ML12137A012

Annual Radiological Environmental Operating Report 2011 - Cover Through Chapter 3.0

ML12137A012
Person / Time
Site:	Catawba
Issue date:	12/31/2011
From:	Duke Energy Carolinas
To:	Office of Nuclear Reactor Regulation
References
Download: ML12137A012 (46)

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0 AREOR Annual Radiological Environmental 0 Operating Report S 2011 S

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• TABLE OF CONTENTS 1.0 Executive Summary . . . . . . . . . . 1-1 2.0 Introduction 2-1 2.1 Site Description and Sample Locations 2-1 2.2 Scope and Requirements of the REMP 2-1 2.3 Statistical and Calculational Methodology . 2-2 2.3.1 Estimation of the Mean Value . 2-2 2.3.2 Lower Level of Detection and Minimum Detectable Activity 2-3 2.3.3 Trend Identification. 2-3 3.0 Interpretation of Results . 3-1 3.1 Airborne Radioiodine and Particulates 3-3 3.2 Drinking Water. 3-7 3.3 Surface Water . 3-9 3.4 Ground Water . 3-11 3.5 Milk. 3-12 3.6 Broadleaf Vegetation. 3-14 3.7 Food Products 3-17 3.8 Fish. 3-18 3.9 Shoreline Sediment 3-21 3.10 Direct Gamma Radiation 3-24 3.10.1 Environmental TLD 3-24 3.10.2 ISFSI 3-24 3.11 Land Use Census 3-29 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 Eckert & Ziegler Analytics Cross Check Program 5-2 5.7 ERA Proficiency Testing 5-2 5.8 Duke Energy Audits . 5-2 5.9 U.S. Nuclear Regulatory Commission Inspections 5-2 5.10 State of South Carolina Intercomparison Program 5-3 5.11 TLD Intercomparison Program . 5-3 5.11.1 Nuclear Technology Services Intercomparison Program 5-3 5.11.2 Internal Crosscheck (Duke Energy). 5-3 6.0 References 6-1 i

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0 Appendices Appendix A: Environmental Sampling and Analysis Procedures A-1 0

1. Change of Sampling Procedures A-2 II. Description of Analysis Procedures A-2 III. Change of Analysis Procedures. A-3 IV. Sampling and Analysis Procedures A-3 A.1 Airborne Particulate and Radioiodine A-3 A.2 Drinking Water . . . . . . . . . . A-3 A.3 Surface Water . . . . . . . . . . A-3 A.4 Ground Water. A-4 A.5 Milk A-4 A.6 Broadleaf Vegetation A-4 A.7 Food Products. . . . . A-4 A.8 Fish A-5 A.9 Shoreline Sediment. A-5 A.10 Direct Gamma Radiation (TLD) . . . . . . . A-5 A. 11 Annual Land Use Census . . . . . . . . A-5 V. Global Positioning System (GPS) Analysis. A-6 Appendix B: Radiological Env. Monitoring Program - Summary of Results B-1 Air Particulate .. . . B-2 Air Radioiodine. B-3 Drinking Water. . . . . . . . . . B-4 Surface Water . . . . B-5 Ground Water . . . . . . . . . . . B-6 Milk . . .. ... B-7 Broadleaf Vegetation B-8 Food Products .. . . . B-9 Fish .. ... B-10 Shoreline Sediment B-11 Direct Gamma Radiation (TLD) . . . . . . . . B-12 Air Particulate Excluding Fukushima Daiichi B-14 Air Radioiodine Excluding Fukushima Daiichi B-15 Milk Excluding Fukushima Daiichi . . . . . . . . B-16 Broadleaf Vegetation Excluding Fukushima Daiichi B-17 Fukushima Daiichi Radioactivity Detected in Environmental Media (2011). B-19 Appendix C: Sampling Deviations and Unavailable Analyses C-1 C.1 Sampling Deviations . . . . . . . . . C-2 C.2 Unavailable Analyses C-3 Appendix D: Analytical Deviations .. . . . D-1 Appendix E: Radiological Environmental Monitoring Program Results E-1 Appendix F: Errata to Previous Reports F-I LIST OF FIGURES 2.1-1 Sampling Locations Map (One Mile Radius) . . . . 2-4 2.1-2 Sampling Locations Map (Ten Mile Radius) 2-5 3.1 Concentration of Gross Beta in Air Particulate 3-4 3.2 Concentration of Tritium in Drinking Water 3-8 3.3 Concentration of Tritium in Surface Water. 3-10 3.6 Concentration of Cs-137 in Broadleaf Vegetation 3-15 3.8-1 Concentration of Co-58 in Fish . 3-18 3.8-2 Concentration of Co-60 in Fish . 3-19 3.8-3 Concentration of Cs-137 in Fish. 3-19 3.9-1 Concentration of Co-58 in Shoreline Sediment 3-21 3.9-2 Concentration of Co-60 in Shoreline Sediment 3-22 3.9-3 Concentration of Cs-137 in Shoreline Sediment .

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0 3.10-1 Direct Gamma Radiation (TLD) Results 3-25 3.10-2 Catawba Inner Ring (TLD) Results 3-27 3.10-3 Catawba Outer Ring (TLD) Results 3-28 3.11 2011 Land Use Census Map 3-30

• LIST OF TABLES 0 2.1-A Radiological Monitoring Program Sampling Locations . Sites)2-6

• 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites) . . 2-7 2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2-8 2.2-B REMP Analysis Frequency 2-8 2.2-C Maximum Values for the Lower Limits of Detection . 2-9 3.1-A Mean Concentration of Gross Beta in Air Particulate . 3-5 3.1-B Mean Concentration of Air Radioiodine (1-131) . 3-6 3.2 Mean Concentrations of Radionuclides in Drinking Water 3-8 3.3 Mean Concentrations of Radionuclides in Surface Water 3-10 3.5 Mean Concentration of Radionuclides in Milk 3-13 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation 3-16 3.7 Mean Concentration of Radionuclides in Food Products 3-17 3.8 Mean Concentrations of Radionuclides in Fish 3-20 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment 3-23 3.10-A Direct Gamma Radiation (TLD) Results 3-26 3.10-B Direct Gamma Radiation (TLD) Results Inner Ring 3-27 3.10-C Direct Gamma Radiation (TLD) Results Outer Ring . 3-28 3.11 Land Use Census Results . 3-29 4.1-A 2011 Environmental and Effluent Dose Comparison . 4-3 4.1-B Maximum Individual Dose for 2011 based on Environmental Measurements for Catawba Nuclear Station 4-5 5.0-A 2011 Duke Energy Interlaboratory Comparison Program Results for EnRad Laboratories . 5-4 5.0-B 2011 Eckert & Ziegler Analytics Cross Check Program Results . 5-9 5.0-C 2011 Environmental Resource Associates Quik' Response Program . 5-12 0 5.0-D 2011 Environmental Dosimeter Cross-Check Results . 5-14 0

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LIST OF ACRONYMS USED IN THIS TEXT (in alphabeticalorder)

BW BiWeekly 0 C Control 0 CNS Catawba Nuclear Station DEHNR Department of Environmental Health and Natural Resources 0 DHEC EPA Department of Health and Environmental Control Environmental Protection Agency 0

ERA GI-LLI Environmental Resource Associates Gastrointestinal - Lower Large Intestine 0

GPS Global Positioning System 0 ISFSI Independent Spent Fuel Storage Installation LLD Lower Limit of Detection 0 M Monthly MDA Minimum Detectable Activity 0 MOA mrem Memorandum of Agreement Millirem 0

NIST NRC National Institute of Standards and Technology Nuclear Regulatory Commission 0

ODCM Offsite Dose Calculation Manual 0 pCi/kg picocurie per kilogram pCi/I picocurie per liter 0 pCi/m3 picocurie per cubic meter PIP Problem Investigation Program 0 Q

REMP Quarterly Radiological Environmental Monitoring Program 0

SA SLCs Semiannually Selected Licensee Commitments 0

SM Semimonthly 0 TECH SPECs Technical Specifications TLD Thermoluminescent Dosimeter 0 9Ci/ml UFSAR microcurie per milliliter Updated Final Safety Analysis Report 0

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• 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 2011.

• Included are the identification of sampling locations, descriptions of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and pre-operational environmental data, comparisons of doses calculated from environmental measurements and effluent data, analysis of trends in environmental radiological data as 0potentially affected by station operations, and a summary of environmental radiological sampling results. Evaluation of the effect of trans-Pacific transport of airborne releases from Fukushima Daiichi following the March 11, 2011 Tohoku earthquake is included for affected sample media. Quality assurance practices, sampling deviations, unavailable samples, and 0program changes are also discussed.

Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLCs). Required analyses were performed and detection capabilities were met for all

• collected samples as required by SLCs. Eight-hundred eighty-six samples were analyzed

• comprising 1,198 test results in order to compile data for the 2011 report. Based on the annual land use census, the current number of sampling sites for Catawba Nuclear Station is sufficient.

• Following the March 11, 2011 Tohoku earthquake in Japan, radioactive material migrated

• from the Fukushima Daiichi power plant to the United States. Radioactive material was

• detected at numerous U.S. nuclear plants (including all three Duke nuclear plants) and detected by state and federal monitoring agencies. Where applicable in this report,

• radioactive material determined to be from the Fukushima Daiichi power plant has been

• identified and distinguished from effluents from Catawba Nuclear Station.

Concentrations observed in the environment in 2011 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of data showed 0that 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 attributable to station operation were within limits as specified in SLCs.

• Additionally, environmental radiological monitoring data is consistent with effluents introduced into the environment by plant operations. The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data, excluding TLD results, was 1.94E-01 mrem for 2011. It is therefore concluded that station

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

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2.0 INTRODUCTION

0 O 2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS

• Duke Energy Corporation's Catawba Nuclear Station is a two-unit facility located on the shore of Lake Wylie in York County, South Carolina. Each of the two essentially identical units employs a pressurized water reactor nuclear steam supply system furnished by Westinghouse

• Electric Corporation. Each generating unit is designed to produce a net electrical output of

• approximately 1145 MWe. Units 1 and 2 achieved initial criticality on January 7, 1985, and

• May 8, 1986, respectively.

0Condenser 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 0concentrations in the discharge canal given comparable liquid effluent source terms.

0 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.

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

• 1981, four years prior to operation of Unit I in 1985. The preoperational program provides

• data on the existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station. 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.

This monitoring program is based on NRC guidance as reflected in the Selected Licensee

• Commitments Manual, with regard to sample media, sampling locations, sampling frequency and analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other "man-made" environmental radioactivity. The environmental monitoring program also verifies 0projected and anticipated radionuclide concentrations in the environment and related exposures 0from 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, 0public and state and federal agencies concerned with the environment. Reporting levels for

• activity found in environmental samples are listed in Table 2.2-A.

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0 Table 2.2-B lists the REMP analysis and frequency schedule.

The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified and that 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 3.11.

Participation in an interlaboratory comparison program as required by Selected Licensee 0 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 quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A summary of the results obtained as part of this comparison program are in Section 5 of this annual report. 0 0

2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE 0 There was one (1) basic statistical calculation performed on the raw data resulting from 0 the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the 0 Radiological Environmental Monitoring Program. "Net activity (or concentration)" is 0 the activity (or concentration) determined to be present in the sample. No "Minimum Detectable Activity", "Lower Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of the mean. The following equation was used to estimate the mean (reference 6.8): 0 I0 x = N Where:

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

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

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• 2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM

• DETECTABLE ACTIVITY 0The Lower Level of Detection (LLD), and Minimum Detectable Activity (MDA) are throughout the REMP.

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• 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 priorilower limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample 0size (mass or volume), the radiochemical yield and the radioactive decay of the sample between sample collection and counting. The "required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.

• MDA - The MDA is the net counting rate (sample after subtraction of background) that must be surpassed before a sample is considered to contain a scientifically measurable

• amount of a radioactive material exceeding background amounts. The MDA is calculated using a sample background and may be thought of as an "actual" LLD for a 0particular sample measurement.

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

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

• are not adding that radionuclide to the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, 0 deposition, resuspension, etc.) are influencing the concentration.

Substantial increases or decreases in the amount of a particular radionuclide's release from the nuclear plant will greatly affect the resulting environmental levels; therefore, a knowledge of the release of a radionuclide from the nuclear plant is necessary to 0completely interpret the trends, or lack of trends, determined from the environmental 0data. 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 0location, and addition or deletion of other sources of radioactive materials (such as the

• Chemobyl 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 Section 2 - Page 4

Figure 2.1-2 Catawba Nuclear Station Sampling Locations Map (Ten Mile Radius)

Legend

• TLDLocations

• All Other Locations

/CNSRailroads NavteqHwys

[-- States Counties NHDWaterbody Incorporated Areas Approximate location of features shown N

W-*a 0 1 2 3 Poo ,Miles Projection NCSP NAD27 a

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0 TABLE 2.1-A S

CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 2.1-A Codes W Weekly SM Semtimontly BW BWeekit Q Suartely M Monthl SA Semiannually C Control I Indicator Site Measure Type Location Deescription o* AA Rod.

Surface Water Drintidg Water Shoreline Sediment Food Products Fish Milk Bread Leaf Ground Water S

1. _Type 200 1 Site Boundary (0.63 mi NNE)

Part.

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_ (a) V_ (b)

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201 205 1

I Site Boundary (0.53 mi NE)

Site Boundary (0.25 mi SW)

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M S 208 210 I

I Discharge Canal (0.45 mi S)

Ebenezer Access (2.31 mi SE)

M SA SA SA S 211 I Wylie Dam (4.06 mi ESE) M 0 212 1 Tega Cay (3.32 mi E) W 214 1 Rock Hill Water Supply (7.30 mi SSE) M S 215 216 C

C River Pointe - Hwy 49 (4.21 mi NNE)

Hwy 49 Bridge (4.19 ni NNE)

M SA SA 0 218 221 C

C Belmont Water Supply (13.5 mi NNE)

Dairy (14.5 mi NW)

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222 226 I

I Site Boundary (0.70 mi N)

Site Boundary (0.48 mi S)

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0 254 258 C 1 Residence (0.82 miN)

Fairhope Road (9.84 miW)

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260 I Irrigated Gardens (2.00 mi SSE) M(a) I 0 (a) During Harvest Season 0

(b) When Available S

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

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CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES) 0 S [Table 2.1-B CodesI IR Inner Ring OR Outer Ring 0 C Control SI Special Interest Site Measure Location* Distance Sector Site Measure Location* Distance Sector

1. Type (miles) # Type (miles) 0 200 IR SITE BOUNDARY 0.63 NNE 234 OR WELLS FARGO BANK 4.50 E 0 201 IR SITE BOUNDARY 0.53 NE 235 OR LAKE WYLIE DAM SC WILDLIFE 4.07 ESE 0 203 IR SITE BOUNDARY 0.38 ESE 236 OR FEDERATION OFFICE 4.25 SE TWIN LAKES ROAD AND 0 204 IR SITE BOUNDARY 0.48 SSW 237 OR HOMESTEAD ROAD 4.75 SSE PENNINGTON ROAD 0 205 IR SITE BOUNDARY 0.25 SW 238 OR AND WEST OAK ROAD 4.02 S CARTER LUMBER 206 IR SITE BOUNDARY 0.67 WNW 239 OR COMPANY 4.49 SSW 0 207 IR SITE BOUNDARY 0.95 NNW 240 OR PARAHAM ROAD 4.07 SW 212 SI TEGA CAY AIR SITE 3.32 E 241 OR CAMPBELL ROAD 4.58 WSW OLD ROCK HILL TRANSMISSION TOWER 217 C AIR SITE 10.3 SSE 242 OR ON PARAHAM ROAD 4.56 W 0 222 IR SITE BOUNDARY 0.71 N 243 OR KINGSBERRY ROAD 4.39 WNW BETHEL 223 IR SITE BOUNDARY 0.57 E 244 OR ELEMENTARY SCHOOL 4.02 NW 0 225 IR SITE BOUNDARY 0.68 SE 245 OR CROWDERS CREEK BOAT LANDING 4.01 NNW 0 CAROWINDS 226 IR SITE BOUNDARY 0.48 S 246 SI GUARD HOUSE 7.87 ENE 227 IR SITE BOUNDARY 0.52 WSW 247 C FORT MILL 7.33 ESE 0 PIEDMONT 228 IR SITE BOUNDARY 0.61 W 248 SI MEDICAL CENTER 6.54 S YORK COUNTY 229 IR SITE BOUNDARY 0.84 NW 249 SI OPERATIONS CENTER 7.17 S RIVER HILLS YORK 230 OR CHURCH 4.37 N 250 SI DUKE POWER OFFICE 10.4 WSW RIVER HILLS 231 OR FRONT ENTRANCE 4.21 NNE 251 C CLOVER 9.72 WNW PLEASANT HILL 232 OR ROAD 4.18 NE 255 IR SITE BOUNDARY 0.61 ENE ZOAR ROAD AND 233 OR THOMAS DRIVE 3.95 ENE 256 IR SITE BOUNDARY 0.58 SSE

