Text

Annual Radiological Environmental Operating Report
	ML081440128
Person / Time
Site:	Oconee
Issue date:	05/13/2008
From:	Baxter D; Duke Energy Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML081440128 (88)
	v • d • e

DAVE BAXTER PDuke Vice President W Energy Oconee Nuclear Station Duke Energy Corporation ON01 VP/7800 Rochester Highway Seneca, SC 29672 May 13, 2008 864-885-4460 864-885-4208 fax dabaxter@dukeenergy.com U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Oconee Nuclear Site 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 2007.

Very truly yours, Dave axter Site 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

Document Control Desk May 13, 2008 Page 2 cc w/ attachments:

L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D. C. 20555 L. A. Reyes, Regional Administrator U. S. Nuclear Regulatory Commission -Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Andy Hutto Senior Resident Inspector Oconee Nuclear Station S. E. Jenkins, Manager Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 American Nuclear Insurers-95 Glastonbury Blvd., Suite 300 Glastonbury, CT 06033-4443

Document Control Desk May 13, 2008 Page 3 Cc (Lotus Notes only):

J.A. Twiggs E.H. Wehrman Cc (Attachment 1 only):

NSRB EC05P ONS Document Control ELL EC050 B.G. Davenport Bob Gill

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0 P Duke 0 EEnergy, 0

0 0 Oconee Nuclear Station 0 Units 1, 2 and 3 0

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0 AREOR 0 Annual S Radiological Environmental 0 Operating Report 0 2007

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Duke 4WEnergy.

ANNUAL RADIOLOGICAL

ENVIRONMENTAL OPERATING REPORT 0

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DUKE ENERGY CORPORATION

OCONEE NUCLEAR STATION

Units 1, 2, and 3 0

2007 0

0 0

0

TABLE OF CONTENTS 0

0 ~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-I 5.5 Duke Energy Intercomparison Program 5-2

5.6 Duke Energy Audits . 5-2 5.7 U.S. Nuclear Regulatory Commission Inspections 5-2 5.8 State of South Carolina Intercomparison Program 5-2 5.9 TLD Intercomparison Program . 5-2 5.9.1 Nuclear Technology Services Intercomparison Program 5-2 5.9.2 State of North Carolina Intercomparison Program 5-3

5.9.3 Internal Crosscheck (Duke Energy) . 5-3 6.0 References 6-I

D Appendices

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

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II. Description of Analysis Procedures A-2 III. Change of Analysis Procedures . A-3 IV. Sampling and Analysis Procedures A-3 A. I Airborne Particulate and Radioiodine A-3 A.2 Drinking Water . . . . . . . . . . A-3 A.3 Surface Water. A-4 A.4 Milk A-4 A.5 Broadleaf Vegetation A-4 A.6 Fish A-4 A.7 Shoreline Sediment. A-4 A.8 Direct Gamma Radiation (TLD) A-5 A.9 Annual Land Use Census . A-5 V. Global Positioning System (GPS) Analysis. A-5 Appendix B: Radiological Env. Monitoring Program - Summary of Results. B-1 Air Particulate . B-2 Air Radioiodine. B-3 Drinking Water. B-4 Surface Water . B-5 Milk. B-6 Broadleaf Vegetation B-7 Fish .B-8 Shoreline Sediment B-9 Direct Gamma Radiation (TLD) B- 10 Appendix C: Sampling Deviations and Unavailable Analyses C-1 C. I Sampling Deviations . C-2 C.2 Unavailable Analyses. C-3 Appendix D: Analytical Deviations . D-1 Appendix E: Radiological Environmental Monitoring Program Results E- 1 LIST OF FIGURES 2.1-1 Sampling Locations Map (One Mile Radius) 2-4 2.1-2 Sampling Locations Map (Ten Mile Radius) 2-5 3.1 Concentration of Gross Beta in Air Particulate 3-4 3.2 Concentration of Tritium in Drinking Water 3-5 3.3 Concentration of Tritium in Surface Water . 3-8 3.5 Concentration of Cs- 137 in Broadleaf Vegetation 3-12 3.6-1 Concentration of Cs- 137 in Fish 3-15 3.6-2 Concentration of Cs- 134 in Fish 3-15 3.7-1 Concentration of Cs- 137 in Shoreline Sediment 3-18 3.7-2 Concentration of Co-60 in Shoreline Sediment 3-18 3.8 Direct Gamma Radiation (TLD) Results 3-20 3.9 2007 Land Use Census Map 3-23 LIST OF TABLES 0

2. I-A Radiological Monitoring Program Sampling Locations . Sites)2-6 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites) . . 2-7 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 0

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3.2 Mean Concentrations of Radionuclides in Drinking Water 3-6 3.3 Mean Concentrations of Radionuclides in Surface Water 3-9 3.4 Mean Concentrations of Radionuclides in Milk 3-11 3.5 Mean Concentrations of Radionuclides in Vegetation 3-13 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 3.9 Oconee 2007 Land Use Census Results 3-22 4.1-A 2007 Environmental and Effluent Dose Comparison 4-3

4. I-B Maximum Individual Dose for 2007 based on Environmental 0 Measurements for Oconee Nuclear Station . 4-6 5.0-A 2007 Cross-Check Results for EnRad Laboratories 5-4 5.0-B 2007 Environmental Dosimeter Cross-Check Results 5-9 0

0 LIST OF ACRONYMS USED IN THIS TEXT (in alphabeticalorder)

BW BiWeekly 0 C DEHNR Control Department of Environmental Health and Natural Resources 0 DHEC Department of Health and Environmental Control EPA Environmental Protection Agency GI-LLI Gastrointestinal - Lower Large Intestine GPS Global Positioning System LLD Lower Limit of Detection M Monthly MDA Minimum Detectable Activity mrein Millirem NIST National Institute of Standards and Technology 0 NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual ONS Oconee Nuclear Station 0 pCi/kg pCi/l picocurie per kilogram picocurie per liter 0 pCi/m3 picocurie per cubic meter PIP Problem Investigation Process Q Quarterly 0 REMP SA Radiological Environmental Monitoring Program Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECs Technical Specifications TLD Thermoluminescent Dosimeter P.Ci/ml microcurie per milliliter UFSAR Updated Final Safety Analysis Report W Weekly 0

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S 1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the Oconee Nuclear Station Radiological Environmental Monitoring Program (REMP), and the program results for 0*the calendar year 2007.

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

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

comprising 1,348 test results in order to compile data for the 2007 report. Based on the annual land use census, the current number of sampling sites for Oconee Nuclear Station is sufficient.

SConcentrations observed in the environment in 2007 for station related radionuclides were 5within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, shoreline sediment, and fish are higher than the activities reported for samples collected prior to the operation of the station. 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 0""operations. The total body dose estimated to

the maximum exposed member of the public as

calculated by environmental sampling data, excluding TLD results, was 8.34E-02 mrem for 2007. It is therefore concluded that station 0operations has had no significant radiological

impact on the health and safety of the public or

the environment.

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2.0 INTRODUCTION

2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS

Oconee Nuclear Station (ONS) is located in Oconee County, South Carolina, approximately 8 0miles northeast of Seneca, South Carolina, on the shore of Lake Keowee. This lake was

formed by damming the Keowee and Little Rivers in that location. Immediately to the south

is the U.S. Government Hartwell Project. The Keowee Hydroelectric Plant near the station joins Lake Keowee and the upper reaches of Lake Hartwell. To the north, the Jocassee 0Hydroelectric Plant joins Lake Jocassee and Lake Keowee. Jocassee is a pumped storage

plant.

0 ONS consists of three pressurized water reactors. Each unit has an output of 846 megawatts net. Unit I 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.

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Figures 2.1-1 and 2.1-2 are maps depicting the Thermoluminescent Dosimeter (TLD) monitoring locations and the sampling locations. The location numbers shown on these maps

correspond to those listed in Tables 2.1-A and 2.1-B. Figure 2.1-1 comprises all sample

locations within a one mile radius of ONS. Figure 2.1-2 comprises all sample locations

within a ten mile radius of ONS.

0 2.2 SCOPE AND REQUIREMENTS OF THE REMP SAn environmental monitoring program has been in effect at Oconee Nuclear Station since

1969, four years prior to operation of Unit 1 in 1973. The preoperational program provides data on the existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station.

The operational program provides surveillance and backup support of detailed effluent 0monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.

This monitoring program is based on NRC guidance as reflected in the Selected Licensee 0Commitments Manual, with regard to sample media, sampling locations, sampling frequency, Sand analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other "man-made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related 0exposures from releases of radionuclides from Oconee Nuclear Station. This program satisfies

the requirements of Section IV.B.2 of Appendix I to 10CFR50 and 10CFR72.44(d)(2) and provides surveillance of all appropriate critical exposure pathways to man and protects vital interests of the company, public, and state and federal agencies concerned with the 0

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

The Annual Land Use Census, required by Selected Licensee Commitments, is performed to 0 ensure that changes in the use of areas at or beyond the site boundary are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 3.9.

S Participation in an interlaboratory comparison program as required by Selected Licensee Commitments provides for independent checks on the precision and accuracy of measurements of radioactive material in REMP sample matrices. Such checks are performed as part of the quality assurance program for environmental monitoring in order to demonstrate 0 that the results are valid for the purposes of Section LV.B.2 of Appendix I to IOCFR50. A summary of the results obtained as part of this comparison program are in Section 5 of this annual report.

2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE 0

There was one (1) basic statistical calculation performed on the raw data resulting 0 from the environmental sample analysis program. The calculation involved the 5 determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the Radiological Environmental Monitoring Program. The following equation was 0 used to estimate the mean (reference 6.8): 0 N 0 x -

Ixi

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

NOTE: "Net activity (or concentration)" is the activity (or concentration) determined 0 to be present in the sample. No "Minimum Detectable Activity", "Lower Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of the mean. 0 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

used throughout the Environmental Monitoring Program.

LLD - The LLD, as defined in the Selected Licensee Commitments Manual is the Ssmallest 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 0sample size (mass or volume), the radiochemical yield, and the radioactive decay of the sample between sample collection and counting. The "required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.

MDA - The MDA may be thought of as an "actual" LLD for a particular sample measurement remembering that the MDA is calculated using a sample background instead of a system background.

2.3.3 TREND IDENTIFICATION

One of the purposes of an environmental monitoring program is to determine if there is a buildup of radionuclides in the environment due to the operation of the nuclear station. Visual inspection of tabular or graphical presentations of data (including preoperational) is used to determine if a trend exists. A decrease in a particular 0radionuclide's concentration in an environmental medium does not indicate that reactor 0operations are removing radioactivity from the environment but that reactor operations

are not adding that radionuclide to the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the concentration.

Substantial increases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to 0completely interpret the trends, or lack of trends, determined from the environmental 0data. Some factors that may affect environmental levels of radionuclides include prevailing weather conditions (periods of drought, solar cycles or heavier than normal

precipitation), construction in or around either the nuclear plant or the sampling location, and addition or deletion of other sources of radioactive materials (such as the Chernobyl accident). Some of these factors may be obvious while others are 0sometimes unknown. Therefore, how trends are identified will include some judgment

by plant personnel.

