ML041380382

Annual Radiological Environmental Operating Report

ML041380382
Person / Time
Site:	Catawba
Issue date:	05/10/2004
From:	Jamil D Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML041380382 (90)

Text

Duke

'i

rOPowere, A Duke Energy Company D.M. JAMIL Vice President Duke Power Catawba Nuclear Station 4800 Concord Rd. / CN01 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax May 10, 2004 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 2003 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 2003 Annual Radiological Environmental Operating Report. This report covers operation of Catawba Units 1 and 2 during the 2003 calendar year.

There are no commitments contained in this submittal.

Any questions concerning this report should be directed to Kay Nicholson at 803.831.3237.

Dhiaa M. Jamil Enclosure xc:

(* w/o enclosure)

L. A. Reyes, Regional Administrator,-Region II S. E. Peters, NRR Project Manager

• -;1

• E. F. Guthrie, Senior Resident Inspector

,5 www. duke-energy. corn

Duke dWPower.

Catawba Nuclear Station Units 1 and 2 AREOR Annual Radiological Environmental Operating Report 2003

1h Duke A Duke Energy Company ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE POWER COMPANY CATAWBA NUCLEAR STATION Units 1 and 2 2003

TABLE OF CONTENTS 1.0 Executive Summary.

1-1 2.0 Introduction 2-1 2.1 Site Description and Sample Locations 2-1 2.2 Scope and Requirements of the REMP 2-1 2.3 Statistical and Calculational Methodology.

2-2 2.3.1 Estimation of the Mean Value.

2-2 2.3.2 Lower Level of Detection and Minimum Detectable Activity 2-3 2.3.3 Trend Identification.

2-3 3.0 Interpretation of Results 3-1 3.1 Airborne Radioiodine and Particulates 3-2 3.2 Drinking Water 3-4 3.3 Surface Water 3-6 3.4 Ground Water.

3-8 3.5 Milk.

3-9 3.6 Broadleaf Vegetation.

3-10 3.7 Food Products 3-12 3.8 Fish.

3-13 3.9 Shoreline Sediment 3-16 3.10 Direct Gamma Radiation 3-18 3.11 Land Use Census 3-20 4.0 Evaluation of Dose 4-1 4.1 Dose from Environmental Measurements 4-1 4.2 Estimated Dose from Releases 4-1 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 5A.3 Batch Processing 5-2 5.5 Duke Power Intercomparison Program 5-2 5.6 Duke Power Audits 5-2 5.7 U.S. Nuclear Regulatory Commission Inspections 5-2 5.8 State of South Carolina Intercomparison Program 5-2 5.9 TLD Intercomparison Program.

5-3 5.9.1 Nuclear Technology Services Intercomparison Program 5-3 5.9.2 State of North Carolina Intercomparison Program 5-3 5.9.3 Internal Crosscheck (Duke Power) 5-3 6.0 References 6-1 i

Appcndices Appendix A: Environmental Sampling and Analysis Procedures A-1 I.

Change of Sampling Procedures A-2 II. Description of Analysis Procedures A-2 III. Change of Analysis Procedures A-3 IV. Sampling and Analysis Procedures A-3 A.1 Airborne Particulate and Radioiodine A-3 A.2 Drinking Water A-3 A.3 Surface Water A-4 A.4 Ground Water.

A-4 A.5 Milk A4 A.6 Broadleaf Vegetation A-4 A.7 Food Products.

A-5 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-6 V.

Global Positioning System (GPS) Analysis.

A-6 Appendix B: Radiological Env. Monitoring Program - Summary of Results B-i 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-i i Direct Gamma Radiation (TLD)

B-12 Appendix C: Sampling Deviations and Unavailable Analyses C-1 C. 1 Sampling Deviations C-2 C.2 Unavailable Analyses C-3 Appendix D: Analytical Deviations D-1 Appendix E: Radiological Environmental Monitoring Program Results E-1 LIST OF FIGURES 2.1-1 2.1-2 3.1 3.2 3.3 3.6 3.8-1 3.8-2 3.9-1 3.9-2 3.10 3.11 Sampling Locations Map (One Mile Radius)

Sampling Locations Map (Ten Mile Radius)

Concentration of Gross Beta in Air Particulate Concentration of Tritium in Drinking Water Concentration of Tritium in Surface Water.

Concentration of Cs-137 in Broadleaf Vegetation Concentration of Co-58 in Fish.

Concentration of Co-60 in Fish.

Concentration of Co-58 in Shoreline Sediment Concentration of Co-60 in Shoreline Sediment Direct Gamma Radiation (TLD) Results 2003 Land Use Census Map 24 2-5 3-2 3-5 3-6 3-10 3-14 3-14 3-16 3-17 3-18 3-21 ii

LIST OF TABLES 2.1-A Radiological Monitoring Program Sampling Locations 2.1-B Radiological Monitoring Program Sampling Locations (TLD Sites) 2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2.2-B REMP Analysis Frequency 2.2-C Maximum Values for the Lower Limits of Detection 3.1-A Mean Concentration of Gross Beta in Air Particulate 3.1-B Mean Concentration of Air Radioiodine (I-131).

3.2 Mean Concentrations of Radionuclides in Drinking Water 3.3 Mean Concentrations of Radionuclides in Surface Water 3.5 Mean Concentration of Radionuclides in Milk 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation 3.7 Mean Concentration of Radionuclides in Food Products 3.8 Mean Concentrations of Radionuclides in Fish 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment 3.10 Direct Gamma Radiation (TLD) Results 3.11 Land Use Census Results 4.1-A 2003 Environmental and Effluent Dose Comparison 4.1-B Maximum Individual Dose for 2003 based on Environmental Measurements for Catawba Nuclear Station 5.0-A 2003 Cross-Check Results for EnRad Laboratories 5.0-B 2003 Environmental Dosimeter Cross-Check Results LIST OF ACRONYMS USED IN THIS TEXT (in alphabetical order) 2-6 2-7 2-8 2-8 2-9 3-3 3-3 3-5 3-7 3-9 3-11 3-12 3-15 3-17 3-19 3-20 4-3 4-6 5-4 5-9 BW BiWeekly C

Control CNS Catawba Nuclear Station DEHNR Department of Environmental Health and Natural Resources DHEC Department of Health and Environmental Control EPA Environmental Protection Agency GI-LLI Gastrointestinal - Lower Large Intestine GPS Global Positioning System LUD Lower Umit of Detection M

Monthly MDA Minimum Detectable Activity mrem millirem NIST National Institute of Standards and Technology NRC Nuclear Reg lt Commission ODCM Offsite Dose Calculation Manual pCi/kg picocurie per kilogram pCi/I picocune per liter pCi/m3 picocurie per cubic meter PIP Problem Investigation Process REMP Radiological Environmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECs Technical Specifications TLD Thermoluminescent Dosimeter ACi/ml microcurie per milliliter UFSAR Updated Final Safety Analysis Report W

Weekly iii

1.0 EXECUTIVE

SUMMARY

This Annual Radiological Environmental Operating Report describes the Catawba Nuclear Station Radiological Environmental Monitoring Program (REMP), and the program results for the calendar year 2003.

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

Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLCs).

Required analyses were performed and detection capabilities were met for all collected samples as required by SLCs. Nine-hundred seventeen samples were analyzed comprising 1,275 test results in order to compile data for the 2003 report. Based on the annual land use census, the current number of sampling sites for Catawba Nuclear Station is sufficient.

Concentrations observed in the environment in 2003 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, drinking water, shoreline sediment, and fish are higher than the activities reported for samples collected prior to the operation of the station. Measured concentrations were not higher than expected, and all positively identified measurements were within limits as specified in SLCs.

Additionally, environmental radiological monitoring data is consistent with effluents introduced into the environment by plant operations. The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data, excluding TLD results, was 1.95E-01 mrem for 2003. It is therefore concluded that station Hi operations has had no significant radiological

'D impact on the health and safety of the public or the environment.

Shoreline Sediment sampling Section I - Page 1

2.0 INTRODUCTION

2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Duke Power Company's Catawba Nuclear Station is a two-unit facility located on the shore of Lake Wylie in York County, South Carolina. Each of the two essentially identical units employs a pressurized water reactor nuclear steam supply system furnished by Westinghouse Electric Corporation. Each generating unit is designed to produce a net electrical output of approximately 1145 MWe. Units 1 and 2 achieved initial criticality on January 7, 1985, and May 8, 1986, respectively.

Condenser cooling is accomplished utilizing a closed system incorporating cooling towers, instead of using lake water directly. Liquid effluents are released into Lake Wylie via the 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 (TID) monitoring locations and the sampling locations. The location numbers shown on these maps correspond to those listed in Tables 2.1-A and 2.1-B. Figure 2.1-1 comprises all sample locations within a one mile radius of CNS. Figure 2.1-2 comprises all sample locations within a 10 mile radius of CNS.

2.2 SCOPE AND REQUIREMENTS OF THE REMP 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 operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.

This monitoring program is based on NRC guidance as reflected in the Selected Licensee Commitments Manual, with regard to sample media, sampling locations, sampling frequency and analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other "man-made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related exposures from 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 Section 2 - Page 1

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

Reporting levels for activity found in environmental samples are listed in Table 2.2-A.

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

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

Participation in an interlaboratory comparison program as required by Selected Licensee 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 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 of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the RENT. The following equation was used to estimate the mean (Reference 6.8):

N XX X=

1=1 N

Where:

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

Xi net activity (or concentration) for sample i.

NOTE: "Net activity (or concentration)" is the activity (or concentration) determined to be present in the sample. No "Minimum Detectable Activity", "Lower Limit of Detection",

"Less Than Level", or negative activities or concentrations are included in the calculation of the mean.

Section 2 -Page 2

2.3.2 LOWER LEVEL OF DETECTION AND MINIMUM DETECTABLE ACTIVITY The Lower Level of Detection (LLD), and Minimum Detectable Activity (MDA) are used throughout the REMP.

LLD - The LLD, as defined in the Selected Licensee Commitments Manual is the smallest concentration of radioactive material in a sample that will yield a net count, above the system background, that will be detected with 95% probability with only 5%

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

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

The "required" LLD's for each sample medium and selected radionuclides are given in the Selected Licensee Commitments and are listed in Table 2.2-C.

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

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

Visual inspection of tabular or graphical presentations of data (including preoperational) is used to determine if a trend exists.

A decrease in a particular radionuclide's concentration in an environmental medium does not indicate that reactor operations are removing radioactivity from the environment but that reactor operations are not adding that radionuclide to the environment in quantities exceeding the preoperational level and that the normal removal processes (radioactive decay, deposition, resuspension, etc.) are influencing the concentration.

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

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

Section 2 - Page 3

1 Figure 2.1-1 Section 2 - Page 4 CO\\

Figure 2.1-2 Section 2 - Page 5

TABLE 2.1-A CATAWBA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 2.1-B Codes l

W Weekly SM Semimonthly BW BiWeekly Q

Quarterly M

Monthl SA Semiannually C

Control Site Location Description*

Alr Rod.&

Surface Drinking Shoreline Food rFsh Milk Broad Ground Part Water Water Sediment Products Lear Water

_ __ __ _(a)

V eg. tb) 200 Site Boundary (0.63 mi NNE)

W M

201 Site Boundary (0.53 ni NE)

W

_=

M 205 Site Boundary (0.23 mi SW)

W 208 Discharge Canal (0.45 nmi S)

M SA SA 209 Dairy (5.96 mi SSW)

SM 210 Ebenezer Access (2.31 mi SE)

SA

_

211 Wylie Dam (4.06 mi ESE)

M 212 Tega Cay (3.32 mi E)

W

=

214 Rock Hill Water Supply (7.30 mni SSE)

M 215 C River Pointe - Hwy 49 (4.21 rni NNE)

M SA 216 C Hwy 49 Bridge (4.19 mi NNE)

SA 217 C Rock Hill Substation (10.3 rni SSE)

W M

218 C Belmont Water Supply (13.5 mi NNE)

M 219 Dairy (5.70 mi SW)

=

SM 221 C Dairy (14.5 mi NW)

SM 222 Site Boundary (0.70 mli N)

M 226 Site Boundary (0.48 mi S)

=

M 252 Residence (0.64 mi SW)

Q_

253 Irrigated Gardens (1.90 mi SSE)

M(a) 254 Residence (0.82 mii N)

I_

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

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

Section 2 - Page 6

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

Site Location*

Distance Sector Site Location*

Distance Sector 200 SITE BOUNDARY 0.63 miles NNE 234 HOME FEDERAL BANK 4.50 miles E

201 SITE BOUNDARY 0.53 miles NE 235 LAKE WYLIE DAM 4.07 miles ESE SC WILDLIFE 203 SITE BOUNDARY 0.38 miles ESE 236 FEDERATION OFFICE 4.25 miles SE TWIN LAKES ROAD AND 204 SITE BOUNDARY 0.48 miles SSW 237 HOMESTEAD ROAD 4.75 miles SSE PENNINGTON ROAD AND 205 SITE BOUNDARY 0.23 miles SW 238 WEST OAK ROAD 4.02 miles S

CARTER LUMBER 206 SITE BOUNDARY 0.67 miles WNW 239 COMPANY 4A9 miles SSW 207 SITE BOUNDARY 0.95 miles NNW 240 PARAHAM ROAD 4.07 miles SW 212 SI TEGA CAY AIR SITE 3.32 miles E

241 CAMPBELL ROAD 4.58 miles WSW TRANSMISSION TOWER 217 C ROCK HILL AIR SITE 10.3 miles SSE 242 ON PARAHAM ROAD 4.56 miles W

222 SITE BOUNDARY 0.69 miles N

243 KINGSBERRY ROAD 4.39 miles WNW BETHEL 223 SITE BOUNDARY 0.57 miles E

244 ELEMENTARY SCHOOL 4.02 miles NW CROWDERS CREEK 225 SITE BOUNDARY 0.68 miles SE 245 BOATLANDING 4.01 miles NNW CAROWINDS 226 SITE BOUNDARY OA8 miles S

246 SI GUARD HOUSE 7.87 miles ENE 227 SITE BOUNDARY 0.52 miles WSW 247 C FORT MILL 7.33 miles ESE PIEDMONT 228 SITE BOUNDARY 0.61 miles W

248 SI MEDICAL CENTER 6.54 miles S

YORK COUNTY 229 SITE BOUNDARY 0.84 miles NW 249 SI OPERATIONS CENTER 7.17 miles S

RIVER HILLS YORK 230 COMMUNITY CHURCH 4.37 miles N

250 SI DUKE POWER OFFICE 10.4 miles WSW RIVER HILLS 231 FRONT ENTRANCE 4.21 miles NNE 251 C CLOVER 9.72 miles WNW 232 PLEASANT HILL ROAD 4.18 miles NE 255 SITE BOUNDARY 0.61 miles ENE ZOAR ROAD AND 233 THOMAS DRIVE 3.95 miles ENE 256 SITE BOUNDARY 0.58 miles SSE C = Control SI = Special Interest

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

Section 2 - Page 7

TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis Water Air Particulates Fish Milk Food Products (pCi/liter) or Gases (pCi/kg-wet)

(pCi/liter)

(pCi/klg-wet)

H-3 20,000"'___

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 l

Zn-65 300 20,000 l

Zr-Nb-95 400 I-131 2

0.9 3

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

1 (a) If no drinking water pathway exists, a value of 30,000 pCilliter may be used.

(b) H-3 Reporting level not applicable to surface water TABLE 2.2-B REMP ANALYSIS FREQUENCY Sample Analysis Gamma Tritium Low Gross TLD Medium Schedule Isotopic Level Beta

-1 I-131 Air Radioiodine Weekly X

Air Particulate Weekly X

X Direct Radiation Quarterly X

Surface Monthly Composite X

Water Quarterly Composite X

______ll Drinking Monthly Composite X

l (a)

X Water Quarterly Composite X

Ground Water Quarterly X

X Shoreline Sediment Semiannually X

Milk Semimonthly X

l X

Fish Semiannually X

Broadleaf Vegetation Monthly""

X Food Products Monthlyo' X

(a) Low-level I-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

TABLE 2.2-C MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION Analysis Water Air Particulates Fish E Milk Food Products Sediment (pCi/liter) or Gases (pCi/kg-wet)

(pCilliter)

(pCi/kg-wet)

(pCi/kg-dry) l_

(pCi/mr3)

-_.l Gross Beta 4

0.01 l

H-3 2000 (a)

Mn-54 15 130 l

l Fe-59 30 260 l

Co-58, 60 15 130 Zn-65 30 260 l

Zr-Nb-95 15 I-131 I(b) 0.07 1

60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) If no drinking water pathway exists, a value of 3000 pCi/liter may be used.

