Text

Annual Radiological Environmental Operating Report
	ML101400132
Person / Time
Site:	Catawba
Issue date:	05/13/2010
From:	Morris J; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML101400132 (95)
	v • d • e

JAMES R. MORRIS, VICE PRESIDENT kDuke WEnergy Duke Energy Carolinas,LLC Catawba Nuclear Station / CN01 VP Carolinas 4800 Concord Road York, SC 29745 803-831-4251 803-831-3221 fax May 13, 2010 U.S. Nuclear Regulatory Commission Attn: 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 2009 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 2009 Annual Radiological Environmental Operating Report. This report covers operation of Catawba Units 1 and 2 during the 2009 calendar year.

Any questions concerning this report should be directed to Toni Pasour at (803) 701-3566.

Sincer Attachment www. duke-energy. corn

R U.S. Nuclear Regulatory Commission 2009 Annual Radiological Environmental Operating Report May 13, 2010 Page 2 xc (with attachment):

L.A. Reyes Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. H. Thompson, NRR Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop 8 G9A Washington, D.C. 20555 G. A. Hutto, Ill, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station Russell Keown, Supervisor Analytical & Radiological Environmental Services Division 2600 Bull Street Columbia, SC 29201 803-896-0856/KEOWNRHadhec.sc.qov Sandra Flemming, Director Analytical & Radiological Environmental Services Division 8231 Parklane Road Columbia, SC 29223 803-896-3890/FLEMMISA(cdhec.sc.gov Susan E. Jenkins, Manager Radioactive & Infectious Waste Management Division of Waste Management S.C. Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 803-896-4271/JENKINSE(adhec.sc.qov Tom Knight Contamination Mitigation Section Bureau of Land and Waste Management S.C. Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201

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S Annual S Radiological Environmental S Operating Report S 2009 S

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0 ANNUAL RADIOLOGICAL 0 ENVIRONMENTAL OPERATING REPORT 0

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TABLE OF CONTENTS 0 1.0 Executive Summary 1-1 2.0 Introduction 2-1 2.1 Site Description and Sample Locations 2-1 2.2 Scope and Requirements of the REMP 2-1 2.3 Statistical and Calculational Methodology . 2-2 2.3.1 Estimation of the Mean Value . 2-2 2.3.2 Lower Level of Detection and Minimum Detectable Activity 2-3 2.3.3 Trend Identification. 2-3 3.0 Interpretation of Results . 3-1 3.1 Airborne Radioiodine and Particulates 3-2 3.2 Drinking Water. 3-5 3.3 Surface Water 3-7 3.4 Ground Water 3-9 3.5 Milk. 3-10 3.6 Broadleaf Vegetation. 3-11 3.7 Food Products 3-13 3.8 Fish. 3-14 3.9 Shoreline Sediment 3-17 3.10 Direct Gamma Radiation 3-20 0 3.11 Land Use Census 3-22 4.0 Evaluation of Dose 4-1 4.1 Dose from Environmental Measurements 4-1 4.2 Estimated Dose from Releases . 4-1 4.3 Comparison of Doses. 4-2 5.0 Quality Assurance 5-1 5.1 Sample Collection 5-1 5.2 Sample Analysis 5-1 5.3 Dosimetry Analysis 5-1 5.4 Laboratory Equipment Quality Assurance 5-1 5.4.1 Daily Quality Control 5-1 5.4.2 Calibration Verification 5-1 5.4.3 Batch Processing 5-2 5.5 Duke Energy Intercomparison Program 5-2 5.6 ERA Proficiency Testing . 5-2 5.7 Duke Energy Audits . 5-2 5.8 U.S. Nuclear Regulatory Commission Inspections 5-2 5.9 State of South Carolina Intercomparison Program 5-2 5.10 TLD Intercomparison Program . 5-3 5.10.1 Nuclear Technology Services Intercomparison Program 5-3 5.10.2 Internal Crosscheck (Duke Energy). 5-3

6.0 6 References . . . . . . . . . . . . 6-1 S

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Appendices Appendix A:. Environmental Sampling and Analysis Procedures A-1..A I. Change of Sampling Procedures A-2 II. Description of Analysis Procedures A-2 Il. Change of Analysis Procedures . A-3 IV. Sampling and Analysis Procedures A-3 A. 1 Airborne Particulate and Radioiodine A-3 A.2 Drinking Water A-3 A.3 Surface Water A-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 (LD) A-5 A. 11 Annual Land Use Census A-5 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 Milk. Water Ground B-6 B-7 Broadleaf Vegetation B-8 Food Products . B-9 Fish .B-10 Shoreline Sediment B- 1I 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-1 Appendix E: Radiological Environmental Monitoring Program Results E-i 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 3.1 Concentration of Gross Beta in Air Particulate 3-2 3.2 Concentration of Tritium in Drinking Water 3-6 3.3 Concentration of Tritium in Surface Water. 3-8 3.6 Concentration of Cs-137 in Broadleaf Vegetation 3-11 0 3.8-1 Concentration of Co-58 in Fish . 3-15 3.8-2 Concentration of Co-60 in Fish . 3-15 3.9-1 Concentration of Co-58 in Shoreline Sediment 3-17 3.9-2 Concentration of Co-60 in Shoreline Sediment 3-18 3.10 Direct Gamma Radiation (TLD) Results 3-20 3.11 2009 Land Use Census Map 3-23 0

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0 LIST OF TABLES 0 2.1-A Radiological Monitoring Program Sampling Locations 2-6 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites) 2-7 0 2.2-A Reporting Levels for Radioactivity Concentrations in 0 Environmental Samples 2-8 2.2-B REMP Analysis Frequency 2-8 2.2-C Maximum Values for the Lower Limits of Detection . 2-9 0 3.1-A Mean Concentration of Gross Beta in Air Particulate . 3-3 3.1-B Mean Concentration of Air Radioiodine (1-131) . 3-4 0 3.2 3.3 Mean Concentrations of Radionuclides in Drinking Water Mean Concentrations of Radionuclides in Surface Water 3-6 3-8 3.5 Mean Concentration of Radionuclides in Milk 3-10 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation 3-12 0 3.7 Mean Concentration of Radionuclides in Food Products Mean Concentrations of Radionuclides in Fish 3-13 3.8 3-16 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment 3-19 0 3.10 Direct Gamma Radiation (TLD) Results 3-21 0 3.11 Land Use Census Results . 3-22 4.1-A 2009 Environmental and Effluent Dose Comparison 4-3 0 4.1-B Maximum Individual Dose for 2009 based on Environmental 0 Measurements for Catawba Nuclear Station 4-6 5.0-A 2009 Cross-Check Results for EnRad Laboratories 5-4 0 5.0-B 2009 Environmental Resource Associates QuikTM Response Program 5-9 5.0-C 2009 Environmental Dosimeter Cross-Check Results . 5-11 0

LIST OF ACRONYMS USED IN THIS TEXT (in alphabeticalorder) 0 BW BiWeekly C Control CNS Catawba Nuclear Station 0 DEHNR Department of Environmental Health and Natural Resources DHEC Department of Health and Environmental Control 0 EPA ERA Environmental Protection Agency Environmental Resource Associates GI-LLI Gastrointestinal - Lower Large Intestine GPS Global Positioning System 0 LLD Lower Limit of Detection M Monthly S MDA Minimum Detectable Activity MOA Memorandum of Agreement 0 mrem NIST Millirem National Institute of Standards and Technology 0 NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual pCi/kg picocurie per kilogram pCi/I 0 pCi/m3 picocurie per liter 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 jiCi/ml microcurie per milliliter UFSAR Updated Final Safety Analysis Report W Weekly iii

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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 2009.

Included are the identification of sampling 0locations, descriptions of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and pre-operational environmental data, comparisons of doses calculated from environmental measurements and effluent data, analysis of trends in environmental radiological data as potentially affected by station operations, and a summary of environmental radiological sampling results. Quality assurance practices, sampling deviations, unavailable samples, and program changes are also discussed.

SSampling 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 eighty-eight samples were analyzed comprising 1,197 test results in order to compile data for the 2009 report. Based on the annual land use census, the current number of sampling sites for Catawba Nuclear Station is

sufficient.

S Concentrations observed in the environment in 2009 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of data showed Sthat 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

introduced into the environment by plant operations. The total body dose estimated to the 5maximum exposed member of the public as calculated by environmental sampling data,

excluding TLD results, was 2.01E-01 mrem for 2009. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or S the environment.

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2.0 INTRODUCTION

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2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS 0

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 0employs a pressurized water reactor nuclear steam supply system furnished by Westinghouse 0Electric 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.

SCondenser 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 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.

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

a 10 mile radius of CNS.

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2.2 SCOPE AND REQUIREMENTS OF THE REMP 0

5An 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 0determine whether increases in environmental levels are attributable to the station. The 0operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.

0This monitoring program is based on NRC guidance as reflected in the Selected Licensee 5Commitments 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 0projected and anticipated radionuclide concentrations in the environment and related exposures 5from releases of radionuclides from Catawba Nuclear Station. This program satisfies the

requirements of Section IV.B.2 of Appendix I to 10CFR50 and provides surveillance of all appropriate critical exposure pathways to man and protects vital interests of the company, 0

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public and state and federal agencies concerned with the environment. 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.

0 The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified and that modifications to the REMP are made if required by changes in land use. This census satisfies 0 the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 0 3.11.

Participation in an interlaboratory comparison program as required by Selected Licensee Commitments provides for independent checks on the precision and accuracy of measurements 0 of radioactive material in REMP sample matrices. Such checks are performed as part of the S quality assurance program for environmental monitoring in order to demonstrate that the results 0 are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A summary of the results obtained as part of this comparison program are in Section 5 of this annual report.

2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY S

2.3.1 ESTIMATION OF THE MEAN VALUE 0 0

There was one (1) basic statistical calculation performed on the raw data resulting from 5 the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium.

The mean is a widely used statistic. This value was used in the reduction of the data 0 generated by the sampling and analysis of the various media in the Radiological 0 Environmental Monitoring Program. "Net activity (or concentration)" is the activity (or 5 concentration) determined to be present in the sample. No "Minimum Detectable Activity", "Lower Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of the mean. The following equation was 0 used to estimate the mean (reference 6.8): 0 Lx, N

O X -- iN O Where: O O

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

Xi = net activity (or concentration) for sample i. 0 S

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2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE ACTIVITY

The Lower Level of Detection (LLD), and Minimum Detectable Activity (MDA) are

used throughout the 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%

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 Sbetween sample collection and counting. The "required" LLD's for each sample 0medium and selected radionuclides are given in the Selected Licensee Commitments

and are listed in Table 2.2-C.

MDA - The MDA is the net counting rate (sample after subtraction of background) that 0must be surpassed before a sample is considered to contain a scientifically measurable 0amount of a radioactive material exceeding background amounts. The MDA is calculated using a sample background and may be thought of as an "actual" LLD for a particular sample measurement.

2.3.3 TREND IDENTIFICATION S

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

Visual inspection of tabular or graphical presentations of data (including preoperational) is used to determine if a trend exists. A decrease in a particular radionuclide's 0concentration 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 0influencing the concentration.

