Text

Annual Radiological Environ Operating Rept for 1998. with
	ML20206H914
Person / Time
Site:	Catawba
Issue date:	12/31/1998
From:	Gordon Peterson; DUKE POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9905120051
	Download: ML20206H914 (113)
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l gg Duka Energy Carpor'ti:n EM@= Catawba Nudear Station 4800 Concord Road York, SC 29745 Gary R. Peterson (80J) 831-42510FFICE Vice President (803) 831-3426 FAX l

1 May 4, 1999 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 l

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Subject:

Catawba Nuclear Stations, Units 1 and 2 1 Docket Nos. 50-413 and 50-414 I 1998 Annual Radiological Environmental Operating Report Pursuant to Technical Specification 5.6.2 and Selected Licensee l Commitment 16.11-16.1, please find attached the 1998 Annual '

Radiological Environmental Operating Report. This report covers operation of Catawba Units 1 and 2 during the 1998 calendar year.

Any questions concerning this report may be directed to Kay Nicholson at 803-831-3237.

Sin rely Gary R. Pe erson 1

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TABLE OF CONTENTS 1.0 Esecutive Summary 11 2.0 Introduction ,

2-1 2.1 Site Description and Sample Locations 2-1 2.2 Scope and Requirements of Environmental Monitoring Program. 2-1 2.3 Statistical and Calculational Methodology 2-2 2.3.l Estimation of the Mean Value . 2-2 2.3.2 Lower Lesel of Detection. Minimum Detectable Activity, and Critical Level 23 2.3.3 Trend Identification. 2-3 3.0 Interpretation of Results 31 3.1 Airbome Radioiodine and Particulates 33 3.2 Drinking Water. . 3-5 3.3 Surface Water 3-7 3.4 Ground Water 3-9 3.5 Milk . . . . 3-10 3.6 Broadleaf Vegetation. 3-11 3.7 Food Products 3-12 3.8 Fish . . . 3-13 3.9 Shoreline Sediment 3-16 3.10 Bottom Sediment 3-l9 3.1I Direct Gamma Radiation 3-22 3.12 Land Use Census 3-24 4.0 Esaluation of Dose 4-1 4.1 Dose from Environmental Measurements 4-1 4.2 Estimated Dose from Releases . 4-2 4.3 Comparison of Doses. 4-2 5.0 Quality Assurance 5-1 5.1 Sample Collection 5-l 5.2 Sample Analysis . 5-1 5.3 Dosimetry Analysis 5-l SA Laboratory Equipment Quality Assurance 5-1 5.4.1 Daily Quality Control 5-1 5.4.2 Calibration Verification 5-1 5.4.3 Batch Processing 5-2 5.5 Environmental Protection Agency Intercomparison Program 5.2 5.6 Duke Power Intercomparison Program 5.2 5.7 Duke Power Audits 52 5.7.1 Radiation Protection Section 5-2 5.7.2 EnRad Laboratories . 5-2 5.8 U.S. Nuclear Regulatory Commission Inspections 52 5.0 State of South Carolina Intercomparion Program. 5-3 5.9.1 Environmental Samples 53 5.9.2 TLD Intercomparison Program. 5-3 6.0 References 6-1 i

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Appendices Appendix A: Environmental Sample and Analysis Procedures A-1

1. Change of Sampling Procedures. . . . . A-2 '

11. Description of Analysis Procedures . . . . A2 111. Change of Analysis Procedures . . . . . . A3 IV. Sampling and Analysis Procedures . . . . A3 A. I Airborne Particulate and Radiciodine . A3 A.2 Drinking Water . . A-3 A.3 Surface Water . . A-4 A.4 Ground Water. . . A-4 A.5 Milk . . . . A-4 A.6 Broadleaf Vegetation . . . A-4 A.7 Food Products. . . . A5 A.8 Fish . . . . A-5 A.9 Shoreline Sediment . . . . A-5 A.10 Bottom Sediment . . A-5 A.I I Direct Gamma Radiation (TLD) . . A6 A.12 Annual Land Use Census . . . A-6 V. Program improvements . . . . A-6 Appendix B: Radiological Environmental Monitoring Program Summary of Results 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 . . . B9 Fish . . B-10 Shoreline Sediment . . . . . B-Il Bottom Sediment . . . . . . B-12 Direct Gamma Radiation (TLD) . . . . B-13 Appendix C: Sampling Deviations and Unavailable Analyses . . C1 C.I Sampling Deviations . . . C-2 C.2 Unavailable Analyses . . . C-3 Appendix D: Analytical Deviations - Lower Limits of Detection. . D-l Appendix E:. Radiological Environmental Monitoring Program Results . E-l LIST OF FIGURES 2.1 1 Sampling 1.ocations Map (Site Boundary) . 2-7 2.1 2 Sampling Locations Map (Ten Mile Radius) . 28 3.1 Concentration of Gross Beta in Air Particulate . . . 3-3 3.2 Concentration of Tritium in Drinking Water . . 3-5 3.3 Concentration of Tritium in Surface Water. 37 3.8-1 Concentration of Co 58 in Fish . . . . 3-14 3.8 2 Concentration of Co-60 in Fish . . . 3-14 3.9-1 Concentration of Co-38 in Shoreline Sediment . 3-17 3.9-2 Concentration of Co-60 in Shoreline Sediment . . . 3-17 3.10 1 Bottom Sediment Sampling Locations . 3-19 3.10-2 Concentration of Radionuclides in Bottom Sediment 3-21 3.11 Direct Gamma Radiation (TLD) Results . . 3-22 3.10 Land Use Census Map . . . 3-26

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1 LIST OF TABLES 2.1 -A Radiological Monitoring Program Sampling Locations (TLD Sites) 25 2.1 B Radiological Monitoring Program Sampling Locations . 2-6 2.2- A Reporting Levels for Radioactivity Concentrations in Environmental Samples 2-9 2.2 B REMP Analysis Frequency . 2-10 2.2-C Maximum Values for the Lower Limits of Detection 2-11 3.1 - A Mean Concentrations of Gross Beta in Air Particulate. 3-4 3.1 -B Mean Concentration of Air Radiciodine (1-13 l) . 3-4 3.2 Mean Concentrations of Radionuclides in Drinking Water . 3-6 3.3 Mean Concentrations of Radionuclides in Surface Water 3-8 3.5 Mean Concentrations of Radionuclides in Milk 3-10 3.6 Mean Concentrations of Radionuclides in Broadleaf Vegetation . 3-11 3.7 Mean Concentration of Radionuclides in Food Products 3 12 3.8 Mean Concentrations of Radionuclides in Fish 3-15 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment 3-18 3.l0 Mean Concentrations of Radionuclides in Bottom Sediment 3-21 3.1 l Direct Gamma Radiation (TLD) Results 3-23 3.12 Land Use Census Results . 3-25 4.1 - A 1998 Environmental and Efiluent Dose Comparison 43 4.1 -B i Maximum Indiv dual Dose for 1998 based on Environmental Measurements for Catawba Nuclear Station 4-6 5.0- A Environmental Protection Agency Interlaboratory Comparison Program 5-4 5.0-B Duke Power Company Interlaboratory Comparison Program 5-6 5.0-C State of North Carolina Department of Environmental Health and Natural Resources 1998 Environmental Dosimeter Cross-Check Results . 5-1I

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LIST OF ACRONYMS USED IN Tills TEXT (in alphabe/i d orderj llW Biweekly C Control CL Critical I.evel DEHNR Department of Environmental Health and Natural Resources DHEC Department of Health and Environmental Control EPA Environmental Protection Agency ,

GI-LLI Gastrointestinal - Lower 1.arge Intestine LLD Lower Limit of Detection M Monthly MDA Minimum Detectable Activity Mrem millirem NIST National Institute of Standards and Technology j

NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual pCi/kg picoeurie per kilogram pCi/l picocurie per liter pCi/m3 picoeurie per cubic meter Q Quarterly REMP Radiological Environmental Monitoring Program LA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECH SPECS Technical Specifications TLD Thermoluminescent Dosimeter pCi/mi microcurie per milliliter UFSAR Updated Final Safety Analysis Report W Weekly

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l 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 1998.

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. Supplemental analyses were performed for some media for additional information. Nine-hundred eighty-five samples were analyzed comprising 1115 test results in order to compile data for the 1998 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 1998 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 e pected, and all positively identified measurements were within limits as specified in SLCs.

Additionally, environmental radiological monitoring data is consistent with effluents :

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introduced into the environment by plant p"%

operations. The total body dose estimated to the ma imum e posed member of the public as calculated by environmental sampling data, e cluding TLD results, was 3.49E-~01 mrem for 1998. It is therefore concluded that station operations has had no significant radiological impact on tb- bealth and safety of the public or the environment.

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2.0 INTRODUCTION

2.1 SITE DESCRIPTION AND SAMPl>E I OCATIONS 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 efDuents are released into Lake Wylie via the station discharge canal and are not accompanied by the large additional dilution water How associated with "once-through" condenser cooling. This design results in greater radionuclide concentrations in the discharge canal given comparable liquid effluent source terms.

The CNS Radiological Environmental Monitoring Program sampling locations are summarized in Tables 2.1 - A and 2.1 -B. Table 2.1 -A lists the environmental Thermoluminescent Dosimeter locations. Table 2.1-B lists all other sampling locations. The REMP sampling and analysis procedures are summarized in Appendix A.

Figures 2.1-1 and 2.1-2 are maps depicting the specific positions of all REMP 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 one mile of CNS. Figure 2.1-2 comprises all remaining locations.

2.2 SCOPE AND REOIIIREMENTS 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 monitorm.g 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 Section 2 - Page I

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 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 IEMP 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 ! to 10CFR50. Results are shown in Table 3.12.

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 METIlODOLOGY 2.3.1 ESTIM ATION OF Tile 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 REMP. The following equation was used to estimate the mean (reference 6.8):

N

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x = estimate of the mean, i = individual sample, N = total number of samples with a net activity (or concentration) x, = 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 Section 2 - Page 2

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

2.3.2 LOWER LEVEL OF DETECTION, MINIMUM DETECTABI E ACTIVITY, AND CRITICAL LEVEL The Lower Level of Detection (LLD), Minimum Detectable Activity (MDA), and Critical Level (CL) 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.

CL - The CL is defined as the net count rate which must be exceeded before a sample is considered to contain any measurable activity above the 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 ;

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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.

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TAllLE 2.1-A CATAWilA RADIOLOGICAL SiONITORING PROGRAh!

SAhlPLING LOCATIONS (TLD SITES)

Site Location Distance Sector Site Location ' Distance Sector 200 SITE BOUNDARY 0.6 mi NNE 233 4 5 MILE RADIUS 3.9 mi ENE 201 SITE BOUNDARY 0.5 mi NE 234 4-5 MILE RADIUS 4.5 mi E 202' SITE BOUNDARY 0.6 mi E 235 4 5 MILE RADIUS 3.9 mi ESE 203 SITE BOUNDARY 0.4 mi ESE 236 4 5 MILE RADIUS 4.3 mi SE 204 SITE BOUNDARY 0.5 mi SSW 237 4-5 MILE RADIUS 4.8 mi SSE 205 SITE BOUNDARY 0.3 mi SW 238 4 5 MILE RADIUS 4.0 mi S 206 SITE BOUNDARY 0.7 mi WNW 239 4 5 MILE RADIUS 4.5 mi SSW 207 SITE BOUNDARY 0.9 mi NNW 240 4 5 MILE RADIUS 4.1 mi SW 212 SPECIAL INTEREST 3.3 mi E 241 4-5 MILE RADIUS 4.6 mi WSW 217 CONTROL 10.3 mi SSE 242 4-5 MILE RADIUS 4.6 mi W 222 SITE BOUNDARY 0.7 mi N 243 4 5 MILE RADIUS 4.4 mi WNW 223 SITE BOUNDARY 0.6 mi E 244 4-5 MILE RADIUS 40 mi NW 224' SITE BOUNDARY 0.6 mi ESE 245 4-5 MILE RADIUS 4.1 mi NNW 225 SITE BOUNDARY 0.7 mi SE 246 SPECIAL INTEREST 7.8 mi ENE 226 SITE BOUNDARY 0.5 mi S 247 CONTROL 7.3 mi ESE 227 SITE BOUNDARY 0.5 mi WSW 248 SPECIAL INTEREST 6 6 mi S 228 SITE BOUNDARY 0.6 mi W 249 SPECIAL INTEREST 8.1 mi S 229 SITE BOUNDARY 0.8 mi NW 250 SPECIAL INTEREST 10.4 mi WSW 230 4-5 MILE RADIUS 4.4 mi N 251 CONTROL 9.7 mi WNW 231 4 5 MILE RADIUS 4.2 mi NNE 255 " SITE BOUNDARY 0.6 mi ENE 232 4-5 MILE RADIUS 4.1 mi NE 256 " SITE BOUNDARY 0.6 mi SSE ,