(b) If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

Section 2 - Page 9

3.0 INTERPRETATION OF RESULTS Review of all 2003 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 2003 was compared to preoperational and historical data. Over the years of operation, analysis and collection changes have taken place that do not allow direct comparisons for some data collected from 1984 (preoperational) through 2003.

Summary tables containing 2003 information required by Technical Specification Administrative Control 5.6.2 are located in Appendix B.

Evaluation for significant trends was performed for radionuclides that are listed as required within Selected Licensee Commitments 16.11-13.

The radionuclides include:

H-3, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140 and La-140. Gross beta analysis results were trended for drinking water and gross beta trending for air particulates was initiated in 1996. Other radionuclides detected that are the result of plant operation, but not required for reporting, are trended.

A comparison of annual mean concentrations of effluent-based detected radionuclides to historical results provided trending bases. Frequency of detection and concentrations related to SLC reporting levels (Table 2.2-A) were used as criteria for trending conclusions. All 2003 maximum percentages of reporting levels were well below the 100% action level. The highest value noted during 2003 was 5.25% for tritium in drinking water collected at the Rock Hill Water Supply, Location 214.

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

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 spectroscopy system on September 1, 1987, decreased the number of measurements yielding detectable low-level activity for indicator and control location samples. It was thought that the method used by the previous system was vulnerable to false-positive results.

All 2003 sample analysis results were reviewed to detect and identify any significant trends.

Tables and graphs are used throughout this section to display data from effluent-based radionuclides identified since the system change in late 1987. All negative concentration values were replaced with zero for calculation purposes. Any zero concentrations used in tables or graphs represent activity measurements less than detectable levels.

Review of all 2003 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.

Section 3 - Page 1

3.1 AIRBORNE RADIOIOI)INE AND PARTICULATES In 2003, 260 radioiodine and particulate samples were analyzed, 208 from four indicator locations and 52 at the control location. Particulate samples were analyzed weekly for gamma and gross beta. Radioiodine samples received a weekly gamma analysis.

Figure 3.1 shows individual sample gross beta results for the indicator location with highest annual mean and the control location samples during 2003. The two sample locations' results are similar in concentration and have varied negligibly since preoperational periods.

There were no detectable gamma emitters identified for particulate filters analyzed during 2003. Table 3.1-A shows the highest indicator annual mean and control location annual mean for gross beta in air particulate.

There was no detectable I-131 in air radioiodine samples analyzed in 2003. Table 3.1-B shows the 1 highest indicator annual mean and control location annual mean for I-131 since 1984 (preoperational.

period).

K-40 and Be-7 that occur naturally were routinely detected in charcoal cartridges collected during the year. Cs-137 activity was not detected on any cartridges in 2003. Cs-137 detection on the charcoal cartridge was determined in 1990 to be an active constituent of the charcoal.

A similar study was performed in 2001 again yielding this conclusion. Therefore, any Cs-137 activities were not used in any dose calculations in Section 4.0 of this report.

There is no reporting levelfor gross beta in air particulate Figure 3.1 pcIm3 Concentration of Gross Beta in Air Particulate 1.OOE-01 9.OOE _

8.OOE-02 7.OOE _

6.OOE-02 5.OOE-02 l

4.OOE-02

_X 230OOE 02 A

_>C_

>_S 1.OOE _

O.OOE+00 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 I -

Indicator Location

+

Control Location Section 3 - Page 2

Table 3.1-A Mean Concentration of Gross Beta in Air Particulate Year Indicator Location (pCi/rn2)

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 2.1 1E-2 2.13E-2 1990 2.39E-2 2.72E-2 1991 2.19E-2 2.51E-2 1992 1.90E-2 2.01E-2 1993 1.87E-2 1.94E-2 1994 2.03E-2 2.03E-2 1995 4.88E-2 3.23E-2 1996 3.49E-2 2.60E-2 1997 2.83E-2 2.28E-2 1998 2.69E-2 2.12E-2 1999 2.53E-2 2.04E-2 2000 2.28E-2 1.86E-2 2001 1.76E-2 1.78E-2 2002 1.60E-2 1.57E-2 Average(1993 -2002)

-2.60E-2 2.15E-2 2003 1.54E-2 1.42E-2 Table 3.1-B Mean Concentration of Air Radioiodine (1-131)

Year Indicator Location (pCi/m3)

Control Location (pCi/rm3) 1984 1.30E-3 1A6E-2 1985 4.75E-3 2.38E-2 1986 1A33E-2 1.02E-2 1987 1.38E-2 O.OOEO 1988 0.00E0 O.OOEO 1989 O.OOEO O.OOEO0 1990 0.OOEO 0.00E0 1991 0.00E0 O.OOEO 1992 O.OOEO 0.00E0 1993 0.00E0 0.00E0 1994 0.00E0 0.00E0 1995 0.00E0 0.OOEO 1996 0.001E0 0.001E0 1997 0.00E0 0.00E0 1998 0.00E0 O.OOEO 1999 0.00E0 0.OOEO 2000 0.00E0 O.OOEO 2001 0.00E0 O.OOEO 2002 O.OOEO 0.OOEO 2003

-- O.OOEO-O.OOEO O.OOEO = no detectable measurements Section 3 - Page 3

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

Tritium was detected at low levels in the four indicator samples and three of the four control samples during 2003. The mean indicator tritium concentration for 2003 was 636 pCiA, 3.18% of reporting level. The mean control tritium concentration for 2003 was 288 pCi/l, 1.44% of reporting level. Figure 3.2 and Table 3.2 display the highest indicator and control location annual mean concentrations for tritium since 1984.

The dose for consumption of water was less than one mrem per year, historically and for 2003; therefore low-level iodine analysis is not required.

Table 3.2 shows highest annual mean gross beta concentrations for the indicator location and control location since preoperation. The indicator location (downstream of the plant effluent release point) average concentration was 2.27 pCi/l in 2003 and the control location concentration was 2.02 pCi/l. The 2002 indicator mean was 3.44 pCi/l. The table shows that current gross beta levels are not statistically different from preoperational concentrations.

No gamma emitting radionuclides were identified in 2003 drinking water samples. There have been no gamma emitting radionuclides identified in drinking water samples since 1988.

The region experienced a severe drought over a four year period (1999 to 2002). Rainfall in the area was substantially below normal (approximately 40 inches below normal) for this four year period.

The reduced rainfall resulted in reduced flow in the Catawba River. The increase in drinking water Tritium up to 2002 is considered to be a result of the decreased river flow.

Section 3 - Page 4

Figure 3.2 Table 3.2 Mean Concentration of Radionuclides in Drinkin2 Water Gross Beta (pCi/l)

Tritium (pCi/l)

YEAR Indicator Control Indicator Control Location Location Location Location 1984 4.72 1.83 3.10E-2 3.10E-2 1985 2.70 2.24 4.13E2 4.00E2 1986 3.11 2.26 7.23E2 7.33E2 1987 3.10 2.40 7.80E2 4.80E2 1988 3.60 2.60 6.64E2 0.OOE0 1989 3.60 2.90 8.91E2 5.72E2 1990 4.50 3.20 7.03E2 O.OOEO 1991 3.70 2.20 7.04E2 O.OOEO 1992 3.20 2.40 7.65E2 5.38E2 1993 3.50 2.50 7.06E2 O.OOE0 1994 3.30 2.70 0.OOE0 O.OOE0 1995 4.80 4.50 4.28E2 2.21E2 1996 3.08 3.14 3.71E2 3.27E2 1997 3.74 3.15 3.54E2 2.28E2 1998 2.51 2.44 5.07E2 1.83E2 1999 3.55 2.48 6.71E2 2.70E2 2000 3.04 2.27 5.87E2 3.26E2 2001 3.49 2.30 8.66E2 4.50E2 2002 3.44 2.36 1.22E3 4.11E2 2003 2.27 2.02 6.36E2 2.88E2 O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 5 COL7L

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

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

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

Tritium was the only radionuclide identified in surface water samples collected during 2003.

All indicator location samples contained tritium with an average concentration of 6897 pCi/l.

Indicator Location 208 (Discharge Canal) showed a range of activities from 8260 to 19500 pCi/l which had the highest mean concentration of 13140 pCi/l. Tritium was detected in two of the four control samples during 2003 with an average concentration of 237 pCi/I.

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

Tritium in surface water in 2003 was higher than usual due to the one-time draining of approximately 40,000 gallons of water on 9/8 and 9/9/03 from the Recycle Holdup Tanks following the Unit 1 outage. The Recycle Holdup Tanks contain evaporator distillate water containing tritium. Other surface water samples during the year were normal and did not indicate a trend. The release of the Recycle Holdup Tanks is documented in PIP C-03-5726.

Figure 3.3 pCilniter Concentration of Tritium in Surface Water 16000 -

14000 12000 10000 8000 2000 4000 1990 1992 1994 1996

_199 2000 2002 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002

-Ul Indicator Location

+

Control Location There is no reporting level for tritium in surface water Section 3 -Page 6 CD5 I',, -

-,,,,, -,........I_

Table 3.3 Mean Concentrations of Radionuclides in Surface Water (PCi/O)

YEAR Co-58 Co - Nb-95 Cs-137 H-3 Indicator H-3 Control 1984 4.591E-1 5.71E-1 6.48E-1 9.08E-1 3.35E2 3.18E2 1985 3.46E0 4.83E-2 2.70E0 8.19E-1 1.19E3 5.05E2 1986 3.lOE-1

-4.12E-2 2.05E0 4.85E-1 2.341E3 5.05E2 1987 O.OOEO 3.10EO 4.30E0 9.90E0 4.17E3 6.20E2 1988 9.20E0 O.OOEO O.OOEO O.OOEO 6.03E3 6.07E2 1989 O.OOE0 O.OOE0 0.OOE0 O.OOEO 5.27E3 O.OOEO 1990 6.50E0 0.OOE0 O.OOEO O.OOEO 3.98E3 7.73E2 1991 O.OOEO 0.OOE0 0.OOE0 O.OOEO 4.87E3 O.OOEO 1992 O.OOEO O.OOEO 0.OOE0 O.OOEO 6.91E3 6.64E2 1993 4.70E0 1.80E0 0.00E0 0.00E0 5.98E3 O.OOEO 1994 0.OOE0 0.00E0 O.OOE0 O.OOEO 8.42E3 O.OOE0 1995 0.OOE0 O.OOEO O.OOEO O.OOEO 5.13E3 2.89E2 1996 O.OOEO O.OOE0 O.OOE0 O.OOE 7.36E3 2.61E2 1997 0.00OE0 O.OOEO O.OOE0 O.OOE0 7.77E3 2.20E2 1998 O.OOE0 O.OOEO O.OOEO O.OOE0 6.61E3 O.OOE0 1999 O.OOE0 0.OOE0 O.OOEO O.OOEO 8.13E3 2.41E2 2000 O.OOE0 O.OOEO O.OOEO O.OOEO 7.19E3 2.56E2 2001 O.OOEO O.OOEO 0.00E0 O.OOEO 7.13E3 3.28E2 2002 O.OOE0 O.OOEO O.OOE0 0.00E0 1.00E4 3.80E2 2003 O.OOEO 0.00E0 -:

O.OOEO O.OOE0 1.31E4 2.37E2 O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 7

3.4 GROUND WATER A total of eight ground water samples was collected and analyzed for gamma emitters. There are two indicator locations and no control locations. Naturally occurring K-40 was the only radionuclide identified during 2003.

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

Section 3 - Page 8

3.5 MILK A total of 72 milk samples was analyzed by gamma spectroscopy and low level iodine during 2003. There were two indicator locations and one control location sampled. Two indicator dairies ceased operation in December, 2003 leaving the one control location. No indicator replacement dairies were available.

There were no gamma emitting radionuclides identified in milk during 2003.

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. During 1995 there was also one sample analyzed in which Cs-137 was identified with a concentration of 8.6 pCi/l. 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 K40 and Be-7, reported in milk samples since 1988.

Table 3.5 Mean Concentration of Radionuclides in Milk YEAR

-Cs-137 Indicator (PCi/):

Cs-137 Control (pCi/I) 1984 2.95E0 2.98EO 1985 2.1 1EO 2.12EO 1986 3.76EO 4.54EO 1987 5.OOEO 5.50EO 1988 3.20E0 3.80EO 1989 O.OOEO O.OOEO 1990 8.OOEO 6.70EO 1991 0.OOEO O.OOEO 1992 3.40E0 5.OOEO 1993 5.00EO O.OOEO 1994 2.80EO O.OOEO 1995 8.60EO O.OOEO 1996 6.05EO O.OOEO 1997 O.OOEO O.OOEO 1998 O.OOEO O.OOEO 1999 O.OOEO O.OOEO 2000 O.OOEO O.OOEO 2001 O.OOEO O.OOEO 2002 O.OOEO O.OOEO 2003 O.OOEO O.OOEO O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 9

3.6 BROADLEAF VEGETATION Gamma spectroscopy was performed on 40 broadleaf vegetation samples during 2003.

Four indicator locations and one control location were sampled.

Three of the thirty-two samples collected at indicator locations contained detectable Cs-137 activity. Cs-137 was detected in two of the eight samples collected at Location 226. The highest concentration detected at Location 226 was 54.1 pCi/kg which is 2.71%

of the reporting level. Cs-137 was detected in one of the eight control location samples.

Figure 3.6 shows indicator and control annual means for Cs-137 in vegetation since 1984. Table 3.6 lists indicator and annual means. Values shown from 1984 to 2003 show a stable trend for Cs-137 in vegetation.

No airborne Cs-137 has been released from the plant since 1992.

Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low and highly variable levels.

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

Figure 3.6 pCIkg Concentration of Cs-137 in Broadleaf Vegetation 1200 1000 800 600 400 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 l

Indicator Location

+--

Control Location 50% Reporting Level Section 3 - Page 10

Table 3.6 Mean Concentration of Radionuclides in Broadleaf Vegetation

-YEAR Cs-137 Indicator(pCi/kg)

Cs-137 Control (pCi/kg) 1984 3.76E1 1.30E1 1985 5.48E1 4.16E1 1986 7.42E1 2.22E1 1987 6.10E1 5.10E1 1988 9.1OE1 7AOE1 1989 L.OOE2 4.80E1 1990 7.70E1 5.80E1 1991 1.98E2 8.60E1 1992 9.70E1 O.OOEO 1993 1.13E2 3.20E1 1994 7.001E O.OOEO 1995 3.60E1 O.OOEO 1996 2.23E2 6.22E1 1997 7.57E1 O.OOEO 1998 6.53E1 O.OOEO 1999 1.08E2 O.OOEO 2000 1.04E2 O.OOEO 2001 3.76E1 O.OOEO 2002 7.02E1 O.OOEO 2003

-A4.96E1 2.40E1 O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 11

3.7 FOOD PRODUCTS Collection of food product samples (crops) from an irrigated garden began in 1989. The Li garden is located on Lake Wylie downstream from CNS, Location 253. During the 2003 growing season, six samples were collected and analyzed for gamma radionuclides.

There is no control location for this media type.

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

i_>

Table 3.7 Mean Concentration of Radionuclides in Food Products YEAR Cs-137 Indicator (pCi/kg) 1989 O.OOE0 Li 1990 O.OOEO 1991 O.OOEO 1992 O.OOE0 Li 1993 2.50E1 Li 1994 O.OOEO 1995 O.OOE0 1996 O.OOE0 1997 O.OOE0 1998 O.OOE0 Li 1999 O.OOEO Li 2000 O.OOEO 2001 O.OOEO 2002 O.OOE0 Li 2003 O.OOE0 O.OOEO = no detectable measurements Section 3 - Page 12

3.8 FISH Gamma spectroscopy was performed on 12 fish samples collected during 2003. One downstream indicator location and one control location were sampled.

Co-58, Co-60, and Cs-137 were the predominant radionuclides identified in fish samples.

One of the six indicator location samples contained Co-58. One of the six indicator location samples contained Co-60. One of the six indicator location samples contained Cs-137. Co-58, Co-60, and Cs-137 were not detected in any control location samples.

