appendix A -Page 2 0

0 0

0

• 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.

0 SIl1. CHANGE OF ANALYSIS PROCEDURES

• No analysis procedures were changed during 2009.

• IV. SAMPLING AND ANALYSIS PROCEDURES 0A.1 0 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 0designed 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 Sanalysis 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 = Recreation Site (0.58 mi. WSW)

• Programmaticsampling terminated8/31/2009, reference 6.20 Location 078.1 = Recreation Site (0.53 mi. WSW)

Programmaticsampling initiated8/31/2009, reference 6.20

• 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 0

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 0composites 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) 0 0

0 O ~Appendix A -Page 3

0 0

0 A.3 SURFACE WATER 0 Monthly composite samplers were operated to collect an aliquot at least every 0 two hours. Gamma analysis was performed on the monthly composites. 0 Tritium analysis was performed on the quarterly composites sample. The 0 composites were collected monthly from the locations listed below.

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

Location 063.1 Lake Hartwell Hwy 183 Bridge (0.79 mi. E) 0 A.4 MILK 0 0

Semimonthly grab samples were collected at one location. A gamma and low-level Iodine-131 analysis was performed on each sample. The semimonthly 0 grab samples were collected from the location listed below.

S Location 071 = Clemson Dairy (10.2 mi. SSE) S 0

A.5 BROADLEAF VEGETATION 0

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

0 Location 077 Skimmer Wall (1.00 mi. SW) 0 Location 079 Keowee Dam (0.56 mi. NE) 0 Location 081 Clemson Operations Center (9.33 mi. SE)

Location 084 Sue Craig Road (2.58 mi. NNE) 0 0

A.6 FISH 0

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

0 Location 060 Greenville Water Intake Rd. (2.28 mi. NE) 0 Location 063 Lake Hartwell Hwy 183 Bridge (0.80 mi. ESE)

Location 067 Lawrence Ramsey Bridge Hwy 27 (4.34 mi. SSE) 0 0

A.7 SHORELINE SEDIMENT 0 0

Semiannual samples were collected and a gamma analysis was performed on each sample following the drying and removal of rocks and clams. The samples 0 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

0 S

0

• A.8 DIRECT GAMMA RADIATION (TLD) 0

• 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.

0

• An inner ring of 17 TLDs, one in each meteorological sector in the

• general area of the site boundary.

0An 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.

0

• TLD Locations are listed in Table 2.1-B.

0 A.9 ANNUAL LAND USE CENSUS An annual Land Use Census was conducted to identify within a distance of 8

• D 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 6/15 to 6/16/2009.

0* Results are shown in Table 3.9. No changes were made to the sampling 10 procedures during 2009 as a result of the 2009 census.

V. GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS 0The 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 0reflect 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.

0 0

0 0

• Appendix A -Page 5 0

0 0

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0 0 APPENDIX B 0

0 0 RADIOLOGICAL 0

S ENVIRONMENTAL MONITORING 0

0 PROGRAM 0

0 0

SUMMARY

OF RESULTS 0

0 0 2009 0

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0 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-2009 to 31-DEC-2009 rType and No. of Non-Medium Total Lower Limit All Indicator Location with Highest Control Routine Pathway Number of Detection Locations Annual Mean Location Report Sampled of Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction) 0 Measurement Performed (LLD) Range Code Range Range 0 S

Air Particulate (pCi/m3) 081 (9.33 mi SE)

S S

BETA 312 1.00E-02 1.77E-2 (260/260) 6.54E 3.04E-2 074 (2.36 mi NNW) 1.82E-2 (52/52) 8.92E 2.84E-2 1.80E-2 (52/52) 8.44E 2.94E-2 0

S CS-134 312 5.OOE-02 0.00 (0/260) 0.00 (0/52) 0.00 (0/52) 0 S CS-137 312 6.OOE-02 0.00 - 0.00 0.00 (0/260) 0.00 - 0.00 0.00 (0/52) 0.00 - 0.00 0.00 (0/52) 0 S

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S 1-131 312 7.OOE-02 0.00 (0/260) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S

S Mean and range based upon detectable measurements only S Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) S Zero range indicates no detectable activity measurements S

S S

S S

S S

S S

S S

S S

S S

0 0

Report Generated @ 4/26/2010 11:30 Appendix B - Page 2 S

0 S

0 0

0 0 Environmental Radiological Monitoring Program Summary 0 Facility: Oconee Nuclear Station Docket No. 50-269,270,287 0

Location: Oconee County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0

No. of Non-Type and Total Lower Location with Highest ControlNone Medium or Number Limit of Annual Mean Pathway Detection Locations Name, Distance, Direction Location Report Sampled of Meas.

