ML20217M615
| ML20217M615 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/31/1997 |
| From: | Barron H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9805050069 | |
| Download: ML20217M615 (92) | |
Text
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, ,.. McGuire Nudear Station MG01VP 12700 H2gers Ferry Rd.
Huntenville, NC 28078-9340 H. B. Barron l Vice Prendent, McGuire (704) 875-4800 OFFICE i Nudear Generation Department (704) 875-4809 FAX l April 28, 1998 U. S. Nuclear Regulatory Commission Attention: Document Control Desk ! Washington, D.C. 20555 ) l
Subject:
McGuire Nuclear Station l Docket Nos. 50-369 and 50-370 Annual Radiological Environmental Operating Report j Please find attached the McGuire Nuclear Station Annual Radiological Environmental Operating Report for 1997 pursuant to McGuire Unit 1 and Unit 2 Technical Specification 6.9.1.6. l2 Questions with respect to this report should be directed to Kay Crane, at (704) 875-4306. Very truly yours, lY H. B. Barron, Vice President McGuire Nuclear Station i Mr. Frank Rinaldi, Project Manager Mr. Dayne Brown Office of Nuclear Reactor Regulation Division of Radiation Protection U. S. Nuclear Regulatory Commission P.O. Box 27687 Washington, D.C. 20555 Raleigh, N.C. 27611-7687 j j Mr Luis Reyes ANI Library 1 U. S. Nuclear Regulatory Commission Town Center, Suite 300S l Region II 29 South Main Street 101 Marietta Street, NW - Suite 2900 West Hartford, CT Atlanta, Georgia 30323 06107-2445 1 Mr. Scott Shaeffer l Senior Resident Inspector l McGuire Nuclear Site I
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B Duke Ed Energy ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DUKE POWER COMPANY MCGUIRE NUCLEAR STATION Units 1 and 2 1997
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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 . . . 23 3.0 Interpretation of Results . . 3-1 3.1 Airborne Radioiodine and Particulates . . 3-2 3.2 Drinking Water . . . 3-5 3.3 Surface Water . . . .
. 3-7 3.4 Milk . . . . . . . 3-9 3.5 Broadleaf Vegetation. . . . . 3-10 3.6 Food Products . . . .
3 11 3.7 Fish . . . . . 3-12 3.8 Shoreline Sediment . . . . 3-15 3.9 Direct Gamma Radiation . . . . . 3-17 3.10 Land Use Census . . . . 3-19 4.0 Evaluation of Dose . . . . . . 4-1 4.1 Dose from Environmental Measurements . . . 4-1 4.2 Estimated Dose from Releases . . . . . . . 4-1 4.3 Comparison of Doses. . . . . 4-1 5.0 Quality Assuran:e . . . . . 5-1 5.1 Duke Power Company's REMP. . 51 5.2 Contractor Laboratories . . . . 53 6.0 References . . . . . . 6-1 Appendices Appendix A: Environmental Sample and Analysis Procedures . A-1
- 1. Change of Sampling Procedures . A2
!!. Description of Analysis Procedures . A-2 111. Change of Analysis Procedures . . A3 IV. Sampling and Analysis Procedures . A-3 A.1 Airborne Particulate and Radioiodine . . A-3 A.2 Drinking Water . . A-3 A.3 Surface Water. A-4 A.4 Milk .
. A-4 A.5 Broadleaf Vegetation A-4 A.6 Food Products. .
A-4 A.7 Fish . A-5 i
l A.8 Shoreline Sediment. . . . . . . . . A-5 A.9 ' Direct Gamma Radiation (TLD) . . . . . . . A-5 A.10 Annual Land Use Census . . . . . . . A-6 Appendix B: Radiological Environmental Monitoring Program - Summary of Results
. Air Particulate . . . . . . . . . . . B-2 Air Radioiodine . . . . . . . . . .
s . B3 Drinking Water . . . . . . . . . . , . B-4 Surface Water . . . . . . . . . . , , B5
- Milk . . . . . . . . . . . B-6 Broadleaf Vegetation . . . . . . . . . B-7 Food Products .
. . . . . . . . . . B-8 Fish. . . . . . . . . . . . . . B-9 Shoreline Sediment . . . . . . . . . . . B-10 (
Direct Gamma Radiation (TLD) . . . . . . . B-Il Appendix C: Sampling Deviations and Unavailable Analyses . . . . C1
. C.1 - Sampling Deviations - . . . . . . . . C-2 C.2 Unavailable Analyses . . . . . . . . . C-2 Appendix D: Analytical Deviations - Lower Limits of Detection . . . D-1 Appendix E: Radiological Environmental Monitoring Program Results . . E-1 >
LIST OF FIGURES 2.1-1 Sampling Locations Map (Site Boundary) . . . . . . . 2-6 2.1 2 . Sampling Locations Map (Ten Mile Radius) . . . 27 3.1 Concentration of Gross Beta in Air Particulate . . . . . 33
- 3.2 Concentration of Tritium in Drinking Water . . . . . 35 3.3 Concentration of Tritium in Surface Water . . . . . . 3-7 3.7-1 Concentration of Cs-137 in Fish , . . . . . . . 3 13 3.7 2 Concentration of Co-60 in Fish . . . . . . . . . 3-13 3.8 1 Concentration of Cs-137 in Shoreline Sediment . . . . . 3-15 3.8 2 Concentration of Co-60 in Shoreline Sediment . . . . . . 3-16 3.9 Direct Gamma Radiation (TLD) Results . . . . . . 3-17 3.10 Land Use Census Map . . . . . . . . 3 21 LIST OF TABLES 2.1 A Radiological Monitoring Program Sampling Locations . . . . 2-4 2.1 -B Radiological Monitoring Program Sampling Locations (TLD Sites) . . 2-5 2.2-A Reporting Levels for Radioactivity Concentrations in Environmental Samples . . . . . . . . . 28 2.2 B REMP Analysis Frequency . . . . . . 2-9 2.2-C ' Maximum Values for the Lower Limits of Detection . . . . 2-10 3.1-A Mean Concentrations of Radionuclides in Air Particulate . . . 33
' 3.1-B Mean Concentrations of Air Radioiodine (1-131) . . . . . 3-4 3.2 Mean Concentrations of Radionuclides in Drinking Water . . . 3-6 3.3 Mean Concentrations of Tritium in Surface Water . . . . 3-8 3.4 Mean Concentrations of Cs-137 in Milk . . . . . 3-9 3.5 Mean Concentrations of Cs-137 in Broadleaf Vegetation . . . 3-10 3.6 Mean Concentrations of Cs-137 in Food Products . 3 11 3.7 Mean Concentrations of Radionuclides in Fish . . . 3 14 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment . 3-16 3.9 Direct Gamma Radiation (TLD) Results . . . . . . 3-18 3.10 Land Use Census Results . . . . . 3-20 ii l
4.1 A 1997 Environmental and Efiluent Dose Comparison . . . 43 4.1 -B Maximum Individual Dose for 1997 based on Environmental Measurements for McGuire Nuclear Station . . . . 45 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 Dosimeter Cross-Check Results . . . . 5 16 LIST OF ACRONYMS USED IN TIIIS TEXT (in alphabeticalorder) BW Biweekly C Control CL Critical Level DElINR Department of Environmental liealth and Natural Resources DilEC Department of }lealth and Environmental Control EPA 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 Offsite 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 TECil SPECS Technical Specifications TLD Thermoluminescent Dosimeter pCi/ml microcurie per milliliter UFSAR Updated Final Safety Analysis Report W Weekly f iii
1.0 EXECUTIVE
SUMMARY
This Annual Radiological Environmental Operating Report describes the McGuire 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 environmental data, comparisons of doses calculated from environmental measurements and effluent data, anaiysis of trends in environmental radiological data as potentially affected by station operations, and a summary of environmental radiological sampling results. Quality assurance practices, sampling deviations, unavailable samples, and program changes are also discussed. Sampling activities were conducted as prescribed by Selected Licensee Commitments 4 (SLC's). Required analyses were performed and de ection capabilities were met for all samples as required by SLC's. Supplemental analyses were performed for some media for additional information. Twelve-hundred thirty samples were analyzed comprising 1438 test results in order to compile data for the 1997 report. Based on the annual land use census, the current number of sampling sites for McGuire Nuclear Station is sufficient. 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 S LC's. Additionally, environmental radiological monitoring data is consistent with effluents introduced into the environment by plant operations. The total body dose estimated to the maximum exposed member of the public as calculated by environmental sampling data, excluding TLD results, was 3.12E-02 mrem for 1997. It is therefore concluded that station operations has had no significant radiological impact on the health and safety of the public or the environment. section 1 Page i
1 I
2.0 INTRODUCTION
2.1 SITE DESCRIPTION AND SAMPLE LOCATIONS McGuire Nuclear Station is located geographically near the center of a highly industrialized region of the Carolinas. The land is predominantly rural non-farm with a small amount ofland being used to support beef cattle and farming. Recreation in the area is confined mostly to the lake and shores of Lake Norman and Mountain Island reservoir. The McGuire site is in northwestern Mecklenburg County, North Carolina,17 miles north-northwest of Charlotte, North Carolina. The site is bounded to the west by the Catawba River channel and to the north by 32,510 acre Lake Norman.
' Lake Norman is impounded by Duke Power Company's Cowans Ford Dam Hydroelectric Station, which is located immediately west of the site and on the Catawba River channel. The tailwater of Cowans Ford Dam is the upper limit of Mountain Island Reservoir. Mountain Island Dam is located 15 miles downstream from the site. Lookout Shoals Hydroelectric Station is at the upper reaches of Lake Norman. Marshall Steam Station is located on the western shore of Lake Norman,
.approximately 16 miles upstream from the site (reference 6.3). The site exclusion radius is 2500 feet.
Tables 2.1-A and 2.1-B define the sampling and TLD locations for the McGuire Radiological Monitoring Program. Figures 2.1-1 and 2.1-2 illustrate these locations as compared to McGuire Nuclear Station. 2.2 SCOPE AND REOUIREMENTS OF THE REMP An environmental monitoring program has been in effect at McGuire Nuclear Station since 1977, four years prior to operation of Unit 1 in 1981. The preoperational program provides data on the existing environmental radioactivity levels for the site and vicinity which may be used to determine whether increases in environmental levels are attributable to the station. The operational program provides surveillance and backup support of detailed effluent monitoring which is necessary to evaluate the significance, if any, of the contributions to the existing environmental radioactivity levels that result from station operation. This monitoring program is based on NRC guidance as reflected in the Selected Licensee Commitments Manual, with regard to sample media, sampling locations, sampling frequency, and analytical sensitivity requirements. Indicator and control locations were established for comparison purposes to distinguish radioactivity of station origin from natural or other " man-made" environmental radioactivity. The environmental monitoring program also verifies projected and anticipated radionuclide concentrations in the environment and related exposures from releases of radionuclides from McGuire Nuclear Station. This program satisfies the requirements of Section IV.B.2 of Appendix I to 10CFR50 and provides surveillance of all appropriate critical exposure pathways to man and protects vital interests of the company, public, and state and federal agencies concerned with the environment. Reporting levels for radioactivity found in environmental samples are listed in Table 2.2-A. Table 2.2-B lists the REMP analysis and frequency schedule. ) Section 2. Page ! ) )
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 Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results
. are shown in Table 3.10.