,1 258 SI FAIRHOPE ROAD 9.84 W

• 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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TABLE 2.2-A S

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 0 S

Analysis Water (pCi/liter)

Air Particulates or Gases Fish (pCi/kg-wet)

Milk Food Products S (pCi/liter) (pCi/kg-wet)

(pCi/m3) S H-3 Mn-54 20,000(a),()b) 1,000 30,000 S

Fe-59 400 10,000 S Co-58 1,000 30,000 S Co-60 300 10,000 Zn-65 300 20,000 S Zr-Nb-95 400 0 1-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 0 Cs-137 50 20 2,000 70 2,000 S Ba-La-140 200 300 S

(a) If no drinking water pathway exists, a value of 30,000 pCi/liter may be used. S (b) H-3 Reporting level not applicable to surface water S TABLE 2.2-B S

S REMP ANALYSIS FREQUENCY S S

Sample Analysis Gamma Tritium Low Gross TLD Medium Schedule Isotopic Level Beta S 1-131 S Air Radioiodine Weekly X Air Particulate Weekly X X S Direct Radiation Quarterly X S Surface Monthly Composite X Water Quarterly Composite X S Drinking Monthly Composite X (a) X S Water Quarterly Composite X Ground Water Quarterly X X S Shoreline Sediment Semiannually X S Milk Semimonthly X X Fish Semiannually X S

Broadleaf Vegetation Monthlyb) X S Food Products Monthlyý') X S

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

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

(b) When Available S

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0 TABLE 2.2-C 0

MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION 0

Analysis Water Air Fish Milk Food Products Sediment (pCi/liter) Particulates or (pCi/kg-wet) (pCi/liter) (pCi/kg-wet) (pCi/kg-dry) 0 Gross Beta 4 Gases (pCi/mr3) 0.01 H-3 2000 0 Mn-54 15 130 S Fe-59 30 260 0 Co-58, 60 Zn-65 15 30 130 260 0 Zr-Nb-95 15 S 1-131 1(T 0.07 1 60 Cs-134 15 0.05 130 15 60 150 0 Cs-137 Ba-La-140 18 15 0.06 150 18 15 80 180 (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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0 0 3.0 INTERPRETATION OF RESULTS 0

0 Review of all 2011 REMP analysis results was performed to identify changes in 0 environmental levels as a result of station operations. The following section depicts and 0 explains the review of these results. Sample data for 2011 was compared to preoperational and historical data. Over the years of operation, analysis and collection changes have taken place that do not allow direct comparisons for some data collected from 1984 (preoperational) 0 through 2011. Summary tables containing 2011 information required by Technical 0 Specification Administrative Control 5.6.2 are located in Appendix B.

0 Evaluation for significant trends was performed for radionuclides that are listed as required 0 within Selected Licensee Commitments 16.11-13. The radionuclides include: H-3, Mn-54, 0 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 0 particulates was initiated in 1996. Other radionuclides detected that are the result of plant 0 operation, but not required for reporting, are trended.

0 No Selected Licensee Commitments radionuclides reporting levels were exceeded in 2011 0 due to CNS station operations. However, during the Fukushima Daiichi fallout period several samples exceeded Selected Licensee Commitment reporting levels for 1-131 and are 0 indicated in the table below.

0 Sample Media Date Locations Broadleaf Vegetation 4/5/2011 200, 201,226, 258 0 Milk 3/29/2011 221 Milk 4/12/2011 221 0

0 Because the radioactivity exceeding reporting levels was attributed to Fukushima Daiichi no 0 reports were made to the NRC.

Trending was performed by comparing annual mean concentrations of any effluent related 0 detected radionuclide to historical results. Levels of 1-131, Cs-134, and Cs-137 increased 0 during the Fukushima Daiichi fallout period and comparisons were made to distinguish Fukushima Daiichi activity and normal activity. Samples taken during media-specific 0 Fukushima Daiichi fallout periods (table below) were included in the trend evaluations.

0 Sample Media Fukushima Daiichi Period 0 Air Particulate/Radioiodine 3/15/2011 - 4/19/2011 0 Milk 3/292011 - 4/26/2011 0 Broadleaf Vegetation Crops 4/5/2011 Not Applicable

• 0 *Cropswere seasonallyunavailable duringFukushimaDaiichi Periodat CatawbaNuclear Station 0 A comparison of annual mean concentrations of effluent-based detected radionuclides to historical results provided trending bases. Frequency of detection and concentrations related Section 3 - Page I

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to SLC reporting levels (Table 2.2-A) were used as criteria for trending conclusions. All 2011 0

maximum percentages of reporting levels attributed to CNS operation were well below the S 100% action level. The highest value noted during 2011 due to CNS operation was 4.87% for S H-3 in drinking water.

S Selected Licensee Commitment section 16.11-13 addresses actions to be taken if S radionuclides other than those required are detected in samples collected. The occurrences of S these radionuclides are the result of CNS liquid effluents which contained the radionuclides.

S During 1979-1986, all net activity results (sample minus background), both positive and S negative were included in calculation of sample mean. A change in the EnRad gamma S 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 S

the method used by the previous system was vulnerable to false-positive results. S S

All 2011 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 S radionuclides identified since the system change in late 1987. All negative concentration S values were replaced with zero for calculation purposes. Any zero concentrations used in S tables or graphs represent activity measurements less than detectable levels.

Review of all 2011 data presented in this section supports the conclusion that there were no significant changes in environmental sample radionuclide concentrations of samples collected and analyzed from CNS site and surrounding areas that were attributable to plant operations.

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0 0 3.1 AIRBORNE RADIOIODINE AND PARTICULATES 0 In 2011, 260 radioiodine and particulate samples were analyzed, 208 from four indicator locations and 52 at the control location. Particulate samples were analyzed weekly for gamma S and gross beta. Radioiodine samples received a weekly gamma analysis. During 2011 there was an increase in 1-131 and Cs-137 concentrations due to Fukushima Daiichi fallout activity as 0 indicated in the tables below.

0 Air Particulate Annual Concentration with Annual Concentration without Analysis Fnkushlima Dalichi (pCi/m3) Fukushima Dalichi (eCi/m3)

Indicator FRL Control FRL Indicator FRL Control FRL 0

1-131 1.39E-2 1.54E-2 1.04E-2 1.16E-2 0.00 0 0.00 0 0 Cs-137 3.92E-3 1.96E-4 0.00 FRL = Fraction of Selected Licensee Commitment Reporting Level 0 0.00 0 0.00 0 0

Air Radioiodine Annual Concentration with Annual Concentration without Analy'sis Fnkushima Daiichi (pCi/m)* Fukushima Dalichi (pCi/M*)

Indicator FRL =Control FRL Indicator FRL [ Control FRI 0 1-131 5.53E-2 6.14E-2 I 5.65E-2 6.28E-2 0.00 0 [ 0.00 0 FRL = Fraction of Selected Licensee Commitment Reporting Level 0

0 There was no detectable 1-131 in air samples in 2011 due to CNS plant operations. Table 3.1-B gives the highest indicator location annual mean (including Fukushima Daiichi ) and 0 control location annual mean (including Fukushima Daiichi ) for 1-131 since the 0 preoperational period. The table shows similar concentrations (excluding Fukushima Daiichi )

for both the indicator and control locations and the activities decreasing from early in the 0 operational history of the plant. No 1-131 activity due to CNS plant operations has been detected since 1987.

0 0 Figure 3.1 shows individual sample gross beta results for the indicator location with highest 0 annual mean and the control location samples during 2011. The two sample locations' results are similar in concentration and have varied negligibly since preoperational periods.

0 There were no detectable gamma emitters identified for particulate filters analyzed during 0 2011 due to CNS plant operation. Table 3.1-A shows the highest indicator annual mean and control location annual mean for gross beta in air particulate.

There was no detectable 1-131 in air radioiodine samples analyzed in 2011 due to CNS plant operation. Table 3.1-B shows the highest indicator annual mean and control location annual mean for 1-131 since 1984 (preoperational period).