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TAllLE 2.1-11 CATAWilA RADIOLOGICAL MONITOllING PROGRAM SAMPLING LOCATIONS Table 2.1-B Codes W Weekly SM Semimonthly BW Biweekly Q Quarterly M Monthly SA Semiannually C Control Site {ocat*on i Qscription Surface D,ruening Shoressee Fe Fash Milk Broad Ar, Rad. w,,,, ,,,, m., ,,,,ed w G,remed Part. (a) Yes. (b) 200 Site Boundery (0 6 mi NNE) W M 201 Site Boundary (0 5 mi NE) W M 205 Site Boundary (0 3 mi SW) W 208 Discharge Canal (0.5 mi S) BW SA SA 209 Dairy (6 0 mi SSW) SM 210 Ebenezer Access (2 3 mi SE) SA 21l Wylie Dam (4 0 mi ESE) BW 212 Tega Cay (3.3 mi E) W 214 Rock Hill Water Supply (7.3 mi SE) BW 215 C River Pointe Hwy 49 (4 2 mi NNE) BW SA 216 C Hwy 49 Bridge (4 0 mi NNE) SA 217 C Rock Hill Substation (10 3 mi SSE) W M 218 C Belmont Water Supply (13 4 mi NNE) BW 219 Dairy (5.7 mi SW) SM 221 C Dairy (14.5 mi NW) SM 222 Site Boundary (0 7 mi N) M 226 Site Boundary (0 5 mi S) M 252 Residence (0 7 mi SW) Q 253 Irrigated Gardens (Downstream within 5 mde radius) M(a) 254 Residence (0 8 mi N) Q (a) During Harvest Season (b) When Available I

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TAIILE 2.2-A ItEPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAA1PLES Air ' Food Analysis Water Particulates Fish Milk Products (pCi/ liter) or Gases (pCi/kg-wet) - (pCi/ liter) (pCi/kg-wet) 3 (pCi/m )

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 :

Zn-65 300 20,000 Zr-Nb-95 400 1 131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 (a) NOTE: Ifno drinking waterpathway exists, a value of30,000pCi/ liter may be used i

Section 2 Page 9 1

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TA11LE 2.2-11 REMP ANALYSIS FREQUENCY Sample Analysis Gamma Tritium Low Level Gross TLD Medium Schedule Isotopic l-131 Beta Air Radioiodine Weekly X Air Weekly X Particulates Quarterly X Composite Direct Radiation X Quarterly Monthly Surface Composite X Water Quarterly Composite X Biweekly X Monthly Drinking Composite X X Water Quarterly Composite X Ground Water Quarterly X X Shoreline Sediment Semiannually X Milk Semimonthly X X Fish Semiannually X Broadleaf Monthly Vegetation (when X available)

Monthly Food Products (during X harvest season)

)

I

)

Section 2 - Page 10

TAIILE 2.2-C MAXIMUM VALUES FOlt Tile LOWEll Ll311T OF DETECTION Air Analysis Water Particulates Fish Milk Food Sediment (pCi/ liter) orOases (pCi/kg-wet) (pCi/ liter) Products (pCi/kg-dr,s )

(pCi/m3 ) (pCi/kg-wet)

Gross Beta 4 0.01 F1-3 2000(*)

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-l31 1(b) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 (a) Ifno drinking water pathway exists, a value of3000 pCi/ liter may be used.

(b) Ifno drinking water pathway exists, the LLD ofgamma isotopic analysis may be used.

)

Section 2 Page 1I

) .

3.0 INTERPRETATION OF RESULTS In addition to the required sampling and analyses described in Selected Licensee Commitments Table 16.11-7, the following supplemental measures were taken in 1998.

These measures were first adopted in 1986 to improve assessment of the impact of CNS operations on the environment.

1) Shoreline sediment (required collection at one point along CNS discharge canal, Location 208) was collected at three points (Locations 208-1S,208-2S and 208-3S).

2) Shoreline sediment (required collection semiannually) was collected quarterly. The first and third quarter samples from Locations 208-IS,'210 and 215 are considered required samples and all remaining samples are considered supplemental.

3) Fish (required collection from Location 208 and 216 semiannually) were collected quarterly. Second and fourth quarter samples are the required samples and the first and third quarter samples are supplemental.

4) Bottom sediment (not required to be collected) was collected quarterly at Locations 208-lM,208-2M and 208-3M. These are all supplemental samples.

Review of all 1998 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 1998 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) 4 through 1998.

Summary tables containing 1998 information required by Technical Specification Administrative Control 5.6.2 are located in Appendix B. These tables contain data based upon required sample results and supplemental sample results.

Evaluation for significant trends was performed for radionuclides that are listed as required within Selected Licensee Commitments 16.11-8. The radionucides include: H-3, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, I-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 and 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 NRC reporting levels (Table 2.2) were used as criteria for trending conclusions. All 1998 maximum percentages of reporting levels were well below the 100% action level. The highest :

section 3 - Page i 1 -

value noted during 1998 was 45% for surface water tritium collected during second quarter at discharge canal Location 208.

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 R&ES 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 1998 sample analysis results were reviewed to detect and identify any significant trends.

i 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 1998 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.

l

) section 3 - Page 2

) . - - _ -

3.1 AIRBORNE RADIOIODINE AND PARTICUl>ATES In 1998, 259 radiciodine and particulate samples were analyzed, 207 from four indicator locations and 52 at the control location. Particulate samples were analyzed for gross beta.

Gamma analysis was performed on 20 particulate composite samples,16 at the four indicator locations and four at the control location.

Gross beta analysis is performed on particulate filters. Figure 3.1 shows individual sample gross beta results for the indicator location with highest annual mean and the control location samples during 1998. 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 .! ~ (' *. ~ g... j,p o ~L, 1998. Table 3.1-A shows the highest indicator aD ;

~

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

f

""""40j - 3,? f ;

'j *1"['k

-Y j j a

There was no detectable I-131 in air radioiodine

~

I~

samples analyzed in 1998. Table 3.1-B shows the .. 1 . I highest indicator annual mean and control location annual mean for I-131 since 1984 (preoperational

y 4 3) ~ ,- f period). Routine Air Sampling K-40 and Be-7 that occur naturally were routinely detected in charcoal cartridges collected during the year. Cs-137 activity was detected on three indicator cartridges during 1998. The detection of Cs-137 on the charcoal cartridge was determined in 1990 to be an active constituent of the charcoal (reference 6.5). Therefore, the Cs-137 activity was not used in any dose calculations in Section 4.0 of this report.

Figure 3.1 There is no report:ng levelpr gross beta on air partictolate peilm s Concentration of Gross Beta in Air Particulate 100E-01 9 00E 02 - -

8.00E 02 --

7 00E-02 ; p 6 00E-02 l

5 00E 02 ,

4 00E 02 I L- - L- - -

3 00E 02 - - --

2.00E.02 l - - - - - - - -

_ -- + --

100E 02 ---- ---- ---

f 0 00E+00 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 4 --Indicator Location -+- Control Location I i --. _ - _ . _ _ . _ _ _ _ J Section 3 - Page 3

)

Table 3.1-A Mean Concentration of Gross Heta in Air Particulate Year Indicator Location (pCi/m#) Control Location (pCi/m#)

1984 2.25 E-2 1.82 E-2 1985 2.12E 2 1.53 E-2 1986 3.62E-2 3.41 E-2 1987 2.67 E-2 2.32 E-2 1988 2.29E-2 2.30E-2 1989 2.IIE-2 2.13 E-2 1990 2.39E-2 2.72 E-2 1991 2.19E-2 2.51 E-2 1992 1.90E-2 2.01 E-2 1993 1.87E-2 1.94E-2 1994 2.03 E-2 2.03 E-2 1995 4.88 E-2 3.23E 2 1996 3.49E-2 2.60E-2 l997 2.83 E-2 2.28 E-2 Average (1987 - 1997) 2.60E-2 2.37E-2 1998 2.69 E-2 2.12 E-2 Table 3.1-B Mean Concentration of Air Radioiodine (I-131)

Year Indicator Location (pCi/m*) Control Location (pCi/m#)

1984 1.30 E-3 1.46E-2 1985 4.75 E-3 2.3 8E-2 1986 1.43 E-2 1.02 E-2 ,

1987 1.38 E-2 0.00E0 1988 0.00E0 0.00E0 1989 0.00E0 0.00E0 1990 0.00E0 0.00E0 1991 0.00E0 0.00E0 1992 0.00E0 0.00E0 1993 0.00E0 0.00E0 1994 0.00E0 0.00E0 1995 0.00E0 0.00E0 1996 0.00E0 0.00E0 1997 0.00E0 0.00 E0 1998 0.00E0 0.00E0 0.00E0 = no detectable measurements

)

Section 3 - Page 4

) -

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 three indicator samples and three control samples during 1998. The mean indicator tritium concentration for 1998 was 507 pCi/1,2.54% of reporting level. The mean control tritium concentration for 1998 was 183 pCill,0.92% of e reporting level. Figure 3.2 and Table 3.2 display the highest indicator and control location annual mean concentrations for tritium since 1984.

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 2.51 pCi/l in 1998 and the control location concentration was 2.44 pCi/1. The 1997 indicator mean was 3.74 pCi/1. The table shows that current gross beta levels are not statistically different from preoperational concentrations.

No gamma emitting radionuclides were identified in 1998 drinking water samples. There have been no gamma emitting radionuclides identified in drinking water samples since 1988.

Figure 3.2 pculiter Concentration of Tritium in Drinking Water 2500 2000 1500 1000 500 I 0' ' -

1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998

-G-Indcator Location Cont Location g Le

) seaion 3 - Page S

)

Table 3.2 Mean Concentration of Radionuclides in Drinking Water Gross Beta (pCi/1) Tritium (pCi/l)

YEAR Indicator Control Indicator Control Location Location Location Location 1984 4.72 1.83 3.10 E-2 3.10E-2 1985 2.70 2.24 4. I 3 E2 4.00E2 1986 3. I I 2.26 7.23 E2 7.33 E2 1987 I 10 2.40 7.80E2 4.80E2 1988 3.60 2.60 6.64E2 0.00E0 1989 3.60 2.90 8.91 E2 5.72E2 1990 4.50 3.20 7.03 Fj2 0.00E0 1991 3.70 2.20 7.04Eh 0.00E0 1992 3.20 2.40 7.65 E2 5.38E2 1993 3.50 2.50 7.06E2 0.00E0 1994 3.30 2.70 0.00E0 0.00E0 1995 4.80 4.50 4.28 E2 2.21 E2 1996 3.08 3.14 3.71 E2 3.27E2 I997 3.74 3. I 5 3.54E2 2.28E2 1998 2.51 2.44 5.07E2 1.83E2 0.00E0 = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 6

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 emuent discharge point.

Tritium was the only radionuclide identified in surface water samples collected during 1998. All indicator location samples contained tritium with an average concentration of all indicator locations of 3493 pCi/l. This is 17.5% of reporting limit for tritium in surface water. Indicator Location 208 (Discharge Canal) showed a range of reporting levels from 27.6% to 45.5%. The 1998 mean concentration was 6613 pCi/1. Tritium was not detected in any control samples during 1998.

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

Table 3.3 summarizes gamma spectroscopy results for surface water samples collected since 1984. Values shown on the table from 1988 through 1998 show a relatively stable to slightly increasing trend for tritium.

