ML081370307

Annual Radiological Environmental Operating Report

ML081370307
Person / Time
Site:	Catawba
Issue date:	05/14/2008
From:	Morris J Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML081370307 (91)

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PkIDuke dAEnergyCarolinas JAMES R. MORRIS, VICE PRESIDENT Duke Energy Carolinas, LLC Catawba Nuclear Station 4800 Concord Road / CNO1 VP York, SC 29745 803-701-4251 803-701-3221 fax May 14, 2008 U.S. Nuclear Regulatory Commission ATTENTION:

Document Control Desk Washington, D.C. 20555-0001

Subject:

Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 2007 Annual Radiological Environmental Operating Report Pursuant to Catawba Nuclear Station Technical Specification 5.6.2 and Selected Licensee-Commitment 16.11-16, please find attached the 2007 Annual Radiological Environmental Operating Report. This report covers operation of Catawba Units I and 2 during the 2007 calendar year.Any questions concerning this report should be directed to Marc Sawicki at (803) 701-5191.Sincerely, R. Morris (Attachment) www. duke-energy.

com U.S. Nuclear Regulatory Commission 2007 Annual Radiological Environmental Operating Report May 14, 2008 Page 2 xc (with attachment):

Luis A. Reyes, NRC Region II Administrator U.S. Nuclear Regulatory Commission-Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 J. F. Stang, Jr., Senior NRR Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop 8 G9A Washington, D.C. 20555 A.T. Sabisch, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station 0 0 0* TABLE OF CONTENTS 0 1.0 Executive Smumary ...........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. 3-4 3.3 Surface Water 3-6 3.4 Ground Water 3-8 3.5 Milk. 3-9 3.6 Broadleaf Vegetation.

3-10 3.7 Food Products 3-12 3.8 Fish. 3-13 3.9 Shoreline Sediment 3-16 3.10 Direct Gamma Radiation 3-18 3.11 Land Use Census 3-20 4.0 Evaluation of Dose 4-1 4.1 Dose from Environmental Measurements 4-1 4.2 Estimated Dose from Releases 4-I 4.3 Comparison of Doses. 4-2 5.0 Quality Assurance 5-1 5.1 Sample Collection 5-1 5.2 Sample Analysis 5-1 5.3 Dosimetry Analysis 5-1 5.4 Laboratory Equipment Quality Assurance 5-1* 5.4.1 Daily Quality Control 5-1 5.4.2 Calibration Verification 5-1 5.4.3 Batch Processing 5-2 5.5 Duke Energy Intercomparison Program 5-2 5.6 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 .5-3 5.9.1 Nuclear Technology Services Intercomparison Program 5-3 5.9.2 State of North Carolina Intercomparison Program 5-3 5.9.3 Internal Crosscheck (Duke Energy) 5-3 6.0 References 6-1 0 0 Appendices Appendix A: Environmental Sampling and Analysis Procedures A-I 1 I. Change of Sampling Procedures A-2 II. Description of Analysis Procedures A-2 III. Change of Analysis Procedures

.A-3 IV. Sampling and Analysis Procedures A-3 A. I Airborne Particulate and Radioiodine A-3 A.2 Drinking Water A-3 A.3 Surface Water A-3 A.4 Ground Water. A-4 A.5 Milk A-4 A.6 Broadleaf Vegetation A-4 A.7 Food Products.

A-4 A.8 Fish A-5 A.9 Shoreline Sediment.

A-5 A. 10 Direct Gamma Radiation (TLD) A-5 A. 11 Annual Land Use Census A-5 0 V. Global Positioning System (GPS) Analysis.

A-6 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 Ground Water .B-6 Milk .B-7 Broadleaf Vegetation B-8 0 Food Products .B-9 Fish .B- 10 Shoreline Sediment B-11 I Direct Gamma Radiation (TLD) B-12 Appendix C: Sampling Deviations and Unavailable Analyses C-1 C.1 Sampling Deviations C-2 C.2 Unavailable Analyses C-3 Appendix D: Analytical Deviations D-I Appendix E: Radiological Environmental Monitoring Program Results E-1 0 LIST OF FIGURES 0 2.1-1 Sampling Locations Map (One Mile Radius) 2-4 2.1-2 Sampling Locations Map (Ten Mile Radius) 2-5 0 3.1 Concentration of Gross Beta in Air Particulate 3-2 3.2 Concentration of Tritium in Drinking Water 3-5 3.3 Concentration of Tritium in Surface Water. 3-6 3.6 Concentration of Cs- 137 in Broadleaf Vegetation 3-10 3.8-1 Concentration of Co-58 in Fish .3-14 3.8-2 Concentration of Co-60 in Fish .3-14 3.9-1 Concentration of Co-58 in Shoreline Sediment 3-16 0 3.9-2 Concentration of Co-60 in Shoreline Sediment 3-17 3.10 Direct Gamma Radiation (TLD) Results 3-18 3.11 2007 Land Use Census Map 3-21 0 0 S 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 LIST OF TABLES 2. 1-A Radiological Monitoring Program Sampling Locations 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites)2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2.2-B REMP Analysis Frequency 2.2-C Maximum Values for the Lower Limits of Detection 3. 1-A Mean Concentration of Gross Beta in Air Particulate 3.1 -B Mean Concentration of Air Radioiodine (1- 131) .3.2 Mean Concentrations of Radionuclides in Drinking Water 3.3 Mean Concentrations of Radionuclides in Surface Water 3.5 Mean Concentration of Radionuclides in Milk 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation 3.7 Mean Concentration of Radionuclides in Food Products 3.8 Mean Concentrations of Radionuclides in Fish 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment 3.10 Direct Gamma Radiation (TLD) Results 3.11 Land Use Census Results .4. 1-A 2007 Environmental and Effluent Dose Comparison 4.1-B Maximum Individual Dose for 2007 based on Environmental Measurements for Catawba Nuclear Station 5.0-A 2007 Cross-Check Results for EnRad Laboratories 5.0-B 2007 Environmental Dosimeter Cross-Check Results 2-6 2-7 2-8 2-8 2-9 3-3 3-3 3-5 3-7 3-9 3-11 3-12 3-15 3-17 3-19 3-20 4-3 4-6 5-4 5-9 LIST OF ACRONYMS USED IN THIS TEXT (in alphabetical order)BW Biweekly C Control CNS Catawba Nuclear Station DEHNR Deparment of Environmental Health and Natural Resources 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 mrem Millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual pCi/kg picocurie per kilogram pCi/l picocurie per liter pCi/m3 picocurie per cubic meter PIP Problem Investigation Process Q Quarterly REMP Radiological Environmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECs Technical Specifications TLD Thermoluminescent Dosimeter ltCi/mI microcurie per milliliter UFSAR Updated Final Safety Analysis Report W Weekly iii 0 0 0 0 0 0 0 S 0 0 0 S 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 P Duke WEnergy, Catawba Nuclear Station Units 1 and 2 AREOR Annual Radiological Environmental Operating Report 2007 0 0 0 0 S 0 0 0 0 S 0 0 0 0 0 S 0 0 0 0 S 0 0 0 0 Duke Energy.ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE ENERGY CORPORATION CATAWBA NUCLEAR STATION Units 1 and 2 2007 0** 1.0 EXECUTIVE

SUMMARY

• This Annual Radiological Environmental Operating Report describes the Catawba Nuclear*Station Radiological Environmental Monitoring Program (REMP), and the program results for 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 0sampling results. Quality assurance practices, sampling deviations, unavailable samples, and program changes are also discussed.

Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLCs). Required analyses were performed and detection capabilities were met for all*collected samples as required by SLCs. Eight-hundred ninety-five samples were analyzed*comprising 1,207 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 Catawba Nuclear Station is sufficient.

0 SConcentrations observed in the environment in 2007 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, drinking water, shoreline sediment, and fish are higher than the activities reported for samples collected prior to the operation of the station. Measured concentrations were not higher than expected, and all positively identified measurements were within limits as specified in SLCs.Additionally, environmental radiological monitoring data is consistent with effluents Sintroduced into the environment by plant*operations.

The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data, excluding TLD results, was 3.63E-01 mrem*for 2007. It is therefore concluded that station*operations has had no significant radiological

• impact on the health and safety of the public or the environment.

• Shoreline Sediment sampling S S S*Sectioni1-Pagel1 0

2.0 INTRODUCTION

• 2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS* Duke Energy Corporation's Catawba Nuclear Station is a two-unit facility located on the shore of Lake Wylie in York County, South Carolina.

Each of the two essentially identical units 0 employs a pressurized water reactor nuclear steam supply system furnished by Westinghouse 0 Electric Corporation.

Each generating unit is designed to produce a net electrical output of* approximately 1145 MWe. Units 1 and 2 achieved initial criticality on January 7, 1985, and* May 8, 1986, respectively.

Condenser cooling is accomplished utilizing a closed system incorporating cooling towers,* instead of using lake water directly.

Liquid effluents are released into Lake Wylie via the 0 station discharge canal and are not accompanied by the large additional dilution water flow associated with "once-through" condenser cooling. This design results in greater radionuclide concentrations in the discharge canal given comparable liquid effluent source terms.* 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 CNS. Figure 2.1-2 comprises all sample locations within a 10 mile radius of CNS.* 2.2 SCOPE AND REQUIREMENTS OF THE REMP 0 An environmental monitoring program has been in effect at Catawba Nuclear Station since* 1981, four years prior to operation of Unit 1 in 1985. 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.0 The operational program provides surveillance and backup support of detailed effluent 0 monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.

This monitoring program is based on NRC guidance as reflected in the Selected Licensee 0 Commitments Manual, with regard to sample media, sampling locations, sampling frequency and analytical sensitivity requirements.

Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other "man-made" environmental radioactivity.

The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related 0 exposures from releases of radionuclides from Catawba Nuclear Station. This program* satisfies the requirements of Section IV.B.2 of Appendix I to IOCFR50 and provides surveillance of all appropriate critical exposure pathways to man and protects vital interests of Section 2 -Page I 0 S 0 the company, public and state and federal agencies concerned with the environment.

O Reporting levels for activity 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 O ensure that changes in the use of areas at or beyond the site boundary are identified and that modifications to the REMP are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 1OCFR50. Results are shown in Table 3.11.0 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 IV.B.2 of Appendix I to 1OCFR50. A 0 summary of the results obtained as part of this comparison program are in Section 5 of this 0 annual report.0 2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE O 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 REMP. The following equation was used to estimate the mean (Reference 6.8): 0 0 N zxi 0= -- =1 0 N Where: O x =estimate of the mean, 0 i =individual sample, S N = total number of samples with a net activity (or concentration), Xi = net activity (or concentration) for sample i. 0 NOTE: "Net activity (or concentration)" is the activity (or concentration) determined 0 to be present in the sample. No "Minimum Detectable Activity", "Lower 0 Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of the mean.O 0 O Section 2 -Page 2 0 0 0 0 0 S* 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 REMP.* LLD -The LLD, as defined in the Selected Licensee Commitments Manual is the smallest concentration of radioactive material in a sample that will yield a net count, above the system background, that will be detected with 95% probability with only 5%0 probability of falsely concluding that a blank observation represents a "real" signal.* The LLD is an a priori lower limit of detection.

The actual LLD is dependent upon* the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield and the radioactive decay of the sample between sample collection and counting.

The "required" LLD's for each 0 sample medium and selected radionuclides are given in the Selected Licensee* Commitments and are listed in Table 2.2-C.0 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 S instead of a system background.

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

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

0 Substantial increases or decreases in the amount of a particular radionuclide's release 0 from the nuclear plant will greatly affect the resulting environmental levels; therefore, 5 a knowledge of the release of a radionuclide from the nuclear plant is necessary to completely interpret the trends, or lack of trends, determined from the environmental data. Factors that may affect environmental levels of radionuclides include prevailing S weather conditions (periods of drought, solar cycles or heavier than normal 5 precipitation), construction in or around either the nuclear plant or the sampling 5 location, and addition or deletion of other sources of radioactive materials (such as the Chernobyl accident).

Some of these factors may be obvious while others are sometimes unknown. Therefore, how trends are identified will include some judgment* by plant personnel.

S S S O Section 2 -Page 3 S Figure 2.1-1 Section 2 -Page 4 0000000000F00000000000000000000000000000000g Figure 2.1-2 I.Catawba Nuclear Station Sampling Locations Map (Ten Mile Radius)Legend* TLD Locations* All Other Locations/Nv/ Public Roads Rail Roads"., County Boundary Incorporated Areas Water A~prommate location of features show, 0o 1 2 3,les Projection NCSP NAD27.5 Section 2 -Pag-e 5 TABLE 2.1-A CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 2. 1 -B Codes W Weekly SM Semimonthly BW BiWeekly Q Quarterly M Monthly SA Semiannually C Control Site Location Description*

Air Rad. & Surface Drinking Shoreline Food Fish Milk Broad Ground S Part. Water Water Sediment Products Leaf Water# (a) Veg. ib)200 Site Boundary (0.63 mi NNE) W M 201 Site Boundary (0.53 mi NE) W M 205 Site Boundary (0.23 mi SW) W 208 Discharge Canal (0.45 mi S) M SA SA 210 Ebenezer Access (2.31 mi SE) SA 211 Wylie Dam (4.06 mi ESE) M 212 Tega Cay (3.32 mi E) W 214 Rock Hill Water Supply (7.30 mi SSE) M 215 C River Pointe -Hwy 49 (4.21 mi NNE) M SA 216 C Hwy 49 Bridge (4.19 mi NNE) -- SA 218 C Belmont Water Supply (13.5 mi NNE) M 221 C Dairy (14.5 mi NW) SM 222 Site Boundary (0.70 mi N) M 226 Site Boundary (0.48 mi S) M 252 Residence (0.64 mi SW) Q 253 Irrigated Gardens (1.90 mi SSE) M(a)254 Residence (0.82 mi N) Q 258 C Fairhope Road (9.84 mi W) W M (a) During Harvest Season (b) When Available* 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 6 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 TABLE 2.1-B CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)Site Location' Distance Sector Site Location*