K-40 and Be-7 that occur naturally were routinely detected in charcoal cartridges collected during the year. Cs- 137 detection on the charcoal cartridge was determined in 1990 to be an active constituent of the charcoal. A similar study was performed in 2001 again yielding this conclusion (reference 6.13). Therefore, any Cs-137 activities were not used in any dose calculations in Section 4.0 of this report.

Section 3 - Page 3

0 0

0 Radioactivity identified in CNS air particulate and airborne radioiodine samples during the period of 3/15/2011 through 4/19/2011 was determined to be from the Fukushima Daiichi incident based on the following: 0 (1) The quantities of radioactive airborne effluents from Catawba Nuclear Station during 0

2011 did not increase significantly compared to year 2010. 0 (2) REMP sample results have not detected the presence of these isotopes in airborne particulate and airborne radioiodine samples since 1987.

0 (3) The concentrations being detected in the indicator samples were also identified in the control samples for Catawba Nuclear Station. 0 (4) Similar results were seen at other US nuclear plants and state and local government 0 monitoring agencies.

As such, the atypical detection of these radionuclides in both indicator and control samples is credibly attributed to the trans-Pacific transport of airborne releases from Fukushima Daiichi S following the March 11, 2011 Tohoku earthquake and is not related to the operations of Catawba 0 Nuclear Station.

0 Figure 3.1 0 pCi/m 3 1.OOE-01 Concentration of Gross Beta in Air Particulate S 9.OOE-02 0

8.00E-02 0

7.00E-02 0

6.00E-02 0 5.00E-02 3.00E-02 0 2.OOE-02 1.00E-02 0.00E+00 1984 1987 1990 1993 1996 1999 2002 2005 2008 2011 I -- Indicator Location --- Control Location There is no reportinglevelfor gross beta in airparticulate Section 3 - Page 4

Table 3.1-A Mean Concentration of Gross Beta in Air Particulate 0 Year Indicator Location (pCi/m 3) Control Location (pCi/m 3) 1984 2.25E-2 1.82E-2 1985 2.12E-2 1.53E-2 0 1986 3.62E-2 3.41E-2 1987 2.67E-2 2.32E-2 1988 2.29E-2 2.30E-2 1989 2.1IE-2 2.13E-2 1990 2.39E-2 2.72E-2 1991 2.19E-2 2.5 1E-2 1992 1.90E-2 2.01E-2 1993 1.87E-2 1.94E-2 1994 2.03E-2 2.03E-2 1995 4.88E-2 3.23E-2 0 1996 3.49E-2 2.60E-2 1997 2.83E-2 2.28E-2 1998 2.69E-2 2.12E-2 1999 2.53E-2 2.04E-2 2000 2.28E-2 1.86E-2 2001 1.76E-2 1.78E-2 2002 1.60E-2 1.57E-2 2003 1.54E-2 1.42E-2 2004 1.65E-2 1.49E-2 2005 1.66E-2 1.68E-2 2006 1.74E-2 1.74E-2 2007 1.88E-2 1.86E-2 2008 1.80E-2 1.90E-2 2009 1.78E-2 1.72E-2 2010 2.03E-2 1.90E-2 Average (2001 - 2010) 1.74E-2 1.71E-2 2011 1.98E-2 1.92E-2 S

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

Year Indicator Location Cl/rn Control Location (pCl/rn 1984 1.30E-3 1.46E-2 1985 4.75E-3 2.38E-2 1986 1.43E-2 1.02E-2 1987 1.38E-2 0.OOEO 1988 0.O0E0 0.00E0 1989 0.00E0 0.OOEO 1990 O.OOEO O.OOEO 1991 O.00E0 O.00E0 1992 O.00E0 0.00E0 1993 O.OOE O.00E0 1994 O.OOEO O.00E0 1995 0.OOEO O.OOEO 1996 O.00E0 O.00E0 1997 0.OOEO 0.OOEO 1998 0.OOEO 0.OOEO 1999 0.OOEO 0.OOEO 2000 0.OOEO 0.OOEO 2001 0.00E0 0.00E0 2002 0.00E0 0.OOEO 2003 0.00E0 0.OOEO 0 2004 0.OOEO 0.OOEO 2005 0.OOEO 0.OOEO 2006 0.OOEO 0.OOEO 2007 0.OOEO 0.OOEO 2008 0.OOEO O.OOEO 2009 0.OOEO 0.OOEO 2010 0.OOEO 0.OOEO 2011 5.53E-2 5.65E-2 S

.OOEO = no detectable measurements 2011 concentration affected by Fukushima Daiichi S It St It St 0t St St S

St St St Section 3 -Page 6 5 S

St

0 0

0 3.2 DRINKING WATER 0

Gross beta and gamma spectroscopy were performed on 26 drinking water samples. The 0 samples were composited to create 8 quarterly samples that were analyzed for tritium. One indicator location was sampled, along with one control location.

No gamma emitting radionuclides were identified in 2011 drinking water samples. There 0 have been no gamma emitting radionuclides identified in drinking water samples since 1988.

0 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 0 release point) average concentration was 2.01 pCi/I in 2011 and the control location concentration was 1.71 pCi/l. The 2010 indicator mean was 1.84 pCi/l. The table shows that 0 current gross beta levels are not statistically different from preoperational concentrations.

Tritium was detected in the four indicator samples and the four control samples during 2011.

The mean indicator tritium concentration for 2011 was 973 pCi/l, 4.87% of reporting level.

The mean control tritium concentration for 2011 was 636 pCi/l, 3.18% of reporting level.

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

The concentration of tritium in drinking water is affected by releases from the Catawba plant 0 and the McGuire Nuclear Station, located approximately 40 miles upstream of the Catawba plant on the Catawba River.

0 The dose for consumption of water was less than one mrem per year, historically and for 2011; therefore low-level iodine analysis is not required.

0 0

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0 Section 3 - Page 7

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Figure 3.2 pci/li ter Concentration of Tritium in Drinking Water 5000 0

4500 0

4000 3500 3000 2500 2000 0

1500 1000 0 500 0

0 1984 1987 1990 1993 1996 1999 2002 2005 2008 2011 0 I -iW- Indicator Location Control Location 120% Reporting Level I 0 0

Table 3.2 Mean Concentration of Radionuclides in Drinking Water Gross Beta (pCi/l) Tritium (pCi/l) 0 YEAR Indicator Control Indicator Control Location Location Location Location 1984 4.72 1.83 3.10E-2 3.10E-2 1985 1986 2.70 3.11 2.24 2.26 4.13E2 7.23E2 4.00E2 7.33E2 0

1987 3.10 2.40 7.80E2 4.80E2 0 1988 3.60 2.60 6.64E2 0.OOEO 1989 3.60 2.90 8.91E2 5.72E2 0 1990 4.50 3.20 7.03E2 0.OOEO 1991 1992 3.70 3.20 2.20 2.40 7.04E2 7.65E2 0.OOEO 5.38E2 0

1993 3.50 2.50 7.06E2 0.OOEO 0 1994 3.30 2.70 0.00E0 0.OOEO 1995 4.80 4.50 4.28E2 2.21E2 1996 3.08 3.14 3.71E2 3.27E2 1997 3.74 3.15 3.54E2 2.28E2 0 1998 2.51 2.44 5.07E2 1.83E2 1999 3.55 2.48 6.71E2 2.70E2 2000 2001 3.04 3.49 2.27 2.30 5.87E2 8.66E2 3.26E2 4.50E2 0

2002 3.44 2.36 1.22E3 4.11E2 2003 2.27 2.02 6.36E2 2.88E2 2004 1.88 1.69 5.47E2 2.54E2 2005 2.05 1.84 7.69E2 4.50E2 2006 2.30 2.17 1.59E3 7.70E2 2007 2.34 2.21 1.65E3 9.18E2 2008 2.81 2.16 1.25E3 9.16E2 2009 2.07 1.99 6.34E2 6.81E2 2010 1.84 1.80 7.05E2 4.27E2 2011 2.01 1.71 9.73E2 6.36E2 O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 8

S 0

0 0

3.3 SURFACE WATER 0

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 indicator locations and one control location were sampled. One indicator location (208) is 0 located near the liquid effluent discharge point.

0 All 2011 indicator location samples contained tritium with an average concentration of 4,631 0 pCi/I. Indicator Location 208 (Discharge Canal) showed a range of activities from 4,770 to 11,300 pCi/I which had the highest mean concentration of 8,285 pCi/l. Tritium was detected 0 in all four control samples during 2011 with an average concentration of 541 pCi/l.

