Text

Annual Radiological Environmental Operating Report
	ML11137A211
Person / Time
Site:	Catawba
Issue date:	05/11/2011
From:	Morris J; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML11137A211 (97)
	v • d • e

JAMES R. MORRIS LDuke ifEnergyo Vice President Duke Energy Corporation Catawba Nuclear Station 4800 Concord Road York, SC 29745 803-701-4251 May 11, 2011 803-701-3221 fax 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 2010 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 2010 Annual Radiological Environmental Operating Report. This report covers operation of Catawba Units 1 and 2 during the 2010 calendar year.

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

Sincerely, James R. Morris Attachment www. duke-energy.corn

U.S. Nuclear Regulatory Commission 2010 Annual Radiological Environmental Operating Report May 11, 2011 Page 2 xc (with attachment):

V. M. McCree 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 Sandra Flemming, Director Analytical & Radiological Environmental Services Division 8231 Parklane Road Columbia, SC 29223 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 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

S 0

0 0 Duke 0 Energy.

0 0

0 0 Catawba Nuclear Station 0

Units 1 and 2 0

0 0

0 FRLOP 0

0 0

0 Duke

° Energy.

0

ANNUAL RADIOLOGICAL

ENVIRONMENTAL OPERATING REPORT O

0 0

DUKE ENERGY CORPORATION

CATAWBA NUCLEAR STATION

Units 1 and 2 o

2010 0

o 0

0 0

0

0 0

0 O TABLE OF CONTENTS

1.0 Executive Summary . 1-1 2.0 Introduction 2-1 2.1 Site Description and Sample Locations 2-I 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 3.10.1 Environmental TLD 3-20 3.10.2 ISFSI 3-20 3.11 Land Use Census 3-25 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 5-3 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 References 6-I i

Appendices Appendix A: Environmental Sampling and Analysis Procedures A-I I. Change of Sampling Procedures A-2 II. Description of Analysis Procedures A-2 III. Change of Analysis Procedures . A-3 IV. Sampling and Analysis Procedures A-3 A. 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 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 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 3-2 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 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 3.10-1 Direct Gamma Radiation (TLD) Results 3-21 3.10-2 Catawba Inner Ring (TLD) Results 3-23 3.10-3 Catawba Outer Ring (TLD) Results 3-24 3.11 2010 Land Use Census Map 3-26 0

II 0 0

0 0

LIST OF TABLES 2.1-A Radiological Monitoring Program Sampling Locations 2-6 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites) 2-7 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 . 3-3 3.1-B Mean Concentration of Air Radioiodine (1- 13 1) . 3-4 3.2 Mean Concentrations of Radionuclides in Drinking Water 3-6 3.3 Mean Concentrations of Radionuclides in Surface Water 3-8 3.5 Mean Concentration of Radionuclides in Milk 3-10 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation 3-12 3.7 Mean Concentration of Radionuclides in Food Products 3-13 3.8 Mean Concentrations of Radionuclides in Fish 3-16 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment 3-19 3.10-A Direct Gamma Radiation (TLD) Results 3-22 3.10-B Direct Gamma Radiation (TLD) Results Inner Ring 3-23 3.10-C Direct Gamma Radiation (TLD) Results Outer Ring 3-24 3.11 Land Use Census Results . 3-25 4.1-A 2010 Environmental and Effluent Dose Comparison 4-3 4.1-B Maximum Individual Dose for 2010 based on Environmental Measurements for Catawba Nuclear Station 4-5 5.0-A 2010 Cross-Check Results for EnRad Laboratories 5-4 5.0-B 2010 Environmental Resource Associates QuikTM Response Program 5-9 5.0-C 2010 Environmental Dosimeter Cross-Check Results . 5-11 0

0 0

S 0

0 0

S 0

S S

0 iii S

S

w S

LIST OF ACRONYMS USED IN THIS TEXT (in alphabeticalorder)

S BW BiWeekly S C

CNS Control Catawba Nuclear Station S

DEHNR DHEC Department of Environmental Health and Natural Resources Department of Health and Environmental Control S

EPA Environmental Protection Agency S ERA GI-LLI Environmental Resource Associates Gastrointestinal - Lower Large Intestine S GPS ISFSI Global Positioning System Independent Spent Fuel Storage Installation S

LLD M

Lower Limit of Detection Monthly S

MDA Minimum Detectable Activity S MOA mrem Memorandum of Agreement Millirem S NIST NRC National Institute of Standards and Technology Nuclear Regulatory Commission S

ODCM pCi/kg Offsite Dose Calculation Manual picocurie per kilogram S

pCi/I picocurie per liter S pCi/m3 PIP picocurie per cubic meter Problem Investigation Program S Q

REMP Quarterly Radiological Environmental Monitoring Program S

SA SLCs Semiannually Selected Licensee Commitments S

SM Semimonthly S TECH SPECs TLD Technical Specifications Thermoluminescent Dosimeter S

[ICi/ml UFSAR microcurie per milliliter Updated Final Safety Analysis Report S

W Weekly S S

S S

S iv 6

S

0 0

S 0

1.0 EXECUTIVE

SUMMARY

O This Annual Radiological Environmental Operating Report describes the Catawba Nuclear Station Radiological Environmental Monitoring Program (REMP), and the program results for the calendar year 2010.

O Included are the identification of sampling locations, descriptions of environmental sampling O 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 0 potentially affected by station operations, and a summary of environmental radiological 0 sampling results. Quality assurance practices, sampling deviations, unavailable samples, and program changes are also discussed.

Sampling activities were conducted as prescribed by Selected Licensee Commitments 0 (SLCs). Required analyses were performed and detection capabilities were met for all O collected samples as required by SLCs. Eight-hundred ninety-six samples were analyzed O comprising 1,212 test results in order to compile data for the 2010 report. Based on the annual land use census, the current number of sampling sites for Catawba Nuclear Station is O sufficient.

0 O Concentrations observed in the environment in 2010 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, drinking water, shoreline sediment, and fish O are higher than the activities reported for samples collected prior to the operation of the 0 station. Measured concentrations were not higher than expected, and all positively identified measurements were within limits as specified in SLCs.

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

excluding TLD results, was 2.07E-01 mrem

for 2010. It is therefore concluded that station

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

S 0

0 0

S O ~Section I-Page I 0

0

2.0 INTRODUCTION

2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS

Duke Energy Corporation's Catawba Nuclear Station is a two-unit facility located on the shore of Lake Wylie in York County, South Carolina. Each of the two essentially identical units employs a pressurized water reactor nuclear steam supply system furnished by Westinghouse SElectric 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 concentrations in the discharge canal given comparable liquid effluent source terms.

Figures 2.1-1 and 2.1-2 are maps depicting the Thermoluminescent Dosimeter (TLD) monitoring locations and the sampling locations. The location numbers shown on these maps correspond to those listed in Tables 2.1-A and 2.1-B. Figure 2.1-1 comprises all sample locations within a one mile radius of CNS. Figure 2.1-2 comprises all sample locations within 0*a 10 mile radius of CNS.

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

1981, four years prior to operation of Unit 1 in 1985. The preoperational program provides data on the existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station. 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 0Commitments Manual, with regard to sample media, sampling locations, sampling frequency Sand analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other "man-made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related 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, 0

S

~~Section 2 -Pagel1 0

0 0

public and state and federal agencies concerned with the environment. Reporting levels for O activity found in environmental samples are listed in Table 2.2-A.

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

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

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

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

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

0 0

Section 2 -Page 2 0 0

S S

0

2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM

DETECTABLE ACTIVITY 0The 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%

0probability of falsely concluding that a blank observation represents a "real" signal. The

LLD is an a priori lower limit of detection. The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample size (mass or volume), the radiochemical yield and the radioactive decay of the sample between sample collection and counting. The "required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments

and are listed in Table 2.2-C.

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.

00 2.3.3 TREND IDENTIFICATION 5One 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 5removing radioactivity from the environment but that reactor operations are not adding that radionuclide to the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the concentration.

0 5Substantial 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 5weather 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 SChemobyl accident). Some of these factors may be obvious while others are sometimes

unknown. Therefore, how trends are identified will include some judgment by plant 5personnel.

Section 2 - Page 3 0

Figure 2.1-1 Section 2 - Page 4

- g0.@ee@@..e0..0...*..eoooeoeeoe@@eeeeeooed Figure 2.1-2 Catawba Nuclear Station Sampling Locations Map (Ten Mile Radius)

Legend

. TLD Locations A All Other Locations

- Public Roads y Rail Roads

,. County Boundary Incorporated Areas Water Appro: mate location of features show-n 0 1 2 3les Projection NCSP NAD27 Section 2 - Page 5

4-0 0

0 TABLE 2.1-A 0 0

CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS 0 S

Table 2. 1-A Codes W Weekl SM Semimonthly 0

BW M

NBiWeekly E Monthl SA Quarterly Semiannually 0

C Control I Indicator 0 0

Site

Measure Type Location Descrition* P Air Rad.

Surface Water Drinking Water Shoreline Food Fish Milk Broad Ground Sediment Products Leaf Water Part. (a) Veg. (b) 200 I Site Boundary (0.63 mi NNE) W M 201 I Site Boundary (0.53 mi NE) W M 205 I Site Boundary (0.25 mi SW) W 208 1 Discharge Canal (0.45 mi S) M SA SA 210 I Ebenezer Access (2.31 mi SE) SA 211 I Wylie Dam (4.06 mi ESE) M 212 I Tega Cay (3.32 mi E) W 214 1 Rock Hill Water Supply (7.30 mi SSE) M 215 216 C

C River Pointe - Hwy 49 (4.21 mi NNE)

Hwy 49 Bridge (4.19 mi NNE)

M SA SA 0

218 C Belmont Water Supply (13.5 mi NNE) M 221 C Dairy (14.5 mi NW) SM 222 I Site Boundary (0.70 mi N) M 226 I Site Boundary (0.48 mi S) M S 252 I Residence (0.64 mi SW) Q 253 254 I

I Irrigated Gardens (1.90 mi SSE)

Residence (0.82 mi N)

M(a)

Q 0

258 C Fairhope Road (9.84 mi W) W M 0

(a) During Harvest Season (b) When Available

GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as 0

close as possible to the item of interest. S 0

S 0

0 0

Section 2 - Page 6 S

TABLE 2.1-B CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)

S[ iTable 2.1-B Codes IR Inner Ring OR Outer Ring C Control SI Special Interest Site Measure Location* Distance Sector Site Measure Location* Distance Sector

Type (miles) # Type (miles) 0 S 200 IR SITE BOUNDARY 0.63 NNE 234 OR WACHOVIA BANK 4.50 E 0 201 IR SITE BOUNDARY 0.53 NE 235 OR LAKE WYLIE DAM 4.07 ESE SC WILDLIFE 0 203 IR SITE BOUNDARY 0.38 ESE 236 OR FEDERATION OFFICE TWIN LAKES ROAD AND 4.25 SE 204 IR SITE BOUNDARY 0.48 SSW 237 OR HOMESTEAD ROAD 4.75 SSE 0 205 IR SITE BOUNDARY 0.25 SW 238 OR PENNINGTON ROAD AND WEST OAK ROAD 4.02 S CARTER LUMBER 206 IR SITE BOUNDARY 0.67 WNW 239 OR COMPANY 4.49 SSW 207 IR SITE BOUNDARY 0.95 NNW 240 OR PARAHAM ROAD 4.07 SW 0 212 SI TEGA CAY AIR SITE 3.32 E 241 OR CAMPBELL ROAD 4.58 WSW OLD ROCK HILL TRANSMISSION TOWER 0 217 C AIR SITE 10.3 SSE 242 OR ON PARAHAM ROAD 4.56 W 0 222 IR SITE BOUNDARY 0.71 N 243 OR K1NGSBERRY ROAD 4.39 WNW BETHEL 0 223 IR SITE BOUNDARY 0.57 E 244 OR ELEMENTARY SCHOOL 4.02 NW CROWDERS CREEK 225 IR SITE BOUNDARY 0.68 SE 245 OR BOAT LANDING 4.01 NNW 0 CAROWINDS 0 226 IR SITE BOUNDARY 0.48 S 246 SI GUARD HOUSE 7.87 ENE 0 227 IR SITE BOUNDARY 0.52 WSW 247 C FORT MILL PIEDMONT 7.33 ESE 0 228 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 0 RIVER HILLS YORK 0 230 OR CHURCH RIVER HILLS 4.37 N 250 SI DUKE POWER OFFICE 10.4 WSW 0 231 OR FRONT ENTRANCE PLEASANT HILL 4.21 NNE 251 C CLOVER 9.72 WNW 232 OR ROAD 4.18 NE 255 IR SITE BOUNDARY 0.61 ENE 0 ZOAR ROAD AND 233 OR THOMAS DRIVE 3.95 ENE 256 IR SITE BOUNDARY 0.58 SSE 0

258 SI FAIRHOPE ROAD 9.84 W 0

0

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

Section 2 - Page 7

0W 0

0 0

TABLE 2.2-A 0

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

(pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) (pCi/kg-wet) 0 (pCi/m3)

H-3 20,_000(a)_(b) 0 Mn-54 1,000 30,000 Fe-59 400 10,000 0

Co-58 1,000 30,000 0 Co-60 300 10,000 Zn-65 300 20,000 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 0 Ba-La-140 200 --- F -300 (a) If no drinking water pathway exists, a value of 30,000 pCi/liter may be used.