Figure 3.3 pcmu Concentration of Tritium in Surface Water 12000 10000 l

- A

_ _ \ .

v 4000 2000 l

1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998

___.N2 ._ _.. [$ _

section .3 - Page 7

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

YEAR Co-58 Co-60 Nb-95 Cs-137 11-3 Indicator 11-3 Control 1984 4.59E-l 5.71 E-l 6.48 E-l 9.08 E- l 3.35 E2 3.18E2 1985 3.46E0 4.83 E-2 2.70E0 8.19E-l 1.19E3 5.05 E2 1986 3.10E-l -4.12 E-2 2.05E0 4.85 E-l 2.34E3 5.05E2 1987 0.00E0 3.10E0 4.30E0 9.90E0 4.17E3 6.20E2 1988 9.20E0 0.00E0 0.00E0 0.00E0 6.03 E3 6.07E2 1989 0.00E0 0.00E0 0.00E0 0.00E0 5.27E3 0.00E0 1990 6.50E0 0.00E0 0.00E0 0.00E0 3.98E3 7.73 E2 1991 0.00E0 0.00E0 0.00E0 0.00E0 4.87E3 0.00E0 1992 0.00E0 0.00E0 0.00E0 0.00E0 6.91 E3 6.64 E2 1993 4.70E0 1.80E0 0.00E0 0.00E0 5.98E3 0.00E0 1994 0.00E0 0.00E0 0.00E0 0.00E0 8.42E3 0.00E0 1995 0.00E0 0.00E0 0.00E0 0.00E0 5.13E3 2.89E2 1996 0.00E0 0.00E0 0.00E0 0.00E0 7.36E3 2.61 E2 1997 0.00E0 0.00E0 0.00E0 0.00E0 7.77E3 2.20E2 1998 0.00E0 0.00E0 0.00EO 0.00E0 6.61 E3 0.00E0 0.00E0 = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 8

3.4 GROliND 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 1998.

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

Secuan 3 - Page 9

3.5 MILK A total of 78 milk samples was analyzed by gamma spectroscopy and low level iodine during 1998. There were two indicator locations and one control location sampled.

There were no gamma emitting radionuclides identified in milk during 1998.

There was one gamma emitting radionuclide identified in one indicator sample during 1996. Cs-137 was detected at a concentration of 6.05 pCi/1, which is 8.5% of the reporting level. 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/1. Cs-137 attributable to past nuclear weapons testing is known to exist in many environmental media at low, highly variable levels.

Table 3.5 lists highest indicator location annual mean and control location annual mean for Cs-137 since the preoperational period. Concentrations are similar for the two sample types. Cs-137 is the only radionuclide, other than K-40 and Be-7, reported in milk samples since 1988.

Table 3.5 Mean Concentration of Radionuclides in Milk YEAR Cs-137 Indicator (pCi/l) Cs-137 Control (pCill) 1984 2.95 E0 2.98 E0 1985 2.11 E0 2.12E0 1986 3.76E0 4.54 E0 1987 5.00E0 5.50E0 1988 3.20E0 3.80E0 1989 0.00E0 0.00E0 1990 8.00E0 6.70E0 1991 0.00E0 0.00E0 1992 3.40E0 5.00E0 1993 5.00E0 0.00E0 1994 2.80E0 0.00E0 1995 8.60E0 0.00E0 1996 6.05 EO 0.00E0 1997 0.00E0 0.00E0 1998 0.00E0 0.00E0 0.00E0 = no detectable measurements 1984 - 1986 mean based on all net activity l

Section 3 - Page 10

E 3.6 IIROADLEAF VEGETATION Gamma spectroscopy was performed on 50 broadleaf vegetation samples during 1998.

Four indicator locations and one control location were sampled.

Four of the forty samples collected at indicator locations contained detectable Cs-137 activity. Cs-137 was detected in four of the ten samples collected at Location 201. This location's highest concentration was 65.3 pCi/kg which is 3.27% of the reporting level.

Cs-137 was not detected in the control location.

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.

Broadleaf Vegetation Sampling Table 3.6 Mean Concentration of Radionuclides in Broadleaf Vecetation YEAR Cs-137 Indicator (pCi/kg) Cs-137 Control (pCL'kg) 1984 3.76El 1.30E l 1985 5.48El 4.16E l 1986 7.42E l 2.22E l 1987 6.10El 5.10E l 1988 9.10E l 7.40E l 1989 1.00E2 4.80E l 1990 7.70E l 5.80E l 1991 1.98E2 8.60E l 1992 9.70E I 0.00E0 1993 1.13 E2 3.20E l 1994 7.00E l 0.00E0 1995 3.60E l 0.00E0 1996 2.23 E2 6.22E l I997 7.57E I 0.00E0 1998 6.53El 0.00E0 0.00E0 = no detectable measurements 1984 - 1986 mean based on all net activity section 3 Page iI

1 3.7 FOOD PRODUCTS Collection of food product samples (crops) from an irrigated garden began in 1989. The garden is located on Lake Wylic downstream from CNS, Location 253. During 1998, three samples were collected and analyzed for gamma radionuclides. There is no control location for this media type.

No detectable activity has been reported in food products since 1989. Table 3.7 shows Cs-137 indicator location highest annual mean concentrations since 1984.

Table 3.7 $ lean Concentration of Radionuclides in Food Products YEAR Cs-137 Indicator (pCi/kg) 1989 0.00E0 1990 0.00E0 1991 0.00E0 l992 0.00E0 1993 2.50El 1994 0.00E0 1995 0.00E0 1996 0.00E0 1997 0.00E0 1998 0.00E0 0.00E0 = no detectable measurements J section 3 - Page 12 J

l

1 1

3.8 FISII Gamma spectroscopy was performed on 24 fish samples collected during 1998. One downstream indicator location and one control location were sampled. Co-58, Co-60 and Cs-137 were the preuominant radionuclides identified in fish samples. Four of twelve indicator location samples contained Co-58. Two of twelve indicator location samples contained Co-60. Two of the twelve indicator location samples contained Cs-137.

Cs-137 was identified in one of the twelve control location samples.

The highest average concentration for Co-58 in indicator location samples was 64.4 pCi/kg which represents 0.21% of the reporting level. The highest average concentration for Co-60 in indicator locations was 28.6 pCi/kg which represents 0.29% of the reporting level. For Cs-137 in indicator location samples, the highest average concentration was 15.8 pCi/kg which represents 0.79% of the reporting level. The highest individual sample concentrations were as follows: Co-58, 89.3 pCi/kg (0.3 % of reporting level), Co-60, 30.1 pCi/kg (0.30% of reporting level) and Cs-137,15.9 pCi/kg (0.8% of reparting 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 higher for forager fish than for predator and bottom feeding fish. Similar results have been noted from 1990 through 1997.

Figures 3.8-1 and 3.8-2 are graphs displaying annual mean concentrations for Co-58 and Co-60 which have been major calculated dose contributors from ingestion of fish since 1988. Concentrations of these radionuclides have followed a direct pattern along with their concentrations in liquid effluents released from the plant. The addition of supplemental samples in 1986, has provided additional data to assist in this continuing correlation between radionuclide concentration in indicator fish samples and radionuclide concentration released via the liquid efiluent pathway.

Table 3.8 depicts the highest indicator e, +wp y*.w w location annual mean for radionuclides In addition, radionuclides

~

Fp detected. -

, I identified in fish samples since 1988 have been included in the table. Overall, Q ' :g-j l

radionuclides have not shown a -

"j significant trend or accumulation since L, / .m-1988. e K-40 was observed in fish samples

. ! ' ~.-

collected during 1998. r

- - - - = -

Fish Sampling section 3 Page 13

Figure 3.8-1 pcag Concentration of Co-58 in Fish u0 1800 1600 1400 1200 1000 800 A

o / \

. / \

. _ >\ .__ __ __ _ _ _

\

o. _

l P' ; ; ; -

M- g ,,

1984 1965 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 g.

i Irdcator Locata -*-- Contrd Locate -5 % Reportog Level l t ._. ._ _ _ . _. . . _ _ . _. _. __

l l

Figure 3.8-2 l

peng Concentration of Co-60 in Fish l 600 1

500 400 x0 200 -

A I h _

1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1984 1985 1986 Irocsor Locate -*-- Contrd Locata -5% Repating Level I .__ __ . _ _ _. -

__ __.i Section 3 - Page 14

J Table 3.8 Mean Concentrations of Radionuclides in Fish (pCi/ku) !

Year Mn-54 Co-58 Co-60 Cs-134 Cs-137 Nb-95 Fe-59 Sb-122 Sb-125 1984 3.07E0 3.00E0 6.llE-l -5.32 E0 1.83E0 0.00E0 0.00E0 0.00E0 0.00E0 J 1985 7.68 E-l 3.40El 9. l l E0 3.22 E0 1.28El 5.07E0 0.00E0 0.00E0 0.00E0 {

1986 2.0 l E l 1.86E2 4.0l E l 3.5 t El 9.29El 0.00E0 7.30E0 0.00E0 0.00E0

]

1987 7.24E0 7.57E l 4.8 t E l 3.83E0 4.27El 5.40E0 0.00E0 0.00E0 0.00E0 j 1988 2.85 E l 1.40E2 9.70El I.67El 8.24E l 0.00E0 0.00E0 0.00E0 0.00E0 1 1989 8.28E0 1.33 E2 3.83 E l I.47El 4.37E l 8.58E-I 0.00E0 0.00E0 0.00E0 )

1990 2.51 E l I .75 E2 7.77El 1.32El 4.66El 3.33 E0 0.00E0 7.00E0 9.25 E0 l 1991 3.15 El I.46E2 1.29E2 1.03 E l 4.60E l 7.90E-1 2.30E0 0.00E0 7.45 E0 )

1992 1.34El 9.02E l 6.20E l I.27El 4.61 El 0.00E0 0.00E0 0.00E0 0.00E0 I 1993 2.14El 3.58E2 1.21E2 2.73 E0 2.56E l 0.00E0 0.00E0 0.00E0 0.00E0 1994 1.91E0 4.75E l 1.81 E l 0.00E0 1.75 El 0.00E0 0.00E0 0.00E0 1.45 El 1995 5.65El 8.90E2 2.66E2 0.00E0 6.77E l I.38El 0.00E0 0.00E0 0.00E0 1996 0.00E0 5.95E l 6.68 E l 0.00E0 3.02 E l 0.00E0 0.00E0 0.00E0 0.00E0 1 1997 0.00E0 4.93 E l 9.88 E0 0.00E0 2.74E l 0.00E0 0.00E0 0.00E0 0.00E0 1998 0.00E0 6.44E l 2.86El 0.00E0 1.58El 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 = no detectable measurements l

l l

f l

I l

._,. m

3.9 SIlORELINE SEDIM ENT During 1998, a total of 20 shoreline sediment samples was analyzed, four from indicator location 210 and 12 from indicator location 208. Four control samples were analyzed from control location 215.

Co-58, Co-60, Cs-137, and Mn-54 were identified in samples collected from location 208, which is subdivided into three discharge canal areas (208-IS,208-2S and 208-3S).

These locations are closest to tin plant's liquid emuent release point. Naturally occurring K-40 was identified in many of the indicator and control locations.

The shoreline sediment location with the highest annual mean for all detectable radionuclides was location 208-lS. Cs-137 was identified at location 208-IS with an annual mean concentration of 71.1 pCi/kg. Other radionuclides identified during 1998 at shoreline sediment location 208-3S included Co-58 with an annual mean of 188 pCi/kg, Co-60 with an annual mean of 230 pCi/kg, and Mn-54 with an annual mean of 30.7 pCi/kg. Naturally occurring K-40 and Be-7 were also identified in samples from this location.

Sb-125 was detected during 1997 in one of four samples collected from location 208-IS.

The concentration observed was 176 pCi.kg. Sb-125 was not detected in any of the indicator or control samples during 1998.

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. Both radionuclides have been major contributors to the calculated dose from shoreline sediment since 1986.

l section 3 - Page 16 J

1 --

Figure 3.9-1 pcung Concentration of Co-58 in Shoreline Sediment 2000 1800 - - - - - - - -

1600 ---- -

1400 - - - - -

1200 - - - - --- - -

r---

1000 -f 800

/ \ i

( \ A 200

/

0: .