0 Gamma spectroscopy analysis detected Co-58 and Co-60 in one indicator sample during 2011. Co-58 was detected at location 208 at 8.75 pCi/1 which represents 0.88% of the 0 reporting level and Co-60 was detected at location 208 at 19.6 pCi/I which represents 6.53%

of the reporting level. Table 3.3 summarizes the indicator annual means of radionuclides 0 detected since the change in the gamma spectroscopy analysis system in 1987. Visual 0 inspection of the tabular data did not reveal any increasing trends.

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

Table 3.3 lists the highest indicator annual means.

The concentration of tritium in surface water is affected by releases from the Catawba plant 0 and the McGuire Nuclear Station, located approximately 40 miles upstream of the Catawba plant on the Catawba River.

0 0

0 0

0 0

0 Section 3 - Page 9

0 0

Figure 3.3 0

pCi/liter Concentration of Tritium in Surface Water 40000 35000 0 30000 0 25000 20000 - 0 15000 _ __

10000 0

/-r' 5000 0

0 1984 6=698 1987 9

1990 1993

.199 1996 J996 S99 .64 1999 2002 2005 2005 2

2008 2

2011 0

1 Indicator Location Control Location 7There is no reportinglevel for tritium in surface water,however, ifno drinking waterpathway exists, a value of30, 000pCO/ may be used A drnning 0

water pathway existsfor CatawbaNuclearStation, so this limit does not applyfor surfacewater. See section 3.2for drinking waterresults.

0 Table 3.3 Mean Concentrations of Radionuclides in Surface Water (pCi/1) 0 0

YEAR Co-58 Co-60 Nb-95 Cs-137 H-3 Indicator H-3 Control 1984 4.59E-1 5.71E-1 6.48E-1 9.08E-1 3.35E2 3.18E2 1985 3.46E0 4.83E-2 2.70E0 8.19E-1 1.19E3 5.05E2 1986 3.10E-1 -4.12E-2 2.05E0 4.85E-1 2.34E3 5.05E2 0 1987 0.00E0 3.10E0 4.30E0 9.90E0 4.17E3 6.20E2 1988 1989 9.20E0 0.00E0 0.00E0 0.00E0 0.OOEO 0.00E0 0.00E0 0.OOEO 6.03E3 5.27E3 6.07E2 0.OOEO 0

1990 1991 6.50E0 0.00E0 0.00E0 0.00E0 3.98E3 7.73E2 0 0.00E0 0.00E0 0.00E0 0.00E0 4.87E3 0.00E0 1992 O.00E0 0.OOEO 0.OOEO 0.00E0 6.91E3 6.64E2 0 1993 4.70E0 1.80E0 0.00E0 0.00E0 5.98E3 0.OOEO 1994 1995 0.00E0 0.OOEO 0.00E0 0.OOEO 0.OOEO 0.00E0 0.00E0 0.OOEO 8.42E3 5.13E3 0.OOEO 2.89E2 0

1996 0.00E0 0.00E0 0.00E0 0.00E0 7.36E3 2.61E2 1997 0.00E0 0.OOEO 0.00E0 0.00E0 7.77E3 2.20E2 1998 0.00E0 0.00E0 0.00E0 0.00E0 6.61E3 0,00E0 1999 0.00E0 0.00E0 0.OOEO 0.00E0 8.13E3 2.41E2 2000 0.00E0 0.OOEO 0.OOEO 0.OOEO 7.19E3 2.56E2 2001 0.00E0 0.OOEO 0.00E0 0.00E0 7.13E3 3.28E2 2002 O.00E0 0.00E0 0.00E0 0.00E0 1.00E4 3.80E2 2003 0.00E0 0.00E0 0.00E0 0.00E0 1.31E4 2.37E2 2004 0.00E0 0.00E0 0.00E0 0.00E0 9.43E3 2.60E2 2005 0.00E0 0.00E0 0.00E0 0.00E0 1.40E4 3.78E2 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.67E4 5.83E2 2007 0.OOEO 0.OOEO 0.00E0 0.OOEO 1.01E4 7.82E2 2008 6.80E0 1.16E1 0.00E0 0.OOEO 6.02E3 6.31E2 2009 9.40E0 1.06E1 0.00E0 0.00E0 3.93E3 5.29E2 2010 0.OOEO 0.00E0 0.00E0 0.OOEO 7.26E3 2.94E2 2011 8.75E0 1.96E1 0.00E0 0.OOEO 8.29E3 5.41E2 0.OOEO = no detectable measurements 1984- 1986 mean based on all net activity Section 3 - Page 10

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0 3.4 GROUND WATER 0

A total of four ground water samples was collected and analyzed for gamma emitters and 0 tritium. There is one indicator location and no control location. Naturally occurring K-40 0 was the only radionuclide identified during 2011.

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

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Section 3 - Page 11

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0 3.5 MILK 0 0

A total of 26 milk samples was analyzed by gamma spectroscopy and low level iodine during 2011. There was one control location sampled. No indicator dairies were 0

identified by the 2011 land use census. Iodine-131 was identified in three control milk 0 samples due to Fukushima Daiichi fallout activity as indicated in the table below. 0 0

Annual Concentration with Annual Concentration without 0 Analvsis Fukushima Daiichi (pCi/1) Fukushimia Daiichi (pCi/I)

Indicator FRL Control FRI, Indicator FRIL Control FRL 0

LLI-131 NA NA 6.86 2.29 NA NA 0.00 0 0

FRL = Fraction of Selected Licensee Commitment Reporting Level 0 0

There were no gamma emitting radionuclides due to CNS plant operations identified in milk samples during 2011. Airborne Cs-137 has not been released from the plant since 0 1992. 0 Cs-137 was last detected in an indicator 0

sample during 1996. The occurrence of 0 Cs-137 in milk samples has been noted 0 several times since 1984. Cs-137 0 attributable to past nuclear weapons testing is known to exist in many 0 environmental media at low, highly 0 variable levels. 0 Table 3.5 lists highest indicator location 0 annual mean and control location 0 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, 0

reported in milk samples since 1988. 0 0

Radioactivity identified in the CNS milk samples collected during the period of 3/29/2011 through 4/26/2011 was determined to be from the Fukushima Daiichi incident 0

based on the following: 0 (1) The quantities of radioactive airborne effluents from Catawba Nuclear Station 0 during 2011 did not increase significantly compared to year 2010. 0 (2) REMP sample results have not detected the presence of radionuclides in milk 0 samples since 1996. 0 (3) There are no indicator milk locations for Catawba Nuclear Station. Concentrations being detected were identified in the control samples only for Catawba Nuclear 0

Station. 0 0

0 0

Section 3 - Page 12 0 0

0 0

0

• (4) Similar results were seen at other US nuclear plants and state and local government monitoring agencies.

As such, the atypical detection of these radionuclides in control samples is credibly attributed to the trans-Pacific transport of airborne releases from Fukushima Daiichi following the March 11, 2011 Tohoku earthquake and is not related to the operations of

• Catawba Nuclear Station.

0 Table 3.5 Mean Concentration of Radionuclides in Milk YEAR Cs-137 Indicator (pCI/) Cs-137 Control (pCi/1) 1984 2.95E0 2.98E0 1985 2.11EO 2.12EO 0 1986 3.76E0 4.54E0 1987 5.00E0 5.50E0 1988 3.20E0 3.80E0 1989 0.OOEO 0.00E0 1990 8.00E0 6.70E0

• 1991 0.00E0 0.00E0 1992 3.40E0 5.00E0 1993 5.OOEO 0.OOEO 1994 2.80E0 0.00E0 1995 8.60E0 0.OOEO 1996 6.05E0 0.OOEO 1997 0.00E0 0.00E0 1998 0.00E0 0.00E0 1999 0.00E0 0.00E0 2000 0.OOEO 0.OOEO 2001 0.00E0 0.OOEO 2002 0.00E0 0.00E0 2003 0.OOEO 0.00E0 2004 NO INDICATOR LOCATION O.O0EO 2005 NO INDICATOR LOCATION 0.OOEO 2006 NO INDICATOR LOCATION 0.OOEO 2007 NO INDICATOR LOCATION 0.OOEO 2008 NO INDICATOR LOCATION 0.OOEO 2009 NO INDICATOR LOCATION 0.OOEO 2010 NO INDICATOR LOCATION 0.OOEO S 2011 NO INDICATOR LOCATION 0.OOEO O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity 0