Distance Sector# #200 SITE BOUNDARY 0.63 miles NNE 234 HOME FEDERAL BANK 4.50 miles E 201 SITE BOUNDARY 0.53 miles NE 235 LAKE WYLIE DAM 4.07 miles ESE SC WILDLIFE 203 SITE BOUNDARY 0.38 miles ESE 236 FEDERATION OFFICE 4.25 miles SE TWIN LAKES ROAD AND 204 SITE BOUNDARY 0.48 miles SSW 237 HOMESTEAD ROAD 4.75 miles SSE PENNINGTON ROAD AND 205 SITE BOUNDARY 0.23 miles SW 238 WEST OAK ROAD 4.02 miles S CARTER LUMBER 206 SITE BOUNDARY 0.67 miles WNW 239 COMPANY 4.49 miles SSW 207 SITE BOUNDARY 0.95 miles NNW 240 PARAHAM ROAD 4.07 miles SW 212 SI TEGA CAY AIR SITE 3.32 miles E 241 CAMPBELL ROAD 4.58 miles WSW TRANSMISSION TOWER 217 C ROCK HILL AIR SITE 10.3 miles SSE 242 ON PARAHAM ROAD 4.56 miles W 222 SITE BOUNDARY 0.71 miles N 243 KINGSBERRY ROAD 4.39 miles WNW BETHEL 223 SITE BOUNDARY 0.57 miles E 244 ELEMENTARY SCHOOL 4.02 miles NW CROWDERS CREEK 225 SITE BOUNDARY 0.68 miles SE 245 BOAT LANDING 4.01 miles NNW CAROWINDS 226 SITE BOUNDARY 0.48 miles S 246 SI GUARD HOUSE 7.87 miles ENE 227 SITE BOUNDARY 0.52 miles WSW 247 C FORT MILL 7.33 miles ESE PIEDMONT 228 SITE BOUNDARY 0.61 miles W 248 SI MEDICAL CENTER 6.54 miles S YORK COUNTY 229 SITE BOUNDARY 0.84 miles NW 249 SI OPERATIONS CENTER 7.17 miles S RIVER HILLS YORK 230 COMMUNITY CHURCH 4.37 miles N 250 SI DUKE POWER OFFICE 10.4 miles WSW RIVER HILLS 231 FRONT ENTRANCE 4.21 miles NNE 251 C CLOVER 9.72 miles WNW 232 PLEASANT HILL ROAD 4.18 miles NE 255 SITE BOUNDARY 0.61 miles ENE ZOAR ROAD AND 233 THOMAS DRIVE 3.95 miles ENE 256 SITE BOUNDARY 0.58 miles SSE-258 FAIRHOPE ROAD 9.84 miles W C = Control SI = Special Interest* GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.Section 2 -Page 7 TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water Air Particulates Fish Milk Food Products (pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) (pCi/kg-wet)(pCi/m 3)H-3 20 000(a),(b)

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs- 134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La- 140 200 300 (a) If no drinking water pathway exists, a value of 30,000 pCi/liter may be used.(b) H-3 Reporting level not applicable to surface water TABLE 2.2-B REMP ANALYSIS FREQUENCY S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic 1-131 Beta Air Radioiodine Weekly X Air Particulate Weekly X X Direct Radiation Quarterly X Surface Monthly Composite X Water Quarterly Composite X Drinking Monthly Composite X (a) X Water Quarterly Composite X Ground Water Quarterly X X Shoreline Sediment Semiannually X Milk Semimonthly X X Fish Semiannually X Broadleaf.Vegetation Monthly(b)

X Food Products Monthly(b)

X (a) Low-level 1-131 analysis will be performed if the dose calculated for the consumption of drinking water is> I mrem per year. An LLD of I pCi/liter will be required for this analysis.(b) When Available Section 2 -Page 8 S 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 S S S 0 0 TABLE 2.2-C MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION Analysis Water Air Particulates Fish Milk Food Products Sediment (pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) (pCi/kg-wet) (pCi/kg-dry)(pCi/ni 3)Gross Beta 4 0.01 H-3 2000 (a)Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 1 (b) 0.07 1 60 Cs- 134 15 0.05 130 15 60 150 Cs- 137 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) If no drinking water pathway exists, a value of 3000 pCi/liter may be used.(b) If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.Section 2 -Page 9 0 0 S 3.0 INTERPRETATION OF RESULTS 0*Review of all 2007 REMP analysis results was performed to identify changes in environmental levels as a result of station operations.

The following section depicts and*explains the review of these results. Sample data for 2007 was compared to preoperational and historical data. Over the years of operation, analysis and collection changes have taken place that do not allow direct comparisons for some data collected from 1984 (preoperational) through 2007. Summary tables containing 2007 information required by Technical*Specification Administrative Control 5.6.2 are located in Appendix B.0Evaluation for significant trends was performed for radionuclides that are listed as required*within Selected Licensee Commitments 16.11-13.

The radionuclides 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. Gross beta analysis results were trended for drinking water and gross beta trending for air particulates was initiated in 1996. Other radionuclides detected that are the result of plant operation, but not required for reporting, are trended.A comparison of annual mean concentrations of effluent-based detected radionuclides to historical results provided trending bases. Frequency of detection and concentrations related to SLC reporting levels (Table 2.2-A) were used as criteria for trending conclusions.

All 2007 maximum percentages of reporting levels were well below the 100% action level. The highest*value noted during 2007 was 8.27% for tritium in drinking water collected at the Rock Hill*Water Supply, Location 214.Selected Licensee Commitment section 16.11-13 addresses actions to be taken if radionuclides other than those required are detected in samples collected.

The occurrences of*these radionuclides are the result of CNS liquid effluents which contained the radionuclides.

SDuring 1979-1986, all net activity results (sample minus background), both positive and negative were included in calculation of sample mean. A change in the EnRad gamma spectroscopy system on September 1, 1987, decreased the number of measurements yielding*detectable low-level activity for indicator and control location samples. It was thought that the method used by the previous system was vulnerable to false-positive results.All 2007 sample analysis results were reviewed to detect and identify any significant trends.*Tables and graphs are used throughout this section to display data from effluent-based

• radionuclides identified since the system change in late 1987. All negative concentration values were replaced with zero for calculation purposes.

Any zero concentrations used in tables or graphs represent activity measurements less than detectable levels.Review of all 2007 data presented in this section supports the conclusion that there were no significant changes in environmental sample radionuclide concentrations of samples collected and analyzed from CNS site and surrounding areas that were attributable to plant operations.

0~Section 3 -Page 1 0 3.1 AIRBORNE RADIOIODINE AND PARTICULATES In 2007, 260 radioiodine and particulate samples were analyzed, 208 from four indicator locations and 52 at the control location.

Particulate samples were analyzed weekly for gamma and gross beta. Radioiodine samples received a weekly gamma analysis.Figure 3.1 shows individual sample gross beta results for the indicator location with highest annual mean and the control location samples during 2007. The two sample locations' results are similar in concentration and have varied negligibly since preoperational periods.There were no detectable gamma emitters identified for particulate filters analyzed during 2007. Table 3.1-A shows the highest indicator annual mean and control location annual mean for gross beta in air particulate.

There was no detectable 1-131 in air radioiodine samples analyzed in 2007. Table 3.1-B shows the highest indicator annual mean and control location annual mean for 1-131 since 1984 (preoperational period).K-40 and Be-7 that occur naturally were routinely detected in charcoal cartridges collected during the year. Cs-137 detection on the charcoal cartridge was determined in 1990 to be an active constituent of the charcoal.

A similar study was performed in 2001 again yielding this conclusion.

Therefore, any Cs- 137 activities were not used in any dose calculations in Section 4.0 of this report.0 S S S 0 0 0 S S 0 0 0 S 0 0 0 0 0 0 0 0 0 0 Figure 3.1 There is no reporting levelfor gross beta in air particulate pCi/m 3 Concentration of Gross E 1.OQE-01 9.OOE-02 8.OOE-02 7.OOE-02 6.OOE-02 5.OOE-02 4.OOE-02 3.OOE-02 2.00E-02 1.OOE-02 O.OOE+00 1984 1986 1988 1990 1992 1994 3eta in Air Particulate 1996 1998 2000 2002 2004 2006-Indicator Location--- Control Location Section 3 -Page 2 Table 3.1-A Mean Concentration of Gross Beta in Air Particulate 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Year Indicator Location (pCi/m 3) Control Location (pCi/mr 3)1984 2.25E-2 1.82E-2 1985 2.12E-2 1.53E-2 1986 3.62E-2 3.41E-2 1987 2.67E-2 2.32E-2 1988 2.29E-2 2.30E-2 1989 2.1 IE-2 2.13E-2 1990 2.39E-2 2.72E-2 1991 2.19E-2 2.51E-2 1992 1.90E-2 2.01E-2 1993 1.87E-2 1.94E-2 1994 2.03E-2 2.03E-2 1995 4.88E-2 3.23E-2 1996 3.49E-2 2.60E-2 1997 2.83E-2 2.28E-2 1998 2.69E-2 2.12E-2 1999 2.53E-2 2.04E-2 2000 2.28E-2 1.86E-2 2001 1.76E-2 1.78E-2 2002 1.60E-2 1.57E-2 2003 1.54E-2 1.42E-2 2004 1.65E-2 1.49E-2 2005 1.66E-2 1.68E-2 2006 1.74E-2 1.74E-2 Average (1997 -2006) 2.03E-2 1.80E-2 2007 1.88E-2 1.86E-2 Table 3.1-B Mean Concentration of Air Radioiodine (1-131)Year Indicator Location (pCi/mn 3) Control Location (pCi/rn 3)1984 1.30E-3 1.46E-2 1985 4.75E-3 2.38E-2 1986 1 .43E-2 1.02E-2 1987 1.38E-2 0.OOEO 1988 0.OOEO 0.OOEO 1989 0.OOEO 0.OOEO 1990 0.OOEO 0.OOEO 1991 0.OOEO 0.OOEO 1992 0.OOEO 0.OOEO 1993 0.OOEO 0.OOEO 1994 0.OOEO 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 Section 3 -Page 3 3.2 DRINKING WATER Gross beta and gamma spectroscopy were performed on 26 drinking water samples. The samples were composited to create 8 quarterly samples that were analyzed for tritium. One indicator location was sampled, along with one control location.No gamma emitting radionuclides were identified in 2007 drinking water samples. There have been no gamma emitting radionuclides identified in drinking water samples since 1988.Table 3.2 shows highest annual mean gross beta concentrations for the indicator location and control location since preoperation.

The indicator location (downstream of the plant effluent release point) average concentration was 2.34 pCi/l in 2007 and the control location concentration was 2.21 pCi/l. The 2006 indicator mean was 2.30 pCi/l. The table shows that current gross beta levels are not statistically different from preoperational concentrations.

Tritium was detected in the four indicator samples and the four control samples during 2007.The mean indicator tritium concentration for 2007 was 1653 pCi/l, 8.27% of reporting level.The mean control tritium concentration for 2007 was 918 pCi/l, 4.59% of reporting level.Figure 3.2 and Table 3.2 display the highest indicator and control location annual mean concentrations for tritium since 1984.Tritium in drinking water control and indicator samples was higher in 2007 than in previous years. The concentration of tritium in drinking water is affected by releases from the Catawba plant and the McGuire Nuclear Station, located approximately 40 miles upstream of the Catawba plant on the Catawba River. In addition, an extreme drought during the second half of 2007, affecting the Catawba River Basin, resulted in less dilution volume available in Lake Wylie.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 The dose for consumption of water was less than one 2007; therefore low-level iodine analysis is not required.mrem per year, historically and for Section 3 -Page 4 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Figure 3.2 pCi/lite 5000 4500 -4000 3500 3000 2500 2000 1500 1000 -500 01 191 er Concentration of Tritium in Drinking Water 84 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006-4-Indicator Location--*-Control Location-15% Reporting Level Table 3.2 Mean Concentration of Radionuclides in Drinking Water Gross Beta (pCi/1) Tritium (pCi/I)YEAR Indicator Control Indicator Control Location Location Location Location 1984 4.72 1.83 3.1OE-2 3. 1OE-2 1985 2.70 2.24 4.13E2 4.00E2 1986 3.11 2.26 7.23E2 7.33E2 1987 3.10 2.40 7.80E2 4.80E2 1988 3.60 2.60 6.64E2 0.00E0 1989 3.60 2.90 8.91E2 5.72E2 1990 4.50 3.20 7.03E2 0.00E0 1991 3.70 2.20 7.04E2 0.00E0 1992 3.20 2.40 7.65E2 5.38E2 1993 3.50 2.50 7.06E2 0.00E0 1994 3.30 2.70 0.00E0 0.00EO 1995 4.80 4.50 4.28E2 2.21E2 1996 3.08 3.14 3.71E2 3.27E2 1997 3.74 3.15 3.54E2 2.28E2 1998 2.51 2.44 5.07E2 1.83E2 1999 3.55 2.48 6.71 E2 2.70E2 2000 3.04 2.27 5.87E2 3.26E2 2001 3.49 2.30 8.66E2 4.50E2 2002 3.44 2.36 1.22E3 4.11E2 2003 2.27 2.02 6.36E2 2.88E2 2004 1.88 1.69 5.47E2 2.54E2 2005 2.05 1.84 7.69E2 4.50E2 2006 2.30 2.17 1.59E3 7.70E2 2007 2.34 2.21 1.65E3 9.18E2 0.00E0 = no detectable measurements 1984 -1986 mean based on all net activity Section 3 -Page 5 3.3 SURFACE WATER A total of 39 monthly surface water samples was analyzed for gamma emitting radionuclides.

The samples were composited to create 12 quarterly samples for tritium analysis.