1984 1985 1986 1987 1968 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998

. _ _ _ _ . - _ . ._ _. _ - . _ ._ l There is no reporting levelfor Co-58 in Shoreline Sediment Figu re 3.9-2 pcuke Concentration of Co-60 in Shoreline Sedi nent 2000 1800 -- - - - -- --- - - - -

l - - - - - -- - - - - - -

1600 1400 ---- -

1200 i000 __.-

a 800 - - - - - - - - --- - - - - -- - -- -- - - - -

e00 _

400 -

1 200 - - - - - -- -- -

0: - 1 : !-- :---- ; --- . - :- : : :

1984 1985 1986 1987 1988 1969 1990 1991 1992 1993 1994 1995 1996 1997 1998

. -S-Indicator Locahon -+- Control Locahon 1 _ _ _ . _ _ _ .. _ . _ _ - _ - . _ _ _ ._

There is no reporting levelfor Co-60 in Shoreline Sediment

) Section 3 - Page 17 1 __-

Table 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment (pCi/ku)

Year Mn 54 Co-58 Co-60 Nb-95 Zr-95 Cs-134 Cs-137 Co-57 Sb-125 1984 1.03 E0 4.40E0 -2.34 E0 0.00E0 0.00E0 3.19E l 1.07E2 0.00E0 0.00E0 1985 -3.12 E0 1.16E2 5.18E0 0.00E0 0.00E0 2. l l E2 2.97E2 0.00E0 0.00E0 1986 1.09E2 3.79E2 2.05 E2 0.00E0 3.96E l 6.50E l I.61E2 0.00E0 0.00E0 1987 8.83El 4.08 E2 1.6tE2 4.22E l 0.00E0 6.08 E l 1.26E2 0.00E0 0.00E0 1988 1.07E2 3.29E2 2.63 E2 2.28 E l 7.54E0 2.59El 1.07E2 7.65 E-l 3.68E0 1989 4.58E l 1.94 E2 1.21E2 5.02E0 0.00E0 1.65E l 5.77E l 0.00E0 1.57E l 1990 5.39El 2.08E2 1.77E2 0.00E0 0.00E0 1.66E l 8.18 E l 0.00E0 7.15 E0 1991 8.50E l 3.70E2 4.19E2 5.30E0 0.00E0 1.82 E l 8.33 El 1.20E0 1.50 E l 1992 1.17E2 1.13 E3 5.80E2 3.50E0 0.00E0 1.69E l 1.07E2 3.00E0 2.70E l 1993 1.33 E2 1.07E3 1.04 E3 0.00E0 0.00E0 2.80E l 1.26E2 2.47E l 2.16E2 1994 4.93 E I 7.98 E2 5.73 E2 0.00E0 0.00E0 5.67E0 1.07E2 4.38 E0 4.60E l 1995 1.02 E2 1.33 E3 8.65 E2 1.13 E2 0.00E0 0.00E0 8.50E l 3.69E l I .49E2 1996 8.73 E l 3.39E2 5.8 l E2 0.00E0 0.00E0 0.00E0 8.30E l 0.00E0 1.96E2 1997 6.96El 5.90E2 7.64E2 0.00E0 0.00E0 0.00E0 1.43 E2 0.00E0 1.76E2 1998 3.07E l 1.88E2 2.30E2 0.00E0 0.00E0 0.00E0 7.l l E l 0.00E0 0.00E0 0.00E0 = no detectable measurements 1984 - 1986 mean based on all net activity Negative values are calculated as zeroes

) Secuon 3 - Page 18 3 _ - - - - - - _ -

3.10 IlOTTOM SEDIMENT Bottom sediment samples are not required as a collection media. Samples were first collected during 1985 from three points in the discharge canal (Location 208) following review of shoreline sediment and fish samples collected there. The three points were designated 208-lM, 208-2M and 208-3M (Figure 3.10-1). Bottom sediment control samples have never been collected.

The following radionuclides were identified in bottom sediment samples collected in 1998: Mn-54, Co-57, Co-58, Co-60, Sb-125, and Cs-137. The majority of samples collected contained these radionuclides, as have samples collected and analyzed since 1986.

Figure 3.10-1 Bottom Sediment Sampling Locations in CNS Discharge Canal

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> Section 3 Page 19 1 .

Table 3.10 shows bottom sediment sample annual mean concentrations for the three sample points at indicator Location 208 (CNS discharge canal) for the period 1986 through 1998. Overall detection frequencies were high and relatively stable throughout the period.

From 1986 through 1995, detectable concentrations for bottom sediment correlated well with activities released in liquid effluents. One exception has been Co-60 which has exhibited an increasing trend. Over the period of trending, indications show no significant environmental " removal" processes for Co-60. Considering expected cumulative and decay corrected activities from liquid effluents released since preoperation, one would have expected a decreasing accumulation of the radionuclide.

Figure 3.10-2 shows the major radionuclide contributors identified in bottom sediment from 1986 through 1998. Data shown is annual mean concentrations ofCo-58, Co-60, and Sb-125.

Effluent concentrations from liquid releases during 1998 correlate closely with annual mean concentrations of Co-58, Co-60, and Sb-125 detected in bottom sediment. The impact of plant operation on bottom sediment from location 208 was at an expected level when compared to liquid effluent release data for 1998.

l

) section 3 - Page 20

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Figure 3.10 2 pcukp Concentration of Radionuclides in Discharge Bottom Sediment 20000 16000 16000 14000 12000 10000 8000 -

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There are no reporting levelsfor Co-58. Co-60, andSb-125 Table 3.10 Mean Concentrations of Radionuclides in Bottom Sediment (pCi/ke)

Year M n-54 Co-58 Co-60 N b-95 Cs-134 Cs-137 Cr-51 Co-57 Sb-125 1986 3.60E2 1.09E3 9.64E2 6.99E l 1.71E2 3.48E2 0.00E0 0.00E0 0.00E0 1987 5.63 E2 1.34E3 2.18E3 6.99E l 1.10E2 4.03 E2 0.00E0 0.00E0 0.00E0 1988 5.78 E2 9.52 E2 3.18E3 1.78E l 1.23 E2 5.70E2 0.00E0 5.64E0 6.25 El 1989 3.98E2 4.47E2 3.42E3 4.49E0 1.05 E2 5.04E2 0.00E0 4.48E0 8. l l El 1990 3.81 E2 5.22E2 4.12E3 7.06E0 9.55 E l 5.06E2 0.00E0 4.56E0 2.15 E2 1991 4.15 E2 5.76E2 5.10E3 1.63 E l 8.13 E l 5.02 E2 7.53 E l 8.20E0 2.13 E2 1992 5.25E2 1.34E3 7.10E3 7.20E0 4.55 E l 4.94 E2 2.22 E l 1.97E l 4.33 E2 1993 3.72 E2 1.33 E3 5.79E3 0.00E0 7.66E l 5.38E2 0.00E0 1.58 E l I .33 E3 1994 2.77E2 1.25 E3 5.32 E3 0.00E0 0.00E0 4.27E2 0.00E0 1.72E l 5.98 E2 1995 1.82 E2 8.26E2 5.12E3 1.23 E l 6.00 E0 4. l l E2 0.00E0 1.48E l 5.68 E2 1996 1.90E2 4.05 E2 7.22E3 0.00E0 0.00E0 4.29E2 0.00E0 4.92 E0 6.95 E2 1997 1.76E2 427E2 6.49E3 4.06E l 0.00E0 3.85E2 0.00E0 0.00E0 6.92 E2 1998 l.76E2 3.86E 2 8.27E3 0.00E0 0.00E0 4.30E2 0.00E0 2.56E l 6.68E2 0.00E0 = no detectable measurements

)

Section 3 - Page 21

) _ ---- - - - - - -

3.11 DIRECT G AMM A RADI ATION In 1998,159 TLDs were analyzed,147 at indicator locations and 12 at control loctions.

TLDs are collected and analyzed quarterly. The highest annual mean exposure for an indicator location was 100.8 milliroentgen. The annual mean exposure for the control locations was 64.8 milliroentgen.

Figure 3.11 and Table 3.1I show TLD inner ring (site boundary), outer ring (4-5 miles),

and control location annual averages in milliroentgen per year. Preoperational data and twelve year averages are also given. As shown in the graph, inner and outer ring averages historically compare closely, with control data somewhat higher. 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 1998 was 7.31E-2 mrem, which is 0.09% 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.

I Figure 3.11 i

mR/ year Direct Gamma Radiation (TLD) Results 250.0 200 0 150.0 f

00

% 9p 1

p%p#%v 1 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998

-*--Inner Ring -5 Outer Ring + Control There is no reporting levelfor Direct Radiation (TLD) section 3 - Page 22 l

Table 3.11 I)irect Gamma Radiation (TI.1)) Results !

luner Ring Average Outer Ring Average Control Average Year (mlU) r) (mIUyr) _,

(mIUyr)

!984 87.5 82.6 79.3 1985 I I 6.9 108.7 108.9 1986 104.3 98.5 94.4 1987 97.0 87.4 84.7 1988 74.6 70.3 67.1 1989 67.I 60.8 60.0 1990 52.0 44.5 39.I I99i 62.0 54.I 46.7 l992 80.4 72.5 64.5 I993 70.3 60.9 53.6 I994 76.3 69.3 63.9 I995 99.6 89.7 80.8 1996 84.3 73.9 63.6 1997 82.4 71.9 57.4 Average (1985 - 1997) 82.1 74.0 68.1 1998 85.3 74.2 64.6

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3.12 LAND USE CENSUS The 1998 Annual Land Use Census was conducted July 20 - July 23,1998 as required by SLCs 16.11-14. Table 3.12 summarizes census results. Figure 3.12 contains a map showing identified locations. Sectors shown in Table 3.12 that have no values listed had no corresponding location identified in that sector.

Based upon 1998 Annual Land Use Census results for nearest residences and gardens, dose evaluations were performed to ensure current air and broadleaf vegetation sampling locations complied with requirements of SLCs. No changes to the locations were necessary. The evaluations showed that all existing air and broadleaf vegetation sampling locations complied with SLCs requirements. No changes or additions to the locations were required or made as a result of the 1998 census.

) section 3 - Page 24

)

). -

Table 3.12 Catawba 1998 Land Use Census llesults Sector Distance Sector Distance (Miles) (Miles)

Nearest Residence 0.64 Nearest Residence 0.83 N Nearest Garden 1.54 Nearest Garden 0.79 3

Nearest Milk Cow -

Nearest Beef Cow 4.87 Nearest Beef Cow 4.05 Nearest Goat -

Nearest Goat -

Nearest Residence 0.66 Nearest Residence 0.89 Nearest Garden 1.85 gggy Nearest Garden 0.96 NNE Nearest Milk Cow Nearest Milk Cow -

Nearest Beef Cow -

Nearest Beef Cow 3.04 Nearest Goat -

Nearest Goat -

Nearest Residence 0.60 Nearest Residence 0.65 NE Nearest Garden 0.66 ggy Nearest Garden 0.65 Nearest Milk Cow Nearest Milk Cow -

Nearest Beef Cow -

Nearest Beef Cow 2.59 Nearest Goat -

Nearest Goat 2.95 Nearest Residence 0.62 Nearest Residence 0.79 ENE Nearest Garden 0.60 gyggy Nearest Garden 2.04 Nearest Milk Cow Nearest Milk Cow -

Nearest Beef Cow 4.17 Nearest Beef Cow 2.87 Nearest Goat 1.27 Nearest Goat 2.69 Nearest Residence 0.65 Nearest Residence 0.96 Nearest Garden -

gy Nearest Garden 0.95 E

Nearest Milk Cow -

Nearest Beef Cow -

Nearest Goat -

Nearest Residence 0.84 Nearest Residence 1.10 ESE Nearest Garden 3.63 gyggy Nearest Garden 1.1 i Nearest Milk Cow Nearest Milk Cow -

Nearest Beef Cow -

Nearest Beef Cow 4.34 Nearest Goat -

Nearest Goat 3.63 Nearest Residence 0.99 Nearest Residence 1.31 SE Nearest Garden 1.52 ggy Nearest Garden 1.39 Nearest Milk Cow Nearest Milk Cow -

Nearest Beef Cow -

Nearest Beef Cow 2.30 Nearest Goat 4.05 Nearest Goat 1.44 Nearest Residence 0.62 Nearest Residence 1.06 SSE Nearest Garden 1.70 gggy Nearest Garden 2.19 Nearest Milk Cow Nearest Milk Cow -

Nearest Beef Cow -

Nearest Beef Cow 2.21 Nearest Goat 3.54 Nearrst Goat -

" " indicates no occurrences within the 5 mile radius

)

section 3 - Page 25

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4.0 EVALUATION OF DOSE 4.1 DOSE FRONI ENVIRONNIENTAL NIEASURENIENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 1998 CNS REMP samples. The primary purpose of estimating doses based on sample results was to allow comparison to effluent program dose estimates. Doses based on sample results were conservatively calculated in a manner as equivalent as possible to effluent-based 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.

REMP-based dose estimates were not reported for airborne radioiodine, airborne particulate, milk, or ground water sample types because no radionuclides other than naturally occurring K-40 and Be-7 were detected in the samples. Dose estimates were not reported for surface water or bottom sediment sample types because sampled surface water is not considered to be a potable drinking water source and sample bottom sediment is permanently submerged. Exposure estimates based upon REMP TLD results are discussed in Section 3.11.

The maximum dose to each organ from any single sample type other than direct radiation from gaseous effluents was determined and reported in Table 4.1-B. The maximum organ dose estimate for any single sample type (other than direct radiation from gaseous effluents) collected during 1998 was 0.555 mrem to the maximum exposed child's bone from consuming broadleaf vegetation.

4.2 ESTINIATED DOSE FRONI RELEASES Throughout the year, dose estimates were calculated based on actual 1998 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 1998 CNS Annual Radioactive Effluent Release J

Section 4 Page !