(b) H-3 Reporting level not applicable to surface water 0

0 TABLE 2.2-B 0

REMP ANALYSIS FREQUENCY 0

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

Water Quarterly Composite X Drinking Monthly Composite X (a) X Water Quarterly Composite X Ground Water Quarterly X X Shoreline Sediment Semiannually X Milk Semimonthly X X Fish Semiannually X Broadleaf Vegetation Monthly(b) X Food Products Monthly(b) X (a) Low-level 1-131 analysis will be performed if the dose calculated for the consumption of drinking water is

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

(b) When Available Section 2 - Page 8

0 S TABLE 2.2-C 0 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION 0 Analysis Water Air Particulates Fish Milk Food Products Sediment 0 (pCi/liter) or Gases (pCi/kg-wet) (pCi/liter) (pCi/kg-wet) (pCi/kg-dry) 0 Gross Beta 4 (pCi/ms) 0.01 0 H-3 2000 (a)

Mn-54 15 130 0 Fe-59 30 260 0 Co-58, 60 15 130 Zn-65 30 260 0 Zr-Nb-95 15 0 1-131 1(b) 0.07 1 60 0 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 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.

S 0

0 0

0 Section 2 - Page 9

S 0

0 0

3.0 INTERPRETATION OF RESULTS

Review of all 2010 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 2010 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 2010. Summary tables containing 2010 information required by Technical

Specification Administrative Control 5.6.2 are located in Appendix B.

0Evaluation for significant trends was performed for radionuclides that are listed as required

within Selected Licensee Commitments 16.11-13. The radionuclides include: H-3,

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140 and La-140. Gross beta analysis results were trended for drinking water and gross beta trending

for air particulates was initiated in 1996. Other radionuclides detected that are the result of 0plant operation, but not required for reporting, are trended.

A comparison of annual mean concentrations of effluent-based detected radionuclides to historical results provided trending bases. Frequency of detection and concentrations related

to SLC reporting levels (Table 2.2-A) were used as criteria for trending conclusions. All 2010 maximum percentages of reporting levels were well below the 100% action level. The highest

value noted during 2010 was 4.97% for H-3 in drinking water.

Selected Licensee Commitment section 1.6.11-13 addresses actions to be taken if 0radionuclides other than those required are detected in samples collected. The occurrences of

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

0

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 0spectroscopy 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 2010 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.

0Review of all 2010 data presented in this section supports the conclusion that there were no significant changes in environmental sample radionuclide concentrations of samples collected and analyzed from CNS site and surrounding areas that were attributable to plant operations.

0 0

~~Section 3 -Pagel1 0

0

0 3.1 AIRBORNE RADIOIODINE AND PARTICULATES 0 In 2010, 264 radioiodine and particulate samples were analyzed, 211 from four indicator locations and 53 at the control location. Particulate samples were analyzed weekly for gamma 0

and gross beta. Radioiodine samples received a weekly gamma analysis.

Figure 3.1 shows individual sample gross beta results for the indicator location with highest 0 annual mean and the control location samples during 2010. The two sample locations' results 0 are similar in concentration and have varied negligibly since preoperational periods. 0 There were no detectable gamma emitters 0 identified for particulate filters analyzed during 2010. Table 3.1-A shows the highest indicator annual mean and control location annual mean 0 for gross beta in air particulate.

0 There was no detectable 1-131 in air radioiodine samples analyzed in 2010. Table 3.1-B shows the highest indicator annual mean and control location annual mean for 1-131 0 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 0 active constituent of the charcoal. A similar study was performed in 2001 again yielding this conclusion. Therefore, any Cs-137 activities were not used in any dose calculations in Section 4.0 of this report.

Figure 3.1 pCi/m 3

Concentration of Gross Beta in Air Particulate 0 1.OOE __

9.OOE-02 ---.---- ----------

6.00E-02 -_ -- __ .. _ _ _. . ...

2.OOE-02 3.OOE002 2.001E021 -W 1984 1987 1990 1993 1996 1999 2002 200S 2008 S --- Indicator Location Control Location There is no reportinglevelfor gross beta in air particulate Section 3 - Page 2

Table 3.1-A Mean Concentration of GrossBeta in Air Particulate

Year Indicator Location (pCi/m3 ) Control Location (pCi/m3) 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 0 1992 1.90E-2 2.01E-2 1993 1.87E-2 1.94E-2 1994 2.03E-2 2.03E-2 1995 4.88E-2 3.23E-2 1996 3.49E-2 2.60E-2 1997 2.83E-2 2.28E-2

1998 2.69E-2 2.12E-2 1999 2.53E-2 2.04E-2 2000 2.28E-2 1.86E-2 2001 1.76E-2 1.78E-2 2002 1.60E-2 1.57E-2 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

2009 1.78E-2 1.72E-2 Average (2000 - 2009) 1.77E-2 1.70E-2 2010 2.03E-2 1.90E-2 0

0 0

O ~Section 3 -Page 3 0

0

S 6

6 S

Table 3.1-B Mean Concentration of Air Radioiodine (I-1311 Year Indicator Location (pCi/mr3) Control Location (pCi/m3) 1984 1.30E-3 1.46E-2 0 1985 4.75E-3 2.38E-2 1986 1.43E-2 1.02E-2 1987 1.38E-2 0.00E0 1988 0.OOEO 0.OOEO 1989 0.OOEO 0.OOEO 1990 0.OOEO 0.OOEO 1991 0.00E0 0.OOEO 1992 0.00EO 0.OOEO 1993 0.00E0 0.OOEO 1994 0.OOEO 0.00E0 1995 0.OOEO 0.OOEO 0 1996 0.00E0 0.00E0 1997 0.OOEO 0.00E0 1998 O.00E0 0.OOEO 1999 0.00E0 0.00E0 2000 0.OOEO 0.003E0 2001 0.OOEO 0.OOEO 2002 0.OOEO 0.OOEO 2003 0.OOEO 0.00E0 2004 0.00E0 0.OOEO 2005 0.OOEO 0.OOEO 2006 0.00E0 0.OOEO 2007 0.OOEO 0.00E0 2008 0.OOEO 0.OOEO 2009 0.OOEO 0.OOEO 2010 O.OOEO 0.OOEO 0.00E0 = no detectable measurements 0

0 o

S S

Section 3 - Page 4 S

0 0

3.2 DRINKING WATER 0 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 0 indicator location was sampled, along with one control location.

0 No gamma emitting radionuclides were identified in 2010 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 1.84 pCi/1 in 2010 and the control location 0 concentration was 1.80 pCi/l. The 2009 indicator mean was 2.07 pCi/l. The table shows that 0 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 2010.

The mean indicator tritium concentration for 2010 was 705 pCi/l, 3.53% of reporting level.

The mean control tritium concentration for 2010 was 427 pCi/1, 2.14% of reporting level.

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

S 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 0 plant on the Catawba River.

0 The dose for consumption of water was less than one mrem per year, historically and for 0 2010; therefore low-level iodine analysis is not required.

0 0

Section 3 - Page 5

0 0

Figure 3.2 pOi/liter Concentration of Tritium in Drinking Water 5000 0

4500 0

4000 0 3500 0 3000 2500 0

2000 -

1500 0 1000 0

500 0 0 1984 1987 1990 1993 1996 1999 2002 2005 2008

-*- Indicator Location --

Control Location - 20% Reporting Level 0

Table 3.2 Mean Concentration of Radionuclides in Drinking Water 0

Gross Beta (pCi/I) Tritium (pCi/I)

YEAR Indicator Control Indicator Control 0 Location Location Location Location 0 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 0.00E0 1989 3.60 2.90 8.91 E2 5.72E2 0

1990 4.50 3.20 7.03E2 0.00E0 1991 3.70 2.20 7.04E2 0.00E0 0 1992 1993 3.20 3.50 2.40 2.50 7.65E2 7.06E2 5.38E2 0.OOEO 0

1994 3.30 2.70 0.OOEO 0.OOEO 0 1995 4.80 4.50 4.28E2 2.21 E2 1996 3.08 3.14 3.71E2 3.27E2 0 1997 1998 3.74 2.51 3.15 2.44 3.54E2 5.07E2 2.28E2 1.831E2 0

1999 3.55 2.48 6.7 1E2 2.70E2 0 2000 3.04 2.27 5.87E2 3.26E2 2001 3.49 2.30 8.66E2 4.50E2 2002 3.44 2.36 1.22E3 4.11 E2 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 2010 1.84 1.80 7.05E2 4.27E2 0.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 6

0 0

0 0 3.3 SURFACE WATER A total of 39 monthly surface water samples was analyzed for gamma emitting radionuclides.

The samples were composited to create 12 quarterly samples for tritium analysis. Two indicator locations and one control location were sampled. One indicator location (208) is S located near the liquid effluent discharge point.

0 All 2010 indicator location samples contained tritium with an average concentration of 3,970 0 pCi/l. Indicator Location 208 (Discharge Canal) showed a range of activities from 4,180 to 11,900 pCi/1 which had the highest mean concentration of 7,260 pCi/l. Tritium was detected 0 in three of the four control samples during 2010 with an average concentration of 294 pCi/1.

No gamma emitting radionuclides were identified in 2010 drinking water samples. Table 3.3 0 summarizes the indicator annual means of radionuclides detected since the change in the 0 gamma spectroscopy analysis system in 1987.

S Figure 3.3 displays the indicator and control annual means for tritium since 1984. Table 3.3 0 lists indicator annual means.

0 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

Section 3 - Page 7

0 0

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

35000 0 30000 --- 0 25000 -

0 20000 - - ----- 0 15000 -

10000 _1_

5000 -- --------- -- _ -- - _ _ _- _ 0 0

1984 1987 1990 1993 1996 1999 2002 2005 2008

--*- Indicator Location --- Control Location There is no reportinglevelfor tritium in surface water, however, if no drinking waterpathway exists, a value of 30,O00 pCi/l may be used A drinking waterpathway existsfor CatawbaNuclear Station, so this limit does not applyfor surface water. See section 3.2for drinking water results.

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

YEAR Co-58 Co-60 Nb-95 Cs-137 H-3 Indicator H-3 Control 1984 4.59E-1 5.71E-1 6.48E-1 9.08E-I 3.35E2 3.18E2 0 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 1988 0.00E0 9.20E0 3.10E0 0.OOEO 4.30E0 O.OOE0 9.90E0 0.OOE0 4.17E3 6.03E3 6.20E2 6.07E2 0

1989 0.00E0 0.00E0 0.OOEO 0.00E0 5.27E3 0.00E0 0 1990 1991 6.50E0 0.00E0 0.00E0 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 3.98E3 4.87E3 7.73E2 0.00E0 0

1992 0.OOEO 0.OOEO 0.OOEO 0.OOEO 6.91E3 6.64E2 0 1993 4.70E0 I .80E0 0.OOEO 0.OOEO 5.98E3 0.00E0 1994 0.00E0 O.00E0 0.OOEO 0.OOEO 8.42E3 0.00E0 1995 0.00E0 0.OOEO 0.00E0 0.OOEO 5.13E3 2.89E2 1996 0.00E0 0.00E0 0.OOEO 0.00E0 7.36E3 2.61 E2 1997 0.00E0 0.OOEO 0.00E0 0.OOEO 7.77E3 2.20E2 1998 0.OOEO 0.00E0 0.OOEO 0.OOEO 6.61 E3 0.OOEO 1999 0.00E0 0.OOEO 0.OOEO 0.00E0 8.13E3 2.41 E2 2000 0.OOEO 0.OOEO 0.OOEO 0.OOEO 7.19E3 2.56E2 2001 0.OOEO 0.00E0 0.OOEO 0.OOEO 7.13E3 3.28E2 2002 OOEO 0.OOEO 0.00E0 0.00E0 1.00E4 3.80E2 2003 0.00E0 0.00E0 0.OOEO 0.OOEO 1.3 1E4 2.37E2 2004 0.OOEO 0.OOEO 0.OOEO 0.00E0 9.43E3 2.60E2 2005 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.40E4 3.78E2 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.67E4 5.83E2 2007 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.01E4 7.82E2 2008 6.80E0 1.16E 1 0.00E0 0.OOEO 6.02E3 6.31 E2 2009 9.40E0 1.06E] 0.OOEO 0.OOEO 3.93E3 5.29E2 2010 0.OOEO 0.OOEO 0.OOEO 0.OOEO 7.26E3 2.94E2 0.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 8

0 0

0 3.4 GROUND WATER A total of five ground water samples was collected and analyzed for gamma emitters and 0 tritium. There are two indicator locations and no control locations. Naturally occurring K-40 0 was the only radionuclide identified during 2010.

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

0 0

S 0

0 0

Section 3 - Page 9

3.5 MILK A total of 26 milk samples was analyzed by gamma spectroscopy and low level iodine during 2010. There was one control location sampled. No indicator dairies were identified by the 2010 land use census.

0 There were no gamma emitting radionuclides identified in milk during 2010. 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.

Table 3.5 Mean Concentration of Radionuclides in Milk YEAR Cs-1 37 Indicator (pCi/I) Cs-137 Control (pCi/I) 1984 2.95E0 2.98E0 1985 2.11 EO 2.12E0 1986 3.76E0 4.54E0 1987 5.OOEO 5.50E0 0 1988 3.20E0 3.80E0 1989 0.OOEO 0.OOEO 1990 8.OOEO 6.70E0 1991 0.OOEO 0.OOEO 1992 3.40E0 5.OOEO 1993 5.OOEO 0.OOEO 1994 2.80E0 0.OOEO 1995 8.60E0 0.OOEO 1996 6.05E0 0.00E0 1997 0.00E0 0.00E0 1998 0.OOEO 0.OOEO 1999 0.OOEO 0.OOEO 2000 0.OOEO 0.OOEO 2001 0.OOEO 0.00E0 2002 0.OOEO 0.00E0 2003 0.00E0 0.OOEO 2004 NO INDICATOR LOCATION 0.OOEO 0 2005 NO INDICATOR LOCATION 0.00E0 2006 NO INDICATOR LOCATION 0.OOEO 2007 NO INDICATOR LOCATION 0.OOEO 2008 NO INDICATOR LOCATION 0.OOEO 2009 NO INDICATOR LOCATION 0.OOEO 0 2010 NO INDICATOR LOCATION 0.OOEO 0.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity 0 0

0 Section 3 - Page 10 0

0 0 3.6 BROADLEAF VEGETATION 0 Gamma spectroscopy was performed on 60 broadleaf vegetation samples during 2010.