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

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

Legend

TLD Locations A All Other Locations

" Public Roads

,,*.," State Line Water Approdmate location of features shown

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S 0.25 Oviles Projection NCSP NAD27 Section 2 - Page 4

..e.e..BBSSBOOOBOSBBOOSBSOOBOBBSBOBBOBBBBBB

00t000000900000000000*00000000000Figure02.1-Figure 2.1-2 Catawba Nuclear Station Sampling Locations Map (Ten Mile Radius)

Legend

TLD Locations SAll Other Locations

/ Public Roads Rail Roads

.,,, County Boundary Incorporated Areas Water Approidmate location of features shown 0 1 2 3iles Projedion NCSP NAD27 Section 2 - Page 5

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TABLE 2.1-A 0 CATAWBA RADIOLOGICAL MONITORING PROGRAM 0 SAMPLING LOCATIONS 0 0

Table 2. 1-B Codes 0

W Weekly SM Semimonthly 0 BW BiWeekly Q Quarterly M Monthly I SA Semiannually 0 C Control 0 0

Site Location Description* Air Rad. & Surface Drinking Shoreline Food Fish Milk Broad Ground Part. Water Water Sediment Products Leaf Water

(a) Veg. (h) 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 0 216C Hwy 49 Bridge (4.19 mi NNE) SA 218 C Belmont Water Supply (13.5 mi NNE) M 0 221 C 222 Dairy (14.5 mi NW)

Site Boundary (0.70 mi N)

SM M

0 226 252 Site Boundary (0.48 mi S)

Residence (0.64 mi SW) _____Q M 0 253 Irrigated Gardens (1.90 mi SSE) M(a) 0 254 Residence (0.82 mi N) Q 258 C Fairhope Road (9.84 mi W) W M 0

0 (a) During Harvest Season (b) When Available 0

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

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0 CATAWBA RADIOLOGICAL MONITORING PROGRAM 0 SAMPLING LOCATIONS (TLD SITES) 0 Site Location* Distance Sector Site Location* Distance Sector 0

S 200 SITE BOUNDARY 0.63 miles NNE 234 WACHOVIA BANK 4.50 miles E 0 201 SITE BOUNDARY 0.53 miles NE 235 LAKE WYLIE DAM SC WILDLIFE 4.07 miles ESE 0 203 SITE BOUNDARY 0.38 miles ESE 236 FEDERATION OFFICE TWIN LAKES ROAD AND 4.25 miles SE 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 S 206 SITE BOUNDARY 0.67 miles WNW 239 CARTER LUMBER 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 0 217 C ROCK HILL AIR SITE 10.3 miles SSE 242 TRANSMISSION TOWER ON PARAHAM ROAD 4.56 miles W 222 SITE BOUNDARY 0.71 miles N 243 KINGSBERRY ROAD 4.39 miles WNW BETHEL 0 223 SITE BOUNDARY 0.57 miles E 244 ELEMENTARY SCHOOL CROWDERS CREEK 4.02 miles NW 225 SITE BOUNDARY 0.68 miles SE 245 BOAT LANDING 4.01 miles NNW CAROWINDS S 226 SITE BOUNDARY 0.48 miles S 246 SI GUARD HOUSE 7.87 miles ENE S 227 SITE BOUNDARY 0.52 miles WSW 247 C FORT MILL 7.33 miles ESE 0 228 SITE BOUNDARY 0.61 miles W 248 SI PIEDMONT MEDICAL CENTER 6.54 miles S 0 229 SITE BOUNDARY 0.84 miles NW 249 SI YORK COUNTY 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 0

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 0 258 FAIRHOPE ROAD 9.84 miles W C = Control S 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.

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0 TABLE 2.2-A 0

0 REPORTING LEVELS FOR RADIOACTIVITY 0 CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 0 Analysis Water Air Particulates Fish Milk Food Products 0

(pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) (pCi/kg-wet)

(pCi/m 3)

H-3 20,000_a)'__) 0 Mn-54 1,000 30,000 Fe-59 400 10,000 0 Co-58 1,000 30,000 Co-60 300 10,000 0 Zn-65 300 20,000 0 Zr-Nb-95 400 1-131 2 0.9 3 100 0

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

(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 0

TABLE 2.2-B 0

0 REMP ANALYSIS FREQUENCY 0

Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic 1-131 Beta 0

Air Radioiodine Weekly X Air Particulate Weekly X X 0

Direct Radiation Quarterly X Surface Monthly Composite X 0 Water Quarterly Composite X Drinking Monthly Composite X (a) X 0 Water Quarterly Composite X Ground Water Quarterly X X 0 Shoreline Sediment Semiannually X Milk Semimonthly X X 0 Fish Semiannually X Broadleaf Vegetation Monthly(b) X S Food Products Monthly(b) X 0

(a) Low-level 1-131 analysis will be performed if the dose calculated for the consumption of drinking water is

> 1 mrem per year. An LLD of 1 pCi!liter will be required for this analysis.

(b) When Available Section 2 - Page 8

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MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION 0

Analysis Water Air Particulates Fish Milk Food Products Sediment (pCilliter) or Gases (pCi/kg-wet) (pCi/liter) (pCi/kg-wet) (pCi/kg-dry)

(pCi/m 3) 0 Gross Beta 4 0.01 S H-3 2000 (a)

Mn-54 15 130 0 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 0 Zr-Nb-95 15 1-131 0.07 1 .60 0 1 (b)

Cs-134 15 0.05 130 15 60 150 0 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 0

0 (a) 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.

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3.0 INTERPRETATION OF RESULTS

Review of all 2009 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 2009 was compared to preoperational 0and 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 2009. Summary tables containing 2009 information required by Technical

Specification Administrative Control 5.6.2 are located in Appendix B.

Evaluation 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 0plant operation, but not required for reporting, are trended.

0 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 2009 0maximum percentages of reporting levels were well below the 100% action level. The highest

value noted during 2009 was 3.53% for Co-60 in surface water.

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

P these radionuclides are the result of CNS liquid effluents which contained the radionuclides.

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During 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 0 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 2009 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 2009 data presented in this section supports the conclusion that there were no 0significant changes in environmental sample radionuclide concentrations of samples collected and analyzed from CNS site and surrounding areas that were attributable to plant operations.

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3.1 AIRBORNE RADIOIODINE AND PARTICULATES 0

In 2009, 257 radioiodine and particulate samples were analyzed, 206 from four indicator 0 locations and 51 at the control location. Particulate samples were analyzed weekly for gamma and gross beta. Radioiodine samples received a weekly gamma analysis.

S Figure 3.1 shows individual sample gross beta results for the indicator location with highest annual mean and the control location samples during 2009. The two sample locations' results S are similar in concentration and have varied negligibly since preoperational periods.

There were no detectable gamma emitters identified for particulate filters analyzed during 2009. Table 3.1-A shows the highest indicator 0

annual mean and control location annual mean for gross beta in air particulate.

0 There was no detectable 1-131 in air radioiodine samples analyzed in 2009. Table 3.1-B shows the highest indicator annual mean S and control location annual mean for 1-131 since 1984 (preoperational period). 0 K-40 and Be-7 that occur naturally were routinely detected in charcoal cartridges collected S

during the year. Cs-137 detection on the charcoal cartridge was determined in 1990 to be an 0 active constituent of the charcoal. A similar study was performed in 2001 again yielding 0 this conclusion. Therefore, any Cs-137 activities were not used in any dose calculations in 0 Section 4.0 of this report.

Figure 3.1 3

pCi/m Concentration of Gross Beta in Air Particulate 1.OOE-01 9.OOE-02 8OOE-02 7.00E-02 6.00E-02 5.00E-02 I_ __

4.OOE-02 _____ __________

3.OOE-02 2.OOE-02 1.OO00E-02 OMOE+O0 1984 1987 1990 1993 1996 1999 2002 2005 2008 1 --W-- Indicator Location --W- Control Location There is no reportinglevelfor gross beta in airparticulate Section 3 - Page 2

Table 3.1-A Mean Concentration of Gross Beta in Air Particulate 3

Year 3

Indicator Location (pCi/m ) Control Location (pCi/m )

0 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 2.11E-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 0 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 0 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 2007 1.88E-2 1.86E-2 2008 1.80E-2 1.90E-2

Average (1999 - 2008) 1.84E-2 1.73E-2 2009 1.78E-2 1.72E-2 0

0 0

~~Section 3 -Page 3 0

0

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

Year Indicator Location (pCi/m3 ) Control Location (pCi/m 3) 1984 1.30E-3 1.46E-2 1985 4.75E-3 2.38E-2 1986 1.43E-2 1.02E-2 0 1987 1.38E-2 0.OOEO 1988 0.OOEO 0.OOEO 1989 0.00E0 0.00E0 1990 0.OOEO 0.00E0 1991 0.OOEO 0.00E0 1992 0.OOEO 0.OOEO 1993 0.00E0 0.00E0 1994 0.00E0 0.OOEO S 1995 0.OOEO 0.00E0 1996 0.00E0 O.OOE0 1997 0.00E0 0.00E0 1998 0.OOEO 0.OOEO 1999 0.OOEO 0.00E0 2000 0.OOEO 0.OOEO 2001 0.OOEO 0.OOEO 2002 0.OOEO 0.OOEO 2003 0.00E0 0.OOEO 5 2004 0.OOEO 0.OOEO 2005 0.00E0 0.OOEO 2006 0.OOEO 0.OOEO 2007 0.OOEO 0.OOEO 2008 0.OOEO 0.OOEO 0 2009 0.OOEO 0.OOEO 5 O.OOEO = no detectable measurements S

0 S

S S

S 0

S S

S 0

0 0

S Section 3 -Page 4 S 0

S

0 0

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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 0indicator location was sampled, along with one control location.

N hNo gamma emitting radionuclides were identified in 2009 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 2.07 pCi/l in 2009 and the control location concentration was 1.99 pCi/1. The 2008 indicator mean was 2.81 pCi/l. The table shows that current gross beta levels are not statistically different from preoperational concentrations.

0

Tritium was detected in the four indicator samples and the four control samples during 2009.

The mean indicator tritium concentration for 2009 was 634 pCi/l, 3.17% of reporting level.

The mean control tritium concentration for 2009 was 681 pCi/l, 3.41% of reporting level.

Figure 3.2 and Table 3.2 display the highest indicator and control location annual mean 0concentrations for tritium since 1984.

0 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. Tritium in drinking water indicator samples was lower in 2009 than in previous years. During 2009, tritium released from Catawba was lower than the previous year due to a plant modification that was designed to capture Boron from the primary system. This modification is addressed in reference 6.14. Tritium was identified at the nearest drinking water location but was lower than tritium in the control location.

0Because of this, no dose from drinking water was attributed to releases from Catawba.

0 The dose for consumption of water was less than one mrem per year, historically and for 2009; therefore low-level iodine analysis is not required.

S 0

0 0

0

~Section 3 -Page 5 0

0

Figure 3.2 pCi/liter Concentration of Tritium in Drinking Water 5000 4500 4000 6I 3500 0I 3000 2500 0I 2000 0I 1500 6I 1000 SI 500 6I 01 0I 1984 1987 1990 1993 1996 1999 2002 2005 2008

--R- Indicator Location --* Control Location - 20% Reporting Level 6I 6I Table 3.2 Mean Concentration of Radionuclides in Drinking Water 6I YEAR Indicator Gross Beta (pCi/I)

Control Indicator Tritium (pCi/I)

Control 6I Location Location Location Location 6I 1984 1985 4.72 2.70 1.83 2.24 3.1OE-2 4.13E2 3.1OE-2 4.00E2 6I 1986 3.11 2.26 7.23E2 7.33E2 6I 1987 1988 3.10 3.60 2.40 2.60 7.80E2 6.64E2 4.80E2 0.OOEO 6I 1989 3.60 2.90 8.91 E2 5.72E2 6I 1990 1991 4.50 3.70 3.20 2.20 7.03E2 7.04E2 0.OOEO 0.OOEO 6I 1992 3.20 2.40 7.65E2 5.38E2 SI 1993 3.50 2.50 7.06E2 0.OOEO 1994 3.30 2.70 0.00E0 0.OOEO 0I 1995 1996 4.80 3.08 4.50 3.14 4.28E2 3.71 E2 2.21 E2 3.27E2 6I 1997 3.74 3.15 3.54E2 2.28E2 6I 1998 1999 2.51 3.55 2.44 2.48 5.07E2 6.71 E2 1.83E2 2.70E2 6I 2000 3.04 2.27 5.87E2 3.26E2 0I 2001 2002 3.49 3.44 2.30 2.36 8.66E2 1.22E3 4.50E2 4.11 E2 6I 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 2008 2.81 2.16 1.25E3 9.16E2 2009 2.07 1.99 6.34E2 6.81 E2 0.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 6

0 0

0

3.3 SURFACE WATER 0

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 0indicator locations and one control location were sampled. One indicator location (208) is

located near the liquid effluent discharge point.

0

All 2009 indicator location samples contained tritium with an average concentration of 2292 pCi/l. Indicator Location 208 (Discharge Canal) showed a range of activities from 3530 to

4420 pCi/1 which had the highest mean concentration of 3930 pCi/l. Tritium was detected in

all four control samples during 2009 with an average concentration of 529 pCi/l.

0 Gamma spectroscopy analysis detected Co-58 in four indicator samples and Co-60 in one indicator sample during 2009. Co-58 was detected at indicator location 208 and showed a range of Co-58 activities from 5.43 pCi/1 to 18.7 pCi/l with an average concentration of 9.40

pCi/1 which represents 0.94% of the reporting level. Co-60 was detected at location 208 at

10.6 pCi/l which represents 3.53% of the reporting level. An investigation of these results

was performed to document the review of sample collection and analysis methods and the review of effluent releases (reference 6.15). Co-58 and Co-60 were released in effluents from

Catawba in 2009. Co-58 and Co-60 were also identified in a REMP sample in 2008. No 0problems were identified with the collection or analysis process. Gamma spectroscopy

analysis has not detected any other activity in surface water samples since 1993. Table 3.3 summarizes the indicator annual means of radionuclides detected since the change in the gamma spectroscopy analysis system in 1987. Visual inspection of the tabular data did not Sreveal any increasing trends.