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

Legend

TLD Locations A All Other Locations

,/'i Public Roads

/,\/ County Boundary Water Approdmate location of features shoAn N

0 0 0.25 ,les Projection NCSP NAD27 Section 2 - Page 4

.00 0 0 0 0 0 0 0 0 0 0 0 0 0

0000000000000000000000000000000000000000000o Figure 2.1-2 Section 2 - Page 5

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0 TABLE 2.1-A S

OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS 0 0

Table 2.1 -A Codes 0

W Weekly SM Semimonthly S BW M

BiWeekly Monthly Q

SA Quarterly Semiannually S

C Control Site S Location Description* Air Rad. &

Particulate Surface Water Drinking Shoreline Fish Milk Broadleaf Water Sediment Vegetation 060 Greenville Water Intake Road (3.23 NE) M 060 C Greenville Water Intake Road (2.28 NE) SA 0

062 C Lake Keowee Hydro Intake (0.85 mi ENE)

Lake Hartwell Hwy 183 Bridge M

S 063 (0.80 mi ESE) [000.7] SA SA 0 063.1 Lake Hartwell Hwy 183 (0.79 mi E) M 064 C Seneca (6.67 mi SSW) [004.1] M S 066 Anderson (18.9 mi SSE) [012] M Lawrence Ramsey Bridge Hwy 27 067 (4.34 mi SSE) [005.2] SA SA 068 C High Falls County Park (1.82 mi W) SA 0 071 C 074 Clemson Dairy (10.2 mi SSE) [006.3]

Keowee Key Resort (2.36 mi NNW) W SM 0 077 Skimmer Wall (1.00 mi SW) W M 0 078 079 Recreation Site (0.58 mi WSW)

Keowee Dam (0.56 mi NE)

W W M 0

081 C Clemson Operations Center (9.33 mi SE) W M S 084 Sue Craig Road (2.58 mi NNE) W M 0

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

- 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 (TLD SITES) 0 0 Site Location* Distance Sector Site Location* Distance Sector MICROWAVE TOWER, SIX 020 SITE BOUNDARY 0.16 miles N 040 MILE 4.74 miles E 0

0 021 SITE BOUNDARY 0.25 miles NNE 041 JCT HWY 101 & 133 LAWRENCE CHAPEL 4.25 miles ESE S 022 SITE BOUNDARY 0.53 miles NE 042 CHURCH, HWY 133 HWY 291 AT 4.93 miles SE 0 023 SITE BOUNDARY 0.93 miles ENE 043 ISSAQUEENA PARK HWY 130 AT LITTLE RIVER 4.09 miles SSE 024 SITE BOUNDARY 0.81 miles E 044 DAM 3.96 miles S TERMINUS OF HWY 588 0 025 SITE BOUNDARY 0.42 miles ESE 045 AT CROOKED CREEK 4.78 miles SSW HWY 188 AT 026 SITE BOUNDARY 0.34 miles SE 046 CROOKED CREEK 4.61 miles SW 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 029 SITE BOUNDARY 0.56 miles SSW 049 JCT HWY 201 & 92 3.60 miles WNW STAMP CREEK LANDING, 030 SITE BOUNDARY 0.42 miles SW 050 END OF HWY 92 3.53 miles NW HWY 128, 1 MILE N OF S 031 SITE BOUNDARY 0.27 miles WSW 051 HWY 130 DPC BRANCH OFFICE SITE 4.64 miles NNW 076 SITE BOUNDARY 0.19 miles W 052 - PICKENS 12.4 miles ENE DPC BRANCH OFFICE SITE 0 032 SITE BOUNDARY 0.19 miles WNW 053 - LIBERTY POST OFFICE - HWY 93 11.7 miles E S 033 SITE BOUNDARY 0.21 miles WNW 054 NORRIS 8.60 miles ESE 0 034 SITE BOUNDARY 0.22 miles NW 055 CLEMSON METEOROLOGY PLOT 9.27 miles SSE 0 035 SITE BOUNDARY 0.17 miles NNW 056 WATER TOWER - SENECA 7.30 miles SSW 0 036 MILE CREEK LANDING 4.32 miles N 057 OCONEE MEMORIAL HOSPITAL 8.42 miles SW KEOWEE CHURCH, BRANCH RD SUBSTATION, 037 HWY 327 4.85 miles NNE 058 C WALHALLA 9.39 miles WSW 0 CONVENIENCE MART, 0 038 JCT HWY 183 & 133 HWY 133, 1 MILE EAST 4.24 miles NE 059 TAMASSEE DAR SCHOOL CLEMSON 9.20 miles NW 0 039 OF JCT HWY 183 & 133 4.02 miles ENE 081 C OPERATIONS CENTER 9.33 miles SE C = Control

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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REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water Air Particulates Fish Milk Broadleaf 0 (pCi/liter) or Gases (pCi/m 3 )

(pCi/kg-wet) (pCi/liter) Vegetation (pCi/kg-wet) 0 H-3 20,000(a) 0 Mn-54 1,000 30,000 Fe-59 400 10,000 S Co-58 1,000 30,000 Co-60 300 10,000 0 Zn-65 Zr-Nb-95 300 400 20,000 S 1-131 2 (h) 0.9 3 100 0 Cs-134 Cs- 137 30 50 10 20 1,000 2,000 60 70 1,000 2,000 0

Ba-La- 140 200 300 0 (a) For drinking water samples only. This is 40CFR Part 141 value. 0 (b) If low-level 1- 131 analyses are performed.

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Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic 1-131 Beta Air Radioiodine Weekly X 0 Air Particulate Direct Radiation Weekly Quarterly X X X

S Surface Monthly X 0 Water Quarterly Composite X Drinking Monthly X (a) X 0

Water Quarterly Composite X Shoreline Sediment Semiannually X S Milk Semimonthly X X Fish Semiannually X 0 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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TABLE 2.2-C MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION 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) 0 Gross Beta 4 0.01 0 H-3 Mn-54 2000 15 130 0 Fe-59 30 260 0 Co-58, 60 Zn-65 15 30 130 260 0 Zr-95 15 Nb-95 15 0 1-131 15(a) 0.07 1 60 0 Cs- 134 Cs-137 15 18 0.05 0.06 130 150 15 18 60 150 80 180 Ba-La-140 15 15 (a) LLD for low-level 1- 131 analyses is I pCi/liter if performed 0

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3.0 INTERPRETATION OF RESULTS 0

Review of 2007 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 2007 was compared to preoperational and historical data. Sample data for some media is not 0directly comparable to preoperational and earlier operational sample results because of either

significant changes in the analysis methods or changes in the reporting of the results.

0 Evaluation for significant trends was performed for the radionuclides that have required LLDs listed in Selected Licensee Commitment 16.11.6. These radionuclides are collectively referred to Sas "Selected Licensee Commitments radionuclides" and include H-3, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140, and La-140. Drinking water gross beta results are routinely trended. Trending of air particulate gross beta results was initiated in 1996 when the analysis was resumed. Trending is also performed for other radionuclides that are detected and could have been the result of station effluents. Only Selected Licensee Commitment

radionuclides were detected in 2007.

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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

O 2.2-A). All maximum percent of reporting level values were well below the 100% action level.

The highest value reached during 2007 was 3.73% for Cs-137 in a fish sample collected at

D Location 067.

Changes in sample location, analytical technique, and presentation of results must be considered 0when reviewing for trends. Calculation of the annual mean concentrations has been performed

differently over the history of the REMP. During 1979-1986, all net results (sample minus background), positive and negative, were included in the calculation of the mean. Only positive net activity results were used to calculate the mean for the other years. A change in gamma spectroscopy analysis systems in 1987 ended a period when many measurements yielded

detectable low-level activity for both indicator and control location samples. It is thought that the method the previous system used to estimate net activity may have been vulnerable to false-

positive results.

Data presented in Sections 3.1 - 3.8 support the conclusion that there were no significant 0increases in radionuclides in the environment around ONS due to station operations in 2007.

0Similarly, there was no significant increase in ambient background radiation levels in the surrounding areas.

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3.1 AIRBORNE RADIOIODINE AND PARTICULATES 0 In 2007, 312 radioiodine and particulate samples were analyzed, 260 from five indicator 0

locations and 52 from the control location. Particulate samples were analyzed weekly for gamma 0 and gross beta. Radioiodine samples received a weekly gamma analysis.

0 There was no detectable 1-131 in air 0 samples in 2007. Table 3.1-A gives the 0 highest indicator location annual mean 0 and control location annual mean for 1-131 since the preoperational period. 0 The table shows similar concentrations for both the indicator and control 0

locations and the activities decreasing 0 from early in the operational history of 0 the plant. No 1-131 has been detected 0 since 1994.

-Z 0 Cs-137 was not detected in air radioi Aine samples in 2007. Cs-137 has been detected in 0 cartridges in previous years. A study performed in 1990 determined Cs-137 to be an active 0 constituent of the charcoal. A similkar study was performed in 2001 again yielding this 0 conclusion.

0 There were no detectable gamma emitting radionuclides detected in air particulate samples in 0 2007. No gamma emitting particulates have been detected in indicator location samples since the change in gamma spectroscopy analysis systems in 1987. 0 Beta analysis of particulate filters was initiated in March of 1996 and became required by 0 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 0

required since 1984. Figure 3.1 summarizes gross beta results for the indicator location with the 0 highest annual mean and the control location samples. Both the indicator and control location 0 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. 0 0

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

Year Indicator Location (pCi/rn 3 ) Control Location (pCi/m3)

Preoperational 1969-1972 0.00E0 0.00E0 Feb. 1973 - June 1973 0.00E0 0.00E0 July 1973 - Dec. 1973 0.00E0 0.00E0 Jan. 1974 - June 1974 0.00E0 0.00E0 July 1974 - Dec. 1974 2.60E-2 8.00E-3 Jan. 1975 - June 1975 8.65E-2 3.12E-2

July 1975 - Dec. 1975 1.13E-2 9.52E-3 1976 2.76E-2 2.18E-2 1977 3.60E-2 3.60E-2 1978 2.19E-1 1.15E-I 1979 7.54E-3 4.75E-4 1980 3.07E-3 9.67E-4 1981 6.3 1E-3 5.39E-4 1982 2.87E-3 8. 10E-4 1983 1.48E-3 3.05E-4 1984 8.11E-4 -2.30E-5 1985 7.71E-4 4.54E-4 1986 5.02E-3 7.86E-3 1987 4.29E-3 5.19E-3 1988 0.00E0 0.00E0 1989 4.99E-4 0.00E0 1990 0.OOEO 0.OOEO 1991 0.OOEO 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.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 0.OOEO 0.OOEO 2007 0.OOEO 0.OOEO O.OOEO = no detectable measurements 1979 - 1986 mean based on all net activity results 0

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0 O Section 3 - Page 3 0

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Figure 3.1 S 3

S pCi/M Concentration of Gross Beta in Air Particulate 4.50E-02 0 4.OOE-02 0 3.50E-02 S 3.OOE-02 0 2.50E-02 0 2.OOE-02 0 1.50E-02 0 1.OOE-02 0 5.OOE-03 S O.OOE+00 0 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 0 Pre-operational sample results 3 ranged from 0.04 to 1.46 pCi/m 0 Control Location - Indicator Location S 0

There is no reporting level for gross beta in airparticulate 0 0

Table 3.1-B Mean Concentration of Gross Beta in Air Particulate 0

Monitoring Period Indicator Location (pCi/mn 3

) Control Location (pCi/m3 ) 0 1996 3.87E-2 3.69E-2 0 1997 2.87E-2 2.92E-2 1998 2.47E-2 1.56E-2 S

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

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

2005 1.95E-2 1.91E-2 0 2006 Average ( 1997 - 2006) 2.09E-2 2.25E-2 2.00E-2 2.OOE-2 S

2007 2.31E-2 2.13E-2 0

0 0

0 S

S S

0 Section 3 - Page 4

0 0

0 3.2 DRINKING WATER 0

0 Gross beta analysis and gamma spectroscopy were performed on 39 monthly drinking water 0 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 indicator locations is downstream of the effluent release point.

Table 3.2 lists the highest indicator location annual mean and control location annual mean for 0 gross beta results since the preoperational period. The indicator location had an average S concentration of 1.58 pCi/liter in 2007, and the control location had a concentration of 1.08 pCi/liter. The 2006 indicator mean was 1.54 pCi/liter. The table shows that 2007 gross beta 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 2007; therefore low-level iodine analysis is not required.

Tritium was detected in four of the twelve composite samples during 2007. The 2007 mean 0 indicator location 066 concentration was 402 pCi/liter, which is 2.01% of the reporting level.