Two indicator locations and one control location were sampled. One indicator location (208) is located near the liquid effluent discharge point.Tritium was the only radionuclide identified in surface water samples collected during 2007.All indicator location samples contained tritium with an average concentration of 5868 pCi/l.Indicator Location 208 (Discharge Canal) showed a range of activities from 8210 to 12400 pCi/l which had the highest mean concentration of 10100 pCi/l. Tritium was detected in all four control samples during 2007 with an average concentration of 782 pCi/l.Figure 3.3 displays the indicator and control annual means for tritium since 1984. Table 3.3 lists indicator annual means.The concentration of tritium in surface water is affected by releases from the Catawba plant and the McGuire Nuclear Station, located approximately 40 miles upstream of the Catawba plant on the Catawba River. In addition, an extreme drought during the second half of 2007, affecting the Catawba River Basin, resulted in less dilution volume available in Lake Wylie.Figure 3.3 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 pCi/liter Concentration of Tritium in Surface Water 30000?5000?0000 15000 10000 5000 0 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002-I Indicator Location --Control Location 2004 2006 There is no reporting levelfor tritium in surface water, however, if no drinking water pathway exists, a value of 30,000 pCii1 may be used. A drinking water pathway exists for Catawba Nuclear Station, so this limit does not apply for surface water. See section 3.2 for drinking water results.Section 3 -Page 6

• Table 3.3 Mean Concentrations of Radionuclides in Surface Water (pCi/l)YEAR Co-58 Co-60 Nb-95 Cs-137 H-3 Indicator H-3 Control 1984 4.59E-1 5.71E-1 6.48E-I 9.08E-1 3.35E2 3.18E2* 1985 3.46E0 4.83E-2 2.70E0 8.19E- 1 1.19E3 5.05E2* 1986 3.10E-1 -4.12E-2 2.05E0 4.85E-1 2.34E3 5.05E2 1987 0.OOEO 3.10E0 4.30E0 9.90E0 4.17E3 6.20E2 1988 9.20E0 0.OOEO 0.OOEO 0.OOEO 6.03E3 6.07E2 1989 0.003E 0.OOEO 0.OOEO 0.00E0 5.27E3 0.OOEO 1990 6.50E0 0.OOEO 0.00E0 0.00E0 3.98E3 7.73E2 1991 0.00E0 0.OOEO 0.00E0 0.OOEO 4.87E3 0.OOEO* 1992 0.00E0 0.00E0 0.00E0 0.00E0 6.91 E3 6.64E2 1993 4.70E0 1.80E0 0.OOEO 0.OOEO 5.98E3 0.00E0 1994 0.00E0 0.00E0 0.OOEO 0.00E0 8.42E3 0.00E0* 1995 0.OOEO 0.00E0 0.00E0 0.OOEO 5.133E3 2.89E2 1996 0.OOEO 0.00E0 0.00E0 0.00E0 7.36E3 2.61 E2 1997 0.00E0 0.OOEO 0.00E0 0.00E0 7.77E3 2.20E2 1998 0.00E0 0.OOEO 0.00E0 0.00E0 6.61 E3 0.00E0 1999 0.00EO 0.OOEO 0.00E0 0.OOEO 8.13E3 2.41 E2 2000 0.OOEO 0.OOEO 0.OOEO 0.OOEO 7.19E3 2.56E2 2001 O.O0EO 0.00E0 0.OOEO 0.00E0 7.13E3 3.28E2 2002 0.00E0 0.OOEO 0.OOEO 0.00E0 L.00E4 3.80E2 2003 0.OOEO 0.OOEO 0.00E0 0.OOEO 1.3 1 E4 2.37E2 2004 0.00E0 0.OOEO 0.00E0 0.OOEO 9.43E3 2.60E2 2005 0.00E0 0.00E0 0.00E0 0.OOEO 1.40E4 3.78E2 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.67E4 5.83E2 2007 .003E0 O.OOEO 0.OOEO 0.OOEO 1.01 E4 7.82E2 O.OOEO = no detectable measurements 1984 -1986 mean based on all net activity S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O Section 3 -Page 7 3.4 GROUND WATER A total of eight ground water samples was collected and analyzed for gamma emitters and tritium. There are two indicator locations and no control locations.

Naturally occurring K-40 was the only radionuclide identified during 2007.There have been no radionuclides identified in ground water samples since 1988. Only naturally occurring K-40 and Be-7 were noted.Section 3 -Page 8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0* 3.5 MILK A total of 26 milk samples was analyzed by gamma spectroscopy and low level iodine during 2007. There was one control location sampled. No indicator dairies were identified by the 2007 land use census.*There were no gamma emitting radionuclides identified in milk during 2007. Airborne Cs- 137 has not been released from the plant since 1992.*Cs-137 was last detected in an indicator sample during 1996. The occurrence of Cs-137*in milk samples has been noted several times since 1984. Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low, highly variable levels.0Table 3.5 lists highest indicator location annual mean and control location annual mean for Cs- 137 since the preoperational period. Concentrations are similar for the two sample*types. Cs-137 is the only radionuclide, other than K-40 and Be-7, reported in milk*samples since 1988.*Table 3.5 Mean Concentration of Radionuclides in Milk 0 YEAR Cs-137 Indicator (pCi/l) Cs-137 Control (pCi/I)1984 2.95E0 2.98E0 1985 2.1 IEO 2.12E0 1986 3.76E0 4.54E0 1987 5.OOEO 5.50E0 1988 3.20E0 3.80E0 1989 O.OOEO O.OOEO* 1990 8.OOEO 6.70E0 1991 O.OOEO O.OOEO* 1992 3.40E0 5.OOEO 1993 5.OOEO O.OOEO 1994 2.80E0 O.OOEO 1995 8.60E0 0.OOEO 1996 6.05E0 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 0.00E0 2002 0.00E0 0.00E0* 2003 0.00E0 0.00E0 2004 NO INDICATOR LOCATION 0.00E0 2005 NO INDICATOR LOCATION 0.00E0 2006 NO INDICATOR LOCATION 0.OOEO* 2007 NO INDICATOR LOCATION 0.OOEO O.OOEO = no detectable measurements 1984 -1986 mean based on all net activity 0 0 O ~Section 3 -Page 9 0 3.6 BROADLEAF VEGETATION Gamma spectroscopy was performed on 60 broadleaf vegetation samples during 2007.Four indicator locations and one control location were sampled.Six of the forty-eight samples collected at indicator locations contained detectable Cs- 137 activity.

Cs-137 was detected in five of the twelve samples collected at Location 201.The highest concentration detected at Location 201 was 96.5 pCi/kg which is 4.83% of the reporting level. Cs-137 was not detected in any of the twelve control location samples.Figure 3.6 shows indicator and control annual means for Cs-137 in vegetation since 1984. Table 3.6 lists indicator and annual means. Values shown from 1984 to 2007 show a stable trend for Cs-137 in vegetation.

No airborne Cs-137 has been released from the plant since 1992. Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low and highly variable levels.K-40 and Be-7 were observed in broadleaf vegetation samples.Figure 3.6 0 0 S 0 0 S S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 pCi/kg Concentration of Cs-137 in Broadleaf Vegetation 1200 1000 800 600 400 200 0 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2' Indicator Location Q Control Location -50% Reporting Level 004 2006 Section 3 -Page 10

• Table 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation YEAR Cs-137 Indicator (pCi/kg) Cs-137 Control (pCi/kg)1984 3.76E1 1.30E]* 1985 5.48E1 4.16E1* 1986 7.42E1 2.22E1 1987 6.10El 5.10El* 1988 9.10El 7.40E1 1989 1.00E2 4.80E1* 1990 7.70E1 5.80E1 1991 1.98E2 8.60E1* 1992 9.70E1 0.00E0 1993 1.13E2 3.20E1 1994 7.OOEI 0.00E0 1995 3.60E1 0.00E0 1996 2.23E2 6.22E1 1997 7.57E1 0.00E0 1998 6.53E1 0.00E0 1999 1.08E2 0.OOEO 2000 1.04E2 0.OOEO 2001 3.76E1 0.00E0 2002 7.02El 0.00E0 2003 4.96E1 2.40E1 2004 5.45E1 0.OOEO* 2005 5.48E1 0.OOEO 2006 5.79E1 0.OOEO 2007 6.31E1 0.OOEO O.OOEO = no detectable measurements 1984 -1986 mean based on all net activity 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O ~Section 3 -Page 11 0 3.7 FOOD PRODUCTS 0 Collection of food product samples (crops) from an irrigated garden began in 1989. The garden is located on Lake Wylie downstream from CNS, Location 253. During the 2007 growing season, eight samples were collected and analyzed for gamma radionuclides.

There is no control location for this media type.Table 3.7 shows Cs-137 indicator location highest annual mean concentrations since 1989.Table 3.7 Mean Concentration of Radionuclides in Food Products 0 YEAR Cs-137 Indicator (pCi/kg)1989 0.00E0 1990 0.OOEO 1991 0.00E0 1992 0.00E0 1993 2.50E1 1994 0.OOEO 1995 0.OOEO 1996 0.00E0 1997 0.00E0 1998 0.OOEO 1999 0.OOEO 2000 0.00E0 2001 0.OOEO 2002 0.OOEO 2003 0.OOEO 2004 0.OOEO 2005 0.OOEO 2006 0.OOEO 2007 0.00E0.OOEO = no detectable measurements 0 There is no control location for Food Products.

S S 0 0 S 0 0 0 0 0 0 0 0 Section 3 -Page 12 0 S 0 0 S 0 S 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 S 0 S 0 S 0 3.8 FISH Gamma spectroscopy was performed on 12 fish samples collected during 2007. One downstream indicator location and one control location were sampled.Co-58, Co-60, and Cs-137 are normally the predominant radionuclides identified in fish samples. There were no gamma emitting radionuclides identified in fish during 2007.During 2006, Cs-137 was detected in one indicator sample at a concentration of 14.4 pCi/kg, which is 0.72% of the reporting level. Cs-137 was not detected in any control location samples.Figures 3.8-1 and 3.8-2 are graphs displaying annual mean concentrations for Co-58 and Co-60. Table 3.8 depicts the highest indicator location annual mean for radionuclides detected.

In addition, radionuclides identified in fish samples since 1988 have been included in the table. Overall, radionuclides have not shown a significant trend or accumulation.

K-40 was observed in fish samples collected during 2007.Section 3 -Page 13 Figure 3.8-1 pCi/kg Concentration of Co-58 in Fish 2000 1800 1600 1400 1200 1000 800 600 400 200 0 -1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006--0i-Indicator Location ""OýControl Location -5 % Reporting Level S S 0 0 S S S 0 S S S S S S S S S S S S S S S S S S S S 0 S S S S S S S S S S S S S S Figure 3.8-2[p%.'1Kg Concentration of Co-60 in Fish 700 600 500 400 300 200 100 0 0S-1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 2004 2006-"-- Indicator Location -'1--Control Location -5% Reporting Level Section 3 -Page 14

• Table 3.8 Mean Concentrations of Radionuclides in Fish (pCi/kg)0 Year Mn-54 Co-58 Co-60 Cs-134 Cs-137 Nb-95 Fe-59 Sb-122 Sb-125 1984 3.07E0 3.OOEO 6.11E-1 -5.32E0 1.83E0 0.OOEO 0.OOEO 0.00E0 0.OOEO 1985 7.68E-1 3.40E1 9.1 lEO 3.22E0 1.28E1 5.07E0 0.OOEO 0.OOEO 0.OOEO 1986 2.01E1 1.86E2 4.01EI 3.51E1 9.29E1 0.OOEO 7.30E0 0.OOEO 0.OOEO 1987 7.24E0 7.57E1 4.81E1 3.83E0 4.27E1 5.40E0 0.OOEO 0.OOEO 0.OOEO 1988 2.85E1 1.40E2 9.70E1 1.67E1 8.24E1 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1989 8.28E0 1.33E2 3.83E1 1.47E1 4.37E1 8.58E-1 0.OOEO 0.OOEO 0.OOEO 1990 2.51E1 1.75E2 7.77E1 1.32E1 4.66E 1 3.33E0 O.00E0 7.00E0 9.25E0 1991 3.15E1 1.46E2 1.29E2 1.03El 4.60EI 7.90E-1 2.30E0 0.00E0 7.45E0 1992 1.34E1 9.02E 1 6.20E1 1.27E1 4.61E1 0.00E0 0.00E0 0.OOEO 0.00E0 1993 2.14E1 3.58E2 1.21E2 2.73E0 2.56E1 0.00E0 0.00E0 0.00E0 0.00E0 1994 1.91E0 4.75E 1 1.81E1 0.00E0 1.75E1 0.00E0 0.00E0 0.OOEO 1.45E1 1995 5.65E1 8.90E2 2.66E2 0.00E0 6.77E1 1.38E1 0.OOEO 0.OOEO 0.00E0 1996 0.00E0 5.95E1 6.68E1 0.OOEO 3.02E1 0.OOEO 0.OOEO 0.00E0 O.OOEO 1997 0.OOEO 4.93EI 9.88E0 0.00E0 2.74E1 0.00E0 0.OOEO 0.00E0 0.00E0 1998 0.00E0 6.44E1 2.86E 1 0.OOEO 1.58El 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1999 0.OOEO 3.12E 1 2.71E1 0.OOEO 1.87E I 0.00E0 0.OOEO 0.OOEO 0.OOEO 2000 0.OOEO 2.13E2 2.69E2 0.OOEO 1.52E1I .OOEO 0.OOEO 0.OOEO 0.OOEO 2001 0.OOEO 4.66E I 0.OOEO 0.00E0 2.08E1 0.00E0 0.OOEO 0.00E0 0.00E0 2002 0.OOEO 5.23E1 7.00E1 0.OOEO 1.73E1 0.00E0 0.OOEO 0.00E0 0.00E0 2003 0.OOEO 1.43E2 2.61E1 0.00E0 1. 19E 1 0.OOEO 0.00E0 0.OOEO 0.00E0 2004 4.92E1 1.81E1 0.00E0 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.00E0 2005 0.00E0 0.00E0 0.00E0 0.00E0 0.OOEO 0.00E0 0.OOEO 0.OOEO 0.00E0 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.44E1 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2007 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO O.OOEO = no detectable measurements S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O ~Section 3 -Page 15 0 3.9 SHORELINE SEDIMENT During 2007, a total of 6 shoreline sediment samples was analyzed, four from two indicator locations and two from the control location.Co-58, Co-60, and Cs-137 were identified in one sample collected from indicator location 208-1S, which is closest to the plant's liquid effluent release point. Naturally occurring K-40 was identified in many of the indicator and control locations.

Activity released in plant effluents has decreased since 1996 and as a result decreased activity has been measured in the environment.

The shoreline sediment location with the highest annual mean for all detectable radionuclides was location 208-1S. Co-58 was identified at location 208-IS with an annual mean concentration of 87.7 pCi/kg. Co-60 was identified with an annual mean concentration of 94.6 pCi/kg. Cs-137 was identified with an annual mean concentration of 61.3 pCi/kg. Naturally occurring K-40 and Be-7 were also identified in samples from this location.Table 3.9 lists highest indicator location annual mean since 1984. Included in the table are radionuclides that have been identified in shoreline sediment samples since 1988.Figure 3.9-1 graphically depicts Co-58 annual mean concentrations.

Figure 3.9-2 depicts Co-60 annual mean concentrations.