Participation in an interlaboratory comparison program as required by Selected Licensee Commitments provides for independent checks on the precision and accuracy of measurements of radioactive material in REMP sample matrices. Such checks are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR50. A summary of the results obtained as part of this comparison program are in Section 5 of this annual report. 2.3 STATISTICAL AND CALCULATIONAL METHODOLOGY 2.3.1 ESTIMATION OF THE MEAN VALUE There was one (1) basic statistical calculation performed on the raw data resulting from the environmental sample analysis program. The calculation involved the determination of the mean value for the indicator and the control samples for each sample medium. The mean is a widely used statistic. This value was used in the reduction of the data generated by the sampling and analysis of the various media in the Radiological Environmental Monitoring Program. The following equation was used to estimate the mean (reference 6.8): N
,.i
$l
=
N Where: I = estimate of the mean, i = individual sample, N = total number of samples with a net activity (or concentration) xi = net activity (or concentration) for sample i. NOTE: " Net activity (or concentration)" is the activity (or concentration) determined to be present in the sample. No " Minimum Detectable Activity", " Lower Limit of Detection",
"Less Than Level", or negative activities or concentrations are included in the calculation of the mean.
Section 2 - Page 2
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---,,-,-w-2.3.2 LOWER LEVEL PF DETECTION. MINIMUM DETECTABLE .
ACTIVITY. ANilCRITICAL LEVEL The Lower Level of Detection (LLD), Minimum Detectable Activity (MDA), and Critical Level (CL) are used throughout the Environmental Monitoring Program. LLD - The LLD, as defined in the Selected Licensee Commitments Manual is the smallest concentration of radioactive material in a sample that will yield a net count, above the system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is an a priorilower limit of detection.' The actual LLD is dependent upon the standard deviation of the background counting rate, the counting efficiency, the sample 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 h 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 i knowledge of the release of a radionuclide from the nuclear plant is necessary to completely l interpret the trends,~ or lack of trends, determined from the environmental data. Some factors that may affect environmental levels of radionuclides include prevailing weather conditions (periods of drought, solar cycles or heavier than normal precipitation), construction in or around either the nuclear plant or the sampling location, and addition or deletion of other sources of radioactive materials (such as the Chernobyl accident). Some of these factors may be obvious while others are sometimes unknown. Therefore, how trends are identified will include somejudgment by plant personnel. Section 2 - Page 3
I l l TAI)LE 2.1-A MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Tabic 2.1-A Codes W Weekly SM Semimonthly llW Biweekly Q Quarterly M Monthly SA Semiannually C Control Sa Location Description ^"""- "'*" * *"*" '"' "'" "" '-*
.g a Port Weser Weser mesheest Predeces Leaf vea.
I19 Mt. llolly Municipal Water Supply ( 7.4 mi SSW ) BW l20 Site Boundary ( 0.5 mi NNE ) W M(b) 121 Site floundary ( 0.5 mi NE ) W
- 125 Site Inoundary ( 0.4 mi SW ) W M(b) 128 Discharge Canal Bridge ( 0.4 mi NE ) BW 129 Discharge Canal Entrance to Lake Norman ( 0.5 mi ENE) SA SA 130 Hwy 73 Bridge Downstream ( 0.5 mi SW ) SA 13l Cowans Ford Dam ( 0.6 mi WNW ) BW 132 Charlotte Municipal Water Supply ( l I.2 mi SSE ) BW I33 Cornelius ( 6.2 mi NE ) W 134 C East Lincoln JrJiigh School ( 8.8 mi WNW ) W M(b) 135 C Plant Marshall intake Canal ( lI.9 mi N ) BW 136 C Mooresville Municipal Water Supply ( 12.7 mi NNE ) BW 137 C Pinnacle Access Area ( 12.0 mi N ) SA SA 138 Henry Cook Dairy ( 3.1 mi ESE ) SM i39 William Cook Dairy ( 2.5 mi E ) SM 140 Kidd Dairy-Cows ( 2.8 mi SSE ) SM 141 C Lynch Dairy-Cows ( 14.8 mi WNW ) SM i88 5 mile radius Gsikiis ( 2.8 mi N )
M (a ) 192 Peninsula ( 2.8 mi NNE ) W 193 Site Boundary ( 0.2 mi N ) 194 M(b) East Lincoln County Wavn Supply ( 6.7 mi NNW ) flw 195 Fishing Access Road ( 0.2 mi N ) W (a) During Harvest Season (b) When Available Section 2 - Page 4 I
TABLE 2.1-B MCGUIRE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES) m. s w.= n=w m. w omw s 143 SITE BOUNDARY 0.3 miles NW 167 4-5 MILE RADIUS 4.9 miles SW 144 SITE BOUNDARY 0.5 miles NNE 168 4-5 MILE RADIUS 4.6 miles WSW 145 SITE BOUNDARY 0.5 miles NE 169 4-5 MILE RADIUS 4.0 miles W 146 SITE BOUNDARY 0.4 miles ENE 170 4 5 MILE RADIUS 4.3 miles WNW 147 SITE BOUNDARY 0.4 miles E 171 4-5 MILE RADIUS 4.0 miles NW 148 SITE BOUNDARY 0.5 miles ESE 172 4-5 MILE RADIUS 5.7 miles NNW 149 SITE BOUNDARY 0.5 miles SE - 173 SPECIAL INTEREST 8.4 miles NNW 151 SITE BOUNDARY 0.4 miles S 174 SPECIAL INTEREST 8.8 miles WNW 152 SITE BOUNDARY 0.4 miles SSW 175- CONTROL 15.5 miles WNW 153 SITE BOUNDARY 0.5 miles SW 176 SPECIAL INTEREST 11.0 miles SW 154 SITE BOUNDARY 0.5 miles W 177 SPECIAL INTEREST 8.8 miles S 156 SITE BOUNDARY 0.5 miles WNW 178 SPECIAL INTEREST 9.3 miles SE 189 SITE BOUNDARY 0.4 miles SSE 179 SPECIAL INTEREST 10.6 miles ESE
=
190 SITE BOUNDARY 0.4 miles WSW 180 SPECIAL INTEREST 12.7 miles NNE 157 4-5 MILE RADIUS 4.7 miles N 181 SPECIAL INTEREST 7.0 miles NE-158 4-5 MILE RADIUS 4.3 miles NNE 182 SPECIAL INTEREST 6.2 miles NE 159 4-5 MILE RADIUS 5.0 miles NE 183 SPECIAL INTEREST 5.8 miles S 160 4-5 MILE RADIUS 4.9 miles ENE 186 SPECIAL INTEREST 0.2 miles NNW 161 4-5 MILE RADIUS 4.7 miles E 187 SPECIAL INTEREST 0.2 miles N 162 4-5 MILE RADIUS 4.5 miles ESE 191 SITE BOUNDARY 2.8 miles NNE 163 4-5 MILE RADIUS 4.9 miles SE 1% SPECIAL INTEREST 1.0 miles S 164 4-5 MILE RADIUS 4.6 miles SSE 197 SPECIAL INTEREST 1.1 miles S 165 4-5 MILE RADIUS 5.1 miles S 198 SPECIAL INTEREST 1.3 miles S 166 4-5 MILE RADIUS 5.3 miles SSW 199 SPECIAL INTEREST 1.5 miles S
- All TLDs are collected quarterly i
Section 2 - Page 5 ): ?
McGuire Nuclear Station Figure 2.1-1 Sampling Locations Map (Site Boundary)
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McGuire Nuclear Station Figure 2.1-2 Sampling Locations Map (Ten Mile Radius)
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TABLE 2.2-A REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Analysis . Water . Air Particulates Fish. Milk Broadleaf (pCi/ liter) or Gases (pCi/kg-wet) (pCi/ liter)- Vegetation (pCi/m') - (pCi/kg-wet) - 11 3 20,000'" Mn-54 1,000 30,000 Fe 59 400 10,000 - Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I131 2 1 3 100 Cs134 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 of30,000pCuliter may be used.
I i Section 2 - Page 8
1 l
.1 TABLE 2.2-B REMP ANdLYSIS FREQUENCY Sample . Analysis Gamma Tritium Low Level Gross TLD l - Medium Schedule isotopic - I-131 Beta Air Radioiodine . Weekly X Air Weekly X Particulates Quar'erly X Composite Direct Radiation Quarterly X Monthly Surface Composite X Water Quarterly Composite X Monthly Drinking Composite X X Water _ Quarterly Composite X Shoreline Sediment Semiannually X Milk Semimonthly X X Fish Semiannually X Broadleaf Monthly Vegetation (when available) X Monthly Food Products . (during harvest X season)-
Section 2 - Page 9
TABLE 2.2-C MAXIMUM VALUES FOR TIIE LOWER LIMITS OF DETECTION Air Analysis - . Water . Particulates '- ' Fish Milk BroadLeaf Sediment (pCi/ liter) or Gases (pCi/kg-wet) . (pCi/ liter) . : Vegetation (pCi/kg-dry) (pCi/m') .(pCi/kg-wet) Gross Beta 4 H-3 2000(*) Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 l Zr-Nb-95 15 1-131 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 of30mipCuliter may be used. (b) Ifno drinking waterpathway exists, the LLD ofgamma isotopic analysis may be used. i i i I l 1
)
Section 2 - Page tv
i 3.0 INTERPRETATION OF RESULTS This section provides a summary and review of all 1997 REMP analysis results to detect and identify changes in environmental levels as a result of station operation. The radionuclides with Selected Licensee Commitments reporting levels that indicate consistent detectable activity have , been historically trended from preoperation to present. Analyses from 1977 - 1978 have been excluded since these results were much higher than the other preoperational years due to outside influences such as weapons testing. The preoperational analyses from 1981 were combined with the operational analyses from the latter part of 1981 and averaged to give one concentration for i each radionuclide for that year. The highest annual mean concentration of applicable Selected Licensee Commitments l radionuclides from the indicator locations for each media type was used for trending purposes. ; L Trending was performed by comparing annual mean concentrations to historical results. Factors { ! evaluated include the frequency of detection and the concentration in terms of the percent of the l radionuclide's NRC reporting level (Table 2.2-A). All maximum percent of reporting level values were well below the 100% action level. The highest value reached during 1997 was 2.43% for surface water tritium at the discharge canal (Location 128). Only Selected Licensee Commitments radionuclides were detected in 1997. Changes in sample location, analytical technique, and presentation of results must be considered when reviewing for trends. Calculation of the annual mean concentrations has been performed differently over the history of the REMP. During 1979-1986, all net results (sample minus i background) positive and negative, were included in the calculation of the mean. Only positive net activity results were used to calculate the mean for the other years. All negative values were replaced with a zero for calculational and graphical purposes to properly represent environmental conditions. A change in gamma spectroscopy analysis systems in 1987 ended a period when
- ' many measurements yielded detectable low-level activity for both indicator and control location l samples. It is possible that the method the previous system used to estimate net activity may have
! been vulnerable to false-positive results. This section includes tables and graphs containing the highest annual mean concentrations of any effluent related radionuclide detected since the change in analysis systems in 1987. Any zero concentrations used in tables or graphs represent activity measurements less than detectable levels. Only the specific radionuclides that represent the highest dose contributors or demonstrate ! consistent detectable activity are shown graphically. Data presented in Sections 3.1 through 3.9 support the conclusion that there was no significant increase in radioactivity in the environment around McGuire Nuclear Station due to station l operations in 1997. Similarly, there was~no significant increase in ambient background radiation levels in the surrounding areas. The 1997 land use census data, shown in Section 3.10, indicates that no program changes are required as a result of the census. Section 3.Page I
3.1 AIRBORNE RADIOIODINE AND PARTICULATES In 1997,364 particulate and radioiodine samples were analyzed,312 at six indicator locations and 52 at the control location. Particulate samples were analyzed weekly for gross beta. Gamma analysis was performed on 28 particulate composite samples,24 at the six indicator locations and four at the control location. Radioiodine samples received a weekly gamma analysis. Per Selected Licensee Commitments, if gross beta in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on individual samples. As in previous years, the location with the highest mean (2.34E-2 pCi/m') in 1997 was less than ten times the yearly mean of the control location (3.62E-2 pCi/m'). Therefore, gamma isotopic analysis was performed quarterly on composite particulate filters. No detectable gamma emitting particulate activity has been found in environmental air samples since 1987. No detectable I-131 activity in environmental air radioiodine samples was found in 1997. Cs-137 was found in five indicator samples and in one of the control samples. However, no Cs-137 was found on the corresponding particulate filters. An investigation performed in 1990 concluded that Cs-137 activity detected only on the cartridges was not attributed by station efiluents but was an active constituent of the charcoal media (reference 6.5). Therefore, the Cs-137 activity was not used to calculate doses. Figure 3.1 shows gross beta highest annual mean indicator and control location concentrations since 1985. There is no reporting level for gross beta. Table 3.1-A shows indicator and control location highest annual means for Cs-137 and gross beta. Preoperational data and ten year averages are also shown. Since no gamma activity was detected in 1997, no reporting levels were approached. Table 3.1-B gives indicator location highest annual means and control means since 1979 for I-131. Preoperational and ten year averages are also shown. No I-131 activity has been detected since 1989. Since no radionuclides were detected in 1997, no reporting levels were approached.