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

0 There were no gamma emitting radionuclides identified in drinking water samples in 2007.

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

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

0 Figure 3.2 Currentreporting level implemented 1984 0

pCilliter Concentration of Tritium in Drinking Water 5000 4500 4000 3500 0 3000 2500 0 2000 0 1500 0 1000 0 500 0 0 1974 1975 1977 1979 1981 1983 1985 1987 1989 1991 a-1993 1995 1997 1999 2001 2003 2005 2007

-*--Control Location -W-Indicator Location - 20% Reporting Level 0

Section 3 - Page 5 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 Qualitative results reported Analysis not required 0 June 1973 - Dec. 1973 7.15 21.78 Analysis not required 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 July 1975 - Dec. 1975 1.98 2.01 1.59 1.22 600 2990 300 505 0

1976 2.38 2.00 2196 224 0 1977 1978 2.70 2.56 2.30 2.17 1200 1050 290 333 0

1979 1.83 1.36 576 235 0 1980 1.86 1.63 660 200 0 1981 1.98 1.88 830 127 1982 2.04 1.45 643 153 0 1983 1.85 1.54 937 220 1984 1985 1.87 2.14 1.08 1.16 765 856 145 210 0

1986 1.91 1.04 1240 503 0 1987 2.00 1.20 815 680 1988 2.00 1.40 1570 0.00 1989 2.30 1.80 1350 559 0 1990 3.00 2.70 0.00 0.00 S 1991 1.80 1.40 558 0.00 1992 3.20 1.60 0.00 0.00 0 1993 2.10 1.90 0.00 0.00 1994 1995 1.90 5.10 2.10 2.90 0.00 248 0.00 0.00 0

1996 2.07 1.77 214 0.00 0 1997 2.52 2.23 194 0.00 0 1998 2.48 1.70 0.00 0.00 1999 1.73 1.49 185 0.00 0 2000 2.07 1.68 251 0.00 0 2001 1.75 1.29 '390 0.00 2002 1.61 1.21 338 0.00 0

2003 1.51 1.05 266 0.00 0 2004 2005 1.58 1.28 1.25 1.37 225 377 0.00 0.00 0

2006 1.54 1.75 340 0.00 0 2007 1.58 1.08 402 0.00 0 0.00 =no detectable measurements 1989 - Clemson water plant closes; nearest downstream plant is Anderson.

1979 - 1986 mean based on all net activity results 0

0 0

0 Section 3 - Page 6 0

0

0 0

3.3 SURFACE WATER S Gamma spectroscopy was performed on 26 monthly surface water samples. These samples were 0composited to form eight quarterly samples for Tritium analysis. One indicator and one control location were sampled. The indicator location is near the liquid effluent release point.

Tritium was detected in the four indicator location samples. The 2007 average concentration was 9,910 pCi/liter. The individual samples ranged from 1,580 pCi/liter to 19,100 pCi/liter. The 02006 mean concentration was 6,718 pCi/liter. Tritium was not detected in any control surface water samples.

,Figure 3.3 shows the indicator and control annual means for Tritium since the preoperational period. Table 3.3 lists the t 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. An extreme

drought beginning mid-2007 could impact

. surface water tritium concentrations.

Gamma spectroscopy analysis did not detect any station related activity during 2007. 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 0change in the gamma spectroscopy analysis system in 1987. Visual inspection of the gamma

spectroscopy tabular data covering the early operational period through 2007 did not reveal any 5increasing trends.

K-40 is the naturally occurring radionuclide observed in surface water samples in 2007.

S S

S 0

S S

SSection 3 -Page 7 S

o

0 0

Figure 3.3 0 0

pCi/liter Concentration of Tritium in Surface Water S 60000 0 50000-0 0

40000- 0 0

30000-0 20000-0 0

10000- 0 0

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

0

-Control Location - Indicator Location 0

S There is no reporting level for Tritium in surface water S

0 0

0 6

0 0

0 6

0 0

6 0

0 0

Section 3 - Page 8 0

0

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

Preoperational 1969 Qualitative results reported 4.86E2

Preoperational 1970 5.94E2 Preoperational 1971 4.01E2

Preoperational 1972 3.62E2

1973 0.00E0 1974 0.00E0 1.32E1 0.00E0 1.60E1 1.99E3 Jan. 1975- June 1975 0.00E0 0.OOEO 0.00E0 0.OOEO 1.56E4 July 1975 - Dec. 1975 0.OOEO 1.34E1 0.OOEO 0.00E0 5.52E4 1976 1.08E2 3.30E 1 .OOEO 3.50E 1 2.95E4 1977 2.60E1 1.80E1 0.OOEO 3.10E1 2.90E3 1978 2.96E2 0.00E0 0.00E0 2.22E 1 8.00E2 1979 1.33E0 2.60E0 1.78E0 2.82E0 4.37E3 1980 1.56E0 2.30E0 1.22E0 5.40E0 4.93E3 1981 1.1OEO 6.10E-1 1.70E0 3.90E0 7.21E3 1982 6.14E- 1 1.99E0 2.29E0 4.85E0 6.13E3 1983 6.99E- 1 3.02E0 3.91 E-1 6.83E-1 8.40E3 1984 9.40E- 1 6.30E-1 7.90E- l 4.83E- 1 9.90E3 1985 2.15E- 1 6.27E-I 4.95E-1 9.90E-1 1.05E4 1986 3.28E0 1.23E0 1.14E0 3.07E- I 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 0.00E0 0.00E0 0.00E0 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 0.00E0 0.OOEO 0.OOEO 0.00E0 4.54E3 1997 0.OOEO 0.OOEO 0.OOEO 0.00E0 5.50E3 1998 0.OOEO O.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 0.00E0 0.OOEO 0.OOEO 0.OOEO 7.43E3 2002 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.00E4 2003 0.OOEO 0.OOEO O.OOEO 0.OOEO 4.77E3 2004 0.OOEO 0.OOEO 0.OOEO 0.OOEO 3.86E3 2005 0.OOEO 0.OOEO 0.OOEO 0.OOEO 5.15E3 2006 0.OOEO 0.00E0 0.OOEO 0.00E0 6.72E3 2007 0.OOEO 0.OOEO 0.OOEO 0.OOEO 9.9 1E3 0 O.OOEO no detectable measurements 1979-1986 mean based on all net activity results 0

0 0

O Section 3 - Page 9 0

0

S S

0 3.4 MILK 0 Gamma spectroscopy and low level iodine analysis was performed on 27 milk samples collected S in 2007. One control location was sampled. No indicator dairies were identified by the 2007 0 land use census. 0 There were no gamma emitting radionuclides S identified in milk samples in 2007. Cs-137 is 0 the only radionuclide, other than naturally S occurring, reported in milk samples since 0 1988. Cs-137 in milk is not unusual. It is a constituent of nuclear weapons test fallout and S has been observed in samples from indicator 0 and control locations in previous years. S Table 3.4 lists the highest indicator location S annual mean and control location annual mean S for Cs-137 since the preoperational period. S The table shows similar concentrations for S both indicator and control locations.

S K-40 is a naturally occurring radionuclide observed in milk samples in 2007. S S

S S

0 0

S S

0 S

S S

S Section 3 - Page 10 S

S S

0 0 Table 3.4 Mean Concentration of Radionuclides in Milk Year Cs-137 Indicator (pCi/l) Cs-137 Control (pCi/l)

Preoperational 1.57E11 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 1.11EI 0.00E0 Jan. 1975 -June 1975 1.51E 1 9.45E0 July 1975 - Dec. 1975 0.00E0 0.00E0 1976 1.80E1 7.47E0 1977 0.OOEO 0.OOEO 1978 1.33El 1.33E1 t979 7.25E0 2.52E0 1980 3.58E0 2.63E0 1981 5.52E0 5.5 1E0 1982 2.71E0 3.25E0 1983 5.04E0 -4.27E-I 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 0.OOEO 1993 0.00E0 0.00E0 1994 0.00E0 1.80E0 1995 2.30E0 2.OOEO

1996 0.00E0 4.1OEO 1997 0.00E0 0.00E0

1998 0.OOEO 0.00E0 1999 0.OOEO 0.OOEO 2000 0.00E0 0.00E0 2001 0.OOEO 0.OOEO 2002 0.00E0 0.00E0 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 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

2007 land use census.

Section 3 - Page II

0 0

3.5 BROADLEAF VEGETATION S

Gamma spectroscopy was performed on 48 broadleaf vegetation samples during 2007. Three indicator locations and one control location were sampled. There were no gamma emitting radionuclides identified in vegetation samples in 2007. Table 3.5 shows control location 0 samples have historically contained measurable concentrations of Cs-137 but none was reported in 2007. 0 0

Cs-137 is the only radionuclide, other than naturally occurring, reported in indicator location 0 vegetation samples since the change in gamma spectroscopy analysis systems in 1987.

It is not unusual for Cs- 137 to be present in vegetation. It is a constituent of nuclear weapons test fallout and has been observed in samples from indicator and control locations in previous 0 years. Table 3.5 lists the highest indicator location annual mean and control location annual 0 mean for Cs-137 since early in the station's operational history. Visual inspection of the tabular data did not reveal any increasing trends.

0 K-40 and Be-7 are naturally occurring radionuclides that were observed in broadleaf vegetation samples in 2007. 0 Figure 3.5 0

pCi/kg Concentration of Cs-137 in Broadleaf Vegetation 2500 r 0

2000 1500 0 0

1000 500 0

0a A, b W_ 4 0 1974 1975 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 2007

- Indicator Location -- Control Location Reporting Level Section 3 - Page 12

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

July 1974 - Dec. 1974 1.54E3 0.OOEO Jan. 1975 - June 1975 1.55E3 1.59E3 July 1975 - Dec. 1975 0.00E0 0.00E0 1976 0.OOEO 0.OOEO 1977 0.OOEO 7.90E2 1978 1.19E2 8.19E1 1979 5.04E 1 2.96E 1 1980 2.80E1 1.55E1 1981 2.99E1 2.60E 1 1982 2.42E 1 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 2.40E 1 7.50E1 1989 0.OOEO 1.08E2 1990 2.73E2 1.74E2 1991 2.20E 1 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 4.73EI 1.35E2 1998 7.28E1 1.61E2 1999 1.34E2 0.OOEO 2000 1.06E2 0.OOEO 2001 3.19E 1 0.OOEO 2002 8.44E 1 0.OOEO 2003 0.OOEO 0.OOEO 2004 0.OOEO 5.96E I 2005 4.51EI 4.11E1 2006 1.77E 1 0.OOEO 2007 0.OOEO 0.OOEO 0.00E0 = no detectable measurements Only qualitative results reported prior to 1974 Control location changed to 073 in 1984 Control location 081 added in 1998 0 Control location 073 was removed in 1999 1979 - 1986 mean based on all net activity results S

0 0

0 O ~Section 3 -Page 13 0

0

0 3.6 FISH 0

In 2007, gamma spectroscopy was performed on 12 fish samples. Two downstream indicator and one control location were sampled. Cs-137 was identified in seven of the eight indicator location samples. Cs-137 was detected in two of the four control location samples at a mean concentration of 19.1 pCi/kg.

0 The highest average concentration for Cs-137 was 41.0 pCi/kg (2.05% of reporting level).

The highest individual sample concentration for Cs-137 was 74.6 pCi/kg (3.73% of reporting level).

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

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

0 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.

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

Table 3.6 lists the highest indicator location annual means since the preoperational period for radionuclides detected in 2007. 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.

0 0

Section 3 -Page 14 0 0

0

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

2000 0

0 1500 1000 0

0 500 0 - - Me= __ r 1970 1973 1975 1976 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 2007

-- Control Location - Indicator Location -Reporting Level Figure 3.6-2 0

pCi/kg Concentration of Cs-134 in Fish 700 0 600 0 500 400 0

300 200 0 100 0

00

.6 =. r__-

-- - - - - - -e- @ --- e E u' ' " " ". - -

1970 1973 1975 1976 1977 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997 1999 2001 2003 2005 2007 0 0 Control Location Indicator Location -50 % Reporting Level Current reporting levels implemented 1984 Section 3 - Page 15 S

