ML20217H398
| ML20217H398 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/31/1997 |
| From: | Gordon Peterson DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9804290365 | |
| Download: ML20217H398 (104) | |
Text
Duke Power Comparty p &, A D* E='v %?9
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Catawba Naulear Station
- '""8 . 4800 Concord Road York, SC 29745 Gesy R. Prsereon (803) 831-4251 omcr Via />rsident (803) 831-3426 fax April 23, 1998 U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
Subject:
Catawba Nuclear Stations, Units 1 and 2 Docket Nos. 50-413 and 50-414 1997 Annual Radiological Environmental Operating Report Pursuant to Technical Specification 6.9.1.6 and Selected Licensee Commitment 16.11-16.1, please find attached the 1997 Annual Radiological Environmental Operating Report. This report covers operation of Catawba Units 1 and 2 during the 1997 calendar year.
Any questions concerning this report may be directed to Kay Nicholson at 803- 1-3237.
Si rely i A a R. Peterson Attachment xc: (*w/o attachment)
L. A. Reyes, Regional Administrator P. S. Tam, ONRR
- D. J. Roberts, SRI
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M Duke EdEnergy ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE POWER COMPANY CATAWBA NUCLEAR STATION Units 1 and 2 1997 ujR >N\
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TABLE OF CONTENTS 1.0 Executive Summary . . 1-1 2.0 Introduction . . . . . 2-1 2.1 Site Description and Sample Locations . . 2-1 2.2 Scope and Requirements of Environmental Monitoring Program 2-1 2.3 Statistical and Calculational Methodology. . . 2-2
, 2.3.1 Estimation of the Mean Value. . . 2-2 2.3.2 Lower Level of Detection, Minimum Detectable Activity, and Critical Level . . . 2-3 2.3.3 Trend Identification . . . 2-3 3.0 Interpretation of Hesults . . . 3-1 3.1 Airborne Radioiodine and Particulates . 3-3 3.2 Drinkicg 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 Sedimeni . . . . 3-19 3.11 Direct Gamma Radiation . 3 22 3.12 Land Use Census . . . . 3-24 4.0 Evaluation 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. . 4-3 5.0 Quality Assurance .
. 5-1 5.1 Duke Power Company's REMP. . 5-1 5.2 Contractor Laboratories 5-3 6.0 References .
6-1 Appendices Appendix A: Environmental Sample and Analysis Procedures A-1
- 1. Change of Sampling Procedures A-2 II. Description of Analysis Procedures A-2 III. Change of Analysis Procedures . A-3 IV. Sampling and Analysis Procedures A-3 A.I Airborne Particulate and Radiciodine A-3 A.2 Drinking Water . . A-3 A.3 Surface Water A-4 A.4 Ground Water. A-4 A.5 Milk A-4 i
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A.6 Broadleaf Vegetation . . . . . . . A-4 A.7 Food Products. . . . . . . . . . A-5 A.8 Fish . . . . . . . . . . . . A-5 A.9 Shoreline Sediment. . . . . . . . . . A-5 A.10 Bottom Sediment . . . . . . . . . . A-5 A.II Direct Gamma Radiation (TLD) . . . . . . . A-6 A.12 Annual Land Use Census . . . . . . A-6 V. Program improvements . . . . . . . . A-6 Appendix B: Radiological Environmental Monitoring Program - Summary of Results Air Paniculate . . , . . . . . . . . . B-2 Air Radioiodine . . . . . . . . . . . B-3 Drinking Water . . . . . . . . . . . . B-4 Surface Water . . . . . . . . . . . B-5 Ground Water . . . . . . . . . . . B-6 Milk . . . . . . . . . . . B-7 BroadleafVegetation . . . . . . . . B-8 Food Products . . . . . . . . . . B-9 Fish . . . . . . . . . . . B-10 Shoreline Sediment . . . . . . . . B-ll Bottom Sediment . . . . . . . . . B-12 Direct Gamma Radiation (TLD) . . . . . . B-13 Appendix C: Sampling Deviations and Unavailable Analyses . . . . C-1 C.1 Sampling Deviations . . . . . . C-2 C.2 Unavailable Analyses . . . . . . . C-2 Appendix D: Analytical Deviations - Lower Limits of Detection . . D-1 Analytical Deviations . . . . . . . . . D-2 Appendix E: Radiological Environmental Monitoring Program Results . E-l LIST OF FIGURES 2.1-1 Sampling locations Map (Site Boundary) . . . . . . . 2-7 2.1-2 Sampling Locations Map (Ten Mile Radius) . . . . . 2-8 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 . . . 3-7 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-58 in Shoreline Sediment . . . . . 3 17 3.9-2 Concentration of Co-60 in Shoreline Sediment . . . . 3-17 3.10-1 Bottom Sediment Sanspling 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 LIST OF TABLES 2.1-A Radiological Monitoring Program Sampling Locations (TLD Sites) . . 2-5 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 ofGross Beta in Air Particulate . . 3-4 ii
l 3.1 -B Mean Concentration of Air Radioiodine (I-131) 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 3.10 Mean Concentrations of Radionuclides in Bottom Sediment . . 3-21 3.11 Direct Gamma Radiation (TLD) Results . . . . 3-23 3.12 Land Use Census Results . . . . . . . 3-25 4.1 -A 1997 Environmental and Efiluent Dose Comparison . . . . 4-4 4.1 B Maximum Individual Dose for 1997 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 Iksimeter Cross-Check Results . . . . 5-16 LIST OF ACRONYMS USED IN TIIIS TEXT (in alphabc/icalorder) flW lliWeekly C Control CL Critical Level DEllNR Department of Environmental IIcalth and Natural Resources DilEC Department of Ilealth and Environmental Control WA Environmental Protection Agency LLD Lower Limit of Detection M Monthly MDA Minimum Detectable Activity mrem millirem NIST National Institute of Standards and Technology NRC Nuclear Regulatory Commission ODCM OfTsite Dose Calculation Manual pCi/kg picocurie per kilogram pCi/l picocurie per liter pCi/m3 picoeurie per cubic meter Q Quarterly REMP Radiological Environmental Monitoring Program SA Semiannually SLCs Selected Licensee Commitments SM Semimonthly TECll SPECS Technical Specifications TLD Thermoluminescent Dosimeter pCi/mi microcurie per milliliter UFSAR Updated Final Safety Analysis Report W Weekly m
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 1997.
Included are the identification of sampling locations, descriptions of environmental sampling and analysis procedures, comparisons of present environmental radioactivity levels and pre-operational enviromnental 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.
l Sampling activities were conducted as prescribed by Selected Licensee Commitments (SLCs). Required analyses were performed and detection capabilities were met for all samples as required by SLCs. Supplemental analyses were performed for some media for additional information. Nine-hundred seventy-nine samples were analyzed comprising 1109 test results in order to compile data for the 1997 report. Based on the I annual land use census, the current number of sampling sites for Catawba Nuclear l
Station is sufficient.
l Concentrations observed in the environment in 1997 for station related radionuclides were generally within the ranges of concentrations observed in the past. Inspection of data showed that radioactivity concentrations in surface water, drinking water, shoreline sediment, and fish are higher than the activities reported for samples collected prior to the operation of the station. Measured concentrations were not higher than expected, and all positively identified measurements were within limits as specified in SLCs. ,
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Additionally, environmental radiological '-
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monitoring data is consistent with effluents .
a introduced into the environment by plant -
operations. The total body dose estimated to '
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the maximum exposed member of the public as calculated by environmental sampling - r data, excluding TLD results, was 4.08E-01 .
mrem for 1997, it is therefore concluded
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that station operations has had no significant .
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radiological impact on the health and safety
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of the public or the environment. Shoreline sediment sampling Section 1 - Page i
2.0 INTRODUCTION
2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Duke Power Company's Catawba Nuclear Station is a two-unit facility located on the shore of Lake Wylie in York County, South Carolina. Each of the two essentially identical units employs a pressurized water reactor nuclear steam supply system furnished by Westinghouse Electric Corporation. Each generating unit is designed to produce a net electrical output of approximately 1145 MWe. Units 1 and 2 achieved initial criticality on January 7,1985, and May 8,1986, respectively.
Condenser cooling is accomplished utilizing a closed system incorporating cooling towers, instead of using lake water directly. Liquid effluents are released into I.ake Wylie via the station discharge canal and are not accompanied by the large additional dilution water flow associated with "once-through" condenser cooling. This design results in greater radionuclide concentrations in the discharge canal given comparable liquid effluent source terms.
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 REOUIREMENTS OF THE REMP An environmental monitoring program has been in effect at Catawba Nuclear Station since 1981, four years prior to operation of Unit 1 in 1985. The preoperational program provides data on the existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station.
The operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation.
This monitoring program is based on NRC. guidance as reflected in the Selected Licensee Commitments Manual, with regard to sample media, sampling locations, sampling frequency and analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other " man-section 2 - Page 1
made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related exposures from releases of radionuclides from Catawba Nuclear Station. This program satisfies the requirements of Section IV.B.2 of Appendix 1 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 REMP analysis and frequency schedule.
The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified and that modifications to the REMP are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix ! 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 METHODOLOGY 2.3.1 ESTIM ATION OF THE MEAN VALUE There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the REMP. The following equation was used to estimate the mean (reference 6.8):
N
$1 x =
N Where:
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x = estimate of the mean, i = individual sample, N = total number of samples with a net activity (or concentration) xi = net activity (or concentration) for sample i.
section 2 - Page 2 l
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NOTE: " Net activity (or concentration)" is the activity (or concentration) determined to be present in the sample. No " Minimum Detectable Activity", " Lower Limit of Detection", "Less Than Level", or negative activities or concentrations are included in the calculation of the mean.
2.3.2 LOWER LEVEL OF DETECTION. MINIMUM DETECTABLE ACTIVITY, AND CRITICAL LEVEL The Lower Level of Detection (LLD), Minimum Detectable Activity (MDA), and Critical Level (CL) are used throughout the REM.P.
LLD - The LLD, a; 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 Section 2 - Page 3
data. Factors that may affect environmental levels of radionuclides include prevailing weather conditions (periods of drought, solar cycles or heavier than normal precipitation), construction in or around either the nuclear plant er 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 somejudgment by plant personnel.
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TAHLE 2.1-A CATAWHA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)
Nete Location EHetance Sector Mee incat6os IHetence sector 200 SITE HOUNDARY 0.6 mi NNE 233 4-5 MILE RADIUS 3.9 mi ENE 201 SITE HOUNDARY 0.5 mi NE 234 4-5 MILE RADIUS 4.5 mi E 202* SITE HOUNDARY 0.6 mi E 235 4-5 MILE RADIUS 3.9 mi ESE 203 SITE HOUNDARY 0.4 mi ESE 236 4-5 MILE RADIUS 4.3 mi SE 204 SITE ilOUNDARY 0.5 mi SSW 237 4-5 MILE RADIUS 4.8 mi SSE 205 SITE HOUNDARY 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 HOUNDARY 0.7 mi N 243 4-5 MILE RADIUS 4.4 mi WNW 223 SITE ilOUNDARY 0.6 mi E 244 4-5 MILE RADIUS 4.0 mi NW 224* SITE HOUNDARY 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 IlOUNDARY 0.5 mi WSW 248 SPECIAL INTEREST 6.6 mi S 228 SITE HOUNDARY 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 l
- Deleted 09/14/89
- Added 09/14/89 Section 2 Page 5
TAllLE 2.1-11 CATAWilA RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 2.1-B Codes W Weekly SM Semimonthly HW HiWeekly Q Quarterly M Monthly SA Semiannually C Control
- I'ocation Descrintionr ""a"
- " *Woest *"""' '*d " "" "'*" '""*'
g %sser neshmeme Prederte 14af Water Port. (a) Vu (h) 200 Stc floundary (0 6mi NNF) W M 201 Site floundary (0.5 mi NE) W M 205 Ltc floundary (0.3 mi SW) W 208 Discharge Canal (0.5 mi S) HW SA SA 209 Dairy (6.0 mi SSW) SM 210 Ebenezer Access (2.hii SE) SA 21I Wylie Dam (4.0 mi ESE) HW 212 'lega Cay (3.3 mi E) W 214 Rock liill Water Supply (7.3 mi SF) HW 215 C River Pointe - Hwy 49 (4.2mi NNF) ElW SA 216 C liwy 49 Hridge (4 Omi NNE) SA 217 C Rock flill Substation (10.3 mi SSE) W M 218 C ilelmont Water Supply (13.4mi NNE) ISW 219 Dairy (5.7 mi SW) SM 221 C Dairy (l4.5 mi NW) SM 222 Site floundary (0.7 mi N) M 226 Site floundary (0.5 mi M M 252 Residence (0.7mi SW) Q 253 trngated Gardens (Downstream within 5 mile radius) M(a) 254 Residence (0.8mi N) Q (a) During llan est Season (b) When Available Section 2 - Page 6
Catawba Nuclear Station Figure 2.1-1 Sampling Locations Map (Site Boundary)
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TAILLE 2.2-A
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REPORTING LEVELS FOR RADIOACTIVITY
) CONCENTRATIONS IN ENVIRONMENTAL SAMPLES l l !