0 Four indicator locations and one control location were sampled.

Three of the forty-eight samples collected at indicator locations contained detectable Cs-137 activity. Cs-137 was detected in three of the twelve samples collected at Location S 201. The highest concentration detected at Location 201 was 55.8 pCi/kg which is 2.79%

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

0 Figure 3.6 shows indicator and control annual means for Cs-137 in vegetation since 1984. Table 3.6 lists indicator and S annual means. Values shown from 1984 to 2010 show a stable trend for Cs-137 S in vegetation.

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

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

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

1000 800 600 400 200 0

1984 19 87 1990 1993 1996 1999 2002 2005 2008 Indicator Location -- W- Control Location - 50% Reporting Level!

Section 3 - Page 1]

Table 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation YEAR Cs-137 Indicator (eCi/kg) Cs-137 Control (pCi/kg) 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 1.00E2 4.80E1 1990 7.70E1 5.80E1 1991 1.98E2 8.60EI 1992 9.70E1 0.OOEO 1993 1.13E2 3.20E1 1994 7.OOEl 0.OOEO 1995 3.60E1 0.00E0 1996 2.23E2 6.22E1 1997 7.57E1 0.00E0 1998 6.53E1 0.00E0 1999 1.08E2 0.OOEO 2000 1.04E2 0.OOEO 2001 3.76E1 O.OOEO 2002 7.02EI 0.00E0 2003 4.96E1 2.40E1 2004 5.45E1 0.OOEO 2005 5.48E1 0.00E0 2006 5.79E1 0.00E0 2007 6.31E1 0.00E0 i 2008 4.44E1 0.00E0 2009 4.25E1 0.00E0 2010 3.77E1 0.OOEO O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity 5

0 0

0 S

S 0

0 0

S S

Section 3 -Page 12 S

0 0

3.7 FOOD PRODUCTS

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

began in 1989. The garden is located

on Lake Wylie downstream from CNS, Location 253. During the 02010 growing season, six samples 0were collected and analyzed for gamma radionuclides. There is no control location for this media type.

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

Table 3.7 Mean Concentration of Radionuclides in Food Products YEAR Cs-137 Indicator (pCi/kg) 1989 0.OOEO 1990 O.OOEO 1991 0.OOEO 1992 0.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.OOEO 2003 0.OOEO 2004 0.OOEO 2005 0.OOEO 2006 0.OOEO 2007 0.OOEO 2008 0.OOEO 2009 0.OOEO 2010 0.OOEO O.OOEO = no detectable measurements There is no control location for Food Products.

0 0

0 0 Section 3 -Page 13 0

0

0 0

3.8 FISH 0 0

Gamma spectroscopy was performed on 12 fish samples collected during 2010. One 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 0 samples. There were no gamma emitting radionuclides identified in any indicator 0 location or control location fish samples during 2010.

0 Figures 3.8-1 and 3.8-2 are graphs 0 displaying annual mean concentrations 0 for Co-58 and Co-60. Table 3.8 depicts 0 the highest indicator location annual mean for radionuclides detected. In 0

addition, radionuclides identified in fish 0 samples since 1988 have been included in 0 the table. Overall, radionuclides have not 0 shown a significant trend or accumulation. 0 0

K-40 was observed in fish samples 0 collected during 2010. 0 0

0 0

0 Section 3 - Page 14 0

0

0 0

0 Figure 3.8-1 0

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

1600____ -

0 1400 0 1200 - ____

1000 - __ _____ _____

800 -- -- ----- __ -

600 - - _ - - - _ -_ _

400 - --

200 ---. - .- -

04 1984 1987 1990 1993 1996 1999 2002 2005 2008 I -U- Indicator Location --W Control Location - 5 % Reporting Level I Figure 3.8-2 0

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

0 600 0 500 -

0 400 0

0 300 ... -- .

0 200 - -- - ----------------- -- --------------- ------ -- -

0 100 0 -

0 . . . ..

0 1984 1987 1990 1993 1996 1999 2002 2005 20i08 0 -A--- Indicator Location -A-- Control Location - 5% Reporting Level I 0

0 0

0 Section 3 - Page 15 0

0

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

Year Mn-54 Co-58 Co-60 Cs-134 Cs-137 Nb-95 Fe-59 Sb-122 Sb-125 0 1984 3.07E0 3.00E0 6.11E-1 -5.32E0 1.83E0 0.OOEO 0.00E0 0.OOEO 0.00E0 1985 7.68E-1 3.40E1 9.11EO 3.22E0 1.28E1 5.07E0 0.00E0 0.OOEO 0.OOEO 1986 2.01El 1.86E2 4.01E1 3.51E1 9.29E1 0.00E0 7.30E0 0.00E0 0.00E0 1987 7.24E0 7.57E1 4.81E1 3.83E0 4.27E1 5.40E0 0.00E0 0.OOEO 0.OOEO 1988 2.85E1 1.40E2 9.70E1 1.67E1 8.24E1 0.00E0 0.00E0 0.OOEO 0.00E0 1989 8.28E0 1.33E2 3.83E1 1.47E1 4.37E1 8.58E-1 0.OOEO 0.00E0 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 1.03E1 4.60E1 7.90E-1 2.30E0 0.OOEO 7.45E0 1992 1.34E1 9.02E1 6.20E1 1.27E1 4.61E1 0.OOEO O.OOEO 0.OOEO 0.OOEO 1993 2.14E1 3.58E2 1.21E2 2.73E0 2.56E1 0.00E0 0.OOEO 0.OOEO O.OOEO 1994 1.91E0 4.75E1 1.81El 0.OOEO 1.75E1 O.00E0 0.00E0 0.OOEO 1.45E1 1995 5.65E1 8.90E2 2.66E2 O.OOEO 6.77E1 1.38E1 0.00E0 0.OOEO O.OOEO 1996 0.OOEO 5.95E1 6.68E1 O.OOEO 3.02E1 0.OOEO O.OOEO 0.00E0 O.OOEO 1997 0.00E0 4.93E1 9.88E0 O.OOEO 2.74E1 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1998 0.OOEO 6.44E1 2.86EI 0.OOEO 1.58E1 0.OOEO 0.OOEO O.OOEO O.OOEO 1999 0.OOEO 3.12E1 2.71E1 0.OOEO 1.87E1 0.00E0 0.OOEO 0.OOEO O.OOEO 2000 0.OOEO 2.13E2 2.69E2 0.00E0 1.52E1 0.OOEO 0.00E0 0.OOEO 0.OOEO 2001 0.OOEO 4.66E1 0.OOEO 0.OOEO 2.08E1 0.OOEO 0.00E0 0.00E0 0.00E0 2002 0.OOEO 5.23E1 7.OOEl 0.OOEO 1.73E1 0.OOEO 0.00E0 0.OOEO 0.OOEO 2003 0.OOEO 1.43E2 2.61E1 0.OOEO 1.19El 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2004 4.92E1 1.81El 0.00E0 0.OOEO 0.OOEO 0.OOEO 0.00E0 0.00E0 0.00E0 2005 0.OOEO 0.OOEO 0.00E0 O.OOEO 0.OOEO 0.OOEO O.OOEO 0.OOEO O.OOEO 2006 0.OOEO 0.OOEO 0.OOEO 0.OOEO 1.44E1 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2007 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2008 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO O.OOEO 2009 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 2010 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO 0.OOEO0 O.OOEO = no detectable measurements 0 0

0 0

Section 3 -Page 16 0 0

0

0 0

0 3.9 SHORELINE SEDIMENT 0

During 2010, a total of 6 shoreline sediment samples was analyzed, four from two 0 indicator locations and two from the control location.

0 Co-58 and Co-60 were identified in two samples collected from indicator location 208-1 S, which is closest to the plant's liquid effluent release point. Cs-137 was identified in one sample collected from location 208-1 S. Naturally occurring K-40 was identified in 0 many of the indicator and control locations. Activity released in plant effluents has 0 decreased since 1996 and as a result decreased activity has been measured in the environment.

The shoreline sediment location with the highest annual mean for all detectable 0 radionuclides was location 208-iS. Co-58 was identified at location 208-IS with an 0 annual mean concentration of 65.6 pCi/kg. Co-60 was identified with an annual mean concentration of 137 pCi/kg. Cs-137 was identified with an annual mean concentration of 25.6 pCi/kg. Naturally occurring K-40 and Be-7 were also identified in samples from this location.

Table 3.9 lists highest indicator location annual mean since 1984. Included in the table 0 are radionuclides that have been identified in shoreline sediment samples since 1988.

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

0 Figure 3.9-1 pCi/kg 0 2000 --

Concentration of Co-58 in Shoreline Sediment 0 1800 1600 0 1400 1200 1000 800 4--

600 400 +

200

-Indicator Location - Control Location There is no reporting level for Co-58 in Shoreline Sediment Section 3 - Page 17

0 0

S 0

Figure 3.9-2 0

Concentration of Co-60 in Shoreline Sediment pCi/kg 2000 0

1800 - 0 1600 0 1400 1400 _________I_ ____

1200 0

800 _

600 -_____

400 0 0L -. 0 0l 0 0h 0 0 b 1984 1987 1990 1993 1996 1999 2002 2005 2008 F Indicator Location --*- Control Location 0

There is no reporting level for Co-60 in Shoreline Sediment 0

0 0

Section 3 - Page 18

WTable 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment (pC/ka) 0 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.OOEO 1.65E1 5.77E1 0.OOEO 1.57E1 1990 5.39E1 2.08E2 1.77E2 0.00E0 0.00E0 1.66E1 8.18E1 0.OOEO 7.15E0 1991 8.50E1 3.70E2 4.19E2 5.30E0 0.OOEO 1.82E1 8.33E1 1.20E0 1.50E]

1992 1.17E2 1.13E3 5.80E2 3.50E0 0.00E0 1.69E1 1.07E2 3.OOEO 2.70E1 1993 1.33E2 1.07E3 1.04E3 0.OOEO 0.OOEO 2.80E1 1.26E2 2.47E1 2.16E2

1994 4.93E1 7.98E2 5.73E2 0.OOEO 0.OOEO 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 0.00E0 0.OOEO 0.OOEO 8.30E1 0.OOEO 1.96E2

1997 6.96E1 5.90E2 7.64E2 0.00E0 0.00E0 0.00E0 1.43E2 0.00E0 1.76E2 1998 3.07E1 1.88E2 2.30E2 0.OOEO 0.00E0 0.OOEO 7.11El 0.00E0 0.OOEO

1999 7.28E1 2.29E2 4.39E2 0.OOEO 0.00E0 0.00E0 9.42E1 0.00E0 1.40E2 2000 0.OOEO 3.90E1 1.03E2 0.OOEO 0.OOEO 0.OOEO 4.96E1 0.OOEO 0.OOEO 2001 3.86E1 8.27E1 3.29E2 0.OOEO 0.OOEO 0.OOEO 5.58E1 0.OOEO 0.OOEO

2002 3.51E1 2.41E2 2.22E2 0.OOEO 0.OOEO 0.00E0 8.83E1 0.00E0 0.OOEO 2003 2.17E1 8.75E1 1.08E2 O.O0EO 0.OOEO 0.00E0 2.69E1 0.00E0 0.OOEO 2004 6.60E1 2.67E2 3.83E2 0.OOEO 0.00E0 0.00E0 3.79E1 0.OOEO 0.OOEO

2005 0.00E0 1.61E2 1.41E2 0.OOEO 0.OOEO 0.00E0 0.OOEO 0.OOEO 0.OOEO 2006 0.OOEO 5.40E1 1.11E2 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 6.13EI 0.OOEO 0.OOEO

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 6.56EI 1.37E2 0.OOEO 0.OOEO 0.OOEO 2.56E1 0.OOEO 0.OOEO SO.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Negative values are calculated as zeroes 0 S 0

0 0

0 O ~Section 3 -Page 19 0

0

3.10 DIRECT GAMMA RADIATION 0 3.10.1 ENVIRONMENTAL TLD 0 0

In 2010, 163 TLDs were analyzed, 151 at indicator locations and 12 at control locations. TLDs are collected and analyzed quarterly. The highest annual mean exposure for an indicator location was 96.0 milliroentgen. The annual mean exposure for the control locations was 57.2 milliroentgen.

Figure 3.10-1 and Table 3.10-A show TLD inner ring (site boundary), outer Ring (4-5 miles), and control location annual averages in milliroentgen per year. Preoperational data and rolling ten year operational data averages are also given. As shown in the graph, inner ring, outer ring, and control data averages historically compare closely. Inner and outer ring averages comprise a number of data points with control averages representing only three locations.

Figures 3.10-2 and 3.10-3 show the TLD mean for each inner and outer ring TLD location from 1986 through 2010.

The calculated total body dose (from gaseous effluents) for 2010 was 2.25E0 mrem, which is 2.76% 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.

0 3.10.2 ISFSI 0

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 steel dry storage canisters containing irradiated fuel assemblies.

0 The ISFSI is located approximately 300 meters north of the Unit 2 reactor building.

TLD results are evaluated quarterly to identify trends and demonstrate 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 sector. Catawba began storage of spent fuel at the ISFSI in 2007. Six storage modules were loaded with spent fuel in 2010 for a total of sixteen modules.