S 0

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

Preop ending Jan. 1971 0.OOEO 0.OOEO 0.00E0 1.46E2 Preop ending Jan. 1973 0.OOEO 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 0.00E0 1.89E2 Jan. 1974 - June 1974 0.OOEO 0.OOEO 0.OOEO 2.47E1 July 1974 - Dec. 1974 O.O0EO 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.OOE I 3.13E2 1976 5.70E 1 1.14E2 7.73E1 1.66E2 1977 0.OOEO O.OOEO 1.80E2 3.60E2 1978 3.27E2 0.OOEO 3.3 1E2 0.OOEO 1979 1.91E0 1.56E1 9.26E 1 3.88E2 1980 1.45E1 1.90El 1.10E2 3.99E2 1981 2.25E 1 1.49E1 1.40E2 4.51 E2 1982 9.83E-1 8.03E0 1.17E2 2.94E2 1983 3.35E1 4.53E0 1.24E2 3.32E2 1984 1.21E2 6.23E 1 3.87E2 1.04E3 1985 1.62E1 1.1OEI 7.93E1 2.85E2 1986 9.56E1 2.59E1 2.57E2 7.36E2 1987 1.63E2 6.30E1 9.80E 1 3.93E2 1988 9.60E1 0.00E0 7.20E 1 2.60E2 1989 4.30E 1 1.50EI 8.60E 1 3.36E2 1990 1.50E t 0.00E0 4.80E 1 1.19E2 1991 4.59E I 0.00E0 1.25E2 1.94E2 1992 6.10EI 0.00E0 4.80E 1 1.36E2 1993 0.OOEO 0.OOEO 2.1OE1 1.10E2 1994 0.00E0 0.OOEO 2.80E 1 1.05E2 1995 0.00E0 0.00E0 3.10E1 9.20E 1 1996 0.OOEO 0.OOEO 4.49E 1 1.25E2 1997 0.00E0 0.00E0 0.OOEO 1.18E2 1998 0.00E0 0.00E0 0.00E0 5.79E1 1999 0.00E0 0.00E0 0.OOEO 1.04E2 2000 0.OOEO 0.OOEO 0.OOEO 7.54E 1 2001 1.72E1 0.00E0 0.OOEO 9.92E 1 2002 0.00E0 0.00E0 0.00E0 9.37E I 2003 5.02E 1 0.OOEO 0.00E0 6.04E I 2004 0.OOEO 0.00E0 0.OOEO 5.29E1 2005 0.00E0 0.00E0 0.00E0 5.14E I 2006 0.OOEO 0.OOEO 0.OOEO 5.58E1I 2007 0.OOEO 0.OOEO 0.OOEO 4.1OE I O.0OE0 = no detectable measurements 1979 - 1986 mean based on all net activity results 5 0

0 0

Section 3 -Page 16 0 0

0 0

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

Cs-137 was identified in three of the four indicator location samples. Cs-137 was not 0 observed in any control location samples. The highest 2007 indicator location annual mean 0 was 297 pCi/kg. The highest individual sample concentration of 472 pCi/kg was confirmed through resampling (PIP G-07-00400). Table 3.7 lists the highest indicator location annual means since shoreline sediment was initiated in 1984. Included in the table are radionuclides 0 that have been identified in this media since the change in analysis systems in 1987.

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

0 0 K-40 and Be-7 are naturally occurring radionuclides observed in shoreline sediment samples in 2007.

0 0

S 0

0 0

0 0 Section 3 - Page 17 0

0

0 0

Figure 3.7-1 0

pCi/kg Concentration of Cs-137 in Shoreline Sediment 1000 0

900 800 . 0 700 0 600 0 500 400 0 300 ..

0 100 0

0 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006

-- O--Control Location 068 --- Indicator Location 063 Indicator Location 067 S

0 0

Figure 3.7-2 0

pCi/kg Concentration of Co-60 in Shoreline Sediment 600 S 0

500 0

400 6

0 300 S 0

200 6

100 0

061==w ba 0 09=4 0 M n m E NM m M m !

6 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 6

-- Control Location 068 Indicator Location 063 A Indicator Location 067 There are no reporting levels for shoreline sediment Section 3 - Page 18

Table 3.7 Mean Concentrations of Radionuclides in Shoreline Sediment (PCi/kG)

Year Mn-54 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ag-ll0m Sb-125 1984 1.1OEI 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 3.30EI 1.20E2 1.87E2 6.70E1 6.60E1 7.59E2 1.62E2 3.67E2 1989 2.30E1 1.24E2 1.96E2 0.00E0 5.40EI 8.48E2 5.50E1 1.86E2 1990 3.40E1 8.00El 2.59E2 0.OOEO 4.50E1 5.36E2 1.71E2 9.OOEl 1991 3.26E1 5.60E1 8.57E1 0.OOEO 6.91E1 1.24E2 1.10E2 1.78E2 1992 8.79EI 1.79E2 1.12E2 0.OOEO 5.60E1 3.31E2 1.69E2 2.08E2 1993 8.20E1 8.20E1 6.50E1 0.00E0 3.20E1 I1.36E2 5.63E1 1.11E2 1994 5.30E1 7.00E1 1.49E2 0.00E0 6.70El 2.38E2 1.04E2 1.29E2 1995 1.43E2 3.90E1 2.40E1 0.00E0 i.IOEI 5.20E1 0.OOEO 0.00E0 1996 O.O0EO 5.10El 0.00E0 0.00E0 1.98El 1.19E2 0.00E0 0.00E0 1997 0.00E0 0.OOEO 0.00E0 0.00E0 0.OOEO 1.06E2 0.00E0 0.00E0 1998 0.00E0 0.00E0 0.OOEO 0.00E0 0.00E0 1.01E2 0.OOEO 0.00E0 1999 6.96E1 0.00E0 0.00E0 0.00E0 0.OOEO 7.38E1 0.OOE0 O.OOEO 2000 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 8.54E1 0.OOEO 0.OOEO 2001 0.00E0 2.10El 0.00E0 0.00E0 0.00E0 1.20E2 0.OOEO 0.00E0 2002 0.00E0 0.00E0 0.OOEO 0.00E0 0.00E0 6.96E1 0.OOEO 0.00E0 2003 0.OOEO 0.00E0 0.00E0 0.00E0 0.OOEO 1.93E2 0.00E0 0.00E0 2004 8.54E1 0.00E0 0.00E0 0.00E0 0.00E0 9.56E1 0.OOEO 0.00E0 2005 2.00E2 O.OOEO 0.00E0 0.00E0 0.OOEO 6.53E1 0.OOEO 0.00E0 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 5.01EI 0.OOEO 0.OOEO 2007 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2.97E2 0.OOEO 0.OOEO O.OOEO = no detectable measurements 1984-1986 mean based on all net activity results S

0 0

0 O ~Section 3 -Page 19 0

0

0 0

0 3.8 DIRECT GAMMA RADIATION 0 0

In 2007, 168 Thermoluminescent Dosimeters (TLD) were analyzed, 160 at indicator S 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 036, 4.32 miles from the station. The annual mean exposure for S the control locations was 108 milliroentgen. 0 Figure 3.8 and Table 3.8 show TLD inner ring (site boundary), outer ring (4-5 miles), and 6 control location annual averages in milliroentgen per year. Data is provided from 1984 when TLD locations were added and arranged in an inner ring and outer ring configuration. 0 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 0

ring averages comprise a number of data points with control averages representing only two 6 locations.

The calculated total body dose (from gaseous effluents) for 2007 was 1.91 E-2 mrem, which is 0 0.02% of the average inner ring TLD values. Therefore, it can be concluded that discharges 0 from the plant had very little impact upon the measured TLD values. 6I The maximum measurement from TLDs at the Independent Spent Fuel Storage Installation 6I (ISFSI) was 750 milliroentgen per standard quarter. This is consistent with previous 6I measurements. TLD measurements in the inner ring (site boundary) have remained relatively 0I constant.

6I Figure 3.8 6I mR/year Direct Gamma Radiation (TLD) Results 250 200 150 II II 100 II II 50 II II 0

II 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006 II

-i--Inner Ring --- Outer Ring -- *-- Control II I

There is no reporting level for Direct Radiation (TLD) I Section 3 - Page 20

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

Preoperational 113.1 123.9 148.9 1984 79.4 83.8 110.3 1985 116.9 121.5 156.6 1986 104.2 106.0 150.9 1987 84.3 88.8 104.3 1988 72.3 78.6 112.6 1989 63.7 61.7 89.4 1990 52.2 50.7 70.1 1991 61.2 65.0 88.0 1992 76.2 73.2 92.0 1993 74.8 80.6 93.0 1994 86.8 94.7 112.0 1995 93.6 101.7 132.0 1996 68.5 78.3 101.0 1997 72.8 83.8 104.5 1998 71.7 80.8 118.0 1999 74.5 82.5 104 2000 76.2 84.5 105.6 2001 73.6 82.4 102.2 2002 76.6 85.3 108.0 2003 77.4 86.6 108.8 2004 80.1 87.5 1 10.4 2005 79.3 89.0 104.7 2006 82.0 90.2 108.8 Average (1997 - 2006) 76.4 85.3 107.5 2007 81.0 90.0 108 S

0 0

0Section 3 -Page 21 0

0

0 0

3.9 LAND USE CENSUS 0 0

The Land Use Census was conducted during the growing season (6/5 - 6/6/2007) as required by SLC 16.11.6. Table 3.9 summarizes census results. A map indicating identified locations 0

is shown in Figure 3.9. The nearest residence is located in the NW sector at 1.04 miles. No 0 program changes were required based on the results of the census. 0 0

Table 3.9 Oconee 2007 Land Use Census Results 0

0 Sector Distance Sector Distance (Miles) (Miles) 0 Nearest Residence 2.98 Nearest Residence 1.96 0 Nearest Milk Animal N Nearest Milk Animal - S 0 Nearest Residence 1.85 Nearest Residence 1.36 0

- SSW Nearest Milk Animal NNE Nearest Milk Animal 0 Nearest Residence 1.20 Nearest Residence 1.32 0 NE Nearest Milk Animal - SW Nearest Milk Animal -

0 Nearest Residence 1.34 Nearest Residence Nearest Milk Animal 1.81 0

ENE Nearest Milk Animal - WSW 0

Nearest Residence 1.14 Nearest Residence 1.76 E Nearest Milk Animal - W Nearest Milk Animal S 0

Nearest Residence 1.57 Nearest Residence 1.35 ESE Nearest Milk Animal - WNW Nearest Milk Animal 0 Nearest Residence 1.46 Nearest Residence 1.04 0

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

0 0

0 Section 3 - Page 22 0 0

0

Figure 3.9 Oconee Nuclear Station 2007 Land Use Census Map Legend

Residence

,\'Public Roads

/N/Rail Road

/\/County Boundary

~~Water Approximate location of features shown 0 0.5 1 2 Miles Projection NCSP NAD27 June 2007 Section 3 - Page 23

0 0

00 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 2007 ONS REMP samples. The primary purpose of 0estimating doses based on sample results is to allow comparison to effluent program dose estimates. Doses based on sample results were conservatively calculated in a manner as equivalent as possible to effluent-based dose estimates.

0Doses based on REMP sample results were calculated using the methodology and data 0presented 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 0radionuclide and organ.

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

are contained in Table 4.1-B.

0 No radionuclides were detected in broadleaf vegetation, milk, airborne radioiodine or airborne particulate samples other than naturally-occurring K-40 and Be-7. Dose estimates were not calculated for surface water samples because surface water is not considered a potable 0drinking water source although surface water tritium concentrations are used in calculating doses from fish. REMP TLD exposure results are discussed in Section 3.8.

The maximum environmental organ dose estimate for any single sample type (other than

direct radiation from gaseous effluents) collected during 2007 was l.O1E-1 mrem to the child 0liver from consuming fish.

0

4.2 ESTIMATED DOSE FROM RELEASES 0

Throughout the year, dose estimates were calculated based on actual 2007 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 0 dose estimates. Summaries of RETDAS dose calculations are reported in the Annual Radioactive Effluent Release Report (reference 6.6).

0The effluent-based liquid release doses are summations of the dose contributions of the drinking water, fish and shoreline pathways. The effluent-based gaseous release doses report 0 Section 4 - Page I 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 S

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. This indicates that effluent program dose estimates are both valid and reasonably conservative.

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 2007 environmental sample results was 1.01E-I mrem to the child liver. The maximum total organ dose of 8.59E-2 mrem for liquid effluent-based estimates was to the child liver.

0 In calculations based on gaseous release pathways, vegetation was the predominant dose 0 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 7.06E-2 mrem to the child thyroid. No radioactivity was detected from gaseous pathways in environmental samples; therefore, there is no calculated dose. 0 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 40CFR190 dose commitment limits for members of 0 the public. Doses to members of the public attributable to the operation of ONS are being 0 maintained well within regulatory limits.