Air Food Analysis ' Water Particulates Fish Milk Products !
(pCi/ liter) or Gases (pCi/kg-wet) (pCi/ liter) (pCi/kg-wet) i (pCi/m') l
)
11-3 20,000'"
Mn-54 1,000 30,000 ;
Fe-59 400 10,000 1 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 of30,000 pCi/ liter may be used.
i Section 2 - Page 9
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) TABLE 2.2-B I
I REMP ANALYSIS FREQUENCY
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1 f - Sample . Analysis Gamma _ Tritium Low Level Gross TLD l - Medium Schedule - Isotopic I-131 Beta -
) Air Radioiodine Weekly X
)
Air Weekly X Pasticulates Quarterly X Composite
) Direct Radiation X y Quarterly Monthly
)
Surface Composite X i
Water Quarterly j Composite X Biweekly X Monthly Drinking Composite X X Water Quarterly Composite X Shoreline Sediment Semiannually X i Milk Semimonthly X X Fish Semiannually X Broadleaf Monthly Vegetation (when X available)
Monthly Food Products (during X harvest season)
Section 2 - Page 10 l
TABLE 2.2-C MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION Air Analysis Water Particulates Fish Milk Food Sediment (pCi/ liter) or Gases (pCi/kg-wet) (pCi/ liter) Products (pCi/kg-dry)
(pCi/m') (pCi/kg-wet)
Gross Beta 4 0.01 11-3 2000(')
Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 1*) 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 waterpathway exists, a value of3000pCi/ liter may be insed.
(b) Ifno drinking waterpathway exists, the LLD ofgamma isotopic analysis may be used.
Section 2 - Page 11
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 1997.
l These measures were first adopted in 1986 to improve assessment of the impact of CNS 1 operations on the environment.
i 1) Shoreline sediment (required collection at one point along CNS discharge canal, l Location 208) was collected at three points (Locations 208-lS,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.
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- 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 j third quarter samples are supplemental. ;
- 4) Bottom sediment (not required to be collected) was collected quarterly at Locations 208-1M,208-2M and 208-3M. These are all supplemental samples.
1 Review of all 1997 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 1997 was compared to preoperational and historical data. Over the years of operation, analysis and collection changes have taken j place that do not allow direct comparisons for some data collected from 1984 (preoperational) through 1997. ]
Summary tables containing 1997 information required by Technical Specification Administrative Control 6.9.1.6 are located in Appendix B. These tables contain data based l upon required sample results and supplemental sample results.
Evaluation for significant trends was performed for radionuclides that are listed as required l
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-95,1-131, Cs-134, Cs-137, Ba-140 and La-140.
Gross beta analysis results were trended for drinking water and gross beta trending for air particulates was initiated in 1996. Other radionuclides detected 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 1997 maximum percentages of reporting levels were well below the 100% action level. The sectbn 3. Page I
i highest value noted during 1997 was 43% 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 1997 sample analysis results were reviewed to detect and identify any significant trends.
Tables and graphs are used throughout this section to display data from effluent-based radionuclides identified since the system change in late 1987. All negative concentration values were replaced with zero for calculation purposes. Any zero concentrations used in tables or graphs represent activity measurements less than detectable levels.
Review of all 1997 data presented in this section supports the conclusion that there were no significant changes in enviromnental sample radionuclide concentrations of samples collected and analyzed from CNS site and surrounding areas that were attributable to plant operations.
section 3 - Page 2
3.1 AIRBORNE RADIGIODINE AND PARTICULATES In 1997,260 radioiodine and paniculate samples were analyzed,208 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 paniculate filters. Figure 3.1 shows individual sample gross beta results for the indicator location with highest annual mean and the control location samples during 1997. 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 !
pe '..
1997. Table 3.1-A shows the highest indicator - ' .
- - ' M ,r%'
annual mean and control location annual mean for I E 3 . j,
- iT gross beta in air particulate. i '"' .
l 1 ;,', -
)
There was no detectable I-131 in air radioiodine samples analyzed in 1997. Table 3.1-B shows the '
highest indicator annual mean and control location J .. ;l annual mean for I-131 since 1984 (preoperational
- L E --- - ----
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 not detected on any indicator or control cartridges during 1997. The detection of Cs-137 on the charcoal cartridges 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 Concentration of Gross Beta in Air Particulate pcum*
100E41 8 00E-02 l 6 00E-02 4 00E42 -
2.00E-02 %r 000E+00 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997
--S-Indcator Location --+- Control Locaton ]
There is no reporting levelfor gross beta in airparticulate section 3 - Page 3
Table 3.1-A Mean Concentration of Gross Beta in Air Particulate Year Indicator Location (pCi/m') Control Location (pCi/m')
1984 2.25 E-2 1.82E-2 1985 2.12 E-2 1.53 E-2 1986 3.62E-2 3.41 E-2 1987 2.67E-2 2.32E-2 1988 2.29E-2 2.30E-2 1989 2.11 E-2 2.13 E-2 1990 2.39E-2 2.72E-2 1991 2. I 9E-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 4.88E-2 3.23 E-2 1996 3.49E-2 2.60E-2 Average (1987 - 1996) 2.58E-2 2.38E-2 1997 2.83 E-2 2.28E-2 Table 3.1-B Mean Concentration of Air Radioiodine(I-131)
Year Indicator Location (pCi/m') Control Location (pCi/m')
!!'84 1.30E-3 1.46E-2 1985 4.75E-3 2.38E-2 1986 1.43 E-2 1.02E-2 1987 1.38E-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 Average (1987 - 1996) 1.38E-3 0.00E0 1997 0.00E0 0.00E0 0.00E0 = no detectable measurements Section 3 - Page 4 l . .. .
, 3.2 DRINKING WATER l
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 all indicator samples and one control sample during 1997. The mean indicator tritium concentration for 1997 was 354 pCi/1,1.77% of reporting level. The mean control tritium concentration for 1997 was 228 pCi/1,1.14% of reporting level. Figure 3.2 and Table 3.2 display the highest indicator and control location annual mean concentrations for tritium since 1984. Ten year averages are also shown.
i l
Table 3.2 shows highest annual mean gross beta concentrations for the indicator location and control location for since preoperation. The indicator location (downstream of the plant f effluent release point) average concentration was 3.74 pCi/l in 1997 and the control location j
concentration was 3.15 pCi/1. The 1996 indicator mean was 3.08 pCi/1. The table shows that ,
current gross beta levels are not statistically different from preoperational concentrations. l No gamma emitting radionuclides were identified in 1997 drinking water samples. There have been no gamma emitting radionuclides identified in drinking water samples since 1988.
Figure 3.2 Concentration of Tritium in Drinking Water pCl/ liter 2500 - _ _ __--- - . - _ _ _ . . . . _ . - -
2000 1500 1000 500 0: --
1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 e-_ hdcator Locaton _ Control Location 10% Reportang Level section 3 - Page 5
)
Table 3.2 Mean Concentration of Radionuclides in Drinking Water
)
) Gross Beta (pCi/l)
( Tritium (pCill)
/ YEAR Indicator Control Indicator Control Location Location Location Location 1984 4.72 1.83 3.10E-2 3.1 OE-2 i985 2.70 2.24 4.13E2 4.00E2 1986 3.11 2.26 7.23E2 7.33 E2 f
1987 3.10 2.40 7.80E2 4.80E2 1988 3.60 2.60 6.64E2 0.00E0
(
t I989 3.60 2.90 8.91 E2 5.72E2 1990 4.50 3.20 7.03E2 0.00E0
)
1991 3.70 2.20 7.04E2 0.00E0 1992 3.20 2.40 7.65E2 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 4.28E2 2.21 E2 f 1996 3.08 3. I4 3.71 E2 3.27E2 Average (1987 - 1996) 3.64 2.85 6.01 E2 2.14E2 1997 3.74 3.15 3.54E2 2.28E2 0.00E0 = no detectable measurements
( 1984 - 1986 mean based on all net activity
) I
{
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 effluent discharge point.
Tritium was the only radionuclide identified in surface water samples collected during 1997. Seven of the eight indicator location samples contained tritium with an average concentration of all indicator locations of 4081 pCi/1. This is 20.4% of reporting limit for tritium in surface water. Indicator Location 208 (Discharge Canal) showed a range of reporting levels from 31.0% to 43%. The 1997 mean concentration was 7777 pCi/1. The control sample highest annual mean for 1997 was 220 pCi/1.
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 1997 show a relatively stable to slightly increasing trend for tritium.
Figure 3.3 Concentration of Tritium in Surface Water pClatter 12000 ---
10000 i
8000 M '
. .. A/ \ M 4000 8
_ / .
0E - -
1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 l -G-Indcator Location -*-Control Locaton 50% Reporting Level l Section 3 - Page 7
Table 3.3 Mean Concentrations of Radionuclides in Surface Water (DCi/I)
YEAR Co-58 Co-60 Nb-95 Cs-137 11-3 Indicator H-3 Control 1984 4.59E-1 5.71 E-1 6.48E-1 9.08E-1 3.35E2 3.18E2 1985 3.46E0 4.83 E-2 2.70E0 8.19E-1 1.19E3 5.05E2 1986 3.10E-l -4.12E-2 2.05E0 4.85 E-1 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 6.03E3 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 6.64E2 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 2.6I E2 Average (1987 - l'196) 2.04E0 4.90E-1 4.30E-1 9.90E-1 5.81E3 3.21 E2 1997 0.00E0 0.00E0 0.00E0 0.00E0 7.77E3 2.20E2 0.00E0 = no detectable measurements
, 1984 - 1986 mean based on all net activity Section 3 - Page 8
i 3.4 GROUND WATER A total of eight ground water samples was collected and analyzed for gamma emitters.
There are two indicator locations and no control locations. Naturally occurring K-40 was the only radionuclide identified during 1997.
There have been no radionuclides identified in ground water samples since 1988. Only naturally occurring K-40 and Be-7 were noted.
l 1
i
)
l i
l l
1 section 3 - Page 9
I l
3.5 MILK l l
A to+al of 78 milk samples was analyzed by gamma spectroscopy and low level iodine during 1997. There were two indicator locations and one control location sampled.
i There were no gamma emitting radionuclides identified in milk during 1997.
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 pCill. Cs-137 attributable to past nuclear weapons i 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.
I Table 3.5 Mean Concentration of Radionuclides in Milk YEAR Cs-137 Indicator (pC1/I) Cs-137 Control (pCl/l)
I984 2.95 2.98 1985 2.11 2.12 1986 3.76 4.54 1987 5.00 5.50 1988 3.20 3.80 1989 0.00 0.00 1990 8.00 6.70 1991 0.00 0.00 1992 3.40 5.00 1993 5.00 0.00 1994 2.80 0.00 1995 8.60 0.00 1996 6.05 0.00 Average (1987 - 1996) 4.21 2.10 1997 0.00 0.00 0.00E0 = no detectable measurements 1984 - 1986 mean based on all net activity Section 3 - Page 10
3.6 BROADLEAF VEGETATION Gamma spectroscopy was performed on 10 broadleaf vegetation samples during 1997.
Four indicator locations and one control location were sampled.