Section 3 -Page 20 0

0 0

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

Figure 3.10-1 0 mR/year Direct Gamma Radiation (TLD) Results 0 250 200 0

150 100 0 50 0 0 0 1984 1987 1990 1993 1996 1999 2002 2005 2008 0 -h-*Inner Ring --W- Outer Ring - Control 0

There is no reportinglevel for Direct Radiation (TLD) 0 0

0 0

S 0

Section 3 - Page 21

0 Table 3.10-A Direct Gamma Radiation (TLD) Results Inner Ring Average Outer Ring Average Control Average Year (mR/lyr) (mR/yr) (mR/lyr) 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 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 Average (2000 - 2009) 79.4 72.4 56.7 2010 81.4 71.6 57.2

Preoperational Data 0

0 0

Section 3 - Page 22 0 0

0 0

Figure 3.10-2 0

mR/year Catawba Inner Ring (TID) Results 140 ,

0 120 -

0 100 0

0 80 -

0 60 0

40 -

0 20 N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 0 (222) (200) (201) (255) (223) (203) (225) (256) (226) (204) (205) (227) (228) (206) (229) (207)

I -A--&2010 Mean - 1986- 2009 High/Low/Mean =

0 Table 3.10-B Direct Gamma Radiation (TLD) Results Inner ] Riniz High/Low/Mean 0 --A-- 2010 Mean

-- 1986- 2009 0 Sector (Location) 1986 - 2009 Mean 1986 - 2009 Low 1986 - 2009 High 2010 Mean S N (222) 5.93E+01 3.63E+01 8.33E+01 7.30E+01 0 NNE (200) 7.25E+01 4.17E+01 9.54E+01 7.1OE+01 NE (201) 7.21E+01 4.75E+01 9.76E+01 7.40E+01 ENE (255) 7.83E+01 4.74E+01 1.01E+02 8.40E+01 S E (223) 8.11E+01 5.22E+01 1.06E+02 8.1OE+0I ESE (203) 8.53 E+01 5.32E+01 1.16E+02 8.60E+01 SE (225) 8.22E+01 5.66E+01 1.11E+02 7.60E+0I SSE (256) 8.11 E+01 5.45E+0 I 1.05E+02 8. 1OE+OI 0 S (226) 7.25E+01 4.81E+01 1.02E+02 8.OOE+0I SSW (204) 8.14E+0I 5.63E+01 1.05E+02 7.60E+01 SW (205) 8.30E+01 4.33 E+01 .08E+02 9.60E+0 I WSW (227) 7.76E+01 5.37E+01 1.05E+02 7.60E+01 W (228) 7.36E+01 4.97E+01 1.04E+02 7.70E+0I WNW (206) 8.76E+01 6.83E+01 1.14E+02 9.OOE+01 NW (229) 9.10E+01 6.27E+01 1.16E+02 9.OOE+01 NNW (207) 8.90E+01 5.99E+01 1.08E+02 9.20E+01 Section 3 - Page 23

0 0

0 Figure 3.10-3 S

mR/year Catawba Outer Ring (TLD) Results 160 -

0 140 0

120 0 100 0

0 80" 0

60-40 -

0 20" 0

N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW (230) (231) (232) (233) (234) (235) (236) (237) (238) (239) (240) (241) (242) (243) (244) (245) 1 -&- 2010 Mean - 1986-20091High/Low/Mean =

0 0

Table 3.10-C Direct Gamma Radiation (TLD) Results Outer Ring Sector 0 (Location) 1986 - 2009 Mean 1986 - 2009 Low 1986 - 2009 High 2010 Mean N (230) 5.65E+01 3.72E+O1 8.73E+01 5.60E+01 NNE (231) 7.1OE+01 3.75E+O1 8.75E+01 8.1OE+O1 NE (232) 8.70E+O1 5.85E+01 1.17E+02 9.OOE+O1 ENE (233) 6.38E+01 3.50E+01 9.27E+01 6.60E+01 0

E (234) 8.45E+01 5.37E+01 1.11E+02 7.30E+01 ESE (235) 8.43E+01 4.89E+01 1.09E+02 7.30E+01 0 SE (236) 8.99E+'01 6.60E+0O1 1.22E+02 7.1OE+0 I 0 SSE (237) 8.87E+01 5.53E+01 1.34E+02 9.30E+01 S (238) 7.45E+01 5.24E+01 1.06E+02 7.OOE+0 I SSW (239) 7.43E+01 4.87E+01 1.06E+02 7.70E+01 SW (240) 5.39E+01 3.10E+01 7.87E+01 5.30E+01 WSW (241) 5.69E+I01 2.99E+O1 8.29E+01 5.60E+01 W (242) 6.76E+01 4.3 1E+01 9.55E+01 6.80E+01 WNW (243) 6.98E+01 4.60E+01 9.47E+01 6.80E+01 NW (244) 6.67E+01 3.78E+01 9.26E+01 6.80E+01 NNW (245) 5.81E+01 2.95E+01 7.55E+01 6.70E+I01 Section 3 - Page 24

0 0

3.11 LAND USE CENSUS 0

0 The 2010 Annual Land Use Census was conducted July 14, and July 15, 2010 as required by SLC 16.11-14. Table 3.11 summarizes census results. A map indicating identified locations is shown in Figure 3.11.

0 During the 2010 census, two nearer residences were identified; no irrigated gardens 0 (superior to existing gardens) or milk locations were identified. The nearest residence is 0 located in the NE sector at 0.56 miles. No environmental program changes were required as a result of the 2010 land use census.

0 Table 3.11 Catawba 2010 Land Use Census Results Sector Distance Sector Distance 0 (Miles) (Miles)

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

0 Nearest Residence 0.66 Nearest Residence 0.81 0 NNE Nearest Garden 4.39 SSW Nearest Garden 2.04 Nearest Milk Animal - Nearest Milk Animal -

0 Nearest Residence 0.56 Nearest Residence 0.63 0 NE Nearest Garden Nearest Milk Animal 0.68 SW Nearest Garden Nearest Milk Animal 2.29 0

Nearest Residence 0.61 Nearest Residence 0.60 1.10 0 ENE Nearest Garden Nearest Milk Animal 2.84 WSW Nearest Garden Nearest Milk Animal -

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

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

0 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 0.91 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 25

Figure 3.11 Section 3 - Page 26 00*000000000*000000000000000000000000000000o

0 0

4.0 EVALUATION OF DOSE 0

4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured

concentrations of radionuclides in 2010 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

presented in NRC Regulatory Guide 1.109. Measured radionuclide concentrations, 0averaged over the entire year for a specific radionuclide, indicator location and sample type, were used to calculate REMP-based doses. Where applicable, average background concentration at the corresponding control location was subtracted. Regulatory Guide 1.109 consumption rates for the maximum exposed individual 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, drinking water, 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 0particulate, milk, or ground water sample types because no radionuclides other than 0naturally occurring K-40 and Be-7 were detected in the samples. Dose estimates are not reported for surface water because sampled surface water is not considered to be a

potable drinking water source although surface water tritium concentrations are used in calculating doses from fish. Exposure estimates based upon REMP TLD results are in Section 3.10.

0*discussed The maximum environmental organ dose estimate for any single sample type (excluding

TLD results) collected during 2010 was 3.21E-1 mrem to the maximum exposed child bone from consuming broadleaf vegetation.

4.2 ESTIMATED DOSE FROM RELEASES 0

Throughout the year, dose estimates were calculated based on actual 2010 liquid and gaseous effluent release data. Effluent-based dose estimates were calculated using the

RETDAS computer program which employs methodology and data presented in NRC

Regulatory Guide 1.109. These doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimates. Summaries of RETDAS dose calculations

are reported in the Annual Radioactive Effluent Release Report (reference 6.6).

0 0 Section 4 -Page 1 0

0

The effluent-based liquid release doses are summations of the dose contributions from the drinking water, fish, and shoreline pathways. For iodine, particulate, and tritium exposure the effluent-based gaseous release doses are summations of the dose contributors from ground/plane, inhalation, milk and vegetation pathways.

4.3 COMPARISON OF DOSES 0

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 addition, Catawba began reporting estimated dose from effluent Carbon 14 (C-14).

This change came about with the issuing of Regulatory Guide 1.21, Revision 2, Measuring, Evaluating and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste. A description of this change is found in the 2010 Annual Radiological Effluent Release Report. C-14 is not measured in the environment and therefore, environmental and effluent doses from C-14 cannot be compared directly.

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 .2010 environmental sample results was 3.79E-2 mrem to the child total body. The maximum total organ dose of 1.06E- I mrem for liquid effluent-based estimates was to the adult GI-LLI.

In calculations based on gaseous release pathways, vegetation was the predominant dose pathway for effluent samples. The maximum total organ dose for gaseous effluent estimates was 4.78E0 mrem to the child bone. Vegetation was the predominant dose pathway for environmental samples. The maximum total organ dose for gaseous environmental estimates was 3.21 E- 1 mrem to the child bone.

0 The doses calculated do not exceed 40CFR190 or 10CFR50 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.

S 0

0 0

Section 4 -Page 2 0 0

0 0

TABLE 4.1-A 0 Page 1 of 2 0 CATAWBA NUCLEAR STATION 2010 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIQUID RELEASE PATHWAY Critical Critical Maximum Dose (3)

Organ Effluent Data or Environmental Age (1) Pathway (2) (mrem) 0 Skin Environmental Teen Shoreline Sediment 208 (0.45 mi S) 1.82E-03 0 Skin Effluent Teen Shoreline Sediment Discharge Pt. 9.79E-03 Bone Environmental - 0.OOE+00 Bone Effluent Teen Fish Discharge Pt. 2.53E-02 0

Liver Environmental Child Drinking Water 214 (7.30 mi SSE) 3.76E-02 0 Liver Effluent Child Drinking Water 7.30 mi SSE 1.04E-01 0

T. Body Environmental Child Drinking Water 214 (7.30 mi SSE) 3.79E-02 0 T. Body Effluent Child Drinking Water 7.30 mi SSE 8.75E-02 0

0 Thyroid Environmental Child Drinking Water 214 (7.30 mi SSE) 3.76E-02 Thyroid Effluent Child Drinking Water 7.30 mi SSE 8.32E-02 0

Kidney Environmental Child Drinking Water 214 (7.30 mi SSE) 3.76E-02 0 Kidney Effluent Child Drinking Water 7.30 mi SSE 9.OOE-02 Lung Environmental Child Drinking Water 214 (7.30 mi SSE) 3.76E-02 0 Lung Effluent Child Drinking Water 7.30 mi SSE 8.57E-02 0

GI-LLI Environmental Child Drinking Water 214 (7.30 mi SSE) 3.76E-02 S GI-LLI Effluent Adult Drinking Water 7.30 mi SSE 1.06E-01 P

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

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

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

00 S0 0

Section 4 - Page 3

0 0

0 Page 2 of 2 0 GASEOUS RELEASE PATHWAY 0 0

IODINE, PARTICULATE, and TRITIUM Environmental or Critical Critical Maximum Dose (3) 0 Organ Effluent Data Age Pathway (2) Location (mrem) 0 0

Skin Environmental - 0.OOE+00 0

Skin Effluent All Ground Plane 0.5 mi NE 1.80E-03 Bone Environmental Child Vegetation 201 (0.53 mi NE) 3.21E-01 Bone Effluent Child Vegetation 0.5 mi NE 4.78E+00 Liver Environmental Child Vegetation 201 (0.53 mi NE) 3.07E-01 Liver Effluent Child Vegetation 0.5 mi NE 2.25E+00 T. Body Environmental Adult Vegetation 201 (0.53 mi NE) 1.72E-01 T. Body Effluent Child Vegetation 0.5 mi NE 2.25E+00 Thyroid Environmental 0.OOE+00 Thyroid Effluent Child Vegetation 0.5 mi NE 2.25E+00 Kidney Environmental Child Vegetation 201 (0.53 mi NE) 1.OOE-01 Kidney Effluent Child Vegetation 0.5 mi NE 2.25E+00 0 Lung Environmental Child Vegetation 201 (0.53 mi NE) 3.60E-02 0 Lung Effluent Child Vegetation 0.5 mi NE 2.25E+00 0

GI-LLI Environmental Adult Vegetation 201 (0.53 mi NE) 5.09E-03 S GI-LLI Effluent Child Vegetation 0.5 mi NE 2.25E+00 0

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

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

0 Section 4 - Page 4

0000009000000000000000000000000000000000000o TABLE 4.1-B Maximum IndividualDose for 2010 based on Environmental Measurements (mrem) for Catawba Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Drinking Water 0.00E+00 2.83E-02 2.83E-02 2.83E-02 2.83E-02 2.83E-02 2.83E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 TOTAL O.OOE+00 2.83E-02 2.83E-02 2.83E-02 2.83E-02 2.83E-02 2.83E-02 O.OOE+00 Child Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Drinking Water O.OOE+00 2.88E-02 2.88E-02 2.88E-02 2.88E-02 2.88E-02 2.88E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation 3.21E-01 3.07E-01 4.53E-02 0.00E+00 1.OOE-01 3.60E-02 1.92E-03 0.00E+00 Fish O.OOE+00 8.78E-03 8.78E-03 8.78E-03 8.78E-03 8.78E-03 8.78E-03 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 3.24E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.81E-04 TOTAL 3.21E-01 3.45E-01 8.32E-02 3.76E-02 1.38E-01 7.36E-02 3.95E-02 3.81E-04 Teen Airborne O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Drinking Water O.OOE+00 1.50E-02 1.50E-02 1.50E-02 1.50E-02 1.50E-02 1.50E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation 1.77E-01 2.36E-01 8.22E-02 O.OOE+00 8.03E-02 3.12E-02 3.36E-03 O.OOE+00 Fish O.OOE+00 1.06E-02 1.06E-02 1.06E-02 1.06E-02 1.06E-02 1.06E-02 O.OOE+00 Shoreline Sediment O.OOE+00 0.00E+00 1.55E-03 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1.82E-03 TOTAL 1.77E-01 2.62E-01 1.09E-01 2.56E-02 1.06E-01 5.68E-02 2.90E-02 1.82E-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 2.13E-02 2.13E-02 2.13E-02 2.13E-02 2.13E-02 2.13E-02 O.OOE+00 Milk O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Broadleaf Vegetation 1.92E-01 2.63E-01 1.72E-01 O.OOE+00 8.93E-02 2.97E-02 5.09E-03 O.OOE+00 Fish O.OOE+00 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.38E-02 O.OOE+00 Shoreline Sediment O.OOE+00 O.OOE+00 2.78E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.27E-04 TOTAL 1.92E-01 2.98E-01 2.07E-01 3.51E-02 1.24E-01 6.48E-02 4.02E-02 3.27E-04 Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 5