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

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

CS-134 312 5.OOE-02 0.00 (0/260) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 312 6.OOE-02 0.00 (0/260) 0.00 (0/52) 0.00 (0/52) 0 0 1-131 312 7.OOE-02 0.00 - 0.00 0.00 (0/260) 0.00 - 0.00 0.00 (0/52) 0.00 0.00

- 0.00 (0/52) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S

S 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 0

0 0

0 0

S 0

0 0

Report Generated @ 4/26/2010 11:30 Appendix B - Page 3

0 0

0 Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 0 Location: Oconee County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0

No. of Non-Lower Location with Highest Cnr outine Medium or Type and Total Number Limit of Annual Mean Pathway Detection Locations Name, Distance, Direction Location Report of Sampled Meas. 0 Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed Range Code Range Range 0 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 1.30 (19/26) 066 1.37 (12/13) 1.19 (7/13) 0 0.69-2.11 (18.9 mi SSE) 0.69-2.11 0.64- 1.62 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 415 (4/8) 066 415 (4/4) 0.00 (0/4) 0 347-531 (18.9 mi SSE) 347-531 0.00-0.00 1-131 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 0

MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 NB-95 39 15 0.00 - 0.00 0.00 (0/26) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0 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 S 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 39 15 0.00 (0/26) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0 0 0

S 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 S S

0 Report Generated @ 4/26/2010 11:30 Appendix B - Page 4

S 0

0 Environmental Radiological Monitoring Program Summary 0

Facility: Oconee Nuclear Station Docket No. 50-269,270,287 0 Report Period: 01-JAN-2009 to 31-DEC-2009 Location: Oconee County, South Carolina 0

0 No. of Non-Medium or Type and Total Lower All Idit Location with Highest Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction Leaor Meas.

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

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 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 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 8 2000 4678 (4/4) 063. 1 4678 (4/4) 0.00 (0/4) 0 S 1-131 26 15 1440 - 9760 0.00 (0/13)

(0.79 mi E) 1440 - 9760 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S 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 0 NB-95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 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 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 0

S 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 0

0 Report Generated @ 4/26/2010 11:30 Appendix B - Page 5

S 0

0 Environmental Radiological Monitoring Program Summary 0

0 Facility: Oconee Nuclear Station Docket No. 50-269, 270, 287 0 Location: Oconee County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Number Limit of Annual Mean Pathway Locations Name, Distance, Direction Location Report Sampled of Detection Meas.

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

Measurement Performed (LLD) 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 0

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 1-131 26 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 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 0

Mean and range based upon detectable measurements only 0

Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) S Zero range indicates no detectable activity measurements 0

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0 0 Environmental Radiological Monitoring Program Summary 0 Facility: Oconee Nuclear Station Docket No. 50-269,270,287 0

Location: Oconee County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0 No. of Non-Lower Location with Highest ControlNone Medium or Type and Total 0 Pathway Number Limit of Annual Mean Locations Name, Distance, Direction Location Report Sampled of Detection Meas.

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

Measurement Performed (LLD) 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 S 1-131 48 60 0.00 0.00

- 0.00 (0/36) 0.00 0.00

- 0.00 (0/12) 0.00 0.00

- 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

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 0

0 0

0 0

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Report Generated @4/26/2010 11:30 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-2009 to 31-DEC-2009 Lower Location with Highest No. of Non-Medium or Type and Total All Indicator Control Routine Number Limit of Annual Mean Pathway Detection Locations Name, Distance, Direction Location Report Sampled of Meas.