Figure 3.9-1 S 0 0 0 0 S 0 S 0 0 0 0 0 0 0 0 0 0 0 S 0 0 pCi/kg Concentration of Co-58 in Shoreline Sedime 2000 1800 1600 1400 1200 1000 800 600 400 200 o0 ...............1984 1986 1988 1990 1992 1994 1996 1998 2000-Indicator Location -- Control Location nt 2002 2004 2006 There is no reporting levelfor Co-58 in Shoreline Sediment Section 3 -Page 16 0* Figure 3.9-2 pCi/kg Concentration of Co-60 in Shoreline Sediment 2000 1800 01600 0 1400 .. ... .. ..1200 0 o1000 800 0 600 400 0 200 0 0 1984 1986 1988 1990 1992 1994 1996 _ 1998 2000 2002 2004 2006-- Indicator Location -Control Location* There is no reporting level for Co-60 in Shoreline Sediment*Table 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/kg)Year Mn-54 Co-58 Co-60 Nb-95 Zr-95 Cs-134 Cs-137 Co-57 Sb-125 1984 l.03E0 4.40E0 -2.34E0 0.OOE0 O.OOEO 3.19E 1 1.07E2 0.OOEO 0.OOEO 1985 -3.12E0 1.16E2 5.18E0 0.OOEO 0.OOEO 2.11 E2 2.97E2 0.OOEO 0.OOEO 1986 1.09E2 3.79E2 2.05E2 0.OOEO 3.96E1 6.50E1 1.61 E2 0.OOEO 0.OOEO 1987 8.83E1 4.08E2 1.61E2 4.22E1 0.OOEO 6.08E1 1.26E2 0.OOEO 0.OOEO 1988 1.07E2 3.29E2 2.63E2 2.28E1 7.54E0 2.59E1 1.07E2 7.65E-1 3.68E0 1989 4.58E1 1.94E2 1.21E2 5.02E0 0.OOEO 1.65E1 5.77EI O.OOEO 1.57E1* 1990 5.39E1 2.08E2 1.77E2 0.OOEO 0.OOEO 1.66E1 8.18E] O.OOEO 7.15E0 1991 8.50E1 3.70E2 4.19E2 5.30E0 0.OOEO 1.82E1 8.33E1 1.20E0 1.50E]0 1992 1.17E2 1.13E3 5.80E2 3.50E0 0.OOEO 1.69E1 1.07E2 3.OOEO 2.70E1 1993 1.33E2 1.07E3 1.04E3 0.OOEO 0.OOEO 2.80E1 1.26E2 2.47E1 2.16E2 1994 4.93E1 7.98E2 5.73E2 0.OOEO O.OOEO 5.67E0 1.07E2 4.38E0 4.60E1 1995 1.02E2 1.33E3 8.65E2 1.13E2 0.OOEO 0.OOEO 8.50E1 3.69E1 1.49E2 1996 8.73E1 3.39E2 5.81E2 0.OOEO 0.OOEO 0.OOEO 8.30E1 0.OOEO 1.96E2 1997 6.96E1 5.90E2 7.64E2 0.OOEO 0.OOEO 0.OOEO 1.43E2 0.OOEO 1.76E2* 1998 3.07E1 1.88E2 2.30E2 0.OOEO 0.OOEO 0.OOEO 7.11E1 0.OOEO 0.OOEO 1999 7.28E1 2.29E2 4.39E2 0.OOEO 0.OOEO 0.OOEO 9.42E1 O.OOEO 1.40E2 2000 0.OOEO 3.90E1 1.03E2 0.OOEO 0.OOEO 0.OOEO 4.96E1 0.OOEO 0.OOEO* 2001 3.86E1 8.27E1 3.29E2 0.OOEO 0.OOEO 0.OOEO 5.58E1 0.OOEO 0.OOEO 2002 3.51E1 2.41E2 2.22E2 0.OOEO 0.OOEO 0.OOEO 8.83E1 0.OOEO 0.OOEO 2003 2.17E1 8.75E1 1.08E2 O.OOEO 0.OOEO 0.OOEO 2.69E1 0.OOEO 0.OOEO* 2004 6.60E1 2.67E2 3.83E2 0.OOEO 0.OOEO 0.OOEO 3.79E1 0.OOEO 0.OOEO 2005 O.0OE0 1.61E2 1.41E2 0.OOEO 0.OOEO 0.OOEO 0.OOEO O.OOEO 0.OOEO 2006 0.OOEO 5.40E 1 1.11 E2 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2007 0.OOEO 8.77E1 9.46E I 0.OOEO 0.OOEO 0.OOEO 6.13E1 0.OOEO 0.OOEO O.OOEO = no detectable measurements 1984 -1986 mean based on all net activity Negative values are calculated as zeroes 0 0 O ~Section 3 -Page 17 0 3.10 DIRECT GAMMA RADIATION In 2007, 162 TLDs were analyzed, 151 at indicator locations and 11 at control locations.

TLDs are collected and analyzed quarterly.

The highest annual mean exposure for an indicator location was 105.2 milliroentgen.

The annual mean exposure for the control locations was 59.2 milliroentgen.

Figure 3.10 and Table 3.10 show TLD inner ring (site boundary), outer ring (4-5 miles), and control location annual averages in milliroentgen per year. Preoperational data and rolling ten year operational data averages are also given. As shown in the graph, inner ring, outer ring, and control data averages historically compare closely. Inner and outer ring averages comprise a number of data points with control averages representing only three locations.

The calculated total body dose (from gaseous effluents) for 2007 was 8.95E-1 mrem, which is 1.11% of the average inner ring TLD values. Therefore, it can be concluded that discharges from the plant had very little impact upon the measured TLD values.Figure 3.10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 mH/year Direct Gamma Radiation (TLD) Results 250 200 150 100 50 0 1984 1986 1988 1990 1992 1994 1996 1998 2000 Inner Ring - Outer Ring --- Control 2002 2004 2006 There is no reporting level for Direct Radiation (TLD)Section 3 -Page 18 0 0 O Table 3.10 Direct Gamma Radiation (TLD) Results Inner Ring Average Outer Ring Average Control Average Year (mR/yr) (mR/yr) (mR/yr)1984* 87.5 82.6 79.3 1985 116.9 108.7 108.9 1986 104.3 98.5 94.4 1987 97.0 87.4 84.7 1988 74.6 70.3 67.1 1989 67.1 60.8 60.0 1990 52.0 44.5 39.1* 1991 62.0 54.1 46.7 1992 80.4 72.5 64.5* 1993 70.3 60.9 53.6 1994 76.3 69.3 63.9 1995 99.6 89.7 80.8 1996 84.3 73.9 63.682.4 71.9 57.4 1998 85.3 74.2 64.6 1999 80.0 68.1 57.875.0 63.0 52.481.0 70.5 55.2 2002 78.8 69.5 55.2 2003 81.7 72.6 56.0 2004 78.6 73.8 55.6 2005 79.8 75.2 57.7 2006 76.9 73.6 57.2 Average ( 1997 -2006) 80.0 71.2 57.080.5 76.4 59.2 O

• Preoperational Data S 0 0 0 0 0 0 0 0* vrg 19 06* 078. 645.O SPeeoierati-naagData 0

3.11 LAND USE CENSUS The 2007 Annual Land Use Census was conducted July 10 and July 11, 2007 as required by SLC 16.11-14.

Table 3.11 summarizes census results. A map indicating identified locations is shown in Figure 3.11.During the 2007 census, no new or closer irrigated gardens were identified.

The nearest residence is located in the NE sector at 0.56 miles. No environmental program changes were required as a result of the 2007 land use census.Table 3.11 Catawba 2007 Land Use Census Results Sector Distance Sector Distance (Miles) (Miles)Nearest Residence 0.63 Nearest Residence 0.63 N Nearest Garden 1.55 S Nearest Garden 0.80 Nearest Milk Animal -Nearest Milk Animal Nearest Residence 0.66 Nearest Residence 0.81 NNE Nearest Garden 2.53 ssw Nearest Garden 1 .02 Nearest Milk Animal -Nearest Milk Animal Nearest Residence 0.56 Nearest Residence 0.66 NE Nearest Garden 0.66 SW Nearest Garden (irrigated) 0.66 Nearest Milk Animal -Nearest Milk Animal Nearest Residence 0.61 Nearest Residence 0.61 ENE Nearest Garden (irrigated) 0.61 wsw Nearest Garden 2.04 Nearest Milk Animal -Nearest Milk Animal Nearest Residence 0.65 Nearest Residence 0.74 E Nearest Garden 2.25 w Nearest Garden 0.96 Nearest Milk Animal -Nearest Milk Animal Nearest Residence 0.84 Nearest Residence 1 .10 ESE Nearest Garden 1.23 WNW Nearest Garden 1.19 Nearest Milk Animal -Nearest Milk Animal Nearest Residence 0.97 Nearest Residence 1.39 SE Nearest Garden (irrigated) 2.55 NW Nearest Garden 1.54 Nearest Milk Animal -Nearest Milk Animal Nearest Residence 0.74 Nearest Residence 1.01 SSE Nearest Garden 1.01 NN W Nearest Garden 2.21 Nearest Milk Animal Nearest Milk Animal indicates no occurrences within the 5 mile radius S S 0 S S 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S Section 3 -Page 20 Figure 3.11 Section 3 -Page 21 0 0 S* 4.0 EVALUATION OF DOSE S S* 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 2007 CNS REMP samples. The primary purpose 0of estimating doses based on sample results is to allow comparison to effluent 0program dose estimates.

0 Doses based on sample results were calculated using the methodology and data presented in NRC Regulatory Guide 1.109. Measured radionuclide concentrations, 0averaged over the entire year for a specific radionuclide, indicator location and sample type, were used to calculate REMP-based doses. Where applicable, average background concentration at the corresponding control location was subtracted.

Regulatory Guide 1.109 consumption rates for the maximum exposed individual 0were used in the calculations.

When the guide listed "NO DATA" as the dose factor 0for a given radionuclide and organ, a dose factor of zero was assumed.0 Maximum dose estimates (Highest Annual Mean Concentration) based on drinking water, broadleaf vegetation, fish, and shoreline sediment sample results are reported*in Table 4.1-A. The individual critical population and pathway dose calculations are*reported in Table 4.1-B.S REMP-based dose estimates are not reported for airborne radioiodine, airborne particulate, milk, or ground water sample types because no radionuclides other than naturally occurring K-40 and Be-7 were detected in the samples. Dose estimates are 0not reported for surface water because sampled surface water is not considered to be 5a potable drinking water source although surface water tritium concentrations are*used in calculating doses from fish. Exposure estimates based upon REMP TLD results are discussed in Section 3.10.0The maximum environmental organ dose estimate for any single sample type (other*than direct radiation from gaseous effluents) collected during 2007 was 5.36E-1 mrem to the maximum exposed child bone from consuming broadleaf vegetation.

• 4.2 ESTIMATED DOSE FROM RELEASES 0 5Throughout the year, dose estimates were calculated based on actual 2007 liquid and 5gaseous effluent release data. Effluent-based dose estimates were calculated using the RETDAS computer program which employs methodology and data presented in NRC Regulatory Guide 1.109. These doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimates.

Summaries of RETDAS dose 5calculations are reported in the Annual Radioactive Effluent Release Report (reference 6.6).Section 4 -Page 1 0 0 The effluent-based liquid release doses are summations of the dose contributions from the drinking water, fish, and shoreline pathways.

The effluent-based gaseous release doses report noble gas exposure separately from iodine, particulate, and0 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, inhalation, milk and vegetation pathways.4.3 COMPARISON OF DOSES0 The environmental and effluent dose estimates 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 effluent0 measurements and modeling of the environmental exposure pathways.

This indicates0 that effluent program dose estimates are both valid and reasonably conservative.

There are some differences in how effluent and environmental doses are calculated that affect the comparison.

Doses calculated from environmental data are0 conservative because they are based on a mean that includes only samples with a net0 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 pathways, fish, drinking water, and shoreline0 sediment were the predominant dose pathways based on environmental and effluent data. The maximum total organ dose based on 2007 environmental sample results was 8.81lE-2 mrem to the child total body. The maximum total organ dose of 8.65E-2 mrem for liquid effluent-based estimates was to the adult GI-LLI.0 In calculations based on gaseous release pathways, vegetation was the predominant0 dose pathway for effluent samples. The maximum total organ dose for gaseous0 effluent estimates was 8.95E-1 mrem to the child's liver, total body, thyroid, kidney, lung, and GI-LLI. Vegetation was the predominant dose pathway for environmental0 samples. The maximum total organ dose for gaseous environmental estimates was0 5.3 6E-l1 mrem to the child bone.0 Noble gas samples are not collected as part of the REMP, preventing an analogous comparison of effluent-based noble gas exposure estimates.

The doses calculated do not exceed the 40CFRI90 dose commitment limits for members of the public. Doses to members of the public attributable to the operation0 of CNS are being maintained well within regulatory limits.Section 4 -Page 20 0 0 0 0 0 0 0 0 0 TABLE 4.1-A Page 1 of 3 CATAWBA NUCLEAR STATION 2007 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIQUID RELEASE PATHWAY Environmental or Critical Critical Maximum Dose (3)Effluent Data Age (1) Pathway (2) (mrem)Skin Environmental Teen Shoreline Sediment 208 (0.45 mi S) 1.56E-03 Skin Effluent Teen Shoreline Sediment Discharge Pt. 5.99E-03 Bone Environmental

--0.OOE+00 Bone Effluent Teen Shoreline Sediment Discharge Pt. 1.02E-02 Liver Environmental Child Drinking Water 214 (7.30 mi SSE) 8.78E-02 Liver Effluent Child Drinking Water 7.30 mi SSE 7.58E-02 T. Body Environmental Child Drinking Water 214 (7.30 mi SSE) 8.8 1E-02 T. Body Effluent Child Drinking Water 7.30 mi SSE 7.09E-02 Thyroid Environmental Child Drinking Water 214 (7.30 mi SSE) 8.78E-02 Thyroid Effluent Child Drinking Water 7.30 mi SSE 6.89E-02 Kidney Environmental Child Drinking Water 214 (7.30 mi SSE) 8.78E-02 Kidney Effluent Child Drinking Water 7.30 mi SSE 7.09E-02 Lung Environmental Child Drinking Water 214 (7.30 mi SSE) 8.78E-02 Lung Effluent Child Drinking Water 7.30 mi SSE 6.97E-02 GI-LLI Environmental Child Drinking Water 214 (7.30 mi SSE) 8.78E-02 GI-LLI Effluent Adult Fish Discharge Pt. 8.65E-02 (1) Critical Age is the highest total dose (all pathways) to an age group.(2) Critial Pathway is the highest individual dose within the identified Critical Age group.(3) Maximum dose is a summation of the fish, drinking water and shoreline sediment pathways.Section 4 -Page 3 Page 2 of 3 GASEOUS RELEASE PATHWAY IODINE, PARTICULATE, and TRITIUM Environmental or Critical Critical Maximum Dose (3)Effluent Data Age (1) Pathway (2) (mrem)Skin Environmental