! y p ,- r ; 3 p., y 3
n h po 5
. . .; sM y; A ,. 'r l, *.*n
--mw ( <
3%il '. , I 4 . { s ,
,. , .f 0
'I'. ,
Air Sampling at McGuire Nuclear Station ) Secum 3 - Page 2 ) )
Figure 3.1 Concentration of Gross Beta in Air Particulate 1.00E-01 8 00E-02 i 6.00E-02 4.00E-02 !ll l 2.00E-02 "- U 0.00E+00 ! ' 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997
-Indicator Location --+-- Control Location There is no reporting levelfor Gross Beta in airparticulate Table 3.1-A Mean Concentrations of Radionuclides in Air Particulate YEAR Cs-137 Indicator Cs-137 Control Beta Indicator Beta Control (pCl/m8) (pC1/m8) (pCi/m8 ) (pCi/m8) 1979* 4.40E-3 1.47E-3 " **
1980* 6.70E-3 4.53 E-3 ** ** I 1981* 6.16E 3 5.32E-3 " ** 1982* 3.82E-3 2.29E-3 ** " 1983* 2.93 E-3 3.21 E-3 " " 1984 1.74E-3 8.29E-4 " ** 1985 1.86E 3 1.32E 3 2.44 E-2 2.40E-2 1986 4.98E-3 3.03 E-3 2.64E-2 2.52 E-2 1987 1.07E-2 7 91E 3 2.54E-2 2.59E-2 1988 0.00E0 0.00E0 7.49E-2 5.51 E-2 1989 0.00E0 0.00E0 2.22 E-2 2. I4E-2 1990 0.00EO 0.00E0 2.58E-2 2.37E-2 1991 0.00E0 0.00E0 2. I 6E-2 2.15 E-2 1992 0.00E0 0.00E0 1.92 E-2 2.02 E-2 1993 0.00E0 0.00E0 1.93 E-2 2.04 E-2 1994 0.00E0 0.00E0 2.28 E-2 2.02 E-2 1995 0.00E0 0.00E0 3.02 E-2 5.17E-2 1996 0.00E0 0.00E0 3.11 E-2 5.49E 2 ~ Average (1987 - 1996) 1.07 E-3 7.91 E-4 2.93E 2 3.15 E-2 _____ 1997 0.00E0 0.00E0 2.34E-2 3.62E-2 0.00E0 = no detectable measurements
- Radioiodines and Particulates analyzed together
** Gross Beta analysis not performed Section 3 Page 3
I i l l 1 Table 3.1-B Mean Concentrations of Air Radiolodine (I-131) Year Indicator Location (pCi/m') Control Location (pCi/m') ! 1979* 3.28E-3 1.04E-3 l 1980* 2.01 E-3 1.10E-3 l 1981* 4.17 E-3 6.27E-4 1982* 1.42E-3 2.48E-3 1983* 1.99E-3 2.01 E-4 I 1984 3.17E-3 0.00E0 l l 1985 3.15 E-3 1.04E-3 I 1986 1.27E 2 6.10E-3 1987 1.07E-2 6.60E-3 1988 0.00EO 0.00E0 1989 2.18 E-2 0.0dE0 1990 0.00E0 0.00E0 1991 0.00E0 0.00E0 l 1992 0.00E0 0.00E0 l 1993 0.00E0 0.00E0 l 1994 0.00E0 0.00E0 1 1995 0.00E0 0.00E0 1996 0.00E0 0.00E0 Average (1987 - 1996) 3.25 E-3 6.60E-4 1997 0.00E0 0.00E0 l 0.00E0 = no detectable measurements
- Radioiodines and Particulates analyzed together.
{ r l l l t SCCliOf) 3
- Page 4 I
3.2 DRINKING WATER in 1997, 52 drinking water samples were analyzed for gross inta and gamma emitting radionuclides. Thirty-nine samples were from the three indicator locations and 13 from the control location. Tritium (H-3) analyses were performed on 16 composite samples,12 at indicator locations and four at the control location. No detectable gamma activity was found in drinking water samples in 1997 and has not been detected since 1987. Gross beta analyses indicated 2.70 pCi/l at the location with the highest annual mean and 2.24 pCi/l at the control location. Tritium was detected in four of the 12 indicator composite samples taken in 1997 with the highest annual mean resulting in only 1.45% of the reporting level. The dose for consumption of water was less than one mrem per year, historically and for 1997; therefore low-level iodine analysis is not required. Figure 3.2 shows tritium highest annual mean indicator and control location concentrations with comparisons to 10% of the reporting level. Table 3.2 gives indicator location highest annual means and control means since 1979 fe tritium and gross beta. Preoperational and ten year averages are shown. There is no reporting level for gross beta. Figure 3.2 penter Concentration of Tritium in Drinking Water 2500 - q 2000 1500 ; 1000 ) . 500- IW S (
~
0 mw # ' _ : /% . 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997
-e-Indicator Location -*- Control Locaten """10% Reporting Level
) ) se.% s ) l
) ) ) Table 3.2 Mean Concentrations of Radionuclides in Drinkine Water ) Gross Heta (pCill) Tritium (pCill) YEAR ) lodicator Control - Indicator Control ( Location Location Location Location - f 1979 2.40E0 2.03E0 1.65E2 1.50E2 ) 1980 2.34E0 1.87E0 1.63E2 2.05E2 1981 2.79E0 2.41 E0 1.88E2 1.78E2 1982 2.62E0 2.43E0 2.43E2 1.45E2 f 1983 1.80E0 1.87E0 2.65E2 1.45E2 ) 1984 2.78E0 1.81EO 5.77E2 2.45E2 1985 1.88E0 1.90E0 l ) 5.93E2 4.00E2 j 1986 2.13E0 2.15E0 1.14E3 4.37E2 l ) 1987 2.30E0 2.00E0 1.35E3 7.75E2 { 1988 2.00E0 2.00E0 9.92E2 7.I 1 E2 ) ) 1989 2.80E0 2.70E0 5.62E2 0.00E0 i f 1990 3.70E0 4.30E0 7.32E2 6.ll E2 f 1991 2.40E0 2.50E0 5.22E2 0.00E0 i 1992 2.00E0 1.70E0 6.73E2 0.00E0 , 1993 2.80E0 2.40E0 0.00E0 0.00E0 f ) 1994 2.47E0 2.90E0 0.00E0 0.00E0
]
1995 4.20E0 3.30E0 3.58E2 0.00E0 l 1996 2.75E0 2.1 lE0 3.60E2 . 0.00E0 I f Average (1987 - 1996) 2.74E0 2.59E0 5.55E2 2.10E2 f 1997 2.70E0 2.24E0 2.90E2 0.00E0 ) 0.00E0 = no detectable measurements I ) I i l ) i L Section 3. Page 6
3.3 SURFACE WATER In 1997,39 surface water samples were analyzed for gamma emitting radionuclides,26 at the two indicator locations and 13 at the control location. Analyses for H-3 were performed on 12 samples, eight at indicator locations and four at the control location. No detectable gamma activity was found in - surface water samples in 1997 and has not Lg: been detected since 1988. Tritium was - 1. ; . ~ detected in six of the eight indicator
.- ^ 1 ,*. J - E1, composite samples taken in 1997 with the highest annual mean resulting in only 2.43% -
of the reporting level. .
/
o Figure 3.3 shows tritium highest annual mean indicator and control location concentrations with comparisons to 20% of ; the reporting level. Preoperational and ten 3 year averages are also shown. Table 3.3 h .._-1 gives indicator and control location highest annual means since 1979 for H-3. Surface Water Sampling at McGuire Nuclear Station Figure 3.3 pcweer Concentration of Tritium in Surface Water 4500 4000 l l l 3500 3000 2500 2000 b 1500 \ 1000 / \ 3 } ( & Q ) o :-
< M (/ \ , .h / 1 1970 1981 1983 1985 1987 1989 1991 1993 1995 1997
-e-Indicator Locabon -e-Control Location 20% Reporting Level Section 3 Page7
19 ole 3.3 Mean Concentrations of Tritium in Surface Water YEAR _ H 3 Indicator (pCl/l) H-3 Control (pCl/l) 1979 1.85E2 1.66E2 1980 2.13E2 1.93E2 1981 1.75E2 1.70E2 1982 3.30E2 1.23E2 1983 5.75E2 3.67E2 1984 4.10E2 2.65E2 1985 7.33E2 0.00E0 1986 2.33 E3 6.13E2 1987 9.20E2 7.70E2 1988 9.40E2 0.00E0 1989 8.22E2 0.00E0 1990 6.77E2 0.00E0 1991 7.53E2 0.00E0 1992 8.I3E2 0.00E0 1993 6.85E2 0.00E0 1994 0.00E0 0.00E0 1995 3.15E2 0.00E0 1996 8.08E2 ' O.00E0 Average (1987 - 1996) 6.73 E2 7.70El 1997 4.85E2 0.00E0 0.00E0 = no detectable measurements ( ) Section 3-Page 8 I
i I I l 3.4 MILK l In 1997,104 milk samples were analyzed for low level I-131 and other gamma emitting radionuclides, 78 at the three indicator locations and 26 at the control location. l ) l No detectable activity was found in milk samples in 1997. Cs-137 has not been detected in milk 1 samples since 1990 and all other radionuclides have not been detected since 1987. Table 3.4 gives indicator location highest annual means and control means since 1979 for Cs-137. Preoperational data and ten year averages are also shown. Since no activity was detected in 1997, I no reporting level- ;re approached. Table 3.4 Mean Concentrations of Cs-137 in Milk j j YEAR Cs-137 Indicator (pCl/1) Cs-137 Control (pCf/1) 1979 2.48E1 6.04E0 1980 1.72E 1 4.13E0 1981 2.04El 4.15E0 1982 1.21 El 5.20E0 1983 2.01 El 2.82E0 1984 1.48El 2.56E0 1985 1.42El 2.72E0 1986 3.74E0 3.45E0 1987 5.20E0 8.60E0 1988 3.40E0 2.90E0 1989 6.00E0 5.60E0 l 1990 5.30E0 2.60E0 ; 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) 1.99E0 1.97E0 1997 0.00E0 0.00E0 0.00E0 = no detectable measurements Section 3. Page 9 l
l 3.5 llROADLEAF VEGETATION In 1997,32 broadleaf vegetation samples were analyzed,24 at the three indicator locations l and eight at the controllocation. No detectable activity was found in vegetation samples in 1997. Cs-137 has not been l detected in vegetation samples since 1993 and all other radionuclides have not been detected l since 1987. Table 3.5 gives indicator and control l i location highest annual means since 4
! 1979 for Cs-137. Preoperational ,
and ten year averages are also ) shown. Since no activity was l detected in 1997, no reporting levels were approached. l l 1 i l Broadleaf Vegetation Sampling at McGuire Nuclear Station Table 3.5 Mean Concentrations of Cs-137 in Broadleaf Vegetation ! l YEAR : Cs-137 Indicator (pCl/kg) Cs-137 Control (pCl/kg) i 1979 2.19El 1.93 El l 1980 2.30El 1.92El l 2.46El . 1983 9.07E0 7.85E0 l 1984 1.02El 1.05El j 1985 8.05E0 2.37E-2 ! 1986 4.03 El 1.27El 1987 2.20El 1.70El 1988 3.90El 3.40El I 1989 9.60El 0.00E0 1990 4.00El 0.00E0 1991 3.30E1 0.00E0 1992 4.90El 0.00E0 1993 1.60El 0.00E0 1994 0.00E0 0.00E0 1995 0.00E0 0.00E0 1996 0.00E0 0.00EO Average (1987 - 1996) 2.95El 5.10E0 1997 0.00E0 0.00E0 0.00E0 = no detectable measurements secdon 3 - Page 10
i l 3.6 FOOD PRODUCTS In 1997,12 food prxlucts (crops) samples were analyzed, all at one indicator location. There is no controllocation for this media. No det.tetable activity has been detected in this media since 1987. Table 3.6 shows Cs-137 indicatc r highest annual means with preoperational data and ten year averages. Since no activity was detated in 1997, no reporting levels were approached. Table 3.6 Mean Concentrations of Cs-137 in Food Products YEAR Cs-137 Indicator (pC1/kg) 1979 2.I9EI 1980 2.30El 1981 3.04El 1982 2.46El 1983 9.07E0 1984 8.45E0 1985 7.99E0 1986 2.15EI 1987 2.90EI 1988 0.00E0 1989 0.00E0 1990 0.00E0 1991 0.00E0 1992 0.00E0 1993 0.00E0 1994 0.00E0 1995 0.00E0 1996 0.00E0 Average (1987 - 1996) 2.90E0 1997 0.00E0 0.00E0 = no detectable measurements section 3.Page ii f
) 3.7 FISII ) In 1997,12 fish samples were analyzed for ganuna emitting radionuclides, six at the indicator ( / location and six at the control Iccation. ) Figure 3.7-1 shows Cs-137 highest annual mean indicator and control location concentrations i with comparisons to 5% of the reporting level. Figure 3.7-2 shows Co-60 highest annual l mean indicator and control location concentrations also with comparisons to 5% of the k reporting level. These two radionuclides represent the highest dose contributors for fish. i ) Table 3.7 gives indicator location highest annual means since 1980 for all radionuclides ! j detected since the analysis change in 1988. Preoperational data and ten year averages are also shown. No indicator samples were analyzed in 1979. Only Cs-137 activity was detected in ) 1997 in three of the six indicator sarples. All other radionuclides not shown in the table have demonstrated no detectable activity since 1986. The highest annual mean for Cs-137 activity resulted in only 0.81% of the reporting level . I l s - g - *, ,._ ya
- p. y ,g
+ .y' to
@. xd4f .