J 3 --

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.

The effluent-based liquid release doses are summations of the dose contributions from the drinking water and tish pathways. Shoreline sediment dose was not required to be calculated per the ODCM. The efnuent-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 and vegetation pathways.

4.3 COMPARISON OF DOSES The environmental and release data doses given in Table 4.1-A agree reasonably well. The similarity of the doses indicate that the radioactivity levels in the environment do not differ significantly from those expected based on efnuent measurements and modeling of the environmental exposure pathways. This indicates that efnuent program dose estimates are both valid and reasonably conservative.

In calculations based on liquid release pathways, fish and drinking water consumption were the predominant dose pathways based on environmental and .

efnuent samples. The maximum total organ doce based on 1998 environmental l sample results was 5.44E-2 mrem to the child's liver. The maximum total organ dose of 1.77E-1 mrem for liquid effluent-based estimates was to the adult GI-LLI.

For all organs, liquid effluent doses were higher than REMP data doses.

In calculations based on gaseous release pathways, goat milk was the predominant dose pathway for effluent samples. The maximum total organ dose for gaseous efnuent estimates was 1.60E0 mrem to the infant'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 5.55E-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

TAllLE 4.1-A Page 1 of 3 CATAWIlA NUCLEAR STATION 1998 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIOUID RELEASE PATHWAY Environmental or Critical Critical Maximum Dose *

'""" Effluent Data Age Pathway (mrem)

Skin Environmental Teen Shoreline Sediment 208 (0.5 mi S) 3.59E-03 Skin Effluent - -

1.0 mi ENE Not Calculated Bone Environmental Teen Fish 208 (0.5 mi S) 1.15E-02 Bone Eftluent Child Fish 1.0 mi ENE 8.24E-02 Liver Environmental Child Drinking Water 214 (7.3 mi SE) 5.44E-02 Liver Effluent Adult Fish 1.0 mi ENE 1.44E-01 T. Body Environmental Adult Fish 208 (0.5 mi S) 5.06E-02 T. Body Effluent Adult Fish 1.0 mi ENE 1.16E-01 Thyroid Environmental Child Drinking Water 214 (7.3 mi SE) 4.25 E-02

, Thyroid Effluent Adult Fish 1.0 mi ENE 4.64E-02

' Kidney Environmental Child Drinking Water 214 (7.3 mi SE) 4.57E-02

' Kidney Effluent Adult Fish 1.0 mi ENE 7.88E-02 i

, Lung Environmental Child Drinking Water 214 (7.3 mi SE) 4.37E-02 Lung Efiluent Adult Fish 1.0 mi ENE 5.71 E-02 h GI-LLI Environmental Adult Fish 208 (0.5 mi S) 8.33 E-02 ll GI-LLI Effluent Adult Fish 1.0 mi ENE 1.77E-01 h

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

)

section 4 Page 3

)

l

Page 2 of 3 GASEOUS RELEASE PATHWAY l IODINE, PAllTICULATE, and TitITIUM Organ Location Effluent Data Age Pathway (mrem)

Skin Environmental . - - -

0.00E+00 Skin Effluent All Ground / Plane 1.0 mi ENE 5.05E-06 Bone Environmental Child Vegetation 201 (0.5 mi NE) 5.55 E-01 Bone Effluent All Ground / Plane 1.0 mi ENE 4.31 E-06 Liver Environmental Child Vegetation 201 (0.5 mi NE) 5.31 E-01 Liver Ellluent Infant Goat Milk 1.0 mi ENE 1.60E+00 1

T. Body Environmental Adult Vegetation 201 (0.5 mi NE) 2.98E-01

T. Body Efiluent Infant Goat Milk 1.0 mi ENE 1.60E+00

Thyroid Environmental - - -

0.00E+00

Thyroid Et11uent Infant Goat Milk 1.0 mi ENE 1.60E+00

' Kidney Environmental Child Vegetation 201 (0.5 mi NE) 1.73 E-01 Kidney Effluent Infant Goat Milk 1.0 mi ENE l.60E+00 Lung Environmental Child Vegetation 201 (0.5 mi NE) 6.23 E-02 Lung Effluent Infant Goat Milk 1.0 mi ENE 1.60E+00 GI-LLI Environmental Adult -

Vegetation 201 (0.5 mi NE) 8.82E-03 GI-LLI Effluent Infant Goat Milk 1.0 mi ENE 1.60E+00 l

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

Section 4. Page 4

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

5.2 SANIPLE ANALYSIS EnRad Laboratories performed the .

environmental sample analyses as specified g by approved analysis procedures. En. Rad Laboratories is located in lluntersville, N % -

North Carolina, at Duke Power Company's : -

> "U Environmental Center.

F g s-~;

. 2 m 5.3 DOSIN1ETRY ANALYSIS ouke 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 EOUIPNIENT OUALITY ASSURANCE 5.4.1 DAILY OUALITY CONTROL EnRad Laboratories has an internal quality assurance program which monitors each type ofinstrumentation 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 CAllBRATION 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 1 J

J _ - - - - -

5.4.3 BATCH PROCESSING ,

Method spike and blank samples are analyzed with sample analyses that are processed in batches. These include gross beta in drinking water and all tritium analyses.

5.5 ENVIRONMENTAL PROTECTION AGENCY INTERCOMPARISON PROGRAM l

EnRad Laboratories participated in the Environmental Protection Agency (EPA) ,

cross check program during 1998. Results of these cross-checks are displayed in l Table 5.0-A.

l 5.6 DUKE POWER INTERCOMPARISON PROGRAM EnRad Laboratories participated in the Duke Power Nuclear Generation Department Intercomparison Program during 1998. 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 1998 is documented in Table 5.0-B.

5.7 DUKE POWER AUDITS 5.7.1 RADI ATION PROTECTION SECTION The Catawba Nuclear Station Radiation Protection Section participated in a Duke Power Quality Assurance audit in 1997. This audit is performed biannually; therefore, no audit was conducted in 1998.

5.7.2 ENRAD LABORATORIES EnRad Laboratories participated in a Duke Power Quality Assurance audit in February 1997. This audit is performed biannually; therefore, no audit was conducted in 1998.

5.8 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The Catawba Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in December 1998. There were no findings from this audit.

EnRad Laboratories was not audited by the NRC in 1998.

Section 5 Page 2 l l

l m.

5.9 STATE OF NORTII CAROLINA INTERCOMPARISON PROGRAM 5.9.1 ENVIRONMENTAL SAMPl ES EnRad Laboratories routinely participates with the Bureau of Radiological Health of the State's Department of Health and Environmental Control (DHEC) in an intercomparison program. EnRad Laboratories sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the State of South Carolina DHEC Laboratory for intercomparison analysis.

5.9.2 TLD 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 1998 is documented in Table 5.0-C.

l l

6

} section 5 - Page 3 J

) - - - - - -

TABLE 5.0-A U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLA13 ORATORY COMPARISON PROGRAM 1998 CROSS-CIIECK RESULTS FOR ENRAD LAllORATORIES 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.

Gamma in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 4/21/98 Blind B Co-60 4.13 El 5.87 El 5.00 El 5.14 El 3 Pass Cs- 134 1.33 El - 3.07 El 2.20 El 2.15 El 3 Pass Cs-137 1.30 EO - 1.87 El 1.00 El 1.07 El 3 Pass 6/5/98 Mixed Co-60 3.30 EO 2.07 El 1.20 El 1.43 E l 3 Pass Gamma Zn-65 8.67 El 1.21 E2 1.04 E2 1.06 E2 3 Pass Cs-134 2.23 El - 3.97 El 3.10 El 2.93 El 3 Pass Cs-137 2.63 El - 4.37 El 3.50 El 3.46 El 3 Pass Ba-133 3.13 El - 4.87 El 4.00 El 4.08 El 3 Pass 10/20/98 Blind B Co-60 1.23 El - 2.97 El 2.10 El 2.30 El 3 Pass Cs-l 34 0.00 EO - 1.47 El 6.00 EO 6.17 EO 3 Pass Cs- 137 4.13 El 5.87 El 5.00 E l 4.72 El 3 Pass i1/6/98 Mixed Co-60 2.93 El - 4.67 El 3.80 El 3.88 El 3 Pass Gamma Zn-65 1.08 E2 - 1.53 E2 1.31 E2 1.46 E2 3 Pass Cs- 134 9.63 El - 1.14 E2 1.05 E2 9.96 El 3 Pass Cs- 137 1.01 E2 - 1.21 E2 1.11 E2 1.13 E2 3 Pass Ba-133 4.56 El - 6.64 El 5.60 El 5.71 El 3 Pass Beta in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCill pCi/l I/30/98 N/A BEIA 0.00 EO - 1.26 El 3.90 El 7.33 EO 3 Pass 10/20/98 l Blind B l BETA l 7.67 El - 1.1l E2 l 9.40 El l 7.22 E2 l 3/3 High "'

l I/13/98 l N/A l 13 E l'A l 0.00 EU - 1.22 El } 3.50 EO l 3.87 EU l 3 Pass (l) Failmg results most hkely due to prepration error associated with the mitial cross-check sample dilution. Results could not be reproduced during the subsequent investigation 2 Section 5 Page 4

) __ - - - - - - - -

l Tritium in Water Reterence Sample 1.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCill 3/13/98 N/A H-3 1.55 E3 - 2.76 E3 2.16 E3 2.24 E3 3 Pass 8/7/98 l N/A l H' ,1 ; 1.49 E4 2.11 E4 l 1.80 E4 l 1.66 E4 } 3 Pass l

lodinein Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status

! pCi/l pCi/l pCi/l 2/6/98 N/A l 131 8.67 El - 1.23 E2 1.05 E2 1.13 E2 3 Pass l 9/l1/98 l N/A l l-131 l 2.60 EO - 9.6 E0 l 6.10 E0 l 8.05 E0 l 3 Pass "'

l I

l (2) This sample was not reported to EPA by the required due date so u was not mcluded in the EPA summary report.

l l

l Section 5. Page 5

TABLE 5.0-B DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 1998 CROSS-CllECK 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.

Gammain Water 3.5 liters Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/2/98 Q981GWS Cr-51 4.03 - 7.14 E4 5.37 E4 5.26 E4 3 Pass Mn-54 2.12 - 3.77 E4 2.83 E4 2.80 E4 3 Pass Fe-59 1.73 - 3.07 E4 2.31 E4 2.35 E4 3 Pass Co-60 1.34 - 2.37 E4 1.78 E4 1.72 E4 3 Pass Zn-65 2.28 - 4.04 E4 3.04 E4 3.03 E4 3 Pass Cs- 134 1.32 - 2.34 E4 1.76 E4 1.63 E4 3 Pass Cs 137 2.51 - 4 45 E4 3.34 E4 3.16 E4 3 Pass Ce-141 1.35 - 2.40 E4 l.80 E4 1.79 E4 3 Pass 5/26/98 Q9820WR Mn-54 1.98 - 3.50 E2 2.64 E2 2.95 E2 3 Pass Fe-59 0.35 1.39 E2 6.92 El 9.64 E l 3 Pass l Co-60 1.46 - 2.58 E2 1.94 E2 2.10 E2 3 Pass Zn-65 2.01 - 3.57 E2 2.68 E2 2.98 E2 3 Pass Cs-134 1.37 2.44 E2 1.83 E2 1.98 E2 3 Pass l Cs-137 2.80 - 4.97 E2 3.74 E2 3.95 E2 3 Pass Ce-141 2.48 - 4.40 El 3.31 El 0.00 El 3/3 Low 8/19/98 Q9830W IL Cr-51 4.83 - 8.56 E4 6.43 E4 6.54 E4 3 Pass Mn 54 0.85 - 1.50 E4 1.13 E4 1.18 E4 3 Pass Fe-59 1.16 2.05 E4 1.54 E4 1.62 E4 3 Pass Co-60 1.58 - 2.81 E4 2.11 E4 2.13 E4 3 Pass Zn-65 2.27 - 4.03 E4 3.03 E4 3.2 I E4 3 Pass Cs 134 0.89 1.57 E4 1.18 E4 1.10 E4 3 Pass Cs-137 1.41 - 2.50 E4 1.88 E4 1.80 E4 3 Pass Ce-141 3.30 - 5.85 E4 4.40 E4 4.43 E4 3 Pass 12/7/9M Q9840WR Cr-51 0.67 - 1.18 E3 8.86 E2 1.04 E3 3 Pass Mn-54 1.43 - 2.54 E3 1.91 E3 1.97 E3 3 Pass Fe-59 4.52 - 8.02 E2 6.03 E2 6.67 E2 3 Pass Co-60 3.28 - 5.82 E3 4.38 E3 4.45 E3 3 Pass Zn-65 3 60 - 6.38 E3 4.80 E3 4.98 E3 3 Pass Cs- 134 1.73 - 3.06 E3 2.30 E3 2.18 E3 3 Pass Cs-137 3.03 - 5.37 E3 4.04 E3 3.90 E3 3 Pass Cc-14 l 0.68 - 1.21 E3 9.10 E2 9.17 E2 3 Pass Section 3 Page 6