0

Figure 3.3 displays the indicator and control annual means for tritium since 1984. Table 3.3 lists indicator annual means.

0The 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. Tritium in surface water indicator samples was lower in 2009 than in previous years. During 2009, tritium released from Catawba was lower than the previous year due to a plant modification that was designed to capture Boron from the

- primary system. This modification is addressed in reference 6.14.

S 0

0 0

0 O Section 3 - Page 7 0

0

0 6

0 0

Figure 3.3 0 pCi/liter Concentration of Tritium in Surface Water S 30000 S

25000 S 6

20000 - 0 15000 10000 _ _ _ S S

5000 - - __ - _____ ___ __

0 S

1984 1987 1990 1993 1996 1999 2002 2005 2008 6 1--- Indicator Location --*- Control Location 0

There is no reportinglevel for tritium in surface water, however, if no drinking waterpathway exists, a value of30,000 pCi/l may be used A 6 drinkingwaterpathway existsfor CatawbaNuclear Station, so this limit does not applyfor surface water. See section 3.2for drinkingwater results. 6 Table 3.3 Mean Concentrations of Radionuclides in Surface Water (pCi/l) 6 YEAR Co-58 Co-60 Nb-95 Cs-137 H-3 Indicator H-3 Control 6 1984 1985 4.59E-1 3.46E0 5.71E-1 4.83E-2 6.48E-1 2.70E0 9.08E-1 8.19E-1 3.35E2 1.19E3 3.18E2 5.05E2 6

1986 3.10E-1 -4.12E-2 2.05E0 4.85E-1 2.34E3 5.05E2 0 1987 1988 0.OOEO 9.20E0 3.10E0 0.OOEO 4.30E0 0.OOEO 9.90E0 0.OOEO 4.17E3 6.03E3 6.20E2 6.07E2 S

1989 0.OOEO 0.00E0 0.OOEO 0.OOEO 5.27E3 0.OOEO S 1990 6.50E0 0.OOEO 0.OOEO 0.00E0 3.98E3 7.73E2 1991 1992 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.00E0 0.00E0 4.87E3 6.91 E3 0.00E0 6.64E2 0

1993 4.70E0 1.80E0 0.OOEO 0.00E0 5.98E3 0.00E0 0 1994 1995 0.00E0 0.00E0 0.00E0 0.OOEO 0.00E0 0.OOEO 0.00E0 0.00E0 8.42E3 5.13E3 0.OOEO 2.89E2 0

1996 0.OOEO 0.OOEO 0.00E0 0.OOEO 7.36E3 2.61 E2 1997 0.OOEO 0.00E0 0.OOEO 0.OOEO 7.77E3 2.20E2 1998 1999 0.OOEO 0.00E0 0.00E0 0.00E0 0.OOEO 0.00E0 0.OOEO 0.00E0 6.61E3 8.13E3 0.00E0 2.41 E2 0

2000 0.OOEO 0.OOEO 0.OOEO 0.OOEO 7.19E3 2.56E2 S 2001 2002 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 0.OOEO 0.00E0 0.OOEO 7.13E3 1.00E4 3.28E2 3.80E2 6

2003 2004 0.00E0 0.00E0 0.OOEO 0.00E0 0.00E0 0.OOEO 0.00E0 0.00E0 1.31E4 9.43E3 2.37E2 2.60E2 6

2005 0.OOEO 0.00E0 0.00E0 0.OOEO 1.40E4 3.78E2 S 2006 2007 0.OOEO 0.00E0 0.OOEO 0.OOEO 0.OOEO 0.00E0 0.OOEO 0.00E0 1.67E4 1.01E4 5.83E2 7.82E2 S

2008 6.80E0 1.16E 1 0.OOEO 0.00E0 6.02E3 6.31 E2 0 2009 0.OOEO no detectable measurements 9.40E0 1.06EI 0.OOEO 0.OOEO 3.93E3 5.29E2 0

1984 - 1986 mean based on all net activity S Section 3 - Page 8 S

0 0

0 3.4 GROUND WATER 0 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 2009.

0 There have been no radionuclides identified in ground water samples since 1988. Only 0 naturally occurring K-40 and Be-7 were noted.

0 0

Section 3 - Page 9

S 0

0 3.5 MILK A total of 26 milk samples was analyzed by gamma spectroscopy and low level iodine 0 during 2009. There was one control location sampled. No indicator dairies were identified by the 2009 land use census.

There were no gamma emitting radionuclides identified in milk during 2009. 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.

Table 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.

0 Table 3.5 Mean Concentration of Radionuclides in Milk YEAR Cs-137 Indicator (pCi/i) Cs-137 Control (pCi/i) 1984 2.95E0 2.98E0 1985 2.11EO 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 O.OOEO 1996 6.05E0 0.00E0 1997 0.OOEO O.O0EO 1998 0.00E0 0.00E0 1999 0.00E0 0.OOEO 2000 0.00E0 0.OOEO 2001 0.00E0 0.00E0 2002 0.00E0 0.OOEO 2003 0.00E0 0.00E0 2004 NO INDICATOR LOCATION 0.00E0 2005 NO INDICATOR LOCATION 0.00E0 2006 NO INDICATOR LOCATION 0.00E0 2007 NO INDICATOR LOCATION 0.00E0 2008 NO INDICATOR LOCATION 0.00130 2009 NO INDICATOR LOCATION 0.00E0 0.00E0 no detectable measurements 0 1984 - 1986 mean based on all net activity 0

Section 3 - Page 10

0 0

0 0 3.6 BROADLEAF VEGETATION 0 Gamma spectroscopy was performed on 60 broadleaf vegetation samples during 2009.

Four indicator locations and one control location were sampled.

S One of the forty-eight samples collected at indicator locations contained detectable 0 Cs-137 activity. Cs-137 was detected in one of the twelve samples collected at Location 0 201. The highest concentration detected at Location 201 was 42.5 pCi/kg which is 2.13%

of the reporting level. Cs-137 was not detected in any of the twelve control location 0 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 2009 show a stable trend for Cs-137 0 in vegetation.

0 No airborne Cs-137 has been released 0 from the plant since 1992. Cs-137 attributable to past nuclear weapons 0 testing is known to exist in many 0 environmental media at low and highly variable levels.

S 0 K-40 and Be-7 were observed in broadleaf vegetation samples.

0 Figure 3.6 0 pCi/kg Concentration of Cs-137 in Broadleaf Vegetation 0 1200 0 1000 0

0 800 600 ______ ______ _____

400 20 4 1984 1987 1990 1993 1996 1999 2002 2005 2008

-F - Indicator Location -Control Location - 50% Reporting Level I Section 3 - Page 11

S 0

0 0

Table 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation YEAR Cs-137 Indicator (pCi/kg) Cs-137 Control (pCi/kgý 1984 3.76E1 1.30El 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.OOEO 1993 1.13E2 3.20E1 1994 7.00El 0.OOEO 1995 3.60E1 0.OOEO 1996 2.23E2 6.22E1 1997 7.57E1 0.OOEO 1998 6.53E1 0.00E0 1999 1.08E2 0.OOEO 2000 1.04E2 0.OOEO 2001 3.76E1 0.OOEO 2002 7.02E1 0.OOEO 2003 4.96E1 2.40E1 2004 5.45E1 0.OOEO 2005 5.48E1 0.OOEO 2006 5.79E1 0.OOEO 2007 6.31El 0.OOEO 2008 4.44E1 0.OOEO 2009 4.25E1 0.OOEO O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity 5 0

0 0

S 0

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Section 3 -Page 12 0 0

0

0 0

O 3.7 FOOD PRODUCTS 0 Collection of food product samples 0 (crops) from an irrigated garden O began in 1989. The garden is located ?T on Lake Wylie downstream from CNS, Location 253. During the 2009 growing season, seven samples were collected and analyzed for gamma radionuclides. There is no O control location for this media type.

O Table 3.7 shows Cs-137 indicator location highest annual mean concentrations since 1989.

0

Table 3.7 Mean Concentration of Radionuclides in Food Products OYEAR Cs-137 Indicator (pCi/kg)

O1989 0.00E0 O1990 0.00E0 1991 0.00E0 1992 0.00E0 O1993 2.50E1 O1994 0.00E0 1995 0.00E0 O1996 0.00E0 O1997 0.00E0 1998 0.00E0 O1999 0.00E0 O2000 0.00E0

2001 0.OOEO 2002 0.OOEO O 2003 0.OOEO O 2004 0.OOEO 2005 0.OOEO

2006 0.OOEO

2007 0.OOEO 2008 0.OOEO O 2009 0.OOEO O.OOEO = no detectable measurements There is no control location for Food Products.

0 0

0 O ~Section 3 -Page 13 0

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0 0

3.8 FISH 0

Gamma spectroscopy was performed on 12 fish samples collected during 2009. One 0 downstream indicator location and one control location were sampled. 0 0

Co-58, Co-60, and Cs-137 are normally the predominant radionuclides identified in fish samples. There were no gamma emitting radionuclides identified in any indicator 0 location or control location fish samples during 2009. 0 0

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 0

the table. Overall, radionuclides have not 0 shown a significant trend or 0 accumulation. 0 K-40 was observed in fish samples 0

collected during 2009. 0 0

0 0

Section 3 - Page 14

0 0

0 Figure 3.8-1 0

pCi/kg Concentration of Co-58 in Fish 0 2000 0 1800 0 1600 -____

1400 0 1200 9799999 200 0 1000 0 800 ______ ____ _____

0 600 -_____

400 -___ -

200-0 -____ _____ _

1984 1987 1990 1993 1996 1999 2002 2005 2008 F -0I- IdctrLctoCotoLoainSReporting Lý1 0

0 0

Figure 3.8-2 S

pCi/kg Concentration of Co-60 in Fish 7O00 0

0 600 500 0

0 0

0 200 0 100 01~ -

1984 1987 1990 1993 1996 1999 2002 2005 2008

--- Indicator Location -*- Control Location - 5% Reporting Level Section 3 - Page 15

Table 3.8 Mean Concentrations of Radionuclides in Fish (pCi/kg)

Year Mn-54 Co-58 Co-60 Cs-134 Cs-137 Nb-95 Fe-59 Sb-122 Sb-125 0 1984 3.07E0 3.OOEO 6.11E-1 -5.32E0 1.83E0 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1985 7.68E-1 3.40E1 9.1IEO 3.22E0 1.28E1 5.07E0 0.OOEO 0.OOEO 0.OOEO 1986 2.01EI 1.86E2 4.01El 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 0.00E0 0.00E0 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 4.66E1 3.33E0 0.00E0 7.OOEO 9.25E0 1991 3.15E1 1.46E2 1.29E2 1.03El 4.60E1 7.90E-1 2.30E0 0.00E0 7.45E0 1992 1.34E1 9.02E1 6.20E1 1.27E1 4.61E1 0.OOEO 0.00E0 O.OOEO 0.OOEO 1993 2.14E1 3.58E2 1.21E2 2.73E0 2.56E1 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1994 1.91E0 4.75E1 1.81El 0.OOEO 1.75E1 0.OOEO 0.OOEO 0.OOEO 1.45E1 1995 5.65E1 8.90E2 2.66E2 0.00E0 6.77E1 1.38E1 0.00E0 0.OOEO 0.00E0 1996 0.00E0 5.95E1 6.68E1 0.OOEO 3.02E1 0.OOEO 0.OOEO 0.00E0 0.OOEO 1997 O.OOEO 4.93E1 9.88E0 0.00E0 2.74E1 0.OOEO 0.OOEO 0.00E0 0.00E0 1998 O.OOEO 6.44E1 2.86E1 0.OOEO 1.58E1 0.OOEO 0.OOEO 0.OOEO O.OOEO 1999 0.OOEO 3.12E1 2.71E1 0.00E0 1.87E1 0.00E0 0.00E0 0.00E0 0.00E0 2000 0.OOEO 2.13E2 2.69E2 0.00E0 1.52E1 0.OOEO 0.OOEO O.OOEO 0.OOEO 2001 0.OOEO 4.66E1 0.OOEO 0.00E0 2.08E1 0.OOEO 0.00E0 0.OOEO 0.OOEO 9 2002 0.OOEO 5.23E1 7.OOEI O.OOEO 1.73E1 0.OOEO 0.OOEO 0.OOEO 0.00E0 2003 0.OOEO 1.43E2 2.61El 0.OOEO 1.19El 0.00E0 0.00E0 O.00E0 0.OOEO 2004 4.92E1 1.81El 0.00E0 O.OOEO O.00E0 0.OOEO 0.OOEO 0.00E0 0.OOEO 2005 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.00E0 0.OOEO O.OOEO 0.OOEO 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.44E1 0.OOEO 0.OOEO 0.OOEO O.OOEO 2007 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2008 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.00E0 2009 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO

.O0E0 = no detectable measurements 0

0 0

0 Section 3 - Page 16 0 0

0

0 0

3.9 SHORELINE SEDIMENT 0

During 2009, a total of 6 shoreline sediment samples was analyzed, four from two 0 indicator locations and two from the control location.