CatawbaNuclear Station Dosefrom Drinking Water Pathwayfor 2010 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 Ingestion Dose Factor Concentration Dose (mrcm)

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body Thyroid Kidney Lung GI-LLI NMn-54 NO DATA 1.99 E-05 4.51 E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 ALL 0.00 0.OOE+O0 0.OOE+00 0.OOE+00 .001E+00 O.OOE+00 0.OOE+00 O.OOE+O0

.001E+00 Co-58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 ALL 0.00 O.OOE+00 0.OOE+00 O.00E+00 0.00E+00 O.OOE+00 0.00E+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 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 .002E+00 Co-60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 ALL 0.00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+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 O.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 Nb-95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 0.00E+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 O.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 .001E+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 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 Cs-134 3.77 E-04 7,03E-04 7.10E-05 NO DATA l.81E-04 7.42E-05 1.91 E-06 ALL 0.00 O.OOE+00 0.0012+00 O.00E+00 O.OOE+00 O.OOE+00 O.OOE+O0 .002E+00 0.00E+00 Cs-137 5.22E-04 6.11 E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91 E-06 ALL 0.00 O.OOE+O0 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 .001E+00 BaLa-140 1.71 E-04 1.71 E-07 8.81 E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 ALL 0.00 O.OOE+00 0.0012+00 0.00E+00 O.ooE+00 O.00E+00 0.00E+00 O.00E+00 11-3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 214 278 0.OOE+00 2.83E-02 2.83 E-02 2.83E-02 2.83E-02 2.83E-02 2.83E-02 Dose Conmnitnment (torero) = 0.00E+00 2.83E-02 2.83E-02 2.83E-02 2.83E-02 2.83E-02 2.83E-02 Section 4 - Page 6 10OOOOO00O0*0000000OO0000000000000000000000OO

CatawbaNuclear Station Dose from Drinking Water Pathwayfor 2010 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/I)

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

Indicator Water Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/I) Bone Liver T. Body TIhyroid Kidney Lung GI-LLI Nlui-54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA 8.98E-06 ALL 0.00 0.OOE+00 0.OOE-t00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.00E+00 Co-58 NO I)ATA 1.80E-06 5.51 E-06 NO DATA NO DATA NO DATA LOSE-05 ALL 0.00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+i00 VC-59 i.65E-05 2.67E1-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 ALL 0.00 O.OOE+00 0.OOE+00 0.00E+00 O.OOE+i00 9.OOE+00 O.OOE+O0 O.OOE+/-00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 O.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00 Zn-65 1.37 E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41 E-06 ALL 0.00 O.OOE+00 0.OOEi-00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 O.OOE+00 Nb-95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+O0

'Lr-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-tOO 0.OOE+00 O.OOE+00 O.OOE+00 0.00 E+00 0.OOE+O0 V-131 1.72E-05 1.73 E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0 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 O.OOE+00 O.OOE+00 O.OOE-t00 0.OOE+00 0.OOE+00 0.OOE+00 0.00 E-i00 Cs-137 3.27E-04 3.13E-04 4.62 E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 ALL 0.00 O.OOE+O0 0.00E+00 0.OOE+00 0.0OE+00 O.OOE+00 0.OOE+00 O.OOE+00 Ba La- 140 8.31 E-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+O0 0.OOE+00 0.OOE+00 0.OOE+OO 11-3 NO DATA 2.03E-07 2.03 E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 214 278 O.OOE+00 2.88E-02 2.88E-02 2.88E-02 2.88E-02 2.88E-02 2.88E-02 Dose Commitment (tnrern) = 0.OOE+00 2.88E-02 2.88E-02 2.88E-02 2.88E-02 2.88E-02 2.88E-02 Section 4 - Page 7

Catawba Nuclear Station Dosefrom BroadleafVegetation Pathway for 2010 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-LL1 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.OOE+00 0.OOE+00 O.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 1.96 E-06 201 37.7 3.21E-01 3.07E-01 4.53E-02 0.00E+00 1.00E-01 3.60E-02 1.92E-03 Dose Commitment (mrem) = 3.21E-01 3.07E-01 4.53E-02 0.OOE+00 1.OOE-01 3.60E-02 1.92E-03 Section 4 - Page 8

Catawba Nuclear Station Dose from Fish Pathwayfor 2010 Data Maximum Exposed Child Child Dose from Fish Pathway (torem) = 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 = 6966 pCi/I x 0.9 = 6269 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 Gt-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 O.OOE+O0 O.OOE+00 0.OOE+00 O.OOE+00 O.OOk+O0 0.OOk+00 Co-58 NO DATA 1.80E-06 5.51 E-06 NO DATA NO DATA NO DATA 1.05E-05 ALL 0.00 0.00 E+00 O.OOk+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOk+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 O.OOE+00 0. 00E +00 0.OO+00 O.OOE+00 0.OOE+00 O.OOE+O0 O.OOE+00 CO-60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 ALL 0.00 0.0Ok+00 0.0OE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.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 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.00 E+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+O0 O.OOE+00 0.OOE+00 O.00E+00 0.OOE+00 O.00E+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.OOk+00 O.O0E+00 0.00E+00 0.OOE+00 O.OOE+O0 0.00 k-s00 0.OOk+00 H-3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 208 6269 O.OOE+00O 8.78E-03 8.78E-03 8.78E-03 8.78E-03 8.78E-03 8.78E-03 Dose Commitment (tnrero) = O.OOE+00 8.78E-03 8.78E-03 8.78E-03 8.78E-03 8.78E-03 8.78E-03 Section 4 - Page 9

CatawbaNuclear Station Dosefrom Shoreline Sediment Pathwayfor 2010 Data Maximum Exposed Child Shoreline Recreation = 14 hr (in one year)

Shore Width Factor = 0.2 2 Sediment Surface Mass = 40 kg/mn Child Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrcm/hr per pCi/m 2 ) x Shore Width Factor x Sediment Surface Mass (kg/mr2) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/mn2) Indicator Sediment (mrenm)

Radionuclide T. Body Skin Location (pCi/kg) T. Body Skin Mn-54 5.?IUE-1J9 6.80L-09 ALL 0.00 0.00E+00 0.01OE+00 Co-58 7.00E-09 8.20E-09 208-IS 65.6 5.14E-05 6.0 2E-05 Co-60 1.70E-08 2.00E-08 208-IS 137 2.61 E-04 3.0 7E-04 Cs-134 1.20E-08 i.40E-08 ALL 0.00 0.OOE+00 0.01OE+00 Cs-137 4.20E-09 4.90E-09 208-IS 25.6 1.20E-05 1.40E-05 Dose Commitment (f nrero) = 3.24E-04 3.81 E-04 Section 4 - Page 10

CatawbaNuclear Station Dosefrom Drinking Water Pathwayfor 2010 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (inrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/i)

Usage (intake in one year) - 510 I Highest Annual Net Mean In2estion Dose Factor Concentration Dose (mrem)

Indicator Water Radionucelide 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 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 O.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 0.00E+00 0.OOE+00 0.OOE+00 O.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 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.81 E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.OOE+00 O.OO'E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zu-65 5.76E-06 2.OOE-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE-'00 0.00E+00 O.OOE+00 0.OOE+00 0,OOE+00 N b-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 1.91 E-08 NO DATA 3.00E-05 ALL 0.00 0.OOE+00 0.OOE-t00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 5.85L-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 NO DATA 1.62E-06 ALL 0.00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOEi-00 Cs- 134 8.37E-05 1.97L-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+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 5.07 E-05 1.97E-05 2.12E-06 ALL 0.00 0.OOE+00 0.OOE-s00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BaLa-140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 ALL 0.00 O.OOE+00 O.OOE-i00 0.OOE+00 0.OOE+i00 O.OOE+00 0.OOE-t00 0.OOE-.00 1-1-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 214 278 0.OOE-400 1.50E-02 1.50E-02 1.50E-02 1 .50E-02 I1.50E-02 1.50E-02 Dose Commitment (torern)= 0.OOE+00 1.50E-02 1.SOJE-02 1.50E-02 1.50E-02 1.50E-02 1.50E-02 Section 4 - Page I1

CatawbaNuclear Station Dosefrom BroadleafVegetation Pathwayfor 2010 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 (pCilkg) 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 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Cs-134 8.37E-05 1.97 E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 ALL 0.00 O.OOE+00 O.OOE+0O 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Cs-137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1,97E-05 2.12E-06 201 37.7 1.77E-01 2.36E-01 8.22E-02 0.OOE+00 8.03E-02 3.12E-02 3.36E-03 Dose Commitment (mrem) = 1.77E-01 2.36E-01 8.22 E-02 O.OOE+00 8.03E-02 3.12E-02 3.36E-03 Section 4 - Page 12

CatawbaNuclear Station Dosefrom Fish Pathwayfor 2010 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 = 6966 pCi/I x 0.9 = 6269 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 1'. Body Thyroid Kidney Lung GI-LLI I n-54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.2 1E-05 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Co-58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 ALL 0.00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+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 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.81F-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 ALL 0.00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.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 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+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 0o.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 1.12E-04 1.49L-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 ALL 0.00 0,00E+00 0.00E+00 0.OOE+00 0.001E+00 0.001300 0.00E+00 0.OOE+00 11-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 208 6269 0.00E+00 1.06F-02 1.06E-02 1.06E-02 1.06E-02 1.06E-02 1.06E-02 Dose Commitment (torem) 0.00E+00 1.06E-02 1,06E-02 1.06E-02 1.06E-02 1.06E-02 1.06E-02 Section 4 - Page 13

CatawbaNuclear Station Dosefrom Shoreline Sediment Pathwayfor 2010 Data Maximum Exposed Teen Shoreline Recreation = 67 hr (in one year)

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

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/mn2) 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 0.00E+00 Co-58 7.00E-09 8.20E-09 208-IS 65.6 2.46E-04 2.88E-04 Co-60 1.70E-08 2.00E-08 208-IS 137 1.25E-03 1.47E-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 25.6 5.76E-05 6.72E-05 Dose Commitment (mrem) 1.55E-03 1.82E-03 Section 4 - Page 14

Catawba Nuclear Station Dosefrom Drinking Water Pathwayfor 2010 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 4.57 E-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 0.00E+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 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 4.34E-06 1.02E-05 3.91 E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE-00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02 E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Zn-65 4.84E-06 I.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 0.00E+00 0.00E+00 Nb-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+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 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+/-00 1-131 4.16E-06 5.95E-06 3.4 iE-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE-tOO 0.00E+00 0.OOE+00 0.0OE+i00 0.OOE+00 Cs-134 6.22E-05 1.48E-04 1.2 i E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+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 Ba La- 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 0.00E+00 0.OOE+00 0.OOE+00 0.00L+00 0.OOE+00 0.OOE+00 11-3 NO DATA 1.05E-07 1.05L-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 214 278 0.OOE+00 2.13E-02 2.13E-02 2.13 E-02 2.13E-02 2.13E-02 2.13E-02 Dose Commitment (rero): 0.OOE+00 2.13E-02 2.13E-02 2.13E-02 2.13E-02 2.13E-02 2.13E-02 Section 4 - Page 15

Catawba Nuclear Station Dosefrom BroadleafVegetation Pathwayfor 2010 Data Maximum Exposed Adult Adult Dose froin Vegetation (torero) = Usage (kg) x Dose Factor (mreni/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-LLU Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung CI-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.OOE+00 O.OOE+00 0.00E+00 0.00k+00 0.OOE+O0O0.OOE+00 0.OOE+OO 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 O.OOE+00 O.OOE+00 0.OOE+00 0.0OE+00 O.OOE+O0 0.OOE+O0O0.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 37.7 1.92E-01 2.63E-01 1.72E-01 O.00E+O0 8.93E-02 2.97E-02 5.09E-03 Dose Commitment (nirein) = 1.92E-01 2.63E-01 1.72E-01 O.OOE+00 8.93E-02 2.97E-02 5.09E-03 Section 4 - Page 16

CatawbaNuclear Station Dosefrom Fish Pathwayfor 2010 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 = 6966 pCi/I x 0.9 = 6269 pCi/kg Usage (intake in one year) = 21 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Radionuclide Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg) Bone Liver T. Body Thyroid Kidney Lung GI-LLI MIaa-54 NO DATA 4.57 E-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 1.51 E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 4.34E-06 1.02E-05 3.91 E-06 NO DATA NO DATA 2.85E-06 3.40E-05 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Co-60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02 E-05 ALL 0.00 0.QOE+00 o.OOE+Oo O.OOE+00 0.00E+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 Cs- 134 6.22E-05 1.48E-04 1.21 E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 3

('s-1 7 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11 E-06 ALL 0.00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 11-3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 208 6269 0.OOE+00 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.38E-02 Dose Commitment (tnreo) = 0.OOE+00 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.38E-02 Section 4 - Page 17

Catawba Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2010 Data Maximum Exposed Adult Shoreline Recreation = 12 hr (in one year)

Shore Width Factor = 0.2 Sediment Surface Mass = 40 kg/n 2 Adult Dose from Shoreline Sediment Pathway (norero) = Shoreline Recreation (hr) x External 2

Dose Factor (mrem/hr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/rn ) x Sediment Concentration (pCi/kg)

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

(niren/hr per pCi/M2 ) Indicator Sediment Radionuclide T. Body Skill Location (pCi/kg) T. Body Skill Mn-54 5.80E-09 6.80E-09 ALL 0.00 0.00E+00 0.OOE+00 Co-58 7.O0E-09 8.20E-09 208-IS 65.6 4.41E-05 5.16E-05 Co-60 1.70E-08 2.OOE-08 208-IS 137 2.24E-04 2.63E-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 25.6 1.03E-05 i.20E-05 Dose Commitment (noreno) 2.78E-04 3.27E-04 Section 4 - Page I 8

0 0

5.0 QUALITY ASSURANCE

5.1 SAMPLE COLLECTION 0

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

0

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.