The highest average concentration for Co-58 in indicator location samples was 143 pCifkg which represents 0.48% of the reporting level. The highest average concentration for Co-60 in indicator location samples was 26.1 pCi/kg which represents 0.26% of the reporting level.

The highest average concentration for Cs-137 in indicator location samples was 11.9 pCi/kg which represents 0.60% of the reporting level.

Sample results for fish collected at indicator Location 208 were reviewed by type of fish.

Results show that all radionuclide detection frequencies and concentrations are slightly higher for forager fish than for predator and bottom feeding fish. Similar results have been noted from 1990 through 2002.

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

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

significant trend -or accumulation.

K-40 was observed in fish samples collected during 2003.

Section 3 - Page 13

Figure 3.8-1 PCI/kg Concentration of Co-58 in Fish 2000 -

1600 1400 800_

200 L.0 1.'X 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002

-U*-

Indicator Location

-- *Control Location

~

5 % Reporting Level Figure 3.8-2 pCIkg Concentration of Co-60 in Fish 700 600-400__

300 200

__A 100 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 Indicator Location Control Location 5% Reporting Level Section 3 - Page 14 C OX

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

Year Mn-54 Co-58 Co-60

---Cs-134 Cs-137 Nb-95 Fe-59 Sb-122 Sb-125 1984 3.07E0 3.OOEO 6.1lE-1

-5.32E0 1.83EO O.OOEO O.OOEO O.OOEO O.OOEO 1985 7.68E-1 3.40E1 9.1 IEO 3.22E0 1.28E1 5.07EO O.OOEO O.OOEO O.OOEO 1986 2.01E1 1.86E2 4.01E1 3.51E1 9.29E1 O.OOEO 7.30EO O.OOEO O.OOEO 1987 7.24E1 7.57E1 4.81E1 3.83E0 4.27E1 5.40EO O.0020 0.OOEO O.OOEO 1988 2.85E1 1.40E2 9.70E1 1.67E1 8.24E1 O.OOEO O.OOEO O.OOEO O.OOEO 1989 8.28E0 1.33E2 3.83E1 1.47E1 4.37E1 8.58E-1 O.OOEO O.OOEO O.OOEO 1990 2.51E1 1.75E2 7.77E1 1.32E1 4.66E1 3.33EO O.OOEO 7.00E0 9.25EO 1991 3.15E1 1.46E2 1.29E2 1.03E1 4.60E1 7.90E-1 2.30EO O.OOEO 7.45EO 1992 1.34E1 9.02E1 6.20E1 1.27E1 4.61E1 O.OOEO O.OOEO O.OOEO O.OOEO 1993 2.14E1 3.58E2 1.21E2 2.73E0 2.56E1 O.OOEO O.OOEO O.OOEO O.OOEO 1994 1.91E0 4.75E1 1.81E1 O.OOEO 1.75E1 O.OOEO O.OOEO O.OOEO 1.45E1 1995 5.65E1 8.90E2 2.66E2 O.OOEO 6.77E1 1.38E1 O.OOEO O.OOEO O.OOEO 1996 0.0020 5.95E1 6.68EI 0.0020 3.02E1 0.00E0 0.OOEO 0.00E0 0.00E0 1997 O.OOEO 4.93E1 9.88EO O.OOEO 2.74E1 O.OOEO O.OOEO O.OOEO O.OOEO 1998 0.OOEO 6.44_1 2.86E_

0.0020 1.58E1 0.0020 0.0020 0.OOEO 0.00E0 1999 O.OOEO 3.12E1 2.71E1 O.OOEO 1.87E1 O.OOEO O.OOEO O.OOEO O.OOEO 2000 O.OOEO 2.13E2 2.69E2 O.OOEO 1.52E1 O.OOEO O.OOEO O.OOEO O.OOEO 2001 O.OOEO 4.66E1 O.OOEO O.OOEO 2.08E1 O.OOEO O.OOEO O.OOEO O.OOEO 2002 O.OOEO 5.23E1 7.00E1 O.OOEO 1.73E1 O.OOEO O.OOEO O.OOEO O.OOEO 2003 O.OOEO 1.43E2 2.61E1=

O.OOEO-1.19E1 O.OOEO O.OOEO O.OOEO OOOEO' O.OOEO = no detectable measurements Section 3 - Page 15

3.9 SHORELINE SEDIMENT During 2003, a total of 6 shoreline sediment samples was analyzed, four from two indicator locations and two from the control location.

Mn-54, Co-58, Co-60, and Cs-137 were identified in samples collected from indicator location 208-1S, which is closest to the plant's liquid effluent release point. Naturally occurring K-40 was identified in many of the indicator and control locations. Activity released in plant effluents has decreased since 1996 and as a result decreased activity has been measured in the environment.

The shoreline sediment location with the highest annual mean for all detectable radionuclides was location 208-iS. Cs-137 was identified at location 208-1S with an annual mean concentration of 26.9 pCi/kg. Other radionuclides identified during 2003 at shoreline sediment location 208-IS included Mn-54 with an annual mean of 21.7 pCi/kg, Co-58 with an annual mean of 87.5 pCi/kg, and Co-60 with an annual mean of 108 pCi/kg. Naturally occurring K-40 and Be-7 were also identified in samples from this location.

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

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

Figure 3.9-1 pC/kg Concentration of Co-58 in Shoreline Sediment 2000 1800 1600 1400

=

1200 1000 400 600 200 0

-r-1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 lU-Indicator Location

+

Control Location I There is no reporting level for Co-58 in Shoreline Sediment Section 3 - Page 16 Cot

Figure 3.9-2 pCVkg Concentration of Co-60 in Shoreline Sediment 2000 1800 1600

==

1400 1200 1000 800 600 7

7

_7 400 200 1984 1986 1988 1990 1992 1994 1996 1998 2000 2002 1

4 Il Indicator Location

+

Control Location There is no reporting levelfor Co-60 in Shoreline Sediment Table 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment (DC0k2)

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 O.OOEO O.OOEO 3.19E1 1.07E2 O.OOEO O.OOEO 1985

-3.12E0 1.16E2 5.18E0 O.OOEO O.OOEO 2.11E2 2.97E2 O.OOEO O.OOEO 1986 1.09E2 3.79E2 2.05E2 O.OOEO 3.96E1 6.50E1 1.61E2 O.OOE0 O.OOEO 1987 8.83E1 4.08E2 1.61E2 4.22E1 O.OOEO 6.08E1 1.26E2 O.OOEO O.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 O.OOEO 1.65E1 5.77E1 O.OOEO 1.57E1 1990 5.39E1 2.08E2 1.77E2 O.OOEO O.OOEO 1.66E1 8.18E1 O.OOEO 7.15E0 1991 8.50E1 3.70E2 4.19E2 5.30E0 O.OOEO 1.82E1 8.33E1 1.20E0 1.50E1 1992 1.17E2 1.13E3 5.80E2 3.50E0 O.OOEO 1.69E1 1.07E2 3.OOEO 2.70E1 1993 1.33E2 1.07E3 1.04E3 O.OOEO O.OOEO 2.80E1 1.26E2 2.47E1 2.16E2 1994 4.93E1 7.98E2 5.73E2 O.OOEO O.OOEO 5.67E0 1.07E2 4.38E0 4.60E1 1995 1.02E2 1.33E3 8.65E2 1.13E2 O.OOEO O.OOEO 8.50E1 3.69E1 1.49E2 1996 8.73E1 3.39E2 5.81E2 O.OOEO O.OOEO O.OOEO 8.30E1 O.OOEO 1.96E2 1997 6.96E1 5.90E2 7.64E2 O.OOEO O.OOEO O.OOEO 1.43E2 O.OOEO 1.76E2 1998 3.07E1 1.88E2 2.30E2 O.OOEO O.OOEO O.OOEO 7.L1E1 O.OOEO O.OOEO 1999 7.28E1 2.29E2 4.39E2 O.OOEO O.OOEO O.OOEO 9.42E1 O.OOEO 1.40E2 2000 O.OOEO 3.90E1 1.03E2 O.OOEO O.OOEO O.OOEO 4.96E1 O.OOEO O.OOEO 2001 3.86E1 8.27E1 3.29E2 O.OOE0 O.OOEO O.OOEO 5.58E1 O.OOEO O.OOEO 2002 3.51E1 2.41E2 2.22E2 O.OOEO O.OOEO O.OOEO 8.83E1 O.OOEO O.OOEO 2003 2.17E1 8.75E1 1.08E2 O.OOEO O.OOEO O.OOEO 2.69E1 O.OOEO O.OOEO O.OOEO = no detectable measurements 1984 - 1986 mean based on all net activity Negative values are calculated as zeroes Section 3 - Page 17

3.10 DIRECT GAMMA RADIATION In 2003, 160 TLDs were analyzed, 148 at indicator locations and 12 at control locations.

TLDs are collected and analyzed quarterly. The highest annual mean exposure for an indicator location was 100 milliroentgen.

The annual mean exposure for the control locations was 56.0 milliroentgen.

Figure 3.10 and Table 3.10 show TLD inner ring (site boundary), outer ring (4-5 miles),

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

The calculated total body dose (from gaseous effluents) for 2003 was 1.01 mrem, which is 1.24% of the average inner ring TLD values. Therefore, it can be concluded that discharges from the plant had very little impact upon the measured TLD values.

Figure 3.10 mRfyear Direct Gamma Radiation (TLD) Results 250__

200 150 100 m

A 0--

1984 1986 1988 1990 1992 1994 1996 1998 2000 2002

-a-Inner Ring O-Outer Ring

+

Control

-4 There is no reporting level for Direct Radiation (TLD)

Section 3 - Page 18

Table 3.10 Direct Gamma Radiation (TLD) Results Inner Ring Average Outer Ring Average Control Average Year (mRlyr) --

(niR/yr)

(mR/yr) 1984*

87.5 82.6 79.3 1985 116.9 108.7 108.9 1986 104.3 98.5 94.4 1987 97.0 87.4 84.7 1988 74.6 70.3 67.1 1989 67.1 60.8 60.0 1990 52.0 44.5 39.1 1991 62.0 54.1 46.7 1992 80.4 72.5 64.5 1993 70.3 60.9 53.6 1994 76.3 69.3 63.9 1995 99.6 89.7 80.8 1996 84.3 73.9 63.6 1997 82.4 71.9 57.4 1998 85.3 74.2 64.6 1999 80.0 68.1 57.8 2000 75.0 63.0 52.4 2001 81.0 70.5 55.2 2002 78.8 69.5 55.2 Average (1993-2002) 81.3 71.1 60.5 2003 81.7 72.6 56.0

• Preoperational Data Section 3 - Page 19

3.11 LAND USE CENSUS The 2003 Annual Land Use Census was conducted July 7 - July 10, 2003 and August 19, 2003 as required by SLC 16.11-14.

Table 3.11 summarizes census results. A map indicating identified locations is shown in Figure 3.11.

During the 2003 census, no new or closer irrigated gardens were identified. The nearest residence is located in the NE sector at 0.56 miles. No program changes were required as a result of the 2003 land use census.

Table 3.11 Catawba 2003 Land Use Census Results Sector Distance Sector Distance (Miles)

(Miles)

Nearest Residence 0.63 Nearest Residence 0.63 N

Nearest Garden 0.93 S

Nearest Garden (Irrigated) 1.26 Nearest Milk Animal Nearest Milk Animal Nearest Meat Animal Nearest Meat Animal (Cow) 4.11 Nearest Residence 0.66 Nearest Residence 0.78 NNE Nearest Garden 2.53 ssw Nearest Garden (Irrigated) 0.96 Nearest Milk Animal Nearest Milk Animal Nearest Meat Animal Nearest Meat Animal (Cow) 3.31 Nearest Residence 0.56 Nearest Residence 0.66 NE Nearest Garden 0.65 Sw Nearest Garden 2.32 Nearest Milk Animal Nearest Milk Animal Nearest Meat Animal Nearest Meat Animal (Cow) 3.86 Nearest Residence 0.61 Nearest Residence 0.78 ENE Nearest Garden (Irrigated) 0.61 Wsw Nearest Garden 2.04 Nearest Milk Animal Nearest Milk Animal Nearest Meat Animal (Cow) 4.54 Nearest Meat Animal (Cow) 2.87 Nearest Residence 0.65 Nearest Residence 0.97 E

Nearest Garden 0.84 w

Nearest Garden 0.96 Nearest Milk Animal Nearest Milk Animal Nearest Meat Animal (Cow) 4.35 Nearest Meat Animal Nearest Residence 0.84 Nearest Residence 1.10 ESE Nearest Garden 1.23 W

Nearest Garden 1.19 Nearest Milk Animal N

Nearest Milk Animal Nearest Meat Animal Nearest Meat Animal Nearest Residence 0.97 Nearest Residence 1.39 SE Nearest Garden 1.70 NW Nearest Garden 1.54 Nearest Milk Animal Nearest Milk Animal Nearest Meat Animal (Cow) 4.20 Nearest Meat Animal (Cow) 1.39 Nearest Residence 0.74 Nearest Residence 1.06 SSE Nearest Garden 1.69 NNW Nearest Garden 2.64 Nearest Milk Animal Nearest Milk Animal Nearest Meat Animal Nearest Meat Animal

"-" indicates no occurrences within the 5 mile radius Section 3 - Page 20

Figure 3.11

'U Catawba Nuclear Station 2003 Land Use Census Map Legend Q

MeatAnimal (Cow)

A Irrigated Garden Ai Non-irrigated Garden Residence

/

- PLblic Road

/ij Railroad a,\\,.' State Boundary Water 2003 data in red Approxmate Ication of dtures shown t+

0 0.5 1

2, l

=_MMIIVe Piojedion NCSP NAD27 July 2003 a

Section 3 - Page 21 C})

4.0 EVALUATION OF DOSE 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 2003 CNS REMP samples. The primary purpose of estimating 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, averaged 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 radionuclide and organ, a dose factor of zero was assumed.

Maximum dose estimates (Highest Annual Mean Concentration) based on drinking water, broadleaf vegetation, fish, and shoreline sediment sample results are reported in Table 4.1-A. The individual critical population and pathway dose calculations are reported in Table 4.1-B.

REMP-based dose estimates are not reported for airborne radioiodine, airborne particulate, milk, or ground water sample types because no radionuclides other than naturally occurring K40 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. Exposure estimates based upon REMP TLD results are discussed in Section 3.10.

The maximum environmental organ dose estimate for any single sample type (other than direct radiation from gaseous effluents) collected during 2003 was 2.18E-1 mrem to the maximum exposed child bone from consuming broadleaf vegetation.

4.2 ESTIMATED DOSE FROM RELEASES Throughout the year, dose estimates were calculated based on actual 2003 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. The 2003 CNS Annual Radioactive Effluent Release Report (Reference 6.6) included calendar year dose estimates for the location with the highest individual organ dose from liquid and gaseous effluent releases. These reported doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimates.

Section 4 - Page I

The effluent-based liquid release doses are summations of the dose contributions from the drinking water, fish, and shoreline pathways. The effluent-based gaseous release doses report noble gas exposure separately from iodine, particulate, and tritium exposure.

For noble gas exposure there is no critical age group; as the maximum exposed individuals are assumed to receive the same doses, regardless of their age group.

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

4.3 COMPARISON OF DOSES The gaseous environmental and effluent dose estimates given in Table 4.1-A agree reasonably well. The calculated environmental doses for liquid pathways are slightly higher than liquid effluent doses. Effluent models are based on historical averages.

The region experienced a severe drought from 1999 to 2002 which has resulted in differences in the actual river flow versus the historical values used in the model.

Drought conditions lessened during 2003.

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

Doses calculated from environmental data are conservative because they are based on a mean that includes only samples with a net positive activity versus a mean that includes all sample results (i.e. zero results are not included in the mean). Also, airborne tritium is not measured in environmental samples but is used to calculate effluent doses.

In calculations based on liquid release pathways, fish, drinking water, and shoreline sediment were the predominant dose pathways based on environmental and effluent data. The maximum total organ dose based on 2003 environmental sample results was 1.20E-1 mrem to the adult GI-LLI. The maximum total organ dose of 1.14E-1 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 l.0lE0 mrem to the child's liver, total body, thyroid, kidney, lung, and GI-LLI. Vegetation was the predominant dose pathway for environmental samples. The maximum total organ dose for gaseous environmental estimates was 2.18E-1 mrem to the child bone.