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• Section 3 -Page 13 0

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0 3.6 BROADLEAF VEGETATION 0 0

Gamma spectroscopy was performed on 60 broadleaf vegetation samples during 2011. 0 Four indicator locations and one control location were sampled. During 2011 there was an increase in 1-131, Cs-134, and Cs-137 concentrations due to Fukushima Daiichi fallout 0

activity as indicated in the tables below. 0 Broadleaf Vegetation 0 Annual Concentration with Annual Concentration without 0 Analysis Fukushima Daiichi (pCi/kg) Fukushima Daiichi (pCi/kg)

Indicator FRL Control FRL Indicator FRL Control FRL 0 1-131 132 1.32 156 1.56 0.00 0.00 0.00 0.00 Cs-134 12.8 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0 Cs-137 26.2 0.01 0.00 0.00 26.2 0.01 0.00 0.00 0 FRL = Fraction of Selected Licensee Commitment Reporting Level 0

Five of the forty-eight samples collected at indicator locations contained detectable Cs-137 activity. Two of the Cs-137 detections were attributable to Fukushima Daiichi 0 fallout activity since they were observed at locations that have not historically indicated 0 Cs- 137 activity. Cs- 137 was detected in three of the twelve samples collected at Location 0 201. The highest concentration detected at Location 201 was 38.8 pCi/kg which is 1.94%

of the reporting level. Cs-137 was not detected in the control location samples.

Figure 3.6 shows indicator and control annual 0 means for Cs-137 in vegetation since 1984.

Table 3.6 lists indicator and annual means.

Values shown from 1984 to 2011 show a stable 0 trend for Cs-137 in vegetation.

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

0 K-40 and Be-7 were observed in broadleaf 0 vegetation samples. 0 Radioactivity identified in the CNS broadleaf vegetation samples collected 4/5/2011 was 0

determined to be from the Fukushima Daiichi incident based on the following: 0 (1) The quantities of radioactive airborne effluents from Catawba Nuclear Station during 2011 did not increase significantly compared to year 2010.

(2) Similar results were seen at other US nuclear plants and state and local government monitoring agencies.

Section 3 - Page 14

S 0

0 0 (3) Cs-137 detected at location 201 on 4/5/2011 was not attributed to Fukushima Daiichi because it has historically been detected at this location.

0 As such, the atypical detection of these radionuclides in both indicator and control samples 0 is credibly attributed to the trans-Pacific transport of airborne releases from Fukushima Daiichi following the March 11, 2011 Tohoku earthquake and is not related to the 0 operations of Catawba Nuclear Station.

0 Figure 3.6 0 pCi/kg Concentration of Cs-137 in Broadleaf Vegetation 0 1200 0 1000 0 800 0 600 O

400 0

0 200 0 1984 1987 1990 1993 1996 1999 2002 2005 2008 2011 0 - Indicator Location A-- Control Location - 50% Reporting Level 0

0 0

0 0

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0 Section 3 - Page 15

0 Table 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation S YEAR Cs-137 Indicator (pCI/k2 Cs-137 Control (pCi/ka) 1984 3.76E1 1.30El 1985 5.48E1 4.16E1 1986 7.42E1 2.22E1 1987 6.10El 5.10El 1988 9.10E1 7.40E1 1989 L.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.OOEI O.OOEO 1995 3.60E1 0.OOEO 1996 2.23E2 6.22E1 1997 7.57E1 0.OOEO 1998 6.53E1 0.OOEO 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 2010 3.77E1 0.OOEO 2011 2.62E1 0.00E0 O.OOEO = no detectable measurements.0 1984 - 1986 mean based on all net activity 2011 concentration affected by Fukushima Daiichi 0

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Section 3 -Page 16 0 0

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• 3.7 FOOD PRODUCTS

• Collection of food product samples (crops) from an irrigated garden

• began in 1989. The irrigated garden at Location 253 was discontinued by the owner in 2011 and was replaced by another irrigated garden. The

• replacement irrigated garden is located on Lake Wylie downstream

• from CNS, Location 260. During the 2011 growing season, five samples were collected and analyzed for gamma radionuclides. There is no

• control location for this media type.

• Crops were seasonally unavailable during the Fukushima Daiichi period at Catawba

• Nuclear Station.

0Table 3.7 shows Cs-137 indicator location highest annual mean concentrations since

• 1989.

• Table 3.7 Mean Concentration of Radionuclides in Food Products

• YEAR Cs-137 Indicator (pCi/kg) 1989 O.OOEO 1990 O.OOEO 1991 O.OOEO 1992 O.OOEO 1993 2.50E1 1994 0.OOEO 1995 0.OOEO 1996 0.OOEO 1997 0.OOEO 1998 0.OOEO 1999 0.OOEO 2000 0.OOEO 2001 0.OOEO 2002 0.00E0 2003 0.00E0 2004 0.OOEO 2005 0.OOEO 2006 0.OOEO 2007 0.OOEO 2008 0.OOEO 2009 0.OOEO 2010 0.OOEO 2011 0.OOEO 0 0.OMEO = no detectable measurements There is no control location for Food Products.

0 0

• Section 3 -Page 17 0

0

0 0

0 3.8 FISH 0

Gamma spectroscopy was performed on S 12 fish samples collected during 2011. 0 One downstream indicator location and one control location were sampled.

0 Co-58, Co-60, and Cs-137 are normally the predominant radionuclides identified 0 in fish samples. Cs-137 was detected in one indicator sample in 2011 at a concentration of 21.6 pCi/kg, which is 1.08% of the reporting level. Cs-137 was not detected in any control location 0 samples.

0 Figures 3.8-1, 3.8-2, and 3.8-3 are graphs displaying annual mean concentrations for 0 Co-58, Co-60, and Cs-137. Table 3.8 depicts the highest indicator location annual mean for radionuclides detected. In addition, radionuclides identified in fish samples since 0 1988 have been included in the table. Overall, radionuclides have not shown a significant 0 trend or accumulation.

K-40 was observed in some fish samples collected during 2011. 0 0

Figure 3.8-1 pCI/kg Concentration of Co-58 in Fish 0

2000 1800 0

1600 0 1400 0 1200 S

1000 _____

S 800 0

600 400 0

200 0p -f-t 1984 1987 1990 1993 1996 1999 2002 2005 2008 2011 Indicator Location - Control Location -5  % Repor~tin~gLevel.

Section 3 - Page 18

0 0

0 0 Figure 3.8-2 S

0 pCi/kg 700 Concentration of Co-60 in Fish 0

600 0 500 0 400 0

300 0 200 100 0-4 1984 1987 1990 1993 1996 1999 2002 2005 2008 2011 I -A- Indicator Location --* Control Location -5% Reporting Level I 0 Figure 3.8-3 0

0 pCi/kg 600 ,

Concentration of Cs-137 in Fish 0

0 500 0 400 0

0 300 0 200 0

100

'N 0 0+/-

0 1984 1987 1990 1993 1996 1999 2002 2005 2008 2011 0 1 Al Indicator Location - Control Location - 20% Reporting LevelI 0