-O.OOE+00 Skin Effluent 0.5 mi S O.OOE+00 Bone Environmental Child Vegetation 201 (0.53 mi NE) 5.36E-01 Bone Effluent 0.5 mi S 0.OOE+00 Liver Environmental Child Vegetation 201 (0.53 mi NE) 5.14E-01 Liver Effluent Child Vegetation 0.5 mi S 8.95E-01 T. Body Environmental Adult Vegetation 201 (0.53 mi NE) 2.88E-01 T. Body Effluent Child Vegetation 0.5 mi S 8.95E-01 Thyroid Environmental 0.OOE+00 Thyroid Effluent Child Vegetation 0.5 mi S 8.95E-0 I Kidney Environmental Child Vegetation 201 (0.53 mi NE) 1.67E-01 Kidney Effluent Child Vegetation 0.5 mi S 8.95E-01 Lung Environmental Child Vegetation 201 (0.53 mi NE) 6.02E-02 Lung Effluent Child Vegetation 0.5 mi S 8.95E-01 GI-LLI Environmental Adult Vegetation 201 (0.53 mi NE) 8.52E-03 GI-LLI Effluent Child Vegetation 0.5 mi S 8.95E-01 0 0 0 0 S 0 S 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 (1) Critical Age is the highest total dose (all pathways) to an age group.(2) Critial Pathway is the highest individual dose within the identified Critical Age group.(3) Maximum dose is a summation of the ground/plane, inhalation, milk and vegetation pathways.Section 4 -Page 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 Page 3 of 3 NOBLE GAS Air Environmental or Critical Critical Maximum Dose Dose Effluent Data Age Pathway (mrad)Beta Environmental Not Sampled Beta Effluent N/A Noble Gas 0.5 mi. NNE 1.25E-02 Gamma Environmental Not Sampled Gamma Effluent N/A Noble Gas 0.5 mi. NNE 2.93E-02 Section 4 -Page 5 TABLE 4.1-B Maximum Individual Dose for 2007 based on Environmental Measurements (mrem) for Catawba 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 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-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 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-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 7.61E-02 7.61E-02 7.61E-02 7.61E-02 7.61E-02 7.61E-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 5.36E-01 5.14E-01 7.58E-02 O.OOE+00 1.67E-01 6.02E-02 3.22E-03 O.OOE+00 Fish O.OOE+00 1.17E-02 1.17E-02 1.17E-02 1.17E-02 1.1 7E-02 1.17E-02 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 2.78E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.26E-04 TOTAL 5.36E-01 6.02E-01 1.64E-01 8.78E-02 2.55E-01 1.48E-01 9.1OE-02 3.26E-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 3.97E-02 3.97E-02 3.97E-02 3.97E-02 3.97E-02 3.97E-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 2.97E-01 3.95E-0I 1.38E-0 I O.OOE+00 1.34E-01 5.22E-02 5.62E-03 O.OOE+00 Fish O.OOE+00 1.42E-02 1.42E-02 1.42E-02 1.42E-02 1.42E-02 1.42E-02 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 1.33E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.56E-03 TOTAL 2.97E-01 4.49E-01 1.93E-01 5.39E-02 1.88E-01 1.06E-01 5.95E-02 1.56E-03 Adult Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Drinking Water O.OOE+00 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 O.OOE+00 Milk O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation 3.22E-01 4.40E-01 2.88E-01 O.OOE+00 1.49E-01 4.97E-02 8.52E-03 O.OOE+00 Fish O.OOE+00 1.85E-02 1.85E-02 1.85E-02 1.85E-02 1.85E-02 1.85E-02 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 2.38E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.80E-04 TOTAL 3.22E-01 5.15E-01 3.63E-01 7.48E-02 2.24E-01 1.25E-01 8.33E-02 2.80E-04 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 -Page 6 Catawba Nuclear Station Dose from Drinking Water Pathway for 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 i Radionuclide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs- 137 BaLa-140 H-3 Bone NO DATA NO DATA 3.08E-05 NO DATA 1.84E-05 4.20E-08 2.06E-07 3.59E-05 3.77E-04 5.22E-04 1.7 1E-04 NO DATA Liver 1 .99E-05 3.60E-06 5.38E-05 1 .08E-05 6.31 E-05 1 .73E-08 5.02E-08 4.23E-05 7.03E-04 6.11 E-04 1.7 1 E-07 3.08E-07 T. Body 4.51IE-06 8.98E-06 2.12F-05 2.55E-05 2.9 1 E-05 I .0E-08 3.56E-08 1 .86E-05 7. 1OE-05 4.33F-05 8.81 E-06 3.08E-07 Ingestion Dose Factor Thyroid Kidney Lung NO DATA 4.4 1E-06 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 1.59E-05 NO DATA NO DATA NO DATA NO DATA 3.06E-05 NO DATA NO DATA 1.24E-08 NO DATA NO DATA 5.41E-08 NO DATA 1.39E-02 4.94E-05 NO DATA NO DATA 1.81E-04 7.42E-05 NO DATA 1.64E-04 6.64E-05 NO DATA 4.06E-08 1.05E-07 3.08E-07 3.08E-07 3.08E-07 GI-LLI 7.31IE-06 8.97E-06 2.57E-05 2.57E-05 5.33E-05 1.46E-05 2.50E-05 1.5 1 E-06 1.91 E-06 1.91 E-06 4.20E-05 3.08E-07 Highest Annual Net Mean Concentration Indicator Water Location (pCi/I) Bone ALL 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.00E+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 214 735 0.OOE+00 Dose (mrem)Liver 0.OOE+00 0.OOE+U0 0.tIOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.47E-02 T. Body 0.OOE+00 0.OOE+00 0.0OF+00 0.OOE+00 0.OOE+00 0.OOE+00 (J.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 7.47E-02 Thyroid 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-i00 0.OOE+00 0.OOE-i00 7.47E-02 Kidney Lung 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.47E-02 7.47E-02 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 7.47E-02 Dose Commitment (mrem) =0.OOE+00 7.47E-02 7.47E-02 7.47E-02 7.47E-02 7.47E-02 747E-02 Section 4 -Page 7 Catawba Nuclear Station Dose from Drinking Water Pathway for 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 Ingestion Dose Factor Radionuclide Mn-54 Co-58 Fe-59 CO-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs- 137 HaLa-140 Bone NO DATA NO DATA 1.65E-05 NO DATA 1.37E-05 2.25E-08 1.16E-07 1.72E-05 2.34E-04 3.27E-04 8.31E-05 Liver 1.07E-05 i .80E-06 2.67E-05 5.29E-06 3.65E-05 8.76E-09 2.55E-08 1.73E-05 3.84E-04 3.13E-04 7.28E-08 T. Body 2.85E-06 5.5 1E-06 1.33E-05 1.56E-05 2.27E-05 6.26E-09 2.27E-08 9.83E-06 8. 1 OE-05 4.62E-05 4.85E-06 Thyroid NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 5.72E-03 NO DATA NO DATA NO DATA Kidney Lung GI-LLI 3.OOE-06 NO DATA 8.98E-06 NO DATA NO DATA 1.05E-05 NO DATA 7.74E-06 2.78E-05 NO DATA NO DATA 2.93E-05 2.30E-05 NO DATA 6.41E-06 8.23E-09 NO DATA 1.62E-05 3.65E-08 NO DATA 2.66E-05 2.84E-05 NO DATA 1.54E-06 1. 19E-04 4.27E-05 2.07E-06 1.02E-04 3.67E-05 1.96E-06 2.37E-08 4.34E-08 4.2 1 E-05 2.03E-07 2.03E-07 2.03E-07 Highest Annual Net Mean Concentration Indicator Water Location (pCi/I) Bone ALL 0.00 0.OOE+00 ALL 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 Liver 0.OOE÷00 0.OOE+00 0.OOE+00 0.OOE+OO 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 7.61IE-02 T. Body 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 7.61E-02 Thyroid 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.61 E-02 Kidney 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+O0 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 7.6 1E-02 Lung GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.00E+00 0.OOE+00 7.61E-02 7.61E-02 Dose (mrem)ALL ALL 214 0.00 0.00 735 0.00E+00O 0.OOE+00 0.OOE+00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 Dose Commitment (inrem) =Section 4 -Page 8 0.OOE+00 7.61E-02 7.61E-02 7.61E-02 7.6 1E-02 7.61E-02 7.61E-02*.e0000000000000000000000000000000000000000o Catawba Nuclear Station Dose from Broadleaf Vegetation Pathway for 2007 Data Maximum Exposed Child Child Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)Usage (intake in one year) =26 kg Radionuclide 1-131 Cs-134 Cs- 137 Bone 1 .72E-05 2.34E-04 3.27E-04 Ingestion Dose Factor Liver T. Body Thyroid Kidney Lung 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 3.84E-04 8. 1OE-05 NO DATA 1. 19E-04 4.27E-05 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 GI-LLI 1 .54E-06 2.07E-06 1 .96F-06 Highest Annual Net Mean Concentration Indicator Food Location (pCi/kg)ALL 0.00 ALL 0.00 201 63.1 Bone Liver T. Body 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.36E-0I 5.14E-01 7.58E-02 Dose (mrem)Thyroid Kidney Lung GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1 .67E-01 6.02E-02 3.22E-03 Dose Commitment (mrem) =5.36E-01 S. 14E-01I 7.58E-02 0.OOE+00 1.67E-01 6.02E-02 3.22E-03 Section 4 -Page 9 Catawba Nuclear Station Dose from Fish Pathway for 2007 Data Maximum Exposed Child Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/! = 9318 pCi/I x 0.9 = 8386 pCi/kg Usage (intake in one year) = 6.9 kg Radionuclide Mn-54 Co-58 Fe-59 CO-60 Zn-65 Cs-134 Cs- 137 H-3 Bone NO DATA NO DATA 1.65E-05 NO DATA 1.37E-05 2.34E-04 3.27E-04 NO DATA Liver 1.07E-05 1.80E-06 2.67E-05 5.29E-06 3.65E-05 3.84E-04 3.13E-04 2.03E-07 1T. Body 2.85E-06 5.51 E-06 1.33E-05 1.56E-05 2.27E-05 8.10E-05 4.62E-05 2.03E-07 Ingestion Dose Factor Thyroid Kidney Lung NO DATA 3.00E-06 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 7.74E-06 NO DATA NO DATA NO DATA NO DATA 2.30E-05 NO DATA NO DATA 1.19E-04 4.27E-05 NO DATA 1.02E-04 3.67E-05 2.03E-07 2.03E-07 2.03E-07 GI-LLI 8.98E-06 1.05E-05 2.78E-05 2.93E-05 6.41E-06 2.07E-06 1.96E-06 2.03E-07 Highest Annual Net Mean Concentration Indicator Fish Location (pCi/kg)ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.0 208 8386 Bone 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00)E+00 0).00)E+00 O.00E+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 1.17E-02 T. Body 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.17E-02 Dose (mrem)Thyroid Kidney 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 o.ooE+00 O.OOE+00 1.17E-02 1.17E-02 Lung 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 1.17E-02 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 1.17E-02 Dose Commitment (mrem) =0.OOE+00 1.17E-02 1.17E-02 1.17E-02 1.17E-02 1.17E-02 1.17E-02 Section 4 -Page 10

• @ee@@@e0eeee@Oe0e@@@@O@@@@@e@@@@O0ee0eO0ee@

Catawba Nuclear Station Dose from Shoreline Sediment Pathway for 2007 Data Maximum Exposed Child Shoreline Recreation

= 14 hr (in one year)Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/m 2 Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/mi 2) x Shore Width Factor x Sediment Surface Mass (kg/nm 2) x Sediment Concentration (pCi/kg)External Dose Factor Standing on Contaminated Ground Highest Annual Net Mean Concentration Dose Radionuclide Mn-54 Co-58 Co-60 Cs-134 Cs-137 (mrem/hr per pCi/m 2) Indicator T. Body Skin Location 5.80E-09 6.80E-09 ALL 7.00E-09 8.20E-09 208-IS 1.70E-08 2.OOE-08 208-IS 1.20E-08 1.40E-08 ALL 4.20E-09 4.90E-09 208-IS Dose Commitment (mrem) =Sediment (pCi/kg)0.00 87.7 94.6 0.00 61.3 (mrem)T. Body Skin 0.OOE+00 0.OOE+00 6.88E-05 8.05E-05 1.80E-04 2.12E-04 0.OOE+00 0.OOE+00 2.88E-05 3.36E-05 2.78E-04 3.26E-04 Section 4 -Page 11 Catawba Nuclear Station Dose from Drinking Water Pathway for 2007 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)Usage (intake in one year) =510 i Radionuclide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 BaLa-140 H-3 Bone NO DATA NO DATA 5.87E-06 NO DATA 5.76E-06 8.22E-09 4.12E-08 5.85E-06 8.37E-05 1.12E-04 2.84E-05 NO DATA Liver 5.90E-06 9.72E-07 1.37E-05 2.81IE-06 2.OOE-05 4.56E-09 1 .30E-08 8.19E-06 1 .97E-04 1.49E-04 3.48E-08 1 .06E-07 T. Body 1.17E-06 2.24E-06 5.29E-06 6.33E-06 9.33E-06 2.51 E-09 8.94E-09 4.4011-06 9.14E-05 5.19E-05 1 .83E-06 1.06E~-07 Ingestion Dose Factor Thyroid Kidney Lung GI-LLI NO DATA 1.76E-06 NO DATA 1.21E-05 NO DATA NO DATA NO DATA 1.34E-05 NO DATA NO DATA 4.32E-06 3.24E-05 NO DATA NO DATA NO DATA 3.66E-05 NO DATA 1.28E.05 NO DATA 8.47E-06 NO DATA 4.42E-09 NO DATA 1.95E-05 NO DATA 1.91E-08 NO DATA 3.OOE-05 2.39E-03 1.41E-05 NO DATA 1.62E-06 NO DATA 6.26E-05 2.39E-05 2.45E-06 NO DATA 5.07E-05 1.97E-05 2.12E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 1.06E-07 1.06E-07 1.06E-07 1.06E-07 Highest Annual Net Mean Concentration Indicator Water Location (pCi/I) Bone ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 O.00E+00 ALL 0.00 0.00E+00 ALL 0.00 O.OOE+00 ALL 0.00 O.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.00E+00 214 735 0.OOE+00 Dose (mrem)Liver 0.OOE+00 0.OOE+00 0.OOE+00 0.OO11+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 3.97E-02 T. Body 0.OOE+00 0.OOE+00 0.OOE+0O 0.0011+00 0.OOE+00 0.OOE+00 0.0013+00 0.OOE+00 0.0011+00 0.OOE+00 0.00E+00 3.97E-02 Thyroid 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 3.97E-02 Kidney Lung GI-LLI 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OO11+00 0.00E+00 0.00E+00 0.OO11+00 3.97E-02 0.OOE+00 0.OO11+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0011+00 3.97E-02 0.OOEe-00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+O0 0.0O11+00 0.OOE+00 3.97E-02 Dose Commitment (mrem)=0.OOE+00 3.97E-02 3.9711-02 3.97E-02 3.97E-02 3.9711-02 3.97E.02 Section 4 -Page 12 0 0 0 0 010 0