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

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

Section 4 -Page 2

TABLE 4.1-A Page 1 of 3 CATAWBA NUCLEAR STATION 2003 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIQUID RELEASE PATHWAY Organ Environmental or Critical Critical Location Maximum Dose (3)

Effluent Data Age (1)

Pathway (2)

(mrem)

Skin Environmental Teen Shoreline Sediment 208 (0.45 mi. S) 1.69E-03 Skin Effluent Teen Shoreline Sediment 0.5 mi. S 1.30E-02 Bone Environmental Child Fish 208 (0.45 mi. S) 2.68E-02 Bone Effluent Teen Fish 0.5 mi. S 2.47E-02 Liver Environmental Adult Fish 208 (0.45 mi. S) 8.30E-02 Liver Effluent Child Drinking Water 0.5 mi. S 1.12E-01 T. Body Environmental Adult Fish 208 (0.45 mi. S) 7.81E-02 T. Body Effluent Adult Drinking Water 0.5 mi. S 9.93E-02 Thyroid Environmental Child Drinking Water 214 (7.30 mi. SSE) 5.23E-02 Thyroid Effluent Child Drinking Water 0.5 mi. S 9.44E-02

/

Kidney Environmental Adult Fish 208 (0.45 mi. S) 6.16E-02

/Kidney Effluent Child Drinking Water 0.5 mi. S 9.98E-02 Lung Environmental Adult Fish 208 (0.45 mi. S) 5.54E-02 Lung Effluent Child Drinking Water 0.5 mi. S 9.63E-02 GI-LLI Environmental Adult Fish 208 (0.45 mi. S) 1.20E-01 GI-LLI Effluent Adult Fish 0.5 mi. S 1.14E-01 (1) Critical Age is the highest total dose (all pathways) to an age group.

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

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

Section 4 - Page 3

Page 2 of 3 GASEOUS RELEASE PATHWAY IODINE, PARTICULATE, and TRITIUM Organ Environmental or Effluent Data Critical Age (1)

Critical Pathway (2)

Location Maximum Dose (3 (mrem)

F Skin Skin Environmental Effluent O.OOE+00 O.OOE+00 Bone Bone Liver Liver Environmental Effluent Environmental Effluent Child Child Child Vegetation Vegetation Vegetation 226 (0.48 mi. S) 226 (0.48 mi. S) 0.5 mi. N 2.18E-01 0.OOE+00 2.08E-01 1.01E+00 T. Body T.Body Thyroid Thyroid Kidney Kidney Lung Lung GI-LLI GI-LLI Environmental Effluent Environmental Effluent Environmental Effluent Environmental Effluent Environmental Effluent Adult Child Child Child Child Child Child Adult Child Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation 226 (0.48 mi. S) 0.5 mi. N 0.5 mi. N 226 (0.48 mi. S) 0.5 mi. N 226 (0.48 mi. S) 0.5 mi. N 226 (0.48 mi. S) 0.5 mi. N 1.17E-01 1.01E+00 0.OOE+00 1.01E+00 6.79E-02 1.01E+00 2.44E-02 1.01E+00 3.46E-03 1.01E+00 (1) Critical Age is the highest total dose (all pathways) to an age group.

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

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

Section 4 - Page 4

-j

-j

-j

-j

-j k-

L

L-/

L-)

L-)

Li Li Page 3 of 3 NOBLE GAS Air Environmental or Critical Critical Maximum Dose Dose Effluent Data Age Pathway Location (mrad)

Beta Environmental Not Sampled Beta Effluent N/A Noble Gas 0.5 mi. NNE 1.60E-02 Gamma Environmental Not Sampled Gamma Effluent N/A Noble Gas 0.5 mi. NNE 2.15E-02

-j k--)

k---)

-j

-j k--j k-j

I-j

-j Li

-j k-/

-j L-./

L-/

-j L-./

L-I/

L-./

L-I/

-j

-j Li Section 4 - Page S

c C C C C C C C C I C C C C C C C C C C C C C C C C C C

( C C C C C C C C C C C C C C TABLE 4.1-B Maxinmwn individual Dosefor 2003 based onl Environniental Measiurenients (mrenz)for Catawba Nuclear Station Age Sample Medium Bone Liver T. Body Thyroid Kidney Lung GI-LLI Skin Infant Airborne Drinking Water Milk TOTAL Child Airborne Drinking Water Milk Broadleaf Vegetation Teen Fish Shoreline Sediment TOTAL Airborne Drinking Water Milk Broadleaf Vegetation Fish O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.001E+00 0.001E+00 0.00E+00 O.OOE+00 O.OOE+00 3.54E-02 3.54E-02 3.54E-02 3.54E-02 3.54E-02 3.54E-02 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 3.54E-02 3.54E-02 3.54E-02 3.54E-02 3.54E-02 3.54E-02 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 3.60E-02 3.60E-02 3.60E-02 3.60E-02 3.60E-02 3.60E-02 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 2.68E-02 4.47E-02 2.83E-02 1.63E-02 2.46E-02 1.93E-02 3.21E-02 O.OOE+00 0.00E+00 O.OOE+00 3.01E-04 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 3.54E-04 2.68E-02 8.07E-02 6.46E-02 5.23E-02 6.06E-02 5.53E-02 6.81E-02 3.54E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 1.88E-02 1.88E-02 1.88E-02 1.88E-02 1.88E-02 1.88E-02 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.001E+00 0.00E+00 O.OOE+00 0.001E+00 0.001E+00 2.13E-02 5.15E-02 3.73E-02 1.97E-02 2.93E-02 2.34E-02 6.60E-02 0.00E+00 O.OOE+00 O.OOE+00 1.44E-03 O.OOE+00 O.OOE+00 O.OE+00 0.00E+00 1.69E-03 2.13E-02 7.03E-02 5.75E-02 3.85E-02 4.81E-02 4.22E-02 8.48E-02 1.69E-03 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.67E-02 2.67E-02 2.67E-02 2.67E-02 2.67E-02 2.67E-02 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.99E-02 5.63E-02 5.11E-02 2.56E-02 3.49E-02 2.87E-02 9.35E-02 O.OOE+00 O.OOE+00 O.OOE+00 2.58E-04 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 3.03E-04 1.99E-02 8.30E-02 7.81E-02 5.23E-02 6.16E-02 5.54E-02 1.20E-01 3.03E-04 Shoreline Sediment TOTAL Adult Airborne Drinking Water Milk Broadleaf Vegetation Fish Shoreline Sediment TOTAL Note: Dose tables are provided for sample media displaying positive nuclide occurrence.

Section 4 - Page 6

(CCCCLCCCCCCCCCCCCCCcccccrCCcCrICcrrCCC cCC CCC Catawba Nuclear Station Dosefrom Drinking Water Pathwayfor 2003 Data Maximum Exposed Infant Infant Dose from Drinking Water Pathway (mrem) = Usage (1) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/l)

Usage (intake In one year) =

330 1 Ineestion Dose Factor Highest Annual Net Mean Concentration Indicator Water Location (pCiI)

Dose (mrem)

Radionuclide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 BaLa.140 H-3 Bone NO DATA NO DATA 3.08E-0S NO DATA 1.U4E-OS 4.20E-08 2.06E-07 3.59E-05 3.77E-04 5.22E-04 1.71E-04 NO DATA Liver 1.99E-OS 3.60E-06 5.38E-05 1.08E-05 6.31E-OS 1.73E-08 5.02E4O8 4.23E-05 7.03E-04 6.11E04 1.71E-07 3.08E-07 T. Body Thyroid Kidney Lung Gl-LLI 4.51E-06 NO DATA 4.41E46 NO DATA 7.31E-06 898E-06 NO DATA NO DATA NO DATA 8.97E-06 2.12E-05 NO DATA NO DATA 159E-OS 257E-05 2.55E-OS NO DATA NO DATA NO DATA 2.57E-05 2.91E-05 NO DATA 3.06E4-5 NO DATA 5.33E-05 1.OOE-08 NO DATA 1.24E-08 NO DATA 1.46E-O5 3.56E-08 NO DATA S.41E-08 NO DATA 2.50-O05 1.86E-45 1.39E402 4.94E-0 NO DATA 151E-O6 7.10E-05 NO DATA 1.81E-04 7.42E-OS 1.91E46 4.33E-OS NO DATA 1.64E-04 6.64E-05 1.91E-46 8.81W-06 NO DATA 4.06E-08 1.05E-07 4.20E4-5 3108E-07 3.08E-07 3.08E-07 3.08E407 3.08E-07 ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL 214 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 348.00 Bone Liver T. Body Thyroid Kidney Lung C1-LLI O.OOE00 0.00K

.OOE O.OOE400 0.OOE+OO O.OOE+KO 0.00E+OO 0.00E+00 0.00E+O0 0.00KE-C0 0.00E+00 0Q00E+O0 O.OOE+OO O.OOE+-O 0.00E+00 0.00E+00 O.OOE+OO O.OOE+O0 0.OOE+00 0.00E+O0 O.OOE+O 0.00KE+-O O.OOE+0 0.OOE+-00 0.00K-+OO 0.OOE+OO 0.00E+00 0.00E+OO 0.00E+00 0.00E+KO 0.00-E+OO 0.00E+OO 0.00E+00 0.00E-0 0.OOE+0O 0.00-E+O 0.00E+90 O.OOE+0O O.OOE+-O 0.00K-+OO 0.00-E+O O.OOE+00 O.OOE+0O Q.OOE+O O.OOE+-O O.OOE+0O 0.00E+O0 0.00-+OO 0.00KE+OO 0.OOE+OO

.OOE+O0 0.00KE+O 0O.OOO QOOE+OO OOE+0KOO 0O O

O.OOE+Ku 0.00K-OO 0.00E+OO 0.OOE+00 0.00K-+OO O.OOE+OO 0.00E+KO O.OOE+00 0.00E+OO O.OOE+0OO O.OOE+O O.OOE+0OO O.OOE+0O O.OOE+O 0.00E+O 0.00E+-OO O.OOE+00 O.OOE+O 0.00KE+O O.OOE+0O 0.00K+OO 0.00E+OO O.OOE+00 O.OOE+00 3.54E-02 3.54E-02 3.54E-02 3.54E-02 3.54E-02 3.54E-02 Dose Commitment (mrem) =

Section 4 - Page 7 O.OOE+00 3.54E-02 3.54E-02 354E-02 354E-02 354E-02 3.54E-02

cCCCCCCCCCCCCCCCCCCc(CCC CCC(((C(CC(CCCCCCCCCS Catawba Nuclear Station Dose from Drinking Water Pathway for 2003 Data Maximum Exposed Child Child Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCiAi)

Usage (intake In one year)=

510 1 fneestion Dose Factor Hghest Annual Net Mean Concentration Indicator Water Location (pCI/)

Dose (mrem)

Radionuclide Mn-54 CO-58 Fe-59 CO-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs.137 BaLa-140 11-3 Bone NO DATA NO DATA 1.65E-05 NO DATA 1.37E-05 2.25E-08 1.16E-07 1.72E-05 234E-04 3.27E-04 8.31E-05 NO DATA Liver 1.07E-05 1.80E.06 2.67E.05 5.29E-06 3465E-05 8.76E.09 2.55E-08 1.73E-05 3.84E-04 3.13E-04 7.28E.08 2.03E.07 T. Body 2.8SE-06 5.51E.06 1.33E3-05 1.56E-05 2.27E-05 6.26E-09 2.27E-O8 9.83E.06 8.1OE.05 4.62E-05 4.8E-06 2.03E-07 Thyroid Kidney Lung GI.LLI NO DATA 3.00E-06 NO DATA M98E-06 NO DATA NO DATA NO DATA 1.OSE-05 NO DATA NO DATA 7.74E-06 2.78E-05 NO DATA NO DATA NO DATA 2.93E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 NO DATA 8.23E-09 NO DATA 1.62E-05 NO DATA 3.65E-08 NO DATA 2.66E-05 5.72E-03 2.84E-05 NO DATA 1.54E-06 NO DATA 1.19E-04 4.27E-05 2.07E-06 NO DATA 1.02E-04 3.67E-05 1.96E406 NO DATA 2.37E-08 4.34E-08 4.21E-05 2.03E-07 2.03E-07 2.03E-07 2.03E407 ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL 214 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 348.00 Bone 0.00E.O0 0.00E+O0 0.00E+O0 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE1+00 0.00E+00 0.00E+00 Liver 0.00E+O0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00EO00 0.OOE+00 0.00E+00 0.00E+00 3.60E.02 T. Body Thyroid 0.00E+00 0.00E4-00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.001E+00 0.OOE+00 3.60E.02 3.60E.02 Kidney Lung GI-LLI 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.O0E+00 0.O0E+00 0.00E+00 0.001E+00 0.00E+00 0.00E+00 0.00E+00 3.60E-02 0.O0E+O0 0.OOE+00 0.00E+00 0.O0E+00 0.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.60E-02 0.00Ee-00 0.00E+00 0.O0E+00 0.OOE+00 0.O0E+00 0.O0E+00 0.O0E+00 0.OOE+00 0.00E+00 0.00E+00 0.O0E+00 3.60E-02 Dose Commitment (mrem) =

Section 4 - Page 8 0.O0E+00 3.60E.02 3.60E.02 3.60E.02 3.60E-02 3.60E-2 3.60E-02

CCCCCCCCCCCCCCCCCCCCCCCCCC C CCCCCCCjCCCCCCCC Catawba Nuclear Station Dose from Broadleaf Vegetation Pathway for 2003 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 Radlonuclide 1.131 Cs-134 Cs-137 Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Food Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCI/kg)

Bone Liver T. Body Thyroid Kldney Lung GI-LLI 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 234E-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 0.OOE+0 O.OOE+E00 0O.OOE+00 O.OOE+00 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67K-05 1.96E-06 226 25.60 2.18E-01 2.08E-01 3.08E-02 O.OOE+00 6.79E-02 2.44E-02 1.30E-03 Dose Commitment (mrem) =

2.18E-01 2.08E-01 3.08E-02 O.OOE+00 6.79E-02 2.44E-02 1.30E-03 Section 4 - Page 9

CCCCCCCCCCCCCCCCCCCCCCCCCC CCCCCCCCCCCCCCC C

Catawba Nuclear Station Dose from Fish Pathway for 2003 Data Maximum Exposed Child Child Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

H-3 Concentration in Fish = Surface Water pCi/A x Bloaccumulation Factor 0.9 pCi/kg per pCi/l = 12903 pCi/l x 0.9 = 11613 pCi/kg Usage (intake In one year)=

6.9 kg Radionuclide Mn-54 Co-58 Fe-39 CO-60 Zn-65 CS-134 Cs-137 11.3 Bone NO DATA NO DATA 1.65E-05 NO DATA 1.37E-05 2.34E-04 3.27E-04 NO DATA Iniestion Dose Factor Liver T. Body Thyroid Kidney Lung Gl-LLI 1.07E-05 2.85E-06 NO DATA 3.OOE-06 NO DATA &98E-06 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 2.67E-05 1.33E405 NO DATA NO DATA 7.74E.06 2.78E-05 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 3.65E45 2.27E-05 NO DATA 2.30E.05 NO DATA 6.41E-06 3.84E-04 8.OE-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 2.03E-07 2.03E-07 2.03E-07 2.03E.07 2.03E-07 2.03E4-7 Highest Annual Net Mean Concentration Indicator FIsh Location (pC/kg)

ALL 0.00 208 143.00 ALL 0.00 208 26.10 ALL 0.00 ALL 0.00 208 11.90 208 11613.00 Bone Liver T. Body Thyroid Kidney Lung GI-LLI 0.001E+00 0.00E+OO O0.OE+O0 0.00E3+00 0.001E+00 0.00E+00 0.00E+00 0.OOE+00 1.78E-03 5.44E-03 0.OOE3+00 0.OOE+00 0.00E+00 1.04E-02 0.00E+00 0.00E+00 0.001E+00 0.OOE1+00 0.OOE+O0 0.OOE+0O 0.00E+OO 0.OOE+00 9.531E.04 2.81E-03 0.OOE+O0 0.OOE+00 0.O0E+00 S.281E-03 0.00E+00 0.00E+00 0.00E+00 0.001E+00 0.00E+00 0.OOE+00 O.OOEi-00 0.OOE.00 0.OOE+00 0.00E+00 0.001E+00 0.00E+00 O.00E+00 O.00E+O00 2.68E-02 2.57E-02 3.79E.03 0.00E+00 8.38E-03 3.01E.03 1.61E-04 0.O0E+00 1.63E-02 1.63E.02 1.63E-02 1.63E-02 1.63E-02 1.63E-02 Dose Commitment (mrem) -

2.68E-02 4.47E.02 2.83E-2 1.631E-02 2.461E.02 1.93E-02 3.21E.02 Section 4 -Page 10

CCCCCCCCCCCCCC CCCCCCCCCCCCCCCCCCCCCCCCCCCCC Catawba Nuclear Station Dosefrom Shoreline Sediment Pathwayfor 2003 Data Maximum Exposed Child Shoreline Recreation =

14 hr (in one year)

Shore Width Factor =

0.2 Sediment Surface Mass =

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

External Dose Factor Standing on Contaminated Ground Highest Annual Net Mean Concentration Dose (mrem/hr per pCViT?)