0 Co-58 was identified in two samples and Co-60 was identified in one sample collected from indicator location 208-1S, which is closest to the plant's liquid effluent release 0 point. Cs-137 was identified in one sample collected from location 208-1S. 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.

0 0 The shoreline sediment location with the highest annual mean for all detectable radionuclides was location 208-1S. Co-58 was identified at location 208-1S with an 0 annual mean concentration of 110 pCi/kg. Co-60 was identified with an annual mean concentration of 104 pCi/kg. Cs-137 was identified with an annual mean concentration of 22.7 pCi/kg. Naturally occurring K-40 and Be-7 were also identified in samples from 0 this location.

0 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.

0 Figure 3.9-1 graphically depicts Co-58 annual mean concentrations. Figure 3.9-2 depicts 0 Co-60 annual mean concentrations.

0 Figure 3.9-1 0

0 pCi/kg Concentration of Co-58 in Shoreline Sediment 2000 0 1800 0 1600 1400 0

1200 1000 _____ _____ _ _

800 600 - -

400-__ _

200__

0 4fý

-*--- ~ ..-

1984 1987 1990 1993 1996 1999 2002 2005 2008 5--W-Indicator Location -- Control Location There is no reportinglevelfor Co-58 in Shoreline Sediment Section 3 - Page 17

S 0

0 S

Figure 3.9-2 S S

pC!/kgConcentration of Co-60 in Shoreline Sediment S 2000 S

1800 1600 -____

S 1400 S

S 1200 1000 _____

IN__________

S 800 ______ ______ _____

S 600 _________ _____

S 400 S S

S 1984 1987 1990 1993

- Indicator Location 1996 1999 2002

- Control Location 2005 2008 S

S There is no reportinglevel for Co-60 in Shoreline Sediment S

S S

S 0

S S

S Section 3 - Page 18 S S

S

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 1.03E0 4.40E0 -2.34E0 0.OOEO 0.OOEO 3.19E1 1.07E2 0.OOEO 0.OOEO 1985 -3.12E0 1.16E2 5.18E0 0.OOEO 0.OOEO 2.11E2 2.97E2 0.OOEO 0.OOEO 1986 1.09E2 3.79E2 2.05E2 0.OOEO 3.96E1 6.50E1 1.61E2 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 0.00E0 1.65E1 5.77E1 0.00E0 1.57E1 1990 5.39E1 2.08E2 1.77E2 0.OOEO 0.00E0 1.66E1 8.18E1 0.OOEO 7.15E0 1991 8.50E1 3.70E2 4.19E2 5.30E0 0.00E0 1.82E1 8.33E1 1.20E0 1.50El 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 0.00E0 0.OOEO 2.80E1 1.26E2 2.47E1 2.16E2 1994 4.93E1 7.98E2 5.73E2 0.00E0 0.OOEO 5.67E0 1.07E2 4.38E0 4.60E1 1995 1.02E2 1.33E3 8.65E2 1.13E2 0.00E0 0.OOEO 8.50E1 3.69E1 1.49E2 1996 8.73E1 3.39E2 5.81E2 0.00E0 0.00E0 0.00E0 8.30E1 0.00E0 1.96E2 1997 6.96E1 5.90E2 7.64E2 0.00E0 0.OOEO O.00E0 1.43E2 0.OOEO 1.76E2 1998 3.07EI 1.88E2 2.30E2 0.00E0 0.OOEO 0.00E0 7.11El 0.OOEO 0.OOEO 1999 7.28E1 2.29E2 4.39E2 0.OOEO 0.OOEO 0.00E0 9.42E1 0.OOEO 1.40E2

2000 0.OOEO 3.90E1 1.03E2 0.00E0 0.00E0 0.00E0 4.96E1 0.OOEO 0.OOEO 2001 3.86E1 8.27E1 3.29E2 0.OOEO 0.00E0 0.00E0 5.58E1 0.OOEO 0.OOEO 2002 3.51E1 2.41E2 2.22E2 0.OOEO 0.OOEO 0.OOEO 8.83E1 0.00E0 0.OOEO

2003 2.17E1 8.75E1 1.08E2 0.OOEO 0.OOEO 0.OOEO 2.69E1 0.00E0 0.00E0 2004 6.60E1 2.67E2 3.83E2 0.00E0 0.OOEO 0.OOEO 3.79E1 0.OOEO 0.OOEO 2005 0.00E0 1.61E2 1.41E2 0.OOEO O.00E0 0.OOEO 0.OOEO 0.00E0 O.00E0 2006 0.00E0 5.40E1 1.11E2 0.OOEO 0.OOEO 0.00E0 0.OOEO 0.00E0 0.00E0 2007 0.00E0 8.77EI 9.46E1 0.OOEO 0.OOEO 0.OOEO 6.13EI 0.OOEO 0.OOEO 2008 0.OOEO 1.48E2 6.24E1 0.OOEO 0.OOEO 0.OOEO 2.57E1 O.O0EO 0.OOEO

2009 0.00E0 1.10E2 1.04E2 O.O0EO 0.00E0 0.00E0 2.27E1 0.00E0 0.00E0 0 O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Negative values are calculated as zeroes S

S 0

S Seto -ae1 0

S

6I 6I 6I 6I 3.10 DIRECT GAMMA RADIATION 6I 6I In 2009, 162 TLDs were analyzed, 150 at indicator locations and 12 at control locations.

6I TLDs are collected and analyzed quarterly. 6I The highest annual mean exposure for an 6I indicator location was 95.6 milliroentgen. The 6I annual mean exposure for the control locations was 58.0 milliroentgen.

6I 6I Figure 3.10 and Table 3.10 show TLD inner 0I ring (site boundary), outer ring (4-5 miles), 6I and control location annual averages in milliroentgen per year. Preoperational data and rolling ten year operational data averages 6 are also given. As shown in the graph, inner ring, outer ring, and control data averages 0I historically compare closely. Inner and outer ring averages comprise a number of data 6I points with control averages representing only three locations. 0I The calculated total body dose (from gaseous effluents) for 2009 was 1.54E0 mrem, 6I which is 1.93% of the average inner ring TLD values. Therefore, it can be concluded that 6I discharges from the plant had very little impact upon the measured TLD values. SI 6I Figure 3.10 6I 0I mR/year Direct Gamma Radiation (TLD) Results 6I 250 0I 200 SI 6I 150 0 6

100 99890 9 1996 1999 2002 2005 2008 50 _____ ______ SI 6

1984 1987 1990 1993 1996 1999 2002 2005 2008 6I I A InnerRing --- Outer Ring --- Control 0i 0I There is no reportinglevel for Direct Radiation (TLD) 6I 0I 0

6I Section 3 - Page 20 6 6I

0 S

0 0

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 63.6 1997 82.4 71.9 57.4 1998 85.3 74.2 64.6 1999 80.0 68.1 57.8 2000 75.0 63.0 52.4 2001 81.0 70.5 55.2 S 2002 78.8 69.5 55.2 S 2003 81.7 72.6 56.0 2004 78.6 73.8 55..6 S 2005 79.8 75.2 57.7 S 2006 76.9 73.6 57.2 S 2007 2008 80.5 81.5 76.4 77.1 59.2 60.4 S Average (1999 - 2008) 79.4 72.0 56.7 S 2009 79.9 71.9 58.0 O

Preoperational Data S S S

S S

S Secteooerat-onageDat S

S

0 0

0 3.11 LAND USE CENSUS 0 0

The 2009 Annual Land Use Census was conducted July 15, and July 16, 2009 as required 0 by SLC 16.11-14. Table 3.11 summarizes census results. A map indicating identified 0 locations is shown in Figure 3.11. 0 During the 2009 census, no new residences, irrigated gardens (superior to existing 0

gardens) or milk locations were identified. The nearest residence is located in the NE 0 sector at 0.56 miles. No environmental program changes were required as a result of the 0 2009 land use census. 0 Table 3.11 Catawba 2009 Land Use Census Results 0 Table 3.11 Catawba 2009 and Use Census Results 0 0

Sector Distance Sector Distance 0 (Miles) (Miles) 0 Nearest Residence 0.63 Nearest Residence 0.63 N Nearest Garden (irrigated) 1.55 S Nearest Garden 0.80 0 Nearest Milk Animal - Nearest Milk Animal -

0 Nearest Residence 0.66 Nearest Residence 0.81 1.02 0

NNE Nearest Garden 4.39 SSW Nearest Garden Nearest Milk Animal - Nearest Milk Animal - 0 Nearest Residence 0.56 Nearest Residence 0.66 0 NE Nearest Garden Nearest Milk Animal 0.68 SW Nearest Garden Nearest Milk Animal 2.29 0

Nearest Residence 0.61 Nearest Residence 0.61 0

ENE Nearest Garden (irrigated) 0.61 WSW Nearest Garden 1.10 0 Nearest Milk Animal Nearest Milk Animal - -

0 Nearest Residence 0.65 Nearest Residence 0.68 3.51 W Nearest Garden 0.96 0

E Nearest Garden Nearest Milk Animal - Nearest Milk Animal - 0 Nearest Residence 0.84 Nearest Residence 1.10 0 WNW Nearest Garden 1.87 ESE Nearest Garden Nearest Milk Animal 3.70

- Nearest Milk Animal - 0 Nearest Residence 0.97 Nearest Residence 1.39 0 SE Nearest Garden (irrigated) 2.55 NW Nearest Garden Nearest Milk Animal 1.54 0

Nearest Milk Animal -

Nearest Residence 0.74 Nearest Residence 0.91 0

SSE Nearest Garden 1.64 NNW Nearest Garden 2.21 0 Nearest Milk Animal indicates no occurrences within the 5 mile radius

- Nearest Milk Animal -

0 0

Section 3 - Page 22 0

0 0

Figure 3.11 Section 3 - Page 23

4.0 EVALUATION OF DOSE

4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured 0concentrations of radionuclides in 2009 CNS REMP samples. The primary purpose of 0estimating doses based on sample results is to allow comparison to effluent program dose estimates.

Doses based on sample results were calculated using the methodology and data 0presented 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 were used in the

calculations. When the guide listed "NO DATA" as the dose factor for a given 0radionuclide and organ, a dose factor of zero was assumed.

0

Maximum dose estimates (Highest Annual Mean Concentration) based on 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.

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 not 0reported for surface water because sampled surface water is not considered to be a 0potable 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 enviroumental organ dose estimate for any single sample type (other than

direct radiation from gaseous effluents) collected during 2009 was 3.61E-1 mrem to the maximum exposed child bone from consuming broadleaf vegetation.

0 4.2 ESTIMATED DOSE FROM RELEASES

Throughout the year, dose estimates were calculated based on actual 2009 liquid and 0gaseous 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 0corresponding REMP-based dose estimates. Summaries of RETDAS dose calculations 0are reported in the Annual Radioactive Effluent Release Report (reference 6.6).

0 0

O ~Section 4.-Page 1 0

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

0 4.3 COMPARISON OF DOSES 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 effluent measurements and modeling of the environmental exposure pathways. This indicates 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 are conservative because they are based on a mean that includes only samples with a net positive activity versus a mean that includes all sample results (i.e. zero results are not included in the mean). Also, airborne tritium is not measured in environmental samples but is used to calculate effluent doses.

0 In calculations based on liquid release pathways, drinking water, fish, and shoreline sediment were the predominant dose pathways based on environmental and effluent data.

The maximum total organ dose based on 2009 environmental sample results was 7.OOE-3 mrem to the adult total body. The maximum total organ dose of 6.80E-2 mrem0 for liquid effluent-based estimates was to the adult GI-LLI.