• 0 0 0 *0 0 0 0 0 0 0 0 0

• 0 Catawba Nuclear Station Dose from Broadleaf Vegetation Pathway for 2007 Data Maximum Exposed Teen Teen Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)Usage (intake in one year) =Radionuclide 1-131 Cs-134 Cs-137 Bone 5.85E-06 8.37E-05 1.12E-04 42 kg Ingestion Dose Factor Liver T. Body Thyroid Kidney Lung GI-LLI 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 Highest Annual Net Mean Concentration Indicator Food Location (pCi/kg)ALL 0.00 ALL 0.00 201 63.1 Bone Liver T. Body 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.O0E+00 0.00E+00 2.97E-01 3.95E-01 1.38E-01 Dose (mrem)Thyroid Kidney Lung GI-LLI 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.34E-01 5.22E-02 5.62E-03 Dose Commitment (mrem)2.97E-01 3.95E-01 1.38E-01 0.00E+00 1.34E-01 5.22E-02 5.62E-03 Section 4 -Page 13 Catawba Nuclear Station Dose from Fish Pathway for 2007 Data Maximum Exposed Teen Teen Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/l = 9318 pCi/I x 0.9 = 8386 pCi/kg Usage (intake in one year) = 16 kg Radionuclide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 H-3 Bone NO DATA NO DATA 5.87E-06 NO DATA 5.76E-06 8.37E-05 1.12E-04 NO DATA Liver 5.90E-06 9.72E-07 1 .37E-05 2.8 1E-06 2.OOE-05 1 .97E-04 1 .49E-04 1 .06E-07 T. Body 1.17E-06 2.24E-06 5.29E-06 6.33E-06 9.33E-06 9.14E-05 5.19E-05 1.06E-07 Ingestion Dose Factor Thyroid Kidney Lung NO DATA 1.76E-06 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 4.32E-06 NO DATA NO DATA NO DATA NO DATA 1.28E-05 NO DATA NO DATA 6.26E-05 2.39E-05 NO DATA 5.07E-05 1.97E-05 1.06E-07 1.06E-07 i .06E-07 GI-LLI 1.2IE-05 1 .34E-05 3.24E-05 3.66E-05 8.47E-06 2.45E-06 2.12E-06 1 .06E-07 Highest Annual Net Mean Concentration Location (pCi/kg)ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 208 8386 Bone 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.42E-02 T. Body 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.42E-02 Dose (mrem)Thyroid Kidney 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.42E-02 1.42E-02 Lung 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.42E-02 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.42E-02 Dose Commitment (mrem) =0.OOE+00 1.42E-02 1.42E-02 1 .42E-02 i .42E-02 1.42E-02 1.42E-02 Section 4 -Page 14 Catawba Nuclear Station Dose from Shoreline Sediment Pathway for 2007 Data Maximum Exposed Teen Shoreline Recreation

= 67 hr (in one year)Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/m 2 Teen Dose from Shoreline Sediment Pathway (noreno) = Shoreline Recreation (hr) x External Dose Factor (lnrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/m2 ) x Sediment Concentration (pCi/kg)External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/rn 2)Radionuclide T. Body Skin Mn-54 5.80E-09 6.80E-09 Co-58 7.OOE-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Cs-134 1.20E-08 1.40E-08 Cs-137 4.20E-09 4.90E-09 Dose Commitment (mrem) =Indicator Location ALL 208-IS 208-IS ALL 208-IS Sediment (pCi/kg)0.00 87.7 94.6 0.00 61.3 (inrem)T. Body Skin 0.00E+00 0.00E+00 3.29E-04 3.85E-04 8.62E-04 1.01E-03 0.00E+00 0.00E+00 1.38E-04 1.61E-04 1.33E-03 1.56E-03 Section 4 -Page 15 Catawba Nuclear Station Dose from Drinking Water Pathway for 2007 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/i)Usage (intake in one year) =730 1 Ingestion Dose Factor Radionuclide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 BaLa-140 H-3 Bone NO DATA NO DATA 4.34E-06 NO DATA 4.84E-06 6.22E-09 3.04E-08 4.16E-06 6.22E-05 7.97E-05 2.03E-05 NO DATA Liver 4.57E-06 7.45E-07 1 .02E-05 2.14E-06 1.54E-05 3.46E-09 9.75E-09 5.9SE-06 1.48E-04 1 .09E-04 2.55E-08 1 .05E-07 T. Body 8.72E-07 1.67E-06 3.9 1E-06 4.72E-06 6.96E-06 1.86E-09 6.60E-09 3.41E-06 1.2 1E-04 7.14E-05 1.33E-06 1.05E-07 Thyroid Kidney NO DATA 1.36E-06 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 1.03E-05 NO DATA 3.42E-09 NO DATA 1.53E-08 1.95E-03 1.02E-05 NO DATA 4.79E-05 NO DATA 3.70E-05 NO DATA 8.67E-09 1.05E-07 1 .05E-07 Lung GI-LLL NO DATA 1.40E-05 NO DATA 1.51E-05 2.85E-06 3.40E-05 NO DATA 4.02E-05 NO DATA 9.70E-06 NO DATA 2.1OE-05 NO DATA 3.09E-05 NO DATA 1.57E-06 1.59E-05 2.59E-06 1.23E-05 2.1 IE-06 1.46E-08 4.18E-05 1.05E-07 1.05E-07 Highest Annual Net Mean Concentration Indicator Water Location (pCi/I) Bone ALL 0.00 0.OOE+00 ALL 0.00 0.00E+00 ALL 0.00 0.00E+00 ALL 0.00 0.OOE+00 ALL 0.00 0.00E+00 ALL 0.00 0.OOE+00 ALL 0.00 O.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 ALL 0.00 0.OOE+00 214 735 0.OOE+00 Liver 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.63E-02 T. Body 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 5.63E-02 Thyroid 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.63E4)2 Dose (mrem)Kidney Lung GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 5.63E-02 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 5.63E-02 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.63E-02 Dose Commitment (mrem) =0.OOE+00 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 5.63E-02 Section 4 -Page 16 10900010*00*0001000000000000100000000000000000 Catawba Nuclear Station Dose from Broadleaf Vegetation Pathway for 2007 Data Maximum Exposed Adult Adult Dose from Vegetation (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)Usage (intake in one year) =64 kg Radionuclide 1-131 Cs- 134 Cs-137 Bone 4.16E-06 6.22E-05 7.97E-05 Liver T. Body 5.95E-06 3.41E-06 1.48E-04 1.21 E-04 1.09E-04 7.14E-05 Ingestion Dose Factor Thyroid Kidney Lung GI-LLI 1.95E-03 1.02E-05 NO DATA 1.57E-06 NO DATA 4.79E-05 1.59E-05 2.59E-06 NO DATA 3.70E-05 1.23E-05 2.11E-06 Highest Annual Net Mean Concentration Indicator Food Location (pCi/kg)ALL 0.00 ALL 0.00 201 63.1 Bone Liver 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 3.22E-01 4.40E-01 T. Body 0.00E+00 0.OOE+00 2.88E-01 Dose (mrem)Thyroid Kidney Lung GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 1.49E-01 4.97E-02 8.52E-03 Dose Commitment (mrem) =3.22E-01 4.40E-01 2.88E-01 I .OOE+00 1 .49E-01 4.97E-02 8.52E-03 Section 4 -Page 17 Catawba Nuclear Station Dose from Fish Pathway for 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 = 9318 pCi/l x 0.9 = 8386 pCi/kg Usage (intake in one year) = 21 kg Radionuclide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs- 137 H-3 Bone NO DATA NO DATA 4.34E-06 NO DATA 4.84E-06 6.22E-05 7.97E-05 NO DATA Liver 4.57E-06 7.45E-07 1 .02E-05 2.14E-06 1 .54E-05 1 .48E-04 1 .09E-04 1 .05E-07 Ingestion Dose Factor T. Body Thyroid Kidney 8.72E-07 NO DATA 1.36E-06 1.67E-06 NO DATA NO DATA 3.9 1E-06 NO DATA NO DATA 4.72E-06 NO DATA NO DATA 6.96E-06 NO DATA 1.03E-05 1.21 E-04 NO DATA 4.79E-05 7.14E-05 NO DATA 3.70E-05 1.05E-07 1.05E-07 1.05E-07 Lung NO DATA NO DATA 2.85E-06 NO DATA NO DATA 1.59E-05 1 .23E-05 1.05E-07 GI-LLI 1.40E-05 1.51 E-05 3.40E-05 4.02E-05 9.70E-06 2.59E-06 2.11 E-06 1.05E-07 Highest Annual Net Mean Concentration Location (pCi/kg)ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 ALL 0.00 208 8386 Bone 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.09E+00 0.00E+00 0.OOE+00 0.OOE+00 Liver O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 1.85E-02 T. Body 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 1.85E-02 Dose (mrem)Thyroid Kidney 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.85E-02 1.85E-02 Lung 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.85E-02 GI-LLI 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1 .85E-02 Dose Commitment (mrem) =0.OOE+00 1.85E-02 1.85E-02 1.85E-02 1.85E-02 1.85E-02 1.85E-02 Section 4 -Page 18 Catawba Nuclear Station Dose from Shoreline Sediment Pathway for 2007 Data Maximum Exposed Adult Shoreline Recreation

= 12 hr (in one year)Shore Width Factor = 0.2 Sediment Surface Mass 40 kg/m 2 Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (nmrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/mi 2) x Sediment Concentration (pCi/kg)External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem)(mren/hr per pCi/m 2) Indicator Sediment Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.00E+00 0.00E+00 Co-58 7.00E-09 8.20E-09 208-IS 87.7 5.89E-05 6.90E-05 Co-60 1.70E-08 2.00E-08 208-1S 94.6 1.54E-04 1.82E-04 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.OOE+00 0.OOE+00 Cs°137 4.20E-09 4.90E-09 208-IS 61.3 2.47E-05 2.88E-05 Dose Commitment (mrem) = 2.38E-04 2.80E-04 Section 4 -Page 19 0* .0 S EnRad Laboratories, Fisheries, and Aquatic Ecology performed the environmental 0 sample collections as specified by approved sample collection procedures.

0* 5.2 SAMPLE ANALYSIS 0 EnRad Laboratories performed the environmental sample analyses as specified sl 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 The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

• 5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE S*5.4.1 DAILY QUALITY CONTROL S EnRad Laboratories has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy.

Daily quality control 0checks ensure that instruments are in proper working order and these checks Sare used to monitor instrument performance.

0 5.4.2 CALIBRATION VERIFICATION

• National Institute of Standards and Technology (NIST) standards that represent*counting geometries are analyzed as unknowns at various frequencies ranging*from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance.

Investigations are performed and documented should calibration verification data fall out of*limits.0 0 0 0 5 Section 5 -Page 1 S 0 S 0 5.4.3 BATCH PROCESSING 0 0 Method quality control samples are analyzed with sample analyses that are processed in batches. These include gross beta in drinking water and tritium analyses.0 5.5 DUKE ENERGY INTERCOMPARISON PROGRAM 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 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 S The Catawba Radiation Protection Section was not audited by the Quality Assurance Group in 2007. The program was audited in 2006. There were no REMP recommendations as a result of the 2006 audit.0 EnRad Laboratories was not audited by the Quality Assurance Group in 2007. The program was audited in 2006. There were no REMP recommendations as a result of the 2006 audit.5.7 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS 0 0 The Catawba Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in 2007 (Reference 6.12). An issue with dual air sampler configuration was identified with the potential for sampler intake to be diluted by the other's exhaust. Resolution of this issue is described in PIP C-07-04135.

0 5.8 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM 0 0 EnRad Laboratories routinely participates with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) in an intercomparison program. EnRad Laboratories sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the State of South Carolina DHEC Laboratory.

0 0 0 0 0 Section 5 -Page 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.9 TLD INTERCOMPARISON PROGRAM 5.9.1 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM Radiation Dosimetry and Records participates in a quarterly TLD intercomparison program administered by Nuclear Technology Services, Inc.of Roswell, GA. Nuclear Technology Services irradiates environmental dosimeters quarterly and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure.

A summary of the Nuclear Technology Services Intercomparison Report is documented in Table 5.0-B.5.9.2 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM The State of North Carolina Radiation Protection Section suspended this program during 2007 as described in PIP G-07-00366.

5.9.3 INTERNAL CROSSCHECK (DUKE ENERGY)Radiation Dosimetry and Records participates in a quarterly TLD intracomparison program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff irradiates environmental dosimeters quarterly and submits them for analysis of the unknown estimated delivered exposure.

A summary of the Internal Cross Check (Duke Energy) Result is documented in Table 5.0-B.Section 5 -Page 3 TABLE 5.0-A DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 2007 CROSS-CHECK RESULTS FOR ENRAD LABORATORIES Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all three analyses yielded results within the designated acceptance range. A status of "I Pass" indicates that one analysis of the cross-check was performed.