Indicator Sediment Radionuclide T. Body Skin Location (pCi/kg)

Mn-54 5.80E-09 6.80E-09 208-IS 21.70 Co-58 7.00E-09 8.20E-09 208-iS 87.50 Co-60 1.70E-08 2.00E-08 208-IS 108.00 Cs.134 1.20E-08 1.40E-08 ALL 0.00 Cs-137 4.20E-09 4.90E-09 208-iS 26.90 Dose Commitment (mrem) =

(mrem)

T. Body Skin 1.41E.05 1.65E-05 6.86E-05 8.04E-05 2.06E-04 2.42E-04 O.OOE+00 O.OOE+00 1.27E.05 lA18E-05 3.01E.04 354E-04 Section 4 -Page I I

CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC Catawba Nuclear Station Dosefrom Drinking Water Pathway for 2003 Data Maximum Exposed Teen Teen Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi Ingested) x Concentration (pCi/l)

Usage (Intake in one year)=

510 1 Ingestion Dose Factor Highest Annual Net Mean Concentration Indicator Water Location (pCIA)

Dose (mrem)

Radionudlde Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 BaLa-140 Bone NO DATA NO DATA 5.87E-06 NO DATA 5.76E-06 822E-09 4.12E-08 5.85E-06 837E-05 1.12E-04 Z84E-05 Liver 5.90E-06 9.72E-07 137E-05 2.81E-06 2.OOE-05 4.56E-09 130E-08 819E-06 1.97E-04 1A9E-04 3.48E-08 T. Body 1.17E-06 2.24E-06 529E-06 633E-06 9.33E-06 2.51E-09 894E-09 4.40E-06 9.14E-05 5.19E-05 1.83E,06 Thyroid Kidney Lung GI-LLI NO DATA 1.76E-06 NO DATA 1.21E-0S NO DATA NO DATA NO DATA 1.34E-05 NO DATA NO DATA 4.32E-O6 3.24E-45 NO DATA NO DATA NO DATA 3.66E-0S NO DATA 1USE-OS NO DATA 847E-06 NO DATA 4.42E-09 NO DATA 1.95E-05 NO DATA 1.91E-08 NO DATA 3.OOE-OS 2.39E-03 1A1E-05 NO DATA 1.62E-06 NO DATA 6.26E-05 2.39E-05 2.45E-06 NO DATA 5.07E-5 1.97E-05 2.12E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL 214 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 348.00 Bone O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Liver O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 1.8SE-02 T. Body 0.00E+00 O.OOE+00 O.OOE+00 Q.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 1.88E-02 Thyrold O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 1.88E-02 Kidney Lung O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 QOOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 1.88E-02 1.88E-02 GI-LLI 0.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 1.88E-02 H-3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 Dose Commitment (mrem)=

Section 4 - Page 12 o.ooE+00 1.88E-02 1.88E-02 1.88E402 1.88E-02 1.88E42 1.88E-02

CC C CCCCCC CC C CCCCC Ccc cCCCrCCCCcCCccccCC Catawba Nuclear Station Dosefrom Broadleaf Vegetation Pathway for 2003 Data Maximum Exposed Teen Teen Dose from Vegetation Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

Usage (intake in one year) =

Radionuclide 1.131 Cs-134 Cs-137 Bone 5.S5E-06 S.37E-05 1.12E-04 42 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Food Liver T. Body Thyroid Kidney Lung GI.LLI Location (pCi/kg)

Bone Liver T. Body Thyroid Kidney Lung Gl-LLI 8.19E-06 4.40E-06 2.39E-03 1.41E405 NO DATA 1.62E-06 ALL 0.00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+OO 0.OOE+00 0.OOE+00 0.00E+00 1.97E404 9.14E-05 NO DATA 6.26E45 2.39E-05 2.45E-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.0OE+00 O.OOE+00 0.OOE+00 0O.OOE+00 1.49E-04 5.19E-05 NO DATA 5.07E4O5 1.97E-05 2.12E-06 226 25.60 1.20E-41 1.60E-01 5.58E-02 O.OOE+00 5.45E-02 2.12E-02 2.28E-03 Dose Commitment (mrem) =

1.20E-41 1.60E-01 5.58E-02 O.OOE+00 5.45E-02 2.12E-02 2.28E-03 Section 4 - Page 13

C C C C C C, C C C C C C C C C C C C C C C C C C C C C C C C C C C C C C C C C C C C C Catawba Nuclear Station Dose from Fish Pathway for 2003 Data Maximum Exposed Teen Teen Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg) 11-3 Concentration in Fish = Surface Water pCi/l x Bioaccumulation Factor 0.9 pCi/kg per pCi/ = 12903 pCI/i x 0.9 = 11613 pCi/kg Usage (intake In one year) =

16 kg Ingestion Dose Factor Radionuclide Mn.54 Co-58 Fe-59 Co-60 Zn-65 Cs.134 Cs-137 11.3 Bone NO DATA NO DATA 5.87E-06 NO DATA 5.76W-6 S37E-05 1.12E-04 NO DATA Liver 5.90E.06 9.72E.07 1.37iFZ-S 2.81E.06 2.OOE.05 1.97E044 1.49E-04 1.0611-07 T. Body Thyroid Kidney Lung GI-LLI 1.17EW06 NO DATA 1.76W,06 NO DATA 1.21E-O5 2.24W,06 NO DATA NO DATA NO DATA 1.34EWOS S.29E-06 NO DATA NO DATA 4.32E-06 3.24E05 6.33W,06 NO DATA NO DATA NO DATA 3.66EWO5 9.33E-06 NO DATA 1.28SW05 NO DATA 8.47E-06 9.14E-05 NO DATA 6.26E-05 2.39E-5 2.45E-06 5.19W-OS NO DATA 5.07E-05 1.97E-OS 2.12E-06 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 HIighest Annual Net Mean Dose (mrem)

Concentration Location (pCi/kg)

Bone Liver T. Body Thyrold Kidney Lung GI-LLI ALL 0.00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 208 143.00 O.OOE+00 2.22E-03 5.13E-03 O.OOE+00 O.OOE+00 O.OOE+00 3.07E-02 ALL 0.00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 208 26.10 O.OOE+00 1.17W-03 2.64W-03 O.OOE+00 O.OOE+00 O.OOE+00 1.53W-02 ALL 0.00 O.OOE+00 O.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.00E+00 O.OOE+00 0.00E+00 208 11.90 2.13E-02 2.84E-02 9.88EW03 O.OOE+00 9.65E-03 3.75E-03 4.04W-04 208 11613.00 O.OOE+00 1.97E-02 1.97E-02 1.97E-02 1.97E-02 1.97E-02 1.97E-02 m) =

2.13EW02 5.15E-02 3.73W-02 1.97E-02 2.93E-02 2.34E-02 6.60E-02 Dose Commitment (mre Section 4 - Page 14

CCCCCCc c

c ccccccccccc c§c CrCcCr cCCCC CCCcCCC Catawba Nuclear Station Dose from Shoreline Sediment Pathway for 2003 Data Maximum Exposed Teen Shoreline Recreation =

67 hr (in one year)

Shore Width Factor =

0.2 Sediment Surface Mass =

40 kg/r 2 Teen Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mrem/hr per pCim2) x Shore Width Factor x Sediment Surface Mass (kg/tn) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/ni)

Radionuclide T. Body Skin Mn-54 5.80E-09 6.80E-09 Co-58 7.OOE-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Cs-134 1.20E-08 1AOE-08 Cs-137 4.20E-09 4.90E-09 Dose Commitment (mrem) =

Indicator Location 208-IS 208-IS 208-IS ALL 208-1S Sediment (pCi/kg) 21.70 87.50 108.00 0.00 26.90 (mrem)

T. Body Skin 6.75E-05 7.91E-05 3.28E-04 3.85E-04 9.84E-04 1.16E-03 O.OOE+0O 0.00E+O0 6.06E-05 7.07E-05 1.44E-03 1.69E-03 Section 4 - Page 15

Cc ccCCcCcCcCCcC ccccccCcCC ccCCCCCCcccCccccCc Catawba Nuclear Station Dose from Drinking Water Pathway for 2003 Data Maximum Exposed Adult Adult Dose from Drinking Water Pathway (mrem) = Usage (I) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/)

Usage (intake In one year) =

730 1 Highest Annual Insestion Dose Factor Radionuclide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 BaLa-140 H-3 Bone NO DATA NO DATA 4.34E-06 NO DATA 4.84E-06 6.22E-09 3.04E-08 4.16E-06 6.22E-05 7.97E-05 2.03E-05 NO DATA Liver 4.57E-06 7.45E-07 1.02K-0S 2.14E46 1.54E-05 3.46E409 9.75E409 5.95E-06 1.48E-04 1.09E-04 2.55E-08 1.05E4-7 T. Body 872E-07 1.67E-06 3.91E406 4.72E-06 6.96E-06 1.86E-09 6.60E-09 3.41E46 1.21E-04 7.14K-OS 1.33E-06 1.OSE-07 Thyroid Kidney Lung GI-LLI NO DATA 136E-46 NO DATA 1.40E-05 NO DATA NO DATA NO DATA 1.51E405 NO DATA NO DATA 2.85E-06 3.40E-OS NO DATA NO DATA NO DATA 4.02E-OS NO DATA 1.03E4-5 NO DATA 9.70E4-6 NO DATA 3.42W09 NO DATA 2.10E-05 NO DATA 1.53E-08 NO DATA 3.09E-05 1.95E-03 1.02E4-5 NO DATA 1.57E46 NO DATA 4.79E4-5 1.59E45 2.59E-06 NO DATA 3.70E-05 1.23KE45 2.11E-6 NO DATA S67E-09 1.46-08 A4.18E-05 1.05E-07 1.OSE-07 1.05E-07 1.054-07 Net Mean Concentration Dose (mrem)

Indicator Water Location (pCIit)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI ALL 0.00 0.OOE+O0 O.OOE+O0 0.00E+OO O.OOE+OO O.OOE+O0 O.OOE+0O O.OOE+0O ALL 0.00 O.OOE+00 0.00E+00 0.OOE+0 0.OO0E+0 0.OOE+OO O.OOE+OO O.OOE+O0 ALL 0.00 0.OOE+O O.OOE+OO 0O.OOE40 O.OOE+00 0.00E+0O 0.00E+00 O.OOE+OO ALL 0.00 0.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+OO 0.OOE+OO 0.OOE+0O O.OOE+O0 ALL 0.00 O.OOE+00 O.OOE+O0 0.OOE+OO O.OOE+OO 0.OOE+00 0.OOE+O0 0.00E+O0 ALL 0.00 0.OOE+O0 O.OOE+OO 0.00E+00 O.OOE+00 O.00E+00 O.OOE+OO O.OOE+00 ALL 0.00 O.OOE+0 O.OOE+OO O.OOE+OO 0.OOE+OO O.OOE+00 0.00E+O0 O.OOE+O0 ALL 0.00 O.OOE+O0 O.OOE+0O O.0E+0 O.OOE+

O.O.OOE+OO 0.OOE+OO O.OOE+O0 ALL 0.00 0.00E+O 0.00QE+00 0.00E+00 0OOE+0O O.0E+O0 0.00E+00 0.00E+O ALL 0.00 O.OE+OO O.OOE+000 0.OOE+00 0.OOE+0

.OOE+OO 0.OOE+0O O.OOE+0 ALL 0.00 0.00KC+C 0.00E+00 0.00KE+O 0.00E+O0 O.OOE+0K O.OOE+0K 0.00-E+O 214 348.00 O.OOE+00 2.67E-02 2.67E-2 2.67E-02 2.67E-02 2.67E-O2 2.67E-02 im) =

0.00O+OO 2.67E-02 2.67EK-2 2.67K4-2 2.67E4O2 2.67E-02 2.67E-02 Dose Commitment (mrel Section 4 - Page 16

CcccccccccccccccccccccccCC CCCCCCCCCCCcccCCccC Catawba Nuclear Station Dose from Broadleaf Vegetation Pathway for 2003 Data Maximum Exposed Adult Adult Dose from Vegetation (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg)

Usage (intake In one year) =

64 kg Highest Annual Net Mean Ingestion Dose Factor Concentration Dose (mrem)

Indicator Food Radionuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Location (pCi/kg)

Bone Liver T. Body Thyroid Kidney Lung G-LLI 1.131 4.16E-46 5.95E4-6 3.41E-06 1.95E4-3 1.02E-O5 NO DATA 1.5-06 ALL 0.00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.00K+00 O.OOE+00 Cs-134 6.22E-OS 1.48E404 1.21E-04 NO DATA 4.79E-O5 1.59E4O5 2.59E-06 ALL 0.00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 Cs-137 7.97EK-5 1.09E-04 7.14E4-5 NO DATA 3.70E-05 1.23E-05 2.11EK-6 226 25.60 1.31E1-O 1.79EK-1 1.17E4-1 O.OOE+00 6.06E-02 2.02E-02 3.46E-03 Dose Commitment (wrem) =

1.31E-1 1.79E4-1 1.17K1-0 O.OOE+00 6.06E4-2 2.02E-02 3.46E-03 Section 4 - Page 17

rC C c C C c

C c C cc c cc C c C c C C cccc c c c c c C C c C C c Cc C C c C c c Catawba Nuclear Station Dosefrom Fish Pathwayfor 2003 Data Maximum Exposed Adult Adult Dose from Fish Pathway (mrem) = Usage (kg) x Dose Factor (mrem/pCi ingested) x Concentration (pCi/kg) 11-3 Concentration in Fish = Surface Water pCifi x Bioaccumulation Factor 0.9 pCi/kg per pCifi = 12903 pCiI x 0.9 = 11613 pCi/kg Usage (intake in one year) =

21 kg Inuestion Dose Factor Radionuciide Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 11.3 Bone NO DATA NO DATA 4.34E-06 NO DATA 4.84E-06 6.22E-05 7.97E-05 NO DATA Liver 4.57E-06 7.45E-07 1.02E-05 2.14E-06 1.54E-05 1.48E-04 1.09E-04 1.05E-07 T. Body Thyroid Kidney Lung GI-LLI

.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-0S 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 3.91E-06 NO DATA NO DATA 2.8SE-06 3.40E-05 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 1.21E-04 NO DATA 4.79EOS 1.59E-W5 2.59E-06 7.14E-05 NO DATA 3.70E-05 1.23E-O5 2.11E-06 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 Highest Annual Net Mean Concentration Dose (mrem)

Location (pCihkg)

Bone Liver T. Body Thyroid Kidney Lung GI-LLI ALL 0.00 0.00E+O0 O.OOE+00 O.OOE+O0 O.OOE+00 0.00E+OO O.OOE+00 0.OOE+OO 208 143.00 0.00E+O0 2.24E-03 5.02E03 0.OOE+OO O.OE+00 0.OOE+OO 4.53E-02 ALL 0.00 O.OOE+00 O.OOE+00

.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 0.00E+00 208 26.10 0.OOE+00 1.17E-03 2.59E03 O.OOE+00 0.OOE+OO0 O.OOE+00 2.20E-02 ALL 0.00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 ALL 0.00 0.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+OO QEOOE+0 0

0.0OE+00 0.OOE+00 208 11.90 1.99E-02 2.72EW02 1.78EW02 O.OOE+00 9.25W,03 3.07E-03 5.27E-04 208 11613.00 0.00E+00 2.56E-02 2.56E-02 2.56E02 2.56E-02 2.56W,02 2.56E-02 n) =

1.99E-02 5.63EW02 5.11EW02 2.56E402 3.49E-02 2.87E-02 9.35E-02 Dose Commitment (mrei Section 4 - Page 18

rcCcccccccCccCCccccccccCCrcccCCCCCCCCCCcCcr Catawba Nuclear Station Dose from Shoreline Sediment Pathway for 2003 Data Maximum Exposed Adult Shoreline Recreation =

12 hr (in one year)

Shore Width Factor 0.2 Sediment Surface Mass =

40 kglm2 Adult Dose from Shoreline Sediment Pathway (mrem) = Shoreline Recreation (hr) x External Dose Factor (mremlhr per pCi/m2) x Shore Width Factor x Sediment Surface Mass (kg/"?) x Sediment Concentration (pCi/kg)

External Dose Factor Standing Highest Annual Net Dose on Contaminated Ground Mean Concentration (mrem/hr per pCi/in2)

Indicator Radionuclide T. Body Skin Location Mn-54 5.80E-09 6.80E-09 208-lS Co-58 7.OOE-09 8.20E-09 208-IS Co-60 1.70E-08 2.OOE-08 208-IS Cs-134 1.20E-08 1.40E-08 ALL Cs.137 4.20E-09 4.90E-09 208.1S Dose Commitment (mrem) =

Sediment (pCi/kg) 21.70 87.50 108.00 0.00 26.90 (mrem)

T. Body Skin 1.21E-05 1.42E-05 5.88E-05 6.89E-05 1.76E-04 2.07E-04 O.OOE+00 O.OOE-i-00 1.08E-05 1.27E-05 2.58E-04 3.03E-04 Section 4 -Page 19

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

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

EnRad Laboratories is located in Huntersville, North Carolina, at Duke Power Company's Environmental Center.

e 5.3 DOSIMETRY ANALYSIS Duke Power Company's Environmental Center The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures.