Nine of the thirty-two samples collected at indicator locations contained detectable Cs-137 activity. Cs-137 was detected in five of the nine samples collected at Location 201. This location's highest concentration was 98.9 pCi/kg. 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 Veeetation YEAR Cs-137 Indicator (pCi/kg) Cs-137 Control (pCl/kg) 1984 3.76EI 1.30EI 1985 5.48E1 4.16El 1986 7.42El 2.22EI 1987 6.10El 5.10EI 1988 9.10El 7.40El 1989 1.00E2 4.80EI 1990 7.70E1 5.80E1 i991 1.98E2 8.60EI 1992 9.70E1 0.00E0 1993 1.13E2 3.20El 1994 7.00EI 0.00E0 1995 3.60E1 0.00E0 1996 2.23E2 6.22E1 Average (1987 - 1996) 1.07E2 4.1lEl I997 75.7EI 0.00E0 0.00E0 = no detectable measurements 1984 - 1986 mean based on all net activity section 3 - Page 11
1 1
3.7 FOOD PRODUCTS l Collection of food product samples (crops) from an irrigated garden began in 1989. The l l garden is located on Lake Wylie downstream from CNS, Location 253. During 1997, I l five samples were collected and analyzed for gamma radionuclides. There is no control l location for this media type.
No detectable activity has been reported in food products since 1989. Table 3.7 shows l
Cs-137 indicator location highest annual mean concentrations since 1984.
t Table 3.7 Mean Concentration of Radionuclides in Food Products l
YEAR Cs-137 f ndicator (pCi/kg) 1989 0.00E0 l 1990 0.00E0 1991 0.00E0 1992 0.00E0 1993 2.50El 1994 0.00E0 ;
1995 0.00E0 i
, 1996 0.00E0 Average (1989 - 1996) 3.13E0 1997 0.00E0 0.00E0 = no detectable measurements l
l -
l l
section 3 - Page 12
3.8 FISII Gamma spectroscopy was performed on 24 fish saraples collected during 1997. One downstream indicator location and one control location were sampled. Co-58, Co-60 and Cs-137 were the predominant radionuclides identified in fish samples. Three of twelve indicator location samples contained Co-58. One of twelve indicator location samples contained Co-60. Nine of the twelve indicator location samples contained Cs-137.
Cs-137 was identified in one of the twelve control beation samples.
The highest average concentration for Co-58 in indicator location samples was 49.3 pCi/kg which represents 0.16% of the reporting level. For Cs-137 in indicator location samples, the highest average concentration was 27.4 pCi/kg which represents 1.37% of the reporting level. The highest individual sample concentrations were as follows:
Co-58, 87.2 pCi/kg (0.29 % of reporting level), Co-60,9.88 pCi/kg (0.09% of reporting level) and Cs-137, 49.9 pCi/kg (2.5% of reporting level).
) Sample results for fish collected at indicator Location 208 were reviewed by type of fish.
) Results show that all radion'iclide detection frequencies and concentrations are higher for j forager fish than for predator and bottom feeding fish. Similar results have been noted j from 1990 through 1996.
)
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 copbruing
)
correlation between radionuclide concentration in indicator fish samples and rao.iuclide concentration released via the liquid effluent pathway.
Table 3.8 depicts the highest indicator n # . ..
location annual mean for radionuclides t'" 4)5 detected. In addition, radionuclides '
IL ,
p identified in fish samples since 1988 have y 3g -
been included in the table. Overall, ?fJ p radionuclides have not 'shown a sigmficant trend or accumulation smce
- /
} ,v A / --
1988.
g N.m K-40 was observed in fish samples collected during 1997.
2- -. -
Fish Sampling section 3 Page 13
Figure 3.8-1 Concentration of Co-58 in Fish pCVkg 2000 1800 j 1600 I 1400 1200 1000 !
8x n Sm / \
4m o / \
2m /\ ^ / \ l 0: -a . . We 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997
--s bdicator Location _,_. Control Location 5 % Reporting Level Figure 3.8-2 Concentration of Co 60 in Fish pCVkg 700 . _ _ _ _______
600 500 ,
400 300.,
200 100 A JL 0; p M : .
1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997
--m hocator Locaton _. Control Locaton 5% Reporting Level Section 3 . Page 14
Table 3.8 Mean Concentrations of Radionuclides in Fish (pCi/ke)
Year Mo-54 Co-58 Co-60 Cs-134 Cs-137 Nb-95 Fe-59 Sb-122 Sb-125 I984 3.07E0 3.00E0 6.11E-1 -5.32E0 1.83EO 0.00E0 0.00E0 0.00E0 0.00E0 1985 7.68E-1 3.40El 9.llE0 3.22E0 1.28El 5.07E0 0.00E0 0.00E0 0.00E0 1986 2.01EI 1.86E2 4.01EI 3.5IE1 9.29EI 0.00E0 7.30E0 0.00E0 0.00E0 1987 7.24E0 7.57El 4.81El 3.83E0 4.27El 5.40E0 0.00E0 0.00E0 0.00E0 1988 2.85El 1.40E2 9.70El 1.67El 8.24El 0.00E0 0.00E0 0.00E0 0.00E0 1989 8.28E0 1.33E2 3.83El 1.47El 4.37El 8.58E-1 0.00E0 0.00E0 0.00E0 1990 2.51El 1.75E2 7.77El 1.32El 4.66El 3.33E0 0.00E0 7.00E0 9.25E0 1991 3.15El 1.46E2 1.29E2 1.03El 4.60El 7.90E-1 2.30E0 0.00E0 7.45E0 1992 1.34El 9.02El 6.20El 1.27El 4.61El 0.00E0 0.00E0 0.00E0 0.00E0 1993 2.14El 3.58E2 1.21E2 2.73E0 2.56El 0.00E0 0.00E0 0.00E0 0.00E0 1994 1.91E0 4.75El 1.81El 0.00E0 1.75El 0.00E0 0.00E0 0.00E0 1.45El 1995 5.65El 8.90E2 2.66E2 0.00E0 6.77El 1.38El 0.00E0 0.00E0 0.00E0 1996 0.00E0 5.95El 6.68El 0.00E0 3.02El 0.00E0 0.00E0 0.00E0 0.00E0 Average
( 1987-1996) 1.94El 2.llE2 9.24El 7.42E0 4.49El 2.42E0 2.30E-1 7.00E-1 3.12E0 1997 0.00E0 4.93El 9.88E0 0.00E0 2.74El 0.00E0 0.00E0 0.00E0 0.00E0 0.00E0 = no detectable measurements Section 3 Page 15
3.9 SHORELINE SEDIMENT During 1997, 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, Mn-54, and Sb-125 were identified in samples collected from l location 208, which is subdivided into three discharge canal areas (208-1S, 208-2S and 208-3S). These locations are closest to the plant's liquid effluent release point. One control location sample identified Mn-54 in addition to the naturally occurring K-40.
l l The shoreline sediment location with the highest annual mean for all detectable radionuclides was location 208-3S. Cs-137 was identified with an annual mean concenuation of 143 pCi/kg. Other radionuclides identified during 1997 at shoreline sediment site 208-3S included Co-58 with an annual mean of 590 pCi/kg, Co-60 with an i annual mean of 764 pCi/kg, and Mn-54 with an annual mean of 69.6 pCi/kg. Naturally l occurring K-40 and Be-7 were also identified in samples from this location.
l Sb-125 was detected in one of four samples collected from location 208-IS. The concentration observed was 176 pCi.kg. ;
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. From these graphs the trends for both Co-58 and Co-60 are apparent. The accumulation of the radionuclides over time is significant based on radiological half-life and the direct correlation to actual l
concentrations released in liquid effluents. In addition to the two cobalt isotopes, Cs-137 has been a major contributor as well. Concentrations of Co-58 observed during 1997 are
! similar to those observed during 1996 (590 pCi/kg and 339 pCi/kg). Therefore, observations of these trends show that environmental removal processes have not overcome the accumulation of annual activity released via liquid effluents in shoreline
! sediment samples at least through 1997.
Section 3 - Page 16 l
l
Figure 3.9-1 Concentration of Co-68 in Shoreline Sediment pCvkg 2000 _.
1800 1600 _
1400 1200 N iw0 1% / \
8m / N"/ \
6m / \ _
4m .
.. 1 \sr /
f 'MQ f '
0: : : : $
1964 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 l + bdicator Location Control Locaton J
There is no reporting levelfor Co-58 in Shoreline Sediment Figure 3.9-2 Concentration of Co 60 in Shoreline Sediment pCVkg 2000.._ ~. _ _ _ .
1800 1600 1400 1200 1000 ll 800 /\ Ji.
600
[ ,
[ .)
400 a 200 - A 0 :-
1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997
+ bdcator Locaton Control Locaton There is no reporting levelfor Co-60 in Shoreline Sediment Section 3 - Page 17
Table 3.9 Mean Concentrations of Radionuclides in Shoreline Sediment (DCI/kE)
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 -2.34E0 0.00E0 0.00E0 3.19El 1.07E2 0.00E0 0.00E0 1985 -3.12E0 1.16E2 5.18E0 0.00E0 0.00E0 2.l lE2 2.97E2 0.00E0 0.00E0 1986 1.09E2 3.79E2 2.05E2 0.00E0 3.96El 6.50El 1.61E2 0.00E0 0.00E0 1987 8.83El 4.08E2 1.61E2 4.22El 0.00E0 6.08El 1.26E2 0.00E0 0.00E0 1988 1.07E2 3.29E2 2.63E2 2.28El 7.54E0 2.59El 1.07E2 7.65 E-1 3.68E0 1989 4.58El 1.94E2 1.21 E2 5.02E0 0.00E0 1.65El 5.77El 0.00E0 1.57El 1990 5.39El 2.08E2 1.77E2 0.00E0 0.00E0 1.66El 8.18El 0.00E0 7.15E0 1991 8.50El 3.70E2 4.19E2 5.30E0 0.00E0 1.82El 8.33 El 1.20E0 1.50El 1992 1.17E2 1.13 E3 5.80E2 3.50E0 0.00E0 1.69El 1.07E2 3.00E0 2.70El 1993 1.33E2 1.07E3 1.04E3 0.00E0 0.00E0 2.80El 1.26E2 2.47El 2.16E2 1994 4.93El 7.98E2 5.73E2 0.00E0 0.00E0 5.67E0 1.07E2 4.38E0 4.60El 1995 1.02E2 1.33E3 8.65E2 1.13E2 0.00E0 0.00E0 8.50El 3.69El 1.49E2 1996 8.73 E1 3.39E2 5.8IE2 0.00EO 0.00EO 0.00E0 8.30EI 0.00E0 1.96E2 Average (1987 - 1996) 8.69El 6.18E2 4.78E2 1.92El 7.54E 1 1.89El 9.64El 7.09E0 6.76El 1997 6.96E1 5.90E2 7.64E2 0.00E0 0.00E0 0.00EO 7.4X2 0.00E0 1.76E2 0.00E0 = no detectable measurements 1984 - 1986 mean based on all net activity Negative values are calculated as zeroes Section 3 - Page 18
3.10 HOTTOM SEDIMENT Bottom sediment samples are not required as a collection media. Samples were first collected during 1986 from three points in the discharge canal (Location 208) following review of shcreline 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 1997: Mn-54, Co-58, Co-60, Nb-95, 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 a ot5088K g wcstSOE8K 3g8 (35) '
(IMI I
e aos tes) 200 (*)
ftlW (15) aos ( *) anno its satsu l
Section 3. Page 19
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 1997. Overall detection frequencies were high and relatively stable throughout the period. Shoreline sediment data reflected similar concentrations and frequencies for 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 1997. Data shown is annual mean concentrations of Mn-54, Co-58, Co-60, Cs-137 and Cs-134.
Effluent concentrations from liquid releases during 1997 follow the same changes as the annual mean concentrations of radionuclides detected in bottom sediment. Therefore, the impact of plant operation on bottom sediment from Location 208 was at an expected level when considering liquid ellluent data for 1997.