1 l

Gamma in Water 1.0 liter '

Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check l

Date Range Value Value Status )

pCi/l pCi/l pCill 3/2/98 Q981GWS Cr-51 4.03 - 7.14 E4 5.37 E4 5.08 E4 3 Pass Mn-54 2. l2 - 3.77 E4 2.83 E4 2.81 E4 3 Pass Fe-59 1.73 - 3.07 E4 2.31 E4 2.38 E4 3 Pass Co-60 1.34 2.37 E4 l.78 E4 1.73 E4 3 Pass 2n-65 2.28 - 4.04 E4 3.04 E4 3.13 E4 3 Pass Cs134 l.32 - 2.34 E4 1.76 E4 1.58 E4 3 Pass Cs-137 2.51 - 4.45 E4 3.34 E4 3.15 E4 3 Pass Cc-141 1.35 - 2.40 E4 l.80 E4 1.75 E4 3 Pass 8/19/98 Q9830W I L Cr-S i 4.83 - 8.56 E4 6.43 E4 6.54 E4 3 Pass Mn-54 0.85 - 1.50 E4 1.13 E4 1.19 E4 3 Pass l Fe-59 1.16 2.05 E4 1.54 E4 1.68 E4 3 Pass Co-60 1.58 - 2.81 E4 2. l l E4 2.15 E4 3 Pass Zn 65 2.27 - 4.03 E4 3.03 E4 3 23 S4 3 Pass Cs- 134 0.89 1.57 E4 1.18 E4 1.11 E4 3 Pass Cs 137 1.41 - 2.50 E4 1.88 E4 1.82 E4 3 Pass Ce-141 3.30 - 5.85 E4 4.40 E4 4.46 E4 3 Pass 12/7/98 Q9840WR Cr 51 0.67 - 1.18 E3 8.86 E2 9.70 E2 3 Pass Mn-54 1.43 - 2.54 E3 1.91 E3 1.94 E3 3 Pass Fe-59 4.52 - 8.02 E2 6.03 E2 6.36 E2 3 Pass Co-60 3.28 - 5.82 E3 4.38 E3 4.34 E3 3 Pass Zn-65 3.60 - 6.38 E3 4.80 E3 4.96 E3 3 Pass Cs-134 1.73 - 3.06 E3 2.30 E3 2.12 E3 3 Pass Cs-137 3.03 - 5.37 E3 4.04 E3 3.80 E3 3 Pass Ce-141 0.68 1.21 E3 9.10 E2 8.83 E2 3 Pass i

i l

Gamma in Water 0.5 liter l Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/2/98 Q981GWS Cr 51 4.03 7.14 E4 5.37 E4 5.07 E4 3 Pass )

Mn 54 2.12 - 3.77 E4 2.83 E4 2.84 E4 3 Pass Fe-59 1.73 - 3.07 E4 2.31 E4 2.39 E4 3 Pass Co-60 1.34 2.37 E4 1.78 E4 1.73 E4 3 Pass Zn-65 2.28 - 4.04 E4 3.04 E4 3.12 E4 3 Pass Cs-134 1.32 - 2.34 E4 1.76 E4 1.54 E4 3 Pass Cs-137 2.51 - 4.45 E4 3.34 E4 3.13 E4 3 Pass Ce 141 1.35 - 2.40 E4 1.80 E4 1.73 E4 3 Pass 8/19/98 Q983GW I L Cr 51 4 83 - 8.56 E4 6.43 E4 6.54 E4 3 Pass Mn-54 0.85 - 1.50 E4 1.13 E4 1.19 E4 3 Pass Fe-59 1.16 - 2.05 E4 1.54 E4 1.68 E4 3 Pass Co-60 1.58 2.81 E4 2.11 E4 2.15 E4 3 Pass Zn 65 2.27 4.03 E4 3.03 E4 3.23 E4 3 Pass Cs-134 0.89 - l.57 E4 1.18 E4 1. l l E4 3 Pass Cs-137 1.41 - 2.50 E4 1.88 E4 1.82 E4 3 Pass Cc-141 3.30 - 5.85 E4 4.40 E4 4.46 E4 3 Pass Secuan 5 Page 7

Gamma in Water 0,5 liter continued 12/7/98 Q9840WR Cr-S i 0.67 1.18 E3 8.86 E2 1.06 E3 3 Pass Mn 54 1.43 - 2.54 E3 1.91 E3 2.06 E3 3 Pass Fe 59 4.52 - 8.02 E2 6.03 E2 6.66 E2 3 Pass Co-60 3.28 - 5.82 E3 4.38 E3 4.47 E3 3 Pass Zn-65 3.60 - 6.38 E3 4.80 E3 5.26 E3 3 Pass Cs-134 1.73 - 3.06 E3 2.30 E3 2.08 E3 3 Pass Cs-137 3.03 - 5.37 E3 4.04 E3 3.81 E3 3 Pass Cc-141 0,68 - 1.21 E3 9.10 E2 9.25 E2 3 Pass Gamma in Filter Reference Sample 1.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/ total pCi/ total pCi/ total 2/20/98 A10347 Cr-51 4.72 - 8.37 E4 6 29 E4 6.55 E4 3 Pass Mn-54 1.98 - 3.5 I E4 2.64 E4 2.91 E4 3 Pass Fe-59 1.85 - 3.27 E4 2.46 E4 2.84 E4 3 Pass Co-60 1.22 2.17 E4 1.63 E4 1.72 E4 3 Pass 2n-65 2.15 - 3.80 E4 2.86 E4 3.29 E4 3 Pass ,

Cs- 134 1.22 - 2.15 E4 1.62 E4 1.47 E4 3 Pass Cs 137 2.30 - 4.07 E4 3.06 E4 3.10 E4 3 Pass Cc-141 1.52 2.70 E4 2.03 E4 2.20 E4 3 Pass 6/11/98 E 1443-37 Cr-51 0.96 1.70 E2 1.28 E2 1.42 E2 3 Pass Mn-54 0.77 1.37 E2 1.03 E2 1.18 E2 3 Pass

'l Fe-59 3.30 - 5.85 E l 4.40 El 5.42 El 3 Pass Co-60 1.05 1.86 E2 1.40 E2 1.53 E2 3 Pass Zn 65 0.89 - 1.58 E2 1.19 E2 1.47 E2 3 Pass Cs-134 0.69 - 1.22 E2 9.20 El 8.02 El 3 Pass l Cs-137 5.18 - 9.18 E l 6.90 E l 7.14 El 3 Pass Ce-141 0.73 - 1.29 E2 9.70 El 1.03 E2 3 Pass 12/10/98 E-162137 Cr-51 3.90 6.92 E2 5.20 E2 5.44 E2 3 Pass Mn-54 0.57 1.01 E2 7.60 El 9.05 El 3 Pass Fe-59 0.59 - 1.05 E2 7.90 El 9.53 El I/3 High Co-60 0.71 1.26 E2 9.50 El 1.04 E2 3 Pass 2n-65 5 55 9.84 El 7.40 El 9.86 El 1/3 liigh Cs 134 0.88 - 1.56 E2 1.17 E2 1.03 E2 3 Pass Cs-137 0.73 - 1.29 E2 9 70 El 1.03 E2 3 Pass Ce-141 2.97 - 5.27 E2 3.96 El 4.40 E2 3 Pass Sechon 5 Page 8 f

lodine in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/2/98 098 i L1W-I l-131 5.50 - 9.75 EI 7.33 El 9.06 E I I Pass 3/2/98 l 098tLlW 2 l l 131 l 0.00 - 0.00 EO l 0.00 EU l 0.00 Eu l l Pass 3/2/98 l 0981LlW-3 l l 131 l 0.98 - 1.73 E l l 1.30 El l 1.78 El l l/l High 8/19/98 l 0983LlWI l i-131 l 4.06 - 7.19 E l l 5.41 E l l 5.68 El l l Pass 8/19e98 l Q983LlW2 l l-131 l 0.84 - 1.49 El l 1.12 El l 1.09 El l t Pass 8/19/98 l 0983LlW3 l l-131 l 2.40 - 4.26 El l 3.20 El l 3.10 El l l Pass lodinein hfilk Refereoce Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 5/26/98 0982LIMI l 131 5.22 - 9.25 E l 6.96 E l 6.44 El 3 Pass 5/26/98 l Q982 LIM 2 l i 131 l 2.80 - 4.97 E l l 3.74 El l 3.49 El l 3 Pass 5/26/98 l 0982 LIM 3 l l 131 l 0.00 - 0.00 E0 l 0.00 EO l 0.00 E0 l 3 Pass lodine Cartridge Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi pCi pCi 2/20/98 A 10348-04 1 131 2.25 3.99 E5 3.00 ES 3.04 ES 3 Pass 6/11/98 l E 1444-37 l l-131 l 4.65 - 8.25 El l 6.20 E l l 6.69 El l 3 Pass 8/l4/98 l A 11038-04 l l 131 l 1.47 - 2.61 E5 l 1.96 E5 l 2.10 E5 l 3 Pass 12/10/98 ) El622 37 l l-131 l 0.60 - 1.06 E2 l 8.00 E l l 8.30 El l 3 Pass Beta in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status pCi/l pCi/l pCi/l 3/12/98 E 1334-47 Beta 2.02 - 3.58 E2 2.69 E2 2.47 E2 3 Pass 9/24/98 l E l 547-37 l Beta l I.49 - 2.63 E2 l 1.98 E2 l 2.07 E2 l 3 Pass Secuon 5 - Page 9

)

) - _

I.

)

) Beta Smear Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status

) pCi/ total pCi/ total pCi/ total 2/20/98 A IO351-04 Beta 2.94 - 5.23 E3 3.92 E3 4.51 E4 3 Pass f

)

2/20/98 l A lu352-04 l Beta l 3.30 - 5.85 E3 l 4.40 E3 l 4.22 E3 l 3 Pass

)

) Beta Smear Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check Date Range Value Value Status uCi/ total uCi/ total uCi/ total

)

8/14/98 A l l041-04 Beta 4.92 - 8.72 E-3 6.56 E-3 6.05 E-3 3 Pass

)

8/ l4/98 l A i 1042 04 l Beta l 0.60 1.06 E-2 l 7.93 E 3 l 6.87 E-3 l 3 Pass

) 8/14/98 l A i 1044-37 l Beta l 5.12 - 9.08 E-3 l 6.83 E 3 l 5.84 E-3 l 3 Pass

)

) Tritium in Water Reference Sample I.D. Nuclide Acceptance Reference Mean Reported Cross Check

) Date Range Value Value Status

) pCVI pCi/l pCi/l 3/2/98 098IlWS 2 H-3 1.04 1.85 E4 1.39 E4 1.59 E4 Pass J/2/98 l 098 t l W S 3 l H-3 l 0.00 - 0.00 EO l 0.00 E0 l 0.00 EO j 3 Pass

)

) 5/26/98 l 09821W R2 l H-3 l 0.81 1.43 E3 } l.08 E3 l 0.94 E3 l 3 Pass

) $/20/98 l U9821'WR3 l H-3 l 2.51 - 4.45 E3 l 3.35 E3 l 3.05 E3 l 3 Pass

)

, 8/19/98 l 09831 WR I l H-3 } 2.85 5.05 E3 l 3.80 E3 l 3.36 E3 l 1 Pass f

)

8/19/98 l 09831'W R2 l H-3 { l.41 2.50 E3 l 1.88 E3 l 1.76 E3 l l Pass

) 8/19/98 l 0983iWR3 l H3 l 0.00 - 0.00 E0 1 0.00 EU l 0.00 Eu l t Pass

) 12/7/98 l 09841 WR 1 l H-3 l 3.91 - 6.94 E3 l 5.22 E3 l 5.55 li3 l 3 Pass .;

) l l

i

) l f

1 Section 5 Page 10 i \

TABLE 5.0-C STATE OF NORTII CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES 1998 ENVIRONMENTAL DOSIMTER CROSS-CIIECK RESULTS State of Acceptance Cross-Check North Carolina Radiation Dosimetry & Records Criteria Date Delivered Value Reported Value (mR) (mR) +/- 10%

June 1998 6.00 E l 5.64 El -5.93 December 1998 l 6.00 El l 5.71 El l -4.82 l

I l

Section 5 - Page l I

Y l

6.0 REFERENCES

6.1 Catawba Selected License Commitments 6.2 Catawba Technical Specifications l

l 1

6.3 Catawba Updated Final Safety Analysis Review 6.4 Catawba Offsite Dose Calculation Manual 6.5 Catawba Annual Environmental Operating Report 1985 - 1997 6.6 Catawba Annual Effluent Report 1985 - 1998 6.7 Probability and Statistics in Engineering and Management Science, Hines and Montgomery,1969, pages 287-293.