5.4 LABORATORY EQUIPMENT QUALITY ASSURANCE 5.4.1 DAILY QUALITY CONTROL EnRad Laboratories has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.

5.4.2 CALIBRATION VERIFICATION National Institute of Standards and Technology (NIST) standards that represent counting geometries are analyzed as unknowns at various frequencies ranging from weekly to annually to verify that efficiency calibrations are valid. The frequency is dependent upon instrument use and performance. Investigations are performed and documented should calibration verification data fall out of limits.

Section 5 -Page I

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 POWER INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Power Nuclear Generation Department Intercomparison Program during 2003. Interlaboratory cross-check standards, including, Marinelli beakers, air filters, air cartridges, gross beta on smears, and tritium in water samples were analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program. A summary of these Intercomparison Reports for 2003 is documented in Table 5.0-A.

5.6 DUKE POWER AUDITS The Catawba Radiation Protection Section was not audited by the Quality Assurance Group in 2003. A Quality Assurance audit was performed in January of 2002. Two examples were identified where personnel failed to complete procedures documenting review of radiological environmental monitoring data that occurred during 2001. All SLC testing requirements were satisfied and there were no situations which would have required the generation of a Special Report or an update to the ODCM.

EnRad Laboratories was not audited by the Quality Assurance Group in 2003. A Quality Assurance audit was performed in June of 2002. Laboratory practices and procedures were reviewed. No significant problems were identified as a result of this 2002 audit.

5.7 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The Catawba Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in June 2003 (Reference 6.12). There were no findings or issues identified by the audit.

EnRad Laboratories was audited by the NRC in January of 2003. There were no findings of significance as a result of the audit.

There were some inspector recommendations as a result of the 2003 audit which are described in PIPs G 00014 and G-03-00016.

5.8 STATE OF SOUTH CAROLINA INTERCOMPARISON PROGRAM EnRad Laboratories routinely participates with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) in an Section S - Page 2

intercomparison program. EnRad Laboratories sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the State of South Carolina DHEC Laboratory for intercomparison analysis.

5.9 TLD INTERCOMPARISON PROGRAM 5.9.1 NUCLEAR TECHNOLOGY SERVICES INTERCOMPARISON PROGRAM Radiation Dosimetry and Records participates in a quarterly TLD intercomparison program administered by Nuclear Technology Services, Inc.

of Roswell, GA.

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

5.9.2 STATE OF NORTH CAROLINA INTERCOMPARISON PROGRAM Radiation Dosimetry and Records routinely participates in a TLD intercomparison program. The State of North Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the State of North Carolina Environmental Dosimetry Intercomparison Report for 2003 is documented in Table 5.0-B.

5.9.3 INTERNAL CROSSCHECK (DUKE POWER)

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 Power) Result is documented in Table 5.0-B.

Section 5 - Page 3

TABLE 5.0-A DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 2003 CROSS-CIIECK RESULTS FOR ENRAD LABORATORIES Cross-Check samples are normally analyzed a minimum of three times. A status of "3 Pass" indicates that all three analyses yielded results within the designated acceptance range. A status of "I Pass" indicates that one analysis of the cross-check was performed.

Footnote explanations are included following this data table.

Gamma in Water 3.5 liters Reference Sample l.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status

_ _ _VI pCi/I pCi/l 5/21/2003 Q032GWS Cr-SI 1.32-2.35 ES 1.76 ES 1.79 ES 3 Pass Mn-54 6.23. 11.05 E4 8.31 E4 8.62 E4 3 Pass Co-58 3.68-6.53 E4 4.91 E4 4.95 E4 3 Pass Fe-59 4.46-7.91 E4 5.95 E4 6.15 E4 3 Pass Co-60 4.27-7.56 E4 5.69 E4 5.87 E4 3 Pass Zn-65 6.17 - 10.94 E4 8.23 E4 8.62 E4 3 Pass Cs-134 3.38-5.99 E4 4.50 E4 4.18 E4 3 Pass Cs-137 7.37-13.07 E4 9.83 E4 9.51 E4 3 Pass Ce-141 1.45-2.56 ES 1.93 ES 1.95 ES 3 Pass Co-57 0.00- 0.00 E0 0.00 E0 5.90 E2 3 Pass("

Ce-139 0.00 - 0.00 E0 0.00 EO 8.20 E2 3 Pass"'

12/23/2003 Q034GWR Cr-51 2.32-4.11 E3 3.09 E3 3.21 E3 3 Pass Mn-54 1.88 -3.34 E3 2.51 E3 2.58 E3 3 Pass Co-58 1.10 -1.95 E3 1.47 E3 1.50 E3 3 Pass Fe-59 0.95-1.68 E3 1.26 E3 1.39E3 3 Pass Co-60 1.72-3.05 E3 2.29 E3 2.28 E3 3 Pass Zn-65 2.13-3.78 E3 2.84 E3 2.95 E3 3 Pass Cs-134 150-2.66 E3 2.00 E3 1.92 E3 3 Pass Cs-137 1.44-2.56 E3 1.93 E3 1.84 E3 3 Pass Ce-141 1.74-3.09 E3 2.33 E3 2.36 E3 3 Pass Co-57 0.00-0.00 EO 0.00 E0 9.78 El 3 Pass!'"

Ce-139 0.00-0.00 EO 0.00 E0 3.52 El 3

Gamma in Water 1.0 liter Reference Sample l.D.

Nuclide Acceptance

-Reference Mean Reported Cross Check Date Range Value Value Status pCV pCi/l pCi/I 5/21/2003 QO32GWS Cr-SI 1.32-2.35 ES 1.76 ES 1.79 ES 3 Pass Mn-54 6.23-11.05 E4 8.31 E4 8.61 E4 3 Pass Co-58 3.68-6.53 E4 4.91 E4 4.91 E4 3 Pass Fe-59 4.46-7.91 E4 S.95 E4 6.26 E4 3 Pass Co-60 4.27-7.56 E4 5.69 E4 5.91 E4 3 Pass Zn-65 6.17 - 10.94 E4 8.23 E4 8.85 E4 3 Pass Cs-134 3.38 -5.99 E4 4.50 E4 3.95 E4 3 Pass Cs-137 7.37-13.07 E4 9.83 E4 9.36 E4 3 Pass Ce-141 1.45 -256 ES 1.93 ES 1.94 ES 3 Pass Co-57 0.00 -0.00 EO 0.00 ED 5.19 E2 3 Pass')

Ce-139 0.00-0.00 EO 0.00 E0 8.83 E2 3 Pass" Li Lu)

Lu)

Secton 5 -Page 4

Gamma in Water 1.0 liter, continued Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status ppCi/

pCi/l pCi/I 12/23/2003 Q034GWR Cr-51 2.32-4.11 E3 3.09 E3 3.19 E3 3 Pass Mn-54 1.88 - 3.34 E3 2.51 E3 2.65 E3 3 Pass Co-58 1.10 - 1.95 E3 1.47 E3 1.55 E3 3 Pass Fe-59 0.95 - 1.68 E3 1.26 E3 1.42 E3 3 Pass Co-60 1.72-3.05 E3 2.29 E3 2.35 E3 3 Pass Zn-65 2.13 -3.78 E3 2.84 E3 2.97 E3 3 Pass Cs-134 1.50-2.66 E3 2.00 E3 1.81 E3 3 Pass Cs-137 1.44-2.56 E3 1.93 E3 1.87 E3 3 Pass Ce-141 1.74-3.09 E3 2.33 E3 2.38 E3 3 Pass Co-57 0.00-0.00 EO 0.00 EO 8.90 El 3 Pass" Ce-139 0.00 -0.00 EO 0.00 EO 3.57 El 3 PassM 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/l pCi/l 5/21/2003 Q032GWS Cr-SI 1.32-2.35 E5 1.76 E5 1.75 E5 3 Pass Mn-54 6.23 - 11.05 E4 8.31 E4 8.72 E4 3 Pass Co-58 3.68 -653 E4 4.91 E4 4.95 E4 3 Pass Fe-59 4.46 - 7.91 E4 5.95 E4 6.35 E4 3 Pass Co-60 4.27-7.56 E4 5.69 E4 5.87 E4 3 Pass Zn-65 6.17 - 10.94 E4 8.23 E4 8.96 E4 3 Pass Cs-134 3.38-5.99 E4 4.50 E4 3.93 E4 3 Pass Cs-137 7.37-13.07 E4 9.83 E4 9.51 E4 3 Pass Ce-141 1.45-2.56 E5 1.93 E5 1.94 E5 3 Pass Co-57 0.00-0.00 EO 0.00 EO 6.42 E2 3 Pass")

Ce-139 0.00-0.00 EO 0.00 EO 8.19 E2 3 Pass"'

12/23/2003 Q034GWR Cr-51 2.32 -4.11 E3 3.09 E3 3.24 E3 3 Pass Mn-54 1.88-3.34 E3 2.51 E3 2.64 E3 3 Pass Co-58 1.10 - 1.95 E3 1.47 E3 1.52 E3 3 Pass Fe-59 0.95 - 1.68 E3 1.26 E3 1.41 E3 3 Pass Co-60 1.72-3.05 E3 2.29 E3 2.33 E3 3 Pass Zn-65 2.13 - 3.78 E3 2.84 E3 3.00 E3 3 Pass Cs-134 1.50-2.66 E3 2.00 E3 1.75 E3 3 Pass Cs-137 1.44-2.56 E3 1.93 E3 1.84 E3 3 Pass Ce-141 1.74-3.09 E3 2.33 E3 2.35 E3 3 Pass Co-57 0.00 - 0.00 EO 0.00 EO 8.72 El 3

Gamma in Water 0.25 liter Reference Sample l.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status

_pCi_

pCi/I pCi_

512112003 Q032GWS Cr-51 1.32-2.35 E5 1.76 E5 1.79 E5 3 Pass Mn-54 6.23 - 11.05 E4 8.31 E4 8.80 E4 3 Pass Co-58 3.68 -6.53 E4 4.91 E4 5.01 E4 3 Pass Fe-59 4.46-7.91 E4 5.95 E4 6.50 E4 3 Pass Co-60 4.27-7.56 E4 5.69 E4 5.99 E4 3 Pass Zn-65 6.17-10.94 E4 8.23 E4 9.08 E4 3 Pass Cs-134 3.38-5.99 E4 4.50 E4 4.01 E4 3 Pass Cs-137 737 - 13.07 E4 9.83 E4 9.58 E4 3 Pass Ce-141 1.45-2.56 E5 1.93 E5 1.97 E5 3 Pass Co-57 0.00-0.00 EO 0.00 EO 5.83 E2 3 Pass"I Ce-139 0.00-0.00 EO 0.00 EO 7.90 E2 3 Passr, Section 5 - Page 5

Gamma in Water 0.25 liter, continued Reference Sample l.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCil pCi/I pCi/I 12/2312003 Q034GWR Cr-51 2.32-4.11 E3 3.09 E3 3.33 E3 3 Pass Mn-54 1.88 - 3.34 E3 2.51 E3 2.59 E3 3 Pass Co-58 1.10- 1.95 E3 1.47 E3 1.55 E3 3 Pass Fe-59 0.95-1.68 E3 1.26 E3 1.39 E3 3 Pass Co-60 1.72-3.05 E3 2.29 E3 2.33 E3 3 Pass Zn-65 2.13-3.78 E3 2.84 E3 3.15 E3 3 Pass Cs-134 1.50-2.66 E3 2.00 E3 1.76 E3 3 Pass Cs-137 1.44-2.56 E3 1.93 E3 1.86 E3 3 Pass Ce-141 1.74 -3.09 E3 2.33 E3 2.35 E3 3 Pass Co-57 0.00-0.00 EO 0.00 EO 1.12 E3 3 Pass°"

Ce-139 0.00-0.00 EO 0.00 EO 3.49 El 3PAST' Gamma in Filter Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCiltotal

.pCittotal pCi/total 12/1112003 E4020-37 Cr-51 1.39-2.53 E2 1.87 E2 1.88 E2 3 Pass Mn-54 0.86-1.53 E2 1.15 E2 1.19 E2 3 Pass Co-58 5.56-9.86 El 7.41 El 7.61 El 3 Pass Fe-59 5.12-9.08 El 6.83 El 6.63 El 3 Pass Co-60 0.78-1.38 E2 1.03 E2 1.07 E2 3 Pass Zn-65 1.20-2.14 E2 1.60 E2 1.25 E2 3 Pass' Cs-134 6.80- 12.06 El 9.07 El 9.09 El 3 Pass Cs-137 6.44-114A2 El 8.58 El 8.11 El 3 Pass Ce-141 1.01 - 1.79 E2 1.35 E2 1.37 E2 3 Pass Co-57 0.00- 0.00 EO 0.00 EO 3.48 EO 3 Pas Iodine in Water Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status K illA pCi/I pCi/I 1/1012003 Q031LIWI 1-131 3.64-6.46 E2 4.86 E2 5.40 E2 3 Pass I/102003 Q031LIW2 1-131 1.22-4.90 EO 2.45 EO 2.53 EO 3 Pass 1/10/2003 Q031LIW3 1-131 1 4.91 -8.71 El 6.55 El 5.64 El 3 Pass 7/112003 Q033LIWI 1-131 6.65-11.78 E2 8.86 E2 10.10 E2 3 Pass 7/112003 Q033L1W2 I-131 3.56 - 6.87 EO 4.94 EO 6.82 EO 1/3 High'j 7/1/2003 Q033LIW3 1-131 1.68-2.97 E2 2.23 E2 2.51 E2 3 Pass Iodine in Milk Reference Sample l.D.

Nuclide Acceptance

-Reference Mean Reported Cross Check Date Range Value l

Value Status

-pCi/I pCi/

I pCi/I 5/2112003 Q032LIMI 1-131 4.63 - 8.22 E2 6.18 E2 6.07 E2 3 Pass 5121/2003 Q032LlM2 1-131 1.97-3.49 E2 2.63 E2 2.52 E2 3 Pass 5121/2003 Q032LIM3 1-131 0.00-0.00 EO 0.00 EO 0.00 EO 3 Pass Section 5 -Page 6

Iodine in Milk, continued Reference Sample l.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status piAI pi/l pCiA 11/18t2003 Q034LIM1 1-131 4.10-7.27 E2 5.47 E2 6.10 E2 3 Pass 11/18/2003 Q034LIM2 1-131 0.00-0.00 EO 0.00 EO 0.00 EO 3 Pass 11/18/2003 Q034LIM3 1-131 1.92-3.40 El 2.56 El 2.65 El 3 Pass Iodine Cartridge Reference Sample I.D.