0 0

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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 O.OOEO O.OOEO O.OOEO 1985 7.68E-1 3.40E1 9.11EO 3.22E0 1.28E1 5.07E0 O.OOEO O.OOEO 0.OOEO 1986 2.01El 1.86E2 4.01El 3.51E1 9.29E1 O.OOEO 7.30E0 O.OOEO O.OOEO 1987 7.24E0 7.57E1 4.81E1 3.83E0 4.27E1 5.40E0 O.OOEO O.OOEO O.OOEO 1988 2.85E1 140E2 9.70E1 1.67E1 8.24E1 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1989 8.28E0 1.33E2 3.83E1 1.47E1 4.37E1 8.58E-1 0.OOEO 0.OOEO 0.OOEO 1990 2.51E1 1.75E2 7.77E1 1.32E1 4.66E1 3.33E0 0.OOEO 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.OOEO 0.OOEO 0.00E0 1993 2.14E1 3.58E2 1.21E2 2.73E0 2.56E1 0.OOEO 0.OOEO 0.00E0 0.OOEO 1994 1.91E0 4.75E1 1.81E1 0.OOEO 1.75E1 0.00E0 0.00E0 0.OOEO 1.45E1 1995 5.65E1 8.90E2 2.66E2 0.OOEO 6.77E1 1.38E1 0.OOEO 0.OOEO 0.OOEO 1996 0.OOEO 5.95E1 6.68E1 0.OOEO 3.02E1 0.OOEO 0.00E0 0.OOEO 0.00E0 1997 0.OOEO 4.93E1 9.88E0 0.OOEO 2.74E1 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1998 0.OOEO 6.44E1 2.86E1 0.OOEO 1.58E1 0.00E0 0.OOEO 0.OOEO 0.OOEO 1999 0.OOEO 3.12E1 2.71E1 0.OOEO 1.87E1 0.00E0 0.00E0 0.00E0 0.OOEO 2000 0.OOEO 2.13E2 2.69E2 0.00E0 1.52E1 0.00E0 0.OOEO 0.OOEO 0.OOEO 2001 0.OOEO 4.66E1 0.OOEO 0.OOEO 2.08E1 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2002 0.OOEO 5.23E1 7.OOEl 0.OOEO 1.73E1 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2003 0.OOEO 1.43E2 2.61E1 0.00E0 1.19El 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2004 4.92E1 1.81El 0.00E0 0.00E0 0.00E0 0.OOEO 0.00E0 0.OOEO 0.00E0 2005 0.00E0 0.OOEO 0.00E0 0.OOEO 0.OOEO 0.OOEO 0.00E0 0.00E0 0.OOEO 2006 0.OOEO 0.00E0 0.OOEO 0.OOEO 1.44E1 0.OOEO 0.OOEO 0.00E0 0.00E0 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 0.00E0 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2009 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO O.OOEO 2010 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2011 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2.16E1 0.OOEO 0.OOEO 0.OOEO 0.OOEO O.OOEO = no detectable measurements S

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0 0 3.9 SHORELINE SEDIMENT During 2011, a total of 6 shoreline sediment samples was analyzed, four from two 0 indicator locations and two from the control location.

Co-58, Co-60, and Cs-137 were identified in two samples collected from indicator 0 location 208, which is closest to the plant's liquid effluent release point. Co-57 and Cs-134 were identified in one sample collected from location 208. Naturally occurring 0 K-40 was identified in many of the indicator and control locations. Activity released in 0 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 0 radionuclides was location 208. Radionuclides identified at location 208 consist of 0 Co-57 with an annual mean concentration of 10.5 pCi/kg, Co-58 with an annual mean concentration of 83.6 pCi/kg, Co-60 with an annual mean concentration of 236 pCi/kg, 0 Cs-134 with an annual mean concentration of 36.2 pCi/kg, and Cs-137 with an annual mean concentration of 43.3 pCi/kg. Co-57 and Cs-134 are normal in plant effluents and 0 though not usually detected in the environment, their presence is not unexpected.

Naturally occurring K-40 and Be-7 were also identified in samples from this location.

S 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.

S Figures 3.9-1, 3.9-2, and 3.9-3 are graphs displaying annual mean concentrations for 0 Co-58, Co-60, and Cs-137.

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

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600 400 200 -

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• 1984 1987 1990 1993 1996 1999 2002 2005 2008 2011 4-- Indicator Location 0 Control Location There is no reportinglevel for Co-58 in Shoreline Sediment Section 3 - Page 21

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Figure 3.9-2 0

0 PCIl /kg Concentration of Co-60 in Shoreline Sediment 2000 1800 1600 0 1400 1200 0

1000 0

800 600 400 0 200 0 a 0 0 0 Ole 0 1984 1987 1990 1993 1996 1999 2002 2005 2008 2011 1 Indicator Location Control Location 0

There is no reportinglevel for Co-60 in Shoreline Sediment 0

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pCl/ki Concentration of Cs-137 in Shoreline Sediment S

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400 I I t I 4 4 4 *1- 1-- 0 350 4 4 4 4 4 4 4 .4. .4.- 0 300 0 250 0 200 150 10 0 .a-.-a a-~--~ ~ a-a--a a 1984 1987 1990 1993 1996 1999 2002 2005 2008 2011

--- Indicator Location +- Control Location There is no reportinglevel for Cs-137 in Shoreline Sediment Section 3 - Page 22

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 3.19EI 1.07E2 0.OOEO 0.OOEO 1985 -3.12E0 1.16E2 5.18E0 0.OOEO 0.00E0 2.11 E2 2.97E2 0.OOEO 0.OOEO 1986 1.09E2 3.79E2 2.05E2 0.00E0 3.96E1 6.50E1 1.61E2 0.00E0 0.00E0 1987 8.83E1 4.08E2 1.61E2 4.22E1 0.00E0 6.08E1 1.26E2 0.OOEO 0.00E0 1988 1.07E2 3.29E2 2.63E2 2.28E1 7.54E0 2.59E1 1.07E2 7.65E-1 3.68E0 1989 4.58El 1.94E2 1.21E2 5.02E0 0.OOEO 1.65E1 5.77E1 0.0OEO 1.57El 1990 5.39E1 2.08E2 1.77E2 0.OOEO 0.00E0 1.66E1 8.18E1 0.00E0 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 0.00E0 1.69E1 1.07E2 3.00E0 2.70E1 1993 1.33E2 1.07E3 1.04E3 0.OOEO 0.OOEO 2.80E1 1.26E2 2.47E1 2.16E2 1994 4.93E1 7.98E2 5.73E2 0.00E0 0.00E0 5.67E0 1.07E2 4.38E0 4.60E1 1995 1.02E2 1.33E3 8.65E2 1.13E2 0.00E0 0.00E0 8.50E1 3.69E1 1.49E2 1996 8.73E1 3.39E2 5.81E2 0.OOEO O.OEO 0.OOEO 8.30E1 0.OOEO 1.96E2 1997 6.96E1 5.90E2 7.64E2 0.00E0 0.00E0 0.00E0 1.43E2 0.OOEO 1.76E2 0 1998 3.07E1 1.88E2 2.30E2 0.OOEO 0.00E0 0.OOEO 7.11 El 0.00E0 0.OOEO 1999 7.28E1 2.29E2 4.39E2 0.OOEO 0.OOEO 0.OOEO 9.42E1 0.OOEO 1.40E2 2000 0.OOEO 3.90E1 1.03E2 0.OOEO 0.OOEO O.OOEO 4.96E1 0.OOEO 0.OOEO

• 2001 3.86E1 8.27E1 3.29E2 0.OOEO 0.00E0 0.00E0 5.58E1 0.00E0 0.00E0 2002 3.51E1 2.41E2 2.22E2 0.OOEO 0.00E0 0.OOEO 8.83E1 0.OOEO 0.00E0 2003 2.17E1 8.75E1 1.08E2 0.00E0 0.00E0 0.00E0 2.69E1 0.OOEO 0.00E0 2004 6.60E1 2.67E2 3.83E2 0.OOEO 0.OOEO 0.00E0 3.79E1 0.OOEO 0.00E0 2005 O.00E0 1.61E2 1.41 E2 0.OOEO 0.00E0 0.OOEO 3.04E1 0.OOEO 0.00E0 2006 0.OOEO 5.40E 1 1.1 1E2 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2007 0.OOEO 8.77E1 9.46E1 0.OOEO 0.OOEO 0.OOEO 6.13E1 0.OOEO 0.OOEO 0 2008 0.OOEO 1.48E2 6.24E1 0.OOEO 0.OOEO 0.OOEO 2.57E1 0.OOEO 0.OOEO 2009 0.OOEO 1.10E2 1.04E2 0.OOEO 0.OOEO 0.OOEO 2.27E1 0.OOEO 0.OOEO 2010 0.OOEO 6.56E1 1.37E2 0.OOEO 0.OOEO 0.OOEO 2.56E1 0.OOEO 0.OOEO 2011 0.OOEO 8.36E1 2.36E2 0.OOEO 0.OOEO 3.62E1 4.33E1 1.05E1 0.OOEO O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Negative values are calculated as zeroes S

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3.10 DIRECT GAMMA RADIATION 3.10.1 ENVIRONMENTAL TLD In 2011, 164 TLDs were analyzed, 152 at indicator locations and 12 at control locations. TLDs are collected and analyzed quarterly. A transit background for environmental TLDs is determined based on ANSI N545. The highest annual mean exposure for an indicator location was 93.2 milliroentgen. The annual mean exposure for the control locations was 58.4 milliroentgen.