0Duke Energy Corporation's

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

0 5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 0

5.4.1 DAILY QUALITY CONTROL 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 0

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 0frequency is dependent upon instrument use and performance. Investigations 0are performed and documented should calibration verification data fall out of

limits.

0 0

0 O ~Section 5 -Pagel1 0

0

0 0

5.4.3 BATCH PROCESSING Method quality control samples are analyzed with sample analyses that are processed in batches. These include gross beta in drinking water and tritium analyses.

5.5 DUKE ENERGY INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Energy Nuclear Generation Department Intercomparison Program during 2010. 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 2010 is documented in Table 5.0-A.

5.6 ERA PROFICIENCY TESTING 0

EnRad Laboratories performed method proficiency testing through a program administered by Environmental Resource Associates (ERA) of Arvada, CO. ERA supplied requested method proficiency samples for analysis and nuclide concentration determination. ERA reported proficiency test results to the North Carolina Department of Health and Human Services, North Carolina Public Health Drinking Water Laboratory Certification Program. A summary of these proficiency test data for 2010 is documented in Table 5.0-B.

5.7 DUKE ENERGY AUDITS 0

The Catawba Nuclear Station Radiological Environmental Monitoring Program was audited by the Quality Assurance Group in 2010. Procedure and sampling equipment enhancements were identified as part of this audit (reference 6.16).

During the McGuire 2010 Quality Assurance audit an item was identified concerning the calibration media used for fish and vegetation. Special tests were performed to confirm that the existing calibration media are acceptable. Additional information is included in Table 5.0-A and reference 6.17.

5.8 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS 0

The Catawba Nuclear Station Radiological Environmental Monitoring Program was not audited by the NRC in 2010. The program was audited by the NRC in 2009 (reference 6.12). No findings were noted in the 2009 report.

0 0

Section 5 -Page 2 0

0

0 0

5.9 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM

Catawba Nuclear Station routinely participates with the Bureau of Radiological Health

of the State's Department of Health and Environmental Control (DHEC) in an intercomparison program. The Memorandum of Agreement (MOA) between SC DHEC and Duke Energy describes the sampling frequency and analysis parameters for drinking water, surface water, milk, fish, vegetation, and shoreline sediment samples collected by EnRad Laboratories. Samples are routinely split with DHEC for 0intercomparison analysis. DHEC collects air samples near two of the locations

sampled for air by CNS. Results of the analyses performed on split and duplicate

samples are sent to DHEC.

0 5.10 TLD INTERCOMPARISON PROGRAM

5.10.1 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM 0

Radiation Dosimetry and Records participates in a quarterly TLD 0intercomparison program administered by Nuclear Technology Services, Inc. of Roswell, GA. Nuclear Technology Services irradiates environmental

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

5.10.2 INTERNAL CROSSCHECK (DUKE ENERGY) 0

Radiation Dosimetry and Records participates in a quarterly TLD

intracomparison program administered internally by the Dosimetry Lab. The Dosimetry Lab Staff irradiates environmental dosimeters quarterly and submits them for analysis of the unknown estimated delivered exposure. A summary of

the Internal Cross Check (Duke Energy) Result is documented in Table 5.0-C.

0 0

0

~~Section 5 -Page 3 0

0

0 0

TABLE 5.0-A S DUKE ENERGY INTERLABORATORY COMPARISON PROGRAM 0 0

2010 CROSS-CHECK RESULTS FOR 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 Gamma in Water 3.5 liters 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status 0 pCi/I pCi/I pCi/I 2/22/2010 Q1OIGWR Co-57 0.86- 1.52 E4 1.14 E4 1.16 E4 3 Pass S

Co-60 2.72-4.82 E3 3.62 E3 3.66 E3 3 Pass Ba-133 5.31 -9.43 E3 7.09 E3 5.70 E3 3 Pass Cs-137 4.67-8.27 E3 6.22 E3 6.15 E3 3 Pass 0 6/2/2010 Q102GWSL Cr-51 1.15-2.05 E5 1.54 E5 1.85 E5 3 Pass 0

Mn-54 4.91- 8.70 E4 6.54 E4 6.65 E4 3 Pass 0 Co-58 3.10-5.49 E4 4.13 Fe-59 3.79-6.72 E4 5.05 E4 E4 4.37 5.87 E4 E4 3

3 Pass Pass 0

Co-60 5.63-9.99 E4 7.51 E4 7.39 E4 3 Pass Zn-65 6.00 - 10.63 E4 7.99 E4 8.28 E4 3 Pass 0 Cs-134 3.62-6.42 E4 4.82 E4 4.33 E4 3 Pass Cs-137 Ce-141 4.29-7.61 3.66-6.49 E4 E4 5.72 4.88 E4 E4 5.38 5.70 E4 E4 3

3 Pass Pass 0

9/9/2010 Q103GWSL Cr-51 Mn-54 1.00- 1.77 4.34-7.69 E5 E4 1.33 5.79 E5 E4 1.35 6.05 E5 E4 3

3 Pass Pass S

Co-58 2.82-5.00 E4 3.76 E4 3.82 E4 3 Pass 0 Fe-59 3.64-6.46 E4 4.86 E4 5.21 E4 3 Pass Co-60 6.13 - 10.86 E4 8.17 E4 8.38 E4 3 Pass 0

Zn-65 7.44- 13.19 E4 9.92 E4 10.43 E4 3 Pass 0 Cs-134 3.35- 5.94 E4 4.47 E4 4.13 E4 3 Pass Cs-137 3.38-6.00 E4 4.51 E4 4.45 E4 3 Pass 0 Ce-141 5.41- 9.59 E4 7.21 E4 7.37 E4 3 Pass 0 0

Gamma in Water 1.0 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/I pCi/I pCi/I 2/22/2010 Q1OIGWR Co-57 0.86- 1.52 E4 1.14 E4 1.12 E4 3 Pass Co-60 2.72- 4.82 E3 3.62 E3 3.73 E3 3 Pass Ba-133 5.31 -9.43 E3 7.09 E3 5.56 E3 3 Pass Cs-137 4.67-8.27 E3 6.22 E3 6.06 E3 3 Pass Section 5 - Page 4

Gamma in Water 1.0 liter, continued Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range pCi/I Value pCi/I Value pCi/I Status 6/2/2010 Q102GWSL Cr-51 1.15- 2.05 E5 1.54 E5 1.85 E5 2 Pass 0 Mn-54 4.91- 8.70 E4 6.54 E4 6.70 E4 2 Pass 0 Co-58 Fe-59 3.10-5.49 E4 3.79-6.72 E4 4.13 E4 5.05 E4 4.38 E4 5.91 E4 2

2 Pass Pass 0 Co-60 5.63- 9.99 E4 7.51 E4 7.44 E4 2 Pass 0 Zn-65 Cs-134 6.00 - 10.63 E4 3.62- 6.42 E4 7.99 E4 4.82 E4 8.35 E4 4.25 E4 2

2 Pass Pass Cs-137 4.29-7.61 E4 5.72 E4 5.39 E4 2 Pass 0 Ce-141 3.66-6.49 E4 4.88 E4 5.69 E4 2 Pass 0 9/9/2010 Q103GWSL Cr-51 1.00-1.77 E5 1.33 E5 1.33 E5 3 Pass Mn-54 4.34-7.69 E4 5.79 E4 5.98 E4 3 Pass Co-58 2.82-5.00 E4 3.76 E4 3.76 E4 3 Pass 0 Fe-59 3.64-6.46 E4 4.86 E4 5.16 E4 3 Pass 0 Co-60 6.13 - 10.86 E4 8.17 E4 8.32 E4 3 Pass Zn-65 7.44- 13.19 E4 9.92 E4 10.43 E4 3 Pass 0 Cs-134 3.35- 5.94 E4 4.47 E4 3.98 E4 3 Pass 0 Cs-137 Ce-141 3.38-6.00 E4 5.41- 9.59 E4 4.51 7.21 E4 E4 4.43 7.24 E4 E4 3

3 Pass Pass 0

0 Gamma in Water 0. 5 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/I pCi/l 2/22/2010 Q101GWR Co-57 0.86- 1.52 E4 1.14 E4 1.12 E4 3 Pass 0 Co-60 2.72-4.82 E3 3.62 E3 3.73 E3 3 Pass Ba-133 5.31- 9.43 E3 7.09 E3 5.53 E3 3 Pass 0 Cs-137 4.67-8.27 E3 6.22 E3 6.04 E3 3 Pass 0 6/2/2010 Q102GWSL Cr-51 1.15- 2.05 E5 1.54 E5 1.81 E5 3 Pass 0 Mn-54 Co-58 4.91- 8.70 3.10-5.49 E4 E4 6.54 4.13 E4 E4 6.45 4.22 E4 E4 3

3 Pass Pass Fe-59 3.79-6.72 E4 5.05 E4 5.73 E4 3 Pass Co-60 5.63- 9.99 E4 7.51 E4 7.24 E4 3 Pass 0 Zn-65 Cs-134 6.00 - 10.63 3.62-6.42 E4 E4 7.99 4.82 E4 E4 8.10 4.10 E4 E4 3

3 Pass Pass Cs-137 4.29-7.61 E4 5.72 E4 5.17 E4 3 Pass Ce-141 3.66-6.49 E4 4.88 E4 5.46 E4 3 Pass 9/9/2010 Q103GWSL Cr-51 1.00-1.77 E5 1.33 E5 1.26 E5 3 Pass 0 Mn-54 4.34-7.69 E4 5.79 E4 5.55 E4 3 Pass Co-58 2.82-5.00 E4 0 Fe-59 3.64-6.46 E4 3.76 4.86 E4 E4 3.47 4.85 E4 E4 3

3 Pass Pass Co-60 6.13 - 10.86 E4 8.17 E4 7.80 E4 3 Pass Zn-65 7.44 - 13.19 E4 9.92 E4 9.76 E4 3 Pass Cs-134 3.35-5.94 E4 4.47 E4 3.69 E4 3 Pass Cs-137 3.38-6.00 E4 4.51 E4 4.11 E4 3 Pass Ce-141 5.41-9.59 E4 7.21 E4 6.68 E4 3 Pass Section 5 - Page 5

0 0

0 Gamma in Water 0.25 liter Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0

Date Range Value Value Status 0 pCi/l pCi/I pCi/I 2/22/2010 QIOIGWR Co-57 0.86- 1.52 E4 1.14 E4 1.09 E4 3 Pass 0 Co-60 Ba-133 2.72- 4.82 5.31-9.43 E3 E3 3.62 E3 7.09 E3 3.71 E3 5.56 E3 3

3 Pass Pass 0

Cs-137 4.67 - 8.27 E3 6.22 E3 5.88 E3 3 Pass 0 6/2/2010 Q102GWSL Cr-51 1.15-2.05 E5 1.54 E5 1.77 E5 3 Pass 0

Mn-54 4.91- 8.70 E4 6.54 E4 6.39 E4 3 Pass 0 Co-58 3.10-5.49 E4 4.13 E4 4.20 E4 3 Pass Fe-59 3.79-6.72 E4 5.05 E4 5.68 E4 3 Pass 0 Co-60 Zn-65 5.63-9.99 6.00 - 10.63 E4 E4 7.51 7.99 E4 E4 7.21 8.09 E4 E4 3

3 Pass Pass 0

Cs-134 3.62-6.42 E4 4.82 E4 4.09 E4 3 Pass 0 Cs-137 Ce-141 4.29-7.61 3.66-6.49 E4 E4 5.72 4.88 E4 E4 5.19 5.34 E4 E4 3 3 Pass Pass 0

0 9/9/2010 Q103GWSL Cr-51 1.00-1.77 E5 1.33 E5 1.35 E5 Mn-54 4.34-7.69 E4 5.79 E4 5.90 E4 3 3 Pass Pass 0

Co-58 2.82-5.00 E4 3.76 E4 3.67 E4 3 Pass 0 Fe-59 3.64-6.46 E4 4.86 E4 5.18 E4 3 Pass Co-60 Zn-65 6.13 - 10.86 E4 7.44- 13.19 E4 8.17 9.92 E4 E4 8.25 10.33 E4 E4 3

3 Pass Pass 0

Cs-134 3.35- 5.94 E4 4.47 E4 3.92 E4 3 Pass 0 Cs-137 3.38-6.00 E4 4.51 E4 4.33 E4 3 Pass Ce-141 5.41- 9.59 E4 7.21 E4 7.09 E4 3 Pass 0 0

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

pCi pCi pCi 0 6/17/2010 E7153-37 Cr-51 2.46-4.36 E2 3.28 E2 3.76 E2 2 Pass Mn-54 1.23-2.18 E2 1.64 E2 1.65 E2 2 Pass 0 Co-58 7.34 - 13.02 El 9.79 El 9.93 El 2 Pass 0 Fe-59 0.86- 1.53 E2 1.15 E2 1.05 E2 2 Pass Co-60 1.43- 2.53 E2 1.90 E2 1.86 E2 2 Pass 0 Zn-65 Cs-134 1.49-2.65 E2 0.92-1.62 E2 1.99 E2 1.22 E2 1.92 E2 1.13 E2 2