If applicable, footnote explanations are included following this data table.Gamma in Water 3.5 liters Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/i pCi/I 6/26/2007 Q072GWR Cr-51 1.06- 1.88 E4 1.41 E4 1.37 E4 3 Pass Co-57 2.68-4.76 E2 3.58 E2 3.80 E2 3 Pass Co-60 1.46-2.59 E3 1.95 E3 1.94 E3 3 Pass Sr-85 1.83- 3.24 E3 2.44 E3 2.30 E3 3 Pass Y-88 2.82-5.00 E3 3.76 E3 3.62 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 1.85 E3 3 Pass Te-123M 3.73-6.61 E2 4.97 E2 4.78 E2 3 Pass Cs-137 1.13-2.00 E3 1.51 E3 1.45 E3 3 Pass 11/20/2007 Q074GWS Cr-51 2.96- 5.24 E5 3.94 E5 3.97 E5 3 Pass Co-57 1.33- 2.37 E4 1.78 E4 1.86 E4 3 Pass 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 Y-88 1.23-2.19 E5 1.65 E5 1.64 E5 3 Pass Cd-109 3.93-6.96 E5 5.24 E5 5.31 E5 3 Pass Sn-l 13 6.18- 10.96 E4 8.24 E4 8.29 E4 3 Pass Te-123M 1.61-2.85 E4 2.15 E4 2.20 E4 3 Pass Cs-137 6.07 -10.76 E4 8.09 E4 7.82 E4 3 Pass Gamma in Water 1.0 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 6/26/2007 Q072GWR Cr-51 1.06-1.88 E4 1.41 E4 1.41 E4 3 Pass Co-57 2.68- 4.76 E2 3.58 E2 3.89 E2 3 Pass Co-60 1.46-2.59 E3 1.95 E3 1.97 E3 3 Pass 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 Cd-109 0.77- 1.36 E4 1.02 E4 1.06 E4 3 Pass 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 Cs-137 1.13-2.00 E3 1.51 E3 1.38 E3 3 Pass S 0 0 0 S 0 S 0 S S 0 S 0 0 S 0 0 0 0 0 0 S 0 0 0 S S 0 0 0 0 0 S S 0 S 0 0 S 0 S S S 0 Section 5 -Page 4 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 S 0 0 0 0 0 0 Gamma in Water 1.0 liter, continued 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 £4 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 Date Range Value Value Status pCi/I pCi/1 pCi/l 6/26/2007 Q072GWR Cr-51 1.06- 1.88 E4 1.41 E4 1.41 E4 3 Pass Co-57 2.68-4.76 E2 3.58 E2 3.76 E2 3 Pass Co-60 1.46-2.59 E3 1.95 E3 1.97 E3 3 Pass Sr-85 1.83-3.24 E3 2.44 E3 2.32 E3 3 Pass Y-88 2.82-5.00 E3 3.76 E3 3.62 E3 3 Pass Cd-109 0.77- 1.36 E4 1.02 E4 1.02 E4 3 Pass 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 4.88 E2 3 Pass 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 Co-57 1.33-2.37 E4 1.78 E4 1.79 E4 3 Pass Co-60 7.33 -12.99 E4 9.77 E4 9.54 E4 3 Pass Sr-85 7.21 -12.78 E4 9.61 E4 9.28 E4 3 Pass Y-88 1.23-2.19 E5 1.65 E5 1.61 E5 3 Pass Cd-109 3.93-6.96 E5 5.24 E5 5.26 E5 3 Pass 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 Gamma in Water 0.25 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/I pCi/I 6126/2007 Q072GWR Cr-51 1.06-1.88 E4 1.41 E4 1.44 E4 3 Pass 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-I 13 1.40-2.49 E3 1.87 E3 1.86 E3 3 Pass Te-123M 3.73-6.61 E2 4.97 E2 4.86 E2 3 Pass Cs-137 1.13-2.00 E3 1.51 E3 1.45 E3 3 Pass Section 5 -Page 5 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 Co-57 1.33- 2.37 E4 1.78 E4 1.82 E4 3 Pass Co-60 7.33 -12.99 E4 9.77 E4 9.56 E4 3 Pass Sr-85 7.21 -12.78 E4 9.61 E4 9.27 E4 3 Pass Y-88 1.23-2.19 E5 1.65 E5 1.62 E5 3 Pass Cd-109 3.93-6.96 E5 5.24 E5 5.12 E5 3 Pass Sn-113 6.18- 10.96 E4 8.24 E4 8.08 E4 3 Pass Te-123M 1.61-2.85 E4 2.15 E4 2.15 E4 3 Pass Cs-137 6.07 -10.76 E4 8.09 E4 7.67 E4 3 Pass Gamma in Filter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 6/14/2007 E5415-37 Cr-51 2.63 -4.67 E2 3.51 E2 3.25 E2 3 Pass Mn-54 0.86- 1.52 E2 1.14 E2 1.18 E2 3 Pass Co-58 1.02-1.81 E2 1.36 E2 1.28 E2 3 Pass Fe-59 0.86- 1.52 E2 1.14 E2 1.20 E2 3 Pass Co-60 1.22-2.17 E2 1.63 E2 1.57 E2 3 Pass Zn-65 1.72-3.05 E2 2.29 E2 2.31 E2 3 Pass Cs-134 1.25-2.21 E2 1.66 E2 1.48 E2 3 Pass Cs-137 0.87- 1.54 E2 1.16 E2 1.06 E2 3 Pass Ce-139 0.00-0.00 E1 0.00E+00 3.10 E1 3 Pass Ce-141 1.03- 1.82 E2 1.37 E2 1.29 E2 3 Pass Iodine in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 5/15/2007 Q072LIWI 1-131 N/A 0.001+00 0.00E+00 3 Pass 5/15/2007 Q072LIW2 1-131 1.84-3.27 E3 2.46 E3 2.06 E3 3 Pass 5/15/2007 Q072LIW3 1-131 1.70- 3.01 E1 2.26 E1 2.20 E1 3 Pass Iodine in Milk Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 7/25/2007 Q073LIMI 1-131 0.95- 1.68 E3 1.27 E3 1.11 E3 3 Pass 7/25/2007 Q073LIM2 1-131 3.62-8.34 E0 5.49 E0 5.65 E0 3 Pass 7/25/2007 Q073LIM3 1-131 2.30-4.07 El 3.06 E1 2.67 E1 3 Pass S 0 0 S S S 0 S S S S S S 0 S S S 0 S 0 0 S S 0 0 S S S S S 0 S S 0 S 0 S I I Section 5 -Page 6 0 0 0* Iodine on Cartridge Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status 6/pCi pCi pCi 6/14/2007 E5416-37 1-131 5.92 -10.49 E1 7.89 El 9.77 El 3 Pass*Beta Air Particulate Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 6/14/2007 E5417-37 Cs-137 0.92- 1.62 E2 1.22 E2 1.14 E2 3 Pass**Beta in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check* Date Range Value Value Status O pCi/l pCi/I pCi/l 6/14/2007 E5418-37 Cs-137 1.11- 1.97 E2 1.48 E2 1.58 E2 3 Pass 0*Beta Smear Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status dpm dpm dpm 1/11/2007 A21058-04 Beta 1.01 -1.80 E4 1.35 E4 1.32 E4 3 Pass Tritium in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/I pCi/I 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 6/25/2007 Q072TWR3 H-3 1.32-2.34 E3 1.76 E3 1.64 E3 3 Pass[0/7/2007 Q074TWSLI H-3 N/A 0.OOE+00 0OOE+00 3 Pass 0 10/7/2007 Q074TWSL2 H-3 2.71 -4.81 E4 3.62 E4 3.63 E4 3 Pass 0 0 0 0 0 0 0 0 O ~Section 5 -Page 7 0 0 Table 5.0-A Footnote Explanations (1) Gamma in Filter, Sample ID E5415-37, Reference Date 6/14/2007 Ce-139 was identified in cross-check sample and reported.

The cross check supplier does not include this radionuclide on the certificate of analysis for this cross-check sample. The radionuclide was determined to be an inherent contaminant in the cross-check sample.0 0 S 0 0 0 0 S 0 0 0 S ,0 S 0 0 S 0 0 S 0 0 S 0 0 0 0 0 0 S 0 0 0 S 0 Section 5 -Page 8 S 0 0 0 9 0 0 0 0 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 IBI+S 4.44 <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 102174 65.5 63.7 -2.75 <+/-15% Pass 102006 92.2 99.0 7.38 <+/-15% Pass 102220 65.5 67.7 3.36 <+/-15% Pass 102093 92.2 97.5 5.75 <+/-15% Pass 102236 65.5 64.5 -1.53 <+/-15% Pass 102244 92.2 103.6 12.36 <+/-15% Pass 102302 65.5 66.5 1.53 <+/-15% Pass 102343 92.2 100.3 8.79 <+/-15% Pass 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 Standard Deviation (S) 2.44 Standard Deviation (S) 2.46 Measure Performance JBI+S 2.75 <15% Pass Measure Performance IBI+S 11.16 <15% Pass 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Section 5 -Page 9 Internal Crosscheck (Duke Energy)ist Quarter 2007 TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 100770 24.0 22.3 -6.97 <+/-15% Pass 100522 24.0 23.6 -1.70 <+/-15% Pass 100041 24.0 22.0 -8.22 <+/-15% Pass 100038 24.0 23.0 -4.28 <+/-15% Pass 100762 24.0 21.1 -11.93 <+/-15% Pass 100148 24.0 23.2 -3.41 <+/-15% Pass 100279 24.0 23.0 -4.37 <+/-15% Pass 100619 24.0 23.2 -3.48 <+/-15% Pass 100784 24.0 22.0 -8.45 <+/-15% Pass 100814 24.0 22.8 -4.93 <+/-15% Pass Average Bias (B) -5.77 Standard Deviation (S) 3.07 Measure Performance 1BI+S 8.84 <15% Pass 2nd Quarter 2007 TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 101190 48.0 47.1 -1.88 <+/-15% Pass 100026 48.0 46.4 -3.33 <+/-15% Pass 100148 48.0 46.3 -3.54 <+/-15% Pass 100038 48.0 47.2 -1.67 <+/-15% Pass 100096 48.0 46.4 -3.33 <+/-15% Pass 100770 48.0 46.1 -3.96 <+/-15% Pass 100740 48.0 46.9 -2.29 <+/-15% Pass 100784 48.0 45.6 -5.00 <+/-15% Pass 100619 48.0 47.1 -1.88 <+/-15% Pass 100814 48.0 47.0 -2.08 <+/-15% Pass Average Bias (B) -2.90 Standard Deviation (S) 1.10 Measure Performance IBI+S 4.00 <15% Pass 3rd Quarter 2007 TLD Delivered Reported Number (mrem) (mrem)100389 24.0 22.7 100407 24.0 22.8 100629 24.0 22.9 100409 24.0 23.7 100647 24.0 23.5 100274 24.0 22.8 100117 24.0 22.6 100162 24.0 22.1 100423 24.0 23.1 100611 24.0 23.6 Average Bias (B)Standard Deviation (S)Measure Performance 1B1+S Bias Pass/Fail (% diff) Criteria Pass/Fail-5.42 <+/-15% Pass-5.00 <+/-15% Pass-4.58 <+/-15% Pass-1.25 <+/-15% Pass-2.08 <+/-15% Pass-5.00 <+/-15% Pass-5.83 <+/-1 5% Pass-7.92 <+/-1 5% Pass-3.75 <+/-15% Pass-1.67 <+/-15% Pass-4.25 2.09 6.34 <15% Pass 4th Quarter 2007 TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail 100412 12.0 11.9 -0.83 <+/-15% Pass 100733 12.0 11.3 -5.83 <+/-15% Pass 100477 12.0 11.6 -3.33 <+/-15% Pass 100406 12.0 11.5 -4.17 <+/-15% Pass 100863 12.0 11.8 -1.67 <+/-15% Pass 100870 12.0 11.6 -3.33 <+/-15% Pass 100752 12.0 12.1 0.83 <+/-15% Pass 101021 12.0 11.6 -3.33 <+/-15% Pass 100096 12.0 11.9 -0.83 <+/-15% Pass 101307 12.0 11.4 -5.00 <+/-15% Pass Average Bias (B) -2.75 Standard Deviation (S) 2.08 Measure Performance IBI+S 4.83 <15% Pass 0 0 0 0 S 0 0 S 0 0 0 0 0 0 0 0 0 0 Secton -Pag 100 0 0 0 0 0 0*

6.0 REFERENCES

.06.1 Catawba Selected License Commitment Report 6.2 Catawba Technical Specifications 6.3 Catawba Updated Final Safety Analysis Review 6.4 Catawba Offsite Dose Calculation Manual 6.5 Catawba Annual Environmental Operating Report 1985 -2006 6.6 Catawba Annual Effluent Report 1985 -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 83-93.0 6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of*Evaluating Compliance with 1OCFR50, Appendix I.0 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 Inspection Report 2007004 October 29, 2007 6.13 Duke Energy Corporation EnRad Laboratory Charcoal Cartridge Study, performed 2001 0 0 0 0 0 0 0 0 0 0 0 0~~Section 6 -Pagel1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PROCEDURES Appendix A -Page I 0 0 0 0 APPENDIX A 0 ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES 0 Adherence to established procedures for sampling and analysis of all environmental media at Catawba Nuclear Station was required to ensure compliance with Station Selected Licensee Commitments.

Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved.Environmental sampling and analyses were performed by EnRad Laboratories, Dosimetry and Records, Fisheries and Aquatic Ecology.S This appendix describes the environmental sampling frequencies and analysis procedures by media type.0 I. CHANGE OF SAMPLING PROCEDURES 0 TLD 222 (Site Boundary, N sector) was relocated due to safety access issues from 0.69 miles to 0.71 miles as described in PIP G-06-00151.

II. DESCRIPTION OF ANALYSIS PROCEDURES 0 Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software.

Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy.

Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry.Low-level iodine analyses are performed by passing a designated sample aliquot through a pre-weighed amount of ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried, mixed thoroughly, and a net resin weight determined before being transferred to appropriate counting geometry and analyzed by gamma spectroscopy.

Tritium analyses are performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system or Perkin-Elmer 2900TR liquid scintillation system. Tritium samples are distilled and batch processed with a tritium spike and blank to verify instrument performance and sample preparation technique are acceptable.

0 0 0 Appendix A -Page 2 0 0 0 0* Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by Tennelec XLB Series 5 gas-flow proportional counters.Samples are batch processed with a blank to ensure sample contamination has not 0occurred.

• III. CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 2007.* IV. SAMPLING AND ANALYSIS PROCEDURES 0 A.1 AIRBORNE PARTICULATE AND RADIOIODINE 0Airborne particulate and radioiodine samples at each of five locations were composited continuously by means of continuous air samplers.

Air particulates

• were collected on a particulate filter and radioiodines were collected in a*charcoal cartridge positioned behind the filter in the sampler. The samplers are designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute. Filters and cartridges were collected weekly. A separate weekly gamma analysis was*performed on each charcoal cartridge and air particulate.

A weekly gross beta*analysis was performed on each filter. The continuous composite samples were collected from the locations listed below.*Location 200 = Site Boundary (0.63 mi. NNE)*Location 201 = Site Boundary (0.53 mi. NE)*Location 205 = Site Boundary (0.23 mi. SW)Location 212 = Tega Cay (3.32 ml. E)Location 258 = Fairhope Road (9.84 mi. W)0 A.2 DRINKING WATER Monthly composite drinking water samples were collected at each of two*locations.

A gross beta and gamma analysis was performed on monthly*composites.

Tritium analysis was performed on the quarterly composites.

The composites were collected monthly from the locations listed below.Location 214 = Rock Hill Water Supply (7.30 mi. SSE)*Location 218 = Belmont Water Supply (13.5 mi. NNE)0*A.3 SURFACE WATER 0 Monthly composite samples were collected at each of three locations.

A gamma*analysis was performed on the monthly composites.

Tritium analysis was A 0 0* Appendix A -Page 3 0 performed on the quarterly composites.

The composites were collected monthly from the locations listed below.Location 208 Location 211 Location 215 Discharge Canal (0.45 mi. S)Wylie Dam (4.06 mi. ESE)River Pointe -Hwy 49 (4.21 mi. NNE)A.4 GROUND WATER Grab samples were collected quarterly from residential wells at each of two locations.