0 0

Section 4 - Page 2 0 0

0

0 0

TABLE 4.1-A 0 Page I of 3 OCONEE NUCLEAR STATION 0 2007 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON 0

0 LIOUID RELEASE PATHWAY 0

S Environmental Critical Critical Maximum Dose (3)

Organ or (1) (2) Location M mum )

0 Effluent Data Age Pathway (mrem) 0 Skin Environmental Teen Shoreline Sediment 067 (4.34 mi SSE) 7.80E-04 0 Skin Effluent Teen Shoreline Sediment Discharge Pt. 3.90E-04 0

Bone Environmental Child Fish 067 (4.34 mi SSE) 4.94E-02 S Bone Effluent Child Fish Discharge Pt. 2.35E-02 0

Liver Environmental Child Fish 067 (4.34 mi SSE) 1.01E-01 0 Liver Effluent Child Drinking Water 18.9 mi SSE 8.59E-02 0

0 T. Body Environmental Adult Fish 067 (4.34 mi SSE) 8.34E-02 0 T. Body Effluent Adult Fish Discharge Pt. 7.69E-02 0 Thyroid Environmental Child Drinking Water 066 (18.9 mi SSE) 5.41E-02 Thyroid Effluent Child Drinking Water 18.9 mi SSE 6.50E-02 0

Kidney Environmental Child Drinking Water 066 (18.9 mi SSE) 6.95E-02 0 Kidney Effluent Child Drinking Water 18.9 mi SSE 7.04E-02 0

Lung Environmental Child Drinking Water 066 (18.9 mi SSE) 5.96E-02 0 Lung Effluent Child Drinking Water 18.9 mi SSE 6.57E-02 0

GI-LLI Environmental Child Drinking Water 066 (18.9 mi SSE) 5.44E-02 0 GI-LLI Effluent Adult Fish Discharge Pt. 7.50E-02 0

(1) Critical Age is the highest total dose (all pathways) to an age group.

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

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

Section 4 - Page 3

0 0

Pae o 0

GASEOUS RELEASE PATHWAY Pae 0o S

IODINE, PARTICULATE, and TRITIUM Environmental or Critical Critical Maximum Dose (3)

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

Skin Environmental - 0.00E+00 Skin Effluent All Ground Plane 1.0 mi. SW 6.09E-05 Bone Environmental - 0.OOE+00 Bone Effluent Child Vegetation 1.0 mi. SW 2.16E-04 Liver Environmental - 0.00E+00 Liver Effluent Child Vegetation 1.0 mi. SW 1.91E-02 T. Body Environmental - 0.00E+00 T. Body Effluent Child Vegetation 1.0 mi. SW 1.91 E-02 Thyroid Environmental - o.OOE+00 Thyroid Effluent Child Vegetation 1.0 mi. SW 7.06E-02*

Kidney Environmental - 0.00E+00 Kidney Effluent Child Vegetation 1.0 mi. SW 1.92E-02 Lung Environmental - 0.OOE+00 Lung Effluent Child Vegetation 1.0 mi. SW 1.90E-02 GI-LLI Environmental - 0.OOE+00 GI-LLI Effluent Child Vegetation 1.0 mi. SW 1.90E-02

The highest hypothetical effluent organ dose was to the infant thyroid from goat milk. However, since no goats were identified by the land use census, 0v the most accurate comparison is to the dose to the child thyroid from vegetation. 0 0

(1) Critical Age is the highest total dose (all pathways) to an age group. 0 (2) Critial Pathway is the highest individual dose within the identified Critical Age group.

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

0 0

0 Section 4 - Page 4 0 0

0 Page 3 of 3 0 NOBLE GAS Air Environmental or Critical Critical Maximum Dose 0 Dose Effluent Data Age Pathway (mrad) 0 Beta Environmental - Not Sampled Beta Effluent N/A Noble Gas 1.0 mi. SW 2.09E-02 0 Gamma Environmental - Not Sampled Gamma Effluent N/A Noble Gas 1.0 mi. SW 7.96E-03 0

0 0

S 0

0 0

0 Section 4 - Page 5 0

TABLE 4.1-B Maximum Individual Dose for 2007 based on Environmental Measurements (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 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-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 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-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 4.16E-02 4.16E-02 4.16E-02 4.16E-02 4.16E-02 4.16E-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 Broadleaf Vegetation O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fish 4.94E-02 5.98E-02 1.95E-02 1.25E-02 2.79E-02 1.80E-02 1.28E-02 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 1.40E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.63E-04 TOTAL 4.94E-02 1.01E-01 6.12E-02 5.41E-02 6.95E-02 5.96E-02 5.44E-02 1.63E-04 Teen 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 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-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 Broadleaf Vegetation O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fish 3.92E-02 6.73E-02 3.33E-02 1.51E-02 3.29E-02 2.20E-02 1.59E-02 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 6.69E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.80E-04 TOTAL 3.92E-02 8.90E-02 5.57E-02 3.68E-02 5.46E-02 4.37E-02 3.76E-02 7.80E-04 Adult 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 3.08E-02 3.08E-02 3.08E-02 3.08E-02 3.08E-02 3.08E-02 0.00E+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 Broadleaf Vegetation O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Fish 3.67E-02 6.98E-02 5.25E-02 1.97E-02 3.67E-02 2.53E-02 2.06E-02 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 1.20E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.40E-04 TOTAL 3.67E-02 1.01E-01 8.34E-02 5.05E-02 6.75E-02 5.61E-02 5.14E-02 1.40E-04 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6 Oo*@ooOO@@OOoOeO@@@@O@OO@@@@O@@@@O@O@@@@@@0

Oconee Nuclear Station Dose from Drinking Water Pathwayfor 2007 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake in one year) = 330 1 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 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.011E+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 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+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 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 Co-60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Zn-65 1.84E-05 6.3 1E-05 2.9 1E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 0.00E+00 0.00E+00 0.O0E+00 0.OOE+00 0.00F+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 0.00E+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 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.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 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E +00 0.O0E+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 O.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 6.11 E-04 4.33E-05 NO DATA 1.64E.04 6.64E-05 1.91E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00) 0.00E+00 O.OOE+00 BaLa-140 1.7 lE-04 1.7 1E-07 8.81 E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 ALL 0.00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+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-07 066 402 0.00E+00 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-02 Dose Commitment (mrem) = O.00E+00 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-02 Section 4 - Page 7

Oconee Nuclear Station Dose from Drinking Water Pathwayfor 2007 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

Usage (intake in one year) = 510 1 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 1.07E-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 0.00E+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA l.05E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+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 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Nb-95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 ALL 0.00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 i.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 0.00E+00 0.00E+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 i.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+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 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0.00 0.OE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+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-07 066 402 0.OOE+00 4.16E-02 4.16E-02 4.16E-02 4.16E-02 4.16E-02 4.16E-02 Dose Commitment (mrem) = 0.OOE+00 4.16E-02 4.16E-02 4.16E-02 4.16E-02 4.16E-02 4.16E-02 Section 4 - Page 8 01001*000000 000 0000000 00004D0000000600 00*09000100

Oconee Nuclear Station Dosefrom Fish Pathwayfor 2007 Data Maximum Exposed Child Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mremn/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 9910 pCi/I x 0.9 = 8919 pCi/kg Usage (intake in one year) = 6.9 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Fish Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E -06 ALL 0.00 0.00E+00) 0.00EW0O 0.00E+00 0.00E+00 O.OOE+00 0.0OE+00) O.00E+0O Co-58 NO DATA 1 .80E-06 5.5 1E-06 NO DATA NO DATA NO DATA 1.05EF-0S ALL 0.00 (LOOE+00 0A)OE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+0O Fe-59 I.65E-05 2.67E-05 I .33E-05 NO DATA NO DATA 7.74E-06 2.78C,-05 ALL 0.00 O.OOE+00 0.OOE+00 O.IOE+O0 O.OOE+00 0.00E+00 0.OOF+00 O.OOE+0O CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93F-05 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+O0 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41F-06 ALL 0.00 0.00E+00 0A(OE+00 0,00E+00 O.OOE+00 O.OOE+00 O.OOE+0O O.OOE+OO Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.00E+00 0,00E+00) 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+O0 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 067 21.9 4.94E-02 4.73E-02 6.98E-03 O.OOE+00 1.54E-02 5.55E-03 2.96E-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 8919 0.00E+00 1.25E-02 1 .25E-02 1.25E-02 1.25E-02 1.25E-02 I1.25E-02 Dose Commitment (mrero) = 4.94E-02 5.98E-02 1.95E-02 1.25E-02 2.79E-02 1.80E-02 I.28E-02 Section 4 - Page 9

Oconee Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2007 Data Maximum Exposed Child Shoreline Recreation 14 hr (in one year)

Shore Width Factor = 0.2 2

Sediment Surface Mass = 40 kg/m Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/mr2) x Shore Width Factor x Sediment Surface Mass (kg/mr2) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mremn/hr per pCi/m 2) Indicator Sediment (mrem)

Radionuclide T. Body Skin Location (pCi/kg) T. Body Skini Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.OOE+00 0.OOE+00 Cs-137 4.20E-09 4.90E-09 067 297 1.40E-04 1.63E-04 Dose Commitment (n trem) = 1.40E-04 1.63E-04 Section 4 -Page 10 O00 00 0 0 000 0 00 00 00 00 00 0 0010QOOOO000

@OO@.....O@...@OO.@O@@O@@.e.O0eeO@@@S0eO@O@

Oconee Nuclear Station Dose from Drinking Water Pathwayfor 2007 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (1)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 1.1I7E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 O.00E+00 0.OOE+00 0.09E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O9E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.00E+00 o.OOiE+oo 0.OOE+00 0.OOE+00 0.OO11+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 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.81 E-06 6.33E~-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.OOE+00 0.0011+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 0.0011+00 0.OOE+00 0.OOE÷00 0.OOE+00 0.OOE+00 Nb-95 8.22E-09 4.56E-09 2.51 E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 0.00 0.OOE+00 0.00E+00 0.O0E+00 0.OOE+00 0.Of11+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.OOE-05 ALL 0.00 0.OOE+00 0.00E+00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.O+001+H 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+00 0.OOE+0() 0.OOE+00 Cs- 134 8.37E-05 1.97E-04 9.1I4E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+0() 0.OOE+00 0.OOE+00 0.OOE+00 0.OO11+00 Cs-137 1.12E-04 1.49E-04 5.1911-05 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-07 066 402 0.OOE+00 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 Dose Commitment (ntrern)= 0.OOE+00 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 Section 4 - Page I I

Oconee Nuclear Station Dosefrom Fish Pathwayfor 2007 Data Maximum Exposed Teen Teen Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (nirem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 9910 pCi/I x 0.9 = 8919 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 Wr-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21 E-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 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Co-60 NO DATA 2.8 1E-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 0.00E+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 O.OOE+00 Cs-134 8.37E-05 i.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 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Cs- 137 1.12E-04 1.49E-04 5.1 9E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 067 21.9 3.92E-02 5.22E-02 1.82E-02 0.00E+00 1.78E-02 6.90E-03 7.43E-04 1H-3 NO DATA 1.06E-07 1 .06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 063.1 8919 0.OOE+00 1.51 E-02 1.51E-02 1.51E-02 1.51E-02 1.51E-02 ISI5E-02 Dose Commitment (mrem) = 3.92E-02 6.73E-02 3.33E-02 1.51F-02 3.29E-02 2.20E-02 1.59E-02 Section 4 - Page 12 0000000000000004lis0 0 0 0 0 0 0000

Oconee Nuclear Station Dose from Shoreline Sediment Pathwayfor 2007 Data Maximum Exposed Teen Shoreline Recreation = 67 hr (in one year)

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

External Dose Factor Standing IHighest Annual Net Dose on Contaminated Ground N'ean Concentration (mrem/hr per pCi/mr2) In dicator Sediment (mrem)

Radionuclide T. Body Skin Lo cation (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-09 067 297 6.69E-04 7.80E-04 Dose Commitment (mrem) = 6.69E-04 7.80E-04 Section 4 - Page 13

Oconee Nuclear Station Dosefrom Drinking Water Pathwayfor 2007 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (i) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

Usage (intake in one year) = 730 1 Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCiII) Bone Liver T. Body Thyroid Kidney Lung GI-LLL Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51 E-05 ALL 0.00 0.OOE+00 0.0011+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Fe-59 4.34E-06 1.02E.05 3.91 E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.0013+00 0.00E+00 0.00E+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00F+00 0.00E+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 0.0011+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.0011+00 0.00E+00 Zr-95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00F+00 0.00E+00 0.00E+00 1-131I 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 6.22E-05 1.48E-04 1.21IE-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.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 2.11 E-06 ALL 0.00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 BaLa-140 2.03E-05 2.55E-08 1 .33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 ALL 0.00 0.OOE+00 0.0011+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 11-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 066 402 0.OOE+00 3.08E-02 3.08E-02 3.08E-02 3.08E-02 3.08E-02 3.08E-02 Dose Commitment (mrem) = 0.002E+00 3.08E-02 3.08E-02 3.08E-02 3.08E-02 3.08E-02 3.08E-02 Section 4 - Page 14

Oconee Nuclear Station Dosefrom Fish Pathwayfor 2007 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/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 9910 pCi/l x 0.9 = 8919 pCi/kg Usage (intake in one year) 21 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Thyroid Kidney Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Lung GI-LLI Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA IAO0E-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 i.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 0.00E+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Co-641 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.tIOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0,0OE+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 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 6.22E-05 1.48F-04 1.2 1E-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 0.00I(+00 0.OOE+00 Cs- 137 7.97E-05 I .0E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11 E-06 067 21.9 3.67E-02 5.0 1E-02 3.28E-02 0.OOE+00 1.70E-02 5.66E-03 9.70E-04 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 063.1 8919 0.OOE+00 1.97E-02 1.97E-02 1.97E-02 1.97E-02 1.97E-02 1.97E-02 Dose Commitment (nirero) = 3.67E-02 6.98F-02 5.25E-02 1.97E-02 3.67E-02 2.53E-02 2.06E-02 Section 4 - Page 15

Oconee Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2007 Data Maximum Exposed Adult Shoreline Recreation = 12 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/m2 Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mremi/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.OOE+00 0.OOE+00 Cs-137 4.20E-09 4.90E-09 067 297 1.20E-04 1.40E-04 Dose Commitment (mnrem) = 1.20E-04 1.40E-04 Section 4 - Page 16 0 0 0 0 0 00 0 40 09 0 *0 (a 00 0 00 0 0 0 0 0 0

0 0

0 5.0 QUALITY ASSURANCE

5.1 SAMPLE COLLECTION 0

0EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental sample 0collections as specified by approved sample collection procedures.