)
4 1
i section 3 - Page 20
Figure 3.10-2 pc % Concentration of Radionuclides in Bottom Sediment 9000 8000
\
som
/
/ %s l 4000 "
i 3000 m-2000 10w !
0"
.h"'%w. "
/ '
i tm.5 5
5 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1990 1997
- +- Mn e- Co-58 -*- Co-60 -e- Cs.134 O Cs-137 There are no reporting levelsfor Mn-54 Co-58. Co-60. Cs-134, and Cs-137 in Bottom Sediment Table 3.10 Mean Concentrations of Radionuclides in Bottom Sediment (pCi/kg)
Year Mn-54 Co-58 Co-60 Nb-95 Cs-134 Cs-137 Cr-51 Co-57 Sb-125 1986 3.60E2 1.09E3 9.64E2 6.99El 1.71E2 3.48E2 0.00E0 0.00E0 0.00E0 1987 5.63 E2 1.34E3 2.18E3 6.99El 1.10E2 4.03E2 0.00E0 0.00E0 0.00E0 1988 5.78E2 9.52E2 3.18E3 1.78El 1.23E2 5.70E2 0.00E0 5.64E0 6.25El 1989 3.98E2 4.47E2 3.42E3 4.49E0 1.05E2 5.04E2 0.00E0 4.48E0 8.l l El 1990 3.81 E2 5.22E2 4.12E3 7.06E0 9.55El 5.06E2 0.00E0 4.56E0 2.15E2 1991 4.15E2 5.76E2 5.10E3 1.63El 8.13El 5.02E2 7.53 El 8.20E0 2.13E2 1992 5.25E2 1.34E3 7.IOE3 7.20E0 4.55E1 4.94E2 2.22EI 1.97EI 4.33E2 1993 3.72E2 1.33E3 5.79E3 0.00E0 7.66El 5.38E2 0.00E0 1.58El 1.33E3 1994 2.77E2 1.25E3 5.32E3 0.00E0 0.00E0 4.27E2 0.00E0 1.72El 5.98E2 1995 1.82E2 8.26E2 5.12E3 1.23 El 6.00E0 4.l l E2 0.00E0 1.48El 5.68E2 1996 1.90E2 4.05 E2 7.22E3 0.00E0 0.00E0 4.29E2 0.00E0 4.92E0 6.95E2 Average (1987- 1997) 4.24E2 9.25E2 4.95E3 1.89El 8.14El 4.78E2 9.75E0 9.53E0 4.20E2 1997 1.76E2 6.27E2 6.49E3 4.06El 0.00E0 3.85E2 0.00E0 0.00E0 6.92E2 0.00E0 = no detectable measurements h
L l
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Section 3 Page 21
3.11 DIRECT GAMMA RADIATION l
l In 1997,159 TLDs were analyzed,147 at indicator locations and 12 at control loctions.
I The highest annual mean exposure for an indicator location was 97.4 milliroentgen. The annual mean exposure for the control locations was 57.2 milliroentgen. j l
Figure 3.11 and Table 3.11 show TLD inner ring (site boundary), outer ring (4-5 miles), i l and control location annual averages in milliroentgen per year. Preoperational data and j twelve year averages are also given. As shown in the graph, inner and outer ring i averages historically compare closely, with control data somewhat higher. Inner and outer ring averages comprise sixteen locations each with control averages representing only three locations.
l l The calculated total body dose (from gaseous effluents) for 1997 was 4.50E-2 mrem, I which is <0.06% of the measured TLD values. Therefore, it can be concluded that !
discharges from the plant had very little impact upon the measured TLD values.
l Figure 3.11
'"*' Direct Gamma Radiation (TLD) Results 250.0 - - - - - - - - - -
200.0
- i
( 150 0
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00 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997
-*--Inner Ring -e-Outer Ring -e-Control i
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Section 3. Page 22 l
l Table 3.11 Direct Gamma Radiation Radiation (TLD) Results Inner Iting Average Outer Ring Average Control Average Year v.:aR/yr) (mR/yr) (mR/yr)
~
1984 87.5 82.6 79.3 1985 116.9 108.7 108.9 l 1986 104.3 98.5 94.4 1987 97.0 87.4 84.7 1988 74.6 70.3 67.I 1989 67.I 60.8 60.0 1990 52.0 44.5 39.I i l
1991 62.0 54.1 46.7 '
1992 80.4 72.5 64.5 1993 70.3 60.9 53.6 1994 76.3 69.3 63.9 1995 99.6 89.7 80.8 1996 84.3 73.9 63.6 Average (1985 - 1996) 82.1 74.2 68.9 1997 82.4 71.9 57.4 l
l I
Section 3 Page 23
3.12 LAND USE CENSUS The 1997 Annual Land Use Census was conducted July 8 - July 10,1997 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 1997 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 1997 census.
e l
Section 3 - Page 24
Table 3.12 Catawha 1997 Land Use Census Results l
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 Milk Cow -
Nearest Beef Cow 4.87 Nearest BeefCow 4.05 Nearest Goat -
Nearest Goat -
Nearest Residence 0.63 Nearest Residence 0.89 NNE Nearest Garden 1.85 ggw Nearest Garden 0.96 Nearest Milk Cow -
Nearest Milk Cow -
Nearest Beef Cow -
Nearest Beef Cow 3.04 Nearest Goat -
Nearest Goat -
Nearest Residence 0.6 Nearest Residence 0.65 NE Nearest Garden 0.66 gg Nearest Garden -
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 wgg Nearest Garden 2.04 Nearest Milk Cow -
Nearest Milk Cow -
Nearest Beef Cow 4.17 Nearest Beef Cow 2.87 Nearest Goat 1.27 Nea est Goat 2.69 Nearest Residence 0.65 Nearest Residence 0.96 E Nearest Garden Nearest Milk Cow w Nearest Garden 0.95 Nearest Milk Cow -
Nearest Beef Cow -
Nearest Becf Cow 3.81 Nearest Goat -
Nearest Goat -
Nearest Residence 0.84 Nearest Residence 1.10 ESE Nearest Garden 3.63 wgg Nearest Garden 1.11 Nearest Milk Cow Nearest Milk Cow -
Nearest Beef Cow -
Nearest Beef Cow 4.34 Nearest Goat -
Nearest Goat 3.63 l
Nearest Residence 0.99 Nearest Residence 1.31 f SE Nearest Garden 1.52 Nearest Garden 1.52 NW
) Nearest Milk Cow -
Nearest Milk Cow -
l Nearest Beef Cow 4.05 Nearest Beef Cow 2.30 f Nearest Goat 4.05 Nearest Goat 1.44
)
Nearest Residence 0.62 Nearest Residence 1.06 i ggg Nearest Garden 1.70 NNW Nearest Garden 2.19 Nearest Milk Cow -
Nearest Milk Cow -
Nearest Beef Cow -
Nearest Beef Cow 2.21 Nearest Goat 3.54 Nearest Goat 2.62
" " indicates no occurrences within the 5 mile radius Section 3 Page 25
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4.0 EVALUATION OF DOSE 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Annual doses to maximum exposed individuals were estimated based on measured concentrations of radionuclides in 1997 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 REMFs based doses. Where applicable, average background concentration at the corresponding control location was subtracted.
l Regulatory Guide 1.109 consumption rates for the maximum exposed individual l were used in the calculations. When the guide listed "NO DATA" as the dose l factor for a given radionuclide and crgan, a dose factor of zero was assumed.
One radionuclide detected in 1997 REMP samples, Sb-125 had no dose factor listed in Regulatory Guide 1.109. The dose factor for Sb-125 was taken from Appendix C, NUREG/CR-1276.
l l Maximum dose estimates (Highest Annual Mean Concentration) based on drinking water, milk, broadleaf vegetation and shoreline sediment sample results are reported in Table 4.1-A.
i REMP-based dose estimates were not reported for airborne radioiodine, airbome particulate 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 1997 was 0.644 mrem to the maximum exposed child's bone from consuming broadleaf vegetation.
Section 4 - Page 1 l
i l In order to generate REMP-based dose estimates that are comparable to reported l effluent-based dose estimates, two additional evaluations were performed:
- Maximum 1997 REMP-based dose estimates for drinking water, shoreline l sediment and fish sample results were summed to determine maximum total doses for all sampled liquid efiluent release pathways. The dose contribution from shoreline sediment to each organ other than skin was assumed equal to total body contribution from shoreline sediment. The maximum total organ dose estimates for the critical age groups are reported on Table 4.1-A. The
- maximum total organ dose estimate for all liquid release pathways sampled during 1997 was 0.07 mrem to the maximum exposed child's liver.
1 e Maximum 1997 REMP-based dose estimates for airborne radioiodine, airborne particulate and broadleaf vegetation sample results were summed to determine ;
the maximum total REMP-based doses for all sampled gaseous effluent release pathways. The resulting maximum total organ dose estimates for the critical age
( groups are reported in Table 4.1-A. The maximum total organ dose estimate for l all gaseous effluent release pathways sampled during 1997 was 0.64 mrem to the maximum exposed child's bone.
4.2 ESTIMATED DOSE FROM RELEASES l l
l Throughout the year, dose estimates were calculated based on actual 1997 liquid and gaseous effluent release data. Effluent-based dose estimates were calculated
! using the LADTAP and GASPAR computer programs that employ methodology l
and data presented in NRC Regulatory Guide 1.109. The 1997 CNS Annual Radioactive Effluent Release Report included calendar year dose estimates for the maximum exposed individual from liquid and gaseous effluent releases. Reported doses are shown in Table 4.1-A along with the corresponding REMP-based dose estimate. -
l Effluent-based liquid release doses are summations of dose contributions from drinking water, fish and shoreline sediment (estimated for discharge canal) pathways.
The etiluent-based gaseous release doses of Table 4.1-A report noble gas exposure and 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 age group. For iodine, particulate and tritium exposure, maximum total organ dose was 0.82 mrem for lung and the critical age was child.
The critical pathway for exposure was broadleaf vegetation.
I 4
section 4. Page 2
i 4.3 COMPARISON OF DOSES Table 4.1-A shows comparisons of REMP-based versus emuent-based maximum dose estimates, critical ages and critical pathways for liquid and gaseous release pathways. As discussed in Part 4.1, REMP-based estimates have been calculated to be analogous to corresponding effluent-based estimates. The estimates can then be compared directly.
One difference between environmental and emuent-based dose estimates is all effluent-based dose estimates include pathway contributions from tritium contained in liquid and gaseous effluents. Drinking water pathways include ' dose contributions from tritium. Air, milk and broadleaf vegetation pathways do not include a contribution from tritium. Similar differences exist for other radionuclides detected in effluent samples. However, as a result of dilution, '
transport and radioactive decay, the concentrations are too low to be detected in REMP samples (and their associated dose contributions are therefore not accounted for in REMP-based dose estimates). These differences result in REMP-based dose estimates that are lower in comparison to effluent-based estimates.
Significant levels of tritium and Cs-137 are present throughout the environment and not attributable to Catawba effluents. REMP samples often contain these i radionuclides, often at detectable levels much greater than levels anticipated due to station effluents. In addition, high variability in the frequency and level that tritium and Cs-137 are detected in REMP indicator and control location samples introduce uncertainties when estimating REMP-based dose contributions from net detectable concentrations of the radionuclides. All 1997 REMP-based dose estimates, other ;
than those samples collected at the discharge canal, are entirely attributable to l detection of tritium or Cs-137 in corresponding REMP samples.
Doses typically overestimate the true contributions from tritium and Cs-137 released via Catawba efiluents.
4 Airborne noble gas samples are not collected as part of the REMP, which prevent an analogous comparison of effluent-based noble gas exposure estimates.
REMP-based dose estimates were lower than the corresponding effluent-based estimates for liquid and gaseous release pathways during 1997. This indicates that the effluent program dose estimates are appropriate and reasonably conservative.