A gamma analysis and tritium analysis were performed on each sample. The samples were collected from the locations listed below.Location 252 Location 254 Residence (0.64 mi. SW)Residence (0.82 mi. N)A.5 MILK Biweekly grab samples were collected at one location.

A gamma and low-level Iodine-131 analysis was performed on each sample. The biweekly grab samples were collected from the location listed below.0 0 0 0 0 0 0 S 0 0 0 S S 0 0 0 0 0 0 Location 221= Dairy (14.5 mi. NW)A.6 BROADLEAF VEGETATION Monthly samples were collected at each of five locations.

A gamma analysis was performed on each sample. The samples were collected from the locations listed below.Location 200 Location 201 Location 222 Location 226 Location 258 A.7 FOOD PRODUCTS Site Boundary (0.63 mi. NNE)Site Boundary (0.53 mi. NE)Site Boundary (0.70 mi. N)Site Boundary (0.48 mi. S)Fairhope Road (9.84 mi. W)Monthly samples were collected when available during the harvest season at one location.

A gamma analysis was performed on each sample. The samples were collected from the location listed below.Location 253= Irrigated Gardens (1.90 mi. SSE)Appendix A -Page 4 0 S 0 0 0 0 S 0 0 0 0 0 S 0 0 0 0 S 0 0 S 0 0 0 0 A.8 FISH Semiannual samples were collected at each of two locations.

A gamma analysis was performed on the edible portions of each sample. Boney fish (i.e. Sunfish)were prepared whole minus the head and tail portions.

The samples were collected from the locations listed below.Location 208 Location 216 Discharge Canal (0.45 mi. S)Hwy 49 Bridge (4.19 mi. NNE)A.9 SHORELINE SEDIMENT Semiannual samples were collected at each of three locations.

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 208 Location 210 Location 215 Discharge Canal (0.45 mi. S)Ebenezer Access (2.31 mi. SE)River Pointe -Hwy 49 (4.21 mi. NNE)A.10 DIRECT GAMMA RADIATION (TLD)Thermoluminescent dosimeters (TLD) were collected quarterly at forty-one locations.

A gamma exposure rate was determined for each TLD. TLD locations are listed in Table 2.1-B. The TLDs were placed as indicated below.An inner ring of 16 TLDs, one in each meteorological sector in the general area of the site boundary.An outer ring of 16 TLDs, one in each meteorological sector in the 6 to 8 kilometer range.The remaining TLDs were placed in special interest areas such as population centers, residential areas, schools, and at three control locations.

AMl ANNUAL LAND USE CENSUS An Annual Land Use Census was conducted to identify within a distance of 8 kilometers (5.0 miles) from the station, the nearest location from the site boundary in each of the sixteen meteorological sectors, the following:

The Nearest Residence The Nearest Garden greater than 50 square meters or 500 square feet Appendix A -Page 5

• The Nearest Milk-giving Animal (cow, goat, etc.)The census was conducted during the growing season on 7/10 and 7/11/2007.

Results are shown in Table 3.11. No changes were made to the sampling procedures during 2007 as a result of the 2007 census.V. GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS The Catawba site centerline used for GPS measurements was referenced from the Catawba Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1.1, Specification of Location.

Waypoint coordinates used for CNS GPS measurements were latitude 35 0-Y-5"N and longitude 81'-4'-10"W.

Maps and tables were generated using North American Datum (NAD) 27. Data normally reflect accuracy to within 2 to 5 meters from point of measurement.

All GPS field measurements were taken as close as possible to the item of interest.

Distances for the locations are displayed using three significant figures.S S 0 S S S 0 S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S S 0 Appendix A -Page 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PRO GRAM

SUMMARY

OF RESULTS 2007 Appendix B -Page I Environmental Radiological Monitoring Program Summary Facility:

Catawba Nuclear Station Location:

York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2007 to 31-DEC-2007 Type and Lower Location with Highest No. of Non-Medium or Total Low All Indicator AnLo at w est Control Routine Pathway Limit of Annual Mean Sampled Number Detection Locations Name, Distance, Direction Location Report*of Meas.Unit of Analyses LLD Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Air Particulate 258 (pCi/m3) (9.84 mi W)BETA 260 L.OOE-02 1.80E-2 (208/208) 212 1.88E-2 (52/52) 1.86E-2 (52/52) 0 4.66E-3 -3.75E-2 (3.32 mi E) 8.15E-3 -3.75E-2 8.66E-3 -3.50E-2 CS-134 260 5.OOE-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 260 6.OOE-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 1-131 260 7.OOE-02 0.00 (0/208) 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 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated

@ 2/26/2008 07:29 Appendix B -Page 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Environmental Radiological Monitoring Program Summary Facility:

Catawba Nuclear Station Location:

York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2007 to 31-DEC-2007 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 Medium or Type and Lower Location with Highest Control No. of Non-Total All Indicator L ocation Pathway Number Limit of Locations Annual Mean Location Routine Sampled of Detection Name, Distance, Direction Report Meas.Unit of Analyses Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Air Radioiodine 258 (pCi/m3) (9.84 mi W)CS-134 260 5.OOE-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 260 6.OOE-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 1-131 260 7.OOE-02 0.00 (0/208) 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 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated

@ 2/26/2008 07:30 Appendix B -Page 3 Environmental Radiological Monitoring Program Summary Facility:

Catawba Nuclear Station Location:

York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2007 to 31-DEC-2007 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone All Indicator Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction Lepor Meas.Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Drinking Water 218 (pCi/liter)

(13.5 mi NNE)BALA-140 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 BETA 26 4 2.34 (13/13) 214 2.34 (13/13) 2.21 (13/13) 0 0.82 -2.97 (7.30 mi SSE) 0.82 -2.97 1.56- 3.10 CO-58 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CO-60 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-134 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 26 18 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 FE-59 26 30 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 H-3 8 2000 1653(4/4) 214 1653(4/4) 918(4/4) 0 1110-2280 (7.30 mi SSE) 1110-2280 850-991 1-131 26 15 0.00(0/13) 0.00(0/14) 0.00(0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 MN-54 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 NB-95 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 ZN-65 26 30 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 ZR-95 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0,00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 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 Report Generated

@ 2/26/2008 07:33 Appendix B -Page 4 Environmental Radiological Monitoring Program Summary Facility:

Catawba Nuclear Station Location:

York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2007 to 31-DEC-2007 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.Unit of Analyses Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Surface Water 215 (pCi/liter)

(4.21 mi NNE)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 CO-58 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CO-60 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-134 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 39 18 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 H-3 12 2000 5868(8/8) 208 10100 (4/4) 782(4/4) 0 1090- 12400 (0.45 mi S) 8210- 12400 701 -899 1-131 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 NB-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 ZN-65 39 30 0,00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 ZR-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated

@ 2/26/2008 07:39 Appendix B -Page 5 Environmental Radiological Monitoring Program Summary Facility:

Catawba Nuclear Station Location:

York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2007 to 31-DEC-2007 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Ground Water NO CONTROL (pCi/liter)

LOCATION BALA-140 8 15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CO-58 8 15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CO-60 8 15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-134 8 15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 8 18 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 FE-59 8 30 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 H-3 8 2000 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 1-131 8 15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 MN-54 8 15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 NB-95 8 15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 ZN-65 8 30 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 ZR-95 8 15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 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 Report Generated

@ 2/26/2008 07:39 Appendix B -Page 6 0 0 0 0 0 0 0 S 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 Environmental Radiological Monitoring Program Summary Facility:

Catawba Nuclear Station Location:

York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2007 to 31-DEC-2007 No. of Non-Medium or Type and Total Lower All Idit Location with Highest Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction Lepor Meas.Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Milk NO INDICATOR 221 (pCi/liter)

LOCATION (14.5 mi NW)BALA-140 26 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-134 26 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 26 18 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 1-131 26 15 0.00 (0/0) 0.00(0/0) 0.00 (0/26) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 LLI-131 26 1 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated

@ 2/26/2008 07:40 Appendix B -Page 7 Environmental Radiological Monitoring Program Summary Facility:

Catawba Nuclear Station Location:

York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2007 to 31-DEC-2007 No. of Non-Medium or Type and Total Lower Location with Highest NontrolNone All IndicatorCoto Ruin Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Broadleaf 258 Vegetation (9.84 mi W)(pCi/kg-wet)

CS-134 60 60 0.00 (0/48) 0.00 (0/12) 0.00 (0/12) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 60 80 56.1 (6/48) 201 63.1 (5/12) 0.00 (0/12) 0 20.9 -96.5 (0.53 mi NE) 41.0- 96.5 0.00 -0.00 1-131 60 60 0.00 (0/48) 0.00 (0/12) 0.00 (0/12) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated

@ 2/26/2008 07:42 Appendix B -Page 8 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Environmental Radiological Monitoring Program Summary Facility:

Catawba Nuclear Station Location:

York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2007 to 31-DEC-2007 S 0 0 0 0 0 0 S S 0 0 0 S 0 0 0 0 0 0 0 0 S 0 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone All Indicator Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Meao.Meas.Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Food Products NO CONTROL (pCi/kg-wet)

LOCATION CS-134 8 60 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 8 80 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 1-131 8 60 0.00 (018) 0.00 (0/8) 0.00(0/0) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated

@ 2/26/2008 07:43 Appendix B -Page 9 Environmental Radiological Monitoring Program Summary Facility:

Catawba Nuclear Station Location:

York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2007 to 31-DEC-2007 No. of Non-Medium or Type and Total Lower Location with Highest Co.trolNone All Indicator Control Routine Pathway Number Limit of Locations Annual Mean Location Report Sampled of Detection Name, Distance, DirectionMeas.

Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Fish 216 (pCi/kg-wet)

(4.19 mi NNE)CO-58 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 -0.00 0.00 (0/6) 0.00 -0.00 CO-60 12 130 0.00 (0/6) 0.00 -0.00 0.00 (0/6) 0 0.00 -0.00 0.00 (0/6) 0.00 -0.00 CS-134 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 12 150 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 FE-59 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 MN-54 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 ZN-65 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 S 0 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 Report Generated

@ 2/26/2008 07:44 Appendix B -Page 10 Environmental Radiological Monitoring Program Summary Facility:

Catawba Nuclear Station Location:

York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2007 to 31-DEC-2007 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.Unit of Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Shoreline 215 Sediment (4.21 mi NNE)(pCi/kg-dry)

MN-54 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2)0.00 -0.00 0.00 -0.00 0.00 -0.00 CO-58 6 0 87.7 (1/4) 208-IS 87.7 (1/2) 0.00 (0/2) 0 87.7 -87.7 (0.45 mi S) 87.7 -87.7 0.00 -0.00 CO-60 6 0 94.6 (1/4) 208-IS 94.6 (1/2) 0.00 (0/2) 0 94.6 -94.6 (0.45 mi S) 94.6 -94.6 0.00 -0.00 CS-1 34 6 150 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 CS-137 6 180 61.3(1/4) 208-IS 61.3 (1/2) 0.00(0/2) 0 61.3-61.3 (0.45 mi S) 61.3-61.3 0.00-0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated

@ 2/26/2008 07:48 Appendix B -Page 11 Environmental Radiological Monitoring Program Summary Facility:

Catawba Nuclear Station Location:

York County, South Carolina Docket No. 50-413,414 Report Period: 01-JAN-2007 to 31-DEC-2007 Type and No. of Non-Medium or Total Lower Al Indicator Location with Highest Control Routine Paha Smld ubr Limit of AlndctrAnnual MeanLoainRpr Pathway Sampled Number Detection Locations Name, Distance.

Direction Location Report of Meas.Unit of Measurement Analyses (LLD) Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

U Performed Range Code Range Range Direct Radiation 217 (10.3 mi SSE)TLD 247 (7.33 mi ESE)(mR/standard quarter) 251 (9.72 mi WNW)162 0.00E+00 19.3 (151/151) 235 26.3(4/4) 14.8 (11/11) 0 11.6- 29.1 (4.07 mi ESE) 23.7-29.1 11.2-20.3 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated

@ 4/t/2008 09:37 Appendix B -Page 12 0 0 0 0 S S 0 0 0 0 S S S 0 0 0 0 0 S 0 0 0 0 0 S 0 S S 0 0 S 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES Appendix C -Page I APPENDIX C CATAWBA NUCLEAR STATION SAMPLING DEVIATIONS

& UNAVAILABLE ANALYSES DEVIATION

& UNAVAILABLE REASON CODES BF Blown Fuse P0 Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair 1W Inclement Weather SL Sample Loss/Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Torn Filter P1 Power Interrupt VN Vandalism PM Preventive Maintenance CN Construction C.1 SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Power outage to sampling equipment due to tripped breaker. Breaker was reset and 200 7/24 -7/31/2007 7/24 -7/27/2007 P0 normal sampling resumed.Power outage to sampling equipment due to tripped breaker. Breaker was reset and 258 8/28 -9/5/2007 8/28 -8/28/2007 P0 normal sampling resumed.Surface Water Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Reservoir pump inoperative at time of collection.

Work request 41322 written.Work completed and normal sampling 215 1/16 -2/13/2007 1/18 -2/13/2007 PS resumed 1/18/2007.

Reservoir pump inoperative at time of collection.

Work request 43820 written.Intake line was repaired and pump was replaced.

Normal sampling resumed 208 3/13 -4/10/2007 3/13 -4/10/2007 PS 4/12/2007.

PIP C-07-01721 written.Reservoir pump inoperative at time of scheduled 4/10/2007 collection.

Work request 43820 written. Intake line was repaired and pump was replaced.

Normal sampling resumed 4/12/2007.

PIP 208 4/10 -5/8/2007 14/12 -5/8/2007 LC C-07-01721 written.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Appendix C -Page 2 0 S 0 0 0 0 0 0 S 0 S 0 0 0 0 0 0 S 0 0 0 0 0 C.2 UNAVAILABLE ANALYSES TLD Scheduled Reason Location Collection Dates Code Corrective Action 249 12/13 -3/14/2007 OT TLD missing. 2 nd quarter 2007 TLD placed in field.247 9/12 -12/12/2007 VN TLD missing. 1St quarter 2008 TLD placed in field.Appendix C -Page 3 S 0 0 0 0 0 0 0 S 0 0 0 0 0 0 S 0 0 0 0 S 0 0 0 0 APPENDIX D ANALYTICAL DEVIATIONS No Analytical deviations were incurred for the 2007 Radiological Environmental Monitoring Program Appendix D -Page I S 0 0 0 0 0 0 0 S 0 S 0 0 0 0 0 S 0 0 0 0 0 APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 2007. Appendix E is located separately from 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.Appendix E -Page I