0

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.

5.3 DOSIMETRY ANALYSIS Duke Energy Corporation's

Environmental Center SThe Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

0 5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE

5.4.1 DAILY QUALITY CONTROL

EnRad Laboratories has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to 0monitor instrument performance.

0 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 frequency is dependent upon instrument use and performance. Investigations are performed and

documented should calibration verification data fall out of limits.

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 analyses.

0 O ~Section 5 -Page 1 0

0

0 0

5.5 DUKE ENERGY INTERCOMPARISON PROGRAM

0 EnRad Laboratories participated in the Duke Energy Nuclear Generation Department Intercomparison Program during 2007. 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 by the four counting laboratories in Duke 0 Energy for this program. A summary of these Intercomparison Reports for 2007 is documented in Table 5.0-A.

5.6 DUKE ENERGY AUDITS

0 The Oconee Radiation Protection Section was not audited by the Quality Assurance Group O in 2007. The program was audited in 2006. There were no REMP recommendations as a result of the 2006 audit.

EnRad Laboratories was not audited by the Quality Assurance Group in 2007. The program 0 was audited in 2006. There were no REMP recommendations as a result of the 2006 audit. O 0

5.7 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The Oconee Nuclear Station Radiological Environmental Monitoring Program was not O audited by the NRC in 2007. The program was audited by the NRC in 2006 (reference 0 6.12). No findings were noted in the report.

0 5.8 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM Oconee Nuclear Station routinely participates with the Bureau of Radiological Health of the 0 State's Department of Health and Environmental Control (DHEC) in an intercomparison O program. Water, milk, vegetation, sediment, and fish samples collected by EnRad Laboratories are routinely split with DHEC for intercomparison analysis. DHEC collects air samples near two of the locations sampled for air by ONS. Results of the analyses performed on split and duplicate samples are sent to DHEC. 0 0

5.9 TLD INTERCOMPARISON PROGRAM 0 5.9.1 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM 0 Radiation Dosimetry and Records participates in a quarterly TLD intercomparison 0 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 unknown estimated delivered exposure. A summary of the Nuclear Technology Services Intercomparison Report is documented in Table 5.0-B.

0 0

Section 5 - Page 2 0 0

0

0 0 5.9.2 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM 0 The State of North Carolina Radiation Protection Section suspended this program 0 during 2007 as described in PIP G-07-00366.

5.9.3 INTERNAL CROSSCHECK (DUKE ENERGY) 0 Radiation Dosimetry and Records participates in a quarterly TLD intracomparison 0 program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff 0 irradiates environmental dosimeters quarterly and submits them for analysis of the unknown estimated delivered exposure. A summary of the Internal Cross Check 0 (Duke Energy) Result is documented in Table 5.0-B.

0 0

S 0

0 0

S 0

0 0

S Section 5 - Page 3

0 0

0 TABLE 5.0-A 0 DUKE POWER COMPANY 0 INTERLABORATORY COMPARISON PROGRAM 0 2007 CROSS-CHECK RESULTS FOR 0

ENRAD LABORATORIES 0 0

Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all three analyses yielded results within the designated acceptance range. A status of "1 Pass" indicates that one 0 analysis of the cross-check was performed. 0 If applicable, footnote explanations are included following this data table. 0 0

Gamma in Water 3.5 liters Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0

Date Range Value Value Status 0 pCi/I pCi/1 pCi/I 6/26/2007 Q072GWR Cr-51 1.06- 1.88 E4 1.41 E4 1.37 E4 3 Pass 0

Co-57 2.68-4.76 E2 3.58 E2 3.80 E2 3 Pass 0 Co-60 Sr-85 1.46-2.59 1.83-3.24 E3 E3 1.95 2.44 E3 E3 1.94 2.30 E3 E3 3

3 Pass Pass 0

Y-88 2.82-5.00 E3 3.76 E3 3.62 E3 3 Pass 0 Cd-109 Sn-I 13 0.77- 1.36 1.40-2.49 E4 E3 1.02 1.87 E4 E3 1.07 1.85 E4 E3 3

3 Pass Pass 0

Te-123M 3.73-6.61 E2 4.97 E2 4.78 E2 3 Pass 0 Cs-137 1.13-2.00 E3 1.51 E3 1.45 E3 3 Pass 0

11/20/2007 Q074GWS Cr-51 2.96-5.24 E5 3.94 E5 3.97 E5 3 Pass 0 Co-57 1.33-2.37 E4 1.78 E4 1.86 E4 3 Pass 0 Co-60 7.33 - 12.99 E4 9.77 E4 9.69 E4 3 Pass Sr-85 7.21 - 12.78 E4 9.61 E4 9.48 E4 3 Pass 0 Y-88 1.23-2.19 E5 1.65 E5 1.64 E5 3 Pass 0 Cd-109 3.93- 6.96 E5 5.24 E5 5.31 E5 3 Pass Sn-l13 6.18- 10.96 E4 8.24 E4 8.29 E4 3 Pass 0 Te-123M 1.61-2.85 E4 2.15 E4 2.20 E4 3 Pass 0 Cs-137 6.07 - 10.76 E4 8.09 E4 7.82 E4 3 Pass 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 6/26/2007 Q072GWR Cr-5 pCi/I 1.06- 1.88 E4 pCi/I pCi/l 0

1.41 E4 1.41 E4 3 Pass Co-57 2.68- 4.76 E2 3.58 E2 3.89 E2 3 Pass 0 Co-60 1.46-2.59 E3 1.95 E3 1.97 E3 3 Pass 0 Sr-85 1.83- 3.24 E3 2.44 E3 2.37 E3 3 Pass Y-88 2.82-5.00 E3 3.76 E3 3.77 E3 3 Pass 0 Cd-109 0.77- 1.36 E4 1.02 E4 1.06 E4 3 Pass 0 Sn- 113 1.40-2.49 E3 1.87 E3 1.87 E3 3 Pass Te-123M 3.73- 6.61 E2 4.97 E2 5.03 E2 3 Pass 0 Cs-137 1.13-2.00 E3 1.51 E3 1.38 E3 3 Pass 0 0

0 Section 5 - Page 4 0

0 Gamma in Water 1.0 liter, continued 0 11/20/2007 Q074GWS Cr-51 2.96-5.24 E5 3.94 E5 4.00 E5 3 Pass Co-57 1.33-2.37 E4 1.78 E4 1.87 E4 3 Pass Co-60 7.33 - 12.99 E4 9.77 E4 9.80 E4 3 Pass Sr-85 7.21 - 12.78 E4 9.61 E4 9.61 E4 3 Pass Y-88 1.23-2.19 E5 1.65 E5 1.66 E5 3 Pass Cd-109 3.93- 6.96 E5 5.24 E5 5.36 E5 3 Pass Sn-113 6.18- 10.96 E4 8.24 E4 8.34 E4 3 Pass Te-123M 1.61-2.85 E4 2.15 E4 2.19 E4 3 Pass Cs-137 6.07 - 10.76 E4 8.09 E4 7.95 E4 3 Pass Gamma in Water 0.5 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status 0 6/26/2007 Q072GWR Cr-51 pCi/I 1.06-1.88 E4 pCi/I 1.41 E4 pCi/I 1.41 E4 3 Pass 0 Co-57 2.68-4.76 E2 3.58 E2 3.76 E2 3 Pass 0 Co-60 Sr-85 1.46-2.59 1.83-3.24 E3 E3 1.95 2.44 E3 E3 1.97 2.32 E3 E3 3

3 Pass Pass 0 Y-88 2.82-5.00 E3 3.76 E3 3.62 E3 3 Pass 0 Cd-109 Sn-113 0.77- 1.36 1.40-2.49 E4 E3 1.02 1.87 E4 E3 1.02 1.87 E4 E3 3

3 Pass Pass 0 Te-123M 3.73-6.61 E2 4.97 E2 4.88 E2 3 Pass 0 Cs-137 1.13-2.00 E3 1.51 E3 1.40 E3 3 Pass 11/20/2007 Q074GWS Cr-51 2.96-5.24 E5 3.94 E5 3.95 E5 3 Pass 0 Co-57 1.33-2.37 E4 1.78 E4 1.79 9.54 E4 E4 3

3 Pass Pass Co-60 7.33- 12.99 E4 9.77 E4 Sr-85 7.21 - 12.78 E4 9.61 E4 9.28 E4 3 Pass 0 Y-88 1.23-2.19 E5 1.65 E5 1.61 E5 3 Pass Pass Cd-109 3.93- 6.96 E5 5.24 E5 5.26 E5 3 Sn-113 6.18-10.96 E4 8.24 E4 8.16 E4 3 Pass Te-123M 1.61 -2.85 E4 2.15 E4 2.13 E4 3 Pass Cs-137 6.07- 10.76 E4 8.09 E4 7.59 E4 3 Pass 0

0 Gamma in Water 0.25 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status 0 6/26/2007 Q072GWR Cr-51 pCi/I 1.06- 1.88 E4 pCi/I 1.41 E4 pCi/I 1.44 E4 3 Pass 0 Co-57 2.68-4.76 E2 3.58 E2 3.95 E2 3 Pass Co-60 1.46-2.59 E3 1.95 E3 1.93 E3 3 Pass Sr-85 1.83- 3.24 E3 2.44 E3 2.42 E3 3 Pass Y-88 2.82-5.00 E3 3.76 E3 3.67 E3 3 Pass Cd-109 0.77- 1.36 E4 1.02 E4 1.07 E4 3 Pass Sn- 113 1.40-2.49 E3 1.87 E3 1.86 E3 3 Pass 0 Te-123M 3.73-6.61 E2 4.97 E2 4.86 E2 3 Pass 0 Cs- 137 1.13-2.00 E3 1.51 E3 1.45 E3 3 Pass 0 I I S

0 Section 5 - Page 5 0

0

Gamma in Water 0.25 liter, continued 11/20/2007 Q074GWS Cr-51 2.96-5.24 E5 3.94 E5 3.90 E5 3 Pass 0

Co-57 1.33- 2.37 E4 1.78 E4 1.82 E4 3 Pass 0 Co-60 Sr-85 7.33 - 12.99 7.21 - 12.78 E4 E4 9.77 9.61 E4 E4 9.56 9.27 E4 E4 3

3 Pass Pass 0

Y-88 1.23-2.19 E5 1.65 E5 1.62 E5 3 Pass 0 Cd-109 Sn-i 13 3.93-6.96 6.18- 10.96 E5 E4 5.24 8.24 E5 E4 5.12 8.08 E5 E4 3

3 Pass Pass 0

Te-123M 1.61-2.85 E4 2.15 E4 2.15 E4 3 Pass 0 Cs-137 6.07 - 10.76 E4 8.09 E4 7.67 E4 3 Pass 0 0

Gamma in Filter 0 Reference Date Sample I.D, Nuclide Acceptance Range Reference Value Mean Reported Value Cross Check Status 0

pCi pCi pCi 0 6/14/2007 E5415-37 Cr-51 Mn-54 2.63-4.67 0.86-1.52 E2 E2 3.51 E2 1.14 E2 3.25 1.18 E2 E2 3