) ;N ,1 i A_ / ' *cc.p o i . .. . G.
~
.e.
ww-+--+*-,. , - - - - . - m s _ m . s m ,. ~ _ s,., m section 3.Page 12
~
Figure 3.7-1 pcuke Concentration of Cs 137 in Fish 140 120 100 80 L Y q t. . N/ K ~w,n 0 . . 1980 1982 1984 1980 1988 1990 1992 1994 1996
-G--Indicator Location -*- Control Location 5% of Reporting Level Figure 3.7-2 pcuke Concentration of Co-60 in Fish soo . _ . _.. __ .
300 l-400 g .. 200 100 N 0 0
' ^
-E" * " -
1980 1982 1984 1986 1988 1990 1992 1994 1996 l -G-Indicator Location -*- Control Locaten 5% OF REPORTING LEVEL l f l l t i Section 3 Page 13
Table 3.7 Mean Concentrations of Radionuclides in Fish (pC1/ku) ! Mn-54 Co-58 Co-60 Cs-134 Cs-137 j YEAR Indicator Indicator Indicator Indicator Indicator l 1980 -1.97El 8.36E0 -2.25 E l 2.70El -4,13 E0 ! 1981 2.71 E0 -2.98 E0 -2.65E0 -1.99E0 1.80El 1982 -3.83E0 8.16E0 -4.34 E-1 -8.22E 1 2.69El 1983 2.60E0 2.60E l 1.llEl -1.32E0 6.03El 1984 3.61 E0 1.45E2 2.82El 3.ll El 4.38El 1985 2.53E-1 7.19E0 1.72El -1.56E0 1.86El 1986 1.03E0 3.17E l 2.96El 1.67El 3.49El l 1987 0.00E0 2.71 E2 1.25 E2 2.60El 5.10El 1988 1.20El 7.70El 0.00E0 2.70E l 3.60El
. 1989 9.00E l 4.05E2 2.99E2 1.10El 3.50El 1990 0.00E0 5.60El 4.10El 0.00E0 3.30El
!091 6.20E0 ' l.40El 6.50El 5.90E0 2.60El l l',92 0.00E0 0.00E0 0.00E0 0.00E0 2.90El 1993 0.00E0 8.20El 1.30El 0.00E0 1.60El 1994 0.00E0 0.00E0 0.00E0 0.00E0 3.10El 1995 0.00E0 0.00E0 0.00E0 0.00E0 2.70El i 1996 0.00E0 0.00E0 0.00E0 0.00E0 2.78El Average (1987 - 1996) 1.08El 9.05El 5.43 El 6.99E0 3.12El 1997 0.00E0 0.00E0 0.00E0 0.00E0 1.62El 0.00E0 = no detectable measurements All negative values have been replaced with zeros for calculational purposes l
1 1 l Section 3. Page 14 t
3.8 SIIORELINE SEDIMENT In 1997, six shoreline sediment samples were analyzed, four from two indicator locations and two at the control location. Figure 3.8-1 shows Cs-137 highest annual mean indicator and control location concentrations since 1979. Figure 3.8-2 shows Co-60 highest annual mean indicator and control location concentrations since 1979. These two radionuclides represent the highest dose contributors for shoreline sediment. Table 3.8 gives indicator location highest annual means since 1979 for all radionuclides detected since the analysis change in 1988. Preoperational data and ten year averages are also shown. There is no reporting level for shorelbie sediment. Figure 3.8-1 pcl/kg Concentration of Cs 137 in Shoreline Sediment soo. _ .._ _ _ _ . _ _ _ _ _ _ . . _ _ _ _ _ . . _ . . . _ _ . - 450 400 350 3m 250 N w /\ - 1so v / \ LJ
/ \ ..-
"- - -V77TI so x d V / \.
,MW~%~w m I \
- 1979 1961 1983 1965 1987 1989 1991 1993 1995 1997 l -e--Indicator Locaton -e--Control Locaton l There is no reporting levelfor Cs.I37 in shoreline sediment section 3-Page 15
r j l Figure 3.8-2 ! i l pcWho Concentration of Co-60 in Shoreline Sediment l l l 180- - - - - - - - - - - - - - -- j 180 . !
- 4
'* /N !
j r \ iM ! i
,,0 l \ 1
.0 . I \ n /\
.0 /\ l \ /\ /:
. / \ l V
\ /i :
20 0: : : :" : :
- 1979 1981 1983 1985 1987 1989 1991 1993 1995 1997
--o- Indicator Locaten Control Locaton There u no reporting levelfor Co-60 in shoreline sediment Table 3.8 Mean Concentrations of Radionuclides in Shoreline Sediment (pCl/ke) i Mn-54 Co-58 Co-60 Cs-134 Cs-137 YEAR Indicator Indicator Indicator Indicator Indicator 1979 1.07El 2.25El -6.50E0 0.00E0 1.20El 1980 1.06El 8.74E0 2.36El 3.53 E0 1.44El 1981 2.13E l 1.20E l 8.21E0 3.97El 3.36El 1982 5.38El 1.66El -1.69E0 7.67El 4.40El 1983 4.40E0 3.43 El 2.12El 7.65El 8.02E1 1984 1.19E l 7.ll El 3.04El 3.34El 9.13 El 1985 4.77E0 1.46E l 9.20E0 2.02El 1.61E2 i 1986 1.37El 1.02El 1.16El 6.35El 1.53E2 l 1987 0.00E0 1.06E2 2.10El 4.20El 1.65E2 1988 6.50E0 9.20El 1.20El 9.10E0 2.66E2 1989 2.90El 3.80El 2.90El 5.30El 6.50El 1990 3.80El 2.70El 1.68E2 0.00E0 6.10El 1991 2.80El 5.30El 1.31E2 0.00E0 1.03E2 1992 9.40E0 0.00E0 5.10El 9.20E0 8.60El 1993 0.00E0 2.20El 8.60El 0.00E0 9.30El 1994 4.10El 0.00E0 0.00E0 0.00E0 8.00El I
1995 1.70E l 0.00E0 2.30El 0.00E0 1.38E2 1996 2.90EI 1.78E1 3.50E1 0.00E0 1.47E2 Average (1987 - 1996) 1.98El 3.56E l 5.56El 1.13 E l 1.20E2 1997 0.00E0 0.00E0 1.IIE2 3.10E1 1.36E2 Section 3 Page 16
1 1 3.9 DIRECT GAMMA RADIATION l 1 In 1997,189 TLD's were analyzed,185 at indicator locations and four at the control location. Figure 3.9 and Table 3.9 show TLD inner ring (site boundary), outer ring (4-5 miles), and control ! location annual averages in millirem per year. Preoperational data and fifteen year averages are 4 also given. As shown in the graph, inner and outer ring averages historically compare closely, with control data somewhat higher. Inner and outer ring averages comprise a number of data points with control averages representing only one location. The calculated total body dose from gaseous efiluents for 1997 was 3.30E-02 millirem, which is 0.05% of the average inner ring TLD values. Therefore, it can be concluded that discharges from the plant had very little impact on the measured TLD values. i Figure 3.9 I l mreyr Direct Gamma Radiation (TLD) Results 200 . 180 . t l 160 l 140 l I 120. N A m
~
100 m /A\ / V \ x _j l
- .0 KAi W% \ / .
7 60 L # M n q .. .. 20 0 i 1979 1981 1963 1985 1967 1989 1991 1993 1995 1997
+ hner Rng _as. Outer Rng + Control There is no rep >rting levelfor Direct Radiation (TLD)
{ section 3 Page 17
i i l Table 3.9 Direct Gamma Radiation (TLD) Results YEAR. Inner Ring Average Outer Ring Average Control (mR/yr) (mR/yr) (mR/yr) 1979 7.9I E1 8.82E1 8.32Ei 1980 7.54 El
- 8.29E!
- 1.05E2 1981 1.01 E2 9.31 El 1.05E2 1982 8.95El 8.97El 1.10E2 1983 1.16E2 1.14E2 1.30E2 1984 7.85El 7.83E l 9.02El l 1985 9.54El 9.69E l 1.27E2 1986 8.91El 9.35El 1.10E2 1987 7.58El 7.71 El 1.23 E2 1988 6.03 El 6.42El 5.48El 1989 5.37 El 5.30El 7.55El
!990 4.34E1 4.78EI 6.25E1 1991 5.14El 5.59El 6.80El 1992 5.65E1 5.55 EI 7.60E1 1993 5.61E1 5.7I EI 7.20EI 1994 6.40El 6.93 El 9.55 E I 1995 8.36El 8.25EI 1.08E2 1996 7.18EI 7.02E1 9.88El
~
Average (1982 - 1996) 7.23El 7.37El 9.34El 1997 6.22El 6.68El 9.4SEI
- Values are based on two quarters due to change in TLD locations.