In calculations based on gaseous release pathways, vegetation was the predominant dose pathway for effluent samples. The maximum total organ dose for gaseous effluent estimates was 1.54E0 mrem to the child's liver, total body, thyroid, kidney, lung, and GI-LLI. Vegetation was the predominant dose pathway for environmental samples. The maximum total organ dose for gaseous environmental estimates was 3.61E-1 mrem to the child bone.

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

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

0 0

0 Section 4 - Page 2 0 0

0

0 0

0 S TABLE 4.1-A Page 1 of 3 0 CATAWBA NUCLEAR STATION S 2009 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON 0

0 LIOUID RELEASE PATHWAY S

0 Environmental or Critical Critical Maximum Dose (3)

Effluent Data Age 1 Pathway (2) (mrem)

Skin Environmental Teen Shoreline Sediment 208 (0.45 mi S) 1.66E-03 Skin Effluent Teen Shoreline Sediment Discharge Pt. 9.40E-03 Bone Environmental - 0.OOE+00 Bone Effluent Teen Shoreline Sediment Discharge Pt. 1.49E-02 Liver Environmental Adult Fish 208 (0.45 mi S) 6.75E-03 Liver Effluent Child Drinking Water 7.30 mi SSE 5.38E-02 T. Body Environmental Adult Fish 208 (0.45 mi S) 6.75E-03 T. Body Effluent Child Drinking Water 7.30 mi SSE 4.74E-02 Thyroid Environmental Adult Fish 208 (0.45 mi S) 6.75E-03 0 Thyroid Effluent Child Drinking Water 7.30 mi SSE 4.45E-02 S Kidney Environmental Adult Fish 208 (0.45 mi S) 6.75E-03 0 Kidney Effluent Child Drinking Water 7.30 mi SSE 4.75E-02 0 Lung Environmental Adult Fish 208 (0.45 mi S) 6.75E-03 Lung Effluent Child Drinking Water 7.30 mi SSE 4.55E-02 0

0 GI-LLI Environmental Adult Fish 208 (0.45 mi S) 6.75E-03 0 GI-LLI Effluent Adult Fish 7.30 mi SSE 6.80E-02 0

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

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

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

Section 4 - Page 3

0 0

Page 2 of 3 GASEOUS RELEASE PATHWAY 0

0 0

IODINE, PARTICULATE, and TRITIUM 0

Critical Critical Maximum Dose (3) S Organ Environmental or Effluent Data Age (1) Pathway (2) Location (mrem)

Skin Environmental - 0.OOE+00 Skin Effluent -

Bone Environmental Child Vegetation 201 (0.53 mi NE) 3.61E-01 Bone Effluent -

Liver Environmental Child Vegetation 201 (0.53 mi NE) 3.46E-01 Liver Effluent Child Vegetation 0.68 mi NE 1.54E+00 T. Body Environmental Adult Vegetation 201 (0.53 mi NE) 1.94E-01 T. Body Effluent Child Vegetation 0.68 mi NE 1.54E+00 Thyroid Environmental - 0.OOE+00 Thyroid Effluent Child Vegetation 0.68 mi NE 1.54E+00 0 Kidney Environmental Child Vegetation 201 (0.53 mi NE) 1.13E-01 0 Kidney Effluent Child Vegetation 0.68 mi NE 1.54E+00 S

Lung Environmental Child Vegetation 201 (0.53 mi NE) 4.06E-02 S Lung Effluent Child Vegetation 0.68 mi NE 1.54E+00 0 0

GI-LLI Environmental Adult Vegetation 201 (0.53 mi NE) 5.74E-03 GI-LLI Effluent Child Vegetation 0.68 mi NE 1.54E+00 0 0

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

0 (2) Critial Pathway is the highest individual dose within the identified Critical Age group. 0 (3) Maximum dose is a summation of the ground/plane, inhalation, milk and vegetation pathways.

Section 4 - Page 4

0 S

Page 3 of 3 S

NOBLE GAS 0

S 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 1.23E-02 Gamma Environmental - Not Sampled 0 Gamma Effluent N/A Noble Gas 0.5 mi. NNE 3.21E-02 S

0 0

S S

0 0

0 Section 4 - Page 5

TABLE 4.1-B Maximum Individual Dosefor 2009-basedon EnvironmentalMeasurements (mrem) for CatawbaNuclear 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 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 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 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 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 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 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 3.61 E-0 1 3.46E-0 1 5.11E-02 O.OOE+00 1.13E-0 1 4.06E-02 2.17E-03 O.OOE+00 Fish O.OOE+00 4.29E-03 4.29E-03 4.29E-03 4.29E-03 4.29E-03 4.29E-03 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 2.95E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.46E-04 TOTAL 3.61E-01 3.50E-01 5.57E-02 4.29E-03 1.17E-01 4.49E-02 6.46E-03 3.46E-04 Teen Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

+/- .O0E+00O.OOE+00 Drinking Water O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 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.OOE-01 2.66E-01 9.26E-02 O.OOE+00 9.05E-02 3.52E-02 3.78E-03 O.OOE+00 Fish O.OOE+00 5.19E-03 5.19E-03 5.19E-03 5.19E-03 5.19E-03 5.19E-03 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 1.41E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.66E-03 TOTAL 2.OOE-01 2.71E-01 9.92E-02 5.19E-03 9.57E-02 4.04E-02 8.97E-03 1.66E-03 Adult Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 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 2.17E-01 2.96E-01 1.94E-01 O.OOE+00 1.01E-01 3.35E-02 5.74E-03 O.OOE+00 Fish O.OOE+00 6.75E-03 6.75E-03 6.75E-03 6.75E-03 6.75E-03 6.75E-03 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 2.53E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.97E-04 TOTAL 2.17E-01 3.03E-01 2.01E-01 6.75E-03 1.08E-01 4.03E-02 1.25E-02 2.97E-04 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6 0 0 0 0 0 0 *00 0 0 00 0 0 0 0 0 0 0 0 0 010 0

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

Usage (intake in one year) = 330 I Highest Annual Net Mean In2estion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 ALL 0.00 0.OOE+00 0.OOE+00 o.ooE+00 0.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 Fe-59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 ALL 0.00 0.OOE4-00 0.OOE+00 0.OOE+00 0.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 1.08 E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 Zn-65 1.84E-05 6.31 E-05 2.91 E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 Nb-95 4.20E-08 1.73E-08 1.OOE-08 NO DATA 1.24E-08 NO DATA 1.46E-05 ALL 0.00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 Zr-95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 Cs-134 3.77E-04 7.03E-04 7.10E3-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 Cs-137 5.22E-04 6.11 E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 BaLa-140 1.71E-04 I.7E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 ALL 0.00* 0.OOE+00 O.ooE+00 0.OOE+00 0.OOE+00 00.OOE+00 0.OOE+00 0.OOE+00 Dose Commitment (mrem) = 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

Tritium was identified at the indicator location; however because it was less than the control location, no dose was attributed to releases from Catawba.

Section 4 - Page 7

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

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/i) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 Co-58 NO DATA 1.80E-06 5.5 1E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+/-00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+/-00 0.OOE+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 Zr-95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE÷00 0.OOE+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 BaLa-140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 ALL 0.00* 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Dose Commitment (mrem) = 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

Tritium was identified at the indicator location; however because it was less than the control location, no dose was attributed to releases from Catawba.

Section 4 - Page 8 OOiOisOOOOOOOOOOOOOOOOOOOOOOOOOOOOO0OOOOOOOOOOO00 00 00 4 0 0 00 00

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Catawba NuclearStation Dosefrom BroadleafVegetation Pathwayfor 2009 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 Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0;00E+00 0.00E+00 0.OOE+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 201 42.5 3.61E-01 3.46E-01 5.11E-02 0.00E+00 1.13E-01 4.06E-02 2.17E-03 Dose Commitment (mrem) = 3.61E-01 3.46E-01 5.11E-02 0.00E+00 1.13E-01 4.06E-02 2.17E-03 Section 4 - Page 9

Catawba NuclearStation Dosefrom Fish Pathwayfor 2009 Data Maximum Exposed Child Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/Il = 3401 pCi/I x 0.9 = 3061 pCi/kg Usage (intake in one year) = 6.9 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Fish Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA 8.98E-06 ALL 0.00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+/-00 Fe-59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALl, 0.00 0.0ifv+0o 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+60 Zn-65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Cs-137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 ALL 0.0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 208 3061 0.OOE+00 4.29E-03 4.29E-03 4.29E-03 4.29E-03 4.29E-03 4.29E-03 Dose Commitment (mrem) = 0.00E+00 4.29E-03 4.29E-03 4.29E-03 4.29E-03 4.29E-03 4.29E-03 Section 4 - Page 10 OQO000000000010100 000000 000 00 000000 000

0000000900000*00000000000*00009000000*00000o CatawbaNuclear Station Dosefrom Shoreline Sediment Pathwayfor 2009 Data Maximum Exposed Child Shoreline Recreation = 14 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass 40 kg/m2 Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m2 ) x Shore Width Factor x Sediment Surface Mass (kg/m 2 ) x Sediment Concentration (pCi/kg)

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

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.OOE+00 Co-58 7.00E-09 8.20E-09 208-IS 110.0 8.62E-05 1.O1E-04 Co-60 1.70E-08 2.00E-08 208-IS 104.0 1.98E-04 2.33E-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 22.7 1.07E-05 1.25E-05 Dose Commitment (mrem) = 2.95E-04 3.46E-04 Section 4 - Page II

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

Usage (intake in one year) = 510 1 Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O O.OOE+00 0.OOE+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.8 1E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 5.76E-06 2.OOE-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+OO Nb-95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zr-95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.OOE-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+/-00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-i00 0.OOE+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 BaLa-140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 ALL 0.00* 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Dose Commitment (mrem)= 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

Tritium was identified at the indicator location; however because it was less than the control location, no dose was attributed to releases from Catawba.

Section 4 - Page 12

000000000000000000000000000000000000000000oQ Catawba NuclearStation Dosefrom BroadleafVegetation Pathwayfor 2009 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) = 42 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 201 42.5 2.OOE-01 2.66E-01 9.26E-02 0.OOE+00 9.05E-02 3.52E-02 3.78E-03 Dose Commitment (mrem) = 2.O0E-01 2.66E-01 9.26E-02 0.OOE+/-00 9.05E-02 3.52E-02 3.78E-03 Section 4 - Page 13

Catawba Nuclear Station Dosefrom Fish Pathwayfor 2009 Data Maximum Exposed Teen Teen Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 3401 pCi/I x 0.9 = 3061 pCi/kg Usage (intake in one year) = 16 kg Highest Annual Ingestion Dose Factor Net Mean Dose (mrem)

Concentration Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 5.76E-06 2.OOE-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 208 3061 0.OOE+00 5.19E-03 5.19E-03 5.19E-03 5.19E-03 5.19E-03 5.19E-03 Dose Commitment (mrem) = 0.OOE+00 5.19E-03 5.19E-03 5.19E-03 5.19E-03 5.19E-03 5.19E-03 Section 4 - Page 14

Catawba NuclearStation Dosefrom ShorelineSediment Pathwayfor 2009 Data Maximum Exposed Teen Shoreline Recreation 67 hr (in one year)

Shore Width Factor = 0.2 2 Sediment Surface Mass 40 kg/m Teen Dose from Shoreline Sediment Pathway (torem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/M 2) x Sediment Concentration (pCi/kg)

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

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.OOE+00 Co-58 7.OOE-09 8.20E-09 208-1S 110.0 4.13E-04 4.83E-04 Co-60 1.70E-08 2.OOE-08 208-IS 104.0 9.48E-04 1.1iE-03 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 22.7 5.11E-05 5.96E-05 Dose Commitment (mrem) = 1.41E-03 1.66E-03 Section 4 - Page 15

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

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 Co-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0200OE+00 0.OOEO00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zr-95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 0.OOE+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BaLa-140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Dose Commitment (mrem) = 0.OOE+/-00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

Tritium was identified at the indicator location; however because it was less than the control location, no dose was attributed to releases from Catawba.