Nuclide Acceptance

-Reference Mean Reported Cross Check Date Range Value Value Status 62 3pCi pci pci 6/12t2003 E3678-37 1-131 4.65-8.25 El 6.20 El 8.14 El 3 Pass p

Cs-137 0.00-0.00 EO 0.00 EO 58.77 EO 3 Pass 12/11/2003 1 E4021-37 1-131 5.97-10.58 El 7.96 El 9.33 El 3 Pass Beta in Water Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date I

Range j

Value Value Status

-pai/l

. pCi/l pCiA 9/18/2003 E3849-37 Gross Beta 1.85 -3.27 E2 2.46 E2 2.26 E2 3 Pass Beta Smear Reference Sample l.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date I

Range Value Value T Status

.dprn dpmn dpm.

5/1612003 A16754-37 Gross Beta 7.09 - 12.58 E3 9.46 E3 9.20 E3 3 Pass Tritium in Water Reference Sample I.D.

Nuclide Acceptance Reference Mean Reported Cross Check Date I

J Range Value Value Status j

l pCi/l l

pCiA pCi/l 5/21/2003 Q032TWS1 H-3 0.00 -0.00 EO 0.00 EO 0.00 EO 3 Pass 5/21/2003 Q032XtS2 H-3 5.83 - 10.35 E4 7.78 E4 6.89 E4 l

3 Pass 12/23/2003 Q034TWRI H-3 1.37-4.07 E2 2.37 E2 3.19 E2 3 Pass 12t23/2003 I Q034TWR21 H-3 0.00-0.00 EO 0.00 EO 0.00 EO 3 Pass 12/23/2003 Q034TWR3 H-3 0.97-1.73 E3 1.30 E3 1.31 E3 3 Pass Secon S - Page 7

Table 5.0-A Footnote Explanations (1) Gamma in Water, Sample ID Q032GWS, Reference Date 5/21/2003: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli, 0.25 L Marinelli Gamma in Water, Sample ID Q034GWR, Reference Date 12/23/2003: 3.5 L Marinelli, 1.0 L Marinelli, 0.5 L Marinelli, 0.25 L Marinelli Co-57 and Ce-139 were observed in cross-checks and was attributed to a contaminant arriving with the source.

The nuclides were determined to be present, but there was no reference activity applicable to the results. Ce-139 was not detected in the Q034GWR, Reference Date 12/23/2003 0.5 L Marinelli analysis.

(2) Gamma in Filter, Sample ID E4020-37, Reference Date 12/11/2003 Cross-check was vendor-prepared.

Zn-65 activities for this cross-check were consistently low. The source was analyzed at Catawba and similar results were observed. Co-57 was an unintended contaminant in the sample. General Office PIP G-04-00047 was written to record investigative actions.

Gamma in Filter, Sample ID E3677A-37, Reference Date 6/12/2003 was a vendor-prepared cross-check.

A uniform overestimation of about 72% for all nuclides was consistently observed in each analysis. The source or its calibration certificate was determined to be in error.

Data for this cross-check was not included in the Annual Radiological Environmental Operating Report. General Office PIP G-04-00039 was written to record investigative actions.

(3) Iodine in Water, Sample ID Q033LIW2, Reference Date 7/1/2003 Three results for low-level I-131 [364.48 keV] analysis were reported, with one being above acceptance limit. General Office PIP G-04-00146 was written to record investigative actions.

(4) Iodine Cartridge, Sample ID E3678-37, Reference Date 6/12/2003 Cs-137 is a known contaminant of the charcoal media and was detected in all reported analyses. The nuclide was determined to be present, but there was no reference activity applicable to the results.

Section 5 - Page 8

TABLE 5.0-B 2003 ENVIRONMENTAL DOSIMETER CROSS-CHECK RESULTS Nuclear Technology Services 1st Quarter 2003 TLD Delivered Reported Number (mrem)

(mrem) 101327 89 95.2 101200 89 97.0 101166 89 95.7 101102 89 96.6 101274 89 94.7 Average Bias (B)

Standard Deviation (S)

Measure Performance IBI+S Bias

(% diff) 6.97 8.99 7.53 8.54 6.40 7.69 1.07 8.76 Pass/Fail Criteria Pass/Fail

<+1-15%

Pass

<+1-15%

Pass

<+1-15%

Pass

<+1-15%

Pass

<+1-15%

Pass

<15%

Pass 2nd Quarter 2003 TLD Delivered Reported Bias Pass/Fail Number (mrem)

(mrem)

(% diff)

Criteria Pass/Fail 101196 70 71.9 2.71

<+/-15%

Pass 101149 70 74.8 6.86

<+1-15%

Pass 101152 70 71.8 2.57

<+1-15%

Pass 101188 70 76.4 9.14

<+1-15%

Pass 101151 70 72.7 3.86

<+/-15%

Pass Average Bias (B) 5.03 Standard Deviation (S) 2.87 Measure Performance IBI+S 7.90

<15%

Pass 3rd Quarter 2003 TLD Delivered Reported Number (mrem)

(mrem) 100113 90 93.8 100215 90 94.4 100138 90 94.4 100380 90 93.5 100126 90 93.7 Average Bias (B)

Standard Deviation (S)

Measure Performance IB1+S Bias

(% diff) 4.22 4.89 4.89 3.89 4.11 4.40 0.46 4.86 Pass/Fail Criteria Pass/Fail

<+1-15%

Pass

<+1-15%

Pass

<+1-15%

Pass

<+1-15%

Pass

<+/-15%

Pass

<15%

Pass 4th Quarter 2003 TLD Delivered Reported Bias Pass/Fail Number (mrem)

(mrem)

(% diff)

Criteria Pass/Fail 100075 76.4 81.7 6.94

<+1-15%

Pass 100397 76.4 83.2 8.90

<+1-15%

Pass 100335 76.4 82.7 8.25

<+1-15%

Pass 100050 76.4 82.0 7.33

<+1-15%

Pass 100030 76.4 83.8 9.69

<+1-15%

Pass Average Bias (B) 8.22 Standard Deviation (S) 1.12 Measure Performance IBI+S 9.34

<15%

Pass k~j Li Li Lij Li Li Lij Li Li)

State of North Carolina, Division of Radiation Protection Spring 2003 TLD Delivered Reported Number (mrem)

(mrem) 100964 65 70.0 100159 65 72.2 100815 65 69.1 100759 65 70.5 100150 65 72.3 100823 65 72.2 100169 65 67.9 100921 65 71.1 Average Bias (B)

Standard Deviation (S)

Measure Performance IBI+S Bias Pass/Fail

(% diff)

Criteria Pass/Fail 7.69

<+1-15%

Pass 11.08

<+1-15%

Pass 6.31

<+1-15%

Pass 8.46

<+1-15%

Pass 11.23

<+1-15%

Pass 11.08

<+1-15%

Pass 4.46

<+1-15%

Pass 9.38

<+1-15%

Pass 8.71 2.48 11.19

<15%

Pass Fall 2003 TLD Delivered Reported Bias Pass/Fail Number (mrem)

(mrem)

(% diff)

Criteria Pass/Fail 100940 59.4 63.1 6.23

<+1-15%

Pass 100723 59.4 58.8

-1.01

<+1-15%

Pass 100747 59.4 61.2 3.03

<+1-15%

Pass 101020 59.4 59.0

-0.67

<+1-15%

Pass 100080 59.4 60.8 2.36

<+1-15%

Pass 100356 59.4 60.7 2.19

<+1-15%

Pass 100818 59.4 59.6 0.34

<+1-15%

Pass 101122 59.4 59.4 0.00

<+1-15%

Pass Average Bias (B) 1.56 Standard Deviation (S) 2.41 Measure Performance IBI+S 3.96

<15%

Pass Section 5 - Page 9

Internal Crosscheck (Duke Power) 1st Quarter 2003 TLD Delivered Reported Number (mrern)

(mrem) 100050 39 37.5 100030 39 37.3 100008 39 36.3 100140 39 39.3 100007 39 36.7 100957 39 38.1 100996 39 37.5 100940 39 38.9 100954 39 37.0 100955 39 38.0 Average Bias (B)

Standard Deviation (S)

Measure Performance IB!+S Bias Pass/Fail

(% diff)

Criteria Pass/Fail

-3.85

<+1-15%

Pass

-4.36

<+1-15%

Pass

-6.92

<+1-15%

Pass 0.77

<+/-15%

Pass

-5.90

<+1-15%

Pass

-2.31

<+1-15%

Pass

-3.85

<+1-15%

Pass

-0.26

<+1-15%

Pass

-5.13

<+1-15%

Pass

-2.56

<+1-15%

Pass

-3.44 2.41 5.84

<15%

Pass 2nd Quarter 2003 TLD Delivered Reported Bias Pass/Fail Number (mrem)

(mrein)

(% diff)

Criteria Pass/Fail 100155 65 63.0

-3.08

<+1-15%

Pass 100792 65 64.7

-0.46

<+1-15%

Pass 100769 65 64.4

-0.92

<+1-15%

Pass 100061 65 64.7

-0.46

<+1-15%

Pass 100799 65 63.4

-2.46

<+1-15%

Pass 100117 65 63.7

-2.00

<+1-15%

Pass 100012 65 63.8

-1.85

<+1-15%

Pass 100114 65 65.0 0.00

<+1-15%

Pass 100366 65 64.8

-0.31

<+1-15%

Pass 100314 65 63.9

-1.69

<+1-15%

Pass Average Bias (B)

-1.32 Standard Deviation (S) 1.04 Measure Performance lB k+S 2.36

<15%

Pass 3rd Quarter 2003 TLD Delivered Reported Number (mrem)

(mrem) 100511 26 25.8 100552 26 25.9 100590 26 26.0 100470 26 25.8 100481 26 25.8 101201 26 24.4 101204 26 25.6 101205 26 25.0 101207 26 25.4 101208 26 25.6 Average Bias (B)

Standard Deviation (S)

Measure Performance 1B1+S Bias Pass/Fail

(% diff)

Criteria Pass/Fail

-0.77

<+1-15%

Pass

-0.38

<+1-15%

Pass 0.00

<+1-15%

Pass

-0.77

<+1-15%

Pass

-0.77

<+1-15%

Pass

-6.15

<+1-15%

Pass

-1.54

<+1-15%

Pass

-3.85

<+1-15%

Pass

-2.31

<+1-15%

Pass

-1.54

<+1-15%

Pass

-1.81 1.88 3.69

<15%

Pass 4th Quarter 2003 TLD Delivered Reported Bias Pass/Fail Number (mrem)

(mrem)

(% diff)

Criteria Pass/Fail 100085 39 37.9

-2.82

<+1-15%

Pass 100976 39 38.5

-1.28

<+1-15%

Pass 101413 39 37.2

-4.62

<+1-15%

Pass 101397 39 37.0

-5.13

<+1-15%

Pass 100260 39 39.0 0.00

<+1-15%

Pass 100584 39 38.2

-2.05

<+1-15%

Pass 100343 39 38.4

-1.54

<+1-15%

Pass 100158 39 37.2

-4.62

<+1-15%

Pass 100225 39 41.7 6.92

<+1-15%

Pass 100112 39 37.7

-3.33

<+1-15%

Pass Average Bias (B)

-1.85 Standard Deviation (S) 3.50 Measure Performance IBI+S 5.34

<15%

Pass Section S - Page 10

Li)

Li.

Lij Li/

Li)

Li)

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6.0 REFERENCES

6.1 6.2 6.3 6.4 6.5 6.6 6.7 6.8 6.9 6.10 6.11 6.12 6.13 Catawba Selected License Commitments Catawba Technical Specifications Catawba Updated Final Safety Analysis Review Catawba Offsite Dose Calculation Manual Catawba Annual Environmental Operating Report 1985 - 2002 Catawba Annual Effluent Report 1985 - 2003 Probability and Statistics in Engineering and Management Science, Hines and Montgomery, 1969, pages 287-293.

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

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.

EnRad Laboratories Operating Procedures RETDAS, Radiological Effluent Tracking and Dose Assessment Software, Canberra Version 3.5.1, DPC Revision #4.0 NRC Integrated Inspection Report 03-03 Duke Power Company EnRad Laboratory Charcoal Cartridge Study, performed 2001 Section 6 - Page I

APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PRO CEDURES Appendix A - Page I

APPENDIX A 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 The indicator dairies at locations 209 (5.96 mi SSW) and 219 (5.70 mi SW) discontinued operation.

Changes to the milk sampling program were implemented effective 12/2/2003. No replacement dairies were available.

Location 214 (Rock Hill Water Supply) was determined to be in the SSE sector at 7.30 miles following 2003 GPS measurement.

Previous documentation listed the location as in the SE sector at 7.30 miles. No site relocation or modifications were necessary as a result of the change.

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 rmixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry. Ten percent of samples receiving gamma analysis are analyzed as duplicate analyses.

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.

Appendix A - Page 2

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

Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by gas-flow proportional counters. Samples are batch processed with a blank to ensure sample contamination has not occurred.

III. CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 2003.

IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRBORNE PARTICULATE AND RADIOIODINE Airborne particulate and radioiodine samples at each of six locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge positioned behind the filter in the sampler. The samplers are designed to operate at a constant flow rate (in order to compensate for any filter loading) and are set to sample approximately 2 cubic feet per minute. Filters and cartridges were collected weekly. A separate weekly gamma analysis was performed on each charcoal cartridge and air particulate. A weekly gross beta analysis was performed on each filter. The continuous composite samples were collected from the locations listed below.

Location 200

=

Site Boundary (0.63 mi. NNE)

Location 201

=

Site Boundary (0.53 mi. NE)

Location 205

=

Site Boundary (0.23 mi. SW)

Location 212

=

Tega Cay (3.32 mi. E)

Location 217

=

Rock Hill Substation (10.3 mi. SSE)

A.2 DRINKING WATER Monthly composite drinking water samples were collected at each of two locations. A gross beta and gamma analysis was performed on monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected biweekly from the locations listed below.

Location 214

=

Rock Hill Water Supply (7.30 mi. SSE)

Location 218

=

Belmont Water Supply (13.5 mi. NNE)

Appendix A - Page 3

A.3 SURFACE WATER Monthly composite samples were collected at each of three locations. A gamma analysis was performed on the monthly composites.

Tritium analysis was performed on the quarterly composites.

The composites were collected biweekly from the locations listed below.

Location 208 Location 211 Location 215

=

Discharge Canal (0.45 mi. S)

=

Wylie Dam (4.06 mi. ESE)

=

River Pointe - Hwy 49 (4.21 mi. NNE)

A.4 GROUND WATER Grab samples were collected quarterly from residential wells at each of two locations.

A gamma analysis and tritium analysis were performed on each sample. The samples were collected from the locations listed below.

Location 252 Location 254

=

Residence (0.64 mi. SW)

=

Residence (0.82 mi. N)

A.5 MILK Biweekly grab samples were collected at each of three locations. A gamma and low-level Iodine-131 analysis was performed on each sample. The biweekly grab samples were collected from the locations listed below.

Location 209 Location 219 Location 221

=

Dairy - (5.96 mi. SSW)

=

Dairy - (5.70 mi. SW)

=

Dairy- (14.5 mi. NW)

A.6 BROADLEAF VEGETATION Monthly samples were collected as available at each of five locations. A gamma analysis was performed on each sample. The samples were collected from the locations listed below.

Location 200 Location 201 Location 217 Location 222 Location 226 Site Boundary (0.63 mi. NNE)

=

Site Boundary (0.53 mi. NE)

Rock Hill Substation (10.3 mi. SSE)

=

Site Boundary (0.70 mi. N)

=

Site Boundary (0.48 mi. S)

Appendix A - Page 4

A.7 FOOD PRODUCTS Monthly samples were collected when available during the harvest season at one location. A gamma analysis was performed on each sample. The samples were collected from the location listed below.

Location 253

=

Irrigated Gardens (1.90 mi. SSE)

A.8 FISH Semiannual samples were collected at each of two locations. A gamma analysis was performed on the edible portions of each sample. Boney fish (i.e. Sunfish) were prepared whole minus the head and tail portions.

The samples were collected from the locations listed below.

Location 208

=

Discharge Canal (0.45 mi. S)

Location 216

=

Hwy 49 Bridge (4.19 mi. NNE)

A.9 SHORELINE SEDIMENT Semiannual samples were collected at each of three locations.

A gamma analysis was performed on each sample following the drying and removal of rocks and clams. The samples were collected from the locations listed below.