NOTE: The expected background for North Carolina is 120 mrem per year (Reference 6.3). ! l l l l l l l i l Section 3 - Page 18
3.10 LAND USE CENSUS The land use census was conducted June 9 - June 10,1997 and the resu'ts are shown in Table 3.10 and Figure 3.10. During the 1997 census, no new or closer irrigated gardens were identified. The census revealed six milk animal locations that were not included in the 1997 sampling l program. Five of the locations (goats) do not produce sufficieni volume to be added to the program and the. sixth (cow) was not added due to lower deposition factc value compr. red to the other three REMP sites. The nearest residence is located in the East sectar at 0.46 miles. No j program changes were required as a result of the 1997 land use census. 1 i l i
)
l 1 l l l l l 1 Section 3.Page t9
Table 3.10 McGuire 1997 Land Use Census Results Sector Distance Sector Distance (Miles) (Miles) Nearest Residence 2.50 Nearest Residence 1.62 N Nearest Garden 2.79 Nearest Garden 3.04 3 Nearest Milk Cow - Nearest Milk Cow - Nearest Beef Cow - Nearest Beef Cow 3.01 Nearest Goat - Nearest Goat - Nearest Residence 1.29 Nearest Residence 2.57 NNE Nearest Garden 2.87 ggw Nearest Garden 2.95 Nearest Milk Cow - Nearest Milk Cow - Nearest Beef Cow - Nearest Beef Cow 2.75 Nearest Goat - Nearest Goat - l l Nearest Residence 1.20 Nearest Residence 1.80 l NE Nearest Garden 2.10 gg Nearest Garden 1.80 Nearest Milk Cow - Nearest Milk Cow - Nearest Beef Cow - Nearest Beef Cow - Nearest Goat 4.95 Nearest Goat - Nearest Residence 0.56 Nearest Residence 1.01 ENE Nearest Garden 2.55 wgw Nearest Garden 1.16 Nearest Milk Cow 3.51 Nearest Milk Cow - Nearest Beef Cow 3.81 Nearest Beef Cow 1.32 Nearest Goat - Nearest Goat 3.97 Nearest Residence 0.46 Nearest Residence 0.82 E Nearest Garden 0.47 w Nearest Garden 0.90 Nearest Milk Cow 2.46 Nearest Milk Cow - Nearest Beef Cow 4.08 Nearest Beef Cow 3.07 Nearest Goat - Nearest Goat 3.83 Nearest Residence 0.67 Nearest Residence 0.91 ESE Nearest Garden 0.85 WNW Nearest Garden 2.15 Nearest Milk Cow 3.07 Nearest Milk Cow - Nearest Beef Cow 1.30 Nearest Beef Cow - Nearest Goat 1.40 Nearest Goat - Nearest Residence l.17 Nearest Residence 0.93 SE Nearest Garden 1.21 -gw Nearest Garden 1.37 Nearest Milk Cow Nearest Milk Cow - Nearest Beef Cow 2.79 Nearest Beef Cow 3.85 Nearest Goat - Nearest Goat - Nearest Residence 1.06 Nearest Residence 1.53 SSE Nearest Garden 1.26 NNW Nearest Garden 1.77 Nearest Milk Cow 2.76 Nearest Milk Cow - Nearest Beef Cow I.48 Nearest Beef Cow 3.67 Nearest Goat 1.30 Nearest Goat -
" " indicates no occurrences within the 5 mile radius Section 3 Page 20
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4.0 EVALUATION OF DOSE 4.1 DOSE FROM ENVIRONMENTAL MEASUREMENTS Doses were estimat:d for measured concentrations of radionuclides in direct pathways to man using NRC Regulatory Guide 1.109 methodology and factors. - A dose factor of zero was used when the Reg. Guide listed "NO DATA" for a factor. The highest annual mean values for each sample type and radionuclide as given in Appendix B were used after the background concentrations, as measured at the control location, had been subtracted. The maximum exposed individual doses are summarized in Tables 4.1-A and 4.1-B Dose calculations sheets for each age and pathway that indicated environmental doses greater than zero can be found following Tables 4.1-A and 4.1-B. ! 4.2 ESTIMATED DOSE FROM RELEASES Doses were estimated for release concentrations of radionuclides in direct pathways to man using NRC Regulatory Guide 1.109 methodology. The doses were calculated using GASPAR and LADTAP computer programs as reported in the 1997 McGuire Annual Radioactive Emuent Release Report (reference 6.6). The emuent liquid release doses are summations of the dose contributions from the liquid pathways. Noble gas exposure and iodine, particulate, and tritium exposure gaseous release doses are reported separately. For noble gas exposure, there is no critical age group, as the maximum exposed individuals are assumed to receive the same doses, regardless of their age group. For iodine, particulate, and tritium exposure, the maximum total organ dose for the highest dose location is given for the maximum organ (thyroid) for the critical age group (child). The maximum exposed individual doses are summarized in Table 4.1-A with the critical age and critical pathway listed. 4.3 COMPARISON OF DOSES The environmental and emuent doses given in Table 4.1-A agree reasonably well. The similarity of the doses indicate that the radioactivity levels in the environment do not differ significantly from those expected based on emuent measurements and modeling of the environmental exposure pathways. In calculations based on liquid release emuent pathways, drinking water consumption was the predominant dose path based on emuent data for 1997. For 1997 environmental samples, drinking water also was the predominant dose path followed by fish. The only radionuclide detected in drmking water in 1997 was tritium. The only radionuclide detected
'a fish in 1997 was Cs-137. Tritium from surface water samples also was included in the fish pathway.
) so, % ) ) )
) ) t ) No environmental doses resulted from the gaseous pathway in 1997. Broadleaf vegetation, j milk, and airbome radiciodines and particulates indicated no activity in 1997. The effluent data dose for iodine, particulate, and tritium is based on the vegetation pathway to the child f with the majority of the dose contributed by tritium. ) The doses, as calculated using the environmental sample results, are well below the limits specified in Selected Licensee Commitments Manual Section 16.11-12 and do not exceed ) the 40CFR190 dose commitment limits for members of the public. ) ) ) ) , ) ) ) h t f ) ) secem 4.Page2
l TABLE 4.1-A Page 1 of 2 MCGUIRE NUCIsEAR 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 1.78E-03 Skin Effluent Teen Shoreline Sediment 8.68E-04 Bone Environmental Teen Fish 3.31E-03 Bone Effluent Child Fish 3.86E-02 Liver Environmental Child Drinking Water 3.31 E-02 Liver Effluent Child Drinking Water 8.84E-02 T. Body Environmental Child Drinking Water 3.12E-02 T. Body Effluent Adult Drinking Water 6.50E-02 Thyroid Environmental Child Drinking Water 3.09E-02 Thyroid Effluent Child Drinking Water 4.96E-02 Kidney Environmental Child Drinking Water 3.16E-02 Kidney Effluent Child Drinking Water 6.22E-02 Lung Environmental Child Drinking Water 3.12E-02 Lung Effluent Child Drinking Water 5.40E-02
. GI-LLI Environmental Child Drinking Water 3.09E-02 GI-LLI Effluent Child Drinking Water 5.24E-02 0 Maximum dose is a summation of the fish, drinking water and shoreline sediment pathways.
Section 4 - Page 3 ) )
Page 2 of 2 GASEOUS RELEASE PATHWAY l NOBLE GAS EXPOSURE Environmental or Critical Critical Maximum Dose
**" Emuent Data Age Pathway (mrem)
Skin Environmental - - Not Sampled Skin Efiluent N/A Noble Gas 5.44E-02 T. Body Environmental - - Not Sampled T. Body Effluent N/A Noble Gas 3.30E-02 IODINE, PARTICULATE, and TRITIUM , t 1 Environmental or Critical Critical Maximum Dose
- f 4*" Emuent Data Age Pathway (mrem) f Bone Environmental - -
0.00E+00 ) ) Liver Environmental - - 0.00E+00 I Liver Effluent Child Vegetation 2.04E-01 ) T. Body Environmental - - 0.00E+00 f. Thyroid Environmental - - 0.00E+00 1 Kidney Environmental - - 0.00E+00 Lung Environmental - - 0.00E+00 ) GI-LLI Environmental - - 0.00E+00 I
- Maximum dose is a summation of the inhalation, milk and vegetation pathways.
/ Section 4 Page 4 i L
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en ')h )g E E E E t n _ din nu O' k S 0 0 0 0 e Gk k p 2 0 4 9 h n d e pO a or r 8 2 1 4 o S - S r (p e pe n t SG e p i n u n rd r y 9 8 8 9 m = s s ir riot l oe hd 0 0 0 0 m o o n= = a t o - - oh c t E E- E E C r o r r oMe a a a m e B. e Fi n 0 0 it o h emtn r r 0 0 s fe a t t c a c e FF af c a S mr o mc e e s m ( mT 0 7 7 1 2 1 2 4 D o _ o a r s c e h h u r f r ( r o n Dn o t d e o R t Md t S e s toC hc 4 7 D e i t u c t l aC u 8 0 3 3 inHM ne l e e e n D Fa en n r n n o 5-o 6-o 1 s 1 5 r r r u ku es d im e o di C C C C _ bhSh e o d S d e ADS e E t x R a m. m a
I l l 5.0 QUALITY ASSURANCE i I l 5.1 DUKE POWER COMPANY'S REMP j j 5.1.1 SAMPLE COLLECTION Radiological and Environmental Services, Fisheries, and Aquatic Ecology performed the environmental sample collections as specified by approved sample collection procedures. 5.1.2 SAMPLE ANALYSIS - y
' ^
Radiological and Environmental Services , performed the environmental sample . analyses as specified by approved analysis c 1 procedures. The Radiological and , Wg ij g Environmental Services Laboratory is located in Huntersville, North Carolina, at
; e b i Duke Power Company's Environmental #- == -
Center. Duke Power Company's Environmental Center 5.1.3 DOSIMETRY ANALYSIS The Radiation Dosimetry and Records group performed environmental dosimetry measurements as specified by approved dosimetry analysis procedures. 5.1.4 INTRALABORATORY OUALITY ASSURANCE Radiological and Environmental Services has an internal quality assurance program which monitors each type of instrumentation for reliability and accuracy. Daily quality control checks ensure that instruments are in proper working order and these checks are used to monitor instrument performance. 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 i
l 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 l analyses. l 5.1.5 INTERLABORATORY OUALITY ASSURANCE f 5.1.5.1 INTERLABORATORY OUALITY ASSURANCE PROGRAM The Radiological and Environmental Services Laboratories participated in the l Environmental Protection Agency (EPA) cross check program during 1997. Results of these cross-checks are displayed in Table 5.0-A. l 5.1.5.2 DUKE POWER'S INTERCOMPARISON PROGRAM l ! Radiological and Environmental Services participated in the Duke Power l Nuclear Generation Department Intercomparison Program during 1997. j Interlaboratory cross-check standards, including Marinelli beakers, air filters,
- air cartridges, gross beta on smears, and tritium in water samples were i