Section 4 - Page 16 OOOOOO09 400 40100 0400 00000 0400 00 0 000

000000000000*e@Oe@*eeeOee@@@eoee0oeeOOeeeooe CatawbaNuclearStation Dosefrom BroadleafVegetation Pathwayfor 2009 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 Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.00E+00 O.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 201 42.5 2.17E-01 2.96E-01 1.94E-01 0.OOE+00 1.01E-01 3.35E-02 5.74E-03 Dose Commitment (mrem) = 2.17E-01 2.96E-01 1.94E-01 0.OOE+00 I.O1E-01 3.35E-02 5.74E-03 Section 4 - Page 17

CatawbaNuclear Station Dosefrom Fish Pathwayfor 2009 Data Maximum Exposed Adult Adult Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/I x Bioaccumulation Factor 0.9 pCi/kg per pCi/I = 3401 pCi/I x 0.9 = 3061 pCi/kg Usage (intake in one year) = 21 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI Mn-54 NO DATA 4. 57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-t00 0.OOE+00 Co-58 NO DATA 7. 45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 ALL 0.00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALI, 0.00 0.00F+00 fl0f0f0E+f+i0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zn-65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ALL 0.00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-134 6.22E-05 1.48E-04 1.2 1E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cs-137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 H-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 208 3061 0.OOE+00 6.75E-03 6.75E-03 6.75E-03 6.75E-03 6.75E-03 6.75E-03 Dose Commitment (mrem) = 0.OOE+00 6.75E-03 6.75E-03 6.75E-03 6.75E-03 6.75E-03 6.75E-03 Section 4 - Page 18

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

Shore Width Factor = 0.2 2 Sediment Surface Mass 40 kg/m Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/M 2) x Sediment Concentration (pCi/kg)

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

(mrem/hr per pCi/m 2) Indicator Sediment Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.00E+00 0.OOE+00 Co-58 7.00E-09 8.20E-09 208-1S 110.0 7.39E-05 8.66E-05 Co-60 1.70E-08 2.OOE-08 208-1S 104.0 1.70E-04 2.00E-04 Cs-134 1.20E-08 1.40E-08 ALL 0.00 0.OOE+00 0.00E+00 Cs-137 4.20E-09 4.90E-09 208-1S 22.7 9.15E-06 1.07E-05 Dose Commitment (mrem) = 2.53E-04 2.97E-04 Section 4 - Page 19

0 S

5.0 QUALITY ASSURANCE S

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

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

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

- Center.

Duke Energy Corporation's

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

5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 0

5.4.1 DAILY QUALITY CONTROL 0EnRad Laboratories has an internal quality assurance program which monitors

each type of instrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.

5.4.2 CALIBRATION VERIFICATION S

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 Sfrequency is dependent upon instrument use and performance. Investigations 5are performed and documented should calibration verification data fall out of

limits.

S 0

0

~~Section 5 -Pagel1 0

0

0 5.4.3 BATCH PROCESSING 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.

5.5 DUKE ENERGY INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Energy Nuclear Generation Department Intercomparison Program during 2009. Interlaboratory cross-check standards, including, Marinelli beakers, air filters, air cartridges, gross beta on smears, and tritium in water samples were analyzed at various times of the year. A summary of the EnRad Laboratory program results for 2009 is documented in Table 5.0-A. 0

.5.6 ERA PROFICIENCY TESTING 0 S

EnRad Laboratories performed method proficiency testing through a program administered by Environmental Resource Associates (ERA) of Arvada, CO. ERA S supplied requested method proficiency samples for analysis and nuclide concentration determination. ERA reported proficiency test results to the North Carolina Department of Health and Human Services, North Carolina Public Health Drinking Water Laboratory Certification Program. A summary of these proficiency test data for 2009 is documented in Table 5.0-B.

5.7 DUKE ENERGY AUDITS 0 S

The Catawba Radiation Protection Section was not audited by the Quality Assurance Group in 2009, but was audited in 2008 (reference 6.16). There were no REMP recommendations as a result of the 2008 audit.

0 EnRad Laboratories was not audited by the Quality Assurance Group in 2009, but was audited in 2008 (reference 6.17). There were some REMP recommendations as a result of the 2008 audit.

0 5.8 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS 0 0

The Catawba Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in 2009 (Reference 6.12). No findings were noted in the report.

5.9 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM 5 0

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

0 0

S 0

S intercomparison program. The Memorandum of Agreement (MOA) between SC S DHEC and Duke Energy describes the sampling frequency and analysis parameters for drinking water, surface water, milk, fish, vegetation, and shoreline sediment samples S collected by EnRad Laboratories. Samples are routinely split with DHEC for intercomparison analysis. DHEC collects air samples near two of the locations sampled for air by CNS. Results of the analyses performed on split and duplicate 0 samples are sent to DHEC.

0 5.10 TLD INTERCOMPARISON PROGRAM S

0 5.10.1 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM 0 Radiation Dosimetry and Records participates in a quarterly TLD intercomparison program administered by Nuclear Technology Services, Inc. of S Roswell, GA. Nuclear Technology Services irradiates environmental 0 dosimeters quarterly and sends them to the Radiation Dosimetry and Records S group for analysis of the unknown estimated delivered exposure. A summary of the Nuclear Technology Services Intercomparison Report is documented in Table 5.0-C.

0 5.10.2 INTERNAL CROSSCHECK (DUKE ENERGY) 0 Radiation Dosimetry and Records participates in a quarterly TLD 0 intracomparison program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff irradiates environmental dosimeters quarterly and submits 0 them for analysis of the unknown estimated delivered exposure. A summary of 0 the Internal Cross Check (Duke Energy) Result is documented in Table 5.0-C.

0 0

S 0

0 0

S Section 5 - Page 3

0 0

TABLE 5.0-A 0 DUKE ENERGY 0 INTERLABORATORY COMPARISON PROGRAM 0 2009 CROSS-CHECK RESULTS FOR 0 ENRAD LABORATORIES 0 Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all 0 three analyses yielded results within the designated acceptance range. A status of "1 Pass" indicates that one analysis of the cross check was performed 0

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

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

Date Range Value Value Status 0 pCi/I pCi/I pCi/I 2.06 E5 3 Pass 0

3/5/2009 Q091GWL Cr-51 1.54-2.73 E5 2.05 E5 Mn-54 4.68- 8.30 E4 6.24 E4 6.47 E4 3 Pass 0

Co-58 4.88- 8.65 E4 6.50 E4 6.52 E4 3 Pass 0 Fe-59 4.40-7.80 E4 5.87 E4 6.15 E4 3 Pass 0 Co-60 5.08-9.02 E4 6.78 E4 7.05 E4 3 Pass 0 Zn-65 5.79 - 10.26 E4 7.72 E4 8.01 E4 3 Pass 0 Cs-134 3.38- 5.99 E4 4.50 E4 4.13 E4 3 Pass 0 Cs-137 3.96-7.03 E4 5.28 E4 5.05 E4 3 Pass Ce-141 4.55- 8.07 E4 6.07 E4 5.99 E4 3 Pass 0

0 7/29/2009 Q093GWS Co-57 1.22-2.16 E5 1.62 E5 1.73 E5 2 Pass 0 Co-60 1.88-3.33 E5 2.50 E5 2.65 E5 2 Pass 0 Y-88 1.22-2.16 E5 1.62 E5 1.63 E5 2 Pass Sn-l13 1.91-3.38 E5 2.54 E5 2.46 E5 2 Pass 0

Cs-137 3.28- 5.81 E5 4.37 E5 4.46 E5 2 Pass 0 0

Gamma in Water 1.0 liter 0

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status pCi/I pCi/I pCi/I 0

3/5/2009 Q091GWL Cr-51 1.54-2.73 E5 2.05 E5 2.04 E5 3 Pass 0 Mn-54 4.68- 8.30 E4 6.24 E4 6.53 E4 3 Pass 0 Co-58 4.88- 8.65 E4 6.50 E4 6.48 E4 3 Pass 0 Fe-59 4.40- 7.80 E4 5.87 E4 6.17 E4 3 Pass 0 Co-60 5.08- 9.02 E4 6.78 E4 6.96 E4 3 Pass 0

Zn-65 5.79 - 10.26 E4 7.72 E4 7.98 E4 3 Pass Cs-134 3.38- 5.99 E4 4.50 E4 4.03 E4 3 Pass 0

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

0 Section 5 - Page 4 0

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

S Gamma in Water 0.5 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status 0 pCi/l pCi/I pCi/l 0 3/5/2009 Q091GWL Cr-51 1.54-2.73 E5 2.05 E5 2.05 E5 3 Pass Mn-54 4.68- 8.30 E4 6.24 E4 6.35 E4 3 Pass Co-58 4.88-8.65 E4 6.50 E4 6.27 E4 3 Pass 0 Fe-59 4.40-7.80 E4 5.87 E4 6.10 E4 3 Pass 0 Co-60 5.08-9.02 E4 6.78 E4 6.94 E4 3 Pass Zn-65 5.79 - 10.26 E4 7.72 E4 8.01 E4 3 Pass 0

Cs-134 3.38- 5.99 E4 4.50 E4 3.88 E4 3 Pass Cs-137 3.96-7.03 E4 5.28 E4 4.90 E4 3 Pass S Ce-141 4.55- 8.07 E4 6.07 E4 5.80 E4 3 Pass 0 7/29/2009 Q093GWS Co-57 1.22-2.16 E5 1.62 E5 1.61 E5 3 Pass 0 Co-60 1.88-3.33 E5 2.50 E5 2.55 E5 3 Pass 0 Y-88 1.22-2.16 E5 1.62 E5 1.58 E5 3 Pass 0 Sn- 113 1.91- 3.38 E5 2.54 E5 2.36 E5 3 Pass 0 Cs-137 3.28- 5.81 E5 4.37 E5 4.27 E5 3 Pass S

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

0 0

Gamma in Water 0.25 liter, continued 0

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range pCi/I Value pCi/i Value pCi/I Status S

7/29/2009 Q093GWS Co-57 1.22-2.16 E5 1.62 E5 1.58 E5 2 Pass 0 Co-60 1.88- 3.33 E5 2.50 E5 2.57 E5 2 Pass 0 Y-88 1.22-2.16 E5 1.62 E5 1.58 E5 2 Pass 0 Sn-113 1.91-3.38 E5 2.54 E5 2.32 E5 2 Pass 0 Cs-137 3.28-5.81 E5 4.37 E5 4.13 E5 2 Pass 0

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

6/18/2009 E6701-37 Cr-51 0.29- 10.17 E2 1.73 E2 1.61 E2 2 Pass 0 Mn-54 4.45-7.89 El 5.93 El 5.96 El 2 Pass 0 Co-58 2.94-5.36 El 3.97 El 3.95 El 2 Pass 0 Fe-59 2.06 - 13.54 El 5.29 El 4.50 El 2 Pass 0 Co-60 1.01- 1.80 E2 1.35 E2 1.36 E2 2 Pass 0

Zn-65 5.68 - 10.07 El 7.57 El 8.01 El 2 Pass 0

Cs-134 5.38-9.54 El 7.17 El 6.50 El 2 Pass Cs-137 6.23 - 11.04 El 8.30 El 7.61 El 2 Pass 0

Ce-141 0.92- 1.64 E2 1.23 E2 1.30 E2 2 Pass 0 0

Iodine in Water 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status pCi/1 pCi/l pCi/I 0

7/21/2009 Q093LIWI 1-131 1.99-3.53 E2 2.65 E2 2.29 E2 3 Pass 0 0

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

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

0 0

0 Section 5 - Page 6 0

0 0

Iodine in Milk 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check S Date Range pCi/l Value pCi/l Value pCi/l Status 3/4/2009 Q091LIM2 1-131 3.30 - 5.85 E3 4.40 E3 2.65 E3 3/3 Low (2)

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

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

S 6/8/2009 Q092LIM3 1-131 7.49 - 13.28 El 9.99 El 9.61 E1 3 Pass 0

0 Iodine on Cartridge Reference Sample l.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status pCi pCi pCi 0 6/18/2009 E6702-37 1-131 7.24- 12.83 El 9.65 El 9.53 El 3 Pass 0

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

0 Tritium in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status pCi/l pCi/l pCi/l 0 1/28/2009 Q091TWRI H-3 4.30-7.62 E3 5.73 E3 5.54 E3 3 Pass 0 1/28/2009 Q091TWR2 H-3 0.86- 1.53 E4 1.15 E4 1.09 E4 3 Pass 7/22/2009 Q093TWSI H-3 0.88- 1.56 E4 1.18 E4 1.13 E4 3 Pass 7/22/2009 Q093TWS2 H-3 3.43- 6.61 E2 4.76 E2 5.10 E2 3 Pass 11/12/2009 Q094TWS1 H-3 5.30-9.40 E8 7.07 E8 7.82 E8 3 Pass 11/12/2009 Q094TWS2 H-3 0.77-1.36 E5 1.02 E5 0.97 E5 3 Pass I I Section 5 - Page 7

0 0

Table 5.0-A Footnote Explanations 0 0

(1) Iodine in Water, Sample ID Q093LIW2, Reference Date 7/21/2009 0 0

One of three results was outside of the acceptance range (reference 6.18). 0 (2) Iodine in Milk, Sample ID Q091LIM2, Reference Date 3/4/2009 0

0 Three results for this cross-check were reported. All three of the reported results 0 trended low and were outside of the acceptance range (reference 6.19). 0 (3) Iodine in Milk, Sample ID Q091LIM3, Reference Date 3/4/2009 0 0

Three results for this cross-check were reported. Two of the three reported results 0 trended low and were outside of the acceptance range (reference 6.19).