Figure 3.10-1 and Table 3.10-A show TLD inner ring (site boundary),

outerRing (4-5 miles), and control location annual averages in milliroentgen 0 per year. Preoperational data and rolling ten year operational data averages are 0 also given. As shown in the graph, inner ring, outer ring, and control data averages historically compare closely. Inner and outer ring averages comprise a number of data points with control averages representing only three locations.

Figures 3.10-2 and 3.10-3 show the TLD mean for each inner and outer ring TLD location from 1986 through 2011.

The calculated total body dose (from gaseous effluents) for 2011 was 2.01E0 0 mrem, which is 2.55% of the average inner ring TLD values. Therefore, it can be concluded that discharges from the plant had very little impact upon the measured TLD values.

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

3.10.2 ISFSI M The Catawba Independent Spent Fuel Storage Installation (ISFSI) is a secured area constructed to provide dry storage for spent nuclear fuel. The principal components of the ISFSI are concrete vertical storage modules that hold stainless 0 steel dry storage canisters containing irradiated fuel assemblies.

The ISFSI is located approximately 300 meters north of the Unit 2 reactor 0 building. TLD results are evaluated quarterly to identify trends and demonstrate 0 compliance with dose and dose rate limits at the ISFSI boundaries, the Owner Control fence north of ISFSI and at the Exclusion Area Boundary in the west Section 3 - Page 24 0 0t 0t

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S sector. Catawba began storage of spent fuel at the ISFSI in 2007. Eight storage modules were loaded with spent fuel in 2011 for a total of twenty-four modules.

0 Doses measured by environmental TLDs show little or no change since the current TLD system was implemented.

0 Figure 3.10-1 0

0 mR/year S 250 r-0 200 S

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100 50 0

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Table 3.10-A Direct Gamma Radiation (TLD) Results 0 Inner Ring Average Outer Ring Average Control Average Year (mR/yr) (mRlyr) (mR/yr) 1984* 87.5 82.6 79.3 1985 117 109 109 1986 104 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 2002 78.8 69.5 55.2 2003 81.7 72.6 56.0 2004 78.6 73.8 55.6 2005 79.8 75.2 57.7 2006 76.9 73.6 57.2 2007 80.5 76.4 59.2 2008 81.5 77.1 60.4 2009 79.9 71.9 58.0 2010 81.4 71.6 57.2 Average (2001 - 2010) 80.0 73.2 57.2 2011 78.9 70.3 58.3 Preoperational Data 0

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0 Table 3.10-B Direct Gamma Radiation (TLD) Results Inner Ring (mR/year) 0 Sector 0 _ALocation) 1986 - 2010 Mean 1986 - 2010 Low 1986 - 2010 High 2011 0 N (222) 5.98E+01 3.63E+01 8.33E+01 7.00E+01 0 NNE (200) 7.25E+01 4.17E+01 9.54E+01 7.20E+01 0 NE (201) 7.22E+01 4.75E+01 9.76E+01 7.32E+01 ENE(255) 7.85E+01 4.74E+01 1.1IE+02 8.12E+01 E (223) 8.11EE+01 5.22E+01 1.06E+02 8.52E+01 0 ESE (203) 8.53E+01 5.32E+01 1.16E+02 7.92E+01 SE (225) 8.20E+01 5.66E+01 1.11E+02 8.00E+01 SSE (256) 8.11E+01 5.45E+01 1.05E+02 8.00E+01 S (226) 7.28E+01 4.81E+01 1.02E+02 7.32E+01 SSW (204) 8.12E+01 5.63E+01 1.05E+02 7,12E+01 SW (205) 8.35E+01 4.33 E+01 1.08E+02 8.40E+01 WSW (227) 7.75E+01 5.37E+01 1.05E+02 7.40E+01 W (228) 7.37E+01 4.97E+01 1.04E+02 7.60E+01 WNW (206) 8.77E+01 6.83E+01 1. 14E+02 9.20E+01 NW (229) 9.10E+01 6.27E+01 1.16E+02 8.80E+01 NNW (207) 8.91E+01 5.99E+01 1.08E+02 8.52E+01 Section 3 - Page 27

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S Figure 3.10-3 mR/year 0

Catawba Outer Ring (TLD) Results 160 -

140 0

120 100 80 60 40 0 20' 0 N

(230)

NNE (231)

NE (232)

ENE (233)

E (234)

ESE (235)

SE (236)

SSE (237)

S (238)

SSW (239)

SW (240)

WSW (241)

W (242)

WNW (243)

NW (244)

NNW (245) 0 1 -- 2011 - 1986 -2010 High/Low/Mean 0

Table 3.10-C Direct Gamma Radiation (TLD) Results Outer Rine (mR/year) 0 Sector 0

(Location) 1986 - 2010 Mean 1986 - 2010 Low 1986 - 2010 High 2011 N (230) 5.64E+01 3.72E+01 8.73E+01 5.40E+01 NNE (231) 7.14E+01 3.75E+01 8.75E+01 7.92E+01 0 NE (232) 8.71E+01 5.85E+01 1.17E+02 8.72E+01 ENE (233) 6.39E+01 3.50E+01 9.27E+01 6.20E+01 0 E (234) 8.41E+01 5.37E+01 1.11E+02 6.80E+01 ESE (235) 8.38E+01 4.89E+01 1.09E+02 6.92E+01 SE (236) 8.99E+01 6.60E+01 1.22E+02 8.52E+01 SSE (237) 8.89E+01 5.53E+01 1.34E+02 9.32E+01 S (238) 7.43E+01 5.24E+01 1.06E+02 6.80E+01 SSW (239) 7.44E+01 4.87E+01 1.06E+02 7.72E+01 SW (240) 5.38E+01 3.1OE+01 7.87E+01 5.32E+01 WSW (241) 5.68E+01 2.99E+01 8.29E+01 5.60E+01 W (242) 6.76E+01 4.31E+01 9.55E+01 6.9213+01 WNW (243) 6.97E+01 4.60E+01 9.47E+01 6.72E+01 NW (244) 6.67E+01 3.78E+01 9.26E+01 7.00E+01 NNW (245) 5.84E+01 2.95E+01 7.55E+01 6.72E+01 Section 3 - Page 28

0 0 3.11 LAND USE CENSUS 0

The 2011 Annual Land Use Census was conducted July 13, and July 14, 2011 as required 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 2011 census, one nearer residence was identified; no irrigated gardens S (superior to existing gardens) or milk locations were identified. The irrigated garden 0 location 253 (SSE sector, 1.90 miles), discontinued by the owner, was replaced by an irrigated garden in the SSE sector at 2.00 miles and assigned location 260 (reference 0 6.16). The nearest residence is located in the NE sector at 0.56 miles. No environmental program changes were required as a result of the 2011 land use census.

0 Table 3.11 Catawba 2011 Land Use Census Results 0

Sector Distance Sector Distance 0 (Miles) (Miles)

Nearest Residence 0.63 Nearest Residence 0.63 0 N Nearest Garden (irrigated) 1.55 S Nearest Garden 1.25 Nearest Milk Animal Nearest Milk Animal -

Nearest Residence 0.66 Nearest Residence 0.81 NNE Nearest Garden 4.39 SSW Nearest Garden 2.04 Nearest Milk Animal -

0 Nearest Milk Animal Nearest Residence 0.56 Nearest Residence 0.63 0 NE Nearest Garden Nearest Milk Animal 0.68 sw Nearest Garden Nearest Milk Animal 2.54 Nearest Residence 0.61 Nearest Residence 0.60 ENE Nearest Garden 2.84 wsw Nearest Garden 1.10 Nearest Milk Animal Nearest Milk Animal -

Nearest Residence 0.65 Nearest Residence 0.68 0 E Nearest Garden 3.51 w Nearest Garden 0.96 Nearest Milk Animal Nearest Milk Animal -

Nearest Residence 0.84 Nearest Residence 1.10 ESE Nearest Garden 3.83 WNW Nearest Garden 1.49 Nearest Milk Animal Nearest Milk Animal -

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

Nearest Residence 0.74 Nearest Residence 0.86 SSE Nearest Garden 1.64 NNW Nearest Garden 2.21 Nearest Milk Animal Nearest Milk Animal -

indicates no occurrences within the 5 mile radius Section 3 - Page 29

Figure 3.11 V

Catawba Nuclear Station 2011 Land Use Census Map Legend A CNSGardens

• CNSResidence

/VN CNSRailroads

- NavteqHwys NavteqStreets States m Counties NHD~aterbody Approximate location of features shown

+

0 0.5 1 2Miles Projection NCSP NAD27 a

Section 3 - Page 30