analyzed at various times of the year by the four counting laboratories in Duke Power Company for this program. A summary of these Intercomparison l Reports for 1997 is documented in Table 5.0-B. 5.1.5.3 DUKE POWER'S AUDIT DIVISION The McGuire Nuclear Station Radiation Protection Section participated in a Quality Assurance audit July 14 through July 24, 1997. Radiological and Environmental Services participated in a Quality Assurance audit in February, 1997. These audits were conducted by the Nuclear Assessment and Issues Division, Regulatory Audit Group. There were no fmdings from these audits. 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. l 5.1.5.4 U.S. NUCLEAR REGULATORY COMMISSION INSPECTIONS The McGuire Nuclear Station Radiological Environmental Monitoring Program was audited by the NRC in January 1997. There was one recommendation to evaluate the height placement of TLDs. This evaluation was performed and TLDs are now placed at a consistent height (except where possible vandalism requires alternate placement). Radiological and Environmental Services was not audited by the NRC in 1997. Section 5 Page 2
r 5.1.5.5 NRC/ STATE OF N.C. SAhlPLING INTERCOAf PARISON PROGRAM Radiological and Environmental Services routinely participates with the State of North Carolina Department of Environmental Health and Natural Resources (DEHNR) in an intercomparison program. Radiological and l Environmental Services sends air, water, milk, vegetation, sediment, and fish samples which have been collected to the State of North Carolina Radiation Protection Section for intercomparison analysis 5.1.5.6 STATE OF N.C. TLD INTERCOSIPARISON PROGRANI Radiation Dosimetry and Records routinely participates in a TLD intercomparison program. Every six to eight months, the State of North ! Carolina Radiation Protection Section irradiates environmental dosimeters and sends them to the Radiation Dosimetry and Records group for analysis of the unknown estimated delivered exposure. A summary of the State of North l Carolina Environmental Dosimetry Intercomparison Report for 1997 is documented in Table 5.0-C. l 5.2 CONTRACTOR LABORATORIES No contractor laboratories were used during 1997, 1 l l l l Section 5 - Page 3
I TABLE 5.0-A U.S. ENVIRONMENTAL PROTECTION AGENCY INTERLABORATORY COMPARISON PROGRAM 1997 CROSS-CIIECK RESULTS FOR TIIE RADIOLOGICAL & ENVIRONMENTAL SERVICES LABORATORY l Gammain Water: Reference Geometry Nuclide Acceptance Range Reference Reported Cross-Check Date (pCi/ liter) Value Value Status
- l (pCi/ liter)' (pCi/ liter) l 3.5 liter l 2/7/97 Marinelli 1-131 70.4 - 102 86.0 94.2 PASS
- 4/15 i7 3.51 iter Co-60 12.3 - 29.7 21.0 24.6 PASS Marinelli Cs-134 22.3 - 39.7 31.0 31.9 PASS l 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 32.3 - 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 - 18.7 10 17.56 PASS l l Marinelli { I1/7/97 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 j Ba-133 81.7 - 116 99.0 104 PASS
- Pass = Data wrthon ControlLsmsts. AC = Above ControlLsmst. BC = Below Control Limit l
I Section 5 Page 4
Beta in Water: 1 i Reference Geometry - Nuclide ' Acceptance Range Reference Reported Cross-Check j Date (pCi/ liter) . Value Value Status
- l
- (pCi/ liter) (pCi/ liter) I Gross 1/31/97 2" Planchet Beta 6.0 - 23.4 14.7 25.0 AC*
J 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 4 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 ACW Pass = Data within Control Lamais . AC = Above Control Limat. BC = Below Contrut Limst (1) Reported value is an average ofthree analyses, one ofwhich was above the controllimit. Tritium in Water: Reference Geometry Nuclide Acceptance Range Reference Reported Cross-Check ' Date (pCi/ liter) Value ' Value Status * (pCi/ liter) (pCi/ liter) - 4/1/97 Plastic 10:10 H3 6530 - 9271 7900 9835 ACm 8/8/97- Plastic 10:10 H3 9100 - 12920 11010 11047 PASS Pass = Data wrthm Control Limits , AC = Above Control Ltmit. BC = Below Control Limit (1) Reported value is an average ofthree analyses, one ofwhich was above the controllimit l Section 5 - Page 5 f l [
1 l t TABLE 5.0-B DUKE POWER COMPANY . INTERLABOR.ATORY COMPARISON PROGRAM l ! 1997 CROSS-CIIECK RESULTS FOR 4 TIIE RADIOLOGICAL & ENVIRONMENTAL SERVICES LABORATORY l l l Gamma in Charcoal Cartridge: l Reference Units of . Nuclide Acceptance Range Reference Reported - Cross-Check l Date - : Activity Value Value Status *' l 2/21/97 pCi/ total 1131- 1.50E5 - 2.66E5 2.00E5 1.98E5 PASS i 6/19/97 pCi/ total . l l 131 72.8 - 129 97.0 104 PASS l l l l I ) 8/22/97 l pCi/ total l l 131 1.51 E5 - 2.67ES l 2.01 E5 l 2.04E5 l PASS : i l 12/11/97 l pCi/ total l l 131 l 23.3 - 41.2 l 31.0 l 29.5 l PASS l
- Pass
- LMra wsthan Control Lumsts . AC = Above Control Lamot. BC = Below Control Limit
! Gamma in Soil: Reference Geometry Units of Nuclide Acceptance Range Reference Reported Cross-Check
' Date Activity Value Value Status
- l 2/21/97 0.5 liter pCi/kg Cr-51 171 - 303 228 273 AC
l 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 l131 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 = ikta withsn Control Lsmits , AC = Above Control Lsmst. BC = Below Control Limit
()) Reported value is an average ofthree analyses. one of which was above the controllimit Section $ Page 6
\
t Gamma in Filter: i Reference Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status
- 2/21/97 pCi/ total Cr-51 1.13 E5 - 2.01 E5 1.51E5 1.55E5 PASS Mn-54 2.78E4 - 4.93 E4 3.71E4 4.07E4 PASS Co-58 1,54E4 - 2.73E4 2.05 E4 2.12E4 PASS !
Fe-59 3.26E4 - 5.77E4 4.34E4 5.09E4 PASS : 1 l Co-60 2.65E4 - 4.69E4 3.53E4 ; 3.70E4 PASS 1 Zn-65 2.66E4 - 4.71 E4 3.54E4 4.28E4 PASS 4 l !
. Cs-134 2.18E4 - 3.87E4 2.91 E4 2.40E4 PASS Cs-137 1.7E4 - 3.01E4 2.26E4 2.26E4 PASS Ce-141 6.14E4 - 1.08E5 8.18E4 8.72E4 PASS p 3/20/97 pCi/ total Cr 51 216 383 288 289 PASS 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 1
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 Ce141 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 l Cs-134 66.8 - 118 89.0 74.5 PASi. Cs-137 93.8 - 166 125 130 PASS Ce-141 108 - 192 144 136 PAS 5
- Pass = Data wuthon Control Lsmots . AC = Above Control Lumst. BC = Below Control Limit Section 5 Page 7
I l Gamma in Filter continued: l Reference ~ Units of Nuclide Acceptance Range Reference Reported Cross-Check l 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 86.2 PASS ! Co-58 36.8 - 65.2 49.0 55.4 PASS Fe-59 72.0 - 128 96.0 120 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-l 37 64.5 - 114 86.0 81.9 PASS Cc-141 46.5 - 82.5 62.0 - 70.6 PASS 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 Zn-65 84.0 - 149 112 131 PASS Cs-134 59.3 - 105 79.0 68.3 PASS Cs-137 61.5 - 109 82.0 87.1 PASS Ce141 57.8 - 102 77.0 86.9 PASS o Pass = Data within Control Limits. AC = Above Control Limit. BC = Below Control L mit (lJ Reported value is an average ofthree analyses, one of nhich was above the controllimit. Section $ - Page 8
I l l Gamma in Water: Reference Geometry Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Wlue Value Status
- 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 ! I-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 j 2/21/97 3.5 liter pCi/ liter Cr-51 5.74E4 - 1.01ES 7.61 E4 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 h .34E4 - 2.36E4 1.78E4 1.81E4 PASS
~
Zn-65 1.34E4 - 2.38E4 1.79E4 1.92E4 PASS I-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 Ce-141 3.09E4 - 5.48E4 4.12E4 4.18E4 PASS 5/29/97 0.5 liter pCi/ liter Mn-54 518 - 918 690 797 " PASS Marinelli Co-58 138 - 243 183 207 ' PASS Fe-59 167 - 297 223 300 PASS Co-60 589 - 1044 785 873 ~ PASS Zn-65 467 - 827 622 677 PASS I-131 523 - 927 697 703 PASS Cs-134 461 - 817 614 560 PASS Cs-137 390 - 692 520 530 PASS Cc-141 179 - 317 238 253 PASS
- Pass = Data wuthm Control Lsmits, AC = Above ControlLsmit. BC = Below Control Lomit (2) Reported value is an average ofthree analyses, two of wisich were above the controllimit.
l Section 5 Page 9
i I l 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
)
I Fe-59 167- 297 223 257- PASS ! Co-60 589 - 1044 785 843 PASS Zn-65 467 - 827 622 740 PASS I-131 523 - 927 697 700 PASS Cs-134 461 - 817 614 553 PASS Cs-137 390 692 520 523 PASS Ce141 179 317 238 260 PASS 5/29/97 3.$ liter pCi/ liter Mn-54 518 - 918 690 730 FASS 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 l 131 523 927 697 727 PASS Cs-134 461 - 817 614 587 PASS Cs-137 390 692 520 547 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 Marinelli Mn-54 1.25E4 - 2.22E4 1.67E4 1.80E4 PASS Co-58 3.33E3 - 5.91E3 4.44E3 4.63E3 PASS 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 Cc-141 4.32E3 - 7.67E3 5.77E3 5.97E3 PASS
- Pass
- Data withm ControlLimats , AC = Above Control Lamat. BC = Below Control Lamit l
l l Section 5 Page 10
r l
' Gamma in Water continued:
l Reference - Geometry . Units of Nuclide Acceptance Range ~ Reference - - Reported Cross-Check l Date Activity Value Value Status
- 8/25/97 0.5 liter pCi/ltter Cr-51 3.08E4 - 5.45E4 4.10E4 4.20E4 PASS Marinelli Mn 54 5.17E3 - 9.16E3 6.89E3 7.52E3 PASS Co-58 4.23E3 - 7.50E3 5.64E3 6.25E3 PASS Fe-59 9.60E3 - 1.70E4 1.28E4 1.42E4 PASS
' Co-60 1.10E4 - 1.96E4 1.47E4 1.59E4 PASS Zn-65 1.17E4 - 2.07E4 1.56E4 1.79E4 PASS I 131 1.82E4 - 3.22E4 2.42E4 2.29E4 PASS Cs-134 5.79E3 - 1.03E4 7.73E3 7.26E3 PASS Cs-137 5.95E3 - 1.06E4 7.93E3 7.98E3 PASS Ce-141 7.09E3 - 1.26E4 9.45 E3 9.51E3 PASS 8/25/97 1.0 liter pCi/ liter Cr-51 3.08E4 - 5.45E4 4.10E4 4.28E4 PASS 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 Co-60 1.10E4 - 1.96E4 1.47E4 1.57E4 PASS l Zn-65 1.17E4 - 2.07E4 1.56E4 1.74E4 -PASS l
I 131 1.82E4 - 3.22E4 2.42E4 2.38E4 PASS Cs-134 5.79E3 - 1.03E4 7.73E3 7.42E3 PASS Cs-137 5.95E3 - 1.06E4 7.93E3 8.13E3 PASS Ce-141 7.09E3 - 1.26E4 9.45E3 9.87E3 PASS I 8/25/97 3.5 liter pCi/ liter Cr-51 3.08E4 - 5.45 E4 4.10E4 4.29E4 PASS Marinelli Mn-54 5.17E3 - 9.16E3 6.89E3 7.38E3 PASS Co-58 4.23E3 - 7.50E3 5.64E3 6.21E3 PASS Fe-59 9.60E3 - 1.70E4 1.28E4 1.40E4 PASS I Co-60 1.10E4 - 1.96E4 1.47E4 1.57E4 PASS ! Zn-65 1.17E4 - 2.07E4 1.56E4 1.70E4 PASS j I 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 - 1.06E4 7.93E3 7.85E3 PASS Ce-141 7.09E3 - 1.26E4 9.45E3 9.78E3 PASS
- Pass = Data withm ControlLimsts, AC = Above ControlLimar, BC = Below ControlLimit l
Section $ - Page i1
i 1 l L ) l Gamma in Water continued: .; l 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 l I-131 212 375 282 212 BC* 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 - 111 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 I131 251 444 334 338 PASS Cs-134 206 - 366 275 268 PASS Cs-137 230 - 408 307 306 PASS Ce-141 33.5 - 59.3 44.6 50.2 PASS
- Pass = Data wsthan Control Lomits , AC
- Above ControlLimot, BC = Below Control Limit (3) Reported value is an average ofthree analyses, one ofwhich was below the controlIsmit.