2 Pass Pass 0

Cs-137 1.09-1.93 E2 1.45 E2 1.40 E2 2 Pass 0 Ce-141 0.80- 1.42 E2 1.07 E2 1.01 E2 2 Pass 0

Gamma in Soil (SpecialTesting)

0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range pCi/kg Value pCi/kg Value pCi/kg Status 0 12/9/2010 E7380-37 Cr-51 2.60-9.98 E2 5.09 E2 5.85 E2 4 Pass 0 Mn-54 1.01- 1.78 E2 1.34 E2 1.42 E2 4 Pass Co-58 0.76- 1.34 E2 1.01 E2 0.96 E2 1/4Low 1 l) 0 Fe-59 0.95- 2.25 E2 1.46 E2 1.42 E2 4 Pass 0 Co-60 2.52-4.47 E2 3.36 E2 3.27 E2 4 Pass Zn-65 1.46-2.58 E2 1.94 E2 1.97 E2 4 Pass 0

Cs-134 1.31-2.33 E2 1.75 E2 1.54 E2 4 Pass 0 Cs-137 2.24-3.96 E2 2.98 E2 2.89 E2 4 Pass INOS Audit 1O-15(INOS)(REC)(MNS) 2010, PIP M-10-06597 Section 5 - Page 6

0 0

0 Gamma in Vegetation (Special Testing)

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status pCi/kg pCi/kg pCi/kg 12/9/2010 E7381-37 Cr-51 2.36-11.11 E2 5.12 E2 5.10 E2 1 Pass 0 Mn-54 1.01- 1.78 E2 1.34 E2 1.51 E2 1 Pass Co-58 0.76- 1.34 E2 1.01 E2 1.00 E2 1 Pass S Fe-59 0.84-2.57 E2 1.47 E2 1.54 E2 1 Pass Co-60 2.54-4.50 E2 3.38 E2 3.38 E2 1 Pass 0 Zn-65 1.46-2.59 E2 1.95 E2 2.24 E2 1 Pass Cs-134 1.32-2.34 E2 1.76 E2 1.51 E2 1 Pass Cs-137 1.57-2.78 E2 2.09 E2 2.03 E2 I Pass 0 INOS Audit 10-15(INOS)(REC)(ANS) 2010, PIPM-10-06597 0 Iodine in Milk Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check 0 Date Range Value Value Status S 37/72/01 Q101LIM1 I -131 pCi/l 2.29-4.06 E pCi/l

--7.76E pCi/l 2.38 El 1 Pass 0 3/2/2010 Q 1LIM2 1-131 1.25-2.21 E3 1. 3 1.39 E3 3 Pass 0 3/2/2010 Q101LIM3 1-131 6.27 -11.13771 8.37 E3 6.44 E3 2 Pass 0

0 Iodine on Cartridge 0 Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 6/17/2010 E7154-37 1-131 6.01 - 10.65 i 8.7E 8.39 El 3 Pass 0

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

-72/T/ -101TW H-7 6.68 - 11.84 E 5 9.00 E5 3 Pass 2/22/2010 Q101TWS2 H-3 0.79- 1.40 E7 1.05 E7 -T.00E 3 Pass 0 11/4/2010 Q1U41WRI H-3 3.14-5.56 E3 4.18 E3 3.91 E3 3 Pass 0 11/4/2010 Q104TW=2 H-3 3.40-6.02 E4 4.53 E4 4.26 E4 3 Pass S 11/4/2010 Q104TWR3 H-3 4.98-8.83 E! 6.64 E2 6.12 E2 3 Pass 0

Gross Beta in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/I pCi/I 11/7 Q104ABWI s-377 5.43-9.63 = 7.7TE 6.79 E I Pass 11/18/201I Q104ABW2 I Cs-137 1 4.88-8.66 El 6.51 El 6.44 E1 3 Pass I1I/18}2s/0101IU5Q104ABW3 I Cs-137 1 1.15-2.03 El 1.53 El 1.52 El 3 Pass Section 5 - Page 7

0 0

Table 5.0-A Footnote Explanations 0 0

(1) Gamma in Soil (Special Testing), Sample ID E7380-37, Reference Date 12/9/2010 0 0

One of four Co-58 results was biased low and outside of the acceptance range 0 (reference 6.18).

0 0

0 Section 5 - Page 8 0

0 0

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

QUIK TM RESPONSE PROGRAM 0

2010 PROFICIENCY TEST RESULTS FOR 0 ENRAD LABORATORIES S

0 ERA LABORATORY CODE: D242401 0 Proficiency test samples are received, prepared, analyzed, and reported to Environmental Resource Associates 0 as described in the "Quik" Response instruction package within the study period. Proficiency test data are reported to ERA for evaluation. ERA reports proficiency test results to the North Carolina Department of S 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 0 Date Range Value Value Status 0 pCi/l pCi/I pCi/l 4/5/2010 RAD-81* Ba-133 5.49 - 7.25 El 6.59 El 7.26 El High (1)

Cs-134 5.84 - 7.88 E1 7.16 El 6.74 El Pass 0 Cs-137 1.31 - 1.63 E2 1.46 E2 1.33 E2 Pass 0 Co-60 7.60 - 9.53 El 8.45 E1 8.40 El Pass 0 Zn-65 1.67 - 2.19 E2 1.86 E2 1.93 E2 Pass 0 1/10/2010 Quik 120810K** Ba-133 6.10 - 8.02 E1 7.29 E1 7.75 El Pass 0 Cs-134 5.15 - 6.97 El 6.34 El 6.18 El Pass 0 Cs-137 1.08 - 1.34 E2 1.20 E2 1.14 E2 Pass 0 Co-60 8.10 - 10.1 El 9.00 El 9.90 El Pass 0 Zn-65 1.89 - 2.46 E2 2.10 E2 2.12 E2 Pass Tritium in Water 0 Reference Sample I.D. Nuclide Acceptance Reference Reported Proficiency Check 0 Date Range pCi/l Value pCi/I Value pCi/I Status 0 4/5/2010 RAD-81* H-3 1.08 - 1.36 E4 1.24 E4 1.16 E4 Pass 1/10/2010 Quik 120810K** H-3 3.16-4.10 E3 3.72 E3 3.58 E3 Pass 0

ERA study period 4/5/2010 - 5/20/2010, ERA datareport issue date 5/26/2010

- ERA study period 12/8/2010 - 3/30/2011, ERA data report issue date 3/30/2010 Section 5 - Page 9

Table 5.0-B Footnote Explanations (1) Gamma Emitters in Water, Sample ID RAD-8 1, Reference Date 4/5/2010 0

Reported result for Ba-133 was above the acceptance range limit (reference 6.19). 0 0

0 0

Section 5 - Page 10 0

0

0 0

0 TABLE 5.0-C 0 2010 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS 0

Nuclear Technology Services 1w 1st Quarter 2010 2nd Quarter 2010 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail

102379 105.0 101.9 3.04 <+/-15% Pass 102501 71.0 73.0 -2.74 <+/-15% Pass 102385 103.0 101.9 1.08 <+/-15% Pass 102013 73.0 73.0 0.00 <+/-15% Pass 102403 103.0 101.9 1.08 <+/-l 5% Pass 100309 73.0 73.0 0.00 <+/-1 5% Pass 102480 101.0 101.9 -0.88 <+/-15% Pass 100623 70.0 73.0 -4.11 <+/-15% Pass 102505 103.0 101.9 1.08 <+/-15% Pass 102060 72.0 73.0 -1.37 <+/-15% Pass Average Bias (B) 1.08 Average Bias (B) -1.64 Standard Deviation (S) 1.39 Standard Deviation (S) 1.79 Measure Performance IBI+S 2.47 <15% Pass Measure Performance IB +S 3.43 <15% Pass 3rd Quarter 2010 4th Quarter 2010 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 100252 56.1 55.9 0.36 <+/-15% Pass 102367 88.0 84.0 4.76 <+/-15% Pass 100403 55.2 55.9 -1.25 <+/-15% Pass 102399 91.0 84.0 8.33 <+/-15% Pass 101143 55.3 55.9 -1.07 <+/-15% Pass 102402 87.0 84.0 3.57 <+1-15% Pass 100065 54.2 55.9 -3.04 <+/-15% Pass 102480 90.0 84.0 7.14 <+/-15% Pass 100054 57.2 55.9 2.33 <+/-15% Pass 102510 90.0 84.0 7.14 <+/-15% Pass Average Bias (B) -0.54 Average Bias (B) 6.19 Standard Deviation (S) 2.00 Standard Deviation (S) 1.96 Measure Performance IBI+S 2.54 <15% Pass Measure Performance IBI+S 8.15 <15% Pass 0

0 0

0 Section 5 - Page II 0

0

Internal Crosscheck (Duke Energy) 0 1st Quarter 2010 2nd Quarter 2010 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail 0 Number (mR) (mR) (% diff) Criteria Pass/Fail Number 102384 21.5 22.0 -2.18 <+/-15% Pass 101183 (mR) 29.2 (mR) 30.0

(% diff)

-2.60 Criteria Pass/Fail

<+/-15% Pass 0

102399 21.4 22.0 -2.82 <+/-15% Pass 100709 29.8 30.0 -0.70 <+/-15% Pass 0 102406 102487 21.9 20.5 22.0 22.0

-0.50

-6.68

<+/-15%

Pass Pass 101167 101290 29.0 28.2 30.0 30.0

-3.30

-6.07

<+/-15%

Pass Pass 0

102260 21.1 22.0 -4.27 <+/-15% Pass 100027 28.2 30.0 -6.07 <+/-15% Pass 0 102504 21.2 22.0 -3.45 <+/-15% Pass 101310 28.6 30.0 -4.67 <+/-15% Pass 0 102393 20.8 22.0 -5.45 <+/-15% Pass 101189 29.6 30.0 -1.33 <+/-15% Pass 102261 21.2 22.0 -3.68 <+/-15% Pass 101158 29.7 30.0 -1.03 <+/-15% Pass 0 102343 20.9 22.0 -5.09 <+/-15% Pass 101386 31.0 30.0 3.47 <+/-15% Pass 0 101235 21.5 22.0 -2.36 <+/-15% Pass 101398 32.4 30.0 8.03 <+/-15% Pass Average Bias (B) -3.65 Average Bias (B) -1.43 0

Standard Deviation (S) 1.81 Standard Deviation (S) 4.38 0 Measure Performance IBI+S 5.46 <15% Pass Measure Performance IBI+S 5.81 <15% Pass 0 3rd Quarter 2010 4th Quarter 2010 0 TLD Reported Delivered Bias Pass/Fail TLD Reported Delivered Bias Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail Number (mR) (mR) (% diff) Criteria Pass/Fail 0 102264 96.8 100.0 -3.21 <+/-15% Pass 102301 33.1 35.0 -5.46 <+/-15% Pass 0 102406 101.4 100.0 1.41 <+/-15% Pass 102471 34.8 35.0 -0.49 <+/-15% Pass 102399 99.7 100.0 -0.30 <+/-15% Pass 102083 33.7 35.0 -3.66 <+/-15% Pass 0

102403 97.0 100.0 -2.97 <+/-15% Pass 102442 33.4 35.0 -4.60 <+/-15% Pass 0 102480 102505 98.8 99.0 100.0 100.0

-1.17

-1.00

<+/-15%

Pass Pass 102389 102362 33.4 33.9 35.0 35.0

-4.46

-3.20

<+/-15%

Pass Pass 0

102440 95.1 100.0 -4.95 <+/-15% Pass 101413 33.4 35.0 -4.66 <+/-15% Pass 0 102479 101136 95.7 98.2 100.0 100.0

-4.33

-1.84

<+/-15%

Pass Pass 102007 102509 33.1 34.9 35.0 35.0

-5.57

-0.31

<+/-15%

Pass Pass 0

102339 95.6 100.0 -4.41 <+/-15% Pass 102058 33.2 35.0 -5.23 <+/-15% Pass 0 Average Bias (B) -2.28 Average Bias (B) -3.76 0 Standard Deviation (S) 2.05 Standard Deviation (S) 1.92 Measure Performance IBI+S 4.33 <15% Pass Measure Performance IBI+S 5.68 <15% Pass 0 0

0 0

0 Section 5 - Page 12 0

0 0

0

6.0 REFERENCES

6.1 Catawba Selected License Commitment Report 6.2 Catawba Technical Specifications 6.3 Catawba Updated Final Safety Analysis Review 0 6.4 Catawba Offsite Dose Calculation Manual 6.5 Catawba Annual Environmental Operating Report 1985 - 2009 0

6.6 Catawba Annual Effluent Report 1985 - 2010 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 Doses to Man from Routine Releases of Reactor Effluents for the Purposes of

Evaluating Compliance with 10CFR50, Appendix I.

6.10 EnRad Laboratories Operating Procedures 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) 0 6.15 Nuclear System Directive (NSD) 701, Records Management 6.16 Radiological Effluents Controls INOS Audit 10-13(INOS)(REC)(CNS) 0 6.17 Radiological Effluent Controls INOS Audit 10-1 5(INOS)(REC)(MNS) 6.18 Problem Investigation Program Database, V 3.4.1, Duke Energy Company, G- 11-00581 0

6.19 Problem Investigation Program Database, V 3.4.1, Duke Energy Company, G- 11-00598 6.20 Problem Investigation Program Database, V 3.4.1, Duke Energy Company, G-11 -01294 0

0 Section 6 -Page 1 0

0

0 0

0 APPENDIX A S

0 0 ENVIRONMENTAL SAMPLING 0

0 &

0 ANALYSIS PROCEDURES 0

0 0

S 0

0 Appendix A - Page 1 0

0

0 APPENDIX A 0 0

0 ENVIRONMENTAL SAMPLING AND 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.

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 Location 205 (Air Particulate, Air Radioiodine, TLD) distance was updated from 0.23 miles to 0.25 miles as a result of assessment RP-SA-2009-0025 (reference 6.20). 0 II. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software. Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy. Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry.