3 Pass Pass 0

Co-58 1.02-1.81 E2 1.36 E2 1.28 E2 3 Pass 0 Fe-59 Co-60 0.86- 1.52 1.22-2.17 E2 E2 1.14 E2 1.63 E2 1.20 1.57 E2 E2 3

3 Pass Pass 0

Zn-65 1.72-3.05 E2 2.29 E2 2.31 E2 3 Pass 0 Cs-134 Cs-137 1.25-2.21 0.87- 1.54 E2 E2 1.66 E2 1.16 E2 1.48 1.06 E2 E2 3

3 Pass Pass 0

Ce-139 0.00-0.00 El 0.OOE+00 3.10 E1 3 Pass~') 0 Ce-141 1.03- 1.82 E2 1.37 E2 1.29 E2 3 Pass 0 0

Iodine in Water 0 Reference Date Sample I.D. Nuclide Acceptance Range Reference Value Mean Reported Value Cross Check Status 0

pCi/l pCi/I pCi/l 0

5/15/2007 Q072LIW 1 I-131 N/A 0.00E+00 0.00E+00 3 Pass 0

5/15/2007 Q072LIW2 1-131 1.84- 3.27 E3 2.46 E3 2.06 E3 3 Pass 0 5/15/2007 Q072LIW3 1-131 1.70- 3.01 El 2.26 E1 2.20 E1 3 Pass 0

0 0

Iodine in Milk Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0

Date Range Value Value Status 0 pCi/l pCi/1 pCi/l 7/25/2007 Q073LIM1 1-131 0.95-1.68 E3 1.27 E3 1.11 E3 3 Pass 0

0 7/25/2007 Q073LIM2 1-131 3.62-8.34 E0 5.49 E0 5.65 E0 3 Pass 0

7/25/2007 Q073LIM3 1-131 2.30-4.07 El1 3.06 E1 2.67 E 1 3 Pass 0 0

0 0

Section 5 - Page 6 0

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0 S

0 0

Iodine on Cartridge Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status 0 6/14/2007 E5416-37 1-131 pCi 5.92- 10.49 El pCi 7.89 El pCi 9.77 El 3 Pass Beta Air Particulate 0

0 Beta in Water 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status 0 6/14/2007 E541.-37 Cs-137 pCi/l 1.l- 1.97 E2 pCi/l 1.48 E2 pCi/l 1.58 E2 3 Pass Beta Smear 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status dpm dpm dpm 0 1/11/2007 A21058-04 Beta 1.01 - 1.80 E4 1.35 E4 1.32 E4 3 Pass 0 Tritium 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 6/25/2007 Q072TWRI H-3 3.87-7.69 E2 5.45 E2 4.83 E2 3 Pass 6/25/2007 Q072TWR2 H-3 0.78- 1.38 E4 1.04 E4 0.98 E4 3 Pass 0

6/25/2007 Q072TWR3 H-3 1.32-2.34 E3 1.76 E3 1.64 E3 3 Pass 10/7/2007 Q074TWSLI H-3 N/A 0.OOE+00 0.OOE+00 3 Pass 10/7/2007 Q074TWSL2 H-3 2.71 - 4.81 E4 3.62 E4 3.63 E4 3 Pass 0

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0 0 Section 5 - Page 7

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Table 5.0-A Footnote Explanations 0 0

(1) Gamma in Filter, Sample ID E5415-37, Reference Date 6/14/2007 0

0 Ce-139 was identified in cross-check sample and reported. The cross check 0 supplier does not include this radionuclide on the certificate of analysis for this 0 cross-check sample. The radionuclide was determined to be an inherent contaminant in the cross-check sample.

0 0

Section 5 - Page 8 0 0

TABLE 5.0-B 2007 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Nuclear Technology Services 1st Quarter 2007 2nd Quarter 2007 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 102164 73.0 73.4 0.55 <+/-15% Pass 102493 90.5 92.8 2.54 <+/-15% Pass 102322 73.0 77.3 5.89 <+/-15% Pass 102316 90.5 94.2 4.09 <+/-15% Pass 102263 73.0 76.0 4.11 <+/-15% Pass 102476 90.5 94.0 3.87 <+/-15% Pass 102250 73.0 77.8 6.58 <+/-15% Pass 102492 90.5 94.6 4.53 <+/-15% Pass 102184 73.0 79.3 8.63 <+/-15% Pass 102470 90.5 92.7 2.43 <+/-15% Pass Average Bias (B) 5.15 Average Bias (B) 3.49 Standard Deviation (S) 3.04 Standard Deviation (S) 0.95 Measure Performance IBI+S 8.19 <15% Pass Measure Performance JBI+S 4.44 <15% Pass 3rd Quarter 2007 4th Quarter 2007 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 0 102174 65.5 63.7 -2.75 <+/-15% Pass 102006 92.2 99.0 7.38 <+/-15% Pass 0 102220 102236 65.5 65.5 67.7 64.5 3.36

-1.53

<+/-l 5%

<+/-15%

Pass Pass 102093 102244 92.2 92.2 97.5 103.6 5.75 12.36

<+/-15%

Pass Pass 0 102302 65.5 66.5 1.53 <+/-15% Pass 102343 92.2 100.3 8.79 <+/-15% Pass 0 102304 65.5 66.1 0.92 <+/-15% Pass 102436 92.2 100.7 9.22 <+/-15% Pass Average Bias (B) 0.31 Average Bias (B) 8.70 0 Standard Deviation (S) 2.44 Standard Deviation (S) 2.46 0 Measure Performance IBI+S 2.75 <15% Pass Measure Performance IBI+S 11.16 <15% Pass S

0 0

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0 Section 5 - Page 9 S

0

Internal Crosscheck (Duke Energy) 1st Quarter 2007 2nd Quarter 2007 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/Faill 100770 24.0 22.3 -6.97 <+/-15% Pass 101190 48.0 47.1 -1.88 <+/-15% Pass 100522 24.0 23.6 -1.70 <+/-15% Pass 100026 48.0 46.4 -3.33 <+/-15% Pass 100041 24.0 22.0 -8.22 <+/-15% Pass 100148 48.0 46.3 -3.54 <+/-15% Pass 100038 24.0 23.0 -4.28 <+/-15% Pass 100038 48.0 47.2 -1.67 <+/-15% Pass 100762 24.0 21.1 -11.93 <+/-15% Pass 100096 48.0 46.4 -3.33 <+/-15% Pass 100148 24.0 23.2 -3.41 <+/-15% Pass 100770 48.0 46.1 -3.96 <+/-15% Pass 100279 24.0 23.0 -4.37 <+/-15% Pass 100740 48.0 46.9 -2.29 <+/-15% Pass 100619 24.0 23.2 -3.48 <+/-15% Pass 100784 48.0 45.6 -5.00 <+/-15% Pass 100784 24.0 22.0 -8.45 <+/-15% Pass 100619 48.0 47.1 -1.88 <+/-15% Pass 100814 24.0 22.8 -4.93 <+/-15% Pass 100814 48.0 47.0 -2.08 <+/-15% Pass Average Bias (B) -5.77 Average Bias (B) -2.90 Standard Deviation (S) 3.07 Standard Deviation (S) 1.10 Measure Performance IBI+S 8.84 <15% Pass Measure Performance jBI+S 4.00 <15% Pass 3rd Quarter 2007 4th Quarter 2007 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 100389 24.0 22.7 -5.42 <+/-15% Pass 100412 12.0 11.9 -0.83 <+/-15% Pass 100407 24.0 22.8 -5.00 <+/-15% Pass 100733 12.0 11.3 -5.83 <+/-15% Pass 100629 24.0 22.9 -4.58 <+/-15% Pass 100477 12.0 11.6 -3.33 <+/-15% Pass 100409 24.0 23.7 -1.25 <+/-15% Pass 100406 12.0 11.5 -4.17 <+/-15% Pass 100647 24.0 23.5 -2.08 <+/-15% Pass 100863 12.0 11.8 -1.67 <+/-15% Pass 100274 24.0 22.8 -5.00 <+/-15% Pass 100870 12.0 11.6 -3.33 <+/-15% Pass 100117 24.0 22.6 -5.83 <+/-15% Pass 100752 12.0 12.1 0.83 <+/-15% Pass 100162 24.0 22.1 -7.92 <+/-15% Pass 101021 12.0 11.6 -3.33 <+/-15% Pass 100423 24.0 23.1 -3.75 <+/-15% Pass 100096 12.0 11.9 -0.83 <+/-15% Pass 100611 24.0 23.6 -1.67 <+/-15% Pass 101307 12.0 11.4 -5.00 <+/-15% Pass Average Bias (B) -4.25 Average Bias (B) -2.75 Standard Deviation (S) 2.09 Standard Deviation (S) 2.08 Measure Performance IBI+S 6.34 <15% Pass Measure Performance IB1+S 4.83 <15% Pass

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S Section 5 -Page 10 5 S

0 0

6,0 REFERENCES 0

S6.1 Oconee Selected License Commitment Manual 6.2 Oconee Technical Specifications 6.3 Oconee Updated Final Safety Analysis Report 0

6.4 Oconee Offsite Dose Calculation Manual 6.5 Oconee Annual Radiological Environmental Operating Report 1969-2006 6.6 Oconee Annual Radioactive Effluent Release Report 2007 6.7 Probability and Statistics in Engineering and Management Science, Hines and

Montgomery, 1969, pages 287-293.

0 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 0Doses to Man from Routine Releases of Reactor Effluents for the Purposes of

Evaluating Compliance with 10CFR50, Appendix I.

6.10 EnRad Laboratories Operating Procedures 6.11 RETDAS, Radiological Effluent Tracking and Dose Assessment Software, Canberra

Version 3.5.1, DPC Revision #4.0 0

6.12 NRC Integrated Inspection Report 50-269/06-03, 50-270/06-03, 50-287/06-03, and 0 72-4/06-01 6.13 Duke Energy Corporation EnRad Laboratory Charcoal Cartridge Study, performed 2001 S

0 0

O ~Section 6 -Pagel1 0

0 0

0 0 APPENDIX A 0

0 0

0 ENVIRONMENTAL SAMPLING 0

0 0 ANALYSIS PROCEDURES 0

0 0

0 Appendix A - Page I 0

0

0 0

APPENDIX A 0 0

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 Conmmitments detection capabilities were achieved.

0 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 Location 084 (Air Radioiodine, Air Particulate, Vegetation) was added as a replacement for indicator location 060 (Air Radioiodine, Air Particulate, Vegetation), which was removed from the program. Movement of the indicator air radioiodine, air particulate, and vegetation location is described in PIP G-06-00180.

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.

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 A

0 0

Appendix A -Page 2 0 0

0 0

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

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

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

0 III. CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 2007.

0 S IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE 0

Airborne particulate and radioiodine samples at each of six locations were 0 composited continuously by means of continuous air samplers. Air particulates 0 were collected on a particulate filter and radioiodines were collected in a 0 charcoal cartridge positioned behind the filter in the sampler. The samplers are 0 designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute. Filters 0 and cartridges were collected weekly. A separate weekly gamma analysis was 0 performed on each charcoal cartridge and air particulate. A weekly gross beta analysis was performed on each filter. The continuous composite samples were collected from the locations listed below.

0 0 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)

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) 0 0 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 0 composites. Tritium analysis was performed on the quarterly composites. The S composites were collected monthly from the locations listed below.

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

Location 064 Seneca (6.67 mi. SSW) 0 Location 066 Anderson (18.9 mi SSE) 0 Appendix A - Page 3

0 S

0 A.3 SURFACE WATER 0

Monthly composite samplers were operated to collect an aliquot. at least every 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) 0 Location 063.1 Lake Hartwell Hwy 183 Bridge (0.79 mi. E) 0 A.4 MILK S

Semimonthly grab samples were collected at one location. A gamma and low- 0 level Iodine-131 analysis was performed on each sample. The semimonthly 0 grab samples were collected from the location listed below. 0 Location 071 = Clemson Dairy (10.2 mi. SSE) 0 A.5 BROADLEAF VEGETATION Monthly samples were collected and a gamma analysis was performed on each sample. The samples were collected from the locations listed below. S 0

Location 077 Skimmer Wall (1.00 mi. SW)

Location 079 Keowee Dam (0.56 mi. NE) 0 Location 081 Clemson Operations Center (9.33 mi. SE) 0 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 S edible portions of each sample. The samples were collected from the locations 0 listed below. S Location 060 Greenville Water Intake Rd. (2.28 mi. NE)

Location 063 Lake Hartwell Hwy 183 Bridge (0.80 mi. ESE) 0 Location 067 Lawrence Ramsey Bridge Hwy 27 (4.34 mi. SSE) 0 A.7 SHORELINE SEDIMENT 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 were collected from the locations listed below.