l l i l l i Section 5 Page 12
l-l Iodinein Water: \ l i Reference Units of Nuclide ! Acceptance Range Reference . Reported Cross-Check j Date Activity Value Value Status
- 2/24/97 pCi/ liter 1131 8.01 - 14.3 10.8 11.4 PASS 5/29/97 pCi/ liter 1-131 65.0 - 115 86.4 113 AC"'
l l l l 1 7/2/97 pCi/ liter l l 131 144 - 255 192 215 PASS l l l l i 7/2/97 pCi/ liter I-131 66 - 117 87.7 76 PASS l l l l l 8/25/97 l pCi/ liter l l131 l 16 - 28 20.8 24 PASS l l l pCi/ liter l 131 5.19 - 9.21 6.92 9.05 AC"' 8/25/97 l l l l l l I l pCi/ liter l I 131 36.0 - 63.8 48.0 45.7 PASS 10/6/97 l l l l l l pCi/ liter I 131 24.1 - 42.8 32.2 31.2 PASS 10/6/97 l l l l l l pCi/ liter l-131 31,1 - 55.2 41.5 42.6 PASS 12/2/97 l l l l l l 12/2/97 l pCi/ liter l I 131 l 141 250 188 212 PASS l l l
- Pass = Data withm contrcl Limsts , AC = Above Control Limit, BC = Below Control Lamat (1) Reported value is an average ofthree analyses, one ofwhich was above the controllimit..
lodine in Miik: 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 5/29/97 pCi/ liter l l131 l 81.2 - 144 l 108 130 PASS l l 7/2/97 pCi/ liter l-131 167 - 297 223 219 PASS l l l pCi/ liter j 1-131 9.32 - 16.5 12.4 15.51 PASS 8/25/97 l l l l pCi/ liter l-131 96.2 - 171 128 131 PASS 12/2/97 l l l l l Section 5 - Page 13
i I l fodinein Milk continued: -l 1 Reference . Units of . Nuclide . Acceptance Range < Reference Reported Cross-Check Date L Activity Value - Value Status
- 12/2/97 pCi/ liter I-131 31.5 - 55.9 42.0 45.8 PASS l
-
- Pass = Data wahm ControlLsmits , AC = Above Controllimit. BC = Below ControlLima Tritium in Water: l Reference Units of ~ Nuclide Acceptance Range Reference Reported Cross-Check Date . Activity Value -Value Status
- 2/19/97 . pCilliter. H 3. 1013 - 17 % 1350 1573 PASS pCi/ liter H-3 19050 - 33782 25400 25113 PASS 2/19/97 l l l l l.
pCi/ liter H-3 609 - 1080 813 978 PASS I 5/29/97 l l l l l l 5/29/97 l pCi/ liter l H3 l 11985 - 21253 15980 15300 PASS l .l l 5/29/97 = pCilliter H-3 1298 - 2302 1731 1918 PASS l l l l l 5/29/97 l pCi/ liter l H3 l 14768 - 26188 l 19690 17646 PASS l l 8/25/97 l pCi/ liter l H3 l 4402 - 78 % 5869 5574 PASS l l 8/25/97 l pCi/ liter l H3 l 268 475 357 342 PASS l l 12/2/97 l pCi/ liter N3 7665 - 13593 l 10220 11141 PASS l l
- Pass = Data withm Control Limits , AC = Above ControlLimit, BC = Below Control Lomit Section 5 Page 14
l l l Lia in Water: l j Reference Units of Nuclide Acceptance Range Reference Reported Cross-Check l Date Activity Value Value Status
- i l Gross 3/20/97 pCi/ liter Beta 108 - 192 144 172 PASS I 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 l I
- Pass = Data wuthin ControlLimits , AC = Above Control Lomit, BC = Below Control Limit Beta in Air Particulate:
1 1 Reference Units of Nuclide Acceptance Range Reference Reported Cross-Check Date Activity Value Value Status
- I 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 within ControlLimits, AC = Above ControlLimit. BC = Below ControlLimit Section 5 Page 15
1 TABLE 5.0-C STATE OF NORTH CAROLINA DEPARTMENT OF ENVIRONMENTAL HEALTH AND NATURAL RESOURCFmS l 1997 ENVIRONMENTAL DOSIMETER CROSS-CIIECK RESULTS I l 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 I 1 I i l i 1 l I Section 5 - Page 16 1
i l l l
6.0 REFERENCES
l 6.1 McGuire Selected License Commitments i 6.2 McGuire Technical Specifications 6.3 McGuire Final Safety Analysis Review 6.4 McGuire Offsite Dose Calculation Manual j 6.5 McGuire Annual Environmental Operating Report 1979 - 1996 l 6.6 McGuire Annual Radioactive Effluent Release Report 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 1. 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 I
APPENDIX A ENVIRONMENTAL SAMPLING l l ANALYSIS PROCEDURES , I 1 j l l l Appendix A Page i
APPENDIX A ENVIRONMEN" ' ', SAMPLING AND ANALYS1 ROCEDURES Adherence to established procedures for sampling and analysis of all environmental media at McGuire Nuclear Station was required to ensure compliance with Station Selected Licensee Commitments. Analytical procedures were employed to ensure that Selected Licensee Commitments detection capabilities were achieved. Environmental sampling and analyses were performed by Radiological and Environmental Services, Dosimetry and Records, and Fisheries and Aquatic Ecology. Section A.1 of this appendix describes the environmental sampling frequencies and analysis procedures by media type. I. CIIANGE OF SAMPLING PROCEDURES No sampling changes were made to the sampling procedure during 1997. In the environmental program, the air deposition parameters (D/Q) are used to detennine air, broadleaf vegetation and milk sampling locations. McGuire's sectors with the three highest values have not changed in 1997. 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 Appendix A- Page 2
samples are batch processed with a tritium spike to verify instrument performance and sample preparation technique are acceptable. Gross beta analysis is performed by concentrating a designated aliquot of sample precipitate and analyzing by gas 41ow proportional counters. Samples are batch processed with a spike sample to verify instrument perfonnance 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.1 AIRBORNE PARTICULATE AND RADIOIODINE Airbome particulate and radioiodine samples at each of seven locations were composited continuously by means of continuous air samplers. Air paniculates were collected on a paniculate filter and radiciodines 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 perfonned on the filter composite. The filter and charcoal cartridge were analyzed independently. The continuous composite samples were collected from the locations listed below. Location 120 = Site Boundary (0.5 mi. NNE) Location 121 = Site Boundary (0.5 mi. NE) Location 125 = Site Boundary (0.4 mi SW) Location 133 = Cornelius, NC (6.2 mi. NE) Location 134 = East Lincoln Junior High School (8.8 mi. WNW) Location 192 = Peninsula development (2.8 mi. NNE) Location 195 = Fishing Access Road (0.2 mi. N) A.2 DRINKING WATER Biweekly composite samples were collected. A gross beta and gamma analysis was performed on montMy composites. Tritium analysis was paformed on the quarterly composites. The composites were collected biweekly frem the locations listed below. Location i19 = Mt. Holly Municipal Water Supply (7.4 mi. SSW) Appendit A - Page 3
Location 132 = Charlotte Municipal Water Supply (11.2 mi. SSE) Location 136 = Mooresville Municipal Water Supply (12.7 mi. NNE) Location 194 = East Lincoln Water Supply (6.7 mi. NNW) A.3 SURFACE WATER Biweekly composite samples were collected. A gamma analysis was performed on the monthly composites. Tritium analysis was performed on the quarterly composites sample. The composites were collected biweekly from the locations listed below. Location 128 = Discharge Canal Bridge (0.4 mi. NE) Location 131 = Cowans Ford Dam (0.6 mi. WNW) Location 135 = Plant Marshall Intake Canal (11.9 mi. N) A.4 MILK Biweekly grab samples were collected at each dairy. A gamma and low-level Iodine-131 analysis was performed on each sample. The biweekly grab samples were collected from the locations listed below. Location 138 = Henry Cook Dairy - COWS (3.1 mi. ESE) Location 139 = William Cook Dairy - COWS (2.5 mi. E) Location 140 = Kidd Dairy - COWS (2.8 mi. SSE) Location 141 = Lynch Dairy - COWS (14.8 mi. WNW) A.5 BROADLEAF VEGETATION Monthly samples were collected as available and a gamma analysis was performed on each sample. The samples were collected from the locations listed below. Location 120 = Site Boundary (0.5 mi. NNE) Location 125 = Site Boundary (0.4 mi. SW) Location 134 = East Lincoln Junior High School (8.8 mi. WNW) Location 193 = Site Boundary (0.2 mi. N) A.6 FOOD PRODUCTS Samples were collected monthly when available during the harvest season and a gamma analysis was performed on each. The samples were collected at the location listed below. Location 188 = Garden (2.8 mi N) Appendia A Page 4
A.7 FISil Semiannual samples were collected and 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 129 = Discharge Canal Entrance to Lake Norman (0.5 mi.ENE) Location 137 = Pinnacle Access Area (12.0 mi. N) A.8 SHORELINE SEDINIENT Semiannual samples were collected and a gamma analyas was performed on each following the drying and removal of rocks and clams. The samples were collected from the locations listed below. Location 129 = Discharge Canal Entrance to Lake Norman (0.5 mi. ENE) Location 130 = Highway 73 Bridge Downstream (0.5 mi. SW) Location 137 = Pinnacle Access Area (12.0 mi. N) A.9 DIRECT GANINTA RADIATION (TLD) Thermoluminescent dosimeters (TLD) were collected quarterly at forty-nine locations. A gamma exposure rate was determined for each TLD. The TLDs wete placed as indicated below. An inner ring of 14 TLDs at the site boundary, one in each available meteorological sector. The site boundary locat:ons in the N and NNW sectors are over water; however, two special interest TLD's were placed in these sectors inside the site boundary in March,1991. 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 control locations. TLD locations are listed in Table 2.1-B. Appendix A - Page 5 i
A.10 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 June 9,1997 and completed on June 10,1997. Results are shown in Table 3.10. 4 Appendix A Page 6
APPENDIX B RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
OF RESULTS 1997 ) Appendix B - Page 1
Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: Ol-JAN 1997 to 31-DEC-1997 Medium or Type and Total Lower No.of Non-L cation with Highest iI die Control Routine Pathway Number Limit cf ;9 Annual Mean Sampled of Detection . Location Report Name, Distance, Direction Unit of Analyses Mean (Fraction) Location Measurement Performed (LLD) Mean Range Mean Range Range Code Air Particulate 134 (pCi/m3) (8.8 mi WNW) BETA 364 1.00E-02 2.13E-2 (312/312) 133 2.34E-2 (52/52) 3.62E-2 (52/52) 0 8.50E-3 9.14E-2 (6.2 mi NE) 9.20E 9.14E-2 1.26E 1.08E-l CS-134 28 5.00E-02 0.00(0/24) 0.00 (0/4) 0 0.00 (0/4) 0/X) - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 28 6.00E-02 0.00 (0/24) 0.00 (0/4) 0.00 (0/4) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 1 131 28 7.00E-02 0.00 (0/24) 0.00 (0/4) 0.00 (0/d) 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 detectabte activity measurements if LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 1/30/98 10:24 A.M Appendix B Page 2
Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecktenburg County, North Carolina Report Period: Ol-JAN-1997 to 31-DEC-1997 Medium or , Lower * "*
- All Indicator Control ou i e Pathway Limit of ; Annual Mean Sampled
. Location Report gp Detection - Name, Distance, Direction Meas.