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

6.9 Nuclear Regulatory Commission Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10CFR50, Appendix 1.

6.10 Radiological and Environmental Services Operating Procedures 6.11 RETDAS, Radiological Effluent Tracking and Dose Assessment Software, Vertechs Version 3.4.1, Duke Power Revision # 2.0 section 6 - Page i

muum pai m APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PROCEDURES J

Appendix A - Page 1 J

l _ - _ - - - - - -

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.

1. CIIANGE OF SAMPl>ING PROCEDURES No sampling changes were made to the sampling procedure during 1998.

11. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software. Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy. Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry. 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 an ion exchange resin to remove and concentrate any iodine in the aqueous sample (milk). The resin is then dried and transferred to appropriate counting geometry and analyzed by gamma spectroscopy.

Tritium analyses are performed quarterly by using low-level environmental liquid scintillation analysis technique on a Packard 2550 liquid scintillation system. 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

)

J

} Appendix A - Page 2 1 -

processed with a spike sample to verify instrument performance and a blank to ensure sample contamination has not occurred.

III. CHANGE OF ANALYSIS PROCEDURES No analysis procedures were changed during 1998.

IV. SAMPLING AND ANALYSIS PROCEDURES A.1 AIRilORNE PARTICUI. ATE AND RADIOIODINE Airborne particulate and radioiodine samples at each of five locations were composited continuously by means of continuous air samplers. Air particulates were collected on a particulate filter and radioiodines were collected in a charcoal cartridge situated 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 weekly gross beta analysis was performed on each filter and a weekly gamma analysis was performed on each charcoal cartridge. Filters were segregated by location and a quarterly gamma analysis was performed on the filter composite. The filter and charcoal cartridge were analyzed independently. The continuous composite samples were collected from the locations listed below.

Location 200 =

Site Boundary (0.6 mi. NNE)

Location 201 =

Site Boundary (0.5 mi. NE)

Location 205 = Site Boundary (0.3 mi. SW)

Location 212 =

Tega Cay, SC (3.3 mi. E)

Location 217 =

Rock Hill Substation (10.3 mi. SSE)

A.2 DRINKING WATER Biweekly composite drinking water samples were collected at each of two locations. A low-level Iodine-131 analysis was performed on each biweekly composite sample. 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 (7.3 mi. SE)

Location 218 =

Belmont Water Supply (13.4 mi. NNE)

)

) Appendix A - Page 3 Y .- - - -

1

4.3 SUltFACE WATEll Biweekly composite samples were collected at each of three locations. A gamma analysis was performed on the monthly composites. Tritium analysis wm peSormed on the quarterly composites. The composites were collected biweekly from the locations listed below.

L,ocation 208 = Discharge Canal (0.5 mi. S)

Location 211 = Wylie Dam (4.0 mi. ESE)

Location 215 = River Pointe - mvy 49 (4.2 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 =

Residence (0.7 mi. SW)

Location 254 =

Residence (0.8 mi. N)

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

Location 209 =

Weod Dairy - (6.0 mi. SSW)

Location 219 =

Pursley Dairy - (5.7 mi. SW)

Location 221 =

Oates Dairy -(14.5 mi. NW)

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

Location 200 =

Site Boundary (0.6 mi. NNE)

Location 201 =

Site Boundary (0.5 mi. NE)

Location 217 =

Rock Hill Substation (10.3 mi. SSE)

Location 222 =

Site Boundary (0.7 mi N)

Location 226 = Site Boundary (0.5 mi. S)

)

) Appenda A - Page 4 1 _ - - _ - - _ _

I.

A.7 FOOD PROI)UCTS 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 = Cloninger Irrigated Garden (2.1 mi. SSE)

A.8 FISil 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 (0.5 mi. S)

Location 216 = Hwy 49 Bridge (4.0 mi. NNE)

A.9 SIIOREI INE SEI)IMENT Semiannual samples were collected at each of three locations. A gamma analysis was perfonned 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 (0.5 mi. S)

Location 210 =

Ebenezer Access (2.3 mi. SE)

Location 215 = River Pointe - Hwy 49 (4.2 mi. NNE)

A.10 IlOTTOM SEDIMENT Quarterly samples were collected at each of three locations. A gamma analysis was performed on each sample following the druning and removal of rocks and clams. The samples were collected from the locations listed below.

Location 208-1M = Closest to RL Discharge Location 208-2M = Approximate midpoint of Discharge Canal Location 208-3M = Site 208 Surface Water sampling pier vicinity A.11 DIRECT G AMM A R ADI ATION (TLD)

Thermoluminescent dosimeters (TLD) were collected quarterly at forty locations. A gamma exposure rate was determined for each TLD. The TLDs j were placed as indicated below.

Appendix A - Page 5

_J

An inner ring of16 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.

TLD locations are listed in Table 2.1-A.

A.12 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.)

This census was initiated on July 20,1998 and completed on July 23,1998.

. Results are shown in Table 3.12.

V. PROGRAM IMPROVEMENTS Trending of air sampler and water sampler site locations is performed for continuous identification of problems impacting deviation rate of the Radiological Environmental Monitoring Program. A continued program of preventive maintenance, improved equipment quality and trending have proven to be extremely beneficial.

l

) Appendix A Page 6

) .

i = , in. .

gi .

APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

OF RESULTS 1998 l

l u,.uix o . r... i

Environmental Radiological Monitoring Program Summary Fccility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-J AN-1998 to 31-DEC-1998 Type and "~

Medium or Lower Location with liighest I ^ " ' " '" ' "**

Pathway Limit of Annual Mean "5' Location Report Sampled Detection Name, Distance, Direction of Meas.

Unit of Analyses "" '" " " " "" "} "" "}

Measurement Performed (LLD) Range Code Range Range Air Particulate 217 (pCi/m3) (10.3 mi SSE)

BETA 259 1.00E-02 2.48E-2 (207/207) 212 2.69E-2 (52/52) 2.12E-2 (52/52) 0 1.77E 7.1 I E-2 (3.3 mi E) 1.77E 7.1 l E-2 8.99E 4.03 E-2 CS-134 20 5.00E-02 0.00 (0/16) 0.00 (0/4) 0.00 (0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 20 6.00E-02 0.00 (0/16) 0.00(0/4) 0.00(0/4) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 l-131 20 7.00E-02 0.00 (0/16) 0.00 (0/4) 0.00(0/4) 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 @ 3/19/99 9.13 AM Appendix B - Page 2 D

1 . _ -_--

l Environmental Radiological Monitoring Program Stimmary Freility: Catawba Nuclear Station Docket No. 50-413,414 Locztion: York County, South Carolina Report Period: 01-JAN 1998 to 31-DEC-1998

"" "~

Medium or Lower Location with Highest

"' ^ " " '" I nq l ut:ne Pathway Limit of Annual Mean

"* ' "" "' Location Report Sampled Detection Name, Distance, Direction of Meas.

Unit of Analyses (LLD)

"" I ' ' ") '" " **" ( "** ") #"I "'I "I Measurement Performed Range Code Range Range Air Radiciodine 217 (pCi/m3) (10.3 mi SSE)

CS-134 259, 5.00E-02 0.00 (0/207) , _ . _ _

0.00 (0/52) 0.00 (0/52] _

0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 CS 137 259 6.00E-02 9.22E-3 (3/207) 200 1.24 E-2 (2/52) 0.00 (0/52) 0 7.37E 1.24E-2 (0.6 mi NNE) 1.24E 1.24E 2 0.00 - 0.00 1 131 259 7.00E-02 0.00(0/207) 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 @ 3/19/99 9.12 AM d Appendix B Page 3 1 _ _ _ - - - - -

I Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-1998 to 31-DEC-1998 Medium or Type and Total Lower Location with Highest Pathway Number Limit of

^" #"' ' nk I utme Annual Mean can ns L cation Report Sampled of Detection Name, Distance, Direction Meas.

Unit of Analyses ##" *# "} #" " ##" ( "" "} #" "# "}

Measurement Performed (LLD) Range Code Range Range Drinking Water 218 (pCi/ liter) (13.4 mi NNE)

BALA-140 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 0.00 0.00 0.00 0.00 - 0.00 BETA 26 4 2.51 (13/13) 214 2.51 (13/13) 2.44 (13/13) 0 l.22 3.83 (7.3 mi SE) 1.22 - 3.83 0.91 - 3.89 CO-58 26 15 0.00 (0/13) 0.00 (0/13) 0.00(0/l3) _ 0 0.00 - 0.00 0.00 0.00 0.00 - 0.00 CO-60 26 15 0.00 (0/I3) 0.00 (0/I3) 0.00 (0/I3) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 26 15 0.00 (0/l3) 0.00 (0/I3) 0.00 (0/13) 0 0 -

. - . . - ~

0

0

0.00 - 0.00 0.00 0.00 0.00 - 0.00 FE-59 26 30 0.00(0/l3) 0.00 (0/13) 0.00 (0/13) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 Il 3 8 2000 507(3/4) 214 507(3/4) I83 (2/4) 0 331-68l (7.3 mi SE) 331 681 159 - 208 l-131 26 15 0.00 (0/I3) 0.00 (0/13) 0.00(0/I3) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 26 15 0.00 (0/13) 0.00 (0/13) 0 00 (0/13) 0 0.00 - 0.00 0.00 0.00 0.00 - 0.00 NB 95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 0.00 ZN-65 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 '

ZR 95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/l3) 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 ReportGenerated @ 3/19/99 912 AM Appendix B - Page 4

) _ _ - _ - _

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-1998 to 31-DEC-1998 Medium or Type and Total Lower No. of Non-

" "* E #8 All Indicator Control Routine Pathway Numbe- Limit of . Annual Mean .

Sampled of Detection Name, Distance, Direction L cation Report Meas.

Unit of Analyses " " " # " #" ## " "" "# "}

Measurement Performed (LLD) Range Code Range Range Drinking Water 218 (pCi/ liter) (13.4 mi NNE)

BALA.I 40 26 15 0.00 (0/13) 0.00 (0/I3) 0.00 (0/13) 0 0.00 0.00 0.00 0.00 0.00 - 0.00 BETA 26 4 2.51 (13/13) 214 2.51 (13/13) 2.44 (13/13) 0 1.22 - 3.83 (7.3 mi SE) !.22 3.83 0.91 - 3.89 CO-58 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 , 0.00 0.00 0.00 - 0.00 CO-60 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 0.00 0.00 0.00 !

CS-134 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 0.00 CS 137 26 I8 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 26 30 0.00 (0/13) 0.00(0/I3) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 11 3 8 2000 507(3/4) 214 507(3/4) 183 (2/4) 0 331 681 (7.3 mi SE) 331 681 159 - 208 l-131 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 26 I5 0.00 (0/I3) 0.00 (0/13) 0.00 (0/13) 0

_ _ . _ _ . _ . _ _ 99 _ _ . _ . _ _ _ _ _ _ , 0 QO O O . _ _ _ . _

0.00 - 0.00 0.00 - 0.00 0 00 - 0.00 ZN-65 26 30 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0 00 0.00 - 0.00 0.00 - 0.00 ZR 95 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 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 @ 3/19/99 9:12 AM Appendix B - Page 4 J

l _-- - - - - - - - - - - - - - - -

i Environmental Radiological Monitoring Program Summary l

Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-1998 to 31-DEC-1998 Medium or Pathway Type and Total Number Lower Limit of g g; wau ns Location with Highest Annual Mean

"{ "'

Sampled of Detection Name, Distance, Direction #E "

Meas.