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.

0 0

0 Appendix A -Page 2 0

0 0

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

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

0 III. CHANGE OF ANALYSIS PROCEDURES 0

No analysis procedures were changed during 2010.

IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE 0Airborne particulate and radioiodine samples at each of five locations were 0composited 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 (0.25 mi. SW)

Location 212 Tega Cay (3.32 mi. E) 0*Location 258 = Fairhope Road (9.84 mi. W)

A.2 DRINKING WATER 0* Monthly composite drinking water samples were collected at each of two locations. 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

0 Appendix A -Page 3 0

S 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) 0 Location 215 River Pointe - Hwy 49 (4.21 mi. NNE) 0 S

A.4 GROUND WATER 0

Grab samples were collected quarterly from residential wells at each of two locations. A gamma analysis and tritium analysis were performed on each sample. The samples were collected from the locations listed below.

S Location 252 Residence (0.64 mi. SW) 0 Location 254 Residence (0.82 mi. N) 0 A.5 MILK 0 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 S were collected from the location listed below. 0 Location 221 - Dairy (14.5 mi. NW) 0 A.6 BROADLEAF VEGETATION S Monthly samples were collected at each of five locations. A gamma analysis 0

was performed on each sample. The samples were collected from the locations 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)

Location 226 Site Boundary (0.48 mi. S) 0 Location 258 Fairhope Road (9.84 mi. W) 0 A.7 FOOD PRODUCTS 0 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

S 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) 0 A.9 SHORELINE SEDIMENT 0Semiannual 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) 0A.10 DIRECT GAMMA RADIATION (TLD)

Thermoluminescent dosimeters (TLD) were collected quarterly at forty-one locations. A gamma exposure rate was determined for each TLD. TLD locations are listed in Table 2.1-B. The TLDs were placed as indicated below.

SAn 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 0*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 0

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:

0

The Nearest Residence

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

0 0

O Appendix A - Page 5 0

0 0

The Nearest Milk-giving Animal (cow, goat, etc.) 0 0

The census was conducted during the growing season from 7/14 to 7/15/2010. 0 Results are shown in Table 3.11. No changes were made to the sampling procedures during 2010 as a result of the 2010 census.

0 0

V. GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS 0 0

The Catawba site centerline used for GPS measurements was referenced from the 0 Catawba Nuclear Station Updated Final Safety Analysis Report (UFSAR), section 2.1.1.1, Specification of Location. Waypoint coordinates used for CNS GPS 0

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 0 measurements were taken as close as possible to the item of interest. Distances for the locations are displayed using three significant figures.

0 0

Appendix A - Page 6 0

0 0

0 APPENDIX B 0

0 0 RADIOLOGICAL 0

0 ENVIRONMENTAL MONITORING 0 PROGRAM 0

0 0

SUMMARY

OF RESULTS 0

0 0 2010 0

0 0

S 0

0 0

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 0

Report Period: 01-JAN-2010 to 31-DEC-2010 0

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

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

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

BETA 264 L.00E-02 1.98E-2 (211/211) 212 2.03E-2 (53/53) 1.90E-2 (53/53) 0 0 8.86E 3.83E-2 (3.32 mi E) 1.08E 3.67E-2 8.59E 3.73E-2 0 CS-134 264 5.OOE-02 0.00 (0/211) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 264 6.OOE-02 0.00 (0/211) 0.00 (0/53) 0.00 (0/53) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 264 7.OOE-02 0.00 (0/211) 0.00 (0/53) 0.00 (0/53) 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)

Zero range indicates no detectable activity measurements 0

0 0

0 Report Generated @ 5/2/2011 12:16 Appendix B - Page 2

0 0

0 Environmental Radiological Monitoring Program Summary 0 Facility: Catawba Nuclear Station Docket No. 50-413,414 0i Location: York County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 0

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

Sampledof 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)

CS-134 264 5.OOE-02 0.00 (0/211) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S CS-137 264 6.OOE-02 0.00 (0/211) 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 1-131 264 7.OOE-02 0.00 (0/211) 0.00 - 0.00 0.00 (0/53) 0.00 (0/53) 0 0.00 - 0.00 0.00 - 0.00 0 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

0 0

0 0 Report Generated @ 5/2/2011 12:16 0 Appendix B - Page 3

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-2010 to 31-DEC-2010 Location with Highest ControlNone No. of Non- 0 Medium or Type and Total Lower Limit of Annual Mean Pathway Number Detection Locations Name, Distance, Direction Location Report 0 Sampled of Meas.

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

Measurement Performed Range Code Range Range 0 Drinking Water 218 (pCi/liter) (13.5 mi NNE) 0 BALA-140 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 BETA 26 4 1.84 (13/13) 214 1.84 (13/13) 1.80 (12/13) 0 0.82 -2.87 (7.30 mi SSE) 0.82 - 2.87 1.01 - 2.71 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 705 (4/4) 214 705 (4/4) 427 (4/4) 0 507-993 (7.30 mi SSE) 507-993 292-619 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) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 26 15 0.00 (0/13) 0.00 (0/13) 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 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements 0 0

0 Report Generated @ 5/2/2011 12:16 0

Appendix B - Page 4 0

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 0 No. of Non-Medium or Type and Total Lower All Idit Location with Highest Control Routine Pathway Number Limit of Annual Mean 0 Sampled of Detection Name, Distance, Direction Lepor Meas.

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

Surface Water 215 (pCi/liter) (4.21 mi NNE)

BALA-140 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CO-58 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CO-60 39 15 0.00 (0/26) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0.00 (0/13) 0.00 - 0.00 0

0 CS-134 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 39 18 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 H-3 12 2000 3970 (8/8) 208 7260 (4/4) 294 (3/4) 0 0 468- 11900 (0.45 mi S) 4180-11900 221 -390 1-131 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 MIN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 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

0 0

0 Report Generated @ 5/2/2011 12:16 0 Appendix B - Page 5

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-2010 to 31-DEC-2010 0

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

Sampled Meas.

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

Measurement Performed Range Code Range Range Ground Water NO CONTROL (pCi/liter) LOCATION BALA-140 5 15 0.00 (0/5) 0.00 (0/4) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 5 15 0.00 (0/5) 0.00 (0/4) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 5 15 0.00 (0/5) 0.00 (0/4) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 5 15 0.00 (0/5) 0.00 (0/4) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 CS-137 5 18 0.00 (0/5) 0.00 (0/4) 0.00 (0/0) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 5 30 0.00 (0/5) 0.00 (0/4) 0.00 (0/0) 0 0

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 H-3 5 2000 0.00 (0/5) 0.00 (0/4) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

1-131 5 15 0.00 (0/5) 0.00 (0/4) 0.00 (0/0) 0 0 MN-54 5 15 0.00 - 0.00 0.00 (0/5) 0.00 - 0.00 0.00 (0/4) 0.00 - 0.00 0.00 (0/0) 0 0

0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 NB-95 5 15 0.00 (0/5) 0.00 (0/4) 0.00 (0/0) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 5 30 0.00 (0/5) 0.00 (0/4) 0.00 (0/0) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 5 15 0.00 (0/5) 0.00 (0/4) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 5/2/2011 12:16 Appendix B - Page 6

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 No. of Non-Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean 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 Milk NO INDICATOR 221 (pCi/liter) LOCATION (14.5 mi NW) 0 BALA-140 26 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 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 0 CS-137 26 18 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 26 15 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 S LLI-131 26 1 0.00 (0/0) 0.00 (0/0) 0.00 (0/26) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 Mean and range based upon detectable measurements only 0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements 0

0 0

0 0 Report Generated @ 5/2/2011 12:16 Appendix B - Page 7

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-2010 to 31-DEC-2010 0 0

No. of Non-Medium or Type and Total Lower All IndicatorCotl Location with Highest ControlNone Ruin 0

Number Limit of Annual Mean Pathway 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 Broadleaf 258 Vegetation (9.84 mi W)

(pCi/kg-wet)

CS-134 60 60 0.00 (0/48) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0

CS-137 60 80 37.7 (3/48) 201 37.7 (3/12) 0.00 (0/12) 0 0 20.6 - 55.8 (0.53 mi NE) 20.6 - 55.8 0.00 - 0.00 1-131 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 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 @ 5/2/2011 12:16 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-2010 to 31-DEC-2010 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 Food Products NO CONTROL (pCi/kg-wet) LOCATION 0 CS-134 6 60 0.00 (0/6) 0.00 (0/6) 0.00 (0/0) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 6 80 0.00 (0/6) 0.00 (0/6) 0.00 (0/0) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 6 60 0.00 (0/6) 0.00 (0/6) 0.00 (0/0) 0 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 0 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) 0 Zero range indicates no detectable activity measurements 0

0 S

0 0

0 Report Generated @ 5/2/2011 12:16 Appendix B - Page 9

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-2010 to 31-DEC-2010 No. of Non- 0 Medium or Type and Total Lower Location with Highest ControlNone Pathway Number Limit of Annual Mean of Detection Locations Name, Distance, Direction Location Report Sampled Meas.

0 Unit of Measurement Analyses Performed (

LLD Mean (Fraction)

Range Location Code Mean (Fraction)

Range Mean (Fraction)

Range 0

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

CO-58 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 (0/6) 0.00 - 0.00 0 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 0 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

0.00 - 0.00 0.00 -0.00 0.00- 0.00 0 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

0 Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) S 0

Zero range indicates no detectable activity measurements 0

0 0

0S 0

0 0

0 Report Generated @ 5/2/2011 12:16 Appendix B - Page 10 00 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-2010 to 31-DEC-2010 No. of Non-0 Medium or Type and Total Lower Location with Highest ControlNone Number Limit of Annual Mean 0 Pathway Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

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

Measurement Performed Range Code Range Range Shoreline 215 Sediment (4.21 mi NNE)

(pCi/kg-dry)

MN-54 6 0 0.00 (0/4) 0.00 (0/2) 0.00 (0/2) 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 6 0 65.6 (2/4) 208-IS 65.6 (2/2) 0.00 (0/2) 0 63.0-68.1 (0.45 mi S) 63.0-68.1 0.00-0.00 CO-60 6 0 137 (2/4) 208-IS 137 (2/2) 0.00 (0/2) 0 31.5-243 (0.45 mi S) 31.5-243 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 25.6 (1/4) 208-1S 25.6 (1/2) 0.00 (0/2) 0 0 25.6 - 25.6 (0.45 mi S) 25.6 - 25.6 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)

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

0 0

0 Report Generated @ 5/2/2011 12:16 Appendix B - Page 11 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-2010 to 31-DEC-2010 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 @ 5/2/2011 12:16 0 Appendix B - Page 12 0

0

0 0

0 APPENDIX C 0

0 0

SAMPLING DEVIATIONS 0 &

0 UNAVAILABLE ANALYSES 0

0 0

0 0 Appendix C - Page 1 0

S S

I S

S APPENDIX C S S

S CATAWBA NUCLEAR STATION S SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES S S

BF Blown Fuse DEVIATION & UNAVAILABLE REASON CODES PO Power Outage S

FZ Sample Frozen PS Pump out of service / Undergoing Repair 1W Inclement Weather SL Sample Loss/Lost due to Lab Accident S LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Tom Filter S

PI Power Interrupt VN Vandalism S PM WO Preventive Maintenance Well Unavailable/Out of Service CN Construction S 6

C.1 SAMPLING DEVIATIONS S S

Air Particulate and Air Radioiodines S Scheduled Actual Reason S Location Collection Dates Collection Dates Code Corrective Action Power interruption due to breaker trip.

S Breaker was reset and normal sampling S 258 2/16 - 2/23/2010 2/16 - 2/18/2010 PO resumed. S Power interruption due to breaker trip.

Work request 77735 initiated to verify S electrical supply stability. Breaker reset, S 258 3/9 - 3/16/2010 3/9 - 3/10/2010 PO normal sampling resumed.

S Surface Water S Intake line clog to sampling equipment. S Work request 79212 written. Flow restored 5/11/2010. Second line clog S

interrupted sampling during subsequent S monitoring period. Work request 80216 written. Maintenance increased water S

5/4 - 6/2/2010 5/11 - 6/2/2010 flow through intake line. PIP G-10-00819 S 215 6/2 - 6/29/2010 6/10 - 6/29/2010 LC written.

S S

Appendix C - Page 2 S

S S

0 0

0 C.2 UNAVAILABLE ANALYSES 0 Air Particulate and Air Radioiodines Scheduled Reason 0 Location Collection Dates Code Corrective Action 0 Power interruption due to surge protector failure.

Sampling equipment did not operate to collect 0 205 5/18 - 5/25/2010 PO sufficient volume for analysis.

0 Ground Water Scheduled Reason 0 Location Collection Dates Code Corrective Action 0 6/8/2010 Well at this location (residence) is out of service.

0 9/8/2010 Residence is vacant and power is not available to 252 12/7/2010 WO operate well pump. PIP G-10-00754 generated.

0 0 TLD 0 Scheduled Reason Location Collection Dates Code Corrective Action 249 6/16 - 9/15/2010 VN I TLD missing. 4th quarter 2010 TLD placed in field.

0 0

0 S

0 Appendix C - Page 3

0 0

APPENDIX D 0

0 0 ANALYTICAL DEVIATIONS 0

0 No Analytical deviations were incurred for the 0 2010 Radiological Environmental Monitoring Program 0

0 S

0 0

Appendix D - Page 1

ML11137A211

Contents

Text

Subject:

SUMMARY

2.0 INTRODUCTION

6.0 REFERENCES

SUMMARY

Navigation menu

ML11137A211

Text

Subject:

SUMMARY

2.0 INTRODUCTION

6.0 REFERENCES

SUMMARY

Navigation menu

Search