Considering current 40CFR190 requirements, no dose limits were exceeded. Doses l
to members of the public attributable to the operation of CNS are maintained well within regulatory guidelines and limits, section 4 - Page 3
TABLE 4.1-A Page 1 of 2 CATAWBA NUCLEAR STATION 1997 ENVIRONMENTAL AND EFFLUENT DOSE COMPARISON LIOUID RELEASE PATHWAY Environmental or Critical Critical Maximum Dose *
'E*"
Emuent Data Age Pathway (mrem)
Skin Environmental Teen Shoreline Sediment 1.17E-02 Skin Emuent Teen Shoreline Sediment 1.62E-02 Bone Environmental Child Fish 5.18E-02 Bone Effluent Child Fish 9.72E-02 Liver Environmental Teen Fish 8.20E-02 Liver Emuent Teen Fish 1.50E-01 T. Body Environmental Adult Fish 6.21E-02 T. Body Emuent Adult Fish 1.11 E-01 Thyroid Environmental Teen Fish 2.83E-02 Thyroid Emuent Teen Fish 4.08E-02 Kidney Environmental Teen Fish 4.62E-02 Kidney Emuent Teen Fish 7.66E-02 Lung Environmental Teen Fish 3.53E-02 Lung Emuent Teen Fish 5.42E-02 GI-LLI Environmental Adult Fish 5.13E-02 GILLI Emuent Adult Fish 3.18E-01 0 Maximum dose is a summation of the fish, drinking water and shoreline sediment pathways.
section 4 - Page 4
l l
l Page 2 of 2 GASEOUS RELEASE PATHWAY l NOBLE GAS EXPOSURE Environmental or Critical Critical Maximum Dose Organ Emuent Data Age Pathway (mrem)
Skin Environmental - -
Not Sampled Skin Emuent N/A Noble Gas 1.09E-01 T. Body Environmental - -
Not Sampled T. Body Effluent N/A Noble Gas 4.50E-02 IODINE, PARTICULATE, and TRITIUM Environmental or Critical Critical Maximum Dose
- Organ Emuent Data Age Pathway (mrem)
Bone Environmental - - 6.94E-01 1
Liver Environmental - - 6.87E-01 l
l T. Body Environmental - - 1.23E-01 l Thyroid Environmental - - 2.b E-02
! Kidney Environmental - - 2.39E-01 Lung Environmental - - 1.00E-01 Lung Emuent Child Vegetation 8.20E-01 GI-LLI Environmental - - 3.23E-02
- Maximum dose is a summation of the inhalation, milk and vegetation pathways.
Section 4 - Page 5 l
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5 0 QUALITY A.SSURANCE l
5.1 DUKE POWER CONIPANY'S RENIP l
5.1.1 SAMPLE COLLECTION Radiological and Environmental Services, Fisheries, and Aquatic Ecology performed l the environmental sample collections as specified by approved sample collection procedures. l 5.1.2 SAMPLE ANALYSIS l y.
..~
.. g Radiological and Environmental Services performed the environmental sample -
i analyses as specified by approved analysis .
' 7 procedures. The Radiological and I Environmental Services Laboratory is ,: er 2
located in Huntersville, North Carolina, at #_
Duke Power Company's Environmental 1" '"' =* - l Center. Duke Power Company's Environmental Center 5.1.3 DOSIMETRY ANALYSIS The Radiation Dosimetry and Records group performed environmental dosimetry I measurements as specified by approved dosimetry analysis procedures.
5.1.4 INTRALABORATORY OUALITY ASSURANCE Radiological and Environmental Services has an internal q tality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily !
quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance.
Additionally, 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 oflimits.
Section 5 - Page 1
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.
5.1.5 INTERLABORATORY OUALITY ASSURANCE 5.1.5.1 INTERLABORATORY OUALITY ASSURANCE PROGRAM The Radiological and Environmental Services Laboratories participated in the Environmental P.w: tion Agency (EPA) cross check program during 1997. Results of these noss-checks are displayed in Table 5.0-A.
5.1.5.2 DUKE POWER'S INTERCOMPARISON PROGRAM i Radiological and Environmental Services participated in the Duke Power Nuclear Generation Department Intercomparison Program during 1997.
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 summar) of these Intercomparison Reports for 1997 is documented in Table 5.0-B. j 5.1.5.3 DUKE POWER'S AUDIT DIVISION The Catawba Nuclear Station Radiation Protection Section parti:ipated in a Quality Assurance audit in May 1997. This audit was conducted by the Nuclear Assessment and Issues Division, Regulatory Audit Group. There was one recommendation from this audit to evaluate broadleaf vegetation sampling requirements. A new broadleaf sampling site was added to the ;
program in August 1997 as a result of this audit.
Radiological and Environmental Services participated in a Quality Assurance audit in February,1997. This audit was conducted by the Nuclear Assessment and Issues Division, Regulatory Audit Group. There were no findings from this audit.
5.1.5.4 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS i The Catawba Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in 1997. There were no findings from this audit. Radiological and Environmental Services was not audited by the NRC in 1997.
4 Section 5 - Page 2
f i
5.1.5.5 NRC/ STATE OF N.C. SAN 1PLING INTERCONIPARISON PROGRANI i i
l Radiological and Environmental Services routinely participates with the i
Bureau of Radiological Health of the State's Department of Health and Environmental Control (DiiEC) in an intercomparison program.
Radiological and Environmental Services sends air, water, milk, vegetation, l sediment, and fish samples which have been collected to the State of South l Carolina DHEC Laboratory for intercomparison analysis.
l 5.1.5.6 STATE OF N.C. TLD INTERCONIPARISON PROGRANI Radiation Dosimetry and Records routinely participates in a TLD ,
l intercomparison program. Every six to eight months, the State of North l 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 1997 is documented in Table 5.0-C.
5.2 CONTRACTOR LABORATORIES No contractor laboratories were used during 1997.
l l
l l
l l
i Section $ - Page 3
1 i
i l
l TABLE 5.0-A 1 l
1 U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM i
1997 CROSS-CIIECK RESULTS FOR TIIE RADIOLOGICAL & ENVIRONMENTAL SERVICES LABORATORY Gamma in Water:
Reference Geometry Nuclide Acceptance Range Reference Reported Cross-Check Date (pCi/ liter) Value Value Status *
(pCi/ liter) (pCi/ liter) 3.5 liter 2/7/97 Marinelli l-131 70.4 - 102 86.0 94.2 PASS 4/15/97 3.5 liter Co-60 12.3 - 29.7 21.0 24.6 PASS j Marinelli Cs-134 22.3 - 39.7 31.0 31.9 PASS Cs-137 13.3 - 30.7 22.0 24.2 PASS 6/6/97 3.5 liter Co-60 9.30 - 26.7 18.0 18.0 PASS Marinelli Zn-65 82.7 - 117 100 100 PASS Cs-134 13.3 - 30.7 22.0 17.7 PASS Cs-137 40.3 - 57.7 49.0 54.3 PASS Ba-133 16.3 - 33.7 25.0 28.3 PASS 10/21/97 3.5 liter Co-60 1 34 - 18.7 10.0 11.0 PASS Marinelli Cs-134 ' .3 - 49.7 41.0 39.0 PASS Cs-137 25.3 - 42.6 34.0 34.8 PASS 10/31/97 3.5 liter 1-131 1.34 - l 8.7 10 17.56 PASS Marinelli l1/7/97 3.5 liter Co-60 18.3 - 35.7 27.0 30.7 PASS Marinelli Zn-65 61.1 - 88.9 75.0 80.0 PASS Cs-134 1.30 - 18.7 10.0 11.2 PASS Cs-137 65.3 - 82.7 74.0 76.4 PASS Ba-133 81.7 - 116 99.0 104 PASS
- Pass = Data within Control Lamals , AC = Above Control Limit, BC = Below Control Lamar Section 5. Page 4
i l
Betain Water:
Reference Geometry Nuclide Acceptance Range Reference Reported Cross-Check j Date (pCi/ liter) ' Value Value Status *
(pCi/ liter) (pCi/ liter)
Gross 1/31/97 2" Planchet Beta 6.0 - 23.4 14 7 25.0 AC" Gross 4/15/97 2" Planchet Beta 75.6 - 129 102.1 94.9 PASS Gross 7/18/97 2" Planchet Beta 6.4 - 23.8 15.1 17.0 PASS l
l Gross 10/21/97 2" Planchet Beta 131 - 156 143.4 148.3 PASS i
Gross 10/31/97 2" Planchet Beta 40.2 - 57.6 48.9 60.4 AC" Pass = Data wuthin Con:rolLumets. AC = Above ControlLimit. BC = Below ControlLamut l (1) Reported value is an average ofthree analyses, one ofwhnch was above the controllimit.
l Tritium in Water:
l Reference Geometry Nuclide Acceptance Range Reference Reported Cross-Check Date (pCi/ liter) Value Value Status *
(pCilliter) (pCi/ liter) 4/1/97 Plastic 10:10 H-3 6530 - 9271 7900 9835 ACD l
l Pass = Data withm ControlLimits , AC = Above ControlLsmit, BC = Below Control Lamot
(
(1) Reported value is an average ofthree analyses. one ofwhich was above the controllimit L
Section 5 - Page $
I l
TABLE 5.0-B DUKE POWER COMPANY INTERLABORATORY COMPARISON PROGRAM 1997 CROSS-CllECK RESULTS FOR TIIE RADIOLOGICAL & ENVIRONMENTAL SERVICES LABORATORV Gamma in Charcoal Cartridge:
Reference Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status
- 2/21/97 pCi/ total 1-131 1.50E5 - 2.66E5 2.00E5 1.98E5 PASS 6/19/97 l pCi/ total l l-131 l 72.8 - 129 l 97.0 l 104 l PASS 8/22/97 l pCi/ total l l-131 l 1.51 E5 - 2.67E5 l 2.01E5 l 2.04E5 l PASS 12/11/97 l pCi/ total l I-131 l 23.3 - 41.2 l 31.0 l 29.5 l PASS
- Pass = Data withun Control Lamats , AC = Above ControlLimit, BC = Below Control Limit Gamma in Soil:
Reference Geometry Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status
- 2/21/97 0.5 liter pCi/kg Cr-51 171 - 303 228 273 AC*
Marinelli Mn-54 41.9 - 74.4 55.9 66.5 PASS Co-58 23.3 - 41.2 31.0 33.9 PASS Fe-59 49.2 - 87 2 65.6 74.5 PASS Co-60 39.8 - 70.6 53.1 52.6 PASS Zn-65 40.1 - 71.2 53.5 52.8 PASS l 131 37.3 --66.1 49.7 51.4 PASS Cs-134 32.9 - 58.4 43.9 46.4 AC*
Cs-137 25.7 - 45.5 34.2 34.6 PASS Cc-141 92.3 - 164 123 135 PASS
- Pass = Data within Control Lamsts , AC = Above Control Lomst. BC = Below Control Lomst (1) Reported value is an average ofthree analyses, one of which was abow the control hmot Section 5 - Page 6
Gamma in Filter:
I Reference Units of Nuclide . Acceptance Rar.ge Reference Reported Cross-Check Date Activity Value Value Status
- 2/21/97 pCi/ total Cr-51 1.13E5 - 2.01 E5 1.51E5 1.55E5 PASS Mn-54 2.78E4 - 4.93E4 3.71 E4 4.07E4 PASS Co-58 1.54E4 - 2.73E4 2.0$E4 2.12E4 PASS Fe-59 3.26E4 - 5.77E4 4.34E4 5.09E4 PASS Co-60 2.65E4 - 4.69E4 3.53E4 3.70E4 PASS Zn-65 2.66E4 - 4.71 E4 3.54E4 4.28E4 PASS Cs-134 2.18E4 - 3.87E4 2.91E4 2.40E4 PASS Cs-137 1.7E4 - 3.01 E4 2.26E4 2.26E4 PASS Ce-141 6.14E4 - 1.08E5 8.18E4 8.72E4 PASS 3/20/97 pCi/ total Cr-51 216 - 383 288 289 PASS l Mn-54 98.3 - 174 131 146 PASS Co-58 44.3 - 78.5 59.0 60.1 PASS Fe-59 80.3 - 142 107 129 PASS Co-60 98.3 - 174 131 135 PASS Zn-65 92.3 - 164 123 135 PASS Cs-134 79.5 - 140 106 93.5 PASS Cs-137 63.0 - 112 84.0 87.5 PASS Ce-141 129 - 229 172 177 PASS 6/19/97 pCi/ total Cr-51 162 - 288 216 228 PASS Mn-54 69.0 - 122 92.0 93.9 PASS Co-58 63.0 - 112 84.0 87.7 PASS Fe-59 62.0 - 109 82.0 87.0 PASS Co-60 84.8 - 150 113 114 PASS Zn-65 114 - 202 152 179 PASS Cs-134 66.8 - 118 89.0 74.5 PASS Cs-137 93.8 - 166 125 130 PASS Ce 141 108 - 192 144 136 PASS
- Pass = Data warhm Control Lsmuts , AC = Above Control Lamst. BC = Below Control Lsmit Section 5. Page 7
Gamma in Filter continued:
Reference Units of Nuclide- Acceptance Range Reference Reported - Cross-Check Date Activity Value Value Status
- 9/18/97 pCi/ total Cr-51 183 - 325 244 307 AC'"
Mn-54 53.3 - 94.4 71.0 36.2 - PASS Co-58 36.8 - 65.2 49.0 55.4 PASS Fe-59 72.0 - 128 %.0 120 PASS Co-60 119 - 211 159 175 PASS Zn-65 119 - 210 158 212 AC'"
Cs-134 61.5 - 109 82.0 70.4 PASS Cs-137 64.5 - 114 86.0 81.9 PASS Ce-141 46.5 - 82.5 62.0 70.6 PASS l i
12/11/97 pCi/ total Cr-51 116 - 205 154 179 PASS Mn-54 48.0 - 85.I 64.0 77.2 PASS Co-58 30.8 - 54.5 41.0 46.3 PASS Fe-59 33.8 - 59.9 - 45.0 56.9 PASS Co-60 56.3 - 99.8 75.0 81.9 PASS l Zn-65 84.0 - 149 112 13i PASS Cs-134 59.3 105 79.0 68.3 PASS l Cs-137 61.5 - 109 82.0 87.1 PASS Cc-141 57.8 - 102 77.0 86.9 PASS j l
- Pass = Data wsthm Control Lsmuts . AC = Above Control Lumst, BC = Below ControlLumst (1) Reported value is an awrage ofthree analyses, one ofwhich vos above the controllimst.