0 0

0 6

0 Section 5 - Page 8 0 0

0 0

0 TABLE 5.0-B 0 ENVIRONMENTAL RESOURCE ASSOCIATES (ERA)

QUIK M RESPONSE PROGRAM 0

2009 PROFICIENCY TEST RESULTS FOR 0 ENRAD LABORATORIES ERA LABORATORY CODE: D242401 0

0 Proficiency test samples are received, prepared, analyzed, and reported to Environmental Resource Associates as described in the "Quik" Response instruction package within the study period. Proficiency test data 0 are reported to ERA for evaluation. ERA reports proficiency test results to the North Carolina Department of Health and Human Services, North Carolina Public Drinking Water Laboratory Certification Program.

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

0 Gamma Emitters in Water 0 Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check Date Range Value Value Status 0 pCi/l pCi/l pCi/1 S 4/6/2009 RAD-77* Ba-133 4.34 - 5.83 El 5.27 E1 6.18 El High (1)

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

0 10/5/2009 RAD-79** Ba-133 7.83 - 10.2 El 9.29 El 9.35 El Pass Cs-134 6.50 - 8.73 El 7.94 E1 7.60 El Pass Cs-137 4.91 - 6.29 E1 5.46 E1 5.51 El Pass 0

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

ERA study period4/6/2009 - 5/21/2009, ERA data report issue date 6/3/2009

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

0 0

Table 5.0-B Footnote Explanations 0 0

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

Reported result for Ba-133 was above the acceptance range limit (reference 6.20).

0 0

0 Section 5 - Page 10 0

0

S 0

0 0 TABLE 5.0-C 2009 ENVIRONMENTAL DOSIMETER 0

CROSS-CHECK RESULTS 0

Nuclear Technology Services S

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

0 0

0 S

0 0

0 Section 5 - Page 11 0

0

Internal Crosscheck (Duke Energy)

S 1st Quarter 2009 2nd Quarter 2009 S TLD Delivered Reported Bias Pass/Fail TLD Delivered Reported Bias Pass/Fail S Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) 101297 18.3 (mrem) 19.0

(% diff)

-3.95 <+/-15% Pass 102325 49.1 50.0 -1.78 <+/-15% Pass S

101286 18.5 19.0 -2.58 <+/-15% Pass 102491 48.7 50.0 -2.68 <+/-15% Pass S 101258 18.2 19.0 -4.26 <+/-15% Pass Pass 102374 102084 48.4 47.6 50.0 50.0

-3.26

-4.88

<+/-15%

Pass Pass S

101216 18.4 19.0 -3.42 <+/-15%

101252 18.1 19.0 -4.74 <+/-15% Pass 102404 51.3 50.0 2.56 <+/-15% Pass S 101356 18.7 19.0 -1.74 <+/-15% Pass 102396 47.8 50.0 -4.32 <+/-15%

<+/-15%

Pass Pass S

101339 18.2 19.0 -4.32 <+/-15% Pass 102346 48.7 50.0 -2.60 101127 17.6 19.0 -7.47 <+/-15% Pass 102485 48.6 50.0 -2.80 <+/-15% Pass S 101278 19.4 19.0 1.89 <+/-15% Pass 102059 48.2 50.0 -3.68 <+/-15% Pass S Pass 102263 50.0 50.0 -0.08 <+/-15% Pass 101305 18.4 19.0 Average Bias (B)

-3.05

-3.36

<+/-15%

Average Bias (B) -2.35 S Standard Deviation (S) 2.40 Standard Deviation (S) 2.18 S Measure Performance IBI+S 4.53 <15% Pass Measure Performance IBI+S 5.76 <15% Pass I [

S 3rd Quarter 2009 4th Quarter 2009 TLD Delivered Reported Bias Pass/Fail S

TLD Delivered Reported Bias Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail Number (mrem) (mrem) (% diff) Criteria Pass/Fail S 102400 25.9 27.0 -3.93 <+/-15% Pass 100955 20.4 22.0 -7.14 <+/-15% Pass S 25.7 27.0 -4.70 <+/-15% Pass 100050 20.0 22.0 -9.18 <+/-15% Pass 102486 102402 25.9 27.0 -4.04 <+/-15% Pass 100885 21.2 22.0 -3.68 <+/-15% Pass S 102406 26.9 27.0 -0.44 <+/-15% Pass 101409 19.2 22.0 -12.77 <+/-15% Pass S 22.0 -7.82 <+/-15% Pass 102435 102442 26.6 25.3 27.0 27.0

-1.63

-6.48

<+/-15%

<+/-l 5%

Pass Pass 100389 100401 20.3 20.4 22.0 -7.18 <+/-15% Pass S

102436 25.9 27.0 -3.93 <+/-l 5% Pass 101383 21.0 22.0 -4.45 <+/-15% Pass S 102440 25.1 27.0 27.0

-7.19

-6.81

<+/-15%

Pass Pass 100551 100748 20.4 20.9 22.0 22.0

-7.14

-4.95

<+/-15%

Pass Pass S

102479 25.2 102384 26.0 27.0 -3.67 <+/-15% Pass 100263 20.9 22.0 -4.91 <+/-15% Pass S Average Bias (B) -4.28 Average Bias (B) -6.92 2.68 S

Standard Deviation (S) 2.17 Standard Deviation (S)

Measure Performance IBI+S 6.45 <15% Pass Measure Performance IBI+S 9.61 <15% Pass S S

S S

S Section 5 - Page 12 S S

S

0 0

0 0 .

6.0 REFERENCES

0 6.1 Catawba Selected License Commitment Report 6.2 Catawba Technical Specifications 0

6.3 Catawba Updated Final Safety Analysis Review 6.4 Catawba Offsite Dose Calculation Manual 6.5 Catawba Annual Environmental Operating Report 1985 - 2008 6.6 Catawba Annual Effluent Report 1985 - 2008 6.7 Probability and Statistics in Engineering and Management Science, Hines and

Montgomery, 1969, pages 287-293.

0 6.8 Practical Statistics for the Physical Sciences, Havilcek and Crain, 1988, pages 83-93.

6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual 0Doses to Man from Routine Releases of Reactor Effluents for the Purposes of

Evaluating Compliance with 10CFR50, Appendix I.

6.10 EnRad Laboratories Operating Procedures 0

6.11 RETDAS, Radiological Effluent Tracking and Dose Assessment Software, Canberra

Version 3.5.1, DPC Revision #4.0 6.12 NRC Integrated Inspection Report 05000413/2009003 and 05000414/2009003 0

6.13 Duke Energy Corporation EnRad Laboratory Charcoal Cartridge Study, performed 2001 6.14 Catawba Modifications CN-18103 (Unit 1), CN-28103 (Unit 2) 6.15 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-09-00688, G-09-00913 6.16 Radiological Effluents Controls Audit 08-20(INOS)(REC)(CNS) 0 6.17 Radiological Effluent Controls Audit 08-23(INOS)(REC)(NGO) 6.18 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-09-01278 6

6.19 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-09-00423 6.20 Problem Investigation Process Database, V 3.2.27, Duke Power Company, G-09-0 1295

~Section 6 - Page 1 0

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APPENDIX A S ENVIRONMENTAL SAMPLING AND 0 ANALYSIS PROCEDURES 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.

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

This appendix describes the environmental sampling frequencies and analysis procedures by media type.

I. CHANGE OF SAMPLING PROCEDURES No changes were made to the sampling procedure during 2009.

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 0 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.

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

A 0

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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.

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

III. CHANGE OF ANALYSIS PROCEDURES 0

No analysis procedures were changed during 2009.

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 mi. 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 0locations. A gross beta and gamma analysis was performed on monthly 0composites. 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 Monthly composite samples were collected at each of three locations. A gamma 0analysis was performed on the monthly composites. Tritium analysis was A

0 0

Appendix A -Page 3 0

0 performed on the quarterly composites. The composites were collected monthly 0

from the locations listed below.

0 Location 208 Discharge Canal (0.45 mi. S)

Location 211 Wylie Dam (4.06 mi. ESE)

Location 215 River Pointe - Hwy 49 (4.21 mi. NNE) 0 A.4 GROUND WATER 0 0

Grab samples were collected quarterly from residential wells at each of two locations. A gamma analysis and tritium analysis were performed on each 0 sample. The samples were collected from the locations listed below. 0 Location 252 Residence (0.64 mi. SW) 0 Location 254 Residence (0.82 mi. N) 0 A.5 MILK S Biweekly grab samples were collected at one location. A gamma and low-level 0 Iodine-131 analysis was performed on each sample. The biweekly grab samples were collected from the location listed below. 0 Location 221 = Dairy (14.5 mi. NW) 0 A.6 BROADLEAF VEGETATION 0 Monthly samples were collected at each of five locations. A gamma analysis was performed on each sample. The samples were collected from the locations 0

listed below. 0 Location 200 - Site Boundary (0.63 mi. NNE) 0 Location 201 = Site Boundary (0.53 mi. NE)

Location 222 = Site Boundary (0.70 mi. N) 0 Location 226 = Site Boundary (0.48 mi. S)

Location 258 = Fairhope Road (9.84 mi. W) 0 A.7 FOOD PRODUCTS 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 0

0 0 A.8 FISH 0 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 = Discharge Canal (0.45 mi. S)

Location 216 = Hwy 49 Bridge (4.19 mi. NNE)

A.9 SHORELINE SEDIMENT 0 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 = Discharge Canal (0.45 mi. S)

Location 210 = Ebenezer Access (2.31 mi. SE)

Location 215 = River Pointe - Hwy 49 (4.21 mi. NNE) 0 A.10 DIRECT GAMMA RADIATION (TLD) 0 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.

A.11 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:

S* The Nearest Residence S* The Nearest Garden greater than 50 square meters or 500 square feet 0

0 0

O Appendix A - Page 5 0

0 0

0 The Nearest Milk-giving Animal (cow, goat, etc.) 0 The census was conducted during the growing season from 7/15 to 7/16/2009. 0 Results are shown in Table 3.11. No changes were made to the sampling 0 procedures during 2009 as a result of the 2009 census. 0 0

V. GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS 0

The Catawba site centerline used for GPS measurements was referenced from the 0 Catawba Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 0 2.1.1.1, Specification of Location. Waypoint coordinates used for CNS GPS measurements were latitude 35°-3'-5"N and longitude 81'-4'-10"W. Maps and 0 tables were generated using North American Datum (NAD) 27. Data normally 0 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 0

the locations are displayed using three significant figures. 0 0

0 0

0 Appendix A - Page 6 0

0

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APPENDIX B 0

0 RADIOLOGICAL 0

0 ENVIRONMENTAL MONITORING 0 PROGRAM 0

0 0

SUMMARY

OF RESULTS 0

0 0

0 2009 0

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0 Appendix B - Page 1 0

0 0

0 Environmental Radiological Monitoring Program Summary 0 Facility: Catawba Nuclear Station Docket No. 50-413,414 0 Location: York County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0

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

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

Measurement Performed (LLD) Range Code Range Range Air Particulate 258 (pCi/m3) (9.84 mi W)

BETA 257 L.OOE-02 1.74E-2 (206/206) 212 1.78E-2 (52/52) 1.72E-2 (51/51) 0 0 5.43E 3.36E-2 (3.32 mi E) 9.20E 3.01E-2 5.77E 2.90E-2 0 CS-134 257 5.OOE-02 0.00 (0/206) 0.00 (0/52) 0.00 (0/51) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 257 6.00E-02 0.00 (0/206) 0.00 (0/52) 0.00 (0/51) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 257 7.OOE-02 0.00 (0/206) 0.00 (0/52) 0.00 (0/51) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

Mean and range based upon detectable measurements only 0

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

0 0

Report Generated @ 4/26/2010 16:07 Appendix B - Page 2

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 MediumMeim r Total Type and Lower All Indicator Location with Highest Control No. of Non-Pathway Number Limit of Locations Annual Mean Location Routine Sampled of Detection Name, Distance, Direction Report Meas.