Location 208

=

Discharge Canal (0.45 mi. S)

Location 210

=

Ebenezer Access (2.31 mi. SE)

Location 215

=

River Pointe - Hwy 49 (4.21 mi. NNE)

A.10 DIRECT GAMMA RADIATION (TLD)

Thermoluminescent dosimeters (TLD) were collected quarterly at forty locations. A gamma exposure rate was determined for each TLD.

TLD locations are listed in Table 2.1-B. The TLDs were placed as indicated below.

An inner ring of 16 TLDs, one in each meteorological sector in the general area of the site boundary.

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

The remaining TLDs were placed in special interest areas such as population centers, residential areas, schools, and at three control locations.

Appendix A - Page 5

A.11 ANNUAL LAND USE CENSUS An Annual Land Use Census was conducted to identify within a distance of 8 kilometers (5.0 miles) from the station, the nearest location from the site boundary in each of the sixteen meteorological sectors, the following:

The Nearest Residence The Nearest Meat Animal The Nearest Garden greater than 50 square meters or 500 square feet The Nearest Milk-giving Animal (cow, goat, etc.)

The census was conducted during the growing season from 7/7 to 7/10/2003, and 8/19/2003. Results are shown in Table 3.11. No changes were made to the sampling procedures during 2003 as a result of the 2003 census.

V.

GLOBAL POSITIONING SYSTEM (GPS) ANALYSIS Catawba Nuclear station Radiological Environmental Monitoring Program (REMP) locations were verified using global positioning system (GPS) technology during the summer of 2003.

Most GPS measurements were taken during June, 2003 through July, 2003. All current REMP sample locations were measured. Historical locations (i.e. no longer in service) were not measured during this evaluation.

Additionally, all 2003 Catawba land use census items of interest were measured.

GPS equipment was utilized to determine the distance and sector from the Catawba site centerline to the nearest residence, milk animal, meat animal, and garden in each of the sixteen meteorological sectors.

Prior to this evaluation, PIP 0-02-06264 was generated as the result of an NRC (Nuclear Regulatory Commission) inspection which included the use of a GPS unit by the NRC inspector. The inspector measured a TLD site (Oconee site 056) and a discrepancy was observed.

The PIP generated required that all locations be measured using standard GPS parameters and methodologies.

The Catawba site centerline used for all GPS measurements was referenced from the Catawba Nuclear Station Updated Final Safety Analysis Report (UFSAR),

section 2.1.1.1, Specification of Location. Waypoint coordinates used for CNS GPS measurements were latitude 350-3'-5"N and longitude 810-4'-10"W. Maps and tables were generated using North American Datum (NAD) 27.

Data normally reflect accuracy to within 2 to 5 meters from point of measurement. All GPS field measurements were taken as close as possible to the item of interest. Distances for the locations are displayed using three significant figures.

Appendix A - Page 6

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF RESULTS 2003 Appendix B - Page I

Environmental Radiological Monitoring Program Summary L-Facility: Catawba Nuclear Station L

Ln Location: York County, South Carolina Docket No. 50413,414 Report Period: 01-JAN-2003 to 31-DEC-2003 Type and w

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

Unit of Analyses Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed (LD)

Range Code Range Range Air Particulate 217 (pCi/m3)

(10.3 mi SSE)

BETA 260 L.OOE-02 1.43E-2 (208/208) 205 1.54E-2 (52152) 1.42E-2 (52/52) 0 5.79E 2.69E-2 (0.23 mi SW) 5.79E 2.69E-2 6.94E 2.41E-2 CS-134 260 5.00E-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 260 6.00E-02 0.00 (01208) 0.00 (0/52) 0.00 (0/52) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 1-131 260 7.OOE-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 -0.00 0.00 - 0.00 0.00 - 0.00 L_

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

Li Zero range indicates no detectable activity measurements I

Report Generated @ 4/19/2004 4:51 PM Appendix B - Page 2

. Environmental Radiological Monitoring Program Summary U

Facility: CatawbaNuclearStation L

Ln Location: York County, South Carolina Docket No.

50-413,414 Report Period: 01-JAN-2003 to 31-DEC-2003 Medium or Tyean Lower A

Location with Highest No. of Non-Total All Indicator Highl ean Control Rotn Pathway Limit of Annual Mean Routine Sampled Number Detection Locations Name, Distance, Direction Location Report Meas.

of Unit of Analyses Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed Range Code Range Range Air Radioiodine 217 (pCilm3)

(10.3 mi SSE)

CS-134 260 5.OOE-02 0.00 (0/208) 0.00 (0152) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 260 6.00E-02 0.00 (0/208) 0.00(0/52) 0.00(0/52) 0 0.00 - 0.00 0.00- 0.00 0.00 - 0.00 1-131 260 7.00E-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/19/2004 4:51 PM Appendix B - Page 3

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.

50-413,414 Report Period: 01-JAN.2003 to 31-DEC-2003 No. of Non~

Medium or Type and Total Lower All

d.tLocation with Highest Cnr outine Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

Unit of Analyses Mean (Fraction)

Location Mean (Fraction) Mean (Fraction)

Measurement Performed (LL)

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

(13.5 mni NNE)

BALA-140 26 15 0.00 (0/13) 0.00 (0/14) 0.00(0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 BETA 26 4

2.27 (13/13) 214 2.27 (13113) 2.02 (13/13) 0 1.35 -2.98 (7.30 mi SSE) 1.35 - 2.98 1.12 - 3.25 CO-58 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 CO-60 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 26 18 0.00(0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 26 30 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H-3 8

2000 636 (4/4) 214 636 (4/4) 288 (3/4) 0 283 - 1050 (7.30 mi SSE) 283 - 1050 189 - 433 1-131 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 -0.00 MN-54 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00- 0.00 NB-95 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00 - 0.00 0.00 -0.00 0.00- 0.00 ZN-65 26 30 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00-0.00 0.00- 0.00 0.00 -0.00 ZR-95 26 15 0.00 (0/13) 0.00 (0/14) 0.00 (0/13) 0 0.00- 0.00 0.00 - 0.00 0.00- 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Li Zero range indicates no detectable activity measurements Report Generated @ 4/19/2004 4:51 PM Appendix B - Page 4

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.

50-413,414 Report Period: 01-JAN-2003 to 31-DEC-2003 No. of Non-Medium or Type and Total Lower Location with Highest Control Noutin Pathway Number Limit of A IndiatorAnnual Mean c

Sampled of Detection Locations Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Measurement Performed (D)

Range' Code Range Range Surface Water 215 (pCi/liter)

(4.21 nil NNE)

BALA-140 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 - 0.00 0.00 - 0.00 CS-137 39 18 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 -0.00 0.00 - 0.00 H-3 12 2000 6897 (8/8) 208 13140 (4/4) 237 (2/4) 0 249 - 19500 (0.45 mi S) 8260 - 19500 220 - 254 I-131 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00- 0.00 0.00-0.00 0.00-0.00 NB-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 - 0.00 0.00 -0.00 ZN-65 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 - 0.00 0.00 -0.00 ZR-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 -0.00 0.00 -0.00 0.00 -0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/19/2004 4:51 PM Appendix B - Page 5

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.

50413,414 Report Period: 01-JAN-2003 to 31-DEC-2003 LocaionwithHigestNo.

of Non-Medium or Type and Total Lower Location with Highest Pathway Number Limit of aAnnual Mean S

Locations A

Mean

.Location Report Sampled of Detection Name, Distance, Direction 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 8

15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 8

15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 8

15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00- 0.00 0.00- 0.00 0.00 - 0.00 CS-134 8

15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 8

18 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 8

30 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 H-3 8

2000 0.00 (0/8) 0.00 (0/8) 0.00(0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 -0.00 1-131 8

15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 8

15 0.00 (0/8) 0:00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 8

15 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 8

30 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00- 0.00 0.00 - 0.00 0.00- 0.00 ZR-95 8

15 0.00 (018) 0.00 (0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/19/2004 4:52 PM Appendix B - Page 6

Environmental Radiological Monitoring Program Summary U

Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.

50413,414 Report Period: 01-JAN-2003 to 31-DEC-2003 No. of Non-Medium or Type and Total Lower Al dtLocation with HighestCotl Ruin Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

Unit of Analyses Mean (Fraction)

Location Mean (Fraction) Mean (Fraction)

Measurement Performed Range Code Range Range Milk 221 (pCifliter)

(14.5 mi NW)

BALA-140 72 15 0.00 (0/46) 0.00 (0/26) 0.00 (0/26) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 72 15 0.00 (0/46) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 72 18 0.00 (0/46) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 72 15 0.00 (0/46) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLI-131 72 1

0.00 (0/46) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/19/2004 4:52 PM Appendix B - Page 7

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.

50413,414 Report Period: 01-JAN-2003 to 31-DEC-2003

=-

.No.

of Non-Medium or Type and Total Lower Location with Highest of None All Indicator AnulControl Routine Pathway Number Limit of n

La.

t Annual Mean Sampled of Detection Locatons Name, Distance, Direction Meas.

Unit of Analyses Mean (Fraction)

Location Mean (Fraction)

Mean (Fractionj Measurement Performed Range Code Range Range Broadleaf 217 Vegetation (10.3 mi SSE)

(pCi/kg-wet)

CS-134 40 60 0.00 (0/32) 0.00 (0/8) 0.00 (0/8) 0 0.00- 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 40 80 39.0 (3/32) 226 49.6 (2/8) 24.0 (1/8) 0 17.9 -54.1 (0.48 mi S) 45.1 - 54.1 24.0- 24.0 1-131 40 60 0.00 (0/32) 0.00 (0/8) 0.00 (0/8) 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 @ 4/19/2004 4:52 PM Appendix B - Page 8

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.

50-413,414 Report Period: 01-JAN-2003 to 31-DEC-2003 No. of Non-Medium or Type and Total Lower All Idit Location with Highest Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

Unit of Analyses Mean (Fraction)

Location Mean (Fraction) Mean (Fraction)

Measurement Performed (LL)

Range -

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

LOCATION CS-134 6

60 0.00 (0/6) 0.00 (0/6) 0.00 (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 (016) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 6

60 0.00 (016) 0.00 (016) 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)

t.

Zero range indicates no detectable activity measurements Report Generated @ 4/1912004 4:52 PM U

Appendix B - Page 9

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.

50-413,414 Report Period: 01-JAN-2003 to 31-DEC-2003 No. of Non-Medium or Type and Total Lower A

t Location with Highest Cnr outine Pathway Number Limit of Annual Mean Sampled of Detection Locations Name, Distance, Direction Location Report Meas.

Unit of Analyses Mean (Fraction)

Location Mean (Fraction) Mean (Fraction)

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

(4.19 mi NNE)

CO-58 12 130 143 (1/6) 208 143 (1/6) 0.00 (0/6) 0 143 - 143 (0.45 mi S) 143 - 143 0.00 - 0.00 CO-60 12 130 26.1 (1/6) 208 26.1 (1/6) 0.00 (0/6) 0 26.1 -26.1 (0.45 mi S) 26.1 - 26.1 0.00 - 0.00 CS-134 12 130 0.00 (016) 0.00 (0/6) 0.00 (016) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 12 150 11.9 (1/6) 208 11.9 (1/6) 0.00 (0/6) 0 11.9-11.9 (0.45 mi S) 11.9 - 11.9 0.00 - 0.00 FE-59 12 260 0.00 (0/6) 0.00 (016) 0.00 (016) 0 0.00 - 0.00 0.00- 0.00 0.00 -0.00 MN-54 12 130 0.00 (0/6) 0.00 (016) 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 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses. (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/19/2004 4:52 PM Appendix B - Page 10

Environmental Radiological Monitoring Program Summary L-Facility: Catawba Nuclear Station i

,Location:

York County, South Carolina Docket No.

50413,414 Report Period: 01-JAN-2003 to 31-DEC-2003 No. of Non-Medium or Type and Total Lower Location with Highest Cnr outin Pathway Number Limit of All Indicator Annual Mean Coctiol Rort Sampled of Detection Locations Name, Distance, Direction Meas; Unit of Analyses Mean (Fraction)

Location Mean (Fraction) Mean (Fraction)

Measurement Performed (LLD)

Range,

Code Range Range Shoreline 215 Sediment (4.21 mi NNE)

(pCi/kg-dry)

MN-54 6

0 21.7 (1/4) 208-lS 21.7 (112) 0.00 (0/2) 21.7 - 21.7 (0.45 mi S) 21.7 -21.7 0.00 - 0.00 CO-58 6

0 87.5 (1/4) 208-IS 87.5 (1/2) 0.00 (0/2) 0 87.5 - 87.5 (0.45 mi S) 87.5 - 87.5 0.00 - 0.00 CO-60 6

0 108 (1/4) 208-IS 108 (1/2) 0.00 (0/2) 0 108 -108 (0.45 mi S) 108 - 108 0.00 - 0.00 CS-134 6

150 0.00 (014) 0.00 (0/2) 0.00 (012) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 6

180 26.9 (2/4) 208-IS 26.9 (2/2) 0.00 (0/2) 0 13.9 - 39.9 (0.45 mi S) 13.9 - 39.9 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) t..'

Zero range indicates no detectable activity measurements k,

If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 411912004 4:52 PM Appendix B - Page 11

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Location: York County, South Carolina Docket No.

50413,414 Report Period: 01-JAN-2003 to 31-DEC-2003 Type and Location with Highest No. of Non-Medium or Total All Indicator

-Control Routine Limit of Annual Mean Pathway Sampled Number Dtcion Locations -

Nm Ance, Decn Location Report of Detection

-a XName, Distance, Direction es of Meas.

Analyses Mean (Fraction)

Location Mean (Fraction)

Mean (Fraction)

Performed Range Code Range Range Direct Radiation 217 (10.3 mi SSE)

TLD 247 (7.33 mi ESE)

(mRlstandard quarter) 251 (9.72 mni WNW) 160 O.OOE+00 18.9 (148/148) 229 25.0 (4/4) 14.0 (12/12) 0 11.1 -29.6 (0.84 mi NW) 21.1 -28.2 10.1 - 18.0 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

Zero range indicates no detectable activity measurements Report Generated @ 4/19/2004 4:52 PM Appendix B - Page 12

APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES Appendix C - Page I

APPENDIX C CATAWBA NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES DEVIATION & UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage FZ Sample Frozen PS _

Pump out of service / Undergoing Repair 1W Inclement Weather SL Sample Loss/Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Tom Filter PI Power Interrupt VN Vandalism PM Preventive Maintenance C.1 SAMPLING DEVIATIONS Air Particulate and Air Radioiodines Scheduled Actual

-Reason Location Collection Dates Collection Dates Code Corrective Action Power to the air sampler was interrupted, presumably by a severe storm during the composite period. The clock on the operative air sampler (sampler 00298) indicated 78.01 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of run time.

Sampler 00298 was operating at the time the collector arrived at the air station, which was 7/15/2003 10:44. The backup sampler (sampler 00311) was not operative at the time of collection and the clock indicator was blank. The composite period was determined by subtracting the run time of 78.01 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (3.25 days) from the end date of the composite period. This yielded a composite period of 7/12/2003 04:44 to 212 7/8 - 7/15/03 7/12 - 7/15/03 PI 7/15/2003 16:49.

Surface Water

- Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action Intake line clogged, stopping water flow.

Work request 98270547 was written. A grab sample was taken. Temporary water sampling equipment was placed into 215 1/21 -218/03 2/18 - 2/18/03 OT operation until repair was completed.

Appendix C - Page 2

Surface Water, continued Scheduled Actual Reason Location Collection Dates Collection Dates -

Code Corrective Action The pier at this site which houses the submersible pump for water sampling was replaced. Power to sampling equipment was interrupted for maintenance personnel to remove and replace the old pier structure. A grab sample was collected on 6/10/2003 and normal sampling was resumed. PIP C-02-01903 and C-03-00387 document the pier 215 5/13 - 6/10/03 6/10 - 6/10/03 PO replacement.

C.2 UNAVAILABLE ANALYSES There no unavailable analyses for the 2003 REMP.

Appendix C - Page 3

APPENDIX D ANALYTICAL DEVIATIONS No Analytical deviations were incurred for the 2003 Radiological Environmental Monitoring Program Appendix D - Page I

APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 2003. Appendix E is located separately from this report and is permanently archived at Duke Power Company's Environmental Center radiological environmental master file, located at the McGuire Nuclear Station Site in Huntersville, North Carolina.

Appendix E - Page I