Section 5 - Page 8
Gammain Water:
Reference Geometry Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status
- i 2/21/97 3.5 liter pCi/ liter Cr-51 257 - 455 342 449 AC*
Marinelli Mn-54 62.9 - 112 83.9 99.9 PASS Co-58 34.9 - 61.8 46.5 50.2 PASS Fe-59 73.8 - 131 98.4 109 PASS Co-60 59.8 - 106 79.7 83.7 PASS Zn-65 60.2 - 107 80.3 102 PASS l-131 55.9 - 99.1 74.5 80.8 PASS Cs-134 49.4 - 87.5 65.8 71.5 PASS Cs-137 38.5 - 68.2 51.3 54.4 PASS Cc-141 139 - 246 185 203 PASS 2/21/97 3.5 liter pCi/ liter Cr-51 5.74E4 - 1.01 E5 7.61E4 7.67E4 PASS Marinelli Mn-54 1.38E4 - 2.44E4 1.87E4 1.95E4 PASS Co-58 7.80E3 - 1.38E4 1.04E4 1.06E4 PASS Fe-59 1.64E4 - 2.91 E4 2.19E4 2.28E4 PASS Co-60 1.34E4 - 2.36E4 1.78E4 1.81E4 PASS Zn-65 1.34E4 - 2.38E4 1.79E4 1.92E4 PASS 1-131 1.25E4 - 2.21 E4 1.66E4 1.68E4 PASS Cs-134 1.10E4 - 1.96E4 1.47E4 1.37E4 PASS Cs-137 8.55E3 - 1.52E4 1.14E4 1.12E4 PASS Cc-141 3.09E4 - 5.48E4 4.12E4 4.18E4 PASS
$/29/97 0.51 iter pCi/ liter Mn-54 518 - 918 690 797 PASS Marinelli Co-58 138 -243 183 207 PASS 1 Fe-59 167 - 297 223 300 PASS Co-60 589 - 1044 785 873 PASS Zn-65 467 - 827 622 677 PASS 1-131 523 - 927 697 703 PASS Cs-134 461 - 817 614 560 PASS !
Cs-137 390 - 692 $20 530 PASS 179 - 317 238 253 PASS
{Cc-141
- Pass = Data wathun Control Limuts . AC = Above Control Lamst. BC = Below ControlLamat (2) Reported value is an average ofthree ana&ses, two of which were above the controlhmit l
Section 5 - Page 9
Gamma in Water continued:
Reference Geometry Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status
- 5/29/97 1.0 liter pCi/ liter Mn-54 518 - 918 690 780 PASS Marinelli Co-58 138 - 243 183 203 PASS Fe-59 167 - 297 223 257 PASS Co-60 589 - 1044 785 843 PASS Zn-65 467 - 827 622 740 PASS 1-131 523 - 927 697 700 PASS Cs-134 461 - 817 614 553 PASS Cs-137 390 - 692 520 523 PASS Ce-141 179 317 238 260 PASS 5/29/97 3.5 liter pCi/ liter Mn-54 518 918 690 730 PASS Marinelli Co-58 138 - 243 183 193 PASS Fe59 167 - 297 223 253 PASS Co-60 589 - 1044 785 843 PASS Zn-65 467 - 827 622 737 PASS 1 131 523 - 927 697 727 PASS Cs-134 461 - 817 614 587 PASS Cs-137 390 - 692 $20 547 PASS Cc-141 179 - 317 238 253 PASS 5/29/97 3.5 liter pCi/ liter Cr-51 5.59E3 - 9.92E3 7.46E3 8.06E3 PASS l Marinelli Mn-54 1.25E4 - 2.22E4 1.67E4 1.80E4 PASS Co-58 3.33 E3 - 5.91 E3 4.44E3 4.63E3 PASS I Fe-59 4.04E3 - 7.17E3 5.39E3 5.93E3 PASS Co-60 1.43E4 - 2.53E4 1.90E4 2.03E4 PASS Zn-65 1.13E4 - 2.01E4 1.51E4 1.70E4 PASS 1-131 1.27E4 - 2.25E4 1.69E4 1.80E4 PASS Cs-134 1.12E4 - 1.98E4 1.49E4 1.40E4 PASS Cs-137 9.45E3 - 1.68E4 1.26E4 1.30E4 PASS
( Ce-141 4.32E3 - 7.67E3 5.77E3 5.97E3 PASS
Section 5 - Page 10
Gammain Watercontinued: \
l Rzference Geometry Units of Nuclide Acceptance Range Reference Reported Cross-Check " i Date Activity Value ' Value Status *
]
8/25/97 0.5 liter pCi/ liter Cr-51 3.08E4 - 5.45E4 4.10E4 4.20E4 PASS Marinelli Mn-54 5.17E3 9.16E3 6.89E3 7.52E3 PASS i Co-58 4.23E3 - 7.50E3 5.64E3 6.25E3 PASS l Fe-59 9.60E3 1.70E4 1.28E4 1.42E4 PASS l l
Co-60 1.10E4 - 1.%E4 1.47E4 1.59E4 PASS I Zn-65 1.17E4 - 2.07E4 1.56E4 1.79E4 PASS l
l-131 1.82E4 - 3.22E4 2.42E4 2.29E4 PASS Cs-134 5.79E3 - 1.03E4 7.73E3 7.26E3 PASS f
I Cs-137 5.95E3 - 1.%E4 7.93E3 7.98E3 PASS Ce-141 7.09E3 - 1.26E4 9.45E3 9.51E3 PASS l 8/25/97 1.0 liter pCi/ liter Cr-51 3.08E4 - 5.45E4 4.10E4 4.28E4 PASS I Marinelli Mn-54 5.17E3 - 9.16E3 6.89E3 7.40E3 PASS Co-58 4.23E3 - 7.50E3 5.64E3 6.36E3 PASS Fe-59 9.60E3 - 1.70E4 1.28E4 1.41E4 PASS l Co-60 1.10E4 - 1.%E4 1.47E4 1.57E4 PASS Zn-65 1.17E4 - 2.07E4 1.56E4 1.74E4 PASS j 1-131 1.82E4 - 3.22E4 2.42E4 2.38E4 PASS Cs-134 5.79E3 - 1.03E4 7.73E3 7.42E3 PASS l
Cs-137 5.95E3 - 1.%E4 7.93E3 8.13E3 PASS Ce-141 7.09E3 - 1.26E4 9.45E3 9.87E3 PASS 8/25/97 3.5 liter pCi/ liter Cr-51 3.08E4 - 5.45E4 4.10E4 4.29E4 PASS Marinelli Mn-54 5.17E3 - 9.16E3 6.89E3 7.38E3 PASS I Co-58 4.23E3 - 7.50E3 5.64E3 6.21E3 PASS l Fe-59 9.60E3 - 1.70E4 1.28E4 1.40E4 PASS Co-60 1.10E4 - 1.96E4 1.47E4 1.57E4 PASS i Zn-65 1.17E4 - 2.07E4 1.56E4 1.70E4 PASS l
l-131 1.82E4 - 3.22E4 2.42E4 2.43E4 PASS Cs-134 5.79E3 - 1.03E4 7.73E3 7.50E3 PASS Cs-137 5.95E3 - 1.%E4 7.93E3 7.85E3 PASS Cc-141 7.09E3 - 1.26E4 9,45E3 9.78E3 PASS
- Pass = Data withm Controlbmits , AC = Above ControlDmit. BC = Below ControlLimit Section 5 - Page i1
Gamma in Water continued:
Reference Geometry Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status
- 8/25/97 3.5 liter pCi/ liter Cr-51 '
359 - 636 478 506 PASS Marinelli Mn-54 60.2 - 107 80.3 88.8 PASS Co-58 49.4 - 87.5 65.8 77.2 PASS Fe-59 112 - 198 149 166 PASS Co-60 129 - 229 172 177 PASS Zn-65 136 - 241 181 206 PASS I-131 212 - 375 282 212 BCW Cs-134 67.5 - 120 90.0 88.8 PASS Cs-137 69.3 - 123 92.4 92.8 PASS Cc-141 82.5 - 146 110 119 PASS 12/2/97 3.5 liter pCi/ liter Cr-51 101 - 178 134 144 PASS Marinelli Mn-54 162 - 287 216 236 PASS Co-58 62.6 - 1 I I 83.5 94 PASS Fe-59 80.3 - 142 107 118 PASS Co-60 416 - 737 554 580 PASS Zn-65 344 - 609 458 512 PASS 1-131 251 - 444 334 338 PASS Cs-134 206 -366 275 268 PASS Cs-137 230- 408 307 3% PASS Ce-141 33.5 - 59.3 44.6 50.2 PASS
- Pass = Data withm Control Limits , AC = Above Control Lumut. BC = Below ControlLimit (3) Reported value is an overage ofthree analyses. one ofwhich was below the controllimit.
l l
Section 5 - Page 12
lodinein Water:
Reference Units of Nuclide . Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status
- 2/24/97 pCi/ liter 1-131 8.01 - 14.3 10.8 11.4 PASS 5/29/97 l pCi/ liter 65.0. 115 86.4 AC(4 l l-131 l l l 113 l
7/2/97 pCi/ liter 144 - 255 l l l131 l l 192 l 215 l PASS 7/2/97 l pCi/ liter I 131 66 - 117 87.7 76 PASS l l l l 8/25/97 l pCi/ liter l l-131 l 16 28 20.8 24 PASS l l l pCi/ liter 5.19 - 9.21 6.92 9.05 AC'"
8/25/97 l l l-131 l l l l 10/6/97 pCi/ liter l l-131 l 36.0 63.8 48.0 45.7 PASS l l l 10/6/97 l pCi/ liter l I-131 l 24.1 42.8 32.2 31.2 PASS l l l 12/2/97 l pCi/ liter l I-131 l 31.1 - 55.2 l 41.5 l 42.6 l PASS 12/2/97 pCi/ liter 141 - 250 188 212 PASS l l I-131 l l l l
- Pass e Data withm Contrvilimits, AC = Above Control Limit. BC = Below ContmlLnmit (2) Reported value o an average ofthree analyses, one of which was above the controllimit..