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

Appendix A - Page 4

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

Location 068 = High Falls County Park (1.82 mi. W) 0 A.8 DIRECT GAMMA RADIATION (TLD)

Thermoluminescent dosimeters (TLD) were collected quarterly at forty-two

locations. A gamma exposure rate was determined for each TLD. The TLDs

- were placed as indicated below.

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

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

kilometer range.

0The remaining TLDs were placed in special interest areas such Sas population centers, residential areas, schools, and control

locations.

0

TLD Locations are listed in Table 2.1-B.

A.9 ANNUAL LAND USE CENSUS 0

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

S* The Nearest Residence S* The Nearest Milk-giving Animal (cow, goat, etc.) where milk is used for human consumption

- The census was conducted during the growing season from 6/5 to 6/6/2007.

- Results are shown in Table 3.9. No changes were made to the sampling

procedures during 2007 as a result of the 2007 census.

V. GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS

The Oconee site centerline used for GPS measurements was referenced from the

Oconee Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1.1, Specification of Location. Waypoint coordinates used for ONS GPS measurements were latitude 34°-47'-38.2"N and longitude 82°-53'-55.4"W. Maps

and tables were generated using North American Datum (NAD) 27. Data normally 0* reflect accuracy to within 2 to 5 meters from point of measurement. GPS field measurements were taken as close as possible to the item of interest. Distances for

the locations are displayed using three significant figures.

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O Appendix A - Page 5 0

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S APPENDIX B 0

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S RADIOLOGICAL 0 ENVIRONMENTAL MONITORING S

S PRO GRAM 0

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SUMMARY

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S Appendix B - Page I S

S

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2007 to 31-DEC-2007 Type and Location with Highest No. of Non-Medium or Medium Total Lower Limit Local M ean Control Routine Pathway Number of Detection All Indicator Locations Annual Mean Location Report Sampled of Name, Distance, Direction Meas.

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

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

BETA 312 L.OOE-02 2.20E-2 (260/260) 078 2.31E-2 (52/52) 2.13E-2 (52/52) 0 1.13E 4.41E-2 (0.58 mi WSW) 1.41E 4.15E-2 1.10E 3.88E-2 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 CS-137 312 6.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 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 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

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Report Generated @ 2/25/2008 09:43 Appendix B - Page 2 S

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0 0 Environmental Radiological Monitoring Program Summary S Facility: Oconee Nuclear Station Docket No. 50-269,270,287 0 Report Period: 01-JAN-2007 to 31-DEC-2007 Location: Oconee County, South Carolina 0

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

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

Air Radioiodine (pCi/m3) 081 (9.33 mi SE) 0 0 CS-134 312 5.OOE-02 0.00 (0/260) 0.00 - 0.00 0.00 (0/52) 0.00 - 0.00 0.00 (0/52) 0.00 - 0.00 0

CS-137 312 6.00E-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 1-131 312 7.OOE-02 0.00 (0/260) 0.00 (0/52) 0.00 (0/52) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 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

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Report Generated @ 2/25/2008 09:46 S Appendix B - Page 3 0

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

Location: Oconee County, South Carolina Report Period: 01-JAN-2007 to 31-DEC-2007 ControlNone No. of Non- 0 Type and Total Lower Location with Highest Medium or Pathway Number Limit of Annual Mean 0 Locations Location Report Sampled of Detection Name, Distance, Direction Lepor Meas.

0 S

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

Measurement Performed Range Code Range Range 0

0 Drinking Water 064 0 (pCi/liter) (6.67 mi SSW) 0 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 1.36 (21/26) 066 1.58 (12/13) 1.08 (9/13) 0 0.72 - 2.46 (18.9 mi SSE) 0.75 - 2.46 0.63 - 2.07 CO-58 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 CO-60 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 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 0 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 0 H-3 12 2000 402 (4/8) 066 402 (4/4) 0.00 (0/4) 0 285 - 498 (18.9 mi SSE) 285 - 498 0.00 - 0.00 1-131 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 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 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 NB-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 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 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 @2/25/2008 09:51 Appendix B - Page 4 0 0

0

0 0

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

Location: Oconee County, South Carolina Report Period: 01-JAN-2007 to 31-DEC-2007 S ControlNone No. of Non-Location with Highest 0 Medium or Pathway Type and Total Number Lower Limit of All Indicator Annual Mean týControl Routine Sampled of Detection Name, Distance, Direction Lepor Meas.

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

Measurement Performed Range Code Range Range 0 Surface Water 062 0 (pCi/liter) (0.85 mi ENE) 0 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 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CO-60 26 15 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0

0 CS-134 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 0 CS-137 26 18 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0

FE-59 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 8 2000 9910(4/4) 063.1 9910 (4/4) 0.00 (0/4) 0 1580- 19100 (0.79 mi E) 1580- 19100 0.00-0.00 0 1-131 26 15 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0

0 MN-54 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 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 0 ZN-65 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0 ZR-95 26 15 0.00 (0/13) 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 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 S

S Report Generated @ 2/25/2008 09:53 Appendix B - Page 5 0

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269, 270, 287 Location: Oconee County, South Carolina Report Period: 01-JAN-2007 to 31-DEC-2007 No. of Non-0 Medium or Type and Total Lower Location with Highest Annual Mean Control Routine 0

Pathway Number Limit of Indicator AllLocations Location Report Detection Name, Distance, Direction Meao.

Sampled of Meas..

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

Measurement Performed Range Code Range Range Milk NO INDICATOR 071 (10.2 mi SSE) Sl (pCi/liter) LOCATION BALA-140 27 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/27) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 27 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/27) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 27 18 0.00 (0/0) 0.00 (0/0) 0.00 (0/27) 0 W 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 1-131 27 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/27) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLI-131 27 1 0.00 (0/0) 0.00 (0/0) 0.00 (0/27) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

Iý w

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 S

S 0

S Report Generated @ 2/25/2008 09:56 Appendix B - Page 6 0

S

Environmental Radiological Monitoring Program Summary Facility: Oconee Nuclear Station Docket No. 50-269,270,287 Location: Oconee County, South Carolina Report Period: 01-JAN-2007 to 31-DEC-2007 0 No. of Non-Type and Total Lower Location with Highest ContrflNone Medium or 0 Pathway Number Limit of Annual Mean 0 Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

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

0 Broadleaf Vegetation 081 (9.33 mi SE) 0 (pCi/kg-wet) 0 CS-134 48 60 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 48 80 0.00 (0/36) 0.00 (0/12) 0.00 (0/12) 0 0 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 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

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

0 Report Generateti @ 2/25/2008 09:58 Appendix B - Page 7

S 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-2007 to 31-DEC-2007 0 INo. of Non- 0 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 Fish 060 (pCi/kg-wet) (2.28 mi NE)

CO-58 12 130 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 12 130 0.00 (0/8) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0,00 - 0.00 S

CS-134 12 130 0.00 (0/8) 0.00(0/4) 0.00 (0/4) 0 CS-137 12 150 0.00 - 0.00 31.6 (7/8) 067 0.00 - 0.00 41.0 (3/4) 0.00 - 0.00 19.1 (2/4) 0 0

15.7 -74.6 (4.34 mi SSE) 21.9 -74.6 13.3 - 24.9 0 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 0 MN-54 12 130 0.00 (0/8) 0.00 - 0.00 0.00 (0/4) 0.00 - 0.00 0.00 (0/4) 0.00 - 0.00 0

S 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 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

S 0

0 Report Generated @ 2/25/2008 10:02 Appendix B - Page 8

0 S 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-2007 to 31-DEC-2007 5 Medium or Type and Total Lower All Idit Location with Highest Control No. of Non-Routine Pathway Number Limit of Annual Mean S Sampled of Detection Name, Distance, Direction Lepor Meas.

Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction) 0 Measurement Performed Range Code Range Range S Shoreline 068 Sediment (1.82 mi W) 0 (pCi/kg-dry)

CS-134 6 S 150 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0 CS-137 6 180 0.00 - 0.00 218 (3/4) 067 0.00 - 0.00 297 (2/2) 0.00 - 0.00 0.00 (0/2) 0 59.9 - 473 (4.34 ml SSE) 122 - 473 0.00 - 0.00 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

0 0

0 0 Report Generated @ 2/25/2008 10:06 Appendix B - Page 9

0 0

S 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-2007 to 31-DEC-2007 0 No. of Non-Type and Total Lower Limit All Indicator Annalo Mean Medium or Number ofet L ocaton Ame,Ds an Control Routine Pathway Sampled of of Detection Locations Name, Distance, Direction Location Report Meas.

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

Performed Range Code Range Range Direct Radiation 0

TLD 058 (9.39 mi WSW) 0 (mR/standard quarter) 081 (9.33 mi SE)

S 168 0.OOE+00 21.6 (160/160) 036 27.6 (4/4) 27.0 (8/8) 0 0 12.7 -31.4 (4.32 mi N) 24.7-30.8 20.7 -34.0 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 S

0 0

S S

0 S

S 0

S S

0 0

S 0

0 Report Generated @ 2/25/2008 11:21 Appendix B - Page 10

0 0

0 APPENDIX C 0

0 0 SAMPLING DEVIATIONS 0

0 0 UNAVAILABLE ANALYSES 0

0 0

0 Appendix C - Page I 0

0

S S

0 APPENDIX C S 0

OCONEE NUCLEAR STATION S SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES 0

IWVTATTAN A~ I1NAVAITARhi~ 1WA~ON UOfl1~

BF Blown Fuse PO Power Outage S

FZ Sample Frozen PS Pump out of service / Undergoing Repair 0 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

0 C.1 SAMPLING DEVIATIONS S 0

Air Particulate and Air Radioiodines 0 Scheduled Actual Reason S Location Collection Dates Collection Dates Code Corrective Action Power to sampling equipment was S interrupted during composite period due 0 to a tripped breaker. The breaker was 081 1/22 - 1/29/2007 1/22 - 1/28/2007 PO reset and normal sampling resumed. 0 Power to sampling equipment was 0 interrupted during composite period due to a tripped breaker. The breaker was 0 081 11/26 - 12/3/2007 11/26 - 12/1/2007 PO reset and normal sampling resumed. 0 0

Drinking Water S Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action 0

Breaker supplying power to sampling 0 equipment tripped during composite S period. Insufficient composite sample was available. A grab sample was taken. S Breaker was reset, equipment verified operational, and normal sampling was 0

060 7/2 - 7/30/2007 7/30/2007 PO resumed. 0 S

0 S

S S

0 Appendix C - Page 2 S 0

S 0

0 Surface Water 0 Scheduled Actual Reason 0 Location Collection Dates Collection Dates Code Corrective Action Reservoir pump found inoperative at time of collection. Work request 42992 written. Problem identified as an electrical short in the reservoir pump.

The pump was replaced and normal 0 063.1 3/12 - 4/9/2007 3/13 - 4/9/2007 PS sampling resumed 3/13/2007 14:00.

Reservoir pump found inoperative at time of collection. Work request 46300 0 written. Daily grab samples were taken until flow was restored and normal 063.1 17/2 - 7/30/2007 17/2 - 7/30/2007 PS sampling was resumed 7/6/2007 16: 10.

0 C.2 UNAVAILABLE ANALYSES 0

There were no unavailable analyses during 2007.

0 0

0 S

0 0

S 0

0 0

Appendix C - Page 3 0

0

0 0

0 S

0 0

0 APPENDIX D 0

0 ANALYTICAL DEVIATIONS 0

0 No Analytical deviations were incurred for the 2007 Radiological Environmental Monitoring Program 0

0 0

0 Appendix D - Page 1

0 0

0 APPENDIX E 0

0 0 RADIOLOGICAL 0

0 ENVIRONMENTAL MONITORING 0 PROGRAM RESULTS 0

0 0

0 This appendix includes all of the sample analysis reports generated from each sample medium for 2007. Appendix E is located separately from 0 this report and is permanently archived at the Duke Energy Corporation Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.

0 0

0 S

0 Appendix E - Page 1 0

ML081440128

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