0 Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction) 0 Measurement Performed Range Code Range Range Fish 060 (pCi/kg-wet) (2.28 mi NE) 0 CO-58 12 130 9.01 (1/8) 063 9.01 (1/4) 0.00 (0/4) 0 0 9.01 - 9.01 (0.80 mi ESE) 9.01 - 9.01 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 0

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 24.2 (8/8) 063 26.8 (4/4) 14.6 (3/4) 0 14.9-51.4 (0.80 mi ESE) 15.2-51.4 12.1 - 18.3 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 0 0

Mean and range based upon detectable measurements only 00 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 0

00 Zero range indicates no detectable activity measurements 0

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S 0 Environmental Radiological Monitoring Program Summary 0

0 Facility: Oconee Nuclear Station Docket No. 50-269,270,287 0 Location: Oconee County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0 No. of Non-0 Medium or Type and Total Lower Location with Highest ControlNone Number Limit of Annual Mean Pathway 0 Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

Unit of Analyses (LLD)Co: Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

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 65.6 (2/4) 063 69.7 (1/2) 0.00 (0/2) 0 61.5 -69.7 (0.80 mi ESE) 69.7-69.7 0.00-0.00 0

Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements 0

S 0

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S Report Generated @ 4/26/2010 11:30 Appendix B - Page 9

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0 Environmental Radiological Monitoring Program Summary 0

0 Facility: Oconee Nuclear Station Docket No. 50-269,270,287 0

Location: Oconee County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0 No. of Non-ne Lower and Total Litof Location with Highest ControlNo Medium or MType Nme All Indicator AnaMenControl Routine Number Limit of Annual Mean Pathway Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

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

Unit of Measurement Performed Range Code Range Range Direct Radiation TLD 058 (9.39 mi WSW) 0 (mR/standard quarter) 081 (9.33 mi SE) 0 168 0,00E+00 22.3 (160/160) 042 27.5 (4/4) 27.5 (8/8) 0 0

13.9 - 30.9 (4.93 mi SE) 23.2 -30.7 20.4 - 34.8 0 0

Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0 0

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0 Report Generated @4/26/2010 11:30 Appendix B - Page 10

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0 0 APPENDIX C 0

0 0 SAMPLING DEVIATIONS 0

0 &

S UNAVAILABLE ANALYSES 0

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0 APPENDIX C 0 S

0 OCONEE NUCLEAR STATION 0 SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES 0 DEVIATION & UNAVAILABLE REASON CODES 0

BF Blown Fuse PO Power Outage 0 FZ Sample Frozen PS Pump out of service / Undergoing Repair 1W Inclement Weather SL Sample Loss/Lost due to Lab Accident 0 LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Torn Filter 0 PI Power Interrupt VN Vandalism 0 PM Preventive Maintenance CN Construction 0

C.1 SAMPLING DEVIATIONS 0

Air Particulate and Air Radioiodines Scheduled Actual Reason 0 Location Collection Dates Collection Dates Code Corrective Action Power to sampling equipment was 0 interrupted for about 35 minutes due to 078 1/5 - 1/12/2009 1/5 - 1/12/2009 PI scheduled maintenance by Site Services. 0 Power to sampling equipment was interrupted for about 4.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to 0 underground electrical line repair work 078 1/12 - 1/19/2009 1/12 - 1/19/2009 PI performed by Site Services.

Power outage to sampling equipment due S

to indeterminate cause. Work request 078 3/30 - 4/6/2009 3/30 - 4/3/2009 PO 66771 initiated.

Power interruption to sampling 0

equipment. Work request 67111 initiated. 0 081 4/13 - 4/20/2009 4/20 - 4/27/2009 4/13 - 4/14/2009 4/22 - 4/27/2009 PI PI Power restored by maintenance personnel 4/22/2009 and normal sampling resumed.

0 Surface Water 0 Scheduled Actual Reason 0 Location Collection Dates Collection Dates Code Corrective Action 0 Pump out of service at time of collection.

Work request 71950 written. Composite 0

sample volume was available at time of 0 062 8/24 - 9/21/2009 8/24 - 9/21/2009 PS collection. A grab sample was also taken.

C.2 UNAVAILABLE ANALYSES There were no unavailable analyses during 2009.

Appendix C - Page 2

0 0

0 0

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,0 0 APPENDIX D 0

0 ANALYTICAL DEVIATIONS 0

0 No Analytical deviations were incurred for the 2009 Radiological Environmental Monitoring Program 0

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Appendix D - Page 1

0 0

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0 APPENDIX E 0

S RADIOLOGICAL 0 ENVIRONMENTAL MONITORING 0

PROGRAM RESULTS 0

0 0

This appendix includes all of the sample analysis reports generated from 0 each sample medium for 2009. Appendix E is located separately from this report and is permanently archived at the Duke Energy Corporation 0 Environmental Center radiological environmental master file, located at 0 the McGuire Nuclear Station Site in Huntersville, North Carolina.

0 0

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Appendix E - Page 1