Iodinein Milk:
Reference Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status
- 2/19/97 pCi/ liter I-131 72.4 - 128 96.5 104 PASS pCi/ liter 1 131 81.2 - 144 108 130 PASS 5/29/97 l l l l 7/2/97 pCi/ liter 167 - 297 223 219 PASS l l I-131 l l l pCi/ liter 1131 9.32 - 16.5 12.4 15.51 PASS 8/25/97 l l l l l 12/2/97 pCi/ liter 96.2 - 171 128 131 PASS l l l-131 l l l Section 5 - Page 13 i
Iodine in Milk continued:
Reference Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status
- 12/2/97 pCi/ liter l 131 31.5 - 55.9 42.0 45.8 PASS l
- Pass = Data withm ControlLsmits, AC = Abow Control Lsmat. BC = Below Control Lsmit Tritium in Waten Reference - Units of Nuclide Acceptance Range Reference . Reported Cross-Check Date Activity Value Value Status
- 2/19/97 pCi/ liter H-3 1013 - 1796 1350 1573 PASS l 2/19/97 pCi/ liter H-3 19050 - 33782 25400 25113 PASS l l l l l l 5/29/97 l pCilliter l H-3 609 - 1080 813 978 PASS l l l l 5/29/97 l pCi/ liter l H3 l 11985 - 21253 l 15980 l 15300 PASS l
pCi/ liter H-3 1298 - 2302 1731 1918 PASS 5/29/97 l l l l l l 5/29/97 pCi/ liter H-3 14768 - 26188 1 % 90 17646 PASS l l l l l l 8/25/97 pCi/ liter H-3 4402 - 7806 5869 5574 PASS l l l l l l 8/25/97 pCi/ liter H-3 268- 475 357 342 PASS l l l l l l
12/2/97 pCi/ liter H-3 7665 - 13593 10220 11141 PASS l l l l l
Section 5 - Page 14
Beta in Water:
Reference Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status
- Gross 3/20/97 pCi/ liter Beta 108 - 192 144 172 PASS Gross 6/19/97 pCi/ liter Beta 104 - 185 139 131 PASS l
Gross 9/18/97 pCi/ liter Beta 218 - 387 291 287 PASS Gross 12/11/97 pCi/ liter Beta 173 - 306 230 225 PASS
Beta in Air Particulate:
Reference Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status *
~~
Gross 2/21:97 dpm/ total Beta 4928 - 8739 6571 6729 PASS Gross 2/21/97 pCi/ total Beta 2235 - 3963, 2980 2828 PASS Gross 8/22/97 pCi/ total Beta 3570 - 6331 4760 4830 PASS
- Pass = Data wsthsn Contra;Lamsts , AC = A bove Control Limit. BC - Below Control Lemst Section 5 - Page 15
TABLE 5.0-C STATE OF NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCES 1997 ENVIRONMENTAL DOSIMETER CROSS-CIIECK RESULTS Radiation Dosimetry &
Cross-Check State of N.C. Delivered Records Acceptance Date Value Reported Value Criteria (mR) (mR) +/- 10 %
Jun-97 80.0 78.0 Pass Section 5 - Page 16
6.0 REFERENCES
6.1 Catawba Selected License Commitments 6.2 Catawba Technical Specifications 6.3 Catawba Updated Final Safety Analysis Review 6.4 Catawba Offsite Dose Calculation Manual 6.5 Catawba Annual Environmental Operating Report 1985 - 1996 6.6 Catawba Annual Effluent Report 1985 - 1997 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 I.
6.10 Radiological and Environmental Services Operating Procedures 6.11 NUREG/CR-1276, Users Manual for LADTAP II- A Computer Program for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents.
6.12 NUREG - 0597, Users Guide to GASPAR Code Section 6 - Page 1
APPENDIX A ENVIRONMENTAL SAMPLING ANALYSIS PROCEDURES Appendix A - Page 1 i
APPENDIX A ENVIRONMENTAL SAMPLING AND ANALYSIS PROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at Catawba Nuclear Station was required to ensure compliance with Station Selected Licensee Conunitments. Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved.
Environmental sampling and analyses were performed by Radiological and Environmental Services, Dosimetry and Records, Fisheries and Aquatic Ecology.
This appendix describes the environmental sampling frequencies and analysis procedures by media type.
I. CHANGE OF SAMPLING PROCFDURES Broadleaf vegeLeion location 222 (N sector, 0.7 miles) was added to the REMP to comply with SLC requirements to sample broadleaf vegetation at each of two offsite locations with the highest predicted annual average ground level D/Q.
II. DESCRIPTION OF ANALYSIS PROCEDURES Gamma spectroscopy analyses are performed using high purity germanium gamma detectors and Canberra analytical software. Designated sample volumes are transferred to appropriate counting geometries and analyzed by gamma spectroscopy. Perishable samples such as fish and broadleaf vegetation are ground to achieve a homogeneous mixture. Soils and sediments are dried, sifted to remove foreign objects (rocks, clams, glass, etc.) then transferred to appropriate counting geometry. 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 instmment performance and sample preparation technique are acceptable.
Appendix A - Page 2
Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by gas-flow proportional counters. Samples are batch processed with a 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 1997.
IV. SAMPLING AND ANALYSIS PROCEDURES A.I AIRBORNE PARTICULATE 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. NNt!)
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
A.3 SURFACE WATER Biweekly composite samples were collected at each of three locations. A gamma analysis was performed on the monthly composites. Tritium analysis was performed on the quarterly composites. The composites were collected biweekly from the locations listed below.
Location 208 = Discharge Canal (0.5 mi. S)
Location 211 =
Wylie Dam (4.0 mi. ESE)
Location 215 = River Pointe - Hwy 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 MILK Biweekly grab samples were collected at each of three locations. A gamma and low-level Iodine-131 analysis was performed on each sample. 'Ihe biweekly grab samples were collected from the locations listed below.
Location 209 = Wood Dairy -(6.0 mi. SSW)
Location 219 =
Pursley Dairy -(5.7 mi. SW)
Location 221 = Oates Dairy-(14.5 mi. NW)
A.6 HROADLEAF 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) l Appendix A . Page 4
A.7 FOOD PRODUCTS Monthly samples were collected when available during the harvest season at one location. A gamma analysis was performed on each sample. The samples were collected from the location listed below.
Location 253 = Cloninger Irrigated Garden (2.1 mi. SSE)
A.8 FISH Semiannual samples were collected at each of two locations. A gamma analysis was performed on the edible portions of each sample. Boney fish (i.e. Sunfish) were prepared whole minus the head and tail portions. The samples were collected from the locations listed below.
Location 208 = Discharge Canal (0.5 mi. S)
Location 216 = Hwy 49 Bridge (4.0 mi. NNE)
A.9 SHORELINE SEDIMENT Semiannual samples were collected at each of three locations. A gamma analysis was performed on each sample following the drying and removal of rocks and clams. The samples were collected from the locations listed below.
Location 208 = Discharge Canal (0.5 mi. S)
Location 210 =
Ebenezer Access (2.3 mi. SE)
Location 215 =
River Pointe - Hwy 49 (4.2 mi. NNE)
A.10 HOTTOM 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-lM = Closest to RL Discharge Location 208-2M = Approximate midpoint of Discharge Canal Location 208-3M = SiM 208 Surface Water sampling pier vicinity Appendix A - Page 5
A.11 DIRECT GAMMA RADIATION (TLIM Thermoluminescent dosinaters (TLD) were collected quarterly at forty locations.
A gamma exposure rate was determined for each TLD. The TLDs were placed as indicated below.
An inner ring of 16 TLDs, one in each meteorological sector in the general area of the site boundary.
An outer ring of 16 TLDs, one in each meteorological sector in the 6 to 8 kilometer range.
The remaining TLDs were placed in special interest areas such as population centers, residential areas, schools, and at three control locations.
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 8,1997 and completed on July 10,1997 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.
Appendia A - Page 6 l
APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF RESULTS 1997 Appendix D - Page I
Environmental Radiological Monitoring Program Summary F:cility: Catawba Nuclear Station Docket No. 50-413,414 Locatim: York County, South Carolina Report Period: OI-JAN-1997 to 31-DEC-1997 T ta All Indicator Control ou i e Pithway Limit of Annual Mean Number . Locations Location Report Sampled Detection Name, Distance, Direction of Meas.
Unit of Analyses #*" '"* " * "
Measurement Performed (LLD) Mean Range Mean Range Range Code Air Ptrticulate 217 (pCi/m3) (10.3 mi SSE)
BETA 260 1.00E-02 2.65E-2 (208/208) 212 2.83E-2 (52/52) 2.28E-2 (52/52) 0 1.04E 6.48E-2 (3.3 mi E) 1.09E 6.48E-2 1.08E 5.08E-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 1-131 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 If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 1/30M8 10:29 AM Appendix B Page 2
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: Ol-J AN-1997 to 31-DEC-1997 tal All Indicator Control ou i e Pathway g Limit of g, Annual Mean Sampled Detection Location Report Name, Distance, Direction 7 Mm Unit of Analyses Mean (Fraction) Location
} **" "E' **" E#
Measurement Performed Range Code Air Radioiodine 217 (pCi/m3)
(10.3 mi SSE)
CS-134 260 5.00E-02 0.00(0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 260 6.00E-02 0.00 (0/208) 0.00(0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 I-131 260 7.00E-02 0.00 (0/208) 0.00 (0/52) 0.00 (0/52) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 1/30/98 10:29 AM Appendix B - Page 3 i
J
Environmental Radiological Monitoring Program Sumn:ary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: OI-JAN-1997 to 31 DEC-1997 Medium or Type and Total Lower No. of Non.
All Indicator Control Routine Pathway Number Limit of . Annual Mean .
Sampled of Detection Name, Distance, Direction M
Unit of Analyses Mean (Fraction) Locatien Measurement Performed (LLD) Mean Range Mean Range Range Code Drinking Water 218 (pCi/ liter)
(13.4 mi NNE)
BAl.A 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 3.74 (11/13) 214 3.74 (11/13) 3.15 (13/13) 0
~
0.88 - 6.78 (7.3 mi SE) 0.88 - 6.78 1.71 - 5.47 CO-58 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 26 15 0.00 (0/13) 0.00 (0/13) 0.00(0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 26 18 0.00 (0/13) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00
'FE-59 26 30 0.00(0/I3) 0.00 (0/I3) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 l{-3 8 2000 354 (4/4) 214 354 (4/4) 228 (1/4) 0 216 - 480 (7.3 mi SE) 216- 480 228 - 228 l-131 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/I3) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 M N-54 26 15 0.00 (0/13) 0.00 (0/13) 0.00 (0/I3) 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/I3) 0.00 (0/I3) 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 If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 1/30M8 10:29 AM Appendix B - Page 4 l
Environmental Radiological Monitoring Program Summary Focility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: Ol-J AN-1997 to 31-DEC-1997 Medium or Type and Total Lower No. of Non-All Indicator Control Routine Pathway Number Limit of Annual Mean Sampled of " * ' " "
Detection Name, Distance, Direction M s Unit of Analyses Mean (Fraction) Location Measurement Performed (LLD) Range Mean Range Mean Range Code 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 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 39 15 0.00(0/26) 0.00 (0/13) 0.00(0/I3) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-134 39 15 0.00(0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 39 18 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 _
FE-59 39 30 0.00(0/26) 0.00 (0/13) 0.00(0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 11-3 12 2000 4081(7/8) 208 7777 (4/4) 220 (1/4) 0 248 8621 (0.5 mi S) 6201 - 8621 220- 220 I-131 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 39 15 0.00 (0/26) 0.00 (0/13) 0.00(0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZN-65 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 ZR-95 39 15 0.00(0/26) 0.00 (0/13) 0.00(0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selecsed Licensee Commitments Repon Generated @ 1/30/98 10:29 AM Appendix B - Page 5 w . . -
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413.414 Location: York County, South Carolina Report Period: Ol-JAN-1997 to 31-DEC-1997 Medium or Type and Total Lower """* No. of Non-All Indicator Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction
- " #E "
Meas.