Unit of Analyses "" "" "} "" " "" "" " "" "}

Measurement Performed (LLD) Range Code Range Range Surface Water 215 (pCi/ liter) (4.2 mi NNE)

BALA-140 39 15 0.00(0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO 58 39 I5 0.00(0/26) 0.00 (0/I3) 0.00 (0/I3) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 39 I5 0.00 (0/26) 0.00 (0/I3) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-l 34 39 I5 0.00 (0/26) 0.00 (0/13) 0.00 (0/I3) 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 H3 12 2000 3493 (8/8) 208 6613 (4/4) 0.00 (0/4) 0 149 - 9108 (0.5 mi S) 5220 - 9108 0.00 - 0.00 l.I31 39 15 0.00 (0/26) 0.00 (0/I3) 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/I3) 0.00 (0/I3) 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

__ . _ _ __ ._Q 0 - ._____,____0. 0 _, 0 00 O_

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 parenthese:;,(Fraction)

Zero range indicates no detectable activity measurements

} Report Generated @ 3/19/99 912 AM Appendix B Page 5 1

1 Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket h 50-413,414 Location: York County, South Carolina Report Period: Ol-JAN 1998 to 31-DEC-1998 Medium or Type and Total Lower No. of Non-

"" "

E

AllIndicator Control Routine Pathway Number Limit of g, Annual Mean Location Report Sampled of Detection Name, Distance, Direction Unit of Analyses #" " ## " "" " "} ##" "}

Measurement Performed (LLD) Range Code Range Range Ground Water NO CONTROL (pCi/ liter) LOCATION BALA-I40 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' O.00 - 0.00 0.00 - 0.00 0.00 0.00 ZN-65 8 30 0.00 (0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 -0.00 0.00 - 0.00 0.00 0.00 ZR-95 8 15 0.00(0/8) 0.00 (0/8) 0.00 (0/0) 0 0.00 0.00 0.00 0.00 0.00 0.00 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 @ 3/19/99 9.12 AM Appendix B - Page 6

)

) - _ - - - -

I Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-1998 to 31 DEC-1998 Medium or Type and Total Lower No. of Non.

gg Location with Highest Pathway Number Limit of Control

g Annual Mean Routine Sampled of Detection Name, Distance, Direction Location Report Mm Unit of Analyses #"" ** "

(LLD) # " #" " " " "# "

Measurement Performed Range Code Range Range Milk (pCi/ liter) 221 (14.5 mi NW)

BALA-140 78 15 0.00(0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 CS-134 0.00 0.00 78 15 0.00 (0/52) 0.00(0/26) 0.00(0/26) 0 0.00 - 0.00 0.00 - 0.00 CS 137 0.00 - 0.00 78 18 0.00 (0/52) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 l 131 0.00 - 0.00 78 15 0.00 (0/52) 0.00(0/26) 0.00 (0/26) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 LLI131 78 1 0.00 (0/52) 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 @ 3/19/99 9 I2 AM Appendix B - Page 7

Environmental Radiological Monitoring Program Summary Fccility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: Ol-JA%l998 to 31-DEC-1998 I Medium or Type and Total Lower Location with Highest

^" *'

l Pathway Number Limit of Annual Mean Control Locatmn Routme Report Sampled of Detection Name, Distance, Direction I Meas.

I Unit of Analyses #" '" ") '# " ##" '"" "} ##" ( "" ")

Measurement Performed (LLD) g Range Code Range Range I Broadleaf 217 I Vegetation (10.3 mi SSE) g (pCi/kg wet)

CS-134 50 60 0.00 (0/40) 0.00(0/9) 0.00 (0/10) 0 I 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 g CS 137 50 80 65.3 (4/40) 201 65.3 (4/10) 0.00 (0/10) 0 30.1 - 114 (0.5 mi NE) 30.1 - 114 0.00 - 0.00 1-131 50 60 0.00 (0/40) 0.00 (0/9) 0.00 (0/10) 0 g 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 D

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

Zero range indicates no detectabla activity measurements I

I

[

t

)

t

)

[

)

c

)

(

) Report Generated @ 3/19/99 9.11 AM Appendix B - Page 8

) - _ ---

Environmental Radiological Monitoring Progrant Suniniary Facility: Catawba Nuclear Station Docket No. 50 413,414 Locction: York County, South Carolina Report Period: Ol-JAN-1998 to 31-DEC-1998

" ' I " "'

Medium or Type and Total Lower Location with Highest Pathway Number Limit of AH n cator Annual Mean "'S

"" "* ""I' " "E "

Sampled of Detecticn Name, Distance, Direction Meas.

Unit of Analyses (LLD)

"" ( ** "} "" " *" 'I ") '"" ( ""* "I Measurement Performed Range Code Range Range Food Products NO CONTROL (pCi/kg wet) LOCATION CS-134 3 60 0.00 (0/3) 0.00(0/3) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 3 80 0.00(0/3) 0 00 (0/3) 0.00(0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 3 60 0.00 (0/3) 0.00 (0/3) 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 a

t Report Generated @ 3/19/99 912 AM Appendix B - Page 9

Environinental Radiological Monitoring Prograni Sumniary Frcility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: Ol-JAN 1998 to 31 DEC-1998*

Medium or Type and Total Lower Location with Highest Pathway Number Limit of ^ " '" .##

' nr R utine Annual Mean Sampled of Detection Name, Distance, Direction L cation Report Meas.

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

Measurement Perfonned (LLD)

Range Code Range Range Fish 216 (pCi/kg wet) (4 0 mi NNE)

CO-58 __ 24 130 _ 64.4 (4/l2) ,_ 20_8_ 64.4 (4/12) 0.00 (0/12) 0

_ . _ _ 26.1 89.3 _ _ (0 5_mi S)__ _26 1 _89.3, 0.00 - 0.00 __

CO-60 24 130 28.6 (2/12) 208 28.6 (2/I2) 0.00 (0/12) 0 27.1 - 30.1 (0.5 mi S) 27.1 - 30.I 0.00 - 0.00 CS-l 34 24 130 0.00 (0/12) 0.00 (0/12) 0.00(0/I2) 0

'~

CS-137 24 150 5 (2/1 ) ~ 108' 5 /12 ~T~

15.7 - 15.9 (0.5 mi S) 15.7 - 15.9 11.1 II.l _

FE 59 24 260 0.00 (0/12) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 24 130 0.00(0/12) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 24 260 0.00 (0/12) 0.00 (0/12) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) ;

Zero range indicates no detectable activity measurements l

Includes allfish samples collectedfor period Ul/98 - 12BI/98 (First throughfourth quarter sampling)

Report Generated @ 3/19/99 9.12 AM Appendix 0 Page 10

l 1

Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: Ol-JAN-1998 to 31-DEC-1998*

Medium or Type and Total Lower Pathway g; g; , Location with Highest No. of Non-Number Limit of Control Sampled ; Annual Mean Routine of Detection Location Name, Distance, Direction .

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

Measurement Performed Range Code Range Range Shoreline Sediment 215 (pCi/kg-dry) (4.2 mi NNE)

CO 58 20 0 163 (12/16) 208 1S 188 (4/4) 0.00(0/4) 0 53.3 -344 118 344 CO-60 20 0 0.00 - 0.00 172(12/I6) 208 1S 230 (4/4) 0.00 (0/4) 0 49.7 -355 136 355 CS-134 20 150 0.00 0.00 0.00 (0/16) 0.00(0/4) 0.00(0/4) 0 0.00 0.00 0.00 0.00 CS-137 20 180 0.00 0.00 60.9(9/16) 208 1S 71,1 (4/4) 0.00 (0/4) 0 30.4 - 112 MN 54 20 49.0 112 0.00 - 0.00 0 30.7 (2/16) 208-3S 30.7(2/4) 0.00 (0/4) 0 24.3 -37.2 24.3 - 37.1 0 00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measureme its at specified locations is indicated in parentheses, (Fraction)

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

Includes all shoreline sediment cohectedfor period I/U98 12/3U98 (First throughfour/h quarter s I

Repon Generated @ 3/I9/99 9.12 AM Appenda B Page 11

)

Environrnental Radiological Monitoring Prograni Sunirnary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-1998 to 31 DEC-1998*

Medium or Type and Total Lower

^"'""' Location with liighest

?"~

Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction Lca$' tion Report Meas.

Unit of Analyses #"" '"# ") #" " #"" '" "} #"" '"#I ")

Measurement Performed (LLD) Range Code Range Range Bottom NO CONTROL Sediment LOCATION (pCi/kg dry)

CO-57 12 0 25.6 (1/12) 208 - 1M 25.6 (I/4) 0.00 (0/12) 0 25.6 25.6 25.6 -25.6 0.00 - 0.00 CO-58 12 0 386 (8/12) 208 - IM 655 (3/4) 0.00 (0/12) 0 61.0 - 929 378 - 929 0.00 0.00 CO-60 12 0 8273 (12/12) 208 - 2M 14570 (4/4) 0.00 (0/12) 0 715 - 19200 10280 - 19200 0.00 0.00 CS-137 12 0 430 (12/12) 208 - 3M 584 (4/4) 0.00 (0/12) 0 113 - 636 520 636 0.00 - 0.00 M N-54 12 0 176 (9/12) 208 - 2M 253 (3/4) 0.00 (0/12) 0 48.3 -395 94.4 - 395 0.00 - 0.00 SB 125 12 0 668 (12/12) 208 - 2M 1203 (4/4) 0 00 (0/12) 0 224 - l 759 723 - l759 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)

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

Includes all bottom sediment collectedfor period I/1/98 - 12/31/98 (First throughfourth quarter sampling)

) Report Generated @ 3/19/99 9.12 AM Appt.ndix 0 Page 12

). .

l

Environmental Radiological Monitoring Program Summary Focility: Catawba Nuclear Station Docket No. 50-813,414 Location: York County, South Carolina Report Period: Ol JAN 1998 to 31 DEC-1998

' " S

Medium or Total All Indicator Control Ikout e g

Pathway Sampled Number Locations "" "

Name, Distance, Direction #E "

of Meas.

Analyses Mean (Fraction) Location Mean (Fraction) Mean (Fraction)

Unit of Measurement }

Performed Range Code Range Range Direct Radiation 217 (10.0 mi SSE)

TLD 247 (7.5 mi ESE)

(mR/ standard quarter) 251 (9.8 mi WNW) 159 0 00E+00 19.69 (147/147) 229 25.2 (4/4) 16.2 (12/12) 0 10.7 -27.9 (0.8 mi NW) 23.8 - 26.6 12.7 - 22.0 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 @ 3/19/99 9-13 AM !

Appendix 8 Page 13

) - _ _ _ - - _ - - - - - _

APPENDIX C SAMPLING DEVIATIONS UNAVAILABLE ANALYSES Appendix C - Page I

l I

APPENDIX C CATAWBA NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES l l

DEVIATION & UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair j IW Inclement Weather SL Sample Loss / Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized i OT Other TF Torn Filter Pl Power Interrupt VN Vandalism PM Preventive Maintenance .

C.1 SAMPLING DEVIATIONS Air Particulate and Air Radiciodines Scheduled Actual Reason Location Collection Dates Collection Dates Code Corrective Action 1/14 - 1/21/98 1/14 - 1/15/98 PO Power interruption to sampling equipment 1/28 - 2/4/98 !/29 - 2/4/98 PO due to bad breaker box. Following 3/4 - 3/l1/98 3/4 -3/7/98 PO repeated problems with this site's power 4/8 - 4/15/98 4/8 - 4/9/98 PO supply, a work request was written to 4/l5 - 4/17/98 PO initiate site repair. A 20 amp breaker box 4/15 - 4/22/98 200 was placed into operation and the air 4/29 - 5/6/98 4/29 - 5/2/98 PO sampler power supply problems were 7/15 - 7/22/98 7/15 - 7/21/98 PO eliminated.

7/22 - 7/29/98 7/22 - 7/23/98 PO l

8/5 - 8/12/98 8/5 - 8/6/98 PO 9/16 - 9/23/98 9/16 - 9/17/98 PI Blown fuse in air sampling equipment due to an electrical short. Sampler was 201 5/20 - 5/27/98 5/20 - 5/24/98 BF replaced and sampling resumed.

Blown fuse in air sampling equipment.

205 9/23 - 9/30/98 9/23 - 9/27/98 BF Fuse replaced and sampler restarted.

Appendix C - Page 2

{

C.2 UNAVAILAHLE ANALYSES Air Particulate and Air Radiciodines Scheduled Reason Location Collection Dates Code Corrective Action Power interruption to sampling equipment due to bad 200 t/21 - 1/28/98 PO breaker box.

TLD Scheduled Reason Location Collection Dates Code Corrective Action 248 l 6/25 - 9/24/98 l VN l TLD missing. 4'" quarter TLD placed in field.

)

Appendix C - Page 3

)

) . _ _ _ _ _ - _ _ _ _ _ - _

APPENDIX D ANALYTICAL DEVIATIONS No analytical deviations were incurred for the 1998 Radiological Environmental Monitoring Program

)

Appendix D - Page 1

)

APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 1998. 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 1

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ML20206H914

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