Unit of Analyses Mean (Fraction) Location Measurement Performed (LLD) Range Mean Range Mean Range
; Code Air Radiciodine 134 (pCi/m3) (8.8 mi WNW)
CS-134 364 5.00E-02 0.00 (0/312) 0.00 (0/52) 0.00 (0/52) 0
$ 0.00 - 0.00 0.00 0.00 7.00E 7.00E-3 CS-137 364 6.00E-02 7.55E-3 (5/312) 133 8.20E-03 (1/52) 7.00E-3 (1/52) 0 6.70E-3 8.20E-3 (6.2 mi NE) 8.20E 8.20E-03 0.00 - 0.00 1.I31 364 7.00E-02 0.00(0/312) 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 specilled 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 10:25 AM Appendix B - Page 3 g -
Environmental Radiological Monitoring Program Summary Focility: McGuire Nuclear Station Docket No. 50-369,370 - L.estion: Mecklenburg County, North 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 ions Location Report Sampled of Detection Name, Distance, Direction g Unit of Analyses Mean (Fraction) Location Measurement Performed (LLD) Range Mean Range Mean Range Code Drinking Water 136 (pCi/ liter) (12.7 mi NNE) BALA-140 52 15 0.00 (0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 BETA 52 4 2.53 (28/39) 119 2.70 (10/13) 2.24 (9/13) 0 0.95 - 4.88 (7.4 mi SSW) 0.95 - 4.88 1.56 - 3.75 CO-58 52 15 0.00(0/39) 0.00 (0/13) 0.00(0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 $2 15 0.00(0/39) 0.00 (0/13) 0.00 (0/I3) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS 134 52 15 0.00 (0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 52 18 0.00 (0/39) 0.00 (0/13' O.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 FE-59 52 30 0.00 (0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 11-3 16 2000 284 (4/12) 132 290 (2/4) 0.00 (0/4) 0 222 - 332 (11.2 mi SSE) 287 - 293 0.00 0.00 I-131 52 15 0.00 (0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 MN-54 52 15 0.00 (0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 NB-95 52 15 0.00 (0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 0.00 ZN-65 52 30 0.00(0/39) 0.00 (0/13) 0.00 (0/13) 0 0.00 0.00 0.00 0.00 0.00 - 0.00 ZR-95 52 15 0.00 (0/39) 0.00 (0/13) 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 @ 3/12/98 1:34 PM 4oerdix B Page 4
Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,37( Location: Mecktenburg County, Nortli Carolina Report Period: Ol JAN-1997 to 31 DEC 1997 9 Medium or No. of Non-Type and Total Lower * "*I *** All indicator Control Routine Pathway Number Limit of Annual Mean Sampled of Location Report Detection Name, Distance, Direction Mm Unit of Analyses "" '* "} " Measurement Performed (LLD) Range Mean R'ange Mean Range Code Surface Water 135 (pCi/ liter) (11.9 mi N) BAI.A. I40 39 15 0.00 (0/26) 0.00 (0/I3) 0.00 (0/I3) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-58 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 , 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 39 15 0.00(0/26) 0.00 (0/13) 0.00 (0/13) 0
- 0.00 - 0.00 0.00 0.00 0.00 0.00 CS-134 39 15 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 0.00 0.00 - 0.00 0.00 0.00 CS-137 39 18 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 0.00 0.00 0.00 FE-59 39 30 0.00 (0/26) 0.00 (0/13) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 H3 12 2000 384 (6/8) 128 485 (3/4) 0.00 (0/4) 0 '
238 512 (0.4 mi NE) 438 - 512 0.00 - 0.00 I 131 39 I5 0.00 (0/26) 0.00 (0/I3) 0.00 (0/13) 0 0.00 - 0.00 0.00 - 0.00 0.00 0.00 MN-54 39 15 0.00 (0/26) 0.00 (Q'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/I3) 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/I3) 0 0.00 - 0.00 0.00 0.0F 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 a.tivity measurements if LLD is equal to 0.00, then the LI D is not required by Selected Licensee Commitments Report Generated @ l/30/98 10:25 AM Appendix B Page 5
Environmental Radiological Monitoring Program Summary Focility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Pe.-iod: 01-JAN-1997 to 31-DEC 1997 No. of Non- % Medium or Type and Total Lower Location with Highest . y, g; Control Routine Pathway Number Limit of . Annual Mean
"*""* *"I " *E "
Sampled of Detection Name, Distance, Direction Meas. Unit of Analyses Mean (Fraction) Location Measurement (LLD) Mean Range Mean Range Performed Range Code Milk 141
- tpCi/ liter) (14.8 mi WNW)
DALA-140 104 15 0.00 (0/78) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 - CS-134 104 15 0.00 (0/78) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CS-137 104 I8 0.00 (0/78) 0.00 (0/26) 0.00 (0/26) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 U31 104 15 0.00 (0/78) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 LLI-131 104 1 0.00 (0/78) 0.00 (0/26) 0.00 (0/26) 0 0.00 - 0.00 0.00 0.00 0.00 0.00 s> Mean and range based upon detectable measurements only Fractior 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
'n Report Generated @ 2/2/98 7:24 AM Appendix B Page 6
Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAN-1997 to 31 DEC-1997
.I Medium or Type and Total Lower AllIndicator Locati n with Highest rol Ro ]
Limit of Pathway Number Annual Mean
,, Location Report Sampled of Detection Name, Distance, Direct. ion g ,
Unit of Analyses Mean (Fraction) Location Measurement Performed I Range
**" ""E* #"" ""8*
Code < Broadleaf 134 j Vegetation (8.8 mi WNW) (pCi/kg wet) ' CS-134 32 60 0.00 (0/24) 0.00 (0/8) 0.00(0/8) 0 0.00 - 0.00 0.00 0.00 0.00 - 0.00 CS-137 32 80 0.00(0/24) 0.00(0/8) 0.00 (0/8) 0 g 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 r 1 131 32 60 0.00 (0/24) 0.00 (0/8) 0.00 (0/8) 0 0.00 - 0.00 0.00 0.00 0.00 - 0.00 Mean and range based upon detectable measurements only Fraction of detectable measurements at specified locations is indicated in parentheses, (Fraction) Zero range indicates no detectable activity measurements If LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments Report Generated @ 18098 10:26 AM Appendix B - Page 7 n.
.. Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecktenburg County, North Carolina Report Period: Ol-JAN-1997 to 31-DEC-1997 No. of Non-Medium or Type and Total Lower Location with Highest g;gg; Control Routine Pathway Number Limit of Annual Mean Sampled of "" "
Detection Name, Distance, Direction M Unit of Analyses "*" '"# "} ** " Measurement Performed (LLD) Mean Range Mean Range Range Code Food Products No Control (pCi/kg-wet) locations CS-134 12 60 0.00 (0/12) 0.00 (0/12) 0.00 (0/0) 0 0.00 - 0.00 0.00 0.00 0.00 0.00 CS-137 12 80 0.00 (0/12) 0.00 (0/12) 0.00 (0/0) 0 0.00 0.00 0.00 - 0.00 0.00 - 0.00 1 131 12 60 0.00 (0/12) 0.00 (0/12) 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 8 i _ _ ______.__m._
Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Dodet No. 50 369,370 Location: Mecklenburg Connty, North Carolina 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 Location Report Sampled of Detection Name, Distance, Direction
- Unit of Analyses "" #" * "
Measurement Performed (LLD) Mean Range Mean Range Range Code Fish 137 (pCi/kg-wet) (12.0 mi N) CO-58 12 130 0.00(0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 - 0.00 0.00 0.00 CO-60 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 0.00 0.00 0.00 0.00 - 0.00 CS-134 12 130 0.00(0/6) 0.00(0/6) 0.00 (0/6) 0
~
0.00 - 0.00 0.00 0.00 0 00 - 0.00 C -137 12 1*4 16.2 (3/6) 129 16.2 (3/6) 15.2 (1/6) 0 12.4 21.5 (0.5 mi ENE) 12.4 - 21.5 15.2 15.2 h49 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 0.00 0.00 0.00 0.00 0.00 MN 54 12 130 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 0.00 0.00 0.00 ZN-65 12 260 0.00 (0/6) 0.00 (0/6) 0.00 (0/6) 0 0.00 - 0.00 0.00 0.00 0.00 0.00 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 (dj 1/30/98 10:26 AM Appendix 11 - Page 9
Environmental Radiological Monitoring Program Summary Facility: McGuire Nuclear Station Docket No. 50-369,370 Location: Mecklenburg County, North Carolina Report Period: 01-JAh-1997 to 31 DEC-1997 Medium or Type and Total Lower No. of Non-gg g, Location with flighest Control Routine Pathway Number Limit of Annual Mean Sampled of Detection Name, Distance, Direction - M s Unit of Analyses Mean (Fraction) Location Measurement Performed
)
Range
**" *"E* "" ""E Code -
Shoreline 137 Sediment (12.0 mi N) (pCi/kg dry) CO-58 6 0 0.00 (0/4) 0.00 (0/4) 0.00 (0/2) 0 0.00 - 0.00 0.00 - 0.00 0.00 - 0.00 CO-60 6 0 75.5 (2/4) 130 111(l/2) 0.00 (0/2) 0 39.6 111 (0.5 mi SW) 111 - 111 0.00 - 0.00 CS-134 6 150 31.0(1/4) 130 31.0(1/2) 0.00 (0/2) 0 31.0 31.0 (0.5 mi SW) 31.0 - 31.0 0.00 - 0.00 CS I37 6 I80 94.0 (4/4) 130 136 (2/2) 0.00 (0/?) 0 29.8 !$5 (0.5 mi SW) I18 155 0.00 0.00 M N-54 6 0 0.00(0/4) 0.00 (0/4) 0.00 (0/2) 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 Uf LLD is equal to 0.00, then the LLD is not required by Selected Licensee Commitments t Report Generated @ 1/30/98 10:26 AM Appendix 3 Page 10
Environmental Radiological Monitoring Program Summary Focility: McGuire Nuclear Station Docket No. 50-369,370 Locotion: Mecklenburg County, North Carolina Report Period: 01.JAN-1997 to 31 DEC 1997 Medium or T tal All Indicator Control Routi Pathway Sampled Number kunit7*'f o Locations
^ " " " ' **"
3 Detection Name, Distance, Direction Location Report 97 Meas. Analyses Mean (Fraction) Location Unit of Measurement g (LLD) **" ""8 **" ""8" Range Code Direct Radiation 175 TLD (15.5 mi WNW) (mIWtandard quaner) 189 0.00E +00 16.7(185/185) 173 26.0(4/4) 23.6 (4/4) 0 10.4 27.1 (8.4 mi NNW) 23.3 - 27.1 23.1 - 25.2 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 @ 3/12/98 1:36 PM Appendix B - Page i1
APPENDIX C SAMPLING DEVIATIONS
' UNAVAILABLE ANALYSES Appendix C - Page 1 I
APPENDIX C MCGUIRE 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 PI Power Interrupt VN Vandalism PM Preventive Maintenance C.1 SAMPLING DEVIATIONS Surface Water Scheduled Actual Reason Location Collection Collection Code Corrective Action Dates Dates Sampler pump out of service. A grab sample taken. Temporary sampler was placed in service to collect composite 131 I/14 - 2/11/1997 2/11 - 2/11/1997 PS while processing repair work request. C.2 UNAVAILABLE ANALYSES TLD Scheduled Reason Location Collection Dates Code Corrective Action 186 12/30 - 3/24/1997 VN TLD missing. 2dQuarter TLD placed in tield. 181 12/30 - 3/24/1997 SL TLD collected but could not be located for analysis 146 9/22 12/29/1997 SL TLD collected but could not be located for analysis Appendix C- Page 2 l l
1 APPENDIX D ANALYTICAL DEVIATIONS No analytical deviations were incurred for the 1997 Radiological Environmental Monitoring Program
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a Appendix D- Page I
APPENDIX E RADIOLOGICAL ENVIRONLMENTAL 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 Huntersville, North Carolina. Appendix E - Fage l}}