Unit of Analyses Mean (Fraction) Location Measurement "" 8 '""
Performed Range Code ""8' Ground Water NO CONTROL (pCi/ liter) LOCATION BALA-140 8 15 0.00(0/8) 0.00(0/8) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 8 15 0.00(0/8) 0.00 (0/8) 0.00(0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 8 15 0.00(0/8) 0.00 (0/8) 0 0.00 (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 0.00 (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 0.00(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 0.00 (0/0) 0.00 - 0.00 0.00 - 0.00 0 00 - 0.00 Ii-3 8 2000 0.00(0/8) 0.00 (0/8) 0 0.00 (0/0) 0.00 - 0 00 0.00 - 0.00 0.00 - 0.00 I-131 8 15 0.00 (0/8) 0.00 (0/8) 0 0.00 (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 0.00 (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 0.00 (0/0) 0.00 - 0.00 0.00 0.00 0.00 - 0.00 ZN-65 8 30 0.00(0/8) 0.00(0/8) 0 0.00 (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 0.00(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 reage indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ l/30'98 10:30 AM Appendix B - Page 6
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carollas Report Period: Ol-JAN-1997 to 31-DEC-1997 Medium or Type and Total Lower No. of Non-g, g; Location with Highest Control Routine Pathway Number Limit of Annual Mean ca 1 n Sampled of Detection Name, Distance, Direction ePod Meas.
Unit of Analyses Mean (Fraction) Location Measurement Performed (LLD) Mean Range Mean Range Range Code Milk 221 (pCi/ liter) (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 0.00 - 0.00 CS-134 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 CS-137 78 18 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 1-131 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 LLI-131 78 1 0.00(0/52) 0.00 (0/26) 0.00 (0/* 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0. . ,
Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ l/30/98 10:30 AM Appendix B - Page 7
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 location: York County, South Carolina Report Period: Ol-JAN-1997 to 31-DEC-1997 Medium or Type and Total Lower No. of Non-q g, g; Location with Highest Pathway 9, Control Routine Number Limit er Annual Mean .
Locations Location Report Sampled of Detection Name, Distance, Direction Meas.
Unit of Analyses Mean (Fraction) Location Measurement Performed (LLD) Mean Range Mean Range Range Code Broadleaf 217 Vegetation (10.3 mi SSE)
(pCi/kg-wet)
CS-134 40 60 0.00 (0/32) 0.00(0/9) 0.00 (0/8) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 40 80 61.9 (6/32) 201 75.7(5/9) 0.00 (0/8) 0 42.7 - 98.9 (0.5 mi NE) 42.7 -98.9 0.00 - 0.00 I-131 40 60 0.00 (0/32) 0.00(0/9) 0.00(0/8) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction)
Zero range indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments i
Report Generated @ 1/30/98 10:30 AM Appendix B - Page 8
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-1997 to 31-DEC-1997 Medium or Type and Total Lower No. of Non-
,, g; Location with Highest Control Routine Pathway Number Limit of . Annual Mean .
xations Na 1 n Sampled of Detection Name, Distance, Direction ePod Meas.
Unit of Analyses Mean (Fraction) Location Measurement Performed can ange en ange Range Code Food Products NO CONTROL (pCi/Lg-wet) LOCATION CS-134 5 60 0.00 (0/5) 0.00(0/5) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.')0 0.00 - 0.00 CS-137 5 80 0.00 (0/5) 0.00 (0/5) 0.00 (0/0) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 1-131 5 60 0.00(0/5) 0.00 (0/5) 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 If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 2/4/98 6:16 AM Appendix B - Page 9
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Imstica: York County, Soutb Carolina Report Period: Ol-JAN-1997 to 31-DEC-1997*
No. of Non-Medium or Type and Total Lower L cati n with liighest All Indicator Control Routine - -
Pathway Number Limit of Armual Mean Sampled of Detection Name, Distance, Direction P Me s Uni' of Analyses Mean (Fraction) Location Measurement Performed
)
Range Code **" #"E# **" ""E' Fish 216 (pCi/kg-wet) (*.0 mi NNE) ,
s CO-58 24 130 49.3 (3/12) 208 49.3 (3/12) 0.00 (0/12) 0 24.1 - 87.2 (0.5 mi S) 24.1 - 87.2 0.00 - 0.00 t CO-60 24 130 9.88 (1/12) 9.88 - 9.88 208 (0.5 mi S) 9.88 (1/12) 9.88 - 9.88 0.00 (0/12) 0.00 - 0.00 0
]
CS-134 24 130 0.00 (0/12) 0.00 (0/12) 0.00 (0/12) 0 '-
O.00 0.00 0.00 - 0.00 0.00 - 0 00 CS 137 24 150 27.4 (9/12) 208 27.4 (9/12) 5.38 (1/12) 0 , .
14.7 - 49.9 (0.5 mi S) 14.7 - 49.9 5.38 - 5.38 FE-59 24 260 0.00 to/12) 0.00 (0/12) 0.00 (0/12) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 2'4 130 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 If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments
- Includes allfish samples collectedfor period 1/1/97 - 12/31/97 (First throughfourth quarter sampling) s Report Generated @ l/30/98 10:31 AM Appendix B Page 10
Environmental Radiological Monitoring Program Summary Facility: Catanba Nuclear Station Backet No. 50-413.414 Location: York County. South Carolina Report Period: 01-JAN-1997 to 31-DEC-1997*
No. of Non-Medium or Type and Total Lower All Indicator Control Routine Pathway Number Limit of Armual Mean "I'. "* ""."
Sampled of Detection Name, Distance, Direction M s Unit of Analyses Mean (fraction) Location Measurement Performed (LLD) Mean Range Mean Range Range Code Shoreline 215 Sediment (4.2 mi NNE)
(pCi/kg-dry)
CO-58 20 0 391(12/16) 208-3S 590 (4/4) 0.00 (0/4) 0 138 - 818 147 - 818 0.00 0.00 CO-60 20 0 428(12/16) 208-3S 764 (4/4) 0.00(0/4) 0 73.7 - 1437 272 - 1437 0.00 - 0.00 CS-134 20 150 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 20 180 90.7 (11/16) 208-3S 143 (4/4) 0.00 (0/4) 0 21.9 212 68.4 212 0.00 - 0.00 MN-54 20 0 52.8(9/16) 208 3S 69.6(4/4) 12.8 (1/4) 0 18.1 - 122 37.8 - 122 12.8 - 12.8 SB-125 20 0 144 (5/16) 208-IS 176 (1/4) 0.00 (0/4) 0 67.9 - 176 176 - 176 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 shoreline sediment collectedforperiod 1/1/97 - 1231/97 (First throughfourth quarter sampling)
Report Generated @ 1/30/98 10:31 AM Appendix D - Page 1l
Environmental Radiological Monitoring Program Summary
' Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-1997 to 31 DEC-1997*
No. of Non-Medium or Type and Total Lower * "*
- All Indicator Control Routine Pathway Number Limit of ;9 Annual Mean Location Report 2 Sampled of Detection Name, Distance, Direction Mm Unit of Analyses Mean (Fraction) Location Measurement Performed (LLD) Mean Range Mean Range Range Code Bottom NO CONTROL Sediment LOCATION (pCi/kg-dry)
CO-58 12 0 627(7/12) 208 - 1M 934 (4/4) 0.00 (0/12) 0 181 - 1872 470 - I870 0.00 - 0.00 CO-60 12 0 6493 (12/12) 208 - 2M 14375 (4/4) 0.00 (0/12) 0 378 - 10750 10750 - 16420 0.00 - 0.00 CS-134 12 0 0.00 (0/12) 0.00 (0/4) 0.00 (0/12) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 12 0 385(12/12) 208 - 2M 749 (4/4) 0.00 (0/12) 0 <
77.8 - 749 431 - 749 0.00 - 0.00 MN-54 12 0 177 (10/12) 208 - 2M 317 (4/4) 0.00 (0/12) 0 49.5 405 238 - 405 0.00 - 0.00 NB-95 12 0 40.6 (2/12) 208 - 1M 40.6(2/4) 0.00 (0/12) 0 19.1 - 62.1 19.1 - 62.1 0.00 0.00 SB-125 12 0 692 (9/12) 208 - 2M i181 (4/4) 0.00 (0/12) 0 136 - 1548 986 - l548 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 1/1/97 - 12/31/97 (First throughfourth quarter sampling)
Report Generated @ 2/2/98 3:02 PM Appendix B Page 12
Environmental Radiological Monitoring Program Summary Facility: Catawba Nuclear Station Docket No. 50-413,414 Location: York County, South Carolina Report Period: 01-JAN-1997 to 31-DEC-1997 Medium or T ta Y' Limit of All Indicator Annual Mean Control I outin Pathway Sampled Number "" " "
Detection Name, Distance, Direction of Meas.
Unit of Measurement "" YS**
(LLD)
M an Range Mean Range pg d R ge 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 18.l(147/147) 229 24.0(4/4) 14.4 (12/12) 0 10.7- 26.8 t0.8 mi NW) 22.6 25.8 10.0 - 21.4 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 j Report Generated @ 3/12/98 2:10 PM Appendix B Page 13
APPENDIX C SAMPLING DEVIATIO.NS 't UNAVAILABLE ANALYSES Appendix C Page 1
APPENDIX C CATAWBA NUCLEAR STATION SAMPLING DEVIATIONS & UNAVAILABLE ANALYSES DEVIATION & UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair IW Inclement Weather SL Sample Loss / Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Torn Filter Pl Power Interrupt VN Vandalism PM Preventive Maintenance C.1 SAMPLING DEVI ATIONS Air Particulate and Air RadioiodineS Scheduled Actual Reason Location Collection Collection Code Corrective Action Dates Dates Power to sampler was interrupted due to demolition work in site vicinity. Local power operations service center was 200 4/23 - 4/30/1997 4/23 - 4/29/1997 PO contacted to restore power to air sampler.
Power restored to sampler following 200 4/30 - 5/7/1997 5/1 - 5/7/1997 PO demolition work in site vicinity.
Sampler plug became loose during composite period and power to sumpler was interrupted. The sampler plug was adequately secured during at the next 217 7/23 - 7/30/1997 7/23 - 7/24/1997 OT collection.
Surface Water Scheduled Actual Reason Location Collection Collection Code Corrective Action Dates Dates Water sampler was temporanly tumed ofTfor required maintenance and repair 215 6/18 - 7/2/1997 6/20 - 7/2/1997 PS to composite pump.
Sampler pump inoperable. Work request 215 9/10 - 9/24/1997 9/15 - 9/24/1997 PS submitted for repair C.2 UNAVAILAllLE ANAIMSES There were no unavailable samples for 1997.
Appendix C . Page 2
APPENDIX D -
ANALYTICAL DEVIATIONS I
e l
Appendix D Page i
APPENDIX D CATAWBA NUCLEAR STATION ANALYTICAL DEVIATIONS DEVIATION & UNAVAILABLE REASON CODES BF Blown Fuse PO Power Outage FZ Sample Frozen PS Pump out of service / Undergoing Repair IW Inclement Weather SL Sample Loss / Lost due to Lab Accident LC Line Clog to Sampler SM Motor / Rotor Seized OT Other TF Torn Filter PI Power Interrupt VN Vandalism PM Preventive Maintenance TLD Scheduled Actual Reason Location Collectic.n Dates Collection Dates Code Corrective Action TLD was collected on normally scheduled collection dates. TLD had phosphor damage on all elements which was discovered when analysis 240 9/25 - 12/26/1997 9/25 - 12/26/1997 OT was attempted.
I I
Appendix D Page 2
A.PPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RESULTS This appendix includes all of the sample analysis reports generated from each sample medium for 1997. 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 fluntersville, North Carolina.
Appendix E - Page 1