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

Measurement Performed Range Code Range Range Air Radioiodine 258 (pCi/m3) (9.84 mi W) 0 CS-134 257 5.OOE-02 0.00 (0/206) 0.00 (0/52) 0.00 (0/51) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 257 6.OOE-02 0.00 (0/206) 0.00 (0/52) 0.00 (0/51) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 1-131 257 7.OOE-02 0.00 (0/206) 0.00 (0/52) 0.00 (0151) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

0 0

Report Generated @ 4/26/2010 16:07 Appendix B - Page 3

0 S

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 0 Location: York County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 Medium or Type and Total Lower Location with Highest ControlNone No. of Non- 0 Number Limit of Annual Mean Pathway Sampled of Detection Locations Name, Distance, Direction Location Report 0 Meas.

Unit of Analyses (LLD) Mean (Fraction) Location Mean (Fraction) Mean (Fraction) 0 Measurement Performed Range Code Range Range Drinking Water 218 0 (pCi/liter) (13.5 mi NNE)

BALA-140 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 BETA 26 4 2.07 (13/13) 214 2.07 (13/13) 1.99 (13/13) 0 0.88 - 2.96 (7.30 mi SSE) 0.88 - 2.96 0.95 - 3.86 CO-58 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 26 18 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 8 2000 634 (4/4) 214 634 (4/4) 681 (4/4) 0 439 - 879 (7.30 mi SSE) 439- 879 509 - 885 1-131 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 26 15 0.00 (0/13) 0.60 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0 0 NB-95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0 ZN-65 26 30 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0 0

ZR-95 26 15 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0 0

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 0

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

Report Generated @ 4/26/2010 16:07 Appendix B - Page 4

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0 ControlNone No. of Non-Medium or Type and Total Lower Location with Highest Pathway Number Limit of Annual Mean of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

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

Measurement Performed ( Range Code Range Range 0

Surface Water 215 0 (pCi/liter) (4.21 mi NNE) 0 BALA-140 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0 CO-58 39 15 0.00 - 0.00 9.40 (4/26) 208 0.00 - 0.00 9.40 (4/13) 0.00 - 0.00 0.00 (0/13) 0 0 5.43 - 18.7 (0.45 mi S) 5.43 - 18.7 0.00-0.00 0 CO-60 39 15 10.6 (1/26) 208 10.6 (1/13) 0.00 (0/13) 0 10.6 - 10.6 (0.45 mi S) 10.6 - 10.6 0.00 - 0.00 CS-134 39 15 0.00 (0W26) 0.00 (0/13) 0.00 (0/13) 0 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 2292 (8/8) 208 3930 (4/4) 529 (4/4) 0 475 - 4420 (0.45 mi S) 3530 - 4420 367 - 729 0 1-131 39 15 0.00 (0/26) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0

MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 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 0 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 0 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 0

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

Zero range indicates no detectable activity measurements 0

S 0

0 Report Generated @ 4/26/2010 16:07 Appendix B - Page 5 0

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 Location with Highest ControlNone No. of Non- 0 Type and Total Lower Medium or Pathway Number Limit of Annual Mean Control Rout 0 Sampled of Detection Locations Name, Distance, Direction Location Report 0

Meas.

0 Unit of Measurement Analyses Performed (LLD) Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range 0

0 Ground Water NO CONTROL 0 (pCi/liter) LOCATION 0 BALA-140 8 15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0 0.00- 0.00 0.00- 0.00 0.00- 0.00 0 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 0 CO-60 8 15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0 CS-134 8 15 0.00 - 0.00 0.00 (0/8) 0.00 - 0.00 0.00 (0/8) 0.00 - 0.00 0.00 (0/0) 0 0

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 8 18 0.00 (0/8) 0.00 - 0.00 0.00 (0/8) 0.00 - 0.00 0.00 (0/0) 0.00 - 0.00 0

0 FE-59 8 30 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0 H-3 8 2000 0.00 - 0.00 0.00 (0/8) 0.00 - 0.00 0.00 (0/8) 0.00 - 0.00 0.00 (0/0) 0 0

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 1-131 8 15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 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

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 NB-95 8 15 0.00 (0/8) 0.00 - 0.00 0.00 (0/8) 0.00 - 0.00 0.00 (0/0) 0.00 - 0.00 0

0 ZN-65 8 30 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0 ZR-95 8 15 0.00 - 0.00 0.00 (0/8) 0.00 - 0.00 0.00 (0/8) 0.00 - 0.00 0.00 (0/0) 0 0

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 0

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

0 0

0 Report Generated @ 4/26/2010 16:07 0

Appendix B - Page 6 0 0

0

0 0

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Number Limit of Annual Mean Pathway of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

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

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

S 0

0 0

0 S

0 0

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0

0 0

0 Environmental Radiological Monitoring Program Summary 0 0

Facility: Catawba Nuclear Station Docket No. 50-413,414 0

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

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

Measurement Performed Range Code Range Range Broadleaf Vegetation 258 (9.84 mi W) 0 (pCi/kg-wet) 0 CS-134 60 60 0.00 (0/48) 0.00 (0/12) 0.00 (0/12) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 60 80 42.5 (1/48) 201 42.5 (1/12) 0.00 (0/12) 0 0 42.5 - 42.5 (0.53 mi NE) 42.5 - 42.5 0.00 - 0.00 0 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 0

0 Mean and range based upon detectable measurements only 0

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

0 0

0 Report Generated @ 4/26/2010 16:07 Appendix B - Page 8

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0 No. of Non-Medium or Type and Total Lower All Idit Location with Highest Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction Lepor Meas.

Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction) 0 Measurement Performed Range Code Range Range Food Products NO CONTROL (pCi/kg-wet) LOCATION CS-134 7 60 0.00 (0/7) 0.00 (0/7) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 7 80 0.00 (0/7) 0.00 (0/7) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 7 60 0.00 (0/7) 0.00 (0/7) 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) 0 Zero range indicates no detectable activity measurements 0

0 00 00 0

0 S

0 0

0 S

0 Report Generated @ 4/26/2010 16:07 0 Appendix B - Page 9

0 Environmental Radiological Monitoring Program Summary 0

Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 0

No. of Non-ControlNone Medium or Type and Total Lower Location with Highest Annual Mean 0

Pathway Number Limit of Name, Distance, Direction Location Report Sampled of Detection Locations Meas. 0 Unit of Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Measurement Performed Range Code Range Range 0

Fish 216 (pCi/kg-wet) (4.19 mi NNE) 0 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

Mean and range based upon detectable measurements only 0

Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements 0

S S

0 0

Report Generated @ 4/26/2010 16:07 0

Appendix B - Page 10

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2009 to 31-DEC-2009 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Number Limit of Annual Mean Pathway Detection Locations Name, Distance, Direction Location Report Sampled of Meas.

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

Measurement Performed Range Code Range Range 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 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CO-58 6 0 110(2/4) 208-IS 110(2/2) 0.00(0/2) 0 35.3 - 184 (0.45 mi S) 35.3 - 184 0.00 - 0.00 CO-60 6 0 104 (1/4) 208-IS 104 (1/2) 0.00 (0/2) 0 0 104- 104 (0.45 mi S) 104 - 104 0.00-0.00 CS-134 6 150 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 6 180 22.7 (1/4) 208-IS 22.7 (1/2) 0.00 (0/2) 0 22.7 - 22.7 (0.45 mi S) 22.7 - 22.7 0.00 - 0.00 0

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

Zero range indicates no detectable activity measurements S If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments 0

0 0

S 0

0 0

0 S

0 Report Generated @ 4/26/2010 16:07 Appendix B - Page 11

0 0

0 Environmental Radiological Monitoring Program Summary 0

Facility: Catawba Nuclear Station Docket No. 50-413,414 0

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

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

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 18.7 (150/150) 235 23.9 (3/3) 14.5 (12/12) 0 10.2 - 29.6 (4.07 mi ESE) 17.0 - 29.6 10.2 - 20.6 w

Mean and range based upon detectable measurements only 0

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

0 0

0 Report Generated @ 4/26/2010 16:07 0

Appendix B - Page 12 0 0

S S

0 0

S 0

0 0

S 0

S S

S S APPENDIX C 0

0 S SAMPLING DEVIATIONS S

0 S UNAVAILABLE ANALYSES 0

S 0

0 S

S S

0 S

S 0

0 0

S S

S Appendix C - Page I S

S

S S

0 APPENDIX C 0 CATAWBA NUJCLEAR STATION 0 SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES 0

flFVIATION & IINAVAIIARIF UFA~ON CABF~

BF Blown Fuse P0 Power Outage S FZ Sample Frozen PS Pump out of service / Undergoing Repair SL Sample Loss/Lost due to Lab Accident 0

_____Inclement_____Weather__

LC Line Clog to Sampler SM Motor / Rotor Seized Other ______________ TF Torn Filter 0 PT Power Interrupt VN Vandalism PM Preventive Maintenance CN Construction S

0 C-1 SAMPLING DEVIATIONS 0 Air Particulate and Air Radioiodines Scheduled Actual Reason 0 Location Collection Dates Collection Dates Code Corrective Action Power interruption due to breaker trip.

0 Thunderstorm was suspected cause. 0 258 5/19 - 5/27/2009 5/19 - 5/24/2009 P0 Breaker reset, normal sampling resumed.

Work request 68178 (written from the S

previous composite period) requested site services investigate reliability of location's power delivery system. Breaker replaced during composite period 0 interrupting power to equipment for 200 5/19 - 5/27/2009 5/19 - 5/27/2009 P1 approximately 30 minutes.

Power interruption due to breaker trip.

Thunderstorm was suspected cause.

200)' 7/14 - 7/21/2009 7/14 - 7/18/2009 P1 Breaker reset, normal sampling resumed.

Power interruption due to breaker trip. S Thunderstorm was suspected cause.

258 8/11 - 8/18/2009 8/11 - 8/13/2009 P0 Breaker reset, normal sampling resumed.

Power interruption due to breaker trip.

Thunderstorm was suspected cause.

201(') 9/1 - 9/9/2009 9/1 - 9/6/2009 P0 Breaker reset, normal sampling resumed.

Power interruption due to breaker trip.

Work request 72688 initiated to verify electrical supply stability. Breaker reset, 0

201(') 10/6 - 10/13/2009 10/6 - 10/12/2009 P0 normal sampling resumed.

0 0

0 (1) PIP G-09-01248 initiated to investigate power reliability issues at location 201. 0 Appendix C - Page 2 0 S

0

0 S

0 Air Particulate and Air Radioiodines, continued 0 Power interruption due to breaker trip.

201(') 11/10 - 11/17/2009 11/10 - 11/17/2009 PI Breaker reset, normal sampling resumed.

Power interruption due to breaker trip.

S 258 11/10 - 11/17/2009 11/10 - 11/11/2009 PO Breaker reset, normal sampling resumed.

0 0 C.2 UNAVAILABLE ANALYSES Air Particulate and Air Radioiodines Scheduled Reason Location Collection Dates Code Corrective Action 0 Power interruption due to breaker trip. Insufficient volume collected. Work request 68178 written to 0 determine reliability of power supply. Breaker reset, 200 5/12 - 5/19/2009 PI normal sampling resumed.

0 Power outage due to breaker trip. Suspected cause was thunderstorm. Insufficient volume collected.

0 201(l) 7/21 - 7/28/2009 PO Breaker reset, normal sampling resumed.

0 Power outage due to breaker trip. Insufficient volume 258 11/17 - 11/24/2009 PO collected. Breaker reset, normal sampling resumed.

S TLD S Scheduled Reason 0

Location 235 249 I Collection Dates 6/10 -9/16/2009 9/16 - 12/16/2009 Code CN-VN Corrective Action TLDmissing. 4h quarter 2009 TLD placed in field.

TLD missing. 4" quarter 2009 TLD placed in field.

0

.0 0

0 0

(1) PIPG-09-01248 initiatedto investigate power reliability issues at location 201.

Appendix C - Page 3

S 0

0 0

0 APPENDIX D 0

S 0 ANALYTICAL DEVIATIONS S

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

0 0

0 Appendix D - Page 1

S S

S 0

0 S

0 0

APPENDIX E 0

0 S RADIOLOGICAL 0

0 ENVIRONMENTAL MONITORING PROGRAM RESULTS S

0 0

0 This appendix includes all of the sample analysis reports generated from each sample medium for 2009. 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.

0 0

Appendix E - Page 1

ML101400132

Contents

Text

Subject:

SUMMARY

2.0 INTRODUCTION

6.0 REFERENCES

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ML101400132

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6.0 REFERENCES